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A. EFFLUENT AND WASTE DISPOSAL REPORT This section contains a summary of the liquid and gaseous release limits; I a listing of the maximum permissible c. concentrations of the isotopes re- l 1 eased; a summary of batch and abnormal release data; a summary of total I liquid and gaseous releases; listings of isotopes released classified by pathway, gaseous at liquid, and type, continuous or batch; and a summary of solid radioactive waste shipments. This section represents all re- j leases during the period January 1, 1987 through June 30, 1987. | A. EFFLUENT AND WASTE DISPOSAL REPORT This section contains a summary of the liquid and gaseous release limits; I a listing of the maximum permissible c. concentrations of the isotopes re- l 1 eased; a summary of batch and abnormal release data; a summary of total I liquid and gaseous releases; listings of isotopes released classified by pathway, gaseous at liquid, and type, continuous or batch; and a summary of solid radioactive waste shipments. This section represents all re- j leases during the period January 1, 1987 through June 30, 1987. | ||
As per Technical Specification 3.3.3.11.b the condenser air ejector flow rate measuring device (FR-3100) is reported as inoperable during the period January 1, 1987 through June 30, 1987. As reported in the March 21, 1986 letter to J. B. Martin of USNRC, Region V, this flow rate has been measured every shift using rotometers FI-3111 or FI-3184. The modification of FR-3100 was completed on August 7, 1987. | As per Technical Specification 3.3.3.11.b the condenser air ejector flow rate measuring device (FR-3100) is reported as inoperable during the period January 1, 1987 through June 30, 1987. As reported in the {{letter dated|date=March 21, 1986|text=March 21, 1986 letter}} to J. B. Martin of USNRC, Region V, this flow rate has been measured every shift using rotometers FI-3111 or FI-3184. The modification of FR-3100 was completed on August 7, 1987. | ||
8709030257 07 O PDR R | 8709030257 07 O PDR R | ||
ADOCK 050 344 pop k | ADOCK 050 344 pop k |
Latest revision as of 14:28, 19 March 2021
ML20237H406 | |
Person / Time | |
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Site: | Trojan File:Portland General Electric icon.png |
Issue date: | 06/30/1987 |
From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
To: | |
References | |
NUDOCS 8709030257 | |
Download: ML20237H406 (42) | |
Text
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A. EFFLUENT AND WASTE DISPOSAL REPORT This section contains a summary of the liquid and gaseous release limits; I a listing of the maximum permissible c. concentrations of the isotopes re- l 1 eased; a summary of batch and abnormal release data; a summary of total I liquid and gaseous releases; listings of isotopes released classified by pathway, gaseous at liquid, and type, continuous or batch; and a summary of solid radioactive waste shipments. This section represents all re- j leases during the period January 1, 1987 through June 30, 1987.
As per Technical Specification 3.3.3.11.b the condenser air ejector flow rate measuring device (FR-3100) is reported as inoperable during the period January 1, 1987 through June 30, 1987. As reported in the March 21, 1986 letter to J. B. Martin of USNRC, Region V, this flow rate has been measured every shift using rotometers FI-3111 or FI-3184. The modification of FR-3100 was completed on August 7, 1987.
8709030257 07 O PDR R
ADOCK 050 344 pop k
e
- 4 TABLE A-1 PART A 1 SUPPLEMENTAL 1" FORMATION January 1, 1987 through June 30, 1987 REGULATORY LIMITS First Second Fission and Activation cas Release Rate Limits Unit Quarter Quarter
- 1. Tech Spec 3.11.2.1(a). Instantaneous QTv < 1 Ci/see 1.53E-1 1.89E-1 2.0 K y QTV < 1 Ci/sec 4.00E-1 4.50E-1 0.33 (Ly + 1.1 Wy)
- 2. Tech Spec 3.11.2.2, Quarterly Average QTv'< 1 Ci/sec 5.14E-3 6.21E-3 50 W y QTv < 1 Ci/sec 3.85E-3 3.8BE-3 25 M y
- 3. Tech Spec 3.11.2.4(1), Quarterly Average Requiring Use of the Gaseous Radwaste Treatment System QTv < 1 Ci/see 2.57E-3 3.11E-3 100 N y QTv < 1 Ci/see 1.92E-3 1.94E-3 50 M y A -2
o 4
TABLE A-2 PART A-2 SUPPLEMENTAL INFORMATION January 1, 1987 through June 30, 1987 REGULATORY LIMITS Caseous Iodine 131. Tritium, and Particulate First Second With > 8 Day T1/2 Limits Unit- Quarter Quarter
- 1. Tech Spec 3.11.2.1(b) Instantaneous QTV < 1 Ci/sec 6,14E-4 6.60E-3
.67 Ri
- 2. Tech Spec 3.11.2.3,-Quarterly Average QTV < 1 C1/sec 4.12E-6 4.43E-5 100 Ri
- 3. Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Caseous Radwaste Treatment System QTv < 1 Ci/see 2.06E-6 2.21E-5 200 Ri i
A-3
1 TABLE A-3 PART A-3 SUPPLEMENTAL INFORMATION Januury 1,1987 through June 30, 1987 l
REGULATORY LIMITS Liquid Effluent Limits
- 1. Tech Spec 3.11,1.7 Instantaneous discharge concentrations Instantaneous", less than the maximum permissible concentrations listed in 10 CFR Part 20, Appendix B. Table II, Column 2, for radionuclides other than dissolved or entrained noble gases. For I dissolved or entrained noble gases, the concentration is limited to 2 x 10-4 pCi/mi total activity.
