ML26063A837

STS-231, Revision 0, Maritime Admin - Annual Report for CY2025

ML26063A837
Person / Time
Site:	NS Savannah (NS-001)
Issue date:	02/26/2026
From:	Nuclear Ship Support Services
To:	Office of Nuclear Reactor Regulation
Shared Package
STS-231, Rev 0	List: ML26063A837
References
STS-231, Rev 0
Download: ML26063A837 (0)

Text

Approved:

U.S. Department of Transportation Maritime Administration N.S. SAVANNAH ANNUAL REPORT FOR CY2025 STS - 231 Revision 0 Manager, N.S. SA VANNAH Programs Prepared by:

Nuclear Ship Support Services, LLC I

SAVANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 RECORD OF REVISIONS Revision Summary of Revisions 0

The original version of the 2025 Annual Report, License NS-1 LIST OF EFFECTIVE PAGES Page No.

Rev. No.

Page No.

Rev. No.

Pae:e No.

Rev. No.

1 0

2 0

3 0

4 0

5 0

6 0

7 0

8 0

9 0

10 0

11 0

12 0

Revision 0 2

SAVANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 1.0 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 Table of Contents INTRODUCTION ITEMS REQUIRED BY TECHNICAL SPECIFICATIONS 2.1.1 2.1.2 2.1.3 2.2.l 2.2.2 2.5.1 2.5.2 TS 3.4.2.1.a. Status of the Facility License Activities Organization.

Review of Other Technical Specification Requirements TS 3.4.2.1.b. Radiation Surveys and Monitoring Station Dosimeter Readings Radiation Surveys Monitoring Station Dosimeter Results TS 3.4.2.1.d. Quarterly Intrusion Alarm System Checks TS 3.4.2.1.f. Principal Decommissioning and Maintenance Activities TS 3.4.2.1.g. Unauthorized Entry Into Radiologically Controlled Areas (RCAs)

Event Discussion Improvements to Access Control TS 3.4.2. I.h. Inspection of Primary, Secondary and Auxiliary Systems Degradation TS 3.4.2.1.i. Summary of Occupational Exposure 3.0 OTHER NRC REPORTS 3.1 10 CFR 50.59(d)(2) Report of Changes, Tests or Experiments 3.2 10 CFR 50.54(w)(3) Insurance Annual Report 3.3 Commitment Management 4.0 SIGNIFICANT MARAD ISSUES 5.0 4.1 Remaining Decommissioning Timeline 4.2 4.3 4.4 4.4. I 4.4.2 4.4.3 4.4.4 Public Events, Visitation and Training Historic Stewardship National Historic Preservation Act Consultation Peer Review Group (Stipulation II)

Decommissioning-License Tennination (Stipulation III)

Disposition Alternatives Process (Stipulation IV)

Mitigation Measures (Stipulation V)

REFERENCES Revision 0 4

4 4

5 5

5 7

7 7

7 7

8 8

8 8

8 8

8 9

9 9

9 9

9 10 10 10 10 12 12 3

SA VANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0

1.0 INTRODUCTION

This Annual Report is submitted by the Maritime Administration (MARAD) as licensee for the Nuclear Ship SAVANNAH (NSS) and covers the Calendar Year (CY) 2025 reporting period. This report is arranged into three sections following the introduction. Section 2.0 provides the discussion of the various reporting items required by the Technical Specifications (TSs). Section 3.0 includes other periodic reports required by the Nuclear Regulatory Commission (NRC), and issues ofregulatory significance. Section 4.0 includes facility issues that MARAD believes may be of interest to the NRC.

In accordance with the requirements of TS 3.4.2.1, the written annual report shall be submitted prior to March 1 of the following calendar year and shall specifically include the seven (7) reporting items listed in that specification. These items are addressed in Sections 2.1 through 2.7 inclusive. In addition, TS 3.6.3 requires the Safety Review Committee (SRC) to review ten ( I 0) items, one of which is this annual report. Section 2.1.3 includes the status of these ten (10) SRC review items.

This annual report is provided to parties to the NSS Programmatic Agreement (PA) covering the Decommissioning and Disposition ofNSS ( Reference a), in accordance with Stipulation VIII of that agreement. The NRC is a signatory to the PA. Sections 4.3 and 4.4 of this report cover the reporting requirements contained in Stipulation VIII, including a summary report of work performed pursuant to the terms of the PA, any proposed schedule changes, any problems encountered, and any disputes or objections received.

