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© 2016 Electric Power Research Institute, Inc. All rights reserved.

P. TranRadiation Safety & Decommissioning

Program ManagerTuesday, August 30, 2016

Chemistry and Radiation Safety

Technical Advisory Committee

Date: 8/24/2016

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Together…Shaping the Future of Electricity


Chemistry and Radiation Safety Technical Advisory Committee Meeting

Tuesday, August 30 - Room Location: Roosevelt BR - Salon 5 (ML)

Time Topic

8:00 am Radiation Safety Program 2017-2018

Lead

P. Tran, EPRI

D. Cool, EPRI

C. Gregorich, EPRI K. Kim, EPRI

10:00 am Break

10:30 am Radiation Safety Program 2017-2018 (continued)

11:30 am Program Cockpit Updates N. Lynch, EPRI

12:00 pm Lunch



Tuesday, August 30 - Room Location: Roosevelt BR - Salon 5 (ML)

Time Topic

1:00 pm Member Satisfaction Survey

Lead,

1:30 pm EPRI Occupational Health and Safety Update L. Krishen, EPRI

2:00 pm NEI Update

2:30 pm INPO Radiation Protection Update

E. Anderson, NEI

W. Harris, Exelon 3:00 pm Break

3:30 pm Round Table (OE)

4:15 pm Meeting Plus/Delta All

4:30 pm Adjourn

4:30-5:30

pmFinalize APC Presentation Materials

J. Goldstein, Entergy

W. Harris, Exelon

D. Wells, EPRI

P. Tran, EPRI

The Chemistry and Radiation Safety APC will be held Wed. from 8am to Noon, Chamber 2 &4

C. Olexik, EPRI


Phung TranProgram Manager, Radiation Safety

1.650.855.2158, [email protected]


August 29 - 30, 2016

Radiation Safety Program2017-2018 Work Plan

Donald Cool, Technical Executive

Carola Gregorich, Principal Technical Leader

Karen Kim, Sr. Technical Leader

Joel McElrath, Principal Technical Leader

Rich McGrath, Principal Technical Leader



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

Alternate prioritization projects– Fundamental, Low Dose, Decommissioning

Take into account coordination / leveraging with other programs

Portfolio Considerations


2017 – 2018 Radiation Safety Budget

No change to base funding

Supplemental programs enhance R&D scope

TSGs = Technical Strategy Groups

GW = Groundwater

RMST = Radiation Management and Source Term

LLW = Low Level Waste

0.00

1.00

2.00

3.00

4.00

5.00

6.00

2017 2018

Fun

din

g (i

n m

illio

ns)

Year

Radiation Safety Budget (2017 - 2018)

Decommissioning Supplemental TSGs (RMST, GW, LLW)Leveraged Base


2017 – 2018 Radiation Safety Budget and Funding Distribution

Funding of new projects based on completion of multi-year projects

– Cyclic

Stable funding for long term, strategic projects

– Fundamental

– Decommissioning

– Low Dose

Continuing

20%

New Projects

23%

Fundamental

12%

Low Dose

27%

Decommissioning

18%

2017 BASE DISTRIBUTION

Continuing

39%

New Projects

4%

Fundamental

12%

Low Dose

27%

Decommissioning

18%

2018 BASE DISTRIBUTION


Radiation Safety Research Focus Areas

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.

* Not prioritized


Prioritization Results

Radioactivity Generation and Control

(Source Term)

ALARA Strategies and Technologies

Radiation Measurement

and Dosimetry for Workers and

Public

Effluent and Radwaste

Minimization

Radiation Safety

Guidance

Optimization of Industrial

and Radiological

Safety

Mean = 1.67Mean = 1.44 Mean = 2.04Mean = 2.00 Mean = 2.00 Mean = 2.33

70% Responded!


PrioritizationResponses

27 of 39 Respondents

(70%)

Reactor Type

5 BWR(of 7)

14 PWR/PHWR/VVER(of 22)

8 Both(of 10)

US or non-US

15 US(of 23)

12 non-US(of 16)

40 Comments

Responses are well balanced


Recommended 2017-2018 Radiation Safety Portfolio


(Source Term Reduction)

Surface Passivation(2015-2018)

Hydrophobic Coatings

(2016-2017)

Micro-Environment Effect

(2015-2017)

Silver and Antimony (2016-2018)

Optimized Zn(2018)*

Ultra-low Iron in BWRs (2018-

2019)*


Source Term Decision Logic (2017-2019)*

RMT for Surveys (2017)*

Location Tracking (2017-2019)*

Radiation Measurement and Dosimetry

for Workers and Public

Accurate Effluent Public Dose (2015-

2017)

Shielding Factors for Lens of the Eye

(2017-2018)*

At-power Gamma-isotopic Monitoring

(2018-2020)*


Minimization

Impacts to Effluents and Radwaste from Non-Design Basis Materials (2017-

2019)*

Fuel Material Changes on

Radwaste and Corrosion Behavior

(2018-2019)*

Tritium Removal and Reduction Technologies (2018-2019)*

Effect of KOH on Radiation Fields,

Effluents, and Radwaste (2018-

2019)*

Radiation Safety

Guidance

Review of Radiation Safety

Guidelines for Revision (2016-

2018)