- 2. Tech Spec 3.11.1.2 Gross release limit of 2.5 Ci per Quarterly Average quarter excluding tritium and dissolved noble gases. If this limit is exceeded, cumulative dose due to liquid effluents will be limited to j 1.5 mrem to the whole body and to 2.5 mrem to any organ, using isotope specific methodology in the plant offsite dose calculation manual (ODCM).
- 3. Tech Spec 3.11.1.3 The liquid radwaste treatment system Quarterly Average Requiring shall be maintained and used when Use of'the Liquid Radwaste activity discharged (excluding tritium Treatment System and dissolved noble gas) would exceed 1.25 C1/Qtr.
l 4 Tech Spec 3.11.1.4 The quantity of radioactive material Temporary Storage Tank contained in temporary radwaste storage Activity Limit tanks is limited to s 10 C1 excluding tritium and dissolved nobic gases.
A-4
TABLE A-4 PART A-4 SUPPLEMENTAL INFORMATION January 1, 1987 through June 30, 1987 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid MPC MPC Isotope (uCi/ce) Isotope (uci/ce)
Fluorino 18 8 x 10-4 lodine 131 3 x 10-7 Chromium 51 2 x 10-3 Iodine 132 8 x 10-6 Manganese 54 1 x 10-4 Tellurium 132 2 x 10-5 Iron 55 8 x 10-4 Iodine 133 1 x 10-6 Cobalt 57 4 x 10-4 Cesium 134 9 x 10-6 Cobalt 58 9 x 10-5 Cesium 137 2 x 10-5 Iron 59 5 x 10-5 Cesium 138 3 x 10-6 Cobalt 60 3 x 10-5 Barium 140 2 x 10-5 Rubidium 88 3 x 10-6 Lanthanum 140 2 x 10-5 Strontium 89 3 x 10-6 Cerium 141 9 x 10-5 Strontium 90 3 x 10-7 Cerium 144 1 x 10-5 Zirconium 95 ( n 10-5 Tungsten 187 6 x 10-5 Niobium 95 1 x 10-4 Alpha 3 x 10-8 Molybdenum 99 4 x 10-5 _ Unidentified 3 x 10-8 Technetium 99m 3 x 10-3 Tritium 3 x 10-3 Ruthenium 103 8 x 10-5 Krypton 85m 2 x 10-4 Ruthenium 106 1 x 10-5 Krypton 87 2 x 10-4 Silver 110m 3 x 10-5 Krypton 88 2 x 10-4 Tin 113 8 x 10-5 Kenon 131m 2 x 10-4 Antimony 124 2 x 10-5 Kenon 133 2 x 10-4 Antimony 125 1 x 10-4 Zenon 133m 2 x 10-4 Antimony 127 3 x 10-6 Kenon 135 2 x 10-4 Ienon 135m 2 x 10-4 Caseous Caseous MPCs are not used in calculating technical specifications at Trojan.
