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)

Text

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

MISSION AND SAFETY 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 FinalStatus 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,.... .....................................................................................................

• B-1 2.0 References.................. ..................................................................................................... B-1 3.0 DCGL Approach....... ..................................................................................................... B-2 4.0 DCGL Methodology B-3 V

Plum Brook Reactor Facility FinalStatus 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.B-25 6.0Area Factors,,,,,,,,,,.,,,,,,,,,,,,,,,,,,,...,,,,,,,,

, ,,. 2 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 4.0...............Piping..Versus Embedded Piping Versus Buried .. Piping..C-3 Buried ................................................ ,..................,......C-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 Illustrationsof 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 FinalStatus 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.

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Plum Brook Reactor Facility FinalStatus 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.

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Plum Brook ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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 FinalStatus 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.

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0 0 0 Plum Brook Reactor Facility FinalStatus Surveyi Plan Revision 0 Figure A-1 Part 61 Smear Populations Sample Locations A-6 oO/

Plum Brook ReactorFacility FinalStatus 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.

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Plum Brook ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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.

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Plum Brook ReactorFacility FinalStatus 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

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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 A~k.2.

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Plum Brook Reactor Facility FinalStamus 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

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0 Plum Brook Reactor Faciliti' FinalStatus 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 ReactorFacilitv FinalStatus 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 ReactorFacility FinalStatus 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.

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Plum Brook Reactor Facilitv FinalStatus 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 FinalStatus Survev Plan Revision 0 Figure A-9 Surface Soil Population Sample Locations - ERB NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO I J.

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NX 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 FinalStatus 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.

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Plum Brook ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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 FinalStatus 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 ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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 FinalStatus 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 ReactorFacility FinalStatus 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 Cell Equipment#1 Smaer lit C.l Equipment 42 SrM Hot Cr1lEquipment 63 Smear a Hot (Cl/ilter) (pCU/ilter) 0 (pci/flter)

Results IDA Used Distriuion, Resuls tWDA Used Disttibuton Reuls tlDA Used Dkstribullon 8.83E4t 1.35E+02 0.11%

~iio Arn-24t 7.27E+03 9.25E202 8.0E8W 1.37E+03 7.27E+03 1.37E403 0.15%

0.03%

3.0DE+02 5.05E41 1.242E02 8.12E+01 3.10E+02 124E+02 0.07%

0.03%

1.35E+02 2.40E+02 6.21E401 240E+02 0.20%

C-44 2.4E240 0.02%

O.OOE200 1.2DE+02 12DE+02 0.00% 0.00E400 8.2eE+01 62E+t01 0.01% 0.00E400 2.94E+01 Co47 1.27E+01 2.87E+03 2.20%

2.74E+05 1.24E+02 2.74E+05 5.73% 8.J4E+03 2.25E401 8.84E+03 1.94% 2.87E403 Co40 2A47E41 2.47E41 O.OD%

2.J1t400 7.82+00 712E+00 0.00% 3.77E41 722E4t 7.22241 0.00% 1.J#41 Cm-242 2.BE4+00 5.50E4t1 Z8E+00 0.00%

Crn-2431244 2.2E+02 2.25E+01 224E+02 0.00% 7.55E+00 7.32E41 7.55E000 0.00%

4.14E+02 0.01% 4.01E401 8.92O401 632E Ot 0.02% 803E400 3.01E+01 3.012401 0.03%

Cs134 4.14E+02 1.71E+02 8.07E80 2.05E+02 8.07E+0S 16.09% 2.71E405 8.98E401 2.71E405 80.88% 4.51E+04 3.22E+01 4.51E+04 38.23%

r f137 3.89E+02 1.79Et03 0.04% O.ODE000 8.27E401 L27E401 0.02% 1.94E+02 7.402+01 1.94E402 0.18%

Eu-154 1.79E003 7.50E+01 1.69E+05 3.54% 144E+03 3.18E083 3.65403 0.J8% 1.00E+03 4.09E403 402E+03 3,47%

1.09E+05 8.26E+05 3.04E+02 820E05 13.10% 4.0E8+03 2.53E802 - 4.89E+03 1.05% 1.73E+03 4.51E+02 1.73E+03 1.47%

Hs- 6.51E400

-2.31E+00 2.32E+01 2.32E+01 0.00% 2.03E800 2.14E+01 2.14E+01 0.00% 125241 5.51E400 0.01%

14129 142E401 1.42E+20 0.01%

o.OOE+00 1.18E+02 1.12E+02 0.00% 431+E01 1.59E802 159E+02 0.04% O.OE+00 Ne1-f 1.50E+01 2.92E+01 2.22401 O.O0% 1.18E+02 1.57E+01 1.18E402 0.10%

Nb44 - 4.99E+04 1.52E202 4.99E+04 1.04%

2.90E+02 8.20E+03 0.13% 1388402 1.98E402 1882E02 0.04% Z11E+02 2.70E+02 2.70E402 0.23%

N14-9 8.28E+03 1.80E4+0 1.9E+06 37.67% 3.70E+04 1.80E+03 3.70E804 8.45% 1.58E+04 828E+02 1.5U+04 1t32%

Nl143 g42E+05 2.65Ze4 2.03E+00 0.00% 2.80841 2.80E41 2.60E4t 0.00% 2.58E41 2.S88E4 238E41 0.00%

Np-237 2.03E+00 315FE+03 2.04E+01 3.58E+03 0.07% 2.17E+02 8.34E+00 Z17E402 0.05% 7.52E+01 5.558+00 7.52E+01 0.06%

Pu-rnS 1.79E+02 3.rSE+03 2.04E+01 3.85E+03 0.08% 3.11E+02 2.51E+00 112E+02 0.07% 1.79E+02 Z9E4+00 0.15%

PU-2391240 8.07E+02 0.68%

3.188E04 Z37E+02 3.18E804 0.68% 2.39E+03 1.08E402 2.39E403 0.54% 8.07E+02 1.83E402 Pu-241 i.1E800 4.24E+00 0.00%

2.5SE-01 3.59E+01 359E+Ot 0.00% 5.07E400 3.48E+00 5.07E+00 0.00% 4.24E+00 Pu-242 2.70E+02 2.70E402 0.23%

4.50E+04 2.20E+02 2.202+02 0.00% -2.188404 242E+02 242E+02 0.05% 4.00E+03 Sr-49 3.65E402 4.83E+04 3925%

Sr40 8.27E05 3.49E+02 8.27E+05 17.31% 1.152+05 3.5DE+02 1.158+05 284% 4.53E+04 4.19E+02 1.68E+05 3.52% 3.23E+00 8.12E401 6.122+01 0.01% 8.71E+01 4.552401 8.71E+01 0.05%

Tc-49 1.84E+05 7.48E41 8.89E+02 0.01% 4.23E+01 7.00E41 4.23E+01 O.O% 248E+01 3.01E41 2.48E+01 0.02%

U-23/4 6.6eE+02 7.50E41 4.34E+01 0.00% 2.84E+00 2.75241 284E4+00 0.00% 1.11E+00 3.02E41 1.11E+00 0.00%

U-235/30 4.34E+01 9.35E41 9.58E+00 0.00% 4.57E+00 Z74E41 4.57E+00 0.00% 8.02E41 7.87E41 8.02E41 0.00%

u-23r 90.58E00 4.78E+08 100.00% 4.45E+05 100.00% 1.12E+05 100.00%

Hot Cal Equlpment 14 Snow Not Cell Equiprnmnt 85Smnv Not Cell Equiprmont SO 5mew (pCi/lter) (pci/alter), Cltilber)

Resulms MDA Used Disbibution Result MDA Used Dleirlbutuon Resulms MDA Used Dlstbutien 1.03E+02 0.03% 1.05E+02 2.01E41 1.05E202 0.37%

Arn441 2.78E+01 2.45E41 2.78E+01 0.09% 1.03E+02 7.73E41 1.11% 3.55E+00 3.59E+01 339E401 0.01% 3.e7E+01 3.89E+01 3.9E401 0.14%

C-14 2.80E+01 3.37E+02 3.37E+02 1.13E401 0.04% 8.33E+00 6.15E+01 .15E+01 0.02% O.ODE+00 1.40+E01 1402401 0.05%

Co-57. 5.23E+00 1.13E+01 1.74%

ce-a 1.582403 123E+01 1.58E403 5.20% 3_23E+02 7.082400 3.23E+02 0.10% 4.91E+02 7.50E400 4.91E+02 Crn-242 9.e7E-02 7.40E41 7.40E41 0.00% 1.91E41 285E41 2.82E41 O.D0% 3.9E041 2.38E41 3.90E41 0.00%

Cn-243/244 22E1+00 7.83841 2.21E+00 0.01% 1.45E+00 9.95E41 1.46E00 0.00% 2.42E+00 2.02E41 2A42E+00 0.01%

0.05% 1.82E+01 .532E+01 6.52E4D1 0.02% 4.45E400 1.84E+01 154E401 0.05%

Cse,13at 3.77E400 1.47E+01 147E401 1313% 28E#+05 8.04E+01 288E+05 0887% 1.16E+04 1.47E+01 1.18E+04 41.10%

Cs137 3.99E+03 1.81E+01 3.99E+03 Eu.154 284E+01 3.80E+01 3.N9E401 0.13% 0.00E+00 3.04E+01 334E401 0.01% O.OoE+00 3.11E401 3.11E4D1 0.11%

2.47% 517E+02 8.52E+02 952E402 0.20% 5.54E+02 7.98E+02 7S86E+02 2.83%

0-855 7.50E+02 Z90E+01 7.50E402 3.94E+02 1.51E+04 49.70% 7.812E+1 2.70E+02 2.70E+02 0.08% 1.95E+02 2.63E+02 2.53E402 0.93%

H4-3 1.51E+04 46.22E2Oi 8.17E+00 6.17E400 0.02%

1.38+01 13M401 0.08% -4.97E+00 2.33E201 2ME401 0.01%

1-129 1J.4E+00 0.05%

1.44E+01 144E401 0.05% 1.33E401 8.15E+00 1.33E801 0.00% 1.53E+01 8.23E+00 1.53E+01 Na-22 9.55E+00 028%

-1.25+00 1.27E+01 1.272401 0.04% 2.91E+00 9.20+ 9.20E400 0.00% 3.e4E400 8.03E+01 8.03E401 Li , N-59 .4.30E+01 Z42E402 2A2E+02 0.80% 1.62E+02 2.41E+02 241E402 0.07% 1.17E+02 221E+02 221E402 0.70%

1a29%

/N143 4.50E+03 8.73E+02 4.50E+03 14.81% 1.42E+03 3.67E+02 1.42E403 043% 3.75E+03 4.e9E+02 3.7#8+03 0.00% 4.30E-03 813E41 8.13E41 0.00% 3.02E43 .83E41 6.53E41 0.00%

Np-237 -1.57E41 9.33E841 9.3E41 0.05% 551E+01 ZIE+.00 5.51E+01 0.02% 5.64E401 2.98E+00 5.84E+01 0.20%

Pu-2B 1.882401 3.07E+00 1.88E+01 0.05% 1.04E+02 1.97E+00 1.04E+02 0.03% 4.5#E401 129E+00 4.55E+01 0.15%

tt9/240 1.55E401 2.55+E00 1.558+01 0.53% 739E+02 202E+02 7.39E+02 0.23% 7.10E202 2.00E+02 7.10E+02 2-52%

Pu-241 1.922+02 1387E+02 1.928+02 0.01% 2.49E+00 1.97E+00 2.49E+00 0.00% 3.2E041 2.20E+00 2.2E+00 0.01%

Pu-242 4.77E41 Z558+00 236ZE400 0.88%

sr-B -Z2E+02 2.85E+02 2.J5E402 0.94% 43.6E+03 253E+02 2.53E402 0.08% *3-70E+03 2.47E+02 247E+02 10.47% 3.84E+04 2.87E+02 3.84E+04 11.71% 9.70E+03 3.2E+02 9.70E+03 34,37%

8r40 3.18E+03 3.94E+02 3.10E+03 0.13% 4.e7E+01 1.00E+01 4.67E+01 0.01% 2.44E+01 2.44E+01 2A4E401 0.09%

Tc-9s -1.45E+01 4.05E+01 4.05E401 0.01% 8e10E+00 1.42E+00 8.15E+00 0.00% 2.18+00 8.95E41 2152+00 0.01%

U-233J234 3.82E+00 0.24E01 3.882E00 U-2351236 3124E41 8.2eE41 *262E-O 0.00% 5.32E41 3.19E-01 5.32E41 0.00% 1.87E41 281E41 2.t1E41 0.00%

O.OD% 2.12E41 8.11E41 3.11841 0.00% 2.30E41 2.80E41 2DE041 0.00%

U-238 5.62E41 1.03E+00 1303E400 100.00%

3.04E+04 100.00% 3.28E+05 100.00% 2.a2E+04 NotCeO1 62Stulf-e meer Hot cet Equipment 67 2m- Hot Cedl m Surfceh n btci/iiiter) pi/fittebr) pci/mlter)

Results MDA Used stributilon Results fDA Used Disitutlon Remit MDA 1 Used DistrbUtlon 8.82E+00 3.26E+03 0.88%

2.94E402 2803E41 294E+02 0.07% 1.10E403 1.8JE41 1.10E+03 0.05% 125E+03 Amr441 1.42E+02 8.80E+02 0.19% 3.94402 8.37E+01 3.94E+02 0.02% 1.3sE+02 8.93E+01 1.39E+02 0.04%

C-14 8.8OE002 0.01%

O.OOE+00 4.41+O1 4.411E+O . 0.01% O.OOE+00 1.14E+02 1.14E+02 O0O0% 1.30+01 4.27401 4.27E4 Co-57 203E+01 .012.+03 1.30% 8.18E204 516E+01 5.16E.04 219% O2E04D4 3.13E401 201E204 5.31%

Co-ho 6.O8E+03 0.01%

4.12E41 0.00% 5.84E41 2.11E41 5884E41 0.00% 1.31E+00 232E+01 2.32E+21 Cn-242 4.12E41 009E41 0.01%

1i.M+02 8a41E41 1.93E+02 0.04% 5.07E+01 8.46E41 5.07E+01 0.00% 105E+O1 2.53E401 3.052+01 Cn-243/244 4.1#5+00 4.72E+01 4.72E401 O.O% 9.78E+00 1.17E+02 1.17E+02 O.OD% 1.41E+01 5.03E+01 s.032401 0.01%

Cs1-4 1.OE+-05 5.402E+O1 109E+05 2421% 8.03E+05 1.2#E+02 8.53E405 34.12% 1.09E+05 847E+01 1.084D05 2881%

Cs-137 0.00E+00 7.05E+01 7.tE+Ot 0.02% 1.18E+03 1.44E+02 1.18E+03 0.05% 4.07E402 7.01E401 4.07E402 0.11%

Eu-154 2.38E+03 3.70E+03 3.704D03 0.82% 1.05E+04 428E+03 1.05E+04 0.45% 262E+03 9.04E+02 ze2E+03 0.es%

Fe-O5 1.63E+05 0.91E+02 1.53E+05 35.20% 5.43E+04 4.01E+02 5.43E404 231% 1.80E+04 5.33E+02 1.09E404 Z88%

H-3 2.14E+01 2.UE142 0.00% O.OE+00 133E4O1 333E+01 0.00% O.OOE+00 3.a2401 3J2E21 0.01%

"12s 4.79E41 7.14E2+1 1.782+01 7.14E401 0.02% 0.00E+00 7.17E401 7.17+01 0.00% O.OOE+00 4.01E+01 491E401 0.01%

Ne-.=

8a388EO1 230E+01 .38E4O1 0.02% 8.E6+01 7.08E+01 7.0sE4n 0.00% 278E+01 104E+01 3.644D01 0.01%

Nb-4 OO.E0000 2.68E+02 2.66E402 0.08% 221E403 Z87E+02 Z22E403 0.00% 5.53E+02 2.10E+02 553E+02 0.15%

Nl-S 1.94E+03 4.05E+04 9.00% 1J.8+E05 7.78E+03 1.88E+05 7.05% 8.34E+04 153E+03 8.34E+04 2205%

NI-43 4.058+04 5.80E41 8.24241 0.00% 1J.12400 5.9#E41 1.01E+00 O.OD% 8.98E42 735E41 7JSE41 0.00%

Np-237 8.26E41 1.83E402 170E400 1.53E+02 0.04% 9.4E+02 4.78E+00 949E+02 0.04% 8.75E+02 4.18E+01 8.75E402 023%

Pu-2r Pu-2391240 3.91E+02 1.37E+00 3191E+02 0.09% 3.01E+03 1.09E+00 3.01E+03 0.13% 2012+03 237E401 201E+03 0.53%

Pu-241 1.82E+03 205E+02 1322+03 040% 7r17E+03 1.11E+02 7.17E+03 0.30% 1.4E+04 1A9E402 1.84E+04 4.34%

1.79E+01 3.17E+00 1.72E+01 0.00% 1.40E+o1 1.09E400 402+O41 0.00% 2ZSE+01 4.17E401 4.17E401 0.01%

Pu-242 8.70E+02 2362402 8.70E+02 0.15% -1.90E+00 2.04E402 2.04E+02 0.01% -1.97E+04 270E402 2.782402 0.07%

Sr-49 1.22E+05 3.47E402 1,22E+05 27.1O% 1.258+00 Z72E402 1.252+00 53.12% 115E+05 329E+02 1.15E+05 3040%

Sr-So 7.84E+01 1.08E+02 1.O8E402 0.02% -4.112E+00 .17E+01 6.17E+1 0.00% 1.30E+04 1.04E202 1.3DE+04 3.44%

Tc-91 1.02E+00 7J.2E402 0.17% 1.05E+03 8.27E41 105E403 0.04% 5.43E+01 8.26E41 5.43E401 0.01%

u-23=34 7.a83+02 1.42E+00 4.09E+01 0.01% 5.52E+O1 6.29E841 5.52E+01 0.00% 3.03E+00 8.02E41 3.03E400 0.00%

U-235/2 4.08E+01 1.33E+01 .14UE00 1.332+01 0.00% 3.11E401 2.40E41 3.11E+01 0.00% 2.50E+00 s.53E41 Zs0E+00 0.00%

U-43 4.5DE405 100.00% 2.352+00 100.00% 3.78E+05 100.00%

Page 2 of 4 Attachment A Addendum I Results of Isotopic Analysis of Smear Samples lotCail #4Surfacglmear iiDtCeflh5Suracesm"ea Hot Catll1U Surftce 5neer (PC l4 tef) Resets MDA Used Distrbution Remib 14DA Used Disebution Remsts MDA Used Dvlfslrbn 3.31E+01 0.19% 2.99E+01 2.48E41 2.99E+01 0.11%

526E+01 8.73E4-1 5.265E01 0.45% 33tE+01 2.42E4t 5.84E+01 8J4E+01t 0.33% 4.55E+00 5.45E+01 5.48E+01 O2t%

C-Ia 9.95E+00 3.55E+01 3.55E+01 0.31% -1.08E+01 9J.9E+00 0.05% 1.27E+01 1.50E+01 1.502+40 0.06%

_Co-57 e.00E+00 7.42E+00 7.42E+00 0.05% 9.09E41 9.59E+00 5.70E+00 Z7CE+02 1.54% 1.53E+02 9.e9E+00 1.53E+02 0.55%

3.87E+02 5.70E+00 3.87E+02 3.33% 2.70E+02 2.87E41 2.67E41 0.00% -1.16E45 7 47E41 7A47E4 0.00%

Cm-242 O.OOE+00 3.92E-01 392E-01 0.00% 9.57E42 2.43E41 1.4eE+00 0.01% 9.9542t 7.96E41 9.954t1 0.00%

Cma-243d24 2.065+02 3.43Et01 206E+02 1.75% 142E+00 9.a2E+00 *.62E+00 0.05% 3.63E+00 1.a2E+01 1.112401 0.07%

Ca-134 e86E-02 1i.o0+0i 1 2E+01 0.09% 4.80E+00 5.87E+03 1.17E+01 5.7E+03 33.53% 1.75E+04 1.70E+01 1.75E+04 66.42%

Cs-137 3.572+03 9.55E+00 3.572+03 30.76%

1.92401 0.10% Z2E+00 2.75E+01 2.75E401 0.10%

Eu-154 53Y5+00 Z59E+01 2 2E+O 0.22% 1.76E+00 1.69E+01 7.5SE+02 7.5=+02 4-31% 6.06E+02 7.52E+02 7.52E402 2.85%

F 456 4.50+02 9.34E+02 9S.34E+02 6.05% 6.s4E+02 4.37E+02 5.17E+02 3.52% 332E+01 3.17E+02 3.17E202 1.20%

144 1.71E+01 2-2S6E02 2.2E402 1.95% 8.17E+02 1.53E+01 1.53E+01 0.09% 2.12E+00 7.17E41 Z12E+00 0.01%

NWA WA 0 0.00% -1.39E+00 8.11E+00 6.11E+00 0.03% 9.e2E41 9.96E+OO 96fE+00 0.04%

tNe.22 1.89E+00 9.30E+00 3JOE200 0.05% 5A47E41

-3.24E+00 523E+00 523E+00 0.03% -1.25E+00 7.94E+00 7.4E+00 0.03%

Nbl4 5.04E+00 9.15E+00 1.152400 0.C0%

2.03E+02 2.03E+02 1.16% 1.02E+02 5A7E+00 1.02E+02 0.39%

WA WA 0 0.00% 729E+01 4.32E+03 4.54E+02 4.32E+03 24.57% 9.00E+02 2.53E+02 9.00E+02 3.42%

NI-O3 2.781+03 4.33E+02 Z75E+03 2395%

8.17E41 6.17E41 0.00% -1.42E41 241E+00 241E+00 0.01%

Np-237 5.08E-2 7.785-01 7.718-01 0.01% -141E41 5.17E+00 725+01 0.42% 3.39E+01 1.16E+00 3.3iE+01 0.13%

Pu-23B 1.29E+01 248E+00 1.29E+Ot 0.11% 722E+01 3.04E+00 2.2E+01 0.13% 2.O8E+01 9.S0E+00 2.08E+01 0.06%

Pu-2391240 Z585+01 2.10E+00 2.55E+01 0.22% 2.25E+01 1.55E+02 2.6E+02 1.53% 2.53E202 1.57E+02 2.53E+02 0.95%

Pu-241 3.3SE+02 Z01E+02 3.35E+02 2.89% 2.68E+02 3.69E+00 3.69E+00 0.02% 2.33E+W 1.90E+02 1.802402 0.72%

Pu-242 220E+00 2.48E+00 248E+00 0.02% 6.08E41 2.13E+02 2.13E+02 1.22% -3.70E+02 2.44E+02 244E+02 0.93%

Sr-S 6.9tE+02 3.21E+02 6.91E+02 5.95% 49.25E+02 4.70E+03 3.00E+02 4.70E+03 26.84% 5.E+03 3.562E+02 5.66E+03 21.48%

SrJO Z.24E+03 3.672+02 2.24E+03 19.30%

3.35E+01 33E6401 0.19% -1.182+01 4.90E2+1 4.90E+01 0.19%

Tc49 1.681+01 3.80E+01 3JOE.Ot 0.33% 1.18E+01 83E4-1 1.74E+00 0.01% 3.03E+00 2.84E41 3.03E+00 0.O1%

U.-2334 3.55 C00 1.812+oo00 3.65E+00 0.03% 1.74E+00 8.37E4t1 637E4 0.00% 9.51E42 7.27E41 7.27E41 0.00%

U-23536 241E-41 9.23E0-t 9.23E24 0.01% 5.21E48 1.74E41 2.81E41 2.61E41 0.00% 3.79E41 2.a4E41 3.79E4t 0.00%

U-23S 1.20E-01 1.15+00 1.15E+00 0.01%

1.75E+04 100.00% 2.63E+04 tOO.OO%

1.16E+04 100.00%?

urface Smear MEAN MEAN s5 DEV Hot Callt6 Surtea Smear blatCall? S7 (pClfltefr) PCO/gm) )

(cpvmilter)

Rfesuls MDA Used Dlstributiu Reeuls MDA Used Distributlon 5.3E+01 0.04% 4.523+01 Z70E-01 4.52E+01 0.00% ,Aa.241 9.82E+02 0.19% 0.23%

Am-MI 5J.3E+01 5.55E4t1 4.30E+01 4.97E+01 4.JtE+01 0.10% .0-14 2.9sE+02 0.20% 0.28%

C-14 1.72E+02 5.77E+01 1.72E+02 0.13%

2.Z3E201 2.23E+01 0.04% 4.40E+01 0.03% 0.02%

Co-57 3.36E+01 2.74E+C1 3.36E+C1 0.02% 4.57E+00 5.30E+02 9.30E+00 5.3DE+02 1.03% 23E+04 2.32% 1.a2%

Co40 1.44E+03 9.e9E+00 1.44E+03 1.05%

1.10E+00 1J4E+00 0.00% 2.12E41 5.112E-O .11E41 0.00% Cm-242 2.a4E+00 0.00% 0.00%

Cn-242 -1.58E48 0.47%

1.0C2+00 1.83+00 0.00% 1.082+00 1.2tE+00 12tE+00 0.00% Cm-Ma7C 5.57E+01 0.13%

Cr-2431244 1.01E+00 0.03% 0.03%

3.065+01 3.06E+01 0.02% 9.06E+00 2.73E+01 2.72+401 0.05% Cs-134 6.93E+01 Cs-134 -1.16E+01 76.81% Cs-137 1.28E+05 43.69% 2Z68%

Z75E+01 8.19E+04 5952% 3.9SE+04 2.40E+01 3.95E+04 Cs-137 8.19E+04 Eu-1U5 0.06% 0.0%

4.0CE+01 4.t9+01 0.03% 1.31E+01 3.46E+01 346E+01 0.07% 3.04E+02 Eu-154 O.OOE+00 Fe-55 2.75% Z29%

8.54E+03 8.42W03 6.24% 4.03E+02 8.20E+02 8.20E+02 1.59% 1.59E+04 Fe-55 3.488E03 H44 8.29% 15.29%

2J4E+02 4.47E+02 0.33% 6.81E+02 2.44E+02 8.81E+02 1.32% 6.76E+04 H4-3 4.47E+02 F12i 0.02% 0.03%

Z07E+01 2.07E+01 0.02% 5.41E42 1.11E+01 1.11Et01 0.02% 1.kS2+01 U429 -3232+00 0.02% Ne-22 4.32E+01 0.03% 0.02%

9.79E+00 1J9DE+01 0.01% 4.74E+00 1.22E+01 1_.2E+01 N*f-2 1J09E+01 0.02% 10-44 3.8E+03 0.12% 0.2a%

Nb-4 Z13E+01 1.25E+01 2.13E+C1 0.02% 4A2E41 1.04E+01 1.084E*

1.67E+02 2.35E+02 2.36E+02 0.45% NI-5S 5.40E+02 0.33% 0.35%

NI-S 1.35E+02 2.61E+02 2.18+02 0.19%

2.50E+03 4.18E+02 2.80E+03 5.44% MI-l3 1k.7E+0O 1339% 10.41%

NI-43 5A4E+03 5.49E+02 5.44E+03 3.97%

1.53E4t1 6.2 6.-411 8E801 0.00% MP-237 7.89E41 0.00% 0.00%

d) Np437 2.52E41 5.31E4t1 9341tE 0.00%

0.03% 1.23E+01 Z05E+00 1.23E+01 0.02% Pu-38 4.70E+02 0.11% 0.11%

Pu435 4.53E+01 7.75E+00 4.53E+01 3.07E+01 0.05% pu-23/240 7.54E+02 0.13% 0.13%

Pu.239/240 1.32E+02 1.35E+00 1.32E+02 0.10% 307E+01 1.17E+00 332E+02 Z76E+02 3.32E+02 0.65% Pu-24 4.62E+03 1.19% 1.22%

au-241 4A7E+02 Z02E+02 4A7E+02 0.33%

Z.E4t1 2.70E+00 270C+00 0.01% Pu-44 1.25E+01 0.05% 0.19%

xu-242 8.98E+00 1.3SE+OC 5.9eE+Oo O.Ot%

5.Z3E+02 3.01E+02 3.01E+02 0.59% sr-" 3.18E+02 O.81% 1.54%

-6.97E+03 Z64E+02 2.24E 02 0.19%

5.91E+03 2.95Y+02 5.912+03 11.49% 1.98E+05 25.43% 11.76%

5r40 175E+04 2.89E+02 3.7S1+04 27.39% 540 1.81E+01 4.56E+01 4.58E+Ot 0.09% 1AOE+04 08% 1.23%

3.44E+01 4.27E+01 4J27E+C 0.03%

0.03% 7.5E+00 1.2E+00 7.59E+00 0.01% U-233/23 2.07E+02 0.03% 0.04%

13-2331334 3.91E+01 5.38E41 3.9tE+Ct 0.00%

13-235Zf33 8.41E41 Z970+00 0.00% 4.11E41 7.87E4t 7.87E4t 0.00% U-235/236 1.18E+01 0.00%

2.97E+00 0.00% 1.03E4t 9.82E41 93.2241 0.00% U-2u 52t1E+00 0.00% 0.00%

U-23S 1.42E+00 1.06E+00 1.42E+00 1.37E+05 100.00% 5.14E+04 100.00% 100.00%

Units for sampleconantrtioa ae presented inpiOlr. Flter In thierontext Isdenned a standard rnearsample takeover a 100l 2 area.

Page 3 of 4 Attachment A Addendum I Results of Isotopic Analysis of Smear Samples BALANCE OF PLANT

'Quad C Smer CanalSE Smear Quad A Sre (peuvifltar)

Disobtudon Resuls 1MDA Used Distwulon Results MDA Used Disrton Results MDA Used 9.21E+00 1.98E+02 0.22%

5.73E701 7.24E+00 5.83E+01 0.05% 4A4E+01 7.67E+00 4A4E+01 0.07% 1.98E+02 8.o0E-01 1.2E+Oo 0.00% 3.48E+00 3.6DE041 3.48E+DO 0.00%

Arr-2411 10A3E.O0 1.02E+00 1A32+DO 0.00% 1.t2E+00 1.08% 7.W8E+02 4.89E+01 7.60E+02 1.20% 7.9S2+82 4.42E+01 752E+02 0.87%

C-14 4.47E+01 1.0E9+03 3.78% 4.50E+03 7.40E+00 4.50E+03 7.10% 7.e1E+03 9.3ZE+00 7.etE+03 8.38%

C*410 3.7W+04 7.07E+00 3.76E+03 0.02% Z1E+01 2.-OE01 Z182E01 0.03% 1.79E+01 3.62E41 1.79E+01 0.02%

CQn24324 5.0DE201 1.2d+00 1.70E201 3.23E41 1.40E+00 O.OD% 223E+00 4.18E-01 2.2E+00 0.00%

Crn-2451246 s.73E4t 7.22E-01 9.73E-0 0.80% 1.40E+00 0.12% 7A44E 01 1.02E+01 7.44E+01 0.12% 1.A4E+02 1.23E+01 1A4E+02 0.19%

Cs-I37 1.22E 02 9.49E+00 1822E02 0.04% 5.17E+01 211+E01 5.17E+01 0.08% 0.52E+01 ZSE+01 6.e52+01 0.07%

Eu.152 4.37E 01 2.0tE+01 4.37E+01 0.02% o.E0+00 2.53E201 238E+O 0.04% O.OOE+00 Z77E+01 2.77E+Ot 0.03%

Eu-1# O.OOEOo 2.31E+01 2.IIE+8O o.88% 9.00E+02 3.8OE+O1 9.00E+02 1.42% 8.080+02 3.79E+01 8.05E+02 o.A9%

r*-a +/-WE+02 3.79E+01 8.58202 80.79% 3.902+04 3.57E+02 3.90E+04 61.57% 4.81E+04 4.14E+02 4.81E+04 5+/-82%

H-s 1.07E+04 5.22E 02 8.07E+04 I-In s.oeEo00 1.57E+01 157E401 0.02% 3.e200 1o35E+01 1.35E+01 0.02% I 3.74E+00 1.82+01 1.9dE+01 0.02%

0.01% -8.07E41 9.2sr+00 3212400 0.01% 1.14E+00 1.11E+01 1.111E+1 0.01%

Nb44 223E OO a.&eeoo 3.4E400 0.22% +/-192+02 8.58E+O1 2.19E+02 0.35% 25dE+02 7.95E+01 2.58E+02 0.28%

4.46E+01 2.2DE+02 9.97E+01 1.76E+04 27.79% 3.2dE+04 1.30E+02 3.29E+04 38.02%

N43 8.84E+01 1.25E+04 1z81% 1.76E+04 O.OD% 1.74E+00 1.1AE+00 1.74E+08 0.00% 3.68E+00 1.84E+00 3.68E+00 0.00%

Pu-2ea e23E-01 2.92E+00 0.00% 7.24E-01 7.03E-01 724E-01 O.OD% 1.84E200 7.07241 1.84E+00 0.00%

PU-239/240 1.28E+00 9.49E-01 1.28E+00 ZSOE201 2.50E2+0 0.04% 213E+01 29aZ+01 2.52E+01 0.03%

Pu-241 1.02E+Oi 2.84E+O1 2.64E+O1 0.03% 5.7E+O0 Sr-SO 1.39E+01 a.86E+00 1.39E+01 0.01% 7.2ZE+00 1A8E+01 1AtE+01 0.02% 1 -1.38E+01 1.18E+01 l1.11E+o O.0O%

0.08% 4.27E+01 9.2DE+00 4.27E+01 0.07% 1.02E+02 8.22E+00 1.02E+02 0.11%

Sr-90 7.93E+01 8.58E+00 7.93E+01 0.03,' 312E+01 3.02E+01 3.19E+01 o.es% 5.81E+01 4.3DE+01 5.91E+01 0.0e%

Tcv- 32DE+01 3.04E+01 3.2DE+01 9A3E-01 0.00% 7.98E-01 7.62E-01 7.98E41 0.00% 4.65E241 5.95E41 3.95E-1 O.OD%

U4-231254 1.94E4-1 SA3E4-1 9.99E+04 100.00% 8.33E+04 woolo%j 9.11E+04

• 100.00s Ufly Pad Smear CTMT OGneral Ares Swar Rx Bulling Smear (pCUfllteri IpCalter) IpCfiIllerl Used 00.1 MDA Used Disbtvuton Results MDA Used Distriuon Results MDA Results 3.e3E+00 4.70E+00 0.05% 8.09E+01 7.47E+00 8.89E+01 0.03% N/A N/A 0 4.70E+00 7.171-01 0.01% 3.81E+00 7.24E-01 3.61E+00 0.08% 7.84E+O1 1.47E+01 7.84E+01 Arn241 7.17E4t C-14 e.25E-01 5.30E+O1 2.38E+01 5.30E+01 0.53% 2.90E+02 4.53E+01 2.90E02 O.11% 203E+01 1.37E+01 209E+01 Oii%

4.03E+00 Z53E+02 281% 3.57E+03 e.77E+00 3.57E+03 1i8% 2.3sE+02 8.51E+00 Z35E+02 1.29%

Ce40 2s53E+02 Crn-2A3244 2.05E+00 .75E-01 2.05E+00 0.02% 4.71E+01 8.a2E-01 4.71E01 0.02% 223E+00 4.02E41 2.39E+00 0-01%

.8DE041 0.01% 9.33E2-1 4.00E2-1 9.33E41 0.00% N/A WA . 0 0.00%

Cm-245s246 88DE-01 3.98E41 4.05E+00 1.39E+01 0.15% 3.6+/-E+02 9.38e+00 3.84E+02 0.14% 4.64E+03 1.02E+01 4.64E+03 25,15%

cs-1S? 1.38E+01 0.35%

0.12% 1AOE+01 2.08E+01 2.0E2+01 0.01% 6.50E+01 3.70E+01 6.50E+01 Eu-152 2.56E+00 1.07E+01 1.7E+01 1.42+401 0.12% o.OE+OO 2.08E+01 2.0dE2+0 0.01% 7.18E+01 1.75E+01 7.19E+01 0.39%

Eu-1# 1.43E+00 1.04E+01 7.stE+02 8.80% 4.43E+03 4.02E+01 4.43E+03 1.68% -1.59E+01 1.79E+01 1.7sE+01 0.10%

7.91E+02 3.a2E+o1 Hp- 8.42E+03 3.03E+02 6A2E+03 71.40% 2.422+08 9.07E+02 2.42E+05 91.95% 1.07E+04 2.89E+01 1.07E+04 58.00%

-I29 1.54E+01 2.21E+01 22t +o t 0.25% 4.022+00 1.0DE+01 12OE+01 0.00% 1.02E201 8.17E+00 1.02E+01 0,06%

412E+00 0.04% 1.732+01 528E+00 1.73E+01 O.O% -3.68E41 9.12E+00 .12E+Oo 0,05%

Nb-4 8.85E-t 3.91E+00 2.32E+02 7.98E+01 7JI2+O, 0.89% 9.04E+01 7.67E+01 9.04E+01 0.03% 2.38E+02 2.ME+01 1'25%

o.OE+O0 1.24E+03 1+/-79% 1.19E+04 8.27E+O1 1.19E+04 4.52% 3.27E+01 8.59E+01 s91E+01 0.36%

N143 1.24E+03 Z68E201 0.16%

Pu45s 224E-1 71Z5E41 7.252E- 0.01% 6.51E41 9.05E4t 93.oE84 O.00% 2.86E+01 3.50E+00 2.86E20i 0.00% 2.16E+00 1.04E+00 2.16E+00 0.00% 1.48E+01 2.71E+00 1.48E+01 0.05%

Pu-2381240 4.33E41 4.14E-01 433E-01 0.34% +/-71E+01 Z37E+01 +/-71E+01 0.01% 1.78E+02 1.43E+02 1.78E+02 0.96%

Pu-241 2.58e+00 308E+01 I.0OS2+01

• .762+00 0.10% +/-902+01 7.18E+OO 2.99E+01 0.01% WA WA 0 0.00%

sr-"s 4.02E-01 a.7sE+00 it '06%

9.77E+00 a.11E+00 9.77E-00 0.11% 2.42E+02 9.64E+00 2,42E+02 0.05% 2.04E+03 1.44E+01 2.04E+03 328E+01 O02% 9.05E+00 3.38E+01 3282+01 0.01% I O.OOE200 281E+01 2J1E+01 0.15%

1.02E+01 3.39E+01 1.0oE+00 1.O1E+00 0.01% 3.73E41 9.00E41 3.002-01 0.00% - 4.38E+00 4.43E+00 4A3E+O0 0.02%

3.14E41 8.992E03 100.00%! 263E+0S 100.00% 1.84E+04 100.00%

I Rx Bulidcng Smar Duplicate IrCifiltmrl MEAN MEAN STD DEV I

Results MDA Used Dlsributlbn (%)

N/A WA 0 0.00% o:Aq4O8rn S.SsE+01 0.05% 0.07%

ArQ-241 1.01E+02 1.00E+O1 1.OE+02 0.47% :A241 2.72E+01 0.13% 0.22%

C-14 2.03E+01 1.37E+01 2.02E+01 0.10% :C44 4.3tE+02 0.58% 0.48%

C040 2.53E+03 7.07E+00 2.53E+03 11.85% :Co-GO 3.21E+03 512% 3.99%

Cm-243/244 231E+00 7.91E41 2.31E+00 0.01% Crr24=" 1.58E+01 0.02% 0.01%

Cm-245J246 NWA N/A 0 0.00% Cm-245/= 8.85E-01 O.OD% 0.00%

5.63E+03 1.01E+01 5.63E+03 28.36% C5437 157E+03 7A6% 1Z501%

Eu-152 3S2E0201 4.82E+O1 4.62E+01 0.22% Eu,152 4.33E+01 0.13% 0.12%

Eu-ISO 9.2E+O+1 1.592+01 9.62E+01 O.5% Eu,154 3.95E+01 0.15% 0.19%

.63E+00 200E2+01 2.oE+Et 0.09% F.-55 1.12F+03 1.99% 3.07%

H-S 1.OSE04 +/-a4E+01 1.05E+04 4s.16% H-3 812E+04 ee.53% 15.60%

1.94E+01 0.03% 1429 1.57E+01 0.05% 0.09%

1-129 1.94E+01 1.00E+01

-1.22+100 a8.sE+oo 9.GO6dO0 0.04% Nb." s.71E+oo 0.03% 0.02%

Nb-4

-1.65E201 2.03E+01 2.03E+O 0.10% 1,11411 1.61E+02 0.45% O08%

Nl1143 e.7sE+01 6.a3E+01 4*.32+01 0.32% MI-53 1.09E+04 13ee% 1378%

3.50E+00 2.8E+01 0.13% PU-= 9.6DE+OO 0.04% 0.07%

Pu-2r 2+/-8E+01 2.71E+00 1.48E+01 0.07% PU-239440 5.15E+oo 0.02% 0.04%

PU-239/240 1A8E+01 Pu-241 1.79E+02 1.A3E+02 .7e+02 0.83% PU-241 7.05E+01 0.32% OA1%

Sr-9s N/A W4A 0 0.00% sr-as 1.13E+01 0.03% 0.03%

Sr-SO 2.04E+03 1.44E+01 Z04E+03 9.55% sr4o 6.51E+02 3.01% 3.80%

Tcvo -1.21E+01 281E+01 2.1E+01 0.12% To-" 3.52E+01 0,12% 0.13%

U.-235234 4.3aE+00 4A43E+00 4A3E+O0 0.02% U-23=934 1.91E+00 0.01% 0.01%

214E+04 100.00% 100.00%

Unils for sarn'paecia laons a prentod in pCVOnar.Fiar Intlh context Ia deind ass etandard esnareawple mbke owe 10mr2am.

Page 4 of 4 Attachment A Addendum I Results of Isotopic Analysis of Smear Samples Reactor Operations & Laboratory Building ROLt SMor ROLB Sonic Dupkate ROtB Senri2 (pcbfltar) (pCiViter) pouflttr)

MDA Used wistrtfrlon Result MDA Used Disribution Results MDA Used Results 0.01% 0.03%

0.01% 1.8E+00 1.t4E+00 1.82E+00 8.07E+00 1.70E+00 6.07E+00 Am-241 1.82E+00 1.64E+00 1.82E+00 0.47%

1.56E201 0.06% 1.05E+01 1.03E+01 1.66E+01 0.04% -4.68E+01 8.614E01 *.8tE+01 0-t4 1.55E+01 1.53E+01 0.48%

1A5% 4.09E+02 1.1SE+01 4.002+02 1i45% 802E+O1 8.51E+00 5.90E+01 co-o 4.09E+02 1.1bE+01 4.09E+02 0.01% -2.54E41 3.27E+00 3m27+00 O.Ot% 8.22E-01 1.53E+00 1.53E+00 0.01%

cn-42 -i54E-0 3.27E+00 3.27E+00 8.01%

O.O% 3.04E+00 1.64E+00 3.04E+00 O.Ot% 85 E4E1 2.09E+00 2.09E+oo Cm-243t244 3.04E+00 1.64E+00 3.04E+00 16.90% 16.18%

18.96% 4.77E+03 1.37E+01 4.77E+03 2.s7E+03 1.14E+01 2.97E+03 Oa-137 4.77E203 1.37E+01 4.77E+03 0.07% 126E+01 1.85E+01 1.s6E+Ot 0.07% 1.46E+02 3.23E+01 3.23E+01 0.18%

Eu-155 1.26E+01 1.86E+01 1 BSE3ltt 3.73%

73.93% 2.05E+04 5.30E+01 2.0tE+04 73.96% 4.92E+02 6.84E+02 *.e4E+02 H-3 2.08E+04 5.30E+01 2.08E+04 5.24%

0.06% 1.b7E+01 1.20E+01 1.67E+O1 0.06% 9.63E+02 1.04E+01 9.63E+02 1-S2 1.67E+01 1.20E+01 1.67E+01 0.c5% 8.74E+00 1.41E+01 IAIE+01 0.05% 1.91E+02 5.11E+00 8.11E+00 0.04%

Nb-U 6.74E+00 141E+01 1A1E+0t 0.69% 2.56%

0.69% 5.16E+01 1.96E+02 105E+02 -4.30E+02 4.71E+02 4.71E+02 N14-9 5.16E+01 1tsE+02 1.5+402 0.24%

0.22% 3.13E+01 630E+01 6.30E+01 0.22% 1.70E+02 4.47E+01 4A47E+01 H4143 3.13E+01 6.30E+01 630E+01 0.04% 4.43E+00 4A3E+00 0.02% 3.eSE+00 1.74£+01 1.74E+01 0.09%

Np-237 4.93E+00 1.00E+01 1.0DE+01 734241 5.64E+00 0.02% 1.0tE+01 3.19E+00 1.06E+01 0.04% 1.8E+00 1.53E+00 1.82E+00 0.01%

P-23Q40 5.64E+00 1.95E+00 0.41%

0.34% 9.32E+01 1.50E+02 1.80E+02 0.53% 8.80E+01 7.57E+01 7.57E+01 Pu-241 5.85E+01 9.47E+01 9.47E+s1 0.19% -1.24E+00 5.26E+01 5.2E+0 0.19% 5.92E+00 4.83E+01 4.83E+01 0.26%

Sb-125 -1.24E+00 5.26E+01 5.262E40 5.44% 1.48E+03 139E+01 1.48E+03 5s26% 4.81E+02 1.23E+01 4.81E+02 2.62%

sr4o 1.53E+03 1.48E+01 1.53E+03 0.10% 5.96E-D 2.80E+01 2.e0E+Dt 0.10% 9.04E+01 8.89E+01 8.89E+01 0.48%

Te49 5.96E41 Z80E+01 280E+01 033% 8.52E+01 1.81E+00 8.52E+01 0.30% 1.1E+04 4.93E+00 1.18E+04 64.02%

U-2331234 9.15E+01 3.97E+00 9.15E+01 2.14%

0.02% 4.42E+00 2.24E+00 4A42E+00 0.02% 3.94E+02 3.35E+00 3.94E+02 U-232136 532+00 2.84E+00 5.82E+00 0.02% 4A46E+00 2.18E+00 4.46E+00 0.02% 1.42E+02 2.71E+00 1.42E+02 0.77%

U-238 4.81E+00 2Z85E+00 4.8iE+00 100.00% Z81E+04 100.00% 1.84E+04 1O%

2.61E+04 ROtB Snar 2 Dupilctae MEAN MEAN SD DEV (peUwItar) IpCUqm) (%)

Results MDA Used Oletribtn A-241 2.35E+00 2.N0£+00 2.00D+00 0.02% Am-241 3.15E+00 0.02=/ 0.01%

0-14 -2.04E+01 8.51E+01 9.51E+01 0.48% 0-14 4.93E+01 0,26% 0.25%

Co-O 9.58E+01 7.77E+00 9.5E+01 0.54% 0+40 Z51E+02 0.95% 0.54%

4 0.01%

Cm-242 4.70E-3 Z23E+00 23E+00 0.01% Cm-2 2 zS5E+00 0.00%

2.11E+00 2.57E+00 0.01% 0.00%

Cm-2431244 8.5DE41 Z11E+00 0.01% Cm -243r44 1.17E+01 2.90E+03 1e.40% Cr-1ft7 3.85E+03 1e.62% 0.40%

c-137 2.90E+03 Eu-1ss 2.77E+01 3.18E+01 3.18E+01 0.18% Eu-155 2.53E+01 0.12% 0.06%

H4- -4.15E+02 6.85E+02 4,5£+02 3.87% H43 1.07E+04 358.7% 40.50%

14129 9.32E+02 1.05E+01 9.32E+02 5.27% 4.02E+02 2.66% 3.00%

Nb-4 1.94E+02 7.77E+00 7.77E+00 0.04% 1.10E+01 0.05% 0.00%

NI-5, 4.2tE+01 4.93E+02 4.93£+02 2.79% 335E+02 1.68% 1.15%

NW 1.68E+02 4.36E+01 4.36E+01 0.25% 5.35E+01 0.23% 0.01%

-1.58E+00 8.72E+00 8.72E+00 0.05% Np-237 1.01E+01 0.05% 0.03%

Pu-239f340 2.00E+00 9.05E41 2.0DE+00 O.Ot% Pu.226/240 5.08E+00 0.02% 0.01%

Pu-241 5.34E+01 9.19E+01 9.19E+01 0.52% Pu.241 1.03E+02 0.45% 0.D9%

Sb-125 4.72E+00 4.69E+01 4.69E+01 0.27% Sb-125 5.01E+01 0.23% 0.04%

srt0 49.7E+02 1.26E+01 4.97E+02 2.81% Sr-so 9.97E+02 4.03% 1.53%

Te4s 4.51E+01 8.87E+01 8.87Ei01 0.50% Tc-99 5.84E+01 0.30% 0.23%

U-233f234 1.11E+04 5.04E+00 1.11E+04 ezs2% U-233/234 5.76E+03 31.87% 36.44%

U-235/23 4.08E+02 3.28E+00 4.05E+02 2.3D% U-2351235 2.03E+02 1.12% 1.27%

U-230 1.52E+02 4.StE+00 1.52E+02 0.85% U-238 7.58E+01 0.42% 0.45%

1.77E+04 10D% 10o.00%

Urits for sampleconreraflne ae prnted topCi~ltar. Fiter In 9hicrtext Is defined-a standardareerwrpbe take evera 100N2 are_.

Page 1 of 3 Attachment A Addendum i Results of Isotopic Analysis of Smear Samples (10% Rule Normalized)

HOT LABORATORY g Hot Car Equipment #2 Smear -Hot CadEquipment 13 Smear 9Hot Col Equipment in Smear (pCViaru HM .(pCltfn

2. lpCmter Used Dsthrbution g MDA n Results MOA Used Dlstrbuttan Results MDA CG3R7sutts 14D+str2bu101 +03 1% 2.67+03 1.27E+01 2.67E+03 2.78% g co Z74E 124 02 2.74E+05 10.81% 8.E8 31.t2% 2.71E+05 5.S9E+01 2.71E+05 67.85% 4.51E+04 3.22E+01 4.51E+04 46.98%

Cs-137 8.07E+05 206E+02 tt07E+05 0.07% 0.00E+00 8.27E+01 8.27E+01 0.02% 1.94E+02 7.49E+01 1.94E+02 0.20%

Eu-154 1.79E+03 3.69E+02 1.79E+03 24.69% 4.69E+03 2.53E+02 4.69E+03 1.17% 1.73E+03 4.51E+02 1.73E+03 1.d0% A H-3 (t.26E+05 3.49E+02 6.26E+05 32.81% 1.15Y+05 3.50E+02 1.15E+05 28.79% 4.63E+04 3.65E+02 4.63E+04 48.23%

Sr-0 8.27E+05 3.49E+02 827E+05 2.54E+06 100.00% 3.99E+05 100.00% 9.60E+04 100.00% E

>5:

Hot CogEquipment t4 Smear Hot COt Equipment 45 Smear .r5 Hot Cal Equipment SOSmear tpewr) lpClfl~ttr) Used Results MDA Used Dkstrtbutlon Results MDA Dlstribution Results HIDA Used Distrbutdan 1.58E+03 6.81% 3.23E+02 7.08E+00 3.23E+02 0.10% 4.91E+02 7.50E+00 4.91E+02 222%

Co40 1.58tE+03 1.23E+01 3.99E+03 16.70% 2.85E+05 6.04E+01 2Z85E+05 87.96% 1.16E+04 1 47E+01 1.16E+04 52.52% 5:

Cs-137 3.99E+03 1.61E+01 3.99E+01 3.99E+01 017% O.OOE+00 3.04E+01 3.04E+01 0.01% 0.00+00 3.11E+01 3.11E+01 0.14%

Eu154 2.64E+01 263E+02 1,19%  ;

1.51E+04 63.21% 7.61E+01 2.70E+02 2.70E+02 0.08% 1.95E+02 2638+02 N 1.51E+04 3.94E+02 9.70E+03 43.9%

3.94E802 3.18E+03 13.31% 3.848+04 2.87E+02 3.94E+04 11 85% 9.70E+03 3.54E+02 Sr-SO 3.18E+03 2.21E+04 100.00%

2.39E+04 100.00% 3.24E805 100.00%

2'Hot Cell Equilpment #7 Smear Hot Cll01 Surface Smear Hot Cdl 82 Surface Smear 1-(pcvMa.,), {~PCVmt.,)

Results MDA Used Dlstrbuteon Wstrbullon Results MDA Used Dtstribution Results MDA Used 1.52% 5.16E+04 5.16E+01 5.1 8E+04 Z39% 201E+04 3.13E+01 2.01E+04 7.87%

Co-Go 6.08E+03 2.03E+01 6.O8E+03 2724% 8.03E+05 1.25E+02 5.03E+05 37.17% 1.09E+05 6.47E+01 1.09E+05 42.68% -

Cs 137 1.09E+05 5.49E+01 1.09E+05 7*5E+01 0.02% 1.18E+03 1.44E+02 1.18E+03 0.05% 4.07E+02 7.91E+01 4.07E+02 0.16%

Eu-154 O.OOE+00 7.95E+01 1.63E+05 5.43E+04 4.01E+02 5.43E+04 2.51% 1.09E+04 5.33E+02 1.09E+04 427%

H43 1.63E+05 8.91E+02 40.73%

45.03%

1.22E+05 30.49% t.25E+06 2.72E+02 1.25E+06 57.87% 1.15E+05 3.29E+02 1.15E+05 Sr40 1.22E+05 347E+02 4.00E+05 100.00% 2.16E+06 100.00% 2.55E+05 100.00%

%HotCel3S Surface Smear Not Cd .ttSurface Smear Hot Cel 6S Surface Smear g

§1PCVXmt)

Results MDA Used Dlstrlbutlon ~. Re"ults MDA Used Dlstuibution R(Cutts

1.53E+02 MDA 9.69E+00 Used 1.53E+02 Distribution 0.65%

Co-Go 3.87E+02 8.70E+00 3.87E+02 6.00% 2.70E+02 5.70E+00 2.70E+02 2.35%

55.36% 5.87E+03 1.17E+01 5.87E+03 51.16% 1.75E+04 1.70E+01 1.75E+04 73.97%

Cs-137  : 3.57E+03 9.55Y+00 3.57E+03 25968+01 0.40% 1.76E+00 1.69E+01 1.69E+01 0.15% 2.62E+00 2.75E+01 2.75E+01 0.12%

Eu-15t 5.35E+00 2.59E+01 3.50% 6.17E+02 4.37E+02 6.17E+02 5.38% 3.32E+01 3.17E+02 3.17E+02 1.34%

H-J 1.71E+01 Z26E+02 2.26E+02 2.24E+03 34.73% 4.70E+03 3.00E+02 4.70E+03 40.96% 5.66E+03 3.5eE+02 .5.66E+03 23.92%

Sr-4 . 2.24E+03 3.67E+02 6.45E+03 100.00% 1.15E+04 100.00% 2.37E+04 100.00%"

eHtCetl 67 Surface Smear MEAN MEAN STD DEV Hot Cot #6 Surface Smear (p'lC01tter)  ;(pCI/am) (5k) fpCpciilr)

Results MDA tsed Dtstrobutien Results MDA Used Dlsrhbutlon :1 1.44E+03 119% 5.308+02 9.30E+00 5.30E+02 1.14% c-Go4 2.83E+04 3.41% 3.15%

Co-Go 1.44E+03 9.69E+00 53.11%

8.19E+04 87-50% 3.95E+04 2.40E+01 3.95E+04 5.66% i55Cs-137 1.88E+05 21.35%

Cs 137 8.19E+04 Z75E+01 0.12% 0.10%

4.01E+01 4.01E+01 0.03% J1.31E+01 3240E+01 346E+01 0.07% +<Eu-154 3.04E+02 Eu-154 O.OOE+00 6.76E+04 10.84% 19.01%

244E+02 4.47E+02 037% .681E+02 2.44E+02 6.81E+02 1.46% kH-S H-3 4.47E+02 1.98E+05 32.52% 13.97%

3.75E+04 2.39E+02 3.75E+04 30.91% 5.91E+03 2.95E+02 5.91E+03 12.67% -. Sr-90 Sr-40 100.00% g 100.00%

121E+05 100.00% 4.S7E+04 coonenfretionsare presentedInpCifiltter.Filter InlUiscontext is defined* a standard ear sarrpie takeover a 100crn2area.

Unitstor sanrphe

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 CTMTGeneral Area Smear IRX BuildingSmer (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 STDDEV 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% mlI 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 InpCi/lfiller.Flterin Nts conext is defled as a standard rnunrsacrpletakeover a 100nn2 area.

Attachment A Pageo3 of 3 Addendum I Results of Isotopic Analysis of Smear Samples (10%Rule Normalized)

Reactor Operations & Laboratory Building ROLt3Sm*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 03 ROLt Smear 2 Dupliate MEAN MEAN STD DEV

~%lCUflttr) lpCl/gm) M("

Results IDA Used Dtribulou Ce-O i.58E+01 7.77E+00 9.58E+01 0.58% Ce40 2.512+02 1.01% 0.04%

Cs-S 2.90E+03 1.17E+01 2.002+53 1744% Cs-137 3.85E+03 17.29% 0.13%

H-S .4,15E+02 6.o'iE02 6.85E+02 4.12% tSt3 1.07E204 33.71% 41.19%

U29 9.32E+02 1.05E+01 932E+02 5.60% U129 4.82E+02 2.82% 3.19%

Sr-DO 4.97E+02 1.26E+01 4.97E+02 2.99% kVSr40 9.97E+02 4.17% 1.49%

1-n3324 1.12E+04 5.04E+00 1.11E+04 68.82% 15-233/234 5.76E+03 33.82% 38.68%

5-235/236 4.08E+02 3.28E+00 4.08E+02 2.45% J-235/2361 2.03E+02 1.19% 1.35%

1.66E+04 100% 100.00%

thik for *arrpb cos entragons a presented in pCi6tIer. Fillterin Is rontext [a defned as a standard rnar sanrrp.take Vera 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(

Adden d.

i ( 4 r AgeI of 16 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 88.66%

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 4.39%

Eu-152 ND ZND :ND J.ND Eu 154 ND fND MND KND 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 6.95%.

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 DD D D 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+00 100.00%

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 C7 (r P'age2 of 16 CORE BORE #6, Containment -25 f Canal E K-40 Co-SO Nb-94 Ag1OSm Cs-137 04NCH DEPTH

~Results ND K.ND

'ND 1.24E+01 222E+02 LC900010111FIUC3L05061 MDA 2.96E+00 9.47E-01 1ST PUCK Used 1.24E+01 0

2.22E+02 5.23% :'ND 93.43%4 C9OOOoi PFLIC3L05O6-0I1A 1ST PUCK 1124NCH DEPTH Results ND ND 6.61E+00 2.70E+02 MDA 3.00E-01 1 8.92E-0 1 Used 0

6.61 E+00 2.70E+02 2.23%

91.10%

ND ND

~'NO NO tiC001OUIFL1C3L0506-02 12 INCH DEPTH Rsults D

MDA 2CND PUCK Used 0

0 0

C90001O01HIFLC1L0506.02A 1.NCH DEPTH

,ResulIs ND

[NO

~ NO ND 2.58E-01 MDA 2CND PUCK Used 0

0 I

1.36E-01 Eu-152 ~ ..ND ND ND ND 2.58E-01 6.23%

EuI1U54 ND 0 342E+00 1.62E+Ot o 3.42E+00 1.15% ND 0 D. 0 T1-208 ND 0 NO 0 ND 0 3.29E-01 1.64E-01 7.96%

3.29E-01 Pb-212 D OD 0 ND 0 6.33E-01 4.58E-01 .6.33E601 15.31%

Pb-214 NDD 0 0 1.486+00 4.98E-01 1.486E+00 17.26% 1.26E+00 4.76E-01 1.26E+00 30.55%

Bl-212 ND 0 6.#E+00 7.08E+O 0 6.546+00 2.21% ND 0 ND 0 Bi-214 ND O 3.10E+o 1.67E+0 0 3.106+00 1.04% 1.52E+00 2.34E-01 1.52E+00 17.77% 1.65E+00 4.49E601 1.65E+00 39,96%

R-226 ND 0 0 6.57E+00 3.89E+00 5.57E+00 64.97% ND 0 Ac-228 ND ND ND Th-234 ND NO ND ND U 235 ND / ND ND INO Am-241 3.17E+00 1.95E+00 3.17E+00 1.33% 6.75E+00 2.23E+0 0 6.736+00 2.27% ND ND 0 Cm-243 ND ND ND ND Cm-245 ND ND ND 2.38E+02 100.00% 2.97E+02 100.00% 8.58E+00 100.00% 4.13E+OO 100.00%

'2 Inch 112 Inch I Inch

\ ': /z 1/2 INCH 1 1/2 INCH

-K40

• .wvcoZO -K 40 wC$137

' ' t>E154 T1-206 T14'05

-Pb-212

""PtP-214

~TI-2O6I wi2s wP0-212l 612 EN02 i0

.WN 0.5 0.5 I 0,0 0.5 0.p1h D.pFt with Cs.137 without Csli37

Attac4 AddenMS.m 2 k4 Preliminary Analysis of Concrete Core "Puck" Samples by.the On-Site Laboratory

( ( age 3 of 16 CORE BORE #7, Reactor Building -15 ft. SE Area NC90001011HFL1C1L0507-01 15 TPUCK C9000101P11FC1L0507-01A 15TPUCK IC9O001111FL1C1L0507-02 2CND PUCK C900010111FUC1L0507-02A 2CND PUCK 0-tiNCH DEPTH 112-NCH DEPTH "1t2. INCH DEPTH ResulIs 1-WNCHDEPTH MDA Used  % 'ftesults MDA Used  % 'fRtsulXt MDA Ued  % wResult MDA Used  %

K-40 138E+00 3.25E+00 1.38E+00 t1.09%,% 1.30E+01 2.13E+00 1.30E+01 49,03% ND Co- 60 0 0 5.02E-01 2.17E-01 5.02E-01 4.04%

- 3.83E-01 2.17E-01 3.83E401 1.44% ND 0 ND 0 Nb-94 ND mND ND ND Ag- 08m Cs-137 Eu-152 ND ND 1.692E00 2.58E-01 1.69E+00 13.57%1 VND ND 1.28E+00 2.06E-01 1.28E+00 4,83% ND ND ND 0

ND ND 0 4'19 Eu-154 ND ND D ND ND Tl-208 'ND ND ND ND Pb-212 ND 0 7.15SE-1 4.35E-01 7.152E-0 2.69% 4.37E-01 4.09E-01 4.37E-01 13.84% 5.282-01 4.38E-01 5.25E-01 4.19S Pb-214 1.79E+00 4.03E-01 1.79E200 14.39% 1.50E+00 4.96E-01 1.50E+00 5.64% 1.60E+00 4.90E-01 1.60E+00 50.72% 1.62E+00 4.792-01 1.62E+00 Ei-212 :X 5.35E+00 1.97E+00 5.35E+00 43.02% ND 12.88%

0 ND 0 ND O 0

8i 214 1.73E+00 4.87E-01 1.73E+00 13.90% 1.67E+00 5.162-01 1.672+00 6.27% 1.12E+00 3.47E-01 1.122+00 35.44% i.28E+00 3.81E-01 1.28E+00 Ra-226 ND 0 8.002+00 5.84E+00 10.20%

8.00E+00 30.10% 6.03E+00 0 9.16E+00 4.41 E+00 Ac 228 ND 9.16E+00 72.72%

ND ND Th-234 NN ND ND ND U 235 ND ND Am 241 ND ND ND ND Cm-243 ND ND ND ND Cn-245 ND ND D ND ND 1.24E+01 100.00% 2.66E+01 100,00% 3.16E+00 100.00% 1.26E+01 100.0 0 inch 1,2 Inc 1/2 Inch

. N11 I,/".

