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NRC-2018-000831 - Resp 2 - Interim (RES Workshop Presentations_Rif) Part 10 of 10
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Evaluating Structures, Systems & Components from Decommissioned/Decommissioning Nuclear Facilities in Canada Presented at the Nuclear Regulatory Commission Harvesting Workshop - March 7-8, 2017 Daniel Tello - CNSC Senior Research Officer Désiré Ndomba - CNSC Technical Specialist Karen Huynh - AECL Federal S&T Manager e-Docs #5196600

Outline

Who we are Canadian Nuclear Safety Commission (CNSC)

Atomic Energy of Canada Limited (AECL)

Canadian Harvesting Projects & Sources Nuclear Power Plants and Research Reactors Nuclear Power Demonstration (NPD) Generating Station Gentilly-2 Nuclear Generating Station Nuclear Research Universal (NRU) Reactor

Summary 2

Canadian Nuclear Safety Commission Canadas nuclear regulator for over 70 years

Canadian Nuclear Safety Commission (CNSC):

Established on May 2000 under the Nuclear Safety Control Act (NSCA);

Replaced the Atomic Energy Control Board, which was established in 1946 under the Atomic Energy Control Act;

CNSCs Mission:

Regulate the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; Implement Canadas international commitments on the peaceful use of nuclear energy; Disseminate objective scientific, technical and regulatory information to the public; 3

Atomic Energy of Canada Limited

AECL is a federal Crown corporation responsible for managing Canada's radioactive waste liabilities and enabling nuclear science and technology

AECL delivers their mandate through a contractual arrangement with Canadian National Energy Alliance (CNEA) for the management and operation of Canadian Nuclear Laboratories (CNL) under a Government-owned, Contractor-operated (GoCo) model

AECL oversees the delivery of the Federal Nuclear Science and Technology Work Plan in order to support the Governments priorities and core responsibilities in areas such as nuclear safety, security, energy, health and the environment

CNL is responsible for the management and operation of the Laboratories, and is the licensee with access rights to AECLs assets and Intellectual Property (IP) 4

Harvesting Materials in Canada Why is Harvesting Important?

The nuclear power plants (NPPs) that are currently in operation were generally designed and built with conservative principles, and in many cases have significant remaining safety margins. Typically, NPPs were designed with the intent of operating for up to 30 years. This is now changing to approximately 60 years.

Harvesting materials from decommissioned or decommissioning facilities is intended to assess the remaining safety margins for the physical condition of structures, systems and components (SSCs) in NPPs through testing to verify and/or validate the technical feasibility of Long Term Operation (LTO).

Canadian Harvesting Projects

Canada currently has harvesting projects in 2 areas from different facilities Analysis of Degradation Mechanisms of Cables Understanding Degradation of Concrete 5

Nuclear Power Demonstration Plant (NPD)

The 20 MW Nuclear Power Demonstration Plant (NPD) was Canadas first nuclear power reactor to supply electricity to Ontario Hydros electrical distribution grid

The reactor permanently shutdown in 1988 after 25 years of service CNSC sponsored a research project with Ontario Hydro in 1991 on:

Cable insulation degradation of the 20 MW Nuclear Power Demonstration Plant AECL currently has a research project to analyze concrete samples from NPD 6

Understanding the Degradation of Concrete

Background

This project will address gaps in the domestic knowledge of concrete degradation in nuclear power plants and will support regulatory decisions for long-term reactor operations of domestic utilities and new reactor technologies, such as SMRs.

Project Objective

To assess concrete core samples for degradation Status

Year one of a three year project

Received 7 concrete cores from Nuclear Power Demonstration (NPD) reactor

Identified test techniques to assess for degradation Other opportunities

Concrete from other decommissioned reactors in Canada such as Gentilly-2, Douglas Point and AECLs whiteshell reactor in Pinawa, Manitoba 7

Gentilly-2 Nuclear Power Plant

Gentilly-2 (G2) Nuclear Power Plant (NPP) is a CANDU-6 675 Mwe nuclear reactor which was permanently shutdown in 2012 after 29 years of service CNSC & AECL/CNL are currently conducting a research project on the Analysis of Degradation Mechanisms of Cable Insulation due to Ageing in a Decommissioned Nuclear Power Plant 8

Cable Harvesting Project from G2

Background

Material properties of cables aged in real time and real operating conditions can be significantly different from the properties received by studying samples aged in laboratory and assumed in codes and standards.

Project Objective

Assess current cable degradation resulting from thermal and radiation ageing

Validate environmental qualification work Status

Reviewed environmental conditions and selected cables to be harvested from Hydro Quebec/Gentilly-2 reactor

CNSC & AECL/CNL staff have recently witnessed the removal of cable samples from the G-2 NPP

Samples will be retrieved and tested to improve cable ageing test parameters used to assess cable condition 9

Cable Harvesting Project from G2 (contd)

Challenges

There were several challenges associated with the cable harvesting project at G2:

removal of material samples from a decommissioned NPP is neither a compliance nor licensing activity for licensees; accessibility of analysis and testing records (data, samples, etc.)

inaccessibility or contamination of materials to be removed cost related to carry out research activity on these materials.

10

National Research Universal (NRU) Reactor

NRU is a 135MWt nuclear research reactor built in the Chalk River Laboratories, Ontario with first criticality achieved on November 3, 1957.

The NRU reactor has three purposes Supplier of industrial and medical radioisotopes used for the diagnosis and treatment of life-threatening diseases; A major Canadian facility for neutron physics research; and Research and development support for CANDU power reactors.

After 5 decades of service, the NRU reactor will shut down permanently in March 2018, after ~270k hours operation.

