ML080990629

Radiological Environmental Monitoring Report

ML080990629
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/19/2008
From:	Berg W Dairyland Power Cooperative
To:	Document Control Desk, NRC/FSME
References
LAC 14031
Download: ML080990629 (6)

Text

WILLIAM L. BERG President and CEO DAIRYLAND POWER COOP E RAT IV E

March 19, 2008 In reply, please refer to LAC-14031 DOCKET NO. 50-409 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Dairyland Power Cooperative La Crosse Boiling Water Reactor Possession-Only License No. DPR-45 Radiological Environmental Monitoring Report

REFERENCES:

(1) DPC Letter, Berg to Document Control Desk, dated February 25, 2008 Our referenced letter transmitted to you, "Radioactive Effluent Report and Radiological Environmental Monitoring Report" for the La Crosse Boiling Water Reactor (LACBWR) for 2007 has been updated. The Radiological Environmental Monitoring Report contained incomplete data in Section A as contractor results had not yet been received. We now have these results and have completed the tables on pages 7, 8, 9 and 10. Also updated is Section 8.0, page 13.

Please remove the original pages 7, 8, 9, 10 and 13 from your copy of the Radiological Environmental Monitoring Report and replace with the new pages enclosed.

If you have any questions, please contact us.

Sincerely, DAIRYLAND POWER COOPERATIVE William L. Berg, President & CEO WLB: LLN: two Enclosure cc/enc:

Peter Lee, Ph.D., NRC Reg. III, Decommissioning Branch Kristina Banovac, NRC Project Manager Don Hendrikse, Wisc. Div. of Health A Touchstone Energy Cooperative jj~y5~O(

3200 East Ave. S. -

PO Box 817

• La Crosse, WI 54602-0817

• 608-787-1258

• 608-787-1469 fax

. www.dairynet.com

EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES

___UNIT QTR QTR QTR QTR TOTAL A.

FISSION & ACTIVATION GASES QTR QTR QTROTA

1.

TOTAL RELEASE Ci 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00

2.

AVERAGE RELEASE RATE FOR IiCi/

0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 PERIOD Sec B.

IODINE 1-131 -

No longer analyzed for.

C.

PARTICULATES

1.

PARTICULATES WITH HALF-Ci 3.90E-06 6.11E-06 1.11E-06 4.63E-07 1.16E-05 LIVES> 8 DAYS

2.

AVERAGE RELEASE RATE FOR

.LCi/

5.01 E-07 7.77E-07 1.40E-07 5.82E-08 PERIOD Sec

3.

GROSS ALPHA RADIOACTIVITY Ci 1.18E-06 1.41E-07 1.50E-07 2.1OE-08 1.49E-06 D.

TRITIUM

1.

TOTAL RELEASE Ci 3.20E-02 1.48E-02 9.39E-03 8.82E-03 6.50E-02

2.

AVERAGE RELEASE RATE FOR

.tCi/

4.12E-03 1.88E-03 1.18E-03 1.11E-03.

PERIOD Sec E.

PERCENTAGE OF ODCM DOSE LIMITS FOR GASEOUS EFFLUENT RELEASES I QTR QTR QTR QTR YEARLY

1.

NOBLE GAS RELEASE GAMMA 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 BETA 0.OOE+00 O.OOE+00 0.OOE+00 j 0.OOE+00 0.OOE+00

2.

H-3 AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS GAMMA (Highest Organ) 2.74E-04 7.70E-04 3.65E-04 1.02E-04 7.20E-04 7

EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOS MODE UNIT QTR QTR QTR QTR TOTAL NUCLIDES RELEASED

1.

FISSION GASES KRYPTON-85 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

2.

IODINE 1-131 - Analysis no longer required.

3.

PARTICULATES STRONTIUM-90 Ci 8.60E-08 4.50E-07 2.85E-07 8.20E-08 9.03E-07 CESIUM-134 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CESIUM-137 Ci 1.32E-06 5.02E-06 6.60E-07 O.OOE+00 7.OOE-06 COBALT-60 Ci 2.49E-06 6.36E-07 1.67E-07 3.81E-07 3.67E-06 Ci Ci Ci Ci Ci Ci TOTALS Ci 3.90E-06 6.11E-06 1.11E-06 4.63E-07 1.16E-05 8

EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)

.TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES I UNIT QTR QTR QTR QTR TOTAL A

FISSION & ACTIVATION PRODUCTS

1.