Atakcl A Addendm 2 Preliminary Analysis of Concrete Core "Puck' Samples by the On-Site Laboratory C ' ( _.age 4 of I6 CORE BORE#9, Containment .25 ft. Area 18

• CS0001011FL1C3L0509-01 1STPUCK rC9000101"FL1C1L0509.OiA 1ST PUCK C900010111FUC1L0509-02 2CND PUCK MC9000101I1FLIC1L0509-02A 2CND PUCK 0-INCH DEPTH /1I2 INCH DEPTH /2-lNCH DEPTH .-INCH DEPTH Resulbt MDA Usad  % Rults IMDA Used %tesults MDA Used  % fRsulbt MDA Used  %

K-40 ND ND ND NO ND Co-60 ND ND ND Nb-94 NO NO ND ND Ag-1OSm ND NO ND ND Cs 137 1.35E+00 2.34E-01 1.35E+00 D 9.81% 7.11E-01 2.34E-01 7.116-01 8.52% ~ 1.406-01 0IMO Eu.152 ND ND ~NO ~ND Eu-154 NO 'ND m NO Tl-208 ND ND

~ND ND Pb-212 5.40E-01 4.27E-01 5.40E4-1 1 3.91% 5.62E-01 4.40E-01 5.62E-01 6.74% 5.58E-01 4.55E-01 5.58E-01 18.70% 6.56E-01 3.42E-01 6.56E-01 20.58%

Pb-214 1.53E+00 4.04E-01 1.53E+OC 11.07% 1.25E+00 5.50E6-1 1.25E+OC 1495% 1.22E+00 3.51E-01 1.22E+00 40.80% 1.39E+00 4.03E-01 1.39E+00 43.57%

61-212 NO C 44.4E00 1.94E+00 4.48E+OC 53.72% NO 0 InND 0 Bl-214 1.59E+00 3.98E-01 1.59E+OO 11.53% 1.34E+00 3.44E-01 1.34E+O( 16.07% 1.21E+00 4.01E-01 1.21E+00 40.50% 1.14E+00 3.22E401 1.14E+00 35.85%

Ra-226 8,78E+00 6.08E+00 S,78E+0O 63.68% ND ONO 0 NO 0 Ac 228 ND ND Th-234 ND NO ND ND D

'NO N U-235 ND ND Am-241 ND NO 'NO ND N NC)

Cm-243 ND ND ~NO MND Cm-245 NO NC) ND ND 1.38E+01 I 100.00% 8.34E+OO 100.00% 2.98E+00 100.00% 3.19E+00 100,00%

0 Irch 1/2 Ihch 1/2 Inch I Ich

\1 1 1/2 INCH 10 C-37

_ ~Pb2t2 o'"Pb-214

_ B1-212 I

_R226 0~5 0.

D.p0.

Attac(

AddenumIt 2 A

Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory

( ( Page 5 of 16 CORE BORE #10, Waste Handling Building 15ft MCS000101UQ1PLC3t.0510-01 15TPUCK CS00010111FIC31.0510-01A 1STPUCK ,CS00010111FL1C1L0510.02 2CNDPUCK C8000101iPLC1L0510.02A 2CND PUCK O-INCH DEPTH 112-.NCH DEPTH 1112-lNCH DEPTH I-INCH DEPTH KResults MDA Used  % sults MDA Used %Reults MDA Used Reults MDA Used X K-40 ND ND 1.20E+01 2.10E+00 1.20E+01 78.10% .11E01 2,10E+00 co-so ND ~ND ND ND 1.11E+01 87.04%

Nb-94 ND NO ND ND Ag-1 Om ND D ND Cs-137 Eu-i 52 ND 8.17E+03 3.85E+00 5.175+03 100.00% 4.37E+03 3.40E+00 4.37E+03 10000% ~ 5.095-01 2A8E-01 5.095-01 3.32% 3.21 E-01 1.39E-01 3.21E-01 2.51%

NO ND ND Eu-154 ND ND ND ND T-208 ND 0 ND 0 3.77E-01 1.26E-01 3.77E-01 2,46% ND 0 Pb-212 ND 0 ND 0 5.12E-01 4.16E-01 5.12E-01 3.34% ND 0 Pb-214 ND 0 ND 0 8.54E-01 5.05E-01 8.4E-01 5.57% ND 0 B1-212 ND ND ND ND E6-214 ND 0 ND 0 1.11E+00 2.40E-01 1.11 E+00 t ND 1.34E+00 2.40E-01 1.34E+00 10.45%

Ra-226 ND ND ND Ac-228 D. ND ND NDD Th-234 ND ND ND U-235 ND ND ND ND Am-241 ND ND ND CM-243 ND ND ND ND Cm-245 ND ND ND 8.17E+03 100.00% 4.37E+03 3 tO.00% 1.53E+01 100O.00% 1 .28E+01 100.00%

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(

Adder( I Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory

( ;Ca§ (agesot16 f

CORE BORE #11, Hot Laboratory 0 ft (0 Inch to 1 Inch)

,MC900010111FL1C1L0511-01 1ST PUCK csooo1o1nIFLICIL051 11-iA 15T PUCK C9oC00101FL1C1Lo01 1-02 2CND PUCK VC900I01HflL1C1L0511-02A 2CND PUCK OJINCHDEPTH 1/2.NCH DEPTH 112-NCH DEPTH 1.NCH DEPTH Rssuls MDA Used  % ztults MDA Used .% .sutts MDA Used  %

K-40 Resulb MDA Used  %

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 Cs-137 1.29E+03 ND 1.46E+00 1.29E+03 97.3S% 6.59E+02 1,22E+00 6.59E+02 98.1 8% 1.39E+01 5 2.72E01 1.39E+01 5267% 1.18E+01 3.31E-01 1.1SE+01 4344%

Eu-1 2 ND iND NDND Eu-154 4.71 E+00 ND

" 3.67E+00 4.71 E+00 0.36% ND 0 DND T1-208 '%ND 0 ND 0 ND ND NO .

Pb 212 M 2.79E+00 ND 0 ND 0 D Pb-214 0 9.33E-01 5.29E-01 9.33E-01 3.43%

'. 3.69E+00 0 ND 0 21*\I%~RND 1 45E+00 5.13E-01 1.45E+00 5.52% 1.03E+00 7.41E-01 1.03E+00 3.80%

61212 ND 0 ND 0 0 ND 0 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 1.32E+03 100.00%

ND '

6.71E+02 100.00%

D ~ND 2.64E+01 100.00 2.72E+01 100.00%A with Cs-137

Attact(

Addend m 2 4

Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Site Laboratory (7 C A09 7 of116 CORE BORE #11, Hot Laboratory O t (1 Inch to 2 Inch)

.C900010111FL1C1L05111-03 3RO PUCK C9000101 FLICILO51103A 3RD PUCK UC1iO5111-04 4TH PUCK RC90OO101MFPLC1L0511-04A 4TH PUCK

.1.NCH DEPTH 112-INCHDEPTH EPTH ~2.INCH DEPTH

'Results MDA Used  % *Results iPDA Used  % MDA Used  % `Resulbt MDA Used 'A K-40 0 8.38E+00 2.13E+00 0.38E+00 0 0 Co-GO0 0 nk0 0 0 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 1.52E+00

• 2.06E-01 1.52E+00 47.92% 1.27E+00 2.46E-01 1.27E+00 37.25%

Eu-i152 Eu-i 5 0 0 0 0 T1-208 Pb-212 O' 0 0 5.03E-01 3.84E-01 5.03E-01 15 87%A 0 Pb-214 t.02E+00 5.60E-01 1.02E+00 20.32% 1.31E+00 4.58E-01 1.31E+00 I.1 E+0CI 4.16E-0,i 1.155+00 36.21% 1.1SE+00 5.19E-01 1.15E+00 33.59%

B1-212 0 2.94E+00 1.97E+00 2.94E+00 0 0 61-214 7.92E-01 2.43E-01 7.92E-01 15.73% 7.48E-01 4.09E-01 7.48E-01 0 9.96E-01 3.17E-01 9.96E-01 29.17%

Ra-226 Ac-228 0 8.22E-01 6.06E-01 8.22E-01 0 0 Th-234 U-235 Arn-24i 0 0 0 0 Cm-243 Cm-245 5.03E+00 100.00% 1.75E+01 100.00%: 3.17E+00 100.00% 3.41E+00 100.00%

1 inch 1 1/2 Inch 1 1/2 inch 2 Ih

' / r.

25 Fco-GoI 1Eu-1541 IWPb.214) 61214 DEPTH without Cs-137

Attac4 Addenf. 2 4

C ( age8 of 16 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 C9000110111FLICIL(51202 2CND PUCK C9000101HIFLIC10512-02A 2CND PUCK 0.NCH DEPTH 12 INCH DEPTH /112-INCH DEPTH 1-INCH DEPTH MR1sult MDA 1 Used  % RI ults MDA Used  % Results MDA Used K-40  % Results MDA Used  %

1.31E+0l Z.62E00 1.31E.O0 4.16% 1.49E+01 3.83E+00 1.49AE01 7.13%0 1.00E+01 2.11E+00 1.002E01 71.84% 9.16E+00 2.11 E+00 9.16E+00 79.06%

Co-60 1.76E201 2.66E-01 1.762+01 5.57% 's 1 26E*01 2.66E-01 1.26E+01 6.02% 2.15E-01 0 ND 0 Nb-94 ND 0 I .38E-1 1.85E.01 5.38E-01 0.26%M 1.49E-01 0 ND 0 Ag-108m D ND ND ND Cs 137 2.81E+02 9.32E-01 Z81E.02 89.02% 1.76E+02 9.92E-01 1.76E202 84.37% 284E-01 1.40E-01 2.84E-01 2.04% ND 0 Eu-152 D ND ND ND Eu-154 ND ND ND ND TI-208 ND I ND ND Pb-212 NO ND 0 ND 0 5.61 E-01 3.46E-01 5.61 E201 4:02% ND 0 Pb-214 ND 0 2.87E+00 2.26E+00 0 t.38E+00 5.84E-01 1.38E200 9.88% 1.06E+00 4.13E-01 1.06E+00 9.13%

61-212 ND0ND ND ND 81-214 ND 0 24E+00 1.24E+00 2.54E+00 1.21% .1.71E+00 4.24E-01 1.71E+00 12.22% 1.37E+00 4.06E-01 1.37E+00 11.81%

Re-226 ND ,ND ND ND Ac-22a ND ND ND ND Th-234 ND ND ND ND U-235 ND ND ND Am-241 ND 3.92E+00 1.732+00 3.92E+00 1.24% 2.112E00 1.53E+00 2.11E+00 1.01 ND ND 0 Cm-243 ND NO ND Cm-245 ND ND ND 3.162E02 100.00% 2.09E+02 100.00% 1.40E+01 100.00%- 1.16E+01 100.00%I 0 hich 1/2 Inch 1/2 inch I Inch I I/./

1,z IINCHI 1/2 INCH I 20 18 16 14 12 -K40 I, E \ . Nb94 U 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 IC C age 9of 1e CORE BORE #13, Hot Laboratory 0 ft (0 Inch to 1 Inch)

C0900010111PFLIC3L0513-01 1STPUCK *C300010111FULC1L0513-01A 1STPUCK %IC9000101HIFLC1L0513-02 2CND PUCK 0C900010111FL1C1L0513-02A 2CNDPUCK

-0NCHDEPTH 112INCH DEPTH 1I2 NCH DEPTH Resulb MOA tZsed .N-ICHDEPTH

% bIts MDA Used  % Results MDA Used K-40 § 1.87E601  % Resulb MDA Used  %

2.70E+00 1.87E+01 0.54% 1.28E+01 2.70E000 1.28E+01 0.53% 9.42E+00 2.24E600 9.42E+00 63.89% 7.90E+00 2.24E+00 7.90E+00 63.50%

Co 60 1.28E+00 2.75E.01 1.286E+00 0.04% 8.12E-01 2.75E-01 8.12E-01 0.03% ND 0 ND 0 Nb-94 ND 0 MND 0 Ag-1 00m 2.37E-01 1.58E-01 2.37E001 1.61% ND 0 ND I ND Cs 137 3.41E+03 2.92E+00 ND 3.41E+03 99.17% 2.40E+03 2.77E+00 2.40E+03 99.44% 1.75E+00 1.48E-01 Eu-i 52 1.75E+00 11.87% 1.09E+00 1.48E-01 1.09E+00 8.73%

ND .NO ND ND Eu-154 ND NO ND ND TI-208 ND 0 ND 0 ND 0 ND 0 Pb-212 ND 0 ND 0 ND 0 7.00E-01 4.55E-01 7,00E-01 Pb-214 ND 0 ND 5.63%

0 1.56E+00 6.00E-01 1.56E600 10.55% 1.16E+00 6.05E-01 1.16E000 BI-212 ND ND 9.31%

ND ND B1-214 ND 0 ND 0 1.78E+00 4.04E-01 1.78E+00 12.08% 1.600+00 2.56E-01 1.60E000 12.83%

Ra.226 ND 0 ND 0 ND 0 ND 0 Ac 22S ND ND ND ND Th 234 ND ND U-235 ND ND ~NO ND ND Am-241 8.58E600 4.49E+00 Cm-243 ND 8.58E000 0.25% ND ND

• 0 NO ND 0 ~ND 0 Cm-245 ND ND ND ND ND 3.44E+03 100.00% 0 2.42E+03 100.00% 1.4SE+01 100.00% 1.241+01 100.00%

0 Inch 1/2 rich 1/2 Inch

, ich

//

1/2 INCH with Cs-137

Attaclh Addentd n 2 A

Preliminary Analysis of Concrete Core "Puck' Samples by the On-Site Laboratory r C.go 10 of 16 CORE BORE #13, Hot Laboratory 0 ft (1 Inch to 2 Inch)

§i CSo000101HnFL1 C3L051J-03 3RO PUCK CS0001o1nIFLIC1L.0513-03, 3A 3FRDPUCK 9C3OOO1011PL1C1LO513-04 4TH PUCK C00101IFILIC110513-04A 4TH PUCK

$ 1-;NCH DEPTH 1 tIZ tNCH DEPTH i 11/2-INCH DEPTH 1\lResults MDA Used z.NCH DEPTH

%¶ Results m

MDA Use d  % Results MDA Used ¶ K-40 1.33E+01 2.1E+00 Results MDA Used  %

1.33E+01 78A3% 1332+01 2.1SE+Ot Co-60 "iik0 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%

Nb-94 Ag-108m O 00 0 Cs-137 i 6.01E01 2.20E-01 6.01E-01 3,54% 5.39E-01 1.97E20' Eu-152 .z 5.39E-01 2.46% 7.212-01 1.40E-01 7.21E-01 4.52% 0 Eu-1 54 .

TF-208 0 4,18E-01 1.79E-0 4.18E-01 1.91%; 0 Pb 212 6.152-01 4.66E-01 6.15-E01 3.62% 8.76E-01 0 3.9-0 8.76E-01 4.00% 6.91E-01 4.76E-01 6.91 E-01 4.33%

Pb-2142 1.342+00 4.85E-01 1.34E+00 5.92E-01 3.27E-01 5.92E-01 4.82%

7.91% 9.57E-01 4.27E-0 9.67E-01 4.42% j 9.57-01 5.26E-01 B2-212 ~§. 9.s57E-1 600%A 1.492+00 4.44£-01 1.49E200 12.17%

Bl-214 Ra-226 1.10E+00 4.55E-01 1.1000 0

6.50%0 7E+00 75 4.30E+O00 5.78E+00 0 1.84E+00 0.4177 1.4E2+00 11.55% 1.04E+00 3.212-01 1.04E200 8.43%p 26.40% 0 0 AC-228 Th-234 U-235 Ani241 :g O 20 1 0 Cm-243 n 0 1 0 Cm-245 1.70E+01 10.00% 2.192+01 100.00% '¶1.602+01 100.00% 1,202.01 100.00% hl 2 inchI 1 1/2 Infh

.. 2, Inch 1/2 INCH 1/2 INCH without Cs-137

Attachf Addendum 2 C ( eli of16 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 C900010111FL1C1L0514-02 2CND PUCK C*0001101ILIC1L05114-02A 2CND PUCK O-INCH DEPTH 1/21NCH DEPTH hM1/2-INCH DEPTH

~ Results MDA Used X lResults MDA Used  % Results MDA Used  %

IINCH DEPTH sulb MDA Used  %

K-40 1.77E+01 2.29E+00 1.77E501 0.82% Jl 7.58E+00 0 1.54E*01 2.1SE+00 1.54E+01 61.13% 9.77E+00 +/-185+00 9.77E+00 77.26%

Co-60 7495+00 Z325-01 7.49E00 0.35% 4.735E00 2.32E-01 4.73E+00 0.37% 2.23E-01 Nb-94 0 2.98E-01 2.22E-01 2.98E-01 2.36%

8.98E-01 5.26E-01 8.98E-01 0.04% 8.635-01 3.77E-01 8.63E-01 0.07% 1.89E-01 0 1.54E-01 0 Ag9OSm ND gND kZND NOD Cs.137 214E503 2.01E+00 2.14E+03 98.80% 1265+03 1.94E+W 1.26E+03 99.56% 1.825-01 0 1A44E-01 0 Eu-152 ND .ND ND Eu-164 ND ND N ND Ti-208 ND ND NO ND Pb-212 ND ND 0 ND 0 4.995-01 3.44E.01 4.99E-01 1.98% 3.72E-01 Pb.214 ND 0 0 ND 0 1.39E+00 3.34E-01 1.39E+00 5.51% 1.115+00 B1-212 6.14E-01 .11E+00 8.78%

ND ND ND Bi-214 ND ND 0 ND 0 1.68E+00 3.49E-01 1.68E+00 6.66% 1.47E+00 6.14E-01 Ra-226 ND 1.47E+00 11.60%

0 NO 0 6.22E+00 4.76E+00 6.22E+00 24.71% 6.19E+00 Ac-228 ND 0 NO ND ND Th-234 ND ND ND U-235 ND ND ND Arn-241 ND ND ND ND Cm-243 D ND D ND ND Cm-245 ND D 1 ND ND 2.17E+03 100.00% 1.265+03 100.00% 2.62E+01 100.00% 1 .26E+01 100.00%

0 inch 1/2 Inch 1/2 Incsh kincch I

1/2 INCH 1 1/2INCH withl Cs.137 without Cs-137

Attact Addenbi.. 2 4

Preliminary Analysis of Concrete Core 'Puck' Samples by the On-Sit. Laboratory C1 ( je12 of 16 CORE BORE #15, Hot Laboratory Oft (OInch to 1 inch)

~:C900010111FULC1L0515.01 1STPUCK C900010111FLC110515.01A 15TPUCK .C900010i1tFL1C1L0515-02 2CNDPUCK MC900010111PL1C1L051b02A 2CND PUCK A.0-6NCH DEPTH , /2-NCHKDEPTH 112U4NCH DEPTH 1-NCH DEPTH Resulb MOA Used  % *sulb MOA Used  % Results MDA Used  % *ItsuIIS K-40 Co-060 1.29E+01 7.20E.01 2.50E+00 5.02E-01 1.29E+01 0.13%; ~1.76E601 2.49E+00 1.76E+01 0.22% 1.406+01 2.10E+00 1.40E+01 46.13% 1.33E+01 MDA 2.10E+00 Used 1.33E+01 53.78%

7.20E+01 0.72% 536E+01 2.53E-01 5.36E+01 0 68% a869-E01 2.13E-01 Nb-94 ND 8.69E-01 2.87% 8.84E-01 2.13E-01 8.84E.01 3.57%

0 1.10E+00 8.53E-01 1.10E+oo 0.01 % ND Ag-1 0 NmD 0 .ND 0 D ND Cs 137 9.87WE+03 99.05% 7.79E+03 4.90E+00 7.79E+03 98.99f 1.40E+01 4.53E-01 1.40E+01 46.41% 8.28E+00 2.94E-01 8.28E+00 33.40%

Eu-152 ND D ND ND Eu-154 ND D ND ND TI-208 DN 0 ND 0 ND 0 Pb-212 ND 0 ND 0 ND 0 ND, 0 Pb-214 ND 0 ND 0 1 39E+00 6.27E-01 1,39E+00 4.59% 1.24E+00 7.66E01 1.24E+00 4.99%

B1-212 ND ND ND ND Bi-214 ND 0 ND 0 ND 0 1.06E+00 6.656-01 1.06E+00 Ra-226 ND 4.26%

ND ND ND Ac-228 ND ND Th-234 D ND ND ND U-235 ND ND NO ND AM-241 9.63E+00 6.17E+00 ND.

9.63E+00 0.10% 7.106+00 6.51E+00 7.106+00 0.09% ND Cm-243 ND 0 ND 0 ND ND Cm-245 ND ND ND ND 9.96E+03 ND 100.00% 7.87e603 100.00% 3.03E+01 100.00% 2.48E+01 100.00%

. 1/2kich with Cs 137

Attac -

Addenf... 1 2 Preliminary Analysis of Concrete Core TPuck' Samples by the On-Site Laboratory C C7~ge 13 of II CORE BORE #15, Hot Laboratory.0 ft (1 Inch to 2 Inch)

• C900O10i1iPL1C1L0515-03 3RD PUCK CS000101 nPFUC1L0515-Ol A 3RD PUCK C900010111FL1C1L0515-04 4TH PUCK tCS000101iIFL1C1L0515-04A 4TH PUCK V1-NCH DEPTH 1 112.NCH DEPTH I 1121INCH DEPTH 1 2-INCH DEPTH 0ZResuIto MDA Used  % sResulbs MDA Used  % ~ Results MDA Used  % *Resulb MDA Used  %

K-40 0o60 ND 9.23E+00 1.79E+00 9.23E+00 0

79.00% ND 0 .. ~ 1.15E+00 2.36E+00 1.15E+00 21.46%i 1.15E+00 2.36E+00 1.15E+00 21.46%

ND 0 NO 0 BND 0 Nb-94 -ND 0 ND 0 ND 0 MND 0 Ags-108m ND IND ND ND Cs-137 3.22E-01 1.18E-1 3.22E-01 Z75%A 6.31E 01 1.18E-0'1 5.31E-01 21.71% 5.95E-1 1.56E-1 5.95E-01 11.05 5.9E-01 1.56E-01 5.95E1 11.05%

Eu-152 'LND ND ND MND Eu 154 ND D ND TI 208 IND ND 0 Z53E-1 1.70E4-41 2.532-01 10.35% ND 0 ND 0 Pb-212 ND 0 D 0 7.17E-01 5.33E-01 7.17E-01 13.32% 7.17E 01 S.33E-01 7.17E201 13.32%

Pb-214 1.24E+00 4.83E-01 1.24E+00 10.61% 1.25E+00 3.18-E4 41 1.25E+00 51.11% 1.19E+00 6.04E-01 1.19E+00 22.1B 1.19E+00 6.042-01 1.19E+00 22.18%

B212 ND ND ND El 214 ND 8.92E41 2.93E41 8.92E41 7.63% 4,11E41 2.04E1 41 4.11E-01 16.83% 1.72E+00 2.70E-01 1.72E+00 31.98% 1.72E+00 2.70E-01 1.72E+00 31.98%

Re-226 ND ND ND ND Act228 ND ND ND Th-234 ND ND D ND U-235 ND ND ND Amr-241 ND ND 0 NO 0 D 0 ND 0 Cr-243 ND ND ND Cm-245 ND ND 2D ND 1.17E+01 100.00% 2.44E+00 100.00% 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 C ( je 14 of I CORE BORE #16, Hot Pipe Tunnel, 412 t C90001OIrLIC1Lo.516-O1 1STPUCK NC9O00101nFuLC1L051 6.01 A 1ST PUCK RC9000101I1FPLC1L0516402 2CND PUCK "C90001011PL1C1L0516-02A 2CND PUCK O-NCH DEPTH M112-NCH DEPTH /112-NCHDEPTH I-INCH DEPTH

%Results MDA Used  % 1Rteults MfDA Used  % ults MDA Used  % . Reults MDA Used  %

K-40 1.32E-01 1.95E+00 1.32E+01 2.15% 4 9.26E+00 1.95E+C0 9.26E*00 2.46% 8.84E+00 2.10E+00 8.84E+00 70.20%1 1,17EE01 2.10E+00 Co-60 2.10E+01 1.98E-01 2.10E+01 3.41% 1.28E+01 1.17E+01 77.73%

1.98E-O41 1.28E+01 3.39% 2.14E-01 0 Nb-94 ND 2.14E-01 0 NO Ag-1 08m ND ND MD ND Cs 137 5.82E+02 1.39E.00 5.82E+02 94.45% 3.53E+02 8.79E-C01 3.53E+02 93.47% 6.17E-01 2.54E-01 6.17E-01 4.89% 8.12E-01 2.27E-01 Eu-152 ND ND 8.12E-01 5.39%

ND ND Eu-154 ND ND ~NO ND Tl-208 Pb-212 ND

• ND 0 ND D

~NO ND 0 6.82E-01 4.07E-01 6,82-01 5.42% 5.55E-01 Pb-214 kND 0 ND 0 0 8.59E-01 5.50E-01 8.59E-01 6.82%A 1.37E+00 5.43E-01 1.37E+00 Bl-212 ND NO 9.12%

END ND El 214 ND 0 2.57E+00 1.35E+O00 2.57E+00 0.68% 1.60E+00 2.40E-01 1.60E+00 12.67% 1.17E+00 3.58E-01 Re-226 D ND 1.17E+00 7.76%

ND ND Ac-228 ND ND ND ND Th-234 ND ND ND U 235 ND ND 1D ND ND Am-241 ND .ND ND ND Crm-243 ND ND ND .ND Crm-245 ND ND ND ND 6.16E+02 100.00% 3.772+02 100.O0%~ 1.26E+01 1 100.00%. 1.50E+01 100.00%

wlth Cs-`1Jr without Cs-137

AttaciC Addendtm 2 4

Preliminary Analysis of Concrete Core "Puck" Samples by the On-Site Laboratory C l.ge 15 of 16 CORE BORE #17, Fan House, -12 ft

. OIC90001011FL1CL0517-01 1STPUCK C9000101NFL1C1L0517-01A 1STPUCK Z oC800011HP1L1C1L.517-02 2CND PUCK ct8 1011FLCC1L.016-02A 2CND PUCK 0lo-NCHDEPTH 1/2-NCH DEPTH " 12-INCHDEPTH

§ Result MDA DEPTH s1-N1CH Used  % *Rsults MDA Used  % 'Results MDA K-40 Used  % Results tDA Used 'A 1.70E+01 2.46E+00 1.70E+01 65.69%*M 1.UE4+01 2.46E+00 1.54E+01 74 32% 1.390+01 2.27E+00 1.39E+01 46,03% 1.57E+01 2.27E+00 1.57E+01 Co060 ND ND 89.44%A4 ND Nb-s4 ND ND ND Ag91osm ND NO 1 .9OE-01 ~~ND ND Cs-137 9.95E-01 1.63E-01 9.95E-01 3.83% t.885E-01 1.63E-01 8.85E-01 4.28% 4.4SED01 1,50E-01 4.4SE-01 1.49% 3.68E-01 Eu-152 ND 0 ND ND ND Eu-154 ND ND ND ND T11208 ND ND Pb-212 6.68E-01 5.552-01 6.68E-01 2.58% 8.81E-01 4.85E-01 8.81E-01 4.26% 6.62E-01 5.11 E-01 6.52E-01 2.17 7.25E-01 6.56E-01 7.255E-1 Pbt214 1.87E+00 7.01E-01 1.87E+00 7.21% 1 792E00 4.13%

6.30E-01 1.79E+00 8.65% 1.34E+00 5.27E501 1.34E+00 4.46% 9.64E-01 BN212 3.71E+00 2.28E+00 4.77E-01 9.64E501 5.49%

3,71Eo00 14.29% ND 0 ND B1214 0 ND 0 1.66E+00 6.272-01 1.66E+00 6.40% 1.76E+00 2.81E-01 1.76E+00 8.49% 9.61 S-01 4.09E-01 9.61 E-01 3.1 1.652-01 2.59E-01 1.65E-01 0.94%

Ra-226 ND 0 e~ND .O0 5.65E+00 5.38E500 6.65E+00 18S77% ND 0 Ac-228 ND 0 ND 0 1.12E+00 645E-01 1.12E+0o 3.70 NO Th-234 ND 0 ND o 0 6.08s+00 6.00E+00 6.08E+00 20.20% ND 0 U-235 ND ND ND NO Am-241 ND N Cm-243 D ND ND ND ND ND Cm-245 ND ND ND ND 2.60E+01 100.00% 2.07E+01 100.00% 3.01E+01 100.00% 1.76E+01 100.00%

0 ich 112IWch 1/2 Inch I hich

/.

1/2 INCH 1 1/2INCH I 10

-K04 14 Ei' s 2 . .. rm.FR-2 12 13-c31i4 SO.1.

4.2121 614 5 _

Th22l4 D-P.,-

ft.

0

= ~ 0.5 0.0 1

Attac(

Addenbu 2 A

Preliminary Analysis of Concrete Core "Puck' Samples by the On-Site Laboratory C C ge 16 of 16 CORE BORE #21, ROLB Fuel Vault

%C900010111FL1C1L0521-01 1STPUCK C900010111FLICL0521.01A 1STPUCK '.C900010111FL1C1L0521-02 2CND PUCK O.N-ICHDEPTH C900010111FL1C1L0521-02A 2CNDPUCK

/12-NCH DEPTH M 112-tNCHDEPTH k,,-NCH DEPTH

,Rosults MDA Used  % ,Resutts MDA Used R sults MDA Used lRosult MDA Used  %

K-40 M 1.50E+01 2.21 E+00 1.50E+01 84.76% I 59E+01 2.21 E+00 1.59E+01 81.31%- 1,33E+01 2.08E+00 1.33E+01 84.59% k 9.65E+00 2.98E+00 9.65E+00 Co-60 ND 87,04%

I ND ND Nb-94 DND ND ND Ag-t 03rn ND ND ND Cs-1 37 , ND 0 2.38E-01 1.46E-01 2.38E-01 1.22%A ND 0 IN 3.05E-01 1.93E-01 3.05E-01 2.75%

Eu-I 52 ND ND ND Eu-I 54  %'ND NO ND ND TI-208 ND Pb-212 ND 0

0 349E-01 6.53E-01 2.66E-01 5.68E-01 3.49E-01 6.53E-01 1,78% ND 3,34% 5.26E-01 0 ~ND 4.71 E-01 5.26E-01 3.35% ND 0 Pb-214 1.39E+00 6.69E-01 1.39E+00 7.85% 1f.06E+00 4.75E-01 1.06E+0O 5.43% 1.024E00 5.06E-01 1.02E+00 6.51 X ND 0 BI-212 ND ND ND ' ND BW-214 1.31E+00 4.05E-01 1.31E+00 7.39X 1.35E+00 5,85E-01 1.35E+00 6.92% 8.70E-01 4.55E-01 8.70E-01 5.55% 1.13E+00 3.62E-01 1.13E+00 10.21l%

Ra-226 ND ND ND Ac-228 ND ND ND Th-234 ND NO ND ND U-235 ND ND ND 1D AM-241 ND ND ND CM-243 ND ND NNDD Cn-246 ND ND ND

1. ND 1.77E+01 100.00% 1.95E+01 1 100.00% 1.57E+01 100.00%~ 1.112+01 100.00%A 0Oc 1/2 lrch 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

Page 1of`3 Attachment A, Addendum 3 Results of Isotopic Analysis of Concrete Core Samplias S:;CTMT-25n, CanalE SEArea IRxldg-1 ,ft gRxBldg.25ft,Area22 Core Location 15 *ZCoreLocation 6 Core Location 37

.fC90001011FL1C3L0506-01 MC90O01O1IFLUC1 L0507-01 j C900101 IFLICI O505-01 MDC Used Disributlon Result MDC Used Disributlon Result MDC Used Disribuilon Result qCl/gm rjCllgm pCligm Y. , Clgm pCI/gm pCI/gm

• x p PCUgm CClgm PCl/gm Y 260% 6 40E+00 5.10E+00 6.40E+00 4.07% 3.00E+00 5.20E+00 6.20E+00 15.33%

H-3 -4.90+00 5.20E+00 6.20E+00 1A3% > .17E+02 ZOOE-01 1.17E+02 74.32% 7.20E01 1.10E-01 7.20E-01 212%

Cs-137 286E+00 1.70E-1 Z8E+00 0.71%

5.65% 2.21E+00 1.20E-01 221E+00 1.40% 1.40E-01 2.40E-01 2.40E1 Co-60 1.13E+01 1.00E-01 1.13E+01 33.48% 1.80E+00 1.20E+01 1.20E+01 7.62% 4.40E401 1.30E+01 1.30E+01 38.33%

Fe-55 1.70E+01 6.70E+01 6.70E+01 53.47% 1.19E+01 1.30E+01 1.30E+01 8.26% 8.30E+00 9.80E+00 9.80E+00 28.89%

Ni-63 ,ii 1.07E+02 Z70E+01 1.07E+02 1.03% 4.60E-01 4.40E-01 4.60E401 0.29% 400E-02 5.70-E1 5.70E-01 1.68%

Sr-9O 2.07E+00 6.40E-01 2.07E+00 0.03% 8.50E-02 Z90E-02 8.50E-02 0.05% 600E-03 5.302-02 5.30E-02 0.16%

Pu-23S 4.10E2-02 6.90E-02 6.90E-02 0.03% 1.90E202 4.70E-02 4.70E-02 0.03% 1.00E-02 2.80E202 2.80E-02 0.08%

Pu-239/240 2.70E-02 5.40E-02 5.40E-02 1.30% 1.20E+00 Z80E+00 2.80E+00 1.78% -2.00E1 Z502+00 2.60E+00 7.37%

Pu-E241 6.002-01 Z60E+00 2.60E+00 1.00E-01 0.29%

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 Am-241 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%

Crn-2451246 5.00E-02 3.90E401 4.00E-2 7.20E-1 2.12% f 6.40E-01 9.00E-02 6.40E401 0.32% 7 50E-01 3.00E-02 7.50E-01 0.48% 7.202-1 U-234 0.05% .130E202 3.40E-02 3AOE-02 0.02% 2.90E-02 7.70E-02 7.70E-02 0.23%

U-235 1.10E-01 7.70E-02 1.102E1 0.31% 8.80E-01 3.00E22 8.80E-01 0.56% 7.80E.01 6.00E-02 7.80E-01 2.30%

U-238 .. 6.20E-01 4.00E-02 6.20E01 1.57E+02 100% 3.39E+01 100%

zOOE+02 100%

Waste Handling Bldg -15 ft Hot Pipe Tunnel,-12ft

,..CTMT -25 ft, Area 18 .

,Core Locatlon #10 Core Location 415

.Core Location #9 C9000..1IFU C3L050741 ..C9.000oIFUC1i055-01.

xgC90001 1IFLI C310509-01 Result MDC Used DWsribution <.

i:K: Result MDC Used Dlsributlon Result MDC Used Dlsributlon ...

PCI/m PCIgm  % opCUIgm pCIgm pC/gm' ¶ f pCI/gm pCVpgm PCmqm PC[/gm p 5302+00 0.09%

• ,'i 1.11E+01 28.99% 2.70E+00 5.30E+00 5.30E+00 0.17% 1.60E+00 5.302+00 H-3 1.11E+01 5.10E+00 4.43E+03 76.87%

8.002-2

-6.10E-1 6.102-1 1 59% 3.15+03 8.00E-01 3.15E+03 98.90%  : 4-43E+03 1.00E+00 Cs-137 2.69E+01 0.47%

Z10E-1 2.32E201 0.61% -3.30E-02 1.10E-01 1.10E-01 0.00% .Z69E+01 3,002E01 Co-so . 2.32201 K:s 3.30E+00 1.40E+01 1.A0E+01 0.44% 1.90E+01 1.70E+01 1.90E+01 0.33%

Fe-55 3.10E+00 1.30E+01 1.30E+01 33.96%

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%

NI-63 -4.10E+00 1.102+01 17.52%

1.18% 1.20E+00 4.80E-02 1.20E+00 0.04% x,.. 1.01E+03 1.00E+00 1.01E+03 Sr-40 4.00E-0 4.51 4. 4.60E-01 1,90E-02 4.80E-02 4.80E-02 0.00% 6.59E+00 5.00E-02 6.59E+00 0.11%

Pu-238 O.OOE+OOO.0OE+00 O.OOE+00 0.00%

1.0-02 3.00E-02 3.00E-02 0.00% 7.58E+00 3.00E-02 7.58E+00 0.13%

Pu-239/240 O.OOE+OO6.00E-02 6.00E-02 0.16%

008% -5.002-1 2.90E+00 2.90E+00 0.09% 7.47E+01 2.70E+00 7.47E+01 1.30%

Pu-241 -ZOOE-23.002-2 30 0-0E2 0.52% 6.00E203 1.00E-01 1.00E-01 0.00% 1.30E+01 3.00E-01 1.30E+01 0.23%

Am-241 0.OOE+00 2.00E-01 2.00E2-1 040% 4.40E-02 8.70E-02 8.70E-02 0.00% 6.95E+00 1.60E-01 6.95E+oo 0.12%

Cm-245/246 1.554-01 9.40E-02 1.55E-01 7.00E-02 1.28E+00 0.02%

7.00E41 4.00E42 7.002-1 1.83% . 502-1 8.00E42 5.OE0-01 0.02% 1.28E+00 U-234 9.102-02 9.102-02 0.00% i 1.7020 4.70E-2 4.70E-2 0.12% 530E-2 4.80E-02 5.30E-02 0.00% 9.00E-02 U-235 1.83% 5.OOE-01 4.00E-02 5.OOE-01 0.02% 9.10E201 7.002-02 9.102-01 0.02%

U-238 .. 7.00201 4.00E-02 7.00E401 3.83E+01 100% 3.182+03 100% 5.76E+03 100%

Hot PipTunnel,4-12 It K'Fan House .12 ft Core Location #17 BALANCE OF PLANT CORE RESULTS

Core Location #16

,-sC9000101IFLICI L051O641 B-C9000101IFLICILD517.Oi Disribuflon Result MDC Used Disribution MEAN MEAN STD DEV Result MDC Used

% pCi/gm pCmgm PCIm  % (pC[/gm) (-/4 pCIgm PCI/gm PCV/gm 0.44% 6.20E+00 5.30+00 6.202+00 15.99% 1H-3 6.24E+00 8.46% 10.57%

H-4 2.10E+00 5.20E+00 5.20E+00 22.04% 4.10E-01 9.00E-02 4.10E-01 1.06% Cs-137 9.95E+02 34.79% 41.45%

Cs-137 2.60E+02 4.00E-01 2.60E+02

-2.70E202 1.10E-01 1.10-E01 0.28% Co-60 6.26E+00 1.23% 1.83%

Co-40 8.97E+00 240E201 8.97E+oo 0.76% 18.93% 17.89%

IAOE+01 1-19% -2.40E+00 1.40E+01 1.AOE+01 36.11% Fe-SB 208E+01 Fe-SS 8.202+00 1.40E+01 4.24% .4.00E+00 1.202+01 1.20E+01 30.95% 1Ni-63 4.67E+01 19.71% 18.76%

Ni-63 5.00E+01 Z50E+01 5.00E+01 24.60%

70.87% O.OE+OO 5.00E-01 .OOE-01 1.29% Sr-Do 2.31E+02 11.74%

Sr-go 8.36E+02 2OOE+00 8.36E+02 0.06%

005% 6.00E-03 5.90E-02 5.90E-02 0.15% Pu-238 9.33E-01 0.07%

Pu-238 1.70-E02 5.60E-1 5.80E41 1102-02 3.10E-02 3.10E-02 0.08% Pu-239/240 9.88E-01 0.06% 0.06%

Pu-2391240 7.30E-02 5.80E-02 7.30E202 0.01% 3.19%

2.70E+00 0.23% .. 9.00E-01 3.00E+00 3.00E+00 7.74% Pu-241 1.14E+Ot 249%

Pu-241 1.902+00 270E+00 5.30E-02 5.30E-02 0.14% Am-241 1.932+00 0.29% 0.35%

Am-241 4.60E-02 6.70E-02 6.70E-02 0.01% ',,-9.00E-03 1.202-01 1.40E-01 1AOE4-01 0.36% CCm-245/246 1.00E+00 0.19% 0.17%

Cni-245/246 0.OOE+OO1.00-E01 1.00E-01 0,01%

0.08% 1.14E+00 4.004-02 1.14E+00 2.94% U-234 8.36E-01 0.98% 1.15%

U-234 9.102-01 6.00E-02 9.10E-01 001% 5.80E-02 ,10E-01 1.10E-01 0.28% 0U235 7.69E-02 0.09% 0.11%

U-235 a 6.50E-02 9.30E-02 9.30E-02 0.08% 1.02E+00 4.00E-02 1.02E+00 Z63%

• U-238 7.90E-01 0.97% 1.10%

U-238, a 9.10E-01 6.00-E02 9.102-01 1.18E+03 100% 3.88E+01 100% 100.00%

Attachment A, Page 2 of 3 Addendum 3 Results of Isotopic Analysis of Concrete Core Samples Hot Laboratory Oft Hot Laboratory Oft

• ";is iiHot Laboratory Oft Core Location 11 i Core Location 312 Core Location S13 C9000iO1iFLI CI LOSt 1-0 i1 IFLIC L0512-01

>f:BC9000101 1 C90001OIFUL1C3i0513-01 Result MDC Used Disribution 1 Result MDC Used Disributlon Result MDC Used Disribution l PCVmrn PCVgm pCltgmrn PClI/m iCI/om PClgrm 4 pClgm o pCLQm pCiIrm 'A H-3 0

-gOOE-02 5.20E+00 5.20E+00 0.50% 600E-01 5.20E+00 6.20E+00 1.82% 7.20E+00 5.40E+00 I7.20E+00 0.37%

-5.30E-01 8.80-E41 8.80E401 009% Z16E+01 1.30E+00 Z16E+01 7.57% 4.10E41 1.20E+00 11.20E+00 0.06% ii;iK C-14 KK 9.45E+02 5.002-01 9.45E+02 91.64% 1.13E+02 3.002-01 1.13E+02 39.60% N 1.71E+03 6.00E41 11.71E+03 88.43%

Cs-137 Co-O 1.82E+00 1.70E-41 1.82E+00 0.18% 5.79E+00 1.30E-01 5.79E+00 2.03% 2 70E401 1.70E41 2.70E201 0.01%

2.50E+01 5.20E+01 5.20E+01 5.04% 1A2E+01 1.20E+01 1.42E+01 4.98% lc-3.00+00 1.10E+01 11.10E+01 0.57%

Ni-63

. 1.18E+01 5.00E-1 1.18E+01 1.14% 1.08E+02 5.00E-01 1.08E+02 37.84% 193E+02 6.00E-01 11.93E+02 9.98%

Sr-0 3.90E-1 5.00E-02 3.90E-01 0.04% 4.80E-01 3.00E-02 4.80E-01 0.17% ' 6.50E241 9.00E-02 I6.50E401 0.03%

Pu-238 2.05E-01 290E-02 2.052E-1 0.02% 6.39E+00 600E-02 6.39E+00 2.24% 5.00E-01 4.00E-02 5.00E1 0.03%

Pu-2391240 2.20E+00 2.90E+00 2.90E+OO 028% 6.80E+00 3.10E+OO 6.80E+00 Z38% 4 70E+00 3.70E+00 44.70E+00 0.24%

Pu-241 K. 9.90E+00 9.00-E01 9.90E+00 0.98% 1.40E+00 1.90E-01 1.40E+00 0.49% 2.90E+00 1.00E+00 2.90E+00 0.15%

An-241 1.90E-01 8.00E-02 1.902-01 0.02% 6.OOE-01 1.20E-1 6.004-01 0.21% 3.80E401 1.20E-01 3.80E-01 0.02%

Cm-2451246 3.60E-01 6.00E-02 3.60E-01 0.03% 1.04E+00 3.00E-02 1.04E+00 0.367 960E-01 4.00E42- 9.60E-01 0.05%

U-234 e5.10i-02 9.00-03 8.90E-02 8.90E-02 0.01% 2Z80E-02 3.80E-02 3.80E-2 0.01% . 5.1-02 4.60E42 0.00%

U-235 ..

4A.4-01 6.002-02 4.40E-01 0.04% 8.50E-01 5.00E-02 8.50E01 0.30% 8.20E-1 4.00E-02 i820E1 0.04%

U-238 1.03E+03 100% Z85E+02 100% 1 .93E+03 100%

Hot Laboratory 0ft K<.:Core Location #14 HOTLAB CORE RESULTS C90001011FL1C3L0514-01 Result MDC Used Disribution MEAN MEAN STD DEV

. Cl/gm pC[/gm PCIIrm ¶4 (pCl/gm) Nl H-3 1.70E+00 5.20E+00 5.20E+00 0.62% H-3 5.70E+OO 0.83% 0.67%

C-14 -6.002E1 1.30E+00 1.30E+00 0.16%

• C-14 6.25E+00 1.97% 3.73%

Cs-137 7.75E+02 5.00E-01 7.75E+02 9248% Cs4137 8.86E+02 78.04% 25.69%

CO-60 3.12E+00 1.20E-01 3.12E+00 0,37% Co-60 2Z75E+00 0.65% 0.93%

Ni-63 1.10E+00 1.502+01 1.50E+01 1.79% f N-63 2.31E+01 3.09% 227%

Sr-90 3.30E+01 4.00E-01 3.30E+01 3,94% Sr-9O 8.65E+01 13.23% 16.82%

Pu-238 9.70E-02 4.90E-02 9.70E-02 001% Pu-238 4.04E-01 0.06% 0.07%

Pu-239/240 5.90E-01 3.00E-02 5.90E.01 0.07% Pu-239/240 1.92E+00 0.59% 1.10%

Pu-241 700E-01 7,OO Z80E+00 Z80E+00 0.33% Pu-241 4.30E+00 0.81% 1.05%

ArF-241 3.202E-1 3.004-02 3.20E-01 0.04% Al-241 3.S3E+00 0.41% 0.41%

Cm-245/246 1.07E-01 8.90E-02 1.07E-01 0,01% Cm-2451246 3.19E2-1 0.07% 0.10%

U-234 8.10E-01 7.00E-02 8.10E-01 0.10% U 234 7.93E401 0.14% 0.15%

U-235 :g 5.90E-02 7.40E-02 7.40E-02 0.01% U-235 6.30E-02 0.01% 0.00%

U-238 6.40E241 6.00E-02 6,40E-01 0.08% U-238 S.88E-01 0.11% 0.12%

8.38E+02 100% 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, Page 1 of 2 Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Sample CS013004-004 Sample CS013004-005 Spill Area 2400303C1 Spill Area 2400303C1 Surface Soils (1st 6") Surface Soils (1st 6")

(pCI/gm) (pCI/gm)

Result MDA Used Result MDA Used AM-241 1.822E-02 4.936E-02 4.94E-02 0.02% AM-241 1.648E-02 1.354E-01 1.35E-01 0.20%

AM243 1.347E-01 1.567E-01 1.57E-01 0.06% AM243 9.944E-02 8.982E-02 9.94E-02 0.14%

C-14 1.377E+0o 1.401E+00 1.40E+0O 0.58% C-14 1.435E+00 1.051E+00 1.44E+00 2.07%

CM-245 1.659E-01 1.590E-01 1.66E-01 0.07% CM-245 9.517E-02 1.556E-01 1.556E-01 0.22%

CO-60 9.387E-02 2.641E-01 2.641E401 0.11% CO-60 2.277E-01 2.486E-01 2.486E-01 0.36%

CS-137, 2.075E+02 4.241E-01 2.08E+02 85.26% CS-137 5.081E+01 2.355E-01 5.08E+01 73.42%

EU-155 1.052E-01 9.603E-01 9.603E-41 0.39% EU-155 6.000E-01 5.594E-01 6.OOE-01 0.87%

H-3 7A97E100 1.012E+01 1.012E+01 4.16% H-3 1.043E+00 9.755E+00 9.755E+00 14.10%

1-129 8.993E-01 6.558E-01 8.99E-01 0.37% 1-129 3.374E-01 3.883E-01 3.8832-01 0.56%

NB-94 3.835E-02 1.926E-01 1.926E-01 0.08% NB-94 -3.178E-02 1.259E-01 1.259E-1 0.18%

NI-63 5.589E-01 1.563E+00 1.563E+O0 0.64% NI-63 1.970E+00 1.836E400 1.97E+00 2.85%

PU-238 4.512E-02 1.092E-01 1.092E-01 0.04% PU-238 1.932E-02 5.234E-02 5.234E-02 0.08%

PU-239 1.811E-02 4.909E-02 4.909E-02 0.02% PU-239 9464E-03 1.165E-01 1.165E-01 0.17%

SR-90 1.990E+01 5.885E-01 1.99E+01 8.17% SR-90 3.200E+00 6.905E-01 3.20E200 4.62%

U-236 1.795E-02 4.866E-02 4.866E-02 0.02% U-236 1.482E-02 1.121E-01 1.121E-01 0.16%

2.43E402 100.00% 6.92E+01 100.00%

Sample CS013004-006 Sample CS013004-007 Spill Area 2400303C1 Spill Area 2400303C1 Surface Soils (1st 6") Surface Soils (1st 6")

(pC,/gm) (pCi/gm)

Result MDA Used Result MDA Used AM-241 4.326E-02 3.908E-02 4.33E-02 0.02% AM-241 O.OOOE+00 6.228E-02 6.23E-02 0.24%

AM243 6.588E-02 8.926E-02 8.93E-02 0.04% AM243 3.134E-02 7.924E-02 7.92E402 0.31%

C-114 6.130E-01 1.378Et00 1.38E+00 0.67% C-14 1.277E+00 1.379E+00 1.38E+00 5.34%

CM-245 7.752E-02 2.188E-01 2.188E-01 0.11% CM-245 2.589E-02 1.048E-01 1.05-E1 0.41%

CO-60 3.030E-02 2.529E-01 2.529E-41 0.12% CO-60 3.570E-02 1.939E-01 1.939E401 0.75%

CS-137 1.744E+02 4.606E-01 1.74E102 84.55% CS-137 9.349E+00 1.823E-01 9.35E+00 36.21%

EU-155 4.207E-01 9.052E-01 9.052E401 0.44% EU-155 1.401E-01 3.895E-01 3.895E-01 1.51%

H4-3 -1.411E-01 9.899E+00 9.899E+00 4.80% H-3 8.951E+00 1.029E+01 1.029E+01 39.87%

l1429 1.256E+00 6.032E-01 1.26EF00 0.61% 1-129 -9.881E-03 3.125E-01 3.125E-1 1.21%

NB-94 -1.763E-02 1.544E-01 1.544E-01 0.07% NB-94 -8.472E-03 1.630E-01 1.630E-01 0.63%

') NI-63 1.173E+00 1.641E400 1.641E+O0 0.80% NI-63 2.145E+00 1.499E+00 2.14E+00 8.31%

PU-238 8.891E-02 1.074E-01 1.074E401 0.05% PU-238 -1.245E-02 1.471E-01 1.471E-01 0.57%

PU-239 1.856E-01 6.289E-02 1.86E-01 0.09% PU-239 2.025E-02 1.129E-01 1.129E401 0.44%

SR-90 1.566E+01 6.545E-01 1.57E+01 7.59% SR-90 1.041E+00 6.891E-01 1.04E+00 4.03%

U-236 2.698E-02 6.822E-02 6.822E-02 0.03% U-236 3.381E-02 4.581E-02 4.581E-02 0.18%

2.06E+02 100.00% 2.58E+01 100.00%

Sample CS013004-008 Sample CS013004-009 Emergency Retention Basin Emergency Retention Basin Surface Soils (1st 6") Surface Soils (1st 6")

(pCI/gm) (PCI/gm)

Result MDA Used Result MDA Used AM-241 1.708E-02 1.403E-01 1.40E-01 0.20% AM-241 6.563E-02 9.722E-02 9.72E402 0.19%

AM243 5.986E-03 1.224E-01 1.22E-01 0.17% AM243 1.550E-01 5.999E-02 1.55E-01 0.30%

C-14 1.121E+00 1.445EFOO 1.44E+00 2.02% C-14 7.087E-01 1.331E+00 1.33E+00 2.59%

CM-245 -3.809E-04 1.406E-01 1.41E-01 0.20% CM-245 1.759E-01 1.039E-01 1.76E-01 0.34%

CO-60 7.355E-01 2.409E-01 7.36E-01 1.03% CO-60 8.647E-01 2.417E-01 8.65E-01 1.68%

CS-137 2.129E+01 2.536E-01 2.13E+01 29.76% CS-137 3.240E201 2.798E-01 3.24E+01 63.03%

EU-165 1.728E-01 4.628E-01 4.628E-01 0.65% EU-155 3.470E-01 5.541E-01 5.541E-01 1.08%

H4-3 4.298E+01 9.814E+00 4.30E101 60.08% H-3 3.006E+00 1.054E+01 1.054E+01 20.51%

1-129 1.526E-02 2.837E-01 2.837E401 0.40% 1-129 -1.874E-02 2.716E-01 2.716E-01 0.53%

NB-94 7.072E-02 2.582E-01 2.582E4-1 0.36% NB-94 5.722E-02 2.256E-01 2.256E-41 0.44%

Nl-63 2.700E+00 1.510E400 2.70E+00 3.77% NI-63 3.210E+00 1.496E+00 3.21E+00 6.24%

PU.238 1.485E-02 1.220E-01 1.220E-01 0.17% PU-i38 4.426E-02 1.445E-01 1.445E-01 0.28%

PU-239 2.250E-02 6.098E-02 6.098E-02 0.09% PU-239 -4.532E-03 1.233E-01 1.233E-01 0.24%

SR-90 7.010E-01 6.790E-01 7.01E-01 0.98% SR-90 1.161EF00 6.452E-01 1.16E+00 2.26%

U-236 4.074E-02 9.868E-02 9.868E-02 0.14% U-236 1.475E-01 4.995E-02 1.48E-01 0.29%

7.15E+01 100.00% 5.14E+01 100.00%

Attachment A, Page 2 of 2 Addendum 4 Results of Isotopic Analysis of Surface Soil Samples Sample CS013004-010 Sample CS013004-011 Emergency Retention Basin Emergency Retention Basin Surface Soils (1st 6") Surface Soils (1st 6")

(pCUgm) (pCigm)

Result MDA Used Result MDA Used AM-241 6.704E-03 1.371E-01 1.37E-01 0.12% AM-241 1.765E-01 1A37E-01 1.77E-01 0.24%

AM243 5.310E-02 1.343E-01 1.34E-01 0.12% AM243 1.039E-01 9.952E-02 1.04E-01 0.14%

C-14 1.210E+00 1A27E+00 1.43E+00 1.24% C-14 1.734E+00 1.524E+00 1.73E+00 2.34%

CM-245 3.384E-02 2.060E-01 2.06E-01 0.18% CM-245 1.124E-01 1.527E-01 1.53E-01 0.21%

CO-60 5.665E+00 2.814E-01 5.67E+00 4.91% CO-60 3.335E+00 2.693E-01 3.34E+00 4.50%

CS-137 5.424E+01 3.064E-01 5.42E+01 47.00% CS-137 3.616E+01 2.683E-01 3.62E+01 48.74%

EU-155 8.057E-02 5.829E-01 5.829E-01 0.51% EU-155 4.595E-02 4.476E-01 4.476E-01 0.60%

H-3 2.845E+01 1.008E+01 2.85E+01 24.66% H-3 3.441E+00 9.854E+00 9.854E200 13.28%

1-129 6.859E-02 2.777E-01 2777E-01 0.24% 1-129 8.316E-02 2.687E-01 2.687E-01 0.36%

NB-94 1.336E-01 3.152E-01 3.152E-01 0.27% NB-94 2.923E-01 2.079E-01 2.92E-01 0.39%

NI-63 1.648E+01 1.396E+00 1.65E+01 14.28% NI-63 1.397E+01 1.395E+00 1.40E+01 18.83%

PU-238 9.437E-02 1.140E-01 1.140E-01 0.10% PU-238 7.927E-02 7.159E-02 7.93E-02 0.11%

PU-239 9.854E-02 6.676E-02 9.85E-02 0.09% PU-239 1.321E-01 7.159E-02 1.32E-01 0.18%

SR-90 7.192E+00 6.492E-01 7.19E+00 6.23% SR-90 7.437E+00 6.639E-01 7.44E+00 10.03%

U-236 4.707E-02 7.696E-02 7.696E-02 0.07% U-236 4.962E-02 4.482E-02 4.96E-02 0.07%

1.1 5E+02 100.00% 7.42E+01 100.00%

MEAN MEAN STANDARD DEVIATION AM-241 0.15% 0.09%

AM243 0.16% 0.10%

-C-14 2.11% 1.51%

CM-245 0.22% 0.11%

CO-60 1.68% 1.94%

CS-137 58.50% 21.34%

EU-155 0.76% 0.38%

H-3 22.68% 19.00%

1-129 0.53% 0.30%

NB-94 0.30% 0.19%

Ni-63 6.96% 6.56%

PU-238 0.17% 0.18%

PU-239 0.16% 0.13%

SR-90 5.49% 3.08%

i U-236 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 FinalStatus 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 ReactorFacility FinalStatus 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

Survey Plan Revision 0 Plum Brook Brook Reactor Facility ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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 FinalStatus Survey Plan Revision 0 Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Bedrock that subcrops at the PBRFconsists ofDevonian Delaware Limestone and the overlying Devonian Plum Brook Shale Member of the Olentangy Shale. The majority of the site is underlainby Olentangy Shale, with the subcrop of DelawareLimestone limited to the northern and southeasternportion of the PBRF. Underlyingthe DelawareLimestone is a thick section ofpredominantly carbonate bedrock consisting of the Columbus Limestone and the DetroitRiver Formation.

The bedrock surface at the PBS generally slopes towardthe north, although the PBS is locatedin an area where an apparentbowl-shapedfeatureis present. In-filling of the bedrock depression has resulted in a similarthickening of unconsolidateddeposits at the PBRF.

Unconsolidateddeposits consist mostly of glacial till that occurs as a thin veneer over the bedrock surface. The thickness of these materials at the PBRFis typically about 25ft. Native surficialdeposits at the PBRF have been extensively disturbed. Boring logsfor the PBRF test borings and monitoring wells show that the unconsolidateddeposits consistpredominantly of cohesive soil, with some relatively thin, discontinuousgranularunits interbedded. The pro-glaciallacustrine depositionalenvironment in which these depositsformed tends to homogenize the deposits through wave reworking. While localized lenses ofgranularmaterialsdo exist, it does not appearthat these lenses are continuous across the site, and these units should not be consideredto be indicative of the typical site stratigraphy.

The United States Department ofAgriculture, NaturalResources Conservation Service (2002) has recently revisedthe Soil Survey of Erie County, Ohio. The soil within the 27-acrePBRFis mapped as Udorthents, disturbedsoil that has been affected by construction activities. Review of the soils surroundingthe PBRFprovides insight regardingwhat was likely presentpriorto disturbance. The soils in the immediate vicinity of the PBRFconsist of Colwood Loam, 0-1 percentslopes (CmA); Elnoraloamyfine sand, 0-4 percentslopes (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 undisturbedsoils are composed of loam, loamyfine sand, fine sandy loam, and loamyfine sand, respectively.

The surficialsoil at the PBRFhas been extensively disturbed. In addition, the entire site was reportedly regradedto promote surface water to flow to the southeast cornerof the PBRF. These excavation andgradingactivities have resulted in the entirePBRF being mapped by NaturalResources Conservation Service as Udorthents.

Photographsduring constructionshow stockpiled soil that was B-5

u B Plum BrookReactorFaciliay FinalStatus Survey Plan Revision 0 presumably used to backfill aroundthe structures and to support the regradingactivity. Therefore, it is likely that the surficialmaterials at the PBRFare a mixture of variable thickness composed of the entire section of unconsolidateddeposits, which at depth predominantly consists of cohesive soils.

Hydraulicconductivityfor the mixed unconsolidateddeposits ranges from 49 to 270 meters/year (m/yr), gradientrangesfrom 0.005 to 0.006fft/ft, and the porosity is expected to rangefrom about 0.35 to 0.70 (Freeze and Cherry, 1979). The hydraulic conductivity of the DelawareLimestone rangesfrom 3 to 188 m/yr, and the gradient rangesfrom 0.002 to 0.003ft/ft. The site-specific effective porosity of the DelawareLimestone has not been established. Therefore, a published valuefor limestone must be used to calculategroundwater 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 FinalStatus Survey Plan Revision 0 Table B-i. Residential Farmer Scenario: Contaminated Zone Parameters Parameter Parameter Value Source Area of contaminated zone 109100 m2 for controlled Teledyne Isotopes, 1987.

area including:

• 102400 m2 for PBRF

• 6700 m2 for Pentolite Ditch Thickness of contaminated zone Im 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/cm3 Hydrogeologic Report PBRF, 2004.

Average value used unconsolidateddeposits.

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 unconsolidateddeposits.

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 m2 RESRAD B-7

Plum Brook ReactorFacility FinalStatus 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/cm3 Hydrogeologic Report PBRF, 2004.

Average value used unconsolidateddeposits.

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 unconsolidateddeposits.

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 m3 /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/cm3 Hydrogeologic Report PBRF, 2004.

Average value used unconsolidateddeposits.

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 unconsolidateddeposits.

B-8

- B R F Plum Brook ReactorFacility FinalStatus 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 m3 /yr NUREG-1549a Mass loading for inhalation 6 x 106 g/m 3 NUREG-1549b Dilution length for airborne dust 3m 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 ReactorFacility FinalStatus 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/m3 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 ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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 FinalStatus Survey Plan Revision 0 Table B-10. Results of Sensitivity Analysis for Source Lifetime Parameter Positive Negative PRCC PRCC 7 5th Quantile 25th Quantile C-14 Fe-55 Co-60 Ni-59 Cs-137 Ni-63 Eu-152 Sr-90 Eu-154 Tc-99 I-129 H-3 Nb-94 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 m2 /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 m2 /h value by the total source area for the room, i.e., 270 in2 . 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 ReactorFacility FinalStatus Survey Plan Revision 0 parameter will result in an ingestion rate equal to 1.IE-04 m2 /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 cm2 for each radionuclide.

Table B-12 provides the DCGLs for the Building Reuse scenario.

B-14

( .a Brook ReactorFacility 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 (M2) 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 Isspent at one receptor 3

location 11 Breathing rate (m /day) B 33.6 NUREG/CR-5512, V3S5.3 Equal to 1.4 m3 /hr which Is median value and DandD V2.1 default 12 Indirect Ingestion rate (m2/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 at1m 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 FGR11 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 2

25 Area (M ) P 15 Site-specific model Wall area is 5m by 3m 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 1

27 Direct Ingestion (hr ) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 m2/hr divided by total source area of 270M 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/100cm 2 to allow for B-15

f r n Brook ReactorFacility iafs Survey Plan RevlA,i 0 No Parameter (unit) Typeo Value/Dlstributlon Source Comments/Justification proporthonal DCGL calculation .

2.Wall I :, , ,, ., , I, , ;. , 1 " 1, . , '. S ~:~

. ,

;E- ,., , , 'I-- , ~ :e .

31 P Area Site-specific model 32 Direction P X Slte-spedfic model 33 Location of center of source: xy,z (m) P 15,2.5,1.5 Site-spedfic model 34 Area (m2) P 15 Site-specific model Wall is 5m by3m 35 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 36 Direct ingestion (Wh) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m2/hr divided by total source area of 270 m2 37 Removable fraction P 0.1 NUREG-1757, V2 SI.6.3.1 Default parameter value for loose fraction from DandD 2.1 38 Lifetime or time for source removal (days) P Nuclide Specific NUREG/CR-6697, C, 8.8 Initial concentration is unit source to allow for proportional DCGL 39 Radionuclide Concentration (pCVm 2) P 45 Site-specific model calculation

-3.Wal 40 Type P Area Site-specific model 41 Direction P Y Site-specific model 42 Location of center of source: x,y,z (m) P 7.5,0, 1.5 Site-specific model 43 Area (m2) P 45 Site-specific model Wall area is 15 m by 3 m 44 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 45 Direct ingestion (hr') B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m2/hr divided by total source area of 270 m2 46 Removable fraction P 0.1 NUREG-1757, V2 Sl.6.3.1 Default parameter value for loose fraction from DandD 2.1 47 Lifetime or time for source removal (days) P Nudide Specific NUREG/CR-6697, C, 8.8 Initial concentration is unit source to allow for proportional DCGL 48 Radionuclide Concentration (pCVM2) P 45 Site-specific model calculation

4. Wallo 49 Type P Area Site-specific model 50 Direction P Y Site-spedfic model 51 Location of center of source: x,y,z (m) P 7.5,.5,1.5 Site-specific model 52 Area (m2) P 45 Site-spedfic model Wall area is 15 m by 3 m 53 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 radionuciides except H-3) B 0.07 NUREG/CR-6697, C, 8.6 Upper bound for contaminated noncombustible solids 54 Direct ingestion (hr') B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m2/hr divided by total source area of 270 m2 55 Removable fraction P 0.1 NUREG-1757, V2 Sl.6.3.1 Default parameter value for loose fraction from DandD 2.1 56 Lifetime or time for source removal (days) P Nucide Specific NUREG/CR-6697, C, 8.8 Initial concentration is unit source to allow for proportional DCGL 57 Radionuclide Concentration (pCim 2) P 45 Site-specific model calculation

5. Floor 58 Type P Area Site-saecific model B-16

f

( n Brook Reactor Facility a Bro eco ailt Ffnalf,Survey uvyPa PIan Tel-6 0 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) P 7.5,2.5,0 Site-specific model 61 Area (mi) P 75 Site-specific model Floor area is 5 m by 15 m 62 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 63 Direct ingestion (hi') B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1E-4 m2/hr divided by total source area of 270 rn2 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 (hr1) B 4.07E-07 NUREG/CR-5512, V3 S5.2.3 Equal to 1.1 E-4 m2/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 FinalStatus Survey Plan Revision 0 Table B-12. DCGLs for Building Reuse Scenario Radionuclide DCGL (dpmn100 cM2)

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 ReactorFacility FinalStatus 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 FinalStatus 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/GroundwaterInteractionsin Support of PerformanceAssessment of Low-Level Radioactive Waste DisposalFacilities. NUREG/CR-6377 (PNL-1 1408).

