ML19319B307
| ML19319B307 | |
| Person / Time | |
|---|---|
| Issue date: | 11/13/2019 |
| From: | NRC/OCIO |
| To: | |
| Shared Package | |
| ML19319B303 | List: |
| References | |
| FOIA, NRC-2018-000831 | |
| Download: ML19319B307 (166) | |
Text
{{#Wiki_filter:From : Ramuhalli Pradeep To : Purtscher Patrick Subject : [External_Sender) RE : [External_Sender) Discuss Report Comments Date: Tuesday, September 26, 2017 10:34 :38 AM Yes, but I will have to get off the call before 10 am Pacific (1 ET) as I have another meeting at that t ime. Any chance you are available later today (after 3 pm) or tomorrow (anytime - I am wide open)? I will go ahead and get th is moved by an hour just in case. With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email : pradeep.ramuhalli@ponl.gov
Ori gin al Appoi ntme nt -----
From: Pu rt sc her, Patrick [ma ilto: Patrick. Pu rtscher@ore.gov] Sent: Tuesd ay, September 26, 2017 3:08 AM To: Ramuha lli, Pradeep
Subject:
New Time Proposed : [Ext ern al_Se nder] Discuss Report Comment s When: Tuesday, Sept ember 26, 2017 8:30 AM-9:30 AM (UTC-08:00) Pacific Time (US & Ca na da). Where: Ca ll-in number below I have had another meeting come up that I need to attend . Can we postpone our call for 1 hour?
From: Ramuhalli Pradeep To: Purtscher Patrick; Hiser Matthew
Subject:
[External_Sender) RE: [External_Sender) TLR Discussion Date: Wednesday, September 19, 2018 9:46 :02 AM Will do. Thanks. With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email: pradeep.ramuhalli@pnnl.gov From: Purtscher, Patrick [1] Sent: Wednesday, September 19, 2018 3:48 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Ramuhalli, Pradeep <Pradeep.Ramuhalli@pnnl.gov>
Subject:
RE: [Extemal_Sender] TLR Discussion
- Pradeep, Can you create a new file with those changes we made that you agree are OK accepted, leaving our changes that you think need further consideration. If we could have that file before the Monday tele-con, it should make our discussion easier.
Pat
Original Appointment-----
From: Hiser, Matthew Sent: Tuesday, September 18, 2018 8:16 PM To: 'Ramuhalli, Pradeep' Cc: Purtscher, Patrick
Subject:
Tentative: [External_Sender] TLR Discussion When: Monday, September 24, 2018 1:00 PM-2:00 PM (UTC-08:00) Pacific Time (US & Canada). Where: Call info forthcoming Hi Pradeep, I have a meeting directly preceding this time that will probably run late. However, you and Pat can meet and I'll catch up when I can after my prior meeting. Out of curiosity, have you had a chance to review our edits? Generally OK with you or many concerns? Thanks! Matt
From : Ramuhalli Pradeep To : Purtscher Patrick Cc : Hiser Matthew Subject : [External_Sender] RE: DMLR Specific Comments on PNNL-27120-pr nrc 9-7-1S_w-PTP_add-ons.docx Date: Friday, September 07, 2018 5:47:58 PM
- Pat, Thanks. Let me review this next week, and we can talk afterwards. Perhaps toward s the end of next week, or early the week after?
With best regards, Pradeep Ramuhal li, PhD Tel : 509-375-2763 Emai l: pradeep ramuha lli@pnn l gov From: Purtsc her, Patrick [mailto :Pat rick.Purtscher@nrc.gov] Sent: Friday, September 07, 2018 10:54 AM To: Ram uha ll i, Pradee p <Pradeep.Ramuha ll i@pnn l.gov> Cc: Hise r, Matthew <Matthew.Hiser@nrc.gov>
Subject:
DMLR Specific Comments on PNNL-27120-pr nrc 9-7-18_w-PTP _add -ons.docx Here is a copy of you r report with al l of our comme nts. We t hink this addresses the NRR comments and we hope it wil l be re lative ly easy for you to review, acceptin g tho se changes that you agree with. Where yo u don' t agree, highl ight them for our further discuss ion. The one ma in comme nt I ha d that is not noted in each case is the ra t ing or rank ing t hat is present, mainly in Tab les 1 through 4. It should be clearly noted where t hose va lues come from, some were from EMDA and others we re from t he author's assessment of t he criter ia in each table. Clearly the fi nal assessment at the bottom of each tab le is TBD by each organization that is conside ring ha rvesting, given t heir own set of priorities . Pat
From: Ramuhalli Pcacteep To: Purtscher Patrick Subject : (External_Sender) RE: RE: draft report from PNNL on Harvesting project Date: Wednesday, December 06, 2017 10:57:29 AM
- Patrick, An update. Looks like the internal approva ls are moving along. I expect it to be approved for release later today or early tomorrow. I will get out an updated version of the document with the PNNL number as soon as this is approved .
With best regards, Pradeep Ramuha ll i, PhD Tel: 509-375-2763 Emai l: pradeep ramuha lli@pnn l Qv From: Purtscher, Patrick [mai lto:Patrick.Purtscher@nrc.gov] Sent: Tuesday, December 05, 2017 7:21 AM To: Ramuha ll i, Pradeep <Pradeep.Ramuha ll i@pnn l.gov>
Subject:
RE: RE: draft report from PNN L on Ha rvesting project Good morning, Thanks for the report. When does this get a PNNL report#? I thin k it needs that before I can officia lly get this into the system. Pat From: Ramuhal li, Pradeep ,oY Sent: Monday, December 04, 2017 4 :22 PM To: Purtscher, Patrick <Patrick Purtscher@nrc QY>
Subject:
[Externa l_Sender] RE : draft report from PNNL on Harvesting project
- Patrick, I don't recal l if I got this back to you or not. If not, attached is the updated version. In addition to t he editoria l changes you suggested, an internal peer review ca ught a few more editorial changes (format checks, grammatica l issues). These are in the attached.
With best regards, Pradeep Ramuha ll i, PhD Tel: 509-375-2763 Emai l: pradeep ramuha lli@poo l QY From: Purtscher, Patrick [mailto*Patrick Purtscher@nrc QY] Sent: Friday, November 24, 2017 10:05 AM To: Ramuha lli, Pradeep <Pradeep Ramuha lli @pnn l QY>
Subject:
FW: draft report from PNNL on Harvesting project Good afternoon, Here is the report with some little ed itorial changes that we would li ke you to make before we send it through for management approva l. Pat
From: Ramuhalli Pcacteep To: Purtscher Patrick Subject : (External_Sender) RE: RE: MDLR comments on PNLL"s Guidelines for Harvesting Materials for SLR Date: Tuesday, April 03, 2018 11:17:56 AM Would tomorrow afternoon work for you? Say arou nd 3 pm eastern ? With best rega rds, Pradeep Ra muha lli, Ph D Tel : 509-375-2763 Emai l: pradeep ramuha lli@pnnl gov From: Purtscher, Patrick [mai lto:Patrick.Purtscher@nrc.gov] Sent: Tuesday, April 03, 2018 4:30 AM To: Ramu hall i, Pradeep <Pradeep.Ramuha lli@pnnl.gov>
Subject:
RE: RE: MDLR comments on PNLL's Guidelines for Harvesting Materials for SLR
- Pradeep, Sorry, I thought I had responded to your last message. I am avai lable today or tomorrow in the afternoon (Eastern time). Pick a time that works for you and I wil l call you.
Pat From: Ramuhal li, Pradeep li@pnnl.gov Sent: Monday, April 02, 2018 5:23 PM To: Purtscher, Patrick <Patrjck.Purtscher@nrc gov>
Subject:
[Externa l_Sender] RE: MDLR comments on PNLL's Guidelines for Harvesting Materials for SLR
- Patrick, Not sure if I missed an email from you, but are you available later this week to talk? Or early next week?
With best rega rds, Pradeep Ramuha ll i, PhD Tel : 509-375-2763 Emai l: pradeep ramuha lli@pnnl gov From: Pu rtscher, Patrick [ma i Ito*Patrick Pu rtscher@nrc gov) Sent: Monday, March 26, 2018 11:51 AM To: Ramuha lli, Pradeep <Pradeep Ramuha llj @pnn l gov>
Subject:
FW: MDLR comment s on PNLL's Guidelines for Harvesting Materials for SLR Hi, I asked NRR for comments and never expected 8 people to review this report. After you have read the comments, we should schedule a t ime to tal k. Let me know when you are ready. Pat From: Brady, Bennett Sent: Tuesday, March 20, 2018 5:19 PM To: Purtscher, Patrick <Patrick Purtscher@nrc gov> Cc: Oesterle, Eric <Eric Oesterle@nrc gov>
Subject:
MDLR comments on PNLL's Guidelines for Harvesting Materials for SLR Pat Following your request, I asked eight of our technical review staff to review and provide comments
on PNNL's technical letter report on harvesting materials. Attached are general comme nts on the report and specific comments that I have compiled in redline/strikeout version of t he report itself. Some of the comments are repetitio us of comments made by other reviews. I have tried to group similar comments together. When you have had a chance to review them, please see me if you have any questions. I will t ry to answer your questions or get you to the right reviewe r. In sp ite of the rather negative comments on this report, we continue to believe that the Materials Harvesting Project will be in valuable in the future as the NRC deals with aging plants and needs an organized approach for selecting materials for harvesting withe the increased avai lability of sources. Bennett Bennett M. Brady Senior Project Manage r Divisi on of License Renewa l Office of Nuclear Reactor Regulation 0 11- 08 301-415-2981
From: Rnmuholli Prn<Jccn To: Hiser Matthew; Punschcr PaJrjck; Knobb.s Katie Cc:
Subject:
(External_Sender] RE: RE: RE: RRIM Date: Friday, August 05, 2016 11 :40:09 AM So - I have to be in a program review on the 30th in DC, so I can not do that day either. I was planning on staying over on the 31st (at least for part of the day). With best rega rds, Pradeep Ramuha ll i, PhD Tel: 509-375-2763 Emai l: pradeep.ramuhaHi@pnnl.gov From: Hiser, M atthew r@nrc.gov Sent: Friday, August 05, 2016 8:27 AM To: Ramu hall i, Pradeep <Pradeep.Ramuha ll i@pn nl.gov>; Purt scher, Patrick <Patrick.Purtscher@nrc.gov>; Knobbs, Katie <katie.knobbs@pnnl.gov> Cc: Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: RE: RE: RRIM My two cents: I think it would be great if we cou ld meet in-person the week of August 29. (I've been interacting with Pradeep on t his for over a year without actually meeting!) My only limitation that week is I can't do August 30, but otherwise am fa irly free ... we could also meet somewhere downtown if that's easier for Pradeep. If t hat won't work, perhaps a ca ll on Aug 18, 19, 25, or 26? (Code is mostly Aug 22-24 ... ) From: Ram uhal li, Pradeep [m ailto:Pradeep.Ramuhalli@pnnl gov] Se nt: Friday, August 05, 2016 11:18 AM To: Purtscher, Patrick <Patrjck.Purtschcr@nrc.gov>; Hiser, Matthew <M atthcw.Hiscr@nrc gov>; Knobbs, Katie <katje knobbs@pool gov> Cc: Hull, Amy <Amy Hull @nrc gov>
Subject:
[Externa l_Sender] RE: RE: RRI M
- Pat, Tha nks. Wou ld the week of the 22nd work (not sure if Code week is t hat week, or the week after)?
Also, t here is a good possibility I wi ll be in DC the week of the 29th for at least a coup le of days. I can always swing by and brief you, M at t, and Amy. With best rega rds, Pradeep Ramuha ll i, PhD Tel: 509-375-2763 Emai l: pradcep ramuhalli@pnnl gov From: Pu rtscher, Patrick [maj)to*Patrjck Purtscher@nrc gov] Sent: Friday, August 05, 2016 8:06 AM To: Hiser, Matthew <M atthew.H iser@nrc.gov>; Ramu haIii, Pradeep <Pradeep.RamuhaHi@pnnl.gov>; Knobbs, Katie <katie,knobbs@pnnl.gov> Cc: Hull, Amy <Amy H uU@nrc.gov>
Subject:
RE: RE: RRIM Good morn ing,
M at t and I have gone t hrough t he docu ment and made some comments. (b )(6~ The timing for our next updat e will depend on a lot of fact ors. I w ill be out of the office onf..._ ___. for part of t he next 2 w eeks and t hen w e have ASM E Code meetings here in DC the last week of August. Matt has ! ! in early Sept ember. Let me know when you th ink you would be ready for a conference cal l. (b)(6.) Pat From: Ram uhalli, Pradeep [maiito*Pradeep.Ramuhalli@pnnl.gov] Sent: Thursday, July 21, 2016 12: 14 PM To: Purtscher, Patrick <Patrjck,Purtscher@nrc.gov>; Hiser, Matthew <Matthew Hiser@nrc.gov>; Knobbs, Katie <katje.knobbs@pnnJ.gov> Cc: Hull, Amy <Amy HuU@nrc.gov>
Subject:
[External_Sender] RE : RRIM Patrick, Matt, Attached is a draft document for discussion later today. With best regards, Pradeep Ramuha ll i, PhD Tel: 509-375-2763 Emai l: pradcep.ramuhalli@pnnl.gov
O riginal Appoi ntment-----
From: Ramu hal li, Pradeep Sent: Tuesday, July 12, 20 16 7:50 AM To: Ramu hall i, Pradeep; 'Pu rtscher, Patrick'; Hiser, Mat t hew (Matthew.Hiser@nrc.gov); Knobbs, Katie Cc: Hu ll, Amy
Subject:
RRIM When : Thursday, July 21, 2016 10:00 AM-11:00 AM (UTC-08:00) Pacific Time (US & Canada). Where: Skype M eet ing
- All, Apologies - I have been incom municado for a couple of weeks. I'd li ke to set up a conf erence call to play cat ch up. Let me know if th is t ime w orks for you.
"7 Join Skype Meeting This is an online meeting for Skype for Business, t he professio nal meetings and communications app fo rmerly known as Lyne. Join by pho ne Join the meetine and have L y ne call you or dial-in (Richland) English (United Stat es) 866-528-1882 or 509-375-4555 (Richland) English (Unit ed States) On-campus PNNL staff dial 5-4555 (Richland) English (United States) f ind a local number Conference ID: I 1* * * * ** .(b}(p} Foreoi your dial-in PlN? Il:k41
From: Ramuhalli Pcacteep To: Purtscher Patrick; Hiser Matthew
Subject:
(External_Sender) RE: RE: TLR Update Date: Thursday, August 30, 2018 12:35:38 PM
- Patrick, No problem. I wil l wa it ti ll next week for the updated file.
W it h best regards, Pradeep Ramuha ll i, Ph D Tel: 509-375-2763 Emai l: pradeep ramuha lli@pnn l gov From: Purtscher, Patrick [mai lto:Patrick.Purtscher@nrc.gov] Sent: Thursday, August 30, 2018 5:50 AM To: Ramuhall i, Pradeep <Pradeep.Ramuha lli@pn nl.gov>; Hiser, Matthew <Matthew.Hiser@ nrc.gov>
Subject:
RE: RE : TLR Update Hi, I made a m ista ke and t he fi le I se nt on Wed nesday did not include all of the comments. We are preparing a comprehensive fi le that should be ready by the end of next week with comments/changes t hat you ca n more easily review and either accept o r rej ect. Those areas t hat you reject can be the areas where we ca n focus our discussions to f inalize the report.
- Thanks, Pat From: Ramuhal li, Pradeep li@pnnl,gov
Sent: Wednesday, August 29, 2018 12:51 PM To: Purtscher, Patrick <Patrick Purtscher@nrc gov>; Hiser, Matthew <Matthew Hjser@nrc gov>
Subject:
[Externa l_Sender] RE: TLR Update
- Patrick, Thanks. Let me review and we ca n ta lk. I am out of the office for most of the rest of this week and next; how about Tuesday Sept 11? In principle, what you suggest below seem to be OK but let me take a look t hrough the document as well.
With best rega rds, Pradeep Ramuha ll i, Ph D Tel : 509-375-2763 Emai l: pradeep ramuha lli@pnn l gov From: Pu rtscher, Patrick [ma i Ito*Patrick Pu rtscher@nrc gov] Sent: Wednesday, August 29, 2018 9:43 AM To: Ramuha lli, Pradeep <Pradeep Ramuha llj @pnn l gov>; Hiser, Matthew <Matthew Hjser@nrc gov>
Subject:
RE: TLR Update Hi, M att and I took turns changing t he report with our recommendations, the attached is a composite of ou r comments. The biggest cha nges were to drop t he abstract, combine sect ions 1 and 2, make t he exa mples in section 3.3.2 int o a separate sect ion, and drop t he specific harvesting exam ples in Section 4. We don't need that level of deta ils for historica l perspective. The genera l lessons learned are t he points to be emphasized. These are suggest ions and would like to discuss wit h you after you have some time to review. Let me
know when you have time . We hope to meet with NRR near the end of Sept. to go over the report and how their comments were considered . Pat From: Ramuhal li , Pradeep [2] Sent: Friday, August 17, 2018 2:45 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
[External_Sender] TLR Update The update so far is attached. This sti ll needs some cleanup and citations incl uded; I am working on a tech editor on these . With best regards, Pradeep Pradeep Ramuha ll i, PhD Senior Research Scient ist, Applied Phys ics Group Pacific Northwest National Laboratory 902 Battelle Blvd. P.O .Box 999, MSIN K5-26 Richland, WA 99352 Tel : 509-375-2763 Emai l: pradeep ramuhalli@pool gov http://www.pnnl.gov
Note to requester: Attach ment to this email is immediately From : l:illlL....&m'. To: Hiser Matthew following. Subject : abstract size constraints ?: Ditto to Rob [eom] : ACTION: PLiM abstract
- revised Date: Monday, May 22, 2017 3:12:15 PM Attachments: Abstract for 4th PUM NRG RES SLR.doc)(
From: Moyer, Carol Sent: Monday, M ay 22, 2017 10:56 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@n rc.gov>; Fra nk l, Istvan <lstvan.Fra nkl@nrc.gov>
Subject:
RE: Ditto to Rob [eom ]: ACTION : Pl iM abstract - rev ised Thank you all. I wi ll submit this abstract today. Separately, I believe Matt H. is drafting an abstract on harvesting. I hope that it, too , will be well received. Carol From: Hull, Amy Sent: M onday, M ay 22, 2017 10:35 AM To: Tregoning, Robe rt <Robert.Tregoning@nrc gov>; Moyer, Carol <Carol Moyer@nrc.gov>; Fran kl, Istvan <Istvan fraokl@orc gov>
Subject:
Dit to to Rob [eom] : ACTION: Pl iM abstract - revised From: Tregoning, Robert Sent: Monday, M ay 22, 2017 10 :08 AM To: Moyer, Carol <CaroLMoyer@nrc.gov>; Fra nkl, Istvan <Istvan frankl@orc gov> Cc: Hu ll, Amy <Amy Hull@orc gov>
Subject:
RE: ACTION: PliM abst ract - revised Carol: I'm okay with it. I would just read it through one more time before sending to make sure that there are no grammatical errors in the final product.
- Cheers, Rob Robert Tregoning Technical Advisor for Materia Is US Nuclear Regulatory Com m ission Two White Flint North, M/ 5 T-10 A36 11545 Rockvi lle Pi ke Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Moyer, Carol Sent: M onday, M ay 22, 2017 9:59 AM To: Frankl, Istvan <Istvan f rankl@orc gov>
Cc: Tregoning, Robert <Robert Tregoning@nrc gov>; Hull, Amy <Amy Hull@nrc gov>
Subject:
RE: ACTION: PliM abst ract - revised
- Steve, Thank you for your review. I agree with your recommended changes.
Amy, Rob -Still OK with this?
Thank you, Carol From: Frankl, Istvan Sent: Friday, May 19, 2017 5:53 PM To: Moyer, Carol <CaroLMoyer@nrc.gov> Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: ACTION: PliM abstract - revised Thanks, Carol. I would recommend change in title. Please see the attachment for additiona l revisions. Steve From: Moyer, Ca rol Sent: Friday, May 19, 2017 5:03 PM To: Frankl, Istvan <Istvan frankl@orc gov> Cc: Tregoning, Robert <Robert Tregoning@nrc.gov>; Hull, Amy <Amy Hull@nrc.gov>
Subject:
ACTION: PliM abstract - revised
- Steve, The draft abstract for our paper for the Plant Life Mana gement (PLiM) conference is included below, for easy ac cess, and attached, for track-c hanges use if needed. This version addresses comments from Amy, Mita, and Rob. I have asked Sherry Bernhoft, w ho is on the organizing committee, to confirm that we can submit the abstract early next week.
I will let you know when I learn her true deadline or any other new info. Comments and suggestions are appreciated. Research Relating to Plant License Renewal and Aging M anagement C. E. Moyer, M . Sircar, J. Philip, J. E. Pires, D. D. Murdock, T. Koshy, A. B. Hull U.S. Nuclear Regulatory Commission (NRC}, Washington, D.C., USA The U.S. Nuclear Regulatory Commission (NRC} issues licenses for commercia l power reactors to operate for up to 40 years. These licenses may be renewed by the regulator for m ultiple 20-year increments. Now that 47 of the 99 operating commercial reactors in the U.S. have entered their first period of extended operation (PEO), severa l licensees have indicated their intention to apply within the next few years for subsequent license renewal (SLR) for an additional 20-year period. The NRC has revised its key guidance documents to indicate its expectations for aging management of passive, long-lived plant systems, structures, and components. Resea rch is being continued beyond the receipt of initial SLR applications to confi rm the adequacy of the se guidance documents through the SLR period. Should the research identify concerns related to aging management, the guidance m ay need to be revised to reflect the new results. Resea rch is ongoing in the following four areas: reactor pressure vessel neutron embrittlement, irradiation assisted stress corrosion cracking of reactor vessel internals, concrete and containment degradation, and electrical cable qua lification and condition assessment. This paper will em phasize research related to concrete degradation, including alkali-silica reaction and irradiation dam age to concrete, and condition assessment of electrical cables. Carol Moyer Sr. Materials Engineer
RES/ DE! CMB carol.mover@nrc.aov 301-415-2153
Proposed Abstract for 4th PLiM C. Moyer (RES/DE/CMB) 5/19/2017 Regulatory Research on the Aging Management of Structures, Systems and Components in Nuclear Power Plants Supporting License Renewal C. E. Moyer, M. Sircar, J. Philip, J. E. Pires, D. D. Murdock, T. Koshy, A. B. Hull U.S. Nuclear Regulatory Commission (NRC) , Washington, D.C., USA The U.S. Nuclear Regulatory Commission (NRC) issues licenses for commercial power reactors to operate for up to 40 years. These licenses may be renewed for multiple 20-year increments. Now that 47 of the 99 operating commercial reactors in the U.S. have entered their first period of extended operation (PEO) to operate for up to 60 years , several licensees have indicated intention to apply within the next few years for subsequent license renewal (SLR} for an additional 20-year period. The NRC has revised its key guidance documents to be ready for the review of SLR applications and to communicate expectations for the aging management of passive, long-lived plant systems , structures, and components (SSCs). Regulatory research on the ag ing management of SSCs is being conducted now and will continue beyond the receipt of the initial SLR applications to confirm the adequacy of these guidance documents through the SLR period. Should regulatory research identify concerns related to aging management, regulatory guidance may be revised to reflect the new resu lts . Regulatory research is ongoing in the following four areas: reactor pressure vessel neutron embrittlement, irradiation assisted stress corrosion cracking of reactor vessel internals, concrete and containment degradation, and electrical cable qualification and condition assessment. This paper will focus on regulatory research related to concrete degradation, including alkali-silica reaction and irradiation damage to concrete , and cond ition assessment of electrical cables .
Note to requester: From: Frankl Istvan A ttachment to this To: Moyer Carol; Hiser Matthew email is imme diately Subject : ACTION: Inputs for EPRI quarterly MOU call Dat e: Tuesday, October 17, 2017 10:32:28 AM following. Attachments: EPRI Quarterlv MOU Status Uodate Oct 2017 cern20171011 .xlsx Importance: High
- Carol, Brian needs additional info on harvesting for the upcoming EPRI quarterly MOU call on 11 /3.
Please address the highlighted request below in your reply and update relevant section of the attached spreadsheet. Please complete this action noon tomorrow.
- Matt, Please assist Carol with this action.
- Thanks, Steve From: Thomas, Brian Sent: Tuesday, October 17, 2017 10:11 AM To: Oberson, Greg <Greg.Obe rson@nrc.gov>; Frankl, Istvan < lstvan.Frankl@n rc.gov>; Iyengar, Raj
<Raj .lyengar@ nrc.gov>; Koshy, Thomas <Thomas.Koshy@n rc.gov>; M il ler, Kenneth A <KennethA.Miller@nrc.gov>; Boyce, Tom <Tom.Boyce@nrc.gov> Cc: Regan, Christopher <Christopher.Rega n@nrc.gov>
Subject:
RE: Inputs for EPR I quarterly MOU cal l
- Folks, The status update for the action items for CMB, ICEEB, and RGGIB needs improvement.
For CIB - I am not aware of any deep dive meetings occurring. Specific accomplishments for such meetings should be identified. Neither I nor Chris attended nor were invited to any such meeting. Information stated was already known and does not portray any progress on the action item. For cable harvesting - please state what was done to enable the completion of the harvesting. Also state what other collaborative activities are needed regarding cable research at this time ? For RGGIB/Codes and Standards - please state what occurred or was agreed to going forward at the Standards Forum. Thanks ... Brian From: Oberson, Greg Sent: Monday, October 16, 2017 4:40 PM To: Thomas, Bria n <Brian.Thomas@nrc.gov> Cc: Regan, Christopher <Christopher.Regan@nrc.gov>
Subject:
Inputs for EPRI quarterly M OU ca ll
- Brian, Attached are the inputs for your consideration. I would like to provide these to Nick by Wednesday if possible.
Greg
Action Item Assianment Status Uodate Challe naes/lssues for Manaaement Attention EPRI and NRC management and staff should be encouraged to continue awareness of decommissioning NPPs in order to identify potential components for future Review the availability of cables that could be harvested from plants in CMB Cables to be harvested for the current harvesting. NRG/RES is undertaking a research project decommissioning to support research on cable aging and performance research project on cable condition to prioritize components for harvesting that will support under realistic conditions. Elevate as needed to EPRI and NRG assessment and cable degradation is aging management studies for SLR, including electrical management to facilitate successful availability. completed. components. EPRI/NRC "deep dives" have been completed. RPVs & Internals: A public workshop on RPVs and internals is planned for Spring 2019. Concrete: A joint (NRC/DOE/EPRI) roadmap meeting on concrete is expected in Q4ofCY2017. Schedule "deep dive* meetings on LTO RPV/ Concrete / Cables research CMB Cables: A joint roadmap meeting on cables EPRI and NRC management and staff should be within the near-term (3-6 months) to assess the status of roadmap is scheduled for 1/8/2018. A public encouraged to continue participation in the joint activities, identify remaining gaps in Research, determine what research workshop on concrete and cables is roadmap process to track completion of confirmatory remains to be completed, and when can we terminate these research planned for Summer 2020. research for LTO, as well as to identify any emerging projects (e.g., concrete irradiation). Additionally, identify options to Based on confirmatory research to date, the opportunities for leveraging or otherwise accelerating complete the research in an efficient manner and that optimizes use of NRG is ready to receive utility submittals in completion of the work. available resources. Assess readiness for potential utility submittals by Dec. 2017. The joint roadmap process is Lessons learned from reviews and implementation of the Dec 2017. Use these updated roadmaps to complete remaining research being used to track completion of remaining lead SLR applications will be fed back into the joint in support of long-term operations. research in support of LTO. roadmap process. After discussions with RES and EPRI staff, it was determined that an SLR workshop in 2017 would not be timely. Near-term applicants are in the peer-review phase, and unlikely to modify applications. CMB Workshops would be more effective after lessons learned from addressing the lead applications. Public workshops on SLR are being planned for Spring 2019 (RPVs and Identify if there are opportunities for an earlier SLR workshop in 2017 in Internals) and Summer 2020 (Concrete and advance of the first SLR aoolication by the end of the year. Cables). Develop technical addendum on advanced reactor materials research which identify planned NRG and EPRI cooperation. Focus on aligning GIB efforts and avoiding unnecessary duplication of activities. Target end of the year. EPRI Quarterly MOU Status Update Oct 2017_cem.xlsx
Brian Thomas sent an email to Kurt Edsinger on 6/28 inviting EPRI to the NRG Standard Forum, and requesting that EPRI RGGIB make their reports publicly available so they can be used for standards. Kurt replied on Kurt E. suggested that we make use of EPRI reports a 6/30 that EPRI would support the Forum, topic for a quarterly meeting or a face-to-face meeting. Forward to Kurt by the end of June the invite to the September 2017 and would likely make their reports available We could also explore whether EPRI could get vendors Standards Forum meeting, which NRG is hosting. to those interested. to particpate in using the reports and creating standards. Work with legal staff to enable domestic distribution of the xLPR code and facilitate futu re international distribution. Explore viable and practical GIB approaches, such as distributing the code to international non-aovernmental entities throuah RISSG. EPRI Quarterly MOU Status Update Oct 2017_cem.xlsx
From: Frankl Istvan To: Purtscher Patrick
Subject:
ACTION: harvesting report Date: Friday, May 25, 2018 11 :04:23 AM Importance: High
- Pat, What is the latest status of the PNNL report? Can we prioritize its publication?
