ALARA%20and%20Radioactive%20Effluents%20Regulatory%20History%20and%20Application%20for%20Next%20Generation%20Power%20Reactor%20Licensing

1
ALARA and Radioactive EffluentsRegulatory
History and Application for Next Generation Power
Reactor Licensing

• June 27, 2006
• 2006 RETS/REMP Workshop
• Presented by
• J. Stewart Bland, CHP
• Chesapeake Nuclear Services, Inc.
• Annapolis, MD
• 410-266-9174
• jsbland_at_chesnuc.com www.chesnuc.com

2
Objectives/Agenda

• Provide the history on the development
  (rulemaking) for 10 CFR 50, Appendix I
• Describe the current regulatory requirements for
  radioactive effluents (e.g., the public exposure
  limits in 10 CFR 20 and
• 10 CFR 50, App I, and Regulatory Guide 1.109)
• Examine the concept of design basis for
  radioactive processing systems (10 CFR 50.34a)
  with implementation requirements (10 CFR 50.36a).
• Briefly describe regulatory approach and status
  of new plant licensing.
• Examine effect of implementing updated regulatory
  approaches and dosimetric modeling (ICRP 30 and
  ICRP 60/72) on Appendix I rule and plant
  implementation.
• Provide an overview of the NRCDose computer code
  (as time permits).

3
ALARA Rulemaking

• ALARA concept originally promulgated December 3,
  1970
• Rulemaking over next 4½ years, involving industry
  participation, hearings, NRC staff proposed
  rules.
• Final rule issued May 5, 1975.
• Rule required each light-water-cooled nuclear
  power plant to submit information necessary for
  evaluating compliance with rule by June 4, 1976.

4
10 CFR 50.34a Requirements

• Provides for the design basis for the plant.
• Description of design and equipment to be
  installed and used for the control of radioactive
  effluents, i.e., maintaining releases ALARA,
  including anticipated operational occurrences.
• Estimate of quantities of radioactive materials
  to be released annually.
• This design basis and ALARA demonstration is part
  of FSAR/USAR Licensing basis for the plant.

5
10 CFR 50, Appendix A General Design Criteria

• GDC 60, Control of Releases of Radioactive
  Materials to the Environment
• ... design shall include means to control
  suitable the release of radioactive materials in
  gaseous and liquid effluents and to handle solid
  radioactive waste produced during normal reactor
  operation, including anticipated operational
  occurrences. Sufficient holdup capacity shall be
  provided ...
• GDC 64, Monitoring Radioactivity Releases
• Means shall be provided for monitoring the
  reactor containment atmosphere, ..., effluent
  discharge paths, and the plant environs for
  radioactivity that may be released from normal
  operations, including anticipated operational
  occurrences, and from postulated accidents.
• USAR design must address these design criteria.

6
10 CFR 20 Requirements Applicable to Effluents

• 10 CFR 20.1301 with reference to 40 CFR 190
• Dose limit of 1 mSv (100 mrem) in a year,
  excluding background, medical, disposal in
  sewerage.
• Dose in any unrestricted area from external
  sources shall not exceed 0.02 mSv/h (2 mrem/h).
• If licensee permits members of public access to
  Controlled Areas, the 1 mSv limit continues to
  apply.
• Licensees subjected to provisions of EPAs 40 CFR
  190 environmental dose standard. HPPOS-008
  provides implementation guidance stating
• RETS/ODCM methods acceptable for demonstrating
  compliance
• Assessment and reporting requirements included in
  Admin Section of TS
• 10 CFR 20.1302 Compliance Methods
• Licensee shall make appropriate surveys of
  radiation levels and radioactive material in
  effluents.
• Annual average concentration of radioactive
  material released in effluents at the boundary of
  the unrestricted area does not exceed the values
  in Appendix B, Table 2 (EC values)
• 0.5 mSv/y (50 mrem/y) from continuous exposure
  stochastic values only)
• 10 CFR 20.1101 Exempts NPP licensees from the
  CAA 10 mrem/y constraint.
• 10 CFR 20.2203 30 day reporting if levels of
  radiation levels or releases of radioactive
  materials exceed 40 CFR 190.

