ML110610343

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Savannah - Annual Report for Cy 2010, Revision 0
ML110610343
Person / Time
Site: NS Savannah
Issue date: 02/28/2011
From: Koehler E
US Dept of Transportation, Maritime Admin
To:
Document Control Desk, NRC/FSME
References
STS-131
Download: ML110610343 (19)
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Text

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

February 28, 2011 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 CY 2010, 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 0 to the CY 2009 Annual Report 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) Insurance 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, and/or e-mail me at 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 CY 2010, Revision 0 February 28, 2011

Enclosure:

1. Annual Report for CY 2010, Revision 0 2 Docket No. 50-238; License NS-1; N.S. SAVANNAH Submittal of Annual Report for CY 2010, Revision 0 February 28, 2011 cc: Electronic copy NSS ESC NSS SRC MAR 610, 612, 615 Hardcopy, cover letter only MAR-600, 640, 640.2 Hardcopy w/ all enclosures MAR-100, 640.2 (if)USNRC (John T. Buckley, Mark C. Roberts)USNRC Regional Administrator

-NRC Region I MD Department of the Environment (Roland G. Fletcher; George S. Aburn, Jr.)NC Department of Environment

& Natural Resources (Beverly 0. Hall)SC Department of Health & Environmental Control (Susan E. Jenkins; Aaron Gantt)VA Department of Emergency Management (Michael M. Cline)VA Department of Health (Leslie P. Foldesi)EWK/jmo 3 U.S. Department of Transportation Maritime Administration SAVANNAH Technical Staff Office of Ship Disposal 1200 New Jersey Ave., SE Washington, DC 20590 Docket No. 50-238; License No. NS-1; N.S. SAVANNAH Enclosure 1 to Submittal of Annual Report for CY 2010, Revision 0 4 U.S. Department of Transportation Maritime Administration Office of Ship Disposal N.S. SAVANNAH ANNUAL REPORT 2010 STS- 13 1 Revision 0 AApproved:

.._SVNqIIPrograms

"'Manager, N.S. SAVANNAH Programs Prepared by: Sayres and Associates Corporation SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 RECORD OF REVISIONS Revision Summary of Revisions 0 The original version of the 2010 Annual Report License NS-1 Revision 0 2 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 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 14 0 15 0 Revision 0 3 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 Table of Contents

1.0 INTRODUCTION

5 2.0 ITEMS REQUIRED BY TECHNICAL SPECIFICATION 3.4.1 5 2.1 Status of the Facility 5 2.1.1 License Activities 5 2.1.2 Organization 6 2.1.3 Review of Other Technical Specifications Requirements 6 2.1.4 Decommissioning Planning Activities 7 2.1.5 SAVANNAH Emergency Radiological Assistance Team (SERAT) 7 2.2 Radiation Surveys and Monitoring Station Dosimeter Readings 7 2.2.1 2010 Radiation Survey Results in Radiologically Controlled Areas 8 2.2.2 Monitoring Station Dosimeter Results 10 2.3 Environmental Sample Analysis Surveys 10 2.4 Quarterly Intrusion Alarm System Checks 11 2.5 Radioactive Materials Removed by Releases, Discharges and Waste Shipments 11 2.5.1 Releases 11 2.5.2 Discharges 11 2.5.3 Shipments 11 2.6 Principal Maintenance and Related Activities 11 2.6.1 American Bureau of Shipping (ABS) Surveys 11 2.6.2 ABS Classification Certificate 11 2.6.3 Fire, Smoke, Flooding and Intrusion Detection and Alarm System 12 2.6.4 Electrical Load Center for Shore Power Distribution 12 2.6.5 Underwater Hull Survey 12 2.6.6 Reactor Space Ventilation (RSV) System 12 2.6.7 Emergency Lighting 13 2.7 Unauthorized Entry Into Radiation Control Areas and Corrective Actions Taken to Improve Access Control 13 2.7.1 Event Discussion 13 2.7.2 Improvements to Access Control 13 2.8 Inspection of Boundaries Containing Radioactive Materials 13 2.9 Summary of 2010 Occupational Exposure 13 3.0 OTHER NRC REPORTS 13 3.1 10 CFR 50.59 Biennial report 13 3.2 Summary of Technical Specification Deviations 14 3.3 Decommissioning Funding Status 14 3.4 10 CFR 50.54(w)(3)

Insurance Annual Report 14 4.0 SIGNIFICANT MARAD ISSUES 14 4.1 Public Events and Visitation 14 4.2 Historic Stewardship 14

5.0 REFERENCES

15 Revision 0 4 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0

1.0 INTRODUCTION

In accordance with the requirements of Technical Specification 3.4.2, an annual written report shall be submitted prior to March 1 of the following calendar year.This report is arranged into two sections.