- Thanks, Steve From: Hiser, Matthew Sent: Thursday, May 24, 2018 12:09 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Aud rain, M argaret
<Ma rgaret.Audrain@nrc.gov>; Pu rtscher, Patrick <Patrick. Pu rtscher@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@n rc.gov>
Subject:
RE: ha rvesting report I agree it wou ld be good to move the publish ing of t hat report ahead exped itiously to help o ur coord ination with EPRI. Last I heard Pat sa id PNNL was working on addressing NRR' s comments - not sure what t he timeline was for doing t hat t hough. Thanks! M att From: Tregoning, Robert Sent: Thursday, May 24, 2018 8:37 AM To: Audrain, M argaret <Margaret.Audrain@nrc.gov>; Hise r, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick Purtscher@nrc gov> Cc: Frankl, Istvan <Istvan Frankl@orc gov>
Subject:
harvest ing report All: Yesterday, during Steve's presentation, EPRI (Dyle and Demma) expressed interest in getting the PNNL report once it's published. We're also planning to have some discussions with EPRI next week during the NRC/EPRI materials meeting to promote future collaboration on harvesting opportunities. Therefore, I think we should make publishing that report a higher priority and we can possibly use it in part to help frame our discussions with EPRI moving forward. Thoughts? Rob
Robert Tregoning Technica l Advisor for Mate ri als US Nuclear Reg ulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockvi ll e Pike Rockvil le, MD 20852 -2738 ph: 301-415 -2324 fax: 301-415-6671
From: l:illlL....&m'. To: Tregoning Robert; Hiser Matthew Subject : ADAMS address to obtain other presentations?: source doc for DOE slide: Harvesting Efforts June NRG-Industry materials mtg 5-28-15 mah.abh.pptx Dat e: Monday, June 01, 2015 12:07:35 PM Thanks. I am working at home. How do I access other presentations? From: Tregoning, Robert Sent: Monday, JuneOJ,20151 1:12AM To: H iser, Matthew Cc: Hull, Amy
Subject:
RE: source doc for DOE slide: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah .abh.pptx Got you; I didn't read the entire thread to really grasp the issue ... Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 2 1 Church Street, MIS CS-5A24 Rockville, MD 20850 ph: 301-25 1-7662 Blackberry: ..... . . . .-. . . .-. . . ...... .
.1.(P)(~.)
fax: 301-251-7425 From: Hiser, Matthew Sent: Monday, June 01, 2015 11:11 AM To: Tregoning, Robert Cc: H ull, Amy
Subject:
RE: source doc for DOE slide: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx Hi Rob, What you have is the final version. T here was a comment from Kathy about cleaning up Slide 15, but the slide was a screenshot from a DOE presentation that Amy has only in PDF form, so it's not possible to fix the formauing (nor desirable really given that it is someone else's slide ... ). Thanks! Matt Matthew Hiser Materials Engineer Corrosion and Metallurgy Branch Division of Engineering Office of Nuclear Regulatory Research 301-25 1-7601 From: Tregoning, Robert Sent: Monday, June 01, 201 5 11 :08 AM To: Hiser, Matthew Cc: Hull, Amy
Subject:
RE: source doc for DOE slide: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx Matt/Amy:
Here's the powerpoint that I have if you need it. Please send me any changes that you make to this so that I can make sure the latest version is available for presenting. RT Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 21 Church Street, M/S CS-5A24 Rockville, MD 20850 ph: 30 1-251 -7662 Blackberry:,..!- - ....j(b)(§) fax: 301 -251-7425 From: Hiser, Matthew Sent: Monday, June 01 ,2015 I0:39A M To: Frankl, Istvan Cc: I-lull, Amy; Tregoning, Robert
Subject:
FW: source doc for DOE slide: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx FYI Steve - it appears Amy has the source slide only in pdf form, so it is not possible to make these changes. I think it works fine as is to convey the necessary information for our purposes ... From: Hull, Amy Sent: Monday, June 01, 2015 7:35 AM To: Hiser, Matthew
Subject:
source doc for DOE slide: Harvesting Efforts June NRC-lndustry materials mtg 5-28-15 mah.abh.pptx Matt, I 'snipped' slide L3 of the attached pdf. I could not figure out how to clean it up. Are you able to? From: Hiser, Matthew Sent: Friday, May 29, 2015 9:39 AM To: Hull, Amy; Frankl, Istvan Cc: Tregoning, Robert.
Subject:
RE: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx Hi Rob, Steve, Arny, I have made the changes in accordance with Kathy's comments as relayed by Steve in the attached PP. One final tweak Arny and I will try to make on Monday is to Slide 15 - if we can clean up the source slide from DOE, just so the information comes through clearly. Thanks! Mau From: Hull, Amy Sent: Thursday, May 28, 2015 10:03 AM To: Frankl, Istvan Cc: Tregoning, Robert; Hiser, Matthew
Subject:
Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx We have made changes suggested . I will drop the 390 form off for you now.
From : ~ To : Moyer carol ; Burke John ; Herrity Thomas ; Hiser Matthew; Audrain Margaret; Purtscher Patrick; Tregon ing
.fu!.Qe.r:t; Harris Brian Cc: Frankl Istvan Subject : Analysis of reception of our RIC posters, thanks for your participatio n, Date: Friday, March 16, 20 18 8:58 :55 AM RIC poster outreach metrics parameter AM Harvesting
# of poster handouts taken to exhibit 75 120
# of poster handouts remain ing on 3/16/2018 1 47
# posters picked up by visitors 74 73
# people noted on contact/interest/signin fo rm 20 27
# of business cards completed , left at exhibit 13 16 completed detailed interest form 7 5 Amy B. Hull, PhD Senior Materials Engineer US Nuclear Regulatory Commission
- Office of Nuclear Regulatory Research Division of Engineering
- Corrosion & Metallurgy Branch (RESIDE/CMS (office T10-D49))
11545 Rockville Pike, Rockville, Maryland 20852 Ph.: (301) 415-2435
- FAX: 301-415-~671 Alt e-mail:! *.. r ceii l._
(b )(6) (b )(6)_
From: Audrain Margaret To : Hjser Matthew; Purtscher Patrjck Subject : ANL Harvesting Trip Date: Thu rsday, November 16, 201 7 2:05:56 PM First attempt at ANL letter. Edit away! Bodgan et all , A few of us at the NRG (Matt Hiser, Pat Purtscher, Rob Tregoning , and me) , are setting up a database of materials for a harvesting program . We'd like to schedule a visit to ANL to be our "guinea pig" site to get rolling with the effort. We have four main material areas of interest: RPV, RVI , cables, & concrete and are interested in what ANL has from past programs with the NRG, DOE and others. We hope to assemble an inventory of available materials to consider for a harvesting program like, or in coordination with , that in the INL NSUF Nuclear Fuels and Materials Library (NFML). Our emphasis is in the four areas outlined earlier, but not necessarily limited to those four. Materials of interest don't have to be material from plants with extensive service history. Would you all be available and have the resources to meet with us to go over the materials ANL has in inventory? We hope that all of you , with the assistance of Omesh Chopra and Bill Shack, will be able to identify materials of interest before we make the trip. This would be some preliminary work on your part and then roughly a half day in person. We are thinking about planning the trip mid-Dec. Would this give you enough time to compile material of potential interest? We can have a phone call in advance to better describe what we're looking for if that would help.
- Thanks, Meg , Matt, Pat and Rob
From: Brady Bennett To : Purtscher Patrick Subject : Comments on PNNL Report Date: Wednesday, March 07, 2018 11:20:18 AM
- Pat, I just got some more comments from Allen Hiser. I am incorporating them in the redline/strikeout version and in the general comments. You may want to delay your review of the comments I sent yesterday until I have them all. I will try to get them to you by the end of the week.
Bennett Bennett M. Brady Senior Project Manager Division of License Renewal Office of Nuclear Reactor Regulation 0 11 - 08 301-415-2981
Criteria Title Description Scoring Guidance H = high risk significance/ little to no available data MH = Medium-high risk significance/ limited data available Crilicalness of Technical Gap Harvesling to address critical gaps should be prioritized over less M = Moderate risk significance/ some Addressed csscn1ial 1echnical gaps data available ML= low to moderate risk slgnficance / H = High sufficient data available for regulatory MH = Medium-high decisions M = Medium L = Low risk significance/ large amount ML= Medium-low of data available L = Low H = Nearly impossible to replicate Key considcra1ions arc the case of labornlory rcplica1ion of aging service enviroment I critically important mechanism and unique field aspccls of the aging mechanism. to use* harvested materials Degradation mechanisms that arc harder 10 replicate with simulalcd MH = Challenging to replicate service aging conditions would be ofl,igher priority for harvesting. For envlroment I important to use example, simultaneous thermal and irradiation concli1ions arc clifl1cult harvested materials to replicate outs ide of the plant environment. Alternatively, M = Possible with some limitations to Importance of Harvested accelerated aging may nol be feasible for a mechanism scnsi1ivc to replicate service envlroment I Materials over Laboratory Aging dose rate. These two degradation mechanisms may be best moderately important to use harvested evaluated using harvested mlilerials. For unique field aspects, legacy materials materials (e.g., fabrication methods, composition) that are no longer ML= Not challenging to replicate available, but may play an iml)onant role in a polcntial degradation service enviroment / less important to mechanism, would have a higher priority than harvesting materials use harvested materials that can be obtained from other sources wi1h representative L = Very easy to replicate service properties. envlroment I not important to use harvested materials H = All plants There is grcnlcr value in developing knowledge lo uddrcss an issue MH = AIIPWRs Applicability 10 US Operating lhat may be applicable to a larger number of plants compared to one M = Ali BWRs or most PWRs Fleet that may only affect a relat ively small number of plants. ML= 15 plants L = <5 plants H = No or very limited inspection methods available/ low confidence in AMPS If ma1urc inspcclion melhods cxisl and arc easy 10 apply 10 monilor MH = Limited Inspection methods degradation, harvesting may be less valuable. If inspection methods available/ low-to-moderate confidence Regulatory Considerations Related do not exist, harvesting may be essential 10 ensure confidence in the In AMPs to lnspcclions an.d AMPs assessment of age-rcla1ed degradation in thal panicular M = Some inspection methods available component.The less confiden.ce thal NRC staff has in the / mode rate confidence In AMPs effectiveness of the reicvanl AMP, the higher priorily for harvesting. ML= Good inspection methods available/ medium-high confidence In AMPs L = Effective, well-accepted inspection H = Highly irradiated (>5 dpa) Activities with higher costs and complexity are less attractive than MH = Lightly irradiated/ contaminated similar activities wi1h lower costs and that arc simpler to execute .. M = Minimal contamination or high effort Harvesting cost and complexity For example, harvesting unirradiated concrete or electrical cables is unirradiated less expensive and less complex than harvcsling from the RPV ML= Unirradiated, moderate effort intcmals or the RPV. expected L = Unirradiated, low effort expected T he ability of a potential harvesting program to provide timely results Timeliness of results 10 support either a technical or regulatory need is impo11ant. I laving high confidence 1ha1 results will be timely increases the priority. Availability of materials for The availability of materials to harvest for a panicuiar data need is harvesting clearly essenlial and increases lhe priority.
Basic Info TKhnical Criteria Projec t Specific Need Oescrtptlon Purpose / Testing Planned Tec:hnlcal Knowledge Gained Criticalness of Technical Gap A ddn,ssed I lm_portanc:e of Harvested . Materials over Laboratory Aging I A,)plk:a,bllity to US Opcrat ln g Fleet Regulotory Conslderotlons Related to Inspections and AM...
!S core Awe,age l Basis fOf' Technkal Priority Cost I Complexity Timelinesr. of results AvJlfJbllity of materials for harvesting RPV Sco,.. I CCll'l'\l'Mnt Score lComm*nt Scor* ICom,rient Score !Commit11t Score lco........nt The ,esuls WIIOUld betfflely
-I The attenuauon models I they are fl.we the feast amc;lU'l1 of developed This WOf1(. has supportjng infonnation Ma~l isimliciated befOl'e 2024 Of' been done belore W hile lhe infom'l.alion Should be oompared to other aspeds i The attaruatiOn study iS w tueh wm afled al ~ tQ coincide OOl1'>eod- There are ncx many genericalty appricable, il for re&atedk>RPV sightly more imponant to me. aspeas of specimen WICh the W(n Should focus Stu<ies that irradial & 6 ID 9 soma reason, 118 rasutts are ernblituemanl. ~ r. IjuSt because there are fewer preparatiOn and adci~ Oh&r lhan Zion oo higer fluences inches of steel $0, from onty appticabfe 10 *high luence" studies IO Gate have ! such studies that have been 1esting Furtler, inlormatk,n m,nerial$, rm RPV - tigt, ftuence & high MeaSlS'a nuenca. to vedy that he that standpon., getting materials/locations, trus might vaidatedl,e 1don&. a.,g able to confirm lalung specimens at being collected nal aware of shift -..essel with well- I loughless. & chemistry as Through thickness section 10 atten.Jatioo trends specimens from an RPV result in les-s relevance IO lower conservativism of existing ! expected trends at hi9ier several lhrough- from industfy Olher RPVs that eslat>ished urwradiated a funcbon of through- validate iklence & auenuaoon aJq)eCted are ars important tor studying tluence plants (IOCkJding atttenuai.on modets used Il\.lencs ~ would lhef'efore lhlckness locations surviellance are avalabfe for thdme55 position models M main ~- IMH atteruatioo M BWRs). I ML in regulalory applic;lbons. IM Ibe useful. MH wiU increlil$e cost. h.lrvest.lg.
"'""'"'" " I believe that The only real .cfYantage tn :we have as good~
DrOOJ8ffi$ The results I enough data has my rrind for having vessel ccnfid&nce in RPV would betmely been devek>ped material for this study is embf"ittlement than wtually iflheyare from both test and that h:tre are no quesllions ' any other degradation that developed Olhef than Zion Ena!* measurement Qf Provides data supporting 8Yolutm from the use ofoorretaM (Charpy-s<.<Veilooce specmet1s sl..ld'I --""' repres.entatfflllness or a,ny
'we study The criy reaJ
'issue Is making sure that While ifs always usetul to have m<)f"e data, especially on Matanal is irradiated whdl will affect al before 2024 or so to CO!nc:.de material'S, rm not wwa<e al any vttssel Ibolh the Charpy transition RPV
- Samples from viftualy c urve and master curve transition temperabxe TO based) to direct mtta suremen!
(rra<:OKe <oogMesS*based) approaches M thoit the link is wel-es~~~*.... 1:1 lt.t.. le ~r incldi:jitiQn compared to h actual MH Anymoonationdeveloped
...,... be generical~ - b l e l ML
'our un~ nding relll<lins
' appltCabl8 at the t.Qhest ,
M*ML RPV materials. I feel that ow mooe1s seady haYe a good technical basis. MH aspects of specimen preparabOn Md t~sbng. with the additional infnnn,,,,ti,,v,, oiher RPVs that are a v ~ for harve$trlg.
Ba.sic Info Technical Criteria Project Specific Rttul1to,y Con1klent1on1 Cfnl I C9mpluky AvailabUyof I Afipkabililyto us Oparating Reel Nffd Oe.llCription PUl'J)OH / THting Planned T.chl'lical Knowledge Gained Crklc,iinea1 ol Techn~1 knpo,tance ol Harveatec:i Relaled to inspeclionS and score AvaageJ BasiS for T*chnical Priority T imelinus of ~suits materiakfor 1 Gap Ad~Wd llaterlals over l.Jlboratoty AOlng AM. .
..... h11rve11,tin,Q RPV I
I sc... l C-1
/ Score C&MHw~
Score c ....... Scon: Com.,... Allanuation lormula has been used tor ye.n. hide tie beltlioe
--1 RPV-Hviftuence&hgh shift vessel wtth well- Measure~. IOugtr'l~S!I. Thrc>u;ft lhickness section IO estabilhed unin'.diJ!ed & ctoeml~ as 8 hJn::taon lhroug'I-1tdness poMllon
°' Va/kSalea..ieoce&attenuatlon modot. - 1 lhebelline.
ChanoeloH MH ~ in change~Heucside ofbelthne eni:wictle1'!'*11isnoc a'l$pec;teclb" irsaocepleOand behoedoo11Serr.ttNe. and~ i& probaDly lrue. Grwter ~ M$0Ciated VJiih harvested data ouuide ol
... I V..,limited a-c:,13nc dala 11111:ists~e Cl*'haP5 6,:,lants) to RPV- ~ ,
s rom anyvessef W'l.t.iallyl Enable, Measui-t1i'ler'll d bellh lheCN Ira $ition tPf" n a'ld m : ; : : :~Ion
~
Pn;,yid@,s data &UPl)Orq evollaJn fmm theUMofco~ c c ~ based} IOdirecuneawrement (fr.lea-;;,~~~ed) MH H iN,j\ f:<'t'briellef'net'lliSnoc illSpect<<.llor
... O()l'l'lp.ke '> SUl'\ldlien:::-e data- ThOse c.Wa th~I dOexiSI Ol)l'l'lpare tea$0f'l~bt;o wdl, &lo, MYe e ~ e ~a,s,o,ns tor disagreement We haVe lilllept,yslcal reason to eapect
~ e s beerNeen et-pant (ha,Nested) d8&8 and st#W6ence data *- but (B!1 noled)"We haVe flDldlecked In that miMY C8!1.e9.
I I I I Basic Info TK hnical Criteria Proiect Specific Purpose / Tasting Criticalness of Technical Importance of Harvested
- RegulJtory ConsldefilltlonS Cost I Complexity Timelinesr. of AvJlfJbllity of Need Oescrtptlon I Pl __ ...
an,..n1 Tec:hnlcal Knowledge Gained Ga Add p nrssv d M *- . , _._ __. .... a ...na1s over Ld. . . . . . .ory .._ng 6 A,)plk:a,bllrty to US Operating Fleet Related to Inspections 11nd AMPs Score Average Basis fOf' Technkal Priority I resu Its materials for harvesting METALS I I Seo,.. CCll'l'\l'Mnt Score Comm* nt Scor* C ~ n t Seor* Comm.,.t Score Co........nt I Likety extenl of void sweling In Fills data gap fof Laboratory repication very c:iffiajt to impossible IO acljeo,,,e fluences with EPRI p8fforming R&D on NOE fof void swet.,g; MRP-227 u ses prwna,rily visual teWlg, which cot.id I I Significance of void swelting at higher ftuences is uncertain, Very Ngh cost tor I Hm fluence ceoclo< ;,t* mals I p---..,. IASCC I.,,. VOid swelling. meehanieaf PWRs dul'ing extended opeta11on impocl on a-adtina L I.,...,...., extended pla,. I..., I representative inadlatJOn con<ilion,; MH APl)lcabl,e to high-fluence components ;, mo,t PWRs MH detect vOld swell,ng once
. ..., -~ a t MRP-227 requir" V1$Ual and inspectiO(ls may detect 3.75 onset ot ,ignmco'" dog,adali..J VH I.,....,..,
tli!1'1t1 fl'adsated I ITBD FlJence levels may be m pection:s. whi eh can be achieYed by ~ t reactor tonowed by 'o'Olumetric to lrradiabon (e_g_ f urther size flaws. However. laek lnspectJORS are required, tu CGR and FT properties for irradiated:1 SS wield and HAZ materials to ir*>rm I Lil1Je IO no data
,I libut mtdi8tion beZoota welds).
would of most of data above 2 ~ aeates uncertainty on lack of data above 2 dpa creates U'!Oertalnty on H.igh cost for Higher fkJence SS welds (>2 IFracture toughness, I inspedion scope l:Uld inlerval and exist$ on SS welds rep,esenU!tive with ex- anumpliorls for CGR af1d 3ssumptions for CGR ood FT imdclted dl;>a) IASCC. and mic:rostrvca..-el flaw evaluation H above 2 ctpa M I !Uni ma1erials. MH A..nt*ahLP. to most PWRs MH FT ri flaw evalua1o'I. 4 in flaw evaluation H components Would gn,atty irlaease Moderate cost lor Purpose of work woi.*:I be confidenoe in large set of contanwiated, but Thermally aged UWT~ted 1F~ rure toughness ~ Fradllre tougtiness data .n real lconcitionsto compare to I ! Validate
~ a1ed aging I Ito pn:Mde Nlai-wotkl valdation of accelefa:ed MoSI applicable to a subse1 of No ISi method iilVaiable to accelerated aging data with testing o f ~
not irradiated, primary stsem CASS mlaostructure act*atod ~ data riiH data H I anlnn in lab t.ainn M PWRs H mt.asll'e IOSS of FT 4.25 mattrlals M I N'll'IVV'll"l,nts May be pos$ible. but Moderate lluence (1-2 dpa) CASS I Fractute toughness and m 1crostructure I Frac:U'e toughMss data near llfflll ren1lllrinnfurtherevaluation ML Confwm r egulalory posiion ""'
~
effects to repliica;elor'lg* term aging and irradialion M Most appl.cable to a subset of PWRs H No ISi method avMabte to meas~elossofFT Would lncreas~ con6dence ~ 3.5 in>n1..latorvpos111on H Hqtco~f-Ot itradated components Moderate cost tor Determine whether sec mitigabon Purpose d this wed iS to cont.anwiated. but Metallic components with known Haws I NOE and destructive exarrination I meihods ~e effective a1 ~ nialg
$CC. effectiveness of NOE at detedion and sizing fiili v~ridale NOE and rl'llbgabOn method effecriYeness t.e-1 Purpose ol won woi.Ad be to provide l'f:ai-workt vaidation of lab testino H * ~ to al l,:1nts ML assess inspection and mliga_o on method effectiveness Increase COl"lfldence ln NOE 3.75 and ,ni+i,,,"tion methods M not fflld~ted.
prima,y stsem i .....................nts Moderate c:ost lor Metalhc components with li'niting fatiQue life I NOE and destructive examination I Det8ffl'llne w heller fatigue flaws are present in hiQh usa<:1e locations I I Plil-t Validate fatigue ife methodolo(Jies I I t.l.. Pu,pose "'"'°"' to proYido re...world WQ'*I ho vaidation cA lab testioa I I H Appica,ble to all plants I I Ml Fatigue calculat- """" sampling lf'lspections of llirrutinq fa6Que locations I IIncrease CXll"lfidence in fabgUe 3.25 life calculations I I M contan'W'lated. but not md~lod, prima,y stsem comPOnents
Basic Info Techni,cal Crimi.a Project Specific Importance of HarvHte d Regulatory Conskferations Cost I Complexity Timeliness of I Avail.ab ility of Purpo se / Testing Criticalness of Technical Need Description Planned Technical Knowle dge Gained Gap Addressed Materials over Laboratory Applicability to US Operating Fleet I Related to Inspections and Sc ore Average Basis for Priority results materials for Aaino AMPs harvesting ELECTRICAL Low and medlum voltage Score IComment Score IComment Score IComment Score IComment Score !Comment cables Cables ptOlected wrth fira reaardant coating 1E MOVs from harsh and mild enwonmencs tE Air operated valves; 4160 1£ breakats 1E Molded case breakers 480V, 25lN DC, 125 VDC. 1E Relays from mid environment GE - HFA. Aga:stat timing relays, any from Westinghouse, Potier Brumfiekl, Stuther.i Dunn Ietc. Batteries Elecb1cal ,trabons F*e research Interest Electrical endosures Distribution: switchgear, MCCs. LCs I Conltol: Horseshoe. SSCP. AS!=', etc.
Basic Info Technical Criteria Project Specific Importance of Harvested Regulatory Considerations Cost/ Complexity Availability of Purpose / Testing Criticalness of Technical Gap Timeliness of Need Description Technical Knowledge Gained Materials over Laboratory Applicability to US Operating Fleet Related to Inspections and Score Average Basis for Priority materials for Planned Addressed results Aaina AMPs harvestino CONCRETE Score Comment Score Comment Score Comment Score Comment Score Comment Struclures Degradalion of concrete Physical and mechanical H Confirm regulatory H Harvesting is of high M MostPWRs H New aging mechanism 4.5 Very limited data, new aging M Moderate TBD e<posed lo high due lo Irradiation, degradation data under service position. Data available importance because no added for further evaluation mechanism added in SLR* cost for radiation attenuation or radiation environment. Level of lrradaiation from 1970's are not data available from in SLR-GALL and SLR* GALL, SLR-SRP. No moderate through concrete. (neutron, gamma, temperature) representative or light service irradiated SRP. No inspection inspeclion method and OE not level of through the concrete and depth of water reactor (LWR1 concrete, inaccessible method and data available. available because location irradiation on irradiation damage. Aggregate environments. Recent for inspection, limited inaccessable, Safety concrete. expansion, cracking of concrete, limited number of data lab test data, small significance for RPV support differential response of components available from NRAJ are scale lab test structures are critical. or concrete, i.e, aggregate, mortar. representative or LWR specimen. and rebarlsteel embeds and environment . Validate degradation under thermo-hydro* accelerated aging data. radio-mechanical environment due Currently no data to radaition. Conduct NOEs. available from service irradated concrete. Real woMd validation of test data and benchmarto.ing of degradation models. Conduct NDEs. Post-tensioned Degradation of post- ln-~tu internal degraclation, MH Investigate and verify MH Real wortd validation of MH About 37% US NPPs H Concrete internal condition 4.25 Improve confidence on L Unirradiated TSO structures tensioning (PT) system. delamination, adjustment of knowedge related to lab testing, bench containment Is post-tenslOned. is not part of ISi. Limited numerical modelling, potential prestress force and interaction with degradation modes under marking of numerical Also there are a few post- condition monitoring for failure modes, degradations, lnsitu degradation. sustained multi axial modelling, potential tensioned/prestressed SFP. tendon. Oetensioning and and NOEs. Collect critical prestessing force wihoul failure modes, retensioning of tendons of information from failed post, radial rebar, lntemal applicable NOEs. aged containment. tensioned containmnet. degradation, degradation Critical information Effective NOE for PT of prestessing system from failed post* containment structure not including anclhorage, tensioned containmnet. available. NOE methods. Degradation of concrete Ongoing research is providing MH To study in-situ effects of M The knowedge gained H One plant severely affected by M Monitoring for 3.75 Inform adjsutements to aging L Unirradiated An iotemational from Alkali-Silica-Reaction undersanding of the concrete ASR concrete from the current ASR in the US. Because ASR manifestation of ASR is management programs. cooperative (ASR) material damage mechanisms and degradation and research is primarity is a slow evolving chemical part of aging management Enhanced understanding of research program the characterization of that damage comparison with derived from controlled mechanism of the concrete programs for concrete the possibillity of combined is being initiated as well as of its implications to understanding developed laboratory testing itseW and all plants have safety- structures. For structures degradation effects io the f.,ld. under the structural performance. The from laboratory testi'lg. involving controlled related concrete structures. with ASR more complex Assess homgeneity of damage auspices fo the knowledge gained Is primarily To investigate possibility aging environments at monitoring for ASR is part of aging management plans in real structures. CSNI. The derived from laboratory testing of combined aging effects constant environemnts, concrete magement programs would monitor the program will test together with visual observations of such as ASR and homogeneous aging for an concrete structures for progression of ASR, concrete samples field structures. reinforcement corrosion. and single aging iong term oeprations. concrete cracijng. harvested from a mechanism. structural deformations decommissioned and, ff needed, iovotve nuclear power coring and testing of ptant in Canada samples. Study orIn-situ extensively conditions would support affected by ASR. implementation of more The NRC plans to Corrosion of effective aging participate in this reinforcing steel, management plans. program. which is tendon, liner, likely to provide embedment *- *"-
Ex-Plant Materials Harvesting Workshop Location: NRC Headquarters in Rockville, MD, USA Dates: March 7-8, 2017 Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning plants, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated.
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking available materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants Workshop will consist of solicited presentations followed by discussion periods. If interested in attending or learning more about the workshop, please reach out to the contacts below.
Contacts: Robert Tregoning, Robert.Tregoning@nrc.gov Matthew Hiser, Matthew. Hiser@nrc.gov Patrick Purtscher, Patrick.Purtscher@nrc.gov
Ex-Plant Materials Harvesting Workshop Agenda Tuesday, March 7 Session Time Organiz.ation Speaker Presentation Title Michael Weber Intro 8:00 NRC Welcome and Introduction to Workshop Robert Tregoning DOIE Rich Reister DOE Perspectives on Material Harvesting EPRI Sherry Bernhoft EPRI Perspective on Harvesting Projects 8:15- 8:45 NRC Robert Tregoning NRC Perspective on Motivation for Harvesting 1 GRS Uwe Jendrich Role of GRS in Decommissioning and LTO CRIEPI Taku Arai CRIEPI Motivations for Harvest ed Material 8:45-9:45 DISCUSSION 9:45-10:00 BREAK 10:00-PNNL (for NRC) Pradeep Ramuhalli Data Needs Best Addressed By Harvesting 10:20 10:20 - NRC Matthew Hiser High-Priority Data Needs for Harvesting 10:30 10:30- LWRS Program Perspective on the Technical DOIE Keith Leonard 10:55 Needs for Harvesting 2 10:55- Review of past RPV sampling t est programs SCK-CEN Rachid Chaouadi 11:20 and perspective for long term operation 11:20 - Importance of Harvesting to Evaluate Westinghouse Arzu Alpan 11:45 Radiation Effects on Concrete Properties 11:45 - DISCUSSION 12:30 12:30-2:00 LUNCH Sources of Mat erials: Past NRC Harvesting and 2:00- 2:10 NRC Matthew Hiser U.S. Decommissioning Plants Harvesting Plans for Mater ials Aging 2:10 - 2:35 EPRI Al Ahluwalia Degradation Research in Korea and Sweden 2:35- 2:50 DOE/ORNL Tom Rosseel Materials Harvested by the LWRS Program 2:50 - 3:00 DOE/I NL John Jackson NSUF Material Sample Library Gerry van 3:00 - 3:15 Energy Solutions Zion Material Harvesting Program Noordennen 3 Potential Harvesting of Concrete from Mihama 3:15- 3:30 Westinghouse Arzu Alpan Unit 1 3:30 - 3:45 BREAK 3:45-4:00 GRS Uwe Jendrich Plants in Decommissioning i n Germany Evaluating Structures, Systems & Components 4:00-4:15 CNSC Daniel Tello from Decommissioned/Decommissioning Nuclear Facilities in Canada 4:15 - 5:00 DISCUSSION
Wednesday, March 8 Session Time Organization Speaker Presentation Title Lessons Learned: Harvesting and Shipping of 8:00 - 8:30 EPRI Jean Smith Zorita Materials 8:30 - 9:00 DOE Tom Rosseel LWRS Program: Harvesting Lessons Learned NRC Perspective on Harvest ing Experience and 9:00-9:30 NRC Matthew Hiser Lessons Learned CRIEPI Research Activities with Harvested 4 9:30 - 10:00 CRI EPI Taku Arai Materials 10:00 - 10:15 BREAK Energy Gerry van 10:15 - 10:45 Zion Harvesting Experience and Lessons Learned Solutions Noordennen 10:45 - 11:15 Dominion Bill Zipp Kewaunee Insights on Material Harvesting 11:15 -12:00 DISCUSSION 12:00-1:30 LUNCH PNNL (for Technical Information Needed for Informed 1:30-1:45 Pradeep Ramuhalli NRC) Harvesting Decisions 1:45- 2:30 DISCUSSION 2:30-3:00 Action Items and Next Steps 5 EPRI Sherry Bernhoft DOE Rich Reister 3:00-4:00 Closing Thoughts NRC Robert Tregoning ALL
Ex-Plant Materials Harvesting Workshop Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning plants, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated.