2. Mattigod, S.V., et. al., 2002. Radionuclide Desorption and Leaching Testsfor Concrete Coresfrom Haddam Neck Nuclear PlantFacilities.Final Letter Report, Battelle, Pacific Northwest Laboratory.

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

StructuralConcretefrom Maine Yankee NuclearPower 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.

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Plum Brook ReactorFacility FinalStatus 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 FinalStatus 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 ReactorFacility FinalStatus 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 m2 )(10,000 cm 2 /m2 )(DCGLEs dpm/1n00 cm 2 )(1 pCi/2.22 dpm)

Concrete Debris Mass = (V m 3 )(lE+06 cmn/m 3 3)(1-ri)(2.4 g/cm3 )

SA = Structure surface area requiring FSS (internal surfaces above and below grade) (m2 )

i= porosity (0.41)

V = Volume of fill required (M3 )

Combining conversion factors and rearranging terms results on the following equation for calculating the DCGLEs:

DCGLES dpm/100 cm2 = 31,435 (DCGLV pCi/g) (V m3 /SA M2 )

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.

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- Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Table B-15. Structure V/SA ratios Structure V/SA Ratio (m3 /m2 )

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.

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Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0

@ Table B-16. Building Reuse DCGLs, Subsurface Structure Effective Surface DCGLs, and DCGLFps Values Building Reuse Subsurface Structure DCGL Effective Surface DCGLFSS Radionuclic le (dpm/100 cm2 ) DCGLEs (dpm/100 cM2)

(from Table B-12) (dpml100 cM2)

C-14 L.OE+07 940,500 940,500 Fe-55 4.OE+07 3.7E+07 3.7E+07 Co-60 11,000 182,500 11,000 Ni-59 9.9E+07 8.0E+07 8.OE+07 Ni-63 3.6E+07 4.3E+07 3.6E+07 Sr-90 136,200 33,100 33,100 Tc-99 1.4E+07 1.3E+06 1.3E+06 Cs-137 40,500 121,700 40,500 Eu-152 24,300 520,000 24,300 Eu-154 4,500 475,800 4,500 H-3 3.2E+08 9.1E+06 9.1E+06 Pu-241 228,000 2.6E+07 228,000 Pu-238 4,900 719,200 4,900 Cm-243/244 4 6,100 265,500 6,100 Ain-241 4,300 210,200 4,300 Eu-155 395,000 1.9E+07 395,000 1-129 67,800 14,900 14,900 Nb-94 15,800 365,100 15,800 Pu-239 4,400 663,900 4,400 U-234 31,500 1.2E+06 31,500 U-235 27,100 995,800 27,100 U-236 33,200 1.2E+06 33,200 U-238 32.900 1.2E+06 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 m2 . The 2,000 m2 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 m2 to 250 m2 to represent the elevated area sizes. RESRAD dose reports used for the calculations are available for review as needed.

B-25

Survey Plan Revision 0 Facility Reactor Facility Plum Brook Reactor FinalStatus FinalStatus Survey Plan Revision 0 The AFs were calculated by dividing the dose result for the 2,000 m2 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 m2 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 m2 to 50 m2 . 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 ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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).

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Plum Brook ReactorFacility FinalStatus 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 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br /> 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 ReactorFacility FinalStatus 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 ReactorFacility FinalStatus 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).

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Plum BrookReactorFacility FinalStatus Survey Plan Revision 00 Plum Brook Reactor Facility FinalStatus Survey Plan Revision

• 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 ReactorFacility FinalStatus 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 _l Line 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-ll 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.

7.0 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 C-7

Plum Brook Reactor Facility FinalStatus 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 FinalStatus 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 FinalStatus 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 BrookReactorFacility 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 l Average 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 3in ID 6 in ID 6 in ID 8 in ID 3 in ID 6 in ID 4 in ID l4-1.5 '-*F 1.5 '-*1 3'

31 0- 3' 4.5' 4.5' 6' 6' 7'

C-12

( .m Brook Reactor Facility E

FinotatusSurvey Plan A",I

-f Revon 0 Figure C-2 Canal F- Pump Fbom -Walkway 9-Rpe Cluster Conceptual Dose Model - Ran View a

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fPlum Brook Reactor Facility FinalStatus 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)

Rpe Cluster Center line fEdg Pump Poom Roor-25 ft.

A Dose'Fbint Anar b eI-CL 9 ft A in .

bek ow-25ftel.I 53.3 cm I' 1 6 67 cm 62.2 cm 1.33 3 in ID IF -ii D - i

-o 1.39 1.37 1.31 Rpe CL 3 in ID 3 in ID 1 3 in ID 13 in above floor II Trench Roor- 28 ft 7 3/4 in I C-14

A:

Plum Brook Reactor Facility

( -(-

FinalStatus Survey Plan Revision 0 Figure C Rimp Fbom Quad & Canal Drain Maniold Rpe Trench Conceptual Dose :Model - Ran View

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Trench SFuth wall DosweFbint 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 ReactorFacility FinalStatus 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 &_12in shld ____ _____

12/21/2005 Line 1.21 B Revised Model Sched 40 Cal&

& 12 -inCs-137 Unit Act w PB122101 3.90E-1 1 conc shield 12/21/2005 Line 1.21 C Revised Model Sched 40 Ca&c

& 12-inEu-152 Unit Act w PB122102 conc shield .825E-10 P120 llI-12/21/2005 Line 1.21 D RevisedModelCal cEu-54 UnitAct w PB122103 2.50E-10 Sched 40 & 12 in conc shield 12/21/2005 Line 1.21 E Revised Model40Calc

& 12- Ag-w Sched lIOSm Unit Act PB122104 1.1 lE-lO 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_ _ _ _ _

12/21/205Line1.23 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 10 1.58E3-10 Sched. 40 & 12 in conc shield ___________

12/29/205Line1.23 G Revised Model Calc 129 Unit Act wPB295 21E3 12_2__ 05_Lie_123_ Sched 40 & 12 in conc shield __B122905 __________

1/4/2006Lne 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 _ _ _ _ _ _

12/29/2005ine 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 FinalStatus 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 & PB1221915 Calc - Nb-94 Unit Act w PB1290_289-1 4.609E-1 12/29/2005__ Lie1.4HSched 40 12 in conc shield 12/29/2005 Line 1.24 G Unit Act w PB122909 Revised Model Calc - I-129 shield 9.09E-36 Sched 40 & 12 in conc 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 sch14 i 12n shid s 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 Unit Act wPB1221 E-1 12/21/2005 12/2l/2005 Line 1.25 D Line 1.25 D Revised Sched & 12 -inEu-154 40 Cac Model 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 12/29/205Line1.25 ~ Revised Model Cabc - Zr-95 Unit Act wPB295 68E1 12_2____05_ Lin ISched 1____25__ 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 12/21/205Line1.26 B Revised Model Calc - Cs-137 Unit Act wPB211 53E3 12__21_2___ Ln126BSched 40 & 12 in conc shield 1221 53E3 12/21/205Line1.26 C Revised Model Calc - Eu-152 Unit Act wPB222 58E1 12/212005ine 126 CSched 40 & 12 in conc shield _B_2122_____1 12/21/205Line1.26 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 ReactorFacility FinalStatus 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 Sched 40 & 12 -inCo-60 Unit Act w PB121915 conc shield PB217 2.90E-10 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 12_2__00__Lie_1_64 Line 1.641Fc CSchedRevised Model 40 Calc

& 12 -inEu-152 Unit Act w PB122130 conc shield __B122127 7.1lE-ll 9_________I 12/21/2005 12_2__00__Lie_1_64Line 1.641 D DSchedRevised Model 40 Calc

& 12 -inEu-154 Unit Act w PB122921 conc shield __B122128 2.33E-35 12/21/2005 Line 1.641H E Revised Model40Calc w Sched & 12- Ag-108m Unit Act PB10406 in conc shield 4.9E-19 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 1.641FI Sched 40 & 12 in conc shield PB12213 3.83-12 12/29/205Line1.641 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 12/21/205Line1.81 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 _ _ _ _ _ _ _ _ _ _ _

12/21/205Line1.81 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 ReactorFacility 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)

Revised Model & 12-inEu-155 40 Calc Unit Act PB122928 2.56E-20 12/29/200512/29/2005 Line L81 JJ Line 1.81 w Sched conc shield P122 .632 12/19/2005 Line 1.82 A2 Revised Model Sched Calc -inCo-60 40 &_12 Unit Act w PB121919 cone shield PB12199 6.12E-l l Line___1_82 A2 _______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 Sched 40 & 12 in cone shield 1.97E-1 1 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 Model Calc RevisedSched -Ag-12 UnitAct PB122139 8.16E-12 7.1-w 40 & 12 in conc shield wP048 12/21/2005 Line 1.82 F Revised Model 40 & Calc12 -Nb-94 Unit Act w PB1221 in conc shield 4.8E-11 I 12__21_2___ Ln182FSched _B1214______

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 shield Unit Act w PBO10408 7.21E-21 Sched 40 & 12 in conc 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 Revised Model & 12-inEu-155 40 Calc Unit Act PB122932 7.31E-12 0 12/29/200512/29/2005 Line 1.82 CJ Line 1.82 w Sched conc shield P123 .131 Unit Act w PB1221 8.9E-12 12/21/2005 1/2/192006 Line 1.83 A2 Line 1.83 E_ Revised Model Sched 40 & Calc12 -inCo-60 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 & 12 -inEu-152 40 Calc Unit Act w PB122933 cone shield 2.59E-36 12__21_2___ Ln183CSched __122142______1 12/21/2005 Line 1.83 D Revised Model Calc12 -inEu-154 Unit Act w PB122143 3.97E-12 Sched 40 & conc shield 1/2/2006 Line 1.83 E RevisedMdel Caic sUnitAct 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______

12/29/2005ine 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 shield Unit Act PB122936 1.671E-21 w Sched 40 & 12 in conc Cl-4

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Pap- :1 File Ref:

DC ile: PB121903.MS5 Date:

Rur te: December 19, 2005 By:

Run Time: 10:34:32 AM Checked:

Duration: 00:00:01 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 ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in xr Dose Points Y I z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Nme Dieiension Material Density Cyl. Core 7.i 52 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad . D25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels0 4Ci/cm0 Co 60 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Activity Fluence Rate Fluence Rate Expoure Rate Exlosure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec rnR/hr mR/hr No Builcug With Buildup No Buildup With Buildup 0.6938 9.909e-04 3.041e.13 5.389e*12 5.872e-16 1.040e-14 1.1732 6.074e+00 1.656e 08 1.527e-07 2.959e- 11 2.728e-10

¶ 3325 6,074e+00 2.723e-08 2.171e-07 4.723e-11 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 FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04.00362)

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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) Photons/cm 2 /sec 3.454e-008 2.930e-007 Photon Energy Fluence Rate MeV/cm2/sec 4.378e-008 3.697e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.682e-01 1 6.494e-010 Absorbed Dose Rate in Air mGy/hr 6.707e-013 5.670e-012 mrad/hr 6.707e-01 I 5.670e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 7.614e-013 6.438e-012 o Opposed 6.558e-013 5.542e-012 o Rotational 6.558e-013 5.542e-012 o Isotropic 5.858e-013 4.950e.012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.105e-013 6.854e-012 o Opposed 7.804e-013 6.598e-012 o Rotational 7.804e-013 6.598e-012 o Isotropic 6.206e-013 5.246e-012 Effective Dose Equivalent Rate (ICRP 51 . 1987) o Anterior/Posterior Geometry mSv/hr 6.856e-013 5.797e-01 2 o Posterior/Anterior 6.316e-013 5.339e.012 o Lateral 5.024e-013 4.244e-012 o Rotational 5.687e-013 4.807e-012 o Isotropic 5.034e-013 4.253e-012 Page 1 Cl-6

Plum BrookReactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122101.MS5 Date:

RL ate: December 21, 2005 By:

RuniTime: 1:04:33 PM Checked:

Duration: 00:00:01 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 ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in

-x lose Points z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields

-Shield Name Di iension MaU Cw Density Cyl. Core 7.152 cm2 Conc rete 1.8 Shield 1 65 cm IroDn 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becauerels IJQi/cmu Bq/cnm Ba-137m 1.5531e-010 5.7464e+000 4.2570e-009 1.5751e-004 Cs 137 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results A~ctivit Fluence Rate Fluence Rate Exposure Rafte Exposure Rate photons/sec MeV/cm2/sec MeV/cm2/sec mRohr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0318 1.190e-01 8.1 59e-60 1.246e-34 6.796e-62 1.038e-36 0.0322 2.195e-01 4.883e-58 2.389e-34 3.930e.60 1.923e-36 C'n364 7.987e-02 1.780e-45 1.33le-34 1.012e-47 7.564e-37 316 5.171e+00 1 .291e-09 2.431e-08 2.503e 12 4.713e 11 Cl-7

Plum Brook ReactorFacility FinalStatus 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 FlueneRt Fluence Rate Exposure Rate Exposure Rate MeV. 1hotons/sec MeV/cm/sec MeV/cmz/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 5.589e+00 1.29le-09 2.43le-08 2.503e-12 4.713e-I 1 Cl-8

Plum Brook Reactor Facility FinalStatus SurveyPlan . Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies) Without With 8uildup Buildup Photon Fluence Rate (flux) Photons/cm 2/sec 1.952e6009 3.674e-008 Photon Energy Fluence Rate MeV/cmt/sec 1.291e-009 2.431e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.503e.012 4.713e-011 Absorbed Dose Rate in Air mGy/hr 2.186e.014 4.114e-013 mrad/hr 2.186e-012 4.114e-011 Deep Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 2.588e 014 4.871e-013 o Opposed 2.072e-014 3.900e-013 o Rotational 2.072e-014 3.900e-013 o Isotropic 1.832e-014 3.449e.013 Shallow Dose Equivalent Rate (ICRP 51- 1987) o Parallel Geometry mSv/hr 2.750e-014 5.177e-013 o Opposed 2.612e-014 4.917e-013 o Rotational 2.612e.014 4.917e-013 o Isotropic 1.958e-014 3.687e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.288e-014 4.307e-013 o Posterior/Anterior 2.020e-014 3.802e-013 o Lateral 1.498e.014 2.819e.013 o Rotational 1.805e-014 3.397e-013 o Isotropic 1.536e-014 2.892e-01 3 Page 1 CJ-9

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page  : 1 File Ref:

DOS File: PB122102.MS5 Date:

RL ate: December 21, 2005 By:

RunriTime: 1:09:19 PM Checked:

Duration: 00:00:01 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 urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in r-n - x Dose Points z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in I Shields Shield Name 12limension Matf Density Cyl. Core 7.62 cm, Conc rete 1.8 Shield 1 .65 cm troan 7.86 Transition Concrete 2.4 Shield 3 I30.48 cm Concrete ! 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide curi s becquerels mCi/cm' 1q/cm4 Eu- 152 1.6417e- 010 6.0744e+000 4.5000e-OC09 1.6650e 004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy -cv Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 3.5 4 e+ MeV/cm2/sec MeV/cm2lsec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

)4 3.594e+00 1.418e-36 8.333e-33 6.272e-39 3.686e-35 cl-Jo

Plum Brook ReactorFacility FinalStatus 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 Activity Fluence Rate Fluence Rate Exposure Rate Exp~osure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.05 8.987e-01 3.132e-26 2.928e-25 8.342e-29 7.801e-28 0.1 1.727e+00 4.074e-15 2.024e-13 6.233e-18 3.096e- 16 0.2 4.552e-01 3.440e-13 2.243e-1 1 6.072e-16 3.959e-14 0.3 1.642e+00 1.054e-1 1 5.126e-10 1.999e-14 9.723e- 13 0.4 3.817e-01 9.797e.12 3.474e-10 1.909e-14 6.769e-13 0.5 3.426e-02 2.465e- 12 6.636e-1 1 4.839e 15 1.303e-13 0.6 2.576e-01 4.189e-I 1 8.937e.10 8.176e-14 1.744e-12 0.8 1.082e+00 6.109e*10 9.029e.09 1.162e-12 1.717e-11 1.0 2.599e+00 3.719e-09 4.152e-08 6.855e. 12 7.654e-1 1 1.5 1.409e+00 9.875e-09 6.928e-08 1.661e-I 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 ReactorFacility FinalStatus Survey Plan - Revision 0 licroShlield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies) Units Without With Buildup Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 1.120e.008 1.033e-007 Photon Energy Fluence Rate MeV/cmz/sec 1.427e-008 1.217e-007 Exposure and Dose Rates:

Exposure Rate in Air .mR/hr 2.476e-01 1 2.138e-O10 Absorbed Dose Rate in Air mGy/hr 2.161e-013 1.867e-012 mrad/hr 2.161e-011 1.867eO010 Deep Dose Equivalent Rate - (ICRP 51 - 1987)' -

o Parallel Geometry mSv/hr 2.459e-013 2.131e-012 o Opposed 2.120e*013 1.824e-012 o Rotational 2.120e-013 1.824e-012 o Isotropic 1.895e-013 1.628e-012 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 2.610e-013 2.265e-012 o Opposed 2.517e.013 2.180e-012 o Rotational 2.517e.013 2.180e-012 o Isotropic 2.002e-013 1.724e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.212e-013 1.914e-012 o Posterior/Anterior 2.039e-013 1.757e.012 o Lateral 1.626e-013 1.392e-012 o Rotational 1.837e-013 1.582e-012 o Isotropic 1.627e-013 1.396e-012 Page 2 CI-12

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page  : 1 File Ref:

DOS File : PB122103.MS5 Date:

R. 'ate: December 21, 2005 By:

Run rime: 1:12:29 PM Checked:

Duration: 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points

£ y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name CDimension Mate riW Density Cyl. Core 7.62 cm2 Conc rete ! 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclid curies 2 becquerels uCi/cm 2 Bq/cm1 Eu.154 1.6417e-I010 6.0744e+000 4.5000e-OC09 1.6650e 004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 2hotons/sec MeV/cm4/sec MleV/crmnLe mR/hr mrR/h No Buildup With Buildup No Buildup With Buildup

)4 1.236e+00 4.878e-37 2.866e-33 2.158e-39 1.268e-35 CI-13

Plum Brook ReactorFacility FinalStatus 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 Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cM2/sec mR/hr mR/hr No Buildups With Buildu No Buildup With Buildup 0.05 3.140e-01 1.094e-26 1.023e-25 2.915e-29 2.726e-28 0.1 2.458e+00 5.798e-15 2.880e. 13 8.871e-18 4.406e-16 0.2 4.148e-01 3.136e- 13 2.044e 11 5.534e.16 3.608e.14 0.4 4.334e-02 1.112e-12 3.944e-1 1 2.167e-15 7.685e- 14 0.5 1.315e-02 9.463e- 13 2.547e-11 1.857e-15 5.000e.14 0.6 4.900e-01 7.968e- 11 1.700e-09 1.555e-13 3.318e.12 0.8 2.369e+00 1.338e-09 1.978e-08 2.545e-12 3.761e-11 1.0 1.869e+00 2.674e-09 2.985e-08 4.929e-12 5.503e-11 1.5 2.370e+00 1.661e.08 1. 165e-07 2.795e-11 1.961e-10 TOTALS: 1.158e+01 2.070e-08 1.679e-07 3.558e.11 2.922e-10 Cl -14

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 icroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies) Units Without Mth Photon Fluence Rate (flux) Photons/cm 2 /sec 1.556e-008 1.353e- 007 Photon Energy Fluence Rate MeV/cm 2 /sec 2.070e-008 1.679e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.558e-011 2.922e.010 Absorbed Dose Rate in Air mGy/hr 3.106e-013 2.55le-012 mrad/hr 3.106e-011 2.55le-010 Deep Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 3.528e*013 2.906e-012 o Opposed 3.053e.013 2.499e-012 o Rotational 3.053e*013 2.499e-012 o Isotropic 2.733e-013 2.233e-012 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 3.741e*013 3.085e.012 o Opposed 3.613e-013 2.974e-012 o Rotational 3.613e*013 2.974e-012 o Isotropic 2.883e-013 2.361e.012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.176e-013 2.612e-012 o Posterior/Anterior 2.934e-013 2.405e*012 o Lateral 2.351e-013 1.915e-012 o Rotational 2.646e-013 2.167e-012 o Isotropic N 2.349e-013 1.916e.012 Page 1 Cl-15

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShleld v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122104.MS5 Date:

Rt *ate: December 21, 2005 By:

Rurn rime: 1:21:22 PM Checked:

Duration : 00:00:01 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 urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in V~-X Dose Points X Y z

1. 1 138.78 crr I 381 cm 45.7 cm 4 ft 6.6 ir I 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Dimension Material Density Cyl. Core 7.62 cm- Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide as becguerels mCi/cm, Ag-108m 1.6417i B-010 6.0744e+000 4.5000e-0 I09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener Activiy Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeVy hotonssec MeV/cm21/sec MeV/cm2/sec mR/h1 mR/hr No Buildup With Buildup No Buildup With Buildup

)2 3.984e+00 3.590e- 187 1.575e-33 1.244e 188 5.457e-35 Cl-16

Plan Revision 0 Facility Plum Brook ReactorFacility Status Survey FinalStatus Final 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 Activity Fluence Rate Fluence Rate Exp~osure Rate Exposure Rate photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr Nlo Buildup With Buildup No Buildup With Buildup 0.03 1.290e-06 3.735e-73 1.128e-39 3.702e-75 1.118e.41 0.08 4.305e-01 2.032e 17 6.656e-16 3.216e-20 1.053e.18 0.4 5.460e+00 1.401e-10 4.969e-09 2.730e-13 9.681e-12 0.6 5.491e+00 8.929e-10 1.905e-08 1.743e*12 3.719e-1 1 0.8 5.497e+00 3.105e-09 4.589e.08 5.906e-12 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 FinalStatus Survey Plan Revision 0 licroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies) UnAit With a uildu BQuiUld Photon Fluence Rate (flux) Photons/cm2/sec 5.720e-009 1.015e-007 Photon Energy Fluence Rate MeV/cm 2 /sec 4.138e-009 6.991e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.922e-012 1.342e-010 Absorbed Dose Rate in Air mGy/hr 6.916e-014 1.17le-012 mrad/hr 6.916e-012 1.171e-010 Deep Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 8.125e-014 1.382e-012 o Opposed 6.590e-014 1.114e-012 o Rotational 6.590e-014 1.114e-012 o Isotropic 5.826e-014 9.850e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.661e-014 1.470e-012 o Opposed 8.249e-014 1.399e-012 o Rotational 8.249e-014 1.399e-012 o Isotropic 6.233e-014 1.054e.012 Effective Dose Equivalent Rate (ICRP 51 -1987) o Anterior/Posterior Geometry mSv/hr 7.214e.014 1.225e-012 o Posterior/Anterior 6.419e-014 1.087e-012 o Lateral 4.818e-014 8.119e-013 o Rotational 5.739e-014 9.708e-013 o Isotropic 4.914e.014 8.297e-013 Page 1 C1-18

Plum Brook ReactorFacility FinalStatus Survey Plan .I Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122105.MS5 Date:

RL ate: December 21, 2005 By:

Run Time: 1:23:24 PM Checked:

Duration :00:00:01 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 rce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in I .a.

)ose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Name Shiel Dirr lension Material Density Cyl. Core 7. 62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30 .48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad . 025 cm Iron 7.86 Source Input Grouping Method: Actual Photon Energies Nuclide curies becguerels ujCi/cm 2 Bq1cm4 Nb-94 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MwY photons/see MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0174 2.148e-03 2.567e-278 6.819e-37 1.386e-279 3.68le 38 0.0175 4.115e-03 1.690e-273 1.319e-36 8.951e-275 6.984e-38 0.0196 1.209e-03 3.203e-201 4.633e-37 1. 182e-202 1.710e-38 0 7026 6.074e+00 1.969e-09 3.433e.08 3.797e-12 6.621e 11 711 6.074e+00 4.910e-09 6.513e 08 9.241e.12 1.226e- 10 CJ-19

Plum Brook Reactor Facility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exiposure Rate MeV photons/sec MeV/cmTl/se MeVtcm 2 /sec mnRBhr mR/hr No Buildup With Buildup With Buildup TOTALS: 1.216e+01 6.879e-09 9.946e-08 1.304e.1 1 1.888e.10 Cl-20

Plum Brook ReactorFacility FinalStatus Survey Plan = Revision 0 icroShield v5.04 (5.04-00362) 12/21/0!

MicroShield v5.04 (5.04-00362)

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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 WiLth Buidu Buidu Photon Fluence Rate (flux) Photons/cm2/sec 8.439e-009 1.236e-007 Photon Energy Fluence Rate MeV/cm 2 /sec 6.879e-009 9.946e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.304e-01 1 1.888e-010 Absorbed Dose Rate in Air mGy/hr 1.138e-013 1.648e-012 mrad/hr 1.138e-011 1.648e-010 Deep Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 1.325e-013 1.920e-012 o Opposed 1.090e-013 1.577e-012 o Rotational 1.090e-013 1.577e-012 o Isotropic 9.639e-014 1.395e-012 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 1.416e-013 2.052e-012 o Opposed 1.35le-013 1.958e-012 o Rotational 1.351e*013 1.958e-012 o Isotropic 1.031e.013 1.492e-012 Effective Dose Equivalent Rate (ICRP 51 1987) o Anterior/Posterior Geometry mSv/hr 1.181e-013 1.710e.012 o Posterior/Anterior 1.059e-013 1.532e.012 o Lateral 8.040e.014 1.162e-012 o Rotational 9.477e-014 1.37le-012 o Isotropic 8.163e-014 1.180e-012 Page 3 Cl-21

Plum Brook ReactorFacility . FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc. 7 Page :1 File Ref:

DOS File: PB122901.MS5 Date:

RL ate: December 29, 2005 By:

Run fime: 2:03:16 PM Checked:

Duration : 00:00:01 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 Sourrce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in V;?.-Ii- I x

)ose Points y z

1. 1 138.78 cm 381 cm 45.7 cm

.1I 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Qir iension Material Density Cyl. Core 7. 62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30..48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad . 125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies uclide curies becquerels pCi/cm2 Bq/cm1 1-129 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Edn Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MBV photons/sec MeV/cm2/sec MeV/cm"/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0295 1.212e+00 4.389e-70 1.007e-33 4.593e-72 1.054e-35 0.0298 2.249e+00 4.520e-68 1.925e-33 4.579e-70 1.951e-35 0.0336 7.995e-01 2.067e-52 1.005e-33 1.471e-54 7.150e-36 0 0396 4.568e-01 3.486e-38 1.022e-33 1.584e-40 4.643e-36 CJ-22

Plum Brook ReactorFacility FinalStatus 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 Activit Fluence Rate Fluence Rate ExQosure Rate Ex~osure Rate MeV photons/sec MeV/cmz/sec MeV/cm2/sec mR/hr mRbhr No Buildup With Buildup No Buildup2 With Buildup TOTALS: 4.718e+00 3.486e-38 4.959e-33 1.584e 40 4.184e-35 Cl-23

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShlield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 8.807e-037 1.546e-031 Photon Energy Fluence Rate MeV/cm 2/sec 3.486e-038 4.959e.033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.584e-040 4. 184e-035 Absorbed Dose Rate in Air mGy/hr 1.383e-042 3.652e-037 mrad/hr 1.383e-040 3.652e-035 Deep Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 1.979e*042 4.181e.037 o Opposed 9.969e-043 2.097e-037 o Rotational 9.026e-043 1.789e-037 o Isotropic 8.635e-043 1.662e-037 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 1.991e-042 4.557e-037 o Opposed 1.375e-042 3.134e-037 o Rotational 1.375e-042 3.134e-037 o Isotropic 1.009e-042 2.316e-037 Effective Dose Equivalent Rate (ICRP 51 1987) o Anterior/Posterior Geometry mSv/hr 1. 154e.042 1.875e-037 o Posterior/Anterior 6.976e-043 9.692e-038 o Lateral 3.854e-043 5.23le-038 o Rotational 6.273e-043 9.630e-038 o Isotropic 5.142e-043 7.979e.038 Page 1 C1-24

P Plum BrookReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref: _ _

Dos File: PBO10401.MS5 Date: _

Ru ate: January 4, 2006 By:

Run Time: 7:40:17 AM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in 1 I x Dose Points X z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in . 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name CDimension. Mate,drall CyL. Core 7.62 cm 2 Conci 'ete 1.8 Shield 1 .65 cm Iroin 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide ur E WCi/cm 2 10/cm Sn-126 1.6417e- 010 6.0744e+000 4.5000e-OC09 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate Me0 photon s/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr' No Buildup With Buildup No Buildup With Buildup

.02 4.702b-01 4.237e- 188 1.859e-34 1.468e 189 6.440e-36 Cl-25

Plum BrookReactor Facility FinalStatus 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 Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cmL/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildu 0.03 1.779e+00 5.151e-67 1.555e-33 5.105e-69 1.541e-35 0.04 3.034e.02 1.197e-38 7.035e-35 5.295e-41 3.111e.37 0.06 5.821e-01 1.833e-21 3.14le*20 3.640e-24 6.240e-23 0.08 2.789e+00 1.317e 16 4.313e-15 2.084e- 19 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 FinalStatus SurveyPlan _ Revision 0 MicroShield v5.04 (5.04-00362) 01/04/0 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies) Units Without With Buildupn Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 1.646e-015 5.391e-014 Photon Energy Fluence Rate MeV/cm 2/sec 1.317e-016 4.313e-015 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.084e-019 6.825e-018 Absorbed Dose Rate in Air mGy/hr I1.819e-021 5.958e-020 mrad/hr 1.819e-019 5.958e-018 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.182e-021 1.042e-019 o Opposed 1.695e-021 5.551e-020 o Rotational 1.647e-021 5.395e-020 o Isotropic 1.636e-021 5.357e-020 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.153e 021 1.033e-019 o Opposed 2.317e.021 7.589e-020 o Rotational 2.317e-021 7.589e-020 o Isotropic 1.701e-021 5.570e-020 Effective Dose Equivalent Rate (ICRP 51

• 1987) o Anterior/Posterior Geometry mSv/hr 2.673e.021 8.753e-020 o Posterior/Anterior 2.039e-021 6.676e*020 o Lateral 1.256e-021 4.115e-020 o Rotational 1.736e-021 5.687e-020 o Isotropic 1.404e-021 4.600e-020 Page:

Cl-27

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DCO File : PB122903.MS5 Date:

Ru-sate: December 29, 2005 By:

Run Time: 2:10:45 PM Checked:

Duration : 00:00:01 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 ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in x

lose Points Y z

1. 1- 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields z Shield Name Dimiension Material Densit Cyl. Core 7.E52 cm2 Concrete 1.8 Shield 1 65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerell wCi/cm Zr-95 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm-/sec mR/hr mR/hr-No Buildup With Buildup No BuilduI2 With Buildup 0.7242 2.652e+00 9.792e-10 1.643e-08 1.883e-12 3.159e-11 0.7567 3.362e+00 1.499e-09 2.378e-08 2.869e-12 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 ReactorFacility FinalStatus Survey Plan Revision 0 MicrcShield vS.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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 Wih Buldup Buildup Photon Fluence Rate (flux) Photons/cm t/sec 3.333e-009 5.410e-008 Photon Energy Fluence Rate MeV/cm 2 /sec 2.478e-009 4.020e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.751e-012 7.709e-01 1 Absorbed Dose Rate in Air mGy/hr 4.148e-014 6.730e-013 mrad/hr 4.148e-012 6.730e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.862e-014 7.890e-013 o Opposed 3.954e-014 6.416e-013 o Rotational 3.954e-014 6.416e-013 o Isotropic 3.495e-014 5.671e-013 Shallow Dose Equivalent Rate (ICRP 51

• 1987) o Parallel Geometry mSv/hr 5.191e-014 8.423e-013 o Opposed 4.947e-014 8.026e-013 o Rotational 4.947e-014 8.026e-013 o Isotropic 3.740e-014 6.069e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 4.319e-014 7.007e-013 o Posterior/Anterior 3.846e-014 6.241e-013 o Lateral 2.892e-014 4.692e-013 o Rotational 3.440e-014 5.582e-013 o Isotropic 2.947e-014 4.782e-013 Page 1 CJ-29

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref: _

DOS File: PB122904.MS5 Date:

Ru ate: December 29, 2005 By:

Run-firme: 2:13:27 PM Checked:

Duration: 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points IZ X Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name [)Dimension Mait (lensity

'Cyl. Core 7.62 cmz Concarete 1.8 Shield 1 .65 cm Iron - 7.86 Transition Concrete 2.4 Shield 3 310.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide curies becqauerels uCi/cm 2 B1/cm6 Eu.155 1.6417e-I 210 6.0744e+000 4.5000e-OC 109 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Erg Activiy Fluence Rate Fluence Rate Exposure Rate Exposure Rate a3 photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup; With Buildup No Buildup With Buildup

)3 1.933e-02 5.599e-69 1.690e-35 5.549e-71 1.675e-37 Cl-30

Plum Brook Reactor Facility FinalStatusSurvey Plan Revision 0 Page :2 DOS File: PB122904.MS5 Run Date: December 29, 2005 Run Time: 2:13:27 PM Duration : 00:00:01 ActivitY Fluence Rate Fluence Rate Exposure Rate Exposure -Rate MeY photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup' With Buildup 0.04 1.lOle+00 4.345e 37 2.553e-33 1.922e-39 1. 129e-35 0.05 3.581e-01 1.248e-26 1.167e-25 3.324e-29 3.109e-28 0.06 7.878e-02 2.480e-22 4.251e-21 4.926e-25 8.444e-24 0.08 1.886e+00 8.905e-17 2.917e-15 1.409e-19 4.615e-18 0.1 1.256e+00 2.962e-15 1.471eK13 4.532e-18 2.251e.16 TOTALS: 4.699e+00 3.051e-15 1.501e*13 4.673e-18 2.297e- 16 Cl-31

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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 With Photon Fluence Rate (flux) Photons/cm t /sec 3.074e-014 1.508e-012 Photon Energy Fluence Rate MeV/cm 2 /sec 3.05le*015 1.50le.013 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.673e-018 2.297e-016 Absorbed Dose Rate in Air mGy/hr 4.079e-020 2.006e-018 mrad/hr 4.079e-018 2.006e-016 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.827e*020 3.355e-018 o Opposed 3.740e.020 1.839e-018 o Rotational 3.737e-020 1.838e-018 o Isotropic 3.619e-020 1.779e-018 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 6.782e-020 3.333e-018 o Opposed 5.254e-020 2.583e-018 o Rotational 5.254e.020 2.583e-018 o Isotropic 3.826e-020 1.88le-018 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 5.865e-020 2.883e-018 o Posterior/Anterior 4.595e-020 2.259e-018 o Lateral 2.836e-020 1.394e-018 o Rotational 3.925e-020 1.930e-018 o Isotropic 3.124e-020 1.535e-018 Page 1 Cl-32

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShleld v5.04 (5.04.00362)

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Palm :1 File Ref:

Dt. ile : PB121907.MS5 Date:

Rur te: December 19, 2005 I By:

Run rime: 10:58:55 AM Checked:

Duration: 00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points

1. 1 138.78cm Y

381 cm z

45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in a Shields Dimension Material Density Cyl. Core 7.62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energ jes Nuclide curies becquerels UCi/CM2 Bq/cm2 Co-60 1.6417e-010 6.0744e+000 4.5000e-0109 1.6650e-004 Buildup The material reference Is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene Activity Flueoce Rate Fluence Rae Exposure Rate Exgosure Rate MeVn photo ns/ sec M eWVcm2/ sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.6938 9.909e-04 3.04le 13 5.389e.12 5.872e.16 1.040e.14 1.1732 6.074e+00 1.656e-08 1.527e.07 2.959e 11 2.728e- 10

' 3325 6.074e+00 2.723e.08 2.171e-07 4.723e1 1I 3.766e.10 T kLS: 1.215e+01 4.378e.08 3.697e.07 7.682e-1 1 6.494e- 10 I

Cl-33

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 3.454e-008 2.930e-007 Photon Energy Fluence Rate MeV/cm 2 /sec 4.378e-008 3.697e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.682e-011 6.494e-010 Absorbed Dose Rate in Air mGy/hr 6.707e-013 5.670e-012 mrad/hr 6.707e-011 5.670e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 7.614e-013 6.438e-012 o Opposed 6.558e-013 5.542e-012 o Rotational 6.558e-013 5.542e-012 o Isotropic 5.858e-013 4.950e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.105e-013 6.854e-012 o Opposed 7.804e-013 6.598e-012 o Rotational 7.804e-013 6.598e-012 o Isotropic 6.206e-013 5.246e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 6.856e-013 5.797e-012 o Posterior/Anterior 6.316e-013 5.339e-012 o Lateral 5.024e-013 4.244e-012 o Rotational 5.687e-013 4.807e-012 o Isotropic 5.034e-013 4.253e-012 Page 1 Cl-34

Plum Brook ReactorFacility FinalStatus Survey Plan . . Revision 0 MicroShleld v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122106.MS5 Date: __ _

RL ate: December 21, 2005 By:

Run-rime: 1:29:02 PM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in 41"N Dose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in I .

Shield Name Shields I Dimension Mate Density Cyl. Core 7.62 cm 2 Conc rete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies . becquerels. w~i/cm2 Bq/cm2 Ba-137m 1.5531e-010 5.7464e+000 4.2570e-009 1.5751e-004 Cs-137 1.6417e-010 . 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exp~osure Rate Mey photons/sec MeV/cmi/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0318 1.190e-01 8.1 59e-60 1.246e-34 6.796e-62 1.038e-36 0.0322 2.195e-01 4.883e-58 2.389e-34 3.930e-60 1.923e-36 0.0364 7.987e-02 1.780e.45 1.331e-34 1.012e-47 7.564e-37 316 5.171e+00 1.291e-09 2.431e-08 2.503e-12 4.713e-11 Cl-35

Plum Brook Reactor Facility FinalStatus 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 Activit Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/CM2/sec mR/hr mR/hr With Buildup No Buildup With Buildu TOTALS: 5.589e+00 1.291e-09 2.431e-08 2.503e-12 4.713e-11 Cl-36

Plum Brook Reactor Facility FinalStatus 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) Photons/cm?/sec 1.952e-009 3.674e-008 Photon Energy Fluence Rate MeV/cm 2 /sec 1.291e-009 2.431e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.503e*012 4.713e-011 Absorbed Dose Rate in Air mGy/hr 2.186e-014 4.114e-013 mrad/hr 2.186e-012 4.114e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.588e.014 4.871e-013 o Opposed 2.072e-014 3.900e-013 o Rotational 2.072e-014 3.900e-013 o Isotropic 1 .832e-014 3.449e-013 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 2,750e.014 5.177c-013 o Opposed 2.612e-014 4.917e-013 o Rotational 2.612e*014 4.917e-013 o Isotropic 1.958e-014 3.687e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.288e.014 4.307e-013 o Posterior/Anterior 2.020e.014 3.802e-013 o Lateral . 1.498e.014 2.819e-013 o Rotational 1.805e-014 3.397e-013 o Isotropic 1.536e-014 2.892e.013 Page 1 C1-37

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122107.MS5 Date:

R. ate: December 21, 2005 By:

Runr rime: 1:30:33 PM Checked:

Duration : 00:00:01 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 iurce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points A y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name I Dmension Mate Density Cyl. Core 7.62 cm2 Conci'ete 1.8 Shield 1 .65 cm Iro n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 curies i becquerels Ci/cm Bqlcm2 Eu-152 1.6417e-I 10 6.0744e+000 4.5000e-OC09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Expsure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buiidup2 No Buildup .With Buildup

)4 3.594e+00 1.418e 36 8.333e-33 6.272e-39 3.686e-35 C1-38

Plum Brook Reactor Facility FinalStatus 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 Activit Fluence Rate Fluen~ce Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm-'/sec mR/hr mR/hr No Buildup With Buiidup No Buildup With Buildu 0.05 8.987e-01 3.132e-26 2.928e-25 8.342e-29 7.801e-28 0.1 1.727e+00 4.074e-15 2.024e- 13 6.233e- 18 3.096e. 16 0.2 4.552e-01 3.440e-13 2.243e- 11 6.072e-16 3.959e- 14 0.3 1.642e+00 1.054e- 11 5.126e-10 1.999e.14 9.723e 13 0.4 3.817e-01 9.797e- 12 3.474e- 10 1.909e-14 6.769e- 13 0.5 3.426e.02 2.465e.12 6.636e-1 1 4.839e-15 1.303e 13 0.6 2.576e-01 4.189e-1 1 8.937e- 10 8.176e-14 1.744e 12 0.8 1.082e+00 6.109e-10 9.029e.09 1.162e-12 1.717e-11 1.0 2.599e+00 3.719e-09 4.152e-08 6.855e-12 7.654e-1 1 1.5 1.409e+00 9.875e-09 6.928e.08 1.661e-11 1.166e-10 TOTALS: 1.408e+01 1.427e-08 1.217e-07 2.476e-I 1 2.138e-10 Cl-39

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MiicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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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 Photon Fluence Rate (flux) Photons/cm 2 /sec 1. 120e-008 1.033e-007 Photon Energy Fluence Rate MeV/cm2/sec 1.427e*008 1.217e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.476e-011 2.138e -010 Absorbed Dose Rate in Air mGy/hr 2.161e-013 1.867e-012 mrad/hr 2.161e-011 1.867e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.459e-013 2.13le-012 o Opposed 2.120e-013 1.824e-012 o Rotational 2.120e-013 1.824e.012 o Isotropic 1.895e-013 1.628e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.610e-013 2.265e-012 o Opposed 2.517e-013 2.180e-012 o Rotational 2.517e-013 2.180e-012 o Isotropic 2.002e-013 1.724e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.212e.013 1.914e-012 o Posterior/Anterior 2.039e-013 1.757e-012 o Lateral 1.626e-013 1.392e-012 o Rotational 1.837e-013 1.582e-012 o Isotropic 1.627e-013 1.396e-012 Page 1 Cl-40

Plum Brook Reactor Facility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122108.MS5 Date:

RL "ate: December 21, 2005 By:

Rui, ime: 1:32:17 PM Checked:

Duration : 00:00:01 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 iurce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in I ft 6.0 in I Shield Name Shields Dtimension Material Density Cyl. Core 7.62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide curies bicquerels jpCi/cm 2 Eu-154 1.6417e- 010 6.0744e+000 4.5000e-OC09 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeY photons/sec MeV/cm2/sc MeV/cm2/sec mR/h1 1nR/hr No Buildup With Buildu No Builduwp With Buildup.

04 1.236e+00 4.878e-37 2.866e-33 2.158e-39 1.268e-35 CJ-41

Plum Brook Reactor Facility FinalStatus 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 Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeVY toQns/sec MeV/cM2/5eg M6V/c~m-/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.05 3.140e-01 1.094e-26 1.023e-25 2.915e-29 2.726e-28 0.1 2.458e+00 5.798e- 15 2.880e.13 8.871e-.18 4.406e- 16 0.2 4.148e-01 3.136e-13 2.044e- 11 5.534e-16 3.608e- 14 0.4 4.334e-02 1.112e-12 3.944e- 11 2.167e-15 7.685e-14 0.5 1.315e-02 9.463e-13 2.547e-1 1 1.857e-15 5.000e-14 0.6 4.900e-01 7.968e-11 1.700e-09 1.555e-13 3.318e-12 0.8 2.369e+00 1.338e-09 1.978e-08 2.545e-12 3.761e-11 1.0 1.869e+00 2.674e-09 2.985e.08 4.929e-12 5.503e- 11 1.5 2.370e+00 1.661e-08 1.165e-07 2.795e- 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 ReactorFacility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 1.556e-008 1.353e -007 Photon Energy Fluence Rate MeV/cm 2/sec 2.070e.008 1.679e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.558e-01 1 2.922e-010 Absorbed Dose Rate in Air mGy/hr 3.106e-013 2.55le.012 mrad/hr 3.106e-01 1 2.55le.010 Deep Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 3.528e-013 2.906e-012 o Opposed 3.053e.013 .2.499e.012 o Rotational 3.053e*013 2.499e*012 o Isotropic 2.733e-013 2.233e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.741e-013 3.085e.O1 2 o Opposed 3.613e-013 2.974e*012 o Rotational 3.613e*013 2.974e.012 o Isotropic 2.883e-013 2.36le-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.176e.013 2.612e-012 o Posterior/Anterior 2.934e-013 2.405e.012 o Lateral 2.35le-013 1 .915e.012 o Rotational 2.646e-013 2.167e-012 o Isotropic 2.349e-013 1.916e.012 Page 1 CJ-43

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122109.MS5 Date:

Ru ate: December 21, 2005 By:

Run- rime: 1:33:55 PM Checked:

Duration : 00:00:01 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 iurce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in

'7, Dose Points X Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields 2:

Shield Name D niaI !Density Cyl. Core 7.62 cm2 Conc rete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 310.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons c 0.015: Excluded Library : Grove Nuclide =cj es becguerels pCi/cm' Bq/cm6 Ag-108m 1.6417 e-010 6.0744e+000 4.5000e-0 I09 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons8sec MeVLcm2/sec 1Me cm7 sec mR/hr mRjhr No Buildu With Buildup No Buildup With Buildu 32 3.984e+00 3.590e- 187 1.575e-33 1.244e-188 5.457e-35 Cl-44

Plum Brook ReactorFacility FinalStatus 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 Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildu With Buildup 0.03 1.290e-06 3.735e-73 1.128e-39 3.702e-75 1.118e-41 0.08 4.305e-01 2.032e-17 6.656e- 16 3.216e-20 1.053e-18 0.4 5.460e+00 1.401e-10 4.969e-09 2.730e.13 9.681e.12 0.6 5.491e+00 8.929e 10 1.905e-08 1.743e 12 3.719e-11 0.8 5.497e+00 3.105e-09 4.589e.08 5.906e-12 8.729e-11 TOTALS: 2.086e+01 4.138e-09 6.991e-08 7.922e-12 1.342e.10 C1-45

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 VlicroShield v5.04 (5.04-00362) 12/21/0!

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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) Photons/cm 2/sec 5.720e-009 1.015e-007 Photon Energy Fluence Rate MeV/cm 2 /sec 4.138e-009 6.991e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.922e*Q12 1.342e-010 Absorbed Dose Rate in Air mGy/hr 6.916e*014 1.17le-012 mrad/hr 6.916e*012 1.171e 010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.125e-014 1.382e.012 o Opposed 6.590e*014 1.114e*012 o Rotational 6.590e-014 1.114e*012 o Isotropic 5.826e.014 9.850e.013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 8.661e.014 1.470e-012 o Opposed 8.249e-014 1.399e-012 o Rotational 8.249e-014 1.399e-012 o Isotropic 6.233e-014 1.054e-012 Effective Dose Equivalent Rate (ICRP 51 1987) o Anterior/Posterior Geometry mSv/hr 7.214e-014 1.225e-012 o Posterior/Anterior 6.419e*014 1.087e*012 o Lateral 4.818e-014 8.119e-013 o Rotational 0 5.739e-014 9.708e-013 o Isotropic 4.914e-014 8.297e-013 Page:

CI Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04.00362)

Radiological Services, Inc.

Page :1 File Ref:

DO File: PB122110.MS5 Date:

Ru ate: December 21, 2005 By:

RunrTime: 1:35:45 PM Checked:

Duration : 00:00:01 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 rce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in

= x I)ose Points Y z

1. 1 138.78 cm 381 cm 45.7 cm p 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name Dinlension Material Density Cyl. Core 7.i62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad . 125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curebecquerels nji B1/cm6 Nb-94 1.6417e.010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm/sec MeV/cm-'/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0174 2.148e-03 2.567e-278 6.819e-37 1.386e-279 3.681e-38 0.0175 4.115e.03 1.690e-273 1.319e-36' 8.951e-275 6.984e-38 0.0196 1.209e.03 3.203e-201 4.633e-37 1.182e.202 1.710e-38 0 7026 6.074e+00 1.969e-09 3.433e-08 3.797e-12 6.621e-1 1 711 6.074e+00 4.910e-09 6.513e.08 9.241e-12 1.226e- 10 CJ-47

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Emsure Rate Exmosure Rate MeV 2hotons/sec MeV/cmL'/sec MeV/cml/sec rnR/hr mR/hr No Buildup With BuilduI2 No Buildue2 With Buildup TOTALS: 1.216e+01 6.879e-09 9.946e-08 1.304e-11 1.888e-10 CI-48

Plum Brook ReactorFacility FinalStatus 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) Photons/cm 2 /sec 8.439e.009 1.236e-007 Photon Energy Fluence Rate MeV/cm 2 /sec 6.879e.009 9.946e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.304e-011 1,888e-010 Absorbed Dose Rate in Air mGy/hr 1.138e.013 1.648e-012 mrad/hr 1.138e-011 1.648e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.325e-013 1.920e-012 o Opposed 1.090e-013 1.577e-012 o Rotational 1.090e-013 1.577e*012 o Isotropic 9.639e-014 1.395e-012 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.416e.013 2.052e-012 o Opposed 1.351e-013 1.958e-012 o Rotational 1.35le-013 1.958e-012 o Isotropic 1.031e-013 1.492e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.181e-013 1.710e.012 o Posterior/Anterior 1.059e-013 1 .532e*012 o Lateral . 8.040e-014 1.162e*012 o Rotational 9.477e-014 1.37le-012 o Isotropic 8.163e-014 1.180e.012 Page 1 CI-49

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122905.MS5 Date:

RL. ate: December 29, 2005 By:

Rur-Time: 2:22:38 PM Checked:

Duration : 00:00:01 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 Soulrce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in

. -x

)ose Points X Y z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields nension Material Density Cyl. Core 7. 62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30 .48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad X)25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide c becquerels pCi/cm' B1/cm6 1129 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With BuiiduD No Buildup With Buildup2 0.0295 1.212e+00 4.389e-70 1.007e-33 4.593e.72 1.054e-35 0.0298 2.249e+00 4.520e-68 1.925e-33 4.579e-70 1.951e-35 0.0336 7.995e-01 2.067e-52 1.005e-33 1.471e-54 7.150e-36 0 0396 4.568e-01 3.486e-38 1.022e-33 1.584e.40 4.643e-36 Cl-SO

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate MTTS photons/sec+ MeV/cm2/sec MeV/cm2/sec mR/hr mERr No Buildup With Buildup With Buildup TOTALS: 4.718e+00 3.486e-38 4.959e-33 1.584e-40 4.184e-35 Cl-51

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 M-croShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.0400362)

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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 Results (Summed over energies) Units Without with Buildup Photon Fluence Rate (flux) Photons/cm2/sec 8.807e-037 1.546e-031 Photon Energy Fluence Rate MeV/cm 2 /sec 3.486e-038 4.959e-033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.584e-040 4.184e-035 Absorbed Dose Rate in Air mGy/hr 1.383e-042 3.652e-037 mrad/hr 1.383e*040 3.652e-035 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.979e-042 4.181e-037 o Opposed 9.969e-043 2.097e-037 o Rotational 9.026e.043 1.789e-037 o Isotropic 8.635e-043 1.662e.037 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 1.991e-042 4.557e-037 o Opposed 1.375e-042 3.134e.037 o Rotational 1.375e-042 3.134e-037 o Isotropic 1 00g9e.042 2.316e.037 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.154e-042 1.875e-037 o Posterior/Anterior 6.976e-043 9.692e-038 o Lateral 3.854e.043 5.231e.038 o Rotational 6.273e-043 9.630e.038 o Isotropic 5.142e.043 7.979e-038 Page 1 Cl-52

Plum Brook Reactor Facilit FinalStatus Survey Plan . Revision 0 Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB010402.MS5 Date:

Rt )ate: January 4, 2006 By:

Run Time: 7-55:14 AM Checked:

Duration: 00:00:01 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 urce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12 ft 6.0 in 1 ft 6.0 in z Shields Shield Name .2Dimension Matehiat Density Cyl. Core 7.62 cm2 Conc rete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 I30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide becguereis WCi/cm 2 Bq/cm 2 Sn-126 1.6417e-I 010 6.0744e+000 4.5000e-001 1.6650e.004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activit Fluence Rate Fluence Rate xposure Rate Exposure Rate, WeV photons/sec MeV/cm2/sec MeV/cm2/sec mrR/h mR/hr No Buildup With Buildup No Buildup With Buildup 32 4.702e-01 4.237e-188 1.859e-34 1.468e-189 6.440e.36 CI-53

Plum Brook ReactorFacility FinalStatus 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 Activit Flugnce Rate Fluence Rate Expo~sure Rate Exposure Rate ph oto n s/sec MeV/cml/sec MeV/cm2/sec mR/hr mR/hr No Buildup W&ith Buildup No Buildup With Buildup 0.03 1.779e+00 5.151e-67 1.555e-33 5.105e-69 1.541e-35 0.04 3.034e-02 1.197e-38 7.035e-35 5.295e-41 3.111e-37 0.06 5.821e-01 1.833e-21 3.14!e-20 3.640e-24 6.240e-23 0.08 2.789e+00 1.317e-16 4.313e-15 2.084e- 19 6.825e- 18 TOTALS: 5.650e+00 1.317e-16 4.313e-15 2.084e- 19 6.825e- 18 Cl-54

Plum BrookReactorFacility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362) 01/04/06 MicroShield v5.04 (5.04-00362)

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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) Photons/cm2/sec 1.646e-015 5.39le.014 Photon Energy Fluence Rate MeV/cm-/sec 1.317e-016 4.313e-015 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.084e-019 6.825e.018 Absorbed Dose Rate in Air mGy/hr 1.819e-021 5.958e-020 mrad/hr 1.819e-019 5.958e.018 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.182e.021 1.042e.019 o Opposed 1.695e-021 5.55le-020 o Rotational 1.647e-021 5.395e.020 o Isotropic 1.636e.021 5.357e.020 Shallow Dose Equivalent Rate (ICRP 51

• 1987) o Parallel Geometry mSv/hr 3.153e.021 1.033e-019 o Opposed 2.317e.021 7.589e-020 o Rotational 2.317e-021 7.589e-020 o Isotropic 1.701e-021 5.570e-020 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.673e-021 8.753e-020 o Posterior/Anterior 2.039e-021 6.676e-020 o Lateral 1.256e-021 4.115e-020 o Rotational 1.736e-021 5.687e-020 o Isotropic 1.404e-021 4.600e-020 Page 1 C-s55

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122907.MS5 Date:

RL ate: December 29, 2005 By:

Run-Time: 2:27:29 PM Checked: _ _

Duration : 00:00:01 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 iurce Dimensions Height 762.0 cm 25 ft

. Radius 7.62 cm 3.0 in Dose Points X z

1. 1 138.78 cm 381 cm 45.7 cm 4 ft 6.6 in 12ft 6.0 in 1 ft 6.0 in S Shields Shield Name Dimension Material Density Cyl. Core 7.62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Enerj Yies Nuclide becguerels mciL/m, 9 Bq/cme Zr-95 1.6417e.010 6.0744e+000 4.5000e-0 )09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Activity Fluence Rate FluenceRate Exposure Rate Exposure Rate Me MeV/cm,/sec MeV/cm2/sec mR/hr mR/hr No Buildup2 With Buildup No Buildup With Buildu 0.7242 2.652e+00 9.792e-10 1.643e-08 1.883e-12 3.159e 11 0.7567 3.362e+00 1.499e-09 2.378e-08 2.869e-12 4.551e-11 TOTALS: 6.014e+00 2.478e-09 4.020e-08 4.751e.12 7.709e-I 1 Cl-56

Plum Brook ReactorFacility FinalStatus Survev Plan . Revision 0 Pm c B k R F lS sS y Pn R MicroShield v5.04 (5.04-00362) 12/29/05 MicroShleld v5.04 (5.04-00362)

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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 With Buildup Buildup~

Photon Fluence Rate (flux) Photons/cmz/sec 3.333e.009 5.410e*008 Photon Energy Fluence Rate MeV/cm2/sec 2.478e.009 4.020e*008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.751e-012 7.709e-011 Absorbed Dose Rate in Air mGy/hr 4.148e-014 6.730e.013 mrad/hr 4.148e 012 6.730e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.862e-014 7.890e-013 o Opposed 3.954e-014 6.416e-013 o Rotational 3.954e.O014 6.416e-013 o Isotropic 3.495e-014 5.671e.013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.19le-014 8.423e-013 o Opposed 4.947e-014 8.026e-013 o Rotational 4.947e-014 8.026e-013 o Isotropic 3.740e-014 6.069e-013 Effective Dose Equivalent Rate (ICRP 51 1987) o Anterior/Posterior Geometry mSv/hr 4.319e.014 7.007e-013 o Posterior/Anterior 3.846e.014 6.241e-013 o Lateral 2.892e.014 4.692e-013 o Rotational 3.440e-014 5.582e-013 o Isotropic 2.947e-014 4.782e-013 Page 1 Cl-57

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

IDOS File : PB122908.MS5 Date:

Rt late: December 29, 2005 By:

Runr rime: 2:29:31 PM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in

1. . 4- X Dose Points z

1. 1 138.78 cm 381 cm 45.7 cm 4ft6.6 in 12 ft 6.0 in 1 ft 6.0 in Shields Shield Name IDmension Malerial Density Cyl. Core 7.62 cm2 Concirete 1.8 Shield 1 .65 cm Iro n 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide i becquerels pCi/cm 2 Bq/cm Eu 155 1.6417e- 010 6.0744e+000 4.5000e-OC09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Acivity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MO9 photons/sec MeV/cm2/sec MeV/cm1/sec mR/hr mR/hr N~o BuilduD With Buildup No Buildup With Buildup

)3 1.933e-02 5.599e-69 1.690e-35 5.549e-71 1.675e-37 Cl-58

Plum Brook Reactor Facility FinalStatus 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 Activitv Fluence Rate Fluence Rate Exposure Rate Expos~ure Rate photons/sec MeV/cm2/sec MeV/cm 2/sec mR/hr mR/hr No Buildup2 With Buildup No Buildup2 With Buildug 0.04 1.lOle+00 4.345e-37 2.553e-33 1.922e-39 1.129e-35 0.05 3.581e-01 1.248e-26 1.167e.25 3.324e-29 3.109e-28 0.06 7.878e-02 2.480e-22 4.251e-21 4.926e-25 8.444e-24 0.08 1.886e+00 8.905e-17 2.917e-15 1.409e-19 4.615e 18 0.1 1.256e+00 2.962e-15 1.471e- 13 4.532e-18 2.25le-16 TOTALS: 4.699e+00 3.051e.15 1.501e.13 4.673e-18 2.297e- 16 Cl-59

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cmz/sec 3.074e-014 1.508e-012 Photon Energy Fluence Rate MeV/cm2/sec 3.05le-015 1.501e-013 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.673e*018 2.297e.016 Absorbed Dose Rate in Air mGy/hr 4.079e-020 2.006e.018 mrad/hr 4.079e*018 2.006e.016 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.827e-020 3.355e-018 o Opposed 3.740e.020 1.839e-018 o Rotational 3.737e-020 1.838e-018 o Isotropic 3.619e-020 1.779e-018 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.782e*020 3.333e-018 o Opposed 5.254e.020 2.583e-018 o Rotational 5.254e.020 2.583e-018 o Isotropic 3.826e-020 1.881e-018 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 5.865e-020 2.883e-018 o Posterior/Anterior 4.595e-020 2.259e-018 o Lateral 2.836e-020 1.394e-018 o Rotational 3.925e-020 1.930e-018 o Isotropic 3.124e-020 1.535e-018 Page 1 Cl-60

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Pare :1 File Ref:

D( ile : PB121909.MS5 Date:

Rue te: December 19, 2005 By:

Run-,ime: 11:05:13AM Checked:

Duration : 00:00:01 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 rce Dimensions Height 762.0 cm 25ft Radius 3.81 cm 1.5 in

[)ose Points z

1. 1 134.97 cm 381 cm 91.44 cm 4ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dia iension Mate rial Cyl. Core 3J.1 cm 2 Conct:ete 1.8 Shield 1 .65 cm Iroi 7.86 Transition Concrete 2.4 Shield 3 30..48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels 4 0i0cm0 Bq/cm Cow60 8.2087e-01 1 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential . 20 Results Energy Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 12hotons/sec MeV/cm2/sec MeV/cmLsec LmR/h No Buildup With Buildup No Buildup With Buildup 0.6938 4.954e-04 7.277e-14 1.510e-12 1.405e-16 2.916e-15 1.1732 3.037e+00 4.717e-09 4.857e-08 8.429e. 12 8.679e 11 1 3325 3.037e+00 8.038e-09 7.095e.08 1.395e-l1 1.231e-10 T kLS: 6.075e+00 1.275e-08 1. 195e-07 2.237e- 11 2.099e-10 Cl-61

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 1.005e.008 9.464e-008 2

-Photon Energy Fluence Rate MeV/cm /sec 1.275e-008 1.195e-007 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.237e-01,1 2.099e-010 Absorbed Dose Rate in Air mGy/hr 1.953e-013 1.832e-012 mrad/hr 1.953e-01 1 1.832e-010 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.217e-013 2.080e-012 o Opposed 1.910e-013 1.79le.012 o Rotational 1.910e-013 1.79le-012 o Isotropic 1.706e-013 1 .600e-012 Shallow Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 2.360e- 013 2.215e-012 o Opposed 2.273e-013 2.132e-012 o Rotational 2.273e-013 2.132e-012 o Isotropic 1.808e-013 1.695e-012 Effective Dose Equivalent Rate (ICRP 51 .1987) o Anterior/Posterior Geometry mSv/hr 1.997e-013 1.873e-012 o Posterior/Anterior 1.840e.013 1.725e-012 o Lateral 1.463e013 1.372e-012 o Rotational 1.657e-013 1.554e-012 o Isotropic 1.466e.013 1.375e-012

-Page 1 CJ-62

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122111.MS5 Date: _

Ru te: December 21, 2005 By:

Run- time: 1:45:09 PM Checked:

Duration: 00:00:01 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 25 ft Radius 3.81 cm 1.5 in Dose Points Y z

1. 1 134.97 cm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name I Dimension Mat erial Density Cyl. Core 3.81 cm2 Con(:rete 1.8 z11

-x Shield 1 .65 cm Ir ton 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclid curies becquerels wCi/cm Bg/cm Ba-137m 7.7654e-011 2.8732e+000 4.2570e-009 1.5751e-004 Cs- 137 8.2087e-01 1 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener Activity Fluence Rate Flece Rate Exposure Rate Exposure Rate Mey photons/sec MeV/cmz/sec MeV/,cm2/sec mR/hr mR/hr Nlo Buildup With Buildup Nlo Buildup With Buildup 0.0318 5.948e-02 1.933e-65 5.403e-35 1.610e-67 4.500e-37 0.0322 1.097e-01 1.659e-63 1.036e-34 1.335e-65 8.337e-37 0 n364 3.994e-02 1.318e-49 5.773e-35 7.489e-52 3.280e-37 i16 2.585e+00 3.035e-10 6.721e-09 5.884e-13 1.303e-11 C1-63

Plum Brook ReactorFacility FinalStatus 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 Activit Fluence Rate Fluence Rate Exposure Rate ExPosurg , Rate

.MOL photons/sec MeV/cm-'/sec MeV/cm2/sec mR/hr mWiB No Buildup With Buildup No Buildup h~B~u itdup TOTALS: 2.794e+00 3.035e- 10 6.721e-09 5.884e- 13 1.303e 11 Cl-64

Plum Brook Reactor Facility FinalStatus Survey Plan - Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.0400362)

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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 Results (Summed over energies) Without .with Bul~duM Photon Fluence Rate (flux) Photons/cm 2 /sec 4.587e-010 1.016e.008 Photon Energy Fluence Rate MeV/cm 2 /sec 3.035e-010 6.72le*009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 5.884e-013 1.303e-01 1 Absorbed Dose Rate in Air mGy/hr 5.137e-015 1.137e-013 mrad/hr 5.137e-013 1.137e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.082e-015 1.347e.013 o Opposed 4.869e*015 1.078e-013 o Rotational 4.869e*015 1.078e.013 o Isotropic 4.306e-015 9.534e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 6.464e-015 I14316-013 o Opposed 6.139e-015 1.359e-013 o Rotational 6.139e-015 1.359e-013 o Isotropic 4.603e-015 1 .019e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 5.378e-0 15 1.19le-013 o Posterior/Anterior 4.747e.015 1.05le-013 o Lateral 3.520e-015 7.794e-014 o Rotational 4.242e*015 9.392e-014 o Isotropic 3.61le-015 7.996e-014 Page 1

_I Cl-65

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DO" File : PB122112.MS5 Date:

RL te: December 21, 2005 By:

Run ime: 1:48:57 PM Checked:

Duration :00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points

1. 1 134.97 cr n Y

381 cm z

91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dimension Mlat tria Density Cyl. Core 3.81 cm2 Conccrete 1.8 Shield 1 .65 cm ircon 7.86

- Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclid1 i becquerels UCi/cm Bq/c6m6 Eu-152 8.2087e- 011 3.0372e+000 4.5000e-OC09 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Atiitb Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 1hoton7/sec MeV/cm25sec MeV/cml/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

)4 1.797e+00- 5.750e-40 3.614e.33 2.543e-42 1.598e-35 Cl-66

Plum Brook Reactor Facility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Eggosure Rate MeV photonstsec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.05 4.493e-01 1 .622e-28 1.584e-27 4.320e-31 4.220e.30 0.1 8.635e-01 2.796e-16 1.693e-14 4.278e- 19 2.591e-17 0.2 2.276e-01 4.533e.14 3.792e- 12 8.00le-17 6.693e-15 0.3 8.212e.01 1.744e.12 1.067e.10 3.309e- 15 2.025e- 13 0.4 1.909e-01 1.864e-12 8.121e 11 3.632e-15 1.582e- 13 0.5 1.713e-02 5.178e.13 1.678e 11 1.016e-15 3.293e- 14 0.6 1.288e-01 9.480e-12 2.399e- 10 1.850e- 14 4.682e- 13 0.8 5.408e-01 1.539e-10 2.629e-09 2.927e-13 5.00le-12 1.0 1.300e+00 1.009e-09 1.275e-08 1.860e. 12 2.350e-11 1.5 7.046e-01 3.006e-09 2.317e-08 5.058e- 12 3.898e- 11 TOTALS: 7.040e+00 4.183e-09 3.899e-08 7.238e-12 6.835e- 11 CJ-67

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/0!