Section 2.0 provides a discussion of the nine items required by the Technical Specifications.

Section 3.0 provides a discussion of other issues.2.0 ITEMS REQUIRED BY TECHNICAL SPECIFICATION 3.4.1 The report shall include the following:

a. The status of the facility.b. The results of the radiation surveys and monitoring station dosimeter readings.c. The results of environmental sample analysis surveys.d. The results of quarterly intrusion alarm system checks.e. The amount of radioactive materials removed from the N.S. SAVANNAH (NSS) by releases, discharges, and shipments of radioactive waste material.f. A description of the principal maintenance performed on the vessel.g. Any unauthorized entry into radiation control areas by visitors or employees and corrective action taken to improve access control.h. Any degradation of one of the several boundaries which contain the radioactive materials aboard the NSS.i. Results of occupational exposure indicated by personal dosimetry.

2.1 Status of the Facility During 2010, the NSS has remained "Mothballed" per the requirements of Regulatory Guide (RG) 1.86,'Termination of Operating Licenses for Nuclear Reactors," Reference (a). This state of protective storage was approved in Reference (b). This RG describes the now outmoded Mothballing option of protective storage.During calendar year (CY) 2010, the ship was berthed at Pier 13, Canton Marine Terminal, 4601 Newgate Ave., Baltimore, MD.Similar to 2007 through 2009, MARAD and contractor personnel were routinely on board the NSS during normal workdays throughout 2010. This regular attendance had the beneficial effect of improving the ship's physical condition and improving staff proficiency with the conduct of licensed activities.

2.1.1 License Activities MARAD completed one significant licensing action in 2010:* Response to Revised Power Reactor Security Rule to Request an Exemption from 10 CFR Part 73 and 10 CFR 5 0.54(p), November 8, 2010.MARAD continued developing and implementing a prioritized procedure and process development program.The USNRC conducted no facility inspections during CY 2010.Revision 0 5 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 2.1.2 Organization In 2010, MARAD made no substantial changes to the organization.

The Nuclear Advisor position was filled in February 2010; that individual also serves as acting Facility Site Manager. By mutual agreement between MARAD and the contractor, Areva Federal Services, Inc., the Engineering, Management and Oversight Services (EMOS) contract was allowed to expire at the end of its option year (December 31, 2010). There has been no activity on the contract in the most recent option year, and no work is projected in the upcoming period due to constrained project funding.2.1.3 Review of Other Technical Specifications Requirements In accordance with the NSS Technical Specification 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.

No changes were proposed to the Technical Specifications in CY 2010.b. Evaluations required by 10 CFR 50.59.In addition to Technical Specification review requirement by the Safety Review Committee, this paragraph is also intended to meet the reporting requirement of 10 CFR 50.59(d)(2) to provide 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 2010 that would require a 50.59 evaluation.

c. Proposed changes or modifications to a Radiological Controlled Area entry alarm system or reactor containment vessel system.Changes to the Alarm System were completed in 2010. The new system and the previous security system are functional.

There were no changes to a reactor containment vessel system.d. Evaluations of substantive changes to the results of radiological surveys.There were no substantive changes to the results of radiation surveys.e. Procedures and revisions per Technical Specification 3.5.Per Technical Specification 3.5, procedures and their revisions were reviewed prior to approval.f. Evaluations of reported violations of Technical Specifications.

Two violations were identified during the calendar year and reported via Corrective Action Reports. The first event involved a visitor not being properly escorted as required by Technical Specification 3.3.2.2: 0 Visitors shall be escorted by MARAD's designated personnel.

This event was reported on CAR 2010-035.

The Safety Review Committee reviewed the evaluation of the violation and the corrective actions taken by licensee staff.The second event involved a delayed procurement action by MARAD, which resulted in a one-week period during which emergency radiological protection was contractually not available to meet the requirements of Technical Specification 3.1.5:* MARAD shall have a health physicist on duty or on call within two hours to provide health physics support and direction for radiological emergencies.

