ML20214L199

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Semiannual Radioactive Effluent Release Rept,Jan-June 1986
ML20214L199
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/30/1986
From: Frisch R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8609090516
Download: ML20214L199 (11)
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s ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY THROUGH JUNE 1986 August 28, 1986 8609090516 860630 PDR R ADOCK 05000155 '~

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o 1 BIG ROCK POINT SEMIANNUAL EFFLUENT RELEASE REPORT JANUARY - JUNE 1986 This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Big Rock Point Plant during the period of January through June 1986 in the format contained in Plant Technical Specification 6.9.2.2. The January - June 1986 Semiannual Effluent Release Report reflects effluent Technical Specification changes effective January 1, 1986. Big Rock Point has been on-line for most of this reporting period.

1. Supplemental Information
a. Batch Release Information relating to batch and continuous releases of liquid and gaseous effluents is provided in Table HP 10.3-1.
b. Abnormal Releases None.
2. Gaseous Effluents Table HP 10.3-2 lists and summarizes all gaseous radioactive effluents released during the reporting period. There was no unidentified beta released. The maximum noble gas release rate for the first and second quarters were 2.09E+03 and 2.42E+03 microcuries/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 2.35% of the total release. The maximum liquid effluent release concentration for the first and second quarters were 9.00E-08 and 7.00E-08 microcuries/ milliliter, respectively.
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 made 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 l GASPAR 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 doses at site boundary due to noble gases were 8.69E-02 and 1.13E-01 millirads beta for the first and second quartets respectively. The maximum offsite air doses for gamma were 1.35E-01 and 1.75E-01 millirads, respectively.

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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 1.38E-02 and 1.73E-02 millirem for the first and second quarters.
c. The maximum total body doses to individuals in unrestricted

, water-related exposure pathways were 8.02E-03 and 3.42E-03 millirem for first and second quarters, respectively, with the maximum organ dose being (child bone) 1.17E-02 and 6.14E-03 millirem per quarter, respectively.

d. Integrated total body doses to the general population and average doses to individuals within the population from liquid effluent
releases within a distance of 50 miles from site boundary were 3.54E-03 and 1.87E-03 manRem for the first and second quarters, respectively, and 2.30E-05 and 1.21E-05 millirem per quarter, respectively.

Integrated total body doses to the general population and average e.

i doses to individuals within the population from gaseous effluent releases within a distance of 50 miles from site boundary were i 1.30E-01 and 1.72E-01 manRem for the first and second quarters respectively with 8.44E-04 and 1.12E-03 millirem per quarter respectively,

f. There were no entrained noble Fas isotopes present in any liquid releases for this reporting period.
6. Process Control Program (PCP)

There were no changes to the PCP this reporting period.

7. Offsite Dose calculation Manual (ODCM)

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

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\ 3 TABLE HP 10.3-1 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JANUARY 1986 to JUNE 1986 A. Gaseous - Continuous Release B. LIQUID Units 1st Quarter 2nd Quarter Number of Releases 3 4 Total Release Time Minutes 5.90E+02 6.45E+02

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Maximum Release Time Minutes 2.11E+02 2.55E+02 Average Release Time Minutes 1.97E+02 1.61E+02 Minimum Release Time Minutes 1.89E+02 8.00E+01 AT0886-0137-NLO2

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! TABLE HP 10.3-2 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JANUARY 1986 to JUNE 1986 Est Total A. FISSION AND ACTIVATION GASES UNITS 1st QUARTER 2nd QUARTER Error

1. Total release Ci 1.12E+04 1.45E+04-
2. Average release rate for period uCi/sec 1.44E+03 1.86E+03 4.57
3. Percent of annual avg limit (TS 13.1.3.1) % 3.87E-01 5.03E-01 B. IODINES
1. Total Iodine Ci 8.46E-03 1.26E-02
2. Average release rate for period uCi/sec 1.09E-03 1.60E-03 *4.83
3. Percent of annual avg limit (TS 13.1.3.1) % 5.53E-05 7.42E-05 C. PARTICULATES 4
1. Particulates with half-life >

