ML24124A124
| ML24124A124 | |
| Person / Time | |
|---|---|
| Site: | NS Savannah |
| Issue date: | 05/08/2024 |
| From: | Koehler E US Dept of Transportation, Maritime Admin |
| To: | Division of Decommissioning, Uranium Recovery and Waste Programs |
| References | |
| Download: ML24124A124 (1) | |
Text
N.S. SAVANNAH License Termination Plan (LTP)
Post-Acceptance Public Meeting
May 8, 2024
Erhard W. Koehler Senior Technical Advisor, NS SAVANNAH Maritime Administration
1200 New Jersey Ave, SE l Washington l DC 20590 -0001 w w w. d o t. g o v Previous Docketed Decommissioning Presentations 03/11/2009: PSDAR Public Meeting 07/12/2017: Pre-Submittal Meeting, Dismantlement and Disposal License Amendment Request 10/24/2019: LTP Pre-Submittal Meeting No.1, Kickoff 06/30/2021: LTP Pre-Submittal Meeting No. 2, End-State Overview 11/17/2021: LTP Pre-Submittal Meeting No. 3, Dose Modeling Workshop Follow-Up Presentations 01/19/2022 NSS 2019 Exterior Hull Survey v FSS and
This presentation is the property e U.S. Government and may not be reproduced or NSS NUREG 1640 Clarification 2 distributed without credit to the U.S. Department of Transportation.
Presentation Outline Introduction / Facility History & Milestones Decommissioning Overview and Progress Historic Preservation and End State Considerations Demonstrating Compliance with the License Termination Radiological Criteria
A copy of this presentation will be posted on MARADs website at:
https://www.maritime.dot.gov/outreach/history/ns-savannah-decommissioning-and -disposition
This presentation is the property e U.S. Government and may not be reproduced or 3 distributed without credit to the U.S. Department of Transportation.
Nuclear Ship SAVANNAH is:
The Worlds First Nuclear-Powered Merchant Ship A National Historic Landmark of the United States (National Park Service, 1991)
An International Historic Mechanical Engineering Landmark (American Society of Mechanical Engineers, 1983)
A Nuclear Engineering Landmark (American Nuclear Society, 1991)
Ship of the Year
This presentation is the property e U.S. Government and may not be reproduced or (Steamship Historical Society, 2012) distributed without credit to the U.S. Department of Transportation. 4 The SAVANNAH Project was proposed by President Eisenhower in 1955 as a joint program of the Atomic Energy Commission and the Maritime Administration.
It was authorized by an Act of Congress on July 30, 1956.
The Savannah is a practical merchant vessel of combined passenger and cargo design.
PL 848 legislative history.
Length Overall 595 ft Beam 78 ft Draft 29 ft Reactor Power 80 MWth Propulsion Power 22,000 SHP Speed 21 kts Passengers 60 Total displacement 22,000 tons Total deadweight 9,570 tons
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 SAVANNAH in Nuclear Context Proposed and Authorized 1955 - 1956 Constructed 1958-1962 Operated 1962-1970 Defueled and Mothballed 1971 - 1976
DOE Manhattan Project Sites at Hanford, Oak Ridge, 1943/44-1970 First nuclear-powered ship: USS Nautilus, 1955-1980 First full-scale nuclear generating station: Shippingport, 1957-1982 First nuclear-powered surface ship: Soviet Icebreaker Lenin, 1959-1989 First nuclear-powered aircraft carrier: USS Enterprise, 1962-2012 Piquanuclear generating station (AEC Demo), 1963-66
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 The core objectives and accomplishments of the SAVANNAH program were:
to demonstrate to the world the peaceful use of atomic power to demonstrate the feasibility of nuclear-powered merchant ships to establish international recognition and acceptance of peaceful nuclear power to establish an infrastructure in the international maritime industry to support operations by nuclear powered merchant ships 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 Key Milestones in the Reactor Operating History
First Criticality: December 21, 1961 Operations under AEC Auth: 1962 - 1965 NS-1 License Issued: August 1965 Final Shutdown: November 9, 1970 Power History: 2.423 EFPY Fuel Removed: September 29, 1971 Defueling Completion: December 3, 1971 -1 Mothballing Preps: 1975-1976 Possession-Only License: 1976
This presentation is the property e U.S. Government and may not be reproduced or (1) This date later accepted as the Permanent Cessation of Operations
distributed without credit to the U.S. Department of Transportation. 8 SAVANNAHs Post-Operations History After defueling, the ship was moved to Savannah, GA to establish the Eisenhower Peace Memorial. This effort was not successful, and SAVANNAH was moved to Charleston, SC in 1975 for possession-only / mothballing work.