I i
A-5
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t 4 TABLE A-5 PART A-5 1 SUPPLEMENTAL INFORMATION January 1, 1987 through June 30, 1987 AVERAGE FNERGY' Effluent release limits are not based upon E, hence, reporting E is not required.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ,
Gaseous Releases f Fission and Activation Gases: Gamma spectrometric analysis of l gaseous grab samples define radionuclides distribution at least l monthly on monitored gaseous release points. Using the known nuclide '
distributions and process radiation monitor readings, the actual l quantities of gaseous releases are calculated. I Iodines: Weekly composite filter and iodine cartridge samples are analyzed by gamma spectroscopy to determine the concentration of particulate and iodine isotopes. Weekly composite samples are analyzed for beta and alpha emitting isotopes by counting with a gas flow proportional counter. Quarterly composite filters are analyzed for Sr-89/90 rsing gas proportional beta counting and chemical separation techniques when necessary.
Tritium: Tritium is collected on dry silica gel in monthly composite samples and counted using liquid scintillation spectroscopy.
Liquid Releases !
Fission and Activation Products: Gamma spectrometric analysis of ,
each batch is performed. Weekly composite samples are maintained for !
continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations.
Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques.
Dissolved and Entrained Gases: Gaseous isotopes are determined by gamma spectrometric analysis of each batch and on a minimum frequency of once per month for continuous releases.
A-6
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TABLE A-6 PART A-6 SUPPLEMENTAL INFORMATION January 1, 1987 through June 30, 1987 ;
BATCH RELEASES Unit Liquid- Caseous Number of Batch Releases 55 70 Total time period for Batch Releases Hours 323.7 3005.5 Maximum time period for Batch Releases Hours l'4 . 6 42.9 Average time period for Batch Releases Hours 5.9 633.0 Minimum time period for Batch Releases Hours 0.1 0.1 Average dilution flow during Batch Releases GPM 30110 NA ABNORMAL RLEASES
'l '
Number of Abnormal Releases 1 3 Total Activity Released Ci 9.18E-8 7.2SEO j l
l L
L rs A-7 L - - - - - - - - - - - - - - - - - - - _ - - - - - _ _ _ _
r t'
TABLE A-7 Sheet 1 of 2 PART B ,
GASEOUS EFFLUENTS SUMHATION OF ALL RELEASES l January 1, 1987 through June 30, 1987 i
First Second' Estimated I FISSION AND ACTIVATION CASES Unit __ Ouarter Quarter Error %
Total Activity Released Ci 8.54E+1 6.13E+1 13.5El {
l Average Release Rate for Quarter WC1/see 1.10E+1 7.80E0 !
Percent of Limit: '
Tech. Spec. 3.11.2.1 (a) - 1.73E-2 3.89E-2 Instantaneous ;
Tech Spec. 3.11.2.2 - 2.79E-1 1.99E-1 Quarterly Average Tech. Spec. 3.11.2.4.(1) - 5.57E-1 3.97E-1 Quarterly Average Requiring Processing IODINE 131 Total Iodine 131 Released C1 1.59E-4 1.50E-3 13.5El i
Average Release Rate for Quarter pC1/sec 2.04E-5 1.91E-4 j PARTICULATE Total with Half-lives > 8 days C1 3.40E-4 ND 13.5El
