ML11160A211

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Request for 10 CFR 20.2002 Alternate Disposal Approval and 10 CFR 30.11 Exemption of Humboldt Bay Power Plant Waste for Disposal at Us Ecology Idaho
ML11160A211
Person / Time
Site: Humboldt Bay
Issue date: 06/07/2011
From: Roller P
Pacific Gas & Electric Co
To:
Document Control Desk, NRC/FSME
References
HBL-11-006
Download: ML11160A211 (54)
v • d • e


Text

Pacific Gas and Electric Company Humboldt Bay Power Plant Paul J. Roller Director and Plant Manager Humboldt Bay Nuclear June 7, 2011 1000 King Salmon Avenue Eureka, CA 95503 (707) 444-0819 10 CFR 20.2002 10 CFR 30.11 PG&E Letter HBL-11-006

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-133, License No. DPR-7 Humboldt Bay Power Plant Unit 3 Request for 10 CFR 20.2002 Alternate Disposal Approval and 10 CFR 30.11 Exemption of Humboldt Bay Power Plant Waste For Disposal at US Ecology Idaho

Dear Commissioners and Staff:

Pacific Gas and Electric Company (PG&E) requests NRC approval for alternate disposal of approximately 2,000,000 cubic feet of hazardous waste containing low-activity radioactive debris, at the US Ecology Idaho (USEI) Resource Conservation and Recovery Act (RCRA) Subtitle C hazardous waste disposal facility located near Grand View, Idaho.

This request is made under the alternate disposal provision contained in 10 CFR 20.2002 and the exemption provision in 10 CFR 30.11. The material will be generated during demolition of structures and remediation activities at the Humboldt Bay Power Plant (HBPP) Unit 3 site. Special Nuclear Material is not present in this waste; therefore a 10 CFR Part 70.17 exemption is not required.

The USEI facility is permitted by the State of Idaho to accept the hazardous component of the waste (classified as RCRA hazardous for lead in accordance with Environmental Protection Agency Code D008). Enclosure 1 provides a conservative radiological assessment of the planned disposal and a description of the waste material'. This waste material description includes the physical and chemical properties important to risk evaluation, along with the proposed manner and conditions of waste disposal. Further information about the USEI facility's environmental setting is provided in Attachment 1 to in compliance with 10 CFR 20.2002.

The subject waste material consists of soil, concrete, steel, insulation, roofing material, gravel and metal, wood and other debris generated during dismantlement activities at the HBPP site. Radioactive contaminants, as shown in Enclosure 1, Table 1, have very low concentrations and are well within the Waste Acceptance Criteria (WAC) set forth in USEI's permit issued by the Idaho Department of Environmental Quality (provided in

ý 92

Document Control Desk PG&E Letter HBL-1 1-006 June 7, 2011 Page 2 ). Specifically, Table C.4b of USEI's WAC allows disposal of byproduct material with a 10 CFR 30.11 exemption.

The concentrations of the radionuclides in the waste are expected to be below levels requiring classification as radioactive material for shipment purposes under applicable U.S. Department of Transportation (DOT) regulations (49 CFR 173.401, Subpart I).

NRC Regulatory Issue Summary 2004-08, "Results of the License Termination Rule Analysis," dated May 28, 2004, states that "10 CFR 20.2002 does not establish a specific standard for approving on-site disposal requests. Staff's current practice is to approve on-site disposal based on a criterion of a 'few millirem'." PG&E performed a radiological assessment in consultation with USEI. Based on this assessment, PG&E concludes that potential doses to members of the public, including workers involved in the transportation and placement of this waste, will be less than one millirem Total Effective Dose Equivalent (TEDE) in one calendar year for this project, and well within the "few millirem" criterion that the NRC has established.

PG&E's request in this letter is similar to the request PG&E made to the NRC in letter HBL-10-003, dated April 1, 2010, and supplemented in letter HBL-10-018, dated August 12, 2010. The NRC approved the previous PG&E request in a letter dated November 2, 2010.

PG&E and NRC personnel met on July 29, 2010 to discuss NRC questions and comments for the previous request, initially submitted April 1, 2010. During the meeting, PG&E addressed the NRC's questions and comments. PG&E's incorporated the responses to the NRC concerns in the August 12, 2010 submittal. The NRC concerns and PG&E responses are included in Enclosure 3 to this submittal.

There are two differences between this request and the previous request. First, the volume in this request is greater than the volume in the previous request (2,000,000 cubic feet compared to 200,000 cubic feet). In addition, this request pertains primarily to wastes generated in Unit 3, whereas the previous request pertained to waste generated primarily in Units 1 and 2, and included some wastes from Unit 3. Nevertheless, the concept of the alternate disposal request is the same in this letter as in the previous letters.

Since implementing the alternate disposal from the previous request, PG&E has collected data for radionuclide concentrations in the shipments. The results of the actual concentrations are approximately 10% of the projected concentrations. PG&E expects similar results for the radionuclide concentrations projected in this alternate disposal request. Therefore, PG&E does not intend to keep a running average of radionuclide

Document Control Desk PG&E Letter HBL-11-006 June 7, 2011 Page 3 concentrations for all shipments; however, PG&E will ensure that the radionuclide concentrations for each shipment will be less than projected.

PG&E intends to begin demolition of the Unit 3 Turbine Building and other large scale structures at the end of 2011. Therefore, PG&E would appreciate your written response to this request within six months for authorization of alternate disposal at USEI under the provisions of 10 CFR 20.2002 and exemption of this material from NRC regulations for the purposes of disposal under the terms of 10 CFR 30.11.

There are no regulatory commitments made in this letter.

If you wish to discuss the information in the enclosure, please contact David Sokolsky at (707) 444-0801.

Sincerely, Paul J. Roller Director and Plant Manager Humboldt Bay Nuclear cc/enc:

Elmo E. Collins, Jr., US NRC Region IV John B. Hickman, US NRC Chad Hyslop, US Ecology Idaho James E. Kennedy, US NRC Keith I. McConnell, US NRC HBPP Humboldt Distribution Enclosures PG&E Letter HBL-11-006 HUMBOLDT BAY POWER PLANT EVALUATION IN SUPPORT OF ALTERNATE WASTE DISPOSAL PROCEDURES IN ACCORDANCE WITH 10 CFR 20.2002

1. INTRODUCTION Pacific Gas and Electric Company (PG&E) requests NRC authorization for disposal of hazardous waste, soils and debris containing low-activity radioactive materials in accordance with the provisions of 10 CFR 20.2002 and issuance of a specific exemption under 10 CFR 30.11. Since the subject material does not contain Special Nuclear Material, a 10 CFR 70.17 exemption is not required or requested. NRC approval of proposed disposal procedures, in accordance with 10 CFR 20.2002, will allow Humboldt Bay Power Plant (HBPP) to dispose of the waste described in Section 3 of this enclosure at the US Ecology Idaho (USEI) disposal facility. The USEI disposal facility is a Subtitle C Resource Conservation and Recovery Act (RCRA) hazardous waste disposal facility permitted by the State of Idaho and located near Grand View, Idaho.

Characteristics and operating parameters of the USEI disposal site are summarized in Section 2, with detailed information provided in Attachment 1. A description of the material to be disposed is included in Section 3. The material description includes physical and chemical properties of the material important to risk evaluation and the proposed conditions of waste disposal. Section 4 provides radiological assessments, including potential transport dose to the public as well as USEI worker dose. A conclusion is provided in Section 5 that confirms doses will be well below NRC limits. provides MicroShield models and results pertaining to potential external and internal radiological dose hazards to the USEI workers and transportation workers. Attachment 3 contains the RESRAD modeling report used to calculate maximum dose projections. Attachment 4 contains an intruder scenario consistent with the NRC's Request for Additional Information on the Westinghouse Hematite project (Docket #07000036)

2. DISPOSAL SITE CHARACTERISTICS A description of the USEI facility near Grand View, Idaho is provided in Attachment
1. USEI has developed a site-specific RESRAD model that reflects parameters and characteristics of the Grand View facility used in lieu of certain RESRAD default values. A summary of model input parameters are provided in Attachment 3.

Page 1 of 6 PG&E Letter HBL-1 1-006

3. DESCRIPTION OF THE WASTE The waste consists of approximately 2,000,000 cubic feet of soil, concrete, steel, insulation, roofing material, gravel and other metal, wood and debris associated with decommissioning the deactivated Unit 3 nuclear power plant. Wastes will be generated from demolition of above-and below-grade structures and soils from Unit 3 over the next four (4) years. Overall, these wastes exhibit an average bulk density of 55 pounds per cubic foot (0.88 grams per cubic centimeter). A portion of the waste may be classified as RCRA hazardous due to the presence of metals, e.g., lead in accordance with Environmental Protection Agency (EPA) Code D008.

The USEI facility is permitted to accept RCRA hazardous waste for treatment to meet EPA Land Disposal Restriction (LDR) requirements. Some asbestos containing material (ACM) may also be included, and is also acceptable at USEI.

Portions of the waste are also contaminated with radionuclide concentrations equal to or less than the concentrations listed in Table 1 below.

Table 1-Radionuclides Potentially Present in HBPP Wastes (All concentrations are in pCilg)

Nuclide pCi/gm Cs-137 15 Co-60 5

Sr-90 1

H-3 100 C-14 1

Fe-55 1

Ni-63 10 Eu-152 1

Eu-154 1

Ag-108M 0.1 All wastes being considered under this disposal request will be fission and activation products from operations at Unit 3. All debris wastes will be scabbled/cleaned and surveyed to verify that alpha contamination from transuranic isotopes is non-detectable prior to loading. HBPP is planning to perform open-air demolition of major outdoor structures at Unit 3, so elimination of alpha contamination was viewed as a prerequisite for accomplishing this goal.

All shipments will have radioactivity concentrations well within the maximum activity levels allowed in the site Waste Acceptance Criteria (WAC) set forth in USEI's permit issued by the Idaho Department of Environmental Quality (provided in Enclosure 2). These concentrations are also below levels requiring the waste to Page 2 of 6 PG&E Letter HBL-11-006 be classified as "radioactive material" for shipment purposes under U.S.

Department of Transportation (DOT) regulations.

Based on the nature of the materials, a 10 CFR Part 30.11 byproduct material exemption is required for these materials. However, a 10 CFR Part 70.17 exemption is not being requested because no Special Nuclear Material will be present in these waste streams.

4. RADIOLOGICAL ASSESSMENT As described in the following exposure scenarios, the dose equivalent for the Maximally Exposed Individual (MEI) has been demonstrated to not exceed "a few millirem per year." This standard of a "few millirem per year" to a member of the public is set forth in NRC Regulatory Issue Summary 2004-08, "Results of the License Termination Rule Analysis," dated May 28, 2004. The transportation workers and workers at the USEI site are treated as members of the public because the USEI site, while permitted by the State of Idaho to accept certain radioactive materials, is not licensed by the US NRC.

External exposure assessments were performed using the MicroShield code, Version 7.02. Evaluations of both potential external and internal dose hazards to USEI workers and transportation workers are discussed in the sections below and in Attachments 2 and 3.

4.1. Transport Dose to the Public All materials will be transported by truck to the USEI facility in Grand View, ID. For normal highway transport conditions, the material will primarily be enclosed in IP-1 intermodal containers, but some oversized debris may also be shipped on flatbed trailers or in end-dump trucks as well. All conveyances will be verified to be in compliance with DOT external loose surface contamination limits prior to shipment.

Therefore, transport will pose no potential for internal dose to the driver or other members of the public.

The distance from HBPP Unit 3 to the USEI disposal facility is approximately 659 miles. Assuming an average speed of 50 miles per hour, the trip is estimated to take 13.18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. It is estimated that approximately 11 trucks will be used to transport the entire volume of anticipated waste over the course of the project (four years) to achieve maximum logistical efficiency. Using 11 trucks, it will take a total of approximately 3367 shipments (or 842 shipments per year), with each truck driver making 76 round trips annually between Eureka, CA and Grand View, ID.

Calculated doses to project truck drivers are estimated to be 0.50 mrem/yr (see Table 2). Because of the very low average concentrations of radionuclides, potential external dose to members of the public has been calculated to be very Page 3 of 6 PG&E Letter HBL-1 1-006 low. As a result, the dose to other members of the general public can be reasonably concluded to be much less.

4.2. USEI Worker Dose Assessment Upon receipt at the facility, the material will be surveyed and screened prior to further processing. Five minutes is required to perform a survey of each truck.

Based on current practice, the surveyor is assumed to stand with his body at a distance of one meter from the truck or trailer during the survey with four surveyors sharing the surveying task. Calculated doses to surveyors are estimated to be 0.10 mrem/yr (see Table 2).

The waste will then be delivered to the stabilization building for treatment of the RCRA hazardous constituents. It is conservatively assumed that all waste from HBPP will require treatment, when in fact a portion of the waste will not, as determined by HBPP through its waste analysis and characterization program. The waste will be placed into a steel-lined concrete tank where it will be mixed with stabilization reagents. Wastes are wetted as they are emptied into the stabilization tanks to reduce dusting. The building is also equipped with a negative pressure air handling system so that air only moves into the building and is exhausted through HEPA filters. The stabilization process requires approximately 45 minutes, during which time the excavator operator is approximately 2.8 meters from the waste wearing a respirator within an enclosed cab. Six operators share the stabilization task. Calculated doses to stabilization operators are estimated to be approximately 0.22 mrem/yr (see Table 2).

After stabilization, the excavator operator removes the treated waste from the stabilization tank and places it into an on-site haul truck for transport to the disposal cell for burial. Doses to haul truck operators will be much less than to the truck drivers transporting the waste from HBPP since exposure times are much shorter. As a result, doses to haul truck operators are not analyzed.

After delivery to the disposal cell, a bulldozer operator wearing a respirator within an enclosed cab then spreads and compacts the waste. For the purpose of the dose assessment, dust loading in the stabilization building is used in calculating a bounding case potential dose for all personnel who could possibly receive an inhalation dose. Personnel who work in the stabilization building are the maximally exposed individuals for inhalation dose compared to operations conducted in open air conditions. As noted, all personnel working in the stabilization building and in the disposal cells are required to wear air purifying respirators at all times. A minimal dose is calculated for the two bulldozer operators who share the task of spreading and compacting the stabilized waste material once it has been deposited within the disposal cell. The average time to spread and compact 60 cubic yards of material (which is the capacity of two intermodal containers) is 15 minutes. This shorter exposure time results in a lesser potential dose from airborne radionuclides than what was calculated for the excavator operator.

Page 4 of 6 PG&E Letter HBL-11-006 Calculated doses to disposal cell bulldozer operators are estimated to be 0.07 mrem/yr (see Table 2).

All USEI employees who work with any hazardous materials are required to participate in an Occupational Safety and Health Administration (OSHA) compliant respiratory protection program. Although respiratory protection is required for the above specified workers, no credit is taken for this proven form of protection in this conservative dose assessment. Table 2 presents a summary of the anticipated annual doses calculated for all transporters as well as USEI workers performing survey, handling, and disposal tasks on wastes from HBPP.

Table 2-Annual Doses to Drivers and USEI Em yees for HBPP Project Waste External No.

Annual Annual Total Contact Exposure Internal Trips External Internal Annual No.

Time Rate Dose Rate Dist.

or Dose Dose Dose Function Persons (hr)

(mR/hr)

(mrem/hr)

(M)

Reps (mrem/yr)

(mrem/yr)

(mrem/yr)

Truck Drivers 11 13.2 4.96E-04 0.00E+00 4.8 842 5.00E-01 0.00E+00 5.00E-01 Survey Crews 4

0.08 5.68E-03 0.00E+00 1.0 842 9.96E-02 0.OOE+00 9.96E-02 Stab. Cell Workers 6

0.75 5.22E-03 9.61 E-07 2.8 337 2.20E-01 4.05E-05 2.20E-01 Waste Cell Operators 2

0.25 1.68E-03 9.61 E-07 2.0 337 7.07E-02 4.05E-05 7.07E-02 4.3. Post Closure Dose to the General Public USEI's RCRA permit requires that it demonstrate that no person will receive a dose exceeding 15 millirem for 1,000 years after closure of the facility. This standard is more restrictive than the 25 millirem Total Effective Dose Equivalent (TEDE) NRC decommissioning limits as well as the limits for near surface disposal of low-level radioactive waste set forth in 10 CFR Part 61. The RESRAD code, Version 6.5, was used for these purposes. A number of default parameters in the model have been replaced with site specific parameters consistent with the facility's 2005 permit modification and a report prepared by its consultant (previously submitted to the NRC as part of an RAI for the Westinghouse exemption request for the Hematite project, Docket #07000036).

