ML20011F568

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Semiannual Radioactive Effluent Release and Waste Disposal Rept,Jul-Dec 1989
ML20011F568
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 12/31/1989
From: Eddy J
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9003060285
Download: ML20011F568 (12)
v • d • e


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Nuclear Regulatory Commission Document Control Desk Washington, DC 20$55 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

SDilANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT - JULY TUROUGH DECEMBER 1989 Attached is the Semiannual Radioactive Efflyent Release and Waste Disposal I

Report for the Big Rock Point Plant covering the period July through December 1989. This submittal is made in accordance with 10 CFR S0.36a and Technical Specification 6.9.2.2

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J Daniel Eddy Plant Licensing Engineer i

CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point Attachment

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Consumers Power Company Big Rock Point Plant Docket 50-155 l

l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JULY THROUGH DFCDtBER 1989 February 26, 1990 h

10 Pages DC0290-0019-NLO2

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Bla Rock Point Semisnnual Radioactive Effluent Release Report July - December 1989 This report provides information relating to the radioactive ef fluent releases and solid radioactive waste disposal operations of Big Rock Point during the period of July - December 1989. Format for this report is contained in Technical Specification 6.9.2.2.

Big Rock Point was online in the third and f ourth quarters, except f or the f ollowingt July 1 to August 13 for REFOUT, August 22 through August 23, and October 28 through November 4.

1.

Supplemental Information A.

Batch Releases Information relating to continuous and batch releases of gaseous and i

liquid effluents is provided in Table HP 10.3-1.

B.

Abnctsal Releases None.

C.

Lower Limits of Detection (LLD's) for gaseous and liquid ef fluents is provided on page 9 of this report.

2.

Caseous Effluents Table HP 10.3-2 lists and summarizes all gaseous radioactive effluents released during the report period. The unidentified beta was 5.86E-07% of the total release. The maximum noble gas release rate for the third and fourth quarters was 2.36E+02 and 2.15E+02 pCi/second, respectively.

3.

Llauid Effluents Table HP 10.3-3 lists and summarizes all liquid radioactive ef fluents released during the reporting period. The unidentified beta was 7.48% of the total release. The maximum liquid effluent release concentration for the third and fourth quarters was 7.03E-07 and 5.41E-08 pCi/m1, respectively.

4.

Solid Radioactive Waste Solid radwaste classification sources, volume shipped, curie and nuclide h.

content are detailed in Table HP 10.3-4.

Radwaste shipments were processed and sent to Barnwell, South Carolina for burial.

IC0290-0048A-HP01 1

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5.

Summary of Radiolonical Imoact 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 off site air doses due to noble gases was during the fourth quarter.

Doses at the site boundary (.57 mi E) were 7.87E-03 millirad beta and 1.40E-02 millired gamma. Doses at the nearest residence / garden (1.40 mi E) were 9.37E-03 millired beta and 1.67E-02 millirad gamma.

B.

The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) f rom gaseous effluents (tritium, particulates, and iodines) was the infant thyroid for both the third and fourth quarters. Doses were 2.10E-03 millirem and 2.41E-03 millirem respectively.

C.

The maximum total body dose to individuals (adult) in unrestricted 9

water-releated expoeure pathways was 6.78E-02 millires for the third quarter and 5.77E-03 millires for the fourth quarter. The maximum organ dose was the adult bone for the third and the fourth quarters.

1 Doses were 1.90E-01 millires and 1.13E-02 millires, respectively.

D.

Integrated total body dose to the general population and average dose to individuals within the population from liquid effluent releases within a distance of 50 miles from the site boundary were 4.26E-02 manRem and 2.77E-04 millires, respectively, for the third quarter, and 2.80E-03 manRem and 1.82E-05 millires, respectively, for the fourth quarter.

E.

Integrated total body dose to the general population and average dose to individuals within the population from gaseous effluent releases-within a distance of 50 miles from the site boundary were 5.12E-03 manRem and 3.32E-05 millires, respectively, for the third quarter, and 8.94E-03 manRen and 5.81E-05 milliram, respectively, for the fourth quarter.

