ML21152A251

NRC-2018-000831 - Resp 12 - Interim, Agency Records Subject to the Request Are Enclosed (Part 1 of 4)

ML21152A251
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Issue date:	05/24/2021
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NRC-2018-000831
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{{#Wiki_filter:Note to requester: Attachments are immediately following this email. Portions of this record are redacted under FOIA Exemption 85, Deliberative Process Privilege. From: Moyer, Carol Sent: Wed, 13 Sep 2017 13:39:30 +0000 To: Rao, Appajosula;Hiser, Matthew;Purtscher, Patrick;Kirk, M ark;Sircar, Madhumita;Philip, Jacob;Murdock, Darrell;Miller, Kenneth A Cc: Hull, Amy;Frankl, lstvan;Seber, Dogan; Koshy, Thomas;Tregoning, Robert;Pires, Jose

Subject:

SLR Research User Need revisions Attachments: UNR NIRR-2017-006 reduced.pdf, Comments on draft UNR NRR 2017-006.docx, SLR UNR response 09-12-2017 cem.docx

Dear SLR Research Team,

In response to NRR's user need request 2017-006 (attached), we sent a draft response for staff-level review and comment. We received some comments and requests for clarification from the NRR staff (attached). The CMB staff members are already working on addressing these comments. By this email, I am looking for your input on Task 1. The comment was related to the timing of workshops to exchange information on SLR research results. I believe the proposed dates for those meetings was always intended to be tentative, subject to change as the research progress warranted . I have proposed revised language for the UNR response (attached). I am asking for your input on: (1) Are the revised target dates OK with you? Do they seem reasonable, given what we know now? And , (2) Are you aware of any planned meetings, workshops, or symposia that would accomplish similar ends? That is, does it make sense to schedule our own information-exchange meetings, or would we possibly be duplicating a meeting already planned by an international technical organization within, say, 6 months of our proposed dates? On this piece of the revised response, I need to have you r input by the end of this week. Please reply to me and to Amy Hull. Thank you, Carol Carol Moyer Sr. Materials Engineer RESIDEICMB carol.moyer@nrc.gov 301-415-2153

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 4, 2017 MEMORANDUM TO: Michael F. Weber, Director Office of Nuclear Regulatory Research FROM: William M. Dean, Director ~~-~~ Office of Nuclear Reactor Regulation

SUBJECT:

RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION The purpose of this memorandum is to request specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years) . These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period. In a previous user need request, UNR-NRR-2010-006, Request for Office of Nuclear Regulatory Research Support in Developing Technical Information to Support Evaluating the Feaslbility of License Renewal Beyond 60 Years,"Agencywide Documents Assess and Management Systems (ADAMS) Accession No. ML092470525), the Office of Nuclear Regulatory Research (RES) assisted the Office of Nuclear Reactor Regulation (NRR) in developing information for consideration in the SLR guidance documents. This new user need request focuses on research activities on the technical issues discussed in the SLR guidance documents and in the staff requirements memorandum to SECY 14-0016 (ADAMS Accession No. ML14241A578). Specifically, NRR is requesting RES support to:

• Hold NRC/industry workshop(s) on the status of domestic and international research activities and operating experience to address issues discussed in the SLR guidance documents;
• Develop and implement a long-term strategy and information tool for harvesting ex-plant components from decommissioning as well as from operating plants;
• Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research for SLR; and
• Use the products from the above three tasks to develop documentation of the status of research for the significant technical issues for SLR.

CONTACT: Bennett M, Brady, NRR/DLR (301) 415-2981

M. Weber Additional details are provided In the Enclosure, "Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation." Resources NRA requests RES to provide the specific resources (contract dollars and full-time equivalent staff) needed to complete the various tasks during the period of activity. Intended Use of RES Products The requested RES products will provide confirmatory research on the technical bases for industry research products related to aging degradation and identified in the staff's review of SLR applications. Coordination and Schedules This request has been coordinated with RES staff in the Division of Engineering (DE). Based on this, we expect that the requested work could be completed within the requested timeframe. We are prepared to work with your staff to further develop a mutually acceptable technical approach and schedule for this activity and to engage industry on this important matter. In addition, the directors of the lead divisions in each of our offices, George Wilson (NRR/Division of License Renewal (DLR)) and Brian T homas (RES/DE), have discussed and agreed with the scope and schedules of the tasks in this request. Priority This request is rated as high ,priority based on NRR office priority ranking tor reactor activities. Points of Contact For NRR, the contact is Bennett Brady, Subsequent Renewal, Guidance, and Operations Branch, DLR. For RES , the contact is Amy Hull, Corrosion and Metallurgy Branch, DE. Additional Information None.

Enclosure:

Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION

Background:

The U.S. Nuclear Regulatory Commission staff (NRC or staff) has recently completed the draft guidance documents for subsequent license renewal (SLR). The draft guidance documents (draft NUREG-2 191 , Volumes 1 and 2, Agencywide Documents access and Management Systems [(ADAMS) Accession Nos. ML16274A389 and ML16274A399, respectively], "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report and the draft NUREG-2192, [ADAMS Accession No. ML16274A402) Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants) were issued for public comment in December 2015. As preparation for drafting these guidance documents, the Office of Nuclear Reactor Regulation (NRA) and the Office of Nuclear Regulatory Research (RES) conducted three audits to investigate the effectiveness of aging management programs (AMPs) used in the plant operating period from 40 to 60 years. The findings from the first two audits are documented in the report titled, "Summary of Aging Management Program Effectiveness Audits to Inform Subsequent License Renewal: R.E. Ginna Nuclear Power Plant and Nine Mile Point Nuclear Station, Unit 1" (ADAMS Accession No. ML13122A007) . The summary of the third audit can be found in the August 5, 2014, report, "H.B. Robinson Steam Electric Plant, Unit 2, Aging Management Program Effectiveness Audit" (ADAMS Accession No . Ml14017A289). RES also published on June 15, 2016, the "Review of Aging Management Programs: Compendium of Insights from License Renewal Applications and from AMP Effectiveness Audits Conducted to Inform Subsequent License Renewal Guidance Documents," a report prepared by the RES contractor, Argonne National Laboratory, that includes NRC staff input (ADAMS Accession No. ML16167A076). RES also completed the Expanded Materials Degradation Assessment (EMDA) in cooperation with the Department of Energy (DOE) Light Water Reactor Sustainability Program. T he resultant reports, NUREG/CR-7153, EMDA, Vol. 1-5 (ADAMS Accession Nos. ML14279A321 , ML14279A331 , ML14279A349, ML14279A430, and ML14279A461) , describe the conclusions from an expert elicitation process to identify the most slgnif1cant aging degradation technical issues for nuclear power reactor operation beyond 60 years. The four most significant technical issues identified below were also outlined in the staff requirements memorandum (SRM) on SECY 14-0016. "Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ADAMS Accession No. ML14241A578):

• Reactor pressure vessel neutron embrittlement at high fluence
• Irradiation-assisted stress corrosion cracking of reactor internals and primary system components
• Concrete and containment degradation
• Electrical cable quali fication and condition assessment ENCLOSURE

The audits and EMDA volumes provided NRC with over 800 suggestions for changes to the license renewal guidance and aging management program activities found acceptable for operation from 60 to 80 years. Staff in several NRR divisions and RES1 Division of Engineering (DE) participated in over 90 expert panels to review these suggestions along with the staff's own suggestions for changes to license renewal guidance documents for the first license renewal. The expert panels dispositioned the recommendations for the guidance for SLR and drafted NUREG-2191 and NUREG-2192. After the draft guidance documents were issued for public comment, the staff held several public meetings with stakeholders and the public to discuss the proposed revisions and the bases for the revisions. In these meetings the staff provided information and clarifications on the proposed changes to the guidance documents, and solicited feedback on the documents. The NRC staff has responded to the public comments and will publish the documents in final form in mid-2017. To support their SLR applications, applicants need to demonstrate that the effects of aging will be adequately managed for an operating period from 60 to 80 years. The NRR staff would like RES' assistance in holding meetings on these issues, participating and interacting with the DOE and other industry organizations, cataloguing the materials needed for research , and documenting the status and products of research for SLR. Description of Scope and Tasks

1. Hold NRC/industry workshop(s) on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR Report Need: In February 2008, the NRC and DOE first co-sponsored a *workshop on U.S.

Nuclear Power Plant Life Extension Research and Development" (ADAMS Accession No. ML080570419), which requested stakeholder input into aging management research areas for life Beyond 60." Since then, there have been multiple domestic and international worksl1ops/meetings on the research activities and operating experience that may impact aging management of systems, structures, and components (SSCs) for an SLR period. The International Atomic Energy Agency will sponsor the "Fourth International Conference on Nuclear Power Plant Life Management in France in October 2017. These meetings have been helpful in facilitating technical discussions, disseminating knowledge and information, enabling the understanding of technical challenges, and paving the path forward for resolution of the challenges and issues related to materials degradation during the SLR period. As the NRC staff prepares for the review of SLR applications, there is a need for continued e ngagement with the domestic industry, DOE, and other Federal organizations, academia, international partners, and Interested public stakeholders through workshops focused on the status and resolution of the most significant technical issues outlined in the GALL-SLR and the SRM. Request: RES is requested to facilitate a minimum of two domestic and international activities (either a workshop, conference , symposium. or meeting), one in the early fall 2018 on the mechanical issues and one in late spring 2020 on the concrete and cables issues. These meetings should address:

• the state of knowledge on the technical issues requested in the SRM on SECY 14-0016,
• on-going research on materials degradation issues and aging management of these issues. as discussed in the GALL-SLR, and
• new operating experience from the initial license renewal period (or the long term operation period for international plants).

These activities should be specifically targeted toward the resolution of technical issues for effective aging management of SSCs during the SLR period. Deliverable: The deliverables include the international activities (either a workshop, conference, symposium, or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SAM on SECY 14-0016 for SLR. Prior to the meetings, RES should provide a draft agenda and proposed presenters. The information from these activities should be documented in a NUREG/CP report, if appropriate, or by other sufficient means. including, at a minimum, a summary of the activity with all relevant contributions. (e.g., presentations or papers) and research insights and knowledge, due 6 months after each meeting. Schedule: The effort should continue until the completion of the deliverables from the second activity, tentatively scheduled for late spring 2020.

2. Develop and implement a long-term strategy for obtaining information on materials degradation f rom decommissioned nuclear power plants, as well as from ex-plant compone nts from operating plants Need: The NRG performs confirmatory research to inform and develop the technical bases for regulatory decisions related to AMPs for SLR. Historically, this research has included testing virgin materials under simulated aging conditions, as well as testing and characterization of ex-plant materials harvested from nuclear power plants. Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation. coolant, etc.), unlike virgin materials tested under simulated conditions in the lab. Testing ex-plant materials also reduces the uncertainty associated with the applicability of the aging conditions. Therefore, this effort Is expected to provide fundamental insights on reactor materials degradation and information addressing potential technical issues or identified gaps to support anticipated future NRC needs. It will also inform the value of existing databases based on simulated aging conditions by assessing their applicability to in-service conditions.

Based on the recent experience of recovering materials from decommissioned plants, such as Zion , Crystal River, and Zorita (Spain), the efforts of planning, coordination, and eventual l1arvesting of these materials can be resource-intensive and time-challenging. Future efforts to retrieve materials from decommissioned plants should be focused on the highest value SSCs by proactively developing a strategic database for obtaining unique and significant materials aging degradation information from ex-plant components. Such a database will enable the NRC to focus its harvesting efforts and expeditiously obtain materials and components from plants to be decommissioned in the near future and develop information and knowledge to assess the efficacy of the AMPs.

Request: RES is requested to: A. Develop an information tool using Microsoft products which identifies and prioritizes the materials, components, and operating conditions that are needed to address the four significant issues outlined In the SAM on SECY 14-0016, and that, due to challenges in simulating actual service conditions, may be best addressed by harvesting either from plants that are entering decommissioning or ex-plant components f ram operating plants. 8 . Develop a process to evaluate the components from plants that are entering decommissioning or ex-plant components fram operating plants t11at would be appropriate candidates for harvesting, and to ensure that timely contact is made with the plant owner to facilitate any I,arvesting targets that may be identified. C. Use the process developed in item B to evaluate the suitability of components from plants that are currently either under decommissioning or replacing components that may be of interest. D. Continue to implement the process developed in item B as components become available from additional plants. E. In coordination with Task 3, pursue domestic and International partnerships to pursue cooperational cost-sharing on retrieval and testing of ex-plant harvested material. Deliverable: RES should provide the database for NRA review, and summarize the priority listing in a letter report. Likewise, items Band C should be documented in a letter report. Item D is a continuing item that should be summarized in a letter report or e-mail as appropriate. Schedule: Items A and B should be completed within 18 months of issuance of this user need request. Item C should be completed within 24 months of issuance of this user need request. Item D is an activity that should continue 36 months from the issuance of this user need request.

3. Continue to Develop Domestic and International Partnerships to Share Expertise, Capabilities and Resources Related to Aging Management Research for Long-Term Operations Need: Various domestic and foreign research organizations, government agencies, utilities and research organizations are presently engaged in aging management research, the results of which may be of value to the NRC regarding plant operations during the SLR period. Additionally, the Electric Power Research Institute is engaged with various international research organizations to develop data on aging mechanisms/effects . As such, it benefits the NRC to be engaged in domestic and international research partnerships in order to evaluate all available operating experience and relevant research, leverage resources, and minimize unnecessary duplication of efforts. It would be advantageous to the NRC to develop partnerships with these entities such that the various research programs could be better coordinated and focused on high-priority needs. The scope of this

                                                *5-coordination includes cooperation and cost-sharing on retrieval and testing of ex-plant harvested material in Task 2.

Request: RES is requested to continue to develop agreements with domestic and international partners to collaborate on aging management research that results in information to help inform agency decisions regarding SLR applications. RES should evaluate products and reports from these organizations that may be provided to NRG in support of generic or plant-specific issues. Deliverable: RES should provide to interested NRR branch chiefs (from DE and the Division of License Renewal (DLR)) and senior staff relevant products (e.g .. trip reports. meeting summaries, papers, presentations, reports and other information) from interactions with domestic and international organizations. In addition, relevant findings from recent Interactions, the status, and future plans should be discussed as a standing agenda item during the quarterly interface meetings between RES/DE, NRA/DLR, and NRA/DE. Schedule: These products should be provided to NRA in a timely manner; the effort should continue until the closure of this user need request. A quarterly report (or slides) for presentation at the Director/Deputy Director Quarterly Interface Meeting should be provided 5 days before the meeting.

4. Documentation and Compilation of Results from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff Need: In the SRM to SECY 14-0016, the Commission directed the staff to keep the Commission informed on the progress in resolving the four significant technical issues related to SLR. The SAM also directed the staff to keep the Commission informed regarding the staff's readiness for accepting an application and any further need for regulatory process changes, rulemaking , or research.

Request: RES is requested to annually prepare a document summarizing the products from tasks 1, 2, and 3 of this user need request to discuss the accomplishments of RES and national and international partners in addressing the four major technlcal Issues in the SAM and other research activities that may be used in reviewing applications for SLR. The annual report should be at a sufficiently high level to be used to support briefings tor the Commission or Advisory Committee on Reactor Safeguards. Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. Schedule: Annual report to be provided in the first quarter of each calendar year beginning in the first quarter of calendar year 2018 discussing the research activities supporting SLR during the previous year.

COMMENTS ON DRAFT UNR NRR 2017-006 TASK 1

• Two RPV experts said it is too early to have an international meeting on neutron embrittlement in 2018. One electrical expert said it would be good to have an electrical meeting in 2020 as NIST will have completed their work at that time. RES should ask staff experts in reactor pressure vessels, internals, concrete, and cables in NRR and RES what would be an appropriate time for international meetings in their areas of expertise. Consideration should be given to times when new information from research will be available and times when no other organizations might be holding large meetings/workshops or symposiums. We do not need to hold a meeting when other organizations have plans for similar meetings.
• It wasn't clear to new readers of the UNR what the purpose and goals of the meetings were and what would be discussed at the meeting. RES needs to include the topics (bullets) in the NRR UNR, including the purpose and goals of any meetings, and what RES intends to provide back to NRR.

TASK2

• It isn't clear what these criteria/approaches/processes for the use of the database are.

Where are they documented or described, how they have been validated or used? Are the criteria/approaches/processes described in the September 2017 TLR? NRR needs to have an idea of what is involved in the steps and how the database will be used.

• It is not clear how the first two activities, the workshop on materials harvesting and prioritizing of issues to be addressed by harvested materials, contribute, or are related to the database. This must be fully explained.
• Why just decommissioned plants? An explanation is required as to why this has been limited in scope.
• It is not clear how the discussion under Subtask 2 are examples of how the database would be used. It seems to be a discussion of harvesting material. This needs to be explained, with clear outcomes defined.

(b)(S) .~J Iseems like a lot to develop an Excel or Access database. Does this include collecting and inputting information on materials needed and the sources of materials expected to be available? This tasking must be better defined. TASK3

• RES staff participate in a lot of domestic and international meeting and activities in partnership with other research organizations. NRR recognizes the importance of these activities and collaborative research. What other UNRs contain a task for partnerships

with other domestic and international research organizations? What are the FTE and contract dollars associated with each of these UNRs. An explanation needs to be included that reflects work being done for other program offices . TASK4

• Task 4 should be focused on providing an annual report for use by RES and NRR as a document annually summarizing the status and the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM .

Task 5? (Starting with the paragraph ("building upon the extensive work .... ")

• RES might propose an unfunded Task 5 to provide confirmatory analyses and expert techn ical assistance with the review of technical documents to be submitted with SLR applications or to be available for assistance in the review of SLR applications . The task wou ld be activated as needed by NRR and scoped and cost estimated as the SLR applications are accepted and RES assistance is needed . At this time, NRR does not see a need for th is task.
• Delete the paragraph "As an example." Assessing the "trend in critical risk-significant electrical equipment" is not the role of DMLR . RES might discuss th is with DE in their UNR.
• Provide task estimates for Task 4 alone without additions .

{I just heard today that DE is setting up a request for informal support (less than 100 hours) with RES to do a techn ical evaluation of Seabrook's proposal for a testing program to determine the modulus of elasticity of their ASR-infected containment. I don 't know if this proposal is for their license amendment request or their application for first license renewal. Brian Wittick, Ang ie Buford , and Bryce Lehman were in the meeting. This is the type of thing I would see RES doing in Task 5 . BMB]

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August xx, 2017 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of Nuclear Regulatory Research (RES) to provide "specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period." This user need request (UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years." This UNR also supersedes NRR-2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" and complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation of reactor vessel internals." For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427). The purpose of this memorandum is to respond to UNR NRR-2017-006 with RES's plans to accomplish the following tasks:

• Task 1: Hold NRG/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ).
• Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvested from operating plants.
• Task 3: Continue to develop domestic and international partnerships to share expertise, capabil ities, and resources related to aging management research.
• Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applicat1ions.

CONTACT : Amy Hull, RES/ DE 301-415-2435

B. Holian RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. RES staff will continue these activities and integrate the results in del iverables under Task 4. The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resou rces and the anticipated schedule for the deliverables. RES staff appreciates the coordination with NRR technical staff and management in this area. We will continue to coordinate with NRR staff and management to ensure that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs cou ld impact the activities, deliverables and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and , if warranted, the UNR will be amended.

Enclosure:

Response to User Need Request for Research Assistance on Potential Significant Technical Issues duri ng the Subsequent Period of Extended Operation

B. Holian

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANC E ON POTENTIAL S IGNIFICANT TECH NICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION : NRR-2017-006 DISTRIB UTION: B . Thomas, RES G Wilson, NRR R. Tregoning, RES A. Hiser, NRR I. Frankl , RES R. Iyenga r, RES T. Koshy, RES K. Miller, RES D. Seber, RES S . Stuche ll, NRR B. Brady, NRR A.Hull , RES C . Moye r, RES M. Hiser, RES M. Kirk, RES J . Philip, RES M. S ircar, RES J . Pires, RES RidsNrrMailCenter ADAMS PackaQe A ccess,on N o.: MLxxxx OFFICE RES/DE/CMS RES/DE/CMB RES/DE/CMB RES/DE/ICEEB NAME C. Moyer A. Hull I. Frankl T. Koshy DATE I /2017 I /2017 I /2017 I /2017 OFFICE RES:DE:SGSEB D:RES:DE RES Mail Room D:RES NAME D. Seber 8 . Thomas K. Johnson M. Weber DATE I /2017 I /2017 I /2017 I /2017 OFFICIAL RECORD COPY

Response to User Need Request NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRG/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two domestic and international activities (either a workshop, conference, symposium, or meeting), one in early autumn 201 Stentatively planned for spring 2019 on mechanical issues and one in late springtentatively planned for summer 2020 on concrete and cables issues. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016, ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR, and any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for international plants). RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. Prior to the meetings, RES will provide a draft agenda with specific topics for the meeting and the proposed presenters. RES will document the information from each of these activities in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting. Mechanical Issues - As part of the requested autumn 2018 workshop/ conference/ symposium/ meeting on mechanical issues, the NRC staff will coordinate a session, or sessions, concerning issues associated with reactor vessel embrittlement during the SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. Concrete, Containment and Electrical Cables Issues - RES will also hold an NRG/industry workshop with international participation in the third quarter of FY20 (spring of 2020) on the state of knowledge for the technical issues in concrete, containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific issues and items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before the workshop. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late spring 2020. Task 2 RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, 2.A -2.D as stipulated on page 4 of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting.

• In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The deliverable provided criteria to assess the need for harvesting to address a particular technical issue. The report then applied these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report also covered the background on the need for harvesting, and past harvesting efforts and experience. The purpose of this report was to serve as a foundation for NRC staff to prioritize technical issues best addressed by harvesting. The initial technical letter report (TLR) for this research is expected to be published in September, 2017, as a PNNL document. This TLR will be reviewed by N RR and RES staff to determine any follow-on work by RES and the final publication type.
• In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested.

The workshop summary report will be distributed among meeting participants and is expected to be finalized by September, 2017. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2 .B. Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may be best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the latest operating experience and research, so that users may understand which data needs can be best addressed by harvesting. As an example, RES will develop a process to evaluate concrete samples harvested from decommissioned plants, and will follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)-affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels {PCCVs); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete from decommissioned reactors, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility fo r regulatory research being conducted under UNR NRR-2017-001. RES will continue to evaluate the SLR-significant issue of cable aging utilizing harvested cables. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011 -014 and NRR-2016-012 to include more cable types (insulation types and medium voltage level cables) and the aging effects on power cables at different voltage levels. Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.0 . Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.0 ., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.0). RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the information tool/database. Task 3 RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of industry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research. RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships will build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as implementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs. RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete , ASR effects, aging management, and supporting technologies like non-destructive examination (NOE). RES is a participant in several multi-national cooperative research programs, including the OECD Halden Reactor Project (HRP), the International Forum on Reactor Aging Management (IFRAM), and many others. For example, the RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. IFRAM is envisioned to be a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research, regulation , education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORN L) submitted white papers to the HRP proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These resu lts will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NEA/CSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE, NRR/DM LR and NRR/DE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task4 RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff. Task 4 also allows for NRR to call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses. RES will also prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Building upon the extensive work previously done under UNR NRR 2014-001 , RES staff will continue to be available to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. As an example, the staff will continue to be available to review operational equipment failures to assess the trend in critical risk-significant electrical equipment. There are concerns with aging effects (including cyclic aging) and design life of other electrical components such as breakers and relays which would need further evaluation to assess its continued service life by exploring other monitoring techniques not generally covered under surveillance tests. Such analyses could complement work in Task 2, whereby critical electrical components can also be harvested and evaluated. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) .ot E ]FTE/year for this task be adjusted once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRC-supported research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. The deliverables and schedules for UNR NRR-2017-006 are shown in the following table. Schedule and Resources for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE Contract$ Number Date 1 Hold NRG/industry l forFY1 8 . .... (b )(S workshops (est. 2018, 2020) and FY 21 and prepare NUREG/CP and FY 2 1 summary reports on four SRM topics I Total (Task 1) 2 Develop a strategy for harvesting materials/components from decommissioned plants 2.A. Develop an information tool/database FY 18 c::::::J -- 1.. ... J. *- .()(et 2.B. Develop a process to evaluate plant components FY 18 [ 3 - . . **- . ...... ............. J J (5)_ 2.C. Use the process from 2.B. to evaluate the suitability of FY 19 G * **********************************************-********************** ...... ()(5) plant components 2.D. Continue to implement the process from 2.B. as Ongoing (FY components become 20-21) available from additional plants 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in retrieval and testing of ex- FY21) Task 3, below plant materials Total (Task 2) 3 Participate in relevant domestic and international activities (e.g., IFRAM, IAEA, FY 18-21 DOE LWRS , EPRI LTO, codes & standards) 4 Develop documentation evaluating significant technical issues germane to FY 18-21 the review of SLR applications Total (Tasks 1-4, over 4 years) I

                                              -10

Note to requester: This record includes the next two pages. l11ternal use 011ly 110 distribution outside NRC; May contain proprietary material David A. Castelveter Office Director U.S. Nuclear Regulat ory Commission Office of Public Affairs (Mail Stop O-16D3) 11555 Rockville Pike, MD 20852 301-415-8200 (0) 240-393-9563 (C) david .castelveter@nrc.gov www.nrc.gov 2

Baran, Jeff From: Cast,elveter, David Sent: Thursday, July 05, 2018 5:01 PM To: Cast,elveter, David

Subject:

Tomorrow's News Tonight 111l:emal use 011ly 110 dist. ibution outside NR:C, May contain proprietary material July 5, 2018 Traditional Media Non Responsive Record OYSTER CREEK - A reporter for RadWaste Monitor asked OPA Region I if NRC was interested in the "harvesting" of components from the plant following its permanent shutdown. We responded that there are no current plans to conduct an autopsy of the site. Non Responsive Record News Releases INon Responsive Record

Baran, Jeff From: Harrington, Holly Sent: Friday, April 13, 2018 5:00 PM To: Harrington, Holly

Subject:

Tomorrow's News Tonight lnte111al use Oiily ;;u distlibutiou out.Jide PJRC May cont ain material proprietary to news agencies April 13, 2018 Traditional Media Non Responsive Record OYSTER CREEK - The Lacey Pat ch sought more information from OPA Region I on whether the NRC might want to "autopsy" the plant following its shutdown later this year. After checking with staff in the Office of Research, we said there are no current plans to "harvest" materials from the facility, based on cost and other considerations. News Releases None 1me111al use 01119 110 dtsu lbut1011 outside r~RC May contain material propriet ary to news agencies

Materials Harvested by the LWRS Program Session 3: Source of Materials Thomas M. Rosseel, Deputy Lead, Materials Pathway And Materials Pathway Research Staff U.S. NRC (cables and concrete) EPRI (cables) WRS Light Water Reactor Sustainability Ex-Plant Materials Harvesting Workshop U.S. Nuclear Regulatory Commission Rockville, MD 7-8 March 201 7 Light Water Reactor Sustainability R&D Program

Given the complexity of reactor systems & materials degradation, a prioritization tool for research was developed to address knowledge gaps Joint DOE/ US NRC organized approach similar to the NRC's Proactive Materials Degradation Assessment (PMDA) on Internals and Primary Piping (NUREGICR-6923) for life extension to 60 years. Leveraged EPRI Materials Reliability Program / Issue Management Tables. Panels composed of Experts from DOE National Labs, Industry, Universities, and International Organizations Results (EPRI: AMP &SLR /NRC: GALL &SLR ILWRS: Research Prioritization) EMDA: An important component of understanding materials degradation is the examination of service-aged materials. Effort encompassed broader systems & longer lifetimes 80 Years O.gradatlon Highly Likely Degradation Highly Ukely

    -   Core internals and primary piping                  Umlted Knowledge to Mitigate It      Knowledge Exists to Mltlgm It
    -   Pressure Vessel
    -   Concrete
    -   Cabling PUBLISHED version of NUREG / CR-7153 is available on-line (NRC ADAMS)                                                                     Degradation ManagNble Extended Materials Degradation                 Degradation may be             1    2      3        By Mltlgatif n poHlble, but limited knowledge Assessment (2011-2013)                    to mitigate It If It did occur   KNOWLEDGE

An important component of understanding Materials degradation is the examination of service-aged materials.

• Access to materials from active or decommissioned nuclear power plants provides:

         - An invaluable resource for which there is limited operational data or experience to inform relicensing decisions and
         - To inform assessments of current degradation models to further develop the scientific basis for understanding and predicting long-term environmental degradation behavior.

• Two important sources of service-aged materials for the LWRS Program:

         - Zion Harvesting Project {cables, RPV, records, electrical) and 4

l(b)( ) Icrystal River 3: EPRI led effort in collaboration with LWRS and NRC (Cables) (b)(4)

(b)(4) ~OAK .. r.i}@ENERGY 4 ~RIDGE N11ional b.bonuory _____,, U Nuc:INr f-,y

(b)(4) Uoh<dSu!!*,?R  : ~~m ~ ~RSfir@ENERGY f'rot=ttng P,opk and,,,, E .. uhvwmmt u Nuc:t.ar 1-,,

The Decommissioning of the Zion Unit 1& 2 NPPs Provided a Timely Opportunity to Examine Service-Aged Materials Degradation

• In support of extended service (and current operations), ORNL coordinated and contracted activities with EnergySolutions.
• May 5, 2011, Workshop at Zion with attendees from: Energy Solutions, Industry, NRC, and DOE LWRS to discuss opportunities and constraints.
• In collaboration with the US NRC, EPRI, and others, a list of materials for "harvesting" has been compiled and feasibility examined.
• Structures and components of interest:
• Thru-wall RPV sections
• Cabling
• Concrete (timing & dose issue)

Rosseel, ORN L

Zion Unit 1 Containment Cables acquired in the Spring 2012 Harvested 6 sets of cables,~ 25' in length, and each containing two cable types - CROM DC power and position indicator. Also harvested 8 thermocouple cables identified during 2011 containment tour The LWRS Program and NRC are studying cables harvested from the Zion NPPs in an attempt to understand and predict cable degradation at extended lifetimes. Some thermocouple cables may still be available for collaborative studies Rosseel, ORN L ~.!-1-.:~ . .:.l!~g tWRS~ @ENEiGv Prom#ng Ptople and the Environmmt Nuc:t.ar f-,y

Zion Records Harvested from Vault 2013 Zion Records: The acquisition of key records from the Zion nuclear power plants provide critical information about the initial materials properties, in service inspection, and operational history of the Zion Nuclear Generating Station necessary to evaluate the degradation of in service materials. Records are stored at ORNL (Zion National Library), available for on site review and copying. Rosseel, ORN L

Zion Cables Part 2 (2013-2017) Harvested Zion Unit 2 low and medium voltage cables in collaboration with the NRC to help understand and predict cable degradation at extended lifetimes.

  -  Validate predictive models (based on accelerated aging studies) with empirical data obtained from field-aged materials and
  -  Provide greater confidence in the performance of cables during an accident with measurable indicators in lieu of relying on the current methodology of calculating service life based on environmental monitoring.
  - Accumulator Discharge MOV Cabling: 0MB, Lower Level of Containment Instrumentation Cables: Instrument Racks, 0MB, Lower Level Containment
  - Air-Operated Valve Cabling, 0MB, Lower Level Containment
  - Cables in Electrical Penetrations, (0MB), Containment elevation 617' Rosseel, ORNL             ~ U.S.NRC *WRS~ lir\'"'*

U,h<<I Sum N~la, R,gulno,y Commu,;0 , -. 0 "u,_..,o, W ENERGY 9 l'rot<<#ngProplumdtheEntnronmmr Nuc:t.ar f-,y

Harvested l&C cables from Crystal River and Zion supports improvement of cable monitoring and maintenance

• Harvested l&C cables play a critical role in developing models to quantify the influence of environmental degradation and develop practical NDE techniques to track the degradation in current NPPs

    - Many of the manufacturers no longer exist
    - Formulations from when cables were installed in
       ?O's and 80's have evolved through supplier changes and functional improvements

• In collaboration with EPRI & NRC in 2016, over 5,000 feet of l&C cable inside containment (Zion Unit 2) and outside of containment from Crystal River NPPs have been harvested and environmental degradation studies on highest priority materials has begun at ORNL and PNNL.
• Some Zion cables may be available {low activity Rad, Rad and asbestos, asbestos, no activity or asbestos)

Quantify/ model remaining useful life Demonstrate practical NOE techniques GOALS Disseminate results to improve current NPP cable aging management programs

Zion Harvesting 2013: Electrical Components for the US NRC

• Zion Electrical Components: Based on the information gathered during the February 25, 2013, visit to Zion to assess certain electrical components, the US NRC and SNL identified an L shaped bus bar that was harvested in 2013 for fire protection testing.
• Consumed in NRC fire protection study Rosseel, ORN L citu.S.NRC Uni!ed Su11:$ Nuclur R.cgul.nory Commiuion Prot<<ti,ix Propk and the Enuirr.mment

Zion Solutions RPV Segmentation Plan RPV by the numbers The Zion RPV had a total height without the head plate of approximately 353 in. (10.6 meters). The vessel wall has an inner diameter of 173 inches (4.4 m) and thickness of 8.8 inches (22 cm) over the beltline region. The nozzle section was approximately 11 inches (28 cm) thick. 31H The reactor vessel weighed 700,000

                                                                                                      ,v
                                       ~
                                         -  hAcomJ
                                            .,tr~                       lbs. (317 ton) and has a total activity of
                         ---=,......,__   I   "      1*~ 1
                                         /                              about 400 curies.

The stainless steel cladding has a nominal thickness of 5/16 inch (8 mm) 2')',_,_n1 The vessel was cut, using an oxy- ....._____ =~-*~ ~ s.sr-oe >>1'~"1 r::~::*..*:*Ven..i_ propane torch into 17 segments over 3 Reactor Pressure Vessel Isometric: View levels ~ lir\'"'*o"u,...10, D. Pryor, Energy Solutions tWRS w ENERGY 1 Nuc:INrf-,y 2

Zion Unit-1 RPV Harvesting (2013-2017

• One panel section, ~14 tons, was harvested in November 2015, cut into blocks that are now being machined into individual test specimens.
• Goal of research: B7835-1 Base Metal o Evaluation of radiation damage models o Comparison to surveillance and high fl reactor experiments o Attenuation and through wall variatio in base and weld metal.

o Mitigation techniques - annealing / -irradiation studies. Zion Unit 1 RPV Segmentation Ian B Welds and Fluence Inform ion WF-70, Belt-line Weld E)

"' fil          .. .

I 1*1 - '

I ,I -

I C:J LI I r I I

                                            *-    I         I  *=*              L lll,t-llMW.i*Undel0Wf*70..,.ldhat ,._,MIOJ7'Cl.l, 0.46M41, _                 1...__ lll,t
,-a ntut.On f l - h .. (>.15d011 fl/fW ()!Mell.. t.nlklpal>>d n alllfl 11 l4S"J. a. 1111!1**

MS Mffllllill O,lnl()u, ~ Ind L.38Mn, -t

LWRS Research plans for harvested Zion RPV material

• Comparison of harvested material to surveillance, computer models & high flux reactor experiment data.
• Determination of variations in base metal and weldment: influence of attenuation, compositional variations, microstructure and property changes.
• Specimen size effects: bias of the pre-cracked Charpy specimen, and testing of m-CT specimen
• Mitigation techniques - annealing / re-irradiation
• Re-irradiation of materials through fast flux irradiations to higher doses weid localiOn, 5 B

Weld loc,lion 1 _ ,, Qak RJdge Natlcw,al t.aboratorv M-1---1 L.oc.,tioos d Level 2 Stgmetits A fortlilivestilg Collaborations and opportunities: ~ K*::,:::* onw::_eld~ - ~ ~ _ _ J:;;:::::::::::+/-::::+/-)t::~~

• Current collaboration: CRIEPI (CNWG): mini C(T) evaluation
• Research that supports LWRS goals and is collaborative

~RS     @ENERGY NuclMt t..,.,
                         ~~1fcE N111ionial Ulhor.atory 14

Discussion? Light Water Reactor Sustainability tWRSfir@eNERGY 1 U NuclNr l-,y 5

LWRS Program: Harvesting Lessons Learned Session 4: Harvesting Experience Thomas M. Rosseel, Deputy Lead, Materials Pathway And Materials Pathway Research Staff U.5. NRC (cables and concrete) EPRI (cables) WRS Light Water Reactor Sustainability Ex-Plant Materials Harvesting Workshop U.S. Nuclear Regulatory Commission Rockville, MD 7-8 March 201 7 Light Water Reactor Sustainability R&D Program

Materials Aging and RPV Research Concrete Degradation Pathway CASS and EAF sec and IASCC Experimental Methodology ~ earch Swelling

                                                                       ~
                                                    .......       y I

I I I I I

                                                                          ¥'

Modeling Long-term phase Addressing scientific gaps in development and 4 knowledge of extended life Harvested I I I radiation-induced changes predictions, requires a Materials I multidirectional approach.

                                                                         - *

• Current status of activity

                                                                         --- Planned near term direction Baffle Bolts Individual tasks within the pathway provide contributions to the overall pathway goal through high quality scientific measurement of materials performance to understand the active modes and mechanism of degradation.

An important component of understanding Materials degradation is the examination of service-aged materials.

• Access to materials from active or decommissioned nuclear power plants provides:

         - An invaluable resource for which there is limited operational data or experience to inform relicensing decisions and
         - To inform assessments of current degradation models to further develop the scientific basis for understanding and predicting long-term environmental degradation behavior.

• Two important sources of service-aged materials for the LWRS Program:

         - Zion Harvesting Project (cables, RPV, records, electrical) and rb)(4)
                        \ Crysta I River 3: EPRI led effort in collaboration with LWRS 0

1< ><*> and NRC (Cab es)

                                                                        ~Rsfir G)eNeRov l~   N11clear Enetl)'

Zion Unit-1 RPV Harvesting 2011-2017

• One panel segment, ~14 tons, was harvested in November 2015, (4 segments) shipped to MPF, cut into blocks, and are being machined into individual test specimens.
• Goal of research:

o Evaluation of radiation damage model o Comparison to surveillance and high ux reactor experiments o Attenuation and through wall var" tion in base and weld metal. o Mitigation techniques - annea ng / re-irradiation Zion Unit 1 RPV Segmentation Ian B Welds and Fluence lnforma on WF-70, Belt-line Weld el "m;. 1-~1- ~,C=.J

                                ~'.I                              1~
             =sa nw _1,..    -1o
   ,._ **ut- "'--

llfKI*

• w,,. _... .._,

fxl'ia

                                                 ..-o.2-,,,,c11.o.~ 1. - i . . - , . . n.

h

• 0,1$,dO" ,ift,s' (>lM*V~ An~*lltd Tf 1hlfl It t*S"'f. .... -
• I Ml ..,mlftll O.lnlC41, ~ IM LJ-*** f'

Lessons Learned and Issues to Consider (1) Long range goals, objectives, framework, partners Work shop at Zion NPP, May S, 2011 including DOE National Labs, Industry, NRC, and EPRI Discussions with Zion/Energy Solutions, NRC, Westinghouse, EPRI) Partnerships (Leverage resources, opportunities for collaboration, publish and share results} Cables (DOE led joint effort with NRC at Zion Ul and U2) Cables (EPRI led effort with NRC and DOE (ORNL and PNNL) Cables from operating plants (EPRI led and shared with DOE: ORNL and PNNL) RPV (CNWG Collaboration with CRIEPI to test mini C(T) specimens from Zion) Limited opportunities Previous attempts to obtain RPV material from Trojan, SONGS 1 via the US NRC HSSI Program were unsuccessful Attempts to obtain surveillance capsules from Zion Unit 2 [capsule X {2e19)]{LWRS) and Palisades [high Ni] {HSSI and LWRS) were unsuccessful Future US opportunities (SONGS 2, Ft. Calhoun, & closure of older, smaller NPPs) Future International opportunities (Japan, Sweden, others?) Research value Compromise between availability and value (EFPY/fluence) Scheduling issues Working within the critical path of the decommissioning organization (priv. vs. gov.) Discussions and meetings with D&D Organization since this not their highest priority (not a reflection of lack of cooperation) Requires regular site visits and contacts!

                                                                              ~Rs6IO G)eNeRov l~   N11clear Enetl)'

Lessons Learned and Issues to Consider (2) Flexibility Ability to modify plans to maintain objectives, adjust to schedule changes and stay within cost constraints) Quantity of material harvested Sufficient material to validate models and compare with accelerated experiments Sufficient to support agreed upon collaborations and partnerships Material Pedigree Records (composition and initial properties), reports (including inspection, qualification, and surveillance results) Characterization after harvesting Hazardous Materials Handling at site, transportation, handling at testing site, disposal, time, and costs Logistics Contracts (8 for Zion materials), liability, shipping, disposal of waste Costs (harvesting, handling, storage, fabrication, testing, & managing) Yes; it is very expensive from planning to execution and testing!

                                                                     ~Rsfir G)eNeRov l~   N11clear Enetl)'

Discussion? Light Water Reactor Sustainability 8

Note to requester: There are 2 attachments to this email, they are both immediately following this email. Portions of this record are redacted under FOIA Exemption B5, From: ~ Deliberative Process Privilege. To : Hiser Matthew Subject : FW: SLR UNR response 07-24-2017_abh .cln (IF) cm .abh ..docx Date: Tuesday, August 01 , 2017 4:40:26 PM Attachments: SLR UNR f!iS!)Q.[lSS 07-24 -2017 abh.cln {IF) cm.abh.. docx.do.cx Matt, please can you look at the comments from Steve that affect you in Task 2? Such as about information tool and PNNL reports? From: Hu ll, Amy Sent: Tuesday, August 01, 201 7 9: 20 AM To: Pires, Jose <J ose .Pires@ nrc.gov> Cc: Moye r, Carol <Ca rol. Moyer@nrc.gov>

Subject:

SLR UN R response 07-24-2017 _abh.cln {IF) cm.abh .. docx Please can you (or Mita or Jake) take a look at the attached comments concerning the following paragraphs and help us improve the following? Based on information gleaned from discussions on the potential for harvesting and testing of concrete from decommissioned reactors, RES will provide a database to NRR on the possibilities for this activity and prioritize testing in a technical letter report (TLR) . As an example , the TLR will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting . Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. RES will provide the database for NRR review and will summarize the priority listing in a TLR. A separate TLR will be submitted to NRR on the process for harvesting and testing of concrete samples from decommissioned plants.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0 C. 20555-0001 Auigust xx, 2017 MEMORANDUM TO: William M-c-GeaABrian E . Holian, Acting Director Commented IFl1]: Please replace w it h Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. W eber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUE NT PERIOD OF EXTENDED OPERATION: N RR-201 7-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of N uclear Regulatory Research (RES) to provide "specific research products to facilitate the technical assistance. with W acilitatel the-- Commented lfl2]: ... provide technical assistance wit h7 evaluation of tl:le-future applications for.E. ia-license to operate during the subsequent license Commented [HA3]: Actually I w as quoting from the renewal (SLR) period (i.e., 60 to 80 years). These products should build upon an alysis request ... methods, tools, and expertise developed a.s part of ongoing and new research activities, Commented [CM4]: Disagree w ith deletion focused specifically on aging effects during the SLR period.: This user need request (UNR} supersedes and incorporates work from the previous UNR N RR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years). ~ his UNR supercedesoverlaps 'Nith NRR= 2014-001 "provnde expert assistance with reviewing the guidance documents for subsequent license renewal." I and Commented [FIS]: The work on UNR 2014-001 1s complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation essentially complete, so I suggest deleting this sentence. If of reactor vessel internals." t here is overlap wi t h UNR NRR-2017-001 t hen that should be stat ed here, including a st atement on w hat we will do t o For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427). ~ ~ The purpose of this memorandum is to respond to the request in NRR-2017-006 prevent duplicati on in effort. Commented [HA6]: I am quoting from t he request and - from the earlier UN Rs. I want to keep this paragraph as it is. with RES's plans to accomplish the requested tasks: Commented [Fl7 ): This t he ADAMS number for the UNR: Task 1 requests RES to hold NRG/industry workshop(s) on the status of domestic and international research activities to address and evaluate tho status of aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR Report. Task 2 requests M L16358A427 Commented [HA8]: That is for 2017-001. - RES to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants, as well as from ex-plant components harvestedrecoverod 1from operating plants. Task 3 requests RES to continue to develop ICommented [CM 9]: Or harvest ed? domestic and international partnerships to share expertise, capabilities" and resources related to aging management research. _Task 4 requests RES to develop documentation and compile resbflts evaluating significant technical issues germane to the review of SLR applications.frem-Tasks 1, 2, and 3 on tho status of research results in support of the Commission' s direction to the-.staff. Based-OR-lat&f-alignmenl between NRRJl)MLRand RESIOEjsta~l'ask 5 was.added Commented [Fl10]: At a minimum w e will need t o claim by RES le pre\*ide confirmatory analyses and exeert technical assistance with the re\'iewing of division level alignm ent for adding Task 5. The OE anticipated industry reports and filB_applications ~of potentially significant technical issues_ management briefing on SLR next week wi ll be a good opportunit y t o bring Brian and Chris up-to-dat e on t his, OO;;a;-tiqht review schedule. suct\-as-tAe-SLR aeelications to be submitted with elant wecifiG- including t he need, if any, for them t o align on t his w ith qao analyse& t heir counterparts. RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. _RES staff will continue these activities and integrate the results in deliverables under Task 4.

The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and the anticipated schedule for the deliverables. CONTACT : Amy Hull, RES/DE 301-415-2435

iw.--OeanB. Holian [ Commented (Fl11]: Please replace with Aeling Director. RES staff appreciates the coordination with NRR technical staff and management in this area. . We will continue lo coordinate with NRR staff and management to ensure that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs could impact the activities, deliverables, and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and, if warranted, the UNR will be amended.

Enclosure:

Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

 ~ B. Holian                                       . 3.                                                    Comme nted (Fl 12): Please replace with Acting Director.

