ML22062B046

Us Dept. of Transportation, Maritime Admin., Annual Report for CY202l, Revision 0. STS-217

ML22062B046
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Site:	NS Savannah
Issue date:	02/28/2022
From:	US Dept of Transportation, Maritime Admin
To:	Office of Nuclear Reactor Regulation
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ML22062B163	List: ML22062B038 ML22062B046
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U.S. Department of Transportation Maritime Administration N.S. SAVANNAH ANNUAL REPORT FOR CY2021 STS - 217 Revision 0 Approved: Date:

Manager, N.S. SAVANNAH Programs Prepared by:

Nuclear Ship Support Services, LLC

SAVANNAH Techn ical Staff STS - 217, Annua I Report for CY2021, Revision 0 RECORD OF REVISIONS Revision Summary of Revisions 0 The original version of the 2021 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 - 217, Annual Report for CY2021, 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. I .2 Organization 5 2.1.3 Review of Other Technical Specification Requirements 6 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.d. Quaiterly Intrusion Alarm System Checks 7 2.4 TS 3 .4.2.1.f. Principal Decommissioning and Maintenance Activities 8 2.5

• TS 3.4.2.1.g. Unauthorized Entry Into Radiologically Controlled Areas (RCAs) 9 2.5.1 Event Discussion 9 2.5.2 Improvements to Access Control 9 2.6 TS 3 .4.2.1.h. Inspection of Primary, Secondary and Auxiliary Systems Degradation 9 2.7 TS 3.4.2.1.i. Summary of Occupational Exposure 9 3.0 OTHER NRC REPORTS 9 3.1 10 CFR 50.59(d)(2) Report of Changes, Tests or Experiments 9 3.2 IO CFR 50.54(w)(3) Insurance Annual Report 9 3.3 Commitment Management 9 4.0 SIGNIFICANT MARAD ISSUES 10 4.1 Remaining Decommissioning Timeline 10 4.2 Decommissioning Project Milestone 10 4.3 Public Events, Visitation and Training 10 4.4 Historic Stewardship 10 4.5 National Historic Preservation Act Consultation 10 4.6 COVID-19 Pandemic National Emergency 10

5.0 REFERENCES

11 APPENDIX A. CY2021 Radiation Survey Results in Radiologically Controlled Areas 12 Revision 0 3

SA VANNAH Technical Staff STS - 217, Annual Report for CY2021, Revision 0

1.0 INTRODUCTION

This Annual Rep01i is submitted by the Maritime Administration (MARAD) as licensee for the Nuclear Ship SAVANNAH (NSS) and covers the Calendar Year (CY) 2021 reporting period. This rep01i is arranged into three sections following the introduction. Section 2.0 provides the discussion of the various repotiing 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, including the COVID-19 pandemic national emergency.

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) repo1iing 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 (IO) 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 seven (7) 1 TS 3.4.2.1 items specifically required to be included in the written annual rep01i 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 quaiierly 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 14, 2021 and by the Executive Steering Committee members during its concurrence routing prior to submission of this annual repo1i to the NRC.

2.1 TS 3.4.2.1.A. STATUS OF THE FACILITY During CY2021, the ship was berthed at Pier 13, Canton Marine Terminal, 4601 Newgate A venue, Baltimore, MD.

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 I .86 was withdrawn as noticed in the Federal Register (81 FR 53507) on August 12, 20 I 6 and that its withdrawal does not impact the 1

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

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SA VANNAH Technical Staff STS - 217, Annual Report for CY202J, 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 on board the ship, and custody and mainteiiance of the ship as the primary physical boundary and protective barrier of the licensed site.

Decommissioning activities conducted during the repo1iing period are described in Sections 2.1.1 and 2.5 below.

2.1.1 LICENSE ACTIVITIES On March 18, 2021, License Amendment 18 (Reference c) was issued. It revised the Technical Specifications to (I) remove a redundant environmental sampling rep01iing requirement, (2) remove a redundant access control requirement, and (3) modify the draft monitoring surveillance by removing references to fixed hull stripes that are inconsistent with active decommissioning ship conditions.

