ML20059K945

U.S. Dept. of Transportation, Maritime Admin. - Annual Report for CY2019, Revision 0

ML20059K945
Person / Time
Site:	NS Savannah
Issue date:	02/26/2020
From:	Koehler E US Dept of Transportation, Maritime Admin
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML20059K945 (17)

Text

l U.S. Department Office of Ship Disposal 1200 New Jersey Ave., SE Washington, DC 20590 of Transportation Maritime Administration Ref: 10 CFR 50.36(c)(5), 50.54(w), 50.59(d)(2)

February 26, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Docket No. 50-238; License No. NS-1; N.S. SAVANNAH Annual Report for CY2019, Revision 0 Pursuant to Technical Specification 3.4.2, the Maritime Administration (MARAD) is required to submit an annual written report. MARAD hereby submits Revision Oto the Annual Report for CY2019 as Enclosure (1).

The annual report is also intended to meet the routine reporting requirements for:

o 10 CFR 50.59(d)(2) requires a summary of safety evaluations for activities implemented under 10 CFR 50.59; and, o 10 CFR 50.54(w) fusurance Annual Report.

This submittal contains no new Regulatory Commitments.

If there are any questions or concerns with any issue discussed in this report, please contact me at (202) 366-2631, a.nd/or e-mail erhard.koehler@dot.gov.

Respectfully, Erhard W. Koehler Senior Technical Advisor, N.S. SAVANNAH Office of Ship Disposal Enclosure

Docket No. 50-238; License NS-1; N.S. SAVANNAH Submittal of Annual Report for CY2019, Revision 0 February 26, 2020

Enclosure:

1. STS-209, Annual Report for CY2019, Revision 0 2

Docket No. 50-238; License NS-1; N.S. SAVANNAH Submittal of Annual Report for CY2019, Revision 0 February 26, 2020 cc:

Electronic copy NSS ESC NSS SRC MAR 610,612,615 Hardcopy, cover letter only MAR-600, 640,640.2 Hardcopy with all enclosures MAR-100, 640.2 (rt)

USNRC (Ted Smith, Katherine Warner)

USNRC Regional Administrator - NRC Region I MD Department of the Environment (Eva Nair)

EWK/jmo 3

U.S. Department Office of Ship Disposal 1200 New Jersey Ave., SE Washington, DC 20590 of Transportation Maritime Administration Docket No. 50-238; License No. NS-1; N.S. SAVANNAH to Submittal of Annual Report for CY2019, Revision 0 STS - 209, ANNUAL REPORT FOR CY2019 4

U.S. Department of Transportation Maritime Administration N.S. SAVANNAH ANNUAL REPORT FOR CY2019 STS - 209 Revision 0 Approved: . Date: February 26, 2020 Manager, N.S. SAVANNAH Programs Prepared by:

TOTE Services, Inc.

SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 RECORD OF REVISIONS Revision, Summary of Revisions 0 The original version of the 2019 Annual Report License NS-1 LIST OF EFFECTIVE PAGES Page No. Rev.No. Page No. Rev. No. Page 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 13 0 Revision 0 2.

SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 Table of Contents

1.0 INTRODUCTION

4 2.0 ITEMS REQUIRED BY TECHNICAL SPECIFICATIONS 4 2.1 TS 3.4.2.1.a. Status of the Facility 4 2.1.1 License Activities 5 2.1.2 Organization 5 2.1.3 Review of Other Technical Specification Requirements 5 2.2 TS 3.4.2.1.b. Radiation Surveys and Monitoring Station Dosimeter Readings 7

