ML20147J141

Rev 0 to Waltz Mill Facility SNM-770 Conceptual Remediation Plan

ML20147J141
Person / Time
Site:	Waltz Mill
Issue date:	09/30/1996
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20147H897	List: ML20147H893 ML20147J131 ML20147J141
References
PROC-960930, NUDOCS 9704110008
Download: ML20147J141 (57)

Text

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WESTINGHOUSE ELECTRIC CORPORATION J

1 WALTZ MILL FACILITY SNM-770 i

CONCEPTUAL REMEDIATION PLAN i

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i Revision 0 September 30,1996 PD ADO Ob 022 P PDR

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WESTINGHOUSE ELECTRIC CORPORATION: .

WALTZ MILL FACILITY

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SNM-770 CONCEPTUAL REMEDIATION PLAN i

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Revision 0 l September 30,1996 l 9704110008 970407 PDR ADOCK 05000022 P PDR

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TABLE OF CONTENTS TABLE OF CONTENTS i

SECTION TITLE PAGE 1 . . . . . . . . . . GENERAL INFORMATION . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 . . . . . . . . . . License lnformation . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1

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1.2 . . . . . . . . . . Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -2 1.3 . . . . . . . . . . Site Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.4 . . . . . . . . . . Administration of the Remediation Plan . . . . . . . . . . . . . . . 1-2

. . . . . . . . . . References For Section 1 . . . . . . . . . . . . . . . .. . . . . . . 1-3 1l l

2 . . . . . . . . . . DESCRIPTION OF PLANNED REMEDIATION ACTIVITIES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1 . . . . . . . . . . Remediation Objective and Activities . . . . . . . . . . . . . . . . . 2-1 2.1.1 . . . . . . . . . Remediation Objective . . . . . . . . . . . . . . . . . . . . . . . . . . 2.1 2.1.2 . . . . . . . . . Remediation Activities . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.1. 3 . . . . . . . . . Schedule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-2 2.1.4 . . . . . . . . . Remediation Methods . . . . . . . . . . . . . . . . . . . . .. . . . 2-2 2.2 . . . . . . . . . . Remediation Controls . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 2.2.1. . . . . . . . . Remediation Organization and Responsibilities . . . . . . . . . . . 2-3 )

2.2.2 . . . . . . . . . Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 2.2.3 . . . . . . . . . Work Controis ...... . . . . . . . . . . . . . . . . . . .. . . . 2-3 2.2.4 . . . . . . . . . Contractor Assistance . . . . . . . . . . . . . . . . . . . . .. . . . 2-4 2.2.5 . . . . . . . . . Training Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-4 2.2.6 . . . . . . . . . Remediation Accident Analysis ................ . . . 2-4

. . . . . . . . . . Re ferences For Section 2 . . . . . . . . . . . . . . . . . . . . . . . . 2-5 3 . . . . . . . . . . RADIOLOGICAL CONTROLS PROGRAM . . . . . .. . . . 3-1 3.1 . . . . . . . . . . Radiation Protection Program . . . . . . . . . . . . . . . . . . . . . 3-1 4 . . . . . . . . . . RADIOLOGICAL ACCEPTANCE CRITERIA AND SURVEYS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1 . . . . . . . . . . Soil Remediation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 l 4.2 . . . . . . . . . . Retired Facilities Remediation . . . . . . . . . . . . . . . . . . . . . 4-1 )

. . . . . . . . . . References For Secticn 4 . . . . . . . . . . . . . . . . . . . . . . . . 4-2 i REVISION 0  !

TABLE OF CONTENTS 5' . . . . . . . . . . FUNDING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 I

......... References For Section 5 . . . . . . . . . . . . . . . . . . . . . . . . 5-2

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. . . . . . . . . . ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1

. . . . . . . . . . Attachment A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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ii REVISION 0

l TABLE OF CONTENTS j TABLE LIST OF TABLES PAGE '

2-1 . . . . . . . . . . List of SNM-770 Retired Facilities and Areas . . . . . . . . . . . 2-6 l l

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TABLE OF CONTENTS l

FIGURE LIST OF FIGURES PAGE

' 2-1 , . . . . . . . . Waltz Mill Proposed Remediation Schedule . . . . . . . . . . . . . 2-8 iv REVISION 0

TABLE OF CONTENTS LNT OF ACRONYMS i

ALARA As Low As Reasonably Achievable CFR Code of Federal Regulations NRC Nuclear Regulatory Commission QA Quality Assurance RCA Radiologically Controlled Area 1

rem Roentgen Equivalent Man  :

SDMP Site Decommissioning Management Plan SNM Special Nuclear Material TBD To Be Determined TEDE Total Effective Dose Equivalent WTR Westinghouse Test Reactor b

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l GENERAL INFORMATION \

l l SECTION 1 GENERAL INFORMATION ,

l The NRC identified the Westinghouse Electric Corporation (Westinghouse) Waltz Mill site, near Madison, Pennsylvania, as a Site Decommissioning Management Plan (SDMP) site. In order to be responsive to NRC concerns and the requirements of NUREG-1444 (Ref.1), Westinghouse is developing a plan to address remediation activities for this site. The site radiological areas have been extensively characterized and are controlled so that they pose no threat to the health and safety of the site worker or the general public. The Waltz Mill site currently operates under NRC Special Nuclear Materials license SNM-770. -Westinghouse is not pursuing license termination and will continue to conduct licensed operations at this facility. Therefore, a ,

decommissioning plan to terminate the license is not appropriate, so the plan will be referred to as a Remediation Plan (" Plan"). The Remediation Plan addresses remediation of the soil and retired facilities / areas of the site under the SNM-770 license.

This document outlines the Remediation Plan being developed for the Waltz Mill site, identifies the basic format /information to be provided and assumptions that will form the Remediation Plan. The Remediation Plan is being prepared using Regulatory Guide 3.65, " Standard Format ,

and Content of Decommissioning Plans for Licensees under 10 CFR Parts, 30,40, and 70" (Ref.

2). Although Regulatory Guide 3.65 is written as guidance for preparing a decommissioning l plan, it is considered appropriate for the development and general format of the Waltz Mill Remediation Plan.

, 1.1 LICENSE INFORMATION License- SNM-770 1

Docket Number: 70-698 l l

Locat i on of Uset Westinghouse Electric Corporation Waltz Mill Site 1 Interstate 70 - Madison Exit 25A P.O. Box 158 Madison, PA 15663 Licensee of Use: Westieghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230 l

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GENERAL INFORMATION 1.2 OBJECTIVE The Remedirtion Plan will describe the objectives, activities, and controls that will apply to the remediation of the soil and retired facilities / areas. The objective of the Remediation Plan is to remediate retired facilities and areas to the extent considered prudent for the continued licensed operation at the site. The following two general criteria are used to obtain this objective:

, 1. Remediate soil to achieve a condition which targets a 15 mrem / year dose from applicable pathways, as demonstrated by the RESRAD comp. iter model.

2. Remediate retired facilities / areas to radiological levels which would not require the application of radiation protection controls for high radiation areas or airborne radioactive material areas.

1.3 SITE DESCRIPTION The Waltz Mill site is located approximately 30 miles southeast of Pittsburgh in Westmoreland County, Pennsylvania. The site is approximately 850 acres and is located about three miles west of the town of New Stanton between the towns of Madison and Yukon. The retired facilities and areas addressed by this Remediation Plan are contained within approximately 85 acres. This 85 acre area is fenced and provided with continuous security. '

The Waltz Mill site is operated under the control of the Nuclear Services Division of the Westinghouse Energy Systems Business Unit. The site operates in accordance with NRC License i Number SNM-770, which encompasses 10 CFR 30,10 CFR 40, and 10 CFR 70 (Refs. 3,4, i and 5, respectively). The Westinghouse Test Reactor (WTR) is maintained by a Possession Only  !

License (TR-2) and is not addressed by this document.

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1.4 ADMINISTRATION OF THE REMEDIATION PLAN I The Remediation Plan will provide sufficient detail of the remediation activities at Waltz Mill to allow NRC review and approval. Major remediation activities will be evaluated to ensure they are consistent with the Remediation Plan. If not, further evaluation will be performed to ensure that the activity does not create a condition which exceeds the consequences of the bounding remediation accident scenario. Should this evaluation conclude that the proposed activity may not proceed, the activity will be altered to comply with the established criteria or NRC approval will be obtained prior to the performance of work. Specific criteria to be used for this evaluation will be proceduralized.

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I 1-2 REVISION 0 l

GENERAL INFORMATION REFERENCES FOR SECTION 1

1. NUREG-1444, Supplement 1, " Site Decommissioning Management Plan," November 1995..

2. NRC Regulatory Guide 3.65, " Standard Format and Content of Decommissioning Plans For Licensees Under 10 CFR Parts 30,40, and 70," August 1989.

3. 10 CFR 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material. "

4. 10 CFR 40, " Domestic Licensing of Source Material."

5. 10 CFR 70, " Domestic Licensing of Special Nuclear Material."

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DESCRIPTION OF PLANNED REMEDIATION ACTIVITIES

. SECTION 2 DESCRIPTION OF PLANNED REMEDIATION ACTIVITIES 2.1 REMEDIATION OBJECTIVE AND ACTIVITIES 2.1.1 Remediation Objective The objective is to remediate retired f'acilities and areas to the extent considered prudent for the continued licensed operation at the site. This remediation objective is compatible with the plans for future use of the Waltz Mill site and Westinghouse is not pursuing termination of the SNM-770 license at this time. The existing condition of the site poses no threat to the health and safety of the general public. In addition, controls are implemented in accordance with the Waltz Mill radiation protection program to assure site workers are adequately protected. The Plan will establish a strategy for the systematic remediation of soil and retired facilities to accomplish the objective.

The first major activity will be to address the soil and groundwater contamination on the Waltz Mill site. The results of soil and groundwater characterization, monitoring and remediation are detailed in References 1,2,3,4, and 5. Remediation of the contaminated soil will reduce the source term for groundwater contamination. Currently, the radiologically affected groundwater is being controlled, monitored and treated. This document establishes the plan for remediation of soil to meet the established criteria (see Section 4).