F.

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

6.

Process Control Proaram (PCP)

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

7.

Offsite Dose Calculation Manual (ODCH)

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

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IC0290-0048A-HP01 2

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TABLE NP 1003-1 BIC ROCK Po!WT SEMI AWWUAL RADICACTIVE EFFLUENT RELEASE REPORT EATCH RELEASES JULY 1989 to DECEMBER 1989 A.

Caseous - Continuous Release 8.

LIQUID 3rd Quarter 4th Quarter Number of Releases 30 Total Release Time Minutes 5.63E+03 8.77E+02 Maximum Release Time Minutes 8.05E+02 2.85E+02 Average Release Time Minutes 1.88E+02 1.75E+02 Minimum Release Time Minutes 3E+00 1.24E+02 h

MIO290-0024A-HP01 3

G ai TABLE WP 10.3-2 SIC ROCK PO!WT SEMI ANWUAL kADI0 ACTIVE EFFLUENT RELEASE REPORT CASCOUS EFFLUENTS - SUMKATION OF RELEASES

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JULY 1989 to DECEMBER 1989 Est Total A.

FISSION AND ACTIVATION CASES UNITS 3rd QUARTER 4th QUARTER Error %

1.

Total release Ci 1.00E+03 1.88E+03 I

2.

Averste release rate for period uCi/see 1.26E+02 2.37E+02 6.1 3.

Percent ot' annual ava MPC 3.54E-02 6.61E-02 B.

IODINES 1.

Total Iodine Ci 1.08E-02 6.90E-03 2.

Averste release rate for period

  • uCi/sec 8.05E-04 7.35E-04 5.02*

3.

Percent of annual ava MPC 2.37E-Oi 2.31E-OS C.

P ARTI CULATES 1.

Particulates with half-life >

8 days Ci 4.70E-04 6.09E-04 2.

Averste release rate for period uCi/sec 5.91E-05 7.66E-05 3.

Percent of annual ava MPC 1.65E-06 9.98E-07 15.7 4.

Cross alpha radioactivity Ci 3.44E-06 5.80E-06 5.

Cross alpha release rate for period uCi/see 4.33E-07 7 30E-07

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D.

TRI TI UM 1.

Total release Ci 1.27E+00 1.34E+00 2.

Average release rate for period uCi/see 1.60E-01 1.69E-01 3.

Percent of annual ava MPC 1

7.27E-06 7.68E-06 E.

I 1.

Beta air dose at site boundary due to Noble Cases (TS 13.1.4.2a) mRads 4.30E-03 7.87E-03 2.

Percent limit 4.30E-02 7.87E-02 3.

Camma air dose at site boundary due to Noble Cases (TS 13.1.6.2a) mRads 7.69E-03 1.40E-02 4

Percent limit 1

1.54E-01 2.80E-01 F.

1.

Maximum organ dose to public based based on critical receptors h

(TS 13.1.4.3a) mrem 2.10E-03 2.41E-03 2.

Percent of limit 2.80E-02 3.21E-02

  • No_tet Data is reportco for 1-131 and I-133 only MIO290-0024A-HP01 4

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TA8LE HP 10.3-2 L

BIC ROCK POINT SEMI ANNUAL RADICACTIVE EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS JULY 1989 to DECEMBER 1989 l

1.

FISSION CASES Units 3rd QUARTER 4th QUARTER c.

Ni t ronen-13 Ci 2.53E+02 5.02E+02 Krypton-85m Cl 1.31E+01 2.33E+01 K rypt on-87 Ci 6.5E+01 1.20E+02 Krypton-88 Cl 4.3E+01 7.3E+01 Xenon-133 Ci 5.1 E+ C 0 9.4E+00 Xenon-133m Ci

<LLD

<tLD Xenon-135 Cl 5.6E+01 1.03E+02 Xenon-135m Cl 1.07E+02 2.04E+02 Xenon-138 Ci 4.60E+02 8.40E+02 Total for Period Cl 1.00E+03 1.88E+03 2.