As can be seen in the RESRAD report (Attachment 3, page 13), the maximum dose calculated by the model for the disposal of the HBPP radionuclides is 4.90E-3 mrem/year at 1,000 years following closure of the facility.

A post-closure intruder scenario was also conducted using the methods found in NUREG-0782. Calculated doses under this scenario for the nuclide concentrations in Table 1 are estimated to be 0.147 mrem/yr, within the NRC's alternate disposal guidance of a few millirem per year. A copy of the intruder spreadsheet is provided in Attachment 4.

Page 5 of 6 PG&E Letter HBL-11-006

5. CONCLUSION PG&E developed this request and related evaluation in consultation with USEI, including health physics personnel responsible for the Grand View disposal facility's waste acceptance and radiological performance assessment programs.

This assessment team performed a radiological dose assessment of the material to be shipped and determined that the potential dose to the workers involved in the transportation and placement of the material and to members of the general public after site closure is less than one millirem per year TEDE for this project. This dose will be a small fraction of the NRC decommissioning limits for exposure to any member of the public of 25 millirem/yr TEDE, and well within the "few millirem per year" criteria that the NRC has established in NRC Regulatory Issue Summary (RIS) 2004-08, "Results of the License Termination Rule Analysis," dated May 28, 2004. RIS 2004-08, page 4, states that "10 CFR 20.2002 does not establish a specific standard for approving on-site disposal requests. Staffs current practice is to approve on-site disposal based on a criterion of a "few millirem." This request meets that criterion.

It should be noted that this request is similar in nature to a previous request that PG&E submitted to the NRC in letters HBL-10-003, dated April 1, 2010, and HBL-10-018, dated August 12, 2010. The NRC approved the previous PG&E request in a letter dated November 2, 2010.

There are two differences between this request and the previous request.

First, the volume in this request is greater than the volume in the previous request (2,000,000 cubic feet compared to 200,000 cubic feet). In addition, this request pertains primarily to wastes generated in Unit 3, whereas the previous request pertained to waste generated primarily in Units 1 and 2, and included some wastes from Unit 3. Nevertheless, the concept of the alternate disposal request is the same in this letter as in the previous letters.

Page 6 of 6 PG&E Letter HBL-11-006 MICROSHIELD MODELS AND RESULTS PERTAINING TO POTENTIAL EXTERNAL AND INTERNAL DOSE HAZARDS TO TRANSPORTATION WORKERS AND TO USEI WORKERS (8 PAGES ATTACHED)

Case Sumxmar of -BPP 3 Mix Page I of 2 MicroShield 7.02 US Ecology, Inc. (08-MSD-7.02-1419)

J;ate 4Y4 1

Checked Filename Run Date Run Time Duration HBPP Mix - IMC Surveyor.ms7 June 2, 2011 9:29:26 AM 00:00:01 Project Info Case Title HBPP 3 Mix Description 30 cy IMC Surveyor Dose Model Geometry 13 - Rectangular Volume Source Dimensions Length 243.8 cm (7 ft 12.0 in)

Width 617.2 cm (20 ft 3.0 in)

Height 152.4 em (5 ft 0.0 in) y Dose Points Ax Y

z 1245.4cm(8ftO.6in) 76.2 cm (2 ft6.Oin) 308.6cm(10ftLL.5in)

X 344.4 cm (11 ft 3.6 in) +/-76.2 cm (2 ft 6.0 in) 308.6 cm (10 ft 1.5 in)

Shields ZOO Shield N Dimension Material Density Source 2.29e+07 omi Concrete 1.3 Shield 1

.5 cm Aluminum 2.7 Air Gap Air 0.00122 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide Ci Bg ttCi/Cm 3 Bq/cm3 Ag-108m 2.0180e-006 7.4667e+004 8.8000e-008 3.2560e-003 Ba-137m 2.8636e-004 1.0595e+007 1.2487e-005 4.6203e-001 C-14 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Co-60 1.0090e-004 3.7334e+006 4.4000e-006 1.6280e-001 Cs-137 3.0270e-004 1.1200e+007 1.3200e-005 4.8840e-001 Eu-152 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Eu-154 2.0180e-005 7.4667e+005 8.80OOe-007 3.2560e-002 Fe-55 2.0180e-004 7.4667e+006 8.8000e-006 3.2560e-001 H-3 2.0180e-003 7.4667e+007 8.8000e-005 3.2560e+000 Ni-63 2.0180e-004 7.4667e+006 8.8000e-006 3.2560e-001 Sr-90 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Y-90 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 I

Buildup: The material reference is Source I

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Integration Parameters I

X Direction 20 YDirection 20 Z Direction 20 Results - Dose Point # 1 - (245.4,76.2,308.6) cm Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm2/see MeV/cm2/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.02 4.897e+04 2.805e-12 3.406e-12 9.716e-14 1.180e-13 0.03 6.241e+05 3.732e-06 5.555e-06 3.699e-08 5.506e-08 0.04 7.410e+05 1.1 17e-04 2.105e-04 4.939e-07 9.309e-07 0.05 1.491e+05 9.378e-05 2.224e-04 2.498e-07 5.923e-07 0.08 5.291e+03 1.720e-05 6.059e-05 2.721e-08 9.589e-08 0.1 5.144e+05 2.704e-03 1.051e-02 4.137e-06 1.608e-05 0.2 1.069e+05 1.770e-03 6.931 e-03 3.125e-06 1.223e-05 0.3 2.019e+05 6.188e-03 2.182e-02 1.174e-05 4.139e-05 0.4 1.194e+05 5.673e-03 1.822e-02 1.105e-05 3.550e-05 0.5 5.829e+03 3.906e-04 1.164e-03 7.667e-07 2.284e-06 0.6 9.694e+06 8.619e-01 2.405e+00 1.682e-03 4.695e-03 0.8 4.917e+05 6.866e-02 1.738e-01 1.306e-04 3.306e-04 1.0 4.283e+06 8.525e-01 2.010e+00 1.571e-03 3.704e-03 1.5 4.198e+06 1.603e+00 3.344e+00 2.698e-03 5.626e-03 Totals 2.118e+07 3.404e+00 7.992e+00 6.114e-03 1.446e-02 Results - Dose Point # 2 - 344.4,76.2,308.6) cm Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cmfsec MeV/cm/sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.02 4.897e+04 1.147e-09 1.350e-09 3.974e-11 4.676e-11 0.03 6.241e+05 1.354e-05 1.876e-05 1.342e-07 1.859e-07 0.04 7.410e+05 1.250e-04 2.095e-04 5.527e-07 9.264e-07 0.05 1.491e+05 6.879e-05 1.395e-04 1.832e-07 3.716e-07 0.08 5.291e+03 9.288e-06 2.833e-05 1.470e-08 4.483e-08 0.1 5.144e+05 1.391e-03 4.710e-03 2.129e-06 7.206e-06 0.2 1.069e+05 8.482e-04 2.926e-03 1.497e-06 5.164e-06 0.3 2.019e+05 2.881 e-03 9.029e-03 5.464e-06 1.713e-05 0.4 1.194e+05 2.589e-03 7.448e-03 5.045e-06 1.451e-05 0.5 5.829e+03 1.755e-04 4.712e-04 3.446e-07 9.249e-07 0.6 9.694e+06 3.825e-01 9.666e-01 7.465e-04 1.887e-03 0.8 4.917e+05 2.984e-02 6.895e-02 5.677e-05 1.312e-04 1.0 4.283e+06 3.645e-01 7.889e-01 6.718e-04 1.454e-03 1.5 4.198e+06 6.645e-01 1.286e+00 1.118e-03 2.163e-03 Totals 2.118e+07 1.449e+00 3.135e+00 2.609e-03 5.681e-03 fileI/G:\\SHARED\\Radiation Program Materials\\USEI - Grandview\\Customer FilesOPG&E Humboldt Bay\\Altemate Disposal Request #2\\licr...

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Case Summary of HBPP Mix Page I of 2 MicroShield 7.02 US Ecology, Inc. (08-MSD-7.02-1419) 4 Date

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Filename Run Date Run Time Duration HBPP Mix - Truck Driver.ms7 June 2, 2011 9:25:07 AM 00:00:01 Project Info Case Title HBPP Mix Description IMC Truck Driver Dose Model - D=4 m Geometry 13 - Rectangular Volume Source Dimensions Length 617.2 cm (20 ft 3.0 in)

Width 243.8 em (7 ft 12.0 in)

Height 152.4 cm (5 ft 0.0 in)

Dose Points

ý # 1 0 +

Am 3 3 I

I z

11 1.0e+3 cn (33 ft 4.5 in) 121.9 cm (3 ft 12.0 in) 60.9 cm 1 ft 12.0 in)

Shields__

Shield N Dimension Material Density Source 2.29e+07 em3 Concrete 1.3 Shield 1

.5 cm Aluminum 2.7 Air Gap Air 0.00122 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide Ci Bg ItC/em3 Bq/cm3 Ag-108m 2.0180e-006 7.4667e+004 8.8000e-008 3.2560e-003 Ba-137m 2.8636e-004 1.0595e+007 1.2487e-005 4.6203e-001 C-14 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Co-60 1.0090e-004 3.7334e+006 4.4000e-006 1.6280e-001 Cs-137 3.0270e-004 1.1200e+007 1.3200e-005 4.8840e-001 Eu-152 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Eu-154 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Fe-55 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 H-3 2.0180e-003 7.4667e+007 8.8000e-005 3.2560e+000 Ni-63 2.0180e-004 7.4667e+006 8.8000e-006 3.2560c-001 Sr-90 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Y-90 2.0180e-005 7.4667e+005 8.8000e-007 3.2560e-002 Buildup: The material reference is Source Integration Parameters I

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Case Summary of HBPP Mix.

Page 2 of 2 I

X Direction I

20 1

Y Direction 20 Z Direction 20 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/see) MeV/cm2/sec MeV/cm2 sec mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.02 4.897e+04 1.345e-12 1.626e-12 4.659e-14 5.633e-14 0.03 6.241e+05 5.746e-07 8.419e-07 5.695e-09 8.343e-09 0.04 7.410e-+05 1.021e-05 1.816e-05 4.515e-08 8.030e-08 0.05 1.491e+05 6.179e-06 1.310e-05 1.646e-08 3.489e-08 0.08 5.291e+03 8.208e-07 2.482e-06 1.299e-09 3.928e-09 0.1 5.144e+05 1.221e-04 4.079e-04 1.868e-07 6.240e-07 0.2 1.069e+05 7.387e-05 2.537e-04 1.304e-07 4.477e-07 0.3 2.019e+05 2.505e-04 7.853e-04 4.752e-07 1.490e-06 0.4 1.194e+05 2.251e-04 6.482e-04 4.386e-07 1.263e-06 0.5 5.829e+03 1.526e-05 4.1010-05 2.994e-08 8.050e-08 0.6 9.694e+06 3.324e-02 8.415e-02 6.487e-05 1.643e-04 0.8 4.917e+05 2.594e-03 6.007e-03 4.933e-06 1.143e-05 1.0 4.283e+06 3.169e-02 6.876e-02 5.841e-05 1.268e-04 1.5 4.198e+06 5.784e-02 1.124e-01 9.732e-05 1.890e-04 Totals 2.118e+07 1.261e-01 2.734e-01 2.269e-04 4.955e-04 fileI/G:\\SHARED\\Radiation Program Materials\\USEI - GrandvievACustomer Files\\PG&E Humboldt BayAlterate Disposal Request #2\\Micr...

6/2/2011

Case Summary of HBPP Mix Page I of 2 MicroShield 7.02 US Ecology, Inc. (08-MSD-7.02-1419)

Date

/DY7 Checked Filename

'Run Date Run'Time Duration HBPP Mix - Waste Cell Operator.ms7 June 2, 2011 9:18:29 AM 00:00:01 Project Info Case Title HBPP Mix Description USEI Waste Cell Operator Dose Model Geometry 13 - Rectangular Volume Source Dimensions Length 91.44 cm (3 ft)

Width 182.88 cm (6 ft)

Hei ght 381.0 cm (12 ft 6.0 in)

Dose Points A

X Y

z

  1. 1 292.6 cm (9 ft 7.2 in) 190.5 cm (6 ft 3.0 in) 45.72 cm (1 ft 6.0 in)

Shields Shield N Dimension Material Density Source 6.37e+06 cm3 Concrete 1.5 Shield 1 1.25 cm Iron 7.86 Air Gap Air 0.00122 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide Ci Bq gCi/cm 3 Bq/cm3 Ag-108m 5.6067e-007 2.0745e+004 8.8000e-008 3.2560e-003 Ba-137m 7.9560e-005 2.9437e+006 1.2487e-005 4.6203e-001 C-14 5.6067e-006 2.0745e+005 8.8000e-007 3.2560e-002 Co-60 2.8034e-005 1.0372e+006 4.4000e-006 1.6280e-001 Cs-137 8.4101e-005 3.1117e+006 1.3200e-005 4.8840e-001 Eu-152 5.6067e-006 2.0745e+005 8.8000e-007 3.2560e-002 Eu-154 5.6067e-006 2.0745e+005 8.8000e-007 3.2560e-002 Fe-55 5.6067e-006 2.0745e+005 8.8000e-007 3.2560e-002 H-3 5.6067e-004 2.0745"007 8.800e-005 3.2560e+000 Ni-63 5.6067e-005 2.0745e+006 8.8000e-006 3.2560e-001 Sr-90 5.6067e-006 2.0745e+005 8.8000e-007 3.2560e-002 Y-90 5.6067e-006 2.0745e+005 8.8000e-007 3.2560e-002 Buildup: The material reference is Source Integration Parameters file:V/G:SHARED'.Radiation Program Materials\\USEI - Grandview\\Customer Files\\PG&E Humboldt Bay>Alternate Disposal Request #2\\Micr...

6/2i2011

Case Summary of HBPP Mix Page 2of 2 I

X Direction I

20 1

Y Direction 20 Z Direction 20 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/see) MeV/cm2/see MeV/cm2/see mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.02 1.361e+04 2.694e-116 3.335e-30 9.332e-118 1.155e-31 0.03 1.734e+05 3.918c-40 9.397e-29 3.883e-42 9.313e-31 0.04 2.059e+05 2.605e-20 1.026e-19 1.152e-22 4.537e-22 0.05 4.142e+04 1.445e-13 9.423e-13 3.849e-16 2.510e-15 0.08 1.470e+03 1.201e-08 1.314e-07 1.900e-11 2.079e-10 0.1 1.429e+05 1.636e-05 1.740e-04 2.502e-08 2.661e-07 0.2 2.971e+04 8.762e-05 6.048e-04 1.547e-07 1.067e-06 0.3 5.609e+04 4.123e-04 2.243e-03 7.821e-07 4.254e-06 0.4 3.316e+04 4.271e-04 1.975e-03 8.323e-07 3.848e-06 0.5 1.619e+03 3.165e-05 1.292e-04 6.212e-08 2.537e-07 0.6 2.693e+06 7.355e-02 2.714e-01 1.436e-04 5.298e-04 0.8 1.366e+05 6.295e-03 2.000e-02 1.197e-05 3.805e-05 1.0 1.190e+06 8.208e-02 2.341e-01 1.513e-04 4.315e-04 1.5 1.166e+06 1.661e-01 3.966e-01 2.795e-04 6.673e-04 Totals 5.885e+06 3.290e-O1 9.273e-01 5.882e-04 1.676e-03 file'JIGSHARS Radiation Program Materials\\USEI - Grandview\\Custome Files\\PG&E Humboldt Bay\\Alternate Disposal Request #2\\Micr...

