ML21152A255

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

ML21152A255
Person / Time
Issue date:	05/24/2021
From:	NRC/OCIO
To:
References
NRC-2018-000831
Download: ML21152A255 (252)

Text

{{#Wiki_filter:Note to requester: The attachment (an email record) is immediately following this email. Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hull, Amy Sent: Thu, 23 Jul 2015 17:09:10 -0400 To: Frankl, Istvan (b )(5) Cc: Hiser, Matthew;Stout, Kathleen (b)(5) ... . L.--

Subject:

                . ...--.. . .---..----------------1 OK, understand .. good news from PNNL, attached !

Attachments: RE: RFP Steve Unwin has assigned Pradeep to work with Katie on this project, as technical lead. See attached. Pradeep is well-aware of work on SLR and LTO and harvesting of ex-plant materials and developing infotools. I have worked with Pradeep before on a project on AET for HTGRs. It is great ! and I am delighted ! From: Frankl, Istvan Sent: Thursday, Ju ly 23, 2015 4:39 PM To: Hull, Amy Cc: Hiser, Matthew; Stout, Kathleen (b)(5)

Subject:

RE:y~ryi111pe>rtc1nJ. - - - - - - - - - - - - - - - - - - - - - - - - - - - , (b)(5) J.. . . .... Amy, (b)(5) Thanks, Steve From: Hull, Amy Sent: Thursday, July 23, 2015 4 :02 PM To: Frankl, Istvan Cc: ~iser, Mat_thew; Stou,...t._

                                            '. K

_a__t_h__ le__ e_n _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___, (b)(5) ..... SYb1ect;veryunp.ortantJ (b)(5) .j . Hi Steve,

Work is progressing quickly now and we should have the Lab cost proposal in 10 days. See attached. From: Frankl, Istvan Sent: Thursday, Ju ly 23, 2015 1 :26 PM To: Stout, Kathleen Cc: Thomas, Brian; Brock, Kathryn; Rao, Appajosula; Iyengar, Raj; Baquera, Mica; Martinez, Erick; Hull, Amy

Subject:

(b)(5) Kathleen , (b)(5) Thanks, Istvan (Steve) Frankl Branch Chief RES/DE/CMB U.S. Nuclear Regulatory Commission Phone: (301) 251-7901 E-mail: lstvan.Frankl@nrc.gov

Note to requster: This email is the attachment to the previous email record . From: Hull, Amy Sent: Thu, 23 Jul 2015 20:34:40 +0000 To: Unwin, Stephen

Subject:

RE: RFP Thanks for the response . I will see Pradeep next week at the QNDE meeting . Amy From: Unwin, Stephen .Unwin@pnnl.gov Sent: Thursday, July 23, 2015 4:33 PM To: Hull, Amy

Subject:

[External_Sender] RFP Hi Amy: Thanks for the RFP and phone call. I've spoken to Katie and I believe we have it in hand . Subject to confirmation, Pradeep Ramuhalli will be our technical lead. Steve Stephen D. Unwin, Ph.D. Manager Nuclear Sector Energy & Environment Directorate Pacific Northwest National Laboratory P.O. Box 999, MSIN K9-69 Richland, WA 99352, USA Tel: 509-375-2448

Note to requester: Portions of the attachment, which is immediately following this email, are redacted under From: Hiser, Matthew FO IA Exemption B5, Deliberative Process Privilege. Sent: Wed, 1 Jul 2015 20:40 :51 +0000 To: Hull, Amy

Subject:

PNNL Harvesting Checklist.docm Attachments: PNNL Harvesting Checklist.docm

     -'U.S.NRC Uut,4 St:atca W.Jnr Lp,.I..,. Co-l  in
 ,.,_.,,,,.r..,-""",..£,,...._,                                            REQUISITION CHECKLIST: /AA/ DOE LABS VERSION CONTROL DATE: JANUARY 26, 2015 Click Here to Hide Purpose The purpose of the Requisition Checklist is to assist Contracting Officer's Representatives (CORs) in developing a complete requisition package. This checklist must be completed and uploaded to the supporting documents library in STAQS before the requisition is routed for approval.

The Requisition Checklist is required for new interagency agreements (including DOE Laboratory Agreements), new task/delivery orders under existing Enterprise Wide Agreements, and modifications to interagency agreements and task orders involving scope changes or ceiling increases. Using the Template: For each item, choose YES, NO or NIA in the right column. Additionally, you can click "Show Additional Guidance" for more guidance information and links to resources. To view the navigation pane, HOLD ALT and PRES V then D to open, use this to navigate through the template. For assistance, please contact the Business Advisory Center (BAC) at BAC.Resource@nrc.gov. I. REQUISITION INFORMATION TO BE PROVIDED IN STAQS Completion of this section is optional ; however this information will be required for completion of your STAQS requisition. COR Name: Amy Hull Purpose & Description of Strategic Approach for Obtaining Material and Component Reaulsltlon: AJ?inJ? Information APP# (If applicable): APP-15-RES-0011 Amount To Be Funded: *** * * * * * *I ' {~)(5) Product/Service Code: R425 - ENGINEERING AND TECHNICAL SERVICES Click Look UP PSC Code Here here to enter Other PSC NAICS Code: 541990 -All Other Professional, Scientific, and Technical Services Search FPDS.Qov or Search Census.Qov Click here to enter Other NA/CS SA Commodity Code: Research Type of Action : Task Order Business Advisory Center (BAC): No Enter BAC Contact Here Notes to Buyer (if applicable): Click here to enter Notes. 1

      -'U.S.NRC Uut,4 St:atca W.Jnr Lp,.I..,. Co-l  in
  ,.,_.,,,,.r..,-""",..£,,...._,                                          REQU ISITION CHECKLIST: /AA/ DOE LABS VERSION CONTROL DATE: JANUARY 26, 2015 II. REQUISITION PACKAGE REQUIREMENTS: IAA/ DOE LABS 11.STRATEGIC SOURCING GROUP (SSG) (EXCLUDING EWA ORDERS)                                                                       I Has this been approved by the Strategic Sourcing Group (SSG)? Hide Additional Guidance Is this requirement valued at $1 Mor more? If yes, please upload the SSG approval to No the supporting documents library in STAQS.

[Please contact the Business Advisorv Center for access to the SSG Template.] 1 z.STATEMENT OF WORK/ PERFORMANCE WORK STATEMENT I A Have you provided a Statement of Work (SOW)? Hide Additional Guidance

                 -     DOE Laboratoty Agreement                                                                    Yes
                 -     lnteragency Agreement B       Are any aspects of the SOW Inherently Governmental Functions?                                              No C       Does the SOW require contractor performance of work that is closely associated to inherently governmental functions?                                                                         No I 3. INDEPENDENT GOVERNMENT COST ESTIMATE ( IGCE)                                                                              I Have you completed an IGCE? Hide Additional Guidance IGCE Templates:

Official Use Only - IGCE for Argonne National Laboratory (ANL) Official Use Only - IGCE for Brookhaven National Laboratory (BNL) Official Use Only - IGCE for DOE Labs other than ANL, BNL, INL, ORN L, PNNL and SNL Official Use Only - IGCE for Idaho National Laboratory (INL) Yes Official Use Only - IGCE for Oak Ridge National Laboratory (ORNL) Official Use Only - IGCE for Pacific Northwest National Laboratory (PNNL) Official Use Only - IGCE for Sandia National Laboratory (SN L) Official Use Only - IGCE for lnteragency Agreements (Other than DOE Labs) I 4. URGENT REQUIREMENTS I Is this requirement urgent? If so, upload the urgency determination to the supporting documents library in STAQS. No DOE Lab Urgency Statement 2

      -'U.S.NRC Uut,4 St:atca W.Jnr Lp,.I..,. Co-l  in
  ,.,_.,,,,.r..,-""",..£,,...._,                                    REQUISITION CHECKLIST: /AA/ DOE LABS VERSION CONTROL DATE: JANUARY 26, 2015 I 5. JUSTIFICATIONS (FOR DOE LAB AGREEMENTS ONLY)                                                                       I A       A DOE Source Selection Justification (SSJ) NRC Form 367 is required to be completed and uploaded to the supporting documents library in STAQS for the following actions:

• New DOE Lab agreement No
• Modification to a DOE Lab agreement or task order that involves a change to the scope of work.

B EWA Source Selection Justification template (applies to EWA's only and is required for all EWA Task Orders). Yes

16. DETERMINATIONS AND FINDINGS (D&F) (FOR NON-DOE LAB IAA ONLY) I A Is a D&F required? FAR 17.502 The Econom~ Act N/A B If so, upload the D&F to the supporting documents library in STAQS.

N/A D&F Temolate I 7. ADDITIONAL APPROVALS I A Personnel Security/Facility Access Hide Additional Guidance If any of the following situations apply, have you uploaded the NRC Form 187, Security/Classification Requirements, to the supporting documents library in STAQS?

                 -     Access to Classified Information
                 -     Facility Clearance
                 -     Unescorted Access to Nuclear Power Plants No
                 -     Access to Unclassified Safeguards Information
                 -     Access to Sensitive IT Systems And Data
                 -     Unescorted Access to NRC HQ Buildings
                 -     Require Operation of Government Vehicles or Transport Passengers for the NRC
                 -     Will Operate Hazardous Equipment at NRC Facilities
                 -     Required to Carry Firearms
                 -     Found to Use or Admit to Use of Illegal Drugs B       Personally Identifiable Information (PII) Hide Additional Guidance No Do the agreement requirements require access to PII to receive, process, and/or possess information?

C Access to a NRC System of Records Hide Additional Guidance No 3

     -'U.S.NRC Uut,4 St:atca W.Jnr Lp,.I..,. Co-l  in
 ,.,_.,,,,.r..,-""",..£,,...._,                                   REQUISITION CHECKLIST: /AA/ DOE LABS VERSION CONTROL DATE: JANUARY 26, 2015 Do the agreement requirements involve contractor access to {design , develop, or operate) a NRC System of Records to accomplish an agency function subject to the Privacy Act of 1974?

D Training Hide Additional Guidance Is training required as part of the requisition? Office of Chief Human Capital Officer (OCHCO) approval is required if the agreement is for training services and/or materials. Please upload the approval (email) from the Chief Learning Officer or designee to the No supporting documents library in STAQS. Branch Chief of Learning Operations Branch: Leslie Donaldson Leslie .Donaldsonra>nrc.qov E Do the requirements include hosting a conference or large meeting? No F Space Approval Hide Additional Guidance Approval is required if NRC Headquarters space is to be used in performance of the No agreement (i.e. , contractor needs office space). Please upload approval from Office space coordinator. 18.INFORMATlON TECHNOLOGY (IT) APPROVALS I A Does this requisition include the requirement for the contractor to provide ELECTRONIC AND INFORMATION TECHNOLOGY (EIT) as a deliverable? Hide Additional Guidance Examples of EIT include the following items, or upgrades to the following items:

         - Software application or operating system (e.g., word processing application, accounting software, authoring and document presentation tools)
         -     Web-based Internet information and applications (e.g., Websites)
         -     Desktop or portable computer (e.g., laptops, PCs, PDAs}
         -     Electronic office product (e.g., photocopiers, calculators, fax machines, printers)           No
         -     Telecommunication product (e.g., telephones, cell phones, pagers)
         -     Video and multimedia product (e.g., televisions, VCRs, DVD players)

If YES , proceed to 9B. If NO, enter NO in the column to the right and proceed to Requirement 10. If unsure, please email CRM.Resource@nrc.gov to determine whether or not IT approvals apply. B If YES , are the exact items that are required listed on the NRC's Technical Reference Model (TRM)? Hide Additional Guidance N/A If the exact items are in the TRM , include a screen shot of the relevant TRM section as a supportinq document in STAQS and proceed to 8D. However, if your item has "Pendinq" 4

      -'U.S.NRC Uut,4 St:atca W.Jnr Lp,.I..,. Co-l  in
  ,.,_.,,,,.r..,-""",..£,,...._,                                  REQU ISITION CHECKLIST: /AA/ DOE LABS VERSION CONTROL DATE: JANUARY 26, 2015 or "Pending Final Review" on the TRM list, this has not been approved by the 1TB. You will need to have 1TB approval; therefore, please proceed to BC.

C If NO to 8B: Complete the Environment Change Request (ECR) form located on the IT/IM Board (1TB) SharePoint site and send the completed form to CRM.Resource@nrc.gov. Hide Additional Guidance Once you obtain the required IT/IM approval(s) from CRM.Resource@nrc.gov, proceed N/A to requirement 8D. Contact CRM.Resource@nrc.gov with any questions or for assistance with this step. D Go to www.buyaccessible.gov, take the following steps: click on "Buyers," click on "Enter Wizard ," click on "New Wizard Session", answer the questions it asks you (click "More Information ..." to obtain clarification or more details), and click "Next" after answering each question. Hide Additiona l Guidance This will help you to determine whether Section 508 of the Rehabilitation Act of 1973, as N/A amended, applies to your EIT requirement, and if so, which criteria apply. Once you are done answering the questions, generate the report and upload it to the supporting documents library in STAQS as a supporting document, along with IT/IM approval(s). If you need additional guidance please contact John Beatty (John.Beatty@nrc.gov). I 9, FUNDING I A Is this requisition subject to availability of funds? No B Is this work FEE-RECOVERABLE? If yes, identify the required TAC codes in the requisition. No If you have any questions, please contact OCFO. 5

From: Frankl, Istvan Sent: Wed, 22 Nov 2017 17:48:17 +0000 To: Audrain, Margaret; Hiser, Matthew;Pu rtscher, Patrick Cc: Hull, Amy

Subject:

RE: ACTION: New Emergent Domestic Trip for CMB Importance: High

Meg, Thanks for your inputs.

Please work with Matt and go forward with the scheduling of the DE management briefing on ex-plant harvesting in early December. The briefing should cover the overall objectives and plans for the harvesting project going forward, including the full plan for how the inventory will be determined and how this aspect fits into the holistic harvesting framework and strategy. Our tentative plans to reach out to all the labs should also be part of the briefing. (Expect pushback on this from DE management.)

Pat, Your related trip in December is basically a rescheduling of an already approved trip, so please submit the trip request with eTravel ASAP.

Thanks, Steve From: Audrain, Margaret Sent: Wednesday, November 22, 201712:04 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: ACTION: New Emergent Domestic Trip for CMB

Steve, In response to Brian's question: yes, we have contacted ANL and they have a very good understanding of what we're looking for. We have some input in the area of irradiated materials and they will work before our trip to compile materials in other areas.

In response to Chris's question: We had tentative plans to reach out to all the labs this FY but didn't really get going with this effort until after the travel call. Instead of waiting until next year, we thought it would be best to tag an extra half day or so on to existing trips to the labs (Pat's ANL trip, my PNNL and Knoxville trips). We can set up a briefing for early Dec if needed. Please let me know.

Happy Thanksgiving, Meg From : Frankl, Istvan Sent: Wednesday, November 22, 201710:34 AM To: Audrain, Margaret <Margaret.Audrain@nrc.gov> Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov> Subject : ACTION: New Emergent Domestic Trip for CMB Importance: High

Meg, Brian and Chris have good questions on the upcoming harvesting trip to ANL.

In your reply to me, please address the highlighted items below. Please reach out to Matt and Amy if you need assistance. If possible, please reply today. My sense is that management would benefit from a briefing on harvesting and on our plans going forward. We need to be more proactive in this area.

Thanks, Steve From: Thomas, Brian Sent: Wednesday, November 22, 201710:06 AM To: Regan, Christopher <Christopher.Regan@nrc.gov>; Oberson, Greg <Greg.Oberson@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: New Emergent Domestic Trip for CMB

Steve, Please refresh my memory - is the explant harvesting contract with ANL? And do you have any input from ANL on the pro osed framework for harvesting and identifying explant materials?

From: Regan, Christopher Sent: Wednesday, November 22, 2017 9:49 AM To: Oberson, Greg <Greg.Oberson@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Thomas, Brian <Brian.Thomas@nrc.gov>

Subject:

RE: New Emergent Domestic Trip for CMB Greg, Steve, I approve. BUT

Steve, I'd like to be informed of the full plan for how the inventory will be determined and how this aspect fits into the holistic harvesting framework and strategy. In theory, had we a fully defined strategy this trip should have been identified and not be considered an "emergent" travel need.

Thanks, Chris From: Oberson, Greg Sent: Wednesday, November 22, 2017 9:44 AM To: Regan, Christopher <Christopher.Regan@nrc.gov>

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

Subject:

New Emergent Domestic Trip for CMB

Chris, Steve requested the emergent travel below. I have added to the running list on sharepoint:

http://fusion.nrc.gov/res/team/de/Divison%20Meeting%20Docs/Travel/FY 18%20Travel/FY 18%2 Otravel%20workbook%20-%20emergent.xlsx Funds are available if you approve. Greg From: Frankl, Istvan Sent: Tuesday, November 21, 2017 6:59 PM To: Oberson, Greg <Greg.Oberson@nrc.gov> Cc: Audrain, Margaret <Margaret.Audrain@nrc.gov>

Subject:

New Emergent Domestic Trip for CMB

Greg, We have another emergent domestic trip next month. Here are the details:

Begin to assemble an inventory of available ex-Priorit pant materials y2-Licen from ANL to ANL Ex- consider for the Aud C Do Mis se Argon Me plant 12/13/ 12/13/ $40 rain M mes sion and ne, harvesting g Harvestin 2017 201 7 0 B tic Regul IL program in g Review ation coordination Relat with that in t he ed INL NSUF Nuclear Fuels and Materials Library (NFML).

This activity directly supports SLR UNR NRR-2017-006. Please note that Pat has changed the date of his approved travel to ANL from April 2018 to next month. The cost of his approved travel is lower by $400 which covers the cost of the above emergent trip.

Thanks, Steve

Note to requester: Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hiser, Matthew Sent: Fri, 3 Apr 2015 11:44:58 +0000 To: Frankl, Istvan

Subject:

RE: ACTION : Request of FYlS Reprommed Funds Hi Steve, My understanding is Amy will be the COR and I will be her backup / assist with some of the tasks, but with all her and my other responsibilities (including Srini's party), we haven't had time to move this forward very much. Hopefully once I return from travel the week after next we can regain some momentum on this .. . Thanks! Matt From: Frankl, Istvan Se nt: Thursday, April 02, 2015 4:34 PM To: Hiser, Matthew

Subject:

RE: ACTION: Request of FY15 Reprommed Funds Thanks, Matt. My understanding was that you were going to assist Amy with the requisition for the strategic harvesting project as COR (or backup COR?). In any case, please reach out to her on this topic. This project has been "languishing" and we will need to proceed with the requisition during this quarter. Steve 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 CMB Restack Importance: High All , As some of you know we had to provide detailed inputs and clarifications to DE management for some of our projects today. Thanks for all of you who participated in this exercise. I . .. ...J (l:l)(5) (b)(5) readsheet w ith the best-estimate s (b)(5) ro*ects. 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) 1Please input the information requested below in sheetlI .___________,J~/.(~L 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 Monda~. Thanks, Steve

Note to requester: The attachments are immediately following this email. Portions of the attachments are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Thu, 19 Oct 201718:33:04 +0000 To: Frankl, Istvan Cc: Hull, Amy

Subject:

RE: ACTION: Revised Draft Response to SLR UNR Attachments: memo SLR UNR response 09-22-2017 (002)BT comments ABH (IF) cem.docx, Response to User Need Request NRR-2017-006 (002).response BT comments abh (IF) EMF cem.docx 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.Moyer@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 Tuesd~ 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 cha nges: 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 UN R Cassandra sent me a version - 9/22 - that predates the version that Brian gave me, and I think predates the version you signed off on (your signature is 9/25). I guess I will wait until Weds (b)(6) ~OE:!QL .  ! 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 ver sion 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?: q uestion -- 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 <Amy.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 .Savoy2@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 .  ! 1am implement ing 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>; Moyer, 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: Moyer, Carol <Carol.Moyer@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: question -- package in ADAMS for SLR UNR

Hi, l got it. What was the fc1st new version that you sent to Cassandra? WE have fours versions in ADAMS; 2 versions from August ,wd 2 versions this month. l will be here to help before I get offat 1:40pm today. Thanks cSJrticieh WerrI 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, Graciella <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), CMB 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 in ADAMS for SLR UNR still old - - this should have new documents??? - do we have duplicate packages? RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON Package Name POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION NRR-2017-006 Accession Number ML17227A483 Package Propenies j Paste into Package Add Document Profile Download Chock Ou1 I Refcesh I Name O - ~A- c-cessioo Number I Official ~ ec-or-d?_

                                                                                                         . __   Availability-ooc

_ u~ nt_D_ AD- AMS D~ te Added

• t*~ -

Non-Publacly Aug 15, 2017 J*OO SLR UNR response 08- 14-2017 cln (002).docx ML17227A484 No Available PM Response 10 User N-1 Request NRR-2017- Non-Publicly Aug 15, 2017 J*OO ML17227A485 No 006 docx Avo,labka PM There are 2 Documents m this Package I( ( Pago 1 ol 1 > )I https ://adamsxt. n re .gov/AdamsXT/packagecontent/packageContent. faces ?id={355A25 00-E6F3-4E 19-A8D8-C627FDDE9FFB}&objectStoreName=Mainlibrary&w ld= 1506629912784

IIJNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555,0001 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. W eber 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 Tasks A and D of 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," andThis U~lR ~lRR 2017 006 serves an integFatii;e function , prnviding as an "umbrella" under which Gtl=lefassociated SLR-focused technical UNRs are coordinatedput in context. These technical UNRs supported include NRR:-2017-001 (reactor vessel internals); NRR-2014-007 (reactor pressure vessel}, NRR-2016-012 (electrical cables). NRR-2012-004 and NRR-2015-007 (concrete degradation). More details on these UNRs are rovided inSee Table 1 of iR-+ask--4 the Enclosure. For tracking purposes, RES has designated this UNR as NRR-2017-006 ML16358A427D~- _ __ Commented [HA1]: confirm the correct ADAMS#. Different from that on the concurrence page. The purpose of this memorandum is to respond to U NR NRR-2017-006 with RES's plans IF: The Ml# on the concurrence should be differe nt and to accomplish the following tasks: should be the ML# for the concurrence package.

• Task 1: Hold NRG/industry workshop(s) on the status of domestic and international Commented [CM2R2]: Confirmed: This is the ML# for the UNR package.

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 g-ermane to the review of SLR applications.
• Task 5: Provide expert assistance with reviewing SLR applications (optional task)

B. Holian 2 CONTACT: Amy Hull, RES/ DE 301-4 15-2435 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 te*chnical 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:

1. 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 SIGN IFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION : NRR-2017-006 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._l'v1cty'er, RES _ _M.Hiser, RES M. Kirk, RES J. Philip, RES M. Sircar, RES J. Pires, RES RidsNrrMailCenter ADAMS Packa 1e Accession No.:ML17227A483 OFFICE RES/DE/CMB RES/DE/CMB RES/DE/CMB NAME C. Mover A. Hull I. Frankl DATE I /2017 I / 2017 I /201 7 OFFICE D:RES:DE RES Mail D:RES NAME M. Weber DATE

                    -B. Thomas I /2017-J$_,Johnson 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 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 NRR-2017-0~h - ~uestfor This UNR is bBased on a orevious UNR NRR- 2012-00Bj!illj updates Commented [IF1]: Why are some UN Rs highlighted on ML16300A303 Assistance to !Reregulatory- research-prejeGI on void swelling and clarifies currentwhal this page? Evaluate proj ects-RES-i&--wff8Ally-ilwel~-with and wllat--future projects that are RES Response to Irradiation- bein g considered. Commented [CM2R2]: fixed NRR-2017-001 Assisted A third task was added to this UNR forMYe RESJQ perform confirmatory ML17110A202 Degradation of Rx evaluation and support ASME code case on new EPRI IASCC crack growth Vessel Internals rate curves. E.\!ill!indGontracl* Commented [IF3]: Please double-check by FY. (b)(S) FY17:I ......,. ................................ 1(b)(S) Commented [CM4R4]: Confirmed with UNR response. (b)(S) FY1'8'

                                                                           ...............                                                          and FY19:

(b)(S) (b)(S)I (b)(S) l'TEsl: FYU;I ... i"FY't8*: t .... I and FY19:I *-! 1011::,1 Commented [IFS]: Same as above NRR-2014-007 Reactor Pressure Thfs UNR superseded UNR NRR-2007-001 and includes 6 tasks: (1) ML14126A818 v 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 NRR-2014-007 vessel material, (4) providing emergent technical assistance, (5) maintaining ML14212A127 database and documentation, and (6) perform ing/ 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 (b)(S) Materials" Rev 2. (b)(S) (b)(S) (b)(S)

                                         ~                       :                       . (b)(S)                                                                   Commented [IF7]: Same as above (b)(S) FY15 ~~ Y16 ; ~

FT.Es~f..¥-1 6-* ** FY17 FYH :~~y~~

• FY18 i *** ....... )(

4 *t

• Commented [IFS]: Same as above NRR-2011-014 Assessment of NRR/DMLR's focus on this UNR is to assess and e'valuate condition ML11307A205 v Cable Condition monitoring methods on electrical cables subjected to accelerated aging Monitoring under normal and accident conditions.

RES Response to Accelera ted 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 ears in the previous UNR). (b)(S) (b)(S) (b)(S) (b)(5) 9:i ca** ~hV~~1 .. -1:*1 Amendment to Electrical Cable undin : Commented [CM9]: Input from T. Koshy NRR-2011-014 Condition f NRR-2016-0121 Monitoring ~ ML16096A221 j (b)(~)5 ' 7hit,;) ~:)(5)_ NRR-2012-004 Alkali-Silica The objective of this UNR is to develop lechn1cal bases for rel)ulatory 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 o btaining data on highly instrumented concrete block ML12152A107 v (b)(5) specimens to monitor the progression of ASR and assess its impact on In- (b)(S)

                                     **sttu-mec.b.anical properties, conducting destructive testing to assess                                                                                ...-~-*

(b)(S) (b)(S) structural frifp*act..inc!~ding seismic response, eval uating numerical modeling b)(S) ~~--***. (b)(5) (b)(S) *******~~:~E~~~ r~i~-~lt*~:~ r:'.,~7~[~2~*;* J*:*** : :i~iisL . . ********** .. Commented [IF10]: Same as above. NRR-2015-007 Effects of The purpose of this UNR is to develop technical b ases for regulatory 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 requlatorythe research is to evaluate the RES Response to Structures impact on structural capacity under design basis loads for service life up to NRR-2015-007 80 years and develop aging management strategy. ML15229A100 The project includes reviewing EPRI and DOE reports by ANL (contract awarded in Jan 2016), harvesting the materials from the decommissioned (b)(S) Jose Cabrera N ~rita, Spain (b)(S)

                                      ...F1mdino*-FY16 - -               FY17 .r---::::,H1S *r - : J(b)(5)

FTEs:IFY16 -t .. 1FY17 -t ..lfYJ!!.*I 1 **. Commented [IF12]: Same as above.

                                                                                                       *-...._                                                      Commented [CM13R13]: Input from D. Seber (b)(S) . \

(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. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) or j jyear for this task be adjusted once the scope of work and the required level of RES

      ***sfafif 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 closely coordinate w ith NRR staff and adjust the schedules for deliverables as needed to support effective regu latory 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 (b)(5) 1 Hold NRC/industry workshops \U/\CJ/ L..,;;;;:JTOt FY 18 (est. 2018, 2020) and prepare and FY 21 NUREG/CP and summary FY 21 0 Year reoorts on four SRM tooics Total (Task 1) II {b){5il (b)(5)y 2 Develop a strategy for harvesting Ex-Plant materials/components {b)(5) 2.A. Develop an information FY 18 b)(5) C:J [:::J ' tool/database 2.B. Develop a process to evaluate plant components FY 18 b)(5) C:J 2.C. Use the process from 2.B. to evaluate the suitability of plant FY 19 comoonents (b)(5) 9=l 2.D. Continue to implement the process from 2.B. as Ongoing (FY 20- c:::Jyear components become available 21) \Totalc:::J (b from additional plants b)(5 \ - * (~.) . 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY 18- Included in Task retrieval and testing of ex-plant FY21) 3, below (b)(5) materials Total (Task 2) ~ (b)(5F ? 3 Participate in relevant domestic and international activities (e.g., (b)(5) c::::Jyear c:::::J .(~)(5) FY 18-21 (total for 4 years * *- IFRAM, IAEA, DOE LWRS, (TotalC) IFRAM dues) EPRI LTO codes & standards) 1bll;' 4 Develop documentation (b)b evaluating significant technical - year FY 18-21 issues germane to the review of (Total 0 (b)(o) SLR aoolications 5 Provide technical assistance to To be funded if To be funded if (optional) 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

Note to requester: Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Iyengar, Raj Sent: Tue, 12 Apr 2016 13:09:39 -0400 To: Hiser, IMatthew;Frankl, Istvan

Subject:

RE: ACTON: Major Unfunded List Modifications Steve, I used some of Matt's information and added the below benefit to line 2 of the worksheet. I have not added any information on Cables and Concrete. I will check with Ilka on that. Depending upon what she has, I can provide some input (or not) to her. (b )(5) Raj From: Hiser, M atthew Sent: Tuesday, April 12, 2016 12:49 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Iyengar, Raj <Raj .lyengar@nrc.gov>

Subject:

RE: ACTON: Major Unfunded List Modificat ions Hi Steve, (b)(5) Thanks! Matt From: Frankl, Istvan Sent: Tuesday, April 12, 2016 12:13 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Iyengar, Raj <Raj. lyengar@nrc.gov>

Subject:

FW: ACTON: Major Unfunded List Modifications Importance: High Raj , Matt, (b)(5) Please provide your inputs ASAP. Thanks, Steve From: Frankl, Istvan Sent: Monday, April 11, 2016 4:50 PM To: Rossi, Matthew <Matthew. Rossi@nrc.gov>; Oberson, Greg <Greg.Oberson@nrc.gov>

Subject:

FW: ACTON: Major Unfunded List Modifications Importance: High Matt, Greg, (b)(5) I need your input by 11 AM tomorro Thanks, Steve From: Berrios, Ilka Sent: Monday, April 11, 2016 4:16 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Rudland, David <David .Rudland@nrc.gov>; Burke, John

<John.Burke@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>

Cc: Thomas, Brian <Brian.Thomas@nrc.gov>; Brock, Kathryn <Kathryn.Brock@nrc.gov>

Subject:

FW: ACTON: Major Unfunded List Modifications Importance: High All,

Please see email below from Veronica Portillo. Please update the benefit column. Please provide your input by tomorrow at noon from Brian and Kathryn's review.

