ML21071A173

NRC-2018-000831 - Resp 10 - Interim, Agency Records Subject to the Request Are Enclosed, Part 7 of 14

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INUEXT-12-24562 Revision 4 U.S. Department of Energy Office of Nuclear Energy

Note to requester: This entire report is also publicly available from the US Department of Energy at https ://www.energy.gov/sites/prod/files/l NL-EXT-12-24562_LWRS-LTO _Joint_RD_Plan_Rev _ 4_0.pdf DISCLAIMER This infom,ation was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied , or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, do not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opi nions of authors expre-ssed herei n do not necessaril y state or reflect those of the .S. Government or any agency thereof.

INL/EXT-12-24562 Revision 4 DOE-NE Light Water Reactor Sustainability Program and EPRI Long Term Operations Program - Joint Research and Development Plan April 2015 Idaho National Laboratory Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517

DOE-NE Light Water Reactor Sustainability Program and EPRI Long Term Operations Program - Joint Research and Development Plan Revision 4 April 2015 Date Light Water Reactor Sustainnbility Technical Integration Office Director. I L Richard Reister Date Light Water Reactor Sustainability Federal Program Director. DOE- E herry 13ernhoft Dale Long Term Operations Program Manager. EPRI

SUMMARY

Nuclear power has safely, reliably, and economically contributed almost 20% of the total amount of electricity generated in the United States over the past two decades. High capacity factors and low operating costs make nuclear power plants some of the most economical power generators available. Further, nuclear power remains the single largest contributor (more than 60%) of non-greenhouse-gas-emitting electric power generation in the United States. Even when major refurbishments are performed to extend operating life, these plants continue to represent cost-effective, low-carbon assets to the nation's electrical generation capability.

At present, over three-quarters of the nuclear power plants in the United States have received a renewed operating license from the U.S. Nuclear Regulatory Commission (NRC), permitting those plants to operate up to 60 years. By the end of 2015, more than one-third of the existing domestic fleet will have passed their 40th anniversary of power operations, and about one-half of the fleet will reach the same 40-year mark within this decade. A regulatory process exists (10 CFR Part 54) for obtaining approval from NRC on extended nuclear power plant operations beyond 60 years. However, NRC will require nuclear power plants that choose to apply for a second renewal of their operating license (identified as "Subsequent License Renewal" by NRC; industry uses the term "Second License Renewal") to demonstrate that adequate design and operational safety margins will be maintained over the duration of the extended operations period.

While recent, overall performance has been excellent (average capacity factors exceeding 90%), the fleet is facing a number of technical challenges related to lo ng-term operatio ns. If current nuclear power plants do not operate beyond 60 years, the total fraction of domestic electrical energy generated from nuclear power will begin to decline-even with the expected addition of new nuclear generating capacity. Replac ing these units will require long-lead planning periods (i.e., 10 to 15 years prior to unit retirement). In addition, significant capital investments (hundreds of billions of dollars) will be needed to design, construct, and commission the replacement generation capacity. Further, if the new capacity has to meet any carbon-neutral criteria (i.e., the replacement units must not produce more greenhouse gas emissions than the units being retired),

costs for replacement generation capacity will be even higher.

Recognizing the challenges associated with pursuing extended service life of commercial nuclear power plants, the U.S. Department of Energy's (DOE)

Office of Nuclear Energy (NE) and the Electric Power Research Institute (EPRl) have established separate but complementary researc h and development (R&D) programs (DOE-NE's Light Water Reactor Sustainability [LWRS] Program and EPRI's Long Tenn Operations [LTO] Program) to address these challenges.

Since calendar year 2010, the LWRS and LTO Programs have cooperatively pursued extensive, long-term R&D activities related to the ability (from a material and economic perspective) of operating the existing fleet for periods up to 80 years and beyond. Contributions to date have advanced the state of knowledge on the measured and predicted performance of materials (e.g., metals, concrete, and cabling) used in nuclear power plant systems, structures, and Ill

components; improved analysis methods and tools for understanding safety margins; and advanced instrumentation, information, and control technologies w ith no generic technical barriers identified that would make long-term plant operations infeasible. The R&D activities of both programs, including progress achieved and plans for continued work, are described herein.

To ensure that a proper linkage is maintained between the programs, DOE-NE and EPRI executed a memorandum of understanding in late 20 IO to "establish guiding principles under which research activities (between the LWRS and LTO Programs) could be coordinated to the benefit of both parties." The memorandum o f understanding calls for DOE-NE and EPRJ to "provide and annually update a coordinated plan for the LWRS and L TO programs. The plan should provide for the integration of the separate L WRS and LTO Program Plans al the project level, showing project scope, schedule, budgets, and key interrelationships between the LWRS and LTO programs, including possible cost sharing." This document represents the fourth annual revision to the initial version (March 2011) o f the plan, as called for in the memorandum of understanding.

IV

CONTENTS

SUMMARY

................................................................................................................................................. iii ACRONYMS .............................................................................................................................................. vii

l. BACKGROUND ................................................................................................................................ 1 1.1 U.S. Department of Energy Office of Nuclear Energy .......................................................... 1 1.2 Electric Power R esearch Institute .......................................................................................... 1 1.3 Research and De velopment Cooperation .............................................................................. I

2. DESCRIPTION OF RESEARCH AND DEVELOPMENT PROGRAMS ....................................... 3 2.1 Department of Energy Office of Nuclear Energy Light Water Reactor Sustainability Program ....................................................................................................................... 3 2.2 Electric Power R esearch Institute Long Term Operations Program .................................... 4 2.3 Reporting of Research and Development Projects ................................................................ 7

3. LIGHT WATER REACTOR SUSTAfNABILITY PROGRAM / LONG TERM OPERATIONS PROGRAM - COORDINATED RESEARCH AND DEVELOPMENT ACTIVITIES ................ ! I

4. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM I LONG TERM OPERATIONS PROGRAM - COLLABORATTVE RESEARCH AND DEVELOPMENT ACTIVITIES ............ 24

5. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM I LONG TERM OPERATIONS PROGRAM - PROGRAM-UNIQUE RESEARCH AND DEVELOPMENT ACTTVITIES ........ 51 Attachment A - Long-Term Operations Issues Tracking Table ................................................................. 62 Appendix A Industry Cost Sharing .......................................................................................................... A-1 TABLES Table 1. Summary overview of the joint research and development plan .................................................... 8 V

VJ ACRONYMS AMP Aging Management Program ASR Alkali Silica Reaction BWR Boiling Water Reactor CASS Cast Austenitic Stainless Steel DOE U.S. Department of Energy EAF Environmentally Assisted Fatigue EMDA Expanded Materials Degradation Assessment EPRI Electric Power Research Institute IASCC Irradiation-Assisted Stress Corrosion Cracking I&C Instrumentation and Control II&C Instrumentation, Information, and Control ILCM Integrated Life-Cycle Management IMT Issues Management Table INL Idaho National Laboratory ITT Issue Tracking Table LTO Long Term Operations LWR Light Water Reactor LWRS Light Water Reactor Sustainability MAaD Materials Aging and Degradation MDM Materials Degradation Matrix MOOSE Multi-physics Object Oriented Simulation Environment NOE Nondestructive Examination NE Office of Nuclear Energy NEI Nuclear Energy Institute NRC U.S. Nuclear Regulatory Commission VII

PWR Pressurized Water R eactor R& D Research and Development RA VEN R eactor Analysis and Yirtual Control ENvironment RELAP R eactor E xcw-sion and !:,eak Analysis f rogram RlMM Risk-Informed Margin Management RISMC Risk-Informed Safety Margin Characterization RPV Reactor Pressure Vessel RST Reactor Safety Technologies SCC Stress Corrosion Cracking SLR Second License Renewal (Subsequent License Renewal for NRC)

SSC Systems, Structures, and Components Vlll

DOE-NE Light Water Reactor Sustainability Program and EPRI Long Term Operations Program - Joint Research and Development Plan

1. BACKGROUND 1.1 U.S. Department of Energy Office of Nuclear Energy The U.S. Department of Energy Office of Nuclear Energy (DOE-NE) conducts research and development (R&D) on nuclear energy to advance nuclear power as a resource capable of meeting U.S. energy, environmental, and energy security needs by resolving technical, cost, safety, proliferation resistance, and security barriers through research, development, and demonstration activities, as appropriate. DOE-NE's Office of Light Water Reactor Technofogies, NE-72, and the program Technical Integratio n Office, located at the Idaho Natio nal Laboratory (INL), manage R&D efforts under the Light Water Reactor Sustainability (LWRS) Program.

1.2 Electric Power Research Institute The Electric Power Research Institute (EPRT) conducts R&D in the public's interest, mostly with funding provided by its membership and the electric utility industry, with respect to the production, transmission, distribution, and utilization of electric power, including research designed to improve the safety, reliability, and economy of nuclear power plants. R&D efforts in the Long Term Operations (LTO) Program are managed as a separate technical program operating in the External Affairs Department of the EPRl Nuclear Power Sector, with the guidance of an industry advisory Integration Committee.

1.3 Research and Development Cooperation T he DOE-NE and EPRI R&D activities directed at providing the technical foundations for licensing and managing the long-term safe and economical operation of commercial nuclear power plants are described in the following documents:

l. Light Water Reactor Sustainability Program Integrated Program Plan (April 2015)

2. EPRI Long Term Operations Program Plan (July 2014).

In late 20 I 0, DOE-NE and EPRI executed a memorandum of understanding" to "establish guiding principles under which research activities (between the LWRS and LTO Programs) could be coordinated to the benefit of both parties." T his cooperation includes the sharing of responsibi lities (leadership and fi nancial) for conducting portions of large, multi-year R&D projects; the exchange of information on R&D work in areas of mutual interest; and participation in periodic conference calls and meetings (technical and budget reviews) for the other program.

a. "Memorandum of Understanding Between United States Department of Energy (DOE) and The Electric Power Research Institute (EPRI) on Light Water Reactor Research Programs," dated November I, 20 I0, and signed by John E. Kelly, Deputy Assistant Secretary for Nuclear Reactor Technologies, Office of Nuclear Energy, DOE and Neil Wilrnshurst, Vice President Nuclear, EPRI.

The work funded and managed by DOE under the LWRS Program is laid out along the fol lowing R&D pathways:b

1. Materials Aging and Degradation (MAaD)

2. Risk-Informed Safety M argin Characterization (RISMC)

3. Advanced Instrumentation, Information, and Control (Il&C) Systems T echnologies

4. Reactor Safety Technologies (RST; added in 2014).

The work funded and managed by EPRI under their LTO Program is organized and managed in the following work areas:

1. Primary System Metals Aging

2. Concrete Structures, incl uding Containment Degradation

3. Cable Aging

4. Instrumentation and Control (l&C) and Information Technology (including online monitoring of critical equipment)

5. Advanced Safety and Risk Analysis Tools

6. Aging Management Program Scope for Operation Beyond 60 Years

7. Integrated Strategy, Process Plan, and Demonstration Plants.

As acknowledged in the memorandum of understanding, " the technical areas above encompassing each participant's work scope are roughly the same;" that is, bo th organizations have the same o bjectives to deli ver technology on critical issues in a time ly manner to inform decisions on life extension and license renewal. LTO Technical Area 6, Aging Management Program Scope, currently is an ex ception for which there is no corresponding LWRS Program pathway. In a few cases, activities are highly collaborative and co-funded - both organizations fund the same activity with the same deliverable.

However, in most cases, as stated in the memorandum of understanding, " .. . the planned work in each program is distinctly different as the result of planning that reduces duplication of effort and takes into account each party's interests and strengths."

At the center of DOE's interest is work to develop new scientific knowledge, models, tools, and technology. DOE brings the strong expertise of national laboratory investigators, un ique laboratory capabilities, and relationships w ith universities and other laboratories. At the center ofEPRI' s interest are adaptation, validation, and impl ementation of technology with d eliverables such as databases, g uidelines, and pilot applicatio ns. EPRTbrings global leadership in cond uc ting publ ic interest R& D with collaboration from nuclear utilities. Through joint planning and defined cooperation, the intent is to leverage the diversity between the LWRS and LTO Programs to more efficiently and effectively meet the joint obj ectives.

b. A fifth pathway, Advanced Light Water Reactor Fuels, was transitioned to the DOE-NE Fuel Cycle R& D Program under the advanced fuels activity at the beginning of Fiscal Year 20 14 .

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2. DESCRIPTION OF RESEARCH AND DEVELOPMENT PROGRAMS 2.1 Department of Energy Office of Nuclear Energy Light Water Reactor Sustainability Program For the LWRS Program, "sustainability" is defined as the ability to maintain safe and economic operation of the existing fleet o f nuclear power plants for a longer-than-initially-licensed lifetime. It has two facets with respect to long-term operations: (l) manage the aging of hardware so the nuclear power plant lifetime can be extended and the nuclear power plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to industry to implement technology to exceed the performance of the current labor-intensive business model and practices.

In April 2010, DOE-NE's R&D Roadmap was issued. The roadmap organized DOE-NE activities in accordance with four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. Obj ective l of the roadmap focuses on developing the technologies and other solutions that can improve reliability, sustain safety, and extend the life of the current fleet of commercial nuclear power plants. The L WRS Program is the primary programmatic activity that addresses Objective I . The LWRS Program is focused on the fo llowing three goals:

1. Developing the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structures, and components (SSCs) as they age in environments associated with continued long-term operation of existing nuclear power plants

2. Applying this fundamental knowledge to develop and demonstrate methods and technologies that support safe and economical long-term operation of existing nuclear power plants

3. Researching new technologies to address enhanced nuc lear power plant performance, economics, and safety.

Through the LWRS Prog ram, DOE collaborates with ind ustry and interfaces with the U.S. Nuclear Regulatory Commission (NRC) in appropriate ways to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, nuclear power plant license extensions, and age-related regulatory oversight decisions. The DOE role focuses on aging phenomena and issues that require long-term r esearch and are generic to reactor type.

The L WRS Program consists of the follow ing primary technical areas of R&D:

1. MAaD with R&D to develop the scientific basis fo r understanding and predicting lo ng-term environmental degradation behavior of materials in nuclear power plants. The work will provide data and methods to assess the performance of SSCs essential to safe and sustained nuclear power plant operations. The R&D products will be used to define operational limits and aging mitigation approaches for materials in nuclear power plant SSCs that are subject to long-term operating conditions, providing key input to both regulators and ind ustry.

2. RISMC with R&D to develop and demonstrate approaches to support the management of uncertainty in safety margins quantificatio n to improve decision making for nuclear power plants.

This pathway will ( I) develop and demonstrate a risk-assessment method tied to safety margin quantification and (2) create advanced tools for safety assessment that enable more acc urate representation of nuclear power plant safety margins and their associated impacts on operations and economics. The R&D products will be used to produce state-of-the-art nuclear power plant safety analysis information that yields new insights on actual nuclear power plant safety and 3

operational margins and permits cost-effective management of those margins during periods of extended operation.

3. Advanced ll&C Systems Technologies with R&D to address long-term aging and modernization of current l&C technologies through development/testing of new l&C technologies and advanced condition monitoring technologies for more automated and reliable plant operation. The R&D products will be used to design and deploy new Il&C technologies and systems in existing nuclear power plants that provide an enhanced understanding of plant operating conditio ns, available margins, and improved response strategies and capabilities fo r operational events.

4. RST with R&D to improve understanding of beyond design basis events and reduce uncertainty in severe accident progression, phenomenology, and outcomes using existing analytical codes and information gleaned fro m severe accidents, in particula r the Fukushima Daiichi events. This information will be used to aid in developing mitigating strategies and improving severe accident management guidelines for the current light water reactor fl eet.

Public Law 109-58 (National Energy Policy Act of 2005 , EPAct 2005) and Congressional language establish a clear expectation that the DOE-NE funding for LWRS Program activities will be supported by industry to "cost share" the overall R&D effort. Cost sharing of LWRS Program R&D proj ects by industry ensures that federal funding is leveraged o n the most important technical challenges re lative to long-term operations of the current reactor fleet. Each LWRS Program pathway considers cost-share contributions from indusu*y as part of the R&D selection process. ln 2015, the value of industry cost sharing for LWRS Program R&D activities is approximately $30.45 millio n. This compares to 20 13 and 2014 values of $ 17 .9 million and $22.0 million, respectively. The major elements of this cost sharing include the value of in-kind contributions of services/resources (subject matter expert involvement in R&D projects, shared test data, and do nated/shared materials for testing). Details are provided in an appendix to this plan.

2.2 Electric Power Research Institute Long Term Operations Program High capacity factors and low operating costs make nuclear power plants some of the most safe and most economical power generators available. Even when major plant components must be upgraded to extend operating life, nuclear power plants often represent a safe, cost-effective, low-carbo n asset. The decision to extend nuc lear power plant life involves inter-related technical, economic, regulatory, and public policy issues. Unknown or uncerta in technical inputs impact the decision-making process both directly and indirectly: directly through design and operational contingencies and indirectly thro ugh impacts on regulatory actions and public policy.

Recognizi ng the many technical challenges confronting nuclear power plant operation, E PRI launched the LTO Project in 2009. LTO is defined as being high-performance nuclear power plant operation under extended service conditions. High performance is measured by reliability, availability, cost of operations, and safety.

The LTO Project at EPRI is justified by the potential benefits that long-term operations present to society and to member companjes. In 20 11 , the EPRI LTO Proj ect was elevated to program status and is funded by all EPRI Nuclear Sector members. However, success is contingent on timely and useful products. LTO products must provide a sound technical basis for decisio ns necessary to achieve high-performance nuclear powe r plant operation under extended service conditio ns. Specificall y, LTO Program projects must address one o r more of the fo llowing:

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l. License renewal for long-term nuclear power plant operation

2. Aging management and life-cycle management throughout long-term operation

3. Opportunities for modernization and performance improvement.

Criteria for selecting technical areas and specific work scopes within technical areas are as follows:

1. Projects address one or more of the following needs:

a. Identify and characterize (or dismiss) a potential life-limiting issue

b. Support aging management and life-cycle management

c. Provide oppo1tu11ities for modernization

d. Develop enabling technology (e.g., analysis methods) that w ill be needed to enhance performance or reduce cost.

2. Useful results are planned for the timeframe to 2019 to support the expected need for decision making.

3. It is unlikely that the planned R&D would be performed within other programs at EPRI.

4. EPRI involvement is necessary to provide industry input to R&D efforts with collaborating partners such as the DOE-NE L WRS Program or NRC 's Office of Nuclear Regulatory Research.

The R&D portfolio addresses the following seven techni-cal areas and associated principal objectives:

I. For primary system metals, characterize the conditions and parameters associated with aging degradation, develop data resources and predictive models for remaining useful life, and provide methods to mitigate risk and extend component life. Individual projects addressing this objecti ve include the following:

a. Extension of Materials Degradation Matrix and Issues Management Tables to include Failure Mechanisms to 80 Years

b. Evaluation of Crack Initiation and Propagation Mechanisms in LWR Components

c. Identifying Mechanisms and Mitigation Strategies for Irradiation-Assisted Stress Corrosion Cracking of Stainless Steel in L WR Core Components

d. Reactor Pressure Vessel (RPV) Embrittlement from Long-Term Fluence

e. Welding of lrradliated Materials for Reactor Internals Repair and Replacement.

2. For concrete structures, including containment, identify and prioritize degradation mechanisms and locations; establish methods fo r issue resolution, including new nondestructive examination (NDE) and forensic concrete examination methods; perform prognostic modeling to determine remaining useful life; and investigate mitigation measures for issues important to long-term operations.

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3. Develop the tech11ical basis for agi11g ma11ageme11t a11d life-cycle ma11ageme11t of cables, specifically, identifying cable aging management activities, classes of cables that can be life limiting, and data and methods for life-cycle management of aging cables. Enhanced testing and end-of-life predictive methods will be investigated.

4. Through support of structured pilot studies, demonstrate and document advanced I&C a11d i11jormatio11 tech11ology to address obsolescence aging of components and systems. Pilot studies will address a highly integrated control room, highly automated nuclear power plant, integrated operations, human performance improvement for field workers, outage safety and efficiency, and centralized online monitoring and information integration. EPRI will participate on a working group that oversees these studies. EPRl also will document good practices and requirements for these studies into an accessible database. For mature applications with generic applicabil ity, EPRI will develop guidelines for future applications.

5. Create adva11ced safety a11d risk a11alysis tools to address anticipated needs during the period of long-term operation and develop an approach for best estimate safety margins assessments that can identify the contributions of desig n and operational changes, aging effects, and key uncertainties.

6. Investigate aging ma11ageme11t program scope for long-term operation. Research resul.ts and operating experience might identify additional components of concern, failure mechanisms, or conditions that would be part of aging management programs for long-term operation. R&D activities will be identified where risk-important gaps exist for aging management activities, including time-limited aging assessments, one-time inspections, and periodic inspections or monitoring.

7. Develop an i11tegrated strategy, process pla11, and demonstratio11 pla11ts to support license renewal, the decision to extend operation, and life-cycle management of assets. Demonstration plants will pilot applications of monitoring methods, inspection guidelines, testing methods, demonstrations of new technologies, and analyses. The principal projects addressing this obj ective are as fol lows:

a. LTO Integration and Collaboration

b. Plant support for second license renewal (SLR) by identifying issues and developing more accurate aging assessments of key components

c. On-going linkage to the integrated life-cycle management (ILCM) software that was developed under LTO and transferred to EPRI Plant Engineering in 2015 for expanded use and long-term support.

In addition, a " living" Issue Tracking Table (ITT) maintains the status of all identified issues and assigned priorities. This table is regularly reviewed for accuracy and completeness by EPRI stakeholders, LWRS Program representatives, a working group of the Nuclear Energy Institute (NEI), and EPRT advisors. The objectives and associated projects listed in this document have been selected from high-priority issues in the ITT that meet the selection criteria and have received concurrence of the LTO Program Integration Committee. A copy of the latest ITT is inc luded as Attachment A to this plan.

Finally, it is important to emphasize that considerable supporting R&D is pursued within EPRI that is driven by current operating nuclear power plant issues rather than by a specific LTO need. For example, buried and underground piping and tank research is an area where the impact is primarily directed at resolving issues for the operating fleet with respect to identifying the extent of in-service 6

degradation and technology to detect and/or mitigate degradation. Additional areas are summarized in Section S and incl ude ILCM, Technical Bases Updates to EPRI Technical Reports to Support SLR, Buried Piping and Tanks, Nuclear Plant Chemistry, and Steam Generator Management Program. If appropriate, work with an LTO focus and objective may be identified as the in-progress R&D efforts yield data and direction.

2.3 Reporting of Research and Development Projects Consistent with the memorandum of understanding, the R&D projects described in the program plans for the LWRS and LTO Programs are presented in this joint plan using the following categories:

I. Section 3 discusses "Coordinated (but independent) Activities," meaning "in general, work in the category will be managed by either DOE or EPRI, using standard, approved processes for R&D management. Funding is also likely to be independent for work in this category. Coordination will be limited to joint planning and communications to limit possible overlaps and gaps that may exist in the planned activities."

2. Section 4 discusses "Co llaborative Activities," meaning "DOE and EPRl intend work in the category to be planned and executed on a collaborative basis. The collaborative efforts between DOE and EPRJ may involve, to a significant degree, jo int funding as permitted by law and available appropriations. DOE and EPRI will determine which organization will lead each effort based on which party is positioned to most efficiently and effectively execute the work."c

3. Section S (added in 2014) discusses "Program Unique Activities," meaning R&D activities supported by DOE-NE (under the LWRS Program) or EPRI that are not considered (per the memorandum of understanding) to be coordinated or collaborative in nature, but yet add to the body of knowledge that may be consulted by nuclear power plant owners and operators as they weigh the technology, regulatory, and business factors involved with pursuing renewals of their plant's operating license from NRC.

In Sections 3 and 4, the work of the lead program for the R&D activity is described first, followed by a similar description of the work by the supporting program (in some cases, the lead for the activity is jointly shared by the LWRS and LTO Programs).

Table 1 represents a summary overview of the joint R&D plan. The table lists (beginning in the left column) the LWRS Program's R&D activities, the corresponding (coordinated or collaborative) LTO Program's R&D activities, and the program-unique R&D activities. For the purposes of this plan, multiple R&D activities are, in selected instances, rolled up under a single heading.

c. As commined to in the memorandum of understanding, "DOE and EPRI endeavor to pla11, integrate. and prioritize nuclear R&D in Coordinated Activities and Collaborative Activities, and intend to keep each other informed of meetings. correspondence, and the status of work in order to strengthen the partnership." Further, the LWRS and LTO Programs arc committed to maintai11ing an inventory of the relevant technical results from these R&D projects and sharing each program's R&D results with the other organization.

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T a ble l Summary overview o f the 1omt

. . researc h andd eve opment pan.

LWRS Program R&D Related LTO Program R&D Coordinated Collaborative Program Unique Activity Activity Activity Activity Activity Materials Aging and Understanding, Prediction, and Degradation Mitigation of Primary System Aging Degradation Expanded Materials LWRS Degradation Assessment Materials Degradation Matrix LTO and Issues Management Tables Reactor Metals RPV - High Fluence, RPV Embrittlement from LWRS-LTO Materials Variability, Long-Term Fluence (focus on joint lead and Attenuation power reactor surveillance Effects on RPV Steels capsules irradiation and analyses)

M echanisms of IASCC: Identifying LWRS-LTO lrradiation-Assisted Mechanisms and Mitigation joint lead Stress Corrosion Strategies for IASCC of Cracking (IASCC) Austenitic Steels and LWR Core Components Irradiation Effects Irradiation Effects (core LWRS-LTO (core internals - internals - IASCC, swelling, joint lead IASCC, swelling, and and phase transformations) phase transformations)

Crack Initiation in Environmental-Assisted LWRS-LTO Ni-Base Alloys Cracking : Evaluation of Crack joint lead Initiation and Propagation Mechanisms in L WR Components Environmentally EAF - Long-term focus; EPRI LWRS-LTO A ssisted Fatigue has a short-term focus effort joint lead (EAF) (i.e., c urrent operating plants) as well Thermal Aging of Thermal Aging of CASS LWRS-LTO Cast Austenitic j oint lead Stainless Steel (CASS)

Concrete Comprehensive Aging LWRS-LTO Manage ment of Concrete joint lead Structures (Technology Roadmap) 8

Table l. Continued.

LWRS Program R&D Related LTO Program R&D Coordinated Collaborative Program Unique Activity Activity Activity Activity Activity Cabling Technical Basis for Aging LWRS-LTO Management and Life-Cycle joint lead Management of Cables Mitigation Strategies Advanced Weld Advanced Welding Methods LWRS-LTO Repair for Irradiated Materials joint lead Advanced Advanced Radiation-Resistant LWRS-LTO Replacement Alloys Materials Program joint lead Thermal (Post- LWRS Irradiation) Annealing integrated Research - Participation in Halden Project LWRS-LTO International j oint lead Activities (Halden Project)

Integrated Research - Partnership in Materials LTO lead International Ageing Institute (EPRI Activities (Materials Nuclear Sector)

Ageing Institute)

Z ion Materials LWRS Management and Coordination NOE Techno logies Opportunities to Employ NOE LWRS-LTO Technologies for Automatic, j oint lead Continuous, ln-Situ Monitoring RISMC Marg ins Analysis Enhanced Safety Analysis LWRS-LTO Techniques Modeling Capability joint lead and Simulation Activities Enhanced Risk Assessment LTO lead and Management Capability Advanced II&C Systems Techno logies New Instrumentation Requirements Database and LWRS lead a nd Control and Guidelines for Advanced l&C, Human System Human System interface, and Interfaces and Information Technology Capabilities (including Advanced Il&C Pilot Projects) 9

Table l. Continued.

LWRS Program R&D Related LTO Program R&D Coordinated Collaborative Program Unique Activity Activity Activity Activity Activity Halden Project Halden Project LWRS-LTO joint lead Centralized Online Centralized Online Monitoring LTO lead Monitoring Methodology, Guidelines, and Pilot Studies (Part of Advanced II&C Pilot Projects)

Industrial and Requirements Database and LTO lead R egulatory Guidelines for Advanced l&C, Engagement Human System Interface, and Information Technology RST Gap Analysis LWRS Accident-Tolerant LWRS Compone nts Severe Accident LWRS Analysis F ukushi ma Inspection LWRS Plan Other Projects Integrated Life-Cycle LTO Management Technical Bases Updates to LTO EPRI Technical Reports to Support SLR Buried Piping and Tanks E PRI (Plant Engineering and NDE)

Nuclear Plant Chemistry EPRI (Water Chemistry)

Steam G enerator Management EPRI (Steam Generator Management Program) 10

3. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM /

LONG TERM OPERATIONS PROGRAM - COORDINATED RESEARCH AND DEVELOPMENT ACTIVITIES MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&DArea System Aging Degradation (LTO)

Reactor Metals L WRS - RPV: High R&D Scope and Objectives:

Fluence, Materials High-Fluence Effects - The last few decades have seen remarkable progress in Variability, and developing a mechanistic understanding of irradiatio n embrittlement for RPVs.

Attenuation Effects However, significant technical issues sti ll need to be addressed to reduce the on RPV Steels uncertainties in regulatory application. T he objective of this research task is to examine and undersland the influence o f irradiatio n at high fluences on RPV embrittkment. Bo th industrial capsules and single variable experiments may be required to evaluate the potential for embrittlement and to provide a better mechanistic understanding of this form of degradation. Acquisitio n of samples from past programmatic campaigns (e.g., NRC programs), specimens harvested from decommissioned reactors (e.g., Zion Units l and 2), surveillance specimens from operating nuclear power plants, and materials irradiated in new test campaigns all have value in understanding high-tluence effects. Testing will include impact and fracture toughness evaluations, hardness, and microstructural analysis (i.e., atom probe tomography, small angle neutron scattering, and/or positron-annihilation spectroscopy). These research tasks all support development of a predictive model for transition-temperature shifts for RPV steels under a variety of conditions. This tool can be used to predict RPV embrittlement over a variety of conditions key to irradiatio n-induced changes (e.g., time, temperature, composition, flux, and fluence) and extends the current loots for RPV management and regulation to extended-service conditions. This model will be delivered in 2016 in a detailed report, along with all supporting research data. In addition, the library o f assembled materials wi ll be available for examination and testing by other stakeholders.

Materials Variabil ity and Attenuation Effects - The subject of materials variability has experienced increasing attention in recent years as additional research programs have begun to focus on development of statistically viable databases.

The objectives of this task involve developing new methods to generate meaningful data out of previously tested specimens. Embrittlement margins for a vessel can be accurately calculated with supplementary alloys and experiments using higher flux test reactors. The potential for non-conservative estimates resulting from these methodologies must be evaluated to fully understand the potential influence on safety margins. C ritical assessments and benchmark experiments will be conducted. Harvesting of through-thickness RPV specimens may be used to evaluate attenuation effects in a detailed and meaningful manner.

Testing will include impact and fracture toughness evaluations, hardness, and microstructural analysis (i.e., atom probe tomography, small angle neutron scalteri11g, and/or positron-annihilalion spectroscopy). The results of these examinations can be used to assess the operational implications of high-fluence effects on RPV. Furthermore, the predictive capability developed in earlier tasks will be modified to address these effects.