IRle:S staff a13f')Fesiates th e seeFdinatien with ~IRR teshnisal staff in this aFea. VVe will sentim1e le soominale with NRR staff and R1anageR1enl le ensure lhal regu latory needs and priorities are satisfiea. Chan9es in the availability of rnso1c1Fses or ~IRR neeas sould impast the aslivilies, deli.1/erable&-a~les-of thi&-UNR.- ffi-6UGh Ga686,changes-will l=J&..implefnefteG jointly-by.. RES ana ~IRR ana, if warrantea, the UNR will be amenaea. EnslOSIJFe: Response to UseF ~leea Request foF ReseaFsh Assistanse en Potential Si9ni~sant Teshnisal lss1Jes El1c1Fin9 the Subsequent Perioa of Extended 013eFatio~ Commented (Fl 13): The memo template has changed, so memo content is not shown on concurrence page DISTRIBUTION: B. Thomas, RES G Wilson, NRR R. Tregoning, RES A. Hiser, NRR I. Frankl, RES R. Iyengar, RES T. Koshy, RES K. Miller, RES D. Seber, RES S. Stuchell,_NRR B.Brady, NRR A.Hull, RES C. Moyer, RES M. H iser, RES M. Kirk, RES J. Philip, RES RidsNrrMailCenter ADAMS Package Access1on No.: Mlxxxx OFFICE RESIDE/CMS RESIDE/CMS RESIDE/CMS RESIDE/GIB RESIDE/ICEEB NAME .,_S. Moyer A. Hull I. Frankl _R. Iyengar T. Koshy DATE

                -          I 12017 I /201~      I  12017 I  12017         I 12017 OFFICE               RES:DE:SGSEB D:RES:DE           RES Mail Room       D:RES NAME                 D. Seber        8 . Thomas      K. Johnson         M. Weber DATE                   I 12017           I /2,017       I 12017           I  120 17 OFFICIAL RECORD COPY

User Need Request (UNR) Response NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRC/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR Report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two dome*stic and international activities (either .a workshop, conference, symposium, or meeting), one in early autumn 2018 on-tl=le mechanical issues and one in late spring 2020 on tl:\e-concrete and cables issues. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016; ongoing research on materials degradation issues and aging management of these issues, as discussed in the GALL-SLR, and any new operating experience from the initial license renewal period (or the long term operation period for international plants). These activities will be specifically targeted toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables include the international activities (either a workshop, conference, symposium, or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR'-~Prior to the meetings, RES will provide a draft agenda and proposed presenters. The information from these activities will be documented in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (e.g., presentations or papers) and research insights and knowledge, provided within 6 months after each meeting. As part of the requested Autumn 2018 workshop/ conference/_symposium/_meeting on mechanical issues, the NRC staff will coordinate a session, or sessions, concerning issues associated with reactor vessel embrittlement during the 13eriee ef SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and international industry and regulatory representatives. The product of these sessions (presentations and/or papers) will be documented ininslueee as 13art ef lhe NUREGICP a report as described above. RES will alsof:)lal:l-te hold an NRC/industry workshop with international participation in the third quarter of FY20 (spring of 2020) on the state of knowledge for the technical issues in concrete and containment degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that the workshop will need to address several concrete-related issues where related research is still active, RES will plan for a three-day workshop that may include breakout sessions for specific5fl8Gialty items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before the workshop. RES will document the results of the workshop in a ~JURl::G/CP report, which will include a summary of the workshop, presentations and workshop insights and conclusions. Task 1 will continue until the completion of the deliverables from thisthe second activity, tentatively scheduled for late spring 2020. h"as k 21 Comme nted [Fl14]: Please add sub-sect ions for Sub-tasks 2A - 2E. This w ill improve clarity and wi ll better align RES staff will continue to develop and implement a long-term strategy for obtaining information the response w ith t he UNR. on materials degradation from decommissioned nuclear power plants, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, 2.A - 2.D as stipulated in the NRR UNR, page 4. Under a long-term research project preceding !His-the current request from NRR, RES has-pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting.Jn the first activity :under Task 2, RES, with contractor support from Pacific Northwest National ( Comme nted [Fl15]: Is t his 2.A? Laboratory (PNNL), has-developed an approach to prioritize technical issues best addressed by harvesting._The deliverable ~v-iaes-provided criteria to assess the need for harvesting to address a particular technical issue. _The report then ~ - Pllli~.Q_lhese criteria to assess four example technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. _This report also 60\'efS-Covered the background on the need for harvesting, and past harvesting e fforts and experience._The purpose of this report is-was to serve as a tool for NRC staff ~ to prioritize technical issues best addressed by harvesting. The final report for this research is expected to be published in August, 2017. Final rnportin!J for this effort is oxpoctos by Au!Just 2017. \ Commented [Fl16]: Will the final PNNL report be shared with NRR or is RES st aff going t o use the PNNL report and In the second preceding activity, the ~JRC RES closely coordinates collaborated with the provide added val1.1e as part of t his UNR? Department of Energy (DOE) and Electric Power Research Institute (EPRI) Gfl::&ltWAl-rnaterials haP1esting ans, as rnentiones abo*1e. hosted to host a workshop on ex-plant materials harvesting on March 7-8,., 2017. _The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning._The workshop was we-II-attended by representatives from DOE, lhe-EPRI, the U.S. industry, and international research organizations. _Key insights from the workshop includeg the need for a clearly de fined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested._The workshop summary report will be distributed among meeting participants and is expected to be finalized by August, 2017. As Bari of tho lsocons activity under Task 2, RES will be (Eommented [Fl17]: Is t his 2.B? pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and creating a 'sources of materials' database. Subtask 2.A. Moving forward , RES will work internally to evaluate how the four significant issues identified for Commented [Fl18]: Would this be an MS-Access SLR in the SRM on SECY-14-001 6 may be best addressed by harvesting, as requested in UNR application? Under 2.A, t he UNR talks about " an Information Subtask 2.A. As an example, RES will develop a database hich identifies and prioritizes the tool" . Would a database alone "foot the bill"? concrete materials, components and operating conditions neede*d to address the significant Comme nted [CM19]: " Information t ool" is often another issues. RES will develop a process to evaluate concrete samples harvested from t erm for database (so, it would f it the bill), w hile skirting decommissioned plants. and~ will follow through with implementing the process as some database const raints. concrete materials become available from additional plants._The scope of the harvesting stra tegy includes: alkali silica reaction (ASR)-affected structures; post-tensioned structures with emphasis on pre: stressed concrete containment vessels (PCCVs); corrosion of pre: stressing tendons, liners, reinforcing steel, and embedments; concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects); and concrete structures exposed to high rad iation (typically bio-shield structures of certain PWR designs). IA-a-OGiliGAr-fef-iffa(jiat~ffeat~te-matei:ialsr-RE.S-will-fGGU&-OR-IAl}.ef.GlaiRlesS-6teel,- l+his is also addressed in UNR NRR 2Q17 001. Commented [Fl20): If there is overlap with other UNRs we need to be more specific to assure that there is no Based on information gleaned from iscussions on the potential for harvesting and testing of duplication in effort. Also, this should be mentioned in the concrete from decommissioned reactors, IRES will provide a database to NRR on the possibilities for this activity ~nd prioritize testing in a technical letter report (TLR),. As an example, the TLR will document the process to evaluate \Re-concrete samples from nuclear memo. Commented [Fl2 1): With whom? Commented [Fl22]: Please clarify. power plants undergeing deoemmissiening er ex plant samples from eperating plants (and its-their suitability Ulal-weuld-e&-a!)f)ropf'iate-sandiGates-for harvesti ng-will-Oe-deG1Jmentee-iR-th&- l e t l ~ A A. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. ~ES will provide the database developed for NRR review and Yl1!!.summarize the priority listing in a TLRleller rei:iert. A separate TLRletter rei:iert will be submitted to NRR on the process for harvesting and testing of concrete samples from decommissioned plants.I Commented [Fl23]: Please combine this with the previous paragraph. Are we lalking about two or three In addition to irradiation effects on concrete materials, RES will continue research on IAD of TLRs? stainless steel. {frhis is also addressed in UNR NRR 2017-001.) Under Task 2 of this UNR, Commented [Fl24): If there is overlap with other UNRs RES will seek potential sources of reactor internals that may become available ior harvesting, to we need to be more specific to assure that there is no evaluate their utility to advance research being conducted under NRR-201-001. duplication in effort. Also, t his should be mentioned In the memo. RES will apply the criteria developed with PNNL described above to the issues for SLR, and Yl1!!.document the outcome of the analysis in an ]information tool\, which identifies and Commented [Fl25]: Please see my comment on this on prioritizes the materials, components, and environmental conditions that should be pursued the previous page. for harvesting. _The intent is for this information tool to be a living document that can be updated to reflect the latest operating experience and research, so that users may le-- understand which data needs may be best addressed by harvesting). [ Commented [Fl2 6]: Please clarify. Subtask 2.B. In parallel with the information tool activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting, as requested in Subtask 2.B. _Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from the plant to make an informed decision on harvesting._ In many cases, this information may not exist, or i!_may be challenging to find in 11:le-plant records. _RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. _A TLR!eGRAiGal-leller reper:t documenting the information tool with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.D. Implementation of the evaluation process developed in Subtask 2.Bc will be pursued in Subtasks 2.C, and 2.D., as requested in the UNR. _RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluationso\1oloflR1ont process will identify confirmatory needs that tho 1c1se of harvested samples can effectively address, will consider decommissioned plants in the U.S. plants-as well as sosoR1mi&&ionos fllanls and abroad, and will leverage to the extent possible domestic and international cooperative research opportunities, as stipulated in [S ubtask 2. E.I Through Commented [CM 27): How Is Subtask 2.E. distinct from their national and international contacts, !Re-RES staff will maintain alertness for harvesting Task 3? opportunities iA-relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the MiGfesefl..information tool. Task 3 RES staff will continue to develop domestic and international partnerships to share expertise, capabilities and resources related to aging management research for long-term operation. These exchanges are critical for the confirmatory review of !Re-industry research or research lhal the ins1c1stry-usegs to justify the adequacy of their aging management programs (AMPs), as Commented [Fl28): Is this wording correct? well as for the NRG independent confirmatory research. The DOE Light Water Reactor Commented [CM 29): The resultant wording looks OK. Sustainability (LWRS) and the EPRI Long-term Operation (LTO) programs support most of the domestic research to support aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of long-term operations. RES staff hiw&-has frequent technical interchange meetings with DOE and EPRI staff, which have concentrated on irradiation effects 1 on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NDE).I Commented [CM30): What has concentrated on these topics - meetings, DOE & EPRI staff, ... 7 RES will continue to nurture The fellowin!I fjara!jrap~Fale a few of the emerging domestic and international partnerships-that-R6S-i&-nurtuf'.ing,-R6S and will-plans-to continue to develop those partnerships, elher e*islin!I fjartnershifl& net insl1c1ses here, as well as other suitable opportunities that may emerge to address the aging degradation issues. RES is a participant in several multi-national coo erative research ro rams includin the Halden Research Pro ram and man others. For exam le Commented [CM 31): As suggest ed, these examples could be omitted.

1. tfhe RES Office Director signed in 2015 a multilateral 4-year memorandum of understanding (MOU) for the International Forum on Reactor Aging Management (IFRAM). IFRAM is envisioned to enable appropriate exchange of information among those parties and organizations around the world that are presently, or are planning on addressing issues of NPP SSC aging management. IFRAM is a network of research organizations, industry groups, regu latory bodies, and academic institutions involved in reactor aging management research, regulation, education and training as well as nonprofit research institutes having academic and industrial links. Four objectives support this purpose: cooperating to achieve common objectives, sharing information, identifying joint research or demonstration projects that can be pursued under separate agreements, and identifying and promoting best practices.

2. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned nuclear power plants worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the joint Halden Research Program proposing research on irradiation effects on steel-concrete bond, and on creep effects on irradiation damage. RES is working to finalize a bilateral agreement with the French lnstitut de Radioprotection et de Surete Nucleaire (IRSN), for exchange of technical information on the effects of ASR on the performance of nuclear concrete.

IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES has an ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete and will continue participating under the international Organization for Economic Cooperation and Development (OECD) and Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations OECD/NEA/CSNI to develop modeling expertise for ASR effected concrete structures. I Commented (Fl32]: In my opini on, this is t oo much detail for a UNR response. Let's discuss. Through their national and international contacts, and through Gl<odes and S§.tandards developing activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide !Q_NRR management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided to NRR in a timely manner; the effort will continue until the closure of this UNR. B elevant findings from recent interactions, status and future plans will be discussed as a Commented (CM33]: This sent ence coul d be omitted. standing agenda item during the interface meetings between RESIDE, NRRIDMLR and NRRIDE. _A qblartorly report (or slides) for presentation at aAY-Director/Deputy Director interface meetings will be provided 5 days before the meeting. RES staff will document and compile results from Tasks 1, 2, and 3 on the status or research results in support of the Commission's direction to the staff. RES will prepare a document annually summarizing the products from the three tasks above and discussiJlg the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. The annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting t*o the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Tas k 5 RES staff will contimie to provide confirmatory analyses and expert technical assistance with the review of reviewingthe technical documents to be lofsubmitted with SLRst11:Jseqt1ent license feflewal applications!, o><orlapping witl=l and building upon the extensive work done fof-under UNR NRR 2014-0011. RES will support tighter SLR application review schedules as well as the Commented (Fl34]: As discussed work under UNR 2014* review of plant- specific gap analyses expected with the first applications. Process optimization 001 is essentially compl ete, so I suggest delet ing this. has resulted in the proposed review time for SLR applications (SLRAs) to be reduced ~ mGfltl:ls-from the 22 months allowed for LRAs to 18 months. Thus the expected work may be more intensive. In addition. t+he initial SLRAs are expected to require the review of plant:- specific gap analyses, especially before critical documents, such as MRP-227 Rev 2 (upon which AMP XI.M16A for PWR vessel internals is based). have been finalized an-d approved by NRC. In the absence of an acceptable generic methodology that considers an operating period of 80 years, the gap analysis is used to ensure that aging management for 2._specified SSC is appropriate for 80 years of operation. RES will assist with the technical evaluation ofevaluate SLR- related licensing oroducts and reports (e.g., topical reports, SLR applications, LERs) that may be submitted~ to NRC in support of emerging generic or plant-specific issues. Representative misoellaAeo1,1s examples include issues such as baffle-former bolt degradation, other concerns related to vessel internals, carbon segregation in vessels, Gf-and concrete degradation. RES subject matter experts (SMEs). as requested by NRR/DMLR, will participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. Based on the latest assessment of projected needs in this area~eS-staff4ias. l;ioon in,.,ol¥oEI in Eliso1,1ssions wilh Y'~e1,1r-neees, RES proposes that the estimate of _c ::]FTE/year for this taskma~ to be adjustediF\Ofea6eo-Of-OeGf-eased once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and, thi.§e effort shallsl:loolG continue until the closure of this UNR.

                                                  -10

Deliverables and Schedules RES staff will participate in ~teekly, monthly and quarterly meetings with NRR staff and Commented [Fl35]: Quarterly counterpart meetings managers to discuss the latest developments and information from industry and NRC- should be sufficient. Obviously the staff will interact more supported research, particularly insights that may impact regu latory decisions or aging frequently, as needed. management guidance. Staff-level interactions are expected to be frequent. as needed. RES staff agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. Deliverables and schedule for UNR NRR-2017-006 are shown )n the following tabl~. Commented [Fl36]: It will be difficult to edit t his table if not In native Word format. Also I could not provide fine Item Schedule and Resources for t he Various T asks specific comments because this table was probably copies Period of Performance (FY18-21) as "picture" from Excel. I suggest using a standard Word isk Nurrb T ask Description Completion Date FTE Contract $ table. {b)(5) (b)(5) .* lforFY18and

                                                                                                                                                                                                                                        -Developing information tool may require more FTE and/or Hold NRG/industry workshops (2018,                                                                                        .

FY21 year (b)(5 FY211 I *** contractor support. Does PNNL have tool that could be 2020) and prepare NUREG/CP and (b)(5 - :.... ... _....,1

                                                                                                                                                                                .... .....                                               modified for this purpose? If so, funds should be added for summarv reoorts on four SRM tooics                                                                                                                                                                       2.A.
                                                                                                                                                                                                                                        -Please add estimated travel costs for participating In (b) 5) domestic and international meetings under Task 3.

strategy for harvesting materialslcompooonts 2 -we may need contractors to assist us with Task s, so please from deeommlssioneo plants add some funds for contractor support related to work on 2 .A Develop a database FY18 I (b) 5) Tasks.

          *** 2]:i" ******* Devetopa*proc!!s*s tci"eviiluafe ilia (b) 5)                           com oonents from olants                                                         ....... .FY.18...
                                                                                                                                                                                                        ' ' * * * * ******m*.................,..,..,.,.,.,.,.**no
                     ......... USelheprocess developed In item B to 2.C               evaluate the suitability of components from (b) 5)                          Iolants                                                                             ....... F.Y.1.9.........
                            . Conffnue     to im plement the process developed in item Bas components                                                           Ongoing (FY20-(b) 5)         20 become available from additionaLolants .. FY21l *                                                                          ... ..!=7vear~                                                                                                                                                                              (b)(5)

Puisue partnerships for cooperative cost-sharing on retrieval and testing of ex-plant Ongoing (FY18-2.E harvested material FY21) oart of Task 3. below {b) 5) .TotaL(Iask.2) j b){5) Participate in relevant Domestic and {b) 5) International aclivlUes (e.g,.JFRAMDOE... FY18-FY21* * *E *--* Jyearr - - - 7 [ 3(totaUor..ll. L.....:::J .. years**tFRAMdues) j b)(5). 3 ..... ** tvvRS. EPRI CiO. codes & standards\ .. @(~L Prepare annual report documenting and (b) 5) compiling results from three preceding....

           ...... 4-. .......

• tasks ....................... * .................................. . . FYl8-FY2L . EJyearc:::::::) r . . . . . .. . . ...
• 1********............................................. .................................................- ....,-....._ ~( 1

                                                                                                                                                                                                                                                                                                                                           )J'\(5~L)

Provide expert technical assistance wnh reviewing documents for subsequent (b) 5) .. . ... . ..... .lic.ense..renewal(-e,g,*SLRAs*;--topical *"" (b )(5) 1 1 5 reoorts) Total Call 5 tasks .ov.~.r.4. wars I ........ . 1 (b) 5) (b)(5) Schedule and Resources for the Various Tasks Period of Performance FY 18-21

                                                                                                                                 - 11

Task Task Description Completion FTE Contract$ Number Date 1 Hold NRG/industry

• ltor*FY18 J ~)(5) workshops (est. 2018. 2020) and. FY 21 (b) 5) and prepare NUREG/CP and ........... FY.21 * ****** Q vear (b)(5)

      ****~****~ ---**~***~ :~t:!:~m~                  **~~;;,~t!~,~~;C:2r:~p-o_        rts_ o_n _fo_u_r ___        .. -
                                                                                                                 * ._J          :;:--:-;--;;;;-----:-----;-c-+ ------ ----1~~;:::=****=**~                                                       ****~        *** t- - - -
                                                                                                                                                                                                                                                     ***~***~l--i (b) 5)                                                                                                                            T.otaUiask...1)..                                                      I              I            1             1                                                                                 _(b)(5)
                       *2 **                    UeveloP a strateov for harvestina materials/ com Jonents from decommissioned Plants (b) 5)                2.A.                        Develop a database                                                               ..... ..EY..1.8... .. . .... I *** 1 2:B: .... Ueveloii*a process to (b) 5)     1-- -**=               ....=...*l:J**e!:!l'.a~

ll!i: lu!l:!a!l:!te:;;J

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                                 ** ****** *Plant components Continue to implement the process from 2.8. as

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( ) ) 1 ************ . 1 available from additional olants 2.E. Pursue partnerships for cooperative cost-sharing on retrieval and testing of ex-Plant materials I (b)(5) I (b)(5) Develop documentation evaluating significant technica l issues germane to the review ot.

                                              ** sLR.applicationse@pafe-
         +     *****************          I annual roaort doouf!1enling i:esulls from +asks 1 3 Develop documentation evaluating significant technica l issues germane to the review of expert SLR applicationsi?:fe¥:ide:......

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                                                                                                                           ******* FY       rn~21* * *****.*.** **

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                                                                                                                                         - 12

UNITED STATES NUCLEAR RE G ULATORY COMMISSION WASHINGTON, D C 20555-0001 August xx, 2017 MEMORANDUM TO: Will* ,,A M n ri£3ri .!l f I 'l , A, :tma Director Comment ed [Fl1]: Please replace w ith Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO RESEARCH ASSISTANGE ON POTE NTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of Nuclear Regulatory Research (RES) to provide "specific research products to facilitate the technical assistance :'!'ti!!)_jacililat~ tho Commented [Fl2]: ... provide technical assistance with? evaluation of lfle-future applications for.J! a-license to operate during the subsequent license Commented [HA3J: Actually I was quoting from t he renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis request ... methods, tools, and expertise developed as part of ongoing and new research activities, Commented [CM4]: Disagree with deletion focused specifically on aging effects during the SLR period.: This user need request (UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years). iThis UNR supercedes.overlaps with NRR= 2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" ~and Commented [FIS]: The work on UNR 2014-001 ls complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation essentially complete, so I suggest deleting this sentence. If of reactor vessel internals." there is overlap with UNR NRR-2017-001 then that should be stated here, including a statement on what we will do to prevent duplication in effort. For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427).

          . The ur ose of this memorandum is to res ond to the re uest in NRR-2017-006                Commented [HA6]: I am quoting from t he request and from the earlier UNRs. I want to keep this paragraph as It is.

with RES's plans to accomplish the requested tasks: Commented [Fl7]: This t he ADAMS number for the UNR: Task 1 requests RES to hold NRG/industry workshop(s) on the status of domestic and ML16358A427 international research activities to address and evaluate tho status of aging degradation issues Commented [HAS]: That is for 2017-001. identified in in the SRM on SECY 14-0016 and in the GALL-SLR Report. Task 2 requests For matt ed: Highlight RES to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants, as well as from ex-plant components harvestedrecevoreel from operating plants. Task 3 requests RES to continue to develop rCommented [CM9]: Or harvested? domestic and international partnerships to share expertise, capabilities, and resources related to aging management research. _Task 4 requests RES to develop documentation anel compile ffiSUlls evaluating significant technical issues germane to the review of SLR applications.fr-Om Tasks 1, 2, anel J en tho status of research results in support of the Commission's elirectien to tho staff. Basoel on later alignment between NRRIOMLR anel R!;;S,10!! staff, Task 5 was adeloel Comment ed [Fl10]: At a minimum we w ill need to claim ~ e r y analyses anel expert leohniGal-a&sislanoe with ~reviewing..Qf division level alignment for adding Task 5. The DE anticipateel inelustry reports anel SLR applieatiens withef petonlially significaAI technical issues_ management briefing on SLR next week will be a good opportunity to bring Brian and Chris up-to-date on this, on a light re*1iow schoelule. suoh as tho SLR applioations to be submittoel with plant spooifio including the need, if any, for them to align on this with aao-aMlyse&c their counterparts. RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. _RES staff will continue these activities and integrate the results in deliverables under Task 4.

The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and ~ anticip*ated schedule for the deliverables. CONTACT : Amy Hull, RES/DE 301-415-2435

 ~ f'      .6. Holian                                                                          Commented [Fl11 ): Please replace with Acting Director.
                                                                                                  ~

,RES staff appreciates the coordination with NRR technical..staff. and management in.this. area. Formatted: Font color: Auto .We.l'lil continue to coordinate wit R staff an mana ement to ensure that re ulator Formatted: Font color: Auto, Not Expanded by/ needs and priorities are.satisfied. Changes in the availability of resources or NRR needs Condensed by could impact the activities, deliverables, and schedules of this UNR. In such cases, changes Formatted: Font color: Auto will be implemented jointly by RES and NRR and, if warranted, the UNR will be amended. Formatted: Font color: Auto, Not Expanded by/

Enclosure:

Condensed by Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Formatted: Font color: Auto Formatted: Font color: Auto, Not Expanded by/ Condensed by Formatted: Font color: Auto Formatted: Font color: Auto, Not Expanded by / -

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W Deans, Holian Comm ent ed [Fl12]: Please replace w ith Acting Director. !RES staff appreciates tl=ie ceersirialieri wilh ~IRR lecl=iriical staff iA ll=iis area. We will ceriliri1c1e le cooFElirialo will=! NRR staff aAEl mariagomont lo oAsuro tl=ial regulatory Aooas aAEl prioFilios are satisfies. Cl=iaAges iA ll=ie availability ef reseurces E>f NRR rieees ceule impact lhe activities, 9&1iverallles aris scl=ieaules of ll=iis U~IR. In such cases, cl=ianges will Ile implemeAlea jeiAlly by RES aAG ~IRR arie, if warrarilee, ll=ie UNR will l:Je amerieee. Ericlesure: Resperise lo User ~I00G R0E!Uest fer Rosoarcl=i AssislaAC0 OA PoleAlial SigAificaAt Tocl=iAical Issues suririg tho Subse(luonl Peries or !ei<lerisee Operalieri Commented [Fl1 3]: The memo t emplat e has changed, so memo content Is not shown on concurrence page DISTRIBUTION:

 ,B. Tho mas, RES                                                                                                  Fo rmatted: Font color: Auto
 ,G Wilson, NRR                                                                                                    Fo rmatted: Font color: Aut o
 ,R . Tregoning, RES A. Hiser, NRR                                                                                                    Formatted: Font color: Auto I. Fra nkl, RES R. Iyengar, RES T. Koshy, RES K. Miller, RES D. Seber, RES
 ,S. Stuchell,_NRR                                                                                                (!om,atted: Font color: Auto B .B rady, NRR A.Hu ll, RES

p. Moye r, RES [io rmatted: Font color: Auto M. Hiser, RES M. Kirk, RES J. Philip, RES RidsNrrMailCenter ADAMS Package Access1on No.: MLxxx x OFFICE RES/DE/CMB RES/DE/CMB RES/DE/CMB RES/DE/CIB RES/DE/ICEEB NAME

                    - C. Moyer
                                     -   A. Hull f-I. Frankl
                                                                         -    R. Iyengar
                                                                                           -    T. Koshy DATE                I /2017             I /2017        I /2017               I /2017          I /2017 OFFICE            RES:DE:SGSEB D:RES:DE               RES Mail Room          D:RES NAME              D. Seber           B. Thomas        K . Johnson         M. Weber DATE                I /2017             I /2017          I /2017             I /2017 OFFICIAL RECORD COPY

User Need Request (UNR) Response NRR-2017-006 Formatted: Footer distance from edge: 0.73" Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRC/industry workshops on the*status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR Report (NUREG-2191). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592l. RES will facilitate a minimum of two domestic and international activities (either a workshop, conference, symposium, or meeting), one in early autumn 2018 on-tJ:\e mechanical issues and one in late spring 2020 on tfle.-concrete and cables issues. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016; ongoing research on materials degradation issues and aging management of these issues, as discussed in the GALL-SLR, and any new operating experience from the initial license renewal period (or the long term operation period for international plants). These activities will be specifically targeted toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables include the international activities (either a workshop, conference, symposium,

• Formatted: lnder1t: Left: O". Don*t add space between or meeting) and summary reports on the research insights and knowledge gained on the four paragraphs of thE> same style, Wid ow/Orphan control, major issues identified in the SRM on SECY 14-0016 for SLR~~Prior to the meetings, RES will Don't adjust space between Latin and Asian text, Don't provide a draft agenda and proposed presenters. The information from these activities will be adjust space between Asian text and numbers documented in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (e.g., presentations or papers) and research insights and knowledge, provided within 6 months after each meeting, (jormatted: Font:

As part of the requested Autumn 2018 workshop/ conference/_symposium/_meeting on mechanical issues, the NRC staff will coordinate a session, or sessions, concerning issues associated with reactor vessel embrittlement during the perieel of SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and international industry and regulatory representatives. The product of these sessions (presentations and/or papers) will be documented iniAclueleel as part of the NUREGJGP 2._report as described above. RES will als o ~ hold an NRC/industry workshop with international participation in the third quarter of FY20 (spring of 2020) on the state of knowledge for the technical issues in concrete and containment degradation identified in the SRM on SECY 14-0016 and in the* GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that the workshop will need to address several concrete-related issues where related research is still active, RES will plan for a three-day workshop that may include breakout sessions for specificspecially items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made publ ic six months before the workshop. RES will document the results of the workshop in a ~lURie:G/CP report, which will include a summary of the workshop, presentations and workshop insights and conclusions. Task 1 will continue until the completion of the deliverables from thistt=te seoona activity, tentatively scheduled for late spring 2020. Commented [Fl14): Please add sub-sections for Sub-tasks 2A - 2E. This will Improve clarity and will better align t he RES staff will continue to develop and implement a long-term strategy for obtaining information response w ith the UNR. on materials degradation from decommissioned nuclear power plants, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, 2.A - 2.D as stipulated in the NRR UNR, page 4 . Under a long-term research project preceding this.the current request from NRR, RES has-pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ox-plant material harvesting. In tho first activity under Task 2, RES, with contractor support from Pacific Northwest National I Commented [fl1 SJ: Is this 2.A? Laboratory (PNNL), MS--developed an approach to prioritize technical issues best addressed by harvesting._The deliverable provisos provided criteria to assess the need for harvesting to address a particular technical issue. _The report then ~applied these criteria to assess four example technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. _This report also oovers-covered the background on the need for harvesting. and past harvesting efforts and experience._The purpose of this report is-was to serve as a tool for NRG staff tG-aWIY-to prioritize technical issues best addressed by harvesting. Tho fin,:il report for this research is expected to be publis_lJ!iQ. in August. 2017 ~ ' J reporting for this eflort is exreotea hy August 2017 l Commented [Fl16): Will the final PNNL report be shared with NRR or Is RES staff going to use the PNNL report and In the second preceding activity, tt=to NRG RES closely ooorainatoa collaborated with the provide added value as part of t his UNR? Department of Energy (DOE) and Electric Power Research Institute (EPRI) on ox pant materials har-,esting and, as mentioned abo¥e, hosted to host a workshop on ex-plant materials harvesting on March 7-8., 2017. _The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future* harvesting program planning._The workshop was well-attended by representatives from DOE, #1&-EPRI, the U.S. industry, and international research organizations. _Key insights from the workshop include£! the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The workshop summary report will be distri buted among meeting participants and is expected to be finalized by August 2017. As part of the fiAGm !=I nr:1,vitv under Task 2. RES will be [ Commented [Fl17): Is this 2.B7 pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and creating a 'sources of materials' database. Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for Commented [Fl18): Would this be an MS-Access SLR in the SRM on SECY-14-0016 may be best addressed by harvesting, as requested in UNR application? Under 2.A, the UNRtalks about "an Subtask 2.A. As an example, RES will develop a database which identifies and prioritizes the information tool". Would a database alone "foot t he bill"? concrete materials, components and opera ting conditions needed to address the significant issues. RES will develop a process to evaluate concrete samples harvested from Commented (CM19): "Information tool" is often another 1 term for database (so, it would fit the bill), while skirting decommissioned plants. and,....ReS will follow through with implementing the process as some database constraints. concrete materials become available from additional plants._ The scope of the haNesting strategy includes: alkali silica reaction (ASR)-affected structures; post-tensioned structures w ith emphasis on pre: stressed concrete containment vessels (PCCVs); corrosion of pre: slressing tendons, liners, reinforcing steel, and embedments; concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects); and concrete structures exposed to high r.adiation (typically bio-shield structures of certain PWR designs). IA additioA, fer irradialioA of.tests oA soAsrete materials, RES will fos1:is oA 1/\D of staiAloss steel.

 '"Ii it'---l&A-ac:'*esi::n,d IA U~JR ~JP~~                                                                Commented [Fl2 0]: If t here is overlap w it h o ther UNRs we need to be more specific to assure that there is no Based on information gleaned from ,discussions .gn the potential for haNesting and testing of               duplication in effort. Also, this should be mentioned in the memo.

concrete from decommissioned reactors, RES will provide a database to NRR on the possibilities for this activity and prioritize testing in a technical letter report (TLR). As an Commented [FI2 1]: With w hom? example, the TLR will document the process to evaluate the concrete samples from ffiJClear Formatted: Highl ight power plants ~ ex plaAt saFAplos l r o m - ~and its-- their suitability) that would !>&-appropriate canoolatos for harvesting-will--ao--OGGl;rnented in the Formatted: Highl ight letter report to MRR. Concurrently, RES will pursue domestic and international partnerships for (commented [Fl22): Please clarif y. cooperative cost sharing on the retrieval and testing of concrete samples. RES will provide the database c' "' 1 for NRR review and "' II summarize the priority listing in a TLRletler report. A separate TLRlelter report will be submitted to NRR on the process for harvesting and testing of concrete samples from decommissioned plants Commented [Fl23]: Please combine this wit h the previous paragrap~. Are we ta lking about two or three In addition to irradiation effects on concrete materials. RES will continue research on IAD of TLRs? stainless steel. (ifhis is also addressed in UNR NRR 2017-001') Under Task 2 of this UNR. Commented [Fl24 ]: If t here is overlap w it h o ther UNRs RES will seek potential sources of reactor internals that may become available for haNesting. to we need to be more specific to assure that there is no evaluate their utility to advance research being conducted under NRR-201-001. duplication in effort . Also, this should be ment ioned in the memo. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool', which identifies and Commented [Fl25]: Please see my comment on t his on prior itizes the materials , components, and environmental cond itions that should be pursued the previous page. for haNesting. The intent is for this information tool to be a living document that can be updated to reflect the latest operating experience and research. so that users may .r understand which data needs may be best addressed by haNesting. [ Commented [Fl26]: Please clarif y. §_uQ.tas1$..1_.!2_. In parallel w ith the information tool activity, RES will develop an effective process to evaluate the applicability of materials available for haNesling, as requested in Subtask 2 .8. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from the plant to make an informed decision on harvesting._ In many cases, this information may not exist, or i!._may be challenging to find in ttl&-plant records. _RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to infor m which harvesting opportunities should be pursued. A TLRteshnisal letter report documenting the information tool with prior itized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C and 2.D. Implementation of the evaluation process developed in Subtask 2.Bc will be pursued in Subtasks 2.C 0 and 2.D~ as requested in Ihle UNR. RES will remain in c lose contact w ith NRR on the latest developments as this process is implemented. The evaluationdevelepment process will identify confirmatory needs that the use of harvested samples can effectively address, will consider decommissioned plants in the U.S. plaRts-as-well as desemmissiened plants and abroad, and will leverage to the extent possible domestic and international cooperative research opportunities, as stipulated in Subtask 2.E. Through their national and international contacts, 11:te-RES staff will maintain alertness for harvesting Commented [CM 27]: How Is Subtask 2.E. distinct from Task 3? l opportunities !fl-relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the Misreseft information tool. Task 3 RES staff will continue to develop domestic and international partnerships to share expertise, capabilities and resources related to aging management research for long-term operation. These exchanges are critical for the confirmatory review of 11=\&-industry research er researsh that the industry usegs to justify the adequ acy of their aging management programs (AMPs), as Commented [Fl28): Is this wording correct? well as for the MRC independent confirmatory research. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI Long-term Operation (LTO) programs support most of the Commented [CM29]: The resultant wording looks OK. l domestic research to support aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of long-term operations. RES staff ha¥&-has frequent technical interchange meetings with DOE and EPRI staff, which have concentrated on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NDE). Commented [CM30]: What has concentrated on these 1 topics - meetings, OOE & EPRI staff, ...7 _J RES will continue to nurture The follewin!J para!Jraphs illustrate a few of the emerging domestic and international partnerships~ and w i l l ~ continue to develop those partnerships, ether exislin!J partnerships net included here, as well as other suitable opportunities that may emerge to address the aging degradation issues. RES 1§.A.Participant in several multi-national cooperative research programs. including the Halden Research Program and many others. For example. Commented [CM31]: As suggested, these examples

1. The RES Office Director signed in 2015 a multilateral 4-year memorandum of could be om itted.

J understanding (MOU) for the International Forum on Reactor Aging Management (IFRAM). IFRAM is envisioned to enable appropriate exchange of information among those parties and organizations around the world that are presently, or are planning on addressing issues of NPP SSC aging management. IFRAM is a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research, regulation, education and training as well as nonprofit research institutes having academic and industrial links. Four objectives support this purpose: cooperating to achieve common objectives, sharing information, identifying joint research or demonstration projects that can be pursued under separate agreements, and identifying and promoting best practices.

2. In relation to concrete irradiation, NRG is exploring opportunities to harvest irradiated concrete from decommissioned nuclear power plants worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the joint Halden Research Program proposing research on irradiation effects on steel-concrete bond, and on creep effects on irrad iation damage. RES is working to finalize a bilateral agreement with the French lnstitut de Radioprotection et de Surete Nucleaire (IRSN), for exchange of technical information on the effects of ASR on the performance of nuclear concrete.

IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES has an ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete and will continue participating under the international Organization for Economic Cooperation and Development (OECD) and Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Installations OECD/NEA/CSNI to develop modeling expertise for ASR effected concrete structures. Commented [Fl32): In my opinion, this Is too much detail for a UNR response*. Let's discuss. Through their national and international contacts, and through Geodes and S§tandards developing activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRG in support of generic or plant-specific issues. RES will provide \Q_ NRR management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided to NRR in a timely manner; the effort will continue until the closure of this UNR. Commented [CM33]: This sentence could be omitted. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during the interface meetings between RES/DE, NRR/DMLR and NRR/DE. _A quarterly report (or slides) for presentation at afly-Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task 4 RES staff will document and compile results from Tasks 1, 2, and 3 on the status of research resu lts in support of the Commission's direction to the staff. RES will prepare a document annually summarizing the products from the three tasks above and discussl!J.g the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. The annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year. beginning in the first quarter of calendar year 2018. discussing the research activities supporting SLR during the previous year. Task 5 RES staff will seffiifll:le-te-provide confirmatory analyses and expert technical assistance with the review of re*1iewingthe technical documents to be fersubmitted with SLRsubsequent license F6Aewal applications, t>, """Pf if, w f-i-dl J building upon the extensive work done ~ L.1 _r UNR NRR 2014-001. RES will support tighter SLR application review schedules as well as the Commented [Fl34]: As discussed work under UNR 2014-review of plant- specific gap analyses expected with the first applications. Process optimization 001 ls essentially complete, so I suggest deleting this. has resulted in the proposed review time for SLR applications (SLRAs) to be reduced te-1 FAGAtR&-from the 22 months allowed for LRAs to 18 months. Thus the expected work may be more intensive. In addition, t+he initial SLRAs are expected to require the review of plant-specific gap analyses, especially before critical documents, such as MRP-227 Rev 2 (upon which AMP XI.M16A for PWR vessel internals is based), have been finalized and approved by NRC. In the absence of an acceptable generic methodology that considers an operating period of 80 years, the gap analysis is used to ensure that aging management for ~ specified SSC is appropriate for 80 years of operation. RES will assist with the technical evaluation ofevaluate SLR- related licensing oroducts and reports (e.g., topical reports, SLR applications, LERs) that may be submitted~ to NRC in support of emerging generic or plant-specific issues. Representative missellaneolJs examples include issues such as baffle-former bolt degradation, other concerns related to vessel internals, carbon segregation in vessels, Of-and concrete degradation. RES subject matter experts (SMEs)i as requested by NRR/DMLR, will participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. Based on the latest assessment of projected needs in this areaTl=le RES staff has eeen invel'leS in sisslelssions with yolelr staff on yolelr nooss, RES proposes that the estimate of c::JFTE/year for this taskmay neos to be adjustedinsroasos or sosreasos once the scope of ,. work and the required level of RES staff inivolvement is better understood after the first SLR appl ication is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, andi thj§.o effort shall&RGlM continue until the closure of this UNR.

                                                      -10

Deliverables and Schedules RES staff will participate in w.- 1ay-fll0rltt,ly 3f quarterly meetings with NRR staff and Commented [Fl35]: Quarterly counterpart meetings managers to discuss the latest developments and information from industry and NRC- should be sufficient. Obviously the staff will Interact more supported research, particularly insights tlhat may impact regulatory decisions o r aging frequently, as needed. manage ment guidance. Staff-level interactions are expected to be frequent. as needed RES staff agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dales. RES staff will closely coord inate w ith NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. Deliverables and schedule for UNR NRR-2017-006 are shown in the following table. Commented [Fl36): It will be difficult to edit this table if not in native Word format. Also I could not provide line item Schedule and Resources for the Various Tasks specific comments because this table was probably copies Period of Performance (FY18-21 ) as " picture" from E<eel. I suggest using a standard Word ask N umb Task Description Comolelion Date FT E Contract $ table. iEllJ for FY18 and -Developing information tool may require more FTE Hold NRC/industry workshops (2018, FY21 (reduced with and/or contractor suppon. Does PN NL have tool that FY21 !Ifil)year 2020) and prepare NUREG/CP and DOE support) could be modified for t his purpose? If so, funds should be 1 summarv reoorts on four SRM tooics added for 2.A. Total (Task 1) ITfil [ZiiiZ[I -Please add estimated travel costs for participating In domestic and international meet ings under Task 3. strategy for haMJsting materials/components 2 -We may need co ntractors to assist us with Task 5, so from decommissioned olsnts please add some funds for contractor support related to 2.A Develop a database FY18 1/ h \ I work on Task 5. Develop a process to evaluate the 2.8 m:r, 1/hvl comoonents from olants FY18 Formatted: Indent: Left: O" Use the process developed in Item B to 2.C evaluate the suitability of components from lolants FY1 9 m;n Continue to implement the process developed in item B as components Ongoing (FY20-2.0 become available from additional olants FY21\ m::n,ear~ Pursue partnerships for cooperative cost-sharing on retrieval and testing of ex-plant Ongoing (FY18-2.E harvested material FY21 ) part of Task 3 below Total (Task 2) IZhlZJ Wili5II Participate in relevant Domestic and [ : ](total*fOf -4 .. International activities (e.g., IFRAM, DOE FY18-FY21 IZE]year ~ years IFRAM dues) 3 LWRS EPRI LTO codes & standards) Prepare annual report documenting and compiling results from three preceding FY18-FY21 l!Byear Kfilfilj 4 tasks Provide expert technical assistance with reviewing documents for subsequent FY18-FY21 (lfilyearlifil[] license renewal (e.g. SLRAs, topical 5 reoorts\ Total (all 5 t.asks over 4 years) I /hi/ I 1/h H'i l Schedule and Resources for the Various Tasks [ Formatted Table Period of Performance FY 18-21

                                                                - 11

Task Task Description Completion FTE Contract S Number Date

                               .1                             Hold NRC/industry

_(b)(~) wpr!<shops fest, 2018, 2020) (b) 5) and prepare NUREG/CP and ............EY..21 .... (b)(5) summarVfeports on four SRM tooics (b) 5) j b)(5)

                      **** z

• mi\.1eloo a stratenv for harveslina materials/ cm""nents from decommissioned olants (b) 5) 2.A Develoo a database (b) 5)

                  **** 2:B: *** Develop process to                      a
                                                       ...... evaluate..0I,m.1..oomoonenis ******

2.C. Use the process from 2.B. to (b) 5) evaluate the suit.a.bility of .....