7
10 CFR 50.36a Requirements

• Requires Technical Specifications for ensuring
  releases are maintained ALARA
• Explicit Requirements
• Releases shall comply with 10 CFR 20.1301
  (formerly 20.106)
• Procedures shall be established and followed for
  operating radwaste treatment systems
• Radwaste systems shall be maintained and used
• Annual release reports shall be prepared and
  submitted to NRC.
• Guidance Requirements
• Releases, on average, should be small fraction of
  10 CFR 20.1301 limit
• Best effort shall be exerted to keep releases
  ALARA
• Appendix I provides numerical guidance on
  limiting conditions for operation for effluents

8
Appendix I Requirements

• Four design objectives - numerical dose values
• Liquid effluents (per unit)
• 3 mrem/yr, total body
• 10 mrem/yr, any organ
• Gaseous effluents (per unit)
• 10 mrad/yr, gamma air
• 20 mrad/yr, beta air
• 5 mrem/yr, total body (any real person)
• 15 mrem/yr, skin (any real person)
• Airborne iodines and particulates (gt 8 day T½ ,
  per unit)
• 15 mrem/yr, critical organ (real pathway)
• Doses (effluents) shall be further reduced as
  much as practical up to the expenditure of 1,000
  per person-rem saved

9
Appendix I Limiting Conditions for Operation

• If releases during any calendar quarter exceed
  half the annual design objectives, licensee shall
  evaluate, correct, and report to NRC in 30 days.
• Surveillance program shall be established to
  monitor releases, monitor the environment and
  identify changes in land use.

10
RM-50-2Annex to Appendix I

• Provides an alternative to Appendix I
  cost-benefit evaluation, based on licensees (and
  NRCs) previous demonstrations with previous,
  interim requirements.
• Saved time and efforts based on licensees and
  NRC staffs previous reviews performed during the
  rulemaking process.
• Applicable only for plants docketed after January
  2, 1971 and prior to June 4, 1976
• For Pre-1971 Plants
• NRC performed study (NUREG-0389) documenting
  cost-benefit evaluation for those plants not
  covered by RM 50-2 alternative.

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NRCs Implementation Guidance

• Regulatory Guide 1.109, Calculation of Annual
  Doses to Man from Routine Releases of Reactor
  Effluents for the Purpose of Evaluating
  Compliance with 10 CFR Part 50, Appendix I,
  (Rev.1) October 1977
• Regulatory Guide 1.110, Cost-Benefit Analysis
  for Radwaste Systems for Light-Water-Cooled
  Nuclear Power Reactors, March 1976
• Regulatory Guide 1.111, Methods for Estimating
  Atmospheric Transport and Dispersion of Gaseous
  Effluents in Routine Releases from
  Light-Water-Cooled Reactors, (Rev. 1) July 1977
• Regulatory Guide 1.112, Calculation of Releases
  of Radioactive Materials in Gaseous and Liquid
  Effluents from Light-Water-Cooled Power
  Reactors, April 1976
• Regulatory Guide 1.113, Estimating Aquatic
  Dispersion of Effluents from Accidental and
  Routine Reactor Releases for the Purpose of
  Implementing Appendix I, (Rev. 1) April 1977

12
Implementation Schedule and Issues

• 10 CFR 50.34a and 50.36a promulgated in December
  1970.
• Appendix I rule finalized and issued May 5, 1975.
• Required Licensees to submit information for
  evaluating compliance by June 4, 1976.
• First version of RETS issued 1978. Atomic
  Industrial Forum established Task Force to
  industry interface and negotiation with NRC on
  implementation. (See AIF letter dated 12/24/81
  NRC Industry Interface tab).
• Revised RETS issued 1979, included NUREG-0133
  (ODCM) approach. (See Charlie Willis and Frank
  Congel presentation NRC Industry Interface
  tab).
• TMI happens major delays in implementation of
  RETS at operating plants.
• RETS finally issued at all operating plants
  around 1984.

13
Industry/NRC Interface for Implementation

• Atomic Industrial Forum Task Force established to
  negotiate with NRC initial implementation RETS
  development.
• Reliance on current design as acceptable basis
  for most monitors and controls.
• Eliminated requirement for P-32 sampling and
  analysis for liquid effluents.
• Annual average met versus real-time relaxation
  of requirement to use short-term met for purges.
  
• Accepted current basis for monitor calibrations
• Use of pump curves in lieu of flow rate monitors
• Relaxed approach to TB sump monitors, composite
  samplers, tank recirc.
• (Refer to NRC/Industry Implementation section)

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NRCs RETS and ODCM Guidance

• NRCs Initial Standard Radiological Effluent
  Technical Specifications (NUREG - 0472 and -
  0473)
• NUREG-0133, Preparation of Radiological Effluent
  Technical Specifications for Nuclear Power
  Plants, October 1978
• keep details out of TS
• presented methods acceptable to NRC
• can be changed without NRC licensing action
• subjected to after-the-fact NRC review (and
  passive approval)
• alarm setpoint methodology
• simplified dose calculations
• guidance for other issues (atmospheric steam
  relief valves, outside tanks, etc.)

