Presentation on theme: "Testing of Dura-Solution at Comanche Peak n The following test results were performed and recorded by the Comanche Peak Radiation Protection Department."— Presentation transcript:
Testing of Dura-Solution at Comanche Peak n The following test results were performed and recorded by the Comanche Peak Radiation Protection Department for comparison and evaluation of decontamination products and methods. n Dura-Solution was compared to surfactant-based products currently in use in the RCA at Comanche Peak Nuclear Power Plant in the reactor cavity de-con evolution and spent fuel pit equipment. Jim Pore 254-897-5339 JKPore@luminant.com
De-contamination of the Unit 2 RX vessel trough using Dura-Solution Cavity Work During 2RF08 Normal Refueling Guide Tube Pin Replacement Mod. RX Vessel Trough De-con §Water and crud was removed (vacuumed) from trough. §Dura-Solution was introduced to trough. §Trough and flange was scrubbed using scrub pads with handles. §Trough and flange was rinsed with water and vacuumed to Lower Internals Storage Area. (LISA). LISA floor was afterward de-conned to 10Kdpm/100cm2 average. Summary of Radiological significance Initial survey 100 to 700 mRad/hr/100cm2 on cavity floor. Initial de-con effort reduced the contamination levels to 400Kdpm/100cm2. The 2 nd De-con effort (mopping of the trough) achieved our goal <100kdpm/100cm2. A rough estimated of 1 man hour and 100mRem was saved. Dura-Solution Decontamination Test in Reactor Cavity at Comanche Peak -2RF08
Conclusion: Westinghouse experienced no personal contamination events during the RX Head tensioning. This was due to reduced contamination levels at the flange and trough area. 2RF08 Cavity de-con was noted by management as excellent. RWST (cavity water) PEAK ENERGY DECAY CORR ISOTOPE ENERGY DIFF (KEV) uCi/ML -------- ------- ---------- ---------- CR-51 320.07 -0.06 1.708E-03 MN-54 834.81 -0.18 3.497E-05 CO-57 122.07 0.24 5.963E-06 CO-58 810.75 -0.09 2.001E-03 FE-59 1099.22 0.26 5.285E-05 CO-60 1332.51 0.08 1.006E-04 ZN-65 1115.52 0.18 7.982E-06 NB-95 765.82 -0.17 1.670E-04 ZR-95 756.72 -0.17 1.140E-04 ------ --------- AVG ENERGY DIFF = 0.01 4.192E-03 = TOTAL GAMMA ACTIVITY
Test results: Dura-Solution vs Detergent 8 Beginning Contamination Levels = 200K dpm/100cm2 In this corner Dura-Solution In this corner Detergent 8 Subject matter: Stainless steel, Fuel Handling Load Guide Assembly Post outage decontamination 1 st decon 3 st decon 2 st decon 1 st decon dpm/100cm2 Results 30K - 40K150K – 200K – 200K 2 st decon15K - 20K 4 st decon-Effect solution35K-40K Note: Dose rate on rags 3-5 mR/hr Dura-Solution 1 Rag + 1 Decon = Rad Waste Reduction Detergent 8 4 Rag + 4 Decons = Rad Waste Increase Round 1 Time in motion study. Deconing to 30K
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