On May 3, 2021, Revision 11 of the Updated Final Safety Analysis Repo1i (Referenced) was submitted. It included the effects of the following:

• All changes made in the facility or procedures as described in the UFSAR;

• All safety evaluations performed to suppo1i license amendments; and,

• All analyses of new safety issues performed by or on behalf of the licensee at Commission request.

On July 23, 2021, Updated Final Safety Analysis Report, Revision 12 and Decommissioning Quality Assurance Plan, Revision 3 (Reference e) were submitted to reflect organizational changes resulting from the new integrated services contract (see 2.1.2 ORGANIZATION).

MARAD requested two License Termination Plan (LTP) pre-submittal meetings; these were held on June 30 and November 17, 2021. The June meeting focused on updating the project status since the previous LTP meeting in November 2019; laying out a notional schedule for the NSS LTP development and submittal; discussing the format of the LTP submittal; reviewing MARAD's LTP Acceptance Criteria Review Matrix (ACRM); and provided an overview of the end-state scenarios being considered by MARAD. The November meeting was a dose modeling workshop based on the preservation and shipbreaking end states.

On October 15, 2021, MARAD submitted a revised license termination schedule (Reference t) as an update to the Post Shutdown Decommissioning Activities Rep011 (PSDAR).

2.1.2 ORGANIZATION There were significant organizational changes during 2021. The Maritime Administration (MARAD) has awarded a five-year integrated services contract to Nuclear Ship Suppo1i Services (NSSSJV)2, LLC, of Seabrook, New Hampshire. The contract Notice to Proceed (NTP) was April I, 2021. The prime contractor, NSSSJV, is a Joint Venture between Radiation Safety and Control Services (RSCS), of New Hampshire and Energy Solutions Federal Supp01i (ESFS), of Utah. Keystone Shipping Co. of Bala Cynwyd, PA is a principal subcontractor to NSSSJV to perform the marine services of ship husbandry and custodial care. The contract is in the same general form and provides the same baseline services as those in previous contracts.

' Because the acronym NSSS is very close to the accepted three-letter-acronym NSS (for Nuclear Ship Savannah), MA RAD will add the letters JV lo more easily distinguish the contractor from the ship.

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SA VANNAH Technical Staff STS - 217, Annual Report for CY2021, Revision 0 The 2018 bridge contract awarded to TOTE Services on September 28, 2018 [see Annual Repo1t for CY2018 (Reference g)] was extended to remain in effect through March 31, 2021 It was extended for an additional one month for ship husbandry services only, ending on April 30, 2021.

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 CY 2021.

Although not a TS change, the SRC was briefed on two options for the form of the LTP submission as a license amendment request. One option involves requesting conditions to be added to the license governing changes to the LTP after its approval by the NRC.

The other option involves referring to a change process chapter in the L TP itself. After

• discussion, the latter course was determined to be the preferred option, and the L TP is being developed accordingly.

b. Evaluations required by JO 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 repo1i.

c. Proposed changes or modifications to a Radiologically Controlled Area entry alarm

.5yste111 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 2.5 ofthis repo1t.

d. Evaluations of substantive changes to the results of radiological surveys There were no substantive changes to the results of radiological surveys.

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 repmiable violations to Technical Specifications in 2021.

g. Evaluations of~*eportable events per TS 3.4.3.1 There were no NRC reportable events in CY2021.

h. Evaluations of deviations allowed by TS 3. 7.1. 7 One new deviation was approved in 2021:

• STS-004 Deviation - Deviation from Technical Specifications 3.7.1.2 and 3.7.1.5, Rev. 1 for B Deck Reactor Compartment Door at Frame 122, the C Deck Door to the Cold Chemistry Laboratory and the D Deck Containment Vessel (CV) Door at Frame 109.

Other deviations in effect at the end of CY 2021:

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SA VANNA I-I Technical Staff STS - 217, Annual Report for CY2021, Revision 0

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

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

1. Audits and se(fassessments to verifj1 the effectiveness of the Decommissioning Quality Assurance Plan Assessments were performed in the following functional areas in the reporting period:

• QSA-2021-001, Procedure Annual Review 2020

• QSA-2021-002, I st Qtr., 2021 First Quarter Radiation Protection Program Assessment

• QSA-2021-002, 2nd Qtr., 2021 Second Quarter Radiation Protection Program Assessment,

• QSA-2021-002, 3rd Qtr., 2021 Third Qumier Radiation Protection Program Assessment

• QSA-2021-002, 4th Qtr., 2021 Fomih Qumier Radiation Protection Program Assessment

• QSA-2021-003, Commitment Periodic Review 2021

• QSA-2021-004, Technical Specification 3.7.1.7 Deviations Review 2021 J. Annual reports to the NRC During CY2021, the following repotis were reviewed prior to their submission to the NRC:

• Annual Repoti for CY2020 (STS-214 ).

