Spent Fuel Management at Stand Alone ISFSI Sites By: Paul Plante, - - PowerPoint PPT Presentation

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Spent Fuel Management at Stand Alone ISFSI Sites By: Paul Plante, - - PowerPoint PPT Presentation

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Spent Fuel Management at Stand Alone ISFSI Sites By: Paul Plante, Project Manager Connecticut Yankee/Maine Yankee/Yankee Rowe IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018 What is an

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Spent Fuel Management at “Stand Alone ISFSI” Sites

By: Paul Plante, Project Manager Connecticut Yankee/Maine Yankee/Yankee Rowe

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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What is an Stand Alone ISFSI?

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

It is a site where:

  • The reactor building and associated structures

have been decommissioned,

  • The associated waste has been removed,
  • The licensed facility has been reduced in size

and scope to an ISFSI.

  • The facility is in steady state, long term
  • perating mode awaiting fuel package removal

by the federal government.

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Before

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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After

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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The 3 Yankees

CY YR Connecticut Yankee 40 Spent Fuel Dry Casks 3 GTCC Dry Casks NAC MPC System CoC Expires 4/10/20 Yankee Rowe 15 Spent Fuel Dry Casks 1 GTCC Dry Casks NAC MPC System CoC Expires 4/10/20 Maine Yankee 60 Spent Fuel Dry Casks 4 GTCC Dry Casks NAC UMS System CoC Expires 11/20/20 MY

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Cask System Life Cycle at ISFSI Only Sites

  • Initial 20 year license life.
  • During this time, inspection and

maintenance requirements are found in the initial Certificate of Compliance (CoC) or Site Specific License and the FSAR.

  • Period of Extended Operation (40 years)
  • During this time, revised inspection and

maintenance plans will be found in the renewed CoC or Site Specific License and the FSAR.

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Spent Fuel Issues for Stand Alone ISFSI Sites

  • Cask system maintenance, inspections and

repairs.

  • Dry storage system amendments and

relicensing.

  • Aging management for dry storage systems.
  • Canister susceptibility to aging mechanisms

(Such as CISCC).

  • Site characterization for aging management.
  • Potential repair and mitigation issues.

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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  • Cask system maintenance and inspections-

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

Requirements for the initial 20 yrs. are in the CofC and FSAR:

  • Cleaning and sealing casks and pads,
  • Annual Inspections of the casks and pads,
  • Coating repairs,
  • Concrete repairs when necessary,
  • Temperature monitoring system maintenance

and upgrades.

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Typical Vertical Concrete Cask

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Cask system maintenance and inspections

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Examples of Reportable Tier 3 Damage

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

Third-Tier Crack

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Pad Delamination From Original Construction

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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  • Dry Storage System Amendments & Relicensing-
  • Complicated and ever evolving.
  • NRC developing and revising NUREG’s.
  • NEI 14-03 Guidelines to the industry.
  • EPRI activities and the technical basis for

relicensing.

  • ASME Code Case development.
  • Sometimes involves amendments to address
  • perating issues.

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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  • Aging Management for Dry Storage Systems-
  • Will require new site specific program and procedures

to be integrated into the existing site architecture.

  • Will be based on a standardized approach identified in

the MAPS NUREG and NEI 14-03 Industry Guidance.

  • Canister Inspections will be based on EPRI Aging

Management Program published in March, 2017 and eventually on ASME Code Case N-860.

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Aging Management Approach

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Canister susceptibility to aging mechanism-SCC

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

  • Using EPRI Susceptibility Criteria, determine the relative

ranking of canisters and their susceptibility to CISCC.

  • Results:
  • Maine Yankee: ZISFSI = 2 / Vcan = 4-5
  • Conn. Yankee: ZISFSI = 1 / Vcan = 4-5
  • Yankee Rowe: ZISFSI = 1 / Vcan = 5
  • Use this ranking, OE and known environmental

characteristics of the ISFSI to develop a strategy for canister inspections.

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Maine Yankee Located on the Back River Brackish Water-Tidal About 12 miles from Open Ocean

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

Determine the nature of the site environment:

  • For use in EPRI susceptibility

rankings.

  • To determine the significance of

Operating experience from other sites.

  • To assess the nature of the site

using technical literature on atmospheric corrosion.

  • Site characterization for aging management-
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Atmospheric Sampling Program

  • Started in August 2012.
  • Utilizes a Hi-Q continuous

duty air sampler.

  • Adjustable flow 20-100 lpm

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Seasonal Comparison of Atmospheric Conditions

0.5 1 1.5 2 2.5

Atmospheric Concentration (µg/m3) Month

Atmospheric Chloride Concentration: Maine Yankee ISFSI & Acadia National Park CASTNET Site

ANP High MY ISFSI High ANP Low MY ISFSI Low

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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SEM/EDS Analysis of Atmospheric Samples

Typical particles collected on 5 micron PTFE Filter Elemental map of particles collected Chloride-containing particles isolated

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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Atmospheric Chloride Deposition: Wet Candle Testing

  • Based on ASTM G140-02

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

Wet Candle (Chloride Deposition Rate) Result Comparison

Site Time period Distance to source Range of values (mg/m2/day) Maine Yankee ISFSI 2013-2017 19K meters (to

  • pen ocean)

1.0 – 5.1 Yankee Rowe ISFSI 2014-2017 160K meters 0.8 – 2.0 Kure Beach, NC (near-ocean) 1 1962-1998 250 meters 50 - 200 Kure Beach, NC (oceanfront) 1 1962-1998 25 meters 200 - 700 Cape Town, South Africa3 2013-2014 50 meters 126.69 2013-2014 150 meters 27.26 2013-2014 250 meters 30.87 2013-2014 2.7K meters 11.23 2013-2014 13.5K meters 10.54

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Surface Salt Sampling - Methods

2014 Sampling Event:  Wipe samples were collected using PTFE, dry cellulose, and wetted cellulose media  Samples collected from vertical and horizontal vent surfaces 2016 Sampling Event:  Objective: collect measurements on vents, shield plug, and from within canister in coordination with EPRI NDI robot demonstration  Tested surfaces:  Inlet & outlet vents on three storage casks:  VCC2 inlet & outlet  VCC9 inlet & outlet  VCC20 inlet & outlet  Shield plug  Coated steel cask base  Analysis  Laboratory analysis of chloride content  Elcometer in-situ analysis  SEM/EDS analysis of cask interior sample

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

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IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

Site Chloride Concentration (mg/m2)

Maine Yankee 0-11 SMUD5 18.5 Hope Creek6 <2.5 -60 Diablo Canyon6 2.0 – 58 Calvert Cliffs 7 < 50 Koeberg (Winter) 8 1,000 – 2,000 Koeberg (Summer) 8 2,500 – 5,000 Kure Beach (25m)9 76,000 – 228,000 Kure Beach (250m)9 21,000 – 60,000 NUREG/CR-717010 100 – 10,000 CRIEPI Threshold for 304L11 800

Surface Deposit Survey

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Canister Inspection Approach

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

  • The ROV was fitted with a borescope camera for inspections.
  • It can traverse 90° turns for navigating through the inlet and outlet vents

and is driven by magnetic wheels for vertical runs on carbon steel surfaces.

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Canister Surface Inspection Footage (GTCC)

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

  • Left view shows manufacturer’s identification number stamped on canister shell

showing detail of inspection capability.

  • Right view shows junction of a canister vertical and horizontal seam weld.
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Canister Surface Inspection Footage

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

  • Likely iron contamination

from initial fabrication.

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Potential repair and mitigation issues.

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

Industry initiatives to identify and scope various: repair options such as: mitigation options such as: Welded repairs Peening or Burnishing Thermal Spray Coatings Brazing/soldering Contaminate traps Patch Repairs Periodic surface cleaning Non-metallic Encapsulation or coatings

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Potential repair and mitigation issues.

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

One example: Failed Canister Over-pack at Maine Yankee

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Summary

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

  • Even in steady state ISFSI Only status, there are many

issues requiring attention:

  • Involvement in industry activities particularly for

areas where policy is being developed.

  • Working with industry partners as well as

government agencies.

  • Supporting research and development on tools to

ensure long term adequacy of dry storage systems.

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Abbreviations and Acronyms

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018

  • ASME: American Society of Mechanical Engineers
  • ASTM: American Society for Testing and Materials
  • CISCC: Chloride Induced Stress Corrosion Cracking
  • CoC: Certificate of Compliance
  • EPRI: Electric Power Research Institute
  • FSAR: Final Safety Analysis Review
  • GTCC: Greater Than Class C Waste
  • ISFSI: Independent Spent Fuel Storage Installation
  • MAPS: Managing Aging Processes NUREG Document
  • MPC: Multipurpose Canister System
  • NAC: NAC International
  • NEI: Nuclear Energy Institute
  • ROV: Remote Operated Vehicle
  • SEM/EDS: Scanning Electron Microscopy/Energy Dispersive Spectroscopy
  • UMS: Universal Multipurpose Storage System
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Spent Fuel Management at “Stand Alone ISFSI” Sites

By: Paul Plante, Cask Relicensing Project Manager Connecticut Yankee/Maine Yankee/Yankee Rowe

IAEA Technical Meeting on the Management of Spent Fuel at Shutdown Reactor Sites: 11-13 June 2018