ML19346E465
| ML19346E465 | |
| Person / Time | |
|---|---|
| Issue date: | 11/29/2019 |
| From: | NRC/OCIO |
| To: | |
| Shared Package | |
| ML19346E464 | List: |
| References | |
| FOIA, NRC-2018-000831 | |
| Download: ML19346E465 (281) | |
Text
Note to requester: Attachments to this email are immediately following .
From: HJser Matthew To: Frankl Jstvao Subject : FW: Harvesting Workshop Date: Monday, January 23, 2017 4:19:00 PM Attachments: Harvesting Workshop intro slides 1-23-17.potx Workshoo Plannina 1*23-17.doc)(,
From: Hiser, M atthew Sent: M onday, January 23, 2017 12:18 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Purtscher, Patrick
<Patrick.Purtscher@nrc.gov>
Subject:
RE: Harvesting Workshop Hi Rob and Pat, Thank you for meeting this morning to discuss the latest on the harvesting workshop planning.
I have updated the workshop planning document and the intro slides (attached).
Please take a look at the slides and provide edits.
Action Items:
- Matt: follow-up with Energy Solutions, Dominion, ENSI, Ahluwalia, AV/transcription
- Rob: Follow-up with GRS, MAI, JNRA/CRIEPI
- Rob and Pat: review slides and provide feedback 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 1Oj]ice: TVi' FN IOD62 Matthew.Hiser@nrc.gov
Original Appointment-----
From:
Sent: Wednesday, January 18, 2017 9:05 AM To: Hiser, M atthew; Tregoning, Robert; Purtscher, Patrick
Subject:
Harvesting Workshop When: Monday, January 23, 2017 9:00 AM-10:00 AM (UTC-05:00) Eastern Time (US &
Canada).
Where: HQ-TWFN-10A73-8p Adding latest w orkshop planning document and draft workshop intro slides.
Following my call with DOE and EPRI last week and additional contacts we've m ade, let's look at the agenda and try to finalize speakers for each slot.
<< File: Workshop Planning 1-17-17.docx >> << File: Harvesting Workshop intro slide.s.pptx >>
Ex-Plant Materials Harvesting Workshop March 7-8, 2017 USNRC HQ Rockville, MD, USA
Motivation
- With plants shutting down both in the U.S. and internationally, there are increasing opportunities to harvest components from decommissioning plants
- Past harvesting efforts generally more reactive and ad hoc as opportunities arose, rather than proactively planned
- Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions
- Reduces the uncertainty associated with the applicability of the aging conditions
- Insights from research on harvested materials can address technical data needs identified for extended plant operation
- Lessons learned from past harvesting programs can help improve future harvesting efforts
- Challenges encountered in previous programs can be shared and mitigated or avoided in future programs
Approach
- Domestic and international researchers, industry, regulators, and decommissioning companies' discuss benefits and challenges with ex-plant harvesting
- Encourage sharing of lessons learned as well as areas of common interest for potential new research programs
- Workshop consists of topical sessions with short presentations and significant time for open discussion
- Goal is to maximize engagement among all meeting participants, rather than presenter/audience mentality
- Scope includes any materials aging issue that could benefit from harvesting: metals, cables, and concrete
Expected Outcome
- Participants are better informed and aware of the benefits and challenges associated with ex-plant harvesting
- Discussions help identify areas of common interest for harvesting to address technical data needs
- Presentations and discussions provide the starting point for a "database" of harvested materials and future harvesting op po rt unities
- Contacts are made among research organizations to allow for further discussion of specific harvesting projects
Session Expectations
- Session 1 Motivation for Harvesting
- Perspective from panel participants on their organizations' interest in and motivation for harvesting
- Brief {5-10 minute) presentation from each panel member followed by open and panel discussion
- Session 2 Technical Data Needs for Harvesting
- Presenters share high-priority data needs that are best addressed by harvesting from their organization's perspective
- Where does harvesting hold particular value compared to other sources of technical data 15-20 minute presentations followed by open discussion of technical data needs for harvesting
Session Expectations
- Session 3 Sources of Materials Information on previously harvested materials and future harvesting opportunities
- Materials in "boneyards" at research and vendor facilities
- Decommissioning plants that may allow for future harvesting Short 5-10 minute presentations followed by open discussion Starting point for potential database of previously harvested materials and future harvesting opportunities
- Session 4 Harvesting Experience: Lessons Learned and Practical Aspects Forward-looking lessons learned from past harvesting programs
- Pitfalls to avoid and strategies to improve likelihood of success Practical perspective from non-researchers on how harvesting interfaces with the decommissioning process International decommissioning and harvesting experience 20-30 minute presentations followed by open discussion
Session Expectations
- Session 5 Future Harvesting Program Planning
- Technical and logistical information needed when planning a specific harvesting program
- Perspective from panel participants on their organizations' future harvesting planning
- Next steps and actions from workshop
- Potential areas of common interest for future harvesting programs
- Brief (5-10 minute) presentation from each panel member followed by open and panel discussion
Workshop Contacts Name Organization Email Contact Through Naoki Soneda CRIEPI soneda@crieQi.denken.or.jQ Rob Rachid Chaouadi SCK-CEN rachid.chaouadi@sckcen.be Rob Kazunobu Sakamoto JNRA kazunobu sakamoto@nsr.go.jQ Rob Gerry van Noordennen Energy Solutions gQvannoordennen@energysolutions.com Pat/Tom R.
Chuck Tomes Dominion charles.a.tomes@dom.com Matt Sherry Bernhoft EPRI sbernhoft@eQri.com Robin Dyle EPRI rdyle@eQri.com Jean Smith EPRI jmsmith@eQri.com Al Ahluwalia EPRI kahluwal@e12ri.com Tom Rosseel DOE rosseeltm@ornl.gov Rich Reister DOE Richard.Reister@nuclear.energy.gov Keith Leonard DOE leonardk@ornl.gov Mi khail A. Sokolov DOE sokolovm@ornl.gov Leo Fyfeld DOE/PNNL Pat Purtscher NRC Patrick. Purtscher@nre.gov Rob Tregoning NRC Robert.Tregoning@nrc.gov Matt Hiser NRC Matthew.Hiser@nrc.gov Anders Jenssen Studsvik anders.jenssen@studsvik.se Matt/Jean Daniel Tello CNSC daniel.tello@canada.ca Matt Heather Malikowski PWROG Heather.Malikowski@exeloncorQ.com Matt Jim Molkenthin PWROG molkenj12@westinghouse.com Matt Regis Nhili MAI regis.nhili@edf.fr Rob Uwe Jendrich GRS Uwe.Jendrich@grs.de Rob Pradeep Ramuhalli PNNL PradeeQ.Ramuhalli@Qnnl.gov Session NRC Lead DOE Lead EPRI Lead 1 Rob Tregoning Rich Reist er Sherry Bernhoft/Robin Dyle 2 Pat Purtscher Keith Leonard (ORNL) Sherry Bernhoft/Robin Dyle 3 Matt Hiser Tom Rosseel (ORNL) Sherry Bernhoft/Robin Dyle 4 Matt Hiser Tom Rosseel (ORNL) Sherry Bernhoft/Robin Dyle 5 Rob Tregoning Rich Reister Sherry Bernhoft/Robin Dyle NRC Presentations Session Topic Speaker 1 Why our organization is interested in harvesting Tregoning 2 Overview of data needs best addressed by harvesting Pradeep / PNNL Available materials from decommissioning plants and Hiser 3
past harvesting programs Perspective on Harvesting Lessons Learned/ Prior TBD 4
Experience Technical information needed for informed harvesting Pradeep / PNNL 5
decisions 5 Perspective on future harvesting planning Tregoning
Session Topic Organization Speaker Status EPRI DOE Rich Reister Why our organization is interested in harvesting NRC Robert Tregoning 1
MAI Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged PANEL DISCUSSION Overview of data needs best addressed by harvesting PNNL (for NRC) Pradeep Ramuhalli EPRI 2 DOE Keith Leonard Perspective on detailed data needs from harvesting SCK-CEN CNSC? Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged Available materials from decommissioning plants and past NRC Matt Hiser harvesting programs Available materials from operating reactors and past harvesting EPRI programs PWROG Emails exchanged 3 Available materials at DOE labs from past harvesting programs DOE Tom Rosseel Upcoming decommissioning sites Energy Solutions Gerry van Noordennen Contact through Tom R.
MAI Emails exchanged International sources of materials JNRA/CRIEPI/JAEA Emails exchanged Korea Need to work w/ Ahluwalia EPRI Perspective on Harvest ing Lessons Learned / Prior Experience DOE Tom Rosseel NRC Decommissioning process and harvesting: schedule, site-specific, Energy Solutions 4 Gerry van Noordennen Contact through Tom R.
t iming for different components Dominion or Utility-Owner perspective on harvesting and decommissioning Emails exchanged Exelon International decommissioning and harvesting experience Germany? Emails exchanged Technical information needed for informed harvesting decisions PNNL (for NRC) Pradeep Ramuhalli EPRI DOE Rich Reister Perspective on future harvesting planning NRC Robert Tregoning 5
MAI Emails exchanged JNRA/CRIEPI/JAEA Emails exchanged PANEL DISCUSSION Discussion of Next Steps / Actions
Note to requester: Attac hments to this email are immediately following .
From: Salley MarkHenry To: Koshy Thomas; Hiser Matthew Cc: Taylor Gabriel; Melly Nicholas; Stroup David; Gonzalez Felix; Thaggard Mark; Check Michael
Subject:
FW: Harvesting Workshop Date: Wednesday, February 22, 2017 4:33:43 PM Attachments: NRCTechnical Data Needs for Harvestina,pptx NRG Perspective on Harvestjna Experience and Lessons Learned ootx Sources of Materials optx imaoeOOJ loo imaae002.jpg Importance: High
- Tom, Thanx for bringing this to my attention!!
- Matt, Couple points:
- 1) For your success story, we had a very important one, and that is the Zion Bus duct Gabe Taylor procured a couple years ago from Zion Solutions through Oak Ridge Nat. Labs. Testing t he duct in our International High Energy Arc Fault (HEAF) program illustrated the problems with Aluminum HEAFs and is now going th rough the Generic Issues program. Please see Nick Melly and he can show you the test video.
- 2) There is a large number of items we could use for further testing, namely, any Electrical component (Bus duct, switchgear, etc.) containing aluminum or aluminum clad components. Switchgear and other assorted electrical enclosures for HRR testing. Installed electrical cables protected with fire retardant coating.
Gabe, could you please take the lead for our branch and contact Matt to discuss?
Please let me know if you require any additional information from me.
Thanx MHS M ark Henry Salley P.E.
Chief, Fi re and External Hazard Ana lysis Branch (FXHAB)
U.S. Nuclea r Regulatory Commission Office of Nuclear Regulatory Research Division of Risk Ana lysis W ashi ngt on, D.C. 20555-0001 Mail Stop: TW FN-10A12 Telephone: (301) 415-2474 FAX: (301) 415-6671 E-Ma ii: markhenry .sal ley@nrc.gov From: Koshy, Thomas Sent: Wednesday, February 22, 2017 2:28 PM Note to requester: The two images To: Salley, MarkHenry <MarkHenry.Sa lley@nrc.gov> above Thomas Koshy's name did
Subject:
FW: Harvesting Workshop not save when uploaded into NRC's Get into the process redaction software. The images are
- mages a photo of Thomas Koshy and the NRC seal.
I R lSl Thomas Koshy, Email: Thomas.Koshy:@nrc.gov
Note to requester: The yellow Tel: Number: 301-415-2154 highlighted portions were on the Room no: TWFN-10848 document as they were p rovided to MS TWFN-10A36 the NRC FOIA staff.
Instrumentation, Controls & Electrical Engineering Branch Division of Engineering, Office Of Research, USNRC From: Hiser, Matthew Sent: Wednesday, February 22, 2017 8:36 AM To: Sircar, Madh umit a <Madhumita.Sircar@nrc.gov>; Koshy, Thomas <Thomas Koshy@nrc gov>
Subject:
Harvest ing Workshop Hi Mita and Tom ,
Just to follow up from our d iscussions yesterday, I've attached the slides for the 3 presentations in Sessions 2-4 of the workshop. The slides are fairly brief and intended to quickly lay out our ideas and input, but leave plenty of time for discussion.
For data needs and sources of materials, please fill in any additional input you have for electrical or concrete topics . For harvesting experience and lessons learned, please take a look and add any additional insights you think we should include in our presentation.
I've also copied below the expectations we have provided to participants for each session for your reference and awareness:
- 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 20 minute presentations followed by open discussion of technical data needs for harvesting
- 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 5-1O 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 30 minute presentations followed by open discussion Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 1Office: TVvFN JOD62 Matt hew.Hiser@nrc.gov
NRC Perspective on Harvesting Experience and Lessons Learned
NRC Harvesting Experience
- RPV materials
- Shoreham, Midland
- Reactor vessel head CRDM penetrations
- North Anna, Davis-Besse
- Pressurizer from St. Lucie
- Reactor internals from Zorita
- Joint harvesting and testing project with EPRI and international
- Neutron absorbers from Zion
- Harvesting coordinated with DOE and EPRI; Independent NRC testing
- Concrete from Zorita
- Cables from Zion and Crystal River
Previous Benefits of Harvesting
- Reduce unnecessary conservatism
- Flaw distributions and Master Curve information came from harvested materials to support PTS rule
- Understand in-service flaws
- Mockups for NDE qualification
- Leak rate methodology from studying in-service flaws
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for research May be only practical source of representative aged materials, particularly if irradiation and temperature are important factors
- Achieving high fluence levels with representative irradiation conditions through other means is very challenging May be able to use limited harvested materials to validate larger accelerated aging data set
- Important to gain as much information as possible in advance before committing to specific harvesting project Ideally a bounding, yet broadly representative, material/environment Understand material information (CMTRs if available) and plant operating conditions
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effort
- Must balance cost with potential benefits carefully
- High technical relevance of materials is needed to ensure value
- Leveraging resources with other research organizations helps mitigate cost challenges
- Can introduce challenges for testing when aligning research priorities and interests of multiple organizations
- May be needed, particularly for expensive testing of irradiated materials
- Transporting irradiated materials, particularly internationally, is cumbersome and time-consuming
- Avoiding extra transport, especially between countries, is highly recommended
NRG High-Priority Data Needs for Harvesting
Metals
- Selected areas of interest for harvested materials:
- High fluence reactor internals
- >50 dpa 304 55 from high core outlet temp plant
- Bounding temperature and high fluence for void swelling
- Thermally aged unirradiated CASS
- >30 years at "'320°C; Validate accelerated aging data
- Moderate fluence (1-2 dpa) CASS
- Bolster technical basis for embrittlement in this fluence range
Metals
- High fluence vessel with relatively high levels of minor alloying elements (Mn, P, etc.)
- Through thickness section
- Measure fluence, toughness, and chemistry as a function of depth
- Validate fluence calculations
- Components with known flaws
- Example: weld overlays over known flaws
- Could be used for NDE evaluations or to assess effectiveness of mitigation techniques
- Components with limiting fatigue life
- Confirm fatigue calculations are accurate by inspecting for flaws
Electrical
- Cables
- Power cables energized and energized in normal operation
- Cables from in containment applications
- Electrical components lE MOVs from harsh and mild environments lE Air operated valves 4160 lE breakers lE Molded case breakers 480V, 250V DC, 125 VDC, lE Relays from mild environment GE - HFA, Agastat timing relays, any from Westinghouse, Potter Brumfield, Stuthers Dunn etc.,
- Other Electrical penetrations Batteries
Concrete
- High fluence irradiated concrete?
- ASR?
- Large sections for structural testing?
Sources of Materials Metals
- Examples of harvested materials used in NRC research programs:
Baral from Zion SS plate and welds from Zorita
- 30455 ranging from <1 to 50 dpa
- Alloy 600 J-groove weld from Davis-Besse
- Alloy 600 CRD nozzle from North Anna
- Shoreham, Midland
Electrical Concrete Recently Shutdown U.S. Plants Kewaunee W 2-loop 1772 39 2013 SONGS 2/3 CE 2-loop 3438 31/30 2013 Crysta I River 3 B&W 2609 36 2013 Vermont Yankee BWR-4/Mark-1 1912 42 2015 Fort Calhoun CE 2-loop 1500 43 2016
Planned Shutdown U.S. Plants Palisades CE 2565 47 2018 Pilgrim BWR-3/Mark-1 2028 47 2019 Oyster Creek BWR-2/Mark-1 1930 so 2019 Indian Point 2/3 W 4-loop 3216 48/46 2021 Diablo Canyon 1/2 W 4-loop 3411 40 2024-5
Additional Information from Plants
- Point of Contact
- Material information
- Fabrication records, CMTRs
- Operating history
- Temperature and fluence for components of interest
- Inspection records
- Components with known flaws
Notes to requester: The two images above Thomas Koshy's name did not save w hen uploaded into NRC's From: Koshy Thomas To: Hiser Matthew redaction software. The images are Cc: Sircar Madhumlta a photo of Thomas Koshy and the
Subject:
FW: Harvesting Workshop Date: Wednesday, February 22, 2017 2:36:08 PM NRC seal. Attachments to this email Attachments: NRCTechnical Data Needs for Harvestina,pptx are immediately following. The NRG Perspective on Harvestjna Experience and Lessons Learned ootx yel low highlighted portions were on sources of Materials optx imaaeoos joa the document as they were provided imaae006.jpg to the NRC FOIA staff.
For electrical, the slides cover the areas of interest Getting relevant documentation would be of great value mages I * [i]
Thomas Koshy, Email: Thomas.Koshy@nrc.gov Tel: Number: 301-415-2154 Room no: TWFN-10848 MS TWFN-10A36 Instrumentation, Controls & Electrical Engineering Branch Division of Engineering, Office Of Research, USNRC From: Sent: Wednesday, Feb rua ry 22, 2017 8:36 AM To: Sircar, Madh umit a < Koshy, Thomas <Thomas.Koshy@nrc.gov>
Subject:
Ha rvesti ng Workshop Hi Mita and Tom, Just to follow up from our discussions yesterday, I've attached the slides for the 3 presentations in Sessions 2-4 of the workshop. The slides are fairly brief and intended to quickly lay out our ideas and input, but leave plenty of time for discussion.
For data needs and sources of materials, please fill in any additional input you have for electrical or concrete topics. For harvesting experience and lessons learned, please take a look and add any additional insights you think we should include in our presentation.
I've also copied below the expectations we have provided to participants for each session for your reference and awareness:
-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 20 minute presentations followed by open discussion of technical data needs for harvesting
- 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 harves,ting experience 30 minute presentations followed by open discussion Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 / -4 /5-2454 1Office: 7WFN IOD62 Matthew Hiser@nrc gov
NRC Perspective on Harvesting Experience and Lessons Learned
NRC Harvesting Experience
- RPV materials
- Shoreham, Midland
- Reactor vessel head CRDM penetrations
- North Anna, Davis-Besse
- Pressurizer from St. Lucie
- Reactor internals from Zorita
- Joint harvesting and testing project with EPRI and international
- Neutron absorbers from Zion
- Harvesting coordinated with DOE and EPRI; Independent NRC testing
- Concrete from Zorita
- Cables from Zion and Crystal River
Previous Benefits of Harvesting
- Reduce unnecessary conservatism
- Flaw distributions and Master Curve information came from harvested materials to support PTS rule
- Understand in-service flaws
- Mockups for NDE qualification
- Leak rate methodology from studying in-service flaws
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for research May be only practical source of representative aged materials, particularly if irradiation and temperature are important factors
- Achieving high fluence levels with representative irradiation conditions through other means is very challenging May be able to use limited harvested materials to validate larger accelerated aging data set
- Important to gain as much information as possible in advance before committing to specific harvesting project Ideally a bounding, yet broadly representative, material/environment Understand material information (CMTRs if available) and plant operating conditions
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effort
- Must balance cost with potential benefits carefully
- High technical relevance of materials is needed to ensure value
- Leveraging resources with other research organizations helps mitigate cost challenges
- Can introduce challenges for testing when aligning research priorities and interests of multiple organizations
- May be needed, particularly for expensive testing of irradiated materials
- Transporting irradiated materials, particularly internationally, is cumbersome and time-consuming
- Avoiding extra transport, especially between countries, is highly recommended
NRG High-Priority Data Needs for Harvesting
Metals
- Selected areas of interest for harvested materials:
- High fluence reactor internals
- >50 dpa 304 55 from high core outlet temp plant
- Bounding temperature and high fluence for void swelling
- Thermally aged unirradiated CASS
- >30 years at "'320°C; Validate accelerated aging data
- Moderate fluence (1-2 dpa) CASS
- Bolster technical basis for embrittlement in this fluence range
Metals
- High fluence vessel with relatively high levels of minor alloying elements (Mn, P, etc.)
- Through thickness section
- Measure fluence, toughness, and chemistry as a function of depth
- Validate fluence calculations
- Components with known flaws
- Example: weld overlays over known flaws
- Could be used for NDE evaluations or to assess effectiveness of mitigation techniques
- Components with limiting fatigue life
- Confirm fatigue calculations are accurate by inspecting for flaws
Electrical
- Cables
- Power cables energized and energized in normal operation
- Cables from in containment applications
- Electrical components lE MOVs from harsh and mild environments lE Air operated valves 4160 lE breakers lE Molded case breakers 480V, 250V DC, 125 VDC, lE Relays from mild environment GE - HFA, Agastat timing relays, any from Westinghouse, Potter Brumfield, Stuthers Dunn etc.,
- Other Electrical penetrations Batteries
Concrete
- High fluence irradiated concrete?
- ASR?
- Large sections for structural testing?
Sources of Materials Metals
- Examples of harvested materials used in NRC research programs:
Baral from Zion SS plate and welds from Zorita
- 30455 ranging from <1 to 50 dpa
- Alloy 600 J-groove weld from Davis-Besse
- Alloy 600 CRD nozzle from North Anna
- Shoreham, Midland
Electrical Concrete Recently Shutdown U.S. Plants Kewaunee W 2-loop 1772 39 2013 SONGS 2/3 CE 2-loop 3438 31/30 2013 Crysta I River 3 B&W 2609 36 2013 Vermont Yankee BWR-4/Mark-1 1912 42 2015 Fort Calhoun CE 2-loop 1500 43 2016
Planned Shutdown U.S. Plants Palisades CE 2565 47 2018 Pilgrim BWR-3/Mark-1 2028 47 2019 Oyster Creek BWR-2/Mark-1 1930 so 2019 Indian Point 2/3 W 4-loop 3216 48/46 2021 Diablo Canyon 1/2 W 4-loop 3411 40 2024-5
Additional Information from Plants
- Point of Contact
- Material information
- Fabrication records, CMTRs
- Operating history
- Temperature and fluence for components of interest
- Inspection records
- Components with known flaws
Note to requester:
Attachments to this email From: Tregoning Robert are immediately following .
To: Hiser Matthew Subject : FW: Harvesting Workshop Slides Date: Wednesday, March 01, 2017 3:12:03 PM Attachments: NRC Persoectlve on Harvestina Exoerience and Lessons Learned.ootx.
NRC Technical Data Needs for* Harvestina.ootx Sources of Materlals.pptx.
So have we gotten everything we need from everyone?
Robert Tregoning Technical Advisor for Materia Is US Nuclear Regulatory Commission Two White Flint North, M/5 T-10 A36 11545 Rockvi lle Pike Rockville, MD 20852-2738 ph: 301-415-2324 fax : 301-415-6671 From: Hiser, M at t hew Sent: Wednesday, M arch 01, 2017 3:06 PM To: Sircar, Madhumita <Madhumita.Sirca r@nrc.gov>; Pires, Jose <Jose .Pires@nrc.gov>; Seber, Dogan <Dogan .Seber@nrc.gov>; Philip, Jacob <Jacob.Philip@nrc.gov>; Ray, Sheila
<Shei la.Ray@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Taylor, Gabriel
<Gabriel.Taylor@nrc.gov>; M urdock, Darrell <Darrell .Mu rdock@nrc.gov>; Kirk, M ark
<Mark.Kirk@nrc.gov>
Cc: Tregoni ng, Robert <Robert.Tregoning@ nrc.gov>; Pu rtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
Ha rvesti ng Workshop Slides Thank you for your input on t he NRC slides for t he harvesting workshop. I have incorporated all comments and input received and attached t he latest version of t he sl ides to be presented next week.
Thanks!
M att
NRC Perspective on Harvesting Experience and Lessons Learned
NRC Harvesting Experience
- RPV materials
- Shoreham, Midland
- Reactor vessel head CRDM penetrations
- North Anna, Davis-Besse
- Pressurizer from St. Lucie
- Reactor internals from Zorita
- Joint harvesting and testing project with EPRI and international
- Neutron absorbers from Zion
- Harvesting coordinated with DOE and EPRI; Independent NRC testing
- Concrete from Zorita
- Cables from Zion and Crystal River
Previous Benefits of Harvesting
- Reduce unnecessary conservatism
- Flaw distributions and Master Curve information came from harvested materials to support PTS rule
- Understand in-service flaws
- Mockups for NDE qualification
- Leak rate methodology from studying in-service flaws
- Identify and better understand safety issues
- High-energy arc fault tests on aluminum electrical components
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for research May be only practical source of representative aged materials, particularly if irradiation and temperature are important factors
- Achieving high fluence levels with representative irradiation conditions through other means is very challenging May be able to use limited harvested materials to validate larger accelerated aging data set
- Important to gain as much information as possible in advance before committing to specific harvesting project Ideally a bounding, yet realistic, material/environment Understand material information (CMTRs if available) and plant operating conditions
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effort
- Must balance cost with potential benefits carefully
- High technical relevance of materials is needed to ensure value
- Leveraging resources with other research organizations helps mitigate cost challenges
- Can introduce challenges for testing when aligning research priorities and interests of multiple organizations
- May be needed, particularly for expensive testing of irradiated materials
- Transporting irradiated materials, particularly internationally, is cumbersome and time-consuming
- Avoiding extra transport, especially between countries, is highly recommended
NRG High-Priority Data Needs for Harvesting
Metals
- RPV High fluence & high shift vessel with well-established unirradiated properties (or a means to estimate them)
- Through thickness section to validate fluence & attenuation models
- Measure fluence, toughness, & chemistry as a function of through-thickness position Samples from virtually any vessel
- Of sufficient size to enable measurement of both the Charpy transition curve and master curve transition temperature TO
- Th is testing
- Enables demonstration of the conservatism of regulatory approaches for transition temperature prediction
- Provides data supporting evolution from the use of correlative (Charpy-based) to direct measurement (fracture toughness-based) approaches
Metals
- CASS and Internals High fluence reactor internals
- >50 dpa 304 SS from high core outlet temp plant
- Bounding temperature and high fluence for void swelling
- Thermally aged unirradiated CASS
- >30 years at "'320°C; Validate accelerated aging data
- Moderate fluence {1-2 dpa) CASS
- Bolster technical basis for embrittlement in this fluence range
- Components with known flaws
- Example: weld overlays over known flaws
- NDE evaluations or to assess effectiveness of mitigation techniques
- Components with limiting fatigue life
- Confirm fatigue calculations are accurate by inspecting for flaws
Electrical
- Cables Power cables energized and de-energized in normal operation Cables from in containment applications Cables protected with fire retardant coating
- Electrical components lE MOVs from harsh and mild environments lE Air operated valves; 4160 lE breakers lE Molded case breakers 480V, 250V DC, 125 VDC, lE Relays from mild environment GE - HFA, Agastat timing relays, any from Westinghouse, Potter Brumfield, Stuthers Dunn etc.,
Electrical penetrations; Batteries
- Fire research interest Electrical enclosures
Concrete
- Structures exposed to high radiation
- Post-tensioned structures
- Corrosion of reinforcing steel, tendon, liner, embedment
- Spent fuel pool and transfer canal-boric acid attack on concrete in PWRs
- Alkali Aggregate Reaction
- Large structural sections for testing
Sources of Materials Metals
- Examples of harvested materials used in NRC research programs:
- Baral from Zion
- SS plate and welds from Zorita
- PWSCC
- Alloy 600 J-groove weld from Davis-Besse
- Alloy 600 CRD nozzle from North Anna
- Alloy 182/82 from VC Summer
- RPV
- Shoreham, Midland
Electrical
- Zion
- 4.16kV non-segregated bus duct
- Used in NRC / OECD High Energy Arc Fault Testing
- Bellefonte
- 8 Electrical enclosures
- Used in NRC very early warning fire detection testing (NUREG-2180)
- Used in NRC heat release rate testing (NUREG/CR-7197)
Recently Shutdown U.S. Plants Kewaunee W 2-loop 1772 39 2013 SONGS 2/3 CE 2-loop 3438 31/30 2013 Crysta I River 3 B&W 2609 36 2013 Vermont Yankee BWR-4/Mark-1 1912 42 2015 Fort Calhoun CE 2-loop 1500 43 2016
Planned Shutdown U.S. Plants Size Years in Planned Plant Design
{MWt} Operation Shutdown I
Palisades CE 2565 47 2018 Pilgrim BWR-3/Mark-1 2028 47 2019 Oyster Creek BWR-2/Mark-1 1930 so 2019 Indian Point 2/3 W 4-loop 3216 48/46 2021 Diablo Canyon 1/2 W 4-loop 3411 40 2024-5
Additional Information from Plants
- Point of Contact
- Drawings and plant design information
- To understand location of components within plant
- Size and dimensions of components
- Operating history
- Environmental information (e.g., temperature, fluence, humidity, pressure, etc.) for components of interest
- Material information
- Fabrication records, CMTRs
- Inspection records
- Components with known flaws
Note to requester:
Attachment to th is email is immediately follow ing.
From : Frankl Istvan To: Thomas Brian Cc: Tregoning Robert; Nakoski John; Hiser Matthew: Purtscher Patrick Subject : FW: Harvesting Workshop talking points.docx Date: Monday, March 06, 2017 1:13:00 PM Attachme nts : Harvestina Workshop talking ooints.docx Importance: High
- Brian, Rob and CMB staff have provided the attached draft talking points for Mike Weber's use tomorrow.
Please let me know if you need additional information or clarifications.
- Thanks, Steve From: Tregoning, Robert Sent: Monday, March 06, 2017 11:33 AM To: Frankl, Istvan <lstvan.Fra nkl@nrc.gov>
Cc: Purtscher, Patrick <Pat rick. Purtscher@nrc.gov>; Hiser, Matthew <M atthew.Hiser@nrc.gov>
Subject:
Ha rvesti ng Workshop t alking points.docx Steve:
Here are some talking points that Mike can use to introduce the workshop tomorrow. I think it's best if it comes through your branch so please forward it to Brian/John so that they can send it along to Mike. Let me know if you have any questions.
- Cheers, Rob
Ex-Plant Materials Harvesting Workshop Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning pla nts, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, iriradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting prog rams to be initiated.
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking available materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers Workshop Approach:
- Each session will consist of solicited presentations followed by lengthy discussion and Q&A period.
Note to requester: Attachment From: Frankl Istvan to this email is immediately To: Hiser Matthew; Purtscher Patrick following.
Subject:
FW: Harvesting Workshop talking points.docx Date: Monday, March 06, 2017 11:38:00 AM Attachments: Harvesting Workshop talki ng oolnts.docx.
Importance: High Matt, Pat, Are you OK with Rob's inputs? Any revisions/ additions?
Please let me know ASAP.
- Thanks, Steve From: Tregoning, Robert Sent: Monday, March 06, 2017 11:33 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Hiser, Matthew <Matthew. Hiser@nrc.gov>
Subject:
Harvesting Workshop talking points.docx Steve:
Here are some talking points that Mike can use to introduce the workshop tomorrow. I think it's best if it comes through your branch so please forward it to Brian/John so that they can send it along to Mike. Let me know if you have any questions.
- Cheers, Rob
Ex-Plant Materials Harvesting Workshop Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning pla nts, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, iriradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting prog rams to be initiated.
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking available materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers Workshop Approach:
- Each session will consist of solicited presentations followed by lengthy discussion and Q&A period.
Note to requester: Attachment to this email is immediately following . The From: HJser Matthew email document was provided to the To: Tregoning Robert; Purtscher Patrick NRC FOIA staff with the yellow text
Subject:
FW: ACTION: One-pager on the Harvesting Workshop highlighted.
Date: Friday, March 24, 2017 11 :44:34 AM Attachments: Harvesting One Pager.doc)(
Hi Rob and Pat, Here is my first stab at t he harvesting one-pager St eve ment ioned below. Please take a look and ed it as needed and I'll send back t o Steve.
Thanks!
M at t From: Frankl, Istvan Sent : Monday, M arch 20, 2017 5:24 PM To: Hiser, Matthew <M atthew .Hiser@nrc.gov>
Subject:
ACTION: One-pager on t he Harvesting Workshop
- Matt, One of the action items that came out of the bi-weekly CMB/CIB status meeting today was Brian's request for a DE "one-pager" on the harvesting workshop.
Please align on this with Rob and get a draft to me for review by next Monday.
- Thanks, Steve
Ex-Plant Materials Harvesting One-Pager M otivation:
- Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in t he lab, which reduces the uncertainty associated with the applicability of the aging conditions.
o With the wave of 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 research would support regulatory decisions for subsequent license renewal (SLR), and could have implications for the current license period depending on the findings.
o There is a task in the new draft UNR for SLR from NRR/DLR requesting RES to investigate opportunities for harvesting where appropriate.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated, leveraging lim ited NRC resources to produce highly representative technical data of materials degradation for extended plant operation.
W orkshop Summary:
- 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. Views and insights from various parties contributed to the discussion
- Workshop participants gave presentations and actively engaged in open discussion of different aspects of ex-plant materials harvesting o Sessions covered motivation for harvesting, data needs, sources of materials, lessons learned, the practical aspects of harvesting, and harvesting decision-making and planning
- 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 to be addressed is clearly defined and addressed by the planned harvesting project.
- The insight s from the utility and decommissioning contractor perspective were extremely valuable t o the discussion.
o NRC staff and stakeholders are better informed and aware of the benefits and challenges associated with ex-plant harvesting.
Path Forward:
- Detailed workshop summary report to be distributed among meeting participants by May 2017
- PNNL report on a strategic approach to ex-plant harvesting to be complete by May 2017
- Internal alignment within NRC on prioritization of harvesting data needs in four primary areas:
o RPV, internals and other metals, electrical, concret e
- RES staff will engage with interested workshop participants on prioritizing data needs and sources of materials database
Note to requester: Attachment to From: Iyengar Raj this email is immediately following .
To: Hiser Matthew Cc:
Subject:
FW: 2016-NRR-UNR-Draft-May 2016.docx Date: Wednesday, May 18, 2016 10:40:45 AM Attachments: 2016-NRR-UNR-Dralt-Mav 2016 docx
Raj From: Iyengar, Raj Sent: M onday, M ay 16, 2016 3:21 PM To: Hu ll, Amy <Amy.Hul l@nrc.gov>; Frankl, Istvan <lstvan. Frankl@nrc.gov>
Subject:
2016-NRR-UN R-Draft-May 2016.docx Steve/Amy, Attached is a draft version of the new UNR, prepared for NRR. This is only the enclosure for the UNR memo. The memo will contain information about staff-level and management-level coordination and the POCs. I will prepare the memo, if NRR wants us to.
For now, please take a look at the five tasks in the attached.
The background section has more information than needed. We can let NRR tailor the background section to fit their style.
I have discussed this with Amy. (Steve, Perhaps, you can wait until Amy reviews it) .
I may provide a courtesy copy to Rob after I incorporate CMB comments.
Raj
Research Request Evaluate Aging Management of systems, structures, and components (SSCs) during a Subsequent License Renewal (SLR) Period
Background:
Although the NRC staff can accept subsequent license renewal applications now, the review would be based on guidance provided in NUREGs-1800 and -1801. Because the guidance in these NUREGs is based on plant operation from 40-60 years, additional review would be needed to ensure that the applicant addressed issues unique to 60-80 years of plant operation for subsequent license renewal. Such reviews would be longer and more resource-intensive.
In cooperation with the DOE Light Water Reactor Sustainability (LWRS) Program, the NRC completed NUREG/CR-7153, "Expanded Materials Degradation Assessment (EMDA), Vol. 1-5" (ADAMS Accession Nos. ML14279A321 , ML14279A331, ML14279A349, ML14279A430, ML14279A461 ), to identify the most significant technical issues for nuclear power reactor operations beyond 60 years. The EMDA ranked the significance, current knowledge, and uncertainty associated with aging-related degradation phenomena that could affect systems, structures, and components over 80 years of operation. As outlined in the SRM on SECY 14-0016, the major technical issue areas are:
- Reactor pressure vessel neutron embrittlement at high fluence;
- Irradiation assisted stress corrosion cracking of reactor internals and primary system components;
- Concrete and containment degradation; and
- Electrical cable qualification and condition assessment.
For SLR, the staff used NUREG-1800 and NUREG-1801 as the basis for developing tlhe guidance for SLR applicants and NRC staff. The development of the guidance was based on an evaluation of domestic and international operating experience of nuclear plants, lessons learned from staff review of previous license renewal applications, and assessment of recent research findings. The guidance documents were issued in mid-December of 2015, as draft "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report,"
(NUREG-2191 , Volumes 1 and 2) and draft "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants" (SRP-SLR) (NUREG-2192).
Since the draft guidance documents were issued, the staff has held several public meetings with stakeholders and the public to discuss the proposed revisions and bases for the revisions. The most recent meetings were held on January 21 and February 19, 2016. Going forward, the NRC staff will continue to lead outreach activities to stakeholders and the public in order to provide information on the proposed changes to the guidance documents, solicit feedback on the documents, and revise the documents, as appropriate, to reflect stakeholder and public feedback. The final guidance documents are expected to be issued in mid-2017.
To support the review of an SLR application, an applicant will need to demonstrate how the effects of aging will be managed, including those associated with the technical issues listed above. Although the industry is conducting research to address these major technical issues for
SLRs, not all the research w ill be completed before the first application is submitted. For those issues that the industry has not yet developed a generic t,echnical basis to support its resolution, the NRC will request applicants to address the technical issues with plant-specific programs in their SLR applications. The staff will review these plant-specific programs that address the SLR technical issues, but anticipates a longer application review process in these cases.
The requested research described below would provide information to support the staff in effectively evaluating aging management practices and developing staff positions to augment staff's preparedness for the evaluation of the feasibility of future applications for an SLR period.
These requested products should build upon analysis methods, tools, and expertise developed as part of ongoing research activities and new research activities focused specifically on aging effects during an SLR period of extended operation (i.e., 60 to 80 years).
