ML21071A176
| ML21071A176 | |
| Person / Time | |
|---|---|
| Issue date: | 03/04/2021 |
| From: | NRC/OCIO |
| To: | |
| Shared Package | |
| ML21071A165 | List: |
| References | |
| NRC-2018-000831 | |
| Download: ML21071A176 (243) | |
Text
From: Frankl, Istvan Sent: Fri, 24 Feb 2017 19:15:25 +0000 To: Hiser, Matthew
Subject:
RE: Harvesting Announcement Email Thanks, Matt.
Please let me know if you need assistance with assuring NRR participation.
Steve From: Hiser, Matthew Sent: Friday, February 24, 2017 1:22 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting Announcement Email Hi Steve, I don't have final names for DE (Poehler or Cheruvenki) or DLR (Yoo or Hiser) or concrete (Mita's lead). I have talked to the DE and DLR staff and they know they need their management to support their time. I don't know when DE and DLR will decide who their confirmed attendees will be, but I think this email should go out regardless to make the broader staff aware in general.
I'll contact Donna-Marie to see what interaction there should be with OIP.
Thanks!
Matt From: Frankl, Istvan Sent: Friday, February 24, 2017 1:10 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Subject:
RE: Harvesting Announcement Email Importance: High
- Matt, Obviously, NRR staff will need OK from their BCs. Please reach out to the tentative attendees from NRR and confirm their participation and then update the list with the confirmed NRR attendees.
Since regulator(s) from other countries will participate, we may need to notify OIP. Please reach out to Donna-Marie for clarification and assistance.
- Thanks, Steve
From: Hiser, M atthew Sent: Friday, February 24, 2017 12:53 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting Announcement Email Hi Steve, We have talked to Mark Yoo and Allen Hiser in DLR for that slot (one of them) and I spoke with Jeff Poehler about he or Ganesh for the NRR/DE spot (I followed this up with an email with Dave Rud land on cc).
Mita was going to reach out to her counterparts in NRR for the NRR concrete person. I think it would be Angela Buford from DLR most likely...
Thanks!
Matt From: Frankl, Istvan Sent: Friday, February 24, 2017 12:48 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
RE: Harvesting Announcement Email Importance: High Thanks, Matt.
Who are the attendees from NIRR? Do I need recommendations from my counterparts?
Steve From: Hiser, Matthew Sent: Friday, February 24, 2017 12:43 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting Announcement Email Hi Steve, No, I haven't received any more presentation titles since the agenda I sent yesterday, so that is the latest.
I have attached a list of attendees, both external and NRC.
Thanks!
Matt From: Frankl, Istvan Sent: Friday, February 24, 2017 12:30 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Subject:
RE: Harvesting Announcement Email Importance: High
- Matt, I expect questions from my NRR counterparts, so please send me the preliminary list of attendees and their affiliation. If from NRC, please identify the office/division/branch.
I am ready to send the announcement, so if you have more up-to-date draft agenda, please attach it to your response.
- Thanks, Steve From: Frankl, Istvan Sent: Friday, February 24, 2017 9:31 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
RE: Harvesting Announcement Email Thanks, Matt.
lwill .
Steve From: Hiser, Matthew Sent: Friday, February 24, 2017 9:27 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting Announcement Email Hi Steve, Feel free to go ahead and send the email if you like Rob's edits. They're fine with me...
Thanks!
Matt From: Tregoning, Robert Sent: Thursday, February 23, 2017 3:45 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Announcement Email Matt:
See my suggested edits and comments;
Dear RES and NRR BCs:
RES is hosting a workshop on ex-plant materials harvesting at NRC headquarters on March 7-8, 2017. The scope includes afl-Y metallic, electrical, and concrete materials or components that could benefit from harvesting, including metallic, electrica l, and concrete components. I have attached the agenda and workshop introduction slides that cover meeting logistics, motivation, approach, expected outcome, and session expectations.
This workshop includes about two dozen external participants, including representatives from DOE and EPRI as well as international research organizations iR from Japan, Europe, and Canada. Unfortunately, these is limited space available for NRG staff in the room. We have reached out to selected staff in RES and NRR to participate in the room to ensure we can fully support the workshop topics. {I would delete this; why do we need to raise this and provide a negative impression}. A webinar will be available to allow additional NRC staff to observe and participate in the workshop: https://attendee.gotowebinar.com/register/6076202901971284226 .
If you have any questions or need additional information about the workshop, please contact myself or Matt Hiser on my staff.
Sincerely, Steve Frankl Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hiser, M atthew Sent: Thursday, February 23, 2017 2:23 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Pat rick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Announcement Email Updated attachments with slight tweaks per our discussion Steve (added "draft" label to agenda given missing presentation titles, added summary report bullet to expected outcome slide).
Rob and Pat, feel free to wordsmith email below before Steve sends it out tomorrow.
Thanks!
Matt Matthew Hiser
Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 I-415-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Hiser, Matthew Sent: Thursday, February 23, 2017 9:27 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
Harvesting Announcement Email Email to send to following RES and NRR BCs regarding workshop. Please take a look and provide any comments or feedback today if possible, so Steve can send email.
Send to:
RES/DE/CIB - Raj Iyengar RES/DE/ICEEB - Ian Jung RES/DE/SGSEB - Dogan Seber NRR/DLR/RARB - Dennis Morey NRR/DLR/RASB - Brian Wittick NRR/DLR/RSRG - Steve Bloom NRR/DE/EPNB - Dave Alley NRR/DE/EVIB - Dave Rudland NRR/DE/EEEB - Jake Zimmerman
Dear RES and NRR BCs:
RES is hosting a workshop on ex-plant materials harvesting at NRC headquarters on March 7-8, 2017. The scope includes any materials that could benefit from harvesting, including metallic, electrical, and concrete components. I have attached the agenda and workshop introduction slides that cover meeting logistics, motivation, approach, expected outcome, and session expectations.
This workshop includes about two dozen external participants, including representatives from DOE and EPRI as well as international research organizations in Japan, Europe, and Canada.
Unfortunately, these is limited space available for NRC staff in the room. We have reached out to selected staff in RES and NRR to participate in the room to ensure we can fully support the workshop topics. A webinar will be available to allow additional NRC staff to observe and participate: https://attendee .gotowebinar.com/register/6076202901971284226 .
If you have any questions or need additional information about the workshop, please contact myself or Matt Hiser on my staff.
Sincerely, Steve Frankl Matthew Hiser Materials Engineer
US uclear Regulatory Commission I Office of uclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 l-415-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov
Note to requester: The box with the X inside it is the Word attachment, which is immediately following.
From: Hiser, Matthew Se nt: Wed, 18 Oct 2017 20:43:51 +0000 To: Tregoning, Robert;Hull, Amy;Purtscher, Patrick;Ramuhalli, Pradeep Cc: Frankl, lstvan;Audrain, Margaret;Moyer, Carol
Subject:
RE: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Attachme nts: IAEA PLiM Hiser 10-18-2017.docx G
Hi Rob, Amy, Pat, Pradeep, I have adapted our previous poster/ presentation into a paper (attached) on very short notice. The deadline for PLiM papers is technically today, but given the extremely late notice, hopefully they can live with receiving it early next week following staff and management review here.
If you can possibly take a look at this by tomorrow (Thursday) or Friday and provide any feedback, that would be great.
I still need to clean up the references section, so don't mind the very casual state of it now. I'll clean that up tomorrow hopefully ...
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office ofNuclcar Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office.* TWFN 10D62 Matthew.Hiser@nrc.gov From: Hiser, Matthew Sent: Tuesday, October 10, 2017 4:41 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hul l@nrc.gov>; Moyer, Carol <Carol.Moyer @nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Ha rvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants
<< File: NRC PLiM slides on Harvesting.pptx >>
Hi Rob, Amy, Pat, Here's is my adaptation of the poster info (along with some additional insights from the workshop) into slides for PLiM.
Please feel free to comment and edit freely. Ideally, we'd like to have these mostly agreed on at a technical level by COB tomorrow (Wednesday) to be able to discuss with NRR on Thursday and enter into management review and concurrence.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division ofEnginecring I Corrosion and Metallurgy Branch Phone: 301-4 I5-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Tregoning, Robert Sent: Tuesday, October 10, 2017 8:32 AM To: Hiser, Allen <Allen.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol
<Carol.Moyer@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Iyengar, Raj
<Raj.lyengar@nrc.gov>
Cc: Thomas, Brian <Brian.Thomas@nrc.gov>; Wilson, George <George.Wilson@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Allen:
Thanks for the head's up and for offering to make a presentation on this for RES. We're targeting to put together a 20 minute presentation on harvesting that we can discuss with you on Thursday morning. We'll also cover your points 2 and 3 at that time.
- Cheers, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission
Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockvil le, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hiser, Allen Sent: Tuesday, October 10, 2017 7:27 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Iyengar, Raj
<Raj.lyengar@nrc.gov>
Cc: Thomas, Brian <Brian.Thomas@nrc.gov>; Wilson, George <George.Wilson@nrc.gov>
Subject:
FW: Harvest ing of Aged Materials from Operating and Decommissioning Nucl ear Power Plants Importance: High Another twist to the harvesting paper/presentation/poster for the PLiM conference.
I am willing to make a presentation at this "side event" if RES will put together slides - I would shoot for 20 minutes.
A couple of questions on this topic:
- 2. Has a paper been prepared (it appears from below that this is possible for inclusion in the conference proceedings)? If so, can I get a copy of it, or other background information.
- 3. When will the poster be available to be mailed to Lyon? (Can I get a copy of what it will look like?)
I am sure that other questions will arise.
Allen
Original Message-----
From: KANG, Ki-Sig [mailto:K.S.Kang@iaea.org1 Sent: Tuesday, October 10, 2017 7:17 AM To: Hiser, Allen <Allen.Hiser@nrc.gov>
Cc: KHAELSS, Martina <M.Khaelss@iaea.org>; KRIVANEK, Robert
<R.Krivanek@iaea.org>; 4th PliM Conference - Contact Point <4th-PLiM-Conference.Contact-Point@iaea.org>
Subject:
[External_Sender] Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants
Dear Allen ,
Regarding " Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants", now this paper will be presented on poster session in programme.
I think all of participants will be very interesting to this topic. But we have no time slot to present in oral session. Thus I recommend to arrange a side event to introduce this topic from 13:20 -14:00 on 24, Oct (Tuesday) if you want.
We can arrange the meeting room for presentation and discussion. Please think about and let me know.
Ki- Sig KANG Technical Head (PLiM/L TO)
Nuclear Power Engineering Section Division of Nuclear Power International Atomic Energy Agency Tel : +43 1 2600 22796 Fax: +43 1 2600 29598 E-mail : Ki-Sig .KANG@iaea .org This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.
Harvesting of Aged M aterials from Operating and Decommissioning Nuclear Power Plants M. Hisera, P. Purtschera, P. RamuhalJib, A. B. Huna, R. Tregoninga au. S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Division of Engineering Washington, DC hPacific Northwest National Laborato ry Richland, WA, USA Abstrac t. Recent developments, including strong interest in extended plant operation and plans to s hut down a number of nuclear power plants (NPPs), provide opportunities for harvesting components that were aged in representative light water reactor ( LWR) environments. Technica l issues associated with extended plant operation. such as reactor pressure vessel (RPV) embrittlement. irradiation-assisted degradation of reactor internals and primary components, concrete 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 may be the only practical source of representative aged materials in some cases.
Harvesting is expensive and time-consuming, which makes it essential to focus on technica l needs of high importance and seek leveraging and cooperation among multiple organizations whenever possible. NRC is interes ted in engaging with other organizations to prioritize data needs for harvesting, identify areas of common interes t, and develop a database for sources of materials fo r harvesting.
1. Background
Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs). In the U.S., there is strong in terest in extend ing NPP lifespa ns thr oug h subsequent license renewal (SLR) from 60 to 80 years [1]. Extended plant operation and SLR raise a number of technical issues that may require further research to understand aging mechanisms. U.S. utilities and the U.S.
Nuclea r Regulatory Comm ission (NRC) have focused o n the aging of systems, structures, and components and in particular four key SLR issues: reactor pressure vessel (RPY) embrittlement, irradiation-assisted degradation of reactor interna ls and pr imary components, concrete structures and containment degradation, and electrical cable aging [2]. Meanwh ile, in recent years, a number of NPPs, both in the U.S. and internationa lly, have shut down or announced plans to shut down for various reasons, including economic, po litical, and technical challenges.
Unlike in the past when there were very few plants shutting down, these new develop ments provide opportunities for harvesting components that were aged in representative light water reactor (LWR) environments. In a third related development, econo mic challenges and limited budgets have restricted the resources available to support new research, including harvesting programs. Given this constrained budget environment, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future research programs.
- 2. NRC Experience with H arvesting NRC has significant experience with harvesting plant components and performing research on harvested materials to address technical issues. This experience includes a range of components from plants in var ious stages of operation both in the U.S. and internationally.
Some of the harvesting projects that the NRC has participated in include:
- RPV materials from the decommissioned Gundr ernmingen plant in Germany to study fluence rate effects on RPV embrittlement [3],
- Cast austenitic stainless steel (CASS) materials from the decommissioned Shippingport reactor in the U.S. to study CASS thermal embrittlement [4],
- RPV materials from the unfinished or never-operated Shoreham and Midland plants to improve understanding of flaw distributions for RPV embrittlement concerns [5-6],
- RPV head control rod drive mechanism penetrations from the operating North Anna and Davis-Besse plants in the U.S. to study primary water stress corrosion 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 in the U.S. to study PWSCC of nickel alloys [ 11-1 2],
- Reactor internals matetials from the decommissioned Jose Cabrera (known as Zorita) plant in Spain to study high-fluence itTadiation effects on stainless steel alloys [ 13],
- Aluminum-based neutron-absorbi ng materia ls from the decommiss ioned Z ion plant in the U.S. to study degradation in the spent fuel pool env ironment [ 14 ],
- E lectrical cab les from the decommissioned Zion and Crystal R iver plants in the U.S. to investigate cable degradation [ 15],
- Electrical bus ducts from the decommissioned Zion plant in the U.S. to study high-energy arc faults in electr ical enclosures [ 16].
NRC is also aware of other harvesting efforts without NRC participation led by the E lectric Power Research Institute (EPRI), the U.S. Department of Energy (DOE) and other research organizations.
As described above, NRC's experience is that harvesting has contributed s ignificantly to improved understanding of important technical issues for nuclear safety. For RPV mate rials, harvesting has increased knowledge of embrittlement mechanisms and the u nderlying flaw d istri butions in the RPV to allow reductio n in unnecessary conservatism as appropriate. For nickel alloys, harvesting has improved understanding of the PWSCC mechanism, whi le also increasing confidence in the ability of NOE m ethods 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 compo nents containing aluminum [17].
- 3. NRC Perspective and Lessons Learned from Harvesting Experience From NRC's perspective and experience, the primary role of harvesting is to provide confirmation of other research results from simulated aging conditions. In many situations, accelerated aging through higher fl ux test reactor irradiations or elevated temperatures can be used to generate s ignificant data to understand aging effects in a more cost-effective manner.
Limited harvesting efforts of materials from highly representative service environments can help provide data to confi1Tn and increase confidence in the broader database from accelerated aging stud ies.
NRC 's experience with harvestin g has provided a number of technical and logistical lessons learned. Harvesting can provide highly representative aged materials for research and may be the only p ractical source of representative aged materials in some cases. For example, achieving high fluence levels with representative irradiation conditions through other means can be very challenging. It is also essential to gain as much information as possible regarding the materials and environment (temperature, fluence, irradiation conditions, chemistry, humidity, etc.) in advance before committing to a specific harvesting project.
In terms of logistics lessons learned, harvesting is expensive and time-consuming; therefore, focusing on technical needs of high importance is key to ensure good value. Likewise, leveraging and cooperation among multiple organizations helps to mitigate cost challenges. A final log istical lesson has been that it is quite challenging to transpo rt irradiated materials, particularly internationally, so minimizing or avoid such transportation in harvesting programs is highly recommended.
- 4. NRC Activities on Harvesting The primary focus ofNRC's harvesting interests are on the four key issues identified for SLR:
reactor pressure vesse l (RPV) embrittlement, irradiation-assisted degradation o f reactor internals and primary components, concrete structures and containment degradation, and electrical cable aging [2]. As described in Section 2 above, NRC has previously pursued harvesting fo r s imilar materials to address these technical issues. However, increasing operating time with extended plant operation leads to new technical gaps in understanding of material behavior at higher fluences and longer exposures to aging conditions.
NRC has recently undertaken an effort, with the assistance of Pacific Northwest National Laboratory (PNNL), to develop a strategic approach for harvesting aged materials from NPPs.
Due to limited opportunities, past harvesting efforts have been reactive to individual plants shutting down and beginning decommissioning. Given the expected availability of materials fro m numerous plants and antic ipated research needs to better understand agi ng out to 80 years of operation, the NRC is pursuing a more proactive approach to prioritize the data needs best addressed by harvesting and identify the best sources of materials to address high-priority data needs fo r regulatory research.
- 5. Prioritization of Data Needs Best Addressed by Harvesting The fi rst step in this strategic approach is to prioritize data needs fo r harvesting. A data need describes a particular degradatio n scenario (combination of material and environment) and should be defined w ith as much detail as appropriate in terms of the material (alloy, composition, etc.) and environment (temperature, fluence, chemi stry, etc.).
A number of criteria may be considered when prioritizing the data needs for harvesting, including:
- Applicability of harvested ma terial for addressing critical gaps o Harvesting for critical gaps should be prioritized over less essential technical gaps
- Ease of laboratory replication of the degradation scenario o For example, simultaneous thermal and irradiation conditions are difficu lt to replicate or accelerated aging may not be feas ible for a mechanism sensitive to dose rate. Other degradation scenarios may be more easily replicated in simulated aging conditions and of lower priority for harvesting.
- Unique field aspects of degradation o For example, legacy materials (fabrication methods, composition, etc.) that are no longer available, but may play an impo,tant role in a potential degradation scenario, could increase the priority of harvesting.
- Fleet-wide vs. plan t-specific applicability of data o There is greater value in addressing an issue applicable to a larger number of plants compared to one that only supp01is a small number of plants.
- Harvesting cost and complexity o For example, harvesting unirradiated concrete or electrical cables is less expensive and less complex than harvesting from the reactor internals or RPV.
This cost and complexity consideration may increase the priority of lower cost needs and decrease the priority of higher cost needs, such as highly irradiated materials.
- Availability ofreliable inspection methods for the degradation scenario o If mature inspection methods exist and are easy to apply to mo nitor degradation, harvesting may be less valuable. If inspection methods do not exist, harvesting may be essential to ensure confidence that the aging wi ll not challenge a safety functio n for the component.
- Timeliness of the expected research results relative to the objective o The ability ofa potential harvesting program to provide results in time to meet the objective of the work is importa nt. Having high confidence that resu lts will be time ly to address the need increases the prio rity.
- Avai labili ty of materia ls for harvesting The above potential criteria provide a systematic approach to pnon t1ze data needs fo r harvesting. Different organizations may weigh and consider each of these criteria d iffe rently based on their interests and perspectives, but each criteria is like ly relevant to some degree fo r any organization. NRC is interested in engaging with other organizations to prioritize data needs for harvesting and identify areas of conunon interest.
- 6. Database of Sources of Materials for Harvesting Another activity NRC is pursuing is the potential development of a database for sources of materials for harvesting, which could include both previously harvested materials and those available for future harvesting. This database would allow for aligning of high-priority data needs to the available somces of materials. As with the data needs effort, the level of detail for the sources of materials database should be appropriate for the fac tors influencing decision-making. NRC is interested in engaging with other organizations to develop a database for sources of materials for harvesting.
- 7. Conclusions NRC's experience is that harvesting can yield highly representative and valuable data on materials aging, but these efforts may be expensive and challenging. Having a clearly defined objective and early engagement with other stakeholders, including the NPP from which harvesting will take place, are key to success. As specific harvesting o pportunities are identified through this strategic approach, the NRC welcomes oppo1iunities for cooperation and leveraging resources with other interested research organizations.
References l . https://www.nrc.gov/reading-nn/doc-collections/commission/slides/20l 7/20170426/remer-20 170426.pdf
- 2. https://www.me.gov/docs/ML 1405/M Ll 4050A306. pdf
- 3. J.R. Hawthorne and A.L. Hiser, Experimental Assessments ofGundremmingen RPV Archive Material for Fluence Rate Effects Studies, NUREG/CR-5201 (MEA-2286),
U.S. Nuclear Regulatory Commission, October 1988.
- 4. O.K. Chopra, and W.J. Shack, Mechanical Properties of Thermally Aged Cast Stainless Steels from Shippingport Reactor Components, NUREG/CR-6275 (ANL-94/37), U.S. Nuclear Regulatory Conunission, April 1995.
- 5. G. J. Schuster, S. R. Doctor, S.L. Crawford, and A. F. Pardini, Characterization of Flaws in U.S. Reactor Pressure Vessels: Dens ity and Distribution of Flaw Indications in the S horeham Vesse l, NUREG/CR-647 1 Volume 3, U .S. Nuclear Regulatory Commission, November 1999.
- 6. G. J. Schuster, S. R. Doctor, A.F. Pardini, and S.L. Crawford, Characterization of Flaws in U.S. Reactor Pressure Vessels: Validatio n of Flaw Density and Distribution in the Weld Metal of the PVRUF Vessel, NUREG/CR-647 1 Volume 2, U.S. Nuclear Regulatory Conunission, August 2000.
- 7. D.E. McCabe, et al. Evaluation of WF-70 Weld Metal From the Midland Unit 1 Reactor Vessel, NUREG/CR-5736 (ORNL/TM- 13748), U.S. N uclear Regu latory Commissio n, November 2000.
- 8. S.E. Cumblidge, et al. Nondestructive and Destructive Examination Studies on Removed-from-Service Control Rod Dri ve Mechani sm Penetrations, NUREG/CR-6996, U.S. Nuclear Regulatory Commission, July 2009.
- 9. S.E. Cumblidge, et al. Evaluation of U ltrasonic Time-of-F light Diffraction Data fo r Selected Contro l Rod Drive Nozzles from Davis Besse Nuclear Power Plant, PNNL-19362, Pacific Northwest National Laboratory, April 2011.
- 10. S.L. Crawford, et al. Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna U nit 2 Contro l Rod Drive Mechanism Nozzle 63 with Destructive Validation, NUREG/CR-7142 (PNNL-21 547), U.S. Nuclear Regulatory Commissio n, August 2012.
11 . B. Alexandreanu, O.K. C hopra, and W .J. Shack, Crack Growth Rates in a PWR Env ironment of N icke l A lloys from the Davis-Besse and V.C. Summer Power Plants, NUREG/CR-6921 (ANL-05/55), U.S. Nuclear Regulatory Commission, November 2006.
- 12. https://www. nrc.gov/docs/ML08 l 6/ML08 J690334.pdfNUREG/CR-6964
- 13. https://www. nrc. gov/docs/MLl4l 5/ML14153A403.pdf
- 14. https://www. nrc.gov/docs/ML 1501 /MLl 50 l 5A02 l .pdf
- 15. https://lwrs.inl.gov/Materials%20Aging%20and%20Degradation/ Status Report and Research Plan for Cables Harvested from Crystal River Un it 3 N uclear Generati ng Plant.pdf
From: Hiser, Matthew Sent: Tue, 10 Oct 2017 20:40:39 +0000 To: Tregoning, Robert;Hull, Amy;Moyer, Carol;Purtscher, Patrick Cc: Frankl, Istvan
Subject:
RE: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Attachments: NRC PLiM slides on Harvesting.pptx Note to requester: The box with the X inside it is the Power Point attachment, which is immediately following.
G Hi Rob, Amy, Pat, Here's is my adaptation of the poster info (along with some additional insights from the workshop) into slides for PLiM .
Please feel free to comment and edit freely. Ideally, we'd like to have these mostly agreed on at a technical level by COB tomorrow (Wednesday) to be able to discuss with NRR on Thursday and enter into management review and concurrence.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Co1Tosion and Metallurgy Branch Phone: 301-415-24541 Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Tregoning, Robert Sent: Tuesday, October 10, 2017 8:32 AM To: Hiser, Allen <Allen.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol
<Carol.Moyer@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Iyengar, Raj
<Raj. lyengar@nrc.gov>
Cc: Thomas, Brian <Brian.Thomas@nrc.gov>; Wilson, George <George.Wilson@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Allen:
Thanks for the head's up and for offering to make a presentation on this for RES. We're targeting to put together a 20 minute presentation on harvesting that we can discuss with you on Thursday morning. We'll also cover your points 2 and 3 at that time.
- Cheers, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hiser, Allen Sent: Tuesday, October 10, 2017 7:27 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Iyengar, Raj
<Raj.lyengar@nrc.gov>
Cc: Thomas, Brian <Brian.Thomas@nrc.gov>; Wilson, George <George.Wilson@nrc.gov>
Subject:
FW: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Importance: High Another twist to the harvesting paper/presentation/poster for the PliM conference.
I am willing to make a presentation at this "side event" if RES will put together slides - I would shoot for 20 minutes.
A couple of questions on this topic:
- 2. Has a paper been prepared (it appears from below that this is possible for inclusion in the conference proceedings)? If so, can I get a copy of it, or other background information.
- 3. When will the poster be available to be mailed to Lyon? (Can I get a copy of what it will look like?)
I am sure that other questions will arise.
Allen
Original Message-----
From: KANG, Ki-Sig [1]
Sent: Tuesday, October 10, 2017 7:17 AM To: Hiser, Allen <Allen.Hiser@nrc.gov>
Cc: KHAELSS, Martina <M.Khaelss@iaea.org>; KRIVANEK, Robert
<R.Krivanek@iaea.org>; 4th PLiM Conference - Contact Point <4th-PLiM-Conferen ce. Contact-Poi nt@iaea.org>
Subject:
[External_Sender] Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants
Dear Allen,
Regarding " Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants", now this paper will be presented on poster session in programme.
