ML20238B014

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Revised Semiannual Radioactive Effluent Release Rept, Jul-Dec 1986
ML20238B014
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 12/31/1986
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20238A995 List:
References
NUDOCS 8709010032
Download: ML20238B014 (16)
v • d • e


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ATTACHMENT 3 Consumers Power Company ,

Big Rock Point Plant Docket 50-155 REVISED SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT JULY THROUGH DECEMBER 1986 August 27, 1987

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8709010032 870827 5 PDR ADOCK 050 R 15 Pages 1 IC0287-0103A-HP01-NLO4 i

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i BIG ROCK POINT SEMIANNUAL EFFLUENT RELEASE PIPORT JULY - DECEriBER 1986 )

This report provides information relating to radioactive effluent releases and solid radioactive waste disposal operations of the Big' Rock Point Plant during 3 i

the period of July through December 1986 in the format contained in Plant Technical Specification 6.9.2.2. The July - December 1986 Semiannual Effluent Release Report reflects effluent Technical Specification changes effective January 1, 1986. Big Rock Point has been continuously 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 A small tube leak within the emergency condenser is suspected to have developed during the 1st Quarter. Based on a calculated leak rate of 1.1 liters pdr day, the following activity levels are reported as having been released to the atmosphere (via the conden-ser vent):

3rd Quarter - 0.85 mci tritium 52 mci fission gases l 4th Quarter - 0.75 mci tritium l 60 mci fission gases j These calculated activity amounts have been included with the Semi-Annual Radioactive Effluent Release Report totals. Previous calculated activity amounts that occurred during the 1st and 2nd Quarters were included in the January - June 1986 Semi-Annual Radioactive Effluent Release Report. The emergency condenser is to be thoroughly inspected and tested during the next scheduled mainte-nance outage.

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 third and fourth quarters was 4.51E+03 and 4.58E+03 uCi/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 4.04% of IC0287-0103A-HP01-NLO4 l

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l the total release. The maximum liquid effluent release concentration for i the third and fourth quarters was 5.77E-07 and 7.75E-08 uCi/ml, l l respectively, l l l

4. Solid Waste No solid radwaste shipments were made during the third or fourth quarters 1986.

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5. Summary of Radiological Impact on Man I j

I Potential doses to individuals and populations were calculated using l GASPAR and LADTAP computer program codes. The third and fourth quarter 1 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 1.55E-01 millirad beta and 2.45E-01 millirad gamma for the third t quarter; and 1.64E-01 millirad beta and 2.53E-01 millirad gamma for l the fourth quarter.

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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 5.04E-02 and 2.45E-02 millirem for the third and fourth quarters, respectively.  ;
c. The maximum total body dose to individuals in unrestricted water-related exposure pathways was 3.26E-02 millirem for the third  !

quarter and 4.58E-03 millirem for the fourth quarter. The maximum j organ dose was (child bone) 4.91E-02 and 7.50E-03 millirem for the third and fourth quarters, 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- i 1.53E-02 manRem and 9.94E-05 millirem for the third quarter; and i 2.06E-03 manRem and 1.34E-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 effluent I releases within a distance of 50 miles from the site boundary were:

2.18E-01 manRem and 1.42E-03 millirem for the third quarter; and 2.60E-01 manRem and 1.69E-03 millirem for the fourth quarter.

f. There was no entrained noble gas present in the fourth quarter liquid releases.
6. Process Control Program (PCP)

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

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7. Offsite Dose Calculation Manual (0DCM) '

The following ODCM changes are being submitted per the requirements of Technical Specifications 6.9.2.2.A(5) and 13.2.3:

a. Offsite Dose Calculations, page 14, Rev 1, items b and c - change b. l to read: 20 millirem to skin of an individual from noble gas; change c. to read: 10 millirem to the total body of an individual from noble gas. The changes meet the design objectives of Technical Specification 13.1.4.2 - Effluent Dose - noble gases.
b. Land Use Census Report, page 36, Rev 2, table 1.4 -. revised distance from plant site to nearest residence, garden, dairy / beef cattle and goat per meteorological sector.