6/2/2011

Case Summary of HBPP 3 Mix Page I of 2 MicroShield 7.02 US Ecology, Inc. (08-MSD-7.02-1419)

Date A

Checked iI

" ' K-Filename I

Run Date Run Time Duration HBPP Mix - Stabilization Operator.ms7 June 2, 2011 9:35:00 AM 00:00:01 Project Info Case Title HBPP 3 Mix Description USEI Stabilization Operator Dose Model Geometry 13 - Rectangular Volume Source Dimensions Length 152.4 cm (5 ft 0.0 in)

Width 274.3 em (8 ft 12.0 in)

Height 1.8e+3 cm (59 ft 0.7 in)

X Dose Points A

x Y

z

  1. 1 352.4 cm (11 ft 6.7 in) 914.4 cm (30 ft) 137.2 cm (4 ft 6.in Shields

[Shield N Dimension Material Density Source 7.52e+07 cm3 Concrete 1.5 Air Gap Air 0.00122 Source Input: Grouping Method - Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide Ci Bg ACi/cm Bq/cm Ag-108m 6.6216e-006 2.4500e+005 8.8000e-008 3.2560e-003 Ba-137m 9.3961e-004 3.4766e+007 1.2487e-005 4.6203e-001 C-14 6.6216e-005 2.4500e+006 8.8000e-007 3.2560e-002 Co-60 3.3108e-004 1.2250e+007 4.4000e-006 1.6280e-001 Cs-137 9.9325e-004 3.6750e+007 1.3200e-005 4.8840e-001 Eu-152 6.6216e-005 2.4500e+006 8.8000e-007 3.2560e-002 Eu-154 6.6216e-005 2.4500e+006 8.8000e-007 3.2560e-002 Fe-55 3.3108e-004 1-.2250e+007 4.4000e-006 1.6280e-001 H-3 6.6216e-003 2.4500e+008 8.8000e-005 3.2560e+000 Ni-63 6.6216e-004 2.4500e+007 8.8000e-006 3.2560e-001 Sr-90 6.6216e-005 2.4500e+006 8.8000e-007 3.2560e-002 Y-90 6.6216e-005 2.4500e+006 8.8000e-007 3.2560e-002 Buildup: The material reference is Source Integration Parameters X Direction 20 I

.II file-./G:\\SHARED\\Radiation P~rogram Materials\\USEX - GrzmdviewMCtstomer Files\\PG&E Humboldt Bay\\Alternate Disposal Request #2Mcir..,

6fM/011I

Case Summary of HBPP 3 Mix Page 2of 2 I

Y Direction I

20 1

Z Direction 20 Results Fluence Rate Fluence Rate Exposure Rate Exposure Rate Energy (MeV) Activity (Photons/sec) MeV/cm/sec MeV/em/see mR/hr mR/hr No Buildup With Buildup No Buildup With Buildup 0.02 1.607e+05 3.152e-07 3.528e-07 1.092e-08 1.222e-08 0.03 2.048e+06 7.097e-05 8.842e-05 7.033e-07 8.763e-07 0.04 2.431q+06 2.564e-04 3.732e-04 1.134e-06 1.651e-06 0.05 4.891q+05 1.024e-04 1.746e-04 2.729e-07 4.651e-07 0.08 1.736e+04 1.072e-05 2.757e-05 1.696e-08 4.363e-08 0.1 1.688e+06 1.534e-03 4.430e-03 2.348e-06 6.778e-06 0.2 3.509e+05 8.750e-04 2.688e-03 1.544e-06 4.744e-06 0.3 6.625e+05 2.897e-03 8.282e-03 5.495e-06 1.571e-05 0.4 3.917e+05 2.563e-03 6.830e-03 4.993e-06 1.33le-05 0.5 1.912e+04 1.718e-04 4.321e-04 3.371e-07 8.481e-07 0.6 3.181e+07 3.710e-01 8.865e-01 7.242e-04 1.730e-03 0.8 1.613e+06 2.860e-02 6.328e-02 5.439e-05 1.204e-04 1.0 1.405e+07 3.463e-01 7.244e-01 6.384e-04 1.335e-03 1.5 1.377e+07 6.240e-01 1.184e+00 1.050e-03 1.993e-03 Totals 6.951e+07 1.378e+00 2.882e+00 2.484e-03 5.223e-03 file'IG:SHAREDMRadiation Program Materials\\USEI - GrandviewNCustomer Files\\PG&E Humboldt Bay\\Alternate Disposal Request #2\\Micr...

6/2/2011 PG&E Letter HBL-11-006 RESRAD REPORT TO DETERMINE MAXIMUM DOSE PROJECTIONS (25 PAGES)

RESRAD, Version 6.5 Tli Limit = 180 days 01/26/2011 15:31 Page I

Summary EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUEST#2_JAN201l.RAD Table of Contents Part I: Mixture Sums and Single Radionuclide Guidelines Dose Conversion Factor (and Related) Parameter Summary...

2 Site-Specific Parameter Summary............................

5 Summary of Pathway Selections...............................

12 Contaminated Zone and Total Dose Summary...................

13 Total Dose Components Time = D.OOOE+00.......................................

14 Time = 1.0OOE+00.......................................

15 Time = 3.000E+00.......................................

16 Time = 1.000E+01.......................................

17 Time = 3.000E+01.......................................

18 Time = 1.000E+02.......................................

19 Time = 3.000E+02.......................................

20 Time = 1.000E+03.......................................

21 Dose/Source Ratios Summed Over All Pathways................

22 Single Radionuclide Soil Guidelines........................

22 Dose Per Nuclide Summed Over All Pathways..................

24 Soil Concentration Per Nuclide..............................

25

RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 2

Summary EGL Vadose Zone Analysis File

C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN201i.RAD Dose Conversion Factor (and Related) Parameter Summary Dose Library:

FGR 12 & FGR II Menu Parameter A-i A-i A-i A-i A-I A-i A-i A-i A-I A-i A-i A-i A-i A-i A-i B-i B-i B-i B-i B-i B-i B-i B-i B-i B-I B-i B-i B-i D-i D-i D-i D-i D-i D-i D-i D-I D-I D-i D-i D-i D-34 D-34 D-34 D-34 D-34 DCF's for external ground ra Ag-108 (Source: FGR 12)

Ag-108m (Source: FGR 12)

Ba-137m (Source: FGR 12)

C-14 (Source: FGR 12)

Co-60 (Source: FGR 12)

Cs-137 (Source: FGR 12)

Eu-152 (Source: FGR 12)

Eu-154 (Source: FGR 12)

Fe-55 (Source: FGR 12)

Gd-152 (Source: FGR 12)

H-3 (Source: FGR 12)

Ni-63 (Source:

FGR 12)

Sr-90 (Source:

FGR 12)

Y-90 (Source: FGR 12)

Dose conversion factors for Ag-108m+D C-14(p)

(Class: ORGANIC)

C-14(g)

(Class: C02)

Co-60 Cs-137+D Eu-152 Eu-154 Fe-55 Gd-152

adiation, (mrem/yr)/(pCi/g) inhalation, mrem/pCi:

Current Value#

1.143E-0:

9.640E+0(

3.606E+0(

1.345E-0(

1.622E+0:

7.510E-0' 7.006E+0(

7.678E+0(

0.OOOE+0(

0.000E+0(

0.000OE+0 0.000E+0(

7.043E-0' 2.391E-0 2.830E-0' 2.090E-04 2.350E-0) 2.190E-0' 3.190E-0(

2.210E-0' 2.860E-0' 2.690E-04 2.430E-0]

6.400E-0(

6.290E-04 1.308E-02 7.620E-04 2.090E-0(

2.690E-0(

5.000E-0!

6.480E-04 9.550E-0 6.070E-0 1.610E-0.

6.400E-0}

5.770E-0 1.528E-0.

1.500E-0:

3.0 00E-0

2.500E-0:

1 0

0 5

1 4

0 0

0 0

0 0

4 2

4 6

8 4

5 4

4 6

1 8

6 3

6 6

5 5

6 6

7 4

8 7

4 1

9 3

i.

7 7

7 0

0 0

0 7

2 2

2 2

2 3

2 2

2 2

6 6

1.

7 2

2 5

6 9

6 1

6 5

1 1

3 2

Base Paran Case*

Nan

.143E-01 DCFI)

.640E+00 DCFI(

.606E+00 DCFI)

.345E-05 DCFl(

.622E+01 DCFI(

.510E-04 DCFI(

.006E+00 DCFI(

.678E+00 DCFI(

.000E+00 DCFI(

.000E+00 DCFi(

.000E+00 DCFI(

.000E+00 DCFI(

.043E-04 DCFI(

.391E-02 DCFI(

.830E-04 DCF2(

.090E-06 DCF2(

.350E-08 Ci4GIr

.190E-04 DCF2(

.190E-05 DCF2(

.210E-04 DCF2)

.860E-04 DCF2(

.690E-06 DCF2(

.430E-01 DCF2(

.400E-08 DCF2(

.290E-06 DCF2(

.300E-03 DCF2(

.620E-06 DCF3(

.090E-06 DCF3(

.690E-05 DCF3(

.000E-05 DCF3(

.480E-06 DCF3(

.550E-06 DCF3(

.070E-07 DCF3(

.610E-04 DCF3(

.400E-08 DCF3(

.770E-07 DCF3(

.420E-04 DCF3(

.500E-01 RTF(

.000E-03 RTF(

.500E-02 RTF(

1) 2)

3) 4)

5) 6)

7) 8)

9) i0) ii) 12) 13) 14) neter 2e H-3 Ni-63 Sr-90+D Dose cor Ag-108m-C-14 Co-60 Cs-137+I Eu-152 Eu-154 Fe-55 Gd-152 H-3 Ni-63 Sr-90+D nversion factors for ingestion, mrem/pCi:

+D D

1) 2)

nhDCF 3) 4)

5) 7)

8) 9)

10) ii) 12) 1)

2) 3)

4) 5)

7) 8)

9) 10) ii) 12) 1,1) 1,2) 1,3)

Food transfer factors:

Ag-108m+D, plant/soil concentration ratio, dimensionless Ag-108m+D

, beef/livestock-intake ratio, (pCi/kg)/(pCi/d)

Ag-108m+D, milk/livestock-intake ratio, (pCi/L)/(pCi/d) 1 3

2

RESRAD, Version 6.5

. T; Limit = 180 days 01/26/2011 15:31 Page 3

Summary EGL Vadose Zone Analysis File

C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Dose Conversion Factor (and Related) Parameter Summary (continued)

Dose Library: FGR 12 & FGR 11 Menu D-34 C-14 D-34 C-14 D-34 C-14 D-34 D-34 Co-6(

D-34 Co-63 D-34 Co-6(

D-34 D-34 Cs-1 D-34 Cs-1 D-34 Cs-.

D-34 D-34 Eu-I)

D-34 Eu-1I D-34 Eu-I1 D-34 D-34 Eu-I)

D-34 Eu-i1 D-34 Eu-I)

D-34 D-34 Fe-5.

D-34 Fe-55 D-34 Fe-55 D-34 D-34 Gd-i15 D-34 Gd-i)

D-34 Gd-l)

D-34 D-34 H-3 D-34 H-3 D-34 H-3 D-34 D-34 Ni-63 D-34 Ni-63 D-34 Ni-6" D-34 D-34 Sr-9(

D-34 Sr-9(

D-34 Sr-9(

Parameter 0

0 0

37 -D 37+D 37+D 52 52 52 S4 54 54 plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) 5 5

5 current value#

5.500E+00 3.100E-02 1.200E-02 6.00 0E-02 2.000E-02 2.OO0E-03 4.O00E-02 3.000E-02 8.000E-03 2.500E 2.OOOE-03 5.OOOE-05

2. 500E-03 2.000E-03 5.OOOE-05 1.000E-03 2.OOOE-02 3.OOOE-04 2.500E-03 2.OO0E-03 2.OOOE-05 4.800E4-00 1.200E-02 1.000E-02 5.OOOE-02 5.OOOE-03 2.OOOE-02 3.OOOE-01 8.OO0E-03 2.OOOE-03 5.OOOE+00 7.700E+02 5.O0OE4-04 9.100E+03 3.OOOE-402 2.OOOE+02 Base Parameter Case*

Name 5.500E+00 RTF(

2,1) 3.100E-02 RTF(

2,2) 1.200E-02 RTF(

2,3) 8.000E-02 RTF(

3,1) 2.000E-02 RTF(

3,2) 2.000E-03 RTF(

3,3) 4.000E-02 RTF(

4,1) 3.000E-02 RTF(

4,2) 8.000E-03 RTF(

4,3) 2.500E-03 RTF(

5,1) 2.000E-03 RTF(

5,2) 5.OOOE-05 RTF(

5,3) 2.500E-03 RTF(

7,1) 2.000E-03 RTF(

7,2) 5.000E-05 RTF(

7,3) 1.000E-03 RTF(

8,1) 2.OOOE-02 RTF(

8,2) 3.000E-04 RTF(

8,3) 2.500E-03 RTF(

9,1) 2.000E-03 RTF(

9,2) 2.000E-05 RTF(

9,3) 4.800E+00 RTF(

10,1) 1.200E-02 RTF(

10,2) 1.000E-02 RTF( 10,3) 5.000E-02 RTF( 1i,i) 5.000E-03 RTF(

11,2) 2.000E-02 RTF(

11,3) 3.OOOE-01 RTF( 12,1) 8.000E-03 RTF(

12,2) 2.000E-03 RTF(

12,3) 5.000E+00 BIOFAC(

1,1) 7.700E+02 BIOFAC(

1,2) 5.OOOE+04 BIOFAC(

2,1) 9.100E+03 BIOFAC(

2,2) 3.000E+02 BIOFAC(

3,1) 2.000E+02 BIOFAC(

3,2) 32 52 52 f

F plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) plant/soil concentration ratio, dimensionless beef/livestock-intake ratio, (pCi/kg)/(pCi/d) milk/livestock-intake ratio, (pCi/L)/(pCi/d) 3 3

3 F

O+D O+D O+D D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 Bioaccumulation factors, fresh water, L/kg:

Ag-108m+D, fish Ag-108m+D, crustacea and mollusks C-14

, fish C-14

, crustacea and mollusks Co-60

, fish Co-60

, crustacea and mollusks

RESRAD, Summary File Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 4

1EGL Vadose Zone Analysis C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Dose Conversion Factor (and Related) Parameter Summary (continued)

Dose Library: FGR 12 & FGR 11 Current

'Base Value#

Case*

Parameter Name Parameter I

I D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 D-5 Cs-137+D

, fish Cs-137+D

, crustacea and mollusks Eu-152

, fish Eu-152

, crustacea and mollusks Eu-154

, fish Eu-154

, crustacea and mollusks Fe-55

, fish Fe-55

, crustacea and mollusks Gd-152 Gd-152 H-3 H-3 Ni-63 Ni-63 Sr-90+D Sr-90+D 2.000E+03 1.000E+02 5.000E+01 1.0008E+03 5.0008E+01 1.000E+03 2.000E+02 3.200E+03 2.500E+01 1.000E+03 1.000E+00 1.000E+00 1.000E+02 1.000E+02 6.000E+01 1.000E+02 2.000E+03 BIOFAC(

1.000E+02 BIOFAC(

5.000E+01 BIOFAC(

1.000E+03 BIOFAC(

5.000E+01 BIOFAC(

1.000E+03 BIOFAC(

2.000E+02 BIOFAC(

3.200E+03 BIOFAC(

2.500E+01 BIOFAC) 1.000E+03 BIOFAC(

1.000E+00 BIOFAC(

1.000E+00 BIOFAC(

1.000E+02 BIOFAC(

1.000E+02 BIOFAC(

6.000E+01 BIOFAC(

1.000E+02 BIOFAC(

fish crustacea and mollusks fish crustacea and mollusks fish crustacea and mollusks fish crustacea and mollusks 4,1) 4,2) 5,1) 5,2) 7,1) 7,2) 8,1) 8,2) 9,1) 9,2) 10,1) 10,2) 11, 1) 11,2) 12,1) 12,2)

  • For DCF1(xxx) only, factors are for infinite depth & area.

