Chemistry and Radiation Safety › v3-app_crowdc › assets › b › b3 › b30a...Joint Water Chemistry and Radiation Safety Research Focus Area: Radioactivity Generation and Control
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Key industry developments, feedback (prioritization), and needs (e.g. changes to regulations or standards, industry focus on cost savings, etc)– Reduced efforts for specific regulatory support due to NRC re-baselining– New project added since prioritization to support cost savings– Scope was adjusted to account for current developments
ALARA Strategies and Technologies•Combines source term reduction technologies with typical dose reduction tools and work planning improvements to provide a comprehensive strategy for reducing dose to workers.
Radioactivity Generation and Control (Source Term Reduction) – Joint w/Chem.•Understanding radioactivity and radiation field generation and transport processes and tools/technologies to improve control of radioactivity.
Radiation Safety Guidance•Development and maintenance of guidelines, guides and sourcebooks for radiation protection, source term reduction, radiological environmental protection (which includes groundwater), and low level waste.
Radiation Measurements and Dosimetry for Workers and Public•Investigates advanced radiation detection and monitoring technologies for site and environmental monitoring purposes. In addition, more accurate dose calculation methodologies will be investigated to improve the quantification of the dose to workers and the public
Effluent and Radwaste Minimization•Investigates effluent (gaseous, liquid), groundwater remediation, and radwaste minimization technologies and management strategies. Also evaluates the impact to effluent and radwaste programs from changes in plant design or operational factors.
Integration of Industrial and Radiological Safety (currently unfunded)•Includes research related to the development of technologies and strategies that better meet the needs for an integrated approach to worker protection – radiological and industrial hazards.
Benchmarking and Trending (Fundamental)*•Maintenance of databases for the Standard Radiation Monitoring Programs (SRMP/BRAC) and the industry low level waste benchmarking database, RadBench™.
Low Dose Radiation Health Effects* •Investigates health effects from exposure to ionizing radiation to inform the development of radiation safety standards, radiation protection practices, and communication of risks to workers and the public.
Decommissioning Technology and Strategy*•Investigates technologies and strategies to facilitate the development and execution of a safe, efficient, and cost-effective decommissioning program.
Low Dose Radiation Risk Communication for Decommissioning
(2018-2019)*
Decommissioning Technology and
Strategies
System Automation for Reactor Internals
Segmentation (2017-2019)
DOE Technology Development (2017-
2018)Decommissioning Experience Wiki
(ongoing)Guidance for Mothballing
(2017-2019)*End of Life Plant
Chemistry(2017-2018)*
Low Dose Radiation Risk Communication for Decommissioning
(2018-2019)*
Funded Work
• Not included in general prioritization. Alternate prioritization used.
• RFA on Radiation Safety Benchmarking and
Trending is fundamental to the R&D completed within the program.
• RFA on Low Dose Radiation Health Effects is unique in the technical subjects addressed and have long term implications; therefore, a separate advisory committee made up of scientists and utility representatives from the TAC and APC have been set up to provide technical input.
• RFA on Decommissioning Technology and
Strategies is funded separately and is focused on accelerating the development of tools, technologies, guidance for safe and efficient decommissioning.
Joint Water Chemistry and Radiation Safety Research Focus Area:
Radioactivity Generation and Control (Source Term)
Focused on minimizing and controlling the radioactivity (i.e. source term) that is generated from nuclear power plant operations
Addresses technologies and strategies for minimizing plant radiation fields
Near term efforts include evaluations of other radionuclides (e.g. non-cobalt) of potential importance to worker exposures, surface modification to minimize contamination and recontamination, optimization of current techniques, and impact of new operating chemistry
Project types Typical deliverables Specific near-term activities
Literature Reviews/Feasibility Studies
Laboratory Testing and Analysis
White Papers Reports Data for R&D
Effect of micro-environments (modified) Surface passivation Hydrophobic treatment technologies Impact of silver and antimony (modified)
Review of Plant Observations Technical Reports Best Practices
Optimization of Zn Injection* Effect of ultra-low iron reducing conditions in
Worker exposure is optimized when source term reduction techniques are coupled with enhancements in worker practices and work planning.
Many technologies have been developed (e.g. zinc injection, fueling cleaning) but an integrated approach and application is needed to fully leverage the benefits of source term and ALARA techniques.
