IR 05000313/1982012
| ML20028G132 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/31/1983 |
| From: | Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8302070438 | |
| Download: ML20028G132 (3) | |
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Docket Nos. 50-313
50-368
Arkansas Power and Light Company ATIN: Mr. William Cavanaugh III Vice President of Generation
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and Construction P. O. Box 551
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Little Rock, Arkansas 77203 Gentlemen:
i This refers to the results of confirmatory measurements performed by your radiochemistry laboratory and the NRC's reference laboratory, Radiological i
and Environmental Sciences Laboratory (RESL) in Idaho Falls, on a liquid radioactive effluent sample collected during an NRC inspection in May 1982,
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and not reported in NRC Inspection Report Nos. 50-313/82-12 and 50-368/82-25.
It was necessary to have the stroritium analysis performed by the NRC's reference laboratory; therefore, delaying the reporting of the results. The analysis results have been received from RESL and are reported below.
Formal comparisons are only made for those nuclides identified by the Region IV i
mobile laboratory or the NRC's reference laboratory (RESL) as being present in concentrations greater than 10 percent of the respective isotopic values for
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liquid and gas concentrations as stated in 10 CFR Part 20, Appendix B, Table II.
Statistical reliability limits apply to each analysis. Measurements made by
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RESL are referenced to the National Bureau of Standards radioactivity measurements system by laboratory intercomparisons. Official documentation I
of these analysis results will appear in the next NRC confirmatory measurements inspection report.
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DR ADOCK 05000313
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JAN 311983 Arkansas Power and Light-2-Attachment No.1 contains the criteria used to compare results.
Liquid Radwaste Effluent from Monitor Tank T-16B (Sampled 16:12 CDT, May 25, 1982)
NRC Result AN0 Result AN0/NRC Nuclide (uCi/ml)
(uCi/ml)
Ratio Decision
Disagreement 5r 5.0 2.0E-07
< 2.92E-07
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90Sr 9.0 1.1E-07 3.17i0.53E-07 0.35 Disagreement Should you have any questions concerning these results, we will be pleased to discuss them with you.
Sincerely, W. C. Seidle, Chief Reactor Project Branch 2 I
cc:
J. M. Levine, Plant Manager
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Arkansas Nuclear One P. O. Box 608
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Russellville, AR 72801 bcc to DMB (IE01)
bcc's distributed by RIV:
Resident Inspector Section Chief (RPS-C)
Accompanying Personnel J. T. Collins, RA R. L. Bangart Info. Systems RPB1 RPB2 TPB
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RIV File
- Arkansas State Dept. Health l
- G. Vissing, NRR
- C. Trammell, NRR
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ATTACHMENT NO. 1 Criteria for Comparing Analytical Measurements The following are the criteria used in comparing the results of capability tests and verification measurements.
The criteria are based on an empirical
relationship established through prior experience and this program's analytical requirements.
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In these criteria, the judgement limits vary in relation to the comparison of the resolution.
Resolution = NRC Value NRC Uncertainly Ratio = _ Licensee Value NRC Value
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Comparisons are made by first determining the resolution and then reading across the same line to the corresponding ratio.
The following tabic shows the acceptance values.
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RESOLUTION RATIO l
Possible Possible Agreement Agreement A Agreement B
0.4 - 2.5 0.3 - 3.0 No comparison
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4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0 E - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 16 - 50 0.75 - 1.33 0.6 - 1.66 0.5 - 2.0 51 - 200 0.80 - 1.25 0.75 - 1.33 0.6 - 1.66 200 0.85 - 1.16'
O.80 - 1.25 0.75 - 1.33
"A" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is greater than 250 Kev.
Tritium analyses of liquid samples.
lodine on adsorbers.
"B" criteria are applied to the following analyses:
Gamma Spectrometry where principal gamma energy used for identification is less than 250 Kev.
9 Sr and Sr Determinations.
Gross Beta where samples are counted on the same date using the same reference nuclide.
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