Text

NRC-2018-000831 - Resp 10 - Interim, Agency Records Subject to the Request Are Enclosed, Part 6 of 14
	ML21071A172
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Issue date:	03/04/2021
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	NRC-2018-000831
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From: Audrain, Margaret Sent: Tue, 14 Nov 2017 16:06:26 -0500 To: Frankl, Istvan; Purtscher, Patrick Cc: Hiser, Matthew

Subject:

RE: plan for meeting at ANL on harvesting

Steve, I put in the emergent request. I used a placeholder date the second week of Dec.

Meg From: Frankl, Istvan Sent: Tuesday, November 14, 2017 3:36 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>

Cc: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: plan for meeting at ANL on harvesting Importance: High

Pat, Did you align the harvesting scope with Matt and Meg?

If so, please add your trip to the list of emergent trip requests using the link below and clarify under justification that this is a date change with extension:

G:\DE\CMB\Travel\FY18 RES-DE travel - CMB.xlsx Again, the justification needs to address specific regulatory objectives/scope that cannot be accomplished without the trip. A specific draft agenda would be helpful in drafting this justification. I assume ANL is not unique, so drafting a broader agenda/scope for the lab visits supporting the harvesting effort would be advantageous.

Meg, Please also submit emergent trip request for this "one time" trip.

Thanks, Steve From: Purtscher, Patrick Sent: Tuesday, November 14, 201710:47 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

FW: plan for meeting at ANL on harvesting

Steve,

Here is the plan for what we will discuss with AN L for harvesting. It seems like the 2nd week of December will be the best time, but I am waiting on a firm date when they will be available.

Pat BACKGROUND March 2017 workshop -

four main areas of consideration for extended service life: RPV, RVI, cables, & concrete

feedback from workshop participants is that harvesting is expensive and time-consuming, need to focus on value (costs vs. benefits)

PNNL report -

Lays out a systematic approach to optimize harvesting outcome by prioritizing needs and surveying available materials from decommissioning of plants, operating plants and previous harvesting programs GOALS for ANL meeting What does ANL have from past programs with NRC, DOE, or others Examples:

SGT program looked at tubes pulled from McGuire

Omesh looked at CASS from Shippingport Materials of interest don't have to be material from plant with extensive service history. Example is FAVOR code for RPV embrittlement. Results from modeling and simulations are dependent on input of the flaws that could be present from fabrication. Sections of old, thick ferritic steel welds from structures with similar acceptance criteria but were never put into service provided important inputs that permitted the computer code to be validated.

A good example of where harvesting is important would be how the BWRVIP is responding to NRC concern for IGSCC mitigation with on-line noble chemistry program. They harvested samples from all regions of operating BWRs to demonstrate the distribution of noble metal particles within the whole syst em. The presence of a pattern of small, discrete deposits of noble metal particles would indicate effective particle distribution to ideally impart good resistance to IGSCC. The individual samples by themselves were not that significant, but taken together, they show that there is effective mitigation in those areas of the system where inspection relief is being requested.

OUTCOME We hope to assemble an inventory of available materials to comider for harvesting program like or in coordination with that in the INL NSUF Nuclear Fuels and M aterials Library (NFML). Our emph asis is in the four areas outlined earlier, but not necessarily limited to those four. Future OpE can change the focus of harvesting needs very quickly.

Pat

From: Purtscher, Patrick Sent: Fri, 7 Oct 2016 11:48:33 +0000 To: 'Ramuhalli, Pradeep'

Subject:

RE: RE: Emailing: MRP-129.pdf As of Dec. 6, 2006, these two reports were made public.

Pat From: Ramuhalli, Pradeep [1]

Sent: Thursday, October 06, 2016 5:17 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>

Subject:

[External_Sender] RE: Emailing: MRP-129.pdf

Patrick, I assume these documents can be shared internally at PNNL? These are marked EPRI Proprietary and I wanted to check before I sent these on to our materials SM Es.

With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email: pradeep.ramuhalli@pnnl.gov From: Purtscher, Patrick [mailto:Patrick. Purtscher@nrc.gov)

Sent: Thursday, October 06, 2016 6:50 AM To: Ramuhalli, Pradeep <Pradeep.Ramuhalli@pnnl.gov>

Subject:

Emailing: MRP-129.pdf Follow up document

From: Tregoning, Robert Sent: Mon, 19 Dec 2016 22:03:08 +0000 To: 'Bernh oft, Sherry'; rich ard. reister@n uclear.energy.gov;Dyle, Robin

Subject:

RE: RE: [External] Harvesting Workshop Sherry:

Thanks for getting back to me so quickly. As you can see in the current agenda, we have identified talks from EPRI and/or the industry within several sessions. Can EPIRI support those talks and if so, can you tell me when you can identify speaker(s) for these talks? We will then start working with the speaker(s) so that the objectives of each session and the overall workshop are met. As always, I'm looking forward to EPRl's participation. Thanks so much for your help.

Have a Happy Holidays!

Rob From: Bernhoft, Sherry [2]

Sent: Monday, December 19, 2016 11:37 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; richard.reister@nuclear.energy.gov; Dyle, Robin

<rdyle@epri.com>

Subject:

[External_Sender] RE: [External) Harvesting Workshop Rob As I understand from Robin, the discussion last week with Kurt was that EPRl's position is we will send someone(s) to participate in the workshop, but we will not be acting in a leadership or coordinating role.

Sherry Bernhoft Electric Power Research Institute EPRI, Senior Program Manager 1300 West WT Harris Boulevard I Charlotte, NC 28262 704.595.2740 (office)

(b)(6) I .. !(cell)

Email: sbernhoft@epri.com www.epri.com Together... Shaping the Future of Electricity From: Tregoning, Robert [3]

Sent: Thursday, December 15, 2016 2:54 PM To: Bernhoft, Sherry <sbernhoft@epri.com>; Reister, Richard < Richard.Reister@nuclear.energy.gov>

Cc: Hiser, M atthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Dyle, Robin <rdyle@epri.com>

Subject:

[External] Harvesting Workshop

Sherry/Rich:

I wanted to thank you again for the discussion that we had last week on the harvesting workshop agenda. I think it was productive and I appreciate the perspective you both brought.

I've attached an announcement for the workshop that were planning to use to solicit participants. Also, we've revised the agenda substantially based on the feedback you both provided. I think it captures the issues you had and I personally think that this is a better model to follow for the workshop.

I'd like to ask you both for two things prior to leaving for the holidays.

1. Could you provide me with any additional changes to the workshop agenda that you recommend? Just mark-up and send back the attached agenda. I'll consolidate and address any remaining suggestions from you both.

2. Could you provide me with a POC for coordinating each of the 5 workshop sessions?

The idea is for the POCs to work together for planning each session. Here are the POCs from the NRC:

a. Session 1 - Rob Tregoning

b. Session 2 - Matt Hiser

c. Session 3 - Pat Purtscher

d. Session 4 - Matt Hiser

e. Session 5 - Rob Tregoning We're hoping to get the planning teams in place before Christmas so that we can hit the ground running in early January to line up all the speakers.

Thanks again for your help. If I don't talk to you beforehand, I hope both you and your families have a Happy Holidays and a Prosperous New Year.

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

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

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

From: Tregoning, Robert Sent: Thu, 5 Oct 2017 16:49:52 +0000 To: 'Bernhoft, Sherry'

Subject:

RE: Re: [EXTERNAL) NRC PUM poster on harvesting Thanks, Sherry. I appreciate your help with this .. ...

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: Bernhoft, Sherry [mailto :sbernhoft@epri.com]

Sent: Thursday, October 05, 2017 12:26 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Ki-Sig Kang <Ki-Sig.Kang@iaea.org>; Hiser, Allen

<Allen.Hiser@nrc.gov>

Cc: r.krivanek@iaea.org; Moyer, Carol <Carol.Moyer@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

[External_Sender] Re: [EXTERNAL] NRC PLiM poster oin harvesting Ki-Sig and Robert, Please see the note below regarding NRC poster on material harvesting. Allen Hiser will be bringing the poster and supporting this during the PUM if you can help ensure it is part of one of the poster sessions that would be greatly appreciated.

See you in a few weeks, Sherry Sent from my iPad On Oct 4, 2017, at 2:26 PM, Tregoning, Robert <Robert.Tregoning@nrc.gov> wrote:

Robert/Sherry:

I just checked the latest PliM program agenda that is on the website and it doesn't have the NRC's poster on material harvesting listed. We submitted the attached abstract and assumed, based on this email chain, that it had been accepted for the poster session. We have prepared the poster and are making plans to have it manned during the conference. I just want to confirm that the poster is accepted and to see if the program can be updated accordingly.

Thanks for your help with this.

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 04, 2017 3:02 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; Tregoning, Robert

<Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Moyer, Carol

<Carol.Moyer@nrc.gov>

Subject:

FW: FW: PLiM abstract on harvesting This email chain I thought confirmed that we were accepted for a poster...

From: Moyer, Carol Sent: Thursday, July 20, 2017 12:49 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject : FW: FW: PLiM abstract on harvesting

Matt, I am a bit confused by the pronoun used in this email .. .

Are you interested in doing a poster instead?

Carol From: KRIVANEK, Robert [4]

Sent: Thursday, July 20, 2017 11:10 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender) FW: PLiM abstract on harvesting You have just agreed that we will add this paper to poster session .

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager

Operational Safety Section I Division of Nuclear Installation Safety IDepartment of Nuclear Safety and Security Intern ation al Ato mic Energy Agen cy I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek @iaea .org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

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From: KRIVANEK, Robert Sent: Thursday, 20 July 2017 16:10 To: 'Caro l. Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

We asked you to submit your synopsis through INDICO (see email below) but it did not happened . So we were not able to send your synopsis to programme committee for evaluation and it will not occur on the conference programme.

Sorry for that but there are currently 300 delegates and 150 synopsis, so we were not able t o track each of them separately.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety IDepartment of Nuclear Safety and Security Internationa l Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.kriva nek@iaea .org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

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From: KRIVANEK, Robert Sent: Friday, 26 May 2017 08:55 To: 'Carol.Moyer@nrc.gov' <Carol.Moyer@nrc.gov>

Cc: KHAELSS, Martina <M.Khaelss@iaea.org>

Subject:

FW: PLiM abstract on harvesting

Dear Carol,

Thank you for your synopsis. We have opened INDICO system for this week, so please submit it through the system .

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety IDepartment of Nuclear Safety and Security International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org IT: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

Follow us on www.iaea.org

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From: Carol.Moyer@nrc.gov (mailto:Carol.Moyer@nrc.gov]

Sent: Friday, 26 May 2017 00:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Tregon ing, Robert

<Robert.Tregoning@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>

Subject:

PUM abstract on harvesting

Dear Mr. Krivanek,

The US NRC would like to propose one more presentation for this autumn's PLiM conference, on harvesting of materials from operating and decommissioning power plants . I understand from Sherry Bernhoft that you already have an impressive number of abstracts, so I will understand if there is not room in the program for this one. Nevertheless, we would appreciate your consideration of this proposal.

Again, please let me know if you need any additional information. Many thanks,

Carol Carol E. Moyer Sr. Materials Engineer Office of Nuclear Regulatory Research RESIDEICMB carol.moyer@nrc.gov 301-415-2153 From: KRIVANEK, Robert [mai lto:R.Krivanek@ iaea.org]

Sent: Tuesday, May 23, 2017 2:41 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

[External_Sender] RE : RE : CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Carol,

I will arrange it. Thank you.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety IDepartment of Nuclear Safety and Security International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.o rg I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

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From: Carol.Moyer@nrc.gov (mailto:Carol.Moyer@nrc.gov]

Sent: Monday, 22 May 2017 20:44 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Subject:

RE : RE : CN246_PLiM_Abst ract deadline extended to 19 May 2017

Dear Mr. Krivanek,

Since the formal deadline for abstract submissions has passed , I am no longer able to access the lndico system through the PLiM website (https://conferences.iaea.org/indico/event/134/). My abstract and Form B are attached .

Are you able to work with these documents? Is there anything else that you need me to do at this time?

Thanks again for your patience and assistance,

Carol From: Moyer, Carol Sent: Monday, May 22, 2017 10:59 AM To: 'KRIVANEK, Robert' <R.Krivanek@ iaea.org>

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

Subject:

RE: RE: CN246_ PLiM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

My abstract is attached to this message, for your info. Separately, I will submit it through the lndico system. Please let me know if you need any other information at this stage.

Thank you, Mrs. Carol Moyer From: KRIVANEK, Robert [mailto:R.Krivanek@iaea.org1 Sent: Monday, May 22, 2017 2:56 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender) RE: CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear Mr Moyer,

It will be fine if you submit your abstracts this week.

We are looking forward to see a strong NRC delegation in Lyon.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety IDepartment of Nuclear Safety and Security International Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

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From: Carol.Moyer@nrc.gov (mailto:Carol.Moyer@nrc.gov]

Sent: Friday, 19 May 2017 23:19 To: KRIVANEK, Robert <R.Krivanek@iaea.org>

Cc: KANG, Ki-Sig <K.S.Kang@iaea.org>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE : CN246_PUM_Abstract deadline extended to 19 May 2017

Dear Mr. Krivanek,

The U.S. NRC intends to submit several abstracts for consideration for the PLiM conference in October. We have a short delay in completing one of our abstracts.

will be submitting it early next week, and I hope that you still will be able to consider it for the conference.

Thank you ,

Carol Moyer

Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol.mover@.nrc.gov 301-415-2153 From: R.Krivanek@iaea .org (mailto:R.Krivanek@ iaea.org1 Sent: Friday, April 21, 2017 8:44 AM To: R.Krivanek@iaea.org

Subject:

[External_Sender] CN246_PLiM_Abstract deadline extended to 19 May 2017

Dear all,

Please be informed that we extended the abstract submission deadline to 19 May 2017 and updated the conference accordingly.

Best regards, Mr Robert KRIVANEK I Senior Safety Officer I LTO Programme Manager Operational Safety Section I Division of Nuclear Installation Safety IDepartment of Nuclear Safety and Security Internationa l Atomic Energy Agency I Vienna International Centre, PO Box 100, 1400 Vienna, Austria I Email: r.krivanek@ iaea.org I T: (+43-1) 2600-22018 I F: (+43-1) 2600-26007 I

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This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not

read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system .

This email message is intended only for the use of the named recipient. Information contained in this email message and its attachments may be privileged, confidential and protected from disclosure. If you are not the intended recipient, please do not read, copy, use or disclose this communication to others. Also please notify the sender by replying to this message and then delete it from your system.

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

Unless otherwise expressed in this message by the sender or except as may be allowed by separate written agreement between EPRI and recipient or recipient's employer, any review, use, distribution or disclosure by others of this message is prohibited and this message is not intended to be an electronic signature, instrument or anything that may fom1 a legally binding agreement with EPRI. If you are not the intended recipient, please contact the sender by reply email and permanently delete all copies of this message. Please be advised that the message and its contents may be disclosed, accessed and reviewed by the sender's email system administrator and/or provider. ***

From: Tregoning, Robert Sent: Thu, 9 Feb 2017 11:56:39 +0000 To: 'NHILI Regis' Cc: Hiser, M atthew;Purtscher, Patrick

Subject:

RE: RE: [External_Sender] RE: RE: RE: RE: RE: Harvesting Workshop Regis:

Thanks for letting me know your situation. While I'm sorry that you won't be able to attend the workshop, I certainly understand. We will be developing a meeting summary. We should be able to provide you with the meeting summary when it's completed.

Please let me know if you have any other questions.

Warm regards, 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: NHILI Regis [mailto: regis.nhili@edf.fr]

Sent: Thursday, February 09, 2017 2:58 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender] RE: [External_Sender] RE: RE: RE: RE: RE: Harvesting Workshop Hi Rob, I have just been informed I need to attend an important meeting on March 7 in France.

So unfortunately, I am not able to participate to your workshop.

I am afraid I don't see any other colleagues who might be able to participate.

So I don't think it is necessary to have a call today.

Is it possible to be informed about the main outcomes of the workshop?

Thank you for your understanding.

Regards, Regis

De : Robert.Tregoning@nrc.gov (mailto:Robert.Tregoning@nrc.gov]

Envoye : mercredi 8 fevrier 201717:03 A: NHILI Regis Objet: Re: [External_Sender] RE: RE: RE: RE: RE: Harvesting Workshop Regis:

Great, I'm looking forward to it!

Rob

Original Message --------

From: NHILI Regis <regi s.nh ili@edf.fr>

Date: Wed, February 08, 2017 10:46 AM -0500 To: "Tregoning, Robert" <Robe1t.Tregoning@nrc.gov>

Subject:

[External_Sender] RE: RE: RE: RE: RE: Harvesting Workshop

Rob, I will call you tomorrow at 4pm .

Regards, Regis De : Tregoning, Robert [mailto: Robert.Tregoning@nrc.gov]

Envoye : mercredi 8 fevrier 201712:42 A: NHILI Regis Objet : RE: RE: RE: RE: RE: Harvesting Workshop Regis:

That should be fine. I have another call at 3:00pm Paris time tomorrow, but we should be finished by 4:00pm. Would you like me to call you?

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: NHILI Regis (mailto:regis.nhili@edf.fr)

Sent: Wednesday, February 08, 2017 2:37 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender) RE : RE : RE: RE: Harvesting Workshop

Rob, I suggest having the call at 4pm (Paris Time) tomorrow. Otherwise I can make at 5 or 6.

Regards, Regis Regis N HILI MAI Director EDF - R&D Materials Ageing Institute (MAI)

EDF LAB Les Renardieres - ECUELLES 77818 Moret-sur-Loing Cedex regis.nhili@edf.fr Landline : +33 (0) 1 60 73 68 47 Mobile : I J(~}(~)

De : Robert.Tregoning@nrc.gov (mailto:Robert.Tregoning@nrc.gov]

Envoye : mardi 7 fevrier 2017 19:03 A: NHILI Regis Cc : Matthew.Hiser@nrc.gov; Patrick.Purtscher@nrc.gov; SZW EDEK Olivier; LECLERCQ Sylvain; SOU LACROIX Julian Objet : RE: RE: RE: RE: Harvesting Workshop Regis:

Attached are the slides I mentioned to Julian. The slides contain more information on the workshop logistics, overall objectives, and the objectives of each session. I'm certainly available for a call on the 9th . I have another call at 3pm (Paris time), but other than that I'm free. Just let me know what time is most convenient for you.

Warm regards, 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: NHILI Regis [mailto:regis.nhili@edf.fr)

Sent: Tuesday, February 07, 2017 11:26 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

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

SZWEDEK Olivier <olivier.szwedek@edf.fr>; LECLERCQ Sylvain <sylvain.leclercq@edf.fr>; SOU LACROIX Julian <julian.soulacroix@edf.fr>

Subject:

[External_Sender) RE: RE: RE: Harvesting Workshop

Dear Rob,

I might be interested to participate to this workshop to present briefly the MAI R&D activities and the use of data from harvested components (BMN, Cables, SG).

Are you available for a quick call tomorrow (8th) after 5pm Paris Time (i.e. 11am Washington Time) or anytime Thursday 9th afternoon Paris Time?

In the meantime, do you have more information about the content of the workshop? (you mentioned some slides to Julian).

Kind regards, Regis Regis NHILI MAI Director EDF - R&D Materials Ageing Institute (MAI)

EDF LAB Les Renardieres - ECUELLES 77818 Moret-sur-Loing Cedex reqls.n hlll@edf.fr Landline : +33 (0) 1 60 73 68 47 Mobile f . . . . . . . . . . . . . !.(~)(E3)

De: Robert.Tregoning@nrc.gov [5]

Envoye: lundi 6 fevrier 2017 19:33 A. : SOULACROIX Julian Cc: Matthew.Hiser@nrc.gov; Patrick.Purtscher@nrc.gov; SZWEDEK Olivier; LECLERCQ Sylvain; NHILI

Regis Objet : RE: RE: RE: Harvesting Workshop

Dear Dr. Soulacroix:

Thank you for clarifying your situation. While I am sorry that you have decided not to participate in the workshop, I recognize that the workshop objectives which focus on future harvesting needs and implementing a more efficient harvesting program are somewhat specialized. For your information, both Oak Ridge National Laboratory and Pacific Northwest National Laboratory will be participating so we will have U.S. laboratory involvement.

I will keep you on the mailing list for the final agenda that will list speakers and talks. This will be developed within the next week or so. Perhaps there is still time to find someone from MAI or EDF who may be interested in participating in the workshop. Please let me know if you have any ideas for a representativ,e that I can contact within the next several days.

Thank you for your help and support.

All the best, 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: SOU LACROIX Julian [6]

Sent: Monday, February 06, 2017 11:41 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

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

SZWEDEK Olivier <olivier.szwedek@edf.fr>; LECLERCQ Sylvain <svlvain.leclercq@edf.fr>; NHILI Regis

<regis.nhili@edf.fr>

Subject:

[External_Sender] RE: RE: Harvesting Workshop

Dear M. Tregoning,

I am sorry to see that there was a misunderstanding on the content of this workshop.

Although this workshop is definitely very interesting for the different harvesting issues, it does not seem appropriate to a laboratory contribution.

Therefore I have to cancel my participation to this workshop. I apologize for the inconvenience.

We have already notified Regis Nhili, and I am sure he will come back to you if a EDF participation is still possible.

Warm regards, Julian SOU LACROIX CEIDRE - DLAB - MEM Tel. : 02.47.98.67.14 Tel portable :l.__ _. . _

. . . ...,J( b)(6 )

De: Robert.Treqoning@nrc.gov [7]

Envoye : jeudi 2 fevrier 2017 22:16 A. : SOULACROIX Julian Cc: Matthew.Hiser@nrc.gov; Patrick.Purtscher@nrc.gov Objet : RE: RE: Harvesting Workshop

Dear M. Soulacroix:

Thank you for replying to my email. I've attached some slides that provide logistical information along with descriptions of the objectives and format for each of the workshop sessions. Please use these slides as guidance when developing your talk. As you can see by the slides and the other information I've communicated , the principal objective of the workshop is to develop a more effective, better informed process for conducting harvesting programs with not a large focus on what technical information has been obtained from harvesting programs. I think that the topics you proposed below can meet this objective but please let me suggest the following ways to focus the topics you proposed below to align with the workshop objectives.

1. Your topic of " ... the contributions of a few studies that we recently carried out on harvested materials to the EDF" could fit really well within Session 4 if it focuses more on the harvesting process used in these studies and the lessons that could be applied for future harvesting programs. While the technical knowledge gained from the program is certainly interesting, it is not the focus of this particular workshop.

2. Your plans for the decommissioned steam generator project could fit well within session 2 if it focuses on the important data/technical needs that will be achieved as part of that program.

3. The description of the new EDF hot laboratory will certainly be interesting to many of the workshop attendees but discussing capabilities at laboratory facilities is not an objective of this particular workshop. I'm wondering if you have a brochure or other literature that could be handed out. Also, this could be part of your presentation. We wouldn't spend time during the meeting discussing it, but all the participants could take this home electronically.

In summary, I'm proposing that you give two separate, shorter talks (instead of a single longer talk): your talk on recent studies (item 1 above) would be in Session 4 and your talk on plans or the decommissioned steam generator project (item 2 above) would be in Session 2.

What are your thoughts about this proposal? Are the workshop objectives, scope, and format clear to you, especially after reviewing the attached slides? Please let me know if you would like to have a phone call to discuss further.

I'm very excited about MAi's participation in the workshop and I'm hoping that it will be a productive two-days for everyone. I'm especially looking forward to meeting you. You will need to bring your passport. I'll be in touch as the meeting gets closer with additional details.

Warm regards, 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: SOU LACROIX Julian [8]

Sent: Thursday, February 02, 2017 11:25 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

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

Subject:

[External_Sender] RE : Harvesting Workshop

Dear M. Tregoning,

I can confirm that I will be able to participate to the workshop.

I can propose a 30 minutes presentation describing the new EDF hot laboratory, the contribution of a few studies that we recently carried out on harvested material to the EDF strategy, and lastly the Sherlock project (examination program planned on a decommissioned Steam Generator).

Does it sound appropriate to you ?

Furt hermore, do you need any complementary information for accessing NRC site (passport ... ) ?

With kind regards Julian SOU LACROIX CEIDRE - DLAB - MEM Tel. : 02.47.98.67.14 Tel portable 1.__ _...._

.............. I .{p.){~L De: Robert.Tregoning@nrc.gov [9]

Envoye: mardi 31 janvier 2017 12:38 A. : SOULACROIX Julian Cc: Matthew.Hiser@nrc.gov; Patrick.Purtscher@nrc.gov Objet: Harvesting Workshop Dr. Soulacroix:

Thank you for your interest and willingness to participate in the workshop. I have attached the workshop announcement along with a few slides describing the motivation for the workshop and the expectations for each session. The workshop is divided into 5 sessions, each with a combination of presentations and discussion:

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 We would like to invite you to present in any of these sessions. We are most interested in MAI participation in sessions 1, 3, and 5 but we would also welcome participation in sessions 2 and

4. For sessions 1, 3, and 5, we are looking for brief 5-10 minute presentations, so just a few slides at most on motivation for harvesting, sources of materials, and any future harvesting plans. For sessions 2 and 4, the presentations are anticipated to be longer, perhaps 20-30 minutes, covering lessons learned from previous harvesting experience (session 4) and data needs best addressed through harvesting (session 2).

Please let me know if you would be able to participate and which sessions you would be willing to support. We will look forward to your participation and contribution to the workshop!

Rob 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 a

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Note to requester: The attachment is immediately following, and is also publicly available in ADAMS at ML16145A001 .

From: Purtscher, Patrick Sent: Mon, 17 Oct 201613:07:58 +0000 To: Ramuhalli, Pradeep

Subject:

RE: RE: harvesting program update Attachments: eval for pulled tubes ML16145A001.pdf Good morning, Here is another example of harvesting that you could reference, but probably don't need to say much about in the report.

When do you think you can get us a draft to review?

Pat From: Ramuhalli, Pradeep [10]

Sent: Thursday, October 06, 2016 1:58 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>

Subject:

[External_Sender] RE: harvesting program update Patrick, Just getting out of another call. Will call in in a couple of minutes.

With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Emai l: pradeep.ramuhalli@pnnl.gov

Original Appointment-----

From: Purtscher, Patrick (mailto:Patrick.Purtscher@nrc.gov]

Sent: Tuesday, October 04, 2016 3:51 AM To: Purtscher, Patrick; Ramuhalli, Pradeep; Hiser, Matthew

Subject:

harvesting program update When: Thu rsday, October 06, 2016 2:00 PM-2:30 PM (UTC-05:00) Eastern Time (US & Canada).

Where: tel con

TECHNICAL LETTER REPORT Evaluation of Possible Examinations for Pulled Steam Generator Tubes May 4, 2016 Prepared by Matthew Rossi US Nuclear Regulatory Commission Rockville, MD 20852 Chi Bum Bahn Argonne National Laboratory Lemont, Illinois 60439 NRC Contract# JCN-N6582 Program Manager: Matthew Rossi

Introduction The US Nuclear Regulatory Commission (NRC) is interested in the causes of steam generator (SG) tube degradation, including wear and cracking. One of the best ways to gain information about degraded SG tubes is to examine tubes that have been removed from operating generators, i.e. a "pulled tube." However, pulling a tube from an operating or retired SG has high financial costs and can result in high radiation dose to personnel; therefore, pulling a tube is a rare event. To better capitalize on these rare events, the NRC researched the types of information that can be gained from the various m ethods used t o examine pulled tubes. An initial literature review found some studies that reviewed the tests which are performed on pulled tubes. This report, in addition to reviewing tube examination methods and their benefits, discusses two guidelines on SG pu lled tube examination: t he Canadian Nuclear Safety Commission (CNSC) Guidelines [1] and the Electric Power Research Institute (EPRI) Guidelines [2]. Actual SG pulled tube examination results are also available in the appendix of the EPRI Guidelines (2] and other open literature (3-7].

Most currently operating SGs contain tubes made from more corrosion resistant materials, such as Alloy 690 or Alloy 800. Therefore, the incidence of cracking in current SGs is low. In fact, as of the time of publication, there have been no reported stress corrosion cracks in Alloy 690 tubes anywhere in the United States. Consequently, the majority of flaws in newer SGs are wear flaws. However, this report on examination techniques is focused on flaws that initiate as a result of stress corrosion cracking or fatigu e cracking, since the root causes of wear defects would most likely be found from design review, analyses, or visual inspection rather than destructive examination of pulled tubes.

CNSC Guidelines The CNSC Guidelines for the examination of pulled SG tubes (1] are discussed below.

Table 1 shows the elements of a SG tube material surveillance examination suggested by CNSC. The primary elements are mand atory although some elements, such as the identification of root causes, are only required when degradation is present. The secondary elements are considered, based on the results from the primary elements.

Table 1. Elements of a steam generator tube material surveillance examination [1].

Element Description Comments Primary Manner of tube removal Required for all exams Elements Suitability of locations examined and examination Required for all exams methods used Identification of significant flaws and conditions Required when degradation is present Identification of root causes Required when degradation is present Estimation of rates of growth of flaws Required when degradation is present Flaw size determination Required wh en degradation is p resent Deposit cha racterization Required wh en 1

I degradation is present 2

Secondary Use of plastic straining None Elements Use of additional methods to check for aggr essive None species Gathering and analysis of deposits None EPRI Guidelines Also considered were the EPRI guidelines for tube removal and examination (2]. The EPRI test and examination methods are categorized into three main areas: Nondestructive Evaluations (NDE) , Pressure Tests, and Metallurgical and Local Chemical Examination. Five m ain reasons for tube r emoval a re identified: Con dition Monitoring and Operational Assessment, NDE Verification, Support of Alternate Repair Criteria (ARC), Chemistry Evaluation, and General Condition Assessment. Table 2 shows the recommended tests and examinations for SG pulled tubes for each tube removal reason. Some evaluations, such as visual inspection, bobbin and rotating probe eddy current tests, and base material ch aracterization (by destructive m ethods or other NDE methods), are recommended for all pulled tube sections. Base material characterization procedures include tensile testing, microstructural examination by optical or electron microscopy, hardness tests, chemical assay, and sensitization tests. NDE includes use of all techniques used in SG tube evaluation: Eddy current (EC), ultras onic test ing (UT), tomography, and radiography. Pressure testing may also be performed for information on leak rates and critical crack opening displacement.

Table 2. Recommended tests and examinations for SG pulled tubes per each tube removal reason [2).

Reason for Exam Exam Methods Description All Tube Nondestructive

Performed prior to any cleaning or decontamination Sections Evaluations

Unmagnified & magnified visual inspection

Dimensional measurements

Bobbin coil EC testing and rotating probe EC testing Base Material

Tensile test using materials from undeformed a r ea Characterization with no detected flaws

Microhardness of base materials across wall thickness

Chemical composition & Microstructure of base material

Sensitization test Condition Nondestructive

NDE using all techniques used in situ Monitoring and Evaluations

Radiography of flaw area Operational

Helium leak test if there is a question about the Assessment possible presence of a small throughwall flaw Pressure Tests

Leak and burst tests of areas with s ignificant flaws

Burst tests of areas with no detected flaws and no significant deformation Metallurgical and

Determine the extent of the major fla ws Local Chemical

Determine th e morphology of major flaws Examination 3

NDE Verification Nondestructive

NDE using all techniques used in SG Evaluations

Radiography of areas with significant NDE indications

Additional NDE techniques for which verification data are desired

Helium leak test if there is a question about the possible presence of a small throughwall flaw Pressure Tests

Leak and burst tests of areas with s ignificant flaws

Burst tests of areas with no detected flaws to establish a baseline Metallurgical and

Consider a method for opening up the flaws and Local Chemical assisting in their detection (swelling, bending, etc.)

