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

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Updated Final Safety Analysis Report - (STS-004-002)Deck/compartments Dose rate found Contaminationfound (dpm/100cm 2 )Aft Mezzanine, mid level between ”C” and “D” Decks 3–5 μR/hour All < backgroundLower level reactor compartment 221 mR/hour All < background13.1.6 Containment VesselTable 13-4 provides a summary of radiological conditions inside of the containment vessel.Table 13-4 Containment Vessel Radiological SummaryDeck/compartments Dose rate found Contaminationfound (dpm/100cm 2 )Containment, upper hatch closed 15 μR/hour All < backgroundContainment, upper hatch open 400 μR/hour All < backgroundContainment, 1st level 500 μR/hour 1200Containment, inside shield tank upper ring 7 mR/hour All < backgroundContainment, 2nd level 3 mR/hour All < backgroundContainment, 3rd level 10 mR/hour < 1000Containment, 3rd level, area over U-tube steamgenerator35 mR/hour < 1000Containment, 4th level 3 mR/hour All < background13.1.7 Estimate of the Quantity and Distribution of RadionuclidesIn order to assess the radioactivity in residual liquids and transferable contamination that may besubject to a spill or spread in the event of damage to the ship or flooding of compartments containingreactor systems, an estimate of the quantity and distribution of radionuclides in primary and auxiliarysystems was performed. The quantity of radioactivity deposited in the system as contamination isvery small compared to the total estimated activity in reactor vessel components.Scans and samples confirmed that the primary nuclide deposited on surfaces in primary and auxiliarysystems is Co-60. The total estimated inventory of Co-60 in surface deposits is approximately 108mCi. Cs-137 is the predominant nuclide present in residual water (approximately 1500 gallons)within the primary coolant system. The total waterborne Cs-137 content in the reactor system isestimated at about 5.91 mCi.These two nuclides represent the bulk of the potentially mobile nuclide inventory. The estimatesupports the conclusion that even a worst-case incident, resulting in the loss of all the transferablecontamination to the environment, would have no significant impact on the environment or on doseRev. VI 138
Updated Final Safety Analysis Report - (STS-004-002)to the public in that the radiological consequences of a breech to the primary coolant system wouldbe insignificant13.1.7.1 General ApproachThe methods used to estimate the residual radioactivity were analyzing liquid samples from theprimary coolant system and directly scanning smears and liquid samples with portable gammaspectroscopy equipment.13.1.7.2 General FindingsCo-60 was expected to be the most widespread nuclide in the primary coolant system due to theradiological decay characteristics of the isotopes involved. This expectation was confirmed inthe measurements taken. All the area monitoring spectra taken around primary and auxiliarysystems indicated Co-60 activity. Most monitored locations also indicated the presence of Cs-137 (this may have some practical implications, as is discussed below).A few smear samples from reactor spaces showed a combination of Co-60 and Cs-137. In onecase, only Cs-137 was present. This is reasonable given the low activity in that area and theratio of Cs-137 to Co-60 on the other smears (see detailed findings). It might also be surmisedthat the presence of the contamination is due to past spills of system coolant or ion exchangemedia, rather than the dry release of crud from piping internals.13.1.7.3 Detailed FindingsSamples from inside the primary coolant system showed the following characteristics. Thesteam generator water sample contained Cs-137 almost exclusively (Cs-137 concentration wasabout 1000 times greater than that of Co-60), but contamination on interior surfaces of thesteam generator was found to contain only Co-60. This is undoubtedly a result of the chemicalform of the contaminants. Co-60 is usually found as an insoluble oxide and tends to deposit onsurfaces of reactor systems (forming the common “crud” deposits found in all reactors),whereas Cs-137 is present as a very soluble oxide or hydroxide.A spill of the coolant would be likely to spread both Co-60 and Cs-137, as the Co-60 is easilyremovable and would be flushed from surfaces by any significant movement of the water (hencethe speculation above that contamination on surfaces in the reactor compartment may be theresult of past liquid (or ion exchange media) spills). A spill to the environment (i.e., into ariver) would probably behave similarly with respect to the distribution of these nuclides. TheCs-137 would likely remain dissolved in the river water, whereas insoluble components wouldeventually find their way into sediment.Tables 13-5 and 13-6 below summarize the area monitoring and sample analysis results.Rev. VI 139
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10 CFR 50.71(e) - Maritime Administration - U.S. Department of ...

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