. 2.2.1 Radiation Surveys 7 2.2.2 Monitoring Station Dosimeter Results 7 2.3 TS 3.4.2.1.c. Environmental Sample Analysis Surveys 7 2.4 TS 3.4.2.1.d. Quarterly Intrusion Alarm System Checks '7 2.5 TS 3.4.2.1.f. Principal Decommissioning and Maintenance Activities 8 2.6 TS 3 .4.2.1.g. Unauthorized Entry Into Radiologically Controlled Areas (RCAs) 8 2.6.1 Event Discussion 8 2.6.2 Improvements to Access Control 8 2.7 TS 3.4.2.1.h. Inspection of Primary, Secondary and Auxiliary Systems Degradation 8 2.8 TS 3.4.2.1.i. Summary ofCY2019 Occupational Exposure 8 3.0 OTHER NRC REPORTS 9 3.1 10 CFR 50.59(d)(2) Report of Changes, Tests or Experiments 9 3.2 10 CFR 50.54(w)(3) Insurance Annual Report 9 3.3 Commitment Management 9 4.0 SIGNIFICANT MARAD ISSUES 9 4.1 Remaining Decommissioning Timeline 9 4.2 Public Events, Visitation and Training 9 4.3 Historic Stewardship 9 4.4 National Historic Preservation Act Consultation 10

5.0 REFERENCES

10 APPENDIX A. CY2019 Radiation Survey Results in Radiologically Controlled Areas 11 APPENDIX B. CY2019 Radiological Environmental Sampling Results 13 Revision 0 3

SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, 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) 2019 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 NRC, and issues of regulatory 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 eight (8) reporting items listed in that specification. These items are addressed in Sections 2.1 through 2.8 inclusive. In addition, TS 3.6.3 requires the Safety Review Committee (SRC) to review ten (10) items, one of which is this annual report. Section 2.1.3 includes the status of these ten (10) SRC review items.

2.0 ITEMS REQUIRED BY TECHNICAL SPECIFICATIONS The eight (8) 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 environmental sample analysis surveys (see 2.3).

d. The results of quarterly intrusion alarm system checks (see 2.4).

e. A description of the principal maintenance performed on the vessel (see 2.5).

f. Any unauthorized entry into radiation control areas by visitors or employees and corrective action taken to improve access control (see 2.6).

g. Any degradation of one of the several boundaries which contain the radioactive materials aboard the NSS (see 2.7).

h. Results of occupational exposure indicated by personal dosimetry (see 2.8).

The status of these subject items were reviewed by the Safety Review Committee at its annual meeting on December 18, 2019 and by the Executive Steering Committee members during its concurrence routing prior to submission of this annual report to the NRC.

2.1 TS 3.4.2.1.A. STATUS OF THE FACILITY During CY2019, the ship was berthed at Pier 13, Canton Marine Terminal, 4601 Newgate Avenue, Baltimore, MD until September 9, 2019 when it was towed to Philadelphia Ship Repair, LLC, (PSR) in Philadelphia, PA for drydocking. The ship arrived at the PSR facility on September 10, and was drydocked on September 11. The NSS remained in drydock for the remainder of the year.

• MARAD holds a Possession-only license for the NSS nuclear utilization facilities that was modified by License Amendment 15 (Reference a) 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 (b). This 1974 RG describes the now outmoded Dismantling option of decommissioning. MARAD understands RG 1.86 was withdrawn as noticed in the Federal Register (81 FR 53507) on August 12, 2016 and that its withdrawal does not impact the Revision 0 4

SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 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 onboard the ship, and custody and maintenance of the ship as the primary physical boundary and protective barrier of the licensed site.

As a result of signing the Consolidated Appropriations Act for FY 2018, decommissioning of the NSS is fully funded with the $131 million estimated to complete decommissioning and terminate the NS S license.

Decommissioning activities conducted during the reporting period are described in Sections 2.1.1 and 2.5 below.

2.1.1 LICENSE ACTIVITIES License Amendment 17 (Reference c) was issued on June 11, 2019. It revised all of Technical Specification (TS) Section 2.0, Radioactive Releases from its original custom form to typical 10 CFR 50.36a Technical Specifications for effluents fi*om nuclear power reactors. It was submitted to NRC as License Amendment Request (LAR) 2018-002. Note that a typographical error in Amendment 17 was corrected by Reference (d).