                                                        ** oranrcomoonents f..9                                 Continue to implement the process from 2.B. as 5)

~~~ 5)

                                                        ......compooer:itS**beeome********************
                                                            .ava1iabJe...from.. actditionaf*******

olants 2.E. Pursue partnerships for cooperative cost-sharing on retrieval and testing of ex-olant materials (b) 5) r::=:::::;::::::=T:;:;=:~:-;::";-:-:::;:::::::;---=r='""= = =4=~ +------..J--

                                                                                                           .IotaUTask..2.l                                                             I       I t --L-*=***=****F*l ***;:;;:;
                                                                                                                                                                                                                    ****"

• 7 *************************** *********** *********************** (~)(5)

                  *************~ ******                 . Parlicfoate in relevant                                                                 ~

~g~ ~~ 1 domesticandmtematron at * *** FYf8:2f  : : . ear

                                                        ... acti'lmes i                              Develop documentation eva luating significant technical t)b) 5)5) """'" --- .                                          issues germane to the review oL .
                                                            *slii:aooiicationsptepaFe-
                                                                                                            .... FYra:2-r *****.*.***.*.*.*.*.*.*.1 .*.*.*.*.*.*.*.*.........'..'.y. ear  !

annuafreport documenting F&SU!ls-fr-Offi-Tosks-4-3 Develop documentation evaluating signi ficant technical issues germane to the review of (b) 5) (b) 5) +************************..**..****..**..* *1~~~;;P;~c;~~i~~~:!~~ ******* r:vrn~2f * ***:~ with reviewing documents for StR-rlooll;JE!jM-tfil)isal i:69flFl6 (b) 5)

                                                                                                                  -12

Note to requester: Attachment is immedately following this email. Portions of this record are redacted under FOIA From: Smith Jean Exemption B5, Deliberative To: Hiser Matthew Process Privilege. Subject : (External_Sender] RE: (External] RE: Ex-plant Materials Harvesting Workshop Presentations Date: Friday, March 3, 2017 9:02:12 AM Attachments: Lessons Learned from Zorita Crvstal River JSmith .DdJ Mat t, Please note the minor change to the title. I've included some information on the cable harvesting from Crystal River. Thanks, Jean From: Hiser, Mat t hew [1] Sent: Wednesday, M arch 1, 2017 8:45 AM To: Bernhoft, Sherry <sbernhoft@epri.com>; Dyle, Robin <rdyle@epri.com>; Smith, Jean

<jmsmith@epri.com>; Ah luwalia, Kawaljit <kahluwa l@epri .com>; 'Richard Reister (Richard.Reister@nuclea r.energy.gov) ' <Richard .Reister@nuclear.energy.gov>; 'leonardk@ornl.gov'
<leonard k@ornl.gov>; 'Rosseel, Thomas M.'<rosseeltm@orn l.gov>; 'William F Zipp (Ge neration - 4)'
<william.f.zipp@dom.com>; '*Gerard P. Van Noordennen'
<gpvannoordennen@energysolutions.com>; 'Ramu ha Iii, Pradeep ( Pradeep. Ramuhalli@pn n I.gov)'
<Pradeep.Ramuha ll i@pn nl.gov>; 'da niel.tello@canada.ca' <daniel.tello@canada.ca>;
'Uwe.Jendrich@grs.de' <Uwe .Jendrich@grs.de>; 'rachid .chaouadi@sckcen.be'
<rach id .chaouad i@sckcen.be >; 'a ra it@criepi.den ken .or.j p' < ara it@criepi.den ken.or.jp>;
'al panfa@westi nghouse.com ' <a lpanfa@westinghouse.com>; Jackson, John Howard
<john.jackson@ inl.gov>

Cc: Tregoning, Robert <Robert.Tregoning@ nrc.gov>; Purtscher, Pat rick <Patrick.Purtscher@nrc.gov>

Subject:

[External] RE: Ex-plan t Materials Harvesting Workshop Present at ions

Dear Presenters:

Thank you for sendi ng presentation t it les . I have all but a couple at t his point and have attached t he updated agenda. I know many of you are working on finalizing your slides for the wor kshop (I already have 2 submitted as of today !). p lease provide slides by Friday if at all possible. It will be very cha llenging to load presentations onto t he comp uter via thumb drive t he day of the workshop due to NRC comput er security restrict ions, so sending t hem in advance is greatly prefer red. Again, best options for sending are either emai l or upload to Google Drive: ,https://drjve google com/drive/folders/0BSDWMLchSYSXcnpZZOJOS0SSOUU?usp-sharing. I am looking forward to a productive workshop next week and appreciate your participation . Please let me know if you have any q uestions or suggestions for the workshop. Thanks! Matt From: Hiser, Matthew Sent: Thursday, February 23, 2017 9:07 AM To: Bernhoft, Sherry (sbernhoft@eprj com) <sbernhoft@epri,com>; Dyle, Robin <rdyle@epri com>; Jean Sm ith (jmsmjth@epri.com) <jmsm jth@epr j,com>; Ahluwalia, Kawalj it <kahluwal@epri.com>; Richard Reister (Richard Rejster@nudear energy gov) <Richard Re jster@nudear energy gov>;

'leonardk@orn l.gov' <leonardk@ornl gov>; 'Rosseel, Thomas M.' <rosseeltm@ornl gov>; 'William F Zipp (Generation - 4)' <w jlljam,f zipp@dom,com>; 'Gerard P. Van Noordennen'

<gpyannoordennen@energysolutions.com>; Ra muhaIIi, Pradeep ( Pradeep. Ramu halli@pnnl.gov) <Pradeep.Ramuha ll i@pn nl.gov>; "daniel.tello@canada.ca* <dan jel tello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe.Jendrjch@grs.de>; 'rachid.chaouadi@sckcen.be' <each id. chaouad i@sckcen.be >; *ara it@criepi .den ken .or.j p' <ara it@crie pi. den ken .or. ip>; 'alpa nfa@westinghouse.com ' <alpanfa@westjnghouse.com>; Jackson, John Howard <iohn.iacksoo@iol.gov>: desire ndomba@canada.ca Cc: Tregoning, Robert <Robert.Tregon ing@nrc.gov>; Pu rtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

RE: Ex-plant Materials Harvesting Workshop Presentations

Dear Presenters:

Friendly reminders:

• Please provide presentation title by February 28.
• Please send me your slides (either via ema il or upload to Google Drive:

https* //drive google com/drive/folders/0BSDWM LchSYSXcnpZZOJOS0SSOUU 7 usp-sha ring) by March 3. I have attached the workshop agenda to t his emai l. Please let me know if you have any questions or corrections. Thanks! Matt From: Hiser, Matthew Sent: Wednesday, February 15, 2017 10:47 AM To: Bernhoft, Sherry (sbernhoft@epri.com) <sbern hoft@epri.com>; Dyle, Robin <rdyle@epri com>; Jean Sm ith /imsmith@epri,com) <jmsmith@epri.com>; Ahluwalia, Kawalj it <kahluwal@eori.com>; Richard Reister (Richard Reister@nudear.energy gov) <Richard Rejster@nuclear.energy gov>; 'leonardk@orn l.gov' <leonardk@ornl gov>: 'Rosseel, Thomas M.' <rosseeltm@ornl gov>; 'William F Zipp (Generation - 4)' <william.f.zipp@dom .com>; 'Gerard P.. Van Noordennen' <gpyannoordennen@energysolutions com>; Ramuhalli, Pradeep (Pradeep Ramuhalli@pnnl gov) <Pradeep.Ramuha lli@pnnl gov>; 'daniel.tello@canada.ca' <dan jeLtello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe Jendrjch@grs de>; 'rachid.chaouadi@sckcen.be' <rachid chaouadi@sckcen be>; arait@criepi.denken.or.j p' <arait@criepi denken or jp>; 0 'alpanfa@westinghouse.com ' <alpanfa@westinghouse.com> Cc: Tregoning, Robert <Robert.Tregon jng@nrc.gov>: Purtscher, Patrick <Patrick.Purtscher@nrc gov>

Subject:

Ex-pla nt Materials Harvesting Workshop Presentations

Dear Harvesting Workshop Presenters:

If you are receiving th is emai l, then I have you down on the agenda to present at the upcoming Ex-plant Materials Harvesting Workshop on March 7-8. I have attached the workshop introduction sl ides that have been shared w ith most, if not al l, of you. These slides cover meeting logistics, motivation, approach, expected outcome, and session expectations. We are hoping these slides provide a common vision for the workshop that will allow for a focused, prod uctive discussion. Please take a look at these slides and try to tailor your presentation to the focus and length of the respective session. There are two actions I request from presenters:

1. 1have attached t he confirmed list of spea kers in an Excel document. Please take a look at this list to confirm you are presenting in the session you expected and if I have made any mistakes in the list of speakers. If you have not already done so, please provide me w ith a presentation title.

2. Please send me your sl ides (either via ema il or upload to Google Drive :

https://drive.google.com/drive/folders/0BSDWMLchSYSXcnpZZ0JOS0SSOUU?usp-sharing\ by the end of February if possib le. Than k you for your participation in t he workshop. We are looking forward to t he discussion and engagement and appreciate your contribution to a productive and intere sting meeting ! Thanks ! Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Offi ce of Nuclear Regulat ory Re search Division of Engineeri ng I Corrosion and Meta llurgy Branch Phone: 301 -415-2454 I Office: TWFN 10062 Matt hew .Hiser@nrc.gov

• • • This email message is for the sole use of the intended recipient(s) and may contain info1mation that is confidential, privileged or exempt from disclosure under applicable law.

Unless otherwise expressed in this message by the sender or except as may be allowed by separate written agreement between EPRI and recipient or recipient's employer, any review, use, distribution or disclosure by others of this message is prohibited and this message is not intended to be an electronic signature, instrument or anything that may form a legally binding agreement with EPRI. If you are not the intended recipient, please contact the sender by reply email and permanently delete all copies of this message. Please be advised that the message and its contents may be disclosed, accessed and reviewed by the sender's email system administrator and/or provider. ***

Epf21 ELECTRIC POWER RESEARCH INSTITUTE Lessons Learned: Harvesting of Zorita and Crystal River Materials Jean Smith, PhD PE EPRI Primary Systems Corrosion Research Principal Technical Leader Ex-Plant Materials Harvesting Workshop March 7-8, 2017 Washington, D.C.

                                          ©2017 Electric Power Research Institute, Inc. All rights reserved.

EPRI Harvesting Projects Zorita Internals Research Project Crystal River Cable Harvesting Zorita Biological Shield Concrete Harvesting Jose Cabrera NPP "Zorita" Crystal River Unit 3 Westinghouse 2-loop design B&W Design 1968- 2006 (--26 EFPY) 1977-2009 2

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project Timeline t Harvesting projects take time

• Extensive effort on the front end of the project
• Testing represents a minority portion of the project timing Task 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 Project Inception ~

Feasibility Study Project Planning Cutting Plans Equipment Design & Manufacturing On-site Preparations Material Extraction I On-site Logistics Shipping Radiation and Temperature Analyses Material Inspection, Inventory, Documentation I Materials Testing I Reporting 3

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project P'loleB Plate [

• Baff le plate and core barrel weld materials 000000000 00 00 *
• Type 304 stainless steel
• Doses ranging from 1-2 dpa (welds) to N50 dpa Pieces 12-25" long x 2" wide x 1" thick 0 0 0 0 0 0 0 0 0 0 0 0 0 Weld at Core Barrel 95'-99° Wtld " \ I I

Weldat 275'-279' \ Core Barr I I I I I I 0 0 0 0 0 10 0 0 0 0 I 4

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project Material Retrieval Challenges ~~

• Decommissioning activities were top priority
• Harvesting tasks could not impact critical path
• Highly-active materials required special handling & equipment
• On-site coordinator was essential and valuable 5

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project On-Site Challenges

• Newly designed equipment required extensive modeling to ensure clearances throughout containment for all maneuvers
• Three-dimensional simulations used to map all areas and activities 6

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project Shipping Issues

• Highly-active materials required fuel-type shipping container
• Changes to shipping dates needed to be accommodated
• Approvals required from numerous authorities in multiple countries 1J Jlil:11;1!;1 ,1,b::b i',\ilrini f r:rfil:. ~~111 7

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project Shipping Issues Zorita RI materials (and other materials such as flux thimble tubes) have been classified as WASTE 8

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Internals Research Project The Bright Side

• Excellent cooperation between many international organizations
• Contractors
• Engineering firms
• Regulators
• Zorita reactor internals currently included in multiple projects
• EPRI MRP, BWRVIP, PSCR
• U.S. NRC 9

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ELECTRIC POWER RESEARCH INSTITUTE

Zorita Biological Shield Concrete Harvesting Large blocks of the Zorita concrete biological shielding have been removed from the reactor cavity

     - Core samples at variable elevations from the beltline (maximum neutron flux) were extracted from the blocks
     - Samples have a range of neutron exposure                                                                                  fl to) 110
     - Maximum fluence expected to be 1OE19 n/cm2 N

(Ll01140 (E > 1 MeV) ClCOl 140 Core samples broke apart during extraction drilling

                                                                                                                       ~~~
     - Affects how the mechanical properties will be                                                            ,**
                                                                                                                    ** V Cl     140 characterized Samples are contaminated and must be stored and tested appropriately
     - ENRESA will be performing characterization of the radioactive samples.

Procedure for extracting the cores was successful and may be applied in the future to other plants undergoing decommissioning 10

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ELECTRIC POWER RESEARCH INSTITUTE

Crystal River Cable Harvesting Lessons Learned Material Concerns Cable availability is not unlimited Systems must be "retired" before cables can be harvested Widespread, fixed contamination (>2000 counts) of desired cables in containment resulted in them not being used for research Cable jackets and fillers had asbestos

    - Increased harvesting/handling cost
    - Usability concerns of labs had to be addressed 11
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ELECTRIC POWER RESEARCH INSTITUTE

Crystal River Cable Harvesting Lessons Learned [ Utility and Site Support Site engineers have "local" knowledge and access to information

  -  Cable availability
  -  Service conditions (temperature and radiation levels)
  -  Design data
  -  Manufacturer's test reports Site staff support required
  - Work package planning
  - Craft support for harvesting cables
  - Rad-worker and Operations support for craft Interfacing with a site from a distance is inefficient
  - No control over priorities, availability of site support
  - Communications with hired support sometimes are miscommunications
  - Sometimes you just need to see things for yourself 12
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ELECTRIC POWER RESEARCH INSTITUTE

Crystal River Cable Harvesting Lessons Learned Harvesting is Expensive!

  -rb)(4)                              I Project Management Time (EPRI)
     - Interface with site engineering and research partners to evaluate and select cables to be harvested Site visit to walkdown cables Distributing cables to labs Harvesting cost
     - Utility picked up cost initially
     - Engineers, planners Lead site engineer left in middle of project Engineering support over 6 months (not full-time, but close)

Planning, maintenance craft, other support 13

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Together... Shaping the Future of Electricity 14

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Note to requester: Portions of this record are redacted under FO IA Exemption B5, Response to User Need Request NRR-2017-006 Deliberative Process Research Assistance on Potential Significant Technical Issues during Privilege. the Subsequent Period of Extended Operation Task 1: Hold NRC/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues RES staff will continue to hold and participate in NRC/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two activities (such as, a workshop, conference, symposium, or meeting) with domestic and international participation, one tentatively planned for spring 2019 on mechanical components and one tentatively planned for summer 2020 on concrete and cables-related issues. In establishing the exact date for these meetings, consideration will be given to the availability of new information on the relevant technical topics. These meetings will address:

• the state of knowledge on the technical issues requested in the SRM on SECY 14-0016,
• ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR report, and
• any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for international plants).

RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before each workshop. RES will document the information from each of these activities in a NU REG report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting. Materials Issues for Mechanical Components -As part of the requested workshop/ conference/ symposium/ meeting on materials issues for mechanical components, tentatively planned for spring 2019, the NRC staff will coordinate a session, or sessions, concerning reactor vessel embrittlement and the degradation of reactor internals due to irradiation during the SLR period. The staff will seek participation from the NRC staff, the regulated domestic industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. 1

Concrete, Containment and Electrical Cable Issues - RES will also hold an NRC/industry workshop with domestic and international participation (tentatively planned for summer 2020) on the state of knowledge for the technical issues in concrete, containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific technical topics and items of interest. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late summer 2020. Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs). as well as from ex-plant components harvested from operating plants RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, described in paragraphs 2.A-2.D of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting. In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The criteria for prioritizing harvesting data needs will be described in the anticipated TLR, expected by the end of 2017 "Criteria and Planning Guidance for ExPlant Harvesting to Support Subsequent License Renewal." The TLR will provide criteria to assess the need for harvesting to address a particular technical issue and then will apply these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report will also cover the background on the need for harvesting, and past harvesting efforts and experience. In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was designed to discuss past harvesting experience and lessons learned and seek leveraging and cooperation with other interested research organizations. Insights from the workshop are integrated into the database and harvesting planning efforts. The database will be developed consistent with the prioritization criteria from PNNL to identify which sources to focus on. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The 2

workshop summary report will be distributed among meeting participants when finalized. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2.8 . Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may be best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. The work in this task includes collecting and inputting information on materials needed and the sources of materials expected to be available. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the lat,est operating experience and research, so that users may understand which data needs can be best addressed by harvesting. The purpose of the database is to have a systematic approach to harvesting materials and to prioritize limited resources to provide best value for harvesting. The database is not an end unto itself, but the means to pursue high priority harvesting for the best technical value. As a specific example, RES will develop a process to evaluate harvested concrete samples, and will follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)- affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels (PCCVs ); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001. RES will continue to evaluate the SLR-significant issue of cable aging using harvested cables. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011-014 and NRR-2016-012 to include more cable 3

types (insulation types and medium voltage level cables) and to evaluate the aging effects on power cables at different voltage levels. Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.D. Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.D., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.D). RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task

3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement.

Information on these opportunities will be retained in the information tool/database. Task 3: Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of industry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research. RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships will build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as implementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs. RES staff have frequent technical exchange meetings with 4

DOE and EPRI staff. These meetings have focused on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NOE). RES is a participant in several multi-national cooperative research programs, including the International Forum on Reactor Aging Management (IFRAM), and many others. The RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. IFRAM is envisioned to be a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research , regulation , education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. The small effort and contract funding to operate the IFRAM program will be funded by this User Need Request. Other international collaborations pursued by RES are also expected to benefit this work, although resources to support those initiatives are tracked separately. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the OECD Halden Reactor Project (HRP) proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These results will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete . IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NEA/CSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will.evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and_international organizations.as a result.of this . 9_9_\i.v.iJY.-.. Il:i.~~~ products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE, NRR/DMLR and NRR(Q!;.,.A.r~.P..9.CT.l9.L~[i_g~~).f9LP.f.~.!?.~f!t9Ji_9.f!_~t.~P.Pr9P.fi.~t~. Qir.~_9.\qr/.0~.P.~tY..Plrnf.\9.Li.r!t~.ct~f ~.... meetings will be provided 5 days before the meeting. 5

Task 4 : Develop docume ntation e valuating significant technical issues germane to the review of SLR applications This UNR (NRR-2017-006) serves as an "umbrella" under which associated SLR-focused technical UN Rs are coordinated. Table 1 below provides additional detail on these UN Rs, along with a summary of the level of effort and funding. Table 1 SLR-Related UNRs Associated with UNR NRR-2017-006 UNR# UNR Title Comments NRR-2017-001 Request for This UNR is based on previous UNR NRR-2012-008 and updates regulatory ML16300A303 Assistance to resea rch on void swelling and clarifies current projects and future projects that RES Response to Evaluate are being considered. NRR-2017-001 Irradiation- A third task was added to this UNR for RES to perform confirmatory ML17110A202 Assisted evaluation and support ASME code case on new EPRI IASCC crack growth rate Degradation of Rx curves. Vessel Internals Fundina: (b)(5 FY17:I "'"'"'=u*u=

                                                                                                                                           ,nn,n"""""'

I (b)(5) FY.18: I (b)(5) ,.,..,.,.,.... , and FY19: I I (b)(5) *****- (taj(p) b)(5) FTEs: FY17:r 7FYf$::r ,.andFY19:r::l .. ~}(?) NRR-2014-007 Reactor Pressure This UNR superseded UNR NRR:2001*001..and..incl.Y.~.~s 6fasks:(l) .............**.*.**********.*.****************** ( ML14126A818 Vessel Integrity Appendix H in process by NRR, NRO, and RES staff; rulerriakTi"igflmded.ir+ J~J 5) RES Response to Issues FY17 and team in place to finalize rulemaking effort, (2) updating the tech NRR-2014-007 bases for Appendix G, (3) examination and analysis of irradiated reactor ML14212A127 vessel material, (4) providing emergent technical assistance, (5) maintaining (package) database and documentation, and (6) performing/ documenting a tech evaluation on irradiation damage mechanisms and potential revisions to 10 CFR, part 50 App. G of RG 1.99 "Radiation Embrittlement of Reactor Vessel Materials" Rev 2. (b,)(5) (b )(5) Fundinn* NRR-2011-014 Assessment of (b )(5) ~+~~:-~Y1s*,1~~~~~J-1 }:~;~b- . 1~: :~=I NRR/DMLR's focus on this UNR is to assess and evaluate condiffon*mohitoting 1

                                                                                                                                                              ;J::.             :.~i~)t!):.                              (b) 5
                                                                                                                                                                                                                                    ':(

ML11307A205 Cable Condition methods on electrical cables subjected to accelerated aging RES Response to Monitoring under normal and accident conditions. NRR-201 1-014 Accelerated aging of the cable samples is expected to commence toward ML11335A169 Amendment to UNR the end of FY2017. (o Amendment to for Assessment of The amendment extends the cable testing period up to 80 years (up from 60 NRR-2011 -014 Electrical Cable ~~~~~n :t he previous UNR). b) 5) . . . (P)() (NRR-2016-012) .... ., .... I ,*.i.: ML16096A221 Condition Monitoring Prior F~ total ~ FY1Bt .L L !FYt9 r = : 7-P 12o r ... {b)i 5 FTEs: Prior FY total --t *** IFY.18,..- .c:JEY:19:* ** ....,.., fcy20*-t NRR-2012-004 Alkali-Silica The objective of this UNR is to deveToplechnical bases for regu1at6rf" ' :::::::::;;

• ML12109A324 Reaction (ASR) guidance for evaluating ASR-affected concrete structures, primarily focusing ** ****** ...

RES Response to Research on impact on the structural capacity under design basis loads through its NRR-2012-004 service life, including PEO, and its aging management. The research at ML12152A107 NIST includes obtaining data on highly instrumented concrete block specimens to monitor the progression of ASR and assess its impact on in-s itu mechanical properties, conducting destructive testing to assess structural impact including seismic response, evaluating numerical modeling methods, an~ ects for determining th~ d rate of ASR. . (b)(5) Funding:IYHs

• FY1 5 - ~Y16 *
• EYJ?,~1 * * * .......

(b)(5 FTE~::F'?14 ... -G FY .... ::: .......**.*.. FY:tz:~ - .. . . . . . ** *.... ~_. -... ,. . NRR-2015-007 Effects of The purpose of this UNR is to develop technical baseidOi'regu1at6fy,.,.._..,., :,:"'*"'****,.., ML15076A217 Irradiation on guidance to evaluate radiation effects on concrete structures close to RES Response to Concrete reactors. The focus of related regulatory research is to evaluate the impact NRR-2015-007 Structures on structural capacity under design basis loads for service life up to 80 years ML15229A100 and develop aging management strategy. The project includes reviewing EPRI and DOE reports by ANL (contract awarded in Jan 2016), harvesting the materials from the decommissioned (t )(5)

                                          ~~~~i~~~~e_;!gP i~*=J~~.;;~t'§:+                                   Evia..~                            *.-.*. :101rnr
                                                                                                                                                                                 ....... ................ ........ .............        (b)(5)

FTEs: FY16 .. EYF.::[):~Y.18.. ,. -...... ,.,, {b)(5r

                                                                                                                 ' .....................,.                                  ..                      .............................,......(p)(?)
                                                                                                                                                                                                                           . .... .(p)(t;J 6

RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to , a summary of products from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff. RES will prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Based on the latest assessment of projected needs in this area, RES proposes that the (b)(5) .. estirnateofE::]FTE/year for this task be adjusted once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. Task 5 (Optional): Provide expert assistance with reviewing SLR applications Under this optional task, NRR may call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses. Building upon the extensive work previously done under UNR NRR 2014-001 , RES staff will continue to be available to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. As an example, the staff will continue to be available to review operational equipment failures to assess the trend in critical risk-significant electrical equipment. There are concerns with aging effects (including cyclic aging) and design life of other electrical components, such as breakers and relays, which would need further evaluation to assess their continued service life by exploring other monitoring techniques not generally covered under surveillance tests. Such analyses could complement work in Task 2 , whereby critical electrical components can also be harvested and evaluated. These SLR-related studies are being pursued independently of this UNR, and the work is being tracked through existing communication between RES and NRR staff. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRG-supported research, as well as collaborative research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. 7

RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. The deliverables and schedules for UNR NRR-2017-006 are shown in Table 2. Table 2: Schedule and Resources 1 for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE Contract $ (b)(5) Number Date

                                                                                                                                                                                        *(b)(S) 1           Hold NRG/industry workshops (est.

• tfofFY18

____ ............ {b)(5f 12018, 2020) and prepare FY 21 ] year ********** andF¥21l NUREG/CP and summary reports on .. **************J , ,(~)(5) four SRM topics (b)(5) rr otal (Task 1) I L.......J

                                                                                                              .... - I

(~ I(?r ~ Develop a strategy for harvesting Ex-Plant materials/components (b)(5) 12.A. Develop an information FY 18 L-1 I

                                                                                                ........ :*::.:::::.::! ::::**-.:-.~          ......................................... I~2(~L ltool/database 12.B.       Develop a process to evaluate plant components FY 18       --=t*                                                                                                                    (b)(5) 12.C.       Use the process from 2.8. to
           ~valuate the suitability of plant       FY 19       r-7               ............. ........ ................... ........................,...,..,,                           (b)(5)

L-.J components 12.D. Continue to implement the process from 2.8 . as components become Ongoing (FY r=lvear . .. .......................................... '"'""-m=m.,,..., (b)(5)

           ~vailable from additional plants       ~0-                               I                                                                                                   (b)(5) 21) 12.E.       Pursue partnerships for cooperative cost-sharing on retrieval and testing Ongoing       Included in bf ex-plant materials                  (FY18- FY21) Task 3, below                                                                                                                    (b)(5)

Total {Task 2) I ******** :*i.f :.** '. ,.... ......................,. (b)(5) ____J 3 Participate in relevant domestic and _, I (b)(5) international activities (e.g., IFRAM, FY 18-21 3 vear ** **(total for4years (b)(5y*** IAEA, DOE LWRS, ,, ,. + IF.RAM. d u.e s). . . . ....... ... ........:(6)(5) , EPRI LTO, codes & standards) ~ Develop documentation evaluating significant technical issues germane FY 18-21 r=lvear - ....... ...........,,..........,........... ................................ (b)(5) Ito the review of SLR applications I (b)(5f 5 Provide technical assistance to NRR To be To be funded if (optional) for reviewing SLR applications. FY 18-21 unded if needed needed !Total (Tasks 1-4, over 4 y,ears) L::J--- .......... ..............******--***:I*.::::::**** .... ~ 1 Note that the resources associated with this UNR include RES/DE/SGSEB (Ifil[] FTE/yr over 4 years andHb)(5) ~ and RES/DE/CMS (balance). All other SLR-related work is covered by the UNRs shown in Table 1. 8

Pacific Northwest Note to requester: Portions of this record are redacted under FO IA NATIONAL LABORATORY Exemption 3, Federal statute 41 U.S.C. §253b(m)(1 ) to protect contractor proposal information that has not been set forth or Proudly Operated by Baneue Since 1965 incorporated by reference into the final contract. Tel: (509) 375-2763 Fax: (509) 375-6497 MSIN: K5-26 pr.idc-cp.ramuhall i@'pnnl .go, August 6, 2015 Michael Turner Contracting Officer U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Proposal for Agreement Number NRC-HQ-25-14-D-0001 , "Technical Assistance in Support of Agency Environmental Reactor Programs", Task Order No. NRC-HQ-60-15-T-0023 "Strategic Approach for Obtaining Material and Components Aging Information", under EWA No. 65559 Our cost proposal for the work statement for Pacific Northwest National Laboratory (PNNL) Project No. 66419, Task Order No. NRC-HQ-60-15-T-0023, "Strategic Approach for Obtaining Material and Components Aging Information", under EWA 65559, NRC Agreement Number NRC-HQ-25-14-D-0001 "Technical Assistance in Support of Agency Environmental Reactor Programs" is attached. The cost proposal covers the cost of the labor and expenses associated with the work statement included in your request for proposal (RFP) dated July 22, 2015. Critical to this effort is a scoping study (Task 1) that reviews relevant literature to identify and assess the needs with respect to SLR, based on which a gaps assessment and additional research to address key gaps (Optional Tasks 2-4) are defined. PNNL staff will use their technical knowledge and experience to propose additio ns, deletions, or deviations from the proposed research plan as research progresses, to address any emergent issues. The work plan for Tasks 2-4 is expected to evolve, depending on the findings from Task 1. Ms. Eva Eckert Hickey is the PNNL Program Manager for the EWA and Dr. Pradeep Ramuhalli is the Task Project Manager. This task proposal includes the cost proposal for Task No. NRC-HQ-60-15-T-0023 (attachment 1), the schedule of deliverables (attachment 2), a proposed staffing plan (attachment 3), and Conflict of Interest Information (attachment 4). Upon request from NRC, the professional qualifications for staff that have previously been submitted will be resubm itted. The proposed period of performance for this task order is September 1, 2015 - August 31, 2019. 902 Battelle Boulevard I P.O. Box 999 I Richland, WA 99352 I 1*B88-375-PNNL (7665) I inquiry@pnnl.gov I www.pnnl.gov

August 6, 2015 Page2 PNNL, to the best of its knowledge and belief, asserts that it has no current work, planned work, and where appropriate, past work for DOE and others (to m ean - organizations in the same and/or similar technical area as the present and/or ongoing NRC project scope of work); and PNNL hereby asserts that it .i s not aware of any same/similar technical work that would give rise to any potential OCOI as defined in the Atomic Energy Act of 1954, as amended, and in the NRC/DOE MOU. See Attachment 4 for disclosed projects. Consistent with DOE ' s full cost recovery policy, DOE co11ects, as part of its standard indirect cost rate, a Laboratory Directed Research and Development (LORD) cost levied on all monies received at the laboratory. The estimated amount of LORD costs is identified in the proposal cost estimate section. DOE !believes that LORD efforts provide opportunities in research that are instrumental in maintaining cutting edge science capabilities that benefit all of the customers at the laboratory. DOE will conclude that by approving and providing funds to DOE to perform the work under this proposal, you acknowled ge that such activities are beneficial to your organization and consistent with appropriations acts that provide fu nds to you. Please note that the LDRD costs do not represent a new charge. Rather, the new Congressional requirement is for DOE to separately identify this indirect cost element. If you have any questions, feel free to contact me at 509-375-2763. Sincerely,

~ -f ~

Dr. Pradeep Ramuhalli T ask Project Manager Applied Physics Group Pacific Northwest National Laboratory cc w/attach: Lori B isping, PNNL Eva Hickey, PNNL Matthew Hiser Amy Hull, NRC Tonya Keller, PNNL Katie Knobbs, PNNL Steve Schlahta, PNNL Steve Unwin, PNNL

ATTACHMENT 1 -COST PROPOSAL Date Proposal Sent: August 2015 PART 1: DOE Laboratory Cost and Technical Proposal for NRC Work Cover Sheet X INew IRevision No. Project

Title:

Strategic Approach for Obtaining Material and Components Aging Information DOE Contractor Account Number NRC Requisitioning Office: Office of Nuclear Regulatory Research NRC Agreement Number: NRC-HQ-25-14-D-0001 DOE Laboratory: Pacific Northwest National Laboratory NRC Agreement Modification Number: DOE Site Address: Richland, WA NRC Task Order Number: NRC-HQ-60-15-T-00,23 NRC Task Order Modification Number: E-MAIL TELEPHONE COGNIZANT PERSONNEL ADDRESS NUMBER NRC COR: NRC Common Cost Center Code Amy B. Hull am:i.hull@nrc.gov 301-251-7656 Other NRC Staff: NRC B&R Number: Matthew Hiser matthew.hiser@ nrc.gov 301-251-7601 NRC BOC DOE Project Manager: jeffre:i.d8:i@12nso.science.doe.gov 509-372-4629 Jeffrey W . Day Laboratory Project Manager: Pradeep Ramuhalli PERIOD OF PERFOR MANCE 12radee12.ramuhalli@12nnl.gov 509-375-2763 Principal lnvestigator(s): Estimated Start Date: Pradeep Ramuhalli 12radee12.ramuhalli@Qnnl.gov 509-375-2763 September 1, 2015 Katie Knobbs katie.knobbs@12nnl.gov 509-372-4560 Estimated End Date: August 31, 2019 PROPOSED COST BY FISCAL YEAR (b)(3):41 U.S.C. § 253b(m)(1) Signature - Approval Authority Date Approval Authority - Name, Email and Phone NOTE: OPTIONAL TASKS 2-4 ARE INCLUDED IN THIS COST PROPOSAL A1.1

1~--**- PART 2

• TOTAL PffC>>'OSED COST BREAK~

l

                                                                         ~T-0,,,.,-
                                                                         ~  l :I-T-I (b)(3):41 U.S.C. § 253b(m)(1 )

A1.2

PART 3: S PENDING PLAN NRC Agreement Number: INRC Agreement Modification Number NRC Task Order Number: INRC Task Order Modification Number I NRC-HO-25-1 4-0-0001 I NRC-HO-60-15-T-0023 Project

Title:

Strategic Approach for Obtaining Material and Components Aging Information (b)(3):41 U.S.C. § 253b(m)( 1) A1.3

Project

Title:

Strategic Approach for Obtaining Mat eria l and Compon ent Aging Information NRC Task Order Number: NRC-HQ-60-15-T-0023 (b)(3):41 U.S.C. § 253b(m)(1) Task 1 Scoping Study and techni cal lite rature review Task 2- Decision Making on Specific Confirmatory Research Option Needed to Address Gaps Task 3-Option Confirmatory Research Addressing Technical Gaps Task4 - Option Development of Independent Decision Making Tools Task 5 Project Management SUM ALL Options Only (highlighted in Blue) A1 .4

COST ELEMENT INFORMATION (b)(3):41 U.S.C. § 253b(m)(1) A1.5

(b)(3):41 U.S.C. § 253b(m)(1) A1.6

ATTACHMENT 2 NRC Agreement Task Order No.: NRC-HQ-60-15-T-0023 - Proposal Strateg ic Approach for Obtaining Material and Components Aging Information As requested in the Statement of Work for Task Order No. NRC-HQ-60-15-T-0023, the scope is provided below. STATEMENT OF WORK NRC Agreement Number NRC Agreement NRC Task Order Number (If NRC Task Order Modification Number Applicable) Modification Number (If Applicable) NRC-HQ-25-14-0 -0001 N/A NRC-HQ-60-15-T-0023 N/A Project Title Strategic Approach for Obtaining Material and Component Aging Information Job Code Number B&R Number DOE Laboratory Pacific Northwest National Laboratory (PNNL) NRC Requisitioning Office Nuclear Regulatory Research (RES) NRC Form 187, Contract Security and Classification Requirements D Involves Proprietary Information Applicable D Involves Sensitive Unclassified [8J Not Applicable ~ Non Fee-Recoverable Fee-Recoverable ( 11checked, complete all applicable sections below) Docket Number (If Fee-Recoverable/Applicable) Inspection Report Number (II Fee Recoverable/Applicable) Technical Assignment Control Number (If Fee- Technical Assignment Control Number Description (If Fee-Recoverable/Applicable) Recoverable/ Applicable)

1.0 BACKGROUND

Regulatory Context: The NRG has established a license renewal process that will allow nuclear power plants (NPP) to renew their licenses for an additional 20 years, via 10 CFR 54.31(d) stating that "a renewed license may be subsequently renewed." The biggest challenges for the NRC and the industry will be addressing the major technical issues for this second "subsequent" license renewal (SLR) A2.1

beyond 60 years. As summarized in SECY-14-0016, the N RC staff believe that the most significant technical issues challenging power reactor operation beyond 60 years are related to:

• Reactor pressure vessel (RPV) neutron embrittlement at high fluence
• Irradiation assisted degradation (IAD) of reactor internals and primary system components
• Concrete and containment degradation
• Electrical cable qualification and condition assessment.

Understanding the causes and control of degradation mechanisms forms the basis for developing aging management programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSC). The resolution to these issues should provide reasonable assurance of safe operation of the components in the scope of license renewal during the subsequent period of extended operation. Because of the cost and inefficiency of piecemeal sampling , there is a need for a strategic and systematic approach to sampling materials from SSC in decommissioning plants. The envisioned work addresses both passive and active components. In that sense, it addresses aging management of passive components under the license renewal rule, 10 CFR 54, as well as the maintenance of active components covered by the maintenance rule, 10CFRS0.65, as seen in Figure 1 below. U.. HC Safety Beyond 60 Years Quality Assurance Program (10 CFR Part 50 Appendix B) Ensures that the effects of aging will be 10 CFR 50.55a effectively managed Requirements [ throughoutthe period of extended operation ( Active Components J Passive Components Aging Management Effectiveness Figure 1 : Relationship between aging management of active and passive components (from NRR/RES presentation to ACRS, 2014) A2.2

In the past few years, four plants have ceased operation or announced that they will cease operation: Crystal River Unit 3 (PWR), Kewaunee (PWR), San Onofre Units 2 & 3 (PWR), and Vermont Yankee (BWR). These plants comprise a range of reactor types, containments, and SSCs important to safety. The primary objective of this project is to develop a long-range strategy for obtaining information from these plants as they go through decommissioning. The focus will be on timely acquisition of experiential real-worlld aging-degradation information that can significantly improve the agency's risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet. Technical Context: Creating a roadmap for obtaining information from designated NPPs as they go through decommissioning is complementary to ongoing NRC research in developing technical information to support evaluating SLR as well as data collection and testing of ex-plant materials. Material degradation has traditionally been managed reactively in response to events and operating experience, rather than proactively to prevent failures. For the NPPs currently entering their first license renewal period from 40-60 years, and submitting SLR applications, it is necessary to evaluate potential degradation mechanisms out to 80 years of operation. Evaluation of material properties in SSCs from actual decommissioned NPPs will provide a basis for comparison with results of laboratory tests and calculations to resolve the four issues listed above. The proactive management of materials degradation (PMMD) information tool was originally created at PNNL for RES (POC: Amy Hull) to give an expert opinion of the possible future degradation mechanisms on a subcomponent/material specific basis (PNNL-17779);. Combined with the LER database, the PMMD information tool allows one to not only react to past events, but to anticipate future issues. The original PMMD information tool was based on NUREG/CR-6923, "Proactive Materials Degradation Assessment (PMDA)," for the first license renewal period, so it is now appropriate to integrate information from the excel databases from the recently-published five volumes of NUREG/CR-7153, "Expanded Materials Degradation Assessment (EMDA)" for SLR. At this juncture, there is demonstrated industry interest in NPP long-term operation (LTO) and regulatory interest in SLR .. 2.0 OBJECTIVES Understanding and managing material and component degradation is a key need for the continued safe and reliable operation of NPPs, but has significant uncertainties. In many cases, the scientific basis for understanding and predicting long-term environmental degradation behavior of materials in NPPs is incomplete. A strategic approach to examination and testing of materials and components from decommissioned reactors can dramatically increase our knowledge-acquisition rate in this very important area. There are three inter-related objectives to this work: A2.3

(1) Develop a long-range strategy for obtaining information from decommissioned NPPs as well as providing the flexibility to get ex-plant components from operating plants as well. The focus will be on timely acquisition of experiential real-world aging-degradation information that can significantly improve the agency's risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet. (2) Construct a strategic plan and specifications for obtaining unique and significant materials aging degradation information from diverse sources (operating experience, other nuclear facilities, other long-lived industrial plants, other materials organizations such as ASM and NACE) that will inform the NRC's age-related regulatory oversight in the future. Implementation of this plan and specifications, in cooperation with industry and DOE partners can be accomplished over time, through individual research projects as the identified plants progress through their decommissioning process. This exploratory research is expected to provide fundamental insights on reactor materials degradation and information addressing potential technical issues or identified gaps to support anticipated future NRC needs. (3) Update the PMMD information tool to incorporate LTO/SLR-relevant information so that it can be better used to inform prioritization in the ex-plant material strategic plan. 3.0 SCOPE OF WORK There are a number of technical gaps that this project seeks to address. Most importantly, the current piecemeal approach can be replaced with a strategic plan that is more comprehensive, broader in scope, and more risk-informed. The strategic plan for inspections and/or testing developed in this project will be useful guidance for obtaining key measurements of degradation in a variety of areas. These measurements will be valuable on their own and will also be useful in basic research on the underlying mechanisms and modes of degradation, and for validation of modeling and simulation tools. Data and information developed from implementation of the strategic plan will also be useful in evaluating aging management and mitigation strategies proposed by the industry. Many sources of materials degradation information will be queried, including human repositories of knowledge both within NRC and within the industry. Both the PMDA and EMDA present information in terms of component or material degradation susceptibility and currently available knowledge for degradation nnitigation or prevention. A component with high degradation susceptibility/low knowledge would be the strongest candidate for proactive actions. It is necessary to be able to understand this before prioritizing ex-plant materials sampling available from a given retired NPP. Previously, under the auspices of NRC contracts (i.e., JCN N6029, N6907), PNNL used the large amount of information presented in the PMDA report to develop a web-based platform to facilitate analysis through interactive visualizations that offer intuitive ways to explore the information. PNNL shall explore the viability of adding materials degradation susceptibility data presented in the EMDA Report. Such an information tool (Figure 2 below) is expected to save considerable staff efforts to understand and apply the PMDA and EMDA insights to regulatory review of licensee A2.4

information. PNNL shall develop a web-based modified scalable reasoning system (SRS) for tracking, disposition, and resolution of critical issues, such as determining the appropriate SSC from which to acquire cast austenitic stainless steel (CASS) material of specific composition and radiation dose. EPRI LTO Decommissioning Reactors Plans Operat ing Information Tool for Prioritization of Experience High-Priority Data Needs Oooortunities NRC Data: SLRGDs, International Data Sources DOE LWRS EMDA, PMDA Figure 2: Pre-conceptual Architecture of prognostic tool to track and resolve critical technical issues for SLR As shown in Figure 2 above, the information tool was originally envisioned as integrating domestic and international operating experience and experimental information as well as information from the EPRI LTO, DOE Light Water Reactor Sustainability (LWRS) program, and NRG sources such as EMDA, PMDA, and SLR guidance documents (SLRGDs) and precursors. The international data sources that might provide effective data feed include the cable aging data and knowledge (CADAK, http://cadak.hrp.no/cadak.) project and the Component Operational Experience, Degradation and Ageing Programme (CODAP, http://www.oecd-nea.org/ jointproj/codap.html ), both sponsored by OECD/ NEA. The Atlas constructed by PNNL from the Program to Assess the Reliability of Emerging Non-destructive Technology (PARENT) and the Program to Inspect Nickel Alloy Components (PINC) Atlas is an international! database containing a vast array of SCC crack morphology and NOE information. PNNL shall investigate whether this is an appropriate framework to track issue resolution associated with SLR. This is a much broader objective than just developing a strategic roadmap for harvesting SSCs. The general tasks and their duration are described in Table 1. A2.5

Table 1: Task Description and Duration Task Task Title/Description Duration (Months) Task 1 Scoping Study and technical literature review 18 Task 2 Decision Making on Specific Confirmatory Research Needed to 6 Address Gaps (optional) Task 3 Confirmatory Research Addressing Technical Gaps (optional) 33 Task 4 Development of Independent Decision Making Tools (optional) 33 The conditional tasks shall be conducted, as detailed in Figure 3 below. A decision on further optional research outlined in Tasks 2, 3, and 4 will be made after completion of Task 1 depending on the outcome and recommendation from the conclusion of specific tasks. The overall nexus between the scoping study and other potential tasks is shown in Figure 3. The PNNL staff shall not restrict their activities solely to these descriptions and shall be flexible in using their technical knowledge and experience in proposing additions, deletions, or deviations from the prescribed requirements as research progresses. Task 1. Terminate Technical Task 2. Gap Further Literature Identification Research Review Yes Task 3. Recommend Research Need

I

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Task 4. :I

I Develop :I

Analysis Tools :

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Figure 3: Schematic of the Overall Research A2.6

4.0 SPECIFIC TASKS Task 1 is the scoping study. Tasks 2-4 are optional. NRG plans to revise the SOW for these tasks based on the outcome of Task 1. The time at which the tasks begin and end will be dependent on available information and NRC's ongoing evaluation of testing priorities. NRC staff does not require that PNNL necessarily perform the tasks be performed sequentially following the order in which they are listed. For the test matrix described in this section, nearly all subtasks will have to be tested in tandem with another subtask in order to complete the program within the requested period of performance. PNNL and the NRC CORs will continually review the testing plan during monthly status update teleconferences. PNNL shall, in the first stage of Task 1, develop a questionnaire and help the NRC staff conduct interviews with focus groups from various technical disciplines within NRC. PNNL shall, in the second stage of Task 1, assist the NRC staff conduct one or two public workshops. PNNL shall analyze and combine the results of the first two phases into a final strategic plan in the third stage. This strategic plan will provide a prioritization of strategic harvesting opportunities. PNNL shall help the NRC staff develop the ex-plant harvesting strategic plan in cooperation with industry and other federal agencies such as DOE as well as any international counterparts that may be interested in participation. In Tasks 2-4, PNNL may be assigned optional tasks to identify requirements to further elucidate the risk assessment of component degradation. Such research should also provide technical data and information, as necessary, to request the national codes and standards bodies (such as ASME, ASTM, or NACE) to re-examine requirements for structural materials for passive components in light water reactors (LWRs) and in assessing material degradation during service and its effect on design safety margin of components. The PNNL principal investigator (Pl) for this project shall attend ASME, ASTM, or NACE Code Committee meetings, as appropriate and as approved by the COR during the course of this research. The Pl shall provide adequate information to support an IAEA international cooperative research program (ICRP) on this subject to bring worldwide resources to address this research need. The specific tasks are as follows: (b)(3):41 U.S.C. § 253b(m)(1) A2.7

(b)(3):41 U.S.C. § 253b(m)(1) Task 1 - Literature Review and Assessment of Greatest Needs in Sampling of Ex-plant Materials NRC recently completed a research program to investigate material degradation after extended operation. To investigate agiing degradation mechanisms, aging degradation effects, and the relative susceptibility to degradation, PNNL shall perform a comparison of available information. PNNL shall conduct the Taslk 1 scoping study and provide all resources necessary to accomplish the subtasks and deliverables. Task 1 shall be performed in stages as shown in the Task-specific subsections below. The activities required for this task are: A2.8

Task 1.1 - Conduct Materials Aging Degradation Literature Review PNNL shall selectively review both domestic and international sources of technical information of generic nature with respect to anticipated material degradation in NPPs during LTO, extrapolating to 80 years of operation. The objective is to identify other issues not in PMDA/EMDA, such as related to active components or spent fuel storage systems, and to determine what is being done to address LTO issues. NRG will provide guidance on appropriate information to review. (b)(3):41 U.S.C. § 253b(m )(1) A2.9

(b)(3):41 U.S.C. § 253b(m)(1) Task 1.2 - Evaluate Availability of Ex-Plant Material and llnformation PNNL shall evaluate what relevant ex-plant material is projected to be available for potential harvesting. PNNL shall work with the NRC COR to develop a questionnaire and interview the cog nizant individuals at the plants who possess critical knowledge. (b)(3):41 U.S.C. § 253b(m)(1) Task 1.3 - Develop Questionnaire and Conduct Interviews with Prospective NRC Stakeholders PNNL shall develop a questionnaire and work with NRC staff to conduct interviews with focus groups from various technical disciplines within NRC. This would include the SLR Expert Panels for a sample of different aging management programs (AMPs) as well as other NRC technical advisory groups. PNNL shall have a comprehensive approach to all the possible stakeholders interested in harvesting materials from decommissioned plants. The objective of this initial scoping study is to assess interest in issues concerning both passive and active component degradation. The questionnaire will address, as a minimum, (1) the perceived A2. 10

needs for ex-plant materials, (2) the perceived utility of the existing information tool and how and where this prognostic tool should be maintained (NRC, contractor, cloud). During the early brainstorming and scoping study, PNNL shall also consider degradation of SSC materials associated with extended long-term storage of used fuel. (b)(3):41 U.S.C. § 253b(m)( 1) Task 1.4 - Develop Questionnaire and Conduct Interviews with Prospective External Stakeholders Based on interactions with NRC staff in Task 1.3 above, PNNL shall propose a prelim inary strategic approach to sampling representative ex-plant materials during one or two presentations at public workshops to further refine the concept of what would be needed in a useful interrogatory tool linking ag ing-degradation research objectives with available resources for ex-plant materials. The searchable information tool shall be available via an interactive web page. (b)(3):41 U.S.C. § 253b(m)(1) A2. 11

(b)(3):41 U.S.C. § 253b(m)(1) Task 1.5 -Conduct Scoping Analysis on Viability of Searchable Information Tool Task 1.5. 1 PNNL shall briefly consider available approaches to creating a preliminary database that will link the highest susceptibility/lowest knowledge anticipated degradation scenarios with potential availability of ex-plant materials. As part of this subtask, PNNL shall review the status and viability of the PMMD information tool created as part of the PMMD project (conducted at PNNL under previous NRC contracts (i.e., JCN N6029, N6907). The goals of the PMMD project were to identify reactor components that could reasonably be expected to experience future degradation, estimate the susceptibility of components to various degradation mechanisms, and assess the degree of knowledge available to develop mitigative strategies. It was anticipated that this information could be used to guide regulatory actions related to license renewal and subsequent license renewal. The PMMD panel evaluated 3863 components (2203 for PWRs, 1603 for BWRs) for their susceptibility to 16 degradation mechanisms (Figure 4 below). Because of the unwieldiness of the source material, a searchable information tool (pmmd.pnl.gov) was developed to make this information usable to NRC staff and others. Task 1.5.2 PNNL shall work with the NRC to create a proposal to develop a platform for the searchable database methodology (selected in Task 1.5.1) that can be supported within NRC. A2.12

PLANT DATA DRAWINGS IT] Based on drawings, documonts. o.g.. FSAR, PJant-spec;fic

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                     . - - - -.,; Excel sproodshoots dovolopod by a Panel              load 9xpert, ,ev;sed based on .

I Members EVALUATIONS Excel spre8dsh881S with d&gradotion mechanisms scor9d and commenlod on by panel mm EVALUATION DATABASE ACCESS dotaboso with all evttluat,ons REPORTS Comp/lat/om, filtors, counts, etc. Figure 4. Flowchart for files created and used in PMMD infotool (b)(3):41 U.S.C. § 253b(m)(1) Task 1.6 - Provide Archival Summary Document of Findings from Task 1 PNNL shall analyze and review the reports generated from the work conducted under Tasks 1.1 through 1.5 and provide a stand-alone NUREG/CR documenting the major findings. A2.13

(b)(3):41 U.S.C. § 253b(m)( 1) Optional Task 2 - Decision Making on Specific Research Need to Address Gaps If the Task 1 scoping study succeeds in determining previously unidentified significant knowledge gaps that need further attention, more work will be done in the context of Task 2, pending the approval from the NRG Contract Officer (CO). Thus, Task 2 is optional pending the outcome of Task 1 and requires NRC activation. The activities required for this task aire: Task 2. 1 - Gap Identification PNNL shall identify specific information and technical data gaps from the execution of Task 1 and document these gaps. In identifying the gaps, PNNL shall include an examination of the current ASME B&PV Code or other industry practices that the NRC has endorsed with respect to addressing the specific degradation mechanism in the design and the assurance of the retention of the design margin during the period of licensed reactor operation time. Task 2.2 - Determine Significance and Disposition of Technical Gaps PNNL shall determine whether or not there are any technical gaps from the execution of Task 2.1. If there are no gaps and if it is determined that the current ASME Code or other industry practices ensure that the design margin for components are adequate, recommend termination of further research in this topic by NRG. If specific information and technical gaps are identified then proceed to Task 3 after getting approval from the NRG Contract Officer (CO). (b)(3):41 U.S.C. § 253b(m)(1) A2.14