PCE Guideline Revision (2017-

2018)*

GW Guideline and Soil and GW Remediation

Guideline Revision(2018-2019)*

Decontamination Sourcebook (2018-

2020)*


and Radiological

Safety

Optimization of Worker Protection

(2018-2019)*

Funded Work Fund with Modification Unfunded * New


Recommended 2017-2018 Radiation Safety Portfolio(Alternate Prioritization Process)

Fundamental: Benchmarking and Trending

Standard Radiation Field Monitoring and

Characterization (SRMC) Program

(ongoing)

RadBench™ (ongoing)

Low Dose Radiation Health

Effects

Scientific Advisory Committee (ongoing)

International Dose Effect Alliance (IDEA)

(ongoing)

Human and Animal Data Analysis for Low

Dose Rate Effects (2017-2019)

Cancer Risk Modeling - Phase 1

(2018-2019)*

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)*


(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.

Unfunded * New


Prioritized Radiation Safety Research Focus Areas


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

BWRs*

* New project




(Source Term)

1 - High Priority

2 - Medium Priority

3 - Low Priority

High Priority

Mean = 1.44

Median = 1

Leveraged

2017 $295k

2018 $310k

Total $605k

Sample Feedback:

“Impacts of increasing chromium as a result of

replacement steam generators.”

“I would give a '1' to both hydrophobic coatings chemistry

strategies for surface passivation”

“The micro-environments project is of most interest”

“ 1. Optimization of Zinc Injection to Maintain Radiation

Field and PWSCC Benefits While Reducing Costs”

Portfolio Recommendations:

Fund continuing projects

Modify and merge micro-environment and

silver/antimony

Fund Zn optimization with PWR TSG

Delay ultra-low iron (possible project in TSG)

Unfunded





(2016-2017)


(2015-2017)


Optimized Zn(2018)*


2019)*

* New projectFunded Work Fund with Modification


Radiation Safety Research Focus Area:


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.


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*

* New project



Sample Feedback:

“Suggest a basis document be created to identifying

the number of AMP-100s or equal a plant needs to

eliminate routine radiation surveys.”

“Decision logic for source term reduction is highest

priority item in this RFA. I would rate the worker

tracking as medium priority.”

“..members feel the decision logic will be very

beneficial. Real time dose data and location tracking

would be less achievable in our plants, so we feel it

is of lower priority.”


Fund decision logic

Added project to investigate feasibility of reducing

survey frequency by using RMT (joint with RMST

TSG)

Delay location tracking workAve. Score 1.44


1 - High Priority

2 - Medium Priority

3 - Low Priority

High Priority

Mean = 1.67

Median = 2

Funded Work Unfunded

Leveraged

2017 $35k

2018 $0k

Total $35k





* New project


ALARA Strategies and Technologies: Decision Logic for Source Term Reduction

Goal – Reducing Uncertainties and Increasing Success Rate_

Radiation fields Result from multi-variate processes,

Are plant and component specific,

Respond differently to changes.

Operating experiences document Plant specific responses

Varying success to same actions

Adverse responses linked to multiple simultaneous changes.

Project Objectives Test the idea of a universally

employable strategic decision logic that considers plant specific aspect,

Kick start development of a programmatic approach to source term reduction and radiation field optimization.

C. Gregorich


ALARA Strategies and Technologies: Decision Logic for Source Term Reduction

Goal – Reducing Uncertainties and Increasing Success Rate_

Work ScopeTask 1: Develop Technical Expert Driven Decision

Logic (2017 - )

Task 2: Feasibility Studies – Real-Life Test Case Scenarios (2018 - ) (Cooperation with sites)

• Sister plant radiation evolution• Response variation to known effective source term

reduction strategies

Value & Benefits Assists EPRI membership in

Plant-specific benefit-driven selection of source term reduction strategies,

Lowering radiation fields, reducing

worker dose and achieving CRE goals,

Reducing costs associated with high

radiation and/or contaminated areas .

Proposed Duration and Timing: 2017-2019 (33 mo.)


Remote Monitoring for Routine Surveys

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

D. Cool & K. Kim


Value for Remote Monitoring

Approach:– Brainstorming during 2016 RMT Workshop– Initial development with RMST TSG– Base and TSG support proposed for 2017

Research Value:– Answer the question of if, and when, remote monitoring can be used to reduce routine

surveys– Improve radiation protection operational efficiency and reduce occupational exposures


Develop basis to reduce routine monitoring, increase efficiency, reduce dose



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*

* New project


Radiation Measurement and Dosimetry for Workers and Public


Sample Feedback:

“(MED/HIGH) - Improved Accuracy and Updating

Methodology in Determining Effluent Dose to

Members of the Public, (HIGH) - Shielding Factors

for Lens of the Eye”

“shielding factors for lens of the eye protective

equipment is of most interest .., although there is

also a growing degree of interest in the use of

gamma-isotopic monitoring.”

“Finish Effluent dose to public We support lens of

the eye work.”


Fund continuing project

Fund Shielding Factors for Lens of the Eye

Delay at power gamma-isotopic

Radiation Measurement and Dosimetry for

Workers and Public

1 - High Priority

2 - Medium Priority

3 - Low Priority

Medium Priority

Mean = 2.00

Median = 2




2017)


(2017-2018)*


(2018-2020)*

* New project

No Leveraged Dollars


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.