. Average Release Rate for Quarter pCi/sec 4.37E-5 NA l Total Gross Alpha Released C1 4.26E-7 7.21E-7 TRITIUM Total Released Cl 1.16E0 7.63E0 13.0E1 Average Release Rate for Quarter pCi/sec 1.49E-1 9.70E-1 :
f A-9
.- 4 TABLE A-7i Sheet 2 of 2-4
)
i IODINE 131. PARTICULATE WITH First Second Estimated i
> 8 DAY T1/2 AND TRITIUM Unit Ouarter Quarter Error % )
Total Released C1 1.16E0 7.63E0 13.5El 1
Average Release Rate for Quarter pCi/see 1.49E-1 9.70E-1
' Percent of Limit:
Tech. Spec. 3.11.2.1 (b) 2.45E-2 7.48E-2 Instantaneous Tech. Spec. 3.11.2.3 3.65E0 2.20E0 Quarterly Average Tech. Spec. 3.11.2.4(2) 7.31E0 4.40E0 Quarterly Average Requiring Processing l
I l
A-10 L_______._. _. _
TABLE A-8 Sheet 1 of 2 PART B-2 CASEOUS EFFLUENTS CROUND LEVEL RELEASES January 1. 1987 through June 30, 1987 NUCLIDES RELEASED Continuous Mode ' Batch Mode Unit lot Quarter 2nd Quarter let Ouarter 2nd Quarter FISSION CASES Krypton 85m C1 1.96E-2 8.00E-5 5.16E-3 ND ,
)
Krypton 85 Ci ND ND 7.29E 1.62E0 I Krypton 87 Ci' '3.57E-2 1.38E-4 ND ND Krypt.on 88 Ci 4.90E-2 2.01E-4 ND ND Xenon 131m Ci ND ND 3.43E-1 4.99E-1 Xenon 133m C1 1.20E-1 6.71E-3 1.05E-1 2.56E-1 Xenon 133 Ci 6.31E+1 1.57E+1 1.97E+1 4.32E+1 Xenon 135m Ci 1.56E-1 3.90E-3 ND ND Xenon 135 Ci 4.75E-1 9.69E-4 1.49E-1 6.91E-2
' Xenon 137 Ci 4.72E-3 ND ND ND Xenon 138 Ci 7.67E-2 3.08E-4 6.88E-2 ND Argon 41 C1 2.29E-2 3.99E-5 1.98E-1 ND TOTAL FOR QUARTER Ci 6.41E+1 1.57E+1 2.13E+1 4.56E+1 A-10
{
( TABLE A-8 Sheet 2 of 2 l
Continuous Mode Batch Mode Unit let Ouarter 2nd Quarter 1st Ouarter 2nd Ouarter IODTFES !
Iodine 131 Ci 1.57E-4 6.50E-4 1.96E-6 8.47E-4 Iodine 132 C1 1.40E-8 ND ND 9.12E-5 Iodine 133 Ci 2.37E-4 ND 1.11E-5 1.04E-4 TOTAL FOR QUARTER C1 3.94E-4 6.50E-4 1.31E-5 1.04E-3 PARTICULATE > 8 DAY T-1/2 Strontium 89 C1 2.5BE-4 ND 1.04E-6 ND Strontium 90 Ci 8.08E-5 ND 3.25E-7 ND Cesium 137 C1 1.57E-9 ND 1.14E-8 ND TOTAL FOR QUARTEK C1 3.39E-4 ND 1.38E-6 ND A-ll
TABLE A-9 PART B-3 CASEOUS EFFLUENTS ELEVATED RELEASES January 1, 1987 through June 30, 1987 l
No Elevated Release Points l A-12
TABLE A-101 PART C-1 LIOUID EFFLUENTS SUMKATION OF ALL RELEASES January 1, 1987 through June 30, 1987 FISSION AND ACTIVATION PRODUCTS First Second Estimated Unit _ Ouarter Quarter Error %
Total Activity Released (excluding Ci 3.34E-2 6.57E-2 13.5E+1 gases, tritium, and alpha)
Average Diluted Concentration pCi/ml 2.11E-9 -4.94E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous % 9.46E-2 3.42E-1 Tech Spec 3.11.1.2 - Quarterly Limit % 1.34E0 2.63E0 Tech Spec 3.11.1.3 - Quarterly Limit % 2.67E0 5.26E0 Requiring Procecsing TRITIUM Total Released Ci 2.60E+1 7.83E+1 13.0E+1 Average Diluted Concentration pCi/ml 1.65E-6 5.89E-6 Fraction of MPC % 5.49E-2 1.96E-1 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 6.68E-3 1.45E-3 13.5E+1 Average Diluted Concentration pCi/ml 4.23E-10 1.09E-10 Fraction of MPC % 2.11E-4 5.45E-5 CROSS ALPHA RADIOACTIVITY 7.stal Activity Released Ci 1.87E-4 ND i3.0E+1 UhDILUTED VOLUME OF WASTE RELEASED Liters 1.22E+7 1.14E+7 15.0E0 VOLUME OF DILUTION WATER Liters 1.58E+10 1.47E+10 il.5E+1 A-13 i
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.1 l l
