IR 05000344/1981029

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IE Insp Rept 50-344/81-29 on 811027.No Noncompliance Noted. Radioactive Liquid Waste Sample Compared W/Doe Radiological & Environ Sciences Lab Calculations
ML20038B864
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 11/17/1981
From: Book H, Hamada G, Wenslawski F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20038B861 List:
References
50-344-81-29, NUDOCS 8112090186
Download: ML20038B864 (4)


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U. S. NUCLEAR REGUL\\ TORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT S.'7,

REGION V

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Report No. 50-344/81-29 Docket No. 50-344 License No.

NPF-1 Safeguards Group Licensee:

Portland General Electric Company 121 S. W. Salmon Street Portland. Oreaon 97204 Facility Nace: Troian Inspection at: Rainier 0 recon Inspection conducted:

October 27, 1981

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Inspectors:

G. Hamada, Radiation Laboratory Specialist Date signed Date Signed Date Signed

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E~ Approved by:

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F. Wenslawski, Chie Ddte ! fig'ned Reactor Radiati tg tion ctio j

j H. E. Book, Chief

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Approved by:

D4te Signed Radiological Safety Branch

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Inspection of October 27,1981 (Report No. 50-344/81-29)

This in-office inspection was conducted as a followup to a previous NRC inspection (Report No. 50-344/81-11) during which radioactive liquid waste samples were obtained for intercomparison measurements between the licensee and the Radiological and Environmental Sciences Laboratory (RESL) of the Department of Energy, an NRC contractor laboratory. Results of this intercomparison are reported herein.

No items of noncompliance were identified.

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RV Form 219 (2)

8112090186 81111g'

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gDRADOCK 05000344 PDR

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DETAILS 1.

Background During the independent measurements verification inspection of~ June 8-12, 1981 (Report No. 50-344/81-11), a liquid sample was obtained from the turbine building sump for intercomparison measurements between the licensee and RESL. The measurements included analysis for Tritium, Gross Beta, Sr-89 and Sr-90.

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Discussion of Results Ratio Range Trojan RESL Ratio Ratio Range For Analysis syCi/ml jgCi/ml Trojan /RESL For Agreement Possible Agreement H-3 3.70 E-4 (4.85+0.03)E-4- 0.76 0.80 - 1.25-0.75 - 1.33 Gross Beta 3.15 E-5 (5.4 T0.4 )E-5 0.58 0.6 - 1.66

.0.4 2.5 Sr-89 5.55 E-6 (5.7 T0.2 )E-6 0.97 0.75 - 1.33 0.5 - 2.0 Sr-90 2.26E-7(1.710.1)E-7 1.33 0.75 - 1.33 0.5 - 2.0 The results above show that both Tritium and Gross Beta analyses fall in the "possible. agreement" category, while Sr-89 and Sr-90 analyses fall in the " agreement" category. Although.the overall agreement is adequate, better agreement in the Tritium and Gross Beta categories would be desirable. During our next routine independent measurements verification inspection, an additional sample; i.e., two separate samples rather than the usual one sample, will be obtained for comparability testing with special attention paid to the Tritium and Gross Beta analysis categories (81-29-01). The attachment to this report provides the criteria for evaluating the intercomparison results.

This completes the independent measurements verification effort for Trojan and open item no. 81-11-01 identified in report no. 50-344/81-11 is closed.

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Exit Interview A telephone interview was conducted on October 27, 1981 with Mr. G.

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Rich to inform him of the results of the split sample intercomparison

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in the future were also discussed.

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.eM ATTACHMENT

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CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS (LICENSEE VALUE)

RATIO (NRC REFERENCE VALUE)

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Possible Possible Resolution Agreement Agreement A'

Agreement B

0.4 - 2.5 0.3 - 3.0 No Comparison 4-7 0.5 - 2.0 0.4 - 2.5 0.3 - 3.0

8 - 15 0.6 - 1.66 0.5 - 2.0 0.4 - 2.5 e

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

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200 0.85 - 1.18 0.80 - 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.

Iodine on adsorbers.

"B" criteria are applied to the fol. lowing analyses:

Gamma spectrometery where principal gamma energy used for identification is less than 250 Kev.

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90 5r and Sr determinations.

Gross Beta where samples are counted on the same date using the same reference nuclide.

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j Procedure a.

'The NRC Reference Laboratory value should be divided by its associated uncertainty to obtain the resolution, b.

The ratio of the two measurements to be compared should be determined by dividing the result to be compared by the NRC Reference Laboratory results.

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c.

Agreement is' considered obtained if.the ratio falls within the range given in the " Agreement" column for the associated resolution.

For example, consider a comparison of Sr-90 determinations.

A licensee obtains a value of 1.97 +.08 x 10-5 uCi/mlandtheNgC-PeferenceLaboratoryreports.aresultof

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2.53 +.06 x 10

and the ratio is 0.78 (1.97/2.53). This -pair of measurements

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would be considered to be in " agreement" because for this

resolution, the " agreement" range is 0.75 - 1.33.

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If " agreement" is not achieved, the ratio should be evaluated for "possible agreement".

In this case,. consideration is made

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'for the type of analyses conducted by selecting a range in the i

appropriate column; i.e., "A" analyses or "B" analyses.

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'If the ratio falls outside the appropriate "possible agreement"

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column, the two measurements will be considered to be in

" disagreement".

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