TOTAL RELEASE (NOT INCL.

Ci 1.70E-02 1.56E-01 7.21 E-02 1.90E-02 2.65E-01 TRITIUM, GASES, ALPHA)

2.

AVERAGE DILUTED 1iCi/

5.90E-09 3.65E-08 2.21E-08 1.96E-8 CONCENTRATION DURING ml PERIOD B.

TRITIUM

1.

TOTAL RELEASE Ci 9.31E-03 3.26E-03 2.45E-03 1.1OE-03 1.61 E-02 AVERAGE DILUTED 1tCi/

3.23E-09 7.62E-10 7.52E-10 1.13E-09 CONCENTRATION DURING ml PERIOD C.

DISSOLVED AND ENTRAINED GASES

1.

TOTAL RELEASE Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2.

AVERAGE DILUTED vCi/

.00 OOOE+00 O.OOE+0 0

O.OOE+00 CONCENTRATION DURING ml PERIOD D.

GROSS ALPHA RADIOACTIVITY

1.

TOTAL RELEASE Ci 4.58E-05 1.10E-04 17.20E-05 5.72E-05 2.85E-04 E.

VOLUME OF WASTE Liters 1.63E+05 8.38E+04 6.36E+04 2.23E+04 3.33E+05 RELEASED (PRIOR TO DILUTION)

F.

VOLUME OF DILUTION Liters 2.88E+09 4.29E+09 3.26E+09 9.73E+08 1.14E+10 WATER USED DURING PERIOD G.

PERCENTAGE OF ODCM LIMITS FOR LIQUID RELEASES QTR QTR QTR QTR YEARLY HIGHEST ORGAN 7.93 45.64 16.13 5.41 37.55 WHOLE BODY 16.7 95.82 33.91 11.39 78.91 9

EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 LIQUID EFFLUENTS NUCLIDES RELEASED UNIT QTR QTR QTR QTR MANGANESE-54 Ci 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 IRON-55 Ci 0.OOE+00 8.33E-05 3.50E-05 3.19E-06 COBALT-60 Ci 1.64E-03 2.27E-03 1.04E-03 3.01 E-04 STRONTIUM-90 Ci 1.63E-04 5.83E-04 5.41E-04 2.17E-04 CESIUM-134 Ci 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 CESIUM-137 Ci 1.52E-02 1.53E-01 7.04E-02 1.87E-02 TOTAL FOR PERIOD Ci 1.70E-02 1.56E-01 7.21 E-02 1.93E-02 (ABOVE)

KRYPTON-85 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 10

EFFLUENT AND WASTE DISPOSAL REPORT - (cont'd)

8. 0 OFFSITE DOSE CALCULATIONS

SUMMARY

AND CONCLUSIONS:

a.

Gaseous Effluent Releases The maximum quarterly offsite gamma dose due to noble gases was 0.00 mRad. The cumulative 2007 annual offsite gamma dose due to noble gases was 0.00 mRad.

The maximum quarterly offsite beta dose due to noble gases was 0.00 mRad. The cumulative 2007 annual offsite beta dose due to noble gases was 0.00 mRad.

The maximum quarterly offsite dose to any organ from the release of H-3 and all radionuclides in particulate form with half-lives greater than 8 days was approximately 5.77E-5 mRem. The cumulative 2007 annual maximum organ dose from these radionuclides was also approximately 1.08E-4 mRem.

The highest historical annual average X/Q equal to 1.82 E-6 sec/m3 for the period 1985-1987 for the worst case offsite receptor location, in accordance with the ODCM, was used to calculate these offsite dose values.

b.

Liquid Effluent Releases The maximum quarterly organ dose from liquid releases Was approximately 2.28 mRem. The cumulative 2007 annual organ dose was approximately 3.76 mRem. The maximum quarterly total body dose for liquid releases was approximately 1.44 mRem, and the cumulative 2007 annual total body dose was approximately 2.37 mRem.

c.

Conclusion All calculated offsite doses were below ODCM limits.

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