ML061390297

Final Status Survey Plan for the Plum Brook Reactor Facility, Revision 0, May 2006, Book 2

ML061390297
Person / Time
Site:	Plum Brook
Issue date:	05/12/2006
From:	US National Aeronautics & Space Admin (NASA), John H. Glenn Research Ctr at Lewis Field
To:	Document Control Desk, NRC/FSME
References
Download: ML061390297 (466)

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{{#Wiki_filter:SAFETY AND MISSION ASSURANCE DIRECTORATE Plum Brook Reactor Facility Final Status Survey Plan for the Plum Brook Reactor Facility (Rev 0)May 2006 BOOK 2 SAFETY AND MISSION SAFETY AND MISSION ASSURANCE DIRECTORATE Plum Brook Reactor Facility Final Status Survey Plan for the Plum Brook Reactor Facility (Rev 0)May 2006 BOOK 2 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 TABLE OF CONTENTS (continued) ATTA CHMENTA 1.0 Purpose.A-. .........................................................................................................................

2.0 References

A-i 3.0 Assumptions and General Information.A-1

3.1 Nuclides

A-I 3.2 RESRAD and RESRAD-BUILD A-I 4.0 Discussion A-i 5.0 Historical Overview A-2 5.1 Assessment of Historical and Operational Factors A-4 6.0 Sample Collection and Analysis A-5 6.1 Smear Samples of Structural Surfaces. ,,,,,, A-5 6.2 Concrete Core Sampling. ,,,,,,,, , A-7 6.3 Soil Sampling ,,,,,, ,A-16 7.0 Evaluation of Sample Results and Elimination of Insignificant Radionuclides A-19 7.1 Minimum Detectable Activity (MDA) .,, -A-19 7;2 Mean Distribution Evaluation .A-19 7.3 Application of the 10% Rule -A-23 8.0 Conclusion A-26 9.0 Addendums A-27.................................................................................................................... Addendum 1. Result of Isotopic Analysis of Smear Samples (7 Pages)Addendum 2. Preliminary Analysis of Concrete Core Puck" Samples by the On-Site Laboratory (16 Pages)Addendum 3. Results of Isotopic Analysis of Concrete Core Samples (3 Pages)Addendum 4, Results of Isotopic Analysis of Surface Soil Samples (2 Pages)ATTACHMENTB 1.0 Purpose,.... 2.0 References.................. 3.0 DCGL Approach....... 4.0 DCGL Methodology ..................................................................................................... .....................................................................................................

• B-1 B-1 B-2 B-3.....................................................................................................

V Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Nw TABLE OF CONTENTS (continued) 5.0 DCGL Bases .B-4 5.1 Residual Contamination in Surface Soils B-4 5.2 Residual Contamination in Buildings. .,.,.,.,, .,,,.,.B-11

5.3 Residual

Contamination in Subsurface Structures B-18 6.0 Area Factors,,,,,,,,,,.,,,,,,,,,,,,,,,,,,,...,,,,,,,, .............................. ,, ,,. , .........2 6.0 Area Factors.B-25 ATTACHMENT C 1.0 Purpose .....,,,,,,,. ......C........I..,., .,., C-1 2.0 References..C-i

3.0 Discussion

C-1 3.1 Industrial Safety. .,,,,,,,,,,,.,,,,,,,..,,,,,,,,,,,,,,,..,,.,,,.,,,,.,,,.,,,,.,,,,.,,,,..C-2

3.2 Waste

Generation C-2 3.3 Cost C-2 4.0...............Piping..Versus ..Buried ................................................ ,..................,......C-

4.0 Embedded

Piping Versus Buried Piping..C-3

4.1 Embedded

Piping DCGL Values......................................................................C-3

4.2 Buried

Piping DCGL Values. .,,, C-3 5.0 Embedded Piping Conceptual Dose Model ...................................... ,.,.,,,,,.,.C-4 6.0 Dose Calculations for 9-Pipe Cluster ............................. , C-5 7.0 Embedded Piping DCGL Values ................................................................ C-7 8.0 Evaluation of Alternative Exposure Scenario ......................................... C-8 9.0 Area Factors C-10 Addendum 1, MicroShield Case Run Reports for Canal F- Pump Room Walkway Pipe Cluster (256 Pages)Addendum 2, MicroShield Case Run Reports for Pump Room Trench Pipe Cluster (14 Pages)Addendum 3, MicroShield Case Run Reports for Area Factor Calculations (51 Pages)ATTACHMENT D Illustrations of Survey Area Classification (33 Pages)Vi Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &Final Status Survey of the Plum Brook Reactor Facility (PBRF) Plum Brook Reactor Facility Final Status Survey Plan Revision 0 1.0 Purpose This attachment provides evaluations of the Plum Brook Reactor Facility (PBRF)radionuclide distribution used to determine the site structure and soil DCGL values.Radionuclides determined to be insignificant contributors per the guidance described in NUREG-1757 (Reference 2.6) were eliminated from further consideration. Embedded piping radionuclide distribution data is provided in Attachment C of this FSSP.2.0 References 2.1 Plum Brook Reactor Facility Decommissioning Plan 2.2 NUREG-1575, Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM)2.3 NUREG/CR-3474, "Long-Lived Activation Products in Reactor Materials" 2.4 NUREG/CR-0130, "Technology, Safety and Cost of Decommissioning"-2.5 NUREG/CR-4289, "Residual Radionuclide Contamination Within and Around Commercial Nuclear Power Plants" 2.6 NUREG-1757, Vol. 2, "Characterization, Survey, and Determination of Radiological Criteria" 2.7 "An Evaluation of the Plum Brook Reactor Facility and Documentation of Existing Conditions," Teledyne Isotopes, December, 1987 3.0 Assumptions and General Information

3.1 Nuclides

positively identified in a single sample were assumed to be present at their stated MDA values in all other samples in their applicable populations where the nuclides were not detected.3.2 RESRAD'and RESRAD-BUILD input values used to evaluate dose contributions from specific radionuclides employ the building reuse, subsurface structure and surface soil parameters and scenarios used for site-specific DCGL development are provided in PBRF Technical Basis Documents and are available for review, as needed.4.0 Discussion The evaluation provided in this attachment was performed to identify the suite of radionuclides that could potentially be present in site structures and soils following completion of decommissioning activities and structure demolition. 10 CFR Part 61 waste stream characterization analyses as well as the results of the isotopic analysis of concrete core samples collected as part of the characterization survey were used to estimate radionuclide distributions. A- I Plum Brook Reactor Facility Final Status Survey Plan Revision 0 A variety of concrete structures containing residual contamination may remain after decommissioning including the walls and floors of the basements of major buildings as well as concrete demolition debris that may be used as clean fill. At PBRF, the two major sources for the radioactive contamination of the concrete were the reactor coolant water, which contained both fission and activation products, and the irradiation of experiments. The presence of low levels of fission products in some of the sample results suggests that a small clad failure or a recycling of treated water from the Hot Laboratory may have occurred.In order to assess the possibility that more than one radionuclide distribution could apply to the concrete structures and post demolition concrete debris that will undergo FSS, both the operational history and uses of the different structures were evaluated.

5.0 Historical

Overview The PBRF was used to perform nuclear irradiation testing of fueled and unfueled experiments for space program applications. Construction of the PBRF began in 1956.Preoperational testing of the reactor was performed during 1961 and 1962 and full power operations began in April 1963. The 60 MW reactor was operated by NASA on an essentially uninterrupted basis for almost 10 years until January 1973 when it was shut down after accumulating 98,000 Mega Watt Days (MWD) of operation. The reactor was defueled from January to July 1973. During that time, the reactor fuel element assemblies (all special nuclear material, source material, and radioactive waste generated at that time) were removed from the PBRF and preliminary decontamination was performed. The fuel assemblies were transferred and reprocessed offsite and the radioactive wastes were disposed of offsite at licensed commercial facilities. The PBRF systems and support facilities not required for safe storage were maintained (mothballed) for possible future operations. During 1997 and 1998, NASA management decided to decontaminate and decommission the PBRF to allow termination of the NRC licenses and release the PBRF for unrestricted use.The PBRF consists of six major buildings, several subsurface "tunnels", three water holding basins and an effluent release "ditch". The major structures include the Containment Building, the Reactor Building, the Hot Laboratory, the Reactor Office and Laboratory Building, the Waste Handling Building, the Primary Pump House and the Fan House. Subsurface structures include the Hot Pipe Tunnel and the Cold Pipe Tunnel.The holding basins include the Hot Retention Basin, the Cold Retention Basin and the Emergency Retention Basin.Reactor fuel was constructed of uranium/aluminum alloy fuel elements clad with aluminum alloy. The reactor fuel material was uranium enriched to about 93% in the U-235 isotope in an aluminum alloy of not more than 25% uranium by weight. The maximum core loading did not exceed 6 kg of U-235. Beryllium reflector pieces surrounded the fuel along with cadmium/beryllium regulating and shim rods. The core was moderated and cooled by de-ionized water which was pressurized by the elevation of water in the head tank and the head of the primary system pumps.A-2 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Most primary system piping and components are located in the Containment Building, the Reactor Building, the Primary Pump House and the Fan House. Primary systems were also present in portions of the Hot Pipe Tunnel. The primary cooling water system was subdivided into four groups, the main loop, the by-pass clean-up loop, the instrument and test hole cooling loop and the shutdown loop. The main loop was a closed loop, 26,000 gallon system that was routed from the reactor through 24 in. supply and return lines to the Primary Pump House where coolant water was passed through two primary heat exchangers, three primary pumps, a strainer and a flow meter and returned to the inlet supply line.During reactor operation, the reactor tank was essentially a closed system. Experiments were inserted by means of two horizontal through tubes, six horizontal beam tubes, and two vertical experiment tubes, all of which are of aluminum alloy construction. However, direct interface with the canal system did occur, most notably in the hydraulic"rabbit" tubes, which transferred experiment materials in and out of the reactor tank using the difference in hydraulic pressure between the reactor coolant and the canals. During shutdown, materials and fuel elements were routinely transferred between the reactor tank and the canals.The reactor tank and concrete biological shield are surrounded by four quadrants, three (A, C, and D) of which could be flooded with water for additional biological shielding. Quadrant B was a dry area. A system of canals was used to transfer materials or fuel assemblies to and from the reactor tank, the fuel storage area, and the adjacent Hot Laboratory. Quadrant D contained the underwater beam room. In the Hot Laboratory, materials were remotely transferred from the canals to either the hot cells or the Hot Dry Storage Area. It was here that irradiated materials were handled and tested.The hot drain system consists of the drain collection systems for all wastewater drainage that originated directly or indirectly from a radioactively contaminated area. The system is made up of 12 collection sumps (located in the Fan House, Waste Handling Building, Reactor Office and Laboratory Building, Primary Pump House, Hot Laboratory, Reactor Building, and inside the containment vessel) along with associated pumps and valves.Pumps were used to move liquids that had collected in the sumps to the Hot Retention Area.The Mock-Up Reactor (MUR) was a 1OOKW swimming pool type reactor located in Canal H and setup to simulate the main Plum Brook Reactor. The MUR used the same uranium enriched aluminum alloy fuel assemblies, with the exception of uranium loadings, as the larger reactor core. As such, the nuclide distribution resultant from the operation of the MUR should be essentially the same as the distribution resultant from the operation of the larger reactor.The secondary coolant system consisted of a single loop system that took waste heat from a pair of primary to secondary heat exchangers, carried it to a cooling tower for disposal, and then returned the water to the heat exchangers located within the Primary Pump House. The secondary system piping leaves the Reactor Building (RB) and proceeds A-3 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 down the length of the Cold Pipe Tunnel that connects the RB to the Service Equipment Building (SEB) and to the cooling tower.The Hot Retention Area, located south of the Fan House, contains eight 60,000 gal and four 7500 gal steel underground storage tanks. The larger tanks, located in an underground concrete room, received all of the radioactively contaminated water from the hot drain system. The four smaller tanks were used as holding tanks. The contaminated water was treated and the water in the holding tanks was monitored and then discharged to the Cold Retention Basins, the quadrant and canal recirculating system, or to the Water Effluent Monitoring Station.The Cold Retention Basins are two 500,000 gal below grade storage basins in the shape of inverted pyramids. The basins were used to store low-level radioactive water primarily from the quadrants and canals in the Reactor Building. During facility operations the basins were known to leak, so a plastic liner was installed. At the time of shutdown, the Cold Retention Basins were opened to permit groundwater to enter the structures to equalize the water levels in the groundwater and basins and prevent the basins from floating in the event of a high groundwater table. Silt and sludge accumulated on the side walls and bottoms of the basins.5.1 Assessment of Historical and Operational Factors The following conclusions were reached following an assessment of the lay-out, structures, systems and processes that were used during the operation of the PBRF. Reactor coolant systems containing reactor originated fission and corrosion products are prevalent in the Containment, the Reactor Building, the Hot Laboratory, the Primary Pump House, the Waste Handling Building, the Fan House and the Hot Pipe Tunnel. Other environmental areas were also directly impacted by exposure to either treated and/or untreated primary coolant, including the Hot Retention Area, the Cold Retention Basins, the Emergency Retention Basin, the Water Effluent Monitoring Station, the Pentolite Ditch and Drainage System. Subsequently, it was anticipated that all the areas listed above should exhibit approximately the same radionuclide mixture.One building, the Reactor Office and Laboratory Building (ROLB) did not contain any major systems that carried primary coolant. It is believed that the source of contamination discovered in the ROLB was from the importation and analysis of reactor coolant and reactor material samples. Radiological operational surveys taken in the fuel vault and in several laboratories located in the ROLB showed significant alpha contamination that was later identified as U-234 and U-235. Subsequent radiological characterization surveys did not identify U-234 and U-235 in any other of the impacted structures at the concentrations observed in the ROLB. As such, the ROLB was evaluated as an area that could exhibit a unique mixture.In the Hot Laboratory, a wide variety of irradiated materials were unpackaged, directly handled and tested in this area. Subsequently, it is anticipated that the A-4 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 radionuclide distribution in the Hot Laboratory could also be significantly different from the balance of plant mixture.6.0 Sample Collection and Analysis 6.1 Smear Samples of Structural Surfaces As part of a previous investigation performed to substantiate the nuclide distribution that would be applicable to waste disposition, twenty-two (22) smear samples were acquired and subjected to 10 CFR Part 61 analyses. The samples were as follows;* 7 smears taken on loose equipment and materials in Hot Cells numbers 1 through 7,* 7 smears taken on structural surfaces in Hot Cells numbers 1 through 7,* 5 smears taken from within the Containment structure, including Quads A, Quad C, Canal E, the Lilly Pad and general area,* 2 smears taken from the Reactor Office and Laboratory Building, and* 1 smear taken from the Reactor Building.In addition, alpha contamination was positively identified by direct measurement and on smear samples collected in the ROLB fuel vault and in several of the laboratories during the radiological evaluation of loose equipment in these areas for disposition and disposal. Additional smear samples were collected specifically at locations in the ROLB where positive alpha measurements were obtained. These smears were combined into composite samples and analyzed for isotopic content. To support the assessment of the nuclide mixture in the ROLB, the results from these samples were added to the Part 61 smear sample population described above. The results of the analyses of these smear samples are presented in Addendum 1 of this attachment. A- S 0 0 0 Plum Brook Reactor Facility Final Status Surveyi Plan Revision 0 Figure A-1 Part 61 Smear Populations Sample Locations A-6 oO/ Plum Brook Reactor Facility Final Status Survey Plan Revision 0 6.2 Concrete Core Sampling In addition to the smears, concrete core bore samples were collected at various locations throughout the PBRF structures. A plan for concrete sample collection was prepared to ensure that core bore samples were collected at representative locations from each of the primary structures designated to remain and be subjected to FSS. Core samples were collected at biased locations in the areas known to be the most exposed to radioactive contamination during plant operation. Areas in lower levels of buildings, areas housing waste processing equipment, and areas near sumps and floor trenches were chosen.The biased location of each core bore was selected by performing a beta scan of the floor area of the targeted structure. The location with the highest total surface contamination reading was identified and assessed for the presence of loose surface contamination. If loose surface contamination was detected, the location was decontaminated. If there was appreciable fixed contamination left following the decontamination, the location was selected for obtaining a core bore sample.By obtaining the highest activity samples from each key structure, the likelihood of detecting nuclides with low activity levels was improved and the relative fractions of the MDA values were minimized. hi total, sixteen core bore samples were obtained. One core sample broke during extraction and was unusable leaving 15 samples for analysis. Of the 15 samples, thirteen were used as sent for isotopic analysis. The other two core samples were saved for possible site-specific KD analysis.Under Characterization Survey Package Number C9000 10111, core bore samples were acquired at the following locations:

• In the Reactor Building on the 0' elevation, southern floor, a core bore sample was acquired on the floor adjacent to a removable steel hatch cover. This sample broke during extraction and was subsequently unusable for further analysis.* In the Reactor Building on the -25' elevation in the southwest quadrant, a core bore sample was acquired on the floor adjacent to the sump in the Area #22 Pump Room.* In the Reactor Building on the -15' elevation in the east floor area, one core bore sample was acquired on the floor adjacent to the concrete shielding for the primary water piping systems.* In the Primary Containment on the -25' elevation at the bottom of Canal "E", a core bore sample was acquired on the floor along the southern wall adjacent to the south canal entrance.A-7 Plum Brook Reactor Facility Final Status Survey Plan Revision 0* In the Primary Containment on the -25' elevation in the west area, a core bore sample was acquired on the floor adjacent to the inner wall across from the west stairwell.
• In the Waste Handling Building on the -13' elevation, a core bore sample was acquired on the floor adjacent to the north building sump.* In the Hot Laboratory on the 0' elevation, four core bore samples were acquired, one on the floor in front of Room #2, one on the floor in front of Room #6, one in the middle of the floor adjacent to Room #5 and one at the entrance to Room #16.* In the Hot Pipe Tunnel on the -12' elevation, two core bore samples were acquired, one in the middle of the tunnel section to the east of the corner and one on the side by the corner. Two additional core samples were acquired and placed in storage.* In the Fan House on the -12' foot elevation, one core bore sample was acquired on the floor adjacent to the air plenum and venture located against the north wall.* In the Primary Pump House on the 0' elevation, three core bore samples were acquired, one on the floors of Room numbers 1, 2 and 4 respectively.

These samples were not included as part of the sample population due to QA concerns that could not be resolved.* In the Reactor Office and Laboratory Building (ROLB), one core sample was acquired on the floor of the New Fuel Vault.Structures that could potentially contain activated concrete such as the bio-shield were not sampled at the time of this study because current decommissioning plans call for the removal of activated portions of the concrete bioshield and disposition of the activated concrete as radioactive waste.Each of the core samples was sliced and surveyed. Two Y2 inch thick "pucks" were sliced from the top of each core. Direct alpha and beta measurements were obtained on both the tops and bottoms of each puck. A preliminary radionuclide analysis was performed on each puck using the PBRF on-site gamma spectroscopy system. This analysis was performed not to specifically assess the nuclide distribution, but rather to qualitatively evaluate the depth of contaminant migration into the concrete at each of these locations. Each l/2 puck was analyzed twice, exposing the detector to both sides of each puck. The results of these analyses are presented in Addendum 2 of this attachment. The data presented suggests that with the exception of the Hot Laboratory, the majority of the reactor produced radionuclides were confined to the Ist "/2 inch of A-8 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 concrete surface. In the Hot Lab, the contaminant migration observed went deeper, at some locations to a depth of one inch.After the preliminary radionuclide analysis was complete, the samples were sent to an off-site laboratory for a full isotopic analysis. The top 1 inch concrete core was pulverized and analyzed for full isotopic content. Samples were prepared by transfer of the sample to a standard geometry or by removing a representative aliquot from the sample and processing the sample in accordance with the analytical technology selected. Gamma emitting isotopes were analyzed using a high purity Germanium (HPGe) gamma detector. Analysis for low energy gamma emitters used a planar, high purity germanium, low energy response gamma ray detector. Analysis for beta emitting isotopes employed beta liquid scintillation and alpha emitting isotopes were analyzed using alpha spectroscopy. These results are presented in Addendum 4 of this attachment. A-9 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Figure A-2 Concrete Core Population Sample Locations -Hot Laboratory NA"U GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO HOT LAORATORY*UILDINO No. 1112 Elfw. 4rf A-JO Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Figure A-3 Concrete Core Population Sample Locations -Hot Pipe Tunnel NASA GLENN EISEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO Mm "Pe Tun_ _ _ _A~k.2.NUM"AVAYM U NEAVATI C.M4 J , 00S40- XhN~mm Pi" Tmmd DA hum 2545 HOT LABORATORY BUILDING No. 1112 Elv. -1Z-0'A-il-ct3-NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO t GM0O w~~~- YL iEilev. X 3 P j5;'0 " B lev .8 00-25'h -Elv. UK REACTOR BUILDING BUILDING No. t1111 Elwv. O<1 0a Plum Brook Reactor Facility Final Stamus Survey Plan Revision 0 Figure A-5 Concrete Core Population Sample Locations -Fan House NASA (LENN RESEARCH CENTER PLUM UROOK STATION SANDUISKY, OHIO FAN HOUSE EUILDING No. 1132 Sav. a- 12-C-A-13 (~-o!'$- 0 Plum Brook Reactor Faciliti' Final Status Survev Plan Revision 0 Figure A-6 Concrete Core Population Sample Locations -Waste Handling Building NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO WASTE HANDLING BUILDING BUILDING Ne. 1133 Eliv. @-13'-0 A-14 0 0 Plum Brook Reactor Facilitv Final Status Survey Plan Revision 0 Figure A-7 Concrete Core Population Sample Locations -ROLB NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO OFFICE AND LAORATORY BUILDING BUILDING No. 1141 soev. a -IWO A-15 C0 07 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 6.3 Soil Sampling Surface soil samples were obtained to assess the radionuclide distribution in soils surrounding the facility. A sampling plan was developed and documented in characterization survey packages A2400 303C2 and A2100 101C2. Gamma scan surveys were performed using sodium iodide (Nal) detectors to ascertain the highest activity locations at the PBRF. Survey areas exhibiting scan results greater than twice the observed background were selected. At the area of highest observed scan activity, a one-liter soil sample was collected. Soil samples were sent to an off-site laboratory for processing and full isotopic analysis. Samples were analyzed for gamma emitting isotopes using a high purity germanium (BPGe) gamma detector. Analysis for low energy gamma emitters used a planar, high purity germanium, low energy response gamma ray detector. Analysis for beta emitting isotopes employed beta liquid scintillation and alpha emitting isotopes were analyzed using alpha spectroscopy. In total, eight soil samples were obtained: four from the Emergency Retention Basin and four from a suspected spill area south of the Waste Handling Building.Other open land areas on site also indicated elevated scan activity; however the eight locations selected were biased in order to acquire samples with relatively high isotopic concentrations in order to minimize the contribution of MDA values to the resultant nuclide distribution. Analytical results for the surface soil samples are presented in Addendum 3 of this attachment. A-16

• 0 *0 Plum Brook Reactor Facilitv Final Status Survey Plan Revision 0 Figure A-8 Surface Soil Population Sample Locations

-WHB Spill Location NASA OLENN RESEARCH CENTER PLUM BROOK SrATION SANDUSKY, OHIO N i CG X X Denotes site fence 0 0 Denotes Survey Unit boundary N Samplp Legatog MAP U -A2400 303C2-1 Rev. 0 urvwy Pack"-e C -A2400 303CR A-17 Plum Brook Reactor Facility Final Status Survev Plan Revision 0 Figure A-9 Surface Soil Population Sample Locations -ERB NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO I J.: : ~SP #2 c SP#1.F X#3 X0 I SF #4 wM10 I N X X -Denotes Survey Unit boundary N M10 -M10 Monument Marker Sarnple LcatIons Emretency Retention Basin MAP -A2100 101C2-1 Rev.O Survey Package # -A2100 101C2 A-18 co Plum Brook Reactor Facility Final Status Survey Plan Revision 0 7.0 Evaluation of Sample Results and Elimination of Insignificant Radionuclides

7.1 Minimum

Detectable Activity (MDA)In all three sample types (smear samples, core samples and soil samples), before the nuclide distribution could be evaluated, the analysis results reported as less than MDA were considered. It was expected that several of the nuclides would be reported as less than MDA since these nuclides have a low probability of being present. Two approaches were considered for evaluating MDA results: 1) include the MDA values as representing actual concentrations, and 2) remove the less than MDA nuclides from the mixture. Removing the nuclides was considered more appropriate and representative of actual site conditions because the non-detected nuclides are believed either to not be present or to be present at negligible concentrations well below the MDA value. A nuclide was included in the "discarded" category if it was not detected at concentrations above MDA in any individual sample in the respective smear, core and/or soil sample population. If a nuclide was detected above MDA in one or more samples in a given population, then the nuclide was retained and included in the mixture. For those radionuclides that were reported as positive in only a portion of the sample population, the MDA values were combined with the positive results to determine the mixture fraction. The MDA values were used in this case because it was conservatively assumed that if a radionuclide was positive in an individual sample then it could also be present in the remaining samples of the population. Using the MDA also has the effect of reducing the probability that a single positive radionuclide result in a given sample population will skew the overall percentage relationship between the isotopes when those percentages are normalized. The remaining nuclides were then evaluated for the presence of naturally occurring isotopes. Naturally occurring isotopes were ignored in subsequent calculations. 7.2 Mean Distribution Evaluation Following the analysis of all nuclides identified at activities greater than their respective MDAs, an assessment was performed to ascertain the activity of radionuclides that could be attributed to background. K-40, Pb-212, Pb-214, Bi-214, Th-228, Th-230, Th-232, and Ra-226 were detected at concentrations commensurate with levels normally found in background. Subsequently, these isotopes were removed from consideration in all the sample populations. The radionuclide distribution percentage for each remaining nuclide was then calculated by dividing the concentration for each nuclide by the sum of all remaining radionuclide concentrations in the sample population expressing the abundance of the specific nuclide compared against the total sample activity. The mean nuclide distribution was then calculated by taking the average of the individual core nuclide fractions in each sample population. A-19 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The smear sample mean nuclide distribution in Table A-I below contains all remaining radionuclides that were above MDA in one or more smear samples.Table A-1 Smear Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant ROLB Ag-108m ND 0.06% ND Am-241 0.19% 0.13% 0.02%C-14 0.20% 0.58% 0.26%Co-57 0.03% ND ND Co-60 2.38% 5.22% 0.98%Cm-242 ND ND 0.01%Cm243/244 0.13% 0.02% 0.01%Cm-245/246 ND ND ND Cs-134 0.03% ND ND Cs-137 43.69% 7.46% 16.62%Eu-152 ND 0.13% ND Eu-154 0.08% 0.15% ND Eu-155 ND ND 0.12%Fe-55 2.75% 1.98% ND H-3 8.29% 66.53% 38.87%I-129 0.02% 0.06% 2.66%Na-22 0.03% ND ND Nb-94 0.12% 0.03% 0.05%Ni-59 0.33% 0.45% 1.68%Ni-63 13.39% 13.66% 0.23%Np-237 ND ND 0.05%Pu-238 0.11% 0.04% ND Pu-239/240 0.13% 0.02% 0.02%Pu-241 1.19% 0.32% 0.45%Pu-242 0.06% ND ND Sb-125 ND ND 0.23%Sr-89 0.81% 0.03% ND Sr-90 25.43% 3.01% 4.03%Tc-99 0.58% 0.12% 0.30%U-233/234 0.03% 0.01% 31.87%U-235/236 ND ND 1.12%U-238 ND ND 0.42%ND -Radionuclide Not Detected A-20 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The nuclide distribution for the Balance of Plant (BOP) smear population indicates a nuclide distribution for H-3 of 66.53%. It is unlikely that the actual contribution of tritium to the nuclide distribution is of this magnitude. The H-3 contribution is skewed by the inherent inaccuracy of the smear sample approach for material sampling as a means to quantify H-3 activity. The core sample data analysis provides a more realistic indication of H-3 concentrations as the core bore material sampling approach results in a volumetric sample medium more appropriate for the quantification of H-3. However, as the presence of H-3 has very little effect on the calculation of the adjusted gross DCGL, the distribution of H-3 in the smear populations was not adjusted.The concrete core samples are believed to be more representative of the mixture that will remain after license termination than the smear samples because the majority of loose contamination will be removed during remediation. The majority of the potentially contaminated surfaces that will remain following structural remediation will be concrete.As previously stated, radionuclides that were not present in concentrations greater than their respective MDA values in any of the concrete core samples were removed from the mixture. These isotopes included Sb-125, Eu-152, Eu-154, Eu-155, Nb-95, 1-129, Np-237, Ni-59, Tc-99 and Cm-243/244. The core sample taken in the ROLB indicated no activity greater than background. Subsequently, a nuclide distribution based upon core sample analysis results can not be presented for the ROLB at this time. The concrete core sample mean nuclide distribution in Table A-2 below contains all remaining radionuclides that were above MDA in one or more core samples.A-21 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table A-2 Concrete Core Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant ROLB Am-241 0.41% 0.29% ND C-14 1.97% ND ND Co-60 0.65% 1.23% ND Cm-245/246 0.07% 0.19% ND Cs-137 78.04% 34.79% ND Fe-55 ND 18.93% ND H-3 0.83% 8.46% ND Ni-63 3.09% 19.71% ND Pu-238 0.06% 0.07% ND Pu-239/240 0.59% 0.06% ND Pu-241 0.81% 2.49% ND Sr-90 13.23% 11.74% ND U-233/234 0.14% 0.98% ND U-235/236 0.01% 0.09% ND U-238 0.11% 0.97% ND ND -Radionuclide Not Detected In the surface soil samples, Th-228, Th-230, Th-232, Th-227, Ra-226, U-234, U-235 and U-238 were detected at concentrations commensurate with levels normally found in background (U-234 concentrations ranged from 0.793 pC/g to 1.876 pC/g, U-235 concentrations ranged from 0.051 pC/g to 0.197 pC/g and U-238 concentrations ranged from 0.850 pC/g to 1.861 pC/g). Subsequently, these isotopes were removed from consideration in the soil radionuclide distribution mixture. The soil nuclide distribution in Table A-3 contains all remaining radionuclides that were above MDA in one or more surface soil samples.A-22 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table A-3 Surface Soil Radionuclide Distribution Radionuclide Open Land Areas Am-241 0.15%Am-243 0.16%C-14 2.11%Cm-245 0.22%Co-60 1.68%Cs-137 58.50%Eu-155 0.76%H-3 22.68%I-129 0.53%Nb-94 0.30%Ni-63 6.96%Pu-238 0.17%Pu-239 0.16%Sr-90 5.49%U-236 0.12%7.3 Application of the 10% Rule Based on data reviewed to date and considering the PBRF operational history, there appear to be three radionuclide mixtures for site structures and one distribution for soils. For site structures, the first applies to the Hot Laboratory, the second to the ROLB and the third to the remaining structures designated as Balance of Plant (BOP).The final step in determining the radionuclide distribution for each of the mixtures involved the elimination of radionuclides that have insignificant dose consequences. NUREG-1757, Vol. 2, Section 3.3, states that nuclides with a combined dose of less than 10% of the 25 mrem/yr unrestricted use criteria can be eliminated from further consideration. To determine which nuclides can be eliminated by the "10%" rule, a RESRAD or RESRAD-Build run was performed using the mean nuclide distribution derived for each sample population. The concentration entered for each radionuclide was the fraction listed in Tables A-1, A-2 and A-3, respectively. The RESRAD/RESRAD-Build runs used to perform the "10%" rule calculations are provided in site Technical Basis Documents and are available for review, as needed.For the mean distribution derived from the smear samples, RESRAD-Build and RESRAD evaluations were performed for the Building Reuse and Subsurface Structure scenarios, respectively. Concrete Kd data were not available in the A-23 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 literature for three radionuclides with very low nuclide fractions; i.e. Na-22, Np-237, and Sb-125 at 0.03%, 0.00%, and 0.23%, respectively. The RESRAD default Kd was used in the Subsurface Structure analysis for these radionuclides. Two radionuclides, Sr-89 and Cm-242, were reported as above MDA in one or more smear samples with mean fractions of 0.81% and 0.00%, respectively. RESRAD and RESRAD-Build do not list these radionuclides. Because of their very low fractions these nuclides were disregarded. In addition, Sr-89 is suspected to be a false positive because the half life is very short relative to the time since plant shutdown.The radionuclides that, in aggregate, were less than 10% of the total dose for both of the scenarios were eliminated. The mixtures were readjusted to 100% based on the relative fractions of the radionuclides remaining after the insignificant radionuclides were removed.The results of all RESRAD-Build and RESRAD runs, i.e. BOP, ROLB and Hot Lab mixtures in the Subsurface Structure and Building Reuse scenarios indicate that for the smear sample population, the aggregate dose from six radionuclides, i.e., Cs-137, Sr-90, Co-60, H-3, Eu-154 and I-129 resulted in 94% or more of the 25 mren/yr limit in all BOP cases, the aggregate dose from five radionuclides, i.e., Cs-137, Sr-90, Co-60, H-3, and Eu-154 resulted in 93% or more of the 25 mrem/yr limit in all Hot Lab cases and the aggregate dose from seven radionuclides, i.e., Cs-137, Sr-90, Co-60, H-3, I-129, U-234 and U-235 resulted in 93% or more of the 25 mrem/yr limit in all ROLB cases.For the core sample population, the aggregate dose from four radionuclides, i.e., Cs-137, Sr-90, Co-60 and H-3, resulted in 90% or more of the 25 mrem/yr limit in all BOP cases and the aggregate dose from three radionuclides, i.e., Cs-137, Sr-90 and Co-60 resulted in 92% or more of the 25 mrem/yr limit in all Hot Lab cases.As previously stated, a nuclide distribution based upon core sample analysis results can not be presented for the ROLB at this time due to the fact that the only available core sample indicated only background activity.The lowest total aggregate dose from the remaining radionuclides was 90% of the 25 mrem/yr criterion, which means that radionuclides potentially representing a dose of 2.5 mrem/yr were eliminated. To ensure the 25 mrem/yr criterion is met, any structural survey unit where the mean of FSS results indicates that the dose may be greater than 22.5 mrem/yr dose (including dose from embedded pipe in the given survey unit, if applicable) shall be reviewed for compliance with the unrestricted use limit. The final normalized radionuclide distributions for structural surfaces are provided in Tables A-4 and A-5 below.Additionally, the current decommissioning strategy for PBRF calls for the removal of activated portions of the concrete bioshield and disposition of the activated concrete as radioactive waste. Therefore, the activated concrete was not evaluated. A-24 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table A-4 Final Smear Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant ROLB Co-60 3.41% 6.72% 1.01%Cs-137 53.11% 7.74% 17.29%Eu-154 0.12% 0.17% ND H-3 10.84% 82.15% 39.71%I-129 ND 0.08% 2.82%Sr-90 32.52% 3.13% 4.17%U-233/234 ND ND 33.82%U-235/236 ND ND 1.19%ND -Radionuclide Not Detected Table A-5 Final Concrete Core Radionuclide Distribution Radionuclide Hot Laboratory Balance of Plant Co-60 0.79% 7.84%Cs-137 83.45% 41.45%H-3 ND 35.35%Sr-90 15.77% 15.36%ND -Radionuclide Not Detected For surface soil samples, the doses from all radionuclides other than Cs-137, Co-60, and Sr-90 totaled 0.5 mrem/yr. Because this dose is 2% of the 25 mrem/yr limit, all radionuclides other than Cs-137, Co-60, and Sr-90 were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, any open land survey unit where the mean of FSS results indicates that the dose may be greater than 24.5 mrem/yr shall be reviewed for compliance with the unrestricted use limit. The final normalized radionuclide distributions for soils are provided in Table A-6 below.Table A-6 Final Soil Radionuclide Distribution Radionuclide Open Land Areas Co-60 2.56 %Cs-137 89.08 %Sr-90 8.36 %A-25 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 8.0 Conclusion Per NUREG-1757 (Reference 2.6), the Nuclear Regulatory Commission (NRC) staff considers radionuclides and exposure pathways that contribute no greater than 10% of the 25 mrem/yr dose criteria to be insignificant contributors. This 10% limit for insignificant contributors is an aggregate limitation only. That is, the sum of the dose contributions from all radionuclides and pathways considered insignificant will be no greater than 10%of the dose criteria of 25 mrem/yr per 10 CFR Part 20, Subpart E.The dose from the insignificant radionuclides will be accounted for in demonstrating compliance, but may be eliminated from further detailed evaluations. The lowest total aggregate dose from the remaining radionuclides was evaluated at 90% of the 25 rnrem/yr criterion, which means that radionuclides potentially representing a dose of 2.5 mrem/yr were eliminated. To ensure the 25 mrem/yr criterion is met, any structural survey unit where the mean of FSS results indicates that the dose may be greater than 22.5 mrem/yr dose (including dose from embedded pipe in the given survey unit, if applicable) shall be reviewed for compliance with the unrestricted use limit.For surface soil samples, the doses from all radionuclides other than Cs-137, Co-60, and Sr-90 totaled 0.5 mrem/yr. Because this dose is 2% of the 25 mrem/yr limit, all radionuclides other than Cs-137, Co-60, and Sr-90 were eliminated from further consideration. To ensure the 25 mrem/yr criterion is met, any open land survey unit where the mean of FSS results indicates that the dose may be greater than 24.5 mrem/yr will be reviewed for compliance with the unrestricted use limit.Based on the evaluation of insignificant radionuclides as described in this attachment, soil and structural surfaces at the PBRF may contain one or more of the radionuclides listed in Table A-7. These radionuclides will be considered during the FSS design and sample analysis process.Table A-7 PBRF Radionuclides of Concern Co-60 Cs-137 Eu-154 H-3 I-129 Sr-90 U-233/234 U-235/236 The BOP core population does not include samples from a number of BOP locations such as the primary pump house and quads. However, the cores collected are considered representative of all BOP areas because the predominant source of contamination in all areas is reactor coolant. Additional confirmatory samples and/or measurements will be A-26 Plum Brook Reactor Facility Final Status Survev Plan Revision 0 performed in appropriate BOP areas to confirm the assumption that the cores collected are representative of all BOP areas. The final radionuclide distribution, gross activity DCGL values, and surrogate DCGL values will be determined and documented in each survey unit FSS design package.9.0 Addendums Addendum 1 -Results of Isotopic Analysis of Smear Samples Addendum 2 -Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory Addendum 3 -Results of Isotopic Analysis of Concrete Core Samples by the Offsite Laboratory Addendum 4 -Results of Isotopic Analysis of Surface Soil Samples A-27 Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &Final Status Survey of the Plum Brook Reactor Facility (PBRF)Addendum 1 Results of Isotopic Analysis of Smear Samples Page 1 of 4 Attachment A Addendum i Results of Isotopic Analysis of Smear Samples HOT LABORATORY a~iio Arn-24t C-44 Co47 Co40 Cm-242 Crn-2431244 Cs134 r f137 Eu-154 Hs-14129 Ne1-f Nb44 -N14-9 Nl143 Np-237 Pu-rnS PU-2391240 Pu-241 Pu-242 Sr-49 Sr40 Tc-49 U-23/4 U-235/30 u-23r 0 Hot Cell Equipment#1 Smaer (pci/flter) Results IDA Used Distriuion, 7.27E+03 8.0E8W 7.27E+03 0.15%9.25E202 1.37E+03 1.37E403 0.03%O.OOE200 1.2DE+02 12DE+02 0.00%2.74E+05 1.24E+02 2.74E+05 5.73%2.J1t400 7.82+00 712E+00 0.00%2.2E+02 2.25E+01 224E+02 0.00%4.14E+02 1.71E+02 4.14E+02 0.01%8.07E80 2.05E+02 8.07E+0S 16.09%1.79E003 3.89E+02 1.79Et03 0.04%1.09E+05 7.50E+01 1.69E+05 3.54%8.26E+05 3.04E+02 820E05 13.10%-2.31E+00 2.32E+01 2.32E+01 0.00%o.OOE+00 1.18E+02 1.12E+02 0.00%4.99E+04 1.52E202 4.99E+04 1.04%8.28E+03 2.90E+02 8.20E+03 0.13%g42E+05 1.80E4+0 1.9E+06 37.67%2.03E+00 2.65Ze4 2.03E+00 0.00%315FE+03 2.04E+01 3.58E+03 0.07%3.rSE+03 2.04E+01 3.85E+03 0.08%3.188E04 Z37E+02 3.18E804 0.68%2.5SE-01 3.59E+01 359E+Ot 0.00%4.50E+04 2.20E+02 2.202+02 0.00%8.27E05 3.49E+02 8.27E+05 17.31%1.84E+05 4.19E+02 1.68E+05 3.52%6.6eE+02 7.48E41 8.89E+02 0.01%4.34E+01 7.50E41 4.34E+01 0.00%90.58E00 9.35E41 9.58E+00 0.00%4.78E+08 100.00%lit C.l Equipment 42 SrM (Cl/ilter) Resuls tWDA Used Disttibuton 3.0DE+02 5.05E41 3.10E+02 0.07%1.242E02 8.12E+01 124E+02 0.03%0.00E400 8.2eE+01 62E+t01 0.01%8.J4E+03 2.25E401 8.84E+03 1.94%3.77E41 722E4t 7.22241 0.00%7.55E+00 7.32E41 7.55E000 0.00%4.01E401 8.92O401 632E Ot 0.02%2.71E405 8.98E401 2.71E405 80.88%O.ODE000 8.27E401 L27E401 0.02%144E+03 3.18E083 3.65403 0.J8%4.0E8+03 2.53E802 -4.89E+03 1.05%2.03E800 2.14E+01 2.14E+01 0.00%431+E01 1.59E802 159E+02 0.04%1.50E+01 2.92E+01 2.22401 O.O0%1388402 1.98E402 1882E02 0.04%3.70E+04 1.80E+03 3.70E804 8.45%2.80841 2.80E41 2.60E4t 0.00%2.17E+02 8.34E+00 Z17E402 0.05%3.11E+02 2.51E+00 112E+02 0.07%2.39E+03 1.08E402 2.39E403 0.54%5.07E400 3.48E+00 5.07E+00 0.00%-2.188404 242E+02 242E+02 0.05%1.152+05 3.5DE+02 1.158+05 284%3.23E+00 8.12E401 6.122+01 0.01%4.23E+01 7.00E41 4.23E+01 O.O%2.84E+00 2.75241 284E4+00 0.00%4.57E+00 Z74E41 4.57E+00 0.00%4.45E+05 100.00%Hot Cr1l Equipment 63 Smear (pCU/ilter) Reuls tlDA Used 1.35E+02 8.83E4t 1.35E+02 2.40E+02 6.21E401 240E+02 0.00E400 2.94E+01 2.4E240 2.87E403 1.27E+01 2.87E+03 1.J#41 2A47E41 2.47E41 2.BE4+00 5.50E4t1 Z8E+00 803E400 3.01E+01 3.012401 4.51E+04 3.22E+01 4.51E+04 1.94E+02 7.402+01 1.94E402 1.00E+03 4.09E403 402E+03 1.73E+03 4.51E+02 1.73E+03 125241 5.51E400 6.51E400 O.OE+00 142E401 1.42E+20 1.18E+02 1.57E+01 1.18E402 Z11E+02 2.70E+02 2.70E402 1.58E+04 828E+02 1.5U+04 2.58E41 2.S88E4 238E41 7.52E+01 5.558+00 7.52E+01 1.79E+02 Z9E4+00 1.79E+02 8.07E+02 1.83E402 8.07E+02 4.24E+00 i.1E800 4.24E+00 4.00E+03 2.70E+02 2.70E402 4.53E+04 3.65E402 4.83E+04 8.71E+01 4.552401 8.71E+01 248E+01 3.01E41 2.48E+01 1.11E+00 3.02E41 1.11E+00 8.02E41 7.87E41 8.02E41 1.12E+05 Dkstribullon 0.11%0.20%0.02%2.20%O.OD%0.00%0.03%38.23%0.18%3,47%1.47%0.01%0.01%0.10%0.23%1t32%0.00%0.06%0.15%0.68%0.00%0.23%3925%0.05%0.02%0.00%0.00%100.00%Arn441 C-14 Co-57.ce-a Crn-242 Cn-243/244 Cse,13at Cs137 Eu.154 0-855 H4-3 1-129 Na-22 Li , N-59/N143 Np-237 Pu-2B tt9/240 Pu-241 Pu-242 sr-B 8r40 Tc-9s U-233J234 U-2351236 U-238 Hot Cal Equlpment 14 Snow (pCi/lter) Resulms MDA Used 2.78E+01 2.45E41 2.78E+01 2.80E+01 3.37E+02 3.37E+02 5.23E+00 1.13E+01 1.13E401 1.582403 123E+01 1.58E403 9.e7E-02 7.40E41 7.40E41 22E1+00 7.83841 2.21E+00 3.77E400 1.47E+01 147E401 3.99E+03 1.81E+01 3.99E+03 284E+01 3.80E+01 3.N9E401 7.50E+02 Z90E+01 7.50E402 1.51E+04 3.94E+02 1.51E+04 1J.4E+00 1.38+01 13M401 9.55E+00 1.44E+01 144E401-1.25+00 1.27E+01 1.272401.4.30E+01 Z42E402 2A2E+02 4.50E+03 8.73E+02 4.50E+03-1.57E41 9.33E841 9.3E41 1.882401 3.07E+00 1.88E+01 1.55E401 2.55+E00 1.558+01 1.922+02 1387E+02 1.928+02 4.77E41 Z558+00 236ZE400-Z2E+02 2.85E+02 2.J5E402 3.18E+03 3.94E+02 3.10E+03-1.45E+01 4.05E+01 4.05E401 3.82E+00 0.24E01 3.882E00 3124E41 8.2eE41 *262E-O 5.62E41 1.03E+00 1303E400 3.04E+04 Dlstbutien 0.09%1.11%0.04%5.20%0.00%0.01%0.05%1313%0.13%2.47%49.70%0.08%0.05%0.04%0.80%14.81%0.00%0.05%0.05%0.53%0.01%0.94%10.47%0.13%0.01%0.00%O.OD%100.00%Not Cell Equiprnmnt 85 Smnv (pci/alter), Resulms MDA Used Disbibution 1.03E+02 7.73E41 1. 03E+02 0.03%3.55E+00 3.59E+01 339E401 0.01%8.33E+00 6.15E+01 .15E+01 0.02%3_23E+02 7.082400 3.23E+02 0.10%1.91E41 285E41 2.82E41 O.D0%1.45E+00 9.95E41 1.46E00 0.00%1.82E+01 .532E+01 6.52E4D1 0.02%28E#+05 8.04E+01 288E+05 0887%0.00E+00 3.04E+01 334E401 0.01%517E+02 8.52E+02 952E402 0.20%7.812E+1 2.70E+02 2.70E+02 0.08%-4.97E+00 2.33E201 2ME401 0.01%1.33E401 8.15E+00 1.33E801 0.00%2.91E+00 9.20+ 9.20E400 0.00%1.62E+02 2.41E+02 241E402 0.07%1.42E+03 3.67E+02 1.42E403 043%4.30E-03 813E41 8.13E41 0.00%551E+01 ZIE+.00 5.51E+01 0.02%1.04E+02 1.97E+00 1.04E+02 0.03%739E+02 202E+02 7.39E+02 0.23%2.49E+00 1.97E+00 2.49E+00 0.00%43.6E+03 253E+02 2.53E402 0.08%3.84E+04 2.87E+02 3.84E+04 11.71%4.e7E+01 1.00E+01 4.67E+01 0.01%8e10E+00 1.42E+00 8.15E+00 0.00%5.32E41 3.19E-01 5.32E41 0.00%2.12E41 8.11E41 3.11841 0.00%3.28E+05 100.00%Cltilber)Result 1.05E+02 3.e7E+01 O.ODE+00 4.91E+02 3.9E041 2.42E+00 4.45E400 1.16E+04 O.OoE+00 5.54E+02 1.95E+02 46.22E2Oi 1.53E+01 3.e4E400 1.17E+02 3.75E+03 3.02E43 5.64E401 4.5#E401 7.10E202 3.2E041*3-70E+03 9.70E+03 2.44E+01 2.18+00 1.87E41 2.30E41 MDA Used 2.01E41 1.05E202 3.89E+01 3.9E401 1.40+E01 1402401 7.50E400 4.91E+02 2.38E41 3.90E41 2.02E41 2A42E+00 1.84E+01 154E401 1.47E+01 1.18E+04 3.11E401 3.11E4D1 7.98E+02 7S86E+02 2.63E+02 2.53E402 8.17E+00 6.17E400 8.23E+00 1.53E+01 8.03E+01 8.03E401 221E+02 221E402 4.e9E+02 3.7#8+03.83E41 6.53E41 2.98E+00 5.84E+01 129E+00 4.55E+01 2.00E+02 7.10E+02 2.20E+00 2.2E+00 2.47E+02 247E+02 3.2E+02 9.70E+03 2.44E+01 2A4E401 8.95E41 2152+00 281E41 2.t1E41 2.80E41 2DE041 2.a2E+04 Not Cell Equiprmont SO 5mew Dleirlbutuon 0.37%0.14%0.05%1.74%0.00%0.01%0.05%41.10%0.11%2.83%0.93%0.02%0.05%028%0.70%1a29%0.00%0.20%0.15%2-52%0.01%0.88%34,37%0.09%0.01%0.00%0.00%100.00%Amr441 C-14 Co-57 Co-ho Cn-242 Cn-243/244 Cs1-4 Cs-137 Eu-154 Fe-O5 H-3"12s Ne-.=Nb-4 Nl-S NI-43 Np-237 Pu-2r Pu-2391240 Pu-241 Pu-242 Sr-49 Sr-So Tc-91 u-23=34 U-235/2 U-43 Hot cet Equipment 67 2m-pci/m lter)Results MDA Used stributilon 2.94E402 2803E41 294E+02 0.07%8.8OE002 1.42E+02 8.80E+02 0.19%O.OOE+00 4.41+O1 4.411E+O .0.01%6.O8E+03 203E+01 .012.+03 1.30%4.12E41 009E41 4.12E41 0.00%1i.M+02 8a41E41 1.93E+02 0.04%4.1#5+00 4.72E+01 4.72E401 O.O%1.OE+-05 5.402E+O1 109E+05 2421%0.00E+00 7.05E+01 7.tE+Ot 0.02%2.38E+03 3.70E+03 3.704D03 0.82%1.63E+05 0.91E+02 1.53E+05 35.20%4.79E41 2.14E+01 2.UE142 0.00%7.14E2+1 1.782+01 7.14E401 0.02%8a388EO1 230E+01 .38E4O1 0.02%OO.E0000 2.68E+02 2.66E402 0.08%4.058+04 1.94E+03 4.05E+04 9.00%8.26E41 5.80E41 8.24241 0.00%1.83E402 170E400 1.53E+02 0.04%3.91E+02 1.37E+00 3191E+02 0.09%1.82E+03 205E+02 1322+03 040%1.79E+01 3.17E+00 1.72E+01 0.00%8.70E+02 2362402 8.70E+02 0.15%1.22E+05 3.47E402 1,22E+05 27.1O%7.84E+01 1.08E+02 1.O8E402 0.02%7.a83+02 1.02E+00 7J.2E402 0.17%4.08E+01 1.42E+00 4.09E+01 0.01%1.33E+01 .14UE00 1.332+01 0.00%4.5DE405 100.00%Hot Cedl m Surfceh n btci/iiiter) Results fDA Used Disitutlon 1.10E403 1.8JE41 1.10E+03 0.05%3.94402 8.37E+01 3.94E+02 0.02%O.OOE+00 1.14E+02 1.14E+02 O0O0%8.18E204 516E+01 5.16E.04 219%5.84E41 2.11E41 5884E41 0.00%5.07E+01 8.46E41 5.07E+01 0.00%9.78E+00 1.17E+02 1.17E+02 O.OD%8.03E+05 1.2#E+02 8.53E405 34.12%1.18E+03 1.44E+02 1.18E+03 0.05%1.05E+04 428E+03 1.05E+04 0.45%5.43E+04 4.01E+02 5.43E404 231%O.OE+00 133E4O1 333E+01 0.00%0.00E+00 7.17E401 7.17+01 0.00%8.E6+01 7.08E+01 7.0sE4n 0.00%221E403 Z87E+02 Z22E403 0.00%1J.8+E05 7.78E+03 1.88E+05 7.05%1J.12400 5.9#E41 1.01E+00 O.OD%9.4E+02 4.78E+00 949E+02 0.04%3.01E+03 1.09E+00 3.01E+03 0.13%7r17E+03 1.11E+02 7.17E+03 0.30%1.40E+o1 1.09E400 402+O41 0.00%-1.90E+00 2.04E402 2.04E+02 0.01%1.258+00 Z72E402 1.252+00 53.12%-4.112E+00 .17E+01 6.17E+1 0.00%1.05E+03 8.27E41 105E403 0.04%5.52E+O1 6.29E841 5.52E+01 0.00%3.11E401 2.40E41 3.11E+01 0.00%2.352+00 100.00%Not CeO1 62 Stulf-e meer pi/fittebr) Remit 1 MDA Used 125E+03 8.82E+00 3.26E+03 1.3sE+02 8.93E+01 1.39E+02 1.30+01 4.27401 4.27E4 O2E04D4 3.13E401 201E204 1.31E+00 232E+01 2.32E+21 105E+O1 2.53E401 3.052+01 1.41E+01 5.03E+01 s.032401 1.09E+05 847E+01 1.084D05 4.07E402 7.01E401 4.07E402 262E+03 9.04E+02 ze2E+03 1.80E+04 5.33E+02 1.09E404 O.OOE+00 3.a2401 3J2E21 O.OOE+00 4.01E+01 491E401 278E+01 104E+01 3.644D01 5.53E+02 2.10E+02 553E+02 8.34E+04 153E+03 8.34E+04 8.98E42 735E41 7JSE41 8.75E+02 4.18E+01 8.75E402 2012+03 237E401 201E+03 1.4E+04 1A9E402 1.84E+04 2ZSE+01 4.17E401 4.17E401-1.97E+04 270E402 2.782402 115E+05 329E+02 1.15E+05 1.30E+04 1.04E202 1.3DE+04 5.43E+01 8.26E41 5.43E401 3.03E+00 8.02E41 3.03E400 2.50E+00 s.53E41 Zs0E+00 3.78E+05 DistrbUtlon 0.88%0.04%0.01%5.31%0.01%0.01%0.01%2881%0.11%0.es%Z88%0.01%0.01%0.01%0.15%2205%0.00%023%0.53%4.34%0.01%0.07%3040%3.44%0.01%0.00%0.00%100.00% Attachment A Addendum I Results of Isotopic Analysis of Smear Samples Page 2 of 4 C-Ia_Co-57 Cm-242 Cma-243d24 Ca-134 Cs-137 Eu-154 F 456 144 tNe.22 Nbl4 NI-O3 Np-237 Pu-23B Pu-2391240 Pu-241 Pu-242 Sr-S SrJO Tc49 U.-2334 U-23536 U-23S Am-MI C-14 Co-57 Co40 Cn-242 Cr-2431244 Cs-134 Cs-137 Eu-154 Fe-55 H4-3 U429 N*f-2 Nb-4 NI-S NI-43 d) Np437 Pu435 Pu.239/240 au-241 xu-242 5r40 13-2331334 13-235Zf33 U-23S Hot Catll1U Surftce 5neer (PC l4 tef)Remib 14DA Used Disebution 526E+01 8.73E4-1 5.265E01 0.45%9.95E+00 3.55E+01 3.55E+01 0.31%e.00E+00 7.42E+00 7.42E+00 0.05%3.87E+02 5.70E+00 3.87E+02 3.33%O.OOE+00 3.92E-01 392E-01 0.00%2.065+02 3.43Et01 206E+02 1.75%e86E-02 1i.o0+0i 1 2E+01 0.09%3.572+03 9.55E+00 3.572+03 30.76%53Y5+00 Z59E+01 2 2E+O 0.22%4.50+02 9.34E+02 9S.34E+02 6.05%1.71E+01 2-2S6E02 2.2E402 1.95%NWA WA 0 0.00%1.89E+00 9.30E+00 3JOE200 0.05%5.04E+00 9.15E+00 1.152400 0.C0%WA WA 0 0.00%2.781+03 4.33E+02 Z75E+03 2395%5.08E-2 7.785-01 7.718-01 0.01%1.29E+01 248E+00 1.29E+Ot 0.11%Z585+01 2.10E+00 2.55E+01 0.22%3.3SE+02 Z01E+02 3.35E+02 2.89%220E+00 2.48E+00 248E+00 0.02%6.9tE+02 3.21E+02 6.91E+02 5.95%Z.24E+03 3.672+02 2.24E+03 19.30%1.681+01 3.80E+01 3JOE.Ot 0.33%3.55 C00 1.812+oo00 3.65E+00 0.03%241E-41 9.23E0-t 9.23E24 0.01%1.20E-01 1.15+00 1.15E+00 0.01%1.16E+04 100.00%?Hot Call t6 Surtea Smear (cpvmilter) Rfesuls MDA Used Dlstributiu 5J.3E+01 5.55E4t1 5.3E+01 0.04%1.72E+02 5.77E+01 1.72E+02 0.13%3.36E+01 2.74E+C1 3.36E+C1 0.02%1.44E+03 9.e9E+00 1.44E+03 1.05%-1.58E48 1.10E+00 1J4E+00 0.00%1.01E+00 1.0C2+00 1.83+00 0.00%-1.16E+01 3.065+01 3.06E+01 0.02%8.19E+04 Z75E+01 8.19E+04 5952%O.OOE+00 4.0CE+01 4.t9+01 0.03%3.488E03 8.54E+03 8.42W03 6.24%4.47E+02 2J4E+02 4.47E+02 0.33%-3232+00 Z07E+01 2.07E+01 0.02%1J09E+01 9.79E+00 1J9DE+01 0.01%Z13E+01 1.25E+01 2.13E+C1 0.02%1.35E+02 2.61E+02 2.18+02 0.19%5A4E+03 5.49E+02 5.44E+03 3.97%2.52E41 5.31E4t1 9341tE 0.00%4.53E+01 7.75E+00 4.53E+01 0.03%1.32E+02 1.35E+00 1.32E+02 0.10%4A7E+02 Z02E+02 4A7E+02 0.33%8.98E+00 1.3SE+OC 5.9eE+Oo O.Ot%-6.97E+03 Z64E+02 2.24E 02 0.19%175E+04 2.89E+02 3.7S1+04 27.39%3.44E+01 4.27E+01 4J27E+C 0.03%3.91E+01 5.38E41 3.9tE+Ct 0.03%2.97E+00 8.41E41 Z970+00 0.00%1.42E+00 1.06E+00 1.42E+00 0.00%1.37E+05 100.00%lotCail #4 Surfacglmear Remsts MDA Used Dvlfslrbn 33tE+01 2.42E4t 3.31E+01 0.19%-1.08E+01 5.84E+01 8J4E+01t 0.33%9.09E41 9.59E+00 9J.9E+00 0.05%2.70E+02 5.70E+00 Z7CE+02 1.54%9.57E42 2.87E41 2.67E41 0.00%142E+00 2.43E41 1.4eE+00 0.01%4.80E+00 9.a2E+00 *.62E+00 0.05%5.87E+03 1.17E+01 5.7E+03 33.53%1.76E+00 1.69E+01 1.92401 0.10%6.s4E+02 7.5SE+02 7.5=+02 4-31%8.17E+02 4.37E+02 5.17E+02 3.52%-1.39E+00 1.53E+01 1.53E+01 0.09%5A47E41 8.11E+00 6.11E+00 0.03%-3.24E+00 523E+00 523E+00 0.03%729E+01 2.03E+02 2.03E+02 1.16%4.32E+03 4.54E+02 4.32E+03 24.57%-141E41 8.17E41 6.17E41 0.00%722E+01 5.17E+00 725+01 0.42%2.25E+01 3.04E+00 2.2E+01 0.13%2.68E+02 1.55E+02 2.6E+02 1.53%6.08E41 3.69E+00 3.69E+00 0.02%49.25E+02 2.13E+02 2.13E+02 1.22%4.70E+03 3.00E+02 4.70E+03 26.84%1.18E+01 3.35E+01 33E6401 0.19%1.74E+00 83E4-1 1.74E+00 0.01%5.21E48 8.37E4t1 637E4 0.00%1.74E41 2.81E41 2.61E41 0.00%1.75E+04 100.00%blat Call? S7 urface Smear (pClfltefr) Reeuls MDA Used Distributlon 4.523+01 Z70E-01 4.52E+01 0.00%4.30E+01 4.97E+01 4.JtE+01 0.10%4.57E+00 2.Z3E201 2.23E+01 0.04%5.30E+02 9.30E+00 5.3DE+02 1.03%2.12E41 5.112E-O .11E41 0.00%1.082+00 1.2tE+00 12tE+00 0.00%9.06E+00 2.73E+01 2.72+401 0.05%3.9SE+04 2.40E+01 3.95E+04 76.81%1.31E+01 3.46E+01 346E+01 0.07%4.03E+02 8.20E+02 8.20E+02 1.59%6.81E+02 2.44E+02 8.81E+02 1.32%5.41E42 1.11E+01 1.11Et01 0.02%4.74E+00 1.22E+01 1_.2E+01 0.02%4A2E41 1.04E+01 1.084E* 0.02%1.67E+02 2.35E+02 2.36E+02 0.45%2.50E+03 4.18E+02 2.80E+03 5.44%1.53E4t1 6.2 8E801 6.-411 0.00%1.23E+01 Z05E+00 1.23E+01 0.02%307E+01 1.17E+00 3.07E+01 0.05%332E+02 Z76E+02 3.32E+02 0.65%Z.E4t1 2.70E+00 270C+00 0.01%5.Z3E+02 3.01E+02 3.01E+02 0.59%5.91E+03 2.95Y+02 5.912+03 11.49%1.81E+01 4.56E+01 4.58E+Ot 0.09%7.5E+00 1.2E+00 7.59E+00 0.01%4.11E41 7.87E4t 7.87E4t 0.00%1.03E4t 9.82E41 93.2241 0.00%5.14E+04 100.00%iiDtCeflh5Suracesm"ea Resets MDA Used Distrbution 2.99E+01 2.48E41 2.99E+01 0.11%4.55E+00 5.45E+01 5.48E+01 O2t%1.27E+01 1.50E+01 1.502+40 0.06%1.53E+02 9.e9E+00 1.53E+02 0.55%-1.16E45 7 47E41 7A47E4 0.00%9.9542t 7.96E41 9.954t1 0.00%3.63E+00 1.a2E+01 1.112401 0.07%1.75E+04 1.70E+01 1.75E+04 66.42%Z2E+00 2.75E+01 2.75E401 0.10%6.06E+02 7.52E+02 7.52E402 2.85%332E+01 3.17E+02 3.17E202 1.20%2.12E+00 7.17E41 Z12E+00 0.01%9.e2E41 9.96E+OO 96fE+00 0.04%-1.25E+00 7.94E+00 7.4E+00 0.03%1.02E+02 5A7E+00 1.02E+02 0.39%9.00E+02 2.53E+02 9.00E+02 3.42%-1.42E41 241E+00 241E+00 0.01%3.39E+01 1.16E+00 3.3iE+01 0.13%2.O8E+01 9.S0E+00 2.08E+01 0.06%2.53E202 1.57E+02 2.53E+02 0.95%2.33E+W 1.90E+02 1.802402 0.72%-3.70E+02 2.44E+02 244E+02 0.93%5.E+03 3.562E+02 5.66E+03 21.48%-1.182+01 4.90E2+1 4.90E+01 0.19%3.03E+00 2.84E41 3.03E+00 0.O1%9.51E42 7.27E41 7.27E41 0.00%3.79E41 2.a4E41 3.79E4t 0.00%2.63E+04 tOO.OO%,Aa.241.0-14 Cm-242 Cm-Ma7C Cs-134 Cs-137 Eu-1U5 Fe-55 H44 F12i Ne-22 10-44 NI-5S MI-l3 MP-237 Pu-38 pu-23/240 Pu-24 Pu-44 sr-" 540 U-233/23 U-235/236 U-2u MEAN PCO/gm)9.82E+02 2.9sE+02 4.40E+01 23E+04 2.a4E+00 5.57E+01 6.93E+01 1.28E+05 3.04E+02 1.59E+04 6.76E+04 1.kS2+01 4.32E+01 3.8E+03 5.40E+02 1k.7E+0O 7.89E41 4.70E+02 7.54E+02 4.62E+03 1.25E+01 3.18E+02 1.98E+05 1AOE+04 2.07E+02 1.18E+01 52t1E+00 MEAN s5 DEV)0.19% 0.23%0.20% 0.28%0.03% 0.02%2.32% 1.a2%0.00% 0.00%0.13% 0.47%0.03% 0.03%43.69% 2Z68%0.06% 0.0%2.75% Z29%8.29% 15.29%0.02% 0.03%0.03% 0.02%0.12% 0.2a%0.33% 0.35%1339% 10.41%0.00% 0.00%0.11% 0.11%0.13% 0.13%1.19% 1.22%0.05% 0.19%O.81% 1.54%25.43% 11.76%08% 1.23%0.03% 0.04%0.00% 0.00%0.00% 0.00%100.00%Units for sampleconantrtioa ae presented in piOlr. Flter In thie rontext Is denned a standard rnearsample takeover a 100l 2 area. Attachment A Addendum I Results of Isotopic Analysis of Smear Samples BALANCE OF PLANT Page 3 of 4 Arr-2411 C-14 C*410 CQn24324 Crn-2451246 Cs-I37 Eu.152 Eu-1#r*-a H-s I-In Nb44 N43 Pu-2ea PU-239/240 Pu-241 Sr-SO Sr-90 Tcv-U4-231254 Quad A Sre Results 5.73E701 10A3E.O0 3.7W+04 5.0DE201 s.73E4t 1.22E 02 4.37E 01 O.OOE Oo+/-WE+02 1.07E+04 s.oeEo00 223E OO 1.28E+00 1.02E+Oi 1.39E+01 7.93E+01 32DE+01 1.94E4-1 MDA 7.24E+00 1.02E+00 4.47E+01 7.07E+00 1 .2d+00 7.22E-01 9.49E+00 2.0tE+01 2.31E+01 3.79E+01 5.22E 02 1.57E+01 a.&eeoo 4.46E+01 8.84E+01 e23E-01 9.49E-01 2.84E+O1 a.86E+00 8.58E+00 3.04E+01 9A3E-01 Used 5.83E+01 1A32+DO 1.0E9+03 3.76E+03 1.70E201 9.73E-0 1822E02 4.37E+01 2.IIE+8O 8.58202 8.07E+04 157E401 3.4E400 2.2DE+02 1.25E+04 2.92E+00 1.28E+00 2.64E+O1 1.39E+01 7.93E+01 3.2DE+01 SA3E4-1 9.99E+04 Disobtudon 0.05%0.00%1.08%3.78%0.02%0.80%0.12%0.04%0.02%o.88%80.79%0.02%0.01%0.22%1z81%O.OD%0.00%0.03%0.01%0.08%0.03,'0.00%100.00%'Quad C Smer Resuls 1MDA Used 4A4E+01 7.67E+00 4A4E+01 1.t2E+00 8.o0E-01 1.2E+Oo 7.W8E+02 4.89E+01 7.60E+02 4.50E+03 7.40E+00 4.50E+03 Z1E+01 2.-OE01 Z182E01 1.40E+00 3.23E41 1.40E+00 7A44E 01 1.02E+01 7.44E+01 5.17E+01 211+E01 5.17E+01 o.E0+00 2.53E201 238E+O 9.00E+02 3.8OE+O1 9.00E+02 3.902+04 3.57E+02 3.90E+04 3.e200 1o35E+01 1.35E+01-8.07E41 9.2sr+00 3212400+/-192+02 8.58E+O1 2.19E+02 1.76E+04 9.97E+01 1.76E+04 1.74E+00 1.1AE+00 1.74E+08 7.24E-01 7.03E-01 724E-01 5.7E+O0 ZSOE201 2.50E2+0 7.2ZE+00 1A8E+01 1AtE+01 4.27E+01 9.2DE+00 4.27E+01 312E+01 3.02E+01 3.19E+01 7.98E-01 7.62E-01 7.98E41 8.33E+04 CTMT OGneral Ares Swar IpCalter)Results MDA Used 8.09E+01 7.47E+00 8.89E+01 3.81E+00 7.24E-01 3.61E+00 2.90E+02 4.53E+01 2.90E02 3.57E+03 e.77E+00 3.57E+03 4.71E+01 8.a2E-01 4.71E01 9.33E2-1 4.00E2-1 9.33E41 3.6+/-E+02 9.38e+00 3.84E+02 1AOE+01 2.08E+01 2.0E2+01 o.OE+OO 2.08E+01 2.0dE2+0 4.43E+03 4.02E+01 4.43E+03 2.422+08 9.07E+02 2.42E+05 4.022+00 1.0DE+01 12OE+01 1.732+01 528E+00 1.73E+01 9.04E+01 7.67E+01 9.04E+01 1.19E+04 8.27E+O1 1.19E+04 6.51E41 9.05E4t 93.oE84 2.16E+00 1.04E+00 2.16E+00+/-71E+01 Z37E+01 +/-71E+01+/-902+01 7.18E+OO 2.99E+01 2.42E+02 9.64E+00 2,42E+02 9.05E+00 3.38E+01 3282+01 3.73E41 9.00E41 3.002-01 263E+0S Distwulon 0.07%0.00%1.20%7.10%0.03%O.OD%0.12%0.08%0.04%1.42%61.57%0.02% I 0.01%0.35%27.79%0.00%O.OD%0.04%0.02% 1 0.07%o.es%0.00%woolo%j CanalS E Smear (peuvifltar) Results MDA Used 1.98E+02 9.21E+00 1.98E+02 3.48E+00 3.6DE041 3.48E+DO 7.9S2+82 4.42E+01 752E+02 7.e1E+03 9.3ZE+00 7.etE+03 1.79E+01 3.62E41 1.79E+01 223E+00 4.18E-01 2.2E+00 1.A4E+02 1.23E+01 1A4E+02 0.52E+01 ZSE+01 6.e52+01 O.OOE+00 Z77E+01 2.77E+Ot 8.080+02 3.79E+01 8.05E+02 4.81E+04 4.14E+02 4.81E+04 3.74E+00 1.82+01 1.9dE+01 1.14E+00 1.11E+01 1.111E+1 25dE+02 7.95E+01 2.58E+02 3.2dE+04 1.30E+02 3.29E+04 3.68E+00 1.84E+00 3.68E+00 1.84E200 7.07241 1.84E+00 213E+01 29aZ+01 2.52E+01-1.38E+01 1.18E+01 l1.11E+o 1.02E+02 8.22E+00 1.02E+02 5.81E+01 4.3DE+01 5.91E+01 4.65E241 5.95E41 3.95E-1 9.11E+04 Disrton 0.22%0.00%0.87%8.38%0.02%0.00%0.19%0.07%0.03%o.A9%5+/-82%0.02%0.01%0.28%38.02%0.00%0.00%0.03%O.0O%0.11%0.0e%O.OD%* 100.00s Arn241 C-14 Ce40 Crn-2A3244 Cm-245s246 cs-1S?Eu-152 Eu-1#Hp--I29 Nb-4 N143 Pu45s Pu-2381240 Pu-241 sr-"s ArQ-241 C-14 C040 Cm-243/244 Cm-245J246 Eu-152 Eu-ISO H-S 1-129 Nb-4 Nl1143 Pu-2r PU-239/240 Pu-241 Sr-9s Sr-SO Tcvo U.-235234 Ufly Pad Smear (pCUfllteri Results MDA 4.70E+00 3.e3E+00 e.25E-01 7.17E4t 5.30E+O1 2.38E+01 2s53E+02 4.03E+00 2.05E+00 .75E-01 88DE-01 3.98E41 1.38E+01 4.05E+00 2.56E+00 1.07E+01 1.43E+00 1.04E+01 7.91E+02 3.a2E+o1 8.42E+03 3.03E+02 1.54E+01 2.21E+01 8.85E-t 3.91E+00 o.OE+O0 7.98E+01 1.24E+03 Z68E201 224E-1 71Z5E41 4.33E41 4.14E-01 2.58e+00 308E+01 4.02E-01 a.7sE+00 9.77E+00 a.11E+00 1.02E+01 3.39E+01 3.14E41 1.0oE+00 Rx Bulidcng Smar Duplicate IrCifiltmrl Results MDA N/A WA 1.01E+02 1.00E+O1 2.03E+01 1.37E+01 2.53E+03 7.07E+00 231E+00 7.91E41 NWA N/A 5.63E+03 1.01E+01 3S2E0201 4.82E+O1 9.2E+O+1 1.592+01.63E+00 200E2+01 1.OSE04 +/-a4E+01 1.94E+01 1.00E+01-1.22+100 a8.sE+oo-1.65E201 2.03E+01 e.7sE+01 6.a3E+01 2+/-8E+01 3.50E+00 1A8E+01 2.71E+00 1.79E+02 1.A3E+02 N/A W4A 2.04E+03 1.44E+01-1.21E+01 281E+01 4.3aE+00 4A43E+00 Used 4.70E+00 7.171-01 5.30E+01 Z53E+02 2.05E+00.8DE041 1.39E+01 1.7E+01 1.42+401 7.stE+02 6A2E+03 22t +o t 412E+00 7JI2+O, 1.24E+03 7.252E-433E-01 I.0OS2+01*.762+00 9.77E-00 328E+01 1.O1E+00 8.992E03 Used 0 1.OE+02 2.02E+01 2.53E+03 2.31E+00 0 5.63E+03 4.62E+01 9.62E+01 2.oE+Et 1.05E+04 1.94E+01 9.GO6dO0 2.03E+O 4*.32+01 2.8E+01 1.48E+01.7e+02 0 Z04E+03 2.1E+01 4A3E+O0 214E+04 Disbtvuton 0.05%0.01%0.53%281%0.02%0.01%0.15%0.12%0.12%8.80%71.40%0.25%0.04%0.89%1+/-79%0.01%0.00%0.34%0.10%0.11%O02%0.01%100.00%!Dlsributlbn 0.00%0.47%0.10%11.85%0.01%0.00%28.36%0.22%O.5%0.09%4s.16%0.03%0.04%0.10%0.32%0.13%0.07%0.83%0.00%9.55%0.12%0.02%100.00%Distriuon 0.03%0.08%O.11%1i8%0.02%0.00%0.14%0.01%0.01%1.68%91.95%0.00%O.O%0.03%4.52%O.00%0.00%0.01%0.01%0.05%0.01% I 0.00% -100.00%Rx Bulling Smear IpCfiIllerl Results MDA N/A N/A 7.84E+O1 1.47E+01 203E+01 1.37E+01 2.3sE+02 8.51E+00 223E+00 4.02E41 N/A WA 4.64E+03 1.02E+01 6.50E+01 3.70E+01 7.18E+01 1.75E+01-1.59E+01 1.79E+01 1.07E+04 2.89E+01 1.02E201 8.17E+00-3.68E41 9.12E+00 2.38E+02 2.ME+01 3.27E+01 8.59E+01 2.86E+01 3.50E+00 1.48E+01 2.71E+00 1.78E+02 1.43E+02 WA WA 2.04E+03 1.44E+01 O.OOE200 281E+01 4.38E+00 4.43E+00 Used 0 7.84E+01 209E+01 Z35E+02 2.39E+00.0 4.64E+03 6.50E+01 7.19E+01 1.7sE+01 1.07E+04 1.02E+01.12E+Oo 2.32E+02 s91E+01 2.86E20i 1.48E+01 1.78E+02 0 2.04E+03 2J1E+01 4A3E+O0 1.84E+04 00.11.29%0-01%0.00%25,15%0.35%0.39%0.10%58.00%0,06%0,05%1'25%0.36%0.16%0.05%0.96%0.00%it '06%0.15%0.02%100.00%I I o:Aq4O8rn:C44:Co-GO Cm-245/=C5437 Eu,152 Eu,154 F.-55 H-3 1429 Nb." 1,11411 MI-53 PU-=PU-239440 PU-241 sr-as sr4o To-" U-23=934 MEAN S.SsE+01 2.72E+01 4.3tE+02 3.21E+03 1.58E+01 8.85E-01 157E+03 4.33E+01 3.95E+01 1.12F+03 812E+04 1.57E+01 s.71E+oo 1.61E+02 1.09E+04 9.6DE+OO 5.15E+oo 7.05E+01 1.13E+01 6.51E+02 3.52E+01 1.91E+00 MEAN STD DEV (%)0.05% 0.07%0.13% 0.22%0.58% 0.48%512% 3.99%0.02% 0.01%O.OD% 0.00%7A6% 1Z501%0.13% 0.12%0.15% 0.19%1.99% 3.07%ee.53% 15.60%0.05% 0.09%0.03% 0.02%0.45% O08%13ee% 1378%0.04% 0.07%0.02% 0.04%0.32% OA1%0.03% 0.03%3.01% 3.80%0,12% 0.13%0.01% 0.01%100.00%Unils for sarn'paecia laons a prentod in pCVOnar. Fiar Intlh context Ia deind ass etandard esnareawple mbke owe 10mr2 am. Page 4 of 4 Attachment A Addendum I Results of Isotopic Analysis of Smear Samples Reactor Operations & Laboratory Building Am-241 0-t4 co-o cn-42 Cm-243t244 Oa-137 Eu-155 H-3 1-S2 Nb-U N14-9 H4143 Np-237 P-23Q40 Pu-241 Sb-125 sr4o Te49 U-2331234 U-232136 U-238 ROLt SMor (pcbfltar) Results MDA Used 1.82E+00 1.64E+00 1.82E+00 1.55E+01 1.53E+01 1.56E201 4.09E+02 1.1bE+01 4.09E+02-i54E-0 3.27E+00 3.27E+00 3.04E+00 1.64E+00 3.04E+00 4.77E203 1.37E+01 4.77E+03 1.26E+01 1.86E+01 1 BSE3ltt 2.08E+04 5.30E+01 2.08E+04 1.67E+01 1.20E+01 1.67E+01 6.74E+00 141E+01 1A1E+0t 5.16E+01 1tsE+02 1.5+402 3.13E+01 6.30E+01 630E+01 4.93E+00 1.00E+01 1.0DE+01 5.64E+00 1.95E+00 5.64E+00 5.85E+01 9.47E+01 9.47E+s1-1.24E+00 5.26E+01 5.262E40 1.53E+03 1.48E+01 1.53E+03 5.96E41 Z80E+01 280E+01 9.15E+01 3.97E+00 9.15E+01 532+00 2.84E+00 5.82E+00 4.81E+00 2Z85E+00 4.8iE+00 2.61E+04 wistrtfrlon 0.01%0.06%1A5%0.01%O.O%18.96%0.07%73.93%0.06%0.c5%0.69%0.22%0.04%0.02%0.34%0.19%5.44%0.10%033%0.02%0.02%100.00%ROLB Sonic Dupkate (pCiViter) Result MDA Used 1.8E+00 1.t4E+00 1.82E+00 1.05E+01 1.03E+01 1.66E+01 4.09E+02 1.1SE+01 4.002+02-2.54E41 3.27E+00 3m27+00 3.04E+00 1.64E+00 3.04E+00 4.77E+03 1.37E+01 4.77E+03 126E+01 1.85E+01 1.s6E+Ot 2.05E+04 5.30E+01 2.0tE+04 1.b7E+01 1.20E+01 1.67E+O1 8.74E+00 1.41E+01 IAIE+01 5.16E+01 1.96E+02 105E+02 3.13E+01 630E+01 6.30E+01 734241 4.43E+00 4A3E+00 1.0tE+01 3.19E+00 1.06E+01 9.32E+01 1.50E+02 1.80E+02-1.24E+00 5.26E+01 5.2E+0 1.48E+03 139E+01 1.48E+03 5.96E-D 2.80E+01 2.e0E+Dt 8.52E+01 1.81E+00 8.52E+01 4.42E+00 2.24E+00 4A42E+00 4A46E+00 2.18E+00 4.46E+00 Z81E+04 Disribution 0.01%0.04%1i45%O.Ot%O.Ot%16.90%0.07%73.96%0.06%0.05%0.69%0.22%0.02%0.04%0.53%0.19%5s26%0.10%0.30%0.02%0.02%100.00%ROtB Senri2 pouflttr)Results MDA Used 8.07E+00 1.70E+00 6.07E+00-4.68E+01 8.614E01 *.8tE+01 802E+O1 8.51E+00 5.90E+01 8.22E-01 1.53E+00 1.53E+00 85 E4E1 2.09E+00 2.09E+oo 2.s7E+03 1.14E+01 2.97E+03 1.46E+02 3.23E+01 3.23E+01 4.92E+02 6.84E+02 *.e4E+02 9.63E+02 1.04E+01 9.63E+02 1.91E+02 5.11E+00 8.11E+00-4.30E+02 4.71E+02 4.71E+02 1.70E+02 4.47E+01 4A47E+01 3.eSE+00 1.74£+01 1.74E+01 1.8E+00 1.53E+00 1.82E+00 8.80E+01 7.57E+01 7.57E+01 5.92E+00 4.83E+01 4.83E+01 4.81E+02 1.23E+01 4.81E+02 9.04E+01 8.89E+01 8.89E+01 1.1E+04 4.93E+00 1.18E+04 3.94E+02 3.35E+00 3.94E+02 1.42E+02 2.71E+00 1.42E+02 1.84E+04 0.03%0.47%0.48%0.01%8.01%16.18%0.18%3.73%5.24%0.04%2.56%0.24%0.09%0.01%0.41%0.26%2.62%0.48%64.02%2.14%0.77%1O%A-241 0-14 Co-O Cm-242 Cm-2431244 c-137 Eu-1ss H4-14129 Nb-4 NI-5, NW Pu-239f340 Pu-241 Sb-125 srt0 Te4s U-233f234 U-235/23 U-230 ROtB Snar 2 Dupilctae (peUwItar) Results MDA 2.35E+00 2.N0£+00-2.04E+01 8.51E+01 9.58E+01 7.77E+00 4.70E-3 Z23E+00 8.5DE41 Z11E+00 2.90E+03 1.17E+01 2.77E+01 3.18E+01-4.15E+02 6.85E+02 9.32E+02 1.05E+01 1.94E+02 7.77E+00 4.2tE+01 4.93E+02 1.68E+02 4.36E+01-1.58E+00 8.72E+00 2.00E+00 9.05E41 5.34E+01 9.19E+01 4.72E+00 4.69E+01 49.7E+02 1.26E+01 4.51E+01 8.87E+01 1.11E+04 5.04E+00 4.08E+02 3.28E+00 1.52E+02 4.StE+00 Used 2.00D+00 9.51E+01 9.5E+01 23E+00 2.11E+00 2.90E+03 3.18E+01 4,5£+02 9.32E+02 7.77E+00 4.93£+02 4.36E+01 8.72E+00 2.0DE+00 9.19E+01 4.69E+01 4.97E+02 8.87Ei01 1.11E+04 4.05E+02 1.52E+02 1.77E+04 Oletribtn 0.02%0.48%0.54%0.01%0.01%1e.40%0.18%3.87%5.27%0.04%2.79%0.25%0.05%O.Ot%0.52%0.27%2.81%0.50%ezs2%2.3D%0.85%10D%Am-241 0-14 0+40 Cm-2 4 2 Cm -243r44 Cr-1ft7 Eu-155 H43 Np-237 Pu.226/240 Pu.241 Sb-125 Sr-so Tc-99 U-233/234 U-2351235 U-238 MEAN IpCUqm)3.15E+00 4.93E+01 Z51E+02 zS5E+00 2.57E+00 3.85E+03 2.53E+01 1.07E+04 4.02E+02 1.10E+01 335E+02 5.35E+01 1.01E+01 5.08E+00 1.03E+02 5.01E+01 9.97E+02 5.84E+01 5.76E+03 2.03E+02 7.58E+01 MEAN (%)0.02=/0,26%0.95%0.01%0.01%1e.62%0.12%358.7%2.66%0.05%1.68%0.23%0.05%0.02%0.45%0.23%4.03%0.30%31.87%1.12%0.42%10o.00%SD DEV 0.01%0.25%0.54%0.00%0.00%0.40%0.06%40.50%3.00%0.00%1.15%0.01%0.03%0.01%0.D9%0.04%1.53%0.23%36.44%1.27%0.45%Urits for sample conreraflne ae prnted to pCi~ltar. Fiter In 9hi crtext Is defined -a standard areerwrpbe take ever a 100N2 are_. Attachment A Addendum i Results of Isotopic Analysis of Smear Samples (10% Rule Normalized) HOT LABORATORY 9Hot Col Equipment in Smear g Hot Car Equipment

1. 2 Smear -Hot Cad Equipment 13 Smear HM 2. (pCViaru .(pCltfn lpCmter CG 3R7sutts MDA 14D+str2bu101 n Results MOA Used Dlstrbuttan Results MDA Used co Z74E 124 02 2.74E+05 10.81% 8.E8 +03 1% 2.67+03 1.27E+01 2.67E+03 Cs- 137 8.07E+05 206E+02 tt07E+05 31.t2% 2.71E+05 5.S9E+01 2.71E+05 67.85% 4.51E+04 3.22E+01 4.51E+04 Eu-154 1.79E+03 3.69E+02 1.79E+03 0.07% 0.00E+00 8.27E+01 8.27E+01 0.02% 1.94E+02 7.49E+01 1.94E+02 H-3 (t.26E+05 3.49E+02 6.26E+05 24.69% 4.69E+03 2.53E+02 4.69E+03 1.17% 1.73E+03 4.51E+02 1.73E+03 Sr-0 8.27E+05 3.49E+02 827E+05 32.81% 1.15Y+05 3.50E+02 1.15E+05 28.79% 4.63E+04 3.65E+02 4.63E+04 2.54E+06 100.00% 3.99E+05 100.00% 9.60E+04 Hot Cog Equipment t4 Smear tpewr)Results HIDA Used Co40 1.58tE+03 1.23E+01 1.58E+03 Cs-137 3.99E+03 1.61E+01 3.99E+03 Eu154 2.64E+01 3.99E+01 3.99E+01 N 1.51E+04 3.94E+02 1.51E+04 Sr-SO 3.18E+03 3.94E802 3.18E+03 2.39E+04 2'Hot Cell Equilpment
2. 7 Smear Results MDA Used Co-Go 6.08E+03 2.03E+01 6.O8E+03 Cs 137 1.09E+05 5.49E+01 1.09E+05 Eu-154 O.OOE+00 7.95E+01 7*5E+01 H43 1.63E+05 8.91E+02 1.63E+05 Sr40 1.22E+05 347E+02 1.22E+05 4.00E+05%Hot Cel3S Surface Smear§1PCVXmt )g Results MDA Used Co-G o 3.87E+02 8.70E+00 3.87E+02 Cs-137 : 3.57E+03 9.55Y+00 3.57E+03 Eu-15t 5.35E+00 2.59E+01 25968+01 H-J 1.71E+01 Z26E+02 2.26E+02 Sr-4 .2.24E+03 3.67E+02 2.24E+03 6.45E+03 Hot Cot #6 Surface Smear fpCpciilr)

Results MDA tsed Co-Go 1.44E+03 9.69E+00 1.44E+03 Cs 137 8.19E+04 Z75E+01 8.19E+04 Eu-154 O.OOE+00 4.01E+01 4.01E+01 H-3 4.47E+02 244E+02 4.47E+02 Sr-40 3.75E+04 2.39E+02 3.75E+04 121E+05 Hot COt Equipment 45 Smear lpClfl~t tr)Distrbutdan Results MDA 6.81% 3.23E+02 7.08E+00 16.70% 2.85E+05 6.04E+01 017% O.OOE+00 3.04E+01 63.21% 7.61E+01 2.70E+02 13.31% 3.848+04 2.87E+02 100.00%Hot Cll 01 Surface Smear 1-(pcvMa.,), Wstrbullon Results MDA 1.52% 5.16E+04 5.16E+01 2724% 8.03E+05 1.25E+02 0.02% 1.18E+03 1.44E+02 40.73% 5.43E+04 4.01E+02 30.49% t.25E+06 2.72E+02 100.00%Not Cd .tt Surface Smear Dlstrlbutlon ~. Re"ults MDA 6.00% 2.70E+02 5.70E+00 55.36% 5.87E+03 1.17E+01 0.40% 1.76E+00 1.69E+01 3.50% 6.17E+02 4.37E+02 34.73% 4.70E+03 3.00E+02 100.00%eHt Cetl 67 Surface Smear (p'lC01tter) Dtstrobutien Results MDA 1 19% 5.308+02 9.30E+00 87-50% 3.95E+04 2.40E+01 0.03% J1.31E+01 3240E+01 037% .681E+02 2.44E+02 30.91% 5.91E+03 2.95E+02 100.00%Used 3.23E+02 2Z85E+05 3.04E+01 2.70E+02 3.94E+04 3.24E805 Used 5.1 8E+04 5.03E+05 1.18E+03 5.43E+04 1.25E+06 2.16E+06 Used 2.70E+02 5.87E+03 1.69E+01 6.17E+02 4.70E+03 1.15E+04 Used 5.30E+02 3.95E+04 346E+01 6.81E+02 5.91E+03 4.S7E+04.r 5 Hot Cal Equipment SO Smear Dkstrtbutlon Results MDA Used 0.10% 4.91E+02 7.50E+00 4.91E+02 87.96% 1.16E+04 1 47E+01 1.16E+04 0.01% 0.00+00 3.11E+01 3.11E+01 0.08% 1.95E+02 2638+02 263E+02 11 85% 9.70E+03 3.54E+02 9.70E+03 100.00% 2.21E+04 Hot Cdl 82 Surface Smear{~PCVmt.,) Dtstribution Results MDA Used Z39% 201E+04 3.13E+01 2.01E+04 37.17% 1.09E+05 6.47E+01 1.09E+05 0.05% 4.07E+02 7.91E+01 4.07E+02 2.51% 1.09E+04 5.33E+02 1.09E+04 57.87% 1.15E+05 3.29E+02 1.15E+05 100.00% 2.55E+05 Hot Cel 6S Surface Smear Dlstuibution R(C utts MDA Used 2.35% :1.53E+02 9.69E+00 1.53E+02 51.16% 1.75E+04 1.70E+01 1.75E+04 0.15% 2.62E+00 2.75E+01 2.75E+01 5.38% 3.32E+01 3.17E+02 3.17E+02 40.96% 5.66E+03 3.5eE+02 .5.66E+03 100.00% 2.37E+04 MEAN MEAN;(pCI/am) (5k)Dlsrhbutlon

1 1.14% c-Go4 2.83E+04 3.41%5.66% i55 Cs-137 1.88E+05 53.11%0.07% +<Eu-154 3.04E+02 0.12%1.46% kH-S 6.76E+04 10.84%12.67% -. Sr-90 1.98E+05 32.52%100.00% g 100.00%Page 1 of 3 Dsthrbution g 2.78% g 46.98%0.20%1.d0% A 48.23%100.00% E>5: Dlstribution 222%52.52% 5: 0.14%1,19% ;43.9%100.00%Dlstrbuteon 7.87%42.68% -0.16%427%45.03%100.00%Distribution 0.65%73.97%0.12%1.34%23.92%100.00%" STD DEV 3.15%21 .35%0.10%19.01%13.97%Units tor sanrphe coonenfretionsare presented In pCifiltter.