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TABLE A-11 Sheet 1 of 2 PART C-2 LIOUID EFFLUENTS January 1, 1987 through June 30, 1987 l
NUCLIDES RELEASED-Continuous Mode Batch Mode Unit 1st Ouarter 2nd Quarter 1st Ouarter 2nd Ouarter Chromium 51 Ci ND ND 1.12E-4 2.74E-3 Manganese 54 Ci ND ND 2.25E-4 3.83E-4 Iron 55 Ci ND ND 7.62E-3 2.54E-2 Cobalt 57 Ci ND ND 1.93E-5 1.08E-5 Cobalt 58 Ci ND ND 1.54E-3 1.24E-2 Iron 59 Ci ND ND ND 4.72E-4 Cobalt 60 C1 ND ND 6.33E-3 8.48E-3 Strontium 89 Ci 5.87E-4 ND 1.23E-4 5.61E-6 Strontium 90 Ci 1.53E-3 ND 1.47E-4 1.93E-6 Zirconium 95 Ci ND ND 1.25E-4 5.28E-4 Niobium 95 Ci ND ND 5.58E-4 1.18E-3 Ruthenium 103 Ci ND ND 4.03E-5 3.35E-4 Ruthenium 106 Ci ND ND 5.59E-3 3.90E-3 Silver 110m Ci ND ND 7.84E-4 7.78E-4 Tin 113 Ci ND ND 3.19E-5 5.24E-6 ,
Antimony 124 Ci ND ND ND ND Antimony 125 Ci ND ND 4.45E-3 3.29E-3 Antimony 127 Ci ND ND 4.39E-5 ND' Iodine 131 Ci ND ND ND 3.08E-4 Iodine 132 Ci ND ND ND 1.12E-4 Tellurium 132 Ci ND ND ND 1.10E-4 l
l' A-14
TABLE A-11 Sheet 2 of 2 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 1st Quarter 2nd Quarter 1st Ouarter 2nd Quarter Iodine 133 Ci ND ND ND 6.27E-6 Cesium 134 Ci ND ND 8.78E-4 9.38E-4 Cesium 137 Ci ND ND 1.69E-3 2.07E-3 Barium 140 Ci ND ND ND 1.08E-6 Lanthanum 140 Ci ND ND ND 7.11E-4 Cerium 141 Ci ND ND ND 1.56E-4 Cerium 144 Ci ND ND 7.98E-4 1.41E-3 Unidentified Ci ND ND ND ND TOTAL FOR QUARTER Ci 2.12E-3 ND 3.11E-2 6.57E-2 Ienon 133 Ci ND ND 6.60E-3 1.45E-3 Kenon 133m Ci ND ND 6.40E-5 ND Ienon 135 Ci ND ND 1.61E-5 ND TOTAL FOR QUARTER Ci ND ND 6.68E-3 1.45E-3 9
i A-15
TABLE A-12 Page 1 of 2 Part D SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1987 through June 30, 1987 SOLID WASTE SHIPPED OFFSITE FOR Activity Volume Estimate BURIAL OR DISPOSAL (Not Irradiated During During Total Fuel) - Tvoe of Waste 6 Months 6 Months Error %
- 1. Spent Resin, Filter Sludges, 12.600Ci GO.43m3 25% ;
Evaporator Bottoms, etc.
- 2. Dry Compressible Waste, 9.556Ci 115.21m3 25%
Contaminated Equipment, etc.
- 3. Irradiated Components, Control O O Rods, etc.
- 4. Other O O ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide
- 1. See attached sheet.
- 2. See attached sheet.
3.
4 I
EQLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 15 Exclusive Truck U.S. Ecology, Inc.
P.O. Box 638 Richland, WA 99352 IRRADIATED FUEL SHIPMENTS DISPOSITION Number of Shipments Mode of Transportation Destination 1
O N/A N/A A-16
TABLE A-12 Page 2 of 2 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE
- 1. Nuclide Ci Nuclide Ci H-3 0.961 Ru-106 0.428 C-14 0.016 Ag-110m 0.035 Cr-51 0.035 Gb-125 0.105 Mn-54 0.112 Cs-134 0.534 Fe-55 1.478 Cs-137 1.139 Co-58 1.222 Ce-144 0.377 Co-60 1.975 Pu-241 0.095 Ni-63 0.861 Sr-89 0.013 Sr-90 0.081 Nb-95 0.049 Zr-95 0.040 TOTAL 9.556
- 2. Nuclide, Ci Nuclide Ci H-3 0.332 Ru-106 0.591 C-14 0.011 Ag-110m 0.038 Cr-51 0.042 Sn-113 0.015 Mn-54 0.073 Sb-125 0.030 Fe-55 5.827 Cs-134 0.086 Co-58 0.344 Cs-137 0.223 Co-60 2.094 Ce-144 0.718 Ni-63 1.073 Pu-241 0.734 Sr-89 0.022 Sr-90 0.138 Nb-95 0.117 Zr-95 0.080 Ru-103 0.012 TOTAL 12.600 A-17 l _ _ _ _ _ - _ _ _ _ _ _ .
l- ..