The NRU reactor contains a vast array of materials and components including structural materials (such as steels and other nickel bearing alloys, zirconium alloys, aluminum, concrete) and welded joints a thermal graphite column equipment (including pumps) graphite seals electrical cables thermocouples o 304 SS, ~1.6 dpa, 35 C,

~3.4x1026 n/m2 (E<0.625 eV) 11

Harvest Material from National Research Universal (NRU) Reactor Project Objective

Create an inventory of irradiated materials which can be harvested from the decommissioned NRU reactor

The inventory will be used to assess irradiation damage on the performance of in-core materials and components Advantages of Harvesting Materials from NRU

Assess the effects of irradiation on the performance and degradation of a variety of materials; wide range of temperature, flux and neutron spectrum irradiation times on the order of power reactor lifetimes the combination of operating conditions and exposure is not always easily or economically obtainable in test programs

Collaborate with various partners throughout the international nuclear industry who also wish to characterize the effects of irradiation on materials

Provide information to decommissioning groups interested in the radionuclide inventory of the decommissioned reactor.

Status 12

One year project that will start on April 1, 2017

Summary

Understanding ageing degradation is an important aspect to ensure nuclear safety as nuclear power plants age

R&D behind SSC material life management is needed to ensure the safe and reliable operation of NPPs

Several nuclear facilities in Canada exist for potential harvesting of Structures, Systems & Components. Examples include:

Nuclear Power Demonstration (NPD) Facility Gentilly-2 (G2)

National Research Universal Reactor (NRU)

Douglas Point AECLs Whiteshell Reactor 13

Contacts Daniel Tello Désiré Ndomba Senior Research Officer Technical Specialist E-mail: daniel.tello@canada.ca E-mail: desire.ndomba@canada.ca Karen Huynh Federal S&T Manager Email: khuynh@aecl.ca Gina Strati Lori Walters Director - Energy Sr Mechanical R&D Email: gina.strati@cnl.ca Email: lori.walters@cnl.ca 14

Questions Thank you!

15

Kori-1 Harvesting Plan for Materials Aging Degradation Research Al Ahluwalia (EPRI) for Han-sub Chung (KHNP)

March 7-8, 2017 KHNP-Central Research KHNP-CRI Institute

Contents

1. Background

2. Research planning using materials from retired Kori-1

3. Future Plans KHNP-CRI

1. BACKGROUND KHNP-CRI

KHNP PWRs and Kori-1 Kori-1 is a Westinghouse two loop PWR SG replaced in 1998, RV head replaced in 2015 Kori-1 will be shutdown on 2017.6.18 (30 year original design life + 10 year extended life)

Seven additional PWRs complete their original 40-year design lives beginning 2023, nearly one plant each year KHNP intends to seek license renewals but it will be a challenging task due to public concern for safety KHNP is planning a comprehensive research program on long-term materials aging degradation KHNP-CRI

Schedule of decommissioning Kori-1 (tentative)

Submission of a KHNP decommissioning plan (2020.6.)

Approval procedures including public hearings Final approval of the decommissioning plan (2022.6.)

Completion of the cutting and dismantling (2024.12.)

KHNP-CRI

2. RESEARCH PLANNING USING MATERIALS FROM RETIRED KORI-1 KHNP-CRI

Planning sub committees (2016.1.~4.)

classification Chair/secretary Members Neutron irradiation embrittlement BS Lee(KAERI)/

of RPV JS Yang(CRI)

SS Hwang(KAERI)/

Reactor internals JS Yang(CRI) 5~10 members each group SCC of Alloy 600 weld nozzles and HP Kim(KAERI)/

from relevant organizations penetrations (CRDM, BMN, DMW) HD Kim(CRI)

(KAERI, KPS, KEPCO-E&C, HP Kim(KAERI)/

Steam generators DHIC, KAIST, and a few HD Kim(CRI) universities)

CH Jang(KAIST)/

Thermal embrittlement MW Kim(CRI)

DJ Kim(KAERI)/

FAC & buried pipes SK Park(CRI)

KHNP-CRI

12 tasks proposed at the subcommittees

1. Irradiation Embrittlement of the Reactor Pressure Vessel Beltline Material

2. Irradiation Embrittlement of RPV Nozzle steel

3. Investigation of the IASCC mechanism

4. Material properties of aged RVI components

5. Residual stress and susceptibility to PWSCC of Alloy 600 welds and penetrations

6. Residual stress and susceptibility to PWSCC of Alloy 690 CRDM penetration nozzles

7. Degradations of steam generator

8. Thermal embrittlement in cast and weld austenitic stainless steel

9. FEM integrity assessment and actual test of a bend portion in an aged real plant pipe

10. Thermal embrittlement of low alloy steel and its weld exposed to PZR temperature

11. FAC and erosion in CS piping in the secondary system and BOP

12. Degradations in buried pipes and inspection performance demonstration KHNP-CRI

Course of test materials and specimens Specimens Radioactive KHNP Maintenance Materials Building at KORI Station (RV, Internals, Pipe)

(Decontamination and Machining)

KAERI CRI Hot lab Platform at KORI-1 (Cutting, Decontamination)

EPRI &

others Non-Radioactive Materials KAERI, CRI (Piping, Structures) colleges KHNP-CRI

KHNP maintenance building in Kori station RCP maintenance facilities Separate rooms Old original Kori-1 RV head KHNP-CRI

Current Activities Input of research plan to KHNP decommissioning plan by 2017.12 Planning of improving KHNP facilities for handling irradiated materials (2016.5.~2018.4.)