Description of Scope and Tasks A. Hold NRC/industry workshop(s) on status of domestic and international research activities and operating experience to address and evaluate tlile status of materials degradation issues, identified in the EMDA reports, for a subsequent license renewal Technical Need: In February 2008, the NRC and DOE co-sponsored a "Workshop on U.S.
Nuclear Power Plant Life Extension Research and Development" (ADAMS Accession Number ML080570419), which requested stakeholder input into aging management research areas for "Life Beyond 60." Since then, there have been multiple workshops/meetings on the research activities, as well as on operating experience, regarding aging management of SSCs for a SLR period of operations. These meetings have been helpful in facilitating technical discussions, disseminating knowledge and information, and enabling the understanding of technical challenges, and paving the path-forward for resolution of the challenges and issues related to materials degradation during the SLR period of operations. As the NRC staff prepare for the review of the future SLR submittals, there is a need for continued engagement with domestic nuclear industry and other industries, DOE and other federal organizatio ns, academia, international partners, and interested public stakeholders, through workshops targeted toward the status and resolutions of major technical issues outlined in the SRM and identified in EMDA.
Deliverable: RES staff should facilitate several workshops/meetings on operating experience from the initial license renewal period, research results on materials degradation issues and aging management of SSCs during a SLR period of operations. These meetings should specifically be targeted toward the resolution of technical issues for effective aging management of SSCs for a SLR period of operations. RES staff should provide an annual technical letter report summarizing the understanding gained through the workshops/meetings. The summary should include the status of domestic and international research activities in addressing materials degradation issues and aging management practices for an SLR period of operations.
The report should also discuss (1) areas of progress and issues resolution, (2) areas of insufficient progress that may warrant additional NRC interactions, and (3) any newly identified technical issues that should be considered for an SLR period of operations.
Schedule: The effort should last no more than 36 months from the period of inception of this user need request.
B. Provide RES staff assessments of the current knowledge and disposition of materials degradation issues identified in the EMDA documents Technical Need: As mentioned earlier, the EMDA volumes identified significant technical issues for nuclear power reactor operations beyond 60 years related to materials degradation. The major materials degradation issues fall under the following four topical areas, as outlined in SRM on SECY 14-0016:
Reactor pressure vessel neutron embrittlement at high fluence; Irradiation assisted stress corrosion cracking of reactor internals and primary system components; Concrete and containment degradation; and
- Electrical cable qualification and condition assessment.
The NRC, DOE, and industry are addressing the key technical issues related to materials degradation at NPPs, in order to gain better understanding of the materials aging and degradation mechanisms and their implications of structural and component integrity. DOE/LWRS and the industry have initiated numerous research activities on the four major technical areas. The NRC staff conducts confirmatory research, through several user need requests on specific technical issues, to independently verify licensee data, determine safety margins, and explore uncertainties. Results from NRC's research will be used, in part, to confirm the adequacy of industry's technical basis for SLR and the associated AMPs. The AMPs are cornerstones for managing materials degradation in SSCs during SLR. In addition, the NRC research will support and increase the efficiency of staff review of SLR applications. To fully support the staff review of the SLR applications, RES should develop staff assessments of the current knowledge and disposition of materials degradation issues related to the four major technical areas. The assessments should also include recommendations on the need for:
- any interim staff guidance (ISG) to address aging management issues, and
- new regulatory guidance and/or revision of existing ones to address uncertainties in knowledge and/or potential non-conservativisms.
Deliverable: Deliver a technical letter report that summaries the state-of-knowledge and current knowledge and disposition of materials degradation issues identified in EMDA. The report should also include recommendations on the need for any new or revised guidance to address component integrity of aging structures.
Schedule: The effort should last no more than 36 months from the period of inception of this user need request. The initial draft report should be completed by the end of FY 2018.
C. Develop a long-term strategy for obtaining information from decommissioned NPPs as well as from ex-plant components from operating plants.
Technical Need: The NRC maintains operating experience databases and also has access to industry and international operating experience databases which deal
with failures of SSCs experienced during plant operation. Because the first plants have just recently entered the initial renewed license operating period, there is limited operating experience information specifically related to aging management issues. To address this gap, research activities are in place to obtain materials degradation data through laboratory tests. However, obtaining data from materials harvested from decommissioned plants and ex-plant components will be crucial bridging the gap between data obtained from simulated experiments in laboratory and service-life components. This 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. Thus, the NRC needs to keep abreast of opportunities to recover materials from plants that are being decommissioned or from ex-plant components.
Based on the recent experience of recovering materials from the decommissioned plants, such as Zion and Crystal River, the efforts of planning, coordination and eventual collection of these materials could be resource-intensive and time-challenging. Future efforts to retrieve materials from decommissioned plants could be accelerated by pro-actively developing a strategic database for obtaining unique and significant materials aging degradation information from diverse sources. Such a database will enable the NRC to expeditiously obtain materials and components from plants to be decommissioned in the near future and develop information and knowledge to access the efficacy of the AMPs.
Deliverable: RES should develop a strategic database containing information on:
- unique and significant materials aging degradation diverse sources (operating experience, other nuclear facilities, other long-lived industrial plants, other materials organizations such as ASM and NACE), and
- materials that can be harvested from to-be-decommissioned NPPs and ex-plant components from operating plants to better inform the NRC's AMPs and aging-related regulatory oversight and to better plan research activities.
RES should deliver periodic reports assessing the effectiveness of such programs and recommending any improvements for a subsequent license renewal period.
Schedule: The effort should last no more than 36 months from the period of inception of this user need request.
D. Continue to Develop Domestic and International Partnerships to Share Expertise, Capabilities and Resources Related to Aging Management Research for Long-Term Operations (LTO)
Technical Need: Various domestic and foreign research organizations, government agencies, utilities and research organizations are presently engaged in aging management research, the results of which may be of value to the NRC regarding plant operations during a subsequent license renewal period. Additionally, th,e Electric Power Research Institute (EPRI) is engaged with various international research organizations to develop data on aging mechanisms/effects. As such, it benefits the agency to be engaged in domestic and international research partnerships in order to evaluate all available operating experience and relevant research, leverage resources
and minimize unnecessary duplication of efforts. It would be advantageous to the agency to develop partnerships with these entities such that the various research programs could be better coordinated and focused on high-priority needs.
Deliverable: Continue to develop agreements with domestic and international pairtners to collaborate on aging management research that results in information to help inform agency decisions regarding a subsequent license renewal and long-term operations.
Integrate as appropriate the results of these collaborative research and information exchanges from international partnerships into Tasks A and B. Provide an annual summary of international collaborative research results and status of interactions (e.g., references to meeting minutes, presentations, technical reports, etc.),
highlighting international activities and results that may affect a subsequent license renewal.
Schedule: The effort should continue until the closure of this user need request.
G. Provide technical assistance, as needed, for preparation of review of SLR applications.
Technical Need: As the NRR staff prepares for the anticipated SLR application in FY18, technical assistance from RES staff on emergent issues may be needed. Such issues may include, but not restricted to, technical suppo1rt for aging management program audits, public meetings related to communication efforts, and confirmatory reviews of licensee submittals.
Schedule: The effort, as needed, should continue until the closure of this user need request.
Notes to requester: Attachment to this email is immediately following. The email that was From: HJser Matthew To: Purtscher Patrick provided to the NRC FOIA staff
Subject:
FW: Request: Need a couple of bullets on Harvesting workshop contained the red text.
Date: Thursday, May 18, 2017 8:26:00 AM Attachments: Draft Talking Points for Brian Thomas for EPRI R2.docx How do these look Pat?
Participants discussed motivation for harvesting, data needs best addressed by harvesting, sources of materials for harvesting and future harvesting program planning.
o Workshop discussion emphasized the high cost and complexity of performing harvesting, which requires a clearly defined objective to justify the level of effort and demonstrate value.
- Workshop summary report will be shared among meeting participants. Future activities from the workshop include cooperative discussion of prioritized data needs for harvesting and development of a sources of materials database.
Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Me1allurgy Branch Phone: 30/-4/5-24541 Of/ice: 7WFN /OD62 Matthew.Hiser@nrc.gov From: Moyer, Carol Sent: Thursday, May 18, 2017 8:15 AM To: Hiser, Matthew; Purtscher, Patrick
Subject:
Request: Need a couple 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 caroLmover@nrc.gov 301-4 15-2153
Draft Talking Points for Brian Thomas for EPRI-NRC Meeting (6/6/2017}
9:30 AM - Long Term Operation {LTO) Beyond 60 Years, Subsequent License Renewal
- The MOU for Long Term Operations Beyond 60 Years extends through Sept., 2021
- NRC appreciates EPRl's active participation in the April Commission briefing
- Biweekly coordination calls (EPRI/NRC/DOE) are successful Progress and readiness for SLR applications
- As reported at the April 261h Commission briefing, NRC is ready to accept applicatio ns.
- Confirmatory research continues, to reduce uncertainty associated with key technical issues.
Public workshop on SLR topics
- At least two workshops are proposed, to include domestic and international participants.
- Fall 2018- Focused on reactor pressure vessels, vessel internals, and piping
- Spring 2020 - Focused on concrete and electrical cable degradation
- Proposed scope of the workshops:
o State of knowledge on the technical issues o Status of on-going research on materials degradation and aging management o New operating experience with implications for LR and SLR Technical reports on continued adequacy of RG 1.99 Highlights of harvesting workshop Research priorities for 2017-2018 10:45-Advanced Reactor Safety Research IAP status
- RES/DSA is supporting IA P-2 (computational codes)
Draft Talking Points for Brian Thomas for EPRI_ R2.docx 11/22/19 15:28
Computational codes for non-LWRs Advanced manufacturing
- Advanced processes, such as additive manufacturing (3D printing), diffusion bonding, friction-stir welding, and powder metallurgy (PM-HIP) have been proposed for use in new reactors.
- Some advanced manufacturing processes may introduce uncertainty in component inspections (pre-service and in-service). Components may be susceptible to flaw types or degradation mechanisms previously unseen in LWRs .
Gen IV materials
- RES/DE (and NRO) are participating in ASME B&PV Code committees working on high temperature materials needed for some advanced reactor designs.
o Alloy 617 o Graphite
- ASME Code is also seeking to expand the temperature range for use of some materials by supplying confirmed materials property data under a broader range of test conditions.
- NRC is collaborating with DOE-NE to avoid surprises in material selection and the establishment of technical bases for the use of newer materials and processes .
11 :15 - xLPR and Leak-Before-Break (LBB) Analyses Current status of MOU development 2:00 - Digital Instrumentation & Control Collaboration Progress during previous year Priorities for 2017-2018 Draft Talking Points for Brian Thomas for EPRI_ R2.docx 11/22/19 15:28
Draft Talking Points for Brian Thomas for EPRI_ R2.docx 11/22/19 15:28
Note to requester:
Attachment to this email is immediately following.
From: HJser Matthew To: Murdock Darren Subject : FW: Ex-Plant Materials Harvesting Date: Wednesday, May 27, 2015 9:55:00 AM Attachments: Harvesting Efforts Hiser June NRC-lndustrv materials mtg 5-27-15.ootx Hi Darrell, Could you take a quick look at Slide 9 on cable harvesting?
Thanks!
Matt Matthew Hiser Materials Engineer Corrosion and Metallurgy Branch Division of Engineering Office of Nuclear Regulatory Research 301-251-7601 From: Hiser, Matthew Sent: Thursday, May 21, 2015 3:51 PM To: Focht, Eric; Murdock, Darrell; Sircar, Madhumita Cc: Hull, Amy
Subject:
RE: Ex-Plant Materials Harvesting Hi All, Here is the current draft of the presentation. Can you fill in the relevant information for your projects on slides 7-9? Amy, can you fill in your slides as appropriate related to approach and engagement?
Thanks!
Matt Matthew Hiser Materials Engineer Corrosion and Metallurgy Branch Division of Engineering Office of Nuclear Regulatory Research 301-251-7601 From: Hiser, Matthew Sent: Friday, May 15, 2015 8 :21 AM To: Focht, Eric; Murdock, Darrell; Sircar, Madhumita Cc: Hull, Amy
Subject:
Ex-Plant Materials Harvesting Hi Mita, Darrell, and Eric, I am working with Amy Hull in my branch on an effort associated with strategic harvesting of ex-plant materials. This effort is just getting underway, but we would like to present the concept at an NRG-industry materials meeting in early June (see attached email). T he purpose of this effort is to develop a more systematic proactive "strategic" approach to ex-plant material harvesting, rather than the more reactive opportunistic approach to date. It is important to share this concept with industry, since they will be vital in providing connections/communication to allow future harvesting projects to take place.
I am putting together a slide or two on the reactor internals materials harvesting project at Zorita that I am involved with. I understand each of you have been / are involved with other harvesting efforts at Zion and Zorita on cables, concrete, and neutron absorbers. If you could just provide a slide or two with a high-level overview of the harvesting project and at least briefly touch on how the harvesting opportunity came together, that would be great.
Thanks!
Matt
Strategic Approach for Obtaining Material and Component Aging Information Amy Hull and Matthew Hiser Division of Engineering Office of Nuclear Regulatory Research 1
Outline
- Purpose
- Background
- Harvesting Experience
- Approach
- Engagement with Other Stakeholders 2
Purpose
- Create a framework for a strategic approach to harvesting ex-plant materials
- Ex-plant materials offer unique environmental exposure that cannot be entirely replicated by laboratory testing with fresh materials
- Combine high priority data needs identified in SLR/LTO activities with harvesting opportunities from decommissioning plants 3
Background
- To date, harvesting opportunities have been limited due to few decommissioning plants
- Zion in U.S., Zorita in Spain
- However, several U.S. plants have already shut down or are planning to do so in the near future
- Kewaunee, SONGS, Crystal River, Vermont Yankee, Oyster Creek
- This provides a unique opportunity to plan harvesting for the maximum utility to address the highest priority technical issues 4
Harvesting Experience
- Past harvesting efforts have generally involved a reactive decision-making process
- Limited opportunities to acquire ex-plant materials
- Limited strategic planning for harvesting
- Harvesting projects with NRC involvement:
- Reactors internal materials from Zorita
- Concrete from Zorita
- Neutron absorber material from Zion
- Cables from Zion and Crystal River 5
Zorita Internals Research
- Materials Harvested:
- Baffle plate and core barrel weld materials
- Scope:
- Mechanical testing (tensile, CGR, FT)
- Microstructural characterization (void swelling)
Purpose:
- High-fluence (up to 50 dpa) IAD effects with representative LWR exposure conditions
- Timeline:
- Initial discussions in 2006, harvesting in 2013, testing ongoing
- Coordination:
- EPRI, international consortium, Studsvik, Halden 6
Neutron Absorbers from Zion
- Materials Harvested:
- Select Baral NAM panels from Regions 1 and 2 of the Zion SFP
- Scope:
- Visual and microstructural examinations (incl. areal density)
...... Corrosion testing
Purpose:
- Identify degradation mechanisms
- Estimate degradation rate
- Confirm results of in-situ areal density measurements
- Timeline:
- Initial discussions in 2014, harvesting in 2015, testing in 2015-2016
- Coordination:
- EPRI, ZionSolutions, SRN L 7
Concrete from Zorita (Plan)
- Materials Harvested:
- Concrete from structures that are in close proximity to RPV
- Scope:
Mechanical testing (compressive, tensile, modulus of elasticity)
...... M icrostructu ra I characterization
- Physical change
Purpose:
- High fluence in combination with temperature and humidity that are representative of LWR environment effects on structural and shielding performance
- Timeline:
- Initial discussions in 2014, harvesting in 2015, testing 2016-2018
- Coordination:
- NRC, ENRESA and CSN 8
Cables from Zion and Crystal River
- Materials Harvested:
- Cables (high/ low voltage??)
- Scope:
- Condition monitoring to assess cable performance under normal operating conditions (accelerated aging) and accident conditions
Purpose:
- Cable degradation due to normal operating environment and accident conditions
- Timeline:
- Initial discussions in ????, harvesting in 2013/2015, testing ongoing -
2017
- Coordination:
- ORNL, Zion Solutions, NIST, EPRI 9
Approach 10
Stakeholder Engagement 11
Acknowledgements
- Robert Tregoning, RES/DE
- Eric Focht, RES/DE
- Darrell Murdock, RES/DE
- Mita Sircar, RES/DE 12
Notes to requester:
Attachment to this email is immediately following . The email was provided to the NRC From:
FOIA staff with the highlighted To: Hiser Matthew
Subject:
FW: ACTION: Division Review of EPRI MOU Addenda & Respons.e Tlmellne portions.
Date: Tuesday, June 14, 2016 7:39:40 AM Attachments: Cover Letter lor NRC-EPRI MOU 2016 Renewal.doc~
DRAFT NBC EPBI MOU Renewal 201 s docx ADDENDUM Template.doc~
EPRI MOUs 06 16.xlsx I mportance: High Do you want something in here for harvesting?
From: Frankl, Istvan Sent: Monday, June 13, 2016 4:09 PM To: Focht, Eric <Eric.Focht@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>;
Oberson, Greg <Greg.Oberson@nrc.gov>
Subject:
ACTION: Division Review of EPRI MOU Addenda & Response Timeli ne Importance: High
- All, Please review the enclosed request from our TA and let me know ASAP if the addendum/addenda for which you are the POC, needs revision, and if so, please provide update to me no later than Monday, June 20.
Based on our earlier communication on this topic my current understanding is that our addenda do not need revisions but please confirm to me ASAP.
- Thanks, Steve From: Berrios, Ilka Sent: Monday, June 13, 2016 3:53 PM To: Rudland, David <David.Rudland@nrc.gov>; Frankl, Istvan <lstvan,Frankl@orc.gov>; Ake, Jon
<Jon Ake@nrc gov>; Jung, Ian <Ian Jung@nrc gov>; Burke, John <John Burke@nrc fNY>; Tregoning, Robert
<Robert Jregoning@nrc gov>
Cc: Focht, Eric <Eric.Focht@nrc gov>; Miller, Kenneth A <Kenn,Miller@nrc.gov>; Hull, Amy
<Amy.Hull@nrc gov>; Iyengar, Raj <Raj.lyengar@nrc.gov>; Oberson, Greg <Greg.Oberson@nrc gov>
Subject:
Division Review of EPRI MOU Addenda & Response Timeline
- All, Attached are the draft cover letter and EPRI MOU that is being developed to support the renewal activity. As you are aware, there are a number of Addenda that expire on Sept 30, 2016, that maybe renewed, modified or cancelled as part of this activity. Hopefully, most addenda will only require updating the expiration date and POCs. A few may require scope modifications to complete these updates and interaction with EPRI counterparts on those revisions. Last attachment contains a list of recent EPRI Addenda. Attached is also a template for a simple Addendum renewal (it is based on ML101270008).
Could you please provide you input by 06/28/2016? Please let me know if you have any questions.
Acquisition and Testing of Zion Spent Fuel Pool September 30, 2016 Eric Focht, DE Neutron Absorber Materials Aging, Qualification and Condition Monitoring of September 30, 2016 Kenn Miller, DE Electrical Cables Digital l&C and Human Factors September 30, 2016 Ian Jung,DE / Sean Peters, DRA Long Term Operations Beyond 60 Years September 30, 2016 Amy Hull, Raj Iyengar DE Primary Water Stress Corrosion Cracking
- Crack September 30, 2016 Erick Focht, Greg
Initiation Testing Oberson DE Primary Water Stress Corrosion Cracking Expert September 30, 2016 Greg Oberson, DE Panel Activities Rob Tregoning, DE Seismic Risk (renewal) September 30, 2016 Jon Ake, DE Cooperative Nuclear Safety Research, Extremely Low Matthew Homiack, DE Probability of Rupture (XLPR) V2
Note to requester: This document is how it was provided to the NRC ADDENDUM FOIA Team, w ith the to highlighted portions.
MEMORANDUM OF UNDERSTANDING between U.S. NUCLEAR REGULATORY COMMISSION and ELECTRIC POWER RESEARCH INSTITUTE, INC.
on COOPERATIVE NUCLEAR SAFETY RESEARCH (Technical Area e.g Probabilistic Risk Assessment]
The Memorandum of Understanding (MOU) (Technical Area) Addendum between the U.S.
Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute, Inc., (EPRI) which provides for the cooperative [PRA] research and accompanying exchange of information, concluded on [prior agreement date - e.g. December 31, 2009.)
Guided by their desire to continue the cooperative effort, the participants hereby extend the MOU (Technical Area) Addendum period of performance to expire on (termination date or the expiration date of the renewal which is September 30, 2021.)
New contact information for NRC and EPRI staff is as follows:
examolel PRA Quality, Modeling and Methodology PRA Quality, Modeling and Methodology Peter Appignani Stuart Lewis U.S. Nuclear Regulatory Commission Electric Power Research Institute M/SC4A07M 1627 Nighbert Ln.
Washington, DC 20555-0001 (865) 246-9715 Knoxville, TN 37922-5400 slewis@epri.com (301) 251 -7608 Peter.Appignani@nrc.gov Etc.
All other MOU [Technical Area) Addendum provisions remain in full force and effect.
Michael F. Weber Date Neil Wilmshurst Date Director Vice President and Chief Nuclear Office of Nuclear Regulatory Research Officer U.S. Nuclear Regulatory Commission Electric Power Research Institute
Comments & Related Tltle Expiration Date RES Contact Accession# links Period of Performance Current Status Extremely Low Probability of Rupture December 31, 2015 Dave Rudland, DE M L12263A043 non-public Expired Welding Residual Stress Model Development and Validation Project December 31, 2015 Michael Benson, DE ML13247A228 non-public Expired Pressurized-Water Reactor Spent Fuel Heatup and Propagation Phenomena Experiments February 29, 2016 Sergio Gonzalez, DSA ML13191B256 non-public Expired MOU between EPRI and NRC on Collaborative Nuclear Safety Resean:h September 30, 2016 Brett Rini ML092290122 public Currently being updated The period of performance of th is project extends until t he expiration of the umbrella Acquisition and Testing of Zion Spent Fuel Pool Neutron pu blic Memorandum of Understand No need for extension - shou Id Absorber Materials September 30, 2016 Eric Focht, DE ML15015A021 ML14217A410 (unsigned) that governs this Addendu m. be reviewed The period of performance of th is project is from the effective date Needs to be reviewed to Aging, Qualification and Condition Monitoring of Electrical of t his Addendum through determine if extension is needed.
Cables September 30, 2016 Kenn M iller, DE M L12261A368 September 30, 2016 public Benchmarking of Emergency Planning and Response Radiological Assessment Software Tools Using Fukushima ?? (Tasks are indicated through Accident Radiological Data September 30, 2016 Anthony H uffert, DSA M L14226A903 public December 2016)
The initial period of performance will be from the effective date Needs to be reviewed to through September 30, 2016, to determine if extension is needed.
Ian Jung,DE / Sean be extended i n writing if mutually Digit al l&C and Hutnan Factors Septetnber 30, 2016 Peters, ORA Ml090440352 public agreeable to EPRI and RES.
The init ial period of performance will be from the effective date Needs to be reviewed to through September 30, 2016, to determine if extension is needed.
be extended in writ ing if mutually Fire Risk September 30, 2016 Mark Salley, ORA ML101450467 public agreeable to EPRI and RES.
The initial period of performance will be from the effective date Needs to be reviewed to throug h September 30, 2016, to determine if extension is needed.
be extended in writing if mutually Long Term Operations Beyond 60 Years September 30, 2016 Amy Hull, Raj Iyengar DE ML100970003 public agreeable to EPRI and RES.
Needs to be reviewed to Primary Water Stress Corrosion Cracking - Crack Initiation Erick Focht, Greg ...effective through September determine if extension is needed.
Testing September 30, 2016 Oberson DE ML14217A006 non-public 30, 2016 Page 1 of 2
Comments & Related Tltle Expiration Date RES Contact Accession# links Period of Performance Current Status The period of performance for this Addendum shall be September 1, 2014 through Needs to be reviewed to September 30, 2016, or the determine if extension is needed.
Primary Water Stress Corrosion Cracking Expert Panel Greg Oberson, DE applicable MOU extension Activities September 30, 2016 Rob Tregoning, DE M L14279A001 public renewal date.
...the participants hereby extend Peter Appignani the MOU Probabilistic Risk Needs to be reviewed to Sean Peters Assessment Addendum period of determine if extension is needed.
John Lane performance t o expire on Probabilistic Risk Assessment (renewal) September 30, 2016 Nathan Siu, DRA ML101270008 public September 30,2016.
Guided by their desire to continue the cooperative effort, Needs to be reviewed to the participants hereby extend determine if extension is needed.
the MOU Seismic Risk Addendum period of performance to expire Seismic Risk (renewal) September 30, 2016 Jon Ake, DE M L100060724 public on September 30, 2016.
public Nondestructive Examination April 30, 2018 Carol Nove, DE Mll4112A187 Mll406SA003 (unsigned) OK Mica Baquera, DE Steam Generator Tube Base Research Program December 31, 2019 Matt Rossi, DE M L13357Al55 non-public OK Cooperative Nuclear Safety Research, Extremely Low ML15364A076 Probability of Rupture (XLPR) V2 Matthew Homiaok, DE Page 2 of 2
Note to requester: The public vers ion of this letter UNITED STATES is publicly available in NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ADAMS at ML16223A496.
Mr. Neil Wilmshurst Vice President and Chief Nuclear Officer Electric Power Research Institute 1300 West W.T. Harris Blvd .
Charlotte, NC 20262
Dear Mr. Wilmshurst:
Please find enclosed the signed Memorandum of Understanding (MOU) and Addenda between the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research (NRC/RES) and the Electric Power Research Institute (EPRI) on Cooperative Nuclear Safety Research.
The enclosed MOU renews our 2007 agreement and continues Cooperative Nuclear Safety Research in [#] technical areas. The Addenda updates to the MOU outlines the specific nature of our cooperation in these technical areas.
T he MOU and Addenda were developed through collaboration between the staff of NRC/RES and Mr. Ken Canavan of your staff. Our two organizations have worked well together over many years, and I believe the cooperation has been mutually beneficial. We look forward to many more successful years for this partnership.
Please sign the enclosed copies, and return one signed copy to the NRC Office of Nuclear Regulatory Research at your earliest convenience. If you have any questions, please feel free to contact Mr. Nicholas DiFrancesco of my staff at 301-415-11 15.
Sincerely, Michael F. Weber, Director Office of Nuclear Regulatory Research
Enclosure:
As stated
ML OFFICE RES/TA Tech Editor RES/DE/D RES/DE/ORA NAME NDiFrancesco J . Zabel BThomas RCorreia DATE 07/ /2016 07/ /2016 07/ /16 07/ /16 OFFICE RES/DE/DSA OGC RES/D NAME Mease MWeber DATE 07/ /16 07/ /16 07/ /16 Note to requester:
The final version of this document is publicly available in ADAMS at MEMORANDUM OF UNDERSTANDING ML16233A497.
between U.S. NUCLEAR REGULATORY COMMISSION and ELECTRIC POWER RESEARCH INSTITUTE, INC.
on COOPERATIVE NUCLEAR SAFETY RESEARCH PURPOSE The U.S. Nuclear Regulatory Commission ("NRC") and the nuclear power industry
("Industry") each conduct research on nuclear reactor safety. The NRC's Office of Nuclear Regulatory Research ("RES") conducts independent research in all areas regulated by the NRC, including ongoing and potential safety issues, risk-informed and performance-based regulation , and operating experience analysis. The Electric Power Research Institute, Inc.
("EPRI") is engaged in research and development in the public interest and on behalf of Industry with respect to the production, transmission, distribution, and utilization of electric power, including research designed to improve the safety, reliability, and economy of nuclear power plants. While the research efforts of the NRC and EPRI may be conducted for different purposes, the underlying data and the results obtained have common value to both the NRC and EPRI. Accordingly, to conserve resources and to avoid unnecessary duplication of effort, both the NRC and EPRI agree to cooperate in selected research efforts and to share information and/or costs related to such research, whenever such cooperation and cost sharing is appropriate and mutually beneficial.
This Memorandum of Understanding ("MOU") is authorized pursuant to Section 31 of the Atomic Energy Act and/or Section 205 of the Energy Reorganization Act. The roles, responsibilities, terms and cond itions of this MOU should not be interpreted in a manner inconsistent with, and shall not supersede, applicable federal laws and regulations.
This MOU describes the parameters within which cooperative research programs between the NRC and EPRI will be considered and conducted. Individual cooperative research programs are described in addenda to this document ("Cooperative Research Programs").
PRINCIPLES OF COOPERATION Article 1- Responsibility of the Parties 1.1 Organizational Accountability within the NRC and EPRI: This MOU will be implemented by the NRC's Office of Nuclear Regulatory Research ("RES") on behalf of the NRC and by EPRl's Nuclear Power Sector ("NPS") on behalf of EPRI. RES and NPS are responsible for conducting cooperative research with third parties in the field of nuclear energy for the NRC and EPRI, respectively.
1.2 Contacts
The NRC's Senior Management Contact shall be the Director of the Office of Nuclear Regulatory Research and EPRl's Senior Management Contact shall be its Chief Nuclear Officer ("Senior Management Contacts"). RES and EPRI will each identify their respective overall coordination contacts ("Overall Coordination Contacts") to serve as the primary interfaces for routine interactions between the NRC and EPRI.
1.3 Management of Cooperative Research Programs:
- a. Meetings: The Senior Management Contacts will confer, either via conference call or in meetings 1 as needed throughout the year, but will formally meet a minimum of once each year to review the status of ongoing Coo~erative Research Programs, to identify opportunities, if any, for additional Cooperative Research Programs, and to expand, modify, or close out existing Cooperative Research Programsexchange views on the strategic direction of the respective research programs and identify opportunities to enhance cooperation. On a periodic basis, normally semiannually, the Senior Management Contacts will confer to identify areas of cooperation warranting greater management attention and resolve any conflicts. The Senior Management Contacts shall agree on the priority, terms and conditions of new Cooperative Research Programs and shall provide direction on ongoing work and other matters, as necessary. The Overall Coordination Contacts and appropriate Cooperative Research Program personnel may meet more frequently as necessary to manage the Cooperative Research Programs.
- b. Selection of Potential Cooperative Research Programs: The NRC and EPRI shall identify potential Cooperative Research Programs of interest to the NRC and the Industry. Factors to be considered when selecting potential programs shall include:
- mutual interest in the subject matter;
- applicability of research results;
- contribution to plant safety;
- impact upon risk reduction ;
- opportunity to leverage resources; and
- timeliness.
Once an area of potential cooperative research is identified, a Cooperative Research Program may be pursued if mutual agreement is reached on the technical requirements of the project, including objectives, scope, approach and quality assurance requirements, and the roles and responsibilities of each party.
- c. Documentation of Cooperative Research Programs: Once approved by the Senior Management Contacts, each Cooperative Research Program will be documented in an Addendum to this MOU. Each Addendum shall set forth in detail the goals and objectives of the Cooperative Research Program, the scope of work to be performed or undertaken by the NRC and EPRI, and, as appropriate, the contractors to be employed, the technical requirements, the 1
NRC published its complete policy statement on meetings open to the public in the Federal Register on May 28, 2002 (67 FR 36920-36924). In general, meetings related to Cooperative Research Programs will not be open to public attendance if the subject matter to be discussed includes discussions related to proprietary information or could result in the inappropriate disclosure and dissemination of preliminary, unverified information.
financial responsibility and resource commitment of the NRC and EPRI, and the anticipated schedule. Each addendum shall also include an affidavit, in accordance with the requirements of 10 CFR §2.390, "Public inspections, exemptions, requests for withholding ," which provides the basis for withholding from public release EPRI reports that may be shared with the NRC in the process of performing the work associated with the specific Addendum 2 . The affidavit will generally describe the documents or information expected to be exchanged for the specific research program for each addenda.
- d. Management of Cooperative Research Programs: Each Cooperative Research Program will be managed by cognizant program managers and/or a technical review group comprised of NRC staff and EPRI employees.
- e. Termination of a Cooperative Research Programs: Either the NRC or EPRI may elect to terminate a Cooperative Research Program due to unsatisfactory contractor performance, lack offunds, changes in priority, or other reason. To effect a termination, the Senior Management Contact of the terminating party shall provide at least 30-days written notice of the intent to terminate continued participation in the specified Cooperative Research Program to the other party's Senior Management Contact. The terminating party shall provide confirmation of termination and the effective date thereof to the other party.
The non-terminating party may continue with the research which is the subject of the Cooperative Research Program and shall have sole control over and use of the results and information obtained from the Cooperative Research Program subsequent to the effective termination date. Results obtained prior to the effective date of termination are governed by Article 2.2.
- f. No Conflict with Federal Rules or Regulations: The NRC's role as an independent agency shall be maintained. Notwithstanding anything to the contrary herein or in any addendum to this Agreement, the cooperation, approval, involvement or guidance of the NRC staff with regard to the Cooperative Research Programs shall not bind the NRC in any manner, especially its rulemaking , licensing or adjudicatory processes. The occasional use of the term "agree" or mandatory language, such as "shall" or "will" in this MOU, or any addendum hereto, is not intended to constitute a binding obligation and does not create an enforceable right of action on the part of either party. EPRI shall not function as an advisory entity to the NRC. To maintain NRC's regulatory independence, the parties shall notjointly interpret the results or implications of the data derived from the Cooperative Research Programs. EPRI shall not claim or publish in its studies, releases, reports, or publications any statements that indicate the NRC's approval or endorsement of any Cooperative Research Program or any related study, report, or publication without the prior written approval of the NRC's Senior Management Contact.
2 This is applicable only to final reports or other intellectual property that EPRI has already developed. Data acquired during the course of the subject collaborative work is considered privileged information and thus will be routinely withheld from release until the final repor~~! on this work is/are made publicly available.
Article 2-Guidelines for Cooperative Resea rch 2.1 The purpose of each Cooperative Research Program shall be to produce research data and results related to nuclear safety. To maintain independence and to avoid conflicts of interest, or even the appearance of any conflicts of interest, the NRC and EPRI shall notjointly derive any conclusions regarding the data or results obtained f rom a Cooperative Research Program or the application of such data or resu lts to any regulation or regulatory guidance. The NRC and EPRI may cooperate in the validation and verification of data to ensure it is ready for use by decision-makers. A ny regulatory analysis of the data to determine applicability to and impact on existi ng or new regulation shall be done independently.
2.2 All non-proprietary data produced by the cooperative programs will be shared by and between all participants in the cooperative program, consistent with each Party's legal obligations. Data produced or used under the cooperative programs or supplied to support the conduct of the research will be handled In accordance with the applicable statutes (e.g., Freedom of Information Act - FOIA), rules, regulations, policies, and procedures of the NRC and EPRI. The Parties recognize that Federal law may require release of this data.
2.3 If an electronic reading room is established, the following conditions will be maintained throughout the duration of this MOU.
The electronic reading room will be password protected and passwords will be assigned to staff directly involved in cooperative research on a need-to know basis The electronic reading room will be sufficiently secure to prevent staff from printing, saving, or downloading any documents Conditions of use of the electronic reading room will be displayed on the log-in screen and will require concurrence by each user of the electronic reading room 2.4 All final data or results produced by a Cooperative Research Program shall be shared by all participants, and each party shall be free to disseminate them to whomever they choose at no additional cost. Proprietary information supplied by EPRI to support conduct of the research will be marked and protected in accordance with applicable Federal laws, rules, and/or regulations, including 10 CFR §2.390. The addenda to this MOU will describe the documents or information to be exchanged for the specific research program involved. In accordance with 10 CFR §2.390, and prior to or contemporaneous with such exchange, EPRI will submit an affidavit covering such material and stati ng the basis for withholding it from public disclosure if the information has not been described in a previous affidavit.
2.5 Publication of priv ileged data or results from Cooperative Research Programs in journals or conference proceedings, by any party or contractor, prior to its public release in the final report(s) on th is work, shall require the written approval of each of the Senior Management Contacts.
2.6 The NRC and EPRI will determine on a project-by-project basis if appropriate patent or copyright applications should be filed with regard to the data or results generated by a Cooperative Research Program.
2.7 Upon request, each party shall have access, contingent upon meeting any required security clearances, to the contractors' facilities, separately or jointly, and may review the data developed by the other party's contractor that is associated with a specific Cooperative Research Program.
2.8 Either the NRC or EPRI may, at its own expense, conduct additional research beyond the scope of the Cooperative Research Program using the same contractor or facility employed with respect to a Cooperative Research Program if it so desires, or may employ such other contractors or facilities as it deems appropriate.
Article 3-Te rmsofAqreem ent
- 3. 1 The term of this MOU shall commence effective upon signing by both NRC and EPRI Senior Management Contacts and shall expire on September 30, 2021.
The addenda that were active as of September 30, 2016, remain as such until they are terminated in accordance with the requirements of this MOU. A list of addenda that were active as of September 30, 2016 is attached hereto as Exhibit A.
3.2 Either party may terminate this MOU at any time upon 90 days prior written notice of such termination.
3.3 This MOU supersedes and replaces the Memorandum of Understanding dated March 14, 2007.
The parties hereto acknowledge that this MOU is non-binding and is solely intended to promote cooperative relationships between the parties.
Michael Weber, Director Neil Wilmshurst, Vice President and Chief Office of Nuclear Regulatory Research Nuclear Officer U.S. Nuclear Regulatory Commission Electric Power Research Institute, Inc.
Date: _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ _ _ _ _ _ _ __
Exhibit A Addenda to NRC-EPRI MOU on Cooperative Nuclear Safety Research that were active and in effect on 30 Sept. 2016 3 Title NRC Contact EPRI Contact Accession#
Acquisition and Testing of Zion Spent Fuel Eric Focht, ML15015A021 Pool Neutron Absorber Materials Matt Rossi DE Aging, Qualification and Condition Kenn Miller DE ML12261A368 Monitorina of Electrical Cables Benchmarking of Emergency Planning John Toman DSA ML14226A903 and Response Radiological Assessment Software Tools Using Fukushima Accident Radioloaical Data Cooperative Nuclear Safety Research, Joseph Kanney ML15321A365 External Flooding Hazards ORA Digital l&C and Human Factors Ian Jung DE, ML090440352 Sean Peters ORA Fire Risk Mark Salley ORA ML101450467 Long Term Operations Beyond 60 Years Amy Hull , Raj ML100970003 Iyengar DE Nondestructive Examination Carol Nave DE ML14112A187 Pressurized-Water Reactor Spent Fuel Sergio Gonzalez ML131918256 Heatup and Propagation Phenomena DSA Experiments Primary Water Stress Corrosion Cracking Erick Focht, Greg ML14217A006
- Crack Initiation Testina Oberson DE Primary Water Stress Corrosion Cracking Greg Oberson, ML14279A001 Expert Panel Activities Rob Tregoning DE Probabilistic Risk Assessment (renewal) Peter Appignani ML101270008 Sean Peters, John Lane, Nathan Siu ORA Seismic Risk (renewal) Jon Ake, DE ML100060724 Steam Generator Tube Base Research Matt Rossi, ML13357A155 Proaram Pat Purtscher DE Cooperative Nuclear Safety Research, Matthew ML15364A076 Extremely Low Probability of Rupture Homiack, DE (XLPR) V2 Exhibit A 3
This listing is a one-time compilation of active Addenda as of 30 Sept. 2016, provided for information. It does not commit the parties to future revisions of this MOU as addenda are added, revised or deleted. Subsequent updates to this list will be managed separately by the overall coordination contacts.
