ML21071A171
| ML21071A171 | |
| Person / Time | |
|---|---|
| Issue date: | 03/04/2021 |
| From: | NRC/OCIO |
| To: | |
| Shared Package | |
| ML21071A165 | List: |
| References | |
| NRC-2018-000831 | |
| Download: ML21071A171 (144) | |
Text
From: Tregoning, Robert Sent: Mon, 28 Aug 2017 11:07:25 +0000 To: Hiser, Matthew
Subject:
RE: Ex-plant M aterials Harvesting Workshop Matt:
Can you give me until the end of this week?
- Thanks, 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, Matthew Sent: Friday, August 25, 2017 10:14 AM To: Tregoning, Robert <Robert .Tregoning@nrc.gov>; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>
Subject:
RE : Ex-plant M aterials Harvesting Workshop Reminder to provide any comments by today before we finalize this meeting summary.
From: Hiser, Matthew Sent: Thursday, August 17, 201712:31 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>
Subject:
RE: Ex-plant Materials Harvesting Workshop Hi Rob and Mita, Here is the latest version of the workshop report. Please take a look and provide any feedback by next Friday, August 25 before I finalize it at the end of the month.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division or Engineering I Corrosion and Metallurgy Branch Phone: 301-4 I 5-2454 I Office: TWFN I 0D62
Matthew.Hiser@nrc.gov From: Hiser, M atthew Sent: Thursday, June 22, 2017 3:20 PM To: 'Bernhoft, Sherry' <sbernhoft@epri.com>; 'Dyle, Robin' <rdyle@epri.com>; 'Jean Smith (jmsmith@epri.com )' <jmsmith@epri.com>; 'Ahluwalia, Kawaljit' <kahluwal@epri.com>; 'Richard Reister (Richard.Reister@nuclear.energy.gov)' <Richard.Reister@nuclear.energy.gov>; 'leonardk@ornl.gov'
<leonardk@ornl.gov>; 'Rosseel, Thomas M.'<rosseeltm@ornl.gov>; 'William F Zipp (Generat ion - 4)'
<william .f.zipp@dom.com>; 'Gerard P. Van Noordennen' <gpvannoordennen@energysolutions.com>;
'Ramuhalli, Pradeep (Pradeep.Ramuhalli@pnnl.gov)' <Pradeep.Ramuhalli@pnnl.gov>;
'daniel.tello@canada.ca' <daniel.tello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe.Jendrich@grs.de>;
'rachid .chaouadi@sckcen.be' <rachid.chaouadi@sckcen .be>; 'arait@criepi.denken.or.jp'
<arait@criepi.den ken.or. jp>; 'al panfa@westinghouse.com' <aI pa nfa@westinghouse.com>;
'sokolovm@ornl.gov' <sokolovm@ornl.gov>; 'desire.ndomba@canada.ca' <desire.ndomba@canada.ca>;
'khuynh@aecl.ca' <khuynh@aecl.ca>; 'higuchi@criepi.denken.or.jp' <higuchi@criepi.denken.or.jp>;
'kazunobu_sakamoto@nsr.go.jp' <kazunobu sakamoto@nsr.go.jp>; 'chimi.yasuhiro@jaea.go.jp'
<chimi.yasuhiro@jaea.go.jp>; 'Jackson, John Howard' <john.jackson@inl.gov>; 'Roussel Guy'
<guy.roussel@Belv.be>; 'john.wagner@inl.gov' <john.wagner@inl.gov>; 'Riccardella, Pete'
<Priccardella@Structint.com>; 'RICHTER, M ark' <mar@nei.org>; 'Amberge, Kyle'
<kamberge@epri.com>; Moyer, Carol <Carol.Moyer@nrc.gov>; Oberson, Greg
<Greg.Oberson@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>; Poehler, Jeffrey
<Jeffrey.Poehler@nrc.gov>; Hiser, Allen <Allen.Hiser@nrc.gov>; Yoo, M ark <Mark.Yoo@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Buford, Angela <Angela.Buford@nrc.gov>; Sircar, Madhumita
<Madhumita.Sircar@nrc.gov>
Cc: Tregon ing, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Pat rick <Patrick.Purtscher@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: Ex-plant Materials Harvesting Workshop I have received input from a couple participants. This is a gentle reminder to please provide any input on the report by next Friday, June 30.
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: 301-415-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Hiser, Matthew Sent: Wednesday, May 31, 2017 4:21 PM To: 'Bernhoft, Sherry' <sbernhoft@epri.com>; 'Dyle, Robin' <rdyle@epri.com>; 'Jean Sm ith (jmsmith@epri.com )' <jmsmith@epri.com>; 'Ahluwalia, Kawaljit' <kahluwal@epri.com>; 'Richard Reister (Richard.Reister@nuclear.energy.gov)' <Richard .Reister@nuclear.energy.gov>; 'leonardk@ornl.gov'
<leonardk@ornl.gov>; 'Rosseel, Thomas M.' <rosseeltm@ornl.gov>; 'William F Zipp (Generation - 4)'
<william.f.zipp@dom.com>; 'Gerard P. Van Noordennen' <gpvannoordennen@energysolutions.com>;
'Ramuhalli, Pradeep (Pradeeo.Ramuhalli@pnnl.gov)' <Pradeep.Ramuhalli@pnnl.gov>;
'daniel.tello@canada.ca' <daniel.tello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe.Jendrich@grs.de>;
'rachid.chaouadi@sckcen.be' <rachid.chaouadi@sckcen .be>; 'arait@criepi.denken.or.jp'
<arait@crieoi.den ken.or. jp>; 'al panfa@westinghouse.com' <aI pa nfa@westinghouse.com>;
'sokolovm@ornl.gov' <sokolovm@ornl.gov>; 'desire.ndomba@canada.ca' <desire.ndomba@canada.ca>;
'khuynh@aecl.ca' <khuynh@aecl.ca>; 'higuchi@criepi.denken.or.jp' <higuchi@crieoi.denken.or.jp>;
'kazunobu_sakamoto@nsr.go.jp' <kazunobu sakamoto@nsr.go.jo>; 'chimi.yasuhiro@jaea.go.j p'
<chimi.yasuhiro@jaea.go.jo>; 'Jackson, John Howard' <john.jackson@inl.gov>; 'Roussel Guy'
<guy.roussel@Belv.be>; 'john.wagner@inl.gov' <john.wagner@inl.gov>; 'Riccardella, Pete'
<Priccardella@Structint.com>; 'RICHTER, M ark' <mar@nei.org>; 'Amberge, Kyle'
<kamberge@epri.com>; Moyer, Carol <Carol.Moyer@nrc.gov>; Oberson, Greg
<Greg.Oberson@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>; Poehler, Jeffrey
<Jeffrey.Poehler@nrc.gov>; Hiser, Allen <Allen.Hiser@nrc.gov>; Yoo, M ark <Mark.Yoo@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Buford, Angela <Angela.Buford@nrc.gov>; Sircar, Madhumita
<Madhumita.Sircar@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>
Subject:
RE: Ex-plant Materials Harvesting Workshop
==Dear Workshop
Participants:
==
I would like to share for your review and comment the workshop summary report (attached). In the report, we tried to capture as much of the discussion as possible, while focusing on the key takeaways that might be useful for all participants as they consider harvesting in the future. In particular, please review how your presentation and contribution to the discussion is characterized, in case you feel it should be clarified in any way. Feel free to provide additional references to previous research on harvested materials that should be captured in this report. Comments, edits, and suggestions on any other parts of the report are welcome.
Please provide your input by June 30 at the latest and we will try to finalize the report by sometime in July.
As indicated in action items 4 and 5, we will be pursuing further coordination efforts on data needs for harvesting and a sources of materials database and welcome any other parties that may be interested in participating in these discussions.
Thank you once again for your participation and engagement in this workshop!
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I CotTOsion and Metallurgy Branch Phone: 301-415-2454 I Office.* TWFN 10D62 Matthew.Hiser@nrc.gov
From: Hiser, Matthew Sent: Friday, March 17, 2017 8:39 AM To: 'Bernhoft, Sherry' <sbernhoft@epri.com>; 'Dyle, Robin' <rdyle@epri.com>; 'Jean Smith (jmsmith@epri.com )' <jmsmith@epri.com>; 'Ahluwalia, Kawaljit' <kahluwal@epri.com>; 'Richard Reister (Richard.Reister@nuclear.energy.gov)' <Richard.Reister@nuclear.energy.gov>; 'leonardk@ornl.gov'
<leonardk@ornl.gov>; 'Rosseel, Thomas M.'<rosseeltm@ornl.gov>; 'William F Zipp (Generation - 4)'
<william.f.zipp@dom.com>; 'Gerard P. Van Noordennen' <gpvannoordennen@energysolutions.com>;
'Ramuhalli, Pradeep (Pradeep.Ramuhalli@pnnl.gov)' <Pradeep.Ramuhalli@pnnl.gov>;
'daniel.tello@canada.ca' <daniel.tello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe.Jendrich@grs.de>;
'rachid.chaouadi@sckcen.be' <rachid.chaouadi@sckcen.be>; 'arait@criepi.denken.or.jp'
<arait@criepi.denken.or.jp>; 'alpanfa@westinghouse.com' <allpanfa@westinghouse.com>;
'sokolovm@ornl.gov' <sokolovm@ornl.gov>; 'desire.ndomba@canada.ca' <desire.ndomba@canada.ca>;
'khuynh@aecl.ca' <khuynh@aecl.ca>; 'higuchi@criepi.denken ..or.jp' <higuchi@criepi.denken.or.jp>;
'kazunobu_sakamoto@nsr.go.jp' <kazunobu sakamoto@nsr.go.jp>; 'chimi.yasuhiro@jaea.go.jp'
<chimi.yasuhiro@jaea.go.jp>; 'Jackson, John Howard' <john.jackson@inl.gov>; 'Roussel Guy'
<guy.roussel@Belv.be>; 'john.wagner@inl.gov' <john.wagner@inl.gov>; 'Riccardella, Pete'
<Priccardella@Structint.com>; 'RICHTER, Mark' <mar@nei.org>; 'Amberge, Kyle'
<kamberge@epri.com>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;
Oberson, Greg <Greg.Oberson@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>; Hiser, Allen <Allen.Hiser@nrc.gov>; Yoo, Mark
<Mark.Yoo@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Buford, Angela
<Angela.Buford@nrc.gov>; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Ex-plant Materials Harvesting Workshop
==Dear Workshop
Participants:
==
I have attached a list of participants in last week's workshop, a long with their email for contact.
Also, I have not received any concerns from the presenters regarding sharing slides, so feel free to share the slides, which are available on Google Drive:
https://drive.google.com/open?id=0BSDWMLchSYSXcnpZZ0JOS0SSQUU .
We hope to sha re a detailed workshop summary report in the next two months.
Thanks!
Matt From: Hiser, Matthew Sent: Friday, March 10, 2017 7:03 AM To: 'Bernhoft, Sherry' <sbernhoft@epri.com>; 'Dyle, Robin' <rdyle@epri.com>; 'Jean Smith (jmsmith@epri.com )' <jmsmith@epri.com>; 'Ahluwalia, Kawaljit' <kahluwal@epri.com>; 'Richard Reister (Richard.Reister@nuclear.energy.gov)' <Richard.Reister@nuclear.energy.gov>; 'leonardk@ornl.gov'
<leonardk@ornl.gov>; 'Rosseel, Thomas M.' <rosseeltm@ornl.gov>; 'William F Zipp (Generat ion - 4)'
<william.f.zipp@dom.com>; 'Gerard P. Van Noordennen' <gpvannoordennen@energysolutions.com>;
'Ramuhalli, Pradeep (Pradeep.Ramuhalli@pnnl.gov)' <Pradeep.Ramuhalli@pnnl.gov>;
'daniel.tello@canada.ca' <daniel.tello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe.Jendrich@grs.de>;
'rachid.chaouadi@sckcen.be' <rachid.chaouadi@sckcen.be>; 'arait@criepi.denken.or.jp'
<arait@criepi.den ken.or. jp>; 'al panfa@westinghouse.com' <aI pa nfa@westinghouse.com>;
'sokolovm@ornl.gov' <sokolovm@ornl.gov>; 'desire.ndomba@canada.ca' <desire.ndomba@canada.ca>;
'khuynh@aecl.ca' <khuynh@aecl.ca>; 'higuchi@criepi.denken ..or.jp' <higuchi@criepi.denken.or.jp>;
'kazunobu_sakamoto@nsr.go.jp' <kazunobu sakamoto@nsr.go.jp>; 'chimi.yasuhiro@jaea.go.jp'
<chimi.yasuhiro@jaea .go.jp>; 'Jackson, John Howard' <john.jackson@inl.gov>; 'Roussel Guy'
<guy.roussel@Belv.be>; 'john .wagner@inl.gov' <john.wagner@inl.gov>; 'Riccardella, Pete'
<Priccardella@Structint.com>; 'RICHTER, Mark' <mar@nei.org>; 'Amberge, Kyle'
<kamberge@epri.com>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>;
Oberson, Greg <Greg.Oberson@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>; Hiser, Allen <Allen.Hiser@nrc.gov>; Yoo, Mark
<Mark.Yoo@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Buford, Angela
<Angela.Buford@nrc.gov>; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Ex-plant Materials Harvesting Workshop
==Dear Workshop
Participants:
==
Thank you for attending and participating in the workshop this week. I appreciate your active participation in what was a very interesting and informative discussion. I hope you were able to come away from the meeting with a better understanding of how to approach harvesting and what to expect in terms of cost, schedule, complexity, challenges, etc.
NRC will be developing a workshop summary report to be shared among meeting participants. We have also placed all of the presentations into a Google Drive folder for sharing among meeting participants (https://drive.google.com/open?id=0BSDWMLchSYSXcnpZZ0JOS0SSQUU ).
I have laid out the action items and planned next steps to address each item below:
- 1. Sharing workshop slides (Ahluwalia)
- a. Next step: Presenters, please reply to this email if you have any concerns with meeting participants sharing your slides with colleagues or other organizations. If I don't hean from you, we'll assume you're OK with sharing.
- a. Available to public for fee
- 3. Cable surveillance programs in Germany
- a. Next step: GRS (Jendrich) to inquire with cable colleagues and share
- 4. Sources of Materials database
- a. Next step: Opportunities presented in this meeting to be documented in workshop summary.
- b. Next step : AECL, CNSC, NRC, PNNL, INL NSUF interested in database development. Any other parties interested?
- 5. Prioritized data needs
- a. Next step: Smaller group meetings to prioritize data needs of interest
- i. Material/ component of interest, purpose, intended outcome
- b. Idea: survey of participants at Environmental Degradation conference
- 6. EPRI report on SFP liner boric acid transport through concrete
- a. NRC (Sircar) to contact EPRI if needed
- 7. Harvested Materials Research Results
- a. Next step: A section of the workshop summary report to cover references from previous harvested materials research
- b. Use references from EMDA as starting point
- c. Next st ep: Please send any references to harvested materials research that shou ld be included and its outcome to Matt Hiser.
Please feel free to contact me with any questions or suggestions for documenting the workshop and the next steps moving forward.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov From: Hiser, Matthew Sent: Friday, M arch 03, 2017 8:22 AM To: 'Bernhoft, Sherry' <sbernhoft@epri.com>; 'Dyle, Robin' <rdyle@epri.com>; 'Jean Smith (jmsmith@epri.com )' <jmsmith @epri.com>; 'Ahluwalia, Kawaljit' <kahluwal@epri.com>; 'Richard Reister (Richard.Reister@nuclear.energy.gov)' <Richard.Reister@nuclear.energy.gov>; 'leonardk@ornl.gov'
<leonardk@ornl.gov>; 'Rosseel, Thomas M.' <rosseeltm@ornl.gov>; 'William F Zipp (Generation - 4)'
<william.f.zipp@dom.com>; 'Gerard P. Van Noordennen' <gpvannoordennen@energysolutions.com>;
'Ramuhalli, Pradeep (Pradeep.Ramuhalli@pnnl.gov)' <Pradeep.Ramuhalli@pnnl.gov>;
'daniel.tello@canada.ca' <daniel.tello@canada.ca>; 'Uwe.Jendrich@grs.de' <Uwe.Jendrich@grs.de>;
'rachid .chaouadi@sckcen.be' <rachid.chaouadi@sckcen.be>; 'arait @criepi.denken.or.jp'
<arait@criepi.denken.or.jp>; 'alpanfa@westinghouse.com' <alpanfa@westinghouse.com>;
'sokolovm@ornl.gov' <sokolovm@ornl.gov>; 'desire.ndomba@canada.ca' <desire.ndomba@canada.ca>;
'khuynh@aecl.ca' <khuynh@aecl.ca>; 'higuchi@criepi.denken.or.jp' <higuchi@criepi.denken.or.jp>;
'kazunobu_sakamoto@nsr.go.jp' <kazunobu sakamoto@nsr.go.jp>; 'chimi.yasuhiro@jaea .go.jp'
<chimi.yasuhiro@jaea.go.jp>; Jackson, John Howard <john.jackson@inl.gov>; 'Roussel Guy'
<guy.roussel@Belv.be>; 'john.wagner@inl.gov' <john.wagner@inl.gov>; 'Riccardella, Pete'
<Priccardella@Structint.com>; 'RICHTER, M ark' <mar@nei.org>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Pat rick <Patrick.Purtscher@nrc.gov>;
Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Ex-plant Materials Harvesting Workshop
Dear Harvesting Workshop Attendees:
You are receiving this email because I have you recorded as attending the upcoming Ex-plant Materials Harvesting Workshop on March 7-8 at USNRC headquarters in Rockville, MD. I have
attached the final workshop agenda as well as the workshop introduction slides that cover meeting logistics, motivation, approach , expected outcome, and session expectations . We are hoping these slides provide a common vision for the workshop that will allow for a focused ,
productive discussion.
The workshop will be held in NRC's Three White Fli nt North (3WFN) build ing , which is directly adjacent to the White Flint Metro station , in room 1C3 on the first floor. I have attached a map of the local area showing the Metro station and the 3WFN build ing.
The workshop is scheduled to start at 8:00 on Tuesday, March 7. I recommend planning to arrive at 3WFN around 7:30-7:45 in order to go through security to enter the building.
If you have not yet responded , please let me know if you plan to join for the dinner with other workshop participants, so I can make the appropriate reservation.
Thank you for your participation in the workshop. We are looking forward to the discussion and engagement and appreciate your contribution to a productive and interesting meeting!
Please let me know if you have any questions .
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: 301 -415-2454 I Office: TWFN J0D62 Matthew.Hiser@nrc.gov
From: Tregoning, Robert Sent: Fri, 19 May 2017 18:10:48 +0000 To: Hull, Amy Cc: Moyer, Carol
Subject:
RE: FYI, anot her idea for PLiM .... : Reviewed with comments -- Harvesting Workshop summary Report draft abh 5-19-17-lpm We could put in a paper for the harvesting effort. I think it's a good idea and would circulate this idea out to a wider audience. However, Carol is the lone person from RES that we're targeting to go to PLiM so she would need to present it.
- Cheers, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hull, Amy Sent: Friday, M ay 19, 2017 1:57 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Cc: M oyer, Carol <Carol.Moyer@nrc.gov>
Subject:
FYI, another idea for PLiM .... : Reviewed with comments -- Harvesting Workshop summary Report draft abh 5-19-17-lpm From: Hull, Amy Sent: Friday, May 19, 2017 1:48 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Subject:
Reviewed with comments -- Harvesting Workshop summary Report draft abh 5-19-17-lpm Hi Matt, This is lovely work and it was a very productive workshop.
I have another suggestion for you --- I think it would be a great idea to also have this as a presentation for IAEA PLiM this Fall. At the last SM IRT, there were summary papers of workshops like this that were very valuable. Condensing wisdom of many people into a short presentation - but you get a refereed
article out of it. I think the short abstracts have to be done soon (today?) so you might want to check with Rob or Carol about th is.
From: Hiser, Matthew Sent: Tue, 10 Oct 2017 16:52:51 -0400 To: Purtscher, Patrick
Subject:
RE: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Feel free to share with Pradeep ....
From: Hiser, Matthew Sent: Tuesday, October 10, 2017 4:41 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer @nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants
<< Fi le: 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 of Engineering I Con-osion and Metallurgy Branch Phone: 301-415-2454 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 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
<Ra j.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-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/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 ,
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From: Audrain, Margaret Sent: Wed, 30 May 2018 14:10:46 +0000 To: Tregoning, Robert;Purtscher, Patrick;Hiser, Matthew
Subject:
RE: harvesting report
- Pat, I'm working on putting together my site visit to PNNL in July. Do you think it'd be easiest to have Steve Bruemmer coordinate with Pradeep on timing/etc? Does Pradeep have the latest version of the spreadsheet to work with in advance of my coming there?
