ML20238B002

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Semiannual Radioactive Effluent Release Rept,Jan-June 1987
ML20238B002
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/30/1987
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20238A995 List:
References
NUDOCS 8709010025
Download: ML20238B002 (11)
v • d • e


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Consumers Power Company Big Rock Point Plant )

Docket 50-155 i

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l SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT I JANUARY THROUGH JUNE 1987 August 27, 1987 8709010025 870827 PDR ADOCK 05000155 R PDR 10 Pages IC0887-0193A-HP01-NLO4

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Big Rock Point Semiannual Radioactive Effluent Release Report January - June 1987 l This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of Big Rock Point during the  !

period of January through June 1987 in the format contained in Technical Specification 6.9.2.2. Big Rock Point was off-line for most of this reporting period due to a refueling / maintenance outage occurring from January 3 -

March 9; and two other maintenance outages occurring from May 18-21 and May 30-June 21. j 1

1. Supplemental Information
a. Batch Release 1

Information relating te batch and continucus releases of gaseous and )

liquid effluents is provided in Table HP 10.3-1.

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b. Abnormal Releases
1) A small tube leak within the emergency condenser is suspected to have developed during the first quarter 1986. Based on a j calculated leak rate of 1.1 liters per day, the following activity levels are reported as having been released to the atmosphere (via the condenser vent) during 1987: 1 First Quarter - 1.9E-04 Ci tritium 2.0E-03 Ci fission gases Second Quarter - 4.6E-04 Ci tritium 5.6E-03 Ci fission gases These calculated activity totals have been included in the Semiannual Radioactive Effluent Release Report. The emergency condenser tube leak was repaired during the May 30 - June 21 maintenance outage.-
2) On June 30, approximately 500 gallons of slightly radioactive contaminated water was released to the Big Rock Point septic system. The incident occurred during the inspection and repair of the plant heating boiler. Water samples collected from the heating boiler fire pit revealed a Cs-137 activity concentra-tion of 1.54E-06 pCi/mi, however additional water samples obtained and analyzed from the septic system were less than the Cs-137 release MPC value (2.0E-05 pC1/ml) referenced in Appen-dix B, Table II, 10CFR20. A calculated activity release of 2.93E-06 Ci Cs-137 has been included with the second quarter liquid effluent Cs-137 total in the Semiannual Radioactive Effluent Release Report.

IC0887-0193A-HP01-NI,04

  • 2 Corrective actions taken to prevent recurrence of the above include: posting of the heating boiler as having potential internal contamination and the collecting / analyzing of boiler water samples prior to performing any inspections or mainte-nance.
2. Caseous Effluents Table HP 10.3-2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 2.34E-06% of the total release. The maximum noble gas release rate for the first and second quarters was 1.74E+03 and 3.59E+02 pCi/second, respectively.
3. Liquid Effluents Table HP 10.3-3 lists and summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 8.54% of the total release. The maximum liquid effluent release concentration for the first and second quarters was 7.32E-07 and 2.97E-07 pCi/ml, respec-tively.
4. Solid Waste Solid radwaste classification, sources, volume shipped, curie and nuclide content are detailed in Table HP 10.3-4. All radwaste shipments were sent to either Barnwell, South Carolina or Richland, Washington for burial.
5. Summary of Radiological Impact on Man Potential doses to individuals and populations were calculated using CASPAR and LADTAP computer program codes. The first and second quarter values for curies released were input for each nuclide and summarized as follows:
a. The maximum offsite air dose at the site boundary due to noble gases was 5.96E-03 millirad beta and 9.27E-03 millirad gamma for e.he first quarter; and 1.42E-02 millirad beta and 2.29E-02 millirad gamma for the second 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 infant thyroid. Doses were 8.32E-03 and 2.05E-03 millirem for the first and second quarters, respectively.
c. The maximum total body dose to individuals (adult) in unrestricted water-related exposure pathways was 6.05E-02 millirem for the first quarter and 1.32E-02 millirem for the second quarter. The maximum organ dose (child bone) was 1.23E-01 and 2.29E-02 millirem for the first and second quarters, respectively.