Filter In lUis context is defined

• a standard ear sarrpie take over a 100crn2 area.

Attachment A Page 2 of 3 Addendum I Results of Isotopic Analysis of Smear Samples (10% Rule Normalized) BALANCE OF PLANT Qud ASmear Quad C Smear &CanaIESm.ar Z Pcwffilter) g(pCVlclar) I(pCftflr) t )Resuls MDA Used Dktrtbutbn Result MDA Used Dlstributlon Reautts MDA Used Dlstulbn CSCo4 j 3.78E+03 7.07E+00 3.782+03 4.46% 4.50E+03 740E+00 4.50E203 10.31% 7.81E203 9.32E+00 761E+03 13.59%Cs-t7 122E+02 9.49E+00 1.2E+.02 014% 744E+01 1.02E+01 7A44E01 0.17% 144E+02 1.23E+01 1A44E2+ 0.26%Eu-154 O.OOE+00 2.31E+01 231E+01 0.03%. 00OE800 2.832+01 2.63E+01 0.06% O.00E+OO Z77E+01 2.77E+01 0.05%tS3 0.07E+04 522E+02 0.07E+04 95.25% 3.90E+04 3.57E+02 3.90E+04 89.33% 4.51E+04 4.14E+02 4.51E+04 85.89%U-i29 5.06E+00 1.57E+01 1.57E+01 0.02% 3.62E+00 1.35E+01 135E+01 0.03% 3.74E+00 1.88E+01 1.88E+01 0.03%Sr490 7.93E+01 8.56E+00 7.93E+01 0.09% 4.27E+01 9.20E+00 4.27E+01 0.10% 1.02E+02 8.25E+00 1.02E+02 0.18%8.47E+04 100 00% 4.37E+04 100.00% 5.80E+04 100.00%lly Pad Smoar CTMT General Area Smear IRX Building Smer (pCflHler) $P Cmted C5lll Results MDA Used lsutrbutbon ResultS MDA Used Distributon

~ Resuls MDA Used Dktrbutlon Co-so 2.53E+02 4.03E+00 2.53E+02 376% 3.57E+03 6.77E+00 3.57E+03 14A% 2.38E+02 8.51E+00 2.38E+02 1.34%Cs-137 1.39E+01 4.05E+00 1.39E+01 0.21% 3.64E+02 9.38E+00 3.64E+02 0.15% 4.84E+03 1.02E+01 4.84E+03 28.21%Eu.1U 153E+00 1.04E+01 1.04E+01 0.15% O.0OE+00 2.08E+01 2.08+401 0.01% 7.18E+01 1.75E+01 7.18E+01 0.41% k*H4 6.42E+03 3.09E+02 &.42E+03 95.41% 2A2E+05 9.07E+02 2.42E+05 98.29% 1.07E+04 2.89E+01 1.07E+04 6045%U29 1.542+01 2.212+01 2.21+01 0.33% -4.02E+00 1.00E+01 1D.0E+01 0.00% 102E+01 817E+00 1.02E+01 0.06%sr-S0 9.77E+00 8.11E+00 9.77E+00 0.15% 2 42E+02 8.84E+00 2A2E+02 0.10% Z 04E+03 1A4E+01 2.04E+03 11 3%8.73E+03 100.00% 248E+05 100.00% .1.77E+04 100.00%", Rx Buiding Smear Duplicate k*pCIlller)

MEAN MEAN STD DEV Results MDA Used Dtrlbuton (pCI/amy ) (S Cu40 2.53E+03 7.07E+00 2.53E+03 1215% 8Co40 3.21E+03 6.72% 5.I7%Cs-137 SJ83E+03 1.01E+01 8.832+03 27.05% Cs 137 1.57E+03 7.74% 12.91%Eu1U5 9.82E+01 1.592+01 9.82E+01 048% Eu-15U 3.95E+01 0.17% 0.19%Hi- 1.05E+04 284E+01 1.05E+04 5044% 4 1-3 625E+04 82.15% 18.93%1429 1.94E+01 1.00E+01 1.94E+01 0.09% ml I 9 1.57E+01 0.08% 0.11%sr-S0 Z04E+03 1.44E+01 2.04E+03 9.80% .Sr4So 8.51E+02 3.13% 3.88%Z.08E+04 100 00% 100.00%Unts for mpnl concentrations are prentd In pCi/lfiller. Flterin Nts conext is defled as a standard rnunr sacrple take over a 100nn2 area. Attachment A Pageo 3 of 3 Addendum I Results of Isotopic Analysis of Smear Samples (10% Rule Normalized) Reactor Operations & Laboratory Building ROLt3 Sm*er ROLt Smear Dupkatt $ROLB Smear 2..)(PgC ter) Ue pCUvlter) -ft wter)_ RRutse DA Used Dktrbudon Results MDA Used Dktrbutlon Results MDA Used Disibufion, Ce-O 4.09E+02 1.18E201 4.09E+02 148% 4.09E+02 1.16E+01 4.092+02 1.48% 8.90E+01 8.81E+00 8.90E+01 0.51%Cs-137 477E+03 1.372401 4.772+03 1727% 4.77E+03 1.37E+01 4.77E+03 17.30% 2.97E+03 1.14E+01 2.97E+03 17.14%FW Z08E+04 5.30E+01 2.08E+04 75.30% 2.08E+04 5230E+01 2.08E+04 75:40% * -4.98E+02 6.UE+02 6.844E02 3.95%U29 1.o7E+01 1.20E+01 1.67E+01 0.06% 1.67E+01 1.202+01 1.67E+01 0.05% 9.83+02 1.042+01 9.632+03 5.55%Sr-0 1.532+03 1482E+01 1.53E+03 5.54% 1.48E+03 1.392+01 148E+03 5.37% 4.812+02 1.23E+01 4.12+02 2.77%U-233/234 9.15E+01 3.97E+00 9.15E+01 0.33% 8.52E+01 1.51E+00 8.52E+01 0.31% 1.18E+04 4.93E+00 1.18E+04 67.81%U-2335/36 5o2E+00 2U4200 5.52Et00 0.02% 4.42E+00 2.24E+00 442E+00 0.02% 3.94E+02 3.35E+00 3.94E+02 227%2.76E+04 100.00% Z76E+024 100.00% 1.73E+04 100% k 0 3 ROLt Smear 2 Dupliate MEAN~%lCUflttr) lpCl/gm)Results IDA Used Dtribulou Ce-O i.58E+01 7.77E+00 9.58E+01 0.58% Ce40 2.512+0 Cs-S 2.90E+03 1.17E+01 2.002+53 1744% Cs-137 3.85E+0 H-S .4,15E+02 6.o'iE02 6.85E+02 4.12% tSt3 1.07E20 U29 9.32E+02 1.05E+01 932E+02 5.60% U129 4.82E+0 Sr-DO 4.97E+02 1.26E+01 4.97E+02 2.99% kVSr40 9.97E+0 1-n3324 1.12E+04 5.04E+00 1.11E+04 68.82% 15-233/234 5.76E+0 5-235/236 4.08E+02 3.28E+00 4.08E+02 2.45% J-235/2361 2.03E+0 1.66E+04 100%MEAN STD DEV M(" 2 1.01% 0.04%3 17.29% 0.13%4 33.71% 41.19%2 2.82% 3.19%2 4.17% 1.49%3 33.82% 38.68%2 1.19% 1.35%100.00%thik for *arrpb cos entragons a presented in pCi6tIer. Fillter in Is rontext [a defned as a standard rnar sanrrp. take Ver a 100cmn2 area. Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &Final Status Survey of the Plum Brook Reactor Facility (PBRF)Addendum 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory Attac( i ( 4 Adden d.Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory CORE BORE #5, Reactor Building -25 ft., Area 22 g C9000101MFL1C1L0505-01 1ST PUCK *C9000101 nFUIIC1L0505 01A 1ST PUCK '.C9000101 nIFLICILOS5.02 2CND PUCK SC900101"nLICIL0505-02A 2CND PUCK OINCH DEPTH it2 HDNCH DEPTHH DPTH-INH DEPTH Resulb MDA Used % Ruls MDA Used S esulb MDA Used % Results MDA Used %K-40 5.26E+00 1.94E+00 6.26E+00 12.35%A 7.102E00 1.94E+00 7.10E+00 22.27% 7.41E+00 2.02E+00 7.41E+00 93.01%M 7.95E+00 2.02E+00 7.95E200 Co-60 2.77E+01 1.97E-01 2.77E+01 64.98% 1. 81E+01 1.97E-01 1.81E+01 56.81%ND 0 D 0 Nb-94 ND D ND D Ag-1 08m 6.61 E-01 3.21 E-01 6.61 E-01 1.55% N ND 0 ND Cs-137 7.74E.00 3.34E-01 7.74E200 18.1 4.56E+00 3.71E-01 4.56E+00 1 N4.31 D O 3.93E-01 2.04E-01 3.93E-01 Eu-152 ND ZND :ND J.ND Eu 154 ND fND M ND K ND TI-208 ND .ND ND %ND Pb 212 ND ND 5.572-01 3.76E-01 5.57E-01 6.99%I 6.24E.01 3.912-01 6.24E-01 Pb-214 ND 0 1.214E00 7.07E.01 1.21E+00 3.79% ND 0 ND 0 81-212 'ND ND .ND ND 51-214 1.26E+00 5.26E-01 1.26E+00 2.95% 9.00E-01 5.24201 9.002-01 2.82% ND 0 ND 0 Ra-226 ND D D DD Ac 228 ND ND NO Th-234 KND ND MND %ND U-235 ND D ND D Am-241 i' ND RND ND MND Cm-243 ND ~'O ND Cm-245 ND ND D ND 4.26E+01 100.00% .0 100.00 7.96E+00 100,00%A 8.97E+00 r AgeI of 16 88.66%4.39%6.95%.100.00%0 Inch 112 ,rc/.12 I\ch I rich z i 1/2 INCH I 1/2 INCH I 3.QOE601_0ce137I h"Pb-2I2-cb-214 Itz 1n2 Oepth AttacC A Adde. .2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory CORE BORE #6, Containment -25 f Canal E LC900010111FIUC3L05061 1ST PUCK C9OOOoi PFLIC3L05O6-0I 04NCH DEPTH 1124NCH DEPTH~Results MDA Used -% Results MDA K-40 1.24E+01 2.96E+00 1.24E+01 5.23% :'ND Co-SO ND 0 6.61E+00 3.00E-01 Nb-94 K.ND ND Ag1OSm 'ND ND Cs-137 222E+02 9.47E-01 2.22E+02 93.43%4 2.70E+02 8.92E-0 Eu-152 ~ ..ND ND EuI 54 1U ND 0 342E+00 1.62E+Ot T1-208 ND 0 NO Pb-212 D OD Pb-214 D ND 0 Bl-212 ND 0 6.#E+00 7.08E+O Bi-214 ND O 3.10E+o 1.67E+0 R-226 ND 0 Ac-228 ND ND Th-234 ND NO U 235 ND ND Am-241 3.17E+00 1.95E+00 3.17E+00 1.33% 6.75E+00 2.23E+0 Cm-243 ND ND Cm-245 ND ND 2.38E+02 100.00%\ ': C7 (r P'age2 of 16 1A 1ST PUCK Used %0 1 6.61 E+00 1 2.70E+02 o 3.42E+00 0 0 0 0 6.546+00 0 3.106+00 0 0 6.736+00 2.97E+02'2 Inch/tiC001OUIFL1C3L0506-02 2CND PUCK 12 INCH DEPTH Rsults MDA Used %D 0 2.23% ND 0 ND~'NO 91.10% NO 0 ND 1.15% ND 0 ND 0 ND 0 1.486+00 4.98E-01 1.486E+00 2.21% ND 0 1.04% 1.52E+00 2.34E-01 1.52E+00 6.57E+00 3.89E+00 5.57E+00 ND ND INO 2.27% ND ND 100.00% 8.58E+00 C90001O01HIFLC1L0506.02A 2CND PUCK 1.NCH DEPTH ,ResulIs MDA Used %ND 0[NO 0~ NO ND 2.58E-01 1.36E-01 2.58E-01 ND D. 0 3.29E-01 1.64E-01 3.29E-01 6.33E-01 4.58E-01 .6.33E601 17.26% 1.26E+00 4.76E-01 1.26E+00 ND 0 17.77% 1.65E+00 4.49E601 1.65E+00 64.97% ND 0 ND ND ND 0 ND ND 100.00% 4.13E+OO I 6.23%7.96%15.31%30.55%39,96%100.00%112 Inch I Inch/z 1/2 INCH 1 1/2 INCH-K40*.wvcoZO wC$137' ' t>E154 T1-206-Pb-212""PtP-214 EN02-K 40 T14'05 wi2s~TI-2O6I wP0-212l 612.WN i0 0.5 0.5 0.p1h I 0,0 0.5 D.pFt without Csli37 with Cs.137 Attac4 k 4 AddenMS.m 2 Preliminary Analysis of Concrete Core "Puck" Samples by. the On-Site Laboratory CORE BORE #7, Reactor Building -15 ft. SE Area NC90001011HFL1C1L0507-01 15 TPUCK C9000101P11FC1L0507-01A 15TPUCK 0-tiNCH DEPTH 112-NCH DEPTH ResulIs MDA Used % 'ftesults MDA Used %K-40 138E+00 3.25E+00 1.38E+00 t1.09%,% 1.30E+01 2.13E+00 1.30E+01 Co- 60 5.02E-01 2.17E-01 5.02E-01 4.04% -3.83E-01 2.17E-01 3.83E401 Nb-94 ND mND Ag- 08m ND VND Cs-137 1.692E00 2.58E-01 1.69E+00 13.57%1 1.28E+00 2.06E-01 1.28E+00 Eu-152 ND ND Eu-154 ND D Tl-208 'ND ND Pb-212 ND 0 7.15SE-1 4.35E-01 7.152E-0 Pb-214 1.79E+00 4.03E-01 1.79E200 14.39% 1.50E+00 4.96E-01 1.50E+00 Ei-212 :X 5.35E+00 1.97E+00 5.35E+00 43.02% ND 0 8i 214 1.73E+00 4.87E-01 1.73E+00 13.90% 1.67E+00 5.162-01 1.672+00 Ra-226 ND 0 8.002+00 5.84E+00 8.00E+00 Ac 228 ND ND Th-234 NN U 235 ND ND Am 241 ND ND Cm-243 ND ND Cn-245 ND D 1.24E+01 100.00% 2.66E+01 (( age 3 of 16 IC9O001111FL1C1L0507-02 2CND PUCK"1t2. INCH DEPTH'fRtsulXt MDA Ued %49,03% ND 0 1.44% ND 0 ND ND 4,83% ND 0 ND ND ND 2.69% 4.37E-01 4.09E-01 4.37E-01 5.64% 1.60E+00 4.90E-01 1.60E+00 ND 0 6.27% 1.12E+00 3.47E-01 1.122+00 30.10% 6.03E+00 0 ND ND ND ND ND 100,00% 3.16E+00 1/2 Inch C900010111FUC1L0507-02A 2CND PUCK 1-WNCH DEPTH wResult MDA Used %0 ND 0 ND ND ND 0 ND ND ND 13.84% 5.282-01 4.38E-01 5.25E-01 50.72% 1.62E+00 4.792-01 1.62E+00 ND 0 O 35.44% i.28E+00 3.81E-01 1.28E+00 9.16E+00 4.41 E+00 9.16E+00 ND ND ND ND ND ND 100.00% 1.26E+01 I,/".4'19 4.19S 12.88%10.20%72.72%100.0 0 inch N11 .1,2 Inc Atakcl A Addendm 2 Preliminary Analysis of Concrete Core "Puck' Samples by the On-Site Laboratory CORE BORE#9, Containment .25 ft. Area 18*CS0001011FL1C3L0509-01 1STPUCK 0-INCH DEPTH Resulbt MDA Usad K-40 ND Co-60 ND Nb-94 NO Ag-1 OSm ND Cs 137 1.35E+00 2.34E-01 1.35E+00 Eu.152 ND Eu-154 NO Tl-208 ND Pb-212 5.40E-01 4.27E-01 5.40E4-1 Pb-214 1.53E+00 4.04E-01 1.53E+OC 61-212 NO C Bl-214 1.59E+00 3.98E-01 1.59E+OO Ra-226 8,78E+00 6.08E+00 S,78E+0O Ac 228 ND Th-234 ND U-235 ND Am-241 ND Cm-243 ND Cm-245 NO 1.38E+01 0 Irch\1 rC9000101"FL1C1L0509.OiA 1ST PUCK/1I2 INCH DEPTH% Rults I MDA Used ND NO NO D 9.81% 7.11E-01 2.34E-01 7.116-01 ND ND 1 3.91% 5.62E-01 4.40E-01 5.62E-01 11.07% 1.25E+00 5.50E6-1 1.25E+OC 4 4.4E00 1.94E+00 4.48E+OC 11.53% 1.34E+00 3.44E-01 1.34E+O(63.68% ND ND NO ND NO ND NC)I 100.00% 8.34E+OO C ' (C900010111FUC1L0509-02 2CND PUCK MC9000101I1FLIC1L0509-02A 2CND PUCK/2-lNCH DEPTH .-INCH DEPTH%tesults MDA Used % fRsulbt MDA Used %ND NO ND ND ND ND ND ND ND 8.52% ~ 1.406-01 0IMO~NO ~ND'ND m NO~ND ND 6.74% 5.58E-01 4.55E-01 5.58E-01 18.70% 6.56E-01 3.42E-01 6.56E-01 1495% 1.22E+00 3.51E-01 1.22E+00 40.80% 1.39E+00 4.03E-01 1.39E+00 53.72% NO 0 InND 0 16.07% 1.21E+00 4.01E-01 1.21E+00 40.50% 1.14E+00 3.22E401 1.14E+00 ONO 0 NO 0 ND D ND'NO N ND NC)'NO N~NO M ND ND ND 100.00% 2.98E+00 100.00% 3.19E+00 20.58%43.57%35.85%100,00%_.age 4 of I6 1/2 Ihch 1/2 Inch I Ich 1 1/2 INCH 10 I C-37_ ~Pb2t2 o'"Pb-214_ B1-212_ R226 0~5 0.D.p0. Attac( A AddenumIt 2 Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory CORE BORE #10, Waste Handling Building 15ft MCS000101UQ1PLC3t.0510-01 15TPUCK CS00010111FI C31.0510-01A 1STPUCK O-INCH DEPTH 112-.NCH DEPTH KResults MDA Used % sults MDA Used K-40 ND ND co-so ND ~ND Nb-94 NO ND Ag-1 Om ND D Cs-137 8.17E+03 3.85E+00 5.175+03 100.00% 4.37E+03 3.40E+00 4.37E+03 Eu-i 52 ND NO Eu-154 ND ND T-208 ND 0 ND 0 Pb-212 ND 0 ND 0 Pb-214 ND 0 ND 0 B1-212 ND ND E6-214 ND 0 ND 0 Ra-226 ND ND Ac-228 D. ND Th-234 ND ND U-235 ND ND Am-241 ND ND CM-243 ND ND Cm-245 ND ND 8.17E+03 100.00% 4.37E+03 (( Page 5 of 16 ,CS00010111FL1C1L0510.02 2CNDPUCK 1112-lNCH DEPTH%Reults MDA Used 1.20E+01 2.10E+00 1.20E+01 ND ND 10000% ~ 5.095-01 2A8E-01 5.095-01 ND ND 3.77E-01 1.26E-01 3.77E-01 5.12E-01 4.1 6E-01 5.12E-01 8.54E-01 5.05E-01 8.4E-01 ND 1.11 E+00 2.40E-01 1.11 E+00 ND ND ND ND ND ND 3 tO.00% 1.53E+01 C8000101iPLC1L0510.02A 2CND PUCK I-INCH DEPTH Reults MDA Used X 78.1 0% .11E01 2,10E+00 1.11E+01 ND ND ND 3.32% 3.21 E-01 1.39E-01 3.21 E-01 ND ND 2,46% ND 0 3.34% ND 0 5.57% ND 0 ND t ND 1.34E+00 2.40E-01 1.34E+00 NDD ND ND ND 100O.00% 1 .28E+01 87.04%2.51%10.45%100.00%0 kch 1/2 Inch 1/2 Inch 1 Inch I, ,1 1/2 INCH 1/2 INCH I IFI IPb314j.-E-214 with C5.137 without Cs.137 Attac( ( (agesot16 Adder( I ;Ca§ f Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory CORE BORE #11, Hot Laboratory 0 ft (0 Inch to 1 Inch),M C900010111FL1C1L0511-01 1ST PUCK csooo1o1nIFLICIL051 11-iA 15T PUCK C9oC00101FL1C1Lo01 1-02 2CND PUCK VC900I01HflL1C1L0511-02A 2CND PUCK OJINCH DEPTH 1/2.NCH DEPTH 112-NCH DEPTH 1.NCH DEPTH Rssuls MDA Used % ztults MDA Used .% .sutts MDA Used % Resulb MDA Used %K-40 6.34E+00 1.S7E+00 6.34E+00 0M8%' 7.61E.00 1.87E+00 7.61E+00 1.13% 9.76E+00 2.25E+00 9.76E+00 37.03 1.34E+01 2.25E+00 1.34E+01 49.33%Co-60 2.836*00 190E-01 2.UE+00 0.21%A 1.36E+00 1.90E-01 1.36E+00 0.20 NO 0 'ND 0 Nb-94 NND ND D ND Ag- lOm NND DND ND Cs-137 1.29E+03 1.46E+00 1.29E+03 97.3S% 6.59E+02 1,22E+00 6.59E+02 98.1 8% 1.39E+01 2.72E01 1.39E+01 5267% 1.18E+01 3.31E-01 1.1SE+01 4344%Eu-1 5 2 ND iND NDND ND Eu-154 " 4.71 E+00 3.67E+00 4.71 E+00 0.36% ND 0 DND 0 ND 0 T1-208 '%ND ND NO ND .ND Pb 212 M 2.79E+00 0 ND 0 D 0 9.33E-01 5.29E-01 9.33E-01 3.43%Pb-214 '. 3.69E+00 0 ND 0 1 45E+00 5.13E-01 1.45E+00 5.52% 1.03E+00 7.41E-01 1.03E+00 3.80%0 21*\I%~RND 0 61212 ND 0 ND 0 ND 0 B6-214 2.10E+00 0 ND 0 1.26E+00 4.12E.01 1.26E+00 4.78 % ND 0 Ra-226 ND ND ND NO Ac-22S `ND 0 ND 0 ND 0 ND 0 Th-234 ND NO NOD ND U-235 D ND ND ND Am241 N 2.00E+01 3.25E+oo 2.0SE+01 1.5S% 3.26E+00 2.04E+00 3.26E+00 0.49% ND 0 D 0 Cm-243 ND D 7ND CM-245 MND ND ' D ~ND 1.32E+03 100.00% 6.71E+02 100.00% 2.64E+01 100.00 2.72E+01 100.00%A with Cs-137 Attact( 4 Addend m 2 Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory CORE BORE #1 1, Hot Laboratory O t (1 Inch to 2 Inch).C900010111FL1C1L05111-03 3RO PUCK C9000101 FLICILO51103A 3RD PUCK.1.NCH DEPTH 112-INCH DEPTH'Results MDA Used % *Results iPDA Used %K-40 0 8.38E+00 2.1 3E+00 0.38E+00 Co-GO0 0 nk0 Nb-94 Ag-108m 08-137 3.22E+00 2.02E-01 3.22E+00 63.95% '-1 3.29E+00 1.41E-01 3.29E+00 Eu-i152 Eu-i 5 0 0 T1-208 Pb-212 O' 0 0 Pb-214 t.02E+00 5.60E-01 1.02E+00 20.32% 1.31E+00 4.58E-01 1.31E+00 B1-212 0 2.94E+00 1.97E+00 2.94E+00 61-214 7.92E-01 2.43E-01 7.92E-01 15.73% 7.48E-01 4.09E-01 7.48E-01 Ra-226 Ac-228 0 8.22E-01 6.06E-01 8.22E-01 Th-234 U-235 Arn-24i 0 0 Cm-243 Cm-245 5.03E+00 100.00% 1.75E+01 (7 C A09 7 of116 1 .52E+00 5.03E-01 I.1 E+0C UC1iO5111-04 4TH PUCK RC90OO101MFPLC1L0511-04A 4TH PUCK EPTH ~2.INCH DEPTH MDA Used % `Resulbt MDA Used 'A 0 0 0 0* 2.06E-01 1.52E+00 47.92% 1.27E+00 2.46E-01 1.27E+00 0 0 3.84E-01 5.03E-01 15 87%A 0 I 4.16E-0,i 1.155+00 36.21% 1.1SE+00 5.19E-01 1.15E+00 0 0 0 9.96E-01 3.17E-01 9.96E-01 0 0 0 0 3.17E+00 100.00% 3.41E+00 37.25%33.59%29.1 7%100.00%100.00%: 1 inch 1 1/2 Inch 1 1/2 inch 2 Ih' / r.25 Fco-GoI 1Eu-1541 IWPb.214)61 214 DEPTH without Cs-137 Attac4 4 Adden f. 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory CORE BORE #12, Hot Laboratory 0 ft C9000101HFL1C3105112.01 1STPUCK %C900010111FL1C1L0512-01A 1STPUCK 0.NCH DEPTH 12 INCH DEPTH MR1sult 1 MDA Used % RI ults MDA Used %K-40 1.31E+0l Z.62E00 1.31E.O0 4.16% 1.49E+01 3.83E+00 1.49AE01 Co-60 1.76E201 2.66E-01 1.762+01 5.57% 's 1 26E*01 2.66E-01 1.26E+01 Nb-94 ND 0 I .38E-1 1.85E.01 5.38E-01 Ag-108m D ND Cs 137 2.81E+02 9.32E-01 Z81E.02 89.02% 1.76E+02 9.92E-01 1.76E202 Eu-152 D ND Eu-154 ND ND TI-208 ND I ND Pb-212 ND 0 ND 0 Pb-214 ND 0 2.87E+00 2.26E+00 0 61-212 ND 0ND 81-214 ND 0 24E+00 1.24E+00 2.54E+00 Re-226 ND ,ND Ac-22a ND ND Th-234 ND ND U-235 ND ND Am-241 3.92E+00 1.732+00 3.92E+00 1.24% 2.112E00 1.53E+00 2.11E+00 Cm-243 ND NO Cm-245 ND ND 3.1 62E02 100.00% 2.09E+02 C ( age8 of 16 C9000110111FLICIL(51202 2CND PUCK/112-INCH DEPTH Results MDA Used %7.13%0 1.00E+01 2.11E+00 1.002E01 6.02% 2.15E-01 0 0.26%M 1.49E-01 0 ND 84.37% 284E-01 1.40E-01 2.84E-01 ND ND ND 5.61 E-01 3.46E-01 5.61 E201 t.38E+00 5.84E-01 1.38E200 ND 1.21% .1.71E+00 4.24E-01 1.71E+00 ND ND ND ND 1.01 ND 100.00% 1.40E+01 C9000101HIFLIC10512-02A 2CND PUCK 1 -INCH DEPTH Results MDA Used %71.84% 9.16E+00 2.11 E+00 9.16E+00 ND 0 ND 0 ND 2.04% ND 0 ND ND NO 4:02% ND 0 9.88% 1.06E+00 4.13E-01 1.06E+00 ND 12.22% 1.37E+00 4.06E-01 1.37E+00 ND ND ND ND ND 0 ND ND 100.00%- 1.1 6E+01 79.06%9.13%11.81%100.00%I 0 hich 1/2 Inch I 1/2 inch I Inch I/./1,z IINCHI 1/2 INCH I I, U 20 18 16 14 12 -K40 E \ .Nb94 I1""Pb-212 6 .131-214 6 .Ar-241 4 0 00 0. 1 Depth Depth with Cs-I37 without Cs-137 Attachd Addendh., Preliminary Analysis of Concrete Core 'Puck" Samples by the On-Site Laboratory CORE BORE #13, Hot Laboratory 0 ft (0 Inch to 1 Inch)C0900010111PFLIC3L0513-01 1STPUCK *C300010111FULC1L0513-01A 1STPUCK-0NCH DEPTH 112 INCH DEPTH Resulb MOA tZsed % bIts MDA Used %K-40 § 1.87E601 2.70E+00 1.87E+01 0.54% 1.28E+01 2.70E000 1.28E+01 Co 60 1.28E+00 2.75E.01 1.286E+00 0.04% 8.12E-01 2.75E-01 8.12E-01 Nb-94 ND 0 MND 0 Ag-1 00m ND I ND Cs 137 3.41 E+03 2.92E+00 3.41E+03 99.17% 2.40E+03 2.77E+00 2.40E+03 Eu-i 52 ND .NO Eu-154 ND NO TI-208 ND 0 ND 0 Pb-212 ND 0 ND 0 Pb-214 ND 0 ND 0 BI-212 ND ND B1-214 ND 0 ND 0 Ra.226 ND 0 ND 0 Ac 22S ND ND Th 234 ND ND U-235 ND ND Am-241 8.58E600 4.49E+00 8.58E000 0.25% ND

• 0 Cm-243 ND ND Cm-245 ND ND 3.44E+03 100.00% 2.42E+03 IC C age 9of 1e%IC9000101HIFLC1L0513-02 2CND PUCK 1I2 NCH DEPTH Results MDA Used %0.53% 9.42E+00 2.24E600 9.42E+00 0.03% ND 0 2.37E-01 1.58E-01 2.37E001 99.44% 1.75E+00 1.48E-01 1.75E+00 ND ND ND 0 ND 0 1.56E+00 6.00E-01 1.56E600 ND 1.78E+00 4.04E-01 1.78E+00 ND 0 ND~NO ND NO 0 ND ND 100.00% 1 .4SE+01 0C900010111FL1C1L0513-02A 2CNDPUCK.N-ICH DEPTH Resulb MDA Used %63.89% 7.90E+00 2.24E+00 7.90E+00 ND 0 1.61% ND 0 ND 11.87% 1.09E+00 1.48E-01 1.09E+00 ND ND ND 0 7.00E-01 4.55E-01 7,00E-01 10.55% 1.16E+00 6.05E-01 1.16E000 ND 12.08% 1.600+00 2.56E-01 1.60E000 ND 0 ND ND~ND 0 ND ND 0 100.00% 1.241+01 , ich 63.50%8.73%5.63%9.31%12.83%100.00%0 Inch 1/2 rich//1/2 Inch 1/2 INCH with Cs-137 Attaclh A Addentd n 2 Preliminary Analysis of Concrete Core "Puck' Samples by the On-Site Laboratory CORE BORE #13, Hot Laboratory 0 ft (1 Inch to 2 Inch)§i CSo000101HnFL1 C3L051J-03 3RO PUCK CS0001o1nIFLIC1L.0513-03,$ 1-;NCH DEPTH 1 tIZ tNCH DEPTH 1\lResults MDA Used %¶ Results MDA K-40 1.33E+01 2.1E+00 1.33E+01 78A3% 1332+01 2.1SE+Ot Co-60 ."iik0 Nb-94 O Ag-108m Cs-137 i 6.01E01 2.20E-01 6.01E-01 3,54% 5.39E-01 1.97E20'Eu-152 .z Eu-1 54 .TF-208 0 4,18E-01 1.79E-0 Pb 212 6.152-01 4.66E-01 6.15-E01 3.62% 8.76E-01 3.9-0 Pb-2142 1.342+00 4.85E-01 1.34E+00 7.91% 9.57E-01 4.27E-0 B2-212 ~§.Bl-214 1.10E+00 4.55E-01 1.1000 6.50%0 Ra-226 0 75 7E+00 4.30E+O0 AC-228 Th-234 U-235 Ani241 O :g Cm-243 n Cm-245 1.70E+01 10.00%r C .go 10 of 16 3A 3F Use 0 2 inch RD PUCK 9C3OOO1011PL1C1LO513-04 4TH PUCK C00101IFILIC110513-04A 4TH PUCK i 11/2-INCH DEPTH z.NCH DEPTH d % Results MDA Used ¶ Results MDA Used %1.33E+01 60.81% 1.17E+01 2.11E+00 1.17E+01 73.60% 9.162+00 2.11E+00 9.162+0 74.59%00 0 m 5.39E-01 2.46% 7.212-01 1.40E-01 7.21E-01 4.52% 0 4.18E-01 1.91%; 0 0 8.76E-01 4.00% 6.91 E-01 4.76E-01 6.91 E-01 4.33% 5.92E-01 3.27E-01 5.92E-01 4.82%9.67E-01 4.42% j 9.57-01 5.26E-01 9.s57E-1 600%A 1.492+00 4.44£-01 1.49E200 12.17%0 1.84E+00 0.4177 1.4E2+00 11.55% 1.04E+00 3.212-01 1.04E200 8.43%p 5.78E+00 26.40% 0 0 2 0 1 0 0 1 0 2.1 92+01 1 00.00% '¶1.602+01 100.00% 1,202.01 100.00% hl..I 1 1/2 Infh 2, Inch 1/2 INCH 1/2 INCH without Cs-137 Attachf Addendum 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory CORE BORE #14, Hot Laboratory 0 ft lCS0001011F1F.C3L0514-01 1STPUCK C90001I01HIFILIC1L0514-01A 1STPUCK O-INCH DEPTH 1/21NCH DEPTH~ Results MDA Used X lResults MDA Used %K-40 1.77E+01 2.29E+00 1.77E501 0.82% Jl 7.58E+00 0 Co-60 7495+00 Z325-01 7.49E00 0.35% 4.735E00 2.32E-01 4.73E+00 Nb-94 8.98E-01 5.26E-01 8.98E-01 0.04% 8.635-01 3.77E-01 8.63E-01 Ag9 OSm ND gND Cs.137 214E503 2.01E+00 2.14E+03 98.80% 1265+03 1.94E+W 1.26E+03 Eu-152 ND .ND Eu-164 ND N Ti-208 ND NO Pb-212 ND 0 ND 0 Pb.214 ND 0 ND 0 B1-212 ND ND Bi-214 ND 0 ND 0 Ra-226 ND 0 NO 0 Ac-228 ND NO Th-234 ND ND U-235 N D ND Arn-241 ND ND Cm-243 D D Cm-245 D ND 2.17E+03 100.00% 1.265+03 C ( eli of16 C900010111FL1C1L0514-02 2CND PUCK hM 1/2-INCH DEPTH Results MDA Used %1.54E*01 2.1SE+00 1.54E+01 0.37% 2.23E-01 0 0.07% 1.89E-01 0 kZND 99.56% 1 .825-01 0 ND ND ND 4.995-01 3.44E.01 4.99E-01 1.39E+00 3.34E-01 1.39E+00 ND 1.68E+00 3.49E-01 1.68E+00 6.22E+00 4.76E+00 6.22E+00 ND ND ND ND ND 1 ND 100.00% 2.62E+01 C*0001101ILIC1L05114-02A 2CND PUCK IINCH DEPTH sulb MDA Used %61.13% 9.77E+00 +/-185+00 9.77E+00 2.98E-01 2.22E-01 2.98E-01 1.54E-01 0 D NO 1A44E-01 0 ND ND ND 1.98% 3.72E-01 0 5.51% 1.11 5+00 6.14E-01 .11 E+00 ND 6.66% 1.47E+00 6.14E-01 1.47E+00 24.71% 6.19E+00 0 ND ND ND ND ND 100.00% 1 .26E+01 kincch 77.26%2.36%8.78%11.60%100.00%0 inch 1/2 Inch I 1/2 Incsh 1/2 INCH 1 1/2INCH withl Cs.137 without Cs-137 Attact 4 Addenbi..

2 Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Sit. Laboratory CORE BORE #15, Hot Laboratory O ft (O Inch to 1 inch)~:C900010111FULC1L0515.01 1STPUCK C900010111FLC110515.01A 15TPUCK A.0-6NCH DEPTH , /2-NCHKDEPTH Resulb MOA Used % *sulb MOA Used %K-40 1.29E+01 2.50E+00 1.29E+01 0.13%; ~ 1.76E601 2.49E+00 1.76E+01 Co-060 7.20E.01 5.02E-01 7.20E+01 0.72% 536E+01 2.53E-01 5.36E+01 Nb-94 ND 0 1.10E+00 8.53E-01 1.10E+oo Ag-1 0 Nm D D Cs 137 9.87WE+03 99.05% 7.79E+03 4.90E+00 7.79E+03 Eu-152 ND D Eu-154 ND D TI-208 DN 0 ND 0 Pb-212 ND 0 ND 0 Pb-214 ND 0 ND 0 B1-212 ND ND Bi-214 ND 0 ND 0 Ra-226 ND ND Ac-228 ND ND Th-234 D ND U-235 ND NO AM-241 9.63E+00 6.17E+00 9.63E+00 0.10% 7.106+00 6.51E+00 7.1 06+00 Cm-243 ND ND Cm-245 ND ND 9.96E+03 100.00% 7.87e603 C1 ( je12 of 16.C900010i1tFL1C1L0515-02 2CNDPUCK 112U4NCH DEPTH Results MDA Used %0.22% 1.406+01 2.10E+00 1.40E+01 0 68% a8 69-E01 2.13E-01 8.69E-01 0.01 % ND 0 98.99f 1.40E+01 4.53E-01 1.40E+01 ND ND ND 0 1 39E+00 6.27E-01 1,39E+00 ND ND 0 ND ND ND 0.09% ND 0 ND ND 100.00% 3.03E+01 MC900010111PL1C1L051b02A 2CND PUCK 1-NCH DEPTH*ItsuIIS MDA Used %46.13% 1.33E+01 2.10E+00 1.33E+01 2.87% 8.84E-01 2.13E-01 8.84E.01.ND 0 ND 46.41% 8.28E+00 2.94E-01 8.28E+00 ND ND ND 0 ND, 0 4.59% 1.24E+00 7.66E01 1.24E+00 ND 1.06E+00 6.656-01 1.06E+00 ND ND ND ND.ND 0 ND ND 100.00% 2.48E+01 53.78%3.57%33.40%4.99%4.26%100.00%.1/2kich with Cs 137 Attac -.Addenf...1 2 Preliminary Analysis of Concrete Core TPuck' Samples by the On-Site Laboratory CORE BORE #15, Hot Laboratory.0 ft (1 Inch to 2 Inch)*C900O10i1iPL1C1L0515-03 3RD PUCK CS000101 nPFUC1L0515-Ol V1-NCH DEPTH 1 112.NCH DEPTH 0ZResuIto MDA Used % sResulbs MDA K-40 9.23E+00 1.79E+00 9.23E+00 79.00% ND 0o60 ND 0 ND Nb-94 -ND 0 ND Ags-108m ND IND Cs-137 3.22E-01 1.18E-1 3.22E-01 Z75%A 6.31E 01 1.18E-0 Eu-152 'LND ND Eu 154 ND D TI 208 ND 0 Z53E-1 1.70E4-Pb-212 ND 0 D Pb-214 1.24E+00 4.83E-01 1.24E+00 10.61% 1.25E+00 3.18-E4 B212 ND ND El 214 8.92E41 2.93E41 8.92E41 7.63% 4,11E41 2.04E1 Re-226 ND ND Act228 ND ND Th-234 ND D U-235 ND Amr-241 ND 0 NO Cr-243 ND ND Cm-245 ND ND 1.17E+01 100.00%C C7 ~ge 13 of II A 3RD PUCK C900010111FL1C1L0515-04 4TH I 1121INCH DEPTH Used % ~ Results MDA Use 0 ..~ 1.15E+00 2.36E+00 0 NO 0 ND ND'1 5.31E-01 21.71% 5.95E-1 1.56E-1 ND ND 41 2.532-01 10.35% ND 0 7.17E-01 5.33E-01 41 1.25E+00 51.11% 1.19E+00 6.04E-01 ND 41 4.11E-01 16.83% 1.72E+00 2.70E-01 ND ND ND ND 0 D ND 2D 2.44E+00 100.00%PUCK tCS000101iIFL1C1L0515-04A 4TH PUCK 1 2-INCH DEPTH d % *Resulb MDA Used %1.15E+00 21.46%i 1.15E+00 2.36E+00 1.15E+00 21.46%0 BND 0 0 MND 0 ND 5.95E-01 11.05 5.9E-01 1.56E-01 5.95E1 11.05%MND IND 0 ND 0 7.17E-01 13.32% 7.17E 01 S.33E-01 7.17E201 13.32%1.19E+00 22.1B 1.19E+00 6.042-01 1.19E+00 22.18%ND 1.72E+00 31.98% 1.72E+00 2.70E-01 1.72E+00 31.98%ND N D ND ND 0 ND 0 ND 5.38E+00 100.00% 5.38E+00 100.00%without Cs-137 Attach4§ 4 Addendum 2 Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory CORE BORE #16, Hot Pipe Tunnel, 412 t C90001OIrLIC1Lo.516-O1 1STPUCK NC9O00101nFuLC1L051 6.01 O-NCH DEPTH M112-NCH DEPTH%Results MDA Used % 1Rteults MfDA K-40 1.32E-01 1.95E+00 1.32E+01 2.15% 4 9.26E+00 1.95E+C Co-60 2.10E+01 1.98E-01 2.10E+01 3.41% 1.28E+01 1.98E-O Nb-94 ND NO Ag-1 08m ND ND Cs 137 5.82E+02 1.39E.00 5.82E+02 94.45% 3.53E+02 8.79E-C Eu-152 ND ND Eu-154 ND ND Tl-208 ND ND Pb-212 *ND 0 D Pb-214 kND 0 ND Bl-212 ND NO El 214 ND 0 2.57E+00 1.35E+O Re-226 D ND Ac-228 ND ND Th-234 ND ND U 235 ND ND Am-241 ND .ND Crm-243 ND ND Crm-245 ND N D 6.16E+02 100.00%C ( je 14 of I A 1ST PUCK RC9000101I1FPLC1L0516402 2CND PUCK/112-NCH DEPTH Used % ults MDA Used 0 9.26E*00 2.46% 8.84E+00 2.10E+00 8.84E+00 41 1.28E+01 3.39% 2.14E-01 0 ND 01 3.53E+02 93.47% 6.17E-01 2.54E-01 6.17E-01 ND~NO~NO 0 6.82E-01 4.07E-01 6,82-01 0 8.59E-01 5.50E-01 8.59E-01 END 00 2.57E+00 0.68% 1.60E+00 2.40E-01 1.60E+00 ND ND ND ND ND ND ND 3.772+02 100.O0%~ 1.26E+01"C90001011PL1C1L0516-02A 2CND PUCK I-INCH DEPTH% .Reults MDA Used %70.20%1 1,17EE01 2.10E+00 1.17E+01 2.14E-01 0 M D 4.89% 8.12E-01 2.27E-01 8.12E-01 ND ND ND 5.42% 5.55E-01 0 6.82%A 1.37E+00 5.43E-01 1.37E+00 ND 12.67% 1.17E+00 3.58E-01 1.17E+00 ND ND 1D ND ND.ND ND 1 100.00%. 1.50E+01 77.73%5.39%9.12%7.76%100.00%wlth Cs-`1Jr without Cs-137 AttaciC 4 Addendtm 2 Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory CORE BORE #17, Fan House, -12 ft.OIC90001011FL1CL0517-01 1STPUCK C9000101NFL1C1L0517-01A 1STPUCK 0lo-NCH DEPTH 1/2-NCH DEPTH§ Result MDA Used % *Rsults MDA Used %K-40 1.70E+01 2.46E+00 1.70E+01 65.69%*M 1.UE4+01 2.46E+00 1.54E+01 Co060 ND ND Nb-s4 ND ND Ag91 osm ND NO Cs-137 9.95E-01 1.63E-01 9.95E-01 3.83% t. 885E-01 1.63E-01 8.85E-01 Eu-152 ND ND Eu-1 54 ND ND T11208 ND ND Pb-212 6.68E-01 5.552-01 6.68E-01 2.58% 8.81 E-01 4.85E-01 8.81 E-01 Pbt214 1.87E+00 7.01E-01 1.87E+00 7.21% 1 792E00 6.30E-01 1.79E+00 BN212 3.71E+00 2.28E+00 3,71Eo00 14.29% ND 0 B1214 1.66E+00 6.272-01 1.66E+00 6.40% 1.76E+00 2.81E-01 1.76E+00 Ra-226 ND 0 e~ND .O0 Ac-228 ND 0 ND 0 Th-234 ND 0 ND 0 U-235 ND ND Am-241 ND N Cm-243 D ND Cm-245 ND ND 2.60E+01 100.00% 2.07E+01 0 ich 112 IWch C Z oC800011HP1L1C1L.517-02 2CND PUCK" 12-INCH DEPTH'Results MDA Used %74 32% 1.390+01 2.27E+00 1.39E+01 ND ND 1 .9OE-01 4.28% 4.4SED01 1,50E-01 4.4SE-01 ND ND 4.26% 6.62E-01 5.11 E-01 6.52E-01 8.65% 1.34E+00 5.27E501 1.34E+00 ND 0 8.49% 9.61 S-01 4.09E-01 9.61 E-01 5.65E+00 5.38E500 6.65E+00 1.12E+00 645E-01 1.12E+0o 6.08s+00 6.00E+00 6.08E+00 ND ND ND ND 100.00% 3.01 E+01 l.ge 15 of 16 ct8 1011FLCC1L.016-02A 2CND PUCK s1-N1CH DEPTH Results tDA Used 'A 46,03% 1.57E+01 2.27E+00 1.57E+01 89.44%A4 ND~~ND 1.49% 3.68E-01 0 ND ND 2.17 7.25E-01 6.56E-01 7.255E-1 4.13%4.46% 9.64E-01 4.77E-01 9.64E501 5.49%ND 0 3.1 1.652-01 2.59E-01 1.65E-01 0.94%1 8S77% ND 0 3.70 NO o 20.20% ND 0 NO ND ND ND 100.00% 1.76E+01 100.00%1/2 Inch I hich/.1/2 INCH 1 1/2INCH I-K04 10 14 13-c31i4 s 2 ...rm.FR-2 1 2 SO.1. 4.2121.Ei' 614 5 _ Th22l4= ~0 0.5 0.0 1 D-P.,-_ ft. Attac( A Addenbu 2 Preliminary Analysis of Concrete Core "Puck' Samples by the On-Site Laboratory CORE BORE #21, ROLB Fuel Vault C C ge 16 of 16 K-40 Co-60 Nb-94 Ag-t 03rn Cs-1 37 Eu-I 52 Eu-I 54 TI-208 Pb-212 Pb-214 BI-21 2 BW-214 Ra-226 Ac-228 Th-234 U-235 AM-241 CM-243 Cn-246%C900010111FL1C1L0521-01 1STPUCK C900010111FLICL0521.01A 1STPUCK O.N-ICH DEPTH /12-NCH DEPTH ,Rosults MDA Used % ,Resutts MDA Used M 1.50E+01 2.21 E+00 1.50E+01 84.76% I 59E+01 2.21 E+00 1.59E+01 ND I ND ND ND , ND 0 2.38E-01 1.46E-01 2.38E-01 ND ND%'ND NO ND 0 349E-01 2.66E-01 3.49E-01 ND 0 6.53E-01 5.68E-01 6.53E-01 1.39E+00 6.69E-01 1.39E+00 7.85% 1f.06E+00 4.75E-01 1.06E+0O ND ND 1.31E+00 4.05E-01 1.31E+00 7.39X 1.35E+00 5,85E-01 1.35E+00 ND ND ND ND ND NO ND ND ND ND ND ND ND ND 1.77E+01 100.00% 1.95E+01 0Oc 1/2 lrch'.C900010111FL1C1L0521-02 2CND PUCK M 112-tNCH DEPTH R sults MDA Used 81.31%- 1,33E+01 2.08E+00 1.33E+01 ND ND ND 1.22%A ND 0 ND ND 1,78% ND 0 3,34% 5.26E-01 4.71 E-01 5.26E-01 5.43% 1.024E00 5.06E-01 1.02E+00 ND 6.92% 8.70E-01 4.55E-01 8.70E-01 ND ND ND 1 D ND ND 1 100.00% 1.57E+01 C900010111FL1C1L0521-02A 2CNDPUCK k,, -NCH DEPTH lRosult MDA Used %84.59% k 9.65E+00 2.98E+00 9.65E+00 87,04%DND N D IN 3.05E-01 1.93E-01 3.05E-01 2.75%ND~ND 3.35% ND 0 6.51 X ND 0' ND 5.55% 1.13E+00 3.62E-01 1.13E+00 10.21l%ND ND NNDD 1. ND 100.00%~ 1.112+01 100.00%A 1/2 Inch Ilkich'I/../ Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &Final Status Survey of the Plum Brook Reactor Facility (PBRF)Addendum 3 Results of Isotopic Analysis of Concrete Core Samples Attachment A, Page 1of` 3 Addendum 3 Results of Isotopic Analysis of Concrete Core Samplias gRxBldg.25ft,Area22 S:;CTMT-25 n, CanalE IRxldg-1 ,ft SEArea Core Location 15 *ZCore Location 6 Core Location 37 j C900101 IFLICI O505-01 .fC90001011FL1C3L0506-01 MC90O01O1IFLUC1 L0507-01 Result MDC Used Disributlon Result MDC Used Disributlon Result MDC Used Disribuilon p CClgm PCUgm PCl/gm Y pCligm rjCllgm qCl/gm Y. , Clgm pCI/gm pCI/gm

• x H-3 -4.90+00 5.20E+00 6.20E+00 260% 6 40E+00 5.10E+00 6.40E+00 4.07% 3.00E+00 5.20E+00 6.20E+00 15.33%Cs-137 286E+00 1.70E-1 Z8E+00 1A3% > .17E+02 ZOOE-01 1.17E+02 74.32% 7.20E01 1.10E-01 7.20E-01 212%Co-60 1.13E+01 1.00E-01 1.13E+01 5.65% 2.21E+00 1.20E-01 221E+00 1.40% 1.40E-01 2.40E-01 2.40E1 0.71%Fe-55 1.70E+01 6.70E+01 6.70E+01 33.48% 1.80E+00 1.20E+01 1.20E+01 7.62% 4.40E401 1.30E+01 1.30E+01 38.33%Ni-63 ,ii 1.07E+02 Z70E+01 1.07E+02 53.47% 1.19E+01 1.30E+01 1.30E+01 8.26% 8.30E+00 9.80E+00 9.80E+00 28.89%Sr-9O 2.07E+00 6.40E-01 2.07E+00 1.03% 4.60E-01 4.40E-01 4.60E401 0.29% 4 00E-02 5.70-E1 5.70E-01 1.68%Pu-23S 4.10E2-02 6.90E-02 6.90E-02 0.03% 8.50E-02 Z90E-02 8.50E-02 0.05% 600E-03 5.302-02 5.30E-02 0.16%Pu-239/240 2.70E-02 5.40E-02 5.40E-02 0.03% 1.90E202 4.70E-02 4.70E-02 0.03% 1.00E-02 2.80E202 2.80E-02 0.08%Pu-E241 6.002-01 Z60E+00 2.60E+00 1.30% 1.20E+00 Z80E+00 2.80E+00 1.78% -2.00E1 Z502+00 2.60E+00 7.37%Am-241 6.00E-02 Z1QE4-1 Z10E-01 0.10% 1.67E+00 3.00E-01 1.67E+00 1.06% 0002+00 1.002-1 1.00E-01 0.29%Crn-2451246 5.00E-02 3.90E401 3.90E-01 0.19% 1.60E-02 8.70E-02 8.702-02 0.06% 1.002.01 1.30E-01 1.302-01 0.38%U-234 6.40E-01 9.00E-02 6.40E401 0.32% 7 50E-01 3.00E-02 7.50E-01 0.48% 7.202-1 4.00E-2 7.20E-1 2.12% f U-235 1.10E-01 7.70E-02 1.102E1 0.05% .130E202 3.40E-02 3AOE-02 0.02% 2.90E-02 7.70E-02 7.70E-02 0.23%U-238 .. 6.20E-01 4.00E-02 6.20E01 0.31% 8.80E-01 3.00E22 8.80E-01 0.56% 7.80E.01 6.00E-02 7.80E-01 2.30%zOOE+02 100% 1.57E+02 100% 3.39E+01 100%,..CTMT -25 ft, Area 18 .Waste Handling Bldg -15 ft Hot Pipe Tunnel,-12ft

.Core Location #9 ,Core Locatlon #10 Core Location 415 xg C90001 1IFLI C310509-01 C9000.. 1IFU C3L050741

.. C9.000oIFUC1i055-01. i:K: Result MDC Used Dlsributlon Result MDC Used Dlsributlon ... Result MDC Used DWsribution <.*,'i pCI/gm pCVpgm PCmqm p PC[/gm PCI/m PCIgm % opCUIgm pCIgm pC/gm' ¶ f H-3 1.11E+01 5.10E+00 1.11E+01 28.99% 2. 70E+00 5.30E+00 5.30E+00 0.17% 1.60E+00 5.302+00 5302+00 0.09%Cs-137 -6.10E-1 8.002-2 6.102-1 1 59% 3.15+03 8.00E-01 3.15E+03 98.90% : 4-43E+03 1.00E+00 4.43E+03 76.87%Co-so .2.32201 Z10E-1 2.32E201 0.61% -3.30E-02 1.10E-01 1.10E-01 0.00% .Z69E+01 3,002E01 2.69E+01 0.47%Fe-55 3.10E+00 1.30E+01 1.30E+01 33.96% 3.30E+00 1.40E+01 1.A0E+01 0.44% 1.90E+01 1.70E+01 1.90E+01 0.33% K:s NI-63 -4.10E+00 1.102+01 1.10E+01 2873% -1.00E+00 1.00E+01 1.00E+01 0.31% 1.61E+02 2.00E+01 1.61E+02 2.79%Sr-40 4.00E-0 4.51 4. 4.60E-01 1.18% 1.20E+00 4.80E-02 1.20E+00 0.04% x,.. 1.01E+03 1.00E+00 1.01E+03 17.52%Pu-238 O.OOE+OO O.0OE+00 O.OOE+00 0.00% 1,90E-02 4.80E-02 4.80E-02 0.00% 6.59E+00 5.00E-02 6.59E+00 0.11%Pu-239/240 O.OOE+OO 6.00E-02 6.00E-02 0.16% 1.0-02 3.00E-02 3.00E-02 0.00% 7.58E+00 3.00E-02 7.58E+00 0.13%Pu-241 -ZOOE-2 3.002-2 30 0-0E 2 008% -5.002-1 2.90E+00 2.90E+00 0.09% 7.47E+01 2.70E+00 7.47E+01 1.30%Am-241 0.OOE+00 2.00E-01 2.00E2-1 0.52% 6.00E203 1.00E-01 1.00E-01 0.00% 1.30E+01 3.00E-01 1.30E+01 0.23%Cm-245/246 1.554-01 9.40E-02 1.55E-01 040% 4.40E-02 8.70E-02 8.70E-02 0.00% 6.95E+00 1.60E-01 6.95E+oo 0.12%U-234 7.00E41 4.00E42 7.002-1 1.83% .502-1 8.00E42 5.OE0-01 0.02% 1.28E+00 7.00E-02 1.28E+00 0.02%U-235 1.7020 4.70E-2 4.70E-2 0.12% 530E-2 4.80E-02 5.30E-02 0.00% 9.00E-02 9.102-02 9.102-02 0.00% i U-238 .. 7.00201 4.00E-02 7.00E401 1.83% 5 .OOE-01 4.00E-02 5.OOE-01 0.02% 9.10E201 7.002-02 9.102-01 0.02%3.83E+01 100% 3.182+03 100% 5.76E+03 100%Hot PipTunnel,4-12 It K'Fan House .12 ft:::::Core Location #16 Core Location #17 BALANCE OF PLANT CORE RESULTS ,-sC9000101IFLICI L051O641 B-C9000101IFLICILD517.Oi Result MDC Used Disribuflon Result MDC Used Disribution MEAN MEAN STD DEV pCIgm PCI/gm PCV/gm % pCi/gm pCmgm PCIm % (pC[/gm) (-/4 H-4 2.10E+00 5.20E+00 5.20E+00 0.44% 6.20E+00 5.30+00 6.202+00 15.99% 1H-3 6.24E+00 8.46% 10.57%Cs-137 2.60E+02 4.00E-01 2.60E+02 22.04% 4.10E-01 9.00E-02 4.10E-01 1.06% Cs-137 9.95E+02 34.79% 41.45%Co-40 8.97E+00 240E201 8.97E+oo 0.76% -2.70E202 1.10E-01 1.10-E01 0.28% Co-60 6.26E+00 1.23% 1.83%Fe-SS 8.202+00 1.40E+01 IAOE+01 1-19% -2.40E+00 1.40E+01 1.AOE+01 36.11% Fe-SB 208E+01 18.93% 17.89%Ni-63 5.00E+01 Z50E+01 5.00E+01 4.24% .4.00E+00 1.202+01 1.20E+01 30.95% 1Ni-63 4.67E+01 19.71% 18.76%Sr-go 8.36E+02 2OOE+00 8.36E+02 70.87% O.OE+OO 5.00E-01 .OOE-01 1.29% Sr-Do 2.31E+02 11.74% 24.60%Pu-238 1.70-E02 5.60E-1 5.80E41 005% 6.00E-03 5.90E-02 5.90E-02 0.15% Pu-238 9.33E-01 0.07% 0.06%Pu-2391240 7.30E-02 5.80E-02 7.30E202 0.01% 1 102-02 3.10E-02 3.10E-02 0.08% Pu-239/240 9.88E-01 0.06% 0.06%Pu-241 1.902+00 270E+00 2.70E+00 0.23% .. 9.00E-01 3.00E+00 3.00E+00 7.74% Pu-241 1.14E+Ot 249% 3.19%Am-241 4.60E-02 6.70E-02 6.70E-02 0.01% ',,-9.00E-03 5.30E-02 5.30E-02 0.14% Am-241 1.932+00 0.29% 0.35%Cni-245/246 0.OOE+OO 1.00-E01 1.00E-01 0,01% 1.202-01 1.40E-01 1AOE4-01 0.36% CCm-245/246 1.00E+00 0.19% 0.17%U-234 9.102-01 6.00E-02 9.10E-01 0.08% 1.14E+00 4.004-02 1.14E+00 2.94% U-234 8.36E-01 0.98% 1.15%U-235 a 6.50E-02 9.30E-02 9.30E-02 001% 5.80E-02 ,10E-01 1.10E-01 0.28% 0U235 7.69E-02 0.09% 0.11%U-238, a 9.10E-01 6.00-E02 9.102-01 0.08% 1.02E+00 4.00E-02 1.02E+00 Z63%

• U-238 7.90E-01 0.97% 1.10%1.18E+03 100% 3.88E+01 100% 100.00%

Attachment A, Addendum 3 Results of Isotopic Analysis of Concrete Core Samples Page 2 of 3 Hot Laboratory Oft Core Location 11 C9000iO1iFLI CI LOSt 1-0 Result MDC PCVmrn PCVgm H-3 0 -gOOE-02 5.20E+00 C-14 -5.30E-01 8.80-E41 Cs-137 KK 9.45E+02 5.002-01 Co-O 1.82E+00 1.70E-41 Ni-63 2.50E+01 5.20E+01 Sr-0 .1.18E+01 5.00E-1 Pu-238 3.90E-1 5.00E-02 Pu-2391240 2.05E-01 290E-02 Pu-241 2.20E+00 2.90E+00 An-241 K. 9.90E+00 9.00-E01 Cm-2451246 1.90E-01 8.00E-02 U-234 3.60E-01 6.00E-02 U-235 9.00-03 8.90E-02 U-238 4A.4-01 6.002-02*";is Hot Laboratory O ft i Core Location 312 i1 >f:BC9000101 IFLIC L0512-01 Used Disribution 1 Result MDC pCltgm rn PClI/m iCI/om 5.20E+00 0.50% 600E-01 5.20E+00 8.80E401 009% Z16E+01 1.30E+00 9.45E+02 91.64% 1.13E+02 3.002-01 1.82E+00 0.18% 5.79E+00 1.30E-01 5.20E+01 5.04% 1A2E+01 1.20E+01 1.18E+01 1.14% 1.08E+02 5.00E-01 3.90E-01 0.04% 4.80E-01 3.00E-02 2.052E-1 0.02% 6.39E+00 600E-02 2.90E+OO 028% 6.80E+00 3.10E+OO 9.90E+00 0.98% 1.40E+00 1.90E-01 1.902-01 0.02% 6.OOE-01 1.20E-1 3.60E-01 0.03% 1.04E+00 3.00E-02 8.90E-02 0.01% 2Z80E-02 3.80E-02 4.40E-01 0.04% 8.50E-01 5.00E-02 1.03E+03 100%iiHot Laboratory O ft Core Location S13 1 C90001OIFUL1C3i0513-01 Used Disributlon Result MDC PClgrm 4 o pClgm pCLQm 6.20E+00 1.82% 7.20E+00 5.40E+00 I Z16E+01 7.57% 4.10E41 1.20E+00 1 1.13E+02 39.60% N 1.71E+03 6.00E41 1 5.79E+00 2.03% 2 70E401 1.70E41 1.42E+01 4.98% lc-3.00+00 1.10E+01 1 1.08E+02 37.84% 193E+02 6.00E-01 1 4.80E-01 0.17% ' 6.50E241 9.00E-02 I 6.39E+00 2.24% 5. 00E-01 4.00E-02 6.80E+00 Z38% 4 70E+00 3.70E+00 4 1.40E+00 0.49% 2.90E+00 1.00E+00 6.004-01 0.21% 3.80E401 1.20E-01 1.04E+00 0.367 9 60E-01 4.00E42 -3.80E-2 0.01% .5.1-02 4.60E42 e 8.50E01 0.30% 8.20E-1 4.00E-02 i Z85E+02 100% 1 Used Disribution lpCiIrm 'A 7.20E+00 0.37%1.20E+00 0.06% ii;iK 1.71E+03 88.43%2.70E201 0.01%1.10E+01 0.57%1.93E+02 9.98%6.50E401 0.03%5.00E1 0. 03%4.70E+00 0.24%2.90E+00 0.15%3.80E-01 0.02%9.60E-01 0.05%5.10i-02 0.00%820E1 0.04% ...93E+03 100%Hot Laboratory 0 ft K<.:Core Location #14 C90001011FL1C3L0514-01 Result MDC Used Disribution .Cl/gm pC[/gm PCIIrm ¶4 H-3 1.70E+00 5.20E+00 5.20E+00 0.62% H-3 C-14 -6.002E1 1.30E+00 1.30E+00 0.16%

• C-14 Cs-137 7.75E+02 5.00E-01 7.75E+02 9248% Cs4137 CO-60 3.12E+00 1.20E-01 3.12E+00 0,37% Co-60 Ni-63 1.10E+00 1.502+01 1.50E+01 1.79% f N-63 Sr-90 3.30E+01 4.00E-01 3.30E+01 3,94% Sr-9O Pu-238 9.70E-02 4.90E-02 9.70E-02 001% Pu-238 Pu-239/240 5.90E-01 3.00E-02 5.90E.01 0.07% Pu-239/240 Pu-241 7,OO 700E-01 Z80E+00 Z80E+00 0.33% Pu-241 ArF-241 3.202E-1 3.004-02 3.20E-01 0.04% Al-241 Cm-245/246 1.07E-01 8.90E-02 1.07E-01 0,01% Cm-2451246 U-234 8.10E-01 7.00E-02 8.10E-01 0.10% U 234 U-235 :g 5.90E-02 7.40E-02 7.40E-02 0.01% U-235 U-238 6.40E241 6.00E-02 6,40E-01 0.08% U-238 8.38E+02 100%HOT LAB CORE RESULTS MEAN (pCl/gm)5.70E+OO 6.25E+00 8.86E+02 2Z75E+00 2.31E+01 8.65E+01 4.04E-01 1.92E+00 4.30E+00 3.S3E+00 3.19E2-1 7.93E401 6.30E-02 S.88E-01 MEAN STD DEV Nl 0.83% 0.67%1.97% 3.73%78.04% 25.69%0.65% 0.93%3.09% 227%13.23% 16.82%0.06% 0.07%0.59% 1.10%0.81% 1.05%0.41% 0.41%0.07% 0.10%0.14% 0.15%0.01% 0.00%0.11% 0.12%100.00%

Attachment A, Pago3of3 Addendum 3 Results of Isotopic Analysis of Concrete Core Samples ROLB Fuel Vault Core Location 121:!: C90001 OO IFLI C1 L0521 O1 Result MDC Use Dsribution pCUQgm pClgm pCt/gm 'A Cs-137 1.30E-02 1.00E-01 1.002-01 6.67%Co.60 4.702-02 1.30E-01 1.30E201 8.67%U-234 6.00E-01 6.OOE-02 6.002-01 40.00%U-238 6.70E-01 3.00E-02 6.70E-01 44.67%1.60E200 100% Final Status Survey Plan for the Plum Brook Reactor Facility Attachment A Radionuclide Distribution Basis for DCGL Determination &Final Status Survey of the Plum Brook Reactor Facility (PBRF)Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Attachment A, Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Page 1 of 2 AM-241 AM243 C-14 CM-245 CO-60 CS-137, EU-155 H-3 1-129 NB-94 NI-63 PU-238 PU-239 SR-90 U-236 AM-241 AM243 C-114 CM-245 CO-60 CS-137 EU-155 H4-3 l1429 NB-94' ) NI-63 PU-238 PU-239 SR-90 U-236 AM-241 AM243 C-14 CM-245 CO-60 CS-137 EU-165 H4-3 1-129 NB-94 Nl-63 PU.238 PU-239 SR-90 U-236 Sample CS013004-004 Spill Area 2400303C1 Surface Soils (1st 6")(pCI/gm)Result MDA Used 1.822E-02 4.936E-02 4.94E-02 1.347E-01 1.567E-01 1.57E-01 1.377E+0o 1.401E+00 1.40E+0O 1.659E-01 1.590E-01 1.66E-01 9.387E-02 2.641E-01 2.641E401 2.075E+02 4.241E-01 2.08E+02 1.052E-01 9.603E-01 9.603E-41 7A97E100 1.012E+01 1.012E+01 8.993E-01 6.558E-01 8.99E-01 3.835E-02 1.926E-01 1.926E-01 5.589E-01 1.563E+00 1.563E+O0 4.512E-02 1.092E-01 1.092E-01 1.811E-02 4.909E-02 4.909E-02 1.990E+01 5.885E-01 1.99E+01 1.795E-02 4.866E-02 4.866E-02 2.43E402 Sample CS013004-006 Spill Area 2400303C1 Surface Soils (1st 6")(pC,/gm)Result MDA Used 4.326E-02 3.908E-02 4.33E-02 6.588E-02 8.926E-02 8.93E-02 6.130E-01 1.378Et00 1.38E+00 7.752E-02 2.188E-01 2.188E-01 3.030E-02 2.529E-01 2.529E-41 1.744E+02 4.606E-01 1.74E102 4.207E-01 9.052E-01 9.052E401-1.411E-01 9.899E+00 9.899E+00 1.256E+00 6.032E-01 1.26EF00-1.763E-02 1.544E-01 1.544E-01 1.173E+00 1.641E400 1.641E+O0 8.891E-02 1.074E-01 1.074E401 1.856E-01 6.289E-02 1.86E-01 1.566E+01 6.545E-01 1.57E+01 2.698E-02 6.822E-02 6.822E-02 2.06E+02 Sample CS013004-008 Emergency Retention Basin Surface Soils (1st 6")(pCI/gm)Result MDA Used 1.708E-02 1.403E-01 1.40E-01 5.986E-03 1.224E-01 1.22E-01 1.121E+00 1.445EFOO 1.44E+00-3.809E-04 1.406E-01 1.41E-01 7.355E-01 2.409E-01 7.36E-01 2.129E+01 2.536E-01 2.13E+01 1.728E-01 4.628E-01 4.628E-01 4.298E+01 9.814E+00 4.30E101 1.526E-02 2.837E-01 2.837E401 7.072E-02 2.582E-01 2.582E4-1 2.700E+00 1.510E400 2.70E+00 1.485E-02 1.220E-01 1.220E-01 2.250E-02 6.098E-02 6.098E-02 7.010E-01 6.790E-01 7.01E-01 4.074E-02 9.868E-02 9.868E-02 7.15E+01 0.02%0.06%0.58%0.07%0.11%85.26%0.39%4.16%0.37%0.08%0.64%0.04%0.02%8.17%0.02%100.00%0.02%0.04%0.67%0.11%0.12%84.55%0.44%4.80%0.61%0.07%0.80%0.05%0.09%7.59%0.03%100.00%0.20%0.17%2.02%0.20%1.03%29.76%0.65%60.08%0.40%0.36%3.77%0.17%0.09%0.98%0.14%100.00%Sample CS013004-005 Spill Area 2400303C1 Surface Soils (1st 6")(pCI/gm)Result MDA Used AM-241 1.648E-02 1.354E-01 1.35E-01 AM243 9.944E-02 8.982E-02 9.94E-02 C-14 1.435E+00 1.051E+00 1.44E+00 CM-245 9.517E-02 1.556E-01 1.556E-01 CO-60 2.277E-01 2.486E-01 2.486E-01 CS-137 5.081E+01 2.355E-01 5.08E+01 EU-155 6.000E-01 5.594E-01 6.OOE-01 H-3 1.043E+00 9.755E+00 9.755E+00 1-129 3.374E-01 3.883E-01 3.8832-01 NB-94 -3.178E-02 1.259E-01 1.259E-1 NI-63 1.970E+00 1.836E400 1.97E+00 PU-238 1.932E-02 5.234E-02 5.234E-02 PU-239 9464E-03 1.165E-01 1.165E-01 SR-90 3.200E+00 6.905E-01 3.20E200 U-236 1.482E-02 1.121E-01 1.121E-01 6.92E+01 Sample CS013004-007 Spill Area 2400303C1 Surface Soils (1st 6")(pCi/gm)Result MDA Used AM-241 O.OOOE+00 6.228E-02 6.23E-02 AM243 3.134E-02 7.924E-02 7.92E402 C-14 1.277E+00 1.379E+00 1.38E+00 CM-245 2.589E-02 1.048E-01 1.05-E1 CO-60 3.570E-02 1.939E-01 1.939E401 CS-137 9.349E+00 1.823E-01 9.35E+00 EU-155 1.401E-01 3.895E-01 3.895E-01 H-3 8.951E+00 1.029E+01 1.029E+01 1-129 -9.881E-03 3.125E-01 3.125E-1 NB-94 -8.472E-03 1.630E-01 1.630E-01 NI-63 2.145E+00 1.499E+00 2.14E+00 PU-238 -1.245E-02 1.471E-01 1.471E-01 PU-239 2.025E-02 1.129E-01 1.129E401 SR-90 1.041E+00 6.891E-01 1.04E+00 U-236 3.381E-02 4.581E-02 4.581E-02 2.58E+01 Sample CS013004-009 Emergency Retention Basin Surface Soils (1st 6")(PCI/gm)Result MDA Used AM-241 6.563E-02 9.722E-02 9.72E402 AM243 1.550E-01 5.999E-02 1.55E-01 C-14 7.087E-01 1.331E+00 1.33E+00 CM-245 1.759E-01 1.039E-01 1.76E-01 CO-60 8.647E-01 2.417E-01 8.65E-01 CS-137 3.240E201 2.798E-01 3.24E+01 EU-155 3.470E-01 5.541E-01 5.541E-01 H-3 3.006E+00 1.054E+01 1.054E+01 1-129 -1.874E-02 2.716E-01 2.716E-01 NB-94 5.722E-02 2.256E-01 2.256E-41 NI-63 3.210E+00 1.496E+00 3.21E+00 PU-i38 4.426E-02 1.445E-01 1.445E-01 PU-239 -4.532E-03 1.233E-01 1.233E-01 SR-90 1.161EF00 6.452E-01 1.16E+00 U-236 1.475E-01 4.995E-02 1.48E-01 5.14E+01 0.20%0.14%2.07%0.22%0.36%73.42%0.87%14.10%0.56%0.18%2.85%0.08%0.17%4.62%0.16%100.00%0.24%0.31%5.34%0.41%0.75%36.21%1.51%39.87%1.21%0.63%8.31%0.57%0.44%4.03%0.18%100.00%0.19%0.30%2.59%0.34%1.68%63.03%1.08%20.51%0.53%0.44%6.24%0.28%0.24%2.26%0.29%100.00% Attachment A, Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Page 2 of 2 Sample CS013004-010 Emergency Retention Basin Surface Soils (1st 6")(pCUgm)Result MDA Used AM-241 6.704E-03 1.371E-01 1.37E-01 AM243 5.310E-02 1.343E-01 1.34E-01 C-14 1.210E+00 1A27E+00 1.43E+00 CM-245 3.384E-02 2.060E-01 2.06E-01 CO-60 5.665E+00 2.814E-01 5.67E+00 CS-137 5.424E+01 3.064E-01 5.42E+01 EU-155 8.057E-02 5.829E-01 5.829E-01 H-3 2.845E+01 1.008E+01 2.85E+01 1-129 6.859E-02 2.777E-01 2777E-01 NB-94 1.336E-01 3.152E-01 3.152E-01 NI-63 1.648E+01 1.396E+00 1.65E+01 PU-238 9.437E-02 1.140E-01 1.140E-01 PU-239 9.854E-02 6.676E-02 9.85E-02 SR-90 7.192E+00 6.492E-01 7.19E+00 U-236 4.707E-02 7.696E-02 7.696E-02 1.1 5E+02 0.12%0.12%1.24%0.18%4.91%47.00%0.51%24.66%0.24%0.27%14.28%0.10%0.09%6.23%0.07%100.00%Sample CS013004-011 Emergency Retention Basin Surface Soils (1st 6")(pCigm)Result MDA Used AM-241 1.765E-01 1A37E-01 1.77E-01 AM243 1.039E-01 9.952E-02 1.04E-01 C-14 1.734E+00 1.524E+00 1.73E+00 CM-245 1.124E-01 1.527E-01 1.53E-01 CO-60 3.335E+00 2.693E-01 3.34E+00 CS-137 3.616E+01 2.683E-01 3.62E+01 EU-155 4.595E-02 4.476E-01 4.476E-01 H-3 3.441E+00 9.854E+00 9.854E200 1-129 8.316E-02 2.687E-01 2.687E-01 NB-94 2.923E-01 2.079E-01 2.92E-01 NI-63 1.397E+01 1.395E+00 1.40E+01 PU-238 7.927E-02 7.159E-02 7.93E-02 PU-239 1.321E-01 7.159E-02 1.32E-01 SR-90 7.437E+00 6.639E-01 7.44E+00 U-236 4.962E-02 4.482E-02 4.96E-02 7.42E+01 0.24%0.14%2.34%0.21%4.50%48.74%0.60%13.28%0.36%0.39%18.83%0.11%0.18%10.03%0.07%100.00%AM-241 AM243-C-14 CM-245 CO-60 CS-137 EU-155 H-3 1-129 NB-94 Ni-63 PU-238 PU-239 SR-90 i U-236 MEAN STANDARD MEAN DEVIATION 0.15% 0.09%0.16% 0.10%2.11% 1.51%0.22% 0.11%1.68% 1.94%58.50% 21.34%0.76% 0.38%22.68% 19.00%0.53% 0.30%0.30% 0.19%6.96% 6.56%0.17% 0.18%0.16% 0.13%5.49% 3.08%0.12% 0.09% Final Status Survey Plan for the Plum Brook Reactor Facility Attachment B Approach and Basis for Development of Site-Specific Derived Concentration Guideline Levels (DCGL) Plum Brook Reactor Facility Final Status Survey Plan Revision 0 1.0 Purpose Document the approach, methodology and bases for the establishment of site-specific Derived Concentration Guideline Levels (DCGL) and to document the actual DCGL(s) and area factors to be used during the performance of Final Status Survey of the Plum Brook Reactor Facility (PBRF).2.0 References

2.1 Title

10, Code of Federal Regulations, Part 20 "Standards for Protection Against Radiation" 2.2 Draft Regulatory Guide DG-4006, "Demonstrating Compliance with the Radiological Criteria for License Termination" (NRC 1998a)2.3 NUREG-1549, "Decision Methods for Dose Assessment to Comply with Radiological Criteria for License Termination" (NRC 1998b)2.4 PBRF Decommissioning Plan 2.5 NUREG-1757 Vol. 2, "Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria" (NRC 2003)2.6 NUREG-5512, Vol. 3, "Parameter Analysis" (NRC 1999)2.7 NUREG/CR-6697, "Development of Probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 Computer Codes" (NRC 2000)2.8 Federal Guidance Report No. 11 (FGR 11), "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion" 2.9 Federal Guidance Report No. 12 (FGR 12), "External Exposure to Radionuclides in Air, Water and Soil" 2.10 NUREG/CR-6377 (PNL-1,1408), Krupka, K.M., and R.J. Seine. 1998. "Effects on Radionuclide Conecentrations by Cement/Groundwater Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities" 2.11 Mattigod, S.V., et. al., 2002. "Radionuclide Desorption and Leaching Tests for Concrete Cores from Haddam Neck Nuclear Plant Facilities. Final Letter Report, Battelle, Pacific Northwest Laboratory" 2.12 Fuhrmann, M., Sullivan, T, 1999. "Leaching and Sorption of Radionuclides: Structural Concrete from Maine Yankee Nuclear Power Station. Final Letter Report, Brookhaven National Laboratory" 2.13 Clapp, R.B., and Hornbergerj G.M., 1978. "Empirical Equations for Some Soil Hydraulic Properties", Water Resources Research 14:601-604. 2.14 Fetter, C.W., 1988. Applied Hydrology, Merrill Publishing Company, Columbus OH.2.15 Freze, RKA. and Cherry, J.A., 1981. Groundwater, Prentice-Hall, Inc. Englewood Cliffs, NJ.B-I Plum Brook Reactor Facility Final Status Survey Plan Revision 0 2.16 Gray, D.M., 1970. Handbook on the Principles of Hydrology, Water Information Center, Inc. Port Washington, NY.2.17 McWorter, D.B. and Sunada, D.K. 1977. Groundwater Hydrology and Hydraulics, Water Resources Publication, Fort Collins, CO.2.18 National Climactic Data Center, NCDC, http://www.ncdc.noaa gov/oa/ncdc.html. 2.19 Teledyne Isotopes, 1987. "An Evaluation of the Plum Brook Reactor Facility and Documentation of Existing Conditions, Volume 3: Physical Characterization of Radioactive/Contaminated Areas of the PBRF." 2.20 US Army Corps of Engineers, 2004. "Hydrogeologic Report Plum Brook Reactor Facility, Sandusky, OH." 2.21 US Department of Energy, 2001. User's Manual for RESRAD Version 6. Office of Scientific and Technical Information, Oak Ridge, TN.3.0 DCGL Approach Consistent with 10 CFR Part 20, decommissioning means reducing residual radioactivity to a level that permits termination of the license and release of the site for unrestricted use.The PBRF license would be terminated after NASA demonstrates that the site meets the criteria for decommissioning specified in 10 CFR Part 20, Subpart E, "Radiological Criteria for License Termination." The two radiological criteria for unrestricted use specified in 10 CFR 20.1402 are: (1) the TEDE from residual radioactivity that is distinguishable from background radiation must not be greater than 25 mrem/yr to the Average Member of the Critical Group (AMCG) and (2) residual radioactivity levels must be ALARA.According to NUREG-1549, "Decision Methods for Dose Assessment to Comply with Radiological Criteria for License Termination" (NRC 1998b), a licensee can demonstrate compliance with the dose criterion either by using a generic screening model or by using site-specific analyses. As recommended by Draft Regulatory Guide DG-4006,"Demonstrating Compliance with the Radiological Criteria for License Termination" (NRC 1998a), this attachment presents the methodology and approach used for the development of site-specific DCGLs. This document also presents the estimated DCGLs for surface soils, building surfaces, and subsurface structures at the PBRF. The DCGLs will be used during the final radiation survey to demonstrate compliance with the two unrestricted use criteria previously specified. The Decommissioning Plan for the PBRF presents the proposed methodology for demonstrating that residual contamination levels are ALARA. The methodology follows the guidance in DG4006 and involves comparing the costs and benefits of postulated decommissioning actions. The Decommissioning Plan also presents options for using DCGLs for specific portions of the PBRF and the timing of the final status survey, including the identification of the criteria that will be used for selecting DCGLs for specific portions of the PBRF.B-2 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 4.0 DCGL Methodology This section presents the methodology used in the calculation of DCGLs (the level of residual contamination that would produce a TEDE of 25 mrem/yr to the AMCG).DCGLs were estimated using existing characterization data. DCGL estimates are based on the analysis of scenarios that could reasonably be expected to occur if a site is released for unrestricted use. A scenario is defined as a set of release modes, receptor metabolic and behavioral characteristics, environmental transport pathways, and exposure modes that result in dose to an individual or population. The dose analysis performed assumes the PBRF site is released for unrestricted use and evaluates the case of members of the public using the site. In actuality, NASA has no plans to sell this property after license termination, so realistic receptors would be members of the public located offsite and NASA employees working onsite after license termination. Thus, unrestricted use of the PBRF site is conservative and bounds the realistically expected scenario.NRC has published guidance on methods for dose analysis supporting license termination under 10 CFR Part 20 (NUREG/CR-5512 [Kennedy and Strenge 1992], DG-4006, NUREG-1549, and NUREG-1757 Vol. 2, "Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria" [NRC 2003]). The guidance allows using either generic screening or site-specific dose assessment in the decision framework. Under the generic screening approach, NRC has identified pathways, scenarios, models, and model parameter values, and has provided analysis results in the form of levels of contamination consistent with the 10 CFR Part 20, Subpart E, dose criteria. The pathways and scenarios constitute the residential farmer and building reuse scenarios. The NRC generic screening analysis of the residential farmer scenario is based on the assumption that all contamination has been distributed into the upper 15 cm (6 in.) of soil. Among the options presented for site-specific analysis is the use of site-specific parameter values and existing models other than the generic NRC model. The guidance recommends that the licensee provide information supporting use of site-specific data or models other than the generic NRC model.Because the generic screening model addresses subsurface contamination through assumed redistribution to surface soil, it is very conservative for the case of residual contamination of subsurface structures. To provide a consistent level of analysis for the contamination of surface soil, building surface, and subsurface structures, a site-specific analysis approach was used for the PBRF.The dose model selected for analyzing residual soil contamination, RESRAD Version 6.0 (Yu et al. 2000), has been formally accepted by the NRC for analysis of residential farmer scenarios. The dose model selected for analyzing residual building surface contamination, RESRAD-BUILD Version 3.22 (Yu et al. 2000), addresses pathways discussed in NRC guidance and is widely used by the U.S. Department of Energy (DOE) and the U.S.Department of Defense when analyzing building reuse scenarios. These two site-specific models include all pathways and exposure modes included in the NRC generic screening models. No conditions outside those incorporated in the site-specific models are expected to occur at the PBRF. The residential farmer scenario presumes that both the residence and garden are located on contaminated soil. Thus, the site-specific modeling is appropriate for assessing doses because of contamination of soil and building surfaces.B-3 -Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The RESRAD Version 6.21 (Yu et al. 2002) model was used to analyze residual subsurface structure contamination to allow a sensitivity analysis to be conducted for the concrete Kd values. In this case, concrete Kd is the most sensitive parameter. No conditions outside those incorporated in the site-specific model are expected to occur at the PBRF, and no pathways have been eliminated. Thus, the site-specific model is appropriate for assessing dose because of residual contamination associated with subsurface structures. Using existing characterization information, site-specific pathway scenarios were used to calculate DCGLs and to develop estimates of dose over time for the AMCG at the PBRF.The site-specific DCGLs were developed by considering PBRF soils and hydrology. 5.0 DCGL Bases 5.1 Residual Contamination in Surface Soils NRC regulatory guidance (DG-4006) recommends analysis of a residential farmer scenario as the basis for the DCGLs for residual contamination in site-wide surface soil. In the residential fanner scenario, an individual could contact residual contamination by establishing a home and garden on contaminated soil or by using groundwater that comes in contact with the residual contamination. The primary release modes are partitioning of contaminants from soil into infiltrating water and resuspension by wind. The environmental transport pathways include ground water transport; translocation into plants, animals, and fish; and atmospheric dispersion. Exposure modes include ingestion of water, crops, animal products, and fish; direct external exposure from the ground; inhalation of airborne material; and inadvertent ingestion of soil.NUREG-1549 identifies DCGLs (i.e., soil concentrations that would result in a TEDE of 25 mrem/yr to the AMCG) for a generic, screening-level exposure scenario. More realistic site-specific DCGLs for the PBRF were developed using RESRAD Version 6.21, a computer code developed by DOE and commonly used to estimate residual contamination in soils. The site-specific DCGLs were calculated based on many variables that characterize the receptors, environmental pathways, and modes of exposure. The estimates of physical, behavioral, and metabolic parameter values were developed from either site measurements or literature review.In support of the PBRF project and resident farmer DCGL development, available hydrogeologic information was consolidated in a report by the US Army Corps of Engineers entitled "Hydrogeological Report Plum Brook Reactor Facility Sandusky, Ohio". This report summarized available information about the geologic and hydrogeologic conditions that exist both regionally and within the PBRF. The following excerpts from the hydrogeologic report were used to develop site-specific RESRAD inputs as shown in Tables B-I through B-4.Note that surface soil dose is insensitive to the hydrogeological parameters but site specific values are provided for completeness. B-4 .Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Bedrock that subcrops at the PBRF consists ofDevonian Delaware Limestone and the overlying Devonian Plum Brook Shale Member of the Olentangy Shale. The majority of the site is underlain by Olentangy Shale, with the subcrop of Delaware Limestone limited to the northern and southeastern portion of the PBRF. Underlying the Delaware Limestone is a thick section ofpredominantly carbonate bedrock consisting of the Columbus Limestone and the Detroit River Formation. The bedrock surface at the PBS generally slopes toward the north, although the PBS is located in an area where an apparent bowl-shapedfeature is present. In-filling of the bedrock depression has resulted in a similar thickening of unconsolidated deposits at the PBRF.Unconsolidated deposits consist mostly of glacial till that occurs as a thin veneer over the bedrock surface. The thickness of these materials at the PBRF is typically about 25ft. Native surficial deposits at the PBRF have been extensively disturbed. Boring logs for the PBRF test borings and monitoring wells show that the unconsolidated deposits consist predominantly of cohesive soil, with some relatively thin, discontinuous granular units interbedded. The pro-glacial lacustrine depositional environment in which these deposits formed tends to homogenize the deposits through wave reworking. While localized lenses of granular materials do exist, it does not appear that these lenses are continuous across the site, and these units should not be considered to be indicative of the typical site stratigraphy. The United States Department ofAgriculture, Natural Resources Conservation Service (2002) has recently revised the Soil Survey of Erie County, Ohio. The soil within the 27-acre PBRF is mapped as Udorthents, disturbed soil that has been affected by construction activities. Review of the soils surrounding the PBRF provides insight regarding what was likely present prior to disturbance. The soils in the immediate vicinity of the PBRF consist of Colwood Loam, 0-1 percent slopes (CmA); Elnora loamy fine sand, 0-4 percent slopes (EnA); Gilfordfine sandy loam, 0-1 percent slopes (GdA); Oakville loamyfine sand, 0-6 percent slopes (Qab), and Udorthents, loamy, 0-6 percent slopes (UdB). These undisturbed soils are composed of loam, loamyfine sand, fine sandy loam, and loamyfine sand, respectively. The surficial soil at the PBRF has been extensively disturbed. In addition, the entire site was reportedly regraded to promote surface water to flow to the southeast corner of the PBRF. These excavation and grading activities have resulted in the entire PBRF being mapped by Natural Resources Conservation Service as Udorthents. Photographs during construction show stockpiled soil that was B-5 u B Plum Brook Reactor Faciliay Final Status Survey Plan Revision 0 presumably used to backfill around the structures and to support the regrading activity. Therefore, it is likely that the surficial materials at the PBRF are a mixture of variable thickness composed of the entire section of unconsolidated deposits, which at depth predominantly consists of cohesive soils.Hydraulic conductivityfor the mixed unconsolidated deposits ranges from 49 to 270 meters/year (m/yr), gradient ranges from 0.005 to 0.006fft/ft, and the porosity is expected to range from about 0.35 to 0. 70 (Freeze and Cherry, 1979). The hydraulic conductivity of the Delaware Limestone ranges from 3 to 188 m/yr, and the gradient ranges from 0.002 to 0.003ft/ft. The site-specific effective porosity of the Delaware Limestone has not been established. Therefore, a published value for limestone must be used to calculate groundwater flow velocity: 0.01 to 0.3 (Fetter, 1988).All the other parameters used in the dose analysis were generic screening values or a most conservative value was chosen. These parameters were estimated based on NRC and DOE guidance for generic screening (i.e., the NUREG-1549 analysis and the RESRAD computer code) and are considered to be prudently conservative. Using a water table drop rate of 0 m/yr is also prudently conservative because it minimizes travel time through the unsaturated zone for the observed thickness of the zone. Using observed values for other site-specific parameters is reasonable because it is consistent with existing conditions and does not introduce a judgment bias that may be conservative or non-conservative depending on the intricacies of pathway analysis for individual radionuclides. Wherever possible, NRC-recommended parameter values were used unless site-specific data were available. In the absence of either site-specific and NRC-recommended values, RESRAD default values were used. The parameter values used in the analysis of the PBRF residential farmer scenario are presented in Tables B-i through B-8. The generic values used for the most dose-sensitive parameter (i.e., the distribution coefficient), are relatively high. This results in retaining radionuclides in soil rather than removing them by groundwater, which produces conservative dose estimates through the external exposure pathway for the radionuclides controlling dose at the PBRF. The radiation dose limit and time for calculations are 25 mrem/yr and 1000 years, respectively, as specified in 10 CFR 20.1401 and 20.1402.B-6 Plum Brook.Reactor Facility Final Status Survey Plan Revision 0 Table B-i. Residential Farmer Scenario: Contaminated Zone Parameters Parameter Parameter Value Source Area of contaminated zone 109100 m 2 for controlled Teledyne Isotopes, 1987.area including:

• 102400 m 2 for PBRF* 6700 m 2 for Pentolite Ditch Thickness of contaminated zone I m Conservative thickness to maximize dose Length parallel to aquifer flow 365 m Teledyne Isotopes, 1987.Radiation dose limit 25 mrem/yr 10 CFR 20.1402 Time since placement of material 0 years Distribution coefficients available Time for calculations Through 1000 years 10 CFR 20.1402 Table B-2. Resident Farmer Scenario:

Cover and Contaminated Zone Hydrologic Data Parameter Parameter Value Source Density of contaminated zone 1.522 g/cm 3 Hydrogeologic Report PBRF, 2004.Average value used unconsolidated deposits.Contaminated zone erosion rate 0.001 m/yr RESRAD Contaminated zone total porosity 0.45 Groundwater Hydrology and Hydraulics, 1977.Contaminated zone field capacity 0.20 RESRAD Contaminated zone hydraulic 270 m/yr Hydrogeologic Report PBRF, 2004. Most conductivity conservative value unconsolidated deposits.Contaminated zone b parameter 7.12 "Empirical Equations for Some Soil Hydraulic Properties", 1978. Sandy clay loam Evapotranspiration coefficient

0.5 RESRAD

Precipitation 0.86 m/yr National Climactic Data Center -Ohio Irrigation 1.04rm/yr NUREG 1549 Irrigation mode Overhead RESRAD Runoff coefficient

0.3 Handbook

on the Principles of Hydrology, 1970.Watershed area for stream or pond I x 106 m 2 RESRAD B-7 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table B-3. Residential Farmer Scenario: Saturated Zone Hydrologic Data Parameter Parameter Value Source Density of saturated zone 1.522 g/cm 3 Hydrogeologic Report PBRF, 2004.Average value used unconsolidated deposits.Saturated zone total porosity 0.45 Groundwater Hydrology and Hydraulics, 1977.Saturated zone effective porosity 0.20 Groundwater Hydrology and Hydraulics, 1977.Saturated zone hydraulic 270 rn/yr Hydrogeologic Report PBRF, 2004. Most conductivity conservative value unconsolidated deposits.Saturated zone hydraulic gradient 0.005 m/m Hydrogeologic Report PBRF, 2004.Saturated zone b parameter NA Water table drop rate 0.0 mryr Most conservative -minimizes transport time Well pump intake depth 8 (m below water table) Hydrogeologic Report PBRF, 2004 Mixing model Nondispersion RESRAD Individual use of groundwater 118 m 3/yr NUREG 1549 Table B4. Residential Farmer Scenario: Uncontaminated and Unsaturated Zone Hydrologic Data Parameter Parameter Value Source Number of unsaturated zone strata 1 Hydrogeologic Report PBRF, 2004.Unsaturated zone thickness 3.0 m Hydrogeologic Report PBRF, 2004.Unsaturated zone soil density 1.522 g/cm 3 Hydrogeologic Report PBRF, 2004.Average value used unconsolidated deposits.Unsaturated zone total porosity 0.45 Groundwater Hydrology and Hydraulics, 1977.Unsaturated zone effective 0.20 Groundwater Hydrology and Hydraulics, porosity 1977.Unsaturated zone b parameter 7.12 "Empirical Equations for Some Soil Hydraulic Properties", 1978. Sandy clay loam Unsaturated zone hydraulic 270 rn/yr Hydrogeologic Report PBRF, 2004. Most, conductivity conservative value unconsolidated deposits.B-8 -B R F Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table B-5. Residential Farmer Scenario: Distribution Coefficients Parameter Value*Element(mL/g) C 21 Fe 891 Co 1,000 Ni 37 Sr 32 Tc 7 Cs 447 Eu 955* Source: NUREG-1549. Table B-6.Residential Farmer Scenario: Dust Inhalation and External Gamma Parameters Parameter Parameter Value Source Inhalation rate 8400 m 3/yr NUREG-1549a Mass loading for inhalation 6 x 106 g/m 3 NUREG-1549b Dilution length for airborne dust 3 m RESRADC Exposure duration 365.25 days NUTREG-1549 Shielding factor, inhalation 0.40 RESRAD Shielding factor, external gamma 0.47 NUREG-1549d Fraction of time indoors, onsite 0.66 NUREG-1549 Fraction of time outdoors, onsite 0.11 NUREG-1549 Shape factor, external gamma 1 RESRAD Fraction of annular areas 0 RESRAD a. NUREG-1549.

b. Activity and time average of NUREG-1549 values.c. RESRAD.d. Sum of the product of the means for the fraction of time and shielding factor for outdoor and indoor exposure.B-9 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table B-7. Residential Farmer Scenario:

Ingestion Pathway, Data Dietary Parameters Parameter Parameter Value Source Fruit, vegetable, and grain consumption 78 kg/yr NUREG-1549ab rate Leafy vegetable consumption rate 15 kg/yr NUREG-1549 Milk consumption 118 L/yr NUJREG-1549 Meat and poultry consumption 52 kg/yr NUREG-1549C Fish consumption 16 kg/yr NUREG-1549 Soil ingestion rate 18.3 g/yr NUREG-1549 Drinking water intake 478 L/yr NUREG-1549 Fraction of drinking water from site 1 RESRADd Fraction of aquatic load from site 0.5 RESRAD a. Sum of individual means for other vegetables, fruit, and grain.b. NUREG-1549.

c. Sum of individual means for meat and poultry.d. RESRAD.Table B-8. Residential Farmer Scenario:

Ingestion Pathway Data, Nondietary Parameters Parameter Parameter Value Source Livestock fodder intake for meat 8.5 kg/day NUREG-1549a Livestock fodder intake for milk 17 kg/day NUREG-1549b Livestock water intake for meat 50 L/day RESRADC Livestock water intake for milk 160 L/day RESRAD Livestock soil intake 0.5 kg/day RESRAD Mass loading for foliar deposition 4 x 104 g/m 3 NUREG-1549d Depth of soil mixing layer 0.15 m NUREG-1549 Depth of roots 0.9 m RESRAD Drinking water fraction from groundwater 1 RESRAD Livestock water fraction from groundwater 1 NUREG-1549 Irrigation fraction from groundwater 1 RESRAD a. NUREG-1549.

b. Sum of individual medians for forage, hay, and grain.c. RESRAD.d. Value for gardening.

