Advanced Nuclear Technology (ANT) Program Overview for CMBG

1. Advanced Nuclear Technology (ANT) ProgramOverview for CMBG Ken Barry, Senior Project Manager Russell Adams, Dominion June 23, 2010

2. © 2008 Electric Power Research Institute, Inc. All rights reserved.

3. EPRI Portfolio Spans the Entire Electricity Sector Generation Nuclear Power Power Delivery & Utilization Environment • Advanced Coal Plants, Carbon Capture and Storage • Combustion Turbines • Environmental Controls • Generation Planning • Major Component Reliability • Operations and Maintenance • Renewables • Material Degradation/Aging • Fuel Reliability • High-Level Waste and Spent Fuel Management • Nondestructive Evaluation and Material Characterization • Equipment Reliability • Instrumentation and Control • Risk and Safety Management • Advanced Nuclear Technology • Low-Level Waste and Radiation Management • Distribution • Energy Utilization • Grid Operations and Planning • Substations and Asset Planning • Transmission and Increased Power Flow • Air Quality • Global Climate Change • Land and Groundwater • Occupational Health and Safety • T&D Environmental Issues • Water and Ecosystems © 2008 Electric Power Research Institute, Inc. All rights reserved.

4. Advanced Nuclear Technology Program Objectives • New nuclear power plants must overcome a number of regulatory, economic, technical, and social challenges prior to becoming a reality • Program efforts focused around: • Facilitating standardization across the new fleet • Transferring technology to new plant designs • Ensuring top plant performance from start of operations • Reduce overall deployment risk and uncertainty • Supporting development of advanced nuclear plants and associated strategic initiatives

5. EPRI’s Response …The ANT Program Materials and Fuels Research Maintenance Optimization Seismic/NDE/Cooling Technologies Advanced Nuclear Technology (ANT) Program Current Plant Technology Near-Term Deployment of ALWRs Strategic Initiatives NPP Cooling Water Utilization Fusion Energy Assessments Integrated Spent Fuel Management Technology Transfer/Lessons Learned Technology Assessment (URD) New Plant Materials Seismic Issues Resolution New Plant Equipment Reliability Non-Destructive Evaluation Initiatives Advanced Nuclear Plants Next Generation Nuclear Plant (NGNP) Small Modular Reactors (SMRs) Advanced Reactor Concepts

6. EPRI’s ANT Program Websitehttp://www.epri.com/ant

7. 2010 ANT Membership Breakdown Current 2010 Membership…$4.225M 2010 Potential…

8. 2008 ANT Projects * Projects completed

9. 2009 ANT Projects * Projects completed

10. 2010 ANT Projects

11. 2010 ANT Projects

12. 2011 Candidate ANT Projects

13. 2011 Candidate ANT Projects

14. 2011 Candidate ANT Projects

15. 2009-01 Achieving New Nuclear Virtual Plant Configuration Management Project Goal • We need a common data language and interoperability standard that will be used by the nuclear plant sub-tier suppliers through the suppliers, through the EPC and reactor vendors, and finally through to the owner and operator

16. 2009-01 Achieving New Nuclear Virtual Plant Configuration Management Progress Standard Configuration Management Reference Model • The Standard Configuration Management Reference Model draft is undergoing a complete re-write. New Nuclear Plant XML Equipment Schemas • The Schema viewer is complete. The project is working with the Hydraulic Institute, NIST and a pump vendor to conduct a pump procurement pilot to determine nuclear specific fields. Also planning pilots with valve operators and electric motors • We are running into more issues with the standardization of XML schemas that anyone had anticipated. The original concern that a few “nuclear specific” fields may be missing has turned into an effort involving schema terminology, complexity, architecture refinement, document maturity validity, etc. Feedback to FIATECH Information Handover Guide • The Handover Guide was published in December 2009 (1019221). • Developing Handover Life Cycle and data requirements.