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MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO)

LTO-RPV R&D Scope and Objectives:

Embrittlement from Currently, RPV embrittlement is not considered to be a life-limiting factor for Long-Term Fluence 60 years of operatio n because of the relatively low fluence level. However, for 80 or more years, refinement of analysis, testing, and validation of embrittlement models using inadiated samples will be needed. This project will design, fabricate, and irradiate two supplemental surveillance capsules that will provide high-fluence irradiated data in approximately 2027 to support future development of embrittlement trend curves applicable for LWR operation at high fluences. This proj ect wi ll perform mechanical property testing and then microstructurally characterize pressurized water reactor (PWR) surveillance materials that were irradiated in both PWR and Advanced T est Reactor irradiation environments to identify and quantify potential flux and dose effects. In addition, there is a need to develop new testing methods to extend the use of existing surveillance specimens to generate master curve fracture toughness data. This proj ect will participate in a round ro bin test program to assess one such method that has been developed.

LWRS-RPV: Milestones:

High-Fluence, High-fluence effects:

Materials

• (20 16) Provide val idated model for transition temperature shifts in RPV Variability, and steels.

Attenuation Effects on RPV Steels Future milestones and specific subtasks will be based on the results of the previous years' testing, as well as ongoing, ind ustry-led research. The experimental data and model are of value to both industry and. regulators. Completion (in 2014) of data acquisition to permit prediction of embrittlement in RPV steels at high fl uence is a major s tep in informing life extension decisions; high-quality data can be used to inform operational decisions for RPY by industry. For example, data and trends w ill be essential in determining operating limits. Data also will allow for extension of regulatory limits and guidelines to extended service conditions. The delivery (in 2016) of a validated model for prediction of transition temperature shi fts in RPV steels will allow for estimation of RPY performance over a wide range of conditions. This will enable extension of current tools for RPV embrittlement (e.g.,

Fracture Analysis of Vessels: Oak Ridged) to extended service conditio ns.

Materials variability and attenuation effects:

• (2016) Complete a detailed review of the NRC pressurized thermal shock re-evaluation project relative to the subject of material variability and identify specific remaining issues.

• (201 9) Complete analysis of hardening and embrittlement through the RPY thickness for the Zion RPV sections.

Future milestones and specific subtasks will be based on the results of the previous years' testing, as well as ongoing, industry-led research. The analysis of hardening and variability through the thickness of an actual RPV section from service has conside rable value to all stakeholders. These data will provide a fi rst look at embrittkment trends through the thickness of the RPV wall and inform operating limits, fracture mechanics models, and safety margins.

d. NU REG/CR-6854, ORN L/fM-2004/244, Fracture Analysis of Vessels - Oak Ridge FAVOR. v04. I , Computer Code: Theo,y and J,np/e111e111ario11 ofAlgorithms, Me1hods, and Correla1ions, P. T. Williams, T. L. Dickson, and S. Yin, Oak Ridge National Laboratory, October 2004.

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MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO)

LTO-RPV Milestones:

Embrittlement from This project involves irradiation of supplemental surveillance specimens to high Long-Term Fluence tluence in a PWR. The follow-up testing and analysis must be performed in a laboratory with the capability of handling irradiated materials and reconstituting Charpy specimens. The project requires 10 or more years to complete the work.

The work w ill be coordinated with o ngoing and planned work within the PWR Materials Reliability Program and Boiling Water Reactor (BWR) Vessel and Internals Project to address RPV embriulement after extended operation.

• (2015) Continuing partic ipation in round robin testing of a new method to extend the use of existing surveillance specimens to generate Master Curve data. Having earlier tested base metal, the 2015 effort seeks to demonstrate efficacy of the method for weld metal.

• (December 2015) Design, fab ricate, and insert a supplemental surveillance capsule in a host PWR.

• (2016) Develop an updated embrittlement trend correlation for p rediction of the decrease in upper shelf enern:v with irradiation.

L WRS - Irradiation R&D Scope and Objectives:

Effects (core IASCC - The objective of this task is to assess high-fluence effects on TASCC for internals - IASCC, core internals. Crack growth-rate testing is especially li mited for high-fluence swelling, and phase specimens. lntergranular frac ture observed in recent experiments suggests more transformations) work is needed. Also of interest is identification of high-tluence materials available for research and testing in all tasks. Research will involve a detailed plan for obtaining high-fluence specimens for IASCC testing from irradiation of as-received material to high fluence in a test reactor, obtaining high-fluence materials for sample manufacturing, or a combination of those two factors. In addition, both tests (i.e., crack growth and tensile tests) wi ll be performed in simulated water environments in addition to complementary post-irradiation examination of irradiation effects. Results from this task can be used to investigate the potential for IASCC under extended service conditions, extend the mechanistic studies from other tasks in the LWRS Program, and be used to validate predictive models at high fluence.

Swelling - This task will provide detailed microstructural analysis o f swelling in key samples and components (both model alloys and service materials), including transmission electron microscopy and volumetric measurements. These results will be used to develop and validate a phenomenological model of swelling under L WR conditions. This will be accomplished by extension o f past models developed for fast reactor cond itions. The data generated and mechanistic studies will be used to identify key operational limits (if any) to minimize swelling concerns, optimize inspection and maintenance schedules to the most susceptible materials/locations, and, if necessary, qualify swelling-resistant materials for LWR service.

Phase T ransformations - This task will provide detailed microstructuraJ analysis of phase transformation in key samples and components (both model alloys and service materials), including transmission electron microscopy, magnetic measurements, and hardness examinations. Mechanical testing to quantify any impacts on embriltlement also may be performed. These results will be used to 13

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO) develop and validate a phenomenological model of phase transformation under LWR conditions. This will be accomplished through use of computatio nal thermodynamics and extension of models for radiation-induced segregation. The generated data and mechanistic studies will be used to identify key operational limits (if any) to minimize phase transformation concerns, optimize inspection and maintenance schedules to the most susceptible materials/locations, and, if necessary, qualify radiation-tolerant materials for L WR service.

L TO - Irradiation R&D Scope and Objectives:

Effects (core EPRJ work on IASCC, swelling, and phase transformations is coordinated under internals - IASCC, the Materials Reliability Program for PWRs and under the BWR Vessel and swelling, and phase Internals Program for BWRs. Significant work, incl uding international cooperative transformations) programs, is funded under these two EPRI Programs. For example, the Gondole Project is a multi-national effort that includes EPRI funding that specifically seeks to develop data via test reactor irradiation of prototypical materials to characterize irradiation-induced swelling degradation effects in stainless steels. The current Phase 2 of the project seeks to drive irradiation to doses of 30 dpa. This phase is in progress, with completion expected in 2018.

Additionally, EPR1 is performing thermal and irradiation embrittlement studies on weld material removed from the retired Zorita PWR in Spain. This information will be used to inform both PWR and BWR fracture toughness considerations.

This effort is in progress and planned for completion in 2015.

L WRS - Irradiation Milestones:

Effects (core IASCC:

internals - IASCC, * (2015) Complete revised joint plan with EPRI for very high-tluence testing swelling, and phase of core internals.

transformations)

Future milestones and specific subtasks will be based on the plan initially developed in 2013 and partnerships developed in early 20 14. Completing a detailed experimental plan for high-fluence IASCC testing was an essential first step in estimating the impact of IASCC at high fluence. This plan also is critical for building support and partnerships with industry and regulators .

Swelling:

• (2016) Deliver predictive capabil ity for swelling in LWR components.

• (2016) Complete post-irradiation testing and examination of swelling in L WR components and materials.

Future milestones and specific tasks will be based on the results of the previous years' testing, as well as ongoing, industry-led research. Development and delivery of a validated model for swelling in core internal components at high fluence is an important step in estimating the useful life of core internal components.

Understanding which components are susceptible to this form of degradation is of value to indusn*y and regulators because it will permit more foc used component inspections, component replacements, and more detailed regulatory guidelines.

Phase transformations:

• (2017) Deliver an experimentally validated, physically based thermodynamic and kinetic model of precipitate phase stabil ity and formation in Alloy 316 14

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO) under anticipated extended lifetime operation of LWRs.

Future milestones and specific tasks will be based on the results of the previous years' testing, as well as ongoing, industry-led research. Development and delivery of a validated model for phase transformations in core internal compon,ents at high fluence is an important step in estimating the useful life of the core internal components. Understanding which components are susceptible to this form of degradation is of value to industry and regulators because it will permit more focused component inspections, component replace ments, and more detailed regulatory guidelines.

L TO - Irradiation Milestones:

Effects (core * (2014) Published a report on improved void swell ing model (MRP-391, EPRT internals - IASCC, report #3002003083).

void swelling, and

• (2015) Interim results of IASCC c rack growth and irradiation embrittlement phase studies on Zorita weld and HAZ material in BWR environments.

transformations)

• (2015-2022) Additional irradiation of welds and HAZ from Zorita to assess crack growth and fracture toughness.

• (2018) Completion of Gondole Phase 2.

• (2019) Final report on Phase 2 Gondole Void Swelling Irradiation and Testing.

LWRS-Crack R&D Scope and Objectives:

Initiation in Ni-Base The objective of this task is the identification of underlying mechanisms of stress Alloys corrosion cracking (SCC) in Ni-base aUoys. Understanding and modeling the mechanisms of crack initiation is a key step in predicting and mitigating SCC in the primary and secondary water systems. An examination into the influence of surface and metallurgical conditions 0111 precursor states and crack initiation also is a key need for Ni-base alloys and austenitic stainless steels. This effort foc uses on SCC crack-initiation testing of Ni-base alloys and stainless steels in simulated LWR water chemistries, but includes direct linkages to SCC crack-growth behavior. Carefully controlled microstructure and surface states will be used to generate single-variable experiments. T he experimental effort in this tas k will be highly complementary to efforts being initiated at the Materials Ageing Institute, which are foc used primarily on modeling of crack initiation. This mechanistic information could provide key operational variables to mitigate or control SCC in these materials, optimize inspection and maintenance schedules to the most susceptible materials/locations, and potentially define SCC-resistant materials.

LTO - R&D Scope and Objectives:

Environmental-Environmental-assisted cracking of primary system components is the most Assisted Cracking:

prevalent degradatio n mechanism that directly impacts the sustainability of reliable Evaluation of Crack operation of L WRs. To achieve long-term operation, it is imperative to extend the Initiation and useful life of components in LWRs through better understanding of the crack Propagation initiation and propagation processes, improved predictive models, and identify Mechanisms in effective countermeasures against SCC. The objectives of this project include the L WR Components follow ing:

• D etermine the composition and impedance properties of metal surface oxides resulting from interaction with LWR environments, including the effects of 15

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO)

Fe'+, Ni'+, and Zn' + cations, to identify the key process leading to crackjng.

• Evaluate the effect of Fe2, Ni2, a nd Zn 2+ cations o n oxide properties .

• Investigate the influence of hydrogen partial pressure on the damage processes prior to crack initiation in Alloy 600 in PWR primary water.

• Understand the mechanistic reasons for the superior performance of Alloy 690 relative to Alloy 600, particularly in the context of long-term performance; such a mechanistic basis will support proposals for optimizing the inspection frequency of Alloy 690 components.

• Participate in a collaborative research program in Japan to deepen the understanding of interface ox idation dynamics through the use of in-situ and ex-situ measurements by synchrotron x-rays at the Spring-8 synchrotron radiation fac ility in Japan.

• Identify the mechanisms leading to decreased fracture resistance in component materials in L WR environments.

• D evelop improved prediction models of IASCC initiation and propagation and evaluation methodologies for assessing the reliability of LWR structural materials to support LTO and xLPR (Extremely Low Probability of Rupture) programs.

• D evelop strategies to mitigate the risk of environmental-assisted cracking degradation and to extend component life, based on a sound mechanistic understanding.

LWRS - Crack Milestones:

Initiation in Ni-Base Alloys

• (2015) Complete Phase 1 mechanistic testing for SCC research .

• (2019) Deliver predictive model capability for Ni-base alloy SCC susceptibility.

Completing research to identify the mechanisms and precw-sor states is an essential step in predicting the extent of this form of degradation under extended service conditions. Understanding the underlying causes for crack initiation may allow for mo re focused material inspections and maintenance, new SCC-resistant alloys, and development of new mitigation strategies, all of which are of high interest to the nuclear industry. This mechanistic understanding also may drive more informed regulatory guidel ines and aging-management programs. In the long-term, mechanistic understanding also enables development of a predictive model, which has been sought by industry and regulators for many years.

LTO - Milestones:

Environmental-Activity 1: In-situ surface oxjde film characterization and correlation between Assisted Cracking:

oxidation and crack initiation:

Evaluation of Crack Initiation and * (2014) Summarize results of in-situ surface oxide film composition and P ropagation impedance properties as functions of materials/LWR environment Mechanisms in combinations, including the effects of cations (delayed, expected completion L WR Components in 2016).

• (2013-2014) Damage Processes Prior to Crack Initiation in Ni Alloys (Published in 2013, EPRI report: 1025119).

• (2014) Summarize the results o f in-situ surface oxide structure and ox idation kinetics. (Published in 2014 as part of POLIM project performed in Japan 16

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO)

EPRI report: 3002003049).

• (September 20 I 6) Establish correlation between oxidation and crack initiation .

Activity 2: Local strain-stress behavior associated with crack:

• (2016) Establish correlation between strain rate and crack growth rate.

Activity 3: Parametric study and development of mitigation strategy:

• (2015) Summary of parametric experiments on crack growth rate .

• (2017) Develop and validate mitigation strategies.

Activity 4: Modeling:

• (2012) Program on Technology Innovation: Hybrid Models of SCC Propagation for Nickel Alloy Welds in Low-Electrochemical Po tential PWR Primary Water Environments (Pub1ished as 1024863, February 2012).

• (2016) Environmental-assisted cracking crack growth prediction model.

• (September 2019) Environmental-assisted cracking crack initiation model.

LWRS - EAF R&D Scope and Objectives:

The objective of this task is to develop a model for EAF mechanisms. This will be supporLed by experimental studies to provide data for the identification of mechanisms and key variables and provide data for model validation. The experimental data will inform regulatory and operational decisions, while the model will provide a capability to extrapolate the severity of this mode of degradation to extended-life conditions .

LTO- EAF R&D Scope and Objectives:

(long-term focus) The lack of definite design rules for EAF creates uncertainty for both new and operating nuclear power plants, where d esign compliance must be shown for the extended operating period (significant u ncertainty for a potential 80-year life). To attain acceptable fatigue usage, design c hanges that increase design, construction, and operations costs without meaningful safety benefits may be require d for previously certified designs, as well as designs currently under review by NRC.

Affected items in the design may include materials selection, piping thickness, fitting tolerances, and number and locations of piping suppo rts. Additio nally, for license renewal, there is uncertainty as to the requirements that may be imposed by NRC because the scope of locations requiring environmental fatigue analysis is open to interpretation.

Several EPRI prog rams w ill combine expertise and share final EAF results to address the current data and analysis process. Upon completion of this work, EPRI intends to work through the American Society of Mechanical Engineers (ASME )

code process to support effective code revisions that resolve the fatigue issue.

These actions will include the following:

• P ublication of reports and related documents that form the technical basis of code modifications in order to obtain code approval and regulatory acceptance, providing appropriate levels of conservatism.

• Development of EPRI guidance and code cases that provide evaluation procedures for assessing fatigue e nvironmental factors that are accepted by 17

MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO) regulatory authorities.

• Promoting an understanding of new procedures to provide for consistency of application by nuclear power plant vendors, construction firms, and utilities (new and operating plant owners).

• Supporting ASME Section III and X I code revisio ns that permane ntly include EAF procedures within the body of the code.

Note that EPRJ continues to perform projects that address fatigue and EAF in the current operating fleet. EPRI is also now considering the potential impacts of fatigue related to flexible operations.

LWRS - EAF Milestones:

• (2015) Complete base model development for EAF in LWR components .

• (2017) Complete experimental validation and deliver model for EAF in L WR components.

Comple ting research to identify the mechanisms o f EAF to support model development is an essential step in predicting the extent of this form of degradation under extended service conditions. This knowledge has been identified as a key need by regulators and industry. Delivering a model for EAF will enable more focused material inspections, material replacements, and more detailed regulatory guidelines.

LTO - EAF Milestones:

• (2012) Roadmap published (EPRl report 1026724) .

• (2013) Publish guidance for EAF methodology. (Published as EPRI report 1025823, December 2012).

• (2014) Feasibility study to determine code margins versus EAF impact (EPRI report# 3002003922).

• (2013 through 2015) Continue international research collaboration with expert panel review and advice.

• (2013 through 2016) Initiate specimen testing and R&D to resolve EAF knowledge gaps - address inconsistenc ies in test data vs. operating plants experience on crack initiation.

• (2013 through 2015): Formulate and validate models of EAF enhancement and retardation in BWR and PWR environments based on fundamental understanding of EAF.

• (2016) Develop a stakeho lder's database of al l published data .

L WRS - Thermal R&D Scope and Objectives:

Aging of CASS In this research task, the effects of elevated temperature service in CASS will be examine d. The possible effects of phase transformations that can adversely impact mechanical properties will be explored. This task is expected to provide conclusive predictions for the integrity of the CASS components of nuclear power plants during extended service life. Mechanical and microstructural data obtained through accelerated aging experiments and computational simulation will be key input for prediction of CASS behaviors and for integrity analyses for various CASS components. While accelerated aging experiments and computational simulations will comprise the main components of the knowled_ge base for CASS a11:in_g, data 18

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO) also will be obtained from operational experience. These data are required to validate the accelerated aging methodology. Therefore, in addition to us ing existing data, a systematic campaign to obtain mechanical data from used materials or components will be pursued. Further, the detailed studies on aging and embrittk ment mechanisms and on deformation and fracture mechanisms are performed to understand and predict the aging behavior over an extended lifetime.

L TO - Thermal R&D Scope and Objectives:

Aging of CASS and Review and evaluate all available data on thermal aging in ferritic-austenitic Stainless Steel Welds stainless welds and CASS material and at LWR temperatures, as wel l as effects of thermal aging on mechanical properties and corrosion resistance. Additionally, EPRI is developing probabilistic fracture mechanics evaluation and acceptance criteria for use by currently o perating nuclear power plants. A technical report has been developed and shared with ASME Code for incorporation into Code Case N-838. It is c urrently in the review/aooroval process .

L WRS - Thermal Milestones:

Aging of CASS * (2017) Complete analysis of CASS specimens harvested from service conditions.

• (2018) Complete analysis and simulatio ns on aging of CASS components and deliver predictive capability for CASS components under extended service conditions.

Completing research to identify potential thermal aging issues for CASS components is an essential step to identifying the possible synergistic effects of thermal aging (e.g., corrosion or mechanical) and predicting the extent of this form of degradation under extended service conditions. Understanding the mechanisms of thermal aging will enable more focused material inspections, material replacements, and more detailed regulatory guidelines. These data also will help close gaps identified in the EPRI Materials Degradation Matrix (MOM) and the Expanded Materials Degradation Assessment (EMDA) reports.

L TO - Thermal Milestones:

Aging of CASS and * (2014) A technical report has been developed and shared with ASME Code Stainless Steel Welds as the basis into Code Case N-838. It is currently in the review/approval process of ASME.

Mitigation Strategies L WRS - Integrated R&D Scope and Objectives:

Research/ Participate in international collaborations that offer opportunities for a broader and International more detailed research program than possible in an isolated research program.

Collaborations Coordinated research with international .institutions (such as the Materials Aging (Halden Project and Institute of which EPRI is a member) w ill provide more collaboration and cost Materials Aging sharing. In addition, research o pportunities through information exchanges with Institute) the Ha lden Proiect are a planning element of the R&D collaboration.

L TO - Integrated R&D Scope and Objectives:

Research/ Participate in international collaborations (such as the Halden Project) that offer International opponunities for a highly leveraged and more detailed research program than is Collaborations possible in an isolated research program. Coordinated research w ith the Materials (Halden Project and Aging Institute (of which EPRI is a member) will provide more collaboration and 19

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO)

Materials Aging cost sharing.

Institute)

L WRS - Integrated Milestones:

Research/ LWRS milestones related to international collaborations are identified under the International specific MAaD R&D areas.

Collaborations LTO - Integrated Milestones Research/ EPRI membership is at a level above the specific LTO Program focus, such that International LTO-relevant R&D is evaluated on a case-by-case basis.

Collaborations LWRS - NDE R&D Scope and Objectives:

NDE R&O is planned for the following MAaO R& O areas:

Concrete - Techniques for NDE of concrete provide new technologies to monitor material and compo ne nt performance. This task will bui ld on an R&O plan developed in 2012. Key issues for cons ideration can include new or adapted techniques for concrete surveillance. Specific areas o f interest may include reinforc ing steel condition, chemical composition, strength, o r stress state.

Cabling - The objectives of this task include development and validation of new NOE technologies for the monitoring of cable insulation condition. Thi s task will build on an R&D plan developed in 2012. In futme years, this research will include an assessment of key aging indicators; development of new and transformational NDE methods for cable insula tion; and utilization of NDE signals and mechanistic knowled ge from other areas of the LWRS Program to provide predictions of remaining useful life. A key element underpinning these three thrusts w i11 be harvesting of aged materials for validation.

LTO - NDE R&D Scope and Objectives:

Identifi.cation and management of aging degradation for critical structures and components is fundamental to long-term operation. One-time inspections are specified to establish the extent of degradation; periodic inspections are specified as part o f aging management programs. For quantitative and trendable results, NDE technology .is used for these inspectio ns. For so me degradation mechanisms, in-situ online monitoring that employs N DE technology can provide quantitative and sometimes predictive results. These monitoring systems can have advantages over traditional periodic inspections (e.g., cost, accuracy, radiation exposure, and prognostic capability).

The EPRJ NOE program provides NOE technology, procedures, validation, and training for identified materials, mechanisms, components, and locations of concern. This process is ongoing and robusl and is expected to be effeclive for the life of the nuclear power plant, including SLR periods. Additiona11y, the NOE program continues to investigate new technologies that may provide enhanced detectio n and fl aw characterization performance that may be incorporated into aging management programs.

The LTO Program investigates opportunities to employ NDE technologies that can be installed for automatic, continuous, in-situ monitoring for certain identified aging degradation concerns. The investigations wil l include identificati on of parameters, design of sensors and sensor configuratio ns, data capture and analysis, 20

MAaD (LWRS) / Understanding, Prediction, and Mitigation of Primary R&DArea Svstem A2in2 De2radation (L TO) validati on of the NOE/monitoring system, and demonstration of the process in an operational environment.

LWRS - NDE Milestones:

Concrete:

• (2016) Complete prototype proof-of-concept system for NOE of concrete sections.

• (2018) Complete prototype of concrete NOE system.

The development of NOE techniques to permit monitoring of the concrete and civil structures could be revolutionary and allow for an assessment of performance that is not currently available via core drill ing in operating plants. This would reduce uncertainty in safety margins and is clearly valuable to both industry and regulato rs.

Cabling:

• (2015) Complete assessment of cable insulation degradation precursors to correlate with performance and NOE signals.

• (2017) Demonstrate field testing of prototype system for NOE of cable insulation.

• (2019) Deliver predictive capability for end-of-useful life for cable insulation.

Development of NOE techniques to permit in-situ monitoring of the cable insulation performance could be revolutionary and allow for an assessment of cable insulation performance at specific locations of interest and at more frequent intervals, which is a significant difference from today's methodology. This would reduce uncertainty in safety margins and is clearly valuable to both industry and regulato rs.

LTO - NDE Milestones:

• (Ongoing) NOE-related work is reported under the topical areas as appropriate.

21

R&D Area Advanced II&C Systems Technolo2ies LWRS - R&D Scope and Objectives:

International The programs of the Halden Reactor Project (Halden) extend to many aspects of Collaborations nuclear power plant operations; however, the area of interest to this R&D (Halden Project) program is the human-machine interface technology research program in the areas o f computerized surve illance systems, human factors, a nd man-machine interac tion in support of control room modernization. Halden has been on the cutting edge of new nuclear power pla nt technologies for several decades and their research is directly applicable to the capabilities being p ursued under the pilot projects. In particular, Halden has assisted a number of European nuclear power plants in implementing II&C modernization proj ects, including control room upgrades.

The Advanced ll&C Systems Technologies Pathway will work closely with Halden to evaluate their advanced II&C techno logies to take advantage of the applicable developments. In addition to the technologies, the validation and human factors studies conducted d uring development of the technolog ies will be carefully evaluated to ensure similar considerations are incorporated into the pilot projects. Bilateral agreements may be employed in areas of research where collaborative efforts with Halden will accelerate development of the techno logies associated w ith the pilot projects.

LTO - Halden R&D Scope and Objectives:

Project EPRJ has established the Productivity Improvements through Advanced Technology Advisory Group. This group is looking at ll&C enabled productivity improvements in nuclear power plants and is interacting c losely with the LWRS Program's Advanced Il&C Systems Technologies Pathway, inc luding participating in the joint annual meeting (first meeting held A ug ust 2012). The Advanced Techno logy Advisory Group had the Halden Reactor Proj ect g ive presentations in the June 2010 and April 2012 meetings. The intent is to identify oppo rtunities to support productivity improvements in nuclear power plants, taking advantage of activities in Halde n's Man-Machine-Technology Program.

EPRI, as an associated member of the Halden Reactor Project, is providing input to Halden on their research activities in the man-machine-technology program.

LWRS - Milestones:

International

• Activities invol ving contributions fro m Halden are discussed under Collaborations individual pilot projects.

(Halden Project)

LTO - Halden Milestones:

Project EPRT membership is at a level above the specific LTO Program focus, such that LTO-relevant R&D is evaluated on a c ase-by-case basis.

R&D Area L TO - Enhanced R&D Scope and Objectives:

Risk Assessment To achieve successful long-term operations of the cwTent fleet of operating and Management nuc lear power plants, it will be imperative that high levels of safety and Capability economic performance are maintained . Therefore, operating nuclear power plants will have a continuing need to undergo design and operational changes and ma nage aging degradation, while s imultaneously preventing the occurrence of safet si nificant events and anal ti call demonstratin im roved nuclear 22

R&D Area RISMC (see "Mare ins Analysis Techniques" for LWRS cooperative R&D) safety. This portion of the EPRI LTO Program addresses the following two specific issues that are imperative to ac hieving these objectives:

(I) F irst, as the current fleet of operational nuclear power plants ages, it is a nticipated that new challenges to plant safety will emerge. These challenges could be due to any number of causes such as a change in regulatory policy or the occurrence of an event at one or more operational nuclear power plants.

(2) Second, as new technologies and capabilities become available, it wi ll be desirable to take advantage of these opportunities to enhance nuclear power plant technical and economic performance. Examples of such e nhancements could include performing extended power uprates or implementation of new technologies or materials.

In each situation, a comprehensive and integrated assessment of the impact on nuclear safety will be required to support effective and efficient decision making.

This research project will develop and validate enhanced risk assessment and management capabilities and tools. A critical element of this research effort will be to integrate the results obtained from the EPRI PHOENIX software development effort, which is being conducted to develop an advanced probabilistic risk assessment and configurat ion risk management integrated tool suite. This research effort will support development of PHOENIX by integrating risk management analytical capabilities that are necessary for nuclear power plant long-term operations (e.g., RISMC/R isk Informed Margin Management

[RIMM]) and providing for the capability of the PHOENIX software to link to the RELAP-7 software to permit its uses as a risk simulation tool. This project also provides signi ficant interface and coordination of research efforts being conducted in safety analysis code development and safety margin analyses being performed bv INL as part of the LWRS Program.

LTO - Enhanced Milestones:

Risk Assessment In previous years, this LTO research effort has supported the Phase I and and Management Phase 2 portions of the PHOENIX research effort. A key milestone provided by Capability this research was develo pment of the PHOENIX functional requirements document and roadmap (EPRI Report 1019207). During 20 13, a "beta" version of the PHOENIX software was produced that concentrates on enhanced methods for configuration risk management applications. During 2015, the support of PHOENIX development, testing, and initial deployment will continue. The following activities are planned:

• (2014) Since the basic PHOENIX infrastructure has been developed with initial testing and deployment in 2015, the level of code development s upports a more integrated interaction between the Phoenix/RAVEN/

RELAP-7 development teams. The primary activity in 2015 will be to identify and prio ritize the appropriate linkages to the Reactor Analysis and Virtual Control ENvironment (RA VEN) controller being developed for use in the interface with the RELAP-7 systems analysis code being developed by INL.

• Initiate an evaluation of PHOENIX LTO for application to LTO-related issues and to integrate necessary capabil ity development/external interfaces into the PHOENIX and RAVEN development plans.

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4. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM /

LONG TERM OPERATIONS PROGRAM-COLLABORATIVE RESEARCH AND DEVELOPMENT ACTIVITIES MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System Aging Degradation (LTO)

Reactor Metals L WRS - Mechanisms R&D Scope and Objectives:

ofIASCC The objective of this work is to evaluate the response and mechanisms of IASCC

.in austenitic stainless steels with single-variable experiments. Crack growth rate tests and complementary microstructure analysis will provide a more complete understanding of IASCC by bui lding o n past EPRI-led work for the Cooperative JASCC Research Group.° Experimental research will include crack-growth testing on hig h-fluence specimens of single-variable alloys in simulated L WR environments, tensile testing, hardness testing, microstructural and microchemical analysis, and detailed efforts to characterize localized deformation. Combined, these single-variable experiments will provide mechanistic understanding that can be used to identify key operational variables to mitigate or control IASCC, optimDze inspection and maintenance schedules to the most susceptible materials/locations, and, in the long-term, design IASCC-resistant materials.

LTO - IASCC: R&D Scope and Objectives:

Identifying A bette r fundamental understanding of key parameters that a ffect JASCC is Mechanisms and required to develop improved materials. For extended operation, JASCC is Mitigation Strategies potentially a major failure mechanism that could impact the reliability of reactor for IASCC of core internal components due to higher tluence. The metallurgical mod ifications Austenitic Steels and caused by neutron irradiation generally increase IASCC susceptibility of LWR Core austenitic stainless steels.

Components Currently, this long-term LTO project is co-funded by EPRI and DOE. The project work is performed by the University of Michigan. The objectives of this LTO project include the following:

• F ull assessment of high-purity solute addition alloys and, in particular, the roles of C, Mo, Ti, Nb, Cr+Ni, and P on crack growth rate and crack initiation.

• F ull assessment of the roles of commercial alloy microstructure on crack growth rate and crack initiation.

• Linkage between irradiated microstructure and crack growth rate or crack initiation for solute addition and commercial alloys, as well as effects of cold work and dose.

• Relation between JASCC cracking susceptibility and neutron-irradiated alloys.

• Determination of the predictive capability of crack initiation due to proton irradiation by assessment against crack initiation due to neutron irradiation.

e. EPRI, "Final Review of the Cooperative Irradiation-Assisted Stress Corrosion Cracking Research Program," Product ID.

1020986, June 3. 20 10.

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

• Role of localized deformation on the IASCC susceptibility in neutron-irradiated materials.

This LTO project o n study of IASCC mechanisms has completed the Phase 1 study, and an EPRI report has been pU!bl ished to summarize the key results from the experiments on fast neutron irradiated alloys.