2.1.2 ORGANIZATION There have been no significant changes to the organization that was reported in the last Annual Report. The organization continues to be made up ofMARAD direct employees, contractors, and consultants.

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

a. Proposed changes to Technical Specifications None

b. Evaluations required by 10 CFR 50.59 Safety Evaluation Screenings were performed as required and forwarded for committee review for information. No screening determined that a 10 CFR 50.59 Evaluation was required; consequently, none were performed. Additional information regarding 10 CFR 50.59 Evaluations is found in Section 3.1 of this report.

c. Proposed changes or modifications to a Radiologically Controlled Area entry alarm system or reactor containment vessel system The Safety Review Committee reviewed all changes to alarm systems and reactor containment vessel system prior to their implementation. These are summarized in Section 2.4of this report.

d. Evaluations of substantive changes to the results of radiological surveys The following Radiologically Controlled Areas (RCA) were cleaned, surveyed and de-posted:

• Port and Starboard Stabilizer Rooms.

• Port and Starboard Charge Pump Rooms.

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 The Forward Control RCA was cleaned and surveyed.

New Waste Storage Areas were created:

• Fish Locker.

• Sugar and Flour Stores,

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 reportable violations to Technical Specifications in 2019. The following Technical Specification violations were documented in the corrective action system:

CAR Number CAR Title Drydock security guards failed to sign-in visitors on aft gangway 2019-059 entrance Drydock security guards unfamiliar with Watchstander 2019-060 responsibilities per STS-007-001, Abnormal and Emergency Conditions, Revision 8 Many Corrective Action Report resolutions were not written or 2019-074 reviewed in a timely manner

g. Evaluations of reportable events per TS 3.4.3.1 There were no NRC reportable events in CY2019.

h. Evaluations of deviations allowed by TS 3. 7.1. 7 Two deviations were approved in 2019. One was associated with alarm monitoring while the ship is moving to and from Philadelphia, PA.

• STS-004 Deviation - B Deck RC door unguarded during CV/RC entry, Rev. 0.

• STS-004 Deviation - Alarm System not functional during ship movement.

The two previously existing deviations were reviewed in 2019 and found correct for the situations they address:

• STS-004 Deviation - Loss of Alarm Coverage of Technical Specification 3.7.1.5 Doors, Rev. 0.

• STS-004 Deviation - Severe Weather prevents daily security patrols.

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0

i. Audits and self-assessments to verify the effectiveness of the Decommissioning Quality Assurance Plan Assessments were performed in the following functional areas in the reporting period:

• QSA-2019-001, 2018 Annual Radiation Protection Program Assessment.

• QSA-2019-002, HASP Safety Inspection Report Review 2019.

• QSA-2019-003, Material Handling Equipment.

• QSA-2019-004, Confined Space Program.

• QSA-2019-005, Commitment Periodic Review.

• QSA-2019-006, Technical Specification 3.7.1.7 Deviations Review.

j. Annual reports to the NRC During CY2019, the CY2018 Annual Report (STS-204) and the CY2018 Decommissioning Funds Status Report (STS-205) were reviewed prior to their submission to the NRC.

2.2 TS 3.4.2.1.B. RADIATION SURVEYS AND MONITORING STATION DOSIMETER READINGS 2.2.1 RADIATION SURVEYS A routine radiological survey program continued to be followed in CY2019. Radiological survey measurements were taken in various RCAs and non-RCAs. All readings in non-RCAs were insignificant as compared to background radiation levels.

The results of the CY2019 Radiation Survey Results in RCAs are listed in Appendix A.

2.2.2 MONITORING STATION DOSIMETER RESULTS Forty-five (45) permanently 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. Results from the TLDs from all monitoring stations indicated that readings were insignificant as compared to the background radiation levels. No fixed-point radiation dose rate exceeded 5 µR/hr (micro-R/hr).

