Nuclear. Advanced Nuclear Technology. Chemistry, Low-Level Waste and Radiation Management. Equipment Reliability. Fuel Reliability

Transcription

1 Nuclear Developing safe, reliable, economical, and environmentally responsible technologies that enable the long-term operation of existing nuclear plants and the deployment of advanced nuclear power plants Advanced Nuclear Technology Chemistry, Low-Level Waste and Radiation Management Equipment Reliability Fuel Reliability Instrumentation and Control Long-Term Operations Materials Degradation/Aging Nondestructive Evaluation and Material Characterization Risk and Safety Management Used Fuel and High-Level Waste Management

2 Advanced Nuclear Technology Incorporate plant operating experience and research results into tools and guidance that increase confidence and reduce risks associated with deploying new nuclear power plants. Program Advanced Nuclear Technology

3 Advanced Nuclear Technology Program Description Program Overview New nuclear power plants incorporating advanced light water reactor (ALWR) technology must overcome a number of regulatory, economic, technical, and social challenges prior to licensing, construction, and successful startup. Many of these challenges can be addressed through application of focused Electric Power Research Institute (EPRI) technical products and targeted deployment tools that minimize deployment risks. The EPRI Advanced Nuclear Technology (ANT) Program complements and helps accelerate industry activities aimed at enabling and building confidence in new nuclear plant deployment through coordinated work on cross-cutting issues. By building upon past industry operating experience and previous research and development (R&D) results, new nuclear plants can realize multiple benefits. These benefits include improved designs for long-term operation, implementation of optimized fabrication and construction practices, and more effective overall deployment of an inherently high-risk project. Research Value Research results from the ANT Program increase confidence and reduce risks associated with developing nextgeneration nuclear plant designs by incorporating current plant operating experience and results from focused research and development. The research addresses the issues that could impact the ability to license, construct, start up, and efficiently operate advanced light water reactors worldwide. Advanced Nuclear Technology participants gain access to the following: Materials Management Matrices for advanced nuclear plant designs that can serve as living documents for managing life-cycle material issues. New Plant Deployment Program Model, which enables users to systematically analyze various licensing, technical, and plant deployment issues, thereby improving the decision-making process. Equipment reliability knowledge and tools that can be incorporated into new plant designs to increase the potential for meeting business goals related to such issues as plant availability and capacity factors. Refined methodologies for applying risk-informed pre-service and in-service inspection techniques to advanced nuclear plant designs. Research supporting design and demonstration of next-generation nuclear plants, including hightemperature gas reactors for process heat, hydrogen production, and cogeneration applications. The Advanced Nuclear Technology Program heavily engages the utility and vendor communities to collaboratively identify and overcome the technical challenges confronting new plant deployment. The Program leverages EPRI expertise in various disciplines to resolve common issues. The ANT Program focuses on four core elements: Facilitating standardization across the new fleet Nuclear plant developers around the world are working to ensure standardization is factored into all aspects of new project development. However, while the designs may be standardized, many of the supporting systems will not be, including startup testing, balance-of-plant components, equipment reliability programs, operational procedures, and configuration management procedures. Transferring technology to new plant designs Lessons learned from existing plants and from EPRI s 30+ years of research and development results are being incorporated into new plant designs to drive overall improved performance. Technology advances and lessons learned in materials, chemistry, equipment reliability, nondestructive evaluation (NDE), and fuel performance are

4 being implemented into new plant designs. EPRI will continue reviewing available information with subject matter experts, designers, and utility representatives to define and prioritize requirements, guidelines, and assessments. Ensuring top plant performance from start of operations Nuclear plant performance is a balancing act of equipment selection, material selection, design, operation, maintenance, management, and many other factors. Current financial models for evaluating new nuclear power plants are based on availability factors reflecting the fleet of existing nuclear plants. EPRI s ANT Program provides guidance allowing utilities to maintain high availability factors from new plant startup. Reducing the overall deployment risk and uncertainty Constructing, starting up, and working through initial operations of new nuclear power plants present many large, first-of-a-kind challenges. These challenges establish a deployment risk and uncertainty that affects the ability of utilities to get plants sited, approved, financed, and licensed. The ANT Program will provide research to decrease deployment risk. Accomplishments EPRI s ANT Program helps accelerate industry activities aimed at enabling and building confidence in new nuclear plant deployment. Recent accomplishments include the following: Secured membership from 21 U.S. and international utilities and critical nuclear industry vendors. Completed materials management matrices for four of the six advanced nuclear designs: Westinghouse AP1000, GE-Hitachi ESBWR and ABWR, and Toshiba ABWR. These tools assist industry in identifying and considering materials issues and mitigation and management opportunities through design, component fabrication, plant construction, and initial operations and maintenance. Evaluated EPRI's Fuel Reliability Guidelines in the context of their applicability to new plant designs. Determined that utilities should apply the recommendations in nearly identical fashion, potentially with some unique considerations for each design. Benchmarked three companies to investigate the methods used to perform tests and inspections on construction modules. Benchmarking results will help the nuclear industry define and deploy best practices as use of modules increases for new plant construction. Summarized industry efforts to capture equipment reliability lessons learned during the design phase of a new plant project. The report compiles non-mandatory recommendations that reflect industry best practices. Identified critical welding and fabrication attributes for specific materials, assessed their effects on potential degradation mechanisms, and identified welding and fabrication process enhancements that can improve long-term asset management of new nuclear plant components. Initiated the following: risk management projects focused in critical areas such as proactive materials degradation management, a change to the American Society of Mechanical Engineers (ASME) code to assist in materials performance, and industry leadership on the seismic source characterization database for nuclear facilities. Current Year Activities Advanced Nuclear Technology Program research and development for 2011 will continue its focus on proactive, risk mitigation/management projects for new plants, while expanding the program scope to include construction and startup activities. Specific efforts will include the following: Complete Materials Management Matrices for all six of the new plant designs, and address common issues identified from various projects Continue ASME code case development and technical justification to allow for fitness-for-purpose under ASME Section III for Pre-Service Inspection (PSI) Advanced Nuclear Technology - Program p. 2