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c. Land Use Critical Receptors, page 37, Rev 2, table 1.4a - ruised ' j critical receptor items / locations with highest X/Q values adjacent a to plant site.

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d. 1986 Gaseous Design Objective Annual Quantities, pages 51 and 52, Rev 2, table 1.9 - revised 1986 gaseous design objective release limits for Big Rock Point.

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IC0287-0103A-HP01-NLO4 i

' VOLUME 25 BRF FADI0 LOGICAL EFFLUE*iT T/S PECUIRED DOCUME!.7S Fev 1 A. CFFSITE DOSE CALCULATIONS Pego ib of 71 l .

a. 1$ eillires to any organ of an individual froe iodines and particulate.
b. 20 millites to skin of an individual from noble gas. I 1
c. 10 millires to the total oody of an individual froe noble gas. I Design basis quantity (Ci) is the smallest value for each nuclide, calculated.by dividing the dose limits (a through c above) by the appropriate dose calculated in step 1; the result then is sultiplied i by the amount of radionuclides (Ci) used to conservatively estimate the doses of Section D, as listed in Table 1.1 (or assumed a hypothetical 1 C1/ year for nuclides not actually present):

DBQ = D (Cc ) (I.15) c where:

D AI = Appendix I dose limit (area or arad).

D c = Calculated dose from step 1 (area or arad).

C

= Quantity of nuclide resulting in dose De (Ci).

DBQ = Design Basis Quantity (C1).

The limiting values for Design Basis Quantities for radionuclides released to the atmosphere are given in Table 1.9.

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Rev. 2 '

Pa;;e 36 of 71 I

BIG ROCK POINT LAND USE CENSUS REPORT 1 1

1 TABLE 1.4 Distance to tb.2 nearest residence, garden, dairy / beef cattle and goat in each I sector. )

l SECTOR- RESIDENCE GARDEN DAIRY COW BEEF CKTTLE GOAT WSW 2.5 mi >5 mi >5 mi >5 mi >5 mi SW 1.1 mi >5 mi >5 mi >5 mi >5 mi SSW 1.3 mi 2.1 mi >5 mi >5 mi >5 mi S 1.9 mi >5 mi >5 mi >5 mi >5 mi SSE 1.7 mi 1.8 mi 3.5 mi 3.5 mi >5 mi SE 1.7 mi >5 mi 4.0 mi 1.7 mi >5 mi ESE 1.5 mi 2.4 mi 2.6 mi 2.6 mi >5 mi E 1.4 mi 2.5 mi 2.5 mi 2.5 mi >5 mi ENE 2.3 mi >5 mi >5 mi >5 mi >5 mi l

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  • Rev. 2

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Table 1.9 i

j BIG ROCK Po1NT PLANT 1986 GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity l Nuclide Ornan aras/Ci (C1) l G1 Tract 1.91E-01 7.85E+01 l Ag-110m Ar-41 Total Body 1.62E-05 3.09EM5 G1 Tract 2.38E-11 6.30E+11 1 Ba-139 Bone-C 1.01E-02 1.49E+03 l Ba-140 Br-82 Total Body 1.38E-03 3.62EM3 Bone-C 9.80E-03 1.53E+03 )

C-14 GI Tract-T 2.80E-02 5.36E+02 i Ce-141 G1 Tract-T 7.45E-01 2.01E+01 l Ca-144 G1 Tract-T 1.88E-02 7.98E+02 l Co-57  !

