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

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Updated Final Safety Analysis Report - (STS-004-002)13 RADIOLOGICAL AND ENVIRONMENTAL CHARACTERIZATIONChapter 13 is a completely new chapter added in Revision IV of the FSAR.13.1 Radiological Characterization Scoping SurveyIn 2005, a radiological and environmental characterization scoping survey of the N.S. SAVANNAH (NSS)was conducted. This characterization task was intended to provide a basis for estimating the cost ofdecommissioning. It is documented in NSS Radiological and Non-Radiological Spaces CharacterizationSurvey Report, Sept 22, 2005, Rev 0.The CV entries associated with this effort were the first in over thirty years. The observed conditionsgenerally supported the reported conditions of 1976. However, discrepancies were noted such aspresence of hydraulic oils, migration of primary system water, significant quantities of trash/debris andsuperficial surface corrosion of components and lighting fixtures.In-depth surveys to determine the extent and types of radioactive materials present were only conductedin those locations and equipment/structures that were expected to be radioactive. The remaining areas(principally aft of the engine room, forward of the reactor compartment, and in the mid-ship-house andpublic areas) were surveyed less rigorously than radiological areas but in sufficient detail to confirm thatno radioactive materials reside in those locations.One hundred eighty-five areas of the NSS were evaluated for radioactivity, including nine decks andseven compartments or areas that span decks vertically. The following sampling was performed:1423 smears surveys;26 paint scrapings;14 metal samples;6 reactor compartment concrete core bores;10 crud (solids) samples from the primary system;4 primary water samples from the steam generators;1 water sample (chromated water over-rinse residue) from the empty primary (neutron) shieldtank; and,11 air samples for radioactive contaminants.Findings of this characterization effort are as follows:Absence of fission products (other than trace quantities of cesium-137), uranium and itsdaughter isotopes, as well as transuranics (e.g., plutonium), indicates there were no significantfuel failures;Crud contribution to total curie content is minimal;No contamination was found in the non-radiological spaces;Minimal contamination was found in radiological spaces;Overall dose rates were much lower than expected;Sites previously identified as radiologically contaminated were found uncontaminated; and,Rev. VI 134
Updated Final Safety Analysis Report - (STS-004-002)Containment vessel systems, structures and components were exceptionally radiologicallyclean.The Characterization Project concluded that the NSS is in very good condition from a radiologicalperspective to support decommissioning. The data obtained in this program may be used to develop thefollowing:Comprehensive decommissioning strategies along with bounding the costs;Effective and appropriate decontamination and dismantling techniques;Activity sequences to support decommissioning;Radioactive material disposal strategies;Assessments of potential hazards during decommissioning and decontamination work todevelop ALARA controls;Accurate schedules; and,Cost estimates of the overall program.13.1.1 Dose RatesFor radiological areas outside of containment and the reactor compartment, general area dose ratesranged from background to 50μR/hour. Contact readings on some pipes reached 2mR/hour.In non-radiological areas, general area dose rates were at or below background, with one exceptionin Cargo Hold 4, where shine from the Cold Water Chemistry Lab, upper level [originally theRadiation Monitoring Room (C-deck level, forward of the reactor compartment Frames 99- 102)].produces approximately 250μR/hour at the Cargo Hold 4 aft bulkhead. Shine is radiation emanatingfrom another location on the ship but being measured remotely.Inside the reactor compartment, dose rates in the upper levels were essentially background. In thelower reactor compartment levels, general area dose rates varied 0.3–1.6 mR/hour, with contactreadings of up to 221 mR/hour.Inside containment, general area dose rates varied 0.1–10 mR/hour, with the highest contact readingaround the “U” tube end of the steam generators of 35 mR/hour.Inside the steam generator primary side inlet plenum dose rates were a maximum of 344 mR/hour inthe mid-plane of the plenum and the highest contact reading was 812 mR/hour, on the tube sheet.A dose rate summary is included in the following sections.13.1.2 Radiological ContaminationNo loose radiological contamination was found in unexpected places. Very little contamination wasfound in areas where it was expected. For example, following all entries, outer shoe covers andouter gloves were frisked and no radiological contamination was found. Several stateroom toilets,sinks, and floor tiles were found to contain naturally occurring radioactive material (NORM). Asummarization of these areas is included in the following tables.13.1.3 Non-Radiological AreasThe non-radiological areas were clear of detectable radiological contamination. The nonradiologicalareas evaluated are summarized in Table 13-1.Rev. VI 135
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