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking availlable materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers Workshop Approach:
- Each session will consist of solicited presentations followed by lengthy discussion and Q&A period.
HARVESTING OF AGED MATERIALS FROM OPERATIN G AND DECOMMISSIONING NUCLEAR POWER PLANTS M. Hiser, P. Purtscher, A. B. Hull, R. Tregoning U. S. Nuclear Regulatory Commission, Office of N uclear Regulatory Research Washington, DC Email: matthew.hiser@nrc.gov P. Ramuhalli Pacific Northwest National Laboratory Richland, WA, USA Abstract Recent plans 10 s hut down a number of nuclear power plants (NPPs) provide opportunities for harvesting components that were exposed to actual light water reactor (L WR) environments. Technical issues associated with extended plant operation, such as reactor pressure vessel ( RPV) embrittleme nt, irradiation-assisted degradation of reactor internals a nd primary components, conc re te structures and containment degradation, and electrical cable aging, may be used to focus harvesting efforts on high-priority issues. 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 10 focus on those technical needs with the highest importance and cooperate with multiple organizations whenever possible 10 o ptimally leverage resources. NRC is interested in e ngaging with other organizations 10 prioritize data needs for harvesting, identify areas of common interest, and develop a database for sources of materials for harvesting.
- 1. BAC KGROUND Recent developments in the nuc lear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs). In the U.S., there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) from 60 to 80 years [ I]. Further research may be required to understand age-related degradation throughout the SLR period to he lp ensure that aging management programs are adequate.
U.S. utilities and the U.S. Nuclear Regulatory Commission (NRC) are focused on the aging of systems, structures, and components in four key technical areas: reactor pressure vessel ( RPV) embrittlement, in-adiation-assisted degradation (IAD) of RPV internals and primary components, concrete structures and containment degradation, and electrical cable aging [2]. In recent years, a number ofNPPs, both in the U.S. and internationally, have s hut down or announced plans to s hut down. Unlike in the past when there were very few decommissioning plants, these plant shutdowns provide opportunities for harvesting components that were exposed to actual light water reactor (L WR) environments. Additionally, harvesting programs can be costly and complex. Given these constraints, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future research programs.
- 2. NRC EXPERJENCE WITH HARVEST ING NRC has significant experience with harvesting plant components and performjng research on harvested materials to address technical issues. This experience includes a range of components from plants in various stages of operation both in the U.S. and internationally. Some of the harvesting projects that the NRC has participated in have studied the following materials or components:
- RPV materials from the decommissioned Gundremmingen plant to study fluence rate effects on RPV embrittlement [3],
- Cast austenitic stainless steel (CASS) materials from the decommissio ned Shippingport reactor. to study CASS thermal embrittlement [4],
- RPV materials from the unfirushed or never-operated Shoreham and Midland plants to improve understanding of flaw distributions for RPV embrittlement concerns [5-6],
- RPV bead control rod drive mechanism p enetrations from the operating North Anna and Davis-Besse plants to study primary water stress con-osion cracking (PWSCC) of nickel alloys and the effectiveness of non-destructive evaluation (NOE) methods [8-12),
- Reactor coolant system (RCS) piping nozzle weld materials from the operating V.C. Summer plant to study PWSCC of nickel alloys [ l l-12],
- Reactor internals materials from the decommissioned Jose Cabrera (known as Zorita) plant to study high-fluence irradiation effects on stainless steel reactor internals materials [13),
- Aluminum-based ne utron-absorbing materials from the decommissioned Zion plant to study degradation in the spent fuel pool environment [ 14),
- Electrical cables from the decommissioned Zion and Crystal River plants to investigate cable degradation [ 15),
- Electrical bus ducts from the decommissioned Zion p lant to study high-energy arc faults in electrical enclos ures [ 16].
As illustrated by these programs, NRC's experience is that harvesting has contributed significantly to improved understanding of important technical issues for nuclear safety. For RPV materials, harvesting has increased knowledge of embrittlement mechanisms and the underlying flaw distributions in the RPV to allow reduction in unnecessary conservatism. For nickel alloys, harvesting has improved understanding of PWSCC and the development of acceptable inspection intervals, while also increasing confidence in the ability ofNDE methods to detect and characterize flaws. Finally, recent work on electrical enclosures has helped to identify a potential new safety issue associated with high-energy arc faults in electrical components containing aluminum [ 16).
- 3. N RC PERSPECTIVE AND LESSONS LEARNED FROM HARVESTING ACTIVITIES From NRC's perspective, a principal role of harvesting is to confirm other research res ults from simulated aging conditions. In many s ituations, accelerated aging through higher flux test reactor irradiations or e levated temperatures can be used to generate significant data to understand aging effects in a more cost-effective manner.
Limited harvesting efforts of materials from actual service e nvironments can help confirm the adequacy of the knowledge gained from accelerated agi ng studies, and thus increase the confidence in the broader knowledge base. However, in certain situations, harvesting may be the only practical source of representative aged materials. For example, achieving high tluence levels with representative irradiation conditions through accelerated aging can be very cha llenging. Additionally, it is essential to gain as much information as possible regarding the materials and environment (temperature, llucncc, irradiation conditions, chemistry, humidity, etc.) in advance before committing to a specifi c harvesting project so that the implications of the results from evaluating the materials can be properly understood. Pragmatically, harvesting can be expensive, complex, and time-consuming; therefore, focusing o n technical needs of high importance will help ensure good value. Likewise, leveraging and cooperation among multiple organizations helps to mitigate cost cha llenges. It is a lso quite c hallenging to transport irradiated materials, particularly internationally, so minimizing or avoiding transportation of irradiated materials is highly recommended.
- 4. NRC ACTIVITIES ON HARVESTING NRC is potentially interested in harvesting materials to assess age-related degradation in the four technical areas identified previously: RPV embrittlement, lAD of RPV internals and primary components, concrete structures and containment degradation, and electrical cable aging [2). The focus is to unders tand the impact of extended plant operation on material behavior, including the effects of higher fluences and longer exposures to aging conditions.
NRC has recently undertake n an effort, with the assistance of Pacific No1thwest National Laboratory (PNNL), to develop a strategic approach for harvesting aged materials from NPPs. Past harvesting activities have been narrowly focused on the relatively few oppo1tunities to get materials from decommiss ioning plants. Given the expected availability of materials from numero us plants and identified research needs to better understand aging out to 80 years of operation, the N RC is developing a more proactive approach to prioritize the data needs best addressed by harvesting and identify the best sources of materials to address high-priority data needs for regulatory research.
- 5. PRIORITIZATION OF DATA NEEDS BEST ADDRESSED BY HARVESTING The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario ( i.e., combination of material and environment) and should be defined with as much detail as appropriate in terms of the material (e.g., a lloy, composition) and environment (e.g., temperature, fluence, chemistry).
A number of criteria are being considered for prioritizing the harvesting data needs, including:
Applicability of harvested material for addressing critical gaps
- Harvesting to address critical gaps shouJd be prioritized over less essential technical gaps Ease of laboratory replication of the degradation scenario
- Degradation mechanisms that are harder to replicate with simulated aging conditions would be of higher priority for harvesting. For example, simultaneous thermal and irradiation conditions are difficult to replicate outside of the plant environment. Alternatively, accelerated aging may not be feasib le for a mechanism sensitive to dose rate. These two degradation mechanisms may be best evaluated using harvested materials.
Unique field aspects of degradation
- For example, legacy materials (e.g., fabrication methods, composition) that are no longer available, but may play an important role in a potential degradation mechanis m, would have a higher priority than harvesting materials that can be obtained from other sources.
Fleet-wide vs. plant-specific applicability of data
- There is greater value in developing knowledge to address an issue that may be applicable to a larger number of plants compared to one that may only affect a relatively small number of plants.
Harvesting cost and complexity
- Activities with higher costs and complexity are less attractive than similar activities with lower costs and that are simpler to execute.. For example, harvesting unirradiated concrete or electrical cables is less expensive and less complex than harvesting from the RPY internals or the RPY.
Availability of reliable inspection methods for the degradation scenario
- Jf mature inspection methods exist and are easy to apply to monitor degradation, harvesting may be less valuable. If inspection methods do not exist, harvesting may be essential to ensure confidence in the assessment of age-related degradation in that particular component.
Timeliness of the expected research results
- The ability of a potential harvesting program to provide timely results to s upport either a technical or regulatory need is important. Having high confidence that results will be timely increases the priority.
Availability of materials for harvesting
- The availability of materials to harvest fo r a particular data need is clearly essential and increases the priority.
The above potential criteria provide a systematic approach for prioritizing harvesting data needs. Different organizations may weigh these criteria differently, but the criteria are intended to be comprehensive. NRC is interested in engaging with other organizations to further refine these criteria, use them to prioritize data needs for harvesting, and ultimately identify areas of common interest that may provide optimal harvesting opportunities.
- 6. DATABASE OF SOURCES OF MATERIALS FOR H ARVESTING NRC is interested in engaging with other organizations to develop a database that identifies sources of materials for harvesting. This database would include both previously harvested materials and those which may be available for future harvesting. This database would be used to align the high-priority harvesting needs to the available materials. As with the harvesting prioritization effort, the level of detail for the sources of materials database should be appropriate for the factors influencing decision-making.
- 7. CONCLUSIONS NRC's experience is that harvesting can y ie ld highly representative and valuable knowledge about materials aging. However, these efforts may be expensive and challenging. Having a clearly defined objective and early engagement with other stakeholders, including the decommissioning plant where harvesting will take place, arc necessary to ensure project success. As specific harvesting opportw1ities are identified through this strategic approach, the NRC will develop strategies for pursuing these opportunities. The NRC also welcomes collaboration from other interested research organizations both in developing the proactive harvesting strategy and in pursuing harvesting opportunities of mutual interest.
REFERENCES [I] REMER, S. J., "NRC Commissioner Briefing on Subsequent License Renewal," NRC Commission meeting on April 26, 2017, https://www.nrc.gov/ reading-rm/doc-collections/commission/slides/20 I7/20170426/remer-20170426.pdf. [2] U.S. NUCLEAR REGULATORY COMMISSION, "Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal," SECY- l 4-0016, 2014, https://www.nrc.gov/docs/ML 1405/ML I 40SOA306.pdf. [3] HAWTHORNE, J.R., HISER, A.L., "Experimenta l Assessments of Gundremmingen RPV Archive Material for Fluenee Rate Effects Studies," NUREG/CR-5201 (MEA-2286), U.S. Nuclear Regulatory Commission, October 1988. [4] CHOPRA, O.K., SHACK, W.J., "Mechanical Properties of Thermally Aged Cast Stainless Steels from Shippingport Reactor Components," NUREG/CR-6275 (ANL-94/37), U.S. Nuclear Regulatory Commission, April 1995. (SJ SCHUSTER., G. J., DOCTOR, S. R., CRAWFORD, S.L., PARDINl , A. F., "Characterization of Flaws in U.S. Reactor Pressure Vessels: Density and Distribution of Flaw Indications in the Shoreham Vessel," NUREG/CR-6471 Volume 3, U.S. Nuclear Regulatory Commission, November 1999. [6] SCHUSTER, G. J., DOCTOR, S. R., PARDIN I, A.F., CRAWFORD, S.L., "Characterization of Flaws in U.S. Reactor Pressure Vessels: Validation of F law Density and Dis tribution in the Weld Metal of the PVRUF Vessel," NUREG/C R-647 1 Volume 2, U.S. Nuclear Regulatory Commission, August 2000. [7] MCCABE, D.E., ET AL., "Evaluation ofWF-70 Weld Metal From the Midland Unit I Reactor Vessel," NUREG/C R-5736 (ORNL/TM- 13748), U.S. Nuclear Regulatory Commission, November 2000. [8] CUMBLIDGE, S.E., ET AL., "Nondestnictive and Destnictive Examination Studies on Removed-from-Service Control Rod Drive Mechanism Penetrations," NUREG/C R-6996, U.S. Nuclear Regulatory Commission, July 2009. [9] CUMBLIDGE, S.E., ET AL., " Evaluation of Ultrasonic Time-of-Flight Diffraction Data for Selected Control Rod Drive Nozzles from Davis Besse Nuclear Power Plant," PNNL-19362, Pacific Northwest National Laboratory, April 20 11. [ IOJ C RAWFORD, S. L., ET AL., "UltTasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Validation," NUREG/CR-7142 (PNNL-2 1547), U.S. Nuclear Regulatory Commission, August 20 12. [II] ALEXANDREANU, B., C HOPRA, O.K., SHACK, W.J ., "Crack Growth Rates in a PWR Environment of N ickel Alloys from the Davis-Besse and V.C. Summer Power Plants," NUREG/CR-6921 (ANL-05/55), U.S. Nuclear Regulatory Commission, November 2006. [12] ALEXANDREANU, B., CHOPRA, O.K., SHACK, W.J., "Crack Growth Rates and Metallographic Examinations of Alloy 600 and Alloy 82/ 182 from Field Components and Laboratory Materials Tested in PWR Environments," NUREG/CR-6964 (ANL-07/ 12), U.S. Nuclear Regulatory Commission, May 2008. [13] BURKE, J. "Characterization of Irradiation-Assisted Degradation of Reactor Internals Materials," IAEA CRP Coordinated Research Meeting, 2014, Vienna, Austria, https://www.nrc.gov/docs/ML 14 l 5/ML 14 l 53A403 .pdf. [J 4] U.S. NUCLEAR REGULATORY COMMlSSJON, "Acquisition and Testing of Zion Spent Fuel Pool Neutron Absorber Materials," Addendum to Memorandum of Understanding between NRC and EPRI, 2014, https://www.nrc.gov/docs/ML 1501/M L I 50 15A02 I .pdf. [ 15] FIFI ELD, L.S., "Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant," PNNL-25833 , September 2016. [ 16] GI ITTER, J. G., Path Forward for Regulatory Treatment of High-Energy Arcing Fault Tests Results that Involve Aluminum," Internal NRC memo, March 2016, https://www.nrc.gov/docs/ML 1606/ML I 6064A250.pdf.
'Annual NRC/EPRI MOU Review Meeting- May 30, 2018 Proposed RES/DE Topics
- 1. Ex-Plant Materials Harvesting
- a. NRC and EPRI have cooperated effectively on several materials harvesting programs, including the reactor internals from Zorita. NRC hosted an ex-plant materials harvesting workshop in March 2017 that was attended by EPRI, DOE and international parties, which provided valuable insights and feedback on best practices and lessons learned from past harvesting efforts.
- b. NRC is priorit1izing data needs for harvesting and collecting information on available sourrces of materials (including operating and decommissioning plants as well as previously harvested materials that we have previously used in NRC-sponsored research activities) to ensure the best value for research on harvested materials.
- c. NRC is interested in engaging with EPRI on their priorities for harvesting and how to achieve the best value in pursuing harvesting opportunities, including leveraging and cooperation .
- d. If EPRI and NRC management are aligned, informal coordination and dialogue will be pursued that could be formalized through MOU addenda or cooperative agreements for any specific research activities that result.
ACTION: Work proactively with EPRI to identify harvesting opportunities in metals, concrete and cables to ensure the best resource leveraging. We propose developing an MOU addendum or cooperative agreement to achieve this outcome.
- 2. Test Reactors and Irradiated Materials Testing (New topic in response to the evolving status of the Halden Reactor)
- a. NRC is performing a strategic review of options for test reactor irradiation and irradiated materials testing capabilities, particularly in light of the potential shutdown of the Halden Reactor.
- b. NRC and EPRI cooperation on the Zorita materials research has been effective for leveraging resource-intensive testing of highly irradiated reactor internals materials.
- c. NRC is interested in further opportunities for leveraging and cooperation with EPRI for test reactor irradiation and irradiated materials testing capabilities, particularly if currently planned efforts at Halden are not able to be completed.
- d. If EPRI and NRC management are aligned, informal coordination and dialogue will be pursued that could be formalized through MOU addenda or cooperative agreements for any specific research activities that result.
ACTION: Actively conduct contingency planning with EPRI to identify the most viable option(s) for the structural material testing that is currently planned under the Halden Research Project. A cooperative agreement or MOU addendum may be proposed to implement the most viable option identified during the planning phase.
- 3. Advanced Manufacturing, including Additive Manufacturing (30 printing)
- a. NRC and EPRI are separately investigating advanced manufacturing techniques that may be applied in operating reactors to produce replacement parts, or in new and advanced reactors to produce novel components.
- b. NRC hosted a public workshop on additive manufacturing (AM) in November 2017 that was attended by EPRI, DOE, and numerous other organizations. The meeting scope included standardization activities, AM research and applications in nuclear and other industries, AM processes and capabilities, and technical and regulatory challenges.
- c. EPRI staff (Dave Gandy) provided NRC with an overview of a DOE-supported demonstration project to produce a 2/3-Scale reactor pressure vessel for a small modular reactor (SMR) using advanced manufacturing with goals of reducing both cost and manufacturing cycle time. The processes employed were powder metallurgy with hot isostatic pressing (PM-HIP), electron beam welding (EBW),
and diode laser cladding (DLC).
- d. NRC is interested in engaging with EPRI on addressing technical and regulatory challenges to adoption of advanced manufacturing techniques. If EPRI and NRC management are aligned, informal coordination and dialogue will be pursued that could be formalized through MOU addenda or cooperative agreements for any specific research activities that result.
ACTION: NRC is starting to develop an agency plan (or roadmap) on AM that will identify research needs. If EPRI has plans to develop a similar roadmap, NRC would like to coordinate with EPRI to ensure that the research planned within each organization is aligned and focused on developing a sufficient technical basis to support implementation of AM within the nuclear fleet. This collaboration could be performed informally or through separate agreements or MOU addenda. It is envisioned that, once the roadmaps are developed, there may also be specific research activities that could be jointly pursued by separate agreements or an MOU addenda.
- 4. Application of Extended Finite Element Method (xFEM)
- a. NRC is developing a research project to explore the applicability Extended Finite Element Method (xFEM) to predict PWSCC crack growth in 30 component geometries., The xFEM technique has several advantages over conventional FEM technique, namely:
- Mesh-independent analysis of flaws
- SIF calculation of multiple cracks shapes without major changes to model
- 30 crack growth without re-meshing
- b. NRC is also participating in international effort on benchmarking of xFEM capabilities. (OECD-CSNI)
- c. The ACRS FY18 biennial review report of research program recommended RES to further explore the applicability of xFEM.
ACTION: NRC would like to engage EPRI in an effort to benchmark the xFEM application to PWSCC crack growth analyses. 2
Note to requester: Attachments From: Moyer, Carol to this email immediately follow. Sent: Thursday, May 18, 2017 12:31 PM To: Martinez Rodriguez, Erick
Subject:
Draft Talking Points for Brian Thomas for EPRI_R3.docx Attachments: Draft Talking Points for Brian Thomas for EPRI_R3.docx; RE: Draft Notes for EPRI mtg 6/6 Hi Erick, The attached file is a work-in-progress, in which I am collecting high level talking points for Brian Thomas for the 6/6 EPRI meeting. I am hoping to compare notes with you, in case you have received input from others. Does the level of detail seem about right? (See Raj's note, attached.) Steve asked me to provide a draft file to Brian today, so I am working to that. Thank you, Carol
Draft Talking Points for Brian Thomas for EPRI-NRC Meeting (6/6/2017} 9:30 AM - Long Term Operation {LTO) Beyond 60 Years, Subsequent License Renewal
- The MOU for Long Term Operations Beyond 60 Years extends through Sept., 2021
- NRC appreciates EPRl's active participation in the April Commission briefing
- Biweekly coordination calls (EPRI/NRC/DOE) are successful Progress and readiness for SLR applications
- As reported at the April 261h Commission briefing, NRC is ready to accept applicatio ns.
- Confirmatory research continues, to reduce uncertainty associated with key technical issues.
Public workshop on SLR topics
- At least two workshops are proposed, to include domestic and international participants.
- Fall 2018- Focused on reactor pressure vessels, vessel internals, and piping
- Spring 2020 - Focused on concrete and electrical cable degradation
- Proposed scope of the workshops:
o State of knowledge o n the technical issues o Status of on-going research on materials degradation and aging management o New operating experience with implications for LR and SLR Technical reports on continued adequacy of RG 1.99
- .. .[CIB input]
Highlights of harvesting workshop
- Workshop well-attended by DOE, EPRI, NRC, US industry, and international participants.
Participants discussed the motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting and future harvesting program planning. o Workshop discussion emphasized the need for a clearly defined objective to justify the level of effort and demonstrate value. o Past harvesting experience shows valuable technical information can be gained, but harvesting efforts are expensive and complex.
- Workshop summary report will be shared among meeting participants (target: 6/30/17).
Future activities from the workshop include cooperative discussion of prioritized data needs for harvesting and potent ial development of a sources of materials database. Research priorities for 2017-2018 10:45 -Advanced Reactor Safety Research Draft Talking Points for Brian Thomas for EPRI_ R3.docx 11/08/19 11 :37
IAP status
- RES/DSA is supporting IAP-2 o Strategy 2: Acquire/develop sufficient computer codes and tools to perform non-LWR regulatory reviews
- RES/DE is supporting IAP-2 and IAP-4 o Strategy 2: Acquire/develop sufficient computer codes and tools to perform non-LWR regulatory reviews, Functional Area - Materials and component integrity o Strategy 4: Facilitate industry codes and standards needed to support the non-LWR life cycle (including fuels and materials)
Computational codes for non-LWRs
- ... [DSA iput]
Advanced manufacturing
- Advanced processes, such as additive manufacturing (30 printing), diffusion bonding, friction-stir welding, electron beam (EB) welding, and powder metallurgy (PM/HIP) have been proposed for use in new reactors.
- Benefits include reduced number of welds/joints, reduced machining waste, reduced time to manufacture, and ability to join metals that are difficult to weld conventionally.
- Some advanced manufacturing processes may introduce uncertainty.
o Material properties need to be confirmed (e.g., PM/HIP vs. forged flanges). o Different inspections (pre-service and in-service) may be needed. o Components may be susceptible to flaw types or degradation mechanisms previously unseen in LWRs. Gen IV materials
- RES/DE (and NRO) staff are participating in ASME B&PV Code committees working on high temperature materials needed for some advanced reactor designs.
o Alloy 617 o Graphite
- ASME Code is also seeking to expand the temperature range for use of some materials by supplying confirmed materials property data under a broader range of test conditions.
- NRC is collaborating with DOE-NE to avoid surprises in material selection and the establishment of technical bases for the use of newer materials and processes .
11 :15 - xLPR and Leak-Before-Break (LBB) Analyses Draft Talking Points for Brian Thomas for EPRI_ R3.docx 11/08/19 11 :37
- ... [CIB input]
Current status of MOU development 2:00 - Digital Instrumentation & Control Collaboration
- ... [ICEEB input]
Progress during previous year Priorities for 2017-2018 Draft Talking Points for Brian Thomas for EPRI_ R3.docx 11/08/19 11 :37
Subsequent License Renewal (SLR} Research Activities Key Messages
- Research is being conducted by the Nuclear Regulatory Commission to confirm safe operation of nuclear power plants as they age particularly beyond the first extended operating period and into subsequent license renewal (SLR).
- Significant progress has been made in addressing the key technical issues pertinent to the aging management of systems, structures and components in nuclear power plants.
- The NRC staff continues to cooperate with the industry, Department of Energy (DOE),
and Electric Power Research Institute (EPRI) to leverage research to ensure that aging effects will be adequately managed during the 60 to 80 year operating period. Facts
- The NRC staff is performing the necessary confirmatory research to support timely and efficient reviews of future SLR applications, including the assessment of reactor structural components that could deteriorate due to material degradation resulting from extended exposure to elevated temperatures, pressures, neutron irradiation, stress, and corrosive media.
- NRC research activities will likely continue for at least 5 years in some of the technical areas, with periodic r,eviews to consider whether the available information is adequate to support the development of generic aging management guidance.
- Near-term confirmatory research efforts will support staff reviews of initial SLR applications.
- Longer-term confirmatory research will augment the technical basis for updating regulatory guidance in the future, as necessary, and inform staff reviews of future SLR applications.
- NRC research supports the safety basis of ongoing revisions to the aging management programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSCs) by enhancingi our understanding of the causes and how to control of degradation mechanisms.
- RES staff is collaborating with EPRl's Long-Term Operations (LTO) program and DOE's Light Water Reactor Sustainability (LWRS) staff on SLR-related research topics (reactor pressure vessel (RPV) embrittlement, irradiation-assisted damage in reactor internals, concrete degradation, and cables qualification and condition assessment).
RES - SLR One Pager- May 2 2017.docx
NRC Readiness for Advanced Reactors (Non-LWRs) Key Messages
- The NRC can review and license new non-LWR designs using the existing re,gulatory framework but is working to improve processes to support effective, efficient and predictable regulatory review activities.
- The NRC is planning and proactively implementing activities in three focus areas to prepare for the effective, efficient and predictable review of non-LWR designs:
enhancing technical readiness, optimizing regulatory readiness, and optimizing communications.
- In the near term (0-5 ye,ars), the NRC is focusing on technology-inclusive activities commensurate with the pace of non-LWR technology development and maturity.
Facts
- Vendors and applicants are responsible for providing sufficient research and documentation to support their safety case, including the identification and resolution of new design issues.
- Challenges have been faced with new vendors due to limited familiarity with the regulatory process and potential vendor budget constraints. The NRC is addressing these challenges through public meetings with the vendors and various industry groups to provide information on the regulatory process and to gain insights into the challenges the vendor community is encountering or anticipating.
- The NRC and DOE have developed plans that describe their respective vision and readiness strategies to support the efficient development, licensing, and deployment of non-LWRs.
o The NRC's vision and strategy document was issued for public comment in July 2016 and was finalized in December 2016. o To execute the NRCs readiness strategy, draft implementation action plans have been developed for the near-term (0-5 years), mid-term (5-1 0 years) and long-term (>10 years)
- The NRC is enhancing its existing regulatory framework to address non-LWRs in a technology neutral manner, which include:
o Development of advanced, non-LWR design criteria. o Developing a conceptual design review process to give vendors regulatory feedback at an early design phase. o Developing a staged review process to allow vendors to get regulatory review at pace with their funding needs. o Developing prototype guidance.
- The NRC is working with DOE to implement a process for providing accurate and current information to DOE in support of the Gateway for Accelerated Innovation in Nuclear (GAIN) initiative under and MOU signed on November 10, 2016.
- The NRC is pursuing outreach activities to educate new vendors on the regulatory process.
The NRC and DOE initiated the Advanced Non-LWR Workshop series to proactively reach out, educate, and interact with as many vendors and stakeholders as possible. A third workshop was held on April 25 and 26, 2017. Adv_Rx_ Readiness_3-31-2017 .docx
Non-Light Water Reactor (Non-LWR) Regulatory Framework Development Key Messages
- The NRC can review and license new non-LWR designs using the existing regulatory framework but is working to improve processes to support timely and efficient licensing activities.
- The NRC and its predecessor agency, the Atomic Energy Commission (AEC), have significant historical experience with non-LWR designs.
- The NRC is enhancing its existing regulatory framework to address non-LWRs in a technology neutral manner as part of its Vision and Strategy for Safely Achieving Effective and Efficient Non-Light Water Reactor Mission Readiness.
- The NRC is collaborating with international counterparts on regulatory approaches to non-LWRs.
Facts
- The AEC reviewed and licensed designs dating back to the construction and operation of the first experimental breeder reactor in 1951 and the establishment of an experimental reactor program in 1954.
- The NRC has not licensed a commercial non-LWR for construction or operation, however, the NRC did review a variety of conceptual designs, at varying levels of detail, between 1978 (Hanford Fast Flux Test Reactor) and 2010 (pebble bed modular reactor (PBMR) and General Electric-Hitachi (GEH) PRISM).
- More recently, in February 2016, the NRC reviewed and approved a construction permit for a new and innovative medical isotope production facility submitted by SHIN E Medical Technologies, Inc. (the "SHINE" facility). This project demonstrated the NRC's ability to review new and innovative facility designs.