8 days Ci 9.33E-04 2.25E-03

2. Average release rate for period uCi/see 1.20E-04 2.86E-04
3. Percent of annual avg limit (TS 13.1.3.1) % 2.47E-06 1.01E-05 19.4 l
4. Gross alpha radioactivity Ci 5.13E-07 1.27E-06 D. TRITIUM
1. Total release Ci 2.25 2.41
2. Average release rate for period uCi/sec 2.89E-01 3.06E-01
3. Percent of annual avg limit (TS 13.1.3.1) % 1.31E-05 1.39E-05 E.
1. Beta air dose at site boundary due to Noble Gases (TS 13.1.4.2a) mRads 8.69E-02 1.13E-01
2. Percent limit  % 8.69E-01 1.13E+00
3. Gamma air dose at site boundary due to Noble Cases (TS 13.1.4.2a) mRads 1.35E-01 1.75E-01
4. Percent limit  % 2.70E+00 3.50E+00 I

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1. Maximum organ dose to public based based on critical receptors (TS 13.1.4.3a) mrem 1.38E-02 1.73E-02
2. Percent of limit  % 1.84E-01 2.31E-01
  • Note: Data is reported for I-131 and I-133 only.

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5 TABLE HP 10.3-2 (Cont'd)

BIG ROCK POINT SEMIANNUAL RADIOACTIVE

EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JANUARY 1986 to JUNE 1986
1. FISSION GASES Units let QUARTER 2nd QUARTER Krypton-85m Ci 4.72E+02 5.83E+02 Krypton-87 Ci 1.29E+03 1.71E+03 Krypton-88 C1 1.24E+03 1.56E+03 Xenon-133 Ci 5. 98 E+02 8.18E+02 Xenon-131m Ci 2.15E+02 None Xenon-135 C1 2.06E+03 2.86E+03
Xenon-135m C1 1.26E+03 2.03E+03 Xenon-138 Ci 3.54E+03 4.45E+03 i Nitrogen-13 Ci 4.93E+02 5.29E+02 Total for Period Ci 1.12E+04 1.45E+04 i

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2. 10 DINES Iodine-131 C1 3.49E-03 4.37E-03 Iodine-132 Ci None None l

Iodine 133 Ci 4.97E-03 8.18E-03 Iodine-134 Ci None None Iodine-135 Ci None None Total for Period Ci 8.46E-03 1.26E-02 i

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TABLE HP 10.3-2 (Cont'd)

BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JANUARY 1986 to JUNE 1986

3. PARTICULATES* Units 1st QUARTER 2nd QUARTER Chromium-51 C1 3.88E-05 2.01E-05 Manganese-54 Ci 9.77E-06 2.01E-06 Cobalt-58 Ci None None Cobalt-60 Ci 4.92E-05 1.40E-05 Zine-65 Ci 8.48E-06 3.36E-06 Molybdenum-99** Ci 4.40E-05 6.01E-05 i Cesium-134 Ci 8.93E-05 2.56E-05 i

Cesium-136 Ci 9.32E-06 None Cesium-137 Ci 1.04E-04 4.40E-05 Lanthanum-140** Ci 9.87E-04 7.41E-04 Barium-140 Ci 2.95E-04 2.25E-04 ,

i Sodium-24** Ci 1.73E-04 2.56E-04 f Bromine-82** Ci 2.44E-03 4.02E-03 i

Strontium-89*** C1 3.25E-04 1.85E-03 i

Strontium-90*** C1 3.72E-06 6.43E-05 l Strontium-91** C1 3.94E-03 2.29E-03 t

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, Net unidentified beta Ci None None i,

f Total Ci 9.33E-04 2.25E-03

  • Particulates with half-lives >8 days.
    • Particulates with half-lives < 8 days; not reflected in overall isotopic totals.
      • Calculated from vendor analysis of monthly stack gas filters.