The second major activity will be the remediation of retired facilities. The results of the retired facility characterizatior, are detailed in Reference 6. Criteria for remediation of the retired facilities will be established (Section 4). The retired facilities will continue to be controlled according to the radiation protection program.

2.1.2 Remediation Activities The Remediation Plan will include a brief description of each retired facility and area governed by the SNM-770 license and a summary of the applicable radiological characterization data.

Table 2-1 provides a list of the retired facilities and areas on the Waltz Mill site governed by IWnse SNM-770 and identifies the general methoci of remediation. For planning purposes Tiole 2-1 categorizes the site into three segments:

o The Solid and Liquid Waste Processing Area o The WTR Area o The General Facilities and Areas Table 2-1 will assign a remediation priority for the retired facilities and areas. The prioritization is based on considerations that include radiological characterization information, dose assessment, current and future uses, and cost benefit.

2-1 REVISION 0

DESC'llPTION OF PLANNED REMEDIATION ACTIVITIES i

The Remediation Plan will contain a discussior /the specific activities and methods planned to .

' be used to remediate the retired facilities and areas. It will also include a recommended work sequence of remediation activities for planning purposes, based on the assigned prioritization. ,

2.1.3. Schedule The soil remediation work is currently scheduled from January 1997. to December 1998. The retired facilities work is currently scheduled from January 1998 to December 1999. The TR-2 .

' (WTR) license termination is currently scheduled from January 1999 to December 2003. See -

Figure 2-1, " Waltz Mill Proposed Remediation Schedule."

Changes to the schedule may be made at Westinghouse's discretion as a result of annual budget '

constraints, availability of a radioactive waste burial site, interference with ongoing Waltz Mill operations, ALARA considerations, the potential for cross contamination of adjacent facilities, .  ;

funher characterization measurements and/or temporary on-site radioactive waste storage l operations.

2.1.41 Remediatinn Methnde Remediation methods are dependent on the facility to be remediated, type and extent of contamination, and the remediation objective. Contaminated facilities and soil will fall into one or more of the following categories for remediation:

1. Remove and dispose of as radioactive waste

2. Decontaminate for unrestricted release

3. Decontaminate to acceptance criteria and leave in place .

4. No action since radiological conditions meet acceptance criteria l

3 Each retired facility and area will be evaluated to determine the best method for remediation. l Criteria that will be used in the evaluations include: availability of a burial facility; the cost of I decontamination versus the cost of burial; radiological and occupational hazards involved; and 1 i site operations in progress or planned.

Removal of structures, equipment and components can be achieved using proven '

mechanical / thermal cutting and demolition equipment. Mechanical methods could involve diamond wire cutting, saw cutting, concrete scabbling, the use ofjackhammers, and machining. ,

Thermal methods could involve metal cutting with an oxy-acetylene torch, plasma arc cutting,  !

i or oxy-lance cutting methods. Soil removal would normally be accomplished by excavation of l the contaminated soil.

Numerous methods of decontamination of contaminated surfaces are available. These include:

wiping down the surface; blasting the surface with grit, sand, ice, abrasive or steel shot; bydrotazing; pressure washing; chemical decontamination; electro-polishing; scabbling concrete.

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These generic material removal and decontamination techniques, and possibly others, will be applied to remediate those retired facilities and soil areas determined to require remediation. The 2-2 REVISION 0 i

b DESCRIPTION OF PLANNED REMEDIATION ACTIVITIES '

Remediation Plan will include a description of specific decontamination arxi/or removal methods -

~ planned to be used for retired facilities and contaminated soil areas. <

2.2 REMEDIATION CONTROLS L -2.2.1 Remadiation Orannivatinn and Ramonsibilitiec

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- The Remediation orgamzation will be integrated into the Westinghouse Waltz Mill facility and  ;

will comply with the existing license and applicable regulatory requirements. A senior level -  ;

, Westinghouse Manager will have overall responsibility for the facility and the functional groups >

for: operations,' engineering, industrial hygiene, safety, security, environmental compliance, facilities support, radiation protection and quality assurance. ]

, The Westinghouse Remediation Project Director will coordinate the elements of the functional

• i groups and contractors.

LA Review Committee will be established to monitor remediation operations to ensure that they 3 -are being performed safely. The Review Committee will be independent of the Remediation '

Project Director. They will review and audit major remediation activities dealing with radioactive ,

material and radiological controls. In addition, the Review Committee will review changes to the Remediation Plan. ,

A description of the remediation project organization, the key organizational positions and their  !

responsibilities will be provided in the Remediation Plan.

a 2.2.2 Procedures 1 Remediation activities will be performed in accordance with the Waltz Mill site administrative '

and implementing procedures. To ensure procedures are adequate to govern remediation ectivities, a review of the current procedures will be performed. If necessary, procedures will be revised and new procedures developed prior to the start of field remediation activities.

2.2.3 Work Controls  !

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The Remediation Plan will establish the guidelit.es for the preparation of a remediation work '

control program. This program will: -

.o . Assure that remediation work is performed in accordance with Waltz Mill administrative

. and implementing procedures o~

Assure that occupational safety and radiation safety requirements are met c . Assure that adequate reviews and approvals are obtained prior to the start of work

' o. . Control changes to work steps o- Describe implementing documents (e.g., work package preparation, review, issue,

. performance, and closure)  !

o  : Assure adequate documentation of remediation work performed l I

2-3 REVISION 0

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DESCRIPTION OF PIANNED REMEDIATION ACTIVITIES i 2.2;4. Cantractor Ansintance

Contractors and subcontractors performing work under this Remediation Plan will be required to comply with the applicable Waltz Mill site procedures.

1 2.2.5 Trainino Prommm i i

Personnel (employees, contractors, and visitors) who may require access to the work areas or )

a radiologically controlled area (RCA) associated with the remediation effort shall receive appropriate training commensurate with the potential hazards to which they may be exposed.

Radiation protection training will be provided to personnel who will be performing remediation I work in radiological areas or handling radioactive materials. The' training will ensure that remediation project personnel have sufficient knowledge to perform work activities in accordance

with the requirements of the radiation protectioi program and accomplish ALARA goals and i '

objectives. The principle objective of the training program is to ensure that personnel understand

. the responsibilities and the required techniques for safe handling of radioactive materials and for minimizing exposure to ionizing radiation.

Records of training will be maintained which include trainees name, date of training, type of  ;

. training, test results, authorization for protective equipment use, and instructor's name. i Radiation protection training will provide the necessary information for workers to implement sound radiation protection practices.

2.2.6 Remedintinn Accident Analysis  ;

The Remediation Plan will include analysis of a postulated remediation accident scenario (s) considered 7.o produce worst-case consequences to offsite individuals. The scenario (s) will be selected such that consequences bound those that could be associated with expected remediation conditions, off-normal occurrences, and remediation accidents. The quantity of radioactivity postulated to be released wil! be documented, along with dose consequences. The objective of

- the bounding remediation accident analysis is to show that remediation of the Waltz Mill site retired facilities and areas can be accomplished with no threat to the general public.

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DESCRIPTION OF PLANNED REMEDIATION ACTIVITIES '

REFERENCES FOR SECTION 2

1. " Data Summary Report, Soil and Groundwater Characterization, Waltz Mill Site,"

Earth Sciences Consultants, May 1993.

2. " Soil and Groundwater Characterization, Waltz Mill Site," Earth Sciences Consultants, August 1994.

3. " Additional Site Characterization, Waltz Mill Site," Earth Sciences Consultants, August 1995.

4. " Bench Scale Study and Leaching Evaluation, Waltz Mill Site," ICF Kaiser, October 27, 1995.

, 5. " Groundwater Modeling for Radiological Dose Assessment, Waltz Mill Facility," ICF Kaiser, March 18,1996 (Revised May 1,19%).

6. " Westinghouse Electric Corporation, Waltz Mill Facility, Characterization Report; Nuclear Material License SNM-770, Active and Retired Facilities," Scientific Ecology Group, dated February 1994.

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2-5 REVISION 0  !

DESCRIPTION OF PIANNED REMEDIATION ACTIVITIES Table 2-1 LIST OF SNM-770 RETIRED FACILITIES AND AREAS FACILITY / AREA EXCEEDS ACCEPTANCE PRIORITY  !

CRITERIA : PROPOSED ACTION SOllD AND LIOUID WASTE PROCESSING AREA Liquid Waste Retention Basin YES: Remove, Structure & TBD Contaminated Soil WTR Basin No.1 TBD*: TBD WTR Basin No. 2 TBD: TBD WTR Basin No. 3 TBD: TBD LLRW Storage Pad TBD: TBD Evaporator Building TBD: TBD 500, A) Gallon Storage Tank TBD: TBD 20,000 Gallon Storage Tanks TBD: TBD Process Drain Line TBD: TBD (1)

WTR AREA Hot Cells YES: Decontaminate Structure TBD Hot Cell Loading Area YES: Decontaminate Stmeture TBD Metallographic Laboratory YES: Decontaminate Stmeture TBD Sub-Cell Room YES: Decontaminate Structure TBD (2)

Sub-Cell Fan Room YES: Decontaminate Structure TBD Sub-Cell Fan Room Systems YES: Remove / Decontaminate TBD Equipment Mechanical Test Facility NO: No Action Required j Annex Transfer Canal YES: Drain & Decontaminate TBD (2)

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2-6 REVISION 0

DESCRIPTION OF PLANNED REMEDIATION ACTIVITIES Table 2-1 LIST OF SNM-770 RETIRED FACILITIES AND AREAS FACILITY / AREA EXCEEDS ACCEPTANCE PRIORITY CRITERIA : PROPOSED ACTION Hot Cell Ventilation Stack Base NO: No Action Required North and South Storage Pits NO: No Action Required Ion Exchange Cubicle NO: No Action Required Primary Coolant Tunnel NO: No Action Required West Annex Utilities Tunnel NO: No Action Required WTR Head Tank Tunnel NO: No Action Required GENERAL FACTIITIES & AREAS Former LLRW Storage Pad TBD: TBD Transfer Building Pool TBD: TBD Laundry Facility NO: No Action Required Parking Lot A, B, C, and D Build.s TBD: TBD Parking Lot G Building TBD: TBD Parking Lot Laundry Facility NO: No Action Required Parking Lot Works Engineering TBD: TBD oTBD - To Be Determined

1. Some work may be performed on the process drain line in the Solid and Liquid Waste Processing Area when remediating soils in this area. However, remediation of the remainder of this line is not required.

l 2. Remediation of these structures will be performed in conjunction with remediation of WTR facilities. '

2-7 REVISION 0 L

s Waltz Mill Proposed Remediation Schedule i

MAJOR ACTIVITIES 1997 1998 1999 2000 2001 2002 2003 t

Soil Remediation Project Preparation Remove Structures and interferences -

Remove Contaminated Soil Remediate SNM-770 Retired Facilities D

WTR License Termination .

