ML19284A454
| ML19284A454 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/01/1979 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML19284A452 | List: |
| References | |
| NUDOCS 7903060445 | |
| Download: ML19284A454 (13) | |
Text
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BIG RCCK POIIIT ITUCLEAR POWER PLAIIT RADICACTIVE EFFLUE:IT RELEASE A:iD E:IVIR0;a:E.TAL MOIIITORI:iG REFORT JULY - DECEIEEE 1978 1
7903060495
This report provides information relating to radicactive effluent releases and solid radioactive vaste disposal operations of the Big Rock Point Plant during the period of July through December 1978 in the format contained in plant Technical Specification 6.9.3 1.
Supplemental Information a.
Batch Releases Information relating to baten releases of liquid and gaseous effluents is provided in Table 1.
b.
Abnormal Releases
- To abnormal releases of radioactive effluents to the ervironment occurred during the period.
However, approximately 25 gallons of contaminated demineralized water was removed frca the site in several containers. Of the 25 gallons of veter retrieved, the highest activity was on the order of 100 MFC in one five-gallon container.
Evaluation of each unretrievable use deter-mined that no human consumption occurred and no undue hazard existed for any employee or member of the public. Refer to Event Rcport LER-R0-78-032 - C0HTAMINATED DEMINERALIZED WATER submitted September 15, 1978.
2.
Gaseous Effluents Table 2a precents a summary of all gaseous radioactive effluents released during the period. Release totals for each radionuclide determined to be present in gaseous effluents are contained in Table 2b.
Gaseous releases of I-133 and I-135 were determined from the ratios of the monthly short-lived halogen analyses to the week.'y I-131 analyses. The maximum noble gas release rate was 1.59 E+03 uCi/second.
3.
Liquid Effluents Table 3a presents a summary of all liquid radioactive effluents released during the period. Release totals for each radionuclide determined to be present in liquid effluents are contained in Table 3b.
The maximum concen-tration was 7.20E-07 pCi/mt.
L.
Solid Waste Table h presents a summary of radioactive waste shipped offsite for burial during the period. Total volume of solid waste shipped offsite during the last six months of 1978 was approximately 173 cubic feet.
Shipment dates were 10-2-78, 10-11-78, 10-23-78, and 11-9-78.
TAI 4LE 1 BIG ROCK POIIIT ITUCLEAR PO'JER PLA!IT BATCH REuEASES (1978)
A.
CASEDUS WASTE GAS DTAY TANKS UNITS TIIIRD QU/.RTER FOURTII QUARTER Uumber of Releases contin.ous continuous Total Release Time Minutes Maximum Release Time Minutes Average Release Time Minutes Minfmum Release Time Minutes D.
LIQUID UNITS TIIIRD QUARTER FOURTil QUARTER Number of Releases 5
8 Total Release Time Minutes 966 1563 Maximum Release Time Minutes 2h5 258 Average Release Time Minutes 193 195 Minimun Release Time Minutes 155 135
TABLE 2a BIG EOCK POINT NUCLEAR POWER PLA T" EFFLUE7T AND WASTE DISMSAL SH4IANNUAL REFORT (1978)
GASEDUS EFFLUENTO - SUW.ATION OF ALL RELEASES THIRD FOURTH
[
UNITS QUARTER QUARTER t
A.
FISSION & ACTIVATION GASES 1.
Total release Ci h.96E+03 5.09E+03 2.
Average rehase rate for period
.uC1/sec 6.2hE+02 6.h0E+02 3
Percent of Technical Specification Limit 6.2hE-02 6.h0E-02 B.
IODI"ES 1.
Total iodine-131 Ci S.88E-Oh h.21E-Oh 9
Average ralesse rate for period pCi/ cec (I-1311 1.12E-Ch 5.30E-05 3.
Percent of Technical Specification Limit (I-131T 9.31E-03 h.h1E-03 C.
PARTICULATES 1.
Particulates with half-lives /8 Ci days 1.35E-03 8.92E-Oh 2.
Average relence rate for period pCi/sec 2.33E-Ch 1.12E-Ch 3
Percent of Technical specification Limit S.i'E-03 5.65E-03 h.
Gross alpha radicactivity Ci 5.52E-07 3.55E-07 D.
TRITIUM 1.
Total release Ci 1.93E+00 1.30E+00 2.
Average releace rate for period pCi/sec 2.b3E-01 2.26E-01 Percent of l'echnical Spacification Limit 1.01E-02 9.hhE-03
TABLE 2b BIG ROCK POIiT NUCLEAR POWER PLAIIT EFFLUE:iT AND WASTE DISPOSAL SE'4IA I:TUAL REPORT (1978)
GASEOUS EFFLUE'ITS - ELEVATED' RELEASE UUCLIDES RELEASED UNITS THIRD (JARTER FOURTH QUARTER I
1.