(b)(3):41 U.S.C. § 253b(m )(1) Optional Task 3 - Research Addressing Technical Gaps Related to Material Degradation If critically important information and technical gaps are identified in Task 2, Task 3 is activated after getting approval from the NRG CO. Thus, Task 3 is optional pending the outcome of Task

2. The activities required for this task are:

Task 3. 1 - Recommend Specific Laboratory Experimentation and Analytical Model Development PNNL shall work with NRG subject matter experts (SMEs) to recommend specific laboratory experimentation and analytical model development, which may address the information gap identified in Task 2.1. If novel nondestructive evaluation methods (such as the next-generation acoustic emission technology which reportedly can 'hear' crack initiation) become available to identify progressing reactor material degradation by the ti me Task 3 is initiated, PNNL shall recommend inservice inspection (ISi) technology enablers which will be suitable for detecting the material changes resulting from different stressors. PNNL shall work with NRG SMEs to recommend the need for developing tools for detection and assessment of potential degradation of the design safety margin to independently confirm the licensee's technical basis for LTO. Task 3.2 - Review Adequacy of Existing Codes and Standards PNNL shall conduct a review of existing applicable ASME B&PV Codes that may need to be revised as a result of Task 2 .1 and PNNL shall work with NRG SMEs to engage relevant ASME A2. 15

Code Committees for assessing future path. PNNL shalll propose other Codes and Standards that should be reviewed (such as but not limited to, ANS, ASTM, and NACE codes and standards). (b)(3):41 U.S.C. § 253b(m )( 1) Optional Task 4 - Investigate Development of Independent Decision Making Tools Task 4 is optional pending the outcome of Tasks 1 - 3. If gaps are identified under Task 2 and appropriate research needed to inform the gaps are also identified under Task 3, NRG expects that the industry will perform the needed research and provide NRC the data for regulatory decisions. Depending on the outcome of Tasks 2 and 3 and ensuing industry research, the decision-making tool development may be complex and truly involve multi-year, multi-disciplinary long term research. It is expected, however, that the decision making tool may include: (a) Material and component condition after different stressors; (b) Better knowledge of specific degradation and its potential for reducing the design safety margin for the components; (c) Incorporation of plant data into the various material, inspection, and structural integrity evaluation models; and (f) An integration of all these aspects into the regulatory decision making process to consider the risk contribution due to material degradation. Specific subtasks for this task will be established later in this research. PNNL shall investigate the feasibility of developing a modern visualization confirmatory analysis research tool for aging management of safety-significant SSC degradation in NPPs. As currently envisioned, this could provide a knowledge management and strategic planning tool for conducting gap assessments and prioritizing R&D resources related to NPP LTO. This research will leverage the work previously performed by PNNL on the PMMD Information Tool, sponsored by RES. RES/DE would benefit from a R&D gap assessment, strateg ic planning and knowledge management tool to enhance the tracking , disposition , resolution of technical issues that surface as industry moves towards S LR. Such a database would save staff time in addressing the degradation challenges for NPP passive components, spent fuel pools, and independent spent fuel storage installations (ISFls). The proposed LTO issues visualization tool can incorporate, up-to-date information on critical issues associated with cable, concrete and RPV aging. Work is actively progressing on developing SLR guidance documents with unresolved techn ical issues arising almost on a daily basis. These could be captured by the proposed service-oriented analytic framework. The existing PMMD database containing detailed information about susceptibility, knowledge, and confidence associated with hundreds of degradation scenarios can be augmented with aging risk indices, when developed by the DOE LWRS research. This will enable a better understanding of service life projections of NPP SSC. A2. 16

(b)(3):41 U.S.C. § 253b(m)(1) 5.0 DELIVERABLES AND/OR MILESTONES SCHEDULE Except for Task 1.6 where a draft summary NU REG/CR is stipulated, all deliverables shall be in the form of technical letter reports or alternatives previously discussed and determined acceptable by the COR. Based on the detailed tasks provided in Section 4.0 of this Statement of Work, PNNL shall estimate the number of Figures/Tables or other copyrighted information from technical journals, etc. a nd shall incorporate this estimation in the cost proposal in addressing the SOW. PNNL shall also estimate reasonable effort by their technical editing staff in order to provide the NRC tech-edited draft final and final reports. (b)(3):41 U.S.C. § 253b(m)(1) A2. 17

Task Deliverable/Milestone Description (include NRG acceptance Due Date (if any) Number criteria if applicable) All Monthly Letter Status Report (MLSR) 201" day of each month 1.1 PNNL to provide Report 1.1 . DraftTLR to NRC on Subtask (1.1 ) NLTG montl)~ '.:1fter (b)(3):41

                                                                                                                                                                                        .............. ...U.S .Q. § 253b reviewing anticipated NPP LTO materials degradation and                                                           contract award (m)(1) prognostics 1.1               NRC to provide comments to contractor on Report 1.1 on NPP                                                        NLT 1 month after LTO materials degradation and prognostics                                                                         receiving draft Report 1.1 from PNNL 1.1               PNNL to publish TLR Report 1.1 on materials degradation and                                                       NLT 1 month after prognostics. Deliver 12 hard copies to the NRC COR, in                                                            receiving NRC addition to an electronic file.                                        (b)(3):41 U .S.C .. §-~53b(m)(1)           comments 1.2               PNNL to provide Report 1.2. Draft TLR to NRC on l                                                               I NLTLJmoDJhs after                         (b)(3):41 (b)(3):41 U.S.C . § 253b(m )(l)               I                        !concerning availability of ex-plant material and                                          contract award
                                                                                                                                                                                            ******      . U .S.C. § 253b (m){1) informatior4                                                                                                  I (b)(3):41 U.S.C. § 2s3~(~2U1                  .1............. ********         I                        (b)(3):41 U.S.C-: §_253b(m)(1) 1.2               NRC to provide comments to contractor on Report 1.2                                                               NLT 1 month after concerning availability of ex-plant material and info rmation                                                      receiving draft Report 1.2 from PNNL 1.2               PNNL to publish TLR Report 1.2 concerning availability of ex-                                                     NLT 1 month after plant material and information. Deliver 12 hard copies to the                                                     receiving NRC NRC COR, in addition to an electronic file.                                                                       comments
                               +.3               PNNb te pFGvide Repert 1.3 (Gensisting ef questiennaire                                                           Nbl 10 menths after and intewiew results) to NRC en Subtask (1.3) conGerning                                                           GentraGt award interast--of pr-ospectwe-NRC--stakeholdei:s-i-n a-5¥.stematiG approach to haF>Jesting ex plant materials
                               +.3               NRC to pFG*Jide somments to GontraGtor on Report 1.3                                                              Nbl 1 month after concerning interest of pFospecti>Je NRC stakeRolders in a                                                         ~

systematiG appraaGh te harvesting ex plant materials fFGm PNNb

                               +A                PNNb te pFGvide Repert 1.4 (Gensisting ef questiennaire                                                           Nbl 14 menths after and lnter>Jiew results) to NRC on Subtask (1.4) concerning                                                         Gontract a*Nard imerest of prospeoove-e-x-ternal stakeh&kieFs-i-n-a systematiG appraaGh te harvesting ex plant materials (b)(3): 41 U.S.C. §
                               +A                NRC to pre*Jide somments te GontraGtor on Repert 1.4                                                              Nbl 1 menth after 253b(m)( 1) 1***   .  ........... coocerning-mtefest-of.-prospectw~Aal-&tak~ in                                                                      F&Geiv-ing-Report-1-.4 a     systematiG apereaGh te har>Jesting ex plant materials                                                        frem PNNb r'Ula.11
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C, i \ ,.,:.L I Nbl 16 menths after (b)(3):41 U.S.C. § suggested alternatives for creating a prognostiG toel to contract award 253b(m)(.1) ** *******

                         -                      traGk and resel>Je GritiGal teGhniGal issues fer SbR NRC to pro*Jide somments te contractor on ReportLJ ............... .NbIJ ffl"'Flth _after                                                                  (b )(3):41 u;s ,c ..§ 253b concerning alternatives for creating a prognostic tool to                                                         recei>,<<ing Report (m)(1) track and resol>Je critical technical i s ~                                                                        -1...6,1 from PNNb Note to requester: The crossed out content on this page is in the final version of the contract (public at ML19129A329), but in the final version it is not crossed out.

A2.18

Note to requester: The crossed out content on this page is in the final version of the contract (public at ML19129A329), but in the final version it is not crossed out. (b)(3):41 U.S.C. § 253b(m)(1) (b)(3):41 Summary Report 1.6. Draft L Jto NRC including, information NLT 20 months after u.s.c. § from Reports 1.1 t hrough 1.5.2. contract award 253b(m) (1) (Note: At the discretion of COR, a decision may also be made to publish Summary Report 1 as a TLR rather than as an NUREG/CR, depending on the significance of the literature review and research assessment results). (b)(3):41 U .S .C . § 253b(m)(1) The Contractor will make a technical presentation to the NRC When the draft *' staff on Summary ReportG atN~C Headquarters in Rockville, Summary Report [J MD. (b)(3Pl1U,S.C, §2.53b(m)(1) is delivered to NRC. NRC to provide comments to contractor on Summary Report NLT 2 months after CJ (b)(3}:4tl,l.?.C: § 253b(m)(1) receiving draft (b}(3):41 _ u.s.c. Summary Report[ =]... (b}(3):41 U .S .C . (b)(3):41 U.S.C. § 253b(m)(1) from PN NL § 253b(m)(1)

                                                                                 .. ,..                § 2531?(rh)(1)

DOE Contractor to publish Summary Report E] as ~ NLT 2 months after Deliver 12 hard copies to the NRC COR, in addition to an receiving NRC electronic file. comments Task 2 is optional pending outcome of Task 1. 2 PNNL to provide Report 2 Draft TLR to NRC based on results NLT 24 months after from Subtask (2. 1) concerning technical gap identification and original contract award subtask (2.2) determination of significance and disposition of gaps 2 NRC to provide comments to contractor on Report 2 concerning NLT 1 month after technical gap identification, significance, and disposition receiving draft Report 2 from PNNL 2 PNNL to publish TLR Report 2 technical gap identification, NLT 1 month after significance, and d isposition. Deliver 12 hard copies to the NRC receiving NRC COR, in addition to an electronic file. comments Task 3 is optional pending outcome of Task 2 3.1 PNNL to provide Report 3.1 Draft TLR to NRC based on results NLT 46 months after (b)(3):41 U.S .C . § 253b(m)(1) .... from Subtc:i§k(3.J l -** ** !concerning, specific contract award laboratory experimentation, aRd analytical model development, l!bl(3l:41 U.S.C. § 253b(ml(1 l I 3.1 NRC to provide comments to contractor on Report 3.1 NLT 1 month after concerning specific laboratory experimentation and analytical receiving draft Report model development 3. 1 from PNNL 3.1 PNNL to publish TLR Report 3. 1 concerning specific laboratory NLT 1 month after (O)(;j):41

                                ....   -/~~-~-~~i~~~~:~i~~'. ~~ ~nalytical model development~                     liver receiving NRC comments U.S .C . §253b     ***

(m)(1) 12 hard copies to the NRC COR, in addition to an electronic file. 3.2 PNNb to pm*1ide Report 3.2 Draft lbR to NRC re¥iewing Nbl 46 months after adeq1:1aGy of existing Godes anEI standards for SbR GontraGt a*11aFEI 3-.2 NRC-t~FOY-ide-comments-to--oontract8f--OR-.Report-3.2 Nbl 1 month alter re¥iewing aEleq1:1aGy of existing GoEles anEI standarEls for reGei¥ing Elraft SbR Repeff-3.2from PNNb 3.2 PNNb to p1:1blish lbR Report 3.2 re*1iewing aEleq1:1aGy of Nbl 1 month after existing Gades and standards for SbR. Deli*1er 12 hard reGei>ling NRC GOpies to the NRG GQR1 in-aEldition to an el&GtFGn~ &emmeAts A2.19

Task 4 is optional pending outcome of Task 1 and partially pending on Task 2 and 3. 4 PNNL to provide Report 4 Draft TLR to NRC documenting NLT 46 months after development of prognostic tool to track and resolve critical SLR contract award technical issues 4 NRC to provide comments to contractor on Report 4 reviewing NLT 1 month after development of prognostic tool to track and resolve critical SLR receiving draft Report technical issues 3.2 from PNNL 4 PNNL to publish TLR Report 4 reviewing development of NLT 1 month after prognostic tool to track and resolve critical SLR technical issues receiving NRC R. Deliver 12 hard copies to the NRC COR, in addition to an comments electronic file. 6.0 TECHNICAL AND OTHER SPECIAL QUALIFICATIONS REQUIRED Specific qualifications for this effort include senior materials engineers and metallurgists who have in-depth knowledge of reactor pressure vessel and core internal materials subjected to irradiation and stress at elevated temperature, and effects of water chemistry on structural reactor materials. The personnel involved should have in-depth experience, knowledge, and demonstrated contributions i n the areas of mechanical deformation, material degradation phenomena, such as corrosion, stress corrosion cracking and irradiation effects. The contract personnel should be well-versed in the use of nuclear power plant ASME B&PV Codes and Standards, Industry Guidance Documents, such as those of NEI, EPRI, NRC's Regulatory Guides and NRC's License Renewal Guidance Documents (such as NUREGs 1800, 1801, and 1950) Information Notice (IN), Regulatory Issue Summary (RIS), Generic Letter (GL), Generic Issue (GI) for licensing review by the NRC staff. The contract personnel should also be aware of the safety evaluation reports (SER) written by the NRC staff on industry guidance documents, as applicable. The contract personnel should have previous experience developing appropriate software architecture for proposed R&D planning tool. (b)(3):41 U.S.C. § 253b(m)(1) A2.20

(b)(3):41 U.S.C. § 253b(m)(1) (b)(3):41 u.s.c. §..253b

• EJ

                 ********** MEETINGS AND TRAVEL (m)(1)

The PNNL Principal Investigator and one other engineer shall visit the NRC Headquarters in Rockville, MD and present the overall research outcome to the staff and share in technical discussions. Any suggestions from the staff, as appropriate, may be considered for the final report by the Pl. No other domestic or foreign travel is permitted under the initial scoping study. (b)(3):41 U.S.C. § 253b(m)(1) A2.21

(b)(3):41 U.S.C. § 253b(m)( 1) (b)(3):41 EJ u.s.c. §2.5 3b *

• REPORTING REQUIREMENTS (m)(1)

PNNL is responsible for structuring the deliverable to follow agency standards. The current agency standard is Microsoft Office Suite 2010. The current agency Portable Document Format (PDF) standard is Adobe Acrobat 9 Professional. Deliverables shall be submitted free of spelling and grammatical errors and conform to requirements stated in this section. Monthly Letter Status Reports In accordance with Management Directive 11 .7, NRC Procedures for Placement and Monitoring of Work with the U.S. Department of Energy, PNNL shall electronically submit a Monthly Letter Status Report {MLSR) by the 201h day of each month to Amy Hull, the Contracting Officer Representative (COR), to Matthew Hiser and Joseph Kanney, the technical monitors, with copies to the Contracting Officer (CO) and the Office Administration/ Division of Contracts to ContractsPOT.Resource@nrc.gov. If a project is a task ordering agreement, a separate MLSR shall be submitted for each task order with a summary project MLSR, even if no work has been performed during a reporting period. Once NRC has determined that all work on a task order is completed and that final costs are acceptable, a task order may be omitted from the MLSR. MLSR should be distributed additionally to the Chief, Corrosion and Metallurgy Branch, RES, the Director, Division of Engineering, RES. Other required distribution will be communicated at the start of this research program. The MLSR shall include the following: agreement number; task order number, if applicable; job code number; title of the project; project period of performance; task order period of performance, if applicable; COR's name, telephone number, and e-mail address; full name and address of the performing organization; principal investigator's name, telephone number, and e-mail address; and reporting period. At a minimum, the MLSR shall include the information discussed in Attachment 1. The preferred MLSR format can also be found in Attachment 1. r b)(3):41 U.S.C. § 253b(m)(1) A2.22

(b)(3):41 U.S.C. § 253b(m)(1) D PERIOD OF PERFORMANCE (b)(3):41 U.S.C. § 253b(m)(1) (b)(3):41 u.s.c . §253b (m)( 1) EJ CONTRACTING OFFICER'S REPRESENTATIVE The COR monitors all technical aspects of the agreement/task order and assists in its administration. The COR is authorized to perform the following functions: assure that the DOE Laboratory performs the technical requirements of the agreement/task order; perform inspections necessary in connection with agreement/task order performance; maintain written and oral communications with the DOE Laboratory concern ing technical aspects of the agreement/task order; issue written interpretations of technical requirements, including Government drawings, designs, specifications; monitor the DOE Laboratory's performance and notify the DOE Laboratory of any deficiencies; coordinate availability of NRG-furnished material and/or GFP; and provide site entry of DOE Laboratory personnel. Contracting Officer's Representative Name: Dr. Amy B. Hull Agency: U.S. Nuclear Regulatory Commission Office: Office of Nuclear Regulatory Research Mail Stop: CS-05-C07M Washington, DC 20555-0001 E-Mail: amy.hu ll@nrc.gov Phone: 301 -251 -7656 Alternate Contracting Officer's Representative Name: Matthew Hiser Agency: U.S. Nuclear Regulatory Commission Office: Office of Nuclear Regulatory Research Mail Stop: CS-05-C07M Washington, DC 20555-0001 E-Mail: Matthew.Hiser@nrc.gov Phone: 301 -251 -7601 A2.23

(b)(3):41 ~~~i~* ~}5.~~ [:] MATERIALS REQUIRED NIA (b)(3):41 U.S.C. § 253b(m)( 1) (b)(3):41 EJ u.s.c . §;?.5.3 b-*-*********** NRC-FURNISHED PROPERTY/MATERIALS (m)(1) PNNL will transfer NRC furnished property and materials acquired under previous contracts (i.e., JCN N6029, N6907) to this task order. NRC will provide additional information from EMDA and SLR databases. (b)(3):41 U.S.C. § 253b(m)( 1) A2.24

(b)(3):41 U.S.C . § 253b(m)(1) [] RESEARCH QUALITY The quality of NRG research programs are assessed each year by the Advisory Committee on Reactor Safeguards. Within the context of their reviews of RES programs, the definition of quality research is based upon several major characteristics: Results meet the objectives (75% of overall score) Justification of major assumptions (12%) Soundness of technical approach and results (52%) Uncertainties and sensitivities addressed ( 11 %) Documentation of research results and methods is adequate (25% of overall score) Clarity of presentation (16%) Identification of major assumptions (9%) It is the responsibility of the DOE Laboratory to ensure that these quality criteria are adequately addressed throughout the course of the research that is performed. The NRG COR shall review all research products with these criteria in mind. (b)(3):41 U.S.C. § 253b(m)(1) c::J STANDARDS FOR CONTRACTORS WHO PREPARE NUREG-SERIES MANUSCRIPTS The U.S. Nuclear Regulatory Commission (NRC) began to capture most of its official records electronically on January 1, 2000. The NRG will capture each final NUREG-series publication in its native application. Therefore, please submit your final manuscript that has been approved by your NRC Project Manager in both electronic and camera-ready copy. The final manuscript shall be of archival quality and comply with the requirements of N RC Management Directive 3.7 "NUREG-Series Publications." The document shall be technically edited consistent with NUREG- 1379, Rev. 2 (May 2009) "NRC Editorial Style Guide." The goals of the "NRC Editorial Style Guide" are readability and consistency for all agency documents. All format guidance, as specified in NUREG-0650, "Preparing NUREG-Series Publications," Rev. 2 (January 1999), will remain the same with one exception. You will no longer be required to include the NU REG-series designator on the bottom of each page of the manuscript. The NRC will assign this designator when we send the camera-ready copy to the printer and will place the designator on the cover, title page, and spine. The designator for each report will no longer be assigned when the decision to prepare a publication is made. The NRC's Publishing Services Branch will inform the NRC Project Manager for the publication of the assigned designator when the final manuscript is sent to the printer. For the electronic manuscript, the Contractor shall prepare the text in Microsoft Word, and use any of the following file types for charts, spreadsheets, and the like. A2.25

File Types to be Used for NUREG-Series Publications File Type File Extension MicrosoftWord .doc Microsoft PowerPoint .ppt MicrosoftExcel .xis MicrosoftAccess .mdb Portable Document Format .pdf This list is subject to change if new software packages come into common use at NRC or by our licensees or other stakeholders that participate in the electronic submission process. If a portion of your manuscript is from another source and you cannot obtain an acceptable electronic file type for this portion (e.g., an appendix from an old publication), the NRC can, if necessary, create a tagged image file format (file extension.tit) for that portion of your report. Note that you should continue to submit original photographs, which will be scanned, since digitized photographs do not print well. If you choose to publish a compact disk (CD) of your publication, place on the CD copies of the manuscript in both (1) a portable document format (PDF); (2) a Microsoft Word file format, and (3) an Adobe Acrobat Reader, or, alternatively, print instructions for obtaining a free copy of Adobe Acrobat Reader on the back cover insert of the jewel box. (b)(3):41 U.S.C. § 253b(m)(1) G 0THER** co'Ns10ERAT10Ns References

1. Bond LJ, SR Doctor, and TT Taylor. 2008. Proactive Management of Materials Degradation - A Review of Principles and Programs. PNNL-17779, Pacific Northwest National Laboratory, Richland, WA.

2. Bond, LJ, TT Taylor, SR Doctor, AB Hull, and SH Malik, (2008) Proactive Management of Materials Degradation for nuclear power plant systems. Proc. Int. Cont. Prognostics and Health Management 2008, Denver, CO, October 6-9. IEEE Reliability Society,# OP-20-01 120

3. Chopra, OK, et al, Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Rev. 0, FCRD-USED-2012-000119, 2012.

4. EPRI 3002000576, Long-Term Operations: Assessment of R&D Supporting AMPs for LTO, Aug. 2013 {80pp).

5. NEI, Roadmap for Subsequent License Renewal, Dec. 2013. (45pp)

A2.26

6. NEI, Second License Renewal Roadmap, May 2015. (22pp).

7. NUREG/CR-6923, Expert Panel Report on Proactive Materials Degradation Assessment, 2007 (3895pp, ML063520517)

8. NUREG/CR-7153, Expanded Materials Degradation Assessment, 5 volumes, October 2014 (861pp)

9. SECY-14-0016, Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal, January 31, 2014 (25pp)

10. Taylor, WB, CE Carpenter, KJ Knobbs, S Malik, Using Technology to Support Proactive Management of Materials Degradation for the U.S. Nuclear Regulatory Commission, Proceedings of the ASME Pressure Vessels & Piping Division/ K-PVP Conference, PVP 2010, July 18-22, 2010. Bellevue, WA, USA. Paper PVP2010-26063.

11 . The Scalable Reasoning System: Lightweight Visualization for Distributed Analytics, IEEE Symposium on Visual Analytics Science & Technology, 978-1-4244-2935-6/08 Access to Non-NRG Facilities/Equipment N/A Applicable Publications N/A Controls over document handling and non-disclosure of materials NIA A2.27

ATTACHMENT 3-STAFFING PLAN NRC Agreement Task Order No.: NRC-HQ-60-15-T-0023 (b)(3 ):41 U.S.C. § 253b(m)(1) A3.1

(b)(3):41 U.S.C. § 253b(m)(1) A3.2

(b)(3):41 U.S.C. § 253b(m)(1) A3.3

(b)(3):41 U.S.C. § 253b(m)(1) A3.4

(b)(3):41 U.S.C. § 253b(m)( 1) A3.5

(b)(3):41 U.S.C. § 253b(m)(1) A3.6

(b)(3):41 U.S.C. § 253b(m)(1) A3.7

(b)(3):41 U.S.C. § 253b(m)(1) A3.8

(b)(3):41 U.S.C. § 253b(m)( 1) A3.9

(b )(3):41 U.S.C. § 253b(m)(1) A3. 10

(b)(3):41 U.S.C. § 253b(m)( 1) A3. 11

(b)(3):41 U.S.C. § 253b(m)(1) A3. 12

ATTACHMENT 4 NRC Agreement Task Order No.: NRC-HQ-60-15-T-0023 Strategic Approach for O btaining Material and Components Aging Information ORGANIZATIONAL CONFLICT OF INTEREST INFORMATION (b)(3):41 U.S.C. § 253b(m)( 1) A4.1

(b)(3):41 U.S.C. § 253b(m)( 1) A4.2

Note to requester: The attachments are immediately following. Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hull, Amy Sent: Tue, 5 Sep 201717:41:29 +0000 To: Hiser, IMatthew;Purtscher, Patrick Cc: Moyer, Carol;Frankl, Istvan (lstvan.Frankl@nrc.gov)

Subject:

Action: Rewrite in response to Feedback on UNR Response Task 2 Attachments: Final draft - Response to User Need Request NRR-2017-006.docx, UNR NRR-2017-006.pdf, Comments on draft UNR NRR 2017-006.docx Hi Matt and Pat, Would you like me to take a crack at the following feedback from NRR (since I put the database in the original SOW) or would you like to rewrite first? Or should we sit down and brainstorm these questions? I have attached the UNR, the response, and the NRR feedback from last Thursday. TASK 2

• It isn't clear what these criteria/approaches/processes for the use of the database are.

Where are they documented or described, how they have been validated or used? Are the criteria/approaches/processes described in the September 2017 TLR? NRR needs to have an idea of what is involved in the steps and how the database will be used.

• It is not clear how the first two activities, the workshop on materials harvesting and prioritizing of issues to be addressed by harvested materials, contribute, or are related to the database. This must be fully explained.
• Why just decommissioned plants? An explanation is required as to why this has been limited in scope.
• It is not clear how the discussion under Subtask 2 are examples of how the database would be used. It seems to be a discussion of harvesting material. This needs to be explained, with clear outcomes defined.

(b)(5) iL I !seems like a lot to develop an Excel or Access database. Does this include collecting and inputting information on materials needed and the sources of materials expected to be available? This tasking must be better defined. Amy 8. Hull, Ph.O Senior Materials Engineer RES/DE/CMB (office T10-D49) US Nuclear Regulatory Commission 11545 Rockville Pike Rockville, Maryland 20852 Telephone: (301) 415-2435 FAX: 301-415-6671 e-mail: amy.hull@nrc.gov

Note to requester: This email, and its attachments (that are immediately fo llowing), are the "Final draft- Response to User Need Request NRR-2017-006.docx" attachment from the previous page. From: Hull, Amy Sent: Wed, 16 Aug 2017 13:49 :38 +0000 To: Brady, Bennett;Stuchell, Sheldon Cc: Frankl, Istvan (lstvan .Frankl@nrc.gov);Moyer, Carol

Subject:

Fina l draft - Response to User Need Request NRR-2017-006.docx Attachments: Response to User Need Request NRR-2017-006.docx, SLR UNR response Memo 08-14-2017 cln ML17227A483 .docx Importance: High Good Morning Sheldon and Bennett, Attached is the final draft of the SLR UNR response that Steve Frankl asked me to share with both of you . You mentioned yesterday having a meeting tomorrow with DMLR management concerning this work. Please feel free to use the attached documents. Thanks , Amy

Response to User Need Request NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRG/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two domestic and international activities (either a workshop, conference, symposium, or meeting), one in early autumn 2018 on mechanical issues and one in late spring 2020 on concrete and cables issues. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016, ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR, and any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for international plants). RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. Prior to the meetings, RES will provide a draft agenda with specific topics for the meeting and the proposed presenters. RES will document the information from each of these activities in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting. Mechanical Issues - As part of the requested autumn 2018 workshop/ conference/ symposium/ meeting on mechanical issues, the NRC staff will coordinate a session, or sessions, concerning issues associated with reactor vessel embrittlement during the SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. Concrete, Containment and Electrical Cables Issues - RES will also hold an NRG/industry workshop with international participation in the third quarter of FY20 (spring of 2020) on the state of knowledge for the technical issues in concrete, containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific issues and items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before the workshop. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late spring 2020. Enclosure

Task 2 RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, 2.A -2.D as stipulated on page 4 of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting.

• In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The deliverable provided criteria to assess the need for harvesting to address a particular technical issue. The report then applied these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report also covered the background on the need for harvesting, and past harvesting efforts and experience. The purpose of this report was to serve as a foundation for NRC staff to prioritize technical issues best addressed by harvesting. The initial technical letter report (TLR) for this research is expected to be published in September, 2017, as a PNNL document. This TLR will be reviewed by NRR and RES staff to determine any follow-on work by RES and the final publication type.
• In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested.

The workshop summary report will be distributed among meeting participants and is expected to be finalized by September, 2017. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2 .B. Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may be best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the latest operating experience and research , so that users may understand which data needs can be best addressed by harvesting. As an example, RES will develop a process to evaluate concrete samples harvested from decommissioned plants, and will follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)-affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels {PCCVs); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete from decommissioned reactors, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001. RES will continue to evaluate the SLR-significant issue of cable aging utilizing harvested cables. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011-014 and NRR-2016-012 to include more cable types (insulation types and medium voltage level cables) and the aging effects on power cables at different voltage levels. Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.0. Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.0., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.0). RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the information tool/database. Task 3 RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of indu stry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research. RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships will build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as 1implementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs. RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete , ASR effects, aging management, and supporting technologies like non-destructive examination (NOE). RES is a participant in several multi-national cooperative research programs, including the OECD Halden Reactor Project (HRP), the International Forum on Reactor Aging Management (IFRAM), and many others. For example, the RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. IFRAM is envisioned to be a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research, regulation, education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the HRP proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These resu lts will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NEA/CSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE, NRR/DMLR and NRR/DE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task4 RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff. Task 4 also allows for NRR to call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses. RES will also prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Building upon the extensive work previously done under UNR NRR 2014-001 , RES staff will continue to be available to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SM Es) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. As an example, the staff will continue to be available to review operational equipment failures to assess the trend in critical risk-significant electrical equipment. There are concerns with aging effects (including cyclic aging) and design life of other electrical components such as breakers and relays which would need further evaluation to assess its continued service life by exploring other monitoring techniques not generally covered under surveillance tests. Such analyses could complement work in Task 2, whereby critical electrical components can also be harvested and evaluated. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) ofL.. Vyear for this task be adjusted once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRC-supported research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. The deliverables and schedules for UNR NRR-2017-006 are shown in the following table. Schedule and Resources for the Various Tasks Period of Performance {FY 18-21) Task Task Description Completion FTE Contract$ Number Date 1 Hold NRC/industry workshops (est. 2018, 2020) (b)(5) I ****** ifor-F-Y 18. . . . and FY 21 and prepare NUREG/CP and FY 21 ~iear summary reports on four SRM topics (b)(5) I * * *

• l{P. (5)

Total (Task 1) LJ I ....f ( b)(5) .... ............... 2 Develop a strategy for haNesting materials/components from decommissioned plants (b)(5) 2.A. Develop an information

                                                                  --                                                                    I                                       l (b)(5)_.

FY 18 tool/database 2.B. Develop a process to evaluate plant components FY 18 G .......................... ,..................... ............

                                                                                                                                                      ************************************( ~ (

5) 2.C. Use the process from 2.B. to evaluate the suitability of plant components FY 19 I J *******-****** .............................

                                                                                                                                                      ******************************** * * ******(b... (

5) 2.D. Continue to implement the process from 2.B . as components become Ongoing (FY [:3'y:ear --- ************************************************************************* ( *~ *.. ( 20-21) (Tota1 [ 3 .....,................

                                                                                                                                                      ******** ************************* J ~.. (

available from additional plants 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in retrieval and testing of ex- FY21) Task 3, below (b)(5) plant materials .,* Total (Task 2) L:::;;J .. (b-)(5 . .. I I 3 Participate in relevant (b)(5) (b )(5) domestic and international O ,year e3 -* activities (e.g., IFRAM, IAEA, FY 18-21 (total for 4 years (Total Q DOE LWRS, EPRI LTO, IFRAM dues) codes & standards) (b)(S) *,. 4 Develop documentation (b)(5) evaluating significant c::::::::::Jyear technical issues germane to FY 18-21 (Total Q the review of SLR aoolications (b)(5) '* Total (Tasks 1-4, over 4 years) c:::i (b)(5). 9 xs) UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of Nuclear Regulatory Research (RES) to provide "specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period." This user need request (UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years." This UNR also supersedes NRR-2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" and complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation of reactor vessel internals." For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427). The purpose of this memorandum is to respond to UNR NRR-2017-006 with RES's plans to accomplish the following tasks:

• Task 1: Hold NRG/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ).
• Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvested from operating plants.
• Task 3: Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research.
• Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applications.

CONTACT : Amy Hull, RES/ DE 301-415-2435

B. Holian 2 RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. RES staff will continue these activities and integrate the results in deliverables under Task 4. The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and the anticipated schedule for the deliverables . RES staff appreciates the coordination with NRR technical staff and management in this area . We will continue to coordinate with NRR staff and management to ensu re that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs cou ld impact the activities, deliverables and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and , if warranted, the UNR will be amended.

Enclosure:

Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

B. Holian 3

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHN ICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION : NRR-2017-006 DIST RIBUTION : B. Thomas, RES G Wilson, NRR R. Tregoning , RES A. Hiser, NRR I. Frankl, RES R. Iyengar, RES T. Koshy, RES K. Miller, RES D. Seber, RES S. Stuchell , NRR B . Brady, NRR A.Hull , RES C. Moyer, RES M. Hiser, RES M. Kirk, RES J. Philip, RES M. Sircar, RES J. Pires , RES RidsNrrMailCenter ADAMS Pac kaae A ccess1on No.: ML17227A483 OFFICE RES/DE/CMS RES/DE/CMS RES/DE/CMS NAME C. Moyer A. Hull I. Frankl DATE I /2017 I /2017 I /2017 OFFICE D:RES:DE RES Mail Room D:RES NAME B. Thomas K. Johnson M. Weber DATE I /2017 I /2017 I /2017 OFFICIAL RECORD COPY

Note to requester: This record is the "UNR NRR-UNITED STATES 2017-006" attachment to NUCLEAR REGULATORY COMMISSION Amy Hull's 9/ 5/2017 Email, WASHINGTON, D.C. 20555-0001 "Action: Rewrite in response to Feedback on UNR Response Task 2". May 4, 2017 MEMORANDUM TO: Michael F. Weber, Director Office of Nuclear Regulatory Research FROM: William M. Dean, Director ~~--14-~ Office of Nuclear Reactor Regulation

SUBJECT:

RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION The purpose of this memorandum is to request specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years) . These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period. In a previous user need request, UNR-NRR-2010-006 , "Request for Office of Nuclear Regulatory Research Support in Developing Technical Information to Support Evaluating the Feasibility of License Renewa l Beyond 60 Years,"Agencywide Documents Assess and Management Systems (ADAMS) Accession No. ML092470525), the Office of Nuclear Regulatory Research (RES) assisted the Office of Nuclear Reactor Regulation (NRR) in developing information for consideration in the SLR guidance documents. This new user need request focuses on research activities on the technical issues discussed in the SLR guidance documents and in the staff requirements memorandum to SECY 14-0016 (ADAMS Accession No. ML14241A578). Specifically, NRR is requesting RES support to:

• Hold NRC/industry workshop(s) on the status of domestic and international research activities and operating experience to address issues discussed in the SLR guidance documents;
• Develop and implement a long-term strategy and information tool for harvesting ex-plant components from decommissioning as well as from operating plants;
• Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research for SLR; and
• Use the products from the above three tasks to develop documentation of the status of research for the significant technical issues for SLR.

CONTACT: Bennett M. Brady, NRR/DLR (301) 415-2981

M. Weber Additional details are provided in the Enclosure, "Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation." Resources NRA requests RES to provide the specific resources (contract dollars and full-time equivalent staff) needed to complete the various tasks during the period of activity. Intended Use of RES Products The requested RES products will provide confirmatory research on the technical bases for industry research products related to aging degradation and identified in the staff's review of SLR applications. Coordination and Schedules This request has been coordinated with RES staff in the Division of Engineering (DE). Based on this, we expect that the requested work could be completed within the requested timeframe. We are prepared to work with your staff to further develop a mutually acceptable technical approach and schedule for tllis activity and to engage industry on this important matter. In addition , the directors of the lead divisions in each of our offices, George Wilson (NRR/Division of License Renewal (DLR)) and Brian Thomas (RES/DE), have discussed and agreed with the scope and schedules of the tasks in this request. Priority This request is rated as high ,priority based on NRA office priority ranking for reactor activities. Points of Contact For NRA, the contact is Bennett Brady, Subsequent Renewal, Guidance, and Operations Branch, DLR. For RES, the contact is Amy Hull, Corrosion and Metallurgy Branch, DE. Additional Information None.

Enclosure:

Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION

Background:

The U.S. Nuclear Regulatory Commission staff (NRC or staff) has recently completed the draft guidance documents for subsequent license renewal (SLR). The draft guidance documents (draft NUREG-2191, Volumes 1 and 2, Agencywide Documents access and Management Systems [(ADAMS) Accession Nos. ML16274A389 and ML16274A399, respectively], "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report" and the draft NUREG-2192, [ADAMS Accession No. ML16274A402) "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants") were issued for public comment in December 2015. As preparation for drafting these guidance documents, the Off ice of Nuclear Reactor Regulation (NRA) and the Office of Nuclear Regulatory Research (A ES) conducted three audits to investigate the effectiveness of aging management programs (AMPs) used in the plant operating period from 40 to 60 years. The findings from the first two audits are documented in the report titled, "Summary of Aging Management Program Effectiveness Audits to Inform Subsequent License Renewal: R.E. Ginna Nuclear Power Plant and Nine Mile Point Nuclear Station, Unit 1" (ADAMS Accession No. ML13122A007). The summary of the third audit can be found in the August 5, 2014, report, "H.B. Robinson Steam Electric Plant, Unit 2, Aging Management Program Effectiveness Audit" (ADAMS Accession No. ML14017A289) . RES also published on June 15, 2016, the "Review of Aging Management Programs: Compendium of Insights from License Renewal Applications and from AMP Effectiveness Audits Conducted to Inform Subsequent License Renewal Guidance Documents," a report prepared by the RES contractor, Argonne National Laboratory, that includes NRC staff input (ADAMS Accession No. ML16167A076). RES also completed the Expanded Materials Degradation Assessment (EMDA) in cooperation with the Department of Energy (DOE) Light Water Reactor Sustainability Program. The resultant reports, NUREG/CR-7153, EMDA, Vol. 1-5 (ADAMS Accession Nos. ML14279A321 , ML14279A331 , ML14279A349, ML14279A430, and ML14279A461 ), describe the conclusions from an expert elicitation process to identify the most significant aging degradation technical issues for nuclear power reactor operation beyond 60 years. The four most significant technical issues identified below were also outlined in the staff requirements memorandum (SAM) on SECY 14-0016, "Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ADAMS Accession No. ML14241A578):

• Reactor pressure vessel neutron embrittlement at high fluence
• Irradiation-assisted stress corrosion cracking of reactor internals and primary system components
• Concrete and containment degradation
• Electrical cable qualification and condition assessment ENCLOSURE

The audits and EMDA volumes provided NRC with over 800 suggestions for changes to the license renewal guidance and aging management program activities found acceptable for operation from 60 to 80 years. Staff in several NRR divisions and RES' Division of Engineering (DE) participated in over 90 expert panels to review these suggestions along with the staff's own suggestions for changes to license renewal guidance documents for the first license renewal. The expert panels dispositioned the recommendations for the guidance for SLR and drafted NUREG-2191 and NUREG-2192. After the draft guidance documents were issued for public comment, the staff held several public meetings with stakeholders and the public to discuss the proposed revisions and the bases for the revisions. In these meetings the staff provided information and clarifications on the proposed changes to the guidance documents, and solicited feedback on the documents. The NRC staff has responded to the public comments and will publish the documents in final form in mid-2017. To support their SLR applications, applicants need to demonstrate that the effects of aging will be adequately managed for an operating period from 60 to 80 years. The NRR staff would like RES' assistance in holding meetings on these issues, participating and interacting with the DOE and other industry organizations, cataloguing the materials needed for research , and documenting the status and products of research for SLR. Description of Scope and Tasks

1. Hold NRC/industry workshop(s) on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR Report Need: In February 2008, the NRC and DOE first co-sponsored a 'Workshop on U.S.

Nuclear Power Plant Life Extension Research and Development" (ADAMS Accession No. ML080570419}, which requested stakeholder input into aging management research areas for "Life Beyond 60." Since then, there have been multiple domestic and international workshops/meetings on the research activities and operating experience that may impact aging management of systems, structures, and components (SSCs) for an SLR period. The International Atomic Energy Agency will sponsor the "Fourth International Conference on Nuclear Power Plant Life Management in France in October 2017. These meetings have been helpful in facilitating technical discussions, disseminating knowledge and information, enabling the understanding of technical challenges, and paving the path forward for resolution of the challenges and issues related to materials degradation during the SLR period. As the NRC staff prepares for the review of SLR applications, there is a need for continued engagement with the domestic industry, DOE, and other Federal organizations, academia, international partners, and interested public stakeholders through workshops focused on the status and resolution of the most significant technical issues outlined in the GALL-SUR and the SRM. Request: RES is requested to facilitate a minimum of two domestic and international activities (either a workshop, conference , symposium , or meeting}, one in the early fall 2018 on the mechanical issues and one in late spring 2020 on the concrete and cables issues. These meetings should address:

• the state of knowledge on the technical issues requested in the SAM on SECY 14-0016,
• on-going research on materials degradation issues and aging management of these issues, as discussed in the GALL-SLR, and
• new operating experience from the initial license renewal period (or the long term operation period for international plants).

These activities should be specifically targeted toward the resolution of technical issues for effective aging management of SSCs during the SLR period. Deliverable: The deliverables include the international activities (either a workshop, conference, symposium , or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SAM on SECY 14-0016 for SLR. Prior to the meetings, RES should provide a draft agenda and proposed presenters. The information from these activities should be documented in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions. (e.g., presentations or papers) and research insights and knowledge, due 6 months after each meeting. Schedule: The effort should continue until the completion of the deliverables from the second activity, tentatively scheduled for late spring 2020.

2. Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants, as well as from ex-plant components from operating plants Need: The NRC performs confirmatory research to inform and develop the technical bases for regulatory decisions related to AMPs for SLR. Historically, this research has included testing virgin materials under simulated aging conditions, as well as testing and characterization of ex-plant materials harvested from nuclear power plants. Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab. Testing ex-plant materials also reduces the uncertainty associated with the applicability of the aging conditions. Therefore, this effort is expected to provide fundamental insi1ghts on reactor materials degradation and information addressing potential technical issues or identified gaps to support anticipated future NRC needs. It will also inform the value of existing databases based on simulated aging conditions by assessing their applicability to in-service conditions.

Based on the recent experience of recovering materials from decommissioned plants, such as Zion , Crystal River, and Zorita (Spain), the efforts of planning, coordination, and eventual harvesting of these materials can be resource-intensive and time-challenging. Future efforts to retrieve materials from decommissioned plants should be focused on the highest value SSCs by proactively developing a strategic database for obtaining unique and significant materials aging degradation information from ex-plant components. Such a database will enable the NRC to focus its harvesting efforts and expeditiously obtain materials and components from plants to be decommissioned in the near future and develop information and knowledge to assess the efficacy of the AMPs.

Request: RES is requested to: A. Develop an information tool using Microsoft products which identifies and prioritizes the materials, components, and operating conditions that are needed to address the four significant issues outlined in the SRM on SECY 14-0016, and that, due to challenges in simulating actual service conditions, may be best addressed by harvesting either from plants that are entering decommissioning or ex-plant components from operating plants. B. Develop a process to evaluate the components from plants that are entering decommissioning or ex-plant components from operating plants that would be appropriate candidates for harvesting, and to ensure that timely contact is made with the plant owner to facilitate any harvesting targets that may be identified. C. Use the process developed in item B to evaluate the suitability of components from plants that are currently either under decommissioning or replacing components that may be of interest. D. Continue to implement the process developed in item Bas components become available from additional plants. E. In coordination with Task 3, pursue domestic and international partnerships to pursue cooperational cost-sharing on retrieval and testing of ex-plant harvested material. Deliverable: RES should provide the database for NRA review, and summarize the priority listing in a letter report. Likewise, items Band C should be documented in a letter report. Item D is a continuing item that should be summarized in a letter report or e-mail as appropriate. Schedule: Items A and B should be completed within 18 months of issuance of this user need request. Item C should be completed within 24 months of issuance of this user need request. Item D is an activity that should continue 36 months from the issuance of this user need request.

3. Continue to Develop Domestic and International Partnerships to Share Expertise, Capabilities and Resources Related to Aging Management Research for Long-Term Operations Need: Various domestic and foreign research organizations, government agencies, utilities and research organizations are presently engaged in aging management research, the results of which may be of value to the NRC regarding plant operations during the SLR period. Additionally, the Electric Power Research Institute is engaged with various international research organizations to develop data on aging mechanisms/effects. As such, it benefits the NRC to be engaged in domestic and international research partnerships in order to evaluate all available operating experience and relevant research, leverage resources, and minimize unnecessary duplication of efforts. It would be advantageous to the NRC to develop partnerships with these entities such that the various research programs could be better coordinated and focused on high-priority needs. The scope of this

coordination includes cooperation and cost-sharing on retrieval and testing of ex-plant harvested material in Task 2. Request: RES is requested to continue to develop agreements with domestic and international partners to collaborate on aging management research that results in information to help inform agency decisions regarding SLR applications. RES should evaluate products and reports from these organizations that may be provided to N RC in support of generic or plant-specific issues. Deliverable: RES should provide to interested NRA branch chiefs (from DE and the Division of License Renewal (DLR)) and senior staff relevant products (e.g., trip reports, meeting summaries, papers, presentations, reports and other information) from interactions with domestic and international organizations. In addition, relevant findings from recent interactions, the status, and future plans should be discussed as a standing agenda item during the quarterly interface meetings between RES/ DE, NRA/DLR, and NRA/DE. Schedule: These products should be provided to NRA in a timely manner; the effort should continue until the closure of this user need request. A quarterly report (or slides) for presentation at the Director/ Deputy Director Quarterly Interface Meeting should be provided 5 days before the meeting.

4. Documentation and Compilation of Results from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff Need: In the SAM to SECY 14-0016, the Commission directed the staff to keep the Commission informed on the progress in resolving the four significant technical issues related to SLR. The SAM also directed the staff to keep the Commission informed regarding the staff's readiness for accepting an application and any further need for regulatory process changes, rulemaking , or research.

Request: RES is requested to annually prepare a document summarizing the products from tasks 1, 2, and 3 of this user need request to discuss the accomplishments of RES and national and international partners in addressing the four major technical issues in the SAM and other research activities that may be used in reviewing applications for SLR. The annual report should be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. Schedule: Annual report to t>e provided in the first quarter of each calendar year beginning in the first quarter of calendar year 2018 discussing the research activities supporting SLR during the previous year.

Note to requester: This record is the "Comm ents on draft UNR NRR 2017

 -006.docx" attachment to Amy Hull's 9/5/2017 Email, "Action: Rewrite in response to, Feedback on UNR Response Task 2".

COMMENTS ON DRAFT UNR NRR 2017-006 TASK 1

• Two RPV experts said it is too early to have an international meeting on neutron embrittlement in 2018 . One electrical expert said it would be good to have an electrical meeting in 2020 as NIST will have completed their work at that time. RES should ask staff experts in reactor pressure vessels, internals, concrete, and cables in NRR and RES what would be an appropriate time for international meetings in their areas of expertise. Consideration should be given to times when new information from research will be available and times when no other organizations might be holding large meetings/workshops or symposiums. We do not need to hold a meeting when other organizations have plans for similar meetings.
• It wasn't clear to new readers of the UNR what the purpose and goals of the meetings were and what would be discussed at the meeting. RES needs to include the topics (bullets) in the NRR UNR, including the purpose and goals of any meetings, and what RES intends to provide back to NRR.

TASK2

• It isn't clear what these criteria/approaches/processes for the use of the database are.

Where are they documented or described, how they have been validated or used? Are the criteria/approaches/processes described in the September 2017 TLR? NRR needs to have an idea of what is involved in the steps and how the database will be used.

• It is not clear how the first two activities, the workshop on materials harvesting and prioritizing of issues to be addressed by harvested materials, contribute, or are related to the database. This must be fully explained.
• Why just decommissioned plants? An explanation is required as to why this has been limited in scope.
• It is not clear how the discussion under Subtask 2 are examples of how the database would be used. It seems to be a discussion of harvesting material. This needs to be explained, with clear outcomes defined.

(b)(5) -* l !seems like a lot to develop an Excel or Access database. Does this include collecting and inputting information on materials needed and the sources of materials expected to be available? This tasking must be better defined. TASK3

• RES staff participate in a lot of domestic and international meeting and activities in partnership with other research organizations. NRR recognizes the importance of these activities and collaborative research. What other UNRs contain a task for partnerships

with other domestic and international research organizations? What are the FTE and contract dollars associated with each of these UNRs. An explanation needs to be included that reflects work being done for other program offices . TASK4

• Task 4 should be focused on providing an annual report for use by RES and NRR as a document annually summarizing the status and the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM .

Task 5? (Starting with the paragraph ("building upon the extensive work .... ")