KHNP maintenance building in Kori station CRI materials test building Improvement of KAERI Irradiated Materials Evaluation Facility KAERI IMEF is overcrowded An EPRI project Analytical assessment of residual stress in a few selected dissimilar metal nozzles in Kori-1 KHNP-CRI

3. FUTURE PLAN KHNP-CRI

Project Schedule (draft)

Phases Description Improvement of KHNP and KAERI facilities Decontamination, movement, machining, and storage of Phase One test materials (2020~2024)

Preliminary analytical studies

- irradiation dose, residual stress, and others Phase Two Test and evaluation (2024~2030)

Phase Three Remaining tasks after completion of Phase Two (2031~, - additional irradiation test, international collaboration, as needed) and others KHNP-CRI

Others Planning of specific projects among Korean organizations Planning of international collaboration via EPRI KHNP-CRI

KHNP-CRI Ex-Plant Harvesting Workshop Session 1 EPRI Perspective Sherry Bernhoft Senior Program Manager NRC Ex-Plant Harvesting Workshop March 7 & 8, 2017

Nuclear Sector Research Areas RISK EQUIPMENT RELIABILITY AND SAFETY NONDESTRUCTIVE LONG-TERM EVALUATION OPERATIONS CHEMISTRY AND RADIATION USED FUEL SAFETY AND HIGH-LEVEL WASTE ADVANCED MANAGEMENT NUCLEAR TECHNOLOGY MATERIAL FUEL DEGRADATION RELIABILITY 2

EPRIs Global Membership GLOBAL PARTICIPANTS GLOBAL BREADTH & DEPTH

>75%

>320 reactors worldwide of the worlds commercial nuclear units Participants Encompass Most Nuclear Reactor Designs 3

EPRI Collaborative Model Suppliers, Vendors Collaborative Technology Basic Inputs Development, Research and Integration, Development and Application National Laboratories, Solutions Universities EPRI Nuclear Utilities 4

LTO Research Focus is on Aging Management

1. Reactor pressure vessel

2. Primary system metals, welds, and piping

3. Electrical cables

4. Concrete and containment structures High Priority 5

Experience With Harvesting Takes longer and cost more than anticipated Incomplete knowledge on the pedigree of the harvested materials Roles and responsibilities not well defined Contracting is complicated Logistics, i.e. transportation and storage are challenging You can spend a lot of money and not get any value 6

EPRIs Criteria for Harvesting Needs to be of value for our members Is prioritized as a need by our members Fills a knowledge gap that can not otherwise be filled Needs to start with a well developed project plan including:

- Funding

- Risk Management plan

- Exit Ramps

- Clear roles and responsibilities 7

TogetherShaping the Future of Electricity 8

Plants in Decommissioning in Germany Uwe Jendrich, GRS March 7, 2017 Ex-Plant Materials Harvesting Workshop US NRC Headquarter, Rockville/MD, USA

Basic Requirements for Decommissioning Regulation of decommissioning in Germany Granting of 1st Final shut down of the decommissioning facility license Power Operation Post operation transition period Decommissioning phase/

Direct dismantling or Safe enclosure Operation Decommissioning NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 2

The German Regulatory System Basic requirements

For a nuclear facility the atomic energy act allows either to immediate dismantle or to dismantle after a safe enclosure Note: no entombment (near surface disposal) is allowed

The operator of a nuclear facility is fully responsible for the decommissioning and dismantling of a nuclear facility.

For any requests on materials: Contact the operator!

There are 4 operators of commercial nuclear reactors in Germany:

1. PreussenElektra1) (KKS, KKI, KKU, KWG, KKG, KBR, KKE)

2. EnBW2) (KWO, GKN, KKP)

3. RWE (KMK, KRB, KWB)

4. Vattenvall (KKB, KKK)

1) until recently known as E.ON Kernkraft

2) Energie Baden-Württemberg NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 3

Overview on Decommissioning Projects in Gemany Past and current decommissioning projects of Prototype or Commercial Reactors Name Abbrev. Reactor type Power Decom. Strategy MWe started Rheinsberg KKR WWER 70 1995 UC Compact Natrium Cooled KKN SNR 21 1993 UC Reactor Multipurpose Research R. MZFR PWR/D2O 57 1987 UC Obrigheim KWO PWR 357 2008 UC Neckarwestheim 1 GKN-1 PWR 840 2017 UC Isar-1 KKI-1 BWR 912 2017 UC Gundremmingen-A KRB-A BWR 250 1983 RCA KRB-II Greifswald 1-5 KGR 1-5 WWER 440 1995 UC Lingen KWL BWR 268 1985 UC after SE UC: unconditional clearance RCA: radiation controlled area, new license SE: safe enclosure NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 4

Overview on Decommissioning Projects in Gemany Past and current decommissioning projects of Prototype or Commercial Reactors Name Abbrev. Reactor type Power Decom. Strategy MWe started Stade KKS PWR 672 2005 UC Research Reactor Jülich AVR HTR 15 1994 UC Thorium High- THTR- HTR 308 1993 SE since 1997 Temperature-Reaktor 300 Würgassen KWW BWR 670 1997 UC Mülheim-Krlich KMK PWR 1302 2004 UC Hot-Steam Reactor HDR HDR 25 1983 UC since 1998 Grosswelzheim Niederaichbach KKN DRR/D2O 106 1975 UC since 1994 Test-Reactor Kahl VAK BWR 16 1988 UC since 2010 UC: unconditional clearance NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany SE: safe enclosure 5

NPPs Preparing for Decommissioning in Gemany Shut down Commercial Reactors

that have no decommissioning license granted yet Name Abbrev. Reactor type Power MWe Date of application Philippsburg-1 KKP-1 BWR 926 2013 / 2014 Grafenrheinfeld KKG PWR 1345 2014 Biblis-A KWB-A PWR 1225 2012 Biblis-B KWB-B PWR 1300 2012 Unterweser KKU BWR 1410 2012 / 2013 Brunsbüttel KKB BWR 806 2012 / 2014 Krümmel KKK BWR 1402 2015 RPV design fluence after 40 years

< 5

1018 n/cm² NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 6

NPPs Preparing for Decommissioning in Gemany Commercial Reactors in operation Name Abbrev. Reactor type Power MWe Anticipated date of final shutdown Gundremmingen-B KRB-II-B BWR 1344 31.12.2017 Philippsburg-2 KKP-2 PWR 1468 31.12.2019 Gundremmingen-C KRB-II-C BWR 1344 31.12.2021 Grohnde KWG PWR 1430 31.12.2021 Brokdorf KBR PWR 1480 31.12.2021 Emsland KKE PWR 1406 31.12.2022 Isar-2 KKI-2 PWR 1485 31.12.2022 Neckarwestheim-2 GKN-2 PWR 1400 31.12.2022 NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 7