5 Evaluate the applicability of EPRI's Water Chemistry Guidelines to each of the new plant designs Continue expanding international participation to increase collaboration with those utilities and vendors currently constructing new nuclear plants worldwide Selected ANT program activities may be conducted in whole or in part in accordance with Title 10, Code of Federal Regulations, Part 50, (10CFR50), Appendix B, and may invoke 10CFR21 at the discretion of ANT member utilities or EPRI, when such action is deemed appropriate. Estimated 2011 Program Funding $6.5 million Program Manager Tom Mulford, , Summary of Projects Project Number Project Title Description P P P P New Nuclear Plant Materials (supplemental) New Nuclear Plant Reliability (supplemental) New Nuclear Plant NDE (supplemental) Security and Seismic (supplemental) Materials management matrices will be produced for each of the advanced light water reactor designs, including ESBWR (completed), AP1000 (completed), ABWR (completed), EPR, APWR, and APR1400. These matrices provide critical materials-related information for each of the components in the nuclear steam supply system and become living documents for managing life-cycle material issues. This project also identifies best practices for welding plant components and for fabricating new plants. EPRI has a substantial portfolio of equipment reliability knowledge that has been effectively deployed across much of the current industry. This project helps deploy existing equipment reliability tools into new plant designs to support high performance and increase the potential for meeting business goals. EPRI is testing and refining a risk-informed in-service inspection methodology for advanced plants. The goal is to develop a single preservice/in-service inspection program for each design (not sitespecific) or provide guidance where there may be site-specific requirements. EPRI also is working with ASME to provide the technical basis to accept benign welding flaws by structural analysis. This project will establish and operate the ultrasonic (UT) examination qualification programs necessary to assure accurate, reliable construction inspections of primary pressure boundary components and welds. EPRI is updating a seismic source characterization model for the Central and Eastern United States (CEUS) that will facilitate new plant siting and respond to regulatory concerns. An updated generic CEUS seismic source characterization model will benefit those companies pursuing new nuclear plant development and those nuclear power plant owners that must respond to issues resulting from Nuclear Regulatory Commission (NRC) Generic Issue 199 (GI- 199). Advanced Nuclear Technology - Program p. 3

6 Project Number Project Title Description P P Achieving Virtual Power Plant Configuration Management (supplemental) Advanced Nuclear Plant Research (base) EPRI is developing a Standard Configuration Management Reference Model and Implementing Guideline to provide a common framework to help manage an automated, integrated, and interoperable configuration management program in a consistent and connected way. The model will be an XML toolkit consisting of configuration management relationship taxonomy, supporting schemas, and supporting Design and Licensing Basis Rule Set. The Implementing Guideline will be a best practices document providing how to details for the use and implementation of the Standard Configuration Management Reference Model. This project supports the development of advanced nuclear plants, including small modular reactor designs and high-temperature gas reactors New Nuclear Plant Materials (supplemental) (066891) Material degradation issues in new nuclear power plants must be actively managed to minimize operational impacts. Increased awareness of materials issues related to advanced light water reactors can limit plant deployment risk and enable the incorporation of lessons learned and materials research advances from the existing fleet into new designs. One of the primary factors affecting materials degradation is residual stresses left during the fabrication process. These tensile residual stresses can cause stress corrosion cracking and other failure mechanisms in nuclear plant piping. Proper selection and control of welding and fabrication processes can reduce or eliminate tensile stresses on the inside diameter surface of piping components. A materials management matrix (MMM) will be produced for each of the advanced light water reactor designs being considered by Advanced Nuclear Technology members (AP1000, EPR, ABWR, APWR, ESBWR, and APR1400). The MMMs will list critical materials-related information for each of the components in the nuclear steam supply system (ASME Class 1 equivalent). These matrices will be living documents that can be used to manage material issues over the operating lives of the reactors. Other materials-related projects including welding best practices will be conducted as needed. A group of welding and materials engineers, fabricators, and other industry metalworking experts will be consulted to develop recommendations and document best practices for welding plant components and for fabricating new plants. Potential benefits from this project include the following: Assist in evaluating materials-related issues that can significantly affect operating costs in existing reactor designs Ensure new plants are economically competitive over their operating life through more effective materials management Minimize tensile residual stresses through application of welding best practices Simplify management and evaluation of materials degradation and flaws Extend initiation time of many degradation mechanisms by eliminating or minimizing the tensile residual stresses in welds Advanced Nuclear Technology - Program p. 4