D. Cool


Value of Shielding Factors

Research Value:– Provide tools and methodologies for the industry to meet new

regulatory requirements– Consistent approach facilitates acceptance and use– Provide a generic set of factors for protection of the lens of the eye

that could be used in a manner similar to the protection factors found in regulations for respiratory protection.


Develop consistent approach to address Global Issue



Effluent and Radwaste Minimization

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


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

Demonstration EPRI technical report

None

* New project



Funded Work Fund with Modification Unfunded


1 - High Priority

2 - Medium Priority

3 - Low Priority

Medium Priority

Mean = 2.00

Median = 2

Sample Feedback:

“H-3 removal work is complete .. and too expensive

to meet Nuclear Promise…”

“(LOW) - Impacts to Effluents and Radwaste from

Radionuclides and Chemicals Generated from Non-

Design Basis Materials, (HIGH) - Effect of a KOH-

based pH Program on Radiation Fields, Radioactive

Effluents and Waste (MED/HIGH)-Tritium Removal

and Reduction Technologies, (HIGH)-Impact of Fuel

Material Changes on Radwaste Characterization and

Corrosion Product Behavior: Scoping Assessment”


Modify and merge Impacts of Non-Design Materials

with Fuel Material Changes

Delay KOH due to delays in KOH material

qualification

Delay but informally monitor tritium removal

developments

* New project


Minimization


2019)*



(2018-2019)*




2019)*

Leveraged

2017 $60k

2018 $95k

Total $155k


Impact of Materials Changes on Radwaste and Corrosion Products – Fuel material scoping assessment

New materials and chemicals have been added– Impacts not understand

Fuel materials are changing– Possible impacts to fuel performance, waste

classification, radiation fields, and filter performance

Nb-93 activates to Nb-94 (20,000 yr, decay by beta/gamma emission)

Nb-95/Zr-95 are gamma emitters (radiation field concern)

– Impacts most design typesGarde, A.M., ASTM STP 1295

Potential impact on radiation field and radwaste not well understood

D. Wells & K. Kim

Element, % Zircaloy-2 Zircaloy-4 Std. Zirlo Opt. Zirlo M5

Zr balance balance balance balance balance

Sn 1.2-1.7 1.2-1.7 0.8-1.1 0.60-0.79

Fe 0.07-0.20 0.18-0.24 0.09-0.13 0.09-0.13

Cr 0.05-0.15 0.07-0.13

Ni 0.03-0.08 Max. 0.007

O 0.09-0.16 0.09-0.16 0.10-0.15 0.10-0.15 0.090-0.149

C Max. 0.027 Max. 0.027

Nb Max. 0.01 Max. 0.01 0.8-1.2 0.8-1.2 0.8-1.2

Hf Max. 0.01 Max. 0.01

W Max. 0.01 Max. 0.01

U Max. 0.00035 Max. 0.00035Fuel Reliability Guidelines: PWR Fuel Cladding Corrosion and Crud, Revision 1: Volume 2, Guidance. EPRI, Palo Alto, CA: 2014. 3002002795.


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 for co-funding with Chemistry, Radiation Safety, and Fuel Reliability




Radiation Safety Guidance

Development and maintenance of guidelines, guides, and sourcebooks in the areas of – radiation protection,

– source term reduction,

– radiological environmental protection, and

– low level waste management

Technical bases and support of regulatory activities (e.g. BTP, VLLW)Project types Typical deliverables Specific near-term activities

Guideline Development Guidelines Best Practices

Review of Radiation Safety Related Guidelines for Revision PCE Guideline Revision* Revision to GW Guideline and Soil and GW Remediation

Guideline*

Sourcebook Development Best Practices Decontamination Sourcebook*

* New project





1 - High Priority

2 - Medium Priority

3 - Low Priority

Medium Priority

Mean = 2.04

Median = 2

Sample Feedback:

“We support revisions to the Personal Contamination

guidelines to correct for NRC comments and update

the low level waste characterization Guidelines only.

Do not fund GP and soil remediation. Do not fund

the Decon Source book…”

“..rated this as high due the cross reference to other

guidance documents (like INPO 05-008 -

Radiological Protection at NPPs)…”


Fund continuing project

Fund PCE GL revision

Delay GW Guideline and Soil and GW Remediation

GL – gap analysis indicates no changes to

recommendations, minor edits only

Delay Decontamination Sourcebook


* New project

Radiation Safety

Guidance



2018)


2018)*




2020)*


PCE Guidelines Update

Background:– The EPRI Guidelines for Industry Response to Personal

Contaminations (Product 1011740) as last revised in November, 2005.

– The Guidelines are a key piece of implementing an effective and protective radiation protection program.

– Requests to assess action levels, measurement locations, further actions for facial and wound contamination, communication of risk.

– NRC concern that the EPRI guidelines might have mischaracterized NRC requirements1.

– A Delivering the Nuclear Promise Efficiency Bulletin2 has resulted in additional focus on use of the guidelines.

D. Cool

1 ADAMS ML15187A3882 NEI Efficiency Bulletin 16-03, Align Personnel Contamination

Event Response to Industry Guidance, February 2, 2016


Value of PCE Guidelines Update

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.