Thanks,

~ 415-2404 From : Dennis, Suzanne Sent: Monday, April 11, 2016 4:09 PM To: Armstrong, Kenneth <Kenneth.Armstrong@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov> Cc: Correia, Richard <Richard.Correia@nrc.gov>; Lund, Louise < Louise.Lund@nrc.gov>; Webber, Kimberly <Kimberly.Webber@nrc.gov>; Johnson, Joanne <Joanne.Johnson@nrc.gov>; Ki, DaBin <DaBin.Ki@nrc.gov> Subject : FW: ACTON: Major Unfunded List Modifications Importance: High Ilka, These updates are for your items. j (b)(5) Kenneth .I Sound good? Suzanne From: Portillo, Veronica Sent: Monday, April 11, 2016 3 :07 PM To: Johnson, Joanne <Joanne.Johnson@nrc.gov> Cc: Dennis, Suzanne <Suzanne.Dennis@nrc.gov>; Ojeda, Jennifer <Jennifer.Ojeda@nrc.gov>; Lund, Louise <Louise.Lund@nrc.gov> Subject : ACTON: Major Unfunded List Modifications Importance: High Hi Joanne, Jenny and I met with Bill Dean this morning on the Lower Priority and Major Unfunded Lists and he requested the following revisions to the RES items. (b)(5)

(b )(5) Please provide you 're your revised input by COB, tomorrow, April 12th . Thank you! Veronica From: Dean, Bill Sent: Monday, April 11, 2016 11:55 AM To: Weber, Michael <Michael.Weber@nrc.gov>; Hackett, Edwin <Edwin.Hackett@nrc.gov> Cc: Ojeda, Jennifer <Jenn ifer.Ojeda@nrc.gov>; Portillo, Veronica <Veronica.Portillo@nrc.gov>; Ross-Lee, MaryJane <MaryJane .Ross-Lee@nrc.gov>; Gavrilas, Mirela <Mirela.Gavrilas@nrc.gov>; Evans, Michele <M ichele.Evans@nrc.gov>; McDermott, Brian <Brian.McDermott@nrc.gov>

Subject:

Major unfunded list modifications (b )(5) !just met with m bud et team on the ma*or unfurided list and wanted ou to be aware of two thin s: (b )(5) Bill Dean Director Office of Nuclear Reactor Regulation

Note to requester: Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Frankl, Istvan Sent: Tue, 12 Apr 2016 13:27:12 -0400 To: Hiser, Matthew Cc: lyenga r, Raj

Subject:

RE : ACTON : M ajor Unfunded List Mod ificat ions Thanks a lot Matt. Sorry, line item 2 is for row 6 in the spreadsheet. I have added your inputs to the spreadsheet. Steve From: Hiser, M atthew Sent: Tuesday, April 12, 2016 12:49 PM To: Frankl, Istva n <lstvan.Frankl @nrc.gov>; Iyengar, Raj <Raj.ly engar@nrc.gov>

Subject:

RE: ACTON: Major Unfunded List Mod ificat ions Hi Steve, (b)(5) Thanks ! M att From : Frankl, Istva n Sent: Tuesday, April 12, 2016 12:13 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Iyenga r, Raj <Raj. lyengar@nrc.gov>

Subject:

FW : ACTON : Major Unfunded List M odifications Importance: High Raj, Matt, (b)(5) Please provide your inputs ASAP.

Thanks, Steve From: Frankl, Istvan Sent: Monday, April 11, 2016 4:50 PM To: Rossi, Matthew <Matthew.Rossi@nrc.gov>; Oberson, Greg <Greg.Oberson@nrc.gov>

Subject:

FW: ACTON: Major Unfunded List Modifications Importance: High Matt, Greg, (b )(5) I need your input by 11 AM tomorrow. Thanks, Steve From: Berrios, Ilka Sent: Monday, April 11, 2016 4:16 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Rudland, David <David.Rudland@nrc.gov>; Burke, John

<John.Burke@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>

Cc: Thomas, Brian <Brian .Thomas@nrc.gov>; Brock, Kathryn <Kathryn.Brock@nrc.gov>

Subject:

FW: ACTON: Major Unfunded List Modifications Importance: High All , Please see email below from Veronica Portillo. Please update the benefit column. Please provide your input by tomorrow at noon from Brian and Kathryn's review. Thanks,

..J'&a 415-2404

From: Dennis, Suzanne Sent: Monday, April 11, 2016 4:09 PM To: Armstrong, Kenneth <Kenneth.Armstrong@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov> Cc: Correia, Richard <Richard.Correia@nrc.gov>; Lund, Louise < Louise.Lund@nrc.gov>; Webber, Kimberly <Kimberly.Webber@nrc.gov>; Johnson, Joanne <Joanne.Johnson@nrc.gov>; Ki, DaBin <DaBin.Ki@nrc.gov>

Subject:

FW: ACTON: Major Unfunded List Modifications Importance: High Ilka, These updates are for your items. (b)(S) Kenneth Sound good? Suzanne From: Portillo, Veronica Sent: Monday, April 11, 2016 3 :07 PM To: Johnson, Joanne <Joanne.Johnson@nrc.gov> Cc: Dennis, Suzanne <Suzanne.Dennis@nrc.gov>; Ojeda, Jennifer <Jennifer.Ojeda@nrc.gov>; Lund, Louise <Louise.Lund@nrc.gov>

Subject:

ACTON: Major Unfunded List Modifications Importance: High Hi Joanne, Jenny and I met with Bill Dean this morning on the Lower Priority and Major Unfunded Lists and he requested the following revisions to the RES items. (b)(5) Please provide you're your revised input by COB, tomorrow, April 12th . Thank you! Veronica

From: Dean, Bill Sent: Monday, April 11, 2016 11:55 AM To: Weber, Michael <M ichael.Weber@nrc.gov>; Hackett, Edwin <Edwin .Hackett@nrc.gov> Cc: Ojeda, Jennifer <Jennifer.Ojeda@nrc.gov>; Portillo, Veronica <Veronica.Portillo@nrc.gov>; Ross-Lee, MaryJane <MaryJane.Ross-Lee@nrc.gov>; Gavrilas, Mirela <Mirela.Gavrilas@nrc.gov>; Evans, Michele <M ichele .Evans@nrc.gov>; McDermott, Brian <Brian.McDermott@nrc.gov>

Subject:

Major unfunded list modifications (b )(5) I just met with m bud et team on the ma *or unfunded listandwanted ou to be aware of two things: Bill Dean Director Office of Nuclear Reactor Regulation

Note to requester: Portions of this record are redacted under FOIA Exemption 85, Deliberative Process Privilege. From: Purtscher, Patrick Sent: Tue, 12 Sep 2017 07:56:39 -0400 To: Hull, Amy;Hiser, Matthew

Subject:

RE: can we talk about parking for adv mfg$ per Frankl: URGENT ACTION: FY18 Budget Allocation for CMB Contracts (b)(5) o me more a out it, am war mg ram hor'n!3 to ay until 0:30 am. (b )(5) . Pat From: Hull, Amy Sent: Monday, September 11, 2017 3:46 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

can we talk about parking for adv mfg$ per Frankl: URGENT ACTION : FY18 Budget Allocation for CMB Contracts Pis See below comments from Steve. From: Frankl, Istvan Sent: Monday, September 11, 2017 8:37 AM To: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: 2 questions: URGENT ACTION : FY18 Budget Allocation for CMB Contracts (b)(5)

Thanks, Steve From: Hull, Amy Sent: Monday, September 11, 2017 7:21 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

2 questions: URGENT ACTION: FY18 Budget Allocation for CMB Contracts

(b)(5) From: Frankl, Istvan Sent: Sunday, September 10, 2017 11:04 PM To: RES_ DE_CMB <RESDECMB@nrc.gov>

Subject:

URGENT ACTION : FY18 Budget Allocation for CMB Contracts Importance: High CORs, (b)(5) If you have questions, please come by my office to discuss. Thanks, Steve

Note to requester: Portions of this record are redact ed under FOIA Exemption B5, Deliberative Process Privilege. From: Hiser, Matthew Sent: Mon, 6 Jun 2016 19:29:46 +0000 To: Frankl, Istvan

Subject:

RE: COR Actions Will do! From: Frankl, Istvan Sent: Monday, June 06, 2016 3 :03 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Subject:

RE : COR Actions Great idea. Please wait until I get response from Amy. From: Hiser, Matthew Sent: Monday, June 06, 2016 3 :02 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE : COR Actions (b)(5) I will add the COR change to the funding REQ for the I Ion that contract. From: Hiser, Matthew Sent: Monday, June 06, 2016 3 :00 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE : COR Actions Oh no, I have no objection - just wanted to confirm © From: Frankl, Istvan Sent: Monday, June 06, 2016 2 :55 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Subject:

RE: COR Actions I think it makes sense for him to assume COR duties for this project, I believe Amy was retained as COR only because of loss of Aloysius. Amy will still be involved in the technical monitoring of this contract. I will send separate email to Amy on this soon. Any reason why we should not make this COR change?

Thanks, Steve

From: Hiser, Matthew Sent: Monday, June 06, 2016 2:40 PM To: Frankl, Istvan <lstvan .Frankl@nrc.gov>

Subject:

RE : COR Actions Hi Steve, OK, so replace Amy with Pat as the COR for PNNL work? Thanks! Matt From: Frankl, Istvan Sent: Monday, June 06, 2016 2:34 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

COR Actions

Matt, My understanding is that Pat is now a certified COR Level I, so please subm it ZEROREQ to add him as COR to the Strategic Harvesting contract with PNNL. (You will still be the backup COR.)

Also, please submit ZEROREQ to extend the POP for the contract with INL. Thanks , Steve.

Note to requester: Portions of this record are redacted under FO IA Exemption B5, Deliberative Process Privilege. From: Frankl, Istvan Sent: Thu, 6 Oct 2016 13 :34:06 -0400 To: Hiser, Matthew Cc: Purtscher, Patrick

Subject:

RE: Harvesting FY17 Funds Thanks for your timely inputs. Steve From: Hiser, Matthew Sent: Thursday, October 06, 2016 1:31 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

Harvesting FY17 Funds Hi Steve, Pat and I discussed the FY17 budget for the harvesting contract at PNNL and agree that we could get by (b)(5) withr:::::=Jin FY17 to do what we need to do with PNNL. Thanks and let us know if you need any more information! Matt

From: Hiser, Matthew Sent: Tue, 19 Jan 2016 20:39:04 +0000 To: Ramuhalli, Pradeep

Subject:

RE: Harvesting Information Tool (Reactor Reliability and Integrity Management) Project Hi Pradeep, FYI - links to public meetings on SLR guidance documents this week: http://adamswebsearch2.nrc.gov/webSea rch2/view?AccessionNumber=M L 16013A054 http://adamswebsearch2.nrc.gov/webSearch2/view?AccessionNumber=M L16015A055 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: 301-415-24541 Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Ramuhalli, Pradeep [1] Sent: Tuesday, January 19, 2016 11:58 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matt hew.Hiser@nrc.gov> Cc: Knobbs, Katie <katie.knobbs@pnnl.gov>

Subject:

[External_Sender) Harvesting Information Tool (Reactor Reliability and Integrity Management) Project Amy, Matt: Happy new year! We have made some progress on this work in the last few weeks (especially around Task 1.1 and the information tool example development). We'd like to go over the status with you (hopefully next week, if that works with your schedule), and begin to populate and update questionnaires as needed. If I recall, the plan was to present some of the example info tool screens and potential questionnaires with your advisory group prior to RIC (which is in March), and roll out the questionnaire at RIC to pot ent ial stakeholders. (b)(5) On a related note, we have about ,__ _ _ _ _ _ _ _ _ _ _ _ __.This will likely take us through the middle of next month. What should I be doing to request the next increment of funding for continuing work on this project? Thanks!

With best regards, Pradeep Pradeep Ramuhal li, 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 Email : pradeep.ramuhalli@pnnl.gov http ://www.pnnl .gov

From: Frankl, Istvan Sent: Tue, 21 Jun 2016 08:54:17 -0400 To: Hull, Amy Cc: Purtscher, Patrick;Hiser, Matthew

Subject:

RE: harvesting project? ACTION: Use of Excess FY16 Funds in CMB

Amy, Thanks, Steve From: Hull, Amy Sent: Tuesday, June 21, 2016 8:10 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Purtscher, Patrick <Patrick. Purtscher@nrc.gov>; Hiser, M atthew <Matthew.H iser@nrc.gov>

Subject:

harvesting project? ACTION: Use of Excess FY16 Funds in CMB From: Frankl, Istvan Sent: Monday, June 20, 2016 2 :55 PM To: RES_ DE_CMB <RESDECMB@nrc.gov>

Subject:

ACTION: Use of Excess FY16 Funds in CMB Importance: High

CORs, (b)(5)

Thanks, Steve

From: Moyer, Carol Sent: Fri, 16 Feb 2018 16:37:23 +0000 To: Frankl, Istvan Cc: Hull, Amy

Subject:

RE: line item after discussions? ... : FY20 DE OR major unfunded items 2-9-18 rlt.xlsx Attachments: Copy of FY20 DE OR major unfunded items 2-9-18 rlt.abh-cib-cmb-cem.xlsx Note to requester: The attachment is immediately following this email record.

Steve, Non Responsive Record

Thanks, Carol From: Frankl, Istvan Sent: Friday, February 16, 2018 9:55 AM To: Hull, Amy <Amy.Hull@nrc.gov>

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

Subject:

RE: line item after discussions?...: FY20 DE OR major unfunded items 2-9-18 rlt.xlsx

Amy, Non Responsive Record

Thanks, Steve From: Hull, Amy Sent: Friday, February 16, 2018 8:27 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

line item after discussions? ... : FY20 DE OR major unfunded items 2-9-18 rlt.xlsx Steve, INon Responsive Record Thanks, Amy From: Frankl, Istvan Sent: Monday, February 12, 2018 9:48 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: 2nd of 2 initial responses... : FY20 DE OR major unfunded items 2-9-18 rlt.xlsx Amy, Carol, INon Respon,;,e Reco,d Steve From: Moyer, Carol Sent: M onday, February 12, 2018 8:52 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: 2nd of 2 init ial responses... : FY20 DE OR major unfunded items 2-9-18 rlt .xlsx Steve, INon Respon,;,e Reomd Carol From: Hull, Amy Sent: Monday, February 12, 2018 8:31 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Moyer, Carol <Carol.Moyer@nrc.gov> Subject : 2nd of 2 initial responses...: FY20 DE OR major unfunded items 2-9-18 rlt.xlsx Hi Steve, Non Responsive Record From: Frankl, Istvan Sent: Friday, February 09, 2018 9:59 PM To: Hull, Amy <Amy.Hull@nrc.gov> Cc: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

FW: FY20 DE OR major unfunded items 2-9-18 rlt.xlsx Importance: High

Amy, Noa Respoos;,e RecoJ

Thanks, Steve, From: Tregoning, Robert Sent: Friday, February 09, 2018 4:30 PM To: Iyengar, Raj <Raj.lyengar@nrc.gov>; Frankl, Istvan <Istvan.Frankl@nrc.gov>

Subject:

RE: Copy of FY20 DE OR major unfunded items 2-9-18 rlt .xlsx Raj: Noa Respoos;,e Reco,dl Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671

From: Iyengar, Raj Sent: Friday, February 09, 2018 4:26 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: Copy of FY20 DE OR maj or unfunded items 2-9-18 rlt.xlsx Rob, Non Responsive Record Raj From: Tregoning, Robert Sent: Friday, February 09, 2018 4:08 PM To: Iyengar, Raj <Ra j.lyengar@nrc.gov>; Frankl, Istvan <Istvan.Frankl@nrc.gov>

Subject:

Copy of FY20 DE OR major unfunded items 2-9-18 rlt.xlsx Steve/Raj: Non Responsive Record Cheers, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671

Non Responsive Record Official Use Only At1achment 3 Items presented ,n the FY 2020 Ma1or Un funded List are pnont1zed highest to lowest wit. h,n each business hne. FY 2020 Budget . Operating Reactors Major Unfunded Items Major Projected FTE Unf\mded FYlO Budget Must adhere To!>I {SK) Request CS&T {IK) to full integer CS&T {SK) auidance Business Hem Line/Product Buslntss (b)(5) Benefit of Funding for This Item Product Line Product ProJecUActMty Tille Offlco Description of ProJecUActMty Describe what wHI b9 accomplish<ld by funding this item. Dot:!Q!..describe the impact of Risk of not funding this Item No. Line Priority Line not funding this item. (H, M, L) OR-H Operating Research Aging and Research actl\litles on RES Research projects on Irradiation-assisted damage of vessel Internals, Lad< of addffional funds will delay the ReactOfS Materials maleria!s degradation and enhancement of component integrity toots for confirmatory anatyses, development of technical bases for Research Irradiation assisted strategic Initiatives to haNesling reactor mater\als toobtain useful evaluation of Irradiation-assisted degradation (IAD) researcli infonnation on materials aging and degradation from decommis$ioned degradation at high nuence,. This may t plants. These projects will support long-tem, operations (LTO) of nudear delay rev.ion of ap~icable aging power plants and subsequent license renewal (SLR). management programs and the review of SLRapplications re<:eived beyond the 2020p<riod. Non Responsive Record Official Use Only* Pre-Decisional Information 107

FY 2020 Budget* Operating Reactors Major Unfunded Item, Major Projected FTE Unfunded FYlO Budget Must adhere Total (SK) Request CS&T (SK) to fuJI integer CS&T (SK) nu/dance Business (b)(5) I Benefit of Funding for This Item Item Line/Product Business Product Line Product Project/Activity Title Office Description of ProjectJActivlty Describe what wif be accomplished by fvnding th~ ,am. Do!Jg/_des""" lh* impact of Risk of not funding this item No. Line Priority Line no( funding this item. IMM II Non Responsive Record Official Use Only - Pre-Decisional Information 108

Note to requester: All the attachments are immediately following this email. From: Moyer, Carol Sent: Tue, 30 Jan 2018 17:45:28 +0000 To: Frankl, Istvan Cc: Hull, Amy;Hiser, Matthew

Subject:

Revised Descriptions for RIC posters Attachme nts: NRC 1102 - AM 20180130.pdf, NRC 1102 - Harvesting 20180130.pdf, Consolidated ePoster Titles and Descriptions from QTE (in alpha order) as of 120417_compare.docx

Steve, Can you please review and approve the attached revised Description paragraphs for the RIC posters on Additive Manufacturing (#6) and Harvesting (#8)? These have been revised as follows:

1. 6AM Revised title (shortened to fit poster template)

Revised text to match what is now on the significantly-revised poster [Note, the text on the RIC website now is incorrect. The text shown for poster #6 should be with poster #8 . RIC staff have been asked by email to change it, but the text remains. Perhaps a replacement Form 1102 will precipitate the needed corrections.]

1. 8 Harvesting Revised title (shortened to fit poster template)

Revised text to reflect QTE recommended edits. I was advised by Brennet Warren on the RIC Team that posters #6 & #8 were not selected for OGC review. The revised posters were submitted to QTE, with a copy to the RIC Team, this morning. The revised Description forms must also go to QTE for editing before the revised titles and text can be uploaded for the conference program. Bren stressed that this was time-sensitive. Please let me know if you have any questions. Thanks, Carol Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol.moyer@nrc.gov 301-415-2153

NRC FORM 1102 U.S. NUCLEAR REGULATORY 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. Harvesting of Aged Materials from Nuclear Power Plants Descriptio n: Description should be innovative, succinct, and include key elements such as purpose, learning objectives, focus areas, and/or take-away messages. Recent plans to shut down a number of nuclear power plants 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 to 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. 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) (Acro nyms) (Non-NRC) Remove(*) Matthew Hiser Materials Division of RES 1 Engineer Engineering 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. Carol Moyer (carol.moyer@nrc.gov, 301-415-2153) - Revised form submitted 1/30/2018 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

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

               \,.,¥\
                   ......~i RIC PROPOSED DIGITAL PRESENTATION SUBMISSION FORM D Original Submission

[Z] 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" width x 22.5" height) mounted on a floor stand; one USB media player; one remote control; one small table and one chair.

• Digital Presentation (Single-slide): Format is a one-slide PowerPoint. Word limit is 400-500 . Limit of 5-6 large photos, images, or 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. Review of Additive Manufacturing by Direct Metal Laser Melting

== Description:== 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 CY2018. In 2017, industry prototyping efforts involved use of the direct metal laser melting (DMLM) method to manufacture parts for reactor components. RES is beginning to evaluate the technology to gain insight into any technical issues that must be addressed to assure safety and reliability of specific DMLM-produced components that may be 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 & standards activities. This poster will give an overview of NRC findings and preliminary 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 and Last Name Position Title Division Title (NRC) (Acronyms) (Non-NRC) Remove(-) 1 Amy Hull Senior Materials Division of RES [!][:] Engineer Engineering 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. Carol Moyer (301-415-2153) - Revised form submitted 1/30/2018 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

                                             'Chl3-15          ,Jn1111al Heg11lato1y
                                                               !11/hrmation Co1ifermCf!

Digital Presentations (ePosters) =9Fouped(Grouped in alpl:ta-oFd&FAlphabetical Order) Non Responsive Record

                       'Chl3-15 ,Jn1111al Heg11lato1y
                                !11/hrmation Co1ifermCf!

Non Responsive Record 2

                                                    'Chl3-15            ,Jn1111al Heg11lato1y
                                                                        !11/hrmation Co1ifermCf!

Non Responsive Record 6 RES- =Evaluation of Add itive Manufacturing of Metallic Parts via Direct Metal Laser Me lting 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.- Extending 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
                                !11/hrmation Co1ifermCf!

Non Responsive Record 4

                       'Chl3-15 ,Jn1111al Heg11lato1y
                                !11/hrmation Co1ifermCf!

Non Responsive Record 5

                       'Chl3-15 ,Jn1111al Heg11lato1y
                                !11/hrmation Co1ifermCf!

Non Responsive Record 6

                       'Chl3-15 ,Jn1111al Heg11lato1y
                                !11/hrmation Co1ifermCf!

Non Responsive Record 7

Note to requester: Portions of this record are redacted under FOIA Exemption 85, Deliberative Process Privilege. From: Frankl, Istvan Sent: Tue, 12 Sep 2017 17:14 :12 -0400 To: Hiser, Matthew Cc: Purtscher, Patrick

Subject:

RE: REMINDER - URGENT ACTION: FY18 Budget Allocation for CMB Contracts Thanks, Matt. Steve From: Hiser, Matthew Sent: Tuesday, September 12, 2017 4:06 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

RE: REMINDER - URGE NT ACTION: FY18 Budget Allocation for CMB Contracts Hi Steve, (b)(6) I wasn't able to touch base with Pat toda If it's alri ht with Pat (b)(5) ........................*(~o~n_2 , ---iiiiiiiiiiii----iiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiii;.====== = - - - - - - - - - - - _ J cc£J.l.L (b)(5) 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: 301-415-2454 I Office: TWFN 10D62 Matthew.Hiser@ nrc.gov From: Frankl, Istvan Sent: Monday, September 11, 2017 3:38 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, Matthew

                                <Matthew.Hiser@nrc.gov>; Huill, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;

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

Subject:

REMINDER - URGENT ACTION: FY18 Budget Allocation for CMB Contracts Importance: High All , So far, only one COR responded to the enclosed request. Please make sure to provide inputs by COB tomorrow. Thanks,

Steve From: Frank l, Istvan Sent: Sunday, September 10, 2017 11:04 PM To: RES_ DE_CMB <RESDECMB@nrc.gov>

Subject:

URGENT ACTION : FY18 Budget Allocation for CMB Contracts Importance: High

CORs, (b)(5)

If you have questions, please come by my office to discuss.

Thanks, Steve

Note to requester: The box with the X inside it is the Word attachment. Portions of the attachment , which is immediately following this email, are redacted under FO IA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Wed, 9 M ay 2018 12:33:47 +0000 To: Hull, Amy;Hiser, Matthew

Subject:

RE : REM INDER ACTION : Prep for the Upcoming NRR/DMLR - RES/DE Quarterly UNR Status Meeting Attachments: EPID st atus sheet - MDA_cem 20180509.docx Amy & Matt, I have a couple of minor questions on Page 4 of the attached. Can you take a look, please?

Thanks, Carol 0

From: Hull, Amy Sent: Wednesday, May 09, 2018 7:33 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: REMINDER ACTION: Prep for t he Upcoming NRR/DMLR - RES/DE Quarterly UNR Status Meeting Looking at it quickly, the SLR part looks OK to me. Carol do you seen anything else that needs to be done? From: Frankl, Istvan Sent: Tuesday, May 08, 2018 5:00 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Purtscher, Patrick < Patrick. Purtsche r@nrc.gov> Cc: Audrain, Margaret <Margaret.Audrain@nrc.gov>

Subject:

REM INDER ACTION: Prep for the Upcoming NRR/DMLR - RES/DE Quarterly UNR Status Meeting Importance: High

All, This is friendly reminder for you to complete this action by COB tomorrow.

Thanks, Steve

From: Frankl, Istvan Sent: Tuesday, May 01, 2018 2:44 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosu la.Rao@nrc.gov>

Subject:

ACTION: Prep for the Upcoming NRR/DMLR - RES/DE Quarterly UNR Status Meeting Importance: High

All, The next quarterly meeting with DMLR management is scheduled for May 16. The format will be the same as last time, i.e. the BCs will summarize the status of UNRs/

RARs using the EPID based format that was used during the last meeting. This action is for the UNR POCs to update the EPID status tables for their UNRs. Please use the following links for your updates and make sure to save and close the file immediately after you complete your update: G:\DE\CMB\User Needs\EPID Summary\EPID status sheet - MDA.docx G:\DE\CMB\User Needs\EPID Summary\EPID status sheet - SGl.docx If someone else is using the file, please notify the user to exit the file. Please note that it is important to keep track changes on, so that I will be able to review the revisions. Also, we are planning to revise some of our UNRs and expect new RARs/UNRs in FY18, FY19 and FY20, so please capture the related FTEs and funds in the Resource Summary table of the specific EPID file. Even if we don't have UNR/RAR in place, please make sure to capture follow-on work in this table. (Please add a new row to the Resource Summary table for each new UNR, RAR or follow-on work.). Please complete this action b COB Wednesday, May 9.

Thanks, Steve

Materials Degradation, Analysis and Mitigation Techniques (R-201 6-M DA-0001) UNRs and Research P lans Assianed to Materials

Dearadation,

Analvsis and Mitiaation Techniaues NA ME Accession Response UNR Date Number Accession Num ber UNR NRR-2013-005: User-Need Request to Develop the Technical Bases for the ML13053A171 ML13151A073 March 2013 Evaluation of Neutron Absorbina Materials in Soent Fuel Pools UNR NRR-2014-001: User Need Request for the Office of Nuclear Regulatory ML13312A267 ML14058A673 February 2014 Research to Provide Expert Assistance with Revising the Guidance Documents for SubseQuent License Renewal UNR NRR-2014-010: User Need Request on Chemical Effects Research to Support ML14198A156 ML14272A392 August 2014 GSl-191 Resolution UNR NRR-2017-001: ReQuest for Research Assistance to Evaluate Irradiation- ML16300A303 ML1711OA202 January 2017 Assisted Dearadation of Reactor Vessel Internals UNR NRR-2017-006: Research Assistance on Potential Significant Technical Issues ML16358A427 ML17227A483 May 2017 During the SubseQuent Period of Extended Operation UNR NRR-2017-010: User Need Request: Flaw Evaluation. Repair and Mitigation ML17166A526 ML17227A004 July 2017 Techniaues for Primarv Water Stress Comosion Crackina FY18 Executed to Date (FTE/SK*) I FY18 Plan (FTE/SK..) I Materials

Dearadation,

Analvsis and Mitiaation Techniaues Resource Summarv FY19 Plan (FTE/$K) I FY20 Plan (FTE/SK) UNR NRR-2013-005 NAM) (b )(5) UNR NRR-2014-001 SLR Assist.\ UNR NRR-2014-010 GSl-1 91 ) UNR NRR-2017-001 IADI UNR NRR-2017-006 SLRI UNR NRR-2017-010 PWSCC Task 11 EPID Total Product Total "Total includes FY17 carrvover contract funds executed in FY18

   * *Total includes FY18 contract funds only
   ...Some resources for irradiated materials testing are executed for FY18 in the EPID: Vessel Integrity (RPV and Internals). and are reported on that status sheet. The resources will be formulated in the EPID: Materials Degradation, Analysis and Mitigation Techniques beginning in FY19. This is the cause of the resource increase for this EPID in FY19.