See

  • Base Case means Default.Lib w/o Associate Nuclide contributions.

ETFG table in Ground Pathway of Detailed Report.

RESRAD, Summary File Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 5

EGL Vadose Zone Analysis C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN20ll.RAD Site-Specific Parameter Summary Menu User Input Default Used by RESRAD Parameter (If different from user input) I Name Parameter i

i i

i R011 R011 R011 R011 R011 R011 R011 R011 R011 ROll R011 R011 R011 R011 R011 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 R012 Area of contaminated zone (m**2)

Thickness of contaminated zone (m)

Fraction of contamination that is submerged Length parallel to aquifer flow (m)

Basic radiation dose limit (mrem/yr)

Time since placement of material (yr)

Times for calculations (yr)

Times for calculations Times Times Times Times Times Times Times for for for calculations calculations calculations (yr)

(yr)

(yr)

(yr)

(yr)

(yr)

(yr)

(yr) for calculations for for for calculations calculations calculations Initial principal Initial principal Initial principal Initial principal Initial Initial Initial principal principal principal radionuclide radionuclide radionuclide radionuclide radionuclide radionuclide radionuclide radionuclide radionuclide radionuclide Initial principal Initial principal Initial principal (pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/g)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

(pCi/L)

Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 Sr-90 Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 Sr-90 8.822E+04

3. 360E+01 0.000E+00
5. 820E+02
2. 500E+01 0.000E+00
1. DOOE+00 3.000E+00 1.000E+01
3. 000E+01 1.0006-E+02 3.000E+02
1. OOE+03 not used not used 1.200E-03 1.200E-02 5.610E-02 1.680E-01 1.200E-02 1.200E-02 1.200E-02 1.120E+00 1.120E-01 1.120E-02 not used not used not used not used not used not used not used not used not used not used 3.600E+00 1.780E+00 1.000E-04 1.500E+00 1.000E-03 4.000E-01 2.000E-01 5.000E+01 5.300E+00 2.000E+00 8.000E+00 7.500E-01 1.840E-01 1.000E+04
2. 000E+00 0.O00E+00 1.000E+02 3.000E+01 0.O00E+00 1.000E+00 3.000E+00 1.000E+01 3.000E+01 1.000E+02 3.000E+02 1.000E+03 0.000E+00
0. 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
0. 000E+00 0.O00E+00 0.000E+00 0.000E+00
0. 000E+00
0. 000E+00 0.000E+00
0. 000E+00 0.000E+00
0. 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.500E+00 1.000E-03 1.500E+00 1.000E-03 4.000E-01 2.000E-01 1.000E+01
5. 300E+00 2.000E+00 8.000E+00 5.000E-01 1.000E+00 AREA THICKO SUBMFRACT LCZPAQ BRDL TI T( 2)

T( 3)

T( 4)

T( 5)

T( 6)

T) 7)

T( 8)

T( 9)

T(10)

Concentration in groundwater Concentration in groundwater Concentration in groundwater Concentration in groundwater Concentration in groundwater Concentration Concentration Concentration Concentration Concentration in groundwater in groundwater in groundwater in groundwater in groundwater Sl(1)

Sl(2)

S1(3)

Sl(4)

Sl)(S)

Sl5)7 Sl 8)

Sl l0)

Sl~ll)

Sl)12)

M1 1)

Wl 2)

W) 3)

Wl 4)

Wl 5)

Wl 7)

Wl 8)

Wl (10)

W1 (11)

Wl (12)

COVERO DENSCV VCV DENSCZ VCZ TPCZ FCCZ HCCZ BCZ WIND HUMID EVAPTR PRECIP R013 Cover depth (m)

R013 Density of cover material (g/cm**3)

R013 Cover depth erosion rate (m/yr)

R013 Density of contaminated zone (g/cm**3)

R013 Contaminated zone erosion rate (m/yr)

R013 Contaminated zone total porosity R013 Contaminated zone field capacity R013 Contaminated zone hydraulic conductivity (m/yr)

R013 Contaminated zone b parameter R013 Average annual wind speed (m/sec)

R013 Humidity in air (g/m**3)

R013 Evapotranspiration coefficient R013 Precipitation (m/yr)

RESRAD, Version 6.5 T'a Limit = 180 days 01/26/2011 15:31 Page 6

Summary EGL Vadose Zone Analysis File C:\\RESRAD FA24ILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN201l.RAD Site-Specific Parameter Summary (continued)

Menu Parameter R013 Irrigation (m/yr)

R013 Irrigation mode R013 Runoff coefficient R013 Watershed area for nearby stream or pond (m**2)

R013 Accuracy for water/soil computations R014 Density of saturated zone (g/cm**3)

R014 Saturated zone total porosity R014 Saturated zone effective porosity R014 Saturated zone field capacity R014 Saturated zone hydraulic conductivity (m/yr)

R014 Saturated zone hydraulic gradient R014 Saturated zone b parameter R014 Water table drop rate (m/yr)

R014 Well pump intake depth (m below water table)

R014 Model: Nondispersion (ND) or Mass-Balance (MB)

R014 Well pumping rate (m**3/yr)

R015 Number of unsaturated zone strata

-I-User Input 2.OOOE-01 2

overhead 0

2.OOOE-01 2

1.000E+06 1

1.OOOE-03 1

1.500E+00 1

4.300E-01 4

4.OOOE-01 2

4.000E-01 2.500E+01 1

1.000E-02 2

5.000OE+00 1.000E-03 1

1.OOOE+01 1

ND N

2.500E+02 2

5

]

2 2

1 1

1 4

2 2

1 2

5 1

N 2

Default

.000E-01 verhead

.000E-01

.000E+06

.000E-03

.500E+00

.000E-01

.000E-01

.000E-01

.000E+02

.000E-02

.300E+00

.000E-03 1.000E+01 ID

.500E+02 1

Used by RESRAD (If different from user input)

-I-Paarameter Name R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 R015 P015 P015 P015 R015 R015 Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

zone 1, thickness (m) zone zone zone zone 1,

1, 1,

i, soil density (g/cm**3) total porosity effective porosity field capacity zone 1, soil-specific b parameter Unsat.

zone 1, hydraulic conductivity (m/yr)

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

zone 2, thickness (m) zone 2, soil density (g/cm**3) zone 2, total porosity zone 2, effective porosity zone 2, field capacity zone 2, soil-specific b parameter zone 2, hydraulic conductivity (m/yr) 1.000E+00 1.630E+00

5. 200E-01 1.000E-01 4.500E-01 1.100E+01 1.500E-02 4.600E+00 1.690E+00 3.400E-01
3. 300E-01 7.000E-02 2.000E+00 2.200E+03 2.130E+01 1.300E+00 5.200E-01 4.000E-01 4.900E-01 3.000E+00
9. 000E+02 1.680E+01 1.310E+00
4. 900E-01 4.300E-01 4.800E-01 5.000E+00 6.000E+01 4.000E+00 1.500E+00 4.000E-01 2.000E-01 2.000E-01 5.300E+00 1.000E+01 0.000E+00 1.500E+00 4.000E-01 2.000E-01 2.000E-01 5.300E+00 1.000E+01 0.000E+00 1.500E+00 4.000E-01 2.000E-01 2.000E-01 5.300E+00 1.000E+01 0.000E+00 1.500E+00 4.000E-01 2.000E-01 2.000E-01 5.300E+00 1.000E+01 RI IDITCH RUNOFF WAREA EPS DENSAQ TPSZ EPSZ FCSZ HCSZ HGWT BSZ VWT DWIBWT MODEL UW NS H (1)

DENSUZ (1)

TPUZ (1)

EPUZ (1)

FCUZ (1)

BUZ (1)

HCUZ (1)

H(2)

DENSUZ (2)

TPUZ (2)

EPUZ(2)

FCUZ (2)

BUZ (2)

HCUZ (2)

H (3)

DENSUZ (3)

TPUZ (3)

EPUZ (3)

FCUZ (3)

BUZ (3)

HCUZ (3)

H (4)

DENSUZ (4)

TPUZ (4)

EPUZ (4)

FcUz (4)

BUZ (4)

HCUZ (4) zone zone zone zone zone 3,

3, 3,

3, 3,

Unsat. zone 3, Unsat. zone 3, thickness (m) soil density (g/cm**3) total porosity effective porosity field capacity soil-specific b parameter hydraulic conductivity (m/yr) thickness (m) soil density (g/cm**3) total porosity effective porosity field capacity soil-specific b parameter hydraulic conductivity (m/yr)

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

Unsat.

zone zone zone zone 4,

4, 4,

4, zone 4, zone 4, zone 4,

RESRAD, Version 6.5 T, Limit = 180 days 01/26/2011 15:31 Page 7

Summary : EGL Vadose Zone Analysis File

C:\\RESRAD FAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Site-Specific Parameter Summary (continued)

User I

Used by RESRAD Parameter Menu Parameter Input Default (If different from user input)

Name I

I R015 Unsat. zone 5, thickness (m) 1.220E+01 0.000E+00 J---

H(5 R015 Unsat. zone 5, soil density (g/cm**3) 1.500E+00 1.500E+00 DENSUZ(5)

R015 Unsat. zone 5, total porosity 5.200E-01 4.OOOE-01 TPUZ(5)

R015 Unsat. zone 5, effective porosity 1.500E-01 2.000E-01 E---

PUZ(5)

R015 Unsat. zone 5, field capacity 3.200E-01 2.OOOE-01 FCUZ(5)

R015 Unsat. zone 5, soil-specific b parameter 8.000E+00 5.300E+00 BUZ(5)

R015 Unsat.

zone 5, hydraulic conductivity (m/yr) 1.0006-01 1.000E+01 HCUZ(5)

R016 Distribution coefficients for Ag-108m R016 Contaminated zone (cm**3/g) 9.000E+01 0.000E+00 DCNUCC) 1)

R016 Unsaturated zone 1 (cm**3/g)

I1.800E+02 0.000E+00 DCNUCU) 1,I)

R016 Unsaturated zone 2 (cm**3/g) 9.000E+01 0.000E+00 DCNUCU( 1,2)

R016 Unsaturated zone 3 (cm**3/g) 9.000E+01 0.000E+00 DCNUCU) 1,3)

R016 Unsaturated zone 4 (cm**3/g) 9.000E+01 0.000E+00 DCNUCU(

1,4)

R016 Unsaturated zone 5 (cm**3/g) 9.000E+01 0.000E+00 DCNUCU(

1,5)

R016 Saturated zone (cml*3/g) 9.000E+01 0.000E+00 DCNUCS(

1)

R016 Leach rate (/yr) 0.000E+00 0.000E+00 1.910E-05 ALEACH(

1)

R016 Solubility constant 0.000E+00 0.000E+00 not used SOLUBK) 1)

R016 Distribution coefficients for C-14 R016 Contaminated zone (cm**3/g) 5.000E+00 0.000E+00 DCNUCC(

2)

R016 Unsaturated zone 1 (cm**3/g) 1.000E+00 0.000E+00 DCNUCU(

2,1)

R016 Unsaturated zone 2 (cm'*3/g) 1.000E+00 0.000E+00 DCNUCU(

2,2)

R016 Unsaturated zone 3 )cm**3/gl 1.0006+00 0.0006+00

_t_

DCNUCU(

2,3)

R016 Unsaturated zone 4 (cr**3/g) 1.000E+00 0.000E+00 DCNUCU(

2,4)

R016 Unsaturated zone 5 (cm**3/g) 1.000E+00 0.000E+00 DCNUCU(

2,5)

R016 Saturated zone (cm**3/g) 1.000E+00 0.000E+00 DCNUCS(

2)

R016 Leach rate (/yr) 0.000E+00 0.000E+00 3.333E-04 ALEACH(

2)

R016 Solubility constant 0.000E+00 0.000E+00 not used SOLUBK(

2)

R016 Distribution coefficients for Co-60 R016 Contaminated zone (cm**3/g) 6.000E+01 1.000E+03 DCNUCC(

3)

R016 Unsaturated zone 1 (cm**3/g) 5.500E+02 1.000E+03 DCNUCU(

3,1)

R016 Unsaturated zone 2 (cm**3/g) 6.000E+01 1.000E+03 DCNUCU(

3,2)

R016 Unsaturated zone 3 (cm**3/g) 6.000E+01 1.000E+03 DCNUCU(

3,3)

R016 Unsaturated zone 4 (cm**3/g) 6.000E+01 1.000E+03 DCNUCU( 3,4)

R016 Unsaturated zone 5 (cm**3/g) 6.000E+01 1.000E+03 DCNUCU(

3,5)

R016 Saturated zone (cm**3/g) 6.000E+01 1.000E+03 DCNUCS(

3)

R016 Leach rate (/yr) 0.000E+00 0.000E+00 2.862E-05 ALEACH(

3)

R016 Solubility constant 0.000E+00 0.000E+00 not used SOLUBK(

3)

R016 Distribution coefficients for Cs-137 R016 Contaminated zone (cm**3/g) 2.800E+02 4.600E+03 DCNUCC(

4)

R016 Unsaturated zone 1 (cm**3/g) 5.000E+02 4.600E+03 DCNUCU(

4,1)

R016 Unsaturated zone 2 (cm**3/g) 2.800E+02 4.600E+03 DCNUCU(

4,2)

R016 Unsaturated zone 3 (cm**3/g) 2.800E+02 4.600E+03 DCNUCU(

4,3)

R016 Unsaturated zone 4 (cm**3/g) 2.800E+02 4.600E+03 DCNUCU( 4,4)

R016 Unsaturated zone 5 (cm**3/g) 2.800E+02 4.600E+03 DCNUCU( 4,5)

R016 Saturated zone (cm**3/g) 2.800E+02 4.600E+03 DCNUCS(

4)

R016 Leach rate (/yr) 0.000E+00 0.000E+00 6.147E-06 ALEACH(

4)

R016 Solubility constant 0.000E+00 0.000E+00 not used SOLUBK(

4)

RESRAD, Version 6.5 Tlf Limit = 180 days 01/26/2011 15:31 Page 8

Summary EGL Vadose Zone Analysis File

C:\\RESPADFA14ILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUEST#2_JAN2011.RAD Site-Specific Parameter Summary (continued)

User Used by RESRAD Parameter Menu Parameter Input Default (If different from user input)

Name I

R016 Distribution coefficients for Eu-152 R016 Contaminated zone (cml*3/g) 1-1.000E+00 I-1.000E+00 I 8.249E+02 DCNUCC(

5)

R016 Unsaturated zone 1 (cm**3/g) 1-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCU( 5,1)

R016 Unsaturated zone 2 (cm**3/g)

I-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCU( 5,2)

R016 Unsaturated zone 3 (cm**3/g) 1-1.000E+00 I-1.OOOE+00 I 8.249E+-02 DCNUCU) 5,3)

R016 Unsaturated zone 4 (cm**3/g)

-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCU(

5,4)

R016 Unsaturated zone 5 (cm**3/g) 1-1.000E+00 1-I.000E+00 I 8.249E+02 DCNUCU(

5,5)

R016 Saturated zone (cm+*3/g)

I-1.000E+00 I-1.OOOE+00 I 8.249E+02 DCNUCS(

5)

R016 Leach rate (/yr) 0.000E+00 0.000E+00 2.087E-06 ALEACH(

5)

R016 Solubility constant 0.000E+00 0.OOOE+00 not used SOLUBK(

5)

R016 Distribution coefficients for Eu-154 R016 Contaminated zone (cm**3/g)

-1.000E+00 I-l.OOOE+00 I 8.249E+02 DCNUCC(

7)

R016 Unsaturated zone 1 (cm**3/g) 1-1.OOOE+00 1-1.000E+00 I 8.249E+02 DCNUCU(

7,1)

R016 Unsaturated zone 2 (cm**3/g) 1-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCU(

7,2)

R016 Unsaturated zone 3 (cm**3/g) 1-1.000E+00 I-l.OOOE+00 I 8.249E+02 DCNUCU(

7,3)

