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

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Updated Final Safety Analysis Report - (STS-004-002)Figure 7-1Plant Arrangement in the Containment VesselRev. VI 62
7.1.2.3 Water ChemistryUpdated Final Safety Analysis Report - (STS-004-002)The water chemistry of the primary, secondary and cooling water systems of the NSS wascarefully controlled to limit corrosionand activation. The primary systemwater quality was maintained to Table 7-1 Primary System Water Qualityconform to the standards shown inMaximum amountTable 7-1. See 8.6 for additionaldescription of Water Chemistry and Total solids, ppm 3.0Control.Dissolved solids, ppm 1.0The water chemistry program wasChloride, ppm 1.0effective in controlling corrosion andactivation of the water systems. Dissolved hydrogen, cc20 to 40Typical measurements of corrosion STP/kg waterproduct activity one day after shutdownpH 6.0 to 9.5were 130 mR/hr in the vicinity of thesteam generators and 25 mR/hr near the reactor vessel.7.1.2.4. RadiochemistryA sustaining program of radiochemical measurements was conducted during the operatingperiod of the NSS. Measurements were begun prior to initial operation of the reactor.Measurements of the system background indicated that the primary system was radiochemicallyclean. At the time of criticality, the multi-channel gamma spectrometer was used to obtaingross spectrum activity and energy peak decay of the primary coolant. At power levels above100 kW and prior to power range testing, only F-18 and N-13 were observed; this was normalfor pressurized-water reactors. The primary system radioactivity characteristics werecontinuously evaluated by measurements of gross-15-minute-degassed and gross-iodine-activitysamples. Extrapolated to 100% power, gross activity was 5.5E-2 µCi/ml and gross iodineactivity was 1.2E-4 µCi/ml immediately after initialoperation.A very slight uranium surface contamination of thefuel pins was indicated. Iodine studies were madeafter power transients and after a scram, but nosignificant changes in iodine level were observed.The amount of fuel element surface contaminationby natural uranium was determined by calculationsbased on fission-product activity in the coolant.The results indicated a uranium concentration ofapproximately 5.0E-2 µCi/cm 2 of fuel elementsurface. This amount of contamination appeared tobe a practical lower limit and caused no operationalproblems.A sample of primary coolant was taken when thereactor was at full power and was analyzed forsuspended solids. More than 99% of the activitywas Mn-56. There was no detectable Fe-59, Co-60,Co-58, W-187, or Cr-51. The total activity of adegassed sample of primary system water wasTable 7-2NuclideN-l3* (* = Notremoved bydegassing)Primary SystemRadiochemistryPercentage ofgross activity1.25F-18 14.9Mn-56 77.9Na-24 4.0Gross I 0.3Cs-138 0.12Ba-139 0.04Total strontium 0.05Rev. VI 63
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10 CFR 50.71(e) - Maritime Administration - U.S. Department of ...

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