Examination

Stereovisual and Scanning Electron Microscopy (SEM) examination of burst test ruptures and other areas (flaws size, morphology, etc.)

Sectioning followed by optical metallography and/ or SEM examination Support of ARC Nondestructive

NDE using ARC technique Evaluations Pressure Tests

Leak test if the maximum flaw depth by NDE is

>80%TW, followed by visual examination to record flaw size opening, if leakage occurs

Burst test of flaw area

Burst tests of areas with no detectable flaws (not mandatory)

Tensile tests (alternate to burst test for a circumferential flaw)

Metallurgical and

Stereovisual and SEM examination of ARC area Local Chemical (flaw s ize, morphology, etc.)

Examination

A full SEM montage of the burst crack face at about 40X and a crack profile.

Sectioning followed by optical metallography and/ or SEM examination Chemistry Metallurgical and

Swelling, axial extension, flattening, and/ or Evaluation Local Chemical bending of flaw areas and examination using SEM, Examination optical metallography, and local surface chemical analysis techniques

Stereovisual and SEM examination of ARC area (flaw size, morphology, etc.)

Sectioning followed by optical metallography and/ or SEM examination

Chemical analysis of deposits at freespan and crevice areas that are still attached

Chemical analysis of deposits from freespan and crevice areas that were removed

Tube surface chemical analysis after the removal of the deposits

Fracture surface chemical analysis

Possibly, chemical analysis of leachates from tube surfaces 4

General Nondestructive

Examination using as sensitive NDE techniques as Condition Evaluations available Assessment Plastic Straining

Tensile tests to Open Up Flaws

Bending

Pressure testing

Mechanically roll expanding the ID (suitable for OD axial or volumetric flaws)

Metallurgical and

Swelling, axial extension, flattening, and/or Local Chemical bending of the most susceptible areas and Examination examination using SEM, optical metallography

Longitudinal sectioning followed by s tereovisual examination of ID surfaces

Stereovisual and SEM examination of any visual flaws (morphology, fracture type, etc.)

Sectioning followed by optical metallography and/ or SEM examination to define morphology of IGA

Sectioning followed by optical metallography and/ or SEM examination of potentially susceptible areas

Chemical analysis of deposits at freespan and crevice areas that are still attached

Chemical analysis of deposits from freespan and crevice areas that were removed

Tube surface chemical analysis after the removal of the deposits

Fracture surface chemical analysis

Possibly, chemical analysis of leachates from tube surfaces Discussion of Examination Purposes Non-destructive and destructive examinations serve many purposes, including:

1) identification of flaws, 2) sizing of flaws, 3) base material characterization,

4) characterization of deposits, 5) tube integrity characterization, and 6) root cause identification.

The six examination purposes listed above are discussed below.

1) Flaw Identification: Destructive or NDE methods may be applied to a pulled tube to identify flaw types and characteristics. Also, testing may be used to verify results of eddy current inservice inspections (ISi).

Some appropriate examination procedures for flaw identification are optical microscopy (metallography) for large size (i.e. visible) flaws, scanning electron microscopy to view fracture surfaces or to view cross sections of crack-lik e flaws in polished and etched samples, and EC, UT, radiography, and tomography to employ as an NDE technique for flaw location or depth below the material surface.

5

2) Flaw sizing: All of the techniques mentioned above for flaw identification also apply to flaw sizing. Again, physical examination may give true flaw s ize information, which may be used to verify the ISi eddy current scan measurements. Also, a comparison of the pulled tube eddy current data to ISi data on the same tube may be valuable for noise and masking effects from tube supports or the tubesheet.

3) Base material characterization: The properties of the base material may be examined for signs of change. Any significant changes in base material properties could be indications of issues with the material itself, or the effects of operating conditions or local environment.

Metallography, electron microscopy, and the other macro- and microstructural examination techniques listed in Table 2 may be employed. Structural integrity changes may be assessed with tensile, fatigue, leak, or burst testing.

4) Characterization of foreign deposits: Many chemical analysis methods exist to characterize deposits on pulled tubes. Atomic absorption s pectrophotometry, x-ray or UV fluorescence would be ideal for a quick identification of elemental composition.

For more detailed information on the possible compounds, electron microscopy, energy dispersive and wavelength dispersive x-ray analysis, transmission electron microscopy, auger analysis, and atomic force methods may be used.

5) Tube integrity characterization: Pressure or leak rate tests may be performed on pulled tubes, or sections thereof, to assess the integrity of the tube. Also, mechanical tests, such as tensile or fracture toughness, may be performed for evaluating mechanical properties.

6) Root cause analysis: Root causes of cracking includes vibrations, foreign matter, operator error, or other possible causes. Use of any or a ll of the above mentioned procedures could yield information about the type of defect, local chemistry, or any deposits. Use of that information, combined with the operating history, conditions, and human factors could yield a root cause determination.

In addition to the above methods, other methods to consider in evaluating pulled tubes are discussed below.

NOE is often used to gain interior and exterior surface information, without a ltering, damaging or destroying the material of a specimen. For a pulled tube specimen, some additional NOE techniques are discussed here:

Radiography is sometimes used to examine cracks in SG tube sections. Radiographs can show interior defects and structures. Synchrotron X-ray micro Computed Tomography (µCT) can provide a better spatial resolution with 3-dimensinal (3-0) crack imaging than conventional radiography. Intergranular stress corrosion cracking has been observed by in situ Synchrotron X-ray µCT (8]. This method permits seeing a 3-0 crack morphology without sectioning the pulled tube. It is noted, however, that there will be a limit to the volume of interest that can be analyzed at any one time. Synchrotron X-radiation may be used not only to obtain tomographic information of cracks but also to obtain a better spatial resolution than conventional phase analysis using in-house X-ray sources or residual stress measurement by X-ray diffraction.

Stress corrosion cracking has been a cause of defects in SG tubes. The chemistry of the water environment on the secondary side (and primary s ide) is an important factor in cracking control. Some contaminants, i.e. lead, may contribute to SG tube cracking. Therefore, a chemical analysis may be very beneficial. 3-D Atom Probe Tomography (3-D APT) is another advanced technique to characterize the local chemistry. When the local chemistry (e .g., along 6

grain boundary or at the crack tip) needs to be evaluated , 3-D AfYf can provide information on the elemental distribution with atomic resolution [9].

Atomic Force Microscopy (AFM) is one of the emerging analysis tools in materials science and engineering field. Sectioned tube samples examined using AFM can provide various microstructural information on a nano-meter scale. Although AFM provides topological information, it is not limited to just topology. AFM can be run in various modes: conducting, work function, magnetic, nano-indentation, or tapping (elastic modulus m a pping). One of advantages of AFM is that analysis is performed in an ambien t condition so that a vacuum system is not required.

Cracking may occur along grain boundaries if the material h as had diffusion of components (chromium depletion, for example) away from boundaries, or deposits of foreign elements (e.g. lead) at grain boundaries. Orientation Image Microscopy (OIM) is often used to analyze grain orientation and grain boundary mismatching. More recently, OIM has been used as a tool to obtain residual strain distribution in grain s. The strain mapping near the crack tip can b e performed using OIM [7].

Summary A main objective of th is report was to evaluate the in formation gained by various methods which are used to examine pulled SG tubes. The intent was to u nders tand how to examine pulled tubes to enhance understanding of root causes of defects and to ensure tube integrity.

Many examination techniques for pulled SG tubes were reviewed, along with th e types of information gained from each examination technique. The CNSC and EPRI guidelines for pulled tube examinations were discussed to provide insights and procedures used in industry.

Combinations of many existing analytical apparatus and techniques may be used to explore physical characteristics, defect parameters, tube integrity, and possibly contribute to determination of the root causes of defects.

References

1. 8. Carroll, S. Liu, J . Riznic, N. Christodoulou, and R. Awad, "CNSC Proposed Guidelines for the Examination of Steam Generator Tubes Removed for Periodic Surveillance," Proc.

6 th CNS International Steam Generator Conference, Toronto, Ontario, Canada, Nov. 8-11, 2009.

2. J. A. Gorman and A. P. L. Turner, "Guidelines for PWR Steam Generator Tubing Specification and Repair, Volume 4, Revision 1: Guidelines for Tube Section Removal and Examination," TR-016743-V4Rl, Electric Power Research Institute, 1997.

3. L. J. Sykes and P.A. Sherburne, "Analysis of Steam Ge nerator Tubing from Oconee Unit 1 Nuclear Station," TR-106484 S413-12, Electric Power Research Institute, 1997.

4. Francois Cattant, "Lessons learned from the examination of tubes pulled from Electricite de France steam generators," Nucl. En g. Des. 168 (1 997) 241-253.

5. S. S. Hwang, D. H. Hur, J . H. Han, and J. S. Kim, "PWSCC of thermally treated alloy 600 pulled from a Korean plant," Nucl. Eng. Des. 127 (2002) 237-245.

6. D. H. Hur, D. H. Lee, M. S. Choi, M. H. Song, and J. H. Han, "Root causes of in tergranular attack in an operating nuclear steam generator tube," J. Nucl. Mater. 375 (2008) 382-387.

7

7. S . Pagan, X. Duan, M. J. Kozluk, B. Mills, and G. Goszczynski, "Characterization and structural integrity tests of ex-service steam generator tubes at Ontario Power Generation," Nucl. Eng. Des. 239 (2009) 477-483.

8. A. King, G. Johnson, D. Engelberg, W. Ludwig, J . Marrow, "Observations of intergranular stress corrosion cracking in a grain-mapped polycrystal," Science 321 (2008) 382- 385.

9. A. Etienne, 8 . Radiguet, P. Pareige, J .-P. Massoud, and C. Pokor, "Tomographic atom probe characterization of the microstructure of a cold worked 316 austenitic stainless steel after neutron irradiation," J . Nucl. Mater. 382 (2008) 64-69.

8

From: Tregoning, Robert Sent: Tue, 20 Dec 2016 15:33:50 +0000 To: 'Reister, Richard'

Subject:

RE: RE: Harvesting Workshop Rich:

Thanks for your reply and POC list. I agree that the speakers and timing need work and that we'll need to work together to achieve that. I've gotten inquiries from NRAJ, CRIEPI, and SCK-CEN about participating thus far. I'm trying to understand which sessions, if any, they might best support. I'll summarize there proposed participation once I understand it better and share it with you and/or the other session chairs so we can determine if/how we want them to participate.

Have a Happy Holidays and peaceful New Year.

Regards, 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: Reister, Richard [11]

Sent: Tuesday, December 20, 2016 10:22 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Cc: Hiser, M atthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Dyle, Robin <rdyle@epri.com>; Bernhoft, Sherry [sbernhoft@epri.com] (sbernhoft@epri.com)

<sbernhoft@epri.com>

Subject:

[External_Sender] RE: Harvesting Workshop Rob:

For DOE I would recommend the following POCs:

Session 1: Rich Reister Session 2: Keith Leonard (ORNL)

Session 3: Tom Rosseel (ORNL)

Session 4: Tom Rosseel Session 5: Rich Reister

Regarding the draft agenda, I don't have any further comments at this point, but the speakers and timing still need some work. I'm sure this will come together based on further discussions as we line up speakers and attendees.

Rich From: Tregoning, Robert (mailto:Robert.Tregoning@nrc.gov]

Sent: Thursday, December 15, 2016 3:54 PM To: Bernhoft, Sherry [sbernhoft@epri.com] (sbernhoft@epri.com ) <sbernhoft@epri .com>; Reister, Richard <Richard.Reister@nuclear.energy.gov>

Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purt scher@nrc.gov>; Dyle, Robin <rdyle@epri.com>

Subject:

Harvesting Workshop Sherry/Rich:

I wanted to thank you again for the discussion that we had last week on the harvesting workshop agenda. I think it was productive and I appreciate the perspective you both brought.

I've attached an announcement for the workshop that were planning to use to solicit participants. Also, we've revised the agenda substantially based on the feedback you both provided. I think it captures the issues you had and I personally think that this is a better model to follow for the workshop.

I'd like to ask you both for two things prior to leaving for the holidays.

1. Could you provide me with any additional changes to the workshop agenda that you recommend? Just mark-up and send back the attached agenda. I'll consolidate and address any remaining suggestions from you both.

2. Could you provide me with a POC for coordinating each of the 5 workshop sessions?

The idea is for the POCs to work together for planning each session. Here are the POCs from the NRC:

a. Session 1 - Rob Tregoning

b. Session 2 - Matt Hiser

c. Session 3 - Pat Purtscher

d. Session 4 - Matt Hiser

e. Session 5 - Rob Tregoning We're hoping to get the planning teams in place before Christmas so that we can hit the ground running in early January to line up all the speakers.

Thanks again for your help. If I don't talk to you beforehand, I hope both you and your families have a Happy Holidays and a Prosperous New Year.

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 20:04:45 +0000 To: Hiser, Matthew

Subject:

RE: RE: Harvesting Workshop Sessions 3 & 4 Matt:

Might be good to follow up w ith a call to Jim and Heather if we don't hear from them within the next week. I can be on call with you .....

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 18, 2017 12:25 PM To: Molkenthin, Jim <molkenjp@westinghouse.com>; Heather Malikowski

<Heather.Malikowski@exeloncorp.com>

Cc: 'Burgos, Brian' <bburgos@epri.com>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

RE : RE: Harvesting Workshop Sessions 3 & 4 Hi Jim and Heather:

NRC is working with EPRI and DOE to host a workshop on ex-plant materials harvesting in early March at NRC HQ in Rockville, MD. I have attached an announcement and condensed workshop agenda for your information and background.

One of the sessions we have planned is on Sources of Materials, which includes archived materials from past harvesting programs as well as future harvesting opportunities. Brian suggested the PWROG may have information related to archive materials held by vendors that could be relevant to this discussion.

For this session, we are looking at short presentations (maybe 2-3 slides, 5-10 min) providing information on sources of harvested materials.

We would certainly appreciate any information on sources of harvested materials that the PWROG can provide or help compile. If you would like to attend the workshop and present, that could work or, if you're unable to attend, you could provide input to myself or EPRI that could be incorporated into our slides.

Thanks!

Matt Hiser

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 I5-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov From: Burgos, Brian [mailto:bburgos@epri.com)

Sent: Wednesday, January 18, 2017 9:37 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Cc: M olkenthin, Jim <molkenjp@westinghouse.com>; Heather Malikowski

<Heather.Malikowski@exeloncorp.com>

Subject:

[External_Sender) RE: Harvesting Workshop Sessions 3 & 4

Matt, Per our discussions yesterday regarding the potential that the PWROG may have information related to materials stored in archives at vendors (e.g., surveillance specimens, flux thimble tubes, etc ... }, please reach out to Jim M olkenthi n (WEC Program M anager) and Heather Malikowski (M aterials Subcommittee Chairman). As I mentioned, they would be a good starting poi nt to help with information for archived materials to support your harvesting workshop. They are copied on t he email.

Brian From: Demma, Anne Sent: Tuesday, January 17, 2017 3:15 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Burgos, Brian <bburgos@epri.com>

Cc: Bernhoft, Sherry <sbernhoft@epri.com>; Dyle, Robin <rdyle@epri.com>

Subject:

RE: Harvesting Workshop Sessions 3 & 4

Matt, I am forwarding your notes to Brian for his information.

Thank you, Anne From: Hiser, Matthew (mai1to:1Matthew.Hiser@nrc.gov)

Sent: Tuesday, January 17, 2017 12:36 PM To: Bernhoft, Sherry <sbernhoft@epri.com>; Rosseel, Thomas M. <rosseeltm@ornl.gov>; Dyle, Robin

<rdyle@epri.com>; Demma, Anne <ademma@epri.com>

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

Subject:

[EXTERNAL) RE: Harvesting Workshop Sessions 3 & 4

- - Exercise caution. This is an EXTERNAL email. DO NOT open attachments or click links from unknown senders or unexpected email. ***.

Thanks everyone for participating today. I appreciate all tine comments and suggestions and we'll adjust the agenda accordingly.

One follow-up: could DOE and EPRI identify who they expect their presenter to be for each of the 5 sessions?

Notes from today's call:

Matt H. described general plans for workshop:

Non-public, keep participation to around 30 individuals for more focused interactive discussion

Goal is to have well-balanced discussion of harvesting, not sales pitches for specific projects or programs

Sherry B. suggested fewer presentations with more panel discussion time

Plan is for roughly 50-60% presentations and remaining time for discussion

Sessions 1 and 5 should be primarily panel discussion

Session 2:

Question raised about covering metals, cables, and concrete

Agreed that all presenters can cover all three types materials, hopefully just a few slides

Suggest presenters focus on high-priority data needs from their organization's perspective

Perhaps some background on what informs their priorities

Session 3:

Suggestions to include EnergySolutions, PWROG, Korea, Japan, and French presentation slots

Emphasize to presenters to avoid "sales pitch," but please provide information on sources of materials

Short -10 min presentations on sources of materials with remaining time for discussion

Hopefully use presented information as starting point for previously harvested materials database

Session 4:

Longer (20-30 min) presentations focused on forward-looking lessons learned

Suggestion to reach out to Exelon (Zion experience plus many operating facilities) if Dominion can't support

Also consider Japan and France for international presentations Actions:

Brian Bergos provide Matt with PWROG contact

Matt look into if affidavit would be needed for any proprietary information from EPRl/industry

Matt update agenda for sessions 3 and 4 and finalize speakers Thanks!

Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Offi ce o f Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Pho11e: 301-415-2454 I Office: TWFN 10D62 M atthew.Hiser@nrc.gov

Original Appointment-----

From: Hiser, Matthew Sent: Monday, January 16, 2017 9:48 AM To: Hiser, Matthew; Bernhoft, Sherry; Rosseel, Thomas M.; Dyle, Robin; Demma, Anne

Subject:

Harvesting Workshop Sessions 3 & 4 When: Tuesday, January 17, 20171:00 PM-2:00 PM (UTC-05:00) Eastern Time (US & Canada).

Where: Telecon: 888-677-8615 passcode:c:::::::J J91(t3)__

888-677-8615 passcode: [==1 (b}(t3)

<< File: Sessions 3 & 4.docx >> << File: Harvesting Workshop Agenda 1-12-17.docx >>

There have been previous discussions between NRC, DOE, and EPRI on the workshop agenda overall to discuss what the workshop is trying to accomplish and the best way to do so. Those conversations did not dig down into each session and make a final decision on exactly who will be the presenters and topics in each session. Internally here at NRC, we've worked to lay that out in the attached documents.

The purpose of this call is to discuss all the specifics of sessions 3 and 4 to identify the right presenters for each slot. This discussion could also lead to adding, eliminating or changing some of the planned presentations if you all have other ideas or suggestions. Our main goal is to have a well-balanced, comprehensive discussion of harvesting that will benefit all participants. We think working with you all up front to help plan and make decisions will give us a better workshop in the end. So please come with ideas and suggestions for sessions 3 and 4 on sources of materials and lessons learned/practical aspects of harvesting.

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

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

From: Tregoning, Robert Sent: Wed, 8 Feb 2017 11:39:53 +0000 To: *:J:&* -f~*

Cc: Hiser, Matthew;Purtscher, Patrick; 133 D fr!Jj$:;soneda@criepi.denken.or.jp;arait@criepi.denken.or.jp

Subject:

RE: RE: Harvesting workshop Kazu:

Thank you for the update. I'll look forward to getting an email from Dr. Arai with his ability to be a panelist during sessions 1 and 5. I look forward to seeing everyone from JNRA, CRIEPI, and JAEA next month at the workshop.

Warm regards, 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: t&* - ii [12]

Sent: Tuesday, February 07, 2017 5:39 PM To: Tregoning, Robert <Robert .Tregoning@nrc.gov>

Cc: Hiser, M atthew <Matthew.Hiser @nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; 83

jft <kiyotaka_taguchi@nsr.go.jp>; soneda@criepi.denken.or .jp; arait@criepi.denken.or.jp

Subject:

[External_Sender] RE: Harvesting workshop

Rob, I had a meeting with Dr. Soneda and Dr. Arai of CRIEPI yesterday.

I conveyed your expectation that CRIEPI guy take on panelist at session 1 or 5, and asked them to contact you directly.

However, I am not sure about that CRIEPI will be able to take on panelist since their situation is also complex.

Anyway, please confer with Dr. Arai who will participate in the workshop.

Sincer ely, Kazu

From: Tregoning, Robert Sent: Tue, 10 Jan 2017 11:55:07 +0000 To: 'CASTELAO LOPEZ CARLOS'

Subject:

RE: RE : Hello Carlos:

(b)(6)

(b)(6) ...._____ _ _ _ _ _ __, With respect to the harvesting workshop, I just want to make clear that the purpose is not to propose harvesting projects, but discuss what we've learned through our past projects (including Zorita), what things we can do better to plan for any future harvesting efforts, and what possible needs do we have that can best be served by harvesting.

We are only considering invited talks so that we can keep this as a working level meeting and not too big. However, if any of the Spanish organizations have a presentation that fits within the objectives of one of the sessions, we would certainly welcome it. Please let me know who from Spain is interested in attending, and if they would like to give a presentation, what the topic would be. You can also put them directly in touch with me.

Are you possibly interested in coming I r Warm regards, 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: CASTE LAO LOPEZ CARLOS [mailto:ccl@csn.es)

Sent: Tuesday, January 10, 2017 3:33 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender) RE: Hello Hello Rob, Well, I see that finally the hydro work remains as a working level document. The important point is that the information is there and can be used for the different organizations as they wish.

About the workshop on harvesting materials I will let the Spanish organizations that participated in the ZIRP to know about it, should they be interested in attending it. Is it possible to make presentations?

May be you know that Studsvik is also proposing a kind of research project, they call it SMILE, using materials from plants under decommissioning (they are proposing Ringhals). They made a presentation at the last CSN I meeting. I suppose you have access to it through your delegate, but if not I could forward it to you. We keep in touch.

Best regards, Carlos De: Tregoning, Robert [13]

Enviado el: martes, 03 de enero de 2017 13:41 Para: CASTELAO LOPEZ CARLOS <ccl@csn .es>

Asunto: RE: Hello Carlos:

Merry Christmas and Happy New Year to you as well. ! * * - - _J__ __(b)(6)

(b)(6) . l. . . . . . IRecall that we decided to just publish the hydro test report as a WGIAGE working level document, so this is now been completed (which is why it wasn't on

- ~?NI ~gE:!QQl!), Pleaseals.oJet.meknow .... - - - -

(b)(6)

- -the if you would like to discuss the upcoming workshop the NRC is having on harvesting materials from decommissioned NPPs. I look forward to hearing from you soon!

All my best, Rob From: CASTE LAO LOPEZ CARLOS [mailto:ccl@csn.es)

Sent: Friday, December 23, 2016 6:49 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender) Hello Hello Rob, (b)(6) L . .. !today I came to CSN. How are things going on? I couldn't att end the CSNI meeting, but I realized that the report about hydro t ests was not included in t he agenda. I know t hat I have a lot of e-mails to read to be aware of all ou have been doin , but so far I hadn't t ime.

(b)(6)

(b)(6) * ....................... ... .__ _ ___, I will let you know.

I read that you are proposing a workshop about R&D taking samples from decommissioning NPPs.

We will talk about it.

Merry Ch istmas and a Happy New Year.

Carlos

From: Tregoning, Robert Sent: Fri, 10 Feb 201712:47:07 +0000 To: Kirk, Mark;lyengar, Raj

Subject:

RE: RE: Meeting during Harvesting Workshop It's March. Change the 5 to a 3 in my dates below. Sorry about the confusion; I'm trying to do too many things at once this morning and my QA measures are clearly lacking .. ...

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: Kirk, Mark Sent: Friday, February 10, 2017 7:46 AM To: Tregoning, Robert <Robert .Tregoning@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>

Subject:

Re: RE: Meeting during Harvesting Workshop Rob-I thought the harvesting workshop wi ll be in March (month 3) not May (month 5). Assuming it is in March i am available at any of your proposed t imes.

best mark From: Tregoning, Robert Sent: Friday, February 10, 2017 6:55 AM To: Kirk, Mark; Iyengar, Raj

Subject:

FW: RE: Meeting during Harvesting Workshop Mark/Raj:

We've got all day Monday (5/6) and Thursday morning (5/9) as possible meeting times with Rach id. We could also meet with him during lunch on 5/7 or 5/8 or after the workshop either day. Let me know what your preferences are and I'll finalize the day and time.

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: Chaouadi Rachid [mailto:rachid.chaouadi@sckcen .be)

Sent: Friday, February 10, 2017 2:26 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender) RE: Meeting during Harvesting Workshop Sure Rob, I will be arriving during the weekend just before the workshop and leaving Thursday afternoon. Si There is plenty of time.

All the best Rach id Sent from my Windows Phone From : Tregoning, Robert Sent: 2/9/2017 21:30 To: Chaouadi Rachid

Subject:

Meeting during Harvesting Workshop Rachid :

I just want to reach out to see if it's possible to have a side meeting to discuss the RPV project that SCK is implementing on behalf of FANC? While we will certainly discuss this topic during the workshop, the scope of the workshop (and the time constraints) probably will not be conducive to a detailed project discussion. Would you have an hour or more either before, during, or after the workshop when we can discuss this project specifically? I would also like others, such as Mark Kirk, who may not be participating in the harvesting meeting, to be part of this more detailed meeting.

Thanks for your consideration, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pi ke Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-6671

..,,

J: 1\ )-c Ir rr _,_._,_*____l_ r _r _>_n_ _ _ _,_. _l_r_ *_- _-_r_ -_r From: Tregoning, Robert Sent: Tue, 20 Dec 2016 14:23:48 +0000 To: *:J:&* -f~*

Subject:

RE: RE: NRC Harvesting Workshop Kazu:

I'm sorry I have not gotten back to you sooner. Last week was very busy for me. Please see the responses to your questions below (in red). Please let me know if you have any other questions pertaining to the workshop. I hope that you and your family will have a Happy Holiday and a prosperous New Year.

Warm Regards, 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: i&* -1~ [14]

Sent: Monday, December 19, 2016 7:41 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender] RE: NRC Harvesting Workshop Hi Rob, To make sure my email transmission, I am sending following message again.

Your prompt reply is greatly appreciated for the approval to attend the workshop.

Best regards, Kazu From: :t:&;cJs; -ig Sent: Wednesday, December 14, 2016 11:08 AM To: 'Tregoning, Robert' Cc: EE ;*rt; 1N.l.J :iEn

Subject:

RE: NRC Harvesting Workshop

Rob, Thanks for the invitation.

As I told in August, we are really interested in participating the workshop because we would like to launch the research program using harvested material from decommissioned plant or replaced components.

Here, I want to make sure followings before I forward this info to Japanese organizations;

-Presentation at the workshop When NRA or other Japanese organizations participate in the workshop, do participants need to prepare presentation material? (Is it OK just joining the discussion?)

Participants do not need to make a presentation . In fact we are inviting organizations directly to give talks on specific topics. We are also trying to keep the workshop fairly small so that we can have good discussion.

If giving presentation is required, please understand that we only able to touch on our wish list that is similar material to August meeting so far, since we have not started the discussion on the topic with Japanese utilities yet.

We would be potentially interested in a talk from NRAJ on research needs that you want (or plan) to address by harvesting. Is this the talk that you propose? Are there any other talks related to the workshop sessions that you would propose to provide?

-Fruits from the workshop Do you anticipate to have consensus or make some recommendation for the future planning. (e.g. launch the international research program under OECD/NEA framework, what materials are participants want to have?)

The principal objective of the workshop is to develop a process for planning harvesting programs that considers all aspects (e.g. , needs, sources of materials, costs, and decommissioning plan) when determining the best approach . It is not an objective to launch an international research program based on the workshop. However, this may be something that organizations decide to pursue after the workshop has been completed.

I would appreciate if you could respond ASAP.

Best regards, Kazu From: Tregoning, Robert [ mailto:Robert.Tregoning@nrc.gov]

Sent: Wednesday, December 14, 2016 6:09 AM To: :rfi* - f~i

Subject:

NRC Harvesting Workshop Kazu:

As discussed in our August meeting, we're holding a workshop on harvesting in March of 2017.

I just sent the following announcement to Olli Nevander to distribute to CSNI members:

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 .

Please contact me if you 're interested in attending or would like to discuss further. I think it would be good to get a perspective from Asia on some of these topics so it would be good to discuss the best way to do this.

Warm regards ,

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

Note to requester: Attachment is immediately following.

From: Tregoning, Robert Se nt: Mon, 6 Feb 2017 13:41:01 +0000 To: 'Yasuhiro Chimi' Cc: Hiser, Matthew;Purtscher, Patrick

Subject:

RE: RE: Participation in Harvesting workshop from JAEA Attachments: Ex-Plant Materials Harvesting Workshop.pptx Dr. Chimi:

Thank you for replying to my email. We look fo1ward to your participation in the workshop. I've attached a slide packet that has some logistical information for your planning. We wiII also provide more logistical information closer to the workshop. Please let me know if you have any questions in the interim.

Warm regards, 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: 30 1-415-2324 fax: 301-415-667 1

Original Message-----

From: Yasuhiro Chimi [15]

Sent: Monday, February 06, 2017 8: 19 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

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

Subject:

[External_Sender) RE: Participation in Harvesting workshop from JAEA

Dear Mr. Tregoning,

Thank you very much for the detailed information on the harvesting workshop. I would like to participate in all the sessions.

Unfortunately, we do not have any plans and experience for harvesting programs yet, so I am afraid I cannot contribute to presentations in the sessions this time.

I look forward to participating in the workshop.

Best regards, Yasuhiro Chimi Yasuhiro Chimi, Ph.D.

Materials and Water Chemistry Research Group Materials and Structural Integrity Research Division Nuclear Safety

Research Center Sector of Nuclear Safety Research and Emergency Preparedness Japan Atomic Energy Agency (JAEA)

Phone: +81 282-6473 , Fax: +8 1-29-282-5406 E-mail: chimi.yasuhiro@jaea.go.jp

Original Message-----

From: Tregoning, Robert [16]

Sent: T uesday, January 31, 20 17 11 :03 PM To: Yasuhiro Chimi <chimi.yasuhiro@jaea.go.jp>

Cc: Hiser, Matthew <Matthcw.Hiser@nrc.gov>; Purtschcr, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

Partic ipation in Harvesting workshop from JAEA Dr. Chimi:

T hank you for your interest in the workshop. I have attached the workshop announcement and condensed agenda along with a few slides describing the motivation for the workshop and the expectations for each session . The workshop is divided into 5 sessions, each with a combination of presentations and discussion:

I. Session I will consist of short presentations and a pane l 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-leamed from past harvesting programs and practical aspects associated with harvesting.

5. Session 5 will attempt to summarize the workshop and planning a harvesting program, as well as discuss actions and next steps We would like to invite you to present in any of these sessions. For sessions I, 3, and 5, we are looking for brief 5-10 minute presentations, so j ust a few slides at most on motivation for harvesting, sources of materials, and any future harvesting plans. For sessions 2 and 4, the presentations are anticipated to be longer, perhaps 20-30 minutes, covering data needs best addressed through harvesting (session 2) and lessons learned from previous harvesting experience (session 4).