• Decommissioning Funds Status Repoti for CY2020 (STS-215).

• Annual Radiological Environmental Monitoring and Radioactive Effluent Release Reports for CY2020 (STS-216).

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 CY2021. 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 CY2021 Radiation Survey Results in RCAs are listed in Appendix A.

2.2.2 MONITORING STATION DOSIMETER RESULTS At the beginning of CY 2021, there were 45 permanently placed thermo-luminescent dosimeter (TLD) monitoring stations dispersed throughout the non-RCAs of the NSS and in those areas of the NSS that are routinely occupied. During 2021 Q3, an additional 13 TLD monitoring stations were established bringing the total number of monitoring stations to 58. 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 wem/hr (micro-rem/hr).

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.

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SA VANNA/-/ Technical Staff STS - 217, Annual Report for CY2021, Revision 0 2.4 TS 3.4.2.1.F. PRINCIPAL DECOAJMISSIONING AND MAINTENANCE ACTIVITIES The following principal decommissioning activities were completed in CY2021:

Completed the final acceptance testing of the Decommissioning Heating Ventilation and Air Conditioning (DHVAC) System.

Completed modifications and outfitting to Cargo Holds (CH) 3 and 4 supporting dismantlement:

• Modified Radiologically Controlled Area (RCA) boundaries to create a new RCA control point for primary access to the CV, Reactor Compartment Lower Level (RCLL), and Waste Material Handling, Storage and Packaging areas in Cargo Holds 4 and 3.

• Constructed a new Personnel and Material Handling Access connecting the RCLL and CH 4 Tank Top.

• Constructed a Contaminated Liquid Transfer and Holding System that included: I) reactivating the Containment Drain Tank as a collection tank for drained primary coolant in the CV; 2) establishing temporary liquid storage locations for other fluid systems drained in the CV and RCLL; 3) providing pumps and piping to connect to a collection bladder located in CH 3 D Deck; and 4) providing a discharge pump, recirculating piping and a discharge connection for transfer of collected liquids to tanker trucks on the pier.

• Completed final access and egress ladder arrangements in CH 4 to suit the new RCA boundary.

• Completed outfitting in the CH 3, C Deck Training area.

• Established Solid Waste Material Handling and Packaging operations in CH 4 11 Verified Reactor Compaiiment (RC) and CV De-Energization of original power supplies

• Installed temporary 480 volt electricity and utilities for work in the CV

" Began dismantlement activities with removal of small bore piping, electrical cabling, ventilation ductwork and other interferences inside the CV. This interference removal activity began in September and was completed in December.

'" Decontaminated Forward Control and the Port Stabilizer Room, as needed.

The following principal maintenance activities were completed in CY 2021:

11 Performed marine services of ship husbandry and custodial care (including maintenance of mooring systems and equipment; minor steel and equipment repairs; and, hull preservation and painting).

Maintained and repaired lighting and electrical distribution systems.

Performed repairs to the anchor windlass hydraulic systems.

" Performed troubleshooting and minor repairs of the impressed current cathodic protection system (note that the system remained functional and the hull was protected throughout the yearj.

• Performed American Bureau of Shipping Annual Survey of Lay-up.

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SAVANNAH Technical Staff STS - 217, Annual Report for CY2021, Revision 0 2.5 TS 3.4.2.1.G. UNA UTHORJZED ENTRY INTO RADIOLOGICALLY CONTROLLED AREAS (RCAS)

No unauthorized entries were made into any RCAs in CY202 l.

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 on December 20, 2021. It is documented in SIC-TS-A-2 RO Structures, Systems and Components Annual Inspection 2021. There was no notable degradation of the primary, secondary or auxiliary systems since the last inspection in 2020.