2.0 ITEMS REQUIRED BY TECHNICAL SPECIFICATIONS The seven (7) 1 TS 3.4.2.1 items specifically required to be included in the written annual report are as follows:

a.

The status of the facility (see 2.1).

b.

The results of the radiation surveys and monitoring station dosimeter readings (see 2.2).

c.

The results of quarterly intrusion alarm system checks (see 2.3).

d.

A description of the principal maintenance performed on the vessel (see 2.4).

e.

Any unauthorized entry into radiation control areas by visitors or employees and corrective action(s) taken to improve access control (see 2.5).

f.

Any degradation of one of the several boundaries which contain the radioactive materials aboard the NSS (see 2.6).

g.

Results of occupational exposure indicated by personal dosimetry (see 2.7).

These TS items were reviewed by the Safety Review Committee at its annual meeting on December 10, 2025. The Executive Steering Committee members reviewed them during concurrence routing of this report prior to submission. Of note, as N RC is aware MARAD does not intend to request any TS revisions prior to license termination; therefore, reporting on these seven items will continue even if not directly applicable to the current condition of the facility.

2.1 TS 3.4.2.1.A. STATUS OF THE FACILITY During CY2025, the ship was be1thed at Pier 13, Canton Marine Tenninal, 4601 Newgate Avenue, Baltimore, MD.

1 There were originally nine (9) requirements lettered a thru i. Items c and e have been deleted through license amendments. This report consolidates the remaining seven (7) requirements and letters them a thru g.

Revision 0 4

SA VANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 MARAD holds a Possession-only license for the NSS nuclear utilization facilities that was modified by License Amendment 15 (Reference b) to allow dismantlement and disposal. As a result of License Amendment 15, the status of the facility is "Dismantlement."

Dismantlement is defined in Regulatory Guide (RG) 1.86, "Termination of Operating Licenses for Nuclear Reactors," Reference (c). This 1974 RG describes the now outmoded Dismantling option of decommissioning. MA RAD understands RG 1.86 was withdrawn as noticed in the Federal Register (81 F R 53507) on August 12, 2016; its withdrawal does not impact the NSS licensing basis. MARAD uses the words 'active decommissioning' and 'dismantlement' interchangeably.

Dismantlement is characterized by removal of radioactive fluids, radioactive wastes and other materials having activities above accepted unrestricted activity levels. Mothballed activities continue to be performed. These include active surveillance, monitoring and maintenance of the nuclear facilities housed on board the ship, and custody and maintenance of the ship as the primary physical boundary and protective barrier of the licensed site.

In the CY 2024 annual repo1t (Reference d), MARAD repo1ted all dismantlement and waste handling/shipping activities were completed in that year. In December 2025, a sho1t section of contaminated piping and one valve was discovered. This is the length of the Containment Vessel (CV) drain between the bottom of the CV, and its penetration into the Reactor Compartment double bottom structure. This piping should have been included in Revision I of the License Termination Plan (L T P). It was removed in early CY 2026 and is awaiting shipment at the time of th is repo1t.

2.1.1 LICENSE ACTIVITIES On January 30, 2025, the LTP was approved (Reference e).

On June 18, 2025, MA RAD presented the results of 15 survey units to NRC at a public meeting (Reference f).

On July 21, 2025, MARAD submitted Updated Final Safety Analysis Repo1t, Revision 14 (Reference g).

On September 4, 2025, MA RAD submitted License Termination Plan, Revision I (Reference h).

On November 20, 2025, MARAD submitted FSS Report I of 5 (Reference i)

On December 15, 2025, MA RAD submitted FSS Report I of 5, Revision I (Reference j) 2.1.2 ORGANIZATION.

There were no significant changes to the organization in CY2025. During the year, individual positions were restaffed as needed. With the completion of dismantlement and waste shipping activities, project staffing was decreased; however, all key personnel positions identified in the STS organization Decommissioning Quality Assurance Plan (Reference k) were maintained.