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

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7 TABLE HP 10.3-3 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JANUARY 1986 to JUNE 1986 Est Total A. FISSION AND ACTIVATION CASES UNITS 1st QUARTER 2nd QUARTER Error

1. Total release (not including tritium, gases, alpha) Ci 7.99E-03 5.34E-03
2. Average diluted concentration during period uCi/ml 3.30E-10 2.15E-10 5.28
3. Percent of MPC (TS 13.1.2.1)  % 3.06E-02 2.37E-02 B. TRITIUM
1. Total release C1 4.26E-02 1.02E-01
2. Average diluted concentration during period uC1/ml 1.76E-09 4.11E-09 4.52
3. Percent of MPC (TS 13.1.2.1)  % 5.87E-05 1.37E-04 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci None None
2. Average diluted concentration during period uCi/ml None None N/A 3 ,, Percent of MPC (TS 13.1.2.1)  % None None D GROSS ALPHA Radioactivity Total Release) C1 1.58E-07 7.96E-07 E. VOLUME OF WASTE RELEASED (prior to Dilution) Liters 5.00E+04 5.39E+04 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.42E+10 2.48E+10 G. MAXIMUM DOSE COMMITMENT - WHOLEBODY mrem 8.02E-03 3.42E-03 2

Percent of TS 13.1.4.la limit  % 5.35E-01 2.28E-01 I

H. MAXIMUM DOSE COMMITMENT - ORGAN mrem 1.17E-02 6.14E-03 Percent of TS 13.1.4. la limit  % 2.34E-01 1.23E-01

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  • 8 TABLE HP 10.3-3 (Cont'd)

BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS JANUARY 1986 to JUNE 1986

1. NUCLIDES REI EASED Unitz ist QUARTER 2nd QUARTER Cesium-137 Ci 2.05E-03 8.83E-04 Cobalt-58 Ci None None Manganese-54 Ci 1.00E-03 9.83E-04 Cobalt-60 C1 1.70E-03 1.53E-03 Cesium-134 Ci 7.59E-04 2.07E-04 Iron-59 Ci None None Lathanum-140 Ci None None Zine-65 Ci 3.44E-04 1.08E-05 Molybdenum-99 Ci None None Cerium-141 Ci None None Cerium-144 Ci None None Iodine-131 Ci 5.74E-05 3.56E-05 Strontium-89*** Ci 1.02E-05 1.02E-05 Strontium-90*** Ci 1.58E-05 2.17E-05 i

Net Unidentified Beta Ci 2.05E-03 1.66E-03 l Fission & Activation Product Total (Above) Ci 7.99E-03 5.34E-03 Xenon-133 Ci None None Ci i

f Ci j Tritium Ci 4.26E-02 1.02E-01 Grand Total Ci 5.06E-02 1.07E-01

      1. 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.

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  • A 9 TABLE HP 10.3-4 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE JANUARY 1986 to JUNE 1986 W;cte Source of Solidification Container Volume Total
  • Principal Cim's Waste Agent Type (Cu.ft.) Curies Radionuclides A DAW N/A B-25 Box-LSA 1260.0 2.0 Mn-54,Co-60,Cs-137, Drums-LSA Zn-65,Ag-110m Strong tight container-LSA A Dewatered N/A HIC-PL 195.0 19.7 Co-60,Fe-55,Mn-54, Filters 195 FF Zn-65 C Irradiated N/A Steel Liner 13.0 230.0 Mn-54,Co-60,Fe-55, Metal Ni-63,Sn-119M Total Shipped 1468.0 251.7 ANote: Gamma Isotopes are measured quantities, all other isotopes are estimated.

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Consumers Power rewaums nu m *""

ANUMEAN5 P-Nt* g" 9 oeneral officos: 1945 West Parnall Road, Jackson, MI 49201 . (517) 788-0550 (g j W 1L

?;s August 28, 1986 N L'"

]t James G Keppler, Administrator Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - JANUARY THROUGH JUNE 1986 Attached is the Semiannual Radioactive Effluent Release Report for Big Rock Point Plant for the period January through June 1986. The attached report is submitted in accordance with 10CFR50.36T(2) and Technical Specification Section 6.9.2.

Ra1 R Frisch Senior Licensing Analyst CC Director, Office of Nuclear Reactor Regulation Director, Office on Inspection and Enforcement NRC Resident Inspector - Palisades Attachment SEP 1 gp M986 0C0886-0137-NLO2

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