I think all of participants will be very interesting to this topic. But we have no time slot to present in oral session. Thus I recommend to arrange a side event to introduce this topic from 13:20 -14:00 on 24, Oct (Tuesday) if you want.
We can arrange the meeting room for presentation and discussion. Please think about and let me know.
Ki- Sig KANG Technical Head (PLiM/LTO)
Nuclear Power Engineering Section Division of Nuclear Power International Atomic Energy Agency Tel: +43 1 2600 22796 Fax: +43 1 2600 29598 E-mail: Ki-Sig.KANG@iaea.org This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.
~ U.S.NRC United States Nuclear Regulatory Commission Protecting Peop/,e and the Environment Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hisera, P. Purtschera, P. Ramuhallib, A. B. Hulla, R. Tregoninga au.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA bpacific Northwest National Laboratory (PNNL), Richland, WA, USA
Outline
- Background and Motivation
- N RC Harvesting Experience
- Recent N RC Activities
- Criteria for Prioritizing Data Needs
- Database for Sources of Materials
- Path Forward 2 ~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Background and Motivation
- Recent trends in global nuclear industry:
Interest in extending nuclear power plant (NPP) lifespans
- Technical basis for managing aging of systems, structures, and components for longer time Numerous NPPs, both in U.S. and internationally, have announced plans to or already have shut down
- New opportunities for harvesting components that were aged in representative light water reactor (LWR) environments
- Limited budgets have restricted the resources available to support new research, including harvesting programs
- Aligning interests and leveraging with other organizations is important to maximize value
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
NRC Harvesting Experience
- N RC has participated in numerous harvesting programs over the years:
RPV, CROM penetrations, RCS piping, RPV internals, neutron absorbers, and cables From operating and decommissioning plants in U.S. and i nternationa Ily
- Significant value in using harvested components to confirm data from other research programs Harvesting materials from highly representative long-term aging environments increases confidence in safety margins
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for research May be only practical source of representative aged materials, particularly if irradiation and temperature are important factors
- Achieving high fluence levels with representative irradiation conditions through other means is very challenging May be able to use limited harvested materials to validate larger accelerated aging data set
- Important to gain as much information as possible in advance before committing to specific harvesting project Ideally a bounding, yet realistic, material/environment Understand material information (CMTRs if available) and plant operating conditions 3 ~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effort
- Must balance cost with potential benefits carefully
- High technical relevance of materials is needed to ensure value
- Leveraging resources with other research organizations helps mitigate cost cha I lenges Can introduce challenges for testing when aligning research priorities and interests of multiple organizations May be needed, particularly for expensive testing of irradiated materials
- Transporting irradiated materials, particularly internationally, is cumbersome and time-consuming Avoiding extra transport, especially between countries, is highly recommended
~ U.S.NRC 5 Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Recent N RC Activities
- Strategic approach to materials harvesting
- Due to limited opportunities, past harvesting efforts have generally been reactive to individual plants shutting down
- Prioritize the data needs best addressed by harvesting
- Criteria for harvesting prioritization developed by PN NL
- Workshop held in March 2017 at NRC HQ to discuss all aspects of harvesting with other interested stakeholders
- Good discussion of experience, including challenges and pitfalls, from those with firsthand knowledge
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Potential Criteria for Harvesting Prioritization
- Applicability of harvested material for addressing critical gaps
- Harvesting for critical gaps prioritized over less essential technical gaps
- Ease of laboratory replication of the degradation scenario
- For example, simultaneous thermal and irradiation conditions are difficult to replicate
- Unique field aspects of degradation
- For example, unusual operating experience or legacy materials (fabrication methods, etc.) no longer available
- Fleet-wide vs. plant-specific applicability of data
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Potential Criteria for Harvesting Prioritization
- Harvesting cost and complexity
- For example, harvesting unirradiated concrete or electrical cables less expensive and less complex than harvesting from the reactor internals
- Availability of reliable in-service inspection (ISi) techniques for the material/ component
- If mature inspection methods exist and are easy to apply, harvesting may be less valuable
- Availability of materials for harvesting
- Timeliness of the expected research results relative to the objective
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Database for Sources of Materials
- NRC is pursuing the development of a database for sources of materials for harvesting
- Includes both previously harvested materials and those available for future harvesting
- Allow for aligning of high-priority data needs to the available sources of materials
- The level of detail should be appropriate for the factors influencing decision-making
- NRC is interested in engaging with other organizations in developing the database
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Conclusion and Path Forward
- Harvesting can yield highly representative and valuable data on materials aging
- Having a clearly defined objective and early engagement with other stakeholders are keys to success
- Data Needs Prioritization and Sources of Materials Database
- N RC is interested in working with other organ izations to identify high-priority data needs of common interest
- As specific harvesting opportunities are identified, NRC welcomes opportunities for cooperation and leveraging with other interested research organizations
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission Prot<<:ting Pnlpk and tlw £nuiro111M11-t
From: Frankl, Istvan Sent: Fri, 29 Jan 2016 11:00:21 -0600 To: Hiser, Matthew Cc: Hull, Amy
Subject:
RE: Harvesting One Pager Note to requester: Attachment is Attachments: Harvesting One Pager (IF) .docx immediately following.
Thanks , Matt.
Nice one-pager.
I have a few comments and revisions. Please see the attachment for details.
Thanks ,
Steve From: Hiser, Matthew Sent: Friday, January 29, 2016 10:05 AM To: Frankl, Istvan; Hull, Amy
Subject:
Harvesting One Pager Hi Steve and Amy, Please find attached the one-pager on the harvesting project to help facilitate transition with Aloysius.
Thanks!
Matt
Strategic Approach to Ex-Plant Harvesting (1/29/2016)
Background
- Understanding the causes and control of degradation mechanisms forms the basis for developing aging management programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSC). The resolution to these issues should provide reasonable assurance of safe operation of the components in the scope of license renewal during the subsequent period of extended operation.
- In many cases, the scientific basis for understanding and predicting long-term environmental degradation behavior of materials in NPPs is incomplete. A strategic approach to the harvesting, examination and testing of materials and components from decommissioned reactors can dramatically increase our knowledge-acquisition rate in this very important area.
- This project i§_to develop a strategic approach to ex-plant harvesting and was originally conceived and initiated through the NRC's Long-Term Research Program (LTRP).
Facts
- A new task order (-NRG-H~0o.'1- Tosk-Gr-Elef-N1;1mbeF-fNRC-HQ 15-T-0023) was placed with the Pacific Northwest National Lab (PNNL) Enterprise W ide Agreement (NRC-HQ-25-14-D-0001) in September 2015 to support NRC in developing a strategic approach to ex-plant harvesting. Task 1 focuses on a scoping study to pull in information from other sources (EMDA, GALL. ASME code, etc.) to populate an information tool that will allow the prioritization of harvesting opportunities.
- An internal NRC working group consisting of staff from RES and NRR was formed to advise the strategic harvesting effort.
- NRR/DLR staff and management have expressed strong support and int-erest in this project and intend to develop a user need reques~(UNR) to support this -effort in the ( Commented [IFl]: Whal Is the status of this?
context of Subsequent License Renewal {SLR}.
Status
- Under Task 1 of the task order, PNNL is currently working on developing examples for dissimilar metal welds and cables of what type of information will be captured and how ii will be presented.
- The working group has met once in December and has another meeting scheduled for February to review some information put together by PNNL.
Next Steps
- By mid-February, PNNL should provide examples for dissimilar metal welds and cables in the information tool. This will allow NRC (likely through the working group) to review what type of information will be captured and how it will be presented.
- NRC staff should work with PNNL to organize a public workshop to discuss the topic of.
ex-plant harvesting and engage relevant stakeholders, particularly EPRI, industry, and DOE that can help provide information and cooperation in these efforts.
- RES staff should work with NRR st aff to ~evelop an updated UNR ,incorporating this (commented [IF2]: Is this a different UNR, or the new~
strategic harvesting effort.
Note to requester: Attachment is immediately following.
From: Frankl, Istvan Se nt: Fri, 29 Jan 201617:53:14 +0000 To: Hiser, Matthew Cc: Hull, Amy
Subject:
RE: Harvesting One Pager Attachments: Harvesting One Pager (IF).docx Thanks, Matt.
I implemented your clarifications in the attachment.
I will schedule meeting with Aloysius and you for early next week to discuss this assignment.
am also thinking about reassigning the GSl-191 effort to him. Any thoughts on this?
Steve From: Hiser, Matthew Se nt: Friday, January 29, 2016 12:16 PM To: Frankl, Istvan Cc: Hull, Amy
Subject:
RE: Harvesting One Pager Hi Steve, OK, I accepted your revisions (attached). To answer your questions:
- 1. What is the status of UNR?
- a. As far as I know, Amy has had some limited discussion with DLR staff and management and they support this effort and would like to put in UNR. I don't think there has been much more progress made on that front, which is something that Aloysius could hopefully lead.
2 . Is this a different UNR, or the new one?
- a. I was referring to the same one as above. There are already UNRs for RES support for SLR, so whether it is "updating" those old ones or creating a "new" UNR from scratch is not much different in my mind.
Thanks!
Matt From: Frankl, Istvan Sent: Friday, January 29, 2016 12:00 PM To: Hiser, Matthew Cc: Hull, Amy
Subject:
RE: Harvesting One Pager Thanks, Matt.
Nice one-pager.
I have a few comments and revisions . Please see the attachment for details.
Thanks ,
Steve From: Hiser, Matthew Sent: Friday, January 29, 2016 10:05 AM To: Frankl, Istvan; Hull, Amy
Subject:
Harvesting One Pager Hi Steve and Amy, Please find attached the one-pager on the harvesting project to help facilitate transition with Aloysius.
Thanks!
Matt
Strategic Approach to Ex-Plant Harvesting (1/29/2016)
Background
- Understanding the causes and control of degradation mechanisms forms the basis for developing aging management programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSC). The resolution to these issues should provide reasonable assurance of safe operation of the components in the scope of license renewal during the subsequent period of extended operation.
- In many cases, the scientific basis for understanding and predicting long-term environmental degradation behavior of materials in NPPs is incomplete. A strategic approach to the harvesting, examination and testing of materials and components from decommissioned reactors can dramatically increase our knowledge-acquisition rate in this very important area.
- This project is to develop a strategic approach to ex-plant harvesting and was originally conceived and initiated through the NRC's Long-Term Research Program (LTRP).
Facts
- A new task order (NRC-HQ-60-15-T-0023) was placed with the Pacific Northwest National Lab (PNNL) Enterprise Wide Agreement (NRC-HQ-25-14-D-0001) in September 2015 to support NRC in developing a strategic approach to ex-plant harvesting. Task 1 focuses on a scoping study to pull in information from other sources (EMDA, GALL, ASME code, etc.) to populate an information tool that will allow the prioritization of harvesting opportunities.
- An internal NRC working group consisting of staff from RES and NRR was formed to advise the strategic harvesting effort.
- NRR/DLR staff and management have expressed strong support and interest in this project and intend to develop a user need request (UNR) to support this effort in the context of Subsequent License Renewal (SLR).
Status
- Under Task 1 of the task order, PNNL is currently working on developing examples for dissimilar metal welds and cables of what type of information will be captured and how it will be presented.
- The working group has met once in December and has another meeting scheduled for February to review some information put together by PNNL.
Next Steps
- By mid-February, PN NL should provide examples for dissimilar metal welds and cables in the information tool. This will allow NRC (likely through the working group) to review what type of information will be captured and how it will be presented.
- NRC staff should work with PNNL to organize a public workshop to discuss the topic of ex-plant harvesting and engage relevant stakeholders, particularly EPRI, industry, and DOE that can help provide information and cooperation in these efforts.
- RES staff should work with NRR staff to develop a new UNR or update the existing UNR for SLR to an updated UNR incorporat~~ this strategic harvesting effort.
Note to requester: The attachments are both immediately following.
From: Hiser, Matthew Sent: Mon, 23 Oct 2017 12:45:05 +0000 To: Tregoning, Robert;Hiser, Allen
Subject:
RE: Harvesting Poster Attachments: IAEA PLiM Hiser 10-23-2017.docx, NRC PLiM slides on Harvesting final.pptx Here's the latest version of the paper (at division level management for approval).
I also attached the slides, which I had sent a couple weeks back.
Did the poster make it to the hotel?
Thanks for presenting and good luck!
Matt From: Tregoning, Robert Sent: Monday, October 23, 2017 8:41 AM To: Hiser, Allen <Allen.Hiser@111rc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
RE: Harvesting Poster Allen:
Do you have the final presentation and latest version of the paper? I'll ask Matt to send you the latest version just in case. Then you can peruse the paper for some additional information.
Thanks again for covering ......
RT Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hiser, Allen Sent: Monday, October 23, 2017 8:38 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, Matt hew <Matthew.Hiser@nrc.gov>
Subject:
Harvesting Poster Importance: High FYI - The poster presentation has gone from lunchtime to in-session in 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to a cancellation.
Any last minute thoughts to convey?
HARVESTING OF AGED MATERIALS FROM OPERATING AND DECOMMISSIONING UCLEAR POWER PLANTS M. Hiser, P. Purtscher, A. B. Hull, R. Tregoning U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research Washington, DC Email: matthew.hiser@nrc.gov P. Ramuhalli Pacific Northwest National Laboratory Richland, WA, USA Abstract Recent plans to shut down a number of nuclear power plants (NPPs) provide opportunities for harvesting components that were exposed 10 actual light water reactor (LWR) environments. Technical iss ues associated with extended plant operation, such as reactor pressure vessel (RPV) embrittlement, irradiation-assisted degradation of reactor internals and primary components, concrete structures and containment degradation, and eleci-rical cable aging, may be used to focus harvesting efforts on high-priority issues. Harvesting can provide highly representative aged materials for research a nd, 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, whic h makes it essential to focus on those technical needs with the highest importance and cooperate with multiple organizations whenever possible to optimally leverage resources. NRC is interested in engaging with other organizations 10 prioritize data needs for harvesting, identify areas of common interest, and develop a database for sources of materials for harvesting.
I . BACKGROUND Recent developments in the nuclear industry include stronger interest in extended plant operation and plans to shut down a number of nuclear power plants (NPPs). In the U.S., there is strong interest in extending NPP li fespans 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) embrinlement, irradiation-assisted degradation (!AD ) of RPV internals and primary components, concrete structures and containment degradation, and electrical cable aging [2]. In recent years, a number of NPPs, both in the U.S. and internationally, have shut 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 (LWR) 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 EXPERI ENCE WITH HARVESTING N RC has significant experience with harvesting plant components and performing 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 Gundrernmingen plant to study fluence rate effects on RPV embrittlement [3],
- Cast austenitic stainless steel (CASS) materials from the decommissioned Shippingport reactor. to study CASS thermal embrittlement [4],
- RPV materials from the unfinished or never-operated Shoreham and Midland plants to improve understanding of flaw distributions for RPV embrittlement concerns [5-6],
- RPV head control rod drive mechanism penetrations from the operating North Anna and Davis-Besse plants to study primary water s tress corrosion cracking (PWSCC) of nickel alloys and the effectiveness ofnon-destructive evaluation (NDE) methods (8-12],
- Reactor coolant system (RCS) piping nozzle weld materials from the operating V.C. Summer plant to study PWSCC of nickel alloys [11 -12],
- Reactor internals materials from the decommissioned Jose Cabrera (known as Zorita) plant to study bigb-fluence irradiation effects on stainless steel reactor internals materials [13],
- Aluminum-based neutron-absorbing materials from the decommissioned Zion plant to study degradation in the spent fuel pool environment [ 14] ,
- E lectrical cables from the decommissioned Zion and Crystal River plants to investigate cable degradation [ 15],
- Electrical bus ducts from the decommissioned Zion plant to study high-e nergy arc fau lts in electrical enclosures [ 16].
As illustrated by these programs, NRC's experience is that harvest.ing has contributed s ignificantly to improved understanding of important technical issues for nuclear safety. For RPV materials, harvesting has increased knowledge of embrittlement mec hanisms and the underly ing flaw distributions in the RPV to a llow 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 of NOE methods to detect and c haracterize flaws. Finally, recent work on e lectrical enclosures has he lped to identify a potential new safety issue associated with high-energy arc fau lts in electrical components containing aluminum
[ 16].
- 3. NRC PERSPECTIVE AND LESSONS LEARNED FROM HARVESTING ACTIVITIES From NRC's perspective, a principal role of ha rvesting is to confitm other research results from s imulated aging conditions. In many situations, accelerated aging through higher nux test reactor irradiations or e levated temperatures can be used to generate significant data to understand aging effects in a more cost-effective manne r.
Limited harvesting e fforts of materials from actual service environments can help confirm the adequacy of the knowledge gained from accelerated aging studies, and thus increase the confidence in the broader knowledge base.
However, in certain s ituations, 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 challe nging. Additionally, it is essential to gain as muc h information as possible regarding the materials and environment (tempe rature, tlue nce, irradiation conditions, chemistry, humidity, etc.) in advance before committing to a specific harvesting project s o that the implications of the results from evaluating the materials can be properly understood.
Pragmatically, harvesting can be expens ive, complex, and time-consuming; therefore, focus ing on technical needs of high importance will he lp ensure good value. Likewise, leveraging a nd cooperation among multiple organizations helps to mitigate cost c hallenges. It is also quite c halleng ing to transport irradiated materials, particularly inte rnationa lly, so minimizing or avoiding transportation of irradiated mate rials is highly recommended.
- 4. N RC ACTIVITIES ON HARVESTING NRC is potentially inte rested in harvesting materials to assess age-related degradation in the four technical areas identified previo us ly: RPV embrittleme nt, IAD of RPV inte rnals a nd primary compone nts, concre te structures and containment degradation, and electrical cable aging [2]. The focus is to unde rsta nd the impact of extended plant operation on materia l behavior, including the effects of higher fluences and longer exposures to aging conditions.
NR C has recently undertaken an effort, with the assistance of Pacific Northwest National Laboratory (PNNL), to develop a strategic a pproach for harvesting aged materials from NPPs. Past harvesting activities have been narrowly focused on the relatively few opportunities to get materials from decommissioning plants. Given the expected availability of materials from numerous plants and ide ntified research needs to better understand aging out to 80 years of operation, the NRC 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. PRIORITlZATION 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 env ironment) and should be defined w ith as much detail as appropriate in terms of the material (e.g., alloy, composition) and environment (e.g., tempe rature, fluence, chemistry).
A number of criteria are being cons idered for prioritizing the harvesting da ta needs, including:
Applicability of harvested material for addressing critical gaps
- Harvesting to address critical gaps should 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 feasible 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 arc no longer available, but may play an important role in a potential degradation mechanism, 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 witJ1 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 RPV internals or the llPV.
Availability of reliable inspection methods for the degradation scenario
- If mature inspection methods exist and arc easy to apply to monitor degradation, harvesting may be less valuable. If ins pection methods do not exist, harvesting may be essential to ensure confidence in the assessment of age-related degradation in that particular component.
T imeliness o f the expected research results
- The ability of a potential harvesting program to provide timely 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 harvesting
- The availabi lity 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 furth er 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 HARVESTING The NRC is also developing a database that identities sources of materials for harvesting. T his database will include both previously harvested materials and those which may be available for future harvesting. This database will 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. NRC is interested in engaging with other organizations to develop a database that identifies sources o f materials for harvesting.
- 7. CONCLUSIONS NRC's experience is that harvesting can yield 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, are necessary to ensure project success. As specific harvesting opportunities 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 17/20 170426/ remer-20170426.pdf.
[2] U.S. NUCLEAR REGULATORY COMMISSION, "Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal," SECY 0016, 2014, https://www.nrc.gov/docs/ML 1405/ML I 4050A306.pdf.
[3] HAWTHORNE, J.R., HISER, A.L., "Experimental Assessments ofGundrernmingen RPV Archive Material for Fluence Rate Effects Studies," NUREG/CR-5201 (MEA-2286), U.S. Nuclear Regulatory Commission, October 1988.
[4] CHOPRA, O.K., SHACK, W.J., "Mechanical Properties ofThermally Aged Cast Stainless Steels from Shippingport Reactor Components," NUREG/CR-6275 (ANL-94/37), U.S. Nuclear Regulatory Commission, April 1995.
[5] SCHUSTER, G. J., DOCTOR, S. R., CRAWFORD, S.L., PARDINI, A. F., "Characterization of Flaws in U.S. Reactor Pressure Vessels: Density and Distribution of Flaw l'ndications in the Shoreham Vessel," NUREG/CR-6471 Volume 3, U.S. Nuclear Regulatory Commission, November 1999.
[6] SCHUSTER, G. J., DOCTOR, S. R., PARDTNT, A.F., CRAWFORD, S.L., "Characterization of Flaws in U.S. Reactor Pressure Vessels: Validation of Flaw Density and Distribution in the Weld Metal of the PVRUF Vessel," NUREG/CR-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/CR-5736 (ORNL/TM-13748), U.S. Nuclear Regulatory Commission, November 2000.
[8] CUMBLIDGE, S.E., ET AL., "Nondestructive and Destructive Examination Studies on Rcmoved-from-Scrvice Control Rod Drive Mechanism Penetrations," NUREG/CR-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 2011.
[JO] CRAWFORD, S.L., ET AL., "Ultrasonic Phased Array Assessment of the Interference Fit and Leak Path of the North Anna Unit 2 Control Rod Drive Mechanism Nozzle 63 with Destructive Val idation," N UREG/CR-7 142 (PNN L-2 1547), U.S. Nuclear Regulatory Commission, August 2012.
[1 1] ALEXANDREANU, B., CHOPRA, O.K., SHACK, W.J., "Crack Growth Rates in a PWR Environment of Nickel Alloys from the Davis-Besse and V.C. Summer Power Plants," NUREG/CR-692 1 (AN L-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 1415/ML14153A403.pdf.
[14] U.S. NUCLEAR REGULATORY COMMISSION, "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/MLl50 I/ MLI 50 15A02 I .pdf.
[I 5] FIFIELD, L.S., "Status Report and Research Plan for Cables Harvested from Crystal River Unit 3 Nuclear Generating Plant," PNNL-25833, September 201 6.
[16] GUTTER, J. G., " Path Forward for Regulatory Treatment of High-Energy Arcing Fault Tests Results that Involve A luminum," internal NRC memo, March 20 16, https://www.nrc.gov/docs/ML 1606/ML I 6064A250.pdf.
~ U.S.NRC United States Nuclear Regulatory Commissio n Protecting Peop/,e and the Environment Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hisera, P. Purtschera, P. Ramuhallib, A. B. Hulla, R. Tregoninga au.s. Nuclear Regulatory Commission {NRC), Washington, D.C., USA bpacific Northwest National Laboratory (PNNL), Richland, WA, USA This presentation was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product, or process disclosed in this presentation [report], or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the U.S. Nuclear Regulatory Commission.
Outline
- Background and Motivation
- N RC Harvesting Experience
- Recent N RC Activities
- Criteria for Prioritizing Data Needs
- Database for Sources of Materials
- Path Forward
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 2 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Background and Motivation
- Recent trends in global nuclear industry:
- Interest in extending nuclear power plant (NPP) lifespans
- Numerous NPPs, both in U.S. and internationally, have announced plans to or already have shut down
- Limited budgets have restricted the resources available to support new research, including harvesting programs
- Aligning interests and leveraging with other organizations is important to maximize value
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 3 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
NRC Harvesting Experience
- N RC has participated in numerous harvesting programs over the years:
- RPV, CROM penetrations, RCS piping, RPV internals, neutron absorbers, and cables
- From unfinished, operating ,and decommissioning plants in U.S. and internationally
- Significant value in using harvested components to confirm data from other research programs
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 4 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for research
- May be only practical source of representative aged materials
- May be able to use limited harvested materials to validate larger accelerated aging data set
- Important to gain as much information as possible in advance before committing to specific harvesting project
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 5 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effort
- Leveraging resources with other research organizations helps mitigate cost challenges
- Transporting irradiated materials, particularly internationally, is cumbersome Lifting operation for and time-consuming irradiated materials transport cask
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 6 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Recent N RC Activities
- Strategic approach to materials harvesting
- Due to limited opportunities, past harvesting efforts have generally been reactive to individual plants shutting down
- Prioritize the data needs best addressed by harvesting
- Workshop held in March 2017 at NRC HQ to discuss all aspects of harvesting with other interested stakeholders
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 7 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Potential Criteria for Harvesting Prioritization
- Applicability of harvested material for addressing critical gaps
- Ease of laboratory replication of the degradation scenario
- Unique field aspects of degradation
- Fleet-wide vs. plant-specific applicability of data
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 8 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Potential Criteria for Harvesting Prioritization
- Harvesting cost and complexity
- Availability of reliable in-service inspection (ISi) techniques for the material/ component
- Availability of materials for harvesting
- Timeliness of the expected research results relative to the objective
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 9 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Database for Sources of Materials
- NRC is pursuing the development of a database for sources of materials for harvesting
- Allow for aligning of high-priority data needs to the available sources of materials Example of reactor
- N RC is interested in engaging with internals harvesting plan other organizations in developing the database
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 10 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Conclusion and Path Forward
- Harvesting can yield highly representative and valuable data on materials aging
- Data Needs Prioritization and Sources of Materials Database
- As specific harvesting opportunities are identified, NRC welcomes opportunities for cooperation and leveraging with other interested research organizations
~ U.S.NRC Unimi Sta[t.J S11dC'ar R.t-gula,ory Commission 11 Prot<<:ting Pnlpk and tlw £nuiro111M11-t
Note to requester: The boxes with the X inside them are the two Word attachments, and the one Power Point attachment, which are immediately following .