In 2015, EPRI and DOE have again j ointly funded a fo llow-on study on IASCC mechanisms. The follow-on study focuses on identifying and modeling the mechanism of IASCC. The strategy for this program is to develop a model for TASCC initiation and growth based o n local ized deformation arising from irradiation-induced changes to the microstructure. The working hypothesis is to quanti fy the stress or strain at the dislocation channel-grain boundary intersectio n, which may induce fracture of the oxide film above the grain boundary.

Determination of which process is responsible for IASCC will provide a pathway to a more physically based model for cracking.

In addition to testing the neutron-irradiated stainless steels, the similar stainless steels irradiated to the similar tluence by proton i1rndiation will be tested by constant extension-rate tensile tests. The cracking susceptibilities associated with neutron irradiation and with proton irradiation will be cross compared. The role of localized deformation on lASCC susceptibility will be investigated.

The additional EPRI-funded IASCC study includes the following:

• Investigate whether small-volume mechanical testing can provide an a lternate method of assessing TASCC susceptibility to enable a potential strategy of retrieval and subsequent mechanical examination of materials from the field, in support of long-term operation.

• Compile crack growth rate data on irradiated stainless steels from several EPRI and international programs and convene an expert panel to screen the avai lable crack growth rate data on irradiated materials using appropriate screening criteria and recommend crack growth disposition curves for BWRs and PWRs to support current and long-term operation.

• Testing in-service materials harvested from L WR plants. The results from testing these plant materials will be important to validate the findings from the mechanistic stud ies currently co-funded bv EPRI and DOE.

L WRS - Mechanisms Milestones:

of IASCC * (2019) Deliver predictive model capability for lASCC susceptibility .

Detailed testing and specific subtasks will be based on the results of the previous years' testing, as well as ongoing, industry-led research. Understanding the mechanism of IASCC will enable more focused material inspections, material replacements, and more detailed regulatory guidelines. In the long-term, mechan istic understanding also enables development of a predictive model, which has been sought for IASCC for decades.

LTO - IASCC: Milestones:

Identifying * (2015) Report on key factors in IASCC initiation and propagation of Mechanisms and a ustenitic alloys in core internals and mitigation measures that could Mitigation Strategies minimize lASCC in current LWR stainless steel components (actually for IASCC of published in 2014, EPRI report: 3002003105).

Austenitic Steels and 25

MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

LWRCore * (2014) Report on improved IASCC crack growth prediction models for Components BWRs and PWRs (published in 2014, EPRI report: 3002003 103).

• (2018) Report on IASCC-resistant materials for repair and replacement.

Concrete L WRS - Concrete R&D Scope and Objectives:

Large areas of most nuclear power plants have been constructed using concrete; there are some data on performance through the first 40 years of service. In general, the performance of reinforced concrete structures in nuclear power plants has been very good. Although the vast majority of these structures will continue to meet their fu nctional or performance requirements during the current and any future licensing periods, it is reasonable to assume that there will be isolated examples where, primarily as a result of environmental effects, the structures may not exh ibit the desired durability (e.g., water-intake structures and freezing/thawing damage of containments) without some form of intervention.

Although a number of organizations have sponsored work addressing the aging of nuclear power plant structures (e.g., NRC, Nuclear Energy Agency, and International Atomic Energy Agency), there are still several areas where additional research is desired to demonstrate that the structures will continue to meet functional and performance requirements (e.g., maintain structural margins).

Structural research topics include ( 1) compi lation of material property data for long-term performance and trending, evaluation of environmental effects, and assessment and validation of NDE methods; (2) evaluation of long-term effects of elevated temperature and radiation; (3) improved damage models and acceptance criteria for use in assessments of the cmrent and future condition of the structures; (4) improved constitutive models and analytical methods for use in determining nonlinear structural response (e.g., accident conditions); (5) nonintrusive methods for inspection of thick, heavily reinforced concrete structures and basemats; (6) global inspection methods for metallic pressure boundary components (i.e., liners of concrete containments and steel containments), including inaccessible areas and the back side of liner; (7) data on application and performance (e.g.,

durability) of repair materials and techniques; (8) utilization of structural reliability theory, incorporating uncertainties to address time-dependent changes to structures to enstu*e that minimum accepted performance requirements are exceeded and to estimate ongoing component degradation of estimate end-of-life; and (9) appl ication of probabilistic model ing of component performance to provide risk-based criteria to evaluate how aging affects structural capacity.

Complementary activities are being conducted under an NRC program at Oak Ridge National Laboratory, by EPRI and by the Nuclear Energy Standards Coordination Collaborative, which is headed by the National Institute for Standards and Technology.

Plans for research at EPRI and NRC will continue to be evaluated to confirm the complementary and cooperative nature of concrete research under the MAaD Pathway. In addition, formation of an Extended Service Materials Working Group for concrete issues will provide a valuable resource for additional and diverse input.

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

LTO- R&D Scope and Objectives:

Comprehensive Aging Adequate understanding and (where necessary) inspection techniques of concrete Management of c ivi l infrastructure in commercial nuclear power plants is an essential need for Concrete Structures comprehensive decision making for long-term operation. There are a variety of kinetic processes that can lead to degradation of c ivil structures and these may be accelerated by operating environments specific to nuclear power plants. It is important that industry understand the impact of accelerated aging of civil infrastructure, particularly for LTO, as individual utilities will be required to prov.ide both sound technical and economic justificatio ns for long-term operation.

The interim goal of this project is to create a project that looks at various degradation phenomena being experienced in operating nuclear power plants. The initial stage of the project compiled an Aging Reference Manual, whic h defined the physics of kinetic degradation processes and discussed operational issues dealt with by the industry over the past 40+ years. The manual contains a framework for identifying at-risk structures and applicable degradation mechanisms. More recently, the NRC published Volume JV of the EMDA (NUREG/CR-7153),

which prioritized aging degradation issues in concrete. Building on these guiding documents, a number of individual research projects, aimed at further understanding of those degradation mechanisms and structures identified as "at-risk," have been and will continue to be undertaken. The results of the individual studies will be merged into an Aging M anagement Toolbox Platform, which will be an open-ended tool for operators to assess the severity of damage and explore repair or mitigation options. It is anticipated that these investigations will yield one or more industry examination guidelines for concrete aging assessment(s).

Key areas of research will cover aging degradation due to irradiation a nd thermal environments, risks and impact of alkali silica reaction (ASR), and assessment of nuclear power plant risks due to concrete creep effects. Related work covering spent fuel pools, including boric acid corrosion assessment, will be addressed.

L WRS - Concrete Milestones:

• (2015) Deliver unified parameter to assess irradiation-induced da mage in concrete structures.

• (201 8) Complete model tool to assess the impact of irradiation on structural performance fo r concrete components.

• (2020) Complete model tool to assess the combined effects of irradiation and a lkali-silica reactions o n structural performance for concrete components.

Future milestones and specific tasks will be based on the results of the previous years' testing, as well as ongoing, industry-led research. The database of concrete performance completed in 2013 is a high-value tool accessible to all stakeholders, is being used to focus research on the remaining knowledge gaps, and will enable more focused material inspections. In the long-term, completion of a concrete and c ivil structures toolkit may allow for more robust prediction of concrete performance over extended service conditions. These tools are of high value to industry, which is a partner in their development.

LTO - Milestones:

Comprehensive Aging * (2014) Initial report o n preliminary findings of the effect of irradiation Management of damage on reactor cavity concrete (Completed - EPRI Report 3002002676).

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

Concrete Structures

• (2013) Containment aging pilot plant investigation Outage 2011 and Outage 2012 reports (results of destructive examination/NOE at Ginna and Nine Mile Point); industry guideline(s) for examination of structures for concrete aging (Completed - EPRI Report 3002002335).

• (2014) Literature review of creep in concrete post-tensioned containment structures (Completed - EPRI Report 3002003220).

• (2016) Report on experimental study of the effects of boric acid corrosion o n concrete.

• (2015) Report on risk screening for ASR in concrete structures in existing plants.

• (2016) Report on radiation damage effects on concrete.

• (2018) Complete concrete and civil infrastructure toolbox develo pment with DOE and Materials Ageing Institute partners.

Cabling L WRS - Cabling R&D Scope and Objectives:

Cable aging mechanisms and degradation is an important area of study. Nuclear power plant operators carry out periodic cable inspections using NOE techniques to measure degradation and determine when replacement is needed. Degradation of cables primarily is caused by long-term exposure to high temperatures.

Additionally, stretches of cables that have been buried underground are frequently exposed to groundwater. Wholesale replacement of cables is econo mjcally undesirable for long-term nuclear power plant operation.

This task provides an understanding about the role of material type, history, and the environment on cable insulatio n degradation; understanding of accelerated testing limitations; and support to partners in modeling activities, surveillance, and testing criteria. This task will provide experimental characterization of key forms of cable and cable insulation in a cooperati ve effort with NRC and EPRI.

Tests will include evaluations of cable integrity following exposure to elevated temperature, humidity, and/or ionizing irradiation. These experimental data will be used to evaluate mechanisms of cable aging and determine the validity or limitations of accelerated aging protocols. The experimental data and mechanistic studies can be used to help identify key operational variables related to cable aging, optimize inspection and mainte nance schedules to the most susceptible materials/locations, and, in the long-range, design tolerant materials.

L TO - Advanced R&D Scope and Objectives:

Cable Testing In 2014, a technical update will be issued on progress made to-date on our Technology for radiation and temperature monitoring Phase II efforts. We are on track to install Life-Cycle the first set of data loggers in a PWR i.n Fall 2015. This is a follow-up to the 2013 Management of research to identify actual containment temperature; dose conditions in actual Cables cable locations will continue. The 2013 collection of data did support the belief that cables see only a fraction of the dose used for environmental qualification, but the data could not be correlated to actual cable locations. The second major effort in 2015 is the harvesting of service-aged cables for accelerated cable aging research in the areas of inverse temperature, diffusion-limited oxidation, and fill gaps in the existing thermal and thermal/radiation models for the most often used cable types.

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

Associated work of interest to LTO is being funded by EPRI's Plant Engineering group to develop the technical basis for aging management and life-cycle management of cable systems.* Specifically, EPRI is performing a submergence qualification for Kerite ethylene propylene rubber insulation and plans are to add pink Okonite ethylene propylene rubber to the proj ect this year. An aging acceleration regime is being attempted in this project using high freque ncy (i.e.,

450 Hz and 900 Hz), along with 2.5 times line voltage. Additionally, research on medium voltage water-related degradation is continuing in 2015 to ide ntify causes of insulation breakdown. Analysis of member-provided Tan 8 data and EPRl-recomrnended acceptance criteria has been validated to classify the degree of wet cable insulation degradation. A report on the data collected since the release of EPRTReport 1025262 in July 2012 will be issued later in 2015. EPRT's Plant Engineering group continues to support aging management implementation through the cable user group meetings . All of these proj ects support identifying cable system aging management activities, the portions of the cable system having limited life, and data and methods for life-cycle management of aging cable systems. Enhanced testing and e nd-of-life predictive methods wrn continue to be investigated.

• Cable systems include the field cables, their terminations and splices, and local wiring, as well as the suooort and protective systems such as trays, conduits, and ducts.

L WRS - Cabling Milestones:

• (2016) Complete analysis o f key degradation modes o f cable insulation.

• (2017) Complete assessment of cable degradation mitigation strategies.

• (2019) Deliver predictive model for cable degradation.

Future milestones and specific tasks will be based on the results of the previous years' testing, as well as ongoing, industry-led research. Completing research to identify and understand the degradatio n modes of cable insulation is an essential step to predicting the performance of cable insulation under extended service conditions. These data are critical to developing and delivering a predictive model for cable insulation degradatio n. Both will enable more focused inspections, material replacements, and better-informed regulations. The development of in-situ mitigation strategies also may a llow for an alternative to cable replacement and would be of high value to industry by avoiding costly replacements.

L TO - Advanced Milestones:

Cable Testing

• (June 2015) Harvesting and distribution of service aged cables from Crystal Technology for River Unit 3 to research proj ects on EMDA gaps of will be completed.

Life-Cycle Management of * (August 201 5) F inalize research needed based on analysis o f existing cable Cables aging research data gaps for major cable types needed to be addressed to qualify condition and remaining useful life.

• (September 2015) Technical update for Phase II of the radiation and temperature monitoring data collection will be issued on the methods and process for data collection.

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

Miti2ation Strate2ies L WRS - Advanced R&D Scope and Objectives:

Weld Repair The objective of this task is to develop advanced welding technologies that can be used to repair highly irradiated reactor internals witho ut helium-induced cracking.

Research includes mechanistic understanding of helium effects in weldments.

This modeling task is supported by characterization of model alloys before and after irradiation and welding. This model can be used by stakeholders to further improve best practices for repair welding for both existing technology and advanced technology. In addition, this task will provide validation of residual stress models under development using advanced characterization techniques such as neutron scattering. Residual stress models also will improve best practices for weldments of reactors today and under extended service conditions. These tools could be expanded to include other ind ustry practices such as peening.

Finally, advanced welding techniques (such as friction-stir welding, laser welding, and hybrid techniques) will be developed and demonstrated on relevant materials (model and service alloys). C haracterization of the weldments and qualifitcation testing will be an essential step. To realize this step, a unique facility (welding c ubicle for hot cell service) has been constructed in partnership with EPRI to develop advanced welding techniques on irradiated materials.

LTO - Advanced R&D Scope and Objectives:

Welding Methods for As the existing L WR fleet ages, the weldability of the structural material used to Irradiated Materials construct the RPVs and reactor internals may be diminished. The decrease in weldability is caused by formation of helium in the base material struc ture. This is caused by nuclear transmutation reactions of boron and nickel within the reactor materials and increases as neutron tluence accumulates. Helium-induced weld cracking is a complex phenomenon that is related to the concentration of helium in the material, heat input of the weldi ng technique used, and stresses during cooling of the weld. Modest improvement in the weldability of irradiated material can be achieved by lowering the heat input using conventional laser beam welding, but once stainless steel components reach a certain fluence (typically at 20 to 30 years of exposure), some may be welded by current welding methods. As nuclear power plants age further (40 years and beyond) consideration of the embrittlement effect of helium on weld repair becomes critical. The development of advance weldi ng processes (hybrid fusion and solid state) is needed to extend the weldability of these irradiated reactor components.

There is significant justification for development of advanced welding methods to repair irradiated reactor materials. However, development of advanced welding processes for repair of irradiated reactor components is a relatively complex task and will take both fundamental rese.u*ch related to welding of irradiated materials and refinement of existing welding technologies. This is a relatively long-lead-time development process and research needs to be started now if welding repair options are to be available for reactor material and internals as they age and require repair or replacement. Expected work includes the following:

• Perform review and prepare summary report on advanced welding processes a nd the potential appl ication for welding of irradiated reactor components in the underwater environment. Processes being considered are Low force friction stir welding 30

MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

Low force friction stir cladding Auxiliary beam laser welding Low dilution laser beam welding

• Prepare a detailed project plan for the multi-year project Sample irradiation plan Welding hot cell design/fabrication/installation Advanced weld ing equip ment technical requirements and p rocurement specification Welding experiments to benchmark models and provide process development/refi nement Budgeting and detailed task planni ng

• Design and procurement of a stainless steel sample set for irradiation.

Proj ect tasks are funded by the LTO Program and the DOE LWRS Program, with some tasks being co-funded. LTO-related work supported by the LWRS Program is performed at Oak Ridge Nationa l Laboratory. The Oak Ridge National Laboratory scope will focus o n development of fundamental science for developing predictive models and simulations for advanced welding processes and measure ment of residual stress at high temperatures.

Oak Ridge National Laboratory has the following facilities to achieve the proj ect goals:

• H igh-Flux Isotope Reactor - Irradiation of the sample set will occur at this facility, as well as potential measmement of residual str esses at high temperature.

• Material Process Hot Cell - Welding of irradiated material requires facilities that can remotely handle radioactive materials.

• A dvanced Microstructure Characterization Laboratory - Examination of rad ioacti ve material at the sub-grain level is a unique capability of Oak R idge National Laboratory.

L WRS - Advanced Milestones:

Weld Repair * (201 5) Demonstrate initial solid-state welding on irradiated materials.

• (20 J 8) Complete transfer of weld-repair technique to industry.

Future milestones and specific tasks w ill be based on the results of the previous years' testing, as well as o ngoing, industry-led research. Demonstration of ad vanced weldment tech niques for irradiated materials is a key step in validating this mitigation strategy. Successful deployment also may allow for an alternative to core internal replacement and would be of high value to industry by avoiding costly replacements. Further, these techno logies also may have utility in repair or compo nent replacement applications in other locations w ithin a nuclear power plant.

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

L TO - Advanced Milestones:

Welding Methods for * (2013) Completed sample set fabrication.

Irradiated Materials

• (2014) Initial irradiation campaign for sample set.

• (2014) Complete fabrication of welding cubicle.

• (2014) Published three technical reports (3002003143, 3002003146, 3002002954).

• (2015) Installation of welding cubicle at Oak Ridge National Laboratory.

• (20 15) Initial welding experimen ts on irradiated material sample set.

L WRS - Advanced R&D Scope and Objectives:

Replacement Alloys Advanced replacement alloys for use in LWR applications may provide greater margins of safety and performance and provide support to industry partners in their programs. This task will explore and develop new alloys in collaboration with the EPRl Advanced Radiation-Resistant Materials Program. Specifically, the LWRS Program will pa1ticipate in expert panel groups to develop a compre hensive R&D plan for these advanced alloys. Future work will include alloy development, alloy optimization, fabrication of new alloys, and evaluation of their performance under LWR-relevant conditions (e.g., mechanical testing, corrosion testing, and irradiation performance among others) and, ultimately, validation of these new alloys. Based o n past experience in alloy development, an optimized alloy (composition and processing details) that has been demonstrated in relevant service conditions can be delivered to industry by 2020.

L TO - Advanced R&D Scope and Objectives:

Radiation-Resistant EPRI has initiated a new .international collaborative project with DOE on Materials Program development of radiation-resistant materials for L WR applications. EPRI and DOE have jointly prepared a comprehensive report on the state of current knowledge of radiation-induced degradation in LWRs and a roadmap to develop and qualify more radiation-resistant materials. The report was prepared by a team of world-class experts and widely reviewed by the international research community. The roadmap w ill be used to formulate a long-range R&D plan to develop improved materials for long-term operation of cuJTent and new nuclear power plants.

L WRS - Advanced Milestones :

Replacement Alloys * (2017) Complete down-select of candidate advanced alloys following ion irradiation campaign.

• (2024) Complete development and testing of new advanced alloy with superior degradation resistance with Advanced Radiation-Resistant Materials partners.

Future milestones and specific tasks will be informed by EPRl's Advanced Radiation-Resistant Materials Program plan that was released in 2013 and j oint assessment of partnerships and available funding. Completing the join t effort with EPRI on the alloy down-select and development plan is an essential first step in this alloy development task. This plan will. he lp identify future roles and responsibilities in this partnership with EPRI.

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MAaD (L WRS) / Understanding, Prediction, and Mitigation of Primary R&D Area System A2in2 De2radation (LTO)

LTO - Advanced Milestones:

Radiation-Resistant * (201 5) Interim report on the results of Phase 1, documenting the results of Materials Program microstructural, mechanical, and SCC studies on proton-irradiated commercial alloys to identify promising materials for further evaluation in Phase 2.

• (2017) Final report on the results of Phase l , recommending alloys for further evaluation under neutron irradiation.

• (201 9) Interim report on the results of Phase 2, documenting microstructural, mechanical, and SCC studies on neutron-irradiated commercial a nd advanced alloys.

• (2022) Final report on the results of Phase 2, identify ing one or two radiation-resistant commerc ial alloys for LWR internals.

R&DArea Advanced II&C Systems Technolo2ies LWRS - New R&D Scope and Objectives:

Instrumentation and This research pathway will address aging and long-term reliability issues of the Control and Human legacy II&C systems used in the current LWR fleet by demonstrating new System Interfaces technologies and operational concepts in actual nuclear power plant settings. This and Capabilities approach drives the following two important outcomes:

(including Advanced

• Reduces the technical, financial, and regulatory risk of upgrading the aging Il&C Pilot Projects)

II&C systems to support extended nuclear power plant life to and beyond 60 years.

• Provides the technological fou ndation for a transformed nuclear power plant operating model that improves plant performance and addresses the challenges of the future business e nvironment.

The research program is being conducted in close cooperation with the nuclear utility industry to ensure that it is respo nsive to the challenges and oppo rtunities in the present operating environment. The scope o f the research program is to develop a seamless integrated digital environment as the basis of the new operating model.

A Utility Working Group, composed of lead ing nuclear utilities across the industry and EPRI, advises the program. The Utility Working Group d eveloped a consensus vision of how more integrated, modernized plant H&C systems could address a number of challenges to the fong-term sustainability of the L WR fleet. r A strategy was developed to transform the nuclear power plant operating mode l by fi rst definin g a future state of plant o perations and support based on advanced technologies and then developing and d emonstrating the needed technologies to individ ually transform the plant's work activities. The collective work activities are grouped into the following maj or areas of enabling capabilities:

1. H uman performance improveme nt fo r nuclear power plant field workers

2. O utage safety and e fficiency

f. Long-Term Instrumentation, lnfonnation, and Control Systems (ll&C) Modernization Future Vision and Strategy.

INUEXT-11 -24 154, Revision 3, November 20 13.

33

R&DArea Advanced II&C Systems Technolo2ies

3. O nline monitoring

4. Integrated operations

5. A uto mated nuclear power plant

6. Hybrid control roo m.

In each of these areas, a series of pilot projects are planned that enable the development and deployment of new Il&C technologies in existing nuclear power plants. A pilot project is an indi vidual R &D project that is part of a larger strategy needed to achieve modernization according to a plan. Note that pilot proj ects have value o n their own, as well as collectively. A pilot proj ect is small enough to be undertaken by a single utility, it demonstrates a key technology or outcome required to achieve success in the higher strategy, and it supports scaling that can be replicated and used by other nuclear power plants. Through the L WRS Program, individual utilities and nuclear power plants are able to partic ipate in these projects or otherwise leverage the results of proj ects conducted at demons tration plants.

The pilot projects conducted through this pathway serve as stepping stones to achieving longer-term o utcomes of sustainable ll&C technologies. They are designed to emphasize success in some crucial aspect of nuclear power plant technology refurbishment and susta inable modernization. They provide the opportunity to develop and demonstrate methods for technology development and deployment that can be broadly standardized and leveraged by the commercial nuclear power fleet. Each of the R&D acti vities in this program achieves a part of the longer-term goals of safe and cost-effective sustainability. They are limited in scope so they can be undertaken and implemented in a manner that minimizes technical and regulatory risk. In keeping with best industry practices, p rudent change management dictates that new technologies are introduced slowly so that they can be validated within the nuclear safety culture model.

L TO - Requirements R&D Scope and Objectives:

Database for EPRT will participate in the L WRS Program working group for Advanced JT&C Advanced l&C, Systems Technologies. This working group includes utility representatives from Human System Exelon, Entergy, Duke, Southern, South Texas Proj ect, Arizona Public Service, Interface, and Constellation, Progress, Tennessee Valley Authority, and the STARS Alliance.

Information Through the working group, the L WRS Program is sponsoring pilot studies of Technology advanced applications of l&C and other information technology p rojects at individ ual utilities. The LWRS Program also has developed a Human Systems Simulation Laboratory to support these applications and to perform related R&D at lNL. The Human Systems S imulatio n Laboratory employs 15 bench-board-style to uch panels that resemble the control panels currently used in nuclear power plants. This equipment is capable of running nuclear power plant simulators to produce a high-fi delity control room environment for control room modernization R&D. EPRI will participate in these activities on behalf of the LTO project membership. EPRI will interact with the working group on the LTO requirements database activities. EPRI is making relevant EPRI technical reports available to INL fm work in the LWRS Program Advanced II&C Systems Technologies area.

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R&DArea Advanced II&C Systems Technolo2ies LWRS - New Milestones:

Instrumentation and Human performance improvement for nuclear power plant field workers:

Control and Human * (2015) Conclude the fi eld evaluation of the added functionality and new System Interfaces design concepts of the prototype computer-based procedures system, and Capabilities evaluating at a host utility the revisions made to the system to ensure it (including advanced encompasses a broad variety of prncedures, instructions, and usage Il&C pilot projects) scenarios.

• (2015) Develop an automated work package prototype that supports paperless work flow and improved human performance.

• (2017) Integrate the automated work package with a wireless plan t smveillance system and demonstrate self-documenting work packages for nuclear power plant surveillances.

• (2017) Publish a report on automated work package implementation requirements for both nuclear power plant field worker usage and self-doc umenting surveillances.

• (2017) Develop and demonstrate augmented reality technologies for visualization of radiation fields for mobile plant workers.

• (2018) Develop and demonstrate augmented reality technologies for v isualization of real-time plant parameters (e.g., pressures, flows, valve positions, and restricted boundaries) for mobile plant workers.

• (2019) Publish a techn ical report on augmented reality technologies de veloped for nuclear power plant field workers, enabling them to visualize abstract data and invisible phenomena, resulting in significantly improved situational awareness, access to context-based plant information, and generally improved effectiveness and efficiency in conducting field work activities.

Outage safety and efficiency:

• (2015) Develop improved graphical displays for an Advanced Outage Control Center, employing human factors principles for effective real-time collaboratio n and collective situational awareness.

• (201 6) Develop technology for real-time plant configuration status during outages to improve work coordination, efficiency, and safety margin .

• (2017) Develop and demonstrate (in the Human Systems Simulation Laboratory) technologies for detecting interactions between plant status (configuration) states and concurrent component manipulations d irected by in-use procedures in consideration of regulatory requirements, technical specifications, and risk management requirements (defense-in-depth).

• (2018) Develop and demonstrate (in the Human Systems Simulation Laboratory) techno logies to detect undesired system configuratio ns based on concurrent work activities (e.g., inadvertent drain paths and interaction of clearance boundaries).

• (20 l 9) Develop a real-time outage risk management strategy and publish a technical report to improve nuclear safety during outages by detec ting configuration control problems caused by work activity interactions with changing system alignments.

Integrated operations:

• (2017) Develop and demonstrate (in the Human Systems Simulation 35

R&DArea Advanced II&C Systems Technolo2ies Laboratory) concepts for an advanced online monitoring facility that can collect and organize data from all types of monitoring systems and activities and can provide visualization of degradation where applicable.

• (201 8) Develop and demonstrate (in the Human Systems Simulation Laboratory) concepts for real-time information integration and collaboration on degrading component issues with remote parties (e.g., control room, outage control center, systems and component engineering staff, internal and external consultants, and suppliers).

• (2019) Develop a digital architecture and publish a technical report for an advanced online monitoring facility, providing long-term asset management and providing real-time information directly to control room operators, troubleshooling and root cause teams, suppliers and technical consultants involved in component support, a nd engineering in support of the system health program.

• (2019) For chemistry activities, conduct a study and publish a technical report on opportunities to provide remote services from centralized or third-party service providers, based on advanced real-time communication and collaboration technologies built on the digital architecture for a highly automated plant. Demonstrate representative remote activities with a host plant.

• (20 19) Develop and demonstrate (in the Human Systems Simulation Laboratory) concepts for a management decision support center that incorporates advanced communication, collaboration, and display technologies to provide enhanced situational awareness and contingency analysis.

• (2020) For maintenance activities, conduct a study and publish a technical report on opportunities to provide remote services fro m centralized or third-party service providers, based on advanced real-time communication and collaboralion technologies built on the digital architecture for a highly auto mated plant. Demonstrate representative remote activities with a host plant.

• (202 1) For radiation protection activities, conduct a study and publish a technical report on oppo1tunities to provide remote services from centralized or third-party service providers, based on advanced real-time communication and collaboration technologies built on the digital architecture for a highly auto mated plant. Demonstrate representative remote activities with a host plant.

• (2022) Publish human and organizational factors studies and a technical report for a virtual plant support organization technology platform consisting of data sharing, communications (voice and video), and collabora tion technologies that will compose a seamless work environment for a geographically dispersed nuclear power plant support organizatio n.

• (2024) Develop and demonstrate (in the H uman Systems Simulation Laboratory) concepts for advanced emergency response facil ities that incorporate advanced communication, collaboration, and display technologies to provide enhanced situational awareness and real-time coordination with the control room, other emergency response fac ilities, field teams, NRC, and other emergency response agencies.

• (2025) Publish human and organizational factors studies and a technical 36

R&D Area Advanced II&C Systems Technolo2ies report for a management decision support center consisting of an advanced digital display and decision-support technologies, thereby enhanc ing nuclear safety margin, asset protection, regulatory performance, and production success.

Automated plant:

• (2015) Complete a digital architecture requirements report documenting the information technology requirements for the advanced digital technology envisioned to be applied to nuclear power plant work activities.

• (20 15) Complete a digital architecture gap analysis report documenting the gap between current typical instrumentation & control and information technology capabilities in nuclear power plants versus those documented in the digital architecture requirements report.

• (20 17) Complete a digital archi.tecture implementation gu.ideline, documenting a graded approach in applying the conceptual model to selected digital technologies and in determining the incremental information technology requirements based on a current state gap analysis.

• (2017) For nuclear power plant operations activities, analyze the staffing, tasks, and cost models to identify the opportunities for application of digital technologies to improve nuclear safety, effi ciency, and human performance based on optimum human-technology function allocation. Demonstrate representative activities as transformed by technology, with results published in a technical repo1t.

• (20 18) For nuclear power plant chemistry activities, analyze the staffing, tasks, and cost models to identify opportunities for application of digital technologies to improve nuclear safety, efficiency, and human performance based on opti mum human-technology fu nction allocation. Demonstrate representative activities as transformed by technology, with results published in a technical repo,t.

• (20 19) For nuclear power plant maintenance activities, analyze the staffing, tasks, and cost models to identify opportunities for application of digital technologies to improve nuclear safety, efficiency, and human performance, based on opti mum human-technology fu nction allocation. Demonstrate representative activities as transformed by technology, with results published in a technical report.

• (2020) For nuclear power radiation protection activities, analyze the staffing, tasks, and cost models to identify opportunities for application of digital technologies to improve nuclear safety, efficiency, and human performance based on optimum human-technology fu nction allocation. Demonstrate representative activities as transformed by technology, with results published in a technical report.

• (2021) Develop and demonstrate (in the Human Systems Simulation Laboratory) prototype plant control automation strategies for representative normal operations evolutions (e.g., plant start-ups and shut-downs, equipment rotation alignments, and test alignments).

• (2024) Develop and demonstrate (in the Human Systems Simulation Laboratory) prototype plant control automation strategies for representative plant transients (e.g., loss of primary letdown flow or loss of condensate pump).

• (2025) Develop the stratee:v and priorities and publish a technical report for 37

R&DArea Advanced II&C Systems Technolo2ies automating operator control actions for important plant state changes, transients, and power maneuvers. resulting in nuclear safety and human performance improvements fo unded on engineering and human factors pr inciples.

Hybrid control room:

• (2015) Develop a distributed control system prototype. Using a participating utility's simulator plant model installed at the Human Systems Simulation Laboratory, develop a functional prototype for the turbine control system uiPgrade. Document the design, development, and functionality of the prototype replacement system.

• (2015) Develop prognostic software for control indicators. Provide demonstration and software for the prognostic system and display interface for installation at the Human Systems Simulation Laboratory.

• (2015) Develop operator performance metrics for verification and validation .

Document the process of how simulator studies should be performed, including the various operator performance metrics that can be collected in support of control room upgrades.