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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: )

3.83E-02 manRem and 2.49E-04 millirem for the first quarter; and- 1 7.13E-03 manRem and 4.63E-05 millirem for the second quarter, i

e. Integrated total body dose to the general population and average dose to individuals withip the population from gaseous effluent ~

releases within a distance of 50 miles from the site boundary were:

8.44E-03 manRem and 5.48E-05 millirem for the first quarter; and 1.44E-02 manRem and 9.35E-05 millirem'for the second quarter.

f. There was no entrained noble gas present in either the first or second quarter liquid releases. .i
6. Process Centrol Program (PCP) q

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

7. Offsite Dose, Calculation Manual (ODCM)

Effective changes made to the ODCM for this reporting period were -

previously submitted with the July-December 1986 Big Rock Point Semi- <

annual Radioactive Effluent Release Report. l l

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IC0887-0193A-HP01-NLO4

i TABLE HP 10.3-2 BIC ROCK POINT SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1

CASE 0VS EFFLUENTS - SUMMATION OF RELEASES I

JANUARY 1987 to JUNE 1987 A. Est Total FISSION AND ACTIVATION CASES ** UNITS lst QUARTER 2nd QUARTER Error %  !

1. Total release Ci 8.34E+02 2.20E+03
2. Average release rate for period uCi/see 1.07E+02 2.80E+02 6.66
3. Percent of annual avg MPC  % 2.80E-02 7. 76 E-02 1

B. IODINES

1. Total Iodine Ci 4.02E-03 8.13E-03
2. Average release rate for period uCi/sec 5.17E-04 l

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1.03E-03 5.65 Percent of annual avg MPC *  % 3.13E-05 2.06E-05 l

C. PARTICULATE

1. Particulate with half-life >

8 days Ci 3. 44 E-04 3.90E-04

2. Average release rate for period uCi/sec 4.43E-05 4.96E-05
3. Percent of annual ava MPC  % 1.54E-06 2.71E-06 10.8 4 Cross alpha radioactivity Ci 4.16 E-0 7 1.10E-06
5. Cross alpha release rate for period uCi/sec 5.35E-08 1.40E-07 D. TRITIUM **
1. Total release Ci 2.12E+00 2.19E+00
2. Average release rate for period uCi/sec 2.72E-01 2.79E-01
3. Percent of annual avg MPC  % 1.24E-05 1.27E-05 E.
1. Beta air dose at site boundary due to Noble Cases (TS 13.1.4.2a) mRads 5.96E-03 1.42E-02
2. Percent limit  % 5.96E-02 1. 42 E- 01
3. Camma air dose at site boundary due to Noble Cases (TS 13.1.4.2a) mRads 9.27E-03 2.29E-02'
4. Percent limit 1.85E-01

% 4.58E-01 F.

1. Maximum organ dose to public based based on critical receptors (TS 13.1.4.3a) mrem 8.32E-03 2.05E-03
2. Percent of limit  % 1.llE-01 2.73E-02
  • Note: Data is reported for I-131 and I-133 only
    • Note: Includes calculated emergency condenser fission gas and tritium releases to atmosphere.

MIO887-0050A-HP01 m _ _ _ _ _____ .__.----- --

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l TABLE HP 10.3-2 l

BIC ROCK POINT SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l

CASEOUS EFFLUENTS JANUARY 1987 to JUNE 1987

1. FISSION CASES Units 1st QUARTER 2nd QUARTER Krypton-85m Ci 2.83E+01 3.74E+01 Krypton-87 Ci 8.83E+01 1.82E+02 Krypton-88 Ci 7. 44 E+ 01 1.07E+02 Xenon-133 Ci 2.95E+01 1.26E+01

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Xenon-133m Ci None I None Xenon-131m Ci None i 6.59E+00 Xenon-135 Ci 1.29E+02 1.66E+02 Xenon-135m Ci 8.85E+01 2.59E+02 Xenon-138 Ci 2.86E+02 1.07E+03 Nitrogen-13 Ci 1.10E+02 3.62E+02 Total for Period

  • Ci 8.34E+02 2.20E+03
2. 10 DI t.S S Iodine-131 Ci 2.23E-03 5.00E-04 l

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Iodine-132 Ci None l

None Iodine 133 Ci 1.79E-03 5.12E-03 Iodine-134 Ci None l

None i Iodine-135 Ci None 2.51E-03  !