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RADIOLCGhCAL CONTROL PROGRAMS

, SECTION 3 '

RADIOLOGICAL CONTROL PROGRAMS 4 3.1 Radiation Protection Program l i The management and control of the Waltz Mill radiation protection program is described in the .  ;

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Waltz Mill Radiation Protection Manual. The Radiation Protection Manual performs the following functions. t

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Documents Westinghouse's commitment to comply with federal and state radiation

protection regulations.

j -o Defines the organization structure used to manage the radiation protection program, and

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'the responsibilities, authorities and qualifications of the key staff positions.

o . Specifies corporate and site policies, program objectives and standards to be followed '

_ through the radiation protection program implementing procedures.

oL Identifies the scope of activities to be controlled through the radiation protection program l l implementing procedures.

The Radiation Protection Manual also presents the policy statements for the respiratory protection l

, and ALARA programs. These policy statements are included to emphasize the commitment of .

Westinghouse to incorporate these program principles and philosophy into all applicable site work activities.

The radiation protection program will control the remediation project work activities for all  :

project personnel. The program is implemented through the Waltz Mill radiation protection  !

j- procedures. Administrative procedures define administrative controls and responsibilities for

program implementation. Implementing procedures provide instructions for performing specific '

program tasks. An overview of the program will be included in the Remediation Plan.

The remediation project may involve work activities which are not normally performed during site operations at Waltz Mill. To ensure the current Waltz Mill radiation protection program is adequate to protect the health and safety of the workers during the remediation project, a review  :

of the current program will be performed. If necessary, program enhancements will be j implemented prior to the start of field remediation activities.  ;

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l 3-1 REVISION 0 1

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RADIOLOGICAL ACCEPTANCE CRITERIA AND SURVEYS SECTION 4 RADIOLOGICAL' ACCEPTANCE CRITERIA AND SURVEYS 4.1 SOIL REMEDIATION Westinghouse has performed extensive characterization of the Waltz Mill site to determine the types and quantities of radioactive materials present in the soil and groundwater (Refs.1, 2, 3, 4 and 5). The results of these studies identify low levels of radioactive material present in small, isolated areas of the site. The presence of the residual radioactive material on the site poses no threat to the health and safety of the general public. The remediation effort will reduce the quantity of radioactive material present to target a 15 mrem / year dose from applicable pathways, as demonstrated by the RESRAD computer model, i ..

The Remediation Plan will present or reference the following information related to the remediation of radioactive material in the site soils.

o A summary of the characterization data for site soils.

o The RESRAD model, input parameters, assumptions, and constraints to be used for calculation of site dose due to residual radioactive material in the soil and groundwater (Refs. 6 and 7). A summary of the Waltz Mill Dose Assessment is included a Attaclunent A. This report presents the input parameters, assumptions, and constraints to be used in the calculation of the dose conversion factors for site soil areas.

o The survey methods, data quality objectives and procedures will be used for collection and analysis of post-remediation soil samples.

4.2 RETIRED FACILITY REMEDIATION Westinghouse has performed an extensive characterization of the retired facilities on the Waltz Mill site to determine the types and quantities of radioactive material present (Ref. 8). The results of this study show that only a small number of retired facilities have radioactive material present in sufficient quantity to constitute a radiological hazard. Currently, these facilities pose no threat to site workers because of the physical and administrative controls. The objective is to reduce the quantity of radioactive material present in these facilities to levels which are As Low As Reasonably AcV:vable (ALARA) and below levels which would require the application of radiation protection controls for high radiation or airborne radioactive material areas.

The Remediation Plan will present the following information related to the remediation of the retired facilities.

o A summary of the characterization data for the retired facilities o The identification of those facilities where remediation is appropriate o Tir goal for reduction of the radiological hazard in each of the facilities to be remediated L

4-1 REVISION 0 l 2

RADIOLOGICAL ACCEPTANCE CRITERIA AND SURVEYS REFERENCES FOR SECTION 4

1. " Data Summary Report, Soil and Groundwater Characterization, Waltz Mill Site,"

Earth Sciences Consultants, May 1993.

2. " Soil and Groundwater Characterization, Waltz Mill Site," Earth Sciences Consultants, August 1994.

3. " Additional Site Characterization, Waltz Mill Site," Earth Sciences Consultants, August 1995.

4. " Bench Scale Study and Leaching Evaluation, Waltz Mill Site," ICF Kaiser, October 27,1995.

5. " Groundwater Modeling for Radiological Dose Assessment, Waltz Mill Facility," ICF Kaiser, March 18,1996 (Revised May 1,1996).

6. NRC NUREG/CR-5512, " Residual Radioactive Contamination Fmm Decommissioning," dated January 1990.

7. NRC Policy and Guidance Directive, PG-8-08, " Scenarios for Assessing Potential Doses Associated with Residual Radioactivity," dated May,1994.

8. " Westinghouse Electric Corporation, Waltz Mill Fxility, Characterization Report; Nuclear Material License SNM-770, Active and Retired Facilities," prepan:d by Scientific Ecology Group, dated February 1994.

1 4-2 REVISION 0 i

FUNDING J ' SECTION 5 FUNDING Westinghouse has established one Financial Assurance Mechanism that encompasses all of the Westinghouse facilities that hold NRC licenses. The Financial Assurance Mechanism established by this approach meets all the requirements of the NRC's decommissioning financial assurance regulations contained in 10 CFR 30,40, and 70. Appropriate updates have been submitted to 1

the NRC to maintain adequate levels of financial assurance.

In March of 1996, Westinghouse submitted to the NRC a revision to the Financial Assurance t Mechanism for Decommissioning its NRC licensed facilities (Ref.1). This submittal addressed the Waltz Mill Site, NRC License Number SNM-770. This submittal was reviewed by the NRC ,

staff and found to be in compliance with the regulations (Ref. 2).

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FUNDING l REFERENCES FOR SECTION 5

1. Westinghouse letter, Nardi to Weber (NRC), dated March 22,1996;

Subject:

" Revised Financial Assurance Mechanism for Decommissioning."

2. NRC letter, Nelson to Nardi (Westinghouse), dated March 29,1996;

Subject:

" Response to Revised Financial Assurance Mechanism for Decommissioning, Dated March 22, 1996."

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5-2 REVISION 0

ATTACHMENTS ,

ATTACHMENTS .

Attachment A:  : Waltz Mill Dose Assessment a

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. A-1 REVISION 0 l

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-Waltz Mill Dose Assessment -

• Dose Convenion Factor Determination c

WALTZ MILL DOSE ASSESSMENT DOSE CONVERSION FACTOR DETERMINATION preparedfor Westinghouse Electric Corporation September 1996

Waltz Mill Dese Assessment Dose Conversion Factor Determination TABLE OF CONTENTS SECTION-PAGE

1. INTRO D U CTI ON . . .. . . .. . . . . . . .. . .. . . . . . . . ... . .. . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . .. . . . . .. . . . . . . . . . . .. . . . . . .. . . .

2. DOSE ASSESSMENT CALCULATIONS: SOIL AND GROUNDWATER................. .. 2-1 2.1 In trod uction . ... .. .. . . . . . . .. . . . ... . . .. . . . . . . . . . . . . . . . . . . . . ... . . .. . . .. . . .. . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .

2.2 Description of Contarninated Regions ...... ......... ..... . .............................................. 2-1 2.2.1 Region 1.............................................................................................2-1 2.2.2 Region 2..................................................................................................2-1 2.2.3 Region 3................ ... .....................................................................2-2 2.2.4 Contamination Zone Factors .... .. ........... . . .... .... ... ... ... ............ ....... .......... 2-2 2.3 Do se Analysis . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . 2-2 2.3.1 Receptors.......................................................................... . . . . . . . . . . . 2-2 2.3.2 Computer Model Development... .............. .. . .......... ....... . .... .. .. . . . ... 2-3 2.4 Dose Pathways /Models . ... .. .. .. .. .. .... ...... . . .. . .. .. .. .. .. .. . ..... .. . . . . . ... .. .. ... . ....... . ... . 2-3 2.4.1 Industrial Scenario.......... ... .. ......... ...................................................2-3 2.4.2 Family-Farm Scenario . ... ... .... ..... . . ... . .. ..... .. . . .. . . ... ..... . .. ... ... . . . . ... . . . .. . .. ... 2-4 2.4.3 Sq uattdeenario .. .. . . ..... ... ........... ... . .. . . . ... ... ..... . .. ... ........ . ..... ... . .. . .. .. . . . . . . . 2-4 2.5 RES RAD Input Parameters .. ..... . . .. .. ........... ........ . ... .. .. ... ... . . .. .. .. .. . . .. . .. .. . . . . . .. .. .. . 2-4 2.5.1 Contaminated Zone Area .. ... .... ......... ........... .. . .. .. ...... . . . .......... .... ..... 2-5 2.5.2 Contamination Zone Thickness ... . ............. .. . .... ...... ........ . .... ....... .. .. 2-5 2.5.3 Distribution Coefficients ..... ......... ........ .... ...... ......... .... .......... . ....... . .. 2-5 2.5.4 Other RESRAD Input Parameters ........ . .... ......... ........ ...... ..... . ...... ... . 2-7 2.6 Base Case Results .. .... ........... . ... ..... . ... .. .... ... ...........................................2-12