17. The Must Nuclear Configuration Management “What needs to be there” Design Requirements Design Basis Conform Conform Plant Docs Facility Configuration Information “What we say is there” “What is actually there” Physical Configuration Physical Plant Conform Work Processes must assure that: Elements conform all the time All changes are authorized Conformance can be verified

18. The Challenge Nuclear Configuration Management Knowledge Workers EDB Challenge Conform Challenge Conform Paper-based Quality Assurance Process PD Plant Documentation Automation Systems AS Conform Challenge Lots of Tribal Knowledge , Semi-Connected and Disconnected Systems, Manual Processes and yes…… Paper

19. Keeping the Ship Heading in the Right Direction - Sustainability 2011 2009 2010 SCMRM Developed Concept Publish SCMRM & Templates Organize SCMRM UG? XML Schemas Reviewed Existing XML Schemas Conduct XML schema pilots* EPC/Supplier Implement? Info Handover Published Info Handover Guide Publish Templates Organize Info Handover UG? * Also participate in POSC Caesar / FIATECH ISO 15926 project

20. 2009-04 Guidance on EMI Protection Eliminating Exclusion Zones Immunity, Φ2 Immunity = immunity of system, not of individual component Φ2 > Φ1 E = allowable field strength (V/m) Pt = effective radiated power of emitter (source) Gt= gain of the source Source Pt , Gt Immunity, Φ1 DigitalDevice d Which variables will affect the E (electric field); reduce it? Receptor Path Source

21. 2009-04 Guidance on EMI Protection Execution2010 Implementation2011 Analysis2009 Develop Base Linefrom Historical Dataof Emissions Datafor Nuclear Plants Develop New RFImmunityRequirements forANPs • New test protocols • Testing & test reporting • In-situ testing • Test report review & system certification New Layers ofEMC ProtectionEliminateExclusionZones Data from 1993to 2009 Done Evaluate PresentEMC Performanceof I&C Equipment Develop SpectrumManagement Planfor ANPs • Initiates required frequency protection margin • Establishes frequency budget • Defines transmitter spacing • Reduces probability of transmitter causing EMI problems New Layers ofEMC ProtectionEliminateExclusionZones Use EPRI TR-102323for Input Use Existing (New)IEEE Standard In Process Analyze FactorsCausing Change inthe ElectromagneticEnvironment for ANPs Initiate Developmentof New Standards(ANSI/IEEE) toAddress these Needs • Establishes normative standards for: • a) Recommended design practices • b) I&C product qualification & In-situ evaluation • c) Refine & keep standards current New Layers ofEMC ProtectionEliminateExclusionZones Incorporate NewWireless Standards In Process Conduct InterferenceAnalysis on FutureI&C Systems forANPs Design a ConformityAssessment Systemto Provide forRF Immunity forANP I&C Equipment • Assures required level of RF immunity • Encompasses process to assure I&C equipment complies with the installed environment with requirements • Conformity assessment systems are ISO standardized I&C EquipCertificationSystem Use Existing (New)IEEE Std. 1900.2 Upcoming • Develop staged process for deployment • Initial testing in laboratory environments • Alpha, then Beta testing in a staged process SupportDeploymentof ImprovedI&C Systems ANSI ASC C63Approved a Study ofNeed for New Stds ConstituteAlpha & Beta TestRecommendationsin ANP Designs Started

22. 2008-06 NDE and Reduction of Repairs in Nuclear Construction Project Goals • Eliminate unnecessary repairs during construction • Influence ASME Code Section III • Establish UT qualification programs • Provide assurance of accurate and reliable weld inspections during the construction • Regulatory acceptance of fitness-for-service philosophy • Cost savings and elimination of delays during construction • Improved resistance to stress corrosion cracking during plant ops

23. 2008-06 NDE and Reduction of Repairs in Nuclear Construction UT Images vs. RT film ? ?