Revision 0 6 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 A Safety Review Committee teleconference was convened upon discovery of this issue, and immediate corrective action was completed on the same day. This event is documented on CAR 2010-039.g. Evaluations of reportable events per Technical Specification 3.4.3.1.There were no reportable events during the reporting period.h. Evaluations of deviations allowed by Technical Specification 3.7. 1.7.All deviations were reviewed prior to implementation.

The following limited duration deviations were used as needed in the reporting period: " Alarm Systems -Testing, Maintenance (Troubleshooting

/ Repair) and Modification.

  • Loss of Electrical Power." Failure to patrol the vessel at least once during a twenty-four (24) hour period per Technical Specification 3.7.1.6 (Severe Weather prevents daily security patrols).i. Audits and self assessments to verify the effectiveness of the Decommissioning Quality Assurance Plan.Self assessments were performed in the following functional areas in the reporting period:* MARAD Program Excellence and Quality Assurance Group (PEQAG) review of NSS Programs;* License Compliance;" License Termination Compliance;
  • Radiological Program;* RCA Boundary Inspection;" Security Compliance; and,* Technical Specification Deviations.
j. Annual reports to the NRC The CY 2009 Annual Report was reviewed prior to its submittal on February 26, 2010.2.1.4 Decommissioning Planning Activities Decommissioning planning during the reporting period focused on reviewing and updating decommissioning plans and cost estimates.

2.1.5 SA VANNAH Emergency Radiological Assistance Team (SERAT)There were no significant changes to the staff or changes to the ship location.

All SERAT members are located within a 2-hour response radius of the ship's current location.2.2 Radiation Surveys and Monitoring Station Dosimeter Readings A routine radiological survey program continued to be followed in 2010. Radiological survey measurements were taken in various non-Radiological Controlled Areas and Radiological Controlled Areas. There were no significant changes found in 2010. All readings in non-Radiological Controlled Areas were insignificant as compared to background radiation levels.Revision 0 7 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 2.2.1 2010 Radiation Survey Results in Radiologically Controlled Areas General Area Highest General Area Highest Area Radiation levels Radiation Contamination Contamination ttR/hr (micro- Level piR/hr Level Level R/hr) (micro-R/hr) (DPM/100cm

2) (DPMI100cm 2)Reactor Compartment 1.0-4.0 10 <1000 <1000 Cupola Level Reactor Compartment 15 at open hatch R er Level 1.0- 1.5 to Reactor <1000 <1000 Upper Level vessel Reactor Compartment Forward Middle Level 1.5 1.5 <1000 <1000 Reactor Compartment 1-2.5 10 on hose <1000 <1000 Aft Middle Level 120,000 on contact with Reactor Compartment 40 -4000 pipe 8 ft in <1000 4041 inside Lower Level overhead; drum 10,000 @ 30 cm.Containment Vessel 150-4502500 along Dr 1st Level 2500 -long <1000 <1000 V LevelSteam Drum Containment Vessel 4000 -5000 2 nd Level 150 -2000 along Steam <1000 <1000 Drum 12000 on Containment Vessel contact with 3rd Level 200-4000 Steam <1000 <1000 Generator; 8000@30cm 80,000 on Containment Vessel contact with 4092 STBD 4h Level pipe; 10,000 side off Deck@30cm 150 to 250 on Port Charge Pump Room 1.5-40 contact with <1000 <1000 pump suction line Revision 0 8 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 General Area Highest General Area Highest Area Radiation levels Radiation Contamination Contamination pR/hr (micro- Level fiR/hr Level Level R/hr) (micro-R/hr) (DPM/100cm
2) (DPM/100cm 2)100 to 180 on Starboard Charge Pump 1.0 -25 contact with <1000 <1000 Room pump suction line 4.0 on contact with sink drain Hot Chemistry Lab 1.7 trap shielding.

