ML15057A424

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NRC Slides Vermont Yankee PSDAR Public Meeting February 19 2015
ML15057A424
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 02/19/2015
From:
Plant Licensing Branch IV
To:
Entergy Nuclear Vermont Yankee
Kim J
References
TAC MF5881
Download: ML15057A424 (32)
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Text

Vermont Yankee Post Shutdown Decommissioning Activities Report Public Meeting February 19, 2015 Brattleboro, Vermont Andrew Persinko, Deputy Director Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards

Welcome

  • Meeting Agenda
  • Meeting Facilitation and Protocol
  • NRC Speakers and Experts
  • Public Comments, Questions and Answers
  • Meeting Feedback Forms
  • Adjourn at 9 PM

Vermont Yankee PSDAR Meeting Agenda

  • Andrew Persinko - Introduction
  • Douglas Broaddus - NRC Review of the PSDAR and Licensing Status
  • Chip Cameron - Public Comment Session
  • Andrew Persinko - Summary Remarks and Meeting Closure by 9 PM

Mission

  • The NRC licenses and regulates the Nation's civilian use of radioactive materials to protect public health and safety, promote the common defense and security, and protect the environment

Decommission (10 CFR 20 Subpart E)

  • To remove (as a facility) safely from service and reduce radioactivity to a level that permits:
  • Release of the property for unrestricted use and termination of the license; or
  • Release of the property under restricted conditions and termination of the license

Release Criteria

  • Unrestricted Release
  • Total Effective Dose Equivalent (TEDE) 25 mrem (0.25 mSv/a) and As Low As is Reasonably Achievable (ALARA)
  • Average member of the critical group
  • All pathways
  • Period of performance - 1000 years
  • Restricted release
  • 25 mrem (0.25 mSv/a) TEDE and ALARA, with institutional controls in effect
  • Legally enforceable institutional controls
  • If institutional controls fail, doses do not exceed 1 mSv/a, or 5 mSv/a, under specific circumstances
  • Financial assurance - independent third party
  • Licensee and NRC public input/outreach requirements

7

NEPA

  • National Environmental Policy Act
  • 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions
  • Bounded environmental effects or Supplemental Environmental Report
  • Environmental Assessment conducted during license termination process

Transition from Operations to Decommissioning

  • Office of Nuclear Reactor Regulation continues Project Management until the Post Shutdown Defueled Technical Specifications are issued
  • Transfer Project Management to the Office of Nuclear Material Safety and Safeguards
  • Inspection Program is transferred to the Division of Nuclear Materials Safety from Division of Reactor Projects
  • Support continues from Nuclear Security and Incident Response

NRC Decommissioning Experience 0

2 4

6 8

10 12 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 Power Reactors Research Reactors Materials Sites

Maine Yankee 11

Connecticut Yankee 12

Yankee Rowe 13

Millstone Unit 1

Vermont Yankee Post Shutdown Decommissioning Activities Report February 19, 2015 Brattleboro, Vermont Bruce A. Watson, CHP Chief, Reactor Decommissioning Branch Office of the Nuclear Material Safety and Safeguards

NRC Decommissioning Regulations - 1997

  • 18 Years of Implementing Experience

Vermont Yankee Decommissioning Milestones

  • December 19, 2014 - PSDAR submitted
  • December 29, 2014 - Vermont Yankee Permanent Cessation of Operation
  • January 12, 2015 - Entergy certified VY permanent cessation of operations and the reactor was permanently defueled
  • NRC issued the public notice for this PSDAR public meeting

Reactor Decommissioning Options

  • DECON: Equipment, structures, etc. are promptly removed or decontaminated to a level that permits radiological release (5 plants in DECON)
  • SAFSTOR: Plant placed in a safe, stable condition and maintained in that state until it is subsequently decontaminated to levels that permit radiological release (14 plants in SAFSTOR)
  • ENTOMB: Plant is encased in a structurally long-lived substance to allow decay until levels permit unrestricted release (not currently available)
  • Radiological Decommissioning must be completed within 60 years

Post Shutdown Decommissioning Activities Report Contents (10 CFR 50.82 - Regulatory Guide 1.185)