15
NRCs RETS and ODCM Guidance (cont)

• NRC Radiological Assessment Branch Technical
  Position, Radiological Environmental
  Monitoring, (Rev. 1) November 1979 (see
  NRC/Industry Implementation tab)
• Types and locations for environmental monitoring
• QA program interlaboratory sample splitting
  program
• Land-Use Census
• Reporting format
• NRCs Technical Specification Improvement Effort
• NRC Generic Letter 89-01
• Encouraged licensees to revise to new format.
• Many advantages with most requirements relocated
  to ODCM.
• Licensee able to revise without NRC approval.
• NUREG - 1301 and - 1302
• NRCs guidance on revised RETS/ODCM format.
• Addresses 10 CFR 20 revision.
• Supports current STS approach.

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RETS Not Directly Required by Appendix I

• Safety Related Requirements
• Control of explosive gas mixtures
• Curie content of waste gas decay tanks
• Activity in BWR main condenser off-gas
• Curie limit for outside liquid storage tanks
• NRC Staffs Interpretation and Application of
  ALARA
• Radioactive material concentration in liquid
  effluents shall not exceed 10X EC (or MPC) at
  discharge point
• Gaseous effluents shall not exceed dose rate of
  500 mrem/yr, total body, 3000 mrem/yr, skin or
  1500 mrem/yr, any organ
• Radwaste systems shall be maintained and used to
  process effluents prior to release when projected
  doses exceed fraction of design objectives

17
Changes to Address 10 CFR 20 Revision

• Acceptable to continue to use old MPC values for
  controlling liquid release rate in lieu of new EC
  values (reference to old 10 CFR 20, Appendix B,
  Table II as opposed to current reference to
  current 10 CFR 20, Appendix B, Table 2).
• 10 times EC values allowed, which represents the
  same dose rate basis as MPCs - 500 mrem/yr.
• Non-stochastic (organ) doses have not been
  considered, because these effects are not
  considered to occur at the member of the public
  dose limits.
• For certain radionuclides, where the organ dose
  is much greater than the resultant EDE (e.g.,
  I-131), 10 x EC will allow increases in maximum
  release rates.
• For inhalation, ingestion, EC values were
  calculated by adjusting the occupational values,
  taking into consideration increased exposure and
  different dose criteria (50 mrem vs 5000 mrem).
  Also factor of 2 included to account for
  different age groups (other than adult worker).

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Liquid and Gaseous Effluent Design, Processing
and Controls

• Primarily a licensing basis issue.
• NRC guidance Standard Review Plan, NUREG-0800,
  Section 11.
• USAR design basis source term and processing
  controls basis for controls.
• June 4, 1976 Appendix I submittals
• Other licensing commitments.
• Provided releases maintained ALARA, predominantly
  a design basis issue.
• Operability maintain and operate i/a/w design.
• Periodic verification of operability
• Important if releases increase
• Ability to handle off-normal conditions

19
NRC Bulletin 80-10

• Title Contamination of Nonradioactive System
  and Resulting Potential for Unmonitored,
  Uncontrolled Release of Radioactivity to
  Environment
• Issued in response to events at NPP where system
  use and operation inconsistent with design basis
  leading to inadequate controls over system
  contamination and releases.
• Required all NPP licensees
• To review system design/operation and institute a
  sampling and analysis program for potential
  unmonitored release points.
• Establish controls and limits on non-radioactive
  systems if become contaminated.
• Invoked 10CFR50.59 process to radioactive
  effluent controls.

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Conducting Releases Evaluations and Records

• Must be conducted i/a/w TS and ODCM
• (Advantages of Generic Letter 89-01 format)
• Must not be in conflict with UFSAR (50.59
  process)
• Normal evaluated and control pathways (per design
  basis)
• Potential for releases from non-radioactive
  systems/pathways (NRC Bulletin 80-10)
• Records
• ODCM dose calculations
• Activities, volumes, time period
• Litigation Protection

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Current Approaches to Pathway and Dose Modeling

• Reg Guide 1.109 and NUREG-0133 based on ICRP-2
  dosimetric modeling (1950's data and critical
  organ approach). Age dependent dose factors
  developed for selected radionuclides.
• Revised 10 CFR 20 (1991) based on ICRP-26/30
  dosimetric modeling and effective dose equivalent
  approach.
• Other Applicable Dose Standards
• 40 CFR 190, Environmental Dose Standard for
  Uranium Fuel Cycle (includes direct dose
  component) based on critical organ concept.
• 40 CFR 141, Drinking Water Standard default
  concentration limits mixed-bag ICRP-2 and
  ICRP-72 (FGR 13) considerations in a Dec. 7,
  2000 final rule
• Clean Air Act NRC licensees exempt
• Decommissioning ICRP-30 based, probabilistic
  modeling (DandD and RESRAD).
• Use of Updated Dosimetry - ICRP-60/72 (FGR 12
  external) NRC has allowed use for certain
  decommissioning projects. Not codified.