Danoff, Karen From: Tregoning, Robert Note to requester:
Sent: Monday, June 20, 2016 8:51 AM Attachment to this email is To: Kirk, Mark; Rao, Appajosula; Hiser, Matthew immediately following.
Cc: Frankl, Istvan; Rudland, David
Subject:
FW: NRC-NRAJ 2016 Materials Meeting Agenda.docx Attachments: NRC- NRAJ 2016 Materials Meeting Agenda.docx All:
Attached is the draft agenda for the NRC/NRAJ meeting on August 8-9. Could you please review the agenda and let me know if you have any issues supporting the meeting? The idea is for each side to have a presentation on research activities associated with these topics and then have a discussion on ways to collaborate and share information related to the topic. Could you also let me know the following w.r.t. the agenda:
- 2. Will Pat Purtscher lead the material harvesting discussion?
Thanks for your help, Rob From: Tregoning, Robert Sent: Friday, June 17, 2016 8:36 AM To: :l&-* -i~ <kazunobu_sakamoto@nsr.go.jp>
Subject:
NRC-NRAJ 2016 Materials Meeting Agenda .docx Kazu:
Attached is a rough draft for our meeting agenda. I've developed this based on the topics that we agreed to last month in our email exchanges. I've tried to group the topics in ways that make sense and I've put some estimates for times as well as speakers. Here's what I think we need to agree on.
- 1. Do you agree with all the topics and the order of the topics?
- 2. Do you agree with the meeting starting and ending times on both days? We could start and end at whatever times are convenient for you.
- 3. Do you agree with the scheduled breaks and lunch times? We could make these shorter or longer depending on your needs.
- 4. Do you agree with the length of time devoted to each topic?
Please feel free to modify the attached agenda to address these four questions.
After we agree on the agenda topics and times, the final step will be to confirm the speakers on the NRC and NRAJ side. Please let me know who your speakers will be for each topic. I have put some ideas down for the NRC speakers but I will still need to confirm this.
As always, thank you for your help with this meeting.
Warm regards, Rob 1
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...* 2_3_2_4 _ __
Blackberry: ! J (b)(§)
fax: 301-415-6671 2
AGENDA NRC/NRAJ Bilateral Meeting on Materials Issues NRC Headquarters, Rockville, MD, USA August 8 - 9, 2016 Monday, August 8111 , 2016 Location: Room 07-B4 Time Topic Speaker 8:00 am Introductions All 8:05 am Welcome B. Thomas, NRC 8:15 am Opening Remarks R. Tregoning, NRC K. Sakamoto, NRAJ Metals Aging 8:30 am RPV embrittlement studies M. Kirk, NRC NRAJ 10:00 am Break 10:15 am Irradiated Assisted Degradation S. Rao/M . Hiser, NRC NRAJ 11:30 am Technical and Regulatory Concerns All 12:00 pm Lunch Cable Aging 1:30 pm NRC Research Activities D. Murdock, NRC 2:30 pm NRAJ Research Activities NRAJ 3:30 pm Break 3:45 pm Technical and Regulatory Concerns All Adjourn 4:30 pm
AGENDA NRC/NRAJ Bilateral Meeting on Materials Issues NRC Headquarters, Rockville, MD, USA August 8 - 9, 2016 Tuesday, August 9 111, 2016 Location: Room 0 7-B4 Time Topic Speaker Concrete Aging All 8:00 am Radiation Effects on Concrete M. Sircar, NRC Structures M. Nakano, NRAJ 8:45 am NDE for Thick Concrete Sections M. Sircar, NRC M. Nakano, NRAJ 9:30 am Monitoring and Aging Management of M. Sircar, NRC ASR Affected Concrete Structures M. Nakano, NRAJ 10:15 am Break 10:30 am Technical and Regulatory Concerns All 12:00 pm Lunch Possible Future Collaboration Areas 1:30 pm Environmentally Assisted Fatigue R. Tregoning, NRC NRAJ 2:00 pm Aging of CASS Rao/Purtcher, NRC NRAJ 2:30 pm Peening J. Collins, NRC NRAJ 3:00 pm Break 3:15 pm Material Harvesting P. Purtcher, NRC NRAJ 3:45 pm Actions and Next Meeting R. Tregoning, NRC K. Sakamoto, NRAJ 4:15 pm Closing Remarks R. Tregoning, NRC K. Sakamoto, NRAJ 4:30 pm Adjorn
Note to requester:
Attachment to this email is From: Moyer carol immediately following.
To: l:il.!!I....AmY Cc: Pbi!iP Jacob
Subject:
FW: Draft UNR response.
Date: Tuesday, June 27, 2017 10:12:00 AM Attachments: UNR-6-26-JZ docx
Can you work with it in this format, to fold his input into the draft on the G-drive?
G:\DE\CMB\2017-006 UNR NRR 2017-006\draft collective SLR UNR response 05 201 7.abh.docx Jake - I thank you for sharing a copy of this with me. Since Amy is working on pulling together the various inputs to write our response, I am forwarding your file to her now. Just curious, why did you send this up to Brian Thomas at this stage, bypassing your branch chief?
Thank you, Carol From: Philip, Jacob Sent: Tuesday, June 27, 2017 9:47 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>
Cc: Thomas, Brian <Brian.Thomas@nrc.gov>; Tregon ing, Robert <Robert.Tregoning@nrc.gov>
Subject:
FW: Draft UNR response.
FYI .... preliminary draft of UNR response.
This write up is for concrete and has to be revised to include the 3 other topics in the SRM.
The cover letter covers all 4 topics.
From: Philip, Jacob Sent: Monday, June 26, 2017 3:06 PM To: Pires, Jose <Jose.Pires@nrc.gov>; Sock, Frederick <Frederick.Sock@nrc.gov>; Cand ra, Hernando
<Hernando.Candra@ nrc.gov>; Li, Huan <Huan.Li@ orc.gov>; Sircar, Madhumita
<Madhum ita.Sirca r@nrc.gov>
Subject:
Draft UNR response.
- Folks, I am enclosing a preliminary draft of the cited subject. Th is response convers concrete degradation only. The 3 other topics in the SRM are from other branches (not SGSEB) and need to be added to this response. We can ask Amy Hull to help in that effort.
Please let me know if you have any comments and suggestions. Some parts of this response has to be filled in by others in the branch as indicated.
Thanks .... Jake
DRAFT MEMORANDUM TO: William M. Dean, Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber, Director Office of Nuclear regulatory Research
SUBJECT:
RESPONSE TO USER NEED REQUEST, "RESEARCH ASSISTANCE ON POTENT IAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION."
By memorandum dated May 4, 2017, the Office of Nuclear Regulatory Regulation (NRR) requested assistance from the Office of Regulatory research (RES) to develop specific research products to facilitate the evaluation of future applicants for a license to operate during the subsequent license renewal period (SLR) i.e. 60 to 80 years. RES is pleased to accept the subject request (UNR) For tracking purposes, RES has designated the UNR as as NRR-2017-xxxx, which is available in the Agency wide Documents Access and management systems (ADAMS) under accession number, MLxxxxxAxxx.
As stated in the NRR request, in a previous user need request, UNR-NRR-2010-006, "Request for Office of Nuclear Regulatory Research in developing Technical Information to Support Evaluating the Feasibility of License Renewal Beyond 60 years, ADAMS accession No.
ML092470525, RES assisted NRR in developing information for consideration in the SLR guidance documents. This new UNR focuses on research activities discussed in the SLR guidance documents and in the staff requirements memorandum (SRM) to SECY 14-0016 (ADAMS Accession No. ML14241A578).
RES accepts the scope, sch,edule and priority described in the UNR, with some additional comments, noted in the RES response to the UNR included in the enclosure. During the course of the research work, RES will inform the Division of License renewal (DLR) of any changes, if required, to arrive at a reasonable solution.
Enclosure:
As stated CONTACT: Xxxxxxx Xxxxx, RES/DE/SGSEB 301-415-xxxx
ENCLOSURE RESPONSE TO NRR USER NEED REQUEST, "RESEARCH ASSISTANCE ON POTENTIALSIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION. "
Technical Issue The four most significant technical issues identified by this new UNR were also outlined in the SRM on SECY 14-0016, "Ongoing Staff activities to ASSESS Regulatory Considerations for Power Reactor Subsequent License Renewal" (ADAMS Accession No. ML14241A578):
- Reactor pressure vessel neutron embrittlement at high fluence
- Irradiation-assisted stress corrosion cracking of reactor internals and primary system components
- Concrete and containment degradation
- Electrical cable qualification and condition assessment The four significant issues noted above were the conclusions from an expert elicitation process to identify the most significant aging degradation technical issues for nuclear power plant operation beyond 60 years. They are described in the Expanded Materials Degradation Assessment (EMDA) reports, developed in cooperation with the Department of Energy (DOE) Water Sustainability Program. The resultant reports, NUREG/CR-7153, EMDA, vol. 1-5 (ADAMS Accession Nos, ML14279A321, ML14279A331, ML14279A3491, ML14279A430, and ML14279A461). NRC staff has also recently completed draft guidance documents for SLR. They include draft NUREG-2191, Volume 1 and 2, (ADAM S Accession Nos. ML16274A389 and ML16274A2399), t he Draft Aging lessons learned for Subsequent license Renewal (GALL_ SLR) Report and the draft NUREG 2192, (ADAMS Accession No, ML 1627A402), "Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants", all issued for public comments in December 2015.
In the Concrete and containment degradation arena, EMDA identified the four issues that needed to be addressed for SLR: These were:
- Irradiation of concrete (shield walls and concrete reactor support)
- Concrete degradation due to Alkali-Silica Reaction (ASR)
- Boric acid attack and chloride corrosion of reinforcing bars
- Creep in post tensioned containment structures RES agrees with the scope of the research outlined in the UNR, with comments. The concrete degradation research response to the UNR request addresses the four areas in concrete noted above.
A summary of the UNR tasks for the area of concrete and containment degradation and the RES response to develop the research requested in the UNR follows.
- Task1: Hold NRG/industry workshop(s) on the status of domestic and international research activities to address and evaluate the status of aging degr.adation issues identified in the SRM on SECY 14-0016 and in the GALL-SLR Report
- Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants, as well as from ex-plant components from operating plants
- Task 3: Continue to develop Domestic and International Partnerships to share expertise capabilities and resources related to Aging management research for Long-term Operations
- Task 4: Documentation and compilation of results from tasks 1, 2, and Task 3 on the status of research results in support of the Commission's direction to staff The RES response to the UNR request (for concrete degradation) follows.
- Task 1: Hold NRG/Industry workshop and prepare NUREG/CP and summary report.
RES will plan to hold an international workshop in early spring 2020 on the state of knowledge on the technical issues in concrete degradation requested in the SRM SECY 14-0016. The international workshop will help RES in securing information on research insights and knowledge from other countries and domestic partners on issues related to concrete materials degradation and aging management as discussed in SECY 14-0016. A draft agenda and a list of presenters at the workshop will be provided to DLR. The results of the workshop will be documented in a NUREG/CP report which will include a summary of the workshop, presentations and workshop insights and conclusions
- Task 2 : Develop and implement a strategy for harvesting materials/components on concrete materials from decommissioned nuclear power plants as well (as from ex-plant components from operating plants).
RES will develop a data base which identifies and prioritizes the concrete materials, components and operating conditions needed to address the significant issues outlined in SECY 14-0016.
RES will develop a process to evaluate concrete samples harvested from decommissioned plants. RES is in very preliminary discussions with international entities (under the NEA/OECD/CSNI umbrella) to recover materials from a decommissioned plant in Canada affected by ASR. The expected outcome from these discussions can lead to evaluating the suitability and focus of testing that could an include removal of core samples from the plant for mechanical and petrographic testing, insitu anchorage and bond testing of the ASR affected concrete and beam structural testing. RES will follow through with implementing the process as concrete materials become available from additional plants. In addition for irradiation effects on concrete materials RES will (fill this on irradiation and other decommissioned plant testing plans).... ... .... ... ... ..... .... .... ... ... .... ... .... .... ... .... .. .. ... ... ..... . .
Based on information gleaned from discussions on the potential for harvesting and testing of concrete from decommissioned reactors, RES will provide a database to NRR on the possibilities for this activity and prioritize testing in a letter report. The process to evaluate the concrete samples from plants undergoing decommissioning or ex-plant samples from operating plants (and its suitability) that would be appropriate candidates for harvesting will be documented in the letter report to NRR. Concurrently RES will pursue domestic and international partnerships for cooperational cost sharing on the retrieval and testing of samples RES will provide the data base developed for NRR review and summarize the priority listing in a letter report. A separate letter report will be submitted to NRR on the process for harvesting a and testing of concrete samples from decommissioned plants.
- Task 3: Develop domestic and international partnerships RES will continue to pursue and develop domestic and international partnerships to share expertise, capabilities and resources related to aging management research for Long-Term operations. RES is working to finalize a bilateral agreement with IRSN, France for exchange of technical information on the effects of ASR on the performance of nuclear concrete. IRSN is conducting a 10-15 year research project focused on studying the long-term performance of concrete affected by ASR, Delayed Ettringite Formation, corrosion and carbonation of nuclear concrete. RES has an ongoing collaboration with DOE/EPRI on ASR and irradiation effects on concrete and will continue participating under the international OECD/NEA/CSNI to develop modeling expertise for ASR effected concrete structures. (fill this on other partnershipos )..... .. ... .... ... ... ... ..... ... ..... .. .... ....... ..... ..... ... .. .... .... ... .... ... .... ... ... .... ..... .. ... .
RES will provide NRR management trip reports, summaries, papers, presentations, reports and other information from interactions with domestic and international organizations as a result of this activity. Relevant findings from recent interactions, status and future plans will be discussed as a standing agenda item during the interface meetings between RES/DE, NRR/DLR and NRR/DE.
- . Task 4: Documentation and Compilation of results from Tasks 1,2 and 3 on the status of research results in accordance with SECY 14-0016.
RES will prepare a document annually summarizing the products from the three tasks above and discuss the accomplishments of RES and national and international partners in addressing the four major technical issues (in this case on concrete degradation) in the SRM.
Resources (To be discussed with others in SGSEB)
Intended Use of RES products RES products will provide confirmatory research on the technical bases for industry research products related to aging degradation as identified in staff's review of SLR applications.
Coordination and Schedules The UNR has been coordinated between RES staff in the Division of Engineering (DE) and DLR staff in NRR. (Need discussion with others in SGSEB)
Priority High Points of Contact NRR: Bennet Brady, Subsequent Renewal , Guidance, and Operations Branch, DLR RES: Amy Hull, Corrosion and Metallurgy Branch, DE
Note to requester: Attachment to this email is immediate! followin .
From: Hiser, Matthew Se nt: Wednesday, July 27, 2016 3:12 PM To: Thompson, Jacqueline
Subject:
FW: NRAJ Bilateral Meeting Presentation on Harvesting Attachments: Harvesting Efforts NRAJ Bilateral 7-20-16.pptx Or Jacquie© From: Hiser, Matthew Sent: Wednesday, July 27, 2016 3:04 PM To: Vera, Graciela <Graciela.Vera@nrc.gov>
Subject:
FW: NRAJ Bi lateral Meeting Presentation on Harvesting Hi Gracie, Can you add this document into non-public ADAMS for me?
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov From: Hiser, Matthew Sent: Tuesday, July 26, 2016 10:01 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
FW: NRAJ Bi lateral Meeting Pr esentation on Harvesting Hi Steve, I have put together slides on the harvesting for the NRAJ bilateral meeting next month and would li ke to share them for your review. These have been reviewed by Rob, Pat and Amy (see email chain below).
Thanks.!
Matt From: Hiser, Matthew Sent: Wednesday, July 20, 2016 1:00 PM To: Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick
<Patrick.Purtscher@nrc.gov>
Subject:
RE: NRAJ Bilateral Meeting Presentation on Harvesting Thanks Rob! I have added a slide at the end for discussion topics, but kept 5 and 7 in. I can breeze through those fairly quickly.
1
Amy and Pat, do either of you have any input? If not, I will go ahead and run these by Steve ...
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office ofNuclcar Regulato1y Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-415-2454 I Office: TWFN 10062 Matthew.Hiser@nrc.gov From: Tregoning, Robert Sent: Friday, July 15, 2016 1:19 PM To: Hiser, Matthew <Mat thew.Hiser@nrc.gov>; Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick
<Patrick.Purtscher@nrc.gov>
Subject:
RE: NRAJ Bilateral Meeting Presentation on Harvesting Matt:
Just got a chance to look at this. Given that you've only got % hour, your 8 slides are probably the max. I would take more than 1O minutes to provide an overview of the activity. If you need to save time, slides 5 and 7 could be eliminated. You could provide them in the slide package but just gloss right over them in the presentation.
Obviously, Japan has a large number of plants that are shut-down. It's still not clear which of these plants will restart. Therefore, there may be a lot of harvesting opportunities there.
The main purpose of this discussion is to see if NRAJ has any activities (or planned activities) to identify harvesting opportunities. If so, it would be good to understand there approach. It would also be good to see if they know which plants are most likely to not restart.
With this in mind it would be good to have a slide or two with a list of questions or discussion topics on this issue to discuss with the Japanese. While we only have% hour, we may be flexible to extend the meeting if we need more discussion time on any topic.
Does this make sense?
Ro Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission Two White Flint North, M/S T-10 A36 11545 Rockville Pike Rockville, MD 20852-2738 ph: 301-415-2324 Blackberry: 1
....- - . . . . -.. . . ..-. . . . ....J (PJ(§.)
fax: 301-415-6671 From: Hiser, Matthew Sent: Tuesday, July 12, 2016 5:13 PM To: Hull, Amy <Amy.Hull@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Tregoning, Robert 2
<Robert.Tregoning@nrc.gov>
Subject:
NRAJ Bilateral Meeting Presentation on Harvesting Hi Amy, Pat, and Rob, I've pulled together a few slides for discussion of the harvesting program at the NRAJ meeting next month.
Please take a look and provide any comments or edits.
Thanks!
Matt 3
t;> U.S.NRC Unired Srarcs Nuclear Regularory Comm ission Protecting People and the Environment
Purpose U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Create a framework for a strategic approach to harvesting ex-plant materials to support regulatory needs associated with subsequent license renewal (SLR)
- Ex-plant materials offer unique environmental exposure that cannot be entirely replicated by laboratory testing with fresh materials
- Align high priority data needs identified in SLR activities with harvesting opportunities from decommissioning plants
Background U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- To date, harvesting opportunities have been limited due to few decommissioning plants
- Zion in U.S., Zorita in Spain
- However, several U.S. plants have already shut down or are planning to do so in the near future
- Kewaunee, San Onofre, Crystal River, Vermont Yankee, Oyster Creek, Fort Calhoun, Clinton, Quad Cities, Diablo Canyon
- This provides a unique opportunity to plan harvesting to address the highest priority technical and regulatory is
Harvesting Experience U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Past harvesting efforts have generally involved reactive decision-making
- Limited opportunities to acquire ex-plant materials
- Limited strategic planning for harvesting
- Harvesting projects with NRC involvement:
- Reactors internal materials from Zorita
- Concrete from Zorita
- Neutron absorber material from Zion
- Cables from Zion and Crystal River
Zorita Internals Research U.S.NRC United Scates Nuclear Regulatory Commission Protecting People and the Environment Project Timeline Task 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 Project Inception ~r Feasibility Study Project Planning Cutting Plans Equipment Design & Manufacturing On-site Preparations Material Extraction I On-site Logistics Shipping Radiation and Temperature Analyses Material Inspection, Inventory, Documentation I Materials Testing I Reporting ,r
Approach: Assessment of Technical Issues U.S.NRC Uni ted Scates Nuclear Regulatory Commission and Available Materials for Harvesting Protecting People and the Environment
- Utilize various sources of technical information with respect to anticipated degradation in NPPs out to 80 years of operation
- Identify high-priority data needs that could be addressed through harvesting ex-plant materials
- Focus on identifying characteristics of important systems, structures, and components (SSCs) for harvesting
- Gather information on ex-plant material expected to be available based on identified needs
- May be from both operating and decommissionin r:~
U.S.NRC Implementation Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- What might the output of this activity look like?
- For example, the review may show there is value in acquiring CASS material around 15% delta ferrite with various dose ranges
(<0.08 dpa, 1-3 dpa, and >5 dpa)
- Once that need is identified, this activity would identify what SSCs might be the best candidates for harvesting
- For example, perhaps lower support columns would be identified as the ideal SSC to address the CASS data need
- As decommissioning plants announce their plans, there is a clear list of SSCs and their characteristics (metallurgy, temperature, fluence, etc.) that would be desired t address the data need
U.S.NRC Current N RC Activities Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- NRC is working with Pacific Northwest National Lab (PNNL) to identify technical issues that may be best addressed by ex-plant harvesting
- Focused on unique value of harvesting to understand material properties in difficult to replicate environments
- NRC also seeking interest from other stakeholders to better understand availability of materials for harvesting
- Considering a public workshop in fall 2016
- Stakeholders include EPRI, DOE, U.S. industry, international
~
partners
U.S.NRC Discussion Topics Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Japanese approach to ex-plant material harvesting
- Information on available harvesting opportunities from Japanese reactors
- Is it known which plants will not restart?
- Opportunities for coordination/ cooperation on ex-plant harvesting
U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment Backup Slides
Neutron Absorbers from Zion U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested:
- Select Bora I NAM panels from Regions 1 and 2 of the Zion SFP
- Scope:
- Visual and microstructural examinations (incl. areal density)
- Corrosion testing
Purpose:
- Identify degradation mechanisms and estimate degradation rate
- Confirm results of in-situ areal density measurements
- Provide confirmatory data to support regulatory decision-making
- Timeline:
- Initial discussions in 2014, harvesting in 2015, testing in 2015-2016
- Coordination:
- EPRI, ZionSolutions, SRNL
Zorita Internals Research Project (ZIRP) U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested: l'IC!t 8 l'I.Cl!t C
- Baffle plate and core barrel weld materials
- Scope: 0 0 0 0 0 0 0 0 0 0 0 0 0~
- Mechanical testing (tensile, CGR, FT)
- Microstructural characterization (void swelling) 0 0 0 0 0 0 0 0 0 0 0 0 Oci---r.
Purpose:
- High-fluence (up to 50 dpa) IAD effects with representative LWR exposure conditions to Support regulatory decision-making associated with SLR
- Timeline:
- Initial discussions in 2006, harvesting in 2013, testing ongoing through 2016
- Coordination:
- EPRI, international consortium, Studsvik, Halden
Concrete from Zorita (Plan) U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested:
- Concrete from structures that are in close proximity to RPV
- Scope:
- Mechanical testing (compressive, tensile, modulus of elasticity)
- Microstructural characterization
- Physical change
Purpose:
- High fluence in combination with temperature and humidity that are representative of LWR environmental effects on structural and shielding performance
- Supports regulatory decision-making associated with SLR
- Timeline:
- Initial discussions in 2014, harvesting in 2015, testing 2016-
- Coordination:
- NRC, ENRESA and CSN
Cables: Zion and Crystal River U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested:
- Low and Medium Voltage Cables
- Scope:
- Condition monitoring to assess cable performance under normal operating conditions (accelerated aging) and accident conditions
Purpose:
- Cable degradation due to normal operating environment and accident conditions
- Supports regulatory decision-making associated with SLR
- Timeline:
- Initial discussions in 2012; Cable samples harvested from Zion in 2013
- Plan is to harvest additional samples from Crystal River and Zion in 2015
- Testing expected to be completed in 2017
- Coordination:
- ORNL, Zion Solutions, NIST, EPRI
Note to requester:
Attachment to this email is From: Moyer carol immediately following .
To: l:il.!!I....AmY Subject : FW: Document for ADAMS, for concurrence Date: Friday, September 22, 2017 11:20:00 AM Attachments: SLR UNR resoonse 09-22-2017.docx,
- Amy, FYI, Cassandra said the memo needed a LOT of formatting changes. I am really surprised at this, since we always start from a previous memo for a job like this. Hmm. She did not include a mark-up, only a request to use this one going forward.
Oh, and yes, she will restore the revised concurrence table!
-Carol From: Cole, Cassandra Sent: Friday, September 22, 2017 11:08 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>
Subject:
RE: Document for ADAM S, for concurrence Ok, got it.
I have attached the f inalized document for you to use for future memos as there were a lot of edits that needed to be made and I just completed it. Documents presented in this format makes it very difficult to do in a timely manner. Edits included columns, section breaks, page breaks, font and font size. I hope this can be a "template" for you to be able to copy and paste your information into. You may save to your desktop for quick access.
I will replace this version along with the enclosure into ADAMS and bring you the hard copy. Let me know if you need anything else.
From: Moyer, Carol Sent: Friday, September 22, 2017 9:06 AM To: Cole, Cassandra <Cassandra,Cole@nrq~ov>
Cc: Hull, Amy <Amy,Hull@nrc gov>; Frankl, Istvan <lstvan,Frankl@nrc gov>
Subject:
RE: Document for ADAMS, for concurrence Importance: High Cassandra, The document that I forwarded this morning contains a memo and its enclosure. These are revised documents, with a version already in ADAMS at ML17227A483.
So, my revised request - Can you please insert this morning's document into the existing ADAMS package, and prepare a concurrence package?
Many thanks, Carol From: Moyer, Carol Sent: Friday, September 22, 2017 8:40 AM To: Cole, Cassa nd ra <Cassandra,Cole@nrc.gov>
Cc: Hull, Amy <Amy.Hull@nrc.gov>; Fran kl, Istvan <lstvan,Frankl@nrc.gov>
Subject:
Document for ADAMS, for concurrence Hello, Cassandra, Would you please place the attached memorandum into ADAMS, and prepare a concurrence package?
Feel free to contact me if you have any questions.
Thank you ,
Carol Carol Moyer Sr. Materials Engineer RES/ DE/CMB carol.mover@arc.Qov 301-415-2153
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 MEMORANDUM TO: Brian E. Holian, Acting Director Office of Nuclear Reactor Regulation FROM: Michael F. Weber Director of Nuclear Regulatory Research
SUBJECT:
RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING THE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-201 7-006 By memorandum dated May 4, 2017, the Office of Nuclear Reactor Regulation (NRR) requested assistance from the Office of Nuclear Regulatory Research (RES) to provide "specific research products to facilitate the evaluation of future applications for a license to operate during the subsequent license renewal (SLR) period (i.e., 60 to 80 years). These products should build upon analysis methods, tools, and expertise developed as part of ongoing and new research activities, focused specifically on aging effects during the SLR period." This user need request (UNR) supersedes and incorporates work from the previous UNR NRR-2010-006 "provide support in developing technical information to support evaluating the feasibility of license renewal beyond 60 years." This UNR also supersedes NRR-2014-001 "provide expert assistance with reviewing the guidance documents for subsequent license renewal" and complements NRR 2017-001 "research assistance to evaluate irradiation-assisted degradation of reactor vessel internals." For tracking purposes, RES has designated this UNR as NRR-2017-006 (ML16358A427).
The purpose of this memorandum is to respond to UNR NRR-2017-006 with RES's plans to accomplish the following tasks:
- Task 1: Hold NRG/in dustry workshop(s) on the status of domestic and international research activities to address and evaluate aging degradation issues identified in in the SRM on SECY 14-001 6 and in the GALL-SLR report (NUREG-2191).
- Task 2: Develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned nuclear power plants (NPPs), as well as from ex-plant components harvested from operating plants.
- Task 3: Continue to develop domestic and international partnerships to share expertise, capabilities, and resources related to aging management research.
- Task 4: Develop documentation evaluating significant technical issues germane to the review of SLR applications.
- Task 5: Provide expert assistance with reviewing SLR applications (optional task)
CONTACT : Amy Hull, RES/ DE 301-415-2435
B. Holian 2 RES staff is conducting ongoing coordinating activities to address Tasks 1, 2, and 3, including both independent and collaborative efforts with industry and other partners. RES staff will continue these activities and integrate the results in deliverables under Task 4. The response has been closely coordinated with NRR technical staff and management. As a result of this effort, RES added optional Task 5. If needed, under this task, RES staff would provide expert assistance with the review and evaluation of SLR applications. The enclosure addresses in greater detail the scope of ongoing and planned activities associated with each task, as well as the estimated resources and the anticipated schedule for the deliverables.
RES staff appreciates the coordination with NRR technical staff and management in this area. We will continue to coordinate with NRR staff and management to ensure that regulatory needs and priorities are satisfied. Changes in the availability of resources or NRR needs could impact the activities, deliverables and schedules of this UNR. In such cases, changes will be implemented jointly by RES and NRR and, if warranted, the UNR will be amended.
Enclosure:
- 1. Response to User Need Request for Research Assistance on Potential Significant Technical Issues during the Subsequent Period of Extended Operation
B. Holian 3
SUBJECT:
RESPONSE TO USER NEED REQUEST FOR RESEARCH ASSISTANCE ON POTENTIAL SIGNIFICANT TECHNICAL ISSUES DURING T HE SUBSEQUENT PERIOD OF EXTENDED OPERATION: NRR-2017-006 DISTRIBUTION:
B . Thomas, RES G Wilson, NRR R . Tregoning, RES A. Hiser, NRR I. Frankl, RES R. Iyengar, RES T . Koshy, Res K. Miller, RES D. Seber, RES S . Stuchell, NRR B .Brady, NRR A. Hull, RES C. Moyer, RES M.Hiser, RES M. Kirk, RES J. Philip, RES M. Sircar, RES J. Pires, RES RidsNrrMailCenter ADAMS Pac kai 1e A ccess1on No.: MLxxxx OFFICE NAME DATE RES/DE/CMB C. Moyer I /2017 RES/DE/CMB A. Hull I /2017 RES/DE/CMB RES/DE/ICEE I. Frankl I /20 17 T. Koshy I /2017 OFFICE RES: DE: SGSI;_,_ D :RES:DE _RES Mail D:RES NAME
- D. Seber B. Thomas K. Johnson M. Weber DATE I /2017 I /20 17 I /2017 I /2017 OFFICIAL RECORD COPY
Notes to requester: Attachment to th is email is immediately following . This document was how it From: Frankl Istvan was provided to the NRC FOIA staff, including the To: Moyer Carol highlighted portions.
Cc: l:wll....Amy; Hiser Matthew
Subject:
FW: ACTION: RIC posters Date: Monday, September 25, 2017 2:45:27 PM Attachments: AdyMfa poster rm docx Importance : High
- Carol, As discussed, we need a proposal for a RIC poster on harvesting by noon tomorro . Matt is on travel, so please work with Amy.
Please use the attached poster for AM as template.
- Thanks, Steve From: Focht, Eric Sent: Monday, September 25, 2017 8:33 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Oberson, Greg <Greg.Oberson@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc.gov>; Rao, Appajosu la <Appajosu la.Rao@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>
Subject:
RE: ACTION: RIC posters FYI, I created a folder on t he G: drive for t his RIC: G:\DE\CMB\RIC\RIC 2017
-Eric From: Frankl, Istvan Sent: Friday, September 22, 2017 3:35 PM To: Rao, Appajosula <Appa josula.Rao@nrc.gov>; Aud rain, Margaret <Margaret.Audraio@nrc.gov>;
Focht, Eric <Eric Focht @nrc.gov>
Cc: Oberson, Greg <Greg Oberson@nrc.gov>; Hiser, Matthew <Matthew.Hiser@nrc gov>
Subject:
ACTION: RIC posters Importance: High Al l, Add it ional posters are needed for the RIC. Brian recommended that we prepare posters for IAD and PWSCC (CGR and Initiation).
Please send me a short description as per the enclosed template by noon Tuesday (I will be in traini ng on Wednesday) .
- Thanks, Steve From: Thomas, Brian Sent: Friday, September 22, 2017 2:44 PM To: Oberson, Greg <Greg Oberson@nrc gov>; Frankl, Istvan <Istvan Frankl@nrc.gov>; Iyengar, Raj
<Ra i.lyengar@nrc,gov>; Boyce, Tom <Tom.Boyce@nrc.gov>; Seber, Dogan <Dogan.Seber@nrc.gov>;
Miller, Kenneth A <KennethA .Miller@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>
Cc: Regan, Christopher <Christopher.Regan@nrc.gov>
Subject:
Re: RIC posters Ok. Let's target the popular stuff:
IAD PWSSC
CONCRETE, ASR, sec MODULES; xLPR On: 22 September 2017 14: 10, "Oberson, Greg" <Greg.Oberson@nrc.gov> wrote:
- Hello, Mike Weber wants RES to propose 4 to 6 more posters for RIC. We have only put forth one idea so far, so we should aim for two more for our division. Please thnk about it and let me know ideas by Wednesday.
Greg
TECHNICAL POSTER/TABLETOP PRESENTATION TOPIC AND DESCRIPTION Poster/Tabletop
Title:
Evaluation of Additive Manufacturing of Metallic Parts via Direct Metal Laser Melting (DMLM)
Poster/Tabletop Topic and
Description:
The NRC has been informed that Additively Manufactured (AM) parts are being considered for applications in the operating fleet as early as calendar year 2018. The first industry alert in June 2017 concerned using the DMLM method to manufacture parts for reactor parts. A sulbsequent scoping study by RES staff provided more insight into the technical issues that must be addressed to assure reliability of specific DMLM-produced components accepted by NRC, including design, precursor materials, finished material properties, structural integrity, nondestructive evaluation, and quality assurance. This poster also discusses the emergence and harmonization of relevant codes & standards activities.
This poster will give an overview of NRC findings and recommendations related to additive manufacturing via DMLM.
Poster/Tabletop Presenter:
- Amy Hull, Senior Materials Engineer, RES/DE/CMB, phone: 301-415-2435, email:
amy.hull@nrc.gov
- NRO?
Note to requester:
Attachments to this email are From: Moyer carol immediately following .
To: l:il.!!I....AmY Subject : FW: Pllm Moyer ABH RO rlt.docx Date: Monday, October 16, 2017 6:45:00 PM Attachments: Plim Moyer ABH RO rlt cem.docx Plim Mover ABH 246-143 R1.docx Sorry - I meant to CC you, as well.
From: Moyer, Carol Sent: Monday, October 16, 2017 6:43 PM To: Tregoni ng, Robert <Robert.Tregoning@nrc.gov>
Cc: Frankl, Istvan <lstvan. Fran kl@nrc.gov>
Subject:
RE: Plim Moyer ABH RO rlt.docx
- Rob, Thanks very much for your detailed review and suggestions for improvement. Please take a look at the revised file (attached) - in both mark-up and clean versions. I will ship the clean version to the other contributors for a quick review.
The files are also in this folder: G:\DE\CMB\2017-006 UNR NRR 2017-006\PLiM paper
-Carol From: Tregoning, Robert Sent: Monday, October 16, 2017 10:37 AM To: Moyer, Carol <CaroLMoyer@nrc.gov>
Subject:
Plim Moyer ABH RO rlt.docx Carol:
Attached is my preliminary mark up of paper. We should talk .....
Rob
MOVER et al.
REGULATORY RESEARCH ON THE AGING MANAGEMENT OF SLRSTRUCTURES, SYSTEMS AND COMPONENTS IN NUCLEAR POWER PLANTS SUPPORTING LICENSE RENEW AL C.E. MOY ER U.S. N uclear Re&,rulatory Commission Washington, D C, USA Ema il: Carol.Moycr@ nrc.gov A.B. H ULL, M. SIRC AR, J. PHILIP, J.E. PIRES, D. D. MURDOC K, T . KOSHY U.S. Nuclear Regulatory Commissio n Washington, DC, USA Abs trac t The U.S. Nuclear Regulatory Commission (NRC) issues licenses fo r commercial power reactors to operate for up to 40 years. These licenses may be renewed for multiple 20-ycar increments. Now that 48 units of the 99 operating commercial reactors in the U.S. have entered the operating period beyond 40 years, their fi rst period of extended operation (PEO) 10 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). However, in order to ensure the continued adequacy of this guidance, research related to aging of SSCs is being conducted now and will continue beyond the receipt of the initial SLR applications. Research is ongoing in the following 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 quali fication and condition assessmenl. The paper wi ll focus on the research related to concrete degradation. including alkali-silica reaction and irradiation damage LO concrete, and condition assessment o f electrical cables.
I. IN TRO DUCTION T he U.S. comme rcia l nuclear power industry intends to submit s ubsequent license renewal applications (SLRAs), which will a llow nuclear power plant (NPP) o peratio n up to 80 years, in accordance with IO C FR Part 54.3 1(d) I that '*a renewed license may be subsequently renewed." However, an SLR applica nt needs to address aging e ffects on passive long-lived systems, structures, a nd compone nts (SSCs) within their SLRA.
Some licensees arc conside ring submitting applicatio11s for a subsequent 20-year (presumably) operating pe riod beyond 60 years. The first of these applications could possibly be subm itted as early as 20 18.
To ensure readiness for review of possible applications for SLR, the NRC has just comple ted the development a nd publishing o f new guidance doctLments, N UREG-2191 and NUREG-2192, 2. 3 for the technical review of SLRAs. An important part o f this g uidance docume nt developme nt was reviewing N PP ope rating experience, including worldwide expe rience with NPP exte nded o pe ratio n. T he technical bases for S LR g uidance are derived from opera ting experience a nd from industry and inde pendent confirma tory research.
Aging management programs (AMPs) are develo ped to anticipate mate rial degradation a nd to help e nsure adequate functionality and safety margins in SSCs. Key technical issues to be addressed in AMPs within subsequen t license renewaJ guidance documents (SLRGD s) include reactor pressure vessel neutron embr ittlement at high fluence; irradiation-assisted stress corrosion cracking of reactor internals and primary syste m components; conc rete and containment degradation, and e lectrical cable qualification a nd condition assessment. 4] T he pape r describes the status of this ongoing research, and focuses on the areas of concrete and e lectrical cable aging manage ment.
