ML20141M552

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Semiannual Radioactive Effluent Release & Waste Disposal Rept for Jan Through June 1992
ML20141M552
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 06/30/1992
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20141M549 List:
References
NUDOCS 9209010143
Download: ML20141M552 (18)
v • d • e


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ATTAcilMENT l

Consumers Power Company flig Rock Point Plant Docket 50-155 4

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! SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE AND l WASTE DISPOSAL REPORT -

JANUARY TilR00Cil JUNE 1992 August 28, 1992 i

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9209010143 920828 PDR ADOCK 05000155 R- PDR I

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To LJKenaga, Big Rock Point t from MLG gd PaIikades CONSUMERS POWER Date August 10, 1992 COMPANY Subject BIG ROCK POINT - Internal SEMI-ANNUAL RADI0 ACTIVE EFFLUENT Correspondence RELEASE REPORT JANUARY - JUNE 1992 CC RMC File, Palisades (2) MLG92*014 RLBurdette, Big Rock DCC: 740/22*07*0l*02/LP Attached please find the subject report prepared and reviewed in accordance with Palisades Procedure HP 10.3. This report i believed accurate, pertinent and complete to the best of our ability in meeting the requirements of 10CFR50.36a and Technical Specification Section 6.9.2.2.

The Big Rock Point Radioactive Effluent Release Report was prepared by RLBurdette, Big Rock Health Physics Department, RTCurnow, MLGrogan and GASturm, Palisades RMC Radiological Services Department with technical review assigned to TPNeal, HP Support Superintendent. Administrative review and report approval was done by LJKenaga, C/HP Superintendent.

Report prepared by:

i MLGrogan, N hO RadpterialShippingSupv. Date Technical Review performed by:

JY [20 V TPNeal, HP Support Superintendent Date Administrative Review and Report approval by:

/ tth) / 2) t llv LJK6riagh,-Chem /HPSuperintendent Da'te

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Consumers Power Company Big Rock Point Plant Docket 50-155 i

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SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE l AND WASTE DISPOSAL REPORT

, JANUARY THROUGH JUNE 1992 i

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3 BIG ROCK POINT SEMI-ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT hauary 1.1992 to June 30. 1992 l This report provides information relating to radioactive effluent releases and solid radioactive waste processing at the Big Rock Point during the period of January 1 through June 30, 1992. The report format is detailed in Plant Technical Specification 6.9.2.2. Big Rock Point was offline from January 1, 1992 to May 16, 1992 for refueling and baffle outage. Offline again June 3, 1992 thru June 8,1992 due to Turbine control problems.

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

The sphere leak rate test was released as a catch on 2-14-92. The activity is included in first quarter totals (Co60-0.50 pCi and Csl37 0.62 pCi).

B. Abnormal Releases None C. Lower Limits of Detection (LLD's) for gaseous and liqui. effluents is provided in Attachment 1.

2. Gaseous Effluents Table HP 10.3-2 lists and summarizes all gaseous radioactive effluents released during the reporting period. The unidentified beta was 7.74E-07% of the total release.
3. Liould Effluents Table HP 10.3-3 liste 9nd summarizes all liquid radioactive effluents released during the reporting period. The unidentified beta was 7.03E-01% of the total releases.
4. Solid Waste There were no solid waste radwaste shipments from January 1 to June 30, 1992.

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5. Summary of Radioloaical Imoact on Man Potential doses to individuals and populations were calculated using 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 offsite air dose at the site boundary (0.57 mi E) due to noble gases were 0.00E400 millirad beta and 0.00E400 millirad gamma for the first quarter; and 3.25E-04 millirad beta and 4.60E-04 millirad gamma for the second quarter. The maximum noble gas offsite air dose to the nearest _ residence (1.4 mi E) occurred during the second quarter,_being 1.57-03 millirads beta and 2.66E-03 millirads gamma.

B. The most restrictive organ dose to an individual in an unrestricted area (based on identified critical receptors) from gaseous effluent releases (tritium, particulate and iodine) was the child bone for the first and infant thyroid for second quarter. Doses were 3.74E-05 and 4.77E-04 millirem, respectively.

