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Testing of Dura-Solution at Comanche Peak . Jim Pore 254-897-5339 JKPore@luminant.com. The following test results were performed and recorded by the Comanche Peak Radiation Protection Department for comparison and evaluation of decontamination products and methods.

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testing of dura solution at comanche peak
Testing of Dura-Solution at Comanche Peak

Jim Pore

254-897-5339

JKPore@luminant.com

  • The following test results were performed and recorded by the Comanche Peak Radiation Protection Department for comparison and evaluation of decontamination products and methods.
  • 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.
slide2

Dura-Solution Decontamination Test in Reactor Cavity at Comanche Peak -2RF08

  • 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 2nd De-con effort (mopping of the trough) achieved our goal <100kdpm/100cm2.
  • A rough estimated of 1 man hour and 100mRem was saved.
slide3

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

slide4

Test results: Dura-Solution vs Detergent 8

150K –

1st decon

200K – 200K

2st decon

3st decon

35K-40K

4st decon-Effect solution

Subject matter: Stainless steel, Fuel Handling Load Guide Assembly

Post outage decontamination

Beginning Contamination Levels = 200K dpm/100cm2

In this corner

Detergent 8

In this corner

Dura-Solution

Results

dpm/100cm2

Results

dpm/100cm2

1st decon

30K - 40K

2st decon

15K - 20K

Note: Dose rate on rags 3-5 mR/hr

Round 1 Time in motion study. Deconing to 30K

Detergent 8

4 Rag + 4 Decons = Rad Waste Increase

Dura-Solution

1 Rag + 1 Decon = Rad Waste Reduction