UNR NRR-2013-005 NAMl Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number TLR on qualification and an RES : E. Focht Start Date: 1/18 1 1.1 assessment of surveillance NRR: M . Yoder Proj. End Date: 91£/18 program for aluminum-based NAMs. NRR will use the RES findings and recommendations to Status Update: In progress inform the development of generic and plant specific 1.2 TLR on degradation RES : E. Focht Start Date: 11/15 regulatory decisions regarding SFP neutron absorbing mechanisms for aluminum- NRR: M . Yoder Proj. End Date: ~ 7/ 18 materials degradation. based NAMs Status Update: SRNL is conducting confirmatory research on the performance of Boral under normal and off-normal SFP service conditions and will prepare a TLR based on the research. TLR on degradation RES: E. Focht Start Date: 11/15 2 2.1 mechanisms for aluminum- NRR: M. Yoder Proj. End Date: ~7/18 based NAMs during and after the following design-basis events: loss of pool NRR will use the RES findings and recommendations to chemistry control, loss of inform the development of generic and plant specific pool cooling, and seismic regulatory decisions regarding SFP neutron absorbing event. This TLR is combined materials degradation. with Deliverable 1.2. Status Update: SRNL is conducting confirmatory research on the performance of Boral under normal and off-normal SFP service conditions and will prepare a TLR based on the research. Internal memo on CNWRA RES : E. Focht Start Date: completed NRR will use the RES findings to disposition technical 3 3.1 reports NRR/DSS: K. Wood Proi. End Date: 4/1 7 issues evaluated in CNWRA reports on NAM performance Staius Update: Completed during SFP accidents Maintain NAM databases RES: E. Focht Start Date: as needed NRR will use the databases to support regulatory decisions 4 4.1 NRR: M. Yoder Proi. End Date: as needed regarding SFP neutron absorbing materials (e.g. license Status Update: Performed on as needed basis. The databases are currently being amendments, FSAR updates). updated based on the information submitted by licensees in response to the NAM Generic Letter 2

UNR NRR-2014-010 /Sumo Cloaaina Chemical Reactions - GSI 191 Closures\ Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number Deterministic GSl-191 RES: M. Hiser Start Date: 7/14 Support provided through this user need will assist NRR's 1 1.1 Resolution NRR: P. Klein Proi. End Date 12/16 review of generic and plant specific chemical effects Status Update: Completed evaluations for both PWRs and BWRs . This support will alsa assist NRR in developing guidance documents for 2 2.1 Risk Informed GSl-191 RES: M. Hiser Start Date: 7/ 14 performing risk-informed chemical effects evaluations Resolution NRR: P. Klein Proi. End Date 12/16 Status Update: Completed 3 3 .1 Generic PWROG Test RES: M. Hiser Start Date: 7/14 F'rooram Evaluations NRR: F'. Klein F'roi. End Date 12/16 Status Update: Completed BWROG Chemical Effects RES: M. Hiser Start Date: 7/14 4 4 .1 Evaluation NRR: P. Klein Proi. End Date 12/18 Status Update: Holding the contract with EMS open in case some unanticipated work comes in before the contract expires UNR NRR-2017-010 IPWSCCl Task 1 Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number 1.1 .1 NUREG/CRs for Crack RES: M. Audrain Start Date: 9/14 Grow1h Rate Curve NRR: J . Collins Proj. End Date: 811 9 Validation Supports the review and validation of CGR curves 1.1 developed by the industry Status Update: In progress. Several NUREGs have been completed. Scheduled to have 2 additional from PNNL and 1 additional from ANL. TLR on Alloy 600/182 (15% RES: E. Focht Start Date: 9/14 1.2.1 cold worked) NRR: J . Collins Proi. End Date: 5/18 Status Update: Phase 1 of A600 testing is completed and will be reported in the TLR. A 182 testina on 15% cold work continues with 6 of the 36 total soecimens still under test. TLR on Alloy 182 (applied RES: E. Focht Start Date: 9/14 1.2.2 stress effects, 15% cold NRR: J . Collins Proj. End Date: 6/20 work) Status Update: Testing on A 182 to investigate applied stress effects began in 11 /17 and will continue. Support xLPR use, mitigation evaluation, and probabilistic 1.2 1.2.3 TLR on Alloy 690/52/1 52 I RES : E. Focht I Start Date: 9/14 flaw evaluation. NRR: J . Collins Proi. End Date: 8121 Status Update: Testing on Alloy 690/52/152 began in 1/16 and continue with no PWSCC crack initiations. 1.2.4 TLR on Alloy 690/52/152 1 RES : E. Focht HAZ/dilution zones and NRR: J. Collins I Start Date: TBD Proj. End Date: 12/21 defects Status Update: This work has not begun, yet, due to materials and testing facility availabilitv. 3

UNR NRR-2017-006 fSLRl Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number Hold focused NRG/industry RES: Carol Moyer Start Date: -FY19 Pave the path forward for resolution of challenges and 1 1.1 workshop on specified NRR: Bennett Brady Proj. End Date - FY20 issues related to materials degradation during the SLR degradation issue(s) and period by ho lding NRG/industry wor1<shop(s) to address prepare NUREG/CP and evaluate aging degradation issues identified in the Status Update: in planninq sta ~es SRM on SECY 14-0016 and in the GALL-SLR report Hold focused NRG/industry RES : Carol Moyer Start Date: - FY20 (NUREG-2191) 1.2 workshop on specified NRR: Bennett Brady Proj. End Date - FY21 degradation issue(s) and prepare NUREG/CP Status Uodate: in lono-term olannino staoes Develop an information RES: Matt Hiser Start Date: - FY18 By developing and implementing a long-term strategy for 2 2.A. tool/database NRR: Bennett Bradv Proi. End Date - FY18 obtaining information on materials degradation from Co mmented [MC1]: Matt: Is this still a good date? Status Update: underway - (lriontization criteria have been develo(led and exercised for decommissioned nuclear power plants (NPPs), as well as Will we have a deliverable by Sept.? metals comtxments . Next steo is to exoand to electrical and concrete. from ex-plant components harvested from operating plants, Develop a process to RES: Matt Hiser Start Date: - FY18 this task will provide fundamental insights on reactor 2.8 evaluate plant comoonents NRR: Bennett Brady Proi. End Date - FY18 materials degradation and information addressing Status Update : underway potential technical issues or identified gaps to s upport 2C Evaluate the suitability of RES : Matt Hiser Start Date: - FY18 anticipated future NRC needs. It will also inform the Diani comoonents NRR: Bennett Bradv Proi. End Date - FY19 value of existing databases based on simulated aging Status Uodate : in olannina staaes, based on results from 28 conditions by assessing their applical:>ility ta in-service Continue to evaluate plant RES: Matt Hiser Start Date: - FY20 conditions. 2.D. comoonents NRR: Bennett Bradv Proi. End Date - FY21 Status Update: underway, based on results from 28 Pursue partnerships for RES: Matt Hiser Start Date: - FY18 2.E cost-sharina NRR: Bennett Bradv Proi. End Date - FY21 Status Update: underway Participate as POC in RES: Carol Moyer Start Date: - FY18 Develop agreements w ith domestic and international 3 3.1 relevant outreach (EPRI, NRR: Bennett Brady Proj. End Date - FY21 partners to collaborate on aging management research DOE IAEA) ~hat results in informatio n to help inform agency Co mmented [MC2]: Amy: Status Update: underway decisions regarding SLR applications. RES should While this term is clear, do you think this would be the Participate as POC in RES: Amy Hull Start Date: - FY18 evaluate p roducts and reports from these orga nizations time to switch to "materials degradation research" or 3.2 relevant outreach (IFRAM , NRR: Bennett Brady Proj. End Date- FY21 that may be provided to NRG in support of generic or "long-term materials degradation research"? IAEA) plant-specific issues. Continue to develop domestic and Status Update: underway international partnerships to share expertise, capabilities, and resources related to aaina manaaement research TLR: "CY17: Status of RES : Amy Hull Start Date: - FY18 Develop documentation evaluating significant technical 4 4 .1 Research for the Significant NRR: Bennett Brady Proj. End Date - FY18 issues germane to the review of SLR applications. Support Technical Issues for SLR" NRR in keeping the Commission informed on the Status Update: underway progress in resolving the four significant technical issues TLR: "CY1 8: Status of RES : Amy Hull Start Date: - FY19 related to SLR . The SRM also directed the staff to keep 4 .2 Research for the Significant NRR: Bennett Brady Proj. End Date - FY19 the Commission informed regarding the staffs readiness Technical Issues for SLR" for accepting an application and any further need for Status Update: in Iona-term olannina staaes regulatory process changes, rulemaking, or research. 4

UNR NRR-2017-006 (SLR) Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number TLR: "CY19: Status of RES : Amy Hull Start Date: - FY20 4.3 Research for the Significant NRR: Bennett Brady Proj. End Date - FY20 Technical Issues for SLR" Status Update: in long-term planning stages TLR: "CY20: Status of RES : Amy Hull Start Date: - FY21 4.4 Research for the Significant NRR: Bennett Brady Proj. End Date - FY21 Technical Issues for SLR" Status Uodate: in Iona-term olannina staaes 4.5 TLR: "CY21: Status of RES : Amy Hull Start Date: - FY22 Research for the Significant NRR: Bennett Brady Proj. End Date - FY22 Technical Issues for SLR" Status Uodate: in Iona-term olannina staaes Provide technical assistance RES : Amy Hull Start Date: as needed Provide independent confirmatory analyses and expert 5 5.1 for reviewing SLR NRR: Bennett Brady Proj. End Date: as needed technical assistance with the review of anticipated SLR aoplications applications with potentially significant issues, such as Status Uodate: Performed on as needed basis. those needing plant-specific gap analyses UNR NRR-2014-001 ISLR Ex1 ert Assistancel Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number Identification of key RES : Amy Hull Start Date: - FY14 Contribute to SLR guidance documents to ensure NRC's 1 1.1

• 1.3 sianificant technical issues NRR: Bennett Bradv Proi. End Date FY18 readiness to review possible license renewal applications Status Update: Completed. (LRAs) for NPPs to operate beyond the first renewal period, beyond 60 years.

The SLR guidance documents NUREGs 2191 and 2192 were published 4 th Q , FY17. The suooorting documents NU RE Gs 2221 and 2222 were published 2"" Q, FY18. Revision of RG 1.188 RES : Amy Hull Start Date: - FY18 Last revised in 2005, RG 1.188 provides guidance on 1.4 NRR: Bennett Bradv Proi. End Date - FY19 information to be submitted in LRAs. Status Uodate: onaoina Provide ongoing subject RES:Amy Hull Start Date:-FY14 Until the publication of NUREGs 2191, 2192, 2221 , and 2 2.1 - 2.2 matter exoerts ISMEs\ NRR: Bennett Bradv Proi. End Date-FY19 2222, RES provided NRR access to SMEs for the Status Uodate: onaoina until the revision of RG 1.188 is comoleted. development of SLRGD content. 5

UNR NRR-2017-001 (IADI Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number 1 1.1 NUREG report on void RES: Appajosula S. Rao Start Date: NRR will use the RES assessment to inform the swellinQ NRR: Mark Yoo Proi. End Date: 9/2018 development of generic and plant-specific regulatory Status Update: ZIRP IASCC crack growth rate (CGR) testing is complete. IASCC CGR decisions regarding the adequacy of aging management of testing of additional materials at ANL is underway. void swelling. RES investigates the causes and mechanisms for void swelling of austenitic stainless steel PWR internals. The RES assessment will address the causes, mechanisms, and oossible extent for olant conditions that cover an ooeratino oeriod of 80 vears. 2 2 .1 Periodic Update Meetings RES: Matt Hiser Start Date: Quarterly NRR will use these periodic update meetings to be Apf)a~ Proj. End Date informed of new information gained from RES's continuing NRR: Mark Yoo interactions with the industry Status Update: Ongoing. RES actively monitors and collaborates with the industry on research projects that are being pursued by the industry and are associated with the aging effects and mechanisms that come from Iona-term ooeration. 2.2 Draft report on industry IAD RES : Matt Hiser Start Date: NRR will use this assessment to better understand and activities l>.J,pajesYla S. Rae Proj. End Date 12/2018 inform the generic and plant-specific regulatory decisions NRR: Mark Yoo regarding the aging effects and mechanisms that come Status Update: Beginning develoQment with information gathering from recent technical from long-term operation. conferences indus!!Jl research 11ublications and dialogue to indust01 research countemarts. '"' 2 .3 Formal report on industry RES: Appajosula S . Rao Start Date: IAD activities (e.g., NUREG, NRR: Mark Yoo Proj. End Date 612019 NUREG/CR} Status Update: Wil start after Task 2,2 is completed. The formal report will include a comprehensive assessment of the results from research P<Oiects that have been completed by the industry. 3 3.1 TLR on assessment of RES: Appajosula S. Rao Start Date: January 2017 NRR will use the RES assessment to inform the generic ASME code case for EPRI NRR: Mark Yoo Proj. End Date 612018 and plant-specific regulatory decisions regarding EPRl's CGR disoosition curves new IASCC crack growth rate curves and to support the Status Update: Ongoing technical SUQl.!Qrt be1!!9 Qrovided b:,: RES to review the basis of NRC participation in the ASME Code group that will the new irradiation-assisted stress corrosion cracking crack (IASCC) growth rates curves consider this code case. develo1;1ed b:,: EPRI. E>rall TLR documenting technical basis for staff 1.12s,tion can be develo ~ if desired bl( NRRis iA plaAAIA!J stage. To date RES su1;1Qort has focused on interactions with industJY through ASME Code. NRC wtll-voteQ negative on ASME IASCC Case (02§/2018). This decision was approved by the NRC Standards Steering Committee. RiaS le ,e.,ieu, It.a basis ef Ille Rau, i,,adiatieA assisted st,ess Ge,.esieA GFaGkiA!J GFaGk

                ~-~~ ~ ~ & - l h e -

dispesibeA SYP*es iAIB IRe AS14!e Ge.:le; he,.,e,.e,, Ille NRG has ABI app,e,.es lllese GYfV8&. 6

UNR NRR-2017-001 IIAD) Deliverables Status Task Deliverable Deliverable POC Schedule Regulatory Use Number 3.2 Technical Support RES : Appajosula S. Rao Start Date: As needed NRR will use RES technical support to inform the generic NRR: Mark Yoo Proi. End Date and plant-specific regulatory decisions regarding aging Status Update: Ongoing activity - limited SUl:!l:!Qrt l:!TOvided to \jat~ ~va,lable as need~ management of baffle bolts in PWRs. by NRR staff. RES to provide technical support to NRR's review of industry actions that are in response to recent ooeratina exoerience involvina sianificant dearadation of baffle bolts at PWRs. 7

Note to requester: Portions of t his record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Shaffer, Sarah Sent: Tue, 11 Oct 2016 08:27:03 -0400 To: Frankl, Istvan Cc: Purtscher, Patrick;Rossi, Matthew;Hiser, Matthew;Berrios, llka;Brezovec, Michael Subject : RE: Request #1 for Transfer of CMB Funds in FYl 7 Ql Steve: The first three have been completed. I only see one APP for CMB, There is no APP for Amy H ull. Did you mean the one below? Testing of Irradiated Ex-Plant M aterials in LWR Environment (including Void APP RES-0006 Appajosula Rao Swelling Investigations of Austenitic SS) From: Frankl, Istvan Sent: Thursday, October 06, 2016 2:24 PM To: Shaffer, Sarah <Sarah.Shaffer@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rossi, Matthew <Matthew.Rossi@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov>; Brezovec, M ichael <Michael.Brezovec@nrc.gov>

Subject:

RE: Request #1 for Transfer of CMB Funds in FYl 7 Ql Importance: High Thanks, Sarah. (b )(5) Steve From: Shaffer, Sarah Sent: Thursday, October 06, 2016 2:05 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rossi, Matthew <Matthew.Rossi@nrc.gov>; Hiser,

Matthew <Matthew.Hiser@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov>; Brezovec, M ichael <Michael.Brezovec@nrc.gov>

Subject:

RE: Request #1 for Transfer of CMB Funds in FYl 7 Ql Steve: (b)(5)

Thanks, Sarah From: Frankl, Istvan Sent: Thursday, October 06, 2016 1:58 PM To: Shaffer, Sarah <Sarah.Shaffer@nrc.gov>

Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rossi, Matthew <Matthew.Rossi@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov>; Brezovec, M ichael <Michael.Brezovec@nrc.gov>

Subject:

RE: Request #1 for Transfer of CMB Funds in FYl 7 Ql Importance: High

Sarah, (b)(5)

Thanks, Steve From: Shaffer, Sarah Sent: Wednesday, October 05, 2016 1:00 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rossi, Matthew <Matthew.Rossi@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov>; Brezovec, M ichael <Michael.Brezovec@nrc.gov>

Subject:

RE: Request #1 for Transfer of CMB Funds in FYl 7 Ql Steve:

Sarah From: Frankl, Istvan Sent: Wednesday, October 05, 2016 10:24 AM To: Shaffer, Sarah <Sarah .Shaffer@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rossi, Matthew <Matthew.Rossi@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

Request #1 for Transfer of CMB Funds in FYl 7 Ql Importance: High Sarah , As discussed please execute the following Q1 transfers Matt H. and PaUMatt R. will review/update respective spending plans in BFS ASAP to support the associated Q1 funding actions. Thanks , Steve

Note to requester: Portions of this record are redacted under FOIA Exemption 85, Deliberative Process Privilege. From: Hiser, Matthew Sent: Thu, 14 Apr 2016 11:47:31 +0000 To: Frankl, Istvan

Subject:

RE: RES-16-0295 Hi Steve, OK, let's discuss next week. 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: 301-415-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Frankl, Istvan Sent: W ednesday, April 13, 2016 10:12 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Subject:

RE: RES-16-0295

Matt, Thanks, Steve From: Hiser, Matthew Sent: Wednesday, April 13, 2016 8:14 AM To: Frankl, Istvan <lstvan.Frank l@nrc.gov>

Subject:

RES-16-0295 Hi Steve,

(b)(5) I had discussed with you on Friday about RES-16-0295, which is for a $20K incremental funding of the harvesting project at PNNL. However, there is only~emaining to the ceiling on this contract, so Sarah recommended just going ahead and funding th is the ceiling (c:::=Jinsteadof jb)(5) $20K). That makes sense to me and now that we have our fu ll budget, we should have the * * ****** necessary funds. If that's OK with you , I will resubmit the REQ for [=:J (b)(5}_ Thanks! Matt Matthew Hiser Materials Engineer US uclear Regulatory Commission I Office of uclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30/-4/5-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov

Note to requester: Both attachments are immediatelly following this email. A portion of the first attachment is redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hiser, Matthew Sent: Tue, 20 Sep 2016 21:10:49 +0000 To: Iyengar, Raj Cc: Pu rtscher, Patrick; Frankl, Istvan

Subject:

RE: Resources and Schedule for Task 2 Attachments: DLR-UNR-Resources.xlsx, 2016 NRR UNR - SLR Draft Enclosure-Bennett-CMBdocx - hiser - Bennett RMl .. .. docx Hi Raj, My input on schedule/resources is attached . I am also cc'ing Pat and Steve for their awareness/input. Thanks! Matt From: Iyengar, Raj Sent: Monday, September 19, 2016 4:21 PM To: Hiser, Matthew <Matthew.H iser@nrc.gov>

Subject:

Resources and Schedule for Task 2

Matt, Attached are the resources document and revised UNR.

Please let me know if you can give me estimates for strategic harvesting task. Raj

Schedule and Resources for the Various Tasks Task Number Task Description Completion Date FTE I Contract$ Hold NRC/industry workshop(s) and (b)(5) 1 prepare TLRs on four SRM topics 1a Hold workshops (2018 , 2020) FY20 1b Prepare TLRs RPV Embrittlement FY17 Vessel Internals FY17 Concrete Degradation FY18 Cables mid-FY19 Develop/Implement a strategy for 2 harvesting materials/components from decommissioned plants 2A FY17 2B FY17 2C FY18 20 Ongoing Develop Domestic and International 3 Partnerships FY17-FY21

User Need Evaluate the Aging Management of Systems, Structures, and Components for Subsequent License Renewal

Background:

The NRC staff {staff) has recently completed the draft guidance documents for subsequent license renewal (SLR), the draft SLR guidance docurRenls which were issued for public comment in December 2015~ The-fdraft NUREG-2191. Volumes 1 and 2. "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) RepG!=tReport:," (NUREG 2191 , \lolurRes 1 and 2) and draft NUREG-2192. "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants" (SRP-SLR) (~IUREG 2-4-92j}. These guidance documents were developed in a multi-year and multi-step process.as dessrieed eelow.NRG ex13erts in the aging degradation of various stn;clures, syslerRs and comrionents 13artici13aled in over ninety ellpert rianels to reyiew 0'Ier 800 corRmenls lhal were ~ e r a l i o n in d e ¥ ~ guidance for 013eration from 60 lo 80 years. Staff from the---GffiGe-Of Nuclear Regulatory Research (RES) were memeers of most of these el113ert rianels, as well as staff meR'leeFS frofR-el~RR-eillisions. The e x ~ ~ 0 R e d ll:l&s8-GOffiffi0Rl&-aRa-draft.ea-tl:l&-Aew-guidaM8-fOf..SbR In one of the key steps. the NRC completed the Expanded Materials Degradation Assessment {EM DA} iSem&-0f-U-10-80Q..oomm61'\ts-oame-frn~~J)QOOeo-Matooals DegraeatieA Oss0ssm0Rt ~EMO) study ani RES' assistanee in the Aging Management Pn~sram (AP1P) E-ffeeti,,onoos Audits at Ouoo J)lants in t~o ~ Q ef oxtonaee&flo~atioo-. ~n cooperation with the Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) Program. The resu ltant reports, the ~IRC completed NUREG/CR-7153, "Expanded Materials Degradation Assessment (EMDA), Vol. 1-5" (ADAMS Accession Nos. ML14279A321, ML14279A331, ML14279A349, ML14279A430, ML14279A461 ). describe the conclusions from an expert elicitation process to le-identify the most significant aging degradation technical issues for nuclear power reactor operation beyond 60 years. The EMDA ranked the significance, current knowledge, and uncertainty associated with aging-related degradation phenomena that could affect systems, structures, and components (SSCs) over 80 years of operation. As outlined in the staff requirements memorandum (SRM) on SECY 14-0016, the major technical issue areas are:

• Reactor pressure vessel neutron embrittlement at high fluencQi
• Irradiation-assisted stress corrosion cracking of reactor internals and primary system componentSi
• Concrete and containment degradation;-aoo
• Electrical cable qualification and condition assessments In another key step. staff from the Office of Nuclear Reactor Regulation (NRR) and the Office of Nuclear Regulatory Research (RES .l_alse-assistee-in-conducted three audits to investigate the 1

effectiveness of aging management programs (AMPs) used in the plant operating period from 40 to 60 years. The find ings from the first two audits are documented in the report titled, "Summary of Aging Management Program Effectiveness Aud its to Inform Subsequent License Renewal: R.E. Ginna Nuclear Power Plant and Nine Mile Point Nuclear Station, Unit 1" (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). In addition on June 15, 2016, the staff issued the Technical Letter Report, "Review of Aging Management Programs: Compendium of Insight from License Renewal Applications and from AMP Efffectivensess Audits Conducted to Inform Subsequent License Renewal Guidance Documents," (ADAMS Accession No. ML16167A076), which provides the staff's observations from reviewing license renewal applications and the AMP audits. As part of the exf)ert panels. ReS e>Jaluateeln addition, an assessment of domestic and international operating experience of nuclear plants, lessons learned from staff review of previous license renewal applications, and .fill_assessment of recent research findings; were considered in the development of the SLR guidance documents. The draft guidance documents were developed by NRCthe staff w ith experience in addressing aging degradation of systemc, strust1:1resstructures .. systems and components. The staff-woo participated in over ninety "expert panels." , These 93Ael6which included staff members from the NRR Division of License Renewal and other NRR divisions, as well as staff from the Gffioo of Nuclear Regulatory Resear.ch (RES). The expert panels dispositioned more than 800 inputs, which Sorno of the 8QQ sornrnents-came from the Rea-Expaneee Materials Oegraeatiefl A6&966fA&l'lt-fEMDA) study~-aAd-R~ssistance-in-the AgiRg-Managemerit Prograrn-{AM P1 geffectiveness 2 Audits at three f)lants in the f)erioEl of extondod Of)eration. and frorn the review of operating experience and other information. SiAGe-After the draft guidance documents were issued for public comment, the staff l:la&-held several public meetings with stakeholders and the public to discuss the proposed revisions and bases for the revisions. J.n.!Tl:le-roost-raGenkllaetings-wera-1:\elEl-on-JaAu~Fy 1Q, 2Q16. I the~rf)osos of those meeling2 the staff wero 01:1treach acti¥itios to-stak~ ~lleliG-IG-provide_g information and clarifications on the proposed changes to the guidance documents, and lo--soliGilsolicited feedback on the documents, and roviso tho doc1a1rnents, as af)f)FOf)riale, to re~ect slakeholeer ane puelic feedeack. The fin a I guieance doc1a1rnents are expected to eo iss1:1ed in mid 2Q17. The NRC staff is currently evaluating the public comments and developing fina l versions of the guidance documents. These documents will be issued in final form in mid-2017. To support their Sl:IWQrt the reYiew of an-SLR application, an-applicant2 will-need to 2

demonstrate that J:law--the effects of aging will be adequately managed for an operating period from 60 to 80 years, including aging effects tRes&-associated with the technical issues listed above. Although the industry is conducting resea rch to address these major technical issues for SLR, not all of the research will be completed before the first application is submitted. [For those issues that the industry has not yet developed a generic technical basis to support its resolution and the staff has not provided generic guidance for aging management, tl=le-NRG will reE11:1est applicants will need to address the technical issues with plant-specific programs in their SLR applications. The staff will review these plant-specific programs--tl'la+-aaGFeS&-Ule-Sl:-R-t&GAAiaal Comme nted [HA 1): Not true in all cases, since GALL- ~ . but anticipates a longer application review process in these cases. SLR has identified generiuc approaches to address some of the issues. The requested research desGJ"ioed-below-would-provide2 information to support the staff in effectively evaluating AMPs and developing staff positions on the technical issues identified in EMDA reports and in the subsequent license renewal guidance.'-This effort will also augment the staffs preparedness for the evaluation of future applications for an SLR period. These requested products should build upon analysis methods, tools, and expertise de,veloped as part of ongoing research activities and new research activities focused specifically on aging effects during an SLR period. Description of Scope and Tasks 1A.- _ Hold NRC/industry workshop(s) on status of domestic and international research activities and operating experience address and evaluate the status of materials degradation issues identified in the EMDA reports, with particular focus on the issues identified in the GALL-SLR and in the SRM on SECY 14-0016_for SLR. Comme nted [BB-2): To be of use to NRR, the workshops should focus on the issues identified in the TeshAisal Need: In February 2008, the NRC and DOE fi rst co-sponsored a "Workshop on GALL-SLR and in SRM on SECY 14-0016 U.S. Nuclear Power Plant Life Extens1ion Research and Development" (ADAMS Accession Number ML080570419), which requested stakeholder input into aging management The EMDA would have been more useful for subsequent license renewal had it been more in line research areas for "Life Beyond 60." ;S ince then, there have been multiple domestic and with GALL components and issues. international workshops/meetings on the research activities and operating experience that may impact aging management of SSCs for an SLR period. with the next such meeting to be sponsored by the International Atomic Energy Agency (IAEA) in France in the October CMB: Revised, Please change as you see fit. 2017. Comme nted [BB-3]: I thought RES was a sponsor for three large international meetings, I attended the third These meetings have been helpful in facilitating technical discussions, disseminating one that was held by IAEA in Salt Lake City. But I knowledge and information, enabling the understanding of technical challenges, and paving thought RES was a sponsor. 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 subsequent license CMB: I do not have the details. Hence not

                                                                                                     ~ ptured. We can add this information, if needed.

renewal applications (SLRAs), 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 major technical issues outlined in the GALL-SLR, the SRM and in EMDA. Request: RES is requested to facilitate a minimum of two international activities (either a workshop. conference. symposium. or meeting) in the early fall 2018 and in late spring 2020 to address: 3

• operating experience from the 1initial license renewal period (or the long term operation period for international plants) the state of knowledge on the relevant technical issues

                                                                                                    =.

Commented IHA4): I am skeptical of this task. We to identify more specific deliverables _ Commented [BB-SJ: I think this is an activity we should

• on- oin research on materials de radation issues and a in mana ement of these support but I am not sure how this would be received in issues. in particular as related to the SLR period the current NRC climate of frugality.

CMB: This was speclflcally requested by Allen These activities sh * **

• oward the resolution of Hiser and agreed upon (in a broad sense) in our t hnic I i sue for the SLR erio . meetings with DLR during the course of Deliverable: ~aff..soould-.facilitato several workshapslmeetiAg&--Oll-OIJ&ffilmg development of this UNR.

Commented [HA6]: I am skeptical of this task. We

                                                                                                    ~ to identify more specific deliverables Commented [BB-7): I think this is an activity we should experience from tho initial license renewal period, research resu lts on materials support but I am not sure how this would be received in degradation issues, and aging management of SSCs during tho SLR period.                the current NRC climate of frugality.

Those meetings sheuld be specifically targeted teward the resolution of technical issues for CMB: This was s peclflcally requested by Allen effective aging management of SSCs during the SLR period!. The deliverables include the Hiser and agreed upon (in a broad sense) in our meetings with DLR during the course of international activities (either a workshop, conference. symposium. or meeting) and development of this UNR. technical letter reports that summarize the state-of-knowledge and resolution of the four major issues identified in the SRM on SECY 14-0016 for SLR" Prior to the meetings. RES should provide a draft agenda and proposed presenters. The Commented [BB-8): We need very explicit deliverables such as an agenda coordinated with NRR, proposed information from these activities should be documented in a NUREG/CP report. if speakers, presentation slides, and a report that addresses aging management programs that may lead appropriate. or by other sufficient means. including. at a minimum. a summary of the activity to revision of our guidance documents with all relevant contributions (e.g., presentations or papers) available for subsequent

   !!.§.ruRES staff should pFOvido an annual technical letter report summarizing the                CMB: Totally agree. During the process of understanding gained through the worl-;shops/meelings. The summary should include the           developing the workshops, we will work closely with DLR to ensure agenda, schedule, speakers are status of domestic and international research activities in adElressing materials ElegraElation agreed upon by all of us. We will mention the issues anEl aging management practices luring the SLR perioEl. The report shoulEl also         close collaboration and alignment with DLR in our d issuss (1) areas of progress anEl issues resolution, (2) areas of insuffisient f;)rogress that response to the UNR. The draft Internal report will may warrant aElElitional ~JRC Elri11on interactions, anEl (J) any newly iElenlifieEl technical  be sent to NRR for review and comment. If NRR
   -issl:les-lRat should be sensieeFOEh                                                             wants to make the final report public, that will be fine. As mentioned before, all milestones will be tracked.

Commented [BB-9J: The previous UNR for SLR also Schedule: The effort should u ntil the completion of the deliverables from the had a task to hold public workshops on aging second activity. tentatively scheduled for late spring 2020.last no more than J6 months from management research with a deliverable after each the period of inception of this user need re11uest. meeting to provide a technical letter report after each meeting. To my knowledge, all we got was a two-page memo from Gene Carpenter. CMB: We will make sure these deliverables, with i a. jPro>Jide R6S staff assessments of the c urrent knowledge a nd Elisposition of due dates, are specifically stated in our response. materials degradation issues identified in the EMDJ\. reports, *.vith particular focus on As soon as the UNR (and the RES response) Is put the issues identified In the GJ\.LL SLR and in SRM on S6CY 14 0016 f or SLR~ In place, CMB will add milestones In our Op Plan to tract the deliverables. DLR will have access and can view the updates on the RES OpPlan. Technical Need: As mentioned earlier, the eMOA reports identified significant test=misal issues fer nuslear !)ewer reastor Ol)eratiens beyena 60 years relates to materials Commented IHA10J: I suggest deleting this. degradation. Those issues fall under the following lour tol)ical areas, as outllinea in the SRM on SECY 14 0016: Commented [BB-11]: Again, it would be more useful to NRR if the assessment of issues focused on the issues o-RoaGIGr-f)F&SSUro-vossol-noutiOA-OmbFittlomonl-al-l=ligl+-f1uenCOr in the GALL-SLR and in the SRM to SECY 14-0016 CMB: Added the emphasis on SRM. 4

• lrraeiation assistoe stress Gorrosion GraGking or roaGtor internals ane i:irimary system SOmJ;!Ononts; GonGroto ane Gontainmont eograeation; ane
• EloGtriGal Gaelo E11cJaliriGation ane Goneition assessment.