R016 Unsaturated zone 4 (cm**3/g) 1-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCU(

7,4)

R016 Unsaturated zone 5 (cm**3/g)

I-1.000E+00 1-1.000E+00 I 8.249E+02 DCNUCU(

7,5)

R016 Saturated zone (cm**3/g) 1-1.000E+00

-1.D00E+00 I 8.249E+02 I DCNUCS(

7)

R016 Leach rate (/yr) 0.000E+00 I 0.OOOE+00 I 2.087E-06 I ALEACH(

7)

R016 Solubility constant I 0.000E+00 I 0.000E+00 not used I SOLUBK(

7)

R016 Distribution coefficients for Fe-55 R016 Contaminated zone (cm**3/g) 2.200E+02 1.000E+03 I I DCNUCC(

8)

R016 Unsaturated zone 1 (cm**3/g) 1.650E+02 1.000E+03 I I DCNUCU( 8,1)

R016 Unsaturated zone 2 (cm**3/g) 2.200E+02 I 1.000E+03 I I DCNUCU( 8,2)

R016 Unsaturated zone 3 (cm**3/g) 2.200E+02 I 1.000E+03 I---

I DCNUCU( 8,3)

R016 Unsaturated zone 4 (cm**3/g)

I 2.200E+02 I 1.000E+03 I---

I DCNUCU(

8,4)

R016 Unsaturated zone 5 (cm**3/g) 2.200E+02 I 1.000E+03 I-I DCNUCU( 8,5)

R016 Saturated zone (cm**3/g)

I 2.200E+02 I 1.000E+03 I I DCNUCS(

8)

R016 I Leach rate (/yr)

I 0.000E+00 I 0.000E+00 I 7.822E-06 I ALEACH(

8)

R016 Solubility constant I 0.000E+00 I 0.000E+00 I not used I SOLUBK(

8)

III I

R016 Distribution coefficients for H-3 I

I I

R016 Contaminated zone (cm**3/g)

I 0.000E+00 I 0.000E+00 I--

DCNUCC(10)

R016 I Unsaturated zone I (cm**3/g) 0.000E+00 0.000E+00 I DCNUCU(10,1)

R016 I Unsaturated zone 2 (cm**3/g) 0.000E+00 I O.OOOE+00 I DCNUCU(10,2)

R016 I Unsaturated zone 3 (cm**3/g)

I 0.000E+00 I 0.000E+00 DCNUCU(10,3)

R016 Unsaturated zone 4 (cm**3/g)

I 0.000E+00 I 0.000E+00 I---

DCNUCU(10,4)

R016 I Unsaturated zone 5 (cm**3/g)

I 0.000E+00 I 0.000E+00 I--

DCNUCU(10,5)

R016 I Saturated zone (cm**3/g)

I 0.000E+00 I 0.000E+00 I DCNUCS(10)

R016 I Leach rate (/yr)

I 0.000E+00 I 0.000E+00 I 1.031E-02 I ALEACH(10)

R016 I Solubility constant I 0.000E+00 I 0.000E+00 I not used I SOLUBK(10)

RESRAD, Summary File Version 6.5 T,. Limit = 180 days 01/26/2011 15:31 Page 9

EGL Vadose Zone Analysis C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Site-Specific Parameter Summary (continued)

Menu Parameter R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R016 R017 R017 R017 R017 R017 R017 R017 R017 Distribution coefficients for Ni-63 Contaminated zone (cm**3/g)

Unsaturated zone 1 (cm**3/g)

Unsaturated zone 2 (cm**3/g)

Unsaturated zone 3 (cm**3/g)

Unsaturated zone 4 (cm**3/g)

Unsaturated zone 5 (cm*13/g)

Saturated zone (cm÷*3/g)

Leach rate (/yr)

Solubility constant Distribution coefficients for Sr-90 Contaminated zone (cm**3/g)

Unsaturated zone 1 (cm**3/g)

Unsaturated zone 2 (cm**3/g)

Unsaturated zone 3 (cm**3/g)

Unsaturated zone 4 )cm**3/g)

Unsaturated zone 5 (cm**3/g)

Saturated zone (cm**3/g)

Leach rate (/yr)

Solubility constant Distribution coefficients for daughter Gd-152 Contaminated zone (cm**3/g)

Unsaturated zone 1 (cm**3/g)

Unsaturated zone 2 (cm**3/g)

Unsaturated zone 3 (cm**3/g)

Unsaturated zone 4 (cm**3/g)

Unsaturated zone 5 (cm**3/g)

Saturated zone (cm**3/g)

Leach rate (/yr)

Solubility constant Inhalation rate (m**3/yr)

Mass loading for inhalation (g/m**3)

Exposure duration Shielding factor, inhalation Shielding factor, external gamma Fraction of time spent indoors Fraction of time spent outdoors (on site)

Shape factor flag, external gamma

-I-I -

I -

I -

I I-I-

I-User Input Default 4.OOOE+02 1.000E+03 6.500E+02 1.OOOE+03 4.000E+02 1.000E+03 4.OOOE+02 1.O00E+03 4.000E+02 1.OOOE+03 4.000E+02 1.OOOE+03 4.000E+02 1.000E+03 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 1.500E+01 3.OOOE+01 1.100E+02 3.OOOE+01 1.500E+01 3.OOOE+01 1.500E+01 3.000E+01 1.5008+01 3.OOOE+01 1.500E+01 3.000E+01 1.500E+01 3.OOOE+01 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 1.000E+00 1-1.000E+00 1.000E+00 1-1.000E+00 1.000E+00 1-1.000E+00 1.000E+00 1-1.000E+00 1.000E+00 1-1.000E+00 1.000E+00 1-1.000E+00 1.000E+00 1-1.000E+00 0.000E+00 I 0.000E+00 0.000E+00 I 0.000E+00 8.400E+03 I 8.400E+03 1.000E-04 1.000E-04 3.000E+01 I 3.000E+01 4.000E-01 I 4.000E-01 7.000E-01 I 7.000E-01 5.000E-01 I 5.000E-01 2.500E-01 I 2.500E-01 1.000E+00 I 1.000E+00 Used by RESRAD (If different from user input) 4.304E-06 not used 1.135E-04 not used 8.249E+02 8.249E+02 8.249E+02 8.249E+02 8.249E+02 8.249E+02 8.249E+02 2.087E-06 not used

>0 shows circular AREA.

Parameter Name DCNUCC()1)

DCNUCU()l, DCNUCU(11, DCNUCU(lI, DCNUCU(ll, DCNUCU(ll, DCNUCS()1)

ALEACH(11)

SOLUBK(I1)

DCNUCC(12)

DCNUCU(12, DCNUCU(12, DCNUCU(12, DCNUCU)12, DCNUCU(12, DCNUCS(12)

ALEACH(12)

SOLUBK(12)

DCNUCC(

9)

DCNUCU(

9, DCNUCU(

9, DCNUCU(

9, DCNUCU(

9, DCNUCU(

9, DCNUCS(

9)

ALEACH(

9)

SOLUBK(

9)

INHALR MLINH ED SHF3 SHF1 FIND FOTD FS 1) 2)

3) 4)

5) 1)

2) 3)

4) 5)

1) 2)

3) 4)

5)

RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 10 Summary :

EGL Vadose Zone Analysis File

C:\\RESRAD_FAMILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUESTff2_JAN201.RAD Site-Specific Parameter Summary (continued)

Menu Parameter User Input Default

+/-

Used by RESRAD (If different from user input)

Parameter Name R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R017 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R018 R019 R019 R019 R019 R019

~1-Radii of shape factor array (used if FS = -1):

Outer annular radius (m),

ring 1:

Outer annular radius Outer annular radius Outer annular radius Outer annular radius Outer annular radius Outer annular radius Outer annular radius Outer annular radius Outer annular'radius Cm),

Cm),

Cm),

Cm),

Cm),

Cm),

Cm),

(m),

(m),

ring ring ring ring ring ring ring ring ring 2:

3:

4:

5:

6:

7:

8:

9:

10:

Outer annular radius (m),

ring 11:

Outer annular radius (m),

ring 12:

not not not not not not not not not not not not not not not not not not not not not used used used used used used used used used used used used used used used used used used used used used

5. 000E+01
7. 071E+01
0. 000E+00
0. 000E+00
0. 000E+00
0. 000E+00
0. 000E+00
0. 000E+00
0. 000E+00
0. 000E+00 0.D 0E+00
0. 000E+00 RADSHAPE) 1)

RADSHAPE) 2)

RADSHAPE) 3)

PADSHAPE) 4)

RADSHAPE) 5)

RADSHAPE) 6)

RAD SHAPE) 7)

RADSHAPE) 8)

RADSHAPE) 9)

RADSHAPE(10)

RADSHAPE(Il)

RAD SHAPE(12)

Fractions of Ring 1

Ring 2

Ring 3

Ring 4

Ring 5

Ring 6

Ring 7

Ring 8

Ring 9

annular areas within AREA:

Ring 10 Ring 11 Ring 12 Fruits, vegetables and grain consumption (kg/yr)

Leafy vegetable consumption (kg/yr)

Milk consumption (L/yr)

Meat and poultry consumption (kg/yr)

Fish consumption (kg/yr)

Other seafood consumption (kg/yr)

Soil ingestion rate (g/yr)

Drinking water intake (L/yr)

Contamination fraction of drinking water Contamination fraction of household water Contamination fraction of livestock water Contamination fraction of irrigation water Contamination fraction of aquatic food Contamination fraction of plant food Contamination fraction of meat Contamination fraction of milk Livestock fodder intake for meat (kg/day)

Livestock fodder intake for milk (kg/day)

Livestock water intake for meat (L/day)

Livestock water intake for milk (L/day)

Livestock soil intake (kg/day) not used not used not used 1.600E+02 1.400E+01 9.200E+01 6.300E+01 not used not used 3.650E+01 5.100E+02 1.O00E+00 not used 1.DDDE+00 1.0OOE+00 not used 1-1 I-i 1-1 6.800E+01 5.500E+01 5.000E+01 1.600E+02 5.000E-01 1

1. OOE+00 I2. 732E-01 I.DDOE+00 I0.DDDOE+0O
0. 00 DE+DD I0. OOOE+00
0. 000 E+00 I0. OOOE+00
0..OOOE-400
0. O.DOE+OD 1

1.600E+02 I9.

200E+01 I.

6300E+01

5..400E+00 I9. OOOE-01 I3.

650E+01

5. 100E+02 1

l.OOOE+00

5. OOOE--01
1. 800 E+01
5. 500DE+01
5. DOOOE-Ol 1 6.00E+02 I5.DOOOE-01 FRACA)

FRACA)

FRACAC FRACA C FRACA C FRACA)

FRACA)

FRACA)

FRACA)

I) 2)

3) 4)

5) 6)

7) 8)

9)

I.

FRACA(10)

FRACA(1)1 FRACA(12)

0. 500E+00
0. 100E+01
0. 100E+01 DIET (l)

DIET (2)

DIET (3)

DIET (4)

DIET(5)

DIET (6)

SOIL DWI FDW FHHW FLW FIRW FR9 FPLANT FMEAT FMILK LF15 LFI6 LWI5 LWI6 LSI

RESRAD, Version 6.5 T* Limit = 180 days 01/26/2011 15:31 Page 11 Summary : EGL Vadose Zone Analysis File

C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUEST22_JAN2011.RAD Site-Specific Parameter Summary (continued)

User Used by RESRAD Parameter Menu Parameter Input Default (If different from user input)

Name R019 Mass loading for foliar deposition (g/m**3) 1.000E-04 1.000E-04 MLFD R019 Depth of soil mixing layer (m) 1.500E-01 1.500E-01 DM R019 Depth of roots (m) 9.000E-01 9.000E-01 DROOT R019 Drinking water fraction from ground water 1.000E+00 1.000E+00 FGWDW R019 Household water fraction from ground water not used 1.000E+00 FGWHH R019 Livestock water fraction from ground water 1.000E+00 1.000E+00 FGWLW R019 Irrigation fraction from ground water 1.000E+00 1.000E+00 FGWIR R19B Wet weight crop yield for Non-Leafy (kg/m**2) 7.000E-01 7.000E-01 YV(1)

R19B Wet weight crop yield for Leafy (kg/m**2) 1.500E+00 1.500E+00 YV(2)

R19B Wet weight crop yield for Fodder (kg/m**2) 1.100E+00 1.100E+00 YV(3)

R19B Growing Season for Non-Leafy (years) 1.700E-01 1.700E-01 TE(1)

R19B Growing Season for Leafy (years) 2.500E-01 2.500E-01 TE(2)

R19B Growing Season for Fodder (years) 8.000E-02 8.000E-02 TE(3)

R19B Translocation Factor for Non-Leafy i1.000E-01 1.000E-01 TIV(1)

R19B Translocation Factor for Leafy 1.000E+00 1.000E+00 TIV(2)

R19B Translocation Factor for Fodder 1.000E+00 1.000E+00 TIV(3)

R19B Dry Foliar Interception Fraction for Non-Leafy 2.500E-01 2.500E-01 RDRY(1)

R19B Dry Foliar Interception Fraction for Leafy 2.500E-01 2.500E-01 RDRY(2)

R19B Dry Foliar Interception Fraction for Fodder 2.500E-01 2.500E-01 RDRY(3)

R19B Wet Foliar Interception Fraction for Non-Leafy 2.500E-01 2.500E-01 RWET(1)

R19B Wet Foliar Interception Fraction for Leafy 2.500E-01 2.500E-01 RWET(2)

R19B Wet Foliar Interception Fraction for Fodder 2.500E-01 2.500E-01 RWET(3)

R19B Weathering Removal Constant for Vegetation 2.000E+01 2.000E+01 WLAM C14 C-12 concentration in water (g/cm1*3) 2.000E-05 2.000E-05 C12WTR C14 C-12 concentration in contaminated soil (g/g) 3.000E-02 3.000E-02 C12CZ C14 Fraction of vegetation carbon from soil 2.000E-02 2.000E-02 CSOIL C14 Fraction of vegetation carbon from air 9.800E-01 9.800E-01 CAIR C14 C-14 evasion layer thickness in soil (m) 3.000E-01 3.000E-01 DMC C14 C-14 evasion flux rate from soil (1/sec) 7.000E-07 7.000E-07 E---

VSN C14 C-12 evasion flux rate from soil (1/sec)

I.'000E-10 1.000E-10 REVSN C14 Fraction of grain in beef cattle feed 8.000E-01 8.000E-01 AVFG4 C14 Fraction of grain in milk cow feed 2.000E-01 2.000E-01 AVFG5 STOR Storage times of contaminated foodstuffs (days):

STOR Fruits, non-leafy vegetables, and grain 1.400E+01 1.400E+01 STOR_T(1)

STOR Leafy vegetables 1.000E+00 1.000E+00 STOR T(2)

STOR Milk 1.000E+00 1.000E+00 STORPT(3)

STOR Meat and poultry 2.000E+01 2.000E+01 STOR_T(4)

STOR Fish 7.000E+00 7.000E+00 STORPT(5)

STOR Crustacea and mollusks 7.000E+00 7;000E+00 STORPT(6)

STOR Well water 1.000E+00 1.000E+00 STOR T(7)

STOR Surface water I1.000E+00 1.000E+00 STOR_T(8)

STOR Livestock fodder 4.500E+01 4.500E+01 STORPT(9)

R021 Thickness of building foundation (m) not used 1.500E-01 FLOOR1 R021 Bulk density of building foundation (g/cm**3) not used 2.400E+00 DENSFL R021 Total porosity of the cover material not used 4.000E-01 TPCV R021 Total porosity of the building foundation not used 1.000E-01 TPFL

RESRAD, Version 6.5 T,ý Limit = 180 days 01/26/2011 15:31 Page 12 Summary EGL Vadose Zone Analysis File
C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Site-Specific Parameter Summary (continued)