Total for Period Ci 4.02E-03

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8.13E-03 l Includes calculated emergency condenser fission gas release to atmosphere.

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MIO887-0050A-HP01 I

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1 TABLE HP 10.3-2 I

BIC ROCK POINT SEMI ANNUAL RADIOACTIVE l

EFFLUENT RELEASE REPORT l

I CASE 0VS EFFLUENTS

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JANUARY 1987 to JUNE 1987 i i

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3. PARTICULATE
  • Utii t s 1st QUARTER 2nd QUARTER Chromium-51 Ci 3.02E-05 4.53E-05 l Manganese-54 Ci 2.79E-05 1.53E-05

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Cobalt-58 Ci 5.80E-07 None  !

Cobalt-60 Ci 5.03E-05 3.57E-05 Zine-65 Ci 8.02E-06 2.18E-06 {

Ba ri um-140 Ci 5.74E-05 1.30E-04 Cesium-134 Ci 4.24E-05 1.72E-05 Cesium-137 Ci 6.49E-05 4.81E-05 l

Niobium-95 Ci 4.20E-07 None  !

Cesium-136 Ci 2.54E-06 None Mercury-203 Ci 3.70E-07 i None Silver-110m Ci 1.05E-05 7.00E-07 i

Molybdenum-99** Ci 1.23E-05 4.70E-06 j La n t ha n um- 14 0** Ci 1.78E-04 3.60E-04 S t ro n t i u m-91 ** Ci 1.61E-04 9.49E-04 l

Sodium-24** Ci 2.85E-05 2.15E-05 Bromine-82** Ci 4.36E-04 1.74E-03 1

l S t ro n t i um-89 *** Ci 2 . 8 E-05 4.1E-05 S t ron t i u m-90 *** Ci 1.7E-06 2.4E-06 Net unidentified beta Ci 1.92E-05 5.17E-05 Total Cross Ci 1.16E-03 3.47E-03 Total Tl > 8 days Ci 3.44E-04 3.90E-04 l

  • Particulate with half-lives >8 days.
    • Particulate with half-lives <8 days; not reflected in overall isotopic totals.

l *** Calculated from vendor analysis of monthly stack gas filters.

NOTE: Reported net beta and vendor analyzed Sr-89/90 results were inpot to OASPAR code as Sr-90 to yield conservative dose estimates.

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TABLE HP 10.3-3 i

BIC ROCK POINT SEMI ANNUAL RADIOACTIVE l EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUHMATION OF RELEASES JANUARY 1987 to JUNE 1987 j

l A. Est Total 1 FISSION AND ACTIVATION PRODUCTS UNITS 1st QUARTER 2nd QUARTER Error %

1. Total release (not including tritium, gases, alpha) Ci 1.45E-01 2.14E-02
2. Average diluted concentration during period uci/mi 1.13E-08 9.64E-10 5.95
3. Percent of MPC 1.32

% 9.05E-02 B. TRITIUM

1. Total release Ci 4.05E-01 6.97E-02
2. Average diluted concentration during period uCi/ml 3.16E-08 3.14E-09 4.96
3. Percent of MPC  % 1.05E-03 1.05E-04 C. DISSOLVED AND ENTRAINED CASES
1. Total Release Ci None i None
2. Average diluted concentration j during period uCi/ml None None N/A
3. Percent of MPC  % None None D. CROSS ALPHA RADIOACTIVITY (Total Release) Ci 6.43E-06 2.09E-06 l