Future efforts will include the development of a Decision Logic for site specific implementation of source term reduction strategies. Ultimately, the integration of this tool with the 3D ALARA planning algorithm and location tracking will provide an integrated means of predicting outage dose rates and worker dose.
Project types Typical deliverables Specific near-term activities
ALARA Planning Tools Source Term Prediction Tools Dose Optimization Strategies
Reports Software Data for R&D
Decision Logic for Source Term Reduction* Use of RMT to Reduce Survey Frequency* Integration of Real Time Dose Data with Location
Tracking for Improved Dose Optimization and Dose Estimates*
Background:– Member feedback suggests that developing a basis document for
using remote monitoring equipment to reduce or eliminate certain types of routine surveys could be a significant efficiency.
– EPRI started initial examination of issues in 2007. – Significant technological advancements have occurred.– Technical and regulatory hurdles need to be addressed. Instrument checks and calibration Area of validity Transients
Radiation Measurement and Dosimetry for Workers and Public
Nuclear power plants need to be able to identify and quantify radiological hazards and exposures on site and in the environment.
Work in this Research Focus Area includes
– Investigating and demonstrating advanced, detection and monitoring technologies for site and environmental use
Information from these systems could be used to streamline survey requirements and inform radioactivity removal strategies, effluent management, and waste handling/treatment methods.
– Researching methods and approaches to improve dosimetry for workers and members of the public (e.g. offsite dose)
Project types Typical deliverables Specific near-term activities Radiation Measurement
EPRI Technical Reports Data for R&D
Plant Demonstration of At-power Gamma-isotopic Monitoring*
Dosimetry EPRI Technical Reports Improved Accuracy and Updating Methodology in
Determining Effluent Dose to Members of the Public Shielding Factors for Lens of the Eye*
Shielding Factors of Protective Equipment for Lens of the Eye
Background:– Global Issue, Right Now– Follow on to EPRI work on Lens of the Eye. – EPRI Lens of Eye Workshop identified need for efforts in area. – There is no methodology or quantification of protection factors for typical
protective equipment used by workers in member facilities– There are no standard phantoms or calibration protocols available, although
progress is being made.
Purpose:– Develop and document a consistent approach for testing of equipment
for protection of the lens of the eye for use by industry and vendors. – Provide a generic set of protection factors for use in planning and
implementing radiation protection for lens of the eye.
Public concerns about radioactive waste management and effluent releases could negatively impact the image of nuclear power around the world.
Work in this RFA supports the minimization and management of effluents and radwaste by:– Investigating advanced technologies and techniques to decrease the generation and release of effluents and low
level waste
– Assessing the impacts to effluents and radwaste programs from changes made to plant design or operations
– Investigating and demonstrating remediation technologies
Project types Typical deliverables Specific near-term activities
Literature Reviews/Feasibility Studies
Laboratory Testing Plant Demonstrations
EPRI technical report Data for R&D
Impacts to Effluents and Radwaste from Radionuclides and Chemicals Generated from Non-Design Basis Materials (modified scope)*
Impact of Fuel Material Changes on Radwaste Characterization and Corrosion Product Behavior: Scoping Assessment*
Effect of a KOH-based pH Program on Radiation Fields, Radioactive Effluents and Waste*
Tritium Removal and Reduction Technologies* Technology Development or
Impact of Materials Changes on Radwaste and Corrosion Products – Fuel Material Scoping Assessment
Objective: Identify potential new source terms and characterize correlations between fuel assembly materials of construction and plant source terms (radiation field and radwaste)
Project Approach– Identify potential new source terms due to non-
design basis materials– Collect and analyze data sources for changes
in contamination due to fuel materials CVCS / RWCU filter use, dose rates,
change-out frequency Coolant activity Ultrasonic fuel cleaning filter dose and
isotopics Crud scrape data
– Summarize findings and determine if future work is warranted
Value: Provide information about Zr and Nbradioisotopic contamination in PWRs and BWRs to aid– Fuel reliability engineers in understanding
prevalence of oxide spallation – Chemistry and radiation management staff and
understanding of impacts on worker dose, reactor coolant purification, and waste classification
Proposed Duration and Timing: 2018-2019 (24 mo.)