From: Hiser, Matthew Sent: Mon, 30 Jan 2017 14:39:47 +0000 To: Purtscher, Patrick
Subject:
RE: Harvesting Workshop Attachments: Workshop Planning 1-30-17.docx, GoToMeeting.docx, Harvesting Workshop intro slides 1-23-17.pptx Will do Pat - here are the documents we'll be speakiing to.
Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-4 15-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Purtscher, Patrick Sent: Monday, January 30, 2017 8:57 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
RE: Harvesting Workshop (b )(6)
You can call me at ._l_ _ _ _..,! 10 AM .
Origi na I Appointment-----
From: Hiser, Matthew Sent: Wednesday, January 25, 2017 9:12 AM To: Hiser, Matthew; Tregoning, Robert; Purtscher, Patrick
Subject:
Harvesting Workshop When: Monday, January 30, 2017 10:00 AM-11:00 AM (UTC-05:00) Eastern Time (US &
Canada).
Where: HQ-TWFN-10A73-8p Discuss latest status of workshop planning.
Workshop Contacts Name Organization Email Contact Through Taku Ara i CRIEPI arait@crieQi.denken.or.jQ Rob Sadao Higuchi CRIEPI higuchi@crieQi.denken.or.jQ Rachid Chaouadi SCK-CEN rachid.chaouadi@sckcen.be Rob Kazunobu Sa kamoto JNRA kazunobu sakamoto@nsr.go.jQ Rob JAEA Gerry van Noordennen Energy Solut ions gQvannoordennen@energysolutions.com Mat t Bill Zipp Dominion william.f.ziQQ@dom.com Matt Sherry Bernhoft EPRI sbernhoft@eQri.com Robin Dyle EPRI rdyle@eQri.com Jean Smith EPRI jmsmith@eQri.com Al Ahluwalia EPRI kahluwal@eQri.com Tom Rosseel DOE rosseeltm@orn I.gov Rich Reister DOE Richard. Reister@n uclea r.energy.gov Keith Leonard DOE leonardk@ornl.gov Mikhail A. Sokolov DOE sokolovm@ornl.gov Leo Fyfeld DOE/PN NL Pat Pu rtscher NRC Patrick. Purtscher@nre.gov Rob Tregoning NRC Robert.Tregoning@nrc.gov Matt Hiser NRC Matthew.Hiser@nrc.gov Anders Jenssen Studsvik anders.jenssen@studsvik.se Matt/Jean Da niel Tello CNSC daniel.tello@canada.ca Matt CNL AECL Heather Malikowski PWROG Heather. Ma Ii kowski@exeloncorQ.com Matt Jim Molkenthin PWROG molkenjQ@westinghouse.com Matt Regis Nhili M AI regis.nhili@edf.fr Rob Uwe Jendrich GRS Uwe.Jendrich@grs.de Rob Pradeep Ramuhalli PNNL PradeeQ.Ramuhalli@Qnnl.gov Session NRC Lead DOE Lead EPRI Lead 1 Rob Tregoning Rich Reister Sherry Bernhoft/Robin Dyle 2 Pat Purtscher Keith Leon ard Sherry Bernhoft/Robin Dyle 3 Matt Hiser Tom Rosseel Sherry Bernhoft/Robin Dyle 4 Matt Hiser Tom Rosseel Sherry Bernhoft/Robin Dyle 5 Rob Tregoning Rich Reister Sherry Bernhoft/Robin Dyle NRC Presentations Session Topic Speaker 1 Why our organizat ion is int erested in harvesting Tregoning 2 Overview of dat a needs be.st addressed by harvesting Pradeep / PN NL Available materials from decommissioning plants and Hiser 3
past harvest ing programs Perspective on Harvesting Lessons Learned / Prior TBD 4
Experience Technical information needled for informed harvesting Pradeep / PNNL 5
decisions 5 Perspective on future harvesting planning Tregoning
Session Topic Organization Speaker Status EPRI DOE Rich Reister Why our organization is interested in harvesting NRC Robert Tregoning 1
MAI Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged PANEL DISCUSSION Overview of data needs best addressed by harvesting PNNL (for NRC) Pradeep Ramuhalli EPRI 2 DOE Keith Leonard Perspective on detailed data needs from harvesting SCK-CEN Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged Available materials from decommissioning plants and past NRC Matt Hiser harvesting programs Available materials from operating reactors and past harvesting EPRI programs PWROG Emails exchanged Available materials at DOE labs from past harvesting programs DOE Tom Rosseel 3
Upcoming decommissioning sites Energy Solutions Gerry van Noordennen Confirmed MAI Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged Internat ional sources of materials CNSC Confirmed - speaker TBD Korea EPRI/ Ahluwalia EPRI Perspective on Harvesting Lessons Learned/ Prior Experience DOE Tom Rosseel NRC 4 Decommissioning process and harvesting: schedule, site-specific, Energy Solutions Gerry van Noordennen Confirmed timing for different components Utility-Owner perspective on harvesting and decommissioning Dominion Bill Zipp Confirmed International decommissioning and harvesting experience Germany? Emails exchanged Technical information needed for informed harvesting decisions PNNL (for NRC} Pradeep Ramuhalli EPRI DOE Rich Reister Perspective on future harvesting planning NRC Robert Tregoning 5
MAI Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged PANEL DISCUSSION Discussion of Next Steps / Actions
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Ex-Plant Materials Harvesting Workshop March 7-8, 2017 USNRC HQ Rockville, MD, USA
Motivation
- With plants shutting down both in the U.S. and internationally, there are increasing opportunities to harvest components from decommissioning plants
- Past harvesting efforts generally more reactive and ad hoc as opportunities arose, rather than proactively planned
- Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions
- Reduces the uncertainty associated with the applicability of the aging conditions
- Insights from research on harvested materials can address technical data needs identified for extended plant operation
- Lessons learned from past harvesting programs can help improve future harvesting efforts Challenges encountered in previous programs can be shared and mitigated or avoided in future programs
Approach
- Domestic and international researchers, industry, regulators, and decommissioning companies' discuss benefits and challenges with ex-plant harvesting
- Encourage sharing of lessons learned as well as areas of common interest for potential new research programs
- Workshop consists of topical sessions with short presentations and significant time for open discussion
- Goal is to maximize engagement among all meeting participants, rather than presenter/audience mentality
- Scope includes any materials aging issue that could benefit from harvesting: metals, cables, and concrete
Expected Outcome
- Participants are better informed and aware of the benefits and challenges associated with ex-plant harvesting
- Discussions help identify areas of common interest for harvesting to address technical data needs
- Presentations and discussions provide the starting point for a "database" of harvested materials and future harvesting opportunities
- Contacts are made among research organizations to allow for further discussion of specific harvesting projects
Session Expectations
- Session 1 Motivation for Harvesting Perspective from panel participants on their organizations' interest in and motivation for harvesting Brief (5-10 minute) presentation from each panel member followed by open and panel discussion
- Session 2 Technical Data Needs for Harvesting
- Presenters share high-priority data needs that are best addressed by harvesting from their organization's perspective
- Where does harvesting hold particular value compared to other sources of technical data 15-20 minute presentations followed by open discussion of technical data needs for harvesting
Session Expectations
- Session 3 Sources of Materials Information on previously harvested materials and future harvesting opportunities
- Materials in " boneyards" at research and vendor facilities
- Decommissioning plants that may allow for future harvesting Short 5-10 minute presentations followed by open discussion Starting point for potential database of previously harvested materials and future harvesting opportunities
- Session 4 Harvesting Experience: Lessons Learned and Practical Aspects Forward-looking lessons learned from past harvesting programs
- Pitfalls to avoid and strategies to improve likelihood of success Practical perspective from non-researchers on how harvesting interfaces with the decommissioning process International decommissioning and harvesting experience 20-30 minute presentations followed by open discussion
Session Expectations
- Session 5 Future Harvesting Program Planning
- Technical and logistical information needed when planning a specific harvesting program
- Perspective from panel participants on their organizations' future harvesting planning Next steps and actions from workshop Potential areas of common interest for future harvesting programs Brief (5-10 minute) presentation from each panel member followed by open and panel discussion
Note to requester: Attachments are immediately following.
From: Hiser, Matthew Sent: Mon, 21 Nov 2016 13:56:33 +0000 To: Tregoning, Robert Cc: Purtscher, Patrick
Subject:
RE: harvesting workshop Attachments: NRC Harvesting Workshop Announcement.docx, Workshop Agenda 11 16.docx Hi Rob, I have attached the latest version of the announcement and agenda. I think the announcement is good and ready for distribution.
For the agenda, the latest status is I sent it to you, Pat, Jeff, and Allen for comment/ feedback. Once we are relatively happy internally, it can go to EPRI/DOE for feedback/ a meeting to discuss.
The other big things we need to do is determine whether this meeting should be open or closed and contact speakers.
Side note: Greg said transcription services were "free" to him when he did the concrete workshop a couple years ago (covered under some other contract I presume). Of course, that could have changed so I need to contact the right people for more info.
Thanks!
Matt From: Tregoning, Robert Sent: Monday, November 21, 2016 8:19 AM To: Hiser, M atthew <Matthew. Hiser@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
FW: harvesting workshop Matt:
Is announcement finished at this point so I can start sending it out? We need to finalize our strawman agenda so it can be sent to both EPRI and DOE. We also need to arrange a meeting to flush this agenda out in December. We should have the agenda finalized before the holidays and speakers contacted if possible. Do you agree?
(b)(6) ..........._I_
. _ _ _ _ _ _ _ _ _ _ _ _ _IPat and I will have to drive this ground in your absence.
Cheers, Rob
Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph : 301-415-2324 fax : 301-415-6671 From: Sokolov, Mikhail A. (mailto:sokolovm@ornl.gov]
Sent: Monday, November 21, 2016 8:03 AM To: Tregoning, Robert <Robert.Tregon ing@nrc.gov>
Subject:
(External_Sender) harvesting workshop Hi Rob, It was nice to see you last week in Orlando.
I forgot to ask you . You are organizing the "harvesting" workshop in March. Since I am involved in Ginna baffle bolts and Zion RPV project, I would be interested in participating to hear the NRC take on this subject. However, there was some moves in dates for it. Have you settled with dates? I have some other commitments in March and trying to manage my trips.
- Thanks, Mikhail Dr. Mikhail A. Sokolov Oak Ridge National Laboratory P.O. Box 2008, M.S. 6151 (for delivery use 1 Bethel Valley Road)
Oak Ridge, TN 37831 865-574-4842 (ph.)
865-241-1026 (fax) sokolovm@ornl.gov
Ex-Plant Materials Harvesting Workshop Location: NRC HQ in Rockville, MD 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 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
- International collaborative programs on specific components at specific plants
Draft Agenda - March 7-8, 2017 Harvesting Workshop Tuesday, March 7, 2017 Introduction
- NRC overview of workshop purpose and objectives 8:00 - 8:10 Session 1: Lessons learned from harvesting experience
- EPRI Perspective on Harvesting Lessons Learned 8:10 - 8:45 o Zorita, Baffle Bolts, Barsebeck, etc.
- DOE Perspective on Harvesting Lessons Learned 8:45 -9:20 o Zion , etc.
- NRC Perspective on Harvesting Lessons Learned 9:20 -9:50 o Shoreham, St. Lucie, Zorita, Zion, etc.
BREAK 9:50 - 10:05
- Japan - JNES / JNRA 10:05 - 10:40 o International Perspective on Harvesting Lessons Learned DISCUSSION 10:40 - 11 :30 LUNCH 11 :30 - 12:30 Session 2: Technical data needs best addressed by harvesting
- PNNL/NRC 12:30 -12:55 o Overview of data needs best addressed by harvesting
- Belgium - Tractebel 12:55 - 1:20 o Perspective on harvesting data needs, particularly RPV
- Korea - KAERI? 1:20 -1 :45 o Perspective on harvesting data needs, Kori plant
- Switzerland - ENSI or PSI? 1:45 - 2:10 o Perspective on harvesting data needs, Muhleberg DISCUSSION 2:10 - 2:45 BREAK 2:45 - 3:00 Session 3: Sources of Materials
- NRC 3:00 - 3:15 o Available materials from decommissioning plants and past harvesting programs
- EPRI/NEI 3:15 - 3:45 o Available materials from operating reactors and past harvesting programs
- IAEA? 4:15 - 4:45
- International harvesting opportunities
DISCUSSION 4:45 - 5:30 Wednesday, March 8, 2017 Session 4: Practical aspects of Harvesting
- US decommissioning company 8:00 - 8:40 o Decommissioning process vs. harvesting: schedule, site-specific, timing for different components
- International decommissioning company- Germany? 8:40 -9:20 o Decommissioning and harvesting plans and experience
- US utility 9:20 -10:00 o Decommissioning process and plans o Owner perspective on harvesting and decommissioning BREAK 10:00 - 10:15
- Researcher perspective - EPRI or DOE or international 10:15 - 10:45 o Practical challlenges to plan for and carry out harvesting DISCUSSION 10:45 - 11 :45 LUNCH 11:45 - 12:45 Session 5: Harvesting Decision-making
- PNNL/NRC 12:45 - 1:15 o Technical information needed for informed harvesting decisions
- EPRI/NEI 1:15 - 1:45 o Balancing costs and benefits to ensure value from harvesting
- DOE 1:45 - 2:15 o Applying past experience to future harvesting decisions
- International - ? 2:15 - 2:45 o Harvesting decision-making
- DISCUSSION 2:45 - 4:00 o Potential harvesting partnerships RPV, internals, piping, concrete, cables US, international opportunities
Discussion 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
Note to requester: Attachments are immediately following.
From: Hiser, Matthew Sent: Fri, 3 Mar 2017 12:48:56 +0000 To: Kirk, Mark Cc: Tregoning, Robert
Subject:
RE: Input on Harvesting Slides Attachments: Harvesting Workshop Final Agenda.docx, Final Harvesting Workshop Attendees.docx Hi Mark, Thank you for your input on the slides. We had a final meeting yesterday afternoon to go over the attendee list and agenda (both attached for your awareness). We are really tight on space for the workshop as we've had several late external requests to participate and wanted to include at least a couple spots for NRR staff. Plus this workshop covers electrical and concrete topics as well, so that makes the limited space more challenging.
We'd like to see if you could participate in the workshop via the webinar (https://attendee.gotowebinar.com/register/6076202901971284226). Obviously, this is not the most ideal situation, but we really appreciate your understanding and engagement in the workshop. Rob will plan to cover the RPV discussion for NRC in the room.
We are planning a dinner with workshop attendees on Tuesday night starting around 6 :00. I would like to invite you to join the dinner. Please let me know by Monday if possible so I can finalize the headcount.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-24541 Office: TWFN J0D62 M atthew .Hiser@ nrc.gov From: Kirk, Mark Sent: Wednesday, March 01, 2017 12:45 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Subject:
RE: Input on Harvesting Slides You bet.
Looking forward to your meeting mark From: Hiser, Matthew Sent: Wednesday, March 01, 2017 12:42 PM
To: Kirk, Mark <Mark.Kirk@nrc.gov>
Subject:
RE: Input on Harvesting Slides Hi Mark, Thank you for taking a look at the slides and providing input. I reworded the statement for your first comment (now "Ideally a bounding, yet realistic, material/environment"). The idea of that bullet is that we choose to harvest from a plant with more severe conditions (be they material composition or environment or both depending on the mechanism) than most (ie, bounding (or nearly so), yet realistic).
This may be in contrast to accelerated aging tests where we may take certain parameters to very unrealistic, but conservative, values to understand a mechanism.
For your second comment, I replaced the language on RPV data needs with your suggestion. The original language came from what I gathered through separate discussions with you and Rob and my limited understanding of RPV materials. Thank you for clarifying and correcting the language.
Thanks!
Matt From: Kirk, Mark Sent: Wednesday, March 01, 2017 9:57 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Cc: Kirk, Mark <Mark.Kirk@nrc.gov>
Subject:
RE: Input on Harvesting Slides Hi Matt-Thanks for providing me the opportunity to comment (sorry it has taken me so long to get to this).
I have one editorial and one technical comment, as detailed below. I'm around today, Frit ay, Monday if you want to discuss. On Thursday I'll be working remote - you can call me on I
- * * * * * * ...{l?).(~L (b)(6) , .................. 1 I Best Mark Slide 4, NRC perspective slides, editorial / logical comment
- You say "Ideally a bounding, yet broadly representative, material/environment". This is a contradictory statement; if something is bounding it is, by definition, NOT representative. Representative would be something closer to average conditions.
Slide 3, NRC Technical Data Needs, technical comment
- You say we want a " High fluence vessel with relatively high levels of minor alloying elements (Mn, P, etc.)
o I agree with the "high fluence" part ... but we should explain why we want this.
o I don't understand / don't agree with the alloying elements part for several reasons:
In RPV steels phosphorus is not an a lloying element, it is a tramp If the reason for looking for "moderately" high Mn is to search for the ever illusive late blooming phase, then we would need to say that we need a high combination of Mn & Ni ... and not moderately high, but REALLY high. What we would need is, in fact, so high that I can tell you it does not exist in the USA fleet. We should not bother to look - it's not there.
- Given all of this I suggest a re-wording of your bullets under RPV , as follows:
- High fluence & high shift vessel with well-established unirradiated properties (on a means to estimate them) o Through thickness section to validate fluence & attenuation models o Measure fluence , toughness, & chemistry as a function of through-thicknes osition
- Samples from vi rtually any vessel o Of sufficient size to enable measurement of both the Charpy transition curve and aster curve transition temperature T 0 o This testing Enables demonstration of the conservatism of regulatory approaches fo ransition temperature prediction Provides data supporting evolution from the use of correlative (Charpy-based) to direct measurement (fracture toughness-based} agproaches From: Hiser, Matthew Sent: Wednesday, February 22, 2017 10:08 AM To: Nove, Carol <Carol.Nove@nrc.gov>; Kirk, Mark <Mark.Kirk@nrc.gov>; Oberson, Greg
<Greg.Oberson@nrc.gov>; Focht , Eric <Eric.Focht@nrc.gov>
Subject:
Input on Harvesting Slides Hi Carol , Mark, Greg, and Eric, We are hosting a workshop w ith a number of external participants in two weeks to discuss ex-plant materials harvesting. I know I've discussed this with at least a couple of you. I have attached the workshop introduction slides that cover meeting logistics, motivation, approach, expected outcome, and session expectations for your awareness.
I have also attached PP slides for NRG presentations in sessions 2, 3, and 4. These slides have been developed primarily with input from myself, Rob Tregoning and Pat Purtscher. The intent of these slides is to be a discussion starter and provide N RC's perspective on the session topics related to harvesting.
Some of the topics covered i n these slides include RPV, N OE, PWSCC, and NAM, so I'd like to share them with each of you for a quick review. Please let me know if you have any questions and provide any comments or feedback at your earliest convenience.
Thanks!
Matt Matthew Hiser Materials Engineer
US uclear Regulatory Commission I Office of uclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 l-415-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov
Ex-Plant Materials Harvesting Workshop Agenda Tuesday, M arch 7 Session Time On~anization Speaker Presentation Title Intro 8:00 NRC Robert Tregoning Welcome and Introduction to Workshop DOE Rich Reister DOE Perspectives on Material Harvesting EPRI Sherry Bernhoft EPRI Perspective on Harvesting Projects 8:15- 8:45 NRC Robert Tregoning NRC Perspect ive on Motivation for Harvesting 1
GRS Uwe Jendrich Role of GRS in Decommissioning and LTO CRIEPI Taku Arai CRIEPI Motivations for Harvested 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 DOE Keith Leonard 10:55 Needs for Harvesting 2
10:55- Review of past RPV sampling test 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 Effect s on Concrete Properties 11:45-DISCUSSION 12:30 12:30 - 2:00 LUNCH Sources of Materials: Past NRC Harvesting and 2:00 - 2:10 NRC Matthew Hiser U.S. Decommissioning Plants Harvesting Plans for Materials 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 Li brary Gerry van 3:00- 3:15 Energy Solutions Zion Material Harvest ing 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 iin 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 Or~anization 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 Harvesting Experience and 9:00- 9:30 NRC Matthew Hiser Lessons Learned CRIEPI Research Activities with Harvested 4 9:30-10:00 CRIEPI 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
Workshop Attendees Name Or2anization Taku Arai CRIEPI Sadao Higuchi CRIEPI Japan Kazunobu Sakamoto JNRA Yasuhiro Chimi JAEA Uwe Jendrich GRS Europe Rachid Chaouadi SCK-CEN Guy Roussel BelV Daniel Tello CNSC Canada Desire Ndomba CNSC Karen Huynh AECL Gerrv van Noordennen Enen1 v Solutions us Bill Zipp Dominion industry Mark Richter NEI Arzu Alpan Westinghouse Sherrv Bernhoft EPRI Robin Dyle EPRI EPRI Jean Smith EPRI Al Ahluwalia EPRI Tom Rosseel ORNL Rich Reister DOE Keith Leonard ORNL DOE Mikhail A. Sokolov ORNL John Wagner INL John Jackson INL Pradeep Ramuhalli PNN L Pat Purtscher NRC/RES Rob Tregoning NRC/RES Matt Hiser NRC/RES Mita Sircar NRC/RES NRC Tom Koshy NRC/RES Jeff Poehler NRC/NRR Allen Hiser NRC/NRR Angela Buford NRC/NRR Pete Ricardella NRC/ACRS
Note to requester: The attachments are immediately following.
From: Hiser, Matthew Sent: Fri, 3 Feb 2017 18:31:35 +0000 To: Purtscher, Patrick
Subject:
RE: RE: Draft slides Attachments: Ex-Plant Materials Harvesting Workshop.pptx, NRC Technical Data Needs for Harvesting.pptx Pat: here's my draft email to Pradeep. If you get the chance to review his slides today and largely agree, please send with me on cc. I might try to give him a call just to make sure my feedback is clear. Thanks!
Hi Pradeep, Thank you for sharing these slides. I've attached a PP that we are distributing to speakers and attendees describing the workshop overall as well as expectations for each session. We just developed this in the past few days, and are starting to distribute now. Please take a look for your awareness.
I think these slides are a good starting point, but are a little too broad for the sessions we' re envisioning.
For the first presentation in session 2, I would focus on capturing Section 3.3 from the draft report you sent a couple days ago. So focus on the criteria for prioritizing harvesting data needs and the examples that PNNL analyzed in the report: CASS, cables, DMWs, internals. We are planning a very short NRC slot in session 2 to cover more comprehensively NRC's data needs for harvesting; we want you to cover the criteria and 4 examples and we'll lay out the whole range of high-priority data needs for metals, cables, and concrete. I've attached the current draft of our slides for you awareness ...
From the slides you have now for session 2, here's my suggestions:
- I would delete slide 2 because it is high-level and more captured in Session 1.
- Keep slide 3 to capture briefly Ch. 2 ideas: why do harvesting, which leads to prioritization criteria
- Add a slide to capture Section 3.1/3.2 on lit review/ basis for information
- Add slide or two on criteria: why these criteria, how are they applied/used
- Add several slides going through examples (maybe 1 slide/example) and how criteria led to an outcome o In other words, explain why we're interested in harvesting cables, CASS, and internals, but not DM welds so much
- That's it!
For session 5 slides, I'd like to focus on Section 4.2 from your report with references to 4.1 (harvesting experience) as needed to explain why we'd like various pieces of information for harvesting planning.
Suggestions on specific slides:
- Delete slides 11/12 - don't need to cover info tool in this presentation
- Maybe 1 or 2 background slides referring to harvesting experience (Ch. 4.1) in general
- Focus several slides on Section 4.2 going in-depth on what information is needed for harvesting planning o This presentation sets the stage in Session 5 for a discussion of harvesting plans from the various participants, so we want to thoroughly systematically lay out what information we think is hellpful for informed decision-making Thanks!
Matt From: Ramuhalli, Pradeep [2]
Sent: Friday, February 03, 2017 10:37 AM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
[External_Sender] RE: Draft slides Shoot! Will resend in a bit.
With best regards, Pradeep Pradeep Ramuhalli, PhD.
Senior Research Scientist Pacific Northwest National Laboratory pradeep.ramuhalli@pnnl.gov 509-375-2763 Sent from my Android phone using Symantec Touch Down (www.symantec.com)
Original Message-----
From: Hiser, Matthew [Matthew.Hiser@nrc.gov]
Received: Friday, 03 Feb 2017, 4:46AM To: Ramuhalli, Pradeep [Pradeep.Ramuhalli@pnnl.gov); Purtscher, Patrick [Patrick.Purtscher@nrc.gov]
Subject:
RE: Draft slides FYI - slides didn't make it through ...
From: Ramuhalli, Pradeep [3]
Sent: Friday, February 03, 2017 1:36 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
[External_Sender] Draft slides Symantec Mail Security replaced Harvesting workshop slides draft.pptx with this text message.
The original file was a malformed file, therefore it cannot be scanned and was quarantined.
ID:HQPWMSMRS04::SYQ3370fc312 The email message was also quarantined.