Menu Parameter R021 R021 R021 R021 R021 R021 R021 R021 R021 R021 R021 R021 R021 TITL TITL TITL Volumetric water content of the cover material Volumetric water content of the foundation Diffusion coefficient for radon gas (m/sec):

in cover material in foundation material in contaminated zone soil Radon vertical dimension of mixing (m)

Average building air exchange rate (1/hr)

Height of the building (room)

(m)

Building interior area factor Building depth below ground surface (m)

Emanating power of Rn-222 gas Emanating power of Rn-220 gas Number of graphical time points Maximum number of integration points for dose Maximum number of integration points for risk no no no no no no no no no no no no User Input Default t used 5.000E-02

)t used 3.000E-02 t used 2.000E-06 t used 3.OOOE-07 t used 2.000E-06 ot used 2.000E+00 t used 5.000E-01 t used 2.500E+00 t used 0.000E+00 ot used I-I.000E+00

)t used 2.500E-01 t used 1.500E-01 512 17 1

Used by RESRAD (If different from user input)

Parameter Name PH20CV PH2OFL DIFCV DIFFL DIFCZ HMIX REXG HRM FAI DMFL EMANA(l)

EMANA(2)

NPTS LIMAX KYMAX Summary of Pathway Selections Pathway User Selection 1 -- external gamma active 2 --

inhalation (w/o radon)l active 3 -- plant ingestion active 4 --

meat ingestion active 5 --

milk ingestion active 6 -- aquatic foods suppressed 7 -- drinking water active 8 --

soil ingestion active 9 --

radon suppressed Find peak pathway doses active

RESRAD, Version 6.5 T12 Limit = 180 days 01/26/2011 15:31 Page 13 Summary : EGL Vadose Zone Analysis File
C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUEST#2_JAN2011.RAD Contaminated Zone Dimensions Initial Soil Concentrations, pCi/g Area:

Thickness:

Cover Depth:

88221.00 square meters 33.60 meters 3.60 meters Ag-108m 1.200E-03 C-14 1.200E-02 Co-60 5.610E-02 Cs-137 1.680E-01 Eu-152 1.200E-02 Eu-154 1.200E-02 Fe-55 1.200E-02 H-3 1.120E+00 Ni-63 1.120E-01 Sr-90 1.120E-02 Total Dose TDOSE(t),

mrem/yr Basic Radiation Dose Limit = 2.500E+01 mrem/yr Total Mixture Sum M(t)

= Fraction of Basic Dose Limit Received at Time (t) t (years):

0.000E+00 1.000E+00 TDOSE(t):

9.343E-23 8.206E-23 M(t):

3.737E-24 3.282E-24 3.000E+00 1.000E+01 3.000E+01 1.000E+02 3.000E+02 1.000E+03 6.331E-23 2.556E-23 1.951E-24 1.720E-27 6.305E-09 4.874E-03 2.532E-24 1.022E-24 7.806E-26 6.881E-29 2.522E-10 1.950E-04 Maximum TDOSE(t):

4.874E-03 mrem/yr at t = 1.000E+03 years

RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 14 Summary
EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 0.000E+00 years Water Independent Pathways (Inhalation excludes radon)

Ground Radio-Nuclide mrem/yr fract.

Ag-108m 6.673E-30 0.0000 C-14 0.000E+00 0.0000 Co-60 9.285E-23 0.9938 Cs-137 1.151E-27 0.0000 Eu-152 1.880E-25 0.0020 Eu-154 3.858E-25 0.0041 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Total 9.343E-23 1.0000 Inhalation mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 OO000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 Radon mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Plant mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Meat mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O000E00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Milk mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Soil mrem/yr fract.

O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 0.000E+00 years Water Dependent Pathways Radio-Nuclide Water mrem/yr fract.

Ag-108m 0.000E+00 0.0000 C-14 0.000E+00 0.0000 Co-60 0.000E+00 0.0000 Cs-137 0.000E+00 0.0000 Eu-152 0.000E+00 0.0000 Eu-154 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Total 0.000E+00 0.0000 Fish mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 Radon mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Plant mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Meat mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 All Pathways*

mrem/yr fract.

6.673E-30 0.0000 0.000E+00 0.0000 9.285E-23 0.9938 1.151E-27 0.0000 1.880E-25 0.0020 3.858E-25 0.0041 0.000E+00 0.0000 0.000E+00 0.0000 0.000+E00 0.0000 0.000E+00 0.0000 9.343E-23 1.0000

  • Sum of all water independent and dependent pathways.

RESRAD, Version 6.5 Tls Limit = 180 days 01/26/2011 15:31 Page 15 Summary EGL Vadose Zone Analysis File

C:\\RESRAD_FAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+00 years Water Independent Pathways (Inhalation excludes radon)

Ground Radio-Nuclide mrem/yr fract.

Inhalation mrem/yr fract.

Radon mrem/yr fract.

Plant mrem/yr fract.

Meat mrem/yr fract.

Milk mrem/yr fract.

Soil mrem/yr fract.

Ag-108m 6.648E-30 C-14 0.000E+00 Co-60 8.152E-23 Cs-137 1.127E-27 Eu-152 1.787E-25 Eu-154 3.571E-25 Fe-55 0.OOOE+00 H-3 0.000E+00 Ni-63 0.000E+00 Sr-90 0.O00E+00 0.0000 0.0000 0.9935 0.0000 0.0022 0.0044 0.0000 0.0000 0.0000 0.0000

0. 000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
0. 000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.000E+00
0. 000E+00
0. OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
0. 000E+00
0. 000E+00
0. 000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.000E+00
0. 000E+00
0. 000E+00 0.000E+00 0.000E+00
0. O00E+00 0.O00E+00 0.O00E+00 0.000E+00
0. 0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0006+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 Total 8.206E-23 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+00 years Water Dependent Pathways Water Radio-Nuclide mrem/yr fraCt.

Fish Radon Plant Meat Milk mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m 0.000+E00 C-14 0.000E+00 Co-60 0.000E+00 Cs-137 0.000E+00 Eu-152 0.000E+00 Eu-154 0.000E+00 Fe-55 0.000E+00 H-3 0.000E+00 Ni-63 0.000E+00 Sr-90 0.000E+00 Total 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.O00E+00 0.O00E+00 O.O00E+00 0.O00E+00 0.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

0. 000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.O00E+00 0.O00E+00 0.O00E+00 0.O00E+00 0.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0006+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000
0. 000E+00 0.000E+00
0. 000E+00 0.000E+00 0.000E+00 0.000E+00
0. 000E+00 0.000E+00
0. 000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00
0. 000E+00 0.000E+00 0.000E+00 0.000E+00
0. 000E+00 0.000E+00
0. 000E+00 0.000E+00 0.O00E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 All Pathways' mrem/yr fract.

6.648E-30 0.0000 0.000E+00 0.0000 8.152E-23 0.9935 1.127E-27 0.0000 1.787E-25 0.0022 3.571E-25 0.0044 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 8.206E-23 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.000E+00 0.0000

  • Sum of all water independent and dependent pathways.
RESRAD, Version 6.5 T* Limit = 180 days 01/26/2011 15:31 Page 16 Summary EGL Vadose Zone Analysis File
C:\\RESPADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUEST#2_JAN2011.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 3.000E+00 years Water Independent Pathways (Inhalation excludes radon)'

Ground Radio-Inhalation Radon Plant Meat Milk Soil Nuclide mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m 6.598E-30 0.0000 C-14 0.000E+00 0.0000 Co-60 6.284E-23 0.9926 Cs-137 1.080E-27 0.0000 Eu-152 1.615E-25 0.0026 Eu-154 3.060E-25 0.0048 Fe-55 0.000E+00 0.0000 H-3 0.OOOE+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00

0. 000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.0000

.O008E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O000E00 0.0000 O.O00E+00 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0008+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O008+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0008+00 0.0000 0.0008+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total 6.331E-23 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 3.000E+00 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways*

Radio-Nuclide mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m 0.000E+00 0.0000 C-14 0.000E+00 0.0000 Co-60 0.000E+00 0.0000 Cs-137 0.000E+00 0.0000 Eu-152 0.000E+00 0.0000 Eu-154 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000+E00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 6.598E-30 0.0000 0.000E+00 0.0000 6.284E-23 0.9926 1.080E-27 0.0000 1.615E-25 0.0026 3.060E-25 0.0048 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.000E+00 0.0000 Total 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 6.331E-23 1.0000

  • Sum of all water independent and dependent pathways.
RESRAD, Version 6.5 T4 Limit = 180 days 01/26/2011 15:31 Page 17 Summary
EGL Vadose Zone Analysis File C:\\RESRAD_FA4ILY\\RESRAD\\6.5\\USERFILES\\HBNPP_ALTDISPREQUEST#2_JAN201l.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+01 years Water Independent Pathways (Inhalation excludes radon)

Radio-Nuci ide Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 Sr-90 Total Ground mrem/yr fract.

6.427E-30 0.0000 0.O00E+00 0.0000 2.527E-23 0.9886 9.293E-28 0.0000 1.134E-25 0.0044 1.781E-25 0.0070 O.O00E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 2.556E-23 1.0000 Inhalation mrem/yr fract.

0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Radon mrem/yr fract.

0.00E+00 0.0000 0.O00E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 Plant mrem/yr fract.

0.000E+00 0.0000 O.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Meat mrem/yr fract.

0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Milk mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.0008+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Soil mrem/yr fract.

0.000E+00 0.0000 0.0008+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+01 years Water Dependent Pathways Water Radio-Nuclide mrem/yr fract.

Ag-108m 0.000E+00 0.0000 C-14 0.000E+00 0.0000 Co-60 0.000E+00 0.0000 Cs-137 0.000E+00 0.0000 Eu-152 0.OOOE+00 0.0000 Eu-154 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Total 0.000E+00 0.0000 Fish Radon Plant Meat Milk mrem/yr fract.

O.O00E+00 0.0000 0.000E+00 0.0000 0.0008+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 mrem/yr fract.

0.0008+00 0.0000 0.000E+00 0.0000 0.0008+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 All Pathways*

mrem/yr fract.

6.427E-30 0.0000 0.000E+00 0.0000 2.527E-23 0.9886 9.293E-28 0.0000 1.134E-25 0.0044 1.781E-25 0.0070 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.o00g+00 0.0000 2.556E-23 1.0000

  • Sum of all water independent and dependent pathways.
RESRAD, Version 6.5 T* Limit = 180 days 01/26/2011 15:31 Page 18 Summary : EGL Vadose Zone Analysis File C:\\RESRAD_FAMILY\\RESRAD\\6.5\\USERFILES\\HBNPP ALTDISPREQUEST#2 JAN2011.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides Wi) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 3.000E+01 years Water Independent Pathways (Inhalation excludes radon)

Ground Radio-Nuclide mrem/yr fract.

Ag-108m 5.963E-30 0.0000 C-14 0.000E+00 0.0000 Co-60 1.872E-24 0.9591 Cs-137 6.055E-28 0.0003 Eu-152 4.131E-26 0.0212 Eu-154 3.796E-26 0.0195 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Inhalation Radon Plant Meat Milk Soil mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.000E+00 0.0000 O.O00E+00 0.0000 0.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total 1.951E-24 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 3.000E+01 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways*

Radio-Nuclide Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 Sr-90 mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00. 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000

.0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.963E-30 0.0000 0.000E+00 0.0000 1.872E-24 0.9591 6.055E-28 0.0003 4.131E-26 0.0212 3.796E-26 0.0195 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.951E-24 1.0000 Total 0.000E+00 0.0000

  • Sum of all water independent and dependent pathways.

RESRAD, Version 6.5 T, Limit = 180 days 01/26/2011 15:31 Page 19 Summary : EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+02 years Water Independent Pathways (Inhalation excludes radon)

Ground Radio-Nuclide mrem/yr fract.

Ag-108m 4.585E-30 0.0027 C-14 0.000E+00 0.0000 Co-60 2.069E-28 0.1203 Cs-137 1.352E-28 0.0786 Eu-152 1.204E-27 0.6998 Eu-154 1.697E-28 0.0986 Fe-55 0.000E+00 0.0000 H-3 0.OOOE+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Total 1.720E-27 1.0000 Inhalation mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000OE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Radon mrem/yr fract.

0.O00E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Plant mrem/yr fract.

0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Meat mrem/yr fract.

O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Milk mrem/yr fract.

O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 Soil mrem/yr fract.

0.0006+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.0006+00 0.0000 O.O006+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+02 years Water Dependent Pathways Water Radio-Nuclide mrem/yr fract.

Ag-108m 0.000E+00 0.0000 C-14 0.000E+00 0.0000 Co-60 0.000E+00 0.0000 Cs-137 0.000E+00 0.0000 Eu-152 0.000E+00 0.0000 Eu-154 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Total 0.000E+00 0.0000 Fish Radon mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Plant mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Meat mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000+E00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Milk mrem/yr fract.

0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 All Pathways*

mrem/yr fract.

4.585E-30 0.0027 0.000E+00 0.0000 2.069E-28 0.1203 1.352E-28 0.0786 1.204E-27 0.6998 1.697E-28 0.0986 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.720E-27 1.0000

  • Sum of all water independent and dependent pathways.
RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 20 Summary : EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 3.000E+02 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m 2.165E-30 0.0000 C-14 0.OOOE+00 0.0000 Co-60 0.000E+00 0.0000 Cs-137 1.864E-30 0.0000 Eu-152 4.940E-32 0.0000 Eu-154 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 H-3 0.000E+00 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 Total 4.078E-30 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000OE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000OE+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000O+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 3.000E+02 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways*

Radio-Nuclide mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 St-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.781E-09 0.7583 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000+E00 0.0000 0.000E+00 0.0000 6.113E-10 0.0970 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.482E-10 0.0394 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 6.646E-10 0.1054 0.000E+00 0.0000 0.000E+00 0.0000 2.165E-30 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.864E-30 0.0000 4.940E-32 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 6.305E-09 1.0000 0.0006+00 0.0000 0.000E+00 0.0000 Total 4.781E-09 0.7583 0.000E+00 0.0000 0.000E+00 0.0000

  • Sum of all water independent and dependent pathways.

6.113E-10 0.0970 2.482E-10 0.0394 6.646E-10 0.1054 6.305E-09 1.0000

RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 21 Summary EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN201l.RAD Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t

= 1.000E+03 years Water Independent Pathways (Inhalation excludes radon)

Ground Inhalation Radon Plant Meat Milk Soil Radio-Nuclide mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 Sr-90 1.565E-31 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.OOOE+00 0.0000 0.000E+00 0.0000 O.OOOE+00 0.0000 O.OOOE+00 0.0000 O.O00E+00 0.0000 O.O000E00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total 1.565E-31 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 Total Dose Contributions TDOSE(i,p,t) for Individual Radionuclides (i) and Pathways (p)

As mrem/yr and Fraction of Total Dose At t = 1.000E+03 years Water Dependent Pathways Water Fish Radon Plant Meat Milk All Pathways*

Radio-Nuclide mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

mrem/yr fract.