IODINES Iodine-131 Ci 6.3E-04 7.40E-04 Iodine 133 ci 5.77E-03 5.10E-03 i

Iodine-135 C1 4.41E-03 1.06E-03 Total for Period Ci 1.08E-02 6.90E-03 h

M10290-0024A-HP01 5

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1 TABLE WP 10.3-2 i

BIC ROCK POINT SEMI ANNUAL RADICACTIVE EFFLUENT RELEASE RF. PORT CASBOUS EFFLUENTS JULY 1989 to DECEMBER 1989 3.

P ARTI CULATES*

Units 3rd QUARTER 4th QUARTER

  • *S od i u m-24 Ci

<tLD 6.70E-04 Chromium-51 Ci 1.70E-05 1.76E-04 Manaanese-54 Ci 7.20E-05 4.10E-05 Cobalt-58 Ci

<tLD 1.41E-06 Iron 59 Ci

< t.LD

<l.I.D Cobalt-60 Ci 6.90E-05 8.00E-05 Zine-65 Ci 1.61E-05 3.60E-06

    • Bromine 82 Ci 1.53E-04 2.77E-04 S t ron t i um-89 Ci 2.00E-05 4.07E-05 Strontium-90 Ci 9.51E-07 8.84E-07
    • Strontium-91 Ci 3.76E-04 9.89E-04
    • M ol ybde num-99 Cl 1.30E-09 3.80E-08 Silver llom Ci 1.29E-05 4.80E-06 Cesium-134 Ci 2.20E-05 1.29E-05 Ce s i um-137 Cl 1.48E-04 9.80E-05 Barium-140 Ci 7.50E-05 1.50E-04
    • Lanthanum-140 Ci 1.94E-04 4.10E-04 Cerium-141 Ci (LLO

<LLD Cerium-144 C1 (LLD

<tl.D W

Net unidem ified beta Ci 1.69E-05 sLLD Total Ci 4.70E-04 6.09E-04 Particulates with half-lives >8 days.

l Particulates with half-lives (8 dayst not reflected in overall isotopic totals.

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' TABLE HP 10.3-3 BIC ROCK POINT SEMIANWUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

LIQUID EFFLUENTS - SUMMATION OF RELEASES JULY 1989 to DECEMBE1 1989 4

Est Total A.

FISSION AND ACTIVATION PRODUCTS UNITS 3rd QUARTER 4th QUARTER.

Error 1 i

1.

Total release (not including I

t ritium. asses, sipha )

C1 1.59E-01 6.92E-03 2.

Average diluted concentration durina period uci/el 8.55E-09 2.76E-10 5.86 3.

Percent of MPC 1

8.82E-01 2.85E-02 i

B.

TRITIUM 1.

Tot al release C1 4.68E-01 1

3.92E-02 l

2.

Average diluted concent ration

~

i durina period

. uci/ml 2.52E-08 1.56E-09 6.70 3.

Percent of MPC I

1 8.39E-04 5.21E-05 C.

DISSOLVED AND ErfRAINE'D CASEE 1.

Total Release Ci (LLD

<LLD 2.

Average diluted concentration during pe riod uCilal NA NA NA 2,_ Percent of MPC 1

NA NA D.

GROSS ALPHA RADI0 ACTIVITY I

(Total Release)

Ci 5.52E-06 i 4.80E-07 E.

VOLUME OF WASTE RELEASED (Prior to Dilution)

Liters 4.84E+05 8.82E+04 F.

VOLUME OF DILUTION WATER USED DURING PERIOD Liters

1. 86 E+ 10 l

2.51E+10 C.

MAXIMUM DOSE COPMITMENT - WHOLEBODY mrem 6.78E-02 5.77E-03 Percent of TS 13.1.4.la limit 1

4.52E+00 i

3.85E-01 H.