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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 WJlih

.Bildup Photon Fluence Rate (flux) Photons/cm 2 /sec 3.233e-009 3.249e-008 Photon Energy Fluence Rate MeV/cm 2 /sec 4.183e-009 3.899e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 7.238e.012 6.835e-011 Absorbed Dose Rate in Air mGy/hr 6.319e.014 5.967e-013 mrad/hr 6.319e-012 5.967e-011 Deep Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 7.183e-014 6.805e-013 o Opposed 6.201e-014 5.835e*013 o Rotational 6.201e-014 5.835e.013 o Isotropic 5.545e-014 5.209e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 7.624e-014 7.232e.O1 3 o Opposed 7.355e-014 6.963e-013 o Rotational 7.355e-014 6.963e-013 o Isotropic 5.858e-014 5.515e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 6.464e-014 6.116e-013 o Posterior/Anterior 5.963e-014 5.620e-013 o Lateral 4.764e-014 4.458e-013 o Rotational 5.375e-014 5.060e-013 o Isotropic 4.764e-014 4.468e-013 Page:

CJ-68

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122113.MS5 Date:

RL te: December 21, 2005 By:

Run ,ime: 1:50:31 PM Checked:

Duration : 00:00:01 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 Source Dimensions Height 762.0 cm 25ft Radius 3.81 cm 1.5 in Dose Points

1. 1 134.97 cr Tn Y z 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dimension Mat reial Density Cyl. Core 3.81 cm 2 Conccrete 1.8 Shield 1 .65 cm Ircon 7.86 z

Transition Conc-rete 2.4 Shield 3 30.48 cm Conc,rete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide ibtecquerel u m BQ/cm6 Eu 154 8.2087e-()11 3.0372e+000 4.5000eOC09 1.6650e 004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activit Fluence Rate Fluence Rae Exposure Rate Exposure Rate MeOY phbotons/s MeV/cm2/sec MeV/cm"/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

. )4 6.181e-01 1.978e-40 1.243e-33 8.748e-43 5.497e-36 CJ-69

Plum Brook Reactor Facility FinalStatus 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& Activit Fluence Rate Fluence Rate Exoosure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.05 1.570e-01 5.666e-29 5.536e-28 1.509e-31 1.475e-30 0.1 1.229e+00 3.980e-16 2.410e-14 6.089e-19 3.687e-17 0.2 2.074e-01 4.131e-14 3.456e-12 7.292e-17 6.099e- 15 0.4 2.167e602 2.117e-13 9.220e-12 4.124e-16 1.796e-14 0.5 6.576e-03 1.988e-13 6.440e- 12 3.901e-16 1.264e-14 0.6 2,450e-01 1.803e 11 4.563e-10 3.519e-14 8.906e-13 0.8 1.184e+00 3.371e-10 5.759e.09 6.41 le-13 1.095e-11 1.0 9.343e-01 7.256e-10 9.166e-09 1.337e-12 1.690e-11 1.5 1. 185e+00 5.057e-09 3.897e-08 8.508e-12 6.557e-11 TOTALS: 5.789e+00 6.138e-09 5.437e-08 1.052e-11 9.434e-11 CI-70

Plum Brook ReactorFacility FinalStatus Survey Plan, Revision 0 licroShield v5.04 (5.04-00362) 12/21/0 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 4.549e.009 4.316e.008 Photon Energy Fluence Rate MeV/cm 2 /sec 6.138e-009 5.437e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.052e-01 1 9.434e-011 Absorbed Dose Rate in Air mGy/hr 9.186e-014 8.236e-013 mrad/hr 9.186e-012 8.236e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.043eO013 9.376e-013 o Opposed 9.036e 014 8.075e-013 o Rotational 9.036e-014 8.075e-013 o Isotropic 8.090e-014 7.218e-013 Shallow Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 1.106e-013 9.952e-013 o Opposed 1.068e-013 9.598e-013 o Rotational 1.068e-013 9.598e-013 o Isotropic 8.533e-014 7.628e-013 Effective Dose Equivalent Rate (ICRP 51 .1987) o Anterior/Posterior Geometry mSv/hr 9.389e.014 8.432eO013 o Posterior/Anterior 8.680e-014 7.767e-013 o Lateral 6.966e-014 6.193e-013 o Rotational 7.83le-014 7.00le-013 o Isotropic 6.957e-014 6.197e-013 Page CI-71

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122114.MS5 Date:

Ru ate: December 21, 2005 By:

Runr rime: 2:10:25 PM Checked: -

Duration : 00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points

1. 1 A

134.97 cr n 381 cm z

91.44 cm 4 ft 5.1 In 12 ft 6.0 in 3ft Shields Shield Name Dimension Mat Kria1 Density Cyl. Core 3.81 cm 2 Conc:rete 1.8 Shield 1 .65 cm Ircon 7.86 z

Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide cud,as uCi/cm2 Bq/Cm2 Ag-108m 8.2087oc-011 3.0372e+000 4.5000e-01)9 1 .6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) - 20 Circumferential 20 Results Ener Activit Fluence Rate Fluence Rate Exposure Rat Exposure Rate 2Y photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr .3mR/h With Buildup No Buildup With Buildup2

)2 1.992e+00 1.913e 206 6.831e-34 6.626e-208 2.366e-35 Cl-72

Plum Brook ReactorFacility FinalStatus 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 Activity Fluence Rate Fiuence Rate Exp~osure Rate Exposure Rate MeY photons/sec MeV/cm2/sec :MeV/cm2/sec mR/hr mR/hr No Buildup With Builldu No Bujildup With Buildup 0.03 6.449e.07 1.192e-79 4.890e.40 1.182e-81 4.846e-42 0.08 2.152e-01 9.096e-19 3.469e- 17 1.439e-21 5.489e-20 0.4 2.730e+00 2.666e-1 1 1.161e-09 5.195e-14 2.263e-12 0.6 2.745e+00 2.021e-10 5.113e-09 3.944e-13 9.981e-12 0.8 2.749e+00 7.822e.10 1.336e-08 1.488e-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 ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShleld v5.04 (5.04-00362)

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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 WULIt Buildup Photon Fluence Rate (flux) Photons/cm2/sec 1.381e.009 2.813e.008 Photon Energy Fluence Rate MeV/cm'/sec 1.01 le-009 1.964e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.934e-012 3.766e-01 I Absorbed Dose Rate in Air mGy/hr 1.689e.014 3.288e*013 mrad/hr 1.689e-012 3.288e-01 1 Deep Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 1.982e*014 3.875e-013

.o Opposed 1.610e-014 3.129e-013 o Rotational 1.610e.014 3.129e-013 o Isotropic 1.423e-014 2.767e-013 Shallow Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 2.114e.014 4.125e-013 o Opposed 2.013e*014 3.926e*013 o Rotational 2.013e-014 3.926e.013 o Isotropic 1.523e-014 2.960e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.760e-014 3.436e.013 o Posterior/Anterior 1.567e-014 3.051e-013 o Lateral 1.178e-014 2.282e-013-o Rotational 1.402e-014 2.726e-013 o Isotropic 1.201e-014 2.33le-013 Page 1 Cl-74

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Plum Brook Reactor Facility Final Status Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122115.MS5 Date:

RL ate: December 21, 2005 By:

Run-Time: 2:04:46 PM Checked:

Duration : 00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in I)ose Points

1. 1 134.97 cm 381 cm z

91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Nam Din lension Material Cyl. Core 3.181 cm' Concrete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30 .48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad . 025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclid curies becguerel wCi/cm2 Bq/CM2 Nb-94 8.2087e-011 3.0372e+000 4.5000e-009 1.6650e 004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener Activit Fluence Rate Fluenre Rate Exposure Rate ,xposure Rate MeV N photons/sec MeV/c-LmLsec MeV/cm"/sec mR/hr mR/hr No Buildup , With Buildup No Buildup ihBuilup 0.0174 1.074e.03 4.704e-307 2.957e-37 2.539e*308 1.596e-38 0.0175 2.057e-03 9.585e.302 5.718e*37 5.076e-303 3.028e-38 0.0196 6.044e-04 1.268e-221 2.009e-37 4.682e-223 7.416e-39 0 7026 3.037e+00 4.733e 10 9.655e-09 9.128e-13 1.862e- 11 711 3.037e+00 1.274e-09 1.937e.08 2.397e- 12 3.646e-1 1 Cl-75

Plum Brook ReactorFacility FinalStatus 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 Activit Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 6.078e+00 1.747e.09 2.903e-08 3.310e-12 5.508e- 11 Cl-76

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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 With Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 2.136e-009 3.598e*008 Photon Energy Fluence Rate MeV/cm 2 /sec 1.747e-009 2.903e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.310e-012 5.508e-01 1 Absorbed Dose Rate in Air mGy/hr 2.890e-014 4.808e-013 mrad/hr 2.890e-012 4.808e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.362e-014 5.600e-013 o Opposed 2.768e-014 4.602e-013 o Rotational 2.768e-014 4.602e-013 o Isotropic 2.447e-014 4.069e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.595e-014 5.986e-013 o Opposed 3.430e-014 5.710e-013 o Rotational 3.430e-014 5.710e-013 o Isotropic 2.619e-014 4.354e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.996e-014 4.989e-013 o Posterior/Anterior 2.688e-014 4.470e-013 o Lateral 2.042e-014 3.391e-013 o Rotational 2.406e-014 4.002e-013 o Isotropic a 2.073e-014 3.445e-013 Page 1 Cl-77

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Page :1 File Ref:

DOS File: PB122909.MS5 Date:

RL ate: December 29, 2005 By:

RurnTime: 2:36:06 PM Checked:

Duration : 00:00:01 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,ce Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in lose Points Y z

1. 1 134.97 cm 381 cm 91.44 cm 4ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dimensinn ~ Mateerial Density Cyl. Core 3.f 31 cmz Conc rete 1.8 Shield 1 65 cm iron 7.86 Transition Concrete 2.4 Shield 3 30. 48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method: Actual Photon Energies Nuclide -0curies 1 3.372e00 4500cm0 1q/cm6 129 8.2087e-011I 3.0372e+000 4.5000e 009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results E dney Activity Fluence Rate Fluence Rate Exposure Rate Exp~osure Rate MOb photons/sec MeV/cml/sec MeV/cmL/sec mR/r mR/hr No Buildup With Buildup No Buildup With Buildup 0.0295 6.061e-01 6.977e-77 4.366e-34 7.301e-79 4.569e-36 0.0298 1.124e+00 1.092e.74 8.349e-34 1.107e-76 8.458e-36 0.0336 3.998e*01 2.344e-57 4.359e-34 1.667e-59 3.100e-36 Co 0396 2.284e-01 1.196e-41 4.431e-34 5.435e-44 2.013e-36 CJ-78

Plum Brook ReactorFacility FinalStatus 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 Fluenice Rate Exposure Rate Exposure Rate May photons/sec MeV/rml/sec MeV/cm2/sec mR/hr mR/hr No BuilduI With Buildup No Buildu With Buildup TOTALS: 2.359e+00 1.196e-41 2.150e-33 5.435e-44 1.814e-35 CJ-79

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04.00362) 12/29/05 MicroShield v5.04 (5.04.00362)

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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 Results (Summed over energies) Units Without With Buld~up Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 3.022e-040 6.702e-032 Photon Energy Fluence Rate MeV/cm 2 /sec 1.196e-041 2.150e-033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 5.435e-044 1.814e-035 Absorbed Dose Rate in Air mGy/hr 4.745e-046 1.584e-037 mrad/hr 4.745e-044 1.584e-035 Deep Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 6.792e-046 1.813e-037 o Opposed 3.421 e-046 9.094e-038 o Rotational 3.097e-046 7.757e-038 o Isotropic 2.963e-046 7.205e-038 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 6.834e-046 1.976e-037 o Opposed 4.717e-046 1.359e-037 o Rotational 4.717e-046 1.359e-037 o Isotropic 3.462e-046 1.004e-037 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.960e-046 8.128e-038 o Posterior/Anterior 2.394e-046 4.203e-038 o Lateral 1.322e-046 2.268e-038 o Rotational 2.153e-046 4.176e-038 o Isotropic 1.764e-046 3.460e-038 Page 1 Cl-80

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Page :1 File Ref:

DOS File : PB122911.MS5 Date:

RL ate: December 29, 2005 By:

Run- fime: 2:42:27 PM Checked:

Duration: 00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in

[)ose Points

1. 1 134.97 cm 381 cm z

91.44 cm 4ft 5.1 in 12 ft 6.0 in 3ft Shields Shed a Dinnension2 Material Density Cyl. Core 81 cm 3.J Concrete 1.8

_. Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30..48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad . 025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies rNuclide curies becquerels 45i0eM 1q.cm6 Zr-95 8.2087e-01 I 3.0372e+000 4.5000e 009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Eneg Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 2hotons/sec MeV/rcm2sec MeV/cm'/lsec mR/hr mR/hr No Buildup With Buildup No Buildup - With Buildup 0.7242 1.326e+00 2.380e.10 4.659e.09 4.577e-13 8.958e- 12 0.7567 1.681e+00 3.702e-10 6.824e.09 7.085e- 13 1.306e- 11 TOTALS: 3.007e+00 6.082e 10 1. 148e-08 1.166e.12 2.202e-1 1 CJ-81

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 IcroShield v5.04 (5.0400362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 8.178e*OlO 1.545e*008 Photon Energy Fluence Rate MeV/cm 2 /sec 6.082e-010 1.148e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.166e-012 2.202e-01 1 Absorbed Dose Rate in Air mGy/hr 1.018e-014 1.922e-013 mrad/hr 1.018e-012 1.922e-011 Deep Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 1.193e-014 2.254e-013 o Opposed 9.705e-015 1.832e-013 o Rotational 9.705e-015 1.832e-013 o Isotropic 8.578eO015 1.620e-013 Shallow Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 1.274e-014 2.406e*013 o Opposed 1.214e-014 2.292e-013 o Rotational 1.214e-014 2.292e-013 o Isotropic 9.181e-015 1.733e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.060e-014 2.00le*013 o Posterior/Anterior 9.441e.015 1.783e*013 o Lateral 7.098e-015 1 .340e-013 o Rotational 8.444e*015 1.594e-013 o Isotropic 7.233e-015 1.366e-013 Page 1 Cl-82

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB010403.MS5 Date: _

RL ate: January 4, 2006 By:

RurVTime: 7:59:23 AM Checked:

Duration :00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points y z

1. 1 134.97 ccm 381 cm 91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3 ft Shields Shield Name Dimension Mate EaW Density Cyl. Core 3.81 cm2 Concirete 1.8 Shield 1 .65 cm Iron 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide curies 2kbecquerels Ci/cm Sn 126 8.2087e-()11 3.0372e+000 4.5000e-OC09 1.6650e-004 Buildup The material reference Is : Cyl. Core tegration Parameters Y Direction (axial) 20 Circumferential 20 Results En Act3v1t Fluence Rat P. Fluence Rate Exposure Rate Exposure Rate MeV photons/sec Me/cAm2Lse MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buiidup

)2 2.35le-01 2.258e.207P 8.062e-35 7.820e 209 2.792e-36 Cl-83

IPlum Brook ReactorFacility FinalStatus Survey Plan Revision O Plum Brook Reactor Facility FinalStatus 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 Fluende Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup2 No Buildup With Buildup 0.03 8.893e-01 1.644e-73 6.743e-34 1.630e-75 6.683e-36 0.04 1.517e-02 4.854e-42 3.051e-35 2.147e.44 1.349e-37 0.06 2.91 le-01 3.017e-23 5.881e-22 5.993e-26 1.168e-24 0.08 1.395e+00 5.894e-18 2.247e- 16 9.326e-21 3.557e-19 TOTALS: 2.825e+00 5.894e-18 2.247e- 16 9.327e-21 3.557e-19 Cl-84

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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 With Buildu Buildup Photon Fluence Rate (flux) Photons/cm2/sec 7.367e-017 2.809e-015 Photon Energy Fluence Rate MeV/cmz/sec 5.894e-018 2.247e-016 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 9.327e-021 3.557e-019 Absorbed Dose Rate in Air mGy/hr 8.142e-023 3.105e-021 mrad/hr 8.142e-021 3.105e-019 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.424e-022 5.43le-021 o Opposed 7.585e-023 2.893e-021 o Rotational 7.373e-023 2.812e-021 o Isotropic 7.320e-023 2.79le-021 Shallow Dose Equivalent Rate (tCRP 51 - 1987) o Parallel Geometry mSv/hr 1.41 le-022 5.380e-021 o Opposed 1.037e-022 3.954e-021 o Rotational 1.037e-022 3.954e-021 o Isotropic 7.612e-023 2.903e-021 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.196e-022 4.561e-021 o Posterior/Anterior 9.123e-023 3.479e-021 o Lateral 5.623e-023 2.144e-021 o Rotational 7.771e-023 2.963e-021 o Isotropic 6.286e-023 2.397e-021 Page 1 Cl-85

Plum Brook ReactorFacility FinalStatus Survey Plan Revisiorn 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOR File: PB122912.MS5 Date:

RL ate: December 29, 2005 By:

Run-Time: 2:45:53 PM Checked:

Duration : 00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points

1. 1 134.97 ciii Y

381 cm z

91.44 cm 4 ft 5.1 in 12 ft 6.0 in 3ft Shields Shield Name Dimension Mat terial Density Cyl. Core 3.81 cm2 Con( :rete 1.8 Shield 1 .65 cm In)on 7.86 z Transition Conmcrete 2.4 Shield 3 30.48 cm Conccrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide curies becquerels JCi/cm2 Eu 155 8.2087e-I01l 3.0372e+000 4.5000e-00'9 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener Activi Fluence Rate Fluence Rate iExosure Rate Exposue Rate MO6 photons/sec MeV/cm2/sec MeV/cm7/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

)3 9.667e 03 1.787e-75 7.330e 36 1.77le-77 7.264e.38 CJ-86

Plum Brook ReactorFacility FinalStatus 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 Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate Key photons/seQ Me~cM21ser. MeqV/m2/sec mR/hr mR/hr No BuilduI With Buildup No Buildup2 With Buildup 0.04 5.505e-01 1.762e -40 1.107e-33 7.791e-43 4.896e-36 0.05 1.791e-01 6.462e-29 6.313e-28 1.721e-31 1.682e-30 0.06 3.939e-02 4.083e-24 7.960e-23 8.1 10e-27 1.581e-25 0.08 9.431e-01 3.986e-18 1.520e-16 6.307e-21 2.405e- 19 0.1 6.279e-01 2.033e-16 1.231e-14 3.111e-19 1.884e-17 TOTALS: 2.350e+00 2.073e.16 1.246e.14 3.174e.19 1.908e-17 CI-87

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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 Results (Summed over energies) Units Without With BuidI Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 2.083e-015 1.250e-013 Photon Energy Fluence Rate MeV/cm 2 /sec 2.073e-016 1.246e-014 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.174e-019 1.908e-017 Absorbed Dose Rate in Air mGy/hr 2.77le-021 1.665e-019 mrad/hr 2.771e-019 1.665e-017 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.635e-021 2.785e-019 o Opposed 2.540e-021 1.526e-019 o Rotational 2.539e-021 1.526e-019 o Isotropic 2.458e-021 1.477e-019 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.604e-021 2.767e-019 o Opposed 3.569e-021 2.145e-019 o Rotational 3.569e-021 2.145e-019 o Isotropic 2.599e-021 1.562e-019 Effective Dose Equivalent Rate (ICRP 51 . 1987) o Anterior/Posterior Geometry mSv/hr 3.982e-021 2.393e-019 o Posterior/Anterior 3.121e-021 1.876e-019 o Lateral 1.926e-021 1.158e-019 o Rotational 2.666e-021 1.602e-019 o Isotropic 2.121e-021 1.275e-019 Page 1 CI-88

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Page :1 File Ref:

DOS File: PB121911.MS5 Date:

Ri )ate: December 19, 2005 By:

Run Time: 11:14:14 AM Checked:

Duration : 00:00:01 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 rce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in I)ose Points

Y  : Z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name D2in iension Matearia I Density Cyl. Core 7.152 cm2 Conci,et e 1.8 Shield 1 .65 cm Iro n 7.86 I Transition Concret e 2.4 Shield 3 30, .48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .0025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies bec+uerels 4Ci/crn 0 Bq/cm1 Co-60 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeVcm2/sec mR/hr rnR/hr No Buildu With Buildup No Buildup 0.6938 9.909e-04 1.951e.14 5.213e-13 3.766e-17 1.006e- 15 1.1732 6.074e+00 1.764e-09 2.250e-08 3.151e-12 4.022e-1 1 1.3325 6.074e+00 3.243e-09 3.513e.08 5.627e-12 6.095e. 11

.ALS: 1.215e+01 5.007e-09 5.764e-08 8.778e-12 1.012e-10 Cl-89

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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) Photons/cm 2/sec: 3.937e-009. 4.555e*008 Photon Energy Fluence Rate MeV/cM2/sec 5.007e*009 5.764e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 8.778e-012 1.012e-010 Absorbed Dose Rate in Air mGy/hr 7.663e*014 8.832e-013 mrad/hr 7.663e-012 8.832e-011 Deep Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 8.699e-014 1.003e-012 o Opposed 7.495e-014 8.636e-013 o Rotational 7.495e-014 8.636e-013 o Isotropic 6.696e.014 7.714e-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) -

o Parallel Geometry mSv/hr 9.259e-014 1.067e-012 o Opposed 8.916e-014 1.028e-012 o Rotational 8.916e-014 1.028e-012 o Isotropic 7.093e-014 8.173e.013 Effective Dose Equivalent Rate (iCRP 51 .1987) o Anterior/Posterior Geometry mSv/hr 7.834e-014 9.030e-013 o Posterior/Anterior 7.218e-014 8.318e-013 o Lateral 5.743e-014 6.614e-013 o Rotational 6.500e-014 7.489e-013 o Isotropic 5.754e-014 6.628e-013 Page 1 Cl-90

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.Plum Facility -FinalStatus Survey Final Status Survey Plan, , Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DO" Pile: PB122116.MS5 Date:

Ru ate: December 21, 2005 By:

Run Time: 2:17:24 PM Checked: _

Duration : 00:00:01 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 -ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in I)ose Points

1. 1 138.78 cm z

381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields ShiedNme Diniension Mlyateriali Density Cyl. Core 7. 62 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 z Transition Concrete 2.4 Shield 3 30..48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .0125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becquerels Ci/cm2 Bq/cm2 Ba-137m 1.5531e-010 5.7464e+000 4.2570e-009 1.5751e-004 Cs-137 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene Activty Fluence R~ate Fluence Rate Exposure Rate Exposure Rate MOV 12hotons/ser. MeV/cM2/sec MeV/L2/sec mRlhr mR/hr No Buildup With Buildup No Buildup 0.0318 1.190e-01 2.257e-73 8.498e-35 1.880e.75 7.078e.37 0.0322 2.195e-01 3.354e-71 1.629e-34 2.699e-73 1.31le-36 rf "364 '7.987e-02 2.920e-55 9.080e-35 1.659e-57 5.159e-37

, j316 5.171e+00 7.886e- 11 2.257e*09 1.529eK13 4.375e- 12 Cl-91

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate MOY photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildlup No Buildup2 With Buildup TOTALS: 5.589e+00 7.886e- 11 2.257e-09 1.529e.13 4.375e-12 Cl-92

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShield v5.04 (5.0400362)

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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 with Buildup Buildup Photon Fluence Rate (flux) Photons/cm2/sec 1.192e-010 3.41le-009 2

Photon Energy Fluence Rate MeV/cm /sec 7.886e*O1 1 2.257e-009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.529e.013 4.375e-01 2 Absorbed Dose Rate in Air mGy/hr 1.335e-015 3.819e-014 mrad/hr 1.335e.013 3.819e.012 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.580e-015 4.522e-014 o Opposed 1.265e-015 3.620e-014 o Rotational 1.265e-015 3.620e-014 o Isotropic 1.119e.015 3.201e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.680e-015 4.806e-014 o Opposed 1.595e-015 4.565e.014 o Rotational 1.595e-015 4.565e-014 o Isotropic 1.196e-015 3.422e-014 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 1.397e-015 3.998e.014 o Posterior/Anterior 1.233e-015 3.529e-014 o Lateral 9.146e-016 2.61 7e-014 o Rotational 1.102e-015 3.154e-014 o Isotropic 9.383e-016 2.685e.014 Page 1 Cl-93

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122117.MS5 Date:

RL ate: December 21, 2005 By:

RundTime: 2:23:34 PM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points x z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name IDimension Mate ria I DensitY Cyl. Core 7.62 cm2 Conc ret,e 1.8 Shield 1 .65 cm Iron 7.86 2: Transition Concret e 2.4 Shield 3 30.48 cm Concreti a 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide curies becquerels UCi/Cm Bq/cm2 Eu.152 1.6417e-I 10 6.0744e+000 4.5000e-O( 809 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy. Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate hotons/sec MeV/cm2/sec MeV/cml/sec mR/h7 mR/hr No Buildu With Buildup No Buildup With Buildup 34 3.594e+00 1.705e-44 5.683e-33 7.540e 47 2.514e-35 CJ-94

Plum Brook Reactor Facility FinalStatus 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 Activity Fluence Rate Fiuence Rate Exposure Rate Exposure Rate MeV p2hotons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buidu With Buildup No Buildup With Buildup 0.05 8.987e-01 2.286e.31 2.318e-30 6.091e-34 6.175e-33 0.1 1.727e+00 1.425e.17 1.080e-15 2.179e 20 1.653e- 18 0.2 4.552e-01 5.009e.15 5.689e-13 8.840e-18 1.004e 15 0.3 1.642e+00 2.624e-13 2.178e 11 4.978e-16 4.132e-14 0.4 3.817e-01 3.443e-13 2.007e- 11 6.708e-16 3.91 le-14 0.5 3.426e.02 1.116e.13 4.775e.12 2.190e 16 9.372e-15 0.6 2.576e-01 2.309e.12 7.607e- 11 4.506e-15 1.485e- 13 0.8 1.082e+00 4.526e-1 1 9.859e 10 8.608e-14 1.875e- 12 1.0 2.599e+00 3.419e-10 5.424e-09 6.302e 13 9.998e-12 1.5 1.409e+00 1.299e-09 1.218e-08 2.185e.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 FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/21/05 MicroShleld v5.04 (5.04-00362)

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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) Photons/cm t /sec 1.270e-009 1.504e-008 2

Photon Energy Fluence Rate MeV/cm /sec 1.689e-009 1.872e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.907e*012 3.261e-011 Absorbed Dose Rate in Air mGy/hr 2.538e-014 2.847e-013 mrad/hr 2.538e-012 2.847e-O11 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 2.882e-014 3.242e-013 o Opposed 2.494e-014 2.789e-013 o Rotational 2.494e- 014 2.789e-013 o Isotropic 2.232e-014 2.491e-013 Shallow Dose Equivalent Rate (ICRP 51

• 1987) o Parallel Geometry mSv/hr 3.058e-014 3.443eO013 o Opposed 2.952e-014 3.318e-013 o Rotational 2.952e-014 3.318e-013 o Isotropic 2.356e-014 2.635e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.595e*014 2.915e-013 o Posterior/Anterior 2.397e-014 2.684e-013 o Lateral 1.920e-014 2.136e-013 o Rotational 2.162e.014 2.418e-013 o Isotropic 1.919e-014 2.139e-013 Page 1 Cl-96

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOF File: PB122118.MS5 Date:

Ru ate: December 21, 2005 By:

RunhTime: 2:24:58 PM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points z

1. 1 138.78 cm 381 cm 137.16 cm 4ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Nam IDniension Mate etaI Density Cyl. Core 7.62 cm2 Conc rete 1.8 Shield 1 .65 cm Iraan 7.86 z Transition Concret e 2.4 Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide i becquerels Uici/cm2 Bq/cm2 Eu-154 1.6417e. 010 6.0744e+000 4.5000e-OC09 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate M&E photons/sec MeV/cM2/sec MeV/cm-/sec mR/br mR/hr Nojuildup With.-Build~up No-uil-d With Buildup 34 1.236e+00 5.864e-45 1.955e-33 2.593e.47 8.646e.36 Cl-97

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/br mR/hr Nlo Buildup No Buildup2 With Buildup2 0.05 3.140e-01 7.989e-32 8.099e.31 2.128e-34 2.158e.33 0.1 2.458e+00 2.027e-17 1.538e.15 3.102e.20 2.352e-18 0.2 4.148e-01 4.565e-15 5.184e.13 8.056e-18 9.150e 16 0.4 4.334e-02 3.909e.14 2.279e- 12 7.616e-17 4.440e- 15 0.5 1.315e-02 4.282e-14 1.833e.12 8.405e-17 3.597e- 15 0.6 4.900e-01 4.391e-12 1.447e-10 8.571e-15 2.824e-13 0.8 2.369e+00 9.912e-11 2.159e-09 1.885e-13 4.107e-12 1.0 1.869e+00 2.458e-10 3.900e09 4.531e.13 7.188e-12 1.5 2.370e+00 2.185e-09 2.049e-08 3.675e-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 FinalStatus Survey Plan Revision 0 AicroShield v5.04 (5.04-00362) 12/21/0 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 1.834e-009 2.051e;008 Photon Energy Fluence Rate MeV/cm 2 /sec 2.534e*009 2.670e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 4.326e-012 4.607e-01 1 Absorbed Dose Rate in Air mGy/hr 3.777e.014 4.022e-013 mrad/hr 3.777e*012 4.022e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.283e*014 4.572e*013 o Opposed 3.719e-014 3.949e-013 o Rotational 3.719e-014 3.949e-013 o Isotropic 3.331e-014 3.533e*013 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 4.539e-014 4.850e-013 o Opposed 4.387e-014 4.68le 013 o Rotational 4.387e-014 4.681e-013 o Isotropic 3.51 le-014 3.730e-013 Effective Dose Equivalent Rate (ICRP 51 }1987) o Anterior/Posterior Geometry mSv/hr 3.858e-014 4.114e-013 o Posterior/Anterior 3.57le.014 3.796e.013 o Lateral 2.872e.014 3.036e.013 o Rotational 3.222e-014 3.423e-013 o Isotropic 2.866e-014 3.035e-013 Page.

Cl-99

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File: PB122119.MS5 Date: _ _ _

Ru ate: December 21, 2005 By:

Run Time: 2:28:46 PM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in Dose Points Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name jDimension Mate 6ad Density Cyl. Core 7.62 cm2 Conciret te 1.8 Shield 1 .65 cm Iron 7.86 z Transition Concret e 2.4 Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons c 0.015 : Excluded Library : Grove Numlide curiaeU becquerels iCi/cm2 B1/cm.

Ag-108m 1.64174e-010 6.0744e+000 4.5000e-0,I09 1.6650e-004 Buildup The material reference Is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energ Activie Fluence Rate Fluence Rate Exposure Rate Exposur ate photons/sec MeV/CM2/sec Me/cem2se.c mR/hr mRbhr No Buildup With Buildup No Buildup With Buildu 32 3.984e+00 3.279e-235 1.074e-33 1. 136e-236 3.722e-35 0l-100

Plum Brook Reactor Facility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exagsure Rate MeV photons/s~c MeV/cm2/sec MeWcmVsec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.03 1.290e-06 6.584e-89 7.69le-40 6.525e-91 7.622e-42 0.08 4.305e-01 2.739e-20 1.249e- 18 4.335e-23 1.976e-21 0.4 5.460e+00 4.924e-12 2.871e-10 9.595e-15 5.594e*13 0.6 5.491e+00 4.921e-11 1.621e-09 9.606e-14 3.165e.12 0.8 5.497e+00 2.300e-10 5.01 le-09 4.375e-13 9.531e-12 TOTALS: 2.086e+01 2.842e-10 6.920e-09 5.432e- 13 1.326e*1 1 CI -101

Plum Brook ReactorFacility FinalStatus 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\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 Results (Summed over energies) Without With Buildup Buildu~

Photon Fluence Rate (flux) Photons/cm 2 /sec 3.819e-010 9.684e-009 Photon Energy Fluence Rate MeV/cm 2 /sec 2.842e-010 6.920e.009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 5.432e-013 1.326e-01 1 Absorbed Dose Rate in Air mGy/hr 4.742e-015 1.157e-013 mrad/hr 4.742e-013 1.157e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.557e-015 1.361e-013 o Opposed 4.523e-015 1.102e-013 o Rotational 4.523e-015 1.102e-013 o Isotropic 3.998e-015 9.744e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 5.931e-015 1.450e-013 o Opposed 5.651e-015 1.381e-013 o Rotational 5.651e-015 1.381e-013 o Isotropic 4.278e-015 1.042e-013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 4.939e-015 1.208e-013 o Posterior/Anterior 4.402e-015 1.074e-013 o Lateral 3.313e-015 8.051e-014 o Rotational 3.937e-015 9.600e-014 o Isotropic 3.375e-015 8.215e-014 Page 1 Cl-102

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122120.MS5 Date:

Ru ate: December 21, 2005 -By:

RunrTime: 2:32:47 PM Checked:

Duration : 00:00:01 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 ce Dimensions Height 762.0 cm 25ft Radius 7.62 cm 3.0 in

-C Dose Points Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields ShieldName DjRnension Mat i Density Cyl. Core 7.452 cm 2 Conc ret e 1.8 Shield 1 .65 cm Iroin 7.86 Transition Concret e 2.4 Shield 3 30. 48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .0'25 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide 1.4ies becquerels 0Ci/cm0 Bq/cm1 Nb-94 1.6417e-010 6.0744e+000 4.5000e-009 1.6650e-004

- Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate ExPosure Rate Exposure Rate MeV photons/sec MeV/cml/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.0174 2.148e-03 0.OOOe+00 4.650e-37 0.OOOe+00 2.510e-38 0.0175 4.115e-03 0.OOOe+00 8.994e-37 0.OOOe+00 4.763e-38 0.0196 1.209e-03 4.082e-252 3.160e-37 1.507e-253 1.166e-38

( 7026 6.074e+00 1.279e.10 3.358e-09 2.467e-13 6.475e-12 711 6.074e+00 3.955e-10 7.629e-09 7.444e-13 1.436e-1 1 Cl-103

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV 12hotons/sec MeV/Cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buidup No Buildup 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 FinalStatus 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) - Photons/cm2 /sec 6.362e-010 1.354e-008 Photon Energy Fluence Rate MeV/cm-/sec 5.235e-010 1.099e-008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 9.91 le-013 2.083e-01 1 Absorbed Dose Rate in Air mGy/hr 8.653e-015 1.819e.013 mrad/hr 8.653e-013 1..81 9e-01 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.006e-014 2.117e-013 o Opposed 8.289e-015 1.74le.013 o Rotational 8.289e-015 1.74le.013 o Isotropic 7.330e-015 1.540e.013 Shallow Dose Equivalent Rate (ICRP 51 . 1987) o Parallel Geometry mSv/hr 1.076e-014 2.264e.013 o Opposed 1.027e-014 2.160e-013 o Rotational 1.027e-014 2.160e-013 o Isotropic 7.844e-015 1.648e.013 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 8.970e-015 1.887e-013 o Posterior/Anterior 8.049e-015 1.691e-013 o Lateral 6.119e-015 1.284e-013 o Rotational 7.207e-015 1.514e-013 o Isotropic 6.210e-015 1.304e-013 Page 1 Cl-105

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122913.MS5 Date:

RL ate: December 29, 2005 By:

RuriTime: 2:49:38 PM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points Y z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name IDimension Mathetia 1 Density Cyl. Core 7.62 cm- Conc cretqe 1.8 Shield 1 .65 cm Iroon 7.86

+/-k Transition Concret e 2.4 Shield 3 30.48 cm Concretee 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies b e wC Bq/cm2 1-129 1.6417e-010 6.0744e+000 4.5000e.009 1.6650e-004 Buildup The material reference Is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate Exp~osure Rate. Exposure Rate W~Y 12hotons/sec MeV/cm 2 /sec MeV/cm2/sec mR/hr mR/hr With Buildup No Buildup With Buildup 0.0295 1.212e+00 1.333e-86 6.866e-34 1.395e-88 7.186e-36 0.0298 2.249e+00 3.950e-84 1.313e-33 4.002e-86 1.330e-35 0.0336 7.995e-01 2.970e.64 6.856e-34 2.113e-66 4.876e-36 0 0)396 4.568e-01 2.750e-46 6.969e-34 1.249e-48 3.167e-36 Cl-106

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate Mey .phtons/sec MeV/cm2/sec MeV/cm2/sec mR/he mR/hr No Buildup With Buildup No Buildup With Buildup TOTALS: 4.718e+00 2.750e-46 3.382e-33 1.249e-48 2.853e-35 i

I I

i i

i Cl-107

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroStield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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 with BuilduI2 Buildug Photon Fluence Rate (flux) Photons/cm 2 /sec 6.947e*045 1.054e.031 Photon Energy Fluence Rate MeV/cm2/sec 2.750e*046 3.382e-033 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.249e-048 2.853e-035 Absorbed Dose Rate in Air mGy/hr 1.09le-050 2.49le-037 mrad/hr 1.091e-048 2.49le-035 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.561e-050 2.852e.037 o Opposed 7.864e-051 1.430e-037 o Rotational 7.120e-051 1.220e-037 o Isotropic 6.81 le-051 1.133e-037 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.57 le-050 3.108e-037 o Opposed 1.084e-050 2.137e-037 o Rotational 1.084e-050 2.137e-037 o Isotropic 7.958e-051 1.580e-037 Effective Dose Equivalent Rate (ICRP 51

• 1987) o Anterior/Posterior Geometry mSv/hr 9.103e-051 1.278e-037 o Posterior/Anterior 5.503e-051 6.610e-038 o Lateral 3.040e-051 3.568e-038 o Rotational 4.948e-051 6.568e-038 o Isotropic 4.056e-051 5.441e-038 Page 1 Cl-108

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOs File: PB010404.MS5 Date:

Rt. ate: January 4, 2006 By:

Run Time: 8:04:03 AM Checked:

Duration : 00:00:01 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 ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points X z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name I imension Mate da I Density Cyl. Core 7.62 cm 2 Conci ,et e 1.8 Shield 1 .65 cm lroin 7.86 z Transition Concret e 2.4 Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide 2 bec6uerels 4Ci/0m0 Bq /CM2 Sn-126 1.6417e-I 010 6.0744e+000 4.5000e 0009 1.6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activiy Fluesnc Rate Fluence Rate Exposure Rate Exposure Rate MeV 2hotons/sec MeV/cm-2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildu With Buildup

)2 4.702e-01 3.869e-236 1.268e-34 1.340e-237 4.392e-36 Cl-109

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec MeV/cm2/=e MeV/cml/sec mR/hr mrR/h No Buildup With Buildup No Buildup With Buildup 0.03 1.779e+00 9.079e-83 1.061e-33 8.997e-85 1.051e-35 0.04 3.034e-02 1.439e-46 4.798e-35 6.365e-49 2.122e-37 0.06 5.821e-01 2.323e-25 5.459e-24 4.615e-28 1.084e-26 0.08 2.789e+00 1.775e.19 8.092e- 18 2.809e-22 1.281e.20 TOTALS: 5.650e+00. 1.775e.19 8.092e-18 2.809e.22 1.281e-20 Cl-110

Plum Brook ReactorFaciit y FinalStatus 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\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 Results (Summed over energies) Units Without With Buildup Photon Fluence Rate (flux) Photons/cm2 /sec 2.219e-018 1.012e-016 Photon Energy Fluence Rate MeV/cm 2 /sec 1.775e-019 8.092e-018 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.809e-022 1.281e-020 Absorbed Dose Rate in Air mGy/hr 2.452e-024 1.1 18e.022 mrad/hr 2.452e-022 1.1 18e-020 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.289e-024 1.955e-022 o Opposed 2.284e-024 1.041e-022 o Rotational. 2.220e-024 1.012e-022 o Isotropic 2.204e-024 1.005e-022 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 4.249e-024 1.937e-022 o Opposed 3.123e-024 1.424e-022 o Rotational 3.123e-024 1.424e-022 o Isotropic 2.292e-024 1.045e-022 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 3.602e-024 1.642e-022 o Posterior/Anterior 2.747e-024 1.253e-022 o Lateral 1.693e-024 7.720e-023 o Rotational 2.340e-024 1.067e-022 o Isotropic 1.893e-024 8.630e-023 Page 1 Cl-lll

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB122915.MS5 Date:

Rt late: December 29, 2005 By:

Run rime: 2:53:47 PM Checked:

Duration :00:00:01 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,ce Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in lose Points z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4 ft 6.0 in Shields Shield Name Din iension Matk MaI Density Cyl. Core 7.4,2 cm2 Conc ret e 1.8 Shield 1 65 cm Iro n 7.86 z Transition Concretee 2.4 Shield 3 30. 48 cm Concret,e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclid c becquerels ulitcm Bq/cm1 Zr-95 1.6417e-010 6.0744e+000 4.5000e.009 1.6650e-004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ene Activity Fluence Rate Fluence Rate Exposure Rate - Exposure Rat p2hotons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.7242 2.652e+00 6.562e-1 1 1.649e-09 1.262e.13 3.170e-12 0.7567 3.362e+00 1.050e-10 2.477e.09 2.010e-13 4.742e- 12 TOTALS: 6.014e+00 1.706e.10 4.126e.09 3.271e.13 7.912e-12 Cl -112

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 ihicroShield v5.04 (5.04-00362) 12/29/05 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies) Units Without With Buildup Photon Fluence Rate (flux) Photons/cm2/sec 2.294e-010 5.55le-009 Photon Energy Fluence Rate MeV/cm 2 /sec 1.706e-010 4.126e-009 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 3.27le-013 7.912e-012 Absorbed Dose Rate in Air mGy/hr 2.856e-015 6.907e-014 mrad/hr 2.856e-013 6.907e-01 2 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.348e-015 8.097e-014 o Opposed 2.723e-015 6.584e-014 o Rotational 2.723e-015 6.584e-014 o Isotropic 2.406e-015 5.820e-014 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 3.574e-015 8.644e-014 o Opposed 3.406e-015 8.237e-014 o Rotational 3.406e-015 8.237e-014 o Isotropic 2.576e-015 6.229e-014 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.973e-015 7.191e-014 o Posterior/Anterior 2.648e-015 6.405e-014 o Lateral 1.991e-015 4.816e-014 o Rotational 2.369e-015 5.729e-014 o Isotropic 2.029e-015 4.907e-014 Page 1 Cl-113

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File : PB122916.MS5 Date:__

RL 'ate: December 29, 2005 By:

Run Time: 2:55:49 PM Checked:

Duration : 00:00:01

- 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

ource Dimensions Height 762.0 cm 25 ft Radius 7.62 cm 3.0 in Dose Points Y.1 z

1. 1 138.78 cm 381 cm 137.16 cm 4 ft 6.6 in 12 ft 6.0 in 4ft 6.0 in Shields Shield Name I imension Mate nia I Density Cyl. Core 7.62 cm 2 Conci ,et e 1.8 Shield 1 .65 cm Iroion 7.86 z Transition Concret e 2.4 Shield 3 30.48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .025 cm Iron 7.86 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons c 0.015 : Excluded Library : Grove Nuclide curies becauerels pjCi/cm 2 B1/cm6 Eu-155 1.6417e-,010 6.0744e+000 4.5000e-OC09 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cmz/see MeV/cm2/sec mR/hr mRlhr No Buildup With Buildup No Buildup With Buildup 1.933e 02 9.868e-85 1.153e-35 9.780e-87 1.143e-37 CU-114

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Fluence Rate Exposure Rate Exposure Rate MeV photons/sec Me/cM2 /sec mR/hr mR/hr No Buildup ,With BuilduQ No Buildup With Buildup 0.04 1.101e+00 5.223e-45 1.741e-33 2.310e*47 7.701e-36 0.05 3.581 e-01 9.111e-32 9.238e.31 2.427e-34 2.461e-33 0.06 7.878e-02 3.144e-26 7.387e-25 6.245e-29 1.467e-27

-0.08 1.886e+00 1.200e-19 5.472e- 18 1.899e-22 8.660e.21 0.1 1.256e+00 1.036e.17 7.855e- 16 1.585e-20 1.202e-18 TOTALS: 4.699e+00 1.048e-17 7.910e-16 1.604e.20 1.210e-18 Cl-115

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 licroShield v5.04 (5.04-00362) 12/29/0 MicroShield v5.04 (5.04-00362)

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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 Results (Summed over energies! Wi~thout With Buildup Photon Fluence Rate (flux) Photons/cm 2 /sec 1.051e 016 7.924e-015 Photon Energy Fluence Rate MeV/cm 2 /sec 1.048e-017 7.910e-016 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.604e 020 1.210e*018 Absorbed Dose Rate in Air mGy/hr 1.400e*022 1.057e-020 mrad/hr 1.400e-020 1.057e-018 Deep Dose Equivalent Rate (ICRP 51 -1987) o Parallel Geometry mSv/hr 2.341e-022 1.767e-020 o Opposed 1.283e-022 9.685e-021 o Rotational 1.283e-022 9.683e-021 o Isotropic 1.242e-022 9.372e-021 Shallow Dose Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 2.326e-022 1.755e-020 o Opposed 1.803e-022 1.361e-020 o Rotational 1,803e-022 1.361e-020 o Isotropic 1.313e-022 9.912e-021 Effective Dose Equivalent Rate (ICRP 51 - 1987) o Anterior/Posterior Geometry mSv/hr 2.012e-022 1.518e-020 o Posterior/Anterior 1.577e*022 1.191e-020 o Lateral 9.735e-023 7.348e-021 o Rotational 1.347e.022 1.017e.020 o Isotropic 1.072e.022 8.090e-021 Page Cl-116

Plum Brook ReactorFacility FinalStatus Survey Plan *. Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOS File: PB121913.MS5 Date:

RL ate: December 19, 2005 By:

Runr'rime: 11:24:57 AM Checked:

Duration : 00:00:01 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 -ce Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in

[)ose Points y z

1. 1 134.97 cm 381 cm 182.88 cm 4ft 5.1 in 12 ft 6.0 in 6 ft Shields Shield Name Din iension Mate aria Density 2

Cyl. Core 3.{ .1 cm Conci ,et e 1.8 Shield 1 .65 cm Iro n 7.86 Transition Concret e 2.4 Shield 3 30..48 cm Concret e 2.4 Air Gap Air 0.00122 Wall Clad .0125 cm Iron 7.86 Source Input Grouping Method : Actual Photon Energies Nuclide curies becuerels WuCi/cm 2 Ba/cm 2 Co-60 8.2087e-01 1 3.0372e+000 4.5000e-009 1.6650e-004 Buildup The material. reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Energy Activity Fluence Rate Fluence Rate EXpQS ,ure.RFate Exposure Rate MAY p2hotons/sec MeV/cmY/sec MeV/cm 2/sec mRlhr mR/hr No Buildup WithBuidu No Buildup With Buildup 0.6938 4.954e-04 2.365e-15 7.879e-14 4.566e-18 1.521e-16 1.1732 3.037e+00 2.935e-10 4.432e-09 5.246e- 13 7.920e-12 1.3325 3.037e+00 5.773e 10 7.308e.09 1.002e-12 1.268e-1 1 ALS: 6.075e+00 8.708e.10 1.174e-08 1.526e-12 2.060e-1 1 C1-117

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362) 12/19/05 MicroShield v5.04 (5.04-00362)

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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) Photons/cm 2 /sec 6.834e-010 9.262e*009 Photon Energy Fluence Rate MeV/cm 2 /sec 8.708e-010 1.174e*008 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.526e-012 2.060e-011 Absorbed Dose Rate in Air mGy/hr 1.332e.014 1.798e-013 mrad/hr 1.332e.012 1.798e-011 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.512e.014 2.042e-013 o Opposed 1.303e-014 1.758e-013 o Rotational 1.303e-014 1.758e-013 o Isotropic 1.164e-014 1.57le-013 Shallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.609e-014 2.173e-013 o Opposed 1.550e-014 2.093e-013 o Rotational 1.550e-014 2.093e-013 o Isotropic 1.233e-014 1.664e-013 Effective Dose Equivalent Rate (ICRP 51 . 1987) o Anterior/Posterior Geometry mSv/hr 1.362e-014 1.838e-013 o Posterior/Anterior 1.255e-014 1.694e-013 o Lateral 9.987e-015 1.347e-013 o Rotational 1.130e-014 1.525e-013 o Isotropic 1.OOle-014 1.350e-013 Page 1 Cl-118

Final Status Survey Plan Revision 0 Facility Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

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Page :1 File Ref:

DOS File : PB122121.MS5 Date:

RL late: December 21, 2005 By:

Run- rime: 3:45:18 PM Checked:

Duration : 00:00:01 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 rce Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in

)ose Points z

1. 1 134.97 cm 381 cm 182.88 cm 4 ft 5.1 in 12 ft 6.0 in 6ft Shields Shield Name Dinlension Materia H Density Cyl. Core 3.1B1 cm2 Conciret :e 1.8 Shield 1 .65 cm Iron 7.86 Transition Concret te 2.4 -

Shield 3 30 .48 cm Concret te 2.4 Air Gap Air 0.00122 Wall Clad X025 cm Iron 7.86 Source Input Grouping Method: Actual Photon Energies Nuclide cus becuerels Ci/cm2 Qq/cm2 Ba-137m 7.7654e-011 2.8732e+000 4.2570e*009 1.5751e-004 Cs- 137 8.2087e-01 1 3.0372e+000 4.5000e*009 1.6650e-004 Buildup The material reference is: Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferential 20 Results Ener Activity Fluence Rate fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm!fier. MeV/cm2/sec mR/hr mR/hr No Buildup WithBuildu No Buildup With Buildup 0.0318 5.948e-02 2.447e.82 3.431e-35 - 2.038e-84 2.858e.37 0.0322 1.097e-01 6.519e-80 6.579e-35 5.246e-82 5.295e-37 0.0364 3.994e-02 8.361e-62 3.666e-35 4.750e-64 2.083e-37 516 2.585e+00 9.264e-12 3.324e-10 1.796e-14 6.443e- 13 Cl -119

Plum Brook ReactorFacility FinalStatus 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 Fluence Rate Exposure Rate Exposure Rate MeV/cm2/ser. MeV/cm 2 /sec mR/hr mR/hr No Buildup With Buildup With Buildup TOTALS: 2.794e+00 9.264e-12 3.324e-10 1.796e- 14 6.443e- 13 Cl-120

Plum Brook ReactorFacility . FinalStatus Survey Plan Revision 0 licroShield v5.04 (5.04-00362) 12/21/C 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 Results (Summed over energies) Units.

Withoutn Photon Fluence Rate (flux) Photons/cm 2 /sec 1.400e-011 5.023e-010 Photon Energy Fluence Rate MeV/cm 2 /sec 9.264e.012 3.324e-010 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 1.796e-014 6.443e-013 Absorbed Dose Rate in Air mGy/hr 1.568e.016 5.625e-015 mrad/hr 1.568e-014 5.625e-013 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry mSv/hr 1.856e-016 6.660e-015 o Opposed 1.486e-016 5.332e-015 o Rotational 1.486e-016 5.332e-015 o Isotropic 1.314e-016 4.715e-015 Shallow Dose Equivalent Rate (ICRP 51 .1987) o Parallel Geometry mSv/hr 1.973e-016 7.078e-015 o Opposed 1.874e-016 6.723e-015 o Rotational 1.874e-016 6.723e-015 o Isotropic 1.405e 016 5.041e-015 Effective Dose Equivalent Rate (ICRP 51 1987) o Anterior/Posterior Geometry mSv/hr 1.641e-016 5.889e-015 o Posterior/Anterior 1.449e-016 5.198e-015 o Lateral 1.074e-016 3.854e-015 o Rotational 1.295e-016 4.645e-015 o Isotropic 1.102e-016 3.954e-015 Page Cl-121

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref:

DOz File: PB122122.MS5 Date:

Ru ate: December 21, 2005 By:

Run Time: 3:50:53 PM Checked:

Duration : 00:00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 3.81 cm 1.5 in Dose Points X z

1. 1 134.97 cim 381 cm 182.88 cm 4ft 5.1 in 12 ft 6.0 in 6 ft Shields Shield Name Dimension Material Densite Cyl. Core 3.81 cm2 Concrete 1.8 Shield 1 .65 cm Iron 7.86 z Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air 0.00122 Wall Clad .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 Nuclide ibecquerels ucilem Bq1cm6 Eu-152 8.2087e-(0)11 3.0372e+000 4.5000e-OC'09 1.6650e 004 Buildup The material reference is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumferentiaf 20 Results En Activity Fluence Rate Fluence Rate Exposure Rate Exposure Rate photons/sec MeV/cm-'/sec MeV/cm-L/sz mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup

.. 04 1.797e+00 7.689e*50 2.295e-33 3.401e-52 1.015e-35 Cl-122

Plum Brook Reactor Facility FinalStatus 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 Activit Fluence Rate Fluence Rate Exp~osure Rate Exposure Rate photons/sec MeV/cml/sec MeV/cm 2 /sec mR/hr No Buildup With Buildup No Buildup With Buildup 0.05 4.493e-01 6.370e.35 2.389e-33 1.697e-37 6.365e-36 0.1 8.635e-01 2.353e*19 2.288e-17 3.600e-22 3.50le-20 0.2 2.276e-01 2.237e.16 3.535e- 14 3.947e-19 6.238e.17 0.3 8.212e-01 1.694e-14 1.920e-12 3.214e- 17 3.642e- 15 0.4 1.909e-01 2.807e*14 2.175e 12 5.470e-17 4.239e- 15 0.5 1.713e-02 1.077e-14 5.981e.13 2.114e-17 1.174e-15 0.6 1.288e-01 2.537e-13 1.061e-11 4.952e- 16 2.071e-14 0.8 5.408e-01 6.015e-12 1.608e- 10 1.144e-14 3.058e-13 1.0 1.300e+00 5.202e-11 9.920e-10 9.589e- 14 1.829e 12 1.5 7.046e-01 2.451e.10 2.658e-09 4.123e 13 4.472e- 12 TOTALS: 7.040e+00 3.034e-10 3.826e-09 5.203e- 13 6.636e- 12 Cl-123

Plum Brook ReactorFacility FinalStatus 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 Ifk Su ildu Phton Fluncse-Rate Okwix) Photonstcmrt/sec 2.235e,010 .996e 009 Phton EmfEy Fluence Rate MeV/cmS/sec 3.034e 010 3,B26te009 Exposure and Dose ORotesn LEposure Rate in Air rnA/hr 5.2-03e 013 6.636e-012 Atibrtc a

D95v Rate in Air rnGy/hr 4-54e6 015 5.794e-014 rrcd/fhr 4.542q-01 3 5,794e-012 Neep Dose .Equivalecnt MatD fICRP 51 - 1987) a Paralnei Geo-metfy rmn$Yhr 5~154e-D1 5 O CppO."w N 4-46ae-016 o Rotational 4.46$e-01 5 5.682?e-0414 a ISis rapie 5 .079e-014 Shal Dw Dose Equivalent Rate (ICRP 51 - 1987) 4000.@-Ol 5 o Par-illiel Grmtry- rr$ve/hr 69.97e-01 4 a Upposed 5.275e-015 6-747e. 0l 4 o Rotational 5 275e'D1 5 6 1476-014 ,

4.219e-15 5 368e-1 4 E£lectivc Dos Cquivioleot Me- (lCPP 51 1 g7) o A.nterior/Posterior Geometry mSv/hr 4i641.A15 5-929e-014 a Poslerioet/Anterior 4.292ee0415 S.46Se-014 o Lateral $.44$e'0 15 4 36] c-t14 I

o Rotational 3.872e.015 4.926e014 a IstoDop, 3.440e-0 15 4.363e-C14 Page 1 Cl-124

PlmBokRatr FaiiyFnlSau Srve lnRvso Plum Brook ReactorFacility FinalStatus Survey Plan ,, Revision 0 MicroSheled Y5.04 (5&04-00362)

Radioiagical Seivices, Inc.

Page :1 rule Ref;_____

005 Fdi: P5122123.MS5 Date:

Ru ate: December 21, 205 R1nTime: 3:53:07 PMI Chec~ed:

Duration . D00:O]

Case Title; Line 1.26 0 D'escrip ReviJsed Model Calek Eu-154 Unit Act wSched 40 &12 InShtd

-n.

Georm;~rr. 10 Cylinder Surface External Doro< Point I

miarce Dimnemions Heighmt 762.0 cm 25 It Radius 3.81 cm 1.5 in Dose Points Y z 91 134.97 cm 381 cm 1828 c~m 4 ft 6.1 in 12 ft 6.0 in 6Gft shields.

Dimensior .Mel ietI1 Density Shield Ng 3.51 cm, Conur e 1,8

.65 Cm Iral I ,.86 Tranisition Concret.Le 274 Shield 3 30.4 = cofwcret e 2.4 Air Gap, Air 0.00122 w441, Cad .025 cm Irgn 7.86 Source Inpu~t Grouping Method :.Standard Ind-lees tNumber of Groups -2 Lower EneWg Cutoff -.0.015 Photons 0&015 : Excluded

't Library rrGiroe A 6-r-mi.,re~t LI~, /kml Eu-154 8.2087e All11 3.0372e+O03 4.50O-00eX 19 1.6650e-fX04 The materala reference Is :Cyl. Care lIutegratron Paramieters 20 Ciiaumterential 20 Results FlyencZ Rate LIMence ai1e Exogsw re Rot MeVCrn2/SP-r ma.w/

. I E6. 181ivit With Buittluj 2.645e-50 7; -9e34 1.17Qe-52 3.491 e-36 Cl-125

Plum Brook ReactorFacility FinalStatus 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 Mlwn,rjc Sate~ Fluence Rate

,MR/hr mR/hr Ng FluOdom With BuIddup No Buildup Wirth awiu d g 0.05 1.570e-01 2.26e-35 8.349e 34 5 g29. 3B 0.1 1.2:29e+00 3.34ge-19 3.257e 1,7 5.124e.22 . 4.,982e-20 0.2 2.074e-1 2,04&16 3.221e414 3.5979.19 5,685e. 17 O.4 2.167e-02 3.187e-16 2.470e- 13 6.210.e-i3 4.812e-16 0.5S 6,43 4, 145 2.2e9i 1fi $. 11 4e 18 4*:5C0;n 1 0.6 2.450eD0 4.886- 13 2.018le I 1 9.41 9.16 3.939e- 14 0.8 1184e400 1.317.e-l 3.52le-14 2.506e14 6.697e- 13 1O 9.343e.O1 3.740e 1 7.132tl ' 6.0O4,eJ4 1312] 51?

1:5s 1 85e.00 4,122e-10 4,471 eQ9 6.935- 13 7.523e 12 TOTALS: 5.789u+0Q 4 633410 5.F557e-09 7.885e-13 9.547e-12 CI-126

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Nlckr*Sh~etd vS.0D4 (5.04-0362> 12121105 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)

SeAli1jr. 411mmari rypr RnPm'=%' JiJ Buedup Photons/cm'f sec 3.295e-0 10 4.1,g9e 009 M*.~ton En'efty fluence, Rate MIUVICM~1seC 4,633e 010 5.557,e-009 Exposure and Doso Rates Exposure fRate in Air mRlhr 7.88se-01 3 9-.547t,0I2 Absorbed Dose Rate in Air mGy/hr 6.884e.015 B.335e-014 it mrad/hr S.88eO 13 8.33 5ct01 2 (ICRP 51 .1987) o Pasrallel Geommetry m~v/hr 72.02e.O015 9.466e- 01 4 Oo ppnsed IS.744eO 15 S. 194e 014 o Rotational 6.784e.0 15 B.194-e-014 LiIto1lropn 6.080e.0 15S 7?.334-a01 4 Sha~lifo Dose Equivalent Rate (ICIP 51 1M7) o Par~mi-el Goc-etry mS'vlhr 8 .264e-O015 1.004e-01 3 H

oG)'.Pose'z 7.~19-e-015 9.694~-01 4 o RotationoiI 7.991 emO1 5 9.694e-01 4 6 .40S-e-O0 5 7.738e-014 (lCRP 51 1487) a Anterior/Posterior Ga-netry m5V~hr 7.02%-.Q] 5 8,52]aUD4 0 P0.SericrlAnierior m 6.5129*015 7-873e-01 4 o Lateral1 S.24&e.O1 5 6.311e014 o Rotational 5 .B7ft.015 TIOle-014 oisotropic 5 .233e.0.15 6-305e-01 4 Page 1 Cl-127

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Microihleld v5.04 (5.0400362)

Radiological Services, Inc.

Page :1 1 File R1_;

DOS File: P8122124.,MS5 Date:

RL . ale: December 21, 2005 By; Rkun-ime: 3:54:55 PM Checiked:

Duratio: 00:0P:01 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 I at -, ",

I curce Dimensions 762.0 cm 25 ft Radiu 3.8.1 cm 1.5 in Ir z

1. 1 Y97 cm 134 381 cm 182,88 cm 4115.1 ifi 12* t6.Oin 6 it Shields I,)itenslon e I Density Cyl. cve 381 cmn' Conci rot te 18 Shield I .65 cm iro n 7.86 p Trtesition Goncret te 2.4 Shield 3 3DAS Cm Conicet

• 2.4 Air Oap Air 0,00122 Wal8 Cad .025 rm Iron 7Mi Souruc input Grcuping Method: Standard Ind-ies.

Number of Groups :25 Lower Energney utoll t 0.015 Photons < 0.015 : Exduded Library: Grove Nur-idt he 4-ot/rems Ui/m?7 Ag-108m 8.2087ie-011 3-h372e+000 4-5Me-0D9 1,6550 W004 Buiildup The material relerence Is : Cyl. Core Integration Parameteys YDirection (axial) 20 Cicumterantia, Resuhs

.Activity Flente Raty FIluence Rate Esxposure Rwtp_

hohtorns/sec Ng R1.5id0 2iLth af lUgg 1 .2 130eil.f2 6 With R 35iun 1 .992c+D 1 51 oe-2-66 4,338e34- 5.230~e-M 1.503e 35 Cl-128

Plum Brook ReactorFacility FinalStatus 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 Fluenc*= Rate Logige Rdl - Emxsuors Rate M.ecrfflpel No Builftd UQ) RI 0iep With guildulg 0.03 6A40e-07 2.76i3e " 3.106e4 2.739e101 3.078a.42 0.08 2 152e-901 2.34se-22 1.293e!20 3.7 1f. 25 2.047e.23 0.4 2.73e40 4.01 se13a 3.112e-.1 7.824e-16 6.063e-I 4 0.6 2. 745-O0 5&408ec12 2.we2 10 1.056. E4 4.414e 1 3 Q8

o. 2.749e#0 3".Q57e-1I 841719. j 5.815e 14 li554o 12 TOTALS: 1 .043a+0I 3.63Be- 11 1.074e.09 6.949.e 14 2.056- 12 Cl-129

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 AfliciothWeId v&04 (I..C4-15090) 12/21/05 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 IV1. ~J14.919 1,U2SO~m RgZ~ 1 5 (SqrTwvg~d Mpr energies~ Witjhrujlf Photon r'lu~rt.o Riktr (flux) Photons/9T/sec 4.823e-0 11 1.4 76e.009 Pttoton Energy Fluence Rate ,3.6309-0 11 1 .074e.009 ULposure arid Dose Rates tLxrooure- Rate ir Air mR/h~r 6.949ge-O14 2.05~6e.0 12 Absorbed Dose Rate inAir mliy/hr 6.0&5eVJO16 1.795e.O 14 mr-ad/hr 6.066e.0 14 1.795e-01 2

'Nee Dose EquiYatnt Rate oa Paraflel ( etr~y m~v/hr 7.1 D2e-0O16 2.10~8e*014 M

5 .79OeQ16 1.71le.014

-o Rotat~onal S.790e.016 1.71 1c014

'o l1-4Opic 5.118e,-016 1.512e-014 SI-aiimwl Omse Equivalent Rkot (ICRP 51 19A7) o Parallel G&e&~netry rnSy/hr 7.582e-01 6 2,4v014 7.227c-016 2-141-e-014 o Rotational pi 7 .227e-01 6 2.14 le-014

5. 4 76e-016 I1.618e-014 (im.p 5I -

o ArntergiorlPostenior Gieoretfy m:Sv/hr 6-314 c-016 .1872e-01 4 N

5-633e-0 16 1.%6$t, 014 oLatoral 4.245eu-O 1 6 1-25le-D14 ai R~otat'~onat 5.O39"O1 6 -4190e. 014 ai Isotropic 4. Mv2,V 16 1.2-76e-O1 4 Page I~

Cl-130

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 Microshield V5.K (5.04.0362)

Radiolaglcal Services, Inc.