The ~JRC, DOE, anEI inEli;stry are aEleroscing tho l<oy toohnioal issi;os related to materials dO§radation at nUGleaf-f)OWOfi)lant&-fNPPs). In or<Jef-l&-9affi-belteHJAGef6taAGing--ef..tl:le

    -mat0fials-a§in~Faeati0fl-ffi06Aani6ffi6-aflEl-tl:leif-imJ;1lisaliens-ekt-ruett1FaH1ne GOmf)OA6At-integrit-y,-DOE-and-the-irldlclStr,,-havHniliated-mimerOOG-l'osear-Gl:l-actwitios-en tl:lo-few= - -major toohniGal areas. Th~oo16-oonfimlatory resoaFGh, threi;!Jl:I
   ,several i;sor nooe-ffi<1t10Sls-9R4.p6Gific toohnioal is&ue&;--le-ffiGef)6RGeAlly ve rify liGonsoe data, eotermino safety margins, ane 0XJ:!loro i;noortaintios. In aeeition, tho NRG research will SlcJJ;lJ;lOrl ane inGroaso tho offisionsy of staff ro 11iow of SLR aJ:!J:!lisatiens. Te fi;lly si;ppert tho staff's review of tho SLR appliGations, RES shoi;IEI Elovolep staff assessments er tho si;rront knewloego ane eispositien of materials eograeation issi;os rolatoe to tho foi;r major tool=mioal areas. Tho assessments shoi;le also inoli;Elo rooommonElations on tho nooe for:

Commented (B11-12] : the assessment of issues

• ~ ow rogi;latory gi;ieanGo anelor .f&lision or existing rogi;latory gi;ieos (RGs) to aeeross focused on the issues in the GALL-SLR and in the i;nGertainties in knowleego anEllor fJOlontial non GOnsorvati*,ism. SRM to SECY 14-0016

~ e l o l: Dolivor a tGGl:lniGal-letter-f0f>erl that si;mmarizos tho Gi;rront-kRewjee§e-and CMB: Added the emphasis on SRM. dispositioo-ef..mat&ials-degradatioo-isSYes-ieontif10£l.tn-EMD4,witt\-f)artiGUlaf-foGys-en-tJ-\o I think DLR is very good at identifying ISGs and revisions to our regulatory guidance. Furthermore, issi;os iElonlifioEI in tho GALL SLR ane in SRM on SECY 14 001e for SLR. Tho F0J;!Ort ISGs may discont inued. sl:IGYIEl-al&e-inGludo rosommonealieA&-on tho nooe for any now GF-r&VisoEl-g1,1HdaAGO-IG aEleross component integrity or aging strnoti;ros. SohoEli;lo: Tho effort shoi;IEI last no more than 3e months from tho porioEI or inception CMB: Reference to ISG deleted. Commented (B11-13]: Need more specifics on what NRR is getting. Is this an annual report? of this i;sor nooe roEji;ost. Tho initial eraft report shoi;le eo somplotoEI ey tho one of f Y CMB: This will be a f inal report {after incorporating ~ 1 NRR comments on the draft report). During the process of developing the report, RES will work G.- .Develop and implement a long-term strategy for obtaining information on with NRR closely, with frequent updates and materials degradation from decommissioned NPPs, as well as from ex-plant meetings. components from operating plants. Commented (B11-14]: Or in the GALL-SLR and SRM?

                                                                                                        ~      : See change.

ToGhniGal Need: The NRC performs confirmatory research to inform and develop the Commented (B11-1 SJ: Why so long? technical basis for regulatory decisions related to aging management programs for CMB: The final report will capture the insights and _SLR. Historically, this research has included testing virgin materials under simulated aging information gathered from the current research activities (conducted by DOE, EPRI, Industry, and conditions, as well as testing a nd characterization of ex-plant materials l"lt!arvested from NRC) on the SRM technical issues. Many of the nuclear power plants. Ex-plant materials are valuable because they have been exposed to activities (cables, internals, selected concrete actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike activities, RPV) are expected to produce results v irgin materials tested under simulated conditions in the lab. Testing ex-plant materials also over the course of the next two years. We reduces the uncertainty associated with tho applicability of the aging conditio ns. The refo re, understand that some of the activities may not be completed (some concrete activities, hlgh-fluence this effort is expected to provide fundamental insights on reactor materials degradation and testing of vessel internals etc.) In two years. For information addressing potential these, we will provide a status update and recommendations, If necessary, for any additional _technical issues or identified gaps to support anticipated future NRC needs. It w ill also research that industry or DOE (or NRC) may want to consider. 5

_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, s uch as Zion, Crystal River and Zorita (Spain), the efforts of planning, coordination and eventual harvesting of these materials could 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 s ignificant materials aging degradatio111 information from ex-plant components. Such a database will enable the NRG 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 a database which identifies and prioritizes the materials, com ponents, and operating conditions that are needed to address the four topical areas 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. Deliverable: RES should provide the database for NRR 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. a&Vel~atabase-ooveFin~F-1~1-afeas ootliRee in the SRM on SECY 14 0016 ana containing infom1ation on: Commented (BB16]: I think this would be a useful product and might reduce research costs by focusing ~ p s for-SbR--tflat-may b&best-addfe6Sed by-hafVe&ting dtKHo-4\allenge&-in only on the material for which research is needed. sim1,1laling asl1,1al ser\lise senailiens, ana Also, as we learned from the concrete samples from Zorita there is a timing issue in that you have to be

• materials that can be harvestea fram le be aecemmissienea MPPs ana eK 13lant ready to be specific what Is needed and in a relatively eom13enen1s from 013orating 13lants to bolter inform tho ~lRC's aging management 13rograms specified by the provider.

{AMP6)-ana-aging-F&lated-fogulatOfY-OV8f6ight a R O - - t ~ v i l i e & . j CMB: This is our position, as well. Commented (HA17]: Suggest that we add confirming current approaches 6

Schedule: Item A and 8 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 The effort sholJld last no more than 36 months from the period of inseptienissuance of this user need request. oi..- Continue to Develop Domestic and International Partnerships to Share Expertise, Capabilities and Resources Related! to Aging Management Research for l ong-Term Operations (L TO)

   +esllnisal-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 (EPRI) 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. Request: RES is requested to continue to develop agreements with domesNc and international partners to collaborate on aging management research that results in information to help inform agency decisions regarding SLR operating periods.

  !Deliverable: 1ContinlJe to develop a!jreeFRents with doFRestis and international partners to sollaeorate en aging FRanageFRent resoarsh that reslJlls in inforFRatien ta help inferm agensy decisions regardin!l SLR and long term operations. lnte!jrate as appropriate the resll lts of these sollaeorati¥e research and information exshan!jes freFR international partnerships into Tasks A and B. RES should pProvide to interested NRR branch chiefs (from DE and 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 and future plans should be discussed as a standing agenda item during quarterly meeti1ngs between RESIDE. NRR/DLR and NRR/DE. an--annl!akumma,y--eHRtomatienal-oollaoor-ative

   -Fe&eafGIHes\llts-aM-&tat~teraGtions (8.J., references to FReetin!j FRinlltos-,
   -prasentations,leGJ:lniGal ropor4&,etG,j, lliglllighting intematiOflal-astivities-and FeSUlt-s tllat FRay affect SLRJ                                                                                     Commented [BB-18]: We had a similar task in the previous UNR and a deliverable of an annual summary of international collaborative research but I don't recall getting any reports.

Schedule: These products should be provided to NRR in a timely manner effort should continue until the closure of this user 111eed request. CMB: Again, we will make sure all the deliverables and schedules are specified In our response to the UNR. And we will track the milestones. Commented [HA 19]: We need to be more specific on task and deliverables 7

Portions of the attachment, which is immediately following this email, is redacted under FOIA Exemption 85, From: Iyengar, Raj Deliberative Process Privilege. Sent: Fri, 30 Sep 2016 11:44:16 -0400 To: Frankl, Istvan Cc: Hull, Amy;Hiser, Matthew

Subject:

RE: Revised estimates and UNR Attachments: DLR-UNR-Resources-Sept26.xlsx

Steve, Yes, Matt provided those estimates. I made a slight revision and ran that by Matt.

Matt, Agree? Raj From: Frankl, Istvan Sent: Friday, September 30, 2016 11:35 AM To: Iyengar, Raj <Raj.lyengar@nrc.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: Revised estimates and UNR Thanks, Raj. Did you align with Matt H. on the harvesting scope as well as related FTEs and contract funds? I have no additional technical comments on the draft UNR (It will need to go to QTE but that will be done at NRR.) If Matt H. is OK with the FTEs and $s for the ex-plant harvesting task, I am OK with the rest.

Thanks, Steve From: Iyengar, Raj Sent: Thursday, September 29, 2016 2:05 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

FW: Revised estimates and UNR

Steve,

You may review the resource estimates. Amy mentioned that DLR did not want to see the TIO task in the new UNR. I have also made a minor change in the deliverables for Task 1. Raj From: Hull, Amy Sent: Thursday, September 29, 2016 1:47 PM To: Iyengar, Raj <Raj .lyengar@nrc.gov> Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Revised est imates and UNR Yes, as far as I am concerned. From: Iyengar, Raj Sent: Thursday, September 29, 2016 1:20 PM To: Hull, Amy <Amy.Hull@nrc.gov> Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Revised estimates and UNR Thanks, Amy. Then, can I send a note to Steve Frankl that he can review the latest estimate (and the minor revision ot the UNR Task 1 deliverable) I sent you all on Monday? From: Hull, Amy Sent: Wednesday, September 28, 2016 3:56 PM To: Iyengar, Raj <Raj .lyengar@nrc.gov> Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE : Revised est imates and UNR As mentioned, I hit wall yesterday. From: Iyengar, Raj Sent: Wednesday, September 28, 2016 2:48 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Revised estimates and UNR Amy/Rob, Steve was inquiring about this. Please let me know if you have changes to the estimates/deliverables/tasks. Thanks so much. Raj

From: Iyengar, Raj Sent: Monday, September 26, 2016 12:07 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert .Tregoning@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

Revised estimates and UNR Amy/Rob , I have added the development of the summary reports to the deliverable for Task 1 (brief addition). I have also revised the resource estimates by rolling the FTE for summary documents with the resources needs for Task 1. If you folks decide to add the new task on TID, please do so in the attached revised UNR. After you make any changes, we can send to those who attended th is AM meeting for comment or awareness. I will leave that to Steve. Raj

Schedule and Resources for the Various Tasks Period of Perfomrance (FY17-20) Task Number Task Description Completion Date FTE Contract$ (b)(5) , I - - !tor-FY18and - - - FY20 Hold NRC/industry workshops (2018, FY20 O year 2020) and prepare NUREG/CP and _ ..,.,. .....~ -** *---~ ***********- o---** 1 summary reports on four SRM topics Total (Task 1) I -- --- - (h)(5) __ I - - - l - (b)(5 1--* ueveIop1ImpIemem a strategy ror 2 harvesting materials/components from decommissioned plants 2A Develop a database FY17 Develop a process to evaluate the 2B --- - - 'lll(;it - components from plants use me process aeveIopea m item ts to FY17 (b)(5) I -* 2C evaluate the suitability of components from plants FY18 Continue to implement the process developed in item B as components (b)(5) Ongoing (FY19- --* become available from additional plants FY20) .- - ---- 20 [3"year Total (Task 2) I - 1- --( b){5)__ I - - J (b.){5)_ _ Develop Domestic and International 3 Partnerships FY17-FY20 Q _y ear (total [J (b)(5) '* .. *- (b)(5)

Note to requester: Both attachments are immediatelly following this email. A portion of the second attachment is redacted under FO IA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Thu, 22 Jun 2017 00:47:55 +0000 To: Hull, Amy;Rao, Appajosula;Hiser, Matthew;Purtscher, Patrick;Kirk, Mark;Sircar, Madhumita;Philip, Jacob;Murdock, Darrell Cc: Frankl, lstvan; lyengar, Raj;Seber, Dogan;Miller, Kenneth A;Koshy, Thomas;Tregoning, Robert;Pires, Jose Bee: Moyer, Carol

Subject:

RE: SLR User Need Request Kickoff Attachments: SLR UNR Response Timeline 20170621.docx, Copy of DLR- UNR-Resources-Sept26.xlsx

Dear SLR Research Team,

As I am sure you have heard by now, Steve Frankl was successful in securing an extension on the RES response to the NRR User Need Request on subsequent license renewal (SLR). While it seems that the new due date of the end of August is a long way off, there really is not much extra time in the schedule, given the complexity of the content and of the concurrence process. A draft timeline for writing the UNR response is in the attached Word file, for your information. Now is the time for the Team members to start entering your proposed response text into the skeleton response memo that Amy has placed in the G-drive folder (G:\DE\CMB\UNR NRR 2017-006). Please try to have your entries completed by June 27th . Also, part of your response to the UNR will need to take into account whether the estimated resources (FTE and $) from NRR are appropriate for the work. Please review the attached table and consider these estimates in your response. Thank you, Carol Carol Moyer Sr. Materials Engineer RESIDEICMB carol.moyer@nrc.gov 301-415-2153 From: Moyer, Carol Sent: Thursday, May 18, 201712:13 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matt hew.Hiser@nrc.gov>; Rao, Appajosula

              <Appajosula.Rao@nrc.gov>; Purtscher, Patrick <Patrick.Purtsch er@nrc.gov>; Sircar, Madhumita
              <Madhumita.Sircar@nrc.gov>; Murdock, Darrell <Darrell.Murdock@nrc.gov>; Koshy, Thomas
              <Thomas.Koshy@nrc.gov>; Kirk, Mark <Mark.Kirk@nrc.gov>; Philip, Jacob <Jacob.Philip@nrc.gov>

Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Iyengar, Raj <Raj .lyengar@nrc.gov>; Seber, Dogan

              <Dogan .Seber@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>; Tregoning, Robert
              <Robert.Tregoning@nrc.gov>; Pires, Jose <Jose.Pires@nrc.gov>

Subject:

RE: SLR User Need Request Kickoff

Dear SLR Research Team,

I just coined this name, and I hope it is all right with all of you. I am not trying to create any new structure or obligations - only to acknowledge that your ongoing research contributes to our collective understanding that supports NRR's subsequent license renewal safety reviews. Second, I neglected to include Mark Kirk and Jake Philip on my previous communications related to NRR-2017-006, the new User Need Request on SLR research. My apologies!! Both RPV integrity and ASR are still included in the confirmatory research for SLR, and they need to be considered in our planning. As you know, Amy Hull is the POC for this User Need with NRR. She and I are working together to develop the RES response. We plan to use, as a starting point, the recently-approved UNR and RES response on irradiation assisted damage (IAD), NRR-2017-001. The response memo can be found here: G:\DE\CMB\UNR NRR 2017-006\1 DLR-related UNRs, responses\lAD response 2017-05 123737 .docx. This provides a good example with respect to length and level of detail. Amy has started a template document for the NRR-2017-006 response, and we are requesting each of the contributing team members to propose edits to this document. The draft response is here: G:\DE\CMB\UNR NRR 2017-006\draft collective SLR UNR response 05 2017.abh.docx. Please use track changes, so I can keep the various contributions and changes straight. Also, if you are proposing to add technical scope to the response - work that is not clearly in NRR's request - please flag that to me right away, so that it can be discussed with our NRR counterparts. The UNR and other related documents may be found in this folder: G:\DE\CMB\UNR NRR 201 7-006 Also, Amy has been updating the SharePoint page on Long Term Operations research, here: http://fusion.nrc.gov/res/team/de/cmb/LTO/default.aspx Thank you, again, Carol From: Moyer, Carol Sent: Tuesday, May 16, 2017 5:40 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, M atthew <M atthew .Hise r@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>; Murdock, Darrell <Darrell.Murdock@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov> Cc: Pires, Jose <Jose.Pires@nrc.gov>

Subject:

SLR User Need Request Kickoff

All, Thank you, again, for participating in today's kickoff meeting for NRR-2017-006 (attached), the recent user need request on research related to subsequent license renewal. RES/DE has been

supporting this work for many years, and this latest request provides a framework for additional related research and documentation of lessons learned. Each of you is doing work related to this request. Again , this UNR is not intended to duplicate ongoing work, and it is hoped that it will not cause confusion in tracking these items, either. As you review the UNR, please consider how you can contribute to any or all of the tasks. I will need input from each of you to compile the response to the UNR. We have been given a due date for the response (to RES/PM DA) of June 12th . If you cannot provide you r input in time to support that target date (due to travel, workload , etc.) - that is, by about June 2nd , please let me know when you will be able to reply. Steve Frankl is willing to request an extension , if needed, but would prefer to do so only once. For each of the four main Tasks in the UNR to which you will contribute, please reply with: A. Description of proposed Subtask B. Recommendation for use of NRC or Contractor staff C. Level of effort (hrs.) , cost($), and rough schedule D. Cross-reference to existing UNRs For example , please note if the proposed work complements or extends work that is tracked under another UNR. If you have any questions on this, please feel free to contact me. Thanks in advance , Carol Carol Moyer Sr. Materials Engineer RESIDE/CMB carol. mover@nrc.gov 301-415-2153

SLR UNR Response Timeline 6/21/2017 Action Start Target Completion Work Lead Comments Date Completion Date days Date (COB) allowed Input from SLR Team 6/21 6/27 5 All members to draft response Review suggested 6/28 6/29 2 Moyer I Hull changes and send draft response to BC: CMB Review & send 6/30 7/5 3 Frankl comments on draft response back to Mover Review draft 6/30 7/7 5 Moyer I Hull response with NRR / Brady PM Make any requested 7/6 7/10 3 Moyer I Hull changes in UNR response and return revised draft to BC:CMB for approval to send to DE BCs for concurrence Second review & 7/11 7/13 3 Frankl concurrence by BC: CMB Email draft response 7/14 7/14 1 Moyer CIB, CMB, with explanatory SGSEB, cover letter to DE ICEEB BCs for review & concurrence BCs review & concur 7/17 7/21 5 DE BCs or return comments to Mover Make any changes in 7/21 7/21 1 Moyer I Hull UNR response and email back to DE BCs for concurrence Second review & 7/24 7/26 3 DE BCs concurrence by BCs Send draft response 7/27 7/27 1 Moyer to DE mgt. for concurrence DE mgt. review & 8/01 8/10 8 Thomas/ Both Moyer concur or return Regan & Hull on comments to Moyer travel Aug 7-9 Brief DE mgt., if 8/02 or 8/02 or 1 Moyer/Hull needed TBD TBD Make any changes in 8/10 8/11 2 Hull/Moyer UNR response and

resubmit to DE mgt. for concurrence Second review and 8/14 8/17 4 Thomas/ Moyer on concurrence by DE Regan travel Aug mqt. 14-17 Send draft response 8/18 8/18 1 Moyer to RES mgt. for concurrence RES mgt. review & 8/21 8/25 5 Weber I concur or return Boland comments to Moyer Brief RES mgt., if 8/22 or 8/22 or 1 Moyer/Hull needed TBD TBD Make any changes in 8/28 8/28 1 Moyer/Hull UNR response and resubmit to RES mgt. for concurrence Second review and 8/28 8/30 3 Weber I concurrence by RES Boland mqt. Transmit response to 8/31 8/31 1 Moyer NRR

Schedule and Resources for the Various Tasks Period of Perfomrance (FY17-20) Task Number Task Description Completion Date FTE (bH5"Contract $ (b)(5) _ I /' I.tor FY 18 and Hold NRC/industry workshops (2018, FY20 [3,y;ar FY20 1 2020) and prepare NUREG/CP and summary reports on four SRM topics _______ - - --- - --__. -l - (b).(-5)__ Total (Task 1)  !(b)(5) I Develop/Implement a strategy for 2 harvesting materials/components from decommissioned plants 2A Develop a database FY17 Develop a process to evaluate the 28 __________ c_o _m _,_p_o_n_e_n_ t s_f_r_o _m_p F_Y_1_7_ _ _ _- - + - - ---1 (b)(5) .,___ _ _ _ _.__l_

                                                  ..._l_a_n_ts_ _ _-+-                                                           -- -_--....-+:._:::-::_:::_:-_----     (b)(5) -

Use the process developed in item B to 2C evaluate the suitability of components from plants FY18 Continue to implement the process developed in item B as components become available from additional plants Ongoing (FY 19-20 FY20) Total (Task 2) 3 Develop Domestic and International Partnerships FY17-FY20 q year (total Q (b)(5) *-. .

Note to requester: Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hiser, Matthew Sent: Thu, 5 Jan 2017 16:23:08 +0000 To: Rao, Appajosula Cc: Frankl, Istvan

Subject:

RE: STAQS Document Notification: For your approval--Requisition: Testi ng of Irradiated Ex-plant Materials in Environment (RES-17-0005) Hi Sri, (b)(5.) Here is the current status in STAQS. The REQ is for with Kathy for approval. CJ (see left column of screenshot) and Summary

                                                 "'3 C     Amendment 000001 Is currently on route pending approval.

Version: view: 000001 Peod,r,g CurrentVe(s,on

• 3 lhe amendment Is currenlly with KATHRYN M. BROCK. CIiek "View route history* below for details.

lhis Ame nd ment: 000001 Whllc would you like co do?

                                                ~

Status: Pending StbQe: Amended RequlSltlon

                                                              &  ~ View r oute hi sto ry l otal Items: 1 (b)(5)
      * *_*~_I Commitment Amount                                   m    View s n.ll)Shot Validate amendment data

_ / View change text Change route Net View of Amendment: 000001 Status: Pending Cancel r ollle Stage: Amended Requisition Switch to a different serslon of this requisition lotal Items: I 000001 Pend,ng

• Commitment A11101111t r,om this requisition t

(b)(5) Cre3te a new document Selecl

                                                       ~IOHomt 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: 301-415-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov Matt: (b)(5) I thought that we are requesting for ._!_ __.lvith this STAQS requisition. I addressed Steve's comments and changes on the evaluation. Please submi1t the form and let me know how much you have added in the requisition. Thank you

Sri

---

Original Message-----

From: Hiser, Matthew Sent: Wednesday, January 04, 2017 12:48 PM To: Rao, Appajosula <Appajosula.Rao@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

FW: STAQS Document Notification: For your approval--Requisition: Testing of Irradiated Ex-plant Materials in Environment (RES-17-0005) Importance: High Hi Sri, Here are Steve's comments/tracked changes on the evaluation. Once you address them, I'll resubmit in STAQS. Thanks! Matt

---

Original Message-----

From: Frankl, Istvan Sent: Wednesday, January 04, 2017 12:24 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: STAQS Document Notification: For your approval--Requisition: Testing of Irradiated Ex-plant Materials in Environment (RES-17-0005) Importance: High Thanks, Matt. I have several comments/corrections for the evaluation. Please see the attachment for details and address them ASAP. Steve

---

Original Message-----

From: Hiser, Matthew Sent: Wednesday, January 04, 2017 10:1 1 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

RE: STAQS Document Notification: For your approval--Requisition: Testing of Irradiated Ex-plant Materials in Environment (RES-17-0005) Hi Steve, Just resubmitted with proposal and evaluation. Wow, didn't realize Kathy was departing so quickly! Thanks! Matt

---

Original Message-----

From: Frankl, Istvan Sent Tuesday, January 03, 2017 3:58 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: STAQS Document Notification: For your approval--Requisition: Testing of Irradiated Ex-plant Materials in Environment (RES-17-0005) Importance: High Matt, Did you assist Sri with this submittal? If not, please reach out to him. As per the Notes section, this action is accepting the ANL proposal and it obligates available (b)(5) f'(l7Q2fundsl * *

• l If this is correct, the forms documenting the evaluation and negotiation (if any) need to be uploaded before I can review/accept this requisition . If possible, please do this ASAP so that Kathryn can also approve it by Friday, Iler last day with DE.

Thanks, Steve

      -----Original Message-----

From: STAQS Notifications NoReply@esc.gov (mailto:STAQS Notifications NoReply@esc.gov) Sent Tuesday, January 03, 2017 1:18 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

(External_Sender] STAQS Document Notification: For your approval--Requisition: Testing of Irradiated Ex-plant Materials in Environment (RES-17-0005) Requisition: RES-17-0005 is ready for your approval in STAQS. Project

Title:

Testing of Irradiated Ex-plant Materials in Environment Amendment: 000001

Description:

"Testing of irradiated ex-plant materials in environment". To conduct crack growth rate and fracture toughness tests in PWR environment and also examine the microstructure of the fractured surface of Zorita reactor internals that were irradiated to high neutron doses.

Owner: MATTHEW A. HISER Requisitioner: APPAJOSULA S. RAO Technical Point of

Contact:

APPAJOSULA S. RAO Buyer: APRIL M. BUCHER Site: RES

Note to requester: Portions of the attachment, which is immediately following this email, is redacted under FO IA Exemption 85, Deliberative Process Privilege . From: Kanney, Joseph Sent: Fri, 8 May 2015 13:14:40 -0400 To: Hiser, Matthew

Subject:

RE: Strategic Harvesting for Active Components Attachments: LTRP-FY2016-Su bmitta 1-JFK-2013-10-09.docx Here is the long-term research idea that I submitted on this topic. The idea was selected by the SL committee, approved by Brian and slated for an early start. That's how we got to this po int. --- Joe X

---

Original Appointment-----

From: Hiser, Matthew Sent: Thursday, May 07, 2015 1:22 PM To: Hiser, Matthew; Kanney, Joseph

Subject:

Strategic Harvesting for Active Components When: Friday, May 08, 2015 1:30 PM-2:00 PM (UTC-05:00) Eastern Time (US & Canada). Where: Matt will call 301-251-7600 Sounds good!

LTRP Submittal FY16 (updated 2013-10-09) Contact Information Name: Kanney, Joseph Organization: RES/DRA/ETB Project Information Project

Title:

Strategic Approach for Obtaining Material and Component Aging Information from Decommissioning Nuclear Power Plants Category: Other

               ! __*-. . .I (bJ(!5)

Cost Estimate:... FTE:LJ (b.)(?L Fiscal Year: FY2016 Work Description Structures, systems and components (SSCs) serving in a nuclear power plant (NPP) must withstand a very harsh environment including extended time at temperature, neutron irradiation, stress, and/or corrosive environments. The many modes of degradation are complex and vary depending on location and material. However, understanding and managing materia l and component degradation is a key for the continued safe and reliable operation of NPPs. The NRC and Industry will soon have an unprecedented opportunity to obtain very valuable but often difficult to obtain information on material and component degradation from the cohort of NPPs that will be decommissioned in the coming decade(s). In the last year four plants have ceased operation or announced that will cease operation in the next year (Crystal River Unit 3, Kewaunee, SONGS Units 2 & 3, and Vermont Yankee). These plants comprise a range of reactor types, containments, as well as structures, systems, and components (SSCs) important to safet y. Other NPPs may be added to this list in the near future. The objective of this project is to develop a long-range strategy or roadmap for obta ining information from these plants as they go t hrough decommissioning. The focus will be on timely acquisition of 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. A very broad range of materials, components or structures could be eventually investigated if the appropriate roadmap is made in advance. Potential items of interest include: 1) corrosion of core internals plus

primary and secondary piping; 2) reactor pressure vessel embrittlement; 3) corrosion of Ni-based metals; 4) concrete degradation; 5) corrosion of buried piping; and 6) degradation of Electrical power and l&C cabling and insulation; 7) effectiveness of previous mitigation or repairs; and 8) performance of replacement materials. Potential activities to consider could range from the relatively simple and inexpensive (e.g. enhanced inspections of previously inaccessible features) to complex and resource intensive (e.g., acquisition of sample materials or components followed by laboratory investigation or destructive testing). The road mapping process will identify a range of options and score them with regard to importance, complexity and resource requirements. The roadmap will, to the extent possible, take into account the type and schedule of decommissioning for NPPs in t he cohort. The roadmap will identify opt ions that represent "low-hanging fruit" as well as options that are high-risk, but high-reward . The roadmap will be developed in three stages. The first stage wi ll consists of a questionnaire and interviews with focus groups from various technical disciplines within NRC. The second stage will comprise one or two public workshops. The results of the first two phases will be combined into a final roadmap in the third stage. The roadmap will be developed in cooperation with Industry and other federal agencies such as DOE. International counterparts may also be interested in participation. Leveraging Resources (weight 10%) The project leverages resources while maintaining the NRC's independence and supporting the need schedule for issue resolution. This project will leverage resources both within and external to NRC. The most important internal resource to be leveraged is the collective knowledge and exper ience of NRC staff and selected contractors who have been engaged in license ext ension reviews, inspections, analysis of operating experience data, research on material and component aging issues, and probabilistic risk assessment. Previous efforts such as those that produced the Generic Aging Lessons Learned (GALL) Report and the Expert Panel Report on Proactive Materials Degradat ion Assessment, as well as insights developed by the "Life Beyond 60" Program will be leveraged in this project. Results of previous research projects on material aging and degradation issues will also be leveraged. One major external resource this project will leverage is DOE's Light Water Reactor Sustainability Program (LWRS) Program, specifically result s from two LWRSP R&D Pathways: 1) Materials Aging &Degradation; and 2) Risk-Informed Safety Margin Characterization. R&D efforts under t he LWRS Program are managed by DOE-NE's Office of Light Wat er Reactor Technologies, NE-72, and t he program Technical Integration Office, located at the Idaho National Laboratory (IN L). Another significant external resource to be leveraged is EPRl's EPRl's Long-Term Operation (LTO) Program; particularly R&D efforts in: 1) Primary System Metals Aging; 2) Concrete Structures, including Containment Degradation; 3) Advanced Safety and Risk Analysis Tools; 5) Cable Aging; and 6) Aging Management Program Scope for Operation Beyond 60 Years. R&D efforts in t he Long-Term Operations (LTO) Program are managed as a separate technical program operating in the Plant Technology

Department of the EPRI Nuclear Power Sector, with the guidance of an industry advisory Integration Committee. An initial list of targets for inspection or testing will be developed mainly through leveraging the internal resources listed above. The roadmap will be modified and refined through interactions with the external resources. But the final roadmap will represent the NRC's priorities and strategies for moving forward. It can serve as the basis for new MOUs, modifications to existing MOUs, or other formal arraignments with Industry. Advancing State Of The Art (weight 30%) The project advances the state of the art in a subject area with significant uncertainties and significant risk or safety implications. Understanding and managing material and component degradation is unquestionably a key need for the continued safe and reliable operation of NPPs. It is also an area with very 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 a relatively large cohort of decommissioning reactors can dramatically increase our knowledge-acquisition rate in this very important area. Independent Decision Making Tool (weight 10%) The project provides an independent tool or information that is needed for future regulatory decision making. This project is aimed at constructing a roadmap for obtaining unique and significant information that will inform the NRC's age-related regulatory oversight decisions over the next two decades, and perhaps beyond. Implementation of the roadmap, in cooperation with Industry and DOE partners can be accomplished over time, through individual research projects as the identified plants progress through their decommissioning phase. Multi-program Improvement (Weight: 20%) The project improves more than one program area or the integration between multiple program areas. The strategic approach to be adopted in this project is aimed at providing benefits to a number of NRC programs. Obviously, acquisition of key material and component aging and degradation information will improve the technical basis for NRR's review of license renewal applications; specifically review of licensee aging management programs. In addition, oversight of operating NPPS would be enhanced by acquisition of data and information useful reducing uncertainties or improving sensitivity analysis in

probabilistic risk assessments (PRA) . Another strategic target could be data and information useful in updating qualification standards for equipment used NPPs . Addressing Gaps (Weight 30%) The project addresses gaps created by tec hnology advancements that may be employed by licensees or applicants. There are a number of technical gaps that this project addresses. Most importantly, the current piecemeal approach that obtains isolated and fragmented degradation information as targets of opportun ity arise at a few plants can be replaced with a strategic plan that is more comprehensive, wider in scope, and more risk-informed. The roadmap 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. They 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 roadmap will also be useful in evaluating aging monitoring and mitigation strategies proposed by Industry. Additional Information Please provide additiona l support information for adding the LTRP in prioritizing your project.