Total Body-c 1.12E-02 4.46EM 2 Co-58 Co-60 Total Body-C 6.66E-02 7.51E+01 l Cr-51 GI Tract-A,T 5.20E-04 2.88E+04 i

9. 80E+00 i Cs-134 Liver-C 1.53E+00 3.40E+02 I Cs-136 Total Body-7. 1.47E-02 Cs-137 Bone-C 1.50E+00 1.00E+01 Cs-138 Total Body 4.32E-22 1.16E+22 Fe-55 Bone-C 4.57E-02 3.28E+02 I Fe-59 GI Tract T 5.33E-02 2.81E+02 H-3 Total Body-C 1.12E-05 4.46E+05 I-131 Thyroid-1 3 A 7t00 4.08EMO I-132 Thyroid-C , Et e Cs 2.0iLMS 1-133 Thyroid-I .V u 4.45E+02 I-134 Thyroid-C 4.v3E-14 3.04E+14 1-135 Thyroid-C 9.93E-05 1.51E+05 Kr-83m Skin 3.94E-08 3.81E+08 Kr-85 Skin 3.91E-06 3.84E+06 Kr-85a Total Body 2.27E-06 2.20E+06 Kr-87 Skin 3.65E-05 4.11E+05 Kr-88 Total Body 2.79E-05 1.79E+05 Kr-89 Total Body 1.18E-06 4.24E+06 La-140 GI Tract-A 1.50E-03 1.00E+04 Mn-54 G1 Tract-T 5.38E-02 2.79E+02 Mn-56 G1 Tract-C 5.07E-08 2.96E+08 Mo-99 Kidney-1 2.20E-03 6.82EM3 N-13 Total Body 1.53E-51 3.27E+51 Na-24 Total Body 1.10E-04 4.55EM 4 Nb-95 GI Tract-A 5.78E-02 2.60EM 2 Ni-65 G1 Tract-C 2.26E-08 6.64E+0B Np-239 G1 Tract 2.52E-04 5.95E+04 Rb-88 Total Body-C 2.66E-33 1.88E+33 Ru-103 G1 Tract-A 9.22E-02 1.63E+02 Sb-124 G1 Tract-T 1.71E-01 8.77E+01 Sb-125 G1 Tract-T 9.67E-02 1.55E+02 1C1286-0272A-HP01

Rev. 2 Page 52 of 71 Table 1.9 (cont'd)

BIG ROCK POINT PLANT 1986 CASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ ares /Ci (C1)

Sr-89 fone-C 2.01E+00 7.46E+00 Sr-90 Boos-C 8.27EMI 1.81E-01 Sr-91 GI Tract 1.28E-05 1.17E+06 Sr-92 GI Tract 1.18E-07 1.27EM 8 Tc- % GI Tract-1 1.12E-07 1.34E+08 Te-101 Total Body 1.26E-40 3.97E+40 Te-127 G1 Tract-A 9.45E-06 1.59E+06 Ka-131m ' Skin 1.73E-06 8.67E+06 Ka-133 Total Body 5.94E-07 8.42EM6 Ie-133m Skin 3.60E-06 4.17E+06 Xe-135 Total Body 3.59E-06 1.39E+06 la-135a Total Body 3.17E-06 1.58EM 6 Xe-137 Skin z.48E-06 6.05E+06 Xa-138 Total Body 8.39E-06 5.96E+05 Zn-65 Total Body-C 1.01E-01 4.95E+01 Zr-95 GI Tract-T 7.04E-02 2.13E+02 4

IC1286-0272A-BP01

TABLE HP 10.3-1 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JULY 1986 to DECEMBER 1986 A. Gaseous - Continuous Release B. LIQUID Units 3rd Quarter 4th Quarter _

Number of Releases 4 4 ,

1 Total Release Time Minutes 1.19E+03 5.15E+02 Maximum Release Time Minutes 5.47E+02 1.61E+02 Average Release Time Minutes 2.96E+02 1.29E+02 l l

!!inimum Release Time Minutes 1.81E+02 8.00E+01 I l

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TABLE HP 10.3-2 BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS - SUMMATION OF RELEASES JULY 1986 to DECEMBER 1986 Est Total A. FISSION _AND ACTIVATION GASES ** UNITS 3rd QUARTER 4th QUARTER Error {

1. Total release Ci 2.13E-04 2.09E+04 l
2. Average release rate for period uCi/sec 2.69E+03 2.62E+03 5.05  !
3. Percent of annual avg MPC