- The NRC is enhancing its existing regulatory framework to address non-LW Rs in a technology neutral manner as part of its Vision and Strategy for Safely Achieving Effective and Efficient Non-Light Water Reactor Mission Readiness.
- The NRC has begun hosting a series of public meetings with non-LWR stakeholders to gain feedback on various regulatory framework activities. Examples of the regulatory framework activities discussed include:
o Developing a conceptual design review process to give vendors regulatory feedback at an early design phase. o Developing a staged licensing process for innovative designs within the current licensing framework. o Developing guidance on prototype licensing and testing. o In advance of the October meeting, the NRC's draft "Regulatory Review Roadmap for Non-Light Water Reactors" was released to facilitate stakeholder discussion and feedback at the meeting.
- The staff also actively participates with our international counterparts as chairs of the NEA working group on regulatory approaches to non-LWRs (focusing on sodium-cooled fast reactors) and in the IAEA Gen-IV international forum (GIF) activities.
Adv_Rx_ Framework_3-31-2017.docx
From: Iyengar Raj To: Moyer Carol Cc: Frankl Istvan; Martinez Rodriguez Erick Subject : RE: Draft Notes for EPRI mtg 6/6 Date: Thursday, May 18, 2017 9:22:09 AM Update from the AM meeting (per Office TA) : Talking points at a high-level (only strategy and vision) - Programmatic details could be addressed later through other exchanges. From: Moyer, Carol Sent: Thursday, May 18, 2017 9:15 AM To: Iyengar, Raj <Raj .lyenga r@nrc.gov> Cc: Frankl, Istva n <lstvan.Frankl@nrc.gov>; Martinez Rodriguez, Erick <Erick. MartinezRodriguez@ nre.gov>
Subject:
RE: Draft Notes for EPRI mtg 6/6 OK, thank you, Raj. From: Iyengar, Raj Se nt: Thursday, May 18, 2017 9:12 AM To: Moyer, Carol <CaroLMoyer@nrc.gov> Cc: Frankl, Istva n <lstvan.Frankl@nrc,goy>; Martinez Rodriguez, Erick <Erick. MartioezRodriguez@ore.gov>
Subject:
RE: Draft Notes for EPRI mtg 6/6
- Carol, I have a number of things to do today. I will see what I can do.
CMB can provide its input to Erick. I can add to it later, if needed. GIB staff has already developed one-pagers for RG1 .99 and xLPR. The topics on Adv. Man. And Gen IV materials come from EPRI. EPRI will be providing brief to our management on those two topics. I have a meeting with Steve Bajorek on IAP 2. I will ask him what Mike Case wants. As you know that topics on IAPs is led by Mike Case. We can certainly provide Brian some talking points on our efforts. Raj From: Moyer, Ca rol Sent: Wednesday, May 17, 2017 6:17 PM To: Iyengar, Raj <Raj.lyengar@nrc gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Martinez Rodriguez, Erick <Erick MartjnezRodriguez@ore.gov>
Subject:
Draft Notes for EP RI mtg 6/6 Importance: High
- Raj, I have been drafting some notes for the EPRI -NRC management meeting on 6/6, but I don 't want to duplicate your efforts on this. Can we combine what we have collected so far, and then see what is missing?
There are topics here that clearly fall within CIB's scope, e.g., RPV embrittlement (RG 1.99), and some that belong to Ian's branch . Also, I let Steve Bajorek know that I would draft some notes on Advanced Reactors, but that I would be looking to him to fill in status on the computational codes. Steve let me know that Brian would like to see draft notes by Thursday (tomorrow), so I hope that we can discuss this in the morning.
- 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. mover@nrc.gov 301-415-2153
Note to requester: Attachments to this email immediately follow. From: Hull, Amy Sent: Monday, February 06, 2017 3:40 PM To: Moyer, Carol Cc: Frankl, Istvan (lstvan.Frankl@nrc.gov)
Subject:
Carol: please review & revise, Main Take-Aways: Subsequent License Renewal Research Presentation to Bill Dean Categorie s: Strategic R&D ex- plant materials Steve suggested I t k to ~o! about this. I will bring over a copy of his markup. I can work on this again tomorrow but must . soon today. (b)(6) RES*SLR* Slides* ... From: Hull, Amy Se nt: Monday, February 06, 2017 8:27 AM To: Frankl, Istvan (lstvan.Frankl@nrc.gov) <lstvan.Frankl@nrc.gov> Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov> Subject : please review & revise, Main Take-Aways: Subsequent license Renewal Research Presentation to Bill Dean Brian Thomas and Raj Iyengar gave an overview of "Subsequent License Renewal Research Activities" coauthored with Amy Hull and Rob Tregoning. Shortly after 1pm, conference room OWFN-13D20 was full. Attendees included (among others) Bloom. Steve Dean, Bill Evans, Michelle iJ Jan 12 Key TakeAways.docx Frankl, Steve Hull, Amy Iyengar , Raj Thomas, Brian Tregoning, Rob Wilson, George In response to his introduction, Bill Dean asked about what additional insights we had gained from interim AMPs (abh note, I think he was referring to LR-ISGs). In response to the discussion on vessel internals, Bill Dean also had comments about the stat.us of MRP-227A (which is relevant to PWR internals, AMP XI.M16A) and UT capabilities related to baffle-former bolts. In response to the discussion on concrete degradation, Bill Dean had concern about the expense to NRC of ASR research when Seabrook is the only American NPP experiencing this problem. He wondered if this was 1
an appropriate use of money and wanted to know more about other ASR work, over and beyond that being done by NRC and in the USA (Abh note, I attended several ASR sessions at SMliRT-23 in Manchester, England and can help prepare an answer for Bill Dean). In response to the discussion on cable qualification and condition assessment, George Wilson wanted to have a discussion about the scope of the NRC test plan. This followup discussion was held the week of January 23rd_ In response to the discussion on collaboration, Bill Dean would like to have more specific information and comparison about what various domestic and international collaborations provide to NRC. In response to the final slide "Look Ahead' Bill Dean expressed most interest in the ex-plant materials harvesting workshop and wanted to make sure it also addressed cables. General observations that were made by NRR managers included: They want specific budget requests related to SLR research. What is the schedule of the research? What research is done? What still needs to be done? What research needs to be completed before the first SLR applications? Distinguish better between near-term and long-term research. Bill De*an stressed that industry "must carry the water" and in conclusion asked how DE/RES would characterize the priority for further research in the four areas discussed. Rob verbally gave the following summary explaining priority for additional research in terms of technical and programmatic needs. TOPIC TECHNICAL PROGRAMMATIC Reactor Pressure Vessel Embrittlement low low Vessel Internals low hiah Concrete Deqradation medium Low- medium Cable Qualification and Condition Monitorinq hiqh hiqh
Original Appointment-----
From: Dean, Bill Sent: Friday, December 16, 2016 1:36 PM To: Dean, Bill; Frankl, Istvan; Hull, Amy; RES_DE_Cal Resource; Bloom, Steven; Wilson, George; Marshall, Jane; Thomas, Brian; Brock, Kathryn
Subject:
FW: Subsequent License Renewal Research When: Thursday, January 12, 2017 1:00 PM-1:45 PM (UTC-05:00) Eastern Time (US & Canada). Where: NRR-OWFN-13D20-15p
-----Original Appointment-----
From: Dean, Bill Sent: Friday, December 16, 2016 1:31 PM To: Dean, Bill; Bloom, Steven; Wilson, George; Marshall, Jane; Thomas, Brian; Brock, Kathryn
Subject:
Subsequent License Renewal Research When: Thursday, January 12, 2017 1:00 PM-1:45 PM (UTC-05:00) Eastern Time (US & Canada). Where: NRR-OWFN-13D20-1Sp POC: Steve x 2431 2
Prior to Research discussion with Glen Tracy 3
Brian Thomas and Raj Iyengar gave an overview of "Subsequent License Renewal Research Activities" coauthored w ith Amy Hull and Rob Tregoning. Shortly after 1pm, conference room OWFN-13D20 was full. Attendees included (among others) Commented (HA1]: Please add names of other Bloom. Steve attendees, l did not document, I think Dennis Morey was Dean, Bill there, and maybe other OLR BCs. Evans, Michelle Frankl, Steve Hull, Amy Iyengar, Raj Thomas, Brian Tregoning, Rob Wilson, George In response to his introduction, Bill Dean asked about what additional insights we had gained from interim AMPs (abh note, I think he was referring to LR-ISGs). In response to the discussion on vessel internals, Bill Dean also had comments about MRP-227A (which is relevant to PWR internals, AMP XI.M16A) and UT capabilities related to baffle-former bolts. In response to the discussion on concrete degradation, Bill Dean had concern about the expense to NRC of ASR research when Seabrook is the only American NPP experiencing th is problem. He wondered if this was an appropriate use of money and wanted to know more about other ASR work, over and beyond that being done by NRC and in the USA. (Abh note, I attended several ASR sessions at SMliRT-23 in Manchester, England and can help prepare an answer for Bill Dean). In response to the discussion on cable qualification and condition assessment, George Wilson wanted to have a discussion about the scope of the NRC test plan. This followup discussion was held the week of January 23rd. Commented (HA2): Please confirm and add a couple lines if needed since I did not attend this meeting. In response to the discussion on collaboration, Bill Dean would like to have more specific information and comparison about what various domestic and international collaborations provide to NRC. In response to the final slide "Look Ahead" Bill Dean expressed most interest in the ex-plant materials harvesting workshop and wanted to make sure it also addressed cables. General observations that were made by NRR managers included: They want specific budget requests related to SLR research. What is the schedule of the research? What research is done? What still needs to be done? What research needs to be completed before the fi rst SLR applications? Distinguish better between near-term and long-term research. Bill Dean stressed that industry "must carry the water" and in conclusion asked how DE/RES would characterize the priority for further research in the four areas discussed. Rob verbally gave the following summary explaining priority for additional research in terms of technical and programmatic needs. TOPIC TECHNICAL PROGRAMMATIC Reactor Pressure Vessel Embrittlement low low Vessel Internals low hiah Concrete Dearadation medium Low - medium Cable Qualification and Condition Monitorinq hiqh hiqh
U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment Subsequent License Renewal Research Activities Briefing for Bill Dean Director Office of Nuclear Reactor Regulation January 12, 2017 Brian Thomas Raj Iyengar Amy Hull Rob Tregoning
Outline U.S.NRC United Stares Nuclear Regu latory Commission Protecting People and the Environment
- Key Messages
Background:
- RES is addressing key technical issues and supporting the development of draft SLR Guidance Documents
- Ongoing RES Support
- Collaboration & Outcomes
- Site Visits
- LookAhead 2
ey Messages U.S.NRC United Stares Nuclear Regu latory Commission Protecting People and the Environment
- The key technical issues for research are as identified in Staff Requirements Memorandum (SRM) on SECY-14-0016 (August 29, 2014; ADAMS Accession No. ML14241A578)
- reactor pressure vessel neutron embrittlement at high fluence
- Irradiation-assisted stress corrosion cracking of reactor vessel internals
- concrete degradation, and
- electrical cable qualification and condition assessment
- In response to the SRM, there has been significant progress in addressing the key technical issues:
- Accomplished through increased leverage with DOE and EPRI through "deep-dive:
meetings (cables aging; concrete degradation; vessel internals; non-destructive examination (NOE) of buried pipes)
- Extensive collaboration with EPRI and DOE on SLR-related research topics
- Progress resulted in enhanced aging management programs (AMPs) addressed in the draft SLR guidance documents.
3
ey Messages (Continued) U.S.NRC United Stares Nuclear Regu latory Commission Protecting People and the Environment
- Research objectives focused on FY2018/2019 (expected time period for initial SLR applications)
Continue research recognizing two periods:
- Near-term to support review of initial SLR applications
- Longer-term to augment the technical basis for further updates to SLR guidance Slide Notes for Slides 3 and 4: Key Messages SRM: "The staff should keep the Commission informed in resolving the following technical issues related to SLR reactor pressure vessel neutron embrittlement at high fluence; irradiation assisted stress corrosion cracking of reactor internals and primary system components; concrete and containment degradation, and electrical cable qualification and condition assessment."
The staff should continue to emphasize in communications with industry the need to strive for satisfactory resolution of these issues prior to the NRC beginning a review of any SLR application. 4
Background U.S.NRC United Stares Nuclear Regu latory Commission Protecting People and the Environment NRR-RES team effort informed the development of draft guidance documents: GALL-SLR, SRP-SLR
- RES Support to NRR (2008-2016):
- Extended Material Degradation Assessment (EMDA) - Technical Issues - AMP Effectiveness Pilot Audits - Implementation/Lessons Learned - Assessment of International Periodic Safety Reviews (PSR) - Lessons Learned - Participation in Codes & Standards (ASME, ASTM, ACI, IEEE) to review/revise applicable Code Cases
- Insights/Results from Previous and Ongoing Research Activities:
- Irradiation-assisted degradation of stainless steel plate and weld materials in RPV - Thermal and Neutron Embrittlement of Cast Austenitic Stainless Steels (CASS) - Environmentally-Assisted Fatigue of Stainless steels - RPV Embrittlement: Enhancement of surveillance database; Enhancement of l1 T models; ASME Code work on Master Curve Fracture Toughness - Containment Liner Corrosion
- Operational Experience (alkali-silica reaction (ASR), cable condition monitoring, selective leaching of buried pipes, coatings) 5
Background (Continued) U.S.NRC United Stares Nuclear Regu latory Commission Protecting People and the Environment NRR-RES team effort informed the development of draft guidance documents: GALL-SLR, SRP-SLR
- 97 specialized expert panels (EP) comprising of staff from NRR, RES, and the Regions for the 52 AMPs, the seven chapters containing tables of AMR line-items in NUREG-1801, and corresponding sections in NUREG-1800).
- 37 EPs for mechanical AMPs - 9 EPs for structural AMPs - 6 EPs for electrical AMPs - 10 EPs for time-limited aging analyses (TLAAs) - 14 EPs for other SRP-LR sections - 18 EPs for other GALL sections and chapters (including 1521 AMR line-items)
- Expert review and comments on draft SLR guidance documents 6
Ongoing RES Support U.S.NRC United Stares Nuclear Regu latory Commission Protecting People and the Environment
- Research Topics:
- Reactor Pressure Vessel Embrittlement
- Vessel Internals
- Neutron Fluence Calculations
- Concrete Degradation
- Cable Qualification and Condition Monitoring
- Technical Expertise
- Domestic and International Coordination 7
Reactor Pressure Vessel Embrittlement U.S.NRC United S1a1cs Nuclear Regulatory Comm ission Protecting People and the Environment
- A well-established framework of U 150 . . . - - - - - - - - 1 All International Surveillance Data (1,834) documents provides formulae to ; ~ lOO I- ...
- USA Surveillance Data (1,040)
.::. e 50 predict the evolution of the RPV's N ._
a: .....
"a;"g 0
CJ?.:; -50 mechanical properties into SLR .-t ...
~ ~ *100 nott-eonservative w (Source: ASTM E900, 2015]
;;_ -150 ..,_._._~~--+-'--'-~~...................__._................."'-+--'--'~
- Advance evidence from surveillance Qj u
100% C 80% I PWRs I programs shows that some of these ~ Qj 60%
- 40years formulae may need updating as 0 40% -
60years SO years irradiation continues, but this is not ...
..c Qj 20%
(Source: EPAI MAP-126, 2011] 0 0% 100% yet an issue for the operating fleet .Q
.., 80% I BWRs !
Qj Qj
~ 60% - 40years
- Industry programs are working to ~ 40%
- 60years
- > - SO years collect more data at high SLR fluence 0 20%
(Source: NRC RVlD, 2000]
~ 0%+-'-'-~~-+-'-'-~~+-"--'-~~-+-'-'-~
in advance of their occurrence in 17 18 19 20 Log10(Fluence) [n/cm 2], E > 1 MeV service
- USA Surveillance Data , __ _ l:; _ _ __
.E 400 Ill
- Other Nations' Surveillance Data
- A RES report evaluating the ~ 350 1-============----- - -
ni 111 300 - --------- continued adequacy of RG1 .99(R2) I-
; ~ 2SO 1------
-..o-lA-'4>-.,-- -...._.,._
E
- S 50 1 -- - -
- Supports AMP XI.M31: Reactor z
o---- Vessel Surveillance Capsules 8
Vessel Internals U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment Irradiation-assisted degradation of stainless steel plate and weld materials
- NRC initiated collaborative programs with Ill 1
~-
Plate Weld Heat-Affected Zone Ongoing domestic and international partners: 2 Previous research
- International Zorita internals research 5 Ongoing 8
project (ZIRP): Testing of ex-plant 304 SS 10 Expected fluence plates (ETC: early 2017). 25 Ongoing at SO years Beyond expect ed fluence at NRC-EPRI collaborative program: Testing so yea rs 65 of weld materials harvested from Zorita 80 Planning plant (up to 2 dpa) Testing and characterization includes crack growth rate (CGR), fracture toughness (FT), t ensile properties, and microstructure (void swelling). (ETC: 2017).
- Halden Research Program: Further irradiation/testing of Zorita weld materials Cast austenitic stainless steel (8 dpa) (ETC: 2022). (CASS)
*NRC - Further testing of CASS
- Research will support AMP XI.M16A:
components (3 dpa). (ETC: 2017) PWR Vessel Internals
*Research will support AMP XI.M12:
Thermal Aging Embrittlement of CASS 9
eutron Fluence Calculations U.S.NRC United S1a1cs Nuclear Regulatory Comm ission Protecting People and the Environment
- Regulatory guide (RG) 1.190 describes acceptable methods for computing neutron flux in the RPV active core height (beltline) region
- During extended period of operations, components located outside of beltline, such as nozzles and vessel internals, experience higher levels of neutron exposure
- Research is being conducted to provide analysis of fluence at vessel locations above and below the reactor core (ETC: 2018)
- Develop technical basis for either revision to RG1 .190 or new RG (will support the new AMP X.M2 on Fluence Monitoring in GALL-SLR)
-D I QQl6VAR 2-S1~CKSH2 IUGW)o.l'M),f!OIIO&.v!t w,, fttJf:io
'"' Slides Notes: This image u*r*MC'D 110 Jl)l'* Ofl.
l(X) illustrates a quadrature Q,O QIO .. sensitivity comparison for 1111/11* .. **1 Q,O the baseline PWR model using a level symmetric S16
...,.... \)
quadrature and a more I. Ul* <<attt i1 accurate QR16 quadrature. l*Jl.*C,P) ! There is only minor effect of quadrature on calculated
*wi... ,.. I J
flu x within the beltline region .iU&.-otl,t (green) but large 1.-..... uo differences, up to 30%, tML*-.JIIIJ outside of the beltline region z near the nozzles (red). 2u,. esu2: 1-.*-eJUlJ
~ IQQ 150 2QQ )00
~Adt,{cn)
Calculated ratio of neutron flux Neutron flux near the centerline of the PWR inlet and outlet nozzles 10
Concrete Degradation U.S.NRC United States Nuclear Regu la tory Commission Protecting People and the Environment Develop the technical basis for guidance to evaluate degradation of nuclear power plant concrete structures:
- Evaluate structural performance and capability to perform intended safety functions under design basis loads and accidents
- Assess aging management programs to monitor and manage aging and degradation Alkali-Silica Reaction (ASR)
- NRC - Ongoing efforts at NIST on effects of ASR on concrete structural performance (ETC: early 2019), Northwestern Univ. of service life degradation (2018), and Univ.
Colorado on testing/ modeling of ASR beams (ETC: 2018)
- DOE/LWRS - Ongoing efforts at Univ. Tennessee on ASR development, NOE, and structural testing (ETC: 2019)
- EPRI - Developing guidelines for ASR-affected structures (early 2018); and repair and mitigation techniques (ETC: 2018)
- Research insights/results to support the SRP-SLR Further Evaluation on ASR-affected Structures Effects of potential boric acid attack on concrete and steel in PWR spent fuel pool
- EPRI - Kinetics and the extent of the attack; Role of concrete composition (ETC: 2017) 11
Concrete Degradation (Contd.) U.S.NRC United States Nuclear Regu la tory Commission Protecting People and the Environment Effects of irradiation on concrete structures
- NRC:
- Confirmatory review of DOE work on characterization of concrete irradiation damage and of EPRI research on susceptible plant configurations and their structural integrity (ETC: 2018)
- Assessment of neutron fluence and gamma dose on the bio-shield concrete (ETC:
2018)
- Evaluation of benefits and opportunities to harvest irradiated concrete from decommissioned plants for confirmatory testing (ETC: 2020)
- EPRI - Conducting research on integrity of concrete based on susceptible plant configuration (ETC: early-2017) - DOE/LWRS - Modeling and prediction of damage in ASR structures (ETC: 2020) - Research insights/results to support the SRP-SLR Further Evaluation on Irradiation Degradation of Concrete structures Creep and creep-fracture interaction of post-tensioned containment - NRC:
- Review of operating experience with post-tensioned containments (loss of prestress, trend analysis of prestress forces, corrosion of prestressing systems and cracking of anchor heads) (ETC: 2019)
- Confirmatory review (EPRI report) of creep effects on pre-stress losses and of potential for creep and fracture interactions (ETC: 2018)
- NEA/CSNI - VERCORS (EDF) - Modeling of structural behavior (ETC: 2021 ). {NRC participation}
12
Cable Qualification and Condition U.S.NRC United Stares Nuclear Regu latory Commission Assessment Protecting People and the Environment Evaluation of Condition Monitoring Techniques - Combined Gamma Radiation and Temperature Exposure
- NRC - Project with NIST & SNL to assess cable aging and evaluate monitoring techniques, such as Tan Delta (ETC: early-2019). - DOE/LWRS (PNNL) - Project to evaluate techniques and develop models for estimating remaining useful life (ETC: mid-2019). - EPRI - Project to assess new techniques - Dielectric Spectroscopy (ETC: late 2018).
Submergence Issues
- NRC - Reviewing EPRI report on medium voltage (MV) Kerite submergence qualification (ETC: 2017).
EPRI - Creating a qualification program for submergence for MV shielded Okonite Okaguard insulations (ETC: 2017). DOE/LWRS - Published a report of potential gaps in knowledge of submerged cable degradation (ETC: 2016). Planning further research into wet cable degradation. EPRI & DOE - Develop lifetime prediction models incorporating uncertainties associated with accelerated aging (ETC: 2019). 13
Collaboration & Outcomes U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Env-ironment
- Since July 2015, the NRC, DOE, and EPRI staff have completed a number of productive meetings under the auspices of DOE/LWRS and EPRI/LTO.
- Addressed existing gaps, planned research activities, schedule, and expected outcomes through open and candid discussions leading to common understanding
- Deep-dive meetings:
- Cables - October & December 2015 - Concrete - October 2015 & April 2016 - Vessel Internals - October 2015 & May 2016 - RPV - October 2015
- Augmentation of DOE and EPRI research activities
- Cable Aging and Condition Monitoring (DOE/LWRS) - Submergence Issues - Cables (EPRI) - Containment Integrity - Degradation due to Neutron Radiation (DOE; EPRI) - Non-Destructive Examination: Concrete Structures (DOE; EPRI); Buried Piping ( DOE) 14
Site Visits U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Env-ironment
- July 2015 - ORNL, Oak Ridge, TN
- April 2016 - Westinghouse Facilities, Cranberry, PA
- Focus on RPV embrittlement, vessel internals degradation and inspection
- July 2016 - PNNL, Richland, WA
- Focus on cables degradation research and NOE techniques
- October 2016 -AREVA Technical Center, Lynchburg, VA
- Focus on vessel internals degradation and inspection
- April 2017 - TBD
- Focus on concrete degradation 15
Slide Notes: N RC/industry workshops (2018 & 2020) on status of domestic and Ook Ahead international research activities and operating experience on long-term operations. Will address and evaluate the status of materials degradation issues in, including but not restricted to, metallic and non-metallic components, concrete U.S.NRC United Stares Nuclear Regu latory Commission structures, and cable insulation. Protecting People and the Environment
- Continued communication with DOE/LWRS and EPRI:
Bi-weekly phone-calls - staff-level; Periodic management meetings Roadmap/Information-Exchange meetings
- RIC 2017:
Technical session on Cables Aging and Condition Monitoring (Lead: NRR) Posters on SLR guidance documents (N RR) and SLR Research Activities (RES)
- Ex-Plant Materials Harvesting Workshop: March 2017 Increase awareness of the challenges and benefits associated with ex-plant harvesting Enable initiation of cooperative ex-plant harvesting programs
- Draft User Need Request with NRR/DLR:
Hold NRC/industry workshops (2018 & 2020) on status of domestic and international research activities and operating experience Ensure documentation on collaborative research activities and progress
- Develop/implement a long-term strategy for obtaining information on materials degradation (decommissioned NPPs, ex-plant components)
- Contribute to IAEA-iGALL development and Safety Aspects of Long Term Operation of Water Moderated Reactors (SALTO) missions 16
Subject:
Debriefing from RIC Harvesting & AM Poster Sessions last week Location: T10- D40, call in# 888-437-3094; passcode: LJ {b){§} Start: Thu 03/22/2018 3:30 PM End: Thu 03/22/2018 4:00 PM Note to requester: Show Time As: Tentative Attachments to this email immediately follow. Recurrence: (none) Meeting Status: Not yet responded Organizer: Hull, Amy Required Attendees: Moyer, Carol; Burke, John; Herrity, Th omas; Hiser, Matthew; Audrain, Margaret; Purtscher, Patrick; Tregoning, Robert; Harris, Brian; Frankl, Istvan This is a followup to the info I sent you last Friday (see below). I think we got fairly good RIC response . rn RIC18 Ad.Mfg. Poster visitor f... 2018 RIC poster draft AM Poster RIC18 Harvesting Schedul e.abh c... Feedback 2018... Poster visito... Rob suggested we get together and discuss the time we spent last Note to requester: The original email document Harvesting RIC18 had the Word file covering the words. Poster Com men... week at the RIC po sters. It looks like most of you are free from 3:30-4pm today. (please propose an alternative time for us, if this does not work for you) What insights? How to improve the process for next year? What to do differently? To that end, I also include the MSW version of the forms I prepared. (it would be nice if prototypes were made available to presenters, I invented these) Steve suggested we look at how to follow up on 'actionables.' I have tried to identify and highlight these in the attached pdfs.
Subject:
Analysis of reception of ou r RIC posters, thanks for your participation, AM Harvesting RIC Doster outreach metrics Darameter
- of poster handouts taken to exhibit 75 120
- of poster handouts remainino on 3/16/2018 1 47
# Dosters picked up by visitors 74 73
- people noted on contacUinteresUsignin form 20 27
- of business cards completed, left at exhibit 13 16
I completed detailed interest form 7 5 2
Poster staffing - 2018 RIC - March 13-15, 2018 Tuesday Wednesday Thursday Adv. Mfg. Harvesting Adv. Mfg. Harvesting Adv. Mfg. Harvesting 7:30 A M Carol Amy Amy Carol Rob Amy 8:00 A M Carol Amy Amy Carol Rob Amy 8:30 A M Carol Meg 9:00 A M Carol Meg 9:30AM Amy Meg 10:00 AM John Pat Tom Meg Amy Pat 10:30 AM Brian Pat 11:00 AM Brian Pat 11:30 AM Amy Pat 12:00 PM Adv. Mfg. 1/2 hr Harvesting 1/2 Amy Pat Carol Meg hr sessions volunteer sessions 12:30 PM Amy Pat Carol Meg Carol M. 7 3 1:00 PM John Pat Carol Rob AmyH. 10 4 1:30 PM J. Burke 2 2:00 PM Thom Herrity 2 2:30 PM Matt Hiser 3:00 PM Amy Carol Tom Meg Meg Audrain 7 3:30 PM Pat Purtscher 8 4:00 PM R. Tregoning 2 1 4:30 PM B. Harris 2 5:00 PM Amy Amy total 25 23 5:30 PM t otal 1/2 hr 25 23 sessions
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITOR NAME/ORG: BUSINESS CARD: 0 YES O NO EMAIL: Do you have any personal experience with AM? l s your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM): I . Do you expect to impl ement AM in your company in the future? How so? When? D Within 5 years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind.
- 3. What should NRC be doing differently to get ready for AM implementation? Would you like NRC to have another public meeting on AM'! Other suggestions'!
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) in terms of interest:
- AM standards &qualification
- Industry activities
- American AM activity in international context
- Cyber security
- Reverse engineering and reactor components
- Effects of process and design parameters
- Irradiation testing & effects on AM
- Nondestructive evaluation of components fa bricated using AM
- Corrosion behavior of AM components
- Other areas NRC should focus on?
Please provide any other comments or feedback that may be important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15, 2018 Name Date
POSTER 7: HARVESTING OF AGED MATERIALS FROM NPPS VISITOR NAME/ORG: BUSINESS CARD: 0 YES O NO EMAIL: Please describe your interest in harvesting components that were aged in representative light water reactor (LWR) environments in nuclear power plants (NPPs). Is your interest related to subsequent license renewal (SLR) and NPP long-term operation (LTO)'? I . Do you expect to have harvestable components that NRC should be aware of? How so? When? D Within 5 years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind about harvesting components.
- 3. Would you like NRC to have a public meeting on harvesting NPP compo nents? Other suggestions?
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) in terms of interest to you:
- Reactor pressure vessel embrittlement
- Electrical cable qualification and condition assessment
- Irradiation-assisted degradation of reactor internals
- Concrete structures and containment degradation
- Availability of reliable inservice inspection (ISI) techniques
- Creating a harvesting database
- More coordination between NRC and industry on harvesting and SLR research
- Other industry activities
- Other areas NRC should focus on?