Note to requester: Portions of this record are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Hiser, Matthew Sent: Wed, 3 Feb 2016 20:23:09 +0000 To: Frankl, Istvan Cc: Obodoako, Aloysius;Tregoning, Robert;Rao, Appajosula; Hull, Amy

Subject:

RE: URGENT ACTION : FY16 Shortfall Funds Hi Steve, (b)(5) Tha nks! M att Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-24541 Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Frankl, Istvan Sent: Wednesday, February 03, 2016 8:59 AM To: RES_DE_CMB <RESDECMB@nrc.gov>

Subject:

URGENT ACTION: FY16 Shortfall Funds Importance: High

CORs,

(b)(5) If possible, I would like to get your input today. Thanks , Steve

Note to requester: Portions of the attachment, which is immediately following this email , are redacted under FOIA Exemption 85, Deliberative Process Privilege. From: Moyer, Carol Sent: Wed, 18 Oct 2017 12:09:09 +0000 To: Seber, Dogan

Subject:

Response to User Need Request NRR-2017-006 (002) .response BT comments abh (IF).docx Attachments: Response to User Need Request NRR-2017-006 (002).response BT comments abh (IF).docx Dogan , Here is the latest working draft of the response to the SLR UNR. I appreciate your help to complete the table that has been inserted, showing related UNRs we are already working on. Thank you , Carol

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 beai:e 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 provideEI criteria to assess the need for harvesting to address a particular technical issue. The report Ytll.Lthen applyieEI 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 j§_was to serve as a foundation for NRG 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 other SLR-focused technical UN Rs are coordinated.9f8Vi$flq an umerella under whish SLR fosused teshnisal UN Rs are put m-oontext~ These technical UNRs:filffif)Ofted are shown in Table 1 below. 5

Table 1. SLR-Related Technical UNRs CoordinatedlRtegratee by UNR NRR-2017-006 UNR# UNR Title Comments INRR-2017-001 Request for This UNR is bBased on a previous UNR NRR- 2012-008.and updates Commented [IF1]: Why are some UN Rs highlighted on ML16300A303 ..J Assistance to Evaluate llleregulatory-_research~ on void swelling and clarifies currentwllal projects~rreAlly-HWel~ and what-future projects that are this page? I RES Response to Irradiation* being considered. 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 c urves. (b}(5) E.\!DQln~ tract ( Commented [IF2]: Please double-check by FY. I FY17:I (b)(5) FY18: I I l and FY19: fl(5) I (b)( ) I (b)(5)I (b)(5) .. N RR-2014-007 Reactor Pressure

                                           'F T Es : FY17iF*"'""IPY18:1...., 1and FY 19: I **I .... ....

Tliis UNR superseded UJILR NRR-2007-001 and includes6tasks:-{1) lb\15\ ICommented [IF3]: Same as above I ML14126A818 ..J 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 IN RR-2014-007 vessel material, (4) providing emergent technical assistance, (5) maintaining ML14212A127 database and documentation, and (6) performingl_documenting a tech {package) ..J evaluation on irradiation damage mechanisms and potential revisions to 10 CFR , part 50 App. G of RG 1.99 "Radiation Embritt lement of Reactor Vessel (b)(5)

                                           ~i:;:,al~~~ :(b)(5)(b)(5)                  (b)(5)                 (b)(5)

ICommented [IF4]: Same as above I (b)(5) FY15 ~~ Y16 - c::::::::J f:Yl7J;2gt 18 -c:::::J ICommented [IFS]: Same as above NRR-2011-014 Assessment of FTEs { f;Y1& -

• FY17 -~ FY18 * *.. b)(5)

NRR/DM LR's focus on this UNR is to assess aride!valuate condition I 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 o f FY2017. ML11335A169 UNR for The amendment extends the cable testing period up to 80 years (up from 60 Assessment of ears in the previous UNR). A mendment to Electrical Cable undin N RR-2011-014 f NRR-2016-0Jl) Condition Monitoring FT ( Commented [IF6]: Please add $sand FTEs by fiscal year. I ML16096A221 NRR-~ *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 stru ctures. 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 concrete block ML12152A107 ..J specimens to monitor the progression of ASR and assess its impact on in* situ mechanical properties, conducting destructive testing to assess structural impact including seismic response, evaluating numerical modeling methods, and material aspects for determining the state and rate of ASR,

                                           ~FTE:s                                                                                  ICommented (IF7]: Same as above.                         I NRR-2015-007     Effects of                The IPUrpose of this UNR is to develop technical bases for regulatory ML15076A217     Irradiation on            guidance to evaluate radiation effects on concrete structures close to Concre te                 reactors .*The focus of related regutatorythe research Is to evaluate the RES Response to  Structures                impact on structural capacity under design basis loads for service life up to N RR-2015-007                              80 years and develop aging management strategy.

ML15229A100 The 1Project includes reviewing EPRI and DOE reports by ANL (contract awarded in Jan 2016), harvesting the materials from the decommissioned Jose Cabrera NPP in Zorita, Spain

                                           ~       '                                                                               [ Commented [IFS]: Same as above.

l 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) oU i/year for this task be adj usted once the scope of work and the required level of RES

      '"siafif 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 NRR staff and adj ust the schedules for deliverables as needed to support effective regu latory 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 (b)(5) 1 Hold NRG/industry workshops (b)(5) [=:::::Jfor*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)1 Total (Task 1) I (b)(Jrt-1 2 Develop a strategy for harvesting Ex-Plant materials/components 2.A. Develop an information tool/database FY 18 b)(5) O c:::::lb)(5) * *** ******o<<,,.,, 2.B. Develop a process to evaluate plant components FY 18 b)(5) C ] { 2.C. Use the process from 2.B. to evaluate the suitability of plant FY 19 (b)(5)9 comoonents 2.D. Continue to implement the process from 2.B. as Ongoing (FY 20- (beb,*year components become available 21) (Total O (b) 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 materials (b)(5) Total (Task 2) ~ -***** (b)(5T T 3 Participate In relevant domestic and international activities (e.g., (b (5) CJ , year c::J._(l:>)(5) FY 18-21 (total for 4 years * ** IFRAM, IAEA, DOE LWRS, (Total Q IFRAM dues) EPRI LTO codes & standards) (b\iS\ 4 Develop documentation \0/\0/ evaluating significant technical c::3'ear FY 18-21 issues germane to the review of (Total t::] ..(tl (?) _ , SLR aPPlications 5 Provide technical assistance to To be funded if To be funded if (optional) 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

Note to requester: Portions of the attachments, which are immediately fo llowing this email , are redacted under FO IA Exemption B5 , Deliberative Process Privilege . From: Moyer, Carol Sent: Wed, 17 Jan 201815 :40 :10+0000 To: Purtscher, Patrick

Subject:

Response to User Need Request NRR-2017-006 response 20171019.docx Attachments: Response to User Need Request NRR-2017-006 response 20171019.docx, memo SLR UNR response NRR-2017-006 20171019.docx

Pat, If you need to ensure you are looking at the final Enclosure, check the package ML# at the end of the memo (also attached).

Carol

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 (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. 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, 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 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 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 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 w ill 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 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. IFRAM 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/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 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 associated SLR-focused technical UNRs are coordinated. These technical UNRs are shown in Table 1 below. 5

Table 1. SLR-Related Technical 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 Fundin (b)(S) (b)(5) an (b)(5) IEs:. EY.1.7, *** FY18 : ****** andEYt9.:...... ,. .. b)(5) (b)(5) NRR-2014-007 Reactor Pressure This UNR superseded I.JNR NRR-2007-001 and includes6fasks: (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 Materials" Rev 2. (b)(S) (b)(5) Fundin : (b)(5) (b)(S) .. . .* .*. .,_ FY15 - FTEs: FYJ6- *** FY17 - FY16 - ....* FY1? .i=::]Fv1s t-

                                                                                                   *** FY18 -     .. .(b)(S           _ _ __,

b 5 NRR-2011-014 Assessment of NRR/DMLR's focus on this UNR is to assess a * * . .i;1[1.Jate 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: (b)(S) .. (b)(5) NRR-2011 -014 Condition Prior FY total -C 3 FYf8 -~ ' FY19 -c:::J FY20 . r = = ; ).(b)(S) (NRR-2016-012) Monitoring FTEs: Prior FY total -c:::::::J FY18 - ****.. _F Y19 - r7 FY20 ~ b}(S) ML16096A221 (b)(5} .f 0(5) "lEi(s,}., . ... .... 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 (b)(5) specimens to monitor the progression of ASR and assess its impact on in-

                                            . -situ mechanical properties, conducting destructive testing to assess (b)~~i(S}           !3tructuraL impact including seismic response, evaluating numerical modeling (b)(S) ..... m_ *e.th.*.*_
                                                         .~.-q~...'..*a.._Q~:f!\i'!terial ~~eects for determining the state and rate of ASR. b}(5 f1.Jr:,d1ng:FY.14              -I -            JFY15                  FY16 ~                  + FYH**- ~+---+--

FTEs*: FY14 2- * ** FY15 .. *** FY16

• J;:.Y.1 L:::: ** . b 5 NRR-2015-007 Effects of The purpose of this UNR is to develop technical bases forreg'tilatory-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 The project includes reviewing EPRI and DOE reports by ANL (contract (b)(5) awarded in Jan 2016), harvesting the materials from the decommissioned (b)(S) ******* JtJse Cabrera NPP in Z-orita, Spain (b)(5}

                                            . ...F.vr,ding: FY1t,~c:::::J FY17 -                                  FYt8     -c:::::::J FTEs: FYt6-                      FY17 - , FY18 -                                       b (b)(5) \          (b)(S} -._

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) oft- - fyear 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} 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 the following table. Schedule and Resources 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) * ** *1for FY 18 (est. 2018, 2020) and prepare and FY 21 NUREG/CP and summary FY 21 [3year reoorts on four SRM tooics Total (Task 1) ~ (b)(5) (b)(5l .._ 2 Develop a strategy for harvesting Ex-Plant materials/components 2.A. Develop an information tool/database FY 18 [ 3(b)(5)_ I * * * *

• l<~l(?)_

2.8. Develop a process to evaluate plant components FY 18 c:::::::J,, , (t/)(5)

                                                                                                *~-.

2.C. Use the process from 2.8. to evaluate the suitability of plant FY 19 c:;}. .(b)(~). components 2.0. Continue to implement the (b)(5) process from 2.8. as Ongoing (FY 20- c::::Jyear

• components become available 21) (Total CJ . .

from additional plants (b)(5) 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in Task retrieval and testing of ex-plant FY21) 3, below materials Total (Task 2) L;;J

                                                                                   -(b)(~)

I ******- -1.(ti)(5) 3 Participate in relevant domestic and international activities (e.g., c::::Jyear (b)(5) I l <b)(~) ** . FY 18-21 (total for 4 years IFRAM, IAEA, DOE LWRS, (Total 1.0) IFRAM dues) EPRI LTO, codes & standards) 4 Develop documentation (b)(5) evaluating significant technical FY 18-21 c:::::]year 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)(S) \ (b)(5) \ 8

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20S55-0001 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 Tasks A and D of 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 serves as an "umbrella" under which associated SLR-focused technical UNRs are coordinated. These technical UNRs include NRR-2017-001 (reactor vessel internals); NRR-2014-007 (reactor pressure vessel), NRR-2016-012 (electrical cables), NRR-2012-004 and NRR-2015-007 (concrete degradation), More details on these UN Rs are provided in Table 1 of the Enclosure. 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 andl 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.
• Task 5: Provide expert assistance with reviewing SLR applications (optional task)

B. Holian 2 CONTACT : Amy Hull , RES/DE 301 -415-2435 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 resu lt 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 ensu re that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs cou ld impact the activities, del iverables 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:

1. 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 . fvbyer, RES M.Hiser, RES M. Kirk, RES J. Philip, RES M. Sircar, RES J. Pires , RES RidsN rrMailCenter ADAMS Pac ka 1e A ccess1on No.: ML17227A483 OFFICE RES/DE/CMB RES/DE/CMB RES/DE/CMB NAME C. Mover A. Hull I. Frankl (email) DATE 10/ /2017 10/ /2017 10/ 19/2017 OFFICE D:RES:DE RES Mai l D:RES NAME B. Thomas K. Johnson M. Weber DATE I /20 17 I /2017 I /2017 OFFICIAL RECORD COPY

Note to requester: A portion of the attachment, which is immediately From: Moyer, Carol following this email, is redacted Sent: Wed, 20 Sep 2017 04:05 :13 +0000 under FOIA Exemption 85, To: Frankl, Istvan Deliberative Process Privilege. Cc: Hull, Amy; Moyer, Carol

Subject:

Revised SLR UNR Response Attachments: SLR UNR response 09-19-2017_cem.docx

Steve, The attached draft response to the SLR User Need Request incorporates the latest changes from Rob T., Amy, and myself, including changes to address NRR/DLR staff comments and questions on our first draft response.

Please review and add your comments. Thank you, Carol

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.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 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.
• Task 5: Provide expert assistance with 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. RES also proposes an additional, optional task, Task 5. If needed by NRR, under this task, RES staff would provide expert assistance to review and evaluate applications for subsequent license renewals . 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 : RESPON SE TO USER NEED REQUEST F OR RESEARCH ASSISTANC E ON POTENTIAL S IGNIFICANT TECHNICAL 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. Iyengar, 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. Sircar, RES J. Pires, RES RidsNrrMailCenter ADAMS PackaQe A ccess,on N o.: MLxxxx OFFICE RES/DE/CMS RES/DE/CMB RES/DE/CMB RE~--+I-G-E--B NAME C. Moyer A. Hull I. Frankl +. Kesl::!y DATE I /2017 I /20 17 I /2017 I t~QH OFFICE ~ D:RES:DE RES Mail Room D:RES NAME Q. SeseF 8 . Thomas K. Johnson M. Weber DATE I t~Gr7 I /2017 I /2017 I /201 7 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 (e-i#\ef-such as, a workshop, conference, symposium, or meeting), one in early autumn 201 Btentatively planned for spring 2019 on mechanical issues components and one in late springtentatively 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 theeach workshop.Prior to tho 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. Materials Issues for Mechan ical Components~ -As part of the requested autumn 2018spring 201 Q workshop/ conference/ symposium/ meeting on materials issues for mechanical componentsfss1:l.es, tentatively planned for spring 2019, the NRC staff will coordinate a session, or sessions, concerning issues associated with 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 Cables Issues - RES will also hold an NRG/industry workshop with international participation in the third !fil!!:!.b_quarter of F¥20 (~ tentatively planned for summer 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 technical topics and items of interest. RES will prepare and will provide to NRR drafts of the agenda, list of in¥ited presenters, and workshop announcoment. 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 summer 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, described in paragraphs 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 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." 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 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. Subtask 2.A. Moving forward, RES will work internally to evaluate how the four significant issues identified for SLR in the SRM on SECY-1 4-0016 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 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 specifiCA example, RES will develop a process to evaluate harvested concrete samples-harvested from decommissioned plants, and will follow through with implementing the process as concrete materials become available from additional pllants. 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 using harvested cables. 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 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 w ill evaluate potentially-available components from plants performing component replacements or entering decommissioning (Subtask 2.C). If other nuclear facilities present opportun ities 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 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 compo nents. 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, tihe 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 t his 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 (HRPl 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. Tasl, 1 alse allews fer MRR te 0all 1;1peR R!iS te previcie inciepeRcieRt eeRfirrnatery aRalyses aRci 01,pert teeRRieal assistaRee witR tRe review ef aRtieipate1 Sid~. applieati@Rs witR p@teRtially

      ~RifioaRt icc1:100, 01:10!;1 as tlotece Roo1in~ ,:3laRt cpooifio ~8f3 aRal;*coc .

RES will atsG---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. 8 1 : M l e t ~ ~ " ~ ~ a - t l l ' l 6 ~ ~ R R 2Q11 001 , R66-staft will-- eentiRuo te 00 availalalo te l'Jf@vi1o 00RfirrnatoP.,1 aRalysoc an1 oitf'JOrt toot:rnioal ascistaRoo wiU:i t-he-ro¥iow @f tlolo toelolRieal 1eeurnoRts te 00 su0rnitto1 witlol SLR afilf'llieatiens. RE!S will 00 availalalo t@ cup~Ft tiglolteF 56R af'lfi)lieatiern ro*;iow oet;i01ul00 as well as tt;io roviow of fillaRt cpeeifie Qafil

      ,;rnalys0s 0xJi)0et01 witlol tlolo firnt Elfilf'llieatieRs. R~S su0joet matter oxJi)orts (SM~s) will bo available to fi)artioifi)ate iR toololRioal 1isoussiens, iR1op0n10Rt roviows, 10¥0leprnorit ef toololRioal bases, aR1 &lolfilfil@Ft 0f mootin~s with iRh~rRal aR1 oxtorRal stal,oholr;fors.

As aR a1tarn13la, tlola staff will l@RtiR1;10 te 00 av0Ka0lo t@ review @porotienal oq1;1ipm0Rt fail1;1ros te assoos-ttoio troR1 iR eritieal risl, cigrufiearit oloetrieal oquiprnorit. Thero aro eeReornc witfl-agiRQ effeets ~iRelw1iRQ eyelie agiRQ) aR1 1esiQR life ef eU=wr eleetrieal eernpeReRts swetoi as smalmrs an! folays wt;iieh wewld-flee1-fwrtRor ovalwatien te assess its eeRtiooo1 soPJieo lif0-l)y-oxpleriRQ etROF FR@RiteriR9 tOGRRiqwos Ret QOROrally GOVOF01 b1R80F SblF¥8illaRGO toots. S1,10t;i aRalyses 001,111 oerni;ilerneRt werl< iR Tasl< 2, wt;iereey eritieal eleetFioal om:i-;ipeRents oan ale@ 00 Rar-vosto1 aR1 ovalwato1, Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) ofJ...

• rvear 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) Task 1 also aUows forShould it choose to implement optional Task 5, NRR te-may call upon RES to provide independent confirmatory analyses and expert technical assistance with the reyjew of anticipated SLR appljcations wjth 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 revjew of the technical documents to be submitted w jth SLR aooljcations RES wm be ayajlable ta su. Q ~hter SLR aQpncatjon review schedules as well as the review of Ql,a nt-specific qaQ,J1n,aJyses exnru;:Jed withlhe first ePPlications, RES subject matter experts <SMEs} will be available to oarticipate in technical discussions, independent reviews, development of technjcal 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 aginal and desjgn life of other e1ectrjca1components *.§uch as breakers and relays. Wftt§Awh ich would need further evaluation to assess it§their contjnue,g_ servjce life by explorjng othe r monjtorjnq techn jques not qeneraliy covered under surve jllance 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 adjust the schedules for deliverables as needed to support effective regulatory 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 (b)(5) 1 Hold NRC/industry workshops (est. 2018, (b)(5) I .f for FY 18 [ Jy~*; r and FY 21 2020) and prepare FY 21 NUREG/CP and summary I ........ 1,t ) (5) reports on four SRM topics Total (Task 1) I * * * * ..... J (b){?) L.:;;J (b){S .* 2 Develop a strategy for harvesting Ex-Plant I  ! ..(b){5 materials/components - ~-- **-

                                                   .J          i-L . _
                                                   -                .J - * -

2.A. Develop an information (b )(5) tool/database FY 18 I ' ' ' ',,,., , I . J ,,,,, ( ) 2.B. Develop a process to evaluate plant components FY 18 I ... *I '************** ............. ...................... .......... ......... .......,. J .) 2.C. Use the process from 2.B. to evaluate the suitability of plant components FY 19 CJ * ( )(5) 2.D. Continue to implement the process from 2.B. as Ongoing (FY c::::J'~ear ............................. .....,. ,.... .....,..................... J )(5) components become 20-21) (Total C ] * ***** ***************

                                                                                                     """                                        ,, ,,,,,,,,,,,,,,,,,,,,,,. ,{J (5}"

available from additional plants 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing Included in retrieval and testing of ex- (FY18-FY21) Task 3, below plant materials Total (Task 2) I - I I L .(b) ?.

                                                                                          -(b)(~)

3 Participate in relevant domestic and international (b)(5) E::Jyear c=::::1 c~x?).. activities (e.g., IFRAM, FY 18-21 (total for 4 years IAEA, DOE LWRS, EPRI (Total ~ IFRAM dues) (b)(5) , LTO, codes & standards) 4 Develop documentation (b)(5) evaluating signiificant c:::::::tyeiar technical issues germane to FY 18-21 (Total Q the review of SLR (b )(S.). applications

     ~      Provide technical To be funded                                      To be funded if (12ro12osed} assistance to NRR for                  FY 18-21 if needed                                                   needed reviewinq SLR aoolications.

Total (Tasks 1-4, over 4 years) c ; J(b)(5)_ I ... ' **, ~ I*(b}(g_)

                                                  -11

Note to requester: A portion of the attachment, which is immediately fo llowing this email , is redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Moyer, Carol Sent: Tue, 24 Oct 201716:50 :17 +0000 To: Cole, Cassandra Cc: Frankl, lstvan;Hull, Amy

Subject:

SLR UN R Response - Revised file for the enclosure Attachments: Response to User Need Request NRR-2017-006 response 20171024.docx Cassandra , The attached file is the electronic version of the paper copy that I gave you this morning , along with the concurrence package. The package is at ML17227A483 . The attached file is the enclosure for the memo, at ML17227A485. Please let me know if you have questions. Thank you , Carol Carol Moyer Sr. Materials Engineer RES/DE/CMB carol.moyer@nrc.gov 301-415-2153

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 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. 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='ini 1.,a :_ _ _ _ _ _ (b_J(_5l_ _ _ _ _ _ _ _ _ _ __, (b)(i) FY17: I..,__ _ _ _ _ _ _ _._ ....._ _ _ _ _ _ _ ___.1_ ___, (b)(5) ty 113;1 ' ' ,,,, ,,,.,,,. ........ I and FY 1 e:' (b)(5) I (b)(5)1 (b)(S) *********** ..._F_T..., "..*:-"-=-** .-**7*- ...,.... E..*s ..-. ... I...F-.¥-**1*-8*r1....-... -.l-an_d_F_Y_1_ 9** -......

                                                                                                                                                                .., -,,b--"-5"_ _ _ _ _ _.;..;..;..;.,i
                                               .....     '""'       ,...~...J.,..J...., .. , -..........                  **;. .                         IJ       .......... IIJJt : )J NRR-2014-007     Reactor Pressure                     This UNR superseded I.JNR NRR-2007-001 and inclu-des 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 Materials" Rev 2. Fundina: (b)(5) (b)(S) (b)(5) (b)(5) (b)(5) (b)(5) FY15 -I + FY16-~ l;::Y.17~~ FY18 ~ FTEs: FY16*I IFY17':i"""f FY18-l f ..(Q)(5) NRR-2011-014 Assessment of NRR/DMLR's focus on this UNR is to assess aria evaluate 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). Amendment to Electrical Cable Funding: (b)(5) (b)(5) (b)(5) (b)(5) NRR-2011 -014 Condition Prior FY total -r:::=7*FY1'8'-=E=] FY19 -c::::::::I_FY20 -i=::::::) ... . . (NRR-2016-012) Monitoring FTEs: Prior FY total --c::J FY18 - Q FY19 -Q FY20 -c:;J,~" ML16096A221 (b)(5} .. (b)(5) , /bl/5\ , (b)(~) . NRR-2012-004 Alkali-Silica The objective of this UNR is tel develop tecfmical 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)(5) situ mechanical properties, conducting destructive testing to assess

                                             *** structU[i:11 impact including seismic response, evaluating numerical modeling (b)(5) methods, aridmaterial.aspects for determining thF! c:t<it" :mrl rate of ASR. (b)(5 (b)(S)                Funding:FY144                                                              I FY'f5 ::::F 7 FY16-I *** . I FY17 -[ 3 lb\15\ FTEs,*-F¥44*- r:::7EY..1.5*: +:7 FY16 -I **I FY1? .,,t ..... : I..."** (b)(~) .                                                                                          (b)(S)

NRR-2015-007 Effects of ThepOrj5clse of this UNR is to develop technical bases for regulatory (@~ 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 The project includes reviewing EPRI and DOE reports by ANL (contract awarded in Jan 2016), harvesting the materials from the decommissioned (b)(5) Jose Cabrera NPP in Zmita, Spain (b)(5) Funding: FY16 - E : : ] FY17 -c:::::::]FYl8 - [::::::::J. (~)(5) FTEs: FY16 - n FY17 - 17FY18 1""l j 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. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(5) qt L ..... !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. 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)

                                                                                                           ****** lforFYT8 (est. 2018, 2020) and prepare                                                                 and FY 21 NUREG/CP and summary FY 21            [ ]year

• reoorts on four SRM tooics Total (Task 1) Q (b)(5' (b)(5) 2 Develop a strategy for harvesting Ex-Plant materials/components 2.A. Develop an information tool/database FY 18 c=J{ b)(p) .. I *********** l ( l))(5)-***

2.8. Develop a process to evaluate plant components FY 18 c:::::J ,{p){?. .'** 2.C. Use the process from 2.8. to evaluate the suitability of plant FY 19 C ](b){?) components 2.0. Continue to implement the (b)(5) process from 2.8. as Ongoing (FY 20- c::::::}'yea r** components become available 21) (Total Q from additional plants (b\(51 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in Task retrieval and testing of ex-plant FY21) 3, below materials Total (Task 2) c::J I *,. I

                                                                                                                           ~o)(-5)_
                                                                                         .(b)f5) 3         Participate in relevant domestic                             (b)(5) and international activities (e.g.,

FY 18-21 C3'year EJ

                                                                                                      *(total for4 years                . . L. )(5)

IFRAM, IAEA, DOE LWRS, (Total [ : ] IFRAM dues) EPRI LTO, codes & standards) (b-) ~J 4 Develop documentation (b)(5) evaluating significant technical c:::::::}year* FY 18-21 issues germane to the review of (Total Q SLR aoolications (b) Q/..., 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)(oJ (b)(5*).... (b)(5) (b)(5) 1 Note that t he resources associated with this UNR include RES/DE/SGS EB U ' , . l yr over 4 years andd and RES/DE/CMB (balance). All other SLR-related work is covered by the UN Rs shown in Table 1. 8

Note to requester: The attachments are immediately following this email. Portions of the two Excel files (.xlsx attachments) are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Frankl, Istvan Sent: Tue, 7 Jul 2015 21:25:10 -0400 To: West, Steven Cc: Brock, Kathryn;Bamford, Lisa;Stout, Kathleen;Hull, Amy;Hiser, Matthew;Focht, Eric

Subject:

STAQS action for "Strategic Approach for Obtaining Material and Component Aging Information" w/ PNNL Attachments: StratHarv SOW 7-6-15.docx, PNNL TASK 1 IGCE.xlsx, PNNL ALL TASKS IGCE.xlsx

Steve, PMDA has notified me today that subject request for proposal and funding action to initiate new work with PNNL had not been routed to you for approval.

This work has three inter-related objectives: (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. 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, nuclear facilities, long-lived industrial plants, materials organizations) that will inform the NRC's age-related regulatory oversight in the future. This exploratory research is expected to provide fundamental insights on reactor materials degradation to support anticipated future NRC needs. (3) Update the Proactive Management of Materials Degradation (PMMD) information tool developed at PNNL for RES to incorporate LTO/SLR-relevant information so that it can be better used to inform prioritization in the ex-plant material strategic plan. The tasks associated with this work and their duration are described in the table below: Task Task Title/Description Duration (Months) Task 1 Scoping Study and technical literature review 18 Optional Decision Making on Specific Confirmatory Research Needed to 6 Task 2 Address Gaps Optional Confirmatory Research Addressing Technical Gaps 33 Task 3 Optional Development of Independent Decision Making Tools 33 Task4

The optional tasks above wil l be conducted, as shown in the figure below: Task 1. Terminate Technical Task 2. Gap Further Literature Identification Research Review Yes Task 3. Recommend Research Need

                                                    ,--------*--------~

I Task 4. :I

I Develop :I

Analysis Tools :

                                                    ~----------------J A decision on further optional research outlined in Tasks 2, 3, and 4 above will be made after completion of Task 1.

For your information I have attached the Statement of Work as well as the Independent Government Cost Estimates that include the cost of the base scope (Task 1) as well as the total cost with options (Tasks 1 through 4). Please let us know if you want this action recalled and resubmitted for your review in STAQS.

Thanks, Istvan (Steve) Frankl Branch Chief RES/DE/CMB U.S. Nuclear Regulatory Commission Phone: (301) 415-2227 (after 6/22/2015)

E-mail: lstvan.Frankl@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.

                           '37
                           ~
                                         .-------L- - - ' - - ~

PARTS INFORMATION Excel spn,adshoo/s by proop dove/oped by BNL. revised bosod on t chnic in t.

