NG-04-0485, Correction to 2003 Annual Materials Release Report

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Correction to 2003 Annual Materials Release Report
ML042160278
Person / Time
Site: Duane Arnold 
Issue date: 07/23/2004
From: Peifer M
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NG-04-0485
Download: ML042160278 (3)


Text

4-N ii' Committed to Nuclear Excele Duane Arnold Energy Center Operated by Nuclear Management Company, LLC July 23, 2004 NG-04-0485 10 CFR 50.36a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC, 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR-49 Correction to 2003 Annual Materials Release Report Please find enclosed corrected pages for the Annual Material Release Report for the Duane Arnold Energy Center (dated April 30, 2004). The pages correct minor typographical errors that have no effect on the original conclusion that gaseous effluent releases resulted in a small fraction of the 10 CFR 20 site boundary concentration limits and the 10 CFR 50, Appendix I dose objectives.

This letter contains no new commitments.

MarkA. P fer-Site Vice President, Duane Arnoid Energy Center Nuclear Management Company, LLC Enclosure CC:

D. Beaulieu (NRC-NRR) (w/a)

J. Caldwell (Region ll) (w/a)

NRC Resident Inspector (w/a)

IRMS

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3277 DAEC Road *.Palo; lowa 52324-9785 Telephones3191851.761.1" I.

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GASEOUS EFFLUENT TABLES T2bIe 2 C,32cous Ernuents ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (2003)

GASEOUS EFFLUENTS BY CALENDAR QUARTER (Curies)

Nuclides Released

[

Unit I 1st Quarter J

2nd Quarter l

3rd Quarter l

4th Quarter

1. Fission cases argon-41 Ci

<LLD 1.67E-1

<LLD 1.96E+0 krypton-85 Ci

<LLD

<LLD

<LLD

<LLD krypton-85m Ci

<LLD 6.72E-2

<LLD 9.04E-1 krypton-87 Ci

<LLD 3.64E-1

<LLD 2.89E-1 krypton-88 Ci

<LLD

<LLD

<LLD

<LLD xenon-133 Ci 3.30E+0 1.70E-1

<LLD 9.06E-1

-(xerhno135

--- Cl -

446E+0--

-4:71E+O-- -2:38E+O-

-6.51E+00 xenon-135m Ci

<LLD 4.53E+0 5.52E+0 1.16E+O xenon-1 38 Ci 2.65E+0 3.69E+0 5.56E+0 4.17E+0 Tritium Ci 6.52E+O 1.24E+1 9.83E+0 1.55E+i Total Fission Gasses for period Ci I.7E+I 2.6E+I 2.3E+1 3.IE+I

2. lodines iodine-131 Ci 3.93E-5 J

2.57E-5 1.04E-5 1.69E-5 iodine-133 Ci 2.56E-5 1.47E-5 1.69E-5 1.84E-5 iodine-135 Ci

<LLD

<LLD

<LLD

<LLD Total lodines for period Ci 6.5E-5 4.0E-5 2.7E-5 3.5E-5

3. Particulates I

I strontium-89 Ci 6.98E-6 4.44E-6 7.66E-6 1.29E-5 strontium-90 Ci 3.09E-6 1.21 E-7 8.28E-8 1.35E-7 cesium-1 34 Ci

<LLD

<LLD

<LLD

<LLD cesium-1 37 Ci 8.12E-6

<LLD

<LLD

<LLD barium-lanthanum-140 Ci

<LLD

<LLD

<LLD

<LLD chromium-51 Ci 3.59E-6 2.03E-5

<LLD

<LLD cobalt-58 Ci 7.57E-7 1.45E-6

<LLD

<LLD cobalt-60 Ci 1.19E-3 1.22E-4

<LLD 1.86E-5 Ci_

-<DLD_

<L SLLD

<LLD manganese-54 Ci 6.30E-4 2.40E-5 1.77E-6 1.50E-7 zinc-65 Ci 1.30E-5

<LLD

<LLD

<LLD Total Particulates for Period Ci 1.9E-3 1.7E-4 9.5E-6 3.2E-5 Total forPeriod jCi j_1.7E+_ l_2.6E+1 J 2.3E+1 3.1E+l Il

<LLD means that the radionuclide was not identified in any samples and all measurement results were less than the lower limit of detection as required by the DAEC Offsite Dose Assessment Manual.

2003 DAEC Annual Radioactive Material Release Report Page 6

, i.

Table 3 (;aseot.% Efflutnt bv Release Point ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT ( 2003)

GASEOUS EFFLUENTS BY RELEASE POINT ('Curies)

REI.EASIE POINT OFFGAS STACK lREACTOR BUILDING

'URBltE BUILDING ll LLRPSF RELEASE IIEIGIIT ll 328 FEET 11 156 FEET 90 ET 65 FEET REL.EASE MODE IF ELEVATED IF"WAKE SPLIT AKE SPLIT IF WAKE SPLIT Ar-41 2.13E+0

<LLD

<LLD

<LLD Kr-85m 9.71 E-1

<LLD

<LLD

<LLD Kr-85

<LLD

<LLD

<LLD

<LLD Kr-87

-6.53 E -

cL_- ~-=<LLD 5LLD-Kr-88

<LLD

<LLD

<LLD

<LLD Xe-133 4.38E+O

<LLD

<LLD

<LLD Xe-135m 1.12E+1

<LLD

<LLD

<LLD Xe-135 1.81 E+1

<LLD

<LLD

<LLD Xe-1 38 1.61 E+1

<LLD

<LLD

<LLD H-3 7.48E+O 2.57E+1 1.08E+1 3.84E-1 Cr-51

<LLD 2.39E-5

<LLD

<LLD Mn-54 3.09E-06 6.53E-4

<LLD

<LLD Co-58 7.57E-7 1.45E-6

<LLD

<LLD Co-60 1.22E-6 1.33E-3

<LLD

<LLD Fe-59

<LLD

<LLD

<LLD

<LLD Sr-89 5.14E-6 2.14E-5 5.43E-6 2.36E-8 Sr-90 3.05E-6 2.12E-7 1.46E-7 2.54E-8 Cs-1 34

<LLD

<LLD

<LLD

<LLD Cs-1 37

<LLD 8.12E-6

<LLD

<LLD Ba-140

<LLD

<LLD

<LLD

<LLD Zn-65 3.35E-7 1.27E-5

<LLD

<LLD 1-131 4.14E-5 2.19E-5 2.90E-5

<LLD 1-133 5.45E-5 1.28E-5 8.19E-6

<LLD 1-135

<LLD

<LLD

<LLD

<LLD Totals 6.1E+1 2.6E+1 1.1E+1 3.8E-1 I

2003 DAEC Annual Radioactive Material Release Report Page 7