Proposed for co-funding with Chemistry, Radiation Safety, and Fuel Reliability
Approach– Short term action to address NRC concern– Working Group to develop revision
Research Value:– Guidance clearly consistent with regulatory requirements and
interpretations– Clarification of special issues not previously addressed– Communication tools for sensitive public and worker topics– Availability of OE and Lessons Learned on prevention, mitigation,
and response– Increase efficiency, reduce cost while maintaining safety
Up to date guidelines address issues, facilitate communicationsProposed Duration and Timing: 2017-2018 (24 mo.)
Optimization of Industrial and Radiological Safety
Radiation safety and Industrial safety are important components of the nuclear industry’s safety culture.
An integrated approach/strategy is needed to address aspects that influence both programs so that workers are protected against the overall risk.
Work may include the development of a systematic approach for risk recognition, risk assessment, and risk mitigation of hazards that impact decisions in industrial safety and radiological safety. Demonstrations of advanced monitoring and protection technologies may also be pursued.
Research will be done in collaboration with EPRI’s Occupational Health and Safety Program.
Project types Typical deliverables Specific near-term activities
Program guidance Technical Reports Best Practices Workshop
Guidance for Optimization of Worker Protection: Addressing Radiation Safety and Industrial Safety Concerns*
Robust datasets are needed to identify improvements in plant operations and enhance public and worker safetyNear term efforts include maintaining RadBench™ website and presenting
trends at annual EPRI/ASME Radwaste WorkshopFuture efforts include continuing expansion of both SRMP/BRAC and
RadBench™ to include data from plants outside the U.S. and begin migration towards internet based access for SRMP/BRAC
Project types Typical deliverables Specific near-term activities
Standard Radiation Field Monitoring and CharacterizationProgram (SRMC)
Benchmarking summary reports Radiation field and characterization
data for R&D
Maintenance of SRMP and BRAC Database enhancements Online access
Low Dose Radiation Health Effects Low dose radiation health effect estimates forms the basis for radiation safety policies/standards and plant
operational practices Sound technical basis is needed to inform standards, policies, and practices. Efforts to date have included reviews and syntheses of studies related to low dose rate cancer risks (e.g.
BEIR VII DDREF), non-cancer risks (e.g. cataracts), and recommendations for the National Academies of Sciences (NAS) cancer study of populations living near nuclear facilities.
Project types Typical deliverables Specific near-term activities
Low Dose is a fundamental, global issue which impacts everything from dose limits to public perceptions Protection policies apply conservative and precautionary approaches due to
not knowing the dose – effect relationship Reduce Uncertainty
Dialogue continues…. ICRP task groups on DDREF, Effective Dose, Detriment … NCRP recommendations under development EPA regulation changes being considered
Goal: Reduce uncertainties in risk estimates to inform next set of standards
Objectives:– Monitor global Low Dose research activities– Provide independent ongoing programmatic review – Provide independent scientific review of research projects and scientific
articles– Provide research ideas
Scientific and Industry input to guide EPRI program
Develop a technical basis for more accurate and plausible radiation health risk models and interpretations that incorporates the most up to date science– Analyze existing epidemiological and animal databases for information to
improve estimates of risk– Comprehensive review of existing, influential studies– Synthesize research into an integrated pictureProvide a platform and lead a dialogue and collaboration
amongst research organizationsProvide technical input to inform decisions related to current
Background:– Research on effects of ionizing radiation is
occurring in many countries throughout the world.
– There are currently no established international mechanisms for discussing and collaborating on low dose radiation research priorities, strategies, programs, or results.
– A forum is needed to facilitate collaboration and cooperation.
Background:– Conservative approach to RP used to address uncertainties– Epidemiology studies do not have sufficient statistical
power to predict risks at occupational dose levels– Radiation Biology provides insights at molecular and cellular levels– A plausible and predictive model to link radiation biology and
Decommissioning Technology and Strategies Part of life cycle of the plant
Oversight of portfolio is provided by decommissioning supplemental program members
Decommissioning of commercial nuclear power reactors is a complex process typically requiring ten years or more to complete, at a cost of more than $600 million.
Opportunities exist for EPRI to facilitate more cost effective, safe decommissioning of nuclear power plants by compiling best practices from past and ongoing decommissioning projects, developing structured and practical guidance for executing an effective decommissioning program, and facilitating technology transfer between nuclear plant owners and industry experts.
