ML20149M982

Semiannual Radioactive Effluent Release Rept for Jul-Dec 1987

ML20149M982
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/31/1987
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20149M967	List: ML20149M966 ML20149M982 ML20149N070
References
NUDOCS 8802290342
Download: ML20149M982 (4)

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. ATTACHMENT-

[ Consumers Power Company l Big Rock Point Plant Docket 50-155; s  :

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SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT' JULY THROUGH DECEMBER 1987 l

, February 26. 1988 l

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BIC ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 1987 This report provides information relating to the radioactive ef fluent releases and solid radioactive waste disposal operations of Big Rock Point during the period o' July - December 1987. Format for this report is contained in Technical Specification 6.9.2.2. Big Rock was on-line for most of this reporting period with the exceptions of the following "mini-outage" dates:

July 24-26; September 8-10, November 9-14, November 21-23 and December 2-7.

Reasons for the maintenance outages were due to minor steam leaks.

1. Supplemental Information A. Batch Releases

Information relating to continuous and batch releases of gaseous and liquid ef fluents is provided in Tsble HP 10.3-1.

B. Abnormal Releases j None. ,

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2. Caseous Effluents i

( Table HP 10.3-2 lists and summarizes all gaseous radioactive effluents

' released during the reporting period. The unidentified beta was >

3.10E-06% of the total release. The maximum noble gas release rate for the third and fourth quarters was 3.69E+02 and 3.65E+02 pCi/second, respectively.

l 3. Liquid Effluents Table HP 10.3-3 lists and summarizes all liquid radioactive effluents l released during the reporting period. The unidentified beta was 15.6% of l the total release. The maximum liquid effluent release concentration for the third and fourth quarters was 1.86E-06 and 1.14E-07 pCi/m1, respec-i j tively.

4. Solid Waste Solid radwaste classification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.3-4. The one radwaste shipment was sent to Richland, Washington for burial.

IC0288-002iA-HP01

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5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using CASPAR and LADTAP computer program codes. The third and fourth quarter values for curies released were input for each nuclide and summarized as follows:

a. The maximum of f site air dose at the site boundary due to noble gases was 1.83E-02 millirad beta and 3.05E-02 millirad gamma for the third quarter; and 1.42E-02 millicad beta and 2.33E-02 millirad gamme for the fourth quarter.

b. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluents (tritium, particulate and iodine) was the child bone. Doses were 1.36E-02 cnd 5.77E-03 millires for the third and fourth quarters, res pect ively.

c. The maximum total body dose to individuals (adult) in unrestricted water-related exposure pathways was 4.65E-02 millires for the third quarter and 7.22E-03 millires for the fourth quarter. The maximum organ dose (child bone) was 1.00E-01 millires for the third quarter and 1.15E-02 millires (teenage liver) for the fourth quarter.

d. Integrated total body dose to the general population and average dose to individuals within the population f rom liquid effluent releases within a distance of 50 miles from the site boundary weret 2.62E-02 manRem and 1.70E-04 millirem for the third quartert and 3.43E-03 manRem and 2.23E-05 millirem for the fourth quarter.

e. Integrated total body dose to the general population and average dose to individuals within the population from gaseous ef fluent releases within a distance of 50 miles from the site boundary were:

1.81E-02 manRem and 1.18E-04 millirem for the third quarter; and 1.45E-02 manRen and 9.42E-05 millires for the fourth quarter.

f. There was no entrained noble gas present in either the third or fourth quarter liquid releases.

6. Proces s Cont rol Program (PCP)

There were no changes to the PCP during this reporting period.

7. Of f site Dose Calculation Manual (ODCM)

There were no changes to the ODCM during this reporting period.

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8. Supplemental Information to the BRP January - June 1987 Semiannual Radioactive Effluent Release Report The Big Rock Point. Semiannual Radioactive Ef fluent Release Report; January - June 1987, Table HP 10.3-2 Caseous Effluents are being submitted as an attachment for the following revisions:

A. Table HP 10.3-2; Caseous Effluents - Summation of Releases, item C.3., 2nd Quarter only:

Change the Particulate Percent of Annual Average MPC from 2.71E-06 to 2.72E-06.

B. Table HP 10.3-2; Caseous Ef fluents (isotopic Ci listings), item 3, Particulates; 2nd Quarter only:

Change Sr-90 from 2.4E-06 Ci to 2.5E-06 Ci. Change Net Unidentified Bets from 5.17E-05 Ci to 5.16E-05 Ci.

Reasons for the above data revisions to the Big Rock Point Semiannual Radioactive Ef fluent Release Report, January - June 1987 was that the calculated Sr-90 releans quantity (gaseous effluent only) was based on an estimated value for the month of June. Teledyne Isotopes Midwest Laboratory had not yet completed the actual sample analysis prior to the Technical Specification Semiannual Reoort due date. All data changes are indicated by "i" in the right-hand margins. There were no reportable dose changes to the public.

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