23
Issues Surrounding New Plant Licensing and ALARA
for Radioactive Effluents
24
Adapted from NEI March 2006 Insight Newsletter.
25
Steps in the Licensing Process

• Radwaste processing system design
• Evaluation of radioactive effluent source term
• Evaluation of compliance with Appendix I
  individual dose design objectives
• Cost-Benefit evaluation of radwaste system design
  -- 1000 per person-rem reduction
• NEPA evaluation
• Licensing hearings
• Development of Technical Specifications, ODCM,
  Radiation Monitoring Manual, Radiological
  Environmental Monitoring Manual

26
Overview of Regulatory Process

• Certified Designs NRC can certify reactor design
  for 15 years through the rulemaking process.
  Certification process addresses safety issues of
  an essentially complete nuclear power plant
  design, independent of a specific site.
• AP1000 - AP1000 Reactor by Westinghouse Electric
  Company
• ESBWR - Economic Simplified Boiling Water Reactor
  by General Electric

27
Early Site Permit Application Reviews

• Clinton ESP Site - Exelon Generation Company, LLC
  ESP - Application submitted 9/25/03
• Grand Gulf ESP Site - System Energy Resources
  Inc. ESP - Application submitted 10/21/03. NRC
  issued final EIS on 4/5/06, concluding no impacts
  that would prevent issuance of EIS
• North Anna ESP Site - Dominion Nuclear North
  Anna, LLC ESP - Application submitted 9/25/03

28
Combined Construction and Operating License (COL)
Applications

• Several planned but no submittals to date.
• Radwaste system design and specifics for the
  radiation monitoring system likely will not be
  finalized in the COL submittals.
• This type information needed for NRCs NEPA
  review and issuance of Environmental Impact
  Statement.

29
NRC Rule Changes Affecting ALARA for Effluents

• 10 CFR 20
• 1991 revision
• Incorporated updated dosimetry ICRP-30
• 100 mrem/y dose to public limit (effluent
  concentration limits based on 50 mrem/y liquid
  and 50 mrem/y atmospheric)
• 1997 revision for license termination
  (decommissioning) rule
• 10 CFR 20.1406, Minimization of Contamination
  (indirectly has potential impact because of plant
  design considerations)

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10 CFR 20.1406

• Applicants for licenses, other than renewals,
  after August 20, 1997, shall describe in the
  application how facility design and procedures
  for operation will minimize, to the extent
  practicable, contamination of the facility and
  the environment, facilitate eventual
  decommissioning, and minimize, to the extent
  practicable, the generation of radioactive waste.

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NRC Rule Changes Affecting ALARA for Effluents
(cont)

• 10 CFR 50, 50.34a, 50.36a, and Appendix I
• Essentially no fundamental changes in approach.
• NRC proposed revisions to clarify (March 13,
  2006, Federal Register Notice) applicability to
  design certification applications, combined
  construction and operating license applications
  and manufacturing license as covered in 10 CFR
  52.
• Standard designs include radwaste system design
  information and calculations of radioactive
  effluents.
• Radioactive Source Term
• NUREG-0016 (BWR-GALE code) and -0017 (PWR-GALE
  code)
• Source term based on 1 or 0.1 failed fuel
  needs clarification.
• Operating license applicants responsible for
  performing the site-specific dose analysis and
  final compliance with the Appendix I ALARA dose
  criteria.