For logistics, the workshop will be held at NRC's headquarters, which is at the White Flint Metro station:

Three White Flint North 1160 I Landsdown Street North Bethesda, MD 20852 The nearest hotel is across the street:

http://www.marriott.com/hotels/travel/wasbn-bethesda-north-marriott-hotel-and-co nference-center/ . Please let me know if you need any other information regarding location or accommodations.

Please also let me know if you would be able to participate and which sessions you would be willing to s upport.

look forward to your participation and contributions to the workshop!

Regards, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, MIS T- 10 A36

11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax: 301-415-667 1

Original Message-----

From: Yasuhiro Chimi [17]

Sent: Tuesday, January 31, 2017 2:05 AM To: Tregoning, Robert <Robert.Trcgoning@nrc.gov>

Subject:

[Extemal_Sender] RE: Participation in Harvesting workshop from JAEA

Dear Mr. Robert Tregoning,

My name is Yasuhiro Chimi. I'm ai member of Nuclear Safety Research Center, Japan Atomic Energy Agency (JAEA), and in charge of IASCC study of stainless steels.

As Mr. Kazunobu Sakamoto told you, I would like to attend the harvesting workshop. Could you give me some more information on the workshop, such as registration, venue, accommodation, how to get there, etc.?

I'm looking forward to hearing from you.

Sincerely yours, Yasuhiro Chimi Yasuhiro Chimi, Ph.D.

Materials and Water Chemistry Research Group Materials and Structural Integrity Research Division Nuclear Safety Research Center Sector of Nuclear Safety Research and Emergency Preparedness Japan Atomic Energy Agency (JAEA)

Phone: +81-29-282-6473 , Fax: +8 1-29-282-5406 E-mail: chimi.yasuhiro@jaea.go.jp

Original Message-----

From: Tregoning, Robert [18]

Sent: Monday, January 23, 20 17 11 :0 I PM To: :lj:,js: - ft/ <kazunobu_sakamoto@nsr.go.jp>

Cc: chimi.yasuhiro@jaea.go.jp; Yutaka Nishiyama (nishiyama.yutaka93@jaea.go.jp)

<nishiyama.yutaka93@jaea.go.jp>; iLfift !];f- <kenichi_takakura0 l@nsr.go.jp>; FFI n ITfft <kiyotaka_taguchi@nsr.go.jp>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hiser, Matthew

<Matthew.Hiser@nrc.gov>

Subject:

RE: Participation in Harvesting workshop from JAEA Kazu:

It's always so good to hear from you. I look fo1ward to hearing from your colleague at JAEA about participation in the harvesting workshop. T also will be in touch with you shortly to coordinate and finalize the contributions from Japan so that we can finalize the agenda.

Warm regards, Rob Robert Tregoning 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: 30 1-415-2324 fax: 30 l -415-667 l From: :IN* -fi§ [mailto:kazunobu sakamoto@nsr.go.jp1 Sent: Thursday, January 19, 20 17 9: 19 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Cc: chimi.yasuhiro@jaea.go.jp; Yutaka Nishiyama (nishiyama.yutaka93@jaea.go.jp)

<nishiyama.yutaka93@jaea.go.jp>; ifli:Q- f'} - <kenichi_takakura0 l@nsr.go.jp>; I]

)1jjt <kiyotaka_taguchi@nsr.go.jp>

Subject:

[External_ Sender) Participation in Harvesting workshop from JAEA Hi Rob, A staff of our technical support organization JAEA wants to participate in the workshop and will contact you soon.

So I would appreciate if you could accept bis participation.

Thanks for your cooperation in advance.

Best regards, Kazu

Ex-Plant Materials Harvesting Workshop March 7-8, 2017 USNRC HQ Rockville, MD, USA

Meeting Logistics

Workshop will be held at NRC's Three White Flint North building Directly adjacent to the White Flint Metro station Nearest hotel within walking distance: Bethesda North Marriott Hotel &

Conference Center

Workshop is a non-public meeting to encourage open discussion

- Presentations and meeting summary will be distributed among meeting participants only

GoToMeeting webinar will be available to support additional attendees Webinar attendees will be primarily observers

Limited opportunities for webinar attendee participation in discussion if time allows Discussion will be recorded through GoToMeeting software to aid capturing discussion in meeting summary

Motivation

With plants shutting down both in the U.S. and internationally, there are increasing opportunities to harvest components from decommissioning plants

- Past harvesting efforts generally more reactive as opportunities arose, rather than proactively planned

Ex-plant materials may be valuable because they have been exposed to actual in-service plant operating conditions

- Can reduce the uncertainty associated with the applicability of the aging conditions

Insights from research on harvested materials can address technical data needs identified for extended plant operation

Lessons learned from past harvesting programs can help improve future harvesting efforts Challenges encountered in previous programs can be shared and mitigated or avoided in future programs

Approach

Domestic and international researchers, industry, regulators, and decommissioning companies' discuss benefits and challenges with ex-plant harvesting

- Encourage sharing of lessons learned as well as areas of common interest

Workshop consists of topical sessions with short presentations and significant time for open discussion

- Goal is to maximize engagement among meeting participants

Scope includes any materials aging issue that could benefit from harvesting, including metals, cables, and concrete

Expected Outcome

Participants become better informed and aware of the benefits and challenges associated with ex-plant harvesting

Discussions help identify areas of common interest for harvesting to address technical data needs

Presentations and discussions provide the starting point for a "database" of harvested materials and future harvesting opportunities

Contacts are made among research organizations to allow for further discussion of specific harvesting projects

Session Expectations

Session 1 Motivation for Harvesting Perspective from panel participants on their organizations' interest in and motivation for harvesting Brief (5-10 minute) presentation from each panel member followed by general discussion

Session 2 Technical Data Needs for Harvesting

- Presenters share high-priority data needs that may be best addressed by harvesting

Where does harvesting hold particular value compared to other sources of technical data 15-20 minute presentations followed by open discussion of technical data needs for harvesting

Session Expectations

Session 3 Sources of Materials Information on previously harvested materials and future harvesting opportunities

Materials located at research and vendor facilities

Decommissioning plants that may allow for future harvesting Short 5-10 minute presentations followed by open discussion Starting point for potential database of previously harvested materials and future harvesting opportunities

Session 4 Harvesting Experience: Lessons Learned and Practical Aspects Improving future efforts with lessons learned from past programs

Pitfalls to avoid and strategies to improve likelihood of success Practical perspective from non-researchers on how harvesting interfaces with the decommissioning process International decommissioning and harvesting experience 20-30 minute presentations followed by open discussion

Session Expectations

Session 5 Future Harvesting Program Planning

- Technical and logistical information needed when planning a specific harvesting program Perspective from panel participants on the workshop Next steps and actions from workshop Potential areas of common interest for future harvesting programs Brief (5-10 minute) presentation from each panel member followed by general discussion

From: Tregoning, Robert Sent: Mon, 19 Dec 2016 21:38:57 +0000 To: 'Dyle, Robin'

Subject:

RE: RE: RE: [External] Harvesting Workshop Okay, thanks. I thought that to be the case but just wanted to confirm before responding to Sherry so I'm sure that I'm on the same page with this moving forward . Have a good Holiday.

Rob From: Dyle, Robin [19]

Sent: Monday, December 19, 2016 4:37 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

[External_Sender] RE: RE: [External] Harvesting Workshop For the materials side of the house that is true. We will send someone (probably more than one). We may end up with someone with a lot of interest that requests t o engage more, but now it is just participate.

Robin Dyle EPRI Nuclear Sector Office: 205-426-5371 (b)(6) C:eU:._

j ......__ _ __,

From: Tregoning, Robert [20]

Sent: Monday, December 19, 2016 12:56 PM To: Dyle, Robin <rdyle@epri.com>

Subject:

FW: RE: [External] Harvesting Workshop Robin:

Just want to confirm that this is EPRl's position.

Rob From: Bernhoft, Sherry [21]

Sent: Monday, December 19, 2016 11:37 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; richard.reister@nuclear.energy.gov; Dyle, Robin

<rdyle@epri.com>

Subject:

[External_Sender] RE: [External] Harvesting Workshop Rob As I understand from Robin, the discussion last week with Kurt was that EPRl's position is we will send someone(s) to participate in the workshop, but we will not be acting in a leadership or coordinating role.

Sherry Bernhoft Electric Power Research Institute EPRI, Senior Program Manager 1300 West WT Harris Boulevard I Charlotte, NC 28262 704.595.2740 (office)

(b)(6) .. I . ! (cell)

Email: sbernhoft@epri.com www.epri.com Together...Shaping the Future of Electricity From: Tregoning, Robert fmailto:Robert.Tregoning@nrc.gov]

Sent: Thursday, December 15, 2016 2:54 PM To: Bernhoft, Sherry <sbernhoft@epri.com>; Reister, Richard < Richard.Reister@nuclear.energy.gov>

Cc: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Dyle, Robin <rdyle@epri.com>

Subject:

[External] Harvesting Workshop Sherry/Rich:

I wanted to thank you again for the discussion that we had last week on the harvesting workshop agenda. I think it was productive and I appreciate the perspective you both brought.

I've attached an announcement for the workshop that were planning to use to solicit participants. Also, we've revised the agenda substantially based on the feedback you both provided. I think it captures the issues you had and I personally think that this is a better model to follow for the workshop.

I'd like to ask you both for two things prior to leaving for the holidays.

1. Could you provide me with any additional changes to the workshop agenda that you recommend? Just mark-up and send back the attached agenda. I'll consolidate and address any remaining suggestions from you both.

2. Could you provide me with a POC for coordinating each of the 5 workshop sessions?

The idea is for the POCs to work together for planning each session. Here are the POCs from the NRC:

a. Session 1 - Rob Tregoning

b. Session 2 - Matt Hiser

c. Session 3 - Pat Purtscher

d. Session 4 - Matt Hiser

e. Session 5 - Rob Tregoning We're hoping to get the planning teams in place before Christmas so that we can hit the ground running in early January to line up all the speakers.

Thanks again for your help. If I don't talk to you beforehand, I hope both you and your families have a Happy Holidays and a Prosperous New Year.

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

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

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

From: Tregoning, Robert Sent: Mon, 9 Jan 2017 15:13:06 +0000 To: 'Dyle, Robin'

Subject:

RE: RE: RE: [External] RE: Final agenda for Harvesting workshop Great, thanks Robin. Have a good trip .. ..

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: Dyle, Robin [22]

Sent: Monday, January 09, 2017 10:12 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Bernhoft, Sherry <sbernhoft@epri.com>

Cc: Hiser, Matthew <Matthew.Hiser @nrc.gov>

Subject:

[External_Sender] RE: RE: [External] RE: Final agenda for Harvesting workshop Rob:

Headed to airport but a quick note. Al Ahluwalia and Jean Smith plan to attend as do I.

Robin Dyle EPRI Nuclear Sector Office: 205-426-5371 (b)(6) ('.:ell.; J . . . . ** *

I From: Tregoning, Robert [23]

Sent: Monday, January 9, 2017 7:14 AM To: Bernhoft, Sherry <sbernhoft@epri.com>

Cc: Dyle, Robin <rdyle@epri.com>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: RE: [External] RE: Final agenda for Harvesting workshop Sherry:

Since this is a closed meeting and we're inviting people to attend, we hadn't planned on having a pre-registration. I agree that it would be good, however, to put together a list of planned attendees to circulate in advance of the meeting. We'll make sure to do this.

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: Bernhoft, Sherry [mailto:sbernhoft@epri.com)

Sent: Monday, January 09, 2017 8:09 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Cc: Dyle, Robin <rdyle@epri.com>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

[External_Sender) RE: [External] RE: Final agenda for Harvesting workshop Sounds good and thanks Will there be some type of pre- registration? Not a necessary but I am curious who all may be attending. I talked with some folks at Westinghouse (on concrete aging) right before the holiday break and mentioned this upcoming workshop. I am not sure if they contacted you since they are interested.

Sherry Bernhoft Electric Power Research Institute EPRI, Senior Program Manager 1300 West WT Harris Boulevard I Charlotte, NC 28262 704.595.2740 (office)

(b)(6) J .. - !(cell)

Email: sbernhoft@epri.com www.epri.com Together...Shaping the Future of Electricity From: Tregoning, Robert [mailto:Robert.Tregoning@nrc.gov)

Sent: Monday, January 09, 2017 6:00 AM To: Bernhoft, Sherry <sbernhoft@epri.com>

Cc: Dyle, Robin <rdyle@epri.com>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

[External) RE: Final agenda for Harvest ing workshop Sherry:

The announcement and agenda that I sent you previously are the latest ones. I've attached both again FYI. The announcement won't change further. The final agenda is still evolving.

We won't have a final agenda until we identify all the speakers and titles of talks. I'm shooting for the end of January to pin down most of these details.

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: Bernhoft, Sherry (mailto:sbernhoft@epri.com)

Sent: Sunday, January 08, 2017 9:55 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Cc: Dyle, Robin <rdyle@epri.com>

Subject:

[Ext ernal_Sender) Final agenda for Harvest ing workshop Rob Hope you are off to a good start for the New Year Do you have the final announcement and agenda for the Harvesting Workshop?

Sherry Bernhoft Electric Power Research Institute EPRI, Senior Program Manager 1300 West WT Harris Boulevard I Charlotte, NC 28262 704.595.2740 (office)

(b)(6) L. H cell)

Email: sbernhoft@epri.com www.epri.com Together... Shaping the Future of Electricity

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

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

From: Purtscher, Patrick Sent: Tue, 26 Jun 2018 18:42:26 +0000 To: 'Ramuh alli, Pradeep'

Subject:

RE: RE: RE: status on report If you could just give me a quick call after your last meeting. 5 minutes is all this should take and anymore can be done on Monday.

PAT (b)(6) ,J,._...""'"

From: Ramuhalli, Pradeep [24]

Sent: Tuesday, June 26, 2018 2:39 PM To: Purtscher, Patrick <Patrick.1Purtscher@nrc.gov>

Subject:

[External_Sender] RE: RE: status on report Pat, I have a couple of other conference calls this afternoon that start in a few minutes and are likely going to go through about 4 pm here. Any chance you are available Monday next week to talk I .. . l {b)(6)

(b)(6) .... I. ..* * * * * * * * ******** *

U?Say around 8.30 am here {11.30 ET)? ** * *******

With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email: pradeep.ramuhalli@pnnl.gov From: Purtscher, Patrick [25]

Sent: Tuesday, June 26, 2018 9:50 AM To: Ramuhalli, Pradeep <Pradeep.Ramuhalli@pnnl.gov>

Subject:

RE: RE: status on repo1rt Sorry, I forgot about the call. You can call me anytime today on my cell._!___._.. _.... _ I

......_.......... (b )(6)_.

Pat From: Ramuhalli, Pradeep [26]

Sent: Tuesday, June 26, 2018 11:33 AM To: Purtscher, Patrick <Patrick.1Purtscher@nrc.gov>

Subject:

[External_Sender] RE: status on report Pat,

Were you going to call me? Or are you at work - I can call you .

With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email: pradeep.ramuhalli@pnnl.gov

Original Appointment-----

From: Purtscher, Patrick fmailto:Patrick.Purtscher@nrc.gov]

Sent: Monday, June 25, 2018 6:29 AM To: Purtscher, Patrick; Ramuhalli, Pradeep

Subject:

status on report When: Tuesday, June 26, 2018 11:30 AM-12 :00 PM (UTC-05 :00) Eastern Time (US & Canada) .

Where: home

From: Purtscher, Patrick Sent: Tue, 21 Feb 2017 19:17:56 +0000 To: Ramuhalli, Pradeep Cc: Hiser, Matthew

Subject:

RE: RE: Slides 3 PM will work for both Matt (work@ home) and me (in office). Send use the phone#.

Pat From: Ramuhalli, Pradeep [27]

Sent: Tuesday, February 21, 2017 12:18 PM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>

Cc: Hiser, Matthew <Matthew.Hiser @nrc.gov>

Subject:

[External_Sender] RE: Slides That works. Say about 2 or 3 pm in the afternoon (EST) tomorrow? I can send out the phone li ne info if you prefer. Slides should be out before then.

Thanks.

With best regards, Pradeep Ramuhalli, PhD Tel: 509-375-2763 Email: pradeep.ramuhalli@pnnl.gov From: Purtscher, Patrick [28]

Sent: Tuesday, February 21, 2017 9:01 AM To: Ramuhalli, Pradeep <Pradeep.Ramuhalli@pnnl.gov>

Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: Slides Good morning, We could talk tomorrow in the afternoon (EST) if you can get the slides out to us before that. Let me know and I will get a phone line for a conference call.

Pat From: Ramuhalli, Pradeep [29]

Sent: Tuesday, Februa ry 21, 2017 11:37 AM To: Purtscher, Patrick <Patrick.1Purtscher@nrc.gov>

Cc: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

[External_Sender] Slides

Patrick, Are you available later this week (tomorrow through Friday) sometime? I am wrapping up the slide updates for the workshop and would like to go over those with you when you get a chance . Updates should be going out tomorrow to you .

With best regards, Pradeep Pradeep Ramuhal li, PhD Senior Research Scientist, Applied Physics Group Pacific Northwest National Laboratory 902 Battelle Blvd .

P.O.Box 999, MSIN KS-26 Richland, WA 99352 Tel : 509-375-2763 Email : pradeep.ramuhalli@pnnl.gov http://www.pnnl.gov

From: Hiser, Matthew Sent: Thu, 18 May 2017 08:46:20 -0400 To: Moyer, Carol;Purtscher, Patrick

Subject:

RE: Request: Need a couple of bullets on Harvesting workshop Hi Carol, Here's our input for the harvesting workshop (Pat, feel free to chime in with any other tweaks):

Workshop well-attended by DOE, EPRI, NRC, US industry, and international participants.

Participants discussed the motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting and future harvesting program planning.

o Workshop discussion emphasized the need for a clearly defined objective to justify the level of effort and demonstrate value.

o Past harvesting experience shows valuable technical information can be gained, but harvesting efforts are expensive and complex.

Workshop summary report will be shared among meeting participants. Future activities from the workshop include cooperative discussion of prioritized data needs for harvesting and potential development of a sources of materials database.

Please let us know if you need any other input or assistance © 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 I 0D62 Matthew.Hiser@ nrc.gov From: Moyer, Carol Sent: Thursday, May 18, 2017 8:15 AM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

Request: Need a couplle of bullets on Harvesting workshop Hi Matt and Pat, In preparation for a management meeting at EPRI, Brian Thomas needs some talking points on DE programs. I have copied out the parts of the agenda that pertain to DE, in the attached outline file.

Can you please provide some high-level bullets (3-4?) on the Harvesting workshop from March, and any plans for follow-on work? I would appreciate your response by around noon today (Thurs), if possible.

Thank you ,

Carol Carol Moyer Sr. Materials Engineer RESIDE/CMB carol.moyer@nrc.gov 301-415-2153

From: Tregoning, Robert Sent: Tue, 12 May 2015 11:45:16 +0000 To: Bernhoft, Sherry

Subject:

RE: response to IAEA CRP Thanks, Sherry. I need to draft a response and will use similar language about support for harvested materials. Our stance will still be that we are potentially interested but need more project details before determining if we will commit to the CRP.

Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 21 Church Street, M/S CS-5A24 Rockville, MD 20850 ph: 301-251-7662 BI ackbe rry p"'

""x6,..

l -------,

fax: 301-251-7425 From: Bernhoft, Sherry [30]

Sent: Tuesday, May 12, 2015 7:22 AM To: richard.reister@nuclear.energy.gov; Tregoning, Robert; busbyjt@ornl.gov

Subject:

response to IAEA CRP We are still reviewing our response internally but I can share with you what we are considering for our response:

Alex, Thank you for the providing the information regarding the Harvested Materials CRP proposed future steps. EPRI fully supports the need for harvested materials as a valuable contribution to studying and understanding the technical basis for safe, long term operations of the existing NPPs. To demonstrate this Dr. Jean Smith of EPRI is leading an international team which has successfully harvested and is the process of testing reactor vessel internals materials from the Zorita plant in Spain. The lessons learned from this harvesting and the test matrix development have been openly shared with the international community at the previous CRP meetings. EPRI is also working very closely with Hamaoka on a number of projects to facilitate their decommissioning work.

EPRI plans to participate on this CRP. Our contribution will be to work directly with Chubu (Hamaoka) on the WG-1 activities through continued decommissioning project support, and providing technical support on lessons learned for harvesting, test matrix development, etc.

I look forward learning the results of the IAEA request to proceed with the CRP.

Please let me know if you have any addition questions,

Our staff in Japan has been talking with Chubu, they understand we will support them but we are fully committed to Zorita and we will not be providing any additional$$$ to support harvesting and testing materials from Hamaoka . Your call but you may want to provide a similar response that you are supportive of harvested materials for LTO, and are doing your part to support the state of knowledge with the Zion work (LWRS) or support of the Zorita work (NRC).

Take care, Sherry Bernhoft Electric Power Research Institute EPRI , Program Manager 1300 West WT Harris Boulevard I Charlotte, NC 28262 704.595.27 40 (office)

(b)(6) I ..

Hcell)

Email: sbernhoft@epri.com www.epri .com Together... Shaping the Future of Electricity

From: Hiser, Matthew Sent: Fri, 30 Sep 2016 11:45:54 -0400 To: Iyengar, Raj;Frankl, Istvan Cc: Hull, Amy;Purtscher, Patrick

Subject:

RE: Revised estimates and UNR Yep, I agree!

From: Iyengar, Raj Sent: Friday, September 30, 2016 11:44 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

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

Subject:

RE: Revised est imates and UNR

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

Matt, Agree?

Raj From: Frankl, Istvan Sent: Friday, Sept ember 30, 2016 11:35 AM To: Iyengar, Raj <Raj.lyengar@nrc.gov>

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

Subject:

RE: Revised est imates and UNR Thanks, Raj.

Did you align with Matt H. on the harvesting scope as well as related FTEs and contract funds?

I have no additional technical comments on the draft UNR (It will need to go to QTE but that will be done at NRR.)

If Matt H. is OK with the FTEs and $s for the ex-plant harvesting task, I am OK with the rest.

Thanks, Steve From: Iyengar, Raj Sent: Thursday, September 29, 2016 2:05 PM

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

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

Subject:

FW: Revised estimates and UNR

Steve, You may review the resource estimates. Amy mentioned that DLR did not want to see the TID task in the new UNR.

I have also made a minor change in the deliverables for Task 1.

Raj From: Hull, Amy Sent: Thursday, September 29, 2016 1:47 PM To: Iyengar, Raj <Raj.lyengar@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Revised est imates and UNR Yes, as far as I am concerned.

From: Iyengar, Raj Sent: Thursday, September 29, 2016 1:20 PM To: Hull, Amy <Amy.Hull@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Revised est imates and UNR Thanks, Amy. Then , can I send a note to Steve Frankl that he can review the latest estimate (and the minor revision ot the UNR Task 1 deliverable) I sent you all on Monday?

From: Hull, Amy Sent: Wednesday, September 28, 2016 3:56 PM To: Iyengar, Raj <Raj.lyengar@nrc.gov>

Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Revised estimates and UNR As mentioned, I hit wall yesterday.

From: Iyengar, Raj Sent: Wednesday, September 28, 2016 2:48 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

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

Thanks so much.

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

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

Subject:

Revised estimates and UNR Amy/Rob, I have added the development of the summary reports to the deliverable for Task 1 (brief addition). I have also revised the resource estimates by rolling the FTE for summary documents with the resources needs for Task 1.

If you folks decide to add the new task on TID , please do so in the attached revised UNR.

After you make any changes, we can send to those who attended this AM meeting for comment or awareness. I will leave that to Steve .

Raj

From: Purtscher, Patrick Sent: Wed, 3 May 2017 11:55:52 +0000 To: Ramuhalli, Pradeep Cc: Hiser, Matthew

Subject:

RE: Status of TLR Thanks for the update.

Pat From: Ramuhalli, Pradeep [31]

Sent: Tuesday, May 02, 2017 11:45 AM To: Purtscher, Patrick <Patrick.lPurtscher@nrc.gov>

Cc: Hiser, Matthew <Matthew. Hiser @nrc.gov>

Subject:

[External_Sender] Status of TLR

Patrick, I wanted to give you an update on the TLR. While mostly complete, it has been edited by our tech editor and she flagged a few things for me to tackle. I am working on that; once complete in the next couple of days it will be re-checked by the tech editor and I can then send it out to you for formal review.

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

From: Tregoning, Robert Sent: Tue, 23 May 2017 20:41:25 +0000 To: Moyer, Carol;Hiser, Matthew Cc: Hull, Amy

Subject:

RE: Synopsis on Harvesting for IAEA PLiM Carol:

What you submitted was fine. If the PLiM organizers have an issue with it, they can get back to us and request a longer abstract.

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: Moyer, Carol Sent: Tuesday, May 23, 2017 4:19 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Cc: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

RE: Synopsis on Harvesting for IAEA PUM Well. .. that's true. I did see that text in the announcement. I was working, however, from examples that were PLiM papers that Amy and louri co-authored in previous conferences. Their abstracts were of the conventional length.

Rob & Amy - What do you think? Do I need to expand on my abstract for PLiM? I have already sent it to Robert Krivanek who said he would submit it for me, but I don't suppose he was commenting yet on the content of the attachment.

Carol From: Hiser, Matthew Sent: Tuesday, May 23, 2017 4:15 PM To: Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: Synopsis on Harvesting for IAEA PUM Hi Carol,

I would have been happy to do only a 1 paragraph abstract © , but the conference guidance talked about a "two page synopsis" (http://www-pu b. iaea .org/MTCD/Meetings/PDF pl us/2017/cn246/cn246An nou nceme nt.pdf):

F. Synopses, Papers and Proceedings Concise papers on issues fall ing within the topics outlined in Section C may be submitted as contributions to the conference. All papers, apart from invited papers, must present original work and they should not have been published elsewhere.

(a) ubmissioo of Extended yoopst.

yone wishing to resent a ~ r or _poster durin this conference must submit a two age syno_es1s in electronic format (no paper copies), directly to the IAEA. Instructions on how to upload the synopsis to the conference' s web browser-based file submi ssion system (IAEA INDICO) wi ll be available on the IAEA web page for the conference (see Secuon 0). The synopses must be submitted M. Key Dates and Deadlines Submission of Fonn for Submission of a Paper (form B) and extended synopsis (800 words) 30 pril 2017 Thanks for the heads-up on your schedule this week. I'll try to get this signed off by Steve by tomorrow and ready to submit by Thursday.

Thanks!

Matt From: Moyer, Carol Sent: Tuesday, M ay 23, 2017 3:52 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

RE: Synopsis on Harvest ing for IAEA PLiM Matt, This is a nice 2-page summary, but it is a bit long for an abstract. Are you planning to write a 1-paragraph version for the PLiM abstract?

By the way, I changed my plans to accommodate the materials meeting schedule this week and (b)(6) ~c:ir,:,~qthermeetings.f . . !and in on Thursday.

Thanks,

Carol From: Frankl, Istvan Sent: Tuesday, May 23, 2017 3:48 PM To: Hiser, Matthew <Matthew. Hiser@nrc.gov>

Cc: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick

<Patrick.Purtscher@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: Synopsis on Harvesting for IAEA PLiM Importance: High

Matt, Thanks for your efforts and initiative.

I have a few corrections and comments in the attachment.

Did your attachment implement Amy's markups/ comments?

In any case, please also send me the final draft for review.

Thanks, Steve From: Hiser, Matthew Sent: Monday, May 22, 2017 2:47 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick

<Patrick.Purtscher@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

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

Subject:

Synopsis on Harvesting for IAEA PLiM I have attached a draft 2 page synopsis on harvesting for the IAEA PLiM conference. T he plan will be for Carol to give the 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 support submission this week.

Thanks!

Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov

From: Tregoning, Robert Sent: Thu, 4 Jun 2015 20:40:14 +0000 To: Hull, Amy

Subject:

Re: Takeaway and Followup from yesterday afternoon strategic harvesting presentation Mike Mcdevitt was 2nd commenter and Tim Wells (I think) was 3rd commenter.

Sent from an NRC Blackberry Robert Tregoning (b)(6) L !

From: Hull, Amy Sent: Thursday, June 04, 2015 08:26 AM To: Hiser, Matthew; Tregoning, Robert Cc: Frankl, Istvan

Subject:

Takeaway and Followup from yesterday afternoon strategic harvesting presentation Hi Matt and Rob, Matt you did a great job speaking ! Wonderful talent for NRC !

Industry seemed to be encouraging with what we are trying to do in our new project.

I got 3 takeaways but only remember the name of one of the commenters. Please add any more insights.

Glenn Gardner (PWROG internals core planning team chair) said that PW ROG could support what we are trying to do with strategic approach for obtaining material and component aging information.

Some older gentleman (??) said that we should go and interview people before decommissioning because information is in their heads.

Another older gentleman (??) said that maybe we should have some kind of portable testing station that can go between decommissioned NPPs because transportation of samples is not so simple.

Robin Dyle said to industry comments that collaboration should be done through the MOU with EPRI because that is what it is for. Maybe we can follow up at ORNL on July 8-9? Robin will be there then.

From: Tregoning, Robert Sent: Mon, 14 May 2018 19:53:21 +0000 To: Frankl, Istvan

Subject:

RE: UPDATE for ACTION : Propose topics for Annual NRC/EPRI MOU review meeting Thanks, I'll be back in touch ....

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: Frankl, Istvan Sent: Monday, M ay 14, 2018 3 :51 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>

Subject:

FW: UPDATE for ACTION : Propose topics for Annual NRC/EPRI MOU review meeting Importance: High

Rob, This is the latest communication I have on this topic.

Thanks, Steve From: Oberson, Greg Sent: Friday, May 11, 2018 4:52 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>

Cc: Hiser, Matthew <M atthew.Hiser@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

RE: UPDATE for ACTION: Propose topics for Annual NRC/EPRI MOU review meeting I provided this to management.

From: Frankl, Istvan Sent: Friday, May 11, 2018 3:27 PM To: Oberson, Greg <Greg.Oberson@nrc.gov>

Cc: Hiser, Matthew <M atthew. Hiser@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>

Subject:

UPDATE for ACTION : Propose topics for Annual NRC/EPRI MOU review meeting Importance: High

Greg, We have one more topic and draft talking points supporting subject management meeting. Please submit them to DE management for consideration ASAP.

1. Ex-Plant Materials Harvesting

a. NRC and EPRI lhave cooperated effectively on several materials harvesting programs, including the reactor internals from Zorita. NRC hosted an ex-plant materials harvesting workshop in March 2017 that was attended by EPRI, DOE and international parties, which provided valuable insights and feedback on best practices and lessons learned from past harvesting efforts.

b. NRC is prioritizing data needs for harvesting and collecting information on available sources of materials (including operating and decommissioning plants as well as previously harvested materials) to ensure the best value for research on harvested materials.

c. NRC is interested in engaging with EPRI on their priorities for harvesting and how to achieve the best value in pursuing harvesting opportunities, including leveraging and cooperation.

d. If EPRI and NRC management are aligned, informal coordination and dialogue will be pursued that could be formalized through MOU addenda or cooperative agreements for any specific research activities that result.

2. Test Reactors and Irradiated Materials Testing (New topic in response to the evolving status of the Halden Reactor)

a. NRC is performing a strategic review of options for test reactor irradiation and irradiat ed materials testing capabilities, particularly in light of the potential shutdown of the Halden Reactor.

b. NRC and EPRI cooperation on the Zorita materials research has been effective for leveraging resource-intensive testing of highly irradiated reactor internals materials.

c. NRC is interested in further opportunities for leveraging and cooperation with EPRI for test reactor irradiation and irradiated materials testing capabilities, particularly if currently planned efforts at Halden are not able to be completed.

d. If EPRI and NRC management are aligned, informal coordination and dialogue will be pursued that could be formalized through MOU addenda or cooperative agreements for any specific research activities that result.