MAXIMUM DOSE COMMITMENT - ORGAN mrem

1. 90 E- 01 l

1.13E-02 Percent of TS 13.1.4.la limit 3.80E400 l

2.26E-01 MIO290-0024A-HP01 7

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TABLE WP 10.3-3 llc ROCK POINT SENIANNUAL RADI0 ACTIVE l

EFFLUENT RELEASE REPORT LIQUID EFFLUENTS 1

JULY 1989 to DECEMBER 1989 1.

NUCLIDES RELEASED Units 3rd QUARTER 4th QUARTER Chr omium-51 Cl 2.46E-03

<LLD Manaanese-54 Ci 4.29E-02

1. 30 E-03 i

Cobalt-58 Ci 1.44E-03 (LLD Iron-59 Ci 9.10E-03 1.0E-04 Cobalt-60 Cl 4.03E-02 1.60E-03 Zine-65 Ci 2.44E-03

<tLD

  • Strontium-89 Cl 9.84E-05 8.61E-06
    • Mol ybd e num-99 Ci (LLD

<LLb Silver llom Ci 7.93E-04

< t LL_

Tin-ll3 Ci 1.18E-04 (LLD Antimonyal24 Ci

,2.12E-04

<LLD Cesium-134 Ci 1.31E-03 1.20E-04 Cesium-137 Ci 9.80E-03 1.70E-03

    • Cerium-141 Ci

<tLD

<LLD

    • Cerium-144 Ci

<LLD

<LLD Net Unidentified Beta C1 4.83E-02 2.07E-03 Fission & Activation Product Total (Above)

Ci 1.59E-01 6.92E-03 Xenon-133 Ci (LLD

<LLD Alpha ci 5.52E-06 4.80E-07 l

Tr i t i wn ci 4.68E-01 3.921: v2 l-Crand Total Ci 6.27E-01 4.61E-02 i

o Calculated f rom vendor analysis of monthly liquid radwaste composites. Reported vendor l

analyzed Sr 89/90 results were input to CASPAR code as Sr90 to yield conservative dose e s t i ma t e s.

    • Particulates with half-lives (8 days; not reflected in overall isotopic totats.

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MIO290-0024A-HP01 8

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Lower Limits of Dotection (LLD's) fer C

Bia Rock Pount Effluents Caseous Effluents kkD (pC1/ml)

Xe-133e 6E-05 Co-58 3E-14 4

Na-24 4E-13 Ce-141 3E-14 Ce-144 1E-13 Fe-59 9E Unidentified S-

$E-14 1

?f Liould Effluents

[

htD (pCi/ml)

Cr-51 1E-06 Co-58 IE-07 Un-65 3E-07 Ho-99 8E-08 As-110m SE-08 Sn4113 2E-07 SS-124 1E-07 Xe-133 3E-07 Ce-141 2E-07 Ce-144 7E-07 l

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TABLE HP 10.3-4 BIC ROCK POINT WUCLEAR PLAWT SEMIAWNUAL LAD 10 ACTIVE EFFLUEWT RELEASE REPORT l

i SOLID RADIOACTIVE WASTE JULY 1989 to DECEMBER 1989 Waste Source of Solidification Container Volume

  • Total
  • Princi pa l Cl as s Waste Aaept Type (cu ft) Curles Radioclides A/U Dry Active Waste N/A

$$ Cal 1320 2.58 Co-60,Mn-54,Cs-137 and Filters drums -

2n-65,Cs-134,Fe-55 LSA B

Resin Dewate red HIC-395 89.5 Co-60,Cs-137,Cs-134, Type A Mn-54,Fe-55,Q-14 C

Resin Dewatered HIC-604 179.6 Cs-137,co-60,Cs-134, Type A Fe-55,Mn-54,Zn-65, Ag-110m TOTAL 2319 271.68 h

CNOTE Camma isotopes are measured quantitiest all other isotopes are estimated.

MIO290-0024A-HP01 10 i

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