ML20212D522

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Semiannual Radioactive Effluent Release Rept,Jul-Dec 1986
ML20212D522
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 12/31/1986
From: Johnson B
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8703040139
Download: ML20212D522 (17)
v • d • e


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.. ' ATTACHMENT s-Consumers Power Company.

Big Rock Point Plant-Docket 50-155 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY THROUGH DECEMBER 1986 February 27, 1987 h

8703040139 861231

. PDR ADOCK 05000155

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I IC0287-0059-NLO4 >[l l l

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BIC ROCK POINT SEMIAhhUAL EFFLUENT RELEASE REPORT J ' JULY - LECEMBER 1986 This report provides information relating to radioactive effluent releases and rolid radioactive waste disposal operations of the Big Rock Point Plant during 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 ef fective January 1, 1986. Big Rock Point has been continuously on-line for most of this reporting period.

~1. Supplemental Inferration

a. Batch Relwase 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 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 unicentified beta was 4.05% of the total release. The maximum liquid effluent release concentration fcr i

the third and fourth quarters was 5.77E-07 and 7.75E-08 uCi/ml, respec-tively.

4. Solid Waste l

l No solid radwaste shipments were made during the third or fourth quarters 1986.

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

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a. Themaxdmum'offsite.airdoseat the site boundary due to noble gases was 1.655E-01 millirad beta and 2.45E-01 millirad gamma _for the third quarter; and l1.64E-01 millirad beta and 2.53E-01.r.1111 rad gamma for the' fourth quarter.

r b. The most restrictive organ dose to an individual in an unrestricted

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area- (based on identified _ critical receptors) f rom- gaseous effluents (tritium,. particulate .and iodine) was the inf ant 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 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 affluent

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

_ l.53E-02 manRem and 9.94E-05 millirem for the third quarter; and 2.06E-03 manRem and 1.34E-05 millires for the fourth quarter.

.e. , Integrated total body dose to the general population and average dose to individuaJs within the population from gaseous effluent 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 2.61E-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.

I 6. Process Centrol Program (PCP)

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

7. Offsite Dose Calculation Manual (ODCM)

The following ODCM changes are being submitted per the requirements of l-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.

r to read: 20 millirem to skin of an individual from noble gas; 2 change c. to read: 10 millirem to the total body of an individual l

from noble gas. The changes meet the design objectives of Technical Specification 13.1.4.2 - Effluent Dose - noble gases.

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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 j goat per meteorological sector.

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c. Land ll[s'eCriticalReceptors,page37,Rev2, table 1.4a-revised critical receptor items / locations with highest X/Q values adjacent to plant site.
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.

NOTE: -See n+ -

hed changed pages from _the ODCM.

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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-Total Release Time Minutes' 1.19E+03 5.15E+02 Maximum Release Time Minutes 5.47E+02 1.61E+02 Averase Release Time Minutes 2.96E+02 1.29E+02 Minimum Release Time Minutes 1.81E+02 8.00E+01 i

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t, 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 QUARTERi4th QUARTER Erro r

1. Total release Ci 2.13E+04 2.09E+04
2. Average release rate for period uCi/sec 2.69E+03 2.62E+03 5.05
3. Percent 13f annual ava MPC -% i 6.24E-01 6.12E 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
3. : Percent of annual ava MPC .

% 1.95E-04 1.04E-04 C. PARTICULATES

1. Particulates with half-life >

8 days Ci 1.80E-03 2 2.42E-03

2. Average release rate for period uCi/sec 2.26E-04 3.04E-04 13.6
3. Percent of annual ava MPC  % 5.51E-06 5.93E-06
4. Gross alpha radioactivity  : Ci 1.57E-06 7.28E-07 i D. -TRITIUM
1. Total release Ci 2.48 2.36 "'
2. Average release rate for period uCi/sec 3.12E-01 2.97E-01 4
3. Percent of annual ava MPC  % 1.42E-05 1.35E-05 i E.
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 ' 4.90E+00 5.06E+00

! u l 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 I  % 6.72E-01 3.27E-01
  • N:te: Data is reported for I-131 and 1-133 only.