- 2. RESEARCH & SLR GUID ANCE DOC UMENT S
lAEA-CN-246-143 The NRC and industry have conducted extensive research over the past several decades to better understand the safety implications and risk associated with aging ofSSCs. Recent presentations (5, <i] reviewed the his tory of NPP license renewal in the U.S and the evolution of the license renewal documents, NUREG-1800 and NUREG-1.80 I [LlJ 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 o ldest plant to postulated aging effects at 80 years' operating experience is nontrivial and required much confirmatory research, both of existing studies and AMP effectiveness audits at plants already in extended operation.
Prior to writing the SLRGDs, extensive research efforts were conducted to understand the sn*engths and shortcomings of the existing guidance documents fo r the initial period of renewal and to try to identify the
' unknown unknowns' [<}.). The 2010 LRGDs were informed by NUREG/CR-6923, JO] 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. T he expanded material degradation assessment (EM DA, N UREG/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 fa ll within the scope of aging management review (AM R) for license renewal.
Thus, in addition to piping and core internals, EMDA also includes the reactor pressure vessel ( RPV), electrical cables, and concrete structures NRC staff recently publis hed the 1400 pg. compendium 12 of AMP Effectiveness Aud its 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 AM Ps. The results from these firs t-of-a-kind audits provided key information to aid the NRC in identifyi ng 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 CA LL-SLR Re1>ort (NUREG-2191)
The two-volume 1190 pg. GALL-SLR Report contains the NRC staff's generic evaluation of plant A MPs and establishes the technical bases for their adequacy. The guidance in this document is for the use of fun1re applicants for SLR and encompasses all of the guidance applicable to initial license renewal.
The 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-speci fic alternatives along with suffic ient justification that the program will adequately manage the aging effects.
2.2 SRP-SLR (NUREG-2192)
T he 509 pg. Standard Review Plan for Review of Subsequent License Renewal (SRP-SLR) provides guidance on the content of applications for renewal of the initial renewed operating license. T he 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
MOVER et al.
The United States' regulations governing the operation ofNPPs, Title 10 oftbe U.S. Code of Federal Regulations, [I] require that Licensees demonstrate safety in design and operation of NPPs. Specifically, IO CFR 54.29(a) requires that licensees manage aging effects so that their intended functions will be maintained consistent with the cu1Tent 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 (iJ include RPV neutron embrittlement at high fluence; 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. RESEARC H ON DEGRA DATl ON TN METAL COMPONENTS
- 4. 1 RPV cmbrittlc ment The safe operation of an N PP relics on maintaining the structural integrity of the RPV during routine operations and postulated accident scenarios. Two key capabilities underpin RPV structural integrity: (I) the ability to predict the behaviour of cracked struct11res under loading, and (2) the ability to predict the effects of irradiation embrittlement on the fracture toughness of RPV steels. Current regulatory procedures depend o n e mpirically based engineering methods that, while generally acknowledged to incorporate large conservatisms, have not necessarily been val idated for SLR conditions. Ongoing researc h is aimed at understanding the adequacy of existing approaches and de veloping 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 guida nce during SLR [ 13].
4.2 IA D of Reactor Internals Limited data are avai lable on irradiation effects at flue nce leve ls cons istent with SLR for properties such as void swelling and resista nce to cracking for reactor internals materials. Preliminary data suggest that the s ignificance of irradiation-assisted degradation (!AD) of LWR vessel internals could increase during long-term operation of N PPs. Particularly, there is interest in understanding the be havior of irradiated stainless steel (SS) weld materials (up to 8 dpa), higher fluence (> IO dpa) SS plate materials, and combined thermal and neutron e mbrittlement of cast austenitic stainless steel (CASS).
Ongoing researc h concerning IAD of RPV internals is focused on assessing the significance of void swelling on the structural and functional integrity of PWR internal components. Research is being conducted o n harvested ex-plant materials. Work is underway to meas ure 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 DEGRADATON 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 expans ion of the altered aggregate by the formatio n 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 (1) the in-situ structural capacity to resist design-basis static and dynamic loads, (2) its future structural 3
IAEA-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 T echnology (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 Energy Agency. In 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.
T he primary objective of this research is to review, evaluate, and enhance the capability to perfonn confinnatory analyses and testing of the effects of irradiation of concrete on the integrity of structures in the prox imity of the RPV over extended periods of operation. T he goal is to provide a technical basis to review plant conditions under AM Ps. 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-term 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 strength) that may affect structural perfom1ance and shielding capacity. Confirmatory testing depends on availability of suitable cores, possibly from decommissioning US plants. This research assesses the structural and safety signi ficancc of concrete irradiation for LTO.
A joint roadmap is being developed by N RC, The US Department of Energy ( DOE), and the Electric Power Research Institute (EPRJ). While EPRI and DOE have jointly published a report on estimated radiation levels for operation up to 80 years. and EPRI has started developing structural assessments, NRC is pursuing coordination with the Halden Research Program for investigating effects of radiation on bond strength. NRC is perfom1i11g fluence modeling to assess configurati on effects. NRC is also developing test plans to study radiation effects on bond strength and creep, and assessing plant configurations and designs to determine 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 prestresscd concrete containment vessels (PCCVs) on their intended safety functions. NUREG/CR-7153 Vol 4, "Aging of Concrete and Civil S1rnctures," [ 11 ] 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, otber repairs, and loss of prestress. As with otber concrete aging mecbanisms, creep and the potential fo r creep-fracture also may interact with other degradation mechanisms, such as ASR, corrosion, and freeze-thaw.
EPRJ, DOE and international organizations, such as the Comm ittee 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/CSNT activity.
- 6. ELECTRICAL CABLE QUALIFICATION AND CONDITION MONlTORING
MOYER et al.
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 control of safety functions. The NRC generic letter, GL 2007-0 1 [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 o n the performance and degradation of both power cables and contro l cables in NPP environments. In re lation to LTO, the NRC is cooperating with DOE and EPRI. A joint ly-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 confi rm that past equipment quali fication practices were adequate, and to determine 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. Fina lly, the aged cables will be subject to loss-of coolant accident testing to determine qualificat io n adequacy and margins.
- 7. CONCLUSION Extending the operating life of exis ting NPPs may be, for some utilities, an economically feasi ble way to meet future energy demands. The responsibility of the NRC is to ens ure 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 veri fy that regulatory requirements wi ll continue to be met. The NRC has conducted confirmatory research to obtain supporting data and to refine models that predict materials degradation during extended aging. Long-term research to confirm the adequacy of guidance for metallic components is ongoing. The NRC is conducting and planning additional research related to concrete structures and electrical cables, to refine 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 Regulations IO CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants, (amended) 1995.
[2) NUREG-2 191, Volumes I and 2, "Generic Aging Lessons Leamed for Subsequent License Renewal (GALL-SLR) Report" (ADAMS Accession Nos. MLI 7187 A03 l and MLI 7 187 A204), 11 90 pp, July 20 17.
[3] NUREG-2 192, *'Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants" (SRP-SLR) (ADAMS Accession No. ML 171 88A I 58) 509pp, July 20 17.
[4) SRM Requirements - SECY- 14-00 16- "Ongoing StafT Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal," August 29. 20 14 (ML1424 l A578).
[SJ Hull, A. B., and Burke, J, "NPP Subsequent License Renewal: Lessons Learned from Aging Management Program (AMP) Effectiveness Audits," Proceedings from SMiRT-23, Manchester UK.
20 15.
[6) Hull, A., Hiser, A., and Lindo-Talin, S., "NPP License Renewal and Aging Management: Revised Guidance," Proceedings from Third International Conference on Nuclear Power Plant Life Management, Salt Lake City, USA 14- 18 May 20 12.
[7) NUREG-1800, Rev. 2, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," 393pp, Dec. 20 I0.
[8) NUREG-1801 , Rev. 2, *'Generic Aging Lessons Learned (GALL) Report," 86lpp, Dec. 20 10.
(9) NUREG-1925, Rev. 3, Research Activities FY20 I 5-FY 20 17," 15 I pp, February 20 16.
( I 0] NUREG/CR-6923, Expert Panel Report on Proactive Materials Degradation Assessment," 2007.
[ 11) NUREG/CR-7 153, "Expanded Materials Degradation Assessment, Vol. 1-5," 20 14
[12) NRC Technical Letter Report, "Review of Aging Management Programs: Compendium of Insights from License Renewal Applications and from AMP Effectiveness Audits Conducted to In form Subsequent License Renewal Guidance Documents." 1400pp, June 15, 20 16 - (MLI 6167A076).
[13) Regulatory Guide 1.99, "Radiation Embrittlement of Reactor Vessel Materials." Revision 2.
May 3 I, 1988.
(14) NRC Generic Letter 2007-0 1 " Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients," February 7, 2007.
MOYER,,
- I.
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~ HQR\4-..a.j REGULATORY RESEARC H ON THE AGrNG MANAGEMENT OF SLRSTRUCTURES, SYSTEMS ANO COM PO ENT S I N NUC LEAR POWER PLANTS SUPPORTING LICENSE RENEWAL C.E. MOYER U.S. Nuclear Regulatory Commission Washington. DC, USA Email: Carol.Moyer@ore.gov A.8. II ULL. M. S IRCAR, J. PHILIP. J.E. PIRES. D. D. MURDOCK. T. KOSII Y U.S. Nuclear Regu lntory Commission Washington. DC, USA Abstracl The U.S. Nuclear Regulooory Commission (NRC) issues licenses for cornniercial power reactors to operate for up to 40 years. These liccn~cs may be renewed for muh1ple 20-ycar increments Nmv thnt 48 unil.s of1hc 99 opcraung commcrcrnl rcaclors: in 1hc U.S. have c111crcd the op'--r.uing pcnod beyond 40 years. 1hcir fir:st period ofcxlcnd(.-d operation (PEO) 10 opcrnlc for up to 60 years. several hcensccs have ind1cutcd intemtefrth:u l ~ d to op11ly w11J1in the ne"t few years for I l
~ubS<.,"quent license rcncw'lll (SLR) for un nddi1ional 20-ycnr period. B~,cd nn cxi,1m.Lknc..w, lcd_g~+ the NRC hrt.'i: created B new set of lieensc renewal guidance documents (LRGDs) ~ for the review of SLR npplications and to communicate cxpccrniions for the oging managemcm of passive. long-lived plant sys1ems. strucrures. nnd components (SSCs). J10\"C"SC, in order 10 cn~urc the con1in11sd adcgun<v o[iln'li auidnn\ic RegoN11ory-,rcscarch ~ O J Hl-...aging nltffltt1;'-~t'k!'f1H,fSSCs is being CQnductcd now ond will con1inm: beyond th~ rcccip1 of the innial SLR application~....~ ..,
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- 111 the follo\"ing four areas: reactor pressure vessel (RPV) ncu1ron cmbrinlcment. irrodiauion ossi.stcd :.lrcss corrosion crocking (IASCC) of reactor vessel internals. concrete and con1oinmen1 degrodotion. ond clcc11icnl coble quolificotion ond l
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mented [ RLn ]: Oon't th lnk we nc-c<i 10 rocus o n ihty 1hat ~ arch m1y rcqutre II cl~llMC 10 our gmd i1ntc m lh1$
condition assessoncnt. The paper w,11 focus on r"!;ttltH-O<y-~rcscarch related to concrete dcsmdntion. mcluding '11kali-silic,l Commented [CM2Rl]: Can we cdrt the Ab<tmc1 ,i ohi! hmc?
rcac1ion and irr.sdiot1on damage 10 concrete. and condi1ion m,$cssmcnt of electrical cubics. I ~c nothing wrong ~"'11h the s:rnttmc:nl ocher than 1hc fact 1ha1 ii nmy be obvk>u"- We ore OOinv conlirmutory rac;:irch. &o confirm adcquncy ofguidoncl.' docum:n1s; that. 1fimplemented.. shou.ld rewlt I. INTRODUCTION in ;w.l<<auruc prutrt.-1-.m ofhcahh & !,,Jlely.
Commented [CM3]: lfch:en~cs 10 1he u~l rl(t Urt' ucccplLtblc. I The U.S. commercial nuclc-ar power industry intends to submi t subscqucn1 license renewal applications do not object 10 Rob's propo~ t:dits on this p.YDifUph (SLRAs)_ which will allow nuclear power plant (NPP) operation up 10 80 years, in accordance wi1h 10 CFR Pan S4.3 1(d) U.l thot "a renewed license may be subsequently renC\\ed." However. me-jln S I R appltcpnt 11e00-1e-feSel""1)6tdltt11H~ httteal-ehttllettge,,-fre1tt-nccd, to pddre" aging effcc1s o n passive long-lived system, structures, and components (SSCs) befure-11,e.NR{' eatt-ltf)pftM>-\\ i1hin their SLR.As. Tll&-NR{rls,11,,..11re 1h~
sSomc licensees arc considering submilling applications for a subsequent 20-ycar {presumably) opcrming pcri I beyond 60 year,,. The first o f t hese applications could possibly be submiucd as early a, 2018.
To e1\Sure readiness for review of possible applications for SU{, the NRC has j ust completed the development and publishing of new guidance documents, NUREG-2191 and NUREG-2192. [2. lj for the lechnical review of btK.'l~>>it.'tllt0t¥.,-SJ..M.,,1ha1-WOukJ....tltlhon,"4)ffln~apt'ft+liOtr4,,,y.,nd~ . Ah impo1tant pan of this guidance documenl development ~ was reviewing NPP 01>eroling experienc,I, including worldwide experience with N l'P ex1endcd operation. The 1echnical bases for SLR guidance arc derived from operating experience and from industry and inde pe ndent confirmatory research.
Aging management programs (A Ml's) arc developed 10 anticipate mate rial degradation and to help ensure adequate functionality and safety margins in SSCs. Key 1echnical issues to be addressed in AMPs wilhin subsequent license renewal guidance documents (SLRGDs) ~s identified by SRMSECY- 14-0016. Commented [ RLT4]: Do "-c really wam 10 rcfol"t'noe an S RM in
{ML14241A578) I_4J include "rcac1or pressure vessel ncu1ron cmbrittlcmcm al high Ouencc: irradia1ion-assis1ed an opcn-.Jitcrature paper? I w{)Uld jus t dc~tc 1his c lause stress corrosion cracking of reactor internals and primary system components: concrele and containment Commented [CM5R4J: Agreed. ,he ob,;a,rc document l)'J>C degradation. and electrical cable qualiticalion and condition assessment." The paper describes the status of this does not need to be menuoned m the tut The rererence [4] should be n:a,vcd lO the end oft.be sco(tnce ongoing research, pa.rtieuhtrly in and focuses on the areas of concrete and electrical cable aging management. J
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- 2. RESEA RCI I & S LR GUIDANCE DOCUMENTS Commented [ RLT6 ] : Thls is CO\'ercd (or should be co,i:rcd) in Allen's paper. Shouldn'I \\cjus1 rcfcrcna: hi.~ pa~r here 111nd climim11c the tc...'<17 If not, \\C rnn the nsk ofslating somcth.ing thal's either contr.tdlc'lOry, U\ConsLQcnt. or re!;uh m confu~IOn for The NRC and industry have conducted extensive research over the past several decades to bener SOmc()nC rcodmg bolh papers.
understand the safely impli cmions nnd risk associated with aging of SSCs. Recent presentations [5. 6j reviewed the history of Nl'P license renewal in 1hc U.S and 1hc evolution of 1l1e license renewal documcms, NUREG-1800 and NUREG-1801 7, 8J for the initial period of renewal. 1-1-,..,.~~~'<>fllt.....-;.'<rtl ltmttrillOlb .. tloti-ctl~,wrgy ,~,Ii.. l't\Ftll11U\...,_ ht, ~r-oYf. nuchmr p-tt""t:r ~,:!'n't!ra\h.m will '-'tlll11m.~ lo ht---H i.!nltcttl CAA'tf'l'll<AI Ill lh< m,*,
- f ell<rg, flrt1tlllctt~A 'Tllefe I IRU<tl mg m.Jw+tfy--ffil~h*,t--f11 !,1.R Mild ~*pp '""~ l<Flll ore, ltlk)ll I I T-0~ l><>..on,ii"" liN Pl O I \ICtH.itllt jh., -Of'<'rttlU'!' ~+1... ol ~,..... nt NPP, tllily~,..~ ,... '*'lll<' -t!ithltt.,"-.
ut>-<<,Ml<"lliwl-1" lelt"1hl...-wa,,-10 Hl<"el.fttltlk-<!O,,t ~y,kmot><h- ~ltN ll>><< f)ffffll, em.,,..J ,1.,,..bh'f"' at,on 11;-:!+~l<l-:-H,u- 11..,,.. .,...-lt-J,.,..,_.1' :,a,,,~""'"'" Being able to extrapolate any observed aging effects from 1hc existing operat ing experience of less 1han 50 yenrs for lhc oldest plani to pos1ula1ed aging effects at 80 years' opera1ing experience is non lrivinl and required much conlirm,uory research, bolh of cxis11ng sllldics and A \1P effcclivcness audits al plants alrc.1dy in extended opernt ion.
Prior to writing the SLRGDs. extensive research effons were conduc1ed lo under.Hand the strengths and shoncomings of the cxis1ing guidance documen1s for lhc ini1ial J>eriod of renewal and to try to iden1ify the
- unknown unknowns* (9). The 2010 LRGDs were informed by NUREGIC R-6923. lll!J 1he J>roactive nmlcrial degradation assessment (PMDA). TI1c PMDA program used cxpcn clicirntion to iden1ify and assess various ma1crials degradation mechanisms that could a1Tcc1 plant SSCs for operation up 10 40 years. Dcgroda1ion scenarios were rnnkcd according 10 1he probabili1y of occurrence. level of knowledge concerning 1ha1 process.
and confidence in scores . n,c expanded material degradation asscssmcni (EM DA. NUREGICR-7153) lf IJ evaluated a broader range of SSCs. up to 80 years. TI,e mntcrials and sys1ems addressed in EMDA arc generully extended 10 a ll of 1hosc which foll wi1hin the scope of aging mn,mgcment review (AMR) for li cense renewal.
Thus. in addition to piping and core in1cmals. EMDA also includes the reactor press ure vessel (R.PV). electrical cables. and co11cre1c strnctun."S NRC stnff recently published 1hc 1400 PIL compendium I 2j of AMP Effcc1ivcncss Audits undcnakcn to provide a more complete undcr.nanding of how A MPs have been implemented by plants during the PEO and lhc degradn1ion that has been identified by the AMPs. The results from 1hcse first-of-a-kind audits provided key infonnation to aid 1hc NRC in idcnlifying needed changes 10 cxis1ing AMPs and new AM Ps 1h01 may be needed to 1mwido ussurance of safe 1>lant operation during an SLR opernting period. The knowledge obtorncd from 1hcse audi1s was a primary source enabling 1hc stuff to develop new SLRGOs. to be used following 1hc lir,1 PEO.
- 2. 1 C ALL-S LR Repor t (N UR EC-2191)
The two-volume 1190 Pill' GALL-SLR Report contains !he NRC siaffs generic cvahrulion o f plant AMPs und establishes lhe technical bases for their adequacy. The guidance in this document Hnu 11,,,..{,AI I SI R R-1~11 ...., , for 1hc use of future a pplicanls for SLR ,rn~ JI"' NR( .~..,.. ""' 1111<<Nl t<+ 1n1ro,<"dk:' ~u,Jttrn:e Commented [ CM7]: 1n,s *PP"""' r,'<lundnni, m 1ht......k,euml.'tll-1tfl~LL~'>b-R R.!f""1 ..,,~--t>-ll-itt*lwr.......,1 ......,-+11ttHtl--or,<.'fillHtt. ~,,,.,,..,,._..,...,,...~
Ii.,,..,., 1h1 ,It'"""'" *A<l 111, (,,\11 'ii ll llef*Hn e ncompass£:, all of 1he guidance applicable 10 initial license renewal. i:!1;, GAi L-SUl R<'f"*tH,lu~,M l - . . J n h.a- ....,llt 11l!mt1u*11.,...,11,'1'1)f*>~t,~""1fl-t.,r<"1 llttt1 1 g:~11~Al'ttlly ttflY,lh..tthll!. '<'='t'r.AinJlp ~hllh <-L~Hllt:l~r af 1R1llul OJ'tltt.llR~' ltt'~R ~. 11 "~11 11 ht1Mt~
tlf'f'ttl'ttt1h-lt1t 1t111Htt-l~"'-f-t1h1,11y- "'"""'""l~ho,,.._.,._.,._.,.,..._..,..,n A~P--ttHlt...-GA! f~'il R-lh,potHII
!}~ ' , ! H O & , Jfo.,..-,.~1'1'ffl'ttfll-ht1~><~t0l-Hl.,~;~lffl.lft"4-""'-';.t,,fW" Wttlt--lhe Ci \I I SIR Herttn Th< <, '\11 "I R. R<Jttttl-f" tde B ~"'""'" < uluflltl*ll ,,r ".~ A14P UIHl ""
Hl.'~'l'ftltthlc Ht-1.'ihoJ ht mHnttg'-'"~lll~1:?flt!'\: ~- 1l+lm1~1lt!'l:tfi~ ttlt~1Httl1¥t:'""i mtt~ ~ ('r-o ~ ~
The GALL-SLR Repon identifies 1hose material. environment and aging effect combinations thal require aging management during 1hc s ubscqucm period of extended opcra1ion (P EO). including approprialc AMPs.
Applicants are responsible for identifying in their applications any additional items that requ ire aging managemcnl. Although tbe GALL-SLR Report identi Gcs one accep1ablc approach to manage aging effects.
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~ HQR\4-..a.j applicams may propose plant-specific altcmativcs along with sufficient justification that the program will adequately manage the aging effects.
The content of NUR EG-2191 was significantly revised from that of the GALL Repon., 'U REG-1801, Rev. 2. Some AMPs were retired, others were added. For example, in those dcsignaied as mechanical A MPs, in the XI.M section, AM Ps X I.M S. "8WR Feedwater Nozzle," and AMP X 1.M6, "8WR Control Rod Drive Return Linc Nozzles" were retired. A new AMP X.M2, Neutron Fluence Monitoring" was added that provides a method that may be used to accept neutron irradiation embrittlcment time limited aging ana lyses (TLAAs) for RPV components in accordance with IO CFR 54.21(c)(I )(iii). This is the TLAA acceptance c riterion that states the effects of aging on the intended function o r functions of the components will be adequately managed during the PEO. The AM P X I.E3 was expanded into three new AMPs to address aspects of industry and NRC guidance related to potentially submerged cables: These are AMP XI.E3A "Medium Volrnge Power Cables," AMP Xl .E38 **Jnstnomcnt and Contro l Cables." und AMP XI.E3C "Low Volrngc Power Cables (both alternate and direct c urrent) ." To reduce the burden for applicants. AMR line-11cms were made more specific. the n umber of AMR line-items citing a plant-specific AMP was sig nificantly ri."<luced, and concomitantly. those that were focused 111creased. Thos resulted in the to tal number of A MR line items increasing from I 52 1 line items in the GALL Report Rev 2 to 2613 for the GALL-SLR Report. Commented [ CM8]: This paragraph l, no, really ahou1 research.
I 1hinl st can be ddc1i:d, 2.2 S RP-SL R ( UR EC-2192)
The 509 pg. Standard Review Plan for Review of Subsequent. License Renewal (SRP-SLR) provides guidance on the content of applications for renewal of the initial renewed operating license. n,. 1>rm,' tf>, I f'ttf~ih.---AA-!1-M-R di<- t t h " l - ~ ~ " " ' 1 t W... I ~ 1 t t l f f \ . i ~ - - -""1 J~tiO\."ll hi-,~-.f1om ~tud* h.t ..:'fttllttH1!"-tt1~lt1.:wnl progrunt.. ttnJ ~hYth't"'~ l(~r Ht~ "7'llh'l.ftk.--H'1 Pf*<). fttlh.*Y..1~ Ii
- lit'*-2~111-PlO (*~w 11>11t,1l--lt<<11,..,_,..,...,v...i-,,.,m.J) TI, "RI' S.l R 111,,., ,,..111l~1...kd ""'""~ T.:' ~Ii*
11 1f,,,n, lM*,* y,.i.*tL*lY"flY.d\tl111~1+--4* '* h ,w::.._,......,1,1t-t1H1 h..-~¥-Hl-.. 1~1 ,....,1 n :.r I t , f*h;:: I thin 00 , ... m ,,
pvw,
- nJlt--t y'it1 J- 1 11 11i,1m*'r ~u iii\.. nut tttt.h,.... I tttttk .,f u h1 H dw. ~K< tt- C'H1.W- ,..rtt\: *s The :r;.afc Commented [ CM9]: ThcS< 1,onoons co11"1 be d<lcttd for tire, uy.
review is based primarily on the informatio n provided by the applicant in a SLR application. Each of the individual SRP-SLR sections addr~sscs: (i) who pcrfonns the review. (ii) ar~us or 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 *1>plican1s to identify acceptable aging management a pproaches, Lhe SRP-SLR provides guidance 10 the staff for its review of SLR applications. 11,e SRP-SLR ensures a consistent and transparent review of S LR applications by documenting 1he acceptance criteria and review procedure, tha1 will be used by tl1c staff in its reviews. 11~ ""'"°"' ol 111< S.Rf'-SI R , h,i-,1l
~ l nl C,/t.l I 'i l M R,,H,rl . lhu lt!htlll~t: I'" lA~ <, *\ l l Fl.I{ R~p,tH I l:IFI! -~ne,l~tl l:ii~ ~A-tin!:'~ Ill lit ~ ~ ~ I 2.3 Docum ents S u p11o rtlo g SLRG Ds To clarify the process and the changes. a Techn ical Bases document [ 13] and an analysis of public comments [14] will accompany the SLRGDs. Both arc knowledge management and knowledge trans fer documents associated with NUREG 2 191 (GALL-SLR) and 'UREG- 2 192 (SRP-SLR). 11,c first documents the technical changes for the review of SLRAs that were made from the gu idance contained in Rcvi.sion 2 of NUREG 1801 (the GALL Report) and NUREG-1800 (SRP-LR). Consequently. this document provides the underlying rationale that the N RC staff used to develop t he S LRGDs. The second document contains the RC staffs analysis of the public comments received 011 the dralls of NUREG--2 191 and NUREG- 2 192. Public comment drnlls of the GALL-SLR Report and tbc SRP-S LR were published on December 15, 2015. with the public comment period expiring o n Febnoary 29. 20 16. A supplement 10 the draft SLRGDs was published on March 29. 2016. witb the public commeat period expiring on May 31. 2016. The dispos ition of comments that t he NRC staff agreed with nnd used as tbe basis for instituting a c hange to either the GALL-SLR Report o r t he SRP-SLR arc detailed in this document. In addition, the public comments that did not result in a change to either NUREG a.re also dispositioned, and the staff's technical basis for not agreeing with these comments is presented. Both documents are expected to be officially published al the end of 2017.
3
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/R 1gM-k,1.J ~fffliA-Hlt'-t.e,td ~ ..1..r p,e,. --1...t.._...- ,mw.. ~ I¥- RvHa&~--p..W.-hn-kJ.-\.~ , -4tRlh.....l RG 1.188 [ 15] will be revised in the process of reviewing and endorsing NEI 17-01 [ 16] which replaces NEI 95-10. Rev. 6 [ 17]. The , El 17-0 I industry guideline for implementing the requirements of 10 CFR Pan 54 for SLR provides an acceptable approach for implementing the requirements of IO CFR Pan 54. the License Renewal Rule, referred 10 a~ the Rule, for SLR. The process outlined io El 17-01 is founded on industry experience in implementing the Rule for initial license renewal and on the lessons lcamed from that industry experience that can be applied 10 SLR. h is expected tlmt following this guideline will offer a stable and e fficien1 process, resuhing in 1hc issuance of a renewed lice nse. However, applicants may elect to use otl1cr sui1ablc methods or approaches for satisfying the Rule's requirements and completing an SLRA. COmmented [CM10) : I pmpose dcktmg 1his sec11on. It 1s very "rcgul1uory," ond u does not supp,on the confirmn1a1*y rcs~ch s1ory that we are tc.ll1ng,
- 3. REGULATORY RESEA RCHj Commented [ RLT11]: Haven't \\.C atrcfKly fritatcd the 1nfom13lt0n 1n Secoon J?
The United States* regulations govcm ing 1he operation ofNPPs, Title 10 of 1he U.S. Code of Federal Commented [ CM12R11]: Tius upnnd.s on the ln1roductt0n Regulations. [ I] require that licensees demonstrate safety in design and operation ofNPPs. Specifically. 10 CFR "°mc:whul I think 11':. OK 54.29(a) rcqllires that licensees manage aging effects so thn11heir imcnded functions will be maintain~d consistent with Lhe current licens ing basis (CLB) for the PEO. In its mission 10 ensure prolecuon of the public hcahh and safely. the NRC conducts confirmatory research 10 bcner undcrsrnnd and quom ify various dcgrodo1ion mechanisms that may impact N l'P SSCs. *n,is research enables regulatory confidence regarding aging management of safety-related SSCs. Rcsuhs from these ongoing researc h programs reduce uncenninty regording license renewal and SLR, and hdp the regulator 10 maintain oppropriotc levels ofconserva1is111 in NRC regu lations and guidance.
Key technical issues 10 be addressed for LTO [4 include RPV ncu1ron cmbriulc111cn1 01 high nucncc:
IASCC ofreoclo r intcmnls and primary system componen1s: concrete a nd contai nment dcgrndnt ion. nnd electrical coble q uolificnt1on and condition assessment.
- T he paper describes the stotus of this ongoing research.
particlllarly in Lhc areas of concrelc and electrical cable aging management.
- 4. MA-'1'6RIAbS IS&l,6S.FOR \4681AN-IGA~-Ni:8-Rl;_S~RCI LQ'I QEQl~.t\OL\T!Ql,I IN
\.1ETAL ( 01\11'0"'1 , I
- 4. 1 RPV cmbritllcmc nt The safe operation of an NPP relics on main1aining the s1ruc1Urul integrity of the RJ'V during ro utine operations and postu lated accident scenarios. Two key capabilities underpin RPV struc turol integri ty: (I) the abi lity to prcdic1 1l1e behaviour of cracked structures under loading. and (2) the ability 10 predict the cffcers of irradia1ion cmbriulcmen1 011 the fracture toughness of RPV steels. C urrell! regulatory procedures depend on empirically based engineeri ng methods that, while generally ack11owlcdged lo incorporate large conservatisms.
have nol necessari ly been validated for SLR conditions. Ongoing research is aimed al understandi ng the adequacy of existing approaches and developing new models and predictive procedures as needed. ~
inclU<.le!--b,ue, ,uch n> late blooming phases ( LBPs), aucnuation. ,!fil[_n ux cffec1s an; bcinLt c1,1lua1cd. Work is also underway to evaluate the continued adequacy of a"ociatcd regulatory gurdancc dunng SLR RG-l ,99~R<w
~ 18)-dllrn,g the perre.i ef HP.HlfK~ett+tttlly-;,ol,;,e(tt1en1-tteet1**re11e,, *L . Fllt e*rsmple . .iurittg e*t1enwe Gperat ion~ th**~*edtc1-tOR!!-Of...RG- L99-ten<l 16-ttll<ler-j>redict the-etnbr.11kment tre,l<l~ f " e d Ul-ej><>Allmg
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4.2 IA D or Re,1c1or Int ernals
~ I im ited data ;!J.Lavailablc on irradiation effects a1 nuencc levels consistent with SLR for propenics s uch as void swelling and resistance 10 cracking for reaclor internals materia ls. Preliminary data suggest that the significance of irradiation-assisted degradation ( IAD) of LWR vessel intemals could increase during l>elh 1lie 111itrnl liee1>se reeev, el pe,1ea (1.e., 48 le 68 , eers) amt d 1 ~ t - -lo11ger-1crin opcra1ion of NPPs . Particularly. there i, in1crc,1 tn undcr~tanding lhe bch:iviorrr -ill'.M,i-of. rn:.-ea-tnclude;-of irradiated stainless steel (SS) weld maleria ls (up to 8 dpa), higher nuence (> 10 dpa) SS plate materials, and combined 1hem1al a nd neutron embriulcmcnt of cast aus1cni1ic stainless steel (CASS). % t k - t k l ~ ~ ~ , e ~ffi!et, llr the.-mlll *gmg ,..,a ,mu:limietHiamag,, en CA&&
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"<!Ssel-intemlll mflter.illb-attrin~tentttll-e.i~idt,d epera1ien-t1j H ~ngoing researc h concerning IA of' RPV internals is focused on assessing the signiiicance of void swelling on the stn,crural and functional integrity of PWR internal components. Research is being conducted on harvested ex-plant materials-e;,-,w Qft-Fef'FeseHtell e tneteri11ls 1m181fileti-tt1 te"it FeeeteFS. Work is underway to mea~urc att-fracture toughness an IASCC for stainless steels & welds. Gt>ff6S16ft-fettgoo-eHfffldt~1als 15 1,eoni; tc!Stetl et Argeru,e Netien
~ Effects of environment and irradiation may be additive or synergistic; further testing wi I confirm the comhrncd nature of these eOccts. Tests ere 1ilenned far fuAl,er iFffldiauea ef :~erite 1Jle1e 1ne1eFi11I I Wf)'-htglt-llt~1'81:-lhs,tHeltttt'ttet.,.;,e;,~w,;1ttttj,"'ttnd-m,;ehtoftiee'1>ro~*-
- 5. RES!;L\RC'I I QN CONCR ETE AND CONTA INMENT DEG RA DA TON S. I AS R Alkali-Silica Reac tion (ASR) is a chemical degradation in concrete that may occur over time as a reaction between the highly ulkalinc cement paste and reactive non-crystalline (amorphous) silic,1 found in many common aggregates. This reaction causes the expans ion of the altered aggregate by the fom1ation of a swelling gel of c.ilciu,n silicate hydrate (C-S-H). The objec1ivc of the research program i;, to develop the technical basis for generic regulatory guidance to evaluate ASR affected NPP concrete s tructures through its service life.
including SLR). TI,e intended outcome of the research is a methodolob'Y to detennine for an /\SR-affected structure (I) the in-situ sm,ctural capacity 10 resist design-basis static and dynamic loads. (2) its fu1ure structural capacity. and (3) a recommended AMP eonsis1en1 with the guidance in SRP-SLR for managing the aging effects of ASR in e xis ting structures.
The NRC sponsors experimental research at the National Institute of Standards and Technology (NIST) 1ha1 involves a combination of testing and modelling 10 study ASR effects on nuclear concrete structures. TI1is program involves assessing in-situ mechanical prope11ics of ASR-affected concrete. bond and lap splice lengths of reinforcing bars, and the seismic response characteristics of structural members. The NRC is panici1>ating i~
an international coopcrnt ivc research program to a;,scss structures subjected 10 concrete pathologies, under the Nuclear Energy Agency. In addition. the RC is involved in a collaborntive program with the technical suppon organizations for the French regulator.
S.2 Radiation induced dcgradntion of concr ete Irradiated concrete can ,mdergo degradation similar to ASR: swelling aggregate cracks the cement phase.
The primary objective of th is research is 10 review, evaluate. and enhance the capability to perform confinnatory analyses and testing of the cffecis of irradiarion of concrete on the integrity of structures in the proximity of the RPV over extended periods of operotion. The goal i, to provide o technica l basis to review plant conditions under AMP~. 4< "' , ,I-,~ .,... ,..i.. w 4,w.-1. ""~* , f "11<<,n-,,, I >k i,. r - ., .,..M 12 ....Ovqr ~ mented [RLT13]: Du we r.:cd ,o >tale dus ogain'I ~
extended 1>criods of operation. concrete structures in the proximity of the RPV, the primary and biological s hield wa lls and the RPV support strncturns for example. can be subjected to high levels of neutron and gwnma rad iation together with sui,tained operating temperatures up 10 about 150° F. Long-1crn1 neutron and gamma irradiation on concrete of the reactor suppons and shie lding structures cw, affect dimension,.
- I -,httnrl (radiation induced volumetric expansion). micro-cracking of the cement paste. and physical and structur~J propcnies o f concrete (e.g., reduction of compressive strength. tensile strength, modulus of elasticity, bond strength) that may affect strnctural performance nnd shielding capacity. Conlirn1atory testing depends on availability of suitable cores. possibly from decommission ing US p lants. 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 (EPRJ). While EPRJ and DOE have jointly published a repon on estimated radiation levels for operation up to 80 years. and EPRJ has started developing structural assessments, , RC is pursuing coordination with the Halden Research Program for investigating effects of radiation on bond strength. NRC is performing nuence modeling to assess conligurat.ion effects. NR C is also developing test plans to s tudy 5
IAL\-CN-H6-I ~, 11-.44<
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5.3 Aging manageme nt of pr estrcssed conc re te containment struct ures The objcc1ive of1his projcc1 is 10 study 1he effecls of ageing and modifications of vPrestrcssed {cconcre1e C1.on1ainmcn1 V_\.cssch (PCCV~) on 1hcir i111encled safety func1ions. NUREG/CR-7 153 Vol 4. "Agi11g of Concrete and Cfril Structures." [ 'l.] iden1ificd creep and lhc polential for creep-related fracture as an aging concern applicable 10 PCCVs because of 1hc susiained, muhi-axial loading from the prcs1rcssing. This is rclevanl for aged PCCVs where reinforcement in 1he rndial direction is not present, and when prcs1ressing syslems require adjus1me111s such as modifications for s tcnm gcncralor repl accmen1. 01her repairs, nnd loss of prcs1rcss. As wi1h 01her concrc1c agi ng mechanisms. creep and 1J1c poten1ial for crccp-frac1urc a lso may intcrnc1 wi1h olher dcgrada1ion mechanisms such as ASR. corrosion, and frceze-1haw.
EPRI, DOE and in1crnational organiza1ions, such as 1hc Commi11cc for the Safety of uclcar lns 1alla1ions of 1hc Organizalion for Economic Ocvclopmcnl ,ind Cooperation (OECD/CSNI) nrc coopcrJling lo address shrinkage. creep, drying. and moisture 1ransport. Spccificnlly. 1his activity focuses o n benchmarking aspects of VERCORS. a comprehensive muhiycar study ofa 1/3 scale PCCV 1ha1 focuses on aging effcc1s, compu1ational modelling and use of non-destructive cva lualion 1cchniqucs (NOE) and sensors for structural moni1oring.