B-10 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The parameters identified in Tables B-I through B-8 were used in the RESRAD code to determine the corresponding radionuclides concentrations in soil (i.e., DCGLs). Table B-9 presents the DCGLs for the radionuclides that may present at PBRF.Table B-9. DCGLs for Surface Soils Site-Specific DCGLa Radionucide (pCi/g)Co-60 3.8 Cs-137 14.7 Eu-152 8.8 Eu-154 8.2 Fe-55 7.1 E+04 Ni-59 1.4 E+04 Ni-63 5.4 E+03 Sr-90 5.4 a. Calculated by RESRAD using the parameters specified in Tables B-I through B-8.5.2 Residual Contamination in Buildings The PBRF buildings that were largely uncontaminated by past operations may be demolished during decommissioning and may be used as clean, hard fill to backfill the subsurface structures. The PBRF buildings having residual contamination may be decontaminated, surveyed, and demolished. If used as a source of fill material, the FSS survey will determine that the buildings meet the criteria for unrestricted release. After a survey of the subsurface structures demonstrates that these areas are suitable for free release, the demolition debris will be placed in the below grade cavities of the buildings. The building reuse scenario was used to develop DCGLs supporting release of PBRF buildings, such as the Reactor Office and Laboratory Building (Building 1141), which is known to have low levels of residual contamination. In the building reuse scenario, residual contamination is assumed to be located on building surfaces (i.e., walls, floors, and ceilings). Exposure modes include direct external exposure, inhalation, and ingestion. To analyze residual contamination in PBRF buildings, a site-specific analysis was conducted using RESRAD-BUILD 3.22. The RESRAD-BUILD parameters were selected in accordance with the methods recommended in NUREG-1757 Vol. 2.The parameters were categorized as behavioral, metabolic, or physical. The B-l1 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 behavioral and metabolic parameters selected were the default values from NUREG-5512, Vol. 3 or the NRC screening code DandD 2.1.0. Because of differences between the RESRAD-BUILD and NUREG-5512 dose assessment models, some parameters required by the RESRAD-BUILD code are not provided in NUREG-5512 Vol. 3. The RESRAD-BUILD specific parameters were derived from NUIREG/CR-6697. The average or most likely value was selected to represent the average member of the critical group.Physical parameters that were not site specific, such as the assumed room dimensions, or selected to be consistent with NUREG/CR-5512 model assumptions (such as evaluating one room for the building occupancy scenario) were selected to be conservative. Physical parameters that did not have a clearly conservative value were evaluated using the probabilistic module of RESRAD-BUILD to determine whether the dose was sensitive to the parameter. The only parameter requiring a sensitivity analysis was the "Lifetime or Time of Source Removal" (Source Lifetime). This represents the time over which surface contamination is removed.The default parameter distribution function (PDF) from NUREG/CR-6697, Attachment C, Section 8.8, was used for the sensitivity analysis of the Source Lifetime parameter. The PDF was a triangular distribution defined by a 1000 day minimum, 100,000 day maximum, and 10,000 day most likely value. The RESRAD-BUILD output for the Partial Rank Correlation Coefficient (PRCC) was used to evaluate the sensitivity of dose to the parameter. The PRCC is one of the recommended methods in NUREG-1757 Section I.7.5. In addition, precedence has been set for the use of PRCC in other previously submitted and approved decommissioning plans. If the PRCC exceeded the absolute value of 0.10, then the dose was considered sensitive to the parameter and either the 2 5 b or 75t quantile of the PDF was selected as the deterministic parameter. The 25t quantile was used if the dose was negatively correlated, i.e., dose increased as the parameter decreased. The 75f quantile was used if the dose was positively correlated, i.e., dose increased as the parameter increased. A negative correlation was indicated by a negative PRCC result and a positive correlation by a ositive PRCC. The 25h quantile for source lifetime was 18,200 days and the 75 quantile was 52,700 days. All of the nucides were sensitive to the Source Lifetime parameter. Table B-10 lists the nuclides according to whether the dose was positively or negatively correlated. In general, a nuclide was positively correlated if the primary dose pathway was direct radiation and negatively correlated if the direct radiation dose was not significant. B-12 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table B-10.Results of Sensitivity Analysis for Source Lifetime Parameter Positive PRCC 7 5 th Quantile C-14 Co-60 Cs-137 Eu-152 Eu-154 I-129 Nb-94 Negative PRCC 25th Quantile Fe-55 Ni-59 Ni-63 Sr-90 Tc-99 H-3 Pu-241 Pu-238 Cm-243 Am-241 Eu-155 Pu-239 U-234 U-235 U-236 U-238 Table B-il lists all of the parameters used in the site-specific RESRAD-BUILD analysis and provides the reference and justification as appropriate. The room dimensions of 15 m [49 fit] long, 5 m [16 ft] wide, and 3 m [10 fit] high represent the largest room expected to have residual contamination and is considered prudently conservative since it maximizes direct radiation fiom the floor and the largest wall because of the relative narrowness of the room. The bases provided in Table B-il for the parameter selections are self-explanatory with one exception, i.e., Direct Ingestion. The Direct Ingestion parameter of 4.07E-07 hr 4 was selected to ensure consistency with the NRC recommended Effective Transfer Rate for Ingestion provided in NUREG/CR-5512 Vol. 3, Section 5.2.3. The recommended Effective Transfer Rate is L.IE-04 m 2/h and applies to loose source surface contamination. RESRAD-BUILD does not have a direct analogy to the Effective Transfer Rate from the source. However, the Direct Ingestion parameter can be modified to result in the same ingestion intake as would occur using the NUREG/CR-5512 model and the Effective Transfer rate. This is accomplished by dividing the 1. IE-04 m 2/h value by the total source area for the room, i.e., 270 in 2.RESRAD-BUnLD calculates the ingestion intake for each of the six sources (4 walls, floor,, and ceiling) by calculating the total inventory (activity/area multiplied by the area)-of each source and then multiplying by the Direct Ingestion parameter. The 4.07E-07 hi 1 B-13 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 parameter will result in an ingestion rate equal to 1. IE-04 m 2/hr when the results of all six sources are summed.The RESRAD-BUILD dose assessment results are contained in three reports that are available for review as needed. The first contains the nuclides requiring a Source Lifetime parameter of 52,700 days, the second those requiring a Source Lifetime of 18,200 days, and a third containing the results for H-3. The DCGLs were calculated by dividing the 25 mrem/yr criteria by the nuclide specific unitized dose factors. The term unitized dose factor was used because the source term was 1 dpm/100 cm 2 for each radionuclide. Table B-12 provides the DCGLs for the Building Reuse scenario.B-14 ( .a Brook Reactor Facility Finalf ! s Survey Plan Red o Table B-11. Building Reuse Scenario: Parameter Values No Parameter (unit) Type, ValuelDistribution Source Comments/Justiflcation I Exposure duration (days) B 365.25 NUREG/CR-5512, V3 S5.2.1 Accounts for leap year 2 Indoor fraction B 0.267 NUREG/CR-5512, V3 S5.2.2 Equal to 97.5 day/year, or 45 hourtweek; average value 3 Evaluation time (year) P 0 4 Number of rooms P 1 NUREG/CR-5512, VI Building occupancy scenario assumes only one contaminated room 5 Deposition velocity (m/sec) P 2.7E-06 NUREG/CR-6697, C, 7.5 Minimum value selected to maximize airborne concentration 6 Resuspension Rate (sec') P 1.4E-05 NUREG/CR-6697, C, 7.2 Maximum value selected to maximize airborne concentration 7 Air exchange rate for building and room (hr') B 0.8 NUREG/CR-6697, C, 7.4 Most likely value 8 Room area (M 2) p 75 Site-spedfic model Largest unit expected at PBRF 9 Room height (m) P 3 Site-specific model Largest unit expected at PBRF 10 T7me fraction B 1.0 NUREG/CR-5512, VI Building occupancy scenario assumes all time Is spent at one receptor location 11 Breathing rate (m 3/day) B 33.6 NUREG/CR-5512, V3 S5.3 Equal to 1.4 m 3/hr which Is median value and DandD V2.1 default 12 Indirect Ingestion rate (m 2/hr) B 0.00E+00 NUREG/CR-5512, V3 S5.2.3 Indirect ingestion not modeled In building occupancy scenario 13 Receptor location: x,y,z (m) B 7.5, 2.5,1 Site-specific model Occupant located at center of room area with exposure at 1m height 14 Shielding thickness (cm) p 0 Site-specific model No shielding Is assumed 15 Shielding density (glcc) P 0 Site-specific model No shielding Is assumed 16 Shielding material P None Site-specific model No shielding Is assumed 17 Number of sources. P 6 Site-specific model All room surfaces assumed to be equally and uniformly contaminated 18 External dose conversion factor (mrem/yr)Y(pCVm

2) M RESRAD-BUILD FGR 12 defaults 19 Air submersion dose conversion factor M RESRAD-BUILD FGR 12 ((rnremlyr)Y(pCi/m

3) defaults 20 Inhalation dose conversion factors (mrem/pCi)

M RESRAD-BUILD FGR 11 defaults 21 Ingestion dose conversion factors (mrem/pCi) M RESRAD-BULD FGR 11 defaults 1 Wall 22 P Area Site-specific model 23 Direction P X Site-specific model 24 Location of center of source: xy,z (m) P 0, 2.5,1.5 Site-specific model 25 Area (M 2) P 15 Site-specific model Wall area is 5 m by 3 m 26 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionucides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 27 Direct Ingestion (hr 1) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m 2/hr divided by total source area of 270 M 2 28 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 29 Lifetime or time for source removal (days) P Nudide Specific NUREG/CR-6697, C, 8.8 30 Radionucide Concentration (pCIr 2) P 45 Site-specific model Initial concentration is unit sourceof I dpm/100 cm 2 to allow for B-15 r n Brook Reactor Facility iafs Survey Plan f RevlA,i 0 No Parameter (unit) Typeo Value/Dlstributlon Source Comments/Justification 2.Wall I : , , , , ., , I , , ;. , " 1, ., '.31 32 Direction 33 Location of center of source: xy,z (m)34 Area (m 2)35 Air fraction for H-3 Air fraction (for all radionuclides except H-3)36 Direct ingestion (Wh)37 Removable fraction 38 Lifetime or time for source removal (days)P Area P X P 15,2.5,1.5 P 15 B 1.00 B 0.07 B 4.07E-07 P 0.1 P Nuclide Specific proporthonal DCGL calculation .S ~: ; ~ ., ,., , , :; E- 'I-- , :e ~ .39 Radionuclide Concentration (pCVm 2) P-3. Wal 40 Type P 41 Direction P 42 Location of center of source: x,y,z (m) P 43 Area (m 2) P 44 Air fraction for H-3 B Air fraction (for all radionuclides except H-3) B 45 Direct ingestion (hr') B 46 Removable fraction P 47 Lifetime or time for source removal (days) P 45 Area Y 7.5,0, 1.5 45 1.00 0.07 4.07E-07 0.1 Nudide Specific 45 Site-specific model Slte-spedfic model Site-spedfic model Site-specific model NUREG/CR-6697, C, 8.6 NUREG/CR-6697, C, 8.6 NUREG/CR-5512, V3 S5.2.3 NUREG-1757, V2 SI.6.3.1 NUREG/CR-6697, C, 8.8 Site-specific model Site-specific model Site-specific model Site-specific model Site-specific model NUREG-CR-6697, C, 8.6 NUREG/CR-6697, C, 8.6 NUREG/CR-5512, V3 S5.2.3 NUREG-1757, V2 Sl.6.3.1 NUREG/CR-6697, C, 8.8 Site-specific model Site-specific model Site-spedfic model Site-specific model Site-spedfic model NUREG/CR-6697, C, 8.6 NUREG/CR-6697, C, 8.6 NUREG/CR-5512, V3 S5.2.3 NUREG-1757, V2 Sl.6.3.1 NUREG/CR-6697, C, 8.8 Site-specific model Wall is 5m by3m Recommended value for gaseous form of H-3 Upper bound for contaminated noncombustible solids Equal to 1.1 E-4 m2/hr divided by total source area of 270 m 2 Default parameter value for loose fraction from DandD 2.1 Initial concentration is unit source to allow for proportional DCGL calculation Wall area is 15 m by 3 m Recommended value for gaseous form of H-3 Upper bound for contaminated noncombustible solids Equal to 1.1 E-4 m2/hr divided by total source area of 270 m 2 Default parameter value for loose fraction from DandD 2.1 Initial concentration is unit source to allow for proportional DCGL calculation Wall area is 15 m by 3 m Recommended value for gaseous form of H-3 Upper bound for contaminated noncombustible solids Equal to 1.1 E-4 m 2/hr divided by total source area of 270 m2 Default parameter value for loose fraction from DandD 2.1 Initial concentration is unit source to allow for proportional DCGL calculation 48 Radionuclide Concentration (pCVM 2)4. Wallo 49 Type 50 Direction 51 Location of center of source: x,y,z (m)52 Area (m 2)53 Air fraction for H-3 Air fraction (for all radionuciides except H-3)54 Direct ingestion (hr')55 Removable fraction 56 Lifetime or time for source removal (days)P P P Area Y P 7.5,.5,1.5 P 45 B 1.00 B 0.07 B 4.07E-07 P 0.1 P Nucide Specific 57 Radionuclide Concentration (pCim 2)5. Floor 58 Type P P 45 Area Site-saecific model----B-16 f n Brook Reactor Facility Tel-6 0 ( a Bro eco ailt uvyPa No Parameter (unit) Type Value/Dlstributlon Source Comments/Justlflcatlon 59 Direction P Z Site-specific model 60 Location of center of source: xy,z (m)61 Area (mi)62 Air fraction for H-3 Air fraction (for all radionuclides except H-3)P 7.5,2.5,0 P 75 B 1.00 B 0.07 Site-specific model Site-specific model NUREG/CR-6697, C, 8.6 NUREG/CR-6697, C, 8.6 Floor area is 5 m by 15 m Recommended value for gaseous form of H-3 Upper bound for contaminated noncombustible solids 63 Direct ingestion (hi') B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 m 2/hr divided by total source area of 270 rn 2 64 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 65 Uifetime or time for source removal (days) P Nucide Specific NUREG/CR-6697, C, 8.8 66 Radionuclide Concentration (pCIM 2) P 45 Site-specific model Initial concentration Is unit source to allow for proportional DCGL 6. Cel~ngcalculation 67 Type P Area Site-spedfic model 68 Direction P Z Site-specific model 69 Location of center of source: x,y,z (m) P 7.5, 2.5, 3 Site-spedfic model 70 Area(i 2) P 75 Site-specific model Ceiling area is 15 m by 5 m 71 Air fraction for H-3 B 1.00 NUREG/CR-6697, C, 8.6 Recommended value for gaseous form of H-3 Air fraction (for all radionuclides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 72 Direct ingestion (hr 1) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m 2/hr divided by total source area of 270 m2 73 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 74 Uifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 75 Radionuciide Concentration (pCVM 2)P 45 Site-specific model Initial concentration Is unit source to allow for proportional DCGL calculation Notes: P = physical, B = behavioral, M = metabolic; [NUREG/CR-6676, App. B, Table B.3]B-17 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table B-12. DCGLs for Building Reuse Scenario Radionuclide DCGL (dpmn100 cM 2)C-14 L.OE+07 Fe-55 4.0E+07 Co-60 11,000 Ni-59 9.9E+07 Ni-63 3.6E+07 Sr-90 136,200 Tc-99 1.4E+07 Cs-137 40,500 Eu-152 24,300 Eu-154 4500 H-3 3.2E+08 Pu-241 228,000 Pu-238 4900 Cm-243/244 6100 Am-241 4300 Eu-155 395,000 I-129 67,800 Nb-94 15,800 Pu-239 4400 U-234 31,500 U-235 27,100 U-236 33,200 U-238 32,900 5.3 Residual Contamination in Subsurface Structures Decontamination and decommissioning of below grade PBRF structures (e.g., the Reactor Building [Building 1111]) will include decontamination of surfaces to building reuse DCGLs and offsite disposal of decontamination waste, removing decontaminated above grade and below grade structures down to 1 m (3 fi) below grade, backfilling belowground cavities with rubble generated from demolishing decontaminated above grade and below grade structures, and installing a cover over the backfilled area.B-18 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Residual activity in the belowground portions of the various structures could be from several sources: in crushed concrete from aboveground structures, in remaining portions of the biological shield, on the surfaces of the canals and quadrants. The resident farmer scenario was used for the Subsurface Structure dose assessment. RESRAD 6.21 was used for the assessment with certain parameter modifications, as listed below, to model the source in the saturated zone. The area used in the dose assessment was a 70-m (230-ft) cylinder (the approximate diameter of the subsurface structures), which extended vertically downward a distance of 3 m (10 ft) placing the contaminated zone directly on top of the saturated zone. The thickness of the contaminated zone is taken as 3 m (10 fit) to maximize dose through the external exposure and crop pathways. The well could be conceptualized as either in the center of the contaminated zone or located on the down gradient edge of the 70-m (230 ft.) diameter cylinder because the mass balance (MB) water transport model was used. The MB model eliminates the inappropriate dilution found in the Non-Dispersion Model that does not apply to the saturated zone equilibrium assumption of the Subsurface Structure fill model. Note that the hydrological parameters used were those provided in the Decommissioning Plan, which in some cases differ slightly from the final parameters listed in Tables B-I through B-3. However, these parameters have no effect on the resulting water concentrations from the Subsurface Structure model because the model was designed to simulate concrete in an equilibrium saturated condition and not flow through an unsaturated contaminated zone.The dose assessment and DCGL development for the Subsurface Structure scenario was performed using RESRAD 6.21 and the deterministic parameters from the surface soil scenario with seven changes as listed below. The unsaturated zone depth, time since material placement, and contaminated zone hydraulic conductivity parameters were selected to allow RESRAD to model a saturated condition.

1. MB water transport model used, 2. unsaturated zone depth 0 m, 3. contaminated zone 3 m, 4. contaminated zone area 3850 m 2 , 5. time since material placement 1 yr, 6. contaminated zone hydraulic conductivity 0.86 m/y, and 7. concrete Kds used in place of soil Kds .A dose assessment was also performed assuming a Im cover is in place, which is the actual planned end state for the site. The "no cover" condition was assumed to be conservative for all radionuclides.

The lm cover analysis was performed to ensure that this assumption was correct. As shown in Table B-14, the Im cover assumption results in a lower DCGL for one radionuclide, i.e., H-3.B-19 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Concrete Kds were used to model the concrete debris to be placed in the subsurface structures. Table B-13 provides the range of concrete Kds for each of the radionuclides that were reported as above detection limits in smear samples of PBRF concrete and represent greater than 0.05% of the smear radionuclide mixture. The final list of radionuclides considered for FSS will include only those radionuclides considered significant per NUREG-1757, Vol. 3.The Kd ranges were derived from the following three references:

1. Krupka, K.M., and R.J. Serne. 1998. Effects on Radionuclide Conecentrations by Cement/Groundwater Interactions in Support of Performance Assessment of Low-Level Radioactive Waste Disposal Facilities.

NUREG/CR-6377 (PNL-1 1408).2. Mattigod, S.V., et. al., 2002. Radionuclide Desorption and Leaching Tests for Concrete Cores from Haddam Neck Nuclear Plant Facilities. Final Letter Report, Battelle, Pacific Northwest Laboratory.

3. Fuhrmann, M., Sullivan, T, 1999. Leaching and Sorption of Radionuclides:

Structural Concrete from Maine Yankee Nuclear Power Station. Final Letter Report, Brookhaven National Laboratory. Kd parameter distribution functions (PDFs) were developed for each radionuclide based on the range of potential values. Table B-13 provides the PDFs and defining numerical parameters. NUREG/CR-6697, Appendix A states that the uniform or loguniform distribution is useful if little is known about the distribution except the minimum and maximum, which is the condition arising from compiling the data from the above references. The loguniform is more appropriate when there is a wide range between the minimum and maximum.Accordingly, the loguniform PDF was selected if the range exceeded a factor of 10. Otherwise, the uniform distribution was used. The three exceptions were Sr-90, Cs-137, and Tc-99. Because the Kd ranges were numerically low, i.e., 10, 18, and 21 for Sr-90, Cs-137, and Tc-99, respectively, the uniform distribution was used.Consistent with the recommendations in NUREG-1757, Vol. 2, an uncertainty analysis was performed to determine if the calculated dose was sensitive to the concrete Kd. The uncertainty analysis was performed using the probabilistic module of RESRAD 6.21 with radionuclide specific PDFs. The RESRAD output report of the Partial Rank Correlation Coefficient (PRCC) for the peak of the mean dose was reviewed. A decision criterion of the absolute value of 0.25 was selected for the PRCC test. The 0.1 and 0.25 values were found acceptable by the NRC through the approval of the Connecticut Yankee License Termination Plan (LTP). The results showed that the PRCC was less than -0.25 for all radionuclides indicating that the parameter was sensitive and the dose negatively correlated to the Kd (i.e., the dose went up as the Kd went down). Because the dose was negatively correlated, the 25th quantile value of each PDF was used as the deterministic Kd parameter in the subsurface structure dose model. See Table B-13 for the 25th quantile Kd values.B-20 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The dose assessment Was performed with and without a 1 meter cover. As expected, the dose was higher with no cover with the exception of H-3 where the dose was higher with the cover in place. This is due to -the unique characteristics of H-3 and the corresponding unique RESRAD environmental transport model.The highest H-3 dose was used for the PBRF DCGL calculation as shown in Table B-14, Column 4.RESRAD output report for the Subsurface Structure dose assessments are contained in a separate report available for review as needed. The RESRAD output report contains the maximum dose results (at t = Oy). The RESRAD output report also contains the RESRAD dose results for the evaluation with 1 m cover at the time of maximum dose (t = Oy).Table B-13.Concrete Kds (mug) for Subsurface Structure Model Dose Assessment Radionuclide Literature' Cy 2 Maine 3 Plum Brook &d PDF 25t" Quantile Kd C 10 -500 10 -500 Loguniform 4 26 Fe 10 -100 7 -18 7 -100 Loguniform 13 Co 10 -100 180 -32500 10- 100 Loguniform 17 Ni 10 -100 10 -61 10 -100 Uniforms 32 Sr 1 -3 10 -11l 0.7 -1.3 1 -11 Uniform 3.5 Tc 0- 100 6-21 0-21 Uniform 5.2 Cs 2 -20 34 -26800 2.9 -3.3 2 -20 Uniform 6.5 Eu 200 -1000 200 -1000 Uniform 400 Pu 500 -5000 500 -5000 Uniform 1625 Cm 200 -1000 200 -1000 Uniform 400 Am 200 -5000 >230 -200 -5000 Loguniform 445>1750 I 1-10 I -10 Uniform 3.2 Nb 100 -1000 100 -1000 Uniform 325 U 100 -2000 100 -2000 Loguniform 212 Footnotes:

1. Krupka 1998 and Bradbury 1998 2. Mattigod 2002 3. Fuhrman 1999 4. Minimum and maximum values of distribution

5. Minimum and maximum of distribution lCY Kd value for Sr-90 was confirmed by an independent review by Brookhaven National Laboratory B-21 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The DCGL calculation was performed by dividing 25 mrem/y by the unitized dose factors from the RESRAD output report (and the corresponding output page for the 1 m cover evaluation).

The term unitized dose factor is used because the source term was 1 pCi/g for each radionuclide. The DCGLs are listed in Table B-14. The radionuclides listed in Table B-14 represent all radionuclides that were reported as above detection limits in smear samples of PBRF concrete.The final list of radionuclides considered for FSS will include only those that are considered significant per NUREG-1757, Vol. 3.Table B-14. DCGLs for Subsurface Structures Radionuclide DCGL DCGL PBRF No Cover 1 m Cover DCGL (pCi/g) (pCi/g) (pCi/g)C-14 17 85 17 Fe-55 685 691 685 Co-60 3.3 17 3.3 Ni-59 2134 2,495 2134 Ni-63 779 911 779 Sr-90 0.6 0.7 0.6 Tc-99 25 87 25 Cs-137 2.2 2.6 2.2 Eu-152 9.4 2,074 9.4 Eu-154 8.6 1,426 8.6 H-3 357 166 166 Pu-241 472 552 472 Pu-238 13 17 13 Cm-243/244 4.8 5.3 4.8 Am-241 3.8 4.0 3.8 Eu-155 354 9,184 354 1-129 0.27 0.27 0.27 Nb-94 6.6 1,504 6.6 Pu-239 12 15 12 U-234 22 24 22 U-235 18 25 18 U-236 23 25 23 U-238 22 25 22 B-22 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The last step in the subsurface structure DCGL calculation is the conversion of the pCi/g volumetric DCGLV to an Effective Surface DCGL (DCGLEs). This allows the FSS to be performed using surface activity measurements and the inclusion of the source term that is present on the subsurface structure surfaces.The DCGLES is calculated using the following basic relationship: DCGLv (pCi/g) = Radionuclide Inventory / Concrete Debris Mass Where: Inventory = (SA m 2)(10,000 cm 2/m 2)(DCGLEs dpm/1n00 cm 2)(1 pCi/2.22 dpm)Concrete Debris Mass = (V m 3)(lE+06 cm 3 n/m 3)(1-ri)(2.4 g/cm 3)SA = Structure surface area requiring FSS (internal surfaces above and below grade) (m 2)i= porosity (0.41)V = Volume of fill required (M 3)Combining conversion factors and rearranging terms results on the following equation for calculating the DCGLEs: DCGLES dpm/100 cm 2 = 31,435 (DCGLV pCi/g) (V m 3/SA M 2)The vast majority of the structure contamination is in the Reactor Building (1111), Reactor Hot Lab (1112), Reactor Primary Pump House (1134), and Reactor Office and Lab Building (1141). These buildings are essentially connected and during demolition the debris from these structures will be expected to mix together. Because of the aforementioned, the V/SA ratio will be based on an average of these four buildings. The DCGLES values calculated using this V/SA ratio will conservatively apply to all subsurface structures. The result is conservative because it is very unlikely the actual inventory of residual radioactivity remaining on any structure surfaces will approach the calculated inventory assuming uniform contamination at the DCGLES level. This ensures with high confidence that the Subsurface. Structure volumetric DCGL will not be exceeded. The V/SA ratios are listed in Table B-15.B-23 -Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table B-15. Structure V/SA ratios Structure V/SA Ratio (m 3/m 2)Reactor Building (1111) 2.91 Hot Laboratory Building (1112) 1.19 Primary Pump House (1134) 1.27 Reactor Office and Laboratory Building (1141) 1.65 Average 1.76 Table B-16 lists the DCGLEs and the Building Reuse DCGL values for each radionuclide that was reported as above detection limits in smear samples of PBRF concrete. The final list of radionuclides considered for FSS will include only those that have a significant dose per NUREG-1757, Vol. 3.The DCGLES values were compared to the Building Reuse DCGLs and the more conservative of the two values designated as DCGLFss as shown in Column 4 of Table B-16. The DCGLFss is the surface activity level that will be used during FSS to determine compliance with the 25 mrem/yr unrestricted use criteria.The use of the DCGLFss value is a conservative approach when the DCGLES is limiting because the radionuclide inventory expected to actually to be present on building surfaces at the time of demolition is much lower than that used in either the DCGL or the DCGLES calculations, which assume uniform contamination at either level.If deemed necessary, the Building Reuse DCGLs could be applied for radionuclides where the DCGLES is limiting. This would require a separate calculation to be performed, based on actual FSS measurement results, to confirm that the radionuclide specific inventory divided by the fill volume is less than the Subsurface Structure volumetric DCGL. For the four structures listed in Table B-15, this confirmation would be based on the average residual surface radioactivity level in the four structures (and the combined subsurface structure volumes). For all other structures the confirmation would be structure specific.B-24 Plum Brook Reactor Facility Final Status Survey Plan Revision 0@ Table B-16. Building Reuse DCGLs, Subsurface Structure Effective Surface DCGLs, and DCGLFps Values Radionuclic C-14 Fe-55 Co-60 Ni-59 Ni-63 Sr-90 Tc-99 Cs-137 Eu-152 Eu-154 H-3 Pu-241 Pu-238 Cm-243/244 Ain-241 Eu-155 1-129 Nb-94 Pu-239 U-234 U-235 U-236 U-238 Building Reuse DCGL le (dpm/100 cm 2)(from Table B-12)L.OE+07 4.OE+07 11,000 9.9E+07 3.6E+07 136,200 1.4E+07 40,500 24,300 4,500 3.2E+08 228,000 4,900 4 6,100 4,300 395,000 67,800 15,800 4,400 31,500 27,100 33,200 32.900 Subsurface Structure Effective Surface DCGLEs (dpml100 cM 2)940,500 3.7E+07 182,500 8.0E+07 4.3E+07 33,100 1.3E+06 121,700 520,000 475,800 9.1E+06 2.6E+07 719,200 265,500 210,200 1.9E+07 14,900 365,100 663,900 1.2E+06 995,800 1.2E+06 1.2E+06 DCGLFSS (dpm/100 cM 2)940,500 3.7E+07 11,000 8.OE+07 3.6E+07 33,100 1.3E+06 40,500 24,300 4,500 9.1E+06 228,000 4,900 6,100 4,300 395,000 14,900 15,800 4,400 31,500 27,100 33,200 32,900 6.0 Area Factors Area factors (AFs) were developed for the Surface Soil and Building Reuse scenarios. The Building Reuse AFs also apply to the Subsurface Structure DCGLES values. The AFs were calculated using Co-60 to ensure the values are conservative for all radionuclides. The AF for the direct exposure pathway is lower than that for the ingestion and inhalation pathways and Co-60 generates the highest direct exposure per pCi/g.The AFs for Surface Soil were calculated by first running the RESRAD code with the Surface Soil parameters and a source area of 2000 m 2.The 2,000 m 2 source area was selected since this is the maximum survey unit size for a Class 1 area. RESRAD was then run using source areas ranging from I m 2 to 250 m 2 to represent the elevated area sizes. RESRAD dose reports used for the calculations are available for review as needed.B-25 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The AFs were calculated by dividing the dose result for the 2,000 m 2 source area by the dose results for the smaller elevated areas. The Surface Soil AFs are shown in Table B-17.The AFs for Building Reuse were calculated in an analogous manner except that an initial source area of 75 m 2 was selected to represent the floor area for the room size used in the RESRAD-BUILD modeling for the Building Reuse scenario. The elevated areas evaluated ranged from 0.25 m 2 to 50 m 2.The RESRAD-BUILD dose reports used for the calculations are available for review as needed. The Building Reuse AFs are listed in Table B-18.Table B-17 Surface Soil Area Factors Elevated Area 1 2 3 5 10 15 25 100 250 2000 (mZ)Area 10.4 6.2 4.7 3.4 2.3 1.9 1.6 1.2 1.1 I Factor Table B-18 Building Reuse Area Factors Elevated Area 0.25 0.50 1 2 4 6 8 10 15 25 50 75 (mZ)Area 40.2 20.8 11.1 6.2 3.6 2.8 2.4 2.1 1.7 1.4 1.1 I Factor B-26 Final Status Survey Plan for the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment & DCGL Calculation Plum Brook Reactor Facility Final Status Survey Plan Revision 0 1.0 Purpose This attachment provides a discussion on the decision to leave selected sections of Plum Brook Reactor Facility (PBRF) embedded and buried piping in place, describes the conceptual dose model, and presents the Derived Concentration Guideline Level (DCGL)values and area factors to be used during final status surveys.2.0 References 2.1 NUREG-1757, Volume 2, Consolidated NMSS Decommissioning Guidance, Characterization, Survey, and Determination of Radiological Criteria 2.2 MWH Constructors, Radionuclide Composition and Activity Ratios in Primary Coolant Piping, Transmittal-No. PBRF-05-0285, March 24,2005 2.3 Grove Software Inc., MicroShield User's Manual, Version 7, 2005 2.4 IAEA, Engineering Compendium on Radiation Shielding, Vol. 1, Springer-Verlag New York, 1968.2.5 NASA Plum Brook Station Drawing PF-00375, Reactor Building Process Piping North Half- Plan -25 ft. Elevation, 08/27/56 2.6 NASA Plum Brook Station Drawing PF-00376, Reactor Building Process Piping, South Half- Plan -25 ft. Elevation, 08/27/56 2.7 NASA Plum Brook Station Drawing PF-00385, Reactor Building Process Piping.Pump Room Plan & Sections. Revised 04/03/67 2.8 NASA Plum Brook Station Drawing PF-04645, Process Piping Tunnel Header &Drains Below First Floor -Plan & Sections, 09/09/57 2.9 ICRP, Publication 74, Conversion Coefficients for Use in Radiological Protection against External Radiation, Elsevier, 1997 (Also ICRU Report No. 51, 1987 2.10 Portland General Electric Co., Final Survey Report. Embedded Pipings December, 2004 3.0 Discussion PBRF has performed an assessment of safety, radioactive waste generation, and cost associated with the removal of embedded and buried piping. PBRF has concluded that the increased risk from industrial safety, time and physical logistics of removing the piping, and cost would justify leaving some piping in place. Therefore, designated sections of embedded and buried piping will be remediated in place and undergo FSS.c-i Plum Brook Reactor Facility Final Status Survey Plan Revision 0 3.1 Industrial Safety A study was performed to determine the industrial safety risks associated with removal of embedded and buried piping. A summary of the activities which elevate the safety risks during removal of embedded and buried piping outside those traditionally associated with reactor decommissioning projects include:* A large percentage of piping is located fifteen (15) to thirty-five (35) feet below grade. Working beneath the ground, the site labor forces must rely on the soil stabilization system to prevent a cave-in or a sudden onrush of groundwater into the work area.* The removal of piping in many areas entails the use of large hydraulic hammers (hoe-rams) for extended periods of time. The utilization of hoe-rams has the potential to increase fugitive dust emissions potentially creating silica exposures to labor forces, significantly increases noise levels throughout the facility, increase the risk to injury by flying debris, building collapse and worker becoming pinched by heavy equipment.

• Piping and rebar will have to be cut using torches which increases the risk of a fire.* The packaging and handling of large quantities of waste debris and operation of heavy equipment increases the risk of an industrial accident.3.2 Waste Generation The removal of the embedded and buried piping will generate significant quantities of potential radioactive waste. The waste will have to be surveyed and sampled and either staged for backfill, if the material meets the release limits, or packaged and shipped to a waste processor.

An estimated 3,565,100 pounds of potential radioactive waste, including soil, concrete, and steel will be generated during removal of just the Primary Cooling Loop and Quadrant and Canal piping.3.3 Cost The cost of removing the piping is high and far more costly than justified by the Nuclear Regulatory Commission (NRC) $2000/person-rem ALARA standard.The operational phase of removing the Primary Cooling Loop was estimated to consume fifty-nine (59) weeks of schedule duration at an estimated cost of eight million to ten million dollars ($8,000,,000-$10,000,000). The addition of removing the embedded Quadrant and Canal piping would have further increased that cost by approximately one million to one million, two hundred fifty thousand dollars (-$1,000,000-$1,250,000). In total, the estimated costs associated with removing the PBRF's embedded piping systems would have ranged, more or less, from nine million dollars to eleven million, two hundred fifty thousand dollars ($9,000,000- $11,250,000). C-2 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Once the preliminary estimates of costs associated with the removal of the PBRF embedded systems were thoroughly evaluated, it was decided that the more prudent and logical course of action would be that of surveying the embedded piping conduits, decontaminating the same as necessary to either meet the DCGL values or ALARA, and subsequently leave the embedded piping in place. The costs associated with the in-situ decontamination of the embedded Primary Cooling Loop, Quadrant and Canal piping, and some sections of buried piping was estimated to range from two million to four millions dollars ($2,000,000- $4,000,000), depending upon the number of access points that need to be cut into the concrete to gain access to piping through floor traps and piping connected by"Tee"s and mitered elbows.4.0 Embedded Piping versus Buried Piping Embedded piping (EP) is any pipe situated below the minus three (-3) foot elevation that is totally encased in concrete or piping directly beneath building floors that may not be totally encased in concrete, but contained within the structural foundation of the building. 1 Examples include Containment Vessel Quadrant and Canal drain piping and remaining sections of the Primary Cooling Loop. Buried piping is any pipe buried in soil and situated outside the structural foundation of a building, such as storm drains.4.1 Embedded Piping DCGL Values Embedded piping DCGL values were derived by developing a conservative conceptual model of piping layouts based on an extensive review of PBRF drawings and facility walk-downs. The calculations were performed using the dose calculation software MicroShielde. Individual DCGL values were calculated for PBRF gamma-emitting radionuclides observed in PBRF embedded piping surface deposits. The DCGL values represent surface activity concentrations that correspond to an annual dose of one millirem per year (1 mrem/yr) to a future building occupant assuming that an individual occupies the facility and is exposed for 2340 hours per year. The PBRF methodology for determining DCGL values is provided in Sections 5.0 through 8.0. The EP DCGL values are provided in Table C-4.4.2 Buried Piping DCGL Values The DCGL values for buried piping will be the same as the structure DCGL values. Refer to Attachment B of the FSSP.1 The Trojan Decommissioning Project followed a similar approach for disposition of piping that was located beneath structures, but not necessarily embedded in concrete. This piping was inspected, cleaned, surveyed to embedded piping DCGL values and grouted in place after regulatory review and inspection/surveys of selected piping. (See Reference 2.10)C-3 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 5.0 Embedded Piping Conceptual Dose Model The EP configuration that delivers the highest dose to a future building occupant was used in the dose model. This individual is assumed to occupy the walkway between Canal F and the Pump Room at the Reactor Building -25 ft. elevation and is exposed to a group of pipes (a pipe cluster) embedded in the concrete beneath the walkway. Plant drawings were reviewed and inspections performed to confirm that the pipe cluster located beneath the Canal F -Pump Room Walkway represents the most conservative case. That is, this pipe cluster is the highest concentration of embedded pipes to which a future building occupant could be exposed while occupying a single location in the facility. Table C-1 describes the piping layout used in the dose model. Figures C-1 and C-2 provide views of the piping model layout and location of the dose point (one meter above the walkway floor) relative to the piping.Table C-1 Description of Pipe Cluster in Canal F -Pump Room Walkway Piping ID Length Horizontal Offset Pipe CL Pipe Top Surf Run ID Description (in.) ( From Dose Point Depth Depth Below floor CL (ft) (in.) (in.)1.21 Canal H Drain 6 81 1.5 16 13.25 1.23 Canal G Drain 6 42 1.5 16 13.25 1.24 Canal G Purge 3 39 3 16 14.75 1.25 Canal F Drain 6 20 4.5 16 13.25 1.26 Canal F Purge 3 19.5 6 16 14.75 1.641 Canal F&G OF Header (1) 8 25 3 38 34.25 1.81 Canal K Floor Drain 6 25 6 25 22.25 1.82 Canal J & HDS Riser (2) 3 25 4.5 25 23.75 1.83 HDS Floor Drain 4 25 7 38 36.25 Average Dimensions => 5.0 33.5 22.9 20.6 Table C-1 Notes: 1. Overflow Header 2. Hot Drain System Riser A review was conducted to identify other piping configurations that could represent potential exposures comparable to or possibly greater than the 9-pipe cluster described above. Plum Brook Reactor Facility drawings were reviewed and walk-downs conducted to identify locations with potential for exposure to clusters of embedded pipes, which terminate at wall surfaces in areas of the facility that could be occupied. A cluster of 10 pipes that terminate in a pipe trench located in the Reactor Building, -25 foot elevation was identified. During facility operation, these pipes emerged from concrete and were C-4 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 connected to a drain manifold in a trench (Quad & Canal Drains). After shutdown, the exposed piping has been removed and the pipe-ends cut flush with the trench wall. The trench is of such dimensions that an individual could occupy the trench and be exposed to gamma radiation emanating from the pipes (piping end-view exposure geometry). The layout of the conceptual model used to calculate doses from end-view exposure to the former drain manifold piping is shown in Figures C-3 and C-4.6.0 Dose Calculations for 9-Pipe Cluster All dose calculations reported herein were performed using MicroShielde Version 5.04.For the primary DCGL dose calculations, MicroShieldo geometry option 10 was used for the 9-pipe cluster Canal F -Pump Room Walkway model.2 This is a cylindrical surface source with external dose point. The following assumptions were used to establish the MicroShielde case runs and for determination of DCGL values:* The dose receptor (dose point) is located one meter above the walkway floor surface on the longitudinal centerline of the pipe cluster and at a distance midway between the pipe ends.* The 9 pipes lie in parallel runs (parallel to each other and to the floor surface) at the same elevation. Per review of PBRF drawings (References 2.5, 2.6, 2.7, &2.8), the actual pipe centerline depths range from 16 to 38 inches and the average depth is 22.9 inches.* The concrete in which the piping is embedded is modeled as a concrete slab shield (density 2.4 g/cc), 12 in. thick, placed between the top pipe surface and the floor elevation.

• All the pipes are cleaned by vacuuming and pressure blasting or mechanical means to remove loose scale and loosely adherent surface contamination.

The pipes are filled with grout (concrete) with density 1.8 glcc.* The pipes are all assumed to be 25 R. in length. Note that the pipe lengths vary from 19.5 to 81 ft. with average length of 33.5 ft. It is found that the calculated dose is not sensitive to pipe length as the length is increased beyond 20 ft.* The pipe wall is modeled as a 1/4 in. thick (0.65 cm) cylindrical shield. This corresponds to Schedule 40 piping wall thickness for 5 in. piping, the average ID of the 9-pipe cluster. Note that the actual piping is all Schedule 80 (0.95 cm. wall thickness) [Reference 2.5, PF-00375]. 2 The MicroShield code has several standard options for combinations of source and shield configurations. These are called "geometries". The geometry used for the default case, Geometry 10 is suitable for dose-receptor points external to the piping and located at positions that lie between the pipe ends (within the two planes perpendicular to the pipe longitudinal axis).C-5 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0* The "buildup" medium for the MicroShield dose calculations is selected as the grout-filled pipe core.* The model includes a piping corrosion layer surrounding the cylindrical surface source, modeled as "cladding" of 0.025 cm thickness.

• The only exposure pathway that is operative for embedded piping is direct dose from gamma-emitting radionuclides.

All the radionuclides that may be present in piping residual contamination are fixed in place by the grout and are not available for transport to ground water or to ingestion or inhalation pathways to a future building occupant.* This DCGL calculation uses MicroShield case run ou ut dose rates in units of mSv/h (Deep Dose Equivalent Rate). The MicroShield code uses dose conversion factors from ICRP Publication 74, 1997 (Reference 2.9). The output dose rates are then converted to mrem/hr (100 mren/hr per mSv/h).The MicroShield source, dose point coordinates and shield dimensions are summarized in Table C-2.Table C-2 Dose Calculation Model Dimensions Source Dimensions Dose Point Coordinates Shields (cm) (cm) (cm)Pipe Radius X 2) (3) Z(4) Wall Pipe Cnrt Length Clad Wall 762 Pipe- Pipe- 381 Pipe- 0.025 0.65 30.48 (25 f.) specific specific (12.5 ft.) specific (1 ft)Table C-2 Notes: 1. This is the radius in cm. corresponding to each pipe ID.2. The x coordinate is the total distance from the center axis of each pipe to the dose point. This includes the pipe radius, wall clad, pipe wall-shield thickness, the 12 in. concrete slab-shield thickness and the 1-meter distance from floor surface to the dose point (receptor center-height above the floor).3. The y coordinate places the dose point at the center of the pipe lengths.4. The z coordinate is the offset distance from the centerline of each pipe to the pipe cluster centerline (the dose point is located directly above the pipe cluster centerline). The dose from each pipe was calculated individually for seven gamma-emitting radionuclides found to be present in primary cooling water piping in 2005 (Reference 2.2).The dose was calculated for unit activity (one dpm/100-cm 2 or 4.5E-09 glCi/cm 2). The dose to the receptor from each radionuclide is obtained as the sum of the contributions from each C-6 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 piping run in the 9-pipe cluster. The results are shown in Table C-3. The MicroShield9 case run reports are provided in Addendum 1.It is noted that DCGL values for radionuclides that emit only beta particles are not calculated for embedded piping, even though several have been measured in piping deposits. They do not contribute to the dose to future building occupants because the piping that remains in place is filled with grout. However their presence must be accounted for when direct beta surface activity measurements are used for FSS of embedded piping.Table C-3 Calculated Doses from Principal Gamma Emitting Radionuclides Canal F -Pump Room Walkway 9-pipe Cluster Piping mrem/hr per dpm/100-cm 2_lLine No. Co-60 Cs-137 Eu-152 Eu-154 Ag-108m Nb-94 1.21 5.54E-10 3.90E-1l 1.82E-10 2.50E-10 1.11E-10 1.58E-10 1.23 5.54E-10 3.90E-11 1.82E-10 2.50E-10 1.1 E-10 1.58E-10 1.24 1.79E-10 1.08E-11 5.84E-II 8.08E-11 3.13E-11 4.60E-1 l 1.25 8.64E-11 3.60E-12 2.79E-11 3.95E-l1 1.1OE-l1 1.74E-1 1 1.26 1.76E-11 5.33E-13 5.68E-12 8.19E-12 1.71E-12 2.87E-12 1.641 2.90E-10 1.64E-11 9.42E-11 1.31E-10 4.79E-11 7.11E-11 1.81 2.43E-11 7.02E-13 7.87E-12 1.14E-11 2.27E-12 3.83E-12 1.82 6.12E-11 2.70E-12 1.97E-11 2.79E-11 8.16E-12 1.28E-l l 1.83 8.29E-12 1.87E-13 2.71E-12 3.97E-12 6.32E-13 1.1lE-12 Total 1.77E-09 1.l3E-10 5.81E-10 8.03E-10 3.25E-10 4.71E-10 Table C-3 Notes: The dose rates from 1-129 (9.89E-35 mrem/hr), Sn-126 (1.45E-17 mrem/hr) and Eu-155 (4.1OE-16 mrem/hr) were calculated, but are found to be at least 5 orders of magnitude below the dose rates from the other gamma emitting radionuclides. They are of no consequence and are eliminated from further consideration. Embedded Piping DCGL Values To obtain individual radionuclide DCGL values, the dose rate for each radionuclide is converted to annual dose by multiplying by 2340 h/y, the exposure-hours for the occupant in the building occupancy scenario. The DCGL values are then obtained as the 7.0 C-7 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 reciprocal of the annual dose. The results of these calculations are provided in Table C-4.The individual radionuclide DCGL values range from 2.408E05 dpm/100-cm 2 for Co-60 to 3.785E06 dpm/l00-cm 2 for Cs-137. The calculated doses and DCGL values are strongly dependent on the thickness of concrete shielding that surrounds the embedded piping. The concrete typically provides a minimum of 12 to 14 inches of shielding for the piping.Table C-4 Individual Radionuclide DCGL Values for Embedded Piping Annual Dose to DCGL Radionuclide Dose from all Pipes Building Occupant (dpm/100-cm 2 per (mrem/hr)(mrem/yr) mrem/yr)Co-60 1.77E-09 4.17E-06 2.408E+05 Eu- 154 8.03E- 10 1.89E-06 5.325E+05 Eu-152 5.81E-10 1.37E-06 7.352E+05 Nb-94 4.71E-10 1.1 lE-06 9.082E+05 Ag-108m 3.25E-10 7.60E-07 1.312E+06 Cs-137 1.13E-10 2.64E-07 3.785E+06 8.0 Evaluation of Alternative Exposure Scenario The potential dose to a future building occupant was evaluated for the cluster of 10 pipes with pipe-ends terminating at the face of the Reactor Building Pump Room trench. The layout shown in Figures C-3 and C-4 were used to set up the MicroShielde dose calculation model. The piping dose model and assumptions are very similar to the approach followed in calculating dose rates to a future building occupant from the 9-pipe cluster beneath the Canal F -Pump Room walkway. The specific assumptions for this scenario are:* The dose receptor is located one meter above the Pump Room trench floor and one meter from the trench wall where the piping runs terminate. With reference to Figure C-3, the distance from the pipe cluster horizontal centerline to the elevation of the dose point is 67 cm.* The 10 pipes are all horizontal and their centerlines are at an elevation of 13 inches (33 cm.) above the trench floor. The pipe centerline separation distance is 1 ft. 9 inches (53.3 cm.).C-8 Plum Brook Reactor Facility Final Status Survey Plan Revision 0* The pipes are modeled as 10 ft long cylindrical surface sources using MicroShield Geometry 10, Cylinder Surface with external dose point.* The shielding provided by the concrete surrounding each pipe is modeled as a cylindrical annular shield that surrounds the surface source. In MicroShielde, when the external dose point lies outside the space between the ends of a cylindrical source (a pipe), compromises are required. The code does not accommodate more than one cylindrical material surrounding the source. Thus, the concrete replaces the steel pipe wall in the model setup. This is conservative, because the calculated doses would be lower, if the shielding effect of the piping wall could be accounted for.To demonstrate that this exposure scenario does not yield limiting case DCGL values, it is sufficient to show that the dose rate for Co-60 is less than from the Canal F -Pump Room Walkway embedded pipe cluster. This result is shown in Table C-5. It is seen that the calculated dose rate is 3.06E-12 mrem/hr is much less than the Co-60 dose rate obtained from the Walkway floor Co-60 dose rate of 1.77E-09 mrem/hr.Table C-5 Summary of Dose Calculations for Pump Room Trench Occupancy Scenario Dose Point X Dose Point Z Dose Rate Pipe Run No. Pipe ID (in) Dimension Dimension e (cm) (cm) me/r 1.36 10 53.3 0 4.225E-13 1.35 3 62.2 53.3 1.305E-12 1.34 10 53.3 106.6 5.920E-15 1.33 3 62.2 160 8.646E-15 1.32 10 53.3 214 8.157E-19 1.31 3 62.2 266.5 1.113E-17 1.37 3 62.2 53.3 1.305E-12 1.38 10 53.3 106.6 5.920E-15 1.39 3 62.2 160 8.646E-15 1.395 10 53.3 214 8.157E-19 Total 3.06213-12 C-9 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 The MicroShield case-run reports for the Pump Room Pipe Trench cluster are provided in Addendum 2. It is noted that due to the symmetry of the piping layout, it is necessary to calculate the doses for only 6 of the 10 pipes. As shown in Figure C-3, there are four pairs of pipes with identical diameters and separation distance on either side of the cluster centerline. 9.0 Area Factors Area factors provide a method to evaluate localized areas encountered in the Final Status Survey of embedded piping that exceed the DCGL (i.e., the elevated area comparison). A working definition of area factor is the multiple of the DCGL that may be permitted in a localized area of specified dimensions such that the basic dose criterion (25 mrem/yr) is not exceeded. The area factors derived in this attachment are based on several assumptions. They are:* A run of piping is considered to be a survey unit.* The length of piping that contains elevated activity is analogous to the area containing elevated activity in a structural survey unit.* The dose from Co-60 per unit activity in embedded piping exceeds that from any of the other gamma-emitting radionuclides observed in PBRF embedded piping.Thus, area factors that are based on the dose from Co-60 will be conservative. That is, the use of area factors derived on this basis will not result in doses that are greater than the dose criterion regardless of the radionuclide mixture that is present.Area factors are calculated using the conceptual dose model described in Section 5.0 and using the same method for calculating doses as described in Section 6.0. It is seen from the dose calculation results in Table C-4, that most of the dose to the future building occupant is received from four of the 9 pipes- in the pipe cluster, approximately 85%.Therefore, it is a reasonable approximation to calculate the dose delivered from various lengths of these four pipes in the derivation of embedded piping area factors. Area factors are calculated for lengths of 1, 2, 5, and 10 feet. They are obtained as ratios of the dose rate from the four pipes of lengths 1, 2, 5, and 10 feet to the total dose rate from the entire length of all the pipes (1.77E-09 mrem/hr from Co-60).The results of the area factor calculations are presented in Table C-6. Figure C-5 shows area factor versus length of elevated section of piping.3 The MicroShield case run reports for area factors are provided in Addendum 3.3 An additional conservatism in the area factors is from the use of the combined dose from four pipe runs in the calculation. From physical principles, the average dose contribution from a single pipe of the specified lengths could@) be used, rather that the sum of the dose contributions. c-lo Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Table C-6 Embedded Piping Area Factors Total Dose from Pipes Pipe Length (ft) of Specified Length Area Factor (mrem/hr)1 3.013E-10 5.9 2 5.834E-10 3.0 5 1.197E-09 1.5 10 1.531E-09

1.2 Total

dose rate from all EP ..> 17E c-li C m BrookReactor Facility F ,-ctatus Survey Plan Revision 0 Figure C-1 Conceptual Model for Embedded Fping DCGL- Dose Calculation Canal F- Rmp Rbom V\alkway9-Rpe Cluster Cross-section Mew Dose Point 0.1 100 cm Canal F- Rjmp Ibom Wablkway Roor lAverage depth to pipe CLis20.6" Minimum depth to pipettop is 13 in 12 in shielding thicknessasumed forall pipes Une 1.26 Une 1.25 Une 1.24 Une 1.23 ' Une 1.21 Une 1.641 Une 1.82 Une 1.81 Une 1.83 3 in ID 6 in ID 3 in ID 6 in ID 6 in ID 8 in ID 3 in ID 6 in ID 4 in IDl4-1.5 '-*F 1.5 '-*1 31 3' 0- 3'4.5' 4.5'6' 6'7'C-12 ( .m Brook Reactor Facility A", E-f I _Finotatus Survey Plan Revon 0 Figure C-2 Canal F- Pump Fbom -Walkway 9-Rpe Cluster Conceptual Dose Model -Ran View I I-A.J.I a., ..* .-. i-I r.i i : I -.- _ X- x .I I I I I L_iI 7.0', .:.,-I. --a ---.9 -a I a I I.I a, 6.0'6.0'II ;P- ._I I.I .a JI'., 4.0'4.0'-a I I. .J.. I ________ .&_j ; ..* 7 lAJI Rpes 25)ng':a Dos) Fbint 1.5' I 1.5'I'......I..I I aqa -- ..h I I 3.0'.1A-L.....L ______ ibi_, ; * !0 9 8 Rpe diuster CLl ...0 I i: 12.5'I I I I I I_ _ _ _ _I__ _ _ _ _ _ _ _ _ _ _I V Une 1.26 3 in ID;.A.. .Une 1.25 6 in ID LUne 1.24 3 in ID Une 1.23 6 in ID a Une 1.21 6 in ID Une 1.641 8 in ID Une 1.82 3 in ID Une i.81 6 in ID I.O.ai Ure 1.83 4 in ID C-13 f Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Figure C-3 Layout for Dose Model of Fbactor Building Pump Fbom Quad and Canal Drain Manifold Fpe Trench (action View at Trench Wallt showing Rpe-Ends)fEdg Pump Poom Roor-25 ft.Rpe Cluster Center line A Dose'Fbint Anar CL 9 ft A in.b eI-bek ow-25ftel.I I' 1 53.3 cm 62.2 cm IF D -ii -i 1.39 1.37 Rpe CL 3 in ID 3 in ID 1 13 in above floor II 6 67 cm 1.33 3 in ID-o 1.31 3 in ID Trench Roor- 28 ft 7 3/4 in I C-14 A: Plum Brook Reactor Facility (-(-Revision 0 Final Status Survey Plan Figure C-4-Rimp Fbom Quad & Canal Drain Maniold Rpe Trench Conceptual Dose :Model -Ran View I2 AJI Rpes 25 ft I I I I a I* I ,-1', '3:3 a.:* :* I, I* a I. .. .. .r ,.* : a::T 2 2 6. 5 ct 3., .I e.: 14 cm?214 ci rI.:ng i .Ii a...160 cn 160 c I.Ia I a 106.6 cn I.-, , , ,.0* 1 106.6 rn)a. _a ,53.3 cm'I 5 .,53.3 crr 1 .: 1 -.I S* I i .i 'aq:i'I Il.,. ,,, .b.a- -- i a a:- lUne 1.395 10 in ID Line 1.39 3 in ID Une 1.38 10 in ID Une 1.37 Une 1.36 3 in ID 10 in ID UneLi .35 3i 1JJ Une 1.34 10 in ID Line 1.33 3 in ID Line 1.32 10. in ID Line 431 3 in EI Trench North wall Trench SFuth wall Rpe Qluster 100 cm OA 00l 1 4.' 10" Doswe Fbint C-15 f /r I Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Figure C-5 Embedded Piping Area Factors C-16 Final Status Survey Plan For the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment & DCGL Calculation Addendum 1 MicroShield Case Run Reports for Canal F Pump Room Walkway Pipe Cluster PlumBrok Ractr Fciliy FnalStaus urve Pln Rvison.Plum Brook Reactor Facility Final Status Survey Plan Revision O MicroShield Case Run Reports for Canal F -Pump Room Walkway Pipe Cluster Index _ -_ -Run Date Case Title Description File Name Result 12/19/2005 Line 1.21 A2 Revised Model DCGL Cale -Co-60 Unit PB121903 5.54E-10 Act wsched 40 &_12 in shld ____ _____12/21/2005 Line 1.21 B Revised Model Cal& -Cs-137 Unit Act w PB122101 3.90E-1 1 Sched 40 & 12 in conc shield 12/21/2005 Line 1.21 C Revised Model Ca&c -Eu-152 Unit Act w PB122102 .825E-10 Sched 40 & 12 in conc shield P120 llI-12/21/2005 Line 1.21 D Revised ModelCal cEu-54 UnitAct w PB122103 2.50E-10 Sched 40 & 12 in conc shield 12/21/2005 Line 1.21 E Revised Model Calc -Ag- lIOSm Unit Act PB122104 1.1 lE-lO w Sched 40 & 12 in conc shield 12/21/2005 Line 1.21 F Revised Model Calc -Nb-94 Unit Act w PB 122105 1.58E-10 Sched 40 & 12 in conc shield 12/19/2005 Line 1.23 A wSched 40 & 12 in con shield PB122901 2.10E-35 12/41/2006 Line 1.21B Revised Model Calc -Sn-126 Unit Act w PB1221 3.90E-ll 12/21/2005 Line 1.23C HSched 40 & 12 in conc shield PB1221 1.82E-10 12/29/2005 Line 1.21 1 Revised Model Calc -Zr-95 Unit Act w PB122903 6.425E-1 1 Sched 40 & 12 in conc shield 12/29/2005 Line 1.21 E Revised Model Calc -Eu-155 Unit Act PB122904 1.841E-16 w Sched 40 & 12 in conc shield 12/19/2005 Line 1.23 I Revised Model DCGL Calc -Co-60 Unit PB121907 5.54E-10______________ Act w sched 40 &_12 in shld_ _ _ _ _12/21/205 Line1.23 B Revised Model Calc -Cs-137 Unit Act w P120 .0-12/29/2005 Line 1.23J- w Sched 40 & 12 in conc shield PB122106 1.84E-16 12/21/2005 Line 1.23 C Revised Model Ca&c -Eu-152 Unit Act w PB122107 1.82E-10 12/21/2005__ L 2Sched 40 & 12 in conc shield 12/21/2005 Line 1.23 D Revised Model Calc -Eu-154 Unit Act w PB122108 2.84E-10___________Sched 40 & 12 in conc shield 12/21/2005 Line 1.23 E Revised Model Calc -Ag-lO0ni Unit Act PB122109 1.11lE-10 w Sched 40 & 12 in conc shield 12/21/2005 Line 1.23 F Revised Model Calc -Nb-94 Unit Act w PB 1221 1 0 1.58E3-10 Sched. 40 & 12 in conc shield ___________ 12/29/205 Line1.23 G Revised Model Calc 129 Unit Act wPB295 21E3 12_2__ 05_Lie_123_ Sched 40 & 12 in conc shield __B122905 __________ 1/4/2006 Lne 1.23 H Revised Model Calc -Sn-126 Unit Act wPB142 55E8__________ Ln123HSched 40 & 12 in conc shield PBO10402_ __________ 12/29/2005 Line 1.23 I Revised Model Calc -Zr-95 Unit Act w PB 122907 6.421E-1 1____________ ~Sched 40 & 12 in conc shield _ _ _ _ _ _12/29/2005 ine 1.23 ~ Revised Model Calc -Eu-l155 Unit ActPB298 14E1 12________ Ln123 w Sched 40 &_12 in conc shield _B12208_______1 12/19/2005 Line 1.24 A2 Revised Model DCGL Calc -Co-60 Unit PB121909 .1.79E-10_________________ Act wsched 40& 12 inshld 12/21/2005 Line 1.24 B Revised Model Calc -Cs-137 Unit Act W PB1221 11 1.08E3-1 I______ _____ ______ ______ Sched 40 &_12 in conc shield_ _ _ _ _12/21/2005 Line 1.24 C Revised Model Calc -Eu-152 Unit Act w PB3 122112 5.84E-1 1____________ ___________ I Sched 40 & _12 in conc shield _ _ _ _ _ _ _ _ _ _ _Cl-l Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield Case Run Reports for Canal F -Pump Room Walkway Pipe Cluster Index Run Date Case Title Description File Name Result (nmremnlhr) 12/21/2005 Line 1.24 D Revised Model Calc -Eu-154 Unit Act w PB122113 8.08E-1 1 Sched 40 & 12 in conc shield PB1214_313 _1 12/21/2005 ine 1.24 E Revised Model Calc -Ag-lIO0m Unit ActPB214 3.E-1 12/21/2005 Line 1.24 F Sched 40 & 12 in conc shield PB122114 4.6131_I 12/21/2005 Line 1.24 F Revised Model Calc -Nb-94 Unit Act w PB1221915 4.609E-1 12/29/2005__ Lie1.4HSched 40 & 12 in conc shield PB1290_289-1 12/29/2005 Line 1.24 G Revised Model Calc -I-129 Unit Act w PB122909 9.09E-36 Sched 40 & 12 in conc shield 12/29/2005 Line 1.24 H Revised Model Calc -Cn-126 Unit Act w PB122910 2.89E-19 Sched 40 & 12 in conc shield Pl217_279-1 12/29/2005 Line 1.24 1 Revised Model Calc -Zr-95 Unit Act w PB122911 1.83E-11 Sched 40 & 12 in conc shield Revised Model Caic -EU-155 Unit Act w B143 15E1 1/4/2006 Line 1.24J Sched 40 & 12 in conc shield PBO10 1.74E-11 12/19/205 Line1.25A2 Revised Model DCGL Caic -Co-60 UnitPB291 .4-1 12/19/2005 Line 1.25 s sch14 i 12n shid ctw PB122911 1.43E-3 12/21/2005 Line 1.25 B Revised Model Calc -Cs-137 Unit Act w PB122116 3.605E-12 12/29/2005__ Ln15wSched 40 & 12 in conc shield PB296 96E1 12/21/2005 Line 1.25 C Revised Model Calc -Eu-152 Unit Act w PB122117 2.79-E-1 I Sched 40 & 12 in conc shield 12/21/2005 Line 1.25 D Revised Model Cac -Eu-154 Unit Act wPB1221 E-1 12/2l/2005 Line 1.25 D Sched 40 & 12 in conc shield PB122118 8.19E-12 12/21/2005 Line 1.25 E Revised Model Calc -Ag-108mn Unit Act PB122119 1.1OE-11 w SchedL 40 & 12 in conc shield 12/21/2005 Line 1.25 F Revised Model Calc -Nb-94 Unit Act w PB122120 1.74E-1 1 Sched 40 & 12 in conc shield 12/29/2005 Line 1.25 G Revised Model Calc 129 Unit Act w PB122913 I1.43E3-35 ____________ ~Sched 40 & 12 in conc shield _ _ _ _ _ _1/4/2006 Line 1.25 H Revised Model Caic -Sn-126 Unit Act w PBO10404 1 .04E-20 Sched 40 & 12 in conc shield 12/29/205 Line1.25 ~ Revised Model Cabc -Zr-95 Unit Act wPB295 68E1 12_2____05_ Lin 1____25__ ISched 40 & 12 in conc shield P121 .831 12/29/2005 Line 1.25 J Revised Model Calc -Eu- 155- Unit Act PB122916 9.69E-19 w Sched 40 & 12 in conc shield 12/19/2005 Line 1.26 A2 Revised Model Calc' -Co-60 Unit Act w PB121913 1.76E3-1 I___________Sched 40 & 12 in conc shield 12/21/205 Line1.26 B Revised Model Calc -Cs-137 Unit Act wPB211 53E3 12__21_2___ Ln126BSched 40 & 12 in conc shield 1221 53E3 12/21/205 Line1.26 C Revised Model Calc -Eu-152 Unit Act wPB222 58E1 12/212005 ine 126 CSched 40 & 12 in conc shield _B_2122_____1 12/21/205 Line1.26 D Revised Model Calc -Eu-154 Unit Act wPB213 89E2 12/11005 Lie .26D .Sched 40 & 12 in conc shield __B_22123 __________ 12/21/2005 Line 1.26 E Revised Model Calc -Ag-108m Unit Act PB122124 I1.711E-12 w Sched 40 & 12 in conc shield ______12/21/2005 Line 1.26 F Revised Model Calc -Nb-94 Unit Act w PB122125 2.87E3-12 Sched 40 & 12 in conc shield Cl-2 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield Case Run Reports for Canal F -Pump Room Walkway Pipe Cluster Index Run Date Case Title Description File Name (Rem/br)12/29/2005 Line 1.26 G Sched 40 & 12 in conc shield w PB122917 5.78E-36 1/4/2006 Line 1.26 H Revised Model Calc -Sn-126 Unit Act w PBO10405 1.08E3-22 Sched 40 & 12 in conc shield 12/29/2005 Line 1.261 Revised Model Calc -Zr-95 Unit Act w PB122919 1.03E-12 Sched 40 & 12 in conc shield 12/29/2005 Line 1.26 J Revised Model CaIc -Eu-155 Unit Act PB122920 2.04E-20 w Sched 40 & 12 in conc shield 12/19/2005 Line 1.641 A2 Revised Model Calc -Co-60 Unit Act w PB121915 2.90E-10 Sched 40 & 12 in conc shield PB217 94El 12/21/2005 Line 1.641 B Revised Model CaIc -Cs-137 Unit Act w PB122126 1.64E-10 Sched 40 & 12 in conc shield 12/21/2005 Line 1.641F c Revised Model Calc -Eu-152 Unit Act w PB122130 7.1lE-ll 12_2__00__Lie_1_64 CSched 40 & 12 in conc shield __B122127 9_________I 12/21/2005 Line 1.641 D Revised Model Calc -Eu-154 Unit Act w PB122921 2.33E-35 12_2__00__Lie_1_64 DSched 40 & 12 in conc shield __B122128 __________ 12/21/2005 Line 1.641H E Revised Model Calc -Ag-108m Unit Act PB10406 4.9E-19 w Sched 40 & 12 in conc shield 12/21/2005 Line 1.641 F Revised Model Calc -Nb-94 Unit Act w PB122130 7.1 1E-1 1 Sched 40 & 12 in conc shield 12/29/2005 Line 1.641 G Revised Model Calc 129 Unit Act w PB122921 2.33E-35____________ ~Sched 40 &_12 in conc shield _ _ _ _ _ _1/4/2006 Line 1.641 H Revised Model Calc -Sn-126 Unit Act w PB10406 4.960E-19 12/21/2005 LinSched 40 & 12 in conc shield 12/29/2005 Line 1.841E Revised Model Calc -Zr-95 Unit Act WPB12213 2.27E-11 12/21/2005 Line 1.641F I Sched 40 & 12 in conc shield PB12213 3.83-12 12/29/205 Line1.641 J Revised Model Calc -Eu-155 Unit ActPB224 29E1 12/29/2005 Line 1.w1J w Sched 40 & 12 in conc shield PB122924 1.414-35 12/19/205 Line181 A2 Revised Model Calc -Co-60 Unit Act w P111 .3-12/49/2006 Line 1.81H Unit ASched 40 & 12 in conc shield ___PB012197 1.35-22I 12/21/2005 Line 1.81 B Revised Model CaIc -Cs-137 Unit Act w PB122131 7.023E-13 Sched 40 & 12 in conc shield ___________ 12/21/2005 Line 1.81 C Revised Model Calc -Eu-152 Unit Act w PB122132 7.87E-12___________ Sched 40 & 12 in conc shield 12/21/205 Line1.81 D Revised Model Calc -Eu-154 Unit Act w P123 .4-12_2__00__Lie ____ DSched 40 & 12 in conc shield __B122133 __________ 12/21/2005 Line 1.81 E Revised Model Calc -Ag-108m Unit Act PB122134 2.273- 12'_____________ w Sched 40 & 12 in conc shield _ _ _ _ _ _ _ _ _ _ _12/21/205 Line1.81 F Revised Model Calc -Nb-94 Unit Act wPB215 38E2 12/1/00 Lie .8 FSched 40 & 12 in conc shield ___122135 __________ 12/29/2005 Line 1.81 G Revised Model Calc 129 Unit Act w PB122925 1.14E-35____________ ~~~Sched 40 & 12 in conc shield _ _ _ _ _ _ _ _ _ _ _1/4/2006 Line 1.81 H Revised Model Calc -Sn-126 Sb-126) PO00 .532 Unit Act w Sched 40 & 12 in conc shieldPB147 13E2 12/29/2005 Line 1.81. I Revised Model Calc -Zr-95 Unit Act W PB122927 1.37E3-12 Sched 40 & 12 in conc shield _____Cl-3 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield Case Run Reports for Canal F -Pump Room Walkway Pipe Cluster Index Run Date Case Title Description ie Name Result_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ ___ (m ren ifhr)12/29/2005 Line 1.81 J Revised Model Calc -Eu-155 Unit Act PB122928 2.56E-20 12/29/2005 Line L81 J w Sched 40 & 12 in conc shield P122 .632 12/19/2005 Line 1.82 A2 Revised Model Calc -Co-60 Unit Act w PB121919 6.12E-l l Line___1_82 A2 Sched 40 &_12 in cone shield PB12199 _______I 12/21/2005 Line 1.82 B Revised Model Calc -Cs-137 Unit Act w PB122136 2.70E-12 Sched 40 & 12 in cone shield 12/21/2005 Line 1.82 C Revised Model Calc -Eu-152 Unit Act w PB122137 1.97E-1 1 Sched 40 & 12 in cone shield 12/21/2005 Line 1.82 D Revised Model Calc -Eu-154 Unit Act w PB122138 2.79E-1 1___________Sched 40 & 12 in conc shield 12/21/2005 Line 1.82 E Revised Model Calc -Ag-12 Unit Act PB122139 8.16E-12 w Sched 40 & 12 in conc shield wP048 7.1-12/21/2005 Line 1.82 F Revised Model Calc -Nb-94 Unit Act w PB1221 4.8E-11 12__21_2___ Ln182FSched 40 & 12 in conc shield _B1214______ I 12/29/2005 Line 1.82 G Revised Model Calc -I-129 Unit Act w PB122929 7.293E-36___________Sched 40 & 12 in conc shield 1/4/2006 Line 1.82 H Revised Model Calc -Sn-126 Unit Act w PBO10408 7.21E-21 Sched 40 & 12 in conc shield 12/29/2005 Line 1.82 I Revised Model Calc -Zr-95 Unit Act w PB122931 4.87E-12 Sched 40 & 12 in conc shield 0 12/29/2005 Line 1.82 C Revised Model Calc -Eu-155 Unit Act PB122932 7.31E-12 12/29/2005 Line 1.82 J w Sched 40 & 12 in conc shield P123 .131 12/21/2005 Line 1.83 A2 Revised Model Calc -Co-60 Unit Act w PB1221 8.9E-12 1/2/192006 Line 1.83 E_ Sched 40 & 12 in conc shield PB129214 6.32E-13 12/21/2005 Line 1.83 B Revised Model Calc -Cs-137 Unit Act w PB122141 1.871E-13 Sched 40 & 12 in conc shield 12/21/2005 Line 1.83 G Revised Model Calc -Eu-152 Unit Act w PB122933 2.59E-36 12__21_2___ Ln183CSched 40 & 12 in cone shield __122142______1 12/21/2005 Line 1.83 D Revised Model Calc -Eu-154 Unit Act w PB122143 3.97E-12 Sched 40 & 12 in conc shield 1/2/2006 Line 1.83 E RevisedMdel Caic sUnit Act PB122144 6.32E-13 w Sched 40 & 12 in cone shield 12/21/2005 Line 1.83 F Revised Model Calc -Nb-94 Unit Act w PB122145 1.1 1E-12 Sched 40 & 12 in conc shield______ 12/29/2005 ine 1.83 G Revised Model Calc 1 29 Unit Act w P 293 65E3 12/.29_2005_Line_1_8 GSched 40 & 12 in conc shield __12933_____-3 1/4/2006 Line 1.83 H Revised Model Calc -Sn-126 Unit Act W PBO10409 5.32E3-24_____________ Sched 40 & 12 in conc shield _ _ _ _ _12/29/2005 Line ~ Revised Model Calc -Zr-95 Unit Act w P 295 38E1 1.83 Sched 40 & 12 in conc shield 12/29/2005 Line 1.83 J Revised Model Calc -Eu-155 Unit Act PB122936 1.671E-21 w Sched 40 & 12 in conc shield Cl-4 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Pap- : 1 DC ile: PB121903.MS5 Rur te: December 19, 2005 Run Time: 10:34:32 AM Duration: 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 A2

Description:

Revised Model Calc. -Co-60 Unit Act w Sched 40 & 12 in shid Geometry: 10 -Cylinder Surface -External Dose Point Sour Height Radius xr# 1 138.78 cm 4 ft 6.6 in Shield Nme Die Cyl. Core 7.i Shield 1 Transition Shield 3 30.Air Gap Wall Clad .Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels0 4Ci/cm0 Co 60 1.6417e-010 6.0744e+000 4.5000e-009 ce Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields iension Material 52 cm2 Concrete.65 cm Iron Concrete 48 cm Concrete Air D25 cm Iron 25 ft 3.0 in I z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 MeV 0.6938 1.1732¶ 3325 Activity photons/sec 9.909e-04 6.074e+00 6,074e+00 Fluence Rate MeV/cm2/sec No Builcug 3.041e.13 1.656e 08 2.723e-08 Results Fluence Rate MeV/cm2/sec With Buildup 5.389e*12 1.527e-07 2.171e-07 Expoure Rate rnR/hr No Buildup 5.872e-16 2.959e- 11 4.723e-11 Exlosure Rate mR/hr With Buildup 1.040e-14 2.728e-10 3.766e-10 1 ALS: 1.215e+01 4.378e-08 3.697e-07 7.682e-1 1 6.494e.10 Cl-S Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04.00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\M5S\DATA\PB121903.MS5 Case Title: Line 1.21 A2 This case was run on Monday, December 19, 2005 at 10:34:32 AM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Units Without Wyth Buildu Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm2/sec 3.454e-008 4.378e-008 2.930e-007 3.697e-007 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 7.682e-01 1 6.707e-013 6.707e-01 I 6.494e-010 5.670e-012 5.670e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 7.614e-013 6.558e-013 6.558e-013 5.858e-013 6.438e-012 5.542e-012 5.542e-012 4.950e.012 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 8.105e-013 7.804e-013 7.804e-013 6.206e-013 6.854e-012 6.598e-012 6.598e-012 5.246e-012 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 6.856e-013 6.316e-013 5.024e-013 5.687e-013 5.034e-013 5.797e-01 2 5.339e.012 4.244e-012 4.807e-012 4.253e-012 Page 1 Cl-6 Plum BrookReactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122101.MS5 RL ate: December 21, 2005 RuniTime: 1:04:33 PM Duration: 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 B

Description:

Revised Model Calc -Cs-137 Unit Act w Sched 40 & 12 in shid Geometry: 10 -Cylinder Surface -External Dose Point Sour Height Radius-x#1 138.78 cm 4 ft 6.6 in-Shield Name Di Cyl. Core 7.1 Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies curies becauerels IJQi/cmu 1.5531e-010 5.7464e+000 4.2570e-009 1.6417e-010 6.0744e+000 4.5000e-009 ce Dimensions 762.0 cm 7.62 cm lose Points 381 cm 12 ft 6.0 in Shields iension MaU 52 cm 2 Conc 65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 Cw rete Dn Concrete 48 cm Concrete Air 25 cm Iron Nuclide Ba-137m Cs 137 Bq/cnm 1.5751e-004 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 0.0318 0.0322 C' n364 316 A~ctivit photons/sec 1.190e-01 2.195e-01 7.987e-02 5.171e+00 Fluence Rate MeV/cm2/sec No Buildup 8.1 59e-60 4.883e-58 1.780e-45 1 .291e-09 Results Fluence Rate MeV/cm2/sec With Buildup 1.246e-34 2.389e-34 1.33le-34 2.431e-08 Exposure Rafte mRohr No Buildup 6.796e-62 3.930e.60 1.012e-47 2.503e 12 Exposure Rate mR/hr With Buildup 1.038e-36 1.923e-36 7.564e-37 4.713e 11 Cl-7 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pige :2 DOS File : PB122101.MS5 Run Date: December 21, 2005 Run Time: 1:04:33 PM Duration : 00:00:01 Energ Activit MeV. 1hotons/sec FlueneRt MeV/cm/sec No Buildup 1.29le-09 Fluence Rate MeV/cmz/sec With Buildup Exposure Rate mR/hr No Buildup Exposure Rate mR/hr With Buildup TOTALS: 5.589e+00 2.43le-08 2.503e-12 4.713e-I 1 Cl-8 Plum Brook Reactor Facility Final Status SurveyPlan .Revision 0 MicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122101.MS5 Case Title:. Line 1.21 B This case was run on Wednesday, December 21, 2005 at 1:04:33 PM Dose Point # 1 -(138.78,381,45.7) cm 12/21/05 Results (Summed over energies)Without 8uildup With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cmt/sec 1.952e6009 3.674e-008 1.291e-009 2.431e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.503e.012 2.186e.014 2.186e-012 4.713e-011 4.114e-013 4.114e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 1987)mSv/hr (ICRP 51- 1987)mSv/hr (ICRP 51 -1987)mSv/hr 2.588e 014 2.072e-014 2.072e-014 1.832e-014 2.750e-014 2.612e-014 2.612e.014 1.958e-014 2.288e-014 2.020e-014 1.498e.014 1.805e-014 1.536e-014 4.871e-013 3.900e-013 3.900e-013 3.449e.013 5.177e-013 4.917e-013 4.917e-013 3.687e-013 4.307e-013 3.802e-013 2.819e.013 3.397e-013 2.892e-01 3 Page 1 CJ-9 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122102.MS5 RL ate: December 21, 2005 Runri Time: 1:09:19 PM Duration: 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 C

Description:

Revised Model Calc -Eu-152 Unit Act w Sched 40 & 12 in shid Geometry: 10 -Cylinder Surface -External Dose Point r-n -x I Height Radius# 1 138.78 cm 4 ft 6.6 in Shield Name 12 Cyl. Core Shield 1 Transition Shield 3 I Air Gap Wall Clad urce Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12 ft 6.0 in Shields limension Matf 7.62 cm, Conc.65 cm tro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4! 2.4 0.00122 7.86 rete an Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method: Standard Indices Number of Groups : 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library : Grove s becquerels mCi/cm'010 6.0744e+000 4.5000e-OC Nuclide curi Eu- 152 1.6417e-09 1q/cm4 1.6650e 004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy -cv MeV 3.5 4 e+)4 3.594e+00 Fluence Rate MeV/cm2/sec No Buildup 1.418e-36 Results Fluence Rate MeV/cm2lsec With Buildup 8.333e-33 Exposure Rate mR/hr No Buildup 6.272e-39 Exposure Rate mR/hr With Buildup 3.686e-35 cl-Jo Plum Brook Reactor Facility Final Status SurveyPlan .Revision 0_ Page : 2 DOS File: PB122102.MS5 Run Date: December 21, 2005 Run Time: 1:09:19 PM Duration : 00:00:01 Ehe MeV 0.05 0.1 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 Activity photons/sec 8.987e-01 1.727e+00 4.552e-01 1.642e+00 3.817e-01 3.426e-02 2.576e-01 1.082e+00 2.599e+00 1.409e+00 Fluence Rate MeV/cm2/sec No Buildup 3.132e-26 4.074e-15 3.440e-13 1.054e-1 1 9.797e.12 2.465e- 12 4.189e-I 1 6.109e*10 3.719e-09 9.875e-09 Fluence Rate MeV/cm2/sec With Buildup 2.928e-25 2.024e-13 2.243e-1 1 5.126e-10 3.474e-10 6.636e-1 1 8.937e.10 9.029e.09 4.152e-08 6.928e-08 Exposure Rate mR/hr No Buildup 8.342e-29 6.233e-18 6.072e-16 1.999e-14 1.909e-14 4.839e 15 8.176e-14 1.162e-12 6.855e. 12 1.661e-I 1 Exp~osure Rate mR/hr With Buildup 7.801e-28 3.096e- 16 3.959e-14 9.723e- 13 6.769e-13 1.303e-13 1.744e-12 1.717e-11 7.654e-1 1 1.166e-10 TOTALS: 1.408e+01 1.427e.08 1.217e-07 2.476e*1 1 2.138e-10 cl-il Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 licroShlield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122102.MS5 Case Title: Line 1.21 C This case was run on Wednesday, December 21, 2005 at 1:09:19 PM Dose Point # 1 -(138.78,381,45.7) cm 12/21/05 Results (Summed over energies)Units Without Buildup With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cmz/sec

1. 120e.008 1.427e-008 1.033e-007 1.217e-007 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air.mR/hr mGy/hr mrad/hr Deep Dose Equivalent Rate -(ICRP 51 -1987)' -o Parallel Geometry mSv/hr o Opposed o Rotational o Isotropic 2.476e-01 1 2.161e-013 2.161e-011 2.459e-013 2.120e*013 2.120e-013 1.895e-013 2.138e-O10 1.867e-012 1.867eO010 2.131e-012 1.824e-012 1.824e-012 1.628e-012 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 .1987)mSv/hr (ICRP 51 -1987)mSv/hr 2.610e-013 2.517e.013 2.517e.013 2.002e-013 2.212e-013 2.039e-013 1.626e-013 1.837e-013 1.627e-013 2.265e-012 2.180e-012 2.180e-012 1.724e-012 1.914e-012 1.757e.012 1.392e-012 1.582e-012 1.396e-012 Page 2 CI-12 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DOS File : PB122103.MS5 R. 'ate: December 21, 2005 Run rime: 1:12:29 PM Duration: 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 D

Description:

Revised Model Calc -Eu-154 Unit Act w Sched 40 & 12 In shid Geometry: 10 -Cylinder Surface -External Dose Point Height Radius£# 1 138.78 cm 4 ft 6.6 in Shield Name C Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points y 381 cm 12 ft 6.0 in Shields Dimension Mate 7.62 cm2 Conc.65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density! 1.8 7.86 2.4 2.4 0.00122 7.86 riW rete n Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method: Standard Indices Number of Groups : 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library: Grove 2 becquerels uCi/cm 2 010 6.0744e+000 4.5000e-OC Nuclid curies Eu.154 1.6417e-I 09 Bq/cm1 1.6650e 004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activity MeV 2hotons/sec )4 1.236e+00 Fluence Rate MeV/cm4/sec No Buildup 4.878e-37 Results Fluence Rate MleV/crmnLe With Buildup 2.866e-33 Exposure Rate mR/hr No Buildup 2.158e-39 Exposure Rate mrR/h With Buildup 1.268e-35 CI-13 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DOS File: PB122103.MS5 Run Date: December 21, 2005 Run Time: 1:12:29 PM Duration : 00:00:01 MeV 0.05 0.1 0.2 0.4 0.5 0.6 0.8 1.0 1.5 Activity photons/sec 3.140e-01 2.458e+00 4.148e-01 4.334e-02 1.315e-02 4.900e-01 2.369e+00 1.869e+00 2.370e+00 Fluence Rate MeV/cm2/sec No Buildups 1.094e-26 5.798e-15 3.136e- 13 1.112e-12 9.463e- 13 7.968e- 11 1.338e-09 2.674e-09 1.661e.08 Fluence Rate MeV/cM2/sec With Buildu 1.023e-25 2.880e. 13 2.044e 11 3.944e-1 1 2.547e-11 1.700e-09 1.978e-08 2.985e-08 1. 165e-07 Exposure Rate mR/hr No Buildup 2.915e-29 8.871e-18 5.534e.16 2.167e-15 1.857e-15 1.555e-13 2.545e-12 4.929e-12 2.795e-11 Exposure Rate mR/hr With Buildup 2.726e-28 4.406e-16 3.608e.14 7.685e- 14 5.000e.14 3.318e.12 3.761e-11 5.503e-11 1.961e-10 TOTALS: 1.158e+01 2.070e-08 1.679e-07 3.558e.11 2.922e-10 Cl -14 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 icroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122103.MS5 Case Title: Line 1.21 D This case was run on Wednesday, December 21, 2005 at 1:12:29 PM Dose Point # 1 -(138.78,381,45.7) cm 12/21/05 Results (Summed over energies)Units Without Mth Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 1.556e-008 2.070e-008 1.353e- 007 1.679e-007 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 3.558e-011 3.106e-013 3.106e-011 2.922e.010 2.55le-012 2.55le-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 .1987)mSv/hr (ICRP 51 .1987)mSv/hr (ICRP 51 -1987)mSv/hr 3.528e*013 3.053e.013 3.053e*013 2.733e-013 3.741e*013 3.613e-013 3.613e*013 2.883e-013 3.176e-013 2.934e-013 2.351e-013 2.646e-013 2.349e-013 N 2.906e-012 2.499e-012 2.499e-012 2.233e-012 3.085e.012 2.974e-012 2.974e-012 2.361e.012 2.612e-012 2.405e*012 1.915e-012 2.167e-012 1.916e.012 Page 1 Cl-15 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShleld v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122104.MS5 Rt *ate: December 21, 2005 Rurn rime: 1:21:22 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 E

Description:

Revised Model Calc- Ag-108m Unit Act w Sched 40 & 12 in shl Geometry: 10 -Cylinder Surface -External Dose Point V~-X Height Radius X# 1 138.78 crr 4 ft 6.6 ir Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad I I urce Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 Source Input Grouping Method: Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library: Grove as becguerels mCi/cm, B-010 6.0744e+000 4.5000e-0 Dimension Material 7.62 cm- Concrete.65 cm Iron Concrete 30.48 cm Concrete Air.025 cm Iron I09 1.6650e-004 Nuclide Ag-108m 1.6417i Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ener MeVy)2 Activiy Fluence Rate hotonssec MeV/cm21/sec No Buildup 3.984e+00 3.590e- 187 Results Fluence Rate MeV/cm2/sec With Buildup 1.575e-33 Exposure Rate mR/h1 No Buildup 1.244e 188 Exposure Rate mR/hr With Buildup 5.457e-35 Cl-16 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision O i_ Page :2 DOS File : PB122104.MS5 Run Date: December 21, 2005 Run Time: 1:21:22 PM Duration : 00:00:01 Eneca 0.03 0.08 0.4 0.6 0.8 Activity photons/sec 1.290e-06 4.305e-01 5.460e+00 5.491e+00 5.497e+00 Fluence Rate MeV/cm2/sec Nlo Buildup 3.735e-73 2.032e 17 1.401e-10 8.929e-10 3.105e-09 Fluence Rate MeV/cm2/sec With Buildup 1.128e-39 6.656e-16 4.969e-09 1.905e-08 4.589e.08 Exp~osure Rate mR/hr No Buildup 3.702e-75 3.216e-20 2.730e-13 1.743e*12 5.906e-12 Exposure Rate mR/hr With Buildup 1.118e.41 1.053e.18 9.681e-12 3.719e-1 1 8.729e-1 1 TOTALS: 2.086e+01 4.138e.09 6.991e-08 7.922e- 12 1.342e-10 Cl-17 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 licroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122104.MS5 Case Title: Line 1.21 E This case was run on Wednesday, December 21, 2005 at 1:21:22 PM Dose Point # 1 -(138.78,381,45.7) cm 12/21/05 Results (Summed over energies)UnAit a uildu With BQuiUld Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm2/sec MeV/cm 2/sec 5.720e-009 4.138e-009 1.015e-007 6.991e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 7.922e-012 6.916e-014 6.916e-012 1.342e-010 1.17le-012 1.171e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 8.125e-014 6.590e-014 6.590e-014 5.826e-014 8.661e-014 8.249e-014 8.249e-014 6.233e-014 7.214e.014 6.419e-014 4.818e-014 5.739e-014 4.914e.014 1.382e-012 1.114e-012 1.114e-012 9.850e-013 1.470e-012 1.399e-012 1.399e-012 1.054e.012 1.225e-012 1.087e-012 8.119e-013 9.708e-013 8.297e-013 Page 1 C1-18 Plum Brook Reactor Facility Final Status Survey Plan .I Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122105.MS5 RL ate: December 21, 2005 Run Time: 1:23:24 PM Duration :00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 F

Description:

Revised Model Calc- Nb-94 Unit Act w Sched 40 & 12 in shl Geometry: 10 -Cylinder Surface -External Dose Point, Soul I .a.Height Radius#1 138.78 cm 4 ft 6.6 in Shiel Name Dirr Cyl. Core 7.Shield 1 Transition Shield 3 30 Air Gap Wall Clad .Source Input Grouping Method: Actual Photon Energies Nuclide curies becguerels ujCi/cm 2 Nb-94 1.6417e-010 6.0744e+000 4.5000e-009 rce Dimensions 762.0 cm 7.62 cm)ose Points Y 381 cm 12 ft 6.0 in Shields 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in lension Material Density 62 cm 2 Concrete 1.8.65 cm Iron 7.86 Concrete 2.4.48 cm Concrete 2.4 Air 0.00122 025 cm Iron 7.86 Bq1cm4 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ener MwY 0.0174 0.0175 0.0196 0 7026 711 Activity photons/see 2.148e-03 4.115e-03 1.209e-03 6.074e+00 6.074e+00 Fluence Rate MeV/cm2/sec No Buildup 2.567e-278 1.690e-273 3.203e-201 1.969e-09 4.910e-09 Results Fluence Rate MeV/cm2/sec With Buildup 6.819e-37 1.319e-36 4.633e-37 3.433e.08 6.513e 08 Exposure Rate mR/hr No Buildup 1.386e-279 8.951e-275

1. 182e-202 3.797e-12 9.241e.12 Exposure Rate mR/hr With Buildup 3.68le 38 6.984e-38 1.710e-38 6.621e 11 1.226e- 10 CJ-19 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File: PB122105.MS5 Run Date: December 21, 2005 Run Time: 1:23:24 PM Duration : 00:00:01 Exergy Activity MeV photons/sec Fluence Rate MeV/cmTl/se No Buildup Fluence Rate MeVtcm 2/sec With Buildup Exposure Rate mnRBhr Exiposure Rate mR/hr With Buildup TOTALS: 1.216e+01 6.879e-09 9.946e-08 1.304e.1 1 1.888e.10 Cl-20 Plum Brook Reactor Facility Final Status Survey Plan = Revision 0 icroShield v5.04 (5.04-00362) 12/21/0!MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122105.MS5 Case Title: Line 1.21 F This case was run on Wednesday, December 21, 2005 at 1:23:24 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Unit1 Without Buidu WiLth Buidu Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm2/sec MeV/cm 2/sec 8.439e-009 6.879e-009 1.236e-007 9.946e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.304e-01 1 1.138e-013 1.138e-011 1.888e-010 1.648e-012 1.648e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 .1987)mSv/hr (ICRP 51 .1987)mSv/hr (ICRP 51 1987)mSv/hr 1.325e-013 1.090e-013 1.090e-013 9.639e-014 1.416e-013 1.35le-013 1.351e*013 1.031e.013 1.181e-013 1.059e-013 8.040e.014 9.477e-014 8.163e-014 1.920e-012 1.577e-012 1.577e-012 1.395e-012 2.052e-012 1.958e-012 1.958e-012 1.492e-012 1.710e.012 1.532e.012 1.162e-012 1.37le-012 1.180e-012 Page 3 Cl-21 Plum Brook Reactor Facility .Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc. 7 Page : 1 DOS File: PB122901.MS5 RL ate: December 29, 2005 Run fime: 2:03:16 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 G

Description:

Revised Model Calc- 1-129 Unit Act w Sched 40 & 12 in shl Geometry: 10- Cylinder Surface -External Dose Point V;?.-Ii- I.1I Sour Height Radius x#1 138.78 cm 4 ft 6.6 in Shield Name Qir Cyl. Core 7.Shield 1 Transition Shield 3 30.Air Gap Wall Clad .Source Input Grouping Method : Actual Photon Energies curies becquerels pCi/cm 2 1.6417e-010 6.0744e+000 4.5000e-009 rce Dimensions 762.0 cm 7.62 cm)ose Points y 381 cm 12 ft 6.0 in Shields iension Material 62 cm 2 Concrete.65 cm Iron Concrete.48 cm Concrete Air 125 cm Iron Bq/cm1 1.6650e-004 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 uclide 1-129 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Edn MBV 0.0295 0.0298 0.0336 0 0396 Activity photons/sec 1.212e+00 2.249e+00 7.995e-01 4.568e-01 Fluence Rate MeV/cm2/sec No Buildup 4.389e-70 4.520e-68 2.067e-52 3.486e-38 Results Fluence Rate MeV/cm"/sec With Buildup 1.007e-33 1.925e-33 1.005e-33 1.022e-33 Exposure Rate mR/hr No Buildup 4.593e-72 4.579e-70 1.471e-54 1.584e-40 Exposure Rate mR/hr With Buildup 1.054e-35 1.951e-35 7.150e-36 4.643e-36 CJ-22 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File: PB122901.MS5 Run Date: December 29, 2005 Run Time: 2:03:16 PM Duration : 00:00:01 Ene MeV Activit photons/sec Fluence Rate MeV/cmz/sec No Buildup 3.486e-38 Fluence Rate MeV/cm2/sec With Buildup 4.959e-33 ExQosure Rate mR/hr No Buildup2 1.584e 40 Ex~osure Rate mRbhr With Buildup 4.184e-35 TOTALS: 4.718e+00 Cl-23 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShlield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\M5S\DATA\PB122901.MS5 Case Title: Line 1.21 G This case was run on Thursday, December 29, 2005 at 2:03:16 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies!Unlits Without With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 8.807e-037 1.546e-031 3.486e-038 4.959e.033 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.584e-040 1.383e-042 1.383e-040

4. 184e-035 3.652e-037 3.652e-035 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 1 .979e*042 9.969e-043 9.026e-043 8.635e-043 4.181e.037 2.097e-037 1.789e-037 1.662e-037 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 1.991e-042 1.375e-042 1.375e-042 1.009e-042 4.557e-037 3.134e-037 3.134e-037 2.316e-037 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 1987)mSv/hr 1. 154e.042 6.976e-043 3.854e-043 6.273e-043 5.142e-043 1 .875e-037 9.692e-038 5.23le-038 9.630e-038 7.979e.038 Page 1 C1-24 P Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 Dos File: PBO10401.MS5 Ru ate: January 4, 2006 Run Time: 7:40:17 AM Duration : 00:00:01 File Ref: _ _Date: _By: Checked: Case Title: Line 1.21 H-Description: Revised Model Calc- Sn-126 Unit Act w Sched 40 & 12 in shid Geometry: 10 -Cylinder Surface- External Dose Point 1 I x Height Radius X# 1 138.78 cm 4 ft 6.6 in Shield Name C CyL. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points 381 cm.12 ft 6.0 in Shields Dimension. Mate, 7.62 cm 2 Conci.65 cm Iroi 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in 1.8 7.86 2.4 2.4 0.00122 7.86 drall'ete n Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library : Grove E WCi/cm 2 010 6.0744e+000 4.5000e-OC Nuclide ur Sn-126 1.6417e-09 10/cm 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ene Me0.02 Activity photo n s/se c 4.702b-01 Fluence Rate MeV/cm2/sec No Buildup 4.237e- 188 Results Fluence Rate MeV/cm2/sec With Buildup 1.859e-34 Exposure Rate mR/hr No Buildup 1.468e 189 Exposure Rate mR/hr'With Buildup 6.440e-36 Cl-25 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File: PB010401.MS5 Run Date: January 4, 2006 Run Time: 7:40:17 AM Duration : 00:00:01£nerfy 0.03 0.04 0.06 0.08 Activity photons/sec 1.779e+00 3.034e.02 5.821e-01 2.789e+00 Fluence Rate MeV/cmL/sec No Buildup 5.151e-67 1.197e-38 1.833e-21 1.317e 16 Fluence Rate MeV/cm2/sec With Buildup 1.555e-33 7.035e-35 3.14le*20 4.313e-15 Exposure Rate mR/hr No Buildup 5.105e-69 5.295e-41 3.640e-24 2.084e- 19 Exposure Rate mR/hr With Buildu 1.541e-35 3.111e.37 6.240e-23 6.825e 18 TOTALS: 5.650e+00 1.317e-16 4.313e- 15 2.084e-19 6.825e- 18 Cl-26 Plum Brook Reactor Facility Final Status SurveyPlan _ Revision 0 MicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PBO10401.MS5 Case Title: Line 1.21 H This case was run on Wednesday, January 4, 2006 at 7:40:17 AM Dose Point # 1 -(138.78,381,45.7) cm 01/04/0 With Buildup Results (Summed over energies)Units Without Buildupn Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 1.646e-015 1.317e-016 5.391e-014 4.313e-015 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.084e-019 I1.819e-021 1.819e-019 6.825e-018 5.958e-020 5.958e-018 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 3.182e-021 1.695e-021 1.647e-021 1.636e-021 3.153e 021 2.317e.021 2.317e-021 1.701e-021 1.042e-019 5.551e-020 5.395e-020 5.357e-020 1.033e-019 7.589e-020 7.589e-020 5.570e-020 (ICRP 51 -1987)mSv/hr Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51

• 1987)mSv/hr 2.673e.021 2.039e-021 1.256e-021 1.736e-021 1.404e-021 8.753e-020 6.676e*020 4.115e-020 5.687e-020 4.600e-020 Page: Cl-27 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DCO File : PB122903.MS5 Ru-sate: December 29, 2005 Run Time: 2:10:45 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.21 1

Description:

Revised Model Calc- Zr-95 Unit Act w Sched 40 & 12 In shid Geometry: 10 -Cylinder Surface -External Dose Point Sour z Height Radius x#1- 138.78 cm 4 ft 6.6 in Shield Name Dim Cyl. Core 7.E Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies curies becquerell wCi/cm 1.6417e-010 6.0744e+000 4.5000e-009 ce Dimensions 762.0 cm 7.62 cm lose Points Y 381 cm 12 ft 6.0 in Shields 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in iension Material Densit 52 cm 2 Concrete 1.8 65 cm Iron 7.86 Concrete 2.4 48 cm Concrete 2.4 Air 0.00122 25 cm Iron 7.86 1.6650e-004 Nuclide Zr-95 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy 0.7242 0.7567 Activity photons/sec 2.652e+00 3.362e+00 Fluence Rate MeV/cm-/sec No Buildup 9.792e-10 1.499e-09 Results With Buildup 1.643e-08 2.378e-08 Exposure Rate mR/hr No BuilduI2 1.883e-12 2.869e-12 Exposure Rate mR/hr-With Buildup 3.159e-11 4.551e-1 1 T'TALS: 6.014e+00 2.478e-09 4.020e-08 4.751e-12 7.709e-11 Cl-28 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicrcShield vS.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122903.MS5 Case Title: Line 1.21 1 This case was run on Thursday, December 29, 2005 at 2:10:45 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Without Buldup 3.333e-009 2.478e-009 Wih Buildup 5.410e-008 4.020e-008 Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm t/sec MeV/cm 2/sec Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 4.751e-012 4.148e-014 4.148e-012 7.709e-01 1 6.730e-013 6.730e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51

• 1987)mSv/hr (ICRP 51 -1987)mSv/hr 4.862e-014 3.954e-014 3.954e-014 3.495e-014 5.191e-014 4.947e-014 4.947e-014 3.740e-014 4.319e-014 3.846e-014 2.892e-014 3.440e-014 2.947e-014 7.890e-013 6.416e-013 6.416e-013 5.671e-013 8.423e-013 8.026e-013 8.026e-013 6.069e-013 7.007e-013 6.241e-013 4.692e-013 5.582e-013 4.782e-013 Page 1 CJ-29 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DOS File: PB122904.MS5 Ru ate: December 29, 2005 Run-firme: 2:13:27 PM Duration: 00:00:01 File Ref: _Date: By: Checked: Case Title: Line 1.21 J

Description:

Revised Model Calc- Eu-155 Unit Act w Sched 40 & 12 in shid Geometry: 10 -Cylinder Surface -External Dose Point IZ Height Radius X# 1 138.78 cm 4 ft 6.6 in Shield Name [)'Cyl. Core Shield 1 Transition Shield 3 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields Dimension Mait 7.62 cmz Conca.65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in (lensity 1.8-7.86 2.4 2.4 0.00122 7.86 rete n Concrete 10.48 cm Concrete Air.025 cm Iron Source Input Grouping Method: Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove becqauerels uCi/cm 2 210 6.0744e+000 4.5000e-OC Nuclide curies Eu.155 1.6417e-I 109 B1/cm6 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Erg Activiy a3 photons/sec )3 1.933e-02 Fluence Rate MeV/cm2/sec No Buildup;5.599e-69 Results Fluence Rate MeV/cm2/sec With Buildup 1.690e-35 Exposure Rate mR/hr No Buildup 5.549e-71 Exposure Rate mR/hr With Buildup 1.675e-37 Cl-30 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File: PB122904.MS5 Run Date: December 29, 2005 Run Time: 2:13:27 PM Duration : 00:00:01 MeY 0.04 0.05 0.06 0.08 0.1 TOTALS: ActivitY photons/sec 1.lOle+00 3.581e-01 7.878e-02 1.886e+00 1.256e+00 4.699e+00 Fluence Rate MeV/cm2/sec No Buildup 4.345e 37 1.248e-26 2.480e-22 8.905e-17 2.962e-15 3.051e-15 Fluence Rate MeV/cm2/sec With Buildup 2.553e-33 1.167e-25 4.251e-21 2.917e-15 1.471eK13 1.501e*13 Exposure Rate mR/hr No Buildup'1.922e-39 3.324e-29 4.926e-25 1.409e-19 4.532e-18 4.673e-18 Exposure -Rate mR/hr With Buildup 1. 129e-35 3.109e-28 8.444e-24 4.615e-18 2.251e.16 2.297e- 16 Cl-31 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122904.MS5 Case Title: Line 1.21 J This case was run on Thursday, December 29, 2005 at 2:13:27 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Without 3.074e-014 3.05le*015 With 1.508e-012 1.50le.013 Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm t/sec MeV/cm 2/sec Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 4.673e-018 4.079e-020 4.079e-018 2.297e-016 2.006e-018 2.006e-016 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 6.827e*020 3.740e.020 3.737e-020 3.619e-020 3.355e-018 1.839e-018 1.838e-018 1.779e-018 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 6.782e-020 5.254e-020 5.254e.020 3.826e-020 3.333e-018 2.583e-018 2.583e-018 1.88le-018 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 5.865e-020 4.595e-020 2.836e-020 3.925e-020 3.124e-020 2.883e-018 2.259e-018 1.394e-018 1.930e-018 1.535e-018 Page 1 Cl-32 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShleld v5.04 (5.04.00362) Radiological Services, Inc.Palm : 1 Dt. ile : PB121907.MS5 Rur te: December 19, 2005 Run rime: 10:58:55 AM Duration: 00:00:01 File Ref: Date: I By: Checked: Case Title: Line 1.23 A2

Description:

Revised Model Calc. -Co-60 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Height Radius Source Dimensions 762.0 cm 7.62 cm 25 ft 3.0 in# 1 138.78cm 4 ft 6.6 in Dose Points Y 381 cm 12 ft 6.0 in z 45.7 cm 1 ft 6.0 in a Shields Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Dimension Material Density 7.62 cm2 Concrete 1.8.65 cm Iron 7.86 Concrete 2.4 30.48 cm Concrete 2.4 Air 0.00122.025 cm Iron 7.86 jes Bq/cm2 09 1.6650e-004 Source Input Grouping Method : Actual Photon Energ Nuclide curies becquerels UCi/CM2 Co-60 1.6417e-010 6.0744e+000 4.5000e-01 Buildup The material reference Is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ene MeVn 0.6938 1.1732' 3325 T kLS: Activity photo ns/ sec 9.909e-04 6.074e+00 6.074e+00 1.215e+01 Flueoce Rate M eWVcm2/ sec No Buildup 3.04le 13 1.656e-08 2.723e.08 4.378e.08 Results Fluence Rae MeV/cm2/sec With Buildup 5.389e.12 1.527e.07 2.171e-07 3.697e.07 Exposure Rate mR/hr No Buildup 5.872e.16 2.959e 11 4.723e1 1I 7.682e-1 1 Exgosure Rate mR/hr With Buildup 1.040e.14 2.728e- 10 3.766e.10 6.494e- 10 I Cl-33 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB121907.MS5 Case Title: Line 1.23 A2 This case was run on Monday, December 19, 2005 at 10:58:55 AM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Units Without With Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 3.454e-008 4.378e-008 2.930e-007 3.697e-007 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 7.682e-011 6.707e-013 6.707e-011 6.494e-010 5.670e-012 5.670e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 7.614e-013 6.558e-013 6.558e-013 5.858e-013 6.438e-012 5.542e-012 5.542e-012 4.950e-012 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 8.105e-013 7.804e-013 7.804e-013 6.206e-013 6.854e-012 6.598e-012 6.598e-012 5.246e-012 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 6.856e-013 6.316e-013 5.024e-013 5.687e-013 5.034e-013 5.797e-012 5.339e-012 4.244e-012 4.807e-012 4.253e-012 Page 1 Cl-34 Plum Brook Reactor Facility Final Status Survey Plan ..Revision 0 MicroShleld v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122106.MS5 RL ate: December 21, 2005 Run-rime: 1:29:02 PM Duration : 00:00:01 File Ref: Date: __ _By: Checked: Case Title: Line 1.23 B

Description:

Revised Model Calc -Cs-137 Unit Act w Sched 40 & 12 in ShId Geometry: 10 -Cylinder Surface -External Dose Point 41"N Height Radius# 1 138.78 cm 4 ft 6.6 in ource Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields Dimension Mate 7.62 cm 2 Conc.65 cm Iro I 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86.Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad I rete n Concrete 30.48 cm Concrete Air.025 cm Iron Nuclide Ba-137m Cs-137 Source Input Grouping Method : Actual Photon Energies curies .becquerels. w~i/cm2 1.5531e-010 5.7464e+000 4.2570e-009 1.6417e-010 .6.0744e+000 4.5000e-009 Bq/cm2 1.5751e-004 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activity Mey photons/sec 0.0318 0.0322 0.0364 316 1.190e-01 2.195e-01 7.987e-02 5.171e+00 Fluence Rate MeV/cmi/sec No Buildup 8.1 59e-60 4.883e-58 1.780e.45 1.291e-09 Results Fluence Rate MeV/cm2/sec With Buildup 1.246e-34 2.389e-34 1.331e-34 2.431e-08 Exposure Rate mR/hr No Buildup 6.796e-62 3.930e-60 1.012e-47 2.503e-12 Exp~osure Rate mR/hr With Buildup 1.038e-36 1.923e-36 7.564e-37 4.713e-11 Cl-35 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 Page :2 DOS File: PB122106.MS5 Run. Date: December 21, 2005 Run Time: 1:29:02 PM Duration: 00:00:01 jgergy MeV Activit photons/sec Fluence Rate MeV/cm2/sec Fluence Rate MeV/CM2/sec With Buildup Exposure Rate mR/hr No Buildup Exposure Rate mR/hr With Buildu 4.713e-11 TOTALS: 5.589e+00 1.291e-09 2.431e-08 2.503e-12 Cl-36 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122106.MS5 Case Title: Line 1.23 B This case was run on Wednesday, December 21, 2005 at 1:29:02 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Units Without With BuilduP Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm?/sec MeV/cm 2/sec 1.952e-009 3.674e-008 1.291e-009 2.431e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.503e*012 2.186e-014 2.186e-012 4.713e-011 4.114e-013 4.114e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 .1987)mSv/hr (ICRP 51 -1987)mSv/hr.2.588e.014 2.072e-014 2.072e-014 1 .832e-014 2,750e.014 2.612e-014 2.612e*014 1 .958e-014 2.288e.014 2.020e.014 1.498e.014 1.805e-014 1.536e-014 4.871e-013 3.900e- 013 3.900e-013 3.449e-013 5.177c-013 4.917e-013 4.917e-013 3.687e-013 4.307e-013 3.802e-013 2.819e-013 3.397e-013 2.892e.013 Page 1 C1-37 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122107.MS5 R. ate: December 21, 2005 Runr rime: 1:30:33 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 C

Description:

Revised Model Calc -Eu-152 Unit Act w Sched 40 & 12 in Shid Geometry: 10- Cylinder Surface -External Dose Point Height Radius A# 1 138.78 cm 4 ft 6.6 in Shield Name I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad iurce Dimensions 762.0 cm 7.62 cm Dose Points y 381 cm 12 ft 6.0 in Shields Dmension Mate 7.62 cm 2 Conci.65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86'ete n Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove i becquerels Ci/cm 10 6.0744e+000 4.5000e-OC curies Eu-152 1.6417e-I 09 Bqlcm2 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Energy Activity MeV photons/sec )4 3.594e+00 Fluence Rate MeV/cm2/sec No Buildup 1.418e 36 Results Fluence Rate MeV/cm2/sec With Buiidup2 8.333e-33 Exposure Rate mR/hr No Buildup 6.272e-39 Expsure Rate mR/hr.With Buildup 3.686e-35 C1-38 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 11~ DOS File: PB122107.MS5 Run Date: December 21, 2005 Run Time: 1:30:33 PM Duration : 00:00:01.ergy MeV 0.05 0.1 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 Activit photons/sec 8.987e-01 1.727e+00 4.552e-01 1.642e+00 3.817e-01 3.426e.02 2.576e-01 1.082e+00 2.599e+00 1.409e+00 Fluence Rate MeV/cm2/sec No Buildup 3.132e-26 4.074e-15 3.440e-13 1.054e- 11 9.797e- 12 2.465e.12 4.189e-1 1 6.109e-10 3.719e-09 9.875e-09 Fluen~ce Rate MeV/cm-'/sec With Buiidup 2.928e-25 2.024e- 13 2.243e- 11 5.126e-10 3.474e- 10 6.636e-1 1 8.937e- 10 9.029e.09 4.152e-08 6.928e.08 1.217e-07 Exposure Rate mR/hr No Buildup 8.342e-29 6.233e- 18 6.072e-16 1.999e.14 1.909e-14 4.839e-15 8.176e-14 1.162e-12 6.855e-12 1.661e-11 mR/hr With Buildu 7.801e-28 3.096e. 16 3.959e- 14 9.723e 13 6.769e- 13 1.303e 13 1.744e 12 1.717e-11 7.654e-1 1 1.166e-10 TOTALS: 1.408e+01 1.427e-08 2.476e-I 1 2.138e-10 Cl-39 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MiicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MSS\DATA\PB122107.MS5 Case Title: Line 1.23 C This case was run on Wednesday, December 21, 2005 at 1:30:33 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Without Bu&ilduI2 1. 120e-008 1 .427e*008 Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm2/sec 1.033e-007 1.217e-007 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.476e-011 2.161e-013 2.161e-011 2.138e -010 1.867e-012 1.867e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.459e-013 2.120e-013 2.120e-013 1 .895e-013 2.13le-012 1.824e-012 1.824e.012 1.628e-012 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.610e-013 2.517e-013 2.517e-013 2.002e-013 2.265e-012 2.180e-012 2.180e-012 1.724e-012 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.212e.013 2.039e-013 1.626e-013 1.837e-013 1.627e-013 1.914e-012 1.757e-012 1.392e-012 1.582e-012 1.396e-012 Page 1 Cl-40 ---Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122108.MS5 RL "ate: December 21, 2005 Rui, ime: 1:32:17 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 D

Description:

Revised Model Calc -Eu-154 Unit Act w Sched 40 & 12 in ShId Geometry: 10 -Cylinder Surface -External Dose Point I Height Radius# 1 138.78 cm 4 ft 6.6 in Shield Name D Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad iurce Dimensions 762.0 cm 25 ft 7.62 cm 3.0 in Dose Points Y z 381 cm 45.7 cm 12 ft 6.0 in I ft 6.0 in Shields timension Material Density 7.62 cm 2 Concrete 1.8.65 cm Iron 7.86 Concrete 2.4 30.48 cm Concrete 2.4 Air 0.00122.025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove bicquerels jpCi/cm 2 010 6.0744e+000 4.5000e-OC Nuclide Eu-154 curies 1.6417e-09 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activity Fluence Rate MeY photons/sec MeV/cm2/sc No Buildup 04 1.236e+00 4.878e-37 Results Fluence Rate MeV/cm2/sec With Buildu 2.866e-33 Exposure Rate mR/h1 No Builduwp 2.158e-39 Exposure Rate 1nR/hr With Buildup.1.268e-35 CJ-41 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2_%WV DOS File: PB122108.MS5 Run Date: December 21, 2005 Run Time: 1:32:17 PM Duration : 00:00:01 tnergy MeVY 0.05 0.1 0.2 0.4 0.5 0.6 0.8 1.0 1.5 Activity toQns/sec 3.140e-01 2.458e+00 4.148e-01 4.334e-02 1.315e-02 4.900e-01 2.369e+00 1.869e+00 2.370e+00 Fluence Rate MeV/cM2/5eg No Buildup 1.094e-26 5.798e- 15 3.136e-13 1.112e-12 9.463e-13 7.968e-11 1.338e-09 2.674e-09 1 .661e-08 Fluence Rate M6V/c~m-/sec With Buildup 1.023e-25 2.880e.13 2.044e- 11 3.944e- 11 2.547e-1 1 1.700e-09 1.978e-08 2.985e.08 1.165e-07 Exposure Rate mR/hr No Buildup 2.915e-29 8.871e-.18 5.534e-16 2.167e-15 1.857e-15 1.555e-13 2.545e-12 4.929e-12 2.795e- 11 Exposure Rate mR/hr With Buildup 2.726e-28 4.406e- 16 3.608e- 14 7.685e-14 5.000e-14 3.318e-12 3.761e-11 5.503e- 11 1.961e-10 TOTALS: 1.158e+01 2.070e.08 1.679e-07 3.558e-1 1 2.922e-10 Cl-42 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122108.MS5 Case Title: Line 1.23 D This case was run on Wednesday, December 21, 2005 at 1:32:17 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies!Units Without With Buildup2 Photon Fluence Rate (flux)Photon Energy Fluence Rate Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air Photons/cm 2/sec MeV/cm 2/sec 1.556e-008 2.070e.008 1.353e -007 1.679e-007 mR/hr mGy/hr mrad/hr 3.558e-01 1 3.106e-013 3.106e-01 1 2.922e-010 2.55le.012 2.55le.010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 3.528e-013 3.053e.013 3.053e*013 2.733e-013 2.906e-012 .2.499e.012 2.499e*012 2.233e-012 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 3.741e-013 3.613e-013 3.613e*013 2.883e-013 3.085e.O1 2 2.974e*012 2.974e.012 2.36le-012 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 3.176e.013 2.934e-013 2.35le-013 2.646e-013 2.349e-013 2.612e-012 2.405e.012 1 .915e.012 2.167e-012 1.916e.012 Page 1 CJ-43 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122109.MS5 Ru ate: December 21, 2005 Run- rime: 1:33:55 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 E

Description:

Revised Model Calc -Ag-108m Unit Act w Sched 40 & 12 in Shl Geometry: 10 -Cylinder Surface -External Dose Point'7, Height Radius X# 1 138.78 cm 4 ft 6.6 in Shield Name D Cyl. Core Shield 1 Transition Shield 3 3 Air Gap Wall Clad iurce Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields 7.62 cm 2 Conc.65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in!Density 1.8 7.86 2.4 2.4 0.00122 7.86 2: niaI rete n Concrete 10.48 cm Concrete Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons c 0.015: Excluded Library : Grove es becguerels pCi/cm'e-010 6.0744e+000 4.5000e-0 Nuclide =cj Ag-108m 1.6417 I09 Bq/cm6 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activity MeV photons8sec 32 3.984e+00 Fluence Rate MeVLcm2/sec No Buildu 3.590e- 187 Results Fluence Rate 1Me cm7 sec With Buildup 1.575e-33 Exposure Rate mR/hr No Buildup 1.244e-188 Exposure Rate mRjhr With Buildu 5.457e-35 Cl-44 Plum Brook Reactor Facility Final Status Survey Plan .-Revision 0 Page : 2 DOS File : PB122109.MS5 Run Date: December 21, 2005 Run Time: 1:33:55 PM Duration : 00:00:01 0.03 0.08 0.4 0.6 0.8 Activity photons/sec 1.290e-06 4.305e-01 5.460e+00 5.491e+00 5.497e+00 Fluence Rate MeV/cm2/sec No Buildup 3.735e-73 2.032e-17 1.401e-10 8.929e 10 3.105e-09 Fluence Rate MeV/cm2/sec With Buildup 1.128e-39 6.656e- 16 4.969e-09 1.905e-08 4.589e.08 Exposure Rate mR/hr No Buildu 3.702e-75 3.216e-20 2.730e.13 1.743e 12 5.906e-12 Exposure Rate mR/hr With Buildup 1.118e-41 1.053e-18 9.681e.12 3.719e-11 8.729e-11 TOTALS: 2.086e+01 4.138e-09 6.991e-08 7.922e-12 1.342e.10 C1-45 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 VlicroShield v5.04 (5.04-00362) 12/21/0!MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122109.MS5 Case Title: Line 1.23 E This case was run on Wednesday, December 21, 2005 at 1:33:55 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over eneriies)Units Without Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 5.720e-009 4.138e-009 1.015e-007 6.991e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 7.922e*Q12 6.916e*014 6.916e*012 1.342e-010 1.17le-012 1.171e 010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr (ICRP 51 1987)mSv/hr 0 8.125e-014 6.590e*014 6.590e-014 5.826e.014 8.661e.014 8.249e-014 8.249e-014 6.233e-014 7.214e-014 6.419e*014 4.818e-014 5.739e-014 4.914e-014 1.382e.012 1.114e*012 1.114e*012 9.850e.013 1.470e-012 1.399e-012 1.399e-012 1.054e-012 1.225e-012 1.087e*012 8.119e-013 9.708e-013 8.297e-013 Page: CI Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04.00362) Radiological Services, Inc.Page : 1 DO File: PB122110.MS5 Ru ate: December 21, 2005 RunrTime: 1:35:45 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 F

Description:

Revised Model Caic- Nb-94 Unit Act w Sched 40 & 12 in Shl Geometry: 10 -Cylinder Surface -External Dose Point Soul p Height Radius I= x#1 138.78 cm 4 ft 6.6 in Shield Name Din Cyl. Core 7.i Shield 1 Transition Shield 3 30.Air Gap Wall Clad .Source Input Grouping Method : Actual Photon Energies Nuclide curebecquerels nji Nb-94 1.6417e.010 6.0744e+000 4.5000e-009 rce Dimensions 762.0 cm 7.62 cm)ose Points Y 381 cm 12 ft 6.0 in 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Shields lension Material Density 62 cm 2 Concrete 1.8.65 cm Iron 7.86 Concrete 2.4 48 cm Concrete 2.4 Air 0.00122 125 cm Iron 7.86 B1/cm6 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 0.0174 0.0175 0.0196 0 7026 711 Activity photons/sec 2.148e-03 4.115e.03 1.209e.03 6.074e+00 6.074e+00 Fluence Rate MeV/cm/sec No Buildup 2.567e-278 1.690e-273 3.203e-201 1.969e-09 4.910e-09 Results Fluence Rate MeV/cm-'/sec With Buildup 6.819e-37 1.319e-36' 4.633e-37 3.433e-08 6.513e.08 Exposure Rate mR/hr No Buildup 1.386e-279 8.951e-275

1. 182e.202 3.797e-12 9.241e-12 Exposure Rate mR/hr With Buildup 3.681e-38 6.984e-38 1.710e-38 6.621e-1 1 1.226e- 10 CJ-47 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 1Page : 2 DOS File: PB122110.MS5 Run Date: December 21, 2005 Run Time: 1:35:45 PM Duration : 00:00:01 MeV 2hotons/sec Fluence Rate MeV/cmL'/sec No Buildup Fluence Rate MeV/cml/sec With BuilduI2 Emsure Rate rnR/hr No Buildue2 Exmosure Rate mR/hr With Buildup TOTALS: 1.216e+01 6.879e-09 9.946e-08 1.304e-11 1.888e-10 CI-48 Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShleld v5.04 (5.04-00362)

Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122110.MS5 Case Title: Line 1.23 F This case was run on Wednesday, December 21, 2005 at 1:35:45 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Without With BuilduI2 Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 8.439e.009 1.236e-007 6.879e.009 9.946e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.304e-011 1.138e.013 1.138e-011 1,888e-010 1.648e-012 1.648e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 1.325e-013 1.090e-013 1.090e-013 9.639e-014 1.416e.013 1.351e-013 1.35le-013 1.031e-013 1.920e-012 1.577e-012 1.577e*012 1.395e-012 2.052e-012 1.958e-012 1.958e-012 1.492e-012 (ICRP 51 -1987)mSv/hr.1.181e-013 1.059e-013 8.040e-014 9.477e-014 8.163e-014 1.710e.012 1 .532e*012 1.162e*012 1.37le-012 1.180e.012 Page 1 CI-49 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122905.MS5 RL. ate: December 29, 2005 Rur-Time: 2:22:38 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 G

Description:

Revised Model Calc 129 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Soul Height Radius.-x X#1 138.78 cm 4 ft 6.6 in Cyl. Core 7.Shield 1 Transition Shield 3 30 Air Gap Wall Clad X Source Input Grouping Method : Actual Photon Energies Nuclide c becquerels pCi/cm'1129 1.6417e-010 6.0744e+000 4.5000e-009 rce Dimensions 762.0 cm 7.62 cm)ose Points Y 381 cm 12 ft 6.0 in Shields nension Material 62 cm 2 Concrete.65 cm Iron Concrete.48 cm Concrete Air)25 cm Iron B1/cm6 1.6650e-004 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activity MeV photons/sec 0.0295 0.0298 0.0336 0 0396 1 .212e+00 2.249e+00 7.995e-01 4.568e-01 Fluence Rate MeV/cm2/sec No Buildup 4.389e-70 4.520e-68 2.067e-52 3.486e-38 Results Fluence Rate MeV/cm2/sec With BuiiduD 1.007e-33 1.925e-33 1.005e-33 1.022e-33 Exposure Rate mR/hr No Buildup 4.593e.72 4.579e-70 1.471e-54 1.584e.40 Exposure Rate mR/hr With Buildup2 1.054e-35 1.951e-35 7.150e-36 4.643e-36 Cl-SO Plum Brook Reactor Facility Final Status Survey Plan Revision 0 vo Page -:2 DOS File : PB122905.MS5 Run Date: December 29, 2005 Run Time: 2:22:38 PM Duration : 00:00:01 Energy Activity MTTS photons/sec+ TOTALS: 4.718e+00 Fluence Rate MeV/cm2/sec No Buildup 3.486e-38 Fluence Rate MeV/cm2/sec With Buildup 4.959e-33 Exposure Rate mR/hr 1.584e-40 Exposure Rate mERr With Buildup 4.184e-35 Cl-51 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 M-croShield v5.04 (5.04-00362) MicroShield v5.04 (5.0400362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122905.MS5 Case Title: Line 1.23 G This case was run on Thursday, December 29, 2005 at 2:22:38 PM Dose Point # 1 -(138.78,381,45.7) cm 12/29/05 Results (Summed over energies)Units Without with Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm2/sec MeV/cm 2/sec 8.807e-037 3.486e-038 1.546e-031 4.959e-033 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.584e-040 1.383e-042 1.383e*040 4.184e-035 3.652e-037 3.652e-035 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.979e-042 9.969e-043 9.026e.043 8.635e-043 4.181e-037 2.097e-037 1.789e-037 1.662e.037 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 1.991e-042 1.375e-042 1.375e-042 1 00g9e.042 4.557e-037 3.134e.037 3.134e-037 2.316e.037 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.154e-042 6.976e-043 3.854e.043 6.273e-043 5.142e.043 1.875e-037 9.692e-038 5.231e.038 9.630e.038 7.979e-038 Page 1 Cl-52 Plum Brook Reactor Facilit Final Status Survey Plan .Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB010402.MS5 Rt )ate: January 4, 2006 Run Time: 7-55:14 AM Duration: 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 H

Description:

Revised Model Calc -Sn-126 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point z Height Radius X# 1 138.78 cm 4 ft 6.6 in Shield Name .2 Cyl. Core Shield 1 Transition Shield 3 I Air Gap Wall Clad urce Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12 ft 6.0 in Shields Dimension Mate 7.62 cm 2 Conc.65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 hiat rete n Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library : Grove becguereis WCi/cm 2 010 6.0744e+000 4.5000e-001 Nuclide Sn-126 1.6417e-I Bq/cm 2 1.6650e.004 -- --- --Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activit WeV photons/sec 32 4.702e-01 Fluence Rate MeV/cm2/sec No Buildup 4.237e-188 Results Fluence Rate MeV/cm2/sec With Buildup 1.859e-34 xposure Rate mrR/h No Buildup 1.468e-189 Exposure Rate, mR/hr With Buildup 6.440e.36 CI-53 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File: PB010402.MS5 Run Date: January 4, 2006 Run Time: 7:55:14 AM Duration: 00:00:01 0.03 0.04 0.06 0.08 Activit ph oto n s/sec 1.779e+00 3.034e-02 5.821e-01 2.789e+00 Flugnce Rate MeV/cml/sec No Buildup 5.151e-67 1.197e-38 1.833e-21 1.317e-16 Fluence Rate MeV/cm2/sec W&ith Buildup 1.555e-33 7.035e-35 3.14!e-20 4.313e-15 Expo~sure Rate mR/hr No Buildup 5.105e-69 5.295e-41 3.640e-24 2.084e- 19 Exposure Rate mR/hr With Buildup 1.541e-35 3.111e-37 6.240e-23 6.825e- 18 TOTALS: 5.650e+00 1.317e-16 4.313e-15 2.084e- 19 6.825e- 18 Cl-54 Plum BrookReactorFacility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362) 01/04/06 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB010402.MS5 Case Title: Line 1.23 H This case was run on Wednesday, January 4, 2006 at 7:55:14 AM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies)Unit Without With Buildug Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm2/sec MeV/cm-/sec 1.646e-015 1.317e-016 5.39le.014 4.313e-015 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.084e-019 1.819e-021 1.819e-019 6.825e.018 5.958e-020 5.958e.018 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 3.182e.021 1.695e-021 1.647e-021 1.636e.021 1.042e.019 5.55le-020 5.395e.020 5.357e.020 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51

• 1987)mSv/hr (ICRP 51 -1987)mSv/hr 3.153e.021 2.317e.021 2.317e-021 1.701e-021 2.673e-021 2.039e-021 1.256e-021 1.736e-021 1.404e-021 1.033e-019 7.589e-020 7.589e-020 5.570e-020 8.753e-020 6.676e-020 4.115e-020 5.687e-020 4.600e-020 Page 1 C-s55 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DOS File: PB122907.MS5 RL ate: December 29, 2005 Run-Time: 2:27:29 PM Duration : 00:00:01 File Ref: Date: By: Checked: _ _Case Title: Line 1.23 1

Description:

Revised Model Calc -Zr-95 Unit Act w Sched 40 & 12 In Shid Geometry: 10 -Cylinder Surface -External Dose Point Height.Radius X# 1 138.78 cm 4 ft 6.6 in iurce Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12ft 6.0 in 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in S Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Shields Dimension Material Density 7.62 cm 2 Concrete 1.8.65 cm Iron 7.86 Concrete 2.4 30.48 cm Concrete 2.4 Air 0.00122.025 cm Iron 7.86 Yies 9 Bq/cme)09 1.6650e-004 Source Input Grouping Method : Actual Photon Enerj becguerels mciL/m, 1.6417e.010 6.0744e+000 4.5000e-0 Nuclide Zr-95 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Me 0.7242 0.7567 Activity 2.652e+00 3.362e+00 Fluence Rate MeV/cm,/sec No Buildup2 9.792e-10 1.499e-09 Results FluenceRate MeV/cm2/sec With Buildup 1.643e-08 2.378e-08 Exposure Rate mR/hr No Buildup 1.883e-12 2.869e-12 Exposure Rate mR/hr With Buildu 3.159e 11 4.551e-11 TOTALS: 6.014e+00 2.478e-09 4.020e-08 4.751e.12 7.709e-I 1 Cl-56 Plum Brook Reactor Facility Final Status Survev Plan .Revision 0 Pm B k R c F l S s S y Pn R MicroShield v5.04 (5.04-00362) 12/29/05 MicroShleld v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122907.MS5 Case Title: Line 1.23 1 This case was run on Thursday, December 29, 2005 at 2:27:29 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies) Units Without Buildup With Buildup~Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cmz/sec MeV/cm2/sec 3.333e.009 5.410e*008 2.478e.009 4.020e*008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 4.751e-012 4.148e-014 4.148e 012 7.709e-011 6.730e.013 6.730e-01 1 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 4.862e-014 3.954e-014 3.954e.O014 3.495e-014 5.19le-014 4.947e-014 4.947e-014 3.740e-014 7.890e-013 6.416e-013 6.416e-013 5.671e.013 8.423e-013 8.026e-013 8.026e- 013 6.069e-013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 1987)mSv/hr 4.319e.014 3.846e.014 2.892e.014 3.440e-014 2.947e-014 7.007e-013 6.241e-013 4.692e-013 5.582e-013 4.782e-013 Page 1 Cl-57 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 IDOS File : PB122908.MS5 Rt late: December 29, 2005 Runr rime: 2:29:31 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.23 J

Description:

Revised Model Calc -Eu-155 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point 1. 4- .X Height Radius# 1 138.78 cm 4ft6.6 in Shield Name I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12 ft 6.0 in Shields Dmension Male 7.62 cm 2 Conci.65 cm Iro 25 ft 3.0 in z 45.7 cm 1 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 rial rete n Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015 : Excluded Library: Grove i becquerels pCi/cm 2 010 6.0744e+000 4.5000e-OC Nuclide Eu 155 1.6417e-09 Bq/cm 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Acivity MO9 photons/sec )3 1.933e-02 Fluence Rate MeV/cm2/sec N~o BuilduD 5.599e-69 Results Fluence Rate MeV/cm1/sec With Buildup 1.690e-35 Exposure Rate mR/hr No Buildup 5.549e-71 Exposure Rate mR/hr With Buildup 1.675e-37 Cl-58 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 kw~ DOS File PB122908.MS5 Run Date: December 29, 2005 Run Time: 2:29:31 PM Duration: 00:00:01 0.04 0.05 0.06 0.08 0.1 Activitv photons/sec 1.lOle+00 3.581e-01 7.878e-02 1.886e+00 1.256e+00 Fluence Rate MeV/cm2/sec No Buildup2 4.345e-37 1.248e-26 2.480e-22 8.905e-17 2.962e-15 Fluence Rate MeV/cm 2/sec With Buildup 2.553e-33 1.167e.25 4.251e-21 2.917e-15 1.471e- 13 Exposure Rate mR/hr No Buildup2 1.922e-39 3.324e-29 4.926e-25 1.409e-19 4.532e-18 Expos~ure Rate mR/hr With Buildug 1.129e-35 3.109e-28 8.444e-24 4.615e 18 2.25le-16 TOTALS: 4.699e+00 3.051e.15 1.501e.13 4.673e-18 2.297e- 16 Cl-59 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122908.MS5 Case Title: Line 1.23 J This case was run on Thursday, December 29, 2005 at 2:29:31 PM Dose Point # 1 -(138.78,381,45.7) cm Results (Summed over energies!Units WB~uidI Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cmz/sec MeV/cm2/sec 3.074e-014 3.05le-015 1.508e-012 1.501e-013 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 4.673e*018 4.079e-020 4.079e*018 2.297e.016 2.006e.018 2.006e.016 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 6.827e-020 3.740e.020 3.737e-020 3.619e-020 3.355e-018 1.839e-018 1.838e-018 1.779e-018 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 6.782e*020 5.254e.020 5.254e.020 3.826e-020 3.333e-018 2.583e-018 2.583e-018 1.881e-018 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 5.865e-020 4.595e-020 2.836e-020 3.925e-020 3.124e-020 2.883e-018 2.259e-018 1.394e-018 1.930e-018 1.535e-018 Page 1 Cl-60 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Pare : 1 D( ile : PB121909.MS5 Rue te: December 19, 2005 Run-,ime: 11:05:13AM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 A2

Description:

Revised Model Calc. -Co-60 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Sour Height Radius[#1 134.97 cm 4ft 5.1 in Shield Name Dia Cyl. Core 3J Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies curies becquerels 4 0i0cm0 8.2087e-01 1 3.0372e+000 4.5000e-009 rce Dimensions 762.0 cm 3.81 cm)ose Points 381 cm 12 ft 6.0 in Shields iension Mate.1 cm 2 Conct.65 cm Iroi 25ft 1.5 in z 91.44 cm 3ft 1.8 7.86 2.4 2.4 0.00122 7.86 rial:ete Concrete.48 cm Concrete Air 125 cm Iron Nuclide Cow60 Bq/cm 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential .20 Energy Activity MeV 12hotons/sec Fluence Rate MeV/cm2/sec No Buildup 7.277e-14 4.717e-09 8.038e-09 Results Fluence Rate MeV/cmLsec With Buildup 1.510e-12 4.857e-08 7.095e.08 Exposure Rate No Buildup 1.405e-16 8.429e. 12 1.395e-l 1 Exposure Rate LmR/h With Buildup 2.916e-15 8.679e 11 1.231e-10 0.6938 1.1732 1 3325 4.954e-04 3.037e+00 3.037e+00 T kLS: 6.075e+00 1.275e-08 1. 195e-07 2.237e- 11 2.099e-10 Cl-61 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MSS\DATA\PB121909.MS5 Case Title: Line 1.24 A2 This case was run on Monday, December 19, 2005 at 11:05:13 AM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over energies)Wthout Buildup Photon Fluence Rate (flux)-Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 1.005e.008 1.275e-008 9.464e-008 1.195e-007 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.237e-01,1 1.953e-013 1.953e-01 1 2.099e-010 1.832e-012 1.832e-010 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.217e-013 1.910e-013 1.910e-013 1.706e-013 2.080e-012 1.79le.012 1.79le-012 1 .600e-012 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 .1987)mSv/hr 2.360e- 013 2.273e-013 2.273e-013 1.808e-013 1.997e-013 1.840e.013 1.463e013 1.657e-013 1.466e.013 2.215e-012 2.132e-012 2.132e-012 1.695e-012 1.873e-012 1.725e-012 1.372e-012 1.554e-012 1.375e-012 -Page 1 CJ-62 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122111.MS5 Ru te: December 21, 2005 Run- time: 1:45:09 PM Duration: 00:00:01 File Ref: Date: _By: Checked: Case Title: Line 1.24 B

Description:

Revised Model Calc. -Cs-137 Unit Act w Sched 40 & 12 in Shl.Geometry: 10 -Cylinder Surface -External Dose Point Source Dimensions Height 762.0 cm Radius 3.81 cm z11# 1 134.97 cm 4 ft 5.1 in Shield Name I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Dose Points Y 381 cm 12 ft 6.0 in Shields Dimension Mat 3.81 cm 2 Con(.65 cm Ir 25 ft 1.5 in z 91.44 cm 3ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 erial:rete ton-x Concrete 30.48 cm Concrete Air.025 cm Iron Nuclid Ba-137m Cs- 137 Source Input Grouping Method : Actual Photon Energies curies becquerels wCi/cm 7.7654e-011 2.8732e+000 4.2570e-009 8.2087e-01 1 3.0372e+000 4.5000e-009 Bg/cm 1.5751e-004 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ener Mey 0.0318 0.0322 0 n364 i16 Activity photons/sec 5.948e-02 1.097e-01 3.994e-02 2.585e+00 Fluence Rate MeV/cmz/sec Nlo Buildup 1.933e-65 1.659e-63 1.318e-49 3.035e-10 Results Flece Rate MeV/,cm2/sec With Buildup 5.403e-35 1.036e-34 5.773e-35 6.721e-09 Exposure Rate mR/hr Nlo Buildup 1.610e-67 1.335e-65 7.489e-52 5.884e-13 Exposure Rate mR/hr With Buildup 4.500e-37 8.337e-37 3.280e-37 1.303e-11 C1-63 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File : PB122111.MS5 Run Date: December 21, 2005 Run Time: 1:45:09 PM Duration : 00:00:01.MOL Activit photons/sec Fluence Rate MeV/cm-'/sec No Buildup Fluence Rate MeV/cm2/sec With Buildup Exposure Rate mR/hr No Buildup ExPosurg mWiB h~B~u , Rate itdup TOTALS: 2.794e+00 3.035e- 10 6.721e-09 5.884e- 13 1.303e 11 Cl-64 Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 MicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.0400362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MI5\DATA\PB122111.MS5 Case Title: Line 1.24 B This case was run on Wednesday, December 21, 2005 at 1:45:09 PM Dose Point # 1 -(134.97,381,91.44) cm 12/21/05 Results (Summed over energies)Without.with Bul~duM Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 4.587e-010 3.035e-010 1.016e.008 6.72le*009 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 5.884e-013 5.137e-015 5.137e-013 1.303e-01 1 1.137e-013 1.137e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 6.082e-015 4.869e*015 4.869e*015 4.306e-015 6.464e-015 6.139e-015 6.139e-015 4.603e-015 1.347e.013 1.078e-013 1.078e.013 9.534e-014 I1 4316-013 1.359e-013 1.359e-013 1 .019e-013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 5.378e-0 15 4.747e.015 3.520e-015 4.242e*015 3.61le-015 1.19le-013 1.05le-013 7.794e-014 9.392e-014 7.996e-014 Page 1_I Cl-65 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DO" File : PB122112.MS5 RL te: December 21, 2005 Run ime: 1:48:57 PM Duration :00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 C

Description:

Revised Model Caic. -Eu-152 Unit Act w Sched 40 & 12 in Shl Geometry: 10 -Cylinder Surface -External Dose Point I X Height Radius Source Dimensions 762.0 cm 3.81 cm 25 ft 1.5 in Nuclid1 Eu-152# 1 134.97 cr 4 ft 5.1 i Shield Name Cyl. Core Shield 1-Transition Shield 3 Air Gap Wall Clad Dose Points Y n 381 cm n 12 ft 6.0 in Shields Dimension Mlat 3.81 cm 2 Conc.65 cm irc tria crete on z 91.44 cm 3ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library : Grove i becquerels UCi/cm 011 3.0372e+000 4.5000e-OC 8.2087e-09 Bq/c6m6 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Atiitb MeV 1hoton7/sec )4 1.797e+00-Fluence Rate MeV/cm25sec No Buildup 5.750e-40 Results Fluence Rate MeV/cml/sec With Buildup 3.614e.33 Exposure Rate mR/hr No Buildup 2.543e-42 Exposure Rate mR/hr With Buildup 1.598e-35 Cl-66 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File : PB122112.MS5 Run Date: December 21, 2005 Run Time: 1:48:57 PM Durztion : 00:00:01 Energv Activity MeV photonstsec 0.05 4.493e-01 0.1 8.635e-01 0.2 2.276e-01 0.3 8.212e.01 0.4 1.909e-01 0.5 1.713e-02 0.6 1.288e-01 0.8 5.408e-01 1.0 1.300e+00 1.5 7.046e-01 Fluence Rate MeV/cm2/sec No Buildup 1 .622e-28 2.796e-16 4.533e.14 1.744e.12 1.864e-12 5.178e.13 9.480e-12 1.539e-10 1.009e-09 3.006e-09 Fluence Rate MeV/cm2/sec With Buildup 1.584e-27 1.693e-14 3.792e- 12 1.067e.10 8.121e 11 1.678e 11 2.399e- 10 2.629e-09 1.275e-08 2.317e-08 Exposure Rate mR/hr No Buildup 4.320e-31 4.278e- 19 8.00le-17 3.309e- 15 3.632e-15 1.016e-15 1.850e- 14 2.927e-13 1.860e. 12 5.058e- 12 Eggosure Rate mR/hr With Buildup 4.220e.30 2.591e-17 6.693e-15 2.025e- 13 1.582e- 13 3.293e- 14 4.682e- 13 5.00le-12 2.350e-11 3.898e- 11 TOTALS: 7.040e+00 4.183e-09 3.899e-08 7.238e-12 6.835e- 11 CJ-67 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/0!MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122112.MS5 Case Title: Line 1.24 C This case was run on Wednesday, December 21, 2005 at 1:48:57 PM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over energies!Ulnd Wiibhout.Bildup WJlih Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 3.233e-009 4.183e-009 3.249e-008 3.899e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 7.238e.012 6.319e.014 6.319e-012 6.835e-011 5.967e-013 5.967e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr (ICRP 51 -1987)mSv/hr 7.183e-014 6.201e-014 6.201e-014 5.545e-014 7.624e-014 7.355e-014 7.355e-014 5.858e-014 6.805e-013 5.835e*013 5.835e.013 5.209e-013 7.232e.O1 3 6.963e-013 6.963e-013 5.515e-013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 6.464e-014 5.963e-014 4.764e-014 5.375e-014 4.764e-014 6.116e-013 5.620e-013 4.458e-013 5.060e-013 4.468e-013 Page: CJ-68 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File : PB122113.MS5 RL te: December 21, 2005 Run ,ime: 1:50:31 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 D

Description:

Revised Model Calc. -Eu-154 Unit Act w Sched 40 & 12 in Shl Geometry: 10 -Cylinder Surface -External Dose Point Height Radius Source Dimensions 762.0 cm 3.81 cm 25ft 1.5 in# 1 134.97 cr 4 ft 5.1 i Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Dose Points Y Tn 381 cm n 12 ft 6.0 in Shields Dimension Mat 3.81 cm 2 Conc.65 cm Irc Conc 30.48 cm Conc reial crete on-rete ,rete z 91.44 cm 3ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 z Air.025 cm Iron Source Input Grouping Method: Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015: Excluded Library : Grove i btecquerel u m)11 3.0372e+000 4.5000eOC Nuclide Eu 154 8.2087e-(09 BQ/cm6 1.6650e 004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy Activit MeOY phbotons/s .)4 6.181e-01 Fluence Rate MeV/cm2/sec No Buildup 1.978e-40 Results Fluence Rae MeV/cm"/sec With Buildup 1.243e-33 Exposure Rate mR/hr No Buildup 8.748e-43 Exposure Rate mR/hr With Buildup 5.497e-36 CJ-69 Plum Brook Reactor Facility Final Status Survey Plan. Revision 0*4/ Page : 2 DOS File : PB122113.MSS Run Date: December 21, 2005 Run Time: 1:50:31 PM Duration ; 00:00:01 En&MeV 0.05 0.1 0.2 0.4 0.5 0.6 0.8 1.0 1.5 Activit photons/sec 1.570e-01 1.229e+00 2.074e-01 2.167e602 6.576e-03 2,450e-01 1.184e+00 9.343e-01 1. 185e+00 Fluence Rate MeV/cm2/sec No Buildup 5.666e-29 3.980e-16 4.131e-14 2.117e-13 1.988e-13 1.803e 11 3.371e-10 7.256e-10 5.057e-09 Fluence Rate MeV/cm2/sec With Buildup 5.536e-28 2.410e-14 3.456e-12 9.220e-12 6.440e- 12 4.563e-10 5.759e.09 9.166e-09 3.897e-08 Exoosure Rate mR/hr No Buildup 1.509e-31 6.089e-19 7.292e-17 4.124e-16 3.901e-16 3.519e-14 6.41 le-13 1.337e-12 8.508e-12 Exposure Rate mR/hr With Buildup 1.475e-30 3.687e-17 6.099e- 15 1.796e-14 1.264e-14 8.906e-13 1.095e-11 1.690e-11 6.557e-11 TOTALS: 5.789e+00 6.138e-09 5.437e-08 1.052e-11 9.434e-11 CI-70 Plum Brook Reactor Facility Final Status Survey Plan, Revision 0 licroShield v5.04 (5.04-00362) 12/21/0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122113.MS5 Case Title: Line 1.24 D This case was run on Wednesday, December 21, 2005 at 1:50:31 PM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over energies)Units Without Buidu Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 4.549e.009 6.138e-009 4.316e.008 5.437e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.052e-01 1 9.186e-014 9.186e-012 9.434e-011 8.236e-013 8.236e-01 1 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 1987)mSv/hr (ICRP 51 .1987)mSv/hr 1.043eO013 9.036e 014 9.036e-014 8.090e-014 1.106e-013 1.068e-013 1.068e-013 8.533e-014 9.389e.014 8.680e-014 6.966e-014 7.83le-014 6.957e- 014 9.376e-013 8.075e-013 8.075e-013 7.218e-013 9.952e-013 9.598e-013 9.598e-013 7.628e-013 8.432eO013 7.767e-013 6.193e-013 7.00le-013 6.197e-013 Page CI-71 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122114.MS5 Ru ate: December 21, 2005 Runr rime: 2:10:25 PM Duration : 00:00:01 File Ref: Date: By: Checked: -Case Title: Line 1.24 E

Description:

Revised Model Calc Ag-108m Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point 4 X Height Radius Source Dimensions 762.0 cm 3.81 cm 25 ft 1.5 in A# 1 134.97 cr 4 ft 5.1 I Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Dose Points n 381 cm n 12 ft 6.0 in Shields Dimension Mat 3.81 cm 2 Conc.65 cm Irc Kria1:rete on z 91.44 cm 3ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 z Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method: Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library: Grove as uCi/cm2 c-011 3.0372e+000 4.5000e-01 Nuclide cud, Ag-108m 8.2087o)9 Bq/Cm2 1 .6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) -20 Circumferential 20 Ener Activit 2Y photons/sec

)2 1.992e+00 Fluence Rate MeV/cm2/sec 1.913e 206 Results Fluence Rate MeV/cm2/sec With Buildup 6.831e-34 Exposure Rat mR/hr No Buildup 6.626e-208 Exposure Rate.3mR/h With Buildup2 2.366e-35 Cl-72 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File : PB122114.MS5 Run Date: December 21, 2005 Run Time: 2:10:25 PM Duration:

00:00:01 Energ MeY 0.03 0.08 0.4 0.6 0.8 Activity photons/sec 6.449e.07 2.152e-01 2.730e+00 2.745e+00 2.749e+00 Fluence Rate MeV/cm2/sec No Buildup 1.192e-79 9.096e-19 2.666e-1 1 2.021e-10 7.822e.10 Fiuence Rate:MeV/cm2/sec With Builldu 4.890e.40 3.469e- 17 1.161e-09 5.113e-09 1.336e-08 Exp~osure Rate mR/hr No Bujildup 1.182e-81 1.439e-21 5.195e-14 3.944e-13 1.488e-12 Exposure Rate mR/hr With Buildup 4.846e-42 5.489e-20 2.263e-12 9.981e-12 2.542e-11 TOTALS: 1.043e+01 1.01 le-09 1.964e-08 1.934e*12 3.766e-1 1 Cl-73 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 12/21/05 MicroShield v5.04 (5.04-00362) MicroShleld v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\M55\DATA\PB122114.M5S Case Title: Une 1.24 E This case was run on Wednesday, December 21, 2005 at 2:10:25 PM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over energies)Units Without Buildup WULIt Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm2/sec MeV/cm'/sec 1.381e.009 1.01 le-009 2.813e.008 1.964e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.934e-012 1 .689e.014 1.689e-012 3.766e-01 I 3.288e*013 3.288e-01 1 Deep Dose Equivalent Rate o Parallel Geometry.o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 1987)mSv/hr (ICRP 51 .1987)mSv/hr 1.982e*014 1.610e-014 1.610e.014 1.423e-014 2.114e.014 2.013e*014 2.013e-014 1.523e-014 3.875e-013 3.129e-013 3.129e-013 2.767e-013 4.125e-013 3.926e*013 3.926e.013 2.960e-013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr.1.760e-014 1.567e-014 1.178e-014 1.402e-014 1.201e-014 3.436e.013 3.051e-013 2.282e-013-2.726e-013 2.33le-013 Page 1 Cl-74 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122115.MS5 RL ate: December 21, 2005 Run-Time: 2:04:46 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 F

Description:

Revised Model CaIc. -Nb-94 Unit Act w Sched 40 & 12 in Sh Geometry: 10 -Cylinder Surface -External Dose Point Height Radius Source Dimensions 762.0 cm 3.81 cm 25 ft 1.5 in I#1 134.97 cm 4 ft 5.1 in Shield Nam Din Cyl. Core 3.1 Shield 1 Transition Shield 3 30 Air Gap Wall Clad .Source Input Grouping Method : Actual Photon Energies Nuclid curies becguerel wCi/cm2 Nb-94 8.2087e-011 3.0372e+000 4.5000e-009)ose Points 381 cm 12 ft 6.0 in Shields lension Material 81 cm' Concrete.65 cm Iron Concrete.48 cm Concrete Air 025 cm Iron z 91.44 cm 3ft 1.8 7.86 2.4 2.4 0.00122 7.86 Bq/CM2 1.6650e 004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ener Activit MeV N photons/sec 0.0174 0.0175 0.0196 0 7026 711 1.074e.03 2.057e-03 6.044e-04 3.037e+00 3.037e+00 Fluence Rate MeV/c-LmLsec No Buildup 4.704e-307 9.585e.302 1.268e-221 4.733e 10 1.274e-09 Results Fluenre Rate MeV/cm"/sec , With Buildup 2.957e-37 5.718e*37 2.009e-37 9.655e-09 1.937e.08 Exposure Rate mR/hr No Buildup 2.539e*308 5.076e-303 4.682e-223 9.128e-13 2.397e- 12 ,xposure Rate mR/hr ihBuilup 1.596e-38 3.028e-38 7.416e-39 1.862e- 11 3.646e-1 1 Cl-75 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 i Page : 2 DOS File : PB122115.MS5 Run Date: December 21, 2005 Run Time: 2:04:46 PM Duration : 00:00:01 MeV Activit photons/sec Fluence Rate MeV/cm2/sec No Buildup Fluence Rate MeV/cm2/sec With Buildup Exposure Rate mR/hr No Buildup Exposure Rate mR/hr With Buildup TOTALS: 6.078e+00 1.747e.09 2.903e-08 3.310e-12 5.508e- 11 Cl-76 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 VlicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122115.MS5 Case Title: Line 1.24 F This case was run on Wednesday, December 21, 2005 at 2:04:46 PM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over energies)Units WithoUt Buildup With Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 2.136e-009

1. 747e-009 3.598e*008 2.903e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 3.310e-012 2.890e-014 2.890e-012 5.508e-01 1 4.808e-013 4.808e-01 1 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 3.362e-014 2.768e-014 2.768e-014 2.447e-014 3.595e-014 3.430e-014 3.430e-014 2.619e-014 5.600e-013 4.602e-013 4.602e-013 4.069e-013 5.986e-013 5.710e-013 5.710e-013 4.354e-013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.996e-014 2.688e-014 2.042e-014 2.406e-014 2.073e-014 4.989e-013 4.470e-013 3.391e-013 4.002e-013 3.445e-013 a Page 1 Cl-77 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DOS File: PB122909.MS5 RL ate: December 29, 2005 RurnTime: 2:36:06 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 G

Description:

Revised Model Calc. 129 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -. External Dose Point Sour, Height Radius#1 134.97 cm 4ft 5.1 in Shield Name Dim Cyl. Core 3.f Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method: Actual Photon Energies-0curies 1 3.372e00 4500cm0 8.2087e-011I 3.0372e+000 4.5000e 009 ce Dimensions 762.0 cm 3.81 cm lose Points Y 381 cm 12 ft 6.0 in Shields ensinn ~ Mate 31 cmz Conc 65 cm iro 25 ft 1.5 in z 91.44 cm 3ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 erial rete n Concrete 48 cm Concrete Air 25 cm Iron Nuclide-1-129 1q/cm6 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 E dney Activity MOb photons/sec 0.0295 0.0298 0.0336 Co 0396 6.061e-01 1.124e+00 3.998e*01 2.284e-01 Fluence Rate MeV/cml/sec No Buildup 6.977e-77 1.092e.74 2.344e-57 1.196e-41 Results Fluence Rate MeV/cmL/sec With Buildup 4.366e-34 8.349e-34 4.359e-34 4.431e-34 Exposure Rate mR/r No Buildup 7.301e-79 1.107e-76 1.667e-59 5.435e-44 Exp~osure Rate mR/hr With Buildup 4.569e-36 8.458e-36 3.100e-36 2.013e-36 CJ-78 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2-0 DOS File : PB122909.MS5 Run Date: December 29, 2005 Run Time: 2:36:06 PM Duration : 00:00:01 Ehergy Activity Fluence Rate May photons/sec MeV/rml/sec No BuilduI TOTALS: 2.359e+00 1.196e-41 Fluenice Rate MeV/cm2/sec With Buildup 2.150e-33 Exposure Rate mR/hr No Buildu 5.435e-44 Exposure Rate mR/hr With Buildup 1.814e-35 CJ-79 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04.00362) MicroShield v5.04 (5.04.00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MSS\DATA\PB122909.MS5 Case Title: Line 1.24 G This case was run on Thursday, December 29, 2005 at 2:36:06 PM Dose Point # 1 -(134.97,381,91.44) cm 12/29/05 With Buildup Results (Summed over energies)Units Without Buld~up Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 3.022e-040 1.196e-041 6.702e-032 2.150e-033 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 5.435e-044 4.745e-046 4.745e-044 1.814e-035 1.584e-037 1.584e-035 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr (ICRP 51 .1987)mSv/hr 6.792e-046 3.421 e-046 3.097e-046 2.963e-046 6.834e-046 4.717e-046 4.717e-046 3.462e-046 1.813e-037 9.094e-038 7.757e-038 7.205e-038 1.976e-037 1.359e-037 1.359e-037 1.004e-037 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 3.960e-046 2.394e-046 1.322e-046 2.153e-046 1.764e-046 8.128e-038 4.203e-038 2.268e-038 4.176e-038 3.460e-038 Page 1 Cl-80 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04.00362) Radiological Services, Inc.Page : 1 DOS File : PB122911.MS5 RL ate: December 29, 2005 Run- fime: 2:42:27 PM Duration: 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 1

Description:

Revised Model Calc- Zr-95 Unit Act w Sched 40 & 12 in Shid Geometry: 10- Cylinder Surface -External Dose Point E~F 'IX Height Radius Source Dimensions 762.0 cm 3.81 cm 25 ft 1.5 in[#1 134.97 cm 4ft 5.1 in Shed a Din Cyl. Core 3.J_. Shield 1 Transition Shield 3 30.Air Gap Wall Clad .Source Input Grouping Method : Actual Photon Energies rNuclide curies becquerels 45i0eM Zr-95 8.2087e-01 I 3.0372e+000 4.5000e 009)ose Points 381 cm 12 ft 6.0 in z 91.44 cm 3ft Shields nension Material Density 81 cm 2 Concrete 1.8.65 cm Iron 7.86 Concrete 2.4.48 cm Concrete 2.4 Air 0.00122 025 cm Iron 7.86 1q.cm6 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Eneg MeV 0.7242 0.7567 TOTALS: Activity 2hotons/sec 1.326e+00 1.681e+00 3.007e+00 Fluence Rate MeV/rcm2sec No Buildup 2.380e.10 3.702e-10 6.082e 10 Results Fluence Rate MeV/cm'/lsec With Buildup 4.659e.09 6.824e.09 1. 148e-08 Exposure Rate mR/hr No Buildup 4.577e-13 7.085e- 13 1.166e.12 Exposure Rate mR/hr-With Buildup 8.958e- 12 1.306e- 11 2.202e-1 1 CJ-81 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 IcroShield v5.04 (5.0400362) 12/29/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122911.MS5 Case Title: Line 1.24 1 This.case was run on Thursday, December 29, 2005 at 2:42:27 PM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over enereies)Without With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 8.178e*OlO 6.082e-010 1.545e*008 1.148e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.166e-012 1.018e-014 1.018e-012 2.202e-01 1 1.922e-013 1.922e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 1987)mSv/hr (ICRP 51 1987)mSv/hr (ICRP 51 -1987)mSv/hr 1.193e-014 9.705e-015 9.705e-015 8.578eO015 1.274e-014 1.214e-014 1.214e-014 9.181e-015 1.060e-014 9.441e.015 7.098e-015 8.444e*015 7.233e-015 2.254e-013 1.832e-013 1.832e-013 1.620e-013 2.406e*013 2.292e-013 2.292e-013 1.733e-013 2.00le*013 1.783e*013 1 .340e-013 1.594e-013 1.366e-013 Page 1 Cl-82 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB010403.MS5 RL ate: January 4, 2006 RurVTime: 7:59:23 AM Duration :00:00:01 File Ref: Date: _By: Checked: Case Title: Line 1.24 H

Description:

Revised Model Calc -Sn-126 Unit Act w Sched 40 & 12 in ShId Geometry: 10 -Cylinder Surface -External Dose Point Height Radius# 1 134.97 c 4 ft 5.1 Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Source Dimensions 762.0 cm 3.81 cm Dose Points y cm 381 cm in 12 ft 6.0 in Shields Dimension Mate 3.81 cm 2 Conci.65 cm Iro 25 ft 1.5 in z 91.44 cm 3 ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 EaW rete n Concrete 30.48 cm Concrete Air.025 cm Iron Source Input Grouping Method: Standard Indices-Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015: Excluded Library: Grove 2 kbecquerels Ci/cm)11 3.0372e+000 4.5000e-OC Nuclide curies Sn 126 8.2087e-(09 1.6650e-004 Buildup The material reference Is : Cyl. Core Y Direction (axial)Circumferential tegration Parameters Results P. Fluence Rate MeV/cm2/sec With Buildup P 8.062e-35 20 20 En Act3v1t MeV photons/sec )2 2.35le-01 Fluence Rat Me/cAm2Lse No Buildup 2.258e.207 Exposure Rate mR/hr No Buildup 7.820e 209 Exposure Rate mR/hr With Buiidup 2.792e-36 Cl-83 IPlum Brook Reactor Facility Final Status Survey Plan Revision O Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File : PB010403.MS5 Run Date: January 4, 2006 Run Time: 7:59:23 AM Duration : 00:00:01 Ebergy MeV 0.03 0.04 0.06 0.08 photons/sec 8.893e-01 1.517e-02 2.91 le-01 1.395e+00 Fluende Rate MeV/cm2/sec No Buildup 1.644e-73 4.854e-42 3.017e-23 5.894e-18 Fluence Rate MeV/cm2/sec With Buildup2 6.743e-34 3.051e-35 5.881e-22 2.247e- 16 Exposure Rate mR/hr No Buildup 1.630e-75 2.147e.44 5.993e-26 9.326e-21 Exposure Rate mR/hr With Buildup 6.683e-36 1.349e-37 1.168e-24 3.557e-19 TOTALS: 2.825e+00 5.894e-18 2.247e- 16 9.327e-21 3.557e-19 Cl-84 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 01/04/06 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB010403.MS5 Case Title: Line 1.24 H This case was run on Wednesday, January 4, 2006 at 7:59:23 AM Dose Point # 1 -(134.97,381,91.44) cm Results (Summed over energies!Units Without Buildu With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air Photons/cm2/sec MeV/cmz/sec 7.367e-017 2.809e-015 5.894e-018 2.247e-016 mR/hr mGy/hr mrad/hr 9.327e-021 8.142e-023 8.142e-021 3.557e-019 3.105e-021 3.105e-019 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.424e-022 7.585e-023 7.373e-023 7.320e-023 5.43le-021 2.893e-021 2.812e-021 2.79le-021 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (tCRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 1.41 le-022 1.037e-022 1.037e-022 7.612e-023 1.196e-022 9.123e-023 5.623e-023 7.771e-023 6.286e-023 5.380e-021 3.954e-021 3.954e-021 2.903e-021 4.561e-021 3.479e-021 2.144e-021 2.963e-021 2.397e-021 Page 1 Cl-85 Plum Brook Reactor Facility Final Status Survey Plan Revisiorn 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOR File: PB122912.MS5 RL ate: December 29, 2005 Run-Time: 2:45:53 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.24 J

Description:

Revised Model Calc -Eu-155 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point 4 X Height Radius Source Dimensions 762.0 cm 3.81 cm 25 ft 1.5 in# 1 134.97 ci 4 ft 5.1 Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Dose Points Y ii 381 cm in 12 ft 6.0 in Shields Dimension Mat 3.81 cm 2 Con(.65 cm In Conm 30.48 cm Conc terial:rete)on crete crete z 91.44 cm 3ft Density 1.8 7.86 2.4 2.4 0.00122 7.86 z Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove becquerels JCi/cm 2 01l 3.0372e+000 4.5000e-00 Nuclide curies Eu 155 8.2087e-I'9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ener Activi MO6 photons/sec )3 9.667e 03 Fluence Rate MeV/cm2/sec No Buildup 1.787e-75 Results Fluence Rate MeV/cm7/sec With Buildup 7.330e 36 iExosure Rate mR/hr No Buildup 1.77le-77 Exposue Rate mR/hr With Buildup 7.264e.38 CJ-86 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 IPage : 2 DOS File: PB122912.MS5 Run Date: December 29, 2005 Run Time: 2:45:53 PM Duration : 00:00:01 Eneg Key 0.04 0.05 0.06 0.08 0.1 Activity photons/seQ 5.505e-01 1.791e-01 3.939e-02 9.431e-01 6.279e-01 Fluence Rate Me~cM21ser. No BuilduI 1.762e -40 6.462e-29 4.083e-24 3.986e-18 2.033e-16 Fluence Rate MeqV/m2/sec With Buildup 1.107e-33 6.313e-28 7.960e-23 1.520e-16 1.231e-14 Exposure Rate mR/hr No Buildup2 7.791e-43 1.721e-31 8.1 10e-27 6.307e-21 3.111e-19 Exposure Rate mR/hr With Buildup 4.896e-36 1.682e-30 1.581e-25 2.405e- 19 1.884e-17 TOTALS: 2.350e+00 2.073e.16 1.246e.14 3.174e.19 1.908e-17 CI-87 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122912.MS5 Case Title: Line 1.24 J This case was run on Thursday, December 29, 2005 at 2:45:53 PM Dose Point # 1 -(134.97,381,91.44) cm 12/29/05 With Buildup Results (Summed over energies)Units Without BuidI Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 2.083e-015 2.073e-016 1.250e-013 1.246e-014 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 3.174e-019 2.77le-021 2.771e-019 1.908e-017 1.665e-019 1.665e-017 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 4.635e-021 2.540e-021 2.539e-021 2.458e-021 2.785e-019 1.526e-019 1.526e-019 1.477e-019 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 4.604e-021 3.569e-021 3.569e-021 2.599e-021 2.767e-019 2.145e-019 2.145e-019 1.562e-019 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 3.982e-021 3.121e-021 1.926e-021 2.666e-021 2.121e-021 2.393e-019 1.876e-019 1.158e-019 1.602e-019 1.275e-019 Page 1 CI-88 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB121911.MS5 Ri )ate: December 19, 2005 Run Time: 11:14:14 AM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.25 A2

Description:

Revised Model CaIc. -Co-60 Unit Act w Sched 40 & 12 in Shid Geometry: 10- Cylinder Surface -External Dose Point Sour Height Radius I#1 138.78 cm 4 ft 6.6 in Shield Name D2in Cyl. Core 7.1 Shield 1 Transition Shield 3 30, Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies curies bec+uerels 4Ci/crn 1.6417e-010 6.0744e+000 4.5000e-009 rce Dimensions 762.0 cm 7.62 cm)ose Points:Y 381 cm 12 ft 6.0 in Shields iension Mate 52 cm 2 Conci.65 cm Iro 25 ft 3.0 in: Z 137.16 cm 4 ft 6.0 in I Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 I aria ,et n Concret.48 cm Concret Air 025 cm Iron Nuclide Co-60 Bq/cm1 0 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 MeV 0.6938 1.1732 1.3325 Activity photons/sec 9.909e-04 6.074e+00 6.074e+00 Fluence Rate MeV/cm2/sec No Buildu 1.951e.14 1.764e-09 3.243e-09 Results Fluence Rate MeVcm2/sec With Buildup 5.213e-13 2.250e-08 3.513e.08 Exposure Rate mR/hr No Buildup 3.766e-17 3.151e-12 5.627e-12 Exposure Rate rnR/hr 1.006e- 15 4.022e-1 1 6.095e. 11.ALS: 1.215e+01 5.007e-09 5.764e-08 8.778e-12 1.012e-10 Cl-89 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield vS.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\M55\DATA\PB121911.M55 Case Title: Line 1.25 A2 This case was run on Monday, December 19, 2005 at 11:14:14 AM Dose Point # 1 -(138.78,381,137.16) cm Results (Summed over energies} Uniti Without Buildup WU~R Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec: MeV/cM2/sec 3.937e-009. 5.007e*009 4.555e*008 5.764e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 8.778e-012 7.663e*014 7.663e-012 1.012e-010 8.832e-013 8.832e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 1987)mSv/hr (ICRP 51 -1987) -mSv/hr (iCRP 51 .1987)mSv/hr 8.699e-014 7.495e-014 7.495e-014 6.696e.014 9.259e-014 8.916e-014 8.916e-014 7.093e-014 7.834e-014 7.218e-014 5.743e-014 6.500e-014 5.754e-014 1.003e-012 8.636e-013 8.636e-013 7.714e-013 1.067e-012 1.028e-012 1.028e-012 8.173e.013 9.030e-013 8.318e-013 6.614e-013 7.489e-013 6.628e-013 Page 1 Cl-90 Plum Brook Reactor Facility Final Status Survey Plan Revision 0.Plum Brook Reactor Facility-Final Status Survey Plan, , Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DO" Pile: PB122116.MS5 Ru ate: December 21, 2005 Run Time: 2:17:24 PM Duration : 00:00:01 File Ref: Date: By: Checked: _Case Title: Line 1.25 B

Description:

Revised Model Calc -Cs-137 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Sour Height Radius I#1 138.78 cm 4 ft 6.6 in ShiedNme Din Cyl. Core 7.Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies curies becquerels Ci/cm 2 1.5531e-010 5.7464e+000 4.2570e-009 1.6417e-010 6.0744e+000 4.5000e-009-ce Dimensions 762.0 cm 7.62 cm)ose Points 381 cm 1 12 ft 6.0 in Shields iension Mlyateriali 62 cm 2 Concrete.65 cm Iron Concrete.48 cm Concrete Air 125 cm Iron 25 ft 3.0 in z 37.16 cm 4 ft 6.0 in Density 1.8 7.86 2.4 2.4 0.00122 7.86 z Nuclide Ba-137m Cs-137 Bq/cm2 1.5751e-004 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ene MOV 0.0318 0.0322 rf "364 , j316 Activty 12hotons/ser. 1.190e-01 2.195e-01'7.987e-02 5.171e+00 Fluence R~ate MeV/cM2/sec No Buildup 2.257e-73 3.354e-71 2.920e-55 7.886e- 11 Results Fluence Rate MeV/L2/sec With Buildup 8.498e-35 1.629e-34 9.080e-35 2.257e*09 Exposure Rate mRlhr No Buildup 1.880e.75 2.699e-73 1.659e-57 1.529eK13 Exposure Rate mR/hr 7.078e.37 1.31le-36 5.159e-37 4.375e- 12 Cl-91 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 Page : 2 DOS File : PB122116.MS5 Run Date: December 21, 2005 Run Time: 2:17:24 PM Duration : 00:00:01 Eerg Activity MOY photons/sec Fluence Rate MeV/cm2/sec No Buildup Fluence Rate MeV/cm2/sec With Buildlup Exposure Rate mR/hr No Buildup2 Exposure Rate mR/hr With Buildup TOTALS: 5.589e+00 7.886e- 11 2.257e-09 1.529e.13 4.375e-12 Cl-92 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.0400362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122116.MS5 Case Title: Line 1.25 B This case was run on Wednesday, December 21, 2005 at 2:17:24 PM Dose Point # 1 -(138.78,381,137.16) cm Results (Summed over energies!Units Without Buildup with Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm2/sec MeV/cm 2/sec 1.192e-010 3.41le-009 7.886e*O1 1 2.257e-009 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.529e.013 1.335e-015 1.335e.013 4.375e-01 2 3.819e-014 3.819e.012 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 1.580e-015 1.265e-015 1.265e-015 1.119e.015 1.680e-015 1.595e-015 1.595e-015 1.196e-015 4.522e-014 3.620e-014 3.620e-014 3.201e-014 4.806e-014 4.565e.014 4.565e-014 3.422e-014 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.397e-015 1.233e-015 9.146e-016 1.102e-015 9.383e-016 3.998e.014 3.529e-014 2.61 7e-014 3.154e-014 2.685e.014 Page 1 Cl-93 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122117.MS5 RL ate: December 21, 2005 RundTime: 2:23:34 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.25 C

Description:

Revised Model Calc- Eu-152 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Height Radius x# 1 138.78 cm 4 ft 6.6 in Shield Name I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12 ft 6.0 in Shields Dimension Mate 7.62 cm 2 Conc.65 cm Iro 25 ft 3.0 in z 137.16 cm 4 ft 6.0 in I DensitY e 1.8 7.86 e 2.4 a 2.4 0.00122 7.86 2: ria ret, n Concret 30.48 cm Concreti Air.025 cm Iron-Source Input Grouping Method: Standard Indices Number of Groups: 25 Lower Energy Cutoff :0.015 Photons < 0.015: Excluded Library : Grove becquerels UCi/Cm 10 6.0744e+000 4.5000e-O(Nuclide curies Eu.152 1.6417e-I 809 Bq/cm2 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy. Activity hotons/sec 34 3.594e+00 Fluence Rate MeV/cm2/sec No Buildu 1.705e-44 Results Fluence Rate MeV/cml/sec With Buildup 5.683e-33 Exposure Rate mR/h7 No Buildup 7.540e 47 Exposure Rate mR/hr With Buildup 2.514e-35 CJ-94 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 4 Page : 2 DOS File : PB122117.MS5 Run Date: December 21, 2005 Run Time: 2:23:34 PM Duration : 00:00:01'Enc MeV 0.05 0.1 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 Activity p2hotons/sec 8.987e-01 1.727e+00 4.552e-01 1.642e+00 3.817e-01 3.426e.02 2.576e-01 1.082e+00 2.599e+00 1.409e+00 Fluence Rate MeV/cm2/sec No Buidu 2.286e.31 1.425e.17 5.009e.15 2.624e-13 3.443e-13 1.116e.13 2.309e.12 4.526e-1 1 3.419e-10 1.299e-09 Fiuence Rate MeV/cm2/sec With Buildup 2.318e-30 1.080e-15 5.689e-13 2.178e 11 2.007e- 11 4.775e.12 7.607e- 11 9.859e 10 5.424e-09 1.218e-08 Exposure Rate mR/hr No Buildup 6.091e-34 2.179e 20 8.840e-18 4.978e-16 6.708e-16 2.190e 16 4.506e-15 8.608e-14 6.302e 13 2.185e.12 Exposure Rate mR/hr With Buildup 6.175e-33 1.653e- 18 1.004e 15 4.132e-14 3.91 le-14 9.372e-15 1.485e- 13 1.875e- 12 9.998e-12 2.050e 1 1 TOTALS: 1.408e+01 1.689e -09 1.872e.08 2.907e-12 3.261e-11 Cl-95 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShleld v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122117.MS5 Case Title: Line 1.25 C This case was run on Wednesday, December 21, 2005 at 2:23:34 PM Dose Point # 1 -(138.78,381,137.16) cm Results (Summed over energies!anit$Wibthu-Wih Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm t/sec MeV/cm 2/sec 1.270e-009 1.504e-008 1.689e-009 1.872e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.907e*012 2.538e-014 2.538e-012 3.261e-011 2.847e-013 2.847e-O11 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51

• 1987)mSv/hr 2.882e-014 2.494e-014 2.494e- 014 2.232e-014 3.058e-014 2.952e-014 2.952e-014 2.356e-014 3.242e-013 2.789e-013 2.789e-013 2.491e-013 3.443eO013 3.318e-013 3.318e-013 2.635e-013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.595e*014 2.397e-014 1 .920e-014 2.162e.014 1.919e-014 2.915e-013 2.684e-013 2.136e-013 2.418e-013 2.139e-013 Page 1 Cl-96 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DOF File: PB122118.MS5 Ru ate: December 21, 2005 RunhTime: 2:24:58 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.25 D

Description:

Revised Model Calc -Eu-154 Unit Act w Sched 40 & 12 In Shid Geometry: 10 -Cylinder Surface -External Dose Point Height Radius# 1 138.78 cm 4ft 6.6 in Shield Nam I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12 ft 6.0 in Shields Dniension Mate 7.62 cm 2 Conc.65 cm Ira 25 ft 3.0 in z 137.16 cm 4 ft 6.0 in I Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 eta ret an z Concret 30.48 cm Concret Air.025 cm Iron Source Input Grouping Method: Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library: Grove i becquerels Uici/cm2 010 6.0744e+000 4.5000e-OC Nuclide Eu-154 1.6417e.09 Bq/cm2 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ene Activity M&E photons/sec 34 1.236e+00 Fluence Rate MeV/cM2/sec Nojuildup 5.864e-45 Results Fluence Rate MeV/cm-/sec With.-Build~up 1.955e-33 Exposure Rate mR/br No-uil-d 2.593e.47 Exposure Rate mR/hr With Buildup 8.646e.36 Cl-97 Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 Page : 2 DOS File: PB122118.MS5 Run Date: December 21, 2005 Run Time: 2:24:58 PM Duration : 00:00:01 Ehergy Activity MeV photons/sec 0.05 0.1 0.2 0.4 0.5 0.6 0.8 1.0 1.5 3.140e-01 2.458e+00 4.148e-01 4.334e-02 1.315e-02 4.900e-01 2.369e+00 1.869e+00 2.370e+00 Fluence Rate MeV/cm2/sec Nlo Buildup 7.989e-32 2.027e-17 4.565e-15 3.909e.14 4.282e-14 4.391e-12 9.912e-11 2.458e-10 2.185e-09 Fluence Rate MeV/cm2/sec 8.099e.31 1.538e.15 5.184e.13 2.279e- 12 1.833e.12 1.447e-10 2.159e-09 3.900e09 2.049e-08 Exposure Rate mR/br No Buildup2 2.128e-34 3.102e.20 8.056e-18 7.616e-17 8.405e-17 8.571e-15 1.885e-13 4.531e.13 3.675e-12 Exposure Rate mR/hr With Buildup2 2.158e.33 2.352e-18 9.150e 16 4.440e- 15 3.597e- 15 2.824e-13 4.107e-12 7.188e-12 3.448e.1 1 TOTALS: 1.158e+01 2.534e-09 2.670e-08 4.326e- 12 4.607e- 11 C1-98 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 AicroShield v5.04 (5.04-00362) 12/21/0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122118.MS5 Case Title: Line 1.25 D This case was run on Wednesday, December 21, 2005 at 2:24:58 PM Dose Point # 1 -(138.78,381,137.16) cm Results (Summed over energies!Units Without With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 1.834e-009 2.534e*009 2.051e;008 2.670e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 4.326e-012 3.777e.014 3.777e*012 4.607e-01 1 4.022e-013 4.022e-01 1 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 4.283e*014 3.719e-014 3.719e-014 3.331e-014 4.539e-014 4.387e-014 4.387e-014 3.51 le-014 4.572e*013 3.949e-013 3.949e-013 3.533e*013 4.850e-013 4.68le 013 4.681e-013 3.730e-013 (ICRP 51 .1987)mSv/hr Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 }1987)mSv/hr 3.858e-014 3.57le.014 2.872e.014 3.222e-014 2.866e-014 4.114e-013 3.796e.013 3.036e.013 3.423e-013 3.035e-013 Page.Cl-99 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122119.MS5 Ru ate: December 21, 2005 Run Time: 2:28:46 PM Duration : 00:00:01 File Ref: Date: _ _ _By: Checked: Case Title: Line 1.25 E

Description:

Revised Model Calc- Ag-108m Unit Act w Sched 40 & 12 in Shid Geometry: 10- Cylinder Surface- External Dose Point 71I Height Radius# 1 138.78 cm 4 ft 6.6 in Shield Name j Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields Dimension Mate 7.62 cm 2 Conci.65 cm Iro 25ft 3.0 in z 137.16 cm 4 ft 6.0 in d Density te 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 6a ret n z Concret 30.48 cm Concret Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons c 0.015 : Excluded Library : Grove eU becquerels iCi/cm2 e-010 6.0744e+000 4.5000e-0, Numlide curia Ag-108m 1.64174 I09 B1/cm.1.6650e-004 Buildup The material reference Is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energ 32 Activie photons/sec 3.984e+00 Fluence Rate MeV/CM2/sec No Buildup 3.279e-235 Results Fluence Rate Me/cem2se.c With Buildup 1.074e-33 Exposure Rate mR/hr No Buildup 1. 136e-236 Exposur ate mRbhr With Buildu 3.722e-35 0l-100 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 4v ,Page : 2 DOS File: PB122119.MS5 Run Date: December 21, 2005 Run Time: 2:28:46 PM Duration : 00:00:01 Energy Activity MeV photons/s~c 0.03 0.08 0.4 0.6 0.8 1.290e-06 4.305e-01 5.460e+00 5.491e+00 5.497e+00 Fluence Rate MeV/cm2/sec No Buildup 6.584e-89 2.739e-20 4.924e-12 4.921e-11 2.300e-10 Fluence Rate MeWcmVsec With Buildup 7.69le-40 1.249e- 18 2.871e-10 1.621e-09 5.01 le-09 Exposure Rate mR/hr No Buildup 6.525e-91 4.335e-23 9.595e-15 9.606e-14 4.375e-13 Exagsure Rate mR/hr With Buildup 7.622e-42 1.976e-21 5.594e*13 3.165e.12 9.531e-12 TOTALS: 2.086e+01 2.842e-10 6.920e-09 5.432e- 13 1.326e*1 1 CI -101 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB122119.MS5 Case Title: Line 1.25 E This case was run on Wednesday, December 21, 2005 at 2:28:46 PM Dose Point # 1 -(138.78,381,137.16) cm 12/21/05 Results (Summed over energies)Without Buildup With Buildu~Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 3.819e-010 2.842e-010 9.684e-009 6.920e.009 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 5.432e-013 4.742e-015 4.742e-013 1.326e-01 1 1.157e-013 1.157e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 5.557e-015 4.523e-015 4.523e-015 3.998e-015 5.931e-015 5.651e-015 5.651e-015 4.278e-015 4.939e-015 4.402e-015 3.313e-015 3.937e-015 3.375e-015 1.361e-013 1.102e-013 1.102e-013 9.744e-014 1.450e-013 1.381e-013 1.381e-013 1.042e-013 1.208e-013 1.074e-013 8.051e-014 9.600e-014 8.215e-014 Page 1 Cl-102 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB122120.MS5 Ru ate: December 21, 2005 RunrTime: 2:32:47 PM Duration : 00:00:01 File Ref: Date:-By: Checked: Case Title: Line 1.25 F

Description:

Revised Model CaIc- Nb-94 Unit Act w Sched 40 & 12 in Shid Geometry: 10

• Cylinder Surface -External Dose Point Sour Height Radius-C#1 138.78 cm 4 ft 6.6 in ShieldName DjR Cyl. Core 7.4 Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies 1.4ies becquerels 0Ci/cm0 1.6417e-010 6.0744e+000 4.5000e-009 ce Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields nension Mat 52 cm 2 Conc.65 cm Iro 25ft 3.0 in z 137.16 cm 4 ft 6.0 in i Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 ret in Concret 48 cm Concret Air'25 cm Iron Nuclide Nb-94 Bq/cm1 1.6650e-004

-Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy MeV 0.0174 0.0175 0.0196 ( 7026 711 Activity photons/sec 2.148e-03 4.115e-03 1.209e-03 6.074e+00 6.074e+00 Fluence Rate MeV/cml/sec No Buildup 0.OOOe+00 0.OOOe+00 4.082e-252 1.279e.10 3.955e-10 Results Fluence Rate MeV/cm2/sec With Buildup 4.650e-37 8.994e-37 3.160e-37 3.358e-09 7.629e-09 ExPosure Rate mR/hr No Buildup 0.OOOe+00 0.OOOe+00 1.507e-253 2.467e-13 7.444e-13 Exposure Rate mR/hr With Buildup 2.510e-38 4.763e-38 1.166e-38 6.475e-12 1.436e-1 1 Cl-103 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 V Page : 2 DOS File : PB122120.MS5 Run Date: December 21, 2005 Run Time: 2:32:47 PM Duration : 00:00:01 Energy Activity MeV 12hotons/sec Fluence Rate MeV/Cm2/sec No Buildup Fluence Rate MeV/cm2/sec With Buidup Exposure Rate mR/hr No Buildup Exposure Rate mR/hr With B3uildup TOTALS: 1.216e+01 5.235e-10 1.099e-08 9.91le-13 2.083e-I 1 Cl -104 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04.00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122120.MS5 Case Title: Line 1.25 F This case was run on Wednesday, December 21, 2005 at 2:32:47 PM Dose Point # 1 -(138.78,381,137.16) cm Results (Summed over energies!Withoutf Buildu1 Photon Fluence Rate (flux)Photon Energy Fluence Rate-Photons/cm 2/sec MeV/cm-/sec 6.362e-010 5.235e-010 1.354e-008 1.099e-008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 9.91 le-013 8.653e-015 8.653e-013 2.083e-01 1 1.819e.013 1..81 9e-01 1 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.006e-014 8.289e-015 8.289e-015 7.330e-015 2.117e-013 1.74le.013 1.74le.013 1 .540e.013 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 .1987)mSv/hr 1.076e-014 1.027e-014 1.027e-014 7.844e-015 2.264e.013 2.160e-013 2.160e-013 1.648e.013 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 8.970e-015 8.049e-015 6.119e-015 7.207e-015 6.210e-015 1.887e-013 1.691e-013 1.284e-013 1.514e-013 1.304e-013 Page 1 Cl-105 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File : PB122913.MS5 RL ate: December 29, 2005 RuriTime: 2:49:38 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.25 G

Description:

Revised Model Calc- 1-129 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Height Radius# 1 138.78 cm 4 ft 6.6 in ource Dimensions 762.0 cm 7.62 cm Dose Points Y 381 cm 12 ft 6.0 in Shields Dimension Math 7.62 cm- Conc.65 cm Iro 25 ft 3.0 in z 137.16 cm 4ft 6.0 in 1 Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86.+/-k Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad I Concret 30.48 cm Concrete Air.025 cm Iron etia cretq on Source Input Grouping Method : Actual Photon Energies curies b e wC 1.6417e-010 6.0744e+000 4.5000e.009 Nuclide 1-129 Bq/cm2 1.6650e-004 Buildup The material reference Is: Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy W~Y 0.0295 0.0298 0.0336 0 0)396 Activity 12hotons/sec 1.212e+00 2.249e+00 7.995e-01 4.568e-01 Fluence Rate MeV/cm 2/sec 1.333e-86 3.950e-84 2.970e.64 2.750e-46 Results Fluence Rate MeV/cm2/sec With Buildup 6.866e-34 1.313e-33 6.856e-34 6.969e-34 Exp~osure Rate.mR/hr No Buildup 1.395e-88 4.002e-86 2.113e-66 1.249e-48 Exposure Rate mR/hr With Buildup 7.186e-36 1.330e-35 4.876e-36 3.167e-36 Cl-106 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page 2 DOS File : PB122913.MS5 Run Date: December 29, 2005 Run Time: 2:49:38 PM Duration : 00:00:01 nergy Activity Mey .phtons/sec TOTALS: 4.718e+00 Fluence Rate MeV/cm2/sec No Buildup 2.750e-46 Fluence Rate MeV/cm2/sec With Buildup 3.382e-33 Exposure Rate mR/he No Buildup 1.249e-48 Exposure Rate mR/hr With Buildup 2.853e-35 I i I i i i Cl-107 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroStield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122913.MS5 Case Title: Line 1.25 G This case was run on Thursday, December 29, 2005 at 2:49:38 PM Dose Point # 1 -(138.78,381,137.16) cm Results (Summed over energies) Units Without BuilduI2 with Buildug Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm2/sec 6.947e*045 2.750e*046 1.054e.031 3.382e-033 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.249e-048 1.09le-050 1.091e-048 2.853e-035 2.49le-037 2.49le-035 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.561e-050 7.864e-051 7.120e-051 6.81 le-051 2.852e.037 1.430e-037 1.220e-037 1.133e-037 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.57 le-050 1.084e-050 1.084e-050 7.958e-051 3.108e-037 2.137e-037 2.137e-037 1.580e-037 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51

• 1987)mSv/hr 9.103e-051 5.503e-051 3.040e-051 4.948e-051 4.056e-051 1.278e-037 6.610e-038 3.568e-038 6.568e-038 5.441e-038 Page 1 Cl-108 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.Page : 1 DOs File: PB010404.MS5 Rt. ate: January 4, 2006 Run Time: 8:04:03 AM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.25 H

Description:

Revised Model Calc- Sn-126 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point VII] PI X Height Radius X# 1 138.78 cm 4 ft 6.6 in Shield Name I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points 381 cm 12 ft 6.0 in Shields imension Mate 7.62 cm 2 Conci.65 cm lroi 25 ft 3.0 in z 137.16 cm 4ft 6.0 in I Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 da ,et n z Concret 30.48 cm Concret Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 2 bec6uerels 4Ci/0m0 010 6.0744e+000 4.5000e 00 Nuclide Sn-126 1.6417e-I 09 Bq /CM2 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy MeV)2 Activiy 2hotons/sec 4.702e-01 Fluesnc Rate MeV/cm-2/sec No Buildup 3.869e-236 Results Fluence Rate MeV/cm2/sec With Buildup 1.268e-34 Exposure Rate mR/hr No Buildu 1.340e-237 Exposure Rate mR/hr With Buildup 4.392e-36 Cl-109 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page , 2 DOS File: PBO10404.MS5 Run Date: January 4, 2006 Run Time: 8:04:03 AM DurAtion : 00:00:01 E g Activity MeV photons/sec 0.03 0.04 0.06 0.08 1.779e+00 3.034e-02 5.821e-01 2.789e+00 Fluence Rate MeV/cm2/=e No Buildup 9.079e-83 1.439e-46 2.323e-25 1.775e.19 Fluence Rate MeV/cml/sec With Buildup 1.061e-33 4.798e-35 5.459e-24 8.092e- 18 Exposure Rate mR/hr No Buildup 8.997e-85 6.365e-49 4.615e-28 2.809e-22 2.809e.22 Exposure Rate mrR/h With Buildup 1.051e-35 2.122e-37 1.084e-26 1.281e.20 TOTALS: 5.650e+00. 1.775e.19 8.092e-18 1.281e-20 Cl -110 Plum Brook Reactor Faciit y Final Status Survey Plan Revision 0-MicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure In air to dose FILE: C:\MS5\DATA\PB010404.MS5 Case Title: Line 1.25 H This case was run on Wednesday, January 4, 2006 at 8:04:03 AM Dose Point # 1 -(138.78,381,137.16) cm 01/04/06 Results (Summed over energies)Units Without With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 2.219e-018 1.775e-019 1.012e-016 8.092e-018 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 2.809e-022 2.452e-024 2.452e-022 1.281e-020 1.1 18e.022 1.1 18e-020 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational. o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 4.289e-024 2.284e-024 2.220e-024 2.204e-024 4.249e-024 3.123e-024 3.123e-024 2.292e-024 3.602e-024 2.747e-024 1.693e-024 2.340e-024 1.893e-024 1.955e-022 1.041e-022 1.012e-022 1.005e-022 1.937e-022 1.424e-022 1.424e-022 1.045e-022 1.642e-022 1.253e-022 7.720e-023 1.067e-022 8.630e-023 Page 1 Cl-lll Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page :1 DOS File: PB122915.MS5 Rt late: December 29, 2005 Run rime: 2:53:47 PM Duration :00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.25 1

Description:

Revised Model Calc- Zr-95 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point 4~i Ix Sour, Height Radius#1 138.78 cm 4 ft 6.6 in Shield Name Din Cyl. Core 7.4 Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies Nuclid c becquerels ulitcm Zr-95 1.6417e-010 6.0744e+000 4.5000e.009 ce Dimensions 762.0 cm 7.62 cm lose Points 381 cm 12 ft 6.0 in Shields iension Matk ,2 cm 2 Conc 65 cm Iro 25 ft 3.0 in z 137.16 cm 4 ft 6.0 in I Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 Ma ret n z Concrete 48 cm Concret, Air 25 cm Iron Bq/cm1 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Ene 0.7242 0.7567 Activity p2hotons/sec 2.652e+00 3.362e+00 Fluence Rate MeV/cm2/sec No Buildup 6.562e-1 1 1.050e-10 Results Fluence Rate MeV/cm2/sec With Buildup 1.649e-09 2.477e.09 Exposure Rate mR/hr No Buildup 1.262e.13 2.010e-13-Exposure Rat mR/hr With Buildup 3.170e-12 4.742e- 12 TOTALS: 6.014e+00 1.706e.10 4.126e.09 3.271e.13 7.912e-12 Cl -112 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 ihicroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\M5S\DATA\PB122915.MS5 Case Title: Line 1.25 I This case was run on Thursday, December 29, 2005 at 2:53:47 PM Dose Point # 1 -(138.78,381,137.16) cm 12/29/05 Results (Summed over energies)Units Without With Buildup Photon Fluence Rate (flux)Photon Energy Fluence Rate Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air Photons/cm2/sec MeV/cm 2/sec mR/hr mGy/hr mrad/hr 2.294e-010 1.706e-010 3.27le-013 2.856e-015 2.856e-013 5.55le-009 4.126e-009 7.912e-012 6.907e-014 6.907e-01 2 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 3.348e-015 2.723e-015 2.723e-015 2.406e-015 8.097e-014 6.584e-014 6.584e-014 5.820e-014 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 -1987)mSv/hr 3.574e-015 3.406e-015 3.406e-015 2.576e-015 2.973e-015 2.648e-015 1.991e-015 2.369e-015 2.029e-015 8.644e-014 8.237e-014 8.237e-014 6.229e-014 7.191e-014 6.405e-014 4.816e-014 5.729e-014 4.907e-014 Page 1 Cl-113 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File : PB122916.MS5 RL 'ate: December 29, 2005 Run Time: 2:55:49 PM Duration : 00:00:01 File Ref: Date:__By: Checked:-Case Title: Line 1.25 J

Description:

Revised Model Calc- Eu-155 Unit Act w Sched 40 & 12 in ShId Geometry: 10- Cylinder Surface -External Dose Point x z Height Radius# 1 138.78 cm 4 ft 6.6 in Shield Name I Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad ource Dimensions 762.0 cm 7.62 cm Dose Points Y.1 381 cm 12 ft 6.0 in Shields imension Mate 7.62 cm 2 Conci.65 cm Iroi 25 ft 3.0 in z 137.16 cm 4ft 6.0 in I Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 nia ,et on Concret 30.48 cm Concret Air.025 cm Iron Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons c 0.015 : Excluded Library : Grove becauerels pjCi/cm 2 010 6.0744e+000 4.5000e-OC Nuclide curies Eu-155 1.6417e-, 09 B1/cm6 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Activity photons/sec 1.933e 02 Fluence Rate MeV/cmz/see No Buildup 9.868e-85 Results Fluence Rate MeV/cm2/sec With Buildup 1.153e-35 Exposure Rate mR/hr No Buildup 9.780e-87 Exposure Rate mRlhr With Buildup 1.143e-37 CU-114 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page : 2 DOS File : PB122916.MS5 Run Date: December 29, 2005 Run Time: 2:55:49 PM Duration : 00:00:01 berer -Activity MeV photons/sec 0.04 0.05 0.06-0.08 0.1 1.101e+00 3.581 e-01 7.878e-02 1.886e+00 1.256e+00 Fluence Rate No Buildup 5.223e-45 9.111e-32 3.144e-26 1.200e-19 1.036e.17 Fluence Rate Me/cM2 /sec ,With BuilduQ 1.741e-33 9.238e.31 7.387e-25 5.472e- 18 7.855e- 16 Exposure Rate mR/hr No Buildup 2.310e*47 2.427e-34 6.245e-29 1.899e-22 1.585e-20 Exposure Rate mR/hr With Buildup 7.701e-36 2.461e-33 1.467e-27 8.660e.21 1.202e-18 TOTALS: 4.699e+00 1.048e-17 7.910e-16 1.604e.20 1.210e-18 Cl-115 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 licroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122916.MS5 Case Title: Line 1.25 J This case was run on Thursday, December 29, 2005 at 2:55:49 PM Dose Point # 1 -(138.78,381,137.16) cm 12/29/0 With Buildup Results (Summed over energies!Wi~thout Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 1.051e 016 1.048e-017 7.924e-015 7.910e-016 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.604e 020 1.400e*022 1.400e-020 1.210e*018 1.057e-020 1.057e-018 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 1987)mSv/hr 2.341e-022 1.283e-022 1.283e-022 1.242e-022 2.326e-022 1.803e-022 1,803e-022 1.313e-022 1.767e-020 9.685e-021 9.683e-021 9.372e-021 1.755e-020 1.361e-020 1.361e-020 9.912e-021 Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 2.012e-022 1.577e*022 9.735e-023 1.347e.022 1.072e.022 1.518e-020 1.191e-020 7.348e-021 1.017e.020 8.090e-021 Page Cl-116 Plum Brook Reactor Facility Final Status Survey Plan *. Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File: PB121913.MS5 RL ate: December 19, 2005 Runr'rime: 11:24:57 AM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.26 A2

Description:

Revised Model Calc. -Co-60 Unit Act w Sched 40 & 12 In Shid Geometry: 10 -Cylinder Surface -External Dose Point MN I Sour Height Radius[#1 134.97 cm 4ft 5.1 in Shield Name Din Cyl. Core 3.{Shield 1 Transition Shield 3 30.Air Gap Wall Clad .0 Source Input Grouping Method : Actual Photon Energies Nuclide curies becuerels WuCi/cm 2 Co-60 8.2087e-01 1 3.0372e+000 4.5000e-009-ce Dimensions 762.0 cm 3.81 cm)ose Points y 381 cm 12 ft 6.0 in Shields iension Mate.1 cm 2 Conci.65 cm Iro 25 ft 1.5 in z 182.88 cm 6 ft Density e 1.8 7.86 e 2.4 e 2.4 0.00122 7.86 aria ,et n Concret.48 cm Concret Air 125 cm Iron Ba/cm 2 1.6650e-004 Buildup The material. reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferential 20 20 Energy MAY 0.6938 1.1732 1.3325 ALS: Activity p2hotons/sec 4.954e-04 3.037e+00 3.037e+00 6.075e+00 Fluence Rate MeV/cmY/sec No Buildup 2.365e-15 2.935e-10 5.773e 10 8.708e.10 Results Fluence Rate MeV/cm 2/sec WithBuidu 7.879e-14 4.432e-09 7.308e.09 1.174e-08 EXpQS ,ure. RFate mRlhr No Buildup 4.566e-18 5.246e- 13 1.002e-12 1.526e-12 Exposure Rate mR/hr With Buildup 1.521e-16 7.920e-12 1.268e-1 1 2.060e-1 1 C1-117 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB121913.MS5 Case Title: Line 1.26 A2 This case was run on Monday, December 19, 2005 at 11:24:57 AM Dose Point # 1 -(134.97,381,182.88) cm Results (Summed over energies)Units Without With Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 6.834e-010 8.708e-010 9.262e*009 1.174e*008 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.526e-012 1.332e.014 1.332e.012 2.060e-011 1.798e-013 1.798e-011 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic (ICRP 51 -1987)mSv/hr 1.512e.014 1.303e-014 1 .303e-014 1.164e-014 2.042e-013 1.758e-013 1.758e-013 1.57le-013 Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 .1987)mSv/hr 1.609e-014 1.550e-014 1.550e-014 1.233e-014 1.362e-014 1.255e-014 9.987e-015 1.130e-014 1.OOle-014 2.173e-013 2.093e-013 2.093e-013 1.664e-013 1.838e-013 1.694e-013 1.347e-013 1.525e-013 1.350e-013 Page 1 Cl-118 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOS File : PB122121.MS5 RL late: December 21, 2005 Run- rime: 3:45:18 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.26 B

Description:

Revised Model Calc -Cs-137 Unit Act w Sched 40 & 12 In ShId Geometry: 10 -Cylinder Surface -External Dose Point Sour Height Radius#1 134.97 cm 4 ft 5.1 in Shield Name Din Cyl. Core 3.1 Shield 1 Transition Shield 3 30 Air Gap Wall Clad X Source Input Grouping Method: Actual Photon Energies cus becuerels Ci/cm 2 7.7654e-011 2.8732e+000 4.2570e*009 8.2087e-01 1 3.0372e+000 4.5000e*009 rce Dimensions 762.0 cm 3.81 cm)ose Points 381 cm 12 ft 6.0 in Shields lension Mate B1 cm 2 Conci.65 cm Iro 25 ft 1.5 in z 182.88 cm 6ft H Density:e 1.8 7.86 te 2.4 -te 2.4 0.00122 7.86 ria ret n Concret.48 cm Concret Air 025 cm Iron Nuclide Ba-137m Cs- 137 Qq/cm2 1.5751e-004 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Ener 0.0318 0.0322 0.0364 516 Activity photons/sec 5.948e-02 1.097e-01 3.994e-02 2.585e+00 Fluence Rate MeV/cm!fier. No Buildup 2.447e.82 6.519e-80 8.361e-62 9.264e-12 Results fluence Rate MeV/cm2/sec WithBuildu 3.431e-35 6.579e-35 3.666e-35 3.324e-10 Exposure Rate mR/hr No Buildup-2.038e-84 5.246e-82 4.750e-64 1.796e-14 Exposure Rate mR/hr With Buildup 2.858e.37 5.295e-37 2.083e-37 6.443e- 13 Cl -119 Plum Brook Reactor Facility Final Status Survey Plan Revision O V40, -Page : 2 DOS File: PB122121.MS5 Run Date: December 21, 2005 Run Time: 3:45:18 PM Duration : 00:00:01 Activity Fluence Rate MeV/cm2/ser. No Buildup Fluence Rate MeV/cm 2/sec With Buildup Exposure Rate mR/hr Exposure Rate mR/hr With Buildup TOTALS: 2.794e+00 9.264e-12 3.324e-10 1.796e- 14 6.443e- 13 Cl-120 Plum Brook Reactor Facility .Final Status Survey Plan Revision 0 licroShield v5.04 (5.04-00362) MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Conversion of calculated exposure in air to dose FILE: C:\MS5\DATA\PB122121.MS5 Case Title: Line 1.26 B This case was run on Wednesday, December 21, 2005 at 3:45:18 PM Dose Point # 1 -(134.97,381,182.88) cm 12/21/C Results (Summed over energies)Units.Withoutn Photon Fluence Rate (flux)Photon Energy Fluence Rate Photons/cm 2/sec MeV/cm 2/sec 1.400e-011 9.264e.012 5.023e-010 3.324e-010 Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air mR/hr mGy/hr mrad/hr 1.796e-014 1.568e.016 1.568e-014 6.443e-013 5.625e-015 5.625e-013 Deep Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Shallow Dose Equivalent Rate o Parallel Geometry o Opposed o Rotational o Isotropic Effective Dose Equivalent Rate o Anterior/Posterior Geometry o Posterior/Anterior o Lateral o Rotational o Isotropic (ICRP 51 -1987)mSv/hr (ICRP 51 .1987)mSv/hr (ICRP 51 1987)mSv/hr 1.856e-016 1.486e-016 1.486e-016 1.314e-016 1.973e-016 1.874e-016 1.874e-016 1.405e 016 1.641e-016 1.449e-016 1.074e-016 1.295e-016 1.102e-016 6.660e-015 5.332e-015 5.332e-015 4.715e-015 7.078e-015 6.723e-015 6.723e-015 5.041e-015 5.889e-015 5.198e-015 3.854e-015 4.645e-015 3.954e-015 Page Cl-121 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) Radiological Services, Inc.Page : 1 DOz File: PB122122.MS5 Ru ate: December 21, 2005 Run Time: 3:50:53 PM Duration : 00:00:01 File Ref: Date: By: Checked: Case Title: Line 1.26 C

Description:

Revised Model Calc -Eu-152 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylinder Surface -External Dose Point Height Radius X# 1 134.97 ci 4ft 5.1 Shield Name Cyl. Core Shield 1 Transition Shield 3 Air Gap Wall Clad Source Dimensions 762.0 cm 3.81 cm Dose Points m 381 cm 1 in 12 ft 6.0 in Shields Dimension Material 3.81 cm 2 Concrete.65 cm Iron Concrete 30.48 cm Concrete Air.025 cm Iron 25 ft 1.5 in z 82.88 cm 6 ft Densite 1.8 7.86 2.4 2.4 0.00122 7.86 z Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015: Excluded Library : Grove i becquerels ucilem 0)11 3.0372e+000 4.5000e-OC Nuclide Eu-152 8.2087e-('09 Bq1cm6 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial)Circumferentiaf 20 20 En..04 Activity photons/sec 1.797e+00 Fluence Rate MeV/cm-'/sec No Buildup 7.689e*50 Results Fluence Rate MeV/cm-L/sz With Buildup 2.295e-33 Exposure Rate mR/hr No Buildup 3.401e-52 Exposure Rate mR/hr With Buildup 1.015e-35 Cl-122 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 Page : 2 DOS File : PB122122.MS5 Run Date: December 21, 2005 Run Time: 3:50:53 PM Dur-tion : 00:00:01 Ehe 0.05 0.1 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 Activit photons/sec 4.493e-01 8.635e-01 2.276e-01 8.212e-01 1.909e-01 1.713e-02 1.288e-01 5.408e-01 1.300e+00 7.046e-01 Fluence Rate MeV/cml/sec No Buildup 6.370e.35 2.353e*19 2.237e.16 1.694e-14 2.807e*14 1.077e-14 2.537e-13 6.015e-12 5.202e-11 2.451e.10 Fluence Rate MeV/cm 2/sec With Buildup 2.389e-33 2.288e-17 3.535e- 14 1.920e-12 2.175e 12 5.981e.13 1.061e-11 1.608e- 10 9.920e-10 2.658e-09 Exp~osure Rate mR/hr No Buildup 1.697e-37 3.600e-22 3.947e-19 3.214e- 17 5.470e-17 2.114e-17 4.952e- 16 1.144e-14 9.589e- 14 4.123e 13 Exposure Rate With Buildup 6.365e-36 3.50le-20 6.238e.17 3.642e- 15 4.239e- 15 1.174e-15 2.071e-14 3.058e-13 1.829e 12 4.472e- 12 TOTALS: 7.040e+00 3.034e- 10 3.826e-09 5.203e- 13 6.636e- 12 Cl-123 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlicroSkleid w5.04 (5.04-W362) 12/21/05 ilcroShield v504 (5.04-00362) Raioiitlceal Setiices, Irec.Conversion of cakulated vxposure in aIr to dose FILE: C.tAdSS\ATA\P8122122ASS5 Csa TRtW¢. Linte L26 C This case was run on Wednesday iDeacunber 21 20025a 3:50.53 FM DM$ PIet P I # (134.07,1

• 2"9 M sgry.*p m ri Png§ unit, Aithout Su ildu I fk Phton Fluncse-Rate Okwix)Phton EmfEy Fluence Rate Exposure and Dose ORotesn LEposure Rate in Air Atibrtc D95v Rate in Air a Photonstcmrt/sec MeV/cmS/sec 2.235e,010 3.034e 010.996e 009 3,B26te009 rnA/hr rnGy/hr rrcd/fhr 5.2-03e 013 4-54e6 015 4.542q-01 3 6.636e-012 5.794e-014 5,794e-012 Neep Dose .Equivalecnt MatD a Paralnei Geo-metfy O CppO."w o Rotational a I Sis rapie Shal Dw Dose Equivalent Rate o Par-illiel Grmtry-a Upposed o Rotational E£lectivc Dos Cquivioleot Me-o A.nterior/Posterior Geometry a Poslerioet/Anterior o Lateral o Rotational a IstoDop, fICRP 51 -1987)rmn$Yhr N (ICRP 51 -1987)rr$ve/hr (lCPP 51 1 g7)mSv/hr I 5~ 1 54e-D1 5 4-46ae-016 4.46$e-01 5 4000.@-Ol 5 5.275e-015 5 275e'D1 5 4.219e-15 4i641.A15 4.292ee0415

$.44$e'0 15 3.872e.015 3.440e-0 15 5.682?e-0414 5 .079e-014 69.97e-01 4 6-747e. 0l 4 6 1476-014 , 5 368e-1 4 5-929e-014 S.46Se-014 4 36] c-t14 4.926e014 4.363e-C14 Page 1 Cl-124 PlmBokRatr FaiiyFnlSau Srve lnRvso Plum Brook Reactor Facility Final Status Survey Plan ,, Revision 0 MicroSheled Y5.04 (5&04-00362) Radioiagical Seivices, Inc.Page : 1 005 Fdi: P5122123.MS5 Ru ate: December 21, 205 R1nTime: 3:53:07 PMI Duration .D00:O]rule Ref;_____Date: Chec~ed: Case Title; Line 1.26 0 D'escrip -n. ReviJsed Model Calek Eu-154 Unit Act w Sched 40 & 12 In Shtd Georm;~rr. 10 Cylinder Surface External Doro< Point I Heighmt Radius 9 1 134.97 cm 4 ft 6.1 in Shield Ng Tranisition Shield 3 Air Gap, w441, Cad miarce Dimnemions 762.0 cm 3.81 cm Dose Points Y 381 cm 12 ft 6.0 in shields.Dimensior .Mel 3.51 cm, Conur.65 Cm Iral 25 It 1.5 in z 1828 c~m 6Gft I1 Density e 1,8 ,.86 Le 274 e 2.4 0.00122 7.86 iet I Concret.30.4 = cofwcret Air.025 cm Irgn Source Inpu~t Grouping Method :. Standard Ind-lees tNumber of Groups -2 Lower EneWg Cutoff -.0.015 Photons 't 0&015 : Excluded Library rrGiroe A 6-r-mi., re~t LI ~, /kml All11 3.0372e+O03 4.50O-00eX Eu-154 8.2087e 19 1 .6650e-fX04 The materala reference Is :Cyl. Care lIutegratron Paramieters Ciiaumterential 20 20.I E6. 181 ivit Results FlyencZ Rate LIMence ai1e MeVCrn2/SP-r ma.w/2.645e-50 7; -9e34 Exogsw re Rot 1.17Qe-52 With Buittluj 3.491 e-36 Cl-125 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 W Page ; 2 DOS File : PB122123.MS5 Run Date; Decemnber 21, 20D5 Run Tifme! 1535W7 PM Dur'tion : 00:00:01 E Adtivity 0.05 1.570e-01 0.1 1.2:29e+00 0.2 2.074e-1 O.4 2.167e-02 0.5 S 6,43 0.6 2.450eD0 0.8 1184e400 1O 9.343e.O1 1:5s 1 85e.00 Mlwn,rjc Sate~Ng FluOdom 2.26e-35 3.34ge-19 2,04&16 3.187e-16 4, 145 4.886- 13 1.317.e-l 3.740e 1 4,122e-10 Fluence Rate With BuIddup 8.349e 34 3.257e 1,7 3.221e414 2.470e- 13 2.2e9i 1fi 2.018le I 1 3.52le-14 7.132tl '4,471 eQ9 ,MR/hr No Buildup 5 g29. 3B 5.124e.22 3.5979.19 6.210.e-i3 $. 11 4e 18 9.41 9.16 2.506e14 6.0O4,eJ4 6.935- 13 mR/hr Wirth awiu d g.4.,982e-20 5,685e. 17 4.812e- 16 4*:5C0;n 1 3.939e- 14 6.697e- 13 1312] 51?7.523e 12 TOTALS: 5.789u+0Q 4 633410 5.F557e-09 7.885e-13 9.547e-12 CI-126 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Nlckr*Sh~etd vS.0D4 (5.04-0362> mi-croshielid V5.04 is;."4-0362) Radiological Seivices, Inc.Coriemioin of Cakculatad exposure in air to dom FILE: CA.MSS\DATA\P-122123.MSS This case was run on Wednesday, Decemiber 21, 2005 at 3:53-.07 PfA Qse~ Pointt 1~(3 31BS)12121105 SeAli1jr. 411mmari rypr RnPm'=%'JiJ Buedup M*.~ton En'efty fluence, Rate Photons/cm'f sec MIUVICM~1seC 3.295e-0 10 4,633e 010 4.1,g9e 009 5.557,e-009 Exposure and Doso Rates Exposure fRate in Air Absorbed Dose Rate in Air it mRlhr mGy/hr mrad/hr 7.88se-01 3 6.884e.015 S.88eO 13 9-.547t,0I2 B. 335e-014 8.33 5ct01 2 o Pasrallel Geommetry Oo ppnsed o Rotational Li Ito1lropn Sha~lifo Dose Equivalent Rate o Par~mi-el Goc-etry o G)'.Pose'z o RotationoiI a Anterior/Posterior Ga-netry 0 P0.SericrlAnierior o Lateral1 o Rotational o isotropic (ICRP 51 .1987)m~v/hr (ICIP 51 1M7)mS'vlhr H (lCRP 51 1487)m5V~hr m 72.02e.O015 IS.744eO 15 6.784e.0 1 5 6.080e.0 15S 8 .264e-O015 7.~19-e-015 7.991 emO1 5 6 .40S-e-O0 5 7.02%-.Q] 5 6.5129*015 S .24&e.O1 5 5 .B7ft.015 5 .233e.0.15 9.466e- 01 4 S. 194e 014 B. 194-e-014 7?.334-a01 4 1.004e-01 3 9.694~-01 4 9.694e-01 4 7.738e-014 8,52]aUD4 7-873e-01 4 6.311e014 TIOle-014 6-305e-01 4 Page 1 Cl-127 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Microihleld v5.04 (5.0400362) Radiological Services, Inc.Page :1 1 DOS File: P8122124.,MS5 RL .ale: December 21, 2005 Rkun-ime: 3:54:55 PM Duratio: 00:0P:01 File R1_;Date: By;Checiked: Case itle Lir L26 E

Description:

Revisod AT9o e- Al-108n U1,1ni1 Act w Sched 40 & 12 In WhAd Geemetry: 10 -Cylinder Surface -External Dose Point a t -, ", I I Radiu# 1 134 Y97 cm 4115.1 ifi curce Dimensions 762.0 cm 3.8.1 cm Ir 381 cm 12* t6.Oin Shields ,)itenslon e 381 cmn' Conci.65 cm iro 25 ft 1.5 in z 182,88 cm 6 it I Density te 1 8 7.86 te 2.4* 2.4 0,00122 7Mi p Cyl. cve Shield I Trtesition Shield 3 Air Oap Wal8 Cad I Goncret 3DAS Cm Conicet Air.025 rm Iron rot n Souruc input Grcuping Method: Standard Ind-ies.Number of Groups :25 Lower Energney utoll t 0.015 Photons < 0.015 : Exduded Library: Grove he 4-ot/rems Ui/m?7 e-011 3-h372e+000 4-5Me-0 Nur-idt Ag-108m 8.2087i D9 1,6550 W004 Buiildup The material relerence Is : Cyl. Core Integration Parameteys Y Direction (axial)Cicumterantia, 20.Activity hohtorns/sec 1 .992c+D Flente Raty Ng R1.5 id0 1 51 oe-2-66 Resuhs FIluence Rate 2iLth af lUgg 4,338e34-1 .2 13 0 eil.f2 6 5.230~e-M Esxposure Rwtp_With R 35iun 1.503e 35 Cl-128 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pae : 2 DOS Fite : PB122124.MS5 [un Date: leeernber 2], 2005 I-own TXmre 3!54:.S5 PM Dur.*tiui: 0:00:01 imar- Adivity 0.03 6A40e-07 0.08 2 152e-901 0.4 2.73e40 0.6 2. 745-O0 o. Q8 2.749e#0 Fluenc*= Rate M.ecrfflpel No Builftd 2.76i3e " 2.34se-22 4.01 se13a 5&4 08ec12 3".Q57e-1I 3.63Be- 11 3.106e4 1 .293e!20 3.112e-.1 2.we2 10 841719. j Logige Rdl -UQ) RI 0iep 2.739e101 3.7 1f. 25 7.824e- 16 1.056. E4 5.815e 14 Emxsuors Rate With guildulg 3.078a.42 2.047e.23 6.063e-I 4 4.414e 1 3 li554o 12 TOTALS: 1 .043a+0I 1.074e.09 6.949.e 14 2.056- 1 2 Cl-129 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 AfliciothWeId v&04 (I..C4-15090) MicroShield v5.04 (5.0-4-00362) Randiological Services. Inc.Cornversion of calkulatcd exposwre ivp air to dose F'ILE: C:\M3S\DATA\PB12Z124.MSS This case was run on Wednesday, December 21, 2006 at 3:54:SS PM noePoint IV 1. ~J14.919 1,U2SO~m RgZ~1 5 (SqrTwvg~d Mpr energies~ Witjhrujlf 12/21/05 Photon r'lu~rt.o Riktr (flux)Pttoton Energy Fluence Rate ULposure arid Dose Rates tLxrooure-Rate ir Air Absorbed Dose Rate inAir'Nee Dose EquiYatnt Rate oa Paraflel ( etr~y-o Rotat~onal 'o l1-4Opic SI-aiimwl Omse Equivalent Rkot o Parallel G&e&~netry o Rotational o ArntergiorlPostenior Gieoretfy oLatoral ai R~otat'~onat ai Isotropic Photons/9T/sec mR/h~r mliy/hr mr-ad/hr m~v/hr M 4.823e-0 11 ,3.6309-0 11 6.949ge-O14 6.0&5eVJO16 6.066e.0 14 7.1 D2e-0O16 5 .79OeQ16 S .790e.016 5.118e,-016 1 .4 76e.009 1 .074e.009 2.05~6e.0 12 1. 795e.O 14 1.795e-01 2 2.10~8e*014 1.71le.014 1.71 1c014 1.512e-014 (ICRP 51 19A7)rnSy/hr pi (im.p 5I -m:Sv/hr N 7.582e-01 6 7.227c-016 7 .227e-01 6 5.4 76e-016 6-31 4 c-016 5-633e-0 1 6 4.245eu-O 1 6 5.O39"O1 6 4. Mv2,V 1 6 2,4v014 2-141-e-014 2.14 le-014 I1.618e-014 .1 872e-01 4 1.%6$t, 014 1-25le-D14 -4190e. 014 1.2-76e-O1 4 Page I~Cl-130 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 Microshield V5.K (5.04.0362) Radiolaglcal Services, Inc.Page -1 1DO:t Fire : Pi221,25NMS5 RF sit: Cecember 21, 2.*5 Rrn iTme: 3:56:37 PNM Durativp :p ;Q!file Rd_Date:_By';;hersed;Case Title: Line 126 F

Description:

Revised Model Caic- Nb-94 Unit Act w Sched 40 & 12 in Shid Geometry: 10 -Cylindet Surface -External Dose Point lC E= - c I.i.i HeigIt FPadius s 1 134..97 cm 41 ft 5.1 in wurce Dimensions 7~,52 -m 3.81 cm Dose Points x-4 .Lrr, 12ft6C.rn Shields) i rr,,rr ,gi ,n~ a-;g.681 cml Co n C:onci I,').i ; r iQZC 25 tt 1,5 in z 182.88 cm 6 tt iI Leluletlk e 1 .8 e 2.4.w 2,4 1 86 e SF-i.*'H lKinma Oyl ccore Shield ~Tranilrf on S;hie d 3 Air Gap, wAl aII C Ilad ret ret'tli.S rm l r Nt-94 Sour'ce Input Gtrouping Method -Actual Photon EDergles r? Ijie% I rNt, r *is ! rL 8 2387-31'.

3 0372vA-(jOJ 4 5i50

3(J 93 RrThrr9 1,565C; 004 Buildup The malerial relerence Is t CyL Core Inrtegration Pararneters CY Diretion ra i-'rcumfrntr;ntia; 20 20 0 8174 K.0175 0.O196 rf 7 026..,._711 1.074e-03 2-C*57e -03 6 04AcQ4-3'037e+QQ 0'000Ga+00 0.000e-.-01

514e- 1 1 Results Mb'th QW}1,94-W 1.878e -3.632e-37 1.2Thie 37 5.-1c9.a0 1i3010-0 ExDowry Rate mRJ/hr 0.ODe+W 9.584e.287 3.016e-14 1.043t:'13 ,FXwgriles Pail~mR/hr Wdit rjuiir1ln, 1 .923e- 38 4.710te39 9.853e 13 2.449e 12 Cl -131 Plum Brook Reactor Facility Final Status Survey Plan i I Revision 0 Page .2 E0S File , PS122i25.MSS RiMn Date. December 21,'2L05 Run Tamne. 3.S6.:37 PIN Duration : 00:00:01 knomy may Activity boatonqfeL Fluence Ratee hM.NJCm~jee NC- K ilk I Fluence Raw.MIVmtIer ith Bauilrp Exrmsure Rte.mPfhr ha Bu~ildup F3(rxljra R;Ztfe i MRIhr With Ri~ifrItir' TOTALS: 6.07-et4 7107.11 1.1 e2e,09 1.345e-13 3.434e. 1 2 Cl-132 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicoSNetdv5.04 (5.04-00362)

UicroShi;Id v5.04 (5L044-M~62) 11adilclegial Services, rInc.Cowersion at calculiIed exposure In air to iflse rILE,- C:\USS\DATAkPB122125.MSS Cost Tktk: Lipe 1~26 F This case was run on Wednesday, December 21, 2006 at 3:S5&:37 PMA Ewimults MSimme=d 4ver Pnrr~ies) Withou 1/2105 with Photn Fltmve Ro.i-tt (ilux)Ph~oton Eneijy Fkuence Rate!Ph~otoris/cmn/sec MeWfcm-?/sec $aS$Sle Di 7.107e-01 1 2.22l1e-009 1.81 2e-09 Expo~sure arnd Dose Rates-Exposure R~ate in Air Absbrbed Dose Rate in Air w MR/hr rnGy/hr mradlhr 1 ,345cefl13

1. 174e-01 5 J. .174-01 3 3.434e-01 2 2 ."9eDI14 2.9~98e-012 o Pa ra~lel Geometry o Rotational Sh'orw -Ds Equivalent Rate o Pe ianIer Geometfy r3 Opposed o Rotational-a Anter or/Poster or GjeG ~try o LateraIi io R-otabonal o iSO1ropic (ICRP 51 -1087)mSv/hr I.ICRP 51 1987)mSv/hr (ICRP 51 1987)rnSv/hr K] .365e.015 1. I25e-0 I5] 125e.015'.~94ZeQ 16 1.460e-Q) 5 1 .393e*-OI 5 1 VVIVe9 i 5 1,217e-015 8.309E-01I6 9.78Oq*O1 5 8.4 30e-01 6 3.A8Be.Q14 1-871 e11 4 2.87 le-O14 2. 5399-0 14 3. 730e-O 14 3.559c,014

,3.55ge-014

2. 7]6c.O14 3.1IO~e*Q014 2,788e-014 2.496e,-O04 Page I Cl-133 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 RllcroSkleld vS04 (5.04-00362)

Radiological Services, Inc.Pap : I DOS Fire : *11122917.IVS-5 Rt etc: Dvernetr 29, 2Of5 Funm f.me: 3:04:1.2 PM Duration:

00. 01 File Ref: _VP.te___ ..By:-Checked: Case Tiitle; Line 1.26 G

Description:

Reised M4$Iel Craek [i l> Unit Aet w Sched 40 & 12 in Sltd Geomwetry: 10 -Cytinder Suirac -ExWrnal DPsG Point C i i I Heaght Radius w 1 13497 cm 4ff5,3 ii Qhield U;Imgr , W.a~ ;--'are Shield I Transik-on Shield 3 ;Air iZ3p.6i,. C!aIc wu~ce Dimensions 762.0 cm 3; l;1 ;;mr Dose Points 1 2 ' c , C,. .-25 ft 1.5 in 12.88 cm e 1 .8_7.5 pa 2.4 c: 2.4 C B ,oa 22 Shields 4.:1 Cm?.b9 tmrrl 41 OCrrIc ret Ir:..: .3C 45 cm 2.rC fel 32,.48 rrij .i93qC~ret Air C-25 -:rni I 'or SOQnC9 IRpLIt Grouping Method -Actual Photon bvergies hla WrJ; U I b-_ZuLje~gs 'Y@.Scifler 1 ,129 8; 2 -X. 1 &3 72c+COQC 4.5 C Civ fCOr 1 C: £fI wuillup The maleftal reference Is : Cyl. Care IInteEtation Parameters Y D'ire'c-:on (axial)Circrumlere.tia-20 20 0.X3295 O.,0295 0,0396 0.0396 I 6.06 1 e-01 1. 1240+0:3.9w98 o: 2 284e0_Flunce Re Nib Ruilrdun 1.1Se ,97 2.055e-94 4 M7e 72 9A463e ^r52 Fluence Ratre MteV/crrl1/sar_ With Blu11dup 2,77 .34 S.302e*.34 2,76f8$4 2,814.34-FZxgosurg Rate-mR/hr No Buildup 1 .87s 99 1.06ge-96 P.039! 74 4.3300e.54 mh/r W'J h 80I~1fu-"N 2.902e*36 5.372e. 36 1, 969p .36 1.279e^36 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 PagE , 2: DOS File P8122917,JS5 Run Date, December 2P, 2005 Rvui Tiare 3:'04:12 PM Duration ; OX:Q0-1;;TrL5 2 AtivilO pfT pht-ons~~ee TOTAIS: ,2.359iD*00 Flwynf* Rote lo S2uild 9,46-3452 Flu3ncg Rate With Bfilur~n 1.366e 33 Exrsooure Rate Melt Nto BtUI du 0 4 XJ00 f54 Ex~surEp Bid O'VARhr With BSiLuo.1.1 .529-35 C1-135 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 Mkru5hickd v,04 (5.04.0O)362) 2129105 MicraShicid w5..04 (504)0~362) Rad~lolgJcal Services, Mec.Cimvers~lon ai calkulaRed exposturt in air to dos*nLE; QWri55\DATA\PB2229217;MSS Case TItle: Line 1..26 11 This cost was run. an Thursdnay, Occember 29, 2005 at 3:04:12 PM Dose Point W 1 -(194.9?,39L=08.B) cm R~esults (Srnrned over en~erieoUW =gu 4.,256e.O32 1 ~366e-033 Photon Fner R-te Rat te)PhDton Energy Mixence R~ate Photons/c~rW/sec MeV/C1W'/We 2 .3gle*050 9,46e'O52 Expo.-ure and Dose Rates E~xposure Rate tin Air Abso~rbed Dose Rate in Air a ImRthr rn~y/hr.nrad/hr 4.300e-054

3. 75-4c;05 3. 754"S04 i 52e-3$5 L OO~e.O37 I .006e'Q35 D'gcp Do s Fqu valont R~tiv a Parallel Gec~etry o Rotational U lsuirupic~

SNi11rrw Dose EquNalent Ratte O Parallel GVimryv-Opoosec" o Rotational U I q0"!or-ce o Anterior./Posterior Ge~metr'f ci PoseriaiY!n'eriar.o Rotational (ICPP r.i .9-M$V/hr mSv/hr 2,7O'6e*056 2 .450e*056 2 .344&.056 5 .406e*056 3 .732eOQ51 3 732e.056 2.7 39*-056 L,894~e-056 I .703e-056 I .$$$e'056 5. 776e*O038 4.92a6e.038 4, 5 7 6e-038 1 .255e,037 15.6301338 8.630e-O038 5 62e.37038 L669e-O389 1.44 le-038 2..652e-0D31 2,.197e-038 Page I Cl-136 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mlcro~hield YS.04 (544.0-362) Radiological SeiTvices. Inc.Page .I 009 F Ile PBO10405.MS5 FLt ate: Jantvary 4, Wont6 Puii Time! 8O!018I AM DuratiGan

00

0001 File Ref:_ __Da _:_By: Checked: Case Metls Lino 1.26 H Doscription;

!Rvjsd Mo~dt) Cal- Sn-I26 Unti Act, V $ched 40 &A12 in SW~Geom~etry: 10 -Cylinder Surface -External Dose Point IMeght Radius g t $-4.97 cm 4 ft 5.1 ..n SI-'f-Iff tJ:%M~ I COd. 'Ccc Shield~ I Shield '3 I Air _ o WIl _d,'wroe 01menslonai D~ose, Points£2 iiE0 -Shields ,65 cmn I rc 25 ft 1 S in z 1B92.88 cm 611 e .~.864 o 2, e .0.0L7'et 4 3048 cm Crncreti Ai!02.5 cmn Ia Sc~urc~e Input Grou~ping Method -,Standard Indices Numkmr of GCroups -2 Low~er IAergy Cuztolff O..O Photons < G.01I Excluded Library : Grove______Lip, WLC'/4; cm l D1 1 J O,372c+000 4,CO0v.-CC Nucift- cur=Sn-126 8.2087e,4 Ig 1 .6650e-034i Ru~idup The material releience Is +/- Cyl. Core Integiration Parmneters. Y D'iwreton (axial)ci rcumirnoatez~a 20 20 2.351le-01 12781-e267 5.1200e.5 6.172e-269 F~xoozur4 Ratm mRl/hr WAh I~ijiqdut, C1-137 Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 Pge 2 DOS File P801405.MS5 Run Daite: *anuary 4. 2006 Run Time- 8!0818 AM~Dumberi : 00-0-: EMW AdiX4is 0.03 8.93e-Ol 0.G4 1.51e02 0.46 2.91 1e;0)0.08 1.395es-00 Fl~uence Rcat.MeV/m2scp 3.81 le-93 6.401e-0;2 4, 132e-28 1.5Me-21 Fluenee Rate 4.282s.34 1.937e-35 l.Zlle 26 ,380e 2Q Exsugre Rate 91MLL~i NDo Buildup 3.777e-95. Z,871eS4-a.208e.31 2,408e24 Exposur rm~hr Wih 8w1l1u 4.244e-36 8,5we 38;2.404e-29 1.326e*22 TOTALS: 2.825e+O 1 .522ei21 8,380e20 2408e 24 1 .326e.22 Cl-138 .Plum Brook Reactor Facility Final Status Survey Plan. .Revision 0 11IcrDShlield v5.04 (5AQ4-OQ362) Micro~hidld YS.44 (5.04-O0,62) Radolofgical: Services 1.Inc.Commersion of, ~u~claId exp~osore 10 air to dOS'e r'ILE: C:\fAS5\DATA\PF0104O5..MS5 Cms Title! Line I.26 L, This case was run an Wedfnesday, Jamuary 4, 2GDG1 at 11:8:128 AM4 PDOS4 Poiuit #1I (134.97M 1 3I$2.AM ~'Rlesults (Summed over enenr~ies U4 ihu 0104I0E Wmb Sul4dup"4i-ton Ereatsv flIenc-e Rats.MOV/CMI/sW 1 .902e-020 i .5220.Q2]1 .048e-01 8 8.380e*O2O Ex~posure andc DoseRts Ex~posure R~ate in Air Abwrbe'j Cim Rate in Air I mR/hr mGy/hw mrad/hr 2 .408e.024 2.102e-026 2,102e?24 1. 326eO022 1.158e.024

1. 158c.,022 ,.Ieep Oc.; Equ iy-ant R**o ParatlIef G~erc-mtry ai 0O;Pq%-d o Rotationajl a I gatopic Shallow Dose Equivalent Rate o ParaIlol Qor-*Kry O rOP-4Sed o Rotational iU kotropic~(ICRP 51 1987)m!Y/hr (ICRP 51 *1987)mbyfhr I.r67 7c026 1 .958e-026 1 .890e.026 3.6421e026 2.677e.0216 2.$77 e*Q26 L 9658.026 2,02 5c.024 1.079e.024 1 .O48e-024 I ,0 4 1 e-024 2 .OO5r.0249 1.474e-024 1 .474e.024 1.0820Y24 Effectie Dose EqLziv~kIcriI Ralc a Arnter.-or/Posternor Ge-aretry o Posterior/Antetrio~r ra Lateral o Rota"~ona' o Isotropic (ICRP 51 1987)mS-y/hr I 3 M88.0216 2..356e.026 1,452c.026 2.006e*026 1 $?4Q~f 1.701e*024 a 2g 7e.O24 7 .995e*O25 1. l05e.024.~[')71-2 Page I Cl -139 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 hlicroShield v5.04 (5.0440036.2)

Radiological Services, Inc.pPage 1 DOS File : PB122919.MS5 FN ate: December 29, 200 FN6f~ ime: 3:09:53 PM1 Duratirn ; QO';QQ;Qj File Ret_By: Cher*ed: Case Title: Line 1.26 1

Description:

Revised Modei Uark Zr-95 UnH Act w Schcd 40 & 12 in ShId Geornety. 10- Cylinder Surface Externai Dose>Paint .1 Sour Heght Radius W ] 134.974em 4ft 5.1 in Cy, re 3J Shield I Transitiorn Shield 3 3G.Air Oap WalT Clad .0 Source Input Groupingr Method : Actual Phton Enertgles he3 ii jrP I ir Irm'7i-G1 1 3.Q37ZvQCQ 4.?OQ0vQ?9 ce Dimensions 762.O cm 3.8.1 cm ,ose Points r 3481 ern 12 t 6.0 in Shields 1.25 ft 1 4 In z 182,81 cm 6 tt 1.86 2.4 2.4 0.00122 7.86 ipsro;iofn Mtripl,.1 cm' Concrete.65 cm I roa--ncrrte 4.8 cm Concrete Air 25 cm IrGn 1 Ri/rM 1 .509-mQ UL Buildup The material relerence Is : Cyl. Core Integration Paraneters Y Direction (axial)ivcumferpentia, 20 20 Ea V Activit.: 0.7242 1 26e+1O 0 75E7 I.68le-00 ice ,Rale 8.182e: 12 1.347c41 1 Results Flrrence er 2.550e- 1 31922e. 1I Expasur,- Ratt LS713 14 2 .57e- 14 Pal mllhr With Hi3t1LJuo 4.903e 13 7.507e. 1.3 TOTAXL; .gQ7s+g3 216se} 11 6.42;e- 10 4.52el 14 1.241e l2 CJ-140 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mk'raShield vS.04 (5.04-00362) 12/29/05 MicroShicild Y'5,04 (5.04-M062) Radiologiccal Services, Inc.Coiv~rslO" of ca.kuiat 4exp"Uire Irtair io dou MiE: C:\MS5\DATA\PB222919.M55 Case Title: Lin~e 1.2$This case, was ruri on Thursfta, December 2, 2005 at 3:09:53 PIM.Doe Poinit *C1(~.7.$t~~ cm Roult; 45umrnprd twor ang- mem).Ur=i Without au d~E.dA Photon Fivret Ra~te (flux)Np1~ton Eeroesy Fluence Rate Plhotions/ernk/we MOMeV/isac 2.911Qe~Q] 2..165e-0Ol1 & 704e-U1 0 6.472e-01 0'Exposure and Dose Rates: Zxposure Rate In Air Ab.%Qrtv Duo Ratv fin Air I mIR/hr rnGy/hr mrrad/br 4-.152ce014 3..624e-016 ,3624e-014 1.241le-;12 .0$31. 014 10.&3e*0 12 7~ucp Dose EqvivoIet Rato lo Parallel Geo metry u) Oopo-Vi lo Rotational Shallc' Dose Equivalent Rate o Para~IeI Geoma~ry o Rotationald a .I ! f ] i Effectivo, Dose Equivalent Rate a Anterior/Paster~or Gevimetry a Postenror,'Anterror a Laiteral a Rotat~ona~ a I 50tfupic (ICRP 51 -1987)mSvfhr (ICRP 51 -1987)mrv/'hr'I.ICRP 51 -1987)m~y/hr a 4,248eOJ3 6 3 455.43-036 3.4 5Se-0i 6 4.536e-0131 4,322o-J1 6 4.322-e-016 3.269CeQ 16f 3,773e-016 3.361e416l 2~.527c,016 3,006e.O 16 2.575e.016 I .27Qc.0 14 1 .033e-O 14 1.033E-014 9.128e-015 1 .356e-014 I 292,ci14 1.2-92e-014 9J.70a,-015 2 .128e-014 I1.005te 014 7 554e-015 8.1986e-D1 S Page I Cl-141 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 fficroSJkid v5,04 (5.04-O0362) Radiological Services, foc.Page l D~rFvra : P82292Q-MS5 fil atV Decamter~ 22 W N#ua Rof- ______I .I C~ise Ttif*: Line 116 J estIptirtt ROY Ised Model Calc- Eu-155 Unit Act w Sthed 40 & 12 In Shid tr~1 Cylihdet Sudface -External Dose Ponin H1 1149 m A ~K in 6 ft ceA-11. I -.';Ap ( WV , u, 48 :-,I $ 1 , 4 Z , -Samrte Inlput GtOirp*1 ng Kothod -Stamdard Indices Notibet of Croup% 25 Lower' Eiwrg CitOW 0-01S Photorns 4- 015 !Exclu~ded Llbraty .Grovia 01 U 3..0372al-O00 4 00eO N Eu -I 'WfiLm~'The mwtarlaf WrtwttiV k CYI. Coar Ijttiegrstvni PFrmin otm Y Dlevaclion (axtia') .... 20 9.V 6 & .O Results 4.142e q5 4.5r3 C4C5097 mEgnur Rb ti 4ma1m Cl-142 Plum Brook ReactorFacility Final Status Survey Plan .Revision 0 Pagre ; 2 J -DO$ File P8122920.MSS Run Date .December 29. 20C5 Run time: 3:11-41 PM Duratin : 00:00:0 gd&=? AroyHy Imom =10ALM2 0.04 0.06 0.08 0.1 5.505e.01 1. 791J c1 3.939e"2 9,041C 1 6.27901 Flimmnre RAn, 2.356e..0 2 538e,35 5.693s-D2 1-02% ,2 L.711e19 With Hijldon 7,031e 34 9.S22e 34 1638e-27 1 664e 17 Fxnntrp *atp.l~Nn Ri d Irlop 1.042e-52 6.7620e3 1.ll1e-31 1.62 124 2.618e*22 Ecsure Rate Aitsh Rniii¢h , 3]1090.36 2. 537e 36 3,254e 30 a.g68e 23 2.545e.20 TOTALS; 2r-5Q+0Q 1.721-19 1.66.- 17 2.634e.22 2.554e-20 Cl-143 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 blicro5blelf r5,0 4 (5 4 G4s00362)Microdbield rS.04 (5.444M62) RadlolqOgcal Servime, Inc.Cmwcrsiun of calculated exposure in air to dose rTHE: C:\MS5\DATAkPB122920.MS5 Case Title-. Lne I-ZS J This case was run an Thursday, Cucembur 29,2005 at 3 :11:41, PM~Dose Polint I 1.(134.97 4 148LIS) cm 12/29/05 8"Ai Its (Surnrnd Dyer eneqgiWs Whntif Ph~oton Fluijicie Rats (flux)rIPton Enefgy Fluence Rate!Phat~ns/crm 2/sec Mevicuesoc 1.724e.018 1.671e-016 1,721c.019 L669e-017 Exposure and Dose Rptes: Exposure Rate in Air Absorbed Dose Rite in Air U mR/hr rnGy/hr mrad/hr 2-634e-022

2. 299c,024 2.-2~9ge*22-2.554e*02QO 2,230e*022 2-2$OLe020 Dheep Dose Equivailont Rate io Parallel Geortnetry in Oppostd io Rotalt' ona~, Shal;,Deo Dos Equivralent Rate in~ rar-A lei Geclcr-etry.

a Qpocsed cl Rolotionol o Isotropic Fi4~fivo Close N~UvI~aent Mott a0 Antedor/Posterior Geornstry oo Iosierlav/Anterior io Latema lo IsQoropic mSv/hr (ICRP 5 1 -1q87).mS-v/hr (UCP 51 .1987)mS~v/hr 0H 3.844e-024

2. 107e-024 2. 107e-024 2,03go-024 3.819cQ2 4 2.962e-024 2.962e-02A 2,1I57e-024 3.304e-024

2.591 e-24 1, 599e-02, 4 2.21 3e-024 j-70~QVg2 3' 727e 022 2 .044e-0O22 2 .044e-022 1 .978e-022 3.?O$~1-022 2.873e-022 2 .873e-022 2.092e-022 3-204e-022 2 512#-022 1 -55le-022 2. 146e-022 I ,797c-0~2 Page I.Cl-144 Plum Brook Reactor Facility Final Status Survey Plan Revision 0.Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Microftield Y5.04 (5.04'00362) ftRadiologlcaI liervcei, Inc.Page :1I 1)0L: FileI 151:11-$RL. ate:- Docern~ber 19, 2(>D5 11unfTime:.

1:09:20 PM Duration QU0;,0-0:2 F~ile Ref: _ _ __ _ _Date: _ _ _ _ _ _By-, Checked: ______Case ioi LUns 1.641 A2 PescriptioI1: Revised Model lcak- Cv-60 Untn Act w Schedl 40 & 12 in 5h1d Geometry: 10 -Cylinder Surf-ace -External Dose Point.Sour HXI~eiht Radius#1 141.32 cm 4 ft 7.6 in Shield Name pj, cyl. Core 10, Shie~d 1 Shietcl 3 30 Aik Gap WallI Clad Source Input Grwipinj Alethod : Actuat Photon Enerpies 2.1 D~jID 8 O992e+000 4..50~00e009 tis imensions 762.0 cm i0.16 cm)gle Mmrr 38: crc.I1241 G.0in Sh~ods itension~ 2=&16 cml Conci ,.65 cr Ifo 25 ft 4.- in z 91.4 c 3ft I 1erlsUt 1.8 2A A 2.4 G0C122 7.86 rete an Corcrctv-48 cm Concrete Air)25 czrl Iron Co-60 1L665Ne{34-Buildup, The material reference Is : Cyl. Core Woegration Parametets Ci rcurnfortPti8 20 20 O.6938 XBI L?03 1.32 8.0990+00.- TALS: I 420Qe4-Q Results 1 OBe 1 3 2.302e-12 I 2.C'9Se~ Ifi 4.444a. 1.5 72209 7.78-6e.08 I13033e. I 1. 391 e*Ic0 1.25E4e0o 2.11S2e*l 1JZ002e.10 1.98 elos 1.933e"07 3.485e11 Cl-145 Plum Brook Reactor Facility Final Status Survey Plan , .Revision 0 Mji,&rsah1d vS.O4 (SMWO4O32) 1WS/M fficit~6hlod v5AP (5,04-QD31P) RAfdkciagIfa S0vvke. lIne.Convevsilom of 4ia~cwalas mrpasurt in air to dess 1FILE: CiAMSI\OA1AP0121916JOSS Cairn Titl; Lime 1.641 AZ This case was om. owm Maondiyk PO*m~ber It. 2005 at 1:09.20 PIA Dot. Puln #I -(14L3Z?381r09L44) on i Pesiuots (51umgmd owpr Pnprcg,.<,~ IM44M0, f 1I.;pirdbnh F1kieic. Rile (Cux)I11-41on Eiwgy fluernce ftate Mevcitwisec 1.65toas 2.53OILOO0 1.987e408 1-933e4O07 T'Npature and fjL)*,.Rtw Ab2,,rbagd Dps49 Rate in Air U m"R/hr may/h~r mead the 3 _A85-01 t 3O41~,13 3 043c. 1:3,39ft O1 2 9G3. 012 2' 963e,010 ()ep Pose Equivalint Rao~o Paral lei Geoa-*tty o Opposed, o Rota~onal Shaliovo Ctfse:Equiva~er,: F'ate tYCRp 51 1987)U 3 Mi44013 2 975, 013 3.677e-013 3,W540~013 3.540e. 1 3 ZA1Vi03 3 018'1012 2.587. 012 3.15 012 3.4484-01 12 31448.,012 2.74 It 0 T2 Eifrtij Dow Eqvivalent iRal or, c~Pstr~ Ge-&,fretry rjP";, __ 7 n ;fr r ...t 0 (iP 1 If~7,)Frr.., Y.hr I 2.2809-0 13 2.284e.013 2.231 S. -012 2,512& 012 2,223vD12 Pap I Cl -146 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 kficro~heIld vS.04 (5.64-0032) Radiological! Services, Inc.Page -I OW- File -~PB122126.MS5 Fo ate Dcecrnber 21, 2005 Run -Tirne., 5:,32.49 PM Duration :00;00;01 File Ref:__ _ _ _ _By:.Checked:____ ___Case Title: Line 1.E41 B Description; Revised Model Oak- Cs-131 Unit Act w $ched 40 & 12 In 9hid Geemetry: 10 -Cylin der Surface -Eftemal Dose Point F1 ---" -.' ~ ; ~~ -;,, " :.%, X Height Radius Souri I.Ca.137m#1 141.32 cm 4 ft 7.6 in Cyl, Core 10i Tr nsitiwq Shietrd 3 30 Air *i~ap Source Input Grouping Method -.Actual Photon Einergies clure,_ eaur uci/r-sn9 2,0708t-0O1O 716?10e443W 4~~ 2,570e O0 2. 1890e .01 0 8.09'2e-000 4.50Ca0e.0C9

.e Dimensions 762.0 cm 10. 16cm 12 ft 6-.0 in Shields 16 cm, cor~cr.65 cm IT01 25 ft 4-0 in 9L44 cm 3ft 1.86 I 2.4 2.4-.1122 7.96 Lit Ores an Cnnicreft 48 cm Concrete Air 125 cm 'Ron 1 .5751e-004 1 .6650le-0Q4 Suirdwip The materfal relletence Is -Cyl. Core Y Dire~t~on integration Parameters

'Y Drecion(axial) Circumferential 20 20 CMi Ativit 0.0318 0.03.22 P ',364' 316:4.5864-131 2.927e-01 Ii~u6$Lv-o 6.894*00C Fluen'ce Rate No Okldiur.2.1 95e-6iS 1 .92.4e-653 1.8 19e-49 4.527 b10 Rus uttE Fluence Rate wqVm'/spc With Builduri 1. 383e-34 2.652e.34 1.47/8e-34 1 021e0 No Buildup~i .828e.67?1.548e.65: .033e-5: 8 75&-13 E Y'ur R/hr 2.i34e*36 1.979e.1 II C1-147 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 POWS File -P5122)G.MS5 Run Date -Decerfbe 21, 2005 Run Time: 5:32 45 EM Duration; QODOM EneTAS Adie+ty TOTALS: 7.452e+00 Fluenn e Rate 4.51ea R!4.511e.lO FluOene Rt 1-02eVfz.No Buildu 8,758ce 13 I l rx.itr-h Et 1 g 1 .97ge-I 1 Cl-148 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 r11kvoShleld vS.04 (5.04-00362) MicroShield v6.04 (5.04-00362) Radiloogical Senices, Inc..Conversion of WculIrlated exposure In air to desc FILE: C:%1TS5%DATAkP6I.22126XMS5 Oms Tftlo- Lloe 1.641 B This case was nw on, Wednesda~y, December 21. 2006 at 5:32:49 PM Dmse Point st 1- (141~,U38i1,0A4) arn 12/21f5 Results ISummgd over enaiesW lUs PhWlon Flwee~ Rate (flux Nvoton Eneirgy Fluence Rate Excposurit~nd D~os Rates-Exposuret Rate ain Air Atsorbed Du Rate in Air co PeralIe! Geomnetry ri C;po*V-1 o Rotational U 1ec2¶'uptC Photorkrri 1/5ei KMeV/Crnk*/eC mRlhr mGy/hr mnrad/hr (ICRP 51 1987)mSvlhr U WlIhrmlt 6.827e-O010 4.517e-l10 8.758e0 13 7.60ce015 7.645e.013 9,052e-015 7.247e6Q1 7.247e-015 6,409e*015 Wut 1-543e-Oa 1.021 e-008 1.979e.OlI 1,728c.0 13 1.728e-012 2JJ46e.-J13 1.638e" 1 3 1 6080*0 1 3 1.448e-0 13 St~aIIiov Do~se Equivalent Rate ii Nraflcl a~nk{ry a Opposed o Rotatiornal a tsa:l'oP&T Effective Do-so Ewuivalent R~ate c Anterior!?osterior Geomietry cx F'rlifi rnr/A i4crirr o Lateral oRa¶oa o I 50tropic mnSv/hr rmSv/hr a 9.621o-0 15 9.1 3ge01 5 9.138E'-015 6451e-Q 15 8&004t*O1 7.065e-015 5.239eO1 5 6.31 3e-01 5 5.375-eO~1 5 2.174e*O13 2,065e.0 13 2.065e.O 13 1 .5 4 e.0eO13 11 8O9e.01 3 1. 184-e-013 1. 4 2 A,*-133 Cl-149 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 U¶JroShl1d wS.O4 (5.04-00362) Radiological Sexvicesm Inc.Pap -1 DOM File : PB1221271MS45 Ri ae;s c mber 21 5 Rvirfimet $,35:40 PM Duritio :. Q;QQMO Fil Rdof;_Date__C 3r: Cheeaed: Case TitIe: Line 1.641 C Description; Rc~ised Model Qski EP122 1lt Act w $ched 40 & 12 in 5-Nd Geonetry. 10 -Cylinder Surface -ExternaI Cose Point ,. ,...- _.Hesght Radius# 1 141.32 cm 4ft in surce Dimensions 762-0 cm O.1I cm DMse Points I 28 .LI'I 12 ft E'. irt 25 ft 4.0 in z 91.44 cm$ it.-hiaje~ Mpmpn Cyl, Core 0 Shield 1 Trbit ari Shield 3 Air Gap W."[C..:ad Shields n~imnr,-i-.r, Mla rinl IA, It 6 wM, Ccn-.nrrtct .65 cm 1ri lon C. c --rmJiCt, 3,48 cm £ rCcnrptE Air.025 cm I ron D~ensit, 1.8_ .4~7 ; 8 Sourzc rnput GrwpingU Method.: Standard Indices wmbkr of eroups 25§Lowettfteetgy Cutoaf t 43.J15 Photons < t0.G5 , Excluded Library: drove ubeaovreol

uCi/mrp 2 1-90a 010 .S99e+OO 4&5O3Ov2 ...N

I, Hde Luw 152 130icrn 1 ,M~5iNM4 Buildup The material reference Is: Cyl. Core nitegration Parameters Y Dire-S-^on

{axial)C3 rcumiorcntia; 20 20 4 A4.7 +9 g 34 4.792eti-.tluflD/5v ND5 Riuitfl 8.91e-40-ErUlls.flulenri-MXee~ VM:V2LV 9.250M-33 Exp:sure Rate fnR/hr No Buildyin 3.645e-42 uro Pw~With RuBitl n -4.091e 35 Cl-150 Plum Brook Reactor Facility Final Status Survey Plan-Revision O Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page -2.O$ Fie PB122127..MS5 Ran Date, Deem ber 21, 2005 Rin Time: 5:35:40 PhM Durtior : 00:00:01 vin A&Mtwt 0.05 1.198e+O0 0 1 2l,303e+00 .2. 6.06!De-.0 0-.3 2,1 WC+0 GA 4 !9(D0-01 0-5 4-56e.02 0,6 3434i-01 0.8 1.442e+00 1 .O 3.465*+0Q 1.5 1.879et00 FLbanre Rat 2. 7S2e-28 4.628e. 16 6Z25e'14 2,579c. 12 2.747e-12 7. 44e.13 1 46e.1 1.2.312e.10

1. 539e-109 4. 762e-OD Fiuence Rate YWith Bu~i ld=2.721e-27 2-7sge. 14.5ZI 7 S- 1 2 5s617i12 1I57le-10 1. 202e- 1I 2.507e-lI 3.62le-10 4,055e*S 2.009a-06 3-022q-O Ex-opsre Rate, mfgfhr 7,410cM3 1 7.061e.19 1 204bf,3i.4.e939-15

5. ~te16 5.352e,15 1 Soe, 15 2 744e- 14 4.398e- 13 2.83&7i(.12 8.012e-12.MR~bL 7.248e.3O 4.221e 1J 9.914e 15 2.9A79e-13:

2,34:a2c 1 ;4.921e.14 7.0S6e, 13;7.713.-12 3704e,1 I 6.430.e 11 TOTAL5; 1.87 7e+O-l 6.553e09 6.303e-08 1.IX3e I 1.103e 10 C1-151 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MIicroShield v5.04 (5.O4-00362) MicmShieId v5.04 (5,04W40D2) Radiologkal Services, In.Canvcsidn

• f calkuldtd exp*Sure in tSr to dosi FILE: C:\MSM\ATAXI-122127.MSS Case Tife- Ltine 1641 C This case was ruw on Wvdrwsday, De mbur 21, 2005 at 5: 35 40 PM Dase Pol I g 1- (141,32,at1,9t449 cm 12/21/05 ujtul (gumn=d r IJnits Without 4Wih-S;1fi P~iston Fluenero Fete (1ate P~ton Energy Fluence R~ate, Phot~r1/rn1jeC M ev/cm-/see 6.0440,09 6.653eLO09 5.215e-008 6.303e mg Expoure, and Dose Rotvs-Exposure Rale In Air Abswrbe Due Rate in Air.1 mR/br rm<y/hr mrad/hhr I .133e-ol 1 9.S"0tQ14 9.9Oe-01 2 1.103e-010 9.633e-DI3 9.633e-01 1 Deepr Dose lEqv~iymfrnlt FRatc!o Parailel Geirmetry 0 oppostid o RPotational o lseopje Shalfow Dose Equivalent Rate.a Paratiel G40i etry o Opposed a Rotationa o I5O1KOiP, Efectivc Nse E quvale-t Rat¢-o Arntenor/Posterior Geometry o Posteriet/Anlerior o Lateraf o Rotational o I$otvop: (ICRtP 51
• 1987)mSv/hr I (ICRP 51. 1987)mSv/hr'U (ICRP 51 .1987)mSv/hr U a 1.124eQ1I3 9 .70E-D14 9.70e-014~8,61c-O14 1.193VO13 115le-013 1.15le-013 9.1l7e.014 1.01 2e-0 1 3 9. 3-4e,014 7.460e. 14 8.414e-014 7.4W'Q 14 1 .096e-0 1 2 9i424e-013 9.424e4 13 8.414e*013

1. 167e-0 12 1.124e0 12 1.1 g24,0 12 8.906E-013 9.872W0 13 9,074 01.3 7.204e-013 8-172cQ 4,3 -7 1 ft 1-o13 Page I C1-152 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShleld i5.04 (5.0403629 Radlolcglcal Services 1 Inc.Pap : 1 DOS File : f1 2212.8.,MS5 Ru a: -O 21, 2005 Rui~Time:

5:48:23 PM Duratio ; 00;00:01 File IReF;Date: .By!Checked;Case Title, Lime 1.641 D Ddscription: Reised til V1 t- Eu154 Unit Att w $ched 40 & 12 in Shid Oeometry: 10 -Cylinder Surface -External Dose Point Height Radius# 1 141.32 c 4 It 7.6 Shieild Nasm Cyl. Core Shield 1 Trensifion Shield 3 Air Gap Wall Ilad Source Dimensions 762.0 cm 10.16 cm P9Fq Point zM 38 cmn in 12 It 6.0 in Shkcds Dimension bflIte 10,16 Crnt QCoc.6 Scm Ire, 25 ft 4.0 in z 91.44 cm 3 it 1.8 7.g6 2.4 2.4 0.0 M 27 7M8 rete fh C~ncrete 30.48 cm Conciete Air ,M2crm Ir Source Input Grouping M4ethod : Standard Indlces Numbcr of Groups .25 Lower Eteray O1o01f 0415 ilPhotonse 0.015 : Excluded Library r Grove D1i 80992,e+C0 4,5000eW00 1Nd iri~r auicœEu-154 2,189Ge-_r 1 65Q-5e-004 Buildup The mateuial relerence Is : Cyl. Core IntegratW Parameiers r Virection (oial)CircumferentiaO 20 20 ElieEy A4Gtifr U MU teL y Lhoionssec MeV sec N~ A~jilduo 1,648e+0 2991e-40 IkRsults Me~fcrn/e.With ui8cu*p 31182t. 3 Emostire Rate ,mR.thr 1 .;323B42[Eqosure RWte hr Wlith Buljdup 1,4070 5 Cl-1S3 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 P; Eo -2 DOS File: PB12212S.MS5 Run Date- December 21. 2W05 Eqn lame. S-A$!2. I>Duraticn: 00:00:01 EGI 005 0.1 0.2 0.4 0.5 0.6 O0s 1.0 1.5 Activity 4.1 87e-01 3-277i'tOO .531e-01 5. 778- 02 I .764e.02 6.53 3eO 1 3. 154+0 2.492e+00 3.I60C+OU Flutice Rals 9.7 1e-29 6, 587e* 16 6.220e* 14 3,1 19e-13 2.934e- I3 2.674e I I 5,064e%..1 7e0Q9 S .0108-09 Fluenep Rate 9 5O7e.28 3.927e- 14 5,119t0-12 1.365e-11 6,887e 10 8.88 e-09 1.445 c0 6.428e-08 Umaisre Rate'me/hr W4o BUildup)2aW e31 10088* 18 1.098e 16 6,077es 16 5.76O0. 16 5,21%,14 9.633e-13 2.040 12 1 i34e&- 11 L-prsr Ratg 2! 533e.30 6.OC8e* I 7 9,035e-1 5 2.659e. 4 1 .:8ae, 1 4 1-!34e- 1 2 1.689- I 1 1.08 le.1c TOTAL S: 1. 544e+C 1 9.&50e-09 8.833e-08 1.653 1 1 1 531e.10 Cl-154 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 mlquahid wSO4 (5S04-00362) 12/21M#4kcr*Wqkd ,r5g@4 (5,G4301672) Itad4fticl St~vfts~ If 0bonvmg $f cakuatcd upcur n 1i r t* doft FI.L MWUN$PATAWPS422IM1M Cmt Thtl*; IMe 1,641 0 This ctk wevg en t Doccwn 21, 200at i5:4423 PM1-vsi PtInM 1 * (Fa13Z31 1 9I~l4*} gm Je il~W~H tfwt I1 WUE; =t--r 7-12Me-0 6."$>OPB{9,65,v^009 $1 ,gO M PIoton FeneluI Rote (fRtx)rP*:ton Enetgy Fluence Rate FMWuon$'/¢sW MeV/C-Mf/'Q 9s O a34 ERb Ctes.-.C upuae Katei en Ae At=-: Dalee R in Air U mRthr mIGytr mradhr 1 453c 1II 1 43e-013 1 443Xe-1 I 1 .531e-fO]1.336e 032 1,3360Qe IO[loop DGSD f qtA4;Ih Rate o Pafallel GetI P) 0 "w, d o Rotational Shhow MDose Equv Pctv n PNralel *trw*y o Opposel a Rotationai 0 15ttrr)Pit OICRP 51 .15M7)mSv/hr (ICAP 51 .M7j mSy/hr a 1 .6fe W013 1 420e4L13 1 .42eN-0 3 I .271t-o}1.737te013 3 679t-013 1.67&e013 173I41e-13 1.521Le012 11311e O1.2 1.3 1le 012 1.172t*012 1.614e 012 1,557e-012 1.557e.012 1.233eQ12 E-~eetive Dose Equ9:ivalvt Rate rC A,7tert or. fPcis~eno l Geometry o P: n'E Aniripr L ROUl10Mtt F..' flgt .Fy rp: ()CRP 51 -1 M7)rrmS/hr W 1.47$e,013 1 34Y, O 3 1 095. 013 3 .231*i0 3 1.93C 013 I .36&O 1 2 106OM~ 12 1.1 412 1 iOOl- 12 PaI I Ci-155 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 I/MJwroShdeld w5.04 (5.04-'D362) Radiological Serivces, Inc.Page :1I DOS Fie : PB12212'9.MS5 Ru tat: Oweribemr 21, 2005 RvifTirne: 5:40:37 PM4 Duratio~n