7 The MMMs function as an ongoing roadmap to material issues for the life of the plant. They will be maintained by EPRI and updated periodically with assistance and feedback from vendors and plant owners. Members will use them to assist with purchase decisions and as an ongoing tool for optimizing inspection schedules and mitigation strategies. New Nuclear Plant Reliability (supplemental) (066888) Equipment reliability at nuclear plants starts with design and procurement and continues through construction and startup. When the plant begins operating, the level of success and cost associated with equipment reliability programs are directly related to the foundation established in the early stages of the plant s life. While equipment vendors can focus on first costs, the owner/operator needs to consider first cost, operating cost, and plant revenue when making decisions. Limited actions have been taken to factor lessons learned from current equipment reliability programs into new plant projects. Also, new plants will apply advanced instrumentation and control (I&C) and communications technologies, including higher-frequency components and wireless, far more extensively than the current nuclear fleet, giving rise to new technical and regulatory concerns. This project will develop numerous products to support enhanced plant reliability programs. Products may address component specifications, commodity standards, and new I&C technology. As one example, a practical, clear, common understanding of the concerns associated with electromagnetic compatibility management and qualification requirements associated with higher-frequency components will be needed among utilities, regulators, and equipment suppliers. Therefore, the current guidance needs to be updated and expanded. Potential benefits from this project include the following: Establish a foundation for a highly effective operating plant equipment reliability program, leading to highcapacity factors and contained operations and maintenance costs Incorporate owner expectations for equipment monitoring into initial project plan Minimize impact of electromagnetic interference through spectrum management planning Incorporate experience on nuclear power plant startup from the international community Plant staff will apply lessons learned, guidelines, and recommendations from existing plants into plant programs for new plants. With respect to advanced I&C and communications technologies, utilities will be able to make the electromagnetic interference information available to their suppliers as needed to ensure that electromagnetic compatibility requirements are met. The project will result in new plants that are much less likely to experience electromagnetic interference problems, with corresponding improvements in plant reliability, safety, and operating costs. Advanced Nuclear Technology - Program p. 5

8 New Nuclear Plant NDE (supplemental) (066885) New nuclear power plants must comply with requirements for pre-service inspection (PSI) and in-service inspection (ISI) of pressure boundary components and supports in accordance with regulatory-accepted codes and standards (for example, American Society of Mechanical Engineers [ASME] Section XI). Although these requirements are typically deterministically based, about 90% of existing plants have transitioned to riskinformed methods. Nuclear power plants also must comply with ASME Section III requirements for construction, pre-service, and inservice volumetric inspection of the primary pressure boundary. The construction volumetric inspection ensures that the components and welds meet applicable codes. Changes to ASME Section III could eliminate unnecessary repairs by allowing acceptance of fabrication flaws that are not structurally significant. This will require industry and regulatory confidence in the volumetric nondestructive evaluation (NDE) methods that are used to detect and size fabrication flaws. The Electric Power Research Institute's (EPRI s) risk-informed in-service inspection methodology will be tested and refined for advanced plant designs. The goal would be to develop a single PSI/ISI program for each design (not site-specific) or define any issues and provide guidance where there may be site-specific requirements. The project also will establish and operate the ultrasonic (UT) examination qualification programs necessary to ensure accurate, reliable construction inspections of primary pressure boundary components and welds. Results from this project could support timely and cost-effective compliance with regulatory requirements for construction inspection, including the following: Regulatory acceptance of fitness-for-service philosophy, eliminating unnecessary repairs Cost savings and elimination of delays during construction Improved resistance to stress corrosion cracking during plant operation Reduced construction, inspection, and acceptance costs Reduced operating costs Shortened construction and turnover schedules by focusing resources on more important systems and components and incurring fewer regulatory actions Members will have access to a regulatory-approved ISI methodology for use in new plant license applications. This also will support future operations and maintenance activities over the life of the plant. Members will use the UT Qualification products in specifying certification levels and specialized qualifications for UT personnel in construction procurements. As a result of these products, the necessary qualified UT personnel will be available to support new plant construction. Advanced Nuclear Technology - Program p. 6