2.1.3 REVIEW OF OTHER TECHNICAL SPECIFICATION REQUIREMENTS In accordance with TS 3.6.3, the Safety Review Committee (SRC) is specifically required to review the following items with or without a formal meeting:

a.

Proposed changes to Technical Specifications There were no proposed changes to Technical Specifications in CY2025.

b.

Evaluations required by 10 CFR 50.59 No Safety Evaluations or Screenings were performed in CY2025.

Revision 0 5

SAVANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0

c.

Proposed changes or modifications to a Radiologically Controlled Area entry alarm system or reactor containment vessel system In CY2025, there were no changes to alarm systems and reactor containment vessel systems.

d.

Evaluations of substantive changes to the results of radiological surveys Given that in November 2024, all remaining radioactive waste was shipped for disposal, there were no substantive changes to the results of radiological surveys in CY2025.

e.

Procedures and revisions per TS 3.5 Procedures and their revisions were reviewed prior to approval.

f.

Evaluations of reported violations of Technical Specifications There were no NRC repmtable violations to Technical Specifications in 2025.

g.

Evaluations of reportable events per TS 3.4.3. 1 There were no repo1table events to the NRC.

h.

Evaluations of deviations allowed by TS 3. 7. 1. 7 Three deviations were in effect, as needed, throughout the year.

S TS-004 Deviation - Radiologically Controlled Area doors unlocked and unguarded during Reactor Compartment and Containment Vessel entry.

S TS-004 Deviation - Loss of Alarm Coverage of Technical Spec(fication 3. 7. 1.5 Doors.

S TS-004 Deviation - Severe Weather prevents daily security patrols.

All deviations were reviewed for continued applicability as required.

1.

Audits and self assessments to verify the effectiveness of the Decommissioning Quality Assurance Plan Assessments were performed in the following functional areas during the repo1ting period:

QSA-2025-00 I, Procedure Annual Review 2024 QSA-2025-003, 1st Half, Radiation Protection Program Assessment QSA-2025-003, 2nd Half, Radiation Protection Program Assessment QSA-2025-003, Annual, Radiation Protection Program Assessment QSA-2025-004, STS-003-011, RO Observation Program QSA-2025-005, Commitment Periodic Review 2025 QSA-2025-006, Technical Specification 3.7.1.7 Deviations Review 2025 J.

Annual reports to the NRC During CY2025, the following repo1ts were reviewed prior to their submission to the NRC:

Annual Repo1t for CY2024 (STS-228).

Decommissioning Funds Status Repo1t for CY2024 (STS-229).

Annual Radiological Environmental Monitoring and Radioactive Effluent Release Reports for CY2024 (STS-230).

Revision 0 6

SA VANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 2.2 TS 3.4.2.1.B. RADIATION SURVEYS AND MONITORING STATION DOSIMETER READINGS 2.2.1 RADIATION SURVEYS The Radiation Protection (RP) Program and baseline RP staffing were maintained during CY2025. They functioned to perform routine clean area surveys where final status surveys were complete, and such other tasks as were required (e.g., collection of water and sediment samples).

Given that radiologically controlled areas were deposted in July 2024, no traditional RP surveys were required or performed after that date.

After all waste was shipped in November 2024, all radioactive material areas were deposted except for the storage area for instrument calibration sources.

2.2.2 MONITORING STATION DOSIMETER RESULTS Sixty-nine (69) permanent ly placed thermo-luminescent dosimeter (TLD) monitoring stations are dispersed throughout the non-RCAs of the NSS and in those areas of the NSS that are routinely occupied. Fixed point radiation surveys are performed during TLD change outs. As would be expected with no radioactive effluents or solid waste on the NSS, the results from the TLDs from all monitoring stations indicated that readings were insignificant as compared to the background radiation levels.

2.3 TS 3.4.2.1.D. QUARTERLY INTRUSION ALARM SYSTEM CHECKS Routine security surveillances were conducted as required by TS 3.7.2.1. On a quarterly basis, the staff performed SIC-TS-Q-1, RCA Entrances Secured, Lock, Key and Seal Number Verification Inspection. Other monitored doors were tested.

2.4 TS 3.4.2.1.F. PRINCIPAL DECOMMISSIONING AND MAINTENANCE ACTIVITIES The Final Status Survey (FSSs) field campaign was completed in January 2025. On an as required basis, additional or repeat measurements were taken throughout the year to support data analysis and evaluation.