00:00:01 F~il Rot; _ _ _ _ _ _Date., _ _ __ _ _BY: Checked:__

_ _ _ _Case iTRWl;Line 1.641 E Description.- Revised Modic Co~c. AW1O m Unit Att, w Sched 40 & 12 in Shild Geornetry.-10 -Cylinder Surface -External Dose Point* 1 141.32 i 4 ft 7-, Cyl. Ogre di Shield I Tranrsil ionl Shield .3 Air Gap Wall Clad Source Dimensions 762 0 cmn Doe~ Puir&I~m 381 cr.65 cm I ro, 25 ft 4.0 in 91.4 cm 3 ft fli.nsity 1.8 7.86 2.4 2.4 0.001 2;7.86 r 30,48 cm C~onc.-ete A hr 025 cm I rci Sowrcc Inpu~t Gtoupling Method -Standard Indices&Number of Groups; 25 Lovd9w iErmgy Cutofft +/- -01S PhwtonsI 0 Q&15 ; EAIlrdnl Library ; Ow Al 1=Wz. Pti*5 e.0.10 B.0992e+0030 4.5~0009.Oi Nw.~iid .AL?.108rn .2.1890 09 fLg fe, 1 .6650e-004 Buildup The material relerence Is : Cyl. Core Integration Parameters V Drection, frdi~l)Circumferential 20 20 11neg IkY Activity S..312e*00 I1.878e-207 F'lbjg1nrr. luq 1.49-6.5-34e-209 6.057e.35 CI-156 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 W Pae e 2 DOS File .PB122129.MSS Ron Date -Decer ber 21. 2005 Run tirne 500:00: P DurAtion .00:00:01 0.03 0.4 0.8 Activity 1,720e.06 5-740e-01 7,2.80e+00 7.321e+O 7,330e+00 n~uemm Ra~t f'evierrA'~ec 1.197e-79 1.$7.2e 8.3.929e-1 1 2.9q7e.10 1.175e-09 FHuena Rate t lem.' .-terv;: With Riom1in 3, 9wS-5.952e417 1. 7ge X 7,718eO9 2.016e.08 Exposure RB mRhr UpM Blildp 1,186e.8l 7,655ea14 S.84"ge-:$ 2 .235e12 rxtslure RatIL r4R/hr With BuiWduo*1.241 u41 9.41ge 20 3,3506e12 1.$Oe61 l a.20e-1 1 TOTALS; Z78e2+Q1 1.514e-0-9 3.O5tte*s 2.89 7I.12 5.762e-1 1 Cl -157 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShiiuld Y5.04 (S.0400362) Ml roShield Y5.04 (5,04-0D362) Radiological Servicet Inc.Conmtilodi of carwiuitcd expesmr In air~ to dose FILE C-AMS5rVATA~l3122129JMSS This case was run on Wednesday, D.m.suber 21, 2005 al 5:40W3 PMA Dose Point. #1. (t4112.3U1191A4) cm Xeut Summ~ed over eneregiesA 6J j 12/21105 Pt~otn Fkier~e Rate (fivx)Photon En~ergy Flu rice Rate~Phaomrs/cn9sc~ MeVel/ns~ec 2,067e.009 4-292e-0O&

1. 5 14e-000 31005e-008 Erxposure and Dose Rates-Kf x.*urt Nate In Aie Abwrbed Dow Rite 'n Air Ii mR/hr MG/hAr mrad/hr 2.897e-012 2?52*-01 4 2-529e-012 S. 762e.0 I 5.030e*O013 5.030a*O 11 a Paralel GeodTetry o Rotational a I 301fopi Shallow Wcse Equvaie~nt Rate o_ Paral 1.l Geormi.4y a Opposed o R-otational a ISOVOPIC (IC9P 51 1987)mtS/hr (ICRP 51 *1937)rmSv/hr.2,6t014 2.41 le-014 2.41 1ec-014 2-131e-014

.3.165t-014 3-01Se*01 4 3-01 Se-DI 4 2.280cc-014 5.926e-0 13 4.7870,013

4. 787eO013 4-233oQ 13 6.309e.013 6.005e.03 6.Q05-0J 3 4.528e*013 Uffccrtive Dose Equiv~itntr Rate a Anterior/Poster;or Geornetry o Lateral o Rotationap f04l-fopiC (ICRP 51 1987)mSv/hr a 2.636.e.O14 2.347e,0 14 I1.764e.0 14 2.099e.O014 I1.00014 5.256e~013 4~ 667e.01 3 3.492e-01 3 4.1 7l-Q!I 4,57~Q01 Page 1.CI-158 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 tlcroSheled v5.04 (5.04-00362)

Radioklogcal Services, Inc.Page ;tI 00" Fia 5 P18122130.MS5 IRub aite P Dernr!er 21, 2005.Run rsme: 5:.43-37 PM Duration ,00;00;01 File Ref _Date.BY!Chocked:______ Case rtite Line 1.641 F Descriptiown Rewrited Model -oak. Nb.94 Undt Act w Sched 40 & 12 iin SWi Geomietry: 10 & Cyl I der Surface -Extef nall Dose Pofint Jt Height Radius x 0 1 141.32 C 4 ft 7.6 S-hiplj4 NAMp Cyli Cjre Shield 1 Transibin Shield 3 Air Gap Wall CIad Source Dimiensions~ 762.0 cm 10.16 cm Doe~ Pints x in 32 ft&.0in Shields.65 cm I r~f 25ft 4.0 in 91.44 cm-enft n7n.8 '1.86'?A*e .4 5.00122 7.86 JL r.4te Canc.r~etr 30.48 cm Cncrrete Air C25 cm Iron sourvir tnput Grouping Ikethod : Actual Photon I!Aetgles. Nudie bjeUral U~ifc N5.)94 2,1090.-010 D 809920+000 4 5000c.0lJ9 1-.6650e00Q4 Buildup The material reference is: Cyl. Core Inrtegration Parametems Y O~irwizon tox*I.,)Ci rcurnterontial 20 20 MS 0.0174 0.0175'.012".102.6 1.A10 ActiA41 2.864e-03 5A487-v03 1.612e.03 8.099c+~I0 8.099e+00 7. 14,9e-309 II Z0403U 9.969a-223 I1 924-09 Re suits 1 .464e-36 5. 14e.37.1,473c.O8 3.01 1 e-08 Exm&Lrr ftt mR/hr 2.85gb. 310 8.9c305 3,62-le-12 Lxms~urf Bzt MR/hr A'dh SRuidig 4.085c.39 7,752e.38 1 .8Ose~ 3it 2,841 C1 II 5.667e-1 1 Cl-159 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Paso 4 2 DOS File PBi12213Q.MS5 Run Date- Decmrnber 21, 2005 Run Time. 5A3.37 FPM Durifon: 00:00:01 Arf;i+y-ohatangf see Sfornrtd Rti Me-femysf.ee Nn R,,ildur-, Fluence Rate, w.Jerw/sef: With Riti1~gp Exp~osu~re Rpge ,MR/hr ND Butildup -Lure -_t With. BUuinu TOTALS 1.621e+al 213OC-09 4.4$4e-08 4,983e 1 2 8.50e- 1I Cl-160 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mi-moShteW v5_04 (5.04-00362) microShieid v5.04 (5.0400D3M2 geicgall Services, Inc.Conmesion of calculatad txposuirr hi AIr to do"t FILE- C.\MS5\ATAXP131221,30.MS5 Cat%* Titll L~ift 1641 F This case, was run an Wedlmsday, December f1, 2005 at 5:43 :37 PM Dose Poirot # 1 -11 3194?cm_(Surnmed over ener~gjW ails~12221/05 Kul 5,553e-008 Proton F~vqr~e Rotc ~fiux)Pw~on Enefgy Fluence Ratew Ph~tr,*"$/risCMV~ Mev(/cmkl/se, I3,214e-009 2 .630e.OGN!xpqs5urv and Dose Ratvs,: Exposure Rate in Air Ab,,orbcd Dose Rate in Air M mR/hr m~y/hr mrad/hr 4.983e-012 4.350c.0 14 4.350e-O012 B.508e-O 11 7427e.013~7.427e.O1 I1 O~cp DCse Eq yiii1nt Rate oParai [le Gi-cetry o Oppozw~d Po Roitational Snallaw Dose Equivalent Rate o Par-01kd Gtqntetry a Roz.ationa Eflarhw Dow Fcruiwaent RPIC a Anrter or/Pstencor Geoer'utry o LatteralI o Rotatoona~(ICRP 51. 1987)mSv/hr (IC-R 51 1987)mSv/hr.a (ICRP 51 -1987)mSv/hr N 5,061 e.014 4,16&6e-014 4.166e-014 3,684c.0 14 5.412cQ14 5.1 64s.014~. 51 64e.014 3,942c'0 14 4.51 1 e-01 4 4.046e.O14 1.074-01 4 3.622e-014 3..1,1~4p94 8B65eO013 7,109e-013 7-10ge-013 6.287e-0 13 9.24 7e.0 13 8.8219-013 &.821 e-Cl1 6.727e*013

7. 706e-O 13 6.90O5c; 1 3.5,240e-0 13 6.182e.0 13 Paso I.Cl-161 Plum Brook Reactor Facility Final Status Survey Plan Revision O Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShleld v5.04 (5.04-OD362)

Radiological Services, Inc.Page ; 1 DO$ File. P812292L1MS5 Rt h tUm: D3M:7:5 5 R~h Ifinle: 3:17:53 PMY Duratio ; M;W;Vt File R'of__Date: Chealed;Case Title. Line 1.641 (Mescription: RetIsed &iodel CaIc- I4129 Unt Act w Sched 40 & 12 In Shid Goomstry: 14 -Ctyiridr tufa ct -IWnal Dam; Pqlpt It.,v-. l.- X Height Radius x N1 141-32c I it 7.6 shield lyarne CW. Core Shield 1 Tran-sition Shield 3 Air Gap Will Vaind Source, Dimensions 762.0 crm 10.16 cm Qwe PPrIA:M 381cm in l2ht60ihn Shislds 10. 16 cm, c~oci.6. cm Irm 25 It 4.0 in z 9144 cm f 3ensltv 1.8 i.86 2;4 2.4 O.001 22 71.8e'ete 7'Cc ncretr 30.48 cm Confcrete Air 2M Cm 1rQn sourcC Input Grocplng blethod : Actual Pkoton Energles uuclide 2imes brgLfrels uCi 1 129 2.1690101 SM92i'rv00. 4.-5000e.009 Dq&.e 1.660o-00 Buildup The material reference Is: Cyt. Core lirtegratio Pwfameters Y Diroo;ion axial)Circumferential 20 20 M-V 0.029!5 0.0298 0.033&0.0396 Arfly--4 1.616eOO 2.§9e4f*00 6.09leeO1 fluoent:, RA40 No Etulldfjj.6Z99C.77 1.0780-74 1-793e-41 Mshio-rr Pigi~Wdth 3UU11dun 1.1 17e 33 2.137e 33 J.1 16e'33 1.134e-33 mR/hr NO B3Ivl7uo 7.01 le-79 I 09S2u 7 6 2.0'73e.59

8. 146ei44 F~auiro ftxm Si With ButiGrus 1. 16ge-35 2.A6se-35 7.93Ee, 36 5 154a-36 Cl-162 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 Pap ;2 DOS File , P812292l.MSS Run Dte >scmber 29 2005 Run time: 3:17:53 PM Duration : O:0.-01 TOArs A6;Kv29e TOTALS: 6,290e*00)

Flu3nr7.4R 1.793Se-41e FItjrenr-w 3F A%Mirth Rijitrhip 5-504e-3.3 Fxnncrtirg ate aa~b f8.14fif.44 EXcour Raste&Mt/hr With Buildup 4-644e4.35 Cl-163 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlcraShield v5.04 (5.D4-00362) f2/2 I05 N1icruSbieid Y5,04 (S.O4.G1'02 R~adioogicgal Sevc, St c..Conversion of calkulatod expos urs in air to dose MIE: C:MXIADATA\P812292LIMIS Co Title. Line L,641 G This casu was run on Thursday. Ducemb'er 29, 2005 at 3:17:53 PM Dose Mmin a I. 14.Mt4)t With Buildup.1.716e.0-3 5,504e-033 Pkboton FIlxsnce Rato (flux)Phvoton Energy fluenoa- Rate Ph.0tons~cm,n!se1c MAeWernk/~ece

4. 529e-040 1.793eM041 Exposure and Ctise Rates Exlpasure Rate in Air Absorbed Dose Rate in Air M rnR/hk Moy/hr mrad/hr 8.146e*044 7.1 1 4C'7. I1 1e-,044 4.-64e-O3-S 4054e-037 4-054e-03S a ParalIef Gveormetry o pposed a Rotational a Is1eopic DoIiw ~se Equ~vaent Mae a PlarafleI Geo"metty c O~ppose~d o RotatioraI Effoctive Do-, Eca.iwalnt Rate o Anterior/Posteri-or Geome",~o Latera I o Rotatiional Li IWa~rcpic~(lCRP 51 1M7)mivfhr M (ICRP 51 .1987)m~y/hr I S (,ICRP 51 -1987)m'Wthr I 1.0Q8e045 5. 127e.046 4.642e-04,6 4.,44le,.04 1 .024e-045.7 ,069e-046 7 .070e-046 5.1 M. aV46 5 ,935e.046 3 ..B e.O46 1.982e.O46 3.226e*046 R,§4rQ+4,641 e.O037 2.328e.037 1.96i43 1L8449.037 5.O580.037 3.478e.037 3.47ge*037 2~571e*037 2-08 1e-037 3 .076~,c-037 5-807e-038 2.0159~e-0$7 Page I Cl-164 Plum Brook Reactor Facility FinalStatusSurveyPlan

.Revision 0 NlicroShield Y5.04 (5.04400362) Radiokoglcal Services, Inc.Page ; 1 Rt. ate: January 4. 2006 Rvr~-ime:rn S. 3, I S AM Duration : 00:00:0I roc4 Re~r; _ _ _ _ _Date:__ _ _ _ _By;Checlied: _ _ _ _ _ _Case Title: Line 1,641 H Des-edpliont Revised Model Galc- So.14i U1~ A41w$~ 40~ & n Shd Geometry; 10 -Cyl Inder Surdace -External Dose Point A Height Radius A 1 141.32'4 Ft 7.E St;irwr Wd NIB Cy! CAre& Shield t Transi1tion Shield 3 Air Gap Wa1 'Clad Sour.e 0imensions 762.0 c~m 10.16 cm Dose Points Y cm ~ 38:1 ca-1 P in 12 ft 6-0 in 25 ft 4.0 In?1.i14 cm Shields I a 1 6 cm Concrete 1~.-S.65 cm Ircel 7.86 Go:ncrrcte 2i4 0.48 cm Ooncf ete 2.4 Air O00D72?'025 cm I rc- 7.86 Souirce Input Grouping Miethod :Standard Indices Number of Groups., 25 Laftr Ea~egy C~tatflt Q.O3.Library .Oroe-r L ho,.:! ~ ~ r~i-rruro9 iirr-DIO & 0992e+000 4.6W000-.OJ uN~dp zaLic~Sn4 126 2.19900-9 1 .6650e -034-Buildup The material reference Is : Cyl. Care lu~Intgration Paiameters Y Direction (auiail)Ctrcumrferential. lsut 20 20&dctiyit nhotonfi/spc 6.26-9e.01 2.21 6e-208 Fluerict Raite 2,064e-34 Eicrxsurei R& to m R/hr 7 .676e.210 Extposure Rate 7. 148e-36 Cl-165 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision O DOS File : P800406.MSS Run Date: lJanuary 4. 200 RFign Time: 8: B13:18 AM Dur'tion : 00:00-01 0.03 0.04 D.06 0.08 ArtiviW 2.371e+00 4,046-02 7.76te-01 3.71 9Oe00 MleVfemkse Nolgtildtjo 1,651e*73 7.340Be42 5.45o23 L0194-17 Fluenoe Rate ki*YicrW/See Wih Buidup I, 726e. 13 7.8Me 35 1,04P2c21 3.857e 16 1 ,636e75 3.246e*44 L062-v,25 1.;612e.20 Wisth Su-iO4;1,71' e35 3.464e9 3 2.070. 24 6. 1 0e-19 TOTALS: 7.534e+00 I 01 g. 17 3.857e. 16 1.612e-20 6,103e.19 Cl-166 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mip4nleid wS.G4 (L5.O4-83U2) 02104/$6* crMShlwik4wS04 (5,04413)WR~kckic urvicts, Inm.ctnwsw of tck1Attdgup9$k i at to &se nLE.; CQ\W5NDATANFPSUMOMAS Case Title tMse L641 HI This ca wai vwr; o i W4fsty, Jaury 4, 24 6 at 5:1rl3$ AM Ofte Poin t -04(tS,231 1,%A) tm ault-s I{umrn~ eve enereWesithout Sui~leiuo Wdh Phdont Fltiaeer hic; Out), ble-ay'Xh 1F.uefi Rate ftrA PA, S, V M-eV,!Cjw,71 e:, 11.273e 0t16 4,821e-015 1.0ilLe-CI ? !A574- 01t tKF~5Ur4,i drni DLo4¢ 1~Ps~f x-pasur# 5tip in Air Abwrbx Dowe FRte in Air I mRR 4'br nlityht 2 612t 020 1 .40I&22] .407-4-V 6 10- 01 9 S 328i 021 S ,3280 19 erep DoQvx Equsl&tlnt Rate a Parx-le Gewnetryn , Rotational ShalI Do se Equgtyaent Rate n P-troiil CinQrtdry u Irioiial U llol (ICPFP 51 -rnSyhr I (IJC RP 5- 187)rrnS3t +'tw 2.462e 222 3 33 le-022 1 .274e-022 2.43ge P_' 79.3e-422+ .1Z793 f0 I i 2 9.342,0 0W!I 4964-021 4.825e-021 4.79OeJ21 9 2330v 01 1 6 .7 86021 6. *78& 02'4.98Ie-021 t-H~ttI ',i ;j i~ts t Rate 6b A.PiAf 1F -Litefltf ) *r ;e mtfy*i. PVt rw gera err ci- Rwitarturaf OCIRP 151 1987)rrPS .'hr a~2 069e-02,2 1 577 022 i9.719e-023 L.343a-922 1.087e fG22?X7e2h02'5 9;O 02i 3.679e 021 5 C85e-O21 4 Mt27 Pape I Cl -167 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicruSbicid Y5.04 (5.04.V03620 RadiDIOICal S'ervices, Inc.Page ; I DOS File : PB122921.MIS5 Fk a Meb nt0C5i Run'rime: 3:21:15 PM Duratigq ; MOMQ FHli Ref;Date: Qhecked;Case Title: Line 1.641 I Desription: Revuised Model Coi4. Zr'.95 Unit Act vi Sched. 40 & 12 in ShId G"ontetry; 10 -Cylindet.Surface -Extern~al Dose Point i Heigit At1 141.32 c 4 I't 7.6 S~hijde Nsrnr, CYI Cc0 a Shuerd 1 Tran~sif ian Shield 3 Air G, p Wadl IClad, Source Diumnsions 762.0 cm~10,16 cm Dose Points:m 381 cm in 12 ft 6.Oin Shields Uif-mo Wz 101~6 zrnr. C~onc.y.65 cm I rc, 25 Ft 4.0 in z 91.44 cm 3ft II., 7.86 2.4 2.4 OO1 22 X.86[--i rete Ornc~retc 30.48 cm Conec'ette Ai'r.025 cm I ror Sou~rce Input Grouping Method : Actual Photon Energies;14wild OLL bgurl wicn Zr-95 2.189DeA31G 8C-992ei-000 4.5000e.009 BgLzzn~LGG665e.004 Bdildup The material reference Is : C 1. Care.y Dr~I on ntIFIN F30On Pararnete-Ts Circurnferentiat 20 20 rrtf-o Activiity 0.7242 3.5.369+D0 t0.7W-7 44830--00 T.MiALS: 8. e+ .Rgsults MeV/cm 2/sec Mdafm2 a, R/r nc ,3.5!57e-10 7,125e.09 6-94De-13 1.370e. 1 1 910le-10 1.760e-08 1.745e-12$,375e.1I Cl -168 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 ilcreShleld aS04 (5.04.00362) M icroShklld T5.04 (5.0400,362) RadhbloicaI Senrices, Inc.Corwursin of C*lIlawd exsur in alr to 40" MILE: C:XMS5\DATA\PB122923.MSS ->$e~~~~s fThle. lwine } ..... 1$ 1 This case was run onThursday, Decmber 2, 2 5 at 3:21:15 PM Doge POint 1, {1LI~tBig944} cm 12/29I05 RPS11lts tSmMed MCenprgip; Adh rtulxdu PtoDtan Fluence Raht Nu)Photon Ene-y Fuence Rate Photons/cm'/sec MeWV/CM TVee 1,224e.0O9 ' 91Ol0iOl1 2.3684-DO8 1.760e- 008 Exposure and Dose Ruitks xwpsure Rate in Air Absorbed Dose Rate in Air II mr/hr mrGytr rhrod/hr J. 745eO 012 1. 523e-14 1.523e, 12 3.375e-1 1 2.946e-01 3 2,946o-D1 1 Deop Dose. EquivWlnt Rate o Paralilel Geometry Fn fpposfrd a Rotational o Itotopic ShallJw Oose Equiv~aent Rate o Paral el Oe nety O Opposed o RotatioAal o Isiatrpic Effective Dose Eqcvivalent: Rate q AtrterrarIPOSternor Clecrnetry o Postailor/Anterior o LOteral o RotationaJ a i$Qtropic (ICRP 51 1987)mSy/hr (IC.RP.51. 1987)mrvhr H mS-v/hr H 1. 786e-14 1 .452e.014 1 452eM14 1 .284e-*14 1-.907e014 1.417-.014 1.8 1 7e-014 l. 374e-4l4 1, 586- ,O] 4 1.413e-014 1.02 .014 1.264e-014 1 .082c-01 4 0 3.454e-01 3 2 4OU-1 3 2-B.8e-013 2-42e- 013 3 6B7e--1 3 3. $3-013-3.513e-013 M.2.67e-01 3 3 067e.013 2. 732e-01 3 2.054e-013 .2.444e -01.3 2.093e-01 3 Page I1 Cl-169 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlicroShilid YS.04 (5.044.O0362) Radiog~ical Serrlces., Inc.DO$ FLk .P122.MS Rt ate. Decemb~er 2~9 20115 Run (firne: 3:44:47 PIM Duration OO0:01):0J File Ref: Dae ___ _ _ _By: Checked: Case Title., Line 1,641 J Desctriptiom.: Revirsed Model Cale- EP-=165 Unilt Ac w Sched. 40 & 1.2 in Sh14Ci1 Geometry: 10 -Cylinder Surface -External Dose Pointi I+I II I I t-x Heh Ra-dus JV 141.32 c 4 It 7.6 Cyl, cwe* Shield I Trowisilion Shield 3 Air Ga p Wa4ll Clad!5urce Dimansions 762.0 cm 10.16 cm Dose Polinft in 1.2ft 6.G in 25 11 4.0 in 9 1.4A cm 3 ft Shields I P EL 2 16 cm-' Concrete 1.8.&Ec-f lrfin 7.B.6 Concrete 2.4 0,48 cm, Concre-e 2.4 Air GLOCC122.025 crr Iron 7.86 Soiarce Inupit Orouping M~ethod -. Siandard Indices Number of Groups : 25 Lowear Envity *"loflll 0,015 Pbotons. < 0.015 .ixcluded LUbrary~ : Groee bg-ccnwals _____,-Nucside ids Eu-155 241899Oe 9 1.665 O-0~4~Buildup The materfal reference Is : CyrI. Care, Fatulration Parameters Y Oirocti on (axrjil)Circurnfere-itial 20 WAY 2,578v.02 Pj-tPnrP POL MeV/cm7YseC No &LIl day IA-794-75 Results With PUP& 'i 1,~876e~35 No 1301dur 1 .778e-77 rr R/hr With FBuiRsuo I ~;-9 -3 Cl-i 70 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pago -2 DOS File -. P8122924.MS5 Run Dale, December 29, 2005 Run Timr; 3,44;L7 PM Duration ; Q0.OO;Q1 0a0-0.05 0-08 0.08 0.1 8 WI i W-hfietong/g~e-1 A6$t+00 4,775e. 01 1.05Oe.01 2.515t+O.1.674e+00 Thiemntce RMi MCV/crny~sp_2 2.64e-40 1.108e48 7.2>4e-24 6.809e- 18 3.365e-16 Fluenra Rate XMeXttot UIM~C,33 1,0104e-27 1.411e 22 26O8e1 6 2-OOie 14 Exioure R&te N D PutiddUp 11 7& 42 2.953e-31 1.437e-26 1,.9O0c20 5.148e.19 Ex-posure Rate Keith Buildup 1 253e-35 2.888e 30 Z8O2e-25 4,127e 19 3.069e* 17 TOTALS: 6.26e6IW 3.434e!16 2.032e, 14 5,257e-19 3.! ZDeI 7 Cl-1 71 Plum Brook Reactor Facility. Final Status Survey Plan Revision 0 MoBit id vS.B04 (S.04-00362) Mkcrohleld wS.04 (5.04-0016,2) Radiological Setvilees. Inc.Cuorivrsion of ca~culated exposure In air to dose FILlEr C:%MSS\DATAPB12§24.MSS CaSc Title Line 1L642 J This cese was run on Thursday, December 29. 200S at &:44:47 PI DO$4 PoIMI .I -(141LZ,381,91A4) cro 12/29/05 tJTit'Ifithoui Pfr~on Fluvncc Rot* (f ux)Photon Eeir&~ Flu-ei~e Rate Photons/cm'/sec M01Crn'/SO 3.45le-015 3*.4344-D11 2.039e*0Ol 3 2,032e.014 Expos~ure and Dose Rates: Expoture Rate in Air AbsQrbed Dim Rate in Air I mR/hr m~y/hr mnrad/hr 6.257e*0 19 4.589e-021 4.56ge-0 11 3.1 1 c~Oe I0 2.715,e-017 COvp Doseo Equivalnt Raite ,a ParalleI Geometry ,a Rotational lwto~opic Shftow Do.se Equivalent Rate!a FRatallel Gec~rnetry I, OPpoSW c' Rotationat n Itaropic Eftective, foso Equivalent Rato o.Anteroor/lPastefior Geometry o Posterior/Anteio o Rotational (ICRP 51 .1987)mSv/hr 7,677s-021 4.207e-021 4.071 e.021 4.54le-019 2.48ge413 9 ,2488e-01 9 2.408e-Ol19 (ICRP 51 1987)mSv/hr a (ICRP 51 1987)mSY/hr U 7,627v.021 5,912e-O21 5.912e-021 4,31)5oCI21 6.597e.021 5.170c*021 3.191e*021 4.416e-021 3.140-21 4, 5 l~e-Ol 9 3.4 98e-01 9 3.4 98c 019 2. 547e-01 9 3.902e-01 9 U.59e-019 1 .888e,01 9.2.613e-019 Page 1 Cl-I 72 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 rNg 1 Fl ,t me 1:18:19 PtA Chec Duration 0:0-3O-1 Case Titlew Liue 2.81 A2 Dv OiPWMI¶ F104 Mo1et C1iC. -Co-O Wflit Act w $O*d 40 A 1! in Shtd____~Geogmetry, 10 Cylinder Suriace

• External iote POlWt I Rol;"lite 6Y-'c*ed: Heftjght padiU3~b I Z4Itb7 cm 4 it 6,6 to wrxt limens-ns 7.62 cm Dm Pintsl:2 ft 6.0, !SllVI.tds 7,62 cm'r~t pnc r..65 cm t ro}F 23ti z 24 r2A 0.00122 7.86 41 Shirel0 Nsro-e COfl. Core.ShIeld 'tran.llsiarl Sh -Rid .?Air Gq p wai ,Culad 7 L-nc ratt 30.48 cm Conti Air.025 cm frm -rete tranplq; Methl ActuaI PaotwEnetpes CO-60 1.6 07t00 Q 647t M 4, .Qe-QO SPc1e:MI 1.65CGe-004z Susldup The MatedikI tefelence 19 : Cyl. COeM C .Intwatlm parwratav 20 2D&r'Otorastsec 0,6%30 19 t 737 1.932S 909,* 04 6074.-O0 6.074i00 Fhuitnco Fato:3.9s5 7 -},1 3 934? .--FUflumic pate.24Lirmt I* r NMIt Bupda 1-04l-1.3!*tpgjurg pste,.rthrt:7.032e-1.3 1N4545~1c112 With Buddut 2.00S1 Jf I .18e-1.1 1.J58e-1n ALS: 1 24:51 1I 175e¢09 E $6P]e D 2.945e 11 Cl-1 73 Plum Brook Reactor Facility Final Status Survey Plan 1,1 Revision 0 Plum~~~ ~ ~ ~ Bro.ecoFclt.ia Sau uvyPlnRvso Mi~i~hiI~

5..4 (S.-04-O0362) fficroShivId vS.4 (6.0400362) Radjological Serwites, Int-Conversion of caIcullalld expos re In air tD dose FILE: 0:\VtS~\I)ATAkP=i1917.MS6 Cae T11th; Linc 1.81 A2 This cawe was run an Mon~day, Dseember 19, .2005 al I1-1S:19 NtA 12119/05 Li-JUJI15.-ASUMMAd Qxu -Ad"ioon Fluenco Rotc (flux)Pitoton Efwgy 1F1"c'e Rate Photon/cm~s~ec.Mev/rn/sec 9 219c'O10 1-1 75e-009 1 279e.008 I .62 1e*ODS'E.xposri arid Dose Rotor~Exposure Rate in Air Absorbed Dms Rate in Air N mR/hr rnGY/hk mrad/hr 2-059e*01 2 1.79BeO014 1 i78,-01 2 2,845e-01 1 2-483e-OI13 2, 4 83c 011I Deop Dose Ecwivo nt Rato o Paafalel seorntry a Oppow'd o Rotational a Isotrop>ic Sballpw Cose Equivalent Rate 0 Parallel accnw-ry o Opposea O Rotational of ectQvpDp$q qil;On R a AntenonrPostenor Geomnetry a o Lateral o Ratalinart o hlaotropiC (ICRP 51

• 1%87)ryiSvlhr N (ICRP 51 1987)mSv/hr (ICRP 51 .197)mS-,vhr 2-04OWO014

1. 758e-01 4 1.7$60 014 1.571e-014 2.72014 2,091e-01 4 2.091 -'0 14 L1,664e.O014 1,837s*014 1.693e.014 I .348e.014 I .525e*O014.

1 .3509*0 14 2,81%,01,3 2 .428e-01 3 2 ,428e-01 3 2.16ge*01 $100le-01 3 2.890e-Oi13 2-$9c 01 3 2..298e-,O 1 3 2-53ge-0 13 2..3-"e.01 3 1,860Ge013 2-106e*O 1 3 1. 864e*0 13 Page I.Cl-i 74 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mlcro~hl~d 0.04 (5.04-00362) Radiological Services. Inc.Page :1 DOW rftk PB112213LIMSS RL 0 ftUM;P 23,40D5 Rvii rime, ; VA Ml Durationm 0:00.-O-D File Ref: BY : Chocked:______ Case 11tle-: Lime 1.81 B Description; Re.vised U10de-1 Cak, Cs13l7 Unilt Agt w Sched 40 & 12 in Stid Goomtetry;. 10 -Cytindee Sutface -Extemal~ DQ4e POWt'i Heigh~t# 1 13B.7B cm 4 ft &6 in Cyl, Ccre Shie~d I Trainsitioni Shield 3 I Air tp wurce Dlmemilsons 720cm 7.62 cmi Dose Points3 y 12ft 6.0 .n ShKOds 7 62 cm' Conci.65 ern ial >25 It 3-0 in%*? ft e 2,4 e 2.4 0,0O1 2z 7.86 ret 11i*Conc~ret, 30.48 cm c~onrirt Air.O025 cm Ironi Ntplidrn Cs. 137 Source-Input Orupn Method :Actual Photon Ewnetiges curies hA~j~1% u Qi rf'(I.SS31e.010 S.7464E4000 4,2,570e-0131

1. 6417c,'010 67044c-POG 4.5000e.0G9 I A565C'c-C0-4 9.zildup The material reference Is Cyl. Care Intug~ration Parameters V Lirection (axial) 20 Circumlereritial 20 Actiit ph.~tns/sec 0.0318 0.0322 0.0364 i1e 1. 190e-01 2.1 I 0e-01 7.987c 02 51l71e+00 8.090o-83 2.278e*80 4. W 4 EP! 5 1.200e4 I.Results M8V/rM,-VsSo 6,7684*35 I1.298e.34 4 .374ue- 10 Expow-~re Rate 6.739e.85 1,8l34c.82 2.63$e-64 2.3269- 14 rxi*u~re Ratso Wdth aisll fa 1 .044e. 36 4,10&~ 37 8.479e- 1 3 ClI -175 Plum Brook Reactor Facility F , Final Status Survey Plan Revision 0 Page 2 DOS File -PB122131.MS5 Run Dab, -Decomber 21 2005 Run TimeS 5S57,30 PM Duration ; OQ;QQ;Q1 MS ,AraixiCr phntorsgsee ElMUM Pad Me#fctfr*Sec No CUImdup#uVflc RSate Mtsh Seidd Fx>ture Rj;ja~,mntlhr No IBu~jg.X p Exposure Rate, MBohr With Builduo TOTAMlS l8-9s+QQ 1.20e-1 1 4,374c. IO 2,.326e-14 8.479e-13 4 Cl-l 76 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShsied Y5.04 (5,0440036Z)

AllcroShilold v5.04 (5.04-00362) Radioaogical Servicai, Inc.Conversion of cakulated exposurv In air lo dose FLLE.- C:XMSSXDATA\Pm122131J4SS Cws TKtIW LUroo L8~'This case was run on Wedmneday, December 21, 2005 at 5:-57:30 PfA t Dose Po~intiv I .- (1&81128cm 12/21/05 Pesulks Murrmmd oyer eneczp-bIdAS Suilduj")y-ith I Awoo-of ftctsoon'i tefgy Fluence Rate Pho4*n/tmVs~c MBV/crW/sec I XI 3101 1 I -200e-01 I 6.6] 1s.010 4.374e-010 Exp~surv arld Dose Rates-Ex~posure Rate in Air Absorbed Dose Rat in Air U mR/hr rnGY/ft mrad/hr 2.326e*0 14 2.O03e0.Q 1 2.030e.O014 8a47~je-013 7,403o.015 7.40-3e*O013 Deep Orse Equ ivaelen Rite ai Para~lel Geometry a~ aOPPOeO o Rotational a isotropic MJallowi Cose EquiJfa lent Rate-- o Parallel Gqwm-ryt a flppDoed o Rotationali a Isalcupec (ICRP 51. 1q87)rmSv/hr a U a ICICRP 51 -1987)rn5v/hr U 2.404e-01 6 1-925t-O16 1.702e-01 6 2.5 55e-01 6 A2 A7cO1 6 2A427e-01 6 1 -Elge,31 6 8. 764e-Oi5 7tO1174c0J5 7.01 7e-015 6.205frO1 5 9.315e-OJ3 5 8,84 7e-01 5 8.84'7e-03 S 61 S0-1 Eflertive Do:se~ Equ~ivalent Roto o Anterior/Pas tffr G-etr'yet o poije'ior/Antervor o Lateral o Roa~taonat (ICRP 51 -1987)mSvfhr a 1 487156-16 I '.41A-ft1A 1 .677e-t116 1.2 v-1 7 .75W01 05 U.40e-01 5 56204a-s-0 5 Page 1: Cl -177 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlcroShield Y5.04 (5.04-00362) Radiological Services, Inc.Page :1 D. S Fite PS122132MS~S RL ate: December 21, 2005 P.lurr-Ame: 6:01:15 PMA Duratign. Q; W0'Q~File Ref; I By: Checked: Case Title: Line 1261 C ftscriplio,: R~evised Model Cak.- Ewt.1S2 Unit Act w $ched 40 &. 12 In $SIdM Geonwtry: 10 -Cylinder Surfa~ce -Exteruat Doe. Point VJ.1 -a ------'A Heigrit Radius gj 1 138-78 cm 4 ft 6-5in wurce Dimensions 762.0 cm Does Paints 381 cmn 12 ft 6.0pn Shields 7.62 cm' Concr.65 Cm I rQ, L z5 ft 3-0 in z 182.8F, cm 6 ft I Densit.7 85? 2.4 2.4 7.86*Cyl. Cmr$hleld I Transition Shield 3 Air Ga p Wal4 Bad I Concreti 3048 cm Goncreh AiT.025 cm I lror ja Souwrce Input Groukping Method : Standard Indices.Numiber of Groups -. 25 Lower Energyr CktftA 015 PhQIgns < ,0Q ; xlui Library: Grove Eu-152 I1,641,74,010 twrniLiP4L 6,0744e+00C 4.500Ce-.009 11 6850e-004 uildWp The material reference Is: Cyl. Core Iategratilon Parameters Y Direction (axial)Circumforential 20 20)4 .3.594e+00 Fitimail Rmto 5.464e-50 4iini, R-o.Exrnnsyro Rate maLb with ByildyRx Cl-1 78 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 VO$ File .PB1a132.rAS5 Ron Date; De'ember 21. 2005 rhun Time- 601A15 PM Duration 00:00:01 0.05 0,1 0.2 0.3 0.4 0.6 0.8 1.0 L.s Acflyity p h tonrt s se 8.987e-01 1 .727e0+O 4.552se -1!A42t+00 3.817e-01 3.426e.02 2.576c. 01 1.082et 1.409e+00 6.428e-35 2,821e-16 2. 1*6e-14 3Z575e-14 1.380e 4 3,272e 13 7.865e-12;6.wt- I I 3.350e.10 3luence Rate MeVfen t f;1gt/Mh ROltipl 4 164e-33.71e-l 7 4,453.-14 2.443e 1 2 2,794 12 7.55e. 1 3 1.388& 1 1 2.14le 10 1.343eQ9 3.726e.09 Exposure Rate nRhr 1,7129-37 4.535e-22 4.979e-19 4.07le 37 6.965e-1 7 2.708e. 17 65386el ' 6 1.49Ee-14 1.2716-I3 5.636~e 13 Expoure Reate Wt uitcun 1.109 35 4. 352e*2D 7.858e. 17 4.634e. 1 5 5,444e 15 1.522e.15, 2,710. 14 4.073e- 3 2.476t, 1Z.6265e iz: TOTA.L*; 1 ,40c+1 4,122e- 10 5,3038e09 7.065e 13.190e}12 Cl -79 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 I1lch~eid v5,04 (5.04-00362) MicroShield Y5.0-4 (5.04-OD362) RadlowicalI Servies, Inc.COMMrIGO Of C3ClakIted 4;PCSUWC In Air to 4doSV FILE: CVIAlSM\ATAWpl2'21SMSSS Casc TIlite: time 2o.1 IC This case was runl on Wednesday, December 21. 2005 at 6.O1,15 PM Dfes Point # I -87,B~1 8 n stkiiMPH nrt s"WIf fim !&Ihbii 1211/05 Pboton, Flueriice Rate OWNix)l. b*Aon E.t-eigy Fluerice Rate Pho'tons/cm'/sec N1CVfkm7/!C; 3.02aefl1 0 4. 122e.OI10 4V 1 5C 009 5 .303e-009 Exposure and Dose Rates-Expqsure Rate In Air Absorbed Dose Rato in Air n mR/hr rnGy/hr mnrad/hr 7.065e-01 3 6. 17e-01 5 6.167e-013

9. 190e-0l12 41-0230.14 8-023e.01 2 Deep- Dose Equiva!ernt Rate a Parariel Geornetry O Opp',seo o Rotational O isalropic Shalkow, Dose Equivalent Rates a Nr8a lel Gecenetry G opposed a Rotational o 15ctropi-C Effective Dose Equivalernt Rate a Anterior/Postenor Geo~metry o Posterior/Anterior a Lateral a Rotatiorn,:

O Isotroipic (ICRP 51 1987)mSv/hr a (ICRP 51 1987)mcv/hr I (ICRP 51 1987)m$vl/hr I 6.997e.O015 5.068e.0 15 6.068e-O 15 5.432e-0 15 7.4 lge-01 S 7.167c*O15 7.167e-016 5,7;0c.0 15 6.101eQ 15 5.828e.0 15.4.68Oe,0 15 5.258e-O015 4,074'10,1 g..124e-014~ 7,570czQ14 7.870e.014 7.0 36e.0 14 0.6Se-014 9. 342e.014 9.342e.014 7.4-35Pr0.Q4 8.209e 014 7. 569e.014 6.042e-O 14 6.822c-014 6.044e*O014 Page I Cl-180 Plum Brook Reactor Facility Final Statss Survey Plan Revision 0 141IcroSfileid vS.04 (S04-00362) Radiological Services, Inc.Page ; 1 POP File PB122133-M& RL att December 21, 2005 Run Time: 6:08:42 FM iDurativ, ; M O P; ]Fil* Rof_, Date: _By;Cheed;:, Case Titiec Line 1,81 D Dcscription: Renised ".d el We. EwIz4 Unit Act w Sched 40 & 12 in Wtd Geometry: 10 -Cyllnder Sufface -Extenal Dose Point T.7 ... ... s__ -_._ _"eight.Ridius x# 1 138.78 cm 4 ft 6.6 in Sh14,ipid Narna I CYJ, Core Shield I Trafn-30, iorn Shield 3 Air (ap WaII Clad Durce Dimensions 762.0 m 7,62,cm Dose Points x 381 crri 12 ft 6.0 in ShieIds limarM c as a 7,62 cm' Cenr;.65 cm I tu 25 ft 3.0 in z 152.88 cm Lit e 1.8/.86 c. Z4 e 2.4 0.0Ci22?1.86 LrA Tt F, i C9.1unt 30.48 cm ConcTet Ai;r.025 cm Ircr Source Input Groupirni Method: Standard Indke&fumber of Groips: 25 Lowet Enetgy Cutoff 0 s Photons c 0.015: Ljcluded Library: Grove 010 6,074.e+000 4.50OaoOC INawfire tcuimi Eu 154 1,641L I" l 19 1Om=1,665t0-004 Buildup The material refroncc is: CyL Core integration Parameters Y Dircmron (tia!5 Ci rcurnterenitial 20 EnAtivit J4 1.236e+00 JJUCJrnrt RalO Fljrin M_ RaF&M4Iat.-m 2 t/~f M#Vkm t/*f~rpfz Nr, ffjildwo~ MMrt SUjI&,D 2.879i 50 M*57oe-J-agowre RIto mR~hr flo 1301Jiggr 8.312e 53 ,Mpftr 6th Ri8l8 titu 6,886e-36 Cl-181 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 DOS Fite 'B:122133.MS15 Fvn Date: DNceimber 21, 2005 (butn tme: 6&08.42 PAA Duration: 0-0M.:01 0.05 3.140-01 0.1 2.45A8eO0 0,2 4.148e.01 0.4 4.334e-02. 0.5 1.315c 02 0.6 4-900e-01 0.8 2.369"O 1.0 1.869et00 1.5 2.370eFOO TOTALS: I1.158e'e01 .ntgen Wv.O B2 &.6ldt=2.246e-35 4.21ge-19 2,571e-16 4.059e-15 6.223a. 13 1.723e-11 4 957e 1 1 5.6a5e.10 6.30 e-10 MyYt RitiCIL I .455e-33 4.066e-17 4,058e 14 3172e-13 2.977¢r13 2.64le-11 9.e57W 10 6,267e-D9 7.728e09 ,Expolgr Ratet 5 953e-38 6.455e-22 4,537t. 19 7.908e 18 0-04De 17 l21 5e 15 3.276e. 14 9l.35e.14 I.46le-13 1 -0 33* 1Z2 Wilth U11uila~3.876e-3G 6.251e-20 7.162c-17 6.181e-16 5.843( I 6 5.154.e14 8.920e,13 1.780c.12 1054e-11 1.327e. 11 Cl-182 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 croShield vS.04 C5.04-W362) hTikro45hbld v5.04 (&04-00362) Radiatoglcal Setvices, Inc.ConywssiOn of caikulatd exposure in air ta dose FILE: CAXMS5XDATA\P8S12.21aHMS Case Ttle:c Line L.S111 This case was run on Wednesday, December 21 2W5 at 6:0B:42 PtA Dose Point F 1 -(13178 ,B 32lt. cm Fistyits -f nmed over energies>'ilithout Mb Ryld poton Flhente RatC (itawx)Photon Energy FlUef e Rate bEposure and Dose, Rates-poure Rate in Air Absorbed Dose Rate in Air a Photons/cmrlJsec MeV/fcm/sec 4.478e-0I 0 6.309L-010

5. 7755009 7.728e.009 mR/hr mradi/hr 1.073eO 012 9,371w 015 9.371e.013 1,327cO 11 1.1618e-013 1.1 68e.0 1I Nep Dose LEuiv-jMen; Rate o Parallel Geometry a appou-d o Rotational a I s0ilropic Shallow oDuse Equivalent Rate o ParalIle G0erMRtry-a (pposed o Rotational a IfOiiOV14C (ICRP 51 *1987)rniv.f hr N N (ICRP 51 .19-7)m~s/hr a 1.062e.014 9.237e.015 9.237e-015 8.278*.01 5 1.125c,014 1 .088e-O14 I.Oa~e.014 8,720e010 5 1.31Sn0 1I3 1.139e-013 LiaS~e 013 1.020e.013 1 295e.013 1.347e-O]

3 I .34-7e013 1 .076e-013 E~-tevo so> Equkvalon Rate a Anteroor/Posterior Geonmetry C' Poniei.'*n1ericr o Later-al o Rotational o I'oE t-,p (1lCRP 51 1 sM7)m.y/hr a 9.5&01 5.86 6e -01 5 7.143e.O15 8-002c.QO] 5 7.125e-O35 1.184e-013 I .M94e-013 8.77c-01,4 9.87 1e-014 S.765e- 0l 4 Page iL Cl-183 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 fAlcroShield v5.04 (5.04=00362) Radiological Serviices, Inc.Page I tDOS Fite !P61I221 34.S5 ML wtv; Dmcerbe 21,. 2005!Rpui'Time:, 6:,04:26 PMA Durativn ; QUOM;Q Fil-* Ref;Date:__ _Byd __Checked: Case Title: Line 1.ii E Descriplion; Revie 994ofe Oaic Ag-1Oam Unit Act w Sch*d 40 & 12 Im Shf-d Geotnetry: 10-~ Cylinder Sufface -Exiteirrial Dose Point TnI I Source Wfeiin Height Rladius* 1 13818e c 4 ft6,6 i Shield 3 Air ~~ap*iV 1i 7-62 cmr IDq Poinb M 381 cm in 12 t 6.0 in Sh~vIds DL+/-imgnao MA=7.62 c~m' ~Donv.65 cm I rat 25 ft 3.0 in z 182.88 cm 15ft'I b~efr71tv e 1.8).86 e 2.4 0.00122 7.56'L1 Ie I I 3i0.448 cm Co~nc'eti AP'S~oirce Input Group~ing Method -. Standard indices N~umber of Groups ,2 Lower Cne#qy Cutaff 0.01$Photons < D.015 : Excl~uded Library , Grove a beaueg~s u(rilcmz V91 §,Q?44v+QQ9 4,5QQQtg.? Ag-106rm IM417 1 99 1 §65X04 134si1dup The mat~erial reference I:Cyl. Care Integra~tion ParameterE-Y Direction (nxiat)Clrcumrfearential 20 20.L % =A r fi ib i l u. r'n f R 9 I~)2 ,984e+O1Q 3.51le-269 Resudts~-ftio~nrA RM't.B ,557e*34 1.2 16e-27GJ rioosure RatR 2. 9649.35 Cl-184 Plum Brook Reactor Facility Final Status Survey Plan 'Revision 0 Pagc :2 DO$ FlIe : P6122134,A$5 Rftn Date; -scamnber 2]. 2005 Run lime, 6:04:26 Pp Duration: 00:00:01.W-d 0.03 0.4 0.6 0.8 Activit inhaloshoee 1.29e406 4.305ew01 5.46O*+00 5.491e40D 5.497e+QQ lyenc* Ralte Nio BuildupD 6.693e- 100 2.930e, 22 5;113e-13 6,975e2i?3.997e-I 1 4.746e. 1 1 RuerPM Rate 6. 125e40 1.6130e2O 3,9%6e 11 2.9%SeI 10 1.Qg80e9 mR/6,633. 102 4.637e-25 9,9 1 .6 1.3f1le 14-7.63e-14 ES ur BetlY 6,070e-4Z 2.553t.23 7.787e- 1 4 2.070t- 1 ;TQTAL3i 2,9mv1 1.424e 09 9,064e 14 2.726e- 12 C1-185 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 M~jCro*$h~e~d Y5.04 (5.04-00362). Mlcrdlhield wY.O04 OA4-00362) RadiotogIcaI SetVkes 4 In.C.ConversOm of cakulated exposure I1w11 AO -dto o FILE: CMASMSDATAIPB12214MSS easc Title; Line 1.U1 E This case was run on; Wednesday, December 21, 2005 al 6:04:26 PM DOm Point # I1. (1387 81A18..8$ cm 12/2.1/05 Rgsults (Sumrnmed over en2Wgie)Pti~ton Fluvrice Ratie (flux)ru'tton Ew~ey Fluence Rate Exposure and Dose Rates-E~xpasure Rate In Air Absorbed Dose Rate in Air Deep Dose Eq~uimaert' Rate a P~arallel Geoffetry o Opposcd o Rotational q l 5 101fopic UD&~Ptiotons/cmi/sec MaeIcm?/56C mR/hr may/hr mrad/lir IVC-RP 51 .1487)m$Vlhr U 6.287c'0 11 4.746e-0O1 1 9.064e-0 14 7.913c.016 7.913e.014 9.263e.016 7.552e-016 7.552e-016 6.676e.016 1 .954e~009 1 .424e*009 2. 726e,012 2. 380e.0 14 2.380e-012

2. 7940-14 2.268e 014 2,268cQ014 2.005e-014 Shikkow' Dqsc !quivvIornt Rwto a Para.leI Genietry o Gposed o Rotationa' o lsoTtOPii (ICRP 51 1987)m~v/hr U 9.890e*016 9I426e.O 16 9.426e-016 7,144co016 2.979e-014 2.837e*014 2.83 ?e-O14 2. 145e.014 a Antertor/Posterior Geor"itry n Pn%1ft1k:.n/Ajter~or o Lateral o Rotatuonw~

o lsc1ropic IJCRP 51. 1987)mSv/hr I 81236e,~01 6 7 .347e.016 5 .537f.O1 6 6.573e.O3 6 5 ,637tO 6 2 .481c.014 2.208e*014 1 .659e 014 1 .976ec-014 1.691v-014 Page 1 Cl-186 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NIIcroShleld Y5.04 (5.0-00362) Radiological Services 4 Inc.Page :1I DE0$ File -,P8122135-US5 RL ate. Dcernber 22. ,)RuTh fi,'me: 6:D6:00 P14 Duration : 00;OU:Oi File Ref_Checked: Case Title; Line 1.1r De~rpso'ioo Rewised Mo~del Ik b -~4iMt kt w Sched 40 & 12 in Shid Geomnetry., 10 -Cytinder Surface. Exutrnal Dose Poir Heie*wt ftdius x O lb 1a.7 tir iuroe Dimensbons 762.0 cmn Dose Points I 22 " U in Shields 7.62 ~~m Concr.63 crn Waro 25 ft 3.0 in I 112.88 Cm 6 i 1v 2A4 e 2.4 O'X1122 7 .&4 Tromiitr S hield 3 Air' Gap WallI cVlad z C'nmue",I 3048 ram Ccwrcret 0-25 cm Air 025- cm ron ret I1 Source, Input Grouping Method ; Actual: Photon Ener 'ies N-,94 1,64 7e (O' 6,Q44o+OoO 4~5000v (39 1-C5Eakm4 The malarial reference is .CyL Core I ntagxation, Parameters ~ Orcumloc.-itia' 20 20 Activity 0.0174 2.148c-03 D.0175 4.li5e-03 0.0196 1.209e-03 0 7026 6.074e#00 Ili 6,0744e+00 0000e400 13.000e*OO 4.07Re 28B 2.031ei 1 7.282e, 1 r luence Rate'3.7 04w 37 7,163e-3,7 2.516e-37 6,748c JO0 1. 743e.09 UnrtoLsurr ROP , 0.000e+DXO 0,Ooae+00 1 .503e-289 3.417ce14 1.37le*L3 3. 79.3e-38&3,291e*1p2 CI-187 Plum Brook Reactor Final Status Survey Plan Revision 0 Plum ffrook AleactorP acility Final Status Survey Plan -~Revision 0 Fage ; 2 pi.FS File: PEI122135.MSS Run ate

• Necernber 2]. 2005 Run Time, 6:06:00 PM Duration ; 0:00:01 Law NIP.Y Activity nhuoton/s RiunseriRat No SuIduR iluence FRate ,Mm,/sett mRlhr mRahr^With Su~itduo TOQTAL; l,2101:'Q 9,3140-11 2A418B-09 L.762e413 4,582e1 2 Cl-188 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Fmicwrohhed v5.04 (5,04-C362)

UIflcroShIild v5.04 (5.04-01362) Radioloagkal Services, Inc.Commes Oon of calulated expowre in air to dose FILE: CtAMS5MATMP812213S1AS5 Case TAJWLin 2.81 F This case was urn on Wednesday December 21, 205 at :06:OO PM Wue Point 9 1 (1,M78,38,18ZOO8 cm 22/21/05 gait5 Summed ovr mnerg-ej Units Withm PhNoton Flueigy FRte Rax)P~tan Ernfg Fluence Rate!Photons/cmr sec Me. V/Cm*/SeC 1 .125.-014 9.314-01 1 2-.962e-OO! 2,418e-00,9 Exposurm and Dose Rate-Exposure Rate In Air Absorbed Dose Rate in Air U mFfhr mGy/hr rmra-/hr 1.752c 013 i.538e4015 1,$o5f(13 4,582e-012 4OOOe.014 4.OOOc.012 Deep DOse Equivaent Rate o Parallel Geowetry n {OppoSe.C o Rotational Shavlvo Dose Equiwi,!Ont ROtO a Parallel Geometry c Oppcsed o Rotational O 1 sotfopi *Eflective Dose Equivalent Ralte u AnterforiPostetior Gewr-try o Posterior/Anterior f LaLteral o RDtat-'.onav fp fidlimfle (ICRP 51 1987)mSv/hr a (fCRP 51

• 1987)mSv/hr (ICRP 51 1987)mSy/hr.!.JlS0?015 1.47e415 1.474evO15 1.304e-015 1 .9136-015 1 825e"S 5 1825e-015 1.39seO015 1.595e015 l43le-O15 1 .890-015 1 .282e-C 15 1L1058415 4.655e.01A4 3.83le-014 383le-O14 313We014.4.977e.014 4.749e4014 4.749e*O14 3.625ei014 4.149e-014 3.721.Q014 2.826e 014 3.331e1tg14 2.86e* 014 Page 1 Cl-189 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mi lcroShield v5.04 (5.04.00362)

RadiolOgical Serices, Inc.Pape :1I DO-- File PBI.22925.14S5 RL .- ate: Coaftr 2%9 2CO5 Duratiarw WQOQO;Q1 Fjil ROf' _ __ _ _ _Date:______ BlY, Case Titl: Line 1.81 G Daesvirptian: Revised Modeli C4.1c- 1-120 Unit At wv Sched 40 & 12 In W4i Gewmetry: 10 -Cyllader Surfac.e -External Doe Point A: Height Radius X;N 13&-78 cm 4 it 6.6 in:Shield I Tronsilion.shield 3 Air Gap Wall~ Clad owrce Dnirensions 762.0 cm 7.62 cm 381 cm 12 ft &O0 n Shields 7.62 cm' ConvJ.65 cm I ra 25 ft 3,0 in z 182.8I8 cm G ft te 1.8 7.86 t 2.4 e 2.4 0,X1 H2 7.86 rat n'I.Concrt 30.48cm Comcvet Air.02 5 cm Iron Source Inuput Caroutping Atethod : Actual Photon Energlei becouprels Orn 1.6417ae0]0 6.0744e*150 4.5000le-009 hn;&1-1.29 1 .6650e-004 Buildup The material reference Is Cyl. Core Intetratlon Parameters Y Direction f axial)Ci~rcurnfarertial 20 a0 Eney 0.0295 o 'n396 1.212e+00 2.249e+00 7.99e*-01 4.568.O I 3.9 14e-98 2.4470*95 1 .708e,72 6.56.5e.52 Re sults Si468e..34 1.046e.33 5,460c-~34 5.650e344 4E.ooste~ 1002 2.479e-97 1,215e, 74-2.98 3e-54 5- 72'3"~6 1 .05ge-35 2,522e-36 I I i Cl-190 Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 Page .2 DOS File; PS122925,MS5 Run Date e December 2E. 2005 Run Time: -3 .Q2 PM Durition 00O-OO01-.zkt Attnrity e photon TOTAL$; 4.718e*0 Fluont* PAg I Flen* We Eounre BLbr.V ~ 69m.c. 2ME111L'o Swildg With Bidp No Igildlu f 565e-52 2c,6934e33 2.983C 54 enrR/hf W2th R22iff.22,72e.3F5 Cl -191 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MilefoShield v5.0A (5.04-00,362) MicroShidd w5.04 (5.044M362) Radoloogical Servim, Inc.Comcrsion of Wccklallcd expos~ure In air to dosi FILE: C:\a1SS\ATAW13122925,.MS5 Csse Tilfe! Une 1.81 G This case was run on Thursday, December 29,2005S at 3:,29.,02 PM~Dose PoiInt a 1. (13 c~~1L m 12/29/01 Ugsults (Suminrd ovier enen&4 e-Phioton Fluerice Rate (flux)"tOton Erbergy Fhence Rate Exposure and Dose Rates: Exposure& Rate in Air Abwrbtd Me Rate in Air I illr Phaotms/cm'/we Mhbnu+/-iA 1.65ge-G5O' 8395t,032.6-56.4Q2 2,694e-03.3 mR/hr Mn~ylhr rnrad/hr 2-9aae-0.4

2. 6O50G0O 2.GO05e-054 2.272e-03$

1 .984.-037 I .984e-035 O'vap Doz Equivalent Rate o Parallel Geometry a Opposcd o Rotational S~l~aIw Dose Ecu-i'alent Rate o Pafallel Geomne try o Opposocd a Rotatt-onall a lsoterm2p o Anterior/Posterior Geowr~try o P'osterior/Antenrta a Lateoral o Rotational o lsotroprpc (ICRP 51 1987)mSv/hr (ICRP 51 -1987)mSv/hr I (ICRP 51 1987)mSv/hr U 3, 7 28e.056 1.878e-0O% 1.70i~5 1,62,6e56 3. 751 eG056 2. 589e*056 2. 589e.056 I ,900e.056 2.174e,056 1.3 14e*056 7.2590.51 1.1 82e*056 9.685e.057 2.27le-03T 11A3ge.O37 9.71 7e-O39 9.025e-039 2, 4 75e-037 1 .7O2e4037 1. 702 0?37'1 .25Be-037 1,01 So.037-5.264e-038. 2,84lvo03& 5.2-31"-38. 4.3343ti o2-W Page 1.C1-192 Plum Brook Reactor Facility .Final Status Survey Plan Revision 0 NicroShleld 15.04 5.04.00362) Radiological Services5 Inc.Pap : 1 IOS File : PB010407,MS5 F. ate; J.Anurny 4-, 2W RuerIime! 8 1 S.821 AM Duratien : 00:00:01 File Rer: __ _ _ _ _Date: _By:, Cheche>d;Case Title: Line 1.81 H DescTirptla: R¢vised M0Ie Cate. Sn-126 Unit Act w $5Ch*d 40 & 12 in Shid Geometrty 10 -CylInder SurfaCe -External Dose Point I leight Raius N1 138,l8cm 4 tt 6.6 in Shield 1 Transit'on Shield 3 Air Gaop wely il uwrce Dimenisions 762.0 cm 7.62 cm DPoe PsintL 381 cm 12 ft .in Shields 7.62 cm' Conc.65 cm Iro 25 lt 3.0 in 182.B cmn 6 Ft B 1.8 7,86 e 2.4 e 2.4 0,00122 7. , Dri ret n1 Concret 30-.48 cm Conrfet Ai-,QZ5 Cm l rwn Source Input Grouping Method Standard Indlces Numrbei of Groups: 25 Lower Energy Cuttol .i 0S'Photans D.015 ; Excluded Library GrwYe I 6e.rninre0744 0 40; r0m2.010 6.0744"00 4.53C380OC Sn-126 1 6417e 'C9 1O-m5 1.6650e-00 BOuldup The material referec Is : CyL Core Integration Parameters Y Direction (axial)Circumferentiat 20 20 Ene I-_.4hn70et 4. 7 02e.0 1 MAV~eltcmte M,-V--nlsf 5e YI~ougiy With Bu 4.143e 270 -1.010e34 N<.5e. Oildt71 I .Q35e271 fEgsyre Rate With kRuildilrn 3,498e 36 Cl-193 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page ; 2 DOS Xfl* : P8010407.ASS Run Date: January 4, 2OOj Ran Time! 8:1$r21 AM Duration : 0 -0:01 003 OMe 0.04 0.060 0.0$TOTALS: Acti 1,7794+100 3.034e-02 5,82le401 2.789e*00 5.650e*00 flutence Rate U0 LDiwv 9.22ge-94 4.613e-52 4.7ge-28 1 .899e-21 1.899e-21 Fiuerice Rat-e W.V/,rrtf ieete With Buildup&.4469e34 3,821c 35 1.4 10e-26 1.045e*19 1 045e-19 Exs osu re RFat ,rj~hr.140 Buildup 9.147e.96 2.040e954 1001e 24 3.UOSeF24 Exwesure Rate MSh.8.371 e.36 1 ,690c37 2.801 e29 1.654e-22 I 654e 22 Cl-194 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicrAideld vb.4 (5.4." 62)MicreShicld .L04 (5.0445.062) ftadlilogicat Services, Inc.CiiwarsiOn of l1cJulated expSr-Mm In air to dWM FILE: C:%MS5%DATAPE01G4G7.MS5 Cate fltie+/- Line 1.1 H This case was run on Wednesday, January 4, 20KS at 8:18$ AM Dose Point i 1 -(138.79S112a.E8) cm 01104/06§4.cg1I ijmr~rA ,w pr gnewiw Photon Itnuence Rate fOUC5)Photon Enefgy FRuence Rate Pot4ns/orr?/%vsc Me/Wemk/sec 1Wi-thout 2. 373e-D2O l899e02 1 Bu~idup 1.307e-018 3 ,045c-03 9 r'xrxmure ad Dose Ratesr Exposure Rate in Air Absorbed Dosc Rate in Air W mR/hr mcy/hr mrad/hr 3.005e-024 2.623e.024 1.654e-022 1.444e-024 1 444e-O22 aop Dosc EPq'vva'nt Rato o Parallel Gmeometry a fOppnsfn'C o Rotational O IsottapleC Sha[fow Dose Equivalent Rate o Parallkd Gieorpltry a Opposed o Robatiottrl o I satrop.c Effective xDse rq"4Vae'?io paic-a Anterior/Posterior Gerometry (i Pewilr/Arnterirjr o Lateraw o Rotational n lsotroptf (ICRP 51 1987)m~vfhr (ICRP 51 *1q87)m!5/hr f,.,CIP 51

• 107)mSy/hr U 4. 5S8e 26 2,444g-26 2. 375e-026 2358&0(26 4.545e=O&6 3.341e.02 6 3.34le-026 2.452e*026 3,853e.026 2.939ef026 1 .B1I e.026 2.$03:3e602p 2.025e-026 2-52fie-024 I 345e-02 4 i 3O8e-024 I .298e-024 2. 502e-024 1 ,839o 024 1 .839e424 1 .350e024 2.12 le-024 1.61 O04 9-72e.025.378e.024 11 Me.O24 Page 1 Cl-195 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 blicrotlield wS.114 (5.04-00362)

Radilogi~cal Services, Inc.Page ~I DC$ Fije

• EPB122927JOM55 Ri. atet Decen-ber 29, 2C05 Run-Time!

3:-3!53 PM Duration, : 00:';00:0] Vito~ R ef; _ _ _ _ _ _Date:______ Chected;', Case TMte: Line I.Eli I lDe~ojp~tlo~: Revised Mod,*I Va~k Zi'-95 Uiit AWt w SOW4 40 Z& 12 in Shld Geomnetry: 10 -CYl1nder Surlace, -External Dose Polint Sour Heighit Radius~1 138.78ecm 4 ft6.6 in Cyl Caore 1 Shield I Transili itnn Shield 3 30, Air (Cap Wall Ciao .0 Sourice Input Grouping hMethod : Actual PhDton Energies 1.64174.010 -6,0744-e+000 4MO5e000'O9 'ce Dimensions 762.0 cm 7.62 cm)Ole Points 3S1 cm 1 12 It 6.0 in Shields~anrbmn M2&t~jP1 52 cml Concreke.65 cm Io Congrcte 481 cm Concrete AIr 25 cm lroo 25 1t z S2.88 tM 6 ft 2,4 2A O.0022 7116 Zr-95 1Bo/cm'KI The mater'IaJ refreme Is Cyl. Care 1ntegration Parameters 2D 20 Enejg AStijjtv MO24 pho.6 s/2e40 Resuhts Eluenc Ratt Fluenco -Rate M2V/CM'fsetc Me0Vkm"/1eq il.064e-1 I 3..374e-10 1 J56O 1 5205*'1Q 0.7567 TATALS: 3.3&2o-00 6.0 14e*00 Eix~osure RM~MR/br 2.046e- 14 5.407e* 14 Ads-h RI ll1diai 6,45.. 12 9.9620 Ls 1.6415e 1 2 2.B2Oe*1 1 8.579e-10 C1-196 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Wlcr*$iged v5.04 (5..04-00362) MicroStdelld v5.04 (50K4-0062) Radoloea Senvitee, Inc.Caomersion of calculated ~osumr In air to dose FnLE: C:IMSM\ATA\P6122227.1M1S5 Car.4'M~ T .~ Lilgi 1*M I This case was fun an Tbursday, Decemiber 29, 21005 at 3:33:53 PM base POWn f0 1. 1f, 812~)c 12/29l05 Re&AW5 , I- -d Ive lnries)USit1 Without Efih Photon Energy Fluence, Rate Photrins/crn'/sec MOV/cm 2/Sec 339OL-01 1 2.B20e01l 1 1.1 54e0O" 8..579e-0100 Exposure and Dose Ratesw j~pfsure, Rate in Air Abs.orbed Dose Rate in Air M mR/hr mrGy/hr mrad/hr 5.407e-01 4 4,721.-016 4.721 e-01 4 1-64ge-012 1 .436e-014 1 .436e-012 O m Dst Equwviont Rate eo Parallel Geometry io Opposed ma Rotational (ICRP 51 -1987)mSv/hr I 5.534e.O16 4 .500e*016 4.$OWL-016 3,978o.0 16.1.693e.01 4 1.369e-014 I .3690oO1S 1.210e*014 Shallow Do~se Equivalent Rater io Parallel Gm4-rtry o, CJOposeed io Rotational la kpolropic mSv/hr U 5 .9g8*.0j16 5,630e.0 16 5-630e.016 4~257e.Q16 I .797o*014 1.713e*014 1,713*.014 L 295e-014 Effociiva Dose Eqiuiv~alcrt Rate* Anterior./Posterior Geometry P3 Ploseriao-/Anlerlar Aa La'ter-W o) Rotational 10 lsafrop" (ICRP 51 .1q87)m~vhr U 4.91$ e016 4.37geQ016 3.292e036 3.916e-016 3.354e,016 1 .495e.014 32333-t,014 1-001e-014 1-l91e.014 I 0,20ff Q04 Page 1 C1-197 Plum Brook Reactor Facility I Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield w5..04 (S..04-00362) Rad~oio~call Services, Inc.Page 1I DOS File PB122928.&MS RL te: December 29,3 5 Rua Time: 3:35:35 PM.Duration : 00:00:01 Fii Ref; __ _ _ _ _Date:__ _ _ _ _ _BY: _ __ _ _Chook.edi _ _ _ _ _Case Title: Line tUi J DecsrlPtlon; Revised 904el Ca~t- Eu*155 Unit AO1 w Sc~hed 40 & 12 in ShId_____ Geometry: 10 -Cylinder Surface -External Dose Point Ilcigeht Radius# 1 13a.78 cr 4 ft 6.6 in LO Name I CyA >teo Shield I TratnitLin Shield 3 Air Gap War! Clad)urce Duimensions 762.0 cm 762 cm 1hliQ' Polfli 381 crn 12 ft 5.0 in Shields 7.62 cm' Cowc-.65 cm Ira~25 ft 3.0 in z 182.8a cmr to 1.8-7.86 e 2.4 e 2.4 0.00122 7.86 Uria ,et 4.30-48 -cm Ccncret Air ,025 v-rrx Iran Source trppta Grou.ping Method -Standard laidces~Number of Groups r.25 Low'er Emurg Outoffi 0.01$~Photons '0.15 : Excluded Library: Gircwe 010 6. 07 4 4e+000 4.50C02e-0O ,Wnriida =64 Eu- 155 1.6417i--9 1 .6650E-DO.1 The material reference Is : Cyl. Core.Integrat;Dn Parameters; Y Direction (axial)'Circumicrential 20 20 O03 1i9~3c02 Flijnn &P1 2elmle fltience. Rait, 9.1B10-36 9.943e.98 Er~2ur#m Rate Cl-198 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pag : 2 DOS File -PEI22928.MSS Run Date: Dscember 29, 2005 Run Time 3:35635 PM, Durltion : 0-0001 0.04 0.06 0.1 Activitc LIOle+tC 3-5$10 01 7,878es02 1 .3it+S0 1 25&e+C0 Fluence Rate 1.674e-50 2.561 e 36 6.467e-29 1.-24e-21 2.155e-19 Fluence Ratp-M.^.VknWrn'Js Wth bQilgUd 1.387e-33 I .esae$3 1 99e-27 7.068e.20 Z.037e-17 FwsturrFt mRfhr No Suildunl 7,403c. 53 6.824e 38 1 .285e-3 1 ZO12e; 24 3.297e 22 ,m~hr With R iljfllP 6. J M 4.421 e 36 3,791 e-30.1.1 19eI22 3.1 93e-20 TOTALS: 4,6We+00 2,168e 19 2.094-17 3$31 8e,22 3r.204e-20 Cl -199 Plum Brook Reactor Facility FinalStatusSurveyPlan Revision 0 MicroSibleld Y5.0.4 (S.04-00362) M~icroShieldf v5.04 (6.044MG32)z Rtadletegkat Servim.~ Inc~.Conversjrjn of C41culitted .xpoaure Iin air to dose MlE: C:AMSS\DATAkPB122-928,MSS C~se Teie+/-, Lizie 1-81, J This. case was run on, Thuzrsday, Doembear 29, 2005 at 3.,35 :35 PtA Dose Point a 1 -8 4 31S28 c 12129105 L'Uslts (Summed over eI1e5rfij; Uanit Without 2.171 e.011 2. 168eO 19 2 .096e*016 2 ,D94-o-017 Photon Fluence Rato (flim)Phoiton Energy Flueime Rate N~iotans/Co1/Se~c MeV/cm t l/sec EZxposure and Dose Rates-Exposure Rate in Ai, Absorbed Dose Rate in Air n mR/hr mGy/hr rmrad/hr 3.3 18e.022 2.a~6e,024 2.896e.022 3..204e-020 2-79,8e-02r0 Ocep Dowse Equiv*lunt Rate!o Parallel Geomretry a Ugpped o Rotational o l$ottopic rnSv/hr 4.$42e!-Q24 2.655e.024 2.654e-024 4 6769-02Z 2.564e-022a 2-564-e,02 2 2,481 e-022 S!mlkow Dose Equivalent Rate'O Parallel Glometry in Oppo"ec'so Rotational IU10vp Etfectiv'e Dose Equivalent Rate a Anter~cir;/Poslerior Geom, try.-o PosteriWrAnterior a Lateral o Rottikinal ci Isotrop~t CICPP 51 .1q87)m~yfhr (IGRP 51- 1q87)m-5v/hr K 4.81 O-024 3.731e.024 3.731e-024 2.71 7*024 4.162e*024

3.263cO;Z4 2,014e.024 2.787e 024 2,217e.024 4,4m022 3.604e-022.

3.604ec 022 2 Z2 4 e-022 4A3 9e-0:22 3.1 52e.022 I1.945e.022 2-69-c2v2 2.1 42e.022 Page I Cl-200 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362~ Radiological Services, Inc.Page. :I I of Flit P8i21919.MS5 Rt ate.- Decembe~r 19% 2005 Rvu "time: 2::4 n M Duration ;0G00M.01 ric Ref;_____ZDate:__ _ _ _ _Cheocfied;__ _ _ _ _Cast TRWle Line 1.82 A2

Description:

Revtised Model Oakc. -Co.60 Wit Att w Sched 4-0 & 12 in Shfd G- eometry: 10 -Cylinder Surface -Extefial base Point Sour Height Radius~1 134.97 cm 4 ft 5-1 in Shield I Transwitioni Shield 3 30 Air Gatp Wall Cad .source Input Grwuping Method : Actual Photon Enwp~es 2=1 b~gass Oilm~8,2067011 3tQ72,v+QQQ 4MMQO0~ 9 ce Dimensions 762.0 cm 3.81 cm Dsse Point 381 cm 12 ft 6.0 in Shields ,1 cm 2 Cow 65 cm Iroor 25 fL I 5 in Z, 137.16 cmi 4it 6.0 in j DcnMO:0A 7.f8b v 2 4)92 0.00122 7.86 fre Goncret 48 cm Concrell 25c an I=1 .&QC-M Buildup'The materlal releience Is : CyL. Core Integralion Parameters Y Direction (axial)Ci rcumfuruwtial 20 20 ct.69398 1,1732 1.3325 4.954e-O4 3.037e;013 Flupance Rate 1,.479e.14 2-$c09 Results With Rujildupw.3.875e- Z3 I 605e.os 7_478PO~B Eypos-ure Rittk 2.856e- 17 23110e*12 7,482.. 16.869t0*1 1 4.299e 1 1.'ALS: 6.075e*00 3.646co09 4,083.08 6.1393 12 7,167o 1 1 Cl-201 Plum Brook Reactor Facility .Final Status Survey Plan Revision 0 M' .creo$ie4,0 v~4 (1-04-00362) Micro~hicid vS.04 (S.04.0032) Radleloglicat Servftres, lne~Covrslion of calculated cxposura in air to dose FILE.- C:%M55\DATAXPB1219190MS5 Cms Titllc LIe L,82 A2 Thi~s cas~e was run on Mon~day, Decemnbeur 19 ,2005 al 2:26:48 P-M 12I19/m S=,JA4t9I 3 PHr nr a=Wgc 4-063e-00a Ph~oton Flut*,e Rate Ctfux)Pliolon Eswzy Fitdence Rate PhotDns,/cm1Vsec 1AWCkmI/Se 2.868e*009 3,64,69-OD9 Exposure and Dose Rates: xpioswr~. Rate in 'i Absorbed Doso Rate in Air mnR/hr mG&Th4 mfrad/hr 6.1303eQ]2 5.581le.014 S'81 e3OJ 7,J67c 01Il 6.257e-01 3 U.57c 01 1 Deep Do'se Equivwdent Rate o Paral lel Geome~try o Dppov.-o o Rotational o Ilsct7opic. Shallow Dose Equwvaent Rate o ParatleI Goomets-y ci Oppos~ed o Rotatonal o Ar~ten or/Posterior Geoiretry o Pos~eriar/Anterior a Liatecral o RotatiOnal o strp (ICRP 51 1987)rnSYvhr (ICRP 51

• 1987)nSW/hr (ICRP 51 1987)mSvlhr 6.335e-01 4 S .458e-01 4 5 .450c ,01 4 4-.876e-01 4 6.743e-01 4 6-493e-DI4 6 4930-014 5-A65e.014

5. 705Le.014 5,256e.O 14 4. 182e.014 4. l33e.014 9 7. 104e-01 3: 6.11se-01S 7 .563e-0113 7..28le-013 5.790e 013 6,397c.0 13 5.892e.0 1 3 4.6&6e-O 13 5.30Ge-0 1 3 4.695e*O1 3 Page I Cl-202 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 filicroShlded v5.04 (5.04-00362)

Radiological Setwlees., Inc.Page. :1 DOE- File :Pal.22136MSS Ru ate.-De.cwmber 212005.Rwi-riew 6,22:30 PM Duratign z QiQ;Q;Q1 File Ref:______ 'Date:______ By., Check~ed: ______Case Title: Line 1.82 B IPoeseipli*a: Revised Model Cuae. Cs-137 Unit Act w Sthed 40 & 12 in ShId__ Geometry: 10 -Cylinder Surface -External Dose Point 91 I-9 ...2'. I Height Radio-C 4 ft 51 in CYl. Core .Shield 1 Shield 3 30.Awr Gap'Nall Claid t0 Source Input Groupings Method : Actuai Pboton Eneties 7..7654e.011. 2.9732e+OWY 4.2570e.00g 8.2087o.01 1 3.0372e4000

4. 50O0e.009 762.0 cmn 3,81 cm lose Points y i81 cmr 12 ft 6.D in Wehlds 31 cm' Conc..64 cm Ire 25 it 1.5 in z 137.16 cm 4 ft6.0in*e 1.8 7.8E6 te Zi4 e 2.4 0.0012?7.86 ret Concret 48 cm C-oncret Al~125 m~ I rcr 19 37m Csa-137 1 .6650e-004-Bui idup The material reference is : Cyl, Core I1tegration Parameters Y Direction (axial)Circumferential 20 20 0.0318 0.0322 o 0364 516 A41IR4J 5.948e402 1 .0§7e-01-3.994C-*02 2.585elkO&

3.402e- 73 4.917e-71 3,40 1 Rerrull.b MJV/rM2/qCAr 4,329e-35 8.299e-:45 4.625.e 35 2-83-te75 3,9578.73 1 .898e 57 1,1Me-13 3.606e.37 6.679e-37 2-6Nt, 3 7 3.262e* 12 C1-203 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 PPc 2 DOS File: P8122136.MS5 Run C>X. December 21H 200$Run Time. &.22-D3 PM burntion 00:00.01 Ahiv-t ohlanq/gene S. e 1. I EulLI Nt.Vkrri'I4 Fluenrw Rate With PLu,,ffiL0 Exxs;urg Rate rhtl ExMlure Pete mR/hr With E3t~ifigi TOOTAL5 2,794e+0 1 6£3e-09 l1.62e-13 3.262e* 12 Cl-204 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MMccro~hieddvS500 55.44O00362 Radlo~icgkall Services, Inc.Conversion of calculatcd a~osurt in air lo doi4 FILES C:MS5\DATA\08122IaLGMSS Cas Title.: Up* 1.82 5 This case. was run an Wedmneday, Dozember 21,2005 at 6:22.30 PMA Dose Point 9 1 .(l~rSr 3.cm 12/a1/ng Re.gv2Zts ~&imme~d over energiel>Igpii Without With 130fdup Phoon Fl.r~e~ R$e NOux Pboton Enetgy Fluencee Rate Phatons/Crnk/sec MeWvrrw/sec 9.OS94*,031 Z.54,3e,009 5.994e-OI 1 1 .683e*009 Expo'sure and Dose Pgtov Exposure Rate In Air.Absorbed Dose Rate in Air I mRfh~r mc~ylhr r.nrad/h r I. ,162e-0,13 I.014e-015 I 0O24e.013 3.262e.O012 2.8$eo 014 2.848s.O012 [Clep Uost Eqvivolerft We o Paral lel Geom~etry iaOpoe o Rotational ro I SOeOPAe (ICRP 51 *1987)m$v'hr I 1.20le-015 94169,016 9.6 l&e-016 8,503CO16~ 3.7ZeQ 14 2 ,699e.OI4 2 .69ge-014 2 387e-014 S~a ll-cei Dose Equ~valent Rate io Paral lel Geom-stry tj Opposed 0o Rcotational o Isolo (ICRP 51 *1987)mSv/hr Il 1.277eZ15 1,212e-015 1.212e-DI5 9.090e:016 .3.6830e-014 3 .404-.014 3.404e-014 2 ,552e-014 Effective Do-so Equivailvnt Rate o Anterior/Posterior Geom-etry o PosteflarlAnterior o LateralI oD Rotational o lI~otropfa (ICRP 51 *1987)mnlfhr H U 1.062e-01 5 9.374e*0 16 6.951e*Q16 8.377e-0 16 7.132e*O1K 2.98 le-Ol14 2.6310,01 4 1 ~951e-OJ14 2..35-2e-0214 Z.QMv-Q14 Page I Cl-205 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-flO362) Radiological Servlces 1 Inc.IDOS File -.P8122137-MS Ruui Time: 6.25:23 PrM File Ref;Date: By;Cheghd_Case Tite; Line 1L82 C ftcsription: RevIsed M~OOe Csk- W.162 O)il MA w Sche4 40 & 12 In shln Geometry: 10 -Cylinder Surface -External Dose Point-x I Heig*&Radius 4 1 134.97 cm 4 ft iln shield IAP Shield 3.Air Gap Wal I -vlpd wurce Dimensions 762.0 cm 3.81 cm 381 cm 12 ft 6.0 in Shields)iFrr iOn ga+: 3,81 cm' ons.65 cm lro 25 ft] 5 in 137.16 cm 4ft6.0 in LI nan-.ily e 1.9 7.86:£ 2.4 e 2.4 o.o0 12 7.86 rria ret 4 30G48 cm CoenEti Ait.025 cm I rqo, SOUrMt Input GroupingMethod Standard Indices&bro roups -25 Lowe: Erwgy Cutoff : 0.01 Photons 4 0.015 : [Exluded Library :drv 011 3,0372e+000 4,5000e~C(Ny'lide vw Eu-152 8,2087e-'9 1 .6650e-004 Buildup The material reference Is :. Cyl. Care Integrabwi Pvuaneter;, .Y Directionl (axial)Ci'-curnlretntial 20 20 34 11.?97etOQ 1,690e-44 Flutepmrr P~atr wV.r~5e P33 7.474.47~.28Os35 Cl-206 Plum Brook Reactor Facility' Final Status Survey Plan Revision 0 Paze ; 2 He Fir PB122137.MSS Ron Date: December 21, 2005 Run rime 6 2S:23 PM Dur.:tign

M-00-.01 Energy Arivi a~y hns 0.05 0.1 0. a 0. ~0,4 0.5 0.6 0.8 1.5 4.49,3e.01 8,635c,01 2,276e-01 8.212e 01 1 .909001 1.713e.02 II.MBe-01 5MA08m01 1.300e+00 7 .I046.Qw.Fhspnrp PRui-0 1.845e31 1.066e-l7 3.876e I5 2.035e- 3 2.66le-13 S.573e J4 1.762o.12 3.405e-I 1 1.223*,.FlieInr R;eim 1 868ae.3& .iSe-16 4.42e- 13 1.613 1.11 1.536e*1 1 3.61 7e- IZ.l7O5e.1 1 7.258e-10 3,9220q09 1.324e-08 ,Rn/ehr 4.916e -34 6.842e- 18 3.86,16 5.184e. 16 1.6834e 16 3,44- 15 6.477e.1 4 4,75e 1 3 1.570e-12 t"4Rlhr With Buildug 4.977e 33 1.247e-1f 7.802e1316 3,192e-14 2.993e 14 7.10e e15 1.1 14e-13 1.38 0e12 7,230c, 12 1.430e-11 TOTALS

7.040e+00 2,106e6 12 2.30ge-1 1 Cl-207 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MkIo~hieId v5.C4 (5~04.O03&2i>

MkrgShield v5.04 (5,04-0036Z Radfolloglea Sezvlces 1 file.FILE: C.-MlSSI)ATAI5B122137J.1US6 Cage TlIV Line 1.2 This case was rum an Wednesday, Decembei 21, 2005 at 6-.25:23 MtA Dose Pouint # 1 (134.1713R11a4IM a*i)212VI0 6_=ltII1; (I;v e-wpr gnpV,:pr6% 9..226.e.010 1 .22Z3e0U9 1 .00e.00a 1 ,324e.008 Ph~or, Flutace Rae ('1ou)P'tiotn Energy Fluenc~e Rate ,Eicpaoure anid Dose Rates Ex*posure Rate in Air Absorbed Dose Rate in Air U Phortons/cm 2/sc~MeV/rcrn/tec imR/hr mGy/hr 2106it 012 1 .139'e-0.4 I189390 012 2.3~e*0 1]2.016e.0 II Necp Dos;e Equivagnt RODi Or Paralle Geo~metry ai Opposed a Rotational a F$ct~ropic (ICRP 51 .1987)mivhr X 2.08ge-014 1 1307e-014 1 £070-01 4 1. 6174, 014 2.256CQ 13.1.974e-0 13 1,974,013 1.764e*013 Shallow Dose Equivalent Rate a Parallel Geometry 4 opposed o Rotational 4 I*Pltropi (ICRP 51 .1987)m5Vhr II.2.216e.O014 2.1ne-o014 2.13ge.014 1 .707t.0 14 2.4$9c.133 2,350e.O013 2.350e.O 13'Effertive Dose Equivalent Pate a Anterior/Posteifiot Gearnwtvy a Posterior/Akrtrior a LateralI o Rotational a Isotropic mSv/hr 1 .880e-014 1. 737c-014 1.391e-014

1. 566e-014 1.390e-014 2.0fl65e-013 1.900e-013 I.512e-013 1.712e' 013 1.514e-013 Page 1 Cl-208 Plum Brook Reactor Facility , .Final Status Survey Plan.Revision 0 .PlumBrok Ractr Fciliy FnalStaus urve Pln Rvison MicroShi~eld Y5..04 (5.04-00362)

Radiological Services, 4 Inc.Page : 1 DOS Fjle ; PB12213VNMS RL a>e: tDecember 21, 2o05 R iftime: 6:-26.:42 PM Duration : 00;00:01 File Ref;Date: By: Checked: Case Title: Line 1.82 D DescriptIion: Rteimd Modet Calic. Eu-154 Unit Act w Sched 40 & 12 in Sh~ld_____ GeomwctY:- 10 -Cyltinder Surfce -External DOm Point Height Radiu&;* 1 134.97 er 4 ft 5.1 iii Cyl. Cors Shield I Tronsition Shield 3 Air GbP Wall Clad ource Dinuensions 762.0 cm 3.81 cm Dose Points 381 cm 12 tt.Qin Sh'uolds llirwnc-i~nn X a, P.,81 cm' Cono.65 cm Ir&25 ft 1,5 in z 137.16 cm 4 ,Qin te lie-7.86 o 2.4 e 2.A 0.00122 7.86 ret n Goncret ao4 Cm C*Mcve Air.025 cm lros S-uarcec Input Grouping Rtethod : Standard Irdidces.Numbsr of Groups -25 Lower Energy Cutofft 005 Photons c 0.015 -E Ududed Library : Groves bacau#erets .uCilr-'9 Eu, 154 8.2 8e-09 1-6650e-CO4 Buildup The material refoererace Is : Cyl. Core Iotegration Paramieter's Y Direrfion (Oxil)Circumfereatial 20 20 EnroeY 5.181s.01 5.61,3&.45 Rosulls;IWit4, Poikjutg 99Ue-34 2.571la.47 4,404e*36 C1-209 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 DOS Fioe .P8122138MSS Run Da te-w.mbr 21y 2005 Run Thv-,e 6.26.42 PM Our*lik 00004 M.e MtYt 0.1 0.2 OA1 0.8 1.0 1.5.I 7e1 1 .229*400 2,074u-01 2. J61u*G2 24509*O1, 1.184e*0O 9.34:3c.1 1.185f+0 mobviemill* 6.4A $vS , 3:533014 3-021* 14 3 29 It 14 3.3$>2.e i}1 7-459 :, 1 1 I 824v 30 Fhunrear Rake wAV/Crn 1/Sq2 6 5276.31-LlO.ICelS 4.(;2%_j3 1.744e 12 1.368e 12 1.05e. 10 1. 590e.O0 2.820e09 1 430se.0B M~h5 Mg Elilrhip 1,7loe 34 6 23, c 9s sa6.."eri? 6.45 17 6.543e-15 1.41 413 3 361-13 2.40e-12 3.125e 12 tih Buisdup I 7Ye 31 1.775e1f3 7.1 1o 1l R 39e-is 2.725e 15 2-i.1' 3 3.02 3-el Slgfi 12 2;&05e-11 T1OALS: 5 7++00 1.830e-09 I .88;h8 3 249C 1 1 Cl -210 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mi~croShltld vS.04 (5.fl400362) MicroShileld v5.04 (6.04-0362) 1R8idficallk* Serivces, Inc-.Con~rmsio of calculated exposure in air to dose FILE-- CMSXMSMATA\FS122I3411VS, Case Mtte: Uina L82 D This case was run an Wedunesday, Deceivmher 21,2Mi at 6,--M4. MtA 0"ts Pouint ft 1 (- MM97,3151,"7.6) -Cm 12i211o5 UUWjt5 (5,gwm.. go par eng 6P4.-, --ril J12b Without 1 M3Be-009 Mffiiu Pti~ton Ernergy Fhi,#nce Rate Photonsfrni/sec MeV/crnl/sec 1 .453e-008 1 .882Ce0t8 Exposure and Dose Rates--xpour~e Rate in Air Absorbed Dose Rate in Air I mR1/hir m~y/hr mrad/hr 3.1 25e.012 2.728e-014 2.72&0~I 2 3.249e-01 1 2.837c,01 3 2,937e-01 1 Z Dcp .ose Equivwmlnt Rate a Parallel Geo'metry ci opposed a Rotational o I sovooic (ICRP 51 1987)mnSv/hr U 3.09Ae-;O1 4 2.685e-01 4 2.686e-01 4 2-406e-O1 4 3-226e-01