% 6.24E-01 6.12E-01 l B. 10 DINES

1. Total Iodine I-131 and I-133 Ci 2.98E-02 1.76E-02  ;
2. Average release rate for period uCi/sec 3.75E-02 2.21E-03 *4.32 I
3. Percent of annual avg MPC  % 1.95E-04 1.04E-04 C. PARTICULATE
1. Particulate with half-life >

8 days Ci 1.80E-03 2.12E-03

2. Average release rate for period uCi/sec 2.26E-04 2.67E-04 13.6
3. Percent of annual avg MPC  % 5.51E-06 4.91E-06
4. Gross alpha radioactivity Ci 1.57E-06 7.28E-07 D. TRITIb"i **
1. Total release Ci 2.48 2.36
2. Average release rate for period uCi/sec 3.12E-01 2.97E-01
3. Percent of annual avg MPC  % 1.42E-05 1.35E-05 l

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1. Beta air dose at site boundary due to Noble Gases (TS 13.1.4.2a) mRads 1.55E-01 1.64E-01
2. Percent limit  % 1.55E+00 1.64E+00
3. Gamma air dose at site boundary due to Noble Gases (TS 13.1.4.2a) mRads 2.45E-01 2.53E-01
4. Percent limit  % 4.90Et00 5.06E+00 F.
1. Maximum organ dose to public based based on critical receptors (TS 13.1.4.3a) mrem 5.04E-02 2.45E-02
2. Percent of limit  % 6.72E-01 3.27E-01
  • Note: Data is reported for I-131 and I-133 only.
    • Note: Includes calculated emergency condenser fission gas and tritium released to the atmosphere.

IC0287-0103A-HP01-NL04

TABLE RP 10.3-2 BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE  !

EFFLUENT RELEASE REPORT 0ASE0US EFFLUENTS JULY 1986 to DECEMBER 1986 l

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1. FISSION GASES Units 3rd QUARTER 4th QUARTEF l Krypton-85m Ci 7.87E+02 9.67E+02 j i

Krypton-87 Ci 2.10E+03 2.41E+03 Krypton-88 Ci 1.93E+03 2.47E+03

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Xenon-133 Ci 1.39E+03 1.60E+03 l 1

i Xenon-133m Ci None None (

l Xenon-135 Ci 3.76E+03 4.65E+03 1 Xenon-135m Ci 3.65E+03 2.70E+03 Xenon-138 Ci 7.24E+03 5.63E+03 i l

Nitrogen-13 Ci 4.81E+02 4.40E+02 l t

Total for Period

  • Ci 2.13E+04 2.09E+04
2. IODINES Iodine-131 Ci 1.28E-02 6.21E-03 l

fodine-132 Ci None None i Iodine 133 Ci 1.70E-02 1.14E-02 Iodine-134 Ci None None Iodine-135 Ci 1.26E-02 None Total for Period Ci 4.24E-02 1.76E-02

  • Note: Includes calculated emergency condenser fission gas release to atmosphere.  !

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O TABLE HP 10.3-2 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JULY 1986 to DECEMBER 1986

3. PARTICULATE
  • Units 3rd QUARTER 4th QUARTER Chromium-51 Ci 1.81E-04 6.17E-04 Manganese-54 Ci 3.15E-06 6.04E-06 Cobalt-58 Ci None 5.63E-06 Cobalt-60 Ci 5.53E-05 1.09E-04 Zinc-65 Ci 1.59E-05 6.50E-05 Molybdenum-99** Ci 7.62E-05 3.48E-04 Cesium-134 Ci 9.60E-05 2.29E-04 Cesium-137 Ci 1.20E-04 2.29E-04 Niobium-95 Ci 3.28E-06 None Bromine-82** Ci 5.22E-03 3.64E-03 Lanthanum-140** Ci '

1.31E-03 1.18E-03 Neptunium-239** Ci None 1.63E-04 Sodium-24** Ci 2.05E-03 4.06E-03 Strontium-91** Ci 6.21E-03 None Barium-140 Ci 4.44E-04 3.71E-04 Cesium-136 Ci None 1.58E-05 Silver-110m Ci 2.17E-05 4.02E-05 Strontium-89*** Ci 8.35E-04 4.04E-04 Strontium-90*** Ci 2.53E-05 3.00E-05 Net unidentified beta Ci None None l

Total Ci 1.80E-03 2.12E-03

  • 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.

