10 CFR 50.71(e) - Maritime Administration - U.S. Department of ...

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Updated Final Safety Analysis Report - (STS-004-002)caulking/grouting. These items must be handled and disposed of in accordance with 40 CFR 761 etseq.13.2.5 MercuryAs part of the hazardous materials characterization, thermometers and switches throughout the shipwere inspected in an effort to determine the potential presence of mercury-containing materials.Based on the inspection and former members of the ship’s crew, no mercury-containingthermometers or switches were documented. Visual observations of the thermometers did notsuggest that any thermometers contained mercury. Based on the year of construction and years ofoperation, some fluorescent light bulbs on the vessel may contain mercury.13.3 Updates to Known Radiological ConditionsUpdates to known radiological conditions are provided to the NRC in the Annual Report per theTechnical Specifications. Survey results are available for review at the ship.13.4 References1 Nuclear Ship SAVANNAH Reactor Pressure Vessel Drilling, Sampling and RadiochemicalAnalysis Project Report, Revision 1, dated January 30, 2006.2. NSS Radiological and Non-Radiological Spaces Characterization Survey Report,Revision 0, Sept 22, 2005.3. N.S. SAVANNAH Primary and Secondary Systems Water Level Determination, Revision 0,June 15, 2005.Rev. VI 148
Updated Final Safety Analysis Report - (STS-004-002)14 ACCIDENT ANALYSISChapter 14 is completely rewritten starting in Revision IV of the FSAR to include credible accidents forthe licensed activities following permanent defueling. These accidents replace the operating accidentsdiscussed in Revision III.14.1 OverviewThis chapter analyzes a potential event which could be postulated to occur during licensed activities andresult in the release of radioactive materials. This event includes those with the potential for airborneradioactive releases during decommissioning.The possession-only license allows the following activities:NS-1 License condition C(2) states “The Licensee shall not dismantle or dispose of the facility withoutprior approval of the Commission.” The following Technical Specifications further define and limitactivities that can be performed on the NSS:Technical Specification 1.0 limits the ship to being in a state of protective storage;Technical Specification 2.1 allows only incidental amounts of liquid to be generated in theunlikely event decontamination is found necessary in controlled areas;Technical Specification 2.2 limits radioactive airborne particulate releases to only those thatmay occur due to maintenance requirements such as cutting and welding of contaminatedcomponents.Technical Specification 2.4 limits generation of solid radioactive waste to generaldecontamination of controlled areas, ship surveillance, and entry into controlled areas.The material handling accident, described in 14.4, is a bounding event based on the limited activities thatcan be conducted on the NSS.Other than activities allowed by the Technical Specifications and those associated with inspections toscope and plan decommissioning, no significant decommissioning activities will be performed until theoperating license is amended to allow them. As a result, there are no licensed activities that will createthe potential for accidental releases that could cause doses at the site boundary to be more than a smallfraction of the EPA PAGs.Because no irradiated fuel has been on board the NSS since September 29, 1971, there have been noradioactive noble gases or radioiodines available for release from the facility after that date. This hasprecluded the possibility of accidental offsite radiological releases that could approach the protectiveaction guidelines (PAGs) for the skin and thyroid. As a result, the PAG for total effective dose equivalent(TEDE) is the limiting criteria for decommissioning.Prior to performing significant decommissioning activities, this chapter will be reviewed to ensure thedescribed accidents are bounding. If not, the appropriate analysis will be performed and updated toanalyze a number of potential events which could be postulated to occur during licensed activities andresult in the release of radioactive materials. These events include those with the potential for liquidand/or airborne radioactive releases during decommissioning.The analyses of these events will use conservative approaches in treating the source terms, as well as inthe methods of calculation. To the extent applicable, these analyses are consistent with approaches usedin the NRC’s examination of postulated accidents during the decommissioning of the Reference PWRRev. VI 149
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