IC0287-0103A-HP01

C TABLE HP 10.3 , BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GASEOUS EFFLUENTS JULY 1986 to DECEMBER 1986 l 1. FISSION GASES Units 3rd QUARTER 4th QUARTER I- Krypton-85m Ci '7.87E+02' 9.67E+02 Krypton-87 Ci 2.10E+03 2.41E+03 I

i Krypton-86 Ci 1.93E+03 2.47E+03 i

Xenon-133 Ci 1.39E+03 1.60Et03 Xenon-133m Ci -None None Xenon-135 Ci 3.76E+03 4.65E+03 Xenon-135m Ci 3.65E+03 2.70E+03 Xenon-138 Ci 7.24E+03' 5.63E+03 Nitrogen-13 Ci 4.81E+02 4.40E+02 Total.for Period Ci 2.13E+04 2.09E+04

2. 10 DINES Iodine-131 Ci 1.28E-02 6.21E-03 Iodine-132 Ci None None

.1 Iodine 133 Ci 1.70E-02 1.14E-02 Iodine-134 Ci None None I Iodine-135 Ci 1.26E-02 None Total for Period Ci 4.24E-02 1.76E-02 TC0287-0103A-HP01

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TABLE HP;10.3-2

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BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6 ,

4 GASEOUS EFFLUENTS JULY 1986 to DECEMBER 1986

3. PARTICULATES* Units 3rd QUARTER I 4th QUARTER Chromium-51 Ci 1.81E-04 6.17E-04 t t

- Manganese-54 Ci 3.'15E-06 6.04E Cobalt-58' Ci None 5.63E-06 i l

Cobalt-60 Ci'  ! 5.53E-05 1.09E-04

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Zinc-65 C1 1.59E-05 6.50E-05  !

Molybdenum-99**- Ci 7.62E-05 3.48E-04 l 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** l Ci 5.22E-03 3.64E-03 Lanthanum-140** Ci 1.31E-03 1.18E-03 Neptunium-239** Ci None 1.63E-04 l Sodium-24** Ci 2.05E-03 4.06E-03 I Strontium-91** Ci . 6.21E-03 None  !

Barium-140 Ci 4.44E-04 3.71E-04 l Cesium-136 Ci None l 1.58E-05 Silver-110m Ci 2.17E-05 l 4.02E-05 t-Strontium-89*** Ci 8.35E-04 l 7.04E-04 Strontium-90*** Ci 2.53E-05 l 2.68E-05 Net unidentified beta Ci None None Total Ci 1.80E-03 2.42E-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.

IC0287-0103A-HP01

e TABLE HP 10.3-3 BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES JULY 1986 to DECEMBER 1986 Est Total A. FISSION AND ACTIVATION GASES UNITS 3rd QUARTER 4th QUARTER Error

1. Total release (not including tritium, gases, alpha) i Ci 5.30E-02 4.57E-03
2. Average diluted concentration j during period , uCi/ml 2.14E-09 1.82E-10 5.46
3. Percent of MPC i  % 4.09E-02 2.82E-03 B. TRITIUM i
1. Total release '

Ci 1.86E-01 2.00E-02

2. Average diluted concentration during period  : uCi/ml 7.50E-09 7.97E-10 A.40
3. Percent of MPC  !  % 2.50E-04 2.66E-05 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 1.12E-04 None
2. Average diluted concentration during period uCi/ml 4.52E-12 None 26.9
3. Percent of MPC  % 2.26E-06 None D. GROSS ALPHA RADI0 ACTIVITY Total Release) Ci 1.60E-06 3.92E-07***

E. VOLUME OF WASTE RELEASED (prior to Dilution) Liters 7.12E+04 4.78E+04 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 2.48E+10 2.51E+10 G. MAXIMUM DOSE COMMITMENT - WHOLEB0DY mrem 3.26E-02 4.58E-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 f rom vendor analysis of monthly radwaste sample composite.