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

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"ABLE HP 10.3-3 1 BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l

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LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l JULY 1986 to DECEMBER 1986 I

Est Total A. FISSION AND ACTIVATION GASES UNITS 3rd QUARTER 4th QUARTER Error

1. Total release (not including tritium, gases, alpha) Ci 5.30E-02 4.56E-03 l j g
2. Average diluted concentration during period uCi/ml 2.14E-09 1.82E-10 5.46
3. Percent of MPC  % 4.09E-02 2.94E-03 l j i

B. TRITIUM

1. Total release Ci 1.86E-01 2.00E-02 1
2. Average diluted concentration i during period uCi/ml 7.50E-09 7.97E-10 4.40 l
3. Percent of MPC  % 2.50E-04 2.66E-05 l C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 1.12E-04 None I
2. Average diluted concentration during period uCi/ml 4.52E-12 None 26.9
3. Percent of MPC  % 2.26E-06 None l

l D. GROSS ALPHA RADIOACTIVITY Total Release) Ci 1.60E-06 5.29E-07***

E. VOLUME OF WASTE RELEASED (prior to Dilution) Liters 7.12E+04 4.78E+04 l F. VOLUME OF DILUTION WATER USED DURING PERIOD Li ters 2.48E+10 2.51E+10 G. MAXIMUM DOSE COMMITMENT - WHOLEBODY mrem 3.26E-02 4.58F-03 Percent of TS 13.1.4.la limit  % 2.17E+00 3.05E-01 H. MAXIMUM DOSE COMMITMENT - ORGAN mrem' 4.91E-02 7.50E-03 Percent of TS 13.1.4.la limit  % 9.82E-01 1.50E-01

      • Calculated from vendor analysis of monthly radwaste sample composite.

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IC0287-0103A-HP01-NLO4

1 TABLE HP 10.3-3 BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS JULY 1986 to DECEMBER 1986 I

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1. NUCLIDES RELEASED Units 3rd QUARTER 4th QUARTER l, Cesium-137 Ci 8.59E-03 1.36E-03 i

Cobalt-58 Ci None None Manganese-54 Ci 4.48E-03 3.98E-04 Cobalt-60 Ci 9.01E-03 9.90E-04 l l

Cesium-134 Ci 2.82E-03 2.86E-04 l

i Iron-59 Ci 4.39E-04 None Chromium-51 Ci 1.55E-02 None Zinc-65 Ci 7.70E-04 None 1

Molybdenum-99 Ci 2.78E-04 None I

Cesium-136 Ci 1.13E-04 None Strontium-92 Ci 2.22E-05 None Iodine-133 Ci 8.55E-05 None l Iodine-131 Ci 1.76E-03 3.85E-06 Strontium-89*** Ci 3.08E-08 9.05E-06 Strontium-90*** Ci 4.27E-08 2.67E-05 Net Unidentified Beta Ci 9.17E-03 1.49E-03 Fission & Activation Product Total (Above) Ci 5.30E-02 4.56E-03 Xenon-133 Ci 1.12E-04 None Tritium Ci 1.86E-01 2.00E-02 Grand Total Ci 2.39E-01 2.46E-02

      • Calculated from vendor analysic 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. i IC0287-0103A-HP01-NLO4 t

i TABLE HP 10.3-4  ;

BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT SOLID WASTE JULY 1986 to DECEMBER 1986 ,

1 Waste Source of Solidification Container Volume Total Principal Class Waste Agent ,

Type (Cu.ft.) Curies Radionuclides No solid radwaste shipments were made during the 3rd and 4th quarte: of 1986 i l

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