Elec1rici1e de France (EDF). which sinned, funds and executes VERCORS, is making infonnation and darn from this study available 10 1hc OECO/CSNI oc1ivity.
- 6. ELECT RICAL CABLE QUALIFICATION A D COND ITION MON ITORING Elec1rical cables are oncn overlooked or ignored in aging analyses and conditio n moni1oring evalua1ions because they arc passive componcms 1ha1 arc generally considered 10 require no routine inspcc1ion and maintenance. lk*IW-.., .el lcctrical cables arc very important safety componcnts~hu,,,"" because they provide power 10 snfcty-rcla1cd cquipmen1 and arc used for ins1rumcnrn1ion and control of safety func1ions. The NRC generic lcncr, GL 2007-01 [!2), s howed 1h01 a ,ignilicanl number of failures occurred under nonnal service condi1ions within 1he service interval of 20-30 years. which is before 1he renewed license period and before 1he end o f the expcc1cd life span of1hc cables. The RC has pursued research on the pcrfonnance and degrJdotion of both power cables and control cables in NP t> environments. In rela1ion 10 LTO, lhc NRC is coopcra1ing wilh DOE and El'RI. A joi ntly-developed roadmap for cooperative research is being used to keep complementary 1es1ing progroms on 1rack.
Research in this area is investigaiing me1hods LL~cd for simulated aging of e lec1r ical "'l'"f"""t-<: hk, as well as condi1ion monitoring 10 confirm 1ha1 pas1 cquipme111 ql1alifiea1ion prnc1iccs were adcqua1c. and 10 detcnnine o p1imu111 condi1ion 111oni1oring methods to monitor cable aging in periods of ex1cnded license renewal. Ongoing research prnjects have obtained new and naturally aged cable samples 1ha1 will be subjected 10 synergistic effects of radia1ion 1empcra1urc, and humidily similar 10 1ha1 seen in opern1ing NPPs. /\ number or condi1ion-moni1oring techniques will be applied during and following aging protocols 10 dc1crmine condition
-monitoring met hod predictive capabili1y. Finally. the '>'""'~"l""'a,. aged cables will be subject to loss-of coolan1 accident testing lo determine qualification adequacy ru1d margins.
- 7. CONCLUSION Commented [ R.Ln4J: Why don't we'"'""" 1n}1l11ng about the research lhal wc*re domg.. even 1f it's o .seoteoce or two. ...
A-A--tt--, e meAI t)I F~illh 1-rt~ttff~) ,mplelnt'IH~tl 111;:t!'n. It!' Fl:!'Plt.'.\*OI :\MP, *.. a r,*rftHl~.--1-tfl--d Ot.'lt~r u1kl~1:,ldfkltnr,--1;,f -4h~rh~numtma fflul--Jnttntt~t:'fln.>n1 t .f ~c ltt11.- lfl'tth!nal.. Jt:~1tklatH.H l nlt.1'\.l\t-11tt.,nh. unJ H>looltt!<Hl,e--tl.,y"1af,~>l-4~~-0H~~ Ex1ending lhe operating life of existing P Ps may be, for some utilities, an economically feasible way to meet future energy demands. The responsibility of th e NRC is to ensure !hat plant life extension is safe - !hat 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
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~HQR\4-..a.j involves rigorous safety and environmental reviews to verify that regulatory requirements will continue to be mel. 1 h1..* .t,.:RC h<h ,:oJldut:tl:'d c.:onlinn.1~01)_ n:~~;trch lo.Qhl,un supr,t1r1111Y..9at.1 mt.I o_r~tinc moc.Jd, that rrc.d1 mJkriab '-kgrnJ.111on dunng c,tcmk*J a4m1?. Lnng-1cn11 rl.:'scarch ht contim\ thl' adi:gual.'y ol gtmlant:~ I( r JlU.:J,1JlK...ffi...11Jl!Qt1£D_h ,.., ,n.~Q1.~u\lJiLJti.Q.1J~.u~11ng .u~L.vJa111J.!.!Jg_Jtilil!.tJ1.~nt1LrJ;,1.~M~*h.Kl,1h;~o!_1.£££I
...tn1ctun...... nnJ clc~1ncal cahlt:sJ, Ill ri:linc uur um.Jcrstandmg_ ur dc,g_rndullon that mu_)* .1ff..:,1 th~,c plJ1 t m:untcnuncc_..._hght l\,Hcr reactor-. ma.y_h~..:rntcd througb 1hc SI R-..ncnr~J safe~
7
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/R1gM-k,1.J~fffliA-Hlt'-t.e,td ~ ..1..r *p,e,.--1...t.._...- ,mw.. ~ 1¥-RVHa&~--p.W-hu-kJ.-\.~ , -4tRlh."'1 R EFERENC ES (I) Code of Federal Regulations 10 CFR r*a rt S4, Require ment< for Renewal of Operating Licc1bC* ror Nuclear Power Plants. (amended) 1995.
(2) NURl:G-2191, Volumes I ond 2, **Generic Aging Lessons Learned ro r Subsequen1 License Re newa l (GALL-SLR) Report" (ADAMS Accession Nos. MLl7187A031 anti MLl7187A204). 1190 pp. July 2017.
(3) NUREG-2192, "S1andard Review Pinn for Review o f Subsequent License Renewal Appliemions for Nuclear Power Plams" (SRP-SLR) (ADAMS Accession No. MLI 7 188A 158) 509pp, July 2017.
(4) SRM Requiremcn,s - SECY-14-0016- "Ongoing S111ff Acthitie< 10 Asscos Regulatory Coosidcra1ions for Po we r Reactor Subsequent License Renewal," Augusl 29. 2014 (MLl424 I AS78).
(51 ll ull, A. 0 .. und Burke. J, "NPP Sub,equcni License Rcncwul : Les,ons Learned from Aging Mcinagcmc nt Program (AMP) Effectiveness AudiL,i;* Proceedings: from SMiRT ~23, Manchcs1cr UK, 2015 .
(6) I lull, A., lliscr. A.. and Linclo-Talin, S .* N PP Licc,,se Renewal a nd Aging Managemcn1: Revised Guid:mcc."' l>roccodmg:s from Third lntcmalional Conference on Nuclcur Power Plan1 Life Monagcmc n1. Salt Lake City, USA 14-18 May 2012.
[7) NUREG-1800. Rev. 2...Siandard Review Plan for Review or License Renewal Applica1ions ror Nuckur Power Planis," 39Jpp. Dec. 20 10.
(81 NURC:G-IROt , Rev. 2. "Gcncnc Agmg Lessons Learned (GALL) Report," 861pp. Dec. 2010.
(9) NUREG-1925, Rev, 3. "Research Ac11v11ics FY2015-l'Y 20 17, I Sipp. Fcbruwy 2016.
[ !OJ NUREG/CR-6923, "Ex:pcr, Panel Repon on rroocuve Mo1criul< Degrndo1ion Assessment," 2007.
[ 1IJ NURl2G/C R-7IS3. "Expanded Malerial* Ocgrudauon Asses.mcnL Vol. l -5."201 4
( 12) NRC Technical Lcucr Report. "Review of Aging M11nagcment Prol!J'ams* Compendium or Insights from License Renewal Applications ond from AMP Effectiveness Audits Conduc1ed to lnfom, Subsequent License Rcnewol Guidance Docum~11ts." 1400pp, June 15. 2016 (ML16167A076).
11.f -!\.l~M:I~ .- ""I.. 1-fthtlff ~-lfft..ei ft.ti ( 'I It~\: tt "'~~~ l.H:."'l!t~.Jt.:1-..,.w.o-l (~1J.1ttt.+-4>..'t,:ttH :-ttH Ma-lU-C~Uht-tJ.M.RH, ll~. I> l r t ' - " " ' ~ r ' " ' I " " " ~ ~ * ~
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_ , >HR!( ~ P'loud>l'IHC <l"~ " INr1, <<1~_,,,..µ,,,_.....,i..,,~>H-o f l~ -M~.ufo+t-ttThlfflh.....t l~ -H~-Y- t "~ndntJ h,rn1it1I .o~J , ... ,,,k4nt-Hw .\rr~i,.'ftittfft,....,.t,. -R~w,w--..Jl..ttt.-kttt 11,......,-l'lttt!H 't"'"'*"'r- i-..,,..,~~~OO<.,
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{ 171 fl I J os 111. Mt: t "' f . ..Iii 1n H\ {,t1*,k-i11t<"' it" lttti,ltr cflhN~ tltc Rt"qttlftlll~Ul~I fl Pdrl f I Bto. I t~'fl!'ll""'-.' R,c. ~w,J.Puk- Jl..11.. tatr l n<< '" lt-....HlHh.: ~ -,)f' ,,11\o 2-00~
J.l.;llLl.LRegulatory Guide 1.99, "Radia1io11 Embrin lcmenl or Reactor Vessel Ma1erials." Revision 2.
May 3 1, 1988.
IO)lliLNRC Generic Letler 2007--01 "Inaccessible or Und erground Power Coble Failures 1ha1 Disable Accident M itigalion Systems or Cause Plant Transients:* February 7. 2007.
Note to requester:
Attachment to this email is immediately following .
From: Moyer carol To: Tregoning Robert Subject : FW: PLIM paper
- draft for review, also 390 form Date: Monday, October 16, 2017 7:33:00 AM Attachments: Plim Mover ABH RO.docx.
NRC 390 GEM PLIM4.od{
- Rob, Thanks in advance for you r review efforts!
-Carol From: Hull, Amy Sent: Friday, October 13, 2017 10:17 AM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>; M oyer, Carol <Ca rol.M oyer@nrc.gov>
Subject:
PLI M paper - draft for review, also 390 form See attached.
- VIOYER et a l.
REGULATORY RESEARCH ON THE ACING MANAGEMENT OF SLRSTRUCTURES, SYSTEMS AND Note to reque ster: This COMPONENTS IN NUCLEAR POWER PLANTS document included the yellow SUPPORTING LICENSE RENEWAL highlighted pages w he n received by the NRC FOIA staff.
C.E. MOYER U.S. Nuclear Regulatory Commission Washington, DC, USA Email: Carol.Moyer(wnrc.gov A.B. IIU LL, M. SIRCAR. J. Pl IILIP, J.E. PIRES. D. D. MURDOC K. T. KOSIIY U.S. Nuclear Regulatory Commission Washington, DC, USA Abstract The U.S. Nuclear Regulatory Commission (NRC) issues licenses for commercial power reactors to operate for up to 40 year;,. These licenses may be rem:wed for multiple 20-year increments. Now that 48 units of the 99 operating commercial re,1ctors 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 intention to apply\\ ithin the next l'cw years for subsequent license renewal (SLR) for an additional 20-year period. The NRC has created a new set ofliccrn,e renewal !,\Uidance documents (LRGDs) to be ready for the review of SLR applications and to communicate expectations for the aging management of passi\ e. long-lived plant systems, structures. and components (SSCs). Regulatory research on the aging management ofSSCs is being conducted now and will continue beyond the receipt of the initial SLR application, to confirm the adequacy of these guidance documents through the SLR period. Should regulatory research identify concerns related to aging management. regu latory guidance may be revised to reflect the new results. Regu la tory research is ongoing in the following four area,: n:actor pressure \esscl (RPV) neutron embritth:mcnt, irradiation as;.istcd stress corrosion cracking (IASC'C') of reactor vcs,,el internab. concrete and containment degradation. and electrical cable qualification and condition assessment. The paper will focus on regulatory research related to concrete degradation, including alkali-silica reaction and irradiation damage to concrete. and condition assessment of electrical cable~.
I. I TRODUCT ION T he U.S. commercial nuclear power industry intends 10 submit subsequent license renewal applications (SLRAs). whic h wi ll allow nuclear power plant (NPP) operation up to 80 years. in accordance with IO CFR Part 54.3 1(d) [I] that "a renewed license may be subsequently renewed." I lowever, the NPPs may need to resolve potentia l technical challenges from aging effects on passive long-lived systems, structures. a nd components (SSCs) before the N RC can approve SLRAs. The NRC is aware that some licensees a rc considering submitting appl icatio ns for a subsequent 20-ycar (presumably) operating period beyond 60 years. The first of these appl icatio ns could possibly be submitted as early as 2018.
To ensure readiness for review of possible applications for SLR. the NRC has just completed the development a nd publishing o f new guidance documents, NUREG-2191 and N UREG-2192. [2, 3] for the technical review of such applications that would authorize plant operation beyond 60 years. An important part o f this guidance document development activity was reviewing NPP operating experience. including worldwide experience with NPP extended o peration. The technical bases for SLR guidance arc derived from operating expe rience and from industry and independent confirmatory research.
Aging management programs (AM Ps) are deve loped to anticipate material degradation and to help ensure adequate functionality and safety margins in SSCs. Key technical issues to be addressed in AM Ps within subsequent license renewal guidance documents (SLRGDs) as identified by SRMS ECY- 14-0016.
(ML14241A578) [4] include "reactor pressure vessel neutron embrittlement at high flue nee; irradiation-assisted stress corrosion cracking of reactor internals and primary system components: concrete and containment degradation. and e lectrical cable qualification and condition assessment. T he paper describes the status of this ongoing research. particularly in the areas of concrete and electrical cable aging management.
IAEA-CN-123/45
- 2. RESEARCH & SLR GUIDANCE DOCUMENTS The NRC and industry have conducted extensive researc h over the past several decades to better unde rs tand the safety implications and risk associated with 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. NU REG-1800 and NUREG- 180 I [7, 8] for the initial period of renewal. The existing 99 licensed. operating commerc ia l NPPs were granted 40-year licenses on the basis of economic and antitrust considerations -- not technical limitations. As g lobal encr1,,y needs continue to grow. nuclear power generation will continue to be a critical component in the mix of energy production. There is increasing industry interest in SLR and NPP long-term operation ( LTO) beyond the first PEO. Extending the operating life of existing PPs may be. for some utilities.
an economically feasible way to meet future energy demands. The first three plants entered extended o peration in 2009; thus they each have 4 8 years operation. Being able to extrapolate any obsen ed aging e ffects from the existing operating experience o f less than 50 years for the o ldest plant to postulated aging effects at 80 years' operating experience is nontrivial and required much confirmatory research. both of existing studies and AMP e ffec tiveness audits at plant~ already in extended operation.
Prior to writing the S LRGDs. extensive research efforts were conducted to understand the strengths and sho rtcomings of the ex isting guidance documents for the initial period of renewal and to try to idcnti fy the
- unknown unknowns* (9). The 2010 LRGDs were informed by NUREG/C R-6923, (10] the proactive material degradation assessment (PMDA). The PMDA program used expe11 e licitation to identify and assess various materials degradation mechanisms that could a ffect plant SSCs for operation up to 40 years. Degradatio n scenarios were ranked according to the probability of occurrence, level of knowledge concerning that process.
and confidence in scores. The expanded material degradation assessment (EM DA. NUREG/CR-7 153) [ 1 ll evalua ted a broader range o f SSCs. up to 80 years. T he materials and systems addressed in EM DA arc generally extended to a ll of those which fall within the scope of aging management review (AMR) for license renewal.
Thus. in addition to piping a nd core internals. EM DA also includes the reactor pressure vessel ( R PV), electrical cables. and concrete structures NRC staff recently published the 1400pg compendium [12) of AMP Effectiveness Audits undertaken to provide a more complete understanding of how AMP!> have been implemented by plant~ 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 S LR operating period. The knowledge obtained from these audits was a primary source enabling the sta ff to develop new SLRGDs, to be used following the first PEO.
2.1 GALL-SLR Report (NUREG-2191)
The two-volume I I 90pp GALL-SLR Report contains the RC staff s generic evaluation of plant A MPs and establishes the technical bases for the ir adequacy. The guidance in this document and the GALL-SLR Report are for the use of future applicants for SLR. The NRC does not intend to impose the g uidance in this document and the GALL-S LR Report on current holders of an initial operating license renewal. However, this document and the GALL-SLR Report encompass all of the guidance applicable to initial license renewal. T he GA LL-SLR Report should be treated in the same manner as an approved topical re port that is generically applicable. Accordingly, both c urre nt holders of initia l operating licenses as well as future applicants for initia l license renewal may voluntarily choose to reference a n AMP in the GALL-SLR Report in their applications.
However. such applicants should inform the N RC that they plan to demo nstrate consistency with the GALL-SLR Report. T he GA LL-SLR Report provides a generic evaluation of ex isting AM Ps and an acceptable method to manage aging effects. plant-specific alternatives may be proposed.
The GALL-SLR Report identifies those material. environment and aging effect combinations that require aging management d uring the subsequent period of extended operation (PEO), including appropriate AM Ps.
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.
- VI OYER et a l.
applicants may propose plant-specific alternatives a long with sufficient justification that the program will adequately manage the aging effects.
The content of NUREG-2 191 was significantly revised from that of the GALL Report, NUREG-180 I.
Rev. 2. Some AMPs were retired, others were added. For example, in those designated as mechanical AMPs. in the XI.M section, AM Ps X I.MS, BWR Feedwater Nozzle." and AMP X I.M6, "BWR Control Rod Drive Return Line Nozzles" were retired. A new AMP X.M2, "Neutron Fluence Mo nitoring" was added tha t provides a method that may be used to accept neutron irradiation embrittlcment time limited aging ana lyses (TLAAs) for RPV components in accordance with IO CFR 54.2 1(c)( I )(iii). This is the TLAA acceptance criterion that states the effects of aging on the intended fu nction or functions of the components wil l be adequately managed d uring the PEO. The AM P XI.E3 was expanded into three new A MPs to address aspects of industry and N RC guidance related to potentially submerged cables: These arc AM P X I. E3A "Medium Voltage Power Cables," AMP XI.E3B " Instrument and Control Cables," and AMP XI. E3C " Low Voltage Power Cables (both alternate and direct current)." To reduce the burden for applicants, AM R line-items were made more specific, the number o f AM R line-items citing a plant-specific AMP was significantly reduced. and concomitantly. those that were focused increased. This resulted in the total number of AMR line items increasing from 152 1 line items in the GALL Report Rev 2 to 26 13 for the GA LL-SLR Report.
2.2 SRP-SLR (NUREG-2192)
The 509 pg. Standard Review Plan for Review of Subsequent License Renewal (SRP-SLR ) provides guidance on the content of applications for renewal of the in itial re newed operating license. The principal purposes of the SRP-S LR arc to ensure the quality and uniformity of NRC staff reviews and to present a well-defined base from which to evaluate applicant programs and activities for the s ubsequent PEO. fo llowing the fi rst 20-year PEO (i.e., the initial license renewal period). The SRP-SLR a lso is intended to make regulatory information widely available to enhance communication w ith interested members of the public and the nuclear power industry and to improve public and industry understa nding o f the NRC staffs review process. The safety review is based primarily on the information provided by the applicant in a SL R application. Each of the individual SRP-SLR sections addresses: (i) who performs the review, (ii) areas of review, (iii) bas is 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 managemen1 approaches, the SRP-SLR provides guidance to the s taff 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. The content o f the SRP-SLR is based on that of GALL-SLR Report: thus changes in the GALL-SLR Report a rc reflected by changes in the SRP-SLR.
2.3 Documents Supporting SLRGDs To clarify the process and the changes, a Technical Bases document [ 13] and an analysis o f public comments [ 14] will accompany the S LRGDs. Both arc knowledge management and knowledge transfer documents associa ted with NUREG 2 191 (G ALL-SLR) and NUREG 2192 (SRP-SLR). The first documents the technical c hanges for the review of SLRAs that were made from the g uidance conta ined in Revis ion 2 o f NUREG- 180 I (the GALL Report) and NUREG- 1800 (SRP-LR). Consequently, this document provides the unde rlying rationale that the NRC staff used to develop the S LRGDs. The second document contains the N RC staffs analysis of the public comments received on the drafts of UREG-2191 and NUREG-2 192. Public comment drafts of the GALL-SLR Report and the SRP-SLR were published on December 15. 20 15. with the public comment period expiring on February 29. 2016. A suppleme nt to the draft SLRGDs was published on Ma rch 29, 2016. with the public comment period expiring on May 3 1, 20 16. The disposition of comments that the NRC staff agreed with and used as the basis for instituting a change to e ither the GALL-SLR Report or the SRP-SLR a re detailed in this document. In add ition. the public comments that did not result in a change to e ither NUREG arc also dispositioncd. and the staffs technical basis for not agreeing with these comments is presented. Both documents arc expected to be o fli cia lly published at the end of 20 I 7.
3
I AEA-CN-123/45 RG 1.188 [ 15] will be revised in the process of reviewing and endorsing NEI 17-0 I [ 16) which reploces NEI 95-10. Rev. 6 [ 17]. The NEI 17-0 1 industry guideline for implementing the requirements of IO CFR Pan 54 for SLR provides an acceptable approach for implementing the requirements of 10 CFR Part 54. the License Renewal Rule. referred to as rhe Rule. for SLR. The process o utlined in NE! 17-01 is founded on industry experience in implementing the Rule for initial license renewal and on the lessons learned from rhat industry experience that can be appl ied to SLR. It is expected that following this guideline will offer a stable and efficient process. resulting in the issuance or a renewed license. I lowever, applicants may e lect to use other suitable methods or approaches for satisfying the Rule's requirements and completing an SLRA.
- 3. REGU LATORY RESEARCH 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. IO CFR 54.29(a) requires that licensees manage aging effects so that the ir 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 10 better understand and quantify various degradation mechanisms that may impact NPP SSCs. This research enables regulatory confidence rcgan.ling 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 or conservatism in NRC regulations and guidance.
Key technical issues to be addressed for LTO f4) include RPV neutron cmbrittlcmcnt at high Oucnce; IASCC 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. MATERIALS ISSUES FOR MECII A ICA L COMPO E TS 4.1 RPV cmbritlle ment The safe operation of an NPP relics on maintaining the structural integrity of the RPV during routine operations and postulated accident scenarios. Two key capabili ties underpin RPV structural integrity: (I) the ability to predict the behaviour of cracked structures under loading, and (2) the ability to predict the effects o r irradiation embrittlement on the fracture toughness of RPV steels. Current regulatory procedures depend on empirically based engineering methods that. while generally acknowledged to incorporate large conservatisms.
have not necessarily been validated for SLR conditions. Ongoing research is aimed a t understanding the adequacy of existing approaches and developing new models and predictive procedures as needed. Concerns include: late blooming phases (LBPs), attenuation. Oux effects. Work is underway to evaluate the continued adequacy of RG 1.99, Rev 2 f 18] during the period of first and potentially subsequent license renewals. For example, during extended operations the predictions of RG 1.99 tend to unde r-predict the embrittlement trends observed in operating reactors.
4.2 IAD of Reactor Internals There is limited data available on irradiation effects at fluence levels consistent with SLR for properties such as void swelling and resistance to cracking for reactor internals materials. Preliminary data suggest that the significance of irradiation-assisted degradation ( IAD) of LWR vessel internals could increase during both the initial license renewal period (i.e.. 40 to 60 years) and during even longer-term operation of NPPs. Particular areas of need include: irradiated stainless steel (SS) weld materials (up to 8 dpa}, higher Ouence (> IO dpa) SS plate materials. and combined thermal and neutron embrittlement of cast austenitic stainless steel (CASS). Work is addressing the synergistic effects ofthcrn1al aging and i1Tadiation damage on CASS.
The objective of this research is to provide confirmatory technical basis for the perfonnancc of reactor vessel internal materials during potential extended operation up to 80 years. Ongoing research concerning IAD of RPV internals is focused on assessing the s ignificance of void swelling on the strnctural and functiona l
- VI OYER et al.
integrity of PWR internal components. Research is being conducted o n harvested ex-plant materials as well as on representative materia ls irradiated in test reactors. Work is underway on fracture toughness and IASCC for stainless steels & welds. Corrosion fatigue of irrad iated materials is being tested at Argonne National Laboratory (ANL). Effects of environment and irradiation may be additive or synergistic; furthe r testing will confinn. Tests are planned for further irradiation of Zorita plate material to very high fluence (80 dpa), then characte rizing void swelling and mechanical properties.
- 5. CONCRETE AND CONTAINMENT DEGRADATON
- 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 format ion o f a swelling gel of calcium silicate hydrate (C-S-11). The objective of the research program is to develop the technical basis for generic regulatory guidance to evaluate ASR affected N PP concrete structures through its service life, including S LR). The intended out<.:ome of the research is a methodology to determine for an ASR-affectcd
- -truc turc (I) the in-situ structura l capacity to resist design-basis static and dynamic loads, (2) its future structural capacily, 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 experimenta l research at the National Institute of Standards and Technology (N IS T) that involves a combination of testing and modell ing to study ASR effects on nuclear concrete structures. T his program involves assessing in-s itu mechanical properties of ASR-affcctcd concrete, bond and lap splice lengths of reinforcing bars and the seismic response characteristics of structural members. The N RC is participating in an interna tio na l cooperative research program to assess structures subjected to concrete pathologies, under the Nuclear Energy Agency. In addition. the NRC is involved in a col laborative program with the technical support o rganizations for the French regulator.
5.2 Radiation induced degradation of concrete Irradiated concrete can undergo degradation simi lar to ASR; swelling aggregate crach the cement phase.
The primary objective of this research is to review, evaluate, and enhance the capability to pcrfonn confirmatory analyses and testing of the effects o f 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 AM Ps. Another goal is to inform development of S LRGD updates for the review of AMPs. Over extended periods of operation. concrete structures in the proximity of the RPV, the primary and biological shield walls and the RPV s upport structures for example. can be subjcctcd to high levels of neutron and gamma radiation together with sustained operating temperatures up to about 150° F. Lo ng-term neutron and gamma irradia tion on concrete of the reactor s up ports and shielding structures can affect dimensional change (radiation induced volumetric expansion), micro-cracking of the cement paste, physical and structural properties of concrete {e.g.. reduction of compressive strength. tensile s trength, modulus of elasticity, bond strength) that may affect structura l performance and s hie ld ing capacity. Confirmatory testing depends o n availabi lity of suitable cores. possibly from decommissioning US plants. This research assesses the structural a nd safety significance of concrete irradiation for LTO.
A joint roadmap is being developed by N RC. The US Department of Energy (DOE). and the Electric Power Research Institute (EPRI). While EPRI and DOE have jointly published a report on esti mated radiation levels for operation u p to 80 years, and EPRI has started develo ping structural assessments, N RC is pursuing coord ination with the I la ldcn Research Program for investigating effects of radiation on bond strength. NRC is pcrfonning nucncc modeling to assess configuration effects. NRC is also developing test plans to study radiation e ffects on bond strength and creep, and assessing plant configurations a nd desig ns to de te rmine the range of plant conditio ns that would indicate a need fo r aging management.
5
IAEA-CN-123/45 5.3 Aging management of prestresse d concrete containment structures The objective of th is project is to study the effects of ageing and modifications of Prestressed Concrete Containment Vessel (PCCV) on their intended safety functions. NUREG/ CR-7153 Vol 4. '"Aging o/Concrete and Civil Structures," [ I I] identified creep and potential for c reep-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. o the r repairs, a nd loss of prestrcss. As w ith o ther concrete aging mechanisms, creep and potentia l for creep-fracture a lso may interact with other degradation mecha nis ms such as ASR, corrosion, a nd freeze-thaw.
E PRI, DOE and international organizations, such as the Committee for the Safety of Nuclear Installations of the Organization for Economic Development and Cooperation (OECD/CSN I) arc cooperating to address shrinkage. creep, d ryi ng, and moisture transport. Specifically, this activity focuses on benchmarking aspects o f VERCORS, a comprehensive multiycar study of a I / 3 scale PCCV that focuses on aging effects, computational modelling and use of non-destructive evaluation techniques (N DE) and sensors for structural monitoring.
E lectricitc de France (EDF), wh ich started, funds a nd executes VE RCORS, is making information and data from this study available to the OECD/CSNI activity.
- 6. ELECTRICAL CABLE QUALIF ICATION AND CONDITION MON ITORING E lectrical cables arc oficn overlooked or ignored in aging analyses and condition monitoring evalua tions because they arc passive components tha t arc generally considered to require no routine inspection and maintenance. I lowcvcr, electrical cables arc very important safety components because they provide power to safety-related equipment a nd arc used for instrumentation and contro l of safety functions. The NRC generic letter, GL 2007-0 I [ 19], showed that a s ignificant numbe r of failures occurred under no rma l service conditions within the service interval o f 20-30 years. which is before the renewed license period and before the end of the expected life span of the cables. The RC has pursued research on the performance and degradation of both power cables and contro l cables in N PP environments. In relation to LTO. the NRC is cooperating with DOE a nd EPR I. 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 equipment as well as condition monitoring to confirm that past equipment quali fication practices were adequate and to determine o ptimum 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-monito ring method p redictive capability. Finally, the synergistically aged cables will be subject to loss-of coolant accident testing to determine qualification adequacy a nd margins.
- 7. CONCLUSION An assessment of results fro m currently implemented license re newal A MPs was performed to obtain a better understanding of the phenomena a nd management of certain materials degradation mechanisms. a nd informed the development of the S LRGDs, completed in 2017. Extending the operating life of existing NPPs may be. for some utilities. an economically feasi ble way to meet future energy demands. The responsibility of the RC is to ensure that plant life extension is safe - that it does not pose additional risk to public health and safety o r lo the environment. The NRC's process for concl uding that a renewed operating license can be issued involves rigorous safety and environmental reviews to verify that regulatory requirements will continue to be met.
- \<JOVER et al.
REF ER E'.'.CES
[I) Code of Federal Regulations IO CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants. (amended) 1995.
[2) UREG-219 I. Volume, I and 2, "Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Report" (ADAMS Accession Nos. MLl7187A031 and ML17187A204). 1190 pp. J uly 20 17.
l3] NUREG-2192, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants" (SRP-SLR) (ADAMS Accession No. ML17188A158) 509pp. July 2017.
(4J SRM Requirements - SECY- 14-00 16- "Ongoing Staff Activities to Assess Regulatory Considerations for Power Reactor Subsequent License Renewal." August 29, 2014 (MLl424 I A578).
15] llull, A. B., and Burke, J, "NPP Subsequent License Renewal : Lessons Learned from Aging Management Program (AMP) Effectiveness Audits." Proceedings from SMiRT-23, \llanchcster UK.
2015.
[6] Hull. A .. Hiser. A.. and Lindo-Talin. S .. "NPP License Renewal and Aging Management: Revised Guida nce." Proceedmgs from Third International Conference on Nuclear Power Plant Life Management. Salt Lake City. USA 14 18 May 20 12.
[7) NUREG-1800, Rev. 2. "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." 393pp. Dec. 20 I 0.
(8 1 NUREG-1801 , Rev. 2. "Generic Aging Lessons Learned (GALL) Report." 861pp. Dec. 2010.
l 9] NURC: G-1925, Re\ . 3. "Research Activities FY2015-FY 20 17," 151 pp. Fcbniary 20 16.
l I OJ NUREG/CR-6923. "Expc11 Panel Report on Proactive Material, Degradation Assessment." 2007.
1111 NURCGICR-7 153. "Expanded Materials Degradation Assessment, Vol. 1-5," 2014
[ 12] NRC Technical Letter Report. "Rcvic\\ o f Aging Management Programs: Compendium of Insights from License Renewal Applications and from AMP Effcctivem:ss Audits Conducted to In form Subsequent License Rene\,al Guidance Documents. 1400pp, June 15. 2016 (MLl6167A076).
l'l JJ NUREG-xxxx, *'Technical Bases for Changes in Subsequent License Renewal Guidance Documents UREG-2 191 and UREG-2 192," 48 I pp. expected publica11on December 2017.
[ 14] NUREG-xxx. "Disposition of Public Comments on the Oran Subsequent License Renewal Guidance Documents NU REG 2191 and NU REG 2 192," 479pp. expected publication December 2017.
l 15] Regulatory Guide I.I 88. Rev. I. "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," September 2005.
[ 16] NEI 17-0 I, "Industry Guideline for Implementing the Requirements of I OCFR Part 54 for Subsequent Licern,e Renewal." Drafi March 20 17.
[ 17] NEI 95- 10. Revis ion 6. " Industry Guideline for Implementing the Requirements of IO CFR Part 54 -
The License Renewal Ruic." Nuclear Energy Institute, 245pp. June 2005.
(18] Regulatory Guide 1.99. "Radiation Embrittlemcnt of Reactor Vessel Materials." Revision 2.
May31.1988.
f 19] NRC Generic Letter 2007-0 I " Inaccessible or Underground Power Cable Failures that Disable Accident M itigation Systems or Cause Plant Transients." February 7. 2007.
7
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 390 10-2011 NRCMD 3.9 RELEASE TO PUBLISH UNCLASSIFIED NRC STAFF SPEECHES, PRESENTATIONS, PAPERS, AND JOURNAL ARTICLES (Please typ e or print)
- 1. TITLE (St*to In flJl/,s ltap~ar1 on u,, spHCh, preHnlllllon, ~~r. or}ouma/artlcle) 2. ADAMS AccHlion No.
(Uae Templat* ADM 039)
REGULATORY RESEARCH ON THE AGING MANAGEMENT OF STRUCTURES, SYSTEMS AND COMPONENTS IN NUCLEAR POWER PLANTS SUPPORTING LICENSE RENEWAL
- 3. AUTHDR(o)
C.E. MOYER, A.B. HULL, M. SIRCAR, J . PHILIP, J . E. PIRES, D. D. MURDOCK, T. KOSHY
- 4. NAME OF CONFERENCE, LOCATION, AND DATE(a)
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- 10. CERTIFICATION YES NO (ANSWER ALL QUESTIONS)
Speeches, presentations, papers, and journal articles require management and policy reviews of technical and policy
._./ D A TECHNICAL AND POLICY REVIEWS - issues per NRC Directive Handbook 3.9, Section 11.A.2. Check the "YES" box to certify that the speech, presentation, paper, or journal article COJnfl!ies with this statement.
Does this speech, presentation, paper, or journal article contain copyrighted matertal?
D0 8. COPYRIGHTED MATERIAL If ves, attach a letter of release from the source that holds the copyright Does this speech, presentation, paper, or journal article require patent dearance?
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If ves, the NRC Patent Counsel must signify clearance by signing below.
SIGNATURE DATE Is all material referenced in this Sfl':ech, presentation, paper, or journal artide available to the public either through a 0D D. REFERENCE AVAILABILITY -
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Does this speech, presentation, paper, or journal article contain measurement and weight values? If yes. all must D0 E. METRIC UNIT CONVERSION - be converted to the International System of Units, followed by the English units in brackets, pursuant to the NRC Policy Statement lmolementlna the Omnibus Trade and ComMtitiveness Act of 1988 Executive Order 12770 Julv 25 1991.
- 11. RESPONSIBLE STAFF MEMBER NAME (Type Of print name) OFFICE/DIVISION MAIL STOP Carol Moyer RES/DE T-10A36 SIGNATURE I DATE TELEPHONE NUMBER (301) 415-2153 E-MAIL 1.0.
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Note to requester:
Attachments to t his email are immediately following .
From: HJser Matthew To: Hiser Allen Subject : FW: Harvesting Workshop Agenda Brainstorming Date: Monday, November 21 , 2016 10:49:36 AM Attachments: Workshoo Agenda 11-4* 16.docx NRG Harvestina Workshoo Announcement.docx If you get a chance, please take a look at the draft agenda and provide any comments or feedback.
From: Hiser, M atthew Sent: Friday, November 04, 2016 12:48 PM To: Hiser, Allen <Allen.Hiser@nrc.gov>
Cc: Tregoning, Robert <Robert.Tregoning@nrc.gov>
Subject:
FW: Harvest ing Workshop Agenda Brainstorming Tying you into this discussion on the harvesting workshop per Rob's suggestion. Any input much appreciated © From: Hiser, M atthew Sent: Friday, November 04, 2016 12 :46 PM To: Purtscher, Patrick <Patrjck.Purtscher@nrc.gov>; Tregoning, Robert
<Robert.Tregoning@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>
Subject:
RE : Harvesting Workshop Agenda Brainstorming Hi Rob, Pat, and Jeff, Please find attached my updates to the agenda based on our discussion yesterday. It may be somewhat premature, but I went ahead and tried to put t imes to the agenda, just to see how it might schedule out. Session S is probably the main area of uncertainty along with international presenters in general.
Please take a look and provide any comments or feedback by next Wednesday, so we can hopefully finalize this and share with DOE/EPRI very soon.
I also attached the latest version of the workshop announcement, which we plan to use to publicize to other attendees and presenters.
Thanks !
M att Origina l Appointment-----
From : Hiser, M atthew Sent: Wednesday, November 02, 2016 2:34 PM To: Hiser, Matthew; Purtscher, Patrick; Tregoning, Robert; Poehler, Jeffrey
Subject:
Harvesting Workshop Agenda Brainstorming When: Thursday, November 03, 2016 1:00 PM -2:00 PM (UTC-05:00) Eastern Time (US &
Canada).
Where: HQ-TWF N-08C01-10p Hi Rob, Jeff, Pat, I've put together an outline of an agenda for this workshop on harvesting that we are planning for March. My first cut at it is attached. I'd like to use this meeting to brainstorm how to structure the workshop and, if possible, who to ask to present and on what topics.
Rob and I were discussing trying to selectively target participants and presentations to cover the topics we'd like, rather than simply asking DOE and EPRI and others for their take on "harvesting." I think if we plan this well, we can get an interesting and substantive discussion. If not, we may just get a rehash of SLR-type talks ...
Thanks!
Matt
<< File: Agenda Outline.docx >>
Ex-Plant Materials Harvesting Workshop Location: NRC HQ in Rockville, MD Dates: March 7-8, 2017 Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning pla nts, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, iriradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated .
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking avai lable materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants
Draft Agenda - March 7-8, 2017 Harvesting Workshop Tuesday, March 7, 2017 Introduction
- NRC overview of workshop purpose and objectives 8:00 - 8:10 Session 1: Lessons learned from harvesting experience
- EPRI Perspective on Harvesting Lessons Learned 8:10 - 8:45 o Zorita, Baffle Bolts, Barsebeck, etc.
- DOE Perspective on Harvesting Lessons Learned 8:45 - 9:20 o Zion, etc.
- NRC Perspective on Harvesting Lessons Learned 9:20-9:50 o Shoreham, St. Lucie, Zorita, Zion, etc.