MARAD's decommissioning contract provides for post-dismantlement activities. Among those completed, or started in CY 2025 are:

Occupational safety modifications to the CV system of ladders and gratings, to ensure accessibility among the three access points considering the retention of primary system components. This work was completed in CY 2025.

Restoration of the CV permanent lighting system, by running new electrical cabling to provide power to retained legacy fixtures throughout the space. This work was started in CY 2025 and was completed in CY 2026 prior to the submission of this repo1t.

Planning for permanent access arrangements into the Reactor Compartment Lower Level at the access into Cargo Hold 4. This includes a permanent steel ladder and chain. The work was completed in in CY 2026 prior to the submission of this report.

Planning for the reinstallation of the CV Cupola Head and removal of the Reactor Compartment hatch external operating system started in CY 2025. The work is scheduled for performance in the first and second quarters of CY 2026.

Planning for the permanent repair of decommissioning-related pipe openings in watertight boundaries.

Maintenance activities fall under the umbrella of ship custodial care and husbandry. Within this umbrella, the day-to-day focus is on the ship"s hull structure, and the mooring systems that keep it Revision 0 7

SAVANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 safely secured to the Pier 13 laybe1th. The utility systems, including shore power and fresh and sanitary water, are routinely inspected. The hul l itself is subject to a preservation program that includes regular painting and cleaning, and completion of minor steel and equipment repairs as these are identified. In addition, the following principal maintenance activities were performed in CY2025:

Surveillance and inspection of the hull structure as the primary site safety boundary.

American Bureau of Shipping (ABS) Annual Survey of Lay-up and Underwater Hul l Survey.

Annual MARAD safety and material condition survey.

Minor steel repairs and renewals as identified by ABS.

Maintained and repaired as required lighting and electrical distribution systems.

Maintained ce1tified firefighting equipment and local fire suppression systems.

Maintained the fire and smoke detection system.

Maintained the intrusion and flooding alarm system.

Environmental remediation was carried out during the year, on both a planned and as-required basis. In general, this involved the removal of legacy hazardous materials such as asbestos and polychlorinated biphenyls (PCB). Significant CY 2025 remediation tasks included: a) the removal of all remaining legacy fluorescent light fixture ballasts throughout the ship, either known or presumed to contain PCBs; and b) the removal of residual hydraulic oil from cargo hatch operating systems (inoperative) in areas where leaks were present.

2.5 TS 3.4.2.1.G. UNAUTHORIZED ENTRY INTO RADIOLOGICALLY CONTROLLED AREAS (RCAS)

The NSS had no RCAs in CY2025.

2.5.1 EVENT DISCUSSION Not Applicable 2.5.2 IMPROVEMENTS TO ACCESS CONTROL Not Applicable 2.6 TS 3.4.2.1.H. INSPECTION OF PRIMARY, SECONDARY AND AUXILIARY SYSTEMS DEGRADATION The annual inspection required by TS 3.7.3.4 was completed in December 2025 even though there were no remaining primary, secondary or auxiliary systems that contain radioactive material. It is documented in SlC-TS-A-2 RO Structures, Systems and Components Annual Inspection 2025.

2.7 TS 3.4.2.1.J.

SUMMARY

OF OCCUPATIONAL EXPOSURE There was no occupational exposure onboard NSS in CY 2025. As noted in Reference d, personnel dosimetry was discontinued in July 2024, after the remaining radiologically controlled areas were deposted. Note that Reference d repo1ted the total occupational dose for 2024 was approximately 9.8 mRem.

3.0 OTHER NRC REPORTS 3.1 10 CFR 50.59(D)(2) REPORT OF CHANGES, TESTS OR EXPERIMENTS The regulations require each power reactor licensee to submit, at intervals not to exceed 24 months, a report containing a brief description of any changes, tests, and experiments, including a summary of the evaluation of each.

Revision 0 8

SA VANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 No Changes, Tests or Experiments were proposed in CY2025 that would require a 10 CFR 50.59 evaluation, and, consequently, no evaluations were completed. No screenings were written in CY2025.