9 Security and Seismic (supplemental) (067606) The underlying generic seismic source model for the Central and Eastern United States is more than 18 years old, and the Nuclear Regulatory Commission is on record as indicating that the model should be updated every 10 years. Also, recent NRC Requests for Additional Information are challenging the previously developed seismic source characterization continuing the NRC trend away from its use of EPRI s baseline seismic source characterization model. EPRI is developing a new seismic source characterization model for the Central and Eastern United States (CEUS) that will facilitate new plant siting and respond to regulatory concerns. The new generic CEUS seismic source characterization model will benefit several industry participants: a) nuclear power plant owners and developers that have submitted an early site permit (ESP) or combined operating license application (COLA) for NRC review in 2007 (or 2008) or will submit a COLA for a second unit in or after 2009; b) nuclear power plant owners and developers that will submit an ESP or COLA for NRC review in or after 2009; and c) operating nuclear power plant owners that must respond to issues resulting from NRC Generic Issue 199 (GI-199). Potential benefits from this project include the following: Realize significant time and resource savings through standardization and partnering Achieve stability in the seismic design of new plants Inform decisions regarding the current state of knowledge in a non-regulatory environment using the approved Senior Seismic Hazard Analysis Committee process Eliminate potential for multiple, possibly conflicting, interpretations of seismic sources by different consultants Avoid challenges to the EPRI-Seismic Owners Group (1989) seismic source characterizations by NRC staff, its consultants, or interveners during the hearing process Minimize potential for duplication of effort because seismic hazard models for many CEUS sites have significant geographic overlap Reduce the opportunity for delays due to more conservative interpretations Members will use project results in developing early site permits, combined operating license applications, and in responding to regulatory concerns. This work replaces a study performed approximately 20 years ago. Since that study was completed, substantial work has been done to improve the understanding of seismic sources and their characterization in the Central and Eastern United States. Achieving Virtual Power Plant Configuration Management (supplemental) (068802) New plants will be designed using advanced 3-D computer-aided design software, producing detailed models that can be integrated with plant design, operations, and maintenance databases. Associated software suites supporting the 3-D models also may support documentation and characterization of facility system, structure, and component data and attributes. An automated, integrated, and interoperable configuration management program must be established to maintain consistency between the design requirements, physical configuration, and facility configuration documentation to ensure the ability to document and maintain compliance with the license basis. Advanced Nuclear Technology - Program p. 7

10 This project consists of three sub-tasks: Develop a Standard Configuration Management Reference Model and Implementing Guideline to provide a common framework to help manage an automated, integrated, and interoperable configuration management program in a consistent and connected way. Develop New Nuclear Plant XML Equipment Schemas for a set of critical components to help facilitate information interoperability throughout the full plant life cycle. Develo p a New Nuclear Plant Information Handover Guide providing a full plant life-cycle information strategy establishing the methodology for defining the information requirements and the how to for developing and implementing an information handover plan. Configuration management programs implemented using the Standard Configuration Management Reference Model and Implementing Guideline can achieve the following benefits and avoid past problems: Clear design basis Plant physical configurations match documents/records and design requirements Operating procedures integrated with design constraints and limits Complete set of records to support maintenance (for example, Q-lists and bill of materials) Designs containing instrumentation for monitoring the physical plant to ensure equipment configuration is maintained consistently with design requirements Avoid long-term plant shutdowns caused in part by configuration management problems The 3-D models will assist plant owners in managing and improving the return on their new build investment. The information developed will be in the form of guidelines and new nuclear plant XML equipment schemas that the plant owner can directly implement. Much of the benefit will be from the industry adoption of data interoperability standards developed in this project. Advanced Nuclear Plant Research (base) (052492) New sources of energy are being developed to alleviate two key challenges facing all industrialized and developing countries: increased energy security to improve national and global security and reduced carbon footprint in all economic sectors to address manmade contributions to global climate change. One such energy source is the high-temperature gas reactor, which can extend the use of improved nuclear technologies into energy sectors beyond electricity generation. This project covers multiple activities associated with various advanced nuclear plant designs: Supporting activities around developing a public/private partnership to determine the feasibility and practicality of using advanced high-temperature gas reactor systems for process heat, hydrogen production, and cogeneration. Studying sonoluminescing bubbles and nanomaterials synthesis. Sonoluminescence is the light emission associated with catastrophic bubble collapse of a gas bubble oscillating under an ultrasonic field. Sonoluminescence can be applied to synthesize nanomaterials, which can be used for the direct catalyzed decomposition of methane into hydrogen a potential process for hydrogen production in hightemperature gas reactors. Advanced Nuclear Technology - Program p. 8