3. RE FERENC E S . . .. . . . .. . . . . .. . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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Waltz Mill Dose Assessment Dese Conversion Factor Determination LIST OF TABLES SECTION-PAGE ,

2.1 Zone Area Sizes for Base Case Calculations... .......................................... ................. 2-13 2.~2 Potentially Contaminated Zone Area: Contamination and Hydrogeological Data....... 2-14 2.3 ~ RES RAD Default Val ues . . . . .. . .. ...... . . . . ..... ... .... . .. ... . . .... . . .. . . . . . ... .. . . . .. .. .. . .... .... .. . .. . . . . .. . .. .. 2- 15 2.4 Distribution Coe fficients .. . . .. . .. ... ... . .. .... . .. . . . .. ...... . . . .... . . .. . .... .... ... .. . . ... .. . . .... .. ...... . . ..... . 2- 15 2.5a Soil Dose Assessment Dose Conversion Factors - 1 9 96 . . . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . . . . . . . . . . 2- 1 6 2.5b Soil Dose Assessment Dose Conversion Factors - 2 016 . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -2 0 l

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- Waltz Mill Dose Assessment Dose Conversion Factor Determination LIST OF FIGURES '

2.1 Waltz Mill Site Layout RESRAD Analysis Regions and Areas . .................. ............ 2-24

2.2 G eneri c S cenario Pathways . . .. . .. . .. ... . .. ... . .. ... .. . . . . .. . .. . . . ... . . ... .. .. . .. . . .. .. ....... . . .. . .. . . .... .. . . . . 2-2 5 APPENDICES A Glossary...................................................................................................................A-1 _

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. Waltz Mill Dose' Assessment i Dose Conversion Factor Determination -

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1. INTRODUCTION -

<. This report, prepared by TLO Services, Inc. (TLG) for Westinghouse Electric Corporation, documents the determination of dose conversion factors for soils at the Westinghouse Waltz Mill site. Annual.

- millirem per unit concentration of radioactivity in soils were calculated for maximally-exposed dose receptors under plausible site release options resulting from exposure to the radionuclides present in the site's soil as of March 1996 and in 2016, after a 20-year delay period.

It is important to note that the exposure scenarios considered herein are hypothetical in nature'and have -  :

never occurred. Operations under existing regulatory controls at the site preclude these exposure pathways and ensuing radiation exposures. This dose assessment analysis was performed in ,

accordance with guidance provided by the U.S. Nuclear Regulatory Commission (NRC) in Policy.

Guide.8-08 [1] and NUREG 5512 [2].

l Section 2 of this report presents a physical description of the contaminated soil regions of the Waltz

- Mill site as was determined from site characterization data provided by Westinghouse. This section then describes plausible scenarios, dose receptors, and pathways by which individuals could receive indiation exposure due to the site's soil radioactivity. The methods and models used to generate dose conversion factors are presented. i 4

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' Wc.Itz Mill Dose Assessment Dese Conversion Factor Determination Section 2, Page 1 of 25

2. DOSE ASSESSMENT CALCULATIONS: SOIL AND GROUNDWATER

2.1 INTRODUCTION

Dose assessment calculations were performed to generate dose conversion factors for a dose receptor (the " critical individual") at me Waltz Mill site - given different site use alternatives -

after SNM-770 and TR-2 license termination. The Waltz Mill site was partitioned into three regions, each with different affected areas; three receptors were considered under two timelines:

immediate (1996) site release for industrial or residential use with no decay of source terms and after a 20-year decay period (2016) to allow for a reduction in source term concentrations.

2.2 DESCRIPTION

OF CONTAMINATED REGIONS Three major Waltz Mill site regions, as shown in Figure 2.1, have been identified based on their hydrological and geological configurations.

2.2.1 Region 1 Region 1 contains four areas:

• Area 1 includes the soils underneath the following facilities: The Truck Lock, the WTR Containment, and the G Building.

• Area 2 includes the soil regions north of the southern end of the G-Building.

• Area 3 contains all soils south of the southern side of the G-Building.

• Area 4 is a contaminated zone, three feet wide by 6" deep, below the process water line contained in Region 1.

This region includes those facilities associated with the Westinghouse Test Reactor (WTR) area and the A through F Buildings. Generally, this area is located on the western end of the site. The north-south run of the process water line has also been included in this region.

2.2.2 Region 2 Region 2 contains three areas:

• Area 1 includes all soils north of the process water line in the region.

• Area 2 is a contaminated zone, three feet wide by 6" deep, below the process water line contained in Region 2.

• Area 3 includes all soils south of the process watee line.

Wcitz Mill Dose Assessment .

Dose Conversion Factor Determination Section 2, Page 2 of 2.5 The second region's facilities include the Transfer Building, the R, S and T Buildirgs, l the GPL-1 Building, Former Waste Storage Pad and Ice Test Facility, and the Laundry i Facility imd Storage Building. This region generally lies in the central portion of the site.

2.2.3 Region 3 Region 3 contains six areas:

• Area 1 includes all soils north of the Evaporator Building and WTR Basin Number 3.

• Area 2 includes all soils beneath the WTR Basin Number 1.

• Area 3 includes all soils beneath WTR Basins Numbers 2 and 3.

. Area 4 includes the soils beneath the Evaporator Building and the 500,000 Gallon Above-Ground Storage Tank.

• Area 5 includes all soils south of the northern side of the Evaporator Building and WTR Basin Number 3.

. Area 6 includes the soils beccath the Liquid Waste Retention Basins (No/So) and three feet surrounding the basin footprint.

The third region's facilities generally include the Solid and Liquid Waste Processing Area, and is situated at the eastern side of the site.

2.2.4 Contamination Zone Factors j I'

Division of the site into regions and subsequent areas was dictated by the thickness and depth of the contamination zones and the hydraulic conductivities in each area. Table 2,1 provides these data and references. The contamination zone thicknesses were extracted from the data provided by Earth Sciences [5]. Figure 46 in the study by Earth Sciences [3] was used to dete mine the occurrence of groundwater in either bedrock or alluvium for each area.

2J DOSE ANALYSIS The identification of dose receptors was constrained by the potential future uses of the site.

Consideration was given to the most plausible receptors expected after release of the site license.

2.3.3 Receptors This study evaluates three dose receptors who currently appear to be appropriate bound-ing cases for future use of the site: (1) an industrial worker (who does not consume drinking water from the site), (2) a family-farm resident (who uses the property for I

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. Dose Conversion Factor Determination Section 2, Page 3 of 25 1

1 sustenance),' and (3) a squatter, who uses.the site after the loss of the institutional controls which had limited the site to industrial-only use.

2.3.2 Computer Model Development The RESRAD VERSION 5.0 [7] computer code was used to calculate annual dose rates per picocurie / gram due to radionuclihs present in soil. All input parameters and assumptions made regarding input parameters are addressed in Section 2.4. RESRAD results were manually transferred to Excel spreadsheets [8] for post-processing reorganization.

2.4 . DOSE PATHWAYS /MODELS

' Unique sets of pathways (scenarios) for radioactive material to reach the dose receptor for the family-farm and the industrial worker situations were developed. Figure 2.2 provides the general diagram for the potential pathways considered for each case. These three pathways are summarized as:

e the external radiation exposure pathway from penetrating radiation e the inhalation exporure pathway from inhalation of contaminated dust e the ingestion radiation exposure pathway from the consumption of plants, animal products, water and soil.

The ingestion pathway is further subdivided into water-dependent and water-independent pathways. Water-dependent pathways are those that receive the radioactive material via contaminated ground or surface water. Water-independent pathways receive the radioac-tive material directly from soil uptake.

l l 2.4.1 Industrial Scenario 1

The dose pathways modeling for this scenario is generally extracted from the U.S.

NRC's " Policy and Guidance Directive PG-8-08." The following model input parameters are taken from this directive:

• Residence time at the site - 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> / year.

• Time spent outdoors at site - 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> / year.

. No drinking water (well water) is consumed at the site by the industrial worker.

. The worker does not consume any produce from the site.

• Indoor and outdoc radon exposures are considered.

. Walls, floors and foundations of the buildings are assumed to reduce external exposure by 33%.

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Dose Conversion Factor Determination Section 2, Page 4 of 25 l

I e Indoor dust levels are assumed to be 50% of the dust level existing outside the buildings.

2.4.2- Family-Farm Scenario The family-farm resident scenario represents the maximum reasonably exposed dose receptor. The dose pathways modeling for this scenario is generally extracted from PG-8 08. The following model input parameters are taken from this directive:

i e Resident spends 55% of the time indoors on the site. j e Time spent outdoors at the site -21% of the year (5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> / day for 365 days). l

• Resident spends 24% of the time away from the site. {

e Gardening occurs in the contaminated area.

• A maximum of 50% of the resident's vegetable, grain and fruit diet is produced from the garden depending upon the size of the contaminated area considered in the calculation. This value may be less if the size considered is less than 1000 m 2, e All milk and 50% of the meat consumed are produced on the site.

• Dust levels in outdoor air in the vicinity of the garden are representative of moving earth due to gardening activities.

. All drinking water consumed at the site is produced by the on-site well, including water used by livestock.

. Indoor and outdoor radon exposures are considered.

. Soil ingestion is considered.

No ponds cr lakes (surface water) are located on the site. Therefore,100% of the fish and shellfish consumed are obtained off site; thus, Figure 2.2 does not consider aquatic foods. In addition, no inigation of crops is assumed. Both of these general inputs to the family-farm scenario are specific to Waltz Mill and have different values in PG-8-08.

2.4.3 Squatter Scenario The resident squatter scenario accounts for a loss ofinstitutional control. This potential case assumes the site's restricted release, but with property rights later being violated or compromised by an unplanned intruder taking up residency on the land or within remaining structures.

2J5 RESRAD INPUT PARAMETERS TLO'S preliminary calculations revealed that three RESRAD input parameters demonstrated the most significant impact upon resultant dose conversion factors. As such, the base case inputs for these parameters are specifically addressed herein. All other input parameters are subject to qualitative sensitivity analysis and are discussed in Section 2.5.4.