3 2.785e-01 3 2.785c-DI3 2..491e-O1 3 Shalio.w Dose Equivalenit Rate ioOpposed c- Rotational (ICRP 5I 1 1987)mSv/hr;U U 3.2,79e-014 3.169e-014 2.535e-014 3..422e-01 3 13.3O1eO1 3 3-303e*01 3 2. 630e.0 13 Effective Dose Eqwivalent

£satc o AnteriortPostenor Geom~etry U PFjota..firor/A~terior, ci Latera I o Rotathonar a Isotropic (ICRP 51 *1987)mSv/hr 2. 787e.-014 2.5S79e"Q14 2.0 74e-0 14 2. 32Be-0 14 2,Q07Q0.Q14 2,902e*O013 2.fi77e-0:t$ 2,141 e.0 13 2.414e,013 2.1 40Je-013 Page L Cl -211 Plum Brook Reactor Facility ..Final Status Survey Plan Revision 0 MicroShield u5.114 (5.04.00362) Radiological Servlces, Inc.Page :1I Daq~ Fite :P8t22139AMS5 Ru de ; December 21, 2O05 Rv&A7arne: 628:.54 PM Duration : .00.00:01 file Rot; _ _ __ _ _fDate:__ _ _ _ _By: _ _ _ _ _D~escript! IS 777 7 -I I t II Nur-lidr, Ag-108m Case Title.; Line 1J82 E wit Revised M~odel Celt- Ag.W0m n iwt A4. w Sched 40 & 12 In Sftd Geomnetry: 10 -Cylinder Su~rface -External Dose Point!Source Dlmeansions Height 762.0 cm Raius 3.E1 cm U 1 134.97 cm 4ft 5] in 381 cm a22ft .0 in 3.81 cm' Conc~.6Ei cm Ire 25 ft 1,5 in z 137.16 cm 4 it 6.0 in I nmm<itX he I -8 e 24 e 2.4 0.00122 7M.CYI Cvire Shield I Transitian Shield 3 Air Ga Wall Clad I Concret W.46 cm Concrat Air.025 cm Iron rat'Source Inputs Grouping Method :Standard Indices Number of Groups : 25 Lower Eniergy Oizioll .1 rhDtons c 0.015 : Ezmluded Library -GrOTO .be t~jruvrftI UOifcrn'~011 3,03720+CXQ0 4,5WOvOe0 8.20871 D09 WCfM~1 .6650C.004. Buildup The material reference is : CyL Core Integration Parameters Y Direction (axial)Circuwrcf.t fial 20 20 adivdi ti ph!2wLs/s 1 .992e+00 Results No ElyiildUp W-4h FRudI4uv 2 1 L69t-234 5.4739.34 9,593o.236 E~xposure Ra~n 1 £99e-35 CI-212 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page 2 DOS FMIe PI12139.4ASS Run Date; Dhecember

21. 2005 Run Tkme! 662854 PM'h Durdtion 00:00:01-tivity 0:03 6.449e407 O01,0 2152e.01 0.4 2.7?Oe+00 0.6 2.745e4M).8 2.7498400 No-5ul0dueb 1 149e-89 2.021 e-20 3.806e- 2: 3.7S7e- 1 1,731e 1O Fluh~rnr R1 Me~fcmlf sec With EHui Iftn 3.9 18c 4 0 9.243e-19 2.197e l0 1 .216el09 3.6809e09 Frimn-cun Pntjp Ntn Ridifikp 1,1 30-.90 3.198e-23 7.415o ]5 7.333e.14

-3.292e. 13 Exrszure RFate m.Rhr With BLAuipU 3.883e42 1 .45c 21 4.281e*13 2,374e. 12 7.01.7e. 12 TOTALS: 1.043e901 2.14 5e.10 5.125e09 4.,100e, 13 CI-213 Plum Brook Reactor Facility Final Status Survey.Plan Revision 0 bkilraSheld v5.04 (5.0440062) Mcru~hkild YS,04 (S.04-003!G2) Radiological Services, Inc.ConveT;10T1 of calzutatud vxposurv In ir lo dose FILE: CAI\JIS5\DATA\PR122UMMSS Cost Titk; Lhin 1.22 E This case was run an Wednesday, December 21, 2005 at 6i.28:54 PIA Doe Point N 1 (1L7)117-)a 12/21/0l~ vMM 414J Aur70r4Yp~ LUoni Wbithu Buildup 2,885!I-O10 2J14$e.0103 7,.187e.OC

5. 125.,009 Photon FIuecfle Rate (flux)PJ~oton Emg Fluence Rate Photons/cmrnsIc MeVlem'l/see Exposure anid Dose Rates-,uposure, Rate Iin Ale Absorbed Dose Rate in Air K mR/hr rnmGy/hr mrad/hr 4.IO0e-013 3.579o-0I 5 3. 57ge-01 3 9.819e-012 8.572e*O014 8.572et.012 Nocr Do-so EqwiYalnt Rate a Parallel G~eometry a Oppoed o Rotatfocnal m~y/hr I 4. 195e-D1 5.3,414e-01 5 3.4 14e-015S 3,0Q80 0I5 I OB0841-0I3

&1 164e-014 a. 164&-01 4 7,217e-01M4 Shall~ow &ose Equivalent Rate 0 Parallel Geometr'y o opposed o Rotational a raotrcopic (I1CRP 51 -1987)Im$Vhr I 4.47-6 e- 1 5 4.265e.O015 4.265e-a 15 3,929e.015 1 ..74- 013 1 .023e-01 3 1.023ewO1 3 7.72 1o-01 4 fifectiiVI Dose Equivalonf Rate so Anteri or/Posterior Geormetry io Lateral o) Rotational (ICAP 51 .M7 rnSvihr 3.728*e 1 5 3.322e.0OI5 2.SO0e,015 2.972e.O15 2.S4'7e-01 5 8,947e.O1 4 7..954e-Ol 4 5,96MI~O4 7.110~e*014 0-04 14 Page 1 C'-214 -PlumBrookReactorFacility .Final Status Survey Plan I Revision 0 MicroShleld w5.04 (5.04.4X)62) Radiological Serviices, Inc..Page -I Dolt Nie -.P812214OIMISS Ru .ate 7Decembuer 21, 00Q5 Rwhrnlie; 6.30:33 PM Duration :-00:00:01 Fire Ref: _ _ _ _ _By: _ _ _ _ _Checked: _____Casm Title. Lino 1.2 F iD~script: fRevised IOde i -4 Unit Act w Sched 40 & 12 In SId Geometry: 10 -Cylinder SuTface -External Dose PoMt Source Dimenslons , I Height 762.0 cm Radius 3.81 cm 4 111 5.1i shiAld Name lCyl -,4~ e Shield I-Tansiliion Shield 3 Air Glop%V41l Vlaf Dose Poin~ts In 381 cr n 12 ft 6,Oin Shields Dimrensipn .t&2 3.81 cm' Cor.65 cm II 25 ft L15 in z 137.16 em 4 ft 6.0 in aI C1nsity 7.86 e 2,4 e 2.4 0.00122 7.86 Icret ron Concrrt 300cm Concret Air IQZ .05;m 1 w Source hiput Grouping Mthod :Actual Photon Energies Huie furiels km~auj=-Is LICi/rC'Nb.94 81087e,011 3.Q0372e-'000 4.50O0~009 1 .6650e-004 Buildup The materlal telerence Is CyL. Care lrrmteiratlon, Pwarneters; .1Y Direction (axtial)Circumforeritiall 20 20 No, Activity MIY haos/e 0.0174 0-0175 0.0196 eV7026 ,71 1 1 .074e.03 2.057e-03 6,044e-04 3..037%.&00 3..037e-'OD Mevg/gm 2/sec C01030e00 O.D30e400 3.91 7e-251 9.696c0] I 2.961e-10 Results Fliuance R-at+-M eV /C Ist/ -0.9 2.369e-37 4.581-e-S7 1 .609,o-37 2.494e-09 5. 580e-09 NO RVJIS&fu 0.000e4. o I .46e.252 I.870e*13!5,573c. 13 1. 279o..2. 426e.38 5.-941e-39 4,809a. 1 2 110Q5Oe11 Cl-215 Plum Brook Reactor Facility Final Status Survey Plan Revision 0-. F ea -2 DOS File .PB12214ONMS5 Rhn Date Decrber 23.j 2005 ru Time 630:S3.3 PM Dur-+ion : 00:00:01 W&Activity phat-iwsr,-Fluence Ralte UplcmI/"ee Nn Ptihiup Fluence Rate t=W*mfeee fth OYid'u my/h o Bul.deup 7,443e-13 ExploLue Rate Mr/Ahr with 1B)AIduo TQTAL$: 6.07-e+0&074e09 1531e-1 Cl-216 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShteld vS.04 (5.04-00362) 12/21/05 kig~roSM9Id v5.04 (S0.00O362) Radiological Services, Inc.Co"i~rorstoii of COIC"1eted exposure I tit to (lose FILE-. C'XMSMXATANP8122140.11VSS Case Title: Line IVS F 7This case was run on Wednesday, Di;~mbftr 21, 2005 at 6:30: 33 PMA DOme Point 9 1 (114.97,381,137.16) cm 2=0ft (St iMMod evvpr PnPCgjW 4.,779c.0i0 9.9$55eOO0 3.931 e-0 1 0 8.074e-009 Pkton Fl1~ Loone Ra, t Mm%Phtoton Energy fi uence Rate Photonsimln/sec MeV/cmr 2/sec Exposure aznd D~ose Rates, Exposu~re Rate in Air Absorbed Dose Rate in Air m mR/li;mGy'/hr 7.4-3i:013 6.497e-015 6.497c.013 1.531e-01 1 1 .337e01 3 1.337so01 1 Oeep DOSe Eq~vyulent Rate a ParalleI Geo-netry o Opposed o Rotat-onal O kItrap~ii (ICRP 51

• 1987)mSY/hr m 1 .556e*015 6.224eO 1 5 6,224e*015 5.504e*015 1 .556e.01 3 1 .Z,8Oe.Oi3 1 .28Oe-01 3 1.132e-013 Shai~ov Do~se, E'w iya-nt Rat*q Pa~rallel G~eanetry DaO Oppsd o Rotational a isotropic Effecti~a Dose Equivalerrit Rat o Aetevior/Posteriar Geo'moetry oD Posterior!Anterior u Laterof Ko Rotational iolur**rn'jv-/hr (ICRP 51 .1,087)rnS'v/hr R 8.081e.015 7.71 1e-0 1 7.71 le*O15 5.890e*015 6.736c.0 15 6.044,e.O15 4,595-Q 1 5 5.412e-01 5 4.1563$01 5 1 .664e-013 1.5MTe013 M5M4.13 1.2 le-013 1.3197evO13 1 .243e*01 3 9,435e-014

1.1 13eoO13

9,581i,014 Page I Cl-217 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 11aSh~if& VS-04,(544-M62) waipooickul Smrkes, Inc.Page D0e File PB1 22929 MS5 RL. 4$a~a Decemnbeir

29. 2005 Run T~mo; 3:42:46 PM DuatonQ:00a01 De-scripdiorn PA 1-I,29 8.208'OK.~e _____COASs TIU*; Una I.S92 a nedrit Model Cak- 1-129 Unit Att w Sdicd. 40 & 12 In SW~"Icryr-) -"yInder Siufaee Cuxtaina DoqSe Point Searcc Namneslo"S H~frt 7620Zn Rod 81#1 1 34.97 en 4 It .5.1 Ii Cyt Cort SeWI Ttontown Shw4ia 3 Att Gap waif wIo aft. Pbivt 38:1 cm ShIletd 3,81 cm, Cor Ca'3048 r Co'25 ft 1$7,16 cm 43 ft 6.0 in I DAtny4 I .86 C ZA e 2.4 0C O0 122 I SB teria xret ton wot Kr ei,.AOi-025 cm trnn source Input Cr.tapng Meth!od -Acttni Photon Cu"tgteS U$ bsaOR5 A 1. 011I 3:0372e*000 4 50Ot-0*09 BM&Wrn 1 .66S0e-W43 Oui~rI"p ThC mIrmial referhence Is : Cyvt. Core Y Litrecion Ilezrm~in Parvastats Y Uirmolon(Pimmil)

Z C-1mumforential 20 LEnm NtOY 0.029S 0.029S 0.0336 r "'396 6.061tV01 3.912i#.0 I 3;998#,O 27441s-86 7.026e84:3 9 6 3 C A 2-764e-46 ROSVIti 3.t97c,34 6 .W&-34 3 492* 34 3 s50k-34 2IO08118t6 1 25%e-48 3.660e*36 6.77~6c,3~6 2.484#-36 1_613e.36 CJ-218 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pae .2 DOS File ,N I12929,MS Run Da;t iecernkbr 291, .O0 Run 1yme, 3:42:46 PM Durtion, iO-00 i TOaerg 2 A23UVJI rOTAI-5 2 359*iW FlusL Rate m4ICrnMMI No Buildup 2. 764e46 f harc723Ra 1,723e.33 MOPS 1,2k48 loby Baed WIE 3euik J3 2 453e.36 Cl-219 Plum Brook Reactor Facility -.Final Status Survey Plan Revision 0 MicreShleld v,S04 (S.04-00362) Rola~'cuIServikei, Ine-Coiwenjon td tAkv~ated exposurt in air to doew riLL musswumT\Fi25mm ss CMi 1)t1: Lim LI 6 This cms was nm an Thunvaj. Dw~Mber 25. 200at1 342:46 PM bastorIS1 )L7~L171)~f ReUU=%O SMEMedovr nergij 1=Photon Ruence Rate (flux)Photon Energy K~umne Rate Exposure and Dose Rates!Expo$ure Rote in Air Abswbed Dose Rate in Air Deep Dose Eqiira-lert Rate o Pita'il Geometry o OpOe o Rotabtiml1 O lSotrOP*C Phutons/cml/sec MeVem/ra9 m.R/hr mGy~hr mrod/hr (ICRP 51 -1987)M&,01V 1 .256CO04 I .097#051)I .091q04W 7-904;05 I 715S8trO051 6$ 80051 5.36%tV03 1.7Th,3c033 1 -A53"-36 1.26ge*037

1.2 69Q'035

1 .453e.037 7 ,286e.038.6215e-038 5,772g-038 I5hallow Dose Equivalent Rate o Parallel Geometry o Oppfte d o Rotatiounal o Is~otropic ENfeivtie Dosie Equivalent Rat#o Anterior/Postef ior Geometry v Past~tfoAnterioar O Rotational O k5QUAReot (ICRP 51 -1987)msv/hft (ICRP 51 19B7)mSbhr IV 59050 L09.M061 1-e090.5 8000* O$I 9.1$2.051 5,53?2051 3,056.051&197$e,05 ,4;018t 51 I 583. 037 1 089e.037 1.08ge-037 1-C038 3.3674.038 1.81 74.038 3.345.038 2,772e-038 Papo 1 Cl-220 Plum BrookReactor Facility .Final Status Survey Plan Revision 0 MICIV5110dl V5,04 (5.44-036.2) Radklologca 5srvim~. Inc.Pft. V -DOS File : MPNO1dB SS ft ate : Jhanuary &. ?00 Run Time-. 8:24:59 AM'D1uration

0D0.00G1 File W .. -__ _ _ _Dothe! ____--boscril Cues 1110A e: Uric LUI ptlen: Revised Model Ca~cq Uri126 Unit Act w Schad 40 & 1.2 in Shid GWm~etay:

2In lCylloadr Suuiace -Exlernal Do*# Polint;I it T I L 12 H~eight As 1 1J4,97 tnm 4ft 5 3 in co1, Core S*~eld I ArGap WallI Clad wuce Dimensioslo 762.0 cm 3.81 cmn Dose Pabfts 381 cmi 12 ff 6.0 in Shildsf?4=110 M&+/-3581~ Pr'Conci 65 cm, Ira 2,5 hit z 4 rt 60 m ~I Dew~ily Y 26 e 24 0 001 22 Fin are~~Concrmt, ,Source Input Grouping Mothad -. Standard Iai~icas NOimnuro 01 Gotps ; 25 Lew*T Efiy Cuwtff: 0.015 Photom ( &MS :Eteluded 1il ~3-372Ze#000 4.5000c, 0o curies 0.2087,e-I 91 1,.6650e 004 Vie. rmaeitlu reference Is -CyI. lCore YChmrehe Isal 20.20 phogtniLw 2.35le-01 3,26ft-235.Results 6,458a, 35.1.132e*236 2.237e-36 C1-221 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page .2 DWO Fril e POO10408, MS6 Run Date: January A. 2006 Run lime. 8:24:59 AMt DuraWtion -0GX;W1 Q.03 0.04 0.06.0108 1.51 7& 62 2.91 lo.01 1 395e1+0 Eluknoff Rate s.y 1,5844182 1.427e 46 1 .747e 25 1,309% 19 5,402-34 2.544e-l3 4 ,092o-24 5A698e-18 1 .57Oe04 6.310*49 3.470e2 8 2.072o,22 S-34e-36 1 08 1e-37 8.127e227 (.478o.2 1 roTAIS: 2.825et-0 1.3.9e 1)S-989e18 2V072#*22 9.478e 21 Cl-222 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 micro5sI4IE d5.04 (S&.O4-00am2 MU104m Mlcro~fteld Y5..04 (5.04.00362) R .Rwoloical Survikts. Ime, Conversion of c~alculatedt exposure fIn air to dIose PtLE, C:-UASSNIDATANWO0104O048A5 Case~ Thtle; Lrin 11 tI This caso was run on Weduiesday, January 4t 2006 at 8:24:199 AM Dose Point 9 I cmI3.9 h37~ n~ut Stymmed ~ey AerE PNttc4 Flowne Rate (16lu)PINOW Enerly Fluent* Ratr V0! h ,Ph crr'ie WOW~u ftomp~J Wilhi 1434-0e18 7,486O1 7 L1309,019 5.989le-018 tno"Orlo send Dose EwO*$w?# kofe In Aar AbW, tMO 0OW Ratp in A'. J, r MW/u mTGyiIv 2,012,022 I'Sw-24 140%O~0?2 9.47&E-02i 9.274,023 8 274e-021 NA"- Dose Equiivatrnt Rati-o P A roli CA, ~e'm.nw1ry ()Opow O ollo., C O, p i PCKP.!Sl 19V)msitthf 3.342 1 ~685s.02-4 1 .608aO24 1,6? 6* 024 I .4 4 7e.022 7.4908e-023 7 .438E-023 Shmdjoe# 0ioi!o EquivaleM~ Rate a Paimtleol Gaomelly O, Opfow .O Rotatlonali

• Isotropic{rCKn. Si 1m~)m~wthe-1.1 34&-024 2 .304.024 2.304e-024 1,~434e-0,22 1 .054eQ22 1 .054cD22 7 735e-023 Effediv Dose Equivalent Rate o Arit-mofIPos~~terior Geaomety o Nstiriorj/Amtermor o Lantefol O kotaffc~al O som mSv/hr 2 655e 024 2 W2.?e024 1-249*024 1 .266e024 I, 396. 024 i 215e.022 9.27i e-0Z-3 5.7 l4W.23 7,897e.023

6. 387e-02~3 PAp I Cl-223 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlerShbeld w6404 46,04.0362)

Page -I 00X)Fki ; PI3I22931AMS RL atti; DawnibeT29, 2006 Runi Tim n., 3S65:03 PIA Durafln~, 0O0O0;01 Fi~t Ref; __ _ _ _ _D~ate: ____ICase Tide. Linme I52I Dc~scription o: Ae~rtd Itiodel C-alt. Zr.05 U4 It At! ~w Sdhed 40 & 2.2 In~ $hi~d aeoearnar: I0 -Cylindes Surface Extorna1 Dose Point w I i A: ii I I .i Z 117 A .I i i 4 41'i! I , , Height it I 134,97 cm 4 ft 5~.1 in*cyl Ue'e 9,4444 1.Wafl Clad mmorw Dim¶en~sions 762.0 can.3,5I cfn acst Points I 12 116,0 in 3.81 cm.' Oof'Ac.65 on Ito 25 ft 1.5 in z 137,1G e-m 4 ft ~6.0 in I P.WfAi&it 1.8 7.86& 2.4 t 2.4 0.00122 7.86 era ret an CwmKret,$04~8 VI" ' ce.D25 cm. iron 5I ource I!pul Grouping Wlethod : Actusil Fhoton Energies hwiw-t1, Igc~8 20197. 011 3.fl372q#+000 4.500OL-009 Nru Ow/Ce.1,66.5I0 004 The mtkeril r"oomwio his CoI. CO Jmtegrtht1 Parameter's Covcurnforonfiui. 200 0- 7242 1 2+0 0.7567 1.681e,000 4.965CI11 7.926t*I 1.Resutus E .222u0 I AItOc 9,!S46t 14.1.17#13 2.350e--12 3-S04e 12 TnlTALS; 3,0070400 3.-053.4e09 2A?4 1$5.4 e 12 Cl-224 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 IdeiffbSield w5.04 (6.04-0O362) mig'oShleld V5.O4 (5O044K136Z) RadialoglemI Sotvices. Inc.Conners of ciklzditod Ospasure In air to 0 FILE; C.\fA55IVATA\PU13ZZ291.I41S5 Case TRW.: Lhim 1.821 Uhfs Casew. Wu~ run on ThwVUY. 0P9COMbe 29, 21M. at 3;55;03 PM Dow O P Ir~ U 1 C34.7,381,37.16) cm 12/2R/O wit, PMarita fiv#wce Rite Olux)Photoft Env, y Fkaenre Rate Exposuro aind Dose Ra~tes'Expoure Rate in Air Ab-,rW~ Doi Rte rin Aor MwniW cmi6tse 1-733oe,010 iI07#-M L ggO0 Q3~O mRlhr i111y/hr mrard/hr 2.472u.Oi I3 2.158e*015 2.lSeO013 5.854* 012 5.1 3I ez.14 5.1 1I e-012 ShaIow I~ime Eclurualent Rate o Ppral4IIo G&Yeornfry 0 014)D15fd a Roatiotkahh t IstrAroplec m-Svihr 0iCAP51 19 87)m~vihr 2.529a 0 I 2 057-9-015 2.573e -015 1-946e 015 4 872c.014 4 872a.014 4 3O6e-14 6 W-o9-c014 6 J095e-014 4 609t 014 Ef etidvo Diose Eq~uivalent Ratit I, .1n!#irw/Pcteficw Geometry O Putf~!Atfo 0 )o? R*~1M3w 0 strp m. Sv/hr 2.24 7e 01 5 2.001v0.015 1.790e~OI L.5331,015

5. 321e.014 4. 73 9t014 3. 5639*014 4.239&.014

~.301c;014 P 1 Cl-225 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield Y5.0A (5.04-00362) Radiological Smiices, Inc..Pag$ : 1 DOA File ! PI122932.MSS Ri tte; iDewmber br29, 05 Run Time: 3:57;38 PM Duration : 00:00:01 file Re_.___Date: Ch y:____Case Title: Line 1.82 J Iftwiptlow Rvised M*41 WC-i 5 Eu1 Wit Ad w SAW 40 & 12 in SW Geometry: 10 -Cylinder Surface -External Dose Point-I I -- --..HeighJt Radius# 1 134,97c 4 ft 5.1 Source Dimensions 7 62.0 cr 3,81 cmn Do-st Points*1 m 32M!r I in 12 ft &0 in Shields, 25 ft 1.5 in z 37.16 cm t f1t 13D Al*Sh~ield Name Wy, Co~ro Shiela 1 Transition Shield 3 Air W-p Wafl- Ci-3 3 51 vr~ Concrcto 1.8.65 cm tron 7.8E Concrete 2,4 AAcm Concrete 2.4 Air 0 .0 Cd2.025 cm ~r-rn 7.8E6 1. 565O source Input Ctrouping Method Standard Iit~ces Numnkf~ of Groups : 26 Laiwetr Eergy Cutllf : 0.0115 Photons .9 0.015 : EK-cuded Library : Grove ibecciverels uCil/rnil O11 3,0372e-O00 Ak50ooov0c Eu-155 8.20874o-K Buildup The maierial reference Is: Cyl. Core Integiation Parameters Y 0Irtlion (axiON)Circumterentiat 20 20 03 9.6670-03 1,.722eS84 Roul~t 5-.672e-367 Firoosure Rate I .UL*5.820e.38 Cl-226 Plum Brook Reactor Facility -Final Status Survey Plan Revision 0 2 Pago ; 2 DOS Fike

• P8122932.MS5 Fun DNtO: Cetnmber :29 2CO5 Run Time: 3:57:38 PM Nr-tio:t *0,04 0.05 0.08 0.10 (.1 photbnws/ee

5. 505e,0 1 1.791e.-l 3.93geO02 9,431s-01 6.279e-01 kleWf'm2J5pa 5.I77a-45 7.354e-32 2.364w-26 4.854e 2O 7.7539.18 Mde~crnlsec:

With Auddipk a8869e 34 7.44Se-31.5 538,e25 4.O50e2 18-.5926e-16 Fx=n %ufl kwrim mRLhr No gJtiajdi 2,290947 1.9sge, 34 4.696e-29 1.401 eC2Z 1.186e 20 r, xe>on % re. P m LM fn-RJhr wpfth Bu~iiduo-3,922e36 1.983e-33 1. 1 ;!-27 6,49e2 1l 9.066e-19 TOTALS 2, 3501+60 7,841 c18 5 966C 16 1.200e-20 9, 13ce-19 C/-227 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 fikrShich! 05,04 ($.04-003362) 12/291 MicroShicld v6..4 CS.04-0016-2) Radkioogical Services, Inc.Comwersion of calculatud exposure in air to dosc nlLE+/- C:\M.SS\%DATAkPl3122932MfSS Case Title; Lint 1,82 J This case was run on Thursday, December' 2S, 2005 at 3:67:38 PM Dose Point St I -(134..97,381,137i16) cm, eg-Ilbj argn1MMFrl rypr nW-P'toton En.etgy F~iuence Rate Wu+hnti+5.976e-O015 5-966e-016 Photons/crW./sec MeV/cmY/Sec 7.863e-01 7 7-.B4 le-01 B Exposure and Dose Rates-Epour* Rate In Air Absorbed Dose Rate in Air N vnR/hzr mGy/hr inrad/hr 1 .2Q0c-020 1-.048&e022 1-04ge-020

9. 1,30e-019 7.970e.021 7-970ewO1 9 DZeep Dose Equivaitnt Pate a Parallel G~eometry O 1"o pprd o Rotational SbhlIicw Dow' EquivtIonlv R~htu n iPayai.el Geometry o Anterior/Posterior eornetr~a Posterior/-Arneriar o Lateraf o Rotational ,a Isllafoplc~(ICRP 51 1987)rnSv/hr U (ICRP 51 1987)rnSv/hr (ICRP 51 1987)mSv/hr.a 1. $e4022 9.603e.023 9.600e*O:23 9.292e.023

1. 740e-022 ,1.350e*022 19.350C.022 9.827e*023 1.3-32e.Q20 7.305e.021 7.304e.02 1 7.069c.02 1 1.324e.020

1.0 27tc020

1 .027e-020 7.476-O,21 1.-14.5*'20 B.980e-02 1 5..S42*O021 7 .66%.O2 1510-fI2 I .506e.022 1, 1 80c.022 7 .285e-023 1 .008e*022~IZCQ Page Cl -228 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 hMicrolihield Y5.0-4 (5.04.00362) Radiological 5evivceiij Inc.Pag .1.DOS rile PF8121921.M9S Ru ate; December 19, 2005 Rufiiime: 2:43:03 PM Duration .00:00.01 Checked: _______Case Title.- Line lU A2 Ovscriptioo; Rovisci MeieI Cole. -Cc-60 Wfit Att w Scheol 40 &12 in Swk Geometry: 10 -Cylinder Surface -Extermall Dose Point ij I ~.gnrse Dimensinsii 21Height 762.0 cm!iRadius 5.08 cm* 1 136-24c-r 4 ft 5.5i.cyl; Care Shield I Shield ~3 Air Gap WaVll Gi~d Dose Points 381 err n 12 ft E.0 -n Shields 5.089 cm, Zow.C-n I 25 ft 2.4 in 213.36 cm 7 ft ta 0in 1 Density:e 1.8 7.86 tc 2.4:e 2.4 0.00122 7.86 Kc'e1 Ibria N 38,48 cmn Conc el Aik.025 c-n lro, -Source Input Grou.ping INhod ; Actual Pboton Ehergies Nucl, JEmi k2=2=rel UOicm'C*OW 1 .0945ev-010 4,049to+000 4,50D0o*009 1I 6650e*004 Buildup The material revrenoce is.: Cyl. Core Integration Parameters Circumferetial 20 20 L=P Arii 1.1 660-10 2.020e-09 .2.084e- 13 3.6We- 12;1.436e.10 3.513e-09 4,226fe- 13 .501 016938 1-1732 1 .3325 7, ALS: 6-E0$e-04, 4.050e+00 4.050e4-00 3.602e 10 5.533o-09 6&310 13 9.705e 12 Cl-229 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 kroShield wS.04 (5.04.0062) iMicroShield v.04 (5.0445O12 Radilologkal Servile, ine.Conversion of calcWI;ad

xposure in air to dasw fMLE

C:\h¶SSXDATA\PB12192iMSS Cave ?ltRe+/- Line 1.3 A2 This case was run on Monday, Decenmbr 19, 2005 at 2:4E3.O PfM tose PFalt a 1 (1&c4m31,2fl4$)

cm BP., i Cfql,,mrPH nvU r anrIip 'I Wdhout 01/02/C Photon Fluevco ftt Ol ax)Pitoton Enewy Flbence Rate Exposure and Dose Rates ExpsXure Rate In Air Abwrbed Dow Rat, in Air U Photons/cwrr?/sec M6VfcMrntc 2.822e-020 3602e-01 0 4.35se-009 5.533e*009 mFR/hr mny/hr mfrad/hr 6.31OE-013

5. 5O910e0 5 5.5Oge-01 3 9.7-OSeO 12 8.472e-014

] 72ea Nop Dose Ecqvivacnt FRatc.a Parallel Gewetry Q stil(U o RRotati-onal Shaltow Dose Equivalent Rate a Parahlei GiemEtrr[i Opposed o Rotational d Isulzf>.ic Ef etive Dose Equivalent Rate uOrttelow/Posterior Geomtfy o Posierior/Anttorior ci Lateral o Rotational Q 150cIroPIC (ICRP 51 1987)mSgv/hr (ICRP 51 1987)mry/hr I (ICRP 51 1987)mSv/hr E a 6-252e-01 5 5.*Oe o15 5. 388e-D1 5 4.814e-D S 5654e.0 15 6.409e0 15 6,409e*01 5 5.09ge 015 6.631 e- 15 5.18e.015 4.130e.8015 4.67 3e.015 4.138-O 15 9..61eO014 8,.28-9e014 B 285e-014 1.024e.013 9.853e 014 9.858e*014 7.841ee014 8.66le-014 7.979o-014 6.348e-014

7. 185e-01 4 6,360e-014 Page Cl-230 I Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 hlicroSheied w5.04 (5.04.00362)

Radiblogical Saivices, Inc.Page :1I IDOR File P8122141.MS5 Rk nde m rrUT21 2005 RuMmre'6'.3811 PM Duration : 0O-00:01 File Rut:______ BY, CQhukeJd;______ Case Title: Line 1.83 B Descrlption,i RevisedI Model Cak.- Cs4317 Unit Att w Sched 40 & i.2 In S~htd Geornetry: 10 -Cythiider Suiface -External Dose Point 1" -;-1--11-----17 -XFwourre if flhpridnt~n IFadius* 1 1.36.24 cm 4 ft 5.6 in 762.0 cm 5.018 cm 301 cmn 12 ft Uin Shisls.5.0B cm' Cowc.6S cm Iroi 25 ft 2.0 in z 211~0 cm 7 R 0.0 n a nD114N e TM6.3 2.4 e 2-4 QQ1 22 7.06 a'Cyt C0,1 Shield 1 Shield 3 Air Gap Wall Clad I Concrel: 30.48 cm Concret Air..025 cm [MAn'et If Ba 137m Cs 137 Sourcec Input iraroauping Method : Actual Photon Energies 1.0354e*010 3.8309e+000 4.2570e-CM L0945et*0I0 4i04~96o+O00, 4.500C0e-CO19 1.57$1-0 L 6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial)Circumfoeq tiat 20 20 0.0318 0.0322 0 0364 316 7.93 1e-02 1 .463cFOI 5. 325e.02 3.447e+00 Na Buildupn 1 .539e-86 JWU48~66 2,.737e 1 2 Rumili~.15e.-35 7.506e-35 4383c 35 1-.163e-10 3.01.5e*9 1 1 .239oB88 i6.1 24e,69 1.3CXe- 15 3.261 e73 6.041le-37 2.255e. 13 Cl-231 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Page :2 DO$ File : PS12214 1,KM -Run Date: DLcemimber 21, 2005 Run Timn': 6:311IJ PM DurAtion: 00:00601 Ea=mg Activity Ogupal Fiuence Rate Re Meilrn*ftd INoQ uildug Flojencp Ra deVrAlsr'se Wfth Qu*idgg Exposu Rate.MR/hi'Awshviry Ruin W~h toldi TOTALS: 3.726e+00 2. 737-12 1.163e 10 5.,306e-1 5 2-255e-13 Cl-232 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MkloSmeh W..04 (504-00362) M~icro~fhiald Y5.04 (5.04'00362) RadiaohglcaI ServIces, Inc.Conversioni of caiclated vxpasurv In air to dose FILE: C:tNIVSSNOAAMPE12214LIVSS Cm~ Title: Lloo 1.83 B This case was run ani Wednesday, Decem~ber 21,2005 al 6:38:fl PMA Dne Point 4 I -(ISC.2 4i,38 213.36) ~t D1I02fO6 Photon Ewfgy Fkaence Rate.Eposure and Dose R-atm Excposure Rate in Air Absorbed Dose Rate in Air a~ Ini~Photonskm/crser Meftm/wn/e mR/hr Imcaythr mrad/ hr wiffintl WOW Wkih Ruijilu~4.137e-012 1.758e.OIO 2,737t~.02 1 163B.010 5.306e.015 -9.63e0-O 7£.632e*015 2.255e-013 1 .969e.015 1 .969LE.013 ,Deep Dose Equivi',ent Rate o2 Parallel Gem-retry 0* 0Copous4 o Rotational n $1,d i ICRP 51 1987)mSv/hr SAS4a4-03 7 42.9l1e-037 4-391ceO]7 3.883e-01 7 23 1 01 5 1.9.66e-015 1,.866e-015 1L651X~ 015 Shallow Cose Equivalent Rate a Parmlel8 Gabsir a Opposed o Rotational Q ISOf0op4c (ICRP 5 1 1Q87)mSv/hr Ff 5-829e-O-17 5,5.36e-01 7 5.536e-01 7 4. 15 le-01 7 2.477e-G1r 2.353,e-015, 2-353c! ais 1.764~e-015 o Anten~or/Posterior Gecvmatry a Post-vior/Anterior o Litora!I o Rotationat o Isotropic (1CRP 51 1S87,\mSv/hr U 4.949e-0i 4.8c01 7 3.1746-017 3M2Se.O 1 7 3.256e-017 2-06 1,,Ol5 LBI819e*01 5 1-349e,015 1-626e-015 1-$t015 Page 1 Cl-233 Plum BrookRea'ctorFacility Final Status Survey Plan Revision 0 MicroShield Y5.04 (5L04400362) Radi~ological Servrices. Inc.Page :1I DOIS File P8122142.MS5 Ru te; Vcougw 1 2005 Rwpt~rme: 6:3,!.33 PIM Duration : 00:00:01 File Ref: By: Checked: Ca". Title: Line; US8 C Description Rievised Modell Cale.- Eu-152 Ulnit Act w Sched 40 & 12 in Sh~d Gconitry; 20 -Cylinder Surface External Chose Point Hai&b Radius 1 136.24 cm 4;ft 5.6 in Shield fbm Shield 23 Air Oi~p Wall Clad Source Input Grouoping Method Standard lindlkes Numbm of Groups -25 Lower Eanetgy CutlolU t 0.015 Photons t 0.015 .Excluded Library : Grave 1,0945tV].0 4,0496v+000 4,5000e.O00 wrce Dimensions 7652.0 cm 5.08 cm Dose Points ,81 cTr)shieldi 5.013cm' Conc.6 5L cm ITQ 25 it 2.0 in z 213.36 cm 7 ft 0.0 in al DansitVr Fe 1-8 7 863 e 2.4 e 2.4 0.O0122 786 Le fret1 Concret WQ8 an Cowet*Q~~rnAiro EU-152 Ia 1 .6650e-C'34 Buildup The material teletence lis : CyL Core Integration Paramieters Y Direct~on (axial)Circumferential 20 20 Meu~y 14 Ar-tivit 2.396ei-00 9.024e-54 Results 2.61se-3.3 F3nnrrp 5E 1.1 513e35 CJ-234 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NE : DOS File', PB122142.MS5 rfun Date December 21, 2005 RPn Time: 6:39:33 PMt Duration 00:00:01 Fneg Attivity Mov .ohoton=/sec 0.05 5.991e-01 0.1 1.161e+00 0.3 1.095e+00 0.4 2-SW4Se-01 0.5 2,28402 0.6 ll717e-01 0.8 7.21e-Di 1.0 1,7339e00 1.5 Q -4e-01 MPugen 1 atec No Builduto 2.00e-37 1.651e,2 3.175e-17 3.l52etlS 6.228 .15 2.722e-15 7.1 04a 14 1.9679 12 1 909VI 1I 1.091e-13 EFXuenc# RRat Flulene Rate I&W-Efa.rsee Wath Bwlldun.2140e33 1 .872e-lB 6.224e I5 4,414e- 3 5.88te-13 I3X e-13 6.157e.I 1 4.2l3o 14 1 341 e-09 Eogmstre Rate 5.3Z9e 40 2,525e-23*S.604e-20 5,900e I8 1213e-17 5.342e1 a 1.387o.16.3.742e-I 3.519e 14 llemie-13 ,mF~hr W~th RlJ;ritin 5.702e-SN 2.8655.21 1.09e 17 8.$72,. 16 I .146o-15 3.572e- 16 6.907-c15 1.171e-13 7.766*-13 2,25G6e12.TOTALS: 9.a37e+00 1i.30&- 10 1828P'9 2 .227a 13 3.159e-12 C1-235 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Micro~lidield w5.04 (5,04-00362) 11MiCF9hieid. Y5.04 (5,,04-00362) Radlologic-al Seivlces, Inc.ConvesmW of cakulated exposure In air lo dose FILE: CA\dS5\OATA\PB12214Z.MAS5 Cst@ Titl: Llitko IRS C This case was run on Wednesday. December 21, 2005 at 6:39-33 PM QMse Point1 #1I (136.24t381,2lS.3$) t 01/02/06 Egcit~ Ca iMrnd nvir nCj&%ffi~thi+ d&J I A- U 801 gA46er-011 1 .40Ie-009 1 303e-0 10 1 .828e.009 PdtKton Fluenmo Ra~te (luxc)Photon Ener~y Fltuence Rate Photonsh/m 2 sez MdV/CM1/we Exposure and Dose Rates;Fxapoure Rate in Air Absorbed Dose Rate in Air rvnR/hr mGY/bhr rnrad/hr 2-2274.01 3 1.944e.01 5 1.944e0.0I 3 3.1"6e0l2 2.758e.014 2.7?58e*Q12 Na Dose Equivalenk Rate a Parad;ef Geomretry o Ophposed o Rotabonat a kclIropie S:ihafl Dose Equivalen' Rat~e o Parallel Geornelry o RotationalI u I 1solopie (ICRP 51 .1987)mSv/hr N 2,205e.0]15 1-914-e-'1 5 1.934elQ15 I .7149.015 3,134*0 14 2. 707e-0 14 2,707~O 14 2.421e.014 (ICRP 51 .1987)mSv/hr U 2-~3170Q]2,259s.0 15 2-2S9e-015 ]Z~OSe.0] 5.3,326iP.014 3.29e*0 14 3.20ge*O 14 2.557e.Q014 Effective Dose Equivalent Rate o Ar te~nor iposterior CGeomTetr~r a Pp-4.rior/Anteriar o Lateral a~ Rotatlonal o ISOtODpC (;CRP 51 1987)mSv/hr.-9~86e.015 11 833eO1 S 1-478e-01.5 1-659e-03 5 1,.47-5e.D15 2.820&"014 2,60,3r~014 2.08le-014 2.,47o.014 7.081e.014 .Pare 1 Cl-236 Plum Brook Reactor Facility Final Status Survey Plan .Revision 0 MicroShde~ld v5.04 (5.04-00362) Radiological sewlce5. Inc..Page :1I D0W File. ; P'8122i43, MS$RL. kge:December 21, 2O05.R~u;me: 6:40:51 PMA Duration O: 00~:O1 File R :_ _ _.Dote: By: Checkec: Case Title: Line 1.83 D, De'scripffon; Reisehd M1odel Cakc. Eu-254 Wksil Act w Sched '40 & 12 in SWil Geometry; 10 -Cylinder Surface -External Dose Point 59ar-ce D~mewimin Heigh~t 762,0 cm Radius 5.08 cm Dose poinbs-4 1 136,24 cm 381 cm 4 ft5.6:in 12ftt6.0 in Shields Cyl Core 5.08 cm' Concre Shield 1 .65 cm I ron Trans~itioni Concre Shield 3 30.48 cm C~rae Air (Op Air Wah Clad .025 cm Iran 25 ft 2.0 in z 213.36 cm 7 It0.0in:e 18 7.A6:e 24 a 224 0,00122 7.86 I Source~ Input Grouping Method :. Slandard Indices, Numnber ofGroups :25 Lower Energy Cutoff: 0.03 Photons c 0.015 :Excluded Library :Groie Eu-.1541 1.0945e,010 4.0496e+000 4.50OO-00Q9 WCM, 1.6655ODO Buildup The material referance Is : Cyl. Core Interation Parameters Y Direction (axial) 20 Circumlerential 20 Fneo i Activill iph,2$2ns /se2 83 $24a0,Q1 MAY/cM21sec. 3.104e-54 Re; ults 9.006e-34 1.373e 56 Eh RuRtittn.3.983e* 36 Cl-237 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Pagh ;2 DOS File; P8122143,MS5 Rutl- Date! December 21, 2=!Run Tjim.; 6;4051 PM Dur-tlon : 00:00:01 0.05 0.1 0.2 0.4 0.6 0.6 0.s8 I.o 1.5 TOTALS;ACtivity Dhotoni tsee 2.093D1 1,639e+O0 2. 76e-01 8.768e-&3 3,266C-Q1 1.579et*O 1,246e00 1 .SB08s00 7.718e+00 Fluenve Rate No Buildugt 2,349t.2O.2.994. 17 7,071e*16 1.045e-15 1,3 5 13 4.30geA12 1.372e 11 1.8.36e-1o 2,.O18e 1 Flusnce Rate Nith Rilrlixp 7T479c;34 2.665e 18 5.672e 15 6,676e-14 6.985e 14 C..731e 12.1.349e*10:3,029 1 0 2.255e*09 2.70 S09 Esure Rote mRhr 14.92c;40 3.5949 23 5..1070,20 1.e378.18 2,05le-18 Z. *16 8.196e-15 2.5130 14 3.I2e-13 3.427e-13 Expqsure Rate With BQjduo 1,992c,36 4.077e-21 1,001047 1.301e 16 1.37le.16 1 314ei 14 2.565e-13 5.W4ew13 i794e 12 4-623e12 Cl-238 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 11troShleld vS..B (5.04-00362 Micro'Shield vS.04 4I.O4-0O2192) Commirsion of calculated ~sxours [R air 10 dOSg FILE: CA.VASS\DATA\P83122143JASS This case was run on Wednesday, December 21.2005 at. 6:40:51 PMf Post P~iml I -(136.24,381,213-3) cm 01/02/I LAdh I .987eM09 2-.700e-009 Photon Flmnce Rate (1lux)Photon Energy.fluenre Rate Exposure and Dose Rates-Exposure Rate In Air Absorbed Dose Rate in Air U Phatons/cmk/sec M6V/crn*/se I A17e-01 2.018e-010 ,n~R/ht mGylhr mrad/h r 3.4274-013 2.,99le-01 3 4.623e-Ol12 -4.036e-O14 4-0L36e-012 Deep Dose Equv~iyint Rate co Par'allel Gieometry o Rotational

~hh~Iovi Dose Equva lent Rate o Parallel Geometry io Rotational C ifmfropc 101-ruvjo~Mt o A.-tterior/Posterior Geornstry r0 Poteriar/Anlerior ci Lo tral-o Rotational fICFP 51

• 1987)mSvfhr U (ICRP 51 1987)mSvfhr (JCRP 51,* 1987)rriSvfhr U 3-38%-015 2. 950e-015S 2. 644e-01!5 3..589e-01 S 3.47 le-Ol 5 3,47le-015S

2. 785e-DI S 3-054C 01- -5 2,831e-01 5 2. 283e-01 S 2.555-e 01l5 2. 2779-015~tZ800i.014 3..971e-014 3 971e-014 3.55r6e-14 S.855e-014 4.69D'et01 4M-e.0e14 3..750e-O 11 4. 324c-014 3a814e-014 3..O63e.0 14 3-441cAJ14 3-O8e.014 PagE Cl-239 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShleld V5.04 (5.04400362)

Radiological Services, Inc.Page ; 1 D0o Filie P812144. MSS Rt ate: January 2) 2006 Run tIme: 8:09:557 AM Duratiev : 0O:D001 FrIe Ref: Date: By: Checaed: .Case Title: Line LM E

Description:

Revised Model CaIc Ag 148m Unit Act w SIvcd 40 & 12 In Shld Geometryr 10 -Cylinder urfawe EdernalDose Ptint_x Hclght Radius t 1 136.24 c 4 ft 5.6 Shiled tosme cysi Core Shield I Transiti on Shield 3 Air Gop Wall Clad Source Dimermsionm 7 62.0 cm 5.08 cm Dose Points I m 381 cm in 12 ft 6.0 in Shields 5.09 cm~r l.65cmn Ire 25 ft 2.0 in.213436 cm 7 Ft 0G0 in wwaliw iB 1.8 7.86 e 2,4 e 2.4.0O122!7.86 ret II Corret 30.48 cmn Corciet Air.025 cm Iran 5wrcc Input Grouping Method: Standard indices Number of Groups : 25 Lowe Energy tutoff -0.015 Photons < Dd)15 : Excluded Library : Growe a berguefu m e 010 4, 415+wo 4.50Q-N;AE ide8 1.si A8- 108m 1 .V945t.'mO 1.650t-010 Buildup The material reference Is : Cyl Core Integration Parameters Y Direction lOxiol)Cicumrerentia! 20'20 Ar.ivi5v 2.6560+0 3. 946em-2 ee NaP F~q~~jd 194Ge-21 Rowits MdeV/C"mOY ae1e 4.9WO 4 Exfft-.tuyk RsMt mR/fhr pln 1LI3h7e-1 .367e-292 F~xro~amire -Patr 7Rthr With Rijilfiim 1.715e-35 Cl-240 Plum Brook Reactor Faciiity Final Status Survey Plan Revision 0 Pa,- .2 DOS File : P12-2144.MSS Rvn Date; JilUhary 2, 2QD6 fRtn Time: 8:09:57 AM Duritiov : 00:00:01 A' tivity hky : 0210W 0,3 0.08 0.4 0.8 TOTALS: S. 599*,07 2,870e-DI 3.f6e4E00 39661,+00 3.65e*00 ,I 391 84O1 3.040e-107

1. D29e.23 8.90e- 14 1.51 4. 12 1.OOOe-1l I.-1'el1 Fltuence Rate Metfoe/Serc

%i1tb QUWLAD:3,543e4f}

6. 3 3e-22 8w.411e-]2 7.543e I 1 3.i,;0e-1O 3.9me6 10 mN t ftihirf 3.013e-109 1 2¶,M.26 1.736e-16.2,95e6015 1.W2e-14 2.21 5e -14 Fxnitzr* gPai'g mht With RusitdtIr 3.5,12e.42 1.009e*24 I,639o.14 1.472-e13 5.953e.13 7,589eo13 Cl -241 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Milem$hkie Y5.04 (5,04.00362)

Mficrofhiold v5.04 (5.04-0062) FrAdloiogical Servim., Inc.Conversion of z.allulated cxposurc in air to dose r1LE: C:\MSS\DATAXP6122144.MS5 Case Title.: Line 1.S3 E This case. was ran on~ Monday, Jarnuary,2, 2006 at 8:00:57 AM Dese Poin~t w 1 -(136.24,8 13 4 fl6) cm ftsUJ~rs (Sunmmd cv.er energiej)Phioton Fluemte Rate OIuxc)ftotion Fswfy Fhjentce Rate Pho~tons/crnzsec meVIC&Wse Without mih 1. 525e-O011 5.380e-010 1.160e (I 3.96ft-030 Exposure andi Dose Rates: Exposure Rate 1In Alf Ab~swbe'd Dose Rate in Air U mR/hr mGy/hr mrnd/hr 2.2158.014 1 .934e-0 16 1.9u4o,014 7.589e-013 6.62sel 01 5 6,625e-01 3 088P DQse. Equigarent Rate a PararIet Geoametry o Oppose~d o Rot~ational S~-altw Docse Equivalent Rate a Parallel G&,cmetry a Oppos~ed o Rotational o kswo~rpq EfJectvye D~ose Eirvivalon't Rate a ArnteriorlPosterio.r Geamerffy a PosIerior/Antftri-w o Lateral a Rotalonal o Iscziropic (ICPP 51 1 287)m.~yhr ,22.16 I .8 4 e.O16 1 .846e.0 16 1 .6320i016 7.770e.015 6.3 18e-015 6.318e.015

5. 585e*015S mSvihr 2I4169.016 6?3-All 2-.303e.016 1-746ft .016 8.289e-O015 7.897s-01 5 7.897e.O1S 5.975e.O015

.m$,Y/hr 2.D12v-016 1.796e-01.6 1 -3540fll 6 1. 607e-01 6 6.900~Q15 6.150o-015 4Z25e-015 SSO50Ce*015 4 7l34e-015 Page 1 Cl-242 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 hMkro$-hleld w5,.04 (5.,04-tN3362), Zealzla Seivices, Inc.Page r I DOS File P.1 2214S.MSS I Fn r Ti me: 6:4.3:57 P M Duration Q0:foos;Q1 File Ref:e Crate., By: Checked: Case Title:- Line 1.,3 F Descriptlotnr ReIl~eO hNTodel Cale- Nb-94 Urth Act w Sehed 40 & 1.2 In ShId Geonetry: 10 -Cylinder Surfac~e -External Dose Polot*1(V TI 5ar Ractlus 4 ft 51 in Li yl Ccre5s z Trn-i~Shield 3 30 Air Gap'Source Input GOtrpIng, WtIhod : Actual Pbfr~on ruE~ces Nb-94 1 .0945o.0 130 4 0496e+000 4 5OUO,0O9 762.0 cm 5.08 cm Joss Points 12it 0.0 in Shields ies~n Mapj 3S cm' Conce.65 cn Irtr Conc',48 cmr Concy* 25 ft 2,0 in 213~36 cmr 7 At q-Q inE:,e 1.8 7.86E;C 2.4:e 2.4 O0,0122 Pni.81 srl ret Air 257n, Irgri 1 -650v-004 OuiOdup The material referemee Is :Cyl. Core l ntegration Paramneters Y D~iroctilir (oxiol>Ci rcumteielitiai 20 20 Enewd Activity na 1h<AnV,"ir 0,0174 0.0175 0.0196 0.7026 711 1 .4342e-03 2.743e-03 8_058e-04 4.050o+00 4105064-00 0.Dowe+00 0.003e+O00 0.000e+O0 4 774a,12 i.8n5e1 1 Re sults Fluence Rate 2.142a 37 4,1~436-37 1.4.6e-37 1.841 e 10 5. 185e* 10 Q.0QOk+00 0.000ei+00 0,QC03e+00 9.207e-15 3.5.67e 1 4 1,156e:38 2,1949-38 5.374e.39 350C13 9.7-5;5e1 3 C1-243 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Paige... :2 K)( F le -P F1 22145.M$S FPun Date: December 21. 20O5 Min Time. 643:57 Pri Duratio: W:X.--01 Adiuiy 8. Mw04c+OO Fluence Raite No PC WU 2.373e- 1 1.ith eind 7.0-8e-10 PZpn,;Irp atep mRf hr Min RIMlfo. .4n.488e- 1 4 Mth pijilrbip. 1.331e 12 TOTALS: Cl-244 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 r14croS$eled vS.04 (5.04-00362) IficroShiold v5.04 (5.04410362) fladlological Sertimes. Inc, Conversion of culculatwd gxposurv lit air to dowo FILE: C:MSM\ATAXPBI22145SX3 Cozse TRWe Lin~e 1A3 F This case was nua on WedooesdayN December 21. 200S at 6:43.-S7 MtA Dose Mmin j I .(11343$ 1,213.a$) cm Resuglts r~ymmgd gler en2W,!W sa Without 01rgov6 P~,oton Fimice Rae t.ux Photon Enewgy flipnce Rate txposure and Dose Rates, cxposure Rate in Akf Absorbed Dose Rate in Air a Photon s/cm~/sec MqV/CM2/SeC mR/hr rnGy/hr mrad/h r 2.855e-O1 l 2.373e-01 1 4.488e.014 3.91se*016 3-918e 014 8&572e,010 7..026e-010 1.162e-014 1 162eO012 C.'ocp r),pp Cqpv wa~nt Pptp o Parallel G-ewnretry O Oppw$-W o Rotational u kl~u¶jpic~ Shaltrow Chse Eqjuivalent Rate a Miarllel G~eci'etry o Oppo~sed o Ratation~al a I wtropic (ICPP 51 1987)rnSv/hr 4.553e016 3.7-55-c036 3.755e-01 6 3321e,-01 6 1.351m 014 1,113e-014 1.1I 13e-01 4 9,8 4 0c-0 15 (ICRP 51 .1987)mSvt'hr 4.870e-01 6 4.,648e-l1 6 4.648e-01 6 3$. 53e4V16 1.445e 014 1 .379e. 14 1 .37ge4 14 1,053e 014 Iffective D~ose ETjiv3lent Rate a Anterior./Posterior Geameliy a Postaorr/Atntg-rior, o Lateral o Rota'lfunia a fSt'ompU2 mS5fhr a N 4.060e.0 16 3.646e.Q 6 2.7749.016 3.264eO016 2,815e-016 1 .205t.Q 14&212e-0 15 8.336e-015 Page I CJ-245 Plum Brook Reactor Facility Final Status Survey Plan -Revision 0 MicroShield Y5.04 (5.04-OD362) Radiol~ogical SerVices, Irtc.Page :1I DOS Fie P8122933.1MS R' 3ate! Jianuary 2, 2006 Rum Time, 8:03:0$ AM Duratign ; W0~0;O10 File Reft: Date: Checkehd;Case hite:. Une 2.83 G

Description:

Revised IodldI Cakc. 1-229 tnat Mrt w Sched 40 & 12 in ShIld G ,Qometry:20 Cylinder~urnlpe, Ett~rnaI Dosefruint Heioht Radiu~s x:W1 136,Z4 C 4 ft 5-6*Qwrw Dimansigns 762.0 cm 5.08 cm Dose points 381 cm 2 in 12ft 6.0 i Shklds 5.08 cm' Concrete£65 cm I rw.Conicute 30 48 cm Concrete ,Q5 rm, I ro 25 ft ZQ in z 13-36 Cm 7 ft 9 ,1in Lzerilitv 1.8 7.86 2,4 2.4 0.001 Z2 7,K I Cyl, Core Shield 1 Trarnsitian Shield 3 Air GaD WMIl 4~n squircir Input Grouping Method : Actual Photon Energies.1-129 1.0945&e.0!0 4.0496o+O0O 4,6" , 05 L m-0 Buildup The malerlal reference Is -.Cyl. Core Intelpation, Parameters Y Dire'ction (axial)Ci rcumnferenitial 20 20 0.0295 0.0293 0.0336.0.0396 a.0a1e-01 I .499e+O0 3.045s-01 Ft tvence RiPtc 8.t,334 106-0095.e- 103 4.584e 78 8.943e-56 Results MAY/cfrI/se 3,163s.34 6.04ge-34 I3.1 56e34 3.2119e.34 Ewxtosure Ralm 8,407c, 108 B. 202e-1 05 4.064a. 58 3.3100o.36 6.1 29e. 36 1 .459e*36 Cl -246 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 D S File : P8122933.MS5 Run Date. January 2, 2QO0 P, n Time: Es P10P AM6, Durati .; W.00;01 T ohotAons:se TOTALS: 3,14.5etOO FIijpnr.o R;t#-P NMf Ps.93du 8.943E-!5.Flusnc* Rate.mAVerr."Appr MbhRliCn/r L5+/-.5LuI Umsunq Rate IM22L 4,ol4t*S8 1.31h.r 1.314e 35 Cl-247 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 UttoSIeld wi.4 (5,LO45 362)OIA22M MicroShield 4.04 (S590162)fthdh4otca Seieim, Inc.cw rsh~n of t*1ciI?1ud

• to~wr In Ir. 1tc 4¢ps FM: C:AllS5\DATA%\PB122'93.MS5 CA$* casl l e, M 1s 22 a lTWs C41S W" rut oo ilw4y, January 2* M at 803"O AM Do Pol!is~ I .(1 36.",2q3213.3;)

cmf RisuIts {Sam m ed ove r eaerniea Whnut Photon Vrkjgw Rate (lux)ftoton Eneigy Flunce Rate Stpajt and D~ow Rate%E34:t! ;-se Rite in A ir Ubote a ~ei i Photons/cffem/ Mee~wctfset 2.259e-054 4.856e 032 8.943e056 1.55b$033 4yfiv mrwaihr 4,064o O5-3.64800 60 3 548e 058 1.1304 -JM 1148.037 1.148e035 Dou Om Eqiyalent Rato* "larail4 Gemtry* Oppwed afiw ol Ewilvflinn, P~r o i rrstry C Rotatiorqli a ;-sotroplc,, f~fe N4$ r4iaie, ta¢S0tt~i,)X~eir s t -, s~e+ .M rcl 1#Er;I I 7',Ic9r 5l 1"7;rnSvpnr MG-'Ir Isv~~5.07ge-060 Z58$W0 2. 316'0600 2.2 15e*060 5.109wfto 3.527e0060 3.1527 9060 2.58e*060 1I314e-037 6.59Oe P3ox;5,62 1.038 5.22 1le038 1,432,t 037 0.846e-03S %846v 038 7,277e-038 ('CE5i 1M7)m5-.dhr 21*1S.060 1.790e-060 9-W.e 061 1 .60%060 i.319e 060 5.90e-038 3.045eM38 j. 44c 0,3 3 026e-038 2.507e 403 Pi 1.1l-Cl-248 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 M MicroShield 5.04 (5.04-00362) Radiologicai Services, Inc.Page : 1 DOS File ; PBOO10409AS FR ate: January 4, 2006 RurfTfime: 8:29.50 AM-Duration .00:00:01 File WRel__Date.By;Chec.ed: Case Title, Line i.S9 H

Description:

Revised Model C.aet Sne126 Unit Axt w Sched 40 & 12 in Shid Gvorrctry 10* CA nder Surface External Dose Point f mf- I-- 'K-Vieilht Rawus# 1 136,24 cm 4 t 5.6 in Sjiefo Nome I cyl. Core Shield I Transition Shield 3 Air Gap WM Qeiad 7762,0 cm Dose Points 381 cm 12 t t.Q n 2$ tt 2,O in 2 23.36 cm 7 ft 9.0 in 1.8 7.86 2.4 2.4 O.OG122 7.8f'Shilds)im~ension 5.08 cm 2.65 cm 30.48 cm'M? -cm M1 "oa I Concrete I r"'Concrete Concrete Air I rq-1 sourct Input Giouping Method :Standard Indices Number of Groups :25 Low&e Energy Cutoff 0.015 Photons ~i 0.015 : Excluded Library : Grove Nujcide crm __________l Uci/crn 1 Sn- 126 1.0945t 010 4.04 96c+000 4,5000c 009 Ba665m-10 Buillduap.The material reference Is .CyL. Core.Intepration Parameters Y Direction (axiol) 20 Circumferential 20 Eftermt lady X ghotjoaslee 3.135c.01 M2 MeV/crrrM~' s~n 4,657e.292 5,14le-35 1,.613e. 293 W~ooith Ruriftt 2.02,3e 36 C1-249 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Fase 2 DOS Fi!e: P8010409. MS5 Run Date; January 4, 2OQ6 Run Lime: 8:29:50 AM Dur~tiom: 0000:01£ae Activity 0.03 1.1.86e*+0 t.04 2.023eo02 O.0M 3.88le.01 0.08 1.859e+00 TOTALS; 3.767e+00 Flurpnm. Ratfe 4.192e-101 7,618e-56 5.S3ie- 30 6.664e-23 6.6i64e.23 Fluenct Rate VeY~ffthBif5tin s!t uildun 4.886e.34.211eN-35 4.1~9 21 4 129e21 Exposure Riate NDo Buildin 4.1 55e-103 ,369e-58 1.09ge. 32 1.055e-25 1.055e-25 With BLI4uit!~4,842e-36 9. 776e-38:3.8130 31 6.535e-24 61$35e.124 Cl-250 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mleo~AtelAMv.4 (L64-t02C2) MicraShIcIld ir5.04 (5.044W6~2) ftadiologleat Services, Inc.Conversion of callullatd egxposure In air to dose FILE: C:%MS~kDATAkP8B01f409MS5 This case was run an Wednesday, January 4. 2006 at 8:29:50 AMA Dose Point 9 I .13.4. oc 01/04/06 PIaevil+; M5 ijmmat4 nvipr Pnht~irai~ LIUni*Photons/crn t/sec MOVICmZ/seo 8.3$) e422 5. 162e-020 6.664e-023 4.12ge*O21 Photon FIvvco R~ate (fkx'c)Photon Erwe~gy Fluence Rate Exposu~rei and Dose Ratcs5: Excpos.ure Rtate In Air Absorbed Dose Rite in Air U mR/hr rrt~y/hr mradlflr 1 .O555,025 9,207e-028 9.207e.O26 6 ,535iC-024 5.706.e-26 5 .705v-024.eVep Dose Equivraiont Rate a Parallel Gieorr~etry Oo ppos'e a Rotational o I aotfopic Shallow Dose,~ Equivolernt Rate o Parallel Geo~metry o Rotational`(ICR.P 51 .1q87)m~vhr M 1 ,610o.027 8.57e08 8.33 7e-028 8,277ti028 1 .5$,5,027 11 73e 027.1 73e~027 8.607e-028 99~72e-026 5r315-026 5.166e-026

5. 129e-026 9.886e9-026 7.266e-02r 7.266e-26 5.33-3e*026 Efifctivo Dose Equivalent Rate o Anterior/Posterior Geoeetry o Pmtvrior/Antcrior o Lateral o Rotatbonal o I otopic (ICFP 51

• 1987)mS-v/hr a 1 .353e-027 1 .a32e-027 6.358e. 028 8.787e-028 7.108e~O28 B.381c.026 6.392e*026 3.939e*02,6 6.445e.026 4.404voQ26 Page I Cl-251 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Microftleld Y5.04 (5.04-00362)

Radiological Services, Inc..Page -I DOS File : PB22935-105 Ft 'ate Decembei 29,2005 M.. Time: 4:09:22 PFM Duration 01O1:00:01 Filt Ref_By:-Checked::_ _Case Titie. Line igg 1 Dcscriptin: Revised oWdel CAIc. Zi.95 Unit Act w Schied 40 & 12 In ShWd Geometry: 10- Cylinder Surface- External Dose Point X burff Dimensions

} H787ht762.0 cm Radius 5.00 cm Dose Pojots#1 136,24 cM 381 cm 4 tt 5.6 in X 1? fj5-.O Shields;-Shield Narrnp- Dimension hMster CtyI 5.08 cm' Goncre S9hield 1 .65 cm Irm1 Trart4'iliori rn 25ft 2,Q in z 2I8.36 cm 71 U7Q in a Den ft to 1.8 1,86 C 24 e 2.4 0.00 22 7M Aq et Shield 3 Air Gap W.VIl! ?V'la 3C048 cm Ooncret Al!.025 rn 1 rgi'5voirc huput Grotipng Method

Actual Photon Eokergles&

Zr95 3,0945eQ1GI 4.049E~e+000 4,500ep-OO Buildup The maeiale'a reference Is Cyl. Care Irllegraion, Parameters Y Direction. (axial) 20 Circumferential 20 1.6650e 004£Ener MeV 0-7242 TOTAL&S Activit Filtuonce Rate 1.768c+00 1 2..241ei,00 4,27ae-12 4,009e-e0I 6.81 7e.12 Ru iuhs% 323c0.i 1 1,464e-120

2. 396o4 10 4,881 o~ 15 1 189L-1 ,307e-~14 ExomRato 1.72o* 2.13 4,593o*13 Cl-252 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MlkrmShlild 4.04 (SA4*U63)Micao~hield A.14 (S404-Att) lRaditok.Il Srikes, fmr Cowetsion o1 caeutaiedI exipose In air to dose FLE C\iM35DATA\22293~SASS Case? tle LUneitf3 I ThFEs V* Wa4 fun 4mn Thundy, OYvmbvr 2S, 2005 at 4,O:i22 PMfl Dos Point 1 1 -(136.24,381,23.11) cm F;awmuI+q (Sijmmnr4

=Pr Pnorgi It ttfs WfthVut~kiduo 01/02/" Ptlotor Ftz- ae Rahe MwOte",taitf-f

1. t 'Leme e Rate Pbotons/cml/sec MeWemAstee 9.15Ne012 6.8170,012 3.221e D10 2.396P 010-mosart, and Do Ralft Ox*re Rtate in AFr Absorte DUose Pate A-r a mG/hr nwa~dlth 1130 1#*4g 1.141s-016 1.141e-0.14 4.01,00o015 4.OIe*013 Cvep Sukya Rqr ,;i!rtc:s O Fpaplle. G..:n.rtri io F;-,ato~b I Sottope ryn$ hr I; .337ec06 I 088~010 6 IO088s-016 q.614e- p0 7.701q0205 J.923e0435 3-823e 015 3 379e.0D5!I.30i-z*f Dr-se Equ ivl3ent Rate Li :F~salaie

5e>ellf'tri' ro pena!tioia I (ICRP 51 -?'I um~viht 1. 28e-036 I X361C.016 13G 1e-0] 6 1 -02'016 5.Ol-'-015 4.782.e-01 4.78eI01 5 31616.e-o 5 Efedivoi Dose Emiwlemi~~l 2,ur r Anrteor/wfosteuor Gte 1miro a t aweral r. i

ctrapic (ICRP 51 -2S,4 I 1.181SWO13 i G,5e-D16 7.957e- 017 9.464q01 7 8&10.e-017 4.1 75c -0 3;71%,^015 2-796oe15 3.326;e-1 5 2 849eO 1 Page 1 CI-253 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield Y5.04 (5.04-00362)

Radiological Ser~cui, Inc.Page : 1 DOS File; P812206.%4S5 P Date: December 29, 005 Rlm Time: 4:10:54 PM Duration : 00:0001 File Rai;_Oate: _By: Checked.:_ Case ride: Line L82 J Decsc~rptiono; Rcitsed Mode We~. Co-4SS Unit Act w Setmed 40 & IZ in Shild Geomnetry: 10 =- Cylilder Surface -External Dose Polfft Haeig-t Radius X* 1 136.24. cm 4 ft 5r.6 in SMSIr1 Name E CYL~ Core Shield I Transitionr Shield 3.Air Gap WM'Valt 762.0 cm Dose Polnts:~81 cm 12 ft ,0 in Shields limnrision 5.08 cm' Conci'M6 cm Ire, 25 ft 2.0 in z 213.36 cm 7 ft o in:e 1.8 7,86:e 2.4:e 2.4 0,001 72 ret W41A cmn Cncirel Air.0Z5 m irg-r S~ourcc Input Grouping Alathod :Standard Indices Numbor of Groups ;25 Lowe: Esietgy Cutoff 0.0Z13 Phot9n -, Q.Q15 ; Ezilvdd Library ,Grove 010 4 0496e+000 4.5000e,00 I Eu-155 1.05450-U II ml 9 1.665N0u0O4 Bu;idup-rhe malerial reference Is :Cyl.'Core Integration Parameters Y Directian (axsial)Circumfren1~tial 20 20 1, 289eOW 4.557e. 1 03 Results 5.31 le-36 Exoos 2reRJit ZILU~5-2,4e.38 CJ-254 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Piz : 2 DOS File : PB122936,1S5 Rw Date: Decemwbr jb, 2.O15 Run Time: 4:10:54 PM Duration.

00-zO

1 Vfte.Xy .b1VItl 0-04 7.341e-01 005 2,388.0,i 006 K.252e.02.A 1-257e+0 Oil 2.37it 01 Fluence Rate 2-765e.,54.

7.971'.39 7.48ge-31 47A&0ei32 4.20Q-Z Fluenoe Rate 8.022e.34 8.27e,34 2.598e-29 279We021 1361Le- 18 1,2239-56 2.12.4e.40 1.4889-33 7.12eZ6 1.836e.23 E=2oU ReFatA-ith Rui1 3 548e.36 2.272e,31 5161e 32 4.4 1e2 4 2.013e.21 TOTALS: 3.133e +0O I2ose.2 1364e 18 I.$We 23 2;087e 21 C1-255 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Mlico~lhleI4 u5,5.4 (5.0l4-00362) M.krcSihsid v6.04 (5.04-OO62) Radiao~okal Setvices, Inc.Corwersion of calculatod exposure Ira air to dose FILX: C,,zM$DATANPU122V3$JS55 Ca'se 7thie: Line 1.83 J This cavc wus ruut on Thiursday', Pccu~mbcr 29, 2005 art 4;10.-54 PIIM Dose Polint At 1 -(13G,24r381r213.3fi? cm F3jAiltg (Surnmed over enemrgis)

WithJou~02/02/O6 WLdh 1 ,365Q1 7 1.364e-018 Rhoton Fluen'C Rate (Pum)Photon EamE48Y Fliuencie Rate IPhoLtmnf/rm2/sec M~eV/crn-/sec 1 .206e-0 19 1 .205e-020 Ex~po~sure andc D~os Ratw~Eyposure&

Rate in Ahe AbwQrin~ DQig Rvtv in Air U mnR/hr rnGy/hr rnradhr 1 .8&3c,023 1 .609e.025 2 15D09o023 2..08?e-02 1.922a,-023 I .B22e-021 Ncvr, Dow, Eqwivaicht Rate a Parallef Geornetry O QpposdO$a Rotational a I Sotropic Shall~ow -Xosr Eqjuivalent~ Rate o Parallel Geemetby a Qp9asnd o Rotatiwnil o lwl~ropic-Efoectivc Dose Ecwivi, nt Mplo.c Anterior/Posterior Geornyetry o Post-etir/A.ntert~r o Lateral a Rotatoonal o Isolifopic (ICRP 51 1987)mnSY/hr (ICRP 51 -1987)rnSv/hr mSv/hr a, 2,68ge -02.5 1 .475e-O2 5 1,475e-025 1 .427e.02S 2.672e-02S 2 ,073e.025 2.073e-026 I1,509e-025 2.3i2e,-025 1.1e-2 I 119e-D25.54ge-0,26 I 232*020,5 3-045e-023 l-670C 023 1.670e.023 It.616e 023 3.026e'023 2.348e-023 2.344te023

1. 70ge-023 2.618e-023 2,053e-023 1 .267e.023 1.75:3e.Q23 1.-39'5c-023 Page I Cl-256 Final Status Survey Plan for the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment

& DCGL Calculation Addendum 2 MicroShield Case Run Reports for Pump Room Trench Pipe Cluster MicroShield Case Run Reports for Pump Room Trench Pipe Cluster Index Run Date Case Title Description File Name Result (mrem/hr)2/3/2006 Line 1.36 A PBRF Pump Room Trench with Co-60, PB020301 4.225E-13 1 ft concrete wall shield 2/3/2006 Line 1.35 A PBRF Pump Room Trench with Co-60, PB020302 1.305E-12 1 ft. concrete wall shield PBRF Pump Room Trench with Co-60, 2/3/2006 Line 1.34 A 1 t oceewl hedPBO20303 5.920E3-15 1 ft. concrete wall shield PBRF Pump Room Trench with Co-60, 2/3/2006 Line 1.33 A PB020304 8.6461E-15 1 ft. concrete wall shield 2/3/2006 Line 1.32 A I A. Roncrench sh PB020305 8.15713E-19 1 ft concrete wall shield 2/3/2006 Line 1.31 A IPBRF Pump Room Trench with Co-60, PO00 .E1 1 ft. concrete wall shield PI 003 I 1.I3E C2-1 MiOro.h1ield Y6D05f (9.5. $2)Radiological Servims. bhe.Pago : 1 DO$ File: PB020301.MS5 Run Date. Fbnuary 3. 2006 F Tin: 7:07:06 PM D diocn : 00:00:00 File Ref: Da__ _By: checI._Case rhie: Line i.3 A Descriptio: PERF Prnp Rm Trench Co-80 w 1 ft con wal shield A conc cores Geoirety. 10 -Cylinder Surface -Externalt Dose Point Height Radius Sourco Dirnonslons 34.6cm 10flOtO.Oin 12.7 cm 5.0 in x Y 1 -Dv.l W#1 53.3 cm S5hield Nelme in Cyl. Core e 2.7 Tfansitlon Air(;ap Was Clad 30.4 Immcrion ource Input 6rouping Method : Actual Photon Energies 1= bemuClr Ucm ta045"010 4.04e4)00O 45soNa00w9 io PQont x 404. 8 an 13 ft 3.4 in ihields P CM7 Cowcete 7 ,na e ;S Air 8 = Concrete Concwto IA.650e.004-z O cm 1.8 2.4 0.00122 2.4 2.4 Nuglide Co-EQ Buildup Thue nmtral rivbrente Is' Cyt. COr Integration Paremetemr Y Direcion (wcal) 20 Cicrrnrenotial 20 0A.M't.1,1732 1.3325 TOTALS.f.1 photonzfsec 860$e-04 4.050e+00 4.050e400 8. 100eO0 Results.Ruance Rate Fluence Rate Exooure Rate EXwsure Rate W-77Ms97 4eJsemRhr mRF/hr LW With BUMd ND Buildup With Builup 8,75ft-18 5 562e-5 s.691e-20 1-074o-i&3.652e-12 01 t~e-1 I 6,47e-16 1.62,.e913 9.129o-12 1.903e-10 t.5E-14 3-31go-13 1,268e- 1I 2.824e-10 2,21&-.14 4.947e-13 C2-2 Microahtled v6.06 (5.O.060352) MicroShield vS.0 (5.DS-00362) Radioloficall Sermices, tnc.Cormermion of caulcuated exposure In air to dose FILE.- C:WSSDATAIPEOM01.11VSS Case Titl.: Urm 1.35 A Thfs; cas* was run on Frktay. February 3, 2106.1t 7WO7O06 PM Dose Point 9 I -(53.3,404.8.0) cm UN 1=T Wgob ithouti 0213106 With BLMM Photon Fbence Rate (flux).Photon Energy Fiuenice Rate Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Ar ,.Pholone/cmtsec Movicn9/se 9.878e01 2 11.25e-oi I 2,212e.01Q 2.82,4e-010 mR/hr mGY/hr mradihf 2.21 8e-0114 11.907e-O 10 1.937e-0-14 4.947e-O13 4 319c-O15 4-319e-013 Deep Dose Equivalent Rato o Parailel Geoleuy o Opposed o Roptin o Iworopic Shalio Dose Equavalent, Rates o ParaJel Gooneity o Oppoed D Rotational o Isotropic Effedive Dose Equivalent Rate c AnterorYPosteror Geornetry o Posterior/Anterim o Lateral of Rotaliorwi o Isotropic (ICRP 51 -19a7)mSv/hr (ICRP 6t -107 rn~vlhr If 2. 19i8-Ol6 1.B95e-016 1.895c-016 1.,94"-16 2.339e.O010 2.253e4.116 2.253e-016 I1.793e.016 4.902a-D015 4.226e-015 4.225e-0 15 317l5e-O015 S 217e"16 5-025e,-015 5,025"-1 5 3,99~8eO5 (ICRI' 51 -19B7)mSvlhr 1 .979e-016 1 625e-016 1 .453e-016 1 643e-0116 1 456e-016 AA1 5e-O 1 4.06ge-015S 3.23ge-OtS 3.664e-015 3 .244e-01 S PagU I-C2-3 MicroShfld. v5AS -00562)Radi1boga llrvbm, Inc.PagO 1 DO$ File: PB020302J.MS Run Date: February 3, 2,00*R Time: 71-3:2 PM DwutiOn : 00:00:00 File Ref:_By:_= __Checkod _Case riie. Lb US A Deatciption: PERF Fmp! Rm Trench Co-S w 1 ft cone wall ahield & conc core Gomota 10 -Cylinder Surffac -Extrnal Doe Point eigt Radhu Sourco Dimensions 304.8 CM 10 ft 0.0 in 3.-1 Om 1.5 in*x 62.2 CM Eh-id Nan N Q Cyl. Core 3.81 Transitlon Air Gap Wall Clad 30.4 Immcws~bn Source Input Grouping Method : Actal Photon Energies Nuelid e 1u21ea I4-000mG Co6 3 7035e-11 Z.2149o+0100 450k00o0 s Poirft Y 404.8 cm 13 ft 3.4 in 5hi-elds Bnsio Mtarinal I cmr Concrht Concreie Air 8 cm Concrete Concrcc 2 53.3 cm It 9,0 In I Donsy I 1.8 2.4 0.00122 2 .4 , 2.4 Bghmf 1.665Sc-004 Buildup Theumtlsral reference is: CyL. Co Ihtogration Parumuwtr Y Direction (axig Cirumferential 20 20 El tivi y M, i2onhs 0.69X8 1.82e-4 1,1732 1-215e+00 1.3325 1.215e+00 TOTALS: 2A43e+Q0 Resullta Flftnog Rgilw FluWO Rs1t E ExposrureRate w-V~gm ee MeVLnMz ME& mRlhr inm FliJKi WLDo Buldm With Buildup_7.A47e-17 Uia&-115 1743&t-1I 6.584M-i 1 ,$72e1 1 3.09e110 2.810e- t4 .602e413;3A85e- I 5-642e-10 6.047e-44 9.788oe-1 5.058u-l1 8721e-i10 8.857e114 1 .62ge-12 C2-4 MicIfShlbad MS (5V0" 362)MicroShleld vS05 (5064032)Radbalogica Services, Inc, Conversion of calculated expoaUr bI mlr to dose FILE: CVSMTATIPB02G30LMS5 Case rTit.l Une 135 A This cas wias run on Friday, Februar 3, 2006 at 7;33;25 PM De Pointr 1- (622,404.8,53.3) tm 021D031 REpImis 19mmed ovr enerniest Photon Fluencia Rate (flux)Photon Energy Fluence Rate Exposure and Dose Ratas: Excpoure Rate in Air AbwrdW Dos Rato in Air Deep Dose Equkatent Rate Q Paraliel Geonetry o Opposed o Rotatool o Iotropic Shallow Dose Equivalent Rate* Parel Geomtcry o Otpposed .O R~otatirnl o Isooropie Effectie Dose Equivalrit Rabte o AnterlorfPsterlor Geomeny o PosteriorArtderior o Lateral o Rolatioml o Isotropic Photonskatwsec meVicWhee mt~hr mGylhr mrwdlhr 41CRP 51 -1957)mgVlhr., WithOUt Builduo 3.g5-01 1 5.058e-0 1 8.'7e.014 7.732e-O16 7.732e"014 8,77se-016 7.564e-016 7,564e-016 6.759e0-16 With 6.858-010 6.721e-010 1 52te-012 1 335e-014 1 .35e-012 1.51$e.014 1 .305e-014 i.30$e-014

1. 16f-014 (ICRP 51 -iS7)mnSvihr RI (ICRP 51 -108-7)H i..1..9.33Sse016 8.995e-O1B 8.995e-016 7.16,8e-016 7.903e-016 7.2$4e4 16&.799e"16 6.560e-016 00 0 a 1 .613e-0I4 1.563e.014 1 .553e-014 1 .235e-014 1 .365o-014 1.267e-014 1 .WOe-014 t. 132e-014 TPag 14 Page C2-5

.MicroShield v5.06 (6,S~06OM62) Radkiolocall Sarvices. Inc.Pape :I DOS File P 02030UItSS Run D.Me, Febtuezy 3, 200$R Tinve: 7:211:118PM Durt iion : (M):O.00-0 File Ref,_ _ChecAed;____ Case Tille. Line 1.34 A

Description:

PBRF Prmp Rm Trench CcA50 w 1 ft conc wall shield & cono core Cleomotryf 10 -Cylinder Surface -Extenal Dose Point Height Radius Sourmo Dimensions 304.0Bicm 10 ft'O.0in 12.7 cm 5A3 in U z# 1 53.3Om I ft 9.0 in Dose polintu x 404 8 em 13 R 3Ain Shields 3 3 Shield Namne Dime co1, c-ore 7r, Trarks~ton Atr Gap Wall Clad 30.4 Im(Mrsion, Souice Input Grouping Method ; Achial Photon Energies curie by~gar& Xtan 2 t.095e-010 4.04960+OO 4.5D0OD-009 nsion Material fConcrete Air 8 cm Concrete Concrete 6.5 cm ft 6.0 in Densitv 1.S 2.4 0.00122 2.4 2.4 Nucbda CO-O0 1.66S0e-OD4 Ruildup Th6 nuiettial Wafronev is -Cy, ~Coro khterali'n Pmrameters YDirection (edaD ~ 210 Ci.crcinfrential 20 Fbl2D1 Riesufts M6 LAnM-./ee MAVimehm, MRthr mR/hr M Buklu VMBol= WBuidup WMibBuirdua 2,788e-14 1.070e.12 O.93e-11? 1.912e-15 9,437e-14 2,693e.12 1,637e-16 .191 0Z936 1.1732 1.3325 6,80$e.04 4.050e*00 4.050e*00 TQTALW 8.100e+00 1223e-13 3.963e-12 2.136e-16 6.930eS15.-C2-6 Page : 2 DOS File .P8=303MSS Run Date; February 3, 2006 Run rime: 6:40:40 PM D1 ..C2-7 MicroShicdd vS-.06 (&05.e0362) MicroShilelld v545 (5.05-003M2 Radiological Sofrkm Ic. hc Conwvrsloi or cattulated expsun in sit to dose FILE: CNW51DATAMPB20303.MS5 Cas-* TO*l: Una 1.34 A Thia case was run an Friday, Febmury 3, 2008 at 7:21:1S PMI DMs Point I1 -(531304 1 4J,106AJ cm Results (Summed ovter n2ErgEm M Withu Buildun 02)103o Mu1u Photon Fluence Rate ({lux)Photon Energy Fluenre PAbe Exposure and Dose Rates: Exposure Rate in At Absotbed Dose Rate in Air Deep Dose Equivalent Pate o Paralel Geometry o Opposed o Ro1etlon~I o Isotropic Photonsbcm 2/sec Me~lct/sec rnR/hr mGylhr mnradff KIRP S1 -198)rn~vlhr In 9.R5ge-014 1 223e-013 2-M3e-016 11.864u-018 1 low'010 2,1150-01B I .M2.01 B 11,825e-018 1 631le-0I8 3.OM3-012 3.963e.12 6,030e-4I S 6.050e-017 6.865"-17 6.MZe4O17 5,M2e-017 S.291*17 IShallow Dose Equivalent Rate o Parallel Geometry o, Opposed o Mo~UMn!o Ieotropec Effective Dose Squiialont Rate o AnterloflPostedor Geometry o Posteriurlnterio! o Lateral o Rottionlaf o Isotropic (ICRP 51 -1987)mnSvlhr In I i (ICRP 51-1987)rnSv/hr of to~2-Me.O1 116136-018 2.168e-0i8 1.727e4O18 1 905e-OiB 1.757L..018 1 .400e-01 B I .583e-018 1 .402e-015 7.037"-17 7.0~37e-01 7 5.603.-1l7 &6,to83ol7 5.701"-17 4,41e-017 5.134e-O17 4.Wo~-017 Page I C2-8 NfcroShield v5.05 (S,D5.O0362) Rad~oogicall Servicos, kmc Page : 1 DOS File, P10209K4.MS5 Run ODae: February 3, 2006 P Time: 7:34:46 PM Dlwabon : WO:0O:00 File Ref: Da le ;-By: Chocked'Case rhide Lne 11il1A Dsaciptioa, PBRF Prnp Rm Trench Co-CO w 1 ft coinc wall sheled & cone cowe Georn~efy. 10 -Cylindar Sudac.e -Extarnal Dowe Foitn Source Dimensions Height 304,8 OM 10ft0.0ii Rais .1 GM 1.5 in 9/f*1i 62,2 on 2 II 0.5 irt Cyl. Core Transition Air Gap Wall CIO4 Immmrign Dose Paints 404. cm 13 fI 3.4 i 160cm 5 ft 3.0 in Stields 3.81 cia 2 Material Concrete Concrete 1.8 2.4 0.00122 2.4 2.4 Air 30.48cm Concrege.C~nureIe Sourme Input Grouping Mauthd : Aduial Photon Energl~a Nuclide curies becquerels [ikym 2 VaOQ 3.2~015 I 1214Wo+QQQ 4.Ngft-UQQ9 Bq/cm2 1 .6650e-004 BWildup The matsrfalrrerncclR is:Cyl. Core lntejyratian Fanmmtomi Y Direction (axcial)Cilum~erntial 20 20 0.6038 1.1732 I 13325 1.g62-04 1 215e+D0 11-215e000 5.2876-20 4,$40eaI4 1.519e-13 Reamdfs FlVicmw Iec 4.1 16o-12 rnRfhr pb 1.021e-22 .9.294e-21 8.8280-ST 2.1.Wel1$2.635e-46 7.14le-15 TOTALS: 2,430e+00 2.01e->13. 6.784-12 3.518e-i6 1.0120e4 C2-9 Mkero W vSAiM (5.ISAM3U Mibt~ShIefd dtLO (&SCiWO32) Radkotolka1t tor v e Inc.Comrsim of .cautded xpowure In air to dw F :LE: C.-W3AU>E120304ASS Case We: Une 1.33 A This case was run an Frlday, Fbruary 3,2006 at 7.34.;4 P1 Dsos Po4t 1.2*6L 4O4,160) cm M06O ROsJfh I$#WwrJ g=110h Matho.Oulddw W h DaLI&ua Photon Fluence Rate (flux)Photon Energy Fluefloo Rate PhQUm*0eh Mewowftef.,.541eO113 4.511e-012 2.O13"13 5.7Me-012 Emmur &W Dow Rateht: Enmwe Raoe in Air Absoed DOme Rate in Ar M MRft m131fi 3 S11kO16 3 071O18 3:10o910 1 012e014 6 36eB017 6103004015 Deep Dose Eqdwiem Rate O POrWIN Geometry o Oppossd o R*ialonna o Isotropic Wh ow Doe lEquivabnt Rale O Paralft GeOrMtry o Oppoed o Isotropic (1CRP St -MT),,'I~ICRP 5t -1987)nsvfr 3 46A 014 3 008e414 3 OOM-O18 2-687n018 3,707e-01$ 3.572e"18 3.672"19 2,844"18¶ 003e-Ol6 8 46ee017 8.-643e-017 7- 726e-0o7 t 067e.016 1t028e-016 t.2ge-016 a 132e-017 Effecte Dosw Equaknt Rate o AnteriorPosterior Gemetry o PosftrifoItefkW o Lateral o Roawiat o Isotropic QCRP Si -1987 nfta~1 U 3.t3ge018 294"c'-1 23Oteis 2.607e"18 2,31 Q41 P 031e-017 e 3250-17-630e017 7.498-01 7 410e-01T Page 1 C2-10 Microfteled ADS.O l565C42 Pag, : Radiological Serv'ices, hIt.DOS File .PBO20305,MS5 Run Date: Febnjory 3, 2006 R- lim: 7:-30:54 PM File Ref:_By: Checked: Case Title: Line 132 A Descriptiaof. PBRF Pmp Rm Trench Co-SO w I ft conc wall shield & conc core Geometry: 10 -Cylinder Surfae -Extemral Dost Point Source Wimonsliis Hleight 3041wn cm 1ft0.frin ROW* 12-7 cm 5.0 in I 7'V l/x# 1 53.3 CM I ft9.Oin Dsue Points 404.e cm 13 ft 3.4in~LLLNL.J I_, TransIitonl Air Gap Wall Clad 30,41 Imrnorion Source Input GroUpinq W~hod : ActUat Photon EneIrgiS 1-0945e-OtO 4.049r6e+000 4.500(~e-009 Concrele Air Rcm Concrete Concrete z 214 cm ft 0.3 In 2.4 0.00122 2.4 2.4 I1.665%-O04 Bliduzp rho malurdal rrektnco is ;. CyL. Coro Integmiaton Furwznstem Y DirecI~on ("axil Ckcumforentlal 20 20 1.1732 1,3325 6,6O0"O 4.050e+00 4,QS6e*O0 Fluence Rate Fluence Rate Exposure Robe Exposure Rate No Buildu= With Build NaBuldu p , With Buildup 6,803e-26' I .47e-23 1 .314e.28 19570-26 1.3680.8 0.626e-17 2."44e-21 1.720e-19 8.273c-8 4.508c1 1.43-5c-21) 7.822e-19 TOTALS: 8,10"e+0 9641e.-18 6,471e-16 1,6>80-21 9.542e-19 C2-11 PAMAcr~eld vS&OI (US-05392) MicroSthield v506 (5.0-0D362) Radiological Servicatu, inc.Corm~rs~on of calculated exposture In air to dose FILE! CAS A P023 IS Case Tidfe: Uni 1.32 A This case was run on Friday, February 3, 2006 at 7r-30G54 PH Dose Point I#1 -63.3,404.8,214) CM-021010 Results (Summed over enemies)Photon Fluence Rate (flux)Photon Energy Fluenoe Rait Without Buildup With Buldwx Photonsla~n'lJsea MeVfawIsec 1.374e-018 4.204"-15 9.641e-018 5.471e-016 Exposure ard Dose Rates: Exposure Rate in Air Absfted Oose Rate In Adr Is mPA'r M130lV mradihr 1 .680"-20 i .486e-422 1.466"-20 9.5429-019 8&330eV01 8.330e-019 Deep Dose Equablent Rats o Parallel Geomety o Opposed e Rottlt.or.l o Isotropic Shallow Dose Equivalern Rate o Parakil Geomalry Q Opposed o Rotalional O IsotropiC (ICRP £1 -1o&7 ni~vihr I.,I 11 803e-22 1 .43fie-022 1 .4316-022 I .284e0-022 1 ,76ge4O22 1 .705e-022 I1.706eA22 1 .35ge-022 9,448e.021 8.1 57e-021 8.1 57e-021 7,293e.021 1 000,020I 9.68te-021 7.718e-021 Effective Dose Equivalent Rateo OMAntrlorlfoti edor Geam4rery o Postwior/Anterloc o, Lateral o, Rotaton~al o, Isotropic (ICRP 51 -1087)m~vhr if'I0 to 1.498e-022 1 .382e-022 1, 103e-022 I1.245e-022 .1,100422 8,511eO021 7.852e-021 6,263e.021 7.074e-021 6,270e.021 Paso I C2-12 Micro~hied vS0 (5,D5-0Q362) RadkAV4 al Scnmkos, Inc.pape : 1 DOS FiePE020306.MS5 Run ChmT: February 3, 2006 R riw: 7:45:12 PM Dutation :00:00:OD File Ref:_Date: By: Checked: Case rTob Une CHl A