2.7 TS 3.4.2.1.I.

SUMMARY

OF OCCUPATIONAL EXPOSURE Because the NSS has been permanently shutdown for more than 50 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 2021, the number of individuals monitored with TLDs during their entries into RCAs was I 04. No individual received more than 10 mrem from occupational sources during the monitoring period.

3_.0 OTHER NRC REPORTS 3.1 JO CFR 50.59(D)(2) REPORT OF CHANGES, TESTS OR EXPERlll1ENTS 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 CY2021 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 COMA1/TMENT MANAGEMENT One Regulatory Commitment was made in CY202 I and met before its due date. The commitment was made in Reference (h) where MARAD committed to submit organizational updates to its Updated Final Safety Analysis Repo1i and Decommissioning Quality Assurance Plan. The one time commitment was rep01ied as complete in Reference (e).

No Regulatory Commitments were revised in CY 2021.

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SA VANNAH Technical Staff STS - 217, Annual Report for CY2021, Revision 0 4.0 SIGNIFICANT MARAD ISSUES 4.1 REMAINING DECOMA11SSJONING TIMELINE The license termination deadline for the NSS is December 3, 203 I 3, based on the Permanent Cessation of Operations milestone date of December 3, I 971. On December 3, 202 I, MA RAD observed the fiftieth anniversary of Permanent Cessation of Operations at the American Nuclear Society Winter Meeting in Washington, DC. Decommissioning is on schedule to be complete well within the allowed 60-year Iicense termination period.

4.2 DECOA1MJSSIONJNG PROJECT A1ILESTONE With the final acceptance testing of the DHY AC system, MARAD's DECON Phase I activities were formally concluded. This milestone occurred within a few weeks of the contract award for Phases II and II I.

4.3 PUBLIC EVENTS, VISITATION AND TRAINING As a result of the CO YID 19 Pandemic, MA RAD continued the suspension of its traditional program of public access and training support for local, state and federal agencies during CY2021.

4.4 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 Transpo1tation 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 ofNHLs. 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 expett advice and guidance to licensee staff in these matters, paiticularly with respect to the implementation of the Secretary of the Interior's Standards for the Treatment of Historic Propetties and Historic Vessel Preservation Projects.

4.5 NATIONAL HISTORIC PRESERVATION ACT CONSULTATION As discussed in previous annual repo1ts, MA RAD 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 is one of four federal agencies and state organizations that are parties to the consultation. 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. Consulting effo1ts were affected by the pandemic, and completion of a Programmatic Agreement (PA) to cover the aspects of the undertaking were still incomplete at the end of the CY2021 reporting period.

4.6 COVID-19 PANDEMIC NATIONAL EMERGENCY The COVID-19 access controls and other return to work (RTW) conditions remained in effect throughout CY 2021. Significant revisions to both the access controls and RTW conditions were implemented based on the vaccination-related executive orders promulgated by the President. The shipboard complement limit was maintained at fo1ty-five (45) persons throughout CY2021.

On November 29, 2021, the Depattment of Transpo1tation released its updated COYID-19 Workplace Safety Plan, which allowed for the relaxation of maximum telework and return of the MARAD workforce effective on January 17. Although ce1tain RTW conditions were planned to be relaxed on NSS on 3

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.

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SA VANNAH Technical Staff STS - 217, Annual Report for CY2021, Revision 0 January 17, including the fo1iy-five (45) person shipboard complement limit, the resurgence of COVID through the Omicron variant led to an indefinite postponement of those plans in early .January. NSS pandemic access controls are partially controlled by the U.S. Coast Guard's Marine Safety Information Bulletin (MSIB) covering masking and physical distancing protocols on transpo1iation conveyances. At the time of this report submittal, the MSIB is scheduled to remain in full effect through mid-March, 2022.