• RES might propose an unfunded Task 5 to provide confirmatory analyses and expert techn ical assistance with the review of technical documents to be submitted with SLR applications or to be available for assistance in the review of SLR applications . The task wou ld be activated as needed by NRR and scoped and cost estimated as the SLR applications are accepted and RES assistance is needed . At this time, NRR does not see a need for th is task.
• Delete the paragraph "As an example." Assessing the "trend in critical risk-significant electrical equipment" is not the role of DMLR . RES might discuss th is with DE in their UNR.
• Provide task estimates for Task 4 alone without additions .

{I just heard today that DE is setting up a request for informal support (less than 100 hours) with RES to do a techn ical evaluation of Seabrook's proposal for a testing program to determine the modulus of elasticity of their ASR-infected containment. I don 't know if this proposal is for their license amendment request or their application for first license renewal. Brian Wittick, Ang ie Buford , and Bryce Lehman were in the meeting. This is the type of thing I would see RES doing in Task 5 . BMB]

Note to requester: Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. The first attachment is immediately following, the second attachment is withheld in full under FO IA Exemption 5 Deliberative Process Privileae. From: Moyer, Carol Sent: Wed, 29 Aug 2018 15:53:40 +0000 To: Frankl, Istvan Cc: Hull, Amy

Subject:

Budget question Attachments: SLR Program at a Glance 20180129cm.abh.pptx, FY19 BE Plan Input Sheet - DE - CMB.xlsx Steve, I am looking at updating the LTO (SLR) Research program at a glance. Currently, it covers FY'17 - FY'19. For FY'19, the estimated budget is shown a~ * +. . . . .. . . j ~)(5) I pulled up the most recent fi le in the G-drive Budget folder, and it shows a FY' 19 estimate of (b)(5) I ......... ..

        ************* 6uclget number that I should use?
                                                                                                             ! Is this the We had some discussions about whether we should be reporting resources ($ + FTE) that are designated only for LTO/SLR research, or whether we should attempt to roll up all of the related research projects into one grand total for materials degradation in long term operation. While that might be an informative number to generate, I think that the Program at a Glance chart should remain focused on the coordination efforts - reporting , workshops, gap analyses - and not roll up all things that could be called aging-related, as this would be confusing and would entail a lot of double counting with other RES/DE projects.

Do we have any guesses at the FY'20 budget target? I found this file in the G-drive CMB Budget folder, "RES FY20 Budget Request 3-1 6-18.xlsx," but I do not seem to be able to open the file. Thank you, Carol Carol Moyer Sr. Materials Engineer RESIDEICMB 301-415-2153 carol.mover@nrc.gov

Subsequent License Renewal Research Safety Intermediate Ultimate RES Objectives Activity Objectives Outcome Outcome Tech basis for Current reliability & Integrity Codes & Standards Technology in Participation (1, 2) Issues in ASME Code ASME Code Development of SLR Creation of SLRGDs GDs (1, 2) Cognizance of Resea rch Strong on Concrete regulatory Degradation (3) system for Cognizance of Research reactor on Fatigue & Vessel integrity to Internals (3) ensure safety of operations 3 during the period of Cognizance of Research extended on Cable Aging (3) operation Resolve spec1f1c technical concern Ex-plant materials Staff development harvesting (3 -2) & tools Tech basis for understanding Prioritization Gap Analyses (1, 2, 3) causes & control of of technical degradation needs mechanisms Emergent needs of Program Office Resolution of Emergent wor k, as (NRR), Regions, needed (3-5) emergent international issues community FY-17 FV-18 FV-19 ABH 3/2018 (b)(5)

FY-17 FY-18 FY-19 UNR Contract ($Kl FTE Contract ($K) FTE Contra ct ($K) FTE NRR-2010-006 NRR-2014-001 NRR -2017-006 EPID: Materials Degradation, Analysis and Mitigation Techniques Following are referenced above under activity:

1) UNR NRR-2010-006 "Support in Developing Technical Information to Support Evaluating the Feasibility of License Renewal Beyond 60 Years"

2) UNR NRR-2014-001 "Provide Expert Assistance with Revising the Guidance Documents for Subsequent License Renewal"

3) UNR NRR-2017-006 "Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation" Database Computer Code

OE,C:18 (b)(5)

(b)(5) (b)(5) Of.ROOIB (b)(5)

OE-sGSCB (b)(5)

OE-sGSCB (b)(5)

(b )(5) (b)(5) (b)(5) (b)(5) Note to requester: Attachments are immediately following this email. From: Hull, Amy Sent: Wed, 24 Jan 2018 20:29:48 +0000 To: Warren, Brenett Cc: Hiser, Matthew;Frankl, Istvan

Subject:

completed but under Division Review: Gentle Reminder for Presentation Submissions to OGC/QTE Attachments: FINAL - ePoster and Digital Presentation Development Flowchart as of 010418 (excel).xlsx, Poster 6 has wrong information : QTE Comments Digital ePosters Importance: High Hi Brennett, Our posters are completed but we do not yet have Division level approval. Please give us a couple more days for the following two posters. Also please note that the abstract for Poster 6, Evaluation of Additive Manufacturing of Metallic Parts via Direct Metal Laser Melting, as available on the RIC site, is still wrong. ( https://ric.nrc.gov/poster ) Please see attached for how it should be written J. Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants In the U.S. nuclear industry today, there are some nuclear power plants (NPPs) that are prematu rely ceasing operation, while other plant operators are making plans to extend operating lifespans through subsequent license renewal from 60 to 80 years. Extending plant operation raises technical issues that may require further research on aging mechanisms to reduce uncertainties associated witlil material performance. Decommissioning plants provide opportunities for harvesting components that have been aged in representati ve light water reactor environments. The NRC has recently undertaken an effort, with the assistance of Paci fic Northwest National Laboratory, to develop a strategic approach to harvest ii1g aged materials from NPPs. The work will identify criteria to consider when prioritizing the data needs for harvesting. The NRC is interested in engaging with other organizations to prioritize data needs for harvesting, to share information about harvested materials and those that may become available, and to identify areas of common interest. The poster will give an overview ofNRC fi ndings and recommendations related to harvesting of components and material specimens from operating NPPs and those undergoing decommissioning.

2. Evaluation of Additive Manufacturing of Metallic Parts via Direct Metal Laser Melting From: RICMST Resource Sent: Wednesday, January 24, 2018 8:09 AM To: Bernardo, Robert <Robert.Bernardo@nrc.gov>; Hall, Victor <Victor.Hall @nrc.gov>; Wilson, Joshua

<Joshua.Wilson@nrc.gov>; Jones, Heather <Heather.Jones@nrc.gov>; Bridge, Joanna <Joanna.Bridge@nrc.gov>; Mendiola, Mary <Mary. M endiola@nrc.gov>; Zuberi, Sardar <Sardar.Zuberi@nrc.gov>; Dembek, Stephen <Stephen.Dembek@nrc.gov>; Yadav, Priya <Priya.Yadav@n rc.gov>; Gifford, Ian <lan .Gifford@nrc.gov>; Smith, Todd <Todd.Smith@nrc.gov>; Orf, Tracy <Tracy.Orf@nrc.gov>; Cruz, Holly <Holly.Cruz@nrc.gov>; Morey, Dennis <Dennis.Morey@nrc.gov>; Oberson, Greg <Greg.Oberson@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Savoy, Joanne <Joanne.Savoy@nrc.gov>; Ralph, Melissa <Melissa.Ralph@nrc.gov>; King, Shannon <Shannon.King@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Armstrong, Kenneth <Kenneth.Armstrong@nrc.gov> Cc: RICMST Resource <RICM ST.Resource@nrc.gov>; Kipfer, Lorna <Lorna.Kipfer@nrc.gov>

Subject:

Gentle Reminder for Presentation Submissions to OGC/QTE Importance: High

Good Morning ePoster and Digital Presenters, This is a gentle reminder to do the following:

• Obtain managerial approval for your ePoster and Digital Presentation
• If your poster has been selected for OGC Review please submit and cc RICMST.Resource@nrc.gov
• Submit your poster to QTE for Level 1 review (note all ePosters and Digital Presentations should be submitted to QTE for final reviews)

Refer to ePoster and Digital Presentation Flowchart for further guidance (also attached). It is im portant that you adhere to the due dates as close as possible. If you are unable to meet this deadline please contact me as soon as possible via email Brenett.warren@nrc.gov or call me at 415-3114. Once again thank you , Program Specialist Office of Nuclear Reactor Regulation NRR / DYIPS/ RISB Location: 0 1305 so 1-4 15-31 14 Follow us on T witter @nrcgov_ric

ePOSTER AND DIGITAL PRESENTATION DEVELOPMENT FLOWCHART Slide Presentations Sllde Presentations Title and Description Yes OGC Review No OGC Review

   -*          -   7            -- -

Presenters revise digital presentations

                                             -    ~* o

• Due date fo r obtaining division-level Due dat e for obtaining division-l evel (ePosters) titles and descriptions based on management approval of ePoster and management approval of ePoster and TRC recommendations; send to Digital Presentation slides complete by Digital Presentation slides complete by RICMST.Resource@nrc.gov complete by 11/27/2017 t RICMST send updated digital presentation Once division-level approval obtained, Presenters send ePoster and digital Once division-level approval obtained, Presenters send ePoster and digital (ePoster) titles and descriptions to presentations to OGCMailCenter. presentations to to QTE.Resource@nrc.gov for level 1 review Resource@nrc.gov for review and cc QTE.Resource@nrc.gov for level 1 complete by U/28/2017 RICMST.Resource@nrc.gov complete by review; and cc RICMST.Resource 01/16/2018

                                                                                                     @nrc.gov complete by 01/26/2018 QTE review and comment on Digital Presentations (ePosters) titles and descriptions; send to OGC review/comment on ePoster and Digital Prese ntations; and send comments QTE reviews ePoster and Digital Presentation slides and provides RICMST.Resource@nrc.gov complete by                       to Presenter and cc                       editorial comments to Presenter for 12/04/2017                                                RICMST.Resource@nrc.gov complete          consideration; and cc' RICMST.
                           ..                             by 01/23/2018                             Resource@nrc.gov complete by RICMST receive QTE editorial comments on fina l digital presentation (ePosters) titles and Presenters receive ePoster and Digital Presentations with OGC editorial 01/31/2018 descriptions; send to Presenters for                                                                Presenters receive QTE comments on comments, revises presentation if consideration/acceptance by 12/05/2017                                                              ePoster and Digital Presentation sl ides; applicable; sends updated presentation to incorporates as appropriate; and sends
                            +                             QTE.Resource@nrc.gov for level 1 review; and cc RICMST.Resource@nrc.gov t o Graphics.Resource@nrc.gov for Presenters confirm acceptance of QTE                                                                 optical review; cc' complete by 01/26/2018 suggest ed edits to digital presentation                                                             RICMST.Resource@nrc.gov complete by (ePoster) titles and descriptions; update w ith                                                      02/05/2018 any new information received incl confirmed                                     t                                           I Presenter names; send to                                  QTE reviews ePoster and Digital                                  T RICMST.Resource@nrc.gov complete by                       Presentation slides and provides editorial  Graphics reviews ePoster and Digital 12/08/2017                                                comments to Present er for consideration;   Presentation slides and provides I
                            'I'                          and cc' RICMST.Resource@nrc.gov             comments to Presenters for complete by 01/31/2018                      consideration; and cc' RICMST.

Presenters complete digit al presentation Resource@nrc.gov complete by (ePoster) A/V Setup Form (including

                                                                                +                    02/06/2018 standard and additional A/V equipment and Presenters receive QTE comments on requirements); send to ePoster and Digital Presentation slides; i,

RICMST.Resou rce@nrc.gov complete by incorporates as appropriate; and sends to Presenters review/accept Gr.aphics 12/21/2017 Graphics.Resource@nrc.gov for optical comments on ePoster and Di gital review ; cc' RICMST.Resource@nrc.gov Presentation slides; incorporate as complete by 02/05/2018 appropriate; sends final to RICMST.

• Resource@gov complete by 02/09/2018 Graphics reviews ePoster and Digital Presentation slides and provides comments to Presenters for consideration, and cc' RICMST.Resource RICMST receives final ePosters and Digital Presentations; sends to RIC

                                                          @nrc.gov complete by 02/06/2018            Contractor for publishing to the RIC website complete by 02/13/2018 Presenters review/accept Graphics comments on ePoster and Digital Presentation slides; incorporate as appropriate; sends final to RICMST.

Resource@gov complete by 02/09/2018

RICMST receives final ePosters and Digit al Presentation slides; sends to RIC Contractor for publishing to t he RIC website complete by 02/13/2018

Note to requester: This email and its attachments (that are immediately following this email) is the second attachment to the January 24, 2018 Email from Amy Hull to Brenett Warren. From: Hull, Amy Sent: Thu, 7 Dec 2017 16:44:09 +0000 To: Warren, Brenett;RICMST Resource Cc: Oberson, Greg;Moyer, Carol;Hiser, Matthew Subject : Poster 6 has wrong information: QTE Comments Digital ePosters Attachments: Consol idated ePoster Titles and Descriptions from QTE (in alpha order) as of 120417_compare.docx, NRC 1102 - AM.PDF Importance: High Hi Brenett, Please correct the following --- 6 RES-Evaluation of Additive Manufacturing of Metallic Parts via Direct Metal Laser Melting Recent plans to shut down a number of nuclear power plants provide opportunities for harvesting components that were eiq30sed to light water reactor environments. Harvesting can provide highly representative aged materials for research and, in some cases, may be the only practical source of representative aged materials to address high priority issues. Harvesting can be e><pensive and time consuming, which makes it essential to focus on technical neecls with the highest importance and to cooperate with multiple organizations *.vhenever possible to optimally leverage resources. The NRG is interested in engaging with otl=!er organizations to prioritize data needs for harvesting, identify areas of common interest, and develop a database for sources of materials for harvesting. It should read--- 6 RES-Evaluation of Additive Manufacturing of Metallic Parts via Direct Metal Laser Melting [ he NRC has been informed that Additively Manufactured (AM) parts are being considered to applications in the operating fleet as early as calendar year 2018. The first industry alert in June 2017 concerned using the DMLM method to manufacture parts for reactor components. A subsequent scoping study by RES staff provided more insight into the technical issues that mus be addressed to assure reliability of specific DMLM-produced components accepted by NRC,

• ncluding design, precursor materials, finished material properties, structural integrity, ondestructive evaluation, and quality assurance. This poster also discusses the emergence and harmonization of relevant codes & standards activities.

~ his poster will give an overview of NRC findings and w eliminary recommendations related to additive manufacturing via DMLM. From: Moyer, Carol Sent: Wednesday, December 06, 2017 6:13 PM To: Hull, Amy <Amy.Hull@nrc.gov> Subject : FW: QTE Comments Digital ePosters Importance: High

Amy, Have you had a chance to look at this mark-up of the RIC poster abstracts? There is a title for a poster on AM, but the text is about harvesting. (There is also one on harvesting, about

harvesting - so it's not as simple as 2 descriptions being swapped.) Your text on the AM poster seems to have been lost. Carol From: Oberson, Greg Sent: Monday, December 04, 2017 2:32 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

FW: QTE Comments Digital ePosters

Hello, Please respond to the action.

Thanks, Greg From: RICMST Resource Sent: Monday, December 04, 2017 11:34 AM To:

Subject:

QTE Comments Digital ePosters We have received the attached comments and recommendations from QTE for each Digital ePoster title and description. Please scroll down and reviiew the comments for your eposter. If you accept all of the recommended changes please send an email to RICMST,Resource@nrc.gov to that effect. However, if you choose not to accept the changes let us know that also. Please respond by 12:00 noon on December 6, 2017. You can refer to your eposter by the number located in front of the title. If you have further questions please contact Bren Warren at 301-415-31 14 or via emai I at RICMST.Resource@nrc.gov or Brenett.Warren@nrc.gov. Thank you, Program Specialist 011kl' of Nuclear Rl'actor Hl'gulation NH.H/ D:vlPS/ HISB Location: 0 l.'JD,, 301 -'1*1 5- S I 11-Brenett. vVarren@nrc.~ov

Follow us on Twitter @nrrgov_ric

                                                    'Chl3-15          ,Jn1111al Heg11lato1y
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Digital Presentations (ePosters) =9Fouped(Grouped in alpl:ta-oFd&FAlphabetical Order) Non Responsive Record

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r on Responsive Record 6 RES- =Evaluation of Add itive Manufacturing of Metallic Parts via Direct Metal Laser Melting Recent plans to shut down a number of nuclear power plants fNP-P-6)-provide opportunities for harvesting components that were exposed to light-: water reactor ~ environments. Harvesting can provide highly representative aged materials for research and, in some cases, may be the only practical source of representative aged materials to address high-: priority issues. Harvesting can be expensive and time-_consuming, which makes it essential to focus on technical needs with the highest importance and !Q_cooperate with multiple organizations whenever possible to optimally leverage resources. The NRC is interested in engaging with other organizations to prioritize data needs for harvesting, identify areas of common interest, and develop a database for sources of materials for harvesting. 8 RES- =Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power

 - - -Plants In the U.S. nuclear industry today, there are some nuclear power plants (NPPs) that are prematurely ceasing operation, while other plant operators are making plans to extend operating lifespans through subsequent license renewa l ~           from 60 to 80-_years.- Exten ding plant operation raises technical issues that may require further research on aging mechanisms to reduce uncertainties associated with material performance. -Decommissioning plants provide opportunities for harvesting components that have been aged in representative light-:water reactor ~         environments.

The NRC has recently undertaken an effort, with the assistance of Pacific Northwest National LaboratoryiPfllNb};, to develop a strategic approach to harvesting aged materials from NPPs. The work w ill identify criteria to consider when prioritizing the data needs for harvesting.- The NRC is interested in engaging with other organizations to prioritize data needs for harvesting, to share information about harvested materials and those that may become available, and to identify areas of common interest. -The poster will give an overview of NRC findings and recommendations related to harvesting of components and material specimens from operating n1:1elear i:iewer i:ilantsNPPs and those undergoing decommissioning. 3

                       'Chl3-15 ,Jn1111al Heg11lato1y
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Non Responsive Record 4

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5

                       'Chl3-15 ,Jn1111al Heg11lato1y
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Non Responsive Record 6

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NRC FORM 1102 U.S. NUCLEAR REG ULATORY COMMISSION (09-2017)

               <¥\
               \,., ......~i RIC PROPOSED DIGITAL PRESENTATION SUBMISSION FORM                                              Original Submission 0 Updated Submission

== Description:== A graphical presentation of research results, the status of standards development, the status of safety or security issues, or other topics of major interest to the agency, interested parties and/or the public. Standard Setup: Standard setup consists of one 46" monitor (screen size 40" w idth x 22.5" height) mounted on a floor stand; o ne USB media player; o ne remote control; one small table and o ne chair.

• Digital Presentation (Single-slide): Format is a one-slide PowerPoint. Word limit is 400-500. Limit of 5-6 large photos, images, o r diagrams.
• Digital Presentation (Multi-slide): Format is a multi-slide PowerPoint. Word li mit is 400-500 per slide .

Limit of 5-6 large photos, images, or diagrams per slide. Submitting Office(s): Enter office acronym, if a joint session, enter lead office followed by supporting office. RES

Title:

Tille should be relatively shorl, yet creative and appealing to the audience. Evaluation of Additive Manufacturing of Metallic Parts via Direct Metal Laser Melting (DMLM) Descriptio n: Description should be innovative, succinct, and include key elements such as purpose, learning objectives, focus areas, and/or take-away messages. The NRC has been informed that Additively Manufactured (AM) parts are being considered for applications in the operating fleet as early as calendar year 2018. The first industry alert in June 2017 concerned using the DMLM method to manufacture parts for reactor components. A subsequent scoping study by RES staff provided more insight into the technical issues that must be addressed to assure reliability of specific DMLM-produced components accepted by NRC, including design, precursor materials, finished material properties, structural integrity, nondestructive evaluation, and quality assurance. This poster also discusses the emergence and harmonization of relevant codes & standardls activities. This poster will give an overview of NRC findings and perliminary recommendations related to additive manufacturing via DMLM. Presenter(s): If known, for each presenter, enter first and last name, position, division title and organization. If possible, list names in the order they will be presenting. Office/Organization Organization/Agency Add(+) No. First a nd Last Name Position Title Division Title (NRC) (Acronyms) (Non-NRC) Remove(*) 1 Amy Hull Senior Materials Division of Engineer Engineering RES GD Thomas Herrity Reactor Operations Division of Construction NRO GD 2 Engineer Inspection & Operational Programs 3 Carol Moyer Senior Materials Division of Engineer Engineering RES GD Topic Submitted By: If the names of the Presenter(s) are not known, enter a point of contact, Name and contact information, for the topic submission. Please submit the completed form, via e-mail, by the following date: Due Date: I 11/27/2017 I NRC FORM 1102 (09-2017) I[ Submit by E-mall ] Page 1 of 1

Note to requester: The attachment is immediately following this email. From: Moyer, Carol Sent: Thu, 7 Jun 2018 22:33:07 +0000 To: Hull, Amy;Rao, Appajosula;Purtscher, Patrick;Focht, Eric;Audrain, Margaret Cc: Frankl, Istvan

Subject:

DMLR User Need Request review meeting, 6/6 Attachments: DMLR' s UN Rs Status FY18 Q2.docx All, On behalf of Steve, I attended a meeting yesterday with NRR/DMLR management, DMLR branch chiefs, DMLR UNR points-of-contact, RES/DE management, and RES/DE BCs for CIB and CMB. The purpose of this 1-hour meeting was a quarterly, high-level status review of all open user need requests between the two divisions. The status table attached was provided by DMLR. It corresponds approximately to the EPID summary sheets that Steve has been asking each PM to update, but this table has less detail and more emphasis on the current status of each UNR. Some of the resource values ($ / FTE) may not line up exactly with what is in your EPID sheets. There were no new Action Items identified for CMB in the meeting. Please review the attached table to ensure that the information related to your individual UN Rs is accurate. If not, please communicate changes to your counterpart POC. Also, Brian Thomas requested that this table include in the "Notes/Status" column a mention of near-term and significant deliverables, such as a NUREG that will soon enter concurrence or a test that will be delayed, as these items should be highlighted during the status review meeting. It was not entirely clear why DMLR chose to have the PO Cs attend the meeting and present each UNR, while DE had only BCs and above there. Them was a disconnect in the communications on this point, it seems. Next quarter, RES/DE will host the meeting, and we will plan to have a better match-up. Carol Carol Moyer Sr. Materials Engineer RESIDEICMB 301-415-2153 carol.moyer@nrc.gov

DMLR/RES User Needs Requests (UNRs) Management Meeting June 6, 2018 ADAMS DMLR RES UNR No./Title Notes/Status References POC POC NRR-2017-006 ML16357A689 Allen Amy Hull

• Focus on research activities on the tech issues discussed in the SLRGDs and the Hiser SRM to SECY-14-0016.

Research RES Response

• Task 1: Hold two NRG/industry workshop(s) (est.2019 and 2020) on the status Assistance on ML17227A483 of domestic and international research activities to address and evaluate aging Potential degradation issues identified in the SRM on SECY 14-0016 and in the GAL L-Significant SLR Report (NUREG-2191 ).

Technical Issues

• Task 2: Develop and implement a long-term strategy for obtaining information on During the materials degradation from decommissioned nuclear power plants (NPPs), as Subsequent PEO well as from ex-plant components harvested from operating plants. PNNL has provided the first deliverable under this task, "Criteria and Planning Guidelines for Ex-Plant Harvesting to Support Subsequent License Renewal. DMLR staff will provide comments to RES.
• Task 3: Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research.
• Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applications.
• Task 5: Provide expert assistance with reviewing SLR applications (optional task).
• Replaces NRR-2010-006 and NRR-2014-001 UNRs .

Non Responsive Record

DMLR/RES User Needs Requests (UNRs) Management Meeting June 6, 2018 I UNR No./Title I ADAMS References I DMLR POC I RES POC I Notes/Status I Non Responsive Record 2

DMLR/RES User Needs Requests (UNRs) Management Meeting June 6, 2018 UNR No. ADAMS I DMLR POC I RES Notes I References POC I Non Responsive Record 3

DMLR/RES User Needs Requests (UNRs) Management Meeting June 6, 2018 UNR No. ADAMS I DMLR POC I RES Notes I References POC I Non Responsive Record 4

DMLR/RES User Needs Requests (UNRs) Management Meeting June 6, 2018 I UNR No. I ADAMS I DMLR POC I RES Dnf' I Notes I Non Responsive Record 5

DMLR/RES User Needs Requests (UNRs) Management Meeting June 6, 2018 UNR No. ADAMS I DMLR POC I RES Notes I I References POC I I Non Responsive Record 6

Note to requester: Portions of this record are redacted under FOIA Exemption 85, Deliberative Process Privilege. From: Hull, Amy Sent: Fri, 3 Apr 2015 08:52:28 -0400 To: Hiser, Matthew Cc: Frankl, Istvan

Subject:

done: ACTION: Request of FYlS Reprommed Funds I went in and did this. Wrote justification and Added another!.____**-******_

                                                                                              *****_******_*** ,1toranothersubtaskJarn (b)(5) working on.

From: Hiser, Matthew Sent: Thursday, April 02, 2015 3:51 PM To: Frankl, Istvan Cc: Hull, Amy

Subject:

RE: ACTION: Request of FY15 Reprommed Funds Hi Steve, I have updated the justifications as necessary. Since Amy is the lead for the strategic harvesting project, I'll leave that to her. Thanks! Matt Matthew Hiser Materials Engineer Corrosion and Metallurgy Branch Division of Engineering Office of Nuclear Regulatory Research 301-251-7601 From: Frankl, Istvan Sent: Thursday, April 02, 2015 2:38 PM To: Hiser, Matthew

Subject:

RE: ACTION: Request of FY15 Reprommed Funds Please provide justification for all of your projects where you are the COR or the backup. Please talk to Sri and Amy on this. Thanks, Steve From: Hiser, Matthew Sent: Thursday, April 02, 2015 10:32 AM To: Frankl, Istvan

Subject:

RE: ACTION: Request of FY15 Reprommed Funds Hi Steve,

This looks good to me! Thanks! Matt From: Frankl, Istvan Sent: Tuesday, March 31, 2015 6:02 PM To: Baquera, Mica; Focht, Eric; Hiser, Matthew; Hull, Amy; Oberson, Greg; Rao, Appajosula

Subject:

ACTION: Request of FY15 Reprommed Funds Importance: High All , (b)(5) This is a quick turnaround item, Since you already provided preliminary info on this, I do not expect that this request will take significant effort. Please provide your inputs by noon Thursday. Thanks, Steve From: Frankl, Istvan Sent: Monday, March 16, 2015 5:18 PM To: Baquera, Mica; Focht, Eric; Hiser, Matthew; Hull, Amy; Oberson, Greg; Rao, Appajosula; Srinivasan, Makuteswara

Subject:

UPDATE: on the CMS Restack Importance: High All , As some of you know we had to provide detailed inputs and clarifications to DE mana ement for some of our projects today. Thanks for all of you who participated in this exercise. - . . .{l:J)(5) (b)(5)

(b)(5) Please continue to update the spreadsheet with the best-estimate spending plans for your (b)(5)

      --- ('oject,;.I                                                                                           (b)(Sil Thanks, Steve From: Frankl, Istvan Sent: Monday, March 16, 2015 10:04 AM To: Baquera, Mica; Focht, Eric; Hiser, Matthew; Hull, Amy; Oberson, Greg; Rao, Appajosula; Srinivasan, Makuteswara

Subject:

UPDATE: ACTION: Update on the CMB Restack All , In order to assure consistent input I created a spreadsheet for this action. (b )(5) I Please input the information requested below in sheet (b)(5) . I --------- Thanks, Steve From: Frankl, Istvan Sent: Thursday, March 12, 2015 4:02 PM To: Baquera, Mica; Focht, Eric; Hiser, Matthew; Hull, Amy; Oberson, Greg; Rao, Appajosula; Srinivasan, Makuteswara

Subject:

ACTION: Update on the CMB Restack Importance: High All , (b)(5) Management requested quick turnaround on this request. So, if your spending plans in BFS are up-to-date and accurate , providing this additional information should not be a significant effort. Therefore, please provide your inputs to me by COB Monday. Thanks , Steve

Note to requester: The attachments are immediately following this email. Portions of this email are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hull, Amy Sent: Wed, 15 Jul 2015 14:41:04 -0400 To: Frankl, Istvan Cc: Hiser, Matthew;Prokofiev, louri (b)(5) ~~~m .

Subject:

                        ***'"""1=-~
                                  * * * ***=*
                                          ..*.*.* *.*=

_-*_- *--*=

                                                                                            .       .JoJlowup"' ..
                                                               *----*--~;;;;;;;;;;;;:,,,,,;,;.;,...:.:.;__   ___;_---=================::::::!....,

Attachments: StratHarv SOW 7-6-15.docx, SOW PARENT-2 draft 07 10 2015 CLEAN.DOC Importance: High Hi Steve, (b)(5) Thanks, Amy From: Frankl, Istvan Sent: Tuesday, July 14, 2015 8:59 AM To: Hull, Amy {b)(5) * * * * * * * * * *

• r~:~j~~q-__-___--.. .- - - - -.-_ .-...-..-....-..__-____-_-__-_-.. . ----------------------

(b)(5) Amy, Thanks, Steve

From: Hull, Amy Sent: Friday, July 10, 2015 3:42 PM To: Frankl, Istvan Cc: Prokofiev, louri; Lin, Bruce (b)(5) Sul:>jE!c~: ................ ............... ---------------- (b)(5) .... c::::J Hi Steve, (b)(5) Thanks, Amy From: Hull, Amy Sent: Wednesday, July 01, 2015 6:28 PM To: Frankl, Istvan Cc: Focht , Eric; Oberson, Greg; Hiser,' Matthew; Tregoning, Robert; Prokofiev, louri

Subject:

everyth ing in STAQS aind routed to you, Kathryn, and Kathleen ...  !-------..-. . -. . .-. ..,,. j b)(5) (b)(5) ,. L* l I Hi Steve, From: Hull, Amy Sent: Monday, July 06, 2015 1:24 PM To: Frankl, Istvan (lstvan.Frankl @nrc.gov) Cc: Hiser, M atthew; Iyengar, Raj (b)(6) _Sul:>ject:! ***************** IORNL presentation info sent to Raj ****1 J (b)(5) __ (b)(5) I I ------------- Hi Steve, (b)(6) (b)(6) -****** L._.;;;;;;;;;;=;;,;;;;;;;;;;;;.;;;:;;;;.;;;:=:::.,;::.:::==--------_JI have transferred the ORNL resentation and background to Raj and have told him all about the purpose and format. -*--*-*********************. .. ( ~)(§) (b)(6)

Sri Rao is working at home this afternoon. Matt Hiser agreed to be acting branch chief for remainder of afternoon. Amy B. Hull, Ph.D Senior Materials Engineer RES/DE/CMB (office T10-D49) US Nuclear Regulatory Commission 11545 Rockville Pike Rockville , Maryland 20852 Telephone: (301) 415-2435 e-mail : amy.hull@nrc.gov

Version Control Date: November 1, 2014 STATEMENT OF WORK NRC Agreement Number NRC Agreement NRC Task Order Number NRC Task Order Modification Number (If Applicable) Modification Number (If Applicable) NRC-HQ-25-14-O-0001 N/A NEW N/A Project Title Strategic Approach for Obtainiing Material and Component Aging Information Job Code Number B&R Number DOE Laboratory Pacific Northwest National Laboratory (PNNL) NRC Requisitioning Office Nuclear Regulatory Research (RES) NRC Form 187, Contract Security and Classification Requirements D Involves Proprietary Information Applicable D Involves Sensitive Unclassified

 ~ Not Applicable
 ~ Non Fee-Recoverable                                 Fee-Recoverable (If checked, complete all applicable sections below)

Docket Number (If Fee-Recoverable/Applicable) Inspection Report Number (If Fee Recoverable/Applicable) Technical Assignment Control Number (If Fee- Technical Assignment Control Number Description (If Recoverable/Applicable) Fee-Recoverable/Applicable)

1.0 BACKGROUND

Regulatory Context: The NRC has established a license renewal process that will allow nuclear power plants (NPP) to renew their licenses for an additional 20 years, via 10 CFR 54.31(d) stating that "a renewed license may be subsequently renewed." The biggest challenges for the NRC and the industry will be addressing the major technical issues for this second "subsequent" license renewal (SLR) beyond 60 years. As summarized in SECY-14-0016, the NRC staff believe that the most significant technical issues challenging power reactor operation beyond 60 years are related to:

• Reactor pressure vessel (RPV) neutron embrittlement at high fluence
• Irradiation assisted degradation (IAD) of reactor internals and primary system components
• Concrete and containment degradation 1

Version Control Date: November 1, 2014

• Electrical cable qualification and condition assessment.

Understanding the causes and control of degradation mechanisms forms the basis for developing aging manageme nt programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSC). The resolution to these issues should provide reasonable assurance of safe operation of the components in the scope of license renewal during the subsequent period of extended operation. Because of the cost and inefficiency of piecemeal sampling, there is a need for a strategic and systematic approach to sampling materials from SSC in decommissioning plants. The envisioned work addresses both passive and active components. In that sense, it addresses aging management of passive components under the license renewal rule, 10 CFR 54, as well as the maintenance of active components covered by the maintenance rule, 10CFR5O.65, as seen in Figure 1 below.

               ,.       U.. RC
                  ,.....,.,.,,.""'... ,..._       Safety Beyond 60 Years Quality Assurance l         Program

( 10 CFR Part 50 Appendi,c B) Ensures that the effects I of aging will be 10 CFR 50.55a effectively managed Requirements throughoutthe period of extended operation I ( Active Components

                                                                                  )

Passive Components Aging Management Effectiveness Figure 1: Relationship between aging management of active and passive components (from NRR/RES presentation to ACRS, 2014) In the past few years, four plants have ceased operation or announced that they will cease operation: Crystal River Unit 3 (PWR), Kewaunee (PWR), San Onofre Units 2 & 3 (PWR), and Vermont Yankee (BWR). These plants comprise a range of reactor types, containments, and SSCs important to safety. The primary objective of this project is to develop a long-range strategy for obtaining information from these plants as they go through decommissioning. The focus will be on timely acquisition of experiential real-worlld aging-degradation information that 2

Version Control Date: November 1, 201 4 can significantly improve the agency's risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet. Technical Context: Creating a roadmap for obtaining information from designated NPPs as they go through decommissioning is complementary to ongoing NRC research in developing technical information to support evaluating SLR as well as data collection and testing of ex-plant materials. Material degradation has traditionally been managed reactively in response to events and operating experience, rather than proactively to prevent failures. For the NPPs currently entering their first license renewal period from 40-60 years, and submitting SLR applications, it is necessary to evaluate potential degradation mechanisms out to 80 years of operation. Evaluation of material properties in SSCs from actual decommissioned NPPs will provide a basis for comparison with results of laboratory tests and calculations to resolve the four issues listed above. The proactive management of materials degradation (PMMD) information tool was orig inally created at PNNL for RES (POC: Amy Hull) to give an expert opinion of the possible future degradation mechanisms on a subcomponent/material specific basis (PNNL-17779)i. Combined with the LER database, the PMMD information tool allows one to not only react to past events, but to anticipate future issues. The original PMMD information tool was based on NUREG/CR-6923, "Proactive Materials Degradation Assessment (PMDA)," for the first license renewal period, so it is now appropriate to integrate information from the excel databases from the recently-published five volumes of NUREG/CR-7153, "Expanded Materials Degradation Assessment (EMDA)" for SLR. At this juncture, there is demonstrated industry interest in NPP long-term operation (LTO) and regulatory interest in SLR. 2.0 OBJECTIVES Understanding and managing material and component degradation is a key need for the continued safe and reliable operation of NPPs, but has significant uncertainties. In many cases, the scientific basis for understanding and predicting long-term environmental degradation behavior of materials in NPPs is incomplete. A strategic approach to examination and testing of materials and components from decommissioned reactors can dramatically increase our knowledge-acquisition rate in this very important area. There are three inter-related objectives to this work: (1) Develop a long-range strategy for obtaining information from decommissioned NPPs as well as providing the flexibility to get ex-plant components from operating plants as well. The focus will be on timely acquisition of experiential real-world aging-degradation information that can significantly improve the agency's risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet. 3

Version Control Date: November 1, 2014 (2) Construct a strategic plan and specifications for obtaining unique and significant materials aging degradation information from diverse sources (operating experience, other nuclear facilities, other long-lived industrial plants, other materials organizations such as ASM and NACE) that will inform the NRC's age-related regulatory oversight in the future. Implementation of this plan and specifications, in cooperation with industry and DOE partners can be accomplished over time, through individual research projects as the identified plants progress through their decommissioning process. This exploratory research is expected to provide fundamental insights on reactor materials degradation and information addressing potential technical issues or identified gaps to support anticipated future NRC needs. (3) Update the PMMD information tool to incorporate LTO/SLR-relevant information so that it can be better used to inform prioritization in the ex-plant material strategic plan. 3.0 SCOPE OF WORK There are a number of technical gaps that this project seeks to address. Most importantly, the current piecemeal approach can be replaced with a strategic plan that is more comprehensive, broader in scope, and more risk-informed. The strategic plan for inspections and/or testing developed in this project will be useful guidance for obtaining key measurements of degradation in a variety of areas. These measurements will be valuable on their own and will also be useful in basic research on the underlying mechanisms and modes of degradation, and for validation of modeling and simulation tools. Data and information developed from implementation of the strategic plan will also be useful in evaluating aging management and mitigation strategies proposed by the industry. Many sources of materials degradation information will be queried, including human repositories of knowledge both within NRC and within the industry. Both the PMDA and EMDA present information in terms of component or material degradation susceptibility and currently available knowledge for degradation mitigation or prevention. A component with high degradation susceptibility/low knowledge would be the strongest cand idate for proactive actions. It is necessary to be able to understand this before prioritizing ex-plant materials sampling available from a given retired NPP. Previously, under the auspices of NRC contracts (i.e., JCN N6029, N6907), PNNL used the large amount of information presented in the PMDA report to develop a web-based platform to facilitate analysis through interactive visualizations that offer intuitive ways to explore the information. PNNL shall explore the viability of adding materials degradation susceptibility data presented in the EMDA Report. Such an information tool (Figure 2 below) is expected to save considerable staff efforts to understand and apply the PMDA and EMDA insights to regulatory review of licensee information. PNNL shall develop a web-based modified scalable reasoning system (SRS) for tracking, disposition, and resolution of critical issues, such as determining the appropriate SSC 4

Version Control Date: November 1, 2014 from which to acquire cast austenitic stainless steel (CASS) material of specific composition and radiation dose. EPRI LTO Decommissioning Reactors Plans Operating Information Tool for Prioritization of Experience High-Priority Data Needs Oooortunities International NRC Data: SLRGDs, Data Sources DOE LWRS EMDA, PMDA Figure 2: Pre-conceptual Architecture of prognostic tool to track and resolve critical technical issues for SLR As shown in Figure 2 above, the information tool was originally envisioned as integrating domestic and international operating experience and experimental information as well as information from the EPRI LTO, DOE Light Water Reactor Sustainability (LWRS) program, and NRC sources such as EMDA, PMDA, and SLR guidance documents (SLRGDs) and precursors. The international data sources that might provide effective data feed include the cable aging data and knowledge (CADAK, http://cadak.hrp.no/cadak.) project and the Component Operational Experience, Degradation and Ageing Programme (CODAP, http://www.oecd-nea.org/jointproj/codap.html ), both sponsored by OECD/NEA. The Atlas constructed by PNNL from the Program to Assess the Reliability of Emerging Non-destructive Technology (PARENT) and the Program to Inspect Nickel Alloy Components (PINC) Atlas is an international database containing a vast array of sec crack morphology and NDE information. PNNL shall investigate whether this is an appropriate framework to track issue resolution associated with SLR. This is a much broader objective than just developing a strategic roadmap for harvesting SSCs. The general tasks and their duration are described in Table 1. 5

Version Control Date: November 1, 2014 Table 1: Task Description and Duration Task Task Title/Description Duration (Months) Task 1 Scoping Study and technical literature review 18 Task 2 Decision Making on Specific Confirmatory Research Needed to 6 Address Gaps (optional) Task 3 Confirmatory Research Addressing Technical Gaps (optional) 33 Task4 Development of Independent Decision Making Tools (optional) 33 The conditional tasks shall be conducted, as detailed in Figure 3 below. A decision on further optional research outlined in Tasks 2, 3, and 4 will be made after completion of Task 1 depending on the outcome and recommendation from the conclusion of specific tasks. The overall nexus between the scoping study and other potential tasks is shown in Figure 3. The PN NL staff shall not restrict their activities solely to these descriptions and shall be flexible in using their technical knowledge and experience in proposing additions, deletions, or deviations from the prescribed requirements as research progresses. Task 1. Terminate Technical Task 2. Gap Further Literature Identification Research Review Yes Task 3. Recommend Research Need

                                                                      ~

I Task4. :I

I Develop :I

Analysis Tools :

                                                            ~----------------j Figure 3: Schematic of the Overall Research 6

Version Control Date: November 1, 2014 4.0 SPECIFIC TASKS Task 1 is the scoping study. Tasks 2-4 are optional. NRC plans to revise the SOW for these tasks based on the outcome of Task 1. The time at which the tasks begin and end will be dependent on available information and NRC's ongoing evaluation of testing priorities. NRC staff does not require that PNNL necessarily perform the tasks be performed sequentially following the order in which they are listed . For the test matrix described in this section, nearly all subtasks will have to be tested in tandem with another subtask in order to complete the program within the requested period of performance. PNNL and the NRC CORs will continually review the testing plan during monthly status update teleconferences. PNNL shall, in the first stage of Task 1, develop a questionnaire and help the NRC staff conduct interviews with focus groups from various technical disciplines within NRC. PNNL shall, in the second stage of Task 1, assist the NRC staff conduct one or two public workshops. PNNL shall analyze and combine the results of the first two phases into a final strategic plan in the third stage. This strategic plan will provide a prioritization of strategic harvesting opportunities. PNNL shall help the NRC staff develop the ex-plant harvesting strategic plan in cooperation with industry and other federal agencies such as DOE as well as any international counterparts that may be interested in participation. In Tasks 2-4, PNNL may be assigned optional tasks to identify requirements to further elucidate the risk assessment of component degradation. Such research should also provide technical data and information, as necessary, to request the national codes and standards bodies (such as ASME, ASTM , or NACE) to re-examine requirements for structural materials for passive components in light water reactors (LWRs) and in assessing material degradation during service and its effect on design safety margin of components. The PNNL principal investigator (Pl) for this project shall attend ASME, ASTM, or NACE Code Committee meetings, as appropriate and as approved by the COR during the course of this research . The Pl shall provide adequate information to support an IAEA international cooperative research program (ICRP) on this subject to bring worldwide resources to address this research need. The specific tasks are as follows: Task 1 - Literature Review and Assessment of Greatest Needs in Sampling of Ex-plant Materials NRC recently completed a research program to investigate material degradation after extended operation. To investigate aging degradation mechanisms, aging degradation effects, and the relative susceptibility to degradation, PNNL shall perform a comparison of available information. 7

Version Control Date: November 1, 201 4 PNNL shall conduct the Task 1 scoping study and provide all resources necessary to accomplish the subtasks and deliverables. Task 1 shall be performed in stages as shown in the Task-specific subsections below. The activities required for this task are: Task 1.1 - Conduct Materials Aging Degradation Literature Review PNNL shall selectively review both domestic and internati1onal sources of technical info rmation of generic nature with respect to anticipated material degradation in NPPs during LTO, extrapolating to 80 years of operation. The objective is to identify other issues not in PMDA/EMDA, such as related to active components or spent fuel storage systems, and to determine what is being done to address LTO issues. NRC will provide guidance on appropriate information to review. Task 1.2 - Evaluate Availability of Ex-Plant Material and Information PNNL shall evaluate what relevant ex-plant material is projected to be available for potential harvesting. PNNL shall work with the NRC COR to develop a questionnaire and interview the cognizant individuals at the plants who possess critical knowledge. Task 1.3 - Develop Questionnaire and Conduct Interviews with Prospective NRC Stakeholders PNNL shall develop a questionnaire and work with NRC staff to conduct interviews with focus groups from various technical disciplines within NRC. Th1is would include the SLR Expert Panels for a sample of different aging management programs (AMPs) as well as other NRC technical advisory groups. PNNL shall have a comprehensive approach to all the possible stakeholders interested in harvesting materials from decommissioned plants. The objective of this initial scoping study is to assess interest in issues concerning both passive and active component degradation. The questionnaire will address, as a minimum, (1) the perceived needs for ex-plant materials, (2) the perceived utility of the existing information tool and how and where this prognostic tool should be maintained (NRC, contractor, cloud). During the early brainstorming and scoping study, PNNL shall also consider degradation of SSC materials associated with extended long-term storage of used fuel. Task 1.4 - Develop Questionnaire and Conduct Interviews with Prospective External Stakeholders Based on interactions with NRC staff in Task 1.3 above, PNNL shall propose a preliminary strategic approach to sampling representative ex-plant materials during one or two presentations at public workshops to further refine the concept of what would be needed in a useful interrogatory tool linking aging-degradation research objectives with available resources 8

Version Control Date: November 1, 2014 for ex-plant materials. The searchable information tool shall be available via an interactive web page. Task 1.5 -Conduct Scoping Analysis on Viability of Searchable Information Tool Task 1.5.1 PNNL shall briefly consider available approaches to creating a preliminary database that will link the highest susceptibility/lowest knowledge anticipated degradation scenarios with potential avai lability of ex-plant materials. As part of this subtask, PNNL shall review the status and viability of the PMMD information tool created as part of the PMMD project (conducted at PNNL under previous NRC contracts (i.e., JCN N6029, N6907). The goals of the PMMD project were to identify reactor components that could reasonably be expected to experience future degradation, estimate the susceptibility of components to various degradation mechanisms, and assess the degree of knowledge available to develop mitigative strategies. It was anticipated that this information could be used to guide regulatory actions related to license renewal and subsequent license renewal. The PMMD panel evaluated 3863 components (2203 for PWRs, 1603 for BWRs) for their susceptibility to 16 degradation mechanisms (Figure 4 below). Because of the unwieldiness of the source material, a searchable information tool (pmmd.pnl.gov) was developed to make this information usable to NRC staff and others. Task 1.5.2 PNNL shall work with the NRC to create a proposal to develop a platform for the searchable database methodology (selected in Task 1.5.1) that can be supported withi n NRC. 9

Version Control Date: November 1, 2014 PLANT DATA DRAWINGS IT] Based on draw,ngs, doc.,monts. o.g.. FSAR. Plant-specif "' information [TI COl'lsultants.

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Panel lead expett, revised based on i Mem bers EVALUATIONS Excel sproachheets with d"f}fadation mechanisms sCOffJd and commented on by panel mcmbt>rs. EVALUATION DATABASE IT] ACCESS database with all

                                                     &v&Jvations REPORTS Compilations.

filtors, counts. etc. Figure 4. Flowchart for files created and used in PMMD infotool Task 1.6 - Provide Archival Summary Document of Findings from Task 1 PNNL shall analyze and review the reports generated from the work conducted under Tasks 1.1 through 1.5 and provide a stand-alone NUREG/CR documenting the major findings. Optional Task 2 - Decision Making on Specific Research Need to Address Gaps If the Task 1 scoping study succeeds in determining previously unidentified significant knowledge gaps that need further attention, more work will be done in the context of Task 2, pending the approval from the NRC Contract Officer (CO). Thus , Task 2 is optional pending the outcome of Task 1 and requires NRC activation. The activities required for this task are: Task 2.1 - Gap Identification PNNL shall identify specific information and technical data gaps from the execution of Task 1 and document these gaps. In identifying the gaps, PNNL shall include an examination of the current ASME B&PV Code or other industry practices that the NRC has endorsed with respect 10

Version Control Date: November 1, 2014 to addressing the specific degradation mechanism in the design and the assurance of the retention of the design margin during the period of licensed reactor operation time. Task 2.2 - Determine Significance and Disposition of Technical Gaps PNNL shall determine whether or not there are any techn ical gaps from the execution of Task 2.1. If there are no gaps and if it is determined that the current ASME Code or other industry practices ensure that the design margin for components are adequate, recommend termination of further research in this topic by NRC. If specific information and technical gaps are identified then proceed to Task 3 after getting approval from the NRC Contract Officer (CO). Optional Task 3 - Research Addressing Technical Gaps Related to Material Degradation If critically important information and technical gaps are identified in Task 2, Task 3 is activated after getting approval from the NRC CO. Thus, Task 3 is optional pending the outcome of Task

2. The activities required for this task are:

Task 3.1 - Recommend Specific Laboratory Experimentation and Analytical Model Development PNNL shall work with NRC subject matter experts (SMEs) to recommend specific labo ratory experimentation and analytical model development, which may address the information gap identified in Task 2.1 . If novel nondestructive evaluation methods (such as the next-generation acoustic emission technology which reportedly can 'hear' crack initiation) become available to identify progressing reactor material degradation by the time Task 3 is initiated, PNNL shall recommend inservice inspection (ISi) technology enablers which will be suitable for detecting the material changes resulting from different stressors. PNNL shall work with NRC SMEs to recommend the need for developing tools for detection and assessment of potential degradation of the design safety margin to independently confirm the !licensee's technical basis for LTO. Task 3.2 - Review Adequacy of Existing Codes and Standards PNNL shall conduct a review of existing applicable ASME B&PV Codes that may need to be revised as a result of Task 2.1 and PNNL shall work with NRC SM Es to engage relevant ASME Code Committees for assessing future path. PNNL shalll propose other Codes and Standards that should be reviewed (such as but not limited to , ANS, ASTM, and NACE codes and standards). Optional Task 4 - Investigate Development of Independent Decision Making Tools Task 4 is optional pending the outcome of Tasks 1 - 3. If gaps are identified under Task 2 and appropriate research needed to inform the gaps are also 1identified under Task 3, NRG expects that the industry will perform the needed research and provide NRC the data for regulatory decisions. Depending on the outcome of Tasks 2 and 3 and ensuing industry research, the decision-making tool development may be complex and truly involve multi-year, multi-disciplinary long 11

Version Control Date: November 1, 2014 term research. It is expected, however, that the decision making tool may include: (a) Material and component condition after different stressors; (b) Better knowledge of specific degradation and its potential for reducing the design safety margin for the components; (c) Incorporation of plant data into the various material, inspection, and structural integrity evaluation models; and (f) An integration of all these aspects into the regulatory decision making process to consider the risk contribution due to material degradation. Specific subtasks for this task will be established later in this research. PNNL shall investigate the feasibility of developing a modern visualization confirmatory analysis research tool for aging management of safety-significant SSC degradation in NPPs. As currently envisioned, this could provide a knowledge management and strategic planning tool for conducting gap assessments and prioritizing R&D resources related to NPP LTO. This research will leverage the work previously performed by PNNL on the PMMD Information Tool, sponsored by RES. RES/DE would benefit from a R&D gap assessment, strategic planning and knowledge management tool to enhance the tracking, disposition, resolution of technical issues that surface as industry moves towards SLR. Such a database would save staff time in addressing the degradation challenges for NPP passive components, spent fuel pools, and independent spent fuel storage installations (ISFls). The proposed LTO issues visualization tool can incorporate, up-to-date information on critical issues associated with cable, concrete and RPV aging. Work is actively progressing on developing SLR guidance documents with unresolved technical issues arising almost on a daily basis. These could be captured by the proposed service-oriented analytic framework. The existing PMMD database containing detailed information about susceptibility, knowledge, and confidence associated with hundreds of degradation scenarios can be augmented with aging risk indices, when developed by the DOE LWRS research. This will enable a better understanding of serviice life projections of NPP SSC. 5.0 DELIVERABLES AND/OR MILESTONES SCHEDULE Except for Task 1.6 where a draft summary NUREG/CR is stipulated, all deliverables shall be in the form of technical letter reports or alternatives previously discussed and determined acceptable by the COR. Based on the detailed tasks provided in Section 4.0 of this Statement of Work, PNNL shall estimate the number of Figures/Tablles or other copyrighted information from technical journals, etc. and shall incorporate this estimation in the cost proposal in addressing the SOW. PNNL shall also estimate reasonable effort by their technical editing staff in order to provide the NRC tech-edited draft final and final reports. 12

Version Control Date: November 1, 2014 Task Deliverable/Milestone Description (include NRG acceptance Due Date (if any) Number criteria if applicable) All Monthly Letter Status Report (MLSR) 20th day of each month 1.1 PNNL to provide Report 1.1 . DraftTLR to NRC on Subtask (1 .1) NLT 6 months after reviewing anticipated NPP LTO materials degradation and contract award prognostics 1.1 NRC to provide comments to contractor on Report 1.1 on NPP NLT 1 month after LTO materials degradation and prognostics receiving draft Report 1.1 from PNNL 1.1 PNNL to publish TLR Report 1.1 on materials degradation and NLT 1 month after prognostics. Deliver 12 hard copies to the NRC COR, in receiving NRC addition to an electronic file. comments 1.2 PNNL to provide Report 1.2. Draft TLR to NRC on Subtask NLT 8 months after (1 .2) concerning availability of ex-plant material and information contract award 1.2 NRC to provide comments to contractor on Report 1.2 NLT 1 month after concerning availability of ex-plant material and information receiving draft Report 1.2 from PNNL 1.2 PNNL to publish TLR Report 1.2 concerning availability of ex- NLT 1 month after plant material and information. Deliver 12 hard copies to the receiving NRC NRC COR, in addition to an electronic file. comments 1.3 PNNL to provide Report 1.3 (consisting of questionnaire and NLT 10 months after interview results) to NRC on Subtask (1 .3) concerning interest of contract award prospective NRC stakeholders in a systematic approach to harvesting ex-plant materials 1.3 NRC to provide comments to contractor on Report 1.3 NLT 1 month after concerning interest of prospective NRC stakeholders in a receiving Report 1.3 systematic approach to harvesting ex-plant materials from PNNL 1.4 PNNL to provide Report 1.4 (consisting of questionnaire and NLT 14 months after interview results) to NRC on Subtask (1.4) concerning interest of contract award prospective external stakeholders in a systematic approach to harvesting ex-plant materials 1.4 NRC to provide comments to contractor on Report 1.4 NLT 1 month after concerning interest of prospective external stakeholders in a receiving Report 1.4 systematic approach to harvesting ex-plant materials from PNNL 1.5.1 PNNL to provide Report 1.5.1 to NRC on Subtask (1 .5.1) with NLT 16 months after suggested alternatives for creating a prognostic tool to track and contract award resolve critical technical issues for SLR 1.5.1 NRC to provide comments to contractor on Report 1.5.1 NLT 1 month after concerning alternatives for creating a prognostic tool to track receiving Report 1.5.1 and resolve critical technical issues for SLR from PNNL 13