Page - 1 file Rd_

1DO:t Fire : Pi221,25NMS5 Date:_

RF sit: Cecember 21, 2.*5 By' RrniTme: 3:56:37 PNM  ;;hersed; Durativp :p ;Q!

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= -1 -- c wurce Dimensions HeigIt 7~,52 -m 25 tt FPadius 3.81 cm 1,5 in Dose Points x z s 1 134..97 cm -4.Lrr, 182.88 cm I

41ft 5.1 in 12ft6C.rn 6 tt

. i. Shields SF-i.*'H lKinma )irr,,rr ,gi ,n~ a-;g iI Leluletlk i ccore 1 .8 Oyl Shield ~ .681 cml Co n ret e e

Tranilrf on C:onci ret e 2.4.

S;hie d 3 I,').i ; riQZC'tli w 2,4 Air Gap, wAlaII C Ilad . S rm lr 186 Sour'ce Input Gtrouping Method - Actual Photon EDergles r? Ijie%

• is I rNt, r rL  ! RrThrr9 Nt-94 8 2387-31'.  ; 3 0372vA-(jOJ 4 5i50:3(J 93 1,565C; 004 Buildup The malerial relerence Is t CyL Core Inrtegration Pararneters CYDiretion ra 20 i-'rcumfrntr;ntia; 20 Results ExDowry Rate ,FXwgriles Pail~

mRJ/hr mR/hr Mb'th QW}1,94-W Wdit rjuiir1ln, 08174 1.074e-03 0'000Ga+00 1.878e -

K.0175 2-C*57e -03 0.000e-.-01 3.632e-37 0.ODe+W 1.923e- 38 0.O196 6 04AcQ4 1.2Thie 37 9.584e.287 4.710te39 rf 7 026 5.-1c9.a0 3.016e-14 9.853e 13

-3'037e+QQ  : 514e-1 1 1i3010-0 1.043t:'13

..,._711 2.449e 12 Cl-131

Plum Brook Reactor Facility FinalStatus 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 Activity Fluence Ratee Fluence Raw Exrmsure Rte. F3(rxljra R;Ztfe may boatonqfeL hM.NJCm~jee .MIVmtIer mPfhr i MRIhr NC- K ilk I ithBauilrp ha Bu~ildup With Ri~ifrItir' TOTALS: 6.07-et4 7107.11 1.1e2e,09 1.345e-13 3.434e. 1 2 Cl-132

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicoSNetdv5.04 (5.04-00362) 1/2105 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 with Photn Fltmve Ro.i-tt (ilux) Ph~otoris/cmn/sec $aS$Sle Di 2.22l1e-009 Ph~oton Eneijy Fkuence Rate! MeWfcm-?/sec 7.107e-01 1 1.81 2e-09 Expo~sure arnd Dose Rates-Exposure R~ate inAir MR/hr 1,345cefl13 3.434e-01 2 Absbrbed Dose Rate in Air rnGy/hr 1.174e-01 5 2."9eDI14 w

mradlhr J..174-01 3 2.9~98e-012 (ICRP 51 - 1087) o Pa ra~lel Geometry mSv/hr ] .365e.015 3.A8Be.Q14 I

1.I25e-0 I5 1-871 e11 4 o Rotational ] 125e.015 2.87 le-O14

'.~94ZeQ 16 2.5399-0 14 Sh'orw -Ds Equivalent Rate .ICRP 51 1987) o Pe ianIer Geometfy mSv/hr 1.460e-Q) 5 3. 730e-O 14 r3 Opposed 1.393e*-OI 5 3.559c,014 o Rotational ,3.55ge-014 1VVIVe9 i 5

2. 7]6c.O14 (ICRP 51 1987)

-a Anter or/Poster or GjeG ~try rnSv/hr 1,217e-015 3.1IO~e*Q014 K

2,788e-014 o LateraIi 8.309E-01I6 io R-otabonal 9.78Oq*O1 5 2.496e,-O04 o iSO1ropic 8.4 30e-01 6 Page I Cl-133

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 RllcroSkleld vS04 (5.04-00362)

Radiological Services, Inc.

Pap :I File Ref: _

DOS Fire : *11122917.IVS-5 VP.te___ ..

Rt etc: Dvernetr 29, 2Of5 By:-

Funm f.me: 3:04:1.2 PM Checked:

Duration: 00. 01 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 Ci i wu~ce Dimensions I Heaght 762.0 cm 25 ft Radius 3; l;1 ;;mr 1.5 in Dose Points w1 13497 cm 12.88 cm 4ff5,3 ii 12 ', C,. c .-

Shields Qhield U;Imgr ,

41 W.a~ ;--'are Shield I Transik-on Shield 3 4.:1 Cm?

.b9 tmrrl 45 rrij 3C

32,.48 cm OCrrIc ret e Ir

..: .

2.rC fel pa 2.4

.i93qC~ret c: 2.4 1 .8

_7.5 Air iZ3p Air C B

,oa 22

.6i,. C!aIc 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) 20 Circrumlere.tia- 20 I

Flunce Re Fluence Ratre FZxgosurg Rate-MteV/crrl1/sar_ mR/hr mh/r Nib Ruilrdun With Blu11dup No Buildup W'Jh 80I~1fu-"N 0.X3295 O.,0295 6.06 1 e-01 1.1Se,97 2,77 .34 1 .87s 99 2.902e*36

1. 1240+0 2.055e-94 S.302e*.34 1.06ge-96 5.372e. 36 0,0396 :3.9w98 o: 4 M7e 72 2,76f8$4 P.039! 74 1,969p .36 0.0396 2 284e0_ 9A463e ^r52 2,814.34- 4.3300e.54 1.279e^36

Plum Brook Reactor Facility FinalStatus 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 Flwynf* Rote Flu3ncg Rate Exrsooure Rate Ex~surEp Bid pht-ons~~ee pfT Melt O'VARhr lo S2uild With Bfilur~n Nto BtUI du 0 With BSiLuo.

TOTAIS: ,2.359iD*00 9,46-3452 1.366e 33 4 XJ00 f54 1.1 .529-35 C1-135

Plum Brook ReactorFacility FinalStatus 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 W1 - (194.9?,39L=08.B) cm R~esults (Srnrned over en~erieoUW =gu Photon Fner R-te Ratte) Photons/c~rW/sec 2 .3gle*050 4.,256e.O32 PhDton Energy Mixence R~ate MeV/C1W'/We 9,46e'O52 1 ~366e-033 Expo.-ure and Dose Rates E~xposure Rate tinAir ImRthr 4.300e-054 i 52e-3$5 Abso~rbed Dose Rate in Air rn~y/hr 3. 75-4c;05 L OO~e.O37 a

.nrad/hr 3. 754"S04 I .006e'Q35 D'gcp Do s Fqu valont R~tiv (ICPP r.i . 9-a Parallel Gec~etry M$V/hr 2,7O'6e*056 5. 776e*O038 o Rotational 2.450e*056 4.92a6e.038 U lsuirupic~ 2.344&.056 4, 57 6e-038 SNi11rrw Dose EquNalent Ratte O Parallel GVimryv 5 .406e*056 1.255e,037

- Opoosec" 3 .732eOQ51 15.6301338 o Rotational 3 732e.056 8.630e-O038 U I q0"!or-ce 2.7 39*-056 5 62e.37038 o Anterior./Posterior Ge~metr'f mSv/hr ci PoseriaiY!n'eriar L,894~e-056 L669e-O389 1.44 le-038

.o Rotational I .703e-056 2..652e-0D31 I .$$$e'056 2,.197e-038 Page I Cl-136

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Mlcro~hield YS.04 (544.0-362)

Radiological SeiTvices. Inc.

Page .I File Ref:_ __

009 FIle PBO10405.MS5 Da _:_

FLt ate: Jantvary 4, Wont6 By:

Puii Time! 8O!018I AM Checked:

DuratiGan ; 00:0001 Case Metls Lino 1.26 H Doscription; !Rvjsd Mo~dt) Cal- Sn-I26 Unti Act, V $ched 40 &A12in SW~

Geom~etry: 10 - Cylinder Surface - External Dose Point wroe 01menslonai IMeght 25 ft Radius 1 S in D~ose, Points g t $-4.97cm z

1B92.88 cm 4 ft 5.1 ..n £2 -

iiE0 611 Shields SI-'f-Iff tJ:%M~ I COd. 'Ccc 'ete .

Shield~I ,65 cmn Irc ~.864 4

Shield '3 I3048 cm Crncreti o 2, Air _o e .

Ai! 0.0L7 WIl _d,' 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 Nucift- cur= ______Lip, WLC'/4; cm l Sn-126 8.2087e,4D1 1 J O,372c+000 4,CO0v.-CCIg 1.6650e-034i Ru~idup The material releience Is +/- Cyl. Core Integiration Parmneters.

Y D'iwreton (axial) 20 ci rcumirnoatez~a 20 F~xoozur4 Ratm mRl/hr WAh I~ijiqdut, 2.351le-01 12781-e267 5.1200e.5 6.172e-269 C1-137

Plum Brook ReactorFacility FinalStatus 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 Fl~uence Rcat. Fluenee Rate Exsugre Rate Exposur MeV/m2scp 91MLL~i rm~hr NDo Buildup Wih 8w1l1u 0.03 8.93e-Ol 3.81 le-93 4.282s.34 3.777e-95. 4.244e-36 0.G4 1.51e02 6.401e-0;2 1.937e-35 Z,871eS4- 8,5we 38; 0.46 2.91 1e;0) 4, 132e-28 l.Zlle 26 a.208e.31 2.404e-29 0.08 1.395es-00 1.5Me-21 ,380e 2Q 2,408e24 1.326e*22 TOTALS: 2.825e+O 1.522ei21 8,380e20 2408e 24 1.326e.22 Cl-138

. Plum Brook ReactorFacility FinalStatus Survey Plan. . Revision 0 11IcrDShlield v5.04 (5AQ4-OQ362) 0104I0E Micro~hidld YS.44 (5.04-O0,62)

Radolofgical: Services1. 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 (134.97M3I$2.AM 1 ~'

Rlesults (Summed over enenr~ies U4 ihu Wmb Sul4dup 1.902e-020 1.048e-01 8 "4i-ton Ereatsv flIenc-e Rats. MOV/CMI/sW i .5220.Q2] 8.380e*O2O Ex~posure andc DoseRts Ex~posure R~ate in Air mR/hr 2 .408e.024 1.326eO022 Abwrbe'j Cim Rate in Air mGy/hw 2.102e-026 1.158e.024 I

mrad/hr 2,102e?24 1.158c.,022

,.Ieep Oc.; Equ iy-ant R** (ICRP 51 1987) o ParatlIef G~erc-mtry m!Y/hr .r677c026 2,02 5c.024 ai 0O;Pq%-d 1 .958e-026 1.079e.024 o Rotationajl 1.O48e-024 a Igatopic 1.890e.026 I ,04 1e-024 Shallow Dose Equivalent Rate (ICRP 51 *1987) o ParaIlol Qor-*Kry mbyfhr 3 .6421e026 2 .OO5r.0249 O rOP-4Sed I 2.677e.0216 1.474e-024 o Rotational 2.$77 e*Q26 1.474e.024 iU kotropic~ L 9658.026 1.0820Y24 Effectie Dose EqLziv~kIcriI Ralc (ICRP 51 1987) a Arnter.-or/Posternor Ge-aretry mS-y/hr 3 M88.0216 1.701e*024 o Posterior/Antetrio~r I 2..356e.026 a 2g 7e.O24 ra Lateral 1,452c.026 7.995e*O25 o Rota"~ona' 2.006e*026 1. l05e.024.

o Isotropic 1 $?4Q~f ~[')71-2 Page I Cl -139

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 hlicroShield v5.04 (5.0440036.2)

Radiological Services, Inc.

pPage 1 File Ret_

DOS File : PB122919.MS5 FN ate: December 29, 200 By:

FN6f~ ime: 3:09:53 PM1 Cher*ed:

Duratirn ; QO';QQ;Qj 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 Sour ce Dimensions Heght 762.O cm 25 ft Radius 3.8.1 cm 14 In

,ose Points r

ern z

.1 W] 134.974em 4ft 5.1 in 3481 12 t 6.0 in 1.

182,81 cm 6 tt Shields ipsro;iofn Mtripl, Cy, re 3J .1 cm' Concrete Shield I .65 cm Iroa 1.86 Transitiorn - -ncrrte 2.4 Shield 3 3G.4.8 cm Concrete 2.4 Air Oap Air 0.00122 WalT Clad .025 cm IrGn 7.86 Source Input Groupingr Method : Actual Phton Enertgles UL he3 ii jrP I ir Irm' 1Ri/rM 7i-G1 1 3.Q37ZvQCQ 4.?OQ0vQ?9 1.509-mQ Buildup The material relerence Is: Cyl. Core Integration Paraneters YDirection (axial) 20 ivcumferpentia, 20 Results Ea V Activit.: ice ,Rale Flrrence er Expasur,- Ratt Pal mllhr With Hi3t1LJuo 0.7242 1 26e+1O 8.182e: 12 2.550e- 1 LS713 14 4.903e 13 0 75E7 I.68le-00 1.347c41 1 31922e. 1I 2 .57e-14 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 FinalStatus 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) Plhotions/ernk/we 2.911Qe~Q] & 704e-U1 0 Np1~ton Eeroesy Fluence Rate MOMeV/isac 2..165e-0Ol1 6.472e-01 0

'Exposure and Dose Rates:

Zxposure Rate In Air mIR/hr 4-.152ce014 1.241le-;12 Ab.%Qrtv Duo Ratv fin Air rnGy/hr 3..624e-016 .0$31. 014 I

mrrad/br ,3624e-014 10.&3e*0 12 7~ucp Dose EqvivoIet Rato (ICRP 51 -1987) lo Parallel Geo metry 4,248eOJ3 6 I .27Qc.0 14 u)Oopo-Vi 3 455.43-036 1 .033e-O 14 lo Rotational 3.4 5Se-0i 6 1.033E-014 mSvfhr 9.128e-015 Shallc' Dose Equivalent Rate (ICRP 51 - 1987) o Para~IeI Geoma~ry mrv/'hr 4.536e-0131 1 .356e-014

'I 4,322o-J1 6 I 292,ci14 o Rotationald 4.322-e-016 1.2-92e-014 a . I !f ] i 3.269CeQ 16f 9J.70a,-015 Effectivo, Dose Equivalent Rate .ICRP 51 - 1987) a Anterior/Paster~or Gevimetry m~y/hr 3,773e-016 2.128e-014 a Postenror,'Anterror a 3.361e416l I1.005te 014 a Laiteral 2~.527c,016 7 554e-015 a Rotat~ona~ 3,006e.O 16 8.1986e-D1 S a I 50tfupic 2.575e.016 Page I Cl-141

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 fficroSJkid v5,04 (5.04-O0362)

Radiological Services, foc.

N#ua Rof-Page l ______

D~rFvra : P82292Q-MS5 I.

fil atV Decamter~ 22 W 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 I

K H1 1149 m A ~

in ceA 6 ft

-11. I.';- 48 :-

Ap ( 44'7I WV el, u, ,I $ 1 , 7 4 Z, -

Samrte Inlput GtOirp*ng1 Kothod -Stamdard Indices Notibet of Croup% 25 Lower' Eiwrg CitOW 0-01S Photorns 4- 015 !Exclu~ded Llbraty . Grovia N WfiLm~

Eu -I 5; 01 U 3..0372al-O00 4 00eO '

'The mwtarlaf WrtwttiV k CYI. Coar Ijttiegrstvni PFrmin otm Y Dlevaclion (axtia') .... 20 Results mEgnur Rbti 9.V

&6 .O 4ma1m 4.142e q5 4.5r3 C4C5097 Cl-142

Plum Brook ReactorFacility FinalStatus 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 Flimmnre RAn, Fxnntrp

• atp.l~ Ecsure Rate Imom =10ALM2 With Hijldon Nn Ri dIrlop Aitsh Rniii¢h ,

0.04 5.505e.01 2.356e..0 7,031e 34 1.042e-52 3]1090.36 1.791J c1 2 538e,35 9.S22e 34 6.7620e3 2.537e 36 0.06 3.939e"2 5.693s-D2 1638e-27 1.ll1e-31 3,254e 30 0.08 9,041C 1 1-02%,2 1.62 124 a.g68e 23 0.1 6.27901 L.711e19 1 664e 17 2.618e*22 2.545e.20 TOTALS; 2r-5Q+0Q 1.721-19 1.66.- 17 2.634e.22 2.554e-20 Cl-143

Survey Plan Revision 0 Facility Plum Brook ReactorFacility FinalStatus Final Status Survey Plan Revision 0 blicro5blelf r5,0 4 (54 G4s00362) 12/29/05 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 I1.(134.974 148LIS) cm 8"Ai Its (Surnrnd Dyer eneqgiWs Whntif Ph~oton Fluijicie Rats (flux) Phat~ns/crm2 /sec 1.724e.018 1.671e-016 rIPton Enefgy Fluence Rate! Mevicuesoc 1,721c.019 L669e-017 Exposure and Dose Rptes:

Exposure Rate in Air mR/hr 2-634e-022 2.554e*02QO Absorbed Dose Rite in Air rnGy/hr 2. 299c,024 2,230e*022 U

mrad/hr 2.-2~9ge*22- 2 -2$OLe020 Dheep Dose Equivailont Rate io Parallel Geortnetry mSv/hr 3.844e-024 3'727e 022 inOppostd 2.107e-024 2.044e-0O22 ioRotalt'ona~, 2. 107e-024 2 .044e-022 2,03go-024 1.978e-022 Shal;,Deo Dos Equivralent Rate (ICRP 51 - 1q87) in~rar-A lei Geclcr-etry. .mS-v/hr 3.819cQ2 4 3.?O$~1-022 a Qpocsed 2.962e-024 2.873e-022 cl Rolotionol 2.962e-02A 2 .873e-022 o Isotropic 2,1I57e-024 2.092e-022 Fi4~fivo Close N~UvI~aent Mott (UCP 51 . 1987) a0 Antedor/Posterior Geornstry mS~v/hr 3.304e-024 3-204e-022 ooIosierlav/Anterior 0H

2.591 e-24 2 512#-022 io Latema 1,599e-02,4 1 -55le-022 2.21 3e-024 2. 146e-022 lo IsQoropic j-70~QVg2 I ,797c-0~2 Page I.

Cl-144

Survey Plan Revision 0

. Plum Brook Reactor Facility Facility FinalStatus Final Status Survey Plan Revision 0 Microftield Y5.04 (5.04'00362) ftRadiologlcaI liervcei, Inc.

Page :1I F~ile Ref: _ _ __ _ _

1)0L: FileI 151:11-$ Date: _ _ _ _ _ _

RL. ate:- Docern~ber 19, 2(>D5 By-,

11unfTime:. 1:09:20 PM Checked: ______

Duration QU0;,0-0:2 Case ioi LUns 1.641 A2 PescriptioI1: Revised Model lcak- Cv-60 UntnAct wSchedl 40 & 12 in 5h1d Geometry: 10 - Cylinder Surf-ace - External Dose Point.

Sour tis imensions HXI~eiht 762.0 cm 25 ft Radius i0.16 cm 4.- in

)gle Mmrr 38: crc.

z

1. 1 141.32 cm 91.4 c 4 ft 7.6 in I1241 G.0in 3ft Sh~ods Shield Name pj, itension~ 2=& I 1erlsUt cyl. Core 10, 16 cml Conci rete Shie~d 1 ,.65 cr Ifoan 1.8 Corcrctv A 2A 2.4 Shietcl 3 30 -48 cm Concrete Aik Gap Air G0C122 WallI Clad )25 czrl Iron 7.86 Source Input Grwipinj Alethod : Actuat Photon Enerpies 2.1 8 O992e+000 4 ..50~00e009 Co-60 D~jID 1L665Ne{34-Buildup, The material reference Is : Cyl. Core Woegration Parametets 20 Ci rcurnfortPti8 20 Results O.6938 L?03 XBI 1 OBe 13 2.302e-12 I 2.C'9Se~ Ifi 4.444a. 1.5 72209 7.78-6e.08 I13033e. I 1.391 e*Ic0 1.32 8.0990+00 1.25E4e0o 2.11S2e*l1JZ002e.10

.- TALS: I 420Qe4-Q 1.98 elos 1.933e"07 3.485e11 Cl-145

Plum Brook ReactorFacility FinalStatus 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) oni Pesiuots (51umgmd owpr Pnprcg,.<,~ IM44M0, f1I.;

pirdbnh F1kieic. Rile (Cux) 1.65toas 2.53OILOO0 I11-41on Eiwgy fluernce ftate Mevcitwisec 1.987e408 1-933e4O07 T'Npature and fjL)*,.Rtw m"R/hr 3 _A85-01 t :3,39ft O1 Ab2,,rbagd Dps49 Rate inAir may/h~r 3O41~,13 2 9G3. 012 U mead the 3 043c. 1 2' 963e,010

()ep Pose Equivalint Rao~

o Paral lei Geoa-*tty 3 Mi44013 o Opposed, 2 975, 013 018'1012 o Rota~onal 2.587. 012 Shaliovo Ctfse:Equiva~er,: F'ate tYCRp 51 1987) 3.677e-013 3.15 012 U

3,W540~013 3.4484-0112 3.540e. 13 31448.,012 ZA1Vi03 3 2.74 It 0 T2 Eifrtij Dow Eqvivalent iRal (iP 1 If~7,)

or, c~Pstr~ Ge-&,fretry Frr..,

Y.hr rjP I

";, __ 7n ;fr

r. ..t 0 2.2809-0 13 2.231 S. -012 2,512&012 2.284e.013 2,223vD12 Pap I Cl -146

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 kficro~heIld vS.04 (5.64-0032)

Radiological! Services, Inc.

Page -I File Ref:__ _ _ _ _

OW- File -~PB122126.MS5 Fo ate Dcecrnber 21, 2005 By:.

Run -Tirne., 5:,32.49 PM Checked:____ ___

Duration :00;00;01 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 Souri :.e Dimensions F1 - .' ~-;

--" ~~-;,, " :.%,X Height 762.0 cm 25 ft Radius 10. 16cm 4-0 in I. #1 141.32 cm 4 ft 7.6 in 12 ft 6-.0 in 9L44 cm 3ft Shields Lit Cyl, Core 10i 16 cm, cor~cr Ores

.65 cm IT01an 1.86 Tr nsitiwq 2.4 CnnicreftI Shietrd 3 3048 cm Concrete 2.4 Air *i~ap Air -.1122 125 cm 'Ron 7.96 Source Input Grouping Method -.Actual Photon Einergies clure,_ eaur uci/r-sn9 Ca.137m 2,0708t-0O1O 716?10e443W 4~~2,570e O0 1.5751e-004 2.1890e .01 0 8.09'2e-000 4.50Ca0e.0C9 1.6650le-0Q4 Suirdwip The materfal relletence Is-Cyl. Core Y Dire~t~onintegration Parameters

'Y Drecion(axial) 20 Circumferential 20 Rus uttE CMi Ativit Fluen'ce Rate Fluence Rate EY'ur R/hr wqVm'/spc No Okldiur. With Builduri No Buildup~

0.0318 :4.5864-131 2.1 95e-6iS 1.383e-34 i .828e.67?

0.03.22 2.927e-01 1.92.4e-653 2.652e.34 1.548e.65 2.i34e*36 P ',364 Ii~u6$Lv-o 1.8 19e-49 1.47/8e-34  :.033e-5:

' 316 6.894*00C 4.527 b10 1021e0 8 75&-13 1.979e.1 II C1-147

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Page :2 POWS File - P5122)G.MS5 Run Date - Decerfbe 21, 2005 Run Time: 5:32 45 EM Duration; QODOM I l EneTAS Adie+ty Fluenne Rate FluOene Rt R!

4.51ea .No Buildu rx.itr-h Et1 g 1-02eVfz TOTALS: 7.452e+00 4.511e.lO 8,758ce 13 1.97ge-I 1 Cl-148

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 r11kvoShleld vS.04 (5.04-00362) 12/21f5 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 Results ISummgd over enaiesW lUs WlIhrmlt Wut PhWlon Flwee~ Rate (flux Photorkrri 1 /5ei 6.827e-O010 1-543e-Oa Nvoton Eneirgy Fluence Rate KMeV/Crnk*/eC 4.517e-l10 1.021 e-008 Excposurit~nd D~os Rates-Exposuret Rate ainAir mRlhr 8.758e0 13 1.979e.OlI Atsorbed Du Rate in Air mGy/hr 7.60ce015 1,728c.0 13 mnrad/hr 7.645e.013 1.728e-012 (ICRP 51 1987) coPeralIe! Geomnetry mSvlhr 9,052e-015 2JJ46e.-J13 ri C;po*V-1 U 7.247e6Q1 1.638e" 13 o Rotational 7.247e-015 1 6080*0 13 U 1ec2¶'uptC 6,409e*015 1.448e-0 13 St~aIIiov Do~se Equivalent Rate ii Nraflcl a~nk{ry mnSv/hr 9.621o-0 15 2.174e*O13 a Opposed 9.1 3ge01 5 2,065e.0 13 o Rotatiornal 9.138E'-015 2.065e.O 13 a tsa:l'oP&T 6451e-Q 15 1.54 e.0eO13 Effective Do-so Ewuivalent R~ate c Anterior!?osterior Geomietry rmSv/hr 8&004t*O1 118O9e.01 3 cxF'rlifi rnr/A i4crirr a 7.065e-015 o Lateral 5.239eO1 5 1.184-e-013 oRa¶oa 6.31 3e-01 5 1.42 A,*-133 o I50tropic 5.375-eO~1 5 Cl-149

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 U¶JroShl1d wS.O4 (5.04-00362)

Radiological Sexvicesm Inc.

Pap -1 Fil Rdof;_

DOM File : PB1221271MS45 Date__

Ri ae;sc mber 21 5 C3r:

Rvirfimet $,35:40 PM Cheeaed:

Duritio :.Q;QQMO 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 surce Dimensions Hesght 762-0 cm 25 ft Radius O.1I cm 4.0 in DMse Points I z

1. 1 141.32 cm 28 . LI'I 91.44 cm 4ft in 12 ft E'. irt $ it Shields

.- hiaje~Mpmpn n~imnr,-i-.r, Mla rinl D~ensit, Cyl, Core IA, It6 wM, Ccn-.nrrtct 1.8 0 Shield 1 .65 cm lon 1ri Trbit ari C.c -- rmJiCt, Shield 3 3,48 cm £ rCcnrptE_ .4 Air Gap Air W."[C..:ad .025 cm Iron ~7;8 Sourzc rnput GrwpingU Method.: Standard Indices wmbkr of eroups 25§ Lowettfteetgy Cutoaf t 43.J15 Photons < t0.G5 , Excluded Library: drove N:I, Hde ubeaovreol  ;:uCi/mrp 130icrn Luw 152 2 1-90a 010 .S99e+OO ... 4&5O3Ov2 1 ,M~5iNM4 Buildup The material reference Is: Cyl. Core nitegration Parameters Y Dire-S-^on {axial) 20 C3 rcumiorcntia; 20

- ErUlls 4 A4.7+9g .tluflD/5v

.flulenri- MXee Exp:sure Rate uro Pw~

~ VM:V2LV fnR/hr ND5Riuitfl No Buildyin With RuBitl n -

34 4.792eti- 8.91e-40 9.250M-33 3.645e-42 4.091e 35 Cl-150

Plum Brook ReactorFacility FinalStatus Survey Plan- Revision O Plum Brook Reactor Facility FinalStatus 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 FLbanre Rat Fiuence Rate Ex-opsre Rate, mfgfhr . MR~bL YWith Bu~i ld=

0.05 1.198e+O0 2.7S2e-28 2.721e-27 7,410cM3 1 7.248e.3O 0 1 2l,303e+00 4.628e. 16 2-7sge. 14. 7.061e.19 4.221e 1J 5ZIS-7 12

.2. 6.06!De-.0 6Z25e'14 5s617i12 1 204bf,3i 9.914e 15 0-.3 2,1WC+0 2,579c. 12 1I57le-10 5. ~te16

.4.e939-15 2.9A79e-13:

GA 4 !9(D0-01 2.747e-12 1. 202e- 1I 5.352e,15 2,34:a2c 1 ;

0-5 4-56e.02 7. 44e.13 2.507e-lI 1 Soe, 15 4.921e.14 0,6 3434i-01 1 46e.1 1 3.62le-10 2 744e- 14 7.0S6e, 13; 0.8 1.442e+00 .2.312e.10 4,055e*S 4.398e- 13 7.713.-12 1 .O 3.465*+0Q 1. 539e-109 2.009a-06 2.83&7i(.12 3704e,1 I 1.5 1.879et00 4. 762e-OD 3-022q-O 8.012e-12 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 ReactorFacility FinalStatus Survey Plan Revision 0 MIicroShield v5.04 (5.O4-00362) 12/21/05 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 Ig 1- (141,32,at1,9t449 cm ujtul (gumn=d r IJnits Without 4Wih

-S;1fi P~iston Fluenero Fete(1ate Phot~r1/rn1jeC 6.0440,09 5.215e-008 P~ton Energy Fluence R~ate, Mev/cm-/see 6.653eLO09 6.303e mg Expoure, and Dose Rotvs-Exposure Rale In Air mR/br I .133e-ol 1 1.103e-010 Abswrbe Due Rate in Air rm<y/hr 9.S"0tQ14 9.633e-DI3

.1 mrad/hhr 9.9Oe-01 2 9.633e-01 1 Deepr Dose lEqv~iymfrnlt FRatc! (ICRtP 51

• 1987) o Parailel Geirmetry mSv/hr 1.124eQ1I3 1.096e-0 12 I

0 oppostid 9 .70E-D14 9i424e-013 o RPotational 9.70e-014 9.424e4 13 o lseopje ~8,61c-O14 8.414e*013 Shalfow Dose Equivalent Rate. (ICRP 51. 1987) a Paratiel G40i etry mSv/hr 1.193VO13 1.167e-0 12 o Opposed ' 115le-013 1.124e0 12 a Rotationa U 1.15le-013 1.1 g24,0 12 o I5O1KOiP, 9.1l7e.014 8.906E-013 Efectivc Nse E quvale-t Rat¢- (ICRP 51 . 1987) o Arntenor/Posterior Geometry mSv/hr 1.01 2e-0 13 9.872W0 13 U

o Posteriet/Anlerior 9. 3-4e,014 9,074 01.3 o Lateraf a 7.460e. 14 7.204e-013 o Rotational 8.414e-014 8-172cQ4,3 -

o I$otvop: 7.4W'Q 14 71 1-o13 ft Page I C1-152

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShleld i5.04 (5.0403629 Radlolcglcal Services1 Inc.

Pap :1 File IReF; DOS File : f1 2212.8.,MS5 Date: .

Ru a: -O 21, 2005 By!

Rui~Time: 5:48:23 PM Checked; Duratio ; 00;00:01 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 Source Dimensions Height 762.0 cm 25 ft Radius 10.16 cm 4.0 in P9Fq Point z

1. 1 141.32 czM 38 cmn 91.44 cm 4 It 7.6 in 12 It 6.0 in 3 it Shkcds Shieild Nasm Dimension bflIte Cyl. Core 10,16 Crnt QCoc rete 1.8 Shield 1 .6Scm Ire,fh 7.g6 Trensifion C~ncrete 2.4 Shield 3 30.48 cm Conciete 2.4 Air Gap Air 0.0 M 27 Wall Ilad ,M2crm Ir 7M8 Source Input Grouping M4ethod : Standard Indlces Numbcr of Groups . 25 Lower Eteray O1o01f 0415 ilPhotonse 0.015 : Excluded Library r Grove 1Nd iri~r auicœ Eu-154 2,189Ge- D1i 80992,e+C0 4,5000eW00 _r 1 65Q-5e-004 Buildup The mateuial relerence Is : Cyl. Core IntegratW Parameiers r Virection (oial) 20 CircumferentiaO 20 IkRsults ElieEy A4Gtifr MUU teL Emostire Rate [Eqosure RWte y MeV Lhoionssec sec Me~fcrn/e ,mR.thr hr N~A~jilduo .Withui8cu*p Wlith Buljdup 1,648e+0 2991e-40 31182t.3 1.;323B42 1,4070 5 Cl-1S3

Plum Brook ReactorFacility FinalStatus 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 Activity Flutice Rals Fluenep Rate Umaisre Rate L-prsr Ratg

'me/hr W4oBUildup) 005 4.1 87e-01 9.7 1e-29 9 5O7e.28 2aW e31 2! 533e.30 0.1 3-277i'tOO 6, 587e*16 3.927e- 14 10088*18 6.OC8e*I 7 0.2 .531e-01 6.220e*14 5,119t0-12 1.098e 16 9,035e-1 5 0.4 5. 778- 02 3,1 19e-13 1.365e-11 6,077es 16 2.659e. 4 0.5 I .764e.02 2.934e- I3 5.76O0. 16 1 .:8ae, 1 4 0.6 6.53 3eO 1 2.674e I I 6,887e 10 5,21%,14 1-!34e- 12 O0s 3. 154+0 5,064e%. 8.88 e-09 9.633e-13 1.689- I 1 1.0 2.492e+00 .1 7e0Q9 1.445 c0 2.040 12 1.5 3.I60C+OU S .0108-09 6.428e-08 1i34e&- 11 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 FinalStatus Survey Plan Revision 0 mlquahid wSO4 (5S04-00362) 12/21M

1. 4kcr*Wqkd ,r5g@4 (5,G4301672)

Itad4fticl St~vfts~ If 0bonvmg $f cakuatcd upcur n1i r t* doft FI.L MWUN$PATAWPS422IM1M Cmt Thtl*; IMe 1,641 0 This ctk wevg en t Doccwn 21, 200ati5:4423 PM1

- vsi PtInM 1 * (Fa13Z31 1 9I~l4*} gm Jeil~ W~H tfwt I1 WUE; =t--r PIoton FeneluIRote (fRtx) FMWuon$'/¢sW 7-12Me-0 6."$>OPB rP*:ton Enetgy Fluence Rate MeV/C-Mf/'Q {9,65,v^009 $1 M,gO 9s a34 O ERb Ctes.

-.Cupuae Katei en Ae mRthr 1453c 1II 1.531e-fO]

At=-: Dalee R in Air mIGytr 1 43e-013 1.336e 032 U

mradhr 1 443Xe-1 I 1,3360Qe IO

[loop DGSD f qtA4;Ih Rate OICRP 51 . 15M7) o Pafallel GetI mSv/hr 1.6feW013 1.521Le012 P) 0 "w,d 1 420e4L13 11311e O1.2 o Rotational 1.42eN-0 3 1.3 1le 012 I .271t-o} 1.172t*012 Shhow MDose Equv Pctv (ICAP 51 . M7j n PNralel *trw*y mSy/hr a

1.737te013 1.614e 012 o Opposel 3 679t-013 1,557e-012 a Rotationai 1.67&e013 1.557e.012 0 15ttrr)Pit 173I41e-13 1.233eQ12 E-~eetive Dose Equ9:ivalvt Rate ()CRP 51 - 1M7) rCA,7tert or.fPcis~eno l Geometry rrmS/hr 1.47$e,013 I .36&O1 2 W

o P: n'E Aniripr 134Y, O 3 1 095. 013 106OM~ 12 L ROUl10Mtt 3.231*i0 3 1.1 412 F..'flgt

.Fy rp: 1.93C 013 1iOOl- 12 PaI I Ci-155

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 I/

MJwroShdeld w5.04 (5.04-'D362)

Radiological Serivces, Inc.

Page :1I F~il Rot; _ _ _ _ _ _

DOS Fie : PB12212'9.MS5 Date., _ _ __ _ _

Ru tat: Oweribemr 21, 2005 BY:

RvifTirne: 5:40:37 PM4 Checked:__ _ _ _ _

Duratio~n :00:00:01 Case iTRWl;Line 1.641 E Description.- Revised Modic Co~c. AW1O m Unit Att, w Sched 40 & 12 in Shild Geornetry. Cylinder Surface - External Dose Point Source Dimensions 762 0 cmn 25 ft 4.0 in Doe~Puir&

• 1 141.32 i I~m 381 cr 91.4 cm 4 ft 7-, 3 ft fli.nsity Cyl. Ogre 1.8 di Shield I .65 cm Iro,r 7.86 Tranrsil ionl 2.4 Shield .3 30,48 cm C~onc.-ete 2.4 Air Gap A hr 0.001 2; Wall Clad 025 cm Irci 7.86 Sowrcc Inpu~t Gtoupling Method - Standard Indices&

Number of Groups; 25 Lovd9w iErmgy Cutofft +/- -01S PhwtonsI 0Q&15 ; EAIlrdnl Library ; Ow Nw.~iid . Al 1=Wz.Pti*5 fLg fe, AL?.108rn .2.1890 e.0.10 B.0992e+0030 4.5~0009.Oi09 1.6650e-004 Buildup The material relerence Is : Cyl. Core Integration Parameters V Drection, frdi~l) 20 Circumferential 20 11neg Activity IkY F'lbjg1nrr. luq S..312e*00 I1.878e-207 1.49- 6.5-34e-209 6.057e.35 CI-156

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 W Paee 2 DOS File . PB122129.MSS Ron Date - Decer ber 21. 2005 Run tirne 500:00: P DurAtion . 00:00:01 Activity n~uemm Ra~t FHuena Rate Exposure RB rxtslure RatIL f'evierrA'~ec t lem.' terv;:

.- mRhr r4R/hr With Riom1in UpM Blildp With BuiWduo*

1,720e.06 1.197e-79 3,9wS- 1,186e.8l 1.241 u41 0.03 5-740e-01 1.$7.2e 8 5.952e417 9.41ge 20 0.4 7,2.80e+00 .3.929e-1 1 1. 7ge X 7,655ea14 3,3506e12 7.321e+O 2.9q7e.10 7,718eO9 S.84"ge-:$ 1.$Oe61 l 0.8 7,330e+00 1.175e-09 2.016e.08 2 .235e12 a.20e-1 1 TOTALS; Z78e2+Q1 1.514e-0-9 3.O5tte*s 2.897I.12 5.762e-1 1 Cl -157

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShiiuld Y5.04 (S.0400362) 12/21105 Ml roShield Y5.04 (5,04-0D362)

Radiological Servicet Inc.

Conmtilodi of carwiuitcd expesmr Inair~ 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 Summ~ed over eneregiesA Xeut j 6J Pt~otn Fkier~e Rate (fivx) Phaomrs/cn9sc~ 2,067e.009 4-292e-0O&

Photon En~ergy Flu rice Rate~ MeVel/ns~ec 1.5 14e-000 31005e-008 Erxposure and Dose Rates-Kf x.*urt Nate InAie mR/hr 2.897e-012 S.762e.0 I Abwrbed Dow Rite 'n Air MG/hAr 2?52*-01 4 5.030e*O013 Ii mrad/hr 2-529e-012 5.030a*O 11 (IC9P 51 1987) a Paralel GeodTetry mtS/hr 2,6t014 5.926e-0 13 2.41 le-014 4.7870,013 o Rotational 2.41 1ec-014 4. 787eO013 a I301fopi 2-131e-014 4-233oQ 13 Shallow Wcse Equvaie~nt Rate (ICRP 51 *1937) o_Paral 1.l Geormi.4y rmSv/hr .3.165t-014 6.309e.013 a Opposed . 3-01Se*01 4 6.005e.03 o R-otational 3-01 Se-DI 4 6.Q05-0J 3 a ISOVOPIC 2.280cc-014 4.528e*013 Uffccrtive Dose Equiv~itntr Rate (ICRP 51 1987) a Anterior/Poster;or Geornetry mSv/hr 2.636.e.O14 5.256e~013 a

2.347e,0 14 4~667e.01 3 o Lateral I1.764e.0 14 3.492e-01 3 o Rotationap 2.099e.O014 4.1 7l-Q!I f04l-fopiC I1.00014 4,57~Q01 Page 1

. CI-158

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 tlcroSheled v5.04 (5.04-00362)

Radioklogcal Services, Inc.

Page ;tI File Ref _

00" Fia 5 P18122130.MS5 Date.

IRub aite P Dernr!er 21, 2005 BY!

.Run rsme: 5:.43-37 PM Chocked:______

Duration ,00;00;01 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 Source Dimiensions~

Height 762.0 cm 25ft Jt Radius 10.16 cm 4.0 in Doe~Pints 01 x

141.32 C x

91.44 cm 4 ft 7.6 in 32 ft&.0in

-enft Shields S-hiplj4 NAMp JL Cyli Cjre r.4te n7n.8 '

Shield 1 .65 cm Ir~f 1.86 Transibin Canc.r~etr '?A Shield 3 30.48 cm Cncrrete *e .4 Air Gap Air 5.00122 Wall CIad C25 cm Iron 7.86 sourvir tnput Grouping Ikethod : Actual Photon I!Aetgles.

Nudie bjeUral U~ifc N5.)94 2,1090.-010D 809920+000 4 5000c.0lJ9 1-.6650e00Q4 Buildup The material reference is: Cyl. Core Inrtegration Parametems Y O~irwizon tox*I.,) 20 Ci rcurnterontial 20 Re suits ActiA41 Exm&Lrr ftt Lxms~urf Bzt MS mR/hr MR/hr A'dh SRuidig 0.0174 2.864e-03 7. 14,9e-309 2.85gb. 310 4.085c.39 0.0175 5A487-v03 II Z0403U 1.464e-36 8.9c305 7,752e.38

'.012 1.612e.03 9.969a-223 5. 14e.37. 1.8Ose~3it

".102.6 8.099c+~I0 1,473c.O8 2,841 C1 II 1.A10 8.099e+00 I1924-09 3.01 1e-08 3,62-le-12 5.667e-1 1 Cl-159

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Paso 42 DOS File PBi12213Q.MS5 Run Date- Decmrnber 21, 2005 Run Time. 5A3.37 FPM Durifon: 00:00:01 Arf;i+y SfornrtdRti Fluence Rate, Exp~osu~re Rpge Lure -_t

-ohatangfsee Me-femysf.ee w.Jerw/sef: ,MR/hr Nn R,,ildur-, With Riti1~gp ND Butildup - With. BUuinu TOTALS 1.621e+al 213OC-09 4.4$4e-08 4,983e 12 8.50e- 1I Cl-160

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Mi-moShteW v5_04 (5.04-00362) 12221/05 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~ Kul Proton F~vqr~e Rotc ~fiux) Ph~tr,*"$/risCMV~ I3,214e-009 5,553e-008 Pw~on Enefgy Fluence Ratew Mev(/cmkl/se, 2 .630e.OGN

!xpqs5urv and Dose Ratvs,:

Exposure Rate in Air mR/hr 4.983e-012 B.508e-O 11 Ab,,orbcd Dose Rate in Air m~y/hr 4.350c.0 14 7427e.013 M

mrad/hr 4.350e-O012 ~7.427e.O1I1 O~cp DCse Eq yiii1nt Rate (ICRP 51. 1987) oParai [le Gi-cetry mSv/hr 5,061 e.014 8B65eO013 oOppozw~d 4,16&6e-014 7,109e-013 Po Roitational 4.166e-014 7-10ge-013 3,684c.0 14 6.287e-0 13 Snallaw Dose Equivalent Rate (IC-R 51 1987) o Par-01kd Gtqntetry mSv/hr 5.412cQ14 9.24 7e.0 13

.a 5.1 64s.014 8.8219-013 a Roz.ationa ~.

51 64e.014 &.821 e-Cl1 3,942c'0 14 6.727e*013 Eflarhw Dow Fcruiwaent RPIC (ICRP 51 - 1987) a Anrter or/Pstencor Geoer'utry mSv/hr 4.51 1e-01 4 7.706e-O 13 N 4.046e.O14 6.90O5c; 13 o LatteralI 1.074-01 4 .5,240e-0 13 o Rotatoona~ 3.622e-014 6.182e.0 13 3..1,1~4p94 Paso I.

Cl-161

Plum Brook ReactorFacility FinalStatus Survey Plan Revision O Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicroShleld v5.04 (5.04-OD362)

Radiological Services, Inc.

Page ;1 File R'of__

DO$ File. P812292L1MS5 Date:

Rt h tUm: D3M:7:5 5 R~h Ifinle: 3:17:53 PMY Chealed; Duratio ; M;W;Vt Case Title. Line 1.641 (

Mescription: RetIsed &iodel CaIc- I4129 Unt Act w Sched 40 & 12 In Shid Goomstry: 14 - Ctyiridr tufact - IWnal Dam; Pqlpt

,v-. l.- X Source, Dimensions Height 762.0 crm 25 It It.

Radius 10.16 cm 4.0 in Qwe PPrIA x z N1 141-32c :M 381cm 9144 cm I it 7.6 in l2ht60ihn Shislds shield lyarne f 3ensltv CW. Core 10. 16 cm, c~oci 'ete 1.8 Shield 1 .6. cm Irm7' i.86 Tran-sition Cc ncretr 2;4 Shield 3 30.48 cm Confcrete 2.4 Air Gap Air O.001 22 Will Vaind 2M Cm 1rQn 71.8e sourcC Input Grocplng blethod : Actual Pkoton Energles uuclide 2imes brgLfrels uCi Dq&.e 1129 2.1690101 SM92i'rv00. 4.-5000e.009 1.660o-00 Buildup The material reference Is: Cyt. Core lirtegratio Pwfameters Y Diroo;ion axial) 20 Circumferential 20 Arfly--4 fluoent:, RA40 Mshio-rr Pigi~ F~auiro Si ftxm M-V mR/hr No Etulldfjj Wdth 3UU11dun NO B3Ivl7uo With ButiGrus 0.029!5 1.616eOO .6Z99C.77 1.1 17e 33 7.01 le-79 1.16ge-35 0.0298 2.§9e4f*00 1.0780-74 2.137e 33 I 09S2u 7 6 2.A6se-35 0.033& J.1 16e'33 2.0'73e.59 7.93Ee, 36 0.0396 6.09leeO1 1-793e-41 1.134e-33 8. 146ei44 5 154a-36 Cl-162

Plum Brook ReactorFacility FinalStatus 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 Flu3nr7.4R FItjrenr-w 3F A Fxnncrtirg ate EXcour Raste

&Mt/hr 1.793Se-41e %Mirth Rijitrhip aa~b With Buildup TOTALS: 6,290e*00) 5-504e-3.3 f8.14fif.44 4-644e4.35 Cl-163

Plum Brook ReactorFacility FinalStatus 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.

Pkboton FIlxsnce Rato (flux) Ph.0tons~cm,n!se1c 4. 529e-040 1.716e.0-3 Phvoton Energy fluenoa- Rate MAeWernk/~ece 1.793eM041 5,504e-033 Exposure and Ctise Rates Exlpasure Rate in Air rnR/hk 8.146e*044 4.-64e-O3-S Absorbed Dose Rate in Air Moy/hr 7.11 4C' 4054e-037 M

mrad/hr 7. I1 1e-,044 4-054e-03S

~(lCRP 51 1M7) a ParalIef Gveormetry mivfhr 1.0Q8e045 4,641 e.O037 o pposed 5. 127e.046 2.328e.037 a Rotational M 4.642e-04,6 1.96i43 a Is1eopic 4.,44le,.04 1L8449.037

~se DoIiwEqu~vaent Mae (ICRP 51 . 1987) a PlarafleI Geo"metty m~y/hr 1 .024e-045 5.O580.037 c O~ppose~d I

.7 ,069e-046 3.478e.037 S

o RotatioraI 7 .070e-046 3.47ge*037 5.1 M.aV46 2~571e*037 Effoctive Do-, Eca.iwalnt Rate (,ICRP 51 - 1987) o Anterior/Posteri-or Geome",~ m'Wthr 5,935e.046 2-08 1e-037 I 3. .B e.O46 3.076~,c-037 o Latera I 1.982e.O46 5-807e-038 o Rotatiional 3.226e*046 2.0159~e-0$7 Li IWa~rcpic R,§4rQ+

Page I Cl-164

Plum Brook Reactor Facility FinalStatusSurveyPlan . Revision 0 NlicroShield Y5.04 (5.04400362)

Radiokoglcal Services, Inc.

Page ;1 roc4 Re~r; _ _ _ _ _

Date:__ _ _ _ _

Rt. ate: January 4. 2006 By; Rvr~-ime:rn S. 3, I S AM Checlied: _ _ _ _ _ _

Duration : 00:00:0I 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 Sour.e 0imensions A Height 762.0 c~m 25 ft Radius 10.16 cm 4.0 In Dose Points Y

A1 141.32' cm ~ 38:1 ca-1 ?1.i14 cm 4 Ft 7.E inP 12 ft 6-0 in Shields St;irwr Wd NIB I Cy! CAre 16 cm Concrete 1~.-S

& Shield t .65 cm Ircel 7.86 Transi1tion Go:ncrrcte 2i4 Shield 3 a0.48 cm Ooncf ete 2.4 Air Gap Air O00D72?

Wa1 'Clad '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 uN~dp zaLic~ L ho,.:! ~ ~ r~i-rruro9 iirr-Sn4126 2.19900- DIO & 0992e+000 4.6W000-.OJ 9 1 .6650e -034-Buildup The material reference Is : Cyl. Care lu~Intgration Paiameters Y Direction (auiail) 20 Ctrcumrferential. lsut 20

&dctiyit Fluerict Raite Eicrxsurei R&to Extposure Rate nhotonfi/spc m R/hr 6.26-9e.01 2.21 6e-208 2,064e-34 7 .676e.210 7. 148e-36 Cl-165

Final Status Survey Plan Revision 0 Plum Brook ReactorFacility Brook Reactor Facility FinalStatus Survey Plan Revision O DOS File : P800406.MSS Run Date: lJanuary 4. 200 8:

RFign Time: B13:18 AM Dur'tion : 00:00-01 ArtiviW Fluenoe Rate MleVfemkse ki*YicrW/See Nolgtildtjo Wih Buidup Wisth Su-iO4; 0.03 2.371e+00 1,651e*73 I, 726e. 13 1,636e75 1,71' e35 0.04 4,046-02 7.340Be42 7.8Me 35 3.246e*44 3.464e9 3 D.06 7.76te-01 5.45o23 1,04P2c21 L062-v,25 2.070. 24 0.08 3.71 9Oe00 L0194-17 3.857e 16 1.;612e.20 6. 10e-19 TOTALS: 7.534e+00 I 01 g. 17 3.857e. 16 1.612e-20 6,103e.19 Cl-166

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Mip4nleid wS.G4 (L5.O4-83U2) 02104/$6

• crMShlwik4wS04 (5,04413)

WR~kckic urvicts, Inm.

ctnwsw of tck1Attdgup9$k i at to &se nLE.; CQ\W5NDATANFPSUMOMAS Case Title tMse L641 HI This ca waivwr; o i W4fsty, Jaury 4, 24 6 at 5:1rl3$ AM Ofte Poin t - 04(tS,2311,%A) tm ault-s I{umrn~ eve enereWesithout Wdh Sui~leiuo Phdont Fltiaeer hic; Out),

ftrA PA, S, Ve:,

M-eV,!Cjw,71 11.273e 0t16 4,821e-015 ble-ay'Xh 1F.uefi Rate 1.0ilLe-CI ? !A574- 01t tKF~5Ur4,i drni DLo4¢ 1~Ps~

f x-pasur# 5tip in Air mRR 4'br 2 612t 020 6 10- 01 9 Abwrbx Dowe FRte in Air 1.40I&22 S 328i 021 I nlityht ] .407-4-V S ,3280 19 erep DoQvx Equsl&tlnt Rate (ICPFP 51 -

a Parx-le Gewnetryn rnSyhr 2.462e 222 9.342,0 0W!I I

3 33 le-022 4964-021

, Rotational 1 .274e-022 4.825e-021 4.79OeJ21 ShalI Do se Equgtyaent Rate (IJC RP 5- 187) n P-troiil CinQrtdry rrnS3t +'tw 2.43ge P_ 9 2330v 01 1

' 79.3e-422 6 .786021 u Irioiial +.1Z793 6.*78& 02' U llol f0I i 2 4.98Ie-021 t-H~ttI ',i ;j t Rate i~ts OCIRP 151 1987) 6b A.PiAf - Litefltf) 1F *r mtfy

e rrPS a~ .'hr 2 069e-02,2 ?X7e2h02'

• i.PVtgerarw err 1 577 022 5 9;O 02i i9.719e-023 3.679e 021 ci- Rwitarturaf L.343a-922 5 C85e-O21 1.087e fG22 4 Mt27 Pape I Cl -167

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MicruSbicid Y5.04 (5.04.V03620 RadiDIOICal S'ervices, Inc.

Page ;I FHliRef; DOS File : PB122921.MIS5 Date:

Fk ant0C5i Meb Run'rime: 3:21:15 PM Qhecked; Duratigq ; MOMQ 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 Source Diumnsions i Heigit 762.0 cm~ 25 Ft 10,16 cm 4.0 in Dose Points z

At1 141.32 c :m 381 cm 91.44 cm 4 I't 7.6 in 12 ft 6.Oin 3ft Shields S~hijde Nsrnr, Uif-mo Wz CYI Cc0 101~6 zrnr. C~onc.yrete II.,

[--i a Shuerd 1 .65 cm Irc, 7.86 Tran~sifian Ornc~retc 2.4 Shield 3 30.48 cm Conec'ette 2.4 Air G, p Ai'r OO1 22 Wadl IClad, .025 cm Iror X.86 Sou~rce Input Grouping Method : Actual Photon Energies; 14wild OLL bgurl wicn BgLzzn~

Zr-95 2.189DeA31G 8C-992ei-000 4.5000e.009 LGG665e.004 Bdildup The material reference Is: C 1.Care.

y Dr~Ion F30On Pararnete-Ts ntIFIN 20 Circurnferentiat 20 Rgsults rrtf-o Activiity MeV/cm 2/sec Mdafm2 a, R/r nc 0.7242 3.5.369+D0 ,3.5!57e-10 7,125e.09 6-94De-13 1.370e. 11 t0.7W-7 44830--00 T.MiALS: 8. e+ . 910le-10 1.760e-08 1.745e-12 $,375e.1I Cl-168

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 ilcreShleld aS04 (5.04.00362) 12/29I05 MicroShklld 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 RPS11lts tSmMed MCenprgip; Adh rtulxdu PtoDtan Fluence Raht Nu) Photons/cm'/sec 1,224e.0O9 2.3684-DO8 Photon Ene-y Fuence Rate MeWV/CM TVee ' 91Ol0iOl1 1.760e- 008 Exposure and Dose Ruitks xwpsure Rate in Air mr/hr J.745eO012 3.375e-1 1 Absorbed Dose Rate in Air mrGytr 1.523e-14 2.946e-01 3 II rhrod/hr 1.523e, 12 2,946o-D1 1 Deop Dose. EquivWlnt Rate (ICRP 51 1987) o Paralilel Geometry mSy/hr 1. 786e-14 3.454e-01 3 Fn fpposfrd 1.452e.014 2 4OU-1 3 a Rotational 1 452eM14 2-B.8e-013 o Itotopic 1.284e-*14 2-42e- 013 ShallJw Oose Equiv~aent Rate (IC.RP.51. 1987) o Paral el Oe nety mrvhr 1-.907e014 3 6B7e--1 3 H

O Opposed 1.417-.014 3.$3-013 o RotatioAal 1.8 1 7e-014 -3.513e-013 o Isiatrpic l. 374e-4l4 M.2.67e-01 3 Effective Dose Eqcvivalent: Rate q AtrterrarIPOSternor Clecrnetry mS-v/hr 1, 586-,O] 4 3 067e.013 o Postailor/Anterior H 1.413e-014 2. 732e-01 3 o LOteral 1.02 .014 2.054e-013 o RotationaJ 1.264e-014 .2.444e-01.3 a i$Qtropic 0 1.082c-01 4 2.093e-01 3 Page I1 Cl-169

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MlicroShilid YS.04 (5.044.O0362)

Radiog~ical Serrlces., Inc.

File Ref:

DO$ FLk .P122.MS Dae ___

Rt ate. Decemb~er 2~9 20115 By:

Run (firne: 3:44:47 PIM Checked:

Duration OO0:01):0J 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

-x Heh !5urce Dimansions I+ 762.0 cm 25 11 Ra-dus 10.16 cm 4.0 in Dose Polinft I

II JV 141.32 c 9 1.4A cm 4 It 7.6 in 1.2ft 6.G in 3 ft I

Shields I I Cyl, cwe P2 16 cm-' Concrete 1.8 t

• Shield I EL .&Ec-f lrfin 7.B.6 Trowisilion Concrete 2.4 Shield 3 0,48 cm, Concre-e 2.4 Air Ga p Air GLOCC122 Wa4ll Clad .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 Nucside ids bg-ccnwals _____,-

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 Results Pj-tPnrP POL WAY MeV/cm7YseC rr R/hr No &LIl day With PUP& 'i No 1301dur With FBuiRsuo 2,578v.02 IA-794-75 1,~876e~35 1 .778e-77 I ~;-9 -3 Cl-i 70

Plum Brook ReactorFacility FinalStatus 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 Thiemntce RMi Fluenra Rate Exioure R&te Ex-posure Rate 8 WIiW-hfietong/g~e- MCV/crny~sp_2 0a0- XMeXttot ND PutiddUp Keith Buildup 1 A6$t+00 2.64e-40 UIM~C,33 11 7& 42 1 253e-35 0.05 4,775e. 01 1.108e48 1,0104e-27 2.953e-31 2.888e 30 0-08 1.05Oe.01 7.2>4e-24 1.411e 22 1.437e-26 Z8O2e-25 0.08 2.515t+O 6.809e- 18 26O8e1 6 1,.9O0c20 4,127e 19 0.1 . 1.674e+00 3.365e-16 2-OOie 14 5.148e.19 3.069e*17 TOTALS: 6.26e6IW 3.434e!16 2.032e, 14 5,257e-19 3.! ZDeI 7 Cl-171

Plum Brook ReactorFacility. FinalStatus Survey Plan Revision 0 MoBit id vS.B04 (S.04-00362) 12/29/05 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 wr tJTit 'Ifithoui Pfr~on Fluvncc Rot* (f ux) Photons/cm'/sec 3.45le-015 2.039e*0Ol 3 Photon Eeir&~ Flu-ei~e Rate M01Crn'/SO 3*.4344-D11 2,032e.014 Expos~ure and Dose Rates:

Expoture Rate in Air mR/hr 6.257e*0 19 3.1 1c~Oe I0 m~y/hr 4 .589e-021 AbsQrbed Dim Rate in Air 2.715,e-017 I

mnrad/hr 4.56ge-0 11 COvp Doseo Equivalnt Raite (ICRP 51 .1987)

,a ParalleI Geometry mSv/hr 7,677s-021 4.54le-019 4.207e-021 2.48ge413 9

,a Rotational ,2488e-01 9 lwto~opic 4.071 e.021 2.408e-Ol19 Shftow Do.se Equivalent Rate! (ICRP 51 1987) a FRatallel Gec~rnetry mSv/hr 7,627v.021 4, 5 l~e-Ol 9 I, OPpoSW a 5,912e-O21 3.4 98e-01 9 c' Rotationat 5.912e-021 3.4 98c 019 n Itaropic 4,31)5oCI21 2. 547e-01 9 Eftective, foso Equivalent Rato (ICRP 51 1987) o.Anteroor/lPastefior Geometry mSY/hr 6.597e.021 3.902e-01 9 o Posterior/Anteio U 5.170c*021 U.59e-019 3.191e*021 1.888e,01 9 o Rotational 4.416e-021 .2.613e-019 3.140-21 Page 1 Cl-I 72

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 rNg 1 Fl I Rol; "lite 6Y-'

me ,t PtA 1:18:19 Checc*ed:

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 wrxt limens-ns Heftjght padiU3~ 23ti 7.62 cm Dm Pints z b I Z4Itb7 cm 4 it 6,6 to l:2 ft 6.0, !

SllVI.tds Shirel0 Nsro-e 7 COfl. Core 7,62 cm'r~t pnc rrete

. ShIeld ' ..65 cm tro}F 41 tran.llsiarl L-nc ratt 24 Sh -Rid .? 30.48 cm Conti r2A Air Gq p Air 0.00122 wai ,Culad .025 cm frm - 7.86 tranplq; Methl ActuaI PaotwEnetpes SPc1e:MI CO-60 1.6 07t00 Q 647t M 4, .Qe-QO 1.65CGe-004z Susldup The MatedikI tefelence 19 : Cyl. COeM C .Intwatlm parwratav 20 2D Fhuitnco Fato - FUflumic pate  !*tpgjurg pste,

&r'Otorastsec .24Lirmt I*r .rthrt NMIt Bupda With Buddut 0,6%30 909,* 04 1-04l-1.3 2.00S1 Jf

3.9s5 7 -},1 1N4545~1c112

7.032e-1.3 19t 737 6074.-O0 3 934? .- I .18e-1.1 1.932S 6.074i00 1.J58e-1n ALS: 1 24:51 1I 175e¢09 E $6P]eD 2.945e 11 Cl-1 73

Plum Brook ReactorFacility FinalStatus Survey Plan 1,1 Revision 0

~

Plum~~~ ~ Bro.ecoFclt.ia Sau uvyPlnRvso Mi~i~hiI~ 5..4 (S.-04-O0362) 12119/05 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 Li-JUJI15.-ASUMMAd Qxu Pnjjrpipn -Ad "ioonFluenco Rotc (flux) Photon/cm~s~ec 9 219c'O10 1 279e.008 Pitoton Efwgy 1F1"c'e Rate .Mev/rn/sec 1-1 75e-009 I .62 1e*ODS

'E.xposri arid Dose Rotor

~Exposure Rate in Air mR/hr 2-059e*01 2 2,845e-01 1 Absorbed Dms Rate in Air rnGY/hk 1.79BeO014 2-483e-OI13 N

mrad/hr 1i78,-01 2 2,4 83c 011I Deop Dose Ecwivo nt Rato (ICRP 51

• 1%87) o Paafalel seorntry ryiSvlhr 2-04OWO014 2,81%,01,3 a Oppow'd N 1.758e-01 4 2 .428e-01 3 o Rotational 1.7$60 014 2 ,428e-01 3 a Isotrop>ic 1.571e-014 2.16ge*01 $

Sballpw Cose Equivalent Rate (ICRP 51 1987) 0 Parallel accnw-ry mSv/hr 2.72014 100le-01 3 o Opposea 2,091e-01 4 2.890e-Oi13 ORotational 2.091 -'0 14 2-$9c 01 3 L1,664e.O014 2..298e-,O 13 of ectQvpDp$q qil;On R (ICRP 51 .197) a AntenonrPostenor Geomnetry mS-,vhr 1,837s*014 2-53ge-0 13 a 1.693e.014 2..3-"e.01 3 o Lateral I .348e.014 1,860Ge013 o Ratalinart I .525e*O014. 2-106e*O 13 o hlaotropiC 1 .3509*0 14 1. 864e*0 13 Page I.

Cl-i 74

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Mlcro~hl~d 0.04 (5.04-00362)

Radiological Services. Inc.

Page :1 File Ref:

DOW rftk PB112213LIMSS RL 0 ftUM;P 23,40D5 BY:

Rvii rime, ; VA Ml Chocked:______

Durationm 0:00.-O-D 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 wurce Dlmemilsons Heigh~t 720cm 25 It 7.62 cmi 3-0 in Dose Points3 y

1. 1 13B.7B cm 4 ft &6 in 12ft 6.0 .n ft

%*?

