IR 05000344/1985019

Insp Rept 50-344/85-19 on 850530 & 0606.No Noncompliance Noted.Major Areas Inspected:Review of radio-analytical Results Obtained for Test Sample Provided by NRC as Part of Confirmatory Measurements Program

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: IR 05000344/1985019 ML20129C557
References
50-344-85-19, NUDOCS 8507160254
Download: ML20129C569 (3)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report N /85-19

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Docket N License N NPF-1

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p Licensee: Portland General Electric Company 121 S. W. Salmon Street

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Portland, Oregon 97204 Facility Name: Trojan Nuclear Power Plant

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Inspection at:

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In-Office v Inspection conducted: May 30 and June 6, 1985

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Inspector: d9kh_k G. H. H a, Ri ion Laboratory Specialist 6//y/g,7 Dite Signed L

Approved By: bh U k G. P. Yu as Chief a (,a// # g 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 NR Results: No items of noncompliance were identified in the areas reviewe ' *

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DETAILS 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 Energ The results are summarized belo 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 explanatio 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 countin 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-5 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 radioactivit . Exit Interview The results of this test were discussed with W. Kernion (Plant Chemist)

by telephon . .

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G Enclosure Criteria for Accepting the Licensee's Measurements Resolution Ratio

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4 - 7 .0 8 - 15 .66 16 -

50 0.75 - 1.33 51 - 200 0.80 - 1.25 - -. -

200 0.85 - 1.18 Comparison --

_ Divide each NRC result by its associated uncertainty to obtain the resolutio (Note: For purposes of this p'rocedure, the uncertainty is defined as the relative standard deviation, one sigma, of the NRC result "

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as calculated from counting statistics.) Divide each licensee result by the corresponding NRC result to obtain the ratio (licensee result /NRC). The licensee's measurement is in agreement if the value of the rati __

falls within the limits shown in the preceding table for the corresponding resolutio .

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