Project types Typical deliverables Specific near-term activities
Program guidance EPRI Technical Reports
Guidance for Mothballing a Nuclear Power Plant* End of Plant Life Chemistry Control Optimization and
Consideration of Cost Minimization and Recovery (joint with Chemistry)*
Best Practices in Low Dose Radiation Risk Communication: Decommissioning (joint with Low Dose)*
Technology demonstrations EPRI technical reports System Automation for Reactor Internals Segmentation DOE Technology Development
Knowledge Transfer Wiki database Commercial Nuclear Plant Decommissioning Experience Wiki
Typically one of the most challenging nuclear power plant decommissioning tasks.– Potential for high exposures– Long project durations (2-3 years)– Contributes to high total costsPrevious EPRI work on automation (Phase 1):
– Systematically evaluated all decommissioning tasks to identify candidate tasks for automation
– Results: highest priority tasks are reactor internals segmentation, site characterization and concrete decontamination
R. McGrath
Goal: Automate reactor internals segmentation to decrease worker exposures and increase efficiency_
System Automation for Reactor Internals Segmentation (2017 –2019)
Objective: Develop manipulator and/or cutting technologies that can be automated to safely reduce the duration of reactor internals segmentation projects. 2017 – Begin development of automated cutting
technology and perform pilot scale testing. 2018 - Based on the results of the pilot scale
testing, full scale testing on non-irradiated metal would be conducted. 2019 - Using technologies tested in 2018, a full
scale field demonstration would be conducted on irradiated metal.
Decommissioning Database (2016 to 2018) A wealth of experience is available from completed
and ongoing decommissioning projects Experience largely captured in more than 35 EPRI
reports There is a need for a searchable database for
decommissioning experience covering all areas (planning, execution, site characterization and release) Began development of Wiki-format database in 2016
– Include EPRI data and other data sources– Database roll out in 2016– Adding functionality and content in 2017 and 2018
Guidance for Mothballing a Nuclear Power Plant (2017-2018)Project
Guidance will include activities in the following areas:– Plant operation during the final operating cycle;– Chemistry controls and other activities during
shutdown;– Establishment of stable storage conditions;– Monitoring and other actions to be taken during
plant storage;– Preparing the plant for restart; and– Controls and monitoring during restart.Guidance will include technical, regulatory
and economic considerationsProposed Duration and Timing: 2017-2019 (36 mo.)
Phase 1: Assess the Impact of Flexible Operations on Source Term/Radiation Fields (2016-2017)
Identify knowledge gaps and challenges to source term and radiation field generation:– Survey component reliability, corrosion behavior, operational
practices, and radiation fields in BWRs and PWRs that have executed load following (e.g. Columbia, Comanche Peak) Hot spots Isotopic data Plant radiation field monitoring
– Review global experiences (e.g. WANO, IAEA, EDF)– Leverage ongoing work from BWR and PWR chemistry and
Phase 2: Assess Impact of Flexible Operations on Effluents (Gaseous, Liquid) and Radwaste (2017- 2018)Assess impacts to gaseous and liquid effluents by
collecting data and OE:– Generation of liquid and gaseous radwaste– Volume, activity concentration, isotopic composition of
radwaste generated– Capacity of gaseous and liquid radwaste systems– Frequency and volume of releases (continuous or batch)Assess impacts on amount and characteristics of
wet solid waste generation, packaging, transport, and disposal
Low Dose Radiation Risk Communication for Decommissioning
(2018-2019)*
Decommissioning Technology and
Strategies
System Automation for Reactor Internals
Segmentation (2017-2019)
DOE Technology Development (2017-
2018)Decommissioning Experience Wiki
(ongoing)Guidance for Mothballing
(2017-2019)*
End of Life Plant Chemistry
(2017-2018)*Low Dose Radiation Risk Communication for Decommissioning
(2018-2019)*
Funded Work
• Not included in general prioritization. Alternate prioritization used.
• RFA on Radiation Safety Benchmarking and
Trending is fundamental to the R&D completed within the program.
• RFA on Low Dose Radiation Health Effects is unique in the technical subjects addressed and have long term implications; therefore, a separate advisory committee made up of scientists and utility representatives from the TAC and APC have been set up to provide technical input.
• RFA on Decommissioning Technology and
Strategies is funded separately and is focused on accelerating the development of tools, technologies, guidance for safe and efficient decommissioning.