Legislation authorized S AVANNAHs operation as a museum at the Patriots Point Naval and Maritime Museum near Charleston. The ship opened to visitation on Christmas Day, 1981. The museum period ended in Spring 1994.
SAVANNAH was drydocked in Baltimore, MD, then moved into retention at MARADs James River Reserve Fleet near Newport News, VA; anticipated storage until 2025.
Plans changed after 9-11. Decommissioning of the ships nuclear power plant was authorized, and the ship moved to Baltimore in 2008. Funding was finally provided in 2017.
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.
MARADs Decommissioning Objective Terminate the NS-1 License Without Restrictions to Permit Disposition of the Ship Afterwards
There are three disposition pathways available to MARAD:
- 1. Preservation
- 2. Destruction via Shipbreaking (recycling / scrapping)
- 3. Sinking as an Artificial Reef
Decommissioning planning considered each pathway; however, preference was given to the preservation outcome, as described in the PSDAR.
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 National Historic Landmark Considerations for NSS Decommissioning Planning
Section 110(f) of the NHPA applies, and states in part:
- before approval of any Federal undertaking which may directly and adversely affect any NHL, the head of the responsible Federal agency shall undertake such planning and actions as may be necessary to minimize harm to such landmark, and shall afford the ACHP a reasonable opportunity to comment
- the agency should consider all prudent and reasonable alternatives to avoid an adverse effect on the NHL.
MARAD had to find a middle ground between decommissioning and minimizing harm. To do so, we adopted preservation-conscious guiding principles.
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 MARADs Decommissioning Principles (established 2005)
Our preferred outcome after decommissioning and license termination is preservation of the ship; consequently:
Wherever possible, decommissioning activities are undertaken in a manner that fosters future preservation; All dismantlement activities will use existing ship accesses to minimize impacts to adjacent structure; Whenever an option is presented or evaluated, the path that promotes preservation is given preferential consideration; and, Opportunities to improve the ship concurrent with decommissioning are exercised.
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 Scope of SAVANNAH Decommissioning
Remove and dispose systems, structures and components as needed to meet license termination criteria:
Control Rod Drive System Pressurizer Reactor Pressure Vessel Neutron Shield Tank Steam Generators Primary System piping Outlying equipment
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 Project Summary 1 Characterization 2018 & 2019 Appropriations in FY 2017 and 2018 Project Phase I started October 1, 2017 Engineering and Planning Developed Supplemental Environmental Assessment License Amendments to authorize and execute Dismantlement Ship Infrastructure Modifications to support DECON Minor systems and components removal, including Charge Pumps while on Drydock.
COVID Pandemic Emergency Suspension, March - July 2020.
Acquisition of DECON-LT services; contract award March 2021.
Phase I completed March 31, 2021.
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 Major Ship Improvements
- Climate controls* Mooring and Access/Egress equipment
- Sanitary spaces* Alarm and monitoring systems (fire/smoke, intrusion,
- Shore power flooding, security cameras)
- Mechanical systems* Restored public spaces, office and admin infrastructure
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. 15 Infrastructure: CV Portal, Liquid Waste Coll, CH 4
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 Safety is Always Job 1
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 Drydocking 2019 - Charge Pump Removal
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 Baltimore 2020: RC Cupola Head & Shield Ring Removal
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 Project Summary 2 Characterization 2018 & 2019 Project Phase II started April 1, 2021 Detailed Engineering and Planning Developed Waste Management Plans Minor components and interference removals began September 2021 Major Component Removal Change in Approach approved February 2022.
Extract RPV from inside the NST; retain NST outer annular wall Remove PZR Internals and retain Shell CRDM Tower, RPV Head, RPV Internals and RPV Removed, July - November 2022.
Major Dismantlement Completed Spring 2023.
Phase II wrap-up in progress.
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 Small Bore Piping Removal, Sept - Dec 2021
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 Waste Material Handling via CV Portal
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 Waste Packaging in CH 4 - (4) 20 Intermodals
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. 23 Dismantlement in RC Lower Level - April 2022
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. 24 Dismantlement in RC Lower Level - April 2022
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. 25 Intermodal Handling and Waste Transportation
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 Intermodal Handling and Waste Transportation
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. 27 July 2022: Control Rod Drive Tower Removal
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. 28 This presentation is the property e U.S. Government and may not be reproduced or N.S. SAVANNAH Reactor Vessel removal, November 8, 2022 distributed without credit to the U.S. Department of Transportation.