24. 2009-08 Safety Related Stationary Battery Qualification Project Description • EPRI Utility Requirements Document (URD) states that Advanced Light Water Reactors (ALWRs) shall utilize passive safety systems to mitigate design basis events up to 72 hours in duration • Passive systems must rely upon stored energy, e.g., batteries • Passive plants (AP1000, ESBWR) require batteries that are qualified to a 72 hour duty cycle • IEEE 535 standard for battery qualification (endorsed by RG 1.158) did not cover duty cycles beyond 8 hours • IEEE 535 only covers Vented Lead Acid (VLA or flooded) batteries – Valve Regulated Lead Acid (VRLA) batteries are not addressed Value • Providing a industry solution to a first-of-a-kind technical challenge for passive plants • Reducing risk through a collaborative approach

25. 80% Service Test, 4h to 1.81vpc showing normal duty cycle enveloped

26. 2010-02 Digital RT Summary of Issue • Currently, the industry is unable to address the evaluation and qualification of filmless radiography systems to detect planar and volumetric fabrication flaws with selected digital detector panels (DR), phosphor plates (CR), and high energy electronic radiation sources capable of penetrating the material thicknesses typically encountered in plant applications Potential Benefit of Project • Expedited ASME Section III volumetric examination of piping welds with CR or DR • Volumetric option/complement to UT • Minimization of weld repairs with ASME Section III volumetric examination • Digital storage of images instead of processed film and associated chemical processing

27. 2010-05 NDE Digital Data Summary of Issue • Archival data is required by the Nuclear Regulatory Commission (NRC) to last for the plant's working lifetime • Many utilities' document control departments will not accept digital non-destructive examination (NDE) data for archival storage and require it to be converted to a hard copy format Potential Benefit of Project • This guide will assist utilities in transferring, retrieving, and archiving their NDE data and allow them a path for any future digital NDE data needs • A consistent and acceptable process is needed for archiving digital NDE records, versus converting them to paper records

28. 2010-10 Concrete Embedded Sensors Summary of Issue • Large concrete structures in nuclear power plants are typically not feasible to replace. These structures can show signs of concrete degradation by the time they go for license renewal • There is a distinct need for frequent inspections of these types of concrete structures. One of the largest hindrances to concrete inspection is the lack of accessibility to many concrete structures Potential Benefit of Project • Optimize inspections • Better positioned for long-term asset management

29. 2010-11 Technical Basis for HDPE Above-Ground Use Summary of Issue • There is no ASME approved code case for above-ground HDPE pipe. One has been developed for below-ground use only • Several new plant designs plan on using HDPE for above-ground application Potential Benefit of Project • Use of HDPE for above-ground applications will require development of appropriate design and construction rules, along with determining the engineering and material properties needed to ensure safe and reliable design and operation  • Critical technical issues that will be addressed include: • seismic qualification (including vents and drains) • large displacements and interactions during thermal expansion and transients • fire • structural damping values • damage during operations

30. 2011 Project - Cooling Tower Sourcebook for New Nuclear Plants Description • Create a sourcebook to support • Design / Application • Operation • Maintenance • Addressing • Natural draft • Mechanical • Dry • Hybrid

31. Project A – Double-walled HDPE Piping Evaluation Issue • 10 CFR 20.1406, “Minimization of Contamination,” requires licensees to minimize contamination and radioactive waste generation • RG 1.143 states that plastic pipe should not be used. • Doubled walled HDPE is a desired option Description • Review the double walled HDPE piping options available to meet the current regulations, including hardware and leak detection / monitoring options. • This work would include further understanding the HDPE materials degradation properties and limitation for exposure to radioactive fluids. • Work to inform a revision to RG 1.143 to acknowledge the option of using double walled plastic pipe (HDPE), with built-in leak detection capability, • Value • HDPE is viewed as a superior material to steel in some applications and is preferred for buried systems • Providing an alternative in the RG will provide greater flexibility • Cost savings on materials, installation and long term operations