11 Support industry activities related to research, demonstration and deployment of emerging small modular reactor (SMR) designs Potential benefits from this project include the following: Accelerate and direct the development, demonstration, and deployment of advanced reactor technology for future energy markets. The commercial deployment of new technologies can help address critical issues of energy security and global climate change. Investigate alternate processes to enable hydrogen production at lower costs and with less energy input. Identify member-driven, common technical requirements for design, development, and operation of small modular reactors, and define potential research gaps. Members will review research and development results to guide awareness and development of advanced nuclear power plants, including small modular reactor designs and high-temperature gas reactors. Advanced Nuclear Technology - Program p. 9

12 Chemistry, Low-Level Waste and Radiation Management Develop guidance and technologies to improve water chemistry practices, enhance low-level waste management, reduce radiation exposure, and inform plant decommissioning efforts. Programs Low-Level Waste and Radiation Management Decommissioning and Technology Development Water Chemistry

13 Low-Level Waste and Radiation Management Program Description Program Overview Nuclear power plants face significant regulatory, economic, environmental, and public perception pressures with respect to low- and intermediate-level waste (LLW) management and personnel exposure to radiation. The safe processing, handling, and disposing of low-level waste requires a detailed familiarity with both technical and regulatory issues. Similarly, as regulatory limits on personnel exposure to radiation decrease, greater effort is needed to develop and demonstrate effective radiation protection and source-term reduction technologies. The Low-Level Waste and Radiation Management program investigates improvements to nuclear plant operational practices that can reduce risks associated with waste management and radiation exposure. The program develops guidelines and technologies for waste disposal volume reduction, dose and radiation field reduction, and nuclear plant decommissioning, resulting in lower electricity production costs, better informed regulatory oversight, and improved public perception. The program also develops technical guidance for early detection, mitigation, and remediation of groundwater contamination, an issue of increasing public concern and regulatory oversight. Research Value Effective management of low- and intermediate-level waste and radiation exposure enables nuclear plants to operate safely, cost-effectively, and with minimal risk to plant personnel, the public, and the environment. Research results are used by radiation protection managers to develop strategies for minimizing waste generation and reducing handling and storage costs. Research results are used by radiation protection managers to minimize radiation fields and reduce activity generation. Low-Level Waste and Radiation Management Program participants gain access to the following: Technologies, assessments, and guidelines that can reduce solid and liquid waste volumes. LLW assessments, for example, have identified optimization recommendations valued at more than $75 million per year. New source-term reduction and radiation protection techniques that can reduce radiation dose. Sourceterm reduction studies have identified methods for reducing radiation fields by as much as 50% over 5 years. Technical guidance for risk-informed regulations in LLW, radiation protection, and groundwater protection that can address public safety and environmental stewardship concerns. Operational strategies for reducing the volume of Class B/C LLW could save the industry more than $27 million per year when fully implemented. The Low-Level Waste and Radiation Management Program develops knowledge, guidance, and tools to reduce the risks and costs associated with waste management and radiation protection. The program also conducts plant assessments to provide expert support and to capture lessons learned that can be shared across the industry. Provide cost-effective, risk-based alternatives for waste disposal due to limited LLW site access (Barnwell closure). Develop guidelines and technologies for reducing waste volumes and worker radiation dose. Establish technical foundations for reduced regulatory burden in the areas of radiation protection and lowlevel waste. Provide tools for improved public perception regarding groundwater protection programs. Low-Level Waste and Radiation Management - Program p. 1

