NUREG/CR-4445, Forwards Ref Documents for NUREG/CR-4445, Effectiveness & Safety Aspects of Selected Decontamination Process

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Forwards Ref Documents for NUREG/CR-4445, Effectiveness & Safety Aspects of Selected Decontamination Process
ML20209D056
Person / Time
Issue date: 09/08/1986
From: Cardile F
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
RTR-NUREG-CR-4445 NUDOCS 8609090178
Download: ML20209D056 (24)
v • d • e


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Effective Rule (RM)

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TABLE -. RADIO %'CLICE CONCENTRATIONS AND CENSITIES OF WASTES (act/:nl wet resin decayed to March 30,1935)a haclide No. IA No. 28 No. 2.1B No. 3C No. 4D No. 4.1D No. SC 3 -**-

H (4.9

  • 0.5 ) E-4 (3.8
  • 0.2 ) E-6 (3.7
  • 0.1 ) E-4 (1.09
  • 0.04) E-3 (2.06
  • 0.09) E-5 (6.0
  • 0.2 ) E-4 .W .., f y 14 C (4.1
  • 0.7 ) E-5 < 1 E-6 < 1 E-5 (3.6
  • 0.2 ) E-5 (' 5*1 ) E-5 < 1 E-6 ##

54 Mn (2.94

  • 0.04) E-1 (8.0
  • 0.2 ) E-1 (1.11
  • 0.05) E-1 1.30
  • 0.02 (2.3
  • 0.1 ) E-1 (3.2
  • 0.3 ) E-1 .

55 Fe 1.44

  • 0.07 5.2
  • 0.3 (3.7
  • 0.2 ) E-1 16.2
  • 0.8 2.3
  • 0.1 NA9 ME 57 D Co (2.5
  • 0.2 ) E-2 ND ND ND ND ND 58 l Co 2.57
  • 0.01 (2.2
  • 0.2 ) E-1 (1.2
  • 0.2 ) E-2 ( 3*1 ) E-2 ( 1*1 ) E-2 ND Mb 60 Co 3.63
  • 0.01 6.41
  • 0.03 (7.00
  • 0.08) E-1 7.05
  • 0.03 4.79
  • 0.02 7.37
  • 0.05 63 (/ , cst-eq .

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4.8

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  • 0.1 ) E-4 241 Pu (4.9
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  • 0.1 ) E-2 (1.8
  • 0.5 ) E-2 241 Am (9.4
  • 0.4 ) E-6 (1.05
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Reference #9 - Main Body of Report Telecon between R. Sachatello of Northeast litilities and Stephen Duce, June, 1984. Subject of call was man-rem savings on decontamination programs.

Mr. Sachatello indicated that the man-rem savings from the chemical decontaminatio' n done at Millstone was on the order of a million dollars.

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Reference #12 Main Body of Report Telecon between Roger Zabadoski of Georgia Power and Stephen Duce Subject of call was the experience at Hatch with pipe replacement.

Roger told me that they used hydolance techniques to decontaminate the system. Prior to making any decision on a chem. decon Georgia Power sent several people to Nine Mile Point to observe the decon there. They also used an artifact to look at the oxide film on the piping surfaces. The film was fairly easily removed. After the decon and the artifact examination they decided to go with high pressure spray. It took three days to hydrolance the system. The area where they got the largest reduction was in the thermal sleeve area and safe end area 20%. The pump casings and impellers were hit with a glass bead hydrolance, where the readings were reduced from 6.8 to 1.1 R/hr and 10-70 and 95-100 R/hr to2-6 and 2-12 R/hr. All water used was first passed through a portable demin and then sent to radwaste sys. Roger estimated that man-rem savings were on the order of 25-40%. Largest savings was in the pump bowl and impeller work. He also said that plasma-arc cutters were used in the drywell and this saved many hours. They were able to use the plasma-arc cutters because of the low levels of contamination in the drywell and building special tents around the cutting area. Less than 92% of the work in the drywell was performed in respirators due to the low contamination levels.

Reference #13 Main Body of Report.

Telecon between Allen Cure Georgia Power and Stephen Duce Sept. 18 Allen Cure called to give me the dose rates pre- and post-decon on the recicr system at Hatch. Pre rates 200 to 500 risers, 100 to 200 ringheader, 150 to 225 suction / discharge, and 150 to 1800 recirc pump elbows, all mr/hr. Post rates85-250, 80 to 150, 80 to 200, and 120 to 1000 mr/hr for all systems.

8c$a ., cu- 2 , AppeoAx A On June 12, 1985 Stephen Duce called Mr. Thorpe of Chem-Nuclear to discuss with him the waste that was generated and solidified at the Pilgrim Station chemical decontamination. He said that they solidified 1300 gallons of concentrated liquids and 90 ft3 of mixed bed resins. The i liquids came from the IT Nuclear R0 unit and the mixed bed resins came from processing other liquids through some Chem-Nuclear mixed bed resin columns.

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On February 2, 1984 Ferrol Simpson was discussing the results of the chemical decontamination with Bud Arrowsmith of IT Nuclear. Bud related some of the problems that IT had in performing the job. He talked about the failed heat exchanger, motor failures, and level indicator readings that were not in agreement.

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Jerry indicated that he had talked to RCT personnel to find out how their instrument had been calibrated. He told me that the RCT GM was calibrated at Nine Nile Point using a Cs-137 point source.

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/&Lme Aom& F STEVEli C. L.u u _ , .w. i . m .v nic., P. U. liox 106, Idatio Falls, ID 63415 Phone: (208) 526-4054, (FTS) 583-4054 ,

VEf'DCR: PLAfiT: dmm u ues rd ems - O e o 6 /'<5 SYSTEM DEC0 fled: /<4se e 'S f steor N- 2 ,

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EFFECTIVEtlESS Af!D SAFETY ASPECTS i (30f) hfY 2LVl 0F SELECTED DEC0t!TA ilt!AT10l! liETH03S 6'/,29) l CUESTIO!!?? AIRE i

1. Precampaign Dose Rates (Equipment and General Area).

l A. Instruments used (Model : c. , Serial tio. , Calibration Date, -

Source type) fecruce. /ft 3/1 Sx.e/s s- c2A9 .

D.  ??ame(s) and affiliation of person (s) performing the survey.

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D. Attach general area surveys for two weeks prior to decontamination.

E. Attach equipment point survey.

Yes X t,'o F. Evaluaticn c' techniques usec.

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ALAP.A A. Frojected dose savings (by jcb title) and assumptions or methods used.

B. Other methods examined for dose reduction. .

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C. Licensee's criteria'for choosing decontamination and why this vendor was chosen.

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9. Job Information A. Job performed on plant system after decentamination.

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