- Thanks, Meg From: Tregoning, Robert Sent: Tuesday, May 29, 2018 7:38 AM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>; Hiser, Matthew <M atthew. Hiser@nrc.gov>;
Audrain, Margaret <Margaret.Audrain@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: harvesting report Pat:
Thanks, they have the slides and summary and we indicated during the meeting last week that the final report is largely consistent with that information. They obviously want the final report however because it will provide much more context and detail and also reflect at least some level of NRC review ....
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: Purtscher, Patrick Sent: Tuesday, May 29, 2018 7:34 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>;
Audrain, Margaret <Margaret.Audrain@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frank l@nrc.gov>
Subject:
RE: harvesting report
All ,
I will contact Pradeep today to see how the revision is coming. In fact, the slides and summary of the workshop (already available to EPRI) would be more valuable to industry than the report itself; these files include slides from Pradeep that reflect the report.
Pat From: Hiser, Matthew Sent: Thursday, May 24, 2018 12:09 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE: harvesting report I agree it would be good to move the publishing of that report ahead expeditiously to help our coordination with EPRI. Last I heard Pat said PNNL was working on addressing NRR's comments - not sure what the timeline was for doing that though.
Thanks!
Matt From: Tregoning, Robert Sent: Thursday, May 24, 2018 8:37 AM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
harvesting report All :
Yesterday, during Steve's presentation, EPRI (Dyle and Demma) expressed interest in getting the PNNL report once it's published. We're also planning to have some discussions with EPRI next week during the NRC/EPRI materials meeting to promote future collaboration on harvesting opportunities. Therefore, I think we should make publishing that report a higher priority and we can possibly use it in part to help frame our discussions with EPRI moving forward.
Thoughts?
Rob Robert Tregoning 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: Tregoning, Robert Sent: Wed, 18 Jan 2017 20:02:45 +0000 To: Hiser, IMatthew;Purtscher, Patrick
Subject:
RE: Harvesting service irradiated material from NPPs Matt:
When we put together our high-priority needs for harvesting, we should have an internal meeting including Mita, Tom Koshy, and Darrell Murdock, at a minimum. They can add items related to concrete, l&C, and electrical. While we don't need to be comprehensive at this point, it would be good to have some examples .....
- Cheers, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hiser, Matthew Sent: Wednesday, January 18, 2017 11:53 AM To: Sircar, Madhumita <Madhumit a.Sircar@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
RE: Harvesting service irradiated material from NPPs Hi Mita, Yes, we're planning for March 7 and 8 in 3WFN. I've attached the meeting announcement and a draft agenda.
Thanks!
Matt From: Sircar, Madhumita Sent: Wednesday, January 18, 2017 11:51 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
Harvesting service irradiated material from NPPs
- Matt,
Rob Tregoning suggested me to contact you regarding the meeting on harvesting service irradiated material from NPPs. Is the meeting in March?
- Thanks, Mita Sircar Tel: 301-415-1804
From: Tregoning, Robert Sent: Wed, 16 Mar 2016 13:21:37 +0000 To: McHale, John
Subject:
RE: Harvesting WG John:
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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...,-,.,.
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fax: 301-415-6671 From: McHale, John Sent: Wednesday, March 16, 2016 8:46 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
Harvesting WG Rob, After our conversation yest erday, I did confirm with Jeff Poehler that he will be our rep on the (b)(6) harvestingWG, L....-----==*;;;;;; ****;;;;;;
- = **"""=""=
"" ;;;;;;;;;;;;;:::::::::::======- - - - - - - - - - - - - - - - . . . . . J (b)(6) J... . * !so he won't be able to make it in today for the meeting. I hope this will not be too much of an impact for today's meeting and we'll be able to support better the next time around.
Jack
From: Tregoning, Robert Sent: Tue, 3 Jan 2017 12:54:26 +0000 To: 'Hojna Anna'
Subject:
RE: Harvesting Workshop - U.S. NRC- March 2017
Dear Anna:
Thank you for your email and for your interest in our upcoming harvesting workshop. We are planning five unique sessions as part of the workshop. Each session has a specific theme, or objective, as outlined below (and in the agenda that you were sent previously).
- 1. Session 1 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 The objective of the workshop is not to look for potential sponsors but to discuss better ways to plan and implement harvesting programs than has been done in the past. With this in mind, we are interested in learning about past experiences that organizations have had with harvesting programs and what has been learned from the program that could inform any future programs. This is the objective of Session
- 4. We're not so much interested in discussing the technical knowledge that has been gained from getting materials from decommissioned nuclear power plants, but in the practical aspects of running the program.
We are trying to keep the workshop participation relatively small so that we can have focused discussion and we are inviting the specific talks. Please let me know if you are interested in attending and if you also have a proposed talk that may fit within the objectives for any of the sessions I listed above. Please also let me know if you have any additional questions.
Warm regards, Rob From: Hojna Anna @cvrez.cz
Sent: Friday, December 23, 2016 7:30 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
[External_Sender] Harvesting Workshop - U.S. NRC - March 2017
Dear Rob Tregoning,
Could you be so kind and give me more information about the Harvesting workshop.
I heard about it, but I do know if the participation is only for invited people or if anybody can come.
I am working in CVR in Czech Republic, the research centre dealing with irradiated materials test ing. In past I was responsible for the project on the irradiated int ernals material of the decommissioned NPP VVER 440 Nord I situated in Greifswald, Germany. I can share my experience with t he testing.
However, it seems to me, that in the workshop you wish to look rather for potential sponsors than experimental labs.
Anyway, I would be glad to hear more about the event. Thanks.
With best regards Anna Hojna Centrum Vyzkumu Rez s.r.o.
Department 8590 VaV Generation IV Rez 130 25068 Husinec Czech Republic http://cvrez.cz Tel.: +420 2 6617 3549 Neuvadi-li se v textu nebo priloze tohoto e-mailujinak, nenijeho obsah zamyslenjako navrh na uzavreni smlouvy (nabidka) nebo prUeti nabidky. Kazda smlouva, pokud bude uzavrena, musi mit vyhradne pisemnouformu. Jnformace obsazene v tomto e-mailujsou urceny vylucne pro potreby j eho adresata. Jeho text nebo pfilohy mohou obsahovat duverne i,daje, pfipadnejine informace podlehajici ochrane die pfislusnych pravnich predpisu. Pokud Vam tento e-mail by/ omylem dorucen, zdrzte se jakehokoli nakladani s textem ci prilohami, jako je kopirovani, preposilani, zpfistupneni dalsi osobe a podobne. 0 chybnem doruceni informujte, prosim, odesilatele a e-mail vcetne priloh vy mazte ze sveho pocitace a dalsich informacnich systemu.
If not stated otherwise, the text of the e-mail is not intended as a contracting offer (draft contract) or offer acceptance. Each contract, should it be concluded, strictly requires a written form. The information contained in this e-mail is intended solely for the addressee. The main body or attachments may contain confidential information or, as the case may be, other information subject to protection under the relevant legal regulations. ff you have received this e-mail in error, please refrain from copying, forwarding or disclosing the content or attachments to other p ersons. Please notify the sender about the mistaken delivery and delete the e-mail, including all attachments, from your computer.
~ Think about the nature... Do you really need to print this e-mail?
From: Tregoning, Robert Sent: Wed, 7 Dec 2016 21:07:09 +0000 To: Hiser, Matthew
Subject:
RE: Harvesting Workshop Agenda Brainstorming Matt:
Just got off the phone with Sherry and Rich. Let's talk about the agenda as soon as possible, either today or tomorrow morning.
- 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, Matthew Sent: Wednesday, December 07, 2016 3:38 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
RE: Harvesting Workshop Agenda Brainstorming
<< File: NRC Harvesting Workshop Announcement 12-7-16.docx >>
Hi Rob, Added some language to the announcement per suggestion from Allen. He suggested addressing whether presentations were open or solicited, as well as when more information on the workshop would be available:
"Workshop will consist of solicited presentations followed by discussion periods. Open attendance and participation in discussion is encouraged. Additional information to be provided by January 13, 2016."
Any thoughts? Look good to you?
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWPN 10D62 Matthew.Hiser@nrc.gov From: Hiser, Matthew Sent: Wednesday, December 07, 2016 2:08 PM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Poehler, Jeffrey
<Jeffrey.Poehler@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, Allen
<Allen.Hiser@nrc.gov>
Subject:
RE: Harvesting Workshop Agenda Brainstorming Updated workshop announcement as requested with figures.
<< Fi le: NRC Harvesting Workshop Announcement 12-7-16.docx >>
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: Hiser, Matthew Sent: Wednesday, November 09, 2016 10:37 AM To: Purtscher, Patrick <Patrick. Purtscher@nrc.gov>; Poehler, Jeffrey
<Jeffrey.Poehler@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, Allen
<Allen.Hiser@nrc.gov>
Subject:
FW: Harvesting Wor kshop Agenda Bra instorming Just wanted to send a reminder for feedback/ input on the workshop agenda.
Thanks!
Matt
Fro m: Hiser, Matthew Sent: Friday, November 04, 2016 12:46 PM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Tregoning, Robert
<Robert.Tregoning@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>
Subject:
RE: Harvesting Workshop Agenda Brainstorming
<< File: Workshop Agenda 11-4-16.docx >> << File: NRC Harvesting Workshop Announcement.docx >>
Hi Rob, Pat, and Jeff, Please find attached my updates to the agenda based on our discussion yesterday. It may be somewhat premature, but I went ahead and tried to put times to the agenda, just to see how it might schedule out. Session 5 is probably the main area of uncertainty along with international presenters in general.
Please take a look and provide any comments or feedback by next Wednesday, so we can hopefully finalize this and share with DOE/EPRI very soon.
I also attached the latest version of the workshop announcement, which we plan to use to publicize to other attendees and presenters.
Thanks!
Matt Original Appointment-----
From: Hiser, Matthew Sent: Wednesd ay, November 02, 2016 2:34 PM To: Hiser, Matthew; Purtscher, Patrick; Tregoning, Robert; Poehler, Jeffrey Subject : Harvesting Workshop Agenda Brainstorming When: Thursday, November 03, 2016 1:00 PM-2:00 PM (UTC-05:00) Eastern Time (US &
Canada).
Where: HQ-TWFN-08C01-10p Hi Rob, Jeff, Pat, I've put together an outline of an agenda for this workshop on harvesting that we are planning for March. My first cut at it is attached. I'd like to use this meeting to brainstorm how to structure the workshop and, if possible, who to ask to present and on what topics.
Rob and I were discussing trying to selectively target participants and presentations to cover the topics we'd like, rather than simply asking DOE and EPRI and others for their take on "harvesting." I think if we plan this well, we can get an interesting and substantive discussion. If not, we may just get a rehash of SLR-type talks ...
Thanks!
Matt
<< File: Agenda Outline.docx >>
From: Tregoning, Robert Sent: Thu, 1 Dec 2016 15:53:18 +0000 To: Hiser, Matthew
Subject:
RE: Harvesting Workshop Agenda Thanks, I'll send the agenda to DOE/EPRI and start circulating the announcement as well. ...
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, Matthew Sent: Thursday, December 01, 2016 10:37 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
Harvesting Workshop Agenda Hi Rob, I've incorporated the tweaks to the agenda that we discussed yesterday. We may want to try to schedule a meeting soon, given the rapidly approaching holidays. We should try to get aligned with DOE and EPRI before the holidays and firm up/contact the presenters. When everyone gets back in January, we'll be about 2 months from the workshop!
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov
From: Tregoning, Robert Sent: Fri, 21 Oct 201613:17:10 +0000 To: Hiser, IMatthew;lyengar, Raj
Subject:
RE: Harvesting Workshop Announcement Let's set the dates based on EPRI/DOE feedback and then I'll start sending internationally once we finalize the dates.
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, Matthew Sent: Friday, October 21, 2016 9:05 AM To: Tregoning, Robert <Robert .Tregoning@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>
Subject:
Harvesting Workshop Announcement Hi Rob and Raj, Please find attached the final v,ersion of the harvesting workshop announcement. If you could share this with your contacts at DOE/EPRI (Raj), and internationally (Rob), that would be great to begin to publicize this workshop and receive feedback on the preferred dates as well as those interested to present at t he workshop.
Thanks!
Matt
From: Tregoning, Robert Sent: Wed, 14 Dec 2016 23:21:11 +0000 To: Purtscher, Patrick
Subject:
RE: Harvesting Workshop Plans Tom Rossel I have his email if you need it trossel@oml.gov. I may not have his name spelled correctly however
Original Message -------- From: "Purtscher, Patrick"
Date: Wed, December 14, 2016 10:13 AM -0500 To: "Tregoning, Robert" <Robert.Tregoning@nrc.gov>
Subject:
RE: Harvesting Workshop Plans Hi, Do you have the contact info for the guy at ORNL who would have worked with Energy Solutions Zion?
Pat From: Hiser, M atthew Sent: Monday, December 12, 2016 2:44 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@ nrc.gov>
Cc: Poehler, Jeffrey <Jeffrey.Poeh ler@nrc.gov>; Hiser, Allen <Allen.Hiser@nrc.gov>
Subject:
Harvesting Workshop Plans Hi Rob and Pat, Following our meeting last week, I made the appropriate updates to the workshop agenda and have attached it to this email. I have also attached a "condensed" workshop agenda that we can share with any interest ed attendees looking for a little more info.
We agreed that Rob will take the lead for organizing Sessions 1 and 5, Pat will take session 3, and I will take sessions 2 and 4.
Action items from that meeting are summarized below:
- Rob: send revised agenda to EPRI/DOE and ask for their leads for each session
- Rob: send announcement to CSNI and other international contacts
- Pat: contact decommissioning branch for contact at EnergySolutions for decommissioning presentation
- Matt: Contact Chuck Tomes at Dominion for U.S. utility talk The list of international parties we think could be interested include:
- ENSI (Muhleberg in Switzerland)
- KINS/KAERI (Kori plant in Korea)
- SCK - RPV interest in Belgium
- MAI in France
- JRC in EU
- JNRA in Japan
- German decommissioning company Thanks!
Matt
From: Tregoning, Robert Sent: Wed, 31 Jan 2018 15:52:36 +0000 To: Hiser, Matthew Cc: Purtscher, Patrick
Subject:
RE: Harvesting Workshop Presentations I'm going to send it to him under our umbrella agreement with CSN that covers information sharing but ask him not to distribute or share outside of his organization .....
Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Hiser, Matthew Sent: Wednesday, January 31, 2018 10:51 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Cc: Purtscher, Patrick <Patrick. Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Presentations I'm fine with it. ..
From: Tregoning, Robert Sent: Wednesday, January 31, 2018 10:50 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Presentations Ah yes, I forgot you put them on google drive and when I scanned the summary report I didn't see a link. Do you see any problems with sending the summary and link to Carlos?
Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671
From: Hiser, Matthew Sent: Wednesday, January 31, 2018 10:48 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Presentations Here's the final report - the presentations are on a folder in my Google Drive that is accessible via a private link (anyone with the link can access them , but otherwise no one can see them):
https://drive.google.com/open?id=0B5DWMLch5YSXcnpZZ0JOS055QUU . This link is in the final report on page 17 under Action Items.
From: Tregoning, Robert Sent: Wednesday, January 31, 2018 10:45 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Presentations Matt:
Thanks, that's what I thought but just wanted confirmation. I got a request from CSN (Carlos Castelao) about the workshop. I was planning on sending him the workshop summary. Are there any issues with this? I was also thinking about sending him the presentations.
Thoughts? How did we ultimately send these to the workshop participants if they are just on the g:\?
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, Matthew Sent: Wednesday, January 31, 2018 10:38 AM To: Tregoning, Robert <Robert .Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Presentations Hi Rob, They are not in ADAMS (since we were in this non-public working space, I never bothered).
Here's their location on the G: drive: G:\DE\CMB\Harvesting Workshop Presentations .
Thanks!
Matt
From: Tregoning, Robert Sent: Wednesday, January 31, 2018 8:38 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
Harvesting Workshop Presentations MatUPat:
I'm assuming that we put all the presentations in ADAMS in a single package. Is this the case?
Can you send me the ADAMS number?
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: Tregoning, Robert Sent: Mon, 1 May 201714:57:16 +0000 To: Hiser, Matthew Cc: Purtscher, Patrick
Subject:
RE: Harvesting Workshop Summary Report Draft Matt:
Thanks, I'm pretty tied up again both this week and early next week (through Wednesday) but I'll do my best. Proceed if you don't hear from me by end of this week. We do need to keep the effort moving on developing wish lists and the sources database. I spoke with Kazu Sakamoto last week and he indicated that he's getting pressure from his bosses to do something in this area so he is now motivated more so than during the workshop to collaborate with us on this.
can provide more details ....
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, Matthew Sent: Monday, May 01, 2017 10:45 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Cc: Purtscher, Patrick <Patrick. Purtscher@nrc.gov>
Subject:
Harvesting Workshop Summary Report Draft Hi Rob, I have started working on the workshop summary report (attached). I bounced this off of Pat last week and he and I are largely aligned in terms of scope and level of detail.
I have currently written up through the background/ intro, session 1 and session 2. When you get a chance, please take a look and provide any feedback on the organization, scope, and level of detail. There is a high-level outline on the first page.
I am hoping to get to a complete first draft by the end of next week and then hopefully something ready to share w ith workshop participants by th e end of May.
Thanks!
Matt Matthew Hiser
Materials Engineer US uclear Regulatory Commission I Office of uclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 /-4/5- 2454 I Office: TWFN I0D62 Matthew.Hiser@nrc.gov
From: Tregoning, Robert Sent: Tue, 17 Jan 2017 13:25:49 +0000 To: Hiser, IMatthew;Purtscher, Patrick
Subject:
RE: Harvesting Workshop Matt:
I think your message is fine and it doesn't hurt to query CNSC a bit about possible contributions. We should, of course, keep in mind that there will likely be less interest in a CANOU-perspective/opportunities/issues since our focus is LWR components.
However, maybe there are other components, like cables or concrete, where there is enough similarities in operating conditions and pedigree.
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, Matthew Sent: Tu esday, January 17, 2017 8:12 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick
<Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop It was a voicemail with a phone number left, so I was planning to call him back later this morning.
My plan was to deliver a similar message as you have to the Japanese: non-public workshop; we are inviting/soliciting presentations; their attendance and participation is welcome, but we are trying to keep it small and focused. Do you think CNSC could present in one of the yellow or red slots below?
Sessio Organizatio Topic Speaker Status n n EPRI
-DOE Why our organization is interested in
- Robert NRC 1 harvesting Tregoning MAI or JRC JNRA PANEL DISCUSSION Overview of data needs best PNNL (for Pradeep addressed by harvesting NRC) Ramuhalli EPRI 2
Perspective on detailed data needs
-DOE from harvesting
-MAI or JRC JNRA SCK-CEN?
CRIEPI?
Available materials from decommissioning plants and past NRC Matt Hiser harvesting programs Available materials from operating 3 EPRI reactors and past harvesting programs Available materials at DOE labs from DOE past harvesting programs (ORNL?)
International sources of materials IAEA?
EPRI Perspective on Harvesting Lessons -DOE Learned / Prior Experience -NRC 4
Decommissioning process and Energy Gerry van harvesting: schedule, site-specific, Solutions Noordennen timing for different components
Utility-Owner perspective on Dominion?
harvesting and decommissioning International decommissioning and Germany?
harvesting experience Technical information needed for PNNL (for Pradeep informed harvesting decisions NRC) Ramuhalli EPRI
-DOE Perspective on future harvesting
- Robert 5 NRC planning Tregoning MAI or JRC JNRA PANEL DISCUSSION Discussion of Next Steps/ Actions 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: 301-4 15-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Tregon ing, Robert Sent : Tuesday, January 17, 2017 8:05 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Are you responding to CNSC?
RT Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two Wh ite Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738
ph: 301-415-2324 fax: 301-415-6671 From: Hiser, Matthew Sent: Tuesday, January 17, 2017 7:27 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick
< Patrick. Purtsche r@nrc.gov>
Subject:
RE: Harvesting Workshop Hi Rob, I think that is an excellent idea. I'll draft up a few slides and share with you two.
Also, I received a message on Friday from someone at CNSC indicating their interest in possibly sending a couple people to the workshop.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office ofNuclcar Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-4 15-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Tregoning, Robert Sent: Thursday, January 12, 2017 4:22 PM To: Hiser, Matthew <Mat thew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Guys:
We haven't explicitly talked about this but I think it would be good to have a 5 - 10 minute talk at the very beginning of the workshop to provide the overall workshop objectives, and discuss the objectives and format/approach of the individual sessions.
Maybe it would also be good to put a few slides together now that we can send to participants so that people are as aligned as possible heading into the workshop.
Thoughts about this idea?
- 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, Matthew Sent: Thursday, January 12, 2017 1:44 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick
< Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop
<< File: Workshop Planning.docx >>
Hi Rob and Pat, Thanks for the productive meeting this morning. I've attached the latest version of the planning document.