P lease provide any other comments or feedback that may be important to NRC's work o n harvesting of aged materials from NPPs. Return to: NRC Staff at Poster 7 across from Salon D By: March l 5, 201 8 Name Date
Beckman & Associates, Inc. Nuclear and Engineering Support Services Donald A. Beckman 1071 State Route 136
~WPR www . mpr.com President Belle Vernon, PA 15012 Phone: 724*872-9157 Email: Don.Beckman@baa-inc.com 724-497-3024 Website: www.baa-inc.com Cell: 702-278-7312 Fax: 724-872-6347 f ; \ NRA,Japan SOUTHWEST RESEARCH INSTITUTE* ~J Nuolew R111U111tlon AutllOrlty 6220 Culebra Road (78238-5166) Tel: (210) 522*2028 o*eputy Director P.O. Drawer 28510 (78228-0510) Fax: (210) 684-4822 San An1onio. Texas Cell: (210) 316*59'48 Kazuko SATO jay.fisher O swri.org Oversight Planning and Coordination Division JAY L. FISHER, Sc.D.
Program Direelor 1 9 Roppongi, Mlnato-ku,Tokyo,JAPAN 106-8450 Sensor Systems & NOE Technology Department PHONE: +81-3-5114-2122 FAX: +81-3-5114-2142 Mechanical Engineering Division e-mall:kazuko_satou@nsr.go.jp http//www.nsr:go.jp
~~
/::I,~ I U , 7.J'- ~ CHRISTOPHER CHARLES ~ rv,, 1, Seniar!M#Br Hag-ki Youm, Ph.D. K[."iiEP
~ Electric 11nd Nuclear Power Division KcttH lnsht*!* ol E111rr, leclul311t1r I
Ill/CLEAR ENERGY INSTITUTE 1201 FStreet, NW, Suite 1100 Washington, DC 20004 p; 202.739.8152 Eval a i:tn and P1111rt1n1 Teheran-ro 114gil 14, Gangnam-gu, Seoul, Korea 06175 M* 7.5717 E: * * @nei.org
*49>* T: @NEI Tel. +82-2-3469-8488 Fax. +82-2-556-1033 Mobile. +82-10-2312-5495 E-mail. hockey@ketep.re.kr LANDREY & COMPANY IFe Bruce Land r ey Helge Thoresen Mart<etillg Manager Nuclear Technology, Physics and Safety P.O. Box 173, N0-1751 Halden, Norway
*~ C: 503.715.7900 b ru ce l@ l a n d reyco. com PO Box 8787 F: 503 226 . 2522 Phone: (+47) 69 21 22 00 [if : . .: *.. Portland, Oregon 97207 USA' Mobile: ("47) 94818 023 helge.thoreS8fl~fe.no www.ife.no Strategic Advisory Services UNITED STATES NUCLEAR 320 King Street REGULATORY COMMISSION Alexandria, VA 22314 Carol E. Moyer www.NuSourcellc.com Senior Materials Engineer (571) 482-7403 (<>),
Division of Engineering f91 oJ 630-11enm; Office of Nuclear Regulatory Research Patrick Butler pbutlerflp.NuSourpeUC.com. Chief Technical Officer Mail Stop: T10-A36 Telephone: 301-415-2153 Washington, D.C. 20555-0001 Fax: 301-415-6671 E-mail: Carol.Moyer@nrc.gov
Safety Evaluation Engineer Non Destructive INSTtTUT Testing O! kAOtOP"-OTlCflON ET OE SU*t.rt l'\IUC~!
- Part of your business Nudear Safety Division Ravi Jathra WlKA Instrument. LP Equipment and Structure Assessment 1000 Wiegand Boulevard Senior Market Segment Department Lawrenceville, GA 30043- 5868 Manager
- Energy
*Mobile (240) 513-5.101 31 avenue de la Division Leclerc ravi.jethra@wika.com B.P. 17
- 92262 Fontenay-aux-Roses Cedex Franco Ph. n* + 33 (0) I 58 3S'JS 2 I Fax +33 (O)l 4H610 14 http://www.wlka.com lill.ducoussoganjehl@irsn.fr UNlTEDSTATESNUCLEAR REGULATORY COMMISSION Amy B. HuU, PhD Sr. Material Engineer, Corrosion & Metallurgy Office of Nuclear Regulatory Research Mail Stop: T-10A36 Telephone: (301) 415-2435 Washington, DC 20555-0001 Fax: (301) 415-6671 E-mail: amy.hull@nrc.gov
' J I
NRC Additive Manufacturing for Reactor Materials & Components (AM-RMC) RIC Poster# 15, March 13-15, 2018 Organizational Current AM-RMC Do you want I Name Affiliation Email p~ 1----~~---------,--- - - - - ~ - - - - -- --+--- - -- - - - - - - - - ~ -c_o_n_t_a_ Phone Interest to be on c t_l_is_t_? ~ 1\ ~ 1. ~ ~ ~~ ~ ~~ ~+-----~ ~ ~ ~- - - - i ~ v ~---l
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NRC Additive Manufacturing for Reactor Materials & Components (AM-RMC) RIC Poster # 15, March 13-15, 2018 Do you want Organizational Current AM-RMC Name Email Phone to be on Affiliation Interest contact list? 39.
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POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITORNAME/ORG: f V'f-v-f j u(ry.l,/J. JWu.(!- BUSINESS CARD: ll) YES ONO EMAIL: Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM):
- 1. Do you expect to implement AM in your company in the future? How so? When?
0 Within 5 years 95-10 years O sometime in future O not likely
- 2. Please comment on the things that stand out in your mind.
- 3. What should NRC be doing differently to get ready for AM implementation? Would you like NRC to have another public meeting on AM? Other suggestions?
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) i~ terms ofintercst:
- AM standards &qualification [ ]
- Industry activities [ )
- American AM activity in international context [ ]
- Cyber security [ ]
- Reverse engineering and reactor components [ ]
- Effects of process and design parameters [
- Irradiation testing & effects on AM [ ]
- Nondestructive evaluation of components fabricated using AM [ ]
- Corrosion behavior of AM components [
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15, 2018 Name Date
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITOR NAME/ORG: A Lex. Po fo vA /c re L o BUSINESS CARD: JR{ YES ONO EMAIL: Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM):
- 1. Do you expect to implement AM in your company in the future? How so? When?
g! Within S years D 5~10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your m; \ _ -~
c.~),~Vl W-u;)t~ M~\.l c.)fv\.°'t o+ ~ )e~SJ ' \"I\Q\U...... S1M1-\\e,.r /Je-rc~ u_d ro COWi WM -\) W{ ~~l~, Yr-cl v\
- 3. What should NRC be doing differently to get ready for AM implementation? Would .J
\(tae~ V\ Vl(\ . you like N1lC to have another public meeting on AM? ~ther sugge,tions?
!' 1 """\v{~ w{ ~ ~~~v\ ~~ \ ,~ \l\=t;e v-) / f vx:,lD5S , \.A o 11'<<1 fu, """~ ~"'~ '
- 4. Please rate the topics on a see from 1 to S (S being highest) i~ terms of interest:
- AM standards &qualification rr 1
- Industry activities [I ]
- American AM activity in international context [ l
- Cyber security [ l
- Reverse engineering and reactor components [ 1)J
- Effects of process and design parameters [4 ]
- Irradiation testing & effects on AM [ ]
- Nondestructive evaluation of components fabricated using AM [ }
- Corrosion behavior of AM components [ i.J
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for re!lctor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15, 2018 Name Date
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITORNAME/ORG: VJt'>/ r,/51/E/:_ BUSINESS CARD: /:'.JYES O NO EMAIL: sh J q z': _:)-; p ,- } SW r,~,07 Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM): vf/,.e.,. a/'.1c ('e.5ea,o 4,,,1-j A 1Y - h @tA,,,-- f vP d tlP~i,/J r.e /.d/;;µ /Jot/ls v- pr# v1de' i/7Sf?/_,/r,(}vJ
- 1. Do you expect to implement AM in your company in the future? How so? When?
~ Within 5 years O 5-10 years O sometime in future D not likely
- 2. Please comment on the things that stand out in your mind.
M -
- 3. What should NRC be doing differently to get ready for AM implementation? Would you like NRC to have another public meeting on AM? Other suggestions?
;i*~
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) i~ terms of interest:
- AM standards &qualification R.]
- Industry activities [ ]
- American AM activity in international context [ )
- Cyber security [ ]
- Reverse engineering and reactor components [j ]
- Effects of process and design parameters [;, ]
- Irradiation testing & effects on AM [ ]
- Nondestructive evaluation of components fabricated using AM [/]
- Corrosion behavior of AM components WT
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15, 201 8 Name Date
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITOR NAME/ORG: :yiaf(l t'sh 4,/f l fY/q, fW I NA 13-BUSINESS CARD: 0 YES ONO EMAD.,: Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM): I . Do you expect to implement AM in your company in the future? How so? When? D Within 5 years D S-10 years EJ sometime in future D not likely
- 2. Please comment on the things that stand out in your mind.
- 3. What should NRC be doing differently to get ready for AM implementation? Would you like NRC to have another public meeting on AM? Other suggestions?
- 4. Please rate the topics on a scale from I to 5 (S being highest) i~ terms of interest:
- AM standards &qualification [ ]
- Industry activities [ ]
- American AM activity in international context [ ]
- Cyber security [ "1
- Reverse engineering and reactor components [ ]
- Effects of process and design parameters ]
- Irradiation testing & effects on AM [ ]
- Nondestructive evaluation of components fabricated using AM [v(
- Corrosion behavior of AM components [ ]
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15, 2018 Name Date
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITOR NAME/ORG: BUSINESS CARD: IX] YES ONO EMAIL: Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM):
- 1. Do you expect to implement AM in your company in the future? How so? When?
D Within S years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind.
- 3. What sh<<fuld NRC be doing differently to get ready for AM implementation? Would you like NRC to have another public meeting on AM? Other suggestions?
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) i~ terms of interest:
- AM standards &qualification [ 6]
- Industry activities [ 5]
- American AM activity in international context [ S]
- Cyber security [:, ]
- Reverse engineering and reactor components [ 5]
- Effects of process and design parameters [.f)
- Irradiation testing & effects on AM [ 5]
- Nondestructive evaluation of components fabricated using AM [4]
- Corrosion behavior of AM components ['5]
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 151 2018 Name Date
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITOR NAM;E/ORG: \<.£ \.J JL '(-01-JE.641'Ast{1 BUSINESS CARD: ~ YES ONO Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM):
- 1. Do you expect to implement AM in your company in the future? How so? Whe.n ?
0 Within 5 years D 5-10 years g sometime in future D not likely
- 2. Please comment on the things that stand out in your mind.
- 3. What should NRC be dong differently to get ready for AM implementation? Would you like .NRC to have another public meeting on AM? Other suggestions?
- 4. Please rate the topics on a scale from 1 to S (5 being highest) i~ terms of interest:
- AM standards &qualification [ )l
- Industry activities [ 41
- American AM activity in international context [ S1
- Cyber security [ 3]
- Reverse engineering and reactor components [ -Z]
- Effects of process and design parameters [4}
- Irradiation testing & effects on AM [ 3J
- Nondestructive evaluation of components fabricated using AM [4 ]
- Corrosion behavior of AM components [ y.J
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15, 2018 Name Date
POSTER 15: AM - REACTOR MATERIALS & COMPONENTS VISITORNAME/ORG: *)LJ (bC?C<'o ..... f.,..f\10*ye;::: \--\\ BUSINESS CARD: ~ *YES ONO EMAil,: ~~ .. c.crt.tft()o-c~/'"rc)Q~,@J L~rv,.. ££.. Do you have any personal experience with AM? Is your organization researching AM? Please describe your interest in advanced or additive manufacturing (AM):
- 1. Do you expect to implement AM in your company in the future? How so? When?
D Within S years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind.
I~ n -\ 'O ~ \ ,-:..~\"f..OO..t.! Cc.. 'Nv',o..,,..,~~c.s. <.\ ,\..', \ '::j d ~ ~~ t...\.~
- 3. What should NRC be doing differently to get ready for AM implementation? Would you like NRC to have another public meeting on AM? Other suggestions?
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) i~ terms of interest:
- AM standards &qualification [ ]
- Industry activities [ ]
- American AM activity in international context [ ]
- Cyber security [ ]
- Reverse engineering and reactor components [ ]
- Effects of process and design parameters [ ]
- Irradiation testing & effects on AM [ ]
- Nondestructive evaluation of components fabricated using AM )>('
- Corrosion behavior of AM components [ ]
- Other areas NRC should focus on?
Please provide any other comments or feedback that is important to NRC's review of AM for reactor materials and components. Return to: NRC Staff at Poster 15 by Salon E By: March 15. 2018 Name Date
~ ( .W~6> ( ~
I VnginiaTech. l__ _ Oanlel P. MIiier, M.S. Ph.D. Student (Gov. Manager-Do0) l 3/11"5/2o11 SclenceandTecmok>gystucles Northern Virginia Center 7054 Haycock Road Falla Church, VA 22043 U.S.A.
~C...f .ct-e-Joshua Hogancamp, Ph.D.
Po1tdoctorol Appointtt PO Box 5800 MS 07~8 Sandia National Laboratories Op,raltd for th< Unil.*d Stoia Otporlmtnl of Eneray by
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=-f'2 1p C/1 703-261-9621 mlllerdp@vt.edu
. Albuquerque, NM 87185 (615) 3111-5284 National Ttthnolot, and Eni1ntttin1 5alutiorrs of Sandia, U.C. r~
- jhoganc@sandla.gov Virginia Polytechnic Institute and State University HIDEO TANAKA VICE DlRECTOR INSTmITE OF NUCLEAR TECHNOLOGY Hag-ki Youm, Ph.D.
Becirk: and Nude¥ Power DMston K§]EP IIC.ctlf t:tubtfleti'fYTt M-O;y tnllll'ttl" nd P'l1iwng Institute of Nuclear Safety System, Incorporated 64 Sata, Mihama-cho, Mikata-gun, Fukui 9 l 9-1205, JAPAN Teheran-ro 114gil 14, Gangnam-gu, Seoul, Korea 06175 Tel : +81*50-7105*0090 (Direct) +81*770*37*9100 (Main) Fax: +81-770-37*2009 Tel +82-2-3469;8488 Fax. +82-2-556-1033 URL : http://www.inss.co.jp Mobile. +82-10-2312-5495 E-mail. hockey@ketep.re.kr E-mail : tanaka.hideo@inss.co.jp
* *
- Herbert W. Massie, Jr.
A Engineering and Management Consultant WIiiiam F. Zipp Dec:ommisslonlng Project Monoger Kewaunee Power Slat/on Donlinlo,i E,..rgy Kewaunee, Inc, N490 Slate Highway 42, Kewaunee, Wl 54216 office: 410.802.3736 Phone: 920-388-8842 Emoil: williomJ.:zippOdom.com 5267 Candy Root Ct. fax: 410.730.5441 Columbia, MD 21045 email: hmassle625@gmail.com
<i}tIB_A~~~c!!?~"" OAK RIDGE N ATIONAL LABORATORY MANAGED BY UT* BATTEll£ FOR THE DEPARTMENT OP ENE\GY Masa Kojima Bruce B. Bevard Senior Program Manager Chief Researcher Advanced Reactor Systems Dlvl,lon of Research for Reactor SY9tem Safety Nuclear Science & Technology Division Secretariat of Nuclear Regulation Authority (865) 574-0279 (865) 241-1044 fax One 8ethel Valley Road Roppongl Flrat BUlkllng, 1-t-* Aoppongl, Mln_.u, Tokyo 106-M50, Japan (865) 300-367 1 cell P.O. Box 2008, MS-6165 Tai: +81-3~114-2100 ex.3469 Fax: +11*3-5114-2233 bevardbb@ornl.gov Oak Ridge, TN 37831-6165 E-fflall: fflUayoahLkoJlm.....r.goJp
\ I Daniel P. MIiier, PMP, PMI-RMP
-- l (IIV~Tech. Program Manage(
j National Capital Region Defense Information Systems Agency (OISA) Science, Technology, and Society Joint Service Provider - (JSP) I The Pentagon Sonja D. Schmid, Ph.D. Northern Virginia Center Architecture, Configuration, Englneerlng and Associate ProressOI" 7054 Haycock Road Solutlons Cenl.ar 703-538-8482 Falls Church, VA22043 Strategic Programs DMslon I JPS 1 sschmid@vt.edu www.sts.vt.edu TEL: (703) 571"3320 DSN: 671-3320 danlet.p.miller36.civ@maK.mil daniel.p.mlUer36.civ@maH.smi.mil Virginia Polytechnic Institute and State University
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NRC Harvesting of Aged Materials from NPPs
- RIC Poster# 7, March 13-15, 2018 Do you want Organizational Email Phone Your Interest? to be on Name Affiliation contact list?
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POSTER 7: H A R V E STING O VISITOR F AGED M N A M E /O RG: ATERIAL
~tJ{ S FROM BUSINES /.Jo j ~rt.tA""' I? NPPS S CARD:
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S ONO o~ I I.a b f Please des E M A il ,: j . { J, M cribe y o u r li g h t w a te in te r e s t in L @ J-'> rr ha 'tdtt11 ,3 q l / re la te d to e a c to r (LWR) envir rvesting componen subsequen onments in ts th a t we r ,e fe t license nuclea re aged in
~ f 1-t,~ r " " ' N l' t/ -~ ,. j ... ( Clj renewal (SLR) a n d NPr power plants (NPPs). representative P long.term 1"1.,./er 1-t r n r, ( . .,.., ,;/.e / v*,.'*"~J .,.tp. t / ~ r.. ,4 /} o f\ /' ID ls o p e ra ti o n y o u r in te r e s t
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- 1. Do you . 11"- ~ j A tr -e f. e
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expect to f 1***rdf.lt lo ,r ." 'f ii . - c ., ., ~ When? have harv estable co nlrot eY:p /, '~ N 'r 6 e. I -Y (. ,,
.,.il< >I\, s 5 i, , 'e 'f J " 1 th a t N R C i?-... o , ~ , e f ~ .
mponents A 1 e Hc- ,+ c\ 0 Within S y should b e aware of? / e a rs O How s o ? S-10 years O sometime in
- 2. Please f u tu r e O comment not likely componen on th e thin 4 ,s - J o .' 1 ts. gs th a t s ta J /, n d o u t in y r :rrtVf, o u r m in d f ,i re . e 'afeJ ( M ~ f e I' f' c ? J 'd rf it a b o u t harv J;,...Jpl,'tza ( .~87 ~ ~ff , esting
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s? e a public v ,. meeting o n harvesti d lt 4ff~ n g N P P co ~ f ""clA C rv,_._ l!/> L -1 " 0 .
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r a te th e to pics o n a s ~Q7,,)4/ h .~r"t/trf:,,,f!J 0 -
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r pressure v 1 to S (5 b eing highe .
- Electric al cable qu essel embri alification ttlement st) in te r m s o f in te r e s t to you:
1'
- Irradia a nd conditio _,
tion-assiste n assessme [
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d degradati nt ]
- Concre on o f reacto te structure r internals [ ]
s and conta
- Avail inment deg ability o f reliable in ra dation [~] p
- Creatin service in g a harvesti sp ection (ISI)
- More c ng databas e
techniques ITT oordination between N l [
]
- Other RC and ind industry ac ustry on ha tivities rvesting a nd SLR res [Yl
- O th e r earch areas NRC [ 7 ']
s h o u ld foc us on? [ ] Please pro vid harvesting e any o th e r comme o f aged m n aterials fr ts o r feedback th a t o m NPPs. may b e im p o r ta n t to N R C 's w o r k on Return to: NRC Staff at Po ster 7 acros Name s from Salo nD B y: Marc h 15, 2018 D a te
POSTER 7: HARVESTING OF AGED MATERIALS FROM NPPS VISITOR NAME/ORG: /1 e r ~ YV\. Q.__ 5S", ~ BUSINESS CARD: QA'Es ONO Please describe your interest in harvesting components that were aged in representative light water reactor (LWR) environments in nuclear power plants (NPPs). Is your interest related to subsequent license renewal (SLR) and NPP long-term operation (LTO)? SL /Z
- 1. Do you expect to have harvestable components that NRC should be aware of? How so?
When? 0 Within 5 years O 5-10 years O sometime in future IRf not likelr 0i"\./+ -,- f<:=--~ L,ul.{> s--f ,'r\ 5 ~ () YrR Vl C( ~
- 2. Please comment on the things that stand out in your mind about harvesting components.
(< ~~ +~ ./\~o-l.; q_ ,-f.; 6"V"\ ~ (ct~ ci5
<Yr'- :"-5~ $~ C t - # ~ s 'i:c.1.-J
- 3. Would you like NRC to have a public meeting on harvesting NPP components? Other suggestions?
'y.JJ,,,1._ I ,.~ ~ s ,, l C<i-<? I;;
- 4. Please rate the topics on a scale from 1 to S (5 being highest) in terms of interest to you:
- Reactor pressure vessel embrittlement [~ ]
,c<S;
- Electrical cable qualification and condition assessment l rt
- Irradiation-assisted degradation of reactor internals {S J
- Concrete structures and contairunent degradation [ 4J
- Availability of reliable inservice inspection (ISi) techniques "ft]
- Creating a harvesting database ff]
- More coordination between NRC and industry on harvesting and SLR research [t./]
- Other industry activities ( ]
- Other areas NRC should focus on?
Please provide any other comments or feedback that may be important to NRC's work on harvesting of aged materials from NPPs. Return to: NRC Staff at Poster 7 across from Salon D By: March 15, 2018 Name Date
\
POSTER 7: HARVESTING OF AGED MATERIALS FROM NPPS VISITORNAME/ORG: I/hi~ liviPt-/ ~/ Z,t/i~~e..<>/ ~c(e'k-J~ ~
~ 7 BUSINESS CARD: c6YEs ONO EMAIL: lMt~b,,.h-!Jea@~.Ciiff Please describe your interest in harvesting components that were aged in representative light water reactor (LWR) environments in nuclear power plants (NPPs). Is your interest related to subsequent license renewal (SLR) and NPP long-term operation (LTO)?
- 1. Do you expect to have harvestable components that NRC should be aware of? How so?
When? Q(Within 5 years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind about harvesting components.
- 3. Would you like NRC to have a p blic meeting on harvesting NPP components? Other suggestions?
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) in terms of interest to you:
- Reactor pressure vessel embrittlement f?t1,;. lti Sv-r,~ ~ro'tf~pJi/ vf ]
- Electrical cable qualification and condition assessment [ ]
- Irradiation-assisted degradation of reactor iµtemals rvf
- Concrete structures and containment degradation [ v(
- Availability of reliable inservice inspection (ISi) techniques [ ]
- Creating a harvesting database [ ]
- More coordination between NRC and industry on harvesting and SLR research [ t{'
- Other industry activities [ ]
- Other areas NRC should focus on?
*-rn4t~:R kce SWJt/f7 t*f CI-Bfc~/ 4 ,
Please provide any other comments or feedback that may be important to NRC's work on harvesting of aged materials from NPPs. Return to: NRC Staff at Poster 7 across from Salon D By: March 15, 2018 Name Date
POSTER 7: HARVESTING OF AGED MATERIALS FROM NPPS VISITORNAME/ORG: D::-.u,c:\ V, ft\ :\\ ec (
/ u*.r3,'o iq_ tecl, BUSINESS CARD: !XI YES ONO EMAIL: /1"' , \ \ ~ ')D . ~ i .
"C C.-(' ~ r i..;;;. V:se \ e ('.'\l~
Please describe your interest in harvesting components that were aged in representative light water reactor (LWR) environments in nuclear power plants (NPPs). Is your interest related to subsequent license renewal (SLR) and NPP long-term operation (LTO)?
- 1. Do you expect to have harvestable components that NRC should be aware of? How so?
When? D Within 5 years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind about harvesting components. -f-~c.c -the. Ma.. i'.5 co11~cW t' /\-{c Qct..t'CJn.~ble ,tr<.orm-i-l.tk,v1
- t-\DCv S'k.~r<.OJ '{. 1 1 - ~l"t{_(c,n:Jh .'y-{a /),~;,ft.(lcl~:
- T111-leorA4.f.tol\"'i cc,,o,~1 /\"'f...LlQ'l ,
- 3. Would you like NRC to have a public meeting on harvesting NPP components? Other suggestions?
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) in terms of interest to you:
- Reactor pressure vessel embrittlement [ SJ
- Electrical cable qualification and condition assessment (> ]
- Irradiation-assisted degradation of reactor internals ['-1 ]
- Concrete structures and containment degradation [ 5]
- Availability of reliable inservice inspection (ISi) techniques [5]
- Creating a harvesting database [ t1
- More coordination between NRC and industry on harvesting and SLR research LL{ ]
- Other industry activities [ ]
- Other areas NRC should focus on?
Please provide any other comments or feedback that may be important to NRC's work on harvesting of aged materials from NPPs. Return to: NRC Staff at Poster 7 across from Salon D By: March 15, 2018 Name Date
POSTER 7: HARVESTING OF AGED MATERIALS FROM NPPS VISITOR NAME/ORG: Gtr,J trO l rt N Nvc l E¥1~ LA-fo c(lfrTCf'2...l ES BUSINESS CARD: 0 YES O NO EMAIL: ~l~e:,@>~~.
~CE ,
Please describe your interest in harvesting components that were aged in representative fV\ 6' \ f-\..f light water reactor (LWR) environments in nuclear power plants (NPPs). Is your interest (fl related to subsequent license renewal (SLR) and NPP long-term operation (LTO)? ~ ~.
- 1. Do you expect to have harvestable components that NRC should be aware of? How so?
When? lbJ Within 5 years D 5-10 years D sometime in future D not likely
- 2. Please comment on the things that stand out in your mind about harvesting components.
, o..ffer 00 '{fS ~*
~e ~ve dtCPMm*1$\ ~ <'..J'IL'S NR\J (UVj._ hcu,-c CU"
- 3. Would you like NRC to have a public meeting on harvesting NPP components? Other (J\ n, ~
M~J~v-e. suggestions? -j)'ff:lv~~.,. I
- 4. Please rate the topics on a scale from 1 to 5 (5 being highest) in terms of interest to you:
- Reactor pressure vessel embrittlement [ ]
- Electrical cable qualification and condition assessment [ ]
- Irradiation-assisted degradation of reactor internals [ ]
- Concrete structures and containment degradation [ ]
- Availability of reliable inservice inspection (ISI) techniques [ ]
- Creating a harvesting database [
- More coordination between NRC and industry on harvesting and SLR research [
- Other industry activities [ ]
- Other areas NRC should focus on?
Please provide any other comments or feedback that may be important to NRC's work on harvesting of aged materials from NPPs. Return to: NRC Staff at Poster 7 across from Salon D By: March 15, 201 8 Name Date
Note to requester: Attachment to email immediately follows. Yellow highlighted portions were in the
.....ito From: Purtscher, Patrick version of the document provided the FOIA team. -
Sent: Tuesday, May 31, 2016 7:38 AM To: Hiser, Matthew; Iyengar, Raj; Frankl, Istvan; Hull, Amy Cc: Tregoning, Robert
Subject:
FW: 2016-NRR-UNR-Draft- May 2016 abh rev.docx Attachments: 2016- NRR-UNR- Draft- May 2016-Enclosure-CLEAN -FINAL.DOCX
- All, I think the draft UNR is OK as is, we don't need an example in the draft at this point. The larger scale of testing was meant to cover the whole range of potential testing configuration, larger coupons to full-scale test, depending on the circumstances.
Pat From: Hiser, Matthew Sent: Friday, May 27, 2016 2:58 PM To: Iyengar, Raj <Raj.lyengar@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: 2016-NRR- UNR-Draft-May 2016 abh rev.docx Hi, Sorry I'm a little late to this co nversation on a Friday before Memorial Day! I agree with capturing Pat's suggestion on specimen size in Task E. I did have one edit to remove the reference to "small-scale specimens and coupons" in Task C, since the specimen size comment is being incorporated into Task E. See tracked changes in t he attached. My thoughts on t his topic in general:
- Looking at K/size effects in irradiated materials is different from what I thought Pat's original proposal was for "testing of larger-scale specimens". To me, looking at K/size effects may involve repeat tests on 0.25T, a.ST and 1T CT specimens (for example), to see the effects of specimen size and determine K validity as specimens size decreases. When Pat was describing " larger-scale testing" I thought he was envisioning full-size piping mockups or something of that nature, which is far different than varying CT specimen size. Pat, can you clarify what you are envisioning?
- For the K/size effect question, I know EPRl's Primary Systems Corrosion Research (PSCR) is already planning and sponsoring testing on the Zorita materials to look at K/size effects by testing multiple CT specimen sizes. The results from that project may at least partially address Pat's suggest ion.
- For this whole discussion on what to include in t he UNR regarding specimen size or large vs small-scale testing, I think it would probably be appropriate to get Rob's perspective and insight on what we need to be focusing on from his SL technical perspective.
Hope everyone has a great weekend and see you next week! Thanks! 1
Matt From: Iyengar, Raj Sent: Friday, May 27, 2016 12:23 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
Re: 2016-NRR-UNR-Draft-May 2016 abh rev.docx
- Steve, Sorry for confusing you . What I meant by disposition document was the deliverable under Task B. This is the disposition of EMDA issues and offering recommendations on less-resolved issues.
I am OK with the draft. No additional input from m e. Raj From: Frankl, Istvan Sent: Friday, May 27, 2016 12:19 PM To: Iyengar, Raj; Purtscher, Patrick; Hull, Amy; Hiser, Matthew
Subject:
RE: 2016-NRR-UNR-Draft-May 2016 abh rev.docx Thanks, Raj. I also like your Task E implementation of Pat's input. You mentioned in your email below that "This will be important for the disposition document." This is why I asked question on public comments (my understanding is that the disposition document addresses these comments) I will not send the drafts to DLR until later today. This will allow all contributors to "reflect" . If you need more time, I can hold off until Monday.