Overview on Decommissioning Projects in Gemany Past and current decommissioning projects of Research Reactors

Total: 35

Removed: 29 Nuclear Ship Otto Hahn

Final Shut down / under dismantling: 4 during operation

Safe

Enclosure:

2

Variety of types of Research Reactors Argonaut type Critical assembly Rad. transport of Educational reactors dismantled pressure vessel Liquid homogenous reactor

Heavy Water reactor (incl. DIDO type)

NRC Harvesting Workshop, Rockville, March 2017, Decommissioning in Germany 8

Overview on Decommissioning Projects in Gemany Past and current decommissioning projects of Prototype or Commercial Reactors

Total: 21 HDR Growelzheim

Removed: 3

Final shut down / under dismantling: 17

Safe enclosure: 1

Reactor types:

PWR BWR Fast Breeder High Temperature Gas Cooled Heavy Water Gas Cooled

Thank you for your attention!

Role of GRS in Decommissioning and LTO Uwe Jendrich, GRS March 7, 2017 Ex-Plant Materials Harvesting Workshop US NRC Headquarter, Rockville/MD, USA

Introduction GRS with its staff of about 430 is Main Technical Support Organization (TSO) in nuclear safety for the German federal government

BMUB (Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety),

BMBF (Federal Ministry of Education and Research),

BMWi (Federal Ministry of Economic Affairs and Energy) and

AA (Federal Ministry of Foreign Affairs) and GRS participates in international activities of

IAEA, OECD, EU (DG Energy, DG RTD, DG DevCo),

NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 2

Services of GRS in Decommissioning of Nuclear Installations

Advice and assessment concrete technical and legal issues strategy and planning of decommissioning projects

Project management, progress monitoring and documentation of decommissioning projects

Support in the drafting of regulations taking into account national specifics

Know-how transfer individually tailored seminars and coaching elaborations on specific issues NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 3

GRS Customers and References in Decommissioning BMUB:

Various projects (since 1998):

technical and organizational requirements analysis of technical aspects, assessment of application and licensing documents BMBF:

Project management (since 2013):

Decommissioning, dismantling and waste management projects relating to nuclear test facilities IAEA:

Decommissioning and Remediation of Damaged Nuclear Facilities (DAROD) (since 2015)

Decommissioning Risk Management (DiRiMa) (since 2012)

Constraints to implementing decommissioning and environmental remediation programs (CIDER) (2013-2015)

EBRD:

Assistance to Bulgaria Nuclear Regulatory Agency (BNRA) decommissioning of Kozloduy NPP units 1-4 (since 2008)

NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 4

GRS Activities in Ageing Management and Long Term Operation BMUB:

Evaluation of nat. & internat. operating experience

Nat. & internat. Regulations and Guidelines on AM EU:

Several INSC projects on Regulatory aspects of LTO, Specific technical aspects

JRC Database EMAR (R&D results on ageing of materials)

IAEA:

International IGALL OECD/NEA:

Database projects CODAP (components), CADAK (cable)

WG IAGE, NUGENIA ANVS (NL):

Assessment of licensing documents for LTO of Borssele NRC Harvesting Workshop, Rockville, March 2017, Role of GRS 5

ENERGYSOLUTIONS Future Harvesting Opportunities at Decommissioning Power Plants Gerry van Noordennen March 7, 2017

Successful Harvesting Opportunities Require Clear Scope and Schedule ENERGYSOLUTIONS

Plant View

- There is no financial incentive to support harvesting

- The research agency must be willing to pay for the costs to surgically remove components

- The research agency must provide a clear scope and schedule at the beginning of the active decommissioning period (DECON)

- Delays in federal approvals mean lost opportunities 2

Flexibility is Key ENERGYSOLUTIONS

Flexibility in the removal schedule is key

- Schedule changes result in components becoming available on short notice

- The research agency must have the funds set aside from one year to the next or miss out on harvesting opportunities 3

Future Opportunities ENERGYSOLUTIONS

Reactor vessel surveillance coupons

- Best removed when work begins on cutting up reactor internals

Reactor vessel weld specimens

- Only applicable for large vessels

- Smaller vessels like SONGS 1 and Ft. Calhoun shipped intact to disposal facility Reactor Vessel Cutting Head 4

Future Opportunities ENERGYSOLUTIONS

Spent fuel rack coupons

- Best removed before or after spent fuel transferred to the ISFSI

- Cannot not interfere with fuel characterization or fuel transfer

Spent fuel rack

- Removed after pool completely empty including GTCC waste

Cabling from Harsh Environments

- Some can be harvested at any time

- High rad environment requires timing of harvest to mesh with source term removal schedule in each area 5

Future Opportunities ENERGYSOLUTIONS

Switchgear, Bus Ducts, Control Panels, Breakers

- Some can be harvested at any time

- Specify cable lengths needed

- High rad environment requires timing of harvest to mesh with source term removal in area

Concrete Cores

- Cores best taken consistent with site characterization needs for License Termination Plan 6

Harvesting Plans Needed Now ENERGYSOLUTIONS

Plants that are entering DECON in the next 2 years need to know now if the NRC or DOE are interested in harvesting materials at these sites:

- San Onofre 2 & 3 (January 2018)

- Vermont Yankee (2019)

Plants potentially entering DECON in the next 2 years should be contacted now:

- Kewaunee

- Crystal River

- Ft. Calhoun 7

ENERGYSOLUTIONS Zion Harvesting Experience and Lessons Learned Gerry van Noordennen March 8, 2017

Zion Nuclear Power Station ZIONSOLUTIONS An EnergySoluitons Company LLC 2

ZIONSOLUTIONS An EnergySoluitons Company LLC Two 4-Loop Westinghouse PWR 3250MWt (1085 MWe)

Construction permit December 1968

Operating Licenses April 1973 (Unit1)