                          '47 ~-L---~

L...'.:'....J COMPONENT SUBGROUPS

                   . - - - --            Exc,il sproadshoola dovelopod by*

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: 6/112015 Independent Government Cost Estimate Fiscal Year Summary Project

Title:

TASK 1

• Strategic Approach for Obtainin Estimated Period of Performance: ______ 1-_S~

ep

                                                                     ~*_20_1_5_ _ _ __      thru                           30-Sep-2019 DOE Laboratory: Pacific Northwest National Laboratory (PNNL)

Matenals Grand Total Labor Subcontractors & Fiscal Year & Travel Other Direct Costs Total G&A Rate DOE Added Factor 3% (Total + G&A Rate + DOE Added (Fully Burdened) Consultants SP.rv1r.P.s F;:ir.tnd FY 2015 (b) 5) FY 2016 FY 2017 FY 2018 FY 2019 FY 2020 Total IGCE Summary

Project

Title:

TASK 1

• Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL)

Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Labor Cost FY 2015 FY 2016 FY 2017 FY 2018 FY 2019 FY 2020 TOTAL Labor Category Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total (b)(5) COMMENTS: labor 8FFICIAL USE ONL't'

Project

Title:

TASK 1

• Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL)

Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Materials & Services Costs COMMENTS: Materials & Services 8FFICIAL USE 8Nt¥

Project

Title:

TASK 1 - Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Travel Costs FY 2015 FY 2016 FY 2017 Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost (b)(5) FY 2018 FY 2019 FY 2020 Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost ( )( ) COMMENTS: Travel OF~ICIAL USE ONLY

Project

Title:

TASK 1 - Strategic Approach for Obtaining Material and Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Subcontract & Consultant Costs Subcontracts* Consultants OFFICIAL USE ONL't'

Project

Title:

TASK 1 - Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Other Direct Cost I I I I: I I I I COMMENTS: Other Direct costs QHl~IP.L 1:15[ 9Nl¥

Iinstructionsfor use: I j .I, DESCRIPTIONS AND VALUES .I, To update the rates for Travel, DOE Added Factor, and G&A, enter the new rate in the "Rate" column (red cells). To update the Labor Categories, make the updates to the columnsGthru X (green/white cells). (b)(5) Maintenance O~~ICIAL 116[ 9Pil¥

Instructions to add additional Labor Rates If the labor rates captured in the IGCE are not an accurate portrayal of the labor rates necessary, additional rates

1. Go to the Maintenance tab and start with cell Gll

2. Enter the new labor category name in Gll

3. Follow Row 11 over and enter in the labor rates for that labor category under the correct fiscal years

4. Continue to add additional labor categories and labor rates in the cells provided until all are captured

5. These labor rates will then populate the respective fields in the other tabs of the IGCE template

Version Control Date: 6/112015 Independent Government Cost Estimate Fiscal Year Summary Project

Title:

Strategic Approach for Obtaining Materia Estimated Period of Performance: ______ 1-_S~ ep

                                                                   ~*_20_1_5_ _ _ __      thru                             30-Sep-2019 DOE Laboratory: Pacific Northwest National Laboratory (PNNL)

Matenals Grand Total Labor Subcontractors & Fiscal Year & Travel Other Direct Costs Total G&A Rate DOE Added Factor 3% (Total + G&A Rate + DOE Added (Fully Burdened) Consultants Services Factor\ FY 2015 (b)(5) FY 2016 FY 2017 FY 2018 FY 2019 FY 2020 Total IGCE Summary OFFICIAi I 15E Ollll:f

Project

Title:

Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Labor Cost FY 2015 FY 2016 FY 2017 FY 2018 FY 2019 FY 2020 TOTAL Labor Category Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total Hour Total Cost Total (b)(5) COMMENTS: labor 8FFICIAL USE 8NL¥

Project

Title:

Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Materials & Services 8FFIEh\L U5E ONtv

Project

Title:

Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Travel Costs (b)(S) FY 2015 FY 2016 FY 2017 Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost rY zurn rr zu,~ rY zuzu Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost Purpose # Staff Duration (Days) Cost ( )( ) COMMENTS: Travel QFFIGIAL USE ONL\'

Project

Title:

Strategic Approach for Obtaining Material and Compom Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Subcontract & Consultant Costs COMMENTS: Subcontracts* Consultants OFFICIAL USE ONLY

Project

Title:

Strategic Approach for Obtaining Material and Component Aging Information Site: Pacific Northwest National Laboratory (PNNL) Estimated Period of Performance: 1-Sep-2015 thru 30-Sep-2019 Other Direct Cost COMMENTS: Other Direct costs OFFIClifcl l::ISE 9NLY

IInstructionsfor use: I I To updatetherates for Travel, DOE Added Factor, and G&A, enter

                         ..::==============:::::.-==================================================================::...
                               .I, DESCRIPTIONS AND VALUES .I, the new rate in the "Rate" column (red cells).

To update the Labor Categories, make the updates to the columnsGthru X (green/white cellsl. (b)(5) Maintenance 6fflel~L U!EOl~Li

Instructions to add additional Labor Rates If the labor rates captured in the IGCE are not an accurate portrayal of the labor rates necessary, additional rates

1. Go to the Maintenance tab and start with cell Gll

2. Enter the new labor category name in Gll

3. Follow Row 11 over and enter in the labor rates for that labor category under the correct fiscal years

4. Continue to add additional labor categories and labor rates in the cells provided until all are captured

5. These labor rates will then populate the respective fields in the other tabs of the IGCE template

Note to requester: The attachments are immediately fo llowing this email. Portions of the second attachment are redacted under FO IA Exemption 85, Deliberative Process Privilege. From: Moyer, Carol Sent: Thu, 19 Oct 2017 19:46:10 +0000 To: Cole, Cassandra;Vera, Graciela Cc: Frankl, lstvan;Hull, Amy

Subject:

UNR Response - Updated files Attachments: memo SLR UNR response NRR-2017-006 20171019.docx, Response to User Need Request NRR-2017-006 response 20171019.docx

Ladies, Please update the ADAMS package at ML17227A483 with the two files attached .

ML17227A484 - memo SLR UNR response NRR-2017-006 20171019.docx ML17227A483 - Response to User Need Request NRR-2017-006 response 20171019 .docx I will bring the concurrence package back to you. Please contact me if you have any questions. Thanks again for your help. Carol Carol Moyer Sr. Materials Engineer RESIDEICMB carol.moyer@nrc.gov 301-415-2153

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20S55-0001 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 Tasks A and D of 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 serves as an "umbrella" under which associated SLR-focused technical UNRs are coordinated. These technical UNRs include NRR-2017-001 (reactor vessel internals); NRR-2014-007 (reactor pressure vessel), NRR-2016-012 (electrical cables), NRR-2012-004 and NRR-2015-007 (concrete degradation), More details on these UN Rs are provided in Table 1 of the Enclosure. 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 andl 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.
• Task 5: Provide expert assistance with reviewing SLR applications (optional task)

B. Holian 2 CONTACT : Amy Hull , RES/DE 301 -415-2435 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 resu lt 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 ensu re that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs cou ld impact the activities, del iverables 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:

1. 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.Jvbyer, RES _ _ M.Hiser, RES M. Kirk, RES J. Philip, RES M. Sircar, RES J. Pires , RES RidsN rrMailCenter ADAMS Pac ka 1e A ccess1on No.: ML17227A483 OFFICE RES/DE/CMB RES/DE/CMB RES/DE/CMB NAME C. Mover A. Hull I. Frankl (email) DATE 10/ /2017 10/ /2017 10/19 /2017 OFFICE D:RES:DE RES Mai l D:RES NAME B. Thomas K. Johnson M. Weber DATE 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 (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. 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, 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 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 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 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 w ill 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 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. IFRAM 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/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 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 associated SLR-focused technical UNRs are coordinated. These technical UNRs are shown in Table 1 below. 5

Table 1. SLR-Related Technical 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 Fundina: (b)(5) FY17:I I (b)(S FY18:*- i - - - - -.-.............-... -......-......-.. ...-. _ _ _ _ _ _ _ _ __._,___ _I (b)(5 ~=***":. . . .~*:::::::::::::::'.'.::'.:::::::::::::::::::::1a~n@:air-Yr !,1 ~r:;_,: (b)(5)1 (b)(5) FTEs: FY.17.J I FY18*:I *+ and..E.Y:.1.9.L ... j ..... (~)(5) \UJ\;l/ 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 Materials" Rev 2. Fundina: (b)(S) ~ (b)(5) (b)(S FY15A I FY16 -r:'7\, FY17 -I Y18 - I .. /  ! (b)(5) FTEs: FY.16 + I FY17 ~ FYJ8:I 1 ..{b}(S) lh\l'i\ NRR-2011-014 Assessment of NRR/DMLR's focus on this UNR is to assess*a11devaluate 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) (b}(S) Amendment to Electrical Cable Funding: (b)(S) (b)(5) .. NRR-2011 -014 Condition Prior FY total -c:::::::::J;*FY18 - c::::::::::JE.Y19 - ~ *** FY20 -c:::::::J (NRR-2016-012) Monitoring FTEs: Prior FY total - Q FY18-Q FY19- * , FY20 - Qb)(5) ML16096A221 {b)(5).. * !c-.. 0r 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 (b)(S) *srracturaLimpact including seismic response, evaluating numerical modeling

                                       ... methods, and*m.aterial aspects for determining the state and rate of ASR.

(b)(5) * *i=unding' Fv14A . 1Fv1s ::t * *  ! Fv16 - * *-.... '. Fv17 -c::J (b)(5) ..... FTES; f:Yt 4 ;;.F'JFY15 - f:7 FY16 - 1 *I FYtZ:l(b)( I 11i,is1(b)@1b11s\**. NRR-2015-007 Effects of The purpose of this UNR is to develop technical bases fofi'egulatory .. 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 The project includes reviewing EPRI and DOE reports by ANL (contract awarded in Jan 2016), harvesting the materials from the decommissioned (b)(5) J?se Cabrera NPP in Z-orita, Spain (b)(5) . . (b)(S) Fuhdihg:FYt6°E : : ] FY17-I - 1FY18**~c::::::::J ************* FTEs: FY16 - 1'1 FY17 -n FY18 -I -J (b)(S) \ ', (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. Based on the latest assessment of projected needs in this area, RES proposes that the estimate (b)(S) ofl ..

• fvear 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} 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 the following table. Schedule and Resources 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 I

• jtorFY18 **

(est. 2018, 2020) and prepare NUREG/CP and summary FY 21 I {~lt~~ar and FY 21 reoorts on four SRM tooics Total (Task 1) (b)(5) 9 b){5)_ 2 Develop a strategy for harvesting Ex-Plant materials/components 2.A. Develop an information tool/database FY 18 [:=J (bX?) . I * ***********l (b)(?) .. 2.8. Develop a process to evaluate plant components FY 18 c:::J {b.)(9 "* 2.C. Use the process from 2.8. to evaluate the suitability of plant FY 19 c=)(P)(?l .. components 2.D. Continue to implement the (b)(5) process from 2.8. as Ongoing (FY 20- c:::]tyear * ** ** components become available 21) (Tota1 9 from additional plants b)("= l 2.E. Pursue partnerships for cooperative cost-sharing on Ongoing (FY18- Included in Task retrieval and testing of ex-plant FY21) 3, below materials (b)(5) Total (Task 2) ~ I .,. ,--* (b){5J .. 3 Participate in relevant domestic and international activities (e.g., c::::::i " .... .L.. IFRAM, IAEA, DOE LWRS, EPRI LTO, codes & standards) FY 18-21

                                                                      ~i (Total     ,

(o)f! l (total for 4 years IFRAM dues) 4 Develop documentation (b)(5) evaluating significant technical c::::::tyear FY 18-21 issues germane to the review of (Total Q SLR aoolications {IJ), 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),',

{DJ(<>/.. 8

ce .... Note to requester: This record was originally provided ~o the '.OIA team in paper, and then scanned. This is the best quahty availabl e. Extended Operalions of the Existing Reactor Fleet Is In the lbdenaiD of NI *1ce Of9 may C811N 119W National Interest chllengN for materl ala Nnloe MAaD Pathway 0-.Slar. . . . a-a,lleq) ICIIIID gnM-M la'n 2012 D L----*-- -- 2IMQ. Allll-111 1.maatd om......._..,.....,,.. Ill~~ I

                                                                            --~

• ru:IISpc .-. . . .

I blgb,_,., ..lllendd _,, t1Slllllll2 1),-

    *1p1 --s,            I *  .,"'111>,,.._
                                                                             ..-..icnti, ._Ofwn,i l
                                                                                                          *amn1~,.-.PQ11Wpl:ril9donotoper.-
                                                                                                          ~eo,-. {n11N...... .. ,..tdl                             ....
                                                                                                                                                                   ~------Dlllll
                                                                                                                                                                            ... _..      .       m,ald_,,_..._..
                                                                                                                                                                   ,.__....- . . . . . . . . _.Cll"l. .

oi-llonll

                                                                                                          ~. . . . D . . . . . . . . . tallllrdon d
                                                                                                          ~---lli agylo miMN ~wll Tllt. . . . . . . . . . . . . . . Aeli'I . ..,......, __,,. .. _
                                                                                                                                                                   ---dlclitlotlllll llmlly-DOE and NRC hive lnvatlglllld lmlea of reaetor aging beyond IO yearw to Identify posalble knowledge gaps                                            Materials Aging and Degradation                                 MAaD Includes a dlvem materials research effort tum
                                                                            * ~~Al lcu" '-n... _.,c: m-... .-n~n baln:e d pail
                                                                                 * ** idlloi

• t I 1S...Cc no9icn ~

                                                                                                                                                     --                                                            --- --~.- *--          -*--
                                                                                 * ~pla e***n... ,nd . . . . . dc:m.., ...                            . . . . . _ l. . .

• lfgh-Aalct lllcla en RPV 11N1
• C1acl--. nlnlbllll elecl.-,,.
• Therml!AQ!tv dc.tAull dic s.illa Slilla Q ~
• Emfllt- -Alllllld F1191a
• Ccmlll: MC~ll llftwll EPRI b:uledcn llllllarllhcls(IUIIPCl 1lnl tiigalltl tlld).AS Rllld~ll ia
• CllltN: Jatnll.-d l plal wltl EPRlnl NRC Dblilllrpt d:tnlaoll0 rcabll HIMEG I CJl.71SS
• __,,fll)l llr,llld. ___llet mlQlll: w.lfll)ll lr~POII lrradlallan.....-ci;Mtalced,.........

The 5 M's of the MAaD/LWRS Pathway Cable Aging and Cable NOE

      . . . . . . . .,. .,,....,....,, Collet high quality dala                                                                                        PurpoN

• Develop cable aging modll/S and mo,,#otfng lechlliques to suppo,t lon{Heml ope,alion of nuclear power plant Qlbo1e aysmms
• llld*llsms ,IfdlpidlOOA. Understand 118 ~ mecllanlsmsforbelW p,8llcllonlllClmlligalan

                                                                                                                                                          ~ ---~ol--and).-t Medlod/,,__,.

_____ to......,.

   * .,,,...._,........,, Usernechndcmodels IOeJll)kndllalllndslOr Research Highlights: Cable Aging and NOE                                *  ,,,..,..  ,a,..
                                                                                                                                                          ~dlomlcal,ond          ol cable lid~_      _ s,steffll

_ ~_In UN

                                                                                                                                                          ..,...,.,.anduyfoclonfo< _ _ _                                        i e$1dedlle
   * . . , . . MonllDr a,d valdall p,d:led oei,adalan
   *   ..............-: DNlapllldnlloglesll)n!ducll . . . oldl!Jadabl, fadaal8eQln0ffllc . . .. and ~ ........ a:tvancad ffllllelialsthatan, lesssm,plble Updllecl. .O-~-1D-OU1.-tr-
                                                                                                                                                          ,..,_,,,.-~,-.--OOl/fflllllaC-...--u-OE/f-~--""""'"'-""~---

1~. Leo Rlleld, 811 Gian 1-:l Robert Ducllwmtll IORNLI * *lr'!;@ ~ 111115 (Dl!iliiiiiir -=-

            =

Consistent differences observed versus Updated Cable Research Roadmap: ~-= -

                                                                                                                                                                                                            *P~--.:;-     ............ -

Cable Aging Degradation and Gap Analysis ":T'.:..

• coonllnat9d,accelttmd . . . oflwwS1adClble l ----

database values for jacket EAB

                                                                                   ~agillgln*IIIOO'C&l2ll'C
                                                                                    - ~c:<>nrdlOdcllill:IIW         !

f

                                                                                                                        *~ r/--..:....-*
                                                                                                                             ~

• I Accelerated Aging lnsulatlon/)adoet..-talslhatare~ lt,palonJaelill*B'R- _ .. ..

of current NPP systems ~IA_..,tor.........,31--!~

                                                                                       ,,,                            ..        t Slatusol-" ..... coa.-.,1 tmlls
                                                                                       ~::~-                               --       . ~    - ... -

Combined thennal/pmma ltRd- series of XI.PE - S..Ord9-- - *

• I at 90C completed

     ~ t h e r m a l. . of harwsted Hypalon/                                       Elol!galDl*---onjacael                              --

CSPI: cables~ a,mpleted Developed .-,ce1 method and ca,relattd - wllh EA11 for thermally aged EPR

                                                                                   -IIV'll _

SCRAPSillllaW!-

                                                                                     -_..,.,_,_~

Data~-~ l- .~:.;;:;. ..:c...:.*: __:::....:-

                                                                                                                                                            =

Began 1M1luat1Dn of new stock of vintage BIW

                                                                                     - _ln..,,,._CS..Ord2)
      ~ P R cable lnWlatlon and jacket                                             OITandOSCdlii_ _. . . ,         !   v

• I  :
• I

                                                                                                                                                                                                              ----- ~
                                                                                                                                                                                                     - - - - - ~ --.,.. ......
\ 115"" ~
                               ..... 1.1 R o b e r t ~ IOML)                           . tf'IS    (Diiiiiir,
                                                                                           .::-.::: - ~

Ulll5

              =

ce NOE of Cable and Cable Insulation Preliminary Conclusions from FDR and TDR Woltl

                                                                                '°  '

FDR Environmental Influences Pw,-*DMq ,lttd. . . ._ ~ . . . . . . ,. . . . . . . . . . . . fl/1flfl,.,. ...... _....

                                                                               -*-.  - ~*--
                                                                              ."°'---*-C

_ _...,,...,W,IRI.

                                                                              .FIFI                  -----
                                                                                                .."°'___QM.
                                                                                                                 -                 -~ .........
                                                                                                                                   * '!Wt bnndl Incllllt Mlllliod ,,.,,.._.

_ lth-

                                                                                                                                     ~---..., ---

cllllt

                                                                                                                                   * "-DOI._ ,

71 - - ~

  ~ .....ble ....                                                                 _... _.._
                                                                              .Ft,....,.,.                 ._., __   __..._.,....  *~.-.iln l(ll',
  ----              -~
                                °""      -"'            _      ___,        _  _~---

______......,_.,'IDR._ ____ ___ ,~~ ~ _,.__..-.,(R)lll_....., __.,._,..,..lloll_af_l ..,,_....,_..,_

                                                                               - *.. -TIii _ _.,.,_...,.
                                                                                                                    -----                                   ---,,..~--..**-*
                                                                                                                                                           ~_._.          .l ~ ~J

_ _ _ _.._..,_._ .,soft-* u Two Diffwlnt Cable FDR Comparisons Among Thfff Instruments Updated Cable Research Roadmap: Condltion

                                                                                                                    ~ -i:---      cable Aging and NDE Continued Work Through FY16
                                                                                                                                       -Zl Rapx-.n. ..,.._nat ldlnlcal-~ . Dr l9llldlrl--- (QIIY) oo.o,a,1- a__
                                                                                                                                                         , N...,.._
                                                                                                                                                                  ,--~-
                                                                                                                                  * ~--Ol- --1111 1-*_... I. .Rdcalllelont
                                                                                                                                     ~ . . . . . . . . . llldllllnlon.-e*PIN.lndORNI.

Slgrtn

   ....,IIIIIDl. .(ltlcMp,
                   )n*-laa:la n  1: lllf'.,...,,._..,..1-:--,"""....,.,Mi,
                                                                                                                                          -----*-*-Oll;T               iall.DIC-11.,i-*-
                                                                                                                                       - ~ - - -,...... , . ..CIN. _ _ _ . . . , _ _ ,.

nnd . . . ._ _ . Tllldlg __,..IIID Uld_ -*'-,..,tl&l Nannnla llld.-..dn lltum--F DA~INl* N/6~111 11--

   . . 111111 lnltnllln.                                                                                                            'nlilnldl., dllpllJCI I--

• PMa.,._a.A'IIIIOPIPlll*. . tCONEM 'nClllllolt, MC*. . lndOIMle

Concrete Tasks Status and Accompllahments Concrete Performance WP: LW-16OR040301 OO}ecflve: Asse.1s the safely and S8MOHbillty of Class / sa(efy concrel8 Concrete Performance, Tl.: Yann Le Pape nudNrat1ucllnSafrededbyell!all-dlca INCfk>tl Acc:ompfishments: Oeeign of Readiwe ConcNlle Mbc for the UTK ASR staff: Alain Gior1a &, Elena Tajuek> Rodriguez Research Highlights: Concrete NOE of Conc:nrte and Civil Structln99, TL: Dwight Clayton lrTadlated Concrete, TL: Tom Roueel and Yann Le Pape staff: Alaln Glorta, Igor Remec, & Elena Tajuelo Rodriguez

                                                                                                                                          - [lii.zl~-1
                                                                                                                                          ~ Junctil>n CO-Gold . . NC        ~-pn,milirQ----

M0t USA plarll (0.5 rnlles-fruft)ag,Md lO IIOle, mil<. _ _ ,___ h Rudy remalniflg ~ llflO aiat. Or>il()ing . . . - l O h l rrilr lO-the hydration Grizzly Conc:nlte lllodel Oevek>pinent. TL: Yann Le Pape MM (9110id Delay.d Etlrlngle - ) - -

• UA.

Slaff: Alain GIO!la ,ea, a Alkali-Silica Test AssNlbly with UT, TL: Yann La Pape UT Lead: Prof. Jon Ma, University of Tennessee l:~--/

~3

                                                                                                                                                                                                           ==.,

l.!!IRS~ * ~ Concrete Performance (Recently initiated) Concrete NOE WP: LW-16OR040303 Collection of ASR Data and Initial SAFT Analysis Data Accompanying Model of the UTK ASR Mockup > Objectlv"

                                                                            - Explore advanced signal processing Explicil modeling of the - I frame and all surfacalembedded structure techniql.sto impnMt deledio<l 9od Objectlv":                                                                     ide,ililicallon
                                                                            - ColtedlinMra,ray~dalafrOman lllkall-diCa rudloll specimen
                                                                            -Peifoon~~ofdata collacled from an abll-slliCII reaction specimen
                                                                        >~                      :
                                                                            - Collection of i s - anay ulnsonie da111 from four ASR specimens (lhifl)
                                                                            - Initial analysis of ASR dala using Synthetic Aport\119 FOQlling Tedmlque (SAFT)
                                                                            - Oevelopng of a quanlitatllle auessment of                                                                   $AFT,........,. ____ ____

damage

ce Deve lopin g a Quan titativ e Asse ssme nt of ASR Damaged Test Block s Need ID raler::t lhe dlference In signal W1J8S llllt can 11e-, from visual Irradia ted Concr ete Task WP: LW-160R040304

                                                                               ~          Tollllln ald .. lllCII r1radllllon Cll~P ft)Pllt ll * ....,.

UID h_.. ._...* .-V ..... . ._ I, __--,A.=--__;-~-=-~_&;- ..

                                                                                                                                                                        -,. -L_=--

lnadlrllell Conc me Aocol np..... ..tsa Wca tlons

                                                                                                                                                                         . . . . _ . ,_ _ A. _ _ .,, _ _ _ _             T.;L
                                                                                                                                                                                                                     -.i :-* ___-*~-=-n.
                                                                                                                                                                                                                            , o-T.
                                                                                                                                                                       ... =.=i:.:ti::=:-.:--.1=-
                                                                               > . .,....... .. ,.,. . . .kdl
   ~                                                                                                                               tofau11 *10,. . . . . . . . -
                                                                                                                                                                                                -0.=~=-==- .w.-=-*....:.-
 ; Needs ID be lndepet ldant of llgnel magnlule and lhe presence of.,..

ID.._. . . . . . ,1 £II 1 * - - *

• lfa Clwu:o lutluaA....... ... llWlll . . . . . .

                                                                                 ......     .                         irr....-..... _....lrnllllllll..,..
                                                                                                                                           .                                 --      1
                                                                                                                                                                                          --~=..--                           ~         --
                                                                                                                                                                                                                        -L.=L.--°i:..~:-*&;
                                                                                 ....... .... tor ...... ....

lags c;_,.. . . . . . . . . . . . NiiijiOl. . . . . ,._... 8-i on the varlablly In signal shape and ina.ec s 09Clllllon OWi' time l'lnllll...... l.,.,., .... 1,, ....... ...

                                                                                                                                .. . . . . ~c,wp /m.llt lol,

_.,.....,c.c,-.i.... ,.=-" .. """~

                                                                                                                                                                                                                         .,:.:. <<-!;- {, -:*.'T':$
                                                                                 ....,..                                                                                                         _..,....,. _., _., ..A....._         ,.....
                                                                                                                                                                      -. ..-_.,-__ _,____::r::::-*-

2. ........,L ;:--.,T.;..... IC.&'-- . . . . Y* CIW__,

which occura In damaged specinlns 1et1 *~----*l rnlfl2II ICGncn llt(ICIC l,.._c~l 1,1 lllw ..... Qmnly WOlti1g will lhe Hl>ert Transf0rm

                                                                                  - o.cr.1:a11111.-,,.,.Usllnly,"-~IIIMIIN,-..,,,.,..._

11Jdp clllllt,C 9'COJ ID....,_ ,.,.,_,.. .....,,,ff

                                                                 ............        ........                                                                               == -:;: ...~*::"i:..:.::-~----

p-..i,

                                            -~... ..._,. _
                                            ... -.........   ........             - CllflllallllDa . ., _ , _ , . . _ . . .. . . . . . . . . . . .
                                                                                  - OaMora bt*Cllld l TCMl:I IIHwnl )'IDw,, _,..,_,.

_ID..........., 1.

                                                                                                                                                                            ~~ ..:: =;- .:- --- - -
                                                                                ~~ ~                                                                                  ~, ~

lmdlat ed ConcretalConcreta Performance Pl~p Reque st UTK MR Mock up, WP= LW-1 80R0 403N UTK ASll llock up - Quic k Facts Cllil****------.-.ctef**--alal 1Jtllll a-SpNIMl na:3 _ _ _ ol100x8 0x-401

• llMde oelop lMnlt/ /lAIR. .,.._,_ ...._.._ _. ..... ncha.Z. ,_.,11(I ""')

                                                                                .n. .......       .i-......,                                                        l-ded rebar01 0': I canlned ASA, I.._.

ASR and I c:idlll. TOlal ol-31 -of __...o.ec1*1 S IMI,- , llllx181 1..-"-14 4boltoa nnedlan a. TOlalweighl

• V....... of_.... _....lll GltlZZ LY

                                                                                             .....,...,.,,_~

O..... ,.***** *a sll1110nliW-.1.g,T.i p la,..... ...,.. Eh*h ****" "C-. 52ftx24f tx 1211 (h) 100"F I ~ RH-a......,.-...- ........

• C ol INIIC4

                                                                                  ~ . , ,_ _ _ _ _ (1'J. _

I Ml1-81NIIT_,...._... 74.... ..,...< --)ICI I _ _ _..,. 24......,...... o,.i. -, _ _ _I) 1280J IO,._. ,_Onll ft81.1 111atn ln_. 4 Tollll , , _ ~ _ _ . . . . . . . . . . . .,..... ......, . ..... ill _ _) 1,,.... ......... _ OIINL.(llftral----~ ....... . ~ ** I I 1 ,---..... .., u...llyt//1_._

                                                                                  ....... .,.,... c....    ...... ..,

1*~.....--c--e,

                                                                                                  -.,_            ..c-- .--.,

llf._..... .._...._._,_,__,__,.,r.2' 111111\4 ** , _. .

                                                                               .,,_..UIIMfa
                                                                                  ~

_ . , . . , _ * .._llffl Nl!el 011hwN Dll

                                                                               ~- ~

GRIZZLY / Raven Concrete Model Developm ent, RIVE "-dllC4HI -Onlflr Model with Rawn

                                                                                                                                                                                                                     . . . . . . . , _ _ , . _ . , . . . . . . . . . AIIIR UTK ASR Mockup - Progress Report                                                  WP LW-16OR040305 I
 ~ -..... l l i d l l l r : ~ ~

SINllnmt: ..... llld~-nw. ,,,geo

• ..........,._m cdlclll0AI. ICM(T--..i Objectives: Develop constitutive model for Finite Element Analysis of Degrading Concrete Structures I' t

sacv..-....... &!Wl (RoclllO-,....._,....,., I: FY2011GoaJs:

 ---0,IO:Sdt_,... =~;~~~;:::::~~;:;:~:

Fillropllt . . . .. -, _ . . . . , D,l,Q(lolnft!IIU.of SC)

                                     * (----+-+-+ --+--+--+- -+--+-~

r

                                                                           ,_..I * ~ o f

• RadlallcMHn d~ Vol-"lc Elcpanalon (RIVE}

lh=l...-,}~,== lll-._-w--"6o =:~.....

                                                                                   ~ , M o d a l (ROM)            *mo RAVEN Modal OM ll1l< ASft lllocl<up Wllh curnnt ASR modal avallallla In GRIZZLY Accompllahm ants:
                                                                                                                                                              ~llodal:
                                                                                                                                                               ----RA

__-/---*MJ-* _ ~ ti - - -- X

                                    *- -.-,   1 * *
                                                                                 * ~ I l l a raducadordar modalwllll , . . _
                                                                                                                                                               - - { G , lIu um~ ~~-*-
                                                                                                                                                                                        - l-y/* - - -

• High Fluence RPV Task: ATR-2 Experime nt ATR-2 a:peri- -dtsiped 10 bridge p,evious lCSt , _ and surw!Uaa,oe claa for imipl OIi the dla:1S of OW< and 11-.c:c in many Various UCSB ATR-2 Spec:lmans Hava Been Packaged and Shipped to UCSB, LAMDA, Olllo\3-IIIIO ...-_IIO HFIR, and BNL

_ _ _ ....,_tl,7. _,lt _ _ _ _ _ T---ol -,- alloys wilb sysenatic variations ln composition.

                                                                                                                                                                 -trtl--.               ...-.T-          .--DC

_,_,...,UC88 ...,._ 111o_ .._ , ........ Ao,oo.,._IJIR _ 11 .. ue&a,-.. ..-

                                                                                      ...~----        --~  ..                   ~.~

r.o_.._Ao,oo _ _

                                                                                                                                                                                     ....  ,...._ ..... OIM.lM,l),\_,     ...

_ _ _ _ _ _ lltaOIIMd si,.-o ......111o _ ORNI.I*----- ----..--. . _.., ATR*I ,

                                                                                                                                                                 ...,....ucsa.

Research Hlghllghla: RtactOf Metals . 1..-CIISoed 0..ICID _ _ _ llllolOll,. ._lD_.....,. ._...,.,. ..ucse. j ,.~ C. NI ._ It

                                                                                                                                                                  -IIDol _ _ _

_.,. .NIVo-,----...---

                                                                                                                                                                                                   ,....11..,W-111~-----*
                                                                                                                                                                   --i-,1
                                                                                                                                                                   ).ffnpalllm-ol15        ....... _---.-

or...., _ _ UC88 _ _ _.., 05-"81oodlllM <t15,..__, 81111-* . .-..,_ l:llt1D-*IJCS............. - -.... _IIOOd-- __ ln addition to meuuhft8 mecbanlcal properties. a major focus is on Mn- ,_._loodll llMl:lltlo_ ll_l 1 . . .- , . - Y _ _ _ _ 11!.. Ni-Si plme Pftdpi!MeS tbal dnelop at bip Ouaia: usin3 a variely of IIICIQl-11io,ljlll2 01I.