Version Control Date: November 1, 2014 1.6 Summary Report 1.6. Draft NUREG/CR to NRC including NLT 20 months after information from Reports 1.1 through 1.5.2. contract award (Note: At the discretion of COR, a decision may also be made to publish Summary Report 1 as a TLR rather than as an NUREG/CR, depending on the significance of the literature review and research assessment results). 1.6 The Contractor will make a technical presentation to the NRC When the draft staff on Summary Report 1.6 at NRC Headquarters in Rockville, Summary Report 1.6 MD. is delivered to NRC. 1.6 NRC to provide comments to contractor on Summary Report NLT 2 months after 1.6. receiving draft Summary Report 1.6 from PNNL 1.6 DOE Contractor to publish Summary Report 1.6 as NUREG/CR. NLT 2 months after Deliver 12 hard copies to the NRC COR, in addition to an receiving NRC electronic file. comments Task 2 is optional pending outcome of Task 1. 2 PNNL to provide Report 2 Draft TLR to NRC based on results NLT 24 months after from Subtask (2.1) concerning technical gap identification and original contract award subtask (2.2) determination of significance and disposition of gaps 2 NRC to provide comments to contractor on Report 2 concerning NLT 1 month after technical gap identification, significance, and disposition receiving draft Report 2 from PNNL 2 PNNL to publish TLR Report 2 technical gap identification, NLT 1 month after significance, and disposition. Deliver 12 hard copies to the NRC receiving NRC COR, in addition to an electronic file. comments Task 3 is optional pending outcome of Task 2 3.1 PNNL to provide Report 3.1 Draft TLR to NRC based on results NLT 46 months after from Subtask (3.1) concerning specific laboratory contract award experimentation and analytical model development 3.1 NRC to provide comments to contractor on Report 3.1 NLT 1 month after concerning specific laboratory experimentation and analytical receiving draft Report model development 3.1 from PNNL 3.1 PNNL to publish TLR Report 3.1 concerning specific laboratory NLT 1 month after experimentation and analytical model development. Deliver 12 receiving NRC hard copies to the NRC COR, in addition to an electronic file. comments 3.2 PNNL to provide Report 3.2 Draft TLR to NRC reviewing NLT 46 months after adequacy of existing codes and standards for SLR contract award 3.2 NRC to provide comments to contractor on Report 3.2 reviewing NLT 1 month after adequacy of existing codes and standards for SLR receiving draft Report 3.2 from PNNL 3.2 PNNL to publish TLR Report 3.2 reviewing adequacy of existing NLT 1 month after codes and standards for SLR. Deliver 12 hard copies to the receiving NRC NRC COR, in addition to an electronic file. comments Task 4 is optional pending outcome of Task 1 and partially pending on Task 2 and 3. 14

Version Control Date: November 1, 2014 4 PNNL to provide Report 4 Draft TLR to NRC documenting NLT 46 months after development of prognostic tool to track and resolve critical SLR contract award technical issues 4 NRC to provide comments to contractor on Report 4 reviewing NLT 1 month after development of prognostic tool to track and resolve critical SLR receiving draft Report technical issues 3.2 from PNNL 4 PNNL to publish TLR Report 4 reviewing development of NLT 1 month after prognostic tool to track and resolve critical SLR technical issues receiving NRC R. Deliver 12 hard copies to the NRC COR, in addition to an comments electronic file. 6.0 TECHNICAL AND OTHER SPECIAL QUALIFICATIONS REQUIRED Specific qualifications for this effort include senior materials engineers and metallurgists who have in-depth knowledge of reactor pressure vessel and core internal materials subjected to irradiation and stress at elevated temperature, and effects of water chemistry on structural reactor materials. The personnel involved should have in-depth experience, knowledge, and demonstrated contributions in the areas of mechanical deformation, material degradation phenomena, such as corrosion, stress corrosion cracking and irradiation effects. The contract personnel should be well-versed in the use of nuclear power plant ASME B&PV Codes and Standards, Industry Guidance Documents, such as those of NEI, EPRI, NRC's Regulatory Guides and NRC's License Renewal Guidance Documents (such as NUREGs 1800, 1801, and 1950) Information Notice (IN), Regulatory Issue Summary (RIS), Generic Letter (GL), Generic Issue (GI) for licensing review by the NRC staff. The contract personnel should also be aware of the safety evaluation reports (SER) written by the NRC staff on industry guidance documents, as applicable. The contract personnel should have previous experience developing appropriate software architecture for proposed R&D planning tool. 15

Version Control Date: November 1, 201 4 7.0 ESTIMATED LABOR CATEGORIES AND LEVELS OF EFFORT Task Labor Category FY15 FY16 FY17 FY18 FY19 Total (hours) (hours) (hours) (hours) (hours) 1 Project Manager 30 15 15 60 1 Senior Key Staff 30 15 15 60 1 Key Staff 75 30 30 135 1 Support Staff 35 30 30 95 2 Project Manager 50 50 100 2 Senior Key Staff 50 50 100 2 Key Staff 100 100 200 2 Support Staff 40 40 80 3 Project Manager 100 100 90 40 330 3 Senior Key Staff 100 100 90 40 330 3 Key Staff 260 260 180 80 780 3 Support Staff 40 40 50 20 150 4 Project Manager 75 60 135 4 Senior Key Staff 75 60 135 4 Key Staff 210 170 380 4 Support Staff 60 55 115 TOTAL 170 830 830 830 525 3185 Task Order Labor Breakdown FY15 FY16 FY17 FY18 FY19 Labor Category Total (hours) (hours) (hours) (hours) (hours) Project Manager 30 165 165 165 100 625 Senior Key Staff 30 165 165 165 100 625 Key Staff 75 390 390 390 250 1495 Support Staff 35 110 110 110 75 440 Total 170 830 830 830 525 3185 16

Version Control Date: November 1, 2014 8.0 MEETINGS AND TRAVEL The PNNL Principal Investigator and one other engineer shall visit the NRC Headquarters in Rockville, MD and present the overall research outcome to the staff and share in technical discussions. Any suggestions from the staff, as appropriate, may be considered for the final report by the Pl. No other domestic or foreign travel is permitted under the initial scoping study. 9.0 REPORTING REQUIREMENTS PNNL is responsible for structuring the deliverable to follow agency standards. The current agency standard is Microsoft Office Suite 2010. The current agency Portable Document Format (PDF) standard is Adobe Acrobat 9 Professional. Deliverables shall be submitted free of spelling and grammatical errors and conform to requirements stated in this section. Monthly Letter Status Reports In accordance with Management Directive 11.7, NRC Procedures for Placement and Monitoring of Work with the U.S. Department of Energy, PNNL shall electronically submit a Monthly Letter Status Report (MLSR) by the 20th day of each month to Amy Hull, the Contracting Officer Representative (COR), to Matthew Hiser and Joseph Kanney, the technical monitors, with copies to the Contracting Officer (CO) and the Office Administration/Division of Contracts to ContractsPOT.Resource@nrc.gov. If a project is a task ordering agreement, a separate MLSR shall be submitted for each task order with a summary project MLSR, even if no work has been performed during a reporting period. Once NRC has determined that all work on a task order is completed and that final costs are acceptable, a task order may be omitted from the MLSR. MLSR should be distributed additionally to the Chief, Corrosion and Metallurgy Branch , RES, the Director, Division of Engineering, RES. Other required distribution will be communicated at the start of this research program. The MLSR shall include the following: agreement number; task order number, if applicable; job code number; title of the project; project period of performance; task order period of performance, if applicable; COR's name, telephone number, and e-mail address; full name and address of the performing organization; principal investigator's name, telephone numb,er, and e-mail address; and reporting period. At a minimum, the MLSR shall include the information discussed in Attachment 1. The preferred MLSR format can also be found in Attachment 1. 10.0 PERIOD OF PERFORMANCE The estimated period of performance for this work is 48 months from date of agreement award. The expected contract beginning date is September 1, 2015. 11.0 CONTRACTING OFFICER'S REPRESENTATIVE The COR monitors all technical aspects of the agreement/task order and assists in its administration. The COR is authorized to perform the following functions: assure that the DOE Laboratory performs the techn ical requirements of the agreement/task order; perform inspections necessary in connection with agreement/task order performance; maintain written and oral communications with the DOE Laboratory concerning technical aspects of the agreement/task order; issue written interpretations of technical requirements, including 17

Version Control Date: November 1, 201 4 Government drawings, designs, specifications; monitor the DOE Laboratory's performance and notify the DOE Laboratory of any deficiencies; coordinate availability of NRC-furnished material and/or GFP; and provide site entry of DOE Laboratory pe rsonnel. Contracting Officer's Representative Name: Dr. Amy 8 . Hull Agency: U.S. Nuclear Regu latory Commission Office: Office of Nuclear Regulatory Research Mail Stop: CS-05-C07M Washington, DC 20555-0001 E-Mail: amy.hull@nrc.gov Phone: 301-251-7656 Alternate Contracting Officer's Representative Name: Matthew Hiser Agency: U.S. Nuclear Regu latory Commission Office: Office of Nuclear Regulatory Research Mail Stop: CS-05-C07M Washington, DC 20555-0001 E-Mail: Matthew.Hiser@nrc.gov Phone: 301-251-7601 12.0 MATERIALS REQUIRED (TYPE N/A IF NOT APPLICABLE) N/A 13.0 NRC-FURNISHED PROPERTY/MATERIALS PNNL will transfer NRC furnished property and materials acquired under previous contracts (i.e., JCN N6029, N6907) to this task order. NRC will provide additional information from EMDA and SLR databases. 14.0 RESEARCH QUALITY (TYPE NIA IF NOT APPLICABLE) The quality of NRC research programs are assessed each year by the Advisory Committee on Reactor Safeguards. Within the context of their reviews of RES programs, the definition of quality research is based upon several major characteristics: Results meet the objectives (75% of overall score) Justification of major assumptions (12%) Soundness of technical approach and results (52%) Uncertainties and sensitivities addressed ( 11 % ) Documentation of research results and methods is adequate (25% of overall score) Clarity of presentation (16%) Identification of major assumptions (9%) It is the responsibility of the DOE Laboratory to ensure that these quality criteria are adequately addressed throughout the course of the research that is performed. The NRC COR shall review all research products with these criteria in mind. 18

Version Control Date: November 1, 2014 15.0 STANDARDS FOR CONTRACTORS WHO PREPARE NUREG-SERIES MANUSCRIPTS (TYPE N/A IF NOT APPLICABLE) The U.S. Nuclear Regulatory Commission (NRC) began to capture most of its official records electronically on January 1, 2000. The NRC will capture each final NUREG-series publication in its native application. Therefore, please submit your final manuscript that has been approved by your NRC Project Manager in both electronic and camera-ready copy. The final manuscript shall be of archival quality and comply with the requirements of NRC Management Directive 3.7 "NU REG-Series Publications." The document shall be technically edited consistent with NUREG- 1379, Rev. 2 (May 2009) "NRC Editorial Style Guide." The goals of the "NRC Editorial Style Guide" are readability and consistency for all agency documents. All format guidance, as specified in NUREG-0650, "Preparing NU REG-Series Publications," Rev. 2 (January 1999), will remain the same with one exception. You will no longer be required to include the NU REG-series designator on the bottom of each page of the manuscript. The NRC will assign this designator when we send the camera-ready copy to the printer and will place the designator on the cover, title page, and spine. The designator for each report will no longer be assigned when the decision to prepare a publication is made. The NRC's Publishing Services Branch will inform the NRC Project Manager for the publication of the assigned designator when the final manuscript is sent to the printer. For the electronic manuscript, the Contractor shall prepare the text in Microsoft Word, and use any of the following file types for charts, spreadsheets, and the like. File Types to be Used for NUREG-Series Publications File Type File Extension MicrosoftWord .doc Microsoft PowerPoint .ppt MicrosoftExcel .xis MicrosoftAccess .mdb Portable Document Format .pdf This list is subject to change if new software packages come into common use at NRC or by our licensees or other stakeholders that participate in the electronic submission process. If a portion of your manuscript is from another source and you cannot obtain an acceptable electronic file type for this portion (e.g., an appendix from an old publication), the NRC can, if necessary, create a tagged image file format (file extension.tit) for that portion of your report. 19

Version Control Date: November 1, 2014 Note that you should continue to submit original photographs, which will be scanned, since digitized photographs do not print well. If you choose to publish a compact disk (CD) of your publlication, place on the CD copies of the manuscript in both (1) a portable document format (PDF); (2) a Microsoft Word file format, and (3) an Adobe Acrobat Reader, or, alternatively, print instructions for obtaining a free copy of Adobe Acrobat Reader on the back cover insert of the jewel box. 16.0 OTHER CONSIDERATIONS (TYPE N/A IF NOT APPLICABLE) References

1. Bond LJ, SR Doctor, and TT Taylor. 2008. Proactive Management of Materials Degradation -A Rev;ew of Principles and Programs. PNNL-17779, Pacific Northwest National Laboratory, Richland, WA.

2. Bond, LJ, TT Taylor, SR Doctor, AB Hull, and SH Malik, (2008) Proactive Management of Materials Degradation for nuclear power plant systems. Proc. Int. Cont. Prognostics and Health Management 2008, Denver, CO, October 6-9. IEEE Reliability Society,# OP-20-01 120

3. Chopra, OK, et al, Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel, Rev. 0, FCRD-USED-2012-000119, 2012.

4. EPRI 3002000576, Long-Term Operations: Assessment of R&D Supporting AMPs for LTO, Aug. 2013 (80pp).

5. NEI, Roadmap for Subsequent License Renewal, Dec. 2013. (45pp)

6. NEI, Second License Renewal Roadmap, May 2015. (22pp).

7. NUREG/CR-6923, Expert Panel Report on Proactive Materials Degradation Assessment, 2007 (3895pp, ML063520517) 8 . NUREG/CR-7153, Expanded Materials Degradation Assessment, 5 volumes, October 2014 (861pp) 9 . SECY-14-0016, Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal, January 31, 2014 (25pp)

10. Taylor, WB, CE Carpenter, KJ Knobbs, S Malik, Using Technology to Support Proactive Management of Materials Degradation for the U.S. Nuclear Regulatory Commission, Proceedings of the ASME Pressure Vessels & Piping Division/K-PVP Conference, PVP 2010, July 18-22, 2010. Bellevue, WA, USA. Paper PVP2010-26063.

11 . The Scalable Reasoning System: Lightweight Visualization for Distributed Analytics, IEEE Symposium on Visual Analytics Science & Technology, 978-1-4244-2935-6/08 Access to Non-NRC Facilities/Equipment (Type NIA if not applicable) NIA Applicable Publications (Type N/A if not applicable) NIA 20

Version Control Date : November 1, 2014 Controls over document handling and non-d isclosure of materials (Type N/A if not applicable) N/A 21

Version Control Date: November 1, 2014 STATEMENT OF WORK NRC Agreement Number NRC Agreement NRC Task Order Number NRC Task Order Modification Modification Number (If Applicable) Number (If Applicable) N/A NEW N/A Project Title PARENT 2, Program to Assess the Reliability of Emerging NOE Techniques and Results Job Code Number B&R Number DOE Laboratory Pacific Northwest National Laboratory (PNNL) NRC Requisitioning Office Nuclear Regulatory Research (RES) NRC Form 187, Contract Security and Classification Requirements D Involves Proprietary Information 0 Applicable D Involves Sensitive Unclassified [8J Not Applicable C8] Non Fee-Recoverable Fee-Recoverable (If checked, complete a ll applicable sections below) Docket Number (If Fee-Recoverable/Applicable) Inspection Report Number (If Fee Recoverable/Applicable) Technical Assignment Control Number (If Fee- Technical Assignment Control Number Description (If Fee-Recoverable/Applicable) Recoverable/Applicable)

1.0 BACKGROUND

For over the past 30 years, NRG has maintained active research programs to generate confirmatory data for independent safety evaluations of proposed industry Code actions and inspection relief requests related to nondestructive evaluation (NDE) and in-service inspection (ISi). Earlier NRG-supported work at PNNL related to the proposed project, such as the Program for the Inspection of Steel Components (PISC), the Program to Inspect Nickel-Alloy Components (PINC) and the Program to Assess the Reliability of Emerging Nondestructive Techniques (PARENT), have provided important insights on parameters that affect primary water stress corrosion cracking (PWSCC) detectability, such as the effects of crack geometry/size, material microstructure and welding defects. Nevertheless, given the complexity of the crack morphology, NRG staff recognizes that key knowledge gaps remain, particularly for potential reactor operation during subsequent license renewal (SLR) up to 80 years. Domestic and international events, in recent years have made it apparent that additional research is needed to address the issue of cracking in welds. Examples of evidences include the operation experience with Palo Verdi bottom-mounted instrumentation (BMI) leak, five 1

Version Control Date: November 1, 2014 missed cracks resulting in leakage at North Anna, and a missed crack in a control rod drive mechanism nozzle in Sharron Harris. The NRC has limited international NOE data for stress corrosion cracking (SCC) under conditions relevant to nuclear power plant (NPP) extended operation and PNNL analysed available information under the auspices of NRC contracts (e.g., JCN N6593, V6286). To date, PARENT (conducted has provided results from round-robin (RR) inspections and international NOE experience that can be used by NRC Program Offices (such as the Office of Nuclear Reactor Regulation (NRR) and the Office of New Reactors (NRO)) in the development of regulatory requirements and by the nuclear industry in the development of international consensus standards, for example, through the ASME Boiler & Pressure Vessel (BPV) Code. The research products of the PARENT RRTs satisfied elements of NRR-2013-09 User Need Request (UNR) related to NOE of pressurized water reactor (PWR) component degradation. The PARENT-generated information related to new emerging techniques and detection of fabrication flaws will be applicable to new builds for which NRO would be the primary user. The research results already accruing from PARENT may prompt changes in codes and standards governing ISi, such as 10CFR50.55a and Reg. Guide 1.147. PINC and PARENT have provided research results in the form of an engineering information technology tool (i.e. Atlas) to support technical justifications for ISi requirements, proven useful to Region-based NRC inspectors who verify the proper implementation of ISi programs. In the context of PINC, fourteen teams from Japan, Korea and Europe participated in RR inspections of dissimilar metal welds (OMWs) and BMI samples. The NRC report NUREG/CR-7019, published in 2010, provided the PINC results to detect and measure the size of cracks in OMWs. This international knowledge base was archived through the information technology tool , the PINC Atlas, on cracking in Alloy 600 and similar nickel-based alloys in NPPs. The public version of the PINC Atlas of crack morphology was also completed in 2010. To date, PARENT applied international RR testing of welded components/samples results to provide valuable insight into the reliability of detection and accuracy of sizing of PWSCC in OMW samples. A total of 23 teams performed 219 inspections for Open tests using 30 procedures. In Blind testing 14 teams performed 71 inspections for a total of 421 flaw observations on OMW, and 77 flaw observations on BMI samples. Previously, under the auspices of NRC contracts (e.g., JCN N6593, V6286), PNNL analyzed the large amount of data generated by participants in the PARENT RR Blind and Open tests. The PARENT follow-on will focus on the RRT results to evaluate various NOE techniques for ISi of OMWs susceptible to PWSCC in PWRs. In-service inspection requirements for nickel-base alloys iin the primary system are found in Section XI of the ASME Boiler and Pressure Vessel Code, referenced in Title 10 of the Code of Federal Regulations, Part 50.55a, as well as approved Code Cases. The technical bases for the inspection requirements are, in part, derived by NOE testing of samples and side specific mock-ups with electrical discharge machining (EOM) or laser notches, laboratory prepared PWSCC growth flaws or with simulated cracks implanted or growth by thermal cycling. Understanding the causes and control of degradation mechanisms, such as PWSCC, forms the basis for developing aging management programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSC) during the period of extended operation. The resolution to these issues should provide reasonable assurance of safe operation of the components in the scope of license renewal during both the first (40-60 years) 2

Version Control Date: November 1, 201 4 period and the second (60-80 years) period of extended operation (PEO). In that sense, the ongoing Program to Assess the Reliability of Emerging NOE Technology addresses both aging management of passive components under the license renewal rule, 10 GFR 54, as well as maintenance of active components covered by the maintenance rule, 10GFR50.65. 2.0 OBJECTIVES PARENT-2 has three major objectives as reflected in Sections 3 - 5 of this statement of work (SOW):

• Provide the experimental data and correlations necessary for the NRG staff to independently evaluate licensees' ISi programs for assessing the integrity of DMWs
• Evaluate current and emerging NOE methods that licensees may be planning to apply for ISi of passive components
• Review and update the format and the technical basis used in developing the information database for Atlas.

3.0 SCOPE OF WORK In the proposed work, the analysis of open testing results will assess the capability of emerging NOE methods for detecting PWSGG at early stages and evaluate techniques suitable for monitoring degradation during reactor operation. In addition, these testing results have data images so that individual NOE responses will be analysed. The further analysis of Blind test results will evaluate the reliability of established NOE techniques and will assess current issues on the uncertainty of the depth-sizing abilities of NOE techniques in large-bore (Reactor inlet and outlet piping) DMWs including welds with smooth ID surfaces. The preceding PARENT activities (e.g., V6286), were successful in answering many questions about the effectiveness of some techniques at finding cracks in, particularly DMWs. However, not all issues were addressed in sufficient detail. The international participants of PARENT defined further the anticipated work to be completed withi n the scope of PARENT follow-on work. PARENT members recently identified a limited scoped, timely, and focused RRT matrix to address specific technical issues. This includes more focus on real flaw evaluation. The general tasks for this SOW and their duration are described in Table 1. Table 2 provides a high-level summary of the written products (generally technical! letter report (TLR) or concise analytical white paper (WP)) expected associated with information gained from subtasks referenced from Task 1, Task 2, and Task 3. Table 1: PARENT-2 Task Description and Duration Task Task Title/Description Duration (Months) Task 1 Support to NRG for PARENT activities and follow-on program 36 Task 2 Extended Research Studies on NDE Effectiveness 36 Task 3 Information Tool Development (Atlas) 36 3

Version Control Date: November 1, 2014 Table 2: Summary of PARENT-2 Written Deliverables ID Subtask Title/Description Due TLR 1.1.1 1.1.1 Review for Atlas Needs and Identification of Technical Data Gaps FY16 TLR 1.1.2 1.1.2 Confirmatory Research to Address Gaps Related to NOE of DMW FY 16 TLR 1.1.3 1.1.3 Recommended Laboratory Experiments and Analytical Model FY16 Development TLR 1.1.4 1.1.4 Development of International NOE Program Proposal and Protocol for FY16 RR Tests WP1.1 .5 1.1.5. Analysis of results from preliminary scoping study of International NOE FY17 2.1.1 Blind RRTs of BMI Proposal and Protocol with cost estimation (J groove weld optional), WP1.1.6 1.1.6. Analysis of results from preliminary scoping study of International NOE FY17 2.2.2 Open RRTs of CASS Proposal and Protocol with cost estimation (with narrow weld optional) WP 1.1.7 1.1.7. Analysis of results from preliminary scoping study for international FY17 2.3.3 NOE RRT proposal for confirmatory narrow gap welds (with narrow weld repairing optional) TLR 2.1.1 1.1 .5, Status of test plans for both additional BMI testing, and for blind testing FY17 2.1.1 for promising open testing techniques, including the results of technique level analysis of blind testing data Input for reviewed NUREG TLR 2.2.1 1.1 .7, Status of additional BMI testing related to peening (optional) and the FY16 2.2.1 blind test assessment of open techniques from PARENT Input for FY17 reviewed NUREG (opt) TLR 2.2.2 1.1 .6, status of additional Open NOE CASS RR testing (optional) and then FY17 2.2.2 the blind test assessment of open techniques from PARENT TLR 2.2.3 1.1.6, Results of implementation of Open NOE CASS RR confirmatory tests FY18 2.2.3 TLR 2.3.1 1.1.4, Promising Emerging Techniques from PARENT Open Testing FY16 2.3.1 Techniques for Blind Assessment." lnQut for reviewed NUREG TLR 2.3.3 1.1.7, Open NOE Narrow gap welds RR confirmatory tests FY18 2.3.3 4.0 SPECIFIC TASKS Task 1 - Support to NRC for PARENT and Follow-on Program 4

Version Control Date: November 1, 2014 PNNL shall support the NRC contracting officer representative (COR) with both an extensive scoping study (Task 1.1) and with implementing and maintaining the international cooperative research project PARENT. This is Task 1.2. Task 1.1: Scoping Study PNNL shall conduct the Task 1.1 scoping study and provide all resources necessary to accomplish the subtasks and deliverables. Task 1.1 shall be performed in stages. Decision on further execution of other subtasks ( 1.1.2-1 .1.4) will be made after the end of the subtask 1.1.1 (Table 3). Table 3. Summary of Task 1.1. Scoping Study Subtask Subtask Title/Description Duration (Months) 1.1 .1 Conduct scoping Study and NDE Technical Information Review for NLT 4 months Atlas Needs and Identification of Technical Data Gaps; submit ACA related TLR 1 .1. 1 1.1.2 Determine Significance and Disposition of Technical Gaps Related NLT 7 months to NDE of DMW (J groove and Narrow welds (optional); submit ACA related TLR 1 .1. 2 1.1 .3 Recommend Laboratory Experiments and Analytical Model NLT 10 Development for Confirmatory Research Addressing Technical months ACA Gaps- (optional) ); submit related TLR 1.1.3 1.1.4 Develop International NDE Program Proposal and Protocol for NLT 13 Round Robin Tests (RRTs) (optional) ); submit related TLR 1.1.4 months ACA 1.1.5 Conduct Scoping Studies for International NOE Blind RRTs of BMI NLT 15 Proposal and Protocol with Cost Estimation (J groove weld months ACA peening optional), (more detailed information under subtask 2.1.1) 1.1.6 Conduct Scoping Studies for International NOE Open RRTs of NLT 18 Cast Austenitic Stainless Steel (CASS) Proposal and Protocol with months ACA Cost Estimation (with narrow weld optional),( more detailed information under subtask 2.2.2) 1.1.7 Conduct Scoping Studies for International NOE RRT Proposal for NLT 20 Confirmatory Narrow Gap Welds (with narrow weld repairing months ACA optional), (more detailed information under subtask 2.2.1) This scoping study will be conducted, as per tasks detailed below for subtasks 1.1.1 and 1.1.2. A decision on further optional research outlined in subtasks 1.1 .3, and 1 .1.4 will be made after completion of subtask 1.1.1 depending on the recommendation from the conclusion of the preceding tasks. Subtasks 1.1.5, 1.1.6, and 1.1.7 are each precursors to subtasks in Task 2. 5

Version Control Date: November 1, 2014 Subtask 1. 1. 1 - Gap Identification PNNL shall identify specific information from the execution of Subtask 1.1.1 and document these gaps. In identifying the gaps, PNNL shall include an examination of the current ASME B&PV Code or other industry practices that the NRC has endorsed with respect to cracking during the NPP PEO. TLR 1.1.1 "Review for Atlas Needs and Identification of Technical Data Gaps" will be drafted at the end of this subtask. Subtask 1. 1.2- Determine Significance and Disposition of Technical Gaps PNNL shall determine whether or not there are any technical gaps from the execution of Subtask 1.1.1. If there are no gaps and if it is determined that the current ASME Code or other US industry or international practice ensure that the design margin for components are adequate, NRC COR has the option of recommending termination of Task 1.1. If specific information and technical gaps are identified then proceed to Subtask 1.1.3 after getting approval from the NRC Contract Officer (CO). Subtask 1. 1. 3 - Recommend Specific Laboratory Experiments and Analytical Model Development PNNL shall work with the PARENT NOE Task Group experts and NRC subject matter experts (SMEs) to recommend specific laboratory experimentation and analytical model development, which may address the information gap identified in Subtask 1.1 .1. Subtask 1.1.4- Develop international program proposal for confirmatory tests If novel NOE methods become available and are identified by the time of subtask inception, PNNL shall implement this Subtask to independently confirm the licensee's technical basis for long-term operation (LTO) and recommend ISi technology which will be suitable to identify the progression of incipient cracking. A deliverable related to this subtask is TLR 1.1.4 which is further referenced in subtasks 2.1.3 and 2.3.2. Subtask 1.1.5- Conduct Scoping Studies for International NOE Blind RRTs of BM/ Proposal and Protocol with cost estimation (J groove weld peening optional) PNNL shall investigate the viability of applying NOE J-groove weld RRT proposal for confirmatory tests. If novel NOE methods become available by this time for J-groove weld examination, PNNL shall implement this Subtask to independently confirm the licensee's technical basis for long term operation (LTO) and recommend ISi technology. The research shall attempt to identify a monitoring procedure to detect size-based cracking indicators and thus enable a peening-based methodology to prevent crack progression. PNNL shall assist the NRC COR in selecting test specimens for peening and Blind RRTs. Planning for this research is addressed as Subtask 2.1.1 and 2.1.4 (optional) Subtask 1.1.6 - Conduct Scoping Studies for NOE CASS RRT proposal for confirmatory tests If novel NOE methods become available by this time for CASS (or narrow weld) examination (EPRI RRTs), PNNL shall implement this Subtask to independently confirm the licensee's technical basis for LTO and recommend ISi technology. The research shall determine how to prevent progressing cracking by detecting the indication changes resulting from size of cracks. 6

Version Control Date: November 1, 201 4 PNNL shall assist the NRC COR in selecting test specimens for weld repairing and Open RRTs. Planning for this research is addressed as Subtask 2.2.2 (optional) Subtask 1. 1. 7 - Conduct Scoping Studies for NOE RRT proposal for confirmatory tests of narrow gap welds If novel NOE methods become available by this time for tlhe narrow gap weld examination (EPRI, Areva's Tests for EPR reactors), PNN L shall implement this Subtask to independently confirm the licensee's technical basis for LTO and recommend ISi technology. The research shall determine how to identify progressing cracking prevention by repairing of flaws detected with emerging technique for crack location and sizing. PNNL shall assist the NRC COR in selecting test specimens for weld repairing and Open RRTs. Planning for this research addressed as Subtask 2.2.1 and 2.3.2 (optional). Task 1.2: Support COR in maintaining effective cooperation in PARENT The NRC contracting officer representative (COR) requires support in implementing and maintaining the international cooperative research project PARENT. As part of this task, PNNL shall organize two meetings per year for the PARENT participants. PNNL shall attempt to ensure that the rotating meeting locations include the home country or continent of each group participating in the program. The next PARENT meeting is scheduled to be held at PNNL, October 26-30, 2015. Other meetings proposed by the international PARENT steering committee are tabulated in Section 8.0 of this SOW. PNNL shall aid the NRC COR in identifying companies and institutes that are interested in participating in the international cooperative. After key individuals have been identified at those organizations, assistance will be provided in coordinating meetings and incorporating the in-kind contributions of program participants into reports and work products for the program. PNNL shall provide presentations as directed by the NRC and send appropriate participants to the PARENT meetings. PNNL shall provide expert advice to the NRC staff regarding operational events related to the PWSCC cracking and leak of welds at nuclear power plants. Through PNNL's continu ing participation in the international PARENT meetings, workshops, codes and standards activities, PNNL staff already understands NOE/ISi issues and advancements in NOE technologies that could addr,ess problems arising in operating nuclear power plants. Task 2 - Extended Research Studies on NDE Effectiveness In this task, PNNL shall assign and carry out additional round-robin tests to enhance BMI test results and shall perform blind test assessment of open techniques from PARENT participants. In addition, PNNL shall perform a technique-level analysis of blind test data from PARENT participants. PNNL shall participate as lead technical staff on the PARENT NOE task group (TG-NDE), the data analysis group (DAG), and shall function as the invigilator for participating US teams. PNNL shall help design, plan and schedule additional round robin testing activities. In addition, PNNL shall assist in the design and procurement of test blocks necessary for additional round robin testing. PNNL shall analyze NOE test data from the additional round-robin tests. The analysis will include frequency of detection as a means of estimating probability of detection and estimation of depth sizing bias and root mean squared error (RMSE). PNNL shall 7

Version Control Date: November 1, 2014 work with the TG-NDE in identifying teams, techniques, and procedures for the BMI testing and blind evaluation of open techniques from PARENT. Associated with Task 2, PNNL shall prepare six TLRs. In FY17, PNNL shall develop TLR 2.1.1 describing status of test plan for additional BMI testing, status of plan for blind testing for promising open testing techniques from PARENT, and including the results of technique level analysis of blind testing data from PARENT. This is defined further in Table 4. In FY17, PNNL shall develop TLR 2.2.1 describing the status of additional BMI testing related to peening (optional) and the blind test assessment of open techniques from PARENT. This is described further in Table 5. In FY18, PNNL shall develop TLR 2.2 .2 describing the status of additional Open NOE CASS RR testing (optional) and the blind test assessment of open techniques from PARENT. This is also described further in Table 5. IN FY18, PNNL shall prepare TLRs 2.2.3, 2.3.1, and 2.3.3 as shown in Table 1. Task 2. 1: Enhancement of BM/ Test Results The objective of this task is to enhance test results for BMI test blocks in PARENT. Limited testing was performed on BMI test blocks in PARENT (ten inspections of J-groove weld surfaces and two inspections of tube IDs) in comparison to the DMW test blocks. As a consequence, conclusions that may be drawn for BMI test results in PARENT are limited, as well. In the earlier PINC and PARENT studies, it was noted that no techniques were applied with the capability to depth size flaws in the J-groove weld region. In addition, the PINC round robin tests did not achieve strong evaluation of the effectiveness of examinations of the interior of BMI penetration tubes. Only two teams examined the interiors of three flawed tubes . In PARENT, limited testing was conducted on tube IDs. Three main subtasks are proposed: Subtask 2.1 .1 - Combining PINC and PARENT BMI test data to improve statistical significance of results Subtask 2.1.2- Develop testing plan for additional detection and depth sizing evaluation of flaws in j-groove weld materials and tube IDs Subtask 2.1.3 - Assessing methods for detection and depth sizing flaws in j-groove weld materials and tube IDs Initial steps for subtask 2.1.2 would include reviewing BM I test blocks in inventory to determine the relevancy and adequacy of test block geometries, materials, and flaws. Another required initial step will be to develop testing objectives and the testing plan (e.g. to perform blind or open testing). Table 4 below further summarizes Task 2.1 in terms of describing subtasks and their duration. The explicit deliverables are prefaced with italicized alphanumeric annotation in square brackets. 8

Version Control Date: November 1, 2014 Table 4. Summary of Task 2.1., Enhancement of BMI Test Results Subtask Subtask Title/Description Duration (Months) 2.1.1 Combining PINC and PARENT BMI test data to improve statistical NLT 1 months significance of results in Final report. after contract award (ACA) [2.1.1. a] PNNL shall provide draft Final Report to NRC on Task 1 2.1 .1 for NRR review with improved statistical results [2.1.1. b] NRC to provide comments to contractor on TLR 2.1 .1. 1 The NRC meeting (March 2016) will discuss the Final report 2.1.2 Develop testing plan for additional detection and depth sizing 1 evaluation of flaws in j-groove weld materials and tube IDs and include test plan in draft TLR 1.1.3 [2.1.2. a] PNNL to provide draft TLR 1.1.3 to NRC with NLT 9 months Recommended Laboratory Experiments and Analytical Model ACA Development (optional) [2.1.2. b] NRC to provide comments to contractor on T LR 1.1.3. NLT 1 month The last PARENT-12 meeting (July 2016) will discuss the test after receiving plan TLR 1.1.3 2.1.3 Assessing methods for detection and depth sizing flaws in j- NLT 12 groove weld materials and tube IDs (optional) months ACA [2.1.3. a] PNNL to provide input for TLR 1.1.4 to NRC on 2 Development International NOE Program Proposal and Protocol for RR (optiona l) to NRC for NRR review [2. 1. 3. b] NRC to provide comments to contractor on TLR 1.1.4. NLT 1 month The new Program kick off meeting (November 2016, NRC DC) after receiving will discuss the TLR 1.1.4 International NOE Program Proposal TLR 1.1.4 and Protocol for RR (optional) 2.1.4 PNNL to Plan tests for International NOE Blind RRTs of BMI NLT 15 Proposal and Protocol with cost estimation ( as mentioned in months ACA subtask 1.1.5)

2. 1.5 PNNL to implement International NOE Blind RR tests of BMI NLT 24 Proposal and Protocol with cost estimation ( as mentioned in months ACA subtask 1.1.5) 9

Version Control Date: November 1, 2014 Task 2.2: Perform analysis of blind test data from PARENT at the technique level The current analysis of PARENT blind test data has been performed at the procedure level (procedures can consist of multiple techniques). This has resulted in limited eddy current technology (ECT) data for analysis (data obtained from one procedure - ECT.135) and has limited comparisons between the "Quick" blind test results and results from the rest of blind testing . Therefore, conducting additional analysis of PARENT blind data at the technique level will provide more data to supplement existing ECT results as ECT data from procedures UT.ECT.144 and UT.TOFO.ECT.101 may be evaluated along with ECT data from ECT.135. Also, a technique level analysis will enable more direct comparisons between the "Quick" blind study and the rest of the blind testing as the UT and PAUT data from the "Quick" blind test procedures UT.PAUT.108 and UT.PAUT.126 can be compared to data obtained from UT and PAUT procedures in the rest of blind testing. Table 5 below further summarizes Task 2.2 in terms of describing subtasks and their duration. The explicit deliverables are prefaced with italicized alphanumeric annotation in square brackets. Table 5. Summary of Task 2.2., Analysis of PARENT blind test data at the technique level, Subtask Subtask Title/Description Duration (Months) 2.2.1 Review test data to conduct additional analysis of PARENT blind 1 data at the technique level resulting in TLR 2.2.1 [2.2.1 a] PNNL to provide the Blind Test Final Report to NRC NLT 2 months for NRR review with additional analysis of PARENT blind data at ACA the technique level (TLR 2.2. 1) [2.2.1 b] NRC to provide comments to contractor on Blind Test NLT 1 month Final Report. The NRC meeting (March 2016) will discuss the after receiving Final report TLR 2.2.1 2.2.2 PNNL to prepare plan for Open NOE CASS RR confirmatory NLT 15 tests (as mentioned previously in subtask 1 .1.6) and submit as months ACA TLR 2.2.2 2.2.3 PNN L implement Open NOE CASS RR confirmatory tests (as NLT 24 mentioned previously in subtask 1.1.6) and submit as TLR 2.2.3 months ACA Task 2.3: Conduct Blind Test Assessment of Promising Open Testing Techniques As reactors age, an increasing number of components are becoming vulnerable to stress corrosion cracking . With new reactor construction, it is possible that the new materials used will experience new forms of materials degradation. Some forms of degradation, such as stress corrosion cracking, are typified by a long incubation period followed by rapid crack growth and provide a challenge to periodic inspections using standard NOE techniques. To deal with rapidly-growing forms of degradation the nuclear NOE community needs to either find a new 10

Version Control Date: November 1, 2014 NOE technique that is able to detect the degradation precursors or use continuous online monitoring. Open testing is useful for performing a basic capability assessment of novel and emerging NOE technologies but the testing format does not facilitate a realistic measure of detection performance. In addition , bias may exist in sizing results. Conducting a blind test of novel and emerging NOE techniques that exhibited high performance in open testing will enable measurement of detection performance for such techniques and a more accurate estimate of sizing capabilities. Task 2.3.1 - Identify promising emerging techniques from PARENT open testing techniques for blind assessment/Planning for blind test assessment Task 2.3.2 - Execute blind test assessment of promising open testing techniques Table 6 below further summarizes Task 2.3 in terms of describing subtasks and their duration. The explicit deliverables are prefaced with italicized alphanumeric annotation in square brackets. Table 6. Task 2.3, Conduct blind test assessment of promising open testing techniques Subtask Subtask Title/Description Duration (Months) 2.3.1 Combine comments on PARENT Open RRT Final Report and 1 review test data to identify promising emerging techniques, TLR 2.3.1 [2.3.1a] PNNL to provide the Open RRT TLR 2.3.1 to NRC for NLT 2 months NRR review with identification of promising emerging techniques ACA [2.3. 1b] NRC to provide comments to contractor on TLR 2.3.1 NLT 1 month "Promising Emerging Techniques from PARENT Open Testing after receiving Techniques for Blind Assessment." The NRC meeting (March TLR 2.3.1 2016) will discuss the Final report 2.3.2 Develop testing plan for additional detection and depth sizing NLT 12 evaluation of flaws for blind test assessment and include test months ACA plan in draft TLR 1.1.4 on Development International NDE Program Proposal. This is closely related to Subtask 2.1.3. [2.3.2a] PNN L to provide draft TLR 1.1.4 to NRC with NLT 15 Recommended Laboratory Experiments and Analytical Model months ACA Development (optional) [2.3.2b] NRC to provide comments to PNNL on T LR 1.1.4. The NLT 1 month last PARENT-12 meeting (July 2016) will discuss the test plan after receiving TLR 1.1.4 11

Version Control Date: November 1, 201 4 2.3.3 Execute blind test assessment of promising open testing 2 techniques for DMW, BMI, or CASS [2.3.3a] PNN L to provide input for TLR 1.1 .4 to NRC on 2 Development International NOE Program Proposal and Protocol for RR (optional) to NRC for NRR review. [2.3.3b] NRC to provide comments to PNNL on TLR 1.1.4. The NLT 1 month new Program kick off meeting (November 2016 , NRC DC) will after receiving discuss the TLR 1.1.4 International NOE Program Proposal and Report 1.1.4 Protocol for RR (optional) PNNL implement Open NOE Narrow gap welds RR confirmatory NLT 36 tests (as mentioned previously in subtask 1 .1. 7) and submit as months ACA TLR 2.3.3 Task 3 - Information Tool Development (Atlas) According to international agreements governing PARENT collaboration, PNNL is to develop and maintain the PARENT Atlas information tool. PNNL shall add data that is offered by the participants - collecting and organizing it in the PARENT Atlas. PNNL shall build the Atlas, making it a reference tool for NRC staff and PARENT participants. PNNL shall design the Atlas database to contain information (excluding that which is determined to be proprietary data that PARENT participants want protected) on the PARENT test blocks and their artificially-implanted cracks and machined reflectors. This Task 3 addresses issues such as competition of the review and analysis of the Open RRT results and preparation of Atlas data. The project assists in developing the engineering information technology tool (PARENT Atlas) and internal NRC Website necessary to support technical j ustifications for IS i requirements. Task 3. 1: Add and organize documentation of field occurrences of SCC into the PARENT Atlas information tool including the results of metallographic analysis when available. The goal of this effort is to provide a reference database of NOE techniques applied in the field and the types of flaws detected by the NOE techniques. In addition, another objective of this task is to compile metallographic results of field flaws that have been analyzed. The focus is on primary water stress corrosion cracking/internal diameter stress corrosion cracking (PWSCC/IDSCC). The initial step for this task will be to review potentially relevant existing databases to focus on filling information gaps in existing databases. Task 3.2: Compare morphologies of laboratory grown sec flaws with documented characteristics of field sec flaws Accurate representation of field PWSCC/IDSCC flaws in !laboratory studies of NOE performance is necessary to ensure generation of useful results. Knowledge of field PWSCC/IDSCC flaw morphologies is limited to data obtained from a handful of failure analysis reports. It may be possible to supplement this limited set of data pertaining to field PWSCC/IDSCC flaw morphologies through analysis of PWSCC/IDSCC flaws grown in laboratories. Thus, laboratory grown PWSCC/IDSCC flaw morphologies will be compared with field PWSCC/IDSCC flaw 12

Version Control Date: November 1, 201 4 morphologies to confirm the relevancy of laboratory grown flaws for simulating field flaws. In addition, if relevancy is confi rmed, data collected from laboratory flaws can be used to enhance the database obtained from field flaws. Task 3.3: Compare signal responses from different flaw types from open testing data and incorporate into the PARENT Atlas Open testing was conducted using test blocks with a variety of simulated flaw types including weld solidification cracks, EDM notches, laboratory grown stress corrosion cracks, mechanical fatigue cracks, and welding defects. A comparison of NDE responses for the different flaw types will help provide insight with respect to which flaw features are significant for NDE response and which simulated flaw types are most suitable for assessing the performance of specific NDE techniques. The PARENT Atlas information tool provides a convenient means to navigate signal responses an d view comparisons. Task 3.4 Update the PARENT Atlas with information collected as part of Tasks 3.1, 3.2, and 3.3. Table 7 below further summarizes Task 3 in terms of describing subtasks and their duration. The expl icit deliverables are prefaced with italicized alphanumeric annotation in square brackets. Table 7. Summary of Task 3 Subtasks, Information Tool Atlas Subtask Subtask Title/Description Duration (Months)

3. 1.1 Review result of Task 1.1 .1 - Gap Identification and include review 0.5 of NDE Technical Information in Atlas 3.1.2 PNNL to provide Draft presentation to NRC on Task 1.1.1 and NLT 5 months 1.1.2 with Review for of NOE Technical Information for Atlas. ACA 3.1.3 NRC to provide comments to contractor on TLR 1.1.2. The NRC NLT 1 month meeting (March 2016) will discuss the Review of Atlas needs and afteir receiving results of gaps analysis TLR 1.1 .2 3.1.4 Adding and organizing documentation of field occurrences of 1 PWSCC/IDSCC into the PARENT Atlas information tool including the results of metallographic analysis when available.

3.2 Comparison of morphologies of laboratory grown SCC flaws with 2 documented characteristics of field SCC flaws 3.3 Comparison of signal responses from different flaw types from 2 open testing data and incorporate into the PARENT Atlas 3.4 PNNL to provide Draft of PARENT Atlas to NRC for review, to be NLT 8 months discussed at PARENT 12 (July 2016) meeting ACA 13

Version Control Date: November 1, 2014 5.0 DELIVERABLES AND/OR MILESTONES SCHEDULE ALL deliverables shall be in the form of technical letter reports (TLRs), concise authoritative report ("white paper"), or alternatives previously discussed and determined acceptable by the COR. Based on the detailed tasks provided in Section 2.0 of this SOW, PNNL shall estimate the number of Figures/Tables or other copyrighted information from technical journals, etc. and shall incorporate this estimation in the cost proposal in addressing the SOW. PNNL shall also estimate reasonable effort by their technical editing staff in order to provide the NRC tech-edited draft final and final reports. In the table below as in the preceding ones, the Due date is expressed in terms of no later than (NLT) x months after contract awarded (ACA). Task Deliverable/Milestone Description for Task 1 (include NRG Due Date (if any) Number acceptance criteria if applicable) All Monthly Letter Status Report (MLSR) 20th day of each month 1.1.1 PNNL to provide Draft TLR 1.1 .1 to NRC on Subtask (1.1 .1) NLT 2 months ACA Review for Atlas Needs and Identification of Technical Data Gaps 1.1.1 NRC to provide comments to contractor on TLR 1 .1.1 Review NLT 1 month after for Atlas Needs and Identification of Technical Data Gaps. The receiving draft TLR PARENT 12 meeting will discuss the Review results 1.1 .1 from PNNL 1.1.1 PNNL to publish TLR 1.1 .1. Deliver copies to the PARENT NLT 1 month after participants, in addition to an electronic file to the NRC COR receiving NRC comments 1.1.2 PNNL to provide draft TLR 1.1.2 to NRC on Subtask (1.1.2) NLT 5 months ACA concerning Confirmatory Research to Address Gaps Related to NOE of DMW (J groove and Narrow welds optional) 1.1.2 NRC to provide comments to contractor on TLR 1 .1.2. The NRC NLT 1 month after meeting (March 2016) will discuss the Review of Atlas needs receiving draft TLR and results of gaps analysis 1.1.2 from PNNL 1.1.2 PNNL to publish TLR 1.1.2 concerning Confirmatory Research NLT 1 month after Address Gaps Re lated to NOE of DMW. Deliver copies to the receiving NRC PARENT participants, in addition to an electronic file to the NRC comments COR. 1.1.3 PNNL to provide draft TLR 1.1.3 to NRC with Recommended NLT 9 months ACA Laboratory Experiments and Analytical Model Development (optional) 1.1.3 NRC to provide comments to contractor on TLR 1 .1 .3 The last NLT 1 month after PARENT-12 meeting (July 2016) will discuss the Review of receiving TLR 1.1.3 Atlas needs, results of gaps analysis and TLR 1.1 .3 from PNNL 1.1.4 PNNL to provide draft TLR 1.1.4 to NRC on Development of NLT 12 months ACA International NOE Program Proposal and Protocol for RR (optional) 14

Version Control Date: November 1, 2014 1.1 .4 NRC to provide comments to contractor on TLR 1 .1.4 The new NLT 1 month after Program kick off meeting (November 2016, NRC HQ, DC) will receiving TLR 1.1.4 discuss the Review of Atlas needs, results of gaps analysis and from PNNL TLR 1.1.4 International NOE Program Proposal and Protocol for RR (optional} 1.1.5 Provide WP 1.1 .5 analyzing results from preliminary scoping NLT 15 months ACA study of International NOE Blind RRTs of BMI Proposal and Protocol with cost estimation (J groove weld optional), this is input to subtask 2 .. 1.1 1.1.6 Provide WP 1.1 .6 analyzing results from preliminary scoping NLT 18 months ACA study of International NOE Open RRTs of CASS Proposal and Protocol with cost estimation (with narrow weld optional}, this is input to subtask 2 .2.2 1.1.7 Provide WP 1.1 .7analyzing results from preliminary scoping NLT 20 months ACA study for international NOE RRT proposal for confirmatory narrow gap welds (with narrow weld repairing optional}, this is input to subtask 2.3.3 1.2 PNNL to provide support for maintaining PARENT teamwork, Throughout 36 month including but not limited to, preparing materials for semiannual period international meetings and coordinating contributions of partners from international institutes (e.g., in Finland, Japan, Korea, Sweden, Switzerland, U.S.) 2.1.1 PNNL to provide Draft Blind RRT Final TLR 2.1.1 for NRR NLT 3 months ACA review with improved statistical results (this integrates deliverable from subtask 1.1 .5) 2.2.1 PNNL to provide the Blind Test Final TLR 2.2.1 to NRC for NRR NLT 4 months ACA review with additional analysis of PARENT blind data at the technique level (this integrates deliverable from subtask 1.1 .7 about narrow gap welds) 2.2.2 PNNL to provide TLR 2.2.2 describing the status of additional NLT 15 months ACA Open NOE CASS RR testing (optional) and the blind test assessment of open techniques from PARENT. (this integrates deliverable from subtask 1.1.6) 2.2.3 PNNL to provide draft TLR 2.2.3 discussion implementation of NLT 24 months ACA Open NOE CASS RR confirmatory tests (as mentioned previously in subtask 1.1.6) 2.3.1 PNNL to provide the Open RRT TLR 2.3.1 for NRR review with NLT 4 months ACA identification of pr,omising emerging techniques, this is incorporates insights from TLR 1.1.4 2.3.3 PNNL to provide draft TLR 2.3.3 discussion of implementation of NLT 30 months ACA Open NOE Narrow gap welds RR confirmatory tests (as mentioned previously in subtask 1.1. 7) 15

Version Control Date: November 1, 2014 2 The Contractor will make a technical presentation on Summary When the Reports are RRT TLRs. The NRC meeting (March 2016) will discuss the delivered to N RC, NLT Final reports at NRC Headquarters in Rockville, MD. 32 months after contract date 2 PNNL provide all TLRs and WPs from Tasks 1 and 2 to review NLT 2 months after for compilation as possible NU REG/CR. Deliver 5 hard copies receiving NRC to the NRC COR, in addition to an electronic file. comments 3 PNNL to provide Draft presentation to NRC on Task 1.1.1 and NLT 5 months after 1.1.2 with Review of NOE Technical Information for Atlas. original contract award 3 PNNL to provide Draft of PARENT Atlas to NRC for review NLT 8 months ACA The PARENT 12 meeting (July 2016) will discuss the Review results The following tasks are optional pending outcome of Task 1.1. 1.1.3 PNNL to provide WP 1.1.3 to NRC based on results from NLT 9 months ACA Subtask 1.1.3 concerning specific laboratory experimentation and analytical model development 1.1.3 NRC to provide comments to contractor on WP 1.1.3 concerning NLT 1 month after specific laboratory experimentation and analytical model receiving WP development 1.1.3.from PNNL 1.1.3 PNNL and NRC COR to coauthor conference article concerning NLT 1 month after specific laboratory experimentation and analytical model receiving NRC development. . comments 1.1.4 PNNL to provide TLR 1.1.4, rev 1 to NRC on Development NLT 18 months ACA International NOE Program Proposal and Protocol to RES for distribution to OIP and NRR 1.1.4 NRC to provide comments to PNNL on TLR 1.1.4, Rev 1. NLT 1 month after receiving draft Report from PNNL 1.1.4 PNNL to publish TLR 1.1.4, Rev 1.concerning International NOE NLT 1 month after Program Proposal and Protocol. Deliver 10 hard c opies to the receiving NRC NRC COR, in addition to an electronic file. comments 6.0 TECHNICAL AND OTHER SPECIAL QUALIFICATIONS REQUIRED Specific qualifications for this effort include materials engiineers who have in-depth knowledge of reactor materials and stress corrosion cracking. The personnel involved should have in-depth experience, knowledge, and demonstrated contributions in the areas of NOE as pertinent to reactor material degradation phenomena. The PNNL staff should be well-versed in the use of NPP ASME B&PV Codes and Standards, Industry Guidance Documents, such as those of NEI, EPRI, NRC's Regulatory Guides Information Notice (IN), Regulatory Issue Summary (RIS), Generic Letter (GL), and Generic Issue (GI) for licensing review by the NRC staff. The PNNL staff should have previous experience working with the ATLAS information tool. 7.0 ESTIMATED LABOR CATEGORIES AND LEVELS OF EFFORT 16

Version Control Date: November 1, 2014 Task Labor Category FY16 FY17 FY18 Total (hours) (hours) (hours) 1 Project Manager 120 120 100 340 1 Senior Key Staff 64 24 24 112 1 Key Staff 160 160 40 360 1 Support Staff 40 40 40 120 2 Project Manager 120 160 180 460 2 Senior Key Staff 36 80 80 196 2 Key Staff 200 400 520 1120 2 Support Staff 40 40 40 120 3 Project Manager 120 120 120 360 3 Senior Key Staff 20 36 16 72 3 Key Staff 40 40 40 120 3 Support Staff 40 40 40 120 TOTAL 1000 1260 1240 3500 Task Order Labor Breakdown FY16 FY17 FY18 Labor Category Total (hours) (hours) (hours) Project Manager 360 400 400 1160 Senior Key Staff 120 140 120 380 Key Staff 400 600 600 1600 Support Staff 120 120 120 360 Total 1000 1260 1240 3500 8.0 MEETINGS AND TRAVEL The PNNL Principal Investigator and one other senior engineer shall visit the NRC Headquarters in Rockville, MD and present the overall research outcome to the staff and share in technical discussions. Any suggestions from the staff, as appropriate, may be considered for the final report by the Pl. The travel anticipated for this task order is listed in the table below for planning purposes only. Al l travel is subject to the availability of funds and requires written Government approval from the Contracting Officer (CO), unless otherwise delegated to the COR. Foreign travel for the PNNL personnel requires a 60-day lead time for NRC approval. For prior approval of foreign travel, PNNL shall submit an NRC Form 445, "Request for Approval of Official Foreign Travel." NRC Form 445 is available in the MD 11.7 Documents library and on the NRC Web site at: http://www.nrc.gov/reading-rm/doc-collections/forms/. All foreign travel 17

Version Control Date : November 1, 2014 must be first approved by the NRC Director of the Office of International Programs (OIP) and the Director of RES . 18

Version Control Date: November 1, 2014 Task Order Anticipated Travel Location Purpose Travelers Dates Washington, DC NRR/RES Review Meeting 2 March, FY16 (2 days) in conjunction with RIC 2016 , PARENT Atlas demo presentation Zurich, Switzerland PARENT 12, Switzerland 1 Spring/Summer, FY16 (6 Final program meeting days) TBD (likely International PARENT 2 Autumn, FY17 (5 days) Washington, DC) Follow-on Kick-off Program Meeting TBD, Helsinki, International Follow-on 1 Spring/Summer, FY17 (6 Finland Program Meeting VTT with days) STUK/lndustry TBD (Seoul, Korea) International Follow-on 1 Spring, FY 18 (6 days) Program Meeting; KINS with Industry or Universities TBD (likely NRR/RES International 1 Autumn, FY18 (5 days) Washington, DC) Follow-on Program Review Meeting 9.0 REPORTING REQUIREMENTS PNNL is responsible for structuring the deliverable to follow agency standards. The current agency standard is Microsoft Office Suite 2010. The current agency Portable Document Format (PDF) standard is Adobe Acrobat 9 Professional. Deliverables shall be submitted free of spelling and grammatical errors and conform to requirements stated in this section. Monthly Letter Status Reports In accordance with Management Directive 11.7, NRC Procedures for Placement and Monitoring of Work with the U.S. Department of Energy, PNNL shall electronically submit a Monthly Letter Status Report (MLSR) by the 20th day of each month to Dr. louri Prokofiev, the Contracting Officer Representative (COR), and to Stephen E. Cumblidge, the technical monitor, with copies to the Contracting Officer (CO) and the Office Administration/Division of Contracts to ContractsPOT.Resource@nrc.gov. If a project is a task ordering agreement, a separate MLSR shall be submitted for each task order with a summary project MLSR, even if no work has been performed during a reporting period. Once NRC has determined that all work on a task order is completed and that final costs are acceptable, a task order may be omitted from the MLSR. 19