'i ShKOds Cyl, Ccre 7 62 cm' Conci ret Shie~d I .65 ern ial>11i Trainsitioni Conc~ret,e 2,4 Shield 3 I30.48 cm c~onrirt e 2.4 Air tp Air 0,0O1 2z

.O025 cm Ironi 7.86 Source-Input Orupn Method :Actual Photon Ewnetiges curies hA~j~1% uQi rf'(

Ntplidrn I.SS31e.010 S.7464E4000 4,2,570e-0131 Cs. 137 1.6417c,'010 67044c-POG 4.5000e.0G9 I A565C'c-C0-4 9.zildup The material reference Is Cyl. Care Intug~ration Parameters VLirection (axial) 20 Circumlereritial 20 Results Actiit Expow-~re Rate rxi*u~re Ratso ph.~tns/sec M8V/rM,-VsSo Wdth aisll fa 0.0318 1.190e-01 8.090o-83 6,7684*35 6.739e.85 0.0322 2.1I 0e-01 2.278e*80 I1.298e.34 1,8l34c.82 1.044e. 36 0.0364 7.987c 02 4. W4 5EP! 2.63$e-64 4,10&~ 37 i1e 51l71e+00 1.200e4 I. 4 .374ue- 10 2.3269- 14 8.479e- 13 ClI-175

Plum Brook ReactorFacility , F FinalStatus Survey Plan Revision 0 Page 2 DOS File - PB122131.MS5 Run Dab,- Decomber 21 2005 Run TimeS 5S57,30 PM Duration ; OQ;QQ;Q1

,AraixiCr ElMUM Pad #uVflcRSate Fx>ture Rj;ja~ Exposure Rate, MS phntorsgsee Me#fctfr*Sec ,mntlhr MBohr No CUImdup Mtsh Seidd No IBu~jg.X p 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 ReactorFacility FinalStatus Survey Plan Revision 0 MicroShsied Y5.04 (5,0440036Z) 12/21/05 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 PfAt Dose Po~intiv I.- (1&81128cm Pesulks Murrmmd oyer eneczp- bIdAS )y-ith I Suilduj" Awoo-of Pho4*n/tmVs~c I XI 3101 1 6.6] 1s.010 ftctsoon'i tefgy Fluence Rate MBV/crW/sec I -200e-01 I 4.374e-010 Exp~surv arld Dose Rates-Ex~posure Rate in Air mR/hr 2.326e*0 14 8a47~je-013 Absorbed Dose Rat in Air rnGY/ft 2.O03e0.Q 1 7,403o.015 U

mrad/hr 2.030e.O014 7.40-3e*O013 Deep Orse Equ ivaelen Rite (ICRP 51. 1q87) ai Para~lel Geometry rmSv/hr 2.404e-01 6 8. 764e-Oi5 a

a~aOPPOeO 7tO1174c0J5 o Rotational U 1-925t-O16 7.01 7e-015 a isotropic a

1.702e-01 6 6.205frO1 5 MJallowi Cose EquiJfa lent Rate ICICRP 51 - 1987)

-- o Parallel Gqwm-ryt rn5v/hr 2.5 55e-01 6 9.315e-OJ3 5 U

a flppDoed A7cO1 6 A2 8,84 7e-01 5 o Rotationali 2A427e-01 6 8.84'7e-03 S a Isalcupec 1-Elge,316 61 S0-1 Eflertive Do:se~Equ~ivalent Roto (ICRP 51 - 1987) o Anterior/Pastffr G-etr'yet mSvfhr 7 .75W01 05 a

o poije'ior/Antervor 1487156-16 U.40e-01 5 o Lateral I '.41A-ft1A o Roa~taonat 1 .677e-t116 1.2 v-1 56204a-s-0 5 Page 1:

Cl-177

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MlcroShield Y5.04 (5.04-00362)

Radiological Services, Inc.

Page :1 File Ref; I D.S Fite PS122132MS~S RL ate: December 21, 2005 By:

P.lurr-Ame: 6:01:15 PMA Checked:

Duratign. Q;W0'Q~

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 ------

wurce Dimensions Heigrit 762.0 cm z5 ft Radius 3-0 in Does Paints z

gj 1 138-78 cm 381 cmn 182.8F, cm 4 ft6-5in 12 ft 6.0pn 6 ft Shields I I Densit.

Cyl. Cmr 7.62 cm' Concr ja L *

$hleld I Transition

.65 Cm IrQ, Concreti ?

7 85 2.4 Shield 3 3048 cm Goncreh 2.4 Air Ga p AiT Wal4 Bad .025 cm Ilror 7.86 Souwrce Input Groukping Method : Standard Indices.

Numiber of Groups -.25 Lower Energyr CktftA 015 PhQIgns < ,0Q ; xlui Library: Grove twrniLiP4L Eu-152 I1,641,74,010 6,0744e+00C 4.500Ce-.009 116850e-004 uildWp The material reference Is: Cyl. Core Iategratilon Parameters YDirection (axial) 20 Circumforential 20 Fitimail Rmto Exrnnsyro Rate 4iini, R-o. maLb with ByildyRx

)4 .3.594e+00 5.464e-50 Cl-1 78

PlumBrook ReactorFacility FinalStatus Survey Plan Revision 0 Page :2 VO$ File . PB1Ža132.rAS5 Ron Date; De'ember 21. 2005 rhun Time- 601A15 PM Duration 00:00:01 Acflyity 3luence Rate Exposure Rate Expoure Reate p h tonrt s se MeVfen tf;1gt nRhr

/MhROltipl Wt uitcun 0.05 8.987e-01 6.428e-35 4 164e-33 1,7129-37 1.109 35 0,1 1 .727e0+O .71e-l 7 4.535e-22 4. 352e*2D 0.2 4.552se -1 2,821e-16 4,453.-14 4.979e-19 7.858e. 17 0.3 !A42t+00 2. 1*6e-14 2.443e 1 2 4.07le 37 4.634e. 1 5 0.4 3.817e-01 3Z575e-14 2,794 12 6.965e-1 7 5,444e 15 3.426e.02 1.380e 4 7.55e.1 3 2.708e. 17 1.522e.15, 0.6 2.576c. 01 3,272e 13 1.388&1 1 65386el ' 6 2,710. 14 0.8 1.082et 7.865e-12 2.14le 10 1.49Ee-14 4.073e- 3 1.0 ;6.wt- II 1.343eQ9 1.2716-I3 2.476t, 1Z.

L.s 1.409e+00 3.350e.10 3.726e.09 5.636~e 13 6265e iz:

TOTA.L*; 1 ,40c+1 4,122e- 10 5,3038e09 7.065e 13 .190e}12 Cl - 79

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 I1lch~eid v5,04 (5.04-00362) 1211/05 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 Pboton, Flueriice Rate OWNix) Pho'tons/cm'/sec 3.02aefl1 0 4V1 5C 009

l. b*Aon E.t-eigy Fluerice Rate N1CVfkm7/!C; 4. 122e.OI10 5 .303e-009 Exposure and Dose Rates-Expqsure Rate In Air mR/hr 7.065e-01 3 9. 190e-0l12 Absorbed Dose Rato in Air rnGy/hr 6.17e-01 5 41-0230.14 n

mnrad/hr 6.167e-013 8-023e.01 2 Deep- Dose Equiva!ernt Rate (ICRP 51 1987) a Parariel Geornetry mSv/hr 6.997e.O015 g..124e-014~

OOpp',seo a 5.068e.0 15 7,570czQ14 o Rotational 6.068e-O 15 7.870e.014 O isalropic 5.432e-0 15 7.0 36e.0 14 Shalkow, Dose Equivalent Rates (ICRP 51 1987) a Nr8a lel Gecenetry mcv/hr 7.4 lge-01 S 0.6Se-014 Gopposed I 7.167c*O15 9. 342e.014 a Rotational 7.167e-016 9.342e.014 o15ctropi-C 5,7;0c.0 15 7.4-35Pr0.Q4 Effective Dose Equivalernt Rate (ICRP 51 1987) a Anterior/Postenor Geo~metry m$vl/hr 6.101eQ 15 8.209e 014 o Posterior/Anterior I 5.828e.0 15 7. 569e.014 a Lateral .4.68Oe,0 15 6.042e-O 14 a Rotatiorn,: 5.258e-O015 6.822c-014 OIsotroipic 4,074'10,1 6.044e*O014 Page I Cl-180

Plum Brook Reactor Facility FinalStatss Survey Plan Revision 0 141IcroSfileid vS.04 (S04-00362)

Radiological Services, Inc.

Page ;1 Fil* Rof_,

POP File PB122133-M& Date: _

RL att December 21, 2005 By; Run Time: 6:08:42 FM Cheed;:,

iDurativ, ; MO P;]

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__

Durce Dimensions "eight. 762.0 m 25 ft Ridius 7,62,cm 3.0 in Dose Points x x z

1. 1 138.78 cm 381 crri 152.88 cm 4 ft 6.6 in 12 ft 6.0 in Lit ShieIds Sh14,ipid Narna I limarM c as a LrA CYJ, Core 7,62 cm' Cenr; Tt e 1.8 Shield I .65 cm I tuF, /.86 i

Trafn-30,iorn C9.1unt c. Z4 Shield 3 30.48 cm ConcTet e 2.4 Air (ap Ai;r 0.0Ci22?

WaII Clad .025 cm Ircr 1.86 Source Input Groupirni Method: Standard Indke&

fumber of Groips: 25 Lowet Enetgy Cutoff 0 s Photons c 0.015: Ljcluded Library: Grove INawfire tcuimi 1Om=

Eu 154 1,641L I" l010 6,074.e+000 4.50OaoOC19 1,665t0-004 Buildup The material refroncc is: CyL Core integration Parameters Y Dircmron (tia!5 Ci rcurnterenitial 20 EnAtivit JJUCJrnrt RalO Fljrin M_RaF& agowre RIto M4Iat.-m 2t/~f M#Vkm t /*f~rpfz mR~hr ,Mpftr Nr, ffjildwo~ MMrtSUjI&,D flo 1301Jiggr 6th Ri8l8titu J4 1.236e+00 2.879i 50 M*57oe-J- 8.312e 53 6,886e-36 Cl-181

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 DOS Fite 'B:122133.MS15 Fvn Date: DNceimber 21, 2005 (butn tme: 6&08.42 PAA Duration: 0-0M.:01

. ntgen Wv.O ,Expolgr Ratet B2 &.6ldt= MyYt RitiCIL Wilth U11uila~

0.05 3.140-01 2.246e-35 I .455e-33 5 953e-38 3.876e-3G 0.1 2.45A8eO0 4.21ge-19 4.066e-17 6.455e-22 6.251e-20 0,2 4.148e.01 2,571e-16 4,058e 14 4,537t. 19 7.162c-17 0.4 4.334e-02. 4.059e-15 3172e-13 7.908e 18 6.181e-16 0.5 1.315c 02 2.977¢r13 0-04De 17 5.843( I 6 0.6 4-900e-01 6.223a. 13 2.64le-11 l21 5e 15 5.154.e14 0.8 2.369"O 1.723e-11 3.276e. 14 8.920e,13 1.0 1.869et00 4 957e 1 1 9.e57W 10 9l.35e.14 1.780c.12 1.5 2.370eFOO 5.6a5e.10 6,267e-D9 I.46le-13 1054e-11 TOTALS: I1.158e'e01 6.30 e-10 7.728e09 1-0 33*1Z2 1.327e. 11 Cl-182

Plum Brook ReactorFacility FinalStatus 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 F

Dose Point 1 - (13178 ,B 32lt. cm Fistyits nmed over energies>

-f 'ilithout Mb Ryld poton Flhente RatC (itawx) Photons/cmrlJsec 4.478e-0I 0 5. 7755009 Photon Energy FlUef e Rate MeV/fcm/sec 6.309L-010 7.728e.009 bEposure and Dose, Rates-poure Rate inAir mR/hr 1.073eO012 1,327cO 11 Absorbed Dose Rate in Air 9,371w 015 1.1618e-013 a

mradi/hr 9.371e.013 1.1 68e.0 1I Nep Dose LEuiv-jMen; Rate (ICRP 51 *1987) o Parallel Geometry rniv.f hr 1.062e.014 1.31Sn01I3 a appou-d N 9.237e.015 1.139e-013 o Rotational 9.237e-015 a Is0ilropic N LiaS~e 013 8.278*.01 5 1.020e.013 Shallow oDuse Equivalent Rate (ICRP 51 .19-7) o ParalIle G0erMRtry m~s/hr 1.125c,014 1 295e.013

-a (pposed a 1.088e-O14 1.347e-O]3 o Rotational I.Oa~e.014 I .34-7e013 a IfOiiOV14C 8,720e010 5 1 .076e-013 E~-tevo so>Equkvalon Rate (1lCRP 51 1sM7) a Anteroor/Posterior Geonmetry m.y/hr 9.5&01 5 1.184e-013 C' Poniei.'*n1ericr a

.866e -01 5 I .M94e-013 o Later-al 7.143e.O15 8.77c-01,4 o Rotational 8-002c.QO] 5 9.87 1e-014 o I'oEt-,p 7.125e-O35 S.765e- 0l 4 Page iL Cl-183

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 fAlcroShield v5.04 (5.04=00362)

Radiological Serviices, Inc.

Page I Fil-* Ref; tDOS Fite !P61I221 34.S5 Date:__ _

ML wtv; Dmcerbe 21,. 2005! Byd __

Rpui'Time:, 6:,04:26 PMA Checked:

Durativn ; QUOM;Q Case

Title:

Line 1.ii E Descriplion; Revie 994ofe Oaic Ag-1Oam Unit Act w Sch*d 40 & 12 ImShf-d Geotnetry: 10-~ Cylinder Sufface - Exiteirrial Dose Point TnI I Height Source Wfeiin 25 ft Rladius 7-62 cmr 3.0 in IDq Poinb

• 1 13818ec M z

381 cm 182.88 cm 4 ft6,6iin 12 t 6.0 in 15ft Sh~vIds DL+/-imgnao MA= 'I b~efr71tv 7.62 c~m' ~Donv 'L1 e 1.8

.65 cm Irat Ie ).86 Shield 3 I I3i0.448 cm Co~nc'eti e 2.4 Air ~~ap AP' 0.00122

• iV 1i 7.56 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(rilcmz1 Ag-106rm IM417 V91 §,Q?44v+QQ9 4,5QQQtg.?99 1 §65X04 134si1dup The mat~erial reference I:Cyl. Care Integra~tion ParameterE

-YDirection (nxiat) 20 Clrcumrfearential 20

. L %=A r fi ibi l u.r'n f R9I~ Resudts~

-ftio~nrARM't. rioosureRatR

)2 ,984e+O1Q 3.51le-269 B,557e*34 1.2 16e-27GJ 2.9649.35 Cl-184

Plum Brook ReactorFacility FinalStatus Survey Plan 'Revision0 Pagc :2 DO$ FlIe : P6122134,A$5 Rftn Date; -scamnber 2]. 2005 Run lime, 6:04:26 Pp Duration: 00:00:01

. W-d Activit lyenc* Ralte RuerPM Rate inhaloshoee mR/ ES urBetlY Nio BuildupD 0.03 1.29e406 6.693e- 100 6. 125e40 6,633. 102 6,070e-4Z 4.305ew01 2.930e, 22 1.6130e2O 4.637e-25 2.553t.23 0.4 5.46O*+00 5;113e-13 3,9%6e 11 9,9 1 .6 7.787e- 14 0.6 5.491e40D 6,975e2i? 2.9%SeI 10 1.3f1le 14-0.8 5.497e+QQ 3.997e-I 1 1.Qg80e9 7.63e-14 2.070t-1 ;

TQTAL3i 2,9mv1 4.746e. 11 1.424e 09 9,064e 14 2.726e- 12 C1-185

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 M~jCro*$h~e~d Y5.04 (5.04-00362). 12/2.1/05 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 Rgsults (Sumrnmed over en2Wgie) UD&~

Pti~ton Fluvrice Ratie (flux) Ptiotons/cmi/sec 6.287c'0 11 1.954e~009 ru'tton Ew~ey Fluence Rate MaeIcm?/56C 4.746e-0O1 1 1.424e*009 Exposure and Dose Rates-E~xpasure Rate In Air mR/hr 9.064e-0 14 2. 726e,012 Absorbed Dose Rate in Air may/hr 7.913c.016 2.380e.0 14 mrad/lir 7.913e.014 2.380e-012 Deep Dose Eq~uimaert' Rate IVC-RP 51 . 1487) a P~arallel Geoffetry m$Vlhr 9.263e.016 2. 7940-14 U

o Opposcd 7.552e-016 2.268e 014 o Rotational 7.552e-016 2,268cQ014 q l5101fopic 6.676e.016 2.005e-014 Shikkow' Dqsc !quivvIornt Rwto (ICRP 51 1987) a Para.leI Genietry m~v/hr 9.890e*016 2.979e-014 oGposed U 9I426e.O 16 2.837e*014 o Rotationa' 9.426e-016 2.83 ?e-O14 o lsoTtOPii 7,144co016 2. 145e.014 IJCRP 51. 1987) a Antertor/Posterior Geor"itry mSv/hr 81236e,~01 6 2.481c.014 n Pn%1ft1k:.n/Ajter~or I 7 .347e.016 2.208e*014 o Lateral 5 .537f.O1 6 1.659e 014 o Rotatuonw~ 6.573e.O3 6 1.976ec-014 o lsc1ropic 5 ,637tO 6 1.691v-014 Page 1 Cl-186

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 NIIcroShleld Y5.04 (5.0-00362)

Radiological Services4 Inc.

Page :1I File Ref_

DE0$ File -,P8122135-US5 RL ate. Dcernber 22.,)

RuTh fi,'me: 6:D6:00 P14 Checked:

Duration : 00;OU:Oi Case Title; Line 1.1r De~rpso'ioo Rewised Mo~del b Ik -~4iMt kt w Sched 40 & 12 in Shid Geomnetry., 10 - Cytinder Surface. Exutrnal Dose Poir iuroe Dimensbons Heie*wt 762.0 cmn 25 ft ftdius 3.0 in Dose Points x I I Olb1a.7 tir 112.88 Cm 22 " U in 6i Shields z

7.62 ~~m Concr ret

.63 crn Waro I1 4

Tromiitr C'nmue",I1v 2A4 S hield 3 3048 ram Ccwrcret e 2.4 Air' Gap O'X1122 WallI cVlad 0-25 cm Air 025-cm ron 7.&

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 20

~

Orcumloc.-itia' 20 Activity r luence Rate' UnrtoLsurr ROP ,

0.0174 2.148c-03 0000e400 3. 704w 37 0.000e+DXO D.0175 4.li5e-03 13.000e*OO 7,163e-3,7 0,Ooae+00 3.79.3e-38&

0.0196 1.209e-03 4.07Re 28B 2.516e-37 1.503e-289 0 7026 6.074e#00 2.031ei 1 6,748c JO0 3.417ce14 Ili 6,0744e+00 7.282e, 1 1.743e.09 1.37le*L3 3,291e*1p2 CI-187

Jactlily Final Status Survey Plan Revision 0 Plum ffrook Reactor Plum Brook AleactorP acility FinalStatus 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 Activity RiunseriRat iluence FRate NIP.Y nhuoton/s ,Mm,/sett mRlhr mRahr No SuIduR ^With Su~itduo TOQTAL; l,2101:'Q 9,3140-11 2A418B-09 L.762e413 4,582e1 2 Cl-188

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Fmicwrohhed v5.04 (5,04-C362) 22/21/05 UIflcroShIild v5.04 (5.04-01362)

Radioloagkal Services, Inc.

CommesOon 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 gait5 Summed ovr mnerg-ej Units Withm PhNoton Flueigy FRte Rax) Photons/cmr sec 1 .125.-014 2-.962e-OO!

P~tan Ernfg Fluence Rate! Me.V/Cm*/SeC 9.314-01 1 2,418e-00,9 Exposurm and Dose Rate-Exposure Rate In Air mFfhr 1.752c 013 4,582e-012 Absorbed Dose Rate in Air mGy/hr i.538e4015 4OOOe.014 U rmra-/hr 1,$o5f(13 4.OOOc.012 Deep DOse Equivaent Rate (ICRP 51 1987) o Parallel Geowetry mSv/hr  !.JlS0?015 4.655e.01A4 n {OppoSe.C a 1.47e415 3.83le-014 o Rotational 1.474evO15 383le-O14 1.304e-015 313We014.

Shavlvo Dose Equiwi,!Ont ROtO (fCRP 51

• 1987) a Parallel Geometry mSv/hr 1 .9136-015 4.977e.014 c Oppcsed 1 825e"S5 4.749e4014 o Rotational 1825e-015 4.749e*O14 O 1sotfopi

• 1.39seO015 3.625ei014 Eflective Dose Equivalent Ralte (ICRP 51 1987) u AnterforiPostetior Gewr-try mSy/hr 1.595e015 4.149e-014 o Posterior/Anterior .

l43le-O15 3.721.Q014 f LaLteral 1 .890-015 2.826e 014 o RDtat-'.onav 1.282e-C 15 3.331e1tg14 fp fidlimfle 1L1058415 2.86e*014 Page 1 Cl-189

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Mi lcroShield v5.04 (5.04.00362)

RadiolOgical Serices, Inc.

Pape :1I Fjil ROf' _ __ _ _ _

DO-- File PBI.22925.14S5 Date:______

RL.- ate: Coaftr 2%9 2CO5 BlY, Duratiarw WQOQO;Q1 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 owrce Dnirensions Height 762.0 cm 25 ft Radius 7.62 cm 3,0 in A:

X z

N 13&-78 cm 381 cm 182.8I8 cm 4 it 6.6 in 12 ft&O0 n G ft Shields 7.62 cm' ConvJratte 1.8

Shield I .65 cm Ira n 7.86

'I.

Tronsilion Concrt t 2.4

.shield 3 30.48cm Comcvet e 2.4 Air Gap Air 0,X1 H2 Wall~Clad .02 5 cm Iron 7.86 Source Inuput Caroutping Atethod : Actual Photon Energlei hn;& becouprels Orn 1-1.29 1.6417ae0]0 6.0744e*150 4.5000le-009 1 .6650e-004 Buildup The material reference Is Cyl. Core Intetratlon Parameters Y Direction f axial) 20 Ci~rcurnfarertial a0 Re sults II Eney 4E.ooste~1002 5- 72'3"~6 0.0295 1.212e+00 3.9 14e-98 Si468e..34 2.249e+00 2.4470*95 1.046e.33 2.479e-97 1.05ge-35 i 7.99e*-01 1 .708e,72 5,460c-~34 1,215e, 74-o 'n396 4.568.O I 6.56.5e.52 5.650e344 2.98 3e-54 2,522e-36 Cl-190

Plum Brook ReactorFacility FinalStatus Survey Plan -Revision 0 Page .2 DOS File; PS122925,MS5 Run Date e December 2E. 2005 Run Time: -3 .Q2PM Durition 00O-OO01

-.zkt Attnrity Fluont* PAg IFlen* We Eounre BLbr.

e photon V69m.c.

~ 2ME111L enrR/hf

'o Swildg With Bidp No Igildlu W2th R22iff.

TOTAL$; 4.718e*0 f 565e-52 2c,6934e33 2.983C 54 22,72e.3F5 Cl -191

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MilefoShield v5.0A (5.04-00,362) 12/29/01 MicroShidd w5.04 (5.044M362)

Radoloogical Servim, Inc.

Comcrsion of Wccklallcd expos~ure Inair 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 m c~~1L Ugsults (Suminrd ovier enen&4 e- illr Mhbnu+/-iA Phioton Fluerice Rate (flux) Phaotms/cm'/we 1.65ge-G5O' 8395t,032 "tOton Erbergy Fhence Rate .6-56.4Q2 2,694e-03.3 Exposure and Dose Rates:

Exposure&Rate in Air mR/hr 2-9aae-0.4 2.272e-03$

Abwrbtd I

Me Rate in Air Mn~ylhr 2. 6O50G0O 1.984.-037 rnrad/hr 2.GO05e-054 I .984e-035 O'vap Doz Equivalent Rate (ICRP 51 1987) o Parallel Geometry mSv/hr 3,7 28e.056 2.27le-03T a Opposcd 1.878e-0O% 11A3ge.O37 o Rotational 1.70i~5 9.71 7e-O39 1,62,6e56 9.025e-039 S~l~aIw Dose Ecu-i'alent Rate (ICRP 51 - 1987) o Pafallel Geomnetry mSv/hr 3.751 eG056 2,4 75e-037 o Opposocd I 2.589e*056 1.7O2e4037 a Rotatt-onall 2. 589e.056 1.702 0?37' a lsoterm2p I,900e.056 1 .25Be-037 (ICRP 51 1987) o Anterior/Posterior Geowr~try mSv/hr 2.174e,056 1,01 So.037-oP'osterior/Antenrta U 1.3 14e*056 5.264e-038.

a Lateoral 7.2590.51 2,84lvo03&

o Rotational 1.1 82e*056 5.2-31"-38.

olsotroprpc 9.685e.057 4.3343ti o2-W Page 1.

C1-192

Plum Brook ReactorFacility . FinalStatus Survey Plan Revision 0 NicroShleld 15.04 5.04.00362)

Radiological Services5 Inc.

Pap :1 File Rer: __ _ _ _ _

IOS File : PB010407,MS5 Date: _

F. ate; J.Anurny 4-, 2W By:,

RuerIime! 8 S.821 1 AM Cheche>d; Duratien : 00:00:01 Case

Title:

Line 1.81 H DescTirptla: R¢vised M0Ie Cate. Sn-126 Unit Act w $5Ch*d40 & 12 in Shid Geometrty 10 - CylInder SurfaCe - External Dose Point uwrce Dimenisions I leight 762.0 cm 25 lt Raius 7.62 cm 3.0 in DPoe PsintL N1 138,l8cm 381 cm 182.B cmn 4 tt 6.6 in 12 ft . in 6 Ft Shields Dri 7.62 cm' Conc ret B 1.8 Shield 1 .65 cm Iron1 7,86 Transit'on Concret e 2.4 Shield 3 30-.48 cm Conrfet e 2.4 Air Gaop Ai- 0,00122 wely il ,QZ5 Cm lrwn 7.,

Source Input Grouping Method Standard Indlces Numrbeiof Groups: 25 Lower Energy Cuttol . 0Si

'Photans D.015 ; Excluded Library GrwYe I 6e.rninre0744 0 40; r0m2. 1O-m5 Sn-126 1 6417e '010 6.0744"00 4.53C380OC C9 1.6650e-00 BOuldup The material referec Is : CyL Core Integration Parameters Y Direction (axial) 20 Circumferentiat 20 Ene fEgsyre Rate 4hn70et MAV~eltcmte M,-V--nlsf 5e YI~ougiy With Bu N<.5e.Oildt71 With kRuildilrn I-_.

4.7 02e.0 1 4.143e 270 - 1.010e34 I .Q35e271 3,498e 36 Cl-193

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page ;2 DOSXfl* : P8010407.ASS Run Date: January 4, 2OOj Ran Time! 8:1$r21 AM Duration : 0 -0:01 Acti flutence Rate Fiuerice Rat-e Exs osu re RFat Exwesure Rate 003 W.V/,rrtf ieete ,rj~hr.

U0 LDiwv With Buildup 140 Buildup MSh.

1,7794+100 9.22ge-94 &.4469e34 9.147e.96 8.371 e.36 OMe 0.04 3.034e-02 4.613e-52 3,821c 35 2.040e954 1,690c37 0.060 5,82le401 4.7ge-28 1.4 10e-26 2.801 e29 0.0$ 2.789e*00 1.899e-21 1.045e*19 1001e 24 1.654e-22 TOTALS: 5.650e*00 1.899e-21 1 045e-19 3.UOSeF24 I 654e 22 Cl-194

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicrAideld vb.4 (5.4." 62) 01104/06 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

§4.cg1I ijmr~rA ,w pr gnewiw 1Wi-thout Bu~idup Photon Itnuence Rate fOUC5) Pot4ns/orr?/%vsc 2. 373e-D2O 1.307e-018 Photon Enefgy FRuence Rate Me/Wemk/sec l899e02 1 3 ,045c-03 9 r'xrxmure ad Dose Ratesr Exposure Rate in Air mR/hr 3.005e-024 1.654e-022 Absorbed Dosc Rate in Air mcy/hr 1.444e-024 W

mrad/hr 2.623e.024 1 444e-O22 aop Dosc EPq'vva'nt Rato (ICRP 51 1987) o Parallel Gmeometry m~vfhr 4. 5S8e 26 2-52fie-024 a fOppnsfn'C 2,444g-26 I 345e-02 4 o Rotational 2. 375e-026 i 3O8e-024 O IsottapleC 2358&0(26 I .298e-024 Sha[fow Dose Equivalent Rate (ICRP 51 *1q87) o Parallkd Gieorpltry m!5/hr 4.545e=O&6 2. 502e-024 a Opposed 3.341e.026 1 ,839o 024 o Robatiottrl 3.34le-026 1.839e424 o Isatrop.c 2.452e*026 1.350e024 Effective xDse rq"4Vae'?io paic- f,.,CIP 51

• 107) a Anterior/Posterior Gerometry mSy/hr 3,853e.026 2.12 le-024 (i Pewilr/Arnterirjr U 2.939ef026 1.61 O04 o Lateraw 1 .B1I e.026 9-72e.025 o Rotational 2.$03:3e602p .378e.024 n lsotroptf 2.025e-026 11 Me.O24 Page 1 Cl-195

Plum Brook Reactor Facility FinalStatus Survey Plan . Revision 0 blicrotlield wS.114 (5.04-00362)

Radilogi~cal Services, Inc.

Vito~R ef; Page ~I _ _ _ _ _ _

DC$ Fije EPB122927JOM55

• Date:______

Ri. atet Decen-ber 29, 2C05 Run-Time! 3:-3!53 PM Chected;',

Duration, : 00:';00:0]

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 'ce Dimensions Heighit 762.0 cm 25 1t Radius 7.62 cm

)Ole Points

~1 138.78ecm z

3S1 cm 1S2.88 tM 4 ft6.6 in 12 It 6.0 in 6 ft Shields

~anrbmn M2&t~jP1 Cyl Caore 152 cml Concreke Shield I .65 cm Io Transili itnn Congrcte 2,4 Shield 3 30,481cm Concrete 2A Air (Cap AIr O.0022 Wall Ciao .025 cm lroo 7116 Sourice Input Grouping hMethod : Actual PhDton Energies 1Bo/cm'KI Zr-95 1.64174.010 -6,0744-e+000 4MO5e000'O9 The mater'IaJ refreme Is Cyl. Care 1ntegration Parameters 2D 20 Resuhts Enejg AStijjtv Eluenc Ratt Fluenco -Rate Eix~osure RM~

M2V/CM'fsetc Me0Vkm"/1eq MR/br MO24 pho.6 s/2e40 Ads-h RI ll1diai il.064e-1 I 3..374e-10 2.046e- 14 6,45.. 12 0.7567 3.3&2o-00 1 1 J56O 5205*'1Q 9.9620 Ls TATALS: 6.0 14e*00 2.B2Oe*1 1 8.579e-10 5.407e* 14 1.6415e 12 C1-196

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Wlcr*$iged v5.04 (5..04-00362) 12/29l05 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 Re&AW5 d, I- - Ivelnries) USit1 Without Efih Photrins/crn'/sec 339OL-01 1 1.1 54e0O" Photon Energy Fluence, Rate MOV/cm 2/Sec 2.B20e01l 1 8..579e-0100 Exposure and Dose Ratesw j~pfsure, Rate in Air mR/hr 5.407e-01 4 1-64ge-012 Abs.orbed Dose Rate in Air mrGy/hr 4,721.-016 1.436e-014 M

mrad/hr 4.721 e-01 4 1.436e-012 OmDst Equwviont Rate (ICRP 51 - 1987) eo Parallel Geometry mSv/hr 5.534e.O16 .1.693e.01 4 io Opposed 4 .500e*016 1.369e-014 maRotational 4.$OWL-016 I .3690oO1S I

3,978o.0 16 1.210e*014 Shallow Do~se Equivalent Rater io Parallel Gm4-rtry mSv/hr 5 .9g8*.0j16 I .797o*014 o, CJOposeed U 5,630e.0 16 1.713e*014 io Rotational 5-630e.016 1,713*.014 la kpolropic 4~257e.Q16 L 295e-014 Effociiva Dose Eqiuiv~alcrt Rate (ICRP 51 .1q87)

• Anterior./Posterior Geometry m~vhr 4.91$ e016 1 .495e.014 P3Ploseriao-/Anlerlar U 4.37geQ016 32333-t,014 Aa La'ter-W 3.292e036 1-001e-014 o)Rotational 3.916e-016 1-l91e.014 10 lsafrop" 3.354e,016 I 0,20ffQ04 Page 1 C1-197

Plum Brook ReactorFacility I FinalStatus Survey Plan Revision 00 Final Status Survey Plan Revision Plum Brook Reactor Facility MicroShield w5..04 (S..04-00362)

Rad~oio~call Services, Inc.

Page 1I Fii Ref; __ _ _ _ _

DOS File PB122928.&MS Date:__ _ _ _ _ _

RL te: December 29,3 5 BY: _ __ _ _

Rua Time: 3:35:35 PM Chook.edi _ _ _ _ _

. Duration : 00:00:01 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

)urce Duimensions Ilcigeht 762.0 cm 25 ft Radius 762 cm 3.0 in 1hliQ' Polfli

1. 1 13a.78 cr 381 crn z

182.8a cmr 4 ft 6.6 in 12 ft 5.0 in Shields LOName I Uria CyA >teo 7.62 cm' Cowc- ,et to 1.8-Shield I .65 cm Ira~ 7.86 4.

TratnitLin e 2.4 Shield 3 30-48 -cm Ccncret e 2.4 Air Gap Air 0.00122 War! Clad ,025 v-rrx Iran 7.86 Source trppta Grou.ping Method -Standard laidces~

Number of Groups r.25 Low'er Emurg Outoffi 0.01$

~Photons '0.15 : Excluded Library: Gircwe

,Wnriida =64 Eu- 155 1.6417i--010 6.074 4e+000 4.50C02e-0O9 1.6650E-DO.1 The material reference Is : Cyl. Core

.Integrat;Dn Parameters; Y Direction (axial) 20

'Circumicrential 20 Flijnn &P1 fltience. Rait, Er~2ur#m Rate 2elmle O03 1i9~3c02 9.1B10-36 9.943e.98 Cl-198

PlumBrook ReactorFacility FinalStatus Survey Plan Revision 0 Pag :2 DOS File - PEI22928.MSS Run Date: Dscember 29, 2005 Run Time 3:35635 PM, Durltion : 0-0001 Activitc Fluence Rate Fluence Ratp- FwsturrFt M.^.VknWrn'Js mRfhr ,m~hr WthbQilgUd No Suildunl With R iljfllP 0.04 LIOle+tC 1.674e-50 1.387e-33 7,403c.53 6. J M 3-5$10 01 2.561 e 36 I .esae$3 6.824e 38 4.421 e 36 0.06 7,878es02 6.467e-29 1 99e-27 1.285e-3 1 3,791 e-30

1. 3it+S0 1.-24e-21 7.068e.20 ZO12e; 24 .1.1 19eI22 0.1 1 25&e+C0 2.155e-19 Z.037e-17 3.297e 22 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 ReactorFacility FinalStatusSurveyPlan Revision 0 MicroSibleld Y5.0.4 (S.04-00362) 12129105 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 431S28 c L'Uslts (Summed over eI1e5rfij; Uanit Without Photon Fluence Rato (flim) N~iotans/Co1/Se~c 2.171 e.011 2.096e*016 Phoiton Energy Flueime Rate MeV/cm tl/sec 2. 168eO 19 2 ,D94-o-017 EZxposure and Dose Rates-Exposure Rate in Ai, mR/hr 3.3 18e.022 3..204e-020 Absorbed Dose Rate in Air mGy/hr 2.a~6e,024 n

rmrad/hr 2.896e.022 2-79,8e-02r0 Ocep Dowse Equiv*lunt Rate!

o Parallel Geomretry rnSv/hr 4.$42e!-Q24 4 6769-02Z a Ugpped 2.655e.024 2.564e-022a o Rotational 2.654e-024 2-564-e,02 2 o l$ottopic 2,481 e-022 S!mlkow Dose Equivalent Rate CICPP 51 .1q87)

'OParallel Glometry m~yfhr 4.81 O-024 4,4m022 inOppo"ec' 3.731e.024 3.604e-022.

so Rotational 3.731e-024 3.604ec 022 IU10vp 2.71 7*024 2Z24e-022 Etfectiv'e Dose Equivalent Rate (IGRP 51- 1q87) a Anter~cir;/Poslerior Geom, try.- m-5v/hr 4.162e*024 4A3 9e-0:22 o PosteriWrAnterior K :3.263cO;Z4 3.1 52e.022 a Lateral 2,014e.024 I1.945e.022 o Rottikinal 2.787e 024 2-69-c2v2 ci Isotrop~t 2,217e.024 2.1 42e.022 Page I Cl-200

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-00362~

Radiological Services, Inc.

Page. :I ric Ref;_____

I of Flit P8i21919.MS5 ZDate:__ _ _ _ _

Rt ate.- Decembe~r 19%2005 Rvu n"time: 2::4 M Cheocfied;__ _ _ _ _

Duration ;0G00M.01 Cast TRWle Line 1.82 A2

Description:

Revtised Model Oakc. -Co.60 Wit Att wSched 4-0 & 12 in Shfd G-eometry: 10 - Cylinder Surface - Extefial base Point Sour ce Dimensions Height 762.0 cm 25 fL Radius 3.81 cm I 5 in Dsse Point Z,

~1 134.97 cm 381 cm 137.16 cmi 4 ft 5-1 in 12 ft 6.0 in 4it 6.0 in Shields j DcnMO

,1 cm2 Cow fre:0A Shield I 65 cm Iroor 7.f8b Transwitioni Goncret v 2 4 Shield 3 30 48 cm Concrell)92 Air Gatp 0.00122 Wall Cad . 25can I= 7.86 source Input Grwuping Method : Actual Photon Enwp~es 2=1 b~gass Oilm~ 1.&QC-M 8,2067011 3tQ72,v+QQQ 4MMQO0~ 9 Buildup

'The materlal releience Is: CyL. Core Integralion Parameters YDirection (axial) 20 Ci rcumfuruwtial 20 Results Flupance Rate Eypos-ure Rittk With Rujildupw ct.69398 4.954e-O4 1,.479e.14 .3.875e-Z3 2.856e- 17 7,482.. 16 1,1732 3.037e;013 I 605e.os 23110e*12 Ž.869t0*1 1 1.3325 2-$c09 7_478PO~B 4.299e 11

.'ALS: 6.075e*00 3.646co09 4,083.08 6.1393 12 7,167o 11 Cl-201

Plum Brook ReactorFacility . FinalStatus Survey Plan Revision 0 M'.creo$ie4,0v~4 (1-04-00362) 12I19/m 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 ,2005al 2:26:48 P-M S=,JA4t9I 3 PHr nr a=Wgc Ph~oton Flut*,e Rate Ctfux) PhotDns,/cm1Vsec 2.868e*009 Pliolon Eswzy Fitdence Rate 1AWCkmI/Se 3,64,69-OD9 4-063e-00a Exposure and Dose Rates:

xpioswr~. Rate in 'i mnR/hr 6.1303eQ]2 7,J67c 01Il Absorbed Doso Rate in Air mG&Th4 5.581le.014 6.257e-01 3 mfrad/hr S'81 e3OJ U.57c 01 1 Deep Do'se Equivwdent Rate (ICRP 51 1987) o Paral lel Geome~try rnSYvhr 6.335e-01 4 7. 104e-01 3:

o Dppov.-o S.458e-01 4 oRotational 5 .450c ,01 4 6.11se-01S oIlsct7opic. 4-.876e-01 4 Shallow Dose Equwvaent Rate (ICRP 51

• 1987) o ParatleI Goomets-y nSW/hr 6.743e-01 4 7.563e-0113 ciOppos~ed 6-493e-DI4 o Rotatonal 6 4930-014 7..28le-013 5-A65e.014 5.790e 013 (ICRP 51 1987) o Ar~ten or/Posterior Geoiretry mSvlhr 5. 705Le.014 6,397c.0 13 o Pos~eriar/Anterior 5,256e.O 14 5.892e.0 13 a Liatecral 4. 182e.014 4.6&6e-O 13 oRotatiOnal 5.30Ge-0 13 o strp 9 4. l33e.014 4.695e*O1 3 Page I Cl-202

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 filicroShlded v5.04 (5.04-00362)

Radiological Setwlees., Inc.

Page. :1 File Ref:______

DOE- File :Pal.22136MSS 'Date:______

Ru ate.-De.cwmber 212005 By.,

.Rwi-riew 6,22:30 PM Check~ed: ______

Duratign zQiQ;Q;Q1 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

- 9 . .. 2 91 Height 762.0 cmn 25 it Radio- 3,81 cm 1.5 in Close Points y z i81 cmr 137.16 cm 12 ft 6.D in 4 ft6.0in 4 ft 51 in

'. I Wehlds CYl. Core . 31 cm' Conc. ret*e 1.8 Shield 1 .64 cm Ire 7.8E6 I Concret te Zi4 Shield 3 30.48 cm C-oncret e 2.4 Awr Gap Al~ 0.0012?

'Nall Claid t0125 m~ I rcr 7.86 Source Input Groupings Method : Actuai Pboton Eneties 1937m 7..7654e.011. 2.9732e+OWY 4.2570e.00g Csa-137 8.2087o.01 1 3.0372e4000 4.50O0e.009 1.6650e-004-Bui idup The material reference is : Cyl, Core I1tegration Parameters Y Direction (axial) 20 Circumferential 20 Rerrull.b A41IR4J MJV/rM2/qCAr 0.0318 5.948e402 3.402e- 73 4,329e-35 2-83-te75 3.606e.37 0.0322 1.0§7e-01 4.917e-71 8.299e-:45 3,9578.73 6.679e-37 o 0364 -3.994C-*02 4.625.e 35 1.898e 57 2-6Nt, 37 516 2.585elkO& 3,40 1 1,1Me-13 3.262e*12 C1-203

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 PPc 2 DOS File: P8122136.MS5 Run C>X. December 21H200$

Run Time. &.22-D3 PM burntion 00:00.01 Ahiv-t EulLI Fluenrw Rate Exxs;urg Rate ExMlure Pete ohlanq/gene rhtl mR/hr Nt.Vkrri'I4 With PLu,,ffiL0 With E3t~ifigi S. e 1. I TOOTAL5 2,794e+0 16£3e-09 l1.62e-13 3.262e*12 Cl-204

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 12/a1/ng 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 Re.gv2Zts ~&imme~d over energiel> Igpii Without With 130fdup Phoon Fl.r~e~ R$e NOux Phatons/Crnk/sec 9.OS94*,031 Z.54,3e,009 Pboton Enetgy Fluencee Rate MeWvrrw/sec 5.994e-OI 1 1.683e*009 Expo'sure and Dose Pgtov Exposure Rate In Air mRfh~r I.,162e-0,13 3.262e.O012

.Absorbed Dose Rate in Air mc~ylhr I.014e-015 2.8$eo014 I r.nrad/h r I 0O24e.013 2.848s.O012

[Clep Uost Eqvivolerft We (ICRP 51 *1987) o Paral lel Geom~etry m$v'hr 1.20le-015 3.7ZeQ 14 iaOpoe I 94169,016 2,699e.OI4 o Rotational 9.6 l&e-016 2.69ge-014 ro ISOeOPAe 8,503CO16~ 2387e-014 S~a ll-cei Dose Equ~valent Rate (ICRP 51 *1987) ioParal lel Geom-stry mSv/hr 1.277eZ15 .3.6830e-014 tj Opposed 1,212e-015 3 .404-.014 0oRcotational Il 1.212e-DI5 3.404e-014 o Isolo 9.090e:016 2 ,552e-014 Effective Do-so Equivailvnt Rate (ICRP 51 *1987) o Anterior/Posterior Geom-etry mnlfhr 1.062e-01 5 2.98 le-Ol14 o PosteflarlAnterior H 9.374e*0 16 2.6310,01 4 o LateralI U 6.951e*Q16 1~951e-OJ14 oD Rotational 8.377e-0 16 2..35-2e-0214 o lI~otropfa 7.132e*O1K Z.QMv-Q14 Page I Cl-205

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield v5.04 (5.04-flO362)

Radiological Servlces1 Inc.

File Ref; IDOS File -.P8122137-MS Date:

By; Ruui Time: 6.25:23 PrM Cheghd_

Case Tite; Line 1L82 C ftcsription: RevIsed M~OOe Csk- W.162 O)il MA wSche4 40 &12 Inshln Geometry: 10 - Cylinder Surface - External Dose Point

-x I Heig*&

wurce Dimensions 762.0 cm 25 ft Radius 3.81 cm ] 5 in 41 134.97 cm 381 cm 137.16 cm 4 ft iln 12 ft 6.0 in 4ft6.0 in Shields

)iFrr iOn ga+:rriaLI nan-.ily shield IAP 3,81 cm' ons ret e 1.9

.65 cm lro 7.86 4

Shield 3.  :£ 2.4 30G48 cm CoenEtie 2.4 Air Gap Ait o.o012 Wal I -vlpd .025 cm Irqo, 7.86 SOUrMt Input GroupingMethod Standard Indices

&bro roups -25 Lowe: Erwgy Cutoff : 0.01 Photons 4 0.015 : [Exluded Library :drv Ny'lide vw Eu-152 8,2087e- 011 3,0372e+000 4,5000e~C( '9 1.6650e-004 Buildup The material reference Is:.Cyl. Care Integrabwi Pvuaneter;, .

YDirectionl (axial) 20 Ci'-curnlretntial 20 Flutepmrr P~atr wV.r~5e P33 34 11.?97etOQ 1,690e-44 7.474.47 ~.28Os35 Cl-206

Plum Brook ReactorFacility' FinalStatus Survey Plan Revision 0 Paze ;2 He PB122137.MSS Fir Ron Date: December 21, 2005 Run rime 6 2S:23 PM Dur.:tign ; M-00-.01 Energy Arivi PRui-0

.Fhspnrp FlieInr R;eim a~y hns ,Rn/ehr t"4Rlhr With Buildug 0.05 4.49,3e.01 1.845e31 1 868ae.3 4.916e -34 4.977e 33 0.1 8,635c,01 1.066e-l7 & .iSe-16 1.247e-1f 0.a 2,276e-01 3.876e I5 4.42e- 13 6.842e- 18 7.802e1316

0. ~ 8.212e 01 2.035e- 3 1.613 1.11 3.86,16 3,192e-14 0,4 1 .909001 2.66le-13 1.536e*1 1 5.184e. 16 2.993e 14 0.5 1.713e.02 S.573e J4 3.61 7e- IZ 1.6834e 16 7.10ee15 0.6 II.MBe-01 1.762o.12 .l7O5e.1 1 3,44- 15 1.1 14e-13 0.8 5MA08m01 3.405e-I 1 7.258e-10 6.477e.1 4 1.380e12 1.300e+00 3,9220q09 4,75e 13 7,230c, 12 1.5 7 .I046.Qw 1.570e-12 1.430e-11 TOTALS: 7.040e+00 1.223*,. 1.324e-08 2,106e6 12 2.30ge-1 1 Cl-207

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 MkIo~hieId v5.C4 (5~04.O03&2i> )212VI0 MkrgShield v5.04 (5,04-0036Z Radfolloglea Sezvlces1 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 6_=ltII1; (I;v iTq4 e-wpr gnpV,:pr6%

Ph~or, Flutace Rae ('1ou) Phortons/cm2 /sc~ 9..226.e.010 1.00e.00a P'tiotn Energy Fluenc~e Rate MeV/rcrn/tec 1.22Z3e0U9 1,324e.008

,Eicpaoure anid Dose Rates Ex*posure Rate in Air imR/hr 2106it 012 2.3~e*0 1]

Absorbed Dose Rate in Air mGy/hr 1.139'e-0.4 U

I189390 012 2.016e.0 II Necp Dos;e Equivagnt RODi (ICRP 51 . 1987)

Or Paralle Geo~metry mivhr 2.08ge-014 2.256CQ 13 X

ai Opposed 1 1307e-014 .1.974e-013 a Rotational 1£070-01 4 1,974,013 a F$ct~ropic 1.6174, 014 1.764e*013 Shallow Dose Equivalent Rate (ICRP 51 . 1987) a Parallel Geometry m5Vhr 2.216e.O014 2.4$9c.133 II.

4opposed 2.1ne-o014 2,350e.O013 o Rotational 2.13ge.014 2.350e.O 13 4 I*Pltropi 1.707t.0 14

'Effertive Dose Equivalent Pate a Anterior/Posteifiot Gearnwtvy mSv/hr 1.880e-014 2.0fl65e-013 a Posterior/Akrtrior 1.737c-014 1.900e-013 a LateralI 1.391e-014 I.512e-013 o Rotational 1.566e-014 1.712e' 013 a Isotropic 1.390e-014 1.514e-013 Page 1 Cl-208

Plum Brook ReactorFacility , . FinalStatus Survey Plan .Revision Rvison 0 .

Ractr Fciliy PlumBrok FnalStaus urve Pln MicroShi~eld Y5..04 (5.04-00362)

Radiological Services,4 Inc.

Page :1 File Ref; DOS Fjle ; PB12213VNMS Date:

RL a>e: tDecember 21, 2o05 By:

R iftime: 6:-26.:42 PM Checked:

Duration : 00;00:01 Case

Title:

Line 1.82 D DescriptIion: Rteimd Modet Calic. Eu-154 Unit Act w Sched 40 & 12 in Sh~ld

_____ GeomwctY: Cyltinder Surfce - External DOm Point ource Dinuensions Height 762.0 cm 25 ft Radiu& 3.81 cm 1,5 in Dose Points z

1 134.97 er 381 cm 137.16 cm 4 ft 5.1 iii 12 tt.Qin 4 ,Qin Sh'uolds llirwnc-i~nn X a, P Cyl. Cors .,81 cm' Cono ret te lie-Shield I .65 cm Ir&n 7.86 Tronsition Goncret o 2.4 Shield 3 ao4 Cm C*Mcve e 2.A Air GbP Air 0.00122 Wall Clad .025 cm lros 7.86 S-uarcec Input Grouping Rtethod

• Standard Irdidces.

Numbsr of Groups -25 Lower Energy Cutofft 005 Photons c 0.015 -EUduded 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) 20 Circumfereatial 20 Rosulls; EnroeY IWit4, Poikjutg 5.181s.01 5.61,3&.45 99Ue-34 2.571la.47 4,404e*36 C1-209

Plum Brook Reactor Facility FinalStatus 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 Fhunrear Rake MtYt mobviemill* wAV/Crn 1/Sq2 0.1 MgM~h5 Elilrhip tih Buisdup

.I 7e1 6.4A $vS 6 5276.31- 1,7loe 34 I 7Ye 31 1.229*400 LlO.ICelS 1.775e1f3 0.2 2,074u-01 6 23, c 9s OA1 3:533014 4.(;2%_j3 7.1 1o 1l 3-021* 14 1.744e 12 sa6.."eri? R39e-is

2. J61u*G2 3 29 It 14 1.368e 12 6.45 17 2.725e 15 24509*O1, 3.3$>2.e i}1 1.05e. 10 6.543e-15 2-i.1' 3 0.8 1.184e*0O 7-459 :, 1.590e.O0 1.41 413 3.02 3-el 1.0 9.34:3c.1 I 824v 1 130 2.820e09 3 361-13 Slgfi 12 1.5 1.185f+0 1 430se.0B 2.40e-12 2;&05e-11 T1OALS: 5 7++00 1.830e-09 I .88;h8 3.125e 12 3 249C 1 1 Cl-210

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 Mi~croShltld vS.04 (5.fl400362) 12i211o5 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 UUWjt5 (5,gwm .. go.-par

, eng

- -ril6P4 J12b Without Mffiiu Photonsfrni/sec 1 M3Be-009 1.453e-008 Pti~ton Ernergy Fhi,#nce Rate MeV/crnl/sec 1 .882Ce0t8 Exposure and Dose Rates-

-xpour~e Rate in Air mR1/hir 3.1 25e.012 3.249e-01 1 Absorbed Dose Rate in Air m~y/hr 2.728e-014 2.837c,01 3 I mrad/hr 2.72&0~I 2 2,937e-01 1

.ose Equivwmlnt Rate Z Dcp (ICRP 51 1987) a Parallel Geo'metry mnSv/hr 3.09Ae-;O1 4 3-226e-01 :3 ci opposed U 2.685e-01 4 2.785e-01 3 a Rotational 2.686e-01 4 2.785c-DI3 o I sovooic 2-406e-O1 4 2..491e-O1 3 Shalio.w Dose Equivalenit Rate (ICRP 5I1 1987) mSv/hr 3.2,79e-014 3..422e-01 3 ioOpposed  ; 13.3O1eO1 3 U

c-Rotational 3.169e-014 3-303e*01 3 U

2.535e-014 2.630e.0 13 Effective Dose Eqwivalent £satc (ICRP 51 *1987) o AnteriortPostenor Geom~etry mSv/hr 2.787e.-014 2,902e*O013 UPFjota..firor/A~terior, 2.5S79e"Q14 2.fi77e-0:t$

ci Latera I 2.0 74e-0 14 2,141 e.0 13 o Rotathonar 2. 32Be-0 14 2.414e,013 a Isotropic 2,Q07Q0.Q14 2.1 40Je-013 Page L Cl-211

Plum Brook ReactorFacility . . FinalStatus Survey Plan Revision 0 MicroShield u5.114 (5.04.00362)

Radiological Servlces, Inc.

Page :1I file Rot; _ _ __ _ _

Daq~ Fite :P8t22139AMS5 fDate:__ _ _ _ _

Ru de ; December 21, 2O05 By: _ _ _ _ _

Rv&A7arne: 628:.54 PM Duration :.00.00:01 Case Title.; Line 1J82 E D~escript! wit Revised M~odel Celt- Ag.W0m n iwt A4. wSched 40 & 12 In Sftd Geomnetry: 10 - Cylinder Su~rface -External Dose Point IS 777 7 -

I !Source Dlmeansions I Height 762.0 cm 25 ft Raius 3.E1 cm 1,5 in t

z U1 134.97 cm 381 cm 137.16 cm 4ft 5] in a22ft .0 in 4 it 6.0 in I I nmm<itX CYI Cvire 3.81 cm' Conc rat' he I -8 Shield I ~.6Ei cm Ire II Transitian Concret e 24 Shield 3 W.46 cm Concrat e 2.4 Air Ga Air 0.00122 Wall Clad .025 cm Iron 7M Source Inputs Grouping Method :Standard Indices Number of Groups : 25 Lower Eniergy Oizioll .1 rhDtons c 0.015 : Ezmluded Library - GrOTO .

Nur-lidr, be t~jruvrftI UOifcrn' WCfM~

Ag-108m 8.20871~011 3,03720+CXQ0 4,5WOvOe0 D09 1.6650C.004.

Buildup The material reference is : CyL Core Integration Parameters YDirection (axial) 20 Circuwrcf.t fial 20 Results adivditi E~xposure Ra~n ph!2wLs/s No ElyiildUp W-4h FRudI4uv 1 .992e+00 2 L69t-234 1 5.4739.34 9,593o.236 1 £99e-35 CI-212

Plum Brook ReactorFacility FinalStatus 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 Fluh~rnr R1 Frimn-cun Pntjp Exrszure RFate Me~fcmlfsec m.Rhr No-5ul0dueb With EHui Iftn Ntn Ridifikp With BLAuipU 0:03 6.449e407 1 149e-89 3.9 18c 4 0 1,1 30-.90 3.883e42 O01,0 2152e.01 2.021 e-20 9.243e-19 3.198e-23 1 .45c 21 0.4 2.7?Oe+00 3.806e- 2: 2.197e l0 7.415o ]5 4.281e*13 0.6 2.745e4M 3.7S7e- 1 1.216el09 7.333e.14 - 2,374e. 12

).8 2.7498400 1,731e 1O 3.6809e09 3.292e. 13 7.01.7e. 12 TOTALS: 1.043e901 2.14 5e.10 5.125e09 4.,100e, 13 CI-213

Plum Brook ReactorFacility FinalStatus Survey.Plan Revision 0 bkilraSheld v5.04 (5.0440062) 12/21/0l 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

~ vMM 414J Aur70r4Yp~ LUoni Wbithu Buildup Photon FIuecfle Rate (flux) Photons/cmrnsIc 2,885!I-O10 7,.187e.OC PJ~oton Emg Fluence Rate MeVlem'l/see 2J14$e.0103 5.125.,009 Exposure anid Dose Rates-

,uposure,Rate Iin Ale mR/hr 4.IO0e-013 9.819e-012 Absorbed Dose Rate in Air rnmGy/hr 3.579o-0I 5 8.572e*O014 K

mrad/hr 3. 57ge-01 3 8.572et.012 Nocr Do-so EqwiYalnt Rate a Parallel G~eometry m~y/hr 4. 195e-D1 5 I OB0841-0I3 I

a Oppoed .3,414e-01 5 &1164e-014 o Rotatfocnal 3.4 14e-015S a.164&-01 4 3,0Q80 0I5 7,217e-01M4 Shall~ow &ose Equivalent Rate (I1CRP 51 -1987) 0 Parallel Geometr'y Im$Vhr 4.47-6 e- 15 1.. 74- 013 I

o opposed 4.265e.O015 1.023e-01 3 o Rotational 4.265e-a 15 1.023ewO1 3 a raotrcopic 3,929e.015 7.72 1o-01 4 fifectiiVI Dose Equivalonf Rate (ICAP 51 . M7 so Anteri or/Posterior Geormetry rnSvihr 3.728*e 15 8,947e.O1 4 3.322e.0OI5 7..954e-Ol 4 io Lateral 2.SO0e,015 5,96MI~O4 o) Rotational 2.972e.O15 7.110~e*014 2.S4'7e-01 5 0-04 14 Page 1 C'-214

- PlumBrookReactorFacility . FinalStatus Survey Plan I Revision 0 MicroShleld w5.04 (5.04.4X)62)

Radiological Serviices, Inc..

Page -I Fire Ref: _ _ _ _ _

Dolt Nie -.P812214OIMISS Ru . ate 7Decembuer 21, 00Q5 By: _ _ _ _ _

Rwhrnlie; 6.30:33 PM Checked: _____

Duration :-00:00:01 Casm Title. Lino 1.2 F iD~script: fRevised IOde i -4 Unit Act wSched 40 & 12 In SId Geometry: 10 - Cylinder SuTface - External Dose PoMt Source Dimenslons

, I Height 762.0 cm 25 ft Radius 3.81 cm L15 in Dose Poin~ts z

In 381 cr 137.16 em 4 111 5.1i n 12 ft 6,Oin 4 ft 6.0 in Shields shiAld Name Dimrensipn .t&2 aI C1nsity lCyl -,4~e 3.81 cm' Cor Icret Shield I .65 cm IIron 7.86

-Tansiliion Concrrt e 2,4 Shield 3 300cm Concret e 2.4 Air Glop Air 0.00122

%V41l Vlaf IQZ

.05;m 1w 7.86 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;

.1YDirection (axtial) 20 Circumforeritiall 20 Results No, Activity Fliuance R-at+-

MIY haos/e Mevg/gm 2 /sec MeV/C Ist/-0.9 NO RVJIS&fu 0.0174 1.074e.03 C01030e00 2.369e-37 0.000e4. o 1.279o..

0-0175 2.057e-03 O.D30e400 4.581-e-S7 2.426e.38 0.0196 6,044e-04 3.91 7e-251 1.609,o-37 I .46e.252 5.-941e-39 eV7026 3..037%.&00 9.696c0] I 2.494e-09 I.870e*13 4,809a. 12

,71 1 3..037e-'OD 2.961e-10 5. 580e-09 !5,573c.13 110Q5Oe11 Cl-215

Plum Brook Reactor Facility FinalStatus 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 hm Activity -Fluence Ralte Fluence Rate ExploLue Rate W& phat-iwsr, UplcmI/"ee t=W*mfeee my/h Mr/Ahr Nn Ptihiup fth OYid'u o Bul.deup with 1B)AIduo TQTAL$: 6.07-e+0 &074e09 7,443e-13 1531e-1 Cl-216

Plum Brook ReactorFacility FinalStatus 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 Pkton Fl1~ Loone Ra,t Mm% Photonsimln/sec 4.,779c.0i0 9.9$55eOO0 Phtoton Energy fi uence Rate MeV/cmr2/sec 3.931e-0 10 8.074e-009 Exposure aznd D~ose Rates, Exposu~re Rate in Air mR/li; 7.4-3i:013 1.531e-01 1 Absorbed Dose Rate in Air mGy'/hr 6.497e-015 1.337e01 3 m

6.497c.013 1.337so01 1 Oeep DOSe Eq~vyulent Rate (ICRP 51

• 1987) a ParalleI Geo-netry mSY/hr 1.556e*015 1.556e.01 3 o Opposed m 6.224eO 15 1.Z,8Oe.Oi3 o Rotat-onal 6,224e*015 1.28Oe-01 3 OkItrap~ii 5.504e*015 1.132e-013 Shai~ov Do~se, E'w iya-nt Rat*

q Pa~rallel G~eanetry rn'jv-/hr 8.081e.015 1.664e-013 DaO Oppsd 7.71 1e-0 1 1.5MTe013 o Rotational 7.71 le*O15 M5M4.13 a isotropic 5.890e*015 1.2 le-013 Effecti~a Dose Equivalerrit Rat (ICRP 51 1,087) o Aetevior/Posteriar Geo'moetry rnS'v/hr 6.736c.0 15 1.3197evO13 oD Posterior!Anterior R 6.044,e.O15 1.243e*01 3 u Laterof 4,595-Q 15 9,435e-014 KoRotational 5.412e-01 5 1.1 13eoO13 iolur** 4.1563$01 5 9,581i,014 Page I Cl-217

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 11aSh~if& VS-04,(544-M62) waipooickul Smrkes, Inc.

Page D0e File PB122929 MS5 OK.~e _____

RL. 4$a~a Decemnbeir 29. 2005 Run T~mo; 3:42:46 PM DuatonQ:00a01 COASs TIU*; Una I.S92 a De-scripdiorn PAnedrit Model Cak- 1-129 Unit Att w Sdicd. 40 & 12 In SW~

"Icryr-) - "yInder Siufaee Cuxtaina DoqSe Point Searcc Namneslo"S H~frt 7620Zn 25 ft Rod 81 aft. Pbivt

1. 1 134.97 en 38:1 cm 1$7,16 cm 4 It .5.1 Ii 43ft 6.0 in ShIletd teria I DAtny4 Cyt Cort 3,81 cm, Cor xret I .86 SeWI ton Ttontown Ca' wot C ZA Shw4ia 3 3048 r Co' Kr ei,e 2.4 Att Gap AOi 0CO0122 waif wIo -025 cm trnn I SB source Input Cr.tapngMeth!od - Acttni Photon Cu"tgteS U$ bsaOR5 A BM&Wrn 1-I,29 8.208'1. 011I 3:0372e*000 4 50Ot-0*09 1 .66S0e-W43 Oui~rI"p ThC mIrmial referhence Is : Cyvt. Core Y Litrecion Ilezrm~in Parvastats Y Uirmolon(Pimmil) Z C-1mumforential 20 ROSVIti LEnm NtOY 0.029S 6.061tV01 27441s-86 3.t97c,34 2IO08118t6 3.660e*36 0.029S 7.026e84 6 .W&-34 6.77~6c,3~6 0.0336 3.912i#.0 I :3 96 3CA 3 492* 34 2.484#-36 r "'396 3;998#,O 2-764e-46 3 s50k-34 1 25%e-48 1_613e.36 CJ-218

Plum Brook ReactorFacility FinalStatus 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 FlusL Rate f harc723Ra loby Baed TOaerg 2 A23UVJI m4ICrnMMI MOPS No Buildup WIE 3euik J3 rOTAI-5 2 359*iW 2. 764e46 1,723e.33 1,2k48 2 453e.36 Cl-219

Plum Brook ReactorFacility - . FinalStatus Survey Plan Revision 0 MicreShleld v,S04 (S.04-00362)

Rola~'cuIServikei, Ine-Coiwenjon td tAkv~ated exposurt inair 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) Phutons/cml/sec 5.36%tV03 Photon Energy K~umne Rate MeVem/ra9 1.7Th,3c033 Exposure and Dose Rates!

Expo$ure Rote in Air m.R/hr 1.256CO04 1-A53"-36 Abswbed Dose Rate in Air mGy~hr I .097#051) 1.26ge*037 mrod/hr I .091q04W 1.269Q'035 Deep Dose Eqiira-lert Rate (ICRP 51 -1987) o Pita'il Geometry M&,01V 1.453e.037 o OpOe 7-904;05 I 7

,286e.038 o Rotabtiml1 715S8trO051 .6215e-038 OlSotrOP*C 6$ 80051 5,772g-038 I5hallow Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry msv/hft IV59050 I 583. 037 o Oppfte d L09.M061 1 089e.037 o Rotatiounal 1-e090.5 1.08ge-037 o Is~otropic 8000* O$I ENfeivtie Dosie Equivalent Rat#

1-C038 (ICRP 51 19B7) o Anterior/Postef ior Geometry mSbhr 9.1$2.051 v Past~tfoAnterioar 5,53?2051 3.3674.038 3,056.051 1.81 74.038 ORotational &197$e,05 3.345.038 O k5QUAReot ,4;018t 51 2,772e-038 Papo 1 Cl-220

Plum BrookReactorFacility . FinalStatus Survey Plan Revision 0 MICIV5110dl V5,04 (5.44-036.2)

Radklologca 5srvim~. Inc.