Program guidance Technical Reports Best Practices Workshop

Guidance for Optimization of Worker Protection: Addressing Radiation Safety and Industrial Safety Concerns*

Advanced technologies Plant Demonstrations None

* New project


Optimization of Industrial and Radiological Safety

Unfunded

Optimization of Industrial and Radiological

Safety

1 - High Priority

2 - Medium Priority

3 - Low Priority

Low Priority

Mean = 2.2

Median = 2

Sample Feedback:

“Relative to the other 5 - I rate this as a medium - but

still important - but everything can't be a one.”

“This can be innovative research with the most

immediate worker benefit/impact. The aging work

force and economic pressures on the industry make

this effort very timely.”


Delay optimization guidance but continue to work

with EPRI’s Occupational Health and Safety group to

identify collaborative opportunities



and Radiological

Safety


(2018-2019)*

* New project


Research Focus Areas Not Included in Prioritization

Fundamental: Benchmarking and TrendingLow Dose Radiation Health Effects

Decommissioning Technology and Strategies



Benchmarking and Trending (Fundamental)

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


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

RadBench™ RadBench™ website RadBench™ Maintenance

C. Gregorich

K. Kim



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.


Low dose cancer risks Peer reviewed journal articles EPRI Key Issue Summary

Analysis of animal and human data for dose rate effects*

Cancer Risk Modeling

Emerging Issues / Non-cancer effects

EPRI Technical reports Peer reviewed journal articles EPRI Publication Summary

Risk Communication Tools EPRI Technical reports Best Practices in Radiation Risk Communication:

Decommissioning

Facilitate international collaboration

Workshops/meetings Executive Briefing of Research and Issues

International Dose Effect Alliance (IDEA)* Low Dose Scientific Advisory Committee (SAC)*

* Continuing project

D. Cool


Why is Low Dose Risk Important?

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


Scientific Advisory Committee

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


Low Dose RFA Objectives

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

issues


Low Dose Portfolio Proposal 2017-2018Low Dose Cancer

RisksEmerging Issues

Non-Cancer RisksGlobal Research

CoordinationCommunication

Tools

Human and Animal Data Analysis

Low Dose Cancer Risk Modeling

Monitor Emerging Issues

Scientific Advisory Committee

International Dose Effect Alliance

Technical Issue Summaries

Communicationrelated toDecommissioning



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.


Research Studies• EPRI Reports• Publications in peer-reviewed journals

Scientific Committees• Review latest science and trends• Consider Experience, Ethics, Prudence

Regulatory Agencies• Review Recommendations• Procedural and Public Processes

Recommendations

Standards

Findings


IDEA Vision

Mission

• Facilitate information exchange and collaboration on low dose radiation research programs.

• Identify issues, areas of synergy, and opportunities for additional research.

• Foster integrated, outcome oriented approaches to resolve low dose risk.

Goals

• Develop connections between programs conducting low dose radiation research.

• Facilitate discussions across countries and regions.

• Organize collaborative forums for exchange of research priorities, strategies, programs, and results.

Phases

• Phase 1:• Initiate discussions,

identify organizations.• Organize a first

workshop to explore current programs and the possibilities for collaborative activity

Vision: International platform for information exchange, discussion, cooperation, and collaboration in low dose radiation research


IDEA Vision

Mission




Goals




Phases






IDEA Vision

Mission




Goals




Phases






IDEA Vision

Mission




Goals




Phases


identify organizations.

• Organize a first workshop to explore current programs and the possibilities for collaborative activity



IDEA Value

– Leverage external research results to enhance and accelerate EPRI’s research program - more bang for the buck

– Global coordination of research to target and solve most important technical gaps

– Information flow to utilities on key issues and developments

Proposed Duration and Timing: ongoing

Leverage global resources to enhance, accelerate, and target research results


Low Dose Cancer Risk Modeling

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

epidemiology has yet to be created

Radiation Cell Tissue Person


Approach to Low Dose Modeling

Develop Model Framework– Logical series of steps from cause to effect– First of its kind application to radiation exposure

Develop steps of model– Build on EPRI work to outline existing body of

knowledge– Possible key step in model – cellular and

intercellular microenvironments and communication– Synthesize available literature to identify key

markers for further evaluation


Value of Low Dose Modeling

Reduce UncertaintyConnect cause and effectsExplain relationshipsRisk Inform approaches - PRA for RPCredible input to regulations, guidance,

programs, communications


Reduced uncertainty risk informed radiation protection



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.


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

* New project

R. Reid & R. McGrath


Why Focus on Reactor Internals Segmentation

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.

Segmentation Plan for Reactor Internals



Development of US Department of Energy D&D Technologies for Commercial Power Plant Decommissioning (2016-2018)

More than 20 years of R&D experience available in the US DOE Environmental Management program– Field-proven technologies in all areas

related to facility decontamination and dismantlement in DOE facilities

– Potential for cost savings Project objectives

– Collaborative demonstration of promising field-proven technologies

– Collaborative R&D to develop new technologies

Integrated Remote Platform for Application ofFixatives on Vertical Surfaces at ORNL

Assessment of US Department of Energy D&D Technologies for Commercial Power Plant Decommissioning, 3002005411, 2015

R. McGrath


Project Approach and Research Value Currently collaborating with DOE to identify

technology(s) of interest for demonstration.