14 Accomplishments The Electric Power Research Institute (EPRI s) Low-Level Waste and Radiation Management Program supports industry efforts to reduce the costs and regulatory burdens associated with low-level waste and to drive reductions in public, environmental, and personnel exposure to radiation. The Program develops and demonstrates innovative technologies, converts industry operating experience into practical guidelines, and explores alternative approaches for more effective LLW and radiation management. Received regulatory endorsement for EPRI's On-Site LLW Storage Guidelines, which provide consistent, industry-driven guidance for operation of on-site LLW storage facilities. Submitted to U.S. Nuclear Regulatory Commission the technical basis for LLW concentration averaging, which would provide $36 million per year in industry cost savings upon implementation. Source-term reduction recommendations implemented at Brown's Ferry Unit 1 helped the unit achieve the lowest dose rates in the boiling water reactor (BWR) fleet following a restart. Based on analysis of industry pressurized water reactor (PWR) dose rate data, identified technical solutions that can provide measurable reductions in plant radiation fields. For example, zinc injection and electropolishing show strong benefit in reducing dose rates. Completed multi-year review of updated research on the health effects associated with low-dose radiation. Analysis concluded that the radiation damage/response paradigm should be expanded to account for increased complexity in biological response mechanisms. Results shared with regulatory community to inform revisions to radiation protection standards. Developed guidance to establish industry-wide practices for monitoring the release of materials and personnel from radiologically controlled and protected areas. Recommendations encompass tools, equipment, volumetric and non-volumetric materials, small quantity materials, non-radioactive shipment vehicles, and personal items. Developed tools for implementing an effective, optimized groundwater monitoring and remediation program, including technical guidelines and supplemental site evaluations. Nuclear Regulatory Commission endorsement of the EPRI Guidelines would provide significant site relief. Current Year Activities Low-Level Waste and Radiation Management program research and development for 2011 will sustain progress toward lower-cost waste handling and disposal, reduced worker dose, and improved detection and monitoring of groundwater. Specific efforts will include the following: Develop the technical basis for regulatory changes to low-level waste classification criteria. Develop EPRI Cobalt Reduction Guidelines, Rev.1. Develop EPRI groundwater remediation guidelines and technologies. Provide site-specific implementation support for source-term reduction technical guidance being developed by the program. Estimated 2011 Program Funding $4.5 million Program Manager Lisa Edwards, , ledwards@epri.com Low-Level Waste and Radiation Management - Program p. 2

15 Summary of Projects Project Number Project Title Description P P a P b P P a P b P Low-Level Waste R&D Program (base) Low-Level Waste Assessment (supplemental) LLW Technical Strategy Group (supplemental) - Annual Membership OR 3- Year Membership + Assessment Radiation Management R&D Program (base) Radiation Management Assessment (supplemental) Radiation Management/Source Term Strategy Group (supplemental) - Annual Membership OR 3-Year Membership + Assessment Groundwater Protection R&D Program (base) (QA) The Low-Level Waste R&D Program conducts research and analysis that can reduce costs and improve efficiency and performance of LLW management strategies, reduce the generation of Class B/C LLW requiring on-site storage, provide clear and concise industry guidance for the safe and regulatory compliant on-site storage of LLW, and where appropriate, provide technical justifications for changes to existing disposal regulations to expand the disposal options available to LLW generators. The low-level waste assessment activities available through this project are designed to help plant personnel fully benefit from base research program results. Participating members will select the assessment area of focus. Common areas of focus include: On-Site Storage, BC Reduction, Solid LLW, Liquid LLW, and Liquid System Manager (LSM) installation. The LLW Technical Strategy Group provides a forum for discussing technical issues and sharing lessons learned regarding strategic LLW management. Members also receive expert technical consulting as part of their membership. The LLW Technical Strategy Group is available in 3-year and 1-year membership options. The 3-year membership includes one full LLW assessment once during the three-year period. The Dose reduction for cumulative and individual exposure tasks will be accomplished by developing a systematic method for evaluating the tasks and determining the optimum strategy for technology evaluation and implementation. A series of assessment activities have been designed to help plant personnel gain the full benefit of the base program results by providing site-specific or unit-specific guidance in implementing the technologies and strategies produced by the base Radiation Management Program. Assessments include as low as reasonably achievable (ALARA) technologies, radiation source term, remote monitoring technology, and scaffolding. The Radiation Management/Source Term Strategy Group provides an interactive forum for members to share and get expert advice in applying ALARA technologies and to gain insights on how to effectively reduce source term. Industry lessons learned and discussion of emergent issues will provide members with the most up-to-date information for making informed decisions on job planning and preparation. EPRI's Groundwater Protection Project provides members with advanced strategies and technologies for improved management of situations involving radiologically contaminated groundwater. This project develops technical guidance for implementing site-specific groundwater monitoring programs geared toward mitigation, early detection, and remediation of groundwater contamination. Implementing these programs will enhance site knowledge and increase confidence and accuracy in communications with stakeholders.this project will evaluate and develop advanced technologies and methodologies for environmental and groundwater protection, monitoring, and remediation at nuclear power plants. Low-Level Waste and Radiation Management - Program p. 3