• (2015) Develop a prototype of an advanced hybrid control room in the Human Systems Simulation Laboratory that includes advanced Ojperator interface technologies such as alarm management systems, computerized procedures, soft controls, large dilsplays, and operator support systems.

• (20 15) Test Human Systems Simulation Laboratory systems in preparation for conducting benefits study with operators. Test Human Systems Simulation Laboratory systems in representative configurations to verify that systems are able to function reliably in operational sequences and scenarios, test data logging and collection systems, and verify the stability of different combinations of digital systems with human interactions in preparation for data collection with actual operating crews.

• (2017) Publish a report documenting the Control Room Upgrades Benefit Study that presents the data, findings, and conclusions on performance improvements that can be obtained thrnugh the technologies of an advanced hybrid control room.

• (2017) Develop concepts for using nuclear power plant full-scope simulators as operato r advisory systems in hybrid control rooms and complete a technical report on prototype demonstrations in the Human Systems Simulation Laboratory.

• (2018) Develop concepts for a real-time plant operational diagnostic and trend advisory system with the ability to detect system and component degradation and complete a technical report on prototype demonstrations in the Human Systems Simulation Laboratory.

• (2019) Develop an operator advisory system fully integrated into a control roo m simulator (Human Systems Simulatio n Laboratory) that provides plant steady-state performance monitoring, diagnostics and trending of performance degradation, operato r alerts for intervention, and recommended actions for problem mitigation, with appl ication of control room design and human factors princ iples.

• (2020) Complete a technical report on operator attention demands and limitations on operator activities based on the current conduct of operations 38

R&DArea Advanced II&C Systems Technolo2ies protocols. This report will identify opportunities to maximize operator efficiency and effectiveness with advanced digital technologies.

• (2021) Develop an end-state vision and implementation strategy for an advanced computerized operator support system, based o n an operator advisory system that provides real-time situational awareness, prediction of the future plant state based on current conditions and trends, and recommended operator interventions to achieve nuclear safety goals.

• (2023) Develop and demonstrate (in the Human Systems Simulation Laboratory) prototype mobile technologies for operator situational awareness and limited plant control capabilities for nuclear power plant support systems (e.g., plant auxiliary systems operations and remote panel operations).

• (2024) Develop and demonstrate (in the Human Systems Simulation Laboratory) new concepts for remo te operator assistance in high activity periods (e.g., refueling outages) and accident/security events, allowing offsite operators to remotely perform low safety-significant operational activities, freeing the control room o perators to concentrate o n safety functions.

• (2025) Develop validated future concepts of operations for improvements in control room protocols, staffing, operator proximity, and control room management, enabled by new technologies that provide mobile information and control capabilities and the ability to interact with other control centers (e.g., emergency response fac ilities for severe accident management guidelines implementation).

L TO - Requirements Milestones:

Database for Advanced l &C,

• (2013) Summary Report on Database Su*ucture Capability Levels and Simple Prototype (Published - EPRI report 3002000503).

Human System Interface, and * (2014) Guidance for Developing a Human Factors Engineering Program for an Operating Nuclear Power Plant (Published - EPRI report 3002002770).

I nformation Technology The following deliverables wi ll be j ointly developed by LWRS and LTO and are listed identically as milestones for each program:

• (2016) Publish interim guidelines to implement technologies for improved outage safety and efficiency.

• (2016) Publish revised interim guidelines to implement technologies for human performance improvement for nuclear power plant field workers.

• (201 8) Publish interim guidelines to implement technologies for a hybrid control room.

• (2018) Publish final guidelines to implement technologies for improved outage safety and effic iency.

• (2019) Publish final guidelines to implement technologies for human pe rformance improvement for nuclear power plant field workers.

• (2020) Publish interim guidelines to implement technologies for integrated operations.

• (2021) Publish interim guidelines to implement technologies for an automated plant

• (2021) Publish revised interim gu idelines to implement technologies for a hybrid control room.

39

R&DArea Advanced II&C Systems Technolo2ies

• (2022) Publish revised interim guidelines to implement technologies for integrated operations.

• (2025) Publish final guidelines to implement technologies for an automated plant.

• (2025) Publish final guidelines to implement technologies for integrated operations.

• (2025) Publish final guidelines to implement technologies for a hybrid control room.

L WRS - Centralized R&D Scope and Objectives:

Online Monitoring As nuc lear power plant systems begin to be operated d uring periods longer lhan originally licensed, the need arises for more and better types of monito ring of material and component performance. This includes the need to move from periodic, manual assessments and surveillances of physical components and structures to centralized online cond ition monitoring. This is an important transformational step in the management of nuclear power plants. It enables real-time assessment and monitoring of physical systems and better management of active components based on their performance. It also provides the ability to gather substantially more data through automated means and to analyze and trend performance using new methods to make more informed decisions concerning component health. Of particular importance will be the capability to determine the remaining useful life of a component to justify its continued operation over an extended nuclear power plant life.

Workjng closely with the MAaD and RISMC Pathways and EPRI, this pathway will develop technologies to complement sensor development and monitoring of materials to assess the performance of SSC materials d uring long-term operation for purposes of decision making a nd asset management. The MAaD Pathway is developing the scientific basis for understanding the modes of degradation and the physical phenomena that give rise to indications of damage and degradation. 1n additio n, the MAaD Pathway is developing models of the degradation and degradation mechanisms, and sensors and techniques for NDE of materials during periodic inspections. The RISMC Pathway is developing tools that can guide sensor development a nd placement. The Advanced II&C Systems Technologies Pathway is developing in-situ methods to interrogate materials for indications of degradation, for monito ring compo nents and materials in place, and for developing the tools to integrate .indices that may be used to make assessments of structural and other aspects of material health in SSCs that are monitored.

L TO - Centralized R&D Scope and Objectives:

Online Monitoring To achieve continued safe and economical long-term operation of the U.S.

do mestic and international nuclear power plants, it will be imperative that nuclear power plants maintain high levels of operational performance and efficiency.

Nuclear power plants have a continuing need to undergo design and operational changes, as well as manage aging SSCs. Effective management of SSCs will require integration of advanced information monitoring and analysis capabilities into nuclear power plant operations, ma intenance, and engineering activities.

Centralized online monitoring is a highly automated condition analysis and asset management system designed to capture and build in knowledge, experience, and intelligence from many diversified operating systems and monitoring environments. Domestic nuclear power plants have constrained resources to 40

R&DArea Advanced II&C Systems Technolo2ies support implementation of advanced technology programs not required for direct plant o peration or regulatory issues. These constraints dictate that a comprehensive online monitoring capability will be an evolutionary development determined by the functional capabilities needed to support current operational requirements and to provide for long-term asset management. A key fu nctional requirement of a well-developed monitoring program is its information interface with the operating nuclear power plant and associated staff.

To achieve the stated strategic goals ofEPRI's LTO project, industry must develop an effective monitoring progra m that has a well-designed data and information integration platform with advanced technologies, including anomaly detection; automated diagnostic capabilities; a repository of equipment failure signatures captured from industry events; and, ultimately, prognostics-remaining useful life capabilities designed to evaluate critical nuclear power plant assets for optimized maintenance and investment decisions to support LTO. EPRI's research will build on previously developed monitoring technologies and leverage the LTO resources with our strategic partners. In support of implementation of nuclear power plant monitoring programs, EPRI has published comprehensive centralized online monitoring implementation guidelines, produced state-of-the-art diagnostics and prognostics technology developed by EPRI, with guidance based on early adopters and EPRI's Generation Division experience from the power industry's operational monitoring centers.

The continued deve lopment and execution of the required research must include broad a nd frequent interfacing with all of EPRI 's strategic partners, including membe r advisors, technical specialists, and their commercial support organizations. Other partners include q ualified vendors, universities, government laboratories, and utility research programs.

L WRS - Centralized Milestones:

Online Monitoring * (2015) Develop select prognostic models for active components in nuclear power plants.

• (20 15) Develop a passive component monitoring framework for aging effects in nuclear power plant materials.

• (2016) Develop a passive component monitoring framework for aging effects of piping and primary and secondary system components in nuclear power plant materials.

• (2017) Develop diagnostic and prognostic models for a second, large, passive plant component based on the information integration framework.

• (2018) Develop and validate a health risk management framework for concrete structures in nuclear power plants, demonstrate for illustrative concrete structures in the nuclear power plant environment, and develop an implementation strategy for nuclear power plants.

• (2018) Publish a technical report on measures, sensors, algorithms, and methods for monitoring active ag ing and degradation phenomena for a second, large, pass.ive plant component, involving nondestructive examination-related online monitoring technology development, including the diagnostic and prognostic analysis framework to support utility implementation of online monitoring for the component type.

• (2020) Publish a technical report on tests of fiber optic systems and correlation of strain measurements with piping wall thickness, piping performance, and relationship with existing plant technical specifications for 41

R&DArea Advanced II&C Systems Technolo2ies risk-informed technical specification implementation.

• (2021) Publish a technical report on measures, sensors, algorithms, and methods for monitoring acti ve ag ing and degradatio n pheno mena for flow-accelerated corrosion and integration with industry standard guidance (e.g., EPRI CheckWorks, etc.).

L TO - Centralized Milestones:

Online Monitoring

• (2014) Complete EPRI prognostics and health management software installation at the pilot plant utilities (EPRI report 3002002762).

• (2014) Production release of EPRI's prognostics and health management software and access to the associated databases (EPRI report 3002004263).

• (2014) Complete joint research on diagnostics and prognostics (remaining useful life) appl ication to critical plant assets (complete demonstration at INL).

• (2015) Proof-of-concept applications of in-situ monitoring of material degradation of passive assets (in progress at TNL).

• (2015) Publish interim guidelines to implement technologies for centralized online monitoring and information integration.

• (2016) Pilot applications of in-situ mo nitoring of material degradation of passive assets.

• (2017) Complete transient analysis R&D.

• (2018) Publish final guidelines to implement technologies for centralized online monitoring and information integration.

L WRS - Industrial R&D Scope and Objectives:

and Regulatory Nuclear asset owner engagement is a necessary and enabling activity to obtain Engagement data and accurate characterization of long-term operational challenges, assess the suitabihty of proposed research for addressing long-term needs, and gain access to data and representative infrastructure a nd expertise needed to ensure success of the proposed R&D activities. Engagement with vendors and suppliers will ensure that vendor expectations and needs can be translated into requirements that can be met through technology commerc ialization.

To ensure appropriate transfer of technology to the nuclear power indlllstry, guidelines documents will be published for each of the areas of enabling capabilities, incorporating the specific technologies and technical reports produced under each of the pilot projects for the respective areas. EPRT has agreed to assume responsibility for developme nt and publication of these guidelines, using their sta ndard methods and utility interfaces to develop the documents and validate them with industry. The Advanced II&C Systems Technologies Pathway will support this effort by providing relevant information and participating in development activities.

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R&DArea Advanced II&C Systems Technolo2ies L TO - Requirements R&D Scope and Obj ectives:

Database for EPRI w ill develop a repository of advanced I&C, human system interface, and Advanced I&C, other information technology requirements and good practices from the pilot Human System studies and from other industry activiti es. The purpose of this repository is to have Interface, and a living resource for utilities to review state-of-the-art and good practices in the Information industry related to l&C enhancemenL projects.

Technolo!!v L WRS - Industrial Milestones:

and Regulatory Human performance improvement for nuclear power plant field workers:

Engagement

• (20 16) Pub I ish interim guide]ines to implement technologies for human pe rformance improvement for nuclear power plant field workers.

• (2019) Publish final guidelines to implement technologies for human pe rformance improvement for nuclear power plant field workers.

Outage safety and e fficiency:

• (2016) Publish inLerim guidelines to implement technologies for improved outage safety and efficiency.

• (2018) Publish final guidelines to implement technologies for improved outage safety and efficiency.

Centralized online monitoring:

• (2016) Publish interim guidelines to implement technologies for centralized online monitoring and information integration.

• (2018) Publish final guidelines to implement technologies for centralized online monitoring and info1mation integration.

Integrated operations:

• (2020) Publish revised interim guidelines to implement technologies for integrated operations.

• (2022) Publish final guidelines to implement technologies for integrated operations.

Automated plant:

• (2021) Publish interim guidelines to implement technologies for an automated plant.

• (2025) Publish final guidelines to implement technologies for an automated plant.

Hybrid control room:

• (201 8) Publish interim guidelines to implement technologies for a hybrid control room.

• (2021) Publish revised interim guidelines to implement technologies for a hy brid control room.

• (2025) Publish final guidelines to implement technologies for a hybrid control room.

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R&DArea Advanced II&C Systems Technolo2ies L TO - Requirements Milestones:

Database for (2018, 2020, and 2025) Releases of repository of advanced l&C requirements Advanced I&C, based on pilot studies within the advanced I&C working group, other industry Human System pilot studies, and LWRS Program user facil ity results.

Interface, and Information (See also the LTO Program milestones listed earlier with the LWRS Advanced Technolo!!v II&C Systems Technologies pilot projects.)

R&D Area RISMC LWRS - Margins R&D Scope and Objectives:

Analysis Techniques The purpose of the RISMC Pathway R&D is to support nuclear power plant and Modeling and decisions for RIMM, with the aim to improve economics and reliability and sustain Simulation Activities the safety of current nuclear power plants over periods of extended operations. The in Support of goals of the RISMC Pathway are twofo ld:

RISMC

l. Develop and demonstrate a risk-assessment method that is coupled to safety margin quantification that can be used by nuclear power plant decision makers as part of RIMM strategies.

2. Create an advanced RISMC Toolkit that enables more accurate representation of nuclear power plant safety margins and their associated impacts on operations and economics.

Margin Management Strategies:

One of the primary items inherent in the goals of the RISMC Pathway is the ability to propose and evaluate margin management strategies. For example, a situation could exist that causes margins associated with one or more key safety functions to become degraded; the methods and tools developed in this pathway can be used to model and measure those margins. These evaluations will then support development and evaluation of appropriate alternative strategies for consideration by key decision makers to maintain and enhance the impacted margins as necessary. When alternatives are proposed that mitigate reductions in the safety margin, these changes are referred to as margin recovery strategies. Moving beyond current limitations in safety analysis, the RISMC Pathway will develop techniques to conduct margins analysis using simulation-based studies of safety margins.

Central to this pathway is the concept of a safety margin. In general terms, a "margin" is usually characterized in one of two ways:

• A deterministic margin, defined by the ratio (or, alternatively, the difference) of an applied capacity (i.e., strength) to the load. For example, a pressure tank is tested to failure, where the tank design is rated for a pressure C and it is known to fai l at pressure L , thus the margin is (L - C) (safety margin) or L/C (safety factor).

• A probabilistic margin, defined by the probability that the load ex.ceeds the capacity. For example, if failure of a pressure tank is modeled where the tank design capacity is a distribution f(C), its loading condition is a second distribution f(L), the probabilistic margin would be represented by the ex.pression Pr[f(L) > f(C)].

In practice, actual loads (L) and capacities (C) are uncertain and, as a consequence, 44

R&D Area RISMC most engineering margin evaluations are of the probabilistic type. In cases where determi nistic margins are evaluated, the analysis is typically very conservative in order to account for uncertainties. The RISMC Pathway uses the probability margin approach to quantify impacts to economics, reliability, and safety to avoid excessive conservatisms (where possibl.e) and treat uncertainties directly. Further, this approach is used in RIMM to present results to decision makers as it relates to margin evaluation, management, and recovery strategies.

To successfully accomplish the pathway goals, the RISMC approach must be defined and demonstrated. The determination of the degree of a safety margin requires an understand ing of risk-based scenarios. Within a scenario, an understanding of nuclear power plant's behavior (i.e., operational rules such as technical specifications, operator behavior, and SSC status) and associated uncertainties w il l be required to interface with a systems code. Then, to characterize safety margin for a specific safety performance metrics of conside ration (e.g., peak fuel clad temperature), the nuclear power plant simulation will determine the ti me and scenario-dependent outcomes for both the load and capacity. Specifically, the safety margin approach will use the physics-based nuclear power plant results (the " load") and contrast these to the capacity (for the associated performance metric) to determine if safety margins have been exceeded (or not) for a family of accident scenarios. Eng ineering insights w ill be derived based on the scenarios and associated outcomes.

The RISMC methods are to be described in a set of technical reports for RIMM.

Margin Analysis Techniques:

This research area develops techniques to conduct margins analysis, including the methodology for carrying out simulation-based studies of safety margin, using the following generic process steps for RISMC applications:

1. Characterize the issue to be resolved in a way that explic itly scopes the modeling and analysis to be performed. Formulate an "issue space" that describes the safety figures of merit to be analyzed.

2. Quantify the decision maker and analyst's state-of-knowledge (u ncertainty) of the key variables and models relevant to the issue. For example, if long-term operation is a facet of the analysis, then potential aging mechanisms that may degrade components should be included in the quantification.

3. Determine issue-specific, risk-based scenarios and accident timelines. The scenarios will be able to capture timing considerations that may affect the safety margins and nuclear power plant physical phenomena, as described in Steps 4 and 5. As such, there will be strong interactions between the analyses in Steps 3 through 5. Also, to "build up" the load and capacity distributions representing the safety margins (as part of Step 6), a large number of scenarios will be needed for evaluation.

g. Safety performance metrics may be application-specific, but, in general, they are engineering characteristics of the nuclear power plant; for example, as defined in IOCFR 50.36, "safety limits for nuclear reactors are limits upon important process variables that are found ro be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity."

45

R&D Area RISMC

4. R epresent nuclear power plant operation probabilistically using the scenarios identified in Step 3. For example, nuclear power p lant operational rules (e.g., operator procedures, technical specifications, and maintenance schedules) are used to provide realism for scenario generation. Because numerous scenarios will be generated, the nuclear power plant and operator behavior cannot be manually created similar to current risk assessment using event and fault trees. In addition to the expected operator behavior (plant procedures), the probabilistic plant representation will account for the possibility of failures.

5. R epresent nuclear power plant physics mechanistically. The nudear power plant systems level code (RELAP-7) will be used to develop distributions for the key plant process variables (i.e., loads) and the capacity to withstand those loads for the scenarios identified in Step 4. Because there is a coupling between Steps 4 and 5, they each can impact the other. For example, a calculated high loading (from pressure, temperature, or radiation) in an SSC may disable a component, thereby impacting an accident scenario.

6. Construct and quantify probabilistic load and capacity distributions relating to the figures of merit that will be analyzed to determine the probabilistic safety margins.

7. Determine how to manage uncharacterized risk. Because there is no way to g uarantee that all scenarios, hazards, fai lures, or physics are addressed, the d ecision maker should be aware of the limitations in the analysis and adhere to protocols of"good engineering practices" to augment the analysis. This step relies on effective commun ication from the analysis steps in order to understand the risks that were characterized.

8. Identify and characterize the factors and controls that determine the relevant safety margins within the issue being evaluated to develop appropriate RIMM strategies. Determine whether additional work to reduce uncertainty would be worthwhile or if additional (or relaxed) safety control is justified.

Case Study Collaborations:

Jointly with EPRI, the RISMC Pathway is working on specific case studies of interest to the nuclear power plant industry. During FY 2013 and FY 2014, the team performed multiple case studies, including a demonstration using the INL's Advanced Test Reactor, a hypothetical p ressurized water reactor, and a boiling water reactor extended power uprate case study. Safety margin recovery strategies will be determined that w ill mitigate the potential safety impacts due to the postulated increase in nominal reactor power that would result from the extended power uprate. An additional task was to develop a technical report that -describes how to perform safety margin-based configuration risk management. Configuration risk management currently involves activities such as the Significance Determination Process, which traditionaJly uses core damage frequency as the primary safety metric - the research will focus o n how the safety margin approach may be used to determine risk levels as different plant configurations are considered.

RISMC Toolkit:

The RISMC Toolkit is being built using INL's Multi-physics Object Oriented 46

R&D Area RISMC Simulation Environment (MOOSE) hig h-performance computing framework."

MOOSE is the ]NL development and runtime environment for the solution of multi-physics systems that involve multiple p hysical models or multiple simultaneous physical phenomena. Models built on the MOOSE framework can be coupled as needed for solving a particular problem. The RISMC Toolkit and ro les are described as follows:

• RELAP-7: RELAP-7 (_Reactor !;xcursion and i_eak Analysis frogram) will be the ma in reactor systems simulatio n tool for RJSMC and the next generation tool in the RELAP reactor safety/systems analysis application series. RELAP-7 development will leverage 30 years of advancements in software design, numerical integration methods, and physical models.

RELAP-7 will simulate behavior at the nuclear power plant level w ith a level of fidelity that will support the analysis and decision making necessary to economically and safely extend and enhance the operation of the c urrent nuclear power plant fleet.

• RAVEN: RAVEN (_Reactor A nalysis and Yirtual Control E Nviron ment) is a multi-tasking application focused on RELAP-7 simulation control, reactor plant control logic, reactor system analysis, uncertainty quantification, and performing probabilistic risk assessments for postulated events. RA VEN will drive RELAP-7 (and other MOOSE-based reactor applications) for conduct of RISMC analyses.

• Grizzly: Grizzly will simulate component aging and damage evolution events for LWRS Program applications. Grizzly will be able to simulate component damage evolution for the RPV, core internals, and concrete support and containment structures subjected to a neutron flux, co1Tosion, and high temperatures and pressures. Grizzly will be able to couple with RELAP-7 and RA VEN to provide aging analysis in support of the RISMC methodology.

• Peacock: Peacock is a general graphical user interface for MOOSE-based applications. Peacock has been bu ilt in a very general fashion to allow specialization of the graphical user interface for different applications. The specialization of Peacock for RELAP-7/RA VEN allows both a graphical input of the RELAP-7 input file and online data visualization and is moving forward to provide direct user control of the simulation and data mining capabilities in support of probabilistic risk assessment analysis.

• External events tools: In 2014, the RISMC Pathway extended its analysis capabilities into additional initiating events, including external events (primarily focusing on seismic and flooding events). External events, such as flooding and seismic events, are be ing explored by leveraging existing tools (such as NEUTRINO for flooding) and by developing new tools (such as for seismic event evaluations).

LTO - Enhanced R&D Scope and Objectives:

Safety Analysis This research project will develop and validate an integrated framework and Capabilities advanced tools for conducting risk-informed assessments that enable accurate characterization, visualization, and management of nuclear power plant safety

h. Gaston, D., G. Hansen, and C. Newm an, 2009, " MOOSE: A Parallel Computational Framework for Coupled Systems for Nonlinear Equations. International Conference on Mathematics," Computmional Methods, and Reactor Physics. Saratoga Springs, NY: American Nuclear Socie ty.

47

R&D Area RISMC margins. This LTO Program task is intended to develop an integrated methodology to assess plant safety margins and perfo rm cost-effective, risk-informed safety analyses to meet these needs. It will achieve this obj ective through demonstration of effective and effi cient application of the RISMC approach to issues important to the long-term operation of nuclear power plants. This proj ect also provides significant interface and coordination of research efforts being conducted in safety analysis code development (via RELAP-7 and RAVEN) and safety margin analyses being performed by INL as part of the LWRS Program.

LWRS - Margins Milestones:

Analysis Techniques Margin management strategies:

and Modeling and * (2017) Complete the technical basis reports for RIMM .

Simulation Activities in Support of Margin analysis techniques:

RISMC * (2016) Demonstrate margins analysis techniques by applying to performance-based emergency core cooling system cladding acceptance criteria.

• (20 16) Demonstrate margins analys is techniques by applying to enhanced external hazard analysis (seismic and flood ing).

• (2017) Apply margins analysis techniques to reactor containment analysis, ind uding hardened reliable vents and shallow and deep-water flooding and seis mic events.

• (201 7) Complete a full -scope margins analysis of a commercial reactor power uprate scenario. Use margins analysis techniques, including a fully coupled RlS MC toolkit, to analyze an ind ustry-important issue (e.g., assessment of major component degradation in the context of lo ng-term operation or assessment of the safety benefit of advanced fuel forms) . Test cases will be chosen in consultation with external stakeholders.

• (201 7) Demonstrate margins analysis techniques, including a fully coupled RlSMC toolkit, for long-term coping studies to evaluate FLEX for extended station blackout conditio ns.

• (2019) Apply margins analysis techniques to evaluation of spent fuel pool issues.

• (20 20) Ensure development and validation to the degree that by the end of 2020, the margins analysis techniques and associated tools are an accepted approach for safety analysis suppor t to plant decision making, covering ana lysis of design-basis events and events within the technical scope of internal and external events probabilistic risk assessment.

RISMC toolkit:

• (2015) Release the beta version of RELAP-7, including limited benchmarking .

• (2015) Complete a report on advan-c ed seismic soil structure modeling .

• (201 6) Re lease the beta versio n l.O of Grizzly. This will include engineering fracture analysis capability for RPVs, with an engineering model for embrittlement, and a modular architecture to enable modeling of aging mechanisms.

• (2016) Complete the optimized and validated version of RELAP-7 that couples to RAVEN and to other applications (e.g., aging and fuels modules) for use as a balance-of-plant capability for multi-dimensional core simulators.

• (20 16) Grizzly (RPV) is validated against an accepted set of data .

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R&D Area RISMC

• (2016) RELAP-7 is validated against an accepted set of data.

• (2016) Release the beta version of initial flooding model.

• (2016) Beta 1.5 release of RELAP-7 with improved closure relationships and steam/water properties, completed LWR zero-dimensional components (such as jet pump and accumulator), improved LWR components (one to two-dimensional downcomer, one-dimensional pressurizer, and optional steam generator designs such as helical), tightly coupled multi-physics fue ls performance (NEAMS code BISON), and single-phase three-dimensional subchannel flow capability.

• (2017) Release the beta version 2.0 of Grizzly. This version w ill include capabilities for modeling selected aging mechanisms in reinforced concrete and for engineering probabilistic RPV fracture analysis.

• (2017) Completed software that couples RA VEN to other applications (e.g., aging and fuels modules) for use as a balance-of-plant capability for multi-dimensional core simulators.

• (2017) Compete flooding fragility experiments for mechanical components .

• (2017) Release beta version of seismic probabilistic risk assessment model.

• (2017) Flooding model is validated against an accepted set of data.

• (2017) Beta 2.0 release of RELAP-7 w ith selected separate effects tests for validation data sets, validation of three-dimensional single-phase subchannel, preliminary tlu*ee-dimensional two-phase (seven-equation) subchannel, multi-physics coupling to reactor physics (NEAMS codes Rattlesnake and MAMMOTH).

• (2018) Grizzly (concrete) is validated against an accepted set of data.

• (2018) Release advanced flooding analysis tool suitable for ocean and river-based flooding scenarios.

• (2018) Compete flooding fragility experiments for electrical components.

• (2018) Initial demonstration RPV steel embrittlement using a bottoms-up, lower-length scale model to capture causal mechanisms of embrittlement.

• (20 18) Flooding fragility models for mechanical components are val idated against an accepted set of data.

• (2018) Beta 3.0 release ofRELAP-7 with additional validation and full multi-physics coupling, validated three-dimensional two-phase subchannel capabil ity, and implementation of droplet model for BWR station blackout scenario, reflood phenomena under loss-of-coolant accident, and PWR feed -

and-bleed process.

• (2018) Version 1.0 release ofRELAP-7 with validation and selected integral effect tests, demonstration of large break loss-of-coolant accident, and three-field flow model, water, steam, droplets.

• (2019) Compete seismic experiments for critical phenomena .

• (2019) Release beta version 3.0 of Grizzly. This version includes capabilities for modeling selected aging mechanisms in reactor internals.

• (2019) Flooding fragility models for electrical components are validated against an accepted set of data.

• (2020) Implement RTMM module in RISMC toolkit that will perform analyst-augmented evaluation of facility safety to search for vulnerabilities and potential management strateg ies.

• (2020) Grizzly (core internals) is validated against an accepted set of data .

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R&D Area RISMC LTO - Enhanced Milestones:

Safety Analysis In previous years, this LTO research effort successfully demonstrated that the Capabilities RISMC methodology could be applied in an economical and efficient manner to analyze issues important to nuclear power plant safety. Key results of this research were documented in EPRI Report 1023032 (Technical Framework for Management of Safety Margins - Loss of Main Feedwater Pilot Application), which applied the RISMC methodology to evaluate the safety margins associated with a loss-of- all-feedwater event at a hypothetical PWR. An initial application of the RISMC approach to evaluate the impact on safety margins in the context ofLTO decision making was conducted in 2012 and documented in EPRI Report 1025291 (Pilot Application of Risk Informed Safety Margins to Support Nuclear Plant Long Term Operation Decisions: Impacts on Safety Margins of Power Uprates for Loss of Main Feedwater Events). In 2013 (and continuing in 2014), the EPRJ LTO portion of the RISMC research expanded and will continue to expand upon this research by performing additional analyses of safety-signi ficant applications that have the potential to impact critical long-term operation decision making. The EPRI research also will engage nuclear power plant owners/operators to initiate transfer of the technology for applicatio n to relevant safety issues with impact on nuclear power plant LTO.

To support these obj ectives, the following activities will be cond ucted during 2015:

Project 1: RISMC Pilot Projects

• Conduct RISMC analysis of safety margins associated with decisions that are bei ng pursued as part of nuclear power plant owner/operato r LTO strategies.

Work is planned to support both domestic (U.S.) and international applications. Work also will be initiated to integrate the results of RISMC evaluations into applicable utility d ecision processes using other LTO developed technologies (e.g. ILCM) as applicable.

• Support utility use of the RJSMC approach to support utility and regulatory evaluations of the safety impact on nuclear power plant events as applicable.

Project 2: Socialize RJSMC Approach Among External Stakeholders

• EPRI and EPRI member utilities will provide technical advice on RISMC/

RIMM development by participation on the RISMC Pathway Advisory Committee being formed by INL as part of the LWRS Program. This committee, which consists of a broad selection of risk assessment/

management technical experts, is being formed to provide external input and advice to the planned RISMC/RlMM development and deployment efforts.

• EPRI will continue engagement with NRC researchers who are involved with similar regulatory research into development and application of the RISMC methodology. This interaction will be conducted under the existing memorandum ofunderstanding between EPRI and NRC'S Office of Nuclear Regulatory Research.

• EPRI also will continue to participate in external communication of RJSMC research at appropriate venues, including conduct of EPRI industry workshops, presentations at applicable conferences, and reporting results of pilot applications in peer-reviewed scientific literature.

In additio n to application of the RISMC methodology, EPRI will continue to support INL development of the next generation safety analysis software 50

R&D Area RISMC (RELAP-7). Previously, EPRI provided important contributions to this work via EPRI Reports 1019206 (Framework/or Risk Informed Safety Margin CharacJerization), which summarized the current state-of-the-art (as of 2009) for the RISMC methodology and deterministic safety analysis and probabilistic risk assessment software tools, and I 021085 (Desired Characteristics for Next Genera/ion Integrated Nuclear S~fety Analysis Methods and Software), which specified desired elements for the next generation safety analysis tool suite (from the perspective of a plant owner/operato r). During 2014, EPRI provided a comprehensive and prioritized catalog o f test data available to support the validation of the RELAP-7 code. The results of this effort were published in EPRI 3002003 11 0 (Data Sources for Capability Assessments of Next Generation Safety Analysis Codes). Since code validation is an essential element for utility use of any safety analysis code, in 2015 and beyond, EPRI will continue to support lNL 's development of RELAP-7 by providing input to its development, val idation, and deployment and supporting the conduct o f trial applications as modules become available.