Wcitz Mill Dose Assessment -

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l 2.5.1 Contaminated Zone Area The resultant dose conversion factors calculated by RESRAD can be influenced by the total area of the contaminated zone since direct exposures are dependent upon the area of the source. However, once the source area exceeds several thousand square meters, ,

increases in size do not significantly impact ground exposures. l Other exposure pathways strongly influenced by contamination zone area are associated with root uptake by leafy vegetables. Contamination areas of less than 1000 m2 are influenced mostly by variations in this input parameter. RESRAD linearly interpolates garden size to its maximum value when the contaminated area reaches 1000 m2 . Areas less than 1000 m2 are assumed to produce less than the total quantity of garden vegetables required for consumption by a family. Table 2.1 provides the zone area sizes for each region of the site used in the base case calculations.

2.5.2 Contamination Zone Thickness A minimum contamination zone thickness of 0.15 meters was used in this dose assessment. Increases in the contaminated zone thickness will generally not impact direct doses from isotopes su h as "Co and "'Cs. However, increasing zone thickness increases the available source term for root uptake and groundwater pathways. Note that increasing contamination zone thickness beyond one meter does not continue to increase plant uptake - the root zone depth default is 0.9 meters. Table 2.2 provides the contaminated zone thickness for the base case calculations.

2.5.3 Distribution Coefficients Distribution coefficients (K,) in the RESRAD data libraries were globally used for all isotopes, with the exceptions as provided below. The choice of distribution coefficients j is complex, and, where Ko's have not been determined analytically, choosing reasonably '

conservative input values requires a knowledge of the impact of each radionuclide upon all potential pathways.

The following radioisotopes have been identified during the site characterization phase at the Waltz Mill site:

Strontium-90 Cesium-137 Cobalt-60 Americium-241 Uranium-234 Uranium-235 Uranium-238 Plutonium-239 Plutonium-240 Curium-243 Curimn-244 i

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Dose Conversion Factor Determination Section 2, Page 6 of 25.

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The strontium K,'s for this study were based on. data obtained experimentally.

e Assuming a very low K, would lead to underestimating root uptake. Assuming a very-high K, would-lead to underestimating the groundwater contamination. RESRAD calculations for the Waltz Mill site result in plant root uptake as' the dominant pathway for strontium as a function of time, using the supplied K,'s.

"'Cs and "Co are water-independent, extemal radiation dose contributors in the scenarios outlined for Waltz Mill. Their release criteria will be influenced minimally by changes in K,. The same is true for2 "U,2"Pu,2"Pu,2cCm and 2"Cm. These isotopes.

are water-independent, inhalation dose contributors - a variation in K, would have little impact upon the dose conversion factor results for these isotopes.

RESRAD calculations for Waltz Mill show that drinking water is the predominant pathway for2"Am, 2"U and 2"U. Dose calculations for these isotopes are highly sensitive to the values assumed for distribution coefficients. A low K, produces conservative results. However, the results can be so conservative that soil release criteria would be'establithed that cannot be measured. Choices of K, values for these isotopes are discussed in detail herein.

Distribution coefficients for radionuclides in unsaturated zones where RESRAD does not provide default values - RESRAD calculates a value for the. distribution coefficient of a radionuclide where one is unavailable in its internal data libraries.

RESRAD uses the algorithm of Sheppard and Thibault [9] and the assumption of a loamy soil type to generate K,'s for the following isotopes:

Neptunium-237*

Curium-243 Curium-244

• (Long-lived decay product of Americium-241)

Values generated by RESRAD.for these isotopes may be found in Table 2.3.

• Distribution coeficientsfor radionuclides in saturated zones occurring in bedrock material-In regions of the site where groundwater is not found until reaching the bedrock layer, the K, for all isotopes, with the exception of "Sr, are estimated as being the lower of either 10% of the value for sandy soils (as calculated by the method of Sheppard and Thibault), or the default value as given in RESRAD.

Values used for saturated zone bedrock K,'s may be found in Tables 2.3 and 2.4. A K, of_ l.45 was used for "Sr in areas where groundwater is first encountered in bedrock material [6].

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L Waltz MiB Dose Assessment l- Dose Conversion Factor Determination - Section 2, Page 7 of 25.

e . Distribution coeficientsfor radionuclides in all unsaturated zones - For strontium, Ko's were analytically determined from "Sr leaching tests using both deionized'and -

groundwater in the Solid and Liquid Waste Processing Area. This Kaiser study [10]

provides a tabulation of Ko's weighted by soil thickness and type. The weighted Ka was most conservative (K = 100) in the surface soils using deionized water. Thus this value was used for unsaturated zones in the Liquid and Solid Waste Processing Area. As soil types over the remainder of the site are similar, based upon drilling and sampling data, this value was also used for other unsaturated zones. Ka's for other radionuclides in all unsaturated zones may be found in Table 2.4. ' These values are either RESRAD default or calculated values. J e . Distribution coefficients for radionuclides in groundwater-bearing soils - The Kaiser study did not provide a weighted Ko for "Sr in groundwater saturated soils. j Although it has not been weighted, K, data were tabulated for various soil / isotope l concentrations in Table 1 of the study. TLG used the minimum (most conservative) value for intermediate stock solution concentrations of strontium in the test data, Ko ,

= 31. This value is consistent with the balance of the groundwater data presented in i the Kaiser study, as well as documented Ko's for strontium found in the RESRAD manual. Distribution coefficients for radionuclides in groundwater-saturated zones l used in this study may be found in Table 2.4. These values are either RESRAD l default or calculated values. 1 2.5.4 Other RESRAD Input Parameters Other RESRAD input parameters, subject to qualitative sensitivity analysis, used in this analysis, are provided here, in the order presented in PG-8-08.

• Dose Factor Library and Cut-ofHalf-Life - All calculations performed herein used the RESRAD default library. This library contains only nuclides with half lives greater than 180 days.

• Source - All isotopes identified in soils at the site were input at I pCi/g soil concentrations for the base case calculations.

. Calculation Times - RESRAD calculations were made for the period extending to 1000 years beyond release of the license. This timeframe ensures the capture of slowly migrating contaminants (particularly the uraniums) in the water pathways.

. Length Parallel to Aquifer Flow- The lengths of the contaminated regions parallel i to the aquifer flow are estimated from the Earth Sciences studies [4 and 5] and are given in Table 2.1.

{

_ _ _ _ = ___ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _

Wailtz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 8 of 25 e Cover Depth - Per the guidance of PG-8-08, the caedations did not take credit for cover material, e Density ofContaminated Zone -ICF Kaiser uses a soil density of 1.7 gm/cm'. This value was used in all calculations.

. Contaminated Zone Erosion Rate - Per PG-8-08, a value of 0.001 m/yr was used.

• Contaminated Zone Total Porosity- Per PG-8-08, a value of 0.3 was used.

• Contaminated Zone Effective Porosity - Per PG-8-08, a value of 0.2 was used for most calculations. However, in the Solid and Liquid Waste Processing Area contaminated region, a value of 0.24 was used as given in the Kaiser study.

• Contaminated Zone Hydraulic Conductivity - Calculations used the hydraulic conductivities for each arca as given in Table 2.2.

• Humidity in Air- Where this parameter is required, the RESRAD default value of 8 gm/m' was used.

. Contaminated Zone b Parameter - The RESRAD default value of 5.3 was used in all calculations.

• Evapotranspiration Coefficient - Per PG-8-08, a value of 0.5 was used.

. Precipitation - Precipitation at the site has been determined by ICF Kaiser. This value of 1.17 m/yr was used for all calculations.

Irrigation -Irrigation is not normally used during the growing season for crops in this region of the country. Therefore, the irrigation is set to 0 m/yr.

• 1rrigation Mode - n/a.

• Runog Coegicient - The value of 0.25 from the Kaiser study was used for all calculations.

• Watershed Areafor Nearby Stream or Pond - There is no nearby stream or pond suitable for fishing. Therefore, the basic watershed area of 10,000,000 m2 was used as input, since the item is required for RESRAD calculation sources.

Density ofSaturated Zone - ICF Kaiser uses a soil density of 1.7 gm/cm'. This value was used for all calculations where groundwater was found in the alluvium

Waltz Mill Dese Assessment Dose Conversion Factor Determination Section 2, Page 9 of 25 layer. Where groundwv.er was found in the bedrock,2.4 gm/cm' was assumed as the density.

• Saturated Zone Total Porosity- Per PG-8-08, a value of 0.3 was used.

• Saturated Zone Effective Porosity- Per PG-8-08, a value of 0.2 was used for most calculations. However, in the Solid and Liquid Waste Processing ' Area contaminated region, a value of 0.24 was used, as given in the Kaiser study.

• Saturated Zone Hydraulic Conductivity - Calculations used the hydraulic conductivities for each area as given in Table 2.2.

• Saturated Zone Hydraulic Gradient - Calculations used the hydraulic gradient for each area as given in Table 2.2.

• Saturated Zone b Parameter - The RESRAD default value of 5.3 was used in all calculations.

• Water Table Drop Rate - The calculations used the conservative water table drop rate of 0 meters /yr as given in PG-8-08. l e Well Pump Intake Depth - A review of the on-site remediation wells from the Kaiser study, and the volume of water they are capable of withdrawing, indicate that an average well pump intake depth of roughly 20 meters is required to draw satisfactory water volume to support a family-farm scenario.

. Modelfor Water Transport Parameters - The non-dispersion water transport model was used for all calculations.

l e Well Pumping Rate - The RESRAD default value is 250 cubic meters / year (approximately 180 gallons / day) and was assumed to be used for family drinking water. TLG has chosen to add a value of 100 cubic meters / year to account for milk _;

livestock water intake and other increased uses of water for a family farm. (Note: i There is no irrigation water to be used from the well, in contrast to the recommendation of PG-8-08).

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• Thickness of Unsaturated Zone - In problems where an unsaturated zone was assumed, the thickness of the zone is assumed to be a conservative 1 meter.

. - Density of Unsaturated Zone - ICF Kaiser uses a soil density of 1.7 gm/cm'. This value was used in all calculations.

Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 10 of 25 I

e UnsaturatedZone TotalPorosity- Per PG-8-08, a value of 0.3 was used.

e Unsaturated Zone Effective Porosity - Per PG-8-08, a value of 0.2 was used for b most calculations. However, in the Solid and Liquid Waste Processing Area contaminated region, a value of 0.24 was used as given in the Kaiser study.

• Unsaturated Zone Hydraulic Conductivity - Calculations will use the hydraulic gradient for each area as given in Table 2.2.

. Inhalation Rate - The default rate of 1.2 m'/hr (10512 m'/yr) was used per PG-8-08 for all calculations.

1 e Mass Loadingfor Inhalation -The default value of 0.0002 gm/m' was used per PG- '

8-08 for all calculations.

1 e Dilution Lengthfor Airborne Dust - The default value of 3 meters was used per PG- l 8-08 for all calculations. l e Exposure Duration - The RESRAD default value of 30 years was used for all calculations.

• Inhalation Shielding Factor - The default value of 0.5 was used per PG-8-08 for all calculations.

• External Gamma Shielding Factor - The default value of 0.33 was used per PG 08 for all calculations.

. Indoor Time Fraction - The indoor time fraction used for the industrial scenario is 0.18. The indoor time fraction used for the residential scenario is 0.55. Both indoor time fractions are per PG-8-08. j

< e Outdoor Time Fraction - The outdoor time fraction used for the industrial scenario is 0.05. The outdoor time fraction used for the residential scenario is 0.21. Both outdoor time fractions are per PG-8-08.

. Shape of the Contaminated Zone - The contaminated zone was assumed to be l circular in shape for all calculations of external exposure.

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• Fruit, Vegetable, and Grain Consumption - The default value of 166 kg/yr was used I

per PG-8-08 for all family-farm calculations.

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. Leafy Vegetable Consumption - The default value of 11 kg/yr was used per PG-8-08 for all family-farm calculations.

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.. Milk Consumption - The default value of 100 L/yr was used per PG-8-08 for all 1 family-farm calculations.

• Meat and Poultry Consumption - The RESRAD default value of 63 kg/yr was used for all family-farm calculations.

. Fish Consumption - This value was set to 0 for all calculations.

• Other Seafood Consumption - This value was set to 0 for all calculations.

. SoilIngestion - The default value of 18.25 gm/yr was used per PG-8-08 for all family-farm calculations.

. Drinking Water Intake - The family-farrn scenario uses the value of 730 L/yr per person, per PG-8-08.

• Contamination Fractions - All drinking water, household water and livestock water was assumed to come totally from the on-site well. All plant and milk food, as well as 50% of the meat was assumed to come from contaminated sources.

. Livestock Fodder Intakefor Meat - The default value of 68 kg/yr was used per PG-8-08 for all family-farm calculations.

. Livestock Fodder Intakefor Milk - The default value of 55 kg/yr was used per PG-8-08 for all family-farm calculations.

. Livestock Water Intakefor Milk- The default value of 50 L/d was used per PG-8-08 for all family-farm calculations.

. Livestock Water Intakefor Meat - The default value of 160 kg/yr was used per PG-8-08 for all family-farm calculations.

• Livestock Intake ofSoil- The RESRAD default value of 0.5 kg/d was used for all family-farm calculations.

• Mass Loadingfor Foliar Deposition - The default value of 0.0001 gm/m' was used per PG-8-08 for all family-farm calculations.

Weltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 12 of 25

. Depth ofSoilMixing Layer - The default value of 0.15 m was used per PG-8-08 for all family-farm calculations.

• Depth ofRoots - The default value of 0.9 m was used per PG-8-08 for all family-farm calculations.

. Radon Data - RESRAD default values were used for .dl radon data with the exceptions as given below:

Contaminated Radon Diffusion Coefficient - Vahtes of 2E-6 and 2E-4 m'Isec were used for the industrial and family-farm scenanc: respectively, as per PG-08-8.

Radon-222 and Radon-220 Emanation Coe))icient - A value of 0.35 was used for all radon emanation coefficients as designated by PG-08-8.

. Storage Times and Carbon-14 Data - RESRAD default values were used for all storage times and "C data.

2.6 BASE CASE RESULTS The Dose conversion factors of the base case calculations are presented in Tables 2.5-a and 2.5-b.

Dose conversion factors were calculated for each region and area of the site, for each of the three receptor scenarios, for each isotope, and for 1996 and 2016 isotopic decay (a total of 286 calculations).

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TABLE 2.1 ZONE AREA SIZES FOR BASE CASE CALCULATIONS Length Parallel to Region Area Size (m') Aquifer Flow (m) i 1 1 6096 104 2 41918 146  !

3 80343 287 {

d 692 757.

]

1 2 1 44398 216 2 254 278 3 43395 211 3 1 19435 122 2 2190 35 3 1973 55 j 4 339 31 1 5 29153 183 1 6 515 27 l l

l 1

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Weltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 14 of 25 TABLE 2.2 1

POTENTIALLY CONTAMINATED ZONE AREA:

CONTAMINATION AND HYDROGEOLOGICAL DATA Contamination Contamination Hydraulic Hydraulic Region Area Vertical Displacement Zone Thickness Gradient Conductivity 1 1 Directly on alluvium 1m 0.009 175 m/yr groundwater 2 Soil surface - 1 m 0.15 m 0.009 175 m/yr uncontaminated zone -

alluvium groundwater 3 Soil surface - 1 m 0.15 m 0.009 31.6 m/yr uncontaminated zone -

bedrock groundwater 4 36" wide zone directly 0.15 m 0.009 175 m/yr on alluvium groundwater o

2 1 Soil surface - 1 m 0.15 m 0.101 175 m/yr uncontaminated zone -

alluvium groundwater 2 36' wide zone directly 0.15 m 0.029 175 m/yr on alluvium groundwater 3 Soil surface - 1 rn 0.3 m 0.029 31.6 m/yr uncontaminated zone -

bedrock groundwater 3 1 Soil surface - 1 m 0.15 m 0.101 31.6 m/yr uncontaminated zone -

bedrock groundwater 2 Directly on bedrock 0.3 m 0.101 31.6 m/yr groundwater 3 Directly on bedrock 0.3 m 0.021 31.6 m/yr groundwater 4 Directly on bedrock 0.3 m 0.021 31.6 m/yr groundwater 5 Soil surface - 1 m 0.15 m 0.021 31.6 m/yr uncontaminated zone -

bedrock groundwater 6 Directly on bedrock 1.0 m 0.021 31.6 m/yr groundwater Note: Ilydraulic Gradient and Conductivity extracted from Reference 10.

Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 15 of 25 TABLE 23 l RESRAD DEFAULT VALUES l (liters /g) l RESRAD Default Sandy Nuclide K, Loamy soil Soil Bedrock Sr 30 53 15 1.45 Cs 1000 144 41 4.1 Co 1000 102 29 2.9 Am 20 910 261 20 Np 204 (Calculated) 204 58 5.8 Th 60000 910 261 26.1 Pb 100 288 82 8.2 Ra 70 144 41 4.1 Pa 50 288 82 8.2 l

Ac 20 576 165 16.5 U 50 576 165 16.5 Pu 2000 910 261 26.1 Cm 910 (Calculated) 910 261 26.1 N:te: The bedrock K, for strontium is taken from a site-specific study.[10] The bedrock K, for americium is the default value for Ko used by RESRAD, which is lower than the assumed 10% of sandy soit value, as calculated by Sheppard and Thibault.

TABLE 2.4 DISTRIBUTION COEFFICIENTS (liters /g)

Unsaturated and Saturated Saturated Nuclide Contaminated Zones Alluvium Bedrock Sr 100 31 1.45 Cs 1000 1000 4.1 Co 1000 1000 2.9 Am 20 20 20 Np 204 (Calculated) 204 5.8 Th 60000 60000 26.1 Pb 100 100 8.2 l Ra 70 70 4.1 Pa 50 50 8.2 Ac 20 20 16.5 U l 50 50 16.5 Pu 2000 2000 26.1 Cm 910 (Calculated) 910 26.1 l

Writz Mill Dose Assessmrt Dose Conversion Factor Determination Section 2, Page 16 of 25 1

TABLE 2.5-a i

l l

[ SOIL DOSE ASSESSMENT DOSE CONVERSION FACTORS - 1996 1 l

l l

\

Residensal industrial l Scenario Residenual Scenario MPer Scenario Nper Reeen pCup k son uman) yrs pCWs M son Reamn 1 Aree1 Br-90 4 719E+00 3 063E43 j Co-137 1.538E +00 3 450E41 )

Co40 6.180E+00 1649E+00  !

Am441 6382E*00 155 1304E41 0-234 2.670E41 512 3 746E42 U-235 1087E+00 1000 1130E41 U-238 2 550E41 184 4144E42 Pw239 7 897E41 1216E41 Pu 240 7897E41 1.216E41 Cm443 7 755E41 1472E41 Cm-244 4 518E41 7.031E42 i

Roomn 1 Area 2 }

St 90 1088E +00 2.957E43 C&137 1.380E +00 3 368E41 Co40 5545E+00 1.526E+W Am-241 1.153E +00 98 1.335E41 U-234 1.595E41 3 833E42 U-235 4 325E41 1150E41 U438 1924E41 4 772E42 Pw239 5 463E41 1245E41 Pu-240 5 462E41 1.245E41 Cm-243 6 018E41 1500E41 Cm-244 3 097E.01 7195E42 e Reamn 1 Aree 3

$r40 1088E+00 2 958E43 C&137 1.367E+00 3.388E41 Co40 5 575E+00 1.534E +00 Am 241 8.168E41 96 1341E41 U434 1800E41 3 849E42 U435 4 351E41 1157E41 0 238 1.932E41 4 800E42 Pu 239 5 480E41 1.250E41 Pw240 5 479E41 1.250E41 Cm443 6 046E41 1508E41 Cm-244 3107E41 7=224E42 Rmpon 1 Are.4 St 90 4 938E41 2 912E43 Co-137 1.157E*00 - 3164E41 Co40 5.127E+00 1426E+00 Am-241 4 956E41 1217E41 4234 1314E41 3 492E 02 S 235 3 923E41 1019E41 U-238 1643E41 4388642 j Pw239 4 640E41 1134E41 Pw240 4 645E41 1134E41 Cm 243 5 391E41 1391641 Cm444 2 678E41 6 654E 02