C. Integrated total body does to the general population and average doses to individuals within the population from gaseous effluent release pathways to a distance of 50 miles from the site boundary were: 4.92E-05 PersonRem and 3.20E-07 millirem for the first quarter; and 1.85E-03 PersonRem and 1.20E-05 millirem for the second quarter.

D. The maximum total body dose to an individual in unrestricted water-related exposure pathways was 2.01E-01 and 1.18E-02 millirems for the first and second quarters, respectively.. The maximum organ doses were 3.55E-01 millirem (teenager bone) for the first quarter and 1.96E-02 millirem (teenager bone) for the second quarter.

E. Integrated total body-doses to the general population and average doses to individuals within the population from liquid effluent release pathways to a distance of 50 miles from the site boundary were: 1.44E-01 PersonRem and 9.35E-04 millirem, respectively, for the first quarter; and 1.19E-02 PersonRem and 7.73E-05 millirem, respectively, for the second quarter.

6. Process Control Proaram (PCP There were no changes to the PCP during this reporting period.

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i . Offsite Dose Calculation Manual (0DCM) i Changes to the Big Rock Point ODCM, Revision 8, are being submitted per the requirement of Technical specification 6.9.2.2. A(5) and 13.2.3 and

, 6.15. These changes result from the 1991 Big Rock Land use census.

The distance in the nearest critical receptor " Goat" changed, which also changed dispersion factors. These changes will not reduce the accuracy or reliability of dose calculations or setpoint i determinations. A complete revision 8 with PRC/ evaluation sheets is provided as Attachment 2. The specific changes are itemized as follows:

A. Updated Land Use Census (Table.l.4)

B. Updated GASBAR Inputs (Table 1.4A)

C. Updated DBQS (Table 1.9)

D. Subscript & Correction, pg 89, Appendix A 4

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)i BIG ROCK POINT _ SEMIANNUAL RADI0 ACTIVE 6 i

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EFFLUENT RELEASE REPORT TABLE HP 10.3-1 BATCH RELEASES January 1. 1992 to June 30. 1922 A. Gaseous - Continuous Release B. LIQUID Units 1st Quarter 2nd Quarter Number of Releases 21 7 Total Release Time Minutes 2.67E+03 875 Maximuta Release Time Minutes 222 205 Average Release Time Minutes 127 125 Minimum Release Time Minutes 4 7

BIG ROCK POINT SEMIANNUAL RAQJ0 ACTIVE 7 EFFLUENT RELEASE REPORT TABLE HP 10.3-2 GASEOUS EFFLUENTS - SUMMATION OF RELEASES January 1. 1992 to June 30, 1992 A. FISSION AND ACTIVATION GASES Units 1st Qtr 2nd Qtr Est Total Error %

1. Total release Ci <LLD 2.20E+02
2. Average release rate for period uCi/sec <LLD 2.80E+01 5.80E+00
3. Percent of annual avg MPC  % <LLD 7.58E-03 B. 10 DINES *
1. Total Iodine Ci 2.22E-07 1.llE-03
2. Average release rate for period uCi/sec 2.82E-08 1.41E-04 5.80E+00
3. Percent of annual avg MPC  % 2.56E-09 4.42E-06 ,

C. PARTICULATES

1. Particulates with half-life > Ci 9.44E-05 1.01E-04 8 days
2. Average release rate for period uCi/sec 1.20E-05 1.32E-05
3. Percent of annual avg MPC  % 2.56E-07 2.54E-07 1.81E+01
4. Gross alpha radioactivity Ci 6.29E-07 1.86E-06 D. TRITIUM
1. Total release Ci 4.23E-01 9.03E-01
2. Average release rate for period uCi/sec 5.38E-02 1.15E-01

. 3. Percent of annual avg MPC  % 2.45E-06 5.22E-06 E.

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Beta Air dost at Site mRads 0.00E+00 3.25E-04 Boundary due to Noble Gases (TS 13.1.4.2a)

2. Percent limit  % 0.00E+00 3.25E-03
3. Gamma Air dose at Site mRads 0. 0E+00 4.60E-04 Boundary due to Noble Gases (TS 13.1.4.2a)
4. Percent limit  % 0.00E+00 9.2CE-03 F.

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1. Maximum Organ Dose to Public mrem 3.74E-05 4.77E-04 Based on Critical Receptors (TS 13.1.4.3a)
2. Percent of limit  % 4.99E-04 6.36E-03 FRDTE: Data is reported for I-131 and I-133 only.

BIG ROCK POINT SEMIANNUAL RADI0 ACTIVE 8-EFFLUENT RELEASE REPORT TABLE HP 10.3-2 GASEOUS EFFLUENTS January 1. 1992 to June 30. 1992 l ,

1. FISSION GASES UNITS IST QUARTER 2ND QUARTER l Krypton-85m Ci <LLD 5.8E+00 Krypton-87 Ci <LLD 2.67E+01 Krypton-88 Ci <LLD 1.83E+01 4

Xenon-133 Ci <LLD 4.99E+00 Xenon-133m Ci <LLD <LLD Xenon-135 Ci <LLD 2.51E+01 Xenon-135m Ci <LLD 2.80E+01 Xenon-138 Ci <LLD 1.llE+02 Total for Period Ci <LLD 2.20E+02

2. 10 DINES Iodine-131 Ci 2.22E-07 1.42E-04 lodine-132 Ci <LLO <LLD Iodine-133 _

Ci <LLD 9.63E-04 ladine-134 Ci <LLD <lLD Iodine-135 Ci <LLD <LLD Total for Period Ci 2.22E-07 1.llE-03 4

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BIG R0(_K POINT SEMIANNUAL RADIOACTIVE 9 EFFLUENT RELEASE REPORT TABLE HP 10.3-2 GASE0US EFFLUENTS Januay 1. 1992 to June 30. 1992

3. PARTICULATES* UNITS lst QUARTER 2nd QUARTER Chromium-51 Ci <LLD 2.18E-06 Manganese-54 Ci 3.85E-05 1.43E-05 Cobalt-58 Ci 7.llE-07 <LLD Iron-59 Ci <LLD <LLD 1
      • Cobalt-60 Ci 4.82E-05 2.23E-05 Zink-65 Ci <LLD 2.21E-06 Silver-110m Ci <LLD 4.46E-06 Cesium-134 Ci <LLD <LLD
      • Cesium-137 Ci 5.83E-06 8.09E-06 Barium-140 Ci <LLD 3.90E-05 Cerium-141 Ci <LLD <LLD Cerium-144 Ci <LLD <LLD Stroncium-89 Ci 6.89E-07 9.74E-06 Stroncium-90 Ci 1.27E-07 4.26E-07
    • Bromine-82 Ci <LLD 1.51E-04

. ** Strontium-91 Ci <LLD 8.31E-05

** Molybdenum-99 Ci <LLD 4.93E-06
    • Lanthanum-140 Ci <LLD 8.30E-05 Net Ci 3.84E-07 1.33E-06 unidentified beta Total Ci Ci 9.44E-05 1.04E-04
  • Particulates with half-lives >8 days.
    • Particulates with half-lives <8 days; not reflected in overall isotopic totals.
      • Includes activity from the sphere le k rate test (ILRT)

ElG ROCK POINT SEMIANNUAL RADI0 ACTIVE 10 EFFLUENT RELEASE RE_EQEI TABLE HP 10.3-3 LIQUID EFTLUENTS - SUMMATION OF ALL RELEASES l l

January 1.1992 to dg; 30.1992 Est Total A. FISSION AND ACTIVATION PRODUCTS Units 1st Otr 2nd Otr Error % ___

l. Total release (Not including Ci tritium, cases. alpha) 1.16E-01 2.98E-02
2. Average diluted concentration duriro oeriod uCi/ml 2.43E-08 2.19E-09 4.9E+00
3. Percent of MPC  % 1.23E-01 7.96E-03 B. TRITIUM
1. Total Release Ci 8.89E-01 1.71E-01
2. Average diluted concentration dur(10 period uCi/ml 1.86E-07 1.26E-08 6.39E+00
3. Perce.nt of MPC  % 6.20E-03 4.19E-04 C. DIS 50LVED'AND ENTRAINED GASES
1. Total Release Ci <llD <LLD
2. Average diluted concentration durina period uCi/ml N/A N/A N/A
3. Percent of MPC  % N/A N/A D. GROSS ALPHA RADI0 ACTIVITY (Total Release) Ci 7.96E-06 5.94E-07 E. VOLUME OF WASTE RELEASED (Prior to Dilution) _ Liters 4.64E+05 9.33E+04 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 4.78E+09 1.36E+10 G. MAXIMUM DOSE COMMITHENT - WHOLEB0DY mrem 2.01E-01 1.18E-02 Percent of TS 13.1.4.la Wholebody limit  % 1.34E+01 7.87E-01 H. MAXIMUM DOSE COMMITMENT - ORGAN mrem 3.55E-01 1.96E-02 Percent of TS 13.1.4.la Oraan limit  % 7.10E+00 3.92E-01

DIG ROCK SEMIANNUAL RADIOACTIVE 11 )

EFFLUENT RELEASE REPORT  !

l TABLE.HP 10.3-3 LIQUID EFFLUENTS .

January 1. 1992 to June 30. 1992

1. NUCLIDES RELEASED
  • Units 1st Quarter 2nd Quarter Chromium-51 Ci 2.10E 04 <LLD Maganese-54 Ci 5.14E-02 1.48E-02 Cobalt-58 Ci 9.18E-04 1.0E-05 Iron 59 Ci 7.86[-03 f.3E-04 Cobalt-60 Ci 3.21E-02 1.13E-02 Zinc-65 Ci 4.81E-04 5.10E-05 Su ontium-89 Ci 1.02E-04 4.63E-06 S t ront i u.a- 90 Ci 2.49E-04 2.82E-05 Molybdenum-99 Ci <LLD <!.LD Silver-110m Ci 1.80E-04 1.24E-04 Iodine-131 Ci <LLD <LLD Cesium-134 Ci 2.41E-04 5.0E-05 Cesium-137 Ci 1.45E-02 1.70E-03 Lathanum-140 Ci <LLD <LLD Cerium-141 Ci <LLD <LLD Cerium-143 Ci <LLD <LLD Antimony-124 Ci 2.44E-04 <LLD Net Unidenti' ed Beta Ci 7.4SE-03 1.06E-03 i fission & Act . ion Product Totai ubove) Ci 1.16E-01 2.98E-02 Xenon-133 Ci <LLD <lLD Tritium Ci 8.89E-01 1.71E-01 Grand Total Ci 1.01E-00 2.01E-01 i

SIG ",00k POINT SEMIANNUAL RADI0 ACTIVE 12 EFFLUENT RELEASE REPORT TABLE HP 10.3-4 SOLID WASTE January 1. 1992 to June 30. 1992 Waste Source of Solidification Container Volume Total Principal Class Waste _ Acent Tvoe (cu ft) Curies Radionuclides NONE f

_,.._..i. ..u . a-4m # . h .+u_ _ 42, - _m . . . _n, 13 Attachment 1 Lower Limits of Detection (LLD's for Bia Rock Effluents Gaseous Effluents Nuclide LLO (uCi/cc)

Xe-133m 6E-05 Co-58 3E-14 Ce-141 3E-14 Ce-144 IE-13 Fe-59 9E-14 Cs-134 3E-14 Liauid Effluents Nuclide LLD (uci/cc)

Co-58 lE-07 Zn-65 3E-07 Mo-99 8E-08 Fe-59 2E-07 1-131 lE-07 Cs-134 2E-07 Xe-133 3E-07 Ce-141 2E-07 Ce-144 7E-07

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 l EFFLUENT T/S REQUIRED DOCUMENTS Page 34 of 94  !

A. OFFSITE DOSE CALCULATIONS TABLE 1.4 Attachment i 1991 BIC ROCK POINT LAND USE CENSUS REPORT

! Distance to the nearest residence, garden, milk cow, beef cow and goat in each sector.