Radioactivity Generation and Control (Source Term Reduction)Chemistry Strategies for Surface Passivation
Why –– All reactors and all metal surfaces are affected– Metallic surface exposed to high-temperature water will corrode– Corrosion products exposed to neutrons will activate – Activated corrosion products will generate radiation fields
What –– Identify novel surface passivation approach that minimizes metal releases,
corrosion rates, and/or activity buildup – during component production and/or in situ – before in service and after decontamination
– Initiate technology transfer of proof-of-principle candidates
So what –Lower corrosion leads to
higher equipment reliability, less maintenance, lower radiation fields and reduced worker dose
Stopping Metal Release is Most Effective Course of Action
Hydrophobic Coatings - Reduce Contamination/Worker DoseKey Research Question: Can commercial hydrophobic coatings assist in
decontamination control and dose reduction? Does their degradation introduce detrimental species? What is their durability? How effective are they?
Can a standard qualification protocolbe developed?
What are reasonable criteria?
Project Approach:1) Survey globally nuclear and non-nuclear industry – best practices
and utilized hydrophobic coatings. Review chemical and physical surface modification treatments and technologies for
a. Durability of hydrophobicity,b. Release of potential detrimental species,c. Compatibility with materials of construction.
2) Create a state-of-the-art knowledge base3) Identify gaps and opportunities.4) Conduct demonstration under plant-like conditions. 5) Develop criteria for plant demonstration, verification and
– Sample sinks– Spent fuel pool tools– Casks (removal of fuel from spent fuel pool to dry cask storage)– Steam Generator downdraft table and water filter
2 types (Rustoleum Never Wet & Ultra Ever Dry) – applied per manufacturer instructions as aerosol Limited independent/verifying performance testing
– Review of use in other industries– Survey of membership – if you’d like to add, send request
to [email protected] most promising coatings for testing in addition
to coating currently used by membersPerform durability and performance testing
– Under common conditions (chemistry and radiation)– Assessing Initial releases of potential detrimental species Releases of potential detrimental species over simulated
Radioactivity Generation and Control (Source Term Reduction)Silver and Antimony Impact on Radiation Field Control
2.5 g cobalt or 1g silver activate to 60Co or 110mAg, resp., and cause radiation fields of equal magnitude.
Silver and antimony* sources might be more abound than previously thought: reactor vessel head seals,reactor control rod cluster assemblies, metal O-rings, valve seat seals, lead-free solder, brazing and welding material – and environmental sources
Silver and antimony chemistries are complex – in particular, under changing redox, pH, and temperature in a radiation field – and therefore, identification and quantification can be challenging.
Obj
ectiv
e
Identify sources Develop better knowledge of high-
temperature Ag and Sb speciation,solubility and reaction dynamics
Control impact on radiation fieldsa) though tools, technologies, strategies or
alternate component materials b) by eliminating ingress of silver and antimonyc) removal the elements effectively before their
activation, or their activation products
Scop
e/Ap
proa
ch Phase 1 – 2016 Survey & review global industry
knowledge base Develop experimental scope of work
Phase 2 – 2017-2018 Detailed plant monitoring program Lab testing – speciation, solubility, and reaction dynamic under simulated conditions
Valu
e/B
enef
it
The knowledge gained and opportunities identified will guide the global fleet in achieving excellence in radiation field control. Furthermore, the results will assist new builds by learning from the current fleet’s experiences and knowledge.
*Fine print: Equivalent masses of nickel or antimony activate to 58Co or 124Sb, resp., and cause radiation fields of equal magnitude.
Merge of Micro-Environment and Silver/Antimony Project
Radiation field effects of micro-environments result from surface interaction of ionic, solvated, and activated species– Species of emphasis originate from Zn, Ni, Co, Cr, Ag, and Sb– Speciation and surface interaction are temperature and pH dependent– Micro environments of emphasis – low temperature region RHR Coolant cleanup system Heat exchangers
Current radiation field challenges make this merge a natural fit– High Ag/Sb contribution in low temperature regions with unclear Zn influence
Review of Radiation Safety Guidelines for Revision• Review the EPRI Radiation Safety (Low Level Waste, Radiation Protection, Groundwater
Protection) Guidelines to determine whether they should be revised to reflect current and international nuclear power plant operating experiences and lessons learned, science, technology, regulations, policies, and regulatory guides.
• Leverage the Radiation Protection/Source Term Reduction, Groundwater, and Low Level Waste Technical Strategy Groups to gain utility member input.