- Thanks, Steve From: Iyengar, Raj Sent: Friday, May 27, 201612:18 PM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>; Hull, Amy
<Amy.Hull@nrc.gov>; Hise r, Matthew <Matthew.Hiser@nrc.gov>
Subject:
Re: 2016-NRR-UNR-Draft-May 2016 abh rev.docx Thanks, Pat. We cain pursue this further next week. All, Have a wonderful long week and Happy M emorial Day! Raj 2
From: Purtscher, Patrick Sent: Friday, May 27, 201612:12 PM To: Iyengar, Raj; Frankl, Istvan; Hull, Amy; Hiser, Matthew
Subject:
RE: 2016-NRR-UNR-Draft-May 2016 abh rev.docx I think section E is appropriate place to mention the size effects. I think one example could be the K/size criterion issue for IASCC crack growth that is discussed extensively in NUREG/CR-7027. Pat From: Iyengar, Raj Sent: Friday, May 27, 2016 12:04 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
Re: 2016-NRR-UNR-Draft-May 2016 abh rev.docx
- Steve, I have attached a revised version of the enclosure that includes some of Pat's comments. The assessment of appropriate testing is referenced in Task E.
On the "gap" of small-scale vs. large scale testing is not new. There has been ample work. But, for components experiencing IAD, there may not be a full understanding. I do not think there was a public comment on this for GALL-SLR. But, I could be wrong. As you had suggested, we can an internal alignment on Pat's idea and pursue it with NRR. There are at least couple of opt ions - Task E (emergent need) from this UNR or IAD UNR. Perhaps, t here are morre options. For now, I have added a phrase (highlighted) in the deliverable of Task E. "Such issues may include, but not restricted to, providing an assessment of effect of specimen size on the prediction of component performance, technical support for aging management program audits, public meetings related to communication efforts, and confirmatory reviews of licensee submittals." Raj From: Frankl, Istvan Sent: Friday, May 27, 2016 11:27 AM To: Iyengar, Raj; Purtscher, Patrick; Hull, Amy; Hiser, Matthew Subject : RE: 2016-NRR-UNR-Draft-May 2016 abh rev.docx
- Raj, Was this issue raised during the public comment period of the GALL-SLR or SRP-SLR?
3
If the identification of a gap in EMDA is new, it needs to be communicated to RES/DE management before we send specifics on it in a draft document to DLR. The EMDA is a RES deliverable, so obviously, RES/DE management should be briefed on it before we notify our counterparts in NRR. Perhaps, you or Pat could add wording to the draft that will allow us to be more specific in our response . Any thoughts? Steve From: Iyengar, Raj Sent: Friday, May 27, 2016 11:11 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
Re: 2016-NRR-UNR-Draft-May 2016 abh rev.docx
- Steve, I just sent another approach. I realized we need to address Pat's idea soon. This will be important for the disposition document. We can also consider his idea in Task B, as part of the recommendations that we will be providing.
I will look over all of Pat's changes and incorporate them (except the one on testing) in Task C. Raj From: Frankl, Istvan Sent: Friday, May 27, 201611:05 AM To: Iyengar, Raj; Purtscher, Patrick; Hull, Amy; Hiser, Matthew
Subject:
RE: 2016-NRR-UNR-Oraft-May 2016 abh rev.docx
- Raj, I agree with your overall assessment. However, I recommend that we (and RES/DE management) should first align with Pat' s recommendations and then we discuss our recommendation with DLR either during our review of their final draft (before they submit the draft UNR for NRR management review/ approval), or during the drafting of the RES response .
Also, are there other revisions/changes from Pat that should be implemented in our final draft?
- Thanks, Steve From: Iyengar, Raj Sent: Friday, May 27, 2016 10:49 AM To: Frankl, Istvan <lstvan .Frankl@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy
<Amy.Hull@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
Re: 2016-NRR-UNR-Draft-May 2016 abh rev.docx Pat/Steve, 4
1looke*d into the additions proposed by Pat (highlighted in yellow). These are very valuable thoughts and should be pursued under the new UNR for IAD. I believe that is in progress. This really does not fit the objective of developing a general database for ex-plant materials (metals, concrete and cables). Further, these points were not vetted with DLR during our staff and management briefings on this UNR. I would prefer not to surprise them by inserting things like this, which are not directly addressing the objective. If you still insist, I will add these to the final version. Raj The EMDA ranking of each aging-related degradation phenomena incorporates multiple factors that may not be adequately resolved by additional coupon testing of ex-plant materials. Part of this user need will be to examine where testing of larger-scale specimens may be appropriate to provide validation of the prediction of component performance from coupon testing. Deliverable: RES shou ld develop a strat egic database for strategic harvesting t hat covers t he four topical areas outlined in SRM on SECY 14-0016, which containsing information on:
- research gaps for SLR that may be best addressed by harvesting due to challenges in simulating actual service conditionsunique and significant materials aging degradation diverse sources (operat ing experience, other nuclear facilities, other long-lived industrial plants, other materials organizations such as ASM and NACE),
- assessment of appropriate testing program that would reduce the concern associated with the EMDA
- ranking, From: Frankl, Istvan Sent: Friday, May 27, 2016 10:22 AM To: Iyengar, Raj; Purtscher, Patrick; Hull, Amy; Hiser, Matthew
Subject:
RE: 2016-NRR-UNR-Draft-May 2016 abh rev.docx
- Raj, I have not yet sent the final revs to DLR, so please consider incorporating Pat's inputs into the final version (this may require copy and paste into t he fina l rev you sent me late yesterday).
- Thanks, Steve 5
From : Iyengar, Raj Sent: Friday, May 27, 2016 10:04 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew
<Matthew.Hiser@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
Re: 2016-NRR-UNR-Draft-May 2016 abh rev.docx Pat, St eve has t he final version. Your points can be included in t he response t hat we provide. W hat do you think? Raj From: Purtscher, Patrick Sent: Friday, May 27, 2016 9:23 AM To: Iyengar, Raj; Hull, Amy; Hiser, M atthew Cc: Frankl, Istvan
Subject:
RE: 2016-NRR-UNR-Draft-May 2016 abh rev.docx I added some additional comments on the harvesting to be considered. Pat From: Iyengar, Raj Sent: Friday, May 20, 2016 11:15 AM To: Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: 2016-NRR-UNR-Draft-May 2016 abh rev.docx Amy/Matt, I have incorporated Matt's revisions to task c. I have also provided responses to your comments. Based on our discussion this AM. I would recommend a different UNR for the AMP audits and the strategic harvesting task (task c here), because of the longer time-frame that may be needed. Besides, these two activities may spill over beyond the receipt of first SLR application (later 2018). This major purpose of this UNR to bring a closure to the EMDA issues, to the extent possible (and recommend further technical activities for unresolved or new emergent issues), through workshops/meetings (Task A) and through disposition documents prepared by RES staff (Task B), before the first application comes in. Please feel free to make your final recommendations/suggestions to the comment boxes and send the document to Steve. Also feel free to add/revise language as you see fit. No need to put that on track changes. I (b)(6) , .. INot sure if I will be here this PM.
- Thank so much for your help and support.
Raj 6
From: Hiser, Matt hew Se nt: Thursday, May 19, 2016 8:33 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov> Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: 2016-NRR- UNR-Draft-May 2016 abh rev.docx Hi Raj and Amy, Please find attached (whenever this email gets to you!) my edits of the harvesting section. I am also ccing Pat Purtscher to provide any input on Task C. Thanks! Matt Matthew Hiser Materials Fngineer US Nuclea1 Regulalory Commi:.~ion I Onice of Nuclear RcgulalOry Rc~carch Di, i\ion of h1ginccring I Corro~ion :ind Mc1:illurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov From: Hull, Amy Sent: Thursday, M ay 19, 2016 7:45 AM To: Iyengar, Raj <Raj.lyengar@nrc.gov>
Subject:
2016-NRR- UNR-Draft-May 2016 abh rev.docx Raj , my two cents worth . 7
User Need Evaluate the Aging Management of Systems, Structures, and Components for Subsequent License Renewal
Background:
Although the NRC staff can accept subsequent license renewal (SLR) applications now, the review would be based on guidance provided in NUREG-1800, Revision 2, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants" and NUREG-1 801, Revision 2, "Generic Aging Lessons Learned {GALL) Report - Final Report." Because this guidance applies to plants operating from 40-60 years, additional review would be needed to ensure that the applicant addressed issues anticipated during 60-80 years of plant operation for SLR. Such reviews would be longer and more resource-intensive. To improve the efficiency of SLR application reviews, the NRC staff has undertaken several activities to revise the guidance documents. These activities include reviews of aging management practices, plant audits, technical information exchanges with industry and Department of Energy (DOE), and confirmatory research. In cooperation with the DOE Light Water Reactor Sustainability {LWRS) Program, the NRC completed NUREG/CR-7153, "Expanded Materials Degradation Assessment (EMDA), Vol. 1-5" (ADAMS Accession Nos. ML14279A321, ML14279A331, ML14279A349, ML14279A430, ML14279A461) to identify the most significant 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 fluence;
- Irradiation-assisted stress corrosion cracking of reactor internals and primary system components;
- Concrete and containment degradation; and
- Electrical cable qualification and condition assessment.
The NRC staff conducted several audits to investigate the effectiveness of aging management programs (AMPs). The findings are documented in the report titled , "Summary of Aging Management Program Effectiveness Audits to Inform Subsequent License Renewal: R.E. Ginna Nuclear Power Plant and Nine Mile Point Nuclear Station, Unit 1" (ML13122A007). The development of SLR guidance was based on NUREG-1800 and NUREG-1801, the understanding gained from the audits, NUREG/CR-7153 (EMDA), an evaluation of domestic and international operating experience of nuclear plants, lessons learned from staff review of previous license renewal applications, and assessment of recent research findings. Draft SLR guidance documents were issued in December 2015, as draft "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report," (NUREG-2191, Volumes 1 and 2) and draft "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants" (SRP-SLR) (NUREG-2192). Since the draft guidance documents were issued, the staff has held several public meetings with stakeholders and the public to discuss the proposed revisions and bases for the revisions. The most recent meetings were held on January 2 1 and February 19, 2016. Going forward, the NRC staff will continue to lead outreach activities to stakeholders and the public in order to
provide information on the proposed changes to the guidance documents, solicit feedback on the documents, and revise the documents, as appropriate, to reflect stakeholder and public feedback. The final guidance documents are expected to be issued in mid-2017. To support the review of an SLR application, an applicant will need to demonstrate how the effects of aging will be managed, including those associated with the technical issues listed above. Although the industry is conducting research to address these major technical issues for SLR, not all 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, the NRC will request applicants to address the technical issues with plant-specific programs in their SLR applications. The staff will review these plant-specific programs that address the SLR technical issues, but anticipates a longer application review process in these cases. The requested research described below would provide information to support the staff in effectively evaluating AMPs and developing staff positions on the technical issues identified in EMDA reports. This effort will also augment the staff's preparedness for the evaluation of the feasibility of future applications for an SLR period. These requested products should !build upon analysis methods, tools, and expertise developed as part of ongoing research activities and new research activities focused specifically on aging effects during an SLR period. Description of Scope and Tasks A. Hold NRC/industry workshop(s) on status of domestic and international research activities and operating experience to address and evaluate the status of materials degradation issues identified in the EMDA reports for SLR. Technical Need: In February 2008, the NRC and DOE first co-sponsored a "Workshop on U.S. Nuclear Power Plant Life Extension Research and Development" (ADAMS Accession Number ML080570419), which requested stakeholder input into aging management research areas for "Life Beyond 60." Since then , there have been multiple workshops/meetings on the research activities and operating experience that may impact aging management of SSCs for an SLR period. These meetings have been helpful in facilitating technical discussions, disseminating knowledge and information, enabling the understanding of technical challenges, and paving the path forward for resolution of the challenges and issues related to materials degradation during the SLR period. As the NRC staff prepares for the review of SLR applications, there is a need for continued engagement with 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 SRM and identified in EMDA. Deliverable: RES staff should facilitate several workshops/meetings on operating experience from the initial license renewal period, research results on materials degradation issues, and aging management of SSCs during the SLR period. These meetings should be specifically targeted toward the resolution of technical issues for effective aging management of SSCs during the SLR period. RES staff should provide an annual technical letter report summarizing the understanding gained through the workshops/meetings. The summary should include the status of domestic and international research activities in addressing materials degradation issues and aging management practices during the SLR period. The report should also discuss (1) areas of progress and issues resolution, (2) areas of insufficient progress that may warrant additional NRC-driven
interactions, and (3) any newly identified technical issues that should be considered . Schedule: The effort should last no more than 36 months from the period of inception of this user need request. B. Provide RES staff assessments of the current knowledge and disposition of materials degradation issues identified in the EMDA reports Technical Need: As mentioned earlier, the EMDA reports identified significant technical issues for nuclear power reactor operations beyond 60 years related to materials degradation. These issues fall under the following fou r topical areas, as outlined in SRM on SECY 14-0016:
- Reactor pressure vessel neutron embrittlement at high fluence;
- Irradiation-assisted stress corrosion cracking of reactor internals and primary system components;
- Concrete and containment degradation; and
- Electrical cable qualification and condition assessment.
The NRC, DOE, and industry are addressing the key technical issues related to materials degradation at NPPs. In order to gain better understanding of the materials aging and degradation mechanisms and their implicat ions of structural and compo nent integrity, DOE and the industry have initiated numerous research activities on the four major technical areas. The NRC staff conducts confirmatory research, through several user need requests on specific technical issues, to independently verify licensee data, determine safety margins, and explore uncertainties. In addition, the NRC research will support and increase the efficiency of staff review of SLR applications. To fully support the staff review of the SLR applications, RES should develop staff assessments of the current knowledge and disposition of materials degradation issues related to the four major technical areas. The assessments should also include recommendations on the need for:
- any interim staff guidance (ISG) to address aging management issues, and
- new reg ulatory guidance and/or revision of existing regulatory guides (RGs) to address uncertainties in knowledge and/or potential non-conservat ivism.
Deliverable: Deliver a technical letter report that summarizes the current knowledge and disposition of materials degradation issues identified in EMDA. T he report should also include recommendations on the need for any new or revised guidance to address component integrity of aging structu res. Schedule: The effort should last no more than 36 months from the period of ince ption of this user need request. The initial draft report should be completed by the end of FY 2018. C. 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. Technical Need: The NRC performs confirmatory research to inform and develop the technical basis for regulatory decisions related to aging management programs for
SLR. Historically, this research has included testing small scale specimens or coupons SA-virgin materials under simulated aging conditions, as well as testing and characterization of ex-plant materials harvested from nuclear power plants. Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab. Testing ex-plant materials also reduces the uncertainty associated with the applicability of the aging conditions. Therefore, this effort is expected to provide fundamental insights on reactor materials degradation and information addressing potential technical issues or identified gaps to support anticipated future NRC needs. It will also inform the value of existing databases based on simulated aging conditions by assessing their applicability to in-service conditions. Based on the recent experience of recovering materials from decommissioned plants, such as Zion, Crystal River and Zorita (Spain), the efforts of planning , coordination and eventual 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 d,eveloping a strategic database for obtaining unique and significant materials aging degradation information from ex-plant components. Such a database will enable the NRC to focus its harvesting efforts and expeditiously obtain materials and components from plants to be decommissioned in the near future and develop information and knowledge to assess the efficacy of the AMPs. Deliverable: RES should develop a database covering the four topical areas outlined in SRM on SECY 14-0016 and containing information on:
- research gaps for SLR that may be best addressed by harvesting due to challenges in simulating actual service conditions, and
- materials that can be harvested from to-be-decommissioned NPPs and ex-plant components from operating plants to better inform the NRC's AMPs and aging-related regulatory oversight and to better plan research activities.
RES should deliver period ic reports assessing the effectiveness of such programs and recommending any improvements for the SLR period. Schedule: The effort should last no more than 36 months from the period of inception of this user need request. D. Continue to Develop Domestic and International Partnerships to Share Expertise, Capabilities and Resources Related to Aging Management Research for Long-Term Operations (LTO) Technical 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. Deliverable: Continue to develop agreements with domestic and international partners to collaborate on aging management research that results in information to help inform agency decisions regarding SLR and long-term operations. Integrate as appropriate the results of these collaborative research and information exchanges from international partnerships into Tasks A and B. Provide an annual summary of international collaborative research results and status of interactions (e.g., references to meeting minutes, presentations, technical reports, etc.), highlighting international activities and results that may affect SLR. Schedule: The effort should continue until the closure of this user need request. E. Provide technical assistance, as needed, for preparation of review of SLR applications. Technical Need: As the NRR staff prepares for the anticipated SLR application in FY18, technical assistance from RES staff on emergent issues may be needed. Such issues may include, but not restricted to, providing an assessment of effect of specimen size on the prediction of component performance, technical support for aging management program audits, public meetings related to communication efforts, and confirmatory reviews of licensee submittals. Schedule: This effort, as needed, should continue until the closure of this user need request.
From: Moyer, Carol Sent: Wednesday, November 30, 2016 10:02 AM To: Hiser, Matthew
Subject:
FW: 42 NUSSC Day 1 FYI, Kathryn plugged your workshop in Vienna this week . From: Thomas, Brian Sent: Wednesday, November 30, 2016 9:58 AM To: Brock, Kathryn <Kathryn.Brock@nrc.gov>; Weber, Michael <Micha,el.Weber@nrc.gov>; Hackett, Edwin <Edwin .Hackett@nrc.gov> Cc: Coffin, Stephanie <Stephanie.Coffin@nrc.gov>; Tappert, John <John.Tappert@nrc.gov>; Abu-Eid, Boby <Boby.Abu-Eid@nrc.gov>; Collins, Daniel <Daniel.Collins@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Layton, Michael <Michael.Layton@nrc.gov>; Pstrak, David <David.Pstrak@nrc.gov> Subject : RE: 42 NUSSC Day 1 Thanks Kathryn. Good plug for our research sessions at the RIC and for opportunities to further our collaboration on research. From: Brock, Kathryn Sent: Wednesday, November 30, 2016 3:07 AM To: Thomas, Brian <Bri!!n,ThQm!!~nrc .gov>; Weber, Michael <Michael.Weber@nrc.gov>; Hackett, Edwin <Edwin.Hackett@nrc.gov> Cc: Coffin, Stephanie <Stephanie.Coffin@nrc.gov>; Tappert, John <John.Tappert@nrc.gov>; Abu-Eid, Boby <Boby.Abu-Eid@nrc.gov>; Collins, Daniel <Daniel.Collins@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Layton, Michael <Michael.Layton@nrc.gov>; Pstrak, David <David.Pstrak@nrc.gov>
Subject:
42 NUSSC Day 1 Hello. 42 NUSSC kicked off in the afternoon, so we are really just getting started. The afternoon was spent discussing general business, with a welcome from Greg Rzentkowski (Director NSNI). Greg gave us a summary of the Senior Regulators Meeting including a discussion on the focus on safety/security interface, regulatory readiness, and the concept of strength in depth. NUSSC Chair Fabien Feron gave a summary of the CSS meeting, which was consistent with the information provided by Michele Sampson. Fabien spoke of the need to have a common standards development process, a common glossary, and a holistic review of the complete collection of safety guides. More to come on those topics, I'm sure. There was another demonstration of the IT Platform, NSS-OUI, and a thank you to the USA and Japan for supporting the tool development. I expressed my support of the tool and that we are starting to use it more. Another exciting IT discussion was related to the possibility of remote access to the standards meetings. I believe this was pi loted by EPReSC and RASSC, so I will follow up with my colleagues. This may be helpful to us if we choose to have a support staff member participate in the meetings from DC - it gives the option of reducing travel costs on a second traveler and it gives the opportunity for others to hear the standards committees in action. ln the morning I had a follow up meeting with Ed Bradley and several Directors responsible for research in fuel cycle, waste technology, materials, reactors, and knowledge management. These folks are excited about 1
potential collaborative efforts with NRC and will be providing us some specific areas to consider where research collaboration may be possible. I told them about the RIC and the March meeting on harvesting of ex-plant material for research purposes. They were excited to hear about the RIC, especially the sessions on leveraging international research. That's all for now. Enjoy your day. Kathy 2
Subject:
Ex- Plant Materials Harvesting Workshop Location: HQ-TWFN-P2AUD-300p Start: Tue 03/07/2017 7:00 AM End: Tue 03/07/2017 6:00 PM Show Time As: Tentative Recurrence: (none) Meeting Status: Not yet responded Organizer: Hiser, Matthew Resources: HQ-TWFN- P2AUD-300p Reserving as placeholder for workshop.
Subject:
Ex-plant Materials Harvesting Workshop Location: HQ- TWFN- P2AUD-300p Start: Thu 03/16/2017 1:00 PM End: Thu 03/16/2017 7:00 PM Show Time As: Tentative Recurrence: (none) Meeting Status: Not yet responded Organizer: Hiser, Matthew Resources: HQ-TWFN -P2AUD-300p Reserving as placeholder for workshop around RIC.
Subject:
Ex-plant Materials Harvesting Workshop Location: HQ-TWFN-P2AUD-300p Start: Fri 03/17/2017 7:00 AM End: Fri 03/17/2017 6:00 PM Show Time As: Tentative Recurrence: (none) Meeting Status: Not yet responded Organizer: Hiser, Matthew Resources: HQ-TWFN-P2AU D-300p Reserving as placeholder for workshop around RIC.
Subject:
Ex- Plant Materials Harvesting Workshop Location: HQ-TWFN- P2AUD-300p Start: Wed 03/08/2017 7:00 AM End: Wed 03/08/2017 6:00 PM Show T ime As: Tentative Recurrence: (none) Meeting Status: Not yet responded Organizer: Hiser, Matthew Resources: HQ-TWFN-P2AUD-300p Reserving as placeholder for workshop.
From: Hiser, Matthew Sent: Wednesday, September 14, 2016 3:01 PM To: Vera, Graciela
Subject:
Ex- plant Materials Harvest ing Hi Gracie, Could you schedule a briefing with Brian Thomas on Ex-Plant Materials Harvesting? Please include the following participants: Brock, Kathryn Tregoning, Robert Thomas, Brian Purtscher, Patrick Frankl, Istvan It looks like there are available times on September 27 or 28. Thanks! Matt Matthew Hiser Materia ls Engineer US Nuc lear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Me tallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hise r@nre.gov 1
From: Hull, Amy Sent: Wednesday, September 02, 2015 2:22 PM To: Iyengar, Raj; Hiser, Matthew
Subject:
cross-cutting topic...: Specific Questions for Internals and Piping Materials for Deep-dive meetings
... I will have to do that tomorrow morning. I have to leave in 10 minutes for another meeting.
From: Hull, Amy Sent: Wednesday, September 02, 2015 8:22 AM To: Iyengar, Raj <Raj.lyengar@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Prokofiev, louri <louri.Prokofiev@nrc.gov>
Subject:
RE: Specific Questions for Internals and Piping Materials for Deep-dive meetings I am making 2 changes this morning 1 Adding a cross-cutting line to account for discussions we need to have with EPRI, LWRS, and NEI concerning our new work on prioritization of strategic harvesting opportunities. This is a followup from the Materials TIE presentation Matt H and I made a few months ago in which industry Qeople said they were interested in participating. (2) revised line for Ni alloy DMWs in BMI (followup from AMP Effectiveness Audit at Ginna and SLR SME panel discussions for AMP XI.M11 Bon NI alloys) - this is louri's contribution that he talked to Raj about From: Iyengar, Raj Sent: Tuesday, September 01, 2015 10:46 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
Specific Questions for Internals and Piping Materials for Deep-dive meetings
- All, Please review the word document on the specific questions related to internals and piping materials. Rob expressed an interest in meeting with you all to seek alignment on the questions. Because I w ill not be in before Noon tomorrow, please go ahead with the meeting (Perhaps, o ne of you could schedule the meeting for tomorrow AM). If not, we can meet after 1 PM tomorrow.
I have i ncluded only those sub-issues that require a deep-dive meeting. I have not included sub-issues related to Alloy 600/690, and the CS - BAC sub-issue. If I have missed any, please let m e know. I need to get questions from DLR (at least on the leaching issue). I believe BT/KB would like to see these questions tomorrow PM . We have already settled down o n the questions related to Cables and Con crete. This is the last major issue that would warrant a deep-dive meeting. I have a lso attached the table (with Rob's edits). Than ks a lot for your willingness to put up with me.
Raj 2
Subject:
Ex- Plant Harvesting Coordination Meeting location: HQ-TWFN-10A73-8p Start: Mon 11/20/2017 10:30 AM End: Mon 11/20/2017 11 :30 AM Show Time As: Tentative Recurrence: Weekly Recurrence Pattern: every 2 week(s) on Thursday from 2:30 PM to 3:30 PM Meeting Status: Not yet responded Organizer: Hiserr, Matthew Required Attendees: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert Resources: HQ-TWFN-10A73-8p Rescheduling for Monday so we can all attend. Setting up a standing every other week meeting on harvesting to help us stay on track and keep making progress. Topics:
- Sources of Materials
- Prioritization of Data Needs
- PNNL TLR
Subject:
Ex- Plant Harvesting Coordination Meeting Location: 10th floor huddle Start: Thu 12/07/2017 10:30 AM End: Thu 12/07/2017 11 :30 AM Show Time As: Tentative Recurrence: Weekly Recurrence Pattern: every 2 week(s) on Thursday from 2:30 PM to 3:30 PM Meeting Status: Not yet responded Organizer: Hiser, Matthew Required Attendees: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert Setting up a standing every other week meeting on harvesting to help us stay on track and keep making progress. Topics:
- Sources of M aterials
- Prioritization of Data Needs
- PNNL TLR
Subject:
Ex-Plant Harvesting Coordination Meeting Location: 10th floor huddle Start: Mon 12/11/2017 1:00 PM End: Mon 12/11/2017 2:00 PM Show Time As: Tentative Recurrence: Weekly Recurrence Pattern: every 2 week(s) on Thursday from 2:30 PM to 3:30 PM Meeting Status: Not yet responded Organizer: Hiser, Matthew Required Attendees: Purtscher, Patrick; Audrain, Margaret Setting up a standing every other week meeting on harvesting to help us st ay on track and keep making progress. Topics:
- Sources of Materials
- Prioritization of Data Needs
- PNNL TLR
Subject : Ex- Plant Harvesting Coordination Meeting Location: HQ-TWFN-1 OA73-8p Start: Tue 01/09/2018 2:00 PM End: Tue 01/09/2018 3:00 PM Show Time As: Tentative Recurr,ence: Weekly Recurrence Pattern: every 2 week(s) on Thursday from 2:30 PM to 3:30 PM Meeting Status: Not yet responded Organizer: Hiser, Matthew Required Attendees: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert Resources: HQ-TWFN-10A73-8p Setting up a standing every other week meeting on harvesting to help us stay on track and keep making progress. Topics:
- Sources of Materials
- Prioritization of Data Needs
- PNNL TLR
Subject:
Ex-Plant Harvesting Location: 10th floor huddle room Start: Thu 08/18/2016 11 :00 AM End: Thu 08/18/2016 11:30 AM Show Time As: Tentative Recurrence: (none) Meeting Status: Not yet responded Organizer: Hiser, Matthew Required Attendees: Frankl, Istvan; Tregoning, Robert; Purtscher, Patrick I think it would be good to get everyone on same page regarding next steps for the harvesting program. We have an early draft of the PNNL deliverable, with the final version expected in early 2017. I'd like to discuss that work as well as the workshop that was discussed with NRAJ last week and been discussed previously. Thanks,! Matt 1
From: Iyengar, Raj Sent: Thursday, May 18, 2017 9:22 AM To: Moyer, Carol Cc: Frankl, Istvan; Martinez Rodriguez, Erick
Subject:
RE: Draft Notes for EPRI mtg 6/ 6 Update from the AM meeting (per Office TA): Talking points at a high-level (only strategy and vision) - Programmatic details could be addressed later throug h other exchanges. From: Moyer, Carol Sent: Thursday, M ay 18, 2017 9:15 AM To: Iyengar, Raj <Raj.lyengar@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>; M artinez Rodriguez, Erick <Erick.MartinezRodriguez@nrc.gov>
Subject:
RE: Draft Notes for EPRI mtg 6/6 OK, thank you, Raj . From: Iyengar, Raj Sent: Thursday, May 18, 2017 9:12 AM To: Moyer, Carol <Carol.Moyer@nrc.gov> Cc: Frankl, Istvan <l~tvan.Frankl@nrc.gov>; Martinez Rodriguez, Erick <~ri~k.M~r!_inezRodriguez@nrc.gov> Subject : RE: Draft Notes for EPRI mtg 6/6
- Carol, I have a number of things to do today. I will see what I can do.
CMS can provide its input to Erick. I can add to it later, if needed . CIB staff has already developed one-pagers for RG1 .99 and xLPR. The topics on Adv. Man. And Gen IV materials come from EPRI. EPRI will be providing brief to our management on those two topics. I have a meeting with Steve Bajorek on IAP 2. I will ask him what Mike Case wants. As you know that topics on IAPs is led by Mike Case. We can certainly provide Brian some talking points on our efforts. Raj From: Moyer, Carol Sent: Wednesday, May 17, 2017 6:17 PM To: Iyengar, Raj <Ra j.lyengar@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Martinez Rodriguez, Erick <~ri.£1~...ME.rti,:iezRodriguez@nrc.gov>
Subject:
Draft Notes for EPRI mtg 6/6 Importance: High Raj ,
I have been drafting some notes for the EPRI-NRC management meeting on 6/6, but I don't want to duplicate your efforts on this. Can we combine what we have collected so far, and then see what is missing? There are topics here that clearly fall within CIB's scope, e.g., RPV embrittlement (RG 1.99), and some that belong to Ian's branch. Also, I let Steve Bajorek know that I would draft some notes on Advanced Reactors, but that I would be looking to him to fill in status on the computational codes. Steve let me know that Brian would like to see draft notes by Thursday (tomorrow), so I hope that we can discuss this in the morning.