Ex-Plant Materials Harvesting Workshop March 7-8, 2017 USNRC HQ Rockville, MD, USA
Meeting Logistics
- Workshop will be held at NRC's Three White Flint North building Directly adjacent to the White Flint Metro station Nearest hotel within walking distance: Bethesda North Marriott Hotel &
Conference Center
- Workshop is a non-public meeting to encourage open discussion
- Presentations and meeting summary will be distributed among meeting participants only
- GoToMeeting webinar will be available to support additional attendees Webinar attendees will be primarily observers
- Limited opportunities for webinar attendee participation in discussion if time allows Discussion will be recorded through GoToMeeting software to aid capturing discussion in meeting summary
Motivation
- With plants shutting down both in the U.S. and internationally, there are increasing opportunities to harvest components from decommissioning plants
- Past harvesting efforts generally more reactive as opportunities arose, rather than proactively planned
- Ex-plant materials may be valuable because they have been exposed to actual in-service plant operating conditions
- Can reduce the uncertainty associated with the applicability of the aging conditions
- Insights from research on harvested materials can address technical data needs identified for extended plant operation
- Lessons learned from past harvesting programs can help improve future harvesting efforts Challenges encountered in previous programs can be shared and mitigated or avoided in future programs
Approach
- Domestic and international researchers, industry, regulators, and decommissioning companies' discuss benefits and challenges with ex-plant harvesting
- Encourage sharing of lessons learned as well as areas of common interest
- Workshop consists of topical sessions with short presentations and significant time for open discussion
- Goal is to maximize engagement among meeting participants
- Scope includes any materials aging issue that could benefit from harvesting, including metals, cables, and concrete
Expected Outcome
- Participants become better informed and aware of the benefits and challenges associated with ex-plant harvesting
- Discussions help identify areas of common interest for harvesting to address technical data needs
- Presentations and discussions provide the starting point for a "database" of harvested materials and future harvesting opportunities
- Contacts are made among research organizations to allow for further discussion of specific harvesting projects
- Workshop summary documenting discussion will be distributed among participants
Session Expectations
- Session 1 Motivation for Harvesting Perspective from panel participants on their organizations' interest in and motivation for harvesting Brief (5-10 minute) presentation from each panel member followed by general discussion
- Session 2 Technical Data Needs for Harvesting
- Presenters share high-priority data needs that may be best addressed by harvesting
- Where does harvesting hold particular value compared to other sources of technical data 15-20 minute presentations followed by open discussion of technical data needs for harvesting
Session Expectations
- Session 3 Sources of Materials Information on previously harvested materials and future harvesting opportunities
- Materials located at research and vendor facilities
- Decommissioning plants that may allow for future harvesting Short 5-10 minute presentations followed by open discussion Starting point for potential database of previously harvested materials and future harvesting opportunities
- Session 4 Harvesting Experience: Lessons Learned and Practical Aspects Improving future efforts with lessons learned from past programs
- Pitfalls to avoid and strategies to improve likelihood of success Practical perspective from non-researchers on how harvesting interfaces with the decommissioning process International decommissioning and harvesting experience 20-30 minute presentations followed by open discussion
Session Expectations
- Session 5 Future Harvesting Program Planning
- Technical and logistical information needed when planning a specific harvesting program Perspective from panel participants on the workshop Next steps and actions from workshop Potential areas of common interest for future harvesting programs Brief (5-10 minute) presentation from each panel member followed by general discussion
~ U.S.NRC Uniced Scaces Nuclear Regulacory Commission Protecting People and the Environment N RC High-Priority Data Needs for Harvesting NRC Staff March 7, 2017
Metals
- RPV High fluence & high shift vessel with well-established unirradiated properties (or a means to estimate them)
- Through thickness section to validate fluence & attenuation models
- Measure fluence, toughness, & chemistry as a function of through-thickness position Samples from virtually any vessel
- Of sufficient size to enable measurement of both the Charpy transition curve and master curve transition temperature T0
- Th is testing
- Enables demonstration of the conservatism of regulatory approaches for transition temperature prediction
- Provides data supporting evolution from the use of correlative (Charpy-based) to direct measurement (fracture toughness-based) approaches 2 ~ U.S.NRC Unlml Statct Ncacln r Rqub1ory Commu,>>o*
Prorttting Ptrople and th, £n11il '()nmntt
Metals
- CASS and Internals High fluence reactor internals
- >50 dpa 304 SS from high core outlet temp plant
- Bounding temperature and high fluence for void swelling Thermally aged unirradiated CASS
- >30 years at ~320°C; Validate accelerated aging data Moderate fluence (1-2 dpa) CASS
- Bolster technical basis for embrittlement in this fluence range
- Components with known flaws
- Example: weld overlays over known flaws
- NDE evaluations or to assess effectiveness of mitigation techniques
- Components with limiting fatigue life Confirm fatigue calculations are accurate by inspecting for flaws 3 ~ U.S.NRC Unlml Statct Ncacln r Rqub1ory Commu,>>o*
Prorttting Ptrople and th, £n11il '()nmntt
Electrica I
- Cables
- Low and medium voltage cables
- Cables protected with fire retardant coating
- Electrical components 1E MOVs from harsh and mild environments 1E Air operated valves; 4160 1E breakers 1E Molded case breakers 480V, 250V DC, 125 VDC, lE Relays from mild environment GE - HFA, Agastat timing relays, any from Westinghouse, Potter Brumfield, Stuthers Dunn etc.,
Electrical penetrations; Batteries
- Fi re research interest Electrical enclosures
4 ~ U.S.NRC Unlml Statct Ncacln r Rqub1ory Commu,>>o*
Prorttting Ptrople and th, £n11il '()nmntt
Concrete
- Structures exposed to high radiation
- Post-tensioned structures
- Corrosion of reinforcing steel, tendon, liner, embedment
- Spent fuel pool and transfer canal-boric acid attack on concrete in PWRs
- Alkali Aggregate Reaction
- Large structural sections for testing 5 ~ U.S.NRC Unlml Statct Ncacln r Rqub1ory Commu,>>o*
Prorttting Ptrople and th, £n11il '()nmntt
From: Hiser, Matthew Sent: Tue, 31 Jan 2017 14:39:52 +0000 To: Tregoning, Robert
Subject:
RE: RE: Participation in Harvesting workshop from JAEA Thanks Rob! Glad things have fallen in place quickly this week...
Original Message-----
From: Tregoning, Robert Sent: Tuesday, January 31 , 2017 9:05 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
RE: RE: Participation in Harvesting workshop from JAEA Okay, T'm caught up with my emails except for SCK-CEN which we should send by the end of the week (by Thursday). We still need to hear back from GRC. I'll call or email if I haven't gotten a response by tomorrow.
Hopefully, the Japanese and MAI will also be finalized this week.
Thanks for your help, Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-667 1
Original Message-----
From: Hiser, Matthew Sent: Tuesday, January 31 , 2017 8:39 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
RE: RE: Participation in Harvesting workshop from JAEA Rob:
Dr. Chimi:
Thank you for your interest in the workshop. I have attached the workshop announcement and condensed agenda along with a few slides describing the motivation for the workshop and the expectations for each session. The workshop is divided into 5 sessions, each with a combination of presentations and discussion:
I. Session I will consist of short presentations and a panel discussion on the motivation for harvesting.
- 2. Session 2 will discuss data needs best met through harvesting.
- 3. Session 3 will discuss sources of materials for harvesting programs 4. Session 4 will discuss lessons-learned from past harvesting programs and practical aspects associated with harvesting.
- 5. Session 5 will attempt to summarize the workshop and planning a harvesting program, as well as discuss actions and next steps We would like to invite you to present in any of these sessions. For sessions l, 3, and 5, we are looking for brief 5-
IO minute presentations, so just a few slides at most on motivation for harvesting, sources of materials, and any future harvesting plans. For sessions 2 and 4, the presentations are anticipated to be longer, perhaps 20-30 minutes, covering data needs best addressed through harvesting (session 2) and lessons learned from previous harvesting experience (session 4).
For logistics, the workshop will be held at NRC's headquarters, which is at the White Flint Metro station:
Three White Flint North 11 60 I Landsdown Street North Bethesda, MD 20852 The nearest hotel is across the street: hltp://www.marriott.com/hotcls/travcl/wasbn-bcthcsda-north-marri-0tt-hotcl-and-confcrencc-ccntcr/ . Please let me know if you need any other information regarding location or accommodations.
Please let me know if you would be able to participate and which sessions you would be willing to support. We will look forward to your participation and contribution to the workshop!
Rob Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 1-415-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov
Original Message-----
From: Tregoning, Robert Sent: Tuesday, January 31, 201 7 6:45 AM To: Hiser, Matthew <Matthew.H iser@nrc.gov>
Subject:
FW: RE: Participation in Harvesting workshop from JAEA Matt:
Herc's JAEA. Can you also put together an email for them as well? Let's ask them in this email if they are willing to participate in any of the sessions.
Thanks for your help, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T- LO A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301 -415-667 1
Original Message-----
From: Yasuhiro Chimi [4]
Sent: Tuesday, January 31, 2017 2:05 AM To: Tregoning, Robert <Robcrt.Trcgoning@nrc.gov>
Subject:
[External_Sender] RE: Participation in Harvesting workshop from JAEA
Dear Mr. Robert Tregoning,
My name is Yasuhiro Chimi. I'm a member of Nuclear Safety Research Center, Japan Atomic Energy Agency (JAEA), and in charge of IASCC study of stainless steels.
As Mr. Kazunobu Sakamoto told you, I would like to attend the harvesting workshop. Could you give me some more infonnation on the workshop, such as registration, venue, accommodation, how to get there, etc.?
I'm looking forward to hearing from you.
Sincerely yours, Yasuhiro Chimi Yasuhiro Chimi, Ph.D.
Materials and Water Chemistty Research Group Materials and Structural Integrity Research Division Nuclear Safety Research Center Sector of Nuclear Safety Research and Emergency Preparedness Japan Atomic Energy Agency (JAEA)
Phone: +81-29-282-6473 , Fax: +8 1-29-282-5406 E-mail: chimi.yasuhiro@jaea.go.jp
Original Message-----
From: Tregoning, Robert [5]
Sent: Monday, January 23, 20 17 I I :0 I PM To: Jj:21,: - f/§ <kazunobu_sakamoto@nsr.go.jp>
Cc: chimi.yasuhiro@jaea.go.jp; Yutaka Nishiyama (nishiyama.yutaka93@jaea.go.jp)
<nishiyama.yutaka93@jaea.go.jp>; iCli:Ct H - <kenichi_takakura0 l @nsr.go.jp>; III [ I fi'H't <kiyotaka_taguchi@nsr.go.jp>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hiser, Matthew
<Matthew.Hiser@nrc.gov>
Subject:
RE: Participation in Harvesting workshop from JAEA Kazu:
It's always so good to hear from you. I look forward to hearing from your colleague at JAEA about participation in the harvesting workshop. I also will be in touch with you shortly to coordinate and finalize the contributions from Japan so that we can finalize the agenda.
Warm regards, Rob
Robert Tregoning T echnical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 30 1-415-2324 fax: 301-415-667 1 From: :lj:,jl: - fa sakamoto@nsr.go. jp
Sent: Thursday, January 19, 2017 9:19 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Cc: chimi.yasuhiro@jaea.go.jp; Yutaka Nishiyama (nishiyama.yutaka93@jaea.go.jp)
<nishiyama.yutaka93@jaea.go.jp>; il'lift ft * < kenichi_takakura0 l @ nsr.go.jp>; If! Cl 7"~:P <kiyotaka_taguchi@nsr.go.jp>
Subject:
[Extemal_Sender] Participation in Harvesting workshop from JAEA Hi Rob, A staff of our technical support organization JAEA wants to participate in the workshop and will contact you soon.
So I would appreciate if you could accept his participation.
T hanks for your cooperation in advance.
Best regards, Kazu
INote to requester: Attachments are immediately following.
From: Tregoning, Robert Sent: Wed, 23 Nov 2016 07 :26:04 -0600 To: Brock, Kathryn;Hiser, Matthew Cc: Frankl, Istvan
Subject:
RE: RIC sessions Attachments: #20 RES Technical Issues - Advanced Non-Light Water Reactors.pdf, #25 RES -
Leveraging International Research and Facility to Inform Regulator Decision-Making.docx, #4 NRO -
Advanced Non-Light Water Reactors - International Coordination and Collaboration.docx, NRC Harvesting Workshop Announcement.docx, Workshop Agenda 11-4-16.docx Kathryn:
Attached are the following:
- 1. Write-ups for the related sessions on ANLWR and Leveraging International Research (ignore the numbers on the files). Also, please note that these write-ups are sparse; there's not much information on them.
- 2. Harvesting workshop announcement
- 3. Draft harvesting workshop agenda (this is very draft. We haven't reached internal consensus yet or shared with EPRI/DOE). I would share with him the topics we are planning but not the details of the agenda.
I'll let Matt provide the bullets. There are several other RIC sessions with an international flavor. I can provide you with any of those write-ups as you like.
Let me know if you have any questions about any of these attachments or need additional information.
- Cheers, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Brock, Kathryn Sent: Wednesday, November 23, 2016 7:31 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frank l@ nrc.gov>
Subject:
RIC sessions Hey Rob and Matt,
I'm wondering if you can help me with something. Whi le I'm in Vienna next week I'm meeting with Ed Bradley, who is part of Nuclear Energy at IAEA and is working to develop cooperative research programs. So I have two requests .. can you please provide a bit of info:
- Matt ...bu llets on our effort to do materials harvesting as well as an agenda for the meeting after the RIC, or perhaps info on who will be participating.
- Rob ... summaries of the RIC sessions Tl, "Advanced non LWR international coordination and collaboration" and TH29, "Leveraging Internationals Research and Facility to Inform Regulatory Decision making" .
I figure I can tell him about the RIC and the harvesting meeting and perhaps he can decide if he thinks it would be worthwh ile to support.
Thanks!!!
RIC 2017 PROPOSED TECHNICAL "SESSION" SUBMISSION FORM Part 1: Session Title and Description
- Session
Description:
The topic should be relevant, topical, new or emerging, and of interest to the audience. The title should be relatively short, creative, and appealing. The description should include details that gives the audience a better understanding of the focus of the session, its purpose, goals, learning objectives, and any takeaway messages. Note: Descriptions (.doc or .docx) are limited to 950 characters including spaces and punctuation.
Submitting Office(s):
Enter office acronym (if a joint RES session, enter lead office followed by supporting office)
Session
Title:
Title should be relatively short, Advanced Non-Light Water Reactors - International and Domestic creative, and appealing Experience in Addressing the Technical Issues and Challenges Sessio*n Description : As part of the near-term implementation of NRC's vision and strategy for improving the agency's readiness to Description should Include details regulate advanced non-light water reactor (ANLWR) technologies, th is session will provide a forum for that gives the audience a better presenting and discussing the technical challenges and opportunities in modeling and testing of reactor understanding of the focus of the designs, high temperature applications of materials, and advanced fuels for ANLWRs, including session, its purpose, goals, learning high-temperature gas reactors, liquid-metal fast reactors, and molten salt reactors. Topics will include objectives, and any takeaway international experience in gas-cooled reactors, pebble-bed moderated reactors and sodium-cooled fast reactors, DOE research activities, and NRG plans and activities in this area.
messages Session Chair:
Enter first and last name, position Kathy Brock, Deputy Director, Division of Engineering, RES/DE title, division name and office.
Example: John Doe, Deputy Director, Division of Engineering, NRRINRC Potential
Enter name, position title, and Center, IGARC, India; 4) Mike Davies, AMEC, UK; 5) Tai Asayama, organization for each speaker or JAEA, Japan; 6) Celine Cabet, CEA, France; 7) Gyeong-Hoi Koo, KAERI, panelist (list In order they will be presenting, if known) Korea; 8) NRC; 9) DOE ; 10) Elysium, NY (Molten Salt Reactor developer)
Sessio,n Coordinator:
Enter first and last name, position Raj Iyengar, RES/DE title, division name, office, Steve Bajorek/Nate Hudson, RE S/DSA telephone number, and email address. Example: John Doe, Steve Downey, NRO Branch Chief, Division of Engineering, NRRINRC, 301-415-0000, John.Doe@nrc.g_ov Topic Submitted By:
If the name(s) of the Session Chair Raj Iyengar, RES/DE and/or Coordinator are not known, enter a point of contact name for the topic submission ENCLOSURE 1
RIC 2017 Part 2: Session Format Session Format Options: (based on technical sessions being 90 minutes in length)
- Presentation Format: Generally this format consists of one Session Chair and up to four speakers. The Session Chair provides a brief introduction and each speaker has approximately 15 minutes to give his or her presentation as it relates to the main session topic. Note: If the Session Chair is also a panel member, then presentation time is reduced for each speaker accordingly.
- Discussion Format: Generally this format consists of one Session Chair and up to four speakers. The Session Chair takes approximately 10 minutes to provide introductory remarks and presents an overview of the main topic to be discussed. The panel discussion of the topic runs for approximately 50 minutes, followed by a question and answer period for approximately 30 minutes. Note: Typically the panelists do not have prepared presentation slides for the discussion portion. The Session Chair uses the last 5 minutes to wrap-up the session.
- Workshop Format: Generally this format consists of one Session Chair and up to four speakers. This forum provides an interactive learning environment. The room set is in small break-out groups. The Session Chair and speakers present different aspects of the main session topic, and encourage participants to breakout into small groups for discussion or case study analysis. To aid in the discussion, the Session Chair and/or speakers may provide workbooks or session materials to session participants.
Session Format:
Enter "Presentation," "Discussion," or "Workshop "
Send completed submission form to RICMST.Resource@nrc .gov by September 29, 2016
RIC 2017 PROPOSED TECHNICAL "SESSION" SUBMISSION FORM Part 1: Session Title and Description
- Session
Description:
The topic should be relevant, topical, new or emerging, and of interest to the audience. The title should be relatively short, creative, and appealing. The description should include details that gives the audience a better understanding of the focus of the session, its purpose, goals, learning objectives, and any takeaway messages. Note: Descriptions (.doc or .docx) are limited to 950 characters including spaces and punctuation.
Submitting Office(s):
Enter office acronym (if a joint RES session, enter lead office followed by supporting office)
Session
Title:
Title should be relatively short, Leveraging International Research and Facility to Inform Regulator creative, and appealing Decision-Making Session
Description:
Description should include details How NRC and Industry leverages the international research and facilities that gives the audience a better to helps identify and resolve safety issues, make regulatory decisions, understanding of the focus of the develop guidance and promulgate regulations for nuclear facilities and session, its purpose, goals, teaming objectives, and any takeaway nuclear material users who are regulated by the agency.
messages Session Chair:
Enter first and last name, position Edwin Hackett title, division name and office.
Example: John Doe, Deputy Director, Division of Engineering, NRRINRC Potential Margaret McGrath, Halden Labs Speakers/Panelists:
Enter name, position title, and Maria Krosnic, NEI, CNO or alternate organization for each speaker or Aladar Csontos, EPRI panelist (list in order they will be presenting, if known) Veronique Rouyer, Chadarache Nuclear center Session Coordinator:
Enter first and last name, position Donna-Marie Sangimino title, division name, office, SR. International Relations Officer telephone number, and email address. Example: John Doe, International Program Team/PMDA Branch Chief, Division of Office of Regulatory Research Engineering, NRRINRC, 301-415-0000, John.Doe@nrc.g_ov Topic Submitted By:
If the name(s) of the Session Chair Rebecca Tadesse and/or Coordinator ara not known, enter a point of contact name for the topic submission ENCLOSURE 1
RIC 2017 Part 2: Session Format Session Format Options: (based on technical sessions being 90 minutes in length)
- Presentation Format: Generally this format consists of one Session Chair and up to four speakers. The Session Cha ir provides a brief introduction and each speaker has approximately 15 minutes to give his or her presentation as it relates to the main session topic . Note: If the Session Chair is also a panel member, then presentation time is reduced for each speaker accordingly.
- Discussion Format: Generally this format consists of one Session Chair and up to four speakers. The Session Cha ir takes approximately 10 minutes to provide introductory remarks and presents an overview of the main topic to be discussed . The panel discussion of the topic runs for approximately 50 minutes, followed by a question and answer period for approximately 30 minutes. Note: Typically the panelists do not have prepared presentation slides for the discussion portion. The Session Chair uses the last 5 minutes to wrap-up the session .
- Workshop Format: Generally this format consists of one Session Chair and up to four speakers. This forum provides an interactive learning environment. The room set is in small break-out groups. The Session Cha ir and speakers present different aspects of the main session topic, and encourage participants to breakout into smal l groups for discussion or case study analysis. To aid in the discussion, the Session Chair and/or speakers may provide workbooks or session materials to session participants.
Session Format:
Enter "Presentation," Discussion,* or Presentations "Workshop "
Send completed submission form to RICMST.Resource@nrc.gov by September 29, 2016
RIC 2017 PROPOSED TECHNICAL "SESSION" SUBMISSION FORM Part 1: Session Title and Description
- Session
Description:
The topic should be relevant, topical, new or emerging, and of interest to the audience. The title should be relatively short, creative, and appealing. The description should include details that gives the audience a better understanding of the focus of the session, its purpose, goals, learning objectives, and any takeaway messages. Note: Descriptions (.doc or .docx) are limited to 950 characters including spaces and punctuation.
Submitting Office(s):
NRO Enter office acronym (if a joint session, enter lead office followed by supporting office)
Session
Title:
Advanced Non-Light Water Reactors - International Coordination and Title should be relatively short, creative, and appealing Collaboration Session
Description:
This session will explore the international coordination and collaboration Description should include details that gives the audience a better activities associated with advanced non-light water reactors (LWRs). It will understanding of the focus of the include presentations regarding the Group on the Safety of Advanced session, its purpose, goals, teaming Reactors (GSAR), the Generation IV International Forum (GIF), and DOE objectives, and any takeaway messages international non-LWR research collaboration. Coordinating with RES to see if they can add a topic to this session.
Session Chair:
D. Jackson, Division of Engineering Infrastructure and Advanced Reactors, Enter first and last name, position title, division name and office. NRO/NRC Example: John Doe, Deputy Director, Division of Engineering, NRRINRC Backup: Amy Cubbage, Division of Engineering Infrastructure and Advanced Reactors, NRO/NRC Potential GSAR -Amy Cubbage or Anna Bradford, Speakers/Panelists:
Enter name, position title, and GIF - John Kelly or Francois Gauche (the new Chair),
organization for each speaker or DOE - Shane Johnson or John Kelly panelist (list in order they will be presenting, if known)
Session Coordinator:
Enter first and last name, position Nishka Devaser, Project Manager, Division of Engineering Infrastructure and title, division name, office, Advanced Reactors, NRO, 301-415-5196, Nishka.Devaser@nrc.gov telephone number, and email address. Example: John Doe, Branch Chief, Division of Backup: Andrew Yeshnik, Acting Technical Assistant, Division of Engineering Engineering, NRRINRC, Infrastructure and Advanced Reactors,301-415-5777, Andrew.Yeshnik@nrc.gov 301-415-0000, John.Doe@nrc.g,ov Topic Submitted By:
If the name(s) of the Session Chair and/or Coordinator are not known, enter a point of contact name for the topic submission
RIC 2017 Part 2: Session Format Session Format Options: (based on technical sessions being 90 minutes in length)
- Presentation Format: Generally this format consists of one Session Chair and up to four speakers. The Session Cha ir provides a brief introduction and each speaker has approximately 15 minutes to give his or her presentation as it relates to the main session topic. Note: If the Session Chair is also a panel member, then presentation time is reduced for each speaker accordingly.
- Discussion Format: Generally this format consists of one Session Chair and up to four speakers. The Session Cha ir takes approximately 10 minutes to provide introductory remarks and presents an overview of the main topic to be discussed . The panel discussion of the topic runs for approximately 50 minutes, followed by a question and answer period for approximately 30 minutes. Note: Typically the panelists do not have prepared presentation slides for the discussion portion. The Session Chair uses the last 5 minutes to wrap-up the session .
- Workshop Format: Generally this format consists of one Session Chair and up to four speakers. This forum provides an interactive learning environment. The room set is in small break-out groups. The Session Cha ir and speakers present different aspects of the main session topic, and encourage participants to breakout into small groups for discussion or case study analysis. To aid in the discussion, the Session Chair and/or speakers may provide workbooks or session materials to session participants.
Session Format:
Enter "Presentation," "Discussion," or Presentation "Workshop "
Send completed submission form to RICMST.Resource@nrc.gov by September 29, 2016
Ex-Plant Materials Harvesting Workshop Location: NRC HQ in Rockville, MD 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 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
- International collaborative programs on specific components at specific plants
Draft Agenda - March 7-8, 2017 Harvesting Workshop Tuesday, March 7, 2017 Introduction
- NRC overview of workshop purpose and objectives 8:00 - 8:10 Session 1: Lessons learned from harvesting experience
- EPRI Perspective on Harvesting Lessons Learned 8:10 - 8:45 o Zorita, Baffle Bolts, Barsebeck, etc.
- DOE Perspective on Harvesting Lessons Learned 8:45 -9:20 o Zion , etc.
- NRC Perspective on Harvesting Lessons Learned 9:20 -9:50 o Shoreham, St. Lucie, Zorita, Zion, etc.
BREAK 9:50 - 10:05
- Japan - JNES / JNRA 10:05 - 10:40 o International Perspective on Harvesting Lessons Learned DISCUSSION 10:40 - 11 :30 LUNCH 11 :30 - 12:30 Session 2: Technical data needs best addressed by harvesting
- PNNL/NRC 12:30 -12:55 o Overview of data needs best addressed by harvesting
- Belgium - Tractebel 12:55 - 1:20 o Perspective on harvesting data needs, particularly RPV
- Korea - KAERI? 1:20 -1 :45 o Perspective on harvesting data needs, Kori plant
- Switzerland - ENSI or PSI? 1:45 - 2:10 o Perspective on harvesting data needs, Muhleberg DISCUSSION 2:10 - 2:45 BREAK 2:45 - 3:00 Session 3: Sources of Materials
- NRC 3:00 - 3:15 o Available materials from decommissioning plants and past harvesting programs
- EPRI/NEI 3:15 - 3:45 o Available materials from operating reactors and past harvesting programs
- IAEA? 4:15 - 4:45
- International harvesting opportunities
DISCUSSION 4:45 - 5:30 Wednesday, March 8, 2017 Session 4: Practical aspects of Harvesting
- US decommissioning company 8:00 - 8:40 o Decommissioning process vs. harvesting: schedule, site-specific, timing for different components
- International decommissioning company- Germany? 8:40 -9:20 o Decommissioning and harvesting plans and experience
- US utility 9:20 -10:00 o Decommissioning process and plans o Owner perspective on harvesting and decommissioning BREAK 10:00 - 10:15
- Researcher perspective - EPRI or DOE or international 10:15 - 10:45 o Practical challlenges to plan for and carry out harvesting DISCUSSION 10:45 - 11 :45 LUNCH 11:45 - 12:45 Session 5: Harvesting Decision-making
- PNNL/NRC 12:45 - 1:15 o Technical information needed for informed harvesting decisions
- EPRI/NEI 1:15 - 1:45 o Balancing costs and benefits to ensure value from harvesting
- DOE 1:45 - 2:15 o Applying past experience to future harvesting decisions
- International - ? 2:15 - 2:45 o Harvesting decision-making
- DISCUSSION 2:45 - 4:00 o Potential harvesting partnerships RPV, internals, piping, concrete, cables US, international opportunities
Discussion 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
Note to requester: Attachment is immediately following.