3.2 JO CFR 50.54(W)(3) INSURANCE ANNUAL REPORT The regulations require each power reactor licensee to obtain insurance available at reasonable costs and on reasonable tenns from private sources or to demonstrate to the satisfaction of the NRC that it possesses an equivalent amount of protection covering the licensee's obligation. MARAD adheres to the Federal rules of self-insurance as a matter of established policy.

3.3 COMMITMENT MANAGEMENT No Regulatory Commitments were made or revised in CY2025.

4.0 SIGNIFICANT MARAD ISSUES 4.1 REMAINING DECOMMISSIONING TIMELINE The license tennination deadline for the NSS is December 3, 20312, based on the Pennanent Cessation of Operations milestone date of December 3, 1971. MARAD anticipates requesting license tennination in CY2026.

4.2 PUBLIC EVENTS, VISITATION AND TRAINING As described in previous reports, MARAD has experienced sustained high levels of interest for tours and professional training employing NSS in a variety of roles. The interest continued throughout CY2025, with that year likely recording the highest number of visitors to the ship since coming to Baltimore in 2008. The regular one Saturday per month visitation continued, with three dates being combined with preservation outreach described in Section 4.4. The National Maritime Day Public Open House was held on Sunday, May 18, 2025, with approximate visitation of 600 persons. On the preceding day, an invitational event hosted by the non-profit N/S SA VANNAH Association featured the dedication of the CV to public access.

Numerous professional training activities were hosted for local first response and law enforcement organizations. The Joint Military Attache School (JMAS) resumed 3 times per year training in the spring.

Other professional organizations were hosted on board for a variety of technical, research, or staff development purposes. Multiple commercial and government organizations researched NSS program files as part of the developing interest in next generation commercial nuclear ship propulsion and floating nuclear power. The American Nuclear Society chose NSS as a technical tour site as part of its Winter Meeting in November.

4.3 HISTORIC STEWARDSHIP The NSS was designated as a National Historic Landmark (NHL) in 1991, and is the only directly-owned, managed, and maintained N HL property in the Department of Transportation inventory. Under the provisions of the National Historic Preservation Act (NHPA) of 1966, as amended, the highest standard of care for historic objects falls upon federal owners of N HLs. MARAD maintains a continuous focus on its historic stewardship responsibilities when conducting activities on the NSS site. All work on the ship, whether radiological or not, is sensitive to maintaining the historic fabric and appearance of the ship.

MARAD's Federal Preservation Officer (FPO) provides expert advice and guidance to licensee staff in these matters, particularly with respect to the implementation of the Secretary of the Interior's Standards for the Treatment of Historic Properties and Historic Vessel Preservation Projects.

2 December 3, 197 1, is the de facto date of permanent cessation of operations date based on completing the reactor defueling that date by tensioning the reactor vessel head with six studs.

Revision 0 9

SAVANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 4.4 NATIONAL HISTORIC PRESERVATION ACT CONSULTATION Because the decommissioning of the nuclear power plant is an adverse effect and the disposition of the NSS is unknown, MARAD entered consultation in compliance with Section 106 of the N HPA and developed a Programmatic Agreement (PA) to guide the process. The PA among the US DOT, MARAD, NRC, the Advisory Council on Historic Preservation (ACH P), and Maryland State Historic Preservation Officer (SH PO), for the Decommissioning and Disposition of the NS SAVANNAH was executed on March 17, 2023. This section of the Annual Repo1t has been prepared in accordance with Stipulation V111 (Monitoring and Repo1ting) of the PA to provide a summary of activities unde1taken pursuant to the PA over the course of CY2025.

4.4. 1 PEER REVIEW GROUP (STIPULATION II)

The Peer Review Group ( PRG), established in accordance with Stipulation II, continued to meet throughout CY 2025. Its members include signatories and concurring patties to the PA, as well as other organizations and individuals with an interest in the ship. PRG meetings were held in January, March, May, July, and September; the November meeting was cancelled due to the government shutdown. P RG members, as well as members of the public, continued to provide individual input and guidance to MARAD during meetings, in correspondence, and through review of documents.