Project Approach
• Up-to-date Guidelines are most valuable for efficient implementation at nuclear power plants and supports knowledge transfer.
• Enhanced Guidelines and associates programs at nuclear power plants supports the continued protection of the health and safety of workers, public, and environment.
Research Value
• Review and revision of Guidelines will include experiences and insights for international nuclear power plants.Global
• Identify gaps and best practices to improve the accuracy and methodology of determining public dose from radionuclides in nuclear power plant effluents.
Project Approach
• Review of industry regulations and regulatory guides associated to off-site dose calculations will be evaluated to identify opportunities for enhancements
• Analyze site-specific practices associated with the implementation of these regulations and regulatory guides to identify opportunities for enhancements.
• Develop technical guidance for enhancing the accuracy of off-site dose calculations.
Research Value
• Supports stakeholder confidence in nuclear power operations, health and safety of the public, and environmental stewardship.
• Inform updates to regulations and regulatory guides.
Global Applicability
• Consolidates best practices from international community of nuclear power plants.
• Potential areas of further investigation for improvements applicable to countries that use similar regulatory framework as the US Nuclear Regulatory Commission (NRC)
Accurate Off-Site/Public Dose Calculation 2015-2016 Regulation/Regulatory Guide Review Update
– Reviewed Regulations/Regulatory Guides from European Union, Sweden, Czech Republic, Spain, United Kingdom, Canada, United States, South Korea.
– Documented potential enhancements in the areas of: General/Regulatory Approach Environmental transport and dispersion modeling (hydrological and
atmospheric) Dose Pathway and Exposure Modeling
– Current methods continue to be protective of the public and calculated doses are small percentages of regulatory limits.
– International community uses updated health physics science and environmental transport model. Some apply probabilistic approaches to public dose calculations.
– Potential enhancements will need to be further investigated to quantify impacts on accuracy.
• Maintain the RadBench™ Database website to ensure its optimal performance.• Support industry benchmarking using RadBench™ data.
Project Approach• Technical support for utility data submittal and conduct analysis of industry data for presentation at ASME Radwaste Workshop• Troubleshooting RadBench™ website issues as they arise• The documentation of needed enhancements to ensure continued optimal operations and also features desired by members
Research Value• Allows utility members to benchmark low level waste performance and supports utility member interaction for sharing additional best practices,
experiences, and technology information (supports Knowledge Transfer.)• Informs EPRI Low Level Waste Research.• Optimized disposal of radioactive waste will ensure that the existing disposal sites can be efficiently utilized to their full capacity.
Global Applicability• The RadBench Database has been recently upgraded with international data entry settings (e.g. units and waste classifications.)
Radioactivity Generation and Control (Source Term Reduction)Effect of Ultra-Low Iron – HWC/OLNC – on Activity Transport
How do current BWR chemistry regimes affect activated corrosion product transport?
FFW Fe in 2000
2002
20042006
FW Fe Median is 0.15 ppb in 2015 vs. ~1 ppb in 2004BWR FW iron concentrations have been reduced to Lower crud burden on core Improve effectiveness of zinc injection
for radiation field reduction
BWR coolant regime transitioned to Low-hydrogen injection with More frequent, lower concentration platinum injections
Current Observations: Elevated Co-60 RW activities Elevated, prolonged particulate releases Cr-51 increasingly observed as activity and dose rate contributor
Radioactivity Generation and Control (Source Term Reduction)Effect of Ultra-Low Iron – HWC/OLNC – on Activity Transport
Develop understanding of ex-core deposit formation processes under current water chemistry control practices with ultra-low FW Fe concentrations
Enhance the knowledge of incorporation and release processes of activated corrosion products into/from ex-core surfaces, i.e. radiation field generation and shutdown/transient particulate releases
Objective1) Review current chemistry practices and data –
(BWR CMA & SRMC) and determine gapsa) Identify bounding criteria of chemistry
conditions and plants matching thoseb) Solicit cooperation of selected plants for
additional data gathering4) Perform at least two subsequent outages
gamma scans at selected plants at all recommended standard radiation field monitoring program points and selected additional locations (if feasible solicit host plant to perform remote isotopic monitoring during at-power operations for a whole cycle)
5) Formulate hypotheses of ex-core deposit formation under current BWR coolant conditions and develop white paper detailing a test plan to verify the hypotheses
ApproachResearch results will provide the basis and understanding to Balance ultra-low feedwater iron
conditions needed to ensure fuel reliability with minimizing radiation field generation in ex-core regions.