  • A description and schedule for the planned decommissioning activities
  • A site-specific decommissioning cost estimate, including the costs of managing irradiated fuel
  • A discussion that provides the means for concluding that the environmental impacts associated with the decommissioning activities will be bounded by appropriately issued Environmental Impact Statements

Power Reactor Decommissioning Process - Post Shutdown Decommissioning Activities Report

  • NRC regulations require that a public meeting be held in the vicinity of the facility to discuss the PSDAR and its contents, as well as to solicit comments
  • NRC does not approve the PSDAR
  • Licensee may begin major decommissioning activities 90 days after NRC receives the PSDAR

The NRC Review Process -

Vermont Yankee PSDAR February 19, 2015 Brattleboro, Vermont Douglas Broaddus, Chief Decommissioning Transition Branch Office of the Nuclear Reactor Regulation

  • NRR project manager coordinates technical reviews of the PSDAR
  • NRC staff may submit Requests for Additional Information (RAIs)

NRCs PSDAR Review Process

  • Does the PSDAR contain the information required by regulation?
  • Can the decommissioning be completed as described, and within 60 years?
  • Can the radiological decommissioning be completed for the estimated cost?
  • Do the decommissioning activities endanger public health and safety or the environment?

NRCs PSDAR Review Process:

Evaluation Criteria

  • Site-specific Decommissioning Cost Estimate

- Reasonable assurance funds are available to perform the radiological cleanup

- If plans are delayed, ensure licensee has a means of adjusting the cost estimate and funding over the storage period

  • Decommissioning Cost Estimate (DCE) and funding level are updated annually NRCs PSDAR Review Process:

Decommissioning Cost Estimate

  • Reasons for concluding that environmental impacts of site-specific decommissioning activities are bounded by previous Environmental Impact Statement(s)

- NUREG-0586, Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities

- Inspection program NRCs PSDAR Review Process:

Environmental Review / NEPA

  • Review considers public comments
  • Staff will notify licensee when no additional information is required

- NRC does not approve the PSDAR

- Staff documents NRC review is complete

  • Licensee may not begin major decommissioning activities until 90 days after NRC receives the PSDAR, per 10 CFR 50.82(a)(5)

NRCs PSDAR Review Process

NRC Oversight Program Reactor Decommissioning & Spent Fuel Storage February 19, 2015 Brattleboro, Vermont Marc S. Ferdas, Chief Decommissioning & Technical Support Branch Region I, Division of Nuclear Materials Safety 1

  • Oversight and monitoring conducted over the entire period of decommissioning process

& 2690 Oversight Program 2

  • Decommissioning inspection program includes both core and discretionary inspections.
  • Implementation depends on activities being planned or performed.

Post-Operation Transition Phase SAFSTOR - Fuel in Spent Fuel Pool SAFSTOR - No Fuel in Spent Fuel Pool Actively Decommissioning - Fuel in Spent Fuel Pool Actively Decommissioning - No Fuel in Spent Fuel Pool Final Surveys Underway Oversight Program 3

  • Organization, Management, & Cost Controls
  • Spent Fuel Pool & Dry Cask Storage Operations
  • Safety Reviews, Design Changes, and Modifications
  • Maintenance and Surveillance Testing
  • Occupational Radiation Exposure
  • Effluent & Environmental Monitoring
  • Physical Security
  • Vermont Yankee is in the Post-Operation Transition Phase as they prepare the site for SAFSTOR.
  • No major decommissioning activities are planned.
  • Vermont Yankee is developing plans to place all spent fuel into dry cask storage.
  • Oversight activities are being performed by resident and regional inspectors.

Oversight Status 5

IMC 2561: Decommissioning Power Reactor Inspection Program IMC 2690: Inspection Program for Dry Storage of Spent Reactor Fuel at Independent Spent Fuel Storage Installations and for 10 CFR Part 71 Transportation Packaging RG 1.184 (rev 1): Decommissioning of Nuclear Power Reactors RG 1.185 (rev 1): Standard Format and Content for Post-Shutdown Decommissioning Activities Report NUREG 1628: Staff Response to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors NRC Web-Page: http://www.nrc.gov/waste/decommissioning.html YouTube Video: http://www.youtube.com/watch?v=GifRku-N7_Q&feature=youtu.be References - Reactor Decommissioning

& Spent Fuel Storage 6

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