ML20210F741
| ML20210F741 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 12/31/1986 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20210F730 | List: |
| References | |
| NUDOCS 8702110150 | |
| Download: ML20210F741 (2) | |
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ADDENDUM TO THE ANNUAL INSPECTION REPORT FOR THE RETIRED WTR (1986).
- 1. Canal Water The samp{e of canal water, which had a gross beta-gamma activity of 1.97x10 p Ci/ml, was analyzed by gamrna spectrometry and the results were as follows:
Cesium - 137 = 1.85x10-4 Cobalt = 2.10x10-6 pCi/ml Cf/ml.
Cesium - 134 =<l .15x10-7 Ci/m. _
It is assumed that some Strontium-90 was also present in this sample but a specific separation and analysis was not performed for the Strontium-90 nuclide.
As previously reported, a particulate filtration and ion exchange system has been installed to process and recirculate the canal water. As of January 8, 1987, a total of 270,750 gallons of WTR canal water had been recirculated through the system. On that date, a sample was taken at the inlet t was2.1x10-gtheionexchangesystemandthegrossbeta-gammaactivity p Ci/ml . However, the sample was not analyzed by gamma spectrometry. Wearecontinuingtorecirculatethecanalwaterthroggh 3 the ion exchange system and are seeing decontamination factors of 10 -10 in the effluent from the system.
- 2. Air Sample in Sub-Pile Room The air sample result reported in Table 1 of the report was based on a single sample collected for 10 minutes with a Staplex sampler and represented a total air volume of 330 cu ft of air. Although the concentration was higher than that found in the sub-pile room in previous years, the difference was not considered to be significant in view of of 4.7x10-zthe relatively t Ci/ml. lowadditional However, counting rate and were samples resulting takenconcentration in the same area and usi were 0.9x10 g the same equipmen hon January 29 and 30 and the results pCi/ml and 1.2x10- pCi/ml,respectively. Although improved precision and sensitivity could be achieved with increased sampling volume and counting time, the overall levels are so low that we have not felt it necessary to implement such changes.
- 3. Equipment and Instrumentation Used a) Water samples were taken in clean polyethylene bottles as " grab" samples from the canal or from sample valves at the inlet to the ion exchange system. The sample was evaporated to dryness in a two-inch stainless steel planchet and counted in an automatic, thin window, gas proportional, alpha-beta anti-coincidence counter. The counting efficiency for beta-gamma activity was 36.4% and the background was 2.45 cpm.
8702110150 B70205 PDR R
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b) Contamination surveyg were performed by taking random smears of approximately 100 cm areas using 3 cm filter paper (Whatman 5 or equivalent). The fitler paper was then counted in the gas propor-tional counter described in a),above. A varying number of smears
. were taken for each area listed in Table 1 and the average value reported, c) Air samples were collected using a Staplex sampler with the particles in. pinging on a lightly greased stainless steel planchet.
The sampler flow rate was approximately 33 cfm and the sampling time was 10 minutes or longer. After sampling, the planchet was counted in the gas proportional counter described in a),above.
d) Radiation surveys were made at random locations within each of theareas shown in Table 1. Measurementsweremadeatwaisj height using an Eberline Model E-520 meter with a 30 mg/cm GM detector. The measurements were made with the detector in both the shielded and unshielded position, with the unshielded values (beta + gamma) being averaged and reported in Table 1.