ML20235F484
| ML20235F484 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/31/1983 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| PGE-1015-83, NUDOCS 8709290148 | |
| Download: ML20235F484 (189) | |
Text
{{#Wiki_filter:. I PGE-1015-83 O ANNUAL REPORT OF TROJAN NUCLEAR PLANT FOR 1983 Docket 50-344 - License NPF-1 O l i l l l-i PORTLAND GENERAL ELECTRIC COMPANY 121 S. W. Salmon Street Portland, OreEon 97204 O e n 4 gramas'efer R d'
TABLE OF CONTENTS .
'J Page
- 1. INTRODUCTION. .. . . . ...-. . . . . . . . . . . . . . . . 1-1 '
2.- REPORTS . . . . . . . . . . . . . . . . . . . . . . 2 A. Effluent and 'Jaste Disposal Report. . . . . . . . . . 2-2 B. Offsite Radiation Deses . . .. . . . . . . . . . . . 2-33 C. Meteorological Data . . . . . . . . . . . . .. . . . 2-78 D. Annual Personnel Exposure and Monitoring Report . . . 2-136 E. -Environmental. Surveillance Report . . . . . . . . . . 2-139 F. Steam Generator Tube Inspections and Maintenance. . . 2-143 G. Relief Valve Challenges . .. . . . . . . . . . . . . 2-144 H. Changes, Tests, and Experiments . . . . . . . . . . . 2-145
- 1. Plant Modifications and Design Changes. . . . . . 2-146
; 2. License Amendments. . . . . . . . . . . . . . . . 2-167
- 3. Licensing Document Change Requests (LDCRs)
Approved During 1983... . . . . . . . . . . . . . 2-174
- 4. Plant Tests . . . . . . . . . . . . . . . . . . . 2-179
- 5. Changes to Procedures . . . . . . . . . . . . . . 2-182
- 6. Setpoint Changes. . . . . . . . . . . . . . . . . 2-183 I i
- 1. INTRODUCTION -
l O The Annual Report of the Trojan Nuclear Plant for 1983 is submitted in accordance with the requirements of Federal Regulations and Facility OperaLing License NPF-1, and as a supplement to the Monthly Operating Reports. Other required reports are included for ease of reference and completeness. The Trojan Nuclear Plant began the year operating at full power. On January 13, power was reduced to 72 percent due to favorable hydro- , electric conditions. Power was returned to 100 percent on January 16, I then again reduced to 72 percent due to availability of excess hydro-electric power on January 21. The Plant was shut down for this reason on January 24. The annucl maintenance and refueling outage officially began on March 7. The Plant refueling outage lasted 131 days, during which time refueling, maintenance and surveillance testing were performed. Fuel unloading of the reactor vessel began on March 30. Inspection of all steam generator J-tubos revealed two tubes in each steam generator requiring re p mment due to erosion problems. Core reload commenced on May 5. On June 2, refueling was completed and the Plant entered Mode 5, cold shudom. The Containment integrated leak rate test (ILRT) was completed satfafactorily on July 2. The reactor was made critical July 14, with or % cor training and Lesting to be performed prior to power generation. The Plant entered Mode 1 on July 22 and operated at or near 40-percent power for the 9 remainder of the month with power escalation testing above 50 percent being deferred until August. The Plant was shut down August 1 in order to block the drain line from the 3B to 2BA feedwater heater. The 2BA heater had been bypassed because of a large number of tube leaks; therefore isolation of the drains was neccesary to return the B train to operation. On August 4, the Plant started up and returned to 50-percent power. This power was maintained until August 17 when repairs to the north condensate pump motor were com-pleted and power escalation began. One hundred percent power was achieved on August 19 and reload power escalation testing was completed August 20. The Plant maintained operation at or near 100 percent for the remainder of the year with the exception of six relatively short forced outages occurring from July through October. The capacity factors for the year are as follows: Month Capacity Factor January 63.8 l l February - March - April - 1-1 l
Month Capacity Factor May - June - July 11.4 1 1 \ August 55.9 l l September 93.7 i l October 95.9 November 97.5 j l December 98.1 f i Overall 43.1 l O O 1-2
1' l-
- 2. REPORTS The reports provided in this document meet the requirements of Federal Regulations (10 CFR 50.59) and of the Trojan Facility Operating License (FOL), Appendix A and Appendix B Technical Specifications. Complete data for the year 1983 have been included, although some-of the data for the first 6 months (January through June) have been previousl.v reported.
e U O 2-1
2.A EFFLUENT AND WASTE DISPOSAL REPORT This section contains a summary of the liquid and gaseous release limits; { a listing of the maximum permlosible concentrations of the isotopes released; a summary of batch and abnormal release data; a summary of cotal liquid and gaseous releases; listings of isotopes released classi-fled by pathway, gaseous or liquid, and type, continuous or batch; and a summary of solid radioactive waste and irradiated fuel shipments. j During the year, the effluer.ts released by the Trojan Nuclear Plant were ( well within the limits set forth in the Environ:aental Technical Specifi-cations to the Plant's Facility Operating License. The data presented in l i this section represent all releases during the period January 1, 1983 through December 31, 1983. m O O 2-2
O TABLE 2.A-1 PART A-1 SUPPLEMENTAL INFORMATION January 1, 1983 through June 30, 1983 l REGULA'IORY LIMITS
- lst 2nd i Fission and Activation Gas Release Rate Limits Unit Quarter Quarter l
- 1. ETS 1.1. 5. a (1) , Instantaneous 1 l QTV 1 2.0 Ky /sec ,1.32E-1
- 1 QTv 1 0.33(Ly + 1.1 Ny ) !** *
~
1
- 2. ETS 1.1.5.b. (1) , Quarterly Average QTv 1 13 Ny /sec 2.88E-2
- 1 QTv 1 6.3 My !**# * ~
- 3. ETS 1.1.5.b.(2), Twelve Month Average 1
QTv 1 25 Ny Ci/sec 1.44E-2 1.37E-2 QTv < g C1/sec 4.96E-3 4.84E-3
- The plant was shutdown for the entire 2nd Quarter 1983. There were no noble gas releases.
O 2-3
} TABLE 2.A-2 PART A-2 SUPPLEMENTAL INFORMATION January 1, 1983 through June 30, 1983 REGULATORY LIMITS Gaseous Iodine Release Limit
- 1. ETS 1.1. 5.b. (5) , Iodine 131 limit of 2.0 Ci during any calendar year.
- 2. ETS 1.1.5.b. (6) , Iodine 131 limit of 4.0 Ci during any consecutive l twelve month period. i I
Particulate Release Limit (For Nuclides with Half Lives Greater than Eight Days)
- 1. ETS 1.1. 5.a . (2) , Instantaneous release rate of 1.27 X.10" Ci/Sec.
- 2. ETS 1.1.5.b.(3), Quarterly average release rate limit of 3.21 X 10 Ci/Sec.
~
- 3. ETS 1.1.5.b. (4) , Twelve month average release rate limit of 1.67 X 10 C1/Sec.
Liquid Effluent Limits (Excluding Tritium and Gases)
- 1. ETS 1.1.2.a, Instantaneous discharge concentrations less than the maximum permissable concentrations listed in 10 CFR 20, Appendix B, Table II, Column 2.
- 2. ETS 1.1.2.b, Gross release limit of 10 Ci in a quarter.
- 3. ETS 1.1.2.c, Gross release limit of 20 Ci in any consecutive twelve month period.
91 2-4 l
F I-I L
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%d TABLE 2.A-3 Sheet 1 of 2
. PART A-3 SUPPLEMENTAL INFORMATION January 1, 1983 through June 30, 1983 i
MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid Isotope MPC (uCi/cc)
~
Sodium 22 3 X 10 ~ Cobalt 58 9 X 10
-5 Cobalt 60 3 X 10 ~
Manganese 54 1 X 10, Fluorine 18 8 X 10 ~ Chromium 51 2 X 10,35 Zirconium 95 6 x 10
~4
[ T Niobium 95 1 X 10 (/ Technetium 99m 3 X 10 Iodine 131 3 X 10 Iodine 133 1 X 10 -6 Cesium 134 9 X 10 -6
-5 Cesium 137 2 X 10 Barium 140 2 X 10 Lanthanum 140 2 X 10 Cerium 141 9 X 10 ~
Antimony 125 1 X 10, Cerium 144 1 X 10 ~ Silver llom 3 X 10 5 Antimony 124 2 X 10
-5 Ruthenium 103 8 X 10,4 Cobalt 57 4 X 10
-5 Tin 113 8 X 10
-6 Strontium 89 3 X 10,7 Strontium 90 3 X 10-Alpha 3 X 10,83 Tritium 3 X 10 -5 Xenon 133 4 X 10 -5 Molybdenum 99 4 X 10
-5 Neodymium 147 6 X 10
-5 Iron 59 5 X 10
-5 Ruthenium 106 1 X 10 -8 Unidentified 3 X 10 1
1 2-5
O .i i TABLE 2.A-3 Sheet 2 of 2 l I MAXIMUM PERMISSIBLE CONCENTRATIONS ( Cont.) Liquid Isotope MP5 (uci/ce)
~
Xenon 135 4 X 10 ' Tellurium 132 2 X 10~.
~
Xenon 133m 4 X 10 Gaseous Gaseous MPC's are not used in calculating technical specifications at Trojan. 1 . O 2-6 i
f
- 1
%.J IABLE 2.A-4 Sheet 1 of 2 PART A-4 SUPPLEMENTAL INFORMATION January 1, 1983 through June 30, 1983 AVERAGE ENERGY ,
Effluent release limits are not based upon E, hence, reporting E is not required. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Gaseous Releases Fission and Activation Gases: Gamma spectrometric ana' lysis of gaseous . grab samples define radionuclides distribution at least monthly on / monitored gaseous release points. Using the known nuclide distri-f-^ butions and process radiation conitor readings, the actual quantities ( )g of gaseous releases are calculated. Iodiness Weekly composite filter samples are analyzed by gamma spectro-scopy to determine the concentration of particulate isotopes. Weekly composite samples are analyzed for bets and alpha emitting isotopes by counting with a gas flow proportional counter using chemical separation techniques when necessary. Quarterly composite filters are analyzed i for Sr-89/90 using chemical separation and gas proportional beta counting. Tritium: Tritium is collected on dry silica gel in monthly composite samples, and counted using liquid scintillation spectroscopy.
]
]
I Liquid Releases ) l Fi,ssion 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. ! l 4 l {} ms i 2-7 .
)
.I TABLE 2.A-4 Sheet 2 of 2 i
1 MEASUREMENTS AND APP 10XIMATIONS OF TOTAL RADIOACTIVITY (Cont.) l Liquid Releases Tritium: Monthly composite samples are distilled and, deionized as necessary to remove contamination and counted by liquid scintillation techniquet. 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, O 2-8
l- Ch TABLE 2.A-5 I PART A-5 SUPPLEMENTAL INFORMATION January 1, 1983 through June 30, 1983 BATCH RELEASES Unit Liquid Gaseous Number of Batch Releases 60 24 Total time period for Batch Releases Hours 256.4 2748.1 Maximum time period for Batch Releases Hours 20.8 1525.0 Average time period for Batch Releases Hours 4.3 114.5 Minimum time period for Batch Releases Hours 0.1 3.8 Average dilution flow during batch releases GPM - 24140 NA Ch ABNORMAL RELEASES Number of Abnormal Releases Ci 0 1 Total Activity Released Ci 0 5.08EO O 2-9
1 - TABLE 2.A-6 Ol PART B-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1983 through June 30, 1983 1st 2nd Estimated FISSION AND ACTIVATION GASES Unit Quarter Quarter Error % l Total Activity Released Ci 6.57E+1 0 13.5E+1 Average Release Rate for Quarter DCi/sec 8.47EO O Percent of Limit - Instantaneous % 2.01E-2 0 j Quarterly Average % 8.06E-2 0 j Twelve Month Average % 3.73E-1 1.77E-1 IODINE 131 . Total Iodine 131 Released Ci 1.27E-3 3.54E-6 13.5E+1 Average Release Rate for Quarter ECi/sec 1.64E-4 4.51E-7 Percent of Limit - Quarterly Total % 6.35E-2 1.77E-4 Twelve Month Total % 1.33E-1 5.98E-2 PARTICULATE Total with Half-Lives > 8 days Ci 2.38E-3 9.44E-4 !3.5E+1 Average Release Rate for Quarter uCi/sec 3.07E-4 1.20E-4 Percent of Limit - Instantaneous % 1.59E-1 1.08E-3 Quarterly Average % 9.52E-1 3.72E-1 Twelve Month Average % 1.84E0 1.21EO Total Gross Alpha Released Ci 5.10E-6 <3.04E-6 TRITIUti Total Released Ci 5.18E+1 5.45E+1 23.0E+1 Average Release Rate for Quarter pCi/sec 6.68EO 6.89EO No Technical Specification Limits 2-10
4' . jq. U TABLE 2.A-7' PART B-2 l- , GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES
' January 1, 1983 through June 30, 1983 y
Continuous Mode Batch Mode Ndclides Released Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter FISSION GASES
- Krypton - 85m Ci 6.16E-3 '1.81E-2 Krypton - 85 Ci 5.87E-1
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Krypten C1 1.04E-2 Krypton - 88 Ci 9.32E-3 Xenon - 131m Ci 7.75E-1 Xenon - 133m Ci 6.11E-1 (" Xenon - 133 Ci 2.98EO 5.78E+1 Xenon - 135m Ci 5.05E-2 6.47E-3 Xenon - 135 Ci ' 7.11E-1 2.04E0 Xenon - 137
~
Ci 2.03E-2 Xenon - 138 C1 2.95E-2
' Argon - 41 g 5.35E-2 TOTAL FOR QUARTER C1 3.82EO O 6.19E+1 0
-IODINES Iodine - 131 Ci 2.14E-4 1.06E-3 3.54E-6 Iodine'- 133 Ci 7.77E-4 1.34E-4 Iodine - 135 Ci 7. 51 E-3 TOTAL FOR QUARTER C1 8.50E-3 0 1.19E-3 3.54E-6 PARTICULATE Strontium - 89. Ci 9.33E-5 $8.59E-5 1.40E-5 4.77E-4 Strontium - 90 Ci 9.33E-5 <4.62E-5 1.40E-5 3.17E-4 Cesium - 137. C1 1.30E-5 1.POE-4 1.41E-5 Cobalt - 58 C1 2.87E-5 3.06E-4 Cobalt - 60 Ci 7.42E-6 2.37E-6 Niobium - 95 C1 1.68E-4 Zirconium - 95 Ci 9.15E-6 Ruthenium - 103 C1 1.58E-4
. TOTAL FOR QUARTER E 4.03E-4 <1.32E-4 6.84E-4 8.08E-4 2-11
t TABLE 2.A-8 PART B-3 GASEOUS EFFLUENTS ELEVATED RELEASES January'1, 1983 through June 30, 1983
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No elevated release points. 9l l l 2-12 l l
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~.s TABLE 2.A-9 PART C LIQUID EFFLUENTS SUMMATION OF ALL RELEASES 'j l
l January 1, 1983 through June 30, 1983 1st 2nd Estimated FISSION AND ACTIVATION PRODUCTS Unit Quarter- Quarter Error % Total Activity Released ..(excluding Ci 4.63E-2 9.81E-2 i3.5E+1 gases,. tritium, and alpha) l Average Diluted Concentration pCi/ml 4.54E-9 1.06E-8 Percent of Limit - Quarterly Total % 4.63E-1 9.81E-1 Twelve Month Total % 3.02EO 2.44EO Fraction of MPC % 4.98E-1 1.92E-1
/
TRITIUM Total Released Ci 8.63E+1 2.15E+1 Average Diluted Concentration pCi/ml 8.46E-6 2.32E-6 3.0E+1 Fraction of MPC % 2.82E-1 7.74E-2 DISSOLVED AND ENTRAINED GASES Total Activity Released Ci 2.08E-2 4.08E-4 Average Diluted Concentration pCi/ml 2.04E-9 4.41E-11 13.5E+1 4 Fraction of MPC % 5.09E-3 1.10E-4 GROSS ALPHA RADIOACTIVITY Total Release Ci <3.87E-4 <l.72E-4 13.0+1 UNDILUTED-VOLUME OF WASTE RELEASED Liters 1.17E7 4.41E6 5.0E0 . I VOLUME OF DILUTION WATER Liters 1.02E10 9.26E9 tl.5E+1 2-13 l u
TABLE 2.A-10 Sheet 1 of 2 IART C-2 LIQUID EFFLUENTS January 1, 1983 through June 30, 1983 Continuous Mode Batch Mode NUCLIDES RELEASED Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Fluorine - 18 Ci 3.39E-5 5.15E-4 Chromium - 51 Ci 3.88E-4 8.87E-4 Cobalt - 58 C1 2.27E-3 2.84E-3 Cobalt - 60 Ci 1.18E-2 5.08E-2 Iron - 59 Ci 2.20E-5 Manganese - 54 Ci 7.59E-4 2.19E-3 Zirconium - 95 Ci . 2.30E-3 4.15E-3 Niobium - 95 Ci 4.78E-3 8.22E-3 Molybdenum - 99 Ci 1.58E-5 Technetium - 99m Ci 1.66E-5 Iodine - 131 Ci 5.48E-4 9 Iodine - 133 Cesium - 134 Cesium - 137 C1 Ci 2.39E-5 8.61E-4 5.91E-4 Ci 8.95E-4 2.50E-3 1.73E-3 Baritm - 140 C1 2.22E-4 9.22E-5 Lanthanum - 140 Ci 7.73E-4 Cerium - 141 C1 1.98E-5 8.91E-5 Antimony - 124 Ci 1.06E-4 Antimony - 125 C1 2.96E-4 7.75E-4 Silver - 110m Ci 4.80E-5 2.42E-4 Ruthenium - 103 Ci 2.32E-4 7.07E-4 Cerium - 144 Ci 7.26E-3 1.30E-2 Cobalt - 57 Ci 8.06E-6 8.11E-5 Ruthenium - 106 C1 4.98E-3 1.06E-2 Strontium - 89 Ci 3.24E-3 2.10E-4 1.15E-3 3.50E-5 Strontium - 90 Ci 8.58E-4 ~<5.57E-5 4.34E-5 2.99E-5 Tellurium - 132
- Ci 8.01E-7 Sodium - 22 C1 1.21E-6 3.01E-7 Neodymium - 147 Ci 5.41E-6 Tin -113 Ci 7.98E-5 4.23E-5 Unidentified C1 2.33E-6 6.47E-7 TOTAL FOR QUARTER Ci 4.99E-3 4.88E-4 4.13E-2 9.76E-2 0
2-14
O TABLE 2.A-10 Sheet 2 of 2 Continuous Mode Batch Mode NUCLIDES RELEASED Units 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Xenon - 133 C1 2.06E-2 2.64E-4 Xencn - 135 Ci 1.56E-4 Xenon - 133m C1 1.44E-4
~
TOTAL FOR QUARTER Ci 0 0 2.08E-2 4.08E-4 O O 2-15
l 1 l-TABLE 2.A-11 Sheet 1 of 2 PART D SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1983 through June 30, 1993 l Activity Volume Estimate ' SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL During During Total (Not Irradiated Fuel) - Type of Waste 6 Months 6 Months Error %
- 1. Spent Resin, Filter Sludges, Evaporator 1672.297 C1 42.34 m 3 25%
Bottoms, etc.
- 2. Dry Compressible Waste, Contaminated 0.989 C1 68.56 m3 25%
Equipment, etc..
- 3. Irradiated Components, Control' Rods, etc. 0 0
- 4. Other 0 -0 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASIT C1 C1
'Nuclide .
- 1. See attached sheet.
'G- 2. See attached' sheet. %) 3.
4. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 10 Exclusive Truck U.S. Ecology P.O. Box 638 Richland, WA 99352 IRRADIATED FUEL SHIPMENTS DISPOSITION Number of Shipments Mode of Transportation Destination 0 N/A N/A O 2-16
i 1 TABLE 2.A-11 Sheet 2 of 2 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide Ci ;
- 1. Mn-54 29.867 Co-57 1.803 Co-58 54.250 Co-60 727.261 Nb-95 0.131 Zr-95 - 0.060 Sb-125 0.027 I-131 0.001 Cs-134 102.334 Cs-137 202.796 Ce-144 0.251 Ru-106 0.216 Sr-89 0.800 Sr-90 24.800 .
Fe-55 157.100 Ni-63 370.600
- 2. Mn-54 0.026 0
Co-58 0.045 Co-60 0.377 Nb-95 0.038 Zr-95 0.027 Sb-125 0.001 Cs-134 0.077 Cs-137 0.192 Ce-144 0.113 Ru-106 0.093 l 2-17
/ '
.I TABLE 2.A-12 PART A-1 SUPPLEMENTAL INFORMATION July 1, 1983 through December 31, 1983
~
FEGULATORY LIMITS 3rd- 4th Fission and Activation Gas Releaza Rate Limits Unit Quarter Quarter
.l. ETS 1.1.5.a (1) , Instantaneous QTv i 1 Ci/sec 1.77E-1 2.27E-1 2.0 Ky O QTv 1 ) Ci/sec 3.08E-1 3.93E-1
- 0. 33 (Lv + 1.1 Ny)
- 2. ETS 1.1.5.b(1) , Quarterly Average QTv i 1 C1/see 2.30E-2 2.84E-2 13 Ny QTv i 1 Ci/see 1.01E-2 1.10E-2 6.3 My
- 3. ETS 1.1.5.b(2) , Twelve Month Average QTv 1 1 Ci/see 1.36E-2 1.48E-2 25 Ny 1:
gTv 1 1 Ci/see 4.90E-3 5.31E-3 {- 13 My g 2-18 I. .
G' TABLE 2.A-13 PART A-2 SUPPLEMENTAL INFORMATION July 1, 1983 through December 31, 1983 REGULATORY LIMITS
- Gaseous Iodine Release Limit
- 1. ETS 1.1.5.b(5), Iodine 131 limit of 2.0 Ci during any calendar year.
- 2. ETS 1.1.5.b(6), Iodinc 131 limit of 4.0 Ci during any consecutive twelve month period. ,
Particulate Release Limit (For Nuclides with Half Lives Greater than Eight Days)
- 1. ETS 1.1.5.a(2), Instantaneous release rate of 1.27 x 10-6 Ci/sec.
- 2. ETS 1.1. 5.b (3 ) , Quarterly average release rate limit of 3.21 X 10-8 Ci/sec.
- 3. ETS 1.1.5.b(4), Twelve month average release rate limit of 1.67 x 10-8 Ci/sec.
Linuid Effluent Limits (Excluding Tritium and Gases)
- 1. ETS 1.1.2.a, Instantaneous discharge concentrations less than the maximum permissible concentrations listed in 10 CFR 20, Appendix B, Table II, Column 2.
- 2. ETS 1.1.2.b, Gross release limit of 10 Ci in a quarter.
- 3. ETS 1.1.2.c, Gross release limit of 20 Ci in any consecutive twelve month period.
O 2-19
1 I "Y a
<w -
,,l TABLE 2.A-14 Sheet 1 of 2 PART A-2
, SUPPLEMENTAL INFORMATION l .
July 1, 1983 through December 31, 1983 u. MAXIMUM' PERMISSIBLE CONCENTRATIONS' Liquid Isotope MPC (UCi/cc) Cobalt 58 9 X 10-5 Cobalt 60 3 X 10-5 Manganese 54 1 X 10-4 Fluorine 18 8 X 10-4 Chromium 51 2 X 10-3 - Zirconium 95 6 x 10-5 Niobium 95 1 X 10-4 Iodine 131 3 X 10-7 [ Iodine 133 1 X 10-6
.\ -Cesium 134- 9 X 10-6, ,
l Cesium 137 2 X 10-5 Barium 140 2 X 10-5 Lanthanum 140 2 X 10-5 ' Cerium'141 9 x 10-5 Antimony 125 1 X 10-4 Cerium 144 1 X 10-5 l Antimony 124 2 X 10-5 Ruthenium 103 S X 10-5 Cobalt 57 4 X 10-4 Strontium 89 3 X 10-6 Strontium 90 3 X 10-7 1 Alpha 3 X 10-8 Tritium 3 X 10-3 Xenon 133 4 X 10-5 Iron 59 5 x 10-5 Ruthenium 106 1 X 10-5 Unidentified 3 X 10-8 k 2-20
O: TABLE 2.A-14 Sheet 2 of 2 MAXIMUM PERMISSIBLE CONCENTRATIONS (Cont.) Liould Isotope MPC (uC1/ce) - Xenon 135 4 X 10-5 Tellurium 132 2 X 10-5 Xenon 133m' 4 X 10-5 Xenon 131m 4 X 10-5 , Gaseous Gaseous MCS's are net used in calculating technical specifications at Trojan. l l
)
l 1 O 2-21 I l 1 t _ _ _ _ _ _ _ _ _
TABLE 2.A-15 Sheet 1 of 2 PART A-4 SUPPLEMENTAL INFORMATION July 1, 1983 through December 31, 1983 i l AVERAGE ENERGY Effluent release limits are not based upon E, hence, reporting E is not required. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Gaseous Releases Fission and Activation Gases Gamma spectrometric analysis of gaseous grab samples define radionuclides distribution at least monthly on monitored gaseous release points. Using the known nuclide distri-butions and process radiation monitor readings, the actual quantities of gaseous releases are calculated. Iodines: Weekly composite filter samples are analyzed by gamma spectro-scopy to determine the concentration of particulate isotopes. Weekly composite samples are analyzed for beta and alpha emitting isotopes by counting with a gas flow proportional counter using chemical separation techniques when necessary. Quarterly composite filters are analyzed for Sr-89/90 using chemical separation and gas proportional beta counting. Tritium: Tritium is collected on dry silica gel in monthly composite samples, and counted using liquid scintillation spectroscopy. Licuid 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. 2-22
1 O l TABLE 2.A-15 Sheet 2 of 2 . I MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY (Cont.) Liquid Releases 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 i i I i i I O 2-23
______7--- t ~- i i TABLE 2.A-16 PART A-5 SUPPLEMENTAL INFORMATION l July 1, 1983 through December 31, 1983 l BATCH RELEASES Unit Liquid Gaseous Number of Batch Releases 73 103 Total time period for Batch Releases Hours 267.1 1911.4-Maximum time period for Batch Releases Hours 14.8 62.5 Average time period for Batch Releases Hours 3.6 18.6. l Minimum time period for Batch Releases Hours 0.4 0.3 Average dilution flow during Batch Releases GPM 19310 N/A O ABNORMAL RELEASES Number of Abnormal Releases 1 0 Total' Activity Released Ci 3.00E-4 0
)
O 2-24
1 o TABLE 2.A-17 PART B-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1983 through December 31, 1983 3rd 4th Estimated FISSION AND ACTIVATION GASES Unit Quarter -Quarter Errort Total Activity Released Ci 3.19E+1 1.31E+2 13.5E+1 - Average Release Rate for Quarter pCi/sec 4.01EO 1. 6 5E+1 Percent of Limit - Instantaneous % 6,71E-3 1.98E-2 Quarterly Average % 3.70E-2 1.51E-1 Twelve Month Average % 2.42E-1 1.40E-1 IODINE 131 Total Iodine 131 Released Ci . 38E-4 3.19E-4 13.5E+1 Average Release Rate for Quarter p Ci/sec 3.00E-5 4. 02E-5 Percent of Limit - Quarterly Total % 1.19E-2 1.60E-2 Twelve Month Total % 5.45E-2 4.58E-2 PARTICULATE Total with Half-Lives >8 days Ci 4.60E-4 5.03E-4 13.5E+1 Average Release Rate for Quarter p Ci/sec 5.84E-5 6. 3 7E-5 Percent of Limit - Instantaneous % 5.72E-3 6.99E-3 Quarterly Average % 1.81E-1 1.98E-1 Twelve Month Average % 1.13E0 8.22E-1 Total Gross Alpha Released Ci < 3. 48E-6 e2.24E-6 TRITIUM Total Released C1 2.43E+1 8.53E0 13.0E+1 Average Release Rate for Quarter pCi/sec 3.06E0 1.08E0 No Technical Specification Limits 2-25
b.' i t TABLE 2.A-18 PART B-2 GASEOUS EFFLUENTS GROUND LFVEL RELEASES July 1, 1983 through December 31', 1983 Continuous Mode Batch Mode NUCLIDES RELEASED Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter FISSION GASES Krypton - 85m Ci 8.74E-3 2.08E-2 8.64E.2 2.49E-2 Krypton - 85 Ci 3.93E-1 9.53E-1 Krypton - 87 Ci. 2.14E-2 4.37E-2 Krypton - 88
.l.12E-2 Ci 1.48E-2 1.06E-1 Xenon - 131m Ci 8.79E-3 4.08E-2 1.06E O Xenon - 133m C1 2.30E-1 9.31E-1 Xenon - 133 Ci 5.32E O 6.72E O 2.33E+1 1.19E+2
! Xenon - 135m Ci 1.07E-1 2.01E-1 1.13E-1 Xenon - 135 Ci 6.33E-1 2.82E-1 1.35E O 1.33E O Xenon - 137 Ci 1.36E Xenon - 138 Ci 4.77E-2 8.23E-2 Argon - 41 Ci 4.49E-3 2.26E-3 1.16E-1 3.49E-1 TOTAL FOR QUARTER E 6.14E O 7.39E O 2.58E+1 1.24E+2 IODINES Iodine - 131 Ci 2.36E-4 3.17E-4 2.03E-6 1.41E-6 Iodine - 133 Ci 1.32E-3 2.86E-3 2.27E-6 4.23g-6 Iodine - 135 C1 1.40E-6 TOTAL FOR QUARTER E 1.56E-3 3.18E-3 4.30E-6 5.64g-6 PARTICULATE Strontium - 89 Ci 1.45E-4 1.15E*4 8.91E-7 7.56E-7 Strontium - 90 Ci 5.40E-5 5.47E-5 1.03E-6 4.26E-7 Cesium - 137 C1 2.10E-5 1.21E-5 4.18E-7 2.56E-7 Cobalt - 58 Ci 1.31E-7 Cobalt - 60 C1 1.41E-7 4.90E-8 Cesium - 134 Ci 8.10E-8 2.47g-B Zirconium - 95 Ci 1.35E-7 TOTAL FOR QUARTER E 2.20E-4 1.82E-4 2.47E-6 1.46E-6 O 2-26
?
l O TABLE 2.A-19 i PART B-3 l' GASEOUS EFFLUENTS ELEVATED RELEASES . July 1, 1983 through December 31, 1983 I I No elevated release points O O 2-27
U 7.q. 1 TABLE 2'.A-20 PART C-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1983 through December 31, 1983 3rd 4th Estimated FISSION AND ACTIVATION PRODUCTS Unit Quarter Quarter Error 4 Total Activity Released (excluding Ci 1.07E-1 5.89E-2 +3.5E+1 gases, tritium and alpha)' Average Diluted Concentration DCi/ml 1.06E-8 6.04E-9 Percent of Limit - Quarterly Total % 1.07E O 5.89E-1 Twelve Month Total % 1.65E O 1.55E O Fraction of MPC % 7.29E-1 2.28E-1 l . TRITIUM gg Total Released Ci 1.20E+2 5.87E O +3.0E+1 Average Diluted Concentration pCi/ml 1.19E-5 6.01E-7 Fraction of MPC % 3.96E-1 2.01E-2 DISSOLVED AND ENTRATNED GASES Total Activity Released C1 2.27E-2 1.29E-2 +3.5E+1 Average Diluted Concentration pCi/ml 2.25E-9 1.33E-9 Fraction of MPC % 5.63E-3 3.31E-3 GROSS ALPHA RADIOACTIVITY Total Release Ci 17.63E-4 11.92E-4 +3.0+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.49E+7 8.24E+6 +5.0E0 VOLUME OF DILUTION WATER Liters 1. 01E+10 9.76E+9 +1.5E+1 2-28
~!
/% 4.
-\). TABLE 2.A-21 Sheet 1 of 2 PART C-2 LIQUID EFFLUENTS July 1, 1983 through December 31, 1983 Continuous Mode. Batch Mode NUCLIDES RELEASED Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter Fluorine - 18 Ci 3.47E-4. 1.08E-4
' Chromium - 51 Ci 6.92E-5 Cobalt - 58 Ci 3.03E-3 8.29E-4 Cobalt - 60 Ci 5.01E-2 1.82E-2 Iron - 59 Ci 7.81E-5 Manganese - 54 Ci 1.90E-3 6.50E-4 Zirconium - 95 Ci 1.56E-3 4.63E Niobium - 95 Ci 3.24E-3 9.15E-4 Iodine - 131 C1 2.07E-4 1.61E-4
. Iod!ne - 133 Ci 2.36E-4 5.75E-5
\ Cesium - 134 C1 4.29E-3 2.64E-3 .{
Cesium - 137 Ci 1.22E-2 7.27E-3 Barium - 140 Ci 2.13E-4 Lanthanum - 140 Ci 2.38E-4 3.51E-4 Antimony - 124 Ci 2.01E-4 7.00E-5 Antimony - 125 Ci 6.72E-3 8.30E-3 Ruthenium - 103 Ci 2.15E-4 3.01E-5 Cerium - 144 Ci 9.82E-3 7.31E-3 Cobalt - 57 Ci 4.10E-5 Ruthenium - 106 Ci 1.14E-2 4.16E-3 Strontium - 89 Ci 7.79E-4 6.41E-3 1.87E-4 1.38E-4 Strontium - 90 Ci 8.92E-5 4.43E-4 7.87E-5 1.42E-6 Tellurium - 132 g 6.53E-6 Unidentified C1 2.04E-4 2.02E-5 TOTAL FOR QUARTER Ci 8.68E-4 7.06E-3 1.06E-1 5.18E-2 V 2-29
O TABLE 2.A-21 Sheet 2 of 2 4 Page 2 continuous Mode Batch Mode NUCLIDES RELEASED Units 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter Xenon - 131m C1 3.6,9E-4 Xenon - 133 Ci 2.20E-2 1.27E-2 Xenon - 135 Ci 1.32E-4 2.37E-4 Xenon - 133m Ci 1.83E-4 TOTAL FOR QUARTER E O O 2.27E-2 1.29E-2 0 2-30
TABLE 2.A-22 Sheet 1 of 2 Part D SOLID WASTE AND IRRADIATED FUEL SHIPMENTS July 1, 1983 through December 31, 1983 Activity Volume Estimate SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL During During Total (Not Irradiated Fuel) - Type of Waste 6 Months 6 Months Error %
- 1. Spent Resin, Filter Sludges, Evaporator 1.561 Ci 75.76 m3 25%
l Bottoms, Filters, etc. l 2. Dry Compressible Waste, Contaminated 0.375 Ci 41.04 m3 25% Equipment, etc.
- 3. Irradiated Components, Control Rods, etc. 0 0
- 4. Other 0 0 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE C1 Ci Nuclide .
- 1. See attached sheet.
- 2. See attached sheet.
3. 4. SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 6 Exclusive Truck U.S. Ecology, Inc. P.O. Box 638 Richland, WA 99352 IRRADIATED FUEL SHIPMENT DISPOSITION Number of Shipments Mode of Transportation Destination 0 N/A N/A
~"
O
l TABLE 2.A-22 Sheet 2 of 2 e f ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide C1 1. Mn-54 0.041 Co-57 0.001 Co-58 0.088 Co-60 0.872 Nb-95 0.052 Zr-95 0.025 Ru-106 0.131 - Sb-125 0.009 q I-131 0.002 Cs-134 0.042 ! Cs-137 0.103 l Ce-144 0.196
- 2. Cr-51 0.010 Mn-54 0.010 .
Co-58 0.021 Co-60 0.139 Nb-95 0.028 Zr-95 0.014 Ru-103 0.001 Ru-106 0.011 Sb-125 0.002 Cs-134 0.021 Cs-137 0.056 Ce-141 0.002 Ce-144 0.057
\
2-32 l
'r '
( ,/ 2.B 0FFSITE RADIATION DOSES Offs!<.e radiation doses from gaseous and liquid effluents for 1983 are presented in this section. Included are 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 con-tinuous releases an'd for noble gas, gaseous iodine and particulate, and liquid effluents. Exposure locations are based on the land-use survey presented in the Updated FSAR, and the annual survey of agriculture production, effective October 4, 1982. Meteorological data used in the analyses are presented in Section 2.C of this report. Models and assumptions used in performing the dose analyses for 1983 are presented in Sections 11.2 and 11.3 of the Trojan Updated FSAR. Addi-tional assumptions are given in this section, j l 1
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2-33 l I L- --_____ -- i
(.,
! TABLE 2.B-1 Sheet 1 of 2- .Qt PARAMETERS USED IN CALCULATING DOERS FROM GASEOUS EFFLUENTS (First Half 1983)
Parameter Value Accumulation and Decay Times (days) l 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 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 vegetables by adult 64.0 Produce by adult- 456.0 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m 3/yr) Adult .8,000.0 Infant. 1,400.0 Animal Consumption Rates (kg/ day) Animal feed by seat animal 50.0 Animal 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 Fraction of Particulate Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulate Initially Deposited on Produce 0.2 Fraction of Icdine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m2) 240.0 l Field Decay Half Life (days) 14.0 Agricultural Productivity (kg/m2) Leafy vegetables 2.0 O Pasture grass Produce 0.7 2.0 2-34
l l TABLE 2.B-1 Sheet 2 of 2 Parameter Value Period of Long-Term Buildup for Activity in Soil (days) 7,300.0 Fraction of Leafy Vegetables Grown in Garden of Interest 1.0 Fraction of Produce Grown in Garden of Interest 0.76 Fraction of Year Animal Grazes on Pasture o,5 Fract. ion of Daily Feed that is Pasture Grass when Animal Grazes 1.0 O O O 2-35
Sheet 1 of 2 TABLE 2.B-2 PARAMETERS USED IN CALCULATING DOSES ( FROM L? QUID EFFLUENTS ' Value Parameter 1st Otr. 1983 2nd Otr. 1983 Plant Dilution Flow Rate (spm) 20,800.0 18,700.0 Columbia River Flow Rate (cfs) 319,883.0 464,069.0 Dilution Factors Drinking water 6,908.0 11.156.0 Swimming water 1,520.0 2,454.0 Aquatic biota 1,520.0 2,454.0 Shoreline sediment 1,520.0 2,454.0 Irrigation water 6,908.0 11.156.0 Milk and meat animal water 6,900.0 11,156.0 Decay Times (days) ~ Discharge to drinking water 0.61 0.57 Discharge to swimming water 0.0 0.0 Discharge to aquatic biota consumption 1.0 O 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 , Discharge to irrigation water withdrawal 0.61 0.57 Discharge to milk and meat anistl water 0.61 0.57 withdrawal Leafy vegetable harvest to consumption by man 1.0 Produce harvest to consumption by man 60.0 Stored feed harvest to consumption by animals 90.0 Pasture grass to consumption by animals 0.0 Animal butchering to consumption 20.0 Food and water ingestion by cow / goat to 2.0 milking Accumulation Times (days) Shoreline sediment 7,300.0 Irrigated soil 7,300.0 Irrigated vegetables 60.0 Pasture grass 30.0 Adult Consumption Rates (kg/yr) Drinking water 730.0 Fish 21.0 Invertebrates (crayfish) 5.0 Irrigated leafy vegetables 64.0 Irrigated produce 456.0 Cow's milk from irrigated pastueeland
- 310.0 Goat's nilk from irrigated pastureland 310.0 Meat from irrigated pastureland 110.0 O-. Annual Exposure Times (he/yr)
Swimming and boating 12.0 Shoreline activities 12.0 Irrigated pasture 2,190.0 2-36
TABLE 2.B-2 Value Parameter 1st Otr. 1983 2nd Ote. 1983 Infant Consumption Rates (kg/yr) Drinking water 330.0 Cow's milk from irrigated pastureland 330.0 Fraction of Year Animals Graze on Pasture 0.5 Fraction of Year Crops are Irrigated 0.5 , Field (Weathering) Half-Life (days) 14.0 ., Irrigation Rate (liters /m2-hr) 0.104 i Fractional concentration of Water in soil (g/g) 0.2 5 Fraction of Leafy Vegetables Crown in Garden of
- 1.0 Interest Fraction of Produce Crown in Garden of Interest 0.76 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Leafy vegetables Fraction of Isot' ope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Grass Yield (kg/m2) 0.7 Vegetable Yield (kg/m2) 2.0 Surface Density of Soil (kg/m2) 240.0 Animal Consumption Rates (kg/ day)
Water by milk cow 60.0 Water by milk goat 8.0 Water by beef 50.0 Pasture vegetation by milk cow 50.0 1 Pasture vegetation by milk goat 6.0 Pasture vegetation by beef 50.0 i O 2-37
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D 42568 76607 2 5 I 00000 00000 0 0 D - - - - - - - - - - - - R EEEEE EEEEE E E Y 34126 39509 5 2 H T 12284 51716 2 1 42568 76657 2 5 L 00000 00000 0 0 AY - - - - - - - - - - - - M TD EEEEE EEEEE E E O OO R F TB l 4.I.2 6 99399 4 2 12284 31776 2 1
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3 E a 8 LS 9 IT 4 1 MN E) R 0UM B. E 5LE 2 T (FR R F-E A EEN T L U S A N B Q ODM E DI( M A T U I L T S NQ D G I R OI E NN D s I IL S IO S F T RI A ND ET D L OE TP E U IT AM T P Y TA HU A ) O A PNG S N N P H MIN KNH I O H UMI COD M S T SAT OCI A R A A T TNNT E P N N f. n SEPOON OOf P RICCB ELMIIO / E ET C VBUTTC M R TPE D IASPP E U AMTGN LTNMMO R S HUATA EOUUT M O SR DGCSS ( P GNBEG NE NNE X NOERN AVEOOR E E ICTUI CCCU S K RSM NYU S O NHEOM OFDTKO D ISVPI i IAOALP CRINXt TEREIX E IDFIES ALPMME G T G L A A I A R _ U R T E Q R O V _ A I T A "dm
h -
-c D TABLE 2.B-5
; Yl'
[ FIRST QUARTER 1983 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site-Boundary [a] ResidenceD I I Beta Air Dose (mead) 2.8E-2 2.6E-2 Camma Air Dose (mead) 1.0E-2 6.7E-3 I Beta + Gamma Skin Dose (mrom) - 1.6E-2 Camma Total Body' Dose (meem) - 5.7E-3 ! I 1 [a] North sector at 663 meters. (b) North sector at 692 meters. 1 ( i l l 1 JD l U 1 2-40 1
TABLE 2.B-6 h! l FIRST QUARTER 1983 CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDEN0E OF i HIGHEST CONCENTRATION ) Site Boundary (a) ResidenceIDI Beta Air Dose (mrad) 2.4E-3 2.3E-3 Gamma Air Dose (mrad) 1.4E-3 9.0E-4 l Beta + Gamma Skin Dose (mram) - 2.1E-3 Gamma Total Body Dose (trem) - 8.2E-4 (a) North sector at 663 meters. ~ (b) North sector at 692 meters. O e O 2-41 1
TABLE 2.B-7 FIRST QUARTER 1983 BATCil + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF { HIGiiEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 3.lE-2 2.9E-2 Camma AiE Dose (mrad) 1.2E-2 7.68-3 Beta + Camma Skin Dose (mrem) - 1.9E-2 Canuna Total Body Dose (mrem) - 0.5E-3 [a] Maximum site boundary location. [b] Maximum residence location. ' O i O 2-42
HEG 1986 8 99608 7 455443 1 455443 TTR 3850 5 01642 0 897970 0 897971 ONO I 2318 1 12845 9 917342 1 917345 44 3 44 4 44 2 2 44 D 00 0 00 0 00 0 0 00 TI - - - - - - - - - - - - NO EE E EE E EE E E EE nR 59 8 49 3 15 9 4 15
!Y 9800 0 41000 6 190000 1 100005 NH . .
IT 6300 1 32000 5 310002 2 310002 2 4454 3 44544 3 443443 3 443443 3 D 0000 0 00000 0 000000 0 000000 TI - - - - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 0949 6 89199 8 652127 5 652125 DY 9803 9 31755 8 095148 4 095146 AH T 6338 4 32141 2 311412 5 311413 S N O 4443 3 44445 3 444454 3 444454 I 0000 0 00000 0 000000 0 000000 T E - - - - - - - - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E NC O 3960 7 99086 6 751262 1 751268 IO B 7806 5 21788 4 195920 5 195928 S DL . E U 2331 2 12185 1 111752 1 111754 S LE A CR e E XU L ES E (O R P 4444 3 44545 4 445454 4 445454 SX 0000 0 00000 0 000000 0 000000 8 H TE G - - - - - - - - - - - - - - - - - - - - - - - - C N N EEEE E EEEEE E EEEEEE E EEEEEE E T EE U 2949 9 49279 6 352101 6 352104 B. A UT L 4823 3 11749 8 090160 0 090161 2 B LI . FS) 2316 1 12633 7 116331 8 116332 9 E 3 FFM 8 EFE L 9 OR B 1 S M A UM( T R OU 4444 3 44545 4 545454 4 545454 E EM 0000 0 00000 0 000000 0 000000 T SI H - - - - - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEEEEE E A GA K 9432 7 86949 4 678211 1 678214 U M S 2544 5 05707 9 729636 6 729639 QM OT 2417 1 12744 8 926341 9 926343 RA 1 F
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8 SS EE SS 4444 3 44545 4 545454 4 545454 3 OA 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 9932 0 89949 7 658211 8 658214 L OO 2844 5 01707 5 799636 2 799639 B TB O 2317 1 12744 8 916341 9 916343 N Y N N N N A ) O ) O ) O ) O H S I S I S I S I H R T R T R T R T T E P E P E P E P A T M T M T M T M P E U E U E U E U N M S M S M S N M S O D NN NN NN O NN I N . OO . OO . OO I . OO T A 9 CI 7 CI 9 CI T CI P N 0 L IEP T 2 L IEPO TN 4 L TNP 9_ 4 L TNM 6 8 1 IEPOM 1 _ IEPOU O 1 NOLM 4 NOLMI 5 NOLMIU _ NOLMIS I T T I OSBU AS T OSBUT I ASP T OSBUTS I ASPN 5_OSBUTN _ ASPO A C A TOTN
- ATEO A _ TOTNM
_ ATEOU A TOTNMO ATEOUC T_I TOTNMC A_ATEOU O R- L GC GCS R GCS LR_L L R_L GCSK L O AEE AO AEE N O AEE NK _ AEE NL T HRVE T HRVEOL TT O_HRVEO E C NU C MT__HRVEO CC NC- NU R E ISYU IC_NU NE OE_ISYU CCI M _ NU AC_ISYUCCM U NS OFD AS__ISYU OFDT OFDT OE_ OFDTT S O E RPAO L A RPAOA L CS_RPAOAH L GS_ RPAOAA P DE_IXER RS_AELP T TH_IXERE AN_AELPM A T KH_IXEREO _ A T KH_IXEREO LH X AS_ O EN_ _ O LN_AELPMC IN_ O E G( T M( T M( T IN__AELPMG M( w s[;
HEG 5505 3 39150 5 322896 5 322891 3 TTR 1108 9 53963 4 604393 7 604395 5 ONO I_ . 2594 7 93423 4 834227 4 834221 5 35 3 45 4 45 3 3 45 D 00 0 00 0 00 0 0 00 TI - - - - - - - - - - - - NO EE E EE E EE E E EE AR 25 7 99 3 42 4 9 42 FY 5100 5 83000 2 200005 1 200007 NH . IT 1500 1 63000 7 630006 7 630009 3533 3 55434 3 454543 3 454343 3 D 0000 0 00000 0 000000 0 000200 TI - - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 2537 6 99862 7 720989 7 720988 5 DY 4148 7 03365 9 805312 7 805311
- AH
- T 2514 8 13823 4 937231 5 937232 6 S
N - O 3533 2 35334 5 454344 3 454343 3 I 0000 0 00000 0 000000 0 000000 T E - - - * - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E S NC O 4516 0 99914 2 923957 9 923955 9 E IO B 4186 4 03089 4 807154 4 S DL ' 807159 A U 2519 1 13153 8 939539 8 939531 9 E LE L CR , E XU R ES (O - S P 5543 3 45434 3 454344 3 U SX 0000 0 454343 3 9 00000 0 000000 0 000000 D TE G - - - - - - - - - - - - - - - - - - - - -
- U N N EEEE E EEEEE E EEEEEE E EEEEEE E B.
N EE U 5574 4 29949 5 220888 4 220889 0 I UT '2 T LI L 1198 9 63862 4 704392 7 704394 5 N FS) 2584 7 93423 4 834227 4 834221 5 E O FFM - L C EFE B OR A 3 S' M T 8 UM( 9 OU 3545 3 45434 3 454344 3 1 EM' ' 0000 0 00000 0 000000 0 454343 3 000000 SI N - - - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEEEEE E E GA K 3485 4 27040 6 331892 5 331890 T M S 1098 9 59963 4 654393 7 654395 5 R M A OT 2684 7 93423 4 834227 4 834221 5 U RA Q F
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SS . 1 EE SS 3543 5 45434 3 454344 3 0 OA 0000 0 454343 3 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 3585 3 29040 5 321892 4 321890 L OO 1198 9 53963 4 604393 7 604395 5 0 TB 0 - 2584 7 93423 4 834227 4 N - 834221 5 Y N N N N A ) O ) O ) O ) N S S O I I S I S I H R T R T R T R T T E P E P E P E P A T M T M T M T M P E U E U E U E U N M S M S M S N M S O D NN NN NN O NN I N . OO . OO . OO I . OO T A 9 CI 7 CI 9 CI T 9 CI P 0 L T 2 L TN 4 L TNP 4 L TNM H 6 IEP 8 IEPO 1 IEPOM 1 IEPOU D 1 NDLM 4 NDLMI 5 NOLMIU 5 NOLMIS I OSBU OSBUT OSBUTS - OSBUTN T T I AS T I ASP T I ASPN T- I ASPO A A TOTN A TOTNM A TOTNMO A TOTNMC O C ATEO ATEOU ATEOUC - ATEOU O R L GC LR L GCS R L GCS R- L GCSK L O AEE AO AEE N O AEE NK O AEE NL T HRVE MT HRVEO T HRVEOL TT HRVEOI E C NU C IC NU CC HC NU R E ISYU NE ISYU CCI AC NU CCM U NS OFD OE ISYU M OE ISYU AS OFDT CS OFDT GS OFDTT S E RPAO L RPAOA L RPAOAH O L - RPAOAA P DE RS IXER AELP A TH IXERE A KH IXEREO A KH IXEREO T AN AELPM LN AELPNC X AS T T LN AELPMG O EN O IN O IN-
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NO EE E EE E EE E E EE E AR 10 5 33 9 55 4 6 55 1 FY 2400 6 05000 2 320007 8 320005 NH IT 2400 2 12000 1 920002 2 920003 3 3433 2 34334 3 343343 2 343343 2 D 0000 0 00000 0 000000 0 0U0000 TI - - - - - - - - - - - - - - - - - - - - - - LD EEEE E EEEEE E EEEEEE E EEEEEE E UR 1071 7 33521 5 957006 2 957003 DY 1447 3 45511 8 222861 1 222868 2 AH T 3445 1 12235. 7 122244 1 122245 S N S O 3432 2 34334 3 343343 2 E I 0000 0 343343 2 00000 0 000000 0 000000 S T E - - - - - - - - - - - - - - - A GA N EEEE E E NC O EEEEE E EEEEEE E EEEEEE E 1023 6 23603 8 132885 0 152884 L IO B 7411 6 25275 8 0 121904 E R U DL 2421 I.21901 LF 1 12164 9 121541 1 121542 S CR s U 'X U O ES U (O N P 3433 3 34434 3 444344 3 444343 3 I SX 0000 9 00000 0 000000 0 000000 T TE G - - - - - - - - - - - - - - - - - - - - - - 0 N N N EEEE E EEEEE E EEEEEE E EEEEEE E 1 O EE U 9028 3 83699 4 550949 5 55D940
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A B OU 3433 3 34434 3 444344 3 444543 T EM 0000 0 00000 0 000000 0 000000 3 SI N - - - - - - - - - - - - - - - - - - - - - - 8 AX I EEEE E EEEEE E EEEEEE E EEEEEE E 9 GA K 6449 1 66848 5 121423 1 121429 1 M S 3105 5 09607 3 661749 7 661748 M . . R OT 2515 9 12533 5 925238 5 925231 6 E RA T F R ) A SS U EE Q SS 3433 3 34454 3 444344 3 444343 OA 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - 1 AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 6049 3 63848 1 151423 7 151429 8 L OO 3405 4 05607 3 621749 6 621748 B TB . . D 2415 9 12533 5 925233 5 N 925231 6 Y N N N N A O O O O N I I I I H T T T T T P P P P A M M M M P U U _ U U N S S _ S N S O D NN NN NN O NN I N OO OO OO I OO T A CI CI CI T CI P L T L TN L TNP L TNM N IEP IEPO . IEPOM IEPOU O N NDLM, N NOLMI N NOLMIU N I O OSBU O_ OSBUT HDLMIS O OSBUTS O bSBUTN T I I AS I I ASP I I ASPN I I ASPO A T TOTN T TOTNM T TOTNMO T TOTNMC C A ATEO A ATEOU A ATEOUC A ATEOU O CL GC LC_L GCS CL GCS C L GCSK L O AEE AO_AEE N O AEE NK O kEE NL E L HRVE ML HRVEO L HRVEOL TL HRVEOI NU C I NU CC H NU CCI A bU CCM _ R M ISYU NM ISYU OM M U NU OFD ISYU OM kSYU
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TABLE 2.B-14 SECOND QUARTER 1983 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site I Boundary (a) ResidenceIDI l i Beta Air Dose (mead) 1.0E-7 9.8E-8 Camma Air Dose (arad) 3.0E-8 2.0E-8 Beta + Camma Skin Dose (mres) - 6.7E-8 Gamma Total Body Dose (meem) - 1.6E-8 [a] North sector at 663 meters. (b) North sector at 692 meters. I e O 2-49
t - , TABLE 2.B-15 SECOND QUARTER 1983 CONTINUOUS RELEASES 1. DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HICHEST CONCENTRATION No continuous noble Eas releases. 2-50
TABLE 2.B-16 SECOND QUARTER 1983 BATCH + CONTINU0US RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 1.0E-7 9.8E-8 Gamma Air Dose (mead) 3.0E-3 2.0E-8 Beta + Gamma Skin Dose (mres) - 6.7E-8 Gamma Total Body Dose (mrom) - 1.6E-8 [a] North sector at 663 meters. ~ (b) North sector at 692 meters. i el 2-51
' AS 0000 0 00000 0 000000 0 000000 0 RNN - - - - - - - - - - - - - - - - - - - - - - -
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- O - 3522 2 45324 2 463344 3 465343 2 I - 00L0 0 00000 0 000000 0 000000 0 T E- - - - - - - - - - - - - - - - - - - - - - - -
GA N EEEE E EEEEE E EEEEEE E EEEEEE E NC O 8121 9 32855 7 313988 8 024422 3 IO B 5419 1 73707 7 841941 0 136605 2 S DL . E U 1615 7 63536 3 261515 8 391821 1 S LE A CR i E XU L ES E (O R P 4532 2 45334 3 464354 3 464354 3 SX 0000 0 00000 0 000000 0 000000 0 7 H TE G - - - - - - - - - - - - - - - - - - - - - - - 1 C N N EEEE E EEEEE E EEEEEE E EEEEEE E T EE U 5169 3 52245 8 611778 2 72l188 1 A UT L 4474 8 73461 5 149587 2 B. B LI FS) 6621 1 23172 9 162151 2 3.l.2 2 7 3 2 - 2 194274 3 3 FFM - E 8 EFE L 9 OR B 1 S M , A UM( T R OU 4532 2 45354 3 464354 3 454354 3 E EM 0000 0 00000 0 000000 0 000000 0 T SI N - - - - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEEEEE E A GA K 5779 3 07255 8 571700 1 592227 1 U M S 8474 8 58461 5 049598 2 101238 3 QM . OT 5721 1 23172 9 172151 2 114274 3 RA 2 F
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8 SS EE SS 4532 2 45354 3 464354 3 464354 3 OA 0000 0 00000 0 000000 0 000000 0 DG L - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 5179 3 02255 7 511700 1 522227 1 L OO 8474 8 53461 5 049598 2 131238 3 B TB . . . . O 5621 1 23172 9 162151 2 194274 3 N _ ) _ Y_ N S N - N N A_ ) O R O ) - O ) O N S I E I S- I S I H R T T T R- T R T T E P E P E_ P E P A T M M M T- M T M P E U U E- U D N D-M S . S M S N E_ S O NN 4 NN NN O M_ NN I N . . OO 1 OO . OO I ._ OO T _ A CI 4 CI 9 CI T 8_ CI P N 9_ 0 L T 2 L TN 4 L TNP 1 _ L INM 6 _ IEP IEPO 1 IEPOM _ IEPOU - O 1 _ NDLM T_ A_NDLMI 5 NDLMIU 2_ NOLMIS I T _ OSBU OSBUT OSBUTS 3_ OSBUTN - T_ TOTNAS _ I - I ASP T I ASPN I ASPO A C A_ATEO R TOTNM O_ATEOU
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SS 2 EE SS 3043 5 40434 5 4l4444 3 0 OA 0100 4l4444 0 01000 0 0I0000 0 0I0000 DG L - - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 0714 8 96976 9 247991 7 328559 L OO 5345 8 05336 8 213306 5 525516 B TB . . . O 1784 6 83422 3 361712 N 1 391815
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ERA EEEE E EEEEE E EEEEEE E EEEEEE E HEG 9114 2 62602 5 719183 8 820786 7 TTR 0469 5 03808 3 242364 7 637080 3 ONO I 2631 2 131)4 1 464214 3 495311 5 35 3 45 4 46 5 3 46 3 3 D 00 0 00 0 00 0 0 00 0 0 TI - - - - - - - - - - - - - - NO EE E EE E EE E E EE E E AR 61 2 02 3 81 6 8 82 8 3 FY 0400 1 43000 7 140003 5 330001 4 NH . . . IT 1600 1 53000 5 260001 1 290003 3 3532 2 35524 2 464344 3 464343 5 D 0000 0 00000 0 000000 0 000000 0 TI - - - - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 9134 2 62701 5 711186 9 823786 7 DY 0469 5 03808 3 243364 7 637080 3 AH T 2631 2 13114 1 464214 3 4953I1 5 S N S O 3522 2 35323 2 463544 2 463243 2 E I 0000 0 00000 0 000000 0 000000 0 S T E - - - - - - - - - - - - - - - - - - - - - - - A GA N EEEE E EEEEE E EEEEEE E EEEEEE E E NC O 0147 3 52731 8 118294 4 127453 6 L IO B 2430 7 53860 5 343362 0 939032 5 E DL R U 3617 8 13631 4 661728 1 691132 1 LE S CR . U XU O ES U (O N P 3532 2 35524 2 464344 3 464345 3 I SX 0000 0 00000 0 000000 0 0000D0 0 9 1 T TE N N G N EEEE E EEEEE E EEEEEE E EEEEEE E
- O EE U 5104 2 926n9 5 018189 9 229785 6 C UT L 1469 5 3 B.
2 + FS) LI 038.o.7 442363 7 836080 3 2631 2 13114 1 464214 3 495311 5 E FFM ' H EFE L C OR B T S M A A UM( T B OU 3552 2 35324 2 464344 3 454343 3 EM 0000 0 00000 0 000000 0 000000 0 3 SI N - - - - - - - - - - - - - - - - - - - - - - - 8 AX I EEEE E E5EEE E EEEEEE E EEEEEE E 9 GA K 9714 2 67601 5 778181 8 890786 6 1 M S 0469 5 02808 3 242364 7 607080 3 M . . . R OT 2731 2 13114 1 474214 3 415311 5 E RA T F R ) A SS U EE Q SS 3532 2 35324 2 464344 5 464543 3 OA 0000 0 00000 0 000000 0 000000 0 DG L - - - - - - - - - - - - - - - - - - - - - - - 2 AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD, 9114 2 62601 5 718181 8 820786 6 8 L OG, 0469 5 03808 3 242364 B . 7 637080 3 O N TB_ 2631 2 13114 1 464214 3 495311 5 Y N N N N A O O O O H I I I I H T T T T T P P P P A M M M M P U U U U N
- S _ S S N S O D NN _ NN NN O NN I N OO _ OO OO I OO T A CI _ CI CI T CI P L T _ L TN L TNP L TNM N IEP _ IEPO IEPOM IEPOU O N NOLM N_NOLMI N NDLMIU N NOLMIS I O OSBU O_ OSBUT O OSBUTS O
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D 8244332 2 5 I 0000000 0 0 O - - - - - - - - - R EEEEEEE E E Y 9298736 5 1 H T 2326322 6 3 8244532 2 5 L 0000000 0 0 AY - - - - - - - - - M TD EEEEEEE E E S O OO 9298735 4 1 E R TB S F 2326322 6 3 A E ) 3L ES . 8E LT 9R IN 0 1 ME S U) 2 RU 0LM EO 5FE B. TU (FR 2 RN E-AI E N UT SSA E QN OUM L O DO( B DC E A N NS T O+ OA C IG EH T SC A T L A U N B P Y O ) O A I N P N T O H P S T M R A U E P S P NN / E OO N R CI E U L TNN R S IEPOO M O NNOLMII ( P OOSBUTT X II ASPP E E STOTNMM S RATEOUU O EL GCSS D MAEE NN BHRVEOO E UNU CCC G SISYU L A OFDTK A R RRPAOAL T E
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d,3 TABLE 2.B-21 Sheet 1 of 2 PARAMETERS USED IN CALCULATING DOSES FROM CASEQUS EFFLUENTS (Second Half 1983) 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 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 vegetables by adult 64.0 Produce by adult 456.0 Heat by adult 110.0 Milk by adult 310.0 Milk by infant '
, . 330.0 Breathing Rates (m3 fye)
Adult 8,000.0 Infant 1,400.0 Animal Consumption Rates (kg/ day) Animal feed by seat animal 50.0 Animal-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 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 l Surface Density of Soil for Root Zone (kg/m 2) 240.0 Field Decay Half Life (days) 14.0 Agricultural Productivity (kg/m 2)
Leafy vegetables O- Pasture grass 2.0 0.7 Produce 2.0 2-56
TABLE 2.B-21 Sheet 2 of 2 Parameter Value Period of Long-Term Buildup for Activity in soil (days) 7,300.0 I Fraction of Leafy Vegetables Grown in Garden of Interest 1.0 Fraction of Produce Grown in Garden of Interest 0.76 Fraction of Year Animal Grazes on Pasture 0.5 Fraction 'of Daily Feed that is Pasture Grass when Animal Grazes 1.0 O 2-57
O 4 TABLE 2.B-22 Sheet 1 of 2 PARAMETERS U.9ED IN CALCULATING DOSES FROM LIQUID EFFLUENTS Value Parameter 3rd Otr. 1983 4th Otr. 1983 Plant Dilution Flow Rate (spm) 24,900.0 19,500.0 Columbia River Flow Rate (cfs) 207,396.0 184,452.0 Dilution Factors Drinking water 4,619.0 4,250.0 Swimming water 1,016.0 935.0 Aquatic biota 1,016.0 935.0 Shoreline sediment 1,016.0 935.0 ! Irrigation water 4,619.0 4,250.0 Milk and meat animal water 4,619.0 4,250.0 Decay Times (days) Discharge to drinking water 0.67 0.69 Discharge to swimming water 0.0 0.0 Discharge to aquatic biota consumption 1.0 1.0 Discharge to deposition on shoreline sediment O 0.0 0.0 Discharge to irrigation water withdrawal 0.67 0.69 l Discharge to milk and meat animal water 0.67 0.69 i withdrawal Leafy vegetable harvest to consumption tar man 1.0 Produce harvest to consumption by man 60.0 Stored feed harvest to consumption by animals 90,0 Paytwee grass to consumption by animals 0.0
.. ail buttitring to consumption 20.0 F6od and water ingestion by cow / goat to 2.0 milking Accumulation Times (days)
Shoreline sediment 7.300.0 Irrigated soil 7,300.0 Irrigated vegetables 60.0 Pasture grass 30.0 Adult Consumption Rates (kg/yr) Drinking water 730.0 l Fish 21.0 Invertebrates (crayfish) 5.0 Irrigated leafy vegetables 64.0 Irrigated produca 456.0 Cow's milk from 4rrigated pastureland 310.0 Goat's milk from irrigated pastureland 310.0 Meat from irrigated pastureland 110.0 Annual Exposure Times (hr/yr) Swimming and boating 12.0 Shoreline activities 12.0 Irrigated pasture 2,190.0 l 2-58
) TABLE 2.B-22 Sheet 2 of 2 O Value Parameter 3rd Ote. 1983 4th Ote. 1983 Infant Consumption Rates (kg/yr) Drinking water 330.0 Cow's milk from irrigated pastureland 330.0 Fraction of Year Animals Graze on Pasture 0.5 Fraction of Year Crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14.0 Irrigation Rate (liters /m 2 -hr) 0.104 FracLlonal Concentration of Water in Soil (g/g) 0.2 FracLlon of Leafy Vegetables Grown in Garden of - 1.0 Interest Fraction of Produce Grown in Garden of Interest 0.7 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by feