ML20153G081

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Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jan-June 1988
ML20153G081
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/30/1988
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20153G020 List:
References
NUDOCS 8809080036
Download: ML20153G081 (17)
v • d • e


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ATTACHMENT Consumers Power Company l

Big Rock Point Plant i Docket 50-155 l

l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND WASTE DISPOSAL REPORT JANUARY THROUGH JUNE 1988 i

i August '31, 1988 i I

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Big Rock Point Semiannual Radioactive .

l Effluent Release Report January - June 1988 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 January - June 1988. Format for this report is contained in Tech- '

i nical Specification 6.9.2.2. Big Rock Point was off-line for the second quarter of 1988 due to a refueling outage.

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1. Supplemental Information A. Batch Releases Information re sting to continuous and batch releases of gaseous and liquid offluent is provided in Table HP 10.3-1.

B. Abnormal Releases I

Wone.

2. Caseous Effluents Table HP 10.3-2 lists and sununarless all gaseous radioactive ef fluents l l released during the reporting period. There was no reported unidentified '

I beta for the total release. The maximum noble gas release rate for the l first and second quarters was 2.93E+02 and 2.15E+02 pci/second, l respectively.  :

3. Liquid Effluents Table HP 10.3-3 lists and suonarizes all liquid radioactive ef fluents released during the reporting period. The unidentified beta was 25.0% of the total release. The maximum liquid effluent release concentration for i l

the first and second quarters was 4.94E-07 and 1.4.E-06 pC1/mt ,

respectively.  ;

4. Solid Radioactive Weste Solid radweste classification sources, volume shipped, curie and nuclide content are detailed in Table HP 10.3-4 Two radwaste shipments were processed and sent to Barnwell, South Carolina for burial. <

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5. Sunenary of R 3 dioloalcal Impact on Man Potential doses to individuals and popule:lons were calculated using CASPAR and LADTAP computer program codes. The first and second quarter values for curics released were input for each nuclide and summarized as follows i iOO88. 01 m .H,01 1

A. The maximum offs?.e air dose due to roble gases was 9.97E-03 millirad beta and 1.73E-02 millirad gamme for the first quarter at site boundaryt and 2.3E-03 millirad beta and 1.96E-03 milliras.

gamma for the second quarter at 1.4 miles (nearest residence).

B. The most rencrictive organ dose to ar individual in an unrestricted area (based on identified celtical receptors) f rom gaseous ef fluents (tritium, poeticulates, and iodines) was the infant thyroid for the first quarter and chlid bone for the second quarter. Doses vere 2.96E-03 m!U lrem and 2.83E-03 millirem, respectively.

C. The maximum total body dose to individuals sedult) in unrestricted water-related exposure pathways was 4.40E-02 millirem for the first quarter and 4.74E-02 millirem for the second quarter. Tt.e as .irum organ dose was the child bone for the first and secone quartars.

Doses were 7.14E-02 millirem and 1.00E-01 millirem, respectively.

D. Integrated total body dose to the general population and averese dose to individuals within the popuistion from liquid effluent releases within a dis'.ance of 50 miles froa the site boundavy sere i 1.92E-02 r.anRem and 1.25E-04 millirem for the first quartert and 3.36E-02 mankem and 2.18E-04 millires for the second quarter.

E. Int 6 grated total body dose to the general population and Avetage dose to individuals within the population from gaseous effluent releaees within a distance of 50 miles from the site boundary weret 1.43E-02 manRem and 9.29E-05 millirem f or the first quartert and 1.84E-03 manRem and 1.19E-05 millirem for the secord quarter.

F. There was no entrained noble gas present in either the first 0-second quarter liquid releases.

6. Process Control Program (PCP)

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

7. Of f site Dose Calculatjon Manual (ODCM1 Changes to the Big Rock Point ODCH, Revi.slon 2, are being submitr ad. per the requirements of Technical Specifications 6.9.2.2. A(5) and * ' '..A completa revision 3 with PRC/ evaluation sheets is provided. 'ha a tific changes are itemired as follows:

A. Table of Contents, pages 1 and 2, ODCH, Revision 3 added to DDCH to indics(9 changes in text.

3. Text of ODCH, pages 14-64, ODCH, Revision $1 the following numbered steps / items are clarifiedt IC0888-0172A-HP01 3

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i 1) I.B.1.3

2) 1.C.
3) I.C.1
4) I.C.2
5) 1.C.4
6) I.D.
7) I.E.
8) II.A.3.

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9) 11.B.1.
10) II.B.2.
11) II.C.1.
12) II.C.2.
13) II.C.2.3.
14) II.E.

C. Test of ODCH, pages 14-64, ODCM, Revision 31 the following data tables were revised:

1) Table 1.3, pages 28 meteorological data based on a three year composite of BRP on-site conditions from 1984 - 1986.
2) Tables 1.4 and 1.4A, pages 36 1987 Land Use census Report with reverified critical receptor and distance locations of the nearest residence, garden, dairy / beef cattle and goats to' BRP.
3) Table 1.9, pages 51 1988 BRP Caseous Design Objective Annual Quantities.
8. Su pplement a t Inf ormation to the BRP July-December 1987 Semi- Annual Radioactive Effluent Release Report The Big Rock Point Semi-Annual Radioactive Ef fluent Release Report July Deceober 1987, tSe following revisions are being submitted:

A. Table HP 10.3-21 Caseous Ef fluents - Sur24 tion of Releases, item C.3, 4th Quarter only Ctsnge the Particulate Percent of Annual Average MPC from 1.67E-06 to 2.31E-06.

B. Table HP 10.3-21 Caseous Ef fluent Isotopic Particulates, item 3, 4th Quarter onlyt Change Sr-89 from 1.0E-04 Ci to e.1E-05 Cil change Sr-90 from 1 .E-06 Ci to 1.3 E-05 Ci and change the net unidentified beta from 4.60E-06 Cl to 2.37E-05 Ci.

C. Table HP 10.3-38 Liquid Effluents - Summation of Relee.:t , item A.1 and A.3, 4th Quarter onlyt IC0888-0172A-HP01 3

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P Change the Fission and Activation Products Total Release from 6.53E-03 Cl to 6.48E-03 Ci and change the Total Release Percent of MPC from 3.74E-03 to 4.77E-03.

D. Table HP 10.3-3 8 Liquid Ef fluent Isotopes, item 1, 4th Quarter only Change Sr-89 from 1.6E-04 Ci to 2.3E-05 Cil change Sr-90 from 1.9E-04 to 3.5E-05 Ci and change the net unidentified beta from none to 2.42E-04 Cl.

E. In the BRP July - December 1987 Semi-Annual Radioactive Effluent L Release Report narrative the following changes are also notedt Item 2 - Caseous Effluents: change f rom "the unidentified beta was 3.10E-06% of the total release" to "the unidentified beta was 3.45E-06% of the total release".

Item 3 - Liquid Effluentet change from "the unidentified beta was 15.6% of the total release" to "the unidentified beta was 15.7% of the total release".

Reasons for the above data revisions to the Big Rock Point Semi-Annual Radioactive Effluent Release Report, July - December 1987 was that the calculated Sr-89 and Sr-90 release quantities (gaseous and liquid effluents, 4th Quarter only) were based on estimated values for the months of October - December. Teledyne Isotopes Midwest Laboratory had out yet completed the actual sample analyses prior to the Technical Specification Semi-Annua! Report due cate. All data changes are indi-cated by "# in the right-hand margins. There were no significant dose changes to the public.

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TABLE HP 10.3-1 ,,

BIC ROCK POINT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1

BATCH RELEA3ES I

JANUARY 1988 to JUNE 1988 A. Caseous - Continuous Release l

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B. LIQUID let Quarter 2nd Quarter Wumber of Releases 8 30 [

Total Release Time Minutes 1.33E+03 6.39E+03 i Maulmum Release Time Minutes 3.110+02 1<22E+03 Averase Release Time Minutes 1.67E+02 2.13E+02 Minimum Release Time Minutes 7.50Z+01 1.10E+01 i

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TABLE HP 10.3-2 I

BIC ROCK POINT SEMI ARNUAL RADIOACTIVE l

EFFLUENT RELEASE REPORT CASEOUS EFFLUENTS - SUMMATION OF RELEASES JANUARY 1988 to JUNE 1988 l Est Total i A. FISSION AND ACTIVATION CASES UNITS let QUARTER 2nd QUARTER Error %

1. Total release Ci 2.17E+03 2.07E+02
2. Averste release rate for period uCi/see 2.76E+02 2.63E+01 5.34
3. Percent of annual ava MPC  % 7.65E-02 7.30E-03 '

! 8. 10 DINES ~~ '

1. Total Iodine Ci 1.67E-02 1.17E-03 l 2. Ave rate rel ea s e r a t e f o r pe r gjl3' uci/see 2.13E-03 1.48E-04 4.47*
3. Percent of annual ava MPC _;* 1 4.17E-05 4.98E-06 C. PARTICULATES
1. Particulates with half-life >

8 days Ci 7.79E-04 9.69E-04

2. Averate release rate f or period uCi/sec 9.91E-05 1.23E-04
3. Percent of annual ava MPC  % 1.31E-06 3.37E-06 11.0 4 Cross alpha radioactivity Ci 3.32E-07 1.65E-06
5. Cross alpha release rate for period uci/sec 4.22E-08 6 2.10E-07 i D. TRITIUM
1. Total release Ci 1.3E+00 1.2E+00
2. Averate release rate for period uCi/see 1.6E-01 1.5E-01
3. Percent of annual ava MPC 1 7.4E-06 6.9E-06 I l

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i 1. Beta air dose at site boundary due i l to Noble Cases (TS 13.1.4.2a) mRads 9.97E-03 9.59E-04 l

2. Percent limit 1 9.97E-02 9.59E-03  !
3. Camma air dose at sitt boundary due  !

to Noble Cases (TS 13.1.4.2a) . mRads 1.73E-02 1.65E-03

4. Percent limit 3.46E-01 l I  % 3.30E-02  ;

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1. Maximum organ dose to public based  !

based on critical receptors i (TS 13.1.4.3a) _

mrem 2.96E-03 2.83E-03

2. Percent of limit t 3.95E-02 3.77E-02
  • Note Data is reported for I-131 and I-133 only i

IC0868-0172A-HP01 6

l TABLE HP 10.3-2 BIC ROCK POINT SEMI AWWUAL RADIOACTIVE EFFLUENT RELEASE REPORT >

CASEOUS EFFLUEKTS JANUARY 1988 to JUNE 1988

1. FISSION CASES Units 1st QUARTER l 2nd QUARTER t

K rypt on-8 5m Ci 3.56E+01 3.90E+00 l

Krypt on-8 7 Cl 1.76E*02 1.40E+01 Krypton-88 Cl 1.10E+02 1.20E+01

, Xenon-133 Cl 1.35E+01 1.50E+00 Xenon-133m Cl None None Xenon-135 Cl 1.75E+02 1.90E+01 r

Xenon-135m Ci 2.44E+02 2.20E+01 L r

Xenon-138 Ci 9.80E+02 9.00E+01 Witroten-13 Cl *.37E+02 4.07E+01 Total for Period Ci 2.17E+03 2.07E+02

2. IODINES Iodine-131 Ci 8.94E-04 1.86E-04 Iodine-132 Ci None None 4 Iodine 133 Ci 7.48E-03 9.80E-04  ;

Iodine-134 Ci None None j

Iodine-135 Ci 8.36E-03 None Total for Period Ci 1.67E-02 1.17E-03 l

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TABLE HP 10.3-2 BIC ROCK POINT SEMIANWUAL RADIOACTIVE EFFLUEN T RELEASE REPORT CASEOUS EFFLUENTS JANUARY 1988 to JUNE 1988 1

3. PARTI CULATES* i Units let QUARTER I 2nd QUARTER Chromium-51 Cl 1.99E-04 , 8.00E-06 Mannanese-54 Ci 2.67E-05 5.57E-05 Cobalt-58 Ci None None Barium-140 Ci 2.45E-04 2.70E-05

__ Cobalt-60 Ci 5.82E-05 6.28E-05 Zine-65 Cl 1.49E-05 5.50E-06 i

Nio bi um-95 ,

Ci 8.76E-07 None Cesium-134 Ci 2.73E-05 1.82E-05 Ce s ium-13 7 Ci 8.67E-05 8.03E-05 Iron-59 Ci 7.36E-06 None Silver-110m Cl 1.14E-05 6.10E-04 i

J Lan t han um-140 ** Cl 6.92E-04 8.10E-05 i S t ron t i um-91** Ci 2.70E-03 6.10E-04 Bromine-82** Ci 2.05E-03 2.50E-04 >

S od i u m-24 ** C1 1.54E-04 None Holybdenum-99** Ci 3.74E-05 None Ne p t u ni um-2 39 ** Cl 1.19E-05 None  !

S t r on t i um-89*** Cl 1.0E-04 1.0E-04 l I i S t r on t i um-9 0* ** Cl 1.2E-06 1.2E-06 3 Net unidentified 1 beta Ci None None  !

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Total Ci 7.79E-04 9.69E-04 o Particulates with half-lives >8 days. l

    • Particulates with half-lives <8 dayst not reflected in overall isotopic totals.
      • Calculated from vendor analysis of monthly stack gas filterst 2nd quarter results based on estimate due to unavailability of sample analyses. Reported vendor analyzed ,

Sr 89/90 results were input to CASPAR code as Sr90 to yield conservative dose estimates.  !

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TABLE HP 10.3-3 BIC ROCK _ POINT SEMI ARNUAL P ADI0 ACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS - SUMMATION OF RELEASES JANUARY 1988 to JUNE 1988 Est Total A. FISSION AND ACTIVATION PRODUCTS UNITS ist QUARTER 2nd QUARTER Error %

1. Total release (not including t r i t i um . asses. alpha) Ci 4.13E-02 1.29E-01
2. Average diluted concentration
durina period uCi/ml 1.66E-09 1.82E-08 5.07
3. Percent of MPC 1 1.18E-01 1.76
8. TRI TI UM
1. Total release ci 8.03E-02 1.99E-01
2. Average diluted concen". ration durina period uCi/mi 3.24E-09 2.80E-08 5.59
3. Percent of MPC 1 1.08E-04 9.34E-04 C. DISSOLVED AND EKTRAINED CASES
1. Total Release Ci None None
2. Average diluted concentration durina period uCl/ml None None None
3. Percent of MPC  % None None f

i D. CROSS ALPHA RADIOACTIVITY 4

(Total Release) Ci 8.29E-07 4.00E-06

1. Average diluted concentratir.n ,

durina period uCi/ml 3.34E-14 5.63E-13 i

E. VOLUME OF WASTE RELEASED (Prior to Dilution) Liters 1.15E+05 4.21F+05 a

F. VOLUME OF DILUTION WATER USED DURING PERIOD Li t e rs 2.48E+10 7.10E+09 l C. M AXIMUM DOSE COMMITMENT - WHOLEBODY mrem 4.40E-02 4.74E-02 '

Percent of TS 13.1.4.la limit 1 2.93 3.16 1 H. M AXIMUM DOSE COMMITMENT - ORC AN l mrem 7.14E-02 l 1.00E-01

, Percent of TS 13.1.4.la limit I  % 1.43 I 2.00 IC0888-0172A-HP01 9 i

TABLE HP 10.3-3 BIC ROCK POINT SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENTS JANUARY 1988 to JUNE 1988

1. NUCLIDES RELEASED Units 1s t QUARTER 2nd QUARTER Ce s ium-13 7 Cl 1.77E-02 9.50E-03 Cobalt-58 Cl 4.27E-05 8.80E-04 Manaanese-54 Cl 5.27E-03 3.15E-02 Cobalt 60 Ci 7.33E-03 3.86E-02 Ceslum-134 , , ,

Cl 8.51E-04 2.22E-03 Iron-59 Ci 6.87E-04 4.88E-03 i

Strontium-92 Ci None 7.32E Zine-65 Cl 1.37E-04 2.00E-03 I Antimony-124 Ci None 4.97E-0) t Molybdenum-99 Ci 8.15E-06 None i

' Chromium-51 Ci None 7.29E-04 l l

S il ve r-110m Ci None 8.00E-04 j Iodine-135 Ci 2.75E-04 None Iodine-133 Cl 5.31E-04 None ,

Iodine-131 Ci 2.16E-04 None 1

S t ron t i um-89** C1 2.7E-04 1.1E-03 '

I Strontium-90&* C '. 2.7E-04 1.6E-03 I Net Unidentified {

Beta ci 7.68E-03 3.49E-02 Fission & Activation Product Total (Above) Ci 4.13E-02 1.29E-01 l

Xenon-133 Ci None None Tritium Ci 8.03E-02 1.99E-01 Crand Total Ci 1.22E-01 3.28E-01 Calculated from vendor analysis of monthly radweste composite samples t 2nd Quarter results based on estimate due to unavailability of sample analyses. Re ported net beta and vendor analyzed Sr 89/90 results were input to LADTAP code as Sr-90 to yield conservative dose estimates.

IC0888-0172A-HP01 10 t _ -

TABLE HP 10.3-4 BIC ROCK POINT SEMI AWNUAL RADICACTIVE 1 EFFLUENT RELEASE REPORT SOLID RADIOACTIVE WASTE JANUARY 1988 to JUNE 1988 Weste Source of Solidification Container Volume Total

  • Principal Class Weste Atent Type (cu ft) Curies Radionuelides C Irradiated N/A Steel 29.2 651.0 Co-60 Fe-55, Metal Liner Mn-54, Ni-63, 2n-65 f
  • WOTE Camma isotopes are measured quantitiest all other isot% pas are estimated.

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