Thanks, Steve

From: Purtscher, Patrick Sent: Mon, 24 Jul 2017 14:00:38 +0000 To: Ramuhalli, Pradeep Cc: Hiser, Matthew

Subject:

RE: You have files ready for pickup Yes, 1 have it now.

Thanks Pat

Original Message-----

From: Ramuhalli, Pradeep [32]

Sent: Sunday, July 23, 2017 8:09 PM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>

Subject:

[Extemal_Sender] You have files ready for pickup

Hello, Ramuhalli, Pradcep (Pradeep.Ramuhalli@pnnl.gov) has sent you the following I file(s:)

Subject:

TLR Comments: Patrick, Looks like the earlier emails have not made it. I am re-sending via FTP. Let me know if you get this.

Pradeep The following files have been uploaded to the MassTransit Web File Transfer Services. You can download them by going to:

(b )( 4) and selecting the fi le(s) and clicking Download (All/Selected).

NOTE: This link and contained passkey are only good for 14 days.

Harvesting TLR DRAFT.docx (5.07M bytes)

This message was automatically generated from the PNNL FX Web File Transfer Service. If you have questions about its validity, please contact the sender listed above.

Note to requester: Attachment is immediately following.

From: Moyer, Carol Sent: Mon, 16 Oct 2017 22:50:34 +0000 To: Kirk, Mark;Sircar, M adhumita;Philip, Jacob;Pires, Jose;Murdock, Darrell;Miller, Kenneth A Cc: Hull, Amy;Frankl, Istvan

Subject:

Request : Quick Review of PLiM Paper Attachments: Plim Moyer ABH 246-143 Rl.docx Ladies & Gentlemen, I have a very short turn-around request for review of the attached paper for the upcoming IAEA Plant Life Management (PLiM) conference.

Amy Hull used your input on SLR-related research, along with 1-pagers and NUREG-1925 articles, to draft our paper to the PLiM conference. Rob Tregoning and I reviewed & revised the paper, and the result is the attached file.

Unfortunately, for several reasons (some of them, pretty good ones .. . ), we are backed up against the submission deadline for getting the paper sent to the conference organizers. Of course the final paper will have to be approved by our Div. management first. As a result, I need you to review the couple of paragraphs that relate to your research, and get back to me tomorrow (Tues., Oct. 17th ), the sooner the better. Again, I do apologize for the short turn-around, but I do not expect this to be a very long assignment.

Please contact me with any questions or comments, as soon as possible. Thanks again for your contributions!

-Carol Carol Moyer Sr. Materials Engineer RESIDE/CMB caro/.moyer@nrc.gov 301-415-2153

MOYER et a l.

REGULATORY RESEARCH ON THE AGING MANAGEMENT OF SLRSTRUCTURES, SYSTEMS AND COMPONENTS IN NUCLEAR POWER PLANTS SUPPORTING LICENSE RENEW AL C.E.MOYER U.S. Nuclear Regulatory Commission Washington, DC, USA Email : Carol.Moycr@nrc.gov A.B. HULL, M. SIRCAR, J. PHILIP, J. E. PIRES, D. D. MURDOCK, T. KOSHY U.S. Nuclear Regulatory Commission Washington, DC, USA A bstract The U.S. Nuclear Regulatory Commission (NRC) issues licenses for commercial power reactors to operate for up to 40 years. These licenses may be renewed for multiple 20-year increments. Now that 48 units of the 99 operating commercial reactors in the U.S. have entered the operating period beyond 40 years, their first period of extended operation (PEO) to operate for up to 60 years, several licensees have indicated that they intend to apply within the next few years for subsequent license renewal (SLR) for an additional 20-year period. Based on existing knowledge, the NRC has created a new set of license renewal guidance documents (LRGDs) for the review of SLR applications and to communicate expectations for the aging management of passive, long-lived plant systems, structures, and components (SSCs). I lowever, in order to ensure the continued adequacy of this guidance, research related to aging ofSSCs is being conducted now and will continue beyond the receipt of the initial SLR applications. Research is ongoing in the fo llowing four areas: reactor pressure vessel (RPV) neutron embrittlement, irradiation assisted stress corrosion cracking (IASCC) of reactor vessel internals, concrete and containment degradation, and electrical cable qualification and condition assessment. The paper will focus on the research related to concrete degradation, including alkali-silica reaction and irradiation damage to concrete, and condition assessment of electrical cables.

I. fNTRODUCTlON The U.S. commercial nuclear power industry intends to submit subsequent license renewal applications (SLRAs), which will allow nuclear power plant (NPP) operation up to 80 years, in accordance with IO C FR Part 54.3 1(d) UJ that "a renewed license may be subsequently renewed." However, an SLR applicant needs to address aging effects on passive long-lived systems, structures, and components (SSCs) within their SLRA.

Some licensees are considering submitting applications for a subsequent 20-year (presumably) operating period beyond 60 years. The first of these applications could possibly be submitted as early as 2018.

To ensure readiness for review o f possible applications for SLR, the NRC has just completed the development and publishing of new guidance documents, NUREG-2 19 1 and NUREG-2192, 2, 3 for the technical review of S LRAs. An important part of this guidance document development was reviewing N PP operating experience, including worldwide experience with NPP extended operation. The technical bases for SLR guidance are derived from operating experience and from indus try and independent confomatory research.

Aging management programs (A MPs) are developed to anticipate material degradation and to help ensure adequate functionality and safety margins in SSCs. Key technical issues to be addressed in A MPs within subsequent license renewal guidance documents (SLRGDs) include reactor pressure vessel neutron embrittlement at high fluence; irradiation-assisted s tress corrosion cracking of reactor internals and primary system com onents; concrete and containment degradation, and electrical cable qualification and condition assessment. 4 The paper describes the status of this ongoing research, and focuses on the areas of concrete and electrical cable aging management.

2. RESEARCH & SLR GUIDANCE DOCUMENTS

lAEA-CN-246-143 Tbe NRC and industry have conducted extensive research over the past several decades to better understand the safety implications and risk associated w ith aging of SSCs. Recent presentations 5 6] reviewed the history of NPP license renewal in the U.S and the evolution of the license renewal documents, NUREG-1800 and NUREG-1801 7, 8 J for the initial period of renewal. Being able to extrapolate any observed aging effects from the existing operating experience of less than 50 years for the oldest plant to postulated aging effects at 80 years' operating experience is nontrivial and required much confimrntory research, both of existing studies and AIM P effectiveness audits at plants already in extended operation.

Prior to writing the SLRGDs, extensive research efforts were conducted to understand the strengths and shortcomings of the existing guidance documents for the initial period of renewal and to try to identify the

' unknown unknowns' [9,]. The 20 IO LRGDs were informed by NUREG/CR-6923, [ I QJ the proactive material degradation assessment (PMDA). The PMDA program used expert elicitation to identify and assess various materials degradation mechanisms that could affect plant SSCs for operation up to 40 years. Degradation scenarios were ranked according to the probability of occurrence, level of knowledge concerning that process, and confidence in scores. The expanded material degradation assessment (EMDA, NUREG/C R-7 153) I I]

evaluated a broader range of SSCs, up to 80 years. The materials and systems addressed in EMDA are generally extended to all of those which fall within the scope of aging management review (AMR) for license renewal.

Thus, in addition to piping and core internals, EMDA also includes the reactor pressure vessel (RPV), electrical cables, and concrete s tructures NRC staff recently published the 1400 pg. compendium I of AMP Effectiveness Audits undertaken to provide a more complete understanding of how AMPs have been implemented by plants during the PEO and the degradation that has been identified by the AMPs. The results from these first-of-a-kind audits provided key information to aid the NRC in identifying needed changes to existing AMPs and new AMPs that may be needed to provide assurance of safe plant operation during an SLR operating period. The knowledge obtained from these audits was a primary source enabling the staff to develop new SLRGDs, to be used following the fi rst PEO.

2. 1 GA LL-SLR Report (NUR.EG-2 19 1)

The two-volume 1190 pg. GALL-SLR Report contains the NRC stafrs generic evaluation of plant AMPs and establishes the technical bases for their adequacy. The guidance in this document is for the use of future applicants for SLR and encompasses all of the guidance applicable to initial license renewal.

T he GALL-SLR Report identifies those material, environment and aging effect combinations that require aging management during the subsequent period of extended operation (PEO), including appropriate AMPs.

Applicants are responsible for identifying in their applications any additional items that require aging management. Although the GALL-SLR Report identifies one acceptable approach to manage aging effects, applicants may propose plant-specific alternatives along with sufficient justification that the program will adequately manage the aging effects.

2.2 SRP-SLR (NUR.EG-2192)

The 509 pg. Standard Review Plan for Review of Subsequent License Renewal (SRP-SLR) provides guidance on tbe content of applications for renewal of the initial renewed operating license. The safety review is based primarily on the information provided by the applicant in a SLR application. Each of the individual SRP-SLR sections addresses: (i) who performs the review, (ii) areas of review, (iii) basis for review, (iv) method of review, and (v) conclusions from the review.

While the GALL-SLR Report is geared towards use by applicants to identify acceptable aging management approaches, the SRP-SLR provides guidance to the staff for its review of SLR applications. The SRP-SLR ensures a consistent and transparent review of SLR applications by documenting the acceptance criteria and review procedures that will be used by the staff in its reviews.

3. REGULATORY RESEARCH

MOYER et a l.

The United States' regulations governing the operation ofNPPs, Title 10 of the U.S. Code of Federal Regulations, [I] require that licensees demonstrate safety in design and operation ofNPPs. Specifically, 10 CFR 54.29(a) requires that licensees manage aging effects so that their intended functions will be maintained consistent with the current licensing basis (CLB) for the PEO. In its mission to ensure protection of the public health and safety, the NRC conducts confirmatory research to better understand and quantify various degradation mechanisms that may impact NPP SSCs. This research enables regulatory confidence regarding aging management of safety-related SSCs. Results from these ongoing research programs reduce uncertainty regarding license renewal and SLR, and help the regulator to maintain appropriate levels of conservatism in NRC regulations and guidance.

Key technical issues to be addressed for LTO [cl)) include RPV neutron embrittlement at high tluence; lASCC of reactor internals and primary system components; concrete and containment degradation, and electrical cable qualification and condition assessment. The paper describes the status of this ongoing research, particularly in the areas of concrete and electrical cable aging management.

4. RESEARCH ON DEGRADATION IN METAL COMPONENTS 4.1 RPV embrittlement The safe operation of an NPP relies on maintaining the structural integrity of the RPV during routine operations and postulated accident scenarios. Two key capabilities underpin RPY structural integrity: (I) the ability to predict the behaviour of cracked structures under loading, and (2) the ability to predict the effects of irradiation embrittlement on the fracture toughness of RPV steels. Current regulatory procedures depend on empirically based engineering methods that, whi le generally acknowledged to incorporate large conservatisms, have not necessarily been validated for SLR conditions. Ongoing research is aimed at understanding the adequacy of existing approaches and developing new models and predictive procedures as needed. Issues such as late blooming phases (LBPs), attenuation, and flux effects are being evaluated. Work is also underway to evaluate the continued adequacy of associated regulatory guidance during SLR [ 13].

4.2 IAD of Reactor Internals Limited data are available on irradiation effects at fluence levels consistent with S LR for properties such as void swelling and resistance to cracking for reactor internals materials. Preliminary data suggest that the significance of irradiation-assisted degradation (lAD) of LWR vessel internals could increase during long-tern1 operation of NPPs. Particularly, there is interest in understanding the behavior of irradiated stainless steel (SS) weld materials (up to 8 dpa), higher fl uence (> I O dpa) SS plate materials, and combined thermal and neutron embrittlement of cast austenitic stainless steel (CASS).

Ongoing research concerning IAD of RPV internals is focused on assessing the significance o f void swelling on the structural and functional i11tegrity of PWR internal components. Research is being conducted on harvested ex-plant materials. Work is underway to measure fracture toughness and lASCC for stainless steels &

welds. Effects of environment and irradiation may be additive or synergistic; further testing will confirm the combined nature of these effects.

5. RESEARCH ON CONCRETE AND CONTAINMENT DEG RADATON 5.1 ASR Alkali-Silica Reaction (ASR) is a chemical degradation in concrete that may occur over time as a reaction between the highly alkaline cement paste and reactive non-crystalline (amorphous) silica found in many common aggregates. This reaction causes the expansion of the altered aggregate by the formation of a swelling gel of calcium silicate hydrate (C-S-H). The objective of the research program is to develop the technical basis for generic regulatory guidance to evaluate ASR affected NPP concrete structures through its service life, including SLR). The intended outcome of the research is a methodology to determine for an ASR-affected structure (l) the in-situ structural capacity to resist design-basis static and dynamic loads, (2) its future structural 3

lAEA-CN-246-143 capacity, and (3) a recommended AMP consistent with the guidance in SRP-SLR for managing the aging effects of ASR in existing structures.

The NRC sponsors experimental research at the National Institute of Standards and Technology (NIST) that involves a combination of testing and modelling to study ASR effects on nuclear concrete structures. This program involves assessing in-situ mechanical properties of ASR-affected concrete, bond and lap splice lengths of reinforcing bars, and the seismic response characteristics of structural members. The NRC is participating in an international cooperative research program to assess structures subjected to concrete pathologies, under the Nuclear Eneq;,,y Agency. Tn addition, the NRC is involved in a collaborative program with the technical support organizations for the French regulator.

5.2 Radiation induced degradation of concrete Irradiated concrete can undergo degradation similar to ASR; swelling aggregate cracks the cement phase.

The primary objective of this research is to review, evaluate, and enhance the capability to perfom1 confirmatory analyses and testing of the effects of irradiation of concrete on the integrity of structures in the proximity of the RPV over extended periods of operation. The goal is to provide a technical basis to review plant conditions under A MPs. Over extended periods of operation, concrete structures in the proximity of the RPV, the primary and biological shield walls and the RPV support structures for example, can be subjected to high levels of neutron and gamma radiation together with sustained operating temperatures up to about 150° F. Long-tem1 neutron and gamma irradiation on concrete of the reactor supports and shielding structures can affect dimensions (radiation induced volumetric expansion), micro-cracking of the cement paste, and physical and structural properties of concrete (e.g., reduction of compressive strength, tensile strength, modulus of elasticity, bond s trength) that may affect structural performance and shielding capacity. Confirmatory testing depends on availability of suitable cores, possibly from decommissioning US plants. This research assesses the structural and safety significance of concrete irradiation for LTO.

A joint roadmap is being developed by NRC, The US Department of Energy (DOE), and the Electric Power Research Institute (EPR.1). While EPR.I and DOE have jointly publ is hed a report on estimated radiation levels for operation up to 80 years, and EPR.1 has started developing structural assessments, NRC is pursuing coordination with the Halden Research Program for investigating effects of radiation on bond strength. NRC is performing fluence modeling to assess configuration effects. NRC is also developing test plans to study radiation effects on bond strength and creep, and assessing plant configurations and designs to detennine the plant conditions that would indicate a need for aging management.

5.3 Aging management of prestressed concrete containment structures The objective of this project is to study the effects of aging and modifications of prestressed concrete containment vessels (PCCVs) on their intended safety functions. NUR EG/CR-7153 Vol 4, "Aging of Concrete and Civil Structures," [ 110 identified creep and the potential for creep-related fracture as an aging concern applicable to PCCVs because of the sustained, multi-axial loading from the prestressing. This is relevant for aged PCCVs where reinforcement in the radial direction is not present, and when prestressing systems require adjustments, such as modifications for steam generator replacement, other repairs, and loss of prestress. As with other concrete aging mechanisms, creep and the potential for creep-fracture also may interact with other degradation mechanisms, such as ASR, corrosion, and freeze-thaw.

EPR.1, DOE and international organizations, such as the Committee for the Safety of Nuclear Installations of the Organization for Economic Development and Cooperation (OECD/CSNI) are cooperating to address shrinkage, creep, drying, and moisture transport. Specifically, this activity focuses on benchmarking aspects of VERCORS, a comprehensive multiyear study of a 1/3 scale PCCV that focuses on aging effects, computational modelling and use of non-destructive evaluation techniques (NDE) and sensors for structural monitoring.

Electricite de France (EDF), which started, funds and executes VERCORS, is making information and data from this study available to the OECD/CSNI activity.

6. ELECTR.ICAL CABLE QUALIFICATION AND CONDITION MONITOR.ING

MOYER et a l.

Electrical cables are often overlooked or ignored in aging analyses and condition monitoring evaluations because they are passive components that are generally considered to require no routine inspection and maintenance. Electrical cables are very important safety components, however, because they provide power to safety-related equipment and are used for instrumentation and contro l of safety functions. The NRC generic letter, GL 2007-01 [14], showed that a significant number of failures occurred under normal service conditions within the service interval of 20-30 years, which is before the renewed license period and before the end of the expected life span of the cables. The NRC has pursued research on the performance and degradation o f both power cables and control cables in NPP environments. Tn re lation to LTO, the NRC is cooperating with DOE and EPRI. A jointly-developed roadmap for cooperative research is being used to keep complementary testing programs on track.

Research in this area is investigating methods used for simulated aging of electrical cables, as well as condition monitoring to confinn that past equipment qualification practices were adequate, and to detenn ine optimum condition monitoring methods to monitor cable aging in periods of extended license renewal. Ongoing research projects have obtained new and naturally aged cable samples that will be subjected to synergistic effects of radiation, temperature, and humidity similar to that seen in operating NPPs. A number of condition-monitoring techniques will be applied during and following aging protocols to determine condition monitoring method predictive capability. Finally, the aged cables will be s ubject to loss-of coolant accident testing to determine qualification adequacy and margins.

7. CONCLUSION Extending the operating life of ex isting NPPs may be, for some utilities, an economically feas ible way to meet future energy demands. The responsibility of the NRC is to ensure that plant life extension is safe - that it does not pose additional risk to public health and safety or to the environment. The NRC's process for concluding that a renewed operating license can be issued involves rigorous safety and environmental reviews to verify that regulatory requirements will continue to be mel. The NRC has conducted confinnatory research to obtain s upporting data and to refine models that predict materials degradation during extended aging. Long-tem1 research to confim1 the adequacy of guidance for metallic components is ongoing. The N RC is conducting and planning additional research related to concrete structures and electrical cables, to reline our understanding of degradation that may affect these plant components. The research will continue through the license renewal period (up to 60 years) and into the subsequent license renewal period (up to 80 years). Data analyzed to date suggest that, with appropriate maintenance, light water reactors may be operated through the SLR period safely.

5

lAEA-CN-246-143 REFERENCES

[I] Code of Federal Regu lations IO CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, (amended) I 995.

[2] NUREG-219 I, Volumes I and 2, " Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report" (ADAMS Accession os. ML17187A031 and MLl7 187A204), I 190 pp, Jul y 20 17.

[3] NUR G-2 I 92, "Standard Review Plan for Review of S ub sequent License Renewal ApplicatiOn8 for Nuclear Power Plants" (S RP- LR) (A DAM Access ion No . ML17188A158) 509pp, July 20 17.

[4] SRM Requirements - SECY-14-0016- " Ongoing Staff Activities to Assess Regulatory Considerations for Power Reacto r Subseq uent License Renewal ," August 29, 2014 (MLI 424 1A578).

[5] Hull , A . B. , and Burke, J, " NPP Subsequent License Renewal: Lessons Learned from Aging Management Program (AMP) Effectiveness Audits," Proceedings from SMiRT-2 3, Manchester UK, 20 15.

[6] Hull , A. , Hise r, A ., and Lindo-Ta lin , ., " NPP License Renewal and Aging Manageme nt: Revised Guidance," Proceedings from Third International o nference n Nuclear Power P lant Life Management, alt Lake ity , A 14- 18 May 2012.

[7] NURE - 1800, Re v. 2, " tandard Review Plan for Review f License Renewal App lications fir Nuclear Power Plants," 393pp Dec. 20 I 0 .

[8] NUR - 1 01 , Rev . 2," e neric Aging Lessons Learned ( ALL) Re po rt," 86 l pp , Dec. 2010.

[9] NU R - I 925, Rev . 3, " Research Activities FY20 I 5-FY 20 I 7," 15 I pp, February 20 I 6.

[ I OJ NUR _ / R-6923 , " xpcrt Panel Report o n Proactive Material Degradation As cs mcnt," 2007.

[ I I] NUR * / R- 7 153, " xpandcd Materi al Degradation A c mcnt, Vol. 1-5," 20 14

[ 12] NR Tc hnica l Letter Rep rt, "Review of Agin g Management Program : ompcndium of In ig hts fr m Licen e Renewa l App lication a nd from AMP ffectivene s Audit nducted t In form ub equen t Licen e Renewal uid a nce Document ," 1400pp, June 15, 20 16 - (ML I 6 167 A076).

[ 13) Regulatory uid e 1.99, " Radiation mbrittlement f Reactor Ve el Material ," Revi ion 2.

May 3 1, 1988 .

[ 14] NR e neric Letter 2007-01 " In accessible or Undergrou nd Power able Failure that Di ab le Accident Mitigation ystem or a use Plant Transients," February 7, 2007 .

From: International Travel Sent: Tue, 24 Jul 2018 07:46:09 -0400 To: Sangimino, Donna-Marie;Valencia, Sylvia;Culp, Lisa;Correa, Yessie;RES International Travel Dist Cc: Tregoning, Robert; Regan, Ch ristopher;Cltravel Resource

Subject:

RES - Pre-Trip Report Notification - NRC JNRA Materials Information Exchange Meeting Greetings, The Pre-Trip Report for the trip, NRC JNRA Materials Informat ion Exchange Meeting has beeni submitted by Tregoning, Robert.

Regards, iTravel Administration Team Trip Name: NRC JNRA Materials Information Exchange Meeting Trip ID: 4428 Travelers: Tregoning, Robert;Regan, Christopher E-Mail: Robert.Tregoning@nrc.gov;Christopher.Regan@nrc.gov Multiple Travelers: Less than 4 Trip POC: Tregoning, Robert Office Director Approvals: RES Office Director (6/28/2018);

Travel Dates: 9/15/2018 - 9/22/2018 Destination: Tokyo, Japan Framework: Bilateral Cooperation,Cooperative Research International Organization: Other Purpose of Travel: Attend annual research and operating exchange meeting with JNRA held under the terms of the current bilateral agreement. Topics related to metals and cable aging related degradation and deterministic and probabilistic structural and component integrity will be discussed. Collaborative research activities on metal fatigue, leak-before-break, material harvesting, and RPV integrity will also be planned/discussed.

Desired outcome: Desired outcomes include leading discussion related to research, regulatory issues, and NPP operating experience associated with age-related degradation of metallic SSCs and safety-related cables. Some specific topics of interest in the area of cable aging include enivronmental qualification procedures, inspection, condition monitoring, synergistic effects, diffusion limited oxidation, and dose rate effects. In the metals area, continued discussion on

the develpment of an international fatigue database, mutual collaboration on deterministic and probabilistic RPV integrity assessment, and probabilistic fracture mechanics will be discussed. NRC and JNRA are currently participating in a leak-before-break benchmarking exercise and interim results and planning for future work under that effort will be discussed. Finally, NRC and JNRA will discuss collaboration on material harvesting topics.

Traveler Role(s): Dr. Tregoning is the principal US NRC contact for the NRC/JNRA bilateral agreement. He will be coordinating the meeting topics and agenda for the NRC side and will also be responsible for all discussions and activities associated with age-related degradation of metallic SSCs, including structural/component integrity assessment. He will also be the NRC lead for identifying material harvesting opportunities for metallic components and, if appropriate, initiating plans for future collaboration with JNRA in this area.

Mr. Murdock will be responsible for all presentations and discussions associated with the age-related degradation of safety- related cables. In addition, Mr. Murdock will be the NRC lead for identifying opportunities to harvest cables and electrical components and, if appropriate, Initiating plans for future collaboration with JNRA in the realm of cable aging.

Mr. Regan will engage with counterpart JNRA leadership to ensure continued cooperation and support for activities conducted under the bilateral agreement. Mr. Regan will also take advantage of the opportunity to meet with JNRA management on their other research programs of current and potential future value to RES (Division of Engineering) activities.

Externally Funded: No Policy Issues: No If yes, how will OCM be informed: N/A

This is an auto distribution sent from the combined International Travel SharePoint Svstem.

For questions, please communicate with your Office point{s) ofcontact.

111 fflt$Jrt~P11f1'01tMA"n'Oii - 0>¥.JC'J)1t ~O'JrtP 0

From: International Travel Sent: Tue, 24 Jul 2018 07:55:13 -0400 To: Sangimino, Donna-Marie;Valencia, Sylvia;Culp, Lisa;Correa, Yessie;RES International Travel Dist Cc: Tregoning, Robert; Regan, Ch ristopher;Cltravel Resource

Subject:

RES - Pre-Trip Report Notification (RESUBMITTAL) - NRC JNRA Materials Information Exchange Meeting Greetings, The Pre-Trip Report for the trip, NRC JNRA Materials Informat ion Exchange Meeting has beeni re-submitted by Tregoning, Robert.

Regards, iTravel Administration Team Trip Name: NRC JNRA Materials Information Exchange Meeting Trip ID: 4428 Travelers: Tregoning, Robert;Regan, Christopher E-Mail: Robert.Tregoning@nrc.gov;Christopher.Regan@nrc.gov Multiple Travelers: Less than 4 Trip POC: Tregoning, Robert Office Director Approvals: RES Office Director (6/28/2018);

Travel Dates: 9/15/2018 - 9/22/2018 Destination: Tokyo, Japan Framework: Bilateral Cooperation,Cooperative Research International Organization: Other Purpose of Travel: Attend annual research and operating exchange meeting with JNRA held under the terms of the current bilateral agreement. Topics related to metals and cable aging related degradation and deterministic and probabilistic structural and component integrity will be discussed. Collaborative research activities on metal fatigue, leak-before-break, material harvesting, and RPV integrity will also be planned/discussed.

Desired outcome: Desired outcomes include leading discussion related to research, regulatory issues, and NPP operating experience associated with age-related degradation of metallic SSCs and safety-related cables. Some specific topics of interest in the area of cable aging include enivronmental qualification procedures, inspection, condition monitoring, synergistic effects, diffusion limited oxidation, and dose rate effects. In the metals area, continued discussion on

the develpment of an international fatigue database, mutual collaboration on deterministic and probabilistic RPV integrity assessment, and probabilistic fracture mechanics will be discussed. NRC and JNRA are currently participating in a leak-before-break benchmarking exercise and interim results and planning for future work under that effort will be discussed. Finally, NRC and JNRA will discuss collaboration on material harvesting topics.

Traveler Role(s): Dr. Tregoning is the principal US NRC contact for the NRC/JNRA bilateral agreement. He will be coordinating the meeting topics and agenda for the NRC side and will also be responsible for all discussions and activities associated with age-related degradation of metallic SSCs, including structural/component integrity assessment. He will also be the NRC lead for identifying material harvesting opportunities for metallic components and, if appropriate, initiating plans for future collaboration with JNRA in this area. Dr.

Tregoning will also be responsible for all presentations and discussions associated with the age-related degradation of safety-related cables and will be the NRC lead for identifying opportunities to harvest cables and electrical components and, if appropriate, initiating plans for future collaboration with JNRA in the realm of cable aging.

Mr. Regan will engage with counterpart JNRA leadership to ensure continued cooperation and support for activities conducted under the bilateral agreement. Mr. Regan will also take advantage of the opportunity to meet with JNRA management on their other research programs of current and potential future value to RES (Division of Engineering) activities.

Externally Funded: No Policy Issues: No If yes, how will OCM be informed: N/A

This is an auto distribution sent from the combined International Travel SharePoint Svstem.

For questions, please communi'cate with your Office point(s) ofcontact.

From: International Travel Sent: Thu, 3 May 2018 17:00:44 -0400 To: RES International Travel Dist;Sangimino, Donna-Marie;Valencia, Sylvia;Culp, Lisa Cc: Pires, Jose;Tregoning, Robert

Subject:

RES - Trip Report Notification - CSNI WGIAGE Working Group Greetings, The Trip Report for the trip, CSNI WGIAGE Working Group has been submitted by Tregoning, Robert.

Regards, iTravel Administration Team Trip Name CSNI WGIAGE Working Group Trip ID: 4427 Travelers: Pires, Jose;Tregoning, Robert Travel Dates: 4/7/2018 - 4/14/2018 Destination: Paris, France Trip Report ML18123A492 Results Achieved: The results achieved during the meeting include the following highlights. In the concrete subgroup meeting, the subgroup discussed and generally concurred with the CNSC proposal for new CSNI project called HARVEST, which will study in-situ effects of ASR using ASR-affected concrete and concrete structures from a decommissioned nuclear power plant in Canada (Gentilly-2). In a breakout meeting on Friday, April 13, the CNSC and interested participants includling the NRC agreed on the general scope and plan for the project. Additionally, EDF provided early results of an experimental program that studies the shear capacity of reinforced concrete beams with low flexural reinforcement and with or without shear reinforcement subjected to axial forces under specific conditions.

In the seismic subgroup meeting, the final report on the use of Probabilistic Seismic Hazard Assessment (PSHA) in areas of low observed seismicity was discussed with plans to finalize this report by June 2018. A questionnaire has been developed to assess single pipe support failure during a seismic event. Responses are due by August 2018. The continuing collaboration between the working group and IAEA on the Database on Nuclear Facilities that Experienced an Earthquake was discussed. NRC is evaluating information for possible submittal to th,e database.

In the metals subgroup meeting, the possibility to share fatigue data among countries was explored. The research activity on a round-robin analysis benchmark on leak-before-break (LBB) in piping systems was initiated and agreement was reached on the scope, approach, deliverables, and schedule associated with the activity. A new round-robin analysis benchmark on xFEM was initiated and the scope and schedule for phase I of the study was confirmed.

The results achieved during the main meeting included discussing of the research activities on the behavior of components and structures due to severe accident loading (COSSAL). This project is in its final phase and the final report is expected within the next year. Also, a round table discussion on research supporting long-term operations and recent component failures or degradation was held.

The meetings were beneficial to the NRC and our regulatory practices because we learned about the latest operating experience related to materials degradation and seismic issues as well as the latest research and findings in these areas. This information is shared throughout the NRC to inform our own research, and associated regulatory, activities.

This is an auto distribution sent from the combined International Travel SharePoint System.

For questions/ please communicate with your Office point(s) of contact

- SCllSEFlf/Eiti,=BRMA 71811 Brr..*c,..*At ~ ot,*t ,,...

From: International Visits Sent: Mon, 27 Feb 2017 11:37:51 -0500 To: Wittick, Susan;Hiser, Matthew Cc: Rodriguez, Veronica;Quinones-Navarro, Lauren;Sangimino, Donna-Marie;Valencia, Sylvia

Subject:

RES,NRR - New Visit - Materials Harvesting Workshop Greetings, The following new visit, Materials Harvesting Workshop has been successfully created in the International Visits site.

The meeting is now pending confirmation.

Click here to confirm.

Regards, iVisits Administration Team Meeting Name: Materials Harvesting Workshop Meeting ID: 241 Meeting Tregoning, Robert;Sircar, Madhumita;Koshy, Thomas;Purtscher, Patrick;Hiser, Participant(s): Matthew OIP POC: Wittick, Susan Meeting 3/7/2017 - 3/8/2017 Dates:

Meeting HQ Location:

Visiting Germany Reactor Safety Authority,Belgium Federal Agency for Nuclear Organizations: Control,Japan Nuclear Regulation Authority,Canadian Nuclear Safety Commission

This is an auto distribution sent from the combined International Vis its SharePoint Svstem.

For questions, please communicate with your Office point(s) ofcontact.

- OEErcZA, USE 9t'll Y**

From: International Visits Sent: Wed, 1 Mar 2017 09:55:05 -0500 To: Wittick, Susan;Hiser, Matthew Cc: Rodriguez, Veronica;Quinones-Navarro, Lauren;Sangimino, Donna-Marie;Valencia, Sylvia

Subject:

RES,NRR - Visit Confirmed - Materials Harvest ing Workshop Greetings, The following new visit, Materials Harvesting Workshop, has been confirmed in the I nternational Visits site.

To the extent possible, a meeting summary should be developed and distributed 15 business days upon completion of the visit.

Click here to add the Meeting Summary.

Regards, iVisits Administration Team Meeting Name: Materials Harvesting Workshop Meeting ID: 241 Meeting Tregoning, Robert;Sircar, Madhumita;Koshy, Thomas;Purtscher, Patrick;Hiser, Participant{s): Matthew OIP POC: Wittick, Susan Meeting 3/7/2017 - 3/8/2017 Dates:

Meeting HQ Location:

Visiting Germany Reactor Safety Authority,Belgium Federal Agency for Nuclear Organizations: Control,Japan Nuclear Regulation Authority,Canadian Nuclear Safety Commission

This is an auto distribution sent from the combined International Visits SharePoint Svstem.

For questions, please communicate with your Office pointfsJ ofcontact.

p I o,f'Jt:f14t Ii~ tJff't )"!IF

From: Hull, Amy Sent: Mon, 12 Mar 2018 21:33:23 +0000 To: Audrain, Margaret;Harris, Brian;Tregoning, Robert;Purtscher, Patrick; Burke, John;Herrity, Thomas Cc: Moyer, Carol;Hiser, Matthew;Frankl, Istvan

Subject:

RIC CAC is MF1396: AM and Harvesting, Posters 15 & 7: RIC EPOSTERS AND DIGITAL PRESENTER GUIDANCE - NEXT STEPS CAC for RIC volunteer work is MF1396 From: Audrain, Margaret Sent: Monday, M arch 12, 2018 12:25 PM To: Hull, Amy <Amy.Hull@nrc.gov>

Subject:

RE: AM and Harvesting, Posters 15 & 7: RIC EPOSTERS AND DIGITAL PRESENTER GUIDANCE -

NEXT STEPS

Amy, It looks good to me. Do you know what the CAC is for this?

Thanks, Meg From: Hull, Amy Sent: Monday, March 12, 2018 8:54 AM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>;

Audrain, Margaret <Margaret.Audrain@nrc.gov>; Hiser, Matthew <Matt hew.Hiser@nrc.gov>

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

Subject:

RE: AM and Harvesting, Posters 15 & 7: RIC EPOSTERS AND DIGITAL PRESENTER GUIDANCE -

NEXT STEPS Steve suggested I also prepare a draft questionnaire for harvesting. Please let me know by COB today if there are any changes you want made. Thanks, Amy From: Hull, Amy Sent: Thursday, March 08, 2018 12:21 PM To: Burke, John (John.Burke@nrc.gov) <John.Burke@nrc.gov>; Herrity, Thomas

<Thomas.Herrity@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>; Tregoning, Robert

<Robert.Tregoning@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Audrain, Margaret

<Margaret.Audrain@nrc.gov>

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

<lstvan.Frankl@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

AM and Harvesting, Posters 15 & 7: RIC EPOSTERS AND DIGITAL PRESENTER GUIDANCE - NEXT STEPS Importance: High

We have scheduling completed for staffing (see attached). For additive manufacturing poster staffing, I have the following suggestions for consideration to help us get information about what industry is doing -

(1) Have along your business cards and try to get a business card from your visitor (if you need extra card stock, I have some in my workspace)

(2) Engage your visitor with topics on the draft questionnaire and try to complete for each visitor (attached draft)

(3) I will make extra small copies of the poster for visitor to take along if interested (4) If nothing else, please try to get the name and affiliation of visitor (attached draft).

If you have comments on the attached drafts or other suggestions on how to make the most of our time next week, please let us know.

Thanks for your participation in this, Amy From: Warren, Brenett Sent: Monday, March 05, 2018 1:55 PM To: Bridge, Joanna <Joanna.Bridge@nrc.gov>; M endiola, Mary <Mary.Mendiola@nrc.gov>; Zuberi, Sardar <Sardar.Zuberi@nrc.gov>; Dembek, Stephen <Stephen.Dembek@nrc.gov>; Yadav, Priya

<Priya.Yadav@nrc.gov>; Kenny, Caylee <Caylee.Kenny@nrc.gov>; Sturzebecher, Karl

<Karl.Sturzebecher@nrc.gov>; Bernardo, Robert <Robert.Bernardo@nrc.gov>; Wilson, Joshua

<Joshua.Wilson@nrc.gov>; Hall, Victor <Victor.Hall@nrc.gov>; Couret, Ivonne

<lvonne.Couret@nrc.gov>; West, Stephanie <Stephanie.West@nrc.gov>; Savoy, Joanne

<Joanne.Savoy@nrc.gov>; King, Shannon <Shannon.King@nrc.gov>; Ralph, Melissa

<Melissa.Ralph@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Steger, Christine

<Christine.Steger@nrc.gov>; Armstrong, Kenneth <Kenneth.Armstrong@nrc.gov>; Gifford, Ian

<lan.Gifford@nrc.gov>; Smith, Todd <Todd.Smith@nrc.gov>; Howells, Christopher

<Christopher.Howells@nrc.gov>; Orf, Tracy <Tracy.Orf@nrc.gov>; Cruz, Holly <Holly.Cruz@nrc.gov>;

Morey, Dennis <Dennis.Morey@nrc.gov>; Oberson, Greg <Greg.Oberson@nrc.gov>; Hull, Amy

<Amy.Hull@nrc.gov>; Moyer, Carol <Carol.Moyer@nrc.gov>; Bowman, Gregory

<Gregory.Bowman@nrc.gov>

Cc: RICMST Resource <RICMST.Resource@nrc.gov>; Kipfer, Lorna <Lorna.Kipfer@nrc.gov>

Subject:

RIC EPOSTERS AND DIGITAL PRESENTER GUIDANCE - NEXT STEPS Importance: High Good Afternoon Poster Presenters, We are 1 week from RIC 2018 and I want to provide you with a few details to assist:

EPOSTER AND DIGITAL PRESENTATION SCHEDULE

ePoster and Digital Presenters should be present at the RIC. Although your poster may be set on a continuous run/feed there should be a person present to discuss the poster

and to field questions from the attendee viewing the slide presentation March 13 - 15, 2018.

Refer to Program Agenda on the RIC website at https://ric.nrc.gov/agenda for t he full schedule of the RIC. Recommended times for visual presence should be during the following:

Tuesday:

7:30 a.m. - 8:30 a.m. Meet and Greet - Networking Opportunity 8:30 a.m. - 10:00 a.m. Opening Sessions 10:00 a.m. - 10:30 a.m. Networking Break 10:30 a.m. 12:00 p.m. Commission Plenary 12:00 p.m. - 1:30 p.m. Lunch Break 3:00 p.m. - 3:30 p.m. Networking Breaks Wednesday:

7:30 a.m. - 8:30 a.m. Meet and Greet - Networking Opportunity 10:00 a.m. - 10:30 a.m. Networking Break 12:00 p.m. - 1:30 p.m. Lunch Break 3:00 p.m. - 3:30 p.m. Networking Breaks Thursday:

7:30 a.m. - 8:30 a.m. Meet and Greet - Networking Opportunity 10:00 a.m. -10:30 a.m. Networking Break LAPTOP SETUP AND TESTING WITH OCIO TECH

Arrive at the Bethesda North Marriott Hotel and Conference Center on Monday, March 12, 2018 between 9:00 a.m. and 11:00 a.m.

o Test laptop/monitor connection o Verify loaded presentation shows accurately on monitor

There will be a NRC technician from OCIO to complete the install of laptops with interactive (multi page slides). Single slide presenters (ePoster) may view their presentation at that time as well.

FLOORPLAN FOR EPOSTER AND DIGITAL PRESENTATIONS

The preliminary floorplan is attached for your reference. If for any reason the floorplan should change, you will be notified.

Ensure accuracy when referring to your poster, refer to the attached ePoster and Digital Presentation by number. Note, the posters were previously renumbered however, some presenters continued to use the old numbers. Please use the following numbered posters and titles.

SHIPPING MATERIALS

If you plan to include materials for your ePoster and Digital Presentation with the bulk shipment from the NRC to the Marriott, it is imperative that you have all of the items properly labeled and taken to the Reprographics OP1-B3500 common area - labeled RIC shipping by close of business Thursday, March 8, 2018.

All materials must be packed, properly labeled and in the designated Reprographics pick up location by close of business March 8, 2018. Provide on the shipping label and also to RICMST.Resource@nrc.gov:

o The total number of boxes o Include your name o Include title of your ePoster and Digital Presentation

We do ask that you limit the amount of materials you will bring due to reduced space in the Marriott foyer area.

Affix a completed shipping label to each box. The materials received will be included on the manifest report for tracking purposes.

Return shipping will occur on March 15 at 1 :00 pm. If you wish to have any materials returned to the NRC prior to your departure from the Marriott, please affix a return To ensure accurate return please affix a label with your name and mailstop. All unmarked materials left in the Marriott foyer unmarked will be discarded.

Thank you, Program Specialist Oflice of Nuclear Heactor Hegulation NHH/ D:vJPS/ IHSB Location: 0 I 3 D 5 SO I - I* I 5-S I 1'1*

Follow 11s 011 Twitter@nrcgov_ric

Note to requester: Attachment is immediately fo llowing.

From: Hiser, Matthew Sent: Tue, 21 Nov 2017 19:53:35 +0000 To: RICMST Resource Cc: Oberson, Greg;Frankl, Istvan

Subject:

RIC ePoster Approval: Harvesting of Aged Materi als from Operating and Decommissioning Nuclear Power Plants Attachments: NRC 1102 - Harvesting.pdf

Dear RICMST,

Please find attached the Form 1102 for the poste r titled, "Harvesting of Aged Materials from Operating and Decommission ing Nuclear Power Plants."

Thanks!

Matt Matthew Hiser Materials Engineer US uclear Regulatory Commission I Office of uclear Regulatory Research Divis ion of Engi neering I Corrosion and Metallurgy Branch Phone: 301-4 15-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov

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

\,.,¥\

......~i RIC PROPOSED DIGITAL PRESENTATION SUBMISSION FORM Original Submission 0 Updated Submission

==

Description:==

A graphical presentation of research results, the status of standards development, the status of safety or security issues, or other topics of major interest to the agency, interested parties and/or the public.

Standard Setup: Standard setup consists of one 46" monitor (screen size 40" w idth x 22.5" height) mounted on a floor stand; o ne USB media player; o ne remote control; one small table and o ne chair.

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

Digital Presentation (Multi-slide): Format is a multi-slide PowerPoint. Word li mit is 400-500 per slide .

Limit of 5-6 large photos, images, or diagrams per slide.

Submitting Office(s): Enter office acronym, if a joint session, enter lead office followed by supporting office.

RES

Title:

Tille should be relatively shorl, yet creative and appealing to the audience.

Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants Descriptio n: Description should be innovative, succinct, and include key elements such as purpose, learning objectives, focus areas, and/or take-away messages.

Recent plans to shut down a number of nuclear power plants (NPPs) provide opportunities for harvesting components that were exposed to light water reactor (LWR) environments. Harvesting can provide highly representative aged materials for research and, in some cases, may be the only practical source of representative aged materials to address high-priority issues. Harvesting can be expensive and time-consuming, which makes it essential to focus on technical needs with the highest importance and cooperate with multiple organizations whenever possible to optimally leverage resources. NRC is interested in engaging with other organizations to prioritize data needs for harvesting, identify areas of common interest, and develop a database for sources of materials for harvesting.

Presenter(s): If known, for each presenter, enter first and last name, position, division title and organization. If possible, list names in the order they will be presenting.

Office/Organization Organization/Agency Add(+)

No. First a nd Last Name Position Title Division Title (NRC) (Acro nyms) (Non-NRC) Remove(*)

Matthew Hiser Materials Division of RES 1

Engineer Engineering GD Topic Submitted By: If the names of the Presenter(s) are not known, enter a point of contact, Name and contact information, for the topic submission.

Please submit the completed form, via e-mail, by the following date: Due Date: I 11/27/2017 I

NRC FORM 1102 (09-2017)

I[ Submit by E-mall ] Page 1 of 1

Note to requester: Attachment is immediately following.

From: Frankl, Istvan Sent: Tue, 17 Oct 2017 08:43:04 -0600 To: Moyer, Carol;Hiser, Matthew

Subject:

UPDAliE ACTION: Inputs for EPRI quarterly MOU call Attachments: EPRI Quarterly MOU Status Update.xlsx Importance: High Please use the latest attached revision of the spreadsheet for your updates and identify the revisions with red font.

Thanks, Steve From: Frankl, Istvan Sent: Tuesday, October 17, 201710:32 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>

Subject:

ACTION : Inputs for EPRI quarterly MOU call Importance: High

Carol, Brian needs additional info on harvesting for the upcoming EPRI quarterly MOU call on 11/3.

Please address the highlighted request below in your reply and update relevant section of the attached spreadsheet.

Please complete this action by noon tomorrow.

Matt, Please assist Carol with this action.

Thanks, Steve From: Thomas, Brian Sent: Tuesday, October 17, 201710:11 AM To: Oberson, Greg <Greg.Oberson@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>; Iyengar, Raj

<Raj.lyengar@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Miller, Kenneth A

<KennethA.Miller@nrc.gov>; Boyce, Tom <Tom.Boyce@nrc.gov>

Cc: Regan, Christopher <Christopher.Regan@nrc.gov>

Subject:

RE: Inputs for EPRI quarterly MOU call

Folks, The status update for the action items for CMB, ICEEB, and RGGIB needs improvement.

For CIB - I am not aware of any deep dive meetings occurring. Specific accomplishments for such meetings should be identified. Neither I nor Chris attended nor were invited to any such meeting. Information stated was already known and does not portray any progress on the action item.

For cable harvesting - please state what was done to enable the completion of the harvesting.

Also state what other collaborative activities are needed regarding cable research at this time?

For RGGIB/Codes and Standards - please state what occurred or was agreed to going forward at the Standards Forum .

Thanks ... Brian From: Oberson, Greg Sent: Monday, October 16, 2017 4:40 PM To: Thomas, Brian <Brian .Thomas@nrc.gov>

Cc: Regan, Christopher <Christopher.Regan@nrc.gov>

Subject:

Inputs for EPRI quarterly MOU call Brian ,

Attached are the inputs for your consideration . I would like to provide these to Nick by Wednesday if possible.

Greg

Action Item Assianment Status U odate For Manaaement Awareness Review the availability of cables that could be harvested from plants in Cable harvesting is complete for the currenl research EPRI and NRC management and staff should be decommissioning to support research on cable aging and perfonnance project on cable condition assessment and cable encouraged to continue awareness of decommissioning under realistic conditions . Elevate as needed to EPRI and NRC degradation. NPPs in order to Identify potentlal componen ts for future management to facilitate successful availability, ICEEB harvesting, NRC/RES is undertaking a research project to prioritize components for harvesting that 'Nill support aging management studies for SLR, Including electrlcal components.

Schedule ~deep dive" meelings on LTO RVPJ Concrete I Cables research EPRUNRC *deep dives" have been completed. EPRI and NRC management and staff should be w ithin the near-term (3-6 months) to assess the status of roadmap activities, encouraged to continue participation In the joint roadmap Identify remaining gaps in Researeh, determine what research remains to RPVs & Internals: A public wori<shop on RPVs and process to track complellon of confirmatory research for be completed, and when can we terminate these research projects (e .g .. internals is planned for Spring 2019. L TO, as well as to ldentiry any emerging oppott1.inilies for concrete irradiation). Add itionally. identify options to complete the research leveraging or otherwise accelerating completion of the in an efficient manner and that optimizes use of available resources. Concrete: A joint (NRC/DOE/EPRI) roadmap work. Lessons learned from reviews and implementation Assess read iness for potentlal ulillty submlttals by Dec 2017. Use lhese meeting on concrete Is expecled In 04 of CY20 17. of the lead SLR appllcatlons 'Nill be fed back into the joint updated roadmaps to complete remaining research in support or long-term roadmap process.

operations . CMB Cables: A joint roadmap meeting on cables is scheduled for 118/2018. A public work.shop on conaele and cables Is planned for Summer 2020.

Based on confirmatory research to date, the NRC is ready to receive utility submittals in Dec . 2017. The joint roadmap process is being used to track complelion of remaining research in support of LTO.

Identify if there are opportunities for an earlier SLR workshop in 2017 in After discussions with RES and EPRI staff , it was None advance of the first SLR application by the end of lhe year. determined that an SLR work.shop in 20 17would not be timely. Near-1errn applicants are In the peer-review phase, and unlikely to modify ap~ications.

Wortl.shops would be more effective after lessons CMB learned from add ressing the lead applications.

Public workshops on SLR are being planned for Spring 2019 (RPVs and Internals) and Summer 2020 (Concrete and Cables).

Responsibility for this action item has been taken by None Develop technical addendum on advanced reactor materials research Kathy Gibson. The MOU will address all ANLWR which identify planned NRC and EPRI cooperation. Focus on aligning CIB research, not just materials. The MOU is nearing efforts and avoiding unnecessary duplication of activities . Targel end of the readiness for management review.

vear.

Forward to Kurt by the end of June lhe invile to the September 20,7 Brian Thomas sent an email to Kurt Edsinger on 6128 Kurt E. suggested that we make use of EPR I reports a Standards forum meeting. which NRC is hosting. inviting EPRI to the NRC Standard Forum, and topic for a quarterly meeting or a face*to-face meeting.

requesting that EPRI make their reports publ icly We could also explore whether EPRI could get vendors to available so they can be used for standards. Kurt particpate in using the reports and creating standards.

RGGIB repUed on 6130 that EPR I would support the Forum, and would likely make their reports available to those interested.

Work with legal staff to enable domestic distribution of the xLPR code and Staff has sent a revised MOU to inlcude domestic* No response yet from EPRI legal counsel. Raj elevated facilitate future international distribution. Explore viable and practical only distribution of xLPR to EPRI legal team late to B. Thomas attention by email oo 10115.

approaches, such as distributing lhe code to International non-govemmenlal August. We are yet to hear back from the EPRI legal entities through RISSC. team.

CIB

Note to requester: Attachment is immediately following. The slide notes are included with the attached file.

From: Frankl, Istvan Sent: Mon, 7 May 2018 21:10:37 +0000 To: Audrain, M argaret; Focht, Eric;Hiser, Matthew;Hull, Amy;Moyer, Carol;Purtscher, Patrick;Rao, Appajosula Cc: Christensen, Jason;Harris, Brian

Subject:

UPDATE ACTION : Topics for Materials Exchange Meeting May 22-26 Attachments: ACRS presentation materials research slide - CMB (Rev 1).pptx Importance: High I had discussion with Rob this morning on the slides for the 30 minute CMB summary. His recommendation was that CMB and CIB use the format of the ACRS briefing slides on DE research (attached), The basic format for the ACRS slides called for 2 pages for each program area (max 3 pages if needed) covering basically four topics for each program: Overview, Ongoing Activities, Accomplishments and Path forward.

Our slides for the Materials Exchange meeting will also need to implement the guidance provided by NRR below.

Thanks, Steve From: Frankl, Istvan Sent: Friday, May 04, 2018 10:13 PM To: Audrain, Margaret <Margaret.Audrain@nrc.gov>; Focht, Eric <Eric.Focht @nrc.gov>; Hiser, Matthew

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

Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>

Cc: Christensen, Jason <Jason.Christensen@nrc.gov>; Harris, Brian <Brian.Harris2@nrc.gov>

Subject:

REM INDER ACTION: Topics for Materials Exchange Meeting May 22-26 Importance: High

All, This is a friendly reminder for the program leads to send me about 3 slides for their specific topic below ASAP but no later than COB Tuesday.

The attached draft agenda is still evolving but based on the latest alignment meeting with DM LR yesterday, there is no major change in the CMB specific sessions. Here are some guidance and takeaways provided by NRR:

The focus of the presentations should be on the impact of the results to plant operation and licensing, and not an emphasis on "here is what we are doing." Make sure the intended messages are clear in each area.

The question to keep in mind for all of the NRC presentations is: why should the indust ry care about the information the NRC is presenting? If we cannot identify a current or short-term

aspect that the industry should care about, then we should hold the topic to a possible presentation at a future meeting.

Please let me know if you need further guidance or clarifications on the above.

Thanks, Steve From: Frankl, Istvan Sent: Wednesday, April 25, 2018 11:28 AM To: RES_ DE_CMB <RESDECMB@nrc.gov>

Subject:

ACTION : Topics for Materials Exchange Meeting May 22-26 Importance: High

All, The attachment is the latest NRR draft agenda. We will need to provide input for AM methods and have responsibility for the 30 minute time slot on 5/23 for "Status of Related Research" in CMB. If you have comments on the draft agenda, please send them to me by COB Friday.

For AM I want to make sure that we are aligned with our counterparts in NRR/NRO on the proposed presentation(s) and presenter(s). (Amy, please get back to me on this.)

For our 30 minute time slot we can cover summaries of some or all topics proposed earlier.

Here is the list:

1. Harvesting - Current plans and activities

2. IAD - confirmatory testing plans

3. PWSCC Crack Growth - Current research plans and results

4. Status Update on the PWSCC Initiation Program

5. Status of Confirmatory Research for SLR/LTO At this stage, I will ask the respective leads to draft about 3 summary slides for each of the above topics.

Thanks, Steve From: Rudland, David Sent: Wednesday, April 25, 2018 6:22 AM To: Alley, David <David.Alley@nrc.gov>; Ruffin, Steve <Steve.Ruffin@nrc.gov>; Collins, Jay

<Jay.Collins@nrc.gov>; Cumblidge, Stephen <Stephen.Cumblidge@nrc.gov>; Davis, Robert

<Robert.Davis@nrc.gov>; Tsao, John <John.Tsao@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>;

Fairbanks, Carolyn <Carolyn.Fairbanks@nrc.gov>; Hovanec, Christopher

<Christopher.Hovanec@nrc.gov>; Yee, On <On.Yee@nrc.gov>; Cheruvenki, Ganesh

<Ganesh.Cheruvenki@nrc.gov>; Hoffman, Keith <Keith.Hoffman@nrc.gov>; Medoff, James

<James.Medoff@nrc.gov>; Iyengar, Raj <Ra j.lyengar@nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>;

Mitchell, Matthew <Matthew.Mitchell@nrc.gov>; Rezai, Ali <Ali.Rezai@nrc.gov>

Subject:

FW: 2018-05-22 agenda draft Everyone Please take a look at the draft agenda for the materials meeting and let me know if you have any comments. We are still determining who will be making what presentation. Can I please get your comments by April 30?

Ali , did Allen talk with you about getting the meeting set up?

Thanks Dave David L. Rudland, Ph.D.

Senior Technical Advisor for Nuclear Power Plant Materials Division of Materials and License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: OWFN-11F01 11555 Rockville Pike Rockville, MD 20852-2738 Office: (301) 415-1896 (b)(6) (:'.f:!JI: 1 --- - I Email: david.rudland@nrc.gov From : Dyle, Robin [33]

Sent: Tuesday, April 24, 2018 9:00 PM To: Hiser, Allen <Allen.Hiser@nrc.gov>; Rud land, David <David .Rudland@nrc.gov>

Subject:

[External_Sender] 2018-05-22 agenda draft Gents - here is a first cut at the agenda. I'll let the 2 of you coordinate with your peers. I sent a copy to the industry leads for their review and comment. We can adjust as needed.

I' m not sure this bunch will interested in the advanced non-LWRs_ If we need more time for other items we could reduce the time for that topic . Also we are very light on Thursday morning so we c an stretch out some items or finish Wednesday afternoon .

Thoughts?

Robin Dyle Office: 205-426-5371 (b)(6) CeU; ... L=

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Materials Research Overview

Points of Contact Raj Iyengar, Branch Chief, Component Integrity Branch Istvan (Steve) Frankl, Branch Chief, Corrosion & Metallurgy Branch Robert Tregoning, Senior Level Advisor

Research Areas Environmentally Assisted Degradation Steam Generator Tube Integrity Reactor Pressure Vessel Integrity Piping Integrity Probabilistic Fracture Mechanics Nondestructive Examination Subsequent License Renewal Spent Fuel Dry Storage Additive Manufacturing of Reactor Components Advanced Non-light Water Reactors (ANLWR) Materials

Environlllentally Assisted Degradation

Overview

- Objective: Evaluate the effects of corrosion, aging and irradiation on the performance of primary system piping, reactor pressure vessel (RPV} internals and RPV head penetrations

- Driver: Reactor coolant pressure boundary leakage and integrity

- Applications:

Primary Water Stress Corrosion Cracking (PWSCC} crack growth rate (CGR} disposition curves and xLPR Code results inform regulatory decisions on inspection requirements

Regulatory guidance for the aging management of RPV internals and reviews

- Collaboration: EPRI, Halden, International Regulators

Ongoing activities for PWSCC

- PWSCC initiation and CGR testing

PWSCC initiation testing is a recently-started cooperative effort

- Evaluation of industry-developed CGR reference curves

Ongoing activities for lriradiation Assisted Degradation (IAD)

- CGR and fracture toughness testing of irradiated ex-plant plate and weld materials

- Fracture toughness testing of irradiated and thermally aged cast austenitic stainless steel (CASS)

- Evaluation of industry-developed CGR reference curves for irradiation-assisted stre corrosion cracking (IASCC} of stainless steels

Summary of Comments on PowerPoint Presentation Page:2 Number: 1 Author: Presenter

Subject:

Presentation Notes Date: 2/19/202 110:50:25 AM My name is Steve Frankl. I am the Branch Chief of the Corrosion and Metallurgy Branch (CMB) in RES/DE. The focus of regulatory research in my branch is material performance and degradation in the operating environment of Nuclear Power Plants (NPPs).

Environmentally Assisted Degradation (EAD)

Overview EAD eva luates the effects of corrosion, aging and irradiation on the performance of primary system piping, reactor pressure vessel (RPV) internals and RPV head penetrations Drive r: Reactor coo lant pressure boundary leakage and component integrity Applications/ use:

PWSCC crack growth rate (CGR) dis position curves and xLPR Code results to inform regulatory decisions on inspection requirements Regulatory guidance for the aging management of RPV internals and regulatory reviews Cooperate with EPRI, Halden and International Regu lators Ongoing Activit ies EAD research in CMB covers PWSCC and IAD.

PWSCC initiation and CGR testing RES/DE has recently started cooperative effort with EPRI for PWSCC in itiation testing on Al loy 600/82/182 and Alloy 690/52/152 to support the xLPR project and to conduct confirmatory research. NRR will use the data to support its review of the xLPR code.

PWSCC CGR testing is being conducted to obtain data for Alloy 690/52/152 to inform inspections requirements for upper heads, piping we lds, overlays, inlays and on lays. RES/DE also participates through our contractors in the development of PWSCC CGR reference curves.

IAD IAD activities are focused on mechanical testing and microstructura l characterization of ex-plant baffle plate and weld materia ls, including those acqu ired in cooperation with EPRI from the Zorita reacto r in Spain as well as potential research on baffle bolts removed from service during recent inspections.

IAD activities also include complet ing fractu re toughness testing on irradiated and thermally aged cast stainless steel (CASS) materi als and providing technical support for the review of industry-developed CGR reference curves for IASCC of sta inless steels.

Next slide please.

Note to requester: The date and time stamp at the top of these comment summary pages are the date and time this file was created for processing. It is not the date and time of document creation .

PWSCC Accomplishments and Path Forward

Aecom plish ments Established NRC PWSCC initiation testing capability at PNNL

Advanced the state-of-art through automation and the optimization of advanced crack detection technology Obtained PWSCC CGR data at ANL and PNNL to support regulatory decision making for inspection intervals and provided basis to support wide-spread use of Alloy 690 in the fleet

Path Forward Near term:

Provide PWSCC initiation data to support V&V and regulatory review of the xLPR Code.

Continue the CGR testing program through early 2019

- Long term: Continue to provide PWSCC initiation data to:

Determine sec initiation modeling parameters for future xLPR updates and possibly other components such as RPV internals.

Inform regulatory decisions on factor of improvement for impact on inspection intervals .

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Presentation Notes Date: 2/19/2021 10:50:25 AM PWSCC Accomplishments and Path Forward Accomplishments The PWSCC project established NRC's capability to perform PWSCC crack initiation testing. The NRC funded PNN L to build two PWSCC cracking init iation testing systems. The systems incorporate state-of-the-art technology for: environmental control (i.e. water chemistry and temperature),

crack init iation detection using direct current potential drop, and automated load shedding to protect adjacent specimens during specimen failures.

Since the early 2000s, industry has been replacing, repairing and mitigating components fabricated from susceptible materials, using alloys that appear to be more resistant to PWSCC, referred to as Alloys 690, 52, and 152.

RES/DE used PWSCC CGR data from ANL and PNN L to help provide technical basis to support widespread use of Alloy 690 in the fleet and to support regulatory decision making for inspection intervals.

[SKIP] The susceptibility of the alloys to cracking can be demonstrated by laboratory tests in which specimens are exposed to stress in simulated primary water. The tests can measure the time required to in itiate a crack once the loading begins, and the rate at which the crack grows once init iated.

PWSCC CGR testing supports:

1. PWSCC relief requests for OM welds and upper/lower head inspect ions

2. LBB and xLPR (C IB)

3. Alloy 690 factor of improvement relief requests (e.g. request to reclassify SG nozzle welds to lower inspection frequency)

Path Forward In the near term:

PWSCC initiation data will be used to support the V&V and the NRR review of the xLPR code.

As the CGR program wraps up by early 2019, the test ing will focus on weld dilution, weld defects, we ld repairs, overlays/inlays/onlays, warm/cold work and we ld parameters.

In the long te rm:

PWSCC initiation data will be used to support future updates to the xLP R crack init iation models to reduce the uncertainties associated with heat-to-heat and weld-to-weld variability, and to further define the effects of applied stress, water chemistry, dilution and pre-existing flaws.

PWSCC initiation data will also support SLR by providing data on PWSCC resistant replacement alloys such as Alloy 690/52/152 to inform decisions regarding potential factors of improvement that wi ll be used to determine inspection interva ls. Additionally, PWSCC initiation data can be used to help inform future inspection requireme nts/intervals for Alloy 600/82/182 components in service beyond 60 years.

Next slide please.

IAD Accomplishments and Path Forward

Accomplishments Completed NUREG/CR reports on thermal and irradiation embrittlement of CASS Completed NUREG/CR reports on fracture toughness of thermally aged and irradiated stainless steels Effectively leveraged partnerships with EPRI and international researchers to conduct high-priority --- 41"l ' . "*

irradiated materials testing on high fluence stainless steel materials harvested from Zorita

Path Forward Final results on cooperative Zorita baffle plate and weld materials testing expected in 2018 and 2019 Confirmatory testing of Zorita baffle plate and weld materials at ANL to begin in 2018 Further irradiation of Zorita welds to higher fluence at Halden expected to provide additional data through 2023 Continue technical support on IASCC CGR reference curves, the review of MRP-227, Rev.l, etc.