From: Hiser, Matthew Sent: Mon, 14 May 201819:47:29 +0000 To: Frankl, Istvan
Subject:
Re: UPDATE ACTION: Topics for Materials Exchange Meeting May 22-26 Attachments: NRC-industry materials meeting - IAD&Harvesting draft slides 5-14-18.pptx Hi Steve, Here's my revision to address your edits. For the one edits I didn't have any changes for: it is MRP-227, Rev. 1 that is under review with Rob and Pat's involvement (the first one was Rev. O).
I also updated the speaker notes as requested.
Thanks!
Matt From: Frankl, Istvan Sent: Monday, May 14, 2018 2 :45 PM To: Hiser, Matthew
Subject:
RE: UPDATE ACTION: Topics for Materials Exchange Meeting May 22-26 Thanks, Matt.
I left the slides with my markups on your chair.
I will need your revision by COB today if possible.
Steve From: Hiser, Matthew Sent: Friday, May 11, 2018 12:53 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Aud rain, Margaret
<Margaret.Audrain@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick
<Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: UPDATE ACTION: Topics for Materials Exchange Meeting May 22-26 Hi guys, I have drafted a few slides for the IAD and harvesting topics for the NRC-industry meeting the week after next. Please take a look and provide any edits or comments.
Thanks!
Matt
From: Frankl, Istvan Sent: Monday, May 07, 2018 5:11 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol
<Carol.Moyer@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula
<Appajosu la.Rao@nrc.gov>
Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>
Subject:
UPDATE ACTION: Topics for Materials Exchange Meeting May 22-26 Importance: High I had discussion with Rob this morning on the slides for the 30 minute CMB summary.
His recommendation was that CMB and CIB use the format of the ACRS briefing slides on DE research (attached), The basic format for the ACRS slides called for 2 pages for each program area (max 3 pages if needed) covering basically four topics for each program: Overview, Ongoing Activities, Accomplishments and Path forward.
Our slides for the Materials Exchange meeting will also need to implement the guidance provided by NRR below.
- Thanks, Steve From: Frankl, Istvan Sent: Friday, May 04, 2018 10:13 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol
<Carol.Moyer@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula
<Appajosu la.Rao@nrc.gov>
Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>
Subject:
REM INDER ACTION : Topics for Materials Exchange M eeting May 22-26 Importance: High
- All, This is a friendly reminder for the program leads to send me about 3 slides for their specific topic below ASAP but no later than COB Tuesday.
The attached draft agenda is still evolving but based on the latest alignment meeting with DMLR yesterday, there is no major change in the CMB specific sessions. Here are some guidance and takeaways provided by NRR:
- The focus of the presentations should be on the impact of the results to plant operation and licensing, and not an emphasis on "here is what we are doing." Make sure the intended messages are clear in each area.
- The question to keep in mind for all of the NRC presentations is: why should the industry care about the information the N RC is presenting? If we cannot identify a current or short-term aspect that the industry should care about, then we shou Id hold the topic to a possible presentation at a future meeting.
Please let me know if you need further guidance or clarifications on the above.
Thanks, Steve From: Frankl, Istvan Sent: Wednesday, April 25, 2018 11:28 AM To: RES_DE_CM B <RESDECMB@nrc.gov>
Subject:
ACTION: Topics for M aterials Exchange Meeting May 22-26 Importance: High All, The attachment is the latest NRR draft agenda. We will need to provide input for AM methods and have responsibility for the 30 minute time slot on 5/23 for "Status of Related Research" in CMB. If you have comments on the draft agenda, please send them to me by COB Frida .
For AM I want to make sure that we are aligned with our counterparts in NRR/NRO on the proposed presentation(s) and presenter(s). (Amy, please get back to me on this.)
For our 30 minute time slot we can cover summaries of some or all topics proposed earlier. Here is the list:
- 1. Harvesting - Current plans and activities
- 2. IAD - confirmatory testing plans
- 3. PWSCC Crack Growth - Current research plans and results
- 4. Status Update on the PWSCC Initiation Program
- 5. Status of Confirmatory Research for SLR/LTO At this stage, I will ask the respective leads to draft about 3 summary slides for each of the above topics.
Thanks,
Steve From: Rudland, David Sent: Wednesday, April 25, 2018 6:22 AM To: Alley, David <David.Alley@nrc.gov>; Ruffin, Steve <Steve.Ruffin@nrc.gov>; Collins, Jay
<Jay.Collins@nrc.gov>; Cumblidge, Stephen <Stephen.Cumblidge@nrc.gov>; Davis, Robert
<Robert.Davis@nrc.gov>; Tsao, John <John.Tsao@nrc.gov>; Poehler, Jeffrey
<Jeffrey.Poehler@nrc.gov>; Fairbanks, Carolyn <Carolyn.Fairbanks@nrc.gov>; Hovanec, Christopher <Christopher.Hovanec@nrc.gov>; Yee, On <On.Yee@nrc.gov>; Cheruvenki, Ganesh
<Ganesh.Cheruvenki@nrc.gov>; Hoffman, Keith <Keith.Hoffman@nrc.gov>; Medoff, James
<James.Medoff@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>; Frankl, Istvan
<lstvan.Frankl@nrc.gov>; M itchell, Matt hew <Matthew.Mitchell@nrc.gov>; Rezai, Ali
<Ali.Rezai@nrc.gov>
Subject:
FW: 2018-05-22 agenda draft Everyone Please take a look at the draft agenda for the materials meeting and let me know if you have any comments. We are still determining who will be making what presentation.
Can I please get your comments by April 30?
Ali, did Allen talk with you about getting the meeting set up?
Thanks Dave David L. Rudland, Ph.D.
Senior Technical Advisor for Nuclear Power Plant Materials Division of Materials and License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: OWFN-11F01 11555 Rockville Pike Rockville, MD 20852-2738 Office: (301) 415-1896 (b)(6) ......... Cell: I I Email: david.rud land@nrc.gov From: Dyle, Robin [6]
Sent: Tuesday, April 24, 2018 9:00 PM
To: Hiser, Allen <Allen .Hiser@nrc.gov>; Rudland, David <David.Rudland@nrc.gov>
Subject:
[External_Sender] 2018-05-22 agenda draft Gents - here is a first cut at the agenda. I'll let the 2 of you coordinate with your peers. I sent a copy to the industry leads for their review and comment. We can adjust as needed.
I'm not sure this bunch will interested in the advanced non-LWRs. If we need more time for other items we could reduce the time for that topic . Also we are very light on Thursday morning so we can stretch out some items or finish Wednesday afternoon .
Thoughts?
Robin Dyle Office: 205-426-537 l (b)(6) CeJLl ** I
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Irradiation-Assisted Degradation
- Overview
- Objective: Evaluate the effects of irradiation and LWR environment on the performance of reactor pressure vessel (RPV) internals
- Applications:
- Regulatory guidance and reviews for the aging management of RPV internals
- Collaboration: EPRI, Halden, International Regulators
- Ongoing activities for Irradiation Assisted Degradation (IAD)
- CGR and fracture toughness testing of irradiated ex-plant plate and weld materials
- Evaluation of industry-developed CGR reference curves for irradiation-assisted stress corrosion cracking (IASCC) of stainless steels
- Accomplishments
- Effectively leveraged partnerships with EPRI and international researchers to conduct high-priority irradiated materials testing on high fluence sta inless stee materials harvested from Zorita
Summary of Comments on PowerPoint Presentation Page: 1 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/202 1 10:48:54 AM Irrad iation Assisted Degradation (EAD)
Overview Objective: Evaluate the effects of irradiation and LWR environment on the performance of reactor pressure vessel (RPV) internals Applications:
Regulatory guidance for the aging management of RPV internals and reviews Collaboration: EPRI, Halden, International Regulators Ongoing activities for Irradiation Assisted Degradation (IAD)
CGR and fracture toughness testing of irradiated ex-plant plate and weld materials Evaluation of industry-developed CGR reference curves for irradiation -assisted stress corrosion cracking (IASCC) of stainless steels Accomplishments Effectively leveraged partnerships with EPRI and internationa l researchers to conduct high-priority irradiated materials testing on high fluence stainless steel materials harvested from Zorita IAD activities are focused on mechanical testing and microstructura l characterization of ex- plant baffle plate and weld materia ls, including those acquired in cooperation with EPRI from the Zorita reactor in Spain as well as potential research on baffle bolts removed from service during recent inspections.
IAD activities also include completing fracture toughness testing on irradiated and thermally aged cast stainless steel (CASS) materials and providing technical support for the review of industry-developed CGR reference curves for IASCC of stainless steels.
Note to requester: The Summary pages contain the comments included in the powerpoint presentation file .
Please note the date/time stamp on the summary pages reflect only when these additional pages were created , not the creation date/time of the presentation file itself.
IAD Path Forward
- Final results on cooperative Zorita baffle plate and weld materials testing expected in 2018 and 2019
- Confirmatory testing of Zorita baffle plate and weld materials at ANL underway
- Further irradiation of Zorita welds to higher fluence at Halden expected to provide additional data through 2023
- Recent news of Halden shutdown will delay these plans
Page: 2 Number: 1 Author: Presenter
Subject:
Presentation Not es Date: 2/26/202 1 10:48:54 AM IAD Pat h Forward Path Forwa rd Cooperative testi ng with EPRI (and others) of the Zo rita baffl e plate and weld materials are expected t o be completed in 2018 and 2019, respectively. The scope of this work includes tensile properties, transm ission electron microscope (TEM) to assess void swell ing and testing for crack init iation, CGR and fractu re toughness.
Independent confirmatory testing on Zorita baffle plate and weld mat erials currently underway at AN L. Th is wi ll provide further insights and clarity on the resu lts from the cooperative testing.
Welds from Zorita at an init ial dose of 2 dpa wi ll be further irrad iated at Halden to a fi nal dose of S and 8 dpa. The 5 dpa specimens are expected to comp lete irrad iation by 2020 and t he 8 dpa specimens by 2023. The recent news of Ha lden's decision to shutdown will delay these plans. NRC is developing backup plans and wil l pursue cooperative efforts with other organizations such as EPRI as appropriate.
RES/DE continues to provide technica l su pport for regulatory activities related to IAD and, in particular, the review of MRP-227, Rev. 1 and an ASME Code Case on IASCC CGR reference curves.
Ex-Plant Materials Harvesting
- Overview Objective: Prioritize technical needs best addressed by harvesting and identify best value harvesting opportunities Driver: Support technical bases to make regulatory decisions for materials degradation during long-term operation
- Ongoing activities Report from PNNL identifies potential criteria for prioritizing harvesting needs and provides some history and lessons learned from past harvesting efforts
- Focused on main issues for materials degradation during long-term operation:
RPV, internals, concrete, electrical NRC staff performing internal prioritization of issues best addressed by harvesting NRC staff compiling information on available materials:
- Previously harvested from prior programs
- From decommissioning plants
Page:3 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 10:48:54 AM Harvesting Overview Objective: Prioritize technical needs best addressed by harvesting and identify best value harvesting opportunities Driver. Support technical bases to make regulatory decisions on applications for SLR Collaboration: DOE, EPRI Ongoing activities Report from PNNL identifies potential criteria for prioritizing harvesting needs and provides some history and lessons learned from past harvesting efforts Focused on main issues for materials degradation during long-term operations: RPV, internals, concrete, electrical NRC staff performing internal prioritization of issues best addressed by harvesting to focus efforts and activities NRC staff comp ili ng information on avai lable materials:
Previously harvested from prior programs From decommissioning plants
Harvesting Accomplishments and Path Forward
- Accomplishments Workshop held in March 2017 with DOE, EPRI, industry and international stakeholders PNNL report near completion
- Path Forward Use criteria to identify NRC priorities for harvesting Review available materials from all sources and compare to identified priorities Seek cooperation and leveraging from other interested organizations to implement best value opportunities for harvesting Continually reassess priorities and available materials based on latest information
Page: 4 Number: 1 Author: Presenter
Subject:
Presentation Not es Date: 2/26/202 1 10:48:54 AM SLR Accompl ishments and Path Forwa rd Accomplishments Wo rkshop held in March 2017 with DOE, EPRI, industry and internationa l stakeholders Va luab le insights from harvesting experience t hat ca n be applied to maximize va lue of future harvesti ng efforts PNN L report near complet ion Path Forwa rd Use crit eria to identify NRC priorities for harvesting Review available mat erials from all sources and compare to ident ified priorities Seek cooperation and leveraging from other interested organ izations to implement best value opportunit ies for harvesting Continually reassess priorities and avai lable materials based on lat est information
Note to requester:
Attachment is immediately following.
From: Hiser, Matthew Sent: Fri, 11 May 2018 16:53:06 +0000 To: Tregoning, Robert;Audrain, Margaret; Hull, Amy;Purtscher, Patrick;Rao, Appajosula Cc: Frankl, Istvan Subject : RE: UPDATE ACTION: Topics for Materials Exchange Meeting May 22-26 Att achments: NRC-industry materials meeting - IAD&Harvesting draft slides 5-11-18.pptx Hi guys, I have drafted a few slides for the IAD and harvesting topics for the NRC-industry meeting the week after next. Please take a look and provide any edits or comments.
Thanks!
Matt From: Frankl, Istvan Sent: Monday, May 07, 2018 5 :11 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, M atthew
<Matthew.Hiser@nrc.gov>; Huill, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>
Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>
Subject:
UPDATE ACTION: Topics for Materials Exchange Meet ing May 22-26 Importance: High I had discussion with Rob this morning on the slides for the 30 minute CMB summary. His recommendation was that CMB and CIB use the format of the ACRS briefing slides on DE research (attached), The basic format for the ACRS slides called for 2 pages for each program area (max 3 pages if needed) covering basically four topics for each program: Overview, Ongoing Activities, Accomplishments and Path forward.
Our slides for the Materials Exchange meeting will also need to implement the guidance provided by NRR below.
- Thanks, Steve From: Frankl, Istvan Sent : Friday, May 04, 2018 10:13 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, Matthew
<Matthew.Hiser@nrc.gov>; Huill, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>
Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>
Subject : REMINDER ACTION: Topics for Materials Exchange Meeting May 22-26 Importance: High
- All, This is a friendly reminder for the program leads to send me about 3 slides for their specific topic below ASAP but no later than COB Tuesday.
The attached draft agenda is still evolving but based on the latest alignment meeting with DM LR yesterday, there is no major change in the CMB specific sessions. Here are some guidance and takeaways provided by NRR:
- The focus of the presentations should be on the impact of the results to plant operation and licensing, and not an emphasis on "here is what we are doing." Make sure the intended messages are clear in each area.
- The question to keep in mind for all of the NRC presentations is: why should the industry care about the information the NRC is presenting? If we cannot identify a current or short-term aspect that the industry should care about, then we should hold the topic to a possible presentation at a future meeting.
Please let me know if you need further guidance or clarifications on the above.
- Thanks, Steve From: Frankl, Istvan Sent: Wednesday, April 25, 2018 11:28 AM To: RES_ DE_CMB <RESDECMB@nrc.gov>
Subject:
ACTION : Topics for Materials Exchange Meeting May 22-26 Importance: High
- All, The attachment is the latest NRR draft agenda. We will need to provide input for AM methods and have responsibility for the 30 minute time slot on 5/23 for "Status of Related Research" in CMB. If you have comments on the draft agenda, please send them to me by COB Frida .
For AM I want to make sure that we are aligned with our counterparts in NRR/NRO on the proposed presentation(s) and presenter(s). (Amy, please get back to me on this.)
For our 30 minute time slot we can cover summaries of some or all topics proposed earlier.
Here is the list:
- 1. Harvesting - Current plans and activities
- 2. IAD - confirmatory testing plans
- 3. PWSCC Crack Growth - Current research plans and results
- 4. Status Update on the PWSCC Initiation Program
- 5. Status of Confirmatory Research for SLR/LTO
At this stage, I will ask the respective leads to draft about 3 summary slides for each of the above topics.
Thanks, Steve From: Rudland, David Sent: W ednesday, April 25, 2018 6:22 AM To: Alley, David <David.Alley@nrc.gov>; Ruffin, Steve <Steve.Ruffin@nrc.gov>; Collins, Jay
<Jay.Collins@nrc.gov>; Cumblidge, Stephen <Stephen.Cumblidge@nrc.gov>; Davis, Robert
<Robert.Davis@nrc.gov>; Tsao, John <John.Tsao@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>;
Fairbanks, Carolyn <Carolyn.Fairbanks@nrc.gov>; Hovanec, Christopher
<Christopher.Hovanec@nrc.gov>; Yee, On <On.Yee@nrc.gov>; Cheruvenki, Ganesh
<Ganesh.Cheruvenki@nrc.gov>; Hoffman, Keith <Keith.Hoffman@nrc.gov>; Medoff, James
<James.Medoff@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>;
Mitchell, Matthew <Matthew.Mitchell@nrc.gov>; Rezai, Ali <Ali.Rezai@nrc.gov>
Subject:
FW: 2018-05-22 agenda draft Everyone Please take a look at the draft agenda for the materials meeting and let me know if you have any comments. We are still determining who will be making what presentation. Can I please get your comments by April 30?
Ali, did Allen talk with you about getting the meeting set up?
Thanks Dave David L. Rudland, Ph.D.
Senior Technical Advisor for Nuclear Power Plant Materials Division of Materials and License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: OWFN-llF0l 11555 Rockville Pike Rockville, MD 20852-2738 Office : (301) 415-1896 (b)(6) ......... Cell: l ****************** I Email: david.rudland@nrc.gov From: Dyle, Robin [7]
Sent: Tuesday, April 24, 2018 9:00 PM
To: Hiser, Allen <Allen.Hiser@nrc.gov>; Rud land, David <David.Rudland@n rc.gov>
Subject:
[External_Sender] 2018-05-22 agenda draft Gents - here is a first cut at the agenda. I'll let the 2 of you coordinate with your peers. I sent a copy to the industry leads for their review and comment. We can adjust as needed.
I'm not sure this bunch will interested in the advanced non-LWRs. If we need more time for other items we cou ld reduce the time for that topic . Also we are very light on Thursday morning so we can stretch out some items or finish Wednesday afternoon .
Tho ughts?
Robin Dyle Office: 205-426-537 l (b)(6) C::t3.U.:J * .. * !
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Irradiation-Assisted Degradation
- Overview
- Objective: Evaluate the effects of irradiation and LWR environment on the performance of reactor pressure vessel (RPV) internals
- Applications:
- Regulatory guidance for the aging management of RPV internals and reviews
- Collaboration : EPRI, Halden, International Regulators
- Ongoing activities for Irradiation Assisted Degradation (IAD)
- CGR and fracture toughness testing of irradiated ex-plant plate and weld materials
- Evaluation of industry-developed CGR reference curves for irradiation-assisted stress corrosion cracking (IASCC) of stainless steels
- Accomplishments
- Effectively leveraged partnerships with EPRI and international researchers to conduct high-priority irradiated materials testing on high fluence stainless steel materials harvested from Zorita
Summary of Comments on PowerPoint Presentation Page: 1 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 11 :10:24 AM My name is Steve Frankl. I am the Branch Chief of the Corrosion and Metallurgy Branch (CMB) in RES/DE. The focus of regulatory research in my branch is material performance and degradation in the operat ing environment of Nuclear Power Plant s (NPPs).
Environmentally Assisted Degradation (EAD)
Overview EAD evaluates the effects of corrosion, aging and irradiation on the performance of pri mary system piping, reactor pressure vessel (RPV) internals and RPV head penetrations Driver: Reactor coolant pressure boundary leakage and component integ rity Applications/ use:
PWSCC crack growth rate (CGR) disposit ion curves and xLPR Code results to inform regulatory decisions on inspection req uirements Regulatory guidance for the aging management of RPV internals and regulatory reviews Cooperate with EPRI, Halden and International Regulators Ongoing Activities EAD research in CMB covers PWSCC and IAD.
PWSCC initiation and CGR testing RES/DE has recently started cooperative effort with EPRI for PWSCC init iation testing on Alloy 600/82/182 and Alloy 690/52/152 to support the xLPR project and to conduct confirmatory research. NRR w ill use the data to support its review of the xLPR code.
PWSCC CGR testing is being conducted to obtain data for Alloy 690/52/152 to inform inspections requ irements for upper heads, piping welds, overlays, inlays and onlays. RES/DE also participates through our contractors in the development of PWSCC CGR reference curves.
IAD IAD activit ies are focused on mechanical testing and microstruct ural characterization of ex-plant baffle plate and weld materials, including t hose acquired in cooperation with EPRI from the Zorita reactor in Spain as well as potential research on baffle bolts removed from service during recent inspections.
IAD activities also include completing fracture toughness testing on irrad iated and thermally aged cast stainless steel (CASS) materials and providing technical support for the review of industry-developed CGR reference curves for IASCC of stainless steels.
Next slide please.
Note to requester: The Summary pages contain the comments included in the powerpoint presentation file. Please note the date/time stamp on the summary pages reflect only when these additional pages were created, not the creation date/time of the presentation file itself.
IAD Path Forward
- Final results on cooperative Zorita baffle plate and weld materials testing expected in 2018 and 2019
- Confirmatory testing of Zorita baffle plate and weld materials at ANL underway
- Further irradiation of Zorita welds to higher fluence at Halden expected to provide additional data through 2023
- Recent news of Halden shutdown will delay these plans
Page:2 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 11 :10:24 AM IAD Accomp li shments and Path Forward Accomplishments We published severa l NUREG/CRs on thermal and irradiation embrittlement of CASS (NUREG/CR-7184, NUREG/CR-7185 and NUREG/CR-4513 Rev. 2) and on fracture toughness of thermally aged and irradiated stainless steels (NUREG/CR-6960, -7 184, -7185).
Effective leveraging with EPRI and other research organizations has enabled signi ficant research on high fluence stainless steel materials harvested from Zorita which provides highly representative data on baffle plate and weld materia ls to higher fluence levels.
Path Forward Cooperative testi ng with EPRI (and others) of the Zo rita baffle plate and weld materials are expected to be completed in 2018 and 2019, respectively. The scope of this work includes tensile properties, transm ission electron microscope (TEM) to assess void swelling and testing for crack init iation, CGR and fractu re toughness.
Independent confirmatory testing on Zorita baffle plate and weld materials will be performed at ANL beg inning in 2018. This will provide further insig hts and clarity on the results from the cooperative testing.
Welds from Zorita at an init ial dose of 2 dpa will be further irradiated at Halden to a fina l dose of 5 and 8 dpa. The 5 dpa specimens are expected to complete irradiation by 2020 and the 8 dpa specimens by 2023.
RES/DE continues to provide technical su pport for regu latory activities related to IAD and, in particular, the review of MRP-227, Rev. 1 and an ASME Code Case on IASCC CGR reference curves.
Next slide please.
Ex-Plant Materials Harvesting
- Overview Objective: Prioritize technical needs best addressed by harvesting and identify best value harvesting opportunities Driver: Support technical bases to make regulatory decisions on applications for SLR Collaboration: DOE, EPRI
- Ongoing activities Report from PNNL identifies potential criteria for prioritizing harvesting needs and provides some history and lessons learned from past harvesting efforts
- Focused on 4 main SLR issues: RPV, internals, concrete, electrical NRC staff performing internal prioritization of issues best addressed by harvesting NRC staff compiling information on available materials:
- Previously harvested from prior programs
- From decommissioning plants
Page: 3 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 11:10:25 AM SLR Overview:
The subsequent license renewal (SLR) program coordinates research across the Division to address technical issues and knowledge gaps for extended reactor operation to 80 years and is aimed at ensuring that we have the necessary technical bases to make regulatory decisions on applications for SLR.
Driver: Support technical bases to make regulatory decisions on applications for SLR Applications/ use:
SLR guidance documents (GALL-SLR, SRP-SLR)
Confirmatory review of SLR applications SLR research is coordinated through domestic and international research for Long Term Operation (LTO) through MOUs/ IAs with:
DOE's Light Water Reactor Sustainability (LWRS) program EPRl's LTO program, and International collaboration on SLR-related research topics.
[SKIP] [IFRAM - International Framework on Reactor Aging Management - Network of researchers concerned with materials degradation. As we re-establish this group, we hope to faci litate information exchange and cooperative research with counterpart organizations (although none is specifically planned under IFRAM).]
Ongoing activities:
The 4 key technical issues for SLR were documented in the SRM to SECY- 14-0016:
Reactor pressure vessel (RPV) neutron embrittlement at high fluence IAD / IASCC of RPV internals and primary system components Concrete and containment degradation - due to alkali silica reaction (ASR) and irradiation damage Electrical cable qualification and condition assessment - with focus on degradation of electrical and control cables Cooperative research (with data sharing and independent assessment) is ongoing w ith DOE and EPRI.
We have biweekly coordination calls Monthly subject matter expert discussions on concrete and cables research programs, and EPRI/ NRC/ DOE joint roadmap meetings 2-3 times per year to update the tracking of research tasks.