32
New Plant LicensingDesign Basis Considerations

• Standard designs include
• Design basis radwaste system
• 10 CFR 50.34a
• Reg Guide 1.143 design criteria
• Standard source term based on existing guidance
  GALE code NUREG-0016 (BWR) and -0017 (PWR)
• 10 CFR 50, GDC 60 -- Radioactive effluent
  monitors, but without specifics.
• Combined Construction/Operating License (COL)
  Application to include
• Radiation monitor setpoint methodology
• Site-specific Appendix I compliance
• Site-specific pathway modeling and dose
  assessment
• Cost-benefit analysis of radwaste system design
  (1000 per person-rem population dose for
  additional radwaste processing capability)
• Plant specific ODCM, REMP, Radiation Monitoring
  Manual, and Radioactive Waste Process Control
  Program (PCP) to be submitted before fuel loading
  (Regulatory approach/position being developed)

33
Dose Pathway Modeling

• Site-specific hydrology/atmospheric dispersion
• Other site-specific ecological factors
• Unique pathways, bioaccumulation
• Environmental usage
• Maximum exposed individual
• population dose assessment
• Biota doses

34
Updated Dosimetry and Pathway Modeling

• Dose Modeling
• Probabilistic (90 CL) versus Deterministic
• Update to ICRP 60/72 dosimetry
• Additional age groups
• Environmental pathway modeling
• Atmospheric dispersion aquatic dilution
• Transport and biological accumulation factors
• Individual usage factors

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Liquid Effluent Source Term Used for Evaluating Doses Based on ICRP-30/72 and RG 1.109 Dose Factors Liquid Effluent Source Term Used for Evaluating Doses Based on ICRP-30/72 and RG 1.109 Dose Factors Liquid Effluent Source Term Used for Evaluating Doses Based on ICRP-30/72 and RG 1.109 Dose Factors
Nuclide Typical BWR Typical PWR
Nuclide (Ci/yr) (Ci/yr)
3H 26 280
24Na 1.60E-03 1.10E-03
54Mn 1.20E-03 3.90E-03
55Fe 2.90E-03 7.30E-03
59Fe 6.00E-05 2.20E-03
58Co 4.40E-03 8.30E-03
60Co 9.90E-03 1.40E-02
65Zn 5.40E-04 4.00E-05
89Sr 2.00E-04 1.00E-04
90Sr 2.00E-05 1.00E-05
131I 8.10E-02 4.60E-02
134Cs 1.30E-02 2.20E-02
137Cs 2.40E-02 3.00E-02
Based on generic release data from NUREG-0016 for BWR and NUREG-0017 for PWR. Based on generic release data from NUREG-0016 for BWR and NUREG-0017 for PWR. Based on generic release data from NUREG-0016 for BWR and NUREG-0017 for PWR.
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Noble Gases Effluent Source Term Noble Gases Effluent Source Term Noble Gases Effluent Source Term
Nuclide BWR PWR
Nuclide (Ci/yr) (Ci/yr)
41Ar 38 -
83mKr - -
85mKr 32 53
85Kr 240 2,000
87Kr 63 18
88Kr 95 65
89Kr 610 -
90Kr - -
131mXe 5.1 1,600
133mXe - 100
133Xe 1,800 4,800
135mXe 990 7
135Xe 1,200 490
137Xe 1,300 -
138Xe 1,000 6
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51
NRCDose

• NRCDose is a user-friendly 16-bit PC-based,
  software interface for the LADTAP II, GASPAR II,
  and XOQDOQ programs which operates under all
  Microsoft WindowsTM platforms.
• LADTAP II, GASPAR II, and XOQDOQ are programs
  developed by NRC for implementing Regulatory
  Guides 1.109 and 1.111, which were originally
  created for mainframe computers and written using
  the FORTRAN programming language.
• These dose modeling codes are currently being
  used for license renewal evaluations. the NRCs
  programs industry standards.
• While still utilizing the FORTRAN code, NRCDose
  incorporates a WindowsTM based interface, which
  allows the user to enter and retrieve data
  through a series of windows. This graphical
  interface allows the user to create sets of data
  that can be named and retrieved at a later date
  for review or modification.

52
LADTAP

• LADTAP II implements the radiological exposure
  models described in Regulatory Guide 1.109, Rev.
  1 for routine releases in liquid effluent.
• Calculates the radiation exposure to man from
  potable water, aquatic foods, shoreline deposits,
  swimming, boating, and irrigated foods, and also
  the dose to biota.
• Doses are calculated for both the maximum
  individual and for the population and are
  summarized for each pathway by age group and
  organ.
• Four different age groups are included in the
  dose assessments - infant, child, teen, and
  adult. LADTAP II also calculates doses to
  certain representative biota other than man in
  the aquatic environment such as fish,
  invertebrates, algae, muskrats, raccoons, herons,
  and ducks using models presented in WASH-1258.
• Reconcentration, if any, of each nuclide is
  determined from one of the three models (chosen
  by the user) available in the program, or the
  user may input the reconcentration factor if none
  of the models available in the program is
  appropriate. Available options include complete
  mixing, partial mixing, or the plug-flow model.
  These models are described in US NRC Regulatory
  Guide 1.113.