<1000 <1000 25 on contact with trap.30 on contact with Steam Health Physics Lab 2.0 -4.0 Generator

<1000 <1000 Primary Side Samples Port Stabilizer Room 1.0-4.5 6.0 grate level <1000 <1000 1000 on contact Port Booster Pump Area 4.0-30 with piping with <1000 <1000 30cm readings up to 150.Starboard Stabilizer Room .05 -1.5 1.5 lower level <1000 <1000 off walkway Stateroom B-1 Rad Waste 2.0-5.0 10 <1000 <1000 Storage Area Fan Room B Deck 1.0-2.0 2.0 <1000 <1000 Cold Chemistry Lab Area 1.5-6.0 26 on contact <1000 <1000 C Deck with the floor 3200 on contact 5139 inside Sample Room D-Deck 20 -500 with overhead <1000 sample sink line Gas Absorber Room 450 on Suction <1000 D-Deck 4Strainer 150 on contact Cargo Hold D Deck <1.0 -6.0 behind aft deck <1000 <1000 plates along Port side Revision 0 9 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 General Area Highest General Area Highest Area Radiation levels Radiation Contamination Contamination ptR/hr (micro- Level pR/hr Level Level R/hr) (micro-R/hr) (DPMI100cm

2) (DPM/100cm 2)Hold Deck Aft of Reactor 50 on contact space port side with piping N/A N/A under the deck plate 2.2.2 Monitoring Station Dosimeter Results Forty-six (46) permanently placed thermoluminescent dosimeter (TLD) monitoring stations are dispersed throughout the non-radiological controlled areas 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 KR/hr (micro-R/hr).

2.3 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 and potential ship's movement to new piers.The environmental sample results indicate that the radiological conditions in the environment surrounding NSS are insignificant as compared to expected background conditions.

Therefore, based on the results of the radiological environmental monitoring program, NSS operations did not have any adverse effects on the health and safety of the public or on the environment in 2010.2010 RADIOLOGICAL ENVIRONMENTAL SAMPLING RESULTS Sample Location Sample Type of Co-60 Cs-137 Date sample Pier #13 Canton Marine Terminal, 3.02E-02 1.48E-01 Baltimore, MD NSS Port Side (Mid) 05/19/2010 Sediment (A) pCi/g (B) pCi/g (C)Pier #13 Canton Marine Terminal, 2.50E-02 1.49E-0I Baltimore, MD NSS Port Side (Aft) 05/19/2010 Sediment (A) pCi/g (B) pCi/g (C)Pier #13, Canton Marine Terminal, 3.74E-02 6.40E-02 Baltimore, MD NSS Port Side (Fwd) 11/18/2010 Sediment (A) pCi/g (B) pCi/g (B)Pier #13, Canton Marine Terminal, 7.23E-02 7.67E-01 Baltimore, MD NSS Port Side (Aft) 11/18/2010 Sediment (A) pCi/g (B) pCi/g (B)Pier #13 Canton Marine Terminal, 05/19/2010 Water 1.50E+00 1.71E+00 Baltimore, MD NSS Port Side (Mid) pCi/L (B) pCi/L (B)Pier #13 Canton Marine Terminal, 05/19/2010 Water 2.23E+00 2.26E+00 Baltimore, MD NSS Port Side (Aft) pCi/L (B) pCi/L (B)Pier #13, Canton Marine Terminal, 11/18/2010 Water 2.90E+00 2.48E+00 Baltimore, MD NSS Port Side (Fwd) pCi/L (B) pCi/L (B)Revision 0 10 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 Sample Location Sample Type of Co-60 Cs-137 Date sample Pier #13, Canton Marine Terminal, 11/18/2010 Water 2.05E+00 1.85E+00 Baltimore, MD NSS Port Side (Aft) pCiIL (B) pCi/L (B)Table Data Notes (A) Sediment samples are reported on a dry weight basis and are decay corrected to the Sample Collect date (B) Calculated MDA as an a-posteriori value at the 95% confidence Level (C) Results are statistically positive at the 95% Confidence level (Activity is greater than or equal to the two sigma uncertainty) 2.4 Quarterly Intrusion Alarm System Checks Routine security surveillances were conducted as required by Technical Specification 3.7.2.1 and the Key and Seal log was reviewed on a quarterly basis. Other monitored doors were tested. Identified deficiencies were corrected on the spot.2. 5 Radioactive Materials Removed by Releases, Discharges and Waste Shipments No radioactive materials were removed from the ship as described below: 2.5.1 Releases There were no releases.2.5.2 Discharges There were no discharges.

2.5.3 Shipments There were no shipments.

2.6 Principal Maintenance and Related Activities The major maintenance activities of CY 2010 continued to focus on routine preventative maintenance, preservation of the ship's structural integrity, and restoration of ship systems and equipment necessary for husbanding the ship and for its long-term retention.