                                                                                      --of-the-mt* mic:rosuucnanl cbaracteriDlion methods.

Progress - ATR-2 Data Compared to Predictions Summary of PIE Progress Multl.PurpoH Olaes lJHd to Obtain lllcro-hanlnesa Data to Alloy,T_ _ .._ , _ _ 290'C e.tlmate lmldletlon-fflduc:ed i n c - tn Yleld Str9nglh and Large lld polallueATR 2 dlll c:om.,.ed 10 4G, piediclions ~* plfflom micnJllrucblr aly~ dJecdw 11- Transition TemperaturN far Nine RNctor Surwlllanc:e llalariala model. TIie laqit IIIJ7 ID die Cu-ftee _., llld uplWina * > 6&10'9 ~ -

                                                                                                                                                                                                                                    . . . .*------*--1-..
                                                                                                                                                                                                      ---             0All.i..
                                                                                                                                                                                                                                                      . .,- . .-   , .-     ~-      _,          .. _ .CAil.

doe 10 MDNISI precipillla.

                                                                                                                                                                                                      .........lfll>fta.........           -,,             ..
                                                                 =.:.-
                                                                 -                 . =-.:.-
  ,-----,I
    .....,               [Z] -.                                I*

I*

                                                                                                                     .                                                                                ...-.          Aft* Altw1M.D c-- 511--- 21 t?l                                                                                                                                                            I I ___

• I * * * *

   ~:.: ......:. =       -,
      -                       e      o       I     f    t

• It t It t It I It I

                          . t 1-I 1*1               _""'_.......

11111 /~- U~-- M '( o

                                       *..._...,..,J.f" I     I     f

• t I

                                                                        ... I I t

• f I t I

                                                                                                                                                                                                   ~~

• t

                                                                           ~

Analytical Electron Microscopy of RPV Steel ATR-2: Surveillance samples Tew. -' -- 1 * -* -

                                         -*- -*-,,. . .. .-~ .. -...--..
                                                           ~
                                                                                                                                                                                                    ~-::-....::.-=.. _,__,-:.,- .----....,,.,..., r---;;:;;;:;;;;.:;:=::;-;~--,
                                                                                                                                                                    .. -~        ----
                                                                                                                                                                                   -cwr a-........_.1...,..-
--                               ..,. -~*- . ... -..-                                                                                                                                                    .........-....,_..... ....=..

0 - .1 ..,._... -a..-

 *---                                          n, M
                                                                                                                                  --y- ~*-*--__ -CZ>--

VC.- LWrlMW.W ,.. ... , -*twl"CI

                                                                                                                                                                                                         =--=-==--=
                                                                                                                                                                             -:f.:!;~=~
  --                             ~
                                                          "                                                                                                         '"'"     -(ZJ-°"""
                                                                                                                                                                                          ~
 --~--                           . . - ..      ,.                -                                   -. -.                                             -....... -* _.,_
                                                                                                                                                                            ~ ... - - -...,n-T81.IM-*-IIH18 .llalo
                                                                                                                                  --....,., ---------"- 'Cl,*-*                                     Mt-SI.....,..,.
                                                                                                                                                                                                                                            --pt-EDI _ _ _ IIONI-
                                                                                                                                                                             -s.us.u>S*
                                                                                                                                  =-:*-

i . . .......... I

                                                                                                                                                                            -1J1w.lM.m*
                                                                                                                                                                                                .~

i..a . .

                                                                                                                                                                                                                                            ==

High Fluence Effects on RPV: Summary of ATR-2 Work Recent Highlights on Stress Corrosion Crack Processes Controlling sec Initiation In ATR-2 is providing a IJQsis rcr iwessing RPV embriUlcmenc .,_ extended plant lire.

                                                                                                   ~---.....

Initiation Research at PNNL

                                                                                         , "'-C......,SCC:lllllalJMloAloylOI
                                                                                                   -------lo~SCC-io...,IUD~loPWR                _,,_       ___ _ -~--lnJ......,

As-Received and Cold-Worked Alloy 600 Materials

                                                                                                                                                                               , SCC _ _

_..o1-,-/n With 1.625 lndivldual spedmem comistina of 172 dlfTettm s1eel alloys, *~~~,-.rp11n..._--c.,t0~ ..... ATR-2 bridges worldwide dalabases for a Mcie range of"""* ftuellCC, ..- __.

                                                                                                   ~-lood---...-.-.._.,___.,._ -------

upllln _ _ ...,....,..__ ...,....., .......... _ temperature and cornpositioa. The lniaal results of a very ag,asive PIE program are io aemlllC:llt witll

                                                                                                   - - . , - - ~ * - - -. .. . - 1 o s c c - . . i
                                                                                                   -,600.                                                                        '°"  _

0 3-4 _ _ _ _,,

                                                                                                                                                                                 -,0--,CC--
                                                                                         ,     ,.,..._C.....,SCC-lt~Mo,IICI previous pllysical models. sbuwina formation of "lat# bloomi*1* M1>-N'..Si pbues. that are not treated ill curren1 n:gulatory models.

ATR-2 will abo provide: (a) verifiallioll of the Master Curve metbod; (b) malerial for a post inadiatioll annealing dalab8se for embrilllement remediation; and, (c) developing of a new class of blah Ni (low Mn) adnnced , c1..-,-,-ln._,.,_..,l90. Alllgll-,al--ca,-- cnct--SCC-0...,-_.,doponclooolle....c l d l - . . i h

                                                                                                   -... ,.._.____ ....... __ . . _.,6CC_Tht ColallcnllooAdtllllos                                                             ------

• a-c nmwn*"'"'""'..,....,

aacb,....Clfllal ...... , . . . . ......

                                                                                                                                                                              , 1 1 , e _ ( D_ _ , , _

RPV alloys (Rolls Royce malerials). pdaay-**~""'1tlll0hlll_, _ _ _ ...,_lo12- loall<*-.. ,......_

• The oVffllJ ATR-2 ~ - involves an lnttl'IIAlioiial fuiidiiig CiiiisOi'liulii lobcnlci1k w..i.dwwwdliiuiooliid-SCCilililonliilv*llliiieiiiiililodilPIINl

                                                                                                                                                                                 .-.-                     /(
                                                                                                                                                                               , llracllf#/ISCC,,.,....,,occv,a, wfNln*

(DOE-LWRS. KAPL Rolls Royce. CREIPI). .-scc _ _ .._ _ _.,EPRl,NAClndRolo~ _sec_.....,,,

                                                                                                                                                                                 ,., _ _.,.__/CW/            1111 1<*

Processes Controlling sec Initiation in CW Alloy 690 , Cna nudaallon 11115 been obslM!d dl.r1ng Jang-lenn anlilll load and bllllt nolcll leSIS on 31% cdd-WOIQd ""'1 890 In 360"C PWR PffllaY __,, EitlansMt (1181n bculdary ca,,ty lormallon ocan and can act as l)l'IQIISQrlo ctadl lnGallon.

                  --~scci-.

Ongoing sec Initiation Reaearch Activities at PNNL

                                                                                         ,.. -~SCC-f/lAloyfOO
                                                                                                 , SCCWlllloli_ca.......,,,_,.._COll..-,land _ _ _ an_
                                                                                                   .....,...,800iNl5lgllllg lltilleclsdafllllld-.
                                                                                                 , ~w1i.g1,1r1111GC-EACMNfrVlnOnarda ......lll)Oll(Mll*be c:omplelldn......,lnJoN2016.

High Fluence IASCC: Goals and Recent Accomplishments

                                                                                                                                                                                -- -,i,,o.~n1;111 ....            -o1w;cc.--

_____OQ..,.__,III_ID-._,.,__.__ol_

n. -,a111e1ASCCCGR~IIJHWC,,,,,.--i_ ..... _ _

___,.,_,..__ _ cnlASCC(,.ol*--*

                         ,. NewnlSUlls rr,ealisolalatl, cisa811 gtlin bcundalyc:aviles
                                                                                                                                                      ,.._COll!IIIMldcn-           - - - - - - ~ - -. . . ..,_._lnlA9CC--,lliltJ.
                                                                                         , -~         SiC     C    -_l /d l~_ N  _l,   ti l f_l 9_  0 In selac:lld 21,. ~ specimens aftllr 10,000 h                          D       la   d                      _
                                                                                                   -nalellond...-load-~ _,.....,...c:a,lly___,,
                                                                                               ~-

a,;,osinswlllcutcradtnucleallon. Thehlgherdenslyof c8'lllias found on and - l i e SUlface nllcale a_,. lllal -cac:ti-.SCC~antlshorlcrll:i~-p~~* **er-a-mur:111anger e,qm,ns may 8IIO lead 10 sec Initiation. l i e ~. lalsllnnSCC~-*-cn-,,,,,690.-. *--- CMS<

                                                                                         ...       ~ . . . , . . . , .. unor.yan.,,&90111dN-30C-tNyaloys~t,e i!lllnlds,afn-,()depriollbelolr~lmsancrackru:toalianllldgrDIIIIII.

_ _ ..,scc _ _ _ _...,an11tEPRIIGE*n DOEOlbd-&letgJSdolas

                                                                                                                                                                                  ......... ~------
                                                                                                                                                                                                                                              -*CAB
                                                                                                   *i.por1onneo1ont,er..Ao,co- os.,.io111tSCC-Aountl ~               SjJldal                                                              * , - , ... CMS
                                                                                                   ~allGC-EAC. EPIUandRallsRo,ce
                                                                                                   ~dSCC IN!lllionllSl.,_.delll,llnclutq_lodlg.._,,.,,...Si..ce pl-.lor . . ~laradlllil. B'Rlllldll!C JtllfltS, ( i ) ~                                 ** .._ , ..... ____............                                    O..f!A.................tcnJ ...

0

Ce Mechanism of IASCC OlljldM :~rwad laacnd llllallar lllldcnd l.-,id.--

  ~dllll, lsublll t. .111-- ..LW R*--- ~--.... .
  . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Clllllllllona (IASCC).

i - . . ,. . . . . .....

                                                                                 .:tl!g IASCC wortl It U. of Michigan

• Tiil bil-poial beDd -apabill ly

                                                                                                  .......t.,lholMl~
                                                                                                  ~IOpco ,,idea.ii caed fllcilicy fordleLWl tSpr011a1 .
                                                                                                                                         ... =----:...-:.::::.......,

I IASCC wor1l at U. of Michigan lllllra .aol.- d..-yC 111c ra.-i* *-~--- 41dltba ld-CGR._ . . . .___,111 qpra:bll ll--olmc ddra111 11318,p ll

• 111.e& n.,....... .,_olthe I: 1111.,._.CIWVl._,..__.~(IMC)ID~--

  *Til0palil l. . . . . .CIIICWJ1 &*                                                              IM2 ~ fooll'p,iatbend lall OD                          l II.-****,.,..
    . .condilla lM.-C_ID _.,                                                                                                                                                    clla!My(HWC)i.11111.......-illld .. CGRlladn)ppldbylllcM_,

ill._111d Ill

                                                                                                  ...........S l04LSS -priw'lll ed

(:

• _ . yr1 ~;~. Clldnol ......

                                                                                                                                                                                                                                           - :.1I 11 CGR .....Clll l l l ~ - - -                                                                             11P 111d NWC

• 21,..

        ~_,.

MI llalCII,

             ...m...--.. _

I lll"C.1 1..iawe ~widi

                                                                                                  -.a-me -alloym amore                                                          __.

TlllngN t-on

                                ..._                                                                                  .ic11..- : ,. .J~f
                                                  ......,.....,_.......~-.-~-___.                                                                                   ::::*

cold womd- , 304l~ ...... (41D47

                                                                                                                                                                                -.BOMO.--

ad. conllcleDce ID die lllilil),., pndicl

• lillld ~era --,_

1tn:111olK**_,.,.

                                                                                                  -,pie main b y - - . bond defleaiOD..

• f * >>
• D
• M * ....

lnlllald). ....... . . . I

                                                                                                                                                                                                                                                      ~I

_ ....,1,ts s._i.1o m-c,--. Twinning In commercial and model alloys deformed In Locallnd corro1ion Is a non-random pn,cess In the specimens high-temperature water* understanding mechanisms Plntic: strain and stress conoslon cracks dlfonnl dhiglHl rnplrllu n--

                                * £a1y dtfofmatlon         ._,.._abserwd
                                   .,.. deformed In hfllM,llnpe,11Ure -

In 304l

• Round COfflplCt t e n s i o n ~ (RCT) -

                                                                                                                                                                                                            .,,....ble for sewiral 304-based model alloyl.
                                                                                      *I -

strain 18te. Twins Inside dlslocaliarl dllnnlll may The end: powth tests were conducled uncl<< pramoe.- locallDll anandaad llna, wel<Dl,ll'Olled environm ent paramete rs and

• _,.,,, _ , e,,plored In 304l-1111Nd model alloy:

stres.s Intensity factor.

  ----*                            304l+ 2"Mo + 11'Hf(II Wllrsad dnaflkllt -

• I t - lmportant 10 "lrwatlp---11..1 pllildclll- .ln

  --~~-                            ~IDord llayJCM }.                                                                                                                                                        mat.nls,n s ac:111'1 durlnacnclt poplpllo ...
 ;rtM iiiii i~,

t.=.:  :.._. .~,

• Malhods: SEM/AalEBSD, TtM, Finite Element

,io'9-. __,_....=_,

             ..lldli-'a,;,.
.......,,_dallla..,.*. ..-,...i-
                           ~

• o.lde~at thelUffa ctand,-s u,faca_, obNrvad ....,.SEM on deformld aus1efl ftlelloy ~ ID NaMemllel'lbn -

and~ Anllysls (FEA). i::-~& ,r *~

~
                    -~~\)-~ -~                                                                                          ............................
                                                                                                                       !i* ~-w*1l& f.1t .~
                                                                                                                        ....... ....... .. _ . ......o1.. :.
                                                                                                                        -at.-;~                ~~:                                                         c-~=-1. :~.*        - ~ ~:
                                                                                                                                                                                                            ~ - - -Tlllll lldlhoft he~ ' *
                                                                                                                                                                                                           'f!tteldlcnck....                                 .

EBSD analysis of plastic strain around the ,tress corrosion cr.1ck Environmentally Assisted Fatigue

                                                                        °"'"'~" O..s!,,p-*-J<-ro,'-'ig>ttift-""9'ft-*~                                                                      :::;;::-a,..:;;::.::!""'"'"              W1oy - * -           _ __

Few Eu111plc,i on Recent Mechanistic Modeling Activilie1

                                                                                                                                                                                                                                                   *-P"W"'"" lolltnrioosf

=--*'",........_ __...._..._.,_.........,.

                                                                                                                                                                                                                                                                          ~

Plas1lc strain distribution was

                                                                        .Mnort .,npniatnnt tntcta**_,.. .....W. '"1'Pff1io., 1..,. dll. . ..,_, ,.llpiDS,
                                                                                                                                                                                             ~
                                                                                                                                                                                             .,..,... .............. miJlla:
                                                                                                                                                                                                                                      ..._.................-,-.a_~-,---~
                                                                                                                                                                                                                                               --~ ~---'-

1-..y--cs-;,j".;;;;;;.*..,;;.,;;;;--,...-.., . . . - _..,.. _______

                                                                        .. w;*--....,.

found to be strongly ,.,...__,,,___ _., ~ lnhomoge11e0us. _.,_,,.,.,. *._...,..,,_G,._O<fool.

• Tian IH~ . , . _ MIiii'
• tatter c:oetJIOIICM _..,. .-di bde- 1N ,.W stra1 _ ,

                                                                                                                                                                                                                                   -            n                       ,,..... .....,,.,

• In ttle crack vicinity (<20-30

                                        µm), many sralns -re
                                                                        ,.....,                                                                                                                                                                ._.,_~-"'-...          , _ _-,..-.n-..,.l tll !ll -

• practlcally stral~free. some grains expenenc:ecl strong _ . ................. -.wi 1-lcnow.,...

plas1lc strain. W...111

                                                                                                                                         . .LWIIS
                                                                                                                                            , . _...,._ . IOklp;.

_.... nprd T

• Plastic strain m.., reflect the nature of grain boundaries J\dottne~N\"..-...rDt ..

                                                                                                                                                                              .,llllilli£ meter             t....,   C . IIIC8Klll4 11 passed by aack; most likely, more resistant boundaries led                                                                   - - -........... - - o f to larger strain In the crack-adjacent grains.

whr:..., ............................................. A:d,,'.*-- ........

                                                                                                                                  - '---~~~-------

OWWlp ........ 9D ---- lomol--1td,ocnd, odlo-Tho....,.__,....,_lAM ~'!!:'~~--- ........ Examples movie (wilh magnificallon faclor S) s howing ru~or displaccmenl and slfl'S!l under load following mode

                                                                         -...-~--......-

__ ,..._LAS__

                                                                          .,,.-oe .......

Few Examplu on Recenl Experimental ActivitieJ

                                                                                                   ~

A t -.. . ~ - . _ . . ,

                                                                                                                                                                                                ~

Cast Austenitic Stainless Steels Aging

                                                                                                                                                                                                    ""'d... _,,_..,        ..     ..............

_ _ (CASS) -"" ..-- w.,,.-.............. - ~ .. ..,..._f..

                                                                                 .........,................... ...,                                                                             *n  _.,LWRl...,.                ___111_,..,.,....,._
                                                                                                                                                                                                           . - p d . . _..,*.,J11119-..-lor                       .. ,_.,dCASS
                                                                               ......,ftflln

(

                                                                               ,*.......,~--Nld .............-.tc;M d'J,.:t . . . . .
                                                                                         ..............rf'Mlb,...........,

w., __ _,..,.....-.-

                                                                               ..... fnldlk: ...........
                                                                                                               ~

l'etf .,_.,~_,_. . . . . . . . . ~..

                                                                                                                                                          ~ -a rw..,......,.w..ti A~(Q2J:

• a,,,p,11,-t ..... andm,llqn ............. lgrPPttAMl!EPBICASJillDICF3-

                                                                                                                                                                                                    ~cast.CfklaicCISI.Cflll~cal.CFaka.._.:aQ_....-,S.
                                                                                                                                                                                                * ~-lor4madllt.\SS 11o,s (Cfl. a3M. Cf8, andCF8Mland 2~11-,s (3041.and316Urwl!d11JOOIIN-'"',vl4.201e.
                                                                               !k,._.,..,....,..

niaillllN...,.. ____ .. -..irnti.6',.......,.,..

                                                                                                             .........,_.......,.....                                                               A/lllf'llld_lor _ _ _ _ _ eglngllal-~T.S. e,....Y. ~.N.R
                                                                               . . . . . . U..tt<l<<&Wl Tin....,_C)dlnllJ~---y-.,.

t.....-.tal........, Oillman.J.T. Bullll; ._AQiv..,_ilCGOUplorSI.-..Sllolr.'Jcunald

                                                                                                                                                                                                    ,.._, 88(2) I 211181507-61&.
                                                                                                                                                                                                    --------granllllandllnd.

• E!?!!MIPPflllRIRI: ra)Tht I-NERlpn,jll:lwillS. KcrN_,Slldy...,..'8inllelllcllln

                                                                               ----......._____........-~~----... .........
                                                                               --.----1rill!r
                                                                               .. n~...a..r-~____... ...........

nit ....., . . . . . . ~ . ~. . . . .

                                                                                ......... ~ ..,,,,,...............111'\ ....................... , , . . . . . . . . . . . ~

(b)ThtNSIJF PftlCIOlll .. wdy S)NIVisitEffeclld~"4fil!land...,_mdilllon_llblilld(Ftllruary21116).

ce

   ---                                    ----..-.e--
              ._... ...__ _ _ _-I CIEPRI la PftNl,:led 4 CASS
                                                                               ~~

Cast Austenltlc Stalnlen Steels Aging

                                          -*IPOl*lll l.~-~ao-1

• Z9C)..400'C.

a.Oldlltwlllltra naliona.....

• it P I fJMrMP"" """_.....,... ,.API-W3& 1MA11P

                                                                                &'181111. . ........ _...,CASS.,_lt_.._, .... **--""'"*--
                                         . . . .,,, . . Cllerpyln-.-:t
                                          ,._ oA IIClfHllll8d EPRl alo\'l-                       .,_ ld...,clillllulDilal..........,_                                                   R. . .rch Hlgtlllghla: Modeling and Simulation

• en en..-.--- .., parfonned.

                                                *-*-~-ave b.Among ,-4 EPRI lloys 1118 a'3        * ,,___llrf fllfM_II_ IMPI*: P t.llllof_....... ...,.,1:1.dw I
                                                                              , .t.         _ , . . .- -........._....ofCASS.... .,_fCFl.

I 111.-<DII. o. USE oA-340.J - ,-1owe11 CFl.a::IM.alaa.1*""' 2IOlll<<IO'Cllr1.!001-*lil~ln D8'TT "'aboul -200'C. Ap;l 111811Uf:11BMAZ1S2~ C. The Mo-<ianlar.,g...., (CF8M) h a ~ hjfl 08TT. -

• I

                                                                                ........_,, I 21 I     *'--CA&l*2_,.....,....,10,000_,_

I dwa11iluloA*t11....._ ti.,g.,..a..g.i c:at

d. The lllalball CR l l l o y -

                        -..... --         lW ~ OBTTa. -71 *c Thermodynamic Tools for Evaluation of Radiation-                                                                                                                                         Valldalion of thermal stability of l 12 phae pr9Cllctad by the P segregation at the grain boundary of a.fe (I)

Induced Effects OCTANT daabaN

• lnc:rNNd Scope fnlffl Hlgb FY15 Canyowr Objedlv.

  ~alN!IIIII IOIIQllan modlllal~ ---Cll llepnbounilay                                                                                        i 1r111in~* nllllanlrda dllgllglllan......
  °"""; *-'~~1 0m111 r.-....1 q----                                                                                                          J
  ....,alCIIIAul llnlcsa.'IIIIIS IIIII                                                                                                       *:I-             .. .....,.~

Al:con\jP t I *1

  ....,_.,.,._.._....111.,....-.-..,...-..

TIL:AA, ulcaldlilnllcil iOilllsbP..,_. . . . . . . lna.fe'-t.ll

                                                                            =~-::--....,:!::,.-:: :,-=-:,::::::.;=::.                                          -- *::*
                                                                                                                                                  ..i,..~~a;=,_.,._,. , _. ,_,. _,. __~
                                                                                                                                                                                         --~
                                                                                                                                                                                         -A-
                                                                                                                                                                                             *oa: _ _ _ ,,,
                                                                                                                                                                                         ~----OCl'Mf ..... ..      __
                                                                           -. ...............                                                                                            --*oc            c-I

___,,_,......,................ ---=-

                                                                                                                                                                                         ~--

la..ut,.aaica.,._ ,.lqlllbaldGn ln llolnlsy~Tll illllon(OBS T) Ill ............ w ............. taxy. l'Ndlclldlwm illlllllllydl1Ul ,Slh').....,._, _....,._..,,a... .............. q ............... ............... ............~. .,..............

  ~avttrnM1 11_...._...- .i....._1100 0C11*111 0"q.                                                                                  ---.                               ,.....

a'Q . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ., ................. um . _ ,

Multi-scale Modeling of Radiation Induced Predictions of Cu-MnNISi Precipitation Models Validation of Cu-MnNiSI Precipitation Models .-----*OMlop.calboll-~o,o.llioo-

         - . ~~ln--

Precipitation in Reactor Pressure Vessel Steels Ouste<l>/Mmlcs*...,_MnNISl...,..(noCul KMC*Anneoled--,.(ooCul _ . . . . , . _ , ** ltodi,g_ .. _ .. _ _

                                                                                                                                                        #    _r----,.,-=...,.,.,,,
  -(RPY)-IDpdi _ _ _ RPY _ _ _
  ~-~                                                                                                                                                   i: k ~

LW R _. ._

  ----Collotl(MC)_..._....,.....,..                                                                                                                     1::: ~      .. .
  ...lalJ.._ _ _ Wo _ _ _ _ _ , , _

____ __ .. I

                                        ,,._.. ..      _  ..                                                                                                      o       20
                                                                                                                                                                   .w-.i-c-,

• eo A srnaU compos,ODn dHferen<< ct.>Mment

_ _ ln_ClD"C! _ _ _ tudl,..,.ID With local MteropMrtv u,n ~ tl!r'te

                                                                                                                                                                                                     --~-w.UCSB+__. . .,. . .,.__
                                                                                                                                            ,.,, modals " -gogd loUClllllt ~ ...
          *--ID-I0-.0
                                              . . . . . ...... --a.-111
                                                                    ............. Nl,flllll\.iilMI                                                                                                  difference M pr<<.ft;lle volume fnimon, e,iperimlnllldlla.

o,.._ ............... F- . -

                         .. ..                                <I                                                                            Cluster dynamcs model can be used lo8Xl)IOte eml)rilllen1enl vs. temparalU!8. h. l\.lence. and a,mposan E-,dl<IICID _ _ _ ID _ _ _ _ _ _ _

KMC model can be used loexplar& amslic scale s (e)llaaa-:

                           *- ~ ~ .............-. ,....
                                                        ..........--..~t......*.~ --,__
                     .,,;;,a;;;.; ,. .,. ._ ~ - ..................      ~
                                                                                                                 ..........~,..

OJ UI U U U Clla,ges In predpitale Cllffll)OSiliOn and swelln.

                                                                                                                                            ~      ..,.,.,...,..,.,,,,.,.a.-.,,...... uaa.
                                                                                                                                                                                               \!fllS..,~
                                                                                                                                                                                                 *e.i,to,9. . . . . . . . . . -
                                                                                                                                                                                                             =
                                                                                                                                                                                                                                       ...- ~ - - . -

Mitigation Technology: Advanced Weld Repair ___ Mitigation __,,__ Technology: __ _ _ __, _ _tor-.,- Advanced Weld Repair

                                                                                                    -~--

A Co. . . I _ , _ .,,.,,,, OOE urrtatLWRS tlltd EPRJ undllrl.anO 1lrDt CJpe,'111icwt

                                                                                                    ~

_,,,........,..,._,._  :,c,.:.~~=:=--------

                                                                                                                                                                                                 =--=~~":-".::'.=::::.*:="8~-=~-=

Research Highlights: Mitigation Strategies _ -cr-.i

                                                                                                      ~-~

onlnlllllald..,._ OANI. _ _ _ _ ., _ _ _ _ _ a d n g _

                                                                                                                                                                                                 ~<oou=.,-=:.=..,y-=:i::%~=-:=".::,::.::-.,~

r.....,...,.......,

                                                                                                                                                                                                                   -~-- i ----~
                                                                                                                                                                                                                                                                    ==-==

___ II.,......_ 3~ ~

                                                                                                                        ....,.._                                                                                                 }.;,:                          - TZ-
                                                                                                                                                                                                                                                               ~

EPAI_,~ ~ - - - * ~-~r_.;:; lllllS (i)liilliiY ta,PIE _ _ _ _ ,

                                                                                                                                                                                                                                            - -~
                                                                                                                                                                                                                                           -~..       --   ----* - .....

CIOl'ldllanland~-- pniceD.....,. PWl0rm IIMlu ~ IOwldllll9fflOdlllnQI

            =

ce =.,~. :..~* __ Mltlptlo n Tect*--.o loarl Advanc ed Weld Repair .............._ a

       ...,..... .+....:t:.:..:r..,- ..,
                                     .=----"

Advanced Replacement Alloys and Fabrtc:atlon Techniques

                                                                 ~DMla!l_..._ ___

d..,.._. _.llr*lnUM l_.,.MIIIIJ p,v,ldt ARM: Recent Progrna

                                                                                                                                         ....,,, .,..........,..,IISO"C i..ad-..d1J IXJ*on._.,   ._ _
                                                                                                                                                                                                ..-- - ----- -~

--** *-...*CIIINL--~---"1111 ~,~~--=-=--==.::".:..-.. =-=- --::. ..... _ __ l1'1._ ....... ,...,...,...,.5__,...,_ -

• 1~~

                                                                 --~--    ---
                                                                 ..,_.,MII--
                                                                    <--. _ _ _ _. _ _ . , . . _                                           - lllo _ _ _. , . . . _
                                                                                                                                             -*--~ to..M JII                                      .           - -

• 4-..:...;;...;.._ ~-

x ____..,.nt*____

                                                                                                                                                                                                                         -       --l
                                                                                                                                             - -. . *te...lfflf1l .

I:

*-     -            -      =-=="--:                              ..__.. __ _

(IASCC)c I t * *Olllllllla n~ llll._..,.,.

                                                                                                                                          , , _...... ___     ...(CERT)_
                                                                    -......____cen.-__--_~.,

pni11,,,11*. . . . , . , . . . .. . . . . . . PWR-

                       *   *   -*   -* - *   *

• I ltlllJ

__ _ _ a.,, ___ ,,_ ~

• pl(INry . . . ll'ld IIWR-ftOllllll.._,dlerill'y C1111111n p-. dlll:tllgllll.

                                                                                                                                          -"-,.____..,a
                                                                                                                                          - _ _ lar,.,,125
                                                                 -\1115-Zion Materia ls HanMS tlng Tak                                        Rationale and Goal of RPV Harvesting

__..,.,....d_.,...._,* .....,..,_..... _, -~USIMl_,.Alair,_._..~

                                                                 .......... .....__llr.. DCEIJl'8,.._ EWl.1111 . .U.S.IR:.llaa . .
                                                                 . . . . . . . . 21111\N 1&2 IIIIIIINwo I

ldad.,._.,.._...,......,._.,.Zlon_,,.._IINlel 6.

                                                                                                                                          -  ~
                                                                                                                                        ...,.- ~_.           ...........

d . .Rf'Yltnota._ ,.. I 1"?1/_...II..._..,..,,__ ReHlrch Hlghllghta: Harvesting Efforts

                                                                      ~---                                                                     - ..._1a: ,___..,..II JM.IIW8- 111~bol.llll ......b ......
                                                                                               ~o..a-2 115
                                                                      ..... 111: . . . . . . .~ ..........,e.g, ~ ..... ~
                                                                      ~~*aev-.1--.                   C...-*.,... ..Zlonon ~J1, zt1,
                                                                                                                                         -WF-1

_,.d.........

• T I . . . . . . . . . . . . !011'1'....

                                                                                                                                         * , . . _ _ , _ _ .._ _ _ . . . . . . . 11111
                                                                                                                                          .,_.,0~----,
                                                                                                                                               ... -111n-,,..---- ~-

Mldlanea,,__ .,E-4lualoi,, ~

                                                                                                                                                                                                                                 ~

0Mlaplnall6 '.-.~ S . . ,llldllmql

                                                                      ,...,,....,.____....._~........
                                                                      .....:a.:Alalhlll . . . . ..__ ...lff_ ._,,..,2,21 1,
                                                                      ...... c... ..,.....,Qll7............___ _                      Wll~Sb ly al Wlldl..,S ..-
                                                                                                                                                                                         ~
                                                                                                                                                                                           ~...............

rw:J -* - . - --

(b)(4)

SUMMARY

OF REVISED MACHINING PLAN :

,  S11mmarJ of._,.      ID be Ndllned from one "C' -(bose melal) 239

• K17x15)-16) 01arpy _ , , .