53
ALARA Dose Analysis

• Drop-down menu offering choice of "Max Exposed
  Individual" and "Additional Usage Locations" data
  entry dialogs. The following describes data
  inputs relative to the presented menu items
• Max Exposed Individual... - presents the dialog
  for modification of the variables corresponding
  to Record Type 7 of the LADTAP input record.
• To change the default usage and consumption data,
  click on the Yes option button in the Population
  Fractions frame and then click on the enabled
  Edit button. A dialog will be presented for
  editing.

54
Population Usage Drinking Water, Shoreline,
Swimming, and Boating

• Drop-down menu offering choice of "Drinking
  Water," "Shoreline," "Swimming," and "Boating."
• Drinking Water... selection of the drinking water
  locations to be edited. Permits entry and
  modification of variables, which correspond to
  the Record Type 13 inputs.
• Shoreline... - same as Drinking Water above, for
  Record Type 14 inputs.
• Swimming... - same as Drinking Water above, for
  Record Type 15 inputs.
• Boating... - same as Drinking Water above, for
  Record Type 16 inputs.

55
Irrigation Food Data

• Drop-down menu offering choice of "Pathway" and
  "Water Usage Locations" data entry dialogs.
  These inputs represent Records 17 and 18, which
  are treated as a data set
• Pathway... selection of the food pathways to be
  edited. The data entry dialog permits entry
  modification of variables, which correspond to
  the Record Type 17 inputs. The bottom frame
  accommodates inputs for optional Record Types
  17a. To change the default food consumption
  data, click on the Yes option button in the
  bottom frame and then click on the enabled Edit
  button. Click the Update button to accept the
  changes or the Cancel button to ignore any
  changes and return to the previous dialog.
• Water Usage Locations... selection of the food
  pathways to be edited. Drop-down list box for
  selecting the food type. The data entry dialog
  presented permits entry modification of
  variables, which correspond to the Record Type 18
  inputs.

56
Biota Exposures

• Dialog for selection of the biota locations to be
  edited. Doses calculated using simplistic
  modeling from BNWL-1754
• Data entry dialog permits entry modification of
  variables, corresponding to the Record Type 19
  inputs.
• Models biota uptake and simplistic dosimetry.
• Doses to fish, invert., algae, muskrat, raccoon,
  heron, duck.
• Better modeling available DOE Guidance, RESRAD
  Biota.

57
GASPAR

• GASPAR implements the methodologies of Regulatory
  Guide 1.109, Rev. 1.
• Output from XOQDOQ is used as meteorological data
  input to GASPAR.
• The special locations are used for evaluating
  maximum-exposed individual doses and standard
  radial distances and segments are used for
  population doses.
• Seven exposure pathways are included within
  GASPAR - plume immersion, groundplane exposure,
  inhalation, vegetation, cow?s milk, goat?s milk,
  and meat.
• External exposure doses to the total body and
  skin are calculated for releases of noble gases
  using semi-infinite plume dose conversion factors
  coupled. Iodine and particulate releases are not
  included in direct exposure dose calculations.
  Similarly, groundplane, inhalation, and food
  pathways only consider radioiodine and
  particulate effluents.
• GASPAR is configured, with its input and output
  data and formats, mainly for performing plant
  design basis evaluations as needed for nuclear
  power plant licensing. However, it can be used
  for evaluating routine effluent releases with the
  input of source term and, as desired, meteorology
  specific to the time period of interest.

58
GASPAR -- Site Specifics

• Dialog for modifying the variables corresponding
  to Record Type 3 of the GASPAR input record.
  Change the presented default values as desired
  and press Update to accept the values or Cancel
  to ignore any changes, and return to the previous
  dialog.
• Average absolute humidity is for the growing
  season. If blank or zero, default of 8 g/m3 is
  used. If an average temperature over growing
  season is input, humidity input should be the
  relative humidity.

59
GASPAR -- Population Data

• Dialog for modifying the variables corresponding
  to Record Types 4 and 4.1 of the GASPAR input
  record.
• The "Title" is the only input for Record Type 4.
  
• Variable IDAT is modified from this program. It
  is internally defaulted to "0," defining North as
  the starting compass center.
• Click on the Data Entry... button to display
  either the dialog for entry of variables
  corresponding to Record Types 4.1.na and 4.1.nb,
  or that for entry of variables corresponding to
  Record Type 4.2.
• The displayed dialog is dependent on the setting
  of variable KT in Record Type 4.1 (Input by
  distance and direction - if checked).
• Data input values are the number of people in
  each sector or total 50-mile population.