2.3 TS 3.4.2.1.C. ENVIRONMENTAL SAMPLE ANALYSIS SURVEYS Environmental water and sediment samples were taken adjacent to the ship at various times during the calendar year as required by TS. The environmental sample results indicate that any changes in the radiological conditions in the environment surrounding NSS are insignificant as compared to the samples taken shortly before the NSS arrived at Pier 13. Therefore, based on the results of the radiological environmental monitoring program,_NSS operations at Pier 13 did not have any adverse effects on the health and safety of the public or on the environment in 2019.

Environmental samples were also taken at PSR prior to the ship's arrival on September 10, 2019.

The results of the CY2019 Radiological Environmental Sampling Results are listed in Appendix B.

2.4 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.

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 2.5 TS 3.4.2.J.F. PRINCIPAL DECOMMISSIONING AND MAINTENANCE ACTIVITIES CY 2019 was the second full-calendar-year of decommissioning, and MARAD's focus was on continued preparations for dismantlement of the primary systems, structures and components in upcoming years. In so doing, MARAD maintained its past focus on occupational and visitor safety, TS-required equipment, routine preventative maintenance, repairs and upgrades, preservation of the ship's structural integrity, and restoration of ship systems and equipment necessary for husbanding the ship. The following significant discrete activities were performed in CY2019:

o Removed contaminated piping in horseshoe (space connecting charge pump rooms to the port stabilizer room).

o Removed contaminated piping and components in Port Stabilizer Room.

o Removed contaminated components in Starboard Buffer Seal Charge Pump Room.

o Removed contaminated components in Port Buffer Seal Charge Pump Room.

o Removed contaminated components in Forward Control Area (aka Cold Chemistry Laboratory);

o Removed piping in Engine Room.

o Replaced Siemens MXL System with Honeywell Notifier for fire and smoke detection.

o Created access openings and installed two (2) watertight doors on C-Deck: one on the port side between Cargo Holds 2 and 3, and the other on the starboard side between Cargo Holds 3 and 4.

o Completed Characterization of all ship spaces.

o The ship was drydocked and the following activities were performed:

• Surveyed, cleaned, repaired and painted the hull.

• Removed three (3) buffer seal charge pumps from their pump rooms to Cargo Hold 4.

2.-6 TS 3.4.2.J.G. UNAUTHORIZED ENTRY INTO RADIOLOGICALLY CONTROLLED AREAS (RCAS)

_No unauthorized entries were made into any RCAs in CY2019.

2.6.1 EVENT DISCUSSION None 2.6.2 IMPROVEMENTS TO ACCESS CONTROL None

2. 7 TS 3.4.2.J.H. INSPECTION OF PRIMARY, SECONDARY AND AUXILIARY SYSTEMS DEGRADATION The annual inspection required by TS 3.7.3.4 was completed on December 3, 2019. It is documented in SIC-TS-A-2 RO Structures, Systems and Components Annual Inspection 2019. There was no notable degradation of the primary, secondary and auxiliary systems since the last inspection in 2018.

2.8 TS 3.4.2.J.L

SUMMARY

OF CY2019 OCCUPATIONAL EXPOSURE Because the NSS has been permanently shutdown for more than 45 years, no individual is expected to receive in one year from sources external to the body, a dose in excess of 10 percent of the limits specified in 10 CFR 20.1201. In 2019, the number of individuals monitored with TLDs during their entries into RC As was 201. No individual received more than 70 mRem from occupational sources during the monitoring period.

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 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.

No Changes, Tests or Experiments were proposed in CY2019 that would require a 10 CFR 50.59 evaluation, and, consequently, no evaluations were completed.

Screenings are forwarded to Safety Review Committee members for information.

3.2 10 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 terms 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 CY2019.

4.0 SIGNIFICANT MARAD ISSUES 4.1 REMAINING DECOMMISSIONING TIMELINE The license termination deadline for the NSS is December 3, 2031, 1 based on the Permanent Cessation of Operations milestone date of December 3, 1971. Decommissioning is scheduled to be complete well within the allowed 60-year license termination period.