Proposed 2017 scope:

– Develop a DOE technology(s) to a field-ready state OR

– Conduct a field demonstration of a field-ready DOE technology not previously demonstrated

Proposed 2018 scope:

– Field demonstration of technology OR

– Conduct a field demonstration of a different field-ready DOE technology


Value: Reduce the overall cost of decommissioning by deploying advanced technologies for

decontamination and dismantlement. Potential cost savings of $300,000+ per day. _


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

R. Reid

Proposed Duration and Timing: ongoing


Guidance for Mothballing a Nuclear Power Plant (2017-2018)Motivation

Economic conditions have forced the early shut down of several plants recently and others are at risk The current practice is permanent plant shut

down, leading to decommissioning An alternative is long term storage until economic

conditions improve (nominally 10 years)– Common practice for fossil plants

This supports the energy strategy in most countries that will rely on nuclear power over the long term to reduce greenhouse gas emissions

R. Reid


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.)


Other Radiation Safety Projects Outside of Base

Radiation Management and Source Term Technical Strategy GroupLow Level Waste Technical Strategy Group

Groundwater Technical Strategy GroupFlexible Operations

Delivering the Nuclear PromiseDecommissioning Supplemental Program


Other Radiation Safety Projects Outside of Base

Radiation Management and Source Term TSG

Low Level Waste TSG Groundwater TSG Flexible Operations Delivering the Nuclear

Promise Decommissioning

Supplemental Program

0.00

1.00

2.00

3.00

4.00

5.00

6.00

2017 2018

Fun

din

g (i

n m

illio

ns)

Year

Radiation Safety Budget (2017 - 2018)

Decommissioning Supplemental TSGs (RMST, GW, LLW)Leveraged Base TSG = Technical Strategy Group


RMST TSG R&D (2016-2017)

Review of state of the art radiation field modeling (3002008176 to be published 2016)

PWR Shutdown Release – 2016 Summary (3002008177 to be published 2016)

Influence of RCP practices during shutdown on outage radiation field (3002008183 to be published 2016)

Ex-core isotopic monitoring following zinc injection start (joint w/ PWR Chemistry TSG)

Use of RMT to reduce survey frequency –feasibility study


LLW TSG R&D (2016-2017)

Low Level Waste Related Knowledge Transfer Management of Hard-to-Detect

Radionuclides in Liquid Radwaste/EffluentsLow Level Waste Sampling and

Characterization Guidance


GW TSG R&D (2016-2017)

Groundwater Knowledge Transfer

Groundwater Site Conceptual Model Template & Sourcebook


Impacts to Radiation Safety from Cycling Power (Flexible Operations)

• Material corrosion behavior

• Primary chemistry• Fuel crud behavior

Corrosion Product Behavior

• Inventory and mobility of activated corrosion products radiation field generation

Radiological Source Term (funded) • Increased liquid

radwaste volumes solid radwaste

• Release of effluents to environment

Effluents and Radwaste (funded)

• Increased monitoring

• Increased exposure

RP and Occupational Exposure (unfunded)

Cycling reactor power may introduce changes that could impact radiation safety programs


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, Byron, Quad Cities) Hot spots Isotopic data Plant radiation field monitoring

– Review global experiences – Leverage ongoing work from BWR and PWR chemistry and

Fuel Reliability

C. Gregorich


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

K. Kim


Optimization of the Frequency of Source Checks of Portable Radiation Survey Instruments Objectives:

– Determine if a technical basis can be developed to optimize the frequency of portable radiation survey meter source checks.

– This technical basis will be based on review of: Existing standards / guidance Current practices - meter testing,

maintenance, and calibration Operational performance history

and maintenance logs.

Project Tasks:– Review regulations and guidance

documents.– Develop data collection protocol– Collect utility data An ion chamber survey meter Provide a summary report of the

results of the data collection.– Provide recommendations and

develop technical basis to support the optimized frequency of source checks.

Need Help

K. Kim


Decommissioning Supplemental R&D Projects (2016 – 2017+) In addition to Base Funded Research

I. Planning and Regulatory Guidance for establishing safe storage

II. Dismantlement Review of US Department of Energy (DOE)

D&D technologies for commercial power plant decommissioning

Review and assessment of robotic systems and process automation for commercial power plant decommissioning

III. Waste Management Characterization of long-lived, hard-to-measure

activation products in irradiated metals

Decommissioning waste management tracking software technical specification (eliminate the mystery drum scenario)

Management of hazardous waste

IV. Site Characterization and Release

Review of geostatistical approaches to characterization of subsurface contamination

Groundwater monitoring during decommissioning

Use of CZT for site characterization and ALARA planning


Radioactivity Generation and Control (Source

Term Reduction) Surface Passivation

(2015-2018)

Hydrophobic Coatings(2016-2017)

Micro-Environment Effect(2015-2017)


Optimized Zn(2018)*

PWR Shutdown Releases

RCP Practices during Shutdown

Impact of Flex Ops on Source Term


Source Term Decision Logic

(2017-2019)*


Review of Radiation Field Modeling



Accurate Effluent Public Dose (2015-2017)