FISSION GASES Xenon-138 C1 1.h9E+03 1.25E+03 Krypton-87 Ci h.23E+02 3.00E+02 Krypton-88 Ci 3.k3E+02 2.81E+02 Krypton-85m Ci 2.12E+02 1.5hE+02 Xenon-135 Ci 6.67E+02 h.19E+02 Xenon-133 Ci 3.32E+01 7.62E+01 Xenon-lh3 Ci Krypton-9h Ci Krypton-93 C1 Xenon-lkl Ci Krypton-92 Ci Krypton-91 Ci 1.82E+00
<1 Xenon-lho Ci 2.09E+01 1.lLE+01 Krypton-90 Ci 1.62E+02 9.08E+01 Xenon-139 Ci 2.19E+02 1.2hE+02 Krypton-89 Ci 1.69E+02 1.01E+02 Xenon-137 Ci 2.76E+02 1.65E+02 Xenon-135m C1 3.62E+02 2.32E+02 Krypton-83m Ci 1.35E+02 9 53E+01 Xenon-133m Ci 8.62E+00 6.55E+00 Xenon-131m Ci
<1
<1
TABLE 2b (Continued)
BIG ROCK POI:IT NUCLEAR POWER PLAIIT EFFLUE:IT AND WASTE DISPOSAL SD!IAIITUAL REPORT (1978)
GASEOUS EFH.,UENTS - ELEVATED RELEASE i
NUCLIDES RELEASED UNITS THIRD QUARTER FOURTH QUARTER 1.
PISSION GASES (Continued)
Krypton-85 Ci
<1
<1 N-13 Ci 3.58E+02 1.78E+03 Total for period Ci h.96E+03 5.09E+03 2.
IODINES Iodine-131 Ci 3.8SE-Oh b.21E-Oh Iodine '?3 Ci 8.30E-03 3 92E-03 Iodine-135 C4 1.0hE-02 h.93E-03 Total for period Ci 1.96E-02 9.27E-03 3.
PARTICULATES Cesium-13h Ci h.61E-06 Cesium-137 Ci 5.93E-05 7.70E-05 E Earium + Lanthanum-lho C1 2.59E-03 1.12E-03
':anganese-5h Ci 3.08E-03 1.62E-05 Cobalt-60 Ci 7.h5E-05 1.25E-Oh Technetium-99m Ci 6.22E-02 Septunium-239 Ci 1.80E-Oh Eromine-82 Ci 3.c6E-03 1.h9E-03 Net Unidentified Beta Ci 6.73E-Oh h.53E-Oh
TABLE la BIG ROCK POII;T ITUCLEAR POWER PLA:T" EFFLUCIT A!TD WASTE DISIOSAL SaiIAM:UAL REPORT (1978)
LIQUID EFFLUENTS - SU?dATI0IT OF ALL RELEASES THIRD FCURTH UITITS QUARTER QUARTER A.
FISSI0Il AIID ACTIVATIO?T PPOIUCTS 1.
Total relesce (not including tritium, Ci rases. altho) 3.25E-02 1.17E-01 2.
Average diluted concentration during pC1/ ml rericd 1.27E-09 h.70E-09 7
Percent o: apolicable limit
'icdified I.'icuid k' acte Ornte, oniv l.65E-02 5.81E-02 i
B. TRITIUM 1.
Tot.al release C1 2.02E-01 3.h9E+00 2.
Average diluted concentration during Ci/ml 7.89E-09 1.h0E-07 veriod 3.
Percent of applicable limit t
I4dif12d Licuid ' Acte System only C.
DISSOLVED AIID E'ITRAITED GASES 1.
Total release C1 2.
Average diluted concentration durin ;
.uCi/ml g
3.
Percent of appl.:able limit 9
~~~~
Medi*'ied Luuid Yaste System only D.
CROSS ALPHA PADICACTDTrf 1.
Total release ci 1.16E-06 2.66E-06 E.
VOLUME OF WA.'2PE RELDSED (P310R 'IO DILUTION', Liters 0 53E+0h 1.56E+05 F.
VOLUME OF DILUTIO!! WATER USED IURI' G FERIOD Liters 2.56E+10 2.h9E+10
TABLE 3b EIG ROOK POI:C IIUCLEAR PC'4ER PLA C EFFLUE'T AND WASTE DISIOSAL SD4IAI;I!UAL REPORT (1978)
LIQUID EFFLUE:ITS '
NUCLIDES RELEASED UNITS THIRD G.UARTE FOURTH OUARTER Cesium-134 C1 2.88E-03 7.27E-03 Cesium-137 Ci 1.82E-00 6.67E-02 Iron-59 C1 2.92E-Oh Cobalt-5d Ci 1.19E-Oh Cobalt-60 Ci 3.55E-03 9.69E-03 Manganese-54 Ci 9 2hE-Oh 3.57E-03 Lanthanum-lLO C1 8.09E-05 Strontium-59 C1 2.ShE-05 1.2SE-Oh Strontium-90 Ci 1.c0E-Oh 1.lhE-Oh Net Unidentified Beta Ci 6.78E-03 2.86E-02 Total for Feriod (Above)
Ci 3.25E-02 1.17E-01
TABLE h BIG FOCK POI?!? !!UCLEAR POWER PLAIIT EFFLUENT AND WASTE DISPOSAL SaiIAIII;UAL REPORT (1978)
SOLID WASTE AND IRRADIATED FUNL SHIPEiTS A.
EDLID WASTE SHIPPED OFFSITE ICR BURIAL OR DISIOSAL (I!OT IRRADIATED FUEL) 1.
Type of Waste SECO:!D Units SIX '10:ITHS a." Spent resins, filter sludges, m3 5.0hE+00 evaporator bottoms, etc.
Ci 2.5hE+01 b.
Dry compres::ible vaste, centaminated m3 equipment, etc.
Ci 3
c.
Irradiated ccmponents, control reds, m
etc.
Ci d.
Other (deceribe) m3 C1 2.
Solid Waste Disposition Destination Number of Shirments Mode of Transportation License Number b
Truck Chem-:Iuclear Systems, Inc.
Earnwell, SC lL6-13536-01 B.
IRRADIATED RIEL SHIF:C;TS (DISFOSI.10N)
No:rber of Shipments Mode of Trantpertation Destination None
II.
ENVIRONMENTAL MONITORING A.
Samplinc Su. ary For each medium sampled, Table II-Al contains the number of sampling locations, total number of samples collected and the number of locations at which levels were found to be significantly above local concurrent background. A listing of the highest, lowest and annual average concen-tration for the sampling point with the highest average concentration is presented in Table II-A2.
B.
Environmental Dose Estimates Levels of radioactive materials in environmental media do not indicate the likelihood of public intake in excess of lf, of those that could res ult from continuous annual exposure to the concentration values listed in Appendix B, Table II, Part 20.
C.
Variation of Environmental Concentrations With Time Statistical analyses of the data for significance at P <0.05 show that there has been no detectable increase in radioactivity levels of environ-mental media thst can be attributed to plant effluents.
D.
Discussion and Interpretation of Results 1.
Air Samnles:
No significant increase above concurrent background was observed at the air particulate campling locations.
No Iodine-131 activity on the charcoal cartridges was observed above the minimum detectable level. This is consistent with expected re-sults based on actual plant effluents and site meteorology.
2.
Lake Water:
Monthly composite samples indicate no significant difference in gross beta or tritium concentrations between the in-take and discharge samples. The intake and discharge simples contained c.bnormally high radioactive materials levels between 7-26-76 and 8-22-78 caused by contamination of the plant demineralized water supply.
De-mineralized water is used to rinse the sampling hardware.
Refer to Event Report LER-RO-78-032 - CONTAMINATED DEMINERALI~ED WATER - sub-mitted September 15, 1978. At no time was the lake water truly con-tarinated. Table II-A3 ccmpares the contaminated sample gross beta and tritium results to that calculated from effluent data.
The Charlevoix sample does not indicate the presence of other than natural background radioactivity.
3.
Well Water-Well water sa:.:ples do not indicate the presence of other than natural background radioactivity.
h.
Milk Strontium-90 and Cesium-137 were the only radionuclides detectable in milk samples collected during the period.
Ocacentrations of these two isotopes are consistent with concurrent background.
5 Acuatic Biota:
Samples of periphyton, algae, crayfish, and fish are collected semiannually, when available.
Periphyton and crayfish samples collected near the discharge appear to contain higher con-centrations of certain radionuclides (Cs-137 and co-60) than samples collected at the remote locations.
Cs-137 and co-60 have consistently been present in liquid effluents frem the plant (Cs-137 is also attri-butable to fallout). Therefore the concentration of these two iso-topss in biota vould be expected to be higher in the immediate vicinity of the discharge.
This localised increase has also been observed and reported by the Great Lakes F,adioecclogy Group at Argonne National Laboratory.
It should be noted, however, that current levels are consistent with or lower than levels observed over the last six or seven years.
6.
Gamma Dose:
Both thermoluminescent dosimetera and film are used to monitor the levels of gamma radiation in the vicinity of the site.