Description:

PBRF Pmp Rm Trench Co460 w 1 ft conc wall shield & cone core Guematay 10 -Cylinder Surface -External Dose Point PHeigh~t Radius Source imanslons; MUM 10 ft 0.0 in 151 cm 1r5 in x/X 1 1 62.2cm 2 0 , 5 In Dose Points 404.8 c-m 13 ft 3.4 in Shlda I Shied N" Dim Cyl. COTe 3.81 TranSatin Air Gap'Vio Clad 30.44 Immmin Source Input Grouping Mathaid .Actual Photon Energies, CO-60 3.28350-01 1 1,2149c+000 4.5400o009M cmt Concreuis Concrele Air 8 cm CGoncrmee 1.665~0"04 z;66.5 cm ft 8_ im 1.8 2.4 0.00122 2.4 2.4 Buildup Tho latarlal rmforanc Is. Cyl. Coro~kftefratlon Parameters Y Diahon(axiaI) +Cimtrciamfoelha 20 20 0.6938 1.1732 1 3325 TOTALS: Aativity 1,982e.'04 1.216et-00 1.21k+4QQ 2.430ei+0O Res-ulls Fle,0 a Flueioe Rale.t* tit.~ Me ExoutRt M^A-2~ mevfls B&M2 4, 193e.2 7.23Wo22 8&0950-27 1.396e-24 2.8170e-1 1.683e-15 5.034e-20 2.82ge.18 1.818e.1B .7A59e-15 2,822e-19 1,302e47t C2-13 ftlirShleld VS510 (O45-036) 0130 OWN MiicroShleld v6.O5 (5,M 0362)Radiologica! Services 1 Inc.Conveirion of Ca dlWexpoisure In air to doze FILE; QVISSM UMMAAPB230SMS5 Caso T116: Uina 1.31 A'thts cast was run en 3rdy 1 FI .r 32006 at 7:45:12 PM 0*08 MMin II -(62.2AN.B,2~665) cm faiks thuM PMe igr nemiWWihri Photon Flueno Rate (flux)Photon Energy Fluence Rate Fhtiadd~!Mzfsec: MeV/CM*lsec I ,243eG016 6,79e.01 5 1.61ge-016 7.45ke-015 Exposure and Dase Rates: Exposure Rate in Air Absutad Dose Rate in Air of mftIr nGYfihr Mrad/tw 2.8226,011B 2.463e.021 2,4,3e-019, 11. 3020,017-1137e-019 113,17e-017 Dueep Dose Equivalent Rafe, o Parallel Geometry o Opposed o Rotational o Isotwpic Shallow Dose Equivatent Rate o Paralbel GeoMetry o Ischoplc (UCP St -1987)mSv/r (ICRP 511 -1987)mSvfhr'I H, 2,794e.021 2.41 2s-021 2.412e.021 2.1 570.021 2.972e-021 2.M6e-0211 286c-0,21 2.2M3-021 12K0e&019 1. 113e-01 9 1.113e.019 9.94go-020 1.372e-019 1-322e-019 1.322e-019 1O0&U-0i19 Effective Dose Equivalent Rate o AnterioriPooterior Geormery o Poftoriot/Anterior o Latera o Rotallonal olIsotropic (ICRP 51 -1987)m~vhr'I I, 2.517e-021 2.322e.021 1 .852e-621 2.092e.021 1,.864e-021 11.1l29-019 1Il71e.0119 8.542e-020 9.652e-020 8-554e20 Pag i C2-14 Final Status Survey Plan for the Plum Brook Reactor Facility Attachment C Embedded Piping Dose Assessment & DCGL Calculation Addendum 3 MicroShield Case Run Reports for Area Factor Calculations MicroShield Case Run Reports for Area Factor Calculations Index MS5 File Dose Rate Run Date Case Title Description Name (mrem/hr)2/4/2006 Line 1.21 AF-A PBR Revsed Model Co60 PB020401 1.0810E-10 Area Factor Calculation 2/4/2006 Line 1.21 AF-B PBRF Revised Model Co-60 PB020402 2.0910E-10 Area Factor Calculation 2/4/2006 Line 1.21 AF-C PBRF Revised Model Co-60 PB020403 4.2570E-10 Area Factor Calculation 2/4/2006 Line 1.21 AF-D PBRF Revised Model Co-60 PB020404 5.3940E-10 Area Factor Calculation 2/4/2006 Line 1.23 AF-A PBRF Revised Model Co-60 PB020405 1.0820E-10 Area Factor Calculation 2/4/2006 Line 1.23 AF-B PBRF Revised Model Co-60 PB020406-2.09 bE-l0 Area Factor Calculation 2/4/2006 Line 1.23 AF-BG PBRF Revised Model Co-60 PB02040 4.28E-10 2/4/2006 Line 1.23 AF-D Area Factor Calculation PBO20407 1.250E-10 2/4/2006 Line 1.23 AF-D PBRF Revised Model Co-60 PB020408 5.3950E-10 Area Factor Calculation 2/4/2006 Line 1.24 AF-A PBRF Revised Model Co-60 PB020409 3.2270E-1 1 Area Factor Calculation 2/4/2006 Line 1.24 AF-B PBRF Revised Model Co-60 PB020410 6.2720E-1 1 Area Factor Calculation 2/4/206 Lie 1.2 AF-C PBRF Revised Model Co-60 PO01 .1031 2/4/2006 Lie 1.24 AF-CArea Factor Calculation PB241 1.13E0 2/4/2006 Line 1.24 AF-D PBRF Revised Model Co-60 PBO20412 1.7250E-10 Area Factor Calculation 2/4/2006 Line 1.641 AF-A PBRF Revised Model Co-60 PBO20413 5.2760E-1 I Area Factor Calculation 2/4/206 Lin 1.64 AF-B PBRF Revised Model Co-60 PB244 105E0 2/4/2006 Line 1.41 AF-BArea Factor Calculation PB244 105E0 2/4/2006 Line 1.641 AF-C PBOFRvsdMde o6 B20415 2.1390E-10 Area Factor Calculation 2/4/2006 Ln164A-D PBRF Revised Model Co-60 PBO20416 2.7950E-10.Line 1-41 AF-DArea Factor Calculation III C3-1 MicroSt~eld v5.05 (S&O6O352) Racft"IoiaI 8orvics, lInc.'Pege :1 D Fofe P0020401.iS5 Run Dale: February 4, 2006 R Time: 2:01:22 PM Dliratin : 00:00:00 File Ref:_ _Date: By: Checked: Case Title: Lion 1.21 AF-A Doesrptioni: PBRF Rev Modol Co40 Aroa Factor Caloutkdln Gewmatqry 10 -Cylinder Surface -External Dose Point I Scurm Height Radius DoK#1 138.78cam Shild ame Djme-Cyl. Core,'1P*~~1Shield 1 I Transalion-shield 31 304 Air Gap Well Clad .02 Grouping Method :Actual Photon Enotilgiu 00-60 6.5669e..012 2.42W-e0011 4.50O~e-0&0 O Dimnisionis 30.48cm 7.82 cm se Poi~nts x 15.24 can 6.0 In 5ani Iror I ft 45.72 cm I l't .0 in 7~ .88,~2A hZA4 0-00122 7.86 ial 8;I 8n ConixetU 5 cm Iron I1.6650e-004 Buildup The maerial reference is: Cyl. Core 0k~l Integra-don Parameterm Y Drecion(axial) Citcurnfewn~lal 20 20 0,593s 1.1732 13. 325 2-A30e-01 2 A30e-01 Fluence RArta Fhuence ae fgar Rate E2x2Mure Rate PAVA7k MVkrfAc ~ v~h 0, O P I Wbiludup .N dd ihui 7.261e-1-4 .'1.178e 1,402e.6 2.274e-i 3.67le-09 3.023e-08 6.381e-12 5.40.2e- 11 5.7Z22 "O 4.1 P1 "- 9.2.0e-iZ 7'.27f-1 1 C3-2 Page :2 DOS Fe: PBO20401 US5S Run CDat,: February 4, 2OO Ron Tone: 2:01t22 PM Durfon : 00;QQ-u ~ R FluenOa RFI Eit Eosurs Rt E ur MY phOtAontec

• ktme s MeVlcfmfsp mRAr Shf*o tjldw M BuIkduo With Buildup TOTALS: 4,86O0e1 G293e-09 7.213e-G 1.631e-11 12'67o-1 w.C3-3 MIcroShlWid vS.06 (6.05.0032)

-, '.02uMo MictorSlld v5.0 (3SA-U2)Raci4lottcai Saoivess. Inc.Comwulon of cakutated oxposure In airto dose FRLiEs C1WATA3POB2041.M$SS COge T1to: U-n 1.21 AFA Th1i case was run an Saturday, February 4,21M at 2:011:22 PM Doma PoInt #1i -(13.7a,1524,4.72) cm Mhout BUluik Buimut Photnn Fluence Rate (flux)Phcton Enorgy Fllue=& Rat Exposure and Dose Rates: Exposure Rote In Air Absodred Done Rate in Air IR Pholonedcmlfec MoVkanmekc 7.38e-009 91293e-009 6.72le-00 7.213e-008 mR/hr mGyhr mfihr.631o4-1 1 1.424e-013 t424e-011 1.267e.010 1.10 e-012 1.1we-010 Deep Dose Equivalent Rate* Parallet Ge1oery o Opposed o RotatonaJ o Isotropic (ICRP 51 -197)mSvlhr n t ,616e-13 1.392e-01 3 ,$'e-013 1.244e-013 1.256e-g12 1.081e-012 1,O1e-012 9.650e-013 ..I k I 1%.)i-i i Shallow Dose Equivalent Rate o Pwrallel Geometry o Opposed o Rotaonst o Isotropic Effectve Dlow Equivulwt FRabt o AnterioPosteror Geometry o PoderiolAftor o Lderal o Rotationaf o Isotopic (ICRP Si -I 7)mivlhr QCRP 51 -19B7)m6vhr I, 1 721e-013 1.657e-G13 1.657e-013 1 3117e-013 1.45t-013 1 .341e-013 t1.C-13 I .0e-01 3 1 9oC-01 3 I .337e-012 1.287e012 1.267"12 1.023e-012 1.131e-012 1.042L-012 8,280e-013 9.379e-013 8,29e-01 3 Page 1 C3-4 M~icrotileld YvSJ6 (5.05-0D362),Radiologieal Sorvicca, lrt.Page3 : 1 DOS File -PB020402.MS5 Run Date: -fabrUrY 4,200 R rime: 2:05:04 PM Dutation : 0O-OD.00 File Rr:_Date: Checked:__ __Case Title: Une 1.21 AF.B Dscription: PBRF Rey Model Co-OD Area Fadw CelculaUon Geametnry 10 -Cylinder Surlace -External Dose Point I I..._,j 7 Height Radius# 1 138.78 4 ft 8.Shield Naw Cyl. Cora SJield I Triewsitn Shild 3 Air Gap YWall Clad Source Dimenslons 60.96 cm 7.h2 cm Wose Points I an 30.48 CM Shlolds 7.62 cm' Conci.$5 cm krai 2 ft 3.0 in 45.72 cm I ft 6,0 In 7.0;: 2.4 2.4 0.00122 7 186:ehi Icommilt 1Q4 ~ CowvrOt, Air.025 cm Iron Source Input Grouping Mthod ; Atual Photon EnartiO alim b rels Uel 1.31 34e-O1 1 4.1595e001 4,5000e-00 Co-OOw 1 ak5OmQ04 BAildup The material rtefrenoo Is : Cy]. Coto Integration Parameters Y Diredioni (axial)Circurnretentiaf 20 2D Mat 0,038 1.1732 1.3325 Aab& Rueoe ate luew* ate 117-oorg; ae Ex~osuta Rate lig E~bg Wth SuldkM No 19uildurii 1f~-O .383e-13 2..260e-12 2.669e-18 4.363e-15 4,8~e-01 et8s-se-os 6.63se-aa 1,2265e.1 1 043e_-10 4.8M0-01 1.1gi0-o0

6. 1 059-Q 1.0Q-11 1.406e-10 C3-5 Page : 2 IX)S FIee P PW2F.O2M$5 xJw Run Cabe: February4, 2006 vRrm Time: U:O O4 PM Di nation A:1DX:0O AAdi'MAil t photoised TOTALS: 9.72M-01 Fluen t OFluence Rate Expoeure Rate Exposure Rat levkmls U zRaht mrihr W m w OUM N Build With Buildup 1.7weW 1.4 7 3.134e-11 2.450a-10 C3-6 Micro~hlicd vh.0el(5.05-003&2 Radfollookcai Sowkce0, Inc.Con-versioa of eacla tedI expmsre In air to doze FILE: CMWSMUITAP13021140LIIS Casa lntIe: LUne 1.21 AF4B Mhs, cae was mun an SUwdsy, Febmary 4, 2000at 2:06:04 PM Dose PMin #1 -(11 3&78,30,48,45.72) cm 02n010 Unft WithMut vWith Photon Fluencs Rate (flux)Photon Energy Fkience Rate Photonwcw/wo MeVkWm~lec 11 41 Oe008 1 .786e-008 1, 1106e.07 I1.394eM07 Exposure and Dose Rates: Exposure Rae in Air Absorbed Dos Rate in Air to m~ihf m~/r mrad/hr 3-134e-O111 2.736e-013 213ft-.1 1 2.450e,-010 2139e-O12 2.139"~10O Deep Dose Equivaloni Raic o Psralld Geometry o Opposed o Rotationai o Isoiropic Shallow Dose Equivalent Rakt o Parallel Geometry o Opposed o RoEational o Isotropic Effective Dose Equivalent Rate o AnteriordPosterior Geomety o PeOrIAntenor o L1e0al o Rotational o Isotropic (ICRP 51 -1987)mSvlhr (ICRP 5t -1987)m6ythr I.It 3. 107e-013 2-675e-01 3 2-675e-01 3 2.39e-01 3 3.3070-0113 3-184e.01 3 3,184e.0113 2..532e-O-13 2.797Q-01 3 2.677e-01 3 2-049e-13 2.320e-01 3 2-064e-01 3 (ICRP 51 -1987)mSvihr of*1 2.4280-01 2 2.091 e-012 2.O91e-0112 1.867'ewD12 2.5155"112 2.489e-01 2.456 e- 1 2 1.979e-012 2.187e-012 2.01 4e-012 1161e.O12 1.81 3e-0 12 i .604e-O1 2 PaeeGll C3- 7 M AcroTghibeld v&6S9 (51MOM11 Ra-diodlogical Sorvices.

Inc..Pago :1 DO$ FiLe: PQO20403ASS Run Dab1: February 4,2006 R Rame; 206:56 PM Duration : 00:00:00 Fibe Ref:____Dale:_____ isY: Ghebked;_ -Case THIte LiUn 121 AF-C

Description:

PBRF Rev Model Co-SO Area. Factor Calculation Gaometry; IO -i r Suifte -External Dose Point&out*C Dimensi Ibitt 1516 ,cm Radius 1.ff2 cm Ions 77 x At1 138,78cm 4 ft6.6 in G yC Core Shield I Transition Shi~eld 3 Air Gap zarn Clad 76.2 Cn'm 2 ft O.0 ine shlelds ftiension Fiatei 7.02 oan' Concm..g5d cm [r 5ft0.0 in 3.0 in z 45.72 cm 1 ft 6.0 in ial Density Ao 1.8;7.88 fte 2.4 ite 2.4 0.00122 I ." j I Concri 50.48 cm Concr Afr.025 cm Iran Souvi* Input Nuclide Grouping.Method -: Actual Photon Energbes Nuc___ 2011EIA QIit CcO-80 3.2&35e-1 1 1.21,49a+OOD 4.5000e-009 I1.6650e-00'4 BuiNdup Tho materfal mfomnevc is : Cyll. Core I ntq atlon Parameterm Y Directon (Axial)<;curcnf~rential 20 20 G.6938 1.1732 1.3325 1 .952e-04 1.21$esc0D 1.215e+00 Resulta FIismnoe RM1 Fluence Rate, E mRt Exposure Rte 1dv~~m ________ j"R~hr mR__No buAm WhBufdDNuild=~ Will, Buildup Id 2.007e.-113 4.4248 3570e4.4w ..4O 1,346"S 5 1.183e-O7 2AD~e-11 .2 1 Se-1 0: C3-8 Page :2 DO File; PIB02S.J$M$$ Run Date: Febwary 4 200(-Tiun e 2Q$.0:6P6 i Duration Q0:00:00.. .m_ :& ,Fluencete hfAe ouata EDeosure Robe IM photofns/ IseI ekm'set MeVmlrnksec inF M No~ul" WNW ih Buildups2 YMUWO A BUM~UD TOTALS: 2A30e+00 3.5M 2.840Wi 07 2uei 4.Me-10 C3-9 Mkro~hlcld vS.eO&d(MSO(-QO33M RadIo1gk*1 Services, Inic, Converalioneolca1lufated exposurlne Inlrto dose FILJE; CAMS ATAIPB0OMIDIUS5 Case TWtA; Una 1.21 AF-C Tbis. case was mmn an Satutrday, February 4. 200& at 2:06:156 PM Dose ftint #1I -(133.7B,76i.2A,5.72) cm=21L1410 Remuifs (Sur~ndoe e iser 2.705eeOO8 2,252e,,O07 3.528e-008 2.,940e-007 Photio Fluenoe Rate (flux)Photon Energy Fazenc Rabe Exposure and Dose Rates: CEpqsura Rate in Air Abwrbed Doc Rota in Air in Plbotons/cmvise~ lAeVkzn 2 sec m!. Rft, rn~y/r mrad/hr el 192e-vo1 5AG5e-013 5.405-e-01 11 4.930Q1 0 4-3559-012 4.365e-01O Deep Dose Equivalent Rate o Parallel Geomery" Opposed o Rotational o Isotropic (ICRP 51 -1q87)m;5vIfr If It to 6.1 37e-013 5.28se-01 3 4,72lo-013 4.,945e-01 2 4.267e-1 2 4~ 257*-t112 3. 802"-12 Shallow Dose Equirtont Rate o Parallel GeomreLry o Opposaed o Rotiotill o Is*opic Efiective Dose Equivelnt Raba o Antedoriftsterior Geometry o PostenrnAneferlor o Lateal o Rotational o WIsoropic (ICRP St -1987)mSvlhr to to to 15532e-013 6.290o-013 6.290Oe- 3 5-002e-01 3 5'LZ50e012 5.068e-012 5.068"~1 2 4-029ge-8I2 1CRP 51 -1iB7)rnSv/hr Is 5 526e-013 5.09le-O013 4.0i4e-01 3 4, 5W4e013 4.067e-01 3-4 453e-.l12-4iO1le-012 3.260ewO`12 3 B92e-612 3-26-7e-012 Page I C3-10 Microghield vL0M (60S-D3C2 Radiblogical SeYicss Inc.Page : 1 DOS File ; PBE20404itS5

Run Date: Febuary 4, 200 R Time: 2:1 1tf PM Durion 000000 Fle Ref: tate .......By :-Checktd:-CEa Trt1a Line 1.21 AF-D Deszciption; PBRF Rev Model Co4O Area Factor Calculation GoomreW. 10 -Cylirder Surrac, -Extornal Dtme point Ke46ht Radius x it 13016 411! 6.4 Source Dimensions 7.52 cm cm 1524 cm 5in 5ft0. in Shfalft;.MO-------- --r 1 1 -l0ft GO in 3.0 in z 4572 oaf 1 ft6.0 in.' ..1 N-n .jl s ,i.y ,-! else;:.' Ir."'I 1.vf,.9 I N ;'~dI i I CO-60 source Inpuzt GTOUI1110 Method : AdtLaI Photorn Enorgcs UOM6~-01 1 .2A28~e4000 4,5000e-009 1 .6650e-004 Buildup That material rtalworce is. Cy* Core Inltegrationl Patamtaters Y Direolion (axial Circumloiential 20 20 IJ732 1.325 3.963e-04 2,430e*0, 2,430'0+Q0 Results Fing!B Fluence Rate Exposurie-Rate Excnosre Rate M ie V krn 'M eu ~ h 3.019o-13 6.320e-12 5..830e-18.

1.027e-14 I1.630e-0 1 .489e-0 201 4e-1 1 2,6$1e.10 2030 2.10ge-07 4.638e-.1 1 3.659e-10 C3-11 Pawe 2 Dds Fe B pW2_0404 A$Run Daft February 4, 2006'Run Time 2:11 O9 sPM Durafin .W.00;TOTAL$.ph&eon 4 MNe4m Fluenc Rat PE Dgoe Re , E=sv-Ae £a RRLt w$A Mu 81ev ..ib H2 Me Ul Hn d Wft Ekii 4.344 3.596e07 7.5152el 6.32le10 C3-12 Ulcroghield v9.06 (UU6162)0M04M rfficroftield vSX0S (&O05-OO362) Radiological Sorvicos Inc..Cowverloim of cakcufaWo exp~surm In air to dos*FiILE: C.-IVSSIDATAWMB204041ASS C~a MUM~ LUna 121 AFOD'Thics~ Ca WAS n on $Sluirday, February 4, 2005 at 2:1 1 :0 PM DossPoift iI I-(38&78,152A.45.72)cm Rest~iummed eovsw enerpiesl. Without f BaL.W BWudd 3.396-e-0 2.882e-00,7

4. 3Qfe-008 3;596e-007 Photon Fluence Rate (flux)Photon Energy Fiuence Rate P1hotonalcan 2 1eec Mevkffelsec Exposure and Dose Rates: Expoure Rate In Air bwrbW D eRte in Air Is nahr mGyihr mradlfti 7T5526-01 8.593e-013 6.593e-Otl 6.32le-010 5.51 Be-012 5.SI Be-010 Deep Dose Eq~ivaInf Rato G Paiallel Geometry o opposedI o Rotational o tsoiropir, mlivlhr W, 7.484e-0 13 6.446e.1 S 6,440e.013 5.758"-1 3 6.265e-012 6.394e-0l2 5,94e-01 2 4.SI Be-012 Shallow Duse Equivalent Rate o Parallel Geo"n*L o Opposed o Ratalional o Isotropic (ICRP 51 -187 m-Svlhr'3 7.967e-O 1 1.67fe.O 1$7.671e-OM1 6.10te-013 6.670"-12 6,42e012 6.422e-012 5.105e-012 4!Effective Dcse Equivalent Rate a Anferior/Posterimr Geoms"r a PasteflarAniefior o I-oferal o Rotational o l9olmprWi mngvlhr It 6. 740e-O 13 6.20ge-O 13 4Mf38-0J13 5.59te-O13 4.948e-O 13 564 le-012 4,13De-012 4.670e-012.

JI40e-01 Page I C3-13 FAicroShientd vL5 (9,."282)Radiological Service, Inc.IPar : I MS File PP80304011MS$

.1 iDb: lMarch 4.2006 Run Time: 3:58:06 PM IDurOn '00:000 FHe Ref_Date: Ched_.._..

CaivTI~e. Line 1123 AF-A escrpion: PBRF Rev Model Oo- Ams Fauor Calculatfn Geomet. 10 -ClinderSurface -Exirnal Dose Point x/1=K I y/TI~:Sol HeigfA Radius x 9 1 138.78 cm 4 ft 6.6 in Cyti Core Shield 1 Tvansition ShiWe 3 2 Air Goo W4a1 Clad urce Dimnrsons 3048acm 7.62 cm S PpTnts y 15.24 cm 6.0 in Shields iMaenl 7.82 cmr Cona 8c5 am Irci Ift 3V in 45.7 cm 1 fj.h 1.8 2.4 2.4;00122 7.86 etk Convec, 30.48 am Conmete cIr 0626 m Iron source Input Groupling Method : Atul Phottn Enwrgkis Nudbde cues beuerels &i-Vm' &m',Co-Q , 5W-12 2. -01Q c 5M-QQ 1 QNV-004 Buffdup Tho matarWF r~k ontc is : Cyl. Cor Intgralion Puramrnteri Y Declion (axi1)Ccufetntia 20 20 Reaults.Fluerce Rube FluenceRte E swre Rat Exosure Rate M J phobris mm ef _t_ Rh tin Build=i NfhP w ho BtrfldUo Witlh Bu.VDu 0.6938 3.963e-05 716e-14 t.178e-12 I1 A0e-16 2.275e-15 1.1732 2.430e-01 ft 572e'09 3.02>3i-Q 0.383e-12 64O3te11 1.3325 2.43OeV1 6.724s-09 4.1922e-08 9.31e-12 7.272e-11 C3-14 Page .2 DO$ Fde; PB03w41.M$ Run Data: March 4,20 Run Trag; 3: 5:0s PFM r ftion: 0100:00 En9Wr. ____ Ru~le aFl Fkmnce Rate EXosure Rate 9 phiorsee A*ffkn'lsec Me\dViensec .iihr ND 13~iv W~h Bufdu N INo adiu TOTALS: 4.W-0U1 92e09- T.21508 1.63le.11 EXPosure Raeb.m~ftr With Bdlupu 1.2!68e40 C3-15 MicroShleld v5.5 J5.0"0O62) O6 MWcroShield vS.05 (5.05410:W) RadiodOiCAl $Oi S , InC.Converlon of colculathd expomuro In aVto doso FLEM C:AMS6DATAIPB30434.1.MSS Cato r1t11: UnI 1.23 AF-A This toso w s mnn on Sat~try, Abrch 4, 2OO$ at $M:OS PM Dose Point# 1 -11378tel524S.7)cm Resufls (Summed over enermieO Without BuldrJi Wth DuEdi Photn Fluence Rate (flux)Photn Energy Fkienr& Rato PhotonscmItWs MeVidan 2 sec 7.340e-009 5,723e-006 9.2D5e-009 7.215e-Mg Exosure and Dose Ratos: Epsure Rte in Air AbmrW Dgw Rabe in Air ,i mlW mGcyihr mradibr 1.631e-01 1 1.424"13 1424e-41 I 1.268e-010 1.107e-012 1.7lOe*-010 Doup Dow Equialent Rato o Parallel Geometry o Oppo o Rot3atonal G Isotropic Shallow Dose Equivalent Rates o Parallel Gdomtry 4 Opposed o Rotabonal a lsoerapiS Efeive Dose Equivalent Ralo o AnteriodPoeterior Geomety o Posterior/Anterlor o LWI1l a Rotatbnal n Isoir cp (ICRP 5t -1987)mnvWhr 11 (ICRP S1 -1987)mSvlhr I1 1.617e-013 t.393e-01 3 1,393e0013 1,244e013 1,721013 t.857e-013 t.67C.01 $f.38ie013 1 .256e-M12 1 .082e-12 1,0Ze-012 9.66le-013 1.338e-012 1 .288e-12 1,$e-012 1 .024e-012 (ICRP 6S -1i-7)m~Whr I 1,.45"13 1.34le 13 t.057e-013 12,a08"1 3 1.06e-013 1131e-012 1.042e-012 8.283e-013 9,382e-13 8.301e-013 Page I C3-16 N HcraSliiokd v&DU (9.0640382) Racriological Servirms, Wn.Pop : 1 DO$ File : PS020406 MAS$Run nate:- Fetbuary4,2O0G R Mm: 2;26;44 PM Du'tm:00:00:00 Fit Ref: Date: By: Mucked: C~a TWte: Une 1~.23 AF.B Danscripfion: PBRF Rfev Modele Co-IC Area Factor Caluhcaiator Ga"Ofih: 10 -Cylindeor Sutfioa -ExderrWa Wo~o Poiint sat, Reight Radius x A 1 135.78 cm Aft 6.S in$hie4" I TPansfitkn Shieki 3 Air Gap Wall Glad irco Dimon-ona, 6. cm 7.82 cm Dama Pointa Y 3(148 rm 1 ft.66 cm Iror 2fr 3,0 in 45.7 c I fi 6.011i 7. 85 t 2.4 t 2.4 M.1002 7.86 ett I Concrok-'0.48 cm Concretf A~r.025 cm Ifon source Input Giv Iimg Mefiodt. Actual Photorn Energies Nucihde curies beocquerols, LQCi/cx CQ.00 1.31-MOe911 4 ~655-QWi 4.5000e900 BQA=a I 50,90-094.Buildup The materia reftranca Is; CyL. Core hIn~rnatlon Parameters. Y Ofreclion (axiaI)Citcumfientfiai 20 20 Ene M C.8938 7.W2e-65 1.3325 4.860e-01 N2 UR -a- a NffiWfih Buiiduo i-383e-13 2.2.6le-12 2.670e-116 4.3650-15 S 6S576-09 : 5840e-06 l,225e-111 1.0414.-4 1. lIG-08 8. losee06 .1.91De-ll I A407e-10 C3-17 Page :2 DO$ File, P80204O W$S Run Date: February 4, 2006 Rkin Time; 2 25A$4 PA DutatimN ;. O;QQQ.TOTALS: 9.720e-01 Fluence Rat Fluence Rate EXDOsure Rnte Mevkcntfte?, e imtr-dNouif With Buildup W Buildup 11,787e-8 1.395e-07 3.135e 11 Exposure Rate act With Buildue 2-45o-10_I.r?C3-18 MkmrShleld V5fl5 (SA)5-00362) MicraSh~eld v5.05 (S.OGOO362) Rafdklo~kaJ Seivices Inc.G*O~vmso~n of calculated exposm: In air to doso IFILE: WM5 T~0246-S Caso TWo: Line 1.23 AF-B U4 cse Ch3 vMs rn on Saturday, Februvy 4, 2005 at 2~25:44 PM Doae Point # I -(138.78,304845.7) cm 02M=6 IRolr~ bisummad mm =Photon F~luence Rate (flux)Photon Ero rgy. Ftunce Rate 1.41 1e-008 1.787e-008 1.11O6c4307 I .39,.ev0Q7 Photonskrn t fsec MeVCrmn"Ieg Expos~ure~ and Dose Rob"s: EiposurefRarte in Air Absorbe'd Dose Rati in Air II mnRIhr MGYftir mrad~hr 3.135e-01 I 2,73?e-01 3 2.737"-1 t 2.450e-010 2,1 39e-012 2.139e-010 Deep Dowe Equivalent Rate c Parallel Geomewry O opposed o Rotatiknal o Isotropic Shalv Doise Equivalent RaF a Parael Geometry o Opposed a RotaUional o Isotropi Effective Do Equivalent Rate a AntehiorPosterior Geometry o Posterior/Antenor o Lateral o Rotational o Isotropic Q*CRIP 51 -1 G87)I mSvlhr II 3.108e-01 3 2.676e-01 3 2,675e-01 3 2.39te-013 2A42M-012 2.091le-012 2,09 1e-012 I .M6B-012 (ICRP SI -I 7 mnSvhr I, (ICRP 51 -1 W7)It of 3t$Oe.01 3 S.lB Oft01 3 3.185e-013 2.533e-O1 3 2.796e0"13 2.578e-01 3 2.O50e-01 3 2.32te.-013 2,054."-13 2.66$e.012 2A490-012 2.490e-012 I .979e-012 2.187,v-012 2.0114e-0112 1 .601e-012 I1.814e0112 1 AO5-tO12 Page I C3-19 Mrcwshield vL& (fSU4D35 RadilorZgal Services Inc.Pae :1 VOS file: P820447,M$5 Run Date: February 4, 2006 R ftii: 224-25 PM Duration : &000:0O File Ref_Date: By_C;her$ko;Cue Tide: Um 1.23 AF-C Dscription.: PBRF Rev Model Co O Area Factor Calculdion Grnetry 10 -t lindor Surface -External Dose Point Height Radius# 1 138.78 41t6.S Shield Narn Sz biled I Tranaion: Shield 3 Air Gsp Wall Cwad Source Dimensions 124 =n, 7.62 im Dse Points cm .76.2 cm 6In 2 ft:.O in Shields Diensein Mate 7. V =cm Eonr.es Cr Iroi 5 ft 0.0 in 3-0in 45.7 cm I ft6.0 in WI Density 3T 11.8 7.8.,te 2.4 iAo 2.4 HN0 22 I7.86 i I Conci X4& cm n onur Air.025 cm Iro Source Input Grouping IWhod; Actual Photon Eniergi Nucdide curies uerels swm CoD 3.28&5es1 1 1 .2149e+0D0 4.500e-009 1 ,6654e0"04 Euildup The material iufernce is ; Cyl. Coe ircton Iht ion Parameters .(amil)Circufemterenw, 20 20 R-sults Ffj~ Fhience Rate Expomure Rate Expmure Rate PAWA- m2 Ml'em'Ittse. m mRfAn 1i W With Buidlup enidp Wth Wildup EfGf8 1.4B2e-04 2.608e-13 4.426EF12 5.036e-16 8.545e-15 i.1732 11215e*00 1.$47e"O8 1,1$041e.0 2.407e011 2.11Se10 1.3325 1.2150+O 2.1Z-9 1.&57e-07 3.787a-11 2.B750010 C3-20 Paw :2 DOS Fie: PS020407.MSS @ Run Date: Febmaty 4, 2006 Run TAe: 214:2n PM Duration O:.O:QO Ml tphoton ec TOTALS: 2.430eUO0 Fluencs Rate, Fience Rate EipoMure Raoe Ex00ure Ftt PItmtJ's~e-mmihr 3.N9epO 4u fout W iln 3.5;29"B -;1-"41w1§ 4,M-t0 C3-21 Mbuo~hl4e v3,6S C2) 0204105 02RB-Mfiero~hield v5&05 (O5,85t03M Conversion~ of callcutated exposuro in air to doeo FALE.- C:MSMIDATA1PBO2UN7.1S55 OmaMe Tf, Line 1.23 AF.C This case was ran an Saturday, February 4, 2006 at 224:26 PM Do-se Point# I -{1138.711.76.2A457) cm R=4 (sum , MW Unit 2.252e-WO 2. 84 le-007 Photon Flurenoe Rate (flux)Photon Energy Fluence Rate Photor~nsimsec Meavelosel:

2. 786e-008 3. 529c-0O3 Exposure and Dose Rates: EPosure Rate In Air Abrarbed Dm Rtat in Air il MMdh rroGyihr rnrad/hr 61-194a-O1 1 5.407e-0l13 5,407e-01 1 4.99De-Olo 4.356e.0112

4. 355e-0 10 Deep Dose Equwalent Rate o Parallel Geomnety 0 oppoSed o Rotonal o Isotropic (ICRP 61 -1987)mSvfhr ,.5; 138e-a1 3 5.287e-O013 6.28a7e-013 4,723eU I 3 4,946e.012 4.25ge-012 4.268e-12 3.803e-012 Sh~allow Dose Equivalent Rate o Par~allel Geometry o Opposed o Rotational o 11Sotopic Effectyse Dose Equivalent Rate, o Anterior1Posterior G~eometry O Posteriar/~nlefior o Lateral o Rotational o Isotropic (GCRP 61 1§87)mSvAr I, O1CRP 61 -M7 m~vlhr tv 15534e..013 6.292e-01 3 e 292e-01 3 5..003e-01 3 5. 092e-013 4O05e-O1 3 4.586e-01 3 4,06 e- O1 3 5266"012 5.070L-012 S,070e-012.

4.030e-012 4.454e-012 4,1020e-012 3.281"-12 3.693e-012 3.268e-012 Page I C3-22 lMicrogbield Y5.05 (5-4003,2) ftdioloql ca1 irvkes, Inc Pae :1 DO$ file PEOM 8.M$5 RUrLDate Febrdafy 4, 2006 FZR re: 2:23:0 PIA Durtofn .MOO;N Fku f: BY: Checked__ ._.Case Tile: Line 1.23 AF)DescrtiW: PBRF R1ev Model Co4l Arta Factor Calculation Goamntry. 10 -Cytindr Surface -Extemal Dos Polnt*r_. .-f Height Radius X#1 13878_4ft6.-1 Shield Name W. C~are 1ield 1 Tramsiltcni Sbitld 3 Air Gap Wall C1 Source Dllmewsorks 7112-cm Dose Points-y cm t52.4 ctn 6in 5fl.0 in shelirs Dimension Mate 7.62cm 2 Caroc4 65= > Iro l0ft O. in 3.0n ,,*,* --del eria N 4$.7 cm 1 1t 6.0 n QpnsiW E 1.8 7,86? 2.4 , 24 0.00122 7.80 Concretx 30.48 cm, Concvel Air.025 cm Vron SourCe Input Groupino Method : Actual Phtton Enarjies Uuctide curies becquerels Ccinz c O.56BE-Q1 2420+pO 4.5M.g-MQ Bg1omn 1.0e5WO4 BuiNdup The matial ratetrnce Ia r Cyl. Core ln4sbrtfn paramraete Y Direcfton {axia)Circumferenual 20 20 R U AtIN FILune oRq7 Rhnce Rate EXPosure Ret Expos U&-f-b -a hn- P- c Hf&OnW se ljewfmase mm'- k- mhr-no B5411t) W h 2 13uiiE-%Qd 0.6938 3.93e-04 3-021e-13 5.322e-12 5.832e-16 I.028e-14 1.t732 .43Oet0h 1 31Ce.O 1,49e0? 2.914e-11 2,662e-tO 1,325 2.41f+WQ .674-06 2.111k-07 4.639e-11 IWX0 C3-23 Pato : 2 DOS File: PB020408MS5 Run Date: Fbfutry 4, 2a;Run Tme: 2300 Pm Durabon: 00:0000 Ac FlBi uenw PKe.. Fbioce Rt Esqmuir lRee i d~r 1R m M6*rny!= MeVkmnp/sec mpihr as~hr No h Wih Bgildut NO =ol uD _ M____uR_QTOLT ; 4.8s0e4OO 4.3D5S"08 -59W-07 7,554e-11 m22o-110 C3-24 MkroSbltil Y~O O&OOfl IWicroleS d .K40 6 IE-OM Converamin of cdui ed expain *afr to 40sa FLE. CMIUSSUATA02040LS5 Cas*e Trh LUne 1.Z3 AF-Thih case was rnm an Sahmrd, ftiriwy 4,2 at 2:220 PM Dow Point I 1- (38A71SMA5A.7) can f1"Uh iFuumnzd r *z _O2U48 XMh (luIaduco 2AO53o-O07 3.e59e-DO7 Photon FRoeie Rate (flux)Phhm Emg Fkolxm RaW Photomi,9/s Mav/mftec 4.305e-008 Ekosur eond Dws R$w tosure Rate in AWf Adwba DQw R inir WI Mtr7 nIRYAW mOganu 7.5-4e011 6 $*e 13 6. 41 I.322e0010 5$5190-0122 5.514e-O10 Dow Dos Eqtivalen4 Rs%o Piva1e o Opposed o RoeonJ a 1rorpi (RP 51 -1987 m5S~r nt 7.487e-013 644k-013 6 4-e013 5170-c013 6.27e-012 5,395o-012 5,395e-012 4.619e-12 Shallow Dose Equivatmd Rate o Pwfalw Ceomry o0 Ooosed o Retational o kgomvic (ICRP St -1I87)mSv/hr I 9$e.013 7.674e-013 7.674e-013

e. 1g03i 3 (337,67Ze12 6.423.12 6.423e-Oi 2 5. 1O5*.g1 Z It io Arweiortftsteuy Gemetiy to PostefKodArcemor 0 L-viei*0 P-ropc (MRP 6i -i W)mSrdhr m 6.742et13 6 211eQ13 4.14013 5'5032 013 4.95013 5.843.e- 12 5, 197?01i2 4.131#41.2 4.6790412 4 141.012 page I C3-25 Mrcroftield V6.05 (5.05-00362)

Radiab~ical Sigivites, Inc..Page : 1 DiO$ File : P8020409.LtS5 Run Date: February 4, 2006 R rime; 2:30:29 PM Duration : OG0:00U F&e W-:.Date: By:, ChedW: Case Tide: LUne 1.24 AF.A

Description:

ERPF Rev Model Co4D Area Factor Calculation Gomet 10 -Cylor Surace -External DoSe Point SoL I I-Iebht Radius# 1 134.Olcxam 4 It 5.1 in Shield Ra I Tfansmtin Shield 3 Air Gop Wag Clad irco Dimensimrs 30AB cm 3.81 cm DQm P91fl x 15.24 cm 6.0 in Shields 3801 cm' ConcF.65 cm Ifor I ft z 91.44 cm 3 sf 7.86 ,i 24 B 2.4 0,00122 7-86 id Concrca 10.4a cmConcreh Air.025 cm Iron Source Input Gruping Method :Actual1Phoo Wsir C"U6 3.2835e.012, 1,214ge-001 4.150O~e.0O Bcalerr 1 .$50e-004 RUMlUP.Tho mawteial ruenem toIs ; cyt. Core l ntegration Parametem V Dired~o" Cagat0 CkrwnfecantWa 20 20 Rasults La= uerice Rs _EMpSure Rate Exposure Rate N2 US Bod.0 N BR~iup Wh OU&IdiiIg 0.6938 1.962e-05 1.605(e-14 3.06U.-13 3.099o-17 5.916e-1O 1 1732 1121ft.Q1 9.3$7e.10 0.0m~e-QD 1.O,74e-12 1,w8e I1I C3-26 Page : 2 DOS File PBO2040.LSS I Run Date: February 4, 2006 Run Tme: 239:29 PM Duratm :Q ROOM TOTALS: a 2.430e-O1 Humus Rarte BenlatI E iosure Rfeht-"tlr.Apls mFil r No Buildu= 3eah Slj No Bujdw 2.491e09 2.153e48 4.371e12 Fxstae &It vft Bumup 3,78le-11 C3-27 lMicrohhwiddvvS (6 06-003fi2 Radi11logical Sogvfts. Inc.Convergion of oacutated exposure In a~lrt dos FILE~ Q[SMATANPRU24OMASS CAU' Titi:Une 1.24 AF-A This-casevws gun on $atvday.Fotwry 4,20% at 2:39-29 PM Doso Poknt #I -(134.2715.24,91.4) can Results{Summed oveirenemies) ihol 021040 Photon Fkuence Rate (flux)Photon EneVy Fluenob Rate Phoatonsk1cn&iec MovlcnWeMc 1 .06Se.O00 2-49le-09 I .70ee.-0O 2.1 53o-008 Exposure and Dose Rates: tvotsure Rate in Air Absorbed Dose Rats in Air If#Rlhr rnGyAhir mraovr 4.37 le-0 12 3.816e-014 $416e.-OI2 3.78 le-01 I 3.30!e-013 3.301eU01 1 Dvep Dose Equivlcrnt Rate, o, Parallel Geometry o Opposed o Rcotal~nal o Isotropic Shallow Dose Equivalent Raba o Parallel Geometry-aOpposed* Rchtafnal o ISGotropi Effactive Dose Equivalant Rate o, Arvienorifatstenor Geomeriey o PostenrlorAnterlor o Lalefal o, Rutational o ksotropic (ICRP SI -1987)rnSv/hr (ICRP 51 -'97 rn~vJhr if 4. 332e-0 14 3.731e..014 3.73le-014 3.333e-9I14 4.BI11e-14 4A4%e-014 4.-440e-014 3.~15e-014 3.7488-O013 3.227e-0Ol3 3.227e-0 13 2.882e-01 3 3.ggle-013 3,642e.aI13 3.842e-0-13 1Q54e-01 3 (ICRP 51 -1987)m~vi'hr I'!i 3.90la-014 3.694e-014 2,656e.O14 3.23ge-014 ,gtWe "14 3.375e-0 13 3.1 0§e-01 3 2,47le-013 2.79Xe-013 a 4?770-01 Page I C3-28 Uicro=Shied vL5.005-003&2) RAdi0Iogika1 Svietos 1 Inc..Pae .:1 -D)O8 Fite: PEO2O Rurt Date: Februl R Frwe: 140:6$Durfation; Qi;W.Q 4110.tS5 ity4, 2006 SPM FRe Rf: Dae:_By: Chocked: Case Tide: Une 1.24 AF-B Descr;iP,: PBRF Rev ftadell Co4O Ama FactDr Calculawion IGomatry: 10 -CyUndor Suface -Exernal Dose foirnt Heigt lRadftsu x a1 134.97 4 ft 5.Cyl. Core.$hie& I Transtkn Shield 3 Air Gap Wall Clad Source Dimensions 60.96 cm 3.81 cm D P;Inb y r 30,4o cm Ilin 1ft Shlbeds 3.81 C Cam.66 cm Ir0x 2ft 1.5 in 91,44 Otl 3ft 1.8 7.8$; 2.4 2 2.4 0.00122 7.86*.-.; *.ria1 I dRJr M2aii I ion Source Input Grouplnn M satod : Atual Ph*Wn Energies kiwueelsn LJ;ikn Co & 565fe-012 2.429Ee-001 4.500DD-00 -r nuildup Tho vhat~3tfl ruferuncc: Is; Cyl. Core rcm2 1 .5ft,004 Ilntegtion Parameters Y Diredicon (8ai Cktun*fenbia 20 20 1.1732 1.3325 3.Vt33e-05 2 43Ae-Z.A -01 Rosufts Riuence; LaB E Rat EBuFBsrel Psute Exmura Re Me WheIS I Mevkrfn 2 M s ME 1210 ReJmik1U NohE3;UD BUilUlD With Builft 0145.2160-13 5...46.47 1,142u3-$5 I .81Ee-9 172$-08 3.235e-t2 3.083e- 1 190514E 2,45ft-00 0.. 12M 4.20':4 C3-29 Page : 2 DXS File PB0204O.hlSS Run DaI: Febmry4, 2008 Run T1m: 2 40-59 PM DLurelin :QQ MOW..AL 1!OTAL$: 4.$60,-1 Fim-wgn M lt.e Fluence MaE Expsure fRtka Exposure Rate MevIcmatsec aMeV te _mRhr mer No ftuildug YM Build= wAtid Bull 4.819"9 4,1854e08 8.455e.12 7.34O-1 C3-30 PFge 3 D06 Fle: P02010MSS Jo Ruil Date; FebuAry 4, 2KS Run Tire: 2A40:59 PM: Dun raWon GOODO t x}a.- -._ ---t~4 ,k- 'p -It--4 --?: ,,-, -:I" D .1 i-- .- --, C3-31 MlcroShield vSD53 (5.05-0362) LticroStdeld vS.05 (5.05-00362) Piadm*2111c81 Sorvices, too~.Corioralon of calculated exposujre In air to dose FILE: C.:IUMSDATAIPBO2041 D.MS5 Caso TItlo: Umc 1.24 AF-S This cae was run on SaturdayFebmuary 4, 2OO~ t 2A4D PM Dose Poi~nt#~ I (134.97.31A8.911A4) cmi O04106 RFe-i;1AS ISUMMEd OVKef*Mr : Photon Fluence Rate (fluxi)Phatb Energy Fimnme Rate xWposum and Dose Rae: Exposure Rate in Air Absorbed Dose Rat in Air., Deep Dose Equivalent Rate o Parallef Geometry o O~posew o Rotationat o Isotropic.Photondalcmqwc MOVAC.111sec mR/hr (ICRP 51 -1987)m5Whlr Whodit 3.801 e-000 4,819c-009 8.456e.02 7.38te-014 7,38t"-12 8,379e-14 7.217e-014 7,21 7'e-4 6,447.-O4 3.Mte-CCIS 4.l84-008 7.349ei-Ol1 6.4 16e-0t3 56416e-0I 1 7 285e-01f3 6.272e-013 $,272e-Wt 5&,2M-013 Sfallow DOSe Equivalent Rab o Paiallel Geometry o Opposed 4 RoWlional o hotropic Effective Dose Equivalent R*o Anerior/Posterior Geomety o PostenrJAnterior o Lata1 o Rotational O Isoropic (FCRP 51 -1Q87 mSvlhr'I ii.(ICRP 6i -iw m~vlhr II 8.920"1O4 8.589e-t14 8,58ge-014 6.830"-14 7.546f.O014 6.95 le-014 5.5299-0l14 6.259ge-014 15.WC.914 7.7550-01l3 7.467e-013 7A407e-013 5.gM3 2-13 5155ge-01$ 6.04 1e-01 3 4.S03e-013 S.44Oe.013 44~14-1 ;Pago i C3-32 MIkShieMd vS.05 I5.O-S0D362) MLdlological Services, Inc.Page :1 DO$ File pSWO411M$5 Run Date: February 4. 2006 R Time R24321 PF Duration :0:0000 Fri Ref: By: Chce, Case Tie: Line C4 AFZ Description PFBRF ROV MOlW GaG Area Factor Caiculation Geomtr; 10 -OylindIr Suface -Extemal Dosa Point S I JILl H-eight Radius* 1 134.97 4 ft 5,§Lield Namre Up. L;f Shield 1 Transition Shiek 3 Air Gap VWal Clad Smarce Dkmnnsions 152.4v 3.81 cm Dose Points y cM 7c2 cun , in 2 ft6.0 In hlds Dimension 3.81 cmr -j;.5 cm' Ifrol Cne 30.4a CMl Qo 5 fi 0.0 in 1.5in z 91.44cm i lens1.B 7.8" X 2.4 0.0012 786 I I I Alr.025 cm Iron Source Ihput Groupiin MIthod ; Actual Photon Energies Co.60 bec7eerels u4jcn!13o-0 1.64176-0111 6.07474601 4.50D09 1650e-004 Buildup lho aatorial rafico is : CL. Corto Integraion Parameters Y Diredion (axial)Or. ffntat, 20 20 1.1732 1.3325 91909e-.D5 6.074e-o1 6.074e0 1 Resldts FluerKe-Rate F pRu a E uRt leVkm 2/se ~ Em'e M'L mf No Buildup W0 99Oiu 1O 018e14 i19w4e-12 3.673e-09 3.5me-O 6.&5e4-12 GAZ7l-11 U158o-O0 6.164e-M 1.068e-11 8.9e59-1I C3-33 Page : 2 DO Q8 File: PB020411.MSS Run Date: FPebray4, 200o Run Time: 2:43:21 PM Duration : 00:00.00 TOTALS-: 1.215e+00 uuenstab Fsence Rate Exposure Rate Exmosurm Rt meylaiwsec Mievefe'e ~ ,m No Buid=t s ty Na Buddup With B4Edup 9.831e-0 8.360M6 1.725e-11 1.539e-10 C3-34 DOS w ie P80ZO4, 1tAS IW) Run Dale Februwxy 4,2006 Run Tvme 24311 PM Duriawfl V QMW----------I -.. .r -.-..: I I 1 -,.' 1 ..of ;f .C3-35 Oierahleld v&O53 (SA6392)Mrshield V.6 (9.04,ml)Riodogleall WrA , In.Convereton of caciulod expmure In S1r do cse FILE: C lMS6DATAUMUE 411 JABS Casa T : Line 1.24AF-C Thla case was rm on Saturfay, Februmy4, 4200a 2:43:21 PM4 Dose Point #1 -(1 34J76.L21.44) cm O.24I0 Re= (Summed Emie)Photon Fluence Rate (flux)Photon Enery FMonfc Rat Exposure and Dose Rates: Evosure Rate in Air Absorbed Dose Rate in Air Deep Doee Equivalent Rate o Parallei Geometry 0 OPposed o Rotational o Isolropic Shallow Dose Equivalent Rate o ParaIl Georometry o Rotational o isotlopic UlOJl Photinsicmyiaee MOeV/crrftf WMht Wo OuouiM2 7.702040 6.941e008 9,831e-009 $,.760e-OO mPlhr mradlbr (ICRP 51 -1987)mSv/hr (ICRP Si1 987)mSvlhr....1.725eO1 1 1.506e-103 1506e.V1 1 1.709e13 1 .472e-013 I .472e 013 1.315e-013 1.820e-013 i ,752e-1 3 1 .752e-013 1.393e-O113 1.53geo-10 1.343e-012 1 ,343e-010 1.525e-012 1.31a3e012 1.313e-012 1.173e-012 1.624e-012 1,56se-0h 1.563e-G12 1.243e-012 Effectie Dose Equvalnt Riat o AnteriodPosterior Geomey o Posterior/Anterlor o La1fal o Rotatiofat, o sotropic (ICRP 51 -197)m5Whr..,.., 1 .539",13 1 .418e-013 t 128"13 1.277e-013 1.130"e13 1.373e-012 i.265e-012 1 0O$e-012 1.13go-012 1.o00e-012 PagE? I C3-36 Micr0hield VS.05 (5.5-0036 JRfid hogical Services, Inc.Poge :1 DO$ FMe: PB32O412 1ShS Run Date: Ftbiuvry 4, 200 R rine: 2:4433 PM Duration: 0000:00 File W-:_Date: By, Checked_: Case Titlse Une 124 AFO DESstrion: PBRF Riv Mod§e Co4O Area Faitor Calculaton Gwnetry 10 -Cylinder Swfate -Extamal Dose PRAnt'k :,, -z .-"F- --I nr --* 1 3-1 1X97 Cm 4 fIt .1 in Ghuld Oa=e ;Uy1. 4 M Shield I Shield3 3 Air Gap Wall Glad irue Vbnalnons 04.8 cm 3.81 cm Doe Points y 152.4 cm 5 ft0.0 in Shle1ds iMensic a 3.8,1.cmw

1. 0.BS cm Iro 10 ft 0.0 in 1-5 in 9144cm 3 ft M1 Densit ft 7.86 reIe 2A4 rete 2.4 r 0.0022 n 7.86 IOAS cm Caona Ali.025 m Iru Nuclde C"0 Soume Input Grouping Meffth -. A:tual Photzn EnebE" curies jbA 3.2835o-01t 1.2149o+000 4.500We-009 1.61BOe-004 Buildup The material reference is -Cyll Come Integrmion Paramnotsr Y Di-re Cf(axial)Cirifemnlhia 20 20 1-1732 1-332S 1 $81e.04 1.215e100 1.216"00 Results EFwne n F kfnefe Rste Fxnmn atme Rt Fxnrmure.

Rat.p MeVdcmlsec M aga 01M A=N Pullduo Wh BA He Puiug Wfth Builup 7.18e-14 1.483e-12 1.3 -16 2.863e-15 4,612e-09 4.692e-03 8.242e- 12 8.384e-11 7.820*-0M 6.818e-08 1 35f-11 1.183e-10 C3-37 Page :2 DOS Fle: PBO2041I2.SS u Run Dsat: Fobrary4,2006 Run Tine; 2:44:33 PM Duratbn :Oo:OQ:-0 Mu Fluence Rate Fluence Rate Exposure RAte Exwsure Rate chotons Mlevtcnec i m e Wmynr No BuIld2 O -Wj1 Buildu N I lo FkdaM WiO 1eUP TOTALS; 2A430e+00 1,244eW 1,15fe-07 2.482e11 2.021e,40 C3-38 MleroShield vS..06 15O.-OO362) LiciroS1hield AM (&U-OOM4)Radio"!-c-Al 8orcees, Inc FILE: CIMSSIDATAMPBO2O412.MS COts TMfE: Uno 1¶24 AF-D This case was rnm on Saturday, Feb~ruary 4, 2008 et 2!44:3S PM Doze Point I 1 -1134.97 152AS1A4) cm 02O410S ResuIts (Summed over eneagieoe Photon Fluence Rate (flux)Photon Energy Fkmance Rate Exposure sid Dose Rates: Exposure Rate in Air Absorbed Dose Rate in Air ,.Without Buildupg Wfth Pholcns~crrifte* MeV/cmwlaec S. 6O5e-009 9Il1 1e-008.1-244e-Q0ft 1.161e-007 mRhr rnGyfti avadthr 2.182e-011I 1.905e-011 1 9Ose-O11 2.021"-10 I .765L-012 I ,7$e-010 Deep Dose Equivalent Rate a Parallel Geomnetry o Opposed o Rotatonal o Isotropic Stallow Dose Equivalent Rato o Parallel Geometry o Oposed o Rotationat o korlpic Q1CRP SI -1q87)m~vlhr'I'I 2103e-013 1 .8f1e-01 3 1.863e-013 1,554e~1 2.302,e-013 2-21'7e-013 2.217e-013 1.76313-013 2,004"-12 1 .725e-012 I .725e-01 2 t .541 e.i12 2.1 33e-0 12 2.064e-O012 2.054e-012 1 .633e-0112 (ICRP 51 -1987)mr.v/hr It Effetve Dose Equivalent Rate o Antefiort'sterior Geoetry o PostedorfAnteflor o Lateral o Rotational o Isotropic (ICRP St -1987)mSvlhr p.I#11 948e.01 3 1 794e-013 1 A27s-01 3 tGI161-013 1 A$,Ie-Q~A! 1 .804"-12 t,662e-012 t.32le-012 I .496e12341 1,734-012 Page 1 C3-39 MicroShield v5IOS (USMOO362) Radiological Services, Inc.NW Pegg : 1 DO$ Fle:t PBO20413 IMSS Run Dab:. Fobruary4, 2006.R Tkhe: 2820 PM Duration ; Q;Q.QQQQ File Ref:__ __Date,____By:_Ohegkud;cab ruTbe: uL 1,641 AF-A

Description:

PBRF Rev Model Co60 Area Factor Calcuaiofu GeomB#ry. 10 -Cylinder Surface -External Dow5 Point SOtj Height Radiuts x:N1 4132 an 4 ft 7.6 ini Shield Nanie, D Cyl COre -,I-Shield I Tiansibton $1h1eWc3 Air Gap Wall Clad irce fntenslons 30.48 cm 10.116Cm DoEss Pohits Y 1524 cm 8.0 in ShiIelds imension Mtet D.1 CT Conel 65 Cm Iror i ft 4,9 In z 3fIt I Densit 0 1.B5 2 14 0.00122 7.86 ia1 71t concrOt OMA cm Congoi Air.025 cm iron Source Input Gsouplag, Method : Actual Photon Energies Nuclide curies _ cikm 2 ____CO-60 8.735590e012 3.2397a-0G1 4.50W04M8O 1.6650e-004 Buildup The mnate~bI ak rernce is : Cyi. Core Integration Purrnveterm Y Direction (axial)CkdUrnforenIdat 20-20 Rasults EMNwv ___ leneBg Emosgre Rao Exyp[ul; E22 &ILE.v yhaotnshse Wftrmntee Uefcd rnR/r mPftkr No Buildu Wt Bu~i2u NO WiBo Wit SWI 0.f6938' 5.285e-05 2A406e-14 4.7080-13; 4.64,5e-17 Q.090e-16 1.1 72 3-240e-01 -1 AS"-O 1 440e0 2,807e-12 2.573e-1ii 1.3325 3,240e-01 2.A5le-09 2.080e-0 4.5k-12 3.$09.1I C3-40 Page -2 DOS Fibe: PB020413.AS5 Run Date: Februaty 4, 200J Run Tine: 2:58:20 PMA Duratbn :. 00:00* Ah& Foeps te* Fluen Exam= uB&k Ex-posurek kp- pbotansatu merec .mRw No itL up Wt.l No fitu S tiwuo TOTALSi; 6.46Oe-01 3 G910e09 3.520e.08 6.M0-12 6.162e-11 C3-41 Microghleld V9L9 (164MA Radi~olb cal Sorvica, Inc.Corwefsjoft Of c~lculatoo expos~ott In air to dasa FILEi- C.-MSMATAIPB&204IMISIS C230 TItUMILline 1.641 AF-A This cas was run an Sau fa~ebruify 4,2+/-008 0 2!68:20 PM Dose Polnt# I. -(141.32,15.24AO1A4) cm 02A041 ,E22fti fSummed ove~eir-ema UnitI Without With Bu§idup Photon Fluence Rate (flux)Photon Energy Fluence Rate Phto~nalkm'sae 1MOVIW/~Saf 3.083e-000 3-910Ge-O0Q 2.78ge-OO8 3.=2e-008 Empsura and Dose Ratos: EVosure Rate in Air Absorbed Dose Rate in Air II.'wPJhr mGyMr mraoft&660"-12 5.90ge-01 4 S0898e412& 182" 11 5.397e-01 3$59e-01 11 Dep Dose EQuivaalent Rate o Parallel Geometry o Opposed o Rotatrinal a lsoIropsir Shallow Dose Equiv.at Rate o Parallel Geometry o Opposad o Rotational o ksotropic (ICRP &1 -187 mSvlhr BP (ICRP 51 -1987)m~vlhr II'I of 67 99".1 4 5. 56"-O14 S. M5e-O1 4 5.231 0-014 T2376.0114 6.908e-014 e.968e.0114

5. 542"-14.6I5.Q12,Be03 5.276e-0113 6&276"1O3 4713e.013 6,524e-O1 3 6.281le-013 6,281e-O13 4 .994e-013 Eifedvce Dos Equiva1#nt Rob~e o Ante ioro~oterior Geomnetty io Posterioc/Anterior o La1efal o Rotational olsotroic (ICRP Si -10B7)m~v/hr ml 6.122e014 5,640e-014 4.486e-014 5.079e-01 4 4.49$".1 4 5.082t-01 3 4.04 la-0113 4.976e-0113 Page I C3-42 Micn)Sh~ield YvS.0 (SAOS0362)

Pe~e :1Radio4Logal Services, Inc.DO~$ File ;PB0,20414.MSS Run IDate: February 4, 2006 R Tsn,3-00:06PA Dutratioin

00 00:00 File Ref: Date: By:____Checked:____

Case fl~e, Line i.441I AF-S Destiptioni., PlBRE Flav Model Co-G0 Ara Factor Callculatiou 2*owmnlty~11O ~C)Iidcr Sirfatc -Extomzal Dos* Point* Height Radius Source Dimensions I609.91 cm 10. 15cm Doze Points# 1 141.32 cm 30A48cm 4fi7.6ir 1 t J I I I , , --, I I i 2 ft z 191 .44 cmn 3 It 7.86 La 2.4 oi 2A4 P.00 122 7.W8_ hields Shield Name Cyl. Core Shield 1 Tramsiion Shield 3 Air GP Wall Clad I)inwDmsio Materis 1Q.$6cm9 Conoret,.65 cm Iron Corwcel 30.48 cmr Concret Air.025 cmn Iron Nc-do Source Input Gruspng Mathod: Actual Photon Enatgks 1.7512e-011 6.47944001 4.5000e-009 1 .6650e-004 RdIldup Tho enaterial ref eronco is : Cyll Cane.btegration Pwairnsters; Y Direction (AxWa1 20 Circumferential 20 Enerpy 0.693B 1.1732 1.3325 photonase L1.057e-0'4 6.47ge-O1 Site=Rata Fkluence, Rate ExoaoureRe ExmsRate M 13&uo NQ PuildWitWith SLA~j 4.615ie-14 9.0850-13 8.9100-IT 1.754e-15 20 7- 9 2.795e-S 6.035e- 12 4.94e411 4.742e-09 4.043c-00 8.228C-12 7.014e-l11 C3-43 Page :2 DOS Ffe Pi0414'4.t$5 Run Date: Febuamry 4,2006 run Roe: 3:00.-O PMA Duratin :O:00000:r Fluenc Rate MFlunce Fae Ex2tfsire Rate Eosure Mg M photanstsec k-tvm4 kmevfv'ee MnRhr lNo Builchr) Vmeuwdyi No Btisu0 15W Buildup TDOTALS; 14290+90 7.550e-09 6.6350- 4B1.326o-l1 142ole-10 C3-44 M-cmshleld v6.6 O5 .5-OO362)Mitronhield v5DSM I5O-O362)Radiotogical Servim, Iunc, ConvceIon of catcuIoted exposwe In idr to glase FILE: CNASMiATAUPB020414.1M1SS Case Mr.c Line 1.641 AF4B Wbk CA*s wss. fun on Satuday, Fobrwary 4, M$ a 3:0O0:06 PM Dose Pcidt #I 1- 141.32 2 DA11tOl 44) cm 02AG405 7.560"0O9 5.4 16e-QO$6M38e4)DB Photon Fluenoe Rate (flux)Photon Energy Fkmnce Rate Photonakim'Isee Exposure and Dose Rates: Exposure Rate in Air Absorbed Dose Rits in Air II mR~th mGy~ir mrad~hr 1 .326e-01 I 1. I5Me-01 1 1.201le-010 I .Q4e-012 11-M48-01O Deep Dose Equivalent Rate o Parallel Geometry o Coosed o Rotatonal a Isotropic Shallow Dose Equivalent Rate ui Parallef Geometry o Opposed o RMational oI Wfpia (ICRP 51 -1987)m-Svlhr of 1.314c-013 I. 132e.-013 1, 1 32"1 3 1.01 I e-0113 1.399e-013 I1.347e.OI3 1,347"-13 1.07le-013 1.19OeN012 1 .025e-012 I.fl2e-012 9, 1 54-01 3 1 .267e-012 1 .220e,012 1 .220e-012 9.700e-01 3 Vfaed~a Dose Equivalent Rate o AnteriortPosterior Geometry o Postenor/Anterior.o Lalefal ci Rotalfonat o Isotropic m~vlhr ff 1, 154"'I 3 1.090e-013 8.674e-014 9.810e~014 U e9114 1.072e-012 9 872e.013 7.848e-013 8A80e-013 T665e-013 Page 1 C3-45 MicraShield vY5(1 (5M-00362) Radlologlal Sorvion, ln Page : 1 DOS Fil: PBO20415.MS5 Run Dat: Februay 4. 2006 R 'rme: 3:012;3PM Duation 00I0O File Ref: Dae__By: Checked, Case Ifriw Unea 1S41 AF-C IDeawiptiow. PBRF Rev Mlodl Co-SO Arma Factor Calculaon Geometry: 10 -Cylrtftr Surface -External Dose Paint UfI Haight 1 Radius# 1 141.32 cm 4 ft 7.61i!Sield Nai Q Cyl.Coro Shietd I Tran5i;on$hief 3 3 Air Gap Well Clad irce Dimensions 1524 cm 10.15 =DmQ Point p6.2 cro 2 ft0.0 in Sields;invnsnion, Mgt3 O.16 Icm, -Cnc.65 cm lIro ft0.0 in 4.0 in z 91.44 cn 3 ft Rte 1.B 1 7.86 ete 2.4 Dte 2.1 O.O122 7.86 r I i Concn 34.0 cm CoW Air.025 cm Iron SoUrCe Input Groupine Method : Mtual Photon Energies Cudide beo[uerels y71ae'h 4.O CO-60 4.37800-Ul 1 1.6198e+OD 4.50e-009 1 .66S0e-004 UNldUP The matarbil reference Is Cyl. COe[ntegration Pammeters Y Direton (A-ha[)Circunmewtial 20 20 Enerav 0,693a 1.1732 1.3325 Rhotongfee 2.-642e.4 1.620e*tOO Resufts F]uence. IRat Fkjenoe Roe F =S re &.e Exposureb RXt W4,/Ovcm&rs aw- i t3Xe ml;t NO Rui~ldu Wh QUkw No Builduo Wdth R;IduW 68 99f-14 1.8228-12 1i.737e-16 3.529e-15-7f23e-09 SA.07e-0 1,19e-11 1.A O1 9ffE2e-O 8.463o-0 1 .8Oe-I 1 1 .46%g-10 e73-46 Pago :2 DOS File: PBO20415.tSS Run W: February4. 2006 Run raw: 3:01 :23 PA Duration : 00:00:00 e--o ph TOTALS: 3.240e400 Fluenp ae F-luexc R& I =me meVtownsec MeVhmtlffct mR/hr 1.D. wth &A up Ng Md 1.5361 1,427&7 2.699-11 Ex~m ab 2Imth Bidup 2.506e-10 C3-47 1icroShield v5.05 (iS.060362) 02AMS UicroShleld v9.MO (SA.60392), Radidolaglcl 5endic, Inc.0o"Verstof Clculated exposwe In aIr t* 4ose FIL: C AMSSMATAWBUM4SMISS Case Title; Line t.1541 AF-C Ths case was Mn on Saturday, Febru y 4, 2006 at 1011:2 PM Ooa^ Polnt # 1, 141.32t.72,9S.,) cin Rpvk (tSurnmed over enemi UnsWtout SuB3Wp Wit BQuidj Photon Fluenoe Rate (flux)Photon Enary F'luence Rate Photonsfan 2 ksec Mevkniset 1.213e-0WB 1.30-07 1;53&0-D08 1.427e"07 Epoure and Dose Rates: ,ure Rate in Air Absorbed Dose Rate in Air II mR/hr mGylhr mr.~hf 2.6Q9e-D1 1 2.36e-.013 2, 35f-t1 1 2.0Be-010 2.188e-012

2. 180"10 DeMp Doe Euivaleot Rate o Parallel Geometry o Opposed o Rotational o Istropic:hallow Dose Equivalent Rate o Pamilet Geometry o Opposed o Rotional o IsoAorpic Effev Dose Equivaeint Rate o AnterioPasteior Geoetxy o PosteriorrAnterlor o Latel o Rotaiional o Isotropic (ICRP 51 -1987),nm~hr (ICRP 51 -1987)nirnSvlhr f.(ICRP 6t -187)mSvYhr'I 2.675-o 1;3 2.314e-f13 2.304e-01 3 2.05o-ItJ3 2.847"-O1 2.42e-013 1184e-013 2,40 013 2.21 9" 13 1.76e-013 1I.9§8e.1 3 1,09813 2.484e-O12

2. 13e-012 2.139,e-012 1.910ei-012 2.644e-012 2.5We-012 2.546e-012 2.024e"12 2.237e-012 2.060e-012.ue-012 1.865e.012

,410-M12 Page 1 C3-48 MicroShield. V5.05 fSJ6-0362J Rafi~ologlicall SenrvceS 1 Inc..Page :1I DO$ File.- P1B020416.IVISS Run Daft: Febtuary 4.2006 R' Tkw :302:23 Ph Dufaffon 0000-00 Fie Ref: Dare: _By: Chocked: Case Thitl: LUne 1.S41 AF-fi

Description:

PBRF Rev Model Co-O AMeA Factor Cac~llatarkn Goothaty: 10 .CylInder Swftce -Extarnal DMOs Point a0 Height Rajdius# 1 141.32 4 It 7, Source Dimension~s Z04.8 rn Dose Points I cm 152.4 cm~6lIn 5 ft 0.mi Shields 10.16 cWu Conci.!ff cm rrnO N~I, A1 10ft 0-0 in 4.0 in OfA4 cm 31t efde. 1.8 ete 2.4 ete 2.4 Q.&0122 m 7., I 711-S hia-id Nani C l. Core Tr.ansition Shield 3 Air ~Op Wall Clad Cowc 30.A8 cm Cow,~Air.025 cm lroq Grouping Method ; Actual Photon Energies.CO-60 8 7M9-D11 3,2397c+000 4.5000c-009 1AM~O-004 Buidup The materal reforenca Is. Cyl. Coro Intoration Parameters Y Direction (aXial)Cicumferential 20 20 7 .6938 V 1732 t13325 ohotonaftec 5.285e-04 3.2400+01) 3.240eO00 IResults FlineRt uence Rate .fouR Rt Exoosure Rate fAeVkm~ispei'c==M-B No Buildwuo Bguif No Buildwi With Buildup 1.0740-3 2.262e&12 .2. 0 fe- 16 4.350e-15 7.136e-09 7.53se-O8 1.276e-,11 1.347e-1O 1.22se-O8 1.111 leZ 2128e-1 1 1.92ge-10 C3-49 Page :2 DOS File; P02041-M.S5) Run Date: February 4,2006 Run Time 3D2:23 PM Duralm .QQ;Qg;Q TOTAL: 6,480e+O0 Flnce 1%Rate 1 os 1 No Builduw Ab.h R"MutL 1.940-OB 1,865.e07 Exposure Fog mR/hr 3.403e-1 1 Wh Bii7uO 3.275610 C3-50 clraShleld v5~S,. (5D5-00362).0140 02AMIG fficro~hleld vZ.05 t5AOSM362) ConwcrsUon of calcirlatccty wxpour In air to dciso ILE: CS5AMMATAIPO20416M5S This ca-se w= run on Saturday, fabruary 4, 200 ut 1~Q2:2$ PHM Dos-ePohnti I- tI41M,2I5AS1A4) cm ffZd oer o~i3s)unkWithoiut With BUWTduO Photon Flunce Rate (flux)Photon Energy Fluenoc Rate Exposure and: Dose Rates: Evosure FRe* In Air Absorbed Dose Rate in Air., Ptbotnstmklsec MeVknifsec I 6geOU 1 .940e-008 I A770-007 I .665e0-007 mRflw mGy/hr mradthr 3.403"-1 I 2.07 e-01 3 2,971 "-0 I 3.275e-010 2.8.Sge-012 2 659e-010 Deep Dose Equhialonl Rati o Parallel Geometry 0 Opposed o Rotational o lsotropic Shallow Dow EquivalarA Rato o Parallel Geometry C. Motoal o Isotropic Effed&ve Dose Equivalernt Rat o AnleroriPoserior Geometry o PosweriorlAnlerior o Latetal o Rotational o Isotropic'I 3.372"-1 3 2.905e-01 3 2.900e-01 3 2.695e..O1 3 3.246e-012 2.795e0.012 2.7VSe.012 2.4970e012 ..(ICRP 51 -1987)4'(ICRP 51 -1987)mSvlr'i.4$.$$Oe-01 3 3.457e-01 3 3.4E57e-01 3 2.749-01 3 3.037'e-01 3 2.78501 3 2.226"-1 3 2,519e-013 2.230e-01 3$A46e.012 3.327e-012 3.327e-(Q12 2.645o-012 2 .92.3e-012 2.692e-0112 2.141e-12 2A424e-%~012 2.1459-012 Page I C3-51 Final Status Survey Plan for the Plum Brook Reactor Facility Attachment D Illustrations of Survey Area Classification NAS GLENN RESEARCH CENTER ho =1 1 PLUM BROOK STATIONl i CLASS 1 9 l CLASS 2 tv _ CLASS 3 c1_.g IF REACTOR BUILDING BUILDING No. 1111 Kiev. Roef ClO NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO C2 cm l-14 im Q C/E;cBL REACTOR BUILDING BUILDING No. 1111 aev. Mezznin MA" GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO z 1 170 CZ;N- 2 Q'illz q-"I X tz 64 C Uc Mo To m a+.11 I IICLASS 1_ CLASS 2_ CLASS 3 REACTOR BUILDING BUILDING No. 1111 Elev. 0-0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO to;k;of m;I, 12.PI To P-1 C n?z c: GM 4:1 2 3 REACTOR BUILDING BUILDING No. 111 Rev. -1 5W4 0W' 3? 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 0 0 o>D a ofl D"I rS t=e!n Ed z m n m CF.a: REACTOR BUILDING BUILDING No. 1111 Eldev. -WS FS.Cicf 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO~w+/-I S 0 0 0 z>0 Dt Z ON tv D~Io M at (A r-_=tAREA 30 1111p A;ii ,, --, ..- ' N N= CLASS_ CLASS i Cl ASS 2 A 29 J/.1 REACTOR BUILDING BUILDING No. 1111 Sub-Pile:7 o~FS 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO St Z>D a z D~1z 2_C-)II r-:1-4 I 0 E-.to c 0 CL 5;1o Eo E.gr=I ICLASS 1_CLASS 2_ CLASS 3 D L HOT LABORATORY BUILDING No. 1112 Elev. Roof cIC 0 00 1 .0 tl 0 g (o W 0+-L." NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO U........... -_ ,.i.f ..-=I CLASS 1_ CLASS 2_ CLASS .NOT LABORATORY BUILDING No. 1112 BWv. +114r NASA GLENN RESEARCH CENTER PLUM BROOK STATION _SANDUSKY, OHIO-t "m= L' .R _ _ 1 -C---=C I-F-I IIL 3f~ _f~ma.3_ __ __ __ __ __ ________=== ___ __ _ __ _ _ _ _ HO AR T R fts rz-Wl o- L -X I r nLm .HOT LABORATORY BUILDING N. 1112 Mewv. LASS 1 LASS 2 LASS 3 Cl% 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO i K -IL+1 X 0l 0~0 t 4-4 lz r.0.CLl 0 1 0"-I~1@z r-m CLASS_ CLASS_ CLASS , ..._B 11 11 VWd 110.l 'jI 1 2 3 HOT LABORATORY BUILDING No. 1112 Elv. -34'Cca 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 1-t 32 9 fl co PI it Us_.zo J CLASS 1=CLASS 2_CLASS 3 HOT LABORATORY BUILDING No. 1112 Elev. S -t Cre-7z 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIOJi m J7I in: KLL N t 0 0 0>D~o t z"I t1i Ll-.i_.3 3 Tor~o 1 2 3 REACTOR SERVICE EQUIPMENT BUILDING BUILDING No. 1131 Elev. Reof 021-NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO_2.tD 4.Cn M C.-5 to;3 b, Q rl%zI 2.Z'Open mets-- treads, pl hi 0=0 tl constructure grating for stair ate covering bottom of runner.= IICLASS 1_ CLASS 2_CLASS 3 H SHOP &EQUIPMENT-,--i i_I.REACTOR SERVICE EQUIPMENT BUILDINO BUILDING No. 1131 MEZZANINE FLOOR ADDITION NASA GLENN RESEARCH CENTER 1- S PLUM BROOK STATION lSANDUSKY, OHIO ETICLASS 1 M CLASS 2 S CLASS 3.._!_C I- --Fm v ~STORAGIE REACTOR SERVICE EQUIPMENT BUILDING BUILDING No. 1131 MEZZANINE FLOOR o , .c. I NASA GLENN RESEARCH CENTER PLUM BFROOK STATION =Jl SANDUSKY, OHIO t .W 9-IZ C,, 0~REACOR -RVIC E-UIP-ENT BUILDING BUILDING No. 1131 FIRST FLOOR 0 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO I r'4.J-j-3-~0Z l L"I e.5--m.1 _ICLASS_ CLASS_ CLASS 1 2 3._I-unww I_n Li m- -- --_ -ri ll REACTOR SERVICE EQUIPMENT BUILDING BUILDING No. 1131 BASEMENT & FOUNDATION FLOOR 02 NASA GLENN RESEARCH CENTER PWLM BROOK STATION SANDUSKY, OHIO EII'CLASS 1=CLASS 2 ICLASS 3 0 rl 0 0 to z o~mD:1 Zq oj AID-.0 0 0 FAN HOUSE BUILDING No. 1132 Ebev. Roeo cCcp 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO In 0I 00 a 0 To me mo I(Z m ED A.-if RU No-=.-AIRWAY=iICLASS 1_ CLASS 2_CLASS 3 OPERATUno RA-ri ---7 I__Di+ + -+ MIA t ,+/-Uin MA No. 4 -I r -A IIIi-- ..... ".-PIPEt ARECH v-= RESIN Pin T i__l g PAN HOUSE BUILDING No. 1132 Meo. 0am Cz- .0 NASA GLENN RESEARCH CENTER PWLM BROOK STATION SANDUSKY, OHIO.. ,, .- --_- _ ---- -- -- ... ...--.....T.. .:: :v.: :: ... .:: -.. :, --, .1 :- .I It :: I : X ..I I: I 'll : : :-1 I : ::: : I I :: : : : ::::..-. I .-- ..-.... ... I. .... .i LE ..4 In~c 0s: w g.+AIRWAY!IY;, I TWOA AAA=IIZCLASS 1_ CLASS 2_ CLASS 3 V X X r 6 I -_ i 0_swrmnT am "a.NM , b S_.]Z3 El a2 aump IUN..?FAN HOUSE BUILDING No. 1132 mev. -12w4 clkZ-NASA GLENN RESEARCH CENTER PLUM UROOK STATION SANDUSKY, OHIO 0 m 0 0 bo CZ 2 z'71 ti.0 cj I 0:0=I ICLASS 1_ CLASS 2_CLASS 3 ,. , ..WASTE HANDLING BUILDING BUILDING No. 1133 Elev. Roof 0:;o C2-?c ) NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSIKY, OHIO rl to (Z A->'=II CLASS 1_CLASS 2_CLASS 3.+0 0 to AD.a: WASTE HANDLING BUILDING BUILDING No. 1133 wEev. a f't0 C-2~ NKAA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 1XK N v E 0r 0%tz 0=I CLASS_CLASS MCLASS 2 3 tz, tb t" 1 4 w rA at, fb z w 010 0 4".CL I0 0m 0 E0 04, 0~WASTE HANDLING BUILDING BUILDING No. 1133 ElWv. a 0-0I m fo C(3j 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 0 0 o 2 on"I, t t4 X" iv_.r-It_.rp A nd ra7-i -'-S---a../ v ' , ">ftya , X + .. .:: : a. m THE ...l4=I ICLASS 1_ CLASS 2_ CLASS 3 EVAPORATOR m 4A A lsTME*4,umw" i I ,4 pm-I*_ Eu'W? t mW *=i ,,'. , -_4 )i WASTE HANDLING BUILDING BUILDING No. 1133 El-v. Q -1 3'C3b-Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO N w+E S (' --i)II.= CLASS 1= CLASS 2_ CLASS 3 PRIMARY PUMP HOUSE BUILDING No. 1134 Wev. Roof Figure D-24 -Primary Pump House Roof Elevation D-24 C2'3 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO PRIMARY PUMP HOUSE BUILDING No. 1134 Elv. +T-W Figure D-25 -Primary Pump House +7'-3" Elevation D-25 I C -3 Cat D-25 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO PRIMARY PUMP HOUSE BUILDING No. 1134 Elev. 0'-Figure D-26 -Primary Pump House 0'-0" Elevation D-26 I C--3,5;7 -, Plum Brook Reactor Facility Final Status Survey Plan Revision 0 NMA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO Rie n PRIMARY PUMP HOUSE BUILDING No. 1134 Elev. -4r Figure D-27 -Primary Pump House -4'-O" Elevation D-27= C3& &I 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION M SANDUSKY, OHIO t tol AD ,TI r0 0'1 c 00 I-0 To ft 0 0 I I a a+IU 0 0 0 0 0 0 I CLASS 1 MCLASS 2_CLASS 3 z z 0 o 0>t 0 0 0 W 0 0 0 0 0 e e0 0 0 a 0 0 OFFICE AND LADORATORY BUILDING BUILDING No. 1141 Elev. Root:X.cn FS,:1 as C-3J NASA GLENN RESEARCH CENTER PLUM BROOK STATION t IFI 1 *9 SANDUSKY, OHIO e am CCLASS 1~ 0 CLASS 2 MCLASS 3 4" 0 0::_I, .S t 3e I @. 0 0 L ws e CLS G _ _ .OFF e _ wI J IJ w OFFICE AND LABORATORY BUILDING BUILDING No. 1141+15' 0 ELEVATION PLAN I NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 0'- w Vg W WCLASS 1= CLASS 2 0 11 =CLASS 3 0 00 00 C O _0 _0 0 _0 s 0 0 blCE c.10lB111 0) 0D 6)0O@ 0 00 0 0 0 0 OFFICE AD LABORATORY BIMLDINO BUILDING No. 1141 W 0' ELEVATION PLAN 0 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 0 W.4 9 5 9 0-I 3 CL 0.co IlI CLASS 1_ CLASS 2_ CLASS 3 ci cl AAN ,.4 ci V 0 2- tW Io 1z z_cn:;: 0 0 I >: _.I ..-.1NIl.-:., < _r 4 P L'.... i;~ )0 D 0D 0 0 0 ~0 0 0 d 0 0 0 OFFICE AND LABORATORY BUILDING BUILDING No. 1141-15 0 ELEVATION PLAN NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 1- 5XI I -W w J.-11+s*>= I CLASS 1 M CLASS 2-' ' ' CLASS 3-, i- 'HO RETENTION-TANKS I c - -=i HOT RETENTION TANKS BUILDING No. 1155 KElv. , H/uA Drook Reactor Facility Final Stats Suwey Plan Revision 0 SMUMaCHCU PM M WrATA MUSn,e000 Cats r 'los Figure D-33 -PBRF Environmental Areas D-33 I}}