Coordination with international counterparts is ongoing through mult ilateral working groups on technical topics including the 4 key technical issues.
[SKIP sub-bullets below]
The IFRAM network was recently re-launched by RES/DE. The current IFRAM Chairman is in Korea.
Participants include China (Chinese Academy of Science), Japan (Tohoku Univ.), Korea (KINS, Seoul Nat'I Univ.), and USA research organizations, including DOE and EPRI There was a side-meeting at the IAEA Plant Life Management (PLiM) Conference, 10/26/2017, to invite additional participants.
IFRAM is independent from, but complementary to, other international organizations, such as IAEA SALTO, CODAP, CADAK, OECD-CSNI, ICG-EAC, Halden Reactor Project (HRP), etc.
In order to improve our understanding of in- service degradation of materials, RES/DE is developing a proactive strategy to evaluate material harvesting opportunities to support materials aging research and to help coordinate efforts to harvest components from reactors entering decommissioning.
A harvesting workshop in spring 2017 addressed factors to consider, prioritization, and lessons learned A poster and presentation were completed for the recent PLiM conference Ongoing work is d irected toward developing a database to help prioritize harvesting, so that we can be ready for harvesting opportunities in the future.
Next slide please.
Harvesting Accomplishments and Path Forward
- Accomplishments Workshop held in March 2017 with DOE, EPRI, industry and international stakeholders PNNL report near completion
- Path Forward Use criteria to identify NRC priorities for harvesting Review available materials from all sources and compare to identified priorities Seek cooperation and leveraging from other interested organizations to implement best value opportunities for harvesting Continually reassess priorities and available materials based on latest information
Page: 4 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 11:10:25 AM SLR Accomplishments and Path Forward Accomplishments:
In 2016, NRC, DOE and EPRI held "deep dive" meetings to share information on materials degradation issues (and sub-issues) identified in the Expanded Materials Degradation Analysis (EMDA). Independent and collaborative research is ongoing to close out most technical sub-issues.
[SKIP] [A few sub-issues were later deemed to be of lower significance and they are not being pursued at this t ime (e.g., very high dose effects, such as void swelling, in stainless st eels) - this is not closed out - IF].
The NRC aging management guidance documents for SLR (GALL-SLR and SRP-SLR} were published in July, 2017 with extensive input from RES/
DE staff.
[SKIP sub-bullets below]
Generic Ag ing Lessons Learned (GALL) report was updated for SLR (published as NUREG-2191) GALL-SLR contains generic aging effects to be managed and guidance to applicant s on developing robust aging management programs (AMPs)
Standard Review Plan was updated for SLR (published as NUREG-2192). SRP-SLR provides guidance to t he staff on reviewi ng SLR applications, including AMPs for operat ion to 80 years.
The staff and industry briefed the Commission o n the status of preparations for SLR reviews on April 26, 2017.
One of t he SLR-related sub-issues is quantifying the fatigue life of metals in LWR environments. Fatigue is called out over 100 t imes in the GALL-SLR and SRP-SLR. The revised guidance documents on fatigue (NUREG/CR-6909, Rev. 1 and Regulatory Guide 1.207) are now in publication:
[SKIP sub-bullets below]
NUREG/CR-6909, Rev. 1, "Effect of LWR Coola nt Environments on the Fatig ue Life of Reactor Materials" Regulatory Guid e 1.207, "Guidelines for Evaluating Fatigue Ana lyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors" (DG- 1309)
Path Forward Ongo ing research is focused on the four key technical issues and, in particular, on the open sub-issues.
In the near-term:
RES/DE will support NRR with confirmatory reviews of plant specific gap analyses of the treatment of RPV internals for the first SLR applications.
Conti11ue collection of RPV embrittlement daita from industry-led surveillance program to confirm predictive methods.
[SKIP] (Eventually ( ~2019), there may be a need to revise RG 1.99 to reflect longer-term data trends. (CIB))
Test CGR of concrete susceptible to ASR (Jose), and Begin accelerated aging under both gamma radiation and elevated temperature of representative cable samples. Tom Koshy will cover this topic later.
[SKIP sub-bullets below]
Samples will be aged in controlled enviro nments, at Sandia Lab.
Testing of mechanical, chemical, and elect rical properties will be done at NIST.
At the same time, industry condit ion monitoring techniques are being assessed.
In the long-term:
RES/DE will continue research on IAD of RPV internals at medium and high fluence levels, Evaluating impacts of IASCC, loss of fracture toughness and void swelling IAD research requires leveraging and long lead-t imes through ~2023 and beyond Collect RPV embrittlement data through the LR and SLR periods to confirm data trends (CIB), and Continue confirmatory research on concrete degradation including effects of ASR and irrad iation on the structural performance of concrete w ith collaborative research agreements. This topic w ill be covered by Dr. Jose Pires later.
[SKIP sub-bullets below]
ASR tests at NIST, complemented by DOE-funded work at Univ. of Tennessee ASR-susceptible concrete blocks are exposed to elevated temperature & humidity.
ASR testing: non-destructive examinations (NOE), mechanical tests of cracked concrete Irradiation effects assessments are based on reviews of industry reports and information from academic and regu latory counterparts.
A decision will be made by staff sometime in 2018 whether to pursue additional NRC*led testing of irradiated concrete.
Opportunities to harvest irradiated concrete from decommissioned plants will be sought.
If necessary, addit ional specimens may be exposed to controlled irradiat ion (e.g., in Halden or ATR), then tested.
Next slide please.
From: Moyer, Carol Sent: Mon, 14 May 201818:44:13 +0000 To: Frankl, Istvan
Subject:
RE: UPDATE ACTION: Topics for Materials Exchange M eeting May 22-26 Attachments: Long term materials degradation slides_CEM_rev2.pptx Note to requester: Attachment is immediately following.
Revised again, as directed.
From: Moyer, Carol Sent: Monday, M ay 14, 2018 12:36 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
Re: UPDATE ACTION: Topics for Mat erials Exchange M eeting May 22-26
- Steve, Revised slides and notes are in the attached file, addressing your comments.
Carol From: Moyer, Carol Sent: Tuesday, May 08, 2018 6:23 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: UPDATE ACTION: Topics for M at erials Exchange Meeting May 22-26
- Steve, Draft slides for Long-Term Materials Degradation (nee SLR Research) are attached. I kept most of the Notes text that had been in the ACRS slides, as it is still applicable.
Carol From: Frankl, Istvan Sent: Monday, May 07, 2018 5 :11 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht@nrc.gov>; Hiser, Matthew
<Matthew.Hiser@nrc.gov>; Huill, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>
Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>
Subject:
UPDATE ACTION: Topics for Materials Exchange M eeting May 22-26 Importance: High I had discussion with Rob this morning on the slides for the 30 minute CMB summary. His recommendation was that CMB and CIB use the format of the ACRS briefing slides on DE research (attached), The basic format for the ACRS slides called for 2 pages for each program area (max 3 pages if needed) covering basically four topics for each program: Overview, Ongoing Activities, Accomplishments and Path forward.
Our slides for the Materials Exchange meeting will also need to implement the guidance provided by NRR below.
- Thanks, Steve From: Frankl, Istvan Sent: Friday, May 04, 2018 10:13 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht @nrc.gov>; Hiser, Matthew
<Matthew.Hiser@nrc.gov>; Huill, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>
Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>
Subject:
REMINDER ACTION: Topics for Materials Exchange Meeting May 22-26 Importance: High
- All, This is a friendly reminder for the program leads to send me about 3 slides for their specific topic below ASAP but no later than COB Tuesday.
The attached draft agenda is still evolving but based on the latest alignment meeting with DM LR yesterday, there is no major change in the CMB specific sessions. Here are some guidance and takeaways provided by NRR:
- The focus of the presentations should be on the impact of the results to plant operation and licensing, and not an emphasis on "here is what we are doing." Make sure the intended messages are clear in each area.
- The question to keep in mind for all of the NRC presentations is: why should the industry care about the information the NRC is presenting? If we cannot identify a current or short-term aspect that the industry should care about, then we should hold the topic to a possible presentation at a futur,e meeting.
Please let me know if you need further guidance or clarifications on the above.
- Thanks, Steve From: Frankl, Istvan Sent: Wednesday, April 25, 2018 11:28 AM To: RES_ DE_CMB <RESDECMB@nrc.gov>
Subject:
ACTION: Topics for Materials Exchange Meeting May 22-26 Importance: High
- All, The attachment is the latest NRR draft agenda. We will need to provide input for AM methods and have responsibility for the 30 minute time slot on 5/23 for "Status of Related Research" in CMB. If you have comments on the draft agenda, please send them to me by COB Friday.
For AM I want to make sure that we are aligned with our counterparts in NRR/NRO on the proposed presentation(s) and presenter(s). (Amy, please get back to me on this.)
For our 30 minute time slot we can cover summaries of some or all topics proposed earlier.
Here is the list:
- 1. Harvesting - Current plans and activities 2 . IAD - confirmatory testing plans
- 3. PWSCC Crack Growth - Current research plans and results
- 4. Status Update on the PWSCC Initiation Program
- 5. Status of Confirmatory Research for SLR/LTO At this stage, I will ask the respective leads to draft about 3 summary slides for each of the above topics.
- Thanks, Steve From: Rudland, David Sent: Wednesday, April 25, 2018 6:22 AM To: Alley, David <David.Alley@nrc.gov>; Ruffin, Steve <Steve.Ruffin@nrc.gov>; Collins, Jay
<Jay.Collins@nrc.gov>; Cumblidge, Stephen <Stephen .Cumblidge@nrc.gov>; Davis, Robert
<Robert.Davis@nrc.gov>; Tsao, John <John.Tsao@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>;
Fairbanks, Carolyn <Carolyn.Fa irbanks@nrc.gov>; Hovanec, Christopher
<Christopher.Hovanec@nrc.gov>; Yee, On <On.Yee@nrc.gov>; Cheruvenki, Ganesh
<Ganesh.Cheruvenki@nrc.gov>; Hoffman, Keith <Keith. Hoffman@nrc.gov>; M edoff, James
<James. M edoff@nrc.gov>; Iyengar, Raj <Ra j.lyengar@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>;
Mitchell, Matthew <Matthew.Mitchell@nrc.gov>; Rezai, Ali <Ali.Rezai@nrc.gov>
Subject:
FW: 2018-05-22 agenda draft Everyone Please take a look at the draft agenda for the materials meeting and let me know if you have any comments. We are still determining who will be making what presentation. Can I please get your comments by April 30?
Ali, did Allen talk with you about getting the meeting set up?
Thanks Dave
David L. Rudland, Ph.D.
Senior Technical Advisor for Nuclear Power Plant Materials Division of Materials and License Renewal Office of Nuclear Reactor Regu lation U.S. Nuclear Regulat ory Commission Mail Stop: OWFN-llF0l 11555 Rockville Pi ke Rockville, MD 20852-2738 Office: (301) 415-1896 (b )(6) . Cell:!. . I Email: david.rudland@nrc.gov From: Dyle, Robin [mailto:rdyle@epri.com)
Sent: Tuesday, April 24, 2018 9:00 PM To: Hiser, Allen <Allen.Hiser@nrc.gov>; Rud land, David <David .Rudland@nrc.gov>
Subject:
[External_Sender) 2018-05-22 agenda draft Gents - here is a first cut at the agenda. I'll let the 2 of you coordinate with your peers. I sent a copy to the industry leads for their review and comment. We can adjust as needed.
I'm not sure this bunch will interested in the advanced non-LWRs. If we need more time for other items we could reduce the time for that topic . Also we are very light on Thursday morning so we can stretch out some items or finish Wednesday afternoon.
Thoughts?
Robin Dyle Office: 205-426-537 l (b)(6) ceu:j ... I
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Unless otherwise expressed in this message by the sender or except as may be allowed by separate written agreement between EPRI and recipient or recipient's employer, any review, use, distribution or disclosure by others of this message is prohibited and this message is not intended to be an electronic signature, instrument or anything that may form a legally binding agreement with EPRI. If you are not the intended recipient, please contact the sender by reply email and permanently de lete all copies of this message. Please be advised that the message and its contents may be disclosed, accessed a nd reviewed by the sender's e mai l system administrator and/or provider. ***
Long-Term Materials Degradation
- Overview Objective: Coordinate confirmatory research programs to address technical issues and knowledge gaps for extended reactor operation to 80 years Driver: Support technical bases to make regulatory decisions on applications for subsequent license renewal (SLR)
Applications:
- SLR guidance documents (GALL-SLR, SRP-SLR)
- Ongoing activities 4 key technical issues: 1) RPV embrittlement at high fluence; 2) IAD of RPV internals; 2) concrete and containment degradation, and 4) electrical cable qualification and condition assessment Coordination with DOE and industry counterparts Coordination with international counterparts through multilateral working groups Developing a proactive strategy to evaluate material harvesting opportunities to support materials aging research
Summary of Comments on PowerPoint Presentation Page: 1 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 11 :32:45 AM SLR Overview:
The long-term materials degradation (LTMD) program coordinates research across the Division to address technical issues and knowledge gaps related to extended reactor operation to 80 years and is aimed at ensuring that we have the necessary technical bases to make regu latory decisions on applications for subsequent license renewal (SLR).
Driver: Support technical bases to make regu latory decisions on applicatio ns for SLR Applications/ use:
SLR guidance documents (GALL-SLR, SRP-SLR)
Confirmatory review of SLR applications Confirmatory research for Long Term Operat ion (LTO) is coordinated with domestic and international counterparts through MOUs/ IAs with:
DOE's Light Water Reactor Sustainability (LWRS) program EPRl's. LTO program, and International collaboration on SLR-related research topics.
For example, IFRAM - International Framework on Reactor Aging Management - is a network of researchers concerned with materials degradation.
Ongoing activities:
The 4 key t echnical issues for SLR were documented in the SRM to SECY- 14-0016:
Reactor pressure vessel (RPV) neutron embrittlement at high fluence IAD / IASCC of RPV internals and primary sys.tern components Concrete and containment degradation - due to alkali silica reaction (ASR) and irradiation damage Electrical cable qualification and condition assessment - with focus on degradation of electrical and control cables The 4 key t echnical issues are all materials-related, hence the new terminology, "Long-Term Materials Degradation."
More information related to t he metals-focused topics was presented under EAD: PWSCC and IAD (previous slides).
Cooperative research (with data sharing and independent assessment) is ongoing w ith DOE and EPRI.
We have biweekly coordination calls Monthly subject matter expert discussions on concrete and cables research programs, and EPRI/ NRC/ DOE joint roadmap meetings 2-3 times per year to update the tracking of research tasks.
Coordination w it h international count erparts is o ngoing through multilateral working groups on technical topics including t he 4 key technical issues.
In order to improve our understanding of in- service degradation of materials, RES/DE is developing a proactive strategy to evaluate material harvesting opportunities to support materials aging research and to help coordinate efforts to harvest components from reactors entering decommissioning.
A harvesting workshop in spri ng 2017 addressed factors to consider, prioritization, and lessons learned.
A poster on harvesting was presented at the 2018 NRC RIC.
Ongoing work is d irected toward developing a database to help prioritize harvesting, so that we can be ready for harvesting opportunities in the future.
Note to requester: The Summary pages contain the comments included in the powerpoint presentation file.
Please note the date/time stamp on the summary pages reflect only when these additional pages were created, not the creation date/time of the presentation file itself.
LTMD Accomplishments and Path Forward
- Accomplishments NRC published aging management guidance documents with significant RES contributions: NUREG-2191 (GALL-SLR), NUREG-2192 (SRP-SLR)
Revised guidance on fatigue life in LWRs: NUREG/CR-6909, RG 1.207
- Path Forward Near Term:
- Evaluate need to revise Regulatory Guide 1.99 on RPV embrittlement
- Support NRR with confirmatory reviews of plant-specific analyses of RPV internals and possible concrete degradation for the first SLR applications
- Test CGR of concrete susceptible to alkali-silica reaction (ASR)
- Begin radiation and thermal aging of representative electrical cables Long Term:
- Continue to trend RPV properties through period of extended operation
- Continue to assess properties of RPV internals materials at medium and high fluence through further irradiation of ex-plant materials
- Determine need for long-term irradiation of concrete specime
- Assess cable condition monitoring techniques
Page:2 Number: 1 Author: Presenter
Subject:
Presentation Notes Date: 2/26/2021 11 :32:45 AM SLR Accomplishments and Path Forward Accomplishments:
In 2016, NRC, DOE and EPRI held "deep dive" meetings to share information on materials degradation issues (and sub -issues) identified in the Expanded Materials Degradation Ana lys is (EMDA). Independent and collaborative research is ongoing to close out most techn ical sub- issues.
The NRC aging management guidance documents for SLR (GALL-SLR and SRP-SLR) were published in July, 2017, with extensive input from RES/
DE staff.
Generic Aging Lessons Learned (GALL) report was updated for SLR (publ ished as NUREG-2191). GALL-SLR contains generic aging effects to be managed and guidance to applicants on developing robust aging management programs (AMPs).
Standard Review Plan was updated for SLR (published as NUREG-2192). SRP-SLR provides guidance to the staff on reviewing SLR applications, including AMPs, for ope ration to 80 years.
One of the identified SLR -related sub-issues is quantify ing the fatigue life of meta ls in LWR environments. Fatigue is ca lled out over 100 times in the GALL-SLR and SRP-SLR. The revised guidance documents on fatigue (NUREG/CR-6909, Rev. 1 and Regulatory Guide 1.207) are now in publication.
NUREG/CR-6909, Rev. 1, "Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials" Regu latory Guide 1.207, "Guidelines for Evaluating Fatigue Ana lyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors" (DG-1309)
Path Forward Ongoing research is focused on the four key techn ical issues and, in particular, on the open sub-issues.
In the near-term:
Continue collection of RPV embrittlement data from industry -led surve illance program to confirm pred ictive methods.
RES/DE will support NRR with confirmatory reviews of plant -specific analyses for RPV internals and for possible concrete degradation for the first SLR applications.
Test the crack growth rate (CGR) in a controlled environment of concrete susceptible to ASR Begin accelerated aging of representative cable samples under both gamma radiation and elevated temperature .
In the long -term:
Collect RPV embrittlement data through the LR and SLR periods to confirm data trends (CIB)
RES/DE will continue research on IAD of RPV interna ls at medium and high fluence levels th rough further irradiation of ex- plant materia ls.
Evaluating impacts of IASCC, loss of fracture toughness, and void swelling IAD research requires leveraging and long lead-times through ~ 2023 and beyond Continue con firmatory research on concrete degradation including effects of ASR and irradiation on the structural performance of concrete.
ASR testing: non -destructive examinations (NDE), mechanical tests of cracked concrete Irradiation effects assessments are based on reviews of industry reports and information from academic and regulatory counterparts.
A decision will be made by staff sometime in 2018 whether to pu rsue additional NRC-led testing of irradiated conc rete.
Opportunities to harvest irradiated concrete from decommissioned plants will be sought.
Evaluate industry (EPRI) gu idance on cable condition monitoring, and benchmark the CM guidance against operat ing experience.
Note to requester:
Attachment is From: Audrain, Margaret immediately following.
Sent: Thu, 14 Dec 2017 14:33:05 +0000 To: Hiser, Matthew
Subject:
FW: Re: upcoming visit Attachments: UIC tallk on ASR_ANL.pdf From: Sasan Bakhtiari [8]
Sent: Wednesday, December 13, 20171:09 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>
Cc: Natesan, Krishnamurti <natesan@anl.gov>; Heifetz, Alexander <aheifetz@anl.gov>
Subject:
[External_Sender] Re: upcoming visit Pat ,
As followup to our conversation this morning , attached is Alex ' s recent presentation on concrete ASR . He is the PI of that work and is Cc ' d on this emai l . Please feel free to contact Alex d irect ly for any questions you might have about this subject . Than ks ,
Sasan Sasan Bakhtiari Nucl ear Engi neering Di v i s i on Argonne National Laboratory Off : 630 . 252 . 8982 (b)(6) CelJ :.L
.. F~x : . 630 . 972 . 4511 bakhtiari@anl . gov On 12/11/2017 1:05 PM, Purtscher, Patrick wrote:
Good afternoon, One quick question, what room and bldg. will we be meeting at on Wednesday?
(b)(6) ...... MycelLphonano, is ._l_____.l if there are any last minute changes.
Thanks, Pat
From: Purtscher, Patrick Se nt: Tuesday, December 05, 201711:17 AM To: 'Natesan, Krishnamurti' <natesan@anl.gov>
Cc: Sasan (bakhtiari@anl.gov) <bakhtiari@anl.gov>; 'Majumdar, Saurin'
<majumdar@anl.gov>
Subject:
upcoming visit Good morning, I wanted to confirm with you my plans for the upcoming visit to ANL. Tuesday afternoon, I would like to address the majority of the SGT issues. There would be some time on Wednesday morning before 10 AM to finish up any SGT issues not completed on Tuesday. Then on Wednesday when Meg Audrain gets there from NRC headquarters, we will meet about harvesting needs to address materials aging degradation for extended plant operation. This will include all materials, I am most aware of the metals issues, but this is more generic. Questions regarding electrical cables and concrete have been specifically noted as important.
Pat From: Purtscher, Patrick Sent: Thursday, November 30, 2017 2:45 PM To: Majumdar, Saurin <majumdar@anl.gov>
Cc: Sasan (bakhtiari@anl.gov) <bakhtiari@anl.gov>; Natesan, Krishnamurti
<natesan@anl.gov>
Subject : RE: Re: fi le transfer I plan to be there by noon on Tuesday the 12th . I need to talk to you and Sasan about the status of reports on U-bend cracking and ODSCC of straight tubes. I also need to talk to Ken Natesan and Sasan about the close out of tasks for the term of the current TIP-5 program, the future for TIP-6, and the status of the laboratory test equipment. On Wednesday the 13th , I have a separate meeting with any interested ANL staff where I and another NRC RES employee will be discussing the new effort the NRC is taking to compile a list of all ex-plant materials available for possible future research into aging effects, this includes metals and non-metallic materials like concrete and cables. I think this meeting will be no earlier than 10 AM on the 13th. I also have a phone call set up that I have to call in for from noon to 1 PM central time. I need to leave for the airport by 3:30 PM I think (b)(6) tocatchal * * !flight home.
Pat From: Majumdar, Saurin [9]
Sent: Thursday, November 30, 2017 10:57 AM
To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
[External_Sender] Re : file transfer Can you send me the agenda?
From: Patrick Purtscher <Patrick. Purtscher@nrc.gov>
Date: Wednesday, November 29, 2017 at 11:30 AM To: Saurin Majumdar <majumdar@anl.gov>
Subject:
file transfer I got the file, thanks.
I plan to be at ANL on Dec. 12 and 13. Will you be available to talk about the report?
Pat
ANALYSIS OF ALKALI-SILICA REACTION IN CONCRETE WITH MICROWAVE BACKSCATTERING AND IMPEDANCE SPECTROSCOPY ALEXANDER HEIFETZ (NE/ANL)
SASAN BAKHTIARI (NE/ANL)
PETER ZAPOL (MSD/ANL)
ANTHONY BENTIVEGNA (CTLGROUP) Argonne National Laboratory Civil and Materials Engineering, UIC 8 December 2017
OUTLINE Introduction to alkali-silica reaction (ASR) in concrete ASR accelerated tests Analysis of ASR with Microwave backscattering Impedance spectroscopy Brief review of delayed ettringite formation (DEF) 3-D printing of concrete Summary CME Seminar, UIC 12/8/2017 2
ALKALI-SILICA REACTION (ASR) IN CONCRETE CME Seminar, UIC 12/8/2017 3
ASR OVERVIEW ASR is common form of damage in aging concrete Concrete mixes containing alkaline Portland cement and silica-rich aggregates are chemically unstable Reaction leads to ASR gel and microcracks formation , and concrete expansion Large visible cracks may take decades to develop Example of ASR damage in concrete (FHWA, 2012)
Examples of problems caused by ASR Concrete cracking weakens structure resilience to extreme events (e.g. earthquake)
Concrete expansion causes tensioning of other structural elements (e.g. bridge steel cables)
Concrete platform expansion causes misalignment of bi-static radar station No remedy for ASR exists Distribution of some of the reported ASR cases in the USA since 1940. Each star represents a Mitigation may consist of confinement reported case of ASR. (FHWA, 2003)
GEM Seminar, UIC 12/8/2017 4
RECENT INTEREST IN ASR Concrete degradation is a challenge to nuclear energy sustainability Nuclear energy brief facts Fleet of about 100 commercial light water reactors (LWR) in US Provide about 20% of energy in US Seabrook Station NPP, Seabrook, NH (NRC Digital Archives)
LWR average age is close to 40 years Expected to last additional 20-40 years Nuclear industry is highly regulated
- Nuclear Regulator Commission (NRG) issues 40-year licenses for reactor operation NRC confirmed ASR in Seabrook NPP in 2011 Mitigation plan for ASR damage is required for relicensing GEM Seminar, UIC 12/8/2017 5
INDUSTRY APPROACH TO ASR DAMAGE ASSESSMENT No reliable non-destructive tests exist Example:
Concrete cores from 60 year old bridge Undesirable 8ft depth 52ft depth for high-value structures GEM Seminar, UIC 12/8/2017 6
CONVENTIONAL APPROACH TO ASR ASSESSMENT Microscopy of polished thin sections
- Optical
- Scanning electron (SEM) with elemental analysis Pore solution elemental analysis
- Solution extracted with pore press
- Elemental analysis with ICP/MS Length expansion is the only reliable NOE indicator
- Not quantitative Length expansion measu rement at CTLGroup No reliable quantitative NOE signatures have been found
- Recent R&D focused on linear and non-linear UT CME Seminar, UIC 12/28/2017 7
PROJECT GOALS Discover new ASR signatures Analyze data obtained from macroscopic nondestructive measurements New signatures correlate with standard length expansion ASR indicator Expected outcome Obtain quantitative information about ASR from nondestructive measurements May lead to development of new in-situ QNDE methods GEM Seminar, UIC 12/8/2017 8
APPROACH Study properties of ASA-affected concrete specimens using Microwave Backscattering Impedance Spectroscopy Thermal tomography Impedance spectroscopy at ANL Validate with a set of accelerated ASR I
specimens Year-long study of ASTM C1293 small *..*...*..*. : *+* :- .
concrete prisms i*-*------ ---~: .: .:-
Microwave backscatter at ANL Year-long size scaling study with large reinforced concrete blocks made with ASTM C1293 concrete mixes GEM Seminar, UIC 12/8/2017 9
BRIEF COMPARISON TO PRIOR WORK Micro""aves Impedance Spectroscopy Prior studies of ASR in Prior studies of concrete small mortar samples material properties placed inside microwave characterization, but not waveguide (Missouri S&T, ASR (Northwestern &
GEM Seminar, UIC 12/8/2017 10
MATERIAL PREPARATION CME Seminar, UIC 12/8/2017 11
ASR IN CONCRETE PRISMS CTLGroup developed concrete Concrete Material or RA NR prism specimens according to Component Property (% vol) (% vol) or Property ASTM 1293 standard Portland pH= 13.1 13.S 9.4 Cement Two types of mixes Fly Ash (Class F) 4.8 Coarse Crushed 3/4-1/2 14 14 Reactive (RA) Aggregates limestone 14 14 1/2-3/8 Non-reactive (NR) 3/8-1/4 14 14 Fine Quartz, Reactive feldspar, < 3/8 25.2 24.2 Properties Aggergates chert, glassy Concrete prisms 3"x3"x11 .25" volcanic Both RA and NR contain small particles reactive aggregates and large Water 17.7 17.7 non-reactive aggregates Air Voids 1.5 2 ASR mitigated in NR by partially 7200 6300 substituting fly ash for Portland cement GEM Seminar, UIC 12/8/2017 12
ASR DEVELOPMENT AND MONITORING Specimens were kept at CTL in environmental humidity chamber
- 38C and 95% RH Specimens were taken out of chamber at specified intervals and transferred to ANL
- 28, 56,120, 183 and 365 days
- Removal .from chamber arrests ASR progression Monitoring at CTL
- Length expansion and mass change measurements
- Petrography of select specimens ASR specimens stored over water in CTL
- Pore solution extraction GEM Seminar, UIC 12/8/2017 13
PORE SOLUTION ANALYSIS Specimens are crushed Pore solution extracted in high pressure device (up to 200,000 psi) and analyzed using ICP/MS pH Si Ca 13.5 I 600 l - . *-
150 13 . .... .