Here were each of our action items:
Rob:
- Sessions 1/5 (mostly panel discussions)
- Contact international participants:
o Oliver Martin - JRC o TG Lian - EPRI/MAI o JNRA/CRIEPI Pat:
- Contact PNNL
- Contact speakers:
o EnergySolutions o Dominion/utility o IAEA/Krivanek
- Transcription/AV Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-24541 Office: TWFN 10D62 M atthew.Hiser@nrc.gov
Origi na I Appointment-----
From: Hiser, Matthew Sent: Monday, January 09, 2017 10:00 AM To: Hiser, Matthew; Tregoning, Robert; Purtscher, Patrick
Subject:
Harvesting Workshop When: Thursday, January 12, 2017 8:00 AM-9:00 AM (UTC-05:00) Eastern Time (US & Canada).
Where: HQ-TWFN-10A73-8p Can we move this a little earlier tomorrow since I now have a conflict at 9:00?
Here is a workshop planning document I've created with a list of contacts/ expected attendees and a table laying out all the planned presentations and sessions to track confirmed speakers.
<< File: Workshop Planning.docx >>
From: Hiser, Matthew Sent: Tue, S Dec 2017 19:40:07 +0000 To: Purtscher, Patrick
Subject:
RE: Harvesting-HR-final DRAFT-12_04_2017.docx I th ink when we met last week we talked about having a meeting with the appropriate folks over there to explain th is report and what is going on with harvesting, rather than just lobbing it over the fence ...
You might want to reach out to Bennett to figure out who would be the right staff in NRR to pull into such a meeting.
From: Purtscher, Patrick Sent: Tuesday, December OS, 2017 2:27 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
FW: Harvesting-HR-final DRAFT- 12_04_2017.docx Should I send this over to Bennett Brady too?
From: Purtscher, Patrick Sent: Tuesday, December OS, 2017 8:20 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Audra in, Margaret <Margaret.Audra in@nrc.gov>;
Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
Harvesting-HR-fina l DRAFT-1 2_04_2017.docx Here is the final draft of the harvesting report.
Pat
From: Tregoning, Robert Sent: Tue, 17 Jan 2017 13:04:02 +0000 To: Hiser, IMatthew;Purtscher, Patrick
Subject:
RE: Hi Matt. I understand that there will be a 2 day harvest ing workshop the week before the RIC? If so can you send me a scheduler for the workshop?
Agreed ....
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, Matthew Sent: Tuesday, January 17, 2017 7:25 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
FW: Hi Matt. I understand t hat there will be a 2 day harvesting workshop the week before the RIC? If so can you send me a scheduler for the workshop?
Got this from Bernie Litkett in DLR last week. We probably need to talk about how to communicate this workshop within NRC ...
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-415-24541 Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Litkett, Bernard Sent: Thursday, January 12, 2017 2:30 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Subject:
Hi Matt. I understand that there will be a 2 day harvesting workshop the week before the RIC?
If so can you send me a schedu ler for the workshop?
Bernard Litkett NRR/DLR/RSRG Project Manager
0- 11C5 301 -415-3657 Bernard. Litkett@nrc.gov
Note to requester: The attachment is immediately following.
From: Tregoning, Robert Sent: Thu, 30 Aug 2018 20:09:03 +0000 To: Audrain, Margaret Cc: Hiser, Matthew;Purtscher, Patrick
Subject:
RE: JNRA Meet ing Sept 2018 Harvesting.ppt x Attachments: JNRA Meeting Sept 2018 Harvesting rlt.pptx Meg, Matthew, Patrick:
Many thanks for your help with this. The presentation looks good and it will be useful for having a targeted discussion on the topic and hopefully we will see some interest from them in this area. I made a few simple formatting changes to a few slides so they all have similar fonts (see attached).
Could you also provide me a reference for the PNNL report (i.e., title and report number)? I'd specifically like to let them know about this report and let them know that we are planning to have it completed sometime in the fall. I'm going to add this as a bullet to one slide.
Matt:
Can I get you to add another slide which summarizes, at a high level the harvesting workshop and then has a reference to the workshop summary report? Basically just a reminder of dates, attendance, agenda/discussion topics, and then the reference to the report. Since Kazu attended the meeting I don't think there are any issues with giving them the summary. Do you agree?
Thanks again, 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: Audrain, Margaret Sent: Thursday, August 30, 2018 2:22 PM To: Tregoning, Robert <Robert .Tregoning@nrc.gov>
Cc: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purt scher@nrc.gov>
Subject:
JNRA Meet ing Sept 2018 Harvesting.pptx
- Rob,
Please see attached for the harvesting presentation . I added the harvesting needs slides , as discussed. Feel free to make edits or let me know if you want something changed .
Thanks ,
Meg
7 U.S.NRC United Stues Nuclear Rcgubtory Commission The views expressed in this presentation are those of the author
' Protectin,r Ptopk and tht Environment not necessarily those of the U.S. NRC.
Motivation ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- US utilities are interested in extending operating lifespans from to 60-80 years:
- Key technical areas for aging management:
- RPV embrittlement, irradiation-assisted degradation of internals, concrete structures and containment, electrical cables
- Many plant shutdowns worldwide provide opportunities to harvest components during decommissioning
- Harvesting can provide valuable information on aging mechanisms to increase confidence in aging management
- Limited budgets make cooperation for new research, including harvesting, essential:
- Important to align interested parties
- Leverage resources for maximum benefit
NRC Harvesting Experience ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- NRC has participated in several programs:
- Materials harvested from unfmished, operating and decommissioning plants
- US and international programs
- NRC experience is there is significant value in using harvested components to confirm data from other research programs
Lessons Learned ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- Technical
- Provides highly representative aged materials for research
- Important to gain as much information as possible before committing to specific harvesting project
- Logistical
- Expensive and time-consuming effort
- Leveraging resources helps mitigate cost challenges
- Transportation of irradiated materials is cumbersome and time-consuming
Current Work ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- Develop strategic approach to materials harvesting
- Past efforts have been reactive to individual plants shutting down
- Developing
- Prioritize data needs best addressed by harvesting, considering:
- Applicability of harvested material for addressing gaps
- Importance of harvested materials over laboratory aging
- Fleet-wide vs plant-specific applicability of data
- Regulatory considerations
- Harvesting cost/complexity
- Database for Sources of Materials
- Compilation of previously harvested materials available at US national labs as well as those available for future harvesting
- NRC is interested in engaging with other organizations in developing the database
Needs - Metals ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- 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 T 0
- This 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
Needs - Metals ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- 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
Needs - Electrical ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- Cables
- Low and medium voltage cables
- Cables protected with fire retardant coating
- Electrical components IE MOVs from harsh and mild environments IE Air operated valves; 4160 IE breakers IE Molded case breakers 480V, 250V DC, 125 VDC, 1E Relays from mild environment GE - HFA, Agastat timing relays, any from Westinghouse, Potter Brumfield, Stuthers Dunn etc.,
Electrical penetrations; Batteries
- Fire research interest Electrical enclosures
Needs - Concrete ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- 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 inPWRs
- Alkali Aggregate Reaction
- Large structural sections for testing
Conclusion ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- Harvesting can yield highly representative and valuable data on materials aging
- A focused approach to choosing harvested materials is necessary to get best outcomes
- NRC is working on a sources of materials database and prioritizing data needs based on relevant criteria to inform decisions on specific harvesting opportunities
- NRC welcomes opportunities for cooperation and leveraging with other interested research organizations
Discussion ~ U.S.NRC Un ited States Nuclear Regulatory Commission Protecting Peopl.e and the Environment
- Has the planned work on harvesting RPV materials and concrete from Hamaoka 1 been completed?
- Can those results be shared with NRC?
- Does NRA/CRIEPI have any other harvesting programs in progress or planned?
- If so, any information that can be shared?
- If still being planned, is there interest in additional partners?
- Would there be interest in participating if a harvesting project was identified in the US or another country?
- Should we reach out to NRA if other harvesting opportunities develop?
From: Tregoning, Robert Sent: Mon, 19 Dec 2016 15:37:38 +0000 To: 'OlliVilhelm.NEVANDER@oecd.org'
Subject:
RE: NRC Harvesting Workshop Thanks, Olli. I greatly appreciate the help. I hope you and your family have a happy and healthy holidays and a prosperous New Year!
Rob From: OlliVilhelm.NEVANDER@oecd.org .NEVANDER@oecd.org
Sent: Monday, December 19, 2016 9:02 AM To: ajh@csn .es; alexander.price@onr.gov.uk; andrei.blahoianu@canada.ca; andrzej.kochmanski@udt.gov.pl; ari.koskinen@vtt.fi; b.martens@sckcen.be; bharat.patel@ec.europa.eu; bj orn .brickstad@ssm.se; borut.mavko@ijs.si; boylydell@msn.com; bruno.barthelet@edf.fr; car@csn.es; ccl@csn.es; ccueto@tecnatom.es; cecile.deust -
dhaultfoeuille@irsn.fr; chris.belsham@onr.gov.uk; cik@kaeri.re.kr; ckr@kins.re.kr; corsi@casaccia.enea.it; daniel.kjellin@ssm.se; dietma r.kalkhof@ensi.ch; Hackett, Edwin
<Edwin. Hackett@nrc.gov>; eric.meister@edf.fr; eric.van.walle@sckcen.be; francois.balestreri@irsn.fr; francois.tarallo@irsn .fr; frank.michel@grs.de; frederic.somville@tractebel.com; fredrik.forsberg@ssm.se; georges.van-goethem@ec.europa.eu; gillemot@sunserv.kfki.hu; giuseppe.pino@ isprambiente.it; guillaume-gontrand.herve@edf.fr; hiroaki_yamazaki@nsr.go.jp; hiroshi_abe@nsr.go.jp; hoj @uj v.cz; igor.simonovski@ec.europa.eu; ilie.petre-lazar@edf .fr; incalcaterra@enea.it; isabelle.delval lee@irsn.fr; jan.borak@enel.com; jan.dotrel@ujv.cz; janosi@hu.inter.net; jari.puttonen@aalto.fi; jikim@kaeri.re.kr; jiri.zdarek@ujv.cz; jjchen@iner.gov.tw; jkgone@aec.gov.tw; jolana.ryd lova@sujb.cz; Pires, Jose <Jose.Pires@nrc.gov>; j ovica.riznic@canada.ca; jsc@csn.es; juergen.sievers@grs.de; jukka.mononen@stuk.fi; j unekl@uam.cz; jure.skodlar@gov.si; jussi.solin@vtt.fi; k211ckk@kins.re.kr; k651pjs@kins.re.kr; karl-fredrik.nilsson@ec.europa.eu; karl-heinz.herter@mpa.uni-stuttgart.de; katsunori_sugaya@nsr.go.jp; kazunobu_sakamoto@nsr.go.jp; kensaku_arai @nsr.go.jp; kikuo_takeshima@nsr.go.jp; kisaburo_azuma@nsr.go.jp; klaus.germerdonk@ensi.ch; klaus.heckmann@grs.de; kostas.xanthopoulos@ssm.se; krajmer.imrich@ebo.seas.sk; l.francia@unesa.es; ladislav.pecinka@ ujv.cz; lars.skanberg@ssm .se; laurent.foucher@asn.fr; laurent.streibig@asn.fr; leon.cizelj@ijs.si; lola.gomezbriceno@ciemat.es; louis.vanderwiel@minvrom.nl; ludovit.kupca@enel.com; lutz.lindhorst@anvs.n l; Sircar, Madhumita
<Madhumita.Sircar@nrc.gov>; makio_ nakano@nsr.go.j p; marc.petit@irsn.fr; masaaki_ishikawa@nsr.go.jp; masakuni_koyama@nsr.go.jp; mh lu@iner.gov.tw; michaela .weber@ensi.ch; michel.desmet@gdfsuez.com; mihdi.elmas@grs.de; miloslav.hrazsky@vuje.sk; ming.han@snclavalin.com; morishita.masaki@jaea.go.jp; mscibett@sckcen.be; Chokshi, Nilesh <Nilesh.Chokshi@nrc.gov>; nilgun.gerceker@taek.gov.tr; obushev@nikiet.ru; oliver.martin@ec.europa .eu; olli. nevander @oecd.org; on izawa.kunio@jaea.go.jp; panagiotis.manolatos@ec.europa.eu; paolo.contri@enel.com; paul.harrop@onr.gov.uk; pentti. varpasuo@partners.fort um.com; peter.haehner@ec.eu ropa.eu; pfan@csn.es; pierre. labbe@edf.fr; pis@ujv.cz; potapov@vniiaes.ru; r.krivanek@iaea.org; rachel.vaucher@asn .fr; rauli.keskinen@stuk.fi; rob.jansen@anvs.nl; Tregoning, Robert <Robert.Tregoning@nrc.gov>;
s.sa maddar@iaea.org; sabhardlwaj@npcil.co.in; sampsa.lau niainen@fortum.com; shingo_nomura@nsr.go.jp; shirimp@kins.re.kr; shunsuke_ogiya@nsr.go.jp; sskang@kins.re.kr;
suzuki.masahide@jaea.go.jp; sychoi@kaeri.re.kr; syed.ali @nrc.gov; takuya_toriyama@nsr.go.j p; thierry.payen@irsn.fr; tomohiro_hojo@nsr.go.jp; toru_iijima@nsr.go.jp; tshoji@fri.niche.tohoku.ac.jp; vanderschaaf@nrg.eu; vincent.deledicque@belv.be; vivekb@barc.gov.in; via dimir.jurco@enel.com; vladimir_magula@ibok.sk; yann.kayser@cea.fr; young@kins.re.kr
Subject:
[External_Sender) NRC Harvesting Workshop NRC harvesting workshop On March 7 - 8, 2016, the U.S. NRC, in cooperation with the U.S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI), is hosting an invited workshop on Material and Component Harvesting in Rockville, MD, USA. Harvesting is the extraction of materials, components, or structures from either operational or decommissioned nuclear plants. There is a long history of research programs using harvested materials. Often, these programs are complicated, costly, and risky, and there is a danger that the knowledge gained by the research is not justified by the effort and cost involved. In the near future, there will be more opportunities to obtain harvested materials from nuclear plants, both in the U.S. and internationally. The objective of the workshop is to identify technical needs best addressed by harvesting, identify possible sources of harvested materials, summarize lessons-learned and practical aspects of harvesting programs, and ultimately outline a process for developing a more efficient plan for harvesting materials.
An announcement for the workshop and a condensed agenda is attached. Please contact Rob Tregoning {rlt@nrc.gov), if you are interested in getting more information about the workshop or possibly contributing to the discussion.
Best regards Olli
\J Olli Nevander Nuclear Safety Specialist Nuclear Safety Division OECD Nuclear Energy Agency (NEA)
Tel.: +33 (0)1 45 24 10 58 Cell: ..___.._________,
(b )(6)
- e-mail: olli.nevander@oecd,ora www.oecd- nea.org Follow the NEA on:
iii,[)
From: Tregoning, Robert Sent: Wed, 11 Oct 201713:16:01 +0000 To: Hiser, Matthew Cc: Moyer, Carol;Hull, Amy;Purtscher, Patrick
Subject:
RE: NRC PLiM slides on Harvesting rlt).pptx Matt:
Think slides look fine; pending additional comments from others on this email, I'm okay with moving to Steve/Brian for review.
- 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, Matthew Sent: Wednesday, October 11, 2017 9:13 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Cc: Moyer, Carol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick
<Patrick. Pu rtscher@nrc.gov>
Subject:
RE: NRC PLiM slides on Harvesting rlt).pptx Hi Rob, Thank you for reviewing and for your input. I greatly reduced the sub bullets and sub sub bullets as you suggested (moving info to the notes) and the slides are much cleaner now.
I also added a couple figures to improve the visual interest.
Thanks!
Matt From: Tregoning, Robert Sent: Wednesday, October 11, 2017 6:59 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Cc: Moyer, Carol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick
<Patrick.Pu rtscher@nrc.gov>
Subject:
NRC PLiM slides on Harvesting rlt).pptx
Matt:
I have only a few comments (attached). I think the key messages are on point. My only real quibble is stylistic. The slides are basically a ton of words. It would be nice to have some representative graphics or illustrations of some of the points just to break up the words .
However, I know it can take time to develop/find good representative graphics and given our limited window, I don't know if you want to tackle this or not. At a minimum, I recommend eliminating many of the sub-bullets and sub-sub-bullets from the slides themselves and moving them to the talking points. This will help Allen out as well.
Good job with this on such short notice!
Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph : 301-415-2324 fax : 301-415-6671
From: Tregoning, Robert Sent: Wed, 22 Feb 2017 19:58:21 +0000 To: Hiser, IMatthew;Purtscher, Patrick
Subject:
RE: NRC Staff Attendance at Workshop Matt:
I'm still a bit unclear on session 5. Maybe I'm being dense PNNL (for NRC) Technical Information Needed for Informed Pradeep Ramuhalli Harvesting Decisions EPRI Sherry Bernhoft DOE Rich Reister NRC Robert Tregoning NRC Perspective on Future Harvesting Planning DISCUSSION Action Items and Closing Thought s What specifically do we want Sherry and Rich to cover in their remarks? I thought we talked yesterday about EPRI, DOE, and NRC just providing some closing thoughts and then opening it up to the group. I envisioned that the session would look like this
- 1. Pradeep's talk
- 2. General Discussion using seeded questions.
- 3. Summary of action items
- 4. Closing thoughts about workshop and harvesting in general: first DOE, EPRI, and NRC and then open it up to the group.
While I'm not opposed to the above layout, I just want to make sure that we're clear what we want Sherry and Rich to communicate in their separate talks prior to the discussion.
On another note, I think it would be good to indicate specific times for each talk, especially within session 2 - 4 to reinforce the notion that each speaker only has been allotted that amount of time.
Otherwise, it looks good but I'd really like to get titles © 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, Matthew Sent: Wednesday, February 22, 2017 1:27 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: NRC Staff Attendance at Workshop Hi Rob, I've attached the latest workshop attendee and webinar contact list. It's only a few external people. INL will be sending John Jackson who will give a brief talk on the NSUF sample library in session 3. Any other INL staff will participate via webinar.
I haven't heard back from EnBW, so I put together the agenda assuming they will not present. We could easily add them into session 4 if necessary. I've attached the final agenda. Please take a look and let me know what you guys think.
Thanks!
Matt From: Tregoning, Robert Sent: Wednesday, February 22, 2017 10:11 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: NRC Staff Attendance at Workshop Matt:
Who's on the final webinar list? I think we have like 3 or 4 people correct? Do we have final confirmation that INL will just send one person? I think adding Mark is fine as long as we're right around 30 people.
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, Matthew Sent: Wednesday, February 22, 2017 9:30 AM To: Tregoning, Robert <Robert.Tregon ing@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc .gov>
Subject:
NRC Staff Attendance at Workshop Pat Purtscher NRC Rob Tregoning NRC Matt Hiser NRC M ita Sircar NRC NRC Tom Koshy NRC NRR/DE NRC NRR/DLR NRC NRR concrete NRC Hi Rob and Pat, This is the current list of NRC staff attending the workshop. Tom Koshy indicated a NRR electrical wouldn't be needed (or if NRR sent an electrica l person then Tom wouldn't be needed), so I haven't included them on here. With these 8 NRC staff plus 23 external participants, we are at 31 total.
The other person that I have discussed this workshop with that has expressed strong interest in attending is Mark Kirk . Given the Belgian participation and interest in RPV topics, we might want to allow him to attend as well. That would put us at 32 total in the room. Thoughts?
Thanks!
Matt
From: Audrain, Margaret Sent: Thu, 29 Mar 2018 20:13:05 +0000 To: Tregoning, Robert;Purtscher, Patrick
Subject:
RE: ORNL visit Yes, that's probably fine. I can explain to Steve the delay.
From: Tregoning, Robert Sent: Thursday, March 29, 2018 2:30 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: ORNL visit Meg:
I have not heard back yet from pinging them again. Do you think you can wait until early next week for your travel or is that too late? If I don't get a reply back by Monday or Tuesday at the latest, we should call them.
RT Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671 From: Audrain, Margaret Sent: Thursday, March 29, 2018 2:26 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
ORNL visit
- Rob, Have you heard from the folks at ORNL about visiting them April 20? I need to get my travel in ASAP.
- Thanks, Meg
From: Hiser, Matthew Sent: Thu, 9 Nov 2017 08:01 :06 -0500 To: Purtscher, Patrick
Subject:
RE: phone call with INL Hi Pat, They've all accepted the meeting. I need to set up a bridge line, so you'll see an update to the scheduler ...
Thanks!
Matt Matthew Hiser Materials Engineer US uclear Re&,'Ulatory Commission I Office of uclear Regulatory Research Division of Engineering I C01Tosion and Metallurgy Branch Phone: 30/-415-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Purtscher, Patrick Sent: Thursday, November 09, 2017 8:00 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>
Subject:
phone call with INL What have you heard from INL about a phone call? I am working from home today but could call in .
Pat
From: Purtscher, Patrick Sent: Wed, 27 Jun 2018 10:08:05 +0000 To: 'Ramuhalli, Pradeep'
Subject:
RE: Phone call That will be fine, try my office line first, 301-415-3942 and if I don't answer, call my cell . _ I_ _ ...,l(t.>X?) ..