November 1973 (Unit 2)

Shutdown (unexpected) February 1998

Permanently Defueled March 1998

License transferred to EnergySolutions September 2010

All Spent Fuel in Dry Storage January 2015

Expected Completion April 2019 3

Decommissioning Progress ZIONSOLUTIONS An EnergySoluitons Company LLC

Plant Decommissioning is on schedule and on budget

Currently demolishing Auxiliary Building

Containment buildings ready for open air demolition in May 2017

Complete building demolition by early 2018

Show demolition video 4

Scope ENERGYSOLUTIONS

Zion Harvesting Program Experience

- Extensive harvesting conducted from 2011 to 2016

- Senior management supportive of program

- Reassignment of plant personnel to support harvesting program

- Demolition organization generally not supportive but tolerated surgical removal of components

- Demolition did not stop for harvesting

- Harvested items only have scrap value 5

Items Harvested ENERGYSOLUTIONS

Reactor Vessel Material Surveillance Capsules

- Capsules were removed during reactor internals cutting and stored on the reactor cavity floor

- Capsule designators were very hard to read

- Only one capsule had research value (X)

- Zion attempt to identify capsule markings failed

- Capsule X ended up being disposed of by the time contract issues were worked out with Westinghouse to retrieve capsule

- Result: All capsules disposed as radwaste 6

Reactor Vessel Weld ENERGYSOLUTIONS

Reactor vessel beltline weld

- Reactor vessels cannot be rotated in cutting machine

- Vessel cutting plan looked like it would work for vessel specimen harvesting plan

- Unit 2 beltline weld was too close to cut line so torch could have affected metal properties

- Unit 1 cut line was far enough away from weld to obtain a successful specimen 7

Safety-Related Cabling ENERGYSOLUTIONS Cabling harvested from Unit 1 (11 Tasks)

1. East Valve House near Steam Tunnel

2. Instrument cabling inside missile barrier

3. Loop Isolation Valve cabling

4. Accumulator discharge valve MOV cabling

5. Instrument Rack cabling in containment

6. Air-operated valve cabling

7. Electrical penetrations assembly and cables

8. Electrical penetration cabling in Aux Bldg.

9. Pressurizer heater cables

10. Cables in steam tunnel

11. Submerged cable in Turbine Bldg. to Crib House 8

Safety-Related Cabling ENERGYSOLUTIONS Experience

Only some of the cables harvested.

- Changing priorities

- Demolition crew not cognizant of research needs

Cable lengths of 30 feet were difficult to obtain in some instances. Could only get 10 feet.

Cable type, age and environment were generally available from plant records 9

Fire Testing Program ENERGYSOLUTIONS

Bus bar section ( 8 feet) removed along with any remaining support hardware and isolators

480-volt distribution center removed

480-volt motor control center removed

Control Room Control Panel removed

Instrument Rack removed in Aux. Bldg..

4KV Switchgear, Relays and Breakers removed

ISO-Phase Bus Duct removed 10

Concrete Core Bores ENERGYSOLUTIONS

Planned to take core bores in containment and under spent fuel pool liner

Task cancelled by ORNL 11

Spent Fuel Pool Storage Racks ENERGYSOLUTIONS

Spent Fuel Pool Testing completed for boron degradation

Remaining coupons retrieved

Storage rack piece cut and shipped

Good onsite coordination with EPRI and NRC

Most work completed during weekend 12

Lessons Learned ENERGYSOLUTIONS

Changing scope leads to frustration on both sides

Delays in paper work for each task authorization lead to lost opportunities

Plan early

Obtain senior plant management support

Have someone on site when harvesting takes place

Be able to deal with changing plant support personnel 13

US Nuclear Science User Facilities (NSUF)

Overview J. Rory Kennedy, Ph.D.

Director, NSUF Idaho National Laboratory March , 2017

NSUF General Established 2007 as DOE Office of Nuclear Energy first and only user facility

Idaho National Laboratory is lead institution

Irradiation effects in nuclear fuels and materials

Provide access to capabilities and expertise at no cost to user

Support design, fabrication, transport, irradiation, PIE, disposition

Link intellectual capital with nuclear research infrastructure to fulfill mission of DOE-NE Generally select projects through open competitive proposal processes

Consolidated Innovative Nuclear Research (CINR FOA, 1 call/year)

Irradiation + PIE ($1.0M - $4.0M, up to 7 years)

PIE only (~$500K, up to 3 years)

Irradiation only ($500K - $3.5M)

Beamlines at other user facilities

Rapid Turnaround Experiments (RTE, 3 calls/year, limited $$, executed within 9 months)

Proposals welcome from University, National Laboratory, Industry, Small Business, Intl researchers 22

NSUF - A consortium A group formed to undertake an enterprise beyond the resources of any one member Expanded capabilities Need for additional capabilities Partner Facilities to date outside INL 8 Universities + 3 Universities in CAES recognized (3 currently expressed interest) early 4 National Laboratories (4 expressed Partner interest) facilities 1 Industrial program established in 2008 3

NSUF General Capabilities Neutron Irradiations

ATR (loop, rabbit), ATRC, HFIR (rabbit), MITR (loop), PULSTAR, NRAD (Future: BR2 - SCK-CEN Belgium), Halden - Norway ?)

