ML20078J653

Radiological Analysis of Strontium Samples,Second Quarter 1983

ML20078J653
Person / Time
Site:	Duane Arnold
Issue date:	10/03/1983
From:	Mineck D IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
DAEC-83-789, NUDOCS 8310170581
Download: ML20078J653 (2)

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{q pt. r 'FiltC Mr. James G. Keppler Regional Administrator Region III U. S. Nuclear. Regulatory Commission 799 Roosevelt! Road Glen Ellyn, IL 60137

Subject:

Duane Arnold Energy' Center Docket No. 50-331 Op. Lic. # DPR-49 Radiological Analysis Confirmatory Measurements Program - Strontium

Dear Mr. Keppler:

As requested by Mr. Steve Rozak during NRC Inspection 83-13 the most recent results of our contractor's (NUS) analysis of DAEC strontium samples are as follows:

Analytics spiked sample of May 24, 1983 Analytics: Sr-89 = 1.54 E-4 pCi/ml Sr-90 = 2.46 E-6 pCi/ml NUS: Sr-89 = 1.50 E-4 pCi/ml Sr-90 = 1.60 E-6 uCi/ml Analytics spiked sample of July 27, 1983 Analytics: Sr-89 = 1.97 E-4 pCi/ml Sr-90 = 2.58 E-6 pCi/ml NUS: Sr-89 = 2.50 E-4 pCi/ml Sr-90 = 4.00 E-6 pCi/ml Analytics spiked sample of February 28, 1983 Analytics: Sr-89 = 2.0 E-4 pCi/mi Sr-90 = 2.3 E-4 uCi/ml NUS: Sr-89 = 9.2 E-5 pCi/ml Sr-90 = 8.2 E-7 pC1/ml Effluent strontium releases from the second quarter,1983:

Initial Results Reactor Bldg.: Sr-89 = 6.10 E-8 uC1/ml Sr-90 = 3.00 E-9 pCi/ml Offgas Stack: Sr-89 = 5.30 E-8 pC1/ml Sr-90 = 2.20 E-8 pCi/ml Turbine Bldg.: Sr-89 = 5.50 E-9 pCi/ml Sr-90 = 1.30 E-8 uCi/ml Re-analysis Results Reactor Bldg.: Sr-89 = 6.80 E-8 uCi/mi Sr-90 = 3.40 E-9 pCi/ml Offgas Stack: Sr-89 = 5.70 E-8 uCi/ml Sr-90 = 2.50 E-8 pCi/ml Turbine Bldg.: Sr-89 = 8.10 E-10 pCi/ml Sr-90 = 1.40 E-8 pCi/ml .

1\Q 8310170581 831003 OCT 13 ;

PDR ADOCK 05000331 R PDR Duane Arnold Energy Cer.ter. P.O. Box 351. Cedar Rapids, Iowa 524C6 319!8517611

, 4-Fr. James G. Keppler October 3, 1983 DAEC-83-789 l Page 2 l

Re-analysis of the semi-annual results for air filters are all within 15%

of the initial analysis, with the exception of Turbine Building strontium-89, which is lower. Even when the most conservative ,alues for all these samples are utilized, the calculated releases are well below DAEC Technical Specification limits.

The above results confinn information which has been provided verbally to Mr. Rozak by my staff. If you have any questions, please contact Mr. Bob Dye, at 319/851-7293.

Very truly yours, Daniel L. Mineck Plant Superintendent - Nuclear DLM/BD/pf*

cc: B. Dye L. Liu S. Tuthill F. Apicella NRC Resident Inspector (Mr.SteveRosak)

Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 File A-102, A-117

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