1/
400 h
_, _, 100 i.12.: tin 200 E
M E so 11.5 R2* :
- o.-91i6*.
- 0
-200 9 I 8 8 100 200 300 0
- 0 100 200 300 0 100 200 300 days days days Na K s 15000 30000 6000 I
_, 10000 M
E 5000 o I 0 100 200 300
_, 20000 M
E 10000 0
\.
- J
~200: 1 4000 \..:
0
=* 100 200 300 0 100 200 300 days days days GEM Sem inar, UIC 12/8/2017 14
PETROGRAPHY ANALYSIS 780µm High resolution optical microscopy of grinded 20µm thick concrete sections Analyzed 1st and 12th month specimens Damage Type Month Month ASR gel partially to completely Many Many Several Several filing air voids ASR gel partially Example of 12th month specimen imaged with plane to completely Several Several None Few polarized light. Blue arrows designate residual filing Portland cement grains. Microcracks (red arrows) microcracks extend from a reacted volcanic glass fine aggregate Microcracks particle (red encirclement) into the paste and nto extending from Some Many None Very another reacted volcanic glass particle (blue within RFA and few encirclement). ASR gel lines an air void. Ettringite is around CA observed lining another air void (purple arrow).
ORI 323 662 15 39 CME Sem inar, UIC 12/8/2017 15
ACOUSTIC MICROSCOPY Examples of Sonoscan acoustic microscopy at UIC (A. Chudovsky's group)
CME Sem inar, UIC 12/8/2017 16
CONCRETE PRISM CONDITION MONITORING Length expansion and mass increase measurements ASTM threshold for ASR confirmation is 0.04°/o length expansion Length expansion in RA and NR specimens Mass increase in RA and NR specimens
-e- NR -e- NR 0 .2 Q) 0)
C
~ 0.8
~ 0.15 C ro u .i::.
u
.c c, ~ 0.6 C ro Q)
-l 0.1 ~
Q) Q)
- 0) 0)
~ ~ 0.4 Q) Q)
~ ~
0 .05 0.2 50 100 150 200 250 300 350 400 50 100 150 200 250 300 350 400 Age (days) Age (days)
CME Seminar, UIC 12/8/2017 17
NORMALIZED AND OVERLAID LENGTH AND MASS EXPANSIONS Reactive specimens Reaction stops after 180 days 0.9 ~ Length Expansion
~ Mass Absorption 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0 l_______.________._____,____------'----__.___________.______._______,
0 50 100 150 200 250 300 350 400 Age (days)
CME Sem inar, UIC 12/8/2017 18
COMPUTER SIMULATIONS OF ASR DAMAGE Reactive Axial Length Expansion 0.300 Calculated ASR 0.250 0.200 Modeling damage in concrete ~0.150
".;; 0.100
- Series2 ASR strain using Microplane 0.050 *
- Simulation model (Caner-Bazant 0.000
-0.050 0 100 200 300 400 500 2013) time (days)
Predict most cracks to develop with normal Predicted cracking pattern visualized orientation to the with Abaqus largest dimension of the sample.
GEM Sem inar, UIC 12/8/2017 19
ASR ANALYSIS Focus on ASR at material surface Surface consists of a layer of cement paste and sand No coarse aggregates ASR gel appears on the surface because of either Gel migration ASR in the surface layer CME Seminar, UIC 12/8/2017 20
MICROWAVE BACKSCATTERING (MBS)
CME Seminar, UIC 12/8/2017 21
RATIONALE FOR MBS Microwaves are very sensitive to water Higher ASR gel content can lead to more water absorption Substance Water 55 Al ka la i-silica glass 5.50 6.4% Na 2O, 6.4% K2O, 87 .2%
SiO 2 Coarse Aggregate 6 Cement (Portland) 4 Sand (fine aggregate) 2.3 Values taken from Von Hippel's reference CME Sem inar 4/25/2016 22
MBS IN TIME DOMAIN Measured microwave backscattering as S 11 network parameter using Keysight PNA Convert frequency-swept PNA signal into time-domain pulse with on-board **
i * * . *. *. *. * . *.*.
FFT l * * * * * *
- MBS measurement setup at ANL X-band antenna (8.2GHz to 12.4GHz) slides along concrete prism Measured S 11 values averaged over spatial positions Calculate £ (real part) from front surface reflection (r=S 11 )
CME Seminar, UIC 12/8/2017 23
. VISUALIZATION TD visualization of microwave pulse propagation and reflection from concrete slab time = 1 ns time= 1 ns time = 3 ns 2 0.1 0.5 0.05 N N w 0 w"' 0 w O*
-0.5 *1 -0.05
- 1 0.4
' -2 *0.1 0.4 0 0.2 0.6 0.8 0 0.2 0.4 0.6 08 0 0.2 0.6 0.8
-3 *4 X 10 X 10-3 x 10 4 4 4 2 . 2 I
I >- 0 ,, I >- 0 r' 0 I II I
- 2 *2 *2
.4 .4 .4 0 0.2 0.4 0.6 0.8 0 0.4 0.6 0.8 0 0.2 0.4 0.6 0.8 x (meters) x (meters) x (meters)
Incident pulse in air Reflection from front edge Reflection from back edge
. Reflected E-field
- 0.8 CME Sem inar, UIC
- 1" ' - - ' - - - - - - ' - - - - - - ' - - - - ' - - - - - - - - ' - - ' - - ---'
0 2 4 6 8 10 12 12/8/2017 24 l(ns)
MBS IN TIME DOMAIN Backscattered signal has two peaks corresponding to front and back surface reflections Front surface , 1 Back surface reflection :I : reflection I
I I I I I I Average bac*cattered S in time 4omain Calculate E (real part) from 11 0.5 front surface reflection r 0.4 0.3 Ji-1 &=(l+r)
(./)
~
2 0.2 r=
Ji+ 1 ~ 1- r 0.1 0.5 1 1.5 2 2.5 3 3.5 4 time (ns)
CME Seminar, UIC 12/8/2017 25
VALIDATION WITH STANDARD MATERIALS Calculated epsilon from microwave surface backscattering compared to values in Von Hippel's reference Material Measured/ Tabulated Error Calculated (%)
Plexiglass 2.63 2.59 1.5 Silicone 2.86 3 4.6 Rubber Alumina- 5.32 4.95 7.4 Silicate Ceramic CME Seminar, UIC 12/8/2017 26
MAXWELL GARNETT (MG)
MODEL FOR DATA INVERSION Effective medium dielectric constant for cement with water / known Ew = dielectric permittivity of water Ee = dielectric permittivity of cement Water volume fraction can be calculated as f w== &w+ 2&c &eff - &c cw- cc C e.ff + 2&c CME Seminar, UIC 12/8/2017 27
DEHYDRATED SPECIMENS Dehydrate all specimens via oven drying until steady-state mass is reached Measure microwave backscattering and calculate epsilon Assume this to be Ee 3.9 3.8 NR 3.85 3.75 a::
z 3.8 3.7 3.75 3.65 3.7 ~~-~-~~-~-~~-~ 3.6 ~~-~-~~-~-~~-~
0 50 100 150 200 250 300 350 400 0 50 100 150 200 250 300 350 400 Age(days) Age(days)
CME Sem inar, UIC 12/8/2017 28
HYDRATED SPECIMENS Hydrate all specimens in water bucket until steady-state mass is reached Measure microwave backscattering and calculate epsilon Assume this to be Eett RA 5.9 7 6 .8 5.8 6 .6 5.7 RA NR 6.4 5.6 6.2
< a::
a::
\i) z
\I) 5.5 6 5.8 5.4 5.6 5.3 5.4 5.2 5.2 0 50 100 150 200 250 300 350 400 0 50 100 1 50 200 250 300 350 400 Age(days) Age(days)
CME Sem inar, UIC 12/8/2017 29
ESTIMATED WATER VOLUME FRACTION FROM MG Water volume fraction for both reactive and non-reactive specimens have linear increase trends Could be due to a combination of processes unrelated to ASR 0.18 0.28 0.17 RA 0.26 NR 0.16 0.24 0.15 0.22
~ ~
0.14 0.2 0.13 0.18 0.12 0.16 0.11 0.14 0 50 100 150 200 250 300 350 400 0 50 100 150 200 250 300 350 400 Age(days) Age(days)
CME Sem inar, UIC 12/8/2017 30
ANALYSIS OF REACTIVE SPECIMEN DATA ASR stops after 180 days Assume linear increase between 180 and 365 days is unrelated toASR Find a linear fit to this segment and subtract linear fit from the curve 0.18 0.17 0.025 0.16 0.02 0.15 Iii Iii 0.14
~ 0.015 0.01 0.13 0.005 0.12 With linear trend Linear trend subtracted 0.11 '---------'------'-----'----'---------'--___.__ ___,_____, 0 ._______.____,__----'-----'----'---------'--___.__ ___,_____,
0 50 100 150 200 250 300 350 400 0 50 100 150 200 250 300 350 400 Age(days) Age(days)
CME Sem inar, UIC 12/8/2017 31
NONLINEAR RESIDUAL Assume residual is related to ASR gel volume fraction Numbers agree with the estimates from petrography Validate with length expansion data
--e-- Normalized fge1 0.9
--e-- Normalized ~I 0.025 0.8
(/) 0. 7 0.02 Q)
- 0
-~ 0.6 ro li; >
1 0.015
- "g 0.5 roE
,._ 0.4 0.01 0 2 0.3 0.2 0.005 Normalized overlaid curves 0.1 0 '-------f' l - - ' - - - - - - ' - - - - - - ' - - - - ' - - - - - - - - ' - - - - - - ' - - - - - - - ' - - - - - ' 0 '-------f' l - - ' - - - - - - ' - - - - - - ' - - - - ' - - - - - - - - ' - - - - - - ' - - - - - - - ' - - - - - '
0 50 100 150 200 250 300 350 400 0 50 100 150 200 250 300 350 400 Age(days) Age(days)
CME Sem inar, UIC 12/8/2017 32
ELECTROCHEMICAL IMPEDANCE SPECTROSCOPY (EIS)
CME Seminar, UIC 12/8/2017 33
RATIONALE FOR EIS Electrical conduction occurs through connected network of pore solution Gel diffusion into pores and microcracks could disrupt network connectivity CME Seminar, UIC 12/8/2017 34
EIS OF CONCRETE One-sided electrical property measurement of concrete with Solartron 2-point probe geometry using flexible carbon black electrodes Uniform electrical coupling to rough concrete surface EIS measurement setup at ANL Increase repeatability of measurements by averaging over 2"x2" electrode area Penetration depth Electrodes placed at 5" distance center-to-center Computer simulations of uniform dielectric indicate 3" penetration depth Preliminary COMSOL simulation of IS CME Seminar, UIC 12/8/2017 35
BRIEF REVIEW OF EIS Measurement of complex valued impedance Z(co) == R(co)- j / coC(co)
In this study 1V AC potential difference Frequency sweep from 1Orn Hz to 150KHz Different ways to present the data IZI and phase(Z) a functions of w ZR and Z1 as functions of w Z vs. ZR (polar or Nyquist plot) 1 CME Seminar, UIC 12/8/2017 36
EIS OF HYDRATED CONCRETE PRISMS All RA and NR prism specimens were hydrated to equalize initial imbibed water levels Bulk resistance (inflection point, where 2 0 = ZR and 2 1 = 0) as invariant in measurements Independent of electrode type (compared carbon black and copper foil)
Independent of translation of electrodes along prism when relative distance is fixed Polar Plot Polar Plot
-10000 -10000
-+- 28 -+- 28
-9000 -+- 56 ASR maturit y -9000 -+- 56 ASR maturit y
~ 120 ~ 120
-8000 -+- 183 -8000 -+- 183
-+- 365 -+- 365
-7000 -7000 Reactive Non-reactive
-6000 -6000 C:
-5000 C:
-5000 N- N
-4000 -4000
-3000 -3000
-2000 -2000
-1000 -1000 8000 10000 12000 14000 8000 10000 12000 14000 ZR(n) ZR(D)
CME Seminar, UIC 12/8/2017 37
EIS DATA ANALYSIS 2 0 increases for both reactive and non-reactive specimens with ASR maturity Ignore the data point at 365 days RA NR 9 42 40 8.5 38 8
36
,...._ 7.5 34 C:
6 2 0
6 32 0
N 7 N 30 6.5 28 26 6
24 5.5 22 0 50 100 150 200 250 300 350 400 0 50 100 150 200 250 300 350 400 Age(days) Age(days)
CME Sem inar, UIC 12/8/2017 38
EIS DATA ANALYSIS Correlation with length expansion RA 6.5 6.4 0.9 6.3 0.8 6.2 (/) 0.7
-e- zo Q) -e- Length expansion
- 0 6.1 -~ 0.6
<1l 2 >
.¥.
0 6 al 0.5 N ~
<1l 5.9 E 0.4 0
2 5.8 0.3 5.7 0.2 5.6 0.1 Normalized overlaid curves 5.5 0 20 40 60 80 100 120 140 160 180 200 20 40 60 80 100 120 140 160 180 200 Age(days) Age (days)
CME Sem inar, UIC 12/8/201 7 39
CONSIDER DIFFERENT REACTION CME Seminar, UIC 12/8/2017 40
DEF SPECIMENS Delayed ettringite formation DEF mortar (DEF) reaction bar specimen at ANL Occurs because of improper curing of cement at high temperature and late formation of ettri ng ite microscopic crystals X 10 4 Nyquist Diagram
-14 ~ - - - - - - - .- .~
Causes long term expansion ,,.
DEF-A-RA DEF-8-NR cracking of concrete -12
-10 Preliminary analysis of DEF t-:
and age-matched control ~--
J*** :.~
mortar bar specimens '"t*
\;,~i>**
(1 "x1"x12") -2 t 0 .
0 0.5 1.5 2 2.5 3 3.5 4 4.5 Real(!'l) X 105 IS response of DEF (red ) and control (blue) mortar bar specimens CME Seminar, UIC 12/8/2017 41
3-D PRINTING OF CONCRETE CME Seminar, UIC 12/8/2017 42
3-D PRINTED CONCRETE STRUCTURES Emerging approach to build concrete structures without molding formwork 3-D concrete printer at CTL
-=--==.;;.~l. .:~ -..
CONCRETE 30 PRINTER CME Sem inar, UIC 12/8/2017 43
ADVANTAGES AND LIMITATIONS Advantages In-situ on-demand construction Construction in hazardous environment High nuclear radiation zone Under water Current technology limitations Requires manual feed of concrete mix Feedline clogging limits aggregate size Mortar is produced instead of high strength concrete No established NOE methods or quality control CME Seminar, UIC 12/8/2017 44
EXAMPLES OF PRINTED STRUCTURES Dome Tower Bricks Specimens brought to Argonne CME Seminar, UIC 12/8/2017 45
OBJECTIVE Develop capability to estimate curing progress and compressive strength in-situ using EIS Flexible electrodes confirm to rough surface of 3-D printed structure EIS provides information on free water content CME Seminar, UIC 12/8/2017 46
MONITORING OF 3-D PRINTED CONCRETE CURING A set of 3-D printed cylinders is divided into two batches Curing of 3-D printed concrete cylinders concurrently monitored Destructively (mechanical strength test) at CTLGroup 3-D printed cylinders at CTLGroup Nondestructively (impedance spectroscopy) at Argonne Flexible electrodes couple to rough surfaces CME Seminar, UIC 12/8/2017 47
MONITORING OF 3-D PRINTED CONCRETE CURING Destructive Test Nondestructive Test Compressive Strength of Curing Concrete Impedance of Curing 3-D Printed Concrete 1.40E+04 3.50E+03 1.20E+04 3.00E+03
~ 1.00E+04 2.50E+03 0.
V)
.s:::.
+-'
00 E
..c
~ 8.00E+03 2, 2.00E+03
+-' Q)
Vl u Q) C
> ro
- v; Vl 6.00E+03 ~ 1.50E+03
...0.
QJ a.
E E
8 4.00E+03 1.00E+03 2.00E+03 5.00E+02 0.00E+00 0.00E+00 0 5 10 15 20 25 30 0 5 10 15 20 25 30 Days Days CME Sem inar, UIC 12/8/2017 48
MONITORING OF 3-D PRINTED CONCRETE CURING Developed calibration curve Calibration Curve l.40E+04 l.20E+04 "vi
..9: l.00E+04
..c 00 C
~ 8.00E+03 V)
QI
-~ 6.00E+03 V,
...a.
QI E 4.00E+03 0
u 2.00E+03 0.00E+00 0.00E+00 5.00E+02 l.00E+03 l.S0E+03 2.00E+03 2.S0E+03 3.00E+03 3.S0E+03 Resistance (Ohms)
CME Sem inar, UIC 12/8/2017 49
PUBLICATIONS AND PRESENTATIONS A. Heifetz, S. Bakhtiari, J. Lu, I. Aronson, V. Vinokour, and A.F Bentivegna, "Development of non-destructive methods for detection of alkali-silica reaction in concrete structures," presented at the 43 rd Annual Review of Progress in Quantitative Nondestructive Evaluation, Georgia Tech, Atlanta, GA, July 2016.
A. Heifetz, S. Bakhtiari , J. Lu, I.S. Aranson , V.M. Vinokur, A.F. Bentivegna, "Development of microwave and impedance spectroscopy methods for in-situ nondestructive evaluation of alkali-silica reaction in concrete," AIP Conference Proceedings 1806(1 ), 12003 (2017).
A. Heifetz, S. Bakhtiari, J. Lu, A. Bentivegna, "Nondestructive evaluation of alkali-silica reaction in high-strength concrete for aging structure sustainability," Transactions of American Nuclear Society 116, 453-456 (2017).
A. Heifetz, S. Bakhtiari , J. Lu, and A. Bentivegna, "Nondestructive evaluation of alkali silica reaction in high-strength concrete for aging structures sustainability," presented at the American Nuclear Society Annual Meeting (ANS 2017), San Francisco, CA, June 2017.
A. Heifetz, S. Bakhtiari, J. Lu, E.R. Koehl, A.F. Bentivegna, C. Arboleda, "Development of electrochemical and electrorhysical methods for nondestructive evaluation of chemo-mechanical damage in concrete," presented at the 44t Annual Review of Progress in Quantitative Nondestructive Evaluation, Utah State University, Provo, UT, July 2017.
S. Bakhtiari, H.T. Chien, A. Heifetz, T.W. Elmer, "Nondestructive testing research and development efforts at Argonne National Laboratory -An overview," submitted to Materials Evaluation (2017).
A. Heifetz, P. Zapel, S. Bakhtiari "Application of microwave backscattering and impedance spectroscopy to nondestructive evaluation of alkali-silica reaction in concrete," manuscript in preparation for Journal of Applied Physics (2017).
CME Seminar, UIC 12/8/2017 50
SUMMARY
Presented recent results of ASR analysis at Argonne Analysis based on accelerated ASTM 1293 small prisms Signatures found in microwave backscattering and impedance spectroscopy correlate with length expansion Next steps Analyze data from cores taken from large blocks Develop quantitative models of observations CME Seminar, UIC 12/8/2017 51
ACKNOWLEDGEMENT Special thanks to all contributors Argonne Sasan Bakhtiari, Peter Zapol, Igor Aronson, Dick Koehl, Mitch Farmer CTLGroup Anthony Bentivegna, Catalina Arboleda, Greg Naweem Other collaborators Sasha Chudnovsky (UIC), Zdenek Bazant (Northwestern)
Interns and summer students Yangquing Liu (UIC), Peter Bevington (UChicago), Juan Lu (IIT)
Project sponsored by Argonne Nuclear Science and Technology LORD CME Seminar, UIC 12/8/2017 52
Note to requester:
Attachment is immediately fo llowing.
From: Hiser, Matthew Sent: Mon, 9 Ju l 2018 15:33:29 +0000 To: Koshy, Thomas;Murdock, Darrell;Sircar, Madhumita;Pires, Jose Cc: Pu rtscher, Patrick;Aud rain, Margaret;Tregon ing, Robert
Subject:
FW: Irrad iat ed materi als from NRU reactor Attachments: Reactor Artefacts Project (ReAP) February 8, 20 18.pdf
Dear Mita and Tom,
I wanted to share some information I received regarding irradiated materials / harvesting from the NRU reactor in Canada. The slides on concrete and electrical components are #30-39.
Please let me know if there 's anything of interest to your areas in what they show on those slides.
Thanks!
Matt
Reactor Artefacts Project (ReAP)
February 8, 2018
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED/ ILLIMITE Introduction
- National Research Universal (NRU) went critical in 1957.
- The original vessel was replaced in 1974.
- NRU missions:
- Supply industrial and medical radioisotopes
- Enable fuel and materials R&D for power reactor development
- Sophisticated material characterization through the neutron beam line.
- In 2018 March, NRU will be shutdown and there is a desire to exploit this asset through artefact harvesting.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Introduction
- The NRU Harvest Project was developed as part of the Federal Nuclear Science & Technology (FNST) program managed by AECL.
- An inventory of materials with operating conditions has been prepared.
- These artefacts, which would otherwise become waste, present a research opportunity to be used to solve industry issues.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Purpose of the Meeting
- Awareness of project and framework.
- Presentation of the CNL inventory of artefacts.
- Obtain input from industry.
- Discussion of sample projects.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE
- Collaborative research project.
- Participation in three ways:
o Participants contribute financially o In-kind contribution o Combination of financial and in-kind contributions
- Contributors/collaborators can participate in various aspects of the research project.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE
- Collaboration with industry will help to grow the project.
- Scope will be developed with input from participants.
- CNL will perform research, co-ordinate collaborative efforts, manage administrative details and organize a joint steering committee to oversee the project.
- Results will be shared with project participants and with the Canadian Federal Family.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Areas of Interest Aging and material degradation issues in the following areas will be assessed:
- Effects of irradiation damage on reactor internals
- Concrete Aging and Degradation o ASR o Structural assessment of irradiated concrete
- Cable Aging and Degradation o Cable vulnerability studies based on temperature and irradiation
- Fuel Assessment (not discussed at this time)
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Canadian Nuclear Laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED/ ILLIMITE Overview
- Artefacts Inventory (in- and out-of-core)
- Opportunities for Research using Artefacts to Resolve Issues in Nuclear Industry
- Timelines for Extraction of Artefacts
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Artefacts for Research & Investigation Materials and components have been irradiated in NRU since 1957 (365k hrs),
some were irradiated since 1974 vessel replacement (270k hrs) over a wide range of temperature {35 °C to 310 °C), flux and neutron spectrum. NRU is heavy water moderated.
The NRU inventory includes: DECK PLATE
- Structural materials steels, lnconels, zirconium, SHELDING BLOCKS - i - + : -.;;&.
aluminum, concrete; FUEL RODS THERMAL SHIELDS
- a thermal graphite column; NEUTRON BEAM HOLES----.:-7H-c--~::1i ALUMINUM TANK BOTTOM RING
- flux detectors; ARM HEAVY WATER THERMAL SHIELDS
- equipment (including pumps); LED HEAVY WATER HEAT EXCHANGER
- elastomers/seals; ,~ c:.m-~ ~
- electrical cables. PROCESS WATER Canadian Nuclear I Laboratoires Nucleaires Laboratories Canadiens UNRESTRICTED/ ILLIMITE NRU Structural Materials and Conditions Assembl Allo Irradiation conditions Loop pressure tubes Zr-2.5Nb Pressure Tubes - various manufacturing routes Up to 8 yrs irradiation, 250-300°(
Up to 6x1025 n/m 2 (E>lMeV)
Loop liner tubes - high strength Zr-2.5Nb (3 available) Up to 9.5 yrs irradiation, 50°C secondary containment Up to 7.3x1025 n/m2 (E>lMeV)
Control rod shroud tube Zr-2 annealed tube: 4-11/16" OD x 0.046" wall Up to 44 yrs, 35 °C.