Ion Irradiations

Tandem Accelerator Ion Beam (U. Wisc), Michigan Ion Beam Lab (U. Mich), IVEM (ANL)

(Future: TAMU, SNL, LANL)

Hot Cells

INL(HFEF, FCF, AL, IASCC), ORNL (IFEL, IMET, REDC), PNNL (RPL), U. Mich (IMC),

Westinghouse (MCOE)

High radiation level measurements/instrumentation

Neutron radiography, elemental & isotopic analyses, gas sampling and analyses, profilometry, gamma scanning, mechanical testing, electron and optical microscopy, thermal analyses, eddy current, IASCC, EPMA, AES, XPS, SIMS, focused ion beam (FIB)

Low radiation level measurements/instrumentation

SEM, TEM, APT, FIB, hardness, micro- & nano-indentation, tensile, thermal analyses, XRD, XPS, AES, SIMS, NMR, PAS Beamlines

X-ray (ANL APS: MRCAT, IIT; BNL NSLS-II: XPD, NST Dept)

Neutron, positron (PULSTAR, NCSU)

High Performance Computing

FALCON machine

Moose-Bison-Marmot Visit nsuf.inl.gov under Research Capabilities tab for details at individual facilities 4

NSUF and GAIN Gateway for Accelerated Innovation in Nuclear (GAIN)

R&D TEST BED Rapid and cost-effective for 1st time cost advancement of scientific underpinning and retirement Investment Levels ($M) 1000 of technical and licensing risk for innovative technologies.

100 DEMO PLATFORM Reduce the commercialization cost and associated risk by minimizing one-time costs. Reduce the cost uncertainty for commercial units.

10 1 2 3 4 5 6 7 8 9 Proof-of-Concept Proof-of-Performance Proof-of-Operations Technology Readiness Levels (TRL) 5

High Impact Nuclear R&D Project portfolio spans a variety of research objectives that are ultimately focused on both near and long-term technology development goals Understanding atomic level phenomena in fuels that affect thermal transport, elemental migration/diffusion, interface interaction, etc. as complex microstructures develop under irradiation

ceramic, metallic, TRISO, ATF Understanding fundamental defect evolution in irradiated structural materials across multiple length scales as they affect mechanical properties.

RPV, austenitic, F/M, Zr alloys, ATF Development of innovative radiation resistant materials for advanced reactor systems Development of radiation resistant sensors for collecting high fidelity on-line irradiation test data Development of materials from advanced manufacturing techniques Providing fundamental actinide nuclear data that can help inform advanced reactor and fuel cycle modeling and simulation campaign. J. Cole contributed to content of 6

Infrastructure Management Program NSUF created a searchable and interactive database of all pertinent infrastructure supported by, or related to, the DOE Office of Nuclear Energy (DOE-NE).

Database known as the Nuclear Energy Infrastructure Database (NEID) and is located at nsuf-infrastructure.inl.gov (public launch Nov 2015)

Used for analyses to identify needs, redundancies, efficiencies, distributions, etc., to best understand the utility of DOE-NEs available infrastructure, inform the content of infrastructure calls, and provide information to NSUF users.

Infrastructure information collected can be combined with information on R&D needs as part of infrastructure gap analysis 7

Nuclear Fuels and Materials Library (NFML)

Provides irradiated samples for users to access for experimentation through one of the competitively reviewed proposal processes.

Critical to reducing costs and taking advantage of new ideas and future analysis techniques and equipment.

The library includes over 3500 specimens as part of the NSUF awarded research. 6K - 7K additional specimens by year end.

INL Most materials in NFML neutron irradiated with small number Legacy materials ion irradiated.

SAM irradiation series to stock library moving forward Effort to consolidate materials into easily accessible locations to reduce costs of Volunteered retrieval. materials from outside Web-based searchable database through the INL nsuf.inl.gov (public launch Sept 14, 2016).

Interest in collaboration on international efforts.

Materials Include:

Supporting

Steels

Pure materials documentation related to

Other alloys

Actinides samples

Ceramics

Fission products 8

Databases Design SME DATABASE PI Name PROJECT DATABASE Subject Matter PROJECT NAME INSTITUTION Project ID Start Date Project Type NEID DATABASE Proposal End Date Material Type INSTITUTION CINR # PI Name Research Area FACILITY RTE # Tech Lead INSTITUTION REACTOR NSUF Call Facility Tech Lead FACILITY Award Date Collaborators Related Documents REACTOR POSITION PROJECT NAME SAMPLE LIBRARY REACTOR REACTOR POSITION Sample ID Code # of Samples PLANNED AS RUN Capsule Samples Remaining Temperature Temperature Packet Specimen Availability Dose (DPA) Actual Dose (DPA)

Material Code Availability Date Fluence [x1020] Fluence [x1020]

Material Name Certification Material Description Certification Code Flux [x1014 ] Flux [x1014 ]

KGT # Storage FACILITY Environment Environment Specimen Type Notes Dimensions 9

10 Kewaunee Power Station Insights on Material Harvesting 1

Kewaunee Power Station 2

Kewaunee Power Station 3

Kewaunee Power Station 2-Loop Westinghouse PWR (590MWe)

Construction permit August 1968 Operating license December 1973 Initial operating license expiration December 2013 Renewed Operating License Issued February 2011 Shutdown decision (unexpected) October 2012 Permanently Shutdown May 2013 ERO offsite response eliminated November 2014 All nuclear fuel in dry storage July 2017 4

Kewaunee Perspective Top priority for decommissioning plants is preserving and good stewardship of the decommissioning trust fund Highest fund drain is staffing Station electrical use also expensive Initial decommissioning actions focus on safety and cost reduction.

Use initial required large staff to prepare plant for long term dormancy and decommissioning Abandon or downsize equipment to reduce ongoing costs.

Then reduce staff commensurate with reduction in risk 5

Kewaunee Power Station Kewaunee Decommissioning Staffing Reductions 700 600 630 500 400 300 300 200 163 147 100 50 0

4/1/2012 8/14/2013 12/27/2014 5/10/2016 9/22/2017 2/4/2019 6

Kewaunee Perspective Timing is everything!

Perhaps best discussed via an example:

Reactor vessel surveillance capsules Two remain in the vessel Logistical considerations:

7

Kewaunee Perspective Circulating Water pumps were high energy consumers Therefore we wanted to retire them as soon as possible Circulating Water pumps were high capacity, low head, very good at dilution for meeting ODCM requirement for radiological discharges Without CW pumps, much smaller capacity service water pumps will be used in the future for dilution..