There were no significant differences in levels observed at the various sampling locations.
TABLE II-Al BIG ROCK POIfiT IIUCLEAR POWER PLA"T RADIOLOGICAL EIIVIR0!PfEIITAL fl0!IITORIIIG SAMPLIIIG AND AllALYSIS SlRetABY JULY 1,1978 TO DECEMBER 31, 1978
- OF
- OF NUMBER OF LOCATIONS SAMPLIIIG SAMPLEa SIGIIIFICAIITLY ABOVE MEDIIU1 DESCRIPTIGII TYPE OF ANALYSIC FREQUEfICY LOCAT.OIIS COLLECTED CONCURREIIT BACKGROUtiD Air Continuous Cross beta, I-131 Weekly 7
182 IIone
@ approx 1 cfm Lake Composite Gross Beta,11-3 Monthly 3
18 None*
Water Well Grab Gross Beta ffonthly 1
6 Ilone Water Milk Grab I-131, Sr-89/90, Monthly h
2h Ilone Gamma Isotopic Gamma Continuous TLD Monthly 12 69 rione Dose Quarte rly 12 21 Mone vilm Monthly 12 07 TIone Aquatic Grab Gross Beta, Semi-annually 5
18
!Ione biota Sr 89/90, Gamma Isotopic IlOTE:
- Intake and discharge samples both high in k instances between 7-13-78 and 9-13-78 due to sample contamination.
However, diceharge at no time indicated significant increase above concurrent intake. See Table II-A3.
TABLE II-A2 BIG ROCK POII!T IUJCLEAR POWER PLA!!T IIIGli, LOW AllD AVERAGE COIlCENTRATIOII FOR Tile IIIGilEST AVERAGE SAMPLIllG LOCATIOIl JULY 1, 1978 TO DECEMBER 31, 1978 MEDIA TYPE OF AIJALYSIS UIllTS LOCATIO!!
IIIGli LOW AVERAGE Air Gross Beta pC1/m TR (50 mi SSW) 0.17 0.03 0.07 3
I-131 pC1/m All
<MDL 1
3 Lake Wate Gross Beta pCi/R Discharge 18 6 9
12 6 6
6 11 - 3 pCi/t Discharge 1300 300 615 Well Unter Gross Beta pCi/t Site 5
<MDL 2
2 3
pCi/t All
<MDL Milk 1-1 31 Cs-137 0 C1/ 2.
LK ( 3.5 mi E) 11 5
8 Sr-894 pCi/t All
<MPL Sr-9) pCi/R LK (3.5 mi E) 25 6
12 Gamma Dose TLD (monthly) rJ1/mo E (0.9 mi SF 7.3 5.2 6.2 7 7
7 7
7 TLD (quarterly) mR/qtr SL (h mi SSE) 15.8 7 13.1 M.5 Film (monthly) mR/mo Iline Mile Pt (3 mi E) 5 0
1 Biotas Periphyton Gross Beta pC1/g (wet)
Mt McCauha (3 mi V) 5 Algae Gross Beta pCi/g (wet)
Iline Mile Pt (3 mi E) 3 Fish Gross Beta pCi/g (wet)
All 1
C ray t'i ch Cross Beta pCi/g (wet)
- k. mi Il and \\ mi G 2
Il0TES :
1 Minimum Detectable Level (MDL) = 0.02 pCi/m3 2
MDL = 1.0 pCi/t.
3 MDL = 0.5 pCi/t.
4 MDL = 5.0 pCi/t.
5 One sample per location.
6 Ilot including samples rinsed with contaminated dcmineralized water.
See text and Table II-A3 7
Includen background and transportation dose.
TABLE II-A3 BIG ROCK PuIIIT IlUCLEAR POWER PLAIIT COMPARISOII OF !!EALURED AIID CALCULATED LAEE WATER C0!!CE'ITRATIGIIS DURIIIG T iE PERIOD WHEII C0!!TNtIIIATED DE'!IIIERALIZED WATER WAS USED TO RIIISE SAbtPLIIIG llARDWARE GROSO BETA COIICE?ITRATIGIl SAf!PLII1G PEHIOD
!.!E ASUR ED CALCULATED AVERAGE
- STAhT FIIIISH DIGCHARGE IIITAKE
!!FT DISCHARGE 7-13-78 8-9-78 3200 3600 1.5 8-10-78 9-13-78 790 790 1.6 TRITIUM COIICIIFTRATIDIl 7-13-78 8-9-78 2200 2200 6.9 8-10-78 9-13-78 3300 2600 700 10.h IIOTE :
- Calculated from quantities released during sampling periods divided by total dilution f' low during that interval.