Sector Residence Carden Dairy Cow Beef Cattle Coat WSW 2.5 mi >5 mi >5 mi >5 mi >5 mi SW l.1 mi >5 mi >5 mi >5 mi >5 mi SSW 1.3 mi 2.1 mi >$ mi >5 mi >5 mi S 1.9 mi >5 mi >5 mi 2.5 mi >5 mi l

SSE 1.7 mi 1.8 mi 3.5 mi 3.5 mi >5 mi SE 1.7 mi 1.7 mi 4.5 mi 2.0 mi 4.0 mi ESE 1.5 mi 1.8 mi 2.6 mi 2.6 mi >5 mi E 1.4 mi 2.5 mi 2.5 mi 2.5 mi >5 mi l

ENE 2.3 mi >5 m: >5 mi >$ mi >5 mi i

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OD0589-1333A-BA01-BA05

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 35 of 94 A. OFFSITE DOSE CALCULATIONS 4

TABLE 1.4a Attachment 4 1992 BIG ROCK POINT CASPAR INPUT PARAMETERS Critical Receptors X/Q X/Q Decay Distance X/Q Decay and Dep D/Q Location Sector (mil e s ) (sec/m3 ) (se./m') (sec/m2 ) (1/m*)

, Residence /Carden E 1.40 5. 20E-08 5.20E-08 5.10E-08 6.80E-10 4

Site Boundary E 0.57 4.70E-08 4.60E-08 4.60E-08 1.30E-09 l (1) Beef Cattle E 2.50 3.80E-08 3.70E-08 3.60E-08 3.50E-10

! Dairy Cow E 2.50 3.80E-08 3.70E-08 3.60E-08 3.50E-10 Coat SE 4.00 1.80E-08 1.80E-08 1.70E-08 9.90E-11 (1) NOTE: Although the beef cattle location is closer in the SE sector (2.00 miles) than in the E sector (2.50 miles), the X/Q for the E sector at 2.50 miles is greater at 3.80E-08 than in the SE sector at 2.00 miles which is 3.10E-08. Thus the E sector at 2.50 miles has the more limiting criteria and will be used for the critical receptor location.

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VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 49 of 94 A. OFFSITE DOSE CALCULATIONS J

TABLE 1.9 i'

Attachment 3 1992 BIC ROCK POINT CASE 0*JS DESIGN l OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ mrem /Ci (Ci)

Ar-41 Total Body 1.02E-05 4.90E+05 Kr-83m Skin 2.47E-08 6.07E+08 Kr-85 Skin 2.23E-06 6.73E+06 Kr-85m Total Body 1.35E-06 3.70E+06 Kr-87 Skin 2.39E-05 6.28E+05 Kr-88 Total Body t.70E-05 2.94E+05 Kr-89 Total Body 1.92E-05 2.60E+05 11 - 3 Total Body-C 6.39E-06 7.82E+05 C-14 Bone-C 5.59E-03 2.68E+03 Cr-51 CI Tract-A,T 1.79E-04 8.38E+04 Hn-54 CI Tract-T 1.85E-02 8.11E+02 Fe-55 Bone-C 1.57E-02 9.55E+02 Co-58 CI Tract-T 1.15E-02 1.30E+03 Fe-59 CI Tract-T 1.84E-02 8.15E+02 Co-60 CI Tract-T 6.57E-02 2.28E+02 Zn-65 Total Body-I 6.23E-02 8.03E+01 Sr-89 Bone-C 6.93E-01 2.16E+01 Sr-90 Bone-C 2.85E+01 5.26E-01 '

Zr-95 CI Tract-T 2.43E-02 6.17E+02 Sb-124 CI Tract-T 5.91E-02 2.54E+02 I-131 Thyroid-I 3.11E+00 4.82E+00 Xe 131m Skin 9.84E-07 1.52E+07 Xe-133 Total Body 3.39E-07 1.47E+07 Xe-133m Skin 2.06E-06 7.28E+06 ,