4.2 PUBLIC EVENTS, VISITATION AND TRAINING Similar to past years, MARAD continued its program of public access and training support during CY2019. Public access was curtailed as needed during significant decommissioning and maintenance activities. A variety of training and meeting events were conducted throughout the year.

Major activities included a decommissioning public information session on May 18 in conjunction with a bicentennial observance of the voyage of the pioneering oceangoing Steam Ship Savannah, and the annual commemoration of National Maritime Day (observed on May 19 with an open house).

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 NHL property in the Department of Transportation inventory. 2 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 NHLs. 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 1

December 3, 1971 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.

2 The NHL Washington (DC) Union Station is owned by the DOT, acting through the Federal Railroad Administration. The station complex, including air rights above the tracks, is managed and maintained by the independent Union Station Redevelopment Corporation, a public-private quasi-governmental entity established in 1983.

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 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.

4.4 NATIONAL HISTORIC PRESERVATION ACT CONSULTATION MARAD initiated consultation under Section 106 of the NHPA in April 2018 to address the potential adverse effects and harm to the NSS as a NHL arising from decommissioning and license termination activities. NRC was one of four agencies and organizations that was invited to join the consultation; all accepted. The other entities include the Advisory Council on Historic Preservation (ACHP), the National Park Service (NPS) and the Maryland Historic Trust (MHT), acting as the State Historic Preservation Officer. The first consultation meeting was held in November 2018. The NHPA undertaking is defined as the combination of decommissioning-license termination and subsequent disposal of the vessel. The parties began to develop a Programmatic Agreement to cover the aspects of the undertaking; the activities remain incomplete at the end of the CY201.9 reporting period.

5.0 REFERENCES

a. Letter from Mr. John B. Hickman (NRC) to Mr. Erhard W. Koehler (MARAD), dated April 23, 2018, Nuclear Ship SAVANNAH - Issuance OfAmendment 15 to revise the License to allow Dismantlement 'and Disposal

b. Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, June 1974

c. Letter from Mr. Theodore B. Smith to Mr. Erhard W. Koehler (MARAD), dated June 11, 2019, Issuance ofAmendment 17 to revise the Technical Specifications to revise the Radioactive Ef]luent Controls and make an Administrative Change

d. Letter from Mr. Theodore B. Smith to Mr. Erhard W. Koehler (MARAD), dated November 20, 2019, Nuclear Ship Savannah - Correction of Typographical Error in Amendment 17 of the Technical Specifications Revision 0 10

SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 Appendix A CY2019 Radiation Survey Results in Radiologically Controlled Areas APPENDIX A. CY2019 RADIATION SURVEY RESULTS IN RADIOLOGICALLY CONTROLLED AREAS Area General Area Highest General Area Highest Radiation Radiation Level Contamination Contamination levels mR/hr mR/hr (milli- Level Level (milli-R/hr) R/hr) (DPM/100cm 2) (DPM/100cm2)

Reactor <1.0 <1.0 <1000 ~1000 Compartment Cupola Level A Deck Reactor <1.0 <1.0 <1000 <1000 Compartment Upper Level B Deck Reactor <1.0 <1.0 <1000 <1000 Compartment Middle Level C Deck Reactor <1.0 <1.0 <1000 <1000 Compartment Middle Level D Deck Reactor <1.0 <1.0 <1000 <1000 Compartment Lower Level Fwd Reactor <1.0 <1.0 <1000 <1000 Compartment Lower Level Aft Containment <1.0 <1.0 <1000 <1000 Vessel 1st Level Containment <1.0 1.5 <1000 <1000 Vessel 2nd Level Containment 1.0 1.6 <1000 <1000 Vessel 3rd Level Containment <1.0 * <1.0 <1000 <1000 Vessel 4th Level Port Charge Pump <1.0 <1.0 * <1000 <1000 Room(B)