Page:4 Number: 1 Author: Presenter

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Presentation Notes Date: 2/19/2021 10:50:25 AM IAD Accomp li shments and Path Forward Accomplishments We published severa l NUREG/CRs on thermal and irradiation embrittlement of CASS (NUREG/CR-7184, NUREG/CR-7185 and NUREG/CR-4513 Rev. 2) and on fracture toughness of thermally aged and irradiated stainless steels (NUREG/CR-6960, -7 184, -7185).

Effective leveraging with EPRI and other research organizations has enabled signi ficant research on high fluence stainless steel materials harvested from Zorita which provides highly representative data on baffle plate and weld materia ls to higher fluence levels.

Path Forward Cooperative testi ng with EPRI (and others) of the Zo rita baffle plate and weld materials are expected to be completed in 2018 and 2019, respectively. The scope of this work includes tensile properties, transm ission electron microscope (TEM) to assess void swelling and testing for crack init iation, CGR and fractu re toughness.

Independent confirmatory testing on Zorita baffle plate and weld materials will be performed at ANL beginning in 2018. This will provide further insig hts and clarity on the results from the cooperative testing.

Welds from Zorita at an init ial dose of 2 dpa will be further irradiated at Halden to a fina l dose of 5 and 8 dpa. The 5 dpa specimens are expected to complete irradiation by 2020 and the 8 dpa specimens by 2023.

RES/DE continues to provide technical su pport for regu latory activities related to IAD and, in particular, the review of MRP-227, Rev. 1 and an ASME Code Case on IASCC CGR reference curves.

Next slide please.

Steam Generator Tube Integrity

Overview Objectives:

Assess reliability of NDE methods for in-service inspection

Confirm steam generator tube integrity based on NDE Driver: Significant number of failures in Alloy 600 mill annealed (MA) tubes

- Applications:

Confirm adequacy of industry practices used for ISls

Effects of probe wear on inspection results Collaboration: EPRI, CNSC {Canada), KINS & KAERI (Korea), and IRSN {France)

Ongoing activities

- Validate NDE techniques for the different degradation modes found in service and assess the effects of probe wear on inspection results

- Develop and validate structural models for tube integrity and determi changes to the performance-based tube inspection procedure structural integrity assessments are warrant ed

Page: 5 Number: 1 Author: Presenter

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Presentation Notes Date: 2/19/2021 10:50:26 AM Steam Generator (SG) Tube Integrity

[SKIP]

Background:

We are near the end of the 5th five year program for the integrity of steam generator tubes, SG-TIPS. The program began in response to significant OpE with Alloy 600 mill annealed (MA) tubes, the material used origina lly in all PWRs. Thermally treated (TT) Alloy 600 was introduced in 1980 and is considered to be highly resistant but not immu ne to PWSCC compared to Alloy 600 MA tubes. For the latest 5Gs, Alloy 690 TT is used because it is largely immune to PWSCC, but is stil l susceptible to other degradation mechanisms, mainly wear. The current operating PWRs include 2 SGs with Alloy 600 MA, 17 SGs with Alloy 600 TT and the rema inder with Alloy 690 TT.

There are no Code-required inspect ions for SG tubes. Current inspections are performance -based with plant-specific technical specifications.

Overview:

The SG research program has two objectives:

Assess reliabi lity of NOE methods for in -service inspection (ISi) and Confirm SG tube integrity based on NOE.

Drive r: Significant number of failures in Al loy 600 mill annealed (MA) tubes Applications/ use:

Confirm adequacy of industry practices used for ISls Effects of probe wear on inspection results As shown above, RES/DE is engaged and coordinates with both domestic and international entities through MOU/ IAs to share OpE and research results from independent programs. The current participants are expected to continue for a 6th term.

[SKIP] Our international partners are focused on many of the same issues as the NRC, but some are not currently being addressed in the SG UNR, such as, secondary-side water chemistry and loose parts detection.

On-going activities:

Ongoing activities include:

Validation of NOE techniques for degradation modes found in service, Assessment of the effects of probe wear on inspection results, Development and validation of structural models for tube integrity, and Determine if changes to the performance-based tube inspection procedures and structu ra l integrity assessments are warranted.

[SKIP]

On the NOE side, our main efforts have looked at both flaw detection and sizing with a variety of different probes. The staff is interacting directly with the Steam Generator Task Force which includes EPRI, uti lity representatives and vendors (like Zetec) who perform the inspect ions to improve tube reliability. Additional experimental work is on-going to demonstrate the effect of probe wear on inspection results.

For assessment of integrity, ANL has focused on flaws in the U-bend section of recircu lating SGs. The work includes generating realistic flaws in the laboratory, pressure testing and then analyzing the flaws that could cause leakage and failure of SG tubes in service. Our main interaction w ith EPRI has been on detection of sub-critical flaws.

Next slide please.

SG Tube Integrity Accomplishments and Path Forward

Accomplishments Publication of NUREG/CR-7225 and NUREG/CR-7210 are pending, Two draft reports, one summarizing pressure testing of U-bend tubes and a second assessing the detection of cracking near volumetric indications will be available by the end of 2017

Path Forward Near term:

Close-out structural integrity work at ANL

Focus research on issues related to eddy current detection and auto-analysis techniques that are being widely used by industry for ISi

Revise the SG UNR to reflect the above

-- Long term:

Ensure knowledge transfer through collaboration with international partners

Consider potential research issues for SGs associated with new a advanced reactors.

Page:6 Number: 1 Author: Presenter

Subject:

Presentation Notes Date: 2/19/202 1 10:50:26 AM SG Tube Integrity Accomplishments and Path Forward Accomplishments The publication of two NUREG/CRs on " Stability of Ci rcumferentia l Flaws in Once-Through Steam Generator Tubes under Thermal Loading During LOCA, MSLB, and FWLB" and "Development and Val idation of Models for Predicting Lea kage from Degraded Tube-to-Tubesheet Joints During Severe Accidents" are pending (NUREG/CR-7225 and 7210),

Two draft reports, one summarizing pressure testing of U-bend tubes and a second assessing the detection of cracking near volumetric indications will be available by the end of 2017 Path Forward In th e near term, based on staff assessment and recommendation, no further research is needed to va lidate the empirica l methods used by industry for structural integrity. Thus, we wi ll close-out this work at ANL SG research wil l focus on issues re lated to eddy current detection and auto -ana lysis techniques that are being wide ly used by industry for ISi. The SG UNR will be revised to align with the cha nge in research priorities.

For the long term, we need to ensure knowledge transfer from international partners to remain cognizant of future developments and to further our capab ilities to deal with ongoing degradation of Alloy 600 (both MA and TT). Research needs for the SG tubes proposed for advanced reactors is just beginning to be discussed as the designs and materials are being identified.

Dr. Raj Iyengar wil l present on RPV integrity.

Next slide please.

Subsequent License Renewal

Overview Objective: Coordinate research programs to address technical issues and knowledge gaps for extended reactor operation to 80 years Driver: Support technical bases to make regulatory decisions on applications for SLR Applications:

SLR guidance documents (GALL-SLR, SRP-SLR)

Confirmatory review of SLR applications Collaboration: DOE, EPRI

Ongoing activities 4 key technical issues: 1) RPV embrittlement at high fluence; 2) IAD of RPV internals; 2) concrete and containment degradation, and 4) electrical cable qualification and condition assessment Coordination with DOE and industry counterparts Coordination with international counterparts through multilateral working groups Developing a proactive strategy to evaluate material harvesting opportunities to support materials aging research

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Presentation Notes Date: 2/19/2021 10:50:27 AM SLR Overview:

The subsequent license renewal (SLR) program coordinates research across the Division to address technical issues and knowledge gaps for extend ed reactor operation to 80 years and is aimed at ensuring that we have the necessary technical bases to make regulatory decisions on applications for SLR.

Driver: Support technical bases to make regulatory decisions on applications for SLR Applications/ use:

SLR guidance documents (GALL-SLR, SRP-SLR)

Confirmatory review of SLR applications SLR research is coordinated through domest ic and international research for Long Term Operation (LTO) through MOUs/ IAs with:

DOE's Light Water Reactor Sustainability (LWRS) program EPRl's LTO program, and International collaboration o n SLR-related research topics.

[SKIP] [IFRAM - International Framework on Reactor Aging Management - Network of researchers concerned with materials degradation. As we re-establish this group, we hope to facilitate information exchange and cooperative research with counterpart organizatio ns (although none is specifically planned under IFRAM).]

Ongoing activities:

The 4 key technical issues for SLR were documented in the SRM to SECY- 14-0016:

Reactor pressure vessel (RPV) neutron embrittlement at high fluence IAD / IASCC of RPV internals and primary system components Concrete and containment degradation - due to alkali silica reaction (ASR) and irradiation damage Electrical cable qualification and condition assessment - with focus on degradation of electrical and control cables Cooperative research (with dat a sharing and independent assessment) is ongoing w ith DOE and EPRI.

We have biweekly coordination calls Monthly subject matter expert discussions on concrete and cables research programs, and EPRI/ NRC/ DOE joint roadmap meetings 2-3 times per year to update the tracking of research tasks.

Coordination w it h international counterparts is ongoing through mult ilateral working groups on technical topics including the 4 key technical issues.

[SKIP sub-bullets below]

The IFRAM network was recently re-launched by RES/DE. The current IFRAM Chairman is in Korea.

Participants include China (Chinese Academy of Science), Japan (Tohoku Univ.), Korea (KINS, Seoul Nat'I Univ.), and USA research organizations, includ ing DOE and EPRI There was a side-meeting at the IAEA Plant Life Management (PLiM) Conference, 10/26/2017, to invite additional participants.

IFRAM is independent from, but complementary to, other international organizations, such as IAEA SALTO, CODAP, CADAK, OECD-CSNI, ICG-EAC, Halden Reactor Project (HRP), etc.

In order to improve our understanding of in- service degradation of materials, RES/DE is developing a proactive strategy to evaluate material harvesting opportunities to support materials aging research and to help coordinate efforts to harvest components from reactors entering decommissioning.

A harvesting workshop in spring 2017 addressed factors to consider, prioritization, and lessons learned A poster and presentation were completed for the recent PLiM conference Ongoing work is directed toward developing a database to help prioritize harvesting, so that we can be ready for harvesting opportunities in the future.

Next slide please.

SLR Accomplishments and Path Forward

Accomplishments Held "deep dive" meetings with DOE and EPRI on materials degradation issues NRC published aging management guidance documents with significant RES contributions: NUREG-2191 (GALL-SLR}, NUREG-2192 (SRP-SLR}

Revised guidance on fatigue life in LWRs: NUREG/CR-6909, RG 1.207

Path Forward Near Term:

Support NRR with confirmatory reviews of plant specific gap analyses of treatment of RPV internals for the first SLR applications

Evaluate need to revise Regulatory Guide 1.99 on RPV embrittlement

Test CGR of concrete susceptible to alkali-silica reaction (ASR)

Begin radiation and thermal aging of representative electrical cables Long Term:

Continue to assess properties of RPV internals materials at medium and high fluence

Continue to trend RPV properties through period of extended operation

Determine need for long-term irradiation of concrete specimens

Assess cable condition monitoring techniques

Page:8 Number: 1 Author: Presenter

Subject:

Presentation Notes Date: 2/19/2021 10:50:27 AM SLR Accomplishments and Path Forward Accomplishments:

In 2016, NRC, DOE and EPRI held "deep dive" meetings to share information on materials degradation issues (and sub-issues) identified in the Expanded Materials Degradation Analysis (EMDA). Independent and collaborative research is ongoing to close out most technical sub-issues.

[SKIP] [A few sub-issues were later deemed to be of lower significance and they are not being pursued at this t ime (e.g., very high dose effects, such as void swelling, in stainless steels) - this is not closed out - IF].

The NRC aging management guidance documents for SLR (GALL-SLR and SRP-SLR} were published in July, 2017 with extensive input from RES/

DE staff.

[SKIP sub-bullets below]

Generic Ag ing Lessons Learned (GALL) report was updated for SLR (published as NUREG-2191) GALL-SLR contains generic aging effects to be managed and guidance to applicants on developing robust aging management programs (AMPs)

Standard Review Plan was updated for SLR (published as NUREG-2192). SRP-SLR provides guidance to the staff on reviewi ng SLR applications, including AMPs for operation to 80 years.

The staff and industry briefed the Commission on the status of preparations for SLR reviews on April 26, 2017.

One of the SLR-related sub-issues is quantifying the fatigue life of metals in LWR environments. Fatigue is called out over 100 times in the GALL-SLR and SRP-SLR. The revised guidance documents on fatigue (NUREG/CR-6909, Rev. 1 and Regulatory Guide 1.207) are now in publication:

[SKIP sub-bullets below]

NUREG/CR-6909, Rev. 1, "Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials" Regulatory Guide 1.207, "Guidelines for Evaluating Fatigue Ana lyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors" (DG- 1309)

Path Forward Ongoing research is focused on the four key technical issues and, in particular, on the open sub-issues.

In the near-term:

RES/DE will support NRR with confirmatory reviews of plant specific gap analyses of the treatment of RPV internals for the first SLR applications.

Conti11ue collection of RPV embrittlement daita from industry-led surveillance program to confirm predictive methods.

[SKIP] (Eventually ( ~2019), there may be a need to revise RG 1.99 to reflect longer-term data trends. (CIB))

Test CGR of concrete susceptible to ASR (Jose), and Begin accelerated aging under both gamma radiation and elevated temperature of representative cable samples. Tom Koshy will cover this topic later.

[SKIP sub-bullets below]

Samples will be aged in controlled environments, at Sandia Lab.

Testing of mechanical, chemical, and electrical properties will be done at NIST.

At the same time, industry condit ion monitoring techniques are being assessed.

In the long-term:

RES/DE will continue research on IAD of RPV internals at medium and high fluence levels, Evaluating impacts of IASCC, loss of fracture toughness and void swelling IAD research requires leveraging and long lead-times through ~2023 and beyond Collect RPV embrittlement data through the LR and SLR periods to confirm data trends (CIB), and Continue confirmatory research on concrete degradation including effects of ASR and irrad iation on the structural performance of concrete w ith collaborative research agreements. This topic w ill be covered by Dr. Jose Pires later.

[SKIP sub-bullets below]

ASR tests at NIST, complemented by DOE-funded work at Univ. of Tennessee ASR-susceptible concrete blocks are exposed to elevated temperature & humidity.

ASR testing: non-destructive examinations (NOE), mechanical tests of cracked concrete Irradiation effects assessments are based on reviews of industry reports and information from academic and regu latory counterparts.

A decision will be made by staff sometime in 2018 whether to pursue additional NRC*led testing of irradiated concrete.

Opportunities to harvest irradiated concrete from decommissioned plants will be sought.

If necessary, addit ional specimens may be exposed to controlled irradiation (e.g., in Halden or ATR), then tested.

Next slide please.

Spent Fuel Dry Storage

Overview Diameler

- Objective: Support the development Welded slainless of regulatory guidance for the aging steel canisler ap belween canister and overpack management of spent fuel dry cask Spenl fuel assemblies storage systems (DCSSs)

- Driver: ISFSI license renewal

- Applications:

Aging management regulatory guidance

Confirmatory reviews

- Collaboration: DOE, EPRI

Ongoing activities

- Assess the effectiveness of NDE inspection systems for dry storage canisters (CIB)

- Provide technical support to NMSS in addressing the materials degradation aspects of chloride-induced stress corrosion cracking (CISCC) of stainless steel canisters (CMB

Page: 9 Number: 1 Author: Presenter

Subject:

Presentation Not es Date: 2/19/202 1 10:50:28 AM Spent Fuel Dry Sto rage Overview RES/DE provides support to NMSS/DSFM in t he area of ag ing management of dry st orage systems t hrough a user need RES support in th is area has extended back t o th e extended storage and t ransportation (EST) p rog ram, but has more rece nt ly been focused on techn ical support for ISFSI li cense renewal aging management guidance and CISCC of stainless steel can isters.

Drive r: ISFSI license renewal Applications/ use:

Aging management regulatory guidance Confirmatory reviews Cooperation in t his area is prima ri ly with DOE PNNL and Sa ndia National Laboratory (SNL) as well as t he EPRI Extended Storage Col laboration Prog ram Ongoing Act ivit ies Ongoing activities include:

Assessment of the effectiveness of NOE inspection systems for dry storage can isters - Dr. Raj Iyengar covered this top ic earlier.

Techn ica l sup port t o NMSS on chlo ride -induced st ress co rrosion cracking (CISCC) for assessing the capabilities an d limitations of canist er inspection methods and supporting ASME code activities related to dry sto rage can ist er ag ing management and inspect ion.

Developi ng a crack growth test plan for potentia l future CISCC CGR testing and reviewing t he tec hnical basis for industry CISCC crack growth ana lyses supporting aging management guida nce.

Next slide please.

Spent Fuel Dry Storage Accomplishments and Path Forward

Accomplishments Published NUREG/CR-7170 on CISCC initiation susceptibility Technical letter report on application of NDE techniques to DCSSs Provided the technical basis to support regulatory guidance for ISFSI license renewal in 2017

Path Forward Develop technical basis to evaluate detection and sizing capability of the in-situ NDE methods for the canister geometry Provide technical support to NMSS for ASME code activities related to ISi requirements Develop a crack growth test plan for potential future CISCC CGR testing Produce realistic CISCC in sample plates for NDE evaluation and first-or CGR estimates Supporting NMSS engagement on EPRI consequenc

Page: 10 Number: 1 Author: Presenter

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Presentation Not es Date: 2/19/202 1 10:50:28 AM Spent Fuel Dry Sto rage Accomplishment s and Path Forwa rd Accomplishments In 2014, NRC published the resu lts of expe ri ment al testing to det ermine the at mospheric cond iti ons for sta inless st eel suscept ib ili ty to CISCC in NU REG/CR-7170, which established that CISCC is plaus ible fo r can ister envi ronments In 2016, CIB led the development of a report assessing the appli cation of NDE techn iques, such as visua l testing , ultrasonic testing and eddy current testing for dry st orage can isters In 2017, RES developed the Ag ing Management Tables, which provide the technical basis for NMSS' license renewal aging management regulatory guidance known as the MAPS report. The result s of these tables highl ight t he primary concerns of CISCC of stainless steel can ist ers and inspection methods to detect and mon ito r CISCC.

Path Forwa rd RES/DE act ivities are prima rily th rough a cont ract w ith PNNL t hat is focused on NDE and CISCC.

The primary objectives of th is work include:

Evaluating detect ion and sizing ca pabi lity of t he NOE method s, Providing t echnica l support to NMSS for ASME code activit ies related to ISi requirements for dry storage canist ers, Developi ng a crack growth test plan for potentia l future CISCC CGR t esting, and Producing real istic CISCC in sample plates for NDE evaluat ion and first-order CGR estimates.

RES is also supporting NMSS engagement on the EPRI consequence analysis to assess t he impact of pot ential canist er breaches.

Next slide please.

Additive Manufacturing (AM) of Reactor Components

Overview

- Objective: Anticipatory research to allow NRC to be ready to assess adequacy of AM parts in NPPs - AM appllications expected in 2018

- Driver/Applications: Provide critical 'jump-start' to ascertain NRC is ready for industry requests including direct metal laser melting (DMLM/AM).

New NRO Research Assistance Request (RAR) to be followed by NRR/NRO UNR

- Collaboration: DOE, ANSI, EPRI, NIST, ASTM, NASA, DOD

Ongoing activities

- Engaging early with potential vendors to understand fabrication processes and material performance issues

- Assessing the technical state-of-the art

- Participating in consensus standards development

Page: 11 Number: 1 Author: Presenter

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Presentation Notes Date: 2/19/2021 10:50:28 AM Additive Manufacturing (AM) of Reactor Components

[The figure is from June 2017 EPRI Journal and symbolizes the process for nuclear applications.]

[SKIP] Background NRO/Division of Construction Inspection and Operational Programs (DCIP) had technical discussions with RES/DE/CMB staff following the June 7, 2017 3-hr public meeting with GE- Hitachi to discuss "general aspects of additive manufacturing" with the GEH focus on direct metal laser melting (DMLM) which is a type of powder bed fusion (PBF). A few weeks later, the RES Office Director identified the long-term performance in licensed facilities of AM components as being an area for anticipatory research. This is newly-emerging Category Ill research, provided seed fund ing from NRO/DCIP via NRO RAR-2017 -008, forma lly started on Oct 19. The scope of this RAR is focused on the DMLM method and has the following focus.

Working with NRR/DE and NRO/Division of Engineering and Infrastructure to Develop Follow-on UNR Engaging ea rly with potential vendors and other government agencies (such as DOE, NIST, DOD, FAA, NASA) to understand fabrication processes and material performance issues Participating in consensus standards development Assessing the technical state-of-the art Overview Anticipatory research on Additive Manufacturing (AM) of reactor components will allow the NRC to be ready to assess adequacy of AM parts in NPPs - applications expected in 2018 Driver/ Applicat ion: Provide critica l 'jump-start' to ascertain NRC is ready for industry requests includ ing direct metal laser melt ing (DMLM/AM). A new NRO Research Assistance Request to be followed by an NRR/NRO UNR.

Collaboration planned with DOE, ANSI, EPRI, NIST, ASTM, NASA and DOD Ongoing Activit ies Ongoing activities include:

NRO/DCIP and RES/DE engaging early with potential vendors to understand fabrication processes and material performance issues, Assessing the technical state -of-the art, and Participating in consensus standards development.

[SKIP bu llets below]

[Identifying initial nuclear appl ications Addressing possible nuclear- relat ed technical and regu latory gaps Reviewing qua lity assurance (QA) provisions for this process]

Next sl ide please.

AM of Reactor Components Accomplishments and Path Forward

Accomplishments

- Formed an NRC working group chartered with developing an agency plan to address AM

- Aligned with NRO on scope of initial work to begin to assess QA issues and technical gaps

- Attended and gave presentation at ANSI Additive Manufacturing Standardization Collaborative (AMSC) Workshop

- Coordinated NRR/NRO/RES visit to Westinghouse Churchill Facility to review AM properties, irradiation testing and tentative plans for component manufacturing

Path Forward

- Host public meeting for NRC/lndustry Additive Manufacturing Technical Information Exchange on November 28-29, 2017

- White Paper or Technical Letter Report on "Eva I uation of Additively Manufactured Reactor Parts by Direct Metal Laser Melting" to be completed by March 2018

- Develop NRR/NRO UNR as stipulated in the NRO RAR for AM

- Participate in ANSI effort to develop joint national roadmap to coordinate and facilitate development of harmonized set of AM standards

- Develop agency plan to address AM

Page: 12 Number: 1 Author: Presenter

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Presentation Notes Date: 2/19/202 1 10:50:29 AM AM Accomp lishment s and Pat Forward Accomplishments Wo rking across offices, RES/D E has formed a coord inat ing group chartered to develop an agency plan to address how to evaluate t he adequacy of AM parts in NPPs. AM applicatio ns and topical reports are expected as ea rly as 2018. We are beg inning to discuss what types of gui da nce documents will be useful. Bui lding on the foundation of wo rk done by other government agencies we are coord inating with the ANSI AM Standa rds Committee (AMS() which has developed an excellent standardization roa dmap for AM . Both WEC and GEH are focused on Powder Bed Fusion, so we led a visit to t he Westing house facility near Monroevi lle, PA.

Path Forwa rd In t he near-term we wil l host a public meeting for NRC/lndust ry Add itive Manufact uring Technica l Information Exchange next month where industry and other agencies will help bring us up to speed on the state-of-the-art. We are also coordinating NRC visit s to the AM faci lit ies at NIST and at t he GEH Advanced Manufacturing Works in Greenville, South Carolina. The fi ndings from the NRO RAR will be completed in Ma rch 2018 to be fo llowed by an NRR/NRO UNR on AM.

In t he longer-term we pla n to participate in ASTM (F42) and ANSI efforts to develop harmonized AM standards, and we wil l be act ively involved in develo ping the agency plan to address AM , such as writ ing guidance documents or regulatory guides to support t he regulatory framework fo r the review of AM applicat ions.

Dr. Raj Iyengar will present on Adva nced Non-light Water Reactors Materia ls.

Next slide please.

Subject:

Update on Harvesting Program Location: T1 0E16 Note to requester:

Attachment is Start: Tue 12/12/2017 8:00 AM immediately following.

End: Tue 12/12/2017 9:00 AM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesFran kl, Istvan; Thomas, Brian; Regan, Christopher; Tregoning, Robert; Audrain, Margaret; Purtscher, Patrick 1, I I I ' j 11 1' r l j 1

1 ) I I I I ' I } : ..

Ex-Plant Materials Harvesting Update M otivat ion and Objective:

Ex-plant materials are valuable for confirmatory testing because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.)

o Generally, research involves accelerated, simulated aging conditions in a lab which may not be as representative of actual in-service aging o Highly representative materials (actual plant components) and aging conditions reduces the uncertainty associated with the applicability of research findings.

With plants shutting down both in the U.S. and Europe, there are increasing opportunities to harvest components from decommissioning plants.

Insights from ex-plant harvesting would support regulatory decisions for subsequent license renewal (SLR), and could have implications for the current license period o There is a task in the new UNR for SLR from NRR/DLR requesting RES to investigate opportunities for harvesting where appropriate.

Requests RES to develop a database to prioritize needs best addressed by harvesting and develop a process to evaluate the suitability of materials available for harvesting Past Activities:

Workshop in March 2017 o NRC staff hosted a 2-day workshop with interested stakeholders, including domestic and international utilities and research organizations, to discuss benefits and challenges associated with ex-plant harvesting.

o Sessions covered motivation for harvesting, data ineeds, sources of materials, lessons learned, the practical aspects of harvesting, and harvesting decision-making and planning o The discussion focused on the importance of clearly identifying the need and purpose for performing a harvesting project. All participants agreed harvesting is a complex and expensive proposition, but one that can be worthwhile if the need is clearly defined and addressed.

PNNL Report on Harvesting Criteria o PNNL has produced a draft final report for NRC on criteria for harvesting decision-making and planning o Provides overview of past harvesting efforts and lessons learned as well as suggestions for approach to prioritize data needs for harvesting

PLiM o NRC staff provided a presentation, poster, and pa per for the recent conference in October 2017.

Path Forward:

Focused on two parallel efforts:

o Developing alignment within NRC on prioritization of harvesting data needs Use criteria identified in PNNL report to establish effective prioritization scheme for relevant areas: RPV, RPV internals and other metals, electrical components, concrete o Developing a database identifying sources of materials for harvesting as requested in UNR Start with lab-based "boneyards" of prior harvested materials

"Low-hanging fruit" opportunities before tackling more challenging prospect of decommissioning plants

Visits to ANL, PNNL, and ORNL (leveraged with already planned travel) support this activity Coordinate with DOE NSUF Nuclear Fuel and Materials Library (NFM L) run by INL as appropriate and beneficial to leverage limited NRC resources

Subject:

Update on Harvesting Program Location: T1 0E16 Start: Tue 12/12/2017 9:00 AM End: Tue 12/12/2017 10:00 AM Note to requester:

Show Time As: Tentative Attachment is immediately following.

Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesFran kl, Istvan; Thomas, Brian; Regan, Christopher; Tregoning, Robert; Audrain, Margaret; Purtscher, Patrick 1, I I I ' j 11 1' r l j 1

1 ) I I I I ' I } : ..

Ex-Plant Materials Harvesting Update M otivat ion and Objective:

Ex-plant materials are valuable for confirmatory testing because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.)

o Generally, research involves accelerated, simulated aging conditions in a lab which may not be as representative of actual in-service aging o Highly representative materials (actual plant components) and aging conditions reduces the uncertainty associated with the applicability of research findings.

With plants shutting down both in the U.S. and Europe, there are increasing opportunities to harvest components from decommissioning plants.

Insights from ex-plant harvesting would support regulatory decisions for subsequent license renewal (SLR), and could have implications for the current license period o There is a task in the new UNR for SLR from NRR/DLR requesting RES to investigate opportunities for harvesting where appropriate.

Requests RES to develop a database to prioritize needs best addressed by harvesting and develop a process to evaluate the suitability of materials available for harvesting Past Activities:

Workshop in March 2017 o NRC staff hosted a 2-day workshop with interested stakeholders, including domestic and international utilities and research organizations, to discuss benefits and challenges associated with ex-plant harvesting.

o Sessions covered motivation for harvesting, data ineeds, sources of materials, lessons learned, the practical aspects of harvesting, and harvesting decision-making and planning o The discussion focused on the importance of clearly identifying the need and purpose for performing a harvesting project. All participants agreed harvesting is a complex and expensive proposition, but one that can be worthwhile if the need is clearly defined and addressed.

PNNL Report on Harvesting Criteria o PNNL has produced a draft final report for NRC on criteria for harvesting decision-making and planning o Provides overview of past harvesting efforts and lessons learned as well as suggestions for approach to prioritize data needs for harvesting

PLiM o NRC staff provided a presentation, poster, and pa per for the recent conference in October 2017.

Path Forward:

Focused on two parallel efforts:

o Developing alignment within NRC on prioritization of harvesting data needs Use criteria identified in PNNL report to establish effective prioritization scheme for relevant areas: RPV, RPV internals and other metals, electrical components, concrete o Developing a database identifying sources of materials for harvesting as requested in UNR Start with lab-based "boneyards" of prior harvested materials

"Low-hanging fruit" opportunities before tackling more challenging prospect of decommissioning plants

Visits to ANL, PNNL, and ORNL (leveraged with already planned travel) support this activity Coordinate with DOE NSUF Nuclear Fuel and Materials Library (NFM L) run by INL as appropriate and beneficial to leverage limited NRC resources

From: Tregoning, Robert Sent: Wednesday, March 15, 2017 2:01 PM To: 011 iVilhelm.N EVAN DER@oecd.org

Subject:

WG IAGE agenda Olli:

I know it's late but I'd like to add an item to the subgroup agenda to discuss the US material harvesting activities. I only need about 15 minutes but if we could allot 30 minutes, that should be more than enough

Thanks, Rob

From: Hull, Amy Sent: Fri, 15 M ay 2015 07:44:09 -0400 To: Tregoning, Robert Cc: Hiser, Matthew;Frankl, Istvan

Subject:

title and t ime: June materials meeting Strategic Approach for Obtaining Material and Component Aging Information Amy Hull & Matt Hiser 30 minutes, Matt will talk 15 minutes about current approach to (and results from) ex-plant harvesting and then I will talk 15 about where we are going From: Tregoning, Robert Sent: Thursday, May 14, 2015 3:43 PM To: Hull, Amy

Subject:

June materials meeting Amy:

I just need a title and an allotted time for your Ex-plant Material Database presentation for the June meeting. Can you send me something either today or early tomorrow?

Thanks so much, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 21 Church Street, M/5 CS-5A24 Rockville, MD 20850 ph: 301-251-7662 (b)(6) ... JUackberry: 1-fax: 301-251-7425

Note to requester: Attachment is immediately fo llowing.

From: Hiser, Matthew Sent: Mon, 22 May 2017 18:47 :00 +0000 To: Hull, Amy;Tregoning, Robert;Purtscher, Patrick;Moyer, Carol Cc: Frankl, Istvan

Subject:

Synopsis on Harvesting for IAEA PLiM Attachments: Harvesting IAEA Plim 2 page synopsis.docx I have attached a draft 2 page synopsis on harvesting for the IAEA PLiM conference. The plan will be for Carol to give the 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 support submission this week.

