ML19308A133
| ML19308A133 | |
| Person / Time | |
|---|---|
| Issue date: | 11/04/2019 |
| From: | Tanya Smith Division of Decommissioning, Uranium Recovery and Waste Programs |
| To: | Bruce Watson Division of Decommissioning, Uranium Recovery and Waste Programs |
| T SMITH DUWP | |
| Shared Package | |
| ML19308A131 | List: |
| References | |
| Download: ML19308A133 (27) | |
Text
N.S. Savannah License Termination Plan Kick-Off Meeting October 24, 2019 Erhard W. Koehler Senior Technical Advisor, NS SAVANNAH Maritime Administration 1200 New Jersey Ave, SE l Washington l DC 20590 -0001 www.dot.gov
Agenda Introduction N.S. Savannah Decommissioning Activities and Current Status Site Characterization Dose Modeling Final Status Survey Near term LAR Next Steps This presentation is the property e U.S. Government and may not be reproduced or 2
distributed without credit to the U.S. Department of Transportation.
Introduction DECON Objectives Terminate the NRC license without restrictions or conditions Allow Unrestricted Release of the ship MARAD Cost Estimates and Project Approach are based on worst-case scenarios; characterization should allow for improvement The actual extent of component removal and remediation efforts will be defined by the characterization data, analysis, and dose modeling This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 3
Introduction Approach and Methodology Three Phase Approach, Up To Seven Years
- (I) DECON Planning and Engineering -2 years;
- (II) Industrial Dismantlement Activity - 4 years; and
- (III) License Termination - 1 year.
The phase durations are approximate, and there will be overlap at the boundaries.
Employ mature commercial nuclear decommissioning technologies and practices Maintain Integrity of Licensed Site and Control of Activities This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 4
Activities and Current Status Phase 1 Began Oct. 1, 2017 No Radiologically Controlled Areas (RCAs) outside of the Reactor Compartment (RC) and Containment Vessel (CV).
No insulation remaining on the Primary Coolant System and any Reactor Plant Auxiliary System.
Dismantlement of Reactor Plant Auxiliary Systems as necessary to implement 1 and 2 above.
Construction / Outfitting to support 1, 2 above and Phase 2 dismantlement.
This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 5
Activities and Current Status Phase 1 RCA End State Yellow shows outlying RCAs and areas containing Reactor Plant Auxiliary Systems Orange shows Reactor Compartment, Containment Vessel and Cold Chemistry Lab Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 6
Activities and Current Status Phase 1 RCA End State - A deck Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 7
Activities and Current Status Phase 1 RCA End State - B deck Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 8
Activities and Current Status Phase 1 RCA End State - C deck Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 9
Activities and Current Status Phase 1 RCA End State - D deck Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 10
Activities and Current Status Phase 1 RCA End State - 14 Flat Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 11
Activities and Current Status Phase 1 RCA End State - Tank top Before After This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 12
Activities and Current Status Phase I Improvements Upgrade Safety Barriers, Lighting/Power Outlet Capacity, HVAC Improve LLW processing capabilities Improved Security System onboard Installed Fire & Smoke and Flooding Detection Systems in the RC and CV This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 13
CV Horizontal Access Portal
Purpose:
Improve safety of worker access This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 14
License Termination Plan Approach Unrestricted Release (10CFR20, Subpart E)
Meet:
- 25 mrem/yr (all pathways)
- ALARA Considers NS Savannah unique design
- No groundwater or soil, i.e., no resident farmer scenario
- Potential pathways for ultimate disposal
- Very compact site
- Historic preservation (Natl. Historic Landmark)
This presentation is the property e U.S. Government and may not be reproduced or 15 distributed without credit to the U.S. Department of Transportation.
