Testing of Dura-Solution at Testing of Dura-Solution at Comanche Peak Comanche Peak

The following test results were performed and The following test results were performed and recorded by the Comanche Peak Radiation recorded by the Comanche Peak Radiation Protection Department for comparison and Protection Department for comparison and evaluation of decontamination products and evaluation of decontamination products and methods.methods.

Dura-Solution was compared to surfactant-Dura-Solution was compared to surfactant-based products currently in use in the RCA at based products currently in use in the RCA at Comanche Peak Nuclear Power Plant in the Comanche Peak Nuclear Power Plant in the reactor cavity de-con evolution and spent fuel reactor cavity de-con evolution and spent fuel pit equipment.pit equipment.

Jim Pore

254-897-5339

JKPore@luminant.com

De-contamination of the Unit 2 RX vessel trough using

Dura-SolutionCavity Work During 2RF08Normal 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 significanceInitial survey 100 to 700 mRad/hr/100cm2 on cavity floor.Initial de-con effort reduced the contamination levels to 400Kdpm/100cm2.The 2nd 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 Dura-Solution Decontamination Test in Reactor Cavity at Comanche Peak -2RF08Cavity 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/100cm2In this corner

Dura-SolutionIn this cornerDetergent 8

Subject matter: Stainless steel, Fuel Handling Load Guide Assembly Post outage decontamination

1st decon

3st decon2st decon1st decon

dpm/100cm2 dpm/100cm2ResultsResults30K - 40K 150K –

200K – 200K

2st decon15K - 20K

4st decon-Effect solution 35K-40KNote: 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