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1. Average diluted concentration during period uci/ml 5.02E-13 9.41E-14 i

E. VOLUME OF WASTE RELEASED (Prior to Dilution) Liters 3.65E+05 8.13E+04 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 1.28E+10 2.22E+10 l C. MAXIMUM DOSE COMMITMENT - WHOLEBODY mrem 6.05E-02 Percent of TS 3.24.4.la limit 1.32E-02_(

)  % 4.03 8.80E-01 1 H. HAXIMUM DOSE COMMITMENT - ORCAN mrem 1.23E-01 2.29E-02 Percent of TS 3.24.4.la limit  % 2.46 4.58E-01 M10887-0050A-HP01

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TABLE HP 10.3-3 l l

BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE ~-~

EFFLUENT RELEASE REPORT

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LIQUID EFFLUENTS JANUARY 1987 to JUNE 1987 l l

1. NUCLIDES RELEASED Units 1st QUARTER 2nd QUARTER Cesium-137 Ci 8.43E-03 3.37E-03*

Cobalt-58 Ci 5.90E-04 None f

j Manganese-54~ Ci 2.88E-02 4.40E-03 j Cobalt-60 Ci 3.90E-02 5.70E-03 Cesium-134 Ci 5.06E-03 8.80E-04 1

Iron-59 Ci 5.01E-03 None )

Chromium-51 Ci 3.95E-03 8.20E-04 1 l

l Zinc-65 Ci 2.46E-03 1.90E-04 l

Niobium-95 C1 1.37E-04 None Strontium-92 Ci None 1.36E-06 Silver-110m Ci 1.09E-03 6.00E-05 Iodine-131 Ci 1.03E-03 None Strontium-89** Ci 2.9E-04 1.3E-04 Strontium-90** Ci 9.3E-05 4.7E-05 Net Unidentified Beta Ci 4.89E-02 5.82E-03 Fission & Activation Product Total (Above) Ci 1.45E-01 2.14E-02 Xenon-133 Ci None None Tritium Ci 4.05E-01 6.97E-02 Grand Total Ci 5.50E-01 9.11E-02

  • Includes calculated Cs-137 release from heating boiler.
    • Calculated from vendor analysis of monthly radwaste composite samples.

NOTE: Reported net beta and vendor analyzed Sr-89/90 results were input to LADTAP code as Sr-90 to yield conservative dose estimates.

MIO887-0050A-HP01-NLO4

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TABLE HP 10.3-1  !

i BIG ROCK POINT SEMIANNUAL RADIOACTIVE

-EFFLUENT RELEASE REPORT BATCH RELEASES JANUARY 1987 to JUNE 1987 i

l A. Gaseous - Continuous Release i

l B. LIQUID l

Number of Releases 21 6 Total Release Time Minutes 5.42E+03 1.27E+03 l Maximum Release Time Minutes 7.65E+02 4.60E+02 Average Release Time Minutes 2.58E+02 '2.llE+02 .{

l Minimum Release Time Minutes 1.18E+02 6.30E+01 I

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MIO887-0050A-HP01

TABLE HP 10.3-4 BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT SOLID RADI0 ACTIVE WASTE JANUARY 198' to JUNE 1987 Waste Source of Solidification Container Volume Total *Principa,1 Class Waste Agent Type (Cu.ft.) Curies Radionuclides A DAW N/A Strong tight 1314.0 2.4 Mn-54,Co-60,Cs-137, container-LSA Fe-55,Ni-63,C-14 B Irradiated N/A Steel Liner 252.0 1132.0 Co-60,Fe-55,Mn-54, Metal Zn-65,Ni-63 C Irradiated N/A Steel Liner 36.4 1161.6 Co-60,Fe-55,Mn-54, Metal Zn-65,Ni-63 Total Shipped 1602.4 2296.0 l

  • Note: Gamma isotopes are measured quantities, all other isotopes are estimated.

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MIO887-0050A-HP01-NLO4

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