Characterization Campaigns Scoping Surveys Nuclear Ship Savannah, Reactor Vessel, Internals and Neutron Shield Tank Characterization and Classification Assessment, Rev. 0, April 3, 2004 NSS Characterization Report, Rev. 0, September 22, 2005 CR-056, RPV Drilling, Sampling, and Radiochemical Analysis Project Report, WPI, January 31, 2006 This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 16
Characterization Campaigns Characterization Surveys STS-198, NS Savannah Characterization Plan, 2016 CR-104, Radiological Characterization Outside of Reactor Compartment and Containment Vessel, January 25, 2019 CR-109, Radiological Characterization -
Reactor Compartment and Containment Vessel, August 30, 2019 Ship Hull Survey, 2019 Drydock This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 17
Characterization 2018 Outside RC and CV 2018 (Aug/Sept)
Characterization 2018 & 2019
- 396 Direct alpha/beta measurements
- 412 Smears
- 10 Tritium Measurements
- 403 Gamma Dose Rates
- Beta Scans
- Gamma Scans
- 69 ISOCS This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 18
Characterization 2019 Inside RC2018 Characterization and& 2019 CV 2019 (Spring/Summer)
- Included interior and exterior (system) surveys
- Areas: 332 smears, 500 LAS, 79 Fixed measurements, 173 scans, 148 dose rates
- Systems: 39 water samples, 7 oil samples, 20 paint chips, 6 sludge, 12 smear composites, 21 tritium smears
- Onsite Gamma analysis and offsite gamma and HTD Analysis (Incl. TRUs)
- Cable, wire, water, and sludge - Offsite Analysis
- Gamma, tritium, N-63, Tc-99, C-14, Metals, PCBs etc This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 19
Characterization Findings 2018 (Outside RC/CV)
- Majority of Activity inside systems
- Some H-3 identified
- No significant Contamination on external surfaces 2019 (Inside RC/CV)
- No Significant TRUs (Actinides)
- Identified Radionuclides:
- General Dose Rates:
- Lower Level RC/CV: less than 1 mrem/hr
- Remainder RC/CV: < .012 mrem/hr Initial Classification Using Default DCGLs This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 20
Exterior Hull Survey (2019)
Class 3 Survey Units 9 Units
- Each Unit , 19 Random Fixed Point Locations
- Starboard, Port, Rudder
- 171 Survey Points Each Fixed-Point Measurement
- Gamma at 1 meter
- 1 m2 beta scan
- 3 minute static count time for each measurement
- 1 smear at each location Results
- No Activity Identified This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 21
Characterization Follow-On Radionuclide Statistical Analysis
- Establish Fixed Radionuclide Mix
- Establish Surrogate Relationships
- Eliminate Insignificant Radionuclides Additional Water and Fluids Removal More Detailed Analysis for some components and systems This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 22
Dose Modeling Anticipated Codes:
- RESRAD BUILD, RESRAD OFFSITE
- Wide-spread use
- Probabilistic and deterministic modules
- Probabilistic Mode for Sensitivity Analysis
- MCNP and/or Microshield
- External Dose Modeling Anticipated Scenarios:
- Building occupancy
- Re-Use/Re-Cycle Models This presentation is the property e U.S. Government and may not be reproduced or 23 distributed without credit to the U.S. Department of Transportation.
Dose Modeling Input Parameters Based Upon:
- Results of sensitivity analysis
- Site-specific information, e.g.,
- Radionuclides of interest at NSS
- Conservative geologic and meteorological data for re-cycle scenarios
- NUREG/CR-5512 Vol. 3
- NUREG/CR-6697 This presentation is the property e U.S. Government and may not be reproduced or 24 distributed without credit to the U.S. Department of Transportation.
Final Status Survey Based on MARSSIM FSS development considerations include:
- DQOs
- Anticipated ship conditions at time of FSS
- Varying radionuclide mix
- Ship contamination distribution
- Monitoring instrumentation FSS Plan included in LTP This presentation is the property e U.S. Government and may not be reproduced or 25 distributed without credit to the U.S. Department of Transportation.
Near Term LAR LAR proposes to address duplicate TSs on security by deleting one TS requirement regarding CV security This presentation is the property e U.S. Government and may not be reproduced or distributed without credit to the U.S. Department of Transportation. 26
Future Meeting Topics Dose Modeling Final Status Survey Submittal Mechanics This presentation is the property e U.S. Government and may not be reproduced or 27 distributed without credit to the U.S. Department of Transportation.