128 * (16

• 81 SS3 lll'lsile specimens Zion Cable Harvesting lftdld-~---

                                                                              -llanUn11bw*-. . . .
                                                                                                      ....   -ln-ailh
                                                                                                                                     .. NRC.,holo..-and 64 *(2 *2* 16) CIJUll00l(formiclosl'dlr,ldwa.llndolo)
, Sunwnafy ol--lDlltl'IIOChinodllanont-0:--t,,old)
                                                                                 ---~-- *-

180*f20*91 C"-l>f-,s ,, Sllu: <:andllplaotlo-Zialtl.loll2- C 3 1 1 ' . . - i 1 t - * . . NAC~ 144

• f9*2*8)SS311nSiolJ)ldrNr-.

n =12,2,18)coo,i,ons f1o<- -> ...,._ ludP'IJllllll\ ...Clllilfldlolly....,..,_,...,._,.,,,..,,_,-.,..,.....)lollt

                                                                              -.-1,yu.,12.2016
                                                                               -~-c:-.----                         ....

80*(10a 8j UT C(l) Simnaryol--lDbtmacllilodflcm 2"1'"-(baselll!lai): 112 = 56f4* 14) 0.5T C(T)a 2"1'"-

• s-nar,o1...,,.1D11t-"7~

                                                                               --11--..-i.--ffl'
                                                                                 --lo--ll.                       Ala ...... Cllllo ........-*-*1r*
        ~f64--

0wpy spOlinens (239 base metal

• 180 Midi
• 419 SS3_. , . . . .1128-melll
• 144wlld)*2n

                                    +n- i*138 Frat1n.,..,._ (112 0.5T C(l) ba!e mel.ll

• 800.4T C(l) weld)
• 192 y

Note to requester: The attachment is withheld in full under FOIA Exemption 4, to protect proprietary information of Westinghouse. From: Hiser, Matthew Sent: Mon, 13 Nov 2017 06 :55:36 -0500 To: Audrain, Margaret;Purtscher, Patrick

Subject:

FW: Table of available information Attachments: Table of available on baffle bolts .docx FYI - from our discussion with INL Thursday regarding baffle bolts. From: Jackson, John Howard [2] Sent: Thursday, November 09, 2017 5:06 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov> Cc: Simon Martin Pimblott <simon.pimblott@inl.gov>

Subject:

[External_Sender) Table of available information

Matt, Per our earlier conversation. See the attached table with the assessment of available information on the 347/316 SS baffle bolts (compiled by Frank Gift at Westinghouse).

-John JOHN H. JACKSON, Ph.D. GAIN Technical Interface/NSUF Industry Program Lead Idaho National Laboratory P.O. Box 1625 Idaho Falls, ID. 83415-3870 Voice: 208-526-0293 Fax: 208-526-4822 john.jackson@inl.gov

(b)(4) (b)(4) Note to requester: Portions of this record are redacted under FO IA Exemption B5, Deliberative Process Privilege. From: Hiser, Matthew Sent: Fri, 27 Jul 2018 18:49:33 +0000 To: Purtscher, Patrick;Audrain, Margaret

Subject:

RE: RE: revision of report Hi Pat, Did Pradeep ever send you the revised report? It'd be good to align on it next week in case I am able to meet with Pradeep the following week while I'm at PNNL... Thanks! Matt From: Hiser, Matthew Sent: Thursday, June 28, 2018 1:47 PM To: Purtscher, Patrick <Patrick.1Purtscher@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>

Subject:

RE: RE: revision of report OK, thanks Pat! Thanks! (b )(5)\ Matt From: Purtscher, Patrick Sent: Thursday, June 28, 2018 1:46 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Audrain, M argaret <Margaret.Audrain@nrc.gov>

Subject:

RE: RE: revision of report (b)(5) (b)(5) ::I::::::::::::::::~~~~~~~~~::::::::::::::::::::::,...H_e_e_x_p_e-ct_e_d_t_o_h_a_v_e-th- e- re-v-is_e_d_J document to us July 9. Regarding the inventory, for the unirradiated ex-plant materials, there is an existing inventory that they did for Care Nove. For irradiated materials, there is no inventory of ex-plant materials, but he expects that most are dissimilar welds from vessel heads. Pat From: Hiser, Matthew Sent: Thursday, June 28, 2018 1:36 PM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Audrain, Margaret <Margaret.Audrain@n rc.gov>

Subject:

RE: RE: revision of report (b)(5) I understand that sentiment of doing a mod for a relatively small action, (b)(5)

Thanks! Matt From: Purtscher, Patrick Sent: Thursday, June 28, 2018 12:20 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>

Subject:

RE: RE: revision of report Pat From: Hiser, Matthew Sent: Thursday, June 28, 2018 11:04 AM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

RE: RE: revision of report Hey Pat, (b)(5) Did you him talk to Steve yesterday!_ _ _ _ _ _ _ _ _ _ _ _ _____,!should I catch up with today? Thanks! Matt From: Audrain, Margaret Sent: Wednesday, June 27, 2011.8 10:27 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov> Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: RE: revision of report Yeah, the hard date for all mods to be completely done is Aug. All of my mods were to the labs a couple weeks ago.

---

Original Message --------

From: "Hiser, Matthew" <Matthew.Hiser@nrc.gov> Date: Wed, June 27, 2018 10:24 AM -0400 To: "Purtscher, Patrick" <Patrick.Purtscher@nrc.gov> CC: "Audrain, Margaret" <Margaret.Audrain@nrc.gov>, "Tregoning, Robert" <Robert. Tregoning@nrc.gov>

Subject:

RE: RE: revision of report Hi Pat,

OK, I'm working from home today. Do you want to talk to Steve? We really need to get something into STAQS ASAP if we' re going to do it... I can go with you to talk to him tomorrow morning as well. .. Thanks! Matt From: Purtscher, Patrick Sent: Wednesday, June 27, 20:11.8 10:20 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov> Cc: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Tregon ing, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: RE: revision of report (b)(5) Pat From: Hiser, Matthew Sent: Wednesday, June 27, 20:11.8 10:17 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov> Cc: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: RE: revision of report I ____________. . , Thanks Pat! What about the funding piece? ... Thanks! Matt From: Purtscher, Patrick Sent: Wednesday, June 27, 20:11.8 10:05 AM To: Hiser, Matthew <M atthew. Hiser@nrc.gov> Cc: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE : RE : revision of report All , Pradeep expects to have the revised document to us by the Monday after the 4 th of July. He now thinks he may be at PNNL when Meg visits. An inventory of unirradiated ex-plant materials is available from previous NRG work. Some irradiated vessel head material does exist in hot cells, but is not included yet in any inventory. Pat

From: Purtscher, Patrick Sent: Monday, June 25, 2018 10:09 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Subject:

FW: RE: revision of report This is the last I have heard from Pradeep. He never did call. (b)(5) *************._1_ Pat From: Ramuhalli, Pradeep (mailto:Pradeep.Ramuhalli@pnnl.gov] Sent: Tuesday, June 05, 2018 6:57 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

[External_Sender] RE: revision of report Patrick, The report update is about3/4 done. I am on travel this week and most of the next two weeks as well. Can I give you a call Tuesday of next week? With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email: pradeep.ramuhalli@pnnl.gov From: Purtscher, Patrick [3] Sent: Monday, June 04, 2018 6:41 AM To: Ramuhalli, Pradeep <Pradeep.Ramuhalli@pnnl.gov>

Subject:

FW: revision of report My office phone got fixed and is now back to the original #, 301-415-3942. Let me know when you have time to talk a little. Pat From: Purtscher, Patrick Sent: Wednesday, May 30, 2018 1:30 PM To: 'Ramuhalli, Pradeep' <Pradeep.Ramuhalli@pnnl.gov>

Subject:

RE: revision of report

I forgot to tell you that my office phone is not working, they have given me a temporary# 301-415-7887. You can always reach me on my cell,! L {~)(6) Pat From: Purtscher, Patrick Sent: Tuesday, May 29, 2018 7:53 AM To: 'Ramuhalli, Pradeep' <Pradeep.Ramuhalli@pnnl.gov>

Subject:

revision of report Good morning, I was just checking to see where you are with revision of the report. If you don 't have time to talk today, just send me a reply with an update. Pat Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch 11545 Rockville Pike I Rockville, MD 20852-2738 Phone: 301 -415-3942 I Office: TWFN 10A49 ptpl@nrc.gov

Note to requester: All the attachments are immediately following this email. Portions of the second attachment are redacted under FOIA Exemption B5, Deliberative Process Privilege. From: Tregoning, Robert Sent: Tue, 7 Feb 2017 13:39:48 +0000 To: Moyer, Carol

Subject:

RE: Looking for slides Attachments: Action It ems from EPRI-NRC Dec 2016 materials meeting.docx, NRC RES Overview rev.pptx, 2016-12-14 RES-EPRI Agenda.docx I'm not going to be much help with either of those items. Here's what I can tell you.

1. I didn't go to LWRS meeting but Raj did. I would ask him for slides. Next option would be Rich Reister

2. EPRI meeting was informal and focused on discussion. We didn't even swap slides. I'm attaching what I have which covers the NRC part as well as agenda and meeting summary/action items. If you want the EPRI slides, I can ask for them.

RT Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Moyer, Carol Sent: Tuesday, February 07, 2017 8:13 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

Looking for slides Hi Rob, I am looking for slide sets from two meetings in December. Do you by chance have a copy? Light Water Reactor Sustainability R&D Program Technical Integration Office LWRS Program - Fa ll Program Review and Technical Information Exchange Meeting Germantown, MD, December 6-7 , 2016 RES/EPRI Meeting, December 14-15, 2016 If you know where either is on a network drive, and can point me there, I would appreciate it. Thanks, Carol Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission

Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol.moyer@nrc.gov 301 -415-2153

Action Items from EPRI-NRC meeting on 12/14/16 in Washington, DC

1. As NRC completes the backlog of old SG NUREG/CR reports, the NRC POCs (P. Purtscher, M.

Rossi) should contact the EPRI POC (H. Cothron) just before each report is published to let her know that it's imminent.

2. NRC and EPRI should compare the IMT with NRC's research priorities after the next time that the IMT is updated. Action for EPRI (R. Dyle) to notify NRC (R. Tregoning) when update is completed. NRC evaluation will be coordinated by R. Tregoning to ensure alignment.

3. Conduct a follow-up meeting on further irradiation of high fluence materials among NRC, EPRI, and DOE. This could either be a call or a face-to-face meeting. NRC (M. Hiser) will lead in setting up meeting.

4. After the next MOM is completed, EPRI (R. Dyle) and NRC (R. Tregoning) will review the MOM priorities to determine the prognosis for future sec research after completing all Alloy 600/690 PWR research. This could be sec of aged SS, BWR Alloy 600 cracking, or another sec mechanism.

5. NRC would like to know more details about the RFA prioritization process to determine if it can also be used to prioritize NRC research activities. EPRI (R. Dyle) and NRC (R. Tregoning) have an action to add this item to the next management meeting between NRC and EPRI. Also, NRC (R.

Tregoning and K. Brock) will determine internally if a vehicle can be established for communicating the information to both NRR and RES Division Director-level management.

6. The xLPR application MOU should be completed with the general activities that will be conducted but not specifics (e.g., conducting a pilot- plant LBB evaluation). One approach could be to state in the MOU that a test or evaluation plan w ill be agreed to by both NRC and EPRI before proceeding with detailed work. NRC POC is M . Homiack and EPRI POC is C. Harrington.

7. Hold a1/2 day meeting between NRC, EPRI and key contractors to determine details of the xLPR application phase, including, a decision on pursuing a pilot plant application and/or an application with a representative plant. The meeting should be jointly arranged by NRC ( M.

Homiack) and EPRI {C. Harrington) .

8. FAVOR V&V: NRC (M. Kirk) will finalize development of a V&V plan and share it with EPRI (T.

Hardin) for their review and comment. EPRI (R. Dyle & T. Hardin) will identify the scope and effort required to summarize past industry V&V activities on FAVOR as well as future participation in V&V. Both NRC (R. Tregoning) and EPRI (R. Dyle) will report on the progress of this activity during the next quarterly materials conference call. If enough progress has been made, this could be discussed during the NRC-lndustry annual materials meeting in May.

9. Due to the large amount of CY-17 activity related to RPV integrity, the status of these activities will be added as standing item to quarterly materials call in 2017. EPRI (R. Dyle) has the lead for adding this to the agenda and reporting.

10. After the public meeting in February 2017 on baffle bolts, NRC (R. Tregoning) and EPRI (R. Dyle) will determine if any needed future collaboration on research activities in this area is needed between NRC and EPRi.

11. Harvesting Workshop in March 2017: NRC (R. Tregoning) will provide draft agenda and announcement to EPRI (R. Dyle) - Complete. NRC (R. Tregoning) w ill also cc R. Dyle on emails to S. Bernhoft requesting EPRI participation and coordination of the workshop sessions and speakers. - Ongoing.

12. HELB Acceptance Criterion work at NRC: NRC (M . Benson) wi ll share documentation report with EPRI (R. Dyle) and any other interested industry organizations. EPRI (R. Dyle) will provide feedback on industry's needs for possibly revising this criterion before NRC starts work in this area. If NRC does start work, NRC (M. Benson) w ill get EPRI (R . Dyle) feedback on the proposed eva luation plan before proceeding.

13. Advanced non-Light Water Reactor discussion : If NRC's implementation action plan (IAP) becomes availab le for public dissemination, NRC (1. Frankl) w il l share the report with EPRI (R.

Dyle). EPRI (R. Dyle) and NRC (R. Tregoning) will keep communicating on this topic for possible partnering with EPRI/ANT, if NRC initiates any research activities.

14. EPRI (R Dyle, A. Demma) w il l provide an update on EPRl's ion irrad iation research program during the lndustry-NRC May materi als meeting.

15. EPRI (K. Edsinger) wi ll identify if EPRI is conducting any research on carbon fiber reinforced polymer (CFRP) materials.

16. NRC and EPRI both agreed that the current meeting format t hat is both informal, focuses on strategic discussions for future research planning, and discusses only a handful of research topics of mutual interest, meets the needs of both organizations. The only change is to hold these meetings annually as a 1-day meeting. Also, the desire is to identify a standing month every year for conducting the meeting. The exact date w ill be picked a few months out in orde r to determine if it can be held adjacent to another meeting. EPRI (R . Dyle) and NRC (R.

Tregoning) have the lead to identify the month for the annual meeting.

United S121cs Nucle2r R,g ul21ory Commissio n Proucting People and the Environment

Office of Nuclear Regulatory ~ U.S.NRC Un ited States Nuclear Regulatory Commission Research (RES) - Overview Protecting Peopl.e and the Environment

• Mission

   - Plan, recommend, and implement nuclear regulatory research, confirmatory analyses, standards development, and resolution of potential generic safety issues for nuclear power plants and other facilities and materials regulated by the NRC
   - Provide technical advice, tools, and information to identify potential safety issues and resolve them as appropriate, support regulatory decisions, and issue regulatory requirements and guidance

• Charter

   - Established by the U.S. Congress in 1974

Office of Nuclear Regulatory ~ U.S.NRC Un ited States Nuclear Regulatory Commission Research (RES) - Overview, cont. Protecting Peopl.e and the Environment

• Approach

   - Focus research primarily on near-term regulatory needs related to the oversight of operating reactors as well as to new and advanced reactor designs
   - Develop technical tools, analytical models, and experimental data to allow the agency to assess potential safety and regulatory issues
   - Use internal expertise as well as contracts with commercial entities, national laboratories, and universities, or collaborations with international organizations, to develop these tools, models, and data

• Customers and Partnerships

   - All NRC offices and the Commission
   - Other government organizations, international regulatory agencies, International nuclear agencies (e.g., NEA, IAEA)
   - Other research organizations
   - Nuclear licensees and other industry stakeholders (e.g. , NEI, EPRI)
   - Public individuals and groups

RES Organization ~ U.S.NRC United States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Three technical divisions and support staff Office of Nuclear Regulatory Research Program Management, Mike Weber, Director Polley Development &

Ed Hackett, Deputy Director Analysis Staff Mindy Landau, Director Michael Brezovec. Deputy Director I I Division of Risk Analysis Division or Engineering Division of Systems Analysis Mark Thaggard, Director (Acting) Brian Thomas, Director Michael Case, Director Kevin Coyne, Deputy Director Kathryn Brock, Deputy Director Kimberly Webber, Deputy Director (Acting)

• Division of Systems Analysis (DSA)
• Research to develop and maintain broad technical expertise, experimental data, numerical simulation analyses tools, and knowledge bases
• Division of Risk Analysis (ORA)
• Research relating to probabilistic risk assessments (PRA); human factors and human reliability analysis; performance and reliability analysis; movement of radionuclides through environmental systems; operating experience and generic issues; and fire safety
• Division of Engineering (DE)
• Research and standards development to support the NRC strategic goals in the design, construction , and operation of current and advanced nuclear power plants and other regulated facilities
• Technical areas include structural and component integrity, material characteristics, aging, natural hazards, and digital instrumental and control

DE Organization ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment Division of Engineering Brian Thomas, Director Kathryn Brock, Deputy Director I I Regulatory Guidance Instrumentation, Structural , Corrosion and Component Integrity and Generic Issues Controls, & Electrical Geotechnical & Metallurgy Branch Branch Branch Engineering Branch Seismic Eng. Branch Istvan Frankl, Chief (Vacant) Thomas Boyce, Ian Jung, Dogan Seber, Chief Chief Chief Chief

• Component Integrity Branch (CIB)
• Corrosion and Metallurgy Branch (CMB)
• Regulatory Guidance and Generic Issues Branch (RGGIB)
• Instrumentation, Controls, and Electrical Engineering Branch (ICEEB)
• Structural, Geotechnical, and Seismic Engineering Branch (SGSEB)

                                                                        ~

DE Organization ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Component Integrity Branch (CIB)
• Corrosion and Metallurgy Branch (CMS)
• Regulatory Guidance and Generic Issues Branch (RGGIB)

   -  Facilitates reviews and updates to agency regulatory guidance, particularly Regulatory Guides (RGs)
   -  Coordinates agency involvement in consensus codes and standards
   -  Manages the congressionally mandated Generic Issues Program

• Instrumentation, Controls, and Electrical Engineering Branch (ICEEB)

   -  Develops and applies methods, data, tools, standards, and guidance to assess the adequacy of digital instrumentation and control and electrical equipment
   -  l&C: digital system contributions to risk, software attributes that can affect safety or security, new reactor designs, and development of consensus standards
   -  Electrical: equipment qualification, associated circuits, grid reliability; monitoring techniques for cable degradation; operating experience

• Structural, Geotechnical, and Seismic Engineering Branch (SGSEB)

   -  Assesses structural performance of systems, structures, and components (SSCs)
   -  Analyzes data related to seismic hazard and seismic performance of structures
   -  Develops and applies seismic design analysis methods and guidance for geotechnical and structural design elements
   -  Evaluates aging of concrete materials and structures

CIB ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Principal Functions Develops methods, data, standards, and modeling tools for identifying and evaluating degradation mechanisms that arise from irradiation on reactor pressure vessel steels

  -  Investigates capabilities of fracture mechanics measurement and analysis technologies Develops methods, data, standards, and modeling tools to assess the mechanical performance of SSCs Develops technical basis for revisions to ASME Section XI Provides and applies tools to quantitatively assess changes in structural reliability of nuclear plant systems, structures and components as a result of operating environment effects or aging of materials Evaluates the reliability of non-destructive examination methods for operating and new reactors Technical Areas and Point of Contact Piping Integrity: Patrick Raynaud     - Weld Residual Stress: Michael Benson xLPR: Matthew Homiack                 - High Energy Line Break: Michael Benson
  -  HOPE: Patrick Raynaud                 - ANLWR Materials & Integrity: Shah Malik CFRP: Patrick Raynaud                 - NOE, Modeling and Simulation: Carol Nave
  -  RPV Integrity: Mark Kirk              - Fluence Evaluation: Jay Wallace

CMB ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Principal Functions Develops the data to characterize the causes and effects of corrosion and environmentally-assisted cracking on the structures and components of nuclear plant systems Conducts materials degradation studies of irradiated-assisted stress corrosion cracking, stress-corrosion cracking, materials fatigue, and general corrosion

   -  Assesses in-service inspection techniques to ensure steam generator integrity Technical Areas and Point of Contact PWSCC CGR: Greg Oberson PWSCC Initiation: Eric Focht IAD: Sri Rao
   -  LTO/SLR: Raj Iyengar ANLWR Materials: Raj Iyengar Neutron Absorber Materials: Eric Focht
   -  Steam Generator Program: Pat Purtscher

Funding Projections ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• FY-17 funding is contingent on actual congressional appropriation to N RC
• FY-18 funding is more uncertain
• CIB Technical Area FY-17 ($Kl I FY-18 (b)(5)

RPV Integrity - Piping Integrity - NOE - HOPE

• CMB Technical Area FY-17 ($K)

(b)(5) I FY-18 NAM PWSCC CGR - PWSCC Initiation IAO - LTO/SLR - SG

Current Memoranda of ~ U.S.NRC Un ited States Nuclear Regulatory Commission Understanding (MOUs) Protecting Peopl.e and the Environment Signing Expiration Title Date Date NRC Contact s EPRI Contact s MOU between EPRI and NRC on Nicholas 9/30/16 9/30/21 Ken Canavan Collaborative Nuclear Safe Research DiFrancesco Acquisition and Testing of Zion Spent 9/30/16 9/30/21 Eric Focht Hatice Akkurt Fuel Pool Neutron Absorber Materials Aging, Qualification and Condition 9/30/16 9/30/21 Darrell Murdock Andrew Mantey Monitoring of Electrical Cables Long Term Operations Beyond 60 Years Amy Hull 9/30/16 9/30/21 Sherry Bernhoft Ra* I en ar Primary Water Stress Corrosion Erick Focht Paul Crooker, 9/30/16 9/30/21 Cracking - Crack Initiation Testing Gre Oberson Al Ahluwalia Primary Water Stress Corrosion 9/30/16 9/30/21 Greg Oberson Paul Crooker Cracking Expert Panel Activities Extremely Low Probability of Rupture 12/16/15 12/31/16 Mathew Homiack Craig Harrington Nondestructive Examination 4/14/14 4/30/18 Carol Nove Greg Selby Steam Generator Tube Base Research Matt Rossi 2/20/14 12/31 /19 James Benson Program Pat Purtscher

Current MOUs: Neutron Absorber Materials

                                                                   ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objectives

  -  Coordinate harvesting and shipping of samples of in-service Boral neutron absorber materials from the spent fuel pool of the decommissioned ZNPP
  -  Conduct research to establish an understanding of degradation mechanisms, the impact on retaining physical integrity and functionality by an examination and analysis of affecting properties
  -  Ensure timely exchange of information on technical approaches, test plans, unprocessed data, interim results, and draft and final reports to obtain degradation data on Boral

• Status

  -  November 2014: NRC witnesses BADGER testing of NAM panels in the Zion SFP
  -  December 2015: NAM panels harvested and delivered to the NRC contractor
  -  September 2017: Expected completion of evaluation of panels

• Deliverables

  -  Witness BADGER testing at the Zion SFP
  -  Boral NAM panels from Zion
  -  Share test plans and data

• Planned Completion Date: September 2017
• Challenges Identified: None

Current MOUs: Long-Term Operations

                                                               ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objectives

  -  Ensure the timely exchange and sharing of information, data, and knowledge on aging management programs and research activities
  -  Develop LTO analysis methods, tools, and/or data to support the second, and subsequent, extended licensing periods
  -  Enhance access to the nuclear power plant aging management technology, methods, and tools

• Status

  -  Continuous engagement and periodic discussions (bi-weekly calls, roadmap meetings, deep-dive meetings)

• Deliverables

  -  Sponsor joint NRG/industry workshop(s) on status of domestic and international research activities and operating experience to address and evaluate materials degradation issues (Spring 2018, Fall 2019)
  -  Investigate aging management through information exchange and data sharing, advances in the development and application of aging management methods, and demonstration of technical tools (Ongoing)

• Planned End Date: September 2021
• Challenges Identified : None

Current MOUs: PWSCC - Crack Initiation

                                                                   ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objectives

  -  Develop a mutually agreeable test plan for alloy 600/182/82 and alloy 690/152/52 materials
  -  Acquire data on cracking characteristics, time-to-initiation, and the quantitative effects of material variability on crack initiation
  -  Share of raw data, technical reports, and monthly status reports, upon receipt.
  -  Share technical reports, documents, or other products resulting from independent review of the data by the NRC and EPRI

• Status

  -  November 2015: Delivered one of two PWSCC crack initiation testing systems
  -  December 2015: Began testing Alloy 690/52/152 specimens
  -  February 2016: Delivered second of two PWSCC crack initiation testing systems
  -  March 2016: Began testing Alloy 600 specimens

• Deliverables

  -  Two PWSCC crack initiation testing systems
  -  PWSCC crack initiation testing data for Alloy 690/52/152 and Alloy 600/82/182.

• Planned Completion Date: December 2020
• Challenges Identified: None

Current MOUs: PWSCC - CGR Expert Panel

                                                                        ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objectives Allow NRC to participate in activities associated with the expert panel to generate crack growth rate disposition curves for Alloys 690/52/152
• NRC contractors participate as members of the data evaluation group
• NRC staff observe expert panel meetings
• Status Data evaluation group:
• Scored most of the available crack growth rate data
• Writing the report sections to document their scoring approach Data applications group:
• Developing the disposition curve models with the scored data
• Deliverables

  -  EPRI expert panel report
  -  No NRC deliverable

• Planned Completion Date: mid to late 2017
• Challenges Identified: None

Current MOUs: xLPR

                                                                   ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objective

  -  Develop a probabilistic software tool to assess compliance with 10 CFR Part 50, Appendix A, GDC 4, to include the capability of modeling active degradation mechanisms, such as primary water stress-corrosion cracking, and associated mitigation measures

• Status

  -  xLPR Version 2 code is technically complete and usable
  -  Completing remaining documentation, such as the user's manual and uncertainty report
  -  Negotiating a new MOU for using xLPR Version 2 in leak-before-break applications

• Deliverables

  -  xLPR Version 2 Software
  -  All associated documentation

• Planned End Date: December 2016
• Challenges Identified

  -  Establishing a suitable legal framework for public distribution of code
  -  Address legal framework under new MOU

Current MOUs: NDE, Modeling and Simulation

                                                                       ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objective Identify and evaluate effectiveness of NOE methods in detecting and characterizing flaws Evaluate the reliability of NOE methods for selected examinations Evaluate aspects of inspector qualifications Specific collaboration areas: Visual testing ; CASS; UT in lieu of RT for repairs, replacements, and modification; documentation of basis for ASME Section XI, Appendix VIII; RMS error; HOPE piping; and NOE modeling
• Status

  -  VT round robin completed in 2016
  -  EPRl's VT report published in 2016
  -  NRC's NUREG/CR (PNNL) VT report is targeted for completion in 2017
  -  Initiated revised MOU addendum: Addressing human performance issues for NOE

• Deliverables

  -  EPRl's VT report
  -  NRC's VT report

• Planned End Date: April 2018
• Challenges Identified

  -  Completing legal review of the revised MOU addendum

Current MOUs: Steam Generator Program

                                                                 ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Objective

  -  Provide the experimental data, predictive correlations, and the models needed to permit evaluation of the integrity of steam generator tubes as plants age and degradation proceeds, new forms of degradation appear, and new defect-specific aging-management schemes are implemented

• Status

  -  Research outlined in agreement is proceeding as planned

• Deliverables

  -  Several NUREG/CR will summarize research completed between now and 2019
  -  Semi-annual meeting to share progress with partners

• Planned End Date: December 2019
• Challenges Identified: None

NRC Topics of Interest ~ U.S.NRC for Further Discussion Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment

• Near-Term Research & Decision making

  -  Baffle bolt research: EPRI update and discussion on possible future collaboration
  -  Material harvesting workshop: NRG update and discussion
  -  xLPR: Future direction and possible applications
  -  RPV Integrity: Future activities and V&V

• LTO/SLR-related topics

  -  High Energy Line Break criterion: Discussion of industry needs
  -  High-fluence testing of stainless steels: Discussion of next steps
  -  Environmentally-assisted fatigue: Discussion of next steps
  -  SCC of aged stainless steel: Discussion of what's next after completing 690 research
  -  Irradiation Effects on Fracture Resistance and SCC in Ni and Ni-welds (X-750): EPRI update
  -  Thermal aging of CASS piping materials: Discussion of possibility to evaluate more representative plant materials (harvesting?)

• Advanced Non-Light Water Reactors

  - ANLWR materials: EPRI and NRC updates related to ASME Div. 5 support and other research activities
  - ANLWR applications: Discussion of future prognosis of materials research

Agenda RES/EPRI meeting December 14 and 15, 2016 December 14 0830-1200

• Introductions
• Finalize agenda for the meeting
• EPRI overview o Current EPRI Nuclear Sector/ MAPC structure o Detail Material! program roles, including new PSCR plans o RFA descriptions (show major topic areas) o Funding planned for 2017 and 2018
• NRC RES overview o Current structure o Details of RES engineering structure and roles o Funding planned for 2017 and 2018
• MOUs o Review status for current projects o Possible topics for future consideration 1200 - 1300 - Lunch on your own 1300-1700 - Detail project reviews (project plan, goals, schedule, etc. )
• PSCR - Demma
• MRP topics - Burgos
• BWR topic - McGehee o NOTE - The expectation for the EPRI folks is the most knowledgeable person presents the story. For example, Brian would speak to BFBs, ATR, RPVs, xLPR. Andy the BWR topics like X-750. Anne gets the lions share for PSCR. I'm open to your suggestions but we could break the discussions along subject matter such as - RPV, SCC EAF, irradiation effects. Open to suggestions
• NRC project discussions December 15 0900 - 1200
• Continue project discussions
• Review of action items

From: Hull, Amy Sent: Tue, 5 Sep 201715:31:11-0400 To: Hiser, IMatthew;Purtscher, Patrick Cc: Frankl, lstvan;Moyer, Carol

Subject:

Thanks Matt!!: Action: Rewrite in response to Feedback on UNR Response Task 2 From: Hiser, Matthew Sent: Tuesday, September 05, 2017 2:23 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov> Cc: Frankl, Istvan <lstvan.Frank l@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

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 ofNuclcar Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-4 I 5-2454 I 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@nrc.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 w ill 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) *** ... j *

• Iseems 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-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}}