B. OFFSITE RADIATION DOSES l
offsite radiation doses from gaseous and liquid effluents for the first
( and second quarters of 1987 are presented in this section. Included are i
quarterly doses to individuals at locations of maximum actual exposure
'and quarterly doses to the 50-mile population. Doses are presented ,
separately for batch and continuous releases and for noble gas, gaseous iodine and particulate, and liquid effluents.
Exposure locations are based on the land-use survey presented in the Up- j dated FSAR and the 1986 annual survey of agricultural production.
Models and assumptions used in performing the dose analyses for 1987 are-presented in Sections 11.2 and 11.3 of the Trojan Updated FSAR.
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l~ ~ TABLE B-l' Sheet 1 of'2 PARAMETERS USED IN CALCULATING DOSES FROM CASEOUS EFFLUENTS (Second Half 1987)
'j Parameter Value Accumulation and Decay Times (days)
Harvest of leafy vegetables to consumption by man
~
1.0 Harvest of pasture grass to consumption by animals
~
0.0 Harvest of stored feed to consumption by animals 90.0 Harvest of produce to consumption by man 60.0 j Animal. butchering to consumption '
20.0 !
Food ingestion by animal to milking 2.0 Accumulation time on ground 7,300.0 ;
Human Consumption Rates (kg/yr)
Leafy vegetabiss by adult 64.0
-Produce by adult. 456'0 Meat by adult 110.0 Milk by adult 310.0 i Milk by infant- 330.0
' Breathing' Rates-(m3 jyr)
Adult. '8,000.0 Infant 1,400.0 Animal Consumption Rates'(kg/ day)
Animal feed by meat animal 50.0
' Anima 1' feed by milk cow 50.0' Animal feed by milk goat, 6.0
]
Exposure Periods During Growing Season (days)
. Leafy vegetables 60.0 Pasture vegetation' 30.0
' Produce 60.0 Residential Structure Shielding Factor 0.7 l
l' Fraction of Particulate Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulate Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of' Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m 2 ) 240.0 Field Decay Half Life (days) 14.0 l
i B-2 l
I
=___-_-_-__--___ .l
9
- l TABLE B-1 Sheet 2 of 2 Parameter _Value Agricultural Productivity (kg/m 2) l
-Leafy vegetables 2.0 Pasture grass 0.7 Produce 2.0 Period of Long-Term Buildup for Activity in Soil (days) 7,300.0 i
Fraction of Leafy. Vegetables Crown in Carden of Interest 1.0 Fraction of Produce Crown in Carden of Interest 0.76 j Fraction of Year Animal Crazes on Pasture 0.5 i
Fraction of Daily Feed that is Pasture Crass When Animal Crazes 1.0 j 1
l I
l B-3
- 1. .- - . . _ _ . _ _ _ _ _ _ _ _ _ _ _
TABLE B-2 Sheet 1 of 2 PARAME*ERS USED IN CALCULATING DOSES FROM LIQUID EFFLUENTS Value Parameter 1st Otr. 1987 2nd Otr. 1987 Plant Dilution Flow Rate (gpm) 32,200. 29,600.
Columbia River Flow Rate (cfs) 161,910. 288,580.
Dilution Factors Drinking water 2,255. 4,834.
Swimming water 496. 1,063.
Aquatic biota 496. 1,063.
Shoreline sediment 496. 1,063.
Irrigation water 2,255. 4,834.
Milk and meat animal water 2,255. 4,834.
Decay Times (days)
Discharge to drinking water 0.71 0.62 Discharge to swimming water 0.0 0.0 Discharge to aquatic biota consumption 1.0 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 Discharge to irrigation water withdrawal 0.71 0.62 Discharge to milk and meat animal water 0.71 0.62 withdrawal Leafy vegetable harvest to consumption by man 1.
Produce harvest to consumption by man 60.
Stored feed harvest to consumption by animals 90.
Pasture grass to consumption by animals 0.
Animal butchering to consumption 20.
Food and water ingestion by cow / goat to 2.
milking Accumulation Times (days)
Shoreline sediment 7.300.
Irrigated soil 7,300.
Irrigated vegetables 60.
Pasture grass 30.
Adult Consumption Rates (kg/yr)
Drinking water 730.
Fish 21. '
Invertebrates (crayfish) 5. j Irrigated leafy vegetables 64. !
Irrigated produce 456.
Cow's milk from irrigated pastureland )
310. '
Goat's milk from irrigated pastureland 310.
Meat from irrigated pastureland 110.
l l
B-4 l
,0' TABLE B-2 Sheet 2 of 2 l
Value- l Parameter let Otr. 1987 2nd Otr. 1987 i
Annual Exposure Times (hr/yr)
Swimming and boating 12.
Shoreline activities 12.
Irrigated pasture 2,190.
Infant. Consumption Rates (kg/yr)
Drinking water 330.
Cow's milk from irrigated pastureland 330.
4 Fraction of Year Animals Craze on Pasture 0.5 I I
Fraction of. Year Crops are Irrigated 0.5 l Field (Weathering) Half-Life (days) 14.
Irrigation Rate (liters /m 2 -br) 0.104 Fractional Concentration of Water in Soll (g/g) 0.2 Fraction of Leafy Vegetables Grown in Garden of 1.
Interest Fraction of Produce Grown in Garden of Interest 0.76 <
Irrigated Soll Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Leafy Vegetables Fraction of' Isotope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Grass Yield (kg/m2) 0.7 Vegetable Yield (kg/m2) 2.
Surface Density of Soil (kg/m2) 240.
.- Animal Consumption Rates (kg/ day)
Water by milk cow 60.
Water by milk goat 8.
Water by beef 50.
Pasture vegetation by allk cow 50.
Pasture vegetation by milk goat 6.
l Pasture vegetation by beef 50.
l B-5
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+ 1- .*_. -
l t
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\:
.I FIRST QUARTh7 1987 ii i s . BATCH RELTASES j
_ li.
. .e,,.
. , +
a
. , l, DOSES FROM NOBLE Cat 2S AT6 \ i sd
,.k h J SITE BOUNDARY'AND RESIDENCP.*0F-s' ; ', -d 'N i8 FIGHE;*?. CONCENTRATION t
i 1
1 '
i ;
w -+ '
t Site' . t'
, , . vy - / A y ' '" ' -
3 Boundarr % : R_esidence [b]
- . s q A. . b, , -
4 ,s ,
e >
,i e s
Peta Air Doce (mrad) *
---: 1.1E-2 ' ri.0E-3 s i, ,s' ,'
C.
i 3 >i i 1 '
' 3,
( ,, g Canna A >r, Dose' (mrad).:, , ,,t .
4.7E-3f 1.7E-3
- J a ii j, t ,
i ; t- .t iheta + Gamma' Si,cin Dose (mrem)
- 4,0E . ,, ,:
s g .s . s , -
1 GammasTotaljBcdy Doss (mrem) -
2.5E-3 b ' <
'i
- 1 t i 4-. \ -f
% g , ,
qv\;,, ,
[a] North sector af. 663 meters. ,
., [b) North sector at 10'JO meters. j. ; >-
3; ,
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3 0 TABLE ~B-6 FIRST QUARTER 1987 rj , ' CONTINUOUS RELEASES j g DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF j HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI I; Beta Air Dose (mrad) 3.1E-2 1.6E-2 Camma Air Dose-(mrad) 1.1E-2 4.2E-3 Beta + Camma Skin Dose (mrem) -
9.7E-3 Camma Total Body Dose (mrem) -
3.6E-3
[a] North sector at 663 meters.
[b] North sector at 1000 meters.
u i
4
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h-h i
B-9 l
L l ') U . )
._. - - _ _ = . . _ _ _
o TABLE B-7 FIRST QUARTER 1987 BATCH + CONTINUOUS RELEASES
[ DOSES FROM NOBLE CASES AT l SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a). Residence [b]
I
~ Beta Air Dose (mrad) 4.2E-2 2.2E-2 Camma Air Dose (mrad) 1.6E-2 5.9E-3 Beta-+ Gamma Skin Dose (mrem) -
1.4E-2 Gamma Total Body Dose (mrem) -
5.1E-3
[a] Maximum site boundary location.
[b] Maximum residence location.
B-10 i
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TI - - - -
00 0 NO EE E E E EE E E EE AR 29 5 1 4 B4 0 7 84 E
FY 5700 5 9000 0 460007 7 7 NH 460000 IT. 1200 1 4000 4 660001 1
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_ L O _- EEEE E EEEE E EEEEEE E UR_ 2939 1 1 831 9 546020 6 EEEEEE E DY_ 1717 3 9001 4 546027 3 764413 7 764418 A H __ 1265 1 4118 2 461112 T_ 5 461112 S
N O 6754 4 8657 5 796677 6 I 0000 0 0000 0 796677 6 T E - - - - 000000 0 000000 GA N EEEE E EEEE E EEEEEE E EEEEEE E NC O 1944 7 1233 2 349915 5 IO B 3753 8 349912 9018 2 860525 5 860525 0 S DL -
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T EE U_ 3963 8 1808 6 EEEEEE E A UT L 146665 5 146667 6706 8 9804 2 365352 8 365355 9 E B LI -
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NO EE E EE E EE E E EE E E AR 41 0 14 2 18 4 8 18 3 7 x Ff 6300 7 20000 2 650005 5 650009 9 NID -
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- A T D N NQ DI(
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M I
D G L
I O OI E NN O C IL S IO S E T _ RI S A _ ND ET D L _ - OE TP E U _
O .-_ AY PNG S N N P . W MIN KNN I O H _ UMI COO M S T SAT OCI A R A NNTA T TNNT E P OONO SEPOON P RICOB ELMIIO /
E ET C VBUTTC M R TPE D IASPP E
_ U AMTON LTNMMO R
_ S WUATA EOUUT M
. O _
SR- DGCSS (
. P _
GNBdG NE NNE
- X _
NOERN AVEOOR E
- E ICTUI CCCU S
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- T G L A A ,
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- A I T A s
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TABLE B-14 SECOND QUARTER 1987 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF
. HIGHEST CONCENTRATION l
Site Boundary [a] Residence [b]
i Beta Air Dose (mrad) 9.6E-3 5.2E-3 Gamma Air Dose (mrad) 3.0E-3 1.1E-3 Beta + Camma Skin Dose (mrem) -
2.9E-3 Gamma Total Body Dose (mrem) -
9.5E-4 la] North sector at 663 meters.
(b) North sector at 1000 meters.
O' f
i B-17 l
._____ -_____- _ _ D
.e
, h .-
TABLE B-15 SECOND QUARTER 1987 CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION.
Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 3.0E-3 1.6E-3
,Camma Air Dose (mrad) 1.0E-3 3.8E-4 Beta + Gamma Skin Dose (mrem) -
9.0E-4 Gamma Total Body Dose (mrem) -
3.2E-4
-[a] North sector at 663 meters.
, [b] North sector at 1000 meters.
l l
I B-18 l
1
ll.
TABLE B-16 SECOND QUARTER 1987 BATCH + CONTINUOUS RELEASES DOSES FROM WOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] Residence [b]
Beta Air Dose (mrad) '1.3E-2 6.8E-3 Gamma Air Dose (mrad) 4.0E-3. 1.SE-3
~
Bete + Gamma Skin Dose (mrem)~ -
3.8E-3 Gamma Total Body Dose (mrem) -
1.3E-3
[a] Maximum site boundary location.
(b) Maximum residence location.
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C. METEOROLOGICAL DATA Meteorological data for 1987 are available for review in the PGE Corporsie Office as per Technical Specification 6.9.1.5.4. Meteorological modelt-and assumptions used in performing the analyses are presented in PCE-1021. "Offsite Dose Calculation Manual".
\
e-
4 M M get Natland General ElectricCorpsiy David W. Cockfield Vice President, Nuclear August 28, 1987 Trojan Nuclear Plant Docket 50-344 Licenso NPF-1 U. S. Nucicar Regulatory Commission /
ATTN: Document Control Desk Washington DC 20555
Dear Sir:
TROJAN NUCLEAR PLANT Semiannual Radioactive Effluent and Waste Disposal Report In accordance with Trojan Nuclear Plant Technical Specifications, attached is the semlannual Radioactive Effluent and Wasto Disposal Report for the period through June 30, 1987. This information will also be included in the 1987 Annual Operating Report.
Sincerely, Attachment c: Mr. David Kish, Director State of Oregon Department of Energy Mr. John B. Martin Regional Administrator, Region V U. S. Nuclear Regulatory Commission Mr. R. C. Barr NRC Resident Inspector Trojan Nucicar Plant e sw sa! mon s:wt. Potard Oxgan 97204 ll
_ _ _ _ _ _ _ _ _ _ _ _ _ _