BREAK 9:50 - 10:05
- Japan - JNES / JNRA 10:05 - 10:40 o International Perspective on Harvesting Lessons Learned DISCUSSION 10:40 - 11 :30 LUNCH 11:30-12:30 Session 2: Technical data needs best addressed by harvesting
- PNNL/NRC 12:30 - 12:55 o Overview of data needs best addressed by harvesting
- Belgium - Tractebel 12:55-1:20 o Perspective on harvesting data needs, particularly RPV
- Korea - KAERI? 1:20 - 1:45 o Perspective o n harvesting data needs, Kori plant
- Switzerland - ENSI or PSI? 1:45 -2:10 o Perspective on harvesting data needs, Mulhleberg DISCUSSION 2:10 -2:45 BREAK 2:45 - 3:00 Session 3: Sources of Materials
- NRG 3:00 -3: 15 o Available materials from decommissioning plants and past harvesting programs
- EPRI / NEI 3:15 -3:45 o Available materials from operating reactors and past harvesting programs
- IAEA? 4:15 - 4:45
- International harvesting opportunities
DISCUSSION 4:45 - 5:30 Wednesday, March 8, 2017 Session 4: Practical aspects of Harvesting
- US decommissioning company 8:00 - 8:40 o Decommissioning process vs. harvesting: schedule, site-specific, timing for different components
- International decommissioning company - Germany? 8:40 - 9:20 o Decommissioning and harvesting plans and experience
- US utility 9:20 - 10:00 o Decommissioning process and plans o Owner perspective on harvesting and decommissioning BREAK 10:00 - 10:15
- Researcher perspective - EPRI or DOE or international 10:15 - 10:45 o Practical challenges to plan for and carry out harvesting DISCUSSION 10:45 - 11 :45 LUNCH 11 :45 - 12:45 Session 5: Harvesting Decision-making
- PNNL / NRC 12:45 - 1:15 o Technical information needed for informed harvesting decisions
- EPRI/NEI 1:15 -1 :45 o Balancing costs and benefits to ensure value from harvesting
- DOE 1:45-2:15 o Applying past experience to future harvesting decisions
- International - ? 2:15-2:45 o Harvesting decision-making
- DISCUSSION 2:45 - 4:00 o Potential harvesting partnerships
- RPV, internals, piping, concrete, cables
- US, international opportunities
Discussion Topics
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking available materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants
Note to requester:
Attachments to this email From: HJser Matthew are immediately following.
To: Poehler Jeffrey Subject : FW: Harvesting Workshop Agenda Brainstorming Date: Monday, November 21, 2016 10:28:17 AM Attachments: Workshoo Agenda 11-4-16.docx NRG Harvestina Workshoo Announcement.docx Hi Jeff, Just wanted to check if you had any input to provide on the harvesting workshop agenda (attached).
Thanks !
Matt From: Hiser, M atthew Sent: Wednesday, November 09, 2016 10:37 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Poehler, Jeffrey
<Jeffrey.Poehler@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Hiser, Allen
<Allen.Hiser@nrc.gov>
Subject:
FW: Harvesting Workshop Agenda Brainstorming Just wanted to send a reminder for feedback/ input on the workshop agenda.
Thanks!
Matt From: Hiser, M atthew Sent: Friday, November 04, 2016 12:46 PM To: Purtscher, Patrick <Patr ick.Purtscher@nrc.gov>; Tregoning, Robert
<Robert.Tregoning@nrc.gov>; Poehler, Jeffrey <Jeffrey.Poehler@nrc.gov>
Subject:
RE : Harvesting Workshop Agenda Brainstorming Hi Rob, Pat, and Jeff, Please find attached my updates to the agenda based on our discussion yesterday. It may be somewhat premature, but I went ahead and tried to put times to the agenda, just to see how it might schedule out. Session 5 is probably the main area of uncerta inty along with
international presenters in general.
Please take a look and provide any comments or feedback by next Wednesday, so we can hopefully finalize this and share with DOE/EPRI very soon.
I also attached the latest version of the workshop announcement, which we plan to use to publicize to other attendees and presenters.
Thanks I Matt Original Appointment-----
From: Hiser, M atthew Sent: Wednesday, November 02, 2016 2:34 PM To: Hiser, M atthew; Purtscher, Patrick; Tregoning, Robert; Poehler, Jeffrey
Subject:
Harvesting Workshop Agenda Brainstorming When: Thursday, November 03, 2016 1:00 PM-2:00 PM (UTC-05:00) Eastern Time (US &
Canada).
Where: HQ-TWF N-08C01-10p Hi Rob, Jeff, Pat, I've put together an outline of an agenda for this workshop on harvesting that we are planning for March. My first cut at it is attached. I'd like to use this meeting to brainstorm how to structure the workshop and, if possible, who to ask to present and on what topics.
Rob and I were discussing trying to selectively target participants and presentations to cover the topics we'd like, rather than simply asking DOE and EPRI and others for their take on "harvesting." I think if we plan this well , we can get an interesting and substantive discussion. If not, we may just get a rehash of SLR-type talks ...
Thanks!
Matt
<< File: Agenda Outline.docx >>
Ex-Plant Materials Harvesting Workshop Location: NRC HQ in Rockville, MD Dates: March 7-8, 2017 Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning pla nts, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, iriradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated .
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking avai lable materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants
Draft Agenda - March 7-8, 2017 Harvesting Workshop Tuesday, March 7, 2017 Introduction
- NRC overview of workshop purpose and objectives 8:00 - 8:10 Session 1: Lessons learned from harvesting experience
- EPRI Perspective on Harvesting Lessons Learned 8:10 - 8:45 o Zorita, Baffle Bolts, Barsebeck, etc.
- DOE Perspective on Harvesting Lessons Learned 8:45 - 9:20 o Zion, etc.
- NRC Perspective on Harvesting Lessons Learned 9:20-9:50 o Shoreham, St. Lucie, Zorita, Zion, etc.
BREAK 9:50 - 10:05
- Japan - JNES / JNRA 10:05 - 10:40 o International Perspective on Harvesting Lessons Learned DISCUSSION 10:40 - 11 :30 LUNCH 11:30-12:30 Session 2: Technical data needs best addressed by harvesting
- PNNL/NRC 12:30 - 12:55 o Overview of data needs best addressed by harvesting
- Belgium - Tractebel 12:55-1:20 o Perspective on harvesting data needs, particularly RPV
- Korea - KAERI? 1:20 - 1:45 o Perspective o n harvesting data needs, Kori plant
- Switzerland - ENSI or PSI? 1:45 -2:10 o Perspective on harvesting data needs, Mulhleberg DISCUSSION 2:10 -2:45 BREAK 2:45 - 3:00 Session 3: Sources of Materials
- NRG 3:00 -3: 15 o Available materials from decommissioning plants and past harvesting programs
- EPRI / NEI 3:15 -3:45 o Available materials from operating reactors and past harvesting programs
- IAEA? 4:15 - 4:45
- International harvesting opportunities
DISCUSSION 4:45 - 5:30 Wednesday, March 8, 2017 Session 4: Practical aspects of Harvesting
- US decommissioning company 8:00 - 8:40 o Decommissioning process vs. harvesting: schedule, site-specific, timing for different components
- International decommissioning company - Germany? 8:40 - 9:20 o Decommissioning and harvesting plans and experience
- US utility 9:20 - 10:00 o Decommissioning process and plans o Owner perspective on harvesting and decommissioning BREAK 10:00 - 10:15
- Researcher perspective - EPRI or DOE or international 10:15 - 10:45 o Practical challenges to plan for and carry out harvesting DISCUSSION 10:45 - 11 :45 LUNCH 11 :45 - 12:45 Session 5: Harvesting Decision-making
- PNNL / NRC 12:45 - 1:15 o Technical information needed for informed harvesting decisions
- EPRI/NEI 1:15 -1 :45 o Balancing costs and benefits to ensure value from harvesting
- DOE 1:45-2:15 o Applying past experience to future harvesting decisions
- International - ? 2:15-2:45 o Harvesting decision-making
- DISCUSSION 2:45 - 4:00 o Potential harvesting partnerships
- RPV, internals, piping, concrete, cables
- US, international opportunities
Discussion Topics
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking available materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants
Note to requester:
Attachment to this From: Moyer carol email is immediately To: Brock Kathryn Cc: freeman Eric following .
Subject:
FW: Harvesting Workshop Date: Wednesday, November 23, 2016 11:11:00 AM Attachments: NRCHarvesting Workshop Announcement ctocx
- Kathryn, Here is another item for your Ed Bradley meeting, just in case there is interest in cooperation on ex-plant materials.
Carol From: Hiser, Mat t hew Sent: Wednesday, November 23, 2016 8:29 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>
Subject:
Harvesting Workshop Hi Carol, Here's the announcement we've been using to publicize the workshop.
Please let me know if you'd like more info © Thanks and happy Thanksgiving I Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 /-4 /5-2454 1Office: 1WFN I OD62 Matthew.Hiser@orc.gov
Ex-Plant Materials Harvesting Workshop Location: NRC HQ in Rockville, MD Dates: March 7-8, 2017 Motivation:
- There are increasing opportunities to harvest the safety-critical components from decommissioning pla nts, both domestic and international.
- The harvested materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, iriradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab.
- Data from ex-plant materials should help address technical gaps identified for extended operation of nuclear power plants due to highly relevant aging conditions.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated .
Workshop Topics:
- Harvesting decision-making and prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced components o Previous harvesting programs - "boneyards" o Tracking avai lable materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants
Note to requester:
Attac hment to this From: HJser Matthew email is immediately To: Tregoning Robert following.
Subject : FW: DE Briefing on Harvesting Date: Wednesday, December 06, 2017 11 :36:00 AM Attachments: Harvesting One Pager 12 17 (IF\ .docx Importance: High Hi Rob, If we rescheduled th is for next Friday, Dec. 15, any chance you could attend or call in ?
Thanks!
Matt From: Frankl, Istvan Sent: Wednesday, December 06, 2017 9:24 AM To: Hiser, Matthew <Matthew.Hiser@n rc.gov>
Cc: Audrain, Margaret <Margaret.Audrain @nrc.gov>; Purtscher, Patrick
<Patrick. Purtscher@ nre.gov>
Subject:
RE : DE Briefing on Harvesting Importance: High
- Matt, I have attached my revisions and comments.
Are you planning to draft slides as well? Please see my comment on this in the attachment.
Also, Chris declined the briefing scheduled for Monday. Usually, briefings like this cannot be completed in less than an hour. I would have liked the briefing to take place before the ANL trip but please try to reschedule to address Chris' request.
- Thanks, Steve From: Hiser, Matthew Sent: Friday, December 01, 2017 3:33 PM To: Frankl, Istvan <Istvan Franki@nrc gov>; Tregoning, Robert <Robert Tregoo iog@nrc.gov>;
Purtscher, Patrick <Patrjck.Purtscher@nrc.gov>; Audrain, M arga ret <Margaret.Audraio@nrc gov>
Subject:
DE Briefing on Harvesting Hi Steve, I have attached a draft one-pager that cou ld be used to brief Brian and Chris on the harvesting efforts in the context of their quest ions regarding t he ANL travel. Do you mind if I go ahead and schedu le someth ing with t hem for next week?
M eg, Pat, and Rob, please feel free to edit / comment on t his draft one-pager as necessa ry.
Thanks!
M att
Ex-Plant Materials Harvesting UpdateOAe Pager Motivation and Objective:
- Ex-plant materials are valuable for confirmatory testing because they have been exposed to actual in-service plant operating cond itions (temperature, irradiation, coolant, etc.)
o Generally, research involves accelerated, simulat ed 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 t he uncertainty associated with the applicability of research find ings.
- With plants shutting down both in t he 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 t ask in the new UNR for SLR from NRR/DLR requesting RES to investigate opportunities for harvesting w here appropriate. Commented [Fl1]: Please summarize full scope of this task including related database.
Past Activities:
- Workshop in March 2017 o NRC st aff hosted a 2-day workshop with interested stakeho lders, including domestic and International utilities and research organizatio ns, to d iscuss benefits and challenges associated with ex-plant harvesting.
o Sessions covered motivation for harvesting, data needs, sources of materials, lessons learned, t he practical aspects of harvest ing, and harvesting decision-making and plann ing o The discussion focused on the importance of clearly identifying the need and purpose for performing a harvesting project. Al l 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 priorit ize data needs for harvesting
- PliM o NRC staff provided a presentation, poster, and paper for the recent PliM conference In October 2017.
Path Forward:
- Focused on two parallel efforts:
o Developing alignment within NRC on prioritization of harvesting data needs Use criteria identified In PNNL report 1.Q...establlsh effective prioritization scheme for relevant areas: RPV, RPV internals and other metals, electrical components, concrete Commented [Fl2 ): Please mention above that this is o Developing a database identifying sources of materials for harvesting supported by the SLR UNR.
St art with lab-based "boneyards" of prior harvested materials Commented [F13J: This needs to be expanded in this
- Visits to AN L, PNNL, and ORNL (leveraged with already planned travel) support one-pager or on separate slides to address DE management comments/questions on the ANL and this activity follow-on trips (please see my prior email on this).
Coordinat e with DOE NSUF Nuclear Fuel and M aterials Library (NFML) run by INL as Commented [Fl4]: There is no approved travel to appropriate and beneficial ORNL In 2018.
Note to requester: The two images above Thomas Koshy's name repeated From: Frankl Istvan To: Moyer Carol throughout this document did not save Cc: Hiser Matthew when uploaded into NRC's redaction
Subject:
FW: ACTION: Input for quarterly EPRI MOU call software. The images are a photo of Date: Thursday, September 21 , 2017 12:03:45 PM Thomas Koshy and the NRC seal.
Attachments: imaae004,ioa lmaaeoos ioa lmaaeooz loo imaaeooa ioa
- Carol, Please review the enclosed request from Greg, align with Matt and if elevation to EPR I and NRC management is necessary, please draft ta lking points to support the upcoming call.
- Thanks, Steve From: Oberson, Greg Sent: Wednesday, September 20, 2017 4:49 PM To: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Cc: Koshy, Thomas <Thomas. Koshy@ nrc.gov>
Subject:
FW: ACTION: Input for quarterly EPRI MOU call
- Steve, There is an action item to: "Review the availability of cables that could be harvested from plants in decommissioning to support research on cable aging and performance under realistic conditions. Elevate as needed to EPRI and NRG management to facilitate successful availability."
Tom suggests that this falls under the scope of the harvesting activity in your branch. Can you take responsibility for this action item?
- Thanks, greg From: Koshy, Thomas Sent: Wednesday, September 20, 2017 3:03 PM To: Oberson, Greg <Greg Obe rson@nrc gov>
Cc: M il ler, Kenn eth A <KennethA Miller@nrc gov>
Subject:
RE : ACTION: Input for quarterly EPR I MOU ca ll Greg Cable harvesting for the project that is currently progressing is completed. I have consulted Kenn Miller on this already We have another big project on harvesting separately to cover many items electrical equipment, cables, concrete , radiated RX components etc., That is progressing separately.
It is done from lstavan's branch I do not see any other inputs from ICEEB mages I R [BJ Thomas Koshy, Acting Branch Chief Instrumentation, Controls & Electrical Engineering Branch Division of Engineering, Office Of Research, USNRC Email: Thomas.Koshy@nrc.gov Tel: Number: 301-415-2154
Room no: TWFN-10B48 MS TWFN-10A36 From: Oberson, Greg Sent: Wednesday, September 20, 2017 1:47 PM To: Koshy, Thomas <Thomas.Koshy@nrc.goy>
Subject:
RE: ACTION: Input for quarterly EPRI MOU ca ll This is the actions list. Yours is the cable harvesting. I have that on the SharePoint spreadsheet already!.
Greg From: Koshy, Thomas Sent: Wednesday, September 20, 2017 1:43 PM To: Oberson, Greg <Greg.Oberson@nrc.gov>
Subject:
RE: ACTION: Input for quarterly EPRI MOU ca ll Can you get me the old agenda to see if l&C/ Electrical had any mages I *
- Thomas Koshy, Acting Branch Chief Instrumentation, Controls & Electrical Engineering Branch Division of Engineering, Office Of Research, USNRC Email: Thomas.Koshy@nrc.gov Tel: Number: 301-415-2154 Room no: TWFN-10B48 MS TWFN-10A36 From: Oberson, Greg Sent: Wednesday, September 20, 2017 11:43 AM To: Frankl, Istvan <lstyan.Frankl@orc gov>; Iyengar, Raj <Rai,lyengar@nrc.gov>; Koshy, Thomas
<Thomas,Koshy@nrc gov>; Miller, Kenneth A <KennethA,Miller@nrc gov>; Boyce, Tom
<Tom Boyce@nrc gov>; Seber, Dogan <Dogan,Seber@nrc gov>
Cc: Regan, Christopher <Christopher Regan @nrc.gov>
Subject:
ACTION : Input for quarterly EPRI MOU call
- BCs, The quarterly EPRI MOU management update call will be held in mid-October. You are responsible for providing updates on action items from the June meeting, as well as to identify challenges/issues that would benefit from management attention. I have placed a spreadsheet file on SharePoint with the action items and I assigned them to a branch to provide an input. Please provide a few sentences to a paragraph update and identify any challenges/issues It is ok to have no challenges/issues. If you believe that I assigned the wrong branch the action, please let me know. Input is requested by COB October 2.
SharePoint file is here:
http://fusion,nrc.gov/res/team/de/Divison%20Meeting%20Docs/EPRl%20MOU%20meeting Please let me know if you have questions.
- Thanks, Greg
Note to requester: This email document is how it was provided to the NRC FOIA staff, with highlighted portions included.
From: Iyengar Raj To: Mehta Sbivani Cc: Noye carol; Tregoning Robert; Hiser Matthew
Subject:
FW: ACTION: IRSN meeting summary Date: Thursday, March 23, 2017 2:59:36 PM Shivani, DE input to IPT is hig hlighted below. Please let m e know if you have changes.
Raj (Folks in Cc: - ff you have any chanaes, otease let Shivani know by oca today,I Action Items :
- IRSN will re-connect NRC (Carol Nove) with Gerard Cattiaux.
- JRSN will send ODOBA agreement to NRC for collaboration.
NRC to follow up on NOE testing work with IRSN, CEA, and PNNL. .{NRC Update:
While the agreement included a task for PNNL to collect data with CEA 's flexible hased-array ultrasonic robe, this task has been on-hold due Lo f uncling limitations. NRQ confirmed that PNNL did not receive the flex ible array probe from CEA.)
- INRC to renew IRSN/RES information exchange on NDE testing. NRC Update: In light of the ex iration date for the current NOE lm lementing Agreement (December 3 1, t20 17, NRC ro oses to meet with IRSN during the summer 20 17 to discuss and Ian the scope of the next A reement.
-NRC will share the actions and results from the Harvesting workshop. (NRC U_pdate:
ction items from the workshop provided. An update on NRC initiative on developing a systematic aPlxoach to harvesting reac tor materials and components is also provided.
P lease contact Rob Tregoning if IRSN is interested in developing a harvesting wish list or in participating in the group to develop sources of material.)
From: Iyengar, Raj Sent: Wednesday, March 22, 2017 10:28 AM To: Nove, Carol <Carol Nove@nrc gov>; Tregoning, Robert <Robert Tregooiog@nrc gov>
Subject:
FW: ACTION: !RSN meeting summa ry Carol/Rob, I have suggested some edits (see highlighted portion below). Please revise, as needed.
Raj
- 1. Integrity of Plant and Structures
- a. Research 011 Material Ageing (including CASS/DMW collaborative research and Materials Harvesting plamzing.for LTO research)
For IRSN: Francois Barre For NRC : Raj Iyengar, Carol Nove and Rob Tregoning IRSN: No update NRC: Update on CASS (dissimilar metal welds)
Brief summary of Harvesting workshop held at the NRC during the week of March 6, 2017. Resulted in two actions: I) Create a list of important data needs from harvesting, and 2) develop a database of available harvesting opp01tunities.
b.Research on Concrete Pathologies (ODOBA)
For IRSN: Francois Barre For NRC : Jacob Philip IRSN: Update on ODOBA NRC: Summary of ASR Research to Date
Action Items :
- IRSN wi ll re-connect NRC (Carol Nove) with Gerard Cattiaux.
- IRSN will send ODOBA agreement to NRC for collaboration.
- NRC to fo llow up on NDE testing work with IRSN, CEA, and PNNL. {NRC: UQon follow up, NRC found that PNNL had not received any information from CEA. NRC reguests IRSN to ens ure information is transmitted to PNNL to enable continued activity in this area.)
C to renew IRSN/RES information exchange o n NOE testing. (Due: )
- N RC will share the actio ns and results from the Harvesting workshop. (Due: )
From: Mehta, Shivani Sent: Friday, March 17, 2017 3:20 PM To: Hoxie, Chris <Chris.Hoxie@nrc.gov>; Hudson, Nathanael <NathanaeLHudson@nrc.gov>;
Santiago, Patricia <Patricia.Santiago@nrc.gov>; Lee, Richard <Richard.Lee@nrc.gov>; Ba les, Michelle
<Michelle.Ba!es@nrc.gov>; Nove, Carol <Carol Nove@nrc.gov>; Iyengar, Raj <Raj lyengar@nrc.gov>;
Tregon ing, Robert <Robert.Tregonjng@nrc gov>; Philip, Jacob <Jacob.Philip@nrc.gov>; Salley, MarkHenry <MarkHenry Sa lley@nrc.gov>; Hamburger, Kenneth <Kenneth Hamburger@nrc gov>;
Kanney, Joseph <Joseph.Kanney@nrc.gov>; Kowalczik, Jeff <Jeff.Kowalczik@nrc.gov>; Grant , Jeffery
<Jeffery.Grant@nrc.gov>
Cc: Herrity, Thomas <Thomas Herrity@nrc.gov>; Berrios, Ilka <llka.Berrios@nrc.gov>; Armstrong, Kenneth <Kenneth.Armstrong@nrc.gov>; Rolf, Joan <Joan.Rolf@nrc.gov>; Sangimino, Donna-Marie
<Donna-Marie.Sangimioo@ore.gov>
Subject:
ACTION: IRSN meeting summary Good Afternoon The draft meeting summary for the IRSN meeting held on Monday, March 13th is attached.
For you topic area: please summarize .bQ1h IRSN"s and your presentations. I have them at a very high level now but please feel free to add as much information as you think would be beneficial for the record of the meeting.
Also, please check the Participant list for anyone I may have missed.
Comments/edits are due by COB March 23m Feel free to reach out if there are any questions
- Thanks, Shivani Shivani N Mehta, P.E.
International Relations Specialist (Rotation)
Office of Nuclear Regulacory Research U.S. Nuclear Regulatory Commission Mail Stop T-10A24 Shivaai Mehta@NRC.gov 301.415.0860 (Desk) 301.415.6671 (FAX)
From: HJser Matthew To: Tregoning Robert Subject : FW: Action: Rewrite In response to Feedback on UNR Response Task 2 Date: Wednesday, September 06, 2017 9:39:33 AM FYI From: Hiser, Matthew Sent: Tuesday, September 05, 2017 2:23 PM To: Hull, Amy; Purtscher, Patrick Cc: Frankl, Istvan ; Moyer, Carol
Subject:
RE : Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Amy, My initial thoughts on how to respond to some of these questions are in red below. I only think maybe 1 or 2 of the bullets need changes to the text of the response (in my opinion).
Do you know who in NRA reviewed Task 2 and provided these comments? It might be just as easy to have a quick meeting with them to explain things more clearly.
I'd suggest you take the lead on editing the response as much (or little) as appropriate, since you and Carol took the lead in compiling the input initially. My feedback is in red below and Pat can certainly add anything from his perspective.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Pho11e: 301-415-2454 I Office: 'fWFN 10D62 Matthew.Hiser@nrc.gov From: Hull, Amy Sent: Tuesday, September 05, 2017 1:42 PM To: Hiser, Matt hew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Moyer, Ca rol <CaroLMoyer@nrc gov>; Frankl, Istva n <Jstvan.Frankl@nrc.gov>
Subject:
Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Matt and Pat, Would you like me to take a crack at the following feedback from NRR (since I put the database in the original SOW) or would you like to rewrite first? Or should we sit down and brainstorm these questions? I have attached the UNR, the response, and the NRR feedback from last Thursday.
IASJU
- It isn't clear what these criteria/approaches/processes for the use of the database are.
Where are they documented or described, how they have been validated or used?
Are the criteria/approaches/processes described in the September 2017 TLR ? The criteria for prioritizing harvesting data needs are described in the September 2017 TLR. NRA needs to have an idea of what is involved in the steps and how the database will be used.
- It is not clear how the first two activities, the workshop on materials harvesting and prioritizing of issues to be addressed by harvested materials, contribute, or are related to the database. This must be fully explained. The workshop was designed to discuss past harvesting experience and lessons learned and seek leveraging and cooperation with other interested research organizations. Insights from the
workshop are integrated into the database and harvesting planning efforts. The database will be developed consistent with the prioritization criteria from PNNL to identify which
- Why just decommissioned plants? An explanation is required as to why this has been limited in scope. This harvesting effort is not limited to only decommissioned plants as stated in draft response: "RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned NPPs, as well as from ex-plant components from OJ?erating plants. "
- It is not clear how the discussion under Subtask 2 are examples of how the database would be used. It seems to be a discussion of harvesting material. This needs to be explained, with clear outcomes defined. The purpose of the database is to have a systematic approach to harvesting materials and prioritize limited resources on the best values for harvesting. The database is not an end unto itself, but the means to do the highest priority harvesting for the best technical value .
- $175 K seems like a lot to develop an Excel or Access database. I don't disagree - I think at this point, it may be a 100% in-house effort. Does this include collecting and inputting information on materials needed and the sources of materials expected to be available? Yes This tasking must be better defined.
Amy B. Hull, Ph.D Senior Materials Engineer RES/DE/CMB (office T10-049)
US Nuclear Regulatory Commission 11545 Rockville Pike Rockville, Maryland 20852 Telephone: (301) 415-2435 FAX: 301 -415-6671 e-mail: amy hull@orc gov
From: HJser Matthew To: ~ ; Frankl Istvan; TregonJng Robert; Purtscher Patrick Subject : FW: Ex-Plant Harvesting
--*--Original Appointment*****
From: Hiser. Matthew Sent: Monday. August 15. 20164:56 PM To: Hiser, Matthew: Frankl, Istvan: Tregoning, Robe1t; Purtscher, Patrick
Subject:
Ex-Plant Harvesting When: Thursday. August 18. 2016 11:00 AM- 11 :30 AM (UTC-05:00) Eastern Time (US & Canada).
Where: I 0th floor huddle room I think it would be good to get everyone on same page regardi ng next steps for the harvesting program.
We have an early draft of the PNNL deliverable. with the final version expected in early 2017. I'd like to discuss that work as well as the workshop that w:is discussed with NRAJ last week and been discussed previously.
Th,mks!
Matt
From: HJser Matthew on behalf of RES PE ca1Resource To: Purtscher Patrick; Thomas Brian; Tregoning Robert; Frankl Istvan; Hiser Matthew; Vera Graciela Subject : FW: Harvesting Workshop
*Original Appointment*****
From: RES_DE_Cal Resource Sent: Thursday. February 23. 2017 9:20 AM To: RES_DE_Cal Resource; Thomas, Brian: Tregoning. Robert: Frankl. Istvan; Hiser, Matthew: Vern. Graciela
Subject:
Harvesting Workshop When: Thursday. March 02. 2017 9:15 AM-9:30 AM (UTC-05:00) Eastern Time (US & Can:tda).
Where: TJO-El6 From: Hiser. Matthew Se111: Thursday. February 23. 2017 9:09 AMI To: Snail. Malika <Malika.Snail@nrc.gov <mailto:Malika.Snail@nrc.gov> >
Subject:
Quick Brief for Brian Thomas Hi Malika.
Could you schedule a 15-minute briefing with Bria111l1omas on the topic of *'Harvesting Workshop" for some time next week?
Allendees should be myself, Rob Tregoning, Steve Frankl, and Brian. It looks like we might all be free on Thursday, March 2 between 9: 30 and 10:00.
Thanks!
Matt Mallhew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 30 1-41 5-24541 Office: TWFN IOD62
From: HJser Matthew To: Noye Carol Cc: Purtscher Patrick; Audrain Margaret
Subject:
FW: inventory of ex-plant materials at PNNL Date: Friday, August 03, 2018 8:55:19 AM Hi Carol, I will be heading to PNNL next week for a trip focused on NMSS dry storage work there with Bruce and Darrell. However, while I'm there I'm planning to spend a little time meeting with Pradeep on the harvesting contract we have with them (Pat Purtscher is the COR; I am alt. COR).
One topic will be a report they're finalizing and addressing NRC comments on, while another will be their efforts to identify previously harvested materials at PNNL. I think they're already doing a large portion of that for you, which probably meets our needs as well. I just wanted to touch base with you on what they are doing under your contract and let you know I'll be there next week and might discuss that some with Pradeep (not give direction of course, just try to be clear on what they're doing for your contract and whether that covers everything we're looking at for harvesting).
Let me know if you have any questions or concerns with that and we can catch up the week of August 13 .. .
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Oflice of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Plto11e: 30 /-4 /5-2454 I Office: 7WFN I OD62 Matthew Hjser@nrc gov From: Purtscher, Pat rick Sent: Thursday, August 02, 2018 11:26 AM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Audrain, Margaret <Ma rgaret.Audrain@nrc.gov>
Subject:
FW: inventory of ex- plant mat erials at PNNL FYI From: Nave, Carol Sent: Thursday, August 02, 2018 10: 17 AM To: Purtscher, Patrick <Pat rick.Purtscher@nrc.gov>
Subject:
RE : inventory of ex-plant mat erials at PNNL
- Pat, I think it will be done before the end of the summer. I'll send it to you when I get it.
Carol From: Purtscher, Patrick Sent: Monday, July 30, 2018 9:3 1 AM To: Nave, Carol <Carol.Nove@ nrc.gov>
Subject:
inventory of ex-plant materials at PN NL Good morning, Pradeep told me that PNNL is doing an inventory of ex-plant materials for you. Do you know when they will complete that task?
Pat M at erials Engineer
US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Meta llurgy Branch 11545 Rockvi lle Pi ke I Rockville, MD 20852-2738 Phone: 301-415-3942 I Office: TWFN 10A49 ptp1@nrc.gov
From:
To: Hiser Matthew
Subject:
FW: Joe, you are a TM on this: STAQS action for "Strategic Approach for Obtaining Material and Component Aging Information" w/ PNNL Date: Monday, July 13, 2015 11 :06:19 AM Attachments: iroaaeoo1 ioa FYI.
From: Kanney, Joseph Sent: Monday, July 13, 2015 10: 19 AM To: Hull, Amy
Subject:
RE: Joe, you are a TM on this: STAQS action for "Strategic Approach for Obtaining Material and Component Aging Informati on" w/ PNNL OK. Thanks!
From: Hull, Amy Sent: Friday, July 10, 2015 3:26 PM To: Kanney,Joseph
Subject:
Joe, you are a TM on t his: STAQS action for "Strategic Approach for Obtaining Material and Component Aging Information " w/ PNNL All approved by RES. As discussed before, you are a TM on this. When we begin the negotiations with PNNL, we will let you know and get you more actively involved.
Monthly Letter Status Reports In accordance with Management Directive 11 .7, NRC Procedures for Placement and Monitoring of Work with the U.S. Department of Energy, PNNL shall electronically submit a Monthly Letter Status Report (MLSR) by the 20th day of each month to Amy Hull, the Contracting Officer Representative (COR), to Matthew Hiser and Joseph Kanney, the technical monitors, with copies to the Contracting Officer (CO) and the Office Administration/Division of Contracts to ContractsPOT.Resource@nrc.gov.
From: Frankl, Istvan Sent: Tuesday, July 07, 2015 9:25 PM To: West, Steven Cc: Brock, Kathryn; Bamford, Lisa; Stout, Kathleen; Hull, Amy; Hise r, Matt hew; Focht, Eric
Subject:
STAQS action for "Strategic Approach for Obta ining Material and Component Aging Information" w/
- Steve, PMDA has notified me today that subject request for proposal and funding action to initiate new work with PNNL had not been routed to you for approval.
This work has three inter-related objectives:
(1) Develop a long-range strategy for obtaining information from decommissioned NPPs as well as providing the flexibility to get ex-plant components from operating plants. The focus will be on timely acquisition of experiential real-world aging-degradation information that can significantly improve the agency"s risk-informed and performance-based regulatory approach, but has been very difficult or impossible to obtain from the operating reactor fleet.
(2) Construct a strategic plan and specifications for obtaining unique and significant materials aging degradation information from diverse sources (operating experience, nuclear facilities, long-lived industrial plants, materials organizations) that will inform the NRC's age-related regulatory oversight in the future. This exploratory research is expected to provide fundamental insights on reactor materials degradation to support anticipated future NRC needs.
(3) Update the Proactive Management of Materials Degradation (PMMD) information tool developed at PNN L for RES to incorporate LTO/SLR-relevant information so that it can be better used to inform prioritization in the ex-plant material strategic plan.
The tasks associated with this work and their duration are described in the table below:
Task Task Title/Description Duration (Months)
Task 1 Scoping Study and technical literature review 18 Optional Decision Making on Specific Confirmatory Research Needed to 6 Task 2 Address Gaps Optional Confirmatory Research Addressing Technical Gaps 33 Task 3 Optional Development of Independent Decision Making Tools 33 Task 4 The optional tasks above will be conducted, as shown in the figure below:
ABH SOW Fig 3 A decision on further optional research outlined in Tasks ~ 3, and 4 above will be made after completion of Task 1.
For your information I have attached the Statement of Work as well as the Independent Government Cost Estimates that include the cost of the base scope (Task 1) as well as the total cost with options (Tasks 1 through 4).
Please let us know if you want this action recalled and resubmitted for your review in STAQS.
- Thanks, Istvan (Steve) Frankl Branch Chief RES/DE/CMB U.S. Nuclear Regulatory Commission Phone: (301) 415-2227 (after 6/22/2015) Note to requester: The figure image E-mail: Istvan frankl@orc gov did not copy when upload into the NRC redaction software. The image has been included on the next page.
Task 1.
Terminate Technical Task 2. Gap Further Literature Identification Research Review Yes Task 3.
Recommend Research Need
,--------*--------~
- I Task 4. :
I
! Develop !
I Analysis Tools :
~----------------J
From : Moyer Carol To: Hiser Matthew Cc: Iceooniog Bobfirt
Subject:
FW: Join us in Nashville!
Date: Wednesday, September 27, 2017 9:12:00 AM Attachments: im.agii_O.Q.L.Qng.
- Matt, This might be of interest to you, for harvesting-related opportunities. The cost looks pretty high, though, so I would want to see who the speakers and exhibitors are going to be.
Carol From: Decommissioning Strategy Forum [1]
Sent: Wed nesday, September 27, 2017 9:04 AM To: Moyer, Carol <Carol.Moyer@nrc.gov>
Subject:
[External_Sender] Join us in Nashville!
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- Acces. lntell1gence LLC
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From: HJser Matthew To: Poehler Jeffrey Subject : FW: Materials Harvesting Workshop
-****Original Appointment*****
From: Hiser. Matthew Sent: Monday. December 12. 2016 4:41 PM To: Hiser, Matthew
Subject:
Materials Harvesting Workshop When: Wednesday. March 08. 20 17 8:00 AM-5:00 PM (UTC-05:00) Eastern Time (US & Canada).
Where: HQ-3WFN- IC03-32p
From: HJser Matthew To: Poehler Jeffrey Subject : FW: Materials Harvesting Workshop
-****Original Appointment*****
From: Hiser. Matthew Sent: Friday, December 09. 2016 9:03 AM To: Hiser, Matthew
Subject:
Materials Ha rvesting Workshop When: Tuesday, March 07. 2017 8:00 AM-5:00 PM (UTC-05:00) Eastern Time (US & Ca nada).
Where: HQ-3WFN- IC03-32p
From : Frankl Istvan To: Oberson Greg; Focht Eric; Rao Appaiosula; Hiser Matthew; Rossi Matthew; Purtscher Patrick Subject : FW: meeting with JNRA on August 7 and 8 Date: Tuesday, May 10, 2016 3:29:24 PM
- All, Rob has requested topics/ sub-topics supporting subject meeting with JNRA. Please review his enclosed email and send me your suggestions gy COB Monday (5/16).
- Thanks, Steve From: Tregoning, Robert Sent: Tuesday, M ay 10, 2016 9:11 AM To: Rudland, David <David.Rudland@ nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>; Jung, Ian
<la n.Jung@nrc.gov>; Alley, David <David.Alley@nrc.gov>; M cHale, John <John.McHale@ nrc.gov>;
Mitchell, Matthew <Matthew.Mitchell@nrc.gov>; Morey, Dennis <Den nis.Morey@n rc.gov>; Burke, John <John.Burke@nrc.gov>
Cc: Hiser, Allen <Al len.Hiser@ nrc.gov>; Manoly, Kamal <Kamal.Manoly@nrc.gov>; Ha rd ies, Robert
<Robert.Ha rd ies@ nrc.gov>; Karwoski, Kenneth <Kenneth. Karwoski@ nrc.gov>; Benson, M ichael
<M ichael.Benson@nrc.gov>
Subject:
meeting w ith JNRA on August 7 and 8 Al l:
Just some advanced notice that the Japanese (JNRA) are coming on August 7 and 8 to the NRC for a 2-day meeting to discuss material's research and issues. We meet about every 18 months with them and the last meeting was in January 2015 at JNRA. All the slides and the meeting summary from that meeting are ava ilable and I can provide t hat information if you are interested. The biggest follow-on areas after t hat meeting were related to cable aging and concrete aging and we had productive discussions with the Japanese in those areas after the January 2015 meeting. I've started to work with JNRA on putting together an agenda for t he meeting. Here are a few topics that I think might be appropriate/of interest to us:
- PWSCC crack growth and crack initiation
- RPV embrit t lement studies
- cable aging
- concrete aging
- irradiated assisted degradation
- probabilistic fracture mechanics of pressure boundary components
- NDE issues (not quite materials but relat ed )
- aging of cast austenitic steels
- peen ing
- degradation of spent fuel pool neutron absorbers
- material harvesting opportunities Please canvas your st aff and respond to me by COB next Tuesday (5/17) with your topics of interest for t he meet ing (either from t his initial list or not). It would also be helpfu l if you ind icate any specific subtopics (say for instance NDE of CASS components) within t hese broader topics that are of most interest. After I get our list together, I' ll send it to JNRA and work with them to get consensus on t he agenda.