Shielding Factors for Lens of the Eye (2017-2018)*

Ex-core Isotopic Monitoring Following Zn

Injection

HTD Radionuclides in Liquid Radwaste and

Effluents

Optimization of Source Checks for Portable

Instruments


Minimization

Impacts to Effluents and Radwaste from Non-

Design Basis Materials (2017-2019)*

Fuel Material Changes on Radwaste and Corrosion Behavior (2018-2019)*

LLW Knowledge Transfer Database

GW Knowledge Transfer Database

Lesson Learned and Observations from GW

Assessments

Impact of Flex Ops on Effluents and Radwaste

Radiation Safety

Guidance

Review of Radiation Safety Guidelines for Revision (2016-2018)

PCE Guideline Revision (2017-2018)*

LLW Sampling and Characterization

Guideline Revision

GW Site Conceptual Model Template and

Sourcebook

Funded Work Fund with Modification * New TSG Funded Other Funded

2017-2018 Radiation Safety and Decommissioning PortfolioIncluding TSG and Non-Radiation Safety Program Funded Work


2017-2018 Radiation Safety and Decommissioning PortfolioIncluding TSG and Non-Radiation Safety Program Funded Work


Standard Radiation Field Monitoring and Characterization (SRMC)

Program(ongoing)



Effects


International Dose Effect Alliance (IDEA) (ongoing)

Human and Animal Data Analysis for Low Dose Rate Effects

(2017-2019)

Cancer Risk Modeling - Phase 1(2018-2019)*


Strategies

System Automation for Reactor Internals Segmentation

(2017-2019)

DOE Technology Development (2017-2018)

Decommissioning Experience Wiki (ongoing)

Guidance for Mothballing(2017-2019)*

Decommissioning Supplemental

Guidance for Safe Storage

Review of DOE Technologies

Review of Robotic and Automation Technologies

Characterization of HTM Activation Products in Irradiated Metals

Decommissioning Waste Tracking Software Specifications

Management of Hazardous Waste

Geostatistical Approaches to Site Characterization

GW Monitoring During Decommissioning

Use of CZT for Site Characterization

Funded Work Supplemental Funding * New


Recommended 2017-2018 Radiation Safety Portfolio





(2016-2017)


(2015-2017)


Optimized Zn(2018)*


2019)*








2017)


(2017-2018)*


(2018-2020)*


Minimization


2019)*



(2018-2019)*




2019)*

Radiation Safety

Guidance



2018)


2018)*




2020)*


and Radiological

Safety


(2018-2019)*

Funded Work Fund with Modification * New


Recommended 2017-2018 Radiation Safety Portfolio(Alternate Prioritization Process)


Standard Radiation Field Monitoring and

Characterization (SRMC) Program

(ongoing)



Effects



(ongoing)

Human and Animal Data Analysis for Low

Dose Rate Effects (2017-2019)

Cancer Risk Modeling - Phase 1

(2018-2019)*


(2018-2019)*


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.

* New


Together…Shaping the Future of Electricity


Chemistry and Radiation Safety Department Contacts

.

Name Email PhoneSam Choi [email protected] +1 650-855-8747Donald Cool [email protected] +1 704-595-2541Lisa Edwards [email protected] +1 469-586-7468Paul Frattini [email protected] +1 650-855-2027Keith Fruzzetti [email protected] +1 650-855-2211Susan Garcia [email protected] +1 650-855-2239Carola Gregorich [email protected] +1 650-855-8917Karen Kim [email protected] +1 650-855-2190Nicole Lynch [email protected] +1 650-855-2060Joel McElrath [email protected] +1 650-714-4557Richard McGrath [email protected] +1 401-258-9093Phung Tran [email protected] +1 650-855-2158Daniel Wells [email protected] +1 650-855-8630
















2017+ Scope Changes and New Project


Merging Micro-Environment and Silver/Antimony Projects

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 regions (RHR, clean-up, heat exchangers)

Current radiation field challenges make a merge a natural fit– High Ag/Sb contribution in low temperature regions

with unclear Zn influence

C. Gregorich

Better Together


Ag/Sb/Zn – Low Temperature Speciation - Scope

2016– Finalize OE review of micro-environments report– Review state-of art knowledge on silver and antimony speciation under LWR

conditions– Develop experimental program to investigate speciation and surface

interaction of silver, antimony, and zinc 2017

– Start experimental studies 2018

– Finalize experimental studies and report findings

Value – Builds Foundation for Modeling and Developing Mitigation Technologies__


Updated Evaluation of the Effect of Zinc

Background:– EPRI published 1021111, “PWR Zinc Application: Data Analysis

and Evaluation of Primary Chemistry Responses” in 2010– Since 2009, 30 additional PWRs have started zinc injection. – The project will evaluate the new experiences along with changes in

practices such as: Optimized injection programs Varying experience with end-of-cycle injection termination

Purpose:– The results of this project will refine the industries’ understanding of how

zinc affects primary system chemistry, and will allow optimization of zinc programs to achieve maximum benefit with minimal risk.