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: 301-415-24541 Office: TWFN 10D62 Matthew .Hiser@nre.gov

Harvesting of Aged M at erials from Operating and Decommissioning Nuclear Power Plants Matthew Hiser, Patrick Purtscher, Pradeep Ramuhalli, Amy Hull, Robert Tregoning, and Carol Moyer In the U.S. and global nuclear industry, two recent developments include strong interest in extended plant operation and a number of nuclear power plants (NPPs) shutting down. In t he 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 research to understand aging mechanisms. U.S. utilities and the NRC have focused on aging in four key areas: the reactor pressure vessel (RPV), RPV internals and piping, concrete, and electrical components.

Meanwhi le, in recent years, a number of nuclear plants, both in the U.S. and int ernationally, have shut down or announced plans to shut down. Unlike in t he past when t here were very few plants shutting down, these new developments provide opportunities for harvesting components that were aged in representative light water reactor (LWR) environments. In a related development, economic challenges for the nuclear industry and limited budgets have restricted the resources available to support new resea rch, including harvesting programs. Given this constrained budget environment, aligning interests and leveraging with other organizations is important to allow maximum benefit and value for future resea rch programs.

NRC has recently undertaken an effort, with the assistance of Pacific Northwest National Lab (PNNL), to develop a strategic approach t o harvesting of aged materials frnm NPPs. Due to limited opportunities, past harvesting efforts have been reactive to individual plants shutting down and beginning decommissioning. Given the expected availability of materials from numerous plants, 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 t hose high-priorit y data needs.

The first step in this strategic approach t o harvesting is to prioritize data needs for harvesting. A data need describes a particu lar material-environment combination and should be defined as detailed as appropriate in terms of the material (alloy, composition, etc.) and environment (temperature, fluence, chemistry, etc.). A number of criteria may be considered when prioritizing data needs for harvesting, including:

Applicability of harvested mat erial for addressing critical gaps o Prioritize harvesting for critical gaps over less essential data needs.

Ease of laboratory replication of the environment-material combination o For example, simultaneous thermal and irradiation conditions may be difficult t o replicate or a m echanism 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 (fabrication methods, composition, etc.) that may no longer be available.

Fleet-wide vs. plant-specific applicability of data

o There is generally greater value in addressing an issue applicable to a larger number of plants.

Avai lability of reliable in-service inspection (ISi) techniques for the material/ component o If inspection methods are mature and easy to apply to monitor and track degradation, perhaps the effort of research with harvested materials is not needed.

Availability of material for harvesting o The necessary materials/ components must be available to be harvested.

Harvesting cost and complexity o For example, harvesting unirradiated concrete or electrical cables should be less expensive and less complex than harvesting from the reactor 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 consider 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, which could include both previously harvested mat erials 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 databa1se 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 can yield highly representative and valuable data on materials aging, but these efforts may be expensive and challenging. Having a clearly defined objective and early engagement with the plant from which harvesting will take place are keys to success. As specific harvesting opportunities are identified through this strategic approach to harvesting, NRC wellcomes opportunities for cooperation and leveraging with other interested research organizations.

From: Hull, Amy Sent: Fri, 7 Aug 2015 09:28:10 -0400 To: Prokofiev, louri; Hiser, Matthew;Frankl, Istvan

Subject:

taking w ith us and using citrix in Britain : Request for Evaluation of RFP No. NRC-HQ-60-15-T-0023 The link is G:\DE\CMB\Hull\Strateqic R&D database ex-plant materials\Auq2015 evaluation From: Turner, Michael Sent: Thursday, August 06, 2015 8:17 PM To: Hull, Amy; Hiser, Matthew

Subject:

Request for Evaluation of RFP No. NRC-HQ-60-15-T-0023

Amy, Attached for your evaluation is a copy of the proposal submitted by the Pacific Northwest National Laboratory (PNNL) in response to the subject Request for Proposal. Please review the proposal and provide your written evaluation to me NL T August 17, 2015 .

If I can be of any assistance during your evaluation, please call me on (301) 415-6712.

Regards, Michael Turner, Contracting Officer U. S. Nuclear Regulatory Commission Acquisition Management Division Technical Acquisition Branch , IAA Team Mai l Stop: TWFN 5E03 Washington, DC 20555 Phone No.: (301) 415-6712 E-mail address: michael.turner@nrc.gov

Subject:

Strategic Harvesting for Active Components Location: Matt will call 301 -251-7600 Start: Fri 5/8/2015 1:30 PM End: Fri 5/8/2015 2:00 PM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesKanney, Joseph Sounds good!

Subject:

Strategic Harvesting Project Location: T1 0D40 Start: Wed 5/18/20161:00 PM End: Wed 5/18/2016 2:00 PM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesFran kl, Istvan; Purtscher, Patrick; Tregoning, Robert; Hull, Amy Reschedu led to allow Amy to participate if possible.

Subject:

Strategic Harvesting Project Location: 10th floor huddle room Sta rt: Wed 5/18/201610:00 AM End: Wed 5/18/2016 11 :00 AM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesFran kl, Istvan; Purtscher, Patrick; Tregoning, Robert; Hull, Amy

._________..,,...a.-----------' let's try to reschedule for Wednesday .

(b)(6) ./

From: Hiser, Matthew Sent: Tue, 26 Apr 2016 19:53 :01 +0000 To: Iyengar, Raj

Subject:

Strategic Harvesting Project Hi Raj ,

Here is my input:

RES is working to develop a strategic approach to ex-plant material harvesting to support SLR research . The goal of this project is to take advantage of the increasing number of plants decommissioning by harvesting materials and components that may be valuable to address research gaps. Harvesting projects from both decommissioning and operating plants have been performed previously and provided valuable information, but there has never been a systematic assessment of when and how to optimally use harvested materials for research .

This effort is focused in two complementary areas: identifying research gaps for SLR that may be best addressed by harvesting and identifying what harvesting opportunities will be available .

The results of this initial assessment will be published in a harvesting plan as a technical letter report in early 2017. This plan will help identify high-priority harvesting opportunities that may be pursued with follow-on activities. The success of this effort is dependent on increased engagement particularly with industry groups such as EPRI to facilitate information gathering regarding what materials may be available from both decommissioning and operating plants.

Thanks!

Matt Matthew Hiser Materials Engineer US uclear Regulatory Commission I Office of uclear Regulatory Research Di vision of Engi neering I Corrosion and Metallurgy Branch Phone: 30 1-4 15-2454 I Office: TWFN 10D62 Matthew.Hiser@nrc.gov

Subject:

Strategic Harvesting Project Location: Steve's office Start: Tue 5/24/2016 9:00 AM End: Tue 5/24/2016 10:00 AM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesFran kl, Istvan; Purtscher, Patrick; Tregoning, Robert; Hull, Amy Just spoke with Amy and Pat, w e all agreed to push to next w eek so everyone can participat e (Amy cannot do today). I will send out an updat e on the status of the work at PNNL in advance of this meeting.

Purpose

Determine staff roles in harvesting project

Discuss path forward for harvesting project UPDATE - Current St atus

PNNL is working on developing a harvesting plan as well as analyzing harvesting needs for a few example degradation mechanisms: PWSCC, CASS, cable aging o This Task 1 deliverable should be finalized by early 2017

Matt reached out to the decommissioning BC in NMSS for info on planned decommission ing schedules o Response was that besides Zion, most plants are not planning to decommission for a long time

Next step should probably be a public workshop to bring in external stakeholders/partners to discuss a strat egic approach to harvesting:

o DOE, EPRI, utilities, international

Subject:

Strategic Harvesting Location: T1 0D40 Start: Thu 2/18/2016 9:00 AM End: Thu 2/18/2016 10:00 AM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesObodoako, Aloysius; Tregoning, Robert; Hull, Amy Push to next week I

Note to requester: The FOIA staff received this email in its original format Outlook. The attached file is blocked from users , and was not provided to the FOIA staff.

From: Hull, Amy Sent: Mon, 1 Jun 2015 07 :34:39 -0400 To: Hiser, Matthew

Subject:

source doc for DOE slide: Harvesting Efforts June NRC-lndustry materials mtg 5-28-15 mah.abh.pptx Attachments: NESCC 15-011 - J. Busby Presentation on LWRS MAaD.pdf- Shortcut.Ink Matt, I 'snipped' slide 13 of the attached pdf. I could not figure out how to clean it up. Are you able to?

From: Hiser, Matthew Sent: Friday, May 29, 2015 9:39 AM To: Hull, Amy; Frankl, Istvan Cc: Tregoning, Robert

Subject:

RE: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx Hi Rob, Steve, Amy, I have made the changes in accordance with Kathy's comments as relayed by Steve in the attached PP . One final tweak Amy and I will try to make on Monday is to Slide 15 - if we can clean up the source slide from DOE , just so the information comes through clearly.

Thanks!

Matt From: Hull, Amy Sent: Thursday, May 28, 2015 10:03 AM To: Frankl, Istvan Cc: Tregoning, Robert; Hiser, Matthew

Subject:

Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx We have made changes suggested. I will drop the 390 form off for you now.

From: Hull, Amy Sent: Thu, 28 May 2015 12:51:59 -0400 To: Tregoning, Robert;Frankl, Istvan Cc: Hiser, Matthew

Subject:

Steve gave 390 form to Kathryn to sigin off on ... : Harvesting Efforts June NRC-lndustry materials mtg 5-28-15 mah.abh.pptx

.. . so it is pretty close to being final version.

From: Tregoning, Robert Sent: Thursday, May 28, 2015 10:21 AM To: Hull, Amy; Frankl, Istvan Cc: Hiser, Matthew

Subject:

RE: Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx All :

Please just let me know when this is final so that I can send it to NRR for placing in ADAMS.

Thanks, Rob Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 21 Church Street, M/S CS-5A24 Rockville, MD 20850 ph: 301-251-7662 (b)(6) Blc:u;kbe.r.r.y: 1-

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

fax: 301-251-7425 From: Hull, Amy Sent: Thursday, May 28, 2015 10:03 AM To: Frankl, I stvan Cc: Tregoning, Robert; Hiser, Matthew

Subject:

Harvesting Efforts June NRC-Industry materials mtg 5-28-15 mah.abh.pptx We have made changes suggested. I will drop the 390 form off for you now.

Subject:

Strategic Harvesting Location: T1 0D40 Start: Wed 2/10/2016 3:00 PM End: Wed 2/10/2016 4:00 PM Show Time As: Tentative Recurrence: (none)

Meeting Status: Not yet responded Organizer: Hiser, Matthew Required AttendeesObodoako, Aloysius; Tregoning, Robert; Hull, Amy Reschedule for snow.

Note to requester: Attachment is immediately fo llowing.

From: Hiser, Matthew Sent: Thu, 3 Nov 2016 14:48:06 +0000 To: Purtscher, Patrick;Tregoning, Robert ;Frankl, Ist van

Subject:

Slide for DLR Quarterl y Next Week Attachments: DLR-RES Quart erly Meeting November 2016 Harvesting.pptx Hi Steve, Rob, and Pat, I have put together this slide on the ex-plant harvesting activities for the DLR quarterly next week. Please review and provide any feedback .

Thanks!

Matt Matthew Hiser Materials Engineer US uclear Regulatory Commission I Office of uclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 l-4 15-2454 I Office: TWFN I 0D62 Matthew.Hiser@nrc.gov

~ U.S.NRC Ex-Plant Harvesting United States Nuclear Regulatory Commission Protecting People and the Environment

Two primary activities:

Contract with PNNL to develop strategic approach to harvesting

Deliverable in early 2017 will identify key factors to consider for harvesting and analyze those factors for some potential harvesting scenarios

- Cables, high-fluence internals, CASS, dissimilar metal welds

Approach can then be applied by NRC staff to other harvesting options Ex-Plant Materials Harvesting Workshop

Planned for March 7-8, 2016 at N RC HQ

Expect domestic and international participation

- Researchers, regulators, utilities, and decommissioning companies

Developing agenda and contacting presenters/participants

Task on harvesting expected in SLR UNR 1

From: Hiser, Allen Sent: Thu, 1 Mar 2018 20 :58:01 +0000 To: Hull, Amy;Moyer, Carol;Hiser, Matthew Cc: Frankl, lstvan;Rudland, David;Ruffin, Steve

Subject:

RIC Harvesting Poster Importance: High Can I get a copy of the RIC harvesting poster?

Thanks ,

Allen

Note to requester: Attachment is immediately following.

From: Moyer, Carol Sent: Wed, 31 Jan 2018 22 :20 :20 +0000 To: GRAPHICS Resource Cc: RICMST Resource;Frank l, lstvan;Hull, Amy;Hiser, Matthew

Subject:

RIC post er (Harvesting) for optical review Please review the attached ePoster file , and return your comments to me at Carol .Moyer@nrc.gov.

Thank you, Carol Carol E. Moyer Sr. Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research MS: T-10A36 Washington, DC 20555-0001 carol. moyer@nrc.gov 301-415-2153

Harvesting of Aged au.s.Materials from Nuclear Power Plants M. Hisera, P. Purtschera, P. Ramuhallib, A.B. Hulla, and R. Tregoninga; Nuclear Regulatory Commission (NRG), bPacific Northwest National Laboratory Background and Motivation Potential Criteria for Harvesting Prioritization Harvesting Database Recent developments in the nuclear industry include stronger interest in extended A number of criteria may be considered when prioritizing the data needs for The NRC is pursuing the development of a database for sources of materials for plant operation and plans to shut down a number of nuclear power plants (NPPs). In harvesting, including the following: harvesting, which could include both previously harvested materials and those the United States, there isstrong interest in extending NPP lifespans through

Applicability of harvested material for addressing critical gaps available for future harvesting. This database would allow for aligning high-priority subsequent license renewal (SLR) from 60 to 80 years. _ Harvesting for critical gaps is prioritized over less essential technical gaps. data needs to the available sources of materials. The level of detail for the database Extended plant operation and SLR raise a number of technical issues that may should be appropriate for the factors influencing decisionmaking. The NRC is

Ease of laboratory replication of the degradation scenario interested in engaging with other organizations in developing the database.

require further research to understand and quantify ag ing mechanisms. U.S. utilities and the U.S. Nuclear Regulatory Commission (NRC) have focused on the aging of _ For example, simultaneous thermal and irradiation conditions are difficult to systems, structures, and components and in particular four key SLR issues: reactor replicate, and accelerated aging may not be feasible for a mechanism Path Forward pressure vessel embrittlement, irradiation-assisted stress-corrosion cracking of reactor sensitive to dose rate.

internals, concrete structures and containment degradation, and electrical cable

Unique field aspects of degradation In the NRC'sexperience, harvesting can yield highly representative and valuable data qualification and condition assessment. _ For example, unusual operating experience or legacy material (fabrication on materials aging, but these efforts will be challenging. Having a clearly defined Meanwhile, in recent years, a number of NPPs, both in the United States and methods, etc.) is no longer available. objective and early engagement with other stakeholders are keys to success. As internationally, have shut down or announced plans to shut down for various

Fleet-wide vs. plant-specific applicability of data specific harvesting opportunities are identified through thisstrategic approach, the reasons, including economic, political, and technical challenges. Unlike in the past _ There is greater value in addressing an issue applicable to a larger number of NRC welcomes opportunities for cooperation and leveraging of resources with other when there were very few plants shutting down, these new developments provide plants. interested research organizations.

opportunities for harvesting components that were aged in representative

Harvesting cost and complexity light-water reactor environments. Plate A (41 .22" wide)

_ For example, harvesting In a third related development, economic challenges and limited budgets have unirradiated concrete or electrical restricted the resources available to support new research, including harvesting cables is less expensive and less programs. Given this constrained budget environment, aligning interests and complex than harvesting from the leveraging with other organizations is important to allow maximum benefit and value reactor internals or reactor for future research programs. Plate C (7.8" wide) pressure vessel.

Availability of reliable inservice Current Activities inspection (ISi) techniques for the material/component The NRC has recently undertaken an effort, with the assistance of Pacific Northwest

_ If mature inspection methods exist National Laboratory, to develop a strateg ic approach to harvesting aged materials and are easy to apply, harvesting from NPPs. Because of limited opportunities, past harvesting efforts have been may be less valuable.

reactive to individual plants shutting down and beginning decommissioning. Given the expected availability of materials from numerous plants and anticipated

Availability of materials for harvesting research needs to better understand ag ing out to 80 years of operation, the NRC is

Timeliness of the expected research pursuing a more proactive approach to prioritize the data needs best addressed by results relative to the objective.

harvesting and identify the best sources of materials to address high-priority data needs for regulatory research.

The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario and should be defined with as much detail as appropriate in terms of the material (alloy, composition, etc.) and environment (temperature, fluence, chemistry, etc.). Lifting operation for irradiated Example of reactor internals harvesting plan materials transport cask

Note to requester: The attachments are immediately following .

From: Moyer, Carol Sent: Tue, 13 Feb 2018 20:33 :37 +0000 To: RICMST Resource Cc: Frankl, lstvan;Hull, Amy;H iser, Matthew;Oberson, Greg;Warren, Brenett

Subject:

RIC ePosters 6 & 8, approved by Graphics The attached ePosters have been reviewed and approved by RES/DE, by QTE, and by Graphics.

RIC Poster 6 on AM_20180213.pptx RIC Poster 8 on Harvesting_20180213.pptx Please contact me if you need any additional information. Otherwise, please forward these to the RTC Contractor.

Thank you, Carol Carol E. Moyer Sr. Materials Engineer Office of uclear Regulatory Research RES/DE/CMB carol.moyer@nrc.gov 301-415-2153

Review of Additive Manufacturing by Direct Metal Laser Melting A. Hull, T. Herrity, and C. Moyer, U.S. Nuclear Regulatory Commission (NRC)

Background and Motivation Current Activities Path Forward The NRC has been informed that parts created by additive manufacturing (AM) The NRC is developing a strategic plan to address the use of additive AM has been identified as a technique that the nuclear industry may use in the are being considered for applications in the operating fleet as early as calendar manufacturing for reactor materials and components. The NRC plans to leverage future. Prevailing questions are: How will AM be used in nuclear power plants, and year 2018. In 2017, industry prototyping efforts involved use of the direct metal ongoing research and evaluation of this technology being pertormed by Federal when? What is the regulatory infrastructure for determining how safe it is?

laser melting (DMLM) method to manufacture parts for reactor components. The counterparts.

Office of Nuclear Regulatory Research is beginning to evaluate the technology to NRC areas of interest include the quality, properties, and structural performance of gain insight into any technical issues that must be addressed to assure safety and The NRC strategic plan will focus on topic areas of interest identified at the AM parts, including their inspectability. The service pertormance and aging reliability of specific DMLM-produced components that may be accepted by the Additive Manufacturing for Reactor Materials and Components public meeting: degradation of AM parts are critical. It will be essential to compare the NRC, including design, precursor materials, finished material properties, structural performance of parts from AM and those from conventional manufacturing integrity, nondestructive evaluation, and quality assurance. This welding-based processes.

process may be susceptible to, for example, porosity, systematic defects, and Quality of AM materials and components for nuclear power plants anisotropy of properties not currently addressed for conventionally manufactured Codes and standards development for AM components. Properties and structural performance Challenges to be addressed include the limited understanding of acceptable ranges of variation for key manufacturing parameters, limited understanding of key Service performance/aging degradation failure mechanisms and material anomalies, the potential for systematic defects, On November 28-29, 2017, the NRC held a public meeting entitled, "Additive Regulatory infrastructure cybersecurity considerations, lack of industry databases, and lack of industry Manufacturing for Reactor Materials and Components." Presentations from specifications and standards. The development of codes and standards for AM is 28 speakers representing American and international industry, EPRI, NEI, DoD key to successful implementation.

facilities, DOE and National Laboratories, ASME, ASTM, ANSI, FAA, NASA, and NIST are available in ADAMS (Accession No. ML17338A880).

lntematk>Ml ASTM Organization '"'"'""

Societyof International Mechanical Standardization Engineers IEE~ -:*"*

SAE International American Wei.ding Society Institute of Electrical and v'l**""' ..

£lectronl~E0ilnee11 IP(-

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Associationfor the Advaocemeot of~tcal AAM':,ll E!ectroolcs~

Instrumentation lndustri~

MetalPo\'.00-100ustr1es Fol,.-.Uoo m

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. . AmericaMakes ~ --

DMLM Process Demonstration Specimen at GE Power Advanced Westinghouse sDMLM Examples: Thimble Plugging Device, Advanced Standards Development Organizations Involved with AM Manufacturing Works, Greenville, SC, C. Moyer, December 11, 2017. Debris Filtering Bottom Nozzle, B. Cleary, November 28, 2017. Standardization, J. McCabe, November 29, 2017

Harvesting of Aged au.s.Materials from Nuclear Power Plants M. Hisera, P. Purtschera, P. Ramuhallib, A.B. Hulla, and R. Tregoninga; Nuclear Regulatory Commission (NRG), bPacific Northwest National Laboratory Background and Motivation Potential Criteria for Harvesting Prioritization Harvesting Database Recent developments in the nuclear industry include stronger interest in extended A number of criteria may be considered when prioritizing the data needs for The NRC is pursuing the development of a database for sources of materials for plant operation and plans to shut down a number of nuclear power plants (NPPs). In harvesting, including the following: harvesting, which could include both previously harvested materials and those the United States, there isstrong interest in extending NPP lifespans through

Applicability of harvested material for addressing critical gaps available for future harvesting. This database would allow for aligning high-priority subsequent license renewal (SLR) from 60 to 80 years. _ Harvesting for critical gaps is prioritized over less essential technical gaps. data needs to the available sources of materials. The level of detail for the database Extended plant operation and SLR raise a number of technical issues that may should be appropriate for the factors influencing decisionmaking. The NRC is

Ease of laboratory replication of the degradation scenario interested in engaging with other organizations in developing the database.

require further research to understand and quantify ag ing mechanisms. U.S. utilities and the U.S. Nuclear Regulatory Commission (NRC) have focused on the aging of _ For example, simultaneous thermal and irradiation conditions are difficult to systems, structures, and components and in particular four key SLR issues: reactor replicate, and accelerated aging may not be feasible for a mechanism Path Forward pressure vessel embrittlement, irradiation-assisted stress-corrosion cracking of reactor sensitive to dose rate.

internals, concrete structures and containment degradation, and electrical cable

Unique field aspects of degradation In the NRC'sexperience, harvesting can yield highly representative and valuable data qualification and condition assessment. _ For example, unusual operating experience or legacy material (fabrication on materials aging, but these efforts will be challenging. Having a clearly defined Meanwhile, in recent years, a number of NPPs, both in the United States and methods, etc.) is no longer available. objective and early engagement with other stakeholders are keys to success. As internationally, have shut down or announced plans to shut down for various

Fleet-wide vs. plant-specific applicability of data specific harvesting opportunities are identified through thisstrategic approach, the reasons, including economic, political, and technical challenges. Unlike in the past _ There is greater value in addressing an issue applicable to a larger number of NRC welcomes opportunities for cooperation and leveraging of resources with other when there were very few plants shutting down, these new developments provide plants. interested research organizations.

opportunities for harvesting components that were aged in representative

Harvesting cost and complexity light-water reactor environments. Plate A (41 .22" wide)

_ For example, harvesting In a third related development, economic challenges and limited budgets have unirradiated concrete or electrical restricted the resources available to support new research, including harvesting cables is less expensive and less programs. Given this constrained budget environment, aligning interests and complex than harvesting from the leveraging with other organizations is important to allow maximum benefit and value reactor internals or reactor for future research programs. Plate C (7.8" wide) pressure vessel.

Availability of reliable inservice Current Activities inspection (ISi) techniques for the material/component The NRC has recently undertaken an effort, with the assistance of Pacific Northwest

_ If mature inspection methods exist National Laboratory, to develop a strateg ic approach to harvesting aged materials and are easy to apply, harvesting from NPPs. Because of limited opportunities, past harvesting efforts have been may be less valuable.

reactive to individual plants shutting down and beginning decommissioning. Given the expected availability of materials from numerous plants and anticipated

Availability of materials for harvesting research needs to better understand ag ing out to 80 years of operation, the NRC is

Timeliness of the expected research pursuing a more proactive approach to prioritize the data needs best addressed by results relative to the objective.

harvesting and identify the best sources of materials to address high-priority data needs for regulatory research.

The first step in this strategic approach is to prioritize data needs for harvesting. A data need describes a particular degradation scenario and should be defined with as much detail as appropriate in terms of the material (alloy, composition, etc.) and environment (temperature, fluence, chemistry, etc.). Lifting operation for irradiated Example of reactor internals harvesting plan materials transport cask

Note to requester: The public version of this records is in ADAMS at ML19129A329.

2OROERNO INTERAGENCY AGREEMENT rNRC-HQ-60-15-T-0023

~ NO

13. REQUISITION NO RES-15-0205 1* SOUCITATION NO

,~ OF I 3 5 EFFECTIVE DATE 18 AWAAO DATE 7 PERIOO OF PERFORMANCE 09/04/2015 09/04/2015 09/17/2015 TO 09/30/2019 8 SERVICING AGENCY 9 OELIIIERTO PACIFIC NORTHWEST NAT LAB US NUCLEAR REGULATORY COMMISSION ALC: 11555 ROCKVILLE PIKE DUNS: +4 : ATTN AMY HULL US DEPARTMENT OF ENERGY MAIL STOP T-10D49 PACIFIC NORTHWEST SITE OFFICE ROCKVILLE MD 20852-2738 PO BOX 350 MS K9-42 RICHLAND WA 99352 POC GENICE MADERA TaEPHONe NO 509-372-4010 10 REOUESTNG AGENCY 11 r-NOICE OFFICE ACQUISITION MANAGEMENT DIVISION US NUCLEAR REGULATORY COMMISSION ALC : 31000001 DUNS: 040535809 +4: ONE WHITE FLINT NORTH US NUCLEAR REGULATORY COMMISSION 11555 ROCKVILLE PIKE ONE WHITE FLINT NORTH MAILSTOP 03-E17A 11555 ROCKVILLE PIKE NRCPAYMENTSNRCGOV ROCKVILLE MD 20852-2738 ROCKVILLE MD 20852-2738 POC MICHAEL TURNER TEI..EPHOhE NO 301-415-6712

12. ISSUlNG OFFICE 13. LEGISl.AT~ AUTHORITY US NRC - HQ Energy Reorganization Act of 1974 ACQUISITION MANAGEMENT DIVISION MAIL STOP TWFN-5E03 WASHINGTON DC 20555-0001 14 PflOJECT 10 15 PflOJECT TITlE SEE BLOCK 118 18 ACCOUNTING DATA 2015-X0200-FEEBASED-60-60D001-11-6-213-1032-253D 17 18 19 20 21 22 ITEM NO SUf'PUESISERVICES QUANTITY UNIT UNIT PRICE AMOUNT Master IAA : NRCHQ2514D0001 00001 Issuance of new Task Order No . NRC-HQ-60-15-T-0( 23 163, 529 . 00 Line Item Ceiling$163 , 529 . 00 Incrementally Funded Amount : $73 , 165 . 00 The NRC and Pacific Northwest National Laborato y (PNNL) hereby enter into this Agreement for the project entitled "Strategic Approach for Obtaining Material and Component Aging Information ."

Continued ...

23 PIIIYMEtlT" PRO\/ISIONS 124 TOTAi.AMOUNT

$73 , 165 . 00 25" SIGNATURE OF GOIIERNMENT REPRESENTATIVE (SERVICING) 2eo SIGNA ~ ATI\IE (REQUESTING) 3/4di A- /.,,, .,...,(A,,/

2Sb NAME N<<J TITLE 2"1>. CONTRACTING OFFICER 1 125c DATE MICHAEL A. TURNER ri7"'i/20J5 I

~

NRC-HQ-60-15-T-0023 2 I3 Period of Performance : September 17 , 2015 -

September 30 , 2019 Consideration and Obligations :

(a) Authorized Cost Ceiling $163 , 529 . 00 (b) The amount presently obligated with respect to this DOE Agreement is $73 , 165 . 00 . When and if the amount(s) paid and payable to the DOE Laboratory hereunder shall equal the obligated amount , the DOE Laboratory shall not be obligatec to continue performance of the work unless and until the NRC Contracting Officer shall increase the amount obligated with respect to this DOE Agreement . Any work undertaken by the DOE Laboratory in excess of the obligated amount specified above is done so at the DOE Laboratory ' s sole risk .

SCHEDULE OF REQUIRED TASKS :

Task 1 - Scoping Study and Technical Literature Review Total Authorized Cost Ceiling ...... $163 , 529 . 00 The Government may require the delivery of the numbered line item identified in the Schedule as

~n option item, in the quantity and at the cost stated in the Schedule . The Contracting Officer

~ill issue a modification to the Agreement to

~uthorize the optional task .

SCHEDULE OF OPTIONAL TASKS :

Task 2 - Decision Making on Specific Confirmatory Research Needed to Address Gaps ($87,775 . 00)

~ask 3 - Confirmatory Research Addressing Technical Gaps ($143 , 240 . 00)

Task 4 - Development of Independent Decision Making Tools ($155 , 462 . 00)

The following document is hereby made a part of this Agreement :

~ttachment No . 1 : Statement of Work

~ontinued ...

NRC-HQ-60-15-T-0023 1-00 PAGE 3

~

I3

~ his agreement is entered into pursuant to the

~uthority of the Energy Reorganization Act of 1974, as amended (42 u.s . c 5801 et seq . ). This

~ ork will be performed in accordance with the

~ RC/DOE Memorandum of Understanding dated

~ ovember 24 , 1998 . To the best of our knowledge ,

the work requested will not place the DOE and its

~ontractor in direct competition with the

~ omestic private sector.

I J Fee Recoverable Work

[XJ Non-fee Recoverable Work PNNL Principal Investigators :

Pradeep Ramuhalli/509-375-2763 Katie Knobbs/509-372- 4560 The total amount of award : $163 , 529.00. The obligation for this a ward is shown in box 24 .

Attachment No. 1 STATEMENT OF WORK NRC Agreement Number NRC Agreement NRC Task Order Number (If NRC Task Order Modification Number Applicable) Modification Number (If Applicable)

NRC-HQ-25-14-O-0001 NIA NRC-HQ-60-15-T-0023 NIA Project Title Strategic Approach for Obtaining Material and Component Aging Information Job Code Number B&R Number DOE Laboratory Pacific Northwest National Laboratory (PNNL)

NRC Requisitioning Office Nuclear Regulatory Research (RES)

NRC Form 187, Contract Security and Classification Requirements D Involves Proprietary Information 0 Applicable D Involves Sensitive Unclassified

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

Docket Number (If Fee-Recoverable/Applicable) Inspection Report Number (If Fee Recoverable/Applicable)

Technical Assignment Control Number (If Fee- Technlcal Assignment Control Number Description (If Fee-Recoverable/Applicable) Recoverable/Applicable)

1.0 BACKGROUND

Regulatory Context:

The NRC has established a license renewal process that will allow nuclear power plants (NPP) to renew their licenses for an additional 20 years, via 10 CFR 54. 31 ( d) stating that "a renewed license may be subsequently renewed." The biggest challenges for the NRC and the industry will be addressing the major technical issues for this second "subsequent" license renewal (SLR) beyond 60 years. As summarized in SECY-14-0016, the NRC staff believe that the most significant technical issues challenging power reactor operation beyond 60 years are related to:

Reactor pressure vessel (RPV) neutron embrittlement at high fluence

Irradiation assisted degradation (IAD) of reactor internals and primary system components

Concrete and containment degradation 1

Attachment No. 1

Electrical cable qualification and condition assessment.