IC0287-0103A-HP01

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sf TABLE HP 10.3-3

~ BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT J

LIQUID EFFLUENTS JULY 1986 to DECEMBER 1986

1. NUCLIDES RELEASED Units 3rd QUARTER 4th QUARTER Cesium-137 Ci 8.59E-03 1.36E-03 Cobalt-58 Ci None None Manganese-54 Ci 4.48E-03 3.98E-04 Cobalt-60 Ci 9.01E-03 9.90E-04 i

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Cesium-134 Ci 2.82E-03 2.86E-04 Iron-59 Ci 4.39E-04 None Chromium-51 Ci 1.55E-02 None Zine-65 Ci 7.70E-04 None Molybdenum-99 Ci 2.78E-04 None

-Cesium-136 Ci 1.13E-04 None Strontium-92 Ci 2.22E-05 None 4

Iodine-133 Ci 8.55E-05 None Iodine-131 Ci 1.76E-03 3.85E-06 Strontium-89*** Ci 3.08E-08 6.60E-06 l

Strontium-90*** Ci 4.27E-08 l 1.58E-05 i Net Unidentified l Beta Ci 9.17E-03 ,,

1.51E-03 Fission & Activation i Product Total (Above) Ci 5.30E-02 l 4.57E-03 i Xenon-133 Ci 1.12E-04 None  !

Tritium Ci 1.86E-01  ! 2.00E-02 i l

Grand Total Ci 2.39E-01 2.46E-02

      • 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.

IC0287-0103A-HP01

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TABLE HP 10.3-4 ,

., ' BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SOLID WASTE JULY 1986 to DECEMBER 1986 W:ste- Source of Solidification. Container Volume Total Principal;

~Cless Waste Atent Type (Cu.ft.) Curies Radionuclides N3 solid radwaste shipments were made during the 3rd and 4th quarters of 1986 t

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8 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

AS DESCRIBED IN ITEM 7 0F THE BIG ROCK POINT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY THROUGH DECEMBER 1986 h

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IC0287-0059-NLO4

5 VOLLHE 23 BRF FAD 0 LOGICAL EFTLUE*iT T/S FECt!IPED XCLHE!.7S Bev 1 A. CFFSITE DCSE CALCULATIONS Paga lb of 71

e. '15 millites to any organ of an individual free iodines and particulates,
b. 20 millires to skin of an individual from noble gas. I
c. 10 millires to the total body of an individual froe noble gas. I Design basis quantity (Ci) is the smallest value for each nuclide, calcula'ted by dividing the dose llaits (a through c above) by the appropriate dose calculated in step 1; the result then is multiplied by the amount of radionuclide (Ci) used to conservatively estimate the doses of Section D, as listed in Table 1.1 (or assumed a hypothetical 1 Ci/ year for nuclides not actually present):

DBQ = DAI (C g ) (I.15)

D, where:

D AI

  • Appendix I ' lose limit (mree or mead).

D, = Calculated dose from step 1 (area or erad).

C, = Quantity of nuclide resulting in dose D, (Ci).

DSQ = Design Basis Quantity (Ci).

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

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  • Rev. 2 Pa;;s 36 of 71 BIG ROCK POINT LAND USE CENSUS REPORT J TABLE 1.4 Distance to the nearest residence, garden, dairy / beef cattle and goat in each sector.

SECTOR RESIDENCE GARDEN DAIRY COW BEET CATTLE 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 at 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

IC0685-0178A-MP01

Rev. 2

. Page 3 7 ol' 71 TABLE 1.4a Critical Receptors BIG ROCE FOINT PLANT f 1987 CASPAR INPUT .

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Distance I/Q X/Q Decay I/Q Decay & Dep D/Q f (sec/m*) (sec/m*) (sec/m*) (1/m*)

Location Sector (miles)

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1.4 5.92E-08 5.90E-08 5.80E-08 1.25E-09 Residence /Carden E i

0.5 9.12E-08 9.09E-08 9.03E-08 1.97E-09 j Site Boundary ESE 1.7 4.!!E-08 4.10E-08 4.01E-08 5.37E-10 I Beef Cow SE 2.5 3.79E-08 3.77E-08 3.64E-08 4.14E-10 l Diary Cow E 1

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? age 31 M 71 Table 1.9 BIG ROCK POINT PLANT

1986 GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Desi8n Objective Dose Factor Annual Quantity Nuclide Orman area /Ci (C1)

