ML023580257

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Licensee Presentation Slides from the December 17, 2002 Meeting Between the NRC Staff and Yankee Atomic Electric Co Regarding the Yankee (Rowe) Nuclear Power Station License Termination Plan
ML023580257
Person / Time
Site: Yankee Rowe
Issue date: 12/17/2002
From:
Yankee Atomic Electric Co
To:
NRC/FSME
References
-RFPFR
Download: ML023580257 (9)


Text

1 Yankee Atomic Electric Company License Termination Plan Meeting with USNRC December 17, 2002 I Agenda

"* Introduction Gerry van Noordennen

"* YNPS History Ellen Heath

"* Decommissioning Activities Ellen Heath

"* LTP Organization/Activities Enc Darois

"* HSANSite Characterization Enc Darois

"* Dose Modeling Jay Tarzia

"* Final Status Survey Jay Tarzia

"* Next Steps Gerry van Noordennen jIntroduction s Purpose of the Meeting

  • Open lines of communication with the NRC
  • Review decommissioning history o Discuss current decommissioning strategy o Review past LTP and FSS activities u Present current LTP team and approach z Obtain NRC feedback on approach

-o Discuss future interactions on selected topics

2

[ YNPS History

"* Achieved Initial Cnticality--1960

"* Began Commercial Operation-1 961

"* Upgrade to 600 MWt-1963

"* Decision to Cease Operations-2/1992

"* Possession Only Status --8/1992

"* Decommissioning Activities -1 992-present

"* Fuel Movement to ISFSI (Begin)-6/2002 IYNPS Decommissioning History

  • Decommissioning Plan Submitted-12/1993
  • Decommissioning Environmental Report 12/1993
  • Characterization Activities Commence-1994
  • Decommissioning Plan Approved 2/1995, Suspended 10/1995 and Re-Approved 10/1996
  • LTP Submitted to NRC (Revision 1 - 12/97)
  • Management Decision to Withdraw LTP (Availability of MARSSIM)-9/99

3 IYNPS Decommnissiomng History (Con't.)

"* Large Components Removed

"* Majority of SSCs Disposed of Off-Site

"* Significant Remediation and FSS Activities Performed Under Previously Submitted LTP

"* FSS Conducted Based Upon Guidance in a RG 1.86 o Draft NUREG/CR-5849 o Draft NUREG-1500 7

I Primary Auxiliary Building Scabblmg 4

I Safety Injection Room Floor Scabbling I Reactor Cavity Scabbling

5 i Near-Term Decommissioning Approach

  • Demolish Buildings to Grade
  • Demolish VC and Remove As Waste
  • Structures To Remain "a

PAB Cubicle Corridor "a SFP/IX Pit

- Turbine, Waste Disposal, Service, and Warehouse Building Pads and Shoreline Structures

  • Pedodic Re-Evaluation of Approach

6 I License Ternmnation Approach

"* Unrestricted Release (IOCFR20, Subpart E)

"* Survey to MARSSIM Guidance

"* Meet:

S25 mrem/yr (all pathways)

SALARA i LTP Project Goals

  • Produce a License Termination Plan That.

3 Satisfies the requirements of 50 82(a)(9) u Considers available NRC guidance z Considers stakeholder interests (e g, Commonwealth of Massachusetts, EPA, local community) a Minimizes NRC requests for additional information LTP Development Approach

"* Ensure Consistency With NRC Guidance Documents (RG 1.179, NUREG-1700, NUREG-1727)

"* Use CY LTP As Model

"* Incorporate Site -Specific Data

"* Incorporate NRC Feedback

"* Maintain Open Communications

7

[LTP Development Considerations

"* Continued Safe Spent Fuel Storage

"* Ongoing Decommissioning Activities

"* Site-Specific Characteristics, e g.

u Geology o Hydrology u Meteorology I HSA/Site Characterization

"* Consistent With MARSSIM

"* Considers Prior Survey Data

"* HSA/Site Characterization Results Will o Provide basis for initial area classification z Identify additional samples/measurements needed z, Create tools to support remediation planning

"* HSA/Site Characterization Reports Will Be Submitted to NRC and Referenced in LTP I Initial Area Classification Activities

  • Validate Instrumentation Used
  • Verify Ongoing Controls/Isolations
  • Include Initial Classification in LTP

8 I Dose Modehng

"* Codes Selected.

RESRAD V6 21, BUILD V3 21

  • Wide-spread use
  • Probabilistic and determinstic modules
  • Addresses complex hydrology and subsurface soil contamination

" Scenarios Considered

[ Resident farmer L Building occupancy

"* Probabilistic Mode for Sensitivity Analysis I Dose Modehng (Continued)

  • Input Parameters Based Upon

-, Results of sensitivity analysis "z Site-specific information, e g,

"* Radionuclides of interest at YNPS

"* Site-specific geologic data

"* Site-specific meteorological data "o NUREG/CR-5512 Vol 3

" NUREG/CR-6697 I Final Status Survey

"* Based on MARSSIM

"* FSS Development Considerations Include u DQOs j Anticipated site conditions at time of FSS i Varying radionuclide mix z Site contamination distnbution z Monitoring instrumentation

"* FSS Plan Included In LTP

2/2003 3/2003 4/2003 5/2003 I Future Meeting Topics/Target Dates

"* Site Charactenzation

"* Dose Modeling

"* Final Status Survey

"* Submittal Mechanics 9

[ Project Milestones

"* Public Comment on Draft:

10/2003

"* Submittal to NRC:

11/2003

"* Public Meeting 3/2004

"* RAI Issued:

7/2004

"* RAI Response 10/2004

"* NRC Approval 11/2004

"* Complete FSS:

2006