(b)(6) I ** I Pat From: Ramuhalli, Pradeep [2]
Sent: Wednesday, June 27, 2018 12:50 AM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>
Subject:
[External_Sender] Phone call Patrick, My apologies - the other phone call ran long and I completely forgot to give you a call afterwards. Can I call you in the morning tomorrow for a few minutes? Probably be around 9.30 or 10 am east coast time, if that is OK. I can call your office.
With best regards, Pradeep Pradeep Ramuhalli, PhD Senior Research Scientist, Applied Physics Group Pacific Northwest National Laboratory 902 Battelle Blvd.
P.O.Box 999, MSIN K5-26 Richland, WA 99352 Tel: 509-375-2763 Emai l: pradeep.ramuhalli@pnnl.gov http://www.pnnl.gov
Note to requester: The "INL NEID Material Library Search Result mah 1-26-18.xlsx" tile is too large to import into the FOIA Team's redaction software. This file will be provided in its original format (Excel) as a seperate document in this interim response. The remaining attachments are immediately following.
From: Hiser, Matthew Sent: Friday, January 26, 2018 3:59 PM To: Purtscher, Patrick; Audrain, Margaret; Tregoning, Robert
Subject:
Ex-Plant Harvesting Coordination Meeting Attachments: INL NEID Material Libra ry Search Result mah 1 18.xlsx; Harvesting Jan 25 Meeting Summary and Path Forward.docx; Harvesting Needs Prioritization 12-1-17.xlsx Hi everyone, Following up from our meeting yesterd ay, I have att ached a meeting summary/ path forward out line covering our current activities. I've also attached the latest version of the prioritization table as well as a modified version of the INL data base as noted in the meeting summary document.
I appreciate you guys continuing to push forward on this effort in my absence and will hopefully be baiek in a few months to pick things back up.
Thanks!
Matt
Harvesting 1/25/2018 Meeting Summary/ Path Forward Harvesting
- Actions o ALL - do prioritization before next meeting: first ad hoc, then by using criteria
- Next, socialize with NRR and NRO technical staff to solicit additional ideas for harvesting and a path to staff consensus on prioritized list o Pat - ANL spreadsheet
- Send requested NRC revisions to ANL
- Identified corresponding columns in INL database to ANL spreadsheet -
see column headings shaded green in attached Excel spreadsheet
- Pat/ Meg - follow-up with INL NFML as-needed o Pat/ Meg - follow-up on RIC poster as needed (per forwarded emails)
- Boneyards o ANL - Pat and Meg
- Visit complete, input complete pending tweaks to spreadsheet o PNNL - Pat coordinate with Pradeep
- Meg and Eric to visit in spring during regular PWSCC meetings
- Contacts: Pradeep Ramuhalli, Steve Doctor o ORNL-Meg
- Meg to visit in April during ICG-EAC travel
- Contacts: Mikhail Sokolov and Tom Rosseel o Battelle - Matt
- Matt to visit in June during EWI training in Columbus
- Contacts: Bruce Young, Paul Scott
- Prioritization table o Latest version attached to email. Use in advance of next meeting and determine future use of table/criteria for prioritization o Engage staff in NRR/NRO/RES for socialization / feedback
- RIC o E-Poster- with division management for approval (emails forwarded to Pat and Meg) o Bi laterals - how much to support each country?
Criteria Title Description Scoring Guidance H = high risk significance/ little to no available data MH = Medium-high risk significance/
limited data available Crilicalness of Technical Gap Harvesting to address critical gaps should be prioritized over less M = Moderate risk significance/ some Addressed essential 1cchnieal gaps data available ML = low to moderate risk slgnficance / H = High sufficient data available for regulatory MH = Medium-high decisions M = Medium L = Low risk significance/ large amount ML= Medium-low of data available L = Low Key considcrntions are the case of laborn1ory re1,licatio11 of aging H = Nearly Impossible to replicate mechanism and unique. field aspects of the aging mechanism. service enviroment / critically important Dcgradaiion mechanisms 1h01 arc harder to rcplicn1c with simulated to use harvested materials aging conditions would be of higher priority for harvesting. For MH = Challenging to replicate service example, simultaneous thermal and irradiation condi1ions arc enviroment / Important to use harvested difficult to replicate outs ide of the p lant environme nt. Alternatively, materials Importancc of Harvested accelerated aging may not be feasible for a mechanism sensitive to M = Possible w ith some limitat ions to Materials over Laboratory Aging dose rate. These two degradatrion mechanisms may be best evaluated replicate service enviroment I moderately using harvested materials. For unique field aspcc1s, legacy nrntcrials important to use harvested materials (e.g., fabrication me thods, composition) that are no longer available, ML= Not challenging to replicate service but may pli1y an important role in a potential degradat ion enviroment / less important to use mechanism, would have a higher priority than harvesting materials harvested materials that can be obiaincd from other sources wilh rcprcseniative L = V&ry easy to replicate service properties. envlroment / not Important to use harvested materials H = All plants There is greater value in developing knowledge to address an issue MH=AII PWRs Applicability 10 US Operating thal may be appl icable to a larger number ol'plants compared to one M = All BWRs or most PWRs Fleet that may only affect a relatively small number of plants. ML= 15 plants L = <5 plants H = No or very limited inspection methods available / low confidence In AMPs If mature inspection methods exist and are easy to apply to mo nitor MH = Limited Inspection methods degradation, harvesting may be less valuable. If inspect ion methods available/ low-to-moderate confidence i n Regulatory Cons;derations do not exist. harvesting may be essential to ensure confidence in the AMPs Related to Inspections and /\MPs assessment of age-related degradation in that particular M = Some inspection methods available /
component.The less confidence that NRC statThas in the moderate confidence In AMPs effectiveness of the relevant AMP, the higher priority for harvesting. ML = Good inspection methods available
/ medium-high confidence In AMPs L = Effective, well-accepted Inspection methods exist / high confidence In AMPs H = Highly irradiated (>5 dpa)
/\c1ivitics with higher costs and complexity are less atlractivc than MH = Lightly Irradiated / contam inated s imilar activities wirh lower costs and lhnt are s impler to execute .. M = Minimal contam ination or high effort Harves1ing cos1 and complexity For cxam1>lc, ltarvcs1ing unirmdiatcd concrclc or electrical cables is unlrradlated less expensive and less complex than harvest ing from the RPV ML= Unirradiated, moderate effort internals or 11te RPV. expected L = Unlrradlated, low effort expected The ability of a potential harvesting program to provide timely results to support either a 1echnical or regulatory need is important.
Timeliness of results Having high confidence lhat rcsuhs will be timely increases the priority.
Avai labili1y of ma1erials for The availabi lity of materials to harvest for a pan icular dala ne.ed is harvesting clearly essential and increases the priority.
Ba.slelnfo Technleal Criteria Prolect Soeclflc Importance of Harvested Cost I Complexity Availability of Purpos* I Test ing Criticalness of TCK:hnlcal Rogul.atOl')I ConsiMrations Timeliness of N eed Description Teehnlcal Knowtedge Gained M*terl.ats over U boratory Appflcabilfty to US Operetlat9 Fleet Score Avet'age BHls for Priority mateNls for Planned Gap Addressed Related to Inspections and AMPs results A ina harvutina METALS Vaid swelling. mechanical likely extent of void s.weiltng 1n PWRs during extended operation and Sco,e Comment Sc~* Comment Sc= Comment Score Comment:
=* Comment 1Monh ~ence 1eac1ot intemats nt....--t..s, lASCC im.-.-t oo crad:'ino TSO TBO Fracture tous;tlneSs dala ln real Therm..., aged unirradiated Fracture tougMe:Ss and oondi6ons 10 compcWe tlO accder81ed CASS microstructura a""'"data Moderate lluence (1*2 d~) Frac:ru-e tougMe1>s 1;md Fraclure I~ $$ data nel;M'" lirrit CASS m5ctostructure r-..rinn. further evaluabon Oetsnnaie whether sec mitigation med'lods are effective at preven1Xlg Metallic components with NOE and destructiY9 8.1(8m.\alion s ec: ettectrveness or NOE at detection and Sil:lno Metallic comc:ionents with N OE and destrudJYe Detennl"le whether f a ~ flaws are limitina £12'ino*elite @XBmmation resen1 in hiah usaae locarions
Purpose I Testing Altcmatlve l o Priority/ Unique aspccl s of ISi Ne*d Oucrlptlon Pl anned T*chnlcal KnoWledge Gained B*neflt I Si gnificance Cost Harvesting? Value Basis tor Priority harvestod maleria Is avallablility ?
METALS RPV
- High nuance & high Measure lluence, High cost nol justif.ad by benefit shift vessel wllh well~ tougtv'less, & chemlslry as Increases confidence In given survelllarlee specimens Vinlage compositions established unirradiated a function ol through- Throu gh lhickness sedion to valida1e existing regulatory and well-established and irradiation properttes thickness position r1uenc:e & attenuation modols af)proach High No LOW envlltlomont trnnd conolations cond,Uons Pro111oes data supporting evolution Enable measurement of from the use of oo"etalive (Charpy- High cost nol juslifllBd by benelit both the: Ctlarpy trar\SIUon bas&d} to diroct measuremet1t l ncteases confidence in givfln surveillar'M:18 specimens Vintage compos,lions RPV - $ .1;1 mples from vinually curve .1;1 nd m,eiste, curve (fr,eic;:ture toughness-based) existing regut1;1tory 1;1nd ~ll~Sl!i!btished end realisiic i"1;1diation anyvti:ssel transitloo tempetature TO approacnes appro.aeh High No LOW envlulement trend co,relations eonOflions
Purpose I Tesling Altcmatlve lo Priority I Unique aspecls of ISi No.d Description Planned T*chnlcal KnoWledge Gained B*noflt I Significance Cost HarvHting? Value Basis for Priority harvostod materials avallablility ?
ELECTRICAL Low and medium vol1age cables. Medium HIGH Cables protected with fire retardant coating 1E MOVs from harsh and mild environments Medium 1E Air operated vatws: 4160 1E breakers, Low 1E Molded case txeakers 4SOV. 250V DC. 125 V DC , Low 1EReia)'S rrOO"lmlld environment GE - HFA, Agasta t timing relays, any from Wes1inghoose, Poner Brumfield, Sluthers Dunn etc.., Low Batteries Low Electrical penetrations Fire reseatch lnt01'osl Electrical enclosures DlstrlbubOn: switch!)eat.
MCCs, LC$ I Control:
li0f'!&Sh08, SSCP, ASP. elc.
Purpose I Testing Altcmatlve lo Priority I Unique aspecls of ISi Ne*d Oucrlptlon Planned T*chnlcal KnoWledge Gained B*neflt I Significance Cost Harvesting? Value Basis for Priority harvostod materials avallablility?
METALS CONCRETE FIMs data gap fOf Slrvctures e ~ d to hi9h Chimge in properties ctt.ie extended pltlnt rndla tion to irradiafon effects Loss of sb'ength ctue to irradia\Jon oporaoon High HIGH Post-tension&d structures Medium LOW Conosk>n of reinforcing steel.
tendon, liner, embedmen1 Medium LOW Spent fuel pool Md transfer carial-boric acid attack on concmte In PV\l'Rs Medium LOW Alkali Aggregate Reaction Medium LOW Validate assumptions of Laroe structural sectlons. fot Eflects of concrete aging aging effects at larger teS,ting Qn 51ructural Ciilpacity SC~ High LOW
From: Ramuhalli Pradeep To: Hiser Matthew: Purtscher Patrick Cc: Knobbs Katie Note to requester: Attachment is Subject : [External_Sender] Updated example immediately following.
Date: Tuesday, May 3, 2016 1:41 :55 PM Attachments: Examole-DM-rev1 .docx Matt, Pat:
The updated document is attached. More to come with CASS and the ha rvesting plan in a week or so.
Pradeep Ramuha ll i, PhD Senior Research Scientist, Applied Physics Group Pacific Northwest National Labora to ry 902 Batte lle Blvd.
P.O.Box 999, MS IN K5-26 Richland, WA 99352 Tel: 509-375-2763 Email : pradeep.ramuhall i@pnn l.gov http://www.pnnl.gov
Draft Examples of Harvesting Prioritization Process
- 1. Ex-plant Harvesting
- a. May help address knowledge gaps in cases where replacement/repair is not possible-i.e., all cases where t he material is going to stay for the duration of the license extension; condition assessment (CA) may or may not be possible on these.
- 2. Harvesting
- a. Literature and Sources
- i. EMDA PIRT, LWRS, LTO, NRC-RES, EDF-MRI, harvesting requests to date ii. Materials divided up into piping and pressure boundary components (metal),
cables,. concrete - all non-replaceable iii. Collate information across these sources as a first cut at identifying harvesting priorities.
- b. Criteria for prioritizing harvesting: Initial criteria focus on the ability of harvested materials to address gaps in materials performance knowledge for SLR. Available documents from the EMDA assessment identify the susceptibility of various materials in relevant environments to a number of degradation mechanisms. In addition to the susceptibility, i nformation is available on the knowledge and confidence in the available knowledge regarding this "Material, Degradation Mechanism, Environment" (<M,M,E>)
combination. In parallel, information in the SLR guidance documents associate similar combinations with relevant AMPs, while other available documents provide insights into the specific knowledge gaps. Questions that would need to be answered in line with these general criteria are:
- i. Is the combination of <M,M,E> rated "High susceptibility" in the EMDA review?
Note tlhat the PIRT review documents for cables and concrete may not be readily available for answering this question.
ii. Is the combination of <M,M,E> rated "Low knowledge" in the EMDA review?
iii. How easy it is to simulate <M,M,E> in the lab?
- 1. Of the environments of interest, radiation environments are I ikely to be the most challenging to duplicate in a lab environment. This is more so for low dose, long term irradiation and is a concern if dose rate effects exist that may influence the mechanism initiation and growth.
Harvesting should focus on irradiated materials where possible.
iv. Is there OE associated with the combination of <M,M,E>? If OE is available, especially for low susceptibility <M,M,.E> (for instance, atmospheric SCC), it may be worth harvesting the material if possible.
- v. Expected benefits from harvested materials
- 1. Can harvested materials be used to address a critical gap in knowledge?
See item (iv) above as an example.
- 2. How will materials be used to address critical gaps? In addition to lab studies using characterization tools, can the material be used in
degradation initiation and growth studies? In cables aging, such studies have been proposed (wear-out aging) .
- 3. Which AMPs are applicable to address the combination of <M,M,E>?
Does OE in particular point to additional AMPs that may be applicable?
- 4. Do ISi methods exist to reliably detect and size degradation in <M,M,E>?
Can harvested material be used to develop/improve ISi for SLR?
Note: Incorporate NRC Safety/regulatory aspects/perspectives - regulatory benefit.
- c. Examples - In the interests of developing the process for prioritizing harvesting further, several examples are being considered. The two listed below are being used to fine-tune the process. Both of these are considered low priority for harvesting (one because of low susceptibility, the other because of significant knowledge already available).
<M,M,E> = <82/182 Welds, SCC,[PWR Primary,borated demin water (normally stagnant),l00F-lSOF,640 psia]>
Components: ECCS Accumulator Piping to Cold Leg Criteria Value Additional Additional Comments Values for information criteria, if any EMDA Low-Medium Temperatures Susceptibility considered too low for Score sec to be concern .
However, cracking is a generic concern for these materials.
EMDA Generally High Knowledge Score Critical gaps in Crack initiation time Crack initiation knowledge probability considered low for the environment listed.
SLR GD Nothing obvious AMP XI. M7, AMPs are for listed for Ml,M2,M19: components similar to environment for this SG, Water the one listed above.
example. Chem., ISi OE? No Nothing was identified in LER searches to date AMP Audit Info? TBD Need to determine if this stays as a criterion, or if it is dropped. The intent is to identify addition al AMPs (or additional detail for existing AMPS) for the
<M,M,E> combination.
ISi Capability for Yes in pressure Detection and sizing Detection/Sizing boundary capability TBD but components. VT for generally capable of internals. meeting acceptance
Unique Field Vintage materia l; Aspects, if any cracking from OE if applicable.
Ease of Lab Medium/High Replication Applicability of Material and Harvested environment can be Material for duplicated in lab Addressing relatively easily.
Critical Gaps Unless there are other operational specific aspects (such as cracking OE, or irradiation, or water chem istry issues), likely that studies can be hand led without harvesting.
Avai lability of TBD Needs input from material for utilities harvesting Cond it ion sec morphology Potential need to Assessment/ISi (COD, shape) va lidate methods for Needs simu lating sec.
Cond it ion assessment methods for SLR may be unconventional.
Given low susceptibility, th is may not be a major concern.
Example: <M,M,E> = <82/182 Welds, SCC,[PWR Primary,reactor water,653F,2250 psia]>
Components: RCS Pressurizer DM Welds, RPV DM welds, RCS SG, ECCS Accumulator piping to Cold Leg, ECCS eves Piping to RCS Cold Leg Criteria Value Additional Additional Comments Values for information criteria, if any EMDA Generally High Susceptibility Score EMDA Generally High Knowledge Score Critical gaps in Crack growth rates, Multiple studies knowledge crack initiation time available on SCC initiation and growth in nickel alloys and DM welds, mitigation proposa Is (overlay) also being studied.
SLR GD Variety of structures AMP XI. M7, and similar Ml,M2,M19:
components SG, Water identified, but no Chem., ISi specifics on materials available OE? Yes AMP Audit Info? TBD ISi Capability for Yes in pressure Detection and sizing Detection/Sizing boundary generally capable of components. VT for meeting acceptance internals. crit eria set in ASME BPV.
Unique Field Vintage material, Aspects, if any operational stress, flaws in weld from fabrication.
Ease of Lab Medium/High Replication Applicability of TBD Harvested Material for Addressing Critical Gaps
Avai lability of TBD Needs input from mat erial for utilities harvesting Cond ition sec morphology Potential need to Assessment/ISi (COD, shape), va lidate methods for accessibility for ISi simu lating sec.
Condition assessment methods for SLR may be unconventional.
Access issues may dictate POD and siz ing performance.
Harvested materials useful to study issue and develop workarounds as needed .
From: Ramuhalli Pradeep To: Hiser Matthew Subject : (External_Sender] RE: Synopsis on Harvesting for IAEA PLiM Date: 24 2017 4 21 4 Wednesday, May * = : o PM INote to requester: Attachment is immediately following.
Attachments: Harvesting IAEA Plim 2 oage svnoosis-or.doc)( .
- Matt, Th is looks good overall. I just had a few edits/comments. Attached is a marked up version (using track changes).
With best regards, Pradeep Ramuhal li, PhD Tel: 509-375-2763 Emai l: pradeep.ramuha 1li@pnn l.gov From: Hiser, Matthew [3]
Se nt: Monday, May 22, 2017 12:19 PM To: Ramu haIii, Pradeep <Pradeep.Ramuha ll i@pn nl.gov>
Subject:
FW: Synopsis on Harvesting for IAEA PLiM Hi Pradeep, In the last couple days, w e've* decided to throw in an abstract at PLiM on harvesting. Please take a look at what I attached and provide any feedback.
If you're planning to attend PLiM, I t hink it'd be best for you to give the ta lk. If not, another staff in our office, Ca rol Moyer, will be attending and ca n give the presentation.
Tha nks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew Hiser@nrc.gov From: Hiser, Matthew Sent: Monday, May 22, 2017 2:47 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregonjng@nrc.gov>; Purtscher, Patrick <Patrick Purtscher@nrc gov>; Moyer, Carol <Carol,Moyer@nrc gov>
Cc: Frankl, Istva n <Istvan Frankl@orc gov>
Subject:
Synopsis on Harvesting for IAEA PLiM I have attached a draft 2 page synopsis on harvesting for the IAEA PLiM conference. The plan wil l be for Carol to give t he presentation at the conference, but we need to submit the abstract by this week if possible (deadline was last Friday).
If possible, please take a look and provide comments or edits to the abstract by Wednesday to su pport su bmission this week.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research
Division of Engineeri ng I Corrosion and Met allurgy Branch Phone: 301 -415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov
Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M atthew Hiser, Patrick Pu rtscher, Pradeep Ramuhalli, Amy Hu ll, Ro be rt Tregon ing, and Carol M oyer In the U.S. and global nuclear industry, two ria>cent development s include strong interest in extended plant operation and a number of nuclear power plants (NPPs) shutting down. In the U.S., there is strong interest in extending NPP lifespans through subsequent license renewal (SLR) from 60 to 80 years.
Extended plant operation and SLR raise a number of technical issues that may require further resea rch to underst and aging mechanisms. U.S. utilities and the NRC have focused on aging in four key areas: the reactor pressure vessel (RPV), RPV intern als and piping, concret e, and electrical component s.