X-750 spring: nominally 3-7/16" ID and 3/16" wire Zr-2: up to 2.9 x1027 n/m2 (E<0.625 eV)
ASTM B637 N07750 Type 1, 2 or 3 X-750: ~4x10 26 n/m2 (E<0.625 eV), 10 dpa, 5000 appm He 304 SS rings riveted at either end of the assembly 304: 2x1026 n/m 2 (E<0.625 eV), 2 dpa, 900 appm He Slowdown Test Facility pressure 347 stainless tube 8 yrs irradiation, tube 4.25" OD x 0.313" wall thickness temp not constant, varied from 40 to 300°C, 10.5 MPa 6.6x10 26 n/m 2 (E<0.625 eV), 2x1024 n/m 2 (E>l MeV) 4 dpa damage, 1600 appm Helium Lower header cups 304 stainless steel (43 available) Up to 44 yrs irradiation, 35 °C top tapered part scales to ~7/16" or 11 mm thick 4.1x1026 n/m 2 (E<0.625 eV) x ~1.611 or 40 mm long 2 dpa, 800 appm He Vessel baffle plate 304 or 347 stainless steel plate 1" x 3.75" x 2 ft long 44 yrs irradiation, 35°C 0.4 dpa, 135 appm He Vessel bolts lnconel X-750 44 yrs irradiation, 35°C Less than 0.4 dpa and 135 appm He Loop fuel carriage tie rod lnconel X-750, AMS-5667 life limit is 1000 days 1/2" bar (10 available) 250 tO 300°(
Iodine rods, Vessel, Re-entrant can Aluminum Alloys 44 yrs, 35 to 55 °C Al -5052 Up to 2.3 x10 27 n/m2 (E<0.625 eV)
Alcan 57S 0.25 dpa, 4.5 Si atom%
Thermal column Graphite 44 yrs, 15 to 230 °C Up to 7.lx1026 n/m2 (E<0.625 eV)
Biological Shield/lnterspace Heavy concrete 60 yrs, 27 to 49 °C concrete Up to 2.5x1021 n/m2 (E<0.625 eV) 3.6x1019 n/m2 (E> lMeV)
/' . - '~ ~>\
3/4~ . "'
Research Oppprtunities .Ll~In,g Artefacts:
Long-term Operation off AN~U Calandr.ia ve?\~\ \
/' J I .
- I ISSUE: The CAN DU calandria vessel and its components are not replaced during refurbishment, remain fit-for-service for periods up to 100 EFPY - identified in Roadmap for the Long-Term Operation of CANDU Reactor Components (ref. OP-17-7006).
Currently part of FNST Project.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED/ ILLIMITE
/' . - ' ~ ~>\
3/4~ . "'
Research Oppprtunities .Ll~In,g Artefacts:
Long-term Operation off AN~U Calandr.ia ve?\~\ \
/' J I .
- I lndustr Issue Artefact Material Work Seo e Pro osed Supporting operation of Materials of interest are 304L Radiation damage CANDU calandria vessels to and 308L weld metal characterization 100 year life Available from NRU is 304 Mechanical property tests irradiated at the appropriate (low) temperature, to an Stress corrosion cracking tests almost bounding DPA and excess He Investigating repair technology Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED/ ILLIMITE Research Opportunities using Artefacts:
Long-term Operation of CANDU Calandria Vessels 304 SS materials irradiated in NRU up to 2 dpa, 820-870 appm helium 100 ear Calandr"a essel C6 tubesheet mid-lattice: - CANDU Tubesheet 3 dpa, 330 appm He - CAN DU Sub shell (60 yr: 1.7 dpa, 145 appm He) - CANDU Annular p lat e C6 tubesheet at CT: 3.7 dpa, 45 appm He - CANDU Main shell (60 yr: 2.2 dpa, 18 appm He) 1.E+o6 - - + - - - ~ - - ~ - - - -~
- - - NRU artefact 1E-08 0 .00001 0 .01 10 Neutron Energy MeV NRU Artefact
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED/ ILLIMITE OPPORTUNITY: Develop dosimetry methods to determine the neutron dose on ex-service materials. Currently part of FNST project.
Industry Issue Artefact Material Work Scope Proposed Develop dosimetry methods to Various components from NRU Establish procedures for determine the neutron dose on to cover a wide range of sub-sampling harvested ex-service materials fluences material and measurement of the required isotopic ratios Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED/ ILLIMITE
- Isotopic ratio measurements of activation products are known to be an accurate approach to determining the dose and are used in international safeguards programs to establish reactor operating history.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED/ ILLIMITE NRU Loop Pressure Tubes 3QQO(
Hanger Plate 3QQO(
L. 0 Pin - _J Q Pout Hanger Rod - -~ ~ I~ E- 2 Q 0 -17 Upper Flux Suppressor - ~ 0 1 Junction_----;-)of_
Centring Ring Reactor Fuel Core Bundle Lower Flux Suppressor Tie Rod U-2 loop 21s c 0
Light water cooled.
Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED/ ILLIMITE NRU Zr Alloy Loop Pressure Tubes Pressure Tube Material Date of Installation Temp °C Press Peak flux Time in Identification x10 17 NRU loops (MPa)
Number n/m2/s EFPH E> lMeV 50206 27% cold drawn Zr-2.SNb 1975 to 1984 275-300 9-10 2.6 53,400 Pickering A tube 1984 to 1988 250-275 10-11 15,400 50207 24% pilger Zr-2.5Nb 1976-1984 275-300 9-10 ~2.s 22,000 50209 As extruded 2.8% CW Excel 1982 to 1985 250-275 10-11 ~2.5 13,034 1985 to 1991 275-300 9-10 12,060 50210 Annealed Excel 1984 to 1991 275-300 9-10 ~2.s 29,426 50213 25% pilger Zr-2.5Nb 1988 to 1991 250-275 10-11 ~2.s 14,232 1994 to 1996 275-300 9-10 15,000 50215 35-45% CW Zr-2.5Nb (TG3Rl) 1994 to 1998 250-275 10-11 ~2.5 22,000 50216 20-30% CW Zr-2.5Nb 1994 to present 275-300 9-10 ~2.s 59,600 Quadmelt, beta quench at log stage.
50217 35-45% CW Zr-2.SNb (TG3Rl) 1997 to 2000 275-300 9-10 ~2.5 15,000 50218 20-30% CW Zr-2.5Nb 1998 to present 250-275 10-11 ~2.5 38,200 Quadmelt, beta quench at log stage 50219 20-30% CW Zr-2.5Nb 2000 to present 275-300 9-10 ~2.5 25,400 (loop shutdown in Qinshan tube, quenched hollow billets
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2009)
I Canadian Nudear laboratoires Nudeaires
' I~ Laboratorie-s Canadie-ns UNRESTRICTED/ ILLIMITE OPPORTUNITY: Obtain the irradiated properties from pressure tubes with various manufacture routes.
Industry Issue Artefact Material Work Scope Proposed Effect of manufacture route NRU loop pressure tubes - Microstructure on pressure tube properties wide range of fluence characterization Creep, fracture toughness, hydrogen ingress, corrosion Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED/ ILLIMITE
- Range of manufacture routes: regular CAN DU PTs (double and quad melt), Qinshan tubes (electrolytic powder), TG3R1 (fabrication tailored for low elongation) and pilgered tubes.
- Transition from high to low to no flux.
- Irradiation "top-up" in a fast flux reactor to get higher fluence properties.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Effect of Irradiation Damage on Pressure Tubes:
Assessment of Assembly 50206 50206 l.2E-07 I E+ l8 290 140 I.0E-07 IE+17 e01 270 120 ...
0 Ill 0 ..J
~ 'E 1,
8.0E-08 IE+l6 z 250 100 C:
~ [ ::c
> 0T'"
- s
-=
C: ::,,
6.0E-08 IE+15 C:
Ill Ill 230 80
"'l!! :,
3 GI ><
I 4.0E-08
- strain rale IE+ l4
-Jt- -e... 210 60 u:::
~
-=
---nux C i= ::c X Hardness ...0 I!! 190 0 Line Breadlh 40 2.0E-08 IE+ IJ
~
GI u
... Flux z
-lE-Rate 0.0E+oo IE+l2
> 170 -+- Intercept 20 3.5 4.0 4.5 s.o 5.5 6.0 6.5 7.0 75 8.0 8.5 150 0 Axial Elevation m 4.3 4.4 4.5 4.6 4.7 4.8 Distance/ m Ref: Griffiths et al, J. of ASTM (2007)
Hardening is observed at very low doses, below the level at which dislocation loops form.
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' It' Canadian Nuclear laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Research Opportunities using Artefacts:
Effect of Microstructure Evolution ISSUE: In the body of a CAN DU pressure tube the flux effect on DHC is well characterized. At the ends of the pressure tubes the low flux effects are more difficult to predict.
Industry Issue Artefact Material Work Scope Proposed Develop understanding of NRU loop pressure tubes - Microstructure the effect of microstructure* wide range of flux and characterization evolution on DHC - low flux fluences DHC tests effects
- The NRU pressure tubes provide material over a wide range of flux and fluence to determine the effect of microstructure evolution on DHC.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE
-_*Research Opportunities ~ - .-...
using Artefacts:
IIJlpro"'ed ' ffi*l*CT Gap Measureme.nts~
*- - --- _r'
- - - - r -6 ~
* -- . - - ~-- . - - -
ISSUE: The PT/CT gap measurements towards the outlet end of the tube are known to be biased and recently attributed to variability in resistivity.
Industry Issue Artefact Material Work Scope Proposed Improved PT/CT gap NRU loop pressure tubes -wide NDE tests to examine PT measurements - critical for range of fluence resistivity over the full length leak before break of the fuel channel Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Research Opportunities using Artefacts:
~J_*
IQ1pr,oj ed Jl!<J,TGap Measurements-
~ - -
(--
- In absence of a technique to actually measure resistivity in-situ and perform the compensation, a better normalization scheme could be derived from a better understanding of the resistivity changes along the entire PT.
- Benefit PT/CT gap measurements including CIGAR/ANOE/BRIMS and AFCIS.
- Resistivity measurements can also be used to understand PT microstructure non-destructively.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Irradiation Effects on 347 Stainless Steel OPPORTUNITY: component with low dpa, high helium.
Loop tube: 4 dpa damage, 1600 appm Helium, operating temperature not constant ranged from 40 to 300°C, 10.SMPa, 6.6x1026 n/m 2 (E<0.625 eV), 2x1024 n/m 2 (E>l MeV)
Type 347 stainless steel is used for baffle bolts in PWR - exposed to primary water, high temperatures and irradiation. Issues include IASCC and fatigue.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Research Opportunities using Artefacts:
Effect of temperature and dose rate on helium bubble evolution in lnconel X-750 OPPORTUNITY: Effects of specimen size, temperature and dose rate to support models on irradiation effects on lnconel X-750 Industry Issue Artefact Material Work Scope Proposed Support for the end of life X-750 hanger bars Microstructure irradiation studies on lnconel characterization Control rod shroud tube spring X-750 Tensile testing, hardness Vessel bolt testing.
Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Research Opportunities using Artefacts:
Effect of temperature and dose rate on helium bubble evolution in lnconel X-750
- NRU material has sufficient volume to make full-size specimens to determining how specimen size effects irradiated mechanical properties.
- X-750 irradiated in different positions in NRU may provide mechanical property data irradiated at various temperatures and dose rates.
- Data can be used to validate models outside of temperature and dose range.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Temperature and Dose Rate Effects in lnconel X-750 t0 1 r -- - r - - - . . - - - - - , . . - - . - - . - - - . - - - - .
0 Ni P--<>
Ref: Judge et al JNM 457 (2015)
,o**300- - -* - - -500 400
-~- 600
- - -700 PEAK SWEWNG TEMPER~TURE C-Cl Larger bubbles and lower density (330°C),
Ref: Packan et al JNM 78 (1978)
Smaller bubbles and higher density {200°C)
High damage rates alter the temperature dependence of the development of m icrostructu ra I defects.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Comparison of Artefact X-750 Materials against Industry Materials l.0E+lS Exp Material : 200-330°(
~ l.0E+14 N
E u
1.0E+13
->=-
~ \
.c Ill
....cu l.0E+12 \
\
...cu
....I CANDU material : 200-330°(,
c.. l.0E+l l X
i!:
l.0E+lO
\
Vessel bolt: 35°C 1.0 E+09
\
l.0E+08 lE-09 0.0000001 0.00001 0.001 0.1 10 Neutron Energy MeV
- - - Tie Rod (NRU artefact) - * *Vessel Bolt (NRU Artefact)
-
- Experimental Material - CANDU Spacer Canadian Nudear Laboratories I Canadiens Laboratoires Nuct~aires OFFIC IAL USE ONLY/ A USAGE EXCLUS IF ISSUE: Concrete structures and components perform important safety functions (e.g., containment & shielding)- chronic, low dose neutron exposure on the integrity of the biological shield concrete will affect mechanical properties.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Concrete in NRU H'- o*
r Ul'flUNINTAL ltOLU
- Concrete cores from N PD .
GATl
- Opportunity to get ITUL lll(l!NAL IHllLQ IIGHT 0.0 l'tl'U TO
~-.--..- HIAT lXCHAN~ll!I concrete cores from G2, ANO ,UNl'I Douglas Pt, WRl and SHUTT(!! - - - -
-::::::=:,.--Hao l!t,LICTOI!
from waste canisters at
- ~ - - HIIVICI IHA'1 WL.
, - o,o 111,LIC:TOtl tltAl't41TI - 0ALANOfUA WALL ALUMINUM IHIILO tc.llC - t.LJ t Uf
~ *, Canadian Nudear I lab~toires Nudeaires
' I~ Laboratorie-s Canad,e-ns UNRESTRICTED/ ILLIMITE Irradiation Effects on Concrete and NRU Artefacts
- Critical levels indicated at 1x1019 to 1x1020 n/cm 2 E<0.1 MeV
[Hilsdorf curve]
- Potential for irradiation to affect microstructure of concrete (e.g, aggregate expansion, shrinkage of cement paste, cracking)
- Heavy concrete from NRU in service for 60 years at 27 to 49°C up to 2.Sx10 17 n/cm 2 (E<0.1 MeV)
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Irradiation Effects on Concrete and NRU Artefacts
- NRU Shield plugs reside in unused experimental hole ports which penetrate the Biological Shield to enable experimental neutron beam research equipment
- Relatively straightforward for removal.
- Some shield plugs are original , ports were not accessed during the lifetime of the reactor.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE Concrete Aging and Degradation
- Evaluating effects of Alkali Silica Reaction (ASR} on structural performance of concrete under design basis static and dynamic loads crn~~aolthe IWfPtt a~d past
- Causes expansion, cracking, loss of mechanical properties.
- ASR is a concern for susceptible aggregates.
- Question surrounding likelihood of occurrence.
Reactive Aggregate
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Cracking through Aggregate Canadian Nudear I laboratoires Nudeaires
' I~ Laboratorie-s Canadie-ns UNRESTRICTED/ ILLIMITE
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~ : - - ~ ----
Graphite Artefact from NRU
- Five graphite sections about 2.4 m x 2.4 m at the inner end to 3.2m x 3.2m at the outside end, total length of 3.7 m.
- In service for 44 yrs, 15 to 230 °C, up to 7.1x10 22 n/cm 2 (E<0.625 eV)
WATER COOLING PASSAGES EXPERIMENTAL HOLES
- n;;
- -::-1/4--+--- STAI NLESS STE£L REf'"LECTOR TAN)($
LEAO FACE PLATE THIN ALUMiHUM WITH SHE[T STEPPED L EAO PLUGS
_....,. HEAVY WATER VESSEL
( CALANOl'IIA )
COOLING LEAD SHUTTER AIR PASSAGES ALUMINUM WATER AEFLEC10A MAIN FLOOR STAI NLESS STEEL 80TTOM HEA0£1'1 SHIELD WATCR
~4------- ftECl:SS ,OR SHUTTER SPACE COOLING AIR P IPES !';-_,: CONCRETE SHIELD MASONITE UNRESTRICTED/ ILLIM ITE Flux Detectors in NRU Flux Detector Service Operation P18 beside U-2 replaced in 1996/1997 Helium atmosphere loop position 017 maintained E22 beside U-2 flux detector wires were replaced Helium atmosphere loop position E20 1998/1999, the rod was not replaced, maintained dates back to the 1974 L06 beside U-1 replaced in 1996/1997 Helium atmosphere loop position LOS maintained M23 beside M-23 has not been replaced, dates Not in operation since 1991 loop position L-24 back to 1974 Each insert contains twelve self-powered flux detectors six of which have platinum-clad lnconel emitters and six with vanadium emitters.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Instrument Control Cables from NRU Cable Jacket Radiation Type Voltage Installation Date Temperature Material Field 18 gauge, 26 600V rating, up to 120 mid 90s or after PEEK (tan) 20 to 300°C, A-41002-SP-5 Max 10 R/hr conductor VAC 2004-2008 20-65°C, 90°C MAX, forced 18 gauge, 24 Up to 130 VDC, Up to later 2012 until XLPO (black) area cooling, NRU-150901- Max 10 R/hr conductor 120 VAC 2016 SP-001, humidity 10-100%
Physics Core 2 conductor, Polyimide calculations twisted pair required.
W 51 in RM315 - 3 Physics Core 65°C MAX at Faces, Room PTFE Dielectric, Up to 600 VDC sets of cables calculations RG393 Coax Temperature 30°C Max for FEP Jacket (1500V rating) installed in mid to required.
other cables.
late 90s WSl in RM315 - 3 Physics Core 65°C MAX at Faces, Room LDPE Dielectric, sets of cables calculations RGll Coax Up to 600 VDC Temperature 30°C Max for PVC Jacket installed in mid to required.
other cables.
late 90s W51 in RM315 - 3 Physics Core 65°C MAX at Faces, Room PE Dielectric, PVC sets of cables calculations RG108 Twinax Up to 600 VDC Temperature 30°C Max for Jacket installed in mid to required.
other cables.
late 90s Max once a year HABIA HFI 140 -
20 gauge 600V swap, 5 year wire (-50°C/+120°C) Max 10 R/hr rated for 106 Gy replacement Max once a year HABIA HFI 140 -
22 gauge 600V swap, 5 year wire (-50°C/+120°C) Max 10 R/hr rated for 106 Gy replacement
ISSUE: aging of elastomers results from oxidation leading to degradation of their mechanical properties, induces a loss of dielectric strength and increased leakage current.
- variety of cable testing techniques to assess the condition of retrieved cables that were naturally aged in the reactor.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE
- compare results using of reference destructive techniques (tensile testing for example) and non-destructive or semi-destructive techniques (such as cable indentation, measurement of electrical dissipation factors, or differential scanning calorimetry)
- Compare expected damage versus observed damage based on residency time
- Assess the validity of accelerated aging performed in the laboratory to simulate natural aging at much lower temperatures and much lower dose rates.
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Canadian Nuclear Laboratories I Laboratoires Nucleaires Canadiens UNRESTRICTED / ILLIMITE
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~ : - - ~ ----
NRU Out-of-core Assemblies Estimated Operating Duration Assembly Material Temp °C Accumulated Dose In Years kRad U2 loop - Auxiliary Heliflow Cooler lnconel and 347 stainless 300 265 N/A steel MHWP Shafts 316 stainless steel 40 various (MHWP#l, 5 and 6:
185 more than 15 years)
Polymers for Fluid Sealing Various polymers Various various various (PEEK/PTFE/EPDM/Viton/ 20 to 300 Nitrile - Buna N)
Lower Service Space Piping Stainless steel (304/316) 40 typical 7173 Up to 60 Electrical/ Various 40 typical Upper service space: 759 Up to 60 Instrumentation Cabling Heat Exchanger Rooms:
846 Helium Freezer Driers - Finned Tubes 304 stainless steel -79 to 74 803 Up to 60 Copper in High Dose Rate Locations Copper -79 to 74 803 Up to 60 Tubes in Main Heat Exchangers 304 stainless steel so 846 Up to 60 Gibbsite Assessment Gibbsite Up to 121 NA Up to 60 Adjuster Rod Cabling Electrical wiring 40 274 53 Loop Flux Detector Cabling Electrical wiring N/A 759 44 Resistance Temperature Detector Wiring Electrical wiring 40 846 Up to 60 in Heat Exchanger Rooms Thermocouples in Biological Shield Instrument wiring Various N/A 60 MHWP Heat Exchanger Bellows Type 347 or 321 stainless 38-53 846 60 steel Fuel Rod Flask Donut - Shielding Lead, paraffin wax-boron heavy water 60000 60 carbide mixture cools to 30-50 Fuel Rod Flask Bellows Stainless Steel as per ASTM 30 to SO 30000 N/A A240 Type 321 or 347 MHWP Check Valves - Waukesha 88 Waukesha alloys 38 846 N/A Bushings UNRESTRICTED/ ILLIMITE
- -cl\*
...~ --~ -
Welds Between Different Alloys in NRU (out-of-core)
Weld location Materials Ul ends of Spool 129 (Fl-1 and Fl-2) 3" diameter Carbon steel {11.13 mm wall)/
304 stainless steel (7.62 mm wall)
Main loop piping between mixer #2 and Inlet to mixer#l Ul inlet and outlet of the Loop Cooler (LC-1 and 3" diameter lnconel (7.62 mm wall)/
LC-2) 347 or 321 stainless steel (7.62 mm wall)
Steam Generator Inlet and outlet 4" diameter 304 stainless steel (13.49 mm)/
carbon steel (13.49 mm)
Main Heliflow Cooler Inlet and outlet, tube side 3" diameter 304 stainless steel (reducer 3" to 2.5" SCH 80)/ lnconel 600 (7.62 mm)
Main Heliflow Cooler: MAWP 2000 psig, Design Temperature 640°F Auxiliary Heliflow cooler inlet and outlet 2" diameter 304 stainless steel (reducer 2" to 1" SCH 80)/lnconel 600 (1.5 mm)
Auxiliary Heliflow Cooler: MAWP 2000 psig, Design Temperature 640°F
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Canadian N udear Laboratorie-s I laboratoires Nudeaires Canadie-ns UNRESTRICTED/ ILLIM ITE Timelines for Extraction of Artefacts from NRU I
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Canadian Nudear Laboratoires Nudeaire NRU SAFE S HUTDOWN STATE SCHEDULE OVERVIEW This is an unofftc.ial overview schedule. 2018 Jan 29 It does not Include all actlvltles and Rev. 02 Laboratories Canadiens (UNOFFICIA L VERSION) Officlill Use Only may not line.up directly willl the Page tl2 a roved schedule.
Q4 Ql Q2 Q3 Q4 Ql Q2 Q$ Q4 : Ql Q2 Q$ Q4 Ql Ql Q3 Q4 Ql Q2 Q3 Q4 2016117 B17/II 2018119 2l1tlfJI 2020.21 JUl/l2 Planning Phase
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- Execution Phase '
Pftmanent Sate Shutdo"-TI
- I NRUt ~r I
- / Post OPeQbonal Clean-Out (POCO SID remaina,g systems st>ge 5)
Key dates:
- Shutdown on March 31, 2018
- De-fuel ~41 days after shutdown
- De-water ~sept 2018 Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED/ ILLIMITE JIB~
IL Timelines for Extraction of Artefacts from NRU Assembly Current Location Availability/Extraction Loop pressure tubes NRU Rod Bays Available now Zr-2.SNb 50216, 50218, 50219 in loops Removal after de-fuel, de-water.
Loop liner tubes NRU Rod Bays Available now Zr-2.SNb Control rod shroud tube In-core As early as FY19/20 Zr-2 annealed tube, X-750 spring, 304 SS rings Slowdown Test Facility pressure tube NRU Rod Bays Available now 347 stainless steel Lower header cups In-Core After de-fuel but before de-water.
304 stainless stee ~June 2018 Vessel baffle plate In-core Challenge but ideally after de-fuel, before de-water 304 or 347 stainless steel Vessel bolts In-core Extraction of a few bolts should be possible at any time following the reactor shutdown.
lnconel X-750 Loop fuel carriage tie rod NRU Rod Bays Available now lnconel X-750 Thermal column In-service ~sept 2019 Graphite Biological Shield/lnterspace concrete In-service M id 2019 for the shield plug, dependent on replacement component.
Heavy concrete Cables In-service End of 2018/early 2019 Discussion
- Are there any other irradiation damage or aging issues that were not discussed and should be considered for the artefact research project?
- Are there industry issues that can be resolved by performing research on these artefacts?
- Are there opportunities for collaboration?
- Should CNL store certain materials for later examination?
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE Follow-up
- COG specific o COG workpackage "Materials Studies of NRU Artefacts" o Follow up detailed technical meetings with working groups
- Outside of COG o Follow up on interest provided in the feedback forms
- Based on feedback on high-interest components, CNL will refine flux and fluence calculations; will develop extraction plans for in-core materials; and will identify sites for storage of artefacts.
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' It' Canadian Nuclear laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE
Contact:
Gina Strati : 613-584-3311 ext. 46309 gina.strati@cnl.ca Lori Walters: 613-584-3311 ext. 46057 lori.walters@cnl.ca
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Canadian Nuclear Laboratories I Canadiens Laboratoires Nucleaires UNRESTRICTED / ILLIMITE