Version Control Date: November 1, 2014 MLSR should be distributed additionally to the Chief, Component Integrity Branch, and the Director, Division of Engineering, RES. Other required distribution will be communicated at the start of this research program. The MLSR shall include the following: agreement number; task order number, if applicable; job code number; title of the project; project period of performance; task order period of performance, if applicable; COR's name, telephone number, and e-mail address; full name and address of the performing organization; principal investigator's name, telephone numb,er, and e-mail address; and reporting period. At a minimum, the MLSR shall include the information discussed in Attachment 1. The preferred MLSR format can also be found in Attachment 1. 10.0 PERIOD OF PERFORMANCE The estimated period of performance for this work is 36 months from date of agreement award. The expected contract beginning date is October 1, 2015. 11.0 CONTRACTING OFFICER'S REPRESENTATIVE The COR monitors all technical aspects of the agreement/task order and assists in its administration. The COR is authorized to perform the following functions: assure that the DOE Laboratory performs the technical requirements of the agreement/task order; perform inspections necessary in connection with agreement/task order performance; maintain written and oral communications with the DOE Laboratory concerning technical aspects of the agreement/task order; issue written interpretations of technical requirements, including Government drawings, designs, specifications; monitor the DOE Laboratory's performance and notify the DOE Laboratory of any deficiencies; coordinate availability of NRG-furnished material and/or GFP; and provide site entry of DOE Laboratory pe rsonnel. Contracting Officer's Representative Name: Dr. louri G. Prokofiev Agency: U.S. Nuclear Regulatory Commission Office: Office of Nuclear Regulatory Research Mail Stop: TWFN-10A36 11555 Rockville Pike Rockville, MD 20852-2738 E-Mail: iouri.prokofiev@nrc.gov Telephone: (301) 415-2447 Fax: (301) 415-6671 Alternate Contracting Officer's IReoresentative Name: Bruce P. Lin Agency: U.S. Nuclear Regulatory Commission Office: Office of Nuclear Regulatory Research Mail Stop: - TWFN-10A36 11555 Rockville Pike Rockville, MD 20852-2738 E-Mail: bruce.linn@nrc.gov Telephone: (301) 415-2446 Fax: (301) 415-6671 12.0 MATERIALS REQUIRED (TYPE N/A IF NOT APPLICABLE) 20

Version Control Date: November 1, 201 4 NIA 13.0 NRC-FURNISHED PROPERTY/MATERIALS PNNL shall transfer NRG furnished property and materials acquired under previous contract (i.e., JCN N6593, JCN V6286) to this task order. NRG will provide additional information as necessary and agreed-upon. 14.0 RESEARCH QUALITY (TYPE NIA IF NOT APPLICABLE) The quality of NRG research programs are assessed each year by the Advisory Committee on Reactor Safeguards. Within the context of their reviews of RES programs, the definition of quality research is based upon several major characteristics: Results meet the objectives (75% of overall score) Justification of major assumptions (12%) Soundness of technical approach and results (52%) Uncertainties and sensitivities addressed ( 11 % ) Documentation of research results and methods is adequate (25% of overall score) Clarity of presentation (16%) Identification of major assumptions (9%) It is the responsibility of the DOE Laboratory to ensure that these quality criteria are adequately addressed throughout the course of the research that is performed. The NRG COR shall review all research products with these criteria in mind. 15.0 STANDARDS FOR CONTRACTORS WHO PREPARE NUREG-SERIES MANUSCRIPTS (TYPE NIA IF NOT APPLICABLE) The U.S. Nuclear Regulatory Commission (NRG) began to capture most of its official records electronically on January 1, 2000. The NRG will capture each final NUREG-series publication in its native application. Therefore, please submit your final manuscript that has been approved by your NRG Project Manager in both electronic and camera-ready copy. The final manuscript shall be of archival quality and comply with the requirements of NRG Management Directive 3.7 "NU REG-Series Publications." The document shall be technically edited consistent with NUREG-1379, Rev. 2 (May 2009) "NRC Editorial Style Guide." The goals of the "NRC Editorial Style Guide" are readability and consistency for all agency documents. All format guidance, as specified in NUREG-0650, "Preparing NU REG-Series Publications," Rev. 2 (January 1999), will remain the same with one exception. You will no longer be required to include the NU REG-series designator on the bottom of each page of the manuscript. The NRC will assign this designator when we send the camera-ready copy to the printer and will place the designator on the cover, title page, and spine. T he designator for each report will no longer be assigned when the decision to prepare a publication is made. The NRC's Publishing Services Branch will inform the NRC Project Manager for the publication of the assigned designator when the final manuscript is sent to the printer. 21

Version Control Date: November 1, 201 4 For the electronic manuscript, the Contractor shall prepare the text in Microsoft Word, and use any of the following file types for charts, spreadsheets, and the like. File Types to be Used for NUREG-Series Publications File Type File Extension MicrosoftWo rd .doc Microsoft PowerPoint ,ppt MicrosoftExcel .xis MicrosoftAccess .mdb Portable Document Format .pdf This list is subject to change if new software packages come into common use at NRC or by our licensees or other stakeholders that participate in the electronic submission process. If a portion of your manuscript is from another source and you cannot obtain an acceptable electronic file type for this portion (e.g., an appendix from an old publication), the NRC can, if necessary, create a tagged image file format (file extension.tif) for that portion of your report. Note that you should continue to submit original photographs, which will be scanned, since digitized photographs do not print well. If you choose to publish a compact disk (CD) of your publlication, place on the CD copies of the manuscript in both (1) a portable document format (PDF); (2) a Microsoft Word file format, and (3) an Adobe Acrobat Reader, or, alternatively, print instructions for obtaining a free copy of Adobe Acrobat Reader on the back cover insert of the jewel box. 16.0 OTHER CONSIDERATIONS (TYPE N/A IF NOT APPLICABLE) References (Type NIA if not applicable)

1. Braatz, B.G. S.E. Cumblidge, S.R. Doctor, and I.G. Prokofiev, Primary Water Stress Corrosion Cracks in Nickel Alloy Dissimilar Metal Welds: Detection and Sizing Using Established and Emerging Nondestructive Examination Techniques , Third International Conference on NPP Life Management (PLi M) for Long Term Operations (LTO) (Proc Conf .

Salt Lake City, Utah, 2012) IAEA-CN-194-025

2. EPRI 3002000576, Long-Term Operations: Assessment of R&D Supporting AMPs for L TO, Aug. 2013 (80pp).

3. NEI, Roadmap for Subsequent License Renewal, Dec. 2013. (45pp) 4 . NEI, Second License Renewal Roadmap, May 2015. (22pp).

5. NUREG/CR-6923, Expert Panel Report on Proactive Materials Degradation Assessment, 2007(3895pp, ML063520517) 22

Version Control Date: November 1, 201 4

6. NUREG/CR-7019, Results of the Program for the Inspection of Nickel Alloy Components, August 2010. (576 pp).

7. NUREG/CR-7153, Expanded Materials Degradation Assessment, 5 volumes, October 2014 (861pp)

8. Prokofiev, I.G, S.E. Cumblidge, and S.R. Doctor, Inspection of Nickel Alloy Welds: Results from Five-Year International Program, in Review of Progress in Quantitative Nondestructive Evaluation, Vol 30B. 201 1, American Institute of Physics, Melville, New York: San Diego, California, p. 1055-1062.

9. SECY-14-0016, Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal, January 31 , 2014 (25pp)

(Type NIA if not applicable) NIA Applicable Publications (Type NIA if not applicable) NIA Controls over document handling and non-disclosure of materials (Type N/A if not applicable) N/A 23

Note to requester: The attachment is immediately following this email. Portions of the attachment are redacted under FO IA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Wed, 20 Sep 2017 18:14:38 +0000 To: Tregoning, Robert

Subject:

FW: ACTION: Request for Expeditious Review of the Final Draft Response to the new SLR UNR Attachments: SLR UNR response 09-19-2017_cem (I F).docx Importance: High

Rob, In the DOE meeting today, you mentioned a PNNL report on harvesting prioritization. Did you say it was not yet published? It is referenced in our SLR UNR response (attached), and Steve asked for the ML# to be inserted. I can do that, if there's a watermarked-draft version of it, I suppose.Thoughts?

[Under Task 2] The criteria for prioritizing harvesting data needs are described in the September 2017 TLR "Criteria and Planning Guidance for ExPlant Harvesting to Support Subsequent License Renewal" (MLXXXXX ). Also, please feel free to give this another read-through and add any comments that you would like. Many thanks, Carol From: Frankl, Istvan Sent: W ednesday, September 20, 2017 1:23 PM To: Seber, Dogan <Dogan.Seber@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Iyengar, Raj <Raj. lyengar@nrc.gov> Cc: Moyer, Carol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hu ll@nrc.gov>

Subject:

ACTION: Request for Expeditious Review of the Final Draft Response to the new SLR UNR Importance: High

Dear Colleagues,

As you may know NRR had additional questions/comments after we completed our draft response. These comments have been addressed in the attached draft. Please review the attachment and send your comments/ revisions, if any, to Carol Moyer and copy me and Amy Hull by COB tomorrow. I would appreciate your quick response.

Thanks, Steve

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0 C . 20555-0001 September xx, 2017 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of N uclear Regulatory Research (RES) to provide "specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period." This user need request {UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years." This UNR also supersedes NRR-2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" and complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation of reactor vessel internals." For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427). The purpose of this memorandum is to respond to UNR NRR-2017-006 with RES's plans to accomplish the following tasks:

• Task 1: Hold NRC/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191).
• Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvestecl from operating plants.
• Task 3: Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research.
• _ Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applications.
• Task 5: Provide expert assistance w ith reviewing SLR applications {optional task)

CONTACT : Amy Hull, RES/DE 301-415-2435

B. Holian RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. RES staff will continue these activities and integrate the results in deliverables under Task 4. The response has been closely coordinated with NRR technical staff and management. As a result of this effort, RES added optional Task 5. If needed, under this task, RES staff would provide expert assistance with the review and evaluation of SLR applications. The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and the anticipated schedule for the deliverables. RES staff appreciates the coordination with NRR technical staff and management In this area. We will continue to coordinate with NRR staff and management to ensure that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRIR needs could impact the activities, deliverables and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and, if warranted, the UNR will be amended.

Enclosure:

Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

B. Holian

• 3*

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-201 7-006 DISTRIBUTION: B. Thomas, RES G Wilson, NRR R. Tregoning, RES A. Hiser, NRR I. Frankl, RES R. Iyengar, RES T. K.o shy, RES K. Miller, RES D. Seber, RES S. Stuchell, NRR B. Brady, NRR A.Hull, RES C. Moyer, RES M. Hiser, RES M. K irk, RES J. Philip, RES M. S ircar, RES J. Pires, RES RidsNrrMailCenter A DAMS Package Accession No.: Mlxxxx OFFICE RES/DE/CMB RES/OE/CMB RES/DE/CMB A. Hull NAME DATE

                 ~

I oyer

                         /2017 I /2017
                                                - -I.I Frankl
                                                        /2017 OFFICE          D:RES:DE        RES Mail Room      D:RES NAME
  -DATE          - B. Thomas -

I /2017 -K. Johnson I /2017 M. Weber I /2017 OFFICIAL RECORD COPY

Response to User Need Request NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRC/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two dome*stic and international activities (such as. a workshop, conference, symposium, or meeting), one tentatively planned for spring 2019 on mechanical components and one tentatively planned for summer 2020 on concrete and cables-related issues. In establishing the exact date for these meetings. consideration will be given to the availability of new information on the relevant technical topics. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016, ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR , and any new operating experience from the initial license renewal period (or t he long-term operation (LTO) period for international plants). RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. each RES will document the information from each of these activities in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting . .M. echanical - As part of the requested workshop/ conference/ symposium/ meeting on mechanical

• tentatively planned for spring 2019, the NRC staff will coordinate a session, or sessions, concerning reactor vessel embrittlement and the degradation of reactor internals due to irradiation during the SLR period. The staff will seek particip ation from the NRC staff, the regulated US industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above.

Concrete. Containment and Electrical Cable Issues - RES will also hold an NRC/industry work shop with international participation (tentatively planned for summer 2020) on the state of knowledge for the technical issues in concrete, containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific technical topics and items of interest. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late summer 2020. RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, described in paragraphs 2.A -2.D of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting. In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. IMLXXXXXl. The deliverable Commented IFI1]: Please add ML# for t h is TLR. -=i provided criteria to assess the need for harvesting to address a particular technical issue. The report then applied these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report also covered the background on the need for harvesting, and past harvesting efforts and experience. The purpose of this report was to serve as a foundation for N RC staff to prioritize technical issues best addressed by harvesting. The initial technical letter report (TLR) for this research is expected to be published in September, 2017, as a PNNL document. This TLR will be reviewed by NRR and RES staff to determine any follow-on work by RES and the final publication type.

• In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting , lessons learned from past harvesting efforts, and future harvesting program planning.

The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The workshop summary report will be distributed among meeting participants and is expected to be finalized by September, 2017. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2.8. Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may l>e best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. RES will apply the criteria developed with PNNL described above to the issues for SLR. and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the latest operating experience and research, so that users may understand which data needs can be best addressed by harvesting. As a example, RES will develop a process to evaluate concrete samples, and will follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)- affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels (PCCVs); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001 . RES will continue to evaluate the SLR-significant issue of cable aging using harvested cables. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011 -014 and NRR-2016-012 to include more cable types (insulation types and medium voltage level cables) and to evaluate the aging effects on power cables at different voltage levels. Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.D. Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.D., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.D). RES will r-emain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E , which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the information tool/database. Task 3 RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of industry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research. RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships will build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as implementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs. RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NOE). RES is a participant in several multi-national cooperative research programs, including the International Forum on Reactor Aging Management (IFRAM), and many others. I he RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. IFRAM is envisioned to be a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research, regulation, education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. The small effort and contract funding to operate the IFRAM program will be funded by this User Need Request. Other international collaborations pursued by RES are also expected to benefit this work. although resources to support those initiatives are* tracked separately. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the OECD Halden Reactor Project (HRP} proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These results will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR. Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NENCSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports. summaries, papers, presentations. reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE. NRR/DMLR and NRR/DE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task4 RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff. RES will prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at .a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) or j tyear for this task be adj usted once the scope of work and the required level of RES

      ** staff involvement is better understood after the first SLR application is received in early FY18.

Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. Task 5 (Optional) Under this optional task. NRR may call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses._Building upon the extensive work previously done under UNR NRR 2014-001, RES staff will continue to be available to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. As an example, the staff will continue to be* available to review operational equipment failures to assess the trend in critical risk-significant electrical equipment. There are concerns with aging effects (including cyclic aging) and design life of other electrical components, such as breakers and relays, which would need further evaluation to assess their continued service life b y exploring other monitoring techniques not generally covered under surveillance tests. Such analyses could complement work in Task 2, whereby critical electrical components can also be harvested and evaluated. These SLR-related studies are being pursued independently of this UNR, and the work is being tracked through existing communication between RES and NRR staff. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRG-supported research. as well as collaborative research particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adj ust the schedules for deliverables as needed to support effective regu latory decision making.

                                               -10

The deliverables and schedules for UNR NRR-2017-006 are shown in the following table. Schedule and Resources for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE Contract$ Number Date /h\/ 5\ 1 Hold NRG/industry (b)(5) [:::=]for FY 18 workshops (est. 2018, 2020) and FY 21 I - - - - -I and prepare NUREG/CP FY 21 D y~ar and summary reports on four SRM topics (b)(5) Total (Task 1) ------ I I (b)(.5) 2 Develop a strategy for harvesting materials/components /h \/5 \ (b)(5) 2.A. Develop an information tool/database FY 18 --- I --* I 2.B. Develop a process to evaluate plant components FY 18 D (b)(~I 2.C. Use the process from 2.B. to evaluate the suitability of FY 19 c:::l--<b) 5) plant components 2.D_ Continue to implement the process from 2.B. as

                                                                 .        (b)(5)

Ongoing (FY O rear

• components become 20-21) (Total Q available from additional plants (b){5 1i 2.E_ Pursue partnerships for cooperative cost-sharing on Ongoing Included in retrieval and testing of ex- (FY18-FY21) Task 3, below plant materials (b)(5)

Total (Task 2) L..;J I I 3 Participate in relevant

                                                                         -~-- *-
                                                                     ,-11--1 b)(5) domestic and international                                                                        L J-{bX?.l activities (e.g_, IFRAM,              FY 18-21        c : J tar (Total .

I (total for 4 years --- IAEA, DOE LWRS, EPRI IFRAM dues) LTO, codes & standards) (b)(5 }_ 4 Develop documentation (b)(5) evaluating significant i=:lyear technical issues germane to FY 18-21 the review of SLR (Total[:::)_ aoolications (b)(S)- 5 Provide technical assistance To be funded To be funded if (oQtional) to NRR for reviewing SLR FY 18-21 if needed needed aoolications. I I Total (Tasks 1-4, over 4 years) 1br / h \/J::\

• 11

No,t e to requester: The attachment is immediately From: Moyer, Carol following this email. Portions of the attachment are Sent: Thu, 19 Oct 2017 20:03:16 +0000 redacted under FOIA Exemption B5 , Deliberative Process Privilege. To: Cole, Cassandra

Subject:

FW: ACTION: Revised Draft Response to SLR UNR Attachments: Response to User Need Request NRR-2017-006 (002).response BT comments abh (IF) EMF cem (IF).docx Importance: High Email concurrence from S. Frankl. From: Frankl, Istvan Sent: Thursday, October 19, 2017 3:29 PM To: Moyer, Carol <Carol.Moyer@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov> Subject : RE: ACTION: Revised Draft Response to SLR UNR Im portance: High Thanks, Carol. The memo is OK and I have only two minor fixes for Table 1 in the attached Enclosure. I concur with the memo and the revised enclosure. Please return this package into concurrence review/approval. As discussed, Amy can concur by email. Steve From: Moyer, Carol Sent: Thursday, October 19, 2017 2:33 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov> Subject : RE: ACTION: Revised Draft Response to SLR UNR Importance: High

Steve, I believe the User Need Request Response on SLR is finally ready to re-enter concurrence.

Please see the attached mark-up copies of the Memo and Enclosure, and provide any additional comments. These files are in the folder: G:\DE\CMB\2017-006 UNR NRR 2017-006\1 current version of response Thank you, Carol

From: Frankl, Istvan Sent: Monday, October 16, 2017 8:49 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: ACTION: Revised Draft Response to SLR UNR Thanks, Amy. From: Hull, Amy Sent: Monday, October 16, 2017 8:43 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Moyer, Carol <Carol.M oyer@nrc.gov>

Subject:

RE : ACTION: Revised Draft Response to SLR UNR This is indeed the version that Brian saw. I put the UNR package and Brian's comments on Carol's desk. The RAR response was approved by Brian Thomas with a few changes he wanted to be made. From: Frankl, Istvan Sent: Saturday, October 14, 2017 12:07 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

ACTION: Revised Draft Response to SLR UNR Importance: High Thanks, Amy. I have attached my revisions with comments. Did you resolve the issue with the different document versions? I am assuming you used the version that Brian reviewed. Please confirm.

Carol, Since Amy is out next week on training, please try to resolve my comments and have the final draft ready for my review by COB Tuesday so that the package can be returned to management for concurrence and approval on Wednesday. (Please note that we may get additional comments from Brian and the RES FO, and I don't want to request another extension.)

Thanks, Steve From: Hull, Amy Sent: Friday, October 06, 2017 2:35 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

my suggested changes: question -- package in ADAMS for SLR UNR This gives you an idea of what I am thinking.

From: Frankl, Istvan Sent: Friday, October 06, 2017 1:34 PM To: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR Great! At least you will be able to document your ideas/thoughts on this now. Steve From: Hull, Amy Sent: Friday, October 06, 2017 1:32 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR OK. I will do that and send to you. Then we can incorporate it into the correct file next Weds. From: Frankl, Istvan Sent: Friday, October 06, 2017 1:29 PM To: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR Thanks for the update, Amy. My recommendation would be for you to draft the text that addresses Brian's generic comments now and then insert it in the final version once you get it from the AAs. Steve From: Hull, Amy Sent: Friday, October 06, 2017 12:43 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR Cassandra sent me a version - 9/22 - that predates the version that Brian gave me, and I think _ e;;~~~~~~~~-~-~ ~~i~~~~u signed off on (,°ur signature is 9/25). I guess I will wait until Weds (b)(6) From: Frankl, Istvan Sent: Friday, October 06, 2017 12:16 PM To: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR Interesting.... This can mean that the final version was not uploaded or has a different ML#. You may need to wait for the AAs to sort this out.

Thanks, Steve From: Hull, Amy Sent: Friday, October 06, 2017 12:12 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR You did explain to me earlier and I understand all that. The problem is that I tried to get it out of ADAMS using, ADAMS# per 9/25/2017 concurrence page, and it is still today the old version from Aug. See attached. From: Frankl, Istvan Sent: Friday, October 06, 2017 12:08 PM To: Hull, Amy <Amv.Hull@nrc.gov>

Subject:

RE: can you send me the most recent version please?: question -- package in ADAMS for SLR UNR

Amy, The version that needs to be updated is the one that Brian reviewed. That version should be in ADAMS (and not the G: drive) and should be considered the "last" version. (You may or may not have owner rights.)

As explained earlier, the AAs control the revision of files in ADAMS once the concurrence package is submitted to management for review/approval. Once you get and update the final version (with track changes enabled), please send it to me for review and then to the AAs, so that they can do the final formatting, the uploading to ADAMS and re-submitting the concurrence package to DE management.

Thanks, Steve From: Hull, Amy Sent: Friday, October 06, 2017 11:54 AM To: Savoy (RES), Steven <Steven .Savov2@nrc.gov>

Cc: Moyer, Carol <Carol.Moyer@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

FW: can you send me t he most recent version please?: question -- package in ADAMS for SLR UNR Steven, (b)(6) J . .. . .. . . . . . . . . . . !I am implementing changes in the version that Brian gave back to me last Friday but I have been working on an old document - not a smart thing to do. Please will you help me find the most recent version? I tried to find it in ADAMS and Gdrive but had no luck. Thanks, Amy From: Hull, Amy Sent: Friday, October 06, 2017 11:33 AM To: Vera, Graciela <Graciela.Vera@nrc.gov>; M oyer, Carol <Carol.Moyer@nrc.gov>

Subject:

can you send me the most recent version please?: question -- package in ADAMS for SLR UNR From: Vera, Graciela Sent: Friday, September 29, 2017 5:57 AM To: M oyer, Ca rol <Carol.Moyer@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: quest ion -- package in ADAM S for SLR UNR lli, I got it. What was the last new version that you sent to Cassandra? WE have fours versions in ADAMS; 2 versions from August and 2 versions this month. I will be here to help before 1get offat 1:40pm today. Thanks (9racida Wera Administrative Assistant Division of Engineering Office of Nuclear Regulatory Research Washington, D.C. 20555 TWFN10-A00 From: Moyer, Carol Sent: Thursday, September 28, 2017 5:04 PM

To: Cole, Cassandra <Cassandra.Cole@nrc.gov>; Vera, Graciel a <Graciela.Vera@nrc.gov>; Savoy (RES), Steven <Steven.Savoy2@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

FW: question -- package in ADAMS for SLR UNR Importance: High Hi Cassandra, On Monday morning (9/25), CMS submitted a User Need Response memo & enclosure for Brian's signature. You logged it for his concurrence (confirmation attached}. The UNR package was an update to a prior version (addressing some NRR comments on our draft response), so we asked that the same ML number be assigned. What is in ADAMS now at that ML# is the August version of the documents, NOT the Sept. 25 version. Can you please check this, and find out what happened? We want to make sure Brian is reviewing the latest version, and that the 9/25 version was not lost. If the newer version was assigned a different number, please let us know what that number is, so we can share it with our NRR customers. Thank you, Carol Moyer & Amy Hull From: Hull, Amy Sent: Thursday, September 28, 2017 4:22 PM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

question -- package iin ADAMS for SLR UNR st ill old - - this should have new documents??? - do we have duplicate packages? RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON Pockoge Nome POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION NRR 2017-006 Access10n Number ML17227A483 Pock&ge Propon;.. j Pas1e M1to PackA<JH MdOonwnont Unfile Pmfile Downlo d Ch ~k Oul ( Refresh j NameO Accessioo Number I Official ~* cord? I Avaifeblllty O Oocuo nt Date I ADAMS Dot*A: : ] Non-Publtcly Aug 15, 2017 J *OO SLR UNR response 08-14-2017 cln (002) docx ML17227A484 No Available PM R8SPQnse to User Need Request NRR-2017-ML17227A485 No Non-Publtely Aug 15, 2017 3 00 006 doc:x Ava11abl9 PM There ero 2 Documents m this Package I( < Page 1 of 1 > >I ~OCNder https://adamsxt.nrc.gov/AdamsXT/packagecontent/packageContent.faces?id={355A25 00-E6F3-4E 19-A8D8-C627FDDE9FFB}&objectStoreName=Mainlibrary&wld=1506629912784

Response to User Need Request NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRC/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two domestic and international activities (such as, a workshop, conference, symposium, or meeting), one tentatively planned for spring 2019 on mechanical components and one tentatively planned for summer 2020 on concrete and cables-related issues. In establishing the exact date for these meetings, consideration will be given to the availability of new information on the relevant technical topics. These meetings will address:

• the state of knowledge on the technical issues requested in the SRM on SECY 14-0016,
• ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR report, and
• any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for international plants).

RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before each workshop. RES will document the information from each of these activities in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting. Materials Issues for Mechanical Components - As part of the requested workshop/ conference/ symposium/ meeting on materials issues for mechanical components, tentatively planned for spring 2019, the NRC staff will coordinate a session, or sessions, concerning reactor vessel embrittlement and the degradation of reactor internals due to irradiation during the SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. Concrete. Containment and Electrical Cable Issues - RES will also hold an NRC/industry workshop with international participation (tentatively planned for summer 2020) on the state of knowledge for the technical issues in concrete, containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific technical topics and items of interest. RES will Enclosure

document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late summer 2020. RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant -components from operating plants. RES will execute the work through a 4-step process, described in paragraphs 2.A -2.D of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting. In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The criteria for prioritizing harvesting data needs will be described in the anticipated TLR, expected by the end of 2017 "Criteria and Planning Guidance for ExPlant Harvesting to Support Subsequent License Renewal." The deliverable will provide criteria to assess the need for harvesting to address a particular technical issue. The report will then apply these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report will also cover_the background on the need for harvesting,. and past harvesting efforts and experience. The purpose of this report is to serve as a foundation for NRC staff to prioritize technical issues best addressed by harvesting. The initial technical letter report (TLR) for this research is expected to be published in September, 2017, as a PNNL document. This TLR will be reviewed by NRR and RES staff to determine any follow-on work by RES and the final publication type. In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was designed to discuss past harvesting experience and lessons learned and seek leveraging and cooperation with other interested research organizations. Insights from the workshop are integrated into the database and harvesting planning efforts. The database will be developed consistent with the prioritization criteria from PNNL to identify which sources to focus on. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The workshop summary report will be distributed among meeting participants and is expected to be finalized by September, 2017. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2.B. 2

Subtask 2.A. Moving forward , RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may l>e best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. The work in this task includes collecting and inputting information on materials needed and the sources of materials expected to be available. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the latest operating experience and research, so that users may understand which data needs can be best addressed by harvesting. The purpose of the database is to have a systematic approach to harvesting materials and prioritize limited resources on the best values for harvesting. The database is not an end unto itself, but the means to do the highest priority harvesting for the best technical value. As a specific example, RES will develop a process to evaluate harvested concrete samples, and will *follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)- affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels (PCCVs); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue resea rch on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001. RES will continue to evaluate the SLR-significant issue of cable aging using harvested cables. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011-014 and NRR-2016-012 to include more cable types (insulation types and medium voltage level cables) and to evaluate the aging effects on power cables at different voltage levels. Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and 3

insights from the harvesting workshop, the greatest challenge in this a rea is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES w ill work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database w ith prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.0. Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.0 ., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.0). RES will r-emain in close contact w ith NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, w ill consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities w ill be retained in the information tool/database. Task 3 RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of industry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research. RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships w ill build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as implementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LT Os. RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NOE). RES is a participant in several multi-national cooperative research programs, including the International Forum on Reactor Aging Management (IFRAM), and many others. The RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. I FRAM is envisioned to be a network of research organizations, industry groups, regulatory 4

bodies, and academic institutions involved in reactor aging management research, regulation, education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. The small effort and contract funding to operate the IFRAM program will be funded by this User Need Request. Other international collaborations pursued by RES are also expected to benefit this work, although resources to support those initiatives are*tracked separately. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the OECD Halden Reactor Project (HRP) proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These results will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NENCSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in al I areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RESIDE, NRRIDMLR and NRRIDE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task4 This UNR (NRR-2017-006) serves as an "umbrella" under which Gthefcassociated SLR-focused technical UN Rs are coordinated.Bre>Jidina an lJn:ibrella lJnEler which SLR feclJsoe technical UNRs are p u t ~ These technical UNRs-SUpj)Olted are shown in Table 1 below. 5

Table 1. SLR-Related Technical UNRs Associated with UNR NRR-2017-006 UNR # UNR Title Comments l'I RR-2017-001...,_ l -+cR~e~q~,u'e--'scc. t c= fo'-c r __ This UNR is bBased on a previous UNR NRR- 2012-008 and updates Commented [IF1]: Why are some UNRs highlighted on ML16300A303 -v Assistance to llleregulatory-_research-f}l'OjeGI on void swelling and clarifies currentwhat this page? Evaluate projects~rr8Ally-HWelY84--with and what-fut ure projects that are RES Response to Irradiation- being considered. Commented [CM2R2]: fixed NRR-2017-001 Assisted A thi:rd task was added to this UNR fort\ave RES.!2 perform confirmatory ML17110A202 Degradation of Rx evaluation and support ASME code case on new E PRI IASCC crack growth Vessel Internals rate curves. E.l!!)Ql_ndGontract (b)(5) Commented [IF3]: Please double-check by FY. FY17:1 I (b)(5) Commented [CM4R4]: Confirmed with UNR response. FY18: (b)(5 I and FY19: (b)(S)I (b)(5) TESI: FY17:1.* I FY18: .... andFY19: ....., ..:011::,1 fnll"ll

                                                                                                                                                                                                                                                ,~ - - - - - - - - - - - - - - - - - - ~

Commented [IFS]: Same as above N RR-2014-007 Reactor Pressure This D NR superseded UNR NRR-2007-00f ahd1ncludes !t1asks: (1) ML14126A818 Vessel Integrity Appendix H in process by NRR, NRO, and RES staff; rulemaking funded in Commented [CM6R6]: Confirmed with UNR response. Issues FY17 and team in place to finalize rulemaking effort, (2) updating the tech RES Response to bases for Appendix G, (3) examination and analysis of irradiated reactor N RR-2014-007 vessel material, (4) providing emergent technical assistance, (5) maintaining ML14212A127 datab ase and documentation, and (6) performingl_documenting a tech {package) evaluation on irradiation damage mechanisms and potential revisions to 10 CFR , part 50 App. G of RG 1.99 "Radiation Embrittlement of Reactor Vessel Materials" Rev 2 . . (b)(5) (b)(5) (b)(5) (b)(5) (b)(5) ~ . . , .. ...... . [ Commented [IF7]: Same as above f-c-,.=-=--..,.,,...,...,.....,. .,...,...--11-,-----," (lb:.,,,)(!,::5'1'-'cF'F**** t.,,,~-;:.,,J

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                                                                                                                                                                                         *'*,**/l    )(2g)'----I-,---

4l -_ _I ,,,,,,..-----1[ Commented [IFS]: Same as above NRR-2011-014 Assessment of NRRJDM LR's focus on this UNR is to assess and *evaluate condition ML11307A205 Cable Condition monitoring methods on electrical cables subj ected to accelerated aging Monitoring under normal and accident conditions. R ES Response to Accelerated aging of the cable samples is expected to commence toward NRR-2011-014 Amendment to the end of FY2017. ML11335A169 UNR for The amendment extends the cable testing period up to 80 years (up from 60 Assessment of

                                                                                         ~~~i~n the pre(b)(g)UN R).                                           (b)(5)                           (b)(5}                        (b)(5) 7:3" A mendment to                          Electrical Cable                                                                                                                                                                                         [ Commented [CM9]: Input from T. Koshy NRR-2011-014 f NRR-2016-0121 Condition Monitoring
                                                                                       ~                                 r=1 :; ~                                               * **                                      r::r** * *

• ML16096A221 /b\/5~ lhW,\ '{b)(5 )
• l hV"'

NRR-2012-004 Alkali-SIiica The obj ective or this UNR'<is to develop technical. bases for regulatory ML12109A324 Reaction {ASR) guidance for evaluating ASR-affected concrete slructures. primarily focusing Research on impact on the stnuctural capacity under design basis loads through its RES Response to service life, including PEO, and Its aging management. The research at (b)(S) NRR-2012-004 (b )(5) NIST includes 0-blaining data on highly instrumented concrete block ML12152A107 spec.i n,iens to monitor lhe progression of ASR and assess its impact on in- (b )(5,).. , (b)(5) situ mechanic.ii properties, conducling destructive testing to assess ...(P)(5) ........ (b)(5) sl i'Uciu.(~I impacfincludi.Q.9 seismic response, evaluating numerical mod~.l,ing . . melhQ~s. and.rn~ ~cts.tor determining the~Jate.oh\Sl t  :<. Jp)(5)......... (b)(5)

                                                                                      ~~                       :.:: ~::l~-*l..                    r:::-7.r-7 **** .,..,...... .. ;::                                      , ...  -I    c:<  11   ;::::

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NRR-2015-007 Effects of The JPUrpose of th,s UNR is to develop technical bases for regulalory ML15076A217 Irradiation on guidance to evaluate radiation effects on concrete structures close to Commented [CM11 R11): Input from J. Philip & D. Seber Concrete reactors .*The focus of related regulatorythe research Is to evaluate the RES Response to Slructures impacl on structural capacity under design basis loads for service life up lo N RR-2015-007 80 years and develop aging management strategy. ML15229A100 The jproject includes reviewing EPRI and DOE reports by ANL (contract awarded in Jan 2016), harvesting the mat~rials from the decommissioned Jose Cabr*** ra Neeln.Zorita, SP.filn_ i~)(o) ,.........., (b)(5) F undina FY.16*-r::::::::-l FY17 r--=:::7FY18 1 *.. I FTEs:I FY16 - I

• IFY17 -I **.IFY18 .1 .1 Commented [IF12]: Same as above.

                                                                                                                                                                        ..                                                                          Commented [CM13R13]: Input from D. Seber (b)(5)

(b)(5), (b)(5) , (b )(5)*. 6

RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff. RES will prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. B.~§ed on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) qf ........********* iyear for this task be adjusted once the scope of work and the required level of RES stafif involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. Task 5 (Optional) Under this optional task, NRR may call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses. Building upon the extensive work previously done under UNR NRR 2014-001, RES staff will continue to be available to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES w ill be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. As an example, the staff will continue to be* available to review operational equipment fa ilures to assess the trend in critical risk-significant electrical equipment. There are concerns with aging effects (including cyclic aging) and design life of other electrical components, such as breakers and relays, which would need further evaluation to assess their continued service life by exploring other monitoring techniques not generally covered under surveillance tests. Such analyses could complement work in Task 2, whereby critical electrical components can also be harvested and evaluated. These SLR-related studies are being pursued independently of this UNR, and the work is being tracked through existing communication between RES and NRR staff. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management t-o discuss the latest developments and information from industry and NRG-supported research, as well as collaborative research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule 7

based on expected project completion dates. RES staff will c losely coordinate with N RR staff and adj ust the schedules for deliverables as needed to support effective regu latory decision making. The deliverables and schedules for UN R NRR-2017-006 are shown in the following table . Schedule and Resources for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE (b)(5 ) Contract $ Number Date 1 Hold NRG/industry workshops (b)(5) L...::..Jr.or FY 18 (est. 2018, 2020) and prepare and FY 21 FY 21 [ 3 year *** NUREG/CP and summary reports on four SRM topics I (b)(5)I Total (Task 1) I L d (b)(5) .. I (b)(~) 2 Develop a strategy for harvesting Ex-Plant materials/components

                                                                           /h\/<;\

(b)(5) 2.A. Develop an information FY 18 Cl c::::::J -.. tool/database 2.B. Develop a process to evaluate plant components FY 18 c::::Jp)(5) 2.C. Use the process from 2.B. to evaluate the suitability of plant FY 19 comoonents c::J(b-)(~} 2.D. Continue to implement the \D/(:l/ process from 2.B. as Ongoing (FY 20-components become available 21) j (T~*; ! 1~ )(§ . from additional plants 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in Task retrieval and testing of ex-plant FY21) 3, below (b)(5) materials Total (Task 2) I (b)(5)y 3 Participate In relevant domestic (b)(5) I=::::J (l?)(5) and international activities (e.g., c:::Jyear. FY 18-21 (total for 4 years ** IFRAM, IAEA, DOE LWRS, (Totalc:::J IFRAM dues) EPRI LTO codes & standards) 4 Develop documentation (b)(5} evaluating significant technical issues germane to the review of FY 18-21 (b (5) c::::JCJ (Total .... (D SLR aPPlications (§)_ 5 Provide technical assistance to To be funded if To be funded if (opti onal) NRR for reviewing SLR FY 18-21 needed needed applications. Total (Tasks 1-4, over 4 years) L...::..J I I

                                                                                                                      \

(b)(5) * (b)(5) \ 8

From: Hiser, Matthew Sent: Wed, 6 Sep 2017 13:39:31 +0000 To: Tregoning, Robert

Subject:

FW: Action: Rewrite in response to Feedback on UNR Response Task 2 FYI From: Hiser, Matthew Sent: Tuesday, September 05, 2017 2:23 PM To: Hull, Amy; Purtscher, Patrick Cc: Frankl, Istvan ; Moyer, Caro l

Subject:

RE: Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Amy, My initial thoughts on how to respond to some of these questions are in red below. I only think maybe 1 or 2 of the bullets need changes to the text of the response (in my opinion). Do you know who in NRR reviewed Task 2 and provided these comments? It might be just as easy to have a quick meeting with them to explain things more clearly. I'd suggest you take the lead on editing the response as much (or little) as appropriate , since you and Carol took the lead in compiling the input initially. My feedback is in red below and Pat can certainly add anything from his perspective. Thanks! Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 l -415-24541 Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Hull, Amy Sent: Tuesday, September 05, 2017 1:42 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov> Cc: Moyer, Carol <Carol.Moyer@n rc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Matt and Pat, Would you like me to take a crack at the following feedback from NRR (since I put the database in the original SOW) or would you like to rewrite first ? Or should we sit down and brainstorm these questions? I have attached the UNR, the response, and the NRR feedback from last Thursday. TASK2

• It isn't clear what these criteria/approaches/processes for the use of the database are.

Where are they documented or described, how they have been validated or used? Are the criteria/approaches/processes described in the September 2017 TLR? The criteria for prioritizing harvesting data needs are described in the September 2017 TLR. NRR needs to have an idea of what is involved in the steps and how the database will be used.

• It is not clear how the first two activities, the workshop on materials harvesting and prioritizing of issues to be addressed by harvested materials, contribute, or are related to the database. This must be fully explained. The workshop was designed to discuss past harvesting experience and lessons learned and seek leveraging and cooperation with other interested research organizations. Insights from the workshop are integrated into the database and harvesting planning efforts. The database will be developed consistent with the prioritization criteria from PNNL to identify which
• Why just decommissioned plants? An explanation is required as to why this has been limited in scope. This harvesting effort is not limited to only decommissioned plants as stated in draft response: "RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants."
• It is not clear how the discussion under Subtask 2 are examples of how the database would be used. It seems to be a discussion of harvesting material. This needs to be explained, with clear outcomes defined. The purpose of the database is to have a systematic approach to harvesting materials and prioritize limited resources on the best values for harvesting. The database is not an end unto itself, but the means to do the highest priority harvesting for the best technical value.

(b)(5) -I * !seems like a lot to develop an Excel or Access database. I don't disagree - I think at this point, it may be a 100% in-house effort. Does this include collecting and inputting information on materials needed and the sources of materials expected to be available? Yes This tasking must be better defined. Amy B. Hull, Ph.D Senior Materials Engineer RES/DE/CMB (office T10-O49) US Nuclear Regulatory Commission 11545 Rockville Pike Rockville, Maryland 20852 Telephone: (301) 415-2435 FAX: 301-415-6671 e-mail: amy.hull@nrc.gov

From: Purtscher, Patrick Sent: Mon, 9 Jul 2018 12:34:58 +0000 To: Hiser, Matthew

Subject:

FW: Cost estimate We should talk today. Pat From: Ramuhalli, Pradeep [2] Sent: Tuesday, July 03, 2018 3:38 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>

Subject:

[External_Sender) Cost estimate

Pat, As we discussed last week, the new tasking for assembling the database of available harvested materials at PNNL could use additional funds. A ballpark cost estimate for this effort is abou{ 3 thoughthe (~)(~)

exact value will depend on the specifics of the scope. Let me know if you have any questions on this. Please note that the material contained herein, including the cost estimate, is submitted for informational purposes and is not binding on Pacific Northwest National Laboratory or the U.S. Department of Energy. Binding commitments can only be made by the submission of a formal proposal that sets forth a specific statement of work, estimated cost, and that is signed by a Pacific Northwest National Laboratory Contracts !Representative and approved by the U.S. Department of Energy. With best regards, Pradeep Pradeep Ramuhalli, PhD Senior Research Scientist, Applied Physics Group Pacific Northwest National Laboratory 902 Battelle Blvd. P.O.Box 999, MSIN KS-26 Richland, WA 99352 Tel: 509-375-2763 Emai l: pradeep.ramuhalli@pnnl.gov http://www.pnnl.gov

Note to requester: Portions of the attachment (immediately fo llowing this email) are redacted under FO IA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Wed, 29 Aug 2018 15:20:29 +0000 To: Frankl, Istvan Cc: Tregoning, Robert

Subject:

Consolidated list of Recommendations for DOE Engagement Attachments: NRC DOE Engagement List 20180829.docx

Steve, The attached document consolidates the lists of topics and "research asks" for DOE from our internal meetings. Please review, as this is the focus of tomorrow's meeting with DE management.

Thank you , Carol Carol Moyer Sr. Materials Engineer RESI DEICMB 301-415-2153 carol.mover@nrc.gov

NRC - DOE Engagement Recommendations & Requests In cooperation with the LWRS Materials Aging and Degradation (MAaD) Pathway: Reactor Internals

• Overarching request - identify opportunities to have meaningful input on the objectives for research pu rsued by DOE. Our staff recommends that we agree with DOE on several topics of mutual interest, and both organizations fund research (to diffe rent levels), so that we can have more meaningful engagement.
• Further irradiation of ex-plant welds harvested from Zorita reactor o Further irradiation of these materials is sought up to - 5 and -8 dpa followed by mechanical testing, including crack growth rate and fracture toughness o Target irradiation from 2020 - 2022 with 5 dpa testing beginning in 2021 and 8 dpa testing in 2023.

o Seeking DOE contribution ofl . !along with NRC and EPRI cooperation to assure effective program ... (b}{5)

• Environmentally Assisted Fatigue (EAF) of Irradiated Stainless Steel **-
• o NRC seeks to plan a joint testing program with material irradiated up to -10 dpa, over a multi-year period , with NRC and EPRI cooperation to assure an effective program.
• Irradiation-Assisted Stress Corrosion Cracking (IASCC) and Void Swelling of Highly-Irradiated Stainless Steel o Irradiation of stainless steel plate material is sought, in excess of 50 dpa, followed by material evaluation of SCC crack growth rate and void formation, and post-irradiation examination of microstructure.

o We request that DOE significantly leverage facilities, expertise, and direct costs. Detailed cost and schedule information would be developed as a part of the (b)(5) ~°i~~~~:=r~~:. Howj;~~*:!~~~~pae~~~i~~=~ ~luch ~ Stress Corrosion Cracking Mechanisms in Nickel-base Alloys

                                                                  ~r~~~:.    ;~(~Ir be resource o The meeting participants expressed that there is a gap in understanding of SCC in Ni-base alloys subject to irradiation.

• Mechanistic Modeling of Environmentally Assisted Fatigue o NRC staff questioned what experimental work is planned for validation of the mechanistic model.
• Long-Term Thermal Aging of Cast Austenitic Stainless Steel (CASS) and Austenitic Stainless-Steel Welds (ASSW) o NRC staff recommends that DOE integrate findings of previous Government-supported research on CASS and ASSW into the current work.
• Evaluation of Ex-Service Baffle Former Bolts o NRC staff suspects that cracking in baffle former bolts (BFBs) is likely related to corrosion fatigue, not IASCC (focus of the DOE work). This research could be valuable in assessing competing theories of the underlying mechanisms of failure among the NRC, DOE, and industry.
• Modeling Radiation-Induced Swelling o As a regulator , NRC needs to document a more validated relationship between voids and mechanical properties. The modeling work described is of the sort that NRC might support with a grant, but it is not a priority for collaborative research.

GEM 8/29/2018

Reactor Pressure Vessels (RPV)

• Low-temperature irradiation effects
• Validity of mini-CT fracture toughness tests
• Fluence modeling beyond the beltline region
• Properties modeling, e.g., using GRIZZLY; validating with experimental data
• Identifying and harvesting relevant RPV materials for benchmarking data
• Experimental plans and results from the ATR experiment, including embrittlement trend modeling Concrete
• Effects of irradiation on steel-concrete bond strength o Expanded study that builds on the NRC limited scope study to establish steel-concrete bond degradation trends, verify repeatability, and reduce uncertainties
• Harvesting and testing of concrete samples from decommissioned NPPs to verify radiation damage and for confirmatory research on:

o Validating predictive models based on accelerated aging studies using empirical data from concrete aged in the field with in-situ radiation fields, temperature and other environmental conditions o Evaluating concrete radiation gradients and damage in the biological shield o Irradiating harvested cores to higher fluence

• Improvement of aging management strategies -Access to the RPV supports and CBS structures is very limiited and development of suitable inspection methodologies would be advantageous o Development of suitable inspection strategies including detection of direct and indirect evidence of degradation o Development of monitoring technologies using, for example, remotely controlled instruments and NDE.
• Irradiation effects on structural steel and rebar (carbon steel) o Start with literature review of existing studies and understanding o Harvesting and testing of harvested steel components for laboratory examination
• Risk-informed aspects of irradiation effects on the RPV support structures and CBS (under the RISMC program)
• Modeling of concrete damage mechanisms o Modeling of cement paste under irradiation to include creep effects (likely to involve irradiation testing of cement paste) o Modeling of concrete material damage combining cement and aggregate damage (may need further irradiation testing of aggregates)
• Concrete models for structural analysis and incorporation in DOE structural analysis codes Cables
• DOE has invited NRC input on experimental test plans for cable aging, including synergistic effects of thermal and radiation aging, compared with sequential exposures.
• DOE work on activation energy will complement NRC's planned work.
• The actual radiation dose rate in NPPs is a knowledge gap. DOE and NRC are doing some modeling, but both look to EPRI for detector data.

2 GEM 8/29/2018

Additional "research asks" from ICEEB input to RES FO for DOE engagement:

• Research is needed to confirm that safety related cables in nuclear power plants operating beyond 60 years of operation have sufficient margin and will continue to perform their intended safety function during and after a design basis accident. The NRC also wishes to better understand the extent to which uncertainties could have a detrimental effect on the environmental qualification of safety related cables beyond 60 years of plant operation.

o Assessment of Condition Monitoring Methods for medium voltage cable in harsh environment with aging (including electrical stressor degradation) and accident testing. o Assessment of Condition Monitoring Methods for low/medium voltage cable in mild environments. o Studies involving degradation of mild environment Class 1E 4160V and 480 distribution equipment (breakers, relays, switches, etc.,) with thermal and cyclic aging to determine if such components can be relied on to perform their intended safety function beyond vendor recommended design/service life. In cooperation with the LWRS Risk Informed Systems Analysis (RISA) Pathway:

• Fragility and performance of flood-resistant features (doors, seals, etc.) in NPPs.