Starboard Charge <1.0 <1.0 <1000 <1000 Pump Room (B)

Cold Chemistry <1.0 <1.0 <1000 <1000 Lab and Rad Monitoring Rm C-Deck Radiation <1.0 <1.0 <1000 <1000 Sampling Room D-Deck (B)

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 Appendix A CY2019 Radiation Survey Results in Radiologically Controlled Areas Area General Area Highest General Area Highest Radiation Radiation Level Contamination Contamination levels mR/hr mR/hr (milli- Level Level 2

(milli-R/hr) R/hr) (DPM/100cm2) (DPM/100cm )

Gas Adsorption <1.0 <1.0 <1000 <1000 Room D-Deck (B)

Cargo Hold 4 C- <1.0 <1.0 <1000 <1000 DeckLLRW Storage Port Cargo Hold 4 C- <1.0 <1.0 <1000 <1000 DeckLLRW Storage Starboard Cargo Hold 4 D- I

<1.0 <1.0 <1000 <1000 DeckLLRW Storage NEWSDDeck <1.0 <1.0 <1000 * <1000 Rad Storage Pathway from <1.0 <1.0 <1000 <1000 Cold Chemistry Lab to NEWS Fish Locker <1.0 <1.0 <1000 <1000 Sugar and Flour <1.0 <1.0 <1000 <1000 Stores Stbd Stabilizer <1.0 <1.0 <1000 <1000 Room(B)

Port Stabilizer <1.0 <1.0 <1000 <1000 Room(B)

Horseshoe below <1.0 <1.0 <1000 <1000 deck plants after component removal Hull Survey <1.0 <1.0 <1000 <1000 (Drydock)

Table Data Notes (A) Historical High value since 2013

.(B) Deposted following removal of contaminated components, cleaning and survey.

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SAVANNAH Technical Staff STS - 209, Annual Report for CY2019, Revision 0 Appendix B CY2019 Radiological Environmental Sampling Results APPENDIXB. CY2019 RADIOLOGICAL ENVIRONMENTAL SAMPLING RESULTS Sample Type of Co-60 Cs-137 Sample Location Date sample

<MDA

<MDA [6.5E-02 Pier #13 Canton Marine Terminal, Sediment (minimum pCi/g (C)]

04/04/2019 Baltimore, MD NSS Stbd Side, Aft (A)(B) detectable activity) MDA=

l.26E-01

. l.47E-01 pCi/g (C)

Pier #13 Canton Marine Terminal, Sediment 09/05/2019 <MDA Baltimore, MD NSS Stbd Side, Aft (A)(B)

MDA=

7.96E-02 Pier #13, Canton Marine Terminal, Sediment 4/04/2019 <MDA <MDA Baltimore, MD NSS Port Side, Forward (A)(B)

<MDA

[6.68-02 Pier #13, Canton Marine Terminal, Sediment pCi/g (C)]

09/05/2019 <MDA Baltimore, MD NSS Port Side, Forward (A)(B)

MDA=

8.82E-02 Pier #13 Canton Marine Terminal, Water(A) <MDA <MDA Baltimore, MD NSS Stbd Side, Aft 4/04/2019 Pier #13 Canton Marine Terminal, Water(A) <MDA <MDA Baltimore, MD NSS Stbd Side, Aft 09/05/2019 Pier #13, Canton Marine Terminal, Water (A) <MDA <MDA Baltimore, MD NSS Port Side, Forward 4/04/2019 Pier #13, Canton Marine Terminal, Water(A) <MDA <MDA Baltimore, MD NSS Port Side, Forward 09/05/2019 Table Data Notes (A) Calculated MDAs are a-posteriori values at the 95% confidence level.

(B) Activity is reported on a dry weight basis unless otherwise indicated in the case narrative and is decay corrected to the sample collect date.

(C) Results are statistically positive at the 95% confidence level. (activity is greater than or equal to the two sigma uncertainty)

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