Pft.V - File W .. - __ _ _ _

DOS File : MPNO1dB SS ft ate : Jhanuary &. ?00 Dothe! ____--

Run Time-. 8:24:59 AM' D1uration : 0D0.00G1 Cues 1110A Uric e: LUI boscrilptlen: Revised Model Ca~cq Uri126 Unit Act w Schad 40 & 1.2 in Shid GWm~etay: 2In lCylloadr Suuiace - Exlernal Do*# Polint wuce Dimensioslo H~eight 762.0 cm 2,5 hit 3.81 cmn

I Dose Pabfts itT z

As1 1J4,97 tnm 381 cmi 4ft 5 3 in 12 ff 6.0 in 4 rt 60 ~m Shildsf

?4=110 M&+/-Fin I Dew~ily co1, Core 3581~ Pr'Conci S*~eld I 65 cm, Iraare Y26

~~Concrmt,e 24 I L 12 ArGap 0 001 22 WallI Clad

,Source Input Grouping Mothad -.Standard Iai~icas NOimnuro01 Gotps ; 25 Lew*T Efiy Cuwtff: 0.015 Photom ( &MS :Eteluded curies 0.2087,e-I 1il ~3-372Ze#000 4.5000c,0o91 1,.6650e 004 Vie. rmaeitlu reference Is - CyI. lCore YChmrehe Isal 20

.20

.Results phogtniLw 2.35le-01 3,26ft-235 6,458a, 35 .1.132e*236 2.237e-36 C1-221

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Page .2 DWO Fril ePOO10408,MS6 Run Date: January A. 2006 Run lime. 8:24:59 AMt DuraWtion -0GX;W1 Eluknoff Rate s.y Q.03 1,5844182 5,402-34 1.57Oe04 S-34e-36 0.04 1.51 7&62 1.427e 46 2.544e-l3 6.310*49 1 08 1e-37 0.06 2.91 lo.01 1.747e 25 4 ,092o-24 3.470e2 8 8.127e227

.0108 1 395e1+0 1,309%19 5A698e-18 2.072o,22 (.478o.2 1 roTAIS: 2.825et-0 1.3.9e 1) S-989e18 2V072#*22 9.478e 21 Cl-222

Plum Brook ReactorFacility Final Status Survey Plan Revision 0 micro5sI4IEd5.04 (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 h37~ cmI3.9 n

~ut Stymmed ~ey AerE V0!h WOW~u Wilhi ftomp~J PNttc4 Flowne Rate (16lu) 1434-0e18 7,486O1 7 PINOW Enerly Fluent* Ratr ,Ph crr'ie L1309,019 5.989le-018 tno"Orlo send Dose Rates-EwO*$w?# kofe In Aar MW/u 2,012,022 9.47&E-02i AbW, tMO 0OW Ratp in A'. J,r mTGyiIv I'Sw-24 9.274,023 140%O~0?2 8 274e-021 NA"- Dose Equiivatrnt Rati- PCKP.!Sl 19V) o PAroli ~e'm.nw1ry CA, msitthf 3.342 I .4 4 7e.022

()Opow 1 ~685s.02-4 O ollo., 1.608aO24 7.4908e-023 C O, p i 1,6?6* 024 7.438E-023 Shmdjoe# 0ioi!o EquivaleM~Rate {rCKn. Si 1m~)

a Paimtleol Gaomelly m~wthe- 1.1 34&-024 1,~434e-0,22 O,Opfow . 2 .304.024 1.054eQ22 O Rotatlonali 2.304e-024 1.054cD22

• Isotropic 7 735e-023 Effediv Dose Equivalent Rate o Arit-mofIPos~~terior Geaomety mSv/hr 2 655e 024 i 215e.022 o Nstiriorj/Amtermor 2 W2.?e024 9.27i e-0Z-3 o Lantefol 1-249*024 5.7 l4W.23 O kotaffc~al 1. 266e024 7,897e.023 O som I, 396. 024 6. 387e-02~3 PAp I Cl-223

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MlerShbeld w6404 46,04.0362)

Page -I Fi~t Ref; __ _ _ _ _

00X)Fki ; PI3I22931AMS D~ate: ____

RL atti; DawnibeT29, 2006 Runi Timn., 3S65:03 PIA Durafln~, 0O0O0;01 ICase Tide. Linme I52I Ae~rtd Itiodel C-alt. Zr.05 U4 It At! ~w Sdhed 40 & 2.2 In~$hi~d Dc~scription o:

aeoearnar: I0 -Cylindes Surface Extorna1 Dose Point I wi mmorw Dim¶en~sions A

ii Height 762.0 can. 25 ft 3,5I cfn 1.5 in I

acst Points I z I . it I 134,97 cm 137,1G e-m i Z 117 4 ft 5~.1 in* 12 116,0 in 4 ft ~6.0 in A. I i

i era I P.WfAi&

4 41 cyl Ue'e 3.81 cm.' Oof'Ac ret it 1.8

'i 9,4444 1. .65 on Itoan 7.86

! I , ,

CwmKret, & 2.4

$04~8 VI"' ce t 2.4 0.00122 Wafl Clad .D25 cm. iron 7.86 5Iource I!pul Grouping Wlethod : Actusil Fhoton Energies hwiw-t1, Igc~ Ow/Ce.

Nru 8 20197. 011 3.fl372q#+000 4.500OL-009 1,66.5I0 004 The mtkeril r"oomwio hisCoI. CO Jmtegrtht1 Parameter's 20 Covcurnforonfiui. Ž0 Resutus E .222u0 4.965CI11 I AItOc 9,!S46t 14 2.350e--12 0- 7242 1 2+0 0.7567 1.681e,000 7.926t*I 1. .1.17#13 3-S04e 12 4

TnlTALS; 3,0070400 3.-053.4e09 2A?4Ž 1$ 5. e 12 Cl-224

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 IdeiffbSield w5.04 (6.04-0O362) 12/2R/O 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 P OIr~ U1 C34.7,381,37.16) cm wit, PMarita fiv#wce Rite Olux) 1-733oe,010 iI07#-M Photoft Env, y Fkaenre Rate MwniW cmi6tse L ggO0 Q3~O Exposuro aind Dose Ra~tes' Expoure Rate in Air mRlhr 2.472u.OiI3 5.854* 012 Ab-,rW~ Doi Rte rinAor i111y/hr 2.158e*015 5.1 3I ez.14 mrard/hr 2.lSeO013 5.1 1Ie-012 m-Svihr 2.529a 0I 2 057-9-015 4 872c.014 4 872a.014 4 3O6e-14 ShaIow I~ime Eclurualent Rate 0iCAP51 19 87) o Ppral4IIo G&Yeornfry m~vihr 0 014)D15fd 6 W-o9-c014 a Roatiotkahh 2.573e -015 6J095e-014 t IstrAroplec 1-946e 015 4 609t 014 Ef etidvo Diose Eq~uivalent Ratit I, .1n!#irw/Pcteficw Geometry m.Sv/hr 2.247e 01 5 5.321e.014 O Putf~!Atfo 2.001v0.015 4.739t014 0) 3.5639*014 o? R*~1M3w 1.790e~OI 4.239&.014 0 strp L.5331,015 ~.301c;014 P 1 Cl-225

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield Y5.0A (5.04-00362)

Radiological Smiices, Inc..

Pag$ :1 file Re_.___

DOA File ! PI122932.MSS Date:

Ri tte; iDewmber br29, 05 Ch y:____

Run Time: 3:57;38 PM Duration : 00:00:01 Case

Title:

Line 1.82 J Iftwiptlow Rvised M*41 WC-iEu15 Wit Ad w SAW 40 & 12 in SW Geometry: 10 - Cylinder Surface - External Dose Point

- I I -- --..

Source Dimensions 762.0 cr 25 ft HeighJt Radius 3,81 cmn 1.5 in Do-st Points

• 1 z

1. 1 134,97c m 32M!r I 37.16 cm 4 ft 5.1 in 12 ft&0 in t f1t 13D Al Shields, Sh~ield Name 3 Wy,Co~ro 3 51 vr~ Concrcto 1.8 Shiela 1 .65 cm tron 7.8E Transition Concrete 2,4 Shield 3 AAcm Concrete 2.4 Air W-p Air 0.0Cd2 Wafl- Ci- .025 cm ~r-rn 7.8E6 source Input Ctrouping Method Standard Iit~ces Numnkf~of Groups : 26 Laiwetr Eergy Cutllf : 0.0115 Photons .90.015 : EK-cuded Library : Grove ibecciverels uCil/rnil K Eu-155 8.20874o- O11 3,0372e-O00 Ak50ooov0c 1.565O Buildup The maierial reference Is: Cyl. Core Integiation Parameters Y0Irtlion (axiON) 20 Circumterentiat 20 Roul~t Firoosure Rate I.UL*

03 9.6670-03 1,.722eS84 5-.672e-367 5.820e.38 Cl-226

Plum Brook ReactorFacility - FinalStatus 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

• Fx=n %ufl kwrim r,xe>on% re. P mLM photbnws/ee kleWf'm2J5pa Mde~crnlsec: mRLhr fn-RJhr With Auddipk No gJtiajdi wpfth Bu~iiduo 0,04 5. 505e,0 1 5.I77a-45 a8869e 34 2,290947 -3,922e36 0.05 1.791e.-l 7.354e-32 7.44Se-31 1.9sge,34 1.983e-33 3.93geO02 2.364w-26 .5 538,e25 4.696e-29 1.1  ;!-27 0.08 4.854e 2O 4.O50e218 1.401 eC2Z 0.10 9,431s-01 6,49e2 1l

(.1 6.279e-01 7.7539.18 -.5926e-16 1.186e 20 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 FinalStatus 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- Wu+hnti+

Photons/crW./sec 7.863e-01 7 5.976e-O015 P'toton En.etgy F~iuence Rate MeV/cmY/Sec 7-.B4 le-01 B 5-966e-016 Exposure and Dose Rates-Epour* Rate In Air vnR/hzr 1 .2Q0c-020 9. 1,30e-019 Absorbed Dose Rate in Air mGy/hr 1-.048&e022 7.970e.021 N

inrad/hr 1-04ge-020 7-970ewO1 9 DZeep Dose Equivaitnt Pate (ICRP 51 1987) a Parallel G~eometry rnSv/hr 1. $e4022 1.3-32e.Q20 O 1"o pprd U 9.603e.023 7.305e.021 o Rotational 9.600e*O:23 7.304e.02 1 9.292e.023 7.069c.02 1 SbhlIicw Dow' EquivtIonlv R~htu (ICRP 51 1987) n iPayai.el Geometry rnSv/hr 1.740e-022 1.324e.020

,1.350e*022 1.027tc020 19.350C.022 1.027e-020 9.827e*023 7.476-O,21 (ICRP 51 1987) o Anterior/Posterior eornetr~ mSv/hr I.506e.022 1.-14.5*'20 a Posterior/-Arneriar .

a 1,180c.022 B.980e-02 1 o Lateraf 7 .285e-023 5..S42*O021 o Rotational 1.008e*022 7 .66%.O2

,a Isllafoplc~ ~IZCQ 1510-fI2 Page Cl -228

Plum Brook ReactorFacility FinalStatus 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 Checked: _______

Duration . 00:00.01 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

!iRadius 762.0 cm 5.08 cm 25 ft 2.4 in Dose Points

• 1 136-24c-r 381 err 213.36 cm 4 ft 5.5i n 12 ft E.0 -n 7 ft ta0in Shields 1 Density

.cyl; Care 5.089 cm, ZowIbria Kc'e1 :e 1.8 Shield I . C-n I 7.86 N

tc 2.4 Shield ~3 38,48 cmn Conc el:e 2.4 Air Gap Aik 0.00122 WaVll Gi~d .025 c-n lro,- 7.86 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 20 Circumferetial 20 L=P Arii 016938 6-E0$e-04, 1-1732 4.050e+00 1.1 660-10 2.020e-09 . 2.084e- 13 3.6We- 12 1 .3325 4.050e4-00 ;1.436e.10 3.513e-09 4,226fe- 13 .501 7, ALS: 3.602e 10 5.533o-09 6&310 13 9.705e 12 Cl-229

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 kroShield wS.04 (5.04.0062) 01/02/C 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 nvUr anrIip 'I Wdhout Photon Fluevco ftt Ol ax) Photons/cwrr?/sec 2.822e-020 4.35se-009 Pitoton Enewy Flbence Rate M6VfcMrntc 3602e-01 0 5.533e*009 Exposure and Dose Rates ExpsXure Rate In Air mFR/hr 6.31OE-013 9.7-OSeO 12 Abwrbed Dow Rat, in Air mny/hr 5. 5O910e0 5 8.472e-014 U

mfrad/hr 5.5Oge-01 3 72ea

]

Nop Dose Ecqvivacnt FRatc. (ICRP 51 1987) a Parallel Gewetry mSgv/hr 6-252e-01 5 9..61eO014 Q stil(U 5.*Oeo15 8,.28-9e014 o RRotati-onal 5. 388e-D1 5 B 285e-014 4.814e-D S Shaltow Dose Equivalent Rate (ICRP 51 1987) a Parahlei GiemEtrr mry/hr 5654e.0 15 1.024e.013 I

[i Opposed 6.409e0 15 9.853e 014 o Rotational 6,409e*01 5 9.858e*014 d Isulzf>.ic 5.09ge 015 7.841ee014 Ef etive Dose Equivalent Rate (ICRP 51 1987) uOrttelow/PosteriorGeomtfy mSv/hr 6.631 e- 15 8.66le-014 E

o Posierior/Anttorior 5.18e.015 7.979o-014 ci Lateral 4.130e.8015 a

6.348e-014 o Rotational 4.67 3e.015 7.185e-01 4 Q 150cIroPIC 4.138-O 15 6,360e-014 Page Cl-230

IPlum Brook ReactorFacility FinalStatus Survey Plan Revision 00 Plum Brook Reactor Facility FinalStatus Survey Plan Revision hlicroSheied w5.04 (5.04.00362)

Radiblogical Saivices, Inc.

Page :1I File Rut:______

IDOR File P8122141.MS5 Rk nde m rrUT21 2005 BY, RuMmre'6'.3811 PM CQhukeJd;______

Duration : 0O-00:01 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 762.0 cm 25 ft IFadius 5.018 cm 2.0 in z

• 1 1.36.24 cm 301 cmn 211~0 cm 4 ft 5.6 in 12 ft Uin 7 R 0.0 n Shisls.

I a nD114N

'Cyt C0,1 5.0B cm' Cowc'et e Shield 1 .6S cm IroiIf TM6 a

Concrel: .3 2.4 Shield 3 30.48 cm Concret e 2-4 Air Gap Air QQ1 22 Wall Clad ..025 cm [MAn 7.06 Sourcec Input iraroauping Method : Actual Photon Energies Ba 137m 1.0354e*010 3.8309e+000 4.2570e-CM 1.57$1-0 Cs 137 L0945et*0I0 4i04~96o+O00, 4.500C0e-CO19 L 6650e-004 Buildup The material reference Is : Cyl. Core Integration Parameters Y Direction (axial) 20 Circumfoeq tiat 20 Rumili Na Buildupn 0.0318 7.931e-02 ~.15e.-35 3.01.5e*9 1 3.261 e73 0.0322 1.463cFOI 1.539e-86 7.506e-35 1.239oB88 6.041le-37 0 0364 5.325e.02 JWU48~66 4383c 35 i6.1 24e,69 316 3.447e+00 2,.737e 12 1-.163e-10 1.3CXe- 15 2.255e. 13 Cl-231

Plum Brook ReactorFacility FinalStatus 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 Fiuence Rate Flojencp Ra Exposu Rate Awshviry Ruin Ogupal Re Meilrn*ftd deVrAlsr'se INoQ uildug Wfth Qu*idgg .MR/hi' W~h toldi TOTALS: 3.726e+00 2. 737-12 1.163e 10 5.,306e-1 5 2-255e-13 Cl-232

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MkloSmeh W..04 (504-00362) D1I02fO6 M~icro~fhiald Y5.04 (5.04'00362)

RadiaohglcaI ServIces, Inc.

Conversioni of caiclated vxpasurv Inair 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

~ Ini~ wiffintl Wkih WOW Ruijilu~

Photonskm/crser 4.137e-012 1.758e.OIO Photon Ewfgy Fkaence Rate Meftm/wn/e 2,737t~.02 1 163B.010

.Eposure and Dose R-atm Excposure Rate in Air mR/hr 5.306e.015 2.255e-013 Absorbed Dose Rate in Air Imcaythr -9.63e0-O 7 1.969e.015 a

mrad/ hr £.632e*015 1.969LE.013

,Deep Dose Equivi',ent Rate ICRP 51 1987) o2Parallel Gem-retry mSv/hr SAS4a4-03 7 231 01 5 0*0Copous4 42.9l1e-037 1.9.66e-015 o Rotational 4-391ceO]7 1,.866e-015 n $1,d i 3.883e-01 7 1L651X~ 015 Shallow Cose Equivalent Rate (ICRP 51 1Q87) a Parmlel8 Gabsir mSv/hr 5-829e-O-17 2.477e-G1r a Opposed 5,5.36e-01 7 2.353,e-015, o Rotational Ff 5.536e-01 7 2-353c! ais QISOf0op4c 4. 15 le-01 7 1.764~e-015 (1CRP 51 1S87,\

o Anten~or/Posterior Gecvmatry mSv/hr 4.949e-0i 2-06 1,,Ol5 a Post-vior/Anterior U 4.8c01 7 LBI819e*01 5 o Litora!I 3.1746-017 1-349e,015 o Rotationat 3M2Se.O 17 1-626e-015 o Isotropic 3.256e-017 1-$t015 Page 1 Cl-233

Plum BrookRea'ctorFacility FinalStatus Survey Plan Revision 0 MicroShield Y5.04 (5L04400362)

Radi~ological Servrices. Inc.

Page :1I File Ref:

DOIS File P8122142.MS5 Ru te; Vcougw 1 2005 By:

Rwpt~rme: 6:3,!.33 PIM Checked:

Duration : 00:00:01 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 wrce Dimensions Hai&b 7652.0 cm 25 it Radius 5.08 cm 2.0 in Dose Points z

1 136.24 cm ,81 cTr) 213.36 cm 4;ft 5.6 in 7 ft 0.0 in shieldi Le al DansitVr Shield fbm 5.013cm' Conc fret1Fe 1-8

.6 5Lcm ITQ 7 863 Shield 23 Concret e 2.4 WQ8 an Cowet e 2.4 Air Oi~p 0.O0122 Wall Clad *Q~~rnAiro 786 Source Input Grouoping Method Standard lindlkes Numbm of Groups - 25 Lower Eanetgy CutlolU t 0.015 Photons t 0.015 .Excluded Library : Grave EU-152 1,0945tV].0 4,0496v+000 4,5000e.O00 Ia 1.6650e-C'34 Buildup The material teletence lis : CyL Core Integration Paramieters Y Direct~on (axial) 20 Circumferential 20 Results Ar-tivit Meu~y F3nnrrp5E 14 2.396ei-00 9.024e-54 2.61se-3.3 1.1 513e35 CJ-234

Plum Brook ReactorFacility FinalStatus 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 MPugen 1 atec EFXuenc# RRat Flulene Rate Eogmstre Rate Mov .ohoton=/sec I&W-Efa.rsee ,mF~hr No Builduto Wath Bwlldun W~th RlJ;ritin 0.05 5.991e-01 2.00e-37 .2140e33 5.3Z9e 40 5.702e-SN 0.1 1.161e+00 1.651e,2 1.872e-lB 2,525e-23 2.8655.21 3.175e-17 6.224e I5 *S.604e-20 1.09e 17 0.3 1.095e+00 3.l52etlS 4,414e- 3 5,900e I8 8.$72,. 16 0.4 2-SW4Se-01 6.228 .15 5.88te-13 1213e-17 I .146o-15 0.5 2,28402 2.722e-15 I3X e-13 5.342e1 a 3.572e- 16 0.6 ll717e-01 7.1 04a 14 1.387o.16 6.907-c15 0.8 7.21e-Di 1.9679 12 6.157e.I 1 .3.742e-I 1.171e-13 1.0 1,7339e00 1 909VI 1I 4.2l3o 14 3.519e 14 7.766*-13 1.5 Q -4e-01 1.091e-13 1 341 e-09 llemie-13 2,25G6e12

.TOTALS: 9.a37e+00 1i.30&- 10 1828P'9 2 .227a 13 3.159e-12 C1-235

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 Micro~lidield w5.04 (5,04-00362) 01/02/06 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 Egcit~ Ca iMrnd nvir nCj&% ffi~thi+ d

&JI A-U 801 PdtKton Fluenmo Ra~te (luxc) Photonsh/m2 sez gA46er-011 1.40Ie-009 Photon Ener~y Fltuence Rate MdV/CM1/we 1 303e-0 10 1.828e.009 Exposure and Dose Rates; Fxapoure Rate in Air rvnR/hr 2-2274.01 3 3.1"6e0l2 Absorbed Dose Rate in Air mGY/bhr 1.944e.01 5 2.758e.014 rnrad/hr 1.944e0.0I 3 2.7?58e*Q12 Na Dose Equivalenk Rate (ICRP 51 .1987) a Parad;ef Geomretry mSv/hr 2,205e.0]15 3,134*0 14 N

o Ophposed 1-914-e-'1 5 2. 707e-0 14 o Rotabonat 1.934elQ15 2,707~O 14 a kclIropie I .7149.015 2.421e.014 S:ihafl Dose Equivalen' Rat~e (ICRP 51 .1987) o Parallel Geornelry mSv/hr 2-~3170Q] .3,326iP.014 2,259s.0 15 3.29e*0 14 o RotationalI U 2-2S9e-015 3.20ge*O 14 I

u 1solopie ]Z~OSe.0] 5 2.557e.Q014 Effective Dose Equivalent Rate (;CRP 51 1987) o Ar te~nor iposterior CGeomTetr~r mSv/hr -9~86e.015 2.820&"014 a Pp-4.rior/Anteriar .

11833eO1 S 2,60,3r~014 o Lateral 1-478e-01.5 2.08le-014 a~ Rotatlonal 1-659e-03 5 2.,47o.014 o ISOtODpC 1,.47-5e.D15 7.081e.014

. Pare 1 Cl-236

Plum Brook ReactorFacility FinalStatus Survey Plan . Revision 0 MicroShde~ld v5.04 (5.04-00362)

Radiological sewlce5. Inc..

Page :1I File R :_ _ _

D0W File. ; P'8122i43, MS$ .Dote:

RL. kge:December 21, 2O05 By:

.R~u;me: 6:40:51 PMA Checkec:

Duration O: 00~:O1 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 25 ft Radius 5.08 cm 2.0 in Dose poinbs z

-4 1 136,24 cm 381 cm 213.36 cm 4 ft5.6:in 12ftt6.0 in 7 It0.0in Shields Cyl Core 5.08 cm' Concre I:e 18 Shield 1 .65 cm Iron 7.A6 Trans~itioni Concre :e 24 Shield 3 30.48 cm C~rae a 224 Air(Op Air 0,00122 Wah Clad .025 cm Iran 7.86 Source~ Input Grouping Method :.Slandard Indices, Numnber ofGroups :25 Lower Energy Cutoff: 0.03 Photons c 0.015 :Excluded Library :Groie WCM, Eu-.1541 1.0945e,010 4.0496e+000 4.50OO-00Q9 1.6655ODO Buildup The material referance Is : Cyl. Core Interation Parameters Y Direction (axial) 20 Circumlerential 20 Re; ults Fneo i Activill iph,2$2ns /se2 MAY/cM21sec. Eh RuRtittn

$24a0,Q1 83 3.104e-54 9.006e-34 1.373e 56 . 3.983e* 36 Cl-237

Plum Brook ReactorFacility FinalStatusSurvey Plan Revision 0 Pagh ;2 DOS File; P8122143,MS5 Rutl-Date! December 21, 2=!

Run Tjim.; 6;4051 PM Dur-tlon : 00:00:01 ACtivity Fluenve Rate Flusnce Rate Esure Rote Expqsure Rate Dhotoni tsee mRhr No Buildugt Nith Rilrlixp With BQjduo 0.05 2.093D1 7T479c;34 14.92c;40 1,992c,36 0.1 1,639e+O0 2,349t.2O 2.665e 18 3.5949 23 4.077e-21 0.2 2. 76e-01 .2.994. 17 5.672e 15 5..1070,20 1,001047 0.4 7,071e*16 6,676e-14 1.e378.18 1.301e 16 0.6 8.768e-&3 1.045e-15 6.985e 14 2,05le-18 1.37le.16 0.6 3,266C-Q1 1,35 13 C..731e 12. Z. *16 1 314ei 14 0.s8 1.579et*O 4.30geA12 1.349e*10 8.196e-15 2.565e-13 I.o 1,246e00 1.372e 11 :3,029 1 0 2.5130 14 5.W4ew13 1.5 1 .SB08s00 1.8.36e-1o 2.255e*09 3.I2e-13 i794e 12 TOTALS; 7.718e+00 2,.O18e 1 2.70 S09 3.427e-13 4-623e12 Cl-238

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 11troShleld vS..B (5.04-00362 01/02/I 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 LAdh Photon Flmnce Rate (1lux) Phatons/cmk/sec I A17e-01 I .987eM09 Photon Energy.fluenre Rate M6V/crn*/se 2.018e-010 2-.700e-009 Exposure and Dose Rates-Exposure Rate In Air ,n~R/ht 3.4274-013 4.623e-Ol12 Absorbed Dose Rate in Air mGylhr -4.036e-O14 U

mrad/h r 2.,99le-01 3 4-0L36e-012 Deep Dose Equv~iyint Rate fICFP 51

• 1987) coPar'allel Gieometry mSvfhr 3-38%-015 tZ800i.014 U

2. 950e-015S 3..971e-014 o Rotational 3 971e-014

2. 644e-01!5 3.55r6e-14

~hh~Iovi Dose Equva lent Rate (ICRP 51 1987) o Parallel Geometry mSvfhr 3..589e-01 S S.855e-014 3.47 le-Ol 5 4.69D'et01 io Rotational 3,47le-015S 4M-e.0e14

2. 785e-DI S 3..750e-O 11 C ifmfropc101-ruvjo~Mt (JCRP 51,* 1987) o A.-tterior/Posterior Geornstry rriSvfhr 3-054C 01- -5 4. 324c-014 r0 Poteriar/Anlerior U 2,831e-01 5 3a814e-014 ci Lo tral 2. 283e-01 S 3..O63e.0 14

-o Rotational 2.555-e 01l5 3-441cAJ14

2. 2779-015~ 3-O8e.014 PagE Cl-239

Plum BrookReactor Facility FinalStatus Survey Plan Revision 0 MicroShleld V5.04 (5.04400362)

Radiological Services, Inc.

Page ;1 FrIe Ref:

D0o Filie P812144. MSS Date:

Rt ate: January 2) 2006 By:

Run tIme: 8:09:557 AM Checaed: .

Duratiev : 0O:D001 Case

Title:

LineLM E

Description:

Revised Model CaIc Ag 148m Unit Act w SIvcd 40 &12 InShld Geometryr 10 -Cylinder urfawe EdernalDose Ptint

_x Source7 Dimermsionm Hclght 62.0 cm 25 ft Radius 5.08 cm 2.0 in.

Dose Points I

t 1 136.24 cm 381 cm 213436 cm 4 ft 5.6 in 12 ft 6.0 in 7 Ft 0G0 in Shields Shiled tosme wwaliw cysi Core 5.09 cm~rl ret iB 1.8 Shield I .65cmn IreII 7.86 Transiti on Correte 2,4 Shield 3 30.48 cmn Corciet e 2.4 Air Gop Air .0O122!

Wall Clad .025 cm Iran 7.86 5wrcc Input Grouping Method: Standard indices Number of Groups : 25 Lowe Energy tutoff - 0.015 Photons < Dd)15 : Excluded Library : Growe N;AEide8 1.si a berguefu m .'mO A8- 108m 1.V945t e010 4, 415+wo 4.50Q- D 1.650t-010 Buildup The material reference Is : Cyl Core Integration Parameters Y Direction lOxiol) 20' Cicumrerentia! 20 Rowits Ar.ivi5v Exfft-.tuyk RsMt F~xro~amire -Patr

3. 946em-2 ee MdeV/C"mOY ae1e mR/fhr 7Rthr NaP F~q~~jd pln 1LI3h7e- With Rijilfiim 2.6560+0 194Ge-21 4.9WO 4 1.367e-292 1.715e-35 Cl-240

Plum Brook ReactorFaciiity FinalStatus 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 Fltuence Rate Fxnitzr* gPai'g hky  :

0210W Metfoe/Serc mNftihirf t mht

%i1tbQUWLAD With RusitdtIr 0,3 S. 599*,07 3.040e-107 :3,543e4f} 3.013e-109 3.5,12e.42 0.08 2,870e-DI 1.D29e.23 6. 3 3e-22 1 2¶,M.26 1.009e*24 0.4 3.f6e4E00 8.90e- 14 8w.411e-]2 1.736e-16 I,639o.14 39661,+00 1.51 4. 12 7.543e I 1 .2,95e6015 1.472-e13 0.8 3.65e*00 1.OOOe-1l 3.i,;0e-1O 1.W2e-14 5.953e.13 TOTALS: ,I 391 84O1 I.-1'el1 3.9me6 10 2.21 5e -14 7,589eo13 Cl -241

Plum Brook ReactorFacility FinalStatus 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 w1 - (136.24,8 13 fl6) 4 cm ftsUJ~rs (Sunmmd cv.er energiej) Without mih Phioton Fluemte Rate OIuxc) Pho~tons/crnzsec 1.525e-O011 5.380e-010 ftotion Fswfy Fhjentce Rate meVIC&Wse 1.160e (I 3.96ft-030 Exposure andi Dose Rates:

Exposure Rate 1InAlf mR/hr 2.2158.014 7.589e-013 Ab~swbe'd Dose Rate in Air mGy/hr 1.934e-0 16 6.62sel 01 5 U

mrnd/hr 1.9u4o,014 6,625e-01 3 088P DQse. Equigarent Rate (ICPP 51 1287) a PararIet Geoametry m.~yhr ,22.16 7.770e.015 o Oppose~d I .84 e.O16 6.3 18e-015 o Rot~ational 1.846e.0 16 6.318e.015 1.6320i016 5. 585e*015S S~-altw Docse Equivalent Rate a Parallel G&,cmetry mSvihr 2I4169.016 8.289e-O015 a Oppos~ed 7.897s-01 5 6?3-All o Rotational .

2-.303e.016 7.897e.O1S o kswo~rpq 1-746ft.016 5.975e.O015 EfJectvye D~ose Eirvivalon't Rate a ArnteriorlPosterio.r Geamerffy m$,Y/hr 2.D12v-016 6.900~Q15 a PosIerior/Antftri-w 1.796e-01.6 6.150o-015 o Lateral 1 -3540fll 6 4Z25e-015 a Rotalonal 1.607e-01 6 SSO50Ce*015 o Iscziropic 4 7l34e-015 Page 1 Cl-242

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 hMkro$-hleld w5,.04 (5.,04-tN3362)

,Zealzla Seivices, Inc.

Page rI File Ref:e DOS File P.1 2214S.MSS Crate.,

By:

IFnr Ti me: 6:4.3:57 P M Checked:

Duration Q0:foos;Q1 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 762.0 cm

• 25 ft Ractlus 5.08 cm 2,0 in Joss Points 213~36 cmr 4 ft 51 in 12it 0.0 in 7 Atq-Q inE Shields ies~nMapj Pni z

Li yl Ccre5s Trn-i~

3S cm' Conce .81:,e

.65cn Irtr srl Conc' ret;C 1.8 7.86E 2.4 Shield 3 30 ,48 cmr Concy :e 2.4 Air Gap Air O0,0122 257n, Irgri

'Source Input GOtrpIng, WtIhod : Actual Pbfr~on ruE~ces Nb-94 1 .0945o.0 130 4 0496e+000 4 5OUO,0O9 1-650v-004 OuiOdup The material referemee Is :Cyl. Core lntegration Paramneters Y D~iroctilir (oxiol> 20 Ci rcumteielitiai 20 Re sults Enewd Activity Fluence Rate na 1h<AnV,"ir 0,0174 1.4342e-03 0.Dowe+00 2.142a 37 Q.0QOk+00 1,156e:38 0.0175 2.743e-03 0.003e+O00 4,1~436-37 0.000ei+00 2,1949-38 0.0196 8_058e-04 0.000e+O0 1.4.6e-37 0,QC03e+00 5.374e.39 0.7026 4.050o+00 4 774a,12 1.841 e 10 9.207e-15 350C13 711 4105064-00 i.8n5e1 1 5. 185e* 10 3.5.67e 14 9.7-5;5e1 3 C1-243

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Paige... :2 K)( F le -PF1 22145.M$S FPun Date: December 21. 20O5 Min Time. 643:57 Pri Duratio: W:X.--01 Adiuiy Fluence Raite PZpn,;Irp atep mRfhr No PC WU .ith eind Min RIMlfo. . Mthpijilrbip.

Mw04c+OO 8.

TOTALS: 2.373e-1 1 7.0-8e-10 4n.488e- 1 4 1.331e 12 Cl-244

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 r14croS$eled vS.04 (5.04-00362) 01rgov6 IficroShiold v5.04 (5.04410362) fladlological Sertimes. Inc, Conversion of culculatwd gxposurv lit air to dowo FILE: C:MSM\ATAXPBI22145SX3 Cozse TRWe Lin~e 1A3 F This case was nua on WedooesdayN December 21. 200S at 6:43.-S7 MtA Dose Mmin j I . (11343$ 1,213.a$) cm Resuglts r~ymmgd gler en2W,!W sa Without P~,oton Fimice Raet.ux Photon s/cm~/sec 2.855e-O1 l 8&572e,010 Photon Enewgy flipnce Rate MqV/CM2/SeC 2.373e-01 1 7..026e-010 txposure and Dose Rates, cxposure Rate in Akf mR/hr 4.488e.014 Absorbed Dose Rate in Air rnGy/hr 3.91se*016 1.162e-014 a

mrad/h r 3-918e 014 1 162eO012 C.'ocp r),pp Cqpvwa~nt Pptp (ICPP 51 1987) o Parallel G-ewnretry rnSv/hr 4.553e016 1.351m 014 OOppw$-W 3.7-55-c036 1,113e-014 o Rotational 3.755e-01 6 1.1I 13e-01 4 u kl~u¶jpic~ 3321e,-01 6 9,8 4 0c-0 15 Shaltrow Chse Eqjuivalent Rate (ICRP 51 .1987) a Miarllel G~eci'etry mSvt'hr 4.870e-01 6 1.445e 014 o Oppo~sed 4.,648e-l1 6 1.379e. 14 o Ratation~al 4.648e-01 6 1.37ge4 14 a Iwtropic 3$. 53e4V16 1,053e 014 Iffective D~ose ETjiv3lent Rate a Anterior./Posterior Geameliy mS5fhr 4.060e.0 16 1.205t.Q 14 a Postaorr/Atntg-rior, a 3.646e.Q 6 o Lateral N 2.7749.016 &212e-0 15 o Rota'lfunia 3.264eO016 a fSt'ompU2 2,815e-016 8.336e-015 Page I CJ-245

Plum Brook ReactorFacility FinalStatus Survey Plan - Revision 0 MicroShield Y5.04 (5.04-OD362)

Radiol~ogical SerVices, Irtc.

Page :1I File Reft:

DOS Fie P8122933.1MS Date:

R' 3ate! Jianuary 2, 2006 Rum Time, 8:03:0$ AM Checkehd; Duratign ; W0~0;O10 Case hite:. Une 2.83 G

Description:

Revised IodldI Cakc. 1-229 tnat Mrt w Sched 40 & 12 in ShIld

,Qometry:20 G Cylinder~urnlpe, Ett~rnaI Dosefruint

• Qwrw Dimansigns Heioht 762.0 cm 25 ft Radiu~s 5.08 cm ZQ in Dose points x z

W1 136,Z4 C 381 cm 213-36 Cm 4 ft 5-6 in 12ft 6.0 i 7 ft 9 ,1in Shklds Lzerilitv Cyl, Core 5.08 cm' Concrete 1.8 Shield 1 £65 cm Irw. 7.86 I

Trarnsitian Conicute 2,4 Shield 3 30 48 cm Concrete 2.4 Air GaD 0.001 Z2 WMIl 4~n ,Q5 rm, Iro 7,K 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) 20 Ci rcumnferenitial 20 Results Ft tvence RiPtc Ewxtosure Ralm MAY/cfrI/se 0.0295 a.0a1e-01 8.t,334 106 3,163s.34 8,407c, 108 3.3100o.36 0.0293 I .499e+O0 -0095.e- 103 6.04ge-34 B. 202e-1 05 6.1 29e. 36 0.0336 4.584e 78 I3.1 56e34

.0.0396 3.045s-01 8.943e-56 3.2119e.34 4.064a. 58 1 .459e*36 Cl-246

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 D S File : P8122933.MS5 Run Date. January 2, 2QO0 P, n Time: Es P10P AM6, Durati .; W.00;01 FIijpnr.o R;t#-P .Flusnc* Rate Umsunq Rate T ohotAons:se .mAVerr."Appr IM22L NMfPs.93du MbhRliCn/r 1.31h.r TOTALS: 3,14.5etOO 8.943E-!5 L5+/-.5LuI 4,ol4t*S8 1.314e 35 Cl-247

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 UttoSIeld wi.4 (5,LO45362) OIA22M MicroShield 4.04 (S590162) fthdh4otca Seieim, Inc.

cwrsh~n of t*1ciI?1ud *to~wr In Ir. 1tc4¢ps FM: C:AllS5\DATA%\PB122'93.MS5 M casll CA$* e, 1s 22a 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) Photons/cffem/ 2.259e-054 4.856e 032 ftoton Eneigy Flunce Rate Mee~wctfset 8.943e056 1.55b$033 Stpajt and D~ow Rate%

4,064o O5- 1.1304 -JM E34:t!

Ubote

-se a

in A ir Rite

~ei i 4yfiv 3.64800 60 1148.037 mrwaihr 3 548e 058 1.148e035 Dou Om Eqiyalent Rato

• "larail4 Gemtry 5.07ge-060 1I314e-037

• Oppwed Z58$W0 6.59Oe P3ox;

',Ic9r 5l 1"7; 2. 316'0600 5,62 1.038 rnSvpnr I 7 2.2 15e*060 5.221le038 afiw ol Ewilvflinn, P~r o irrstry MG-'Ir Isv~~ 5.109wfto 1,432,t 037 3.527e0060 0.846e-03S C Rotatiorqli 3.1527 9060 %846v 038 2.58e*060 7,277e-038 f~fe N4$ r4iaie, ta¢ ('CE5i 1M7) a ;-sotroplc,,

S0tt~i,)X~eir s t - m5-.dhr 21*1S.060 5.90e-038

, s~e+ .M 1.790e-060 3.045eM38 rcl 1#Er;I 9-W.e 061 j. 44c 0,3 1.60%060 3 026e-038 i.319e 060 2.507e 403 Pi 1 . 1l

- Cl-248

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 M

MicroShield 5.04 (5.04-00362)

Radiologicai Services, Inc.

Page :1 File WRel__

DOS File ; PBOO10409AS Date.

FR ate: January 4, 2006 By; RurfTfime: 8:29.50 AM Chec.ed:

-Duration . 00:00:01 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 I--

mf- 'K-Vieilht 7762,0 cm 2$ tt Rawus 2,O in Dose Points 2

1. 1 136,24 cm 381 cm 23.36 cm 4 t 5.6 in 12 tt.Q n 7ft 9.0 in Shilds Sjiefo Nome I)im~ension M1 "oaI cyl. Core 5.08 cm2 Concrete 1.8 Shield I .65 cm Ir"' 7.86 Transition Concrete 2.4 Shield 3 30.48 cm Concrete 2.4 Air Gap Air O.OG122 WM Qeiad 'M? -cm Irq-1 7.8f' sourct Input Giouping Method :Standard Indices Number of Groups :25 Low&e Energy Cutoff 0.015 Photons ~i0.015 : Excluded Library : Grove Nujcide crm __________l Uci/crn1 Ba665m-10 Sn- 126 1.0945t 010 4.04 96c+000 4,5000c 009 Buillduap

.The material reference Is.CyL. Core.

Intepration Parameters YDirection (axiol) 20 Circumferential 20 Eftermt lady ghotjoaslee M2 MeV/crrrM~'

s~n W~ooith Ruriftt X 3.135c.01 4,657e.292 5,14le-35 1,.613e. 293 2.02,3e 36 C1-249

Plum Brook ReactorFacility FinalStatus 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 Flurpnm. Ratfe Fluenct Rate Exposure Riate VeY~ffthBif5tin With BLI4uit!~

s!tuildun NDo Buildin 0.03 1.1.86e*+0 4.192e-101 4.886e.34 4.1 55e-103 4,842e-36 t.04 2.023eo02 7,618e-56 .211eN-35 ,369e-58 9. 776e-38 O.0M 3.88le.01 5.S3ie-30 1.09ge. 32 :3.8130 31 0.08 1.859e+00 6.664e-23 4.1~9 21 1.055e-25 6.535e-24 TOTALS; 3.767e+00 6.6i64e.23 4 129e21 1.055e-25 61$35e.124 Cl-250

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Mleo~AtelAMv.4 (L64-t02C2) 01/04/06 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 PIaevil+; M5ijmmat4 nvipr Pnht~irai~ LIUni*

Photon FIvvco R~ate (fkx'c) Photons/crnt /sec 8.3$) e422 5.162e-020 Photon Erwe~gy Fluence Rate MOVICmZ/seo 6.664e-023 4.12ge*O21 Exposu~rei and Dose Ratcs5:

Excpos.ure Rtate In Air mR/hr 1.O555,025 6,535iC-024 Absorbed Dose Rite in Air rrt~y/hr 9,207e-028 5.706.e-26 U

mradlflr 9.207e.O26 5.705v-024

.eVep Dose Equivraiont Rate a Parallel Gieorr~etry 1,610o.027 99~72e-026 Oo ppos'e 8.57e08 5r315-026 a Rotational (ICR.P 51 .1q87) 8.33 7e-028 5.166e-026 o I aotfopic 8,277ti028 5.129e-026 Shallow Dose,~ Equivolernt Rate o Parallel Geo~metry m~vhr 1.5$,5,027 9.886e9-026 M

11 73e 027 7.266e-02r o Rotational` .173e~027 7.266e-26 8.607e-028 5.33-3e*026 Efifctivo Dose Equivalent Rate (ICFP 51

• 1987) o Anterior/Posterior Geoeetry mS-v/hr a

1 .353e-027 B.381c.026 o Pmtvrior/Antcrior 1.a32e-027 6.392e*026 o Lateral 6.358e. 028 3.939e*02,6 o Rotatbonal 8.787e-028 6.445e.026 o I otopic 7.108e~O28 4.404voQ26 Page I Cl-251

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Microftleld Y5.04 (5.04-00362)

Radiological Services, Inc..

Page -I Filt Ref_

DOS File : PB22935-105 Ft 'ate Decembei 29,2005 By:-

M.. Time: 4:09:22 PFM Checked::_ _

Duration 01O1:00:01 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 25ft Radius 5.00 cm 2,Q in Dose Pojots z

1. 1 136,24 cM 381 cm 2I8.36 cm 4 tt 5.6 in X 1?fj5-.O 71 U7Q in Shields

-Shield Narrnp- Dimension hMster Aqa Denft CtyI 5.08 cm' Goncre to 1.8 S9hield 1 .65 cm Irm1et 1,86 Trart4'iliorirn C 24 Shield 3 3C048 cm Ooncrete 2.4 Air Gap Al! 0.00 22 W.VIl! ?V'la .025 rn 1rgi' 7M 5voirc huput Grotipng Method

Actual Photon Eokergles&

Zr953,0945eQ1GI 4.049E~e+000 4,500ep-OO 1.6650e 004 Buildup The maeiale'a reference Is Cyl. Care Irllegraion, Parameters YDirection. (axial) 20 Circumferential 20 Ru iuhs

£Ener Activit Filtuonce Rate ExomRato MeV 0-7242 1.768c+00 1 %323c0.i1 4,881 o~15 1.72o* 2.13 2..241ei,00 4,27ae-12 1,464e-120 1 189L-TOTAL&S 4,009e-e0I 6.81 7e.12 2. 396o4 10 1,307e-~14 4,593o*13 Cl-252

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MlkrmShlild 4.04 (SA4*U63) 01/02/"

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 Ptlotor Ftz- ae Rahe MwOte Pbotons/cml/sec 9.15Ne012 3.221e D10

",taitf-f t # 'Lemee Rate MeWemAstee 6.8170,012 2.396P 010

-mosart,and Do Ralft Ox*re Rtate in AFr 1130 1#*4g Absorte DUose Pate A-r mG/hr 1.141s-016 4.01,00o015 a

nwa~dlth 1.141e-0.14 4.OIe*013 Cvep Sukya Rqr

,;i!rtc:s O Fpaplle. G..:n.rtri ryn$ hr  ; .337ec06 .701q0205 I

I 088~010 6 J.923e0435 io F;-,ato~ IO088s-016 3-823e 015 b I Sottope q.614e-p07 3 379e.0D5

!I.30i-z*f Dr-se Equ ivl3ent Rate (ICRP 51 -  ?'I Li :F~salaie ;5e>ellf'tri' um~viht 1. 28e-036 5.Ol-'-015 I X361C.016 4.782.e-01 ro pena!tioia I 13G1e-0] 6 4.78eI01 5 1-02'016 31616.e-o 5 Efedivoi Dose Emiwlemi~~l 2,ur (ICRP 51 - 2S,4 r Anrteor/wfosteuor Gte 1miro 1.181SWO13 4.1 75c-0 I i G,5e-D16 3;71%,^015 aweral at 7.957e- 017 2-796oe15 9.464q01 7 3.326;e-1 5

r. i:ctrapic 8&10.e-017 2 849eO 1 Page 1 CI-253

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 MicroShield Y5.04 (5.04-00362)

Radiological Ser~cui, Inc.

Page :1 File Rai;_

DOS File; P812206.%4S5 Oate: _

P Date: December 29, 005 By:

Rlm Time: 4:10:54 PM Checked.:_

Duration : 00:0001 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

=-

762.0 cm Haeig-t 25 ft Radius 2.0 in Dose Polnts

• 1 X

136.24. cm z

~81 cm 213.36 cm 4 ft 5r.6 in 12 ft ,0 in 7 ft o in Shields SMSIr1 Name Elimnrision CYL~Core 5.08 cm' Conci'ret:e 1.8 Shield I M6cm Ire, 7,86 Transitionr :e 2.4 Shield 3 cmn Cncirel:e 2.4 W41A

.Air Gap Air 0,001 72 WM'Valt .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 I UII ml Eu-155 1.05450- 010 4 0496e+000 4.5000e,00 9 1.665N0u0O4 Bu;idup

-rhe malerial reference Is :Cyl.'Core Integration Parameters Y Directian (axsial) 20 Circumfren1~tial 20 Results Exoos 2reRJit ZILU~

1,289eOW 4.557e. 103 5.31 le-36 5-2,4e.38 CJ-254

Plum Brook Reactor Facility FinalStatus 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 Fluence Rate Fluenoe Rate E=2oU ReFatA-ithRui1 0-04 7.341e-01 2-765e.,54. 8.022e.34 1,2239-56 3 548e.36 005 2,388.0,i 7.971'.39 8.27e,34 2.12.4e.40 2.272e,31 006 K.252e.02 7.48ge-31 2.598e-29 1.4889-33 5161e 32

.A 1-257e+0 47A&0ei32 279We021 7.12eZ6 4.4 1e2 4 Oil 2.37it 01 4.20Q-Z 1361Le- 18 1.836e.23 2.013e.21 TOTALS: 3.133e +0O I2ose.2 1364e 18 I.$We 23 2;087e 21 C1-255

Plum Brook ReactorFacility FinalStatus Survey Plan Revision 0 Mlico~lhleI4 u5,5.4 (5.0l4-00362) 02/02/O6 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~ WLdh Rhoton Fluen'C Rate (Pum) IPhoLtmnf/rm2/sec 1.206e-0 19 1,365Q1 7 Photon EamE48Y Fliuencie Rate M~eV/crn-/sec 1.205e-020 1.364e-018 Ex~po~sure andc D~os Ratw~

Eyposure&Rate in Ahe mnR/hr 1 .8&3c,023 2..08?e-02 1 AbwQrin~DQig Rvtv in Air rnGy/hr 1 .609e.025 .922a,-023 U

rnradhr 2 15D09o023 I .B22e-021 Ncvr, Dow, Eqwivaicht Rate (ICRP 51 1987) a Parallef Geornetry mnSY/hr 2,68ge -02.5 3-045e-023 O QpposdO$ 1 .475e-O2 5 l-670C 023 a Rotational 1,475e-025 1.670e.023 a ISotropic 1 .427e.02S It.616e 023 Shall~ow -Xosr Eqjuivalent~Rate (ICRP 51 - 1987) o Parallel Geemetby 2.672e-02S 3.026e'023 a Qp9asnd 2 ,073e.025 2.348e-023 o Rotatiwnil 2.073e-026 2.344te023 o lwl~ropic- rnSv/hr I1,509e-025 1. 70ge-023 Efoectivc Dose Ecwivi, nt Mplo.

c Anterior/Posterior Geornyetry mSv/hr 2.3i2e,-025 2.618e-023 o Post-etir/A.ntert~r a, 1.1e-2 2,053e-023 o Lateral I 119e-D25 1.267e.023 a Rotatoonal .54ge-0,26 1.75:3e.Q23 o Isolifopic I 232*020,5 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, 5.920E3-15 2/3/2006 Line 1.34 A 1t oceewl hedPBO20303 1 ft. concrete PBRF Pump wall shield 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. Roncrenchsh 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 File Ref:

DO$ File: PB020301.MS5 Da__ _

Run Date. Fbnuary 3. 2006 By:

F Tin: 7:07:06 PM checI._

D diocn : 00:00:00 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 Sourco Dirnonslons Height 34.6cm 10flOtO.Oin Radius 12.7 cm 5.0 in x

Dv.ioPQont Y1 -

l W#1 53.3 cm x

404. 8 an z

Ocm 13 ft 3.4 in ihields S5hield Nelme in Cyl. Coree Tfansitlon 2.7PCM77 Cowcete

,na

S e 1.8 2.4 Air(;ap Air 0.00122 Was Clad 30.4 8 = Concrete 2.4 Immcrion Concwto 2.4 ource Input 6rouping Method

Actual Photon Energies Nuglide 1= bemuClr Ucm Co-EQ ta045"010 4.04e4)00O 45soNa00w9 IA.650e.004-Buildup Thue nmtral rivbrente Is' Cyt. COr Integration Paremetemr Y Direcion (wcal) 20 Cicrrnrenotial 20 Results.

Ruance Rate Fluence Rate Exooure Rate EXwsure Rate 0A.M't. photonzfsec 4eJsemRhr W-77Ms97 mRF/hr LW With BUMd ND Buildup With Builup 860$e-04 8,75ft-18 5 562e-5 s.691e-20 1-074o-i&

1,1732 4.050e+00 3.652e-12 01 t~e-1I 6,47e-16 1.62,.e913 1.3325 4.050e400 9.129o-12 1.903e-10 t.5E-14 3-31go-13 TOTALS. 8. 100eO0 1,268e- 1I 2.824e-10 2,21&-.14 4.947e-13 f.1 C2-2

Microahtled v6.06 (5.O.060352) 0213106 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 With UN1=T Wgob ithouti BLMM Photon Fbence Rate (flux) Pholone/cmtsec 9.878e01 2 2,212e.01Q

. Photon Energy Fiuenice Rate Movicn9/se 11.25e-oi I 2.82,4e-010 Exposure and Dose Rates:

Exposure Rate in Air mR/hr 2.21 8e-0114 4.947e-O13 Absorbed Dose Rate in Ar mGY/hr 11.907e-O 10 4 319c-O15 mradihf 1.937e-0-14 4-319e-013 Deep Dose Equivalent Rato (ICRP 51 - 19a7) o Parailel Geoleuy mSv/hr 2.19i8-Ol6 4.902a-D015 o Opposed 1.B95e-016 4.226e-015 o Roptin 1.895c-016 4.225e-0 15 o Iworopic 1.,94"-16 317l5e-O015 Shalio Dose Equavalent, Rates (ICRP 6t - 107 o ParaJel Gooneity rn~vlhr If 2.339e.O010 S217e"16 o Oppoed 2.253e4.116 5-025e,-015 D Rotational 2.253e-016 5,025"-15 o Isotropic I1.793e.016 3,99~8eO5 Effedive Dose Equivalent Rate (ICRI' 51 - 19B7) c AnterorYPosteror Geornetry mSvlhr 1.979e-016 AA1 5e-O 1 o Posterior/Anterim 1 625e-016 4.06ge-015S o Lateral 1.453e-016 3.23ge-OtS of Rotaliorwi 1 643e-0116 3.664e-015 o Isotropic 1 456e-016 3.244e-01 S PagU I

- C2-3

MicroShfld. v5AS -00562)

Radi1boga llrvbm, Inc.

PagO 1 File Ref:_

DO$ File: PB020302J.MS Run Date: February 3, 2,00* By:_= __

R Time: 71-3:2 PM Checkod _

DwutiOn : 00:00:00 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 Sourco Dimensions eigt 304.8 CM 10 ft 0.0 in Radhu 3.-1 Om 1.5 in Dia s Poirft x Y 2 Y

62.2 CM 404.8 cm 53.3 cm 13 ft 3.4 in It 9,0 In 5hi-elds Eh-id Nan QN Bnsio Mtarinal I Donsy Cyl. Core 3.81I cmr ConcrhtI 1.8 Transitlon Concreie 2.4 Air Gap Air 0.00122 Wall Clad 30.4 8 cm Concrete 2.4 Immcws~bn Concrcc, 2.4 Source Input Grouping Method : Actal Photon Energies Nuelid e 1u21ea I4-000mG Bghmf Co6 3 7035e-11 Z.2149o+0100 450k00o0 1.665Sc-004 Buildup Theumtlsral reference is: CyL. Co Ihtogration Parumuwtr Y Direction (axig 20 Cirumferential 20 Resullta El tivi y Flftnog Rgilw FluWO Rs1t E ExposrureRate M, i2onhs w-V~gm ee MeVLnMz ME& mRlhr inm FliJKi WLDo Buldm With Buildup_

0.69X8 1.82e-4 7.A47e-17 Uia&-115 1743&t-1I 6.584M-i 1,1732 1-215e+00 1 ,$72e1 1 3.09e110 2.810e- t4 .602e413; 1.3325 1.215e+00 3A85e- I 5-642e-10 6.047e-44 9.788oe-1 TOTALS: 2A43e+Q0 5.058u-l1 8721e-i10 8.857e114 1.62ge-12 C2-4

MicIfShlbad MS (5V0" 362) 021D031 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 REpImis 19mmed ovr enerniest WithOUt With Builduo Photon Fluencia Rate (flux) Photonskatwsec 3.g5-01 1 6.858-010 Photon Energy Fluence Rate meVicWhee 5.058e-0 1 6.721e-010 Exposure and Dose Ratas:

Excpoure Rate in Air mt~hr 8.'7e.014 1 52te-012 AbwrdW Dos Rato inAir mGylhr 7.732e-O16 1 335e-014 mrwdlhr 7.732e"014 1.35e-012 Deep Dose Equkatent Rate 41CRP 51 -1957)

Q Paraliel Geonetry mgVlhr 8,77se-016 1.51$e.014

., 7.564e-016 1.305e-014 o Opposed o Rotatool 7,564e-016 i.30$e-014 o Iotropic 6.759e0-16 1.16f-014 Shallow Dose Equivalent Rate (ICRP 51 - iS7)

• Parel Geomtcry mnSvihr 9.33Sse016 1.613e-0I4 o Otpposed . RI 8.995e-O1B 1.563e.014 O R~otatirnl 8.995e-016 1.553e-014 o Isooropie 7.16,8e-016 1.235e-014 H

Effectie Dose Equivalrit Rabte (ICRP 51 - 108-7) o AnterlorfPsterlor Geomeny i.

7.903e-016 1.365o-014 o PosteriorArtderior 7.2$4e4 16 1.267e-014 o Lateral &.799e"16 1 .WOe-014

.1 6.560e-016 t. 132e-014 o Rolatioml o Isotropic 00 0 a TPag14 Page C2-5

.MicroShield v5.06 (6,S~06OM62)

Radkiolocall Sarvices. Inc.

Pape :I File Ref,_ _

DOS File P 02030UItSS Run D.Me, Febtuezy 3, 200$

R Tinve: 7:211:118PM ChecAed;____

Durtiion : (M):O.00-0 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 Sourmo Dimensions Height 304.0Bicm 10 ft'O.0in U

Radius 12.7 cm 5A3 in Dose polintu z

1. 1 53.3Om x

404 8 em 3 6.5 cm I ft 9.0 in 13 R3Ain 3ft 6.0 in Shields Shield Namne Dime nsion Material Densitv co1, c-ore 7r, 1.S Trarks~ton fConcrete 2.4 Atr Gap Air 0.00122 Wall Clad 30.4 cm 8 Concrete 2.4 Im(Mrsion, Concrete 2.4 Souice Input Grouping Method ; Achial Photon Energies Nucbda curie by~gar& Xtan2 CO-O0 t.095e-010 4.04960+OO 4.5D0OD-009 1.66S0e-OD4 Ruildup Th6 nuiettial Wafronev is-Cy, ~Coro khterali'n Pmrameters YDirection (edaD ~ 210 Ci.crcinfrential 20 Riesufts Fbl2D1 M6LAnM-./ee MAVimehm, MRthr mR/hr MBuklu VMBol= WBuidup WMibBuirdua 0Z936 6,80$e.04 1.1732 4.050e*00 2,788e-14 1.070e.12 O.93e-11? 1.912e-15 1.3325 4.050e*00 9,437e-14 2,693e.12 1,637e-16 .191 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) 02)103o MicroShilelld v545 (5.05-003M2 Radiological Sofrkm Ic. hc Conwvrsloi or cattulated expsun insit 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

- 4J,106AJ 1 cm Results (Summed ovter n2ErgEm Withu M

Buildun Mu1u Photon Fluence Rate ({lux) Photonsbcm 2/sec 9.R5ge-014 3.OM3-012 Photon Energy Fluenre PAbe Me~lct/sec 1223e-013 3.963e.12 Exposure and Dose Rates:

Exposure Rate in At rnR/hr 2-M3e-016 6,030e-4I S Absotbed Dose Rate in Air mGylhr 11.864u-018 6.050e-017 mnradff 1low'010 Deep Dose Equivalent Pate KIRP S1 - 198) o Paralel Geometry rn~vlhr 2,1150-01B 6.865"-17 o Opposed In I .M2.01 B 6.MZe4O17 o Ro1etlon~I 11,825e-018 5,M2e-017 o Isotropic 1 631le-0I8 S.291*17 IShallow Dose Equivalent Rate (ICRP 51 - 1987) oParallel Geometry mnSvlhr ~2-Me.O1 o,Opposed In 116136-018 7.037"-17 o Mo~UMn! I i 2.168e-0i8 7.0~37e-01 7 o Ieotropec 1.727e4O18 5.603.-1l7 Effective Dose Squiialont Rate (ICRP 51-1987) oAnterloflPostedor Geometry rnSv/hr 1 905e-OiB &6,to83ol7 oPosteriurlnterio! of 1.757L..018 5.701"-17 oLateral to 1.400e-01 B 4,41e-017 o Rottionlaf I .583e-018 5.134e-O17 oIsotropic 1.402e-015 4.Wo~-017 Page I C2-8

NfcroShield v5.05 (S,D5.O0362)

Rad~oogicall Servicos, kmc Page :1 File Ref:

DOS File, P10209K4.MS5 Da le  ;-

Run ODae: February 3, 2006 By:

P Time: 7:34:46 PM Chocked' Dlwabon : WO:0O:00 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 9

Rais .1 GM 1.5 in Dose Paints

/f

• 1i 62,2 on 404. cm 160cm 2 II0.5 irt 13 fI3.4 i 5ft 3.0 in Stields Material Cyl. Core 3.81 cia 2 Concrete 1.8 Transition Concrete 2.4 Air Gap Air 0.00122 Wall CIO4 30.48cm Concrege 2.4 Immmrign . C~nureIe 2.4 Sourme Input Grouping Mauthd : Aduial Photon Energl~a Nuclide curies becquerels [ikym 2 Bq/cm2 VaOQ 3.2~015 I 1214Wo+QQQ 4.Ngft-UQQ9 1.6650e-004 BWildup The matsrfalrrerncclRis:Cyl. Core lntejyratian Fanmmtomi Y Direction (axcial) 20 Cilum~erntial 20 Reamdfs FlVicmw Iec rnRfhr pb 0.6038 1.g62-04 5.2876-20 1.021e-22 .9.294e-21 1.1732 1 215e+D0 4,$40eaI4 8.8280-ST 2.1.Wel1$

I 13325 11-215e000 1.519e-13 4.1 16o-12 2.635e-46 7.14le-15 TOTALS: 2,430e+00 2.01e->13. 6.784-12 3.518e-i6 1.0120e4 C2-9

Mkero WvSAiM (5.ISAM3U M06O Mibt~ShIefd dtLO (&SCiWO32)

Radkotolka1t torv 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 ROsJfh I$#WwrJ g= 110h Matho W h

. Oulddw DaLI&ua Photon Fluence Rate (flux) PhQUm*0eh .541eO113 4.511e-012 Photon Energy Fluefloo Rate Mewowftef., 2.O13"13 5.7Me-012 Emmur &WDow Rateht:

Enmwe Raoe inAir MRft 3 S11kO16 1 012e014 Absoed DOme Rate inAr 3 071O18 6 36eB017 M m131fi 3:10o910 6103004015 Deep Dose Eqdwiem Rate (1CRP St - MT)

OPOrWIN Geometry 3 46A 014 ¶003e-Ol6 o Oppossd ,, 3008e414 8 46ee017 o R*ialonna 3 OOM-O18 8.-643e-017 o Isotropic

'I 2-687n018 7-726e-0o7 Whow Doe lEquivabnt Rale ~ICRP 5t - 1987)

OParalft GeOrMtry nsvfr 3,707e-01$ t 067e.016 o Oppoed 3.572e"18 1t028e-016 3.672"19 t.2ge-016 o Isotropic 2,844"18 a 132e-017 Effecte Dosw Equaknt Rate QCRP Si -1987 o AnteriorPosterior Gemetry nfta~1 3.t3ge018 P031e-017 o PosftrifoItefkW U 294"c'-1 e 3250-17 o Lateral 23Oteis -630e017 o Roawiat 2.607e"18 7.498-01 7 o Isotropic 2,31 Q41 410e-01T Page 1 C2-10

Microfteled ADS.O l565C42 Pag,  : Radiological Serv'ices, hIt. File Ref:_

DOS File .PBO20305,MS5 Run Date: Febnjory 3,2006 By:

R- lim: 7:-30:54 PM 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 I ROW* 12-7 cm 5.0 in 7 Dsue Points l/ x z

'V # 1 53.3 CM 404.e cm 214 cm I ft9.Oin 13 ft 3.4in I ft 0.3 In

~LLLNL.J TransIitonl Concrele 2.4 Air Gap Air 0.00122 Wall Clad 30,41Rcm Concrete 2.4 Imrnorion Concrete 2.4 Source Input GroUpinq W~hod : ActUat Photon EneIrgiS 1-0945e-OtO 4.049r6e+000 4.500(~e-009 I1.665%-O04 Bliduzp rho malurdal rrektnco is ;.CyL. Coro Integmiaton Furwznstem YDirecI~on ("axil 20 Ckcumforentlal 20 Fluence Rate Fluence Rate Exposure Robe Exposure Rate No Buildu= With Build NaBuldu p , With Buildup 6,6O0"O 6,803e-26' I .47e-23 1.314e.28 19570-26 1.1732 4.050e+00 1.3680.8 0.626e-17 2."44e-21 1.720e-19 1,3325 4,QS6e*O0 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) -021010 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 Results (Summed over enemies) Without With Buildup Buldwx Photon Fluence Rate (flux) Photonsla~n'lJsea 1.374e-018 4.204"-15 Photon Energy Fluenoe Rait MeVfawIsec 9.641e-018 5.471e-016 Exposure ard Dose Rates:

Exposure Rate in Air mPA'r 1.680"-20 9.5429-019 Absfted Oose Rate InAdr M130lV i .486e-422 8&330eV01 Is mradihr 1.466"-20 8.330e-019 Deep Dose Equablent Rats o Parallel Geomety 11803e-22 9,448e.021 o Opposed 1.43fie-022 8.1 57e-021 e Rottlt.or.l (ICRP £1 - 1o&7 1.4316-022 8.1 57e-021 o Isotropic ni~vihr I .284e0-022 7,293e.021 Shallow Dose Equivalern Rate I.

o Parakil Geomalry 1,76ge4O22 1000,020I QOpposed 1.705e-022 9.68te-021 o Rotalional ,I I1.706eA22 OIsotropiC 1.35ge-022 7.718e-021 Effective Dose Equivalent Rateo (ICRP 51 - 1087)

OMAntrlorlfoti edor Geam4rery m~vhr 1.498e-022 8,511eO021 o Postwior/Anterloc if 1.382e-022 7.852e-021 o,Lateral 'I0 1,103e-022 6,263e.021 o,Rotaton~al to I1.245e-022 7.074e-021 o,Isotropic .1,100422 6,270e.021 Paso I C2-12

Micro~hied vS0 (5,D5-0Q362)

RadkAV4 al Scnmkos, Inc.

pape :1 File Ref:_

DOS FiePE020306.MS5 Date:

Run ChmT: February 3,2006 By:

R riw: 7:45:12 PM Checked:

Dutation :00:00:OD 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 Source imanslons; PHeigh~t MUM 10 ft 0.0 in Radius 151cm 1r5 in x

Dose Points

/

11 X

62.2cm 404.8 c-m z

I ;66.5cm 2 0 ,5 In 13 ft 3.4 in ft 8_ im Shlda Shied N" Dim Cyl. COTe 3.81 cmt Concreuis 1.8 TranSatin Concrele 2.4 Air Gap Air 0.00122

'Vio Clad 30.448cm CGoncrmee 2.4 Immmin 2.4 Source Input Grouping Mathaid . Actual Photon Energies, CO-60 3.28350-01 1 1,2149c+000 4.5400o009M 1.665~0"04 Buildup Tho latarlal rmforanc Is. Cyl. Coro~

kftefratlon Parameters YDiahon(axiaI) 20

+Cimtrciamfoelha 20 Res-ulls Aativity Fle,0 a Flueioe Rale.t* tit.~ Me ExoutRt M^A-2~ mevfls B&M2 0.6938 1,982e.'04 4,193e.2 7.23Wo22 8&0950-27 1.396e-24 1.1732 1.216et-00 2.8170e-1 1.683e-15 5.034e-20 2.82ge.18 13325 1.21k+4QQ TOTALS: 2.430ei+0O 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! Services1 Inc.