Project 3: RISMC Safety Margin Method and Tool Development (LWRS Program)

• Support development of RELAP-7 by closely working with the INL RELAP-7 development team to provide input to software development and by conducting testing on trial safety analysis applications as modules become available. EPRI also will work closely with INL to develop, prioritize, and conduct appropriate benchmarking and validation efforts as part of the planned RELAP-7 validation effort.

5. LIGHT WATER REACTOR SUSTAINABILITY PROGRAM /

LONG TERM OPERATIONS PROGRAM- PROGRAM-UNIQUE RESEARCH AND DEVELOPMENT ACTIVITIES LWRS - EMDA R&D Scope and Objectives:

The objectives of this research task we re to provide comprehensive assessment of materials degradation, relate to consequences of SSCs and economically important components, incorporate results, guide future testing, and integrate with other pathways and programs. This task provided an organized and updated assessment of key materials aging degradation issues and supported NRC and EPRI efforts to update the Proactive Materials Degradation Assessment or the MDM documents.

Successful completion of this activity p rovides a valuable means of task identification and prioritization within this pathway, as well as identifying new needs for research.

A n EMDA of degradation mechanisms for 60 to 80 years or beyond was identified as a useful tool in further prioritizing degradation for researc h needs.

Based on joint discussions between DOE and NRC, it was decided that the EMDA would consist of separate and focused documents covering the key SSCs. This approach yielded a series of independe nt assessments (i.e., core internals primary and secondary piping, RPV, concrete c ivil structures, and electrical power and l&C cabling and insulation) that, when combined, created a comprehensive EMDA. The LWRS Program will use this as a tool for identifying and prioritizing research in future years. NRC will use the EMDA to inform the regulatory 51

framework. The nuclear industry will use the EMOA results as a complementary tool to their MDM.

Milestone:

• (2014) Complete and deliver a gap analysis of the key materials degradation modes via the EMOA (NUREG/CR-7153, Volumes 1-5 , October 2014).

LTO - MDMand R&D Scope and Objectives:

Issues Management EPRI's MDM, PWR Issues Management Tables ('Ts), and BWR JMTs are Tables three key reference documents that are part of industry's materials initiative g uided by NEI 03-08. The MDM and IMTs identify knowledge gaps based on likely degradation mechanisms and agi ng issues through an expert elic itation process. The MOM and JMTs also assess the state of industry knowledge worldwide, survey the laboratory data and field experience data, and prioritize the gaps for industry to resolve in the most effective way.

MDM results are used as direct inputs into the BWR IMT and PWR IMT.

Degrad ation mechanisms identified in MDM are used as primary input for the set of degradation mechanisms considered by the TMT process. The MOM was first published in 2004 (Rev. 0), and it has been revised three times in 2007 (Rev. 1),

20 10 (Rev. 2), and 2013 (Rev. 3). Sequentially, two lMTs were first published in 2005 (Rev. 0) and then revised in 2008 (Rev. I), 20 IO (Rev. 2), and 2013 (Rev. 3). Rev. 0 and Rev. 1 of MDM and the IMTs only addressed issues related to the current license period (40 years operation) and the license renewal period (from 40 to 60 years operation).

Long-term operation of nuclear power plants up to 80 years may pose additional materials degradation issues that may not be deemed to be life-limiting factors for 60-years operation. For example, the increased fluence level can be a serious concern to some of the reactor internal components. The increased fluence level not only can lead to changes in materials properties and cracking susceptibility, but also can be an issue in repairing the internal components.

In support of the LTO Program, an LTO 'flag' has been added to the MDM (starting with Revision 2 in 2010), indicating ongoing work or evaluation that is needed to support 60 to 80 years o f operatio n. The objective of this addition to the MDM is to

l. Identify applicable degradation mechanisms and assess the extent to which applicable degradation mechanisms are understood

2. Evaluate the state of industry knowl edge worldwide associated w ith mitigation of degradation mechanisms

3. Address any concerns related to regulatory and licensing renewal considerations.

MOM and lM Ts are based on an expert elicitation process. A panel consisting of materials experts, industry personnel, and EPRI staff provided the key inputs for the ongoing revisions. The expert pane l considered relevant operating experience, information from newly published and ongoing research projects worldwide, the consequence of failw*e, and the availability of mitigation strategies when developing the results.

1. Develop a fundamental understanding of the degradation phenomena/mechanisms and dete1mine materials (and locations) that are known o r can logically be assumed to be susceptible to aging/degradation phenomena when exposed to the operating environment.

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2. Conduct generic operability and safety assessments for the locations of the various materials potentially susceptible to damage/degradation phenomena.

3. Develop inspection and evaluation g uidelines and technology for the identified locations, starting with those for which the potential consequences of failure are most severe.

4. Evaluate available mitigation options and, if necessary, develop additional options.

5. Evaluate repair/replace options and, where necessary, encourage/support the development of additional options.

6. Monitor, evaluate, and feedback nuclear power plant operating experience.

7. Obtain regulatory acceptance of the items above and support licensees on nuclear power plant-specific applications as needed.

The MOM focuses on the development of a fu ndamental understanding of the degradation phenomena/mechanisms, based on the materials/environment combination. Expert elicitation, laboratory studies, and field experience were used to identify potential mechanisms by which each of the materials might degrade.

The PWR IMT and BWR IMT are component-based evaluations of the consequence of fai lure. This component-based approach also emphasizes the considerations of mitigation strategies, repair/replacement, inspection and evaluation guidelines, and regulatory requirements. All considerations will be captured in IMT gaps, which will then be prioritized. The prioritization of IMT gaps provides a basis for industry to prioritize R&D efforts to address materials' reliability issues and LTO concerns effectively.

The LTO Program will also support the current EPRI online Materials Information Portal. With built-in navigation and interlinks, the EPRI online Materials Information Portal integrates multiple EPRJ resources (i.e., MDM, PWR IMT, BWR IMT, and the Materials Ha ndbook). This portal provides a comprehensive, integrated view of materials issues and associated information necessary for materials aging management at nuclear power plants.

Milestones:

MOM and IMTs are living documents and they require updates and revisions periodically to reflect the knowledge gained and the evolving challenges. The MOM and IMTs are scheduled to be revised every three years, and more frequent interim updates of underlying information can be achieved through the maintenance of the Materials Information Porta l. The Materials Information Portal maintenance frequency is semi-annual (twice a year). The LTO-supported work will be coordinated with the planned work within the Primary System Corrosion Research program to update and maintain the MOM and Materials Information Portal and work within the PWR Materials Reliability Project and BWR Vessel and Internals Project to update and maintain the IMTs.

• (2013) Update of the MDM complete (EPRI Report 3002000628, Rev 3).

• (2013) Update of the IMTs complete (EPRI Reports 3002000690 for BWRs and 3002000634 for PWRs).

• (2016 and 2019) Planned MOM Updates.

• (2016 and 2019) Planned IMT Updates for BWRs and PWRs.

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L WRS - Thermal R&D Scope and Objectives:

(Post-Irradiation) This task provides critical assessment of thermal annealing as a mitigation Annealing technology for RPV and core internal e mbrittlement and research to support deployment of thermal annealing technology. This task will build on other RPV tasks and extend the mechanistic understanding of irradiation effects on RPV steels to provide an alternative mitigation strategy. This task will provide experimental and theoretical support to resolve technical issues required to implement this strategy. S uccessful completion of this effort will provide data and theoretical understanding to support implementation of this alternative mitigation technology.

Milestones:

• (202 1) Complete reirradiation on RPV sections following thermal annealing.

• (2025) Complete characterization of RPV sections (harvested from a reactor) that have been irradiated, annealed (post-harvesting) and then reirradiated in a test reactor.

While a long-term effort, demonstration of annealing techniques and subsequent irradiation for RPV sections is a key step in validating this mitigation strategy.

Successful deployment also may allow for recovery from embrittlement in RPV, wh ich would be of high value to industry by avoiding costly replaceme nts.

LWRS - Zion R&D Scope and Objectives:

Materials The Zion Harvesting Project, in cooperation with Zion Solutions, is coordinating Management and the selective procurement of materials, structures, components , and other items of Coordination interest to the LWRS Program, ERPI, and NRC from the decommissioned Zion l and Zion 2 nuclear power plants, as we ll as possible access to perform limited, onsite testing of certain structures and components. Materials of high interest include low-voltage cabling, concrete core samples, and through-wall thickness sections of RPV.

Milestones:

• (2015) Document the status of the Service Harvested Materials Database.

D iscussions regarding continued harvesting of material (including cables, concrete, and RPV samples) are underway. Additional milestones will be identified once a revised decommissioning schedule is available.

LWRS - RST (Gap R&D Scope and Objectives:

Analysis) Many of the activities associated with the RST Pathway represent DOE initiatives that had commenced shortly after the Fukushima accident. Thus, there remains a need for a more comprehensive review o n what the industry has engaged for beyond design basis events subjects as well as what R&D activities NRC is supporting for this area. ln 2015, a "gap" analysis will be completed using a team of reactor safety experts from industry (EPRI, BWR and PWR Owners Groups, U.S. ve ndors), DOE and its national laboratories as well as academe. The gap analysis report will help to inform an updated RST Pathway R&D plan (to be issued in the summer of2015) and pathway activities beyond 2015.

Milestones:

• (20 15) Complete a gap analysis o n accident-tolerant components and severe accident analysis.

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LWRS-RST R&D Scope and Objectives:

(Accident-Tolerant The accidents at Three Mile Island Unit 2 and Fukushima demonstrate the Components) importance of accurate, relevant, and timely information o n the status of reactor systems during such an accident to help manage the event. While significant progress in these areas has been made since Three Mile Island Unit 2, the accident at Fukushima suggests that there may still be some potential for further improvement. Recognizing the significant technical and economic challenges associated wilh planl modifications, it is important to deploy a systema lic approach, which uses state-of-the-art accident analysis tools and plant-specific information to identify critical data needs and equipment capable of mitigating the effects of any risk-significant accidenl.

The objective of this R&D activity is to identify opportunities to improve nuclear power plant capability to monitor, analyze, and manage conditions leading to and d uring a beyond-design-basis event. Availabil ity of appropriate data and the operator's ability to interpret and apply that data to respond and manage the accident was an issue during the Fukushima accident. The damage associated with the earthquake and flooding inhibited or disabled the proper functionjng of the needed safety systems or components.

There a re compelling reasons for pursuing this area of R&D both for our domestic reactor fleet and for international collaborations. Results could provide useful in formation to industry regarding poss ible post-Fukushima regulatory actions related to sensor and equipment reliability and/or operability. Additionally, results and processes developed from this research could benefit Design Certification and Combined Operating License applicants as they are challenged to meet new requirements related to equipment survivability during severe accidents. Finally, analyses and experiments in support of industry initiatives may reveal additional margin in reactor safety systems and components.

Milestones:

• (2015) Develop recommendations for accident-tolerant sensor development, based o n evaluation of a PWR severe accident scenario.

• (201 5) Develop recommendations for accident-tolerant sensor development, based on evaluation of a BWR severe accident scenario.

• (2015) Complete reactor core isolation cooling analytical model and a draft testing program.

The recommendations for accident-tolerant sensor development will be provided to the Nuclear Energy Enabl ing Technologies Program for their consideration.

Development of an accident-tolerant sensor is not currently planned under the LWRS Program. Exploration in 2015 into possible testing of a reactor core isolatio n cooling turbine-pump under beyond design basis conditions will inform a future decision as to whether such a test will be carried out under the LWRS Program.

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L WRS - RST (Severe R&D Scope and Objectives:

Accident Analysis) After F ukushima, DOE and other domestic and international groups initiated severe accident analysis efforts aimed at reconstruction and analysis of the Fukushima reactor units. While useful insights were gained as to accident progression, these activities also highlighted where the existing computer system models being used did not always produce consistent results. If such tools were to be used to aid in effective severe accident management guidelines and associated training, further work was needed on identifying the sources of uncerta inties and incons istencies, in order to have greater confidence in the use of these tools.

The objective of this R&D activity is to improve understanding of and reduce uncertainty in severe accident progression, phenomenology, and o utcomes using existing analytical codes, and to use the insights from this improved understanding of the accident to aid in improving severe accident management guidelines for the current L WR fleet. Information gathered from the application of existing codes to the scenario at Fukushima Daiichi could be used to inform improvements to those codes. However, at this time, the LWRS Program does not plan to fund the improvement of legacy codes. Analysis efforts can aid in preparations and p lanning for examination of the damaged Fukushima units.

Milestones:

• (20 15) Complete a MELCOR/MAAP comparison of analyses of the events at Fukushima Daiichi.

• (2015) Complete analysis of uncertainties in MELCOR calculations as applied to the events at Fukushima Daiichi.

• (2017) Complete MAAP-MELCOR crosswalk Phase 2 with collaboration between EPRI, DOE laboratories, NRC, and possibly French and Japanese partners.

• (2019) Complete water management severe accident analysis in support of BWR ex-vessel mitigating strategies.

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LWRS - RST R&D Scope and Objectives:

(Fukushima The Fukushima accident provides the nuclear industry with opportunities to Forensics and incorporate lessons learned into the operation of current plants and the design of Inspection Plan) future plants. Forensic examination of post-accident conditions at Fukushima will provide valuable insights into severe accident phenomena progression and an opportunity to improve severe accident analysis tools and accident management g uidance and training for plant staff.

Experience from the Three Mile Island Unit 2 accident in the United States suggests that critical information can be lost if not obtained as soon as feasible during the cleanup and decommissioning process. Experience also suggests that R&D needs must be fully incorporated early in cleanup and decommissioning plans in order to minimize the impact on decommissioning cost and schedule.

Japan has already begun planning the decommissioning of the damaged Fukushima reactors; therefore, this is a n appropriate time to identify inspection and sampling needs, prioritize them, and sequence them most efficiently into the planning process.

The objective of this R&D activity is to provide U.S. insights into severe accident progression and the status of reactor systems through early data collection, visual examination of in-situ conditio ns of the damaged Fukushima units, and collection and analysis of material samples and radionuclide surveys (e.g., within the reactor building, the drywell, and the vessel). U.S. consensus insights will be obtained from severe accident experts and plant operations experts from national laboratories, academia, and industry (including plant staff, PWR and BWR Owners Groups, and EPRI), and informed by interactions with representatives from NRC and TEPCO. These insights will also contribute to synergistic international efforts, such as the CSNl (Committee on the Safety of Nuclear Installations, under the Office for Economic Cooperation and Development's Nuclear Energy Agency) safely research opportunities post-Fukushima (SAREF).

SAREF is establishing a process for identifying and following up on research opportunities to address safety research gaps and advance safety knowledge related to Fukushima. The ultimate goal of this activity is to use knowledge gained from Fukushima to inform model enhancements to safety analysis codes and to apply lessons learned based on these insights to plant systems and procedures.

Lessons learned may also help improve the design of future reactor safety systems.

Milestones:

• (2015) Complete U.S. input towards a forensics examination plan for Fukushima D aiichi.

This plan will be updated periodically. Future milestones will be informed by activities in 2015.

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L TO - Integrated R&D Scope and Objectives:

Life-Cycle Management To achieve Jong-term operation, nuclear power plant operators must maintain and/or enhance high levels of safety, reliability, and economic performance as are typical today. Nuclear power plant operators will need to be equipped with sound scienti fie and consistent technical knowledge bases to provide them the optimum information in support of their plant asset extended operation decisions of 60 years and beyond. Re furbi shment and/or replacement of large capital assets not normally considered during the origina l licensed life may now come into play.

This project will identify those large capital assets. Some of these assets may not have the operating experience and research sufficient for providing technical bases input into operators' business models. The project will develop method s that nuclear operators can utilize in the determination of the likelihood of failure for selected large capital assets that is supported by science and enabling technology and operating experience. This methodology is JLCM and will pro vide consistency of information nuclear power plant operators can utilize in support of the optimization of their long-range nuclear power plant and/or fleet strategic technical and business decision models. For example, what large capital assets will be required to be refurbished and/or replaced, when they will be required to be addressed in the life cycle and how much it will cost?

The design phase of work will be complete in 2013, with technical transfer scheduled for 2015/2016 to EPRI Plant Engineering.

• The initiative commenced in 20l0 w ith the following accomplishments:

Project requirement documents (database and methods)

Likelihood of failure methodology Proof of concept for likel ihood of failure methods using actual site data for initial components Governance and communication through quarterly advisor meetings and periodic LTO Program executive committee presentations Completion of failure curves for 2010-scoped SSCs Completion of life- limiting and Constellation Energy Nuclear Group demonstration projects Entering into a memorandum of understanding w ith Electricite de France to proceed with collaboration Publicalion of EPRI Technical Update 1021188, Integrated Life Cycle Management Status Report, December 20 10.

• U sing the results from prior year work, develop the modified optimization tools and document them as a production report and user guide by 2014 (EPRI report 3002003010).

• EPRI Software Engineering to complete the !LCM oplimization framework th at incorporates a failure calculator and ILCM modified IPOP (Investments Portfolio Optimal Planning into a single software package. Formal release after pilot appl ications and user beta testing is planned for 2014 (EPRT report 3002004656).

• Establish the necessary code suooort, users group, and training for the 58

optimization tools. In 201 5 and beyond, it is antic ipated that the users group would not only provide for continuity of the optimization tool, but would also provide for continuous improvement.

• In 201 5, technical transfer thro ugh workshops and/or seminars, fai lure c urve o ngoing development, and final report. It is anticipated that an ILCM users group will be created to foster continued component data, fai lure curve development, and refinement to the methods.

LTO-Technical R&D Scope and Objectives:

Bases Updates to The Ag ing Management Program (AMP) Assessment Project foc used on the EPRI Technical technical bases of the currently defined AMPs pe r the NRC report "Generic Aging Reports to Support Lessons Learned" (NUREG-1801, Revision 2). Technical bases are the data and SLR associated implementation tools (e.g., g uidelines, analytical models, evaluation bases, etc.) that provide reasonable assurance that the current condition of the subject SSC is assessed to allow safe, continued operation as is through a defined period prior to reassessment or to allow remedial actions prior to risk of failure.

Under this project, the cunent set of AMPs reviewed for their applicability to a period of extended operation (i.e., 60 to 80 years) that may be allowed via a successful SLR. The review process is intended to help define additional technical needs and/or changes to allow the AMPs to be successfully used for the period from 60 to 80 years of operation. The AMP reviewers included subj ect matter experts drawn from both EPRI staff and external sources, utility staff involved in the design and implementation of AMPs at operating nuclear power plants, and appropriate third parties such as owner 's groups and vendors. The revi.ew focused o n binning AMPs according to the future technical bases required or gaps in those technical bases. The key points of the review were as follows:

• A re there changes in the aging mechanisms, the ir rates, or their extent that may occur after operation to 60 years?

• Are such changes after 60 years being addressed by current or planned R&D efforts?

• Are there technical tools required to effectively address new or changed aging management requirements?

The project identified significant potential "gaps" in the ind ustry technical bases support eight AMPs for the operating period from 60 to 80 years. As somewhat expecte d, the affected AMPs covered reactor internals for both BWR and PWR designs, RPV, the behavior of nickel aJloy CASS subject to extended exposure to operating environments, the monitoring of concrete structures, and the remaining useful life assessment for plant cables. S uch information will then be used to refine industry R&D efforts and to red uce the uncertainties for utility decision making concerning SLR for a specific nuclear power plant.

A n additional fo llow-on effort is focused on the review of EPRI technical documents that form the foundation for AMP actions to assess their applicability thro ugh the extended operating period. Where appropriate, the need for technical updates will be identified and then incorporated into a schedule for suc h updates to be completed. Consideration will be given in the process to supporting potential utility licensing decision making as expected to occur in the 2015 through 201 9 timeframe .

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Buried Piping and R&D Scope and Objectives:

Tanks (work not This research area is under the NEI 09-14 initiative. EPRI buried pipe research is directly in LTO scope foc used on furthering state-of-the-art technologies for inspection, analysis, repair, due to near-term, and mitigation of ongoing corrosion in buried infrastructure. This includes the nuclear power plant following:

operational impact)

• Development and delivery of appropriate reference documents and training to support broad knowledge awareness for buried and underground p iping.

• Development and transfer of new buried pipe inspection technologies, such as remote field NDE inspection robotics.

• ldentification and evaluation of existing technologies that may be directly applied or easily adapted for nuclear power plant buried piping inspection.

• Improved understanding regarding the usefulness of guided wave acoustic NDE technologies for buried piping inspections.

• Availability of repair and replacement alternatives for buried pipe applications, including high-density polyethylene.

• Enhanced buried pipe risk-ranking technologies through updates to existing software.

Research activities arc coordinated across EPRI's Plant Engineering and NOE Programs.

The Plant Engineering Program provides buried pipe program owner guidance documents, reference materials, and upgraded risk ranking software (BPWORKS') and also supports the development of various ASME Code Cases for repair/replacement activities. Training courses are offered for newly assigned Buried Pipe Program owners to help ensure buried pipe management guidance is appropriately deployed in the field. Reference materials on cathodic protection and coatings have been developed to address buried and underground p ipe program needs. Through the Buried Pipe Integrity Group, EPRI provides a forum for information exchange among nuclear power plant personnel, vendors, and other stakeholders to identify and trans.fer best practices for buried pipe inspection and assessment.

The NDE Program is pursuing the identification and assessment of existing robotic and inspection technologies, as well as the development of new robotic inspection technologies using remote field detection technology. Efforts continue to identify, demonstrate, evaluate, and qualify inspection technologies suitable for buried pipe applications, with special emphasis on guided wave ultrasonic technologies.

Nuclear Plant R&D Scope and Objectives:

Chemistry (work not No specific water chemistry program LTO-related R&D gaps were identified. The directly in LTO scope benefit of water chemistry technologies is generally time independent. Although due to near-term, mitigation through chemical means is v ital to long-term aging management, any nuclear power plant changes to program implementation over time are not likely to be related to operational impact) time-dependent factors.

Importantly, implementation of the water chemistry program is specifically within the scope of NEl 03-08. A robust industry program exists to ensure that water 60

chemistry guidelines are periodically reviewed and updated and that related R&D gaps are proactively addressed. Opportunities for AMP implementation improvements may be realized from these ongoing research efforts.

Key existing EPRI reports include the following:

• BWRVIP-190: BWR Vessel and Internals Project, BWR W ater Chemistry Guidelines - Revision l. EPRI, Palo Alto, CA: 2014, 3002002623.

• Pressurized Water Reactor Primary Water Chemfatry Guidelines -

R evision 7. EPRI, Palo Alto, CA: 20 14, 3002000505.

• Pressurized Water Reactor Secondary W ater Chemistry Guidelines, Revision 7. EPRI, Palo Alto, CA: February 2009, 1016555.

Steam Generator The EPRI Steam Generator Management Program provides guidelines for Management inspect.ion, repair, monitoring, and flaw evaluation of steam generator components Program (work not and tubing materials. The Steam Generator Management Program incl udes aging directly in LTO scope management activities for the steam generator tubes, plugs, sleeves, and due to near-term, secondary side components that m*e contained within the steam generator.

nuclear power plant Program implementation is consistent with nuclear power plant technical operational impact) specifi cations and includes commitmen ts to NEI 97-06. The NDE techniques used to inspect tubes, plugs, sleeves, and secondary side internals are intended to identify components (e.g., tubes and plugs) with degradation that may need to be removed from service or repaired. The program additionally provides for degradation assessments, condition monitoring (assessment of past performance),

and operational assessments (forward-looking assessment of anticipated performance until the next inspection). The Steam Generator Management Program is based o n these six EPRI guidelines:

• PWR Stearn Generator Examination Guidelines

• PWR Primary-to-Secondary Leak Guidelines

• PWR Secondary Water Chemistry Guidelines

• PWR Primary Water Chemistry Guidelines

• Steam Generator Integrity Assess ment Guidelines

• Steam Generator In-Situ Pressure Test Guidelines.

These guideline documents are supported by both evaluation handbooks (e.g., flaw evaluation and foreign object evaluation) and by technical reports that document the results of EPRI researc h. Reports are periodically updated using the latest R&D results.

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Attachment A Long Term Operations Issue Tracking Table Long Term Operations (LTO) Issue Tracking Table (ITT)

LEGEND Active on-going work Planned work No planned work_i potential scope Not within LTO sci Complete The purpose of the LTO ITT is to identify and prioritize the R&D projects needed to support safe, reliable and economic long-term operations of nuclear plants. The ITT is the result of an expert solicitation process and is maintained as a living document. It is reviewed on an annual basis by stakeholders from EPRI, NEI, DOE, national laboratories and EPRI utility advisors to ensure accuracy and completeness. The R&D projects are colored coded to indicate their status and assigned to one of the following categories:

A - An industry developed program or R&D results are needed for a utility to submit an application for Second License Renewal (SLR) to the NRC.

B - Sufficient information exists to submit a SLR application, but continued R&D projects are needed to provide informed insights for aging management, inspection intervals and repair/replacement decisions.

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C - R&D projects are not needed for SLR, but the projects support long-term sustainability based on addressing obsolescence and economic improvements for extended operations.

The EPRI-LTO and the DOE-LWRS Program use the ITT to ensure the necessary R&D projects being performed at the right time to support long-term operations of nuclear power plants by plant owners and operators.

In 2014, the ITT was revised to link with an EPRI Technical Report (3002000576) that identified R&D technical needs to support specific Aging Management Programs (AMPs) as they could be applied for SLR. The report noted three categories of R&D efforts:

1. R&D support to address knowledge gaps for 60 to 80 years operation to better understand and manage materials performance.

2. R&D supporting role where aging degradation is well-characterized.

3. No new R&D role identified.

Category 1 broadly represents the highest priority area for R&D supporting LTO. The revised table now links issues to the R&D need category for AMPs from the report. It is important to note, however, that each AMP includes a range of activities and that not all activities in the AMP may benefit from additional R&D. The descriptions in the ITT have been modified to focus on the specific information needs. It is also useful to note that issues have been modified or added to provide correspondence to the issues identified in the Expanded Materials Degradation Assessment (EMDA) published by the NRC (NUREG/CR-7153, Volumes 1-5, October 2014). This report utilized a Phenomena Identification and Ranking Table (PIRT) process to highlight key technical issue areas for metal components (reactor vessel, internals, steam generators, and piping systems),

concrete structures, and electric cables.

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Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 1 Primary PWR Coupons placed in reactors to LTO Materials NA A XI.M31 Commitment to or System Surveillance represent fluence to 60 years are Reliability TLAA implementation of the Metals capsules with important to validate analytical Program B likely fo r su rveillance capsule program is Aging fluence predictions of vessel (MRP) Westing- Category 1 needed for an SLR application.

representa- emb rittlement. house for M31 tive of 60- designs Will be collecting dat a to 80 plus years of The Materials Reliability Program and A fo r years operation.

operatio n (MRP) has two projects in place to B&W generate high fluen ce PWR pending surveillance dat a to 80 years specimen operation; program

1) optimize the withdr awal plan.

schedules of the remaining capsules to provide data coverage to high fluences

2) fabrication and irradiation of supplemental surveillance capsules (slat ed for insertion in 2 PWRs in Fall 2016).

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Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Other) 2 Primary BWR Coupons placed in reactors to LTO Boiling NA A XI.M31 BWRVIP:

System Surveillance represent fluence to 60 years are Water TLAA Task 2.1 Metals capsules with important to validate analytical Reactor Task 2.11 Aging fluence predictions of vessel Vessel Category 1 Task 2.35 representa- emb rittlement. and for M31 Task 2.36 tive of 60- Internals Specific EPRI plus years of The Boiling Water Reactor Vessel Program Project Commitm ent to o r operation and Internals Program (BWRVIP) (BWRVIP) started in implementation of the has a planned project to develop a 2015 t o surveillance capsule program is replacement for or an extension address needed for compliance with of the existing Integrated needs and 10CFRS0 and therefore an SLR Surveillance Program (ISP) from 60 potential application. Extension t o 80 to 80 years of operation. This actions. years will consider work is planned to start in 2015. development of new capsule specimens, use of alternate means t o monitor RPV.

3 Primary Analysis of Understand and assess the MRP B (for Category 1 Related t o Items 1 and 2 fo r System reactor performance t rends of RPV PWRs) for M31 vessel specimens. PWROG Metals pressure embrittlement effects impacting effort to utilize a Master Curve Aging vessel t he nozzle course for PWRs. process for fracture toughness.

embrittle- Tied to industry effort on BTP ment from 5-3.

long-term neutron fluence 65

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 4 Cable Aging Understand Gather actual in-plant radiation LTO DOE B Category 1 Long-term R&D to support the potential and temperature data to LWRS for El and E2 continued improvement of the synergistic determine the actual radiation Category 3 basis for the AMPs.

effects of exposure and temperature for E3 radiat ion and environment for assessing cable Specific EPRI temperature performance for 60 to 80 years. Project on cable started in insulatio n for 2014 and long-term continuing to operations develop actual plant data on radiation and temperature environments 66

Issue Primary Sub-issue Det ailed Descr ipt ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 5 Primary Environ men- Extend dat a on and predictions of LTO Primary DOE B Category 1 PSCR:

System tally assisted crack growth from EAC of Ni alloy System LWRS for MllB Task 8 Metals cracking base material and weld materials Corrosion Subtask 9a Aging (EAC) of (600, 690, 82/ 182, 52/ 152)for Research Develop data nickel alloy operating environments and (PSCR) to update Long-term R&D to support base and f luence conditio ns to 80 years of MRP-227 to continued improvement of the weld operation. address 80 AMPs and appropriat e materials years. RAI locations, if any, to monitor i mpact based on fundamental possible understanding of mechanism.

depending on timing of MRP-227 revision for 80 years.

Category 2 for M l , M2, M4, M7, M8, and 19 Category 3 for M32 67

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 6 Primary Environ men- Extend dat a on and predictions of LTO PSCR NA B Category 1 PSCR:

System tally assisted crack growth from EAC of stainless for M9 Task 8 Metals cracking steel base material and weld Aging (EAC) of materials for operating Develop data stainless steel environments and fluence to update Long-term R& D to support base and conditions to 80 years of BWR continued improvement of the weld operation technical AMPs.

materials bases to address performance to 80 years. Revision to EPRI Technical Report on Divider Plate Category 2 Cracking to address impact to for Ml, M2, 80 years for M19.

M4, M7, M8, M19, M2S, and M35.

Category 3 for M32.

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Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 7 Primary Ir radiation Extend dat a on IASCC of austenit ic LTO BWRVIP DOE B Category 1 PSCR:

System assisted stai nless steel internals (shrouds, MRP LWRS for M9 and Task 1 Metals stress baffle bolts, ... ) and cast stainless PSCR M16A Aging cor rosion steel for operat ing environments BWRVIP:

cracking and fluence conditions to 80 years Category 2 Task 2.5 (IASCC) of of operation. Currently includes for M2 Task 2.6 austenitic t esting of high fluence sample Task 2.7 and cast components as well as irradiation Specific EPRI Task 2.15 stainless and testing of X-750 and XM-19 Proj ect to Task 2.34 steel; shroud repair materials in t h e identify EPRI Ir radiation- future. technical Long-term R&D to support induced report s that continued improvement of the creep of DOE-LWRS is performing swelling may be AMPs.

reactor evaluations and investigation of impacted by internals irradiation-induced phase operation This effort will include updates t ransformations. beyond 60 to EPRI technical reports.

years.