- 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 301-4 15-2153 2
Subject:
Ex-Pilant Harvesting Coordination Meeting Location: HQ-TWFN-10A73-8p Start: Wed 10/18/2017 9:00 AM End: Wed 10/18/2017 10:00 AM Show Time As: Tentative Recurrence: Weekly Recurrence Pattern: every 2 week(s) on Thursday from 2:30 PM to 3:30 PM Meeting Status: Not yet responded Organizer: Hiser, Matthew Required Attendees: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert Resources: HQ-TWFN- 1OA73-8p I' ll be off Thursday afternoon - any chance we can move this to Wednesday morning? Setting up a standing every other week meeting o n harvesting to help us stay on track and keep making progress. Topics:
- Sources of Materials
- Prioritization of Data Needs
- PNNL TLR
Subject:
Ex-Plant Harvesting Coordination Meeting Location: 10th floor huddle Start: Thu 10/19/2017 9:30 AM End: Thu 10/19/2017 10:30 AM Show Time As: Tentative Recurrence: Weekly Recurrence Pattern: every 2 week(s) on Thursday from 2:30 PM to 3:30 PM Meeting Status: Not yet responded Organizer: Hiser, Matthew Required Attendees: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert I'll be off Thursday afternoon - any chance we can move this to Thursday morning? Setting up a standing every other week meeting on harvesting to help us stay on track and keep making progress. Topics:
- Sources of Materials
- Prioritization of Data Needs
- PNNL TLR 1
From: Hiser, Matthew Sent: Thursday, October 19, 2017 9:31 AM To: Tregoning, Robert
Subject:
Ex-Plant Harvesting Coordination Meeting Meg is in, so we'll meet - I can call you on the same number. Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Enginee ring I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov
From: Hiser, Matthew Sent: Thursday, October 19, 2017 10:13 AM To: Audrain, Margaret
Subject:
Ex-Plant Harvesting Coordination Meeting Hi Meg, The names Rob mentioned at ANL are Omesh Chopra and Bill Shack. I'm sure Bogdan will know who they are; my understanding is both authored numerous NU REGs over the years ... Thanks! Matt Matthew Hiser Materia ls Engineer US Nuclear Regulatory Conunission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Me ta llurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov
From: Hiser, Matthew Sent: Friday, December 01, 2017 3:33 PM To: Frankl, Istvan; Tregoning, Robert; Purtscher, Patrick; Audrain, Margaret
Subject:
DE Briefing on Harvesting Attachments: Harvesting One Pager 12 17.docx Note to requester: Attachment to email document immediately follows. Hi Steve, I have attached a draft one-pager that could be used to brief Brian and Chris on the harvesting efforts in the context of their questions regarding the ANL travel. Do you mind if I go ahead and schedule something with them for next week? Meg, Pat, and Rob, please feel free to edit/ comment on this draft one-pager as necessary. Thanks! Matt
Ex-Plant Materials Harvesting One-Pager Motivation and Objective:
- Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.)
o Generally, research involves accelerated, simulated aging conditions in a lab which may not be as representative of actual in-service aging o Highly representative materials (actual plant components) and aging conditions reduces the uncertainty associated with the applicability of research findings.
- With plants shutting down both in the U.S. and Europe, there are increasing opportunities to harvest components from decommissioning plants.
- Insights from ex-plant harvesting would support regulatory decisions for subsequent license renewal (SLR), and could have implications for the current license period o There is a task in the new UNR for SLR from NRR/DLR requesting RES to investigate opportunities for harvesting where appropriate.
Past Activities:
- Workshop in March 2017 o NRC staff hosted a 2-day workshop with interested stakeholders, including domestic and international utilities and research organizations, to discuss benefits and challenges associated with ex-plant harvesting.
o Sessions covered motivation for harvesting, data needs, sources of materials, lessons learned, the practical aspects of harvesting, and harvesting decision-making and planning o The discussion focused on the importance of clearly identifying the need and purpose for performing a harvesting project. All participants agreed harvesting is a complex and expensive proposition, but one that can be worthwhile if the need is clearly defined and addressed.
- PNNL Report on Harvesting Criteria o PNNL has produced a draft final report for NRC on criteria for harvesting decision-making and planning o Provides overview of past harvesting efforts and lessons learned as well as suggestions for approach to prioritize data needs for harvesting
- PLiM o NRC staff provided a presentation, poster, and paper for the recent PLiM conference in October 2017.
Path Forward:
- Focused on two parallel efforts:
o Developing alignment within NRC on prioritization of harvesting data needs
- Use criteria identified in PNNL report establish effective prioritization scheme for relevant areas: RPV, RPV internals and other metals, electrical components, concrete o Developing a database identifying sources of materials for harvesting
- Start with lab-based "boneyards" of prior harvest ed materials
- Visits to ANL, PNNL, and ORNL (leveraged with already planned travel) support this activity
- Coordinate with DOE NSUF Nuclear Fuel and Materials Library (NFML) run by INL as appropriate and beneficial
From: Oberson, Greg Sent: Thursday, June 09, 2016 11 :48 AM To: Hiser, Matthew
Subject:
contact Al Ahluwalia
- Matt, You could contact Al about the Korea plant material harvesting: kahluwal@epri.com 1
From: Frankl, Istvan Sent: Monday, June 06, 2016 3:02 PM To: Hull, Amy Cc: Hiser, Matthew
Subject:
COR Change for Strategic Harvesting Contract with PNNL Importance: High Follow Up Flag: Follow up Flag Status: Flagged
- Amy, Are you OK with Pat assuming COR duties for subject contract?
You will continue to be retained as Technical Monitor. Please let me know ASAP.
- Thanks, Steve
From: Tregioning, Robert Sent: Wednesday, November 18, 2015 10:55 AM To: Hiser, Matthew; Hull, Amy
Subject:
DLR user need Matt/Amy: So NRR\DLR agreed to add the harvesting task to UNR 2010-006. Please verify with Steve that he wants you to start working on this with DLR staff (Bennett/Hiser) .... 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 Blackberry: I I JpJ{§) fax: 301-415-6671
Subject:
Discuss PLiM Presentation on Harvesting Location: HQ-0WFN-08B02-12p Start: Thu 10/12/2017 2:00 PM End: Thu 10/12/2017 3:00 PM Show Time As: Tentative Recurrence: (none) Meeting Status: Not yet responded Organizer: Hiser, Matt hew Required Attendees: Hiser, Allen; Tregoning, Robert; Moyer, Carol; Hull, Amy; Purtscher, Patrick Resources: HQ-OWFN-08B02-12p
From: Moyer, Carol Sent: Thursday, July 27, 2017 10:31 AM To: Hiser, Matthew
Subject:
Decommissioning meeting next June Hi Matt, Just FYI, I came across an advertisement for this meeting on Decommissioning, to be held next June in TN: http://www.exchanqemonitor.com/evtx/decommisioninq-2018/ This appears to be a business/commercial meeting, not a technical conference. But I thought it might be good to know about it, for scheduling & networking purposes, related to your harvesting work. Carol Carol Moyer Sr. Materials Engineer RES/DE/ CMB carol.moyer@nrc.gov 301-415-2153
From: Hiser, Matthew Sent: Friday, May 15, 2015 8:21 AM To: Focht, Eric; Murdock, Darrell; Sircar, Madhumita Cc: Hull, Amy
Subject:
Ex-Plant Materials Harvesting Attachments: title and time: June materials meeting Note to requester: Attachment to this email document is immediately fol lowing. Hi Mita, Darrell, and Eric, I am working with Amy Hull in my brranch on an effort associated with strategic harvesting of ex-plant materials. This effort is just getting underway, but we would like to present the concept at an NRG-industry materials meeting in early June (see attached email). The purpose of this effort is to develop a more systematic proactive "strategic" approach to ex-plant material harvesting, rather than the more reactive opportunistic approach to date. It is important to share this concept with industry, since they will be vital in providing connections/communication to allow future harvesting projects to take place. I am putting together a slide or two on the reactor internals materials harvesting project at Zorita that I am involved with. I understand each of you have been / are involved with other harvesting efforts at Zion and Zorita on cables, concrete, and neutron absorbers. If you could just provide a slide or two with a high-level overview of the harvesting project and at least briefly touch on how the harvesting opportunity came together, that would be great. Thanks! Matt 1
From: Hull, Amy Sent: Friday, May 15, 2015 7:44 AM To: Treg oning, Robert Cc: Hiser, Matthew; Frankl, Istvan
Subject:
title and time: June materials meeting Strategic Approach for Obtaining Material and Component Aging Information Amy Hull & Matt Hiser 30 minutes, Matt will talk 15 minutes about current approach to ( and results from) ex-plant harvesting and then I will talk 15 about where we are going From: Tregoning, Robert Sent: Thursday, May 14, 2015 3:43 PM To: Hull, Amy
Subject:
June materials meeting Amy: I just need a title and an allotted time for your Ex-plant Material Database presentation for the June meeting. Can you send me something either today or early tomorrow? Thanks so much, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 21 Church Street, M/S CS-5A24 Rockville, MD 20850 ph: 301-251-7662 Blackberry: , - - - !
... -. *.-....-.....-..... Jb)(§)
fax: 301-251-7425
From: Hull, Amy Sent: Tuesday, November 10, 2015 3:11 PM To: Hiser, Matthew
Subject:
Bloom approved time of Heather, Bernie, Bennett person NRC affiliation Why? Frankl. Steve CMB Chair (amy asked his interest earlier} Hiser, Matt CMB Member (alternate COR, technical monitor); Zorita ex-plant harvesting Hull, Amy CMB Member (COR, T M) Tregoning, Rob RES/DE Sr advisor for work Kanney. Joe RES/ORA Member (technical monitor); LTRP Steve Bloom approved NRR/DLR/RSRG Bernie - knows plants availability of Bernie, Heather, Heather - knows regional Bennett folks Bennett - plant audits, OpE Murdock, Daryl RES/DE electrical Burke, John RES/DE concrete Mike Benson RES/DE/CIB CODAP POC; database development Oberson, Greg RES/DE/CMB Zion questionnaire; EMDA; ex-plant harvesting Cumblidge, Steve; Dave Alley NRR/DE Member (PNNL & PMMD background} Bob Hardies NRR/DE Member Gary Stevens NRR/DE Member Darrell Dunn or John Wise N MSS/DSFM/RMB Member (decommissioned (Csontos branch) plant availability) Watson, Bruce NMSS Recommended by Steve Bloom Amy B. Hull, Ph.D Senior Materials Engineer RES/OE/CMB (office T10*D4g) US Nuclear Regulatory Commission 11545 Rockville Pike Rockville, Maryland 20852 Telephone: (301) 415-2435 e*mail. amy.hull@nrc.gov 1
From: Hull, Amy Sent: Monday, March 05, 2018 8:47 AM To: Hiser, Allen; Moyer, Carol; Hiser, Matthew Cc: Frankl, Istvan; Rudland, David; Ruffin, Steve; Frankl, Istvan
Subject:
attached: RIC Harvesting & AM Posters Attachments: RIC Poster 6 on AM_20180213.pptx; RIC Poster 8 on Harvesting_20180213.pptx Note to requester: Attachments to this email document are immediately See attached. I also included the AM poster. following. From: Hiser, Allen Sent: Thursday, March 01, 2018 3:58 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer @nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov> Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Rudland, David <David .Rudland@nrc.gov>; Ruffin, Steve <Steve. Ruffi n@nrc.gov>
Subject:
RIC Harvesting Poster Importance: High Can I get a copy of the RIC harvesting poster?
- Thanks, Allen
Review of Additive Manufacturing by Direct Metal Laser Melting A. Hull, T. Herrity, and C. Moyer, U.S. Nuclear Regulatory Commission (NRC} Background and Motivation Current Activities Path Forward The NRC has been informed that parts created by additive manufacturing (AM) The NRC is developing a strategic plan to address the use of additive AM has been identified as a technique that the nuclear industry may use in the are being considered for applications in the operating fleet as early as calendar manufacturing for reactor materials and components. The NRC plans to leverage future. Prevailing questions are: How will AM be used in nuclear power plants. and year 2018. In 2017, industry prototyping efforts involved use of the direct metal ongoing research and evaluation of this technology being performed by Federal when? What is the regulatory infrastructure for determining how safe it is? laser melting (DMLM) method to manufacture parts for reactor components. The counterparts. Office of Nuclear Regulatory Research is beginning to evaluate the technology to NRC areas of interest include the quality, properties. and structural performance of gain insight into any technical issues that must be addressed to assure safety and The NRC strategic plan will focus on topic areas of interest identified at the AM parts, including their inspectability. The service performance and aging reliability of specific DMLM-produced components that may be accepted by the Additive Manufacturing for Reactor Materials and Components public meeting: degradation of AM parts are critical. It will be essential to compare the NRC, including design, precursor materials, finished material properties, structural performance of parts from AM and those from conventional manufacturing integrity, nondestructive evaluation. and quality assurance. This welding-based processes. process may be susceptible to, for example, porosity, systematic defects. and ,:, Quality of AM materials and components for nuclear power plants anisotropy of properties not currently addressed for conventionally manufactured ,:, Codes and standards development for AM components. ,:, Properties and structural performance Challenges to be addressed include the limited understanding of acceptable ranges of variation for key manufacturing parameters. limited understanding of key
*:* Service performance/aging degradation failure mechanisms and material anomalies, the potential for systematic defects.
On November 28-29, 2017, the NRC held a public meeting entitled, "Additive *:* Regulatory infrastructure cybersecurity considerations. lack of industry databases, and lack of industry Manufacturing for Reactor Materials and Components." Presentations from specifications and standards. The development of codes and standards for AM is 28 speakers representing American and international industry, EPRL NEI, DoD key to successful implementation. facilities. DOE and National Laboratories. ASME. ASTM. ANSI, FAA. NASA. and NIST are available in ADAMS (Accession No. ML17338A880). International Amencaa ASTM Organization Societyof Mechanical International Standardization Engineers IEE ........ SAE International Ste l~IUJUIKHl.ll, American Wei.ding Society Institute of
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DMLM Process Demonstration Specimen at GE Power Advanced Westinghouse's DMLM Examples: Thimble Plugging Device. Advanced Standards Development Organizations involved with AM Manufacturing Works, Greenville, SC. C. Moyer. December 11. 2017. Debris Filtering Bottom Nozzle, B. Cleary, November 28, 2017. Standardization, J. McCabe, November 29, 2017
Harvesting of Aged Materials from Nuclear Power Plants M. Hiser0 , P. Purtscher0 , P. Ramuhallib, A.B. Hull 0 , and R. Tregoning 0 ; 0 U.S. Nuclear Regulatory Commission (NRC), bPacific Northwest National Laboratory Background and Motivation Potential Criteria for Harvesting Prioritization Harvesting Database Recent developments in the nuclear industry include stronger interest in extended A number of criteria may be considered when prioritizing the data needs for The NRC is pursuing the development of a database for sources of materials for plant operation and plans to shut down a number of nuclear power plants (NPPs). In harvesting, including the following: harvesting, which could include both previously harvested materials and those the United States, there is strong interest in extending NPP lifespans through , Applicability of harvested material for addressing critical gaps available for future harvesting. This database would allow for aligning high-priority subsequent license renewal (SLR) from 60 to 80 years. _ Harvesting for critical gaps is prioritized over less essential technical gaps. data needs to the available sources of materials. The level of detail for the database Extended plant operation and SLR raise a number of technical issues that may should be appropriate for the factors influencing decisionmaking. The NRC is
, Ease of laboratory replication of the degradation scenario interested in engaging with other organizations in developing the database.
require further research to understand and quantify aging mechanisms. U.S. utilities _ For example, simultaneous thermal and irradiation conditions are difficult to and the U.S. Nuclear Regulatory Commission (NRC) have focused on the aging of systems, structures, and components and in particular four key SLR issues: reactor replicate, and accelerated aging may not be feasible for a mechanism Path Forward pressure vessel embrittlemenf, irradiation-assisted stress-corrosion cracking of reactor sensitive to dose rate. internals, concrete structures and containment degradation, and electrical cable
- Unique field aspects of degradation In the NRC's experience, harvesting can yield highly representative and valuable data qualification and condition assessment. _ For example, unusual operating experience or legacy material (fabrication on materials aging, but these efforts will be challenging. Having a clearly defined Meanwhile, in recent years, a number of NPPs, both in the United States and methods, etc.) is no longer available. objective and early engagement with other stakeholders are keys to success. As internationally, have shut down or announced plans to shut down for various , Fleet-wide vs. plant-specific applicability of data specific harvesting opportunities are identified through this strategic approach, the reasons, including economic, political, and technical challenges. Unlike in the past _ There is greater value in addressing an issue applicable to a larger number of NRC welcomes opportunities for cooperation and leveraging of resources with other when there were very few plants shutting down, these new developments provide plants. interested research organizations.
opportunities for harvesting components that were aged in representative , Harvesting cost and complexity light-water reactor environments. Plate A (41.22" wide) _ For example, harvesting In a third related development. economic challenges and limited budgets have unirradiated concrete or electrical restricted the resources available to support new research, including harvesting cables is less expensive and less programs. Given this constrained budget environment, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future research programs. complex than harvesting from the reactor internals or reactor pressure vessel. A j Plate C (7.8" wide)
- Availability of reliable inservice Current Activities inspection (ISi) techniques for the it .t The NRC has recently undertaken an effort, with the assistance of Pacific Northwest material/component ...,
_ If mature inspection methods exist National Laboratory, to develop a strategic approach to harvesting aged materials and are easy to apply, harvesting from NPPs. Because of limited opportunities, past harvesting efforts have been may be less valuable. reactive to individual plants shutting down and beginning decommissioning. Given the expected availability of materials from numerous plants and anticipated , Availability of materials for harvesting research needs to better understand aging out to 80 years of operation, the NRC is , Timeliness of the expected research ' pursuing a more proactive approach to prioritize the data needs best addressed by results relative to the objective. harvesting and identify the best sources of materials to address high-priority data needs for regulatory research. /'::,* The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario and should be defined with / I as much detail as appropriate in terms of the material (alloy, composition, etc.) and environment (temperature. fluence, chemistry, etc.). lifting operation for irradiated Example of reactor internals harvesting plan materials transport cask
From: Hull, Amy Sent: Friday, May 19, 2017 10:42 AM To: Hiser, Matthew
Subject:
Appendix 2 has what I wanted ---- sorry,...finishing now, 3rd version lost on citrix...[eom]: pis will you send me the draft summary report?: 3 sections revised -- CMB update 20170517. From: Hull, Amy Sent: Friday, May 19, 2017 10:37 AM To: Hiser, Matthew <M atthew.Hiser@nrc.gov> (b )(6)
Subject:
commenfinishing now, 3rd version lost on citrix .... : I will take along printout to! !and get any comment s back to you by 8am tomorrow morning..... [eom]: pis will you send me the draft summary report?: 3 sections revised -- CMB update 20170517.docx ...a main thing, I think it would be useful to attach the agenda to the summary report as an appendix, and to have a table of contents at the front (since it is already 26 pages). This will be archived in ADAMS and you want to have the information easily retrievable in the future. I will send you the detailed corrections but as it stands it does not include title of presentations and attaching the agenda would avoid having to write this in. From: Hull, Amy Sent: Thursday, May 18, 2017 8:31 AM (b)(6) To: Hiser, Matthew <Matthew.Hiser@nrc.gov::> ... ***'
Subject:
I will take along printout t oj land get any comments back to you by 8am tomorrow morning..... [eom]: pis wi ll you send me the draft summary report?: 3 sections revised -- CMB update 20170517.docx From: Hiser, M atthew Sent: Tuesday, May 16, 2017 10:42 AM To: Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: pis will you send me the draft summary report?: 3 sections revised -- CMB update 20170517.docx Hi Amy, Sure thing - here you go © Please take a look and provide any comments or edits. Thank s! Matt Matthew Hiser Materi al s Fnginccr US Nuclear Regulatory Commission I Oflice of Nuclear Regulatory Research Di, i~ion of Fngineering I Corro~ion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062
Matthew.Hiser@nrc.gov From: Hull, Amy Sent: Tuesday, M ay 16, 2017 10:34 AM To: Hiser, M atthew <Matthew.Hiser@nrc.gov>
Subject:
pis will you send me the draft summary report?: 3 sections revised -- CMB update 20170517.docx Strategic Approach for Obtaining Material and Component Aging Information (Amy Hull, Pat Purtscher, Matt Hiser) (LTRP)
- Strategic harvesting is one of the new tasks in the new SLR UNR that will replace NRR-2010-006. Staff are working on specific task for Strategic Harvesting in NRR-2017-006.
- Final deliverable expected by early 2017. Final report publication will wait until after harvesting workshop in March.
- Proceedings from the Ex-Plant Materials Harvesting Workshop, held on March 7-8, are compiled in a CMB SharePoint site http://fusion.nrc.gov/res/team/de/cmb/LTO/default.aspx?RootFolder=%2Fres%2Fteam%2Fde%2Fcmb%2FLTO%
2FProqram%20Documents%2FStrategic%20Approach%20for% 200btaininq%20Material%20and%20Component
%20Aqinq%20lnformation&folderCTID=Ox012000A4119D2C08121 A4CAE71 D67 AEB499BF9&View={A08F4584
-F7E9-4960-9890-37F16055A 16F} . Good frank discussion witln external parties from DOE, EPRI, and international stakeholders on benefits and challenges of harvesting.
- CMB staff preparing workshop summary report (expected by end of May) and follow-up on action items with
.interested workshop attendees focused on a database for sources of materials and prioritizing data needs for harvesting.
- Pradeep Ramuhalli, PNNL contractor, visited RES/DE/CMB staff concerning this project on 4/18/2017. This was a side-trip for another NOE/OLM project funded by DOE related to advanced reactors.
- One-pager submitted for DE management review.
From: Hull, Amy Sent: Tuesday, May 16, 2017 10:28 AM To: Frankl, Istvan (lstvan.Frankl@nrc.gov) <lstvan.Frankl@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Hiser, M atthew <Matthew.Hiser@nrc.gov> Subject : 3 sections revised -- CM B update 20170517.docx 2
From: Hull, Amy Sent: Monday, April 20, 2015 12:01 PM To: Frankl, Istvan
Subject:
answer plus more....: ACTION: Topics for NRC/lndustry Materials Meeting in June Categories: Strategic R&D ex-plant materials ( 1) At the 3/13/2014 NRC/NEI quarterly meeting, both EPRI and PWROG mentioned that they were completing the review of their documents from the perspective of SLR. At that meeting, I mentioned the upcoming June meeting and how that would be a most welcome presentation (listing of references that both groups will revise for SLR, we need to make sure that our references in SLRGOs are consistent with that). (2) Here are my notes from our discussion last Thursday. Please read below and let me know if I do not adequately capture your thoughts. I can give the presentation anytime after May 12 (after NEI and NESCC presentations). Please can you direct me to where I can get access to the PWSCC briefing slides? I guess they are on Gdrive somewhere. 4/16/2015 Steve Frankl initiated discussion about Mgt briefing on SLR
- Somewhat parallel to PWSCC briefing just completed (amy action - get slides!)
- 40 slides, maybe 45 minutes with 15 minutes for discussion
- Briefing on entire scope of RES activity with license renewal & aging management o Historic o Where now o RES deliverables for DLR
- Talk about Commission requests o Be more prepared
- During recent mgt retreat, SLR was singled out on gap analysis and action plans o Relationship between regulatory & technical (research) issues o Look at gaps in process o Possible UNR revision or addition
- Build program o Discuss action plans about how going forward o Resource needs (additional staff for CMB) o Relationship of CMB with other parts of RES (ORA and DE (Rudland, Burke, Sydnor, etc))
o New SOW on harvesting ex-plant materials & database of research prioritization o How to get more out of our MOUs with DOE LWRS and EPRI LTO o International participation in programs (IAEA, CSNI, IFRAM, etc) From: Frankl, Istvan Sent: Thursday, April 16, 2015 5:19 PM To: RES_DE_CMB
Subject:
ACTION: Topics for NRC/Industry Materials Meeting in June 1
- All, Please review Rob's request below and identify topics that we want to make sure are covered during subject materials meeting. Please provide inputs to me no later than COB Wednesday.
- Thanks, Steve
Original Appointment-----
From: Tregoning, Robert Sent: Wednesday, April 01, 2015 10:38 AM To: Tregoning, Robert; Rudland, David; Frankl, Istvan; Rosenberg, Stacey; Alley, David; Karwoski, Kenneth; Mitchell, Matthew
Subject:
Topics for NRC/Industry Materials Meeting in June When: Thursday, April 23, 2015 9:00 AM-10:00 AM (UTC-05:00) Eastern Time (US & canada). Where: HQ-0WFN-09B02-12p All: Purpose is to identify topics that we want to make sure are covered during the materials meeting. Please come to the meeting with your recommendations after polling your staff. The draft topic list will then be shared with industry to finalize the meeting agenda. Meeting is a little later than normal this year, but this is the earliest date/time that everyone is available.
- Cheers, Rob 2
From: Hiser, Matthew Sent: Wednesday, November 08, 2017 4:33 PM Note to Requester: To: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert Attachment to this email
Subject:
Ex-Plant Harvesting Coordination Meeting document is Attachments: Harvesting Needs Prioritization 11 17.xlsx immediately following. Updated criteria titles and "ot her metals" spreadsheet per the feedback received last week. Let's t ry t o run these "other metals" ideas and discuss at our next meeting. Thanks! Matt 1
Criteria Title Description Scoring Guidance H = High MH = Medium-high Criticalness of Technical Gap Harvesting to address critical gaps should be p1ioritized over less M = Medium Addressed essential technical gaps ML= Medium-low L= Low Degradation mechanisms that are harder to replicate with sim ulated aging conditions would be of higher priority fo r harvesting. For example, simultaneous thermal and irradiation conditions are difficult Difficulty of Laboratory to replicate outside of the plant environment. Alternatively, Replication acce lerated aging may not be feasible for a mechanism sensitive to dose rate. These two degradation mechanisms may be best evaluated using harvested materials. For example, legacy mate1ials (e.g. , fabrication methods, composition) that are no longer available, but may play an important Uniqueness Field Aspects of role in a potential degradation mechanism, wou ld have a higher Degradation priority than harvesting materials that can be obtained from other sources. There is greater value in developi11g knowledge to address an issue Applicability to US Operating that may be applicable to a larger number of plants compared to one Fleet that may only affect a relatively small number of plants. lf mature in pection methods exist and are easy to apply to monitor Abse nce of Available Inspection degradation, harvesting may be less valuab le. lf inspection methods Methods do not exist, harvesting may be essential to ens ure confidence in the assessment of age-re lated degradation in that particul ar component. Lower Confidence in Relevant The less confidence that NRC staff has in the effectiveness of the AMP relevant AMP, the higher priority for harvesting. Activities with higher costs and complexity are less attractive than similar activities with lower cos ts and that are simpler to execute .. Harvesting cost and complexity For example, harvesting unirradiated concrete or electrical cables is less expensive and less complex than harvesting from the RPV intema.ls or the RPY. The ability of a potential harvesting program to provide timely results Timeliness of results to support either a technical or regulatory need is important. Having high confidence that results will be timely increases the priority. Availability of materials for The availability of materials to harvest fo r a particular data need is harvesting clearly essential and increases the priority.
Tec.hnic:-11 Crite ri.a PurpoM I Tuting Technic.al Knowl,edge G.ain,ed Crltl~H of T.chnleal Difficulty of Labor-.tory Unlqueon.a Flekl .l5pecl5 AppliCifbilitY to us Ope~ting Fleet Absence of A'Rlilable l.ower Confidence AMP In Relennt S CO<*
- I
,.vengel 8ffi5for PrioritY Planned GapAddreu.d Replication of Degradation ll'ISpec.tion Methods METALS Scor* Comme-nt Seo,.. Comment Score Comment Score CQfflrl'lflnl Likely extent d¥0i<I sweang in ViQge QQtnPOSi'lions ~lo,VC-, S:wne conMel'lce n Vt/f!IYhigl'ICO$l, bu'ltaclcQl d N I ttQh nuence ,eacso, inliemals Void sweHit1g, meCNnieal
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Purposa / Testing A ltornatlve to Priori ty/ Unique .aspects of ISi Need Description Planned Technical Knowledge Gai ned Benefit I Significance Cost Harvestino? Value Basis for Priority harvested materials availablilitv? METALS RPV - H1!11 nuence & high Measure fluence. Hl!Jl cost not justilled by benefit shirt vessel with wen- toughne5s, & chemistry as Through thickness section 10 Increases confidence gN'en surveil lance specimens Vintage compositions established unirr&diated a function of through- vafldate Quence & attenua1ion in e.xisting regulatory and well-estabfished and irradiattOfl proper1ie$ thi1;kne$S posilion models ,eapp,o,ach High No LOW emritllement trend correlations conditions Pmvld8S data suppor'llng evoluUon Enable measuremeni of from the use of coneladve (Charpy- Hl!Jl cost not justified by benefit both the Charpy transrtioo based) to dlrect measurement Increases confidence given surveillance specimens Vintage compositions RPV - Samples from wtualty curve and master oorve (fracture toughness-based) in existing regulatory and well-established and realisOc irradia6on any vessel transition temperature TO approaches 8J)Pf08ch lf,gt, No LOW emrittlement trend correlations oondi6ons
Purposa / Testing Altornatlve to Priority/ Unique .aspects of ISi Need Description Planned Technical Knowledge Gained Benefit I Significance Cost Harvestino? Value Basis for Priority harvested materials availablilitv? ELECTRICAL l ow and medium voltage cables Medium HIGH Cables protected with nre ,etardant coaling 1E MOVs from haNioh and mild ec,vironmenls Medium 1E Ail operated valves; 4160 1E breakers Low 1E Molded case breakers
- aov.2sov oc. 125 voe. Low 1 E Relays lrom mild envitonment GE - HFA.