Understanding the causes and control of degradation mechanisms forms the basis for developing aging management programs (AMPs) to ensure the functionality and safety margins of NPP systems, structures, and components (SSC). The resolution to these issues should provide reasonable assurance of safe operation of the components in the scope of license renewal during the subsequent period of extended operation.

Because of the cost and inefficiency of piecemeal sampling, there is a need for a strategic and systematic approach to sampling materials from SSC in decommissioning plants. The envisioned work addresses both passive and active components. In that sense, it addresses aging management of passive components under the license renewal rule, 10 CFR 54, as well as the maintenance of active components covered by the maintenance rule, 10CFRS0.65, as seen in Figure 1 below.

~ US.NRC

,.,..,,t.. ,..,. , J... , _ -

Safety Beyond 60 Years Maintenance Rule Quality Assurance Aging Management (10CFR S06S) Program (10CFR 54)

( 10CFR Part!SOAp~ndccB) r ensures that the effects' ofagr,g w*be 10 CFR 50.55a effectrvelymanaged Requlremerts throughout the periOd of extended operatlDn

( Active Components

)

Passive Components Aging Management Effectiveness Figure 1: Relationship between aging management of active and passive components (from NRR/RES presentation to ACRS, 2014)

In the past few years, four plants have ceased operation or announced that they will cease operation: Crystal River Unit 3 (PWR), Kewaunee (PWR), San Onofre Units 2 & 3 (PWR), and Vermont Yankee (BWR). Tlhese plants comprise a range of reactor types, containments, and SSCs important to safety. The primary objective of this project is to develop a long-range strategy for obtaining information from these plants as they go through decommissioning. The focus will be on timely acqui1sition of experiential real-world aging-degradation information that 2

Attachment No. 1 can significantly improve the agency's risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet.

Technical Context:

Creating a roadmap for obtaining information from designated NPPs as they go through decommissioning is complementary to ongoing NRC research in developing technical information to support evaluating SLR as well as data collection and testing of ex-plant materials.

Material degradation has traditionally been managed reactively in response to events and operating experience, rather than proactively to prevent failures. For the NPPs currently entering their first license renewal period from 40-60 years, and submitting SLR applications, it is necessary to evaluate potential degradation mechanisms out to 80 years of operation.

Evaluation of material properties in SSCs from actual decommissioned NPPs will provide a basis for comparison with re:sults of laboratory tests and calculations to resolve the four issues listed above.

The proactive management of materials degradation (PMMD) information tool was originally created at PNNL for RES (POC: Amy Hull) to give an expert opinion of the possible future degradation mechanisms on a subcomponent/material specific basis (PNNL-17779t Combined with the LER database, the PMMD information tool allows one to not only react to past events, but to anticipate future issues. The original PMMD information tool was based on NUREG/CR-6923, "Proactive Materials Degradation Assessment (PMDA)," for the first license renewal period, so it is now appropriate to integrate information from the excel databases from the recently-published five volumes of NUREG/CR-7153, "Expanded Materials Degradation Assessment (EMDA)" for SLR. At this juncture, there is demonstrated industry interest in NPP long-term operation (LTO) and regulatory interest in SLR.

2.0 OBJECTIVES Understanding and managing material and component degradation is a key need for the continued safe and reliable operation of NPPs, but has significant uncertainties. In many cases, the scientific basis for understanding and predicting long-term environmental degradation behavior of materials in NPPs is incomplete. A strategic approach to examination and testing of materials and components from decommissioned reactors can dramatically increase our knowledge-acquisition rate in this very important area.

There are three inter-related objectives to this work:

(1) Develop a long-range strategy for obtaining information from decommissioned NPPs as well as providing the flexibility to get ex-plant components from operating plants as well. The focus will be on timely acquisition of experiential real-world aging-degradation information that can significantly improve the agency's risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet.

3

Attachment No. 1 (2) Construct a strategic plan and specifications for obtaining unique and significant materials aging degradation information from diverse sources (operating experience, other nuclear facilities, other long-lived industrial plants, other materials organizations such as ASM and NACE) that will inform the NRC's age-related regulatory oversight in the future.

Implementation of this plan and specifications, in cooperation with industry and DOE partners can be accomplished over time, through individual research projects as the identified plants progress through their decommissioning process. This exploratory research is expected to provide fundamental insights on reactor materials degradation and information addressing potential technical issues or identified gaps to support anticipated future NRC needs.

(3) Update the PMMD information tool to incorporate LTO/SLR-relevant information so that it can be better used to inform prioritization in the ex-plant material strategic plan.

3.0 SCOPE OF WORK There are a number of technical gaps that this project seeks to address. Most importantly, the current piecemeal approach can be replaced with a strategic plan that is more comprehensive, broader in scope, and more risk-informed. The strategic plan for inspections and/or testing developed in this project will be useful guidance for obtaining key measurements of degradation in a variety of areas. These measurements will be valuable on their own and will also be useful in basic research on the underlying mechanisms and modes of degradation, and for validation of modeling and simulation tools. Data and information developed from implementation of the strategic plan will also be useful in evaluating aging management and mitigation strategies proposed by the industry.

Many sources of materials degradation information will be queried, including human repositories of knowledge both within NRC and within the industry. Both the PMDA and EMDA present information in terms of component or material degradation susceptibility and currently available knowledge for degradation mitigation or prevention. A component with high degradation susceptibility/low knowledge would be the strongest candidate for proactive actions. It is necessary to be able to understand this before prioritizing ex-plant materials sampling available from a given retired NPP. Previously, under the auspices of NRC contracts (i.e., JCN N6029, N6907), PNNL used the large amount of information presented in the PMDA report to develop a web-based platform to facilitate analysis through interactive visualizations that offer intuitive ways to explore the information. PNNL shall explore the viability of adding materials degradation susceptibility data presented in the EMDA Report.

Such an information tool (Figure 2 below) is expected to save considerable staff efforts to understand and apply the PMDA and EMDA insights to regulatory review of licensee information. PNNL shall develop a web-based modified scalable reasoning system (SRS) for tracking, disposition, and resolution of critical issues, such as determining the appropriate SSC 4

Attachment No. 1 from which to acquire cast austenitic stainless steel (CASS) material of specific composition and radiation dose.

EPRI LTO Decommissioning Reactors Plans Operating Prioritization of Experience High-Priority Data Needs Oooortunities International Data Sources DOE LWRS Figure 2: Pre-conceptual Architecture of prognostic tool to track and resolve critical technical issues for SLR As shown in Figure 2 above, the information tool was originally envisioned as integrating domestic and international operating experience and experimental information as well as information from the EPRI LTO, DOE Light Water Reactor Sustainability (LWRS) program, and NRC sources such as EMDA, PMDA, and SLR guidance documents (SLRGDs) and precursors. The international data sources that might provide effective data feed include the cable aging data and knowledge (CADAK, http://cadakhrp.no/cadak.) project and the Component Operational Experience, Degradation and Ageing Programme (CODAP, http://www.oecd-nea.org/ jointproj/codap.html ),

both sponsored by OECD/NEA. The Atlas constructed by PNNL from the Program to Assess the Reliability of Emerging Non-destructive Technology (PARENT) and the Program to Inspect Nickel Alloy Components (PINC) Atlas is an international database containing a vast array of SCC crack morphology and NOE information. PNNL shall investigate whether this is an appropriate framework to track issue resolution associated with SLR. This is a much broader objective than just developing a strategic roadmap for harvesting SSCs.

The general tasks and their duration are described in Table 1.

5

Attachment No. 1 Table 1: Task Description and Duration Task Task Title/Description Duration (Months)

Task 1 Scoping Study and technical literature review 18 Task2 Decision Making on Specific Confirmatory Research Needed to 6 Address Gaps (optional)

Task 3 Confirmatory Research Addressing Technical Gaps (optional) 33 Task4 Development of Independent Decision Maki1ng Tools (optional) 33 The conditional tasks shall be conducted, as detailed in Figure 3 below. A decision on further optional research outlined in Tasks 2, 3, and 4 will be made after completion of Task 1 depending on the outcome and recommendation from the conclusion of specific tasks. The overall nexus between the scoping study and other potential tasks is shown in Figure 3 .

The PNNL staff shall not restrict their activities solely to these descriptions and shall be flexible in using their technical knowledge and experience in proposing additions, deletions, or deviations from the prescribed requirements as research progresses.

Task 1.

Technical Terminate Task 2. Gap Literature Identification Further Review Research Yes Task 3.

Recommend Research Need

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

I Task 4. :I

I Develop lI

Analysis Tools :

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

Attachment No. 1 4.0 SPECIFIC TASKS Task 1 is the scoping study. Tasks 2-4 are optional. NRC plans to revise the SOW for these tasks based on the outcome of Task 1. The time at which the tasks begin and end will be dependent on available information and NRC's ongoing evaluation of testing priorities. NRC staff does not require that PNNL necessarily perform the tasks be performed sequentially following the order in which they are listed. For the test matrix described in this section, nearly all subtasks will have to be tested in tandem with another subtask in order to complete the program within the requested period of performance. PN NL and the NRC CORs will continually review the testing plan during monthly status update teleconferences.

PNNL shall, in the first stage of Task 1, develop a questionnaire and help the NRC staff conduct interviews with focus groups from various technical disciplines within NRC. PNNL shall, in the second stage of Task 1, ass1ist the NRC staff conduct one or two public workshops. PNNL shall analyze and combine the results of the first two phases into a final strategic plan in the third stage.

This strategic plan will provide a prioritization of strategic harvesting opportunities. PNNL shall help the NRC staff develop the ex-plant harvesting strategic plan in cooperation with industry and other federal agencies such as DOE as well as any international counterparts that may be interested in participation.

In Tasks 2-4, PNNL may be assigned optional tasks to identify requirements to further elucidate the risk assessment of component degradation. Such research should also provide technical data and information, as necessary, to request the national codes and standards bodies (such as ASME, ASTM, or NACE) to re-examine requirements for structural materials for passive components in light water reactors (LWRs) and in assessing material degradation during service and its effect on design safety margin of components. The PNNL principal investigator (Pl) for this project shall attend ASME, ASTM, or NACE Code Committee meetings, as appropriate and as approved by the COR during the course of this research. The Pt shall provide adequate information to support an IAEA international cooperative research program (ICRP) on this subject to bring worldwide resources to address this research need.

The specific tasks are as fol lows:

Task 1 - Literature Review and Assessment of Greatest Needs in Sampling of Ex-plant Materials NRC recently completed a research program to investigate material degradation after extended operation. To investigate aging degradation mechanisms, aging degradation effects, and the relative susceptibility to degradation, PNNL shall perform a comparison of available information.

PNNL shall conduct the Task 1 scoping study and provide all resources necessary to accomplish the subtasks and deliverables. Task 1 shall be performed in stages as shown in the Task-specific subsections below.

7

Attachment No. 1 The activities required for this task are:

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

Task 1.2 - Evaluate Availability of Ex-Plant Material and Information PNNL shall evaluate what relevant ex-plant material is projected to be available for potential harvesting. PNNL shall work with the NRC COR to develop a questionnaire and interview the cognizant individuals at the plants who possess critical knowledge.

Task 1.3 - Develop Questionnaire and Conduct Interviews with Prospective NRC Stakeholders PNNL shall develop a questionnaire and work with NRC staff to conduct interviews with focus groups from various technical disciplines within NRC. This would include the SLR Expert Panels for a sample of different aging management programs (AMPs) as well as other NRC technical advisory groups. PNNL shall have a comprehensive approach to all the possible stakeholders interested in harvesting materials from decommissioned plants. The objective of this initial scoping study is to assess interest in issues concerning both passive and active component degradation. The questionnaire will address, as a minimum, (1) the perceived needs for ex-plant materials, (2) the perceived utility of the existing information tool and how and where this prognostic tool should be maintained (NRC, contractor, cloud). During the early brainstorming and scoping study, PNNL shall also consider degradation of SSC materials associated with extended long-term storage of used fuel.

Task 1.4 - Develop Questionnaire and Conduct Interviews with Prospective External Stakeholders Based on interactions with NRC staff in Task 1.3 above, PNNL shall propose a preliminary strategic approach to sampling representative ex-plant materials during one or two presentations at public workshops to further refine the concept of what would be needed in a useful interrogatory tool linking aging-degradation research objectives with available resources for ex-plant materials. The searchable information tool shall be available via an interactive web page.

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Attachment No. 1 Task 1.5-Conduct Scoping Analysis on Viability of Searchable Information Tool Task 1.5.1 PNNL shall briefly consider available approaches to creating a preliminary database that will link the highest susceptibility/lowest knowledge anticipated degradation scenarios with potential availability of ex-plant materials. As part of this subtask, PNNL shall review the status and viability of the PMMO information tool created as part of the PMMO project (conducted at PNNL under previous NRG contracts (i.e., JCN N6029, N6907). The goals of the PMMO project were to identify reactor components that could reasonably be expected to experience future degradation, estimate the susceptibility of components to various degradation mechanisms, and assess the degree of knowledge available to develop mitigative strategies. It was anticipated that this information could be used to guide regulatory actions related to license renewal and subsequent license renewal. The PMMD panel evaluated 3863 components (2203 for PWRs, 1603 for BWRs) for their susceptibility to 16 degradation mechanisms (Figure 4 below). Because of the unwieldiness of the source material, a searchable information tool (pmmd.pnl.gov) was developed to make this information usable to NRG staff and others.

Task 1.5.2 PNNL shall worlk with the NRG to create a proposal to develop a platform for the searchable database methodology (selected in Task 1.5.1) that can be supported within NRC.

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Attachment No. 1 Figure 4. Flowchart for files created and used in PMMD infotool Task 1.6- Provide Archival Summary Document of Findings from Task 1 PNNL shall analyze and review the reports generated from the work conducted under Tasks 1.1 through 1.5 and provide a stand-alone NUREG/CR documenting the major findings.

Optional Task 2 - Decision Making on Specific Research Need to Address Gaps If the Task 1 scoping study succeeds in determining previously unidentified significant knowledge gaps that need further attention, more work will be done in the context of Task 2, pending the approval from the NRC Contract Officer (CO). Thus, Task 2 is optional pending the outcome of Task 1 and requires NRC activation. The activities required for this task are:

Task 2.1 - Gap Identification PNNL shall identify specific information and technical data gaps from the execution of Task 1 and document these gaps. In identifying the gaps, PNNL shall include an examination of the current ASME B&PV Code or other industry practices that the NRC has endorsed with respect to addressing the specific degradation mechanism in the design and the assurance of the retention of the design margin during the period of licensed reactor operation time.

Task 2.2 - Determine Significance and Disposition of Technical Gaps PNNL shall determine whether or not there are any technical gaps from the execution of Task 2.1. If there are no gaps and if it is determined that the current ASME Code or other industry practices ensure that the design margin for components are adequate, recommend termination of further research in this topic by NRC. If specific information and technical gaps are identified then proceed to Task 3 after getting approval from the NRC Contract Officer (CO).

Optional Task 3 - Research Addressing Technical Gaps Related to Material Degradation If critically important information and technical gaps are identified in Task 2, Task 3 is activated after getting approval from the NRC CO. Thus, Task 3 is optional pending the outcome of Task

2. The activities required for this task are:

Task 3.1 - Recommend Specific Laboratory Experimentation and Analytical Model Development PNNL shall work with NRC subject matter experts (SMEs) to recommend specific laboratory experimentation and analytical model development, which may address the information gap identified in Task 2.1. If novel nondestructive evaluation methods (such as the next-generation acoustic emission technology which reportedly can 'hear' crack initiation) become available to identify progressing reactor material degradation by the time Task 3 is initiated, PNNL shall recommend inservice inspection (ISi) technology enablers which will be suitable for detecting the material changes resulting from different stressors. PNNL shall work with NRC SMEs to 10

Attachment No. 1 recommend the need for developing tools for detection and assessment of potential degradation of the design safety margin to independently confirm the licensee's technical basis for LTO.

Task 3.2 - Review Adequacy of Existing Codes and Standards PNNL shall conduct a review of existing applicable ASME B&PV Codes that may need to be revised as a result of Task 2.1 and PNNL shall work with NRC SMEs to engage relevant ASME Code Committees for assessing future path. PNNL shall propose other Codes and Standards that should be reviewed (such as but not limited to, ANS, ASTM, and NACE codes and standards).

Optional Task 4 - Investigate Development of Independent Decision Making Tools Task 4 is optional pending the outcome of Tasks 1 - 3. If gaps are identified under Task 2 and appropriate research needed to inform the gaps are also identified under Task 3, NRC expects that the industry will perform the needed research and provide NRC the data for regulatory decisions.

Depending on the outcome of Tasks 2 and 3 and ensuing industry research, the decision-making tool development may be complex and truly involve multi-year, multi-disciplinary long term research. It is expected, however, that the decision making tool may include: (a) Material and component condition after different stressors; (b) Better knowledge of specific degradation and its potential for reducing the design safety margin for the components; (c) Incorporation of plant data into the various material, inspection, and structural integrity evaluation models; and (f)

An integration of all these aspects into the regulatory decision making process to consider the risk contribution due to material degradation.

Specific subtasks for this task will be established later in this research. PNNL shall investigate the feasibility of developing a modern visualization confirmatory analysis research tool for aging management of safety-significant SSC degradation in NPPs. As currently envisioned, this could provide a knowledge management and strategic planning tool for conducting gap assessments and prioritizing R&D resources related to NPP LTO. This research will leverage the work previously performed by PNNL on the PMMD Information Tool, sponsored by RES.

RES/DE would benefit from a R&D gap assessment, strategic planning and knowledge management tool to enhance the tracking , disposition, resolution of technical issues that surface as industry moves towards SLR. Such a database would save staff time in addressing the degradation challenges for NPP passive components, spent fuel pools, and independent spent fuel storage installations (ISFls). The proposed LTO issues visualization tool can incorporate, up-to-date information on critical issues associated with cable, concrete and RPV aging. Work is actively progressing on developing SLR guidance documents with unresolved technical issues arising almost on a daily basis. These could be captured by the proposed service-oriented analytic framework. The existing PMMD database containing detailed information about susceptibility, knowledge, and confidence associated with hundreds of degradation scenarios can be augmented with aging risk indices, when developed by the DOE LWRS research. This will enable a better understanding of service life projections of NPP SSC.

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Attachment No. 1 5.0 DELIVERABLES AND/OR MILESTONES SCHEDULE Except for Task 1.6 where a draft summary NUREG/CR is stipulated, all deliverables shall be in the form of technical letter reports or alternatives previously discussed and determined acceptable by the COR. Based on the detailed tasks provided in Section 4.0 of this Statement of Work, PNNL shall estimate the number of Figures/Tables or other copyrighted information from technical journals, etc. and shall incorporate this estimation in the cost proposal in addressing the SOW. PNNL shall also estimate reasonable effort by their technical editing staff in order to provide the NRC tech-edited draft final and final reports.

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Attachment No. 1 Task Deliverable/Milestone Description (include NRG acceptance Due Date (if any)

Number criteria if applicable)

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

Attachment No. 1 1.6 Summary Report 1.6. Draft NUREG/CR to NRC including NLT 20 months after information from Reports 1.1 through 1.5.2. contract award (Note: At the discretion of COR, a decision may also be made to publish Summary Report 1 as a TLR rather than as an NUREG/CR, depending on the significance of the literature review and research assessment results).

1.6 The Contractor will make a technical presentation to the NRC When the draft staff on Summary Report 1.6 at NRC Headquarters in Rockville, Summary Report 1.6 MD. is delivered to NRC.

1.6 NRC to provide comments to contractor on Summary Report NLT 2 months after 1.6. receiving draft Summary Report 1.6 from PNNL 1.6 DOE Contractor to publish Summary Report 1.6 as NUREG/CR. NLT 2 months after Deliver 12 hard copies to the NRC COR, in addition to an receiving NRC electronic file. comments Task 2 is optional pending outcome of Task 1.

2 PNNL to provide Report 2 Draft TLR to NRC based on results NLT 24 months after from Subtask (2.1) concerning technical gap identification and original contract award subtask (2.2) determination of significance and disposition of gaps 2 NRC to provide comments to contractor on Report 2 concerning NLT 1 month after technical gap identification, significance, and disposition receiving draft Report 2 from PNNL 2 PNNL to publish TLR Report 2 technical gap identification, NLT 1 month after significance, and disposition. Deliver 12 hard copies to the NRC receiving NRC COR, in addition to an electronic file. comments Task 3 is optional pending outcome ofTask 2 3.1 PNNL to provide Report 3.1 Draft TLR to NRC based on results NLT 46 months after from Subtask (3. 1) concerning specific laboratory contract award experimentation and analytical model development 3.1 NRC to provide comments to contractor on Report 3.1 NLT 1 month after concerning specific laboratory experimentation and analytical receiving draft Report model development 3.1 from PNNL 3.1 PNNL to publish TLR Report 3.1 concerning specific laboratory NLT 1 month after experimentation and analytical model development. Deliver 12 receiving NRC hard copies to the NRC COR, in addition to an electronic file. comments 3.2 PNNL to provide Report 3.2 Draft TLR to NRC reviewing NLT 46 months after adequacy of existing codes and standards for SLR contract award 3.2 NRC to provide comments to contractor on Report 3.2 reviewing NLT 1 month after adequacy of existing codes and standards for SLR receiving draft Report 3.2 from PNNL 3.2 PNNL to publish TLR Report 3.2 reviewing adequacy of existing NLT 1 month after codes and standards for SLR. Deliver 12 hard copies to the receiving NRC NRC COR, in addition to an electronic file. comments Task 4 is optional pending outcome of Task 1 and partially pending on Task 2 and 3.

14

Attachment No. 1 4 PNNL to provide Report 4 Draft TLR to NRC documenting NLT 46 months after development of prognostic tool to track and resolve critical SLR contract award technical issues 4 NRC to provide commen ts to contractor on Report 4 reviewing NLT 1 month after development of prognostic tool to track and resolve critical SLR receiving draft Report technical issues 3.2 from PNNL 4 PNNL to publish TLR Report 4 reviewing develop ment of NLT 1 month after prognostic tool to track and resolve critical SLR technical issues receiving NRC R. Deliver 12 hard copies to the NRC COR, in addition to an comments electronic file.

6.0 TECHNICAL AND OTHER SPECIAL QUALIFICATIONS REQUIRED Specific qualific ations for this effort include senior materia ls enginee rs and metallu rgists who have in-depth knowle dge of reactor pressur e vessel and core internal materia ls subject ed to irradiation and stress at elevate d temper ature, and effects of water chemis try on structur al reactor materia ls. The personn el involve d should have in-dept h experie nce, knowle dge, and demons trated contribu tions in the areas of mechan ical deform ation, materia l degrad ation phenom ena, such as corrosio n, stress corrosio n crackin g and irradiati on effects. The contrac t personnel should be well-ve rsed in the use of nuclear power plant ASME B&PV Codes and Standa rds, Industry Guidan ce Docum ents, such as those of NEI, EPRI, NRC's Regula tory Guides and NRC's License Renew al Guidan ce Docum ents (such as NUREG s 1800, 1801, and 1950) Informa tion Notice (IN), Regula tory Issue Summa ry (RIS), Generic Letter (GL), Generic Issue (GI) for licensing review by the NRC staff.

The contrac t personnel should also be aware of the safety evaluat ion reports (SER) written by the NRC staff on industry guidanc e docume nts, as applica ble. The contrac t personn el should have previou s experie nce develop ing approp riate softwar e architec ture for propose d R&D planning tool.

7.0 MEETINGS AND TRAVEL The PNNL Principal Investig ator and one other engine er shall visit the NRC Headqu arters in Rockville, MD and presen t the overall researc h outcom e to the staff and share in technic al discuss ions. Any sugges tions from the staff, as approp riate, may be conside red for the final report by the Pl. No other domest ic or foreign travel is permitt ed under the initial scoping study.

8.0 REPORTING REQUIREMENTS PNNL is respons ible for structur ing the delivera ble to follow agency standar ds. The current agency standar d is Microso ft Office Suite 2010. The current agency Portabl e Docum ent Format (PDF) standar d is Adobe Acroba t 9 Professional. Deliver ables shall be submitt ed free of spelling and gramma tical errors and conform to require ments stated in this section .

Month ly Letter Status Report s In accorda nce with Manag ement Directive 11 .7, NRC Proced ures for Placem ent and Monitoring of Work with the U.S. Departm ent of Energy, PNNL shall electron ically submit a Monthly Letter Status Report (MLSR ) by the 20 th day of each month to Amy Hull, the Contracting Officer 15

Attachment No. 1 Representative (COR), to Matthew Hiser and Joseph Kanney, the technical monitors, with copies to the Contracting Officer (CO) and the Office Adm inistration/Division of Contracts to ContractsPOT.Resource@nrc.gov. If a project is a task ordering agreement, a separate MLSR shall be submitted for each task order with a summary project MLSR, even if no work has been performed during a reporting period. Once NRC has determined that all work on a task order is completed and that final costs are acceptable, a task order may be omitted from the MLSR.

MLSR should be distributed additionally to the Chief, Corrosion and Metallurgy Brancln, RES, the Director, Division of Engineering, RES. Other required distribution will be communicated at the start of this research program.

The MLSR shall include the following : agreement number; task order number, if applicable; job code number; title of the project; project period of performance; task order period of performance, if applicable; COR's name, telephone number, and e-mail address; full name and address of the performing organization; principal investigator's name, telephone number, and e-mail address; and reporting period. At a minimum, the MLSR shall include the information discussed in Attachment 1. The preferred MLSR format can also be found in Attachment 1.

9.0 PERIOD OF PERFORMANCE The period of performance for this work is September 17, 2015 - September 30, 2019.

10.0 CONTRACTING OFFICER'S REPRESENTATIVE The COR monitors all technical aspects of the agreement/task order and assists in its administration. The COR is authorized to perform the following functions: assure that the DOE Laboratory performs the technical requirements of the agreement/task order; perform inspections necessary in connection with agreement/task order performance; maintain written and oral communications with the DOE Laboratory concerning technical aspects of the agreemenUtask order; issue written interpretations of technical requirements, including Government drawings, designs, specifications; monitor the DOE Laboratory's performance and notify the DOE Laboratory of any deficiencies; coordinate availability of NRG-furnished material and/or GFP; and provide site entry of DOE Laboratory personnel.

Contracting Officer's Representative Name: Dr. Amy B. Hull Agency: U.S. Nuclear Regulatory Commission Office: Office of Nuclear Regulatory Research Mail Stop: T-10D49 Washington, DC 20555-0001 E-Mail: amy.hull@nrc.gov Phone: 301 -251-7656 Alternate Contracting Officer's Representative Name: Matthew Hiser Agency: U.S. Nuclear Regulatory Commission Office: Office of Nuclear Regulatory Research Mail Stop: T-10 A36 Washington, DC 20555-0001 16

Attachme nt No. 1 E-Mail: Matthew.Hiser@nrc.gov Phone: 301-251-7601 11 .0 MATERIALS REQUIRED (TYPE N/A IF NOT APPLICABLE)

N/A 12.0 NRC-FURNISHED PROPERTY/MATERIALS PNNL will transfer NRC furnished property and materials acquired under previous contracts (i.e., JCN N6029, N6907) to this task order. NRC will provide additional informat ion from EMDA and SLR databases.

13.0 RESEARCH QUALITY (TYPE N/A IF NOT APPLICABLE)

The quality of NRC research programs are assessed each year by the Advisory Committee on Reactor Safeguards. Within the context of their reviews of RES programs, the definition of quality research is based upon several major characteristics:

Results meet the objectives (75% of overall score)

Justification of major assumptions (12%)

Soundness of technical approach and results (52%)

Uncertainties and sensitivities addressed (11 %)

Documentation of research results and methods is adequat e (25% of overall score)

Clarity of presentation (16%)

Identification of major assumptions (9%)

It is the responsibility of the DOE Laboratory to ensure that these quality criteria are adequately addressed throughout the course of the research that is performed. The NRC COR shall review all research products with these criteria in mind.

14.0 STANDARDS FOR CONTRACTORS WHO PREPARE NUREG -SERIES MANUSCRIPTS (TYPE N/A IF NOT APPLICABLE)

The U.S. Nuclear Regulatory Commission (NRC) began to capture most of its official records electronically on January 1, 2000. The NRC will capture each final NUREG-series publication in its native application. Therefore, please submit your final manusc ript that has been approved by your NRC Project Manager in both electronic and camera-ready copy.

The final manuscript shall be of archival quality and comply with the requirements of NRC Manage ment Directive 3.7 "NUREG-Series Publications." The document shall be technically edited consistent with NUREG -1379, Rev. 2 (May 2009) "NRC Editorial Style Guide."

The goals of the "NRC Editorial Style Guide" are readability and consistency for all agency documents.

All format guidance , as specified in NUREG -0650, "Preparing NUREG-Series Publicat ions,"

Rev. 2 (January 1999), will remain the same with one exception. You will no longer be required to include the NU REG-series designator on the bottom of each page of the manuscr ipt. The NRC will assign this designa tor when we send the camera-ready copy to the printer and will 17

Attachment No. 1 place the designator on the cover, title page, and spine. The designator for each report will no longer be assigned when the decision to prepare a publication is made. The NRC's Publishing Services Branch will inform the NRC Project Manager for the publication of the assigned designator when the final manuscript is sent to the printer.

For the electronic manuscript, the Contractor shall prepare the text in Microsoft Word, and use any of the following file types for charts, spreadsheets, and the like.

File Types to be Used for NUREG-Series Publications File Type File Extension MicrosoftWord .doc Microsoft PowerPoint .ppt MicrosottExcel .xis MicrosoftAccess .mdb Portable Document Format .pdf This list is subject to change if new software packages come into common use at NRC or by our licensees or other stakeholders that participate in the electronic submission process. If a portion of your manuscript is from another source and you cannot obtain an acceptable electronic file type for this portion (e.g ., an appendix from an old publication), the NRC can, if necessary, create a tagged image file format (file extension.tit) for that portion of your report.

Note that you should continue to submit original photographs, which will be scanned, since digitized photographs do not print well.

If you choose to publish a compact disk (CD) of your publication, place on the CD copies of the manuscript in both (1) a portable document format (PDF); (2) a Microsoft Word file format, and (3) an Adobe Acrobat Reader, or, alternatively, print instructions for obtaining a free copy of Adobe Acrobat Reader on the back cover insert of the jewel box.

15.0 OTHER CONSIDERATIONS (TYPE N/A IF NOT APPLICABLE)

References

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

2. Bond, LJ, TT Taylor, SR Doctor, AB Hull, and SH Malik, (2008) Proactive Management of Materials Degradation for nuclear power plant systems. Proc. Int. Cont. Prognostics and Health Management 2008, Denver, CO, October 6-9. IEEE Reliability Society,# OP-20-01 120 18

Attachment No. 1

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

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

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

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

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

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

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

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

11 . The Scalable Reasoning System: Lightweight Visualization for Distributed Analytics, IEEE Symposium on Visual Analytics Science & Technology, 978-1-4244-2935-6/08 Access to Non-NRC Facilities/Equipment (Type N/A if no,t applicable)

NIA Applicable Publications (Type N/A if not applicable)

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

NIA 19

NRC-2018-000831 - Resp 10 - Interim, Agency Records Subject to the Request Are Enclosed, Part 6 of 14
Person / Time
ML21071A172
Issue date:	03/04/2021
From:	NRC/OCIO
To:
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