J. McElrath


Updated Evaluation of the Effect of Zinc

Research Value:This project will provide utilities with information to better optimize the zinc injection regime and to better predict plant behavior when implementing and continuing zinc injection (i.e., both long and short term), including: – Estimating impact upon radiation fields– Estimating impact upon PWSCC mitigation– Assess concerns such as release of nickel, increased radiocobalt

concentrations, shutdown cobalt releases, etc. – Assess potential causes for dose rates reduction outliers



Continuing Project Slides



Continuing Projects


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

C. Gregorich


Project Approach - Progress Phase 1 – Review State-of-the-Art Knowledge Phase 2 – Test most promising technologies – in progress Phase 3 – Develop scale-up protocols and validate Phase 4 – Development of plant demonstration criteria

2015 2016 2017 2018Phase 1

Phase 2 Phase 4Phase 3

Radioactivity Generation and Control (Source Term Reduction)Chemistry Strategies for Surface Passivation

Collaboration with Materials Aging Institute



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

validation.

Objective: Assess hydrophobic coatings effectiveness

and durability Evaluate formation/release of species

detrimental to asset protection and fuel reliability

Develop criteria of performance acceptance

Value: Assist plants in coatings selection Improve contamination control –

fewer PCEs and lower dose Saves cost – reduces qualification testing decontamination and

contamination control efforts

Particulate Surface Contamination Causes Radiation Fields & PCE’s, i.e. Worker Dose

2016

2017


Hydrophobic Coatings - ProgressReview of current use in nuclear and other industries in progressSurvey questionnaire has been send to members

– Responses to-date: 24 responses – 13 utilities (2 non-US) – 18 sites 3 utilities – 6 sites – are using/testing hydrophobic coatings Applications – coating of stainless steel surfaces

– 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


Hydrophobic Coatings – Next StepsFinalize

– 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

lifetime Lifetime of hydrophobic effectiveness

WebCastWhite Paper4th Qtr 2016

Final Report2017



Radioactivity Generation and Control (Source Term Reduction)Impact of Micro-Environment on Radiation Fields

Nee

d Radiation fields are: controlled by local (system) specific

physicochemical conditions impacted by intended and unintended

operational changes

Obj

ectiv

e

Assess impact of chemistry program changes on local radiation fields

Identify local radiation field response variations to the same change

• Survey and evaluate literature on colloid formation under LWR conditions.

• Survey global industry data to identify situations and collate experiences

Phase 1in progressTR in 2016

Experimental program to investigate under specified local conditions:• Effect of radiation on corrosion

product deposition• Colloid formation, transport, and

deposition behavior

Phase 2in planning2016-2017

Expands fundamental knowledge of radiation field generation in multivariate primary coolant systems responding to implemented chemistry mitigation

strategies for asset protection, radiation field and source term reduction

C. Gregorich



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.

C. Gregorich



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


Ag/Sb/Zn – Low Temperature Speciation - Scope

2016– Finalize OE review of micro-environments report– Review state-of art knowledge on silver and antimony speciation under LWR

conditions– Develop experimental program to investigate speciation and surface

interaction of silver, antimony, and zinc 2017

– Start experimental studies 2018

– Report findings


Radiation Safety Guides

Continuing Projects


Review of Radiation Safety Guidelines for RevisionProgram: Radiation Safety

Research Focus Area:


Project Name: Review of EPRI Radiation Safety Guidelines for Revision

Portfolio Years: 2016-2018 (Continuing)

Anticipated Start Date:

05/2016

Anticipated Duration:

30 months

K. Kim


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.

Objective

• Review Groundwater Guidelines (2016), Radiation Protection Guidelines (2017), and Low Level Waste Guidelines (2018).

• 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

Applicability


Radiation Measurements and Dosimetry for Workers and Public

Continuing Projects


Accurate Off-Site/Public Dose CalculationProgram: Radiation Safety


Accurate Dose

Project Name: Improved Accuracy and Updating Methodology in Determining Effluent Dose to Members of the Public

Portfolio Years: 2015-2017 (Continuing)


02/2015


30 months

K. Kim


Accurate Off-Site/Public Dose Calculation

Objective

• 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.


Accurate Off-Site/Public Dose Calculation

2016-2017 Planned Review of Site-Specific Dose Calculation Practices– Review how nuclear power plants incorporate site-specific

information and data into public dose calculations– Assess how site-specific data is used within the current regulatory

framework.– Provide guidance on how use of site-specific data can be enhanced

within the current regulatory framework.– Identify areas where regulations/regulatory guides can be

enhanced to facilitate or allow the use of more site-specific information/data to improve accuracy.


Benchmarking and Trending (Fundamentals)

Continuing Projects


Radiation Safety Benchmarking and Trending (Fundamental): Standard Radiation Field Monitoring & Characterization (SRMC)

Objective:– Establish standard practices for radiation field

monitoring & characterization for all major plant designs (PWR, BWR, VVER, CANDU)

– Collect, house, and make accessible radiation field data

Scope:– Curate data to support cause and effect analysis– Organize information and manage data– Assist plants in implementing the SRMC programs

Value/Benefit:– Access to reliable and validated plant radiation field data taken

following a standardized protocol is crucial for the successful – Execution of utility benchmarking, plant support, plant assessments,

and EPRI research

Monitoring Data are Key to Preserving the Past and Present and to Improve the Future_

C. Gregorich

Proposed Duration and Timing: ongoing)


RadBenchTM MaintenanceProgram: Radiation Safety


Benchmarking and Trending (Fundamental)

Project Name: RadBenchTM Maintenance

Portfolio Years: Ongoing


Ongoing


Ongoing

K. Kim


RadBenchTM MaintenanceObjective

• 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.)