Meanwhile, in recent years, a number of nuclear plants, both in the U.S. and internationally, have shut down or announced plans to shut ~own. Unlike in the past when there were very few p lants shutting Commented [RP*1]: Should some reasons (economics, down, these new developments provide opportunities for harvesting components that were aged in severe aging and degradation, etc.) be given for these decisions, given the earlier statement that there is a strong representative light wat er reactor (LWR) envir onments. In a relat ed development, economic challenges interest In NOT shutting down plants t ill they are 80?
for t he nuclea r industry 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 t o allow maximum benefit and va lue for future research programs.
NRC has recently undertaken an effort, with the assistance of Pacific Northwest National Lab (PNNL), to develop a st rat egic approach to harvesting of aged materials from NPPs. Due to limited opportunities, past harvesting effort s have been reactive t o individual plants shutting down and beginning decommissioning. Given the expected availability of materia ls from numerous plants and anticipated research needs to better understand aging out to 80 years of operation, NRC is pursuing a more proactive approach to prioritize the data needs best addressed by harvesting and identify the best source~ of materials to address those high-priority data needs.
The first step in this strategic approach to harvesting is to prioritize data needs for harvesting. A data need describes a particular material-environment combination and should be Gained-as detailed as appropriate in terms of the material (alloy, co mposition, et c.) and environment (temperature, fluence, chemistry, etc.). A number of criteria may be considered when priorit izing data needs for harvesting, including:
- Applicability of harvested material for addressing critical gaps o Prioritize harvesting for critical gaps over less essential Elata AeeElstechnical gaps.
- Ease of laboratory replication of the environment-material combination o For example, simultaneous thermal and irradiation conditions may be d ifficu lt to replicate or a mechanism sensitive to dose rate may not be good for accelerated aging.
- Unique field aspects of degradation o For example, unusual operating experience or legacy materials (fa brica,t ion method s, composition, etc.) that may no longer be available.
- Fleet-wide vs. plant-specific applicability of data o There is generally greater va lue in addressing an issue applicable to a larger number of plants.
- Availability of reliable in-service inspection (ISi) t echniques for the material/ component o If inspection methods are mature and easy to apply to monitor and track degradation, perhaps the effort af..for research with harvested materials is not needed.
- Availability of material for harvesting o The necessary materials/ compo nent s must be available t o be harvested.
- Harvesting cost and complexity o For example, harvesting unirradiated concrete or electrical cables should be less expensive and less complex tha n harvesting from the reacto r internals or RPV.
- Timeliness of the expected research results relative to the objective.
These potential criteria provide a systematic approach to prioritize data needs for harvesting. Different organizations may weigh and co nsider each of these criteria differently based on their interests and perspective, but each criteria is likely relevant to some degree for any organization. NRC is interested in engaging with other organizations to prioritize data needs for harvesting and identify areas of common interest.
Another activity NRC Is pursuing is the potential development of a database for sources of materials for harvesting, wh ich could include both previously harvested materials and those available for future harvesting. This database would allow for aligning of high-priority data needs to the available sources of materials. As with the data needs effort, the level of detail for the sources of materials database should be appropriate for the important factors for decision-making. NRC is interested in engaging with other organizations to develop a database for sources of materials for harvesting.
NRC's experience is that harvesting ca n 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 wit h other stakeholders, including t he plant from which harvesting will t ake place, are keys to success. As specific harvesting opportunities are identified through this strategic approach to harvesting, NRC welcomes opport unities for cooperation and leveraging with other interested research organizations.
From: Hjser Matthew To: Ramuhalli Pradeep Cc: Purtscher Patrick: Audrain Margaret: Lio Bruce
Subject:
RE: RE: PNNL Visit Date: Thursday, August 2, 2018 4:25:00 PM Attachments : NRCI Lin-Dunn Agenda1 docx Hi Pradeep, Hope you are doing well! I will be visiting PNNL next week and hope we can find a little time to meet to discuss harvesting. I just spoke with Bruce about the agenda for our time there and it looks like maybe Monday morning or Tuesday afternoon might be good times for us to meet.
I also met with Meg and Pat this morning to hear about Meg"s visit a couple weeks ago and the latest on the PNNL report. My thought was we could discuss a couple topics while we have the opportunity in-person:
- the latest on incorporating comments on the report (any questions you may have on how to best address the comments)
- the plans for an inventory of harvested materials at PNNL (I understand much of this is already being done for Carol Nave's contract)
Looking forward to seeing you next week!
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 /-4 / 5-2454 I Office: TWFN 10D62 Matthew Hjser@nrc gov From: Ram uhalli, Pradeep [m ailto:Pradeep.Ramuhalli@pnnl.gov)
Sent: Wednesday, July 11, 2018 11:33 AM To: Hiser, Matthew <Matthew.H iser@nrc.gov>
Cc: Purtscher, Patrick <Pat rick.Purt scher@nrc.gov>; Audrain, M argaret
<M argaret.Aud rain@nrc.gov>; Lin, Bruce <Bruce.Lin@n rc.gov>
Subject:
[Ext ernal_Sender] RE: PNNL Visit
- Matt, Excellent ! Yes, currently I expect to be in town on those dates and should be available to meet. I will let you know if anything changes.
With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Emai l: pradeep.ramuha lli@pnn l.gov From: Hiser, Matthew [maj lto:Matthew.Hjser@nrc.gov]
Sent: Tuesday, July 10, 2018 10:21 AM To: Ramu haIii, Pradeep <Pradeep Ramuha lli @pnn l gov>
Cc: Purtscher, Patrick <Patrick,Purtscher@nrc.gov>; Audrain, M argaret
<Margaret.Audra io@nrc.gov>; Lin, Bruce <Bruce.Lin@nrc.gov>
Subject:
PNNL Visit Hi Pradeep,
I hope all is well with you . I know you 've been in contact with Pat recently on finalizing the report and cataloguing the available materials at PNNL and Meg Audrain will be visiting next week.
I just wanted to let you know that I will be visiting PNNL (along with Bruce Lin and Darrell Dunn from NRG) on August 6-8 for a dry cask storage contract Bruce is managing at PNNL. If you are in town and available at all those dates, it may be a useful opportunity to meet and discuss the harvesting program , particularly any final tweaks to the report or follow-up from Meg 's visit regarding the previously harvested materials at PNNL.
Looking forward to the visit next month and hope we will be able to find some time to meet while I'm there.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 1Office : TWFN 10D62 Matthew Hiser@nrc gov
Inspection Technology Demonstration on PNNL Dry Storage Cask Mock-ups Flaw Detection Pacific Northwest NATIONAL LABORATORY Proucl/y 0/X!'<llecl b)' Battcllc Siuoo 1965 Dates: August 6-8, 201 8 Host: Ryan Meyer RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 10S: Max Wiedmann EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin, Matthew Hiser DATE/TIME TOPIC LOCATION PARTICIPANTS MONDAY, August 6, 2018 7:30 am - 8:00 am Pick up Visitor Badges Discovery PNNL: Ryan Meyer, Sharon Hall to 3440 Bailey Test Area RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 10S: Max Wiedmann EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin, Matthew Hiser 8:00 am - 9:00 am Pre-job Briefing 3440 Test PNNL: Ryan Meyer, Sharon Area Bailey, Ron Mabry RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 10S: Max Wiedmann EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin ,
Matthew Hiser Optional (PNNL): Emily Schinell, Adrian McCall, Drue Col/Ins, Laurie True, Donald Kelly 9:00 am - 10:00 am Unpack Equipment 3440 Test PNNL: Ryan Meyer, Ron Mabry Area RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 10S: Max Wiedmann EPRI: Jeremy Renshaw MONDAY, August 6, 2018 (continued) 10:00 am - 11 :00 am NOE Technology Electrical Safety 3440 Test PNNL: Ryan Meyer, Bobby Inspection Area Sparks Preview Mockups RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 10S: Max Wiedmann EPRI: Jeremy Renshaw
Pacific Northwest NATIONAL LABORATORY Pmu,11)* C)fwrot,d hy Dalele Sm<< 19M DATE/TIME TOPIC LOCATION PARTICIPANTS 11 :00 am - 12:00 pm Set-up and Testing on Horizontal Mock-up 3440 Test PNNL: Ryan Meyer (RTT and EPRI) Area RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 12:00 pm - 1:00 pm Working Lunch: Discuss Morning TBD 105: Max Wi,edmann Progress/Challenges EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin ,
1:00 pm - 6:00 pm Continue Testing on Horizontal Mock-up 3440 Test Matthew Hiser (RTT and EPRI) Area Tuesday, August7, 2018 7:30 am - 12:00 pm Continue Testing on Horizontal Mock-up 3440 Test PNNL: Ryan Meyer (RTT and EPRI) Area RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 105: Max Wi,edmann EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin ,
Matthew Hiser 12:00 pm- 1:00 pm Working Lunch: Discuss Morning Progress, TBD PNNL: Ryan Meyer Review Remaining Testing RTT: Jamie Beard, Andrew Bryant, Steve Glovsky 1:00 pm - 6:00 pm Continue Testing on Horizontal Mock-up 3440 Test 105: Max Wiedmann (RTT and EPRI) Area EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin, Matthew Hiser 7:00 pm Dinner TBD Wednes day, Augus tS, 2018 7:00 am - 9:00 am Mock-up Re-orientation 3440 Test Area 9:00 am - 12:00 pm Testing on Vertical Mock-up 3440 Test PNNL: Ryan Meyer (RTT, EPRI, and IOS) Area RTT: Jamie Beard, Andrew Bryant, Steve Glovsky Testing on Plate Specimens 105: Max Wi,edmann (EPRI) EPRI: Jeremy Renshaw NRC: Darrell Dunn, Bruce Lin ,
12:00 pm - 1:00 pm Working Lunch: Discuss Morning Progress, TBD Matthew Hiser Review Remaining Testing 1:00 pm - 6:00 pm Continue Testing on Vertical Mock-up 3440 Test (RTT, EPRI, and IOS) Area Testing on Plate Specimens (EPRI)
Pacific Northwest NATIONAL LABORATORY 3440 Test Area ... PNNL Core Campus r Hal ToMAMll[R
Note to requester: This note for this slide did not transfer: "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."
Basic question for SLR: Is there adequate confidence that the material will be capable of meeting its functional goals through the end of SLR?
(my opinion! ) Defense in depth through SLR is likely to need Demonstrate that the component will have limited degradation in function due to material aging past 60 physical years of operation (with reasonable confidence)
Implement program to ensure that components can be appropriately monitored to ensure timely detection and mitigation of any aging-related issues Note to requester: This note for this slide did not transfer:
"Left it in hidden mode for now (as a reminder of some of the drivers) - will delete before going final."
EMDA/PMDA, GALL-SLR, Various NUREG/CR, DOE-LWRS, EPRI-LTO, IAEA-TECDOCs, Other DOE/EPRI publications ...
Key needs:
Understand materials degradation processes that contribute to degradation growth Availability of adequate NOE and condition monitoring techniques Crack growth Development of Development of Smal l crack controlled by
~
crack nucleation crack precursors linkage and fracture b.O C
Q) sites (sli p bands, IGA, growt h mechanics
_J
.::it:.
et c.)
u (nm-µm length scales) ro
~
(100s µm length scales) (mm le ngt h scales and u (µm length scales) higher)
Time Key Idea: The two key needs highlighted above are related, and will need to be jointly addressed for long-term operation needs Note t o requester: This note for this slide did not transfer: "DOE includes national laboratory complex. Degradation - if not detected and mitigated - can lead to loss of structural integrity."
Level of specificity varies Specific compositions vs generic alloys Specific conditions vs generic drivers of degradation Increased emphasis on non-metallic materials Identified knowledge gaps in materials degradation and condition monitoring Key finding: Certain materials and mechanisms, within the context of long term operation, may be considered a high priority for addressing technical gaps in degradation initiation, growth and detection .
Dominant effects and synergistic effects Thermal, coolant, and neutron Flow Accelerated Corrosion Stress Corrosion Cracking A need for multiple classes of materials Vibration Fatigue (incl. Fretting}
Dose, dose-rate, spectrum effects Corrosion (Crevice, MIC, Pitting}
Microstructural variations Design & Construction Thermal Fatigue Irradiation-assisted processes Erosion-Cavitation Degradation initiation and growth studies Over-stressed I Over-pressurized Water Hammer Particularly metals Human Error Residual stress Unreported 0.4%
5164 reported failures Mechanical properties Corrosion Fatigue 0.3%
Mitigation actions --------------
Severe Weather (Freezing} 0.1% I 0% 5% 10% 15% 20% 25% 30% 35%
Annealing, peening, ... Lydell 2007 (US Pipe Failure Data by Degradation Mechanisms and Other Sources)
Key Insight: These data needs must be addressed for materials that exist in plants today
Observables that result from aging of materials in real-world environments Measurement targets for condition monitoring Important for cables, concrete in particular Benchmarking of accelerated aging-produced degradation Real-world degradation examples Applicability of lab studies to quantify detectability Detection and sizing limits under real-world conditions Field specimens - impact on detection and sizing Vintage materials not always reproducible in the lab Key Insight: These data needs must be addressed for materials that exist in plants today
2010 2000 1990 1 1980 1970
~ 1960 1950 1940 1930 Vibration TP304 Corr.- Erosion- MIC TP347 PJVSCC fatigue IGSCC fatigue corr . IGSCC Note to requester: This note for this slide did not transfer:
"Interesting graphic - not sure if this should be included in previous charts, or removed. Will discuss."
7
Benchmarking laboratory-scale studies on materials aging Identifying constraints on materials/components replacement in operating plants.
Understanding aging mechanisms and precise margins to failure Determining specific methods for condition assessment that may be applied to these components in the field, to assess component aging.
Answer questions that help bridge the gap from the laboratory to the real-world Note to requester: This note for this slide did not transfer: "Essential to provide reasonable assurance that the materials/components w ill continue to provide adequate defense- in-depth through the end of life.Harvesting from closed plants, or during component maintenance/replacement activities."
Unique field aspects, if any, that drive the importance of harvesting the material Unusual OE - harvest to better understand phenomena Ease of laboratory replication of material and environment combination Applicability of harvested material for addressing critical gaps (dose rate issues, etc. , for instance)
Availability of reliable ISi techniques for the material Availability of material for harvesting Ultimately, harvesting decisions must tradeoff knowledge gain vs costs (including dose to workers)
Criteria ualitative Assessment Comments Unique Field Aspects, if any Vintage formulations, depending on 10-12 manufacturers of vintage cable in U.S. fleet. Within a manufacturer, real-world conditions. single plant, cable types and manufacturers can vary.
Ease of Laboratory Replication Low-medium (long-term aging studies I necessary)
Applicability of Harvested Material for High - Wear-out aging a possibility Requires knowledge on plant conditions Addressing Critical Gaps Condition Monitoring/ISi for detection and Low to medium. Unclear how well proposed Access limited; long-range methods are not fully understood sizing techniques would perform for low dose I rate, low temperature aging of insulation.
Availability of Material for Harvesting TBD EMDA Susceptibility Score Generally High (2-3)
EMDA Knowledge Score Medium (mostly 2) Some data exists on long-term aging. Inverse temperature and synergistic effects are a concern. Inverse temperature effects apply and CSPE is formulation-specific.
GALL-SLR Documented as a potential issue AMP updates ongoing OE? Yes Documented in industry publications Level of Understanding of Mechanism Medium See knowledge gaps below (environmental factors, initiation and growth of degradation, related factors)
Options for Mitigation Low Ease of Replacement Medium Possible but can get expensive depending on specific I
I locations Amount of Use (in a plant and fleet-wide) High LV and MV cables extensively used in plants Contribution to data base for dominant effects, synergistic effects, dose rate effects for understanding accelerated aging vs. field aging, develop and qualify condition monitoring techniques HARVESTING PRIORITY HIGH
Will discuss format and add.
CASS: Open questions for SLR Loss of fracture toughness due to thermal aging Unknown: How radiation interacts with thermal aging Current programs - laboratory studies (accelerated aging) and simulations Example of data Needs: Benchmarking accelerated aging studies, fracture toughness changes between 0.5 dpa and 5 dpa, interaction of neutron and thermal Graphics TBD effects Internals: Open questions for SLR Materials performance with irradiation Crack initiation and growth (IASCC)
Current programs - studies on harvested materials (limited by available materials)
Example of data needs: factors contributing to crack initiation and growth, high-fluence effects on representative LWR components
Concrete Unknown: Inspection techniques for liner corrosion, ASR Example of data needs: Critical flaw sizes, materials with aging-related degradation for benchmarking lab specimens Cables Unknown: What observables may enable rapid assessment and localization of degradation, detection thresholds for field-aging Example of data needs: Aged materials representing spectrum of material formulations, CM measurements on fielded cables (benchmark measurements from lab-aged specimens)
Note to requester: This note for this slide did not transfer: "Can add examples for CASS, etc."
Note to requester: This note for this slide did not transfer: "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."
Multiple projects spanning cancelled, disconnected, SAFSTOR, DEGON(?), etc. plants Zion, Zorita, Crystal River 3, Shoreham, River Bend 2, Ginna, ...
Materials spanning RPV and piping (base metal and welds), cables, internals (baffle former bolts)
General lessons learned Uncertainty about operational environment for materials (especially for localized exposure)
Cost can be significant Supporting resources may be scarce Planning for harvesting must start significantly in advance of opportunity Ultimately, harvesting decisions must tradeoff knowledge gain vs costs (including dose to workers)
Why - Technical gaps Identify the knowledge gaps that will be addressed by this specific harvesting opportunity How - R&D plan Clearly articulate how the harvested material will be used to address knowledge gaps Determine resources (including funds) for R&D on harvested material Who and When - Resource availability and planning for harvesting Secure necessary engineering and labor support - need to justify and prioritize harvesting Timelines and schedule development Can be the greatest challenge in developing informed harvesting decisions What -Availability Post-harvesting planning - should cover everything from shipping to receipt of material and handling for R&D purposes and waste disposal.
Much of this can be assembled prior to material becoming available, but may need to be modified to account for ground realities.
Clear identification of appropriate material - labels, tags, etc.
Critical when harvesting is being coordinated with other activities (maintenance, decommissioning, etc.)
Operational environment documentation General parameters (temperature, radiation)
Proximity to other components Physical contamination Material condition (degradation and aging) and special features Cracking or other unique degradation conditions Welds, terminations, base metal, ...
Detailed knowledge capture about component condition can simplify planning when material becomes available for harvesting.
Add Crystal River 3 documentation, Zion documentation and planning Physical Category, construction info, manufacturer, Material composition, dimensions, special features Service Info System, service application, how often used, safety/maintenance rule significance, age in service Installation location, connected components, supporting structures or conveyances Stressors Installation stressors, in-service environmental, other OE Testing history, failure or degradation
Note to requester: The attachment, "NRC_Materials_and_Component_Spreadsheet_of_lnventory_at_PNNL_Draft.xlsx" file is too large to import into the FOIA Team's redaction software. This file will be provided in its original format (Excel) as a seperate document in this interim response.
From: Lin, Bruce Sent: Tue, 28 Aug 2018 16:03:59 +0000 To: Hiser, IMatthew;Nove, Carol Cc: Purtscher, Patrick;Audrain, Margaret
Subject:
RE: inventory of ex-plant materials at IPNNL Matt, Please see attached inventory list. PNNL also put together a presentation with photos. I have saved a copy at G:\DE\CIB\PNNL NDE Reports file name "NRC_Materials_and_Component_lnventory_at_PNNL_Draft.pptx" Bruce From: Hiser, Matthew Sent: Tuesday, August 28, 2018 11:32 AM To: Nove, Carol <Carol.Nove@nrc.gov>
Cc: Purtscher, Patrick <Patrick. Purtscher@nrc.gov>; Audrain, Margaret <Margaret.Audrain @nrc.gov>;
Lin, Bruce <Bruce.Lin@nrc.gov>
Subject:
RE: inventory of ex-plant materials at PNNL Thanks Carol!
It sounded like from our discussion with Pradeep that what they are putting together for you should "bound" what we are looking for. Can you share with us the inventory of materials whenever you receive it from PNNL?
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division ofEnginccring I Corrosion and Metallurgy Branch Phone: 301-415-24541 Office: TWFN 10D62 Matthew.Hiser@nrc.gov From: Nove, Carol Sent: Monday, August 06, 2018 8:55 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Audrain, M argaret <Margaret.Audrain@nrc.gov>;
Lin, Bruce <Bruce.Lin@nrc.gov>
Subject:
RE: inventory of ex-plant materials at PNNL Hi Matt,
Feel free to talk to Pradeep about the inventory of materials being conducted under my program. If there is some other info you need, let me know so that I can ask them to include it.
- Thanks, Carol From: Hiser, Matthew Sent: Friday, August 03, 2018 8:55 AM To: Nove, Carol <Carol.Nove@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>
Subject:
FW: inventory of ex-plant materials at PNNL Hi Carol, I will be heading to PNNL next week for a trip focused on NMSS dry storage work there with Bruce and Darrell. However, while I'm there I'm planning to spend a little time meeting with Pradeep on the harvesting contract we have with them (Pat Purtscher is the COR; I am alt.