16 Project Number Project Title Description P a P b Groundwater Assessment (supplemental) Groundwater Strategy Group (supplemental) Three types of assessments are available to members through this supplemental assistance program: Groundwater Characterization and Protection, Groundwater Technology Demonstration, and Tritium and Water Management Model. Participants will work with EPRI to select the assessment type that is of most interest to the plant. The generic lessons learned and experiences from each assessment project will be incorporated into the EPRI base program to support further development of technical guidance and technologies. The Groundwater Strategy Group provides members a forum for discussing groundwater protection experiences, lessons learned, and advanced technologies. Members will have access to the Groundwater Strategy Group collaboration website and quarterly conference calls. Those utilities participating in the 3-year membership are eligible for one site-specific Groundwater assessment once during the 3-year period. Low-Level Waste R&D Program (base) (061432) Nuclear power plants continually evaluate opportunities to reduce the costs and improve the efficiency and performance of low-level waste (LLW) management, handling, storage, and disposal programs. EPRI s Low- Level Waste Program helps nuclear plants optimize LLW management programs through advanced media testing, improved technologies and tools, safe and efficient on-site storage of LLW, and the development of technical bases for improved flexibility and risk-informed regulations for LLW disposal. Currently, 85% of the U.S. industry does not have access to Class B/C LLW disposal. EPRI has developed a three-part strategy to address this issue: 1) minimize the generation of Class B and C waste, 2) provide industry guidance for on-site storage of waste, and 3) examine alternatives to existing disposal regulations and guidance. Multiple products have been developed and are under development in support of this strategy. Waste Class B/C Reduction Guide ( ): Revision 1 is a planned product for 2011 Guidelines for Operating an Interim On-Site Low Level Radioactive Waste Storage Facility, Revision 1 ( ) and the Low Level Waste On-Site Storage Operating Guideline Supplemental Information Manual ( ) Proposed Modification to the NRC Branch Technical Position on Concentration Averaging and Encapsulation (BTP), Technical Basis and Consequence Analysis ( ) Technical Progress Report on Options for Improved LLW Disposal Flexibility Using 10CFR61.58 ( ): Final report planned for 2010 Specialized media and other operations continue to be a developing field. The need to reduce Class B and C waste has led to the cost-effective development of nuclide-specific separation methods and innovative processing technologies both within EPRI and by industry service providers. EPRI's LLW R&D Program identifies and conducts performance testing of media and processing strategies that may be considered for reducing Class B and C waste generation and for optimizing liquid radwaste processing system performance. In 2010, this project will evaluate the use of nuclide-specific media by treating plant-generated liquid radioactive waste in a series of test columns. The tests will evaluate the relative removal efficiency as compared to other media types and consolidate existing guidance on multiple media evaluations. Low-Level Waste and Radiation Management - Program p. 4

17 In 2010, EPRI's LLW R&D Program will complete the work on developing a technical basis for options for improved LLW disposal flexibility using 10CFR Performance testing of multiple media for the selective removal of Cs-137 and colloidal cobalt in liquid radwaste processing systems will be conducted. Work will also begin on the revision of the 2007 Waste Class B/C Reduction Guide, the development of global radwaste profiles for member countries, and the development of a technical basis for Very Low Level Waste as a separate waste category. Reduced generation of Class B/C LLW requiring on-site storage. Avoided potential new rule making regarding on-site storage of LLW. The On-Site Storage Guidelines have been reviewed and endorsed by the Nuclear Regulatory Commission as "providing an acceptable method for recordkeeping, determining waste forms and waste containers and monitoring and inspecting the interim long-term storage of LLRW." This effort provides concise guidance to plant operators on how to operate their interim storage facilities in compliance with regulatory expectations. Provided technical basis for modification of the regulatory branch technical position to allow broader blending of compatible waste. If adopted, these changes will favorably increase the volume of waste that is classified as Class A and reduce the amount that is Class B or C. Expanded disposal options for the nuclear industry through more clearly established protection requirements. (Future) Provide technical justification for regulatory relief to the concentration limits defined in 10CFR61 based on existing knowledge of performance assessment technology, realistic dosepathways of existing disposal facilities, and updated dose conversion factors. Program results are used by radwaste managers in developing strategies for minimizing the generation of Class B/C waste and optimizing solid and liquid LLW management programs. Members also can apply technical guidance to ensure compliance with regulatory concerns regarding interim waste storage. Long-term research results will provide the technical basis for future risk-informed regulations and improved flexibility of disposal options. Low-Level Waste Assessment (supplemental) EPRI understands that the implementation of guidance, technologies, and strategies produced by the LLW base research program can be done more quickly and effectively with site-specific assistance. A number of LLW assessment activities can be deployed to help plant personnel gain the full benefit of base EPRI research results. Most assessment activities provide an on-site evaluation of how specific research results, technologies, industry experience, and industry best practices could be applied at a given plant. The assessment delineates actions with the largest potential benefit to the site and identifies potential gaps that, if closed, could provide economic, performance, and/or regulatory margin benefits. Participants can select from several assessment focus areas: on-site storage, BC reduction, solid LLW, liquid LLW, and Liquid System Manager software installation. The utility also may specify a focus area currently challenging the plant. The utility and EPRI Project Manager will then work together to define the scope. Low-Level Waste and Radiation Management - Program p. 5