In addition, the following significant discrete activities were performed:

2.6.1 American Bureau of Shipping (ABS) Surveys Annual surveys are being performed as required.

ABS reviewed the electrical load center modification described below in 2.6.4. ABS is currently reviewing the revised electrical one line diagram.2.6.2 ABS Classification Certificate Effective November 18, 2010, the NSS was restored to classification (hull only) by the American Bureau of Shipping (ABS). The hull is classed as a barge in inland / river service for the purpose of providing independent oversight of its material condition and maintenance; the hull envelope serves as the outer perimeter and primary boundary of the licensed nuclear site. ABS issued a classification certificate to document the action; this certificate replaced the previously-issued interim classification certificate.

Revision 0 I1I SA VANNAJI Technical Staff STS -131, Annual Report 2010, Revision 0 2.6.3 Fire, Smoke, Flooding and Intrusion Detection and Alarm System Installation of the Fire, Smoke, Flooding and Intrusion Detection System was completed in 2010. The system includes a complete (U.S. Coast Guard type-approved)

Marine listed Underwriter Laboratories (UL) programmable (addressable)

Detection and Alarm System.The system consists of speaker strobe devices, smoke and heat detectors, pull stations, flood sensors, limit and magnetic switches, control panel (primary and 2 remotes), and ancillary electrical components.

The cables used for these systems are Shielded, Low Smoke, Commercial Marine Type that met IEEE Standard 45 and were USCG and ABS accepted.2.6.4 Electrical Load Center for Shore Power Distribution As an improvement to electrical safety, a significant modification was installed.

As originally designed and installed, the shore power supply is directed to the main switchboards in the main control room with shore power voltage indicated on the main control room console.Engineering walkdowns had concluded that the age and vintage of electrical components precluded cleaning and inspecting the switchboards.

Rerouting shore power to deenergize the main control room provided the most cost effective safety solution to maintaining aging electrical equipment.

The modification included: " Installing a new load center in the battery room located on "C-deck" cross passageway at approximately frame 146." Replacing Lighting Load Panel A-176-4 with Lighting Load Panel 480V, 225A (item #16) located in lighting load center space port-side "A" deck, frame 176." Replacing Lighting Load Panel A-177-2 with Lighting Load Panel 120V, 400A (item #17) located in lighting load center space port-side "A" deck, frame 176." Installing a new Secondary Power Panel "A" to be located on "B" deck at frame 105 in stairwell space port-side." Installing a new Secondary Power Panel "B" to be located on "A" deck in Asst. Pursers room at approximately frame 189 port-side.

Existing loads needed for current activities are wired on to the panels. Future loads will be added as needed. Deenergizing the switch boards in the main control room allows MARAD to electrically insolate unnecessary loads. More importantly, the modification establishes a known electrical plant status that will improve electrical safety. Revision 6 of the FSAR will include this modification.

2.6.5 Underwater Hull Survey An underwater hull inspection survey was accomplished on July 6, 2010. The overall condition of the coating system was found to be good, with no breakdown.

Moderate marine growth (1/2 inch to 1 inch) was noted to be accumulating on the vessel's hull from the waterline to a depth of approximately 10 feet over the length of the vessel.2.6.6 Reactor Space Ventilation (RSV) System In 2009, the staff investigated water in-leakage in the overhead A Deck starboard passageway near the forward passenger staterooms and discovered significant ventilation duct degradation.

The investigation verified that water in-leakage was from the RSV supply-air housing that is situated on the Promenade Deck, starboard side of the reactor hatch. The housing was deteriorated at the deck edge.The RSV system was deactivated in the mid-1970's, and serves no active function.

It is not planned to be restored to operation.

Revision 0 12 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 In 2009, ship's force installed temporary blanks in the RSV ductwork to prevent further water in-leakage and system degradation.