8

Kewaunee Perspective Therefore - prior to retiring CW pumps, we processed as much radioactive water as possible This included draining the RCS RCS at Kewaunee has no loop isolation valves RCS today is drained to the bottom of the cold legs, about 7 feet below the RV flange RV internals are installed, RV head is on the vessel, flux thimbles are installed in the vessel 9

Kewaunee Perspective So if we wanted to remove surveillance capsules today we would face unique challenges that would not have been present at initial plant shutdown:

Shielding - need to refill the RV (and cavity?)

Lifting the RV head and internals - polar crane is in place, but maintenance has been discontinued Qualified staff - Crane operators, RP technicians, maintenance, operators Rad monitors (many have been abandoned)

Ventilation and atmosphere control, lighting 10

Kewaunee Perspective What generic issues could be resolved or simplified by harvesting and additional testing?

GALL aging management program examples Electrical cables and connections - test power cables taken from adverse localized environments SG divider plates; autogenous welds Buried piping; Inaccessible power cables (buried; underground) 11

Additional Considerations Who will pay?

Why is the material needed?

Whats in it for me?

Are we solving an industry problem? (example -

SFP neutron absorbing material GL 2016-01)

Objectively needing more information to determine if we have a new problem?

Whats the plan? What is done with the information gathered? Is there a driver to review impact on existing programs?

12

Additional Considerations Need to think ahead, plan ahead Some harvesting is very plant condition specific, others maybe not What plants will be entering decommissioning in the future?

Have you reached out to them?

Scope, Schedule, Budget 13

Kewaunee Perspective 14

federaal agentschap voor nucleaire controle agence fédérale de contrle nucléaire Review of Past Reactor Pressure Vessels Test Programs and Perspective for Long Term Operation Rachid Chaouadi 1, François Henry 2, and Guy Roussel 3 1 SCK*CEN Mol, 2 FANC/AFCN Brussels, 3 Bel-V Brussels (Belgium)

Outline Part I : Past test programs analysis Focus on RPV materials (excl. stainless steel cladding, internals, vessel concrete containment, )

Literature survey of test programs on decommissioned RPVs 2 PWRs + 2 VVER-440 + 1 PWR and 1 Magnox gas-cooled reactor Brief description of main outcome and limitations Part II : Discussion (assuming that we are convinced of the benefits of such a test program via vessel sampling)

Overview of Investigated RPVs type (electrical sampling/

reactor location start shutdown power) testing BR3 (YR) Belgium PWR (11 MWe) 1963 1987 ~1995-1999 Chooz-A France PWR (305 MWe) 1967 1991 ~1995-1999 1974 Greifswald-1 to 4 Germany VVER-440 (408 MWe) 1990 ~2004-2012

-1979 Novovoronesh-1 Russia VVER-440 (408 MWe) 1964 1984 ~1993-2000 Gundremmingen-A Germany BWR (237 MWe) 1966 1977 ~1988-1992 Trawsfynydd UK Magnox (195 MWe) 1965 1991 ~1996-2002 PWR (BR3 and Chooz-A)

VVER-440 (Greifswald and Novovoronesh)

BWR (Gundremmingen)

Overview of Investigated RPVs max Tirrad composition reactor condition materials (1019 n/cm², data sets

(°C) Cu/Ni/P (%)

E>1MeV)

Ni-mod BR3 (PWR) IAR 260 4 0.2/0.6/0.02 single A302B multiple 1.2MD07 Chooz-A (PWR) I 255-265 2 0.1/0.6/0.02 through (A336) thickness multiple Greifswald-1 to 4* I, IA, 255 10KhMFT 2 0.15/0.3/0.04 through (VVER-440) IAR, IARA thickness Novovoronesh-1 250 I, IA 15Kh2MFA 1.4 0.15/0.1/0.03 single (VVER-440) (228) multiple Gundremmingen- 20NiMoCr26 I 284-288 0.3 0.2/0.5/0.01 through A (BWR) (A 336) thickness Trawsfynydd manual (Magnox-gas I 190 0.2 0.26/0.1/0.04 mixture SA weld cooled)

Legend : I = as-irradiated ; IA = I + annealing ; IAR = IA + re-irradiation ; IARA = IAR + annealing

Overview of Investigated RPVs test reactor Cu Ni P (T, CVN, FT)

BM 0.19 0.56 0.02 T, CVN, FT BR3 (YR)

Weld -- -- -- --

BM 0.08-0.10 0.59-0.61 0.010-0.015 T, CVN, FT Chooz-A Weld 0.08-0.09 0.13-0.21 0.010-0.016 FT BM 0.13 0.18 0.01 CVN, FT Greifswald-1 to 4 Weld 0.12-0.18 0.19-0.29 0.032-0.036 CVN, FT BM 0.15 0.13 0.015 --

Novovoronesh-1 Weld 0.12 0.12 0.033 CVN BM 0.16 0.74 0.013 T, CVN Gundremmingen-A Weld 0.24 0.11 0.009 CVN BM -- -- -- --

BR3 (PWR)

Conservative regulatory RPV integrity assessment due to Ni-content, temperature and grain size.

Actual embrittlement conditions are less than predicted after comparison with other surrogate materials and direct measurements of fracture toughness on the vessel material.

Chooz-A (PWR)

Source :

ASTM STP 1405 (2001) 28-41.

Chooz-A Weld unirradiated KIc Demonstration of the validity of the surveillance program for the base metal.

Fracture toughness data on the weld metal were all well bounded by the fracture toughness lower bound curve established in the unirradiated condition (KIc based on RTNDT).

Greifswald (VVER-440)

Novovoronech-1 (VVER-440)

Non-uniform through wall distribution of P-content in the weld.

Large scatter in embrittlement based on Charpy impact transition temperature T47J.

Less scatter when master curve T0 is used.

No comparison to surveillance data.

Gundremmingen-A (BWR)

Significant effect of specimen orientation (T-L versus L-T) on T41J and USE.

Effect of specimen orientation.

Significant effect of specimen location in the base metal.