I Wcitz Mill Dose Assessment-Dose Conversion Factor Determination Section 2,Page 17 of 25 -

l TABLE 2+5-a l

(continued)

Roswan.e. -

Scenerlo heeWen.al Scenado m4entrper Scenado mNamtrper Reason pCar a eos wress)m pCss m aos

,R_egLon 2 kos 1 Sr40 1088E *00 2.957E43 Cs-137 1.361E+00 3.369E41 =

Co40 8547E+00 1.526E+00 l M 241 1153E+00 96 1.336E41 U-234 1.595E41 3 835E42 4235 4 328E41 1.150E41 4 238 1924E41 4 779E42 Pw239 5 464E41 1.245E41 Pw240 5.464E41 1245E41 Cm 243 6 020E41 1.501E41 Cm444 3 098E41 7.196E42 Ream 2 kree 2 Sr-90 1876E41 2 854E 03 Cs-137 1073E+00 2 973E41 Co40 4 811E+00 1342E+00 Am441 4 231E41 1.142E-01 0234 1.173E41 3.274E42 0-235 3 658E 01 1.022E41 U438 1479E41 4124E42 Pw239 3 946E41 1.063E41 Pw240 3 495E41 1063E41 f Cm-243 4 792E41 1312E41 Cm444 2.278E41 6145E42 Ream 2 Aree 3 Sr 90 2.110E+00 3 066E43 Co-137 153tE+00 3 802E41 Co40 6.223E +00 1697E*00 Am441 1539E *00 124 1.335E41 U-234 1.735E41 1000 3 834E42 .

U-235 4 491E41 1167E 01 l U438 2 063E41 4 872E42 Pw239 5 988E41 1245E41 Pw240 5 988E41 1.245E41 Cm443 8 440E41 1515E41 Cm-244 3 396E41 7.197E42 Ream 3 Area 1 Gr-90 1077E+00 2 954E43 Co 137 1351E+00 3 351E41 Co40 5 518E*00 1.519E+00 '

Am441 8187E41 96 1.326E41 0434 1562E41 3 806E42 U-235 4 297E41 1.143E41 U438 1910E41 4 747E42 Pw239 5 430E41 1236E41 Pw240 5 430E41 1236EC1 Cm443 5 963E41 1.490E41 Cm444 3 000E41 7.147E42 1

Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 18 of 25 TABLE 2.5-a (continued)

Scenerlo ReeseeneW Scenerte Mper Scenerto M er Resen pcMym esa geen) yrs ocas meen Reaion 3 Area 2 St-00 1447E+00 3 045E43 Co-137 1.311E*00 3 442E41 Co40 5 879E+00 1.622E+00 Am 241 1.698E+00 64 1.273E41 .j U-234 1707E41 73 3 655E42 6 U-235 - 4 220E41 1.121E41 -l U-238 1878E41 4 652E42 6 239 5 691E41 32 1.187E41 N 240 5 681E41 11 1.187E41 1 C O243 6196E41 1450E41 Cm-244 3.265E41 6 861E42

{

(

Reaen 3 Atee 3 Sr-90 1.436E+00 3 043E43 C&137 1.305E+00 3 431E41 Co40 5 659E+00 1.617E+00 Am-241 1.690E+00 64 1.267E41 U-234 1.704E41 74 3.637E42 U-235 4 206E41 1.117E41 U-238 1869E41 4 632E42 N 239 5 86sE41 32 1.181E41 N 240 5 659E41 11 1.181E41 Cm-243 6177E41 1.445E41 Cm-244 3.253E41 6 828E42 Room 3 Neg.,4 St-90 4 826E41 2 981E43 l Cs-137 1179E+00 3.228E41 Co40 5 455E+00 1.518E+00 Am-241 7.202E41 52 1.166E41 U-234 1.246E 01 3 345E42  ;

4235 3 819E41 1.054E41 U 238 1584E41 4 292E42 N 239 4 291E41 1086E41 Pu-240 4 291E41 1.00cE41

~

Cm-243 5112E41 1.349E41 Cm-244 2 475E41 6.278E42 Rooen3 nom Sr-90 1088E+00 2.956E43 Cs-137 1357E+00 3 359E41 I Co40 S.532E+00 1522E+00 ,.

Am441 8.188E41 96 1.331E41 G234 1.591E41 3 822E42 U-235 4 313E41 1.146E41 4 238 1919E41 4.763E42 N 239 5 450E41 1.241E41 N 240 5 450E41 1.241E41 C n243 6 002E41 1.496E41 1 Cm 244 3.000E41 7.175E42 ,

I i

i

...s' '

Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 19 of 25 TABLE 2.5-a (continued)

Meekseneel indusertal Scenarie Meeksential Scenato Mper Sc norso Mper Reelon pC4 h so# t(mar) yrs pCe h so#

Ramon 3 Area 6 St90 2157E+00 3.016E 03 Cs-137 1266E*00 3252E41 Co40 5664E+00 1.554E+00 Am-241 3 297E+00 152 1.190E41 U 234 4 C61E41 714 3 436E42 U-235 8 081E41 579 1070E41 U 238 3.700E41 626 4 390E42 Pu-239 6 404E41 450 1.116E41 Pu 240 6 404E41 458 1.115E41 Cm-243 61G1E41 1.376E41 Cm-244 3 304E41 6 449E42 I

Waltz Mill Dose Assessmect Dose Conversion Factor Determination Section 2, Page 20 of 25 l

TABLE 2.5-b i

SOIL DOSE ASSESSMENT DOSE CONVERSION FACTORS - 2016 i

l

! Roemeal Industrial scenario Ree64enual scenario Mper Scenario sdeneWper medon pC4 m so# Wmax) yrs pCMrin se#

Rooo11 kos1 Sr 90 2 793E+00 1807E43 l

Cs 137 9 636E41 2.162E41 j 1183E41 l Co40 4 417E41 Am 241 6.382E +00 155 9 773E42 U-234 2 670E41 512 3.382E42 U-235 1.0e7E +00 1000 1.023E41 U-238 2.550E41 184 4.279E42 Pw239 7 875E41 1.212E41 Pw240 7 862E41 1.210E41 Cm-243 4 750E 01 9 003E42 Cm-244 2.104E41 3 2'70E42 R , he. 2

) $r-90 4159E41 1255E43 Cs 137 7 909E41 1982E41 Co40 3 689E41 1017E41 Am-241 1153E+00 96 2 036E42 U-234 6.961E42 1674E42 U-235 2.067E41 5 500E 02 U-238 8 637E42 2.153E42 Pw239 4 651E41 1060E41 Pw240 4 643E41 1058E41 .

Cm-243 3 241E41 8123E42 l Cm 244 1209E41 2 009EC Reca i ked Sr 90 4.159E41 1255E43 Cs-137 7 950E41 1993E41 Co40 3 710E41 1022E41 Am 241 8188E41 96 2 470E42 U-234 6 386E42 1681E42 U-235 2 079E41 5 534E42 U-238 8 675E42 2163E42 Pu 239 4 866E41 1064E41 j Pw240 4 658E41 1062E41 l Cm-243 3 256E41 8.165E42 Cm-244 1.213E41 2 820E42 Room i koa 4 Sr-90 1.895E41 1237E43 Cs-137 6 740E41 1646E41 Co40 3.364E41 9 416E42 Am-241 1676E41 1856E@

U 234 5 916E42 1525E42 U-235 1.887E41 5142E42 U-238 7 F13E42 1974E42 Pw239 3 956E41 9653E G Pw240 3 949E41 9 637E 02 Cm443 2.903E41 7 518E42 Cm-244 1.046E41 2 55eE42

Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 21 of 25 TABLE 2.5-b (continued)

Res&dentled Industrial Scenerto Ree6dentled Scenarlo mR*mtr Per Swa mRostrper stagion pC4 m se# q(men) yee pC4m so#

. Reaon 2 Ares 1 St90 4.159E41 1.255E43 Co-137 7.912E41 1982E41 Co40 3 891E41 1017E41 Am-241 1.1536 00 96 2 037E42 U 234 6 963E42 1875E42 U 235 2 068E41 6.503E42 U 238 8 640E 42 2153E42 Pw239 4 652E41 1060E41 Pw240 4 645E41 1058E41 Cm 243 3 242E41 8127E42 Cm-244 1209E41 2.810E42 Regen 2 Aree)

$r40 7.388E42 1213E 03 Co 137 6 210E41 1722E-01 Co80 3147E41 8 780E42 Am 241 3 600E41 1742E42 U 234 5 693E42 1429E42 U-235 1792E41 4 848E-02 U-238 7.164E42 1851E42 Pw239 3 360E41 9 050E42 Pw240 3.354E41 9.035E42 Cm-243 2 583E41 7 073E42 Cm-244 8 900E 02 2 398E 02 Reacn 2 Aree 3 St 90 1033E@ 1603E43 Co-137 9 397E41 2 228E41 Cc 80 4 386E41 1198E41 Am-241 1539E*00 124 5 501E42 U 234 1735E41 1000 2.723E42 U-235 3 203E41 8 308E42 0 238 1453E41 3 457E42 Pw239 5 864E41 1.234E41 Pw240 5 855E41 1232E41 Cm-243 3 859E41 9145E42 Cm-244 1540E41 3 303E42 Reason 3 Area 1 Sr 90 4116E41 1254E43 Cs-137 7 856E41 1972E41 Co40 3 671E41 1012E41 Am 241 8187E41 96 2 025E42 Lk234 6 808E42 1663E42 U 235 2 OSSE 41 5 469E42 0 238 8 577E42 2139E42 Pw239 4 623E41 1053E41 Pw240 4 616E41 1051E41 Cm-243 3 223E41 8.072E 02 Cm-244 1202E41 2 790E42

'I

-EJ Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 22 of 25 TABLE 2.5-b (continued)

Scenslo Resident 6el Scansio mAssWrper Scenerlo mRentraer Region pCMr h so# t(mos) yes pCair h se#