Xe-135 Total Body 2.09E-06 2.39E+06 Xe-135m Total Body 3.60E-06 1.39E+06 i Xe-137 Skin 2.20E-05 6.82E+05 Xe-138 Total Body 1.02E-05 4.90E+05 I-133 Thyroid-I 2.71E-02 5.54E+02 Cs-134 Liver-C. 5.2Bi-01 2.84E+01 Cs-136 Liver-I 1.22E-02 1.23E+03 Cs-137 Bone-C 5.16E-01 2.91E+01 Ba-140 Bona-C 3.50E-03 4.29E+03 Ce-141 CI-Tract-T 9.66E-03 1.55E+03 Cc-144 CI Tract-T- 2.57E-01 5.84E+01 Ma-56 CI Tract-I 6.69E-05 2.24E+05 Co-57 CI Tract-T 6.50E-03 2.31E+03 Ni-65 CI Tract-I 4.63-05 3.24E+05 Rb-88 Total Body-C 1.05E-08 4.76E+08 Nb-95 CI Tract-A 4.31E-02 0.4BE+02 Ho-99 Kidney-I 1.84E-03 8.15E+03 Tc-99m CI Tract-T 7.41E-06 2.02E+06 Ru-103 CI Tract-A 6.86E-02 2.19E+02 OD0589-1333A-BA01-BA05

VOLUME 25 BIC ROCK POINT RADIOLOGICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 50 of 94 A. OFFSITS DOSE CALCULATIONS TABLE 1.9 Attachment 3 1992 BIC ROCK POINT CASLOUS DESICN OBJECTIVE ANNUAL QUANTITIES (Continued)

Design Objective Dose Factor Annual Quantity Nuclide Orran mrem /Ci (Ci)

Sb-125 CI Tract-T 3.33E-02 4.50E+02 Te-127 CI Tract-T 1.05E-04 1.43E+05 I-132 Thyr.;id-C 1.72E-04 8.72E+04 I-134 Thyroid-C 1.98E-05 7.58E+05 I-135 Thyroid-C 9.81E-04 1.53E+04 1.a-140 CI Tract-T 6.94E-04 2.16E+04' N-13 Total Body-I 2.16E-55 2.31E+55 Na-24 Total Body-I 8.56E-05 5.84E+04 Br-82 Total Body-I 1.14E-03 4.39E+03 Sr-91 CI Tract-A 1.84E-05 8.15E+05 St-92 CI Tract-C 1.20E-07 1.25E+08 Tc-101 Total Body-C 3.36E-12 1.49E+12 Ag-110m CI Tract-T 1.69E-01 8.88E+01 Cs-138 Kidney-A 3.75E-20 4.00E+20 Ba-139 CI Tract-C 1.93E-11 7.77E+11 Np-239 CI Tract-A 3.85E-04 3.90E+04 OD0589-1333A-BA01-BA05

I VOLUME 25 BIC ROCK POINT RADIOLOCICAL Revision 8 EFFLUENT T/S REQUIRED DOCUMENTS Page 89 of 94 A. OFFSITE DOSE CALCULATIONS APPENDIX A DISCilARCE CANAL DREDCIWC COMMITMENTS AND REPORTING REQUIREMENTS V.B Inhalation of Re-Suspended Isotopes fro s Dried Sediment Blown by Wind Using methodology of Regulatory Guide 1.109, the annual organ dose from Inhalation of radionuclides in air ist DA (r,0) = Ra I xi (r,0) DFAija Ja g Where L'Alja = inhalation dose factor [ mrem /pC1)

Values o' 1FA given in ODCH Table 1.7.

Ra = annual intake for individual [m3 /yr)

Ra infant = 1400 m3 /yr Ra child = 3700 m /yr Ra teen, Ra adult = 8000 m3 /yr Xi=annualavegageconcentrationofradionuclidein air (pC1/m )

From Mark's Standard Handbook for Mechanical Engineers (pg. 18-12). Tgeamountofsuspendedmatterinnorma' city air = 1.37 mg/m and the amount of suspended matt- in manufacturing plant = 4.58 mg/m OD0589-1333A-BA01-BA05

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