In 2010, the deteriorated ventilation intake enclosure housing was removed. New deck plating was inserted into the opening in the promenade deck. The insert plating forms the new barrier to isolate the fresh air supply to the RC ventilation system.The ventilation intake enclosure house on the promenade deck was repaired and replaced in its original position to maintain the historic appearance of the deck, in accordance with the Secretary of the Interior's Standards:

for a) the Treatment of Historic Properties, and b)Historic Vessel Preservation Projects.2.6.7 Emergency Lighting US Coast Guard type approved battery powered emergency lighting units were installed throughout the normally occupied areas of the ship.27 Unauthorized Entry Into Radiation Control Areas and Corrective Actions Taken to Improve Access Control No unauthorized entries were made into any Radiological Controlled Area in 2010, 2.7.1 Event Discussion None 2.7.2 Improvements to Access Control None 2.8 Inspection of Boundaries Containing Radioactive Materials The annual inspection required by Technical Specification 3.7.6 was conducted in November and December 2010.There was no notable change in the condition of the primary and auxiliary systems since the last inspection in November 2009.Forward and Aft RCLL Sump levels continue to be monitored quarterly.

We attribute lowering sump levels to the RSV system repair described in 2.6.6.2.9 Summary of 2010 Occupational Exposure As a result of the NSS being in the Mothballed state of protective storage, no individual is expected to receive in one year from sources external to the body, a dose in excess of 10% of the limits specified in 10 CFR 20.1201. Thirty-eight (38) individuals were monitored with TLD and self reading dosimetry during their entries into radiological controlled area. All personnel received zero dose from occupational sources during the monitoring period. Therefore, MARAD has no requirement under 10 CFR 20.1502,"Conditions requiring individual monitoring of external and internal occupational dose," to reasonably anticipate that there is a need to "monitor exposure to radiation and radioactive materials at levels sufficient to demonstrate compliance with the occupational of dose limits." Likewise, MARAD has no requirement under 10 CFR 20.2106, "Records of individual monitoring results," to maintain records of doses when an individual is not required to be monitored.

3.0 OTHER NRC REPORTS 3.1 10 CFR 50.59 Biennial report Historically, the Biennial Summary Report has been included in each Technical Specification Annual Report. No 1OCFR50.59 Evaluations were completed in 2010.Revision 0 13 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0 Many Safety Evaluation Screenings were performed.

An example is the Safety Evaluation Screening performed on the modification to install a new Electrical Load Center for Shore Power Distribution.

This screening determined that no 1OCFR50.59 Evaluation was required.3.2 Summary of Technical Specification Deviations One new Technical Specification Deviation was approved by the SRC on February 5, 2010. The deviation is titled "Failure to patrol the vessel at least once during a twenty-four (24) hour period per Technical Specification 3.7.1.6 (Severe Weather prevents daily security patrols)." This deviation describes how the underlying intent of Technical Specification 3.7.1.5 is met when severe weather prevents daily security patrols. Two deviations were determined to no longer be needed and were deleted: a. Loss of Electrical Power during Ship Movement; and, b. Personnel Performing Security Patrols.3.3 Decommissioning Funding Status Beginning with CY 2009, MARAD no longer included the decommissioning funds status report in the Annual Report. The annual decommissioning funds status report will be submitted independently.

3.4 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.4.0 SIGNIFICANT MARAD ISSUES 4.1 Public Events and Visitation During 2010, the SAVANNAH played host to a number of public events and large group tours for a variety of educational, professional and celebratory purposes.

Access controls and procedures were modified and refined to incorporate lessons learned after each event. Significant events of the year included the observance of National Maritime Day on May 22, and a public visitation in conjunction with the Ninth (triennial)

Maritime Heritage Conference on September

18. Over 500 visitors participated in the various public events during 2010.4.2 Historic Stewardship As a National Historic Landmark (NHL) site, 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.Decommissioning activities are subject to the provisions of the National Historic Preservation Act of 1966, as amended, and MARAD includes such planning and consultation as is necessary to ensure that decommissioning activities are in compliance with all applicable historic preservation statutory and regulatory requirements, as well as the relevant executive orders.Revision 0 14 SAVANNAH Technical Staff STS -131, Annual Report 2010, Revision 0

5.0 REFERENCES

a. Regulatory Guide 1.86, Termination of Operating Licenses for Nuclear Reactors, June 1974 b. Letter from Mr. Robert W. Reid (NRC) to U.S. Department of Commerce, Maritime Administration, dated May 19, 1976, No Title [Issuance of Amendment 8, Possession-only License]c. N.S. SAVANNAH Post Shutdown Decommissioning Activities Report (PSDAR), Revision 1, submitted December 11, 2008 under cover letter from Mr. Erhard W. Koehler (MARAD) to U.S. Nuclear Regulatory Commission.

Revision 0 15

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