Ag-108m 0.000E+00 0.0000 C-14 1.659E-03 0.3403 Co-60 0.000E+00 0.0000 Cs-137 0.000E+00 0.0000 Eu-152 0.000E+00 0.0000 Eu-154 0.000E+00 0.0000 Fe-55 0.000E+00 0.0000 H-3 3.143E-29 0.0000 Ni-63 0.000E+00 0.0000 Sr-90 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.072E-03 0.4251 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.019E-30 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 5.534E-04 0.1135 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 1.632E-30 0.0000 0.0006+00 0.0000 0.0006+00 0.0000 0.000E+00 0.0000 5.900E-04 0.1210 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 4.370E-30 0.0000 0.000E+00 0.0000 O.O00E+00 0.0000 1.565E-31 0.0000 4.874E-03 1.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000+E00 0.0000 4.145E-29 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 0.000E+00 0.0000 2.072E-03 0.4251 5.534E-04 0.1135 5.900E-04 0.1210 4.874E-03 1.0000 Total 1.659E-03 0.3403 0.000E+00 0.0000

  • Sum of all water independent and dependent pathways.
RESRAD, Version 6.5 T*i Limit = 180 days 01/26/2011 15:31 Page 22 Summary : EGL Vadose Zone Analysis File
C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Dose/Source Ratios Summed Over All Pathways Parent and Progeny Principal Radionuclide Contributions Indicated Parent (i)

Ag-108m+D C-14 Product (j)

Ag-108m+D C-14 Thread Fraction 1.000E+00 DSR(j,t) At Time in Years (mrem/yr)/(pCi/g) 0.000E+00 1.000E+00 3.000E+00 1.000E+01 3.000E+01 1.000E+02 3.000E+02 1.000E+03 5.561E-27 5.540E-27 5.499E-27 5.356E-27 4.969E-27 3.821E-27 1.804E-27 1.305E-28 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.062E-01 Co-60 Co-60 1.000E+00 1.655E-21 1.453E-21 1.120E-21 4.504E-22 3.336E-23 3.688E-27 1.832E-38 0.000E+00 Cs-137+D Cs-137+D 1.000E+00 6.853E-27 6.708E-27 6.426E-27 5.531E-27 3.604E-27 8.046E-28 1.109E-29 3.414E-36 Eu-152 Eu-152 7.208E-01 1.129E-23 1.073E-23 9.703E-24 6.813E-24 2.481E-24 7.232E-26 2.967E-30 1.401E-45 Eu-152 Eu-152 Eu-152 Eu-152 Gd-152 EDSR (j) 2.792E-01 4.373E-24 2.792E-01 0.000E+00 4.373E-24 4.158E-24 3.758E-24 0.000E+00 0.000E+00 4.158E-24 3.758E-24

2. 639E-24
0. 000E+00 2.639E-24 9.611E-25
0. 000E+00 9.611E-25 2.801E-26
0. 000E+00 2.801E-26 1.149E-30 0.000E+00 0.000E+00 0.000E+00 1.149E-30 0.000E+00 Eu-154 Eu-154 1.000E+00 3.215E-23 2.976E-23 2.550E-23 1.484E-23 3.164E-24 1.414E-26 2.736E-33 0.000E+00 Fe-55 Fe-55 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 H-3 H-3 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.629E-09 3.701E-29 Ni-63 Ni-63 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Sr-90+D Sr-90+D 1.000E+00 1.865E-35 1.825E-35 1.747E-35 1.500E-35 9.693E-36 2.105E-36 2.681E-38 5.605E-45 The DSR includes contributions from associated (half-life
  • 180 days) daughters.

Single Radionuclide Soil Guidelines G(i,t) in pCi/g Basic Radiation Dose Limit = 2.500E+01 mrem/yr Nuclide (i) t= 0.000E+00 1.000E+00 3.000E+00 1.000E+01 3.000E+01 1.000E+02 Ag-108m C-14 Co-60 Cs-137 Eu-152 Eu-154 Fe-55 H-3 Ni-63 Sr-90

  • 2. 609E+13
  • 4.455E+12
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14
  • 2.639E+14
  • 2. 4 10E+15
9. 597E+15
  • 5. 917E+13
  • 1. 365E+14
  • 2.609E+13
  • 4.455E+12
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14
  • 2.639E+14 "2.410E+15
9. 597E+15
  • 5.917E+13
  • 1.365E+14
  • 2.609E+13
  • 4.455E+12
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14
  • 2. 639E+14
  • 2.410E+15
  • 9. 597E+15
  • 5. 917E+13
  • 1.365E+14
  • 2.609E+13
  • 4.455E+12
  • 1. 132E+15
  • 8.704E+13
  • 1.765E+14
  • 2. 639E+14
  • 2. 410E+15
  • 9. 597E+15
  • 5. 917E+13
  • 1.365E+14
  • 2.609E+13
  • 4.455E+12
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14
  • 2.639E+14
  • 2. 410E+15
  • 9. 597E+15
  • 5.917E+13
  • 1.365E+14
  • 2.609E+13
  • 4.455E+12
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14
  • 2.639E+14
  • 2.410E+15
  • 9.597E+15
  • 5. 917E+13
  • 1.3652+14 3.000E+02
  • 2.609E+13
  • 4.4 55E+12
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14

'2. 639E+14

  • 2.410E+15 4.441E+09
  • 5. 917E+13
  • 1.365E+14 1.000E+03
  • 2.609E+13 6.155E+01
  • 1.132E+15
  • 8.704E+13
  • 1.765E+14
  • 2.639E+14
2. 410E+15
  • 9.597E+15
  • 5.917E+13
  • 1.365E+14
  • At specific activity limit

RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 23 Summary : EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Summed Dose/Source Ratios DSR(i,t) in (mrem/yr)/(pCi/g) and Single Radionuclide Soil Guidelines G(i,t) in pCi/g at tmin = time of minimum single radionuclide soil guideline and at tmax = time of maximum total dose = 1.000E+03 years Nuclide Initial tmin DSR(i,tmin) G(i,tmin) DSR(i,tmax) G(i,tmax)

(i)

(pCi/g)

(years)

(pCi/g)

(pCi/g)

Ag-108m 1,200E-03 0.OOOE+00 5.561E-27 *2.609E+13 1.305E-28 *2.609E+13 C-14 1,200E-02 1.000E+03 4.062E-01 6.155E+01 4.062E-01 6.155E+01 Co-60 5,610E-02 0.OOOE+00 1.655E-21 *1.132E+15 0.000E+00 *1.132E+15 Cs-137 1,680E-01 0.000E+00 6.853E-27 *8.704E+13 0.000E+00 "8.704E+13 Eu-152 1,200E-02 0.000E+00 1.566E-23 *1.765E+14 0.O00E+00 *1.765E+14 Eu-154 1,200E-02 0.000E+00 3.215E-23 +2.639E+14 0.000E+00 *2.639E+14 Fe-55 1,200E-02 0.000E+00 0.000E+00 *2.410E+15 0.000E+00 *2.410E+15 H-3 1,120E+00 217.1 +/- 0.4 4.199E-07 5.954E+07 3.701E-29 *9.597E+15 Ni-63 1.120E-01 0.000E+00 0.000E+00 *5.917E+13 0.000E+00 *5.917E+13 Sr-90 1.120E-02 0.000E+00 0.000E+00 *1.365E+14 0.000E+00 *1.365E+14

  • At specific activity limit

RESRAD, Version 6.5 T; Limit = 180 days 01/26/2011 15:31 Page 24 Summary EGL Vadose Zone Analysis File C:\\RESRADFAMILY\\RESRkD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Individual Nuclide Dose Summed Over All Pathways Parent Nuclide and Branch Fraction Indicated Nuclide Parent THF(i)

(j)

(i)

Ag-108m Ag-108m 1.OOOE+00 t= 0.000E+00 1.000E+00 DOSE(jt),

mrem/yr 3.000E+00 1.000E+01 3.000E+01 1.000E+02 3.000E+02 1.000E+03 6.673E-30 6.648E-30 6.598E-30 6.427E-30 5.963E-30 4.585E-30 2.165E-30 1.565E-31 C-14 Co-60 Cs-137 Eu-152 Eu-152 Eu-152 Gd-152 Eu-154 Fe-55 H-3 Ni-63 C-14 1.0006+00 Co-60 1.OOOE+00 Cs-137 1.000E+00 Eu-152 7.208E-01 Eu-152 2.792E-01 ZDOSE(j)

Eu-152 2.792E-01 Eu-154 1.000E+00 Fe-55 1.000E+00 H-3 1.000E+00 Ni-63 1.000E+00 0.000E+00

9. 285E-23 1.151E-27 1.355E-25
5. 248E-26 1.880E-25
0. 000E+00 3.858E-25
0. 0006+00 0.000E+00 0.000E+00 0.000E+00 8.152E-23 1.127E-27 1.288E-25 4.989E-26 1.787E-25 0.000E+00 3.571E-25 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.284E-23
1. 080E-27 1.164E-25 4.510E-26 1.615E-25
0. 000E+00 3.0060E-25 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.527E-23 9.293E-28 8.17 6E-26
3. 167E-26 1.134E-25 0.000E+00 1.781E-25 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.872E-24 6.055E-28 2.977E-26 1.153E-26 4.131E-26 0.000E+00
3. 796E-26
0. O00E+00 0.000E+00 0.000E+00 2.069E-28 1.352E-28 8.678E-28 3.362E-28 1.204E-27 O.O00E+00 1.697E-28 0.000E+00
0. 000E+00 0.000E+00 0.000E+00 1.864E-30 3.561E-32 1.379E-32 4.940E-32 0.000E+00
0. 000E+00 0.000E+00
6. 305E-09 0.000E+00 4.874E-03 0.O00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00
0. 000E+00 0.000E+00 4.145E-29 0.000E+00 0.000E+00 0.000E+00 Sr-90 Sr-90 1.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 THF(i) is the thread fraction of the parent nuclide.

RESRAD, Version 6.5 Ti Limit = 180 days 01/26/2011 15:31 Page 25 Summary :

EGL Vadose Zone Analysis File

C:\\RESRADFAMILY\\RESRAD\\6.5\\USERFILES\\HBNPPALTDISPREQUEST#2_JAN2011.RAD Individual Nuclide Soil Concentration Nuclide Parent THF(iE (M)

(i)

Ag-108m Ag-108m 1.000E+00 Parent Nuclide and Branch Fraction Indicated S(j,t),

pCi/g t= 0.000E+00 1.000E+00 3.000E+00 1.000E+01 3.000E+01 1.000E+02 3.000E+02 1.000E+03 1.200E-03 1.193E-03 1.180E-03 1.136E-03 1.018E-03 6.939E-04 2.321E-04 5.018E-06 C-14 Co-60 Cs-137 Eu-152 Eu-152 Eu-152 C-14 Co-60 Cs-137 Eu-152 Eu-152 ZS(j):

1.000E+00 1.000E+00 1.000E+00 7.208E-01 2.792E-01 1.200E-02 5.610E-02 1.680E-01 8.650E-03 3.350E-03 1.200E-02 0.000E+00 1.200E-02 1.200E-02 1.120E+00 1.120E-01 1.199E-02 1.198E-02 4.919E-02 3.781E-02 1.642E-01 1.567E-01 8.211E-03 7.400E-03 3.181E-03 2.866E-03 1.139E-02 1.027E-02 2.095E-17 5.973E-17 1.109E-02 9.474E-03 9.283E-03 5.555E-03 1.048E+00 9.176E-01 1.112E-01 1.096E-01 1.195E-02 1.506E-02 1.333E-01 5.142E-03 1.992E-03 7.134E-03 1.677E-16 5.459E-03 9.209E-04 5.764E-01 1.042E-01 1.184E-02 1.085E-03 8.398E-02 1.818E-03 7.040E-04 2.522E-03

3. 266E-16 1.130E-03 5.424E-06 1.526E-01 9.018E-02 1.147E-02 1.088E-07 1.666E-02 4.771E-05 1.848E-05
6. 619E-05 4.112E-16 4.553E-06 8.503E-14 1.459E-03
5. 438E-02 1.047E-02 7.619E-03 4.093E-19 0.0006+00 1.638E-04 1.543E-11 1.452E-09 2.255E-25 5.623E-10 8.736E-26 2.014E-09 3.129E-25 4.133E-16 4.127E-16 6.554E-13 7.419E-37 4.270E-36 0.000E+00 2.477E-09 1.579E-29 1.282E-02 8.159E-05 Gd-152 Eu-152 2.792E-01 Eu-154 Eu-154 1.000E+00 Fe-55 Fe-55 1.000E+00 H-3 H-3 1.000E+00 Ni-63 Ni-63 1.000E+00 Sr-90 Sr-90 1.000E+00 1.120E-02 1.094E-02 1.042E-02 8.818E-03 5.465E-03 1.025E-03 8.573E-06 4.596E-13 THF(i) is the thread fraction of the parent nuclide.

RESCALC.EXE execution time =

3.65 seconds PG&E Letter HBL-11-006 USEI PART B PERMIT EPA ID. NO. IDD073114654 REVISION DATE: SEPTEMBER 25, 2008 ISSUED BY THE STATE OF IDAHO CHAPTER C.3 "WASTE ACCEPTANCE CRITERIA" (PAGES 4 THROUGH 8 IN CHAPTER C)

USEI Part B Permit EPA ID. No.: IDD073114654 Revision Date: September 25, 2008 C.3 WASTE ACCEPTANCE CRITERIA C.3.1 Pre-acceptance Review The preacceptance protocol has been designed to ensure that only hazardous and radioactive material that can be properly and safely stored, treated and/or disposed of by USEI are approved for receipt at the facility. A two-step approach is taken by USEI. The first step is the chemical and/or radiological and physical characterization of the candidate waste stream by the generator.

The second step is the preacceptance evaluation performed by USEI to determine the acceptability of the waste for receipt at the facility. Figure C-2 presents a logic diagram of the preacceptance protocol that is utilized at the facility.

C.3.2 Radioactive Material Waste Acceptance Criteria The following waste acceptance criteria are established for accepting radiological contaminated waste material that is generally or specifically exempted from regulation by the Nuclear Regulatory Commission (NRC) or an Agreement State under the Atomic Energy Act of 1954

("AEA"), as amended. Material may also be accepted if it is not regulated or licensed by the NRC or has been authorized for disposal by the IDEQ and is within the numeric waste acceptance criteria. Waste acceptance criteria are consistent with these restrictions.

The following five tables establish types and concentrations of radioactive materials that may be accepted. These tables are based on categories and types of radioactive material not regulated by the NRC based on statute or regulation or specifically approved by the NRC or and Agreement State for alternate disposal. The criteria are consistent with these restrictions and detailed analyses set forth in Waste Acceptance Criteria and Justification for FUSRAP Material, prepared by Radiation Safety Associates, Inc. (RSA) as subsequently refined, expanded and updated in Waste Acceptance Criteria and Justification for Radioactive Material, prepared by USEI.

Material may be accepted if the material has been specifically exempted from regulation by rule, order, license, license condition, letter of interpretation, or specific authorization under the following conditions: Thirty (30) days prior to intended shipment of such materials to the facility, USEI shall notify IDEQ of its intent to accept such material and submit information describing the material's physical, radiological, and/or chemical properties, impact on the facility radioactive materials performance assessment, and the basis for determining that the material does not require disposal at a facility licensed under the AEA. The IDEQ will have 30 days from receipt of this notification to reject USEI's determination or require further information and review. No response by IDEQ within thirty (30) days following receipt of such notice shall constitute concurrence. IDEQ concurrence is not required for generally exempted material as set forth in Table C.4a.

Based on categories of waste described in the waste acceptance criteria, the concentration of the various radionuclides in the conveyance (e.g., rail car gondola, other container etc.) shall not exceed the concentration limits established in the WAC without the specific written approval of the IDEQ unless generally exempted as set forth in Table C.4a. Radiological surveys will be performed as outlined in ERMP-01 to verify compliance with the WAC. If individual "pockets" of activity are detected indicating the limits may be exceeded, the RSO or RPS shall investigate the discrepancy and estimate the extent or volume of the material with the potentially elevated

USEI Part B Permit EPA ID. No.: IDD073114654 Revision Date: September 25, 2008

.radiation levels. The RPS or RSO shall then make a determination on the compliance of the entire conveyance load with the appropriate WAC limits. If the conveyance is determined not to meet the limits, USEI will notify IDEQ's RCRA Program Manager within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a concentration based exceedance of the facility WAC to evaluate and discuss management options. The findings and resolution actions shall then be documented and submitted to the IDEQ.

The radioactive material waste acceptance criteria, when used in conjunction with an effective radiation monitoring and protection program as defined in the USEI Radioactive Material Health and Safety Plan and Exempt Radioactive Materials Procedures provides adequate protection of human health and the environment. Included within this manual are requirements for USEI to submit a written summary report of Table C.1 through C.2 radioactive material waste receipts showing volumes and radionuclide concentrations disposed at the USEI site on a quarterly basis.

USEI will also submit a Table C.3 through C.4b annual report of exempted products devices, materials or items within 60 (sixty) days of year end (December 3 1 st). The annual report will provide total volumes or mass of isotopes and total activity by isotope listing the activity of each radionuclide disposed during the preceding year, and the cumulative total of activity for each radionuclide disposed at the facility. The report will include an updated analysis of the impact on the facility performance assessment.