Project Update Characterization 2018 & 2019 Project Phase III (LT) In Progress Formally started with submittal of the LTP on 10/23/2023 Preparations in progress since Spring 2021 Final Dismantlement in-Progress inside CV Removal of existing grating material (to be replaced with new grating)
Final Status Surveys Commenced week of April 21, 2024 Working towards Confirmatory Surveys, Summer 2024 Monthly Status Meetings with NRC Ongoing
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. 30 Historic Preservation Considerations for the Characterization 2018 & 2019End-State Condition - 1 Consultation under the NHPA Initiated in 2018 (informal discussions back to 2013)
Executed a Programmatic Agreement in March 2023, covering both decommissioning and disposition as a combined Undertaking NRC is a signatory Meeting the Minimize Harm Standard Using characterization data, Identify Components and Structures likely to meet the radiological release criteria. Plan for their retention.
After DCGLs were finalized, and revised RPV removal approach adopted, expand the component retention list.
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. 31 Historic Preservation Considerations for the Characterization 2018 & 2019End-State Condition - 2 Retention of Components and Structures Must Allow Any Disposition Alternative All Disposition Alternatives involve EPA oversight.
MARAD adopted the EPA 15 mrem/year standard to prevent regulatory complication after LT.
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. 32 Characterization 2018 & 2019NSS Exposure v Background Radiation
The average American receives a dose of about 620 mrem per year from all potential sources. About half of this is from background sources.
Background sources are both naturally-occurring, and the result of human actions (weapons testing fallout, accident contamination, etc.).
Numerous factors affect individual dose.
The current background exposure on NSS is estimated at about 26 mrem per year for employees. Annual occupational dose (i.e., dose received from radiation work) was Zero (0) before DECON started.
Public exposure on NSS is less than 1 mrem per visit.
Source - NSS DECON Radiation Fact Sheet 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. 33 Characterization 2018 & 2019NSS Release Considerations
Outside of the Reactor Compartment and outlying Radiologically Controlled Areas (RCA), NSS already meets the unrestricted release criteria.
Implicit in the release criteria is the possibility that some material containing residual radioactivity may remain after the license is terminated.
The NSS challenge is to demonstrate that the dose to workers (and public) from residual radioactivity in the post-license end-state scenarios meets the release criteria.
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. 34 Expected End-State of the Nuclear Power Plant
Equipment and systems in spaces surrounding the Reactor Compartment have been removed.
Inside the Containment Vessel, a surgical approach was taken to extract the Reactor Vessel from its surrounding structure. The exterior annulus of the Neutron Shield Tank remains in place.
Small bore piping, valves, minor equipment was removed. Contaminated interiors of the Pressurizer and Steam Generator heat exchangers were removed.
This approach results in substantial preservation of the viewshed from the CV Portal. The CV has been opened up for access, and future interpretation.
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.
NSS Disposition Alternatives and their License Characterization 2018 & 2019Termination Considerations
Preservation
- Any prospective use of the ship that involves unrestricted public access (museum, conference center, entertainment venue or educational facility)
- Preservation scenarios are not indefinite and will at some future date result in shipbreaking. The LTP demonstrates that this exposure scenario is well below the release criteria for preservation workers. For visitors, exposure is essentially zero.
Shipbreaking
- At the end of the life of the ship, the process by which the steel structure is broken down and recycled. Results in the destruction of the ship.
- Shipbreaking will be performed by MARAD through its Ship Disposal Program.
- The LTP demonstrates that immediate shipbreaking is the worst case exposure scenario, but again well within permissible exposure limits.
Reefing
- Considered as Less Likely But Plausible (LLBP)
- The LTP explains the EPA restrictions likely to be imposed (i.e., removal of remaining structures containing residual radioactivity). Includes analysis of possible exposure This presentation is the property e U.S. Government and may not be reproduced or pathways to residential fishermen, or sport divers if those structures remain in place. 36 distributed without credit to the U.S. Department of Transportation.
This presentation is the property e U.S. Government and may not be reproduced or Charge Pump Rooms - Before and After distributed without credit to the U.S. Department of Transportation.
This presentation is the property e U.S. Government and may not be reproduced or Forward Control - Before and After distributed without credit to the U.S. Department of Transportation.
This presentation is the property e U.S. Government and may not be reproduced or Reactor Compartment Lower Level - Before and After distributed without credit to the U.S. Department of Transportation.
This presentation is the property e U.S. Government and may not be reproduced or Containment Vessel - Before distributed without credit to the U.S. Department of Transportation.
This presentation is the property e U.S. Government and may not be reproduced or Containment Vessel - After distributed without credit to the U.S. Department of Transportation.
One-of -a-kind Preserved Former Nuclear Power Plant
The exposed cross section of the collision boundary is preserved behind plexiglass.
The preserved viewshed inside the Containment Vessel (above), as viewed from the entrance portal. At left is the starboard Steam Generator; in the center is the Neutron Shield Tank outer annulus (reactor was in the center); at right is the Pressurizer shell.
There is no other pressurized water reactor in the world today that can offer this sort of experience. 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. 42 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. 43