5.0 REU'ERENCES

a. Letter from Mr. John B. Hickman (NRC) to Mr. Erhard W. Koehler (MARAD), dated April 23, 2018, Nuclear ShijJ SA l'ANNAH - Issuance Of Amendment I 5 to revise the License lo allow Dismantlement and Di()posal

b. Regulato1y Guide I .86, Termination of Operating Licenses.for Nuclear Reactors, June 1974

c. Letter from Mr. Theodore B. Smith (NRC) to Mr. Erhard W. Koehler (MA RAD), dated March 18, 2021, Nuclear Ship SAVANNAH - Issuance ofA111endment 18 to revise the Technical Specifications to Re111ove Redundant Reporting and Control Requirements and Eliminate the Requirement for a Draft Hull Stripe

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

dated May 3, 2021, Submittal of Updated Final Safety Analysis Report, Revision 11

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

dated July 23, 2021, Submittal of Updated Final Safety Analysis Report, Revision 12 and Deco111111issioning Quality Assurance Plan, Revision 3

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

dated October 15, 2021, Revised License Termination Schedule

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

dated February 27, 2019, Annual Report.for CY2018, Revision 0

h. Letter from Mr. Erhard W. Koehler (Maritime Administration) to Document Control Desk (NRC) dated April 30, 2021, Notice of Management Contract Award Revision 0 11

SA VANNAH Technical Staff STS- 217, Annual Report for CY202J, Revision 0 Appendix A CY2021 Radiation Survey Results in Radiologically Controlled Areas APPENDIX A. CY2021 RADIATION SURVEY RESULTS IN RADIOLOGICALLY CONTROLLED AREAS Area General Area Highest General Area Highest Radiation Radiation Level Contamination Contamination levels mrem/hr mrem/hr Level Level (milli-rem/hr) (milli-rem/hr) (DPM/100cm 2) (DPM/100cm 2 )

Reactor <1.0 <1.0 <1000 ..::::1000 Compartment Cupola Level A Deck Reactor <1.0 <1.0 <1000 <1000 Compaiiment Upper Level 8 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 2.0 15 <1000 <1000 Compartment Contact on Lower Level Fwd overhead line Reactor <1.0 <1.0 <1000 <1000 Compa1iment Lower Level Aft Containment <1.0 <1.0 <1000 <1000 Vessel 1st Level Containment 1.0 1.6 <1000 <1000 Vessel 2nd Level Containment 1.7 2.5 <1000 <1000 Vessel 3rd Level Containment <1.0 <1.0 <1000 <1000 Vessel 4th Level 4.5 between U tube of both steam generators Cold Chemistry Lab and Rad Down posted (CCL Door locked per Tech Spec Req.)

Monitoring Rm C-Deck Radiation <1.0 <1.0 <1000 15200 loose surface Sampling Room on floor at Stbd D-Deck corner Gas Adsorption Down posted (Encompassed within CCL Door, locked per Tech Spec Req.)

Room D-Deck Revision 0 12

SAVANNAH Technical Staff STS - 217, Annual Report for CY2021, Revision 0 Appendix A CY2021 Radiation Survey Results in Radiologically Controlled Areas Area General Area Highest General Area Highest Radiation Radiation Level Contamination Contamination levels mrem/hr mrem/hr Level Level (milli-rem/hr) (milli-rem/hr) (DPM/100cm 2) (DPM/100cm 2)

Cargo Hold 4 D- <1.0 <1.0 <1000 <1000 Deck LLRW Storage NEWS D Deck <1.0 <1.0 <1000 <1000 Rad Storage Sugar and Flour <1.0 <1.0 <1000 <1000 Stores Hull Survey <1.0 <1.0 <1000 <1000 (Drydock)

Po1i Stabilizer <1.0 <1.0 5000 loose surface . <l 000 loose surface Rooms posted as a 2000 fixed on tank Rad Material Area top (A)

Starboard <1.0 <1.0 <1000 <1000 Stabilizer Room posted as a Rad Material Area (8)

Table Data Notes (A) On January 8, 2021, loose surface contamination was discovered and documented in Corrective Action Report (CAR) 2021-002). The room was decontarn inated to

< 1000 DPM/100cm 2 in March 2021. Residual activity remained and the area was posted as Radioactive Material. Subsequently, recontamination was discovered in October 2021 under a leaking pipe cap and is documented in CAR 2021-084. The pipe and contaminated floor have been bagged and the contaminated floor has bee11 covered in yellow polyethylene. The area is tagged as "Caution Radioactive Material."

Remediation of the area is expected in the first quarter of 2022 and is tracked by Comprehensive Action Item Tracking (CATS) Number 5484.

(8) Posted as Rad Material Area due to the common tunnel connecting the two stabilizer rooms, due to survey identifying fixed contamination on p01i side on 1/8/2021.

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