IR 05000344/1985019
| ML20129C569 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/14/1985 |
| From: | Hamada G, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20129C563 | List: |
| References | |
| 50-344-85-19, NUDOCS 8507160254 | |
| Download: ML20129C569 (3) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No.
50-344/85-19
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Docket No.
50-344 License No.
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p Licensee:
Portland General Electric Company
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121 S. W. Salmon Street
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Portland, Oregon 97204 Facility Name:
Trojan Nuclear Power Plant
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Inspection at:
In-Office
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Inspection conducted:
May 30 and June 6, 1985
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Inspector:
d9kh_k 6//y/g,7 G. H. H a, Ri ion Laboratory Specialist Dite Signed L
Approved By:
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G. P. Yu as Chief Da'te Signed Faciliti adiological Protection Section Summary:
In-Office Inspection of May 30 and June 6,1985 (Report No. 50-344/85-19)
This in-office inspection was conducted to review the results obtained on a spiked sample provided by the NRC.
Results: No items of noncompliance were identified in the areas reviewed.
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DETAILS 1.
Discussion:
As a part of the confirmatory measurements program, a spiked solution was submitted to Trojan for radiochemical analysis. This test solution was prepared and' certified by NRC's reference laboratory, the Radiological and Environmental Sciences Laboratory (RESL) of the Department of Energy.
The results are summarized below.
Trojan RESL Ratio Agreement *
Nuclide uCi/ml uCi/ml Trojan /RESL Range H-3 5.39 E-5 5.78 E-5 0.93 0.75 - 1.33 Fe-55 2.66 E-5 2.02 E-5 1.32 0.60 - 1.66 Fe-59 8.84 E-6 5.72 E-6 1.55 0.60 - 1.66 Co-60 1.25 E-5 1.08 E-5 1.16 0.75 - 1.33 Sr-89 2.55 E-4 2.43 E-4 1.05 0.60 - 1.66 Sr-90 2.88 E-5 2.68 E-5 1.07 0.75 - 1.33 Cs-137 1.61 E-5 1.20 E-5 1.34 0.75 - 1.33
- See enclosure for explanation.
In general, the results indicate adequate agreement. The result for Cs-137 is out of the agreement range, but it is just barely out. While the gamma emitters (Fe-59, Co-60, Cs-137) can be readily measured by gamma spectrometry, other components in the mix require radiochemical separation prior to measurement. Tritium (H-3), requires separation prior to measurement by liquid scintillation counting.
Because Fe-55 is a sof t x-ray emitter.(5.9 Kev), iron must be separated from the other components. Even after separation, however, the counting procedure must account for the potential interference from Fe-59.
The beta emitters, Sr-89 and Sr-90, also require separation. The counting procedure must account for measuring each in the presence of the other as well as for the ingrowth of the Y-90 daughter of Sr-90.
With this report Open Item No. 84-28-01.is closed, and it can be concluded that Trojan has successfully demonstrated its ability to satisfactorily perform the required measurements for radioactivity.
2.
Exit Interview The results of this test were discussed with W. Kernion (Plant Chemist)
by telephone.
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G Enclosure Criteria for Accepting the Licensee's Measurements Resolution Ratio
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0.4
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2.5 4 -
0.5 2.0
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0.6
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1.66
50 0.75 -
1.33
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- 200 0.80 -
1.25
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200 0.85 -
1.18 Comparison
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1.
Divide each NRC result by its associated uncertainty to obtain the resolution.
(Note: For purposes of this p'rocedure, the uncertainty is defined as the relative standard deviation, one sigma, of the NRC result as calculated from counting statistics.)
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2.
Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result /NRC).
3.
The licensee's measurement is in agreement if the value of the ratio.
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falls within the limits shown in the preceding table for the corresponding resolution.
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