8 Primary Thermal Investigate fundamental LTO PSCR DOE B Category 1 Long-term R& D to support System aging of cast mechanisms and ext end data on BWRVIP LWRS for M 12 continued improvement of the Metals austenitic thermal aging of ferritic-aust enitic and MRP AMPs. Continui ng effort w ith Aging stainless steel stai nless welds and CASS materials NRC on screening criter ia.

(CASS) and at LWR temperatures and the Stainless effects of thermal aging on Steel Welds mechanical properties and corrosion resistance for operating environments and fluence conditions to 80 years of operation.

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Issue Primary Sub-issue Det ailed Descr ipt ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Descr iption LTO Program LWRS Category and Category (New) Description Status (Ot her) 9 NOE Flaw Need to develop a method for Non- C Cat egory 1 Activities will be i mpacted by Technology d etection NOE of CASS. Current inspection destruc- for M12 screen ing process for CASS Advance- methods for method is enhanced VT-1. tive Qualification materials.

ments cast Evaluation and austenitic (NOE) acceptance stainless Program required for steels NOE 10 Pr im ary Analysis of Continued R&D projects to expand LTO BWRVIP DOE B Category 1 BWRVIP:

System reactor dat a sources for embrittlement MRP LWRS for M31 Task 2.1 M etals pressure t rend correlations and direct Task 2.11 Aging vessel measurement of fracture Develop data Task 2.35 embrittle- toughness to assure accurate to update Task 2.36 ment from assessment of embrittlement technical long-t erm behavior at high fluences bases to Long-term R&D t o support fluence characteristic of 80 years address continued improvement of the operation. DOE-LWRS has performance AMPS.

irradi ated a large number of to 80 years.

specimens at ATR-2. These This work is fully coordinated specimens w ill be tested over a w ith specimen surveilla nce period from 2015 to 2017. progr ams.

EPRI supplemental surveillance capsules will also contribute data.

70

Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Othe r) 11 Concrete Concrete Concrete issues resolution LTO NOE DOE B Cat egory 1 Limited current guidance for and issues guidelines and analysis tools for LWRS for 56 A5R management. LTO funded Concrete resolution, managing alkali silica reaction efforts to address need and if Aging guidelines (A5R), including testing and Develop data further evaluation indicates a and analysis inspection techniques. to update need for aging management tools technical program.

bases to address performance to 80 years.

12 Concrete Concrete Concrete issues resolution LTO NOE B Category 1 Current R&D project in and issues guidelines and analysis tools for (co- for S6 progress expected to provide Concrete resolution, managing boric acid degradation f unded understanding of significance Aging guidelines on the spent fuel pool (5FP) with Develop data to LTO. Project report in 2016.

and analysis concrete and rebar. Pilot study of MAI for to update tools concrete cracking of fuel pools at pilot technical liner connections. The issue is study) bases to corrosion of metal reinforcement address from boric acid. performance to 80 years.

13 Concrete Evaluation of Concrete exposed to external LTO NOE DOE B Category 1 Long-term R&D to support and concrete stressors may age at an LWRS for 56 continued improvement of the Concrete structures accelerated rate. Research will basis for the A MPs.

Aging subject to extend the data on rate of Develop data Project in LTO to fund external degradation to encompass to update additional work to assess stressors potential operation to 80 years or technical radiation effects and if further (radiation beyond for radiation and bases to evaluation indicates a need for and temperature damage to the address aging management program.

temperature) reactor support structure and performance biological shield. to 80 years.

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Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 14 Concrete Evaluation of Assess potential for post- LTO B Category 1 Project in LTO to fund and concrete tensioned concrete structures to for 56 additional work to assess Concrete structures experience creep degradation effects and risks.

Aging subject to over time that impacts structural Develop data creep aging integrit y and performance. to update degradation technical bases to address performance to 80 years.

15 Cable Aging Testing and Testing and aging management of LTO Equip- DOE B Category 1 Long-term R&D to support aging cables including submerged/ ment LWRS for El and E2 continued improvement of the management wetted cables, EQ and non-EQ, Reliability basis to assess r emaining useful of cables medium and low voltage to (ER) Category 3 life.

(submerged/ extend data for operating Program for E3 wetted, environments to 80 years of EQ/non-EQ, operation.

medium and low voltage) 16 Cable Aging Understand Conduct research t o assess impact LTO DOE B Impact to EQ cable basis.

factors of diffusion limited oxidation LWRS/ Current R&D funding under impacting (DLO) on cable qualification and NRC Re- NRC-RES and DOE.

qualified life assess conditions capable of search of cables producing inverse temperature effects on cable aging.

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Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 17 Cable Aging Condition Continue to develop the state-of- LTO ER DOE C Category 1 Supports long-term Monitoring technology on methods for Program LWRS for El and E2 sustainability by addressing for Cables condition monitoring of installed obsolescence and economic cables to allow i mproved accuracy Category 3 improvement.

in tracking actual aging rates for E3 relative to predictive results from t est data.

18 Primary Analysis of Determine if thermal MRP C Currently assessing as a System potential embrittlement is a significant potentia l issue through ASTM M etals thermal aging phenomenon for PWR El0.02 working group. PWROG Aging embrittle- nozzles in LTO. effort also likely in 2017 using ment effects specimens removed from on PWR reactor head.

vessel nozzles 19 Primary Post- Issues associated with annealing LTO DOE C Category 1 Supports long-term System irradiation must be investigated before it can LWRS for M 31 sustainability by addressing Metals annealing of be considered as a mitigation Lower obsolescence and economic Aging reactor option for RPV embrittlement . priorit y item improvement. Not a likely pressure due to low implementation process for vessels likelihood of SLR.

usage 20 NDE Non- NDE methods {irreg. welds, vol. Materials/ C Category 1 Dependent on current Technology dest ruct ive exam of CASS and J-grooves, eddy NOE for M 12 discussion o n screening criteria Advance- evaluation current of SGs). Program Qualification for CASS concerns.

ments methods for and irregular acceptance welds, cast required for austenitic NDE stainless steels, J-grooves, etc.

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Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Othe r) 21 NOE Detection Potential need to develop an NOE No current requirements.

Technology method for efficient method to assess Program Advance- corrosion on corrosion damage to containment Defer to ASME Code ments backside of liner. Current inspections are VT. Requirement, if any.

containment liner 22 Concrete Detection of Potential need for both NOE and LTO NOE DOE B N/A Potential area of concern per and degradation evaluation process to confirm Pr ogram LWRS NRC presentations on Concrete in i naccessi- structural integrity of concrete Structural AMP changes for Aging ble concrete structures without direct surface SLR.

access.

23 Primary Expansion of Expansion of Materials LTO Materials NRC Re- A N/A MOM has been expanded to System MOM and Degradation Matrix (MOM) and Program search include 60 to 80 years of Metals IMTfor Issue Management Tables (IMT) to operation and is reviewed and Aging primary include mechanisms acting DOE updated on a routine cycle.

metals to 80 beyond 60, to 80 years for primary LWRS NRC EMDA wa s published in years metals. EMDA October 2014.

Expansion of the PMDA into the EMDA.

24 Primary Environ men- Conservative assumptions in Reg LTO Materials DOE B TLAA Long-term R&D to support System tal effects on Guide for EAF creates uncerta inty Program continued improvement of the M etals fatigue life fo r long-term operation. Upon Category 2 basis for the A MPs. Key R&D Aging for nickel completion of the work EPRI plans for Ml focus on reconciliation of alloys and t o work through the ASME code Develop data laboratory test results to actual stainless steel on needed code revisions to update in-service material technical performance.

bases to address performance to 80 years.

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Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 25 Concrete Concrete Concrete issues identification, LTO NDE DOE B Initial documentation and issues prioritization from operating LW RS completed subject to periodic Concrete identification experience, expert elicitation, and updates.

Aging considerat ion of experience and analysis from other industries.

26 Neutron Neutron Follow guidance for the High Level B Category 2 Long-term R&D to support Absorber Absorber management of BORAL and Waste for M40 cont inued improvement of t he Materials materia ls for performance accelerated aging (HLW) basis for the A MPs.

long-term tests.

operations 27 Under- Testing and Develop advanced methods for ER B Category 2 NEI Initiative 09-14 was ground and inspection testing, inspection, and Program for M41 completed in 2014.

BOP m ethods for assessment of buried piping.

Equipment buried piping Long-term R&D to support Aging continued improvement of the basis for the AMPS.

28 Under- Mit igation of Develop technical bases and ER B Category 2 Address demonstration of ground and corrosion via guidance for the effective Program for M41 cat hodic prot ection BOP cathodic application of cathodic protection effectiveness for range of soil Equipment protection t o mit igate corrosion of buried conditions and piping lay-o ut.

Aging piping.

29 Under- New New materials and methods for ER C Category 2 Supports long-term ground and mat erials and BOP system replacement or Program for M41 sustainability by addressing BOP m ethods for refurbishment. NDE obsolescence and economic Equipment balance-of- Program improvement in management Aging plant processes.

replacement/

refurbish-ment 75

Issue Primary Sub-issue Det ailed Descr ipt ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 30 Coatings Coatings These issues might be risks such as ER B Category 2 Recent NRC Interim Staff issues that coatings which could block Program for S8 Guidance effort suggests that could impact containment sumps or coating this is an issue area for LTO.

long-term performance issues for Aging of coatings will need to operations containment liners and buried be addressed by developing piping. Issues could be NOE and testing processes to opportunities, such as new confirm coating int egrity.

coatings which have desirable properties that could enhance safety or reduce costs. Current efforts in ER Program.

31 Under- Application of Monitoring, assessment of ER Category 2 BPWorks is a released EPRI ground and BPWORKS degradation, and estimation of Program for M41 software product that will be BOP met hodology RUL using t he EPRI BPWorks maint ained and u pdated.

Equipment to estimate methodology.

Aging remaining useful life 32 Under- Selective Selective leaching of elements ER B Category 3 Plant specific impact that will ground and leaching of from buried metal piping (define Program for M33 likely require new NOE BOP buried metal t ypes) is a form of aging NOE techniques to replace sampling Equipment piping degradation. R&D could be Program and destructive t est ing Aging directed at monitoring, aging approach.

management and lifetime estimation methodology for susceptible p iping.

33 SSC On-line On-line monitoring, diagnostics, LTO C N/A Initial guideline report issued M o nitoring monitoring, and prognostics for active by EPRI.

Diagnostics diagnostics, components including guidelines and and for monitoring, automated Supports long-term Prognostics prognostics diagnostic advisory t ools, and sustainability by addressing for active database of fault signatures. obsolescence and economic components improvement.

76

Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Other) 34 SSC On-line On-line monitoring, diagnostics, LTO lnstrumen DOE C N/A Duke and Exelon pilot plant Monitoring monitoring, and prognostic pilot studies: -tation & LWRS projects.

Diagnostics diagnostics, transformers and emergency Control and and diesel generators. (l&C) Supports long-term Prognostics prognostic Program sustainability by addressing pilot studies Genera- obsolescence and economic for tion improvement.

transformers and generators 35 Asset Life-cycle Developing life cycle management LTO C N/A Supports long-term Manage- management guidelines and analysis tools to & EDF sustainability by addressing ment and tools to support decisions on continued obsolescence and economic ILCM support operation, refurbishment, and improvement. This product will decisions on replacement of large components has been released for use and continued including timing, costs, and will be maintained through a operation, engineering options. software user group process.

refurbish-ment and replacement of large components 36 Risk- Identification Invest igation of safety assessment LTO C N/A Case studies completed.

informed of technical applications that are expect ed to Safety gaps in safety be important to long term Margins assessment operat ions, and identification of Cha racteri- with respect technology gaps that could zation to long-term jeopardize the success of these operations applications.

77

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 37 Risk- Development Based on an inventory and LTO DOE C N/A Supports long-term informed o f enhanced f unctional mapping of current LWRS sustainability by addressing Safety safety safety analysis tools and on the obsolescence and economic Margins analysis technology gaps identified i n issue i mprovement.

Cha racteri- codes to 6.1, enhanced safet y analysis zation address codes and capabilities will be technical specified and developed.

gaps INL is taking the lead in development of next generation code for mechanistic simulation of t ransient s and accidents.

38 W elding W elding of Repair technique- welding of LTO W elding & DOE C N/A WRTC:

technology irradiated irradiated react or internals Repair LWRS 2010-009 reactor materials and weld repair. Technol- He issues at 2010-037 internals ogy high fluence Cent er per operation Supports long-term (WRTC) to 80 years sust ainability by addressing will require obsolescence and economic new improvement.

techniques to allow internals repairs. Plant specific impact.

78

Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Othe r) 39 Digital l&C Next- Pilot studies and Industry LTO DOE C N/A Supports long-term Moderni- generation Guidelines for next generation LWRS sustainability by addressing zation and l&C, human l&C, human/system interface, and obsolescence and economic Enhanced /system information technology improvement.

Functional- interface, and architecture and capabilities.

ity information technology architecture and capabilities 40 SSC On-line On-line m onitoring, d iagnostics, LTO DOE C N/A Supports long-term Monitoring monitoring, and prognostic for passive LWRS sustainability by addressing Diagnostics diagnostics, components. obsolescence and economic and and improvement. In progress work Prognostics prognostics focused on concrete structures.

for passive components 41 NOE Investigate OOE-LWRS program has NOE DOE C May impact Supports long-term Technology techniques developed road maps for future LWRS multiple sustainability by addressing Advance- for NOE that sensor and NOE enhancements. AMPs after obsolescence and economic ments can provide EPRI NOE Program works qualification improvement.

new continues to advance the ability to and technologies detect and monitor for various acceptance to monitor forms of degradation and provide processes are materia l and Industry leadership for NOE complete.

component qualification and testing.

performance.

79

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 42 Digital l&C Dedicated Establish an Information and l&C DOE C N/A Moderni- user facility (IIC) user facility to support the LWRS zation and to support development, modeling, Enhanced development, verification, and testing of Functional- testing, advanced IIC systems.

ity modeling, and verification of advanced information and l&C systems 43 Risk- Enhanced Enhance PRA capabilities and tools LTO C N/A Supports long-term informed probabilistic t o perform risks assessment. sust ainability by addressing Safety risk obsolescence and economic Margins assessment improvement.

Cha racteri- capabilities zation 44 Risk- Development Formulation of margin-based LTO DOE C N/A Supports long-term inform ed of margin- safety case framework, analysis LW RS sustainability by addressing Safety based saf et y capability, and calculation tool obsolescence and economic Margins case (RELAP-7). improvement.

Cha racteri- framework zation and calculat ion tool 80

Issue Primary Sub-issue Det ailed Descr ipt ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her) 45 Methods to Develop Continue development and Materials C N/A Supports long-term mitigate or methods for demonstration work on peening Programs sustainability by addressing improve stress and other techniques for stress obsolescence and economic stresses improvement improvements. Continue work on improvement.

and repair weld overlays as a repair options technique for long-t e rm operations.

46 Fuel Pool Fuel pool Fuel pool liner cracking is an aging NOE C N/A Supports long-term Internals internals degradation issue that can lead to Program sustainability by addressing aging and radiat ion leakage to groundwater obsolescence and economic deterioration or other clean areas and improvement.

deterioration of the fuel pool structure. Methods t o identify, mitigate and repair liners cou ld address this issue.

Plant Terrorism Following the terrorist attacks of Risk& N/A Security threat and September 11, 2001, every U.S. Safety risk plant conducted a risk assessment Manage-assessment against a suite of t hreats using a ment nuclear specific, some considerably beyond the Design Basis Requirements of the plant.

This exercise co nfirmed the resiliency of the plants against these threats or identified opportunities to increase this resiliency or plant response.

Realistic t hreat scenarios evolve, and it is appropriate to perform t his RAMCAP analysis and other assessments periodically.

81

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her)

Nuclear Hydrogen ISFSI licenses are generally for 20 Used Fuel N/A Fuel Design embrittle- years but must be extended much Manage-and Perfor- ment of on- longer for long term operations. ment&

mance site spent An important aging mechanism is High Level fuel storage hydrogen embrittlement that Waste installations could affect the ability to Program t ransport t he f uel or repackage it for transport.

Nuclear Silicon SiC Cladding for Improved Fuel DOE- N/A Fuel Design carbide Operations. Reliability FCR&D and Perfor- cladding for Program mance improved nuclear fuel performance Equipment Reduction in A better technical representation ER N/A Qualifica- scope and of the containment conditions Program tion costs that are used for specifying Improve- associat ed equipment qualifications cou ld ments with allow equipment to operat e equipment longer without repair or qualification replacement and could reduce the due to less procurement costs. A conservative commit ment t o perfor m technical containment temperature assumpt ions monit oring is one consideratio n; use of a smaller, more accurate source term is another.

82

Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Othe r)

Seismic Potential Potential plant modifications in Risk& N/A EPRI SQUG Program.

Issues plant response to greater seismic Safety modifications hazards frequencies or to a seismic Manage-in response event was identified in the EPRI ment to greater study of Life Limiting Issues. It had seismic a relatively high priority among hazards external conditions that could frequencies impact life extension. The seismic or to a hazard distribution for plants in seismic event the Eastern U.S. has increased in change recent years. This increase will flexibility in increase the seismic risk at plants the future which could limit operational and design change flexibility in the future.

Nuclear Advanced Advanced design, safety analysis Consor- DOE N/A Fuel Design design, safety and simulation tool. This tool tium for CASL and Perfor- analysis and includes incorporation of resu lts Advanced mance simulation from issue 5.2, models of Simula-tools for new composite cladding and other tion of nuclear fuel advanced fuel designs, advanced Light approaches mathematical methods, and the Water experimental campaign to verify Reactors the tool. (CASL)

Nuclear Advanced Advanced fuel designs including Fuels DOE - N/A Fuel Design nuclear fuel new geometries, high enrichment, FCR&D and Perfor- designs high power, and high burn-up mance (geometries, fuels. This issue is related to the fuel content, potential benefits from a next high burnup) series of extended power uprates.

83

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her)

Environ- Water Plant cooling depends on the Environ- N/A EPRI Environmental Sector has mental availability continued availability of cooling mental the lead in developing a Interface and quality water of suitable temperature, strategy for t his issue.

and quant ity, and quality. In addition, enhanced licenses to use the water must be cooling maintained even as other stresses technologies on the watershed increase and environmental expectations for plant discharge could be more challenging. Enhanced cooling technologies, water availability management, and better technical understanding of the plants impact can all contribut e to the assurance of long term plant cooling capability.

Primary Advanced Plant uprates and long t erm PSCR DOE N/A Initial screening efforts are in System alloys and operations place additional stress LWRS progress.

Metals fabrication on r eactor internals. Repairs are May impact Aging methods for complicated by radiologically multiple reactor induced changes in the metals and AMPs if new internals by the radioactive environment materials are replacement inside the reactor. This issue qualified and includes construction methods for implemented shroud replacement.

84

Issue Primary Sub-issue Det ailed Descr ipt ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her)

Low Level Impact of Currently, 85% of U.S. utilities lack Chemistry N/A Waste Plant Life the ability to dispose of higher and Low Extensions on activity low-level waste (Class B Level Low Level and Class C wastes). The lack of W aste Waste (LLW) off-site disposal options and (LLW)

Management added storage requirements can and be used as an argument against Decommis- long term operation. With longer sioning operation, activity content may Planning increase due to increased contact time and activation of metal components or, alternatively, increase waste volumes as a result of component replacement s.

Many plants have replaced components with lnconel materials (e.g. Alloy 690, Alloy 800). However, it is uncertain how operation with the new mater ial will affect waste characterization and ultimate disposal of that waste stream. Generation of Nb-94 is a major co ncern for some lnconel materials and may affect disposal during decommissioning.

A plant must develop a long term waste management plan that properly accounts for future waste liabilities. Source term estimates and a material handling plan will be needed.

85

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her)

Digital l&C Development l&C Compatibility Equivalency l&C N/A Moderni- of l&C Database. Program zation and compatibility Enhanced equivalency Functional- database ity Digital l&C Long ter m Addressing obsolescence concerns l&C N/A Moderni- operations of and providing technical Program zation and 7300 l&C justification for long term reliable Enhanced Systems operation of 7300 l&C Systems in Functional- lieu of replacement.

ity Nuclear Advanced Advanced understanding, analysis, Fuel Users N/A Fuel Design understand- and modeling capability of Group and Perfor- ing, analysis, degradation mechanisms for mance and modeling nuclear fuel. Specifically, issues of nuclear include changes in mechanical fuel degrada- properties w it h exposure, pellet tion mecha- clad interaction, coolant crud nisms chemistry interactions, and mesoscale modeling.

Nuclear Effect of Water chemistry is known to have Fuels DOE N/A Fuel Design water both positive and deleterious Program CASL and Perfor- chemist ry on effects on plant materials mance fu el behavior (including fuel behavior). There over are also opportunities to improve extended operations, perhaps by innovative operation chemistry changes or nanopa rticle addition.

86

Issue Primary Sub-issue Det ailed Descript ion EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Ot her)

Environ- Identify and Continued operation of hydro- N/A Plant licensing issues mental propose dams on the same watersheds can Interface technical jeopardize long-term operations if solutions to conditions of FERC re-licensing are hydro-dam unfavorable. This activity could re-licensing identify and propose technical issues that solutions to hydro-dam re-could licensing issues that could jeopardize jeopardize long-term operation.

long t erm operation.

Integrated, Assessment Manufacturing capabilities (large Advanced N/A Phased of large components, etc.). Nuclear Refurbish- component Technol-ments and manufac- ogy (ANT)

Uprates turing capabilities NOE Risk- Total in-service inspectability NOE N/A Technology informed using NDE methods cannot always Program Advance- sampling for be achieved due to inaccessibility ments in-service of the components. Risk informed inspection sampling procedures can be developed and validated where access issues exist.

NDE Analytical Extremely low prob. of failure Materials N/A Technology framework (xLPR - risk informed analysis for /NOE Advance- for extremely hidden welds, etc.). Programs ments low probability of rupture 87

Issue Primary Sub-issue Detailed Description EPRI EPRI DOE- ITT AMP Impact Comments ID Issue Description LTO Program LWRS Category and Category (New) Description Status (Other)

Emergency No LTO issues identified. N/A Prepared-ness Personnel No LTO issues identified. ER N/A knowledge Program Capture Pu blic No LTO issues identified. N/A Education about Current Fleet vs.

New Plants 88

Appendix A Industry Cost Sharing (This appendix is proprietary and has special access requirements.)

A-1

Note to requester: Attachments are immediately following.

From: Moyer, Carol Sent: Thu, 28 Sep 2017 14:30:23 -0400 To: Frankl, Istvan Cc: Hiser, Matthew;Purtscher, Patrick

Subject:

For Review: Harvesting Poster for PLiM Attachments: Harvesting NRC Poster for PLiM_cem_ ptp.pptx, PLiM2017_HarvestingPoster_Hiser_F390.pdf, NRC 665 Harvesting Poster.pdf

Steve, Matt created the attached Harvesting poster for the PLiM conference. The attached version includes some minor edits by Pat and myself.

Carol From: Hiser, Matthew Sent: Friday, Sept ember 15, 2017 11:07 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting Hi Amy and Carol, Here's my initial stab at the harvesting poster for PLiM.

Please take a look and let me know what you t hink.

Thanks!

Matt From: Moyer, Carol Sent: Friday, July 21, 201711:26 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting Thank you both!

The conference website is here: http://www-pub.iaea.org/iaeameetings/50811/Fourth-lnternational-Conference-on-Nuclear-Power-Plant-Life-Management Poster guidelines are here: http://www-pub.iaea.org/MTCD/Meeting s/PDFplus/2017/cn246/cn246PosterGuidelines.pdf No specific due date is listed for posters.

M. Key Dates and Deadlines Submission of Form for Submission of a Paper (Form B) and extended synopsis (800 words) 28 May 2017

Submission of Grant Application Form (Form C): 28 May 2017 Notification of acceptance of papers/posters: 30 June 2017 Submission of full paper (only upon request by the IAEA): 18 October 2017 Posters may only be "due" at the conference itself? It would not hurt to have it done by 18 Oct.,

the paper deadline, though. It is unclear to me what they would do with a full paper, if one was not requested by IAEA. But I think you can prepare one, if you like. If they will not publish it as part of PLiM, we can find another home for it, or just release it as an NRC document.

-Carol From: Hiser, M atthew Sent: Friday, July 21, 2017 11:12 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting OK, I can work with Amy to make a poster. Rob and Pat and our PNNL contractor are also listed as co-authors ...

From: Hull, Amy Sent: Friday, July 21, 2017 11:08 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>; Hiser, M atthew <Matthew.Hiser@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting I think this is a good opportunity to publicize harvesting work and develop collaboration. Task 2 in UNR. I will make the poster. When is it dur?

From: Moyer, Carol Sent: Friday, July 21, 201710:57 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting I'm pretty ambivalent about it. Amy, do you have a strong desire to make up a poster for the PLiM? Are there other co-authors to be consulted?

-Carol From: Hiser, M atthew Sent: Friday, July 21, 2017 7:28 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting Hi Carol, Not terribly interested in a poster... The other thing is then you'd have to babysit the poster during poster session(s)?

I'd suggest we say thanks for the offer, but that's alright... what do you think?

Thanks!

Matt From: Moyer, Carol Sent: Thursday, July 20, 2017 12:49 PM To: Hiser, M atthew <M atthew . Hiser@ nrc.gov>

Subject:

FW: FW: PLiM abstract on harvesting

Matt, I am a bit confused by the pronoun used in this email. ..

Are you interested in doing a poster instead?

Carol From: KRIVANEK, Robert iaea.org

Sent: Thursday, July 20, 201711:10 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] FW: PLiM abstract on harvesting You have just agreed that we will add this paper to poster session.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

@ 60Years I A EA Atmm for P1'llCI' mu/ /)crl'lopme11r

Follow us on www.iaea.org From: KRIVANEK, Robert Sent: Thursday, 20 July 2017 16:10 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

We asked you to submit your synopsis through INDICO (see email below) but it did not happened. So we were not able to send your synopsis to programme committee for evaluation and it will not occur on the conference programme.

Sorry for that but there are currently 300 delegates and 150 synopsis, so we were not able to track each of them separately.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager

Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1} 2600-22018 I F: (+43-1} 2600-26007 I 60 Yea~

IAEA 10111 for P <let mul D1*1* lopmt*111 Follow us on www.iaea.org From: KRIVANEK, Robert Sent: Friday, 26 May 2017 08:55 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Cc: KHAELSS, Martina <M.Khaelss@iaea.org>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

Thank you for your synopsis. We have opened INDICO system for this week, so please submit it through the system.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(~ )

~ 60Years IA EA ,\u,111.1 for l'<'CIC<' mu/ D<*re/opm<'llf Follow us on www.iaea.org

From: Carol.Moyer@nrc.gov [m ailto:Carol.M oyer@nrc.gov]

Sent: Friday, 26 May 2017 00:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: Hiser, M atthew <M atthew. Hiser@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

PLiM abstract on harvesting

Dear Mr. Krivanek,

The US NRC would like to propose one more presentation for this autumn's PLiM conference, on harvesting of materials from operating and decommissioning power plants. I understand from Sherry Bernhoft that you already have an impressive number of abstracts, so I will understand if there is not room in the program for this one. Nevertheless, we would appreciate your consideration of this proposal.