These criteria and procedures are designed to assure that the highest potential dose to a worker handling radioactive material at USEI shall not exceed 400 mrem/year TEDE dose, and that no member of the public is calculated to receive a potential dose exceeding 15 mrem/year TEDE dose, from the USEI program. TEDE is defined as the "Total Effective Dose Equivalent", which equals the sum of external and internal exposures. The public dose limit during operation activities is limited to 100 mrem/yr TEDE dose. An annual summary report of environmental monitoring results will be submitted to IDEQ by June 1 st for the preceding year.

Materials that have a radioactive component that meets the criteria described in Tables C.1 through C.4b and are RCRA regulated material will be managed as described within this WAP for the RCRA regulated constituents.

USEI Part B Permit EPA ID. No.: IDD073114654 Revision Date: July 24, 2009 Table C.1: Unimportant Quantities of Source Material Uniformly Dispersed* in Soil or Other Media**

Status of Equilibrium Maximum Concentration of Sum of Concentrations Source Material Parent(s) and all progeny present***

a Natural uranium in equilibrium with

<500 ppm / 167 pCi/g (""'U activity)

< 3000 pCi/g progeny Refined natural uranium (2 =U, 2' U,

<500 ppm / 333 pCi/g

<2000 pCi/g 234U; 234Th, 234mpa' 231Th)

Depleted Uranium (-",,

Irpa)

<500 ppm / 169 pCi/g

<2000 pCi/g b Natural thorium (""'Th + 2"bTh)

<500 ppm / 110 pCi/g

<2000 pCi/g

- 3 Th in equilibrium with progeny

<0.01 ppm / 200 pCi/g

_<2000 pCi/g ZL-rh (with no progeny) 0.1 ppm /:g2000 pCi/g Any mixture of Thorium and Sum of ratios:_ 1...

_<2000 pCi/g Uranium I

I Table C.2: Naturally Occurring Radioactive Material Other Than Uranium and Thorium Uniformly Dispersed* in Soil or Other Media**

Status of Equilibrium Maximum Sum of Concentrations of Parent Concentration of and All Progeny Present***

Parent Nuclide a

225Ra or 22"Ra with progeny in bulk form 1 500 pCi/g

< 4500 pCi/g Y

2Ra or *Ra with progeny in reinforced 1500 pCi/g 13,500 pCi/g IP-1 containers 1 c

Plupb with progeny( Bi & 2 TuPo) 1500 pCi/g 4500 pCi/g 4UK 818 pCi/g N/A Any other NORM

_<3000 pCi/g TAny material containing ORa greater than 222 pCi/g shall be disposed at least 6 meters from the external point on the completed cell.

Table C.3: Non-Production Particle Accelerator Produced Radioactive Material*****

Acceptable Material Activity or Concentration Any non-production All materials shall be packaged in accordance with USDOT packaging requirements.

particle accelerator Any packages containing iodine or volatile radionuclides will have lids or covers produced sealed to the container with gaskets. Contamination levels on the surface of the radionuclide.

packages shall not exceed those allowed at point of receipt by USDOT rules.

Gamma or x-ray radiation levels may not exceed 10 millirem per hour anywhere on the surface of the package. All packages received shall be directly disposed in the active cell. All containers shall be certified to be 90% full.

  • Average over conveyance or container. The use of the phrase "over the conveyance or container is meant to reflect the variability on the generator side. The concentration limit is the primary acceptance criteria.
    • Unless otherwise authorized by IDEQ, other Media does not include radioactively contaminated liquid (except for incidental liquids in materials). See radioactive contaminated liquid definition (definition section of Part B permit).
  • Diffuse waste with a total concentration (sum of concentrations of all radionuclides present) which is 2000 pCi/g or less may be accepted at the site (i.e., the controlling limit is 2000 pCi/g).

Conc. of U in sample Conc. of Th in Sample Allowable cone. of U + Allowable conc. of Th *1 Any material that has been made radioactive by use of a non-production particle accelerator as set forth in Federal Register, Vol. 72, No. 189, Monday October 1, 2007, page 55868.

USEI Part B Permit EPA ID. No.: IDD073114654 Revision Date: July 24 2009 Table C.4a: NRC Exempted Products, Devices or Items Exemption Product, Device or Item Isotope, Activity or 10CFR Concentration Part*

30.15 As listed in the regulation Various isotopes and activities as set forth in 30.15 30.14, Other materials, products or devices specifically exempted Radionuclides in 30.18 from regulation by rule, order, license, license condition, concentrations consistent with concurrence, or letter of interpretation the exemption 30.19 Self-luminous products containing tritium, '*Kr, 'H or 14 1Pm Activity by Manufacturing license 30.20 Gas and aerosol detectors for protection of life and property Isotope and activity by from fire Manufacturing license 30.21 Capsules containing 14C urea for in vivo diagnosis of

-4C, one pCi per capsule humans 40.13(a)

Unimportant quantity of source material: see table above

_<0.05% by weight source material 40.13(b)

Unrefined and unprocessed ore containing source material As set forth in rule 40.13(c)(1)

Source material in incandescent gas mantles, vacuum tubes, Thorium and uranium, various welding rods, electric lamps for illumination amounts or concentrations, see rules 40.13(c)(2)

(i)Source material in glazed ceramic tableware

  • 20% by weight (ii)Piezoelectric ceramic

<2% by weight (iii) Glassware not including glass brick, pane glass, ceramic

  • 10% by weight tile, or other glass or ceramic used in construction 40.13(c)(3)

Photographic film, negatives or prints Uranium or Thorium 40.13(c)(4)

Finished product or part fabricated of or containing tungsten

  • 4% by weight thorium or magnesium-thorium alloys. Cannot treat or process content.

chemically, metallurgically, or physically.

40.13(c)(5)

Uranium contained in counterweights installed in aircraft, Per stated conditions in rule.

rockets, projectiles and missiles or stored or handled in connection with installation or removal of such counterweights.

40.13(c)(6)

Uranium used as shielding in shipping containers if Depleted Uranium conspicuously and legibly impressed with legend "CAUTION RADIOACTIVE SHIELDING - URANIUM" and uranium incased in at least 1/8 inch thick steel or fire resistant metal.

40.13(c)(7)

Thorium contained in finished optical lenses

  • <30% by weight thorium, per conditions in rule.

40.13(c)(8)

Thorium contained in any finished aircraft engine part

_<4%

by weight thorium, per I containing nickel-thoria alloy, conditions in rule.

Table C.4b: Materials Specifically Exempted by the NRC Or NRC Agreement State Exemption Materials Isotope, Activity or Concentration*_,

10 CFR Byproduct material including production particle Byproduct material at 30.11 accelerator material exempted from NRC or concentrations consistent Agreement State regulation by rule, order, license, with the exemption**

license condition or letter of interpretation may be accepted as determined by specific NRC or Agreement State exemption.****

10 CFR Source material exempted from NRC or Agreement Source material at 40.14***

State regulation by rule, order, license, license concentrations consistent condition or letter of interpretation may be with the exemption.

accepted as determined by specific NRC or Agreement State exemption.****

10 CFR 70.17 Special Nuclear Material (SNM) exempted from SNM at concentrations NRC regulation by rule, order, license, license consistent with the condition or letter of interpretation may be exemption.

accepted as determined by specific NRC or I Agreement State exemption.****

  • Sum of all isotopes up to a maximum concentration of 3,000 pCi/gm.

-Specifically exempted production beam accelerator may be received under Table C.3 provisions [10 CFR 20.2008 (b)]

      • Also includes equivalent Agreement State regulation where applicable.
        • Similar material not regulated or licensed by the NRC may also be accepted.

Sum of all isotopes up to a maximum concentration of 3,000 pCi/gm. IDEQ shall be notified prior to the receipt of Special Nuclear Material not regulated or licensed by the NRC.

Additional Information for USEI's Waste Analysis Plan

1. US Ecology Idaho, Inc. (USEI) may receive contaminated materials or other materials as described in Tables C.1 - C.4b above. USEI may not accept for disposal any material that by its possession would require USEI to have a radioactive material license from the Nuclear Regulatory Commission (NRC).
2. Unless approved in advance by USEI and IDEQ, average activity concentrations may not exceed those concentrations enumerated in Tables C.1 and C.2.

Additionally, for Tables C.1 and C.2, individual pockets of material may exceed the WAC for the radionuclides present as long as the average concentration of all radionuclides within the package or conveyance remains at or below the WAC and the highest dose rate measured on the outside of the unshielded package or conveyance does not exceed those action levels enumerated in ERMP-01.

3. Other items, devices or materials listed in Table C.4a, which are exempted in accordance with 10 CFR Parts 30, 40 or equivalent Agreement State regulations or 10 CFR Part 70 may be accepted at or below the activities (per device or item) or concentrations specified in those exemptions.
4. The generator of the exempted or non-production particle accelerator produced waste must specify that the waste meets applicable acceptance criteria and/or exemption requirements.
5.

In accordance with permit requirements, notification of any exceedance of the WAC will be provided to the RCRA Program Manager within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, in accordance with the permit.

PG&E Letter HBL-1 1-006 HUMBOLDT BAY POWER PLANT PG&E RESPONSES TO QUESTIONS RELATED TO NRC's NOVEMBER 2, 2010 APPROVAL FOR ALTERNATE DISPOSAL OF HAZARDOUS WASTE CONTAINING LOW-ACTIVITY RADIOACTIVE DEBRIS AT US ECOLOGY IDAHO (USEI)

1. INTRODUCTION PG&E and NRC personnel met on July 29, 2010 to discuss NRC questions and comments for the alternate disposal and exemption request initially submitted April 1, 2010 (HBL-10-003). PG&E's previous responses to the NRC questions remain valid for the most part and are reiterated here. Where experience from implementation of the previous request is relevant to this request, the PG&E answer is updated, using italics, to indicate actual results.
2. NRC QUESTIONS & PG&E RESPONSES NRC Question 1: Are the concentrations in Table 1 maximum concentrations? The text on page 2 of Enclosure 1 to PG&E letter HBL-10-003 has conflicting information on this. What variability in the concentration and relative ratios of radionuclides are expected in the waste?

PG&E Response: The average activity in any shipment is not expected to exceed the values in Table 1 (see Enclosure 1 of HBL-11-006). The waste from Units 1 and 2 is expected to have only Cs-1 37 as a result of fallout of gaseous effluent releases during operation of Unit 3. Unit 3 waste will have Cs-1 37 and Co-60, based on on-site analysis, and other scaled nuclides (see Table I in Enclosure 1 of HBL-1 1-006) based on off-site analysis of waste samples. (Clarification:

Transuranic isotopes will be verified as non-detectable for waste shipped under this exemption) The waste material is expected to range from just detectable activity to the levels described in Table 1 for Cs-1 37 and Co-60 (Note: since implementing the alternate disposal from the previous request, PG&E has collected data for radionuclide concentrations in the shipments. The results of the actual concentrations are approximately 10% of the projected concentrations.

PG&E expects similar results for the radionuclide concentrations projected in this alternate disposal request.) The scaled nuclide concentrations were estimated from higher activity waste samples and may not be detectable in all samples of waste to be shipped under the exemption. Therefore the scaled nuclides are expected to range from non-detectable to the levels described in Table 1 (see note above).

Page 1 of 4 PG&E Letter HBL-11-006 NRC Question 2: How do you plan to verify the concentrations in the waste prior to shipment?

PG&E Response: Units 1 and 2 material will be surveyed under a MARSAME protocol with results from individual surface contamination surveys used to calculate the volume concentrations for each shipment. Unit 3 waste will be characterized by gamma analysis samples and scaled for other nuclides from off-site analysis.

NRC Question 3: What is the basis for the amount of dilution of the waste assumed in the source term concentration used in RESRAD? What is the basis for the assumed spreading of the waste (i.e., the area and thickness of the contaminated zone)?

PG&E Response: USEI's permit requires it to model dose from an individual project as if it were evenly distributed across its entire disposal cell (approximately an area of 88,221 square meters and 33.6 meters in depth) in its final submission to the Idaho Department of Environmental Quality. This is the same process that has been used for other submittals to NRC.

NRC Question 4: According to information provided to the NRC as part of a different 20.2002 request (for waste from Hematite site), the cover thickness at US Ecology Idaho ranges from 2.5 to 20 feet thick. A thickness of 11.8 feet is used in RESRAD modeling for the Humboldt Bay 20.2002 request. The external dose from the radionuclides potentially present in the waste from Humboldt Bay Power Plant is much higher when the cover is thinner. The dose calculated based on the concentrations assumed in the RESRAD analyses provided by Humboldt Bay Power Plant may still be acceptable if the cover is thinner, but the dose through a thinner cover may need to be evaluated if the concentration or dilution assumptions change as a result of the answers to the above questions.

PG&E Response: USEI's disposal cell cover is 3.60 meters thick. This depth includes the closure plus select non-radiological waste which serves as a radon barrier. This is the correct thickness for modeling purposes.

NRC Question 5: Can you provide the reference for the C-14 Kd values used?

PG&E Response: Kd values for C-14 are documented in Lapella Report of April 7, 2005, Table 3, "Site Specific values assigned to the RESRAD zones." (See, Attachment 1, Exhibit B in HBL-11-006)

NRC Question 6: What is the basis for the dimensions used in the MicroShield calculations? Also, why is the truck driver so far from the waste (4.8 m)?

PG&E Response: The following table responds to this question:

Page 2 of 4 PG&E Letter HBL-1 1-006 MicroShield File Name Description HBPP mix in 30 cy IM - surveyor rev.ms7 The dimensions are for a standard intermodal shipping container and a surveyor standing one meter from the container.

HBPP mix in 30 cy IM - driver rev.ms7 The dimensions ar6 for a standard intermodal shipping container and the truck driver in the cab of his truck 16 feet from the container. This is a measured distance using pin-type tri-axle intermodal container chassis with the container in its standard position for over the road travel and a tractor with a sleeper cab.

HBPP mix cell rev.ms7 The dimension is for spreading the waste in the disposal cell at USEI. The calculation takes credit for the height and shielding provided to the bulldozer operator by the dozer. The number of repetitions associated with this task assumes disposal of waste comingled in the stabilization process, a standard practice at USEI.

HBPP mix stab.ms7 The dimensions are for USEI's stabilization treatment tank. The volume (and associated repetitions) assumes multiple truckloads of waste are treated in the same batch, a common practice at USEI.

NRC Question 7: Where does the number of repetitions come from for the stabilization worker and cell operator?

PG&E Response:. Per the response to NRC Question 6 above, it is a common practice at USEI to comingle multiple truckloads of waste when performing stabilization for greater operational efficiency. The analyses assume an average of

- 2.5 truckloads of waste are mixed together throughout the project.

NRC Question 8: Is any cleanout of the trucks performed?

PG&E Response: The waste will be transported in lined intermodal containers.

Once emptied, each container will be swept (if required) and surveyed to ensure the container meets the USDOT "return to service" criteria. Because the containers will be used on the same project in a continuous loop, additional cleaning is not expected.

NRC Question 9: The number of employees is less for the surveyor and stabilization worker that was assumed in the 20.2002 request submitted for the disposal of waste from the Hematite site at US Ecology. Can you provide any explanation for why the number of workers is different in these two submittals when they both pertain to the same facility?

Page 3 of 4 PG&E Letter HBL-11-006 PG&E Response: The correct number of trucks is eight and the correct number of stabilization workers is six, consistent with the Westinghouse Hematite alternate disposal requests. The updated Table 2, "Doses to Drivers and USEI Employees,"

is shown in Enclosure 1. The number of stabilization workers for the pervious HBPP submittal remained at 4. The Hematite request involved shipping by rail and truck. As a result, 4 surveyors were used at the rail facility and 4 surveyors were used upon arrival at USEI. The Humboldt request only uses trucks, so only 4 surveyors are used upon arrival at USEI. Note that the current request (HBL-11-006) uses more trucks than the previous request.

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