4.4.2 DECOMMISSIONING - LICENSE TERMINATION (STIPULATION III)

MARAD continued to meet the NHPA requirement to minimize harm and retained as much of the nuclear power plant as feasible during decommissioning efforts as per Stipulation 1l J throughout CY 2025. MA RAD completed the installation of inclined ladders and walkways to provide safer walking access throughout the CV with connections to the three points of access and egress. This work improves the occupational safety of the CY and also allows visitors to experience the space. Interpretive signage and the pennanent lighting effo1ts previously described aid in the visitors' experience and understanding of the former nuclear reactor space.

The CV was formally opened to visitors in May and has been a pa1t of self-guided tours of the ship since then.

4.4.3 DISPOSITION ALTERNATIVES PROCESS (STIPULATION IV)

In fu1therance of MARAD 's affirmative, good-faith effo1t to seek preservation ofNSS, and to suppott the determination of preservation interest per Stipulation IV, MARAD continued to do outreach in a variety of ways. MARAD hosted qua1terly public site visits on board NSS in CY 2025, which included Q & A information sessions and guided and self-guided tours of the ship.

Approximately 362 people visited the ship during the February site visit, 568 people visited the ship during the May site visit, which was held in conjunction with the National Maritime Day (NMD) celebration on the ship, and 361 and 410 people visited during the August and November site visits, respectively. Future public site visits are planned on a qua1terly basis in CY 2026, one of which will again coincide with the observance ofNMD on the ship in May 2026.

MARAD continued to follow-up on interest received from targeted emails sent to science and maritime museums, professional organizations, chambers of commerce, and tourism bureaus in po1t cities where NSS visited during her operation, and held briefings with relevant organizations in states which expressed an interest in the ship, including, but not limited to, preservation organizations, planning commissions, maritime museums and organizations, and educational and science institutions. Approximately 15 briefings/updates were provided during CY 2025, some of which occurred onboard NSS.

Conferences were identified as additional means of outreach to promote the availability of the ship for preservation. MA RAD staff and N/S SAVANNAH Association (NSSA) members Revision 0 10

SAVANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 presented at a number of conferences in CY 2025, including Preserving the Recent Past in Boston, MA in March, Council of American Maritime Museums in Pensacola, FL in April, Society for Industrial Archeology in Buffalo, NY and the Society for History in the Federal Government in Washington, DC in May, the New Jersey Historic Preservation Conference in Burlington, NJ in June, Health Physics Society in Madison, WI in July, and the 12th Maritime Heritage Conference in Buffalo, NY in September. In addition to conferences, MARAD staff and NSSA members made virtual presentations to a variety of interested organizations, including the Ocean Liner Society in April, and the World Ship Society Port ofNew York and American Society of Military Engineers in September.

NSS was featured in a number of articles throughout CY 2025, including in the Society of Naval Architects and Marine Engineers (SNAME) magazine Marine Technology in January 2025, the summer editions of Preservation and Sea History magazines, the Eisenhower Society and Docomomo US newsletters in March and August, respectively, and the Health Physics Society newsletters for October and November.

Relevant organizations who may be able to promote the availability of the ship continued to be identified. MA RAD met with Docomomo US and its local DC chapter and continued to work with entities previously identified. MARAD had anticipated working with the Atomic Legacy Preservation Network (ALPN), a collaboration among several atomic themed museums and sites associated with former Atomic Energy Commission (AEC) and Department of Energy (DOE),

facilities, created by the DOE. However, ALPN has not met since 2024, although MARAD keeps in contact and plans to join when meetings resume.

Perhaps the most significant result of the outreach effects to-date occurred at the end of CY 2025, when Bert Brantley, the President and CEO of the Savannah Area Chamber of Commerce, sent a letter to the Maritime Administrator on behalf of an informal group of Savannah area leaders.

The city of Savannah had previously responded to the Notice of Availability / Request for Information (NOA/RFI) in 2024 with an initial expression of interest, and their recent letter expanded on this interest. Mr. Brantley noted that he was expressing the group 's interest in having Savannah become the ship's permanent home, subject to working out the details of the disposition with MA RAD and doing their own internal feasibility studies. The group has identified a proposed location, adjacent to the newly expanded Convention Center and a hotel which will be open by 2028 and has strong support from the community. MARAD senior management have responded favorably to this development and MA RAD staff will work with the city of Savannah and its representatives to work out a plan for the ships disposition.

Members of the PRG have also provided outreach efforts, and outreach effort remain ongoing in CY 2025.