Please let me know if you have any questions. Thanks for your help.
Rob
From: ~
To: Hiser Matthew
Subject:
FW: need to talk to you ... : NRG/ Industry June Materials Meeting Dat e: Wednesday, May 13, 2015 10:06:45 AM From: Hull, Amy Sent: Wednesday, May 13, 2015 9:33 AM To: Frankl, Istvan ( lstvan.Frankl@nrc.gov)
Subject : need to t alk to you ... : NRG/ Industry June Mat erials Meeting What we are envisioning goes way beyond this. I need to talk to you about this before agreeing. Really, now it would be Zion, Zorita, etc.
From: Tregoning, Robert Sent: Wednesday, May 13, 2015 8:49 AM To: Focht, Eric; Benson, Michael; Oberson, Greg; Hull, Amy Subject : NRG/ Industry June Materials Meeting All:
We're planning on covering the following topics during the June meeting (6/2 - 6/4)
- 1. WRS round robin- Benson/?
- 2. Expert Panel CGR disposition curves - Oberson/ Crooker
- 3. PWSCC initiation research - Focht/Crooker
- 4. Ex-plant material database development - Hull The first three topics are meant to be joint talks with us and industry, while Amy's topic will just be an NRC talk. Can you please provide me with the following information by the end of this week (if possible)?
- a. Title of talk
- b. Presenters - both NRC presenter (or contractor) and industry if joint
- c. Time needed for talk (we've nominally allocated 30 minutes per talk but it can be more or less as needed).
Let me know if you have any questions. Thanks for your help.
Rob Robert Tregoning Technical Advisor for Materia Is US Nuclear Regulatory Com m ission 21 Church St reet , M /S CS-5A24 Rockville, MD 20850 ph: 301-251-7662
_ _J.(bJ(g}
Blackberry:,..!- -__ -_____-______-______...
fax: 301-251-7425
From: HJser Matthew To: Tregoning Robert; Purtscher Patrick Subject : FW: Planning/Setup for Harvesting Workshop
-****Original Appointment*****
From: Hiser. Matthew Sent: Monday. January 30. 2017 8:24 AM To: Hiser, Matthew
Subject:
Planning/Setup for Harvesting Workshop When: Monday. Mnrch 06. 2017 2:00 PM-4:00 PM (UTC-05:00J Eastern Time (US & Canada).
Where: HQ-3WFN- IC03-32p
From : HJser Matthew To: Purtscher Patrick Subject : FW: Pis send us link to the Sept 2017 TLR *** Action: Rewrite in response to Feedback on UNA Response Task 2 Date: Thursday, September 14, 2017 9:36:00 AM Hi Pat, Can you send Amy the latest version of the TLR with comments? I think Amy is just interested for her info in crafting the UNR response ...
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulalory Research Division of Engineering I Corrosion and Metallurgy Bnmch Phone: 301-..J/5-2454 1Office: 'JWFN I OD62 M atthew .Hiser@orc.gov From: Hull, Amy Sent: Wednesday, September 13, 2017 2:06 PM To: Hiser, Matthew; Purtscher, Patrick Cc: Moyer, Carol
Subject:
Pis send us link to t he Sept 2017 TLR ---Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Matt and Pat, Please can you provide us a link to the Sept 2017 TLR?
- Thanks, Amy From: Hiser, Matthew Sent: Tuesday, September 05, 2017 2:23 PM To: Hull, Amy <Amy.Hu ll@nrc gov>; Purtscher, Patrick <Patrjck.Purtscher@nrc gov>
Cc: Frankl, Istva n <lstvan.Erankl@nrc.gov>; Moyer, Carol <Carol. Moyer @nrc,gov>
Subject:
RE: Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Amy, My initial thoughts on how to respond to some of these questions are in red below. I only think maybe 1 or 2 of the bu llets need changes to the text of the response (in my opinion).
Do you know who in NRR reviewed Task 2 and provided these comments? It might be just as easy to have a quick meeting with them to explain things more clearly.
I'd suggest you take the lead on editing the response as much (or little) as appropriate, since you and Carol took the lead in compiling the input initially. My feedback is in red below and Pat can certainly add anything from his perspective.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: 301-4 /5-2454 1Office: TWFN IOD62 Matthew.Hiser@o re.gov From: Hu ll, Amy Sent: Tuesday, September 05, 2017 1:42 PM
To: Hiser, Matthew <Matthew.Hjser@nrc.gov>; Purtscher, Patrick <Patrjck.Purtscher@nrc.gov>
Cc: Moyer, Carol <Carol.Moyer@nrc.gov>; Frankl, Istvan <lstyan.Frankl@orc gov>
Subject:
Action: Rewrite in response to Feedback on UNR Response Task 2 Hi Matt and Pat, Would you like me to take a crack at the following feedback from NRR (since I put the database in the original SOW) or would you like to rewrite first? Or should we sit down and brainstorm these questions? I have attached the UNR, the response, and the NRR feedback from last Thursday.
IASK..2
- It isn't clear what these criteria/approaches/processes for the use of the database are.
Where are they documented or described, how they have been validated or used?
Are the criteria/approaches/processes described in the September 2017 TLR? The criteria for prioritizing harvesting data needs are described in the September 2017 TLR. NRR needs to have an idea of what is involved in the steps and how the database will be used.
- It is not clear how the first two activities, the workshop on materials harvesting and prioritizing of issues to be addressed by harvested materials, contribute, or are related to the database. This must be fully explained. The workshop was designed to discuss past harvesting experience and lessons learned and seek leveraging and cooperation with other interested research organizations. Insights from the workshop are integrated into the database and harvesting planning efforts. The database will be developed consistent with the prioritization criteria from PNNL to identify which
- Why just decommissioned plants? An explanation is required as to why this has been limited in scope. This harvesting effort is not limited to only decommissioned plants as stated in draft response: "RES staff will continue to develop and implement a long-term strategy for obtaining information on materials degradation from decommissioned N PPs, as well as from ex-plant components from operating plants."
- It is not clear how the discussion under Subtask 2 are examples of how the database would be used. It seems to be a discussion of harvesting material. This needs to be explained, with clear outcomes defined. The purpose of the database is to have a systematic approach to harvesting materials and prioritize limited resources on the best values for harvesting. The database is not an end unto itself, but the means to do the highest priority harvesting for the best technical value .
- $175 K seems like a lot to develop an Excel or Access database. I don't disagree - I think at this point, it may be a 100% in-house effort. Does this include collecting and inputting information on materials needed and the sources of materials expected to be available? Yes lihis tasking must be better defined.
Amy B. Hull, Ph.D Senior Materials Engineer RES/DE/CMB (office T10-D49)
US Nuclear Regulatory Commission 11545 Rockville Pike Rockville, Maryland 20852 Telephone: (301) 415-2435 FAX: 301 -415-6671 e-mail: amy hull@orc gov
,..om:
Cc:
~lect:
Oat*:
l 1t1POl'Ull\o t1 o,eg,
- ...WU fW: f'ffl..E~1t1tnt Tnivell0tCIA6 1hunoa,",Jilw 2B,~18 2:~ :0tP-M We have o new eme,aent travel re1 ues1. Oe1a1ts are below and 111 the onck>sed amatl:
V1s11 1-'NNL to ODSON& and d1SW$S Clry cask storage reseatch, including CISCC testing and Ory Cask Priority2
- an EPR I Inspection domon,SCralion on a canlsior oomo,1Jc SlC>r11go ond Llceo10~
HI.soi Mau.hew CMS HarYeStlng MJU,on RegolatJon RICl>IO/\O, WA 08/0512018 Oll/09/2018 Sl .500 mO(:kUj), In add1tl()l'I, mott w~h PNNL Ital!
worb'ig on harvesting and observe PWSCC and ReuatetiVlsit Rolated NOE tes1I~ c.apabllii.es. This .aclilllty di1&e1ly I UOOOl'II UNR NMSS,2011*001 .
- Thanks, Steve From: Hiser, Matthew Sent: Thursday, June 28, 2018 2:04 PM To: Frankl, tnvan <Istvan Frankl@ntc SOY>
SubJ11d: PNNl lmergent Tr;avel Hi Steve, I submilled the emergent 1ravel request to our branch spreadsheet (\\nee QOy\OCc\HQ1Qff/ca\BES\BES\PE1CMS\Tca'e'ftl\FY1 e BFS*PE leave!* CMS KIM) for this 1rip. Oar1e11Dunn and Bruce Un (CIB) will also bo attending this inspection demonstration by EPAI. I want to emphasize that this travel has value for. lhe harvesting pcogram as well.
Also, a reml11der Raj discussed this wl1h Chris last Thursday and got buy-In from Chris and the NMSS BC Hipolito Gonzalez.
Ploaso 101 mo know it thoro's any1hlng else I nee<:! to do to holp support this roquost Tha,,ks!
Matt
From: Oberson Greg To: ~ ; Moyer Carol Cc: Hiser Matthew; Boyce IRES} Tom Subject : FW: QUERY - CLARIFICATION ON ePOSTERS Date: Wednesday, February 14, 2018 9:42:38 AM Attachments: imaaeoo2,ono 1maaeoo3 ona This poster seems to be causing never-ending confusion. Can you confirm which of these is the correct title and who the presenters are?
- Thanks, Greg From: Weber, Michael Sent: Wednesday, February 14, 2018 9:09 AM To: Oberson, Greg <Greg.Oberson@nrc.gov>
Cc: Boyce (RES}, Tom <Tom.Boyce@nrc.gov>; Peters, Sean <Sean.Peters@nrc.gov>; Difrancesco, Nicholas <Nicholas. DiFrancesco@ nrc.gov>
Subject:
QUERY - CLARIFICATION ON ePOSTERS Good morning, Greg. The info that I have from the RIC planners shows you co-authoring presenting two very similar sounding ePosters. Are you doing both? Or is there duplication here in the titles? Please advise.
- Harvesting of Aged Materials from Nuclear Power Plants by Greg Oberson and Amy Hull
- Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants by Greg Oberson and Matt Hiser
- Thanks,
?Jti4e Michael Weber Director of Nuclear Regulatory Research US Nuclear Regulatory Commission 301-41 5-1902 Mail Stop T-10816 Dn l Note to requester: The image did not copy over when this document was uploaded to NRC's FOIA redaction software. Image included on next page.
Intentiona{[y, cfefi6erate[y, ancf yroactive[y inc[uaing emy[oyees to accomy[isli our nuc[ear safety ancf security mission
Note to requester: The attachments to this email are immediately following.
From: HJser Matthew To: Hiser Allen
Subject:
FW: PLiM Slides Submission Date: Monday, October 16, 2017 4:58:00 PM Attachments: NRG PLIM slides on Harvestina final.odf NRG PLiM slides on Harvestino final.ootx PP slides as well in case you need them ...
From: Hiser, M atthew Sent: Monday, October 16, 2017 4:58 PM To: ' PLIM2@iaea.org' <PLIM2@iaea.org>
Cc: Hiser, Allen <Allen .Hiser@ nrc.gov>; Frankl, Istvan <lstvarn. Fran kl@nrc.gov>; Moyer, Carol
<Ca rol. Moyer@nrc.gov>; ' KRIVANEK, Robert' <R .Krivanek@iaea.org>; KANG, Ki-Sig
<K.S.Kang@ iaea.org>
Subject:
PLiM Slides Submission
Dear PLiM Organizers,
I have attached the slides for the presentation entitled: "Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants." An accompanying paper should be sent on a slight delay by this Friday.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regulatory Research Division of Engineering I Corrosion and MetaJiurgy Branch Phone: 301-415-2454 1Office: 7WFN JOD62 Matthew.Hiser@nrc.gov
U.S.NRC Uni ted Stares Nuclear Regulato ry Co mmission Protecting People and the Environment Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hisera, P. Purtschera, P. Ramuhallib, A. B. Hulla, R. Tregoninga au.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA bPacific Northwest National Laboratory (PNNL), Richland, WA, USA This presentation was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereat nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product, or process disclosed in this presentation [report], or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the U.S. Nuclear Regulatory Commission.
Outline
- Background and Motivation
- NRC Harvesting Experience
- Recent N RC Activities
- Criteria for Prioritizing Data Needs
- Database for Sources of Materials
- Path Forward
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 2 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Background and Motivation
- Recent trends in global nuclear industry:
- Interest in extending nuclear power plant (NPP) lifespans
- Numerous NPPs, both in U.S. and internationally, have announced plans to or already have shut down
- Limited budgets have restricted the resources available to support new research, including harvesting programs
- Aligning interests and leveraging with other organizations is important to maximize value
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 3 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
NRC Harvesting Experience
- NRC has participated in numerous harvesting programs over the years:
- RPV, CRDM penetrations, RCS piping, RPV internals, neutron absorbers, and cables
- From unfinished, operating ,and decommissioning plants in U.S. and internationally
- Significant value in using harvested components to confirm data from other research programs
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 4 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for research
- May be only practical source of representative aged materials
- May be able to use limited harvested materials to validate larger accelerated aging data set
- Important to gain as much information as possible in advance before committing to specific harvesting project
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 5 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effort
- Leveraging resources with other research organizations helps mitigate cost challenges
- Transporting irradiated materials, particularly internationally, is cumbersome Lifting operation for and time-consuming irradiated materials transport cask
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 6 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Recent NRC Activities
- Strategic approach to materials harvesting
- Due to limited opportunities, past harvesting efforts have generally been reactive to individual plants shutting down
- Prioritize the data needs best addressed by harvesting
- Workshop held in March 2017 at NRC HQ to discuss all aspects of harvesting with other interested stakeholders
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 7 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Potential Criteria for Harvesting Prioritization
- Applicability of harvested material for addressing critical gaps
- Ease of laboratory replication of the degradation scenario
- Unique field aspects of degradation
- Fleet-wide vs. plant-specific applicability of data
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 8 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Potential Criteria for Harvesting Prioritization
- Harvesting cost and complexity
- Availability of reliable in-service inspection (ISi) techniques for the material/ component
- Availability of materials for harvesting
- Timeliness of the expected research results relative to the objective
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 9 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Database for Sources of Materials
- NRC is pursuing the development of a database for sources of materials for harvesting
- Allow for aligning of high-priority data needs to the available sources of materials Example of reactor
- NRC is interested in engaging with internals harvesting plan other organizations in developing the database
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 10 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
Conclusion and Path Forward
- Harvesting can yield highly representative and valuable data on materials aging
- Data Needs Prioritization and Sources of Materials Database
- As specific harvesting opportunities are identified, NRC welcomes opportunities for cooperation and leveraging with other interested research organizations
~ U.S.NRC UnhtJ Suet'.) N\loCfoar lkpl,u o,y Comm1"1" 11 f>ror<<tir1g P~ple aud 1/,e Enviro11..,,1nu
~u.S.NRC United Sn rc, Nuc lear Rcgula rory Co mmission Protecting People and the Environment Harvesting of Aged Materials from Operating and Decommissioning Nuclear Power Plants M. Hisera, P. Purtschera, P. Ramuhallib, A. B. Hulla, R. Tregoninga au.s. Nuclear Regulatory Commission (NRC), Washington, D.C., USA bPacific Northwest National Laboratory (PNNL), Richland, WA, USA This presentation was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility far any third party's use, or the results of such use, of any information, apparatus, product, or process disclosed in this presentation [report], or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the U.S. Nuclear Regulatoz Commission
Outline
- Background and MotivationNRC Harvesting Experience Recent N RC ActivitiesCriteria for Prioritizing Data NeedsDatabase for Sources of MaterialsPath Forward "U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 2 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Background and Motivation
- Recent trends in global nuclear industry: Interest in extending nuclear power plant (NPP) lifespansNumerous NPPs, both in U.S. and internationally, have announced plans to or already have shut downlimited budgets have restricted the resources available to support new research, including harvesting programsAligning interests and leveraging with other organizations is important to maximize value Note to requester: Presenter notes from this PowerPoint presentation did not copy over when uploaded into NRC's redaction software. Notes from this slide are: "Recent trends in global nuclear industry: Interest in extending nuclear power plant (NPP) lifespans; Technical basis for managing aging of systems, structures, and components for longer time; Numerous NPPs, both in U.S. and internationally, have announced plans to or already have shut down; New opportunities for harvesting components that were aged in representative light water reactor (LWR) environments; Limited budgets have restricted the resources available to support new research, including harvesting programs; Aligning interests and leveraging with other organizations is important to maximize value."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 3 PrutrttinK Pt,,pk 11tu! IM &wlronmau
NRC Harvesting Experience
- NRC has participated in numerous harvesting programs over the years:RPV, CRDM penetrations, RCS piping, RPV internals, neutron absorbers, and cablesFrom unfinished, operating
,and decommissioning plants in U.S. and internationallySignificant value in using harvested components to confirm data from other research programs Note to requester: Presenter notes for this slide exceed the character limit to insert on this page. Notes included as a seperate page after this slide presentation.
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 4 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Technical Lessons Learned
- Harvesting can provide highly representative aged materials for researchMay be only practical source of representative aged materialsMay be able to use limited harvested materials to validate larger accelerated aging data setlmportant to gain as much information as possible in advance before committing to specific harvesting project Note to requester: Presenter notes for this slide are: "Harvesting can provide highly representative aged materials for research. May be only practical source of representative aged materials, particularly if irradiation and temperature are important factors. Achieving high fluence levels with representative irradiation conditions through other means is very challenging. May be able to use limited harvested materials to validate larger accelerated aging data set. Important to gain as much information as possible in advance before committing to specific harvesting project Ideally a bounding, yet realistic, material/environment. Understand material information (CMTRs if available) and plant operating conditions."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 5 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Logistical Lessons Learned
- Harvesting is an expensive, time-consuming effortleveraging resources with other research organizations helps mitigate cost challengesTransporting irradiated materia Is, particularly internationally, is cumbersome and time-consum1n Note to requester: Presenter notes for this slide are: "Harvesting is an expensive, time-consuming effort. Must balance cost with potential benefits carefu lly. High technical relevance of materials is needed to ensure value. Leveraging resources with other research organizations helps mitigate cost challenges. Can introduce challenges for testing when aligning research priorities and interests of multiple Lifting operation for organizations. May be needed, particularly for expensive testing of irradiated materials. Transporting irradiated materials, particularly internationally, is irradiated materials cumbersome and time-consuming. Avoiding extra transport, especially between transport cask countries, is highly recommended."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 6 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Recent NRC Activities
- Strategic approach to materials harvestingDue to limited opportunities, past harvesting efforts have generally been reactive to individual plants shutting downPrioritize the data needs best addressed by harvestingWorkshop held in March 2017 at NRC HQ to discuss all aspects of harvesting with other interested stakeholders Note to requester: Presenter notes for this slide are: "Strategic approach to materials harvesting. Due to limited opportunities, past harvesting efforts have generally been reactive to individual plants shutting down. Prioritize the data needs best addressed by harvesting. Criteria for harvesting prioritization developed by PNNL. Workshop held in March 2017 at NRC HQ to discuss all aspects of harvesting with other interested stakeholders. Good discussion of experience, including challenges and pitfalls, from those with firsthand knowledge."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 7 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Potential Criteria for Harvesting Prioritization
- Applicability of harvested material for addressing critical gapsEase of laboratory replication of the degradation scenarioUnique field aspects of degradationFleet-wide vs.
plant-specific applicability of data Note to requester: Presenter notes for this slide are: "Applicability of harvested material for addressing critical gaps. Harvesting for critical gaps prioritized over less essential technical gaps. Ease of laboratory replication of the degradation scenario. For example, simultaneous thermal and irradiation conditions are difficult to replicate. Unique field aspects of degradation. For example, unusual operating experience or legacy materials (fabrication methods, etc.) no longer available. Fleet-wide vs. plant-specific applicability of data."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 8 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Potential Criteria for Harvesting Prioritization
- Harvesting cost and complexityAvailability of reliable in-service inspection (ISi) techniques for the material/
componentAvailability of materials for harvestingTimeliness of the expected research results relative to the objective Note to requester; Presenter notes for this slide are: "Harvesting cost and complexity.
For example, harvesting unirradiated concrete or electrical cables less expensive and less complex than harvesting from the reactor internals. Availability of reliable in-service inspection (ISi) techniques for the material / component. If mature inspection methods exist and are easy to apply, harvesting may be less va luable. Ava ilability of materials for harvesting. Timeliness of the expected research results relative to the objective."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 9 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Database for Sources of Materials
- NRC is pursuing the development of a database for sources of materials for harvestingAllow for aligning of high-priority data needs to the available sources of materialsNRC is interested
,~
I I
.. -tt<
in engaging with other organizations in developing the database Note to requester: Presenter notes for this slide are: "NRC is pursuing the development of a database for sources of materials for harvesting. Includes both previously harvested materials and those available for future harvesting. Example of reactor Allow for aligning of high-priority data needs to the available sources of materials. The level of detail should be appropriate for the factors influencing internals harvesting plan decision-making. NRC is interested in engaging with other organizations in developing the database."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 10 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Conclusion and Path Forward
- Harvesting can yield highly representative and valuable data on materials agingData Needs Prioritization and Sources of Materials DatabaseAs specific harvesting opportunities are identified, NRC welcomes opportunities for cooperation and leveraging with other interested research organizations Note to requester: Presenter notes for this slide are: "Harvesting can yield highly representative and valuable data on materials aging. Having a clearly defined objective and early engagement with other stakeholders are keys to success. Data Needs Prioritization and Sources of Materials Database. NRC is interested in working with other organizations to identify high-priority data needs of common interest. As specific harvesting opportunities are identified, NRC welcomes opportunities for cooperation and leveraging with other interested research organizations."
"U.S.NRC Vnm'°" 5nr,.., N..ckn 11.,91,1111.,,y c,,,.n11*>"'111 11 PrutrttinK Pt,,pk 11tu! IM &wlronmau
Presenter notes on "NRC Harvesting Experience" slide:
NRC has participated in numerous harvesting programs over the years:
RPV, CRDM penetrations, RCS piping, RPV internals, neutron absorbers, and cables From unfin ished, operating ,and decommissioning plants in U.S. and internationally Significant value in using harvested components to confirm data from other research programs Harvesting materials from highly representative long-term aging environments increases confidence in safety margins Example Proj ects RPV materials Shoreham, Midland Reactor vessel head CROM penetrations North Anna, Davis-Besse Pressurizer from St. Lucie Piping from YC Summer, NMP, Oconee Reactor internals from Zorita Joint harvesting and testing project with EPRT and international Neutron absorbers from Zion Harvesting coordinated with DOE and EPRI; Independent NRC testing Concrete from Zorita Cables from Zion and Crystal River Previous Benefits of Harvesting Reduce unnecessary conservatis m Flaw distributions and Master C urve infomrntion came from harvested materials to support PTS rule Understand in-service flaws Mockups for NDE qual ification Leak rate methodology from studying in-service flaws Identify and better understand safety issues High-energy arc fault tests on alum inum electrical components
Note to requester: The attachment to this email is From: HJser Matthew immediately following .
To: Frankl Jstvao Subject : FW: Ex-Plant Materials Harvesting meeting Date: Thursday, October 06, 2016 2:40:13 PM Attachments: Harvesting Workshop Plan 9-27-16.docx Hi Steve, I just wanted to check if this ever percolated back up to Brian following our briefing of him last week.
Thanks !
M att From: Hiser, M atthew Sent: Tuesday, September 27, 2016 1:03 PM To: Frankl, Istvan <lstvan. Frankl@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>;
Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Subject:
RE: Ex-Plant M at erials Harvesting meeting Hi Steve, I have attached my updates to the one-pager per th e feedback from the meeti ng this morning.
Thanks!
Matt Matthew Hiser Materials Engineer US Nuclc,u- Regulatory Commission I Oflice of Nuclear Regulatory Research Division o f Engineering I Corrosio n and Me tallurgy Branch Phone: 30 /-4 15-245./.1 OJ]ice: TWFN /OD62 Matthew Hiser@nrc gov
Original Appointment-----
From: Vera, Graciela Sent: Friday, September 16, 2016 12:14 PM
To: Vera, Graciela; Brock, Kathryn; RES_ DE_Cal Resource; Thomas, Brian; Frankl, Istvan; Tregoning, Robert; Purtscher, Patrick; Hiser, Matthew
Subject:
Ex-Plant Materials Harvesting meeting When : Tuesday, September 27, 2016 10:00 AM-11:00 AM (UTC-05 :00) Eastern Time (US &
Canada).
Where: TWFN-07B01
Ex-Plant Materials Harvesting Workshop Motivation:
- With the wave of plants shutting down both in the U.S. and Europe, there are increasing opportunities to harvest components from decommissioning plants. Ex-plant materials are valuable because they have been exposed to actual in-service plant operating conditions (temperature, irradiation, coolant, etc.), unlike virgin materials tested under simulated conditions in the lab, which reduces the uncertainty associated with the applicability of the aging conditions.
- Insights from ex-plant harvesting research would support regulatory decisions for subsequent license renewal (SLR), and could have implications for the current license period depending on the findings.
- There is a task in the new draft UNR for SLR from NRR/DLR requesting RES to investigate opportunities for harvesting where appropriate.
Purpose and Objective:
- For NRC staff and interested stakeholders to have greater awareness and knowledge of the benefits and challenges associated with ex-plant harvesting.
- Facilitate contacts and communication to enable specific cooperative ex-plant harvesting programs to be initiated, leveraging limited NRC resources to produce highly representative technical data of materials degradation for extended plant operation.
Approach :
- NRC staff host 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.
- Format will include sessions with time for presentations and open discussion of different aspects of ex-plant materials harvesting.
- Views and insights from domestic and international regulators (JNRA), researchers (DOE, SCK-CEN in Belgium), industry (EPRI, utilities), and decommissioning companies' experience will be encouraged.
- Single talk given at relevant RIC session to disseminate ex-plant harvesting effort and encourage participation in workshop.
Intended Outcome:
- NRC staff and stakeholders are better informed of the benefits and challenges associated with ex-plant harvesting.
- Contacts are made w ith domestic and international utilities and researchers to a llow for further discussion of specific cooperative research projects that may address technical data gaps associated with materials degradation that can be best addressed through ex-plant harvesting.
Potential Dates:
- March 9-10, 2017 - Thursday/Friday before RIC
- March 16-17, 2017 - Thursday/Friday of RIC week
- March 20-21, 2017 - Monday/Tuesday after RIC
Discussion Topics:
- Harvesting decision-making / prioritization o Technical data needs best addressed by harvesting o Technical information needed in advance of harvesting
- Sources of materials:
o Decommissioning reactors o Operating reactors - replaced or failed components o Previous harvesting programs - "boneyards" o Tracking availlable materials
- Harvesting process o Lessons learned from harvesting experience o Perspective of utility-owner and decommissioning contractor on harvesting o Communication and coordination between decommissioning and researchers
- International collaborative programs on specific components at specific plants
Note to requester: The attachment to this email is immediately following.
From: HJser Matthew To: Miller Kenneth A; Sjrcar Madhumjta Cc: Purtscher Patrick; Audrain Margaret
Subject:
FW: Materials Harvesting Date: Friday, August 03, 2018 3:55:25 PM Attachments : Harvestjna Needs Prioritization 8-3-J8 xlsx Hi Kenn and Mita, l just wanted to follow up from this meeting/email back in May on harvest.ing priorities. J have attached a template of the prioritization of harvesting needs in the metals area. Can you follow that template to provide input for the electrical and concrete technical areas?
Please let me (or Meg or Pat OD cc) know if you have any questions.
Thanks!
Matt
Original Message-----
From: Hiser, Matthew Sent: Wednesday, May 16, 2018 10:36 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Audrain, Margaret <Margaret..Audrain@nrc.gov>; Sircar, Madhumita <Madhumita.S ircar@nrc.gov>; Pires, Jose
<Jose.Pires@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Murdock, Darrell
<Darrell.Murdock @nrc.gov>; Philip, Jacob <Jacob.Philip@nrc.gov>
Cc: Miller, Kenneth A <KennethA.Miller@nrc.gov>; Christensen, Jason <Jason.Christensen@nrc.gov>
Subject:
RE: Materials Harvesting Thanks everyone for attending the meeting this morning. I appreciate the update on activities for electrical and concrete and have attached the documents that were printed out this morning.
Action Items for Metals, Concrete, and Electrical l.Use prioritization criteria to prioritize data needs for harvesting in each area.
2.Catalog any previously harvested materials that may be available at labs.
3.Identify relevant information from license renewal documents for decommissioning plants Thanks!
Matt
Original Appointment-----
From: Hiser, Matthew Sent: Monday, May 07, 20 18 3:56 PM To: Hiser, Matthew; Purtscher, Patrick; Tregoning, Robert; Audrain, Margaret; Sircar, Madhurnita; Pires, Jose; Koshy, Thomas; Murdock, Darre!J ; Philip, Jacob Cc: Miller, Kenneth A; Christensen, Jason
Subject:
Materials Harvesting When: Wednesday, May 16, 2018 9:00 AM-10:00 AM (UTC-05:00) Eastern Time (US & Canada).
Where: Tl 0D40 Rescheduling for hopefully a better time for everyone.
We'd like to meet with electrical and concrete research staff to discuss the latest status of the materials harvesting
activities under T ask 2 of UNR NRR-2017-006.
The four topics we'd like to update you on / discuss in this meeting are:
I .CM B staff development of prioritization criteria for harvesting need s and lessons learned from exercising them for metals 2.CMB staff effort to development inventory of previously harvested materials already available at lab facilities 3.Latest status o f harvesting plans for electrical and concrete compone nts 4.Pulling relevant information from license renewal documents for decommissioning plants
Criteria Title Description Scoring Guidance H = high risk significance/ little to no available data MH = Medium-high risk significance/
limited data available Crilicalness of Technical Gap Harvesling to address critical gaps should be prioritized over less M = Moderate risk significance/ some Addressed csscn1ial 1echnical gaps data available ML= low to moderate risk slgnficance / H = High sufficient data available for regulatory MH = Medium-high decisions M = Medium L = Low risk significance/ large amount ML= Medium-low of data available L = Low H = Nearly impossible to replicate Key considcra1ions arc the case of labornlory rcplica1ion of aging service enviroment I critically important mechanism and unique field aspccls of the aging mechanism. to use* harvested materials Degradation mechanisms that arc harder 10 replicate with simulalcd MH = Challenging to replicate service aging conditions would be ofl,igher priority for harvesting. For envlroment I important to use example, simultaneous thermal and irradiation concli1ions arc clifl1cult harvested materials to replicate outs ide of the plant environment. Alternatively, M = Possible with some limitations to Importance of Harvested accelerated aging may nol be feasible for a mechanism scnsi1ivc to replicate service envlroment I Materials over Laboratory Aging dose rate. These two degradation mechanisms may be best moderately important to use harvested evaluated using harvested mlilerials. For unique field aspects, legacy materials materials (e.g., fabrication methods, composition) that are no longer ML= Not challenging to replicate available, but may play an iml)onant role in a polcntial degradation service enviroment / less important to mechanism, would have a higher priority than harvesting materials use harvested materials that can be obtained from other sources wi1h representative L = Very easy to replicate service properties. envlroment I not important to use harvested materials H = All plants There is grcnlcr value in developing knowledge lo uddrcss an issue MH = AIIPWRs Applicability 10 US Operating lhat may be applicable to a larger number of plants compared to one M = Ali BWRs or most PWRs Fleet that may only affect a relat ively small number of plants. ML= 15 plants L = <5 plants H = No or very limited inspection methods available/ low confidence in AMPS If ma1urc inspcclion melhods cxisl and arc easy 10 apply 10 monilor MH = Limited Inspection methods degradation, harvesting may be less valuable. If inspection methods available/ low-to-moderate confidence Regulatory Considerations Related do not exist, harvesting may be essential 10 ensure confidence in the In AMPs to lnspcclions an.d AMPs assessment of age-rcla1ed degradation in thal panicular M = Some inspection methods available component.The less confiden.ce thal NRC staff has in the / mode rate confidence In AMPs effectiveness of the reicvanl AMP, the higher priorily for harvesting. ML= Good inspection methods available/ medium-high confidence In AMPs L = Effective, well-accepted inspection H = Highly irradiated (>5 dpa)
Activities with higher costs and complexity are less attractive than MH = Lightly irradiated/ contaminated similar activities wi1h lower costs and that arc simpler to execute .. M = Minimal contamination or high effort Harvesting cost and complexity For example, harvesting unirradiated concrete or electrical cables is unirradiated less expensive and less complex than harvcsling from the RPV ML= Unirradiated, moderate effort intcmals or the RPV. expected L = Unirradiated, low effort expected T he ability of a potential harvesting program to provide timely results Timeliness of results 10 support either a technical or regulatory need is impo11ant. I laving high confidence 1ha1 results will be timely increases the priority.
Availability of materials for The availability of materials to harvest for a panicuiar data need is harvesting clearly essenlial and increases lhe priority.
Basic Info TK hnical Cri t eria Proiect Specific Regulotory <An*lderotlono Cost I Complexity Avoftobllltyof Purpose / Tasting Criticalness of Technical Importance of Harvested Timeliness of N eed Oescrtptlon Technical Knowledge Gained A,,plica,bllity to US Operating Fleet Related to Inspections and Score Average Basis fOf' Technkal Priority materials for Pl anned Gap A ddn,ssvd Material s over Laboratory Aging results AM... harvestlno META LS S<o,. CCll'l'\r'Mnt Score Comment Scor* Convnent Score Comm.,.t Score Co........nt EPRI p8fforming R&D on Laboratory repication very NOE fof void sweling; c:iffiajt to impossible IO MRP-227 uses prwna,rily Significance of void swelting at Likety extent of void sweling In Fillsdatagapfof act.eYe fluencies with visual teWlg, which co!Ad higher ftuences is uncertain, Very Ngh cosl for VOid swelling. meehanieat PWRs dul'ing extended opeta11on extended pla,. representative inadlatJOn Applcabl,e to high-fluence detect vOld swell.ng once and illSpectiO(IS may detect tlii:,.tyfl'ad.ated I Mint. fluence rel<ldor internals p ~ s . lASCC and impiie:t on aadcina M ..... """""'"' MH components in most PWRs MH fairtv ~~ n t 3.75 onset QI siatiific1:1nt deoradaion VH internals TBD Would g-eatty lhaease Moderate cost for Purpose OI WClfk WOl.6::1 bEI confid&nce., large: set of contama,ated.. but Frac,.w-e 1oughness dauri in re3' Validate 1opro,,,ider~rtd eooeterated aging data with not irradiated, ThermaMy aged Ul'WT'3Ciated CASS Fraetwa toughness and m iet0$UVClure eonciliiOns to compare IO
~,e<1_.......daca ... aoc:eler.!iled agi'lg data H vaidabon of aceeklfated 1,,......,....,inlabt--,......,
May be possible. but M
Most applieabla to a subset Of PWRs H No ISi method avalabloe to meaisl#'e loss of FT lesting of Ul'Wradiatsd 4.25 ma1eria,ls M primary stsem c,on-,endiated
,~ n t s Mooer-ate cost tor contaminated. but Metallic con,pooen~ with Metallic components with NOE and deslrUdive exan*\ation NOE and destrueuve methods ant effective al preventing SCC; elfectivmess of NOE at detec:b::lnandSizinQ Deiermine wheiher fa,t:igue flaws are ore.sent in koo,h usaoe locabons Validate NOE and mitigotion metllod effectiYeness Vali date faligue ife Purpose OI WOfk wo!Ad bEI tol)IU',lidereal-world vaidallon Of lab testinQ Purpose OI WOfk WOi.*i be to proYide re3'-wortd validabon of lab testana H
H A~ t o a l plants Ml assess 111spection and mtigation method enectiveness F.atigu,e c:;;alcJJl.atiOn.s in!Otm sa,mpling inSJ;1ections of 11-n*hnn ~ue locations Increase confidena? in NOE 3.75 and mmn:mnn methods Increase cori6dence in fat,gue 3.25 ife ca1culabons M
not irradiated.
prirn3fystsem 1, - n t s Moderate 00$1 lor contaminat ed, but notffadi.ated, prima,,y stsem limitlna bt..... ... hfe exanh.oon melhodoloo,es A~ t o a l l clants ML M '-nts
Basic Info Techni,cal Crite,fa Pro*ect s -*fic Purpose / Testing Criticalness of Technical lmporbnce of Harvested Regulatory Conskfuations Cost J Comple.xity Timeo;ness of Availability of Need Description Technical Knowle dge Gained Materials over Laboratory Applicability to US Operating Fleet Rel ated to Inspections and Sc ore Average Basis for Priority materials for Planned Gap Addressed An... results A.MPs harvestina ELECTRICAL Score Commen t Score Comment Sc:o re Comment Score Comment S co re 1Commen t Low and medlum voltage cables Cables ptOlected wrth fira reaardant coating 1E MOVs from harsh and mild enwonmencs t E Air operated valves; 4160 1£ breakats 1E Molded case breakers 480V, 25lN DC, 125 VDC.
1E Relays from mid environment GE - HFA.
Aga:stat timing relays, any from Westinghouse, Potier
-~--
Brumfiekl, Stuther.i Dunn Batteries EJectJical DAn&trabonS F*e research Interest Electrical enclosures Distribution: switchgear, MCCs. LCs I Conltol:
Horseshoe. SSCP. AS? etc.
Basic Info Techni,cal Crite,fa Pro*ect s-*fic lmporbnce of Harvested Regulatory Conskfuations Cost J Comple.xity Timeo;ness of Availability of Purpose / Testing Criticalness of Technical Need Description Technical Knowle dge Gained Materials over Laboratory Applicability to US Operating Fleet Related to Inspections and Score Average Basis for Priority materials for Planned Gap Addressed An... results A.MPs harvestina CONCRETE Score Comment Score Comment Sc:ore Comment Score Comment Score 1Comment Structixes exposed 10 liQh radiation Post-tens.oned structures Corroshn of reinlorang steel.
tendon, liner, embedment
~ t fuel pool and 1ranster canal-bone acid attack on concrete a, PWRs Alkali Aggregate Reaction lMge structural sections for testlng
Note to requester: The attachment to this email is From: Sircar Madhumita immediately following .
To: Hiser Matthew Cc: Pires Jose; Seber Dogan
Subject:
FW: Mat erials Harvesting Date: Thursday, September 13, 2018 3:39:28 PM Attachments: Copy of Harvesting Needs Prioritization MS JP.x1sx
- Matt, Please find attached our input on harvesting needs prioritization.