32. Project B – EPRI Groundwater Protection Guidelines for New Nuclear Power Plants Issue • The EPRI Groundwater Protection Guidelines for Nuclear Power Plants (1015118) provides technical guidance for implementing a groundwater protection program that meets the requirements of NEI 07-07. However, it currently does not provide technical guidance for implementing groundwater protection programs, namely the evaluation of plant design and operational procedures, for new plants as outlined in NEI 08-08. Description • EPRI will develop an extension to the EPRI Groundwater Protection Guidelines that provides technical guidance for implementing a groundwater protection program per 10CFR20.1406, RG 4.21, and NEI 08-08. Value • Understanding and preparing for any potential leaks or spills during construction will allow nuclear power plant operator to quickly identify and address any leaks or spills during operation. • Timely leak detection and response will increase stakeholder confidence that utilities are protecting public and environmental health and safety.

33. Project F – NDE Techniques for Concrete Void Detection and Sizing Issue • The main types of degradation related to concrete are the existence of honeycombs and voids due to lack of adequate concrete placement and vibration. • These types of problems are related to poor design and construction, which are the leading causes of age-related degradation in concrete structures Description • Voids (the focus will be on detection capabilities during the placement so that issues can be corrected immediately before curing.) • Wall separation due to concrete shrinkage • Damage under loadings (internal cracks, excessive stress and strain, etc...) Value • Voids in concrete severely reduce the structural and shielding capacity of the concrete structure. The ability for early void detection in a nuclear construction environment will result in both financial and safety improvements. • Long term asset management will also benefit from early detection and correction of construction issues with concrete structures.

34. Project G - URD Update Project Issue • No formal process exists to maintain the URD • No comprehensive listing of EPRI reports applicable to new plants exists Description • Review and disposition the “Margins and Monitoring” work to ensure those recommendations are incorporated into the appropriate URD sections. • Establish EPRI report reference sections for each chapter of the URD • Establish a process for a) collecting input from URD users for review under a specific schedule and b) review newly issued EPRI reports and industry references for inclusion into the URD where appropriate. Value • The results of the Margins work will be visible and reflected in the URD. • Relevant EPRI nuclear sector reports on designing, procuring and constructing new nuclear plants will be comprehensively identified in the URD • URD users will benefit from a process to ensure that their input for changes to the URD are managed in a systematic and timely manner.

35. Project I - QA for 2D and 3D Design and Modeling Software and V&V for Quality Software Issue • The 2D and 3D design and modeling software currently being used to design and ultimately construct the next generation of nuclear power plants do not have to meet NQA-1 requirements for software and data quality. Hence, in order for these systems to be used for the operation of the nuclear power plant – a qualification of the software and data will have to occur. Description • Configuration Control of the Data in Engineering Applications that will have Plant Life Cycle use • Quality Control of the 2D / 3D design and modeling software and other associated databases and software in a commercial grade dedication method prescribed by NQA-1 Value • An industry standard approach to software and data quality for the 2D and 3D design and modeling software and other associated databases and software.

36. Project R – High Strength Rebar use in Nuclear Power Plants Issue • The use of higher strength rebar in the design and construction of safety related concrete structures and / or containment structures could result in cost savings for new nuclear power plants by reducing the quantity of rebar required. Cost savings would result from reduced rebar material purchase costs and reduced construction cost due to reduction in the quantity of rebar placed Description • Develop and implement a concrete testing program to support adoption of higher strength rebar use in ACI 349 and ACI 359. • Involve the NRC to facilitate endorsement of the higher strength rebar in a future revision of Reg. Guide 1.142. Value • The use of High Strength Rebar in the general construction industry has made high strength concrete in seismic zones cheaper and easier to construct due to the lower density of rebar in structures. • High Strength Rebar has greater resistance to corrosion over convention rebar, providing a potential longer life in nuclear plant application.

37. Image from NASA Visible Earth