COR).
One topic will be a report they're finalizing and addressing NRC comments on, while another will be their efforts to identify previously harvested materials at PNNL. I think they're already doing a large portion of that for you, which probably meets our needs as well. I just wanted to touch base with you on what they are doing under your contract and let you know I'll be there next week and might discuss that some with Pradeep (not give direction of course, just try to be clear on what they're doing for your contract and whether that covers everything we're looking at for harvesting).
Let me know if you have any questions or concerns with that and we can catch up the week of August 13 ...
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 l -4 15-24541 Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Purtscher, Patrick Sent: Thursday, August 02, 2018 11:26 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>
Subject:
FW: inventory of ex-plant materials at PNNL FYI
From: Nove, Carol Sent: Thursday, August 02, 2018 10:17 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: inventory of ex-plant materials at PNNL
- Pat, I think it will be done before the end of the summer. I'll send it to you when I get it.
Carol From: Purtscher, Patrick Sent: Monday, July 30, 2018 9:31 AM To: Nove, Carol <Carol.Nove@nrc.gov>
Subject:
inventory of ex-plant materials at PNNL Good morning, Pradeep told me that PNNL is doing an inventory of ex-plant materials for you. Do you know when they will complete that task?
Pat Materials Engineer US Nuclear Regulatory Commiss ion I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch 11545 Rockville Pike I Rockville, MD 20852-2738 Phone: 301 -415-3942 I Office: TWFN 10A49 ptpl@nrc.gov
Note to requester: Attachment is immediately following.
From: Hiser, Matthew Sent: Fri, 20 May 2016 00:33:09 +0000 To: Burke, John;Sircar, Madhumita Cc: Frankl, Istvan
Subject:
FW: 2018-2020 draft proposal, F&M Attachme nts: HP-1490-Vol. 1, Proposal_2018-2020_ Fuels_Materials_draft.pdf Hi John and Mita, Halden has included irradiated concrete work in their draft 2018-2020 proposal. It appears they have just the general idea of acquiring harvested concrete and irradiating it further in their JEEP-II reactor. Beyond that, there is not much specific in their proposal , so we could certainly help suggest approaches and specific activities of interest to us.
Halden will be visiting NRC on August 30 to discuss their 2018-2020 proposal. Following these so-called country visits, in late 2016 - early 2017 HRP members (including NRC) have the opportunity to rank and provide written feedback on research programs in the 2018-2020 proposal.
To summarize, there is no direct action right now needed from you, but please be aware of this and try to be available for the visit on August 30 if possible.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN JOD62 Matthew.Hiser@nrc.gov From: Tu rid Danielsen [4]
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Subject:
[External_Sender] 2018-2020 draft proposal, F&M To the F&M Members of the HPG Please find attached the Draft Proposal for the 2018-2020 Program . It is based on input I've been receiving since my email of February 20th, as well as other earlier discussions at the HPG, and of course the parts of the current Program that are likely to continue past the end of 2017. As usual at t his stage the Draft Proposal contains more than we are likely to be able to do, and fitting the overall Program to the budget we can expect for 2018-2020 will have to be done as part of the process of progressing to the Final Proposal for approval by the Board in June 2017.
However, at this stage the main focus is on technical merit and we will have about one hour at the HPG meeting on Tuesday May 10th to discuss the Draft Proposal in outline, with new items being t he highlight.
I hope you can take the time over the next 3 weeks to read through the Draft Proposal and be prepared for a short discussion on the new/newer items.
Best regards, Margaret IFe Institute for Energy Technology OECD Halden Reactor Project P.B. 173, N0-1751 Halden, Norway (b )(6) MobileJ . .... * ! switchboard: +47 69 212200 turid.danielsen@ife.no ! www.ife .no Enlarged Halden Programme Group Meeting 2016: http://ehpg.hrp. no/
lnst itutt for energiteknikk HP-1490, v o l. 1 OECD HALDEN REACTOR PROJECT For use within the Holden Project Member Organisations only Fuels and Materials Proposal for the Three Year Period 2018-2020
HP-1490, vol. 1 CONTENTS Page INTRODUCTION ..... ............. .. .. ... .................. .. ..... ... ...... .... ......... ... .. .. ... ..... ... ... 3 OECD 1 FUEL SAFETY AND OPERATIONAL MARGINS ..*. ....... .. ...... .. ... ....... .. ... ... .. ... ... 4 Halden Reactor Project 1.1 Long and Short-Term Fuel Performance Irradiations ........ 5 1.1.1 Long-t erm irradiation of enhanced performance fuels ..... 6 1.1.2 BeO doped U02 fuel ........................................................... 7 1.1.3 Short-term irradiation of pre-irrad iated fuel rods ............. 7 1.1.4 Fission induced fuel creep ................................................. 9 1.1.5 High burn-up structure development.. ............................ 10 1.2 Fuel Properties and Behaviour Relat ed to Transient and Accident Conditions ......................................................... 11 1.2.1 Fuel behaviour under LOCA conditions ........................... 11 1.2.2 Behaviour of HBS fuel during transients .......................... 13 1.2.3 Transient fission gas release ............................................ 14 F&M Draft proposal for 1.2.4 Dry-out ............................................................................. 15 the three year period 1.2.5 Power cycling ................................................................... 15 2015-2017 1.3 Cladding Performa nce and Behaviour ............................. 16 1.3.1 Cladding creep ................................................................. 16 1.3.2 Cladding corrosion under high Li conditions ................... 17 1.3.3 Long-t erm irradiation of ATF cladding ............................. 18 1.3.4 Fuel cladd ing behaviour in interim dry storage ............... 19 2 PLANT A GEING AND D EGRADATION .. ............ .................... ....... ............. . 20 2.1 Irradiation Assisted Stress Corrosion Cr acking ................ 20 2.1.1 Crack growth rate studies ................................................ 21 2.1.2 Crack initiation studies ..................................................... 22 2.2 Irr adiation Enhanced Creep and Stress Relaxation .......... 23 2.3 Pressure Vessel Integrity Study ........................................ 24 2.4 Ageing of Concrete ........................................................... 24 April 2016 HALDEN P ROJECT USE ONLY The information contained in this report is to be communicated only to persons and undertakings authorised to receive it by one of the organisations participating in the OECD Halden Reactor Project in accordance with the Project's rules for communication of information
HP-1490, vol. 1 Introduction This document contains proposals for items to be included in the programme to be carried out in the period 2018-2020 aimed at promoting participants' interests on safety and reliability of nuclear power plants. The Fuels & Materials research programme will be based on:
- work carried out in previous programme periods
- discussions in the Halden Programme Group
- input and feedback from member organisations
- guidelines given by the Halden Board of Management In formulating the proposal, account will be taken of the continuity necessary to complete programme elements already start ed in the 2015-2017 period together with needs and priorities for both new long term activities and short-term deliverables.
This document is organised in two Chapters: Fuel Safety and Operational Margins; and Plant Ageing and Degradation.
The Fuels Chapter covers:
- Long and short-term fuel performance irradiations
- Cladding performance and be haviour The Materials Chapter covers:
- Irradiation assisted stress corrosion cracking studies
- Irradiation enhanced creep and stress relaxation
- Reactor pressure vessel (RPV) embrittlement
- Ageing of concrete Development of instruments for improved robustness, use in more demanding conditions or for extended range of measurement will be included as and when needed to fulfil the scope of the programme.
HP-1490, vol. 1 1 Fuel Safety and Operational Margins The safe and economical oper ation of nuclear power plants remains a priority for the nuclear industry. The availability of high performance, reliable fuels is essential for this goal and contr ibutes to competitive electricit y generation from nuclear power. New fuel and cladding materials have been and are being developed to support extended operation cycles, more flexible operation regimes, power up-rates and increased discharge burn-ups in some count ries. As a consequence the performance of nuclear power plants has improved over the years; however, operational experience shows that unexpected deviations from normal fuel performance do occasionally occur in some conditions. Such deviations can limit plant operation or even lead to premature shut-down to discharge the affected fuel.
Counteractive measures to improve fuel rel iability in a variety of demanding service conditions include fuel design modifications, development of new materials or changes t o water chemistry. The success of these approaches is evidenced by a decreasing trend in fuel failure rates. However, for nuclear power to remain competitive and further approach the goal of zero failure, it is essential that the m echanisms responsible for challengi ng the fuel and weakening the cladding during exposure are well understood.
Increased utilisation of fuel provides challenges also in safety transients. Qua lified models and codes are required to define the condition and properties of the fuel before the safety transient or accident scenario as well as its su bsequent behaviour during the transient. It is therefore essential to establish a knowledge base for safety assessments and to demonstrate the capabilities at all exposure levels of fuel in off-normal situations. Since such situations are undesi red and extremely rare by definition, data must be obtained by dedicated investigations conducted in test reactors with complementary work carried out in nuclear laboratories. In-reactor experiments should focus on issues that are essential to safety and that cannot otherwise be resolved.
There is consensus among HRP participants to continue experimenta l activities with the objective of generating new and improved data on fuel properties and fuel behaviour under relevant operational conditions, utilising fuels represent ative of the current and near-term expected industry standard (including burn-up levels). To that end this programme proposal deals with the following phenomena and operational conditions:
- Gas release under i rradiation - fission gas release (FGR) behaviour, gas inventory increase
- Fuel thermal and mechanical performance - conductivity degradation, densification, swelling, fuel creep, pellet-clad-mechanical-interaction (PCMI)
- Fuel behaviour during transients and accident conditions - FGR and PCMI under power transient operation as well as dry-out (departure from nucleate boiling) and LOCA studies
- Cladding performance and behaviour - cladding creep, growth, corrosion and hydriding in-react or and also under boundi ng dry st orage conditions These phenomena and operational conditions are addressed in long and short-term fuel performance irradiations and where several phenomena interact w ith each other in an integral manner as well as in studies where a phenomenon is observed as much as possible in isolation.
HP-1490, vol. 1 Participating organisations contribute to these investigations through providing relevant materials, and it is indispensable that fuel discharged from commercia l nuclear power stations is also made available and can be re-fabricated and instrumented for further irradiation t esting.
In most tests, the fuel rods and re-fabricated segments wi ll be equipped with multiple instruments to study the interrelation between various performance parameters. The in-pile measurements and results will be complemented with post irradiation examinations at the Kjeller hot cell laboratories, and also by specialised PIE at participants' laboratories as needed.
Data eva luation is also essential in o rder to utilise the informat ion generated from the experimental programme for gaining an as complete as possible understanding of fuel performance. This is a crucial step in supporting the development and validation of models and codes for safety assessments.
1.1 Long and Short-Term Fuel Performance Irradiations Fuel behaviour is characterised by the complex interaction of many phenomena which develop and change with burn-up. Experiments are therefore required for generating data which include the effect of inter- dependencies and which can be used for assessing the capability of fuel modelling codes to render inter-dependencies correctly. Pertinent whole rod performance data are obtained from instrumented tests in the Halden reactor. The instrumentation provides information on a number of phenomena, separate and combined, which are essential for fuel performance assessments and safety analyses:
- The fuel thermocouple gives direct information on the fuel temperature and indirectly on fuel thermal conductivity and the changes induced by increasing burn-up.
- The pressure transducer provides data on the kinetics and amount of fission gas release under different operating conditions and how the threshold for fission gas release is reduced with burn-up. Fuel densification and swelling can also be deduced prior to the start of fission gas release.
- The cladding extensometer gives data on the axial stress induced by pellet-cladding interaction and the relaxation with time. Fuel swelling can also be deduced in the case of p revailing contact between fuel and cladding.
- The fuel stack elongation detector measures dimensional changes caused by fuel densification and fuel swelling.
The value of the data obtained with these instruments is enhanced by noise analysis and the evaluation of the transient response of the fuel temperature to reactor scrams.
It is envisaged for the 2018-2020 programme that integral rod behaviour data will mostly be generated from BWR, PWR and VVER types of fuel rods with standard and modified urania fuel.
Other types can be included to the extent that such fuel is made available by participants. The Halden Reactor Project will seek to establish collaborative agreements with participants for providing suitable test material.
HP-1490, vol. 1 Experiments can start with fresh, zero burn-up fuels, or utilise pre-irradiated fuels retrieved from commercial nuclear power stat ions. The latter is especially important for studyi ng the behaviour of high burn-up fuel. In either case, instrumentation is an essential requirement for obtaining in-core data on key performance parameters while phenomena develop. The re-instrumentation technique developed at Halden, and proved in many applications, enables mounting of several rod instruments onto pre-irradiated commercial fuel segments.
The experiments will operate in natural Halden react or thermal hydraulic conditions (usually tests starting with fresh fuel) or make use of loop systems providing prototypical light water reactor thermal-hydraulic and water chemistry conditions (usually for pre-irradiated fuels from commercial nuclear power stations).
1.1.1 Long-term irradiation of enhanced performance fuels Motivation and background Several long-term fuel irradiation experiments have been successfully carried out in the Joint Programme, most recently IFA-677, IFA-676, IFA-681 and IFA-716. A new irradiation of t his type is due to start in the 2015-2017 programme period to study improved performance and advanced designs of fuel pellets including increased tolerance to accident conditions.
The main objective is to study the thermo-mechanical and FGR behaviour of different fuel types proposed as candidate fuels for accident tolerant fuel concepts, by irradiating 6 highly instrumented fuel rods under normal operating conditions in the Halden reactor (HBWR moderator/coolant). The focus is on the following parameters:
- Fuel thermal performance (fuel centre temperature)
- Fuel dimensional changes (densification and swelling)
- Fission gas release (FGR) behaviour The fuels to be irradiated are:
- Variants with uranium nitride compounds, aimed at compensating for the expected cost penalty of moving to ATF cladding concepts by offering a fuel pellet featuring a higher density of uranium than conventiona l U0 2*
- Microcell U02 fuels with microstructures aimed at retaining fission gas products in the pellets during transients/accidents as well as having improved thermal conductivity (thereby reducing FG release).
Work scope The irradiation phase is due to start towards the end of the 2015-2017 period and is expected to continue throughout the 2018-2020 programme period. Each of t he fuels being tested will have been characterised in it s as-manufactured state and archive material will be kept for possible future examinations following the end of the irradiation phase and subsequent PIE.
HP-1490, vol. 1 There is also interest in studying the behaviour of IFBA (Integral Fuel Burnable Absorber) fuel under long-term steady-state irradiation to provide data to validate IFBA end of life rod internal pressure.
Deliverables The aim for the 2018-2020 programme is to:
- Obtain data on the thermo-mechanical performance of enhanced performance fuels
- Produce data on the fission gas re lease properties of enhanced performance fuels
- Provide long term measurements of PCM I behaviour and rod growth rate due to fuel swelling and fuel-clad bonding of enhanced performance fuels 1.1.2 BeO doped UO2 fuel Motivation and background The IFA-716 experiment from the 2015-2017 programme period was designed to address parameters influencing the fission gas release properties of doped, large grain fuel where the effect of increased diffusion length (large grains) competes with the negative influence arising from increases in the diffusion coefficients as a result of the dopants. To this end, the experiment contained large grain fuels with different dopant concentrations as well as standard refere nce fuel. An additional fuel type included in the test was UO2 with BeO added to improve the thermal conductivity and thereby obtain lower fuel temperatures and consequently lower fission gas release.
Work scope The IFA-716 experiment completed its irradiation during the 2015-2017 period and the UO2 / UO2-BeO pair of rods (Rod 3 and Rod 4) is planned to be transferred to a new test rig for continued burn-up accumulation to prepare them for subsequent PCMI/FGR testing. The irradiation phase is due to start towards the end of the 2015-2017 period and is expected to be completed early within the 2018-2020 programme period, with subsequent PCMI/FGR testing being performed towards the end of the period (see 1.1.3).
Deliverables The aim for the 2018-2020 programme is to:
- Generate more data on the thermo-mechanical performance of UO2-BeO fuel
- Prepare UOr BeO fuel for subsequent studies of its fission gas release and PCMI properties 1.1.3 Short-term irradiation of pre-irradiated fuel rods Motivation and background This is an experimental series utilising two types of test rig: IFA-629 (HBWR conditions) and IFA-720 (LWR loop conditions). The aim is to characterise medium to high burn-up fuel performance with respect to fuel thermal properties, fission gas release and pellet-clad-mechanical-interaction. The specific objective is to produce experimental data for understanding and modelling fuel behaviour by
HP-1490, vol. 1 the concurrent measurement of temperature, FGR and PCMI during power increments and holds.
Additional knowledge on the rod dynamic response is obtained by analysis of scram and noise data.
Irradiations in IFA-720 are done under prototypical LWR condit ions, i.e. an LWR loop system is utilized, and sta rt with irradiated fuel segments. The fuel is characterised prior to testing as part of collating the base irradiation information, and also after testing in the Halden reactor with the main purpose to confirm the in-pile observations of FGR.
Work scope It is planned to utilise IFA-629 (or a new test rig of the same design) to test four fuel segments (in two loadings) during the 2018-2020 programme period. While two rods from IFA-716 are already planned to be tested in this rig (IFA-629.10) towards the end of the 2015-2017 programme period (Rod 1, Cr-doped and Rod 5, non-doped), it is also proposed to test the UO2 / UOr BeO pair of rods (Rod 3 and Rod 4) from IFA-716, for which burn-up extension is first planned (see 1.1.2). In addition, it is proposed to test the two 5%Gd-doped VVER fuel rods from IFA-676 (Rod 2 and Rod 5), for which the burn-up accumulation irradiation is planned to be completed during the 2015-2017 programme period. Further, it is proposed to test one of the two extended burn-up Loviisa fuel rods from IFA-789 (multilateral VVER fue l irradiation increment test to ~75 MWd/kgU) in the IFA-720 test rig.
It is expected that the sequence will be:
- [Rod 1 and Rod 5 from IFA-716 (UOi/Cr-doped U02 pairing) in IFA-629.10 - done 2015-2017]
- Rod 2 and Rod 5 from IFA-676 (Gd-bearing VVER) in IFA-629.12 (or similar), early in period
- Rod 1 from IFA-789 (extended burn-up VVER) in IFA-720.5, middle of period
- Rod 3 and Rod 4 from IFA-716 (UO 2/UO 2-BeO pairing) in IFA-629.13 (or similar), end of period There is also interest in subjecting pre-irradiated ATF rods to power transients when possible.
Deliverables The aim for the 2018-2020 programme is to:
- Expand the database of fuel thermal conductivity and its degradation with burn-up from different fuel types and burn-up levels
- Expand the database of PCMI behaviour of different fuels at different exposures
- Provide data on the fission gas release properties of different fuels (grain sizes, microstructures and other additives)
- Expand the database of fission gas release threshold behaviour of different fuel types and burn-up levels
- Provide more data on the behaviour of VVER Gd-UO2 fuel
- Provide data on the behaviour of extended burn-up VVER fuel
- Provide more data on the behaviour of UO 2-BeO fuel
HP-1490, vol. 1 1.1.4 Fission induced fuel creep Motivation and background The understanding of fuel behaviour requires knowledge on many phenomena. While all of these phenomena are present in integral fuel performance experiments, their development may be so weak as not to matter for the particular test, or i nstrumentation may not be present or too insensitive to detect their influence. Separate effect test s are therefore designed and executed for assessing specific phenomena w ith efficient methods, and the results are used for model development and verification. Separate effects tests can also go to condit ions not normally found in LWR operation, generating data allowing model inter polation instead of extrapolation.
One such test approach has been developed at Halden to study irradiation creep of fuels below l000°C i.e. fuel periphery temperatures. Creep behaviour is studied as a function of applied stress, with temperature and power density being cont rolled parameters. The fuel has the shape of disks which are stacked between molybden um disks in order to obtain a more even temperature distribution in the fuel. A compressive load is applied via a bellows unit positioned at the top of the fuel / M o disk stack. The stack length reduction is monitored by an LVDT, and in order to avoid significant creep of the Mo disks contributing to the integral measurement, t he temperature of the disks must be kept below 1000°C. The instrumentation also generates dat a on fuel densification and swelling under controlled temperature.
The fi rst such fission induced fuels creep test was successfully completed in IFA-701 with Cr-doped fuel and UO 2 reference fuel withi n the 2015-2017 programme period. It was then proposed to perform another two tests using the sa me experimental approach, but with gadolinia bearing fuel proposed to be supplied by ENUSA: an 8% and a 3% Gd 2O3 bearing UO2 f uel. The low t emperatures achievable are relevant not only for the periphery of Gd 2Or UO2 fuel pellets but also for the pellet centre temperature during normal BOL operation. As it is possible to obtain fuel densification data from the instrument ation during the initial phase of the test, running the test with Gd-fuel will thus enhance understanding of the densification kinetics differences associated w ith the addition of gadolinia to UO 2, complementing the observations made in IFA-636, IFA-676 and IFA-681, as well as characterizing the irradiation induced creep behaviour of gadolinia bearing fuel. This latter has been inferred as being approximately ten times higher in 8wt% Gd-bearing fuel than for UO2 fuel (at a similar power level / fission rate) from cladding elongation data generated from the power transient, integral performance t est, IFA-720.2 . It is thus expected that despite t h e lower power level of Gd-bearing fuel compared to UO2 under the same reactor conditions, that the creep rate of such fuel will be readily measureable using the "IFA-701 test approach".