18 Expected impacts vary depending on the area of focus, but impacts can include the following: Optimized LLW management program performance Improved regulatory margin Cost savings due to reduced generation of Class B and C waste Improved effluent program performance Cost savings due to reduced wet and dry LLW generation Improved program performance through advanced technology applications Evaluation of site implementation of guidance documents Members participate with an industry expert during the on-site assessment. The area of focus is determined by the assessment activity selected. The process helps plant personnel gain insights about their plant-specific performance and how to apply EPRI guidance, technologies, and tools to the plant's advantage. After the assessment, a confidential site-specific report details the strengths and gaps associated with program implementation and prioritizes recommendations and potential benefits. Later, generic results and lessons learned may be compiled in program reports for industry use. LLW Technical Strategy Group (supplemental) - Annual Membership OR 3-Year Membership + Assessment (004514) Nuclear plants frequently benefit from broader awareness of the LLW management activities practiced at other plants. The LLW Technical Strategy Group provides a forum for discussing technical issues and sharing lessons learned regarding strategic LLW management. Emerging technical issues include the Nuclear Regulatory Commission (NRC) Branch Technical Position on LLW concentration averaging; potential changes to 10CFR61; and LLW disposal site development, blending, encapsulation, solidification, and economics. Members also receive expert technical consulting as part of their membership. The LLW Technical Strategy Group is available in 3-year and 1-year membership options. The 3-year membership includes one full LLW assessment once during the 3-year period The Technical Strategy Group conducts periodic conference calls to keep membership appraised of emerging issues and to solicit input on industry responses to these issues. Webcasts are used to provide members with up-to-date status of LLW disposal options, presentations on new processing strategies, information on new regulatory notices, technical exchanges of lessons learned, and new ideas on cost control. Members of the LLW Technical Strategy Group receive annual on-site expert technical consulting as part of their membership. This consulting time is typically used for continuous improvement of LLW program management strategies and for analysis of special projects. On-site consultation topics are scheduled with individual members. International members participating in the LLW Technical Strategy Group will receive their site-specific support remotely. As noted above, those utilities participating in the 3-year membership are eligible for one site-specific LLW assessment once during the 3-year period. This assessment is conducted on-site for both U.S. and international members. Low-Level Waste and Radiation Management - Program p. 6

19 Participation in the Technical Strategy Group keeps members abreast of emerging issues surrounding LLW management and provides members with a forum for technical exchange. Site-specific consulting time provides expert support for specific plant or corporate project requests. Individual plant and fleet strategies for LLW management are frequently evaluated with this support. Cost evaluations conducted during these consultations often identify significant cost-saving measures. The on-site assessment provided for utilities participating in the 3-year membership evaluates how specific research results, technologies, industry experience, and industry best practices could be applied at a given plant. The assessment delineates actions with the largest potential benefit to the site and identifies potential gaps that, if closed, could provide economic, performance, and/or regulatory margin benefits. On-site consultation time is used to ensure EPRI guidance is applied to emerging and critical plant-specific LLW management issues. Participation in periodic webcasts keeps members abreast of emerging issues in the rapidly changing climate surrounding LLW management and provides members with a forum for technical exchange. The LLW assessment helps plant personnel gain insights about their plant-specific performance and how to apply EPRI guidance, technologies, and tools to the plant's advantage. Radiation Management R&D Program (base) (052350) The nuclear industry's radiation protection organizations are continually challenged to better manage and reduce radiation exposure to workers while balancing increased maintenance work resulting from plant aging issues. There is a worldwide trend to adopt more restrictive worker dose limits while minimizing total collective exposure. In the United States, the Nuclear Regulatory Commission announced its intentions to revise radiation protection regulations in the next several years. Perhaps the most challenging change will be the adoption of lower occupational dose limits, potentially reducing the current limit of 5 rem/yr to as low as 2 rem/yr. EPRI's Radiation Management Program, the Nuclear Energy Institute (NEI), the Institute of Nuclear Power Operations (INPO), and the nuclear industry worked together to develop the RP2020 Initiative, which aims to make radiation exposure a non-issue by the year Use of a wide spectrum of dose reduction and source term reduction technologies will likely be required to meet the regulatory challenges and industry goals of improved radiation protection practices. In addition, better incorporation of the as low as reasonably achievable (ALARA) principles by vendors and other stakeholders in the development of new tools and techniques is needed for plant inspection and maintenance. A new framework for more efficient human resource allocation and coordination of key workers also is needed. To meet these challenges, EPRI's Radiation Management Program will develop guidance, technologies, and operational practices to more aggressively reduce radiation fields (source term) and minimize worker dose to ALARA standards. The Radiation Management Program is divided into two major areas: 1) Source Term Reduction technical area, which is focused on minimizing radiation fields, and 2) Radiation Protection technical area, which is focused on improving the use of dose reduction technologies and improving worker efficiency. The immediate priority for the program is to reduce the number of high-dose workers receiving greater than 1.0 rem/yr through the optimization of tasks and the radiological work environment. Low-Level Waste and Radiation Management - Program p. 7