- Thanks, Mita
Original Message-----
From: Pires, Jose Sent: Wednesday, September 12, 20 l8 5: 17 PM To: Sircar, Madhumita <Madhumjta.Sircar@nrc.gov>; Seber, Dogan <Dogan.Seber@nrc.gov>
Subject:
RE: Materials Harvesring
- Mita, Son-y for the delay. I entered a line for ASR and added something on the first column of the in-adiation.
Jose
Original Message-----
From: Sircar, Madhumita Sent: Monday, September 10, 2018 4:05 PM To: Seber, Dogan <Dogan.Seber@nrc.gov>; Pires, Jose <Jose.Pires@mc.gov>
Subject:
FW: Materials Harvesting
- Jose, As we discussed last week, I have provided input on harvesting needs prioritization for (i) Structures Exposed to High Radiation and (ii) Post-tensioned Structures. Could you please provide input on AAR and review the input 1 provided on the two topics.
1 propose to delete the other topics and keep these 3 topics only. As I understand this form will be used to communicate with NRR and tee-up the discussion with NRR. CMB has a UNR from NRR.
- Dogan, Once Jose and I complete our input, 1 will send it to you for review.
Matt requested to get it by 9/14.
- Thanks, Mita
Original Message-----
From: Hiser, Matthew Sent: Friday, August 03, 2018 3:55 PM To: Miller, Kenneth A <KennethA.Miller@nrc.gov> ; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>
Cc: Purtscher, Patrick <Patrick.Pu rtscher@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc .gov>
Subject:
FW: Materials Harvesting Hi Kenn and Mita,
I just wanted to follow up from this meeting/email back in May on harvesting priorities. I have attached a template of the prioritization of harvesting needs in the metals area. Can you follow that template to provide input for the electrical and concrete technical areas?
Please let me (or Meg or Pat on cc) know if you have any questions.
Thanks!
Matt
Original Message-----
From: Hiser, Matthew Sent: Wednesday, May 16, 2018 10:36 AM To: Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Tregoning, Robert <Robert.Tregoning@nrc.gov>; Audrain, Margaret <Margaret.Audrain@nrc.gov>; Sircar, Madhumita <Madhumita.Sircar@nrc.gov>; Pires, Jose
<Jose.Pires@nrc.gov>; Koshy, Thomas <Thomas.Koshy@nrc.gov>; Murdock, Darrell
<Darrell.Murdock@nrc.gov>; Philip, Jacob <Jacob.Philip@nrc.gov>
Cc: Miller, Kenneth A <KennethA.Miller@nrc.gov>; Christensen, Jason <Jason.Christensen@nrc.gov>
Subject:
RE: Materials Harvesting Thanks everyone for attending the meeting this morning. I appreciate the update on activities for electrical and concrete and have attached the documents that were printed out this morning.
Action Items for Metals, Concrete, and Electrical
!.Use prioritization criteria to prioritize data needs for harvesting in each area.
2.Catalog any previously harvested materials that may be available at labs.
3.Identify relevant information from license renewal documents for decommissioning plants Thanks!
Matt
Original Appointment-----
From: Hiser, Matthew Sent Monday, May 07, 2018 3:56 PM To: Hiser, Matthew; Purtscher, Patrick; Tregoning, Robert; Audrain, Margaret; Sircar, Madhumita; Pires, Jose; Koshy, Thomas; Murdock, Darrell ; Philip, Jacob Cc: Miller, Kenneth A; Christensen, Jason
Subject:
Materials Harvesting When: Wednesday, May 16, 2018 9:00 AM-10:00 AM (UTC-05:00) Eastern T ime (US & Canada).
Where: TlOD40 Rescheduling for hopefully a better time for everyone.
We'd like to meet with electrical and concrete research staff to discuss the latest status of the materials harvesting activities under T ask 2 of UNR NRR-2017-006.
The four topics we'd like to update you on / discuss in t11is meeting are:
l .CMB staff development of prioritization criteria for harvesting need s and lessons learned from exercising them for metals 2.CMB staff effort to development inventory of previously harvested materials already available at lab facilities 3 .Latest status of harvesting plans for electrical and concrete components 4.Pulling relevant information from license renewal documents for decommissioning plants
Criteria Title Description Scoring Guidance H = high risk significance/ little to no available data MH = Medium-high risk significance/
limited data available Crilicalness of Technical Gap Harvesling to address critical gaps should be prioritized over less M = Moderate risk significance/ some Addressed csscn1ial 1echnical gaps data available ML= low to moderate risk slgnficance / H = High sufficient data available for regulatory MH = Medium-high decisions M = Medium L = Low risk significance/ large amount ML= Medium-low of data available L = Low H = Nearly impossible to replicate Key considcra1ions arc the case of labornlory rcplica1ion of aging service enviroment I critically important mechanism and unique field aspccls of the aging mechanism. to use* harvested materials Degradation mechanisms that arc harder 10 replicate with simulalcd MH = Challenging to replicate service aging conditions would be ofl,igher priority for harvesting. For envlroment I important to use example, simultaneous thermal and irradiation concli1ions arc clifl1cult harvested materials to replicate outs ide of the plant environment. Alternatively, M = Possible with some limitations to Importance of Harvested accelerated aging may nol be feasible for a mechanism scnsi1ivc to replicate service envlroment I Materials over Laboratory Aging dose rate. These two degradation mechanisms may be best moderately important to use harvested evaluated using harvested mlilerials. For unique field aspects, legacy materials materials (e.g., fabrication methods, composition) that are no longer ML= Not challenging to replicate available, but may play an iml)onant role in a polcntial degradation service enviroment / less important to mechanism, would have a higher priority than harvesting materials use harvested materials that can be obtained from other sources wi1h representative L = Very easy to replicate service properties. envlroment I not important to use harvested materials H = All plants There is grcnlcr value in developing knowledge lo uddrcss an issue MH = AIIPWRs Applicability 10 US Operating lhat may be applicable to a larger number of plants compared to one M = Ali BWRs or most PWRs Fleet that may only affect a relat ively small number of plants. ML= 15 plants L = <5 plants H = No or very limited inspection methods available/ low confidence in AMPS If ma1urc inspcclion melhods cxisl and arc easy 10 apply 10 monilor MH = Limited Inspection methods degradation, harvesting may be less valuable. If inspection methods available/ low-to-moderate confidence Regulatory Considerations Related do not exist, harvesting may be essential 10 ensure confidence in the In AMPs to lnspcclions an.d AMPs assessment of age-rcla1ed degradation in thal panicular M = Some inspection methods available component.The less confiden.ce thal NRC staff has in the / mode rate confidence In AMPs effectiveness of the reicvanl AMP, the higher priorily for harvesting. ML= Good inspection methods available/ medium-high confidence In AMPs L = Effective, well-accepted inspection H = Highly irradiated (>5 dpa)
Activities with higher costs and complexity are less attractive than MH = Lightly irradiated/ contaminated similar activities wi1h lower costs and that arc simpler to execute .. M = Minimal contamination or high effort Harvesting cost and complexity For example, harvesting unirradiated concrete or electrical cables is unirradiated less expensive and less complex than harvcsling from the RPV ML= Unirradiated, moderate effort intcmals or the RPV. expected L = Unirradiated, low effort expected T he ability of a potential harvesting program to provide timely results Timeliness of results 10 support either a technical or regulatory need is impo11ant. I laving high confidence 1ha1 results will be timely increases the priority.
Availability of materials for The availability of materials to harvest for a panicuiar data need is harvesting clearly essenlial and increases lhe priority.
Basic Info Technical Criteria Project Specific Regulatory Considerations Cost/ Complexity Availability of Purpose / Testing Criticalness of Technical Importance of Harvested Timeliness of Need Description Technical Knowledge Gained Applicability to US Operating Fleet Related to Inspections and Score Average Basis for Technical Priority materials for Planned Gap Addressed Materials over Laboratory Aging results AMPs harvestlna METALS Score Comment Score Comment Score Comment Score Comment Score Comment EPRI perlo,ming R&O on LabOtatory replication very NOE for void swelling:
difficult to impossible to MRP-227 uses primarily Significance of void swelling at Likely extent of void swelling in Fills data gap for achieve nuences with visual testing, which cooid higher ftuences is uncertain, Very high cost for Void swelling, mechanical PWRs during extended operation extended plant representative irradiation Applicable to high-fluence detect void swelling once and inspections may detect highlyirradiated HiQh fluence reactor intemals properties, IASCC and impact on crackillQ M operation MH conditions MH components in most PWRs MH failtv sianif,cant 3.75 onset of siQnificant deQradation VH internals TBO Would greatly increase Moderate cost for Purpose of worl< would be confidence in large set of contaminated, but Fracture toughness data in real Validate to provkle real-world accelerated aging data with net irradiated, Thenmally aged unirradiated Fracture toughness and conditions to compare to accelerated aging validation or accelerated Most applicable to a subset or No ISi method available to testing of unirradiated primarystsem CASS mlcrostructure accelerated aQina data MH data H laaina In lab testina M PWRs H measure loss of FT 4.25 materials M components May be possible, but difficult to replicate long- High cost for Moderate fluence (1*2 dpa) Fracture toughness and Fracture toughness data near limit Confirm regulatory term aging and irradiation Most applicable to a subset of No ISi method available to Would increase confidence in irradiated CASS microstructure reQuiring further evaluation ML IPosition MH effects M PWRs H measure loss of FT 3.5 regulatory position H comPonents Moderate cost for Detenmine whether SCC mltigatk>n Purpose of this worl< is to contaminated, but methods are effective at preventing Validate NDE and Purpose of worl< would be assess inspection and net irradiated.
Metallic components with NDE and destructive SCC; effectiveness of NDE at mitigation method to provide real-world mitigation method Increase confidence in NDE primary stsem known flaws examination detection and sizing MH effectiveness MH validation or tab testing H IApplicable to all plants ML effectiveness 3.75 and mitigation methods M components Moderate cost for contaminated, but Purpose of worl< would be Fatigue calculations inform not irradiated, Metallic components with NOE and destructive Determine whether fatigue flaws are Validate fatigue life to provide real-world sampling inspections of Increase confidence in fatigue primary stsem limiting fatiQue tte examination Ipresent in hiQh usaae locations MH methodok>Qies ML validation of tab testing H IAnnlicable to all plants ML limitina faliaue locations 3.25 life calculations M comPonents
Basic Info Techni,cal Crite,fa Pro*ect s -*fic Purpose / Testing Criticalness of Technical lmporbnce of Harvested Regulatory Conskfuations Cost J Comple.xity Timeo;ness of Availability of Need Description Technical Knowle dge Gained Materials over Laboratory Applicability to US Operating Fleet Rel ated to Inspections and Sc ore Average Basis for Priority materials for Planned Gap Addressed An... results A.MPs harvestina ELECTRICAL Score Commen t Score Comment Sc:o re Comment Score Comment S co re 1Commen t Low and medlum voltage cables Cables ptOlected wrth fira reaardant coating 1E MOVs from harsh and mild enwonmencs t E Air operated valves; 4160 1£ breakats 1E Molded case breakers 480V, 25lN DC, 125 VDC.
1E Relays from mid environment GE - HFA.
Aga:stat timing relays, any from Westinghouse, Potier
-~--
Brumfiekl, Stuther.i Dunn Batteries EJectJical DAn&trabonS F*e research Interest Electrical enclosures Distribution: switchgear, MCCs. LCs I Conltol:
Horseshoe. SSCP. AS? etc.
Basic Info Technical Criteria Project Specific Importance of Harvested Regulatory Considerations Cost/ Complexity Availability of Purpose / Testing Criticalness of Technical Gap Timeliness of Need Description Technical Knowledge Gained Materials over Laboratory Applicability to US Operating Fleet Related to Inspections and Score Average Basis for Priority materials for Planned Addressed results Aaina AMPs harvestino CONCRETE Score Comment Score Comment Score Comment Score Comment Score Comment Struclures Degradalion of concrete Physical and mechanical H Confirm regulatory H Harvesting is of high M MostPWRs H New aging mechanism 4.5 Very limited data, new aging M Moderate TBD e,posed to high due lo Irradiation, degradation data under service position. Data available Importance because no added for further evaluation mechanism added in SLR* cost for radiation attenuation or radiation environment. Level of lrradaiation from 1970's are not data available from in SLR-GALL and SLR* GALL, SLR-SRP. No moderate through concrete. (neutron, gamma, temperature) representative or light service irradiated SRP. No inspection inspection method and OE not level of through the concrete and depth of water reactor (LWR1 concrete, inaccessible method and data available. available because location irradiation on irradiation damage. Aggregate environments. Recent for inspection, limited inaccessable, Safety concrete.
expansion, cracking of concrete, limited number of data lab test data, small significance for RPV support differential response of components available from NRAJ are scale lab test structures are critical.
or concrete, i.e, aggregate, mortar, representative or LWR specimen.
and rebarlsteel embeds and environment . Validate degradation under thermo-hydro* accelerated aging data.
radio-mechanical environment due Currently no data to radaition. Conduct NOEs. available from service irradated concrete. Real world validation of test data and benchmarlling of degradation models.
Conduct NDEs.
Post-tensioned Degradation of post- ln-~tu internal degraclation, MH Investigate and verify MH Real word validation of MH Aboot 37% US NPPs H Concrete internal condition 4.25 Improve confidence on L Unirradiated TSO structures tensioning (PT) system. delamination, adjustment of knowedge related to lab testing, bench containment Is post-tenslOned. is not part of ISi. Lim~ed numerical modelling, potential prestress force and interaction with degradation modes under marlling of numerical Also there are a few post- condition monitoring for failure modes, degradations, ins1tu degradation. sustained multi axial modelling, potential tensioned/prestressed SFP. tendon. Oetensioning and and NOEs. Collect critical prestessing force wihout failure modes, retensioning of tendons of information from failed post*
radial rebar, lntemal applicable NOEs. aged containment. tensioned containmnet.
degradation, degradation Critical information Effective NOE for PT of prestessing system from failed posl* containmenl slructure not including anchcrage, tensioned containmnet. available.
NOE methods.
Degradation of concrete Ongoing research is providing MH To study in-s!u effects of M The knowedge gained H One plant severely affected by M Monitoring for 3.75 Inform adjsutements to aging L Unirradiated An mtemational from Alkali-Silica-Reaction undersanding of the concrete ASR concrete from the current ASR in lhe US. Because ASR manifestation of ASR is management programs. cooperative (ASR) material damage mechanisms and degradation and research is primarity is a slow evolving chemical part of aging management Enhanced understanding of research program the characterization of that damage comparison with derived from controlled mechanism of the concrete programs for concrete the possibillity of combined is being initiated as well as of its implications to understanding developed laboratory testing itseW and all plants have safety- structures. For structures degradation effects mthe f.,ld. under the structural performance. The from laboratory testi'lg. involving controlled related concrete structures, with ASR more complex Assess homgeneity of damage auspices fo the knowledge gained is primarily To investigate possibility aging environments at monitoring for ASR is part of aging management plans in real structures. CSNI. The derived from laboratory testing of combined aging effects constant environemnts, concrete magement programs would monitor the program will test together with visual observations of such as ASR and homogeneous aging for an concrete structures for progression of ASR, concrete samples field structures. reinforcementcorrosion. and single aging iong term oeprations. concrete cracijng, harvested from a mechanism. structural deformations decommissioned and, ff needed, mvotve nuclear power coring and testing of plant in Canada samples. Study orIn-situ extensively conditions would support affected by ASR.
implementation of more The NRC plans to Corrosion of effective aging participate in this reinforcing steel, management plans. program, which is tendon, liner, likely to provide embedment *- *-- *"-
Spent fuel pool and transfer canal-boric acid attack on concrete in PWRs Alf<ali Aggregate Reaction Large structural sections for testing,.__ _ _ _ _ _....._____________.__.__ _ _ _ _ _.....__ _.
Note to requester: The "RES-DE bilaterial meetings RIC 2017" hyperlink in this From: Frankl Istvan document is included on the To: Ireaoolnn Bot>eri Cc: Hiser Manhew; Purtscher Pardck: ~ next page.
Subject:
FW: BIiaterai meetings during the RIC Date: Monday. February 06, 2017 3 :50:00 PM Attachments: ~
- Rob, The only meeting we are planning around the RIC is the Harvesting Workshop. Please provide the latest information as requested by our TA below
- Thanks, Steve From: Berrios, Ilka Sent: Monday, February 06, 2017 2:56 PM To: Iyengar, Raj <Raj.lyengar@ nrc.gov>; Frankl, Istvan <lstvan.Frankl@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>; Boyce, Tom
<Tom.Boyce@nrc.gov>; Seber, Dogan <Dogan.Seber@nrc.gov>
Cc: Thomas, Brian <Brlan.Thomas@nrc.gov>; Nakoski, John <John.Nakoski@nrc.gov>
Subject:
Bilateral meetings during the RIC
- All, Please let me know if you are planning to have any bilateral meetings during the RIC. You can either send me the info or update the file in SharePoint.
RES-DE bilateral meetings BIC 2012 This is the info that we need:
RES/DE Country/
Date T ime Attendees management Topic of discussion Organization needed?
- Thanks, fl!.11 415-2404
RES/ DE Bilateral Meetinas durina the 2017 RIC Country/ RES/DE Branch Date Time Attendees management Topic of discussion Organization "'°' _ _. _ _.,,
SGSEB IAEA 03/16/2017 1-Spm Mr. Shin Morita, A welcome by IAEA's external hazards safety section head, Section Head of RES/DE Morita Shin will be meeting with RES/NRO External Events management technical staff to discuss IAEA's ongoing Safety Section and would be technical activities including progress of IAEA Technical staff from beneficial programs, future collaboration opportunities RES and NRO between IAEA/EESS and NRC in ICEEB Halden Reactor Thursday 16 1-Spm Peter Karpati, Jon no Dl&C safety assurance with special focus on Project, Dl&C Kvalem, and experiences with assurance cases Safety Friday 17 9am - Christian Raspotnig Demonstration 5pm from Halden . Bruce Project group Hallbert, INL (Norway) RES/DE: Sushil, Ian and Derekf CMB EPRI, DOE, 3{7-3/8 8-Spm, 30 attendees No, this is a Discussing better ways to proactively plan for PNNL, ORNL, each day representing the working level harvesting materials from decommissioning Energy NRC and the meeting nuclear power plants Solutions, organizations listed Dominion, CRIEPI, JNRA, JAEA, GRS, SCK-CEN, Studsvik, Westinghouse ,
Danoff, Karen From: Hiser, Matthew Se nt: Wednesday, May 27, 2015 4:01 PM To: Frankl, Istvan
Subject:
FW: slides for next week FYI - Rob's feedback From: Tregoning, Robert Sent: Wednesday, May 27, 2015 3:45 PM To: Hiser, Matthew Cc: Hull, Amy
Subject:
RE: slides for next week Matt/Amy:
I took a quick look at this and think it's generally okay. You have 1h hour and there may be more material here than you can fit into the allotted time. If you were to cut information, I'd consider cutting the slides on our current harvesting programs. While these are interesting, they are not germane to developing an information tool to help select future plant SSCs for evaluation.
I also think it would be good to stress that we want to identify the characteristics of important SSC for harvesting up front so that when plants announce their plans, we can move quickly to identify SSCs of interest.
It would really be nice if you provided a concrete example (bad pun) on how this tool would be used. For example, there could be value in getting CASS material with 15% delta ferrite that has received various amount of irradiation(< 0.08 dpa, 1 - 3 dpa, and> 5 dpa). It might be possible to identify a single component (e.g., lower support columns) that might possess the requisite properties for such an evaluation. In my mind at least, the information tool would ideally identify the material characteristics of interest to study and also components that would possibly satisfy these requirements.
This is just my idea and it may be premature at this point to have in the presentation, but we should be thinking about this now so the information tool is structured appropriately.
- Thanks, Rob PS - let me know when the presentation is final so that I can put it with the rest.
Robert Tregoning Technical Advisor for Materials US Nuclear Regulatory Commission 21 Church Street, M/5 CS-5A24 Rockville, MD 20850 ph: 301-251-7662 Blackberry: ..... (1?)(§)
fax: 301-251-7425 From: Hiser, Matthew Sent: Wednesday, May 27, 2015 2:54 PM To: Tregoning, Robert Cc: Frankl, Istvan; Hull, Amy
Subject:
FW: slides for next week Hi Rob, Please feel free to review and provide comments/edits on these slides on Strategic Harvesting for the meeting next week.
Thanks!
Matt Matthew Hiser Materials Engineer Corrosion and Metallurgy Branch 1
Division of Engineering Office of Nuclear Regulatory Research 301-251-7601 From: Hull, Amy Sent: Wednesday, May 27, 2015 2:52 PM To: Frankl, Istvan Cc: Hiser, Matthew
Subject:
slides for next week Hi Steve, These are ready for you to review. I will complete 390 form now.
2
Note to requester: The From: HJser Matthew To: Tregoning Robert attachment to this Cc: Frankl Istvan; J::i.uJ.I....Aw email is immediately Subject : FW: slides tor next week following.
Date: Wednesday, May 27, 2015 2:54:00 PM Attachments: harvestino - status ootx Hi Rob, Please feel free to review and provide comments/edits on these slides on Strategic Harvesting for the meeting next week.
Thanks!
Matt Matthew Hiser Materials Engineer Corrosion and Metallurgy Branch Division of Engineering Office of Nuclear Regulatory Research 301 -251-7601 From : Hull, Amy Sent: Wednesday, May 27, 2015 2:52 PM To: Frankl, Istvan Cc: Hiser, Matthew Subject : slides for next week Hi Steve, These are ready for you to review. I will complete 390 form now.
t;> U.S.NRC Unired Srarcs Nuclear Regularory Comm ission Protecting People and the Environment
Outline U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Purpose
- Background
- Harvesting Experience
- Approach to Strategic Harvesting
- Engagement with Other Stakeholders
Purpose U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Create a framework for a strategic approach to harvesting ex-plant materials
- Ex-plant materials offer unique environmental exposure that cannot be entirely replicated by laboratory testing with fresh materials
- Combine high priority data needs identified in SLR/LTO activities with harvesting opportunities from decommissioning pla
Background U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- To date, harvesting opportunities have been limited due to few decommissioning plants
- Zion in U.S., Zorita in Spain
- However, several U.S. plants have already shut down or are planning to do so in the near future
- Kewaunee, SONGS, Crystal River, Vermont Yankee, Oyster Creek
- This provides a unique opportunity to plan harvesting for the maximum utility to address the highest priority technical issues
Harvesting Experience U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Past harvesting efforts have generally involved a reactive decision-making process
- Limited opportunities to acquire ex-plant materials
- Limited strategic planning for harvesting
- Harvesting projects with NRC involvement:
- Reactors internal materials from Zorita
- Concrete from Zorita
- Neutron absorber material from Zion
- Cables from Zion and Crystal River
Zorita Internals Research Project (ZIRP) U.S.NRC United Scates Nuclear Regulato ry Commission Protecting People and the E nvironment
- Materials Harvested: l'Lll1t8 l'Llllt(
- Baffle plate and core barrel weld I materials Scope:
0 0 0 010 I'
0 0 0 0
°'o oo-1 I
- Mechanical testing (tensile, CGR, FT) II II
- Microstructural characterization (void I. II swelling) 0 0 0 0 1 0 0 0 0 0 0 10 0 0 I
Purpose:
II
- High-fluence (up to 50 dpa) IAD effects I with representative LWR exposure conditions
- Timeline:
- Initial discussions in 2006, harvesting in 2013, testing ongoing through 2016
- Coordination:
- EPRI, international consortium, Studsvik, Halden
ZIRP Timeline U.S.NRC United Scates Nuclear Regulatory Commission Protecting People and the Environment Task 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 Project Inception ~r Feasibility Study Project Planning Cutting Plans Equipment Design & Manufacturing On-site Preparations Material Extraction I On-site Logistics Shipping Radiation and Temperature Analyses Material Inspection, Inventory, Documentation I Materials Testing I Reporting ,r
Neutron Absorbers from Zion U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested:
- Select Bora I NAM panels from Regions 1 and 2 of the Zion SFP
- Scope:
- Visual and microstructural examinations (incl. areal density)
- Corrosion testing
Purpose:
- Identify degradation mechanisms
- Estimate degradation rate
- Confirm results of in-situ areal density measurements
- Timeline:
- Initial discussions in 2014, harvesting in 2015, testing in 2015-2016
- Coordination:
- EPRI, ZionSolutions, SRNL
Concrete from Zorita (Plan U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested:
- Concrete from structures that are in close proximity to RPV
- Scope:
- Mechanical testing (compressive, tensile, modulus of elasticity)
- Microstructural characterization
- Physical change
Purpose:
- High fluence in combination with temperature and humidity that are representative of LWR environment effects on structural and shielding performance
- Timeline:
- Initial discussions in 2014, harvesting in 2015, testing 2016-2018
- Coordination:
- NRC, ENRESA and CSN
Cables: Zion and Crystal River U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Materials Harvested:
- Low and Medium Voltage Cables
- Scope:
- Condition monitoring to assess cable performance under normal operating conditions (accelerated aging) and accident conditions
Purpose:
- Cable degradation due to normal operating environment and accident conditions
- Timeline:
- Initial discussions in 2012
- Cable samples harvested from Zion in 2013
- Plan is to harvest additional samples from Crystal River and Zion in 2015
- Testing expected to be completed in 2017
- Coordination:
- ORNL, Zion Solutions
Challenge: NPP Safety Beyond 60 Years U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment NPPs allowed 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. The staff currently believe (SECY-14-0016, NUREG-1925) the most significant technical issues challenging power reactor operation beyond 60 years are:
- Reactor pressure vessel (RPV) neutron embrittlement at high fluence
- Irradiation assisted degradation (IAD) of reactor internals and primary system components
- Concrete and containment degradation
- Electrical cable qualification and condition assessment.
As stated in SRM-SECY-14-006, "the staff should continue to emphasize in communications with industry the need to strive for satisfactory resolution of these issues prior to the NRC beginning a review of any SLR application."
Approach: Integrated Aging Degradation U.S.NRC Uni ted Scates Nuclear Regulatory Commission Need/Resource Interrogatory Tool Protecting People and the Environment
- Various domestic and international sources of technical information of generic nature with respect to anticipated degradation in NPPs during LTO, extrapolating to 80 years of operation.
- Evaluate what relevant ex-plant material from decommissioned reactors is projected to be available for potential harvesting.
- Replace current piecemeal approach that obtains isolated and fragmented degradation information as targets of opportunity arise at a few plants with a strategic plan that is more comprehensive, broader in scope, and more risk-informed.
Sources: PMDA & EMDA U.S.NRC United Scates Nuclear Regulatory Commission Protecting People and the Environment How does one try to predict the future?
PLANT DATA DRAWINGS Based on drawings, Plant-specific documents. e.g.* FSAR. information consultants, Experts were tasked with Listing vulnerable reactor components ,
Reviewing relevant degradation mechani sms DJ. PARTS INFORMATION Excel spreadsheets by group developed by BNI., revised Determining the degree to which the components based on tecf)nical lnout.
were vulnerable to these mechanisms Determining confidence level in their predictions [41 COMPONENTSUBGROUPS
- Panel
. Excel spreadsheets developed by a lead expert, revised bas.cl on discussions amono =ne/.
Members
pages long. The electronic version is 121 MB and consists of 16 files EVALUATION DATABASE 0 ACCESS database with ell evaluations The EMDA panels investigated issues of reactor aging beyond 60 years to identify possi ble knowledge gaps, and REPORTS provided an expansion of scope and time 0 Compilations, filters. counts, etc.
EMDA (NUREG/CR-7153} U.S.NRC mt
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EXpa,dtd l&Metllls Oegradlllon 111d Piping Syattmt RC ANlyaft(EIIDA)
Ellpanded MatlNII Dtr,nidadon Volume S: Aglog ol RtoKIOf Prwsur,v..-, ~ l (EMOA)
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Source: DOE LWRS Program U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment (J. Busby, Overview Presentation to NESCC May 12, 2015)
- ,Co,m plete ch a ra ct e,1r*i zat ion o f demonstr,a t'iio n of
- .* Lice1n se * : p tliC'atr. on 1 RPV sect.ions l ected Sul *mitted f o Howin g 1an1n ealliinc a 1n d re i rra d iia1tiio ,n
- Complete devell op1m ent ,a nd t :ie st iin g 1of n e,w 1a dvan11c ed a llll oy w ith s.uperii o r deg1ra datii on reeii sta 1n c e *w it h 1
- Exp,a nded
- Model for
- Predictive ARRIM pa rtn e rs IM ateriials envir oinm e n tallly- capability for end IO e,g rad,a ti10 ,1 n ass i'st,e d fati,g ue i n of useful life for Asse,ssment tWR c ompon e n ts 1 cab le i nsulation
- IM ode,11 fo,1r
- Model! for cab l e 1
- New or improved deg*r ad.a tion NDE technologies for concrete and
Coordination with EPRI and DOE U.S.NRC United Scates Nuclear Regulatory Commission Protecting People and the Environment
- The cooperative program with EPRI LTO ensures the timely exchange of information on planned and ongoing aging management research activities . (MOU until 9/30/2016)
- With the DOE LWRS program, materials related gaps in relation to SLR were identified and documented in NUREG/CR-7153, "Expanded Materials Degradation Assessment, Vol. 1-5,"
2014. This research ranked the significance of aging-related degradation phenomena that could affect reactor system and components during SLR. (MOU until 8/22/2019)
Concrete Aging Material Aging Risk and Safety Equipment Aging GALL Program LTO (NRC)
Digital l&C IGALL (IAEA)
International Experience E r.::5121
,- I"'"'. . .
- 1 "'1(*,HIIIN'I
The Vision: Integrated Aging Degradation U.S.NRC Uni ted Scates Nuclear Regulatory Commission Need/Resource Interrogatory Tool Protecting People and the Environment EPRI LTO Decommissioning Reactors Plans Operating Information Too l fo r Pri oritization of Experience High-Priority Data Strategic Harvesting Needs Oooortu n it ies NRC Data: SLRGDs, Int ernational Dat a Sources DOE LW RS EMDA, PMDA
Stakeholder Engagement U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- IAEA CRP: Evaluation of Structures and Components Material Properties Utilizing Actual Aged Materials Removed from Decommissioned Reactors for Safe LTO.
- Conduct public workshops to further refine the concept of useful database of research objectives for ex-plant materials
- NRC invites collaboration under current EPRI/LTO and DOE/LWRS MOUs.
Acknowledgements U.S.NRC Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- Robert Tregoning, RES/DE
- Eric Focht, RES/DE
- Darrell Murdock, RES/DE
- Mita Sircar, RES/DE
U.S.NRC Acronyms Uni ted Scates Nuclear Regulatory Commission Protecting People and the Environment
- ARRM - advanced radiation resistant
- NAM - neutron absorbing material materials
- NIST - National Institute of Standards
- CG R- crack growth rate & Technology
- CRP - coordinated research project
- NPAR - nuclear plant aging research
{IAEA)
- PMDA- Proactive Materials
- CSN - Spanish regulator Degradation Assessment
- EMDA- expanded materials degradation
- PTS - pressurized thermal shock assessment
- ENRESA- Spanish decommissioning
- SFP-spentfuel pool authority
- FT - fracture toughness
- SLRGDs - subsequent license renewal
- GALL- Generic Aging Lessons Learned guidance documents
- IAD - irradiation-assisted degradation
- SRP-LR standard review plan fo~
- IGALL- international GALL license renewal
- LTO - long-term sustainability
- LWRS - LWR Sustainabi .
From: HJser Matthew To: Tregoning Robert Subject : FW: Revised NRC-NRAJ 2016 Materials Meeting Agenda Date: Thursday, June 23, 2016 12:57:00 PM From: Rao, Appajosula Sent: Thursday, June 23, 2016 12:53 PM To: Hiser, Matthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>
Cc: Frankl, Istvan <lstvan.Frankl@nrc.gov>
Subject:
RE : Revised NRC-NRAJ 2016 Materia ls Meeting Agenda Matt:
You unilaterally decide on actions. If you are the lead and want to present all topics I have no objection. Please do not expect any help in the preparation of the slides or any technical discussion.
Sri From: Hiser, Matthew Sent: Thursday, June 23, 2016 12:28 PM To: Rao, Appajosula <Appa josula Rao@nrc gov>; Purtscher, Patrick <Patrick Purtscher@nrc gov>
Subject:
FW: Revised NRC-NRAJ 2016 Materials Meeting Agenda Hi Guys, Do either of you have a preference on one of these options? I am fine with either ...
- IAD: Sri or Matt
- CASS: Pat or r
- Harvesting: Matt or Pat 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 Ofjice: 1WFN IOD62 Matthew.Hiser@orc.gov From: Tregoning, Robert Sent: Thursday, June 23, 2016 7:13 AM To: Kirk, Mark <Mark.Kirk@nrc.gov>; Murdock, Darrell <Darrell.Murdock@nrc.gov>; Gordon, Matthew <Matthew.Gordon@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>; Hiser, Matthew <Matthew.Hjser@nrc.gov>; Purtscher, Patrick <Pat rjck.Purtscher@nrc.gov>; Sirca r, Madhumita <Madhumjta.Sjrcar@nrc.gov>; Pires, Jose <Jose Pires@nrc.gov>
Cc: Frankl, Istvan <Istvan Frankl@nrc gov>; Rud land, David <David Rud land@nrc gov>; Burke, John
<John.Burke@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>
Subject:
Revised NRC-NRAJ 2016 Materials Meeting Agenda All:
Attached is the revised agenda for the NRC/NRAJ meeting in August. The only change is that the concrete aging and the metals aging portions of the agenda have been swapped so that the first technical topic is concrete. The concrete folks will have additional, more in-depth discussions after the morning of the ath as a side-bar. Please let me know if there are any issues with this revised agenda. I'm still awaiting the following:
- 1. CMB identification of leads for their topics on the agenda.
- 2. NRAJ to identify their speakers for the various topics.
I'll send out a final agenda once 1 and 2 have been completed.
Thanks for your help, Rob
Note to requester: The attachment to this email is From: HJser Matthew To: Rao Appajosula; Purtscher Patrick immediately following .
Subject : FW: Revised NRC-NRAJ 2016 Materials Meeting Agenda Date: Thursday, June 23, 2016 12:28:00 PM Attachments: NRC-NRAJ 2016 Materials Meetina Agenda.doc)(
Hi Guys, Do either of you have a preference on one of these options? I am fine with either ...
- IAD: Sri or Mat~
- CASS: Pat or Sri
- Harvesting: Matt or Pat Thanks!
Matt Matthew Hiser Materials Engineer US Nuclear Regulatory Commission I Office of Nuclear Regula1ory Research Division of Engineering I Corrosion and Metallurgy Branch Phone: JOJ-4 15-2454 1Office: 7WFN IOD62 Matthew Hiser@nrc gov From: Tregoning, Robert Sent: Thursday, June 23, 2016 7:13 AM To: Kirk, Mark <Mark.Kirk@nrc.gov>; M urdock, Darrell <Darrell.M urdock@nrc.gov>; Gordon, M atthew <Matthew.Gordon@nrc.gov>; Rao, Appajosula <Appajosula.Rao@nrc.gov>; Hiser, M atthew <Matthew.Hiser@nrc.gov>; Purtscher, Patrick <Patrick.Purtscher@nrc.gov>; Sircar, Madh umita <Madhumita .Sircar@ nrc.gov>; Pires, Jose <Jose.Pires@nrc.gov>
Cc: Frankl, Istva n <lstvan.Fra nkl@n rc.gov>; Rud land, David <David.Rudland@nrc.gov>; Burke, John
<John.Burke@nrc.gov>; Jung, Ian <lan.Jung@nrc.gov>
Subject:
Revised NRC-NRAJ 2016 Materials Meet ing Agenda All:
Attached is the revised agenda for the NRC/NRAJ meeting in August. The only change is that the concrete aging and the metals aging portions of the agenda have been swapped so that the first technical topic is concrete. The concrete folks will have additional, more in-depth discussions after the morning of the 8111 as a side-bar. Please let me know if there are any issues with this revised agenda. I'm still awaiting the following :
- 1. CMB identification of leads for their topics on the agenda.
- 2. NRAJ to identify their speakers for the various topics.
I'll send out a final agenda once 1 and 2 have been completed.
Thanks for your help, Rob
AGENDA NRC/NRAJ Bilateral Meeting on Materials Issues NRC Headquarters, Rockville, MD, USA August 8 - 9, 2016 Monday, August 8111 , 2016 Location: Room 07-B4 Time Topic Speaker 8:00 am Introductions All 8:05 am Welcome B. Thomas, NRC 8:15 am Opening Remarks R. Tregoning, NRC K. Sakamoto, NRAJ Concrete Aging 8:30 am Radiation Effects on Concrete M. Sircar, NRC Structures M. Nakano, NRAJ 9:15 am NOE for Thick Concrete Sections M. Sircar, NRC M. Nakano, NRAJ 10:00 am Break 10:15 am Monitoring and Aging Management of M. Sircar, NRC ASR Affected Concrete Structures M. Nakano, NRAJ 11:00 am Technical and Regulatory Concerns All 12:00 pm Lunch Cable Aging 1:30 pm NRC Research Activities D. Murdock, NRC 2:30 pm NRAJ Research Activities NRAJ 3:30 pm Break 3:45 pm Technical and Regulatory Concerns All 4:30 pm Adjourn
AGENDA NRC/NRAJ Bilateral Meeting on Materials Issues NRC Headquarters, Rockville, MD, USA August 8 - 9, 2016 Tuesday, August 9 111, 2016 Location: Room 07-B4 Time Topic Speaker Metals Aging 8:00 am RPV embrittlement studies M. Kirk, NRC NRAJ 9:30 am Irradiated Assisted Degradation S. Rao/M. Hiser, NRC NRAJ 10:15 am Break 10:30 am Irradiated Assisted Degrad.ation, cont. S. Rao/M . Hiser, NRC NRAJ 11:00 am Technical and Regulatory Concerns All 12:00 pm Lunch Possible Future Collaboration Areas 1:30 pm Environmentally Assisted Fatigue R. Tregoning, NRC NRAJ 2:00 pm Aging of CASS Rao/Purtscher, NRC NRAJ 2:30 pm Peening J. Collins, NRC NRAJ 3:00 pm Break 3:15 pm Material Harvesting P. Purtscher, NRC NRAJ 3:45 pm Actions and Next Meeting R. Tregoning, NRC K. Sakamoto, NRAJ 4:15 pm Closing Remarks R. Tregoning, NRC K. Sakamoto, NRAJ 4 :30 pm Adjourn