Conveirion of Ca dlWexpoisure In air to doze FILE; QVISSM UMMAAPB230SMS5 Caso T116: Uina 1.31 A

'thts cast was run en 1 FI 32006 3rdy

.r at 7:45:12 PM 0*08 MMin II - (62.2AN.B,2~665) cm faiks thuM PMe nemiWWihri igr Photon Flueno Rate (flux) Fhtiadd~!Mzfsec: I ,243eG016 6,79e.01 5 Photon Energy Fluence Rate MeV/CM*lsec 1.61ge-016 7.45ke-015 Exposure and Dase Rates:

Exposure Rate in Air mftIr 2.8226,011B 3020,017 11.

Absutad Dose Rate inAir nGYfihr 2.463e.021 -1137e-019 of Mrad/tw 2,4,3e-019, 113,17e-017 Dueep Dose Equivalent Rafe, (UCP St - 1987) o Parallel Geometry mSv/r 2,794e.021 12K0e&019 o Opposed 2.41 2s-021 1.113e-01 9 o Rotational 2.412e.021 1.113e.019 oIsotwpic 2.1 570.021 9.94go-020 Shallow Dose Equivatent Rate (ICRP 511 - 1987) o Paralbel GeoMetry mSvfhr 2.972e-021 1.372e-019

'I 2.M6e-0211 1-322e-019 H,

286c-0,21 1.322e-019 o Ischoplc 2.2M3-021 1O0&U-0i19 Effective Dose Equivalent Rate (ICRP 51 - 1987) o AnterioriPooterior Geormery m~vhr 2.517e-021 11.1l29-019

'I o Poftoriot/Anterior 2.322e.021 1Il71e.0119 o Latera I, 1.852e-621 8.542e-020 oRotallonal 2.092e.021 9.652e-020 olIsotropic 1,.864e-021 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 Model Co-60 PBRF Revised Calculation PB020402 2.0910E-10 Area Factor 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 Model Co-60 PBRF Revised Calculation PB020408 5.3950E-10 Area Factor 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 Lie 1.2 AF-C 2/4/206 PBRF Revised Model Co-60 PO01 .1031 Lie 1.24 AF-CArea 2/4/2006 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 Lin 1.64 AF-B 2/4/206 PBRF Revised Model Co-60 PB244 105E0 Line 1.41 AF-BArea Factor Calculation 2/4/2006 PB244 105E0 2/4/2006 Line 1.641 AF-C o6 PBOFRvsdMde B20415 2.1390E-10 Area Factor Calculation 2/4/2006 Ln164A-D PBRF Revised Model Co-60 PBO20416 2.7950E-10

.LineAF-DArea 1-41 Factor Calculation III C3-1

MicroSt~eld v5.05 (S&O6O352)

Racft"IoiaI 8orvics, lInc.'

Pege :1 File Ref:_ _

D Fofe P0020401.iS5 Date:

Run Dale: February 4, 2006 By:

R Time: 2:01:22 PM Checked:

Dliratin : 00:00:00 Case

Title:

Lion 1.21 AF-A Doesrptioni: PBRF Rev Modol Co40 Aroa Factor Caloutkdln Gewmatqry 10 - Cylinder Surface - External Dose Point I Scurm O Dimnisionis Height 30.48cm I ft Radius 7.82 cm DoKse Poi~nts

1. 1 138.78cam x

15.24 can 45.72 cm 6.0 In I l't .0 in Shildame Djme ial

-Cyl. Core,'1P 8; 7~

.88,

• ~~1Shield 1I 5ani Iror I ConixetU ~2A Transalion

-shield 31 304 8n hZA4 Air Gap 0-00122 Well Clad .025 cm Iron 7.86 Grouping Method :Actual Photon Enotilgiu 00-60 6.5669e..012 2.42W-e0011 4.50O~e-0&0 I1.6650e-004 Buildup The maerial reference is: Cyl. Core 0k~l Integra-don Parameterm YDrecion(axial) 20 Citcurnfewn~lal 20 Fluence RArta Fhuence ae Rate fgar E2x2Mure Rate PAVA7k MVkrfAc ~ v~h 0, O P I Wbiludup . N dd ihui 0,593s 7.261e-1-4 .'1.178e 1,402e.6 2.274e-i 1.1732 2-A30e-01 3.67le-09 3.023e-08 6.381e-12 5.40.2e- 11 13.325 2 A30e-01 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 Eosurs Rt Eit 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) Pholonedcmlfec 7.38e-009 6.72le-00 Phcton Enorgy Fllue=& Rat MoVkanmekc 91293e-009 7.213e-008 Exposure and Dose Rates:

Exposure Rote InAir mR/hr .631o4-1 1 1.267e.010 Absodred Done Rate in Air mGyhr 1.424e-013 1.10 e-012 IR mfihr t424e-011 1.1we-010 Deep Dose Equivalent Rate (ICRP 51 - 197)

• Parallet Ge1oery mSvlhr t ,616e-13 1.256e-g12 o Opposed n 1.392e-01 3 1.081e-012 o RotatonaJ ,$'e-013 1,O1e-012 o Isotropic ..

1.244e-013 9.650e-013 Shallow Dose Equivalent Rate (ICRP Si -I 7)

I o Pwrallel Geometry mivlhr 1 721e-013 I .337e-012 1%.)

k I o Opposed 1.657e-G13 1.287e012 o Rotaonst 1.657e-013 1.267"12 i

- i o Isotropic 1 3117e-013 1.023e-012 i

Effectve Dlow Equivulwt FRabt QCRP 51 - 19B7) o AnterioPosteror Geometry m6vhr I,

1.45t-013 1.131e-012 o PoderiolAftor 1.341e-013 1.042L-012 oLderal t1.C-13 8,280e-013 o Rotationaf I .0e-01 3 9.379e-013 o Isotopic 1 9oC-01 3 8,29e-01 3 Page 1 C3-4

M~icrotileld YvSJ6 (5.05-0D362)

,Radiologieal Sorvicca, lrt.

Page3 :1 File Rr:_

DOS File -PB020402.MS5 Date:

Run Date:-fabrUrY 4,200 R rime: 2:05:04 PM Checked:__ __

Dutation : 0O-OD.00 Case

Title:

Une 1.21 AF.B Dscription: PBRF Rey Model Co-OD Area Fadw CelculaUon Geametnry 10 -Cylinder Surlace - External Dose Point Source Dimenslons Height 60.96 cm 2 ft Radius 7.h2 cm 3.0 in Wose Points I # 1 138.78 Ian 30.48 CM 45.72 cm 4 ft 8. I ft 6,0 In I Shlolds

_,j 7

Shield Naw Cyl. Cora 7.62 cm' Conci :ehi SJield I .$5 cm krai I 7.0; Triewsitn commilt: 2.4 Shild 3 1 1Q4 ~ CowvrOt, 2.4 Air Gap Air 0.00122 YWall Clad .025 cm Iron 7 186 Source Input Grouping Mthod ; Atual Photon EnartiO Co-OOw alim b rels Uel 1 ak5OmQ04 1.31 34e-O1 1 4.1595e001 4,5000e-00 BAildup The material rtefrenoo Is : Cy]. Coto Integration Parameters Y Diredioni (axial) 20 Circurnretentiaf 2D Aab&Rueoe ate luew* ate 117-oorg; ae Ex~osuta Rate Mat lig E~bg Wth SuldkM No 19uildurii 0,038 1f~-O

.383e-13 2..260e-12 2.669e-18 4.363e-15 1.1732 4,8~e-01 et8s-se-os 6.63se-aa 1,2265e.1 1 043e_-10 1.3325 4.8M0-01 1.1gi0-o0 6.1059-Q 1.0Q-11 1.406e-10 C3-5

Page :2 IX)S FIee PPW2F.O2M$5 xJw Run Cabe: February4, 2006 vRrm Time: U:O O4 PM Di nation A:1DX:0O AAdi'MAil Fluen t OFluence Rate Expoeure Rate Exposure Rat t photoised levkmls U zRaht mrihr W wm OUM N Build With Buildup TOTALS: 9.72M-01 1.7weW 1.4 7 3.134e-11 2.450a-10 C3-6

02n010 vh.0el(5.05-003&2 Micro~hlicd 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 Unft WithMut vWith Photon Fluencs Rate (flux) Photonwcw/wo 1141 Oe008 1,1106e.07 Photon Energy Fkience Rate MeVkWm~lec 1.786e-008 I1.394eM07 Exposure and Dose Rates:

Exposure Rae in Air m~ihf 3-134e-O111 2.450e,-010 Absorbed Dos Rate in Air m~/r 2.736e-013 2139e-O12 to mrad/hr 213ft-.1 1 2.139"~10O Deep Dose Equivaloni Raic (ICRP 51 - 1987) o Psralld Geometry mSvlhr 3.107e-013 2.4280-01 2 o Opposed 2-675e-01 3 2.091 e-012 o Rotationai 2-675e-01 3 2.O91e-0112 o Isoiropic 2.39e-01 3 1.867'ewD12 Shallow Dose Equivalent Rakt (ICRP 5t - 1987) o Parallel Geometry m6ythr 3.3070-0113 2.5155"112 o Opposed I. 3-184e.01 3 2.489e-01 It o RoEational 3,184e.0113 2.456 e- 12 o Isotropic 2..532e-O-13 1.979e-012 Effective Dose Equivalent Rate (ICRP 51 - 1987) o AnteriordPosterior Geomety mSvihr 2.797Q-01 3 2.187e-012 o PeOrIAntenor of 2.677e-01 3 2.01 4e-012 oL1e0al 2-049e-13 1161e.O12 o Rotational *1 2.320e-01 3 1.81 3e-0 12 o Isotropic 2-064e-01 3 i .604e-O1 2 PaeeGll C3- 7

MAcroTghibeld v&6S9 (51MOM11 Ra-diodlogical Sorvices. Inc..

Pago :1 Fibe Ref:____

DO$ FiLe: PQO20403ASS Dale:_____

isY:

Run Dab1: February 4,2006 R Rame; 206:56 PM Ghebked;_ -

Duration : 00:00:00 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 Ions Ibitt 1516 ,cm 5ft0.0 in Radius 1.ff2 cm 3.0 in x z At1 138,78cm 76.2 Cn'm 45.72 cm 4 ft6.6 in 2 ftO.0 ine 1 ft 6.0 in shlelds ftiension Fiatei jial Density 77 GyC Core 7.02 oan' Concm Ao 1.8; Shield I .. g5dcm [r I 7.88 Transition Concri fte 2.4 Shi~eld 3 50.48 cm Concr ite 2.4 Air Gap Afr 0.00122 zarn Clad .025 cm Iran I ."

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) 20

<;curcnf~rential 20 Resulta FIismnoe RM1 Fluence Rate, E mRt Exposure Rte 1dv~~m ________ j"R~hr mR__

No buAm WhBufdDNuild=~ Will, Buildup Id G.6938 1.952e-04 2.007e.-113 4.4248 3570e4.4w .. 4O 1.1732 1.21$esc0D 1,346"S5 1.183e-O7 2AD~e-11 . 2 1 Se-1 0 1.3325 1.215e+00

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

=21L1410 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 Remuifs (Sur~ndoe e iser Photio Fluenoe Rate (flux) Plbotons/cmvise~ 2.705eeOO8 2,252e,,O07 Photon Energy Fazenc Rabe lAeVkzn 2 sec 3.528e-008 2.,940e-007 Exposure and Dose Rates:

CEpqsura Rate in Air m!.

Rft, el 192e-vo1 4.930Q1 0 Abwrbed Doc Rota inAir rn~y/r 5AG5e-013 4-3559-012 in mrad/hr 5.405-e-01 11 4.365e-01O Deep Dose Equivalent Rate (ICRP 51 - 1q87) o Parallel Geomery m;5vIfr 6.1 37e-013 4.,945e-01 2 If 4.267e-1 2

" Opposed 5.28se-01 3 o Rotational It 4~257*-t112 o Isotropic to 4,72lo-013 3.802"-12 Shallow Dose Equirtont Rate (ICRP St - 1987) o Parallel GeomreLry mSvlhr 15532e-013 5'LZ50e012 o Opposaed to 6.290o-013 5.068e-012 o Rotiotill to 6.290Oe- 3 5.068"~1 2 o Is*opic to 5-002e-01 3 4-029ge-8I2 Efiective Dose Equivelnt Raba 1CRP 51 - 1iB7) o Antedoriftsterior Geometry rnSv/hr 5 526e-013 -4453e-.l12 o PostenrnAneferlor Is 5.09le-O013 -4iO1le-012 o Lateal 4.0i4e-01 3 3.260ewO`12 o Rotational 4, 5W4e013 3 B92e-612 o WIsoropic 4.067e-01 3 3-26-7e-012 Page I C3-10

Microghield vL0M (60S-D3C2 Radiblogical SeYicss Inc.

Page :1 Fle Ref:

DOS File ; PBE20404itS5 tate .......

Run Date: Febuary 4, 200 By  :-

R Time: 2:1 1tf PM Checktd:

Durion 000000

-CEa Trt1a Line 1.21 AF-D Deszciption; PBRF Rev Model Co4O Area Factor Calculation GoomreW. 10 - Cylirder Surrac, - Extornal Dtme point Source Dimensions Ke46ht l0ft GO in Radius 7.52 cm 3.0 in x z it 13016 cm 1524 cm 4572 oaf 411! 6.45in 5ft0. in 1 ft6.0 in r-------- -- 1 1 -

Shfalft

"'I 1.vf,  ;.MO

.9 iHI N ;

.' . 1.

s .jl N-n ,i.

y ,-! else;

'~dI i I

.' Ir.

source Inpuzt GTOUI1110 Method : AdtLaI Photorn Enorgcs CO-60 4,5000e-009 1.6650e-004 UOM6~-01 1 .2A28~e4000 Buildup That material rtalworce is. Cy* Core Inltegrationl Patamtaters Y Direolion (axial 20 Circumloiential 20 Results Fing!B Fluence Rate Exposurie- Rate Excnosre Rate Mie Vkrn 'M eu ~h 3.963e-04 3.019o-13 6.320e-12 5..830e-18. 1.027e-14 IJ732 2,430e*0, I1.630e-0 1 .489e-0 201 4e-1 1 2,6$1e.10 1.325 2,430'0+Q0 2030 2.10ge-07 4.638e-.1 1 3.659e-10 C3-11

Pawe 2 Dds Fe pW2_0404 B A$

Run Daft February 4, 2006

'Run Time 2:11 O9 sPM Durafin . W.00; Fluenc RatPE Dgoe Re , E=sv-Ae £a RRLt ph&eon w$A Mu . . 81ev ib H2 Me Ul Hn d Wft Ekii TOTAL$. 4 MNe4m 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 Ca WAS n on $Sluirday,February 4, 2005 at 2:1 1:0 PM

'Thics~

DossPoift iI I-(38&78,152A.45.72)cm Rest~iummed eovsw enerpiesl. Without f BaL.W BWudd Photon FluenceRate (flux) P1hotonalcan21eec 3.396-e-0 2.882e-00,7 Photon Energy Fiuence Rate Mevkffelsec 4. 3Qfe-008 3;596e-007 Exposure and Dose Rates:

Expoure Rate InAir nahr 7T5526-01 6.32le-010 bwrbW D eRte in Air mGyihr 8.593e-013 5.51 Be-012 Is mradlfti 6.593e-Otl 5.SI Be-010 Deep Dose Eq~ivaInf Rato GPaiallel Geometry mlivlhr 7.484e-0 13 6.265e-012 o opposedI W, 6.446e.1 S 6.394e-0l2 o Rotational 6,440e.013 5,94e-01 2 o tsoiropir, 5.758"-1 3 4.SI Be-012 Shallow Duse Equivalent Rate (ICRP 51 -187 o Parallel Geo"n*L m-Svlhr 7.967e-O 1 6.670"-12

'3 o Opposed 1.67fe.O 1$ 6,42e012 o Ratalional 7.671e-OM1 6.422e-012 o Isotropic 4!

6.10te-013 5.105e-012 Effective Dcse Equivalent Rate a Anferior/Posterimr Geoms"r mngvlhr 6. 740e-O 13 564 le-012 a PasteflarAniefior It 6.20ge-O 13 o I-oferal 4Mf38-0J13 4,13De-012 o Rotational 5.59te-O13 4.670e-012.

o l9olmprWi 4.948e-O 13 JI40e-01 Page I C3-13

FAicroShientd vL5 (9,."282)

Radiological Service, Inc.

IPar :I FHe Ref_

MS File PP80304011MS$ Date:

.1iDb: lMarch 4.2006 Run Time: 3:58:06 PM Ched_.._..

IDurOn '00:000 CaivTI~e. Line 1123 AF-A escrpion: PBRF Rev Model Oo- Ams Fauor Calculatfn Geomet. 10 -ClinderSurface - Exirnal Dose Point x

Solurce Dimnrsons HeigfA 3048acm Ift Radius 7.62 cm 3V in S PpTnts KI x y y/TI~ 91 138.78 cm 15.24 cm 45.7 cm

/1= 4 ft 6.6 in 6.0 in 1 fj.h Shields iMaenl Cyti Core 7.82 cmr Cona etk 1.8 Shield 1 8c5 am Irci Tvansition Convec, 2.4 ShiWe 3 230.48 am Conmete 2.4 Air Goo cIr ;00122 W4a1 Clad 0626 m Iron 7.86 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 ontcis : Cyl. Cor Intgralion Puramrnteri Y Declion (axi1) 20 Ccufetntia 20 Reaults

. Fluerce Rube FluenceRte E swre Rat Exosure Rate M J phobris mm ef _t_ Rh tin Build=i w ho NfhPBtrfldUo Witlh Bu.VDu 0.6938 3.963e-05 716e-14 t.178e-12 I1A0e-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 EXPosure Raeb 9 phiorsee A*ffkn'lsec Me\dViensec . iihr . m~ftr ND 13~iv W~h Bufdu INo N adiu With Bdlupu TOTALS: 4.W-0U1 92e09- T.21508 1.63le.11 1.2!68e40 C3-15

MicroShleld v5.5 J5.0"0O62) O6 MWcroShield vS.05 (5.05410:W)

RadiodOiCAl $OiS , 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 Wth BuldrJi DuEdi Photn Fluence Rate (flux) PhotonscmItWs 7.340e-009 5,723e-006 Photn Energy Fkienr& Rato MeVidan 2 sec 9.2D5e-009 7.215e-Mg Exosure and Dose Ratos:

Epsure Rte in Air mlW 1.631e-01 1 1.268e-010 AbmrW Dgw Rabe inAir mGcyihr 1.424"13 1.107e-012

,i mradibr 1424e-41 I 1.7lOe*-010 Doup Dow Equialent Rato (ICRP 5t - 1987) o Parallel Geometry mnvWhr 1.617e-013 1.256e-M12 11 t.393e-01 3 1.082e-12 o Oppo o Rot3atonal 1,393e0013 1,0Ze-012 G Isotropic 1,244e013 9.66le-013 Shallow Dose Equivalent Rates (ICRP S1 - 1987) o Parallel Gdomtry mSvlhr 1,721013 1.338e-012 4 Opposed I1 t.857e-013 1.288e-12 o Rotabonal t.67C.01 $ 1,$e-012 a lsoerapiS f.38ie013 1.024e-012 Efeive Dose Equivalent Ralo (ICRP 6S- 1i-7) oAnteriodPoeterior Geomety m~Whr 1,.45"13 1131e-012 o Posterior/Anterlor I 1.34le 13 1.042e-012 o LWI1l t.057e-013 8.283e-013 a Rotatbnal 12,a08"1 3 9,382e-13 n Isoir cp 1.06e-013 8.301e-013 Page I C3-16

N HcraSliiokd v&DU (9.0640382)

Racriological Servirms, Wn.

Pop :1 Fit Ref:

DO$ File : PS020406 MAS$ Date:

Run nate:- Fetbuary4,2O0G By:

R Mm: 2;26;44 PM Mucked:

Du'tm:00:00:00 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,irco Dimon-ona, Reight 6. cm 2fr Radius 7.82 cm 3,0 in Dama Pointa x Y A1 135.78 cm 3(148 rm 45.7 c Aft 6.S in 1ft I fi 6.011i ett

$hie4" I .66 cm Iror I 7.85 TPansfitkn Concrok-t 2.4 Shieki 3 '0.48 cm Concretf t 2.4 Air Gap A~r M.1002 Wall Glad .025 cm Ifon 7.86 source Input Giv Iimg Mefiodt. Actual Photorn Energies Nucihde curies beocquerols, LQCi/cx BQA=a CQ.00 1.31-MOe911 4 ~655-QWi 4.5000e900 I 50,90-094

.Buildup The materia reftranca Is; CyL.Core hIn~rnatlon Parameters.

Y Ofreclion (axiaI) 20 Citcumfientfiai 20 Ene M N2 UR -a- a NffiWfih Buiiduo C.8938 7.W2e-65 i-383e-13 2.2.6le-12 2.670e-116 4.3650-15 6S576-09 S  : 5840e-06 l,225e-111 1.0414.-4 1.3325 4.860e-01 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.

Fluence Rat Fluence Rate EXDOsure Rnte Exposure Rate Mevkcntfte?, e imtr act

-dNouif With Buildup WBuildup With Buildue TOTALS: 9.720e-01 11,787e-8 1.395e-07 3.135e 11 2-45o-10

_I

.r

?

C3-18

MkmrShleld V5fl5 (SA)5-00362) 02M=6 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 Ch3 vMs rn on Saturday, Februvy 4, 2005 at 2~25:44 PM U4 cse Doae Point # I - (138.78,304845.7) cm IRolr~bisummad mm =

Photon F~luence Rate (flux) Photonskrnt fsec 1.41 1e-008 1.11O6c4307 Photon Erorgy. Ftunce Rate MeVCrmn"Ieg 1.787e-008 I .39,.ev0Q7 Expos~ure~ and Dose Rob"s:

EiposurefRarte in Air mnRIhr 3.135e-01 I 2.450e-010 Absorbe'd Dose Rati in Air MGYftir 2,73?e-01 3 2,1 39e-012 II mrad~hr 2.737"-1 t 2.139e-010 Deep Dowe Equivalent Rate Q*CRIP 51 - 1G87) c Parallel Geomewry I mSvlhr 3.108e-01 3 2A42M-012 Oopposed II 2.676e-01 3 2.091le-012 o Rotatiknal 2,675e-01 3 2,09 1e-012 o Isotropic 2.39te-013 I.M6B-012 Shalv Doise Equivalent RaF (ICRP SI-I 7 a Parael Geometry mnSvhr 3t$Oe.01 3 2.66$e.012 o Opposed I,

S.lBOft01 3 2A490-012 a RotaUional 3.185e-013 2.490e-012 o Isotropi 2.533e-O1 3 I.979e-012 Effective Do Equivalent Rate (ICRP 51 - 1W7) a AntehiorPosterior Geometry 2.796e0"13 2.187,v-012 o Posterior/Antenor 2.578e-01 3 2.0114e-0112 o Lateral 2.O50e-01 3 1.601e-012 o Rotational It 2.32te.-013 I1.814e0112 o Isotropic of 2,054."-13 1 AO5-tO12 Page I C3-19

Mrcwshield vL& (fSU4D35 RadilorZgal Services Inc.

Pae :1 File Ref_

VOS file: P820447,M$5 Date:

Run Date: February 4, 2006 By_

R ftii: 224-25 PM C;her$ko; Duration : &000:0O Cue Tide: Um 1.23 AF-C Dscription.: PBRF Rev Model Co OArea Factor Calculdion Grnetry 10 -t lindor Surface - External Dose Point Source Dimensions Height 124 =n, 5 ft 0.0 in Radius 7.62 im 3-0in Dse Points

1. 1 138.78 cm . 76.2 cm 45.7 cm 41t6. 6In 2 ft:.O in I ft6.0 in Shields S

Shield Narn Diensein Mate iWI Density 7.V =cm Eonr I 3T 11.8 Szbiled I .es Cr Iroi 7.8.

Tranaion Conci ,te 2.4

Shield 3 X4&cmn onur iAo 2.4 Air Gsp Air HN0 22 Wall Cwad .025cm Iro I7.86 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 Iht ircton ion Parameters

.(amil) 20 Circufemterenw, 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 Fluencs Rate, Fience Rate EipoMure Raoe Ex00ure Ftt Ml tphoton ec PItmtJ's~e- mmihr 3.N9epO fout W4u iln TOTALS: 2.430eUO0 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 Photon Flurenoe Rate (flux) Photor~nsimsec 2.786e-008 2.252e-WO Photon Energy Fluence Rate Meavelosel: 3.529c-0O3 2.84 le-007 Exposure and Dose Rates:

EPosure Rate InAir MMdh 61-194a-O1 1 4.99De-Olo Abrarbed Dm Rtat in Air rroGyihr 5.407e-0l13 4.356e.0112 il rnrad/hr 5,407e-01 1 4.355e-0 10 Deep Dose Equwalent Rate (ICRP 61 - 1987) o Parallel Geomnety mSvfhr 5; 138e-a1 3 4,946e.012 0 oppoSed ,. 5.287e-O013 4.25ge-012 o Rotonal 6.28a7e-013 4.268e-12 o Isotropic 4,723eU I 3 3.803e-012 Sh~allow Dose Equivalent Rate (GCRP 61 1§87) o Par~allel Geometry mSvAr 15534e..013 5266"012 I,

oOpposed 6.292e-01 3 5.070L-012 o Rotational e292e-01 3 S,070e-012.

o11Sotopic 5..003e-01 3 4.030e-012 Effectyse Dose Equivalent Rate, O1CRP 61 - M7 o Anterior1Posterior G~eometry m~vlhr 4.454e-012 OPosteriar/~nlefior tv 5.092e-013 4,1020e-012 o Lateral 4O05e-O1 3 3.281"-12 oRotational 4.586e-01 3 3.693e-012 o Isotropic 4,06 e-O1 3 3.268e-012 Page I C3-22

lMicrogbield Y5.05 (5-4003,2) ftdioloqlca1 irvkes, Inc Pae :1 Fkuf:

DO$ file PEOM 8.M$5 RUrLDate Febrdafy 4,2006 BY:

FZRre: 2:23:0 PIA Checked__ ._.

Durtofn . MOO;N Case Tile: Line 1.23 AF)

DescrtiW: PBRF R1ev Model Co4l Arta Factor Calculation Goamntry. 10 - Cytindr Surface -Extemal Dos Polnt Source Dllmewsorks

• Height l0ft O. in Radius 7112-cm 3.0n Dose Points X -y

1. 1 13878 cm t52.4 ctn 4$.7 cm r_. .- _4ft6. 6in 5fl.0 in 1 1t 6.0 n iI f 1 -1 Shield Name shelirs Dimension Mateeria del QpnsiW W. C~are 7.62cm 2 Caroc4 E 1.8 1ield 1 65=> Iro N 7,86 Tramsiltcni Concretx? 2.4 Sbitld 3 30.48 cm, Concvel , 24 Air Gap Air 0.00122 Wall C1 .025 cm Vron 7.80 SourCe Input Groupino Method : Actual Phtton Enarjies Uuctide curies becquerels Ccinz Bg1omn c O.56BE-Q1 2420+pO 4.5M.g-MQ 1.0e5WO4 BuiNdup The matial ratetrnce Ia Cyl. Core r

ln4sbrtfn paramraete Y Direcfton {axia) 20 Circumferenual 20 RU 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 uenw PKe..

FlBi 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 O2U48 IWicroleSd 6.K40 IE-OM Converamin of cdui ed expain*afr to 40sa FLE. CMIUSSUATA02040LS5 Cas*e Trh LUne 1.Z3 AF-Thihcase was rnm an Sahmrd, ftiriwy 4,2 at 2:220 PM Dow Point I 1- (38A71SMA5A.7) can f1"Uh iFuumnzd *zr _ XMh (luIaduco Photon FRoeie Rate (flux) Photomi,9/s 2AO53o-O07 Phhm Emg Fkolxm RaW Mav/mftec 4.305e-008 3.e59e-DO7 Ekosur eond Dws R$w tosure Rate inAWf Mtr7 7.5-4e011 .322e0010 Adwba DQw R inir nIRYAW 6 $*e 13 5$5190-0122 WI mOganu

6. 41 I 5.514e-O10 Dow Dos Eqtivalen4 Rs% (RP 51 - 1987 o Piva1e m5S~r 7.487e-013 6.27e-012 o Opposed nt 644k-013 5,395o-012 o RoeonJ 6 4-e013 5,395e-012 a 1rorpi 5170-c013 4.619e-12 Shallow Dose Equivatmd Rate (ICRP St - 1I87) o Pwfalw Ceomry mSv/hr I 9$e.013 (337,67Ze12 o0 Ooosed 7.674e-013 6.423.12 o Retational 7.674e-013 6.423e-Oi 2 o kgomvic It e. 1g03i 3 5.1O5*.g1 Z (MRP 6i - i W) ioArweiortftsteuy Gemetiy mSrdhr 6.742et13 5.843.e- 12 m

to PostefKodArcemor 6 211eQ13 5,197?01i2 0 L-viei* 4.14013 4.131#41.2 5'5032 013 4.6790412 0 P-ropc 4.95013 4 141.012 page I C3-25

Mrcroftield V6.05 (5.05-00362)

Radiab~ical Sigivites, Inc..

Page :1 F&e W-:

DiO$ File : P8020409.LtS5 .Date:

Run Date: February 4,2006 By:,

R rime; 2:30:29 PM ChedW:

Duration :OG0:00U Case Tide: LUne 1.24 AF.A

Description:

ERPF Rev Model Co4D Area Factor Calculation Gomet 10 -Cylor Surace - External DoSe Point SoLirco Dimensimrs I-Iebht 30AB cm I ft Radius 3.81 cm I DQm P91fl x z

1. 1 134.Olcxam 15.24 cm 91.44 cm 4 It 5.1 in 6.0 in 3sf Shields Shield RaI 3801 cm' ConcFid

.65 cm Ifor 7.86 Tfansmtin Concrca ,i 24 Shield 3 10.4a cmConcrehB 2.4 Air Gop Air 0,00122 Wag Clad .025 cm Iron 7-86 Source Input Gruping Method :Actual1Phoo Wsir Bcalerr C"U6 3.2835e.012, 1,214ge-001 4.150O~e.0O 1.$50e-004 RUMlUP

.Tho mawteial ruenem toIs ; cyt. Core lntegration Parametem VDired~o" Cagat0 20 CkrwnfecantWa 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 11732 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 :QROOM a Humus Rarte BenlatI E iosure Rfeht Fxstae &It "tlr.Apls mFil r No Buildu= 3eah Slj No Bujdw vft Bumup TOTALS: 2.430e-O1 2.491e09 2.153e48 4.371e12 3,78le-11 C3-27

021040 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 Photon Fkuence Rate (flux) Phoatonsk1cn&iec 1.06Se.O00 I .70ee.-0O Photon EneVy Fluenob Rate MovlcnWeMc 2-49le-09 2.1 53o-008 Exposure and Dose Rates:

tvotsure Rate inAir #Rlhr 4.37 le-0 12 3.78 le-01 I Absorbed Dose Rats inAir rnGyAhir 3.816e-014 3.30!e-013 If mraovr $416e.-OI2 3.301eU01 1 Dvep Dose Equivlcrnt Rate, (ICRP SI - 1987) o,Parallel Geometry rnSv/hr 4.332e-0 14 3.7488-O013 o Opposed 3.731e..014 3.227e-0Ol3 o Rcotal~nal 3.73le-014 3.227e-0 13 o Isotropic 3.333e-9I14 2.882e-01 3 Shallow Dose Equivalent Raba (ICRP 51 - '97 o Parallel Geometry rn~vJhr 4.BI11e-14 3.ggle-013

- aOpposed if 4A4%e-014 3,642e.aI13

• Rchtafnal 4.-440e-014 3.842e-0-13 o ISGotropi 3.~15e-014 1Q54e-01 3 Effactive Dose Equivalant Rate (ICRP 51 - 1987) o,Arvienorifatstenor Geomeriey m~vi'hr 3.90la-014 3.375e-0 13 o PostenrlorAnterlor I' 3.694e-014 3.1 0§e-01 3 o Lalefal !i 2,656e.O14 2,47le-013 o,Rutational 3.23ge-014 2.79Xe-013 o ksotropic ,gtWe"14 a 4?770-01 Page I C3-28

Uicro=Shied vL5.005-003&2)

RAdi0Iogika1 Svietos 1 Inc..

Pae .:1 - FRe Rf:

D)O8 Fite: PEO2O4110.tS5 Dae:_

Rurt Date: Februl ity4, 2006 By:

R Frwe: 140:6$SPM Chocked:

Durfation; Qi;W.Q Case Tide: Une 1.24 AF-B Descr;iP,: PBRF Rev ftadell Co4O Ama FactDr Calculawion IGomatry: 10 -CyUndor Suface - Exernal Dose foirnt Source Dimensions Heigt 60.96 cm 2ft lRadftsu 3.81 cm 1.5 in D P;Inb x y a1 134.97 r 30,4o cm 91,44 Otl 4 ft 5.Ilin 1ft 3ft Shlbeds ria1 Cyl. Core 3.81 C Cam 1.8

• .-.; *. .$hie& I .66 cm Ir0xI 7.8$

Transtkn  ; 2.4 Shield 3 22.4 Air Gap dRJr 0.00122 Wall Clad M2aii Iion 7.86 Source Input Grouplnn M satod  : Atual Ph*Wn Energies kiwueelsn LJ;ikn rcm2 Co & 565fe-012 2.429Ee-001 4.500DD-00 1.5ft,004

- r nuildup Tho vhat~3tfl ruferuncc: Is; Cyl. Core Ilntegtion Parameters Y Diredicon (8ai 20 Cktun*fenbia 20 Rosufts Riuence; LaB E Rat EBuFBsrel Psute Exmura Re Me WheISI Mevkrfn 2 M s ME 1210ReJmik1U NohE3;UD BUilUlD With Builft 3.Vt33e-05 0145.2160-13 5...46.47 1,142u3-$5 1.1732 2 43Ae- I .81Ee-9 172$-08 3.235e-t2 3.083e- 1 1.3325 Z.A -01 190514E 2,45ft-00 0..12M 4.20':4 C3-29

Page :2 DXS File PB0204O.hlSS Run DaI: Febmry4, 2008 Run T1m: 240-59 PM DLurelin :QQ MOW

.. AL Fim-wgn lt.e M Fluence MaE Expsure fRtka Exposure Rate MevIcmatsec aMeV te mer

_mRhr No ftuildug YM Build= wAtid Bull 1!OTAL$: 4.$60,-1 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 x

t }

a t~4 ,k- 'p - -4 - -?

It-  : ,,-,

".D-:I1i C3-31

MlcroShield vSD53 (5.05-0362) O04106 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 RFe-i;1AS ISUMMEd OVKef*Mr: Whodit Photon Fluence Rate (fluxi) .Photondalcmqwc 3.801 e-000 3.Mte-CCIS Phatb Energy Fimnme Rate MOVAC.111sec 4,819c-009 4.l84-008 xWposum and Dose Rae:

Exposure Rate in Air mR/hr 8.456e.02 7.349ei-Ol1 Absorbed Dose Rat in Air 7.38te-014 6.4 16e-0t3

., 7,38t"-12 56416e-0I 1 Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallef Geometry m5Whlr 8,379e-14 7 285e-01f3 o O~posew 7.217e-014 6.272e-013 o Rotationat 7,21 7'e-4 $,272e-Wt o Isotropic 6,447.-O4 5&,2M-013 Sfallow DOSe Equivalent Rab (FCRP 51 -1Q87 o Paiallel Geometry mSvlhr 8.920"1O4 7.7550-01l3 o Opposed 'I 8.589e-t14 7.467e-013 4 RoWlional ii 8,58ge-014 7A407e-013 o hotropic 6.830"-14 5.gM3 2-13 Effective Dose Equivalent R* .(ICRP 6i -iw o Anerior/Posterior Geomety m~vlhr 7.546f.O014 5155ge-01$

o PostenrJAnterior 6.95 le-014 6.04 1e-01 3 oLata1 II 5.5299-0l14 4.S03e-013 o Rotational 6.259ge-014 S.44Oe.013 OIsoropic 15.WC.914 44~14-1 ;

Pago i C3-32

MIkShieMd vS.05 I5.O-S0D362)

MLdlological Services, Inc.

Page :1 Fri Ref:

DO$ File pSWO411M$5 Run Date: February 4. 2006 By:

R Time R24321 PF Chce, Duration :0:0000 Case Tie: Line C4 AFZ Description PFBRF ROV MOlW GaG Area Factor Caiculation Geomtr; S

10 - OylindIr I

Suface -Extemal Dosa Point Smarce Dkmnnsions H-eight 152.4v 5 fi 0.0 in Radius 3.81 cm 1.5in Dose Points y z

• 1 134.97 cM 7c2 cun 91.44cm 4 ft 5,, in 2 ft6.0 In hlds JILl §Lield Namre Up. L;f Shield 1 Transition Shiek 3 Dimension 3.81 cmr

.5 cm' 30.4a CMl

-j; Qo Ifrol CneI Ii I

X lens1.B 7.8" 2.4 Air Gap Alr 0.0012 VWal Clad .025 cm Iron 786 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) 20 Or. ffntat, 20 Resldts FluerKe-Rate F pRu a E uRt 2

/se ~ leVkm Em'e M'L mf No Buildup W0 99Oiu 91909e-.D5 1O018e14 i19w4e-12 1.1732 6.074e-o1 3.673e-09 3.5me-O 6.&5e4-12 GAZ7l-11 1.3325 6.074e0 1 U158o-O0 6.164e-M 1.068e-11 8.9e59-1I C3-33

Page :2 DOQ8 File: PB020411.MSS Run Date: FPebray4, 200o Run Time: 2:43:21 PM Duration : 00:00.00 uuenstab Fsence Rate Exposure Rate Exmosurm Rt meylaiwsec Mievefe'e ~ ,m No Buid=t s ty Na Buddup With B4Edup TOTALS-: 1.215e+00 9.831e-0 8.360M6 1.725e-11 1.539e-10 C3-34

DOS w ieP80ZO4, 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) O.24I0 Mrshield V.6 (9.04,ml)

Riodogleall WrA , In.

Convereton of caciulodexpmure In S1r docse 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 - (134J76.L21.44) cm Re= (Summed Emie) UlOJl WMht Wo OuouiM2 Photon Fluence Rate (flux) Photinsicmyiaee 7.702040 6.941e008 Photon Enery FMonfc Rat MOeV/crrftf 9,831e-009 $,.760e-OO Exposure and Dose Rates:

Evosure Rate inAir mPlhr 1.725eO1 1 1.53geo-10 Absorbed Dose Rate in Air 1.506e-103 1.343e-012 mradlbr 1506e.V1 1 1,343e-010 Deep Doee Equivalent Rate (ICRP 51 - 1987) o Parallei Geometry mSv/hr 1.709e13 1.525e-012 0 OPposed 1.472e-013 1.31a3e012 o Rotational I .472e 013 1.313e-012 o Isolropic 1.315e-013 1.173e-012 Shallow Dose Equivalent Rate (ICRP Si1 987) o ParaIl Georometry mSvlhr 1.820e-013 1.624e-012 i ,752e-1 3 1,56se-0h o Rotational 1 .752e-013 1.563e-G12 o isotlopic 1.393e-O113 1.243e-012 Effectie Dose Equvalnt Riat (ICRP 51 -197) o AnteriodPosterior Geomey m5Whr 1.539",13 1.373e-012 o Posterior/Anterlor 1.418e-013 i.265e-012 o La1fal t 128"13 1 0O$e-012 o Rotatiofat, 1.277e-013 1.13go-012 o sotropic 1.130"e13 1.o00e-012 PagE? I C3-36

Micr0hield VS.05 (5.5-0036 JRfid hogical Services, Inc.

Poge :1 File W-:_

DO$ FMe: PB32O4121ShS Date:

Run Date: Ftbiuvry 4, 200 By, R rine: 2:4433 PM Checked_:

Duration: 0000:00 Case Titlse Une 124 AFO DESstrion: PBRF Riv Mod§e Co4O Area Faitor Calculaton Gwnetry 10 -Cylinder Swfate - Extamal Dose PRAnt irue Vbnalnons

• 1 304.8 cm 10 ft 0.0 in 3.81 cm 1-5 in Doe Points y

-1 1X97 Cm 152.4 cm 9144cm 4 fIt .1 in 5 ft0.0in 3 ft

'k :,, zk,, .-

,4 -

"F- - -I nr -- Ghuld Oa=e  ; Shle1ds iMensic a M1 Densit Uy1. 4M 3.8,1.cmw #0 Shield I .BS cm Iro ft 7.86 reIe 2A4 Shield33 IOAS cm Caona rete 2.4 Air Gap Ali r 0.0022 Wall Glad .025 m Irun 7.86 Soume Input Grouping Meffth -.A:tual Photzn EnebE" Nuclde curies jbA C"0 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) 20 Cirifemnlhia 20 Results EFwne nF Rste kfnefe Fxnmn atme Rt Fxnrmure. Rat.p MeVdcmlsec M aga 01M A=

N Pullduo Wh BA He Puiug Wfth Builup 1$81e.04 7.18e-14 1.483e-12 1.3 -16 2.863e-15 1-1732 1.215e100 4,612e-09 4.692e-03 8.242e- 12 8.384e-11 1-332S 1.216"00 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 e m Wmynr I BuIld2 O -Wj1 Buildu No 1eUP Nlo FkdaM WiO TOTALS; 2A430e+00 1,244eW 1,15fe-07 2.482e11 2.021e,40 C3-38

MleroShield vS..06 15O.-OO362) 02O410S 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 ResuIts (Summed over eneagieoe Without Wfth Buildupg Photon Fluence Rate (flux) Pholcns~crrifte* S.6O5e-009 9Il1 1e-008.

Photon Energy Fkmance Rate MeV/cmwlaec 1-244e-Q0ft 1.161e-007 Exposure sid Dose Rates:

Exposure Rate in Air mRhr 2.182e-011I 2.021"-10 Absorbed Dose Rate in Air rnGyfti 1.905e-011 I .765L-012 avadthr 1 9Ose-O11 I ,7$e-010 Deep Dose Equivalent Rate Q1CRP SI - 1q87) a Parallel Geomnetry m~vlhr 2103e-013 2,004"-12 o Opposed 'I 1.8f1e-01 3 1.725e-012 o Rotatonal

'I 1.863e-013 I .725e-01 2 o Isotropic 1,554e~1 t .541 e.i12 Stallow Dose Equivalent Rato (ICRP 51 - 1987) o Parallel Geometry mr.v/hr 2.302,e-013 2.1 33e-0 12 o Oposed It 2-21'7e-013 2.064e-O012 o Rotationat 2.217e-013 2.054e-012 o korlpic 1.76313-013 1.633e-0112 Effetve Dose Equivalent Rate (ICRP St -1987) o Antefiort'sterior Geoetry mSvlhr 11948e.01 3 1 .804"-12 o PostedorfAnteflor 1794e-013 t,662e-012 o Lateral p. 1A27s-01 3 t.32le-012 o Rotational tGI161-013 I .496e12341 o Isotropic I#

1A$,Ie-Q~A! 1,734-012 Page 1 C3-39

MicroShield v5IOS (USMOO362)

Radiological Services, Inc.

NW Pegg :1 File Ref:__ __

DO$ Fle:t PBO20413 IMSS Date,____

Run Dab:. Fobruary4, 2006 By:_

.R Tkhe: 2820 PM Ohegkud; Duration ; Q;Q.QQQQ cab ruTbe: uL 1,641 AF-A

Description:

PBRF Rev Model Co60 Area Factor Calcuaiofu GeomB#ry. 10 - Cylinder Surface - External Dow5 Point SOtj irce fntenslons Height 30.48 cm i ft Radiuts 10.116Cm 4,9 In DoEss Pohits x Y z

N1 4132 an 1524 cm 4 ft 7.6 ini 8.0 in 3fIt ShiIelds Shield Nanie, Dimension Mtet ia1I Densit Cyl COre -,ID.1 CT Conel 71t0 1.B5

-Shield I 65 Cm Iror Tiansibton concrOt 14 2

$1h1eWc3 OMA cm Congoi Air Gap Air 0.00122 Wall Clad .025 cm iron 7.86 Source Input Gsouplag,Method : Actual Photon Energies Nuclide curies _ cikm2 ____

CO-60 8.735590e012 3.2397a-0G1 4.50W04M8O 1.6650e-004 Buildup The mnate~bI akrernce is : Cyi. Core Integration Purrnveterm YDirection (axial) 20 CkdUrnforenIdat -20 Rasults EMNwv ___ leneBg Emosgre Rao Exyp[ul;&ILE E22

.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 -1AS"-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* FluenuB&k Exam= 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

02A041 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

,E22fti fSummed ove~eir-ema UnitI Without With Bu§idup 2.78ge-OO8 Photon Fluence Rate (flux)

Photon Energy Fluence Rate 1MOVIW/~Saf Phto~nalkm'sae 3.083e-000 3-910Ge-O0Q 3.=2e-008 Empsura and Dose Ratos:

EVosure Rate in Air .'wPJhr &660"-12 &182" 11 Absorbed Dose Rate in Air mGyMr 5.90ge-01 4 5.397e-01 3 II mraoft S0898e412 $59e-0111 Dep Dose EQuivaalent Rate (ICRP &1-187 o Parallel Geometry mSvlhr 6799".1 4 6I5.Q12,Be03 o Opposed BP 5. 56"-O14 5.276e-0113 o Rotatrinal S. M5e-O1 4 6&276"1O3 a lsoIropsir 5.231 0-014 4713e.013 Shallow Dose Equiv.at Rate (ICRP 51 - 1987) o Parallel Geometry m~vlhr T2376.0114 6,524e-O1 3 II o Opposad 6.908e-014 6.281le-013

'I o Rotational e.968e.0114 6,281e-O13 of o ksotropic 5.542"-14. 4.994e-013 Eifedvce Dos Equiva1#nt Rob~e (ICRP Si - 10B7) o Ante ioro~oterior Geomnetty m~v/hr 6.122e014 ioPosterioc/Anterior ml 5,640e-014 5.082t-01 3 o La1efal 4.486e-014 4.04 la-0113 o Rotational 5.079e-01 4 4.976e-0113 olsotroic 4.49$".1 4 Page I C3-42

Micn)Sh~ield YvS.0 (SAOS0362)

Pe~e

1Radio4Logal Services, Inc. File Ref:

DO~$ File ;PB0,20414.MSS Date:

Run IDate: February 4, 2006 By:____

R Tsn,3-00:06PA Checked:____

Dutratioin : 00 00:00 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 Source Dimensions

• Height I609.91 cm 2ft Radius 10. 15cm Doze Points z

1. 1 141.32 cm 30A48cm 191 .44 cmn 4fi7.6ir 1t 3 It I _ hields J I I i Shield Name Cyl. Core I)inwDmsio 1Q.$6cm9 Materis Conoret, I , , - - ,I Shield 1 .65 cm Iron 7.86 Tramsiion Corwcel La 2.4 Shield 3 30.48 cmr Concret oi 2A4 Air GP Air P.00 122 Wall Clad .025 cmn Iron 7.W8 Source Input Gruspng Mathod: Actual Photon Enatgks Nc-do 1.6650e-004 1.7512e-011 6.47944001 4.5000e-009 RdIldup Tho enaterial ref eronco is : Cyll Cane

.btegration Pwairnsters; YDirection (AxWa1 20 Circumferential 20 Enerpy Site=Rata Fkluence, Rate ExoaoureRe ExmsRate photonase M 13&uo NQ PuildWitWith SLA~j 0.693B L1.057e-0'4 4.615ie-14 9.0850-13 8.9100-IT 1.754e-15 1.1732 6.47ge-O1 20 7- 9 2.795e-S 6.035e- 12 4.94e411 1.3325 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 15WBtisu0 Buildup TDOTALS; 14290+90 7.550e-09 6.6350- 4B1.326o-l1 142ole-10 C3-44

M-cmshleld v6.6 O5 .5-OO362) 02AG405 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$a 3:0O0:06 PM Dose Pcidt #I 1-141.322 DA11tOl 44) cm Photon Fluenoe Rate (flux) Photonakim'Isee 5.4 16e-QO$

Photon Energy Fkmnce Rate 7.560"0O9 6M38e4)DB Exposure and Dose Rates:

Exposure Rate in Air mR~th 1.326e-01 I 1.201le-010 Absorbed Dose Rits inAir mGy~ir 1.I5Me-01 1 I .Q4e-012 II mrad~hr 11-M48-01O Deep Dose Equivalent Rate (ICRP 51 - 1987) o Parallel Geometry 1.314c-013 1.19OeN012 o Coosed I. 132e.-013 1.025e-012 o Rotatonal 1,132"1 3 I.fl2e-012 a Isotropic 1.01 Ie-0113 9,154-01 3 Shallow Dose Equivalent Rate ui Parallef Geometry m-Svlhr 1.399e-013 1.267e-012 o Opposed of I1.347e.OI3 1.220e,012 o RMational 1,347"-13 1.220e-012 oI Wfpia 1.07le-013 9.700e-01 3 Vfaed~a Dose Equivalent Rate o AnteriortPosterior Geometry m~vlhr 1,154"'I3 1.072e-012 o Postenor/Anterior 1.090e-013 9 872e.013

.o Lalefal 8.674e-014 7.848e-013 ci Rotalfonat ff 9.810e~014 8A80e-013 o Isotropic U e9114 T665e-013 Page 1 C3-45

MicraShield vY5(1 (5M-00362)

Radlologlal Sorvion, ln Page :1 File Ref:

DOS Fil: PBO20415.MS5 Dae__

Run Dat: Februay 4. 2006 By:

R 'rme: 3:012;3PM Checked, Duation 00I0O Case Ifriw Unea 1S41 AF-C IDeawiptiow. PBRF Rev Mlodl Co-SO Arma Factor Calculaon Geometry: 10 - Cylrtftr Surface - External Dose Paint UfI irce Dimensions Haight 1 1524 cm ft0.0 in Radius 10.15 = 4.0 in DmQ Point z

1. 1 141.32 cm p6.2 cro 91.44 cn 4 ft 7.61i 2 ft0.0 in 3 ft Sields;

!Sield Nai Qinvnsnion, Mgt3 r Cyl.Coro O.16 Icm, -CncIRte 1.B Shietd I .65 cm lIro i1 7.86 Tran5i;on Concn ete 2.4

$hief 3 334.0 cm CoWDte 2.1 Air Gap Air O.O122 Well Clad .025 cm Iron 7.86 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[) 20 Circunmewtial 20 Resufts Enerav F]uence. IRat Fkjenoe Roe F =S re &.e Exposureb RXt Rhotongfee W4,/Ovcm&rs aw- i t3Xe ml;t NO Rui~ldu Wh QUkw No Builduo Wdth R;IduW 0,693a 2.-642e.4 68 99f-14 1.8228-12 1i.737e-16 3.529e-15 1.1732 -7f23e-09 SA.07e-0 1,19e-11 1.A O1 1.3325 1.620e*tOO 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 Fluenp ae F-luexc R& I =me Ex~m ab e--o ph meVtownsec MeVhmtlffct mR/hr wth 1.D.&A up Ng Md 2Imth Bidup TOTALS: 3.240e400 1.5361 1,427&7 2.699-11 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 (tSurnmedover enemi UnsWtout Wit SuB3Wp BQuidj Photon Fluenoe Rate (flux) Photonsfan 2 ksec 1.213e-0WB 1.30-07 Photon Enary F'luence Rate Mevkniset 1;53&0-D08 1.427e"07 Epoure and Dose Rates:

,ure Rate in Air mR/hr 2.6Q9e-D1 1 2.0Be-010 Absorbed Dose Rate in Air mGylhr 2.36e-.013 2.188e-012 II mr.~hf 2,35f-t1 1 2. 180"10 DeMp Doe Euivaleot Rate (ICRP 51 - 1987) o Parallel Geometry ,nm~hr 2.675-o 1;3 2.484e-O12 o Opposed 2.314e-f13 2. 13e-012 oRotational 2.304e-01 3 2.139,e-012 o Istropic 2.05o-ItJ3 1.910ei-012

hallow Dose Equivalent Rate (ICRP 51 - 1987) o Pamilet Geometry nirnSvlhr 2.847"-O1 2.644e-012 o Opposed 2.42e-013 2.5We-012 o Rotional f. 2.546e-012 o IsoAorpic 1184e-013 2.024e"12 Effev Dose Equivaeint Rate (ICRP 6t - 187) o AnterioPasteior Geoetxy mSvYhr 2,40 013 2.237e-012

'I o PosteriorrAnterlor 2.21 9" 13 2.060e-012 o Latel 1.76e-013 .ue-012 o Rotaiional 1I.9§8e.1 1,09813 3 1.865e.012 o Isotropic ,410-M12 Page 1 C3-48

MicroShield. V5.05 fSJ6-0362J Rafi~ologlicall SenrvceS1 Inc.

.Page :1I Fie Ref:

DO$ File.- P1B020416.IVISS Dare: _

Run Daft: Febtuary 4.2006 By:

R' Tkw :302:23 Ph Chocked:

Dufaffon 0000-00 Case Thitl: LUne 1.S41 AF-fi

Description:

PBRF Rev Model Co-O AMeA Factor Cac~llatarkn Goothaty: 10 . CylInder Swftce -Extarnal DMOs Point Source Dimension~s a0 Height Z04.8 rn 10ft 0-0 in Rajdius 4.0 in Dose Points

1. 1 141.32 Icm 152.4 cm OfA4 cm N~I, 4 It 7,~6lIn 5ft 0.mi 31t A1 Shields I 711 - S hia-id Nani C l.Core 10.16 cWu Conci efde. 1.8

.!ffcm rrnO Tr.ansition Cowcete 2.4 Shield 3 30.A8 cm Cow,~ete 2.4 Air~Op Air Q.&0122 Wall Clad .025 cm lroqm 7.,

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 YDirection (aXial) 20 Cicumferential 20 IResults FlineRtuence Rate fouR . Rt Exoosure Rate ohotonaftec fAeVkm~ispei'c==M- B No Buildwuo Bguif No Buildwi With Buildup 7 .6938 5.285e-04 1.0740-3 2.262e&12 . 2.0fe-16 4.350e-15 V1732 3.2400+01) 7.136e-09 7.53se-O8 1.276e-,11 1.347e-1O t13325 3.240eO00 1.22se-O8 1.111leZ 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 Flnce 1%Rate 1 os 1 Exposure Fog mR/hr No Builduw Ab.h R"MutL Wh Bii7uO TOTAL: 6,480e+O0 1.940-OB 1,865.e07 3.403e-1 1 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) Ptbotnstmklsec I 6geOU I A770-007 Photon Energy Fluenoc Rate MeVknifsec 1.940e-008 I .665e0-007 Exposure and: Dose Rates:

Evosure FRe* InAir mRflw 3.403"-1 I 3.275e-010 Absorbed Dose Rate in Air mGy/hr 2.07 e-01 3 2.8.Sge-012 mradthr 2,971 "-0 I 2 659e-010 Deep Dose Equhialonl Rati o Parallel Geometry 3.372"-1 3 3.246e-012 0 Opposed 'I 2.905e-01 3 2.795e0.012 o Rotational 2.900e-01 3 2.7VSe.012 o lsotropic ..

2.695e..O1 3 2.4970e012 Shallow Dow EquivalarA Rato (ICRP 51 - 1987) o Parallel Geometry $.$$Oe-01 3 $A46e.012 3.457e-01 3 3.327e-012 C. Motoal 4' 3.4E57e-01 3 3.327e-(Q12 o Isotropic 2.749-01 3 2.645o-012 Effed&ve Dose Equivalernt Rat (ICRP 51 -1987) o AnleroriPoserior Geometry mSvlr 3.037'e-01 3 2 .92.3e-012 o PosweriorlAnlerior 'i 2.78501 3 2.692e-0112 o Latetal .4 2.226"-1 3 2.141e-12 oRotational 2,519e-013 2A424e-%~012 o Isotropic 2.230e-01 3 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 Q

im C/

E; cBL REACTOR BUILDING BUILDING No. 1111 aev. Mezznin

MA" GLENN RESEARCH CENTER z PLUM BROOK STATION 1 SANDUSKY, OHIO 170 CZ

N-

u 2

Q'il cl lz I IICLASS 1 q- _ CLASS 2

_ CLASS 3 "I

X tz 64 C

Uc Mo To m

a+ .

11 REACTOR BUILDING BUILDING No. 1111 Elev. 0-0

NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO to

k

of m

I, 12.

PI 2 3

To P-1 C

n

?z c:

GM 4:1 REACTOR BUILDING BUILDING No. 111 Rev. -15W4 0W'3?

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION 0 SANDUSKY, OHIO 0

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Eldev. -WS Cicf

0 0

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION 0 SANDUSKY, OHIO z>0 Dt Z

~w+/-I S

tv

= CLASS D~ _ CLASS 2 Io N

i Cl ASS M

ON at

_=tAREA 30 1111p A; A 29 J/

(A r- ii ,, --

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, . .- ' N REACTOR BUILDING :7 BUILDING No. 1111 Sub-Pile o~

FS

0 St NASA GLENN RESEARCH CENTER PLUM BROOK STATION Z SANDUSKY, OHIO

>D a

z D~

1z 2_

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0 C-) to E-.

c0 5;

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HOT LABORATORY BUILDING No. 1112 Elev. Roof cIC

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 1 .

tl =I CLASS 1 0

_ CLASS 2

_ CLASS .

0 (o

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+

-L NOT LABORATORY BUILDING No. 1112 BWv. +114r

NASA GLENN RESEARCH CENTER PLUM BROOK STATION _

SANDUSKY, OHIO

"m= -t L' .

LASS 1

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I-F-I IIL 3f~ _

f~ma.

fts rz 3_ __ __ __ __ __ ________=== ___ __ _ __ _ _ _ _ HO AR T R

- Wl o- L -X I nLm r .HOT LABORATORY BUILDING N. 1112 Mewv. Cl%

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION 0l SANDUSKY, OHIO i K-0~

IL+1 0

X r.

m CLASS 1

_ CLASS 2

_ CLASS 3 0

0 , . . . _

t CLl 0 B 11 11 4-4 lz

. VWd110

. l 'jI

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"-I

@z r-HOT LABORATORY BUILDING No. 1112 Elv. -34' Cca

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO 1-t 32 9 J CLASS 1

=CLASS 2

_CLASS 3 fl co PI it Us zo HOT LABORATORY BUILDING No. 1112 Elev. S-t Cre-7z

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION N Ji-. -I-SANDUSKY, OHIO 0t m

Ji'J7 IJ7 0 0

>D r in:

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-.i t1i

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~o REACTOR SERVICE EQUIPMENT BUILDING BUILDING No. 1131 Elev. Reof 021-

NASA GLENN RESEARCH CENTER ;3 PLUM BROOK STATION b, SANDUSKY, OHIO Q

u rl%

_2. z Open metstl constructure grating for stair cl

-- treads, plate covering bottom of runner. I hi 0=0 11 2.

Z' tD 4.

=

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_ CLASS 2 Cn _CLASS 3 M

C.

-5 H

to SHOP &

EQUIPMENT

_I.

-i i REACTOR SERVICE EQUIPMENT BUILDINO BUILDING No. 1131 MEZZANINE FLOOR ADDITION

NASA GLENN RESEARCH CENTER 1- S PLUM BROOK STATION l SANDUSKY, OHIO ETICLASS 1 M CLASS 2 S CLASS 3

. . _!_C v ~STORAGIE I- -Fm -

o , .c. I REACTOR SERVICE EQUIPMENT BUILDING BUILDING No. 1131 MEZZANINE FLOOR

NASA GLENN RESEARCH CENTER PLUM BFROOK STATION =Jl SANDUSKY, OHIO . W 9 t

-IZ C,,

0~

REACOR -RVIC E-UIP-ENT BUILDING BUILDING No. 1131 FIRST FLOOR

0 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION Ir'4.J-j-SANDUSKY, OHIO 3-~

0Z l

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_n m-ll -- - ri Li REACTOR SERVICE EQUIPMENT BUILDING BUILDING No. 1131 BASEMENT & FOUNDATION FLOOR 02*

NASA GLENN RESEARCH CENTER 0

PWLM BROOK STATION SANDUSKY, OHIO to rl 0

0z o~

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0 FAN HOUSE BUILDING No. 1132 Ebev. Roeo cCcp

0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO AIRWAY

-if

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_ CLASS 2

_CLASS 3 In 0I OPERATUno RA- ri --- 7 a I__

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++ - + MIAt ,+/-Uin Di I(Z 0

m ED MA No. 4 - I r -A A. IIIi

-- ..... -"r",-",-,,--"-,-,-,---. ".

PIPEt ARECH v-= RESIN PinT i__l g PAN HOUSE BUILDING No. 1132 Meo. 0am Cz-

. 0 NASA GLENN RESEARCH CENTER PWLM BROOK STATION SANDUSKY, OHIO

.. ,, .- - - _- _ - --- -- -- ... .. - - . . .... T.. .  :: :v.:

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m PLUM UROOK STATION SANDUSKY, OHIO bo 0

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=IICLASS 1

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0 I

WASTE HANDLING BUILDING BUILDING No. 1133 ;o 0:

Elev. Roof C2-?c )

NASA GLENN RESEARCH CENTER rl PLUM BROOK STATION SANDUSIKY, OHIO to (Z

A-

=II CLASS 1

_CLASS 2

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a:

WASTE HANDLING BUILDING BUILDING No. 1133 wEev. a f't0 C-2~

NKAA GLENN RESEARCH CENTER 0r PLUM BROOK STATION 0%

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=I CLASS

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tb tz, w E0 t"

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0 0

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o 2

on "I,

iv l4 =IICLASS 1 A nd ra7-i - '-S--- _ CLASS 2

_ CLASS 3 a..

/v ' ,">ftya t X+ .. .:: : a. m t4 THE .

X" _.

EVAPORATOR m 4A A mW *

=i lsTME*4,umw" r-i I

,4 pm-I

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WASTE HANDLING BUILDING BUILDING No. 1133 El-v. Q -1 3' C3b-

Plum Brook Reactor Facility FinalStatus Survey Plan Revision 0 NASA GLENN RESEARCH CENTER PLUM BROOK STATION SANDUSKY, OHIO N w+E S

. II

-(' -i) = CLASS 1

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