o Experimental testing of flooding barriers to refine testing procedures o Harvesting of flooding barriers from decommissioning plants o If harvesting is not feasible, in-situ testing of flooding barriers 3 GEM 8/29/2018

Note to requester: Portions of the attachments (immediately following this email) are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Fri, 11 Aug 2017 16:01:16 +0000 To: Frankl, Istvan Cc: Hull, Amy

Subject:

RE: SLR UNR Response, 8/10/17, 4:55 PM Attachments: SLR UNR response 08-07-2017 jap jp kam cem.docx, SLR UNR response 08 2017.docx Steve, The updated response (w/ today's date), as well as the preceding mark-up, are attached to this message for your review. Let me know if you have any questions on this. Meanwhile, I will ask the AAs to put the draft into ADAMS. Carol From: Frankl, Istvan Sent: Friday, August 11, 2017 11:13 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: SLR UNR Response, 8/10/17, 4:55 PM Importance: High Carol, (b)(6) .... ' Amy is on concurrence, so she should definitely review the final draft.

             .I -- . I I,_________             . . ......____..j. (b.)(6)

My recommendation is that once you get input from Kenn Miller, ask the AA to prepare concurrence package that Amy can review/initial on Monday. I will do my part on Tuesday. Should I review the draft you sent yesterday or should I wait for the update with Kenn's additions? Thanks, Steve From: Moyer, Carol Sent: Thursday, August 10, 2017 5:01 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

SLR UNR Response, 8/10/17, 4:55 PM Steve, The latest version of the UNR response is attached (& also on G:), incorporating SGS EB comments. If possible, I would like Amy to look at the way I addressed their suggestions. If you

want to deliver it to Brian tomorrow, however, I will finalize the comments (i .e., clean up some "multiple choice" suggestions). Let me know tomorrow, please. As we discussed, your comments have already been addressed , and CIB had no comments. ICEEB comments are still pending (I have not received a response from Kenn Miller yet today). As soon as I do get something , I will fold in those comments. From what I understand, they propose to add one or two examples of specific activities, similar to those now in the document: IFRAM, HRP, ODOBA. Carol Carol Moyer Sr. Materials Engineer RES/DEICMB carol.mover@nrc.gov 301-415-2153

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0 C . 20555-0001 Auigust xx, 2017 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of Nuclear Regulatory Research (RES) to provide "specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period." This user need request {UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years." This UNR also supersedes NRR-2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" and complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation of reactor vessel internals." For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427). The purpose of this memorandum is to respond to this UNR with RES's plans to accomplish the following tasks:

• Task 1: Hold NRC/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR Report.
• Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvestecl from operating plants.
• Task 3: Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research.
• Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applications.

CONTACT : Amy Hull, RES/ DE 301-415-2435

B. Holian RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. RES staff will continue these activities and integrate the results in deliverables under Task 4. The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and the anticipated schedule for the deliverables. RES staff appreciates the coordination with NRR technical staff and management in this area. We will continue to coordinate with NRR staff and management to ensure that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs could impact the activities, deliverables, and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and, if warranted, the UNR will be amended.

Enclosure:

Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

B. Holian

• 3*

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-201 7-006 DISTRIBUTION: B. Thomas, RES G Wilson, NRR R. Tregoning, RES A. Hiser, NRR I. Frankl, RES R. Iyengar, RES T. K.o shy, RES K. Miller, RES D. Seber, RES S. Stuchell, NRR B . Brady, NRR A.Hu ll, RES C. Moyer, RES M. Hiser, RES M. K irk, RES J. Philip, RES M. S ircar. RES J. Peres, RES RidsNrrMailCenter ADAMS Package Access1on No.: Mlxxxx OFFICE RESIDE/CMS RES/DE/CMB RES/DE/CMB REStDEIC18 RES/DE/ICEEB

                                                          - ~

NAME C. Moyer A. Hull I. Frankl ~yaAgaF T. Koshy DATE

             -      I /2017        I /201~    I /2017
                                                        -    It 12Q17     I /2017 OFFICE          RES:DE:SGSEB D:RES:DE      RES Mail Room   D:RES NAME            D. Seber      B. Thomas    K. Johnson     M. Weber DATE              I /2017        I /2017      I /2017      I /2017 OFFICIAL RECORD COPY

Response to User Need Request NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRG/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM oin SECY 14-0016 and in the GALL-SLR Report (NUREG-2191 ). The critical degradation issues are addressed fu rther in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two domestic and international activities (either a workshop, conference, symposium, or meeting), one in early autumn 2018 on mechanical issues and one in late spri ng 2020 on concrete and cables issues. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016;-.,_ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR, and any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for intern ational plants). RES will -specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the fou r major issues identified in the SRM on SECY 14-0016 for SLR. Prior to the meetings, RES will provide a draft agenda with specific topics for the meeting and the proposed presenters. RES will document the information from each of these activities in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting. Mechanical Issues - As part of the requested autumn 2018 workshop/ conference/ symposium/ meeting on mechanical issues, the NRC staff will coordinate a session, or sessions, concerning issues associated wit h reactor vessel embrittlement during the SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. Concrete. Containment and Electrical Cables Issues - RES will also hold an NRG/industry workshop with international participation in the third quarter of FY20 (spring of 2020) on the state of knowledge for the technical issues in concrete, containment, and cables degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific issues and items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before the workshop. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late spring 2020. Task 2 RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES w ill execute the work through a 4-step process, 2.A - 2.0 as stipulated on page 4 of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting.

• In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The deliverable provided criteria to assess the need for harvesting to address a particular technical issue. The report then applied these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and Irradiation-assisted degradation (IAD) of stainless steel. This report also covered the background on the need for harvesting, and past harvesting efforts and experience. The purpose of this report was to serve as a foundation for NRC staff to prioritize technical issues best addressed by harvesting. The initial technical letter report (TLR) for this research is expected to be published in September, 2017, as a PNNL document. This TLR will be reviewed by NRR and RES staff to determine any follow-on work by RES and the final publication type.
• In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The workshop summary report will be distributed among meeting participants and is expected to be finalized by September, 2017. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2.B.

Subtask 2.A. IMovinQ forward, RES will work internally to evaluate how the four significant issues identified Commented [PJ1 ]: Maybe this part could first address for SLR in the SRM on SECY-14-0016 may be best addressed by harvesting. RES will initially what is applicable to all iss ues and then illustrate it with develop an Excel spreadsheet (precursor to the information tool/database) that identifies and examples fo r some issues (in this case concrete and sta inless prioritizes the materials, components, and operating conditions needed to best address the steel). significant issues. Commented [CM2R2): Agreed. In response to t his suggestion, I propose moving the last paragraph of this [ he intent is for this information tool and its Excel precursor i6-to be a living document that section up to the 2M paragraph position. By creating a new 2"' paragraph, Instead, the SGSEB comment Introduces can be updated to reflect the latest operating experience and research. so that users may redundancy and implies an addit ional TLR, causing some understand which data needs may be best addressed by harvesting. RES will provide the confusion. information tool precursor for NRR review. RES also will submit to NRR a companion Technical Letter Report (TLR) that will document,

• how. if applicable. each of the significant issues can be best addressed through harvesting.
• the process to evaluate samples from nuclear plants and their suitability for harvesting.
• processes for harvesting and testing of h~rvested materials and components. and
• harvesting priorities for each significant issues. as applicable.

This TLR will closel relate to the information tool contents and have standalone arts for each of the four significant issues in the SRM. as applicable. Commented [CM3]: Recommend rejecting this Inserted text. RES will apply the criteria developed with PNNL described above to the issues for SLR. and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel). as described above. which will identify and prioritize the materials. components. and environmental conditions that should be pursued for haryestjng. The intent is for this information tool/database to be a living document that ca evolv.e and be updated to reflec.t the lates! operating ew.elienc.e aod,,r_esearcb so tb,at users may understand which data needs can be best addressed bv harvesting. As an example, RES will develop a process to evaluate concrete samples harvested from decommissioned plants, and will follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiat*ion (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)-affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels (PCCVs); corrosion of pre-stressing tendons. liners, reinforcing steel. and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from ~iscussions :o n the potential for harvesting and testing of Commented [CM4]: I agree with the SGSEB comment to concrete from decommissioned reactors, RES will provide in the information tool the make a general statement, followed by the specific CNSC possibilities for this activity and document testing priorities as applicable. As an example. RES example. But something else is needed in the first sentence. has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about Proposals: " ...from discussions wit h regulatory counterparts on the potential...," or, " ...from discussions with possibilities for harvesting concrete from a decommissioned plant in Canada extensively international counterparts on the potential..." affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials. RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001 . RES will aWl¥-!h9-6F~ia-eevelof)QG-With P~IML---desooaed aoove-ta.#le-iss1ies-to~Sl~e will eooufl'loRt tl:!9-outoofl'lo of 11:10 aRalyoio iR aR 'iRfOFfl'latioA too~alaaaoo' ~aaoe(}oR-Miomooft f'IFOdwslo owoR ao Aooooo eF EKoel). ao doooFiaoe abeve, wl>lioR will idoRlify ORd f)fieritize tRe moterialo, 60Rlf'IOR8RIO, aRe 8R'>'iFORR'l8Rtal OORditiORS tl:iat ohould-be-pu~ foF lmweeliR!j. ne iRl8RI ie foF IRio iRfoFfl'taliOR tool/Eloloeaee le 98 a liviR!! 800blfl'l8RI IRal aaR 81101¥8 0R8 98 l,Jf'l88188 to Fefleot the latest Of'l8FOtiR!! 8Kf'l8Fi8A68 0A8 F9080FOhr 60 that tJGOFG R'lay URIOFOl0AEI 'NRiotzi !ala R001G SOR lw lloet 011FOGG01 ey ROPIOGliR!j. IRES will continue to evaluate how the significant issue of cable aging can be addressed by harvesting. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011-014 and NRR-2016-012 to include more sizes and types of cable (insulation types and medium voltage level cables). In addition. there are concerns with aging effects (including cyclic aging} and design life of other electrical components. such as breakers and relays. which can also be harvested and evaluated.I [ Commented (CMS]: Supplied by K. Miller, 8/10/17 Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.D. Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.D., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting. RES will assist in evaluating the value of such components (Subtask 2.D). RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating lo various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the information tool/database. Task 3 RES staff will ooAliAuo lo Elovoloopursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the confirmatory review of industry research used to justify the Commented [CM6]: I think this is not the best word adequacy of their aging management programs (AMPs), as well as for independent here. In our review function, we are not confirming, we are confirmatory research. RES will continue to ~ultivate emerging domestic and assessing, evaluating, appraising, j udging the Industry safety case, including underlying research. ioterpauooal oartnershjps and will cooliYe to develop exjstjno oartnershjps as weu as other Proposals: Delete "confirmatory," or, " ...critical for the suitable opportunities that may emerge to address aging degradation issues. A majority of review and assessment of industry research ...;" or, u ... critical these partnerships will build upon already existing partnerships with the view of supporting for evaluation of Industry research..." assessment of the status of the research and operating experience in relation to SLR needs as Commented [CM 7]: " Nurture" sounds like it applies to well as implementation of a long-term strategy for the use of harvesting of ex-plant materials existing part nerships (keeping them going), but the w ord and components. RES will G0ntin1a10 tg niar;tyro omorgin~ d0mosti0 and intornational "emerging/' and later, "existing,# makes a distinction P8RA8f6Aips 8AG-aWiH OORliAUEHHle>telep ~&tiAg~FtAeF6Aip&,-e&-wel~s GlA8f sllitaole- between future and present programs m entioned In this 0flflB~URi,li86-ilm~a~* eme~!JB la addrnss a!jiR!j-dB!J~adatieR ismms- The following illustrates sentence. some of those key partnerships and specif1ic planned activities. The pt half of this sentence may not be necessary, since the following sentence says we will build on existing partnerships w it h new ones. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs. RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NOE)._ ReS will Gentimie le nurture emerging demestiG and international 13artnershi13s and will OOfltiAll&4o4welefl-these-paFtneFShips, as well a& otA6f-6tlitael&-eppertlliliti0s-tAat-ffiay-ernerge le address agiAg degradatieA issues. RES is a participant in several multi-national cooperative research programs, including the OECD Halden Reactor Project (HRP), the International Forum on Reactor Aging Management (IFRAM), ~ald&A-ReaGteF-PrejeGI (HRP), and many others. For example, the RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. IFRAM is envisioned to be a network of research organizations, industry groups, regu latory bodies, and academic institutions involved in reactor aging management research, regulation, education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the HRP proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These results will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NEA/CSNI activities that develop and assess expertise in the modeling of ASR eaffected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRG in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE, NRR/ DMLR and NRR/DE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task 4 RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2, and 3 on the status of research results iin support of the Commission's direction to the staff. Task 4 also allows for NRR to call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially signif icant issues, such as those needing plant-specific gap analyses. RES will also prepare a document annually summarizing the products from the three tasks abov-e and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Building upon the extensive work previously done under UNR NRR 2014-001 , RES staff will continue to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted w ith SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. Based on the latest assessment of projected needs in this area, RES proposes that the estimate on * * * * * ..jyeac .(tl){~). for this task be adjusted once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closuire of this UNR. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRG-supported research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. The deliverables and schedules for UNR NRR-2017-006 are shown in the following table. Schedule and Resources for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE Contract$ Num ber Date (b)(S) 1 Hold NRG/industry (b)(5) c : Jror FY 18 workshops (est. 2018, 2020) and FY 21 and prepare NUREG/CP and FY 21 [:Jy~ar summary reports on four SRM topics Total (Task 1) I (b)(5) I (b)(S~ [:::;::J(b)(!5) 2 Develop a strategy for harvesting materials/components from decommissioned plants 2.A. Develop an information tool/database FY 18 (b)(S) C J I J (b){S) 2.B. Develop a process to evaluate plant components FY 18 b)(5) CJ 2.C. Use the process from 2.B. to evaluate the suitability of plant components FY 19 (b)(5) c:;::J 2.D. Continue to implement the (b)(5) process from 2.B. as Ongoing (FY c::::)year components become 20-21) (Total available from additional (b)(S) *.. olants 2.E. Pursue partnerships for cooperative cost-sharing on O ngoing (FY18- Included in retrieval and testing of ex- FY21) Task 3, below (b)(5) olant materials Total (Task 2) I .- I (b)(51-t--1 3 Participate in relevant domestic and international activities (e.g., IFRAM, IAEA, FY 18-21 c::::}y ibJi'5)' .. , [:::](ti)(~) (total for 4 years* * (Total 1.0) DOE LWRS, EPRI LTO, IFRAM dues) codes & standards) 4 Develop documentation evaluating significant (~ ear technical issues germane to FY 18-21 (Total Q the review of SLR aoolications (b)(5)' ..

                                                - 10

(b)(5) (b)(5) Total (Tasks 1-4, over 4 years)

                   - 11

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August xx, 2017 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of Nuclear Regulatory Research (RES) to provide "specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period." This user need request (UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years." This UNR also supersedes NRR-2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" and complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation of reactor vessel internals." For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427). The purpose of this memorandum is to respond to this UNR with RES's plans to accomplish the following tasks:

• Task 1: Hold NRG/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues identified in in the SRM on SECY 14-0016 and in the GALL-SLR Report.
• Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvested from operating plants.
• Task 3: Continue to develop domestic and international partnerships to share expertise, capabil ities, and resources related to aging management research.
• Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applicat1ions.

CONTACT : Amy Hull, RES/ DE 301-415-2435

B. Holian RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners . RES staff will continue these activities and integrate the results in deliverables under Task 4. The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and the anticipated schedule for the deliverables. RES staff appreciates the coordination with NRR technical staff and management in this area . We will continue to coordinate with NRR staff and management to ensure that regulatory needs and priorities are satisfied . Changes in the availability of resources or NRR needs could impact the activities, deliverables, and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and, if warranted, the UNR will be amended.

Enclosure:

Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation

B. Holian

SUBJECT:

RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANC E ON POTENTIAL S IGNIFICANT TECH NICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION : NRR-2017-006 DISTRIB UTION: B . Thomas, RES G Wilson, NRR R. Tregoning, RES A. Hiser, NRR I. Frankl , RES R. Iyenga r, RES T. Koshy, RES K. Miller, RES D. Seber, RES S . Stuche ll, NRR B. Brady, NRR A.Hull , RES C . Moye r, RES M. Hiser, RES M. Kirk, RES J . Philip, RES M. S ircar, RES J . Peres, RES RidsNrrMailCenter ADAMS PackaQe A ccess1on N o.: MLxxxx OFFICE RES/DE/CMB RES/DE/CMB RES/DE/CMB RES/DE/ICEEB NAME C. Moyer A. Hull I. Frankl T. Koshy DATE I /2017 I /2017 I /2017 I /2017 OFFICE RES:DE:SGSEB D:RES :DE RES Mail Room D:RES NAME D. Seber B. Thomas K. Johnson M. Weber DATE I /2017 I /2017 I /2017 I /2017 OFFICIAL RECORD COPY

Respo nse to User Need Request NRR-2017-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1 RES staff will continue to hold and participate in NRG/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR Report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two domestic and international activities (either a workshop, conference, symposium, or meeting), one in early autumn 2018 on mechanical issues and one in late spring 2020 on concrete and cables issues. These meetings will address the state of knowledge on the technical issues requested in the SRM on SECY 14-0016, ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR, and any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for international plants). RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period . The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. Prior to the meetings, RES will provide a draft agenda with specific topks for the meeting and the proposed presenters. RES will document the information from each of these activities in a NUREG/CP report, if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge, to be provided within 6 months after each meeting. Mechanical Issues - As part of the requested autumn 2018 workshop/ conference/ symposium/ meeting on mechanical issues, the NRC staff will coordinate a session, or sessions, concerning issues associated with reactor vessel embrittlement during the SLR period. The staff will seek participation from the NRC staff, the regulated US industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. Concrete. Containment and Electrical Cables Issues - RES will also hold an NRG/industry workshop with international participation in the third quarter of FY20 (spring of 2020) on the state of knowledge for the technical issues in concrete , containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific issues and items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before the workshop. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late spring 2020. Task 2 RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, 2.A - 2 .D as stipulated on page 4 of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting.

• In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The deliverable provided criteria to assess the need for harvesting to address a particular technical issue. The report then applied these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report also covered the background on the need for harvesting, and past harvesting efforts and experience. The purpose of this report was to serve as a foundation for NRC staff to prioritize technical issues best addressed by harvesting. The initial technical letter report (TLR) for this research is expected to be published in September, 2017, as a PNNL document. This TLR will be reviewed by NRR and RES staff to determine any follow-on work by RES and the final publication type.
• In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The workshop summary report will be distributed among meeting participants and is expected to be finalized by September, 2017. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2.8 .

Subtask 2 .A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may be best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the latest operating experience and research, so that users may understand which data needs can be best addressed by harvesting. As an example, RES will develop a process to evaluate concrete samples harvested from decommissioned plants, and will follow through with implementing the process as concr,ete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)-affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels (PCCVs); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete from decommissioned reactors, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurr,ently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001. RES will continue to evaluate how the significant issue of cable aging can be addressed by harvesting. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UN Rs NRR-2011-014 and NRR-2016-012 to include more sizes and types of cable (insulation types and medium voltage level cables). In addition, there are concerns with aging effects (including cyclic aging) and design life of other electrical components, such as breakers and relays, which can also be harvested and evaluated. Subtask 2.8. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records. RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.D. Implementation of the evaluation process developed in Subtask 2.8. will be pursued in Subtasks 2.C. and 2.D., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.D). RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively add ress, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the information tool/database. Task 3 RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of industry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research. RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships will build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as innplementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs . RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NDE). RES is a participant in several multi-national cooperative research programs, including t he OECD Halden Reactor Project (HRP), the International Forum on Reactor Aging Management (IFRAM), and many others. For example, the RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. IFRAM is envisioned to be a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research, regulation, education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORNL) submitted white papers to the HRP proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These results will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NEA/CSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE, NRR/DMLR and NRR/DE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task4 RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2 , and 3 on the status of research results in support of the Commission's direction to the staff. Task 4 also allows for NRR to call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses. RES will also prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activit ies supporting SLR during the previous year. Building upon the extensive work previously done under UNR NRR 2014-001, RES staff will continue to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. Based on the latest assessment of projected needs in this area, RES proposes that the estimate of I

• fyear . . . . . . . ( l::l)(5) .

for this task be adjusted once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. D eliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRG-supported research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. The deliverables and schedules for UNR NRR-2017-006 are shown in the following tabl-e. Schedule and Resources for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE Contract$ Number Date 1 Hold NRG/industry workshops (est. 2018, 2020) (b)(5) I ** ** *lf-0r FY18 . . . . (b)(5) and FY 21 and prepare NUREG/CP and FY 21 [3ry~ar summary reports on four SRM topics I (b)(5) I Total (Task 1) ~ I *-

• L(b)(?)

(b){5), 2 Develop a strategy for harvesting materials/components from decommissioned plants 2.A. Develop an information tool/database FY 18 c::::::::l.tb.).(~)..... '~--. I . .... J .(P.).(~) 2.8. Develop a process to evaluate plant components FY 18 I *- - l (b)(~)-. 2.C. Use the process from 2.B. to evaluate the suitability of plant components FY 19 I . .. , (b)(5) 2.D. Continue to implement the (b)(5) process from 2.8. as Ongoing (FY [ 3ye;r components become 20-21) (Total Q available from additional plants (b)(5)'**.. 2.E. Pursue partnership-s for cooperative cost-sharing on Ongoing (FY18- Included in retrieval and testing of ex- FY21) Task 3, below (b)(5) plant materials

                                                                                                 -** ~-***

Total (Task 2)

                                                          ~          - (b)(~)             I                I 3     Participate in relevant                                (b)(5) domestic and international activities (e.g., IFRAM, IAEA,       FY 18-21      c:::JV.ea r                         I * - I (?)<~! ,

(total for 4 years (Total Q DOE LWRS, EPRI LTO, .. IFRAM dues) codes & standards) (b)(S)*... 4 Develop documentation (b)(5) evaluating significant C:]year technical issues germane to FY 18-21 (TotalQ_ the review of SLR (b)(5) aoolications **. Total (Tasks 1-4, over 4 years) I * *(b)(5).

                                                                 .. I                     I    (b)(5),.

I

                                           - 10

Note to requester: Portions of the attachment (immediately following this email) are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Frankl, Istvan Sent: Wed, 25 Jul 2018 14:01:51 +0000 To: Moyer, Carol

Subject:

RE: SLR meeting references Attachments: Response to User Need Request NRR-2017-006 response 20171024.docx Importance: High Sorry, I did not answer your last question. I meant Table 1 on page 6 from the RES response to the SLR UNR. {Attached the enclosure that has the table.). You can also show Chris a summary version of this info if you wish.

Thanks, Steve From: Frankl, Istvan Sent: W ednesday, July 25, 2018 9:54 AM To: M oyer, Ca rol <Carol.Moyer @nrc.gov>

Subject:

RE: SLR meeting references Thanks, Carol. Regarding "version control" I have attached the last version of the exec table I have in my SLR folder. Did you start revising this version for today's briefing? Steve From: Moyer, Carol Sent: W ednesday, July 25, 2018 9:45 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: SLR meeting references Hi Steve, Thank you for the comments. I'll respond to questions below. -Carol From: Frankl, Istvan Sent: Wednesday, July 25, 2018 9:22 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: SLR meeting references Importance: High

Carol, Good plan. I have a few questions/ comments:

1. Are the exec table and the SLR briefing file the only two documents that you updated/ revised?

Yes.

2. Regarding the exec table, I noticed that AM is back as an open sub-issue under Vessel Internals.

I thought Brian did not want AM discussed under the SLR topic as an "open issue" but for now, leave it as is. (Obviously there is synergism for SLR in terms of replacement components). Agreed , and I will concede this point. Partly it's a version control problem, and partly I left it in there just for discussion today. I do not intend to include that topic in inter-office communications on SLR.

3. The IAD UNR supports all work under Vessel Internal (sub-issues 1 - 4), not just sub-issue 1, so this UNR could be shown right next to "Vessel Internals". OK

4. Did Matt/Sri review "Remaining Work" under Vessel Internals? Some info may be missing. (You can follow up on this after the briefing.)

I used their input in updating the table, but I have some uncertainty about version control that I could not sort out last night. This is another reason for the "work in progress" disclaimer in the header!

5. Although several technical UNRs are supporting SLR, I noticed that only a few are shown in the exec table. Is this because work on others were completed? No, they should be included where relevant. I'll continue working on this.

6. I recommend that you also leave with Chris the printout of the table from the response to the SLR UNR that lists all technical UN Rs with associated budgets and FTEs.

Do you mean the Excel table that I used to get the numbers in the speaker note for Brian's Commissioner briefing slide? Again, I am not fully satisfied with data quality on that, but I can bring it to the discussion for reference.

Thanks, Steve From: Moyer, Carol Sent: Wednesday, July 25, 2018 8:38 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

SLR meeting references Hi Steve, I plan to bring the attached references and examples with me to the discussion with Chris today on SLR/LTO research. I plan to focus on the Exec Summary Table and the SLR Briefing (6 pg, detailed) documents. Carol Carol Moyer Sr. Materials Engineer

RES/DE/CMB 301 -415-2153 caro/.mover@nrc.gov

Response to User Need Request NRR-201 7-006 Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation Task 1: Hold NRC/industry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues RES staff will continue to hold and participate in NRG/industry workshops on the status of domestic and international research activities to address and evaluate the status of aging degradation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR report (NUREG-2191 ). The critical degradation issues are addressed further in the Note to Commissioners Assistants "Status Report on Progress of Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal" (ML15160A592). RES will facilitate a minimum of two activities (such as, a workshop, conference, symposium , or meeting) with domestic and international participation, one tentatively planned for spring 2019 on mechanical components and one tentatively planned for summer 2020 on concrete and cables-related issues. In establishing the exact date for these meetings, consideration will be given to the availability of new information on the relevant technical topics. These meetings will address:

• the state of knowledge on the technical issues requested in the SRM on SECY 14-0016,
• ongoing research on materials degradation issues and related aging management as discussed in the GALL-SLR report, and
• any new operating experience from the initial license renewal period (or the long-term operation (LTO) period for international plants).

RES will specifically target these activities toward the resolution of technical issues for effective aging management of systems, structures, and components (SSCs) during the SLR period. The deliverables will include the two international activities (a workshop, conference, symposium or meeting) and summary reports on the research insights and knowledge gained on the four major issues identified in the SRM on SECY 14-0016 for SLR. RES will prepare and will provide to NRR drafts of the agenda, list of invited presenters, and workshop announcement. RES will plan for a workshop announcement and agenda scope to be made public six months before each workshop. RES will document the information from each of these activities in a NUREG report , if appropriate, or by other sufficient means, including, at a minimum, a summary of the activity with all relevant contributions (presentations or technical articles, for example) and research insights and knowledge , to be provided within 6 months after each meeting. Materials Issues for Mechanical Components - As part of the requested workshop/ conference/ symposium/ meeting on materials issues for mechanical components, tentatively planned for spring 2019, the NRC staff will coordinate a session, or sessions, concerning reactor vessel embrittlement and the degradation of reactor internals due to irradiation during the SLR period. The staff will seek participation from the NRC staff, the regulated domestic industry, and representatives from the international industry and regulators. RES will document the product of these sessions (presentations and/or papers) as described above. Concrete, Containment and Electrical Cable Issues - RES will also hold an NRG/industry workshop with domestic and international participation (tentatively planned for summer 2020) on the state of knowledge for the technical issues in concrete, containment, and cable degradation identified in the SRM on SECY 14-0016 and in the GALL-SLR report. The workshop will help RES secure information on research insights and knowledge from the industry, other domestic institutions working on nuclear safety, and from relevant international experts and institutions. Given that cables and concrete issues involve different technical disciplines and expertise, and Enclosure

that research to address some of these issues is still active, RES will plan for a three-day workshop that may include breakout sessions for specific technical topics and items of interest. RES will document the results of the workshop as described above. Task 1 will continue until the completion of the deliverables from this activity, tentatively scheduled for late summer 2020. Task 2: Develop and impllement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvested from operating plants RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from operating plants. RES will execute the work through a 4-step process, described in paragraphs 2.A -2 .D of the UNR. Under a long-term research project preceding the current request from NRR, RES pursued a strategic approach to ex-plant harvesting through two coordinated activities: technical issue prioritization and a workshop on ex-plant material harvesting. In the first activity, RES, with contractor support from Pacific Northwest National Laboratory (PNNL), developed an approach to prioritize technical issues best addressed by harvesting. The criteria for prioritizing harvesting data needs will be described in the anticipated TLR, expected by the end of 2017 "Criteria and Planning Guidance for ExPlant Harvesting to Support Subsequent License Renewal." The TLR will provide criteria to assess the need for harvesting to address a particular technical issue and then will apply these criteria to assess four representative technical issues: electrical cable degradation, embrittlement of cast austenitic stainless steel (CASS), cracking of dissimilar metal welds, and irradiation-assisted degradation (IAD) of stainless steel. This report will also cover the background on the need for harvesting, and past harvesting efforts and experience. In the second activity preceding UNR NRR-2017-006, RES closely collaborated with the Department of Energy (DOE) and Electric Power Research Institute (EPRI) to host a workshop on ex-plant materials harvesting on March 7-8, 2017. The purpose of this workshop was to engage with various stakeholders involved in the harvesting process to discuss all aspects of harvesting, including motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting, lessons learned from past harvesting efforts, and future harvesting program planning. The workshop was designed to discuss past harvesting experience and lessons learned and seek leveraging and cooperation with other interested research organizations. Insights from the workshop are integrated into the database and harvesting planning efforts. The database will be developed consistent with the prioritization criteria from PNNL to identify which sources to focus on. The workshop was well-attended by representatives from DOE, EPRI, the U.S. industry, and international research organizations. Key insights from the workshop included the need for a clearly defined objective to justify the level of effort, and the benefit of early planning and engagement with the plant from which materials will be harvested. The workshop summary report will be distributed among meeting participants when finalized. RES will be pursuing further engagement with interested workshop participants on two outstanding workshop action items: identifying data needs for harvesting and initially creating a 'sources of materials' information tool/database. This is discussed further under Subtask 2.B. 2

Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-14-0016 may be best addressed by harvesting. RES will initially develop an Excel spreadsheet (precursor to the information tool/database) that identifies and prioritizes the materials, components, and operating conditions needed to best address the significant issues. The work in this task includes collecting and inputting information on materials needed and the sources of materials expected to be available. RES will apply the criteria developed with PNNL described above to the issues for SLR, and will document the outcome of the analysis in an 'information tool/database' (based on Microsoft products such as Access or Excel), as described above, which will identify and prioritize the materials, components, and environmental conditions that should be pursued for harvesting. The intent is for this information tool/database to be a living document that can evolve and be updated to reflect the latest operating experience and research , so that users may understand which data needs can be best addressed by harvesting. The purpose of the database is to have a systematic approach to harvesting materials and to prioritize limited resources to provide best value for harvesting. The database is not an end unto itself, but the means to pursue high priority harvesting for the best technical value. As a specific example, RES will develop a process to evaluate harvested concrete samples , and will follow through with implementing the process as concrete materials become available from additional plants. The scope of the harvesting strategy includes: structures exposed to high radiation (typically bio-shield structures of certain PWR designs); alkali silica reaction (ASR)- affected structures; post-tensioned structures with emphasis on pre-stressed concrete containment vessels (PCCVs); corrosion of pre-stressing tendons, liners, reinforcing steel, and embedments; and concrete cores from PWR spent fuel pool or transfer canals (for boric acid effects). Based on information gleaned from discussions with international counterparts on the potential for harvesting and testing of concrete, RES will provide in the information tool the possibilities for this activity and document testing priorities as applicable. As an example, RES has engaged in discussions with the Canadian Nuclear Safety Commission (CNSC) about possibilities for harvesting concrete from a decommissioned plant in Canada extensively affected by ASR. RES also will document the process to evaluate concrete samples from nuclear power plants and their suitability for harvesting. Concurrently, RES will pursue domestic and international partnerships for cooperative cost sharing on the retrieval and testing of concrete samples. In addition to irradiation effects on concrete materials, RES will continue research on IAD of stainless steel. RES will seek potential sources of reactor pressure vessel internals that may become available for harvesting, to evaluate their utility for regulatory research being conducted under UNR NRR-2017-001. RES will continue to evaluate the SLR-significant issue of cable aging using harvested cables. The goal will be to expand on the selection of cable types harvested as part of the existing similar effort under UNRs NRR-2011-014 and NRR-2016-012 to include more cable types (insulation types and medium voltage level cables) and to evaluate the aging effects on power cables at different voltage levels. Subtask 2.B. In parallel with the information tool/database activity, RES will develop an effective process to evaluate the applicability of materials available for harvesting. Based on past experience and 3

insights from the harvesting workshop, the greatest challenge in this area is expected to be acquiring sufficient information from NPPs to make an informed decision on harvesting. In many cases, this information may not exist, or it may be challenging to find in plant records . RES will work internally and with other interested organizations to identify the best approach to gather the relevant information and use it to inform which harvesting opportunities should be pursued. A TLR documenting the information tool/database with prioritized technical issues and a process to identify suitable sources of materials will be targeted for completion by July, 2018. Subtasks 2.C. and 2.0 . Implementation of the evaluation process developed in Subtask 2.B. will be pursued in Subtasks 2.C. and 2.0 ., as requested in the UNR. RES will evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportunities for material harvesting, RES will assist in evaluating the value of such components (Subtask 2.0). RES will remain in close contact with NRR on the latest developments as this process is implemented. The evaluation process will identify confirmatory needs that harvested samples can effectively address, will consider decommissioned plants in the U.S. and abroad, and will leverage resources to the greatest extent possible for domestic and international cooperative research opportunities, as stipulated in Subtask 2.E, which is closely integrated with Task 3. Through their national and international contacts, RES staff will maintain alertness for harvesting opportunities relating to various critical areas, such as reactor vessel embrittlement. Information on these opportunities will be retained in the information tool/database. Task 3: Continue to develop domestic and international partnerships to share expertise, capabiilities, and resources related to aging management research RES staff pursues domestic and international partnerships to share expertise, capabilities and resources related to aging management research for LTO. These exchanges are critical for the regulatory evaluation of indu stry research used to justify the adequacy of their aging management programs (AMPs), as well as for independent confirmatory research . RES will continue to cultivate emerging domestic and international partnerships and will continue to develop existing partnerships, as well as other suitable opportunities that may emerge to address aging degradation issues. A majority of these partnerships will build upon already existing partnerships with the view of supporting assessment of the status of the research and operating experience in relation to SLR needs as well as implementation of a long-term strategy for the use of harvesting of ex-plant materials and components. The following illustrates some of those key partnerships and specific planned activities. The DOE Light Water Reactor Sustainability (LWRS) and the EPRI LTO programs support most of the domestic research on aging management in NPPs. RES maintains separate collaborative research agreements with each of these organizations to exchange technical information. These exchanges are essential for the review and assessment of the technical bases for the viability of LTOs. RES staff have frequent technical exchange meetings with DOE and EPRI staff. These meetings have focused on irradiation effects on concrete, ASR effects, aging management, and supporting technologies like non-destructive examination (NOE). RES is a participant in several multi-national cooperative research programs, including the International Forum on Reactor Aging Management (IFRAM), and many others. The RES Office Director signed a multilateral 4-year memorandum of understanding (MOU) for IFRAM in 2015. 4

IFRAM is envisioned to be a network of research organizations, industry groups, regulatory bodies, and academic institutions involved in reactor aging management research, regulation , education and training, as well as nonprofit research institutes having academic and industrial links enabling appropriate exchange of information addressing issues of NPP SSC aging management. The small effort and contract funding to operate the IFRAM program will be funded by this User Need Request. Other international collaborations pursued by RES are also expected to benefit this work, although resources to support those initiatives are tracked separately. In relation to concrete irradiation, NRC is exploring opportunities to harvest irradiated concrete from decommissioned NPPs worldwide to study irradiation effects under in-service conditions (in coordination with Subtask 2.E). RES and Oak Ridge National Laboratory (ORN L) submitted white papers to the OECD Halden Reactor Project (HRP) proposing research on irradiation effects on the steel-concrete bond, and on creep effects on irradiation damage. RES is also collaborating with HRP on IAD under the auspices of UNR NRR-2017-001 Task 2. These results will inform Task 4 of UNR NRR-2017-006. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES will build upon its ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete, and will continue to participate in OECD/NEA/CSNI activities that develop and assess expertise in the modeling of ASR affected concrete structures. Through their national and international contacts, and through codes and standards development activities, the RES staff will maintain alertness for partnerships to share expertise, capabilities, and resources in all areas of concern, perhaps especially reactor vessel embrittlement. Information on these opportunities will be communicated to NRR in a timely manner as outlined in the deliverables. RES will evaluate products and reports from these organizations that may be provided to NRC in support of generic or plant-specific issues. RES will provide to cognizant NRR staff and management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. These products will be provided in a timely manner and this effort will continue until the closure of this UNR. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during appropriate interface meetings between RES/DE, NRR/DM LR and NRR/DE. A report (or slides) for presentation at appropriate Director/Deputy Director interface meetings will be provided 5 days before the meeting. Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applications This UNR (NRR-2017-006) serves as an "umbrella" under which associated SLR-focused technical UNRs are coordinated. Table 1 below provides additional detail on these UNRs, along with a summary of the level of effort and funding. 5

Table 1. SLR-Related UNRs Associated with UNR NRR-2017-006 UNR# UNR Title Comments NRR-2017-001 Request for This UNR is based on previous UNR NRR-2012-008 and updates regulatory ML16300A303 Assistance to research on void swelling and clarifies current projects and future projects Evaluate that are being considered. RES Response to Irradiation- A third task was added to this UNR for RES to perform confirmatory NRR-2017-001 Assisted evaluation and support ASME code case on new EPRI IASCC crack growth ML17110A202 Degradation of Rx rate curves. Vessel Internals ... F=un~d=in,..1a_:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I (~~~{5) ~;~;~ *t,I=----.. .-.. .-. . .-.. .-.. . --:*"*"* ~"*'"**-::-:-:-****---------------------,1 (b)(5) *c : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : : t : 1a~n~1a~r-2r_!rn i : 5 (b)( ) (b)(5)1 5 (b)( ) FTEs:F.Y.I7:L:. l F.Y.1.Sd land FY19: r **.l fbl!5l NRR-2014-007 Reactor Pressure This UNR superseded I.JNR NRR-2007-001 and includes 6 tasks: (1) ML14126A818 Vessel Integrity Appendix H in process by NRR, NRO, and RES staff; rulemaking funded in Issues FY17 and team in place to finalize rulemaking effort, (2) updating the tech RES Response to bases for Appendix G, (3) examination and analysis of irradiated reactor NRR-2014-007 vessel material, (4) providing emergent technical assistance, (5) maintaining ML14212A127 database and documentation, and (6) performing/ documenting a tech (package) evaluation on irradiation damage mechanisms and potentia l revisions to 10 CFR, part 50 App. G of RG 1.99 "Radiation Embrittlement of Reactor Vessel (b)(5) Materials" Rev 2. (b)( 5) (b)(5) (b)(5)

                                          . Fundina: (b)(5)                      ___                                   ~~J i=Y1S.d            **t FY16 J                  ./ I FY17 -                     ./' FY18 - I 5

(b)( ) .... FTEs: FY16.:.~,.-. 1FY17- I I FY18 - *** .. {b)(5) NRR-2011-014 Assessment of NRR/DMLR's focus on this UNR is to assess andeValuate condition ML11307A205 Cable Condition monitoring methods on electrical cables subjected to accelerated aging Monitoring under normal and accident conditions. RES Response to Accelerated aging of the cable samples is expected to commence toward NRR-2011 -014 Amendment to the end of FY2017. ML11335A169 UNR for The amendment extends the cable testing period up to 80 years (up from 60 Assessment of years in the previous UNR). (b)(S) Amendment to Electrical Cable Funding: _____jb)(5) ... (b)(5) NRR-2011 -014 Condition Prior FY total -1 ** 1 FV1*R*- c=::Jlv19 - c::::::r.FY20 .c:::=;]..(~)(~) (NRR-2016-012) ML16096A221 Monitoring FTEs: Prior FY total --l.....:;JF'(;,8 - [JFY19 (b)(5) (b)(5)

                                                                                                                                     -LJ          FY20 (b )(5)
                                                                                                                                                          =r:::r-(b )(5)-_

NRR-2012-004 Alkali-Silica The objective of this UNR is to develop technical bases for regulatory ' ML12109A324 Reaction (ASR) guidance for evaluating ASR-affected concrete structures, primarily focusing Research on impact on the structural capacity under design basis loads through its RES Response to service life, including PEO, and its aging management. The research at NRR-2012-004 NIST includes obtaining data on highly instrumented concr-ete block ML12152A107 specimens to monitor the progression of ASR and assess its impact on in-(b)(S) situ mechanical properties, conducting destructive testing to assess

                                             . structural impact including seismic response, evaluating numerical modeling 5

(b)(S) f!l.. (b)( ) ** e****!*h* bds; andmateriaL as~~.~ts for determining the state....and .r.ate ot.ASE-,

                                             . Furiding:FY14 4                               I FYl5 ~*                         1 FY16 -*            .. - I FY17 -~

(b)(5 r *Ftl;s;:FY14:d : . . .,. F:Y:46,.:.r i FY16 -r -l-F.YJ] - I ....,.... (p)(S)" (b){5) (b)/5) NRR-2015-007 Effects of The purpose of this UNR is to develop technical basesfor regul~Jc:iry ..(b)(5) ML15076A217 Irradiation on guidance to evaluate radiation effects on concrete structures close to ** ............... . Concrete reactors. The focus of r-elated regulatory research is to evaluate the impact RES Response to Structures on structural capacity under design basis loads for service life up to 80 years NRR-2015-007 and develop aging management strategy. ML15229A100 (b)(5) The project includes reviewing EPRI and DOE reports by ANL (contract (b)(5) ****** awarded in Jan 2016), harvesting the materials from the decommissioned (b)(5 )

                                              .Jpse..Cabrer~_t-JPP in Z-orita, Spain (b)(5)

Furiding:.fY16 t:=J FTEs:*FYi/S"'.::f"'lFYH:.r,FY1ar-,::::Jb)(5) FY17 '-r--=7FY18 ~ ****** +

                                                                                                                                     .------, (b)(5) 6

RES staff will document the review of the technical issues germane to the review of SLR applications. This will include, but may not be limited to, a summary of products from Tasks 1, 2, and 3 on the status of research results in support of the Commission's direction to the staff. RES will prepare a document annually summarizing the products from the three tasks above and discussing the accomplishments of RES and national! and international partners in addressing the major technical issues in the SRM. This annual report will be at a sufficiently high level to be used to support briefings for the Commission or Advisory Committee on Reactor Safeguards, Commission Assistants' Notes, reporting to the public and interested stakeholders, or other requests for briefings on SLR. This annual report will be provided in the first quarter of each calendar year, beginning in the first quarter of calendar year 2018, discussing the research activities supporting SLR during the previous year. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) _ot L - ltyear for this task be adjusted once the scope of work and the required level of RES staff involvement is better understood after the first SLR application is received in early FY18. Technical assistance products and SME support will be provided to NRR in a timely manner, and this effort shall continue until the closure of this UNR. Task 5 (Optional}: Provide expert assistance with reviewing SLR applications Under this optional task, NRR may call upon RES to provide independent confirmatory analyses and expert technical assistance with the review of anticipated SLR applications with potentially significant issues, such as those needing plant-specific gap analyses. Building upon the extensive work previously done under UNR NRR 2014-001 , RES staff will continue to be available to provide confirmatory analyses and expert technical assistance with the review of the technical documents to be submitted with SLR applications. RES will be available to support tighter SLR application review schedules as well as the review of plant-specific gap analyses expected with the first applications. RES subject matter experts (SMEs) will be available to participate in technical discussions, independent reviews, development of technical bases, and support of meetings with internal and external stakeholders. As an example, the staff will continue to be available to review operational equipment failures to assess the trend in critical risk-significant electrical equipment. There are concerns with aging effects (including cyclic aging) and design life of other electrical components, such as breakers and relays, which would need further evaluation to assess their continued service life by exploring other monitoring techniques not generally covered under surveillance tests. Such analyses could complement work in Task 2, whereby critical electrical components can also be harvested and evaluated. These SLR-related studies are being pursued independently of this UNR, and the work is being tracked through existing communication between RES and NRR staff. Deliverables and Schedules RES staff will participate in periodic meetings with NRR staff and management to discuss the latest developments and information from industry and NRG-supported research, as well as collaborative research, particularly insights that may impact regulatory decisions or aging management guidance. Staff-level interactions are expected to be as frequent as needed. RES agrees with the deliverables proposed by NRR, with some adjustments to the schedule 7

based on expected project completion dates. RES staff will closely coordinate with NRR staff and adjust the schedules for deliverables as needed to support effective regulatory decision making. The deliverables and schedules for UNR NRR-2017-006 are shown in Table 2. Table 2: Schedule and Resources1 for the Various Tasks Period of Performance (FY 18-21) Task Task Description Completion FTE Contract$ Number Date (b)(5) 1 Hold NRC/industry workshops (b)(5) I ** *fforFY-18 (est. 2018, 2020) and prepare and FY 21 NUREG/CP and summary FY 21 0 ye*ar reoorts on four SRM tooics I (b)(5)1 Total (Task 1) Q (b)(§.) I **..... I

                                                                                                                                  /&)(5) 2            Develop a strategy for harvesting Ex-Plant materials/components 2.A. Develop an information tool/database                                FY 18               C:J.1t:i)(?( _                      I           .. J J?)(~)

2.8. Develop a process to evaluate G J b)(5) ____ FY 18 plant components 2.C. Use the process from 2.8 . to evaluate the suitability of plant FY 19 [=:] t~)(?(___ components 2.0. Continue to implement the (b)(5) process from 2.8. as Ongoing (FY 20- [ 3year * **

• components become available 21) (Total Q from additional plants (b)(5D 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in Task retrieval and testing of ex-plant FY21) 3, below (b)(5) materials Total (Task 2) I " I L....::;;J (tl)(5) 3 Participate in relevant domestic and international activities (e.g.,

FY 18-21 c::::3'year , (b)(5) I (total for 4 years 1..(~)(5) IFRAM, IAEA, DOE LWRS, (Total Q IFRAM dues) EPRI LTO, codes & standards) <ti){s 4 Develop documentation (b)(5) evaluating significant technical c:::::)year FY 18-21 issues germane to the review of (Total Q SLR aoolications (b)(5) 5 Provide technical assistance to -. To be funded if To be funded if (optional) NRR for reviewing SLR FY 18-21 needed needed aoolications. Total (Tasks 1-4, over 4 years) I I I I (b)(5)' ,, (b)(5)* .. (b)(5) (b)(5) 1 Note that t he resources associated with t his UNR include RES/DE/ SGSEB c=):~E/yr over 4 years andL J and RES/DE/CMB (balance), All other SLR-related work is covered by the UN Rs shown in Table 1. 8}}