Uniform through wall chemical composition of the weld.

Trawsfynydd (Magnox)

Uniform chemical composition (through wall)

Good agreement with surveillance data Allowed the demonstration of the safety integrity approach followed for this type of reactors.

Outcome reactor outcome Conservative regulatory RPV integrity assessment due to Ni-content, temperature and grain size. Actual embrittlement conditions are less than predicted after comparison BR3 (PWR) with other surrogate materials and measurements of fracture toughness on the vessel material.

Demonstration of the validity of the surveillance program of the base metal. Fracture Chooz-A (PWR) toughness data on the weld metal were all bounded by the fracture toughness lower bound established in the unirradiated condition.

Uniform chemical composition of the weld through the wall thickness except at the weld Greifswald-1 to 4 root but large scatter in the transition temperatures without correlation to the neutron (VVER-440) exposure. Scatter attributed to local microstructure (coarse versus fine). Annealing at 475°C/152h allows an effective recovery. No comparison to surveillance data.

Non-uniform through wall distribution of P-content in the weld. Large scatter in Novovoronesh-1 embrittlement based on Charpy impact transition temperature T47J. Less scatter when (VVER-440) master curve T0 is used. No comparison to surveillance data. Post-irradiation annealing was also investigated and showed that 600°C/2h leads to an effective recovery.

Significant effect of specimen orientation (T-L versus L-T) on the transition temperature Gundremmingen-A T41J and upper shelf energy. Effect of specimen orientation complicated the comparison (BWR) to surveillance data. A significant effect of specimen location was observed for the base metal. Uniform through wall chemical composition of the weld.

Trawsfynydd Good agreement with surveillance data. Allowed the demonstration of the safety (Magnox-gas integrity approach followed for this type of reactors.

Limitations Materials Gen-I materials (BR3 + Chooz-A), VVER-440 welds (high P >0,03%)

Limited to small areas of the reactor vessels Many of these vessels were annealed BR3 (ineffective : 343°C/168h),

Greifswald-1, -2 and -3 (effective : 475°C/152h)

Material variability (VVER-Welds, Gundremmingen base metal)

Systematic absence of archive materials (except Gundremmingen)

Environment Majority irradiated at low temperature : 190 to 265°C except Gundremmingen (~288°C)

Change of temperature during operation : Chooz-A (265 255°C) and Novovoronesh (250 228°C)

Poor and/or unreliable surveillance program (except Chooz-A)

Approach Vessel selection Do we have a choice ?

If yes, what are the selection criteria ? There are many :

Materials composition and damage levels Operation history (neutron fluence, irradiation temperature)

Availability of reliable surveillance data Availability of archive materials Other aspects : material variability, presence of segregated zones, Choice dependent on the targeted objectives What are the priorities International participation There is no ideal choice (except if infinite available budget)

Selection Criteria Materials Preferably representative of modern reactors ( LTO)

More systematic examination using many parts of the vessel (axial and azimuthal)

Available archive materials Irradiation environment LTO-representative fluence levels (> 1019 n/cm², E>1MeV)

Irradiation temperature ~290°C (majority of operating reactors)

Material Variability Material variability scatter Complicates the interpretation of the test results Increase the number of tests and use statistics Important details might be shadowed by the large scatter If the vessels are really inhomogeneous This should be taken into account in safety integrity assessment Check the adequacy of the surveillance program with respect to representativity of the whole vessel What should we favor and at which cost ?

For better understanding and validation of procedures with a minimum of tests (least scatter) or Application (real components) to check whether such material variability is covered by the available safety margins Alternative : availability of multiple locally homogeneous areas 17 © 2017 SCK*CEN

Issues Materials (at multiple locations)

Homogeneity of chemical composition Homogeneity of mechanical properties Identification of segregated area and further analysis Identification of LTO-relevant areas and further analysis Neutron exposure Verification of the neutron calculations dosimetry measurements Through-wall fluence attenuation Vessel versus surveillance program Mechanical properties : vessel versus surveillance Verification of master curve shape at high KJc Thermal ageing assessment Neutron flux/spectrum effects Assessment of regulatory procedures 18 © 2017 SCK*CEN

Organizational Aspects International participation As large as possible In-kind contributions Agreement on the project contents Main topics Vessel selection and sampling Materials transportation Work share and distribution Timeline Start date : 2017 4-5 yr project (benefit of operating reactors) 19 © 2017 SCK*CEN

Financial Aspects Vessel trepanning If the vessel will be anyway cut in small pieces for final storage, the costs will be limited additional work mainly If the vessel was planned to be buried as a whole, then we will have to pay very much all costs SCK*CEN experience BR3 sampling : several trepans taken from the inner side of the vessel ~0,4 M ( of 1995) by PCI Energy Services, Illinois US BR3 dismantling team : several large trepans ~100 k ( of 1995)

Closing Remarks To be effective, need of international program (work sharing)

Focus on most critical issues (prioritization)

Discussion : What do we want to do ?

Which reactor vessel ? Materials compositions ? Irradiation conditions (temperature, fluence) ?

Specifications and requirements ?

Technical issues to be addressed ?

Work sharing ?

This presentation contains data, information and formats for dedicated use only and may not be communicated, copied, reproduced, distributed or cited without the explicit written permission of SCK*CEN.

If this explicit written permission has been obtained, please reference the author, followed by by courtesy of SCK*CEN.

Any infringement to this rule is illegal and entitles to claim damages from the infringer, without prejudice to any other right in case of granting a patent or registration in the field of intellectual property.

SCK*CEN Studiecentrum voor Kernenergie Centre d'Etude de l'Energie Nucléaire Belgian Nuclear Research Centre Stichting van Openbaar Nut Fondation d'Utilité Publique Foundation of Public Utility Registered Office: Avenue Herrmann-Debrouxlaan 40 - BE-1160 BRUSSELS Operational Office: Boeretang 200 - BE-2400 MOL 22 © 2017 SCK*CEN

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