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Milk, Meat and Vegetable Data

• Milk Production Data... - similar to Population
  Data above, but relates to Record Type 5. Refer
  to the Population Data section for description.
• Meat Production Data... - similar to Population
  Data above, but relates to Record Type 6. Refer
  to the Population Data section for description.
• Vegetable Production Data... - similar to
  Population Data above, but relates to Record Type
  7. Refer to the Population Data section for
  description.
• Data input values are in units of L/y (milk) and
  kg/y (meat and vegetables)

61
GASPAR -- Source Terms

• Multiple source terms can be specified for
  distinguishing between different release points
  (and different meteorology).
• Dialog for selection of the source term to be
  edited. Click on the desired source term to
  highlight it for modification of the variables
  corresponding to Record Types 8 and 8.1 of the
  GASPAR input record. The "Title" is the only
  input for Record Type 8.
• Click on the Edit button to display the dialog
  for modifying the source term values (Record
  Types 8.1.n).
• This dialog permits radionuclide information
  entry for up to 33 nuclides. Clicking on the
  NxPg or PrvPg command buttons will move to the
  next or previous page of nuclides.

62
Meteorological Data

• Meteorological Data - presents drop-down menu
  offering choice of "Undecayed, Undepleted,"
  "Decayed, Undepleted," "Decayed, Depleted," or
  "Ground Deposition" data entry dialogs. Need
  entry for each Source Term.
• Undecayed, Undepleted... - dialog for modifying
  the variables corresponding to Record Types 9 and
  9.1 of the GASPAR input record. Click on the Data
  Entry... to display the dialog for entry of
  variables corresponding to Record Types 9.1.na
  and 9.1.nb. Data input units are sec per m3.
• Decayed, Undepleted... - similar to Undecayed,
  Undepleted above, but relates to Record Type 10.
  Units are sec per m3.
• Decayed, Depleted... - similar to Undecayed,
  Undepleted above, but relates to Record Type 11.
  Units are sec per m3
• Ground Deposition... - similar to Undecayed,
  Undepleted above, but relates to Record Type 12.
  Units are m-2.

63
Meteorological Dispersion Parameters
Definitions and Use

• Undecayed, Undepleted Units are second per m3.
  No decay during transit no depletion of plume.
• Decayed, Undepleted Units are seconds per m3.
• Decayed, Depleted Units are seconds per m3
• Ground Deposition Units are m-2.

64
XOQDOQ

• XOQDOQ designed for evaluating routine releases
  from nuclear power plants.
• Primarily designed to calculate annual average
  relative effluent concentrations (X/Q values) and
  annual average relative depositions (D/Q values)
  at user specified locations (for maximum exposed
  individual dose assessment) and at various
  standard radial distances and segments (for
  population dose assessment).
• Evaluation of meteorological dispersion for
  intermittent releases (e.g., containment purge or
  waste gas decay tank releases) may also be
  evaluated. Instead of the annual average, less
  frequent meteorological condition may be assumed.
  An interpolation is performed for correlating
  less frequent meteorological condition to the
  annual average conditions.

65
XOQDOQ (cont)

• The meteorological modeling includes
  consideration of building wake effect, plume
  depletion due to dry deposition and radioactive
  decay.
• Up to three separate decay half-lives can be
  specified
• Regulatory Guide 1.111 recommends the use of a
  2.26 day half-life for short-lived noble gases
  and 8 day half-life for iodines.
• Release height and plume rise can be modeled or
  the plume may be modeled as a ground level
  release.
• XOQDOQ can also utilize a so-called mixed mode
  release, where, under certain meteorological
  conditions, the release is treated as elevated
  and, under other conditions, as ground level.
  The combination of these two conditions produces
  the annual average conditions.

66
XOQDOQ (cont)

• The release may be treated as always elevated,
  always ground level, or a mixed mode, which is
  primarily used in the analysis of vent release
  points at or above the height of adjacent
  structures.
• The effluent plume for elevated releases can
  undergo plume rise due to momentum and/or
  buoyancy.
• Ground-level releases can be affected by
  additional dispersion due to nearby building
  wakes.
• Wind speeds measured at one level may be
  extrapolated to other elevations for release
  point evaluation.
• Plume growth parameters (sy and sz) can be
  described by Pasquill-Gifford curves or desert
  curves by Markee.
• For elevated releases, topography can be inputted
  for use in calculation of the effective plume
  height.
• The plume may undergo radioactive decay for
  varied half-lives.
• The plume may be depleted via dry deposition.

67
XOQDOQ (cont)

• X/Q and D/Q values may be modified by standard or
  inputted values to account for local air
  recirculation or air stagnation.
• X/Q and D/Q values can be evaluated for
  predetermined distance segments and for specified
  points of interest.
• The joint frequency data may be inputted as a
  percent frequency of occurrence or as a total
  frequency of occurrence.
• The wind direction is broken down into the
  standard sixteen (16) 22.5? sectors (e.g., N,
  NNE, NE, ENE, etc.). Up to fourteen (14)
  separate wind speed classes can be modeled and
  the atmospheric stability is grouped according to
  seven (7) categories from extremely unstable (A
  class) to extremely stable (G class).
• The output from XOQDOQ may be modified, which
  will allow its direct use as an input
  meteorological data set for the GASPAR code. An
  example XOQDOQ computer run output, appropriately
  modified, is presented in Attachment 1.

68
XOQDOQ Variables

• Variables menu option presents a drop-down menu
  offering "Options," "Parameters," and "Wind Data"
  selections.
• Options... - presents the dialog shown for
  modifying the variables corresponding to Record
  Type 1 of the XOQDOQ input record. KOPT(11),
  which calculated using 30o sectors is not
  changeable from within this program. It is
  defaulted to "0."
• If first option is checked KOPT(1) 1,
  remember to add 1 to NVEL (number of velocity
  categories), first input in System Parameters
  dialog box.
• Third option KOPT(3), option to compute sector
  spread for comparison to centerline value in
  purge calculations is not currently operable.

69
XOQDOQ -- Parameters

• Parameters... -dialog for modifying the variables
  corresponding to Record Type 3 of the XOQDOQ
  input record.

70
XOQDOQ Parameters (cont)

• NDIS variable (number of distances with terrain
  data for each sector) if greater than "0" enables
  the associated Heights button.
• Clicking on this Heights button displays the
  dialog for entry/modification of variables
  corresponding to Record Types 10 and 11.

71
XOQDOQ Parameters (cont)

• NPTYPE variable (number of titles of receptor
  types) if greater than "0" enables the associated
  Define button.
• Clicking on this Define button displays dialog
  for entering or modifying variables corresponding
  to Record Types 13 and 12.
• Filling in a Title enables the adjacent text box
  for entry of the number of locations (NPOINT),
  which in turn if greater than "0" enables the
  associated Define button.
• Clicking on this Define button displays the
  dialog for entering or modifying variables
  corresponding to Record Type 14.

72
XOQDOQ Parameters (cont)

• NEXIT variable (number of release exit points) if
  greater than "0" enables the associated Define
  button.
• Clicking on this Define button displays dialog
  for editing release point information.
• Click on the desired release point ID and then
  click on Edit to display that permits entering
  and modifying variables which correspond to
  Record Types 15 and 16.
• Click on the More button to enter or modify
  variables which correspond to Record Types 17.
• NCOR variable (number of distances of site
  specific correction factors for recirculation) if
  greater than "0" enables the associated
  Corrections button. Clicking on this Corrections
  button displays a dialog for entry/modification
  of variables corresponding to Record Types 8 and
  9.

73
XOQDOQ Parameters (cont)

• UCOR (wind speed class correction factor) is part
  of Record Type 7.
• Clicking on the adjacent Speed Limits button
  displays for entering or modifying the remaining
  variables corresponding to Record Type 7.
• If KOPT(1) 1 (option set) , calms are a
  distinct wind velocity class and appropriate
  input is required.
• If the wind speed classes are defined in units of
  miles per hour, the wind speed class correction
  factor (UCOR) must be a value greater than 100
  (use 101) to convert inputs to meters per second.

74
XOQDOQ -- Wind Data

• Wind Data presents another drop-down menu
  offering choice of "Misc Parameters," "Calms
  Data," and "Joint Freq Data" data entry dialogs.
  
• Misc Parameters... - presents the dialog for
  modifying location of the variables corresponding
  to Record Type 4 of the XOQDOQ input record.
• Calms Data... - presents the dialog for modifying
  the variables corresponding to Record Type 5 of
  the XOQDOQ input record.
• Joint Freq Data... - presents the dialog for
  modifying the variables corresponding to Record
  Type 6 of the XOQDOQ input record.

75
Joint Freq Data Input

• Joint Freq Data... - presents the dialog for
  modifying the variables corresponding to Record
  Type 6 of the XOQDOQ input record.

76
Questions

• and
• Summary