Agastat timing 1'8lays, an)' from Westinghouse, Potter Brumfield, Stutllers Dunn etc .. Low Batteries Low Eleclrical penetrations Fire researd'l l nterest Electrical enclosures Distribubon : swi1digear, MCCs. LCs I Conttol: Horseshoe. SSC P. ASP. etc.
Purposa / Testing Altornatlve to Priority/ Unique .aspects of ISi Need Description Planned Technical Knowledge Gai ned Benefit I Significance Cost Harvestino? Value Basis for Priority harvested mate rials availablilitv? METALS CONCRETE Fills data gap for Struc.ture-s exposed to high ~iation Change in properties due to irradi1;1tion etfects Loss of strength due to irradiation extend~ ~anl operation ...,, HIGH Post-tensioned structures Medium LOW Corrnslon of relnfo,cing steel, tenoon, liner, embedment Medium LOW Spent fuel pooJ and 11arisfe.r canai..boric acid attaclo. on concrete in PWR:s Medium LOW Allall Aggregate Reaebon "-19d,um LOW Validat8 assumpbons lal'Q8 structural sections fot Eff8cts of concrete aging of aging eff8clS at testing on structural capacity larger sca les High LOW
From: Tregoning, Robert Sent: Tuesday, September 04, 2018 9:59 AM Note to requester: To: Hiser, Matthew Attachment to this
Subject:
Copy of Harvesting Needs Prioritization 8-31 -18 rlt.xlsx Attachments: email is immediately Copy of Harvesting Needs Prioritization 8-31-18 rlt.xlsx following. Matt: Here's. my stab at RPV. There are certainly several other rows that could be added to list, but I'll let Mark take first stab at that.
- Cheers, Rob
Criteria Title Description Scoring Guidance H = high risk significance / little to no available data MH = Medium-high risk significance / limited data available Crilicalness of Technica l Gap Harvesling 10 address crilical gaps should be prioritized over less M = Mode rate risk significance / some Addressed csscnlial 1cchnical gaps data available ML = low to moderate risk slgnficance / H = High sufficient data available for regulatory MH = Medium-high decisions M = Medium L = Low risk significance / large amount ML= Medium-low of data available L = Low H = Nearly impossible to replicate Key considera1ions arc the ease of labornlory rcplica1ion of aging service envlroment / critically Important mechanism and unique field aspecls of the aging mechanism. to use* harvested materials Degradalion mechanisms that arc harder 10 rcplicalc wilh simulaled MH = C hallenging to re plicate service aging conditions would be ofi,igher priority for harvesting. For envlroment I important to use example, simu\1aneous 1hcrmal and irradiation condi1ions arc diflicult harveste d materials to replicate outs ide of the plant environment. Alternatively, M = Possible with some limitations to lmporlnncc of Hmves1cd accelerated aging may nol be feasible for a mechanism scnsilivc 10 replicate service e nvlroment I Materials over Laboralory Aging dose rate. These two degradation mechanisms may be best moderately important to use harvested evaluated using harves1ed mlilerials. ror unique field aspecls, legacy materials materials (e.g., fabrication methods, composition) thal arc no longer ML= Not challenging to replicate available, but may play an iml)onant role in a polcntial degradation service enviroment / less important to mechanism, would have a higher priority than harvesting materials use harvested materials Ihat can be ob1aincd from 01hcr sources wi1h representative L = Ve ry easy to replicate service properties. enviroment I not important to use harveste d materials H = All plants There is grcnler value in developing knowledge lo address an issue MH = AIIPWRs Applicabili1y 10 US Operating
!hat may be applicable to a larger number of plants compared to one M = All BWRs or most PWRs Fleet Ihat may only affccl a relatively small number of plants. ML = 15 plants L = <5 plants H = No or very limited inspection methods available/ low confidence in AMPs lf ma1urc inspcclion mcthods cxisl and arc easy to apply to monitor MH = Lim ited Inspection methods degradation, harvesting may be less valuable. If inspection methods available/ low-to-moderate confidence Regulatory Considernlions Related do 1101 exist, harvesting may be essenlial 10 ensure confidence in lhe In AMPs to Inspections an.d AM Ps asscssmcnl ofagc-rcla1cd dc:grnda1ion in 1hat panieular M = Some inspection methods available component The less confiden.ce 1ha1 NRC staff has in the / moderate confidence In AMPs effecliveness of 1he relcvanl AMP, the higher priorily for harvesting. ML = Good inspection methods available/ medium-high confide nce In AMPs L = Effective, well-accepted Inspection H = Highly Irradiated (>5 dpa)
Activities with higher costs and complexity are less attractive than MH = Lightly irradiated/ contaminated similar ac1ivilics wi1h lower costs and that arc simpler 10 execute .. M = Minimal contamination or high effort Harvesting cos1 and complexity For example, harvesting unirradiated concrete or eleclrical cables is unirradiated less expensive and less complex lhan harvcsling from the RPY ML = Unirradiated, moderate effort internals or the RPV. expected L = Unirradiated, low effort expected The ability of a potential harvest ing program to provide timely results Timeliness of rcsullS 10 support either a technica l or regula1ory need is impo,1an1. Having high confidence 1ha1 results will be timely increases lhe priority. Availability of materials for The availability of materials to harvest for a particular data need is harvesting clearly csscnlial and increases lhc priorily.
Basic Info Technk:.al Criteria Proiect Soecific Pu,pose I Tasting Regl.btory Conslder,tloni Cost I Complolity . 5 Av11llablflty of Need Oescrfptlon Related to Inspections e,nd Score Avere,ge Basis f<< Technkal Priority " ' : : ~ : : of materlals for Planned AM Ps h.arvestlno RPV S<:o,.. C~nt Score Comment Score Comment Score Commit1u Score COfl'k'l'lent The resuls would be trnely The attenuaoon models iflhey are helve the least amc;IUl1 of deYeloped This WOf1(. has supporting inf0ffll3tion Mateool is imldiated bekwe 2024 Of' been done belore Whie the information Should be compared to othet aspeds The attanuatiOn study it wtueh will al'led al so to QOinc:ide
""'""'od-wt:n. Should klcus There are ncx many stu<ies that wradial& 6 ID 9 genericalty aPQricable, if~ for soma reason.. 11a resutts are re&aledioRPV ambc'itlktm9nl. However.
sightly more irnp()f"wlflt to me. juSt because there are fewer aspectS of specimen with ttie preparatiOn and adcitit;n i~ OCher than Zion oo higer flue ~ inches of steel so, from onty applicable 10 *high ftuence'" 5tudies IO 08te have such studies that have been 1esting Furtler, lnlormatkln ~rial$, rm R PV - tigt, ftuence & high Measure fluenca. to Yfriy that n,,e that standpon. getting materials/locations, th.rs might done. Bang able to confirm lalongspeamens at being collected nalawa.-aof shift wssel with well- tougtv,,ess. & chemistry as Through thickness section i o ate.ruatioo trends specimens from an RPV resul in les.s relevaooe IO lower a>nservativism of existing expected trends at hq,er several through- from industfy oihef RPVs that es1abllshed urwradiated a funcbon of tl'lrough- vatdale fkJence & attenuabon ars Important tor studytng tlU8f'IC8 plants finc1Ud1ng atttenuatlan models used I\Jeocs NMMS would therefore lhlckness locabons surviallance are avalat* for nrrV><>rtie5 thidcne5S Do:sition models M m.ain&ained. MH atten.J.atioo M BWRsl. Ml inrera112tr.v i:u1~ s . M be useful. MH wiU increlitSe cost 1 ..........,81Tl$ h.llve-51:nl. Provides data 5141porting e Y ~ I befieve that The onty real .cfYantage tn We h8Ve 8$ good~ WMe ifs always useful to Material is irradiated The results Olher than Zion Enat:. measurement ol from the uss of oorrelaliwl: (Charpy- enough data has rny rrind for having vessel ccnfid&nce in RPV have more data, especially on whfch will affect al would be tmely materiars. rm bolh the Ch~ transition based) to dired mea surement been devek>ped material for this study is emblittlemeot than wtuaHy RPV material s, I feel that OUI" aspects of specimen if lhey 8re nol awaire ol RPV - Samples from wtualty curve and ma*r curve (fl'aeu-e 1ooghM:ss-based) from both test and that h&re are no queslliOns My ltdonnation deveklped any other degradation that models anaay nave a good prepa,at.aon and daYeloped olher RPVs that I anv vessel tran ~ tem,_..,.hse TO a"""'""--hes M siJVeb)ce t.t... aboul1he MH ~ beaenericail"' ...-...w,.,ble tJIL we study. The cdy"reaJ M - ML lechnic:1111 ha~$. MH lestina. before 2024 Of are avaiable for
Basic Info Technk:.al Criteria Proiect Soecific Pu,pose I Tasting Criticalness of Technical Importance of Harvested Regl.btory Conslder,tloni Cost I Complolity Timeliness of Av11llablflty of N eed Oescrfptlon Technical Knowle4ge Gained AppUcabllity to US Operating Fleet Related to Inspections and Score Average Basis f<< Technkal Priority materlals for Pl anned Gap A ddressvd l/lat&rial s ovvr Laboratory Aging resulb AM Ps h.arvestlno META LS S<o,. CCll'l'\l'Mnt Score Comment Score Comment Score Commtt1t Score Comment EPRI pe,forming R&D on Laboratory repicatkln 'llf!:'Y NOE fo<-swelklg; cifficut to impossible IO MRP-227 uses prwna,rily Signilicance of void swelling at Likety extenl d void swelling in Fillsdatagapfof aclieYe fluences with visual testing, which co!Ad higher ftuences is uncertain, Very Ngh cosl 1of VOid ~ ling, meet\aniea! PWRs during extended opeta11on extended pla,. representative irradlatJOn APl)lcable to high-nuence detect void sweu.ng once and inspectiO(ls may cjetect hl!1"Y"""'- I~ ftuence reclCIQr internals prnnariio,,5, IASCC and impillC:I on aadtina M ..... con<ilioo,; MH components in most PWRs MH fairtv~~nt 3.75 onset cfsiariificenideorad.ltion VH internals TBO Would greatty inaease Moderate cost for Purpose Ol 'NOl1t WOt..6::1 be conlid&ncs in large set of eontamriated. but Frac,,,,-e 1oughness daia in real Validate to p,o,,iide real-world ec:oeterated aging data with not irradiated, Thermally aged ~ t t ! d CASS F raetura toughness and m iet05VUclure concitions to compari!!t IO
~,ed_.......dala ... aoc:eler.illled clata agng H
vaidation Of ac::ot!IGrated 1,,.....,......, in Lab MC.tW. May be possible. but M Most applieabla to PWRs a subset Of H No ISi method avaiabkl to meais1Xe loss of FT testing of urwtaciatsd 4.25 materials M primary stsem cfifficui to reQlica!e long- High cost for Modera:e nvence (1 ~2 dpa) Fracture toughness and Fracture loug'Wle$$ daia near limi1 Confirm reg<N!Ory tenn aging and irradialion Mosi applicable to a subset of No ISi method availat:ite to Wovld increase contidenoe n itradialed CASS m iCl'ostruciure ,enilirinnfurtherevaluation ML OOsio> MH *ff- M PWRs H measure loss of FT 3.5 ;r-..,latory POSition H 1, - n t s Moderate cost for Determine whether sec mitigation Purposed this work is IO contaminated. but Metallic compooents with Metallic compooents with NOE and deslnJdive exalTW\cltion NOE and cJesWCUve methods ace etleclive al preventing sec; elfectiv..,.ss of NOE at detec:b::lc°landsizinQ Determine wheiher fatigue flaws are MH Validate NOE and mitigotion m-e,ffediveness Validate faligue life MH Purpose Of 'NOl1t woi.Ad be to p,u.,idereal-world vaidallon Of lab testinQ Purpose Ol 'NOl1t WOl.*i bi!!t to pn)'o'ide reaJ.wortd H A~ t o i ! l l l i ,lants Ml assess SJspection and mtigationmethod effectiveness Fatigue calcul.atiOns in!Otm sampling W'ISJ;Jections of Im"""' ~ l ) 8 locabons Increase confidence in NOE 3.75 and mmnamn methods Increase cori6dence in fatigue 3.25 ife ca1culabons M not inadiated. prim3fy stsem 1, - n t s ModeratEI 00$1 lor conuminat ed, but notffadiated, primwy stsem li'nitina bt..... ... hfe exanh.bon oresent ,n ......,.. usaoe locahons melhodoloa,es valdabon of lab tesbno H A~ t o a l clants ML M '-nts
Basic Info Technical Crite..ia Pro*ect s - 1fic Purpose / Testing Criticalness. of Technical Importance of Harvested Regulatory Conskferations Cost / Comple:xity nmelines.s. of Avti\.ab ilrty of Need Description Te chnical Knowle dge Gained Materials over Laboratory Applicability to US Operating Fleet Rel ated to Inspections and Score Average Basis for Priority materials for Planned Gap Addressed An... results AMPs harvestina El.£CTRICAL Score Comment Score Comment Score Comment Score Comment Score 1Comment Low and medlum voltage cables Cables ptOlacted With fira reaardant coating 1E MOVs from harsh and mild enwonments t E Air operated valves; 4160 1E breakatS 1E Molded case breakers 480V, 250V DC, 125 VDC. 1E Relays from mid environment GE - HFA. Agasta1 tirniog relays, any from Westinghouse, Potter Brumliekl, Stuther.i Dunn ' d r_ Batteries EJecttical DAn&trabonS Electrical enclosures Distribution: switchgear, MCCs. LCs I Control: Horseshoe. SSCP. AS? etc.
Basic Info Technical Crite..ia Pro*ect s -1fic Purpose / Testing Criticalness. of Technical Importance of Harvested Regulatory Conskferations Cost / Comple:xity nmelines.s. of Avti\.ab ilrty of Need Description Te chnical Knowle dge Gained Materials over Laboratory Applicability to US Operating Fleet Related to Inspections and Score Average Basis for Priority materials for Planned Gap Addressed An... results AMPs harvestina CONCRETE Score Comment Score Comment Score Comment Score Comment Score 1Comment Structixes exposed 10 tjgh radiation Post-tens.oned structures Cocros.ion of reinlorang steel. tendon, liner, embedment ~ t fuel pool and ttanster canal*bonc acid attack on concrete in PWRs Alkali Aggregate Reaction LMge structu,al sacUons for testing
From: Hiser, Matthew Note to requester: Sent: Friday, December 01, 2017 2:51 PM Attachment to this email To: Tregoning, Robert; Audrain, Margaret; Purtscher, Patrick is immediately
Subject:
Data Needs Prioritization Attachments: Harvesting Needs Prioritization 12-1-17.xlsx following . Here's the new version with updated criteria and scoring guidance per our discussion on Monday. Let's try to work the examples with this version before t he next meeting on Wednesday. Thanks! Matt
Criteria Title Description Scoring Guidance H = high risk significance / little to no available data MH = Medium-high risk significance/ limited data available Cri1icalness of Technical Gap l-larves1ing 10 address cri1ical gaps should be prioritized over less M = Moderate risk significance / some Addressed csscnlial technical gaps data available ML = low to moderate risk slgnflcance / H = H igh sufficient data available for regulatory MH = Medium-high decisions M = Medium L = Low risk significance/ large amount ML= Medium-low of data available L = Low Key considerations arc 1hc case of laboralory replication of aging H = Nearly impossible to replicate service envlroment / critically Important mechanism and unique field aspects of the aging mechanism. Degrada1ion mechanisms that are harder to repl icate with simulated to use harvested materials aging conditions would be of higher priority for harvesting. For MH = Challenging to replicate service example, simultaneous thennal and irradiat ion conditions arc diflicult envlroment / Important to use to replicate outside of the pla11t environment. Altematively, harvested materials lmportance ofH.arvesled accelerated ag ing may nol be feasible for a mechanism sensitive to M = Possible with some limitations to Materials over Laboratory Aging dose rate. These two degradation mechanisms may be best replicate service envlroment / moderately important to use harvested evaluated using harvested mate1ials. For unique field aspects, legacy materials (e.g., fabrication methods, composition) that arc no longer materials ML= Not challenging to replicate available, but may play an impo11ant role in a potential degradation mechanism, would have a higher priority than harvesting matc,ials service enviroment / less important to that can be obtained from other sources with representative use harvested materials L = Very easy to replicate service pro1Jcr1ics. onvirnmont / nnt imnnrf!:lnt tn 11c:o H =All plants There is greater value i11 developing knowledge 10 address , 111 issue MH = All PWRs Applicability to US Operating that may be applicable to a larger number of plants compared to one M = All BWRs or most PWRs Fleet that may only affect a relatively small number of plants. ML= 15 plants H = No or very limited Inspection methods available/ low confidence in AMPs If mature inspect ion methods exist and arc easy 10 apply to monitor MH = Limited inspection methods degradation. harvesting may be less valuable. If inspection methods available/ low-to-moderate confidence Regulatory Considerations Related do not exist, harvesting may be essential to ensure confidence in the In AMPs 10 Inspections ai, d AMPs assessment of age-related degradation in that particular M = Some inspection methods available component.The less confidence that NRC staff has in the / moderate confidence in AMPs effectiveness of the rclcvunt AMP. the higher prio,ity for harvesting. ML = Good inspection methods available / medium-high confidence in AMPs L = Effective, well-accepted Inspection H = Highly Irradiated (>5 dpa) Activities with higher costs and complexity are less attractive than MH = Lightly irradiated / contaminated similar uctivities with lower costs and that urc simpler to execute.. M = Minimal contamination or high effort Harvesting cost and complexity For example, harvcs1ing unirradia1cd concrete or electrical cables is unirradiated less expensive and less comp lex than harvesting from the RPV ML= Unlrradlated, moderate effort internals or the RPV. expected L = Unirradiated, low effort expected The ability of a potential harvesting program to provide timely results Timeliness of resultS to support either a technical or regulatory need is important. I laving high confidence that results will be timely increases the ptiotity. Availability of materials for The availability of materials to harvest for a particular data need is harvcstinc clcarlv essential and increases the oriotitv.
Basic Info Technical Criteria Protect s -*tic iffll>O.Unet of Huvu tt d Rt11ulatory Contldt l'IIIOM Cost I Complexity Purpose I Testing Critie~lnu.s of Technic.,I Need Description Technical Knowledge Gained Materials over Laboratory Applicability to US Operating Fleet Related t o I nspections and Score Average Basis fo r Priority Planned Gap Addressed An' - AMP* METALS Score Comment Score Comment Score Comment Score Convnent Score Comment Likely extenl of void swelling WI Vold swellln g. mechanical PWRs during extended operation Hiah ftuenoe reactor internals rvnt-11Ac::, IASCC *nn *-*
- TBD TBO Fracture toughness data in real Thermaty aged UfWT3dlated Fracture too~ ess and concitions to oompaie to CASS microstructure Moderat.efluenoe (1*2dpa) Fracture toughless and Frac:ture toughness data near limit l r-11.ee m i -*- **~*, ,,,. p _ ........- , . - ~ - * ~" '* ..........
Determine whether sec mitigation metl'IOds ate effecti~ at pr'8YeftbnQ Metallic components with known Haws Metallic components with NOE and de$tructlve exal'rinatlon NOE and destructive sec: effectiveness o1 NOE at Determine whether fatigue flaws are Jiimitma f.,.tw., ... life P.XRmim:iticm - - n t in hiah usROe ~..~
Purpose/ Testing Altornalive to Priority / Uni que aspects of ISi Need Description Pl anned Technical Knowledge Gained Benefit I Significance Cost Harvestino? Value Basis for Priority harvested materials availablilitv? METALS RPV - High ftLJeflce & high Measure ftuence, High cost not justified by benefit shift yessel with well* toughness, & chemistry as Through thk:kness sectioo to Increases confidence given surveillance specimens Vintage compositions established unirradiated a function of through* validate fluenoe & atteriuation in e,cisting regulatory and well-estabUshed and irradiation Ol'onArtjej; thir:kne!I...,;; noJi.itinn models approach H;gh No LOW e mrittlemeni trend c.n,relRtinns conditions Provides data supporting evotutlon Enable measurement of from the use of cortelatl ...e (Charpy- High cost not Justified by benefit both the Charpy transition based) to direct measurement lnaeases confidence given surveillance specimens Vintage composltlons RPV
- Samples from virtually curve and master curve (fracture toughness-based) In existing regulatory and well-established and reallstlc irradiation any vessel transition temperature TO approaches approach High No LOW emrittlement trend co,rela tions conditions
Purpose/ Testing Altornalive to Priority / Uni que aspects of ISi Need Description Planned Technical Knowledge Gained Benefit/ Significance Cost Harvestino? Value Basis for Priority harvested materials availablilitv? ELECTRICAL Low and medium vol.age cablee, Medium HIGH Cables pro1eciecl with rue ,etardant coallll!l Medium 1E MOVs rrom harsh and mlld envlronmeflts Medium 1E AA operated vatves; 4160 1E breakers Low 1E Molded case breakers 480V. 250VDC. 125VDC. Low e. 1 Relays from mild environment GE - HFA, Agastat timing relays. any from Westinghouse , Potter Brumfield, Stuthers Dunn
- le Low Batteries Low Eleclrical penetrations Fire research interest E.Jectrical enctosures Distribution: switchgear, MCCs, LCs I Control; Horseshoe . SSCP. ASP. etc .
Purpose/ Testing Altornalive to Priority / Uni que aspects of ISi Need Description Pl anned Technical Knowledge Gained Benefit I Significance Cost Harvestino? Value Basis for Priority harvested materials availablilitv? METALS CONCRETE Fins data gap for Structures exposed to high Change in properties due extended plant radiaoon to irradia6on effects Loss of strength due to irradiation ooerallon High HIGH Post. tensioned structures Medium LOW Corrosion of reinforcing steel, tendon. liner. embedment Medium LOW $pent fuel pool and lransfer canal-boric: ac:id attack Of1 wnc:rele in PWRs Medium LOW Altai! Aggregate Reaction Medium LOW Validate assumpllons large structural sec.tions for Effects of concrete aging of aging effects at testing on structural capacity laroer scales H,gh LOW
Note to requester: Highlighted portions of this email document were in the original document From: Frankl Istvan provided to th e FOIA team. To: Purtscher Patrick Subject : RE: CONTRACTOR INADVERTENTLY RELEASED A DRAFT REPORT TO THE PUBLIC Date: Friday, September 28, 2018 11 :27:03 AM Importance: High Thanks, Pat. I agree w ith Sandra's high lighted statement below. We need t o close the loop with PNNL o n this ASAP. This is very important given the fact that t he released report w as not marked draft and did not have disclai mer. As discussed, I need stat us updat e on th is before noon Monday so I can report on this to DE management at t he DE w eekly meet ing at 1 PM. Steve From: Purtscher, Patrick Sent: Friday, September 28, 2018 8 :55 AM To: Frankl, Istvan <lstvan.Fran kl@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Audrain, Margaret <Ma rgaret.Audra in@nrc.gov>; Hiser, Allen <Allen.H iser@nrc.gov>
Subject:
FW: CONTRACTOR INADVERTENTLY RELEASED A DRAFT REPORT TO THE PUBLIC Lat est st at us. Pat From: Nesmith, Sa nd ra Sent: Thursday, September 27, 2018 5 :3 3 PM To: OPA Resource <OPA.Resource@nrc.gov> Cc: Purtscher, Patrick <Patrick Purtscher@nrc gov>
Subject:
CONTRACTOR INADVERTENTLY RELEASED A DRAFT REPORT TO THE PU BLIC One of our contractors, Pacific Northwest National Laboratory (PNNL), inadvertently released a draft report on their public website that was still incorporating comments from RES and NRR. This report was placed on their public website back in December 2017; however, staff in RES were just made aware of this at a public meeting yesterday. I don't think that the report contained any proprietary information or anything that could potentially be harmful to the NRC, but it did have incomplete information and included many statements about critical gaps in our knowledge related to aging components and structures that could be construed as NRC position. PNNL has taken the report down and is working to find out what happened. However, is there anything more that we should do or ask PNNL to do, such as put out a notice that a draft report was inadvertently released, etc.? I'm not sure of everything that we do when this happens here at NRC. Patrick Purtscher is the COR for this particular contract so I
have also copied him on this email, and I am also including the email exchange below. Any advice you could provide would be greatly appreciated. Thanks Sandra R. Nesmith Operations Branch B Acquisition Management Division Office of Administration Mail Stop: TWFN 7839 U.S. Nuclear Regulatory Commission Washington, DC 20555 (301) 415-6836 Sandra.nesmith@nrc.gov From: Nesmith, Sandra Sent: Thursday, September 27, 2018 2:05 PM To: Purtscher, Patrick <Patrick Purtscher@nrc gov>
Subject:
RE: issue with PNN L NRC-HQ-60-15-T-0023
- Patrick, I will have a short meeting with my boss about this later on this afternoon when she is available; however, I am thinking that PNNL should at least put out some type of notice tha 1 the report wasn't final and was inadvertently released . I have to check to see what w would do it happened here. They should also let us know what steps they will take in the future to ensure this doesn't haimen again.
I will be in touch. Sandy From: Purtscher, Patrick Sent: Thursday, September 27, 2018 1:29 PM To: Nesmit h, Sandra <Sandra .Nesmit h@nrc.gov>
Subject:
RE : issue w ith PN NL NRC-HQ-60-15-T-0023 It will be public once it is completed. The draft was started before GALL-SLR was complete and included many statement about critical gaps in our knowledge related to aging components and structures. The text implies that material harvesting from decommissioned and/or operating plants has to be done before SLR applications can be accepted. Pat From: Nesmith, Sandra
Sent: Thursday, September 27, 2018 1:23 PM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE : issue wit h PNNL NRC-HQ-60-15-T-0023 Patrick I haven't had this happen before so I will have to check with some of the other contracting officers here in AMO. Was there any information that could potentially be harmful to the NRC? Would this report have been released to the public once final? From: Purtscher, Patrick Sent: Thursday, September 27, 2018 1:01 PM To: Nesmit h, Sandra <Sandra Nesmith@nrc gov>
Subject:
issue w ith PNNL NRC-HQ-60-15-T-0023 Hi, You were listed as the contract officer on this task order with PNNL. I took over as COR in May 2016. PNNL is finishing a report to complete phase 1 and PNNL released to the public by accident. I am not sure how we should proceed. Are they any precedents for how to address this? Pat 415-3942 Good evening, From: Pu rt scher, Patrick Sent: Wednesday, September 26, 2018 3:5 1 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Alley, David <David.Alley@nrc.gov>; Ruffin, St eve <Steve.Ruffio@nrc.gov> Cc: Hiser, Allen <Allen Hjser@nrc.gov>; Rud land, David <David Rud land@nrc gov>; Tregoning, Robert <Robert.Tregon ing@nrc.gov>; Hiser, M atthew <Matthew.Hiser@nrc.gov>; Audrain, M arga ret <Margaret.Audra in@nrc.gov>
Subject:
RE: RES Follow-up on Gunter question during t oday 's pu blic meet ing re. PN NL harvest ing report
- All,
Looks like PNNL publications folks have pulled it back from a public listing. PNNL is not sure how it got loose, but apparently somewhere along the way it got listed in the system as un li mited distribution and was posted to OSTI. PNNL is still trying to figure out what went wrong and how it got past the mu ltiple checks they have in p lace to avoid precisely this issue. We shou ld talk more about this tomorrow. Paat From: Frankl, Istvan Sent: Wednesday, September 26, 2018 2:43 PM To: Alley, David <David.Alley@nrc.gov>; Ruffin, Steve <Steve.Ruffio@nrc.gov> Cc: Hiser, Allen <Al!en,Hiser@nrc.gov>; Rud land, David <David,Rud laod@nrc.gov>; Tregoning, Robert <Robert Tregon ing@nrc gov>; Purtscher, Patrick <Patrick Purtscher@nrc gov>; Hiser, M atthew <Matthew Hiser@nrc gov>; Audrai n, Margaret <Margaret Audra in@nrc gov>
Subject:
RES Follow-up on Gunter question during today"s public meeting re. PNNL harvesti ng report Importance: High All : This morning it was brought to my attention that during today"s public meeting Gunter referenced the PNNL report on harvesting. Needless to say that RES staff was quite taken aback by this. As you 're aware, this report is still in draft form and is currently incorporating comments from both RES and NRR. We've gone back and found that, unbeknownst to RES, the report was placed on the PNNL public website back in December 2017. What Gunter has is therefore an early version of the draft report that doesn't include several rounds of NRG comments. However, there is no indication within the report released on the website that the report is still a draft and the inside cover also indicates, correctly, that the work was done under NRG sponsorship. This leaves the impression, as reinforced by Gunter, that the contents of the report could be construed as NRG position. RES is taking the follow immediate action.
- 1. We are working with PNNL to get the report removed from the publ ic website as soon as possible.
- 2. We are trying to determine how this happened and what remediation steps are appropriate for this particular action.
- 3. Based on our findings, we will be recommending procedural changes in how PNNL releases information to the public for NRG-sponsored research.
- Thanks, Steve}}