Inform future BWR water chemistry guidance
Guide the development radiation field reduction technologies and/or strategies
• Revise the EPRI Groundwater Protection Guidelines for Nuclear Power Plants (3002000546) and the EPRI Soil and Groundwater Remediation Guidelines (1021104.)
Project Approach• Revise Guidelines documents based on recent industry experiences; developments in science, technology, and
regulations; and EPRI research.• Leverage diverse industry Committee of utility members and colleague organizations (e.g. NEI, ANI, INPO.)
Research Value• Supports stakeholder confidence in nuclear power operations and environmental stewardship.• Minimizes impact on decommissioning (e.g. groundwater remediation and associated radwaste generation/costs.)• Consolidated and up-to-date Guidelines documents for efficient knowledge transfer.
Global Applicability• The technical guidance in these Guidelines documents are applicable nuclear power plants around the world.
resource on plant system or component decontamination.
• Develop a graded approach/benefit matrix to guide decontamination strategy selection
Approach•Hold a workshop in 2018 to
•capture past and current global experiences and practices, •explore the industry needs and challenges, and•connect the generations for effective knowledge transfer and retention
•Survey industry - decontamination best practices (2018)•Collate accumulated data sets (2018)•Build a graded approach/benefit matrix (2019 - 2020)•Form a global industry committee to assist EPRI
Value•Results will•enable efficient selection and application of proven and established methods and practices
•save dose, time, and associated costs.
•aid knowledge retention and transfer of decontamination strategies
RCP Before
& After Decon
Decontamination Handbook – published in 1999 Reactor Cavity Decontamination Sourcebook – published 2015
Reactor life extensions renew interest in decontamination including full system decontaminations
New OE and best practices New methods (decontamination and post-decontamination passivation steps)
Changes in radiation field composition require different approaches
Radiation Measurement and Dosimetry: Plant Demonstration of At-Power Gamma-Isotopic Monitoring
Why at-power isotopic characterization? Real-time response to changes – not cycle snap-shots of typical outage measurements Real-time identification of Contributor – ability to evaluate impact and to mitigate proactively Magnitude on impact of radiation field
Ability to identify in near real-time the cause of the radiation field response
Real-Time Isotopic Radiation Field Monitoring at Your Fingertip_
Plant demonstration – Value & Benefits are in the visualization & implementation of gained insights for optimization of ALARA and work planning Targeted source term reduction/mitigation Radiation field control Coolant chemistry regimes
2018 - 2019Select, test & verify equipment functionality
Establish measurement and analysis protocol2018-2020Collect and analyze at-power isotopic monitoring dataCoordinate with plant radiation protection staff to optimize ALARA and work planning
Develop guidance for implementing at-power isotopic monitoringand for realizing value to worker dose reduction
Impact to Effluents and Radwaste from Radionuclides and Chemicals from Non-Design Materials
Objective• Gain a complete
understanding of the radionuclides and chemicals that are generated in nuclear power plant operation from non-design materials of construction and added chemicals.
Project Approach• Identify non-design materials
and chemicals added to nuclear power plant and the radionuclides and chemicals are generated from them.
• Evaluate transport, and potential impacts on operations, personnel dose, effluents and public dose, radioactive waste, and environment.
• Identify already existing solutions for managing any challenges; identify gaps where they exist.
Research Value• Allow the operators to
implement informed strategies to optimize personnel dose, radwaste, and effluents.
• Knowledge transfer tool; add to consolidated reference of chemicals/radionuclides in plant systems/effluents.
Global Applicability• Research will address
materials and chemicals added to international nuclear power plants.
Impact to Effluents and Radwaste from Radionuclides and Chemicals from Non-Design Materials
Examples of Radionuclides and Impacts of from Non-Design Materials and Added Chemicals:– Ag-108m from control rod drives*– Sb-124 and 125 from start-up sources or reactor coolant pump
seals*– Pt-193 from platinum injected in BWRs– Ar-39 from injection of argon for primary-to-secondary (PSL)
detection.– P-32 from sulfides and seawater– Zinc injection impacts on radwaste
Effluent and Radwaste Management and Control Strategies: Effect of a KOH-based pH Program on Radiation Fields, RadioactiveEffluents and Waste in Western PWRs: Needed Qualification Work
Need– 7LiOH is used to control pH in ‘Western-style’ PWRs – 7Li supply chain has been interrupted and may be so again– VVER reactors control pH with KOH – K is more abundant – feasibility study shows KOH is a promising, economical candidate– Identified technical gaps include aspects of radiation safety, waste and effluent generation, dose pathways and does to public
Objective• Identify potential challenges in
radiation field control and effluent and waste handling caused by implementing a KOH-based pH control program in a “Western-style” PWR.