Work scope It is expected that the first test (in IFA-795) with 8% Gd 2 O3 bearing UO2 fuel will be started during the 2015-2017 programme period and completed early in t h e 2018-2020 programme period, wit h the next test (in a new IFA) w ith 3% Gd2O3 bearing UO2 fuel starting around the m iddle of the 2018-2020 period.
HP-1490, vol. 1 Deliverables The aim for t he 2018-2020 programme is to:
- Produce direct measurements of in-pile fuel creep at two different levels of Gd-content
- Determine the densification of gadolinia bearing fuel at two irradiation temperatu res 1.1.5 High burn-up structure development Motivation and background There is interest in starting a new test in the 2018-2020 programme period to study the development of HBS in a variety of new fuels. For this new study it is planned to collaborate with the NFIR (Nuclear Fuel Industry Research) Group and coordinate with their plans for the NFIR-VII Program, which include the aim to study the properties and behaviour of high burn-up fuels of different types by post irradiation studies. One of the aims of studying these fuel types is to investigate the factors (especially impurities) that promote or delay HBS formation. Another goal is to investigate localization/trapping of volatile fission products by different additives.
On the condition that only one type of fuel is included in a fuel rod, the design of some of the fuel rods to be included in the experiment could also mirror that which was used for IFA-655 i.e. including gas flushing capabilities and fuel stack elongation detectors. This would enable the determination of S/V ratios at given burn-ups throughout the test (by ana lysis of the flushed out radioactive fission products) and thus monitoring of microstructural changes. Densification and swelling could also then be monitored online.
Work scope The study would involve performing a long-term irradiation to provide high burn-up fuel material for future fuel behaviour studies and property test ing, most likely by utilising the fuel disc irradiation approach as used in IFA-655. However, there is also interest to generate HBS in non-disc set-ups i.e.
small diameter fuel pellets in fuel rods operated at high power to accumulate burn-up more quickly than otherwise. Gas flushing and fuel stack elongation detectors could be added to single fuel type rods.
PIE of the fuel after the high burn-up irradiation would include HBS rim thickness values, FGR and retention characteristics, porosity and thermal characteristics. It is expected that participating laboratories would contribute to the PIE. Fuel rods of such HBS fuel discs or pellets would also be available for subsequent testing under power transient conditions such as was done w ith the IFA-655 fuel rods in IFA-629.
Ideas received so far for fuels to be irradiated as discs for future high burn-up properties studies (as well as some online measurements), are given below.
- Very high purity standard grain U02
- Very high purity standard grain U02 with inte ntionally added controlled impurities such as Fe for comparison
HP-1490, vol. 1
- Other commercially produced UO2 with additive fuels
- UO2 with ultra-small grain size
- UO2 with ultra-large grain size
- UO2 variants (normal impurities) small, standard, large grains but irradiated to even higher burn-ups than was possible in the IFA-649 disk irradiation for NFIR IV
- UO2 with "centralized U-235 enrichment" to mit igate burn-up peaking at the rim
- Different fuel types (i.e. not UO2 based) includi ng "cold fuels": silicides, nitrides
- Thorium Fuel variants (Ref: OECD/NEA/Nuclear Science Report 2015)
- U-lOZr Metal Fuel (Ref: Terra Power's TWR Reactor)
Deliverables The aim for the 2018-2020 programme is to:
- Generate high burn-up fuel material for future fuel behaviour and property testing
- Determine S/V ratios at selected burn-up levels from a range of fuel types
- Measure densification and swelling in a range of fuel types 1.2 Fuel Properties and Behaviour Related to Transient and Accident Conditions 1.2.1 Fuel behaviour under LOCA conditions Motivation and background The introduction of new cladding materials and the move to higher burn-up have generated a need to re-examine the saf ety criteria for loss-of-coolant accidents (LOCA) and to verify their continued va lidity. As part of international efforts to th is end, the Ha lden Project has implemented a test series (IFA-650) to study integral in-reactor fuel behaviour under expected and bounding LOCA conditions.
The Halden reactor is suited for integral in-pile testing of fuel behaviour under LOCA conditions using single fuel rods. The decay heat is simulated by a low level of nuclear heating which produces a temperature distribution in the fuel rod similar to the real case. Thus a more correct differential fuel-cladding thermal expansion is obtained compared to out-of-reactor tests where the cladding is heated from outside and more than the fuel.
The objectives of the HRP LOCA test series and t he test execution conditions have been defined in close cooperation with the HPG and ind ividual member organisations as:
- 1. Measure the extent of fuel (fragment) relocation into the ballooned region (determine packing fraction) and evaluate its effect on peak cladding temperature in the balloon zone and subsequent effect on oxidation.
- 2. Investigate the extent (if any) of "secondary transient hydriding" on t he inner side of the cladding above and below the burst region.
HP-1490, vol. 1 3. Determine the extent of iodine release; this objective was added later and addressed in the most recent tests of the series.
The test carried out so far, with irradiated fuel segments in the burn-up range 40 - 92 MWd/kg, have given clear evidence of fuel fragmentation and relocation. The fragmentation propensity increases wit h increasi ng burn-up when a threshold of about 60 MWd/kg is exceeded, but is counteracted if the cladding keeps firm contact with the pellets. Some experiments have shown a slow depressurisation after burst, and it is not clear how this phenomenon influences the fuel's LOCA behaviour.
Work scope It is proposed to continue the HRP LOCA test series with the aim to implement, as far as possible and to the ext ent eventually agreed upon, som e of the following experimental approaches:
- Further investigate any grid effect, especia lly using a grid cell. This is in line with the recommendation from the NEA-CSNI Working Group on Fuel Safety (WGFS) to determine the impact of axial gas transport on ballooning, e.g. by including a spacer grid between the uppe r plenum and the balloon area that would act as a prototypical distension restriction and cooling improvement sim ilar to what can be expected in the real situation.
- Further study how large the gap between pellet and cladding must be before fragmentation occurs (loss of restraint).
- Develop instrumentation to record when fragmentation (and fission gas release) occurs.
- Variation of rod pressure and free volume. This is in line with the recommendation from the WGFS to investigate fue l relocat ion as influenced by the driving force provided by the amount of gas ava ilable in the experiments.
- Position the plen um at the bottom of the rod (to check the fuel "lifting" and expulsion capabilities of gas coming from below the balloon/burst region).
- Include quenching at end of test.
- Axial constraint.
And the following fuel selection ideas:
- Testing of additive fuel segments (especially impact on FFRD behaviour)
- Testing of U02 -Gd 2 0 3 fuel segments (especially impact on FFRD behaviour)
- Testing of fuels with modern cladding materials (MS, Optimized ZIRLO and M-MDA)
HP-1490, vol. 1
- Study the role of gas location within the fuel pellets on fragmentation behaviour: compare for example Cr2 0rdoped fuels subjected first to different power ramps promoting different levels of intragranular gaseous precipitation
- Testing of commercially irradiated fue l that has received additional base irradiation to higher burn-up under prototypic LWR conditions in the Halden reactor. A specific example is: a VVER segment originally from Loviisa that has been irradiated under VVER conditions in the HBWR to an extended burn-up of ~75 MWd/kgU. Another example could be comparing two segments of the same burn-up, base irradiated in an NPP but with different final power periods applied in the HBWR.
The exact conditions for the tests, based on the bullet points above or other possible variants also discussed with the HPG such as tests complementary to those done within the SCIP program will be developed in HPG workshops and Expert Group discussions accompanying the test series.
It is mandatory to utilise fuel rods irradiated in commercial reactors to relevant burn-ups with a thorough characterisation regarding the state of the cladding and the bonding with the fuel.
Participating organisations are requested to continue to provide fuel with the desired characteristics.
Deliverables The aim for the 2018-2020 programme is to:
- Execute three LOCA tests in the Halden reactor - the exact test programme will not only depend on the outcome of the in-core phase, but also on the results of accompanying PIE.
- The LOCA testing programme will be kept flexible in order to be able to address new questions and issues which may emerge as the experiment series and the understanding of phenomena advance.
1.2.2 Behaviour of HBS fuel during transients Motivation and background High-burn-up structure (HBS) fuel is formed in the outer parts of U02 fuel where epithermal energy 238 neutrons are captured due to resonances in the U absorption cross section, generating plutonium and a local power and burn-up peak. It plays an important role in both normal operation and accident conditions. In the LOCA test series for example, fragmentation of high-burn-up structure (HBS) fuel has proved to be important. Such HBS fuel with burn-up exceeding 120 MWd/kg has been produced in previous programme periods (in disc form) and is available for testing in order to shed more light on its behaviour when subjected to a temperature transient. It is also proposed to generate new high burn-up fuel materials with focus on advanced and " designer" fuel types (see Section 1.1.5).
HP-1490, vo l. 1 Work scope Large amounts of HBS fuel (disks) have been produced in previous programme periods from irradiation in IFA-655.1 and IFA-655.2. The four test rods from IFA-655.1 have already been re-inst rumented and tested in IFA-629.5, .6, .7 and .8 to study f ission gas release of HBS fuel subjected to a relatively fast power and temperature up-rating. In addition, the first of the two rods irradiated to 180 MWd/kg in IFA-655.2 is also planned to be tested (in IFA-629.9) during the 2015-2017 progra mme period. The second of the two rods from IFA-655.2 is proposed to be tested in the same manner as the other five rods (in IFA-629.11 or a new test rig of the same design).
Deliverables The aim for the 2018-2020 programme is to:
- Subject high-burn-up structure fuel (1 test segment) to a temperature transient and measure fission gas release and fuel swelling, t hen perform PIE.
1.2.3 Transient fission gas release Motivation and background Anticipated operation occurrences (AOO) such as non-prompt power excursions can contribute to increases i n fission gas inventory that are not always well accounted for in fuel perfor mance models.
Detailed data obtained from carefully controlled and monitored transients applied to medium to high burn-up fuel could be used to improve the accuracy of cu rrent predictions for how the fuel will respond to a defined transient.
Work scope As a continuation of the plans in the 2015- 2017 programme, it is planned to subject commercially irradiated LWR fuel to specific power transients under prototypical LWR condit ions to quantify transient or burst fission gas r elease under AOO conditions. Proposals for different fuel segment s to be studied under specific condit ions are invited from participants, but it is clear t hat there is high interest in testing fuel wit h modern cladding t ypes (MS, Optimized ZIRLO, M -MDA) and pellets with additives as well as ATF. Detailed proposals w ill be presented to the HPG for discussion and their consideration for inclusion in the program. It is expected that 2-4 fuel segments could be studied in 1-2 loadings of the same test rig.
Deliverables The aim for the 2018-2020 programme is to:
- Subject medium to high burn-up fuel to a power transient (non-prompt power excursion) and measure FGR and fuel swelling
HP-1490, vol. 1 1.2.4 Dry-out Motivation and background Light water reactor fuel may be subjected to thermal-hydraulic transients resulting in inadequate cooling for short periods of time. Inadequate cooling may occur in PWRs as departure from nucleate boiling (DNB) and in BWRs as short term dry-out. Operation criteria to assure fuel rod integrity in the event of off-normal transients which may lead to fuel dry-out imposed operating restrictions and may also limit the further use of fuel after dry-out. There is therefore interest in further assessing fuel performance under dry-out conditions in order to assess possible additional margins.
Work scope Of particular interest would be the accumulated effect of " less severe" dry-outs due to for example oscillating flow conditions. Otherwise, dry-outs resu lting in cladding temperatures in the range 500 to 700°C being r eached would be of interest (to fill the knowledge gap in behaviour " between normal conditions and LOCA"). Such a test could also be used to assess the FGR behaviour of the fuel during a dry-out transient as well as the behaviour and consequences for the cladding performance during for example continued operation. It is expected that 2-4 fuel segments could be studied in 1-2 loadings of the test rig.
Deliverables The aim for the 2018-2020 programme is to:
- Subject medium to high burn-up fuel to a dry-out transient(s) and determine the effects by post irradiation examination as well as online instrumentation such as cladding elongation and possibly pressure transducer 1.2.5 Power cycling Motivation and background Nuclear power stations are more and more required to participate in power cycling and load follow.
Concurrent with extended fuel utilization, this entails questions as to whether and how these modes of operation affect fuel performance. A related issue is the kinetics of conditioning/ deconditioning /
reconditioning of fuel and cladd ing. It is therefore of interest t o verify that conventional fuel can sustain power cycling at any level of burn-up, and that new types of fuel and cladding have at least as good properties in that regard.
Work scope This testing would be aimed at defining fuel failure modes and operational limits for power cycling operations and would be informed by related work already done and experience gained in participating countries already operating w ith power cycling.
An idea is to compare the behaviour of "standard" fuel rods i.e. Zr-based cladding with U02 fuel against that of enhanced performance fuel rods (ATF or EATF), which are expected to have improved
HP-1490, vo l. 1 behaviour under flexible operation schemes. Within t he 2018-2020 programme period, it is possible that some low burn-up EATF rods could be sou rced for such testing.
Deliverables The aim for the 2018-2020 programme is to:
- Subject medium to high burn-up fuel to power cycling protocols and determine the effects by both on line measurements and post irradiation examinations 1.3 Cladding Performance and Behaviour All in-core experiments involving the study of cladding behaviour make use of test loops that allow experim ents to be performed under representative thermal-hydraulic and water chemistry conditions, i.e. coolant water pressure, temperature and chemistry. Since t he fuel is also operated under representative linear powers, other parameters such as cladding m id-wall and surface temperatures are also representative. Fast flux levels are maximised where required by surrounding the test fuel with booster fuel rods. All test s are instrumented for measurement of neutron flux and coolant temperature, pressure and flow rate. Test rods are fitted w ith instrumentation appropriate to t he objectives of the experiment.
The experiments related to cladding performance and behaviour considered for the next programme period are indicated in t he following sections.
1.3.1 Cladding creep Motivation and background After the fuel cladding has crept down onto the fuel pellet, which is concurrently swelling, and the initial fuel-clad gap is closed, a stress reversal occurs as fuel swe lling starts to drive general clad creep-out. Subsequent fuel swelling, fission gas release and power variations affect the applied hoop stress on the cladding in terms of both magnitude and direction. At any g iven time the fuel-clad gap, an important parameter for determining the thermal performance of the fue l, is dependent on t he creep of the cladding. In-pile, diametral creep behaviour of LWR fuel cladding under variable loading conditions is thus important and needs to be addressed in fuel performance codes. General discussion indicates that there are specific areas where modellers continue to require creep data on well characterised material test ed under carefully defined in-pile t esting conditions, such as primary creep following repeated stress increments and r eversals, especially for modern cladding materials.
Work scope In-pile cladding creep is investigated using the dual principle of stress application by internal gas pressurisation of closed-end cladding tubes and diameter change measurement via a surface traversing 3-poi nt contact diameter gauge. A wide range of compressive and tensile hoop stresses can be applied to the specim ens, and on-line changes in stress level can be effect ed both rapidly and repeat edly. On-line monitoring of the changing segment o uter diameter can be carried o ut frequently and to an accuracy of +/-2 µm .
HP-1490, vol. 1 It is proposed to complete the test that was started in the 2012-2014 programme period (I FA-741) loaded with four test claddings (MS, M-M DA, EllO-M and optimized ZIRLO) supplied by member organisations. Due to a diameter gauge failure, testing had t o be continued wit h each double-segmented rodlet separately in series, which resulted in a delay to the overall test plan: the rodlet with EllO-M and opt. ZIRLO (741-2) will complete test ing in the middle of the 2015 -2017 period and the rodlet with MS and M -MDA (741-1) wi ll start to be tested straight afterwar ds and is expected to complete testing about the middle of the 2018-2020 period. The test is conducted under representative PWR conditions.
On completion of the IFA-741 test, there is interest in starting a new test to study the creep behaviour of low-tin ZIRLO and Ziron.
Deliverables The aim for the 2018-2020 programme is to:
- Characterise creep behaviour of modern LWR cladding materials under a range of representative compressive and tensile hoop stress levels.
1.3.2 Cladding corrosion under high Li conditions Motivation and background With the trend toward increased fuel cycle length and reactor core ratings, fuel can be challenged by the resulting high discharge burn-up and more aggressive thermal-hydraulic conditions (e.g. coolant temperature and void fraction) and water chemistry conditions. Longer fuel cycles together with power up-rates require higher boron concentrations for reactivity control, which, in turn, leads to the increased need of lithium to maintain the optimal water chemistry conditions. Such operation requires beginni ng of cycle LiOH concentrations above the current widespread industry limit of 3.5 ppm. PWR primary water chemistry is also being optimised to minimise corrosion product release from the surfaces of steam generators and thus out-of-core radiation fields and crud formation on fuel cladding surfaces. Elevated and constant coolant pH is one potential optimisation method.
Operation with constant pH 7.3 or 7.4 (maximum lithium concentration 5-6 ppm) has been demonstrated in a commercial PWR; however before more demanding operation conditions ca n be implemented in PWRs, it is necessary to confirm that they do not have adverse effects on the corrosion and hydriding behaviour of the fuel claddings in use. One concern is t o determine whether a so-called cl iff edge exists, beyond which operation will be unacceptable.
Work scope It is proposed to complete the test that started in the 2015-2017 programme period (IFA-785) loaded with six test rods made with claddings supplied by member organisations: MS, M-MDA-SR and ZIRLO, together with alloys used in previous experiments and development alloys. The irradiation conditions (coolant mass evaporation rate and lithium concentration) were chosen to be more severe t han those currently allowed in commercial PWRs. The irradiation phase will be completed by the end of the 2015-2017 period or early in the 2018-2020 programme period, and it is planned to perform PIE during the 2018-2020 period to complement the interim inspections made during reactor outages for
HP-1490, vol. 1 which oxide thickness was determ ined using an eddy current proximity probe. As part of the PIE, oxide thickness and morphology will be studied on metallography samples, which will also show hydride distributions, and hydrogen content will be determined by the hot extraction method.
There is interest to start a new test to study the corrosion behaviour of low-tin ZIRLO and Ziron.
Deliverables The aim for the 2018-2020 programme is to:
- Deter mine oxide thickness and hydrogen pick-up rates for modern PWR cladd ing m at erials under elevated Li water chemistry conditions (10 ppm Li, pH300 7.4).
1.3.3 Long-term irradiation of ATF cladding Motivation and background Most countries are involved in developing fuel with enhanced accident tolerance (EATF), where the enhanced tolerance is due mainly to advanced cladding designs. A specific objective is to reduce the hydrogen production associated with the Zircaloy-steam reaction at t emperatures in excess of 900°C. It will also be a prerequisite that the performance of EATF claddings is not inferior to that of currently used claddings under normal reactor operation conditions. Thus the decision on whether enhanced accident tolerant fuel can be used in current LWRs will be in part based on its performance under normal reactor operation conditions.
Work scope It is proposed to continue the test that started in the middle of the 2015-2017 programme period (IFA-796) loaded with different U02 fuelled cladding sections (coated Zr -based claddings, a FeCrAI cladding, and M o-based claddings) suppl ied by member organizations. The fuel rods are operated under PWR therma l-hydrau lic and water chemistry conditions, with coating integrity and oxide thickness being determined annually during reactor outages, as well as cladding diameter and length measurements. The irradiation phase is expected to continue throughout the entire 2018-2020 programme period . Assuming this will be the case, post irradiation examinations will be made in the subsequent programme period to evaluate coating integrity, cladding creep, oxide thickness and morphology as well as hydrogen pick-up. Fuel segments will also then be available for additional testing such as under power or thermal-hydraulic transients or accident conditions.
Deliverables The aim for the 2018-2020 programme is to:
- Determine the corrosion, creep and growth behaviour of candidate accident tolerant fuel claddings under normal PWR operation conditions.
HP-1490, vol. 1 1.3.4 Fuel cladding behaviour in interim dry storage Motivation and background Since many spent fuel pools at nuclear power plants are near capacity and there are no permanent spent fuel disposal facilities in operation, many countries are considering extending the capacity or duration of use of interim dry storage facilities for spent fuel. Storage periods of possibly up to 300 years are being considered. Decay heat keeps the cladding temperature elevated, but decreasing over time, and the combination of atmospheric storage pressure with high EOL internal gas pressure results in significant clad hoop stress, which also decreases over time. These conditions increase the possibility of fuel cladding embrittlement in the radial direction due to hydride reorientation (which can have consequences for later handling of the stored fuel) or even failure due to creep rupture. Dry storage conditions will also induce specific cladding microstructural changes and determine creep behaviour, such that the only way to determine the behaviour of fuel cladding in dry storage is to study it under specific dry storage conditions .