Again , please let me know if you need any additional information. Many thanks, Carol Carol E. Moyer Sr. Materials Engineer Office of Nuclear Regulatory Research RES/DEICMB carol.mover@nrc.gov 301-415-2153 From: KRIVANEK, Robert Krivanek@iaea.org

Sent: Tuesday, May 23, 2017 2:41 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Carol,

I will arrange it. Thank you.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r. krivanek@ iaea.org I T: (+43*1) 2600-22018 I F: (+43*1) 2600-26007 I

( AL

~~~

~ 60Years I A EA AW111f for Peace ""cl Dcn*/op111,*11t

Follow us on www.iaea.org (I.J!bg ** Im From: Carol.Moyer@nrc.gov [1]

Sent: Monday, 22 May 2017 20:44 To: KRIVANEK, Robert <R.Krivanek@ iaea.org>

Subject:

RE: RE : CN246_ PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

Since the formal deadline for abstract submissions has passed, I am no longer able to access the lndico system through the PLiM website (https://conferences.iaea.orq/indico/event/134/).

My abstract and Form Bare attached.

Are you able to work with these documents? Is there anything else that you need me to do at this time?

Thanks again for your patience and assistance, Carol

From: Moyer, Carol Sent: Monday, May 22, 2017 10:59 AM To: 'KRIVANEK, Robert' <R.Krivanek@iaea.org>

Cc: Frankl, Istvan <lstvan.Frank l@nrc.gov>

Subject:

RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

My abstract is attached to this message, for your info. Separately, I will submit it through the lndico system. Please let me know if you need any other information at this stage.

Thank you, Mrs. Carol Moyer From: KRIVANEK, Robert fmailto:R.Krivanek@iaea.org]

Sent: Monday, May 22, 2017 2 :56 AM To: Moyer, Carol <Carol. Moyer@ nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

(External_Sender] RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr Moyer,

It will be fine if you submit your abstracts this week.

We are looking forward to see a strong NRC delegation in Lyon.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I tj )

~~ 60Years I A EA A1t11111 for f>c1'1n' mu/ Dc*1*c*lo1n111'1'f

Follow us on www.iaea.org (I.J!bg ** Im From: Carol.Moyer@nrc.gov [2]

Sent: Friday, 19 May 2017 23:19 To: KRIVANEK, Robert <R.Krivanek@ iaea.org>

Cc: KANG, Ki-Sig <K.S.Kang@iaea .org>; Tregoning, Robert <Robert.Tregoning@nrc .gov>

Subject:

RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

The U.S. NRC intends to submit several abstracts for consideration for the PLiM conference in October. We have a short delay in completing one of our abstracts. I will be submitting it early next week, and I hope that you still will be able to consider it for the conference.

Thank you ,

Carol Moyer Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol.moyer@nrc.gov 301 -415-2153 From: R.Krivanek@iaea .org (ma ilto :R.Kri vanek@iaea .org1 Sent: Friday, April 21, 2017 8:44 AM To: R.Krivanek@iaea .org

Subject:

[External_Sender) CN246_ PliM_Abstract deadline extended to 19 May 2017

Dear all,

Please be informed that we extended the abstract submission deadline to 19 May 2017 and updated the conference accordingly.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@i aea.org I T: (+43-1} 2600-22018 I F: (+43-1} 2600-26007 I 60 Years I A EA Atom for P,*a e and D,*,* lopnu flt

Follow us on www.iaea.org This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this

communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only fo r the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Plate A {41-22" wide)

M. Hise r", P. Purtscher", P. Ra muha llih, A. B. Hull*, and R. Tregoning*

• u.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA hPacific Northwest National Laboratory (PNNL), Richland, WA, USA Plate C (7 .811 Background and Motivation Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs). In the U.S., Potential Criteria for Harvest ing Prioritization there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) A number of criteria may be considered when prioritizing the data from 60 to 80 years. needs for harvesting, including:

Applicabil ity of harvested material for addressing critical gaps Extended plant operation and SLR raise a number of technica l issues that may require further research to understand and quantify aging mechanisms. U.S. utilities and the U.S. Harvesting for critical gaps prioritized over less essential Nuclear Regulatory Commission (NRC) have focused on the aging of systems, structures, and t echnical gaps.

components and in particular four key SLR issues: reactor pressure vessel (RPV) Ease of laboratory replication of the degradation scenario embrittlement, irradiation-assisted stress corrosion cracking of reactor internals, concrete For example, simultaneous thermal and irradiation structures and containment degradation, and electrical cable qualification and condition conditions are difficult to replicate, and accelerated aging assessment. may not be feasible for a mechanism sensitive to dose rate.

Meanwhile, in recent years, a number of NPPs, both in the U.S. and internationally, have

• Unique field aspects of degradation shut down or announced plans to shut down for various reasons, including economic, For example, unusual operating experience or legacy materials (fabrication methods, etc.) no longer available.

political, and technical chal lenges. Unlike in the past when there were very few plants

• Fleet-wide vs. plant-specific applicability of data shutting down, these new developments provide opportunities for harvesting components that were aged in representative light water reactor (LWR) environments. Greater value in addressing an issue applicable to a larger number of plants.

In a third related development, economic challenges and limited budgets have restricted

• Harvesting cost and complexity the resources available to support new research, including harvesting programs. Given this For example, harvesting un-irradiated concrete or electrical cables less expensive and less complex than constrained budget environment, aligning interests and leveraging with other organizations harvesting from the reactor internals or RPV.

is important to allow maximum benefit and value for future research programs. Availability of reliable in-service inspection (ISi) techniques for the material/ component Current Activities If mature inspection methods exist and are easy to apply, harvesting may be less valuable.

NRC has recently undertaken an effort, with

• Availability of materials for harvesting the assistance of Pacific Northwest National

• Timeliness of the expected research results relative to the objective.

Laboratory (PNNL), to develop a strategic approach to harvesting aged materials from The above potential criteria provide a systematic approach to prioritize data needs for harvesting. Different NPPs. Due to limited opportunities, past organizations may weigh and consider each of these criteria differently based on their interests and perspectives, but harvesting efforts have been reactive to each criterion is likely relevant to some degree for any organization. NRC is interested in engaging with other individual plants shutting down and beginning organizations to prioritize data needs for harvesting and identify areas of common interest.

decommissioning. Given the expected availability of materials from numerous plants Harvesting Database and anticipated research needs to better The NRC is pursuing the development of a database for sources of materials for harvesting, which could include understand aging out to 80 years of operation, the NRC is pursuing a more proactive approach both previously harvested materials and those available for future harvesting. This database wou ld allow for to prioritize the data needs best addressed by aligning of high-priority data needs to the available sources of materials. The level of detail for the database harvesting and identify the best sources of should be appropriate for the factors influencing decision-making. NRC is interested in engaging with other materials to address high-priority data needs organizations ta in developing a the database.

for regulatory research.

The first step in this strategic approach is to Path Forward prioritize data needs for harvesting. A data NRC's experience is that harvesting can yield highly representative and valuable data on materials aging, but these need describes a particular degradation scenario and should be defined with as much efforts wil l be challenging. Having a clearly defined objective and early engagement with other stakeholders are detail as appropriate in terms of t he material keys to success. As specific harvesting opportunities are identified through this strategic approach, the NRC (alloy, composition, etc.) and environment welcomes opportunities for cooperation and leveraging of resources with other interested research organizations.

(temperature, fluence, chemistry, etc.).

NRC FORM 390 U.S. NUCLEAR REGULATORY COMMISSION 10-2011 NRCMD 3.9 RELEASE TO PUBLISH UNCLASSIFIED NRC STAFF SPEECHES, PRESENTATIONS, PAPERS, AND JOURNAL ARTICLES (Please type or print)

1. TITLE (State In full as It appears on the speech, presentation, paper, orJournal article) 2. ADAMS Accession No.

(Use Template ADM 039)

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants

3. AUTHOR(s)

Matthew Hiser, Patrick Purtscher, P. Ramuhalli, Amy Hull, Robert Tregoning

4. NAME OF CONFERENCE, LOCATION, AND DATE(s)

Fourth International Conference on Nuclear Power Plant Life Management, Lyon , France, October 23-26, 2017

5. NAME O F PUBLICATION Proceedings from Fourth International Conference on Nuclear Power Plant Life Management

6. NAME AND ADDRESS OF THE PUBLISHER 7. TELEPHONE NUMBER OF THE PUBLISHER IAEA YES NO 8. PAGE CHARGES 9. ESTIMATED COST If yes, the Authorizing Official (listed in block 12 below) must approve payment before the paper is No. of Pages @S Per Page = Total 0

sent for publication. If payment Is not authorized, NRC may refuse to pay the page charges, and the author will become personally responsible.

YES 10. CERTIFICATION NO I (ANSWER ALL QUESTIONS) 0 A.

Speeches, presentations, papers, and Journal articles require management and policy reviews of technical and policy TECHNICAL AND POLICY issues per NRC Directive Handbook 3.9, Section 11.A.2. Check the "YES" box to certify that the speech, presentation, REVIEWS I-oaoer or iournal article comolies with this statement.

0 Does this speech, presentation, paper, or journal article contain copyrighted material?

B. COPYRIGHTED MATERIAL If yes, attach a letter of release from the source that holds the copyright.

I-0

. Does this speech, presentation, paper, or journal article require patent clearance?

C. PATENT CLEARANCE If yes, the NRC Patent Counsel must signify clearance by signing below.

NRG PATENT COUNSEL (Type or Print Name) SIGNATURE I DATE 0 Do Is all material referenced in this speech, presentation, paper, or journal article available to the public either through a REFERENCE AVAILABILITY* puolic library, the Government Printing Office, the National Technical Information Service, or the NRC Public Document Room? If no, list below the specific availability of each referenced document.

SPECIFIC AVAILABILITY Does this speech, presentation, paper, or journal article contain measurement and weight values? If yes, all must 0 E. METRIC UNIT CONVERSION - be converted to the International System of Units, followed by the English units in brackets, pursuant to the NRC Policy Statement implementing the Omnibus Trade and Competitiveness Act of 1988, Executive Order 12770, July 25, 1991 .

11 . RESPONSIBLE STAFF MEMBER NAME (Type or print name) OFFICE/DIVISION MAIL STOP Matthew Hiser RES/DE T-10A36 SIGNATURE TELEPHONE NUMBER E-MAIL 1.0.

I DATE (301) 415-2454 MAH3

12. AUTHORIZATION (Cannot be the same person listed in block 11.)

NAME AND TITLE* NRC OFFICIAL AUTHORIZING RELEASE AND, IF APPLICABLE, AUTHORIZING PAYMENT FOR PAGE CHARGES /listed In blocks 8 and 9 abo*e)

Istvan Frankl SIGNATURE TE NRC FORM 390 (10-2011)

NRC FORM 665 /"-...:, U.S. NUCLEAR REGULATORY COMMISSION (07-2016)  !¥ i ADAMSDOCUMENTSUBMIB~ON

\ .....?/ Instructions for completing NRC Form 665 - "Cheat Sheet" (ML15.3.13.A3.1QJ Document Owner Originated By Phone No. (Enter 10 dig its) Mail Stop LAN ID Date Matthew Hiser Carol Moyer (301) 415-2454 T-10A36 MAH3 9/28/2017 If documents are to be put Into a package and have the same release properties, list the Document Titles or Accession Numbers below in the order they should appear. Documents with different release properties and sensitivity levels should be listed on additional forms in the order they should appear. Examples (ML16035A181 J Note: Document Owner is solely responsible for setting the Availability , Document Sensitivity and Document Security Access Level.

Document No. Total Number of Documents in th is package Document Title(s) or Accession No.

Poster, "Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants," for Fourth PLiM Conference Package Title (if necessary):

[Z]

Is this a brief title that can be changed by DPC according to template instruction? Yes No I

[Z]

CEM SUNSI Review has been completed (for Publicly Available Documents) Yes No Initials Document AVAILABILITY (select one)

[{] Publicly Available Non-Publicly Available MD 3.4 Non-Public Item Code (A.3-A.7, B1)

(Indicate Release Date) Document SENSITIVITY (select one)

Immediate Release I I A? I Sensitive Internal Info - Periodic Review Required (all other I I A. 4 I Sensitive Proprietary 0 Normal Release sensitive internal info)

Delay Release Until I I A? I Sensitive Internal Info - No Periodic Review (attorney work I I A. 3 I Sensitive-Security Related - Periodic product & client privilege, and Review Required Date pre-decisional enforcement)

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Document SECURITY ACCESS LEVEL 10 Document Processing Center I =Owner I I [Z] NRC Users I=Viewer I Limited Document Security (Defined by Group or User e.g., Joe Smith= Owner)

Package Accession No. ADAMS Template No. RIDS Code (if applicable) Other Identifiers Special Instructions Submitted By Phone No. (Enter 10 digits) Mail Stop LAN ID Date Submitted to DPC ML020170279 Page 1

Note to requester: Attachment is immediately following.

From: Sircar, Madhumita Sent: Tue, 28 Feb 2017 16:37:54 -0500 To: Hiser, Matthew Cc: Seber, Dogan;Pires, Jose;Philip, Jacob

Subject:

FW: Announcement of Ex-Plant Materials Harvesting Workshop Attachments: NRC Technical Data Needs for Harvesting-MS.pptx

Matt, Please find attached, the last slide is on concrete.

Thanks, Mita Sircar Tel: 301-415-1804 From: Sircar, Madhumita Sent: Tuesday, February 28, 2017 4:32 PM To: Pires, Jose <Jose.Pires@nrc.gov>

Subject:

RE: Announcement of Ex-Plant Materials Harvesting Workshop Sure will do.

From: Pires, Jose Sent: Tuesday, February 28, 2017 4:30 PM To: Sircar, Madhumita <Madhumita.Sircar@nrc.gov>

Subject:

RE: Announcement of Ex-Plant Materials Harvesting Workshop Mita It looks fine to me. Would it be OK to move the second bullet to last? Thanks, Jose.

• Structures exposed to high radiation

.. Large structural sections f.or testing

• Post-tensioned structures

• Corrosion of reinforcing steel, tendon, liner, embedment

• Spent fuel pool and transfer canal-boric acid attack on concrete in PWRs

• Alkali Aggregate Reaction

• Large structural sections for testing From: Sircar, Madhumita Sent: Tuesday, February 28, 2017 3:47 PM To: Pires, Jose <Jose.Pires@nrc.gov>

Subject:

RE: Announcement of Ex-Plant M aterials Harvesting Workshop

Jose,

Please see the last slide (Concrete). Feel free to make any change.

Thanks, Mita Sircar Tel: 301-415-1804 From: Pires, Jose Sent: Monday, February 27, 2017 10:30 AM To: Sircar, Madhumita <Madhumita.Sircar@nrc.gov>; Philip, Jacob <Jacob.Philip@nrc.gov>

Subject:

FW: Announcement of Ex-Plant Materials Harvesting Workshop FYI From: Frankl, Istvan Sent: Friday, February 24, 2017 2:24 PM To: Bloom, Steven <Steven.Bloom@nrc.gov>; Wittick, Brian <Brian.Wittick@nrc.gov>; Morey, Dennis

<Dennis.Morey@nrc.gov>; Alley, David <David.Alley@nrc.gov>; Rudland, David

<David.Rudland@nrc.gov>; Zimmerma n, Jacob <Jacob.Zimmerman@nrc.gov>; Iyengar, Raj

<Raj.lyengar@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>; Seber, Dogan <Dogan.Seber@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>;

Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Pires, Jose <Jose.Pires@nrc.gov>; Berrios, Il ka

<llka.Berrios@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

Announcement of Ex-lPlant M aterials Harvesting Workshop

Dear Colleagues:

RES is hosting a workshop on ex-plant materials harvesting at NRC headquarters on March 7-8, 2017. The scope includes metallic, electrical, and concrete materials or components that could benefit from harvesting. I have attached the draft agenda and workshop introduction slides that cover meeting logistics, motivation, approach, expected outcome, and session expectations.

This workshop includes about two dozen external participants, including representatives from DOE and EPRI as well as international organizations from Japan, Europe, and Canada.

A webinar will be available to allow NRC staff to observe and participate in the workshop:

https://attendee.gotowebinar.com/register/6076202901971284226 .

If you have any questions or need additional information about the workshop, please contact myself or Matt Hiser on my staff.

Thanks, Steve

NRC High-Priority Data Needs for Harvesting

Metals

• Selected areas of interest for harvested materials:

- High fluence reactor internals

• >50 dpa 304 SS from high core outlet temp plant

• Bounding temperature and high fluence for void swelling

- Thermally aged unirradiated CASS

• >30 years at "'320°C; Validate accelerated aging data

- Moderate fluence (1-2 dpa) CASS

• Bolster technical basis for embrittlement in this fluence range

Metals

• RPV

- High fluence vessel with relatively high levels of minor alloying elements (Mn, P, etc.)

- Through thickness section

• Measure fluence, toughness, and chemistry as a function of depth

• Validate fluence calculations

• Components with known flaws Example: weld overlays over known flaws Could be used for NOE evaluations or to assess effectiveness of mitigation techniques

• Components with limiting fatigue life

- Confirm fatigue calculations are accurate by inspecting for flaws

Electrical

• Cables Power cables energized and energized in normal operation Cables from in containment applications

• Electrical components lE MOVs from harsh and mild environments lE Air operated valves 4160 lE breakers lE Molded case breakers 480V, 250V DC, 125 VDC, lE Relays from mild environment GE - HFA, Agastat timing relays, any from Westinghouse, Potter Brumfield, Stuthers Dunn etc.,

• Other Electrical penetrations Batteries

Concrete

• Structures exposed to high radiation

• Post-tensioned structures

• Corrosion of reinforcing steel, tendon, liner, embedment

• Spent fuel pool and transfer canal-boric acid attack on concrete in PWRs

• Alkali Aggregate Reaction

• Large structural sections for testing

Note to requester: Attachments are immediately following.

From: Hiser, Matthew Sent: Tue, 3 Oct 2017 14:07:30 +0000 To: Frankl, Istvan

Subject:

FW: For Review: Harvesting Post er for PliM Attachments: Harvesting NRC Poster for PLiM_cem_ptp.pptx, PliM2017_HarvestingPoster_Hiser_F390.pdf, NRC 665 Harvesting Poster.pdf From: Moyer, Carol Sent: Thursday, September 28, 2017 2:30 PM To: Frankl, Istvan Cc: Hiser, Matthew; Purtscher, Patrick

Subject:

For Review: Harvesting Poster for PliM

Steve, Matt created the attached Harvesting poster for the PLiM conference. The attached version includes some minor edits by Pat and myself .

Carol From: Hiser, Matthew Sent: Friday, Sept ember 15, 2017 11:07 AM To: Moyer, Ca rol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

RE: FW: PliM abstract on harvesting Hi Amy and Carol, Here's my initial stab at the harvesting poster for PliM.

Please take a look and let me know what you think.

Thanks!

Matt From: Moyer, Carol Sent: Friday, July 21, 201711:26 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: FW: PliM abstract on harvesting Thank you both!

The conference website is here: http://www-pub.iaea.org/iaeameetings/50811/Fourth-lnternational-Conference-on-Nuclear-Power-Plant-Life-Management

Poster guidelines are here: http://www-pub.iaea.org/MTCD/Meetings/PDFplus/2017/cn246/cn246PosterGuidelines.pdf No specific due date is listed for posters.

M. Key Dates and Deadlines Submission of Form for Submission of a Paper (Form B) and extended synopsis (800 words) 28 May 2017 Submission of Grant Application Form (Form C): 28 May 2017 Notification of acceptance of papers/posters: 30 June 2017 Submission of full paper (only upon request by the IAEA): 18 October 2017 Posters may only be "due" at the conference itself? It would not hurt to have it done by 18 Oct.,

the paper deadline, though. li t is unclear to me what they would do with a full paper, if one was not requested by IAEA. But I think you can prepare one, if you like. If they will not publish it as part of PLiM, we can find another home for it, or just release it as an NRC document.

-Carol From: Hiser, Matthew Sent: Friday, July 21, 201711:12 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting OK, I can work with Amy to make a poster. Rob and Pat and our PNNL contractor are also listed as co-authors ...

From: Hull, Amy Sent: Friday, July 21, 201711:08 AM To: Moyer, Ca rol <Carol.Moyer@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting I think this is a good opportunity to publicize harvesting work and develop collaboration . Task 2 in UNR. I will make the poster. When is it dur?

From: Moyer, Carol Sent: Friday, July 21, 2017 10:57 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting I'm pretty ambivalent about it. Amy, do you have a strong desire to make up a poster for the PLiM? Are there other co-authors to be consulted?

-Carol From: Hiser, Matthew Sent: Friday, July 21, 2017 7:28 AM

To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: FW: PLiM abstract on harvesting Hi Carol, Not terribly interested in a poster... The other thing is then you'd have to babysit the poster during poster session(s)?

I'd suggest we say thanks for the offer, but that's alright... what do you think?

Thanks!

Matt From: Moyer, Carol Sent: Thursday, July 20, 2017 12:49 PM To: Hiser, Matthew <M atthew. Hiser@nrc.gov>

Subject:

FW: FW: PLiM abstract on harvesting

Matt, I am a bit confused by the pronoun used in this email .. .

Are you interested in doing a poster instead?

Carol From: KRIVANEK, Robert [3]

Sent: Thursday, July 20, 201711:10 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] FW: PLiM abstract on harvesting You have just agreed that we will add this paper to poster session.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Aust ria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I (i~l 60Years I A EA Att11111 for Pe"n' ""cl /)1 l'elop1111*111

From: KRIVANEK, Robert Sent: Thursday, 20 July 2017 16:10 To: 'Carol.Moyer@nrc.gov' <Carol.M oyer@nrc.gov>

Subject:

FW: PLiM abstract on !harvesting

Dear Carol,

We asked you to submit your synopsis through INDICO (see email below) but it did not happened. So we were not able to send your synopsis to programme committee for evaluation and it will not occur on the conference programme.

Sorry for that but there are currently 300 delegates and 150 synopsis, so we were not able to track each of them separately.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(;ffe} 60Years I A EA Ato1111 for A*e1n* mu/ 0<*1*<'101m1t*llf Follow us on www.iaea.org m, From: KRIVANEK, Robert Sent: Friday, 26 May 2017 08:55 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Cc: KHAELSS, Martina <M .Khae lss@iaea.org>

Subject : FW: PLiM abstract on !harvesting

Dear Carol,

Thank you for your synopsis. We have opened INDICO system for this week, so please submit it through the system.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager

Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Securit y I Intern at ional Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I (i )

~ , v# 60 Years I A EA Atom ~for Pean* ,md Den*lopment From: Carol.Moyer@nrc.gov [mailto:Carol.Moyer@nrc.gov)

Sent: Friday, 26 M ay 2017 00:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

PLiM abstract on harvesting

Dear Mr. Krivanek,

The US NRG would like to propose one more presentation for this autumn's PLiM conference, on harvesting of materials from operating and decommissioning power plants. I understand from Sherry Bernhoft that you already have an impressive number of abstracts, so I will understand if there is not room in the program for this one. Nevertheless, we would appreciate your consideration of this proposal.

Again, please let me know if you need any additional information. Many thanks, Carol Carol E. Moyer Sr. Materials Engineer Office of Nuclear Regulatory Research RESI DE/CMB carol.moyer@nrc.gov 301-415-2153 From: KRIVANEK, Robert iaea.org

Sent: Tuesday, May 23, 2017 2::41 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Carol,

I will arrange it. Thank you.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I (j )

~ 60Years IA EA Ato1111 for />run- and 0<*1*rlo1mu*llf From: Carol.Moyer@nrc.gov [m ailt o:Carol.Moyer@nrc.gov)

Sent: Monday, 22 May 2017 20:44 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Subject:

RE: RE: CN246_pLiM_Abstract deadl ine ext ended to 19 May 2017

Dear Mr. Krivanek,

Since the formal deadline for abstract submissions has passed, I am no longer able to access the lndico system through the PLiM website (https://confe rences.iaea.org/indico/evenV134/). My abstract and Form B are attached.

Are you able to work with these documents? Is there anyt hing else that you need me to do at this time?

Thanks again for your patience and assistance, Carol From: Moyer, Carol Sent: Monday, May 22, 201710:59 AM To: 'KRIVAN EK, Robert' <R.Krivanek@iaea.org>

Cc: Frankl, Istvan <lstvan.Frank l@nrc.gov>

Subject:

RE: RE : CN246_PLiM_Abstract deadline ext ended to 19 May 2017

Dear Mr. Krivanek,

My abstract is attached to this message, for your info. Separately, I will submit it through the lndico system. Please let me know if you need any other information at this stage.

Thank you, Mrs. Carol Moyer

From: KRIVANEK, Robert (mailt o:R.Krivanek@ iaea.org)

Sent: Monday, May 22, 2017 2:56 AM To: Moyer, Ca rol <Carol.Moyer@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

(External_Sender] RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr Moyer,

It will be fine if you submit your abstracts this week.

We are looking forward to see a strong NRC delegation in Lyon.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r. krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

( ~iL)

~ 60Years I A EA Atmm for Pt*an* 011d De\"elopment From: Carol.Moyer@nrc.gov (m ailto:Carol.Moyer @nrc.gov]

Sent: Friday, 19 May 2017 23:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: KANG, Ki-Sig <K.S.Kang@iaea.org>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

The U.S. NRC intends to submit several abstracts for consideration for the PUM conference in October. We have a short delay in completing one of our abstracts. I will be submitting it early next week, and I hope that you still will be able to consider it for the conference.

Thank you, Carol Moyer Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research

MS: T-1 0A36 Washington, DC 20555-0001 carol.mover@nrc.gov 301-415-2153 From: R.Kriva nek@iaea.org [4]

Sent: Friday, April 21, 2017 8:44 AM To: R.Krivanek@iaea.org

Subject:

[External_Sender] CN246_pLiM_Abstract deadline extended to 19 May 2017

Dear all,

Please be informed that we extended the abstract submission deadline to 19 May 2017 and updated the conference accordingly.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

~ ) 60Years IA EA Atm111 for Pl'an* mu/ D<*1*r/o1111w111 Follow us on www.iaea.org BJl:r This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this conummication to others. Also please notify the sender by replying to this message and then delete it from your system.

This e mail message is intended on ly for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this conununication to others. Also please notify the sender by replying to this message and then delete it fro m your system.

This email message is intend!ed only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from

disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Plate A {41-22" wide)

M. Hise r", P. Purtscher", P. Ra muha llih, A. B. Hull*, and R. Tregoning*

• u.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA hPacific Northwest National Laboratory (PNNL), Richland, WA, USA Plate C (7 .811 Background and Motivation Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs). In the U.S., Potential Criteria for Harvest ing Prioritization there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) A number of criteria may be considered when prioritizing the data from 60 to 80 years. needs for harvesting, including:

Applicabil ity of harvested material for addressing critical gaps Extended plant operation and SLR raise a number of technica l issues that may require further research to understand and quantify aging mechanisms. U.S. utilities and the U.S. Harvesting for critical gaps prioritized over less essential Nuclear Regulatory Commission (NRC) have focused on the aging of systems, structures, and t echnical gaps.

components and in particular four key SLR issues: reactor pressure vessel (RPV) Ease of laboratory replication of the degradation scenario embrittlement, irradiation-assisted stress corrosion cracking of reactor internals, concrete For example, simultaneous thermal and irradiation structures and containment degradation, and electrical cable qualification and condition conditions are difficult to replicate, and accelerated aging assessment. may not be feasible for a mechanism sensitive to dose rate.

Meanwhile, in recent years, a number of NPPs, both in the U.S. and internationally, have

• Unique field aspects of degradation shut down or announced plans to shut down for various reasons, including economic, For example, unusual operating experience or legacy materials (fabrication methods, etc.) no longer available.

political, and technical chal lenges. Unlike in the past when there were very few plants

• Fleet-wide vs. plant-specific applicability of data shutting down, these new developments provide opportunities for harvesting components that were aged in representative light water reactor (LWR) environments. Greater value in addressing an issue applicable to a larger number of plants.

In a third related development, economic challenges and limited budgets have restricted

• Harvesting cost and complexity the resources available to support new research, including harvesting programs. Given this For example, harvesting un-irradiated concrete or electrical cables less expensive and less complex than constrained budget environment, aligning interests and leveraging with other organizations harvesting from the reactor internals or RPV.

is important to allow maximum benefit and value for future research programs. Availability of reliable in-service inspection (ISi) techniques for the material/ component Current Activities If mature inspection methods exist and are easy to apply, harvesting may be less valuable.

NRC has recently undertaken an effort, with

• Availability of materials for harvesting the assistance of Pacific Northwest National

• Timeliness of the expected research results relative to the objective.

Laboratory (PNNL), to develop a strategic approach to harvesting aged materials from The above potential criteria provide a systematic approach to prioritize data needs for harvesting. Different NPPs. Due to limited opportunities, past organizations may weigh and consider each of these criteria differently based on their interests and perspectives, but harvesting efforts have been reactive to each criterion is likely relevant to some degree for any organization. NRC is interested in engaging with other individual plants shutting down and beginning organizations to prioritize data needs for harvesting and identify areas of common interest.

decommissioning. Given the expected availability of materials from numerous plants Harvesting Database and anticipated research needs to better The NRC is pursuing the development of a database for sources of materials for harvesting, which could include understand aging out to 80 years of operation, the NRC is pursuing a more proactive approach both previously harvested materials and those available for future harvesting. This database wou ld allow for to prioritize the data needs best addressed by aligning of high-priority data needs to the available sources of materials. The level of detail for the database harvesting and identify the best sources of should be appropriate for the factors influencing decision-making. NRC is interested in engaging with other materials to address high-priority data needs organizations in developing the database.

for regulatory research.

The first step in this strategic approach is to Path Forward prioritize data needs for harvesting. A data NRC's experience is that harvesting can yield highly representative and valuable data on materials aging, but these need describes a particular degradation scenario and should be defined with as much efforts wil l be challenging. Having a clearly defined objective and early engagement with other stakeholders are detail as appropriate in terms of t he material keys to success. As specific harvesting opportunities are identified through this strategic approach, the NRC (alloy, composition, etc.) and environment welcomes opportunities for cooperation and leveraging of resources with other interested research organizations.

(temperature, fluence, chemistry, etc.).

NRC FORM 390 U.S. NUCLEAR REGULATORY COMMISSION 10-2011 NRCMD 3.9 RELEASE TO PUBLISH UNCLASSIFIED NRC STAFF SPEECHES, PRESENTATIONS, PAPERS, AND JOURNAL ARTICLES (Please type or print)

1. TITLE (State In full as It appears on the speech, presentation, paper, orJournal article) 2. ADAMS Accession No.

(Use Template ADM 039)

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants

3. AUTHOR(s)

Matthew Hiser, Patrick Purtscher, P. Ramuhalli, Amy Hull, Robert Tregoning

4. NAME OF CONFERENCE, LOCATION, AND DATE(s)

Fourth International Conference on Nuclear Power Plant Life Management, Lyon , France, October 23-26, 2017

5. NAME O F PUBLICATION Proceedings from Fourth International Conference on Nuclear Power Plant Life Management

6. NAME AND ADDRESS OF THE PUBLISHER 7. TELEPHONE NUMBER OF THE PUBLISHER IAEA YES NO 8. PAGE CHARGES 9. ESTIMATED COST If yes, the Authorizing Official (listed in block 12 below) must approve payment before the paper is No. of Pages @S Per Page = Total 0

sent for publication. If payment Is not authorized, NRC may refuse to pay the page charges, and the author will become personally responsible.

YES 10. CERTIFICATION NO I (ANSWER ALL QUESTIONS) 0 A.

Speeches, presentations, papers, and Journal articles require management and policy reviews of technical and policy TECHNICAL AND POLICY issues per NRC Directive Handbook 3.9, Section 11.A.2. Check the "YES" box to certify that the speech, presentation, REVIEWS I-oaoer or iournal article comolies with this statement.

0 Does this speech, presentation, paper, or journal article contain copyrighted material?

B. COPYRIGHTED MATERIAL If yes, attach a letter of release from the source that holds the copyright.

I-0

. Does this speech, presentation, paper, or journal article require patent clearance?

C. PATENT CLEARANCE If yes, the NRC Patent Counsel must signify clearance by signing below.

NRG PATENT COUNSEL (Type or Print Name) SIGNATURE I DATE 0 Do Is all material referenced in this speech, presentation, paper, or journal article available to the public either through a REFERENCE AVAILABILITY* puolic library, the Government Printing Office, the National Technical Information Service, or the NRC Public Document Room? If no, list below the specific availability of each referenced document.

SPECIFIC AVAILABILITY Does this speech, presentation, paper, or journal article contain measurement and weight values? If yes, all must 0 E. METRIC UNIT CONVERSION - be converted to the International System of Units, followed by the English units in brackets, pursuant to the NRC Policy Statement implementing the Omnibus Trade and Competitiveness Act of 1988, Executive Order 12770, July 25, 1991 .

11 . RESPONSIBLE STAFF MEMBER NAME (Type or print name) OFFICE/DIVISION MAIL STOP Matthew Hiser RES/DE T-10A36 SIGNATURE TELEPHONE NUMBER E-MAIL 1.0.

I DATE (301) 415-2454 MAH3

12. AUTHORIZATION (Cannot be the same person listed in block 11.)

NAME AND TITLE* NRC OFFICIAL AUTHORIZING RELEASE AND, IF APPLICABLE, AUTHORIZING PAYMENT FOR PAGE CHARGES /listed In blocks 8 and 9 abo*e)

Istvan Frankl SIGNATURE TE NRC FORM 390 (10-2011)

NRC FORM 665 /"-...:, U.S. NUCLEAR REGULATORY COMMISSION (07-2016)  !¥ i ADAMSDOCUMENTSUBMIB~ON

\ .....?/ Instructions for completing NRC Form 665 - "Cheat Sheet" (ML15.3.13.A3.1QJ Document Owner Originated By Phone No. (Enter 10 dig its) Mail Stop LAN ID Date Matthew Hiser Carol Moyer (301) 415-2454 T-10A36 MAH3 9/28/2017 If documents are to be put Into a package and have the same release properties, list the Document Titles or Accession Numbers below in the order they should appear. Documents with different release properties and sensitivity levels should be listed on additional forms in the order they should appear. Examples (ML16035A181 J Note: Document Owner is solely responsible for setting the Availability , Document Sensitivity and Document Security Access Level.

Document No. Total Number of Documents in th is package Document Title(s) or Accession No.

Poster, "Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants," for Fourth PLiM Conference Package Title (if necessary):

