ML20148L941
| ML20148L941 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/09/1978 |
| From: | Sutherland J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W FLORIDA POWER CORP. |
| References | |
| NUDOCS 7811200422 | |
| Download: ML20148L941 (5) | |
Text
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8-UNITED sT AVES' Mo og t
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i In Reply Refer To:
RII:WJM 50-302/76-18 Florida Power Corporation Attn: Mr. W. P. Stewart, Director Power Production P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Gentlemen:
This refers to the inspection conducted by Mr. W. J. Millsap of this office on June 30, 1978, of activities authorized by NRC Operating License No.
DPR-32 for the Crystal River 3 facility. The results of this inspection are discussed in our Inspection Report No. 50-302/78-18 which was enclosed with our letter to you dated August 25, 1978.
During the inspection, members of your staf f measured the amount of radio-active material in an NRC phantom on the whole body counter. This measure-ment was also made by other NRC 1.icensees and three Department of Energy laboratories. The results of these measurements are given'in the enclosures to this letter. gives the results of the measurements made by your staf f, the actual amount of each radionuclide present in the phantom at the time of this measurement, and the ratio of measured to actual amounts. Enclosure 2 gives the ratio of each measurement result-to the amount actually present in the phantom at the time of the measurement for all measurements made by DOE laboratories and NRC licensees.
Power reactor facility values are denoted
- by ' single letters; Department of Energy laboratory values are denoted by double letters. discusses general recommendations based on the inspector's' observations of these measurements.
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a Florida Power Corporation Should you have any questions concerning this letter, we will be glad to discuss them with you. No reply to this letter is required.
Sincerely, f.
.'4t/sesk
. T. Sutherland, Chief Fuel Facility and Materials Safety Branch
Enclosures:
As stated cc w/ encl:
Mr. G. P. Beatty, Jr.
Nuclear Plant Superintendent P.O. Box 1228 Crystal River, Florida 32629
- AP S
Facility:
Crystal River Nuclear Plant Facility Designation:
C Date of Measurement:
June 30, 1978 Measurement Ratio Result Actual (Measured / Actual) a.
Co-60 0.34 Ci 0.24 pCi 1.42 b.
Cs-137 0.17 Ci 0.13 pCi 1.31 c.
Co-57 0.35 pC2 0.53 pCi 0.66 d.
Cs-134 Not Reported 0.58 nCi
.a..
1 1
l Ratios (Measured / Actual) 1 Facility Co-60 Cs-137 Co-57 Cs-134**
1 A*
1.29 1.62 0.07 NR 2.
B 1.08 1.92 1.22 NR j
3.
C 1.42 1.31 0.66 NR i
4.
D 1.46 0.85 NF NR 5.
E 2.04 2.77 NR NR 6.
F 1.25 0.85 1.22 NR 7.
G 1.42 1.62 1.33 KR 8.
H 0.88 1.62 0.63 43 9.
I 1.63 2.38 0.23 NR 10.
J 2.42 2.62 NR FR 11.
AA 1.36 1.38 2.97 NR 12.
BB 0.78 0.92 0.67 KR 13.
CC 1.13 1.38 1.00 KR l
l Facility A reported Cr-51 present in the amount of 0.10 pC1.
This was not present in the phantom.
NR - Not Reported.
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4 Observations by the inspector durinF the course of all phantom measurement suggest three general recommendations for the improvement of the whole bcdy counting programs.
1.
The spectrum resulting from each whole body count should be observed in its entirety in order that the presence of unexpected radionuclides w211 be recognized. Several licensees failed to recognize the presence of the Co-57 apparently because its gamma energy falls outside a pre-determined region of 2nterest.
2.
Each licensee should determine the energy response (energy / channel) of his detector over the full range of the spectrum.
Several licensees had difficulty identifying the Co-57 once the presence of a low energy emitter was recognized because of the unexpected response of the detectors at low energies.
3.
Each licensee should consider some sort of intercomparison or inde-pendent standard test of his whole body counter (s).
A test of this nature might reveal problems not immediately apparent to an individual group working independently of all others.
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