Ag-110m GI Tract 1.91E-01 7.85EM1 Ar-41 Total Body 1.62E-05 3.09EM S Ba-139 GI Tract 2.38E-11 6.30E+11 Ba-140 Bone-C 1.01E-02 1.49EM 3 Br-82 Total Body 1.38E-03 3.62E+03 C-14 Bone-C 9.80E-03 1.53E+03 Ce-141 GI Tract-T 2.80E-02 5.36EM 2 Co-144 GI Tract-i 7.45E-01 2.01E+01 GI Tract-T 1.88E-02 7.98E+02 Co-57 Co-58 Total Body-C 1.12E-02 4.46E+02 Total Body-C 6.66E-02 7.51E+01 Co-60 GI Tract-A.T 5.20E-04 2.88E+04 Cr-51 Cs-134 Liver-C 1.53E+00 9.80E+00 Ca-136 Total Body-1 1.47E-02 3.40E+02 Cs-137 Bone-C 1.50E+00 1.00E+01 Ca-138 Total Body 4.32E-22 1.16E+22 Fe-55 Bone-C 4.57E-02 3.28EM2 Fe-59 GI Tract-T 5.33E-02 2.81E+02 H-3 Total Body-C 1.12E-05 4.46 EMS I-131 Thyroid-I 3.68E+00 4.08E+00 1-132 Thyroid-C 7.26E-04 2.07EM8 I-133 Thyroid-I 3.37E-02 4.45E+02 I-134 Thyroid-C 4.93E-14 3.04E+14 I-135 Thyroid-C 9.93E-05 1.51EM5 Kr-83a skin 3.94E-08 3.81E+08 Er-85 Skin 3.91E-06 3.84E+06 Er-85a Total Body 2.27E-06 2.20E+06

4.11E+05 Kr-87 Skin 3.65E-05 Total Body 2.79E-05 1.79E+05 Kr-88 Total Body 1.18E-06 4.24E+06 Kr-89 4 La-140 GI Tract-A 1.50E-03 1.00EM4 GI Tract-T 5.38E-02 2.79E+02 Mn-54 Mn-56 GI Tract-C 5.07E-08 2.96EM 8 Kidney-I 2.20E-03 6.82E+03 Mo-99 Total Body 1.53E-51 3.27E+51 I N-13 Total Body 1.10E-04 4.55E+04 i Na-24 2.60E+02 Nb-95 GI Tract-A 5.78E-02 GI Tract-C 2.261-08 6.64E+08 Ni-65 5.95E+04 Np-239 GI Tract 2.52E-04 i 1.88E+33 Rb-88 Total Body-C 2.66E-33 J

GI Tract-A 9.22E-02 1.63E+02 l Ru-103 GI Tract-T 1.71E-01 8.77E+01 Sb-124 CI Tract-T 9.67E-02 1.55E+02 Sb-125 IC1286-0272A-HP01 i

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

. SIC ROCK POINT PLANT 1986 CASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Assual Quantity Ormas ares /Ci (C1)

Nuclide Some-C 2.0!E+00 7.44E+00 Sr-59 Sr-90 Bone-C 8.27E+0L 1.815-01 GI Tract 1.285-05 1.17EM6 Sr-91 G1 Tract 1.188-07 1.27 EMS Sr-92 G1 Tract-1 1.125-07 1.36 EMS Tc-99m Tc-101 Total Body 1.26E-40 3.97t+40 Ta-127 CI Tract-A 9.45E-06 1.59EM6 Skia 1.73E-06 8.675+06 Ka-131m Xa-133 Total Body 5.94E-07 8.42EM6 Xa-133m Skia 3.60E-06 4.17EM6 Total Body 3.59E-06 1.39EM6 Xa-135 Xa-135m Total Body 3.17E- 06 1.58EM6 Xa-137 Skia 2.48E-06 6.05EM6 Xa-138 Total Body 8.395-06 5.96t+05 Total Body-C 1.01E-01 4.95E+01 En-65 GI Tract-T 7.04E-02 2.13E+02 Er-SS I

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1C1286-0272A-RP01

Consumers

@o'0WERN9G MKJNEAN5 NROGRESE power General offices: 1945 West Pernail fload, Jackson, MI 49201 e (517) 70s 0550 February 27, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT -

JULY TilROUCll DECEMBER 1986 Attached please find the Radioactive Effluent Release Report for the Big Rock Point Plant for the period July 1986 through December 1986. The attached report is submitted in accordance with 10CFR50.36a(2) and Technical Specifications Section 6.9.2.2. Included in this report are changes to the Offuite Dose Calculation Manual (ODCM) as required per Technica'6 Specifications 6.9.2.2A and 13.2.3.

p u . n - mu <

Brian D Johnson -

Staff Licensing Engineer ,

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

Attachment .

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OC0287-0059-NLO4 \

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