• Identify implications on the modeling of and impact on dose pathways to environment and public and on the dose to the public.
designs and operating practices and identify differences that may challenge control of radiation fields, effluents and waste
• Evaluate impact of additional activation species introduced by KOH and its potential impurities
Value• Evaluation of radiation safety-related
gaps will provide needed information in preparation for a demonstration of KOH use in a “Western-style” PWR
• Results will yield insights into the potential impact on the plant radioisotopes inventory and therefore on radiation field, effluents, and waste that will occur when moving to a KOH-based pH control.
Objective• Evaluate recently developed technologies and methodologies for the reduction of tritium in nuclear power plants
and their wastes and effluents.
Project Approach• Identify new and innovative technologies and methods for tritium removal and reduction of tritium generation.• Evaluate each for their Technology Readiness Level, potential applicability to light water reactor tritium
concentrations, potential costs and resources required, and footprint.• Evaluate most promising technologies for additional analysis, discussions and concept development with the
technology developer, or bench-top testing.
Research Value• Tritium continues to challenge public confidence in nuclear plant operations. • Provide solutions to post-accident generation of liquid radwaste, remediation of contaminated groundwater, and
the disposal of tritiated water at nuclear power plants that do not have a license release pathway.
Global Applicability• Technologies and methods available will be applicable to global nuclear power plant industry.
Guidance for Optimization of Worker Protection: Addressing Radiation Safety and Industrial Safety Concerns
Background/Need• Radiological Safety and Industrial Safety are two key safety
programs at nuclear power plants.• However, protective actions for one may conflict or have
unintended consequences with the other.• Examples may include:
− Hand protection (gloves) for contamination control while still maintaining dexterity/safe grip
− Personal protective equipment for ionizing radiation and O3/NOx.
Project ObjectivesDevelop practical approaches or guidance for addressing radiological and industrial safety concerns such that the overall risk to the worker is minimized.
Example: Balancing heat stress and protective clothing requirements against contamination
End of Plant Life Chemistry Control OptimizationConsideration of Cost Minimization and Recovery
Description & Objectives Recently announced plant shutdowns were relatively unexpected Guidance for preparing for such shutdowns is limited Chemistry control programs could be modified to maximize resources and potentially provide
economic benefit to the operating utility– Mitigation technologies…stop, reduce, continue?
Hydrogen and noble metal injection in BWRs Zinc addition in PWRs
– Dose reduction technologies…continue? Depleted zinc addition in BWRs and PWRs Source term reduction (CRB, valve replacements)
– Steam generators Use of dispersants
– Monitoring and analysis requirements…can we scale back? Equipment considerations
– Sell or move equipment to other sites– “Run to empty” for some systems– Leftover consumables (zinc, resin, septa, chemicals, etc.)
U.S. BWRs in the short term Also plants in Spain, Sweden,
Switzerland, Taiwan Some plants in Japan will not
be restarting Economic conditions are
unknown at this time, so preparation is key to good decision making
End of Plant Life Chemistry Control OptimizationConsideration of Cost Minimization and Recovery
Careful, detailed evaluation of chemistry control programs, systems, monitoring and consumables prior to shutdown can benefit the utility in a number of ways:– Economic recovery– Dose control– Orderly shutdown
Global Applicability
Proposed Duration and Timing: 2018-2019 (18 mo.)Proposed for co-funding with Chemistry and Decommissioning
Research Value:– An “off the shelf” resource to use whenever faced with the need for communications of
Low Dose information is not readily available for members. The availability of the resource should significantly shorten the time needed to prepare communications, and serve to enhance the communications in a consistent and coherent manner with the available science. Use of the resource will enhance a members communications, and facilitate successful completion of projects.
Proposed Duration and Timing: 2018-2019 (24 mo.)Proposed for co-funding with Decommissioning