[Z]

Is this a brief title that can be changed by DPC according to template instruction? Yes No I

[Z]

CEM SUNSI Review has been completed (for Publicly Available Documents) Yes No Initials Document AVAILABILITY (select one)

[{] Publicly Available Non-Publicly Available MD 3.4 Non-Public Item Code (A.3-A.7, B1)

(Indicate Release Date) Document SENSITIVITY (select one)

Immediate Release I I A? I Sensitive Internal Info - Periodic Review Required (all other I I A. 4 I Sensitive Proprietary 0 Normal Release sensitive internal info)

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Document SECURITY ACCESS LEVEL 10 Document Processing Center I =Owner I I [Z] NRC Users I=Viewer I Limited Document Security (Defined by Group or User e.g., Joe Smith= Owner)

Package Accession No. ADAMS Template No. RIDS Code (if applicable) Other Identifiers Special Instructions Submitted By Phone No. (Enter 10 digits) Mail Stop LAN ID Date Submitted to DPC ML020170279 Page 1

Note to requester:

Attachment is From: Hiser, Matthew immediately following.

Sent: Wed, 4 Oct 2017 19:02:00 +0000 To: Frankl, lstvan;Tregoning, Robert;Hull, Amy;Moyer, Carol

Subject:

FW: FW: PLiM abstract on harvesting Attachments: Harvesting IAEA Plim 2 page synopsis USNRC.docx This email chain I thought confirmed that we were accepted for a poster...

From: Moyer, Carol Sent: Thursday, July 20, 201712:49 PM To: Hiser, Matthew

Subject:

FW: FW: PLiM abstract on harvesting

Matt, I am a bit confused by the pronoun used in this email. ..

Are you interested in doing a poster instead?

Carol From: KRIVANEK, Robert (mailto:R.Krivanek@iaea.org]

Sent: Thursday, July 20, 201711:10 AM To: Moyer, Ca rol <Carol.Moyer@nrc.gov>

Subject:

(External_Sender) FW: PLiM abstract on harvesting You have just agreed that we will add this paper to poster session.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(~ i i 60Years I A EA Atmm for Peace mu/ De1*elopme11r

From: KRIVANEK, Robert Sent: Thursday, 20 July 2017 16:10 To: 'Carol.Moyer@nrc.gov' <Carol.M oyer@n rc.gov>

Subject:

FW: PLiM abstract on !harvesting

Dear Carol,

We asked you to submit your synopsis through INDICO (see email below) but it did not happened. So we were not able to send your synopsis to programme committee for evaluation and it will not occur on the conference programme.

Sorry for that but there are currently 300 delegates and 150 synopsis, so we were not able to track each of them separately.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(~ )

~ 60Years I A EA ,\ta,111 for l't*llet' and Dl*relopm<'llf Follow us on www.iaea.org fiJM,I From: KRIVANEK, Robert Sent: Friday, 26 May 2017 08:55 To: 'Carol.Moyer@nrc.gov' <Carol.M oyer@nrc.gov>

Cc: KHAELSS, Martina <M .Khae lss@iaea.org>

Subject:

FW: PLiM abstract on !harvesting

Dear Carol,

Thank you for your synopsis. We have opened INDICO system for this week, so please submit it through the system.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(j

~ 60Years

)

I A EA Atmm for Pean* and Di l'rlopmrlll Follow us on www.iaea.org ~ **(m From: Carol.Moyer@nrc.gov (mailto:Carol.Moyer@nrc.gov)

Sent: Friday, 26 May 2017 00:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: Hiser, Matthew <M atthew.Hiser@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

PLiM abstract on harvesting

Dear Mr. Krivanek,

The US NRC would like to propose one more presentation for this autumn's PLiM conference, on harvesting of materials from operating and decommissioning power plants. I understand from Sherry Bernhoft that you already have an impressive number of abstracts, so I will understand if there is not room in the program for this one. Nevertheless, we would appreciate your consideration of this proposal.

Again, please let me know if you need any additional information. Many thanks, Carol Carol E. Moyer Sr. Materials Engineer Office of Nuclear Regulatory Research RESIDEICMB carol.moyer@nrc.gov 301-415-2153 From: KRIVANEK, Robert (mailto:R.Krivanek@iaea.org]

Sent: Tuesday, May 23, 2017 2:41 AM To: M oyer, Carol <Carol.Moyer@nrc.gov>

Subject:

(External_Sender) RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Carol,

I will arrange it. Thank you.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I

LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Aust ria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600 26007 I (j )

~ 60Years IA EA Atm111 for P1*e1n* mu/ D,*1*r/op1111*11t From: Carol.Moyer@nrc.gov [mailto:Carol.Moyer@nrc.gov)

Sent: Monday, 22 May 2017 20:44 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Subject:

RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

Since the formal deadline for abstract submissions has passed, I am no longer able to access the lndico system through the PLiM website (https://conferences.iaea.org/indico/evenV134/). My abstract and Form B are attached.

Are you able to work with these documents? Is there anything else that you need me to do at this time?

Thanks again for your patience and assistance, Carol From: Moyer, Carol Sent: Monday, May 22, 2017 10:59 AM To: 'KRIVANEK, Robert' <R.Krivanek@iaea.org>

Cc: Frankl, Istvan <lstvan.Frankl@ nrc.gov>

Subject:

RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

My abstract is attached to this message, for your info. Separately, I will submit it through the lndico system. Please let me know if you need any other information at this stage.

Thank you, Mrs. Carol Moyer From: KRIVANEK, Robert iaea.org

Sent: Monday, May 22, 2017 2 :56 AM

To: Moyer, Ca rol <Carol.Moyer@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender) RE: CN246_PliM_Abstract deadline extended to 19 May 2017

Dear Mr Moyer,

It will be fine if you submit your abstracts this week.

We are looking forward to see a strong NRC delegation in Lyon.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I Intern ational Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I (j )

~ 60Years I A EA Ata1111 for J't>t1n* (IJU/ Dc*relc,p111c*111 From: Carol.Moyer@nrc.gov [5]

Sent: Friday, 19 May 2017 23:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: KANG, Ki-Sig <K.S.Kang@iaea.org>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE : CN246_PliM_Abstract deadline extended to 19 M ay 2017

Dear Mr. Krivanek,

The U.S. NRC intends to submit several abstracts for consideration for the PLiM conference in October. We have a short delay in completing one of our abstracts. I will be submitting it early next week, and I hope that you still will be able to consider it for the conference.

Thank you, Carol Moyer Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol.mover@nrc.gov 301-415-2153

From: R.Krivanek@iaea.org [6]

Sent: Friday, April 21, 2017 8:44 AM To: R.Krivanek@ iaea.org

Subject:

[External_Sender] CN246_PUM_Abstract deadline extended to 19 May 2017

Dear all,

Please be informed that we extended the abstract submission deadline to 19 May 2017 and updated the conference accordingly.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

( ~iL ~

W 60Years I A EA Atmm for Pt*an* and Derelopmenr This email message is intended only for the use of the named recipient. Information contained in this emai l message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this conununication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended on ly for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hiser3 , P. Purtscher3, P. Ramuhallib, A. B. Hull3 , R. Tregoning 3 , and C. E. Moyer3 au.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA bPacific Northwest National Laboratory (PNNL), Richland, WA, USA Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs) In the U.S. , there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) from 60 to 80 years.

Extended plant operation and SLR raise a number of technical issues that may require further research to understand aging mechanisms. U.S. utilities and the U.S . Nuclear Regulatory Commission (NRC) have focused on the aging of systems, structures, and components and in particular fou r key SLR issues: reactor pressure vessel (RPV) embrittlement, irradiation-assisted stress corrosion cracking ofreactor internals, concrete structures and containment degradation, and electrical cable qualification and cond ition assessment. Meanwhile, in recent years, a number of NPPs, both in the U.S. and internationally, have shut down or announced plans to shut down for various reasons, including economic, political, and technical challenges. Unlike in the past when there were very few plants shutting down, these new developments provide opportunities for harvesting components that were aged in representative Iight water reactor (LWR) environments.

In a third related development, economic challenges and limited budgets have restricted the resources available to support new research, including harvesting programs. Given this constrained budget environment, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future research programs.

NRC has recently undertaken an effort, with the assistance of Pacific Northwest National Lab (PNNL), to develop a strategic approach for harvesting aged materials from NPPs. Due to limited opportunities, past harvesting efforts have been reactive to individual plants shutting down and beginning decommissioning. Given the expected ava ilability of materials from numerous plants and anticipated research needs to better understand aging out to 80 years of operation, the NRC is pursuing a more proactive approach to prioritize the data needs best addressed by harvesting and identify the best sources of materials to address high-priority data needs for regulatory research.

The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario (combination of material and environment) and should be defined with as much detail as appropriate in terms of the material (alloy, compos ition, etc.)

and environment (temperature, fluence, chemistry, etc.).

A number of criteria may be considered when prioritizing the data needs for harvesting, including:

• Applicability of harvested material for addressing critica l gaps o Harvesting for critical gaps prioritized over less essential technical gaps.

• Ease of laboratory replication of the degradation scenario o For example, simultaneous the1mal and irradiation conditions are difficult to replicate or accelerated aging may not be feasible for a mechanism sensitive to dose rate.

• Un ique field aspects of degradation o For example, unusual operating experie nce or legacy materials (fabrication methods, composition, etc.) no longer available.

• Fleet-wide vs. plant-specific applicability of data o Greater value in addressing an issue applicable to a larger number of plants.

• Harvesting cost and complexity o For example, harvesting unirradiated concrete or e lectrical cables less expensive and less complex than harvesting from the reactor internals or RPV.

• Availability of reliable in-service inspection (ISi) techniques for the material / component o If mature inspection methods exist and are easy to apply to monitor degradation, harvesting may be less valuable.

• Availability of materials for harvesting

• Timeliness of the expected research results re lative to the objective.

The above potential criteria provide a systematic approach to prioritize data needs for harvesting.

Different organizations may weigh and consider each of these criteria differently based on their interests and perspectives, but each criteria is likely relevant to some degree for any organ ization.

NRC is interested in engaging with other o rganizations to prioritize data needs for harvesting and identify areas of common interest.

Another activity NRC is pursuing is the potential deve lopment of a database for sources of materials for harvesting, which could include both previously harvested materials and those available for future harvesting. This database would allow for aligning of high-priority data needs to the available sources of materials. As with the data needs effort, the level of detail for the sources of materials database should be appropriate for the factors influencing decision-making. NRC is interested in engaging with other organizations to develop a database for sources of materials for harvesting.

NRC 's experience is that harvesting can yield highly representative and valuable data on materials aging, but these efforts may be expensive and challenging. Having a clearly defined objective and early engagement with other stakeholders, including the NPP from which harvesting will take place, are key to success. As specific harvesting opportunities are identified through this strategic approach, the NRC welcomes opportunities for cooperation and leveraging resources with other interested research organizations.

2

From: Jregooiog Robert To: Bernhott Sherry [sbernhoft@epri com) rsbernhott@epri cam\: r krivanek@iaea org Cc: Moyer carol: twJJ..Amy; Hjser Matthew Subject : NRC PLiM poster on harvesting Date: Wednesday, October 4, 2017 3:22:50 PM Attachments: jmaqe001.png jmaoeoo4 °00 imaaeoos ona Note to requester: The attachment is immediately imaoeoos ooa following. The .png files were icons for the IAEA and imaae007.ona social media flatforms.

imaoeoos,pno Haryes)ina IAEA eum 2 page synopsis USNRC docx imaaeooa ooa Robert/Sherry:

I just checked the latest PLiM program agenda that is on the website and it doesn't have the NRC's poster on material harvesting listed. We submitted the attached abstract and assumed, based on this email chain, that it had been accepted for the poster session. We have prepared the poster and are making plans to have it manned during the conference. I just want to confirm that the poster is accepted and to see if the program can be updated accordingly.

Thanks for your help with this.

Rob Robert Tregoning Technica l Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockvi lle, M D 20852-2738 ph: 301-415-2324 f ax: 301-415-6671 From: Hiser, Matthew Sent: Wednesday, October 04, 2017 3:02 PM To: Frankl, Istvan <lstva n.Fran kl@nrc.gov>; Tregoning, Robert <Robert.Tregoning@ nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

FW: FW: PLiM abstract on harvest ing This email chai n I thought confirmed t hat we were accepted for a poster...

From: Moyer, Carol Sent: Thursday, July 20, 2017 12:49 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

FW: FW: PLiM abstract on harvest ing

Matt, I am a bit confused by the pronoun used in this email ...

Are you interested in doing a poster instead?

Carol From: KRIVANEK, Robert [7]

Sent: Thursday, Ju ly 20, 2017 11:10 AM To: Moyer, Carol <Carol Moyer@nrc.gov>

Subject:

[Externa l_Sender] FW: PLiM abstract on harvesting You have j ust agreed t hat we wi ll add t his paper to poster session.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety I Department of Nuclear Safety and Security I Internatio nal Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r krivanek@iaea erg I T: (+43-1) 2600-22018 I F: (+43 1) 2600-26007 I Follow us on www.jaea.org [U [D l J[ [R From: KRIVANEK, Robert Sent: Thursday, 20 July 2017 16:10 To: 'Carol.Moyer@nrc.gov' <Carol Moyer@nrc gov>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

We asked you to submit your synopsis through INDICO (see email below) but it did not happened. So we were not able to send your synopsis to programme committee for evaluation and it will not occur on the conference programme.

Sorry for that but there are currently 300 delegates and 150 synopsis, so we were not able to track each of them separately.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety I Department of Nuclear Safety and Security I Internatio nal Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r krivanek@ iaea org I T: (+431) 2600-22018 I F: (+43 1) 2600 26007 I Follow us on www.jaea.org [BJ.((D []((D ((D From: KRIVANEK, Robert Sent: Friday, 26 May 2017 08:55 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc gov>

Cc: KHAELSS, Mart ina <M.Khaelss@iaea org>

Subject:

FW: PLiM abstract on harvest ing

Dear Carol,

Thank you for your synopsis. We have opened INDICO system for t his week, so please subm it it through the system.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operat ional Safety Section I Division of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.o rg I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I Follow us on www.jaea.org [U I* lI[ r From: Carol. Moyer@nrc.gov Moyer@nrc.gov

Sent: Friday, 26 M ay 2017 00:19 To: KRIVANEK, Robert <R Krjyanek@jaea org>

Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Tregon ing, Robert <Robert.Tregoning@nrc.gov>;

Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

PLiM abstract on harvest ing

Dear Mr. Krivanek,

The US NRG would like to propose one more presentation for this autumn's PLiM conference, on harvesting of materials from operating and decommissioning power plants. I understand from Sherry Bernhoft that you already have an impressive number of abstracts, so I will understand if there is not room in the program for this one. Nevertheless, we would appreciate your consideration of this proposal.

Again, please let me know if you need any additional information. Many thanks, Carol Carol E. Moyer Sr. Materials Engineer Office of Nuclear Regulatory Research RES/DE!CMB carol mover@nrc aov 301 -415-2153 From: KRIVANEK, Robert [mailto*R,Krivanek@ jaea org]

Sent: Tuesday, M ay 23, 2017 2:41 AM To: Moyer, Carol <Carol Moyer@nrc.gov>

Subject:

[Externa l_Sender] RE: RE: CN246_ PLiM_Abstract deadline extended to 19 M ay 2017

Dear Carol,

I will arrange it. Than k you.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety I Department of Nuclear Safety and Security I Internatio nal Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: c krivanek@iaea erg I T: (+43 1) 2600 22018 I F: (+43 1) 2600 26007 I Follow us on www.jaea.org [RI llrrll I From: Carol Moyer@ nrc gov [ma ilt o*carol.Moyer@nrc.gov]

Sent: Monday, 22 May 2017 20:44 To: KRIVANEK, Robert <R.Krivanek@ iaea.org>

Subject:

RE: RE: CN246_PLiM_Abst ract deadline extended to 19 M ay 2017

Dear Mr. Krivanek,

Since the formal deadline for abstract submissions has passed, I am no longer able to access the lndico system through the PLiM website (https:Uconferences.jaea.org/jndjco/eyent/134/). My abstract and Form B are attached.

Are you able to work with these documents? Is there anything else that you need me to do at this time?

Thanks again for your patience and assistance, Carol From: Moyer, Carol Sent: Monday, May 22, 2017 10:59 AM To: ' KRIVANEK, Robert' <R Krjvanek@ jaea org>

Cc: Frankl, Istvan <Istvan Frankl@nrc gov>

Subject:

RE: RE: CN246_ PLiM _Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

My abstract is attached to this message, for your info. Separately, I will submit it through the lndico system. Please l et me know if you need any other information at this stage.

Thank you,

Mrs. Carol Moyer From: KRIVANEK, Robert [8]

Sent: Monday, May 22, 2017 2:56 AM To: Moyer, Carol <Carol Moyer@nrc gov>

Cc: Tregoning, Robe rt <Robert.Tregon ing@nrc.gov>

Subject:

[Externa l_Sender) RE: CN246_ PliM_Abstract deadline extended to 19 May 2017

Dear M r Moyer,

It w ill be fi ne if you submit yo ur abstracts this w eek.

We are looking forward to see a strong NRC delegat ion in Lyon.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme M anager Operational Safety Section I Division of Nuclear Installation Safety I Department of Nuclear Safety and Security I International At omic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r krivanek@iaea erg I T: (+43-1) 2600 22018 I F: (+43 1) 2600 26007 I Follow us on www,iaea.ore [q [R R [R R From: Carol Moyer@nrc gov [ma ilto*Carol Moyer@nrc gov]

Sent: Friday, 19 M ay 2017 23 :19 To: KRIVANEK, Robert <R Krivanek@jaea org>

Cc: KANG, Ki-Sig <Ks Kang@ iaea org>; Tregoning, Robert <Robert Tregooiog@nrc gov>

Subject:

RE: CN246_PLiM_Abst ract dead line extended to 19 M ay 2017

Dear Mr. Krivanek,

The U.S. NRG intends to submit several abstracts for consideration for the PLiM conference in October. We have a short delay in completing one of our abstracts. I will be submitting it early next week, and I hope that you still will be able to consider it for the conference.

Thank you ,

Carol Moyer Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol mover@orc '7PY 301-415-2153 From: B Krivanek@jaea org [mailto*R Krivaoek@jaea org]

Sent: Friday, April 21, 2017 8:44 AM To: R.Krivanek@jaea org

Subject:

[External_Sender] CN246_ PLiM_Abstract dead line extended to 19 May 2017

Dear all,

Please be informed that we extended the abstract submission dead li ne t o 19 May 2017 and updated the conference accordingly.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r krivanek@iaea erg I T: (+43 1) 2600 22018 I F: (+43 1) 2600 26007 I

Follow us on www.jaea.org [ij l ll JBJ l I This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hiser3 , P. Purtscher3, P. Ramuhallib, A. B. Hull3 , R. Tregoning 3 , and C. E. Moyer3 au.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA bPacific Northwest National Laboratory (PNNL), Richland, WA, USA Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs) In the U.S. , there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) from 60 to 80 years.

Extended plant operation and SLR raise a number of technical issues that may require further research to understand aging mechanisms. U.S. utilities and the U.S . Nuclear Regulatory Commission (NRC) have focused on the aging of systems, structures, and components and in particular fou r key SLR issues: reactor pressure vessel (RPV) embrittlement, irradiation-assisted stress corrosion cracking ofreactor internals, concrete structures and containment degradation, and electrical cable qualification and cond ition assessment. Meanwhile, in recent years, a number of NPPs, both in the U.S. and internationally, have shut down or announced plans to shut down for various reasons, including economic, political, and technical challenges. Unlike in the past when there were very few plants shutting down, these new developments provide opportunities for harvesting components that were aged in representative Iight water reactor (LWR) environments.

In a third related development, economic challenges and limited budgets have restricted the resources available to support new research, including harvesting programs. Given this constrained budget environment, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future research programs.

NRC has recently undertaken an effort, with the assistance of Pacific Northwest National Lab (PNNL), to develop a strategic approach for harvesting aged materials from NPPs. Due to limited opportunities, past harvesting efforts have been reactive to individual plants shutting down and beginning decommissioning. Given the expected ava ilability of materials from numerous plants and anticipated research needs to better understand aging out to 80 years of operation, the NRC is pursuing a more proactive approach to prioritize the data needs best addressed by harvesting and identify the best sources of materials to address high-priority data needs for regulatory research.

The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario (combination of material and environment) and should be defined with as much detail as appropriate in terms of the material (alloy, compos ition, etc.)

and environment (temperature, fluence, chemistry, etc.).

A number of criteria may be considered when prioritizing the data needs for harvesting, including:

• Applicability of harvested material for addressing critica l gaps o Harvesting for critical gaps prioritized over less essential technical gaps.

• Ease of laboratory replication of the degradation scenario o For example, simultaneous the1mal and irradiation conditions are difficult to replicate or accelerated aging may not be feasible for a mechanism sensitive to dose rate.

• Un ique field aspects of degradation o For example, unusual operating experie nce or legacy materials (fabrication methods, composition, etc.) no longer available.

• Fleet-wide vs. plant-specific applicability of data o Greater value in addressing an issue applicable to a larger number of plants.

• Harvesting cost and complexity o For example, harvesting unirradiated concrete or e lectrical cables less expensive and less complex than harvesting from the reactor internals or RPV.

• Availability of reliable in-service inspection (ISi) techniques for the material / component o If mature inspection methods exist and are easy to apply to monitor degradation, harvesting may be less valuable.

• Availability of materials for harvesting

• Timeliness of the expected research results re lative to the objective.

The above potential criteria provide a systematic approach to prioritize data needs for harvesting.

Different organizations may weigh and consider each of these criteria differently based on their interests and perspectives, but each criteria is likely relevant to some degree for any organ ization.

NRC is interested in engaging with other o rganizations to prioritize data needs for harvesting and identify areas of common interest.

Another activity NRC is pursuing is the potential deve lopment of a database for sources of materials for harvesting, which could include both previously harvested materials and those available for future harvesting. This database would allow for aligning of high-priority data needs to the available sources of materials. As with the data needs effort, the level of detail for the sources of materials database should be appropriate for the factors influencing decision-making. NRC is interested in engaging with other organizations to develop a database for sources of materials for harvesting.

NRC 's experience is that harvesting can yield highly representative and valuable data on materials aging, but these efforts may be expensive and challenging. Having a clearly defined objective and early engagement with other stakeholders, including the NPP from which harvesting will take place, are key to success. As specific harvesting opportunities are identified through this strategic approach, the NRC welcomes opportunities for cooperation and leveraging resources with other interested research organizations.

2

Note to requester: Attachment is immediately following.

From: Moyer, Carol Sent: Thu, 20 Jul 2017 12:48:58 -0400 To: Hiser, Matthew

Subject:

FW: FW: PLiM abstract on harvesting Attachments: Harvesting IAEA Plim 2 page synopsis USNRC.docx

Matt, I am a bit confused by the pronoun used in this email. ..

Are you interested in doing a poster instead?

Carol From: KRIVANEK, Robert [9]

Sent: Thursday, July 20, 201711:10 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] FW: PLiM abstract on harvesting You have just agreed that we will add this paper to poster session.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r. krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(~ )

~ 60Years IA EA Atm111 for l't*aa a11d 0< 1*rlop111mr 1

Follow us on www.iaea.org From: KRIVANEK, Robert Sent: Thursday, 20 July 2017 16:10 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

We asked you to submit your synopsis through INDICO (see email below) but it did not happened. So we were not able to send your synopsis to programme committee for evaluation and it will not occur on the conference programme.

Sorry for that but there are currently 300 delegates and 150 synopsis, so we were not able to track each of them separately.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager

Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1} 2600-22018 I F: (+43-1} 2600-26007 I 60 Yea~

IAEA 10111 for P <let mul D1*1* lopmt*111 Follow us on www.iaea.org From: KRIVANEK, Robert Sent: Friday, 26 May 2017 08:55 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Cc: KHAELSS, Martina <M.Khaelss@iaea.org>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

Thank you for your synopsis. We have opened INDICO system for this week, so please submit it through the system.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

(~ )

~ 60Years IA EA ,\u,111.1 for l'<'CIC<' mu/ D<*re/opm<'llf Follow us on www.iaea.org

From: Carol.Moyer@nrc.gov [m ailto:Carol.M oyer@nrc.gov]

Sent: Friday, 26 May 2017 00:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: Hiser, M atthew <M atthew. Hiser@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

PLiM abstract on harvesting

Dear Mr. Krivanek,

The US NRC would like to propose one more presentation for this autumn's PLiM conference, on harvesting of materials from operating and decommissioning power plants. I understand from Sherry Bernhoft that you already have an impressive number of abstracts, so I will understand if there is not room in the program for this one. Nevertheless, we would appreciate your consideration of this proposal.

Again , please let me know if you need any additional information. Many thanks, Carol Carol E. Moyer Sr. Materials Engineer Office of Nuclear Regulatory Research RES/DEICMB carol.mover@nrc.gov 301-415-2153 From: KRIVANEK, Robert Krivanek@iaea.org

Sent: Tuesday, May 23, 2017 2:41 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Carol,

I will arrange it. Thank you.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r. krivanek@ iaea.org I T: (+43*1) 2600-22018 I F: (+43*1) 2600-26007 I

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~~~

~ 60Years I A EA AW111f for Peace ""cl Dcn*/op111,*11t

Follow us on www.iaea.org (I.J!bg ** Im From: Carol.Moyer@nrc.gov [10]

Sent: Monday, 22 May 2017 20:44 To: KRIVANEK, Robert <R.Krivanek@ iaea.org>

Subject:

RE: RE : CN246_ PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

Since the formal deadline for abstract submissions has passed, I am no longer able to access the lndico system through the PLiM website (https://conferences.iaea.orq/indico/event/134/).

My abstract and Form Bare attached.

Are you able to work with these documents? Is there anything else that you need me to do at this time?

Thanks again for your patience and assistance, Carol

From: Moyer, Carol Sent: Monday, May 22, 2017 10:59 AM To: 'KRIVANEK, Robert' <R.Krivanek@iaea.org>

Cc: Frankl, Istvan <lstvan.Frank l@nrc.gov>

Subject:

RE: RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

My abstract is attached to this message, for your info. Separately, I will submit it through the lndico system. Please let me know if you need any other information at this stage.

Thank you, Mrs. Carol Moyer From: KRIVANEK, Robert fmailto:R.Krivanek@iaea.org]

Sent: Monday, May 22, 2017 2 :56 AM To: Moyer, Carol <Carol. Moyer@ nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

(External_Sender] RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr Moyer,

It will be fine if you submit your abstracts this week.

We are looking forward to see a strong NRC delegation in Lyon.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I tj )

~~ 60Years I A EA A1t11111 for f>c '1n' mu/ Dc*1*c*lo1n111*11t 1

Follow us on www.iaea.org (I.J!bg ** Im From: Carol.Moyer@nrc.gov [11]

Sent: Friday, 19 May 2017 23:19 To: KRIVANEK, Robert <R.Krivanek@ iaea.org>

Cc: KANG, Ki-Sig <K.S.Kang@iaea .org>; Tregoning, Robert <Robert.Tregoning@nrc .gov>

Subject:

RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

The U.S. NRC intends to submit several abstracts for consideration for the PLiM conference in October. We have a short delay in completing one of our abstracts. I will be submitting it early next week, and I hope that you still will be able to consider it for the conference.

Thank you ,

Carol Moyer Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol.moyer@nrc.gov 301 -415-2153 From: R.Krivanek@iaea .org (ma ilto :R.Kri vanek@iaea .org1 Sent: Friday, April 21, 2017 8:44 AM To: R.Krivanek@iaea .org

Subject:

[External_Sender) CN246_ PliM_Abstract deadline extended to 19 May 2017

Dear all,

Please be informed that we extended the abstract submission deadline to 19 May 2017 and updated the conference accordingly.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section IDivision of Nuclear Installation Safety I Department of Nuclear Safety and Security I International Atom ic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@i aea.org I T: (+43-1} 2600-22018 I F: (+43-1} 2600-26007 I 60 Years I A EA Atom for P,*a e and D,*,* lopnu flt

Follow us on www.iaea.org This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

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communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only fo r the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hiser3 , P. Purtscher3, P. Ramuhallib, A. B. Hull3 , R. Tregoning 3 , and C. E. Moyer3 au.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA bPacific Northwest National Laboratory (PNNL), Richland, WA, USA Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs) In the U.S. , there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) from 60 to 80 years.

Extended plant operation and SLR raise a number of technical issues that may require further research to understand aging mechanisms. U.S. utilities and the U.S . Nuclear Regulatory Commission (NRC) have focused on the aging of systems, structures, and components and in particular fou r key SLR issues: reactor pressure vessel (RPV) embrittlement, irradiation-assisted stress corrosion cracking ofreactor internals, concrete structures and containment degradation, and electrical cable qualification and cond ition assessment. Meanwhile, in recent years, a number of NPPs, both in the U.S. and internationally, have shut down or announced plans to shut down for various reasons, including economic, political, and technical challenges. Unlike in the past when there were very few plants shutting down, these new developments provide opportunities for harvesting components that were aged in representative Iight water reactor (LWR) environments.

In a third related development, economic challenges and limited budgets have restricted the resources available to support new research, including harvesting programs. Given this constrained budget environment, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future research programs.

NRC has recently undertaken an effort, with the assistance of Pacific Northwest National Lab (PNNL), to develop a strategic approach for harvesting aged materials from NPPs. Due to limited opportunities, past harvesting efforts have been reactive to individual plants shutting down and beginning decommissioning. Given the expected ava ilability of materials from numerous plants and anticipated research needs to better understand aging out to 80 years of operation, the NRC is pursuing a more proactive approach to prioritize the data needs best addressed by harvesting and identify the best sources of materials to address high-priority data needs for regulatory research.

The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario (combination of material and environment) and should be defined with as much detail as appropriate in terms of the material (alloy, compos ition, etc.)

and environment (temperature, fluence, chemistry, etc.).

A number of criteria may be considered when prioritizing the data needs for harvesting, including:

• Applicability of harvested material for addressing critica l gaps o Harvesting for critical gaps prioritized over less essential technical gaps.

• Ease of laboratory replication of the degradation scenario o For example, simultaneous the1mal and irradiation conditions are difficult to replicate or accelerated aging may not be feasible for a mechanism sensitive to dose rate.

• Un ique field aspects of degradation o For example, unusual operating experie nce or legacy materials (fabrication methods, composition, etc.) no longer available.

• Fleet-wide vs. plant-specific applicability of data o Greater value in addressing an issue applicable to a larger number of plants.

• Harvesting cost and complexity o For example, harvesting unirradiated concrete or e lectrical cables less expensive and less complex than harvesting from the reactor internals or RPV.

• Availability of reliable in-service inspection (ISi) techniques for the material / component o If mature inspection methods exist and are easy to apply to monitor degradation, harvesting may be less valuable.

• Availability of materials for harvesting

• Timeliness of the expected research results re lative to the objective.

The above potential criteria provide a systematic approach to prioritize data needs for harvesting.

Different organizations may weigh and consider each of these criteria differently based on their interests and perspectives, but each criteria is likely relevant to some degree for any organ ization.

NRC is interested in engaging with other o rganizations to prioritize data needs for harvesting and identify areas of common interest.

Another activity NRC is pursuing is the potential deve lopment of a database for sources of materials for harvesting, which could include both previously harvested materials and those available for future harvesting. This database would allow for aligning of high-priority data needs to the available sources of materials. As with the data needs effort, the level of detail for the sources of materials database should be appropriate for the factors influencing decision-making. NRC is interested in engaging with other organizations to develop a database for sources of materials for harvesting.

NRC 's experience is that harvesting can yield highly representative and valuable data on materials aging, but these efforts may be expensive and challenging. Having a clearly defined objective and early engagement with other stakeholders, including the NPP from which harvesting will take place, are key to success. As specific harvesting opportunities are identified through this strategic approach, the NRC welcomes opportunities for cooperation and leveraging resources with other interested research organizations.

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