Unfunded Project Slides


Integration of Real Time Dose Data with Location Tracking for Improved Dose Optimization and Dose Estimates

Background/Need In order to optimize worker dose, you need to understand

where workers are getting the majority of their exposure. Tracking by task is improving but the task categories can still be

quite large, spanning multiple tasks and locations. Location tracking technologies coupled with dose tracking can

provide a powerful means of dissecting how dose is accrued so that target dose reduction technique can be applied.

Project Objectives Assess feasibility of combining location tracking technologies

with access control and dosimetry to more effectively track dose for work groups.

Reference: Evaluating Indoor Location Tracking Systems in a Nuclear Facility: Experimentation with Different Techniques in an Industrial Environment. 2013. 3002000268.

Example of previous location tracking technology test with EDF

P. Tran


Integration of Real Time Dose Data with Location Tracking for Improved Dose Optimization and Dose Estimates

Work ScopePhase 1: Feasibility Study

• Identify most promising tracking technology for demonstration

• Determine options for linking with access control or dosimetry software

• Identify host site, job to be tracked, and work area

Phase 2: Pilot Demonstration

• Work with site and vendor to create the appropriate database linkages

• Work with site to conduct pilot study

• Analyze location and dose data

Benefits• Improved ALARA planning

• Enhanced job coverage

• Assist with dose and event reconstruction

• Identify potential equipment issues if abnormal radiation fields are detected

• Track waste and radioactive materials

• Track assets

Proposed Duration and Timing

• 2017-2019 (30 mo.)


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

(shutdown releases, surface activities, particulates)

S. Garcia


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

Value/Benefit



Revision of EPRI Groundwater GuidelinesProgram: Radiation Safety



Project Name: Revision of the EPRI Groundwater Protection Guidelines and EPRI Soil and Groundwater Remediation Guidelines

Portfolio Years: 2018-2019 (New)


03/2018


24 months

K. Kim


Revision of EPRI Groundwater GuidelinesObjective

• 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.


Revision of EPRI Groundwater Guidelines Revision Items for Consideration:

– Enhance guidance for risk assessment and mitigation Both for Systems, Structures Components (SSCs)

and Work Practices (WPs) Especially in the area of risk mitigation (i.e. how to

detect/prevent leaks and spills.) Enhance EPRI Priority Index based on plant

experiences.– Enhance guidance on groundwater monitoring and

remediation optimization How to “close” remediation projects How to optimize long term groundwater monitoring

networks.– Incorporate results of 2010-2016 EPRI research

related to groundwater protection and remediation.Proposed Duration and Timing: 2018-2019 (24 mo.)


Radiation Safety Guidance: Decontamination Sourcebook

Objective• Create a Go-To

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

C. Gregorich



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

C. Gregorich


Radiation Measurement and Dosimetry: Plant Demonstration of At-Power Gamma-Isotopic Monitoring

Objective:Demonstrate feasibility, value, and benefit of at-power gamma-isotopic monitoring

2018Solicit candidate plantsSelect measurement locations

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

Program: Radiation Safety/Chemistry


Radioactivity Generation and Control/Source Term

Project Name: Impacts to Effluents and Radwaste from Radionuclides and Chemicals Generated from Non-Design Materials

Portfolio Years: 2017-2019


03/2017


30 months

K. Kim



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.



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

*Already addressed in another proposed project.


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.

Approach• Obtain and evaluate a robust set of

VVER operating experiences • Review additive, consumables,

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.

C. Gregorich



Tritium Reduction and RemovalProgram: Radiation Safety

ResearchFocus Area:

Radioactivity Generation and Control/Source Term

Project Name: Tritium Removal and Reduction Technologies

PortfolioYears:

2018-2019


03/2018


24 months

K. Kim


Tritium Reduction and Removal

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

P. Tran


Guidance for Optimization of Worker Protection: Addressing Radiation Safety and Industrial Safety Concerns

Work Scope1. Form working group of industrial safety and

radiation safety experts to identify top concerns that impact both groups.

2. Develop systematic approach for risk recognition of prioritized set of hazards

3. Develop matrix for determining monitoring or mitigation techniques that address aspects from both programs.

Benefits• An industry guide that balances considerations

from both programs will assist sites in protecting workers against the total risk.

• Globally applicable.

Reference: Guidelines for the Optimization of Protective Clothing: Heat Stress and Skin Contamination Protection, 2003. 1002822



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.)

system shutting down…

S. Garcia


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


Best Practices in Communication: Decommissioning

Background:– Low Dose information needs to be conveyed accurately and effectively to

support communications both within a Utility and with members of the public.

– Many questions have been seen in the decommissioning programs related to the activities, doses, and effects of radiation as part of the effort.

– Currently, there is no “off the shelf” information resource to support development of programs and communications.

Purpose:– Create a resource handbook for RPM's to use when faced with communicating about

radiation risk in decommissioning by applying the best information on low dose to best practices in communication and industry experience.


Best Practices in Communication: 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