In addition, MARAD was awarded the 2025 Outstanding Stewardship by a Government Agency for NSS, by the Maryland Historic Trust (MHT). This award recognized MARA D's stewardship of the ship in Baltimore, stating:

Since 2008, MARAD has meticulously cared for the National Historic Landmark vessel N.S. Savannah, the world 'sfirst nuclear-powered merchant ship, balancing decommissioning efforts with historic preservation. Through innovative approaches, MARAD has restored public spaces, enhanced accessibility, and ensured the ship 's legacy as a symbol of peaceful nuclear technology. MARAD 's efforts set a precedent for preserving historic nuclear facilities while advancing public education and maritime heritage.

The award was presented by Elizabeth Hughes, the MD SHPO, during the NMD celebration in May.

Revision 0 11

SA VANNAH Technical Staff STS - 231, Annual Report for CY2025, Revision 0 The Draft Disposition Alternatives Study that was prepared per Stipulation IV of the PA is under review by MA RAD senior management. Although Stipulation IV calls for the preparation of this study, followed by the preparation of the Disposition Plan, as well as the publication of a Request for Proposal (RFP), because the city of Savannah has expressed interest in the ship, the further development of the study, plan, and RFP may not be required. All future steps will be discussed in consultation with the PRG in CY 2026.

4.4.4 MITIGATION MEASURES (STIPULATION V)

The development of mitigation measures, per Stipulation V, including the Collections Management Policy and Thematic Context, continued in 2025. The Collections Management Plan will also include an Architectural Salvage Plan as an addendum. The Architectural Salvage Plan will identify items from NSS that should be salvaged in the event the ship is not preserved. The Collections Management Policy, along with the Architectural Salvage Plan are planned to be provided to the PRG for review and comment in CY 2026. A draft of the Thematic Context has been reviewed by MARAD and is undergoing minor revisions and is also planned to be provided to the PRG for review and comment in CY 2026.

5.0 REFERENCES

a. Programmatic Agreement Among the U.S. Department of Transportation, Maritime Administration, The U.S. Nuclear Regulatory Commission, the Advisory Council on Historic Preservation, and the Maryland State Historic Preservation Officer for the Decommissioning and Disposition of the Nuclear Ship SA l'ANNAH, Baltimore, Maryland, March 2023

b. Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, June 1 974

c. Letter from Mr. John B. Hickman (NRC) to Mr. Erhard W. Koehler (MARAD), dated April 23, 201 8, Nuclear Ship SA l'ANNAH - Issuance of Amendment 15 to revise the License to allow Dismantlement and Disposal

d. Letter from Mr. Erhard W. Koehler (MA RAD) to U.S. Nuclear Regulatory Commission (NRC),

dated February 27, 2025, Annual Report for CY2024, Revision 0

e. Letter from Tanya Hood (NRC) to Mr. Erhard W. Koehler (MARAD), dated January 30, 2025, Nuclear Ship Savannah - Issuance of Amendment 19 to Facility Operating License to add License Condition lo include License Termination Plan Requirements.

f.

Memorandum to Shaun M. Anderson (NRC) from Tanya Hood (NRC), dated July 7, 2025, Summary of June 18, 2025, Presubmillal Public Meeting Regarding the Final Status Survey Reports for the Nuclear Ship SA l'ANNAH

g. Letter from Mr. Erhard W. Koehler (MARAD) to U.S. Nuclear Regulatory Commission (NRC),

dated July 2 1, 2025, Submillal of Updated Final Safety Analysis Report, Revision 14

h. Letter from Mr. Erhard W. Koehler (MA RAD) to U.S. Nuclear Regulatory Commission (NRC),

dated September 4, 2025, Submillal of Updated License Termination Plan, Revision 1

1. Letter from Mr. Erhard W. Koehler (MA RAD) to U.S. Nuclear Regulatory Commission (NRC),

dated November 20, 2025, Submittal of Final Status Survey Final Report 1 o f 5 J.

Letter from Mr. Erhard W. Koehler (MARAD) to U.S. Nuclear Regulatory Commission (NRC),

dated December 1 5, 2025, Submillal of Final Status Survey Final Report 1 of 5, Revision 1

k. S TS-003-00 1, Decommissioning Quality Assurance Plan, Revision 3 Revision 0 1 2