Work scope This project started during the 2015-2017 programme period to study the dimensional, microstructural, and mechanical properties changes occurring in different irradiated fuel rods during representative dry storage boundary conditions. It is planned to continue this project in order to complete a comparative study of fuel rod variables expected to influence the behaviour of cladding under dry storage conditions, as well as studying the effects of bounding and realistic conditions on commercially irradiated LWR fuel rods.
In addition, there is interest in adding to this project the possibility of quantifying alpha-decay fuel swelling and decay gas release.
Deliverables The aims for the 2018-2020 programme are to:
- Contribute to characterisation of cladding behaviour under interim dry storage conditions in particular for modelling purposes.
HP-1490, vol. 1 2 Plant Ageing and Degradation The plant ageing and degradation programme is aimed at studying the effects of irradiation on reactor vessel int ernals as well as concrete conta inment buildings as the age of operating nuclear power plants increases. The studies address the following issues:
- Irradiation assisted stress corrosion cracking {IASCC} of core component structural materials
- Irradiation enhanced creep and stress relaxation
- Reactor pressure vessel (RPV) embrittlement
- Ageing of concrete The experimental programme on IASCC is aimed at generating data that provide a fundamental mechanistic understanding of the phenomenon, predicting behaviour, in particular the cracking response of irradiated materials, assessing the benefits of countermeasures and determining the limits of operation for existing materials. An understanding of the processes is considered the key to effective ageing management (i.e. mitigation and / or repair). The majority of the IASCC investigations are performed in loops simulating light water reactor operating and water chemistry conditions.
Irradiation enhanced creep and stress relaxation are potential degradation mechanism s that may affect materials' long-term performance. An in-pile study aimed at assessing the effects of irradiation and applied load on creep / stress relaxation of new, accident tolerant fuel (ATF) cladding and improved radiation resistant materials that are being developed for LWRs, may be conducted under dry irradiation conditions.
For the RPV programme, the Halden Project is participating, in collaboration with VUJE, Slovakia, in studies that make use of the smal l punch test method for determining the basic mechanical properties of irradiated RPV materia ls.
An additional area of investigation for the Joint Programme in 2018-2020 is proposed to focus on the ageing of concrete. All nuclear power plants contain concrete structures that are essentially passive under normal operating conditions but play a key role in mitigating the impact of extreme/abnormal operations and environmenta l events. As NPPs age, assurances need t o be provided that the concrete has not deteriorated unacceptably due to environmental effects such as exposure to a radiation environment.
2.1 Irradiation Assisted Stress Corrosion Cracking Motivation and background Irradiation assisted stress corrosion cracking (IASCC) occurs under the combined effects of irradiation, stress and a corrosive environment. IASCC is a degradation mechanism that is of concern for core components as reactors age, and components from both BWRs and PWRs have experienced intergranular cracking attributed to IASCC.
HP-1490, vol. 1 The austenitic stainless steels and nickel based alloys that are used as structural materials for LWR internals are exposed to radiation environments over extended periods of time. The resultant increases in yield strength, radiation induced segregation, changes in the material microstructure, loss of ductility and fracture resistance are all important factors when addressing plant ageing and licence renewal issues. A better understanding of their manifestation can enable better planning of aging management strategies for power plants.
The IA5CC programme focuses on crack growth rate and crack initiation studies.
2.1.1 Crack growth rate studies Workscope Long-term crack growth rate (CGR) data from Compact Tension (CT) specimens prepared from irradiated core component materials will be generated in BWR and PWR environments. The specimens are instrumented with the reversing de potential drop method for crack propagation monitoring and are equipped with bellows for variable load application. The crack growth rate studies are aimed at practical data generation as a function of temperature, corrosion potential /
water chemistry, fast neutron flux and stress intensity (K) levels. Representative materials harvested from commercial power plant components (e.g. control blades, baffle bolts, top guide, core shroud) are employed, concentrating on crack growth rate (CGR) testing over a range of dose levels.
In addition to the comparatively high dose materials retrieved from, for example, control blades and baffle bolts, it is recognized that there is very lim ited crack growth rate data for weld and heat affected zone (HAZ) materials, in particular at t he higher dose levels that are relevant for extended reactor operation. Participant organisations have therefore made available to the Joint programme both core barrel weld and HAZ material with doses of ~1 - 2 dpa, for further irradiation and t esting.
The materials have been machined into 8 1/4T CTs, 8 1/2 T CTs and 8 tensile specimens. Irradiation to higher dose levels began in 2016 and will be continued in the 2018 - 2020 programme period. While the irradiation, as well as most of the testing, will take place within the Joint Programme, the results from specimens tested elsewhere will also be shared with HRP members.
It is expected that one BWR and one PWR crack growth test, each employing 6 CTs, will be conducted in the 2018-2020 programme period: the BWR study, IFA-791, began already in 2016. The materials in the IFA-791 test matrix include ~2 dpa weld and heat affected zone 304 55, 35 dpa 304 555, 2 dpa 321 55 and 4 dpa CW 316 Ti 55. The effects of low ECP (hydrogen addition) as a means of mitigating crack growth rate will be evaluated. In addition, the effects of temperature on crack growth rate will also be studied. The materials and operating cond itions for the PWR study, to be performed after the BWR test, have not yet been identified.
Post irradiation characterisation of the materials that are used in the crack growth rate (and also the crack initiation) tests is an important supplement to the in-pile data. PIE typically includes post irradiation examination of specimen fracture surfaces, hardness measurements and t ensile testing. In addition, detailed TEM / FEG-STEM examination of the materials' microstructures and microchemistries is performed at participant laboratories.
HP-1490, vol. 1 Efforts are also made to obtain information on the flux, fluence and temperatu re to which the materials were exposed in t he commercial nuclear power plants from which they were retrieved.
Deliverables The aims for the 2018 - 2020 programme are to:
Irradiate weld and HAZ specimens to higher dose levels representative of extended reactor operation for subsequent testing in PWR (and BWR) CGR investigations Generate crack growth rate data on irradiated CTs in BWR conditions wit h either 5 ppm 0 2 or 2 ppm H2 in the coolant and evaluate the effect of temperature on growth rate.
Measure crack growth rates in irradiated CTs under PWR conditions Perform detailed post irradiation examination of selected test materials 2.1.2 Crack initiatio n studies Workscope Two crack initiation studies that began in the 2015-2017 programme period will be continued in the 2018-2020 programme period.
The first study, performed under representative PWR conditions, addresses the effects of load transients on the initiation of cracks in tensile specimens prepared from ~4 to 25 dpa CW 316 SS and
~4 to 70 dpa SA 304 SS. The main objective will be to study a proposed engineering sensitivity threshold for crack initiation under transient load conditions. The specimens will be loaded to stress levels below the threshold curve and subjected to load transients above the threshold curve, as illustrated in the figure below.
CD
~ 0,8 "0
=..
CD 0,6 U) 0,4
- e 0,2 0
0 10 20 30 40 50 60 70 80 90 Dose (dpa)
It is proposed that 80 dpa CW 316 SS 0-ring samples be included in a second loading of the test. 0-ring samples prepared from the same material have already been tested out-of-core at a participant laboratory, thus enabling a comparison between in and out of core initiation data.
HP-1490, vol. 1 The second study addresses the initiation of cracks in Alloy 718, also in a simulated PWR environment.
Alloy 718 has shown exceptional mechanical properties and resistance to radiation degradation for certain m aterial compositions and heat treatments. Outside this narrow area, studies have found that the material properties quickly degrade, and PWR operational experience has shown cracking and stress relaxation in a number of 718 components. In order to evaluate the factors affecting the material performance, the effects of stress, heat treatment, % cold work and alloy chemistry on crack initiation of alloy 718 are being assessed in the investigation.
The test was originally performed on a bilateral basis and was continued in the Joint Programme from mid-2016 when the bilateral study was concluded, granting Joint Programme members access to all results. In-pile testing will conclude at the end of 2017 and will be followed by PIE.
Deliverables The aims for the 2018-2020 programme are to:
Assess the effect of load transients on the initiation of cracks in tensile and O-rings samples with different doses Perform PIE on the Alloy 718 specimens 2.2 Irradiation Enhanced Creep and Stress Relaxation Motivation and background New accident tolerant fuel cladding materials as well as more radiation resistant alloys for core structural components are being developed in a number of countries. In addition to evaluating the potentia l application of these materials for fuel cladding and structural components by studying their corrosion performance, there is also a need to evaluate other performance aspects such as in-pile creep behaviour.
Workscope The design of the proposed test will be based on that of an earlier Joint Programme creep and stress relaxation test which was in operation for eight years in the period 2006-2014. Tensile samples are installed in instrumented units. Stress is applied to the specimens by means of bellows which are compressed by gas pressure that is introduced into the chamber housing the bellows, and sample elongation is measured by means of LVDTs. In order to measure creep rates at different stress levels (or to obtain stress relaxation data by maintaining constant displacement on the samples) the applied load may be decreased on-line, by reducing the pressure in the bellows housing units.
In addition to the bellows gas lines for load application, the test units are equipped with gas lines that enable control of the specimen temperatures by altering the composition of helium-argon gas mixture surrounding the specimens.
Materials of interest for inclusion in the study will be discussed with Project participants.
HP-1490, vol. 1 Deliverables The aims for the 2018- 2020 programme are to:
- Provide baseline creep (and stress relaxation) data for new accident tolerant fuel cladding and candidate core component replacement materials.
2 .3 Pressure Vessel Integrity Study Motivation and background The pressure vessel integrity studies are aimed at evaluating the effects of neutron embrittlement on pressure vessel materials as well as on some core component materials. The limited amounts of available material for such tests are resolved through reconstitution techniques and miniaturisation of test specimens.
The use of the small punch test (SPT) method, which reduces the amount of material required to determine the basic mechanical properties of a material, was verified experimentally in the 2009 -
2011 and 2012 - 2014 programme periods in two investigations performed in collaboration with VUJE, Slovakia.
Workscope rd A 3 study, which began in the 2015 - 2017 programme period, will be concluded in 2018 -2020. The main objective is to compare the results obtained from surveillance specimen programmes at Slovakian power reactors with results obtained from specimens irradiated in the Halden reactor. Two sets of SPT and mini tensile specimens prepared from the same materials that are being used in the NPP surveillance programmes are currently being irradiated in the Halden reactor. The specimens are prepared from the RPV base and weld materials of the 3rd and 4th units of the NPP in Mochovce (EMO) . The two units are currently under construction and the start of the operation is expected in 2016 (Unit 3) and in 2017 (Unit 4).
The specimens, comprising 180 SPT and 30 mini tensile specimens, are being irradiated at ~275 *c to 19 20 2 4 x 10 and 1 x 10 n/cm (> lMeV), equivalent to 1 and 3 campaigns in the power reactors. The irradiation will be completed in mid-2017, followed by mechanical testing.
The surveillance specimen programmes for the two Mochovce units also contain several sets of SPT specimens. The results from the Halden and NPP irradiation will be used in safety assessments for both units of the Mochovce NPP.
Deliverables The aim for the 2018 - 2020 programme is to:
Complete mechanica l testing and compare the results from the Slovakian power reactor specimen surveillance programmes with those obtained from Halden reactor.
2 .4 Ageing of Concrete Background and motivation
HP-1490, vol. 1 Concrete is used in the construction of nuclear power plants, e.g. for the containment, the biological shield and the structures carrying the reactor pressure vessel. As the operation of NPPs extends over several decades, it is important to ensure that the concrete structure mainta ins adequate properties also in the long term, considering that such concrete structures are subjected to the damaging effects caused by neutron and gamma radiation.
Workscope The irradiation of concrete would be performed at the JEEP-II reactor at Kjeller, primarily beca use of the low operating t em perature (55 °C) and the low gamma heat (O.l W/g), which give represent ative irradiation conditions for concrete. Experience with concrete irradiat ion and t esting has already been established at IFE through bilateral programmes.
While the scope and objective of the proposed experim ent st ill need t o be discussed further with Project participants, preliminary ideas include:
- Harvesting concrete samples from actual NNPs and irradiating the specimens up to a number of different neutron fluence levels, equivalent to va rious numbers of years of oper ation of an NPP.
- Doing a "system atic scientific study" to learn more about the effects of exposure on the behaviour of differe nt cem ents/aggr egates when exposed to a radiation environment.
The t est assemblies that are irradiated in the Jeep II reactor are able to contain concret e specim ens with a diameter of up to 5 cm. On-line measurements could include monitoring of t emperature and gam m a heat as well as monitoring the concrete sa mples' gas r elease (am ount and composition),
water release and dimensional changes (st ack elongation).
Subsequent post ir radiation measurements of the concrete samples could include some, or all, of the following:
- Change i n m ass and d imensio ns
- Elastic modulus
- Compressive and tensile stre ngth
- Gamma scanning and neutron radiography
- LOM examination and SEM examination Deliverables The aim s for the 2018 -2020 programme are to:
Initiate an investigation aimed at assessing the ageing of concrete as a result of exposure to neutron and gamma radiation
!Note to requester: Attachment is immediately following.
From: Frankl, Istvan Sent: Thu, 2 Feb 2017 07:56:17 -0600 To: Tregoning, Robert Cc: Berrios, llka;Hiser, M atthew;Hull, Amy;Purtscher, Patrick
Subject:
FW: Action: FANC Research on decommissioned RPV Attachments: 16-105 Leaflet SCK FANC BELV.docx Rob Would FANC be a good candidate for the upcoming harvesting workshop?
Thanks, Steve From: Berrios, Ilka Sent: Thursday, February 02, 2017 8:19 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>
Subject:
FW: Action: FANC Research on decommissioned RPV Please see below. Please let me know your thoughts.
Thanks, JrAa; 415-2404 From: Sa ngimino, Donna-Marie Sent: Wednesday, February 01, 2017 5:10 PM To: Berrios, Ilka <llka.Berrios@nrc.gov>
Cc: RES_ lnternationa l_Mailbox <RES International Mailbox@nrc.gov>
Subject:
Action: FANC Research on decommissioned RPV Hi Ilka, OIP reached out regarding the email below and attached, asking if RES is interested in working with the Federal Agency for Nuclear Control (FANC) in Belgium on material properties of decommissioned RPV (no rush).
Thanks Donna-Marie
From: VINCK Marion (mailto:Marion .VINCK@FANC.FGOV.BEl Sent: Friday, December 02, 2016 8:18 AM To: Holzman (Schwartzman), Jennifer <Jennifer.Schwartzman@nrc.gov>
Cc: van Walle Eric (eric.van.walle@sckcen.be) <eric.van.walle@sckcen.be>
Subject:
(External_Sender] RE: Research on decommissioned RPV
Dear Jennifer,
Please find attached the requested leaflet.
Xina regards
.'.Marion "vINCX Management Assistant to the DG FANC-AFCN Tel : +32 (0)2. 289.2100 Fax: +32 (0)2. 289.2103 (b)(6) '?sm .:l - - - - - - - - I
-marion.vinck@fanc.fgov.be http://www.fa nc.fgov. be/
f d ANC g ncy ornuc r con ro From: Holzman (Schwartzman), Jennifer [5]
Sent: donderdag 1 december 2016 20:05 To: VINCK Marion
Subject:
Research on decommissioned RPV
Dear Marion,
Greetings from the USNRC - I hope this message finds you well!
I am writing because, during Director General Bens' meeting with the USNRC delegation during the recent General Conference, he mentioned that FANC may be initiating a research project to examine the dismantled reactor pressure vessel of a decommissioned NPP. A brochure on the project was provided to our delegation. I was hoping that it might be possible to obtain an electronic copy of this information so we may share it with our technical experts. Your assistance is greatly appreciated.
Best regards, Jennifer
Jennifer Schwartzman Holzman Sr. International Relations Officer Office of International Programs U.S. Nuclear Regulatory Commission
+1-301-287-9090 jennifer.schwartzman@nrc.gov Note to requester: This empty box was in the original email record provided to the FOIA team, it links to the FANC web site, https://fanc.fgov.be/nl kdera I, e1 I hap ,oor nucl II ontrole agence ffderale de controle nucleaire Het FANC is houder van het ISO 9001 :2008-certificaat - L' AFCN detient le certificat ISO 9001 :2008.
Denk a.u.b. aan het milieu voordat u deze mail afdrukt.
S.V.P., pensez a l'environnement avant d'imprimer eel e-mail.
Disclaimer (Fr) - Disclaimer (Nil
STUDIECENTRUM VOOR KERNENERGIE F ANC A FCN BEL v' CENTRE OUUOE OE L'EN ERGIE NUCLEAJRE Assessing actual material properties of decommissioned nuclear reactor vessels in comparison to prediction - an international programme This project is aiming to extract irradiated reactor pressure vessel materials from one or more shutdown (decommissioned) nuclear power plants for t esting in different laboratories in order to assess the actual measured properties of the vessel materials versus predicted values. The outcome of this research will improve our understanding of neutron-induced degradation of RPV materials from long-term radiation exposure, to compare them to accelerated material test reactor (MTR) irradiation enabling both the operators and the regulators evaluation of the reliability of the current procedures.
It is a matter of fact that an incredible amount of valuable information can be extracted from the decommissioned vessels upon post-mortem tests by scientists from different organizations to deepen and understand material behavior that have operated under realistic conditions.
Several tens of nuclear power plants were shut down worldwide among which 37 reactors in the last decade. On the other hand, from the operating worldwide nuclear power react or fleet, more than 60 reactors are at present more than 40 years old many reactors licenses will be renewed in the coming years for a further 20 (or even 40) years of operation. As a result, operators and regulators need additional information to understand, assess and manage the degradation of irrad iated materials of nuclear pressure vessels.
Figure showing the BR3 reactor pressure vessel dismantling Historical context Testing irradiated materials from decommissioned vessels is not new. A number of individual initiatives can be found worldwide but the effort is quite limited because of funding constraints (see Table).
Nevertheless, the outcomes from these ind iv idual projects were very pertinent and beneficial. BR3 post-mortem tests demonstrated the conservatism of the regulation. It is interesting to note that the BR3 vessel is very similar to the Yankee Rowe vessel that was shut down in 1991 after many d iscussions on vessel embrittlement. Chooz-A post-mortem tests proved the validity of the surveillance program.
Ref. 16-105/EvW/nvdb 22-09-2016
Within the Gundremmingen-A reactor vessel test program, the mechanical properties of the different forging constituting the vessel were found to be different. However, the surveillance data as well as the regulatory approach remain conservative. The Greifswald post-mortem tests showed that the weld p roperties may significantly vary from one location to another, not always related to fluence level. The chemical composition through the weld thickness is found not constant. This was also observed on the Novovoronesh- 1 reactor where phosphorus content is relatively high. The embrittlement based on regulatory approach is higher than expected but direct fracture toughness measurements are within the Russian code This brief overview, although modest in terms of efforts shows clearly that we need to reactivate such a program but this time in an international context with more extensive investigations.
Table : Reactor vessels on which post - mortem tests w ere performed BR3 Belgium PWR (11 MWe) 1963- 1987 Chooz-A France PWR (305 MWe) 1967-1991 Gundremmingen-A Germany BWR (237 MWe) 1966- 1977 Greifswald-1 to 4 Germany W ER-440 (408 MWe) 1986- 1991 Novovoronesh- 1 Russia VVER-440 (408 MWe) 1964- 1984 The project The proposed project is aiming to gathers several international organizations to assess the reactor vessel materials properties after long term operation conditions and to compare them to surveillance data (moderate lead factor) as well as material test reactor data (lead factor several orders of magnitude higher than the vessel). The final materials selection and test matrix will depend on organizations interests as well as funding. But the outcomes will clearly improve our understanding on materials behavior under neutron irradiation and would allow assessment of spectrum and flu x effects, the final goal being the assessment of the regulatory procedures in place today. The results will benefit the worldwide utilities and regulators, and wi ll also help to better evaluate long term operation programs aiming at a plant lifetime of more than 40 years.
To successfully execute this project, active participation of utilities, regulators and research organizations is a prerequisite. It is important that the utilities offer interesting vessel materials so that a number of issues can be investigated, in particular, material variability (chemical composition as well as mechanical properties), comparison to surveillance program, comparison to accelerated material test reactor data, regulatory-based assessment versus actual vessel properties, post -
irradiation annealing behavior, ...
This project is open for international collaboration including the EU, USA, and Japan where a large number of decommissioned reactors are available. SCK*CEN together with the Belgian nuclear authorities FANC/AFCN and BEL V will act as the Belgian representatives.
Co ntact FANC/ AFCN Jan Bens, Director-General, Ravensteinstraat 36, 1000 Brussel, JAN.BENS@FANC.FGOV.BE Fran<;ois Henry, Expert, Ravenst einstraat 36, 1000 Brussel, Francois.henry@fanc.fgov.be SCK*CEN Eric van Walle, Director-General, Boeretang 200, 2400 Mol, eric.van.walle@sckcen.be Rachid Chaouadi, Deputy Institute Manager NMS, Boeretang 200, 2400 Mol, rachid.chaouadi@sckcen.be Ref. 16- 105/EvW/nvdb 22-09-2016