M 3 kee 2 6 3 St-90 8.156E41 1.592E43 Cs 137 8100E 01 2.132E41 Co.40 4152E41 1.146E41 Am 241 1.600E+00 64 8.243E42 U-234 1.707E41 73 2 596E42 ,

U435 4 220E41 7 984E42 U-238 1853E41 3.300E42 6 239 5 691E41 32 1.176E41 N 240 5 601E41 11 1.174E41 cm443 3 837E41 8.759E42 Cm444 1.556E41 3149E42 Reson 3 keej Sr-90 8 096E41 1 (10E43 Cs 137 8 067E41 2.125E41 Co40 4138E41 1143E41 Am441 1.698E+00 64 5.218E42 U-234 1.704E41 74 2 583E42 U-235 3 546E41 7 960E42 0 238 1847E 01 3.286h42 6 239 5.669E41 32 1.170E41 h 240 5 659E41 11 1.168E41 Cm443 3 825E41 8 726E 02 Cm-244 1551E41 3133E42 9

Recon 3 kes 4 St-90 2 006E41 1558E43 Cs-137 7.290E 01 1990E41 Co40 3 850E41 1.071E41 Am-241 7.202E41 52 4 805E42

! U434 1112E41 2.375E 02 U 235 2 946E 01 7.505E42 U 238 1.340E41 3 044', 02 6 239 4 282E41 1.076E41 h 240 4 275E41 1074E41 Cm-243 3128E41 8145E42 d

Cm-244 1.161E41 2 881E42 Rooen 3 koa 5 Br-90 4.159E 41 1254E43 Ca 137 7.891E41 1997E41 Co40 3 600E41 1014E41 Am441 8188E41 96 2.033E42 U 234 6.946E42 1669E42 U435 2.062E41 5 485E42 U-238 8 018E42 2147E42 4 239 4 640E41 1057E41 Pv440 4 633E41 1.055E41 Cm443 3 232E41 8100E42 Cm444 1206E41 2 000E42 J

l

Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 23 of 25 l

l TABLE 2.5-b (continued) l Reeldenhal induettal 8senado Roehlentlaf Scenado mAenWrper Scenario mAssWrper Region pC@ M eo# ilman) yre pC@ h so#

Reacn 3 Area 6 Sr40 1.357E+00 1700E43 Cs 137 7.943E41 2.030E41 C&60 4 062E41 1.114E41 Am-241 3.297E+00 - 152 8.975E-02 S234 4 00tE41 714 3.103E42 U-235 8 081E41 670 9.6818 42 U 238 3700E41 626 3 961E42 Pw239 6 404E41 458 1.112E41 Pu-240 6 40dE41 458 1110E41 Cm 243 3 862E41 8 415E42 j Cm-244 1593E41 2.999E42 '

t i

l i

l

)

4

Wcitz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 24 of 25 l

1 l i FIGURE 2.1 I WALTZ MILL SITE LAYOUT RESRAD ANALYSIS REGIONS AND AREAS i l

l l

i l

1 1

as .

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u . - 4 m ; #x = = c-' =r@d , - _

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Waltz Mill Dose Assessment Dose Conversion Factor Determination Section 2, Page 25 of 25

'l FIGURE 2.2

GENERIC SCENARIO PATHWAYS l

Source Environmental Pathway Exposure Pathway Dose Direct Exposure l Ground l External

1. : Radiation

• l Dust l On-Site Dust Radon Inhalation -+

Air Contamination Radon a

Effective Dose Plant Foods l Plants l I Residual  :  : Equivalent to

• an Exposed

' Radioactive Mcterialin Soil " Individual l Meat l -

Livestock Meat l Milk Milk  :

Aquatic Foods. l Fish l Ingestion On-site Biotic Contamination .--

On-site Water Contamination aterl

Direct ingestion ISOIII ,

• Waltz Mill pathways analysis does not consider aquatic foods.

Waltz MODese Assessment -

Dese Conversion Factor Determination Section 3, Page 1 of1

3. REFERENCES

1. Policy and Guidance Directive PG-8 Scenariosfor Assessing Potential Doses Associated with ResidualRadioactivity, Division of Waste Management - Office ofNuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, May 1994.

2. ResidualRadioactive Contaminatiwifrom Decommissioning, NUREGICR-5512, U.S. Nuclear Regulatory Commission, October 1992.

3. Soil and Groundwater Characterization - Walt: Mill Site -Madison, Pennsyhania, Earth Sciences Consultants,Inc., August 1994.

t

4. Additional Site Characterization - Waltz Mill Site - Madison, Pennsylvania, Earth Sciences Consultants,Inc., August 1995.

5. Revised Volume Estimate - Soils Containing Radioactive Material above Project-Specified Limits - Westinghouse Electric Corporation Walt: Mill Site -Madison, Pennsylvania, Draft, l

Earth Sciences Consultants, Inc., June 21,1995.

6. GroundwaterModelingfor RadiologicalDose Assessment- Walt:MillFacility-Madison, Pennsylvania, ICF Kaiser Engineers, Inc., March 18,1996.

7. RESRAD-BUILD: A Computer Model for Analyzing The Radiological Doses Resulting from The Remediation and Occupancy of Buildings Contaminated with Radioactive Material, ANUEAD/LD-3, Argonne National Laboratory, November 1994.

8. Microsoft Ercel, Version 5.0a, Microsoft Corporation,1994.

9. Sheppard, M.I., and Thibault, D.H.,1990, " Default Soll Solid /LiquidPartition Coefficients, Ka's,for FourMajor Soil Types: A Compendium," Health Pbysics 59:653-657.

10. Bench Scale Stu& and Leaching Evaluation - Waltz Mill Site -Madison, Pennsyhania, ICE Kaiser Environment and Energy Group, October 27,1995.

l l

Waltz M:] Dose Assessment Dose Convenion Factor Determination Appendix A, Page 1 of 2 APPENDIX A

! GLOSSARY

Committed Effective Dose Eauivalents (CEDE): The dose from residual activity at a site that is distinguishable from background that a member of the public is likely to receive from ingestion and inhalation from environmental transport pathways.

Coa +aminatad Zone Area: The defined area of radioactive contamination utilized by RESRAD to calculate resultant doses.

Contaminated Zone Thickness: The thickness of the radioactive contamination source term in soil, over a defined area, used by RESRAD to evaluate pathway radiation doses.

Decommissioninn (10 CFR 20.1003h A means to remove a facility or site safely from service and reduce residual radioactivity to a level that permits: 1) release of the property for unrestricted use and termination of the license, or 2) release of the property under restricted conditions and termination of the license Distribution Coefficients (Kd: The ratio of the radionuclide concentration in soil to the radionuclide concentration in the surrounding ground porewater.

Dose Pathway: Environmental transport mechanisms by which material may reach the critical individual (receptor) in either the family farm or the industrial worker scenario, contributing to radiation exposure.

Dose Receptor: Person (s) receiving radiation exposure, after release for unrestricted or restricted use  !

of the site, from one or more of the source terms of radioactive material identified on the site.  !

l Familv-Farm: As defined by the US NRC's PG-8-08, this receptor utilizes the site as a full-time I residence after license termination. The family farmer utilizes the land to earn a sustenance living after all stmetures have been demolished and the resultant rubble buried on site. The farmer spends 55% of l his time indoors,21% outdoors, and 24% away from the site. Produce and livestock are raised in all '

areas, including contaminated soil areas. Half of all meat and 100% of all milk consumed are produced on the site. Vegetables, fruits and grains are irrigated with site well water; drinking water for humans and livestock also comes from the site well system.

Industrial Worker: As defined by the US NRC's PG-8-08, this receptor is employed at the site after hcense termination to perform assigned labor. The worker spends 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> per year at the site of which 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> per year are spent outdoors. The worker consumes no drinking water from site wells and eats no produce grown on the site.

Remediation: Removal (demolition) of the structure (with disposal by burial of the building material on tits). A Remediation Worker is a short-term worker used to clear the site of structures in preparation

Waltz MS Dose Assessment Dose Conversion Factor Determination Appendix A, Page 2 of 2

for unrestricted re-use of the site. Time to complete reuedial actions is based on a facility's volume unng R.S. Means Constmetion Cost Estimating Guidelines,19% Ed.

Renovation ' Minor changes to interior surfaces, such as painting, wallpapering, resurfacing, etc. A l Renovation Worker is a short-term worker used to prepare the site's structures for industrial use after license termination. Time to complete renovations was based on a facilicy's surface area using R.S.

Means Constmetion Cost Estimating Guidelines,1996 Ed.

RESRAD: Version 5.0 is a computer code developed by the Argonne National Laboratory to perform dose rate calculations due to radionuclides present in soil via a pathways analysis. RESRAD calculates direct, inhalation and ingestion doses for a hypothetical receptor and source term. ,

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RESRAD-BUILD. A computer code similar to RESRAD, except dose rate calculations are performed j for radiologically-contaminated site structures.

RESRAD Default Values: Values contained in the internal data bases of the RESRAD and RESRAD- )

BUILD computer codes. 4 l' Saturated Zones: The soil or bedrock region below the water table in a RESRAD calculation. i Squatter: A receptor who resides in the buildings 4andoned in place on the site after license termination. Site structures are left standing and may be used as a residence by the receptor. The land is farmed by the receptor to provide a sustenance living. All produce generated on the site is consumed by the receptor, as well as water from the well system.

Total Effective Dose Equivalent (TEDEh The highest dose from residual activity at a site that is distinguishable from background that a member of the public is likely to receive from all environmental transport pathways. The current NRC limit for release of a site is 15 mrem /y. TEDE (ref: NRC DG-8017).

Unsaturated Zones: The soil region above the water table in a RESRAD calculation.

1 Water-Decendent Pathway: A water-borne environmental transport path through which the receptor ingests radioactive material. This includes drinking water and irrigation water (plant food, livestock consumption, milk consumption, aquatic food consumption).

Water-Indeoendent Pathwav: An environmental transport path not directly or indirectly tied to the movement of ground or surface water on the site. Direct exposure, inhalation and ingestion of soil are ,

the primary water-independent pathways. I q

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