Title: ALARA%20and%20Radioactive%20Effluents%20Regulatory%20History%20and%20Application%20for%20Next%20Generation%20Power%20Reactor%20Licensing
1ALARA 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
2Objectives/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).
3ALARA 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.
410 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.
510 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.
610 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.
710 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
8Appendix 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
9Appendix 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.
10RM-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.
11NRCs 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
12Implementation 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.
13Industry/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)
14NRCs 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.)
15NRCs 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.
16RETS 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
17Changes 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).
18Liquid 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
19NRC 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.
20Conducting 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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22Current 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.
23Issues Surrounding New Plant Licensing and ALARA
for Radioactive Effluents
24Adapted from NEI March 2006 Insight Newsletter.
25Steps 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
26Overview 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
27Early 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
28Combined 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.
29NRC 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)
3010 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.
31NRC 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.
32New 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)
33Dose 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
34Updated 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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39Liquid 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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43Noble 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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51NRCDose
- 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.
52LADTAP
- 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.
53ALARA 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.
54Population 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.
55Irrigation 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.
56Biota 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.
57GASPAR
- 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.
58GASPAR -- 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.
59GASPAR -- 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.
60Milk, 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)
61GASPAR -- 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.
62Meteorological 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.
63Meteorological 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.
64XOQDOQ
- 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.
65XOQDOQ (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.
66XOQDOQ (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.
67XOQDOQ (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.
68XOQDOQ 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.
69XOQDOQ -- Parameters
- Parameters... -dialog for modifying the variables
corresponding to Record Type 3 of the XOQDOQ
input record.
70XOQDOQ 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.
71XOQDOQ 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.
72XOQDOQ 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.
73XOQDOQ 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.
74XOQDOQ -- 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.
75Joint Freq Data Input
- Joint Freq Data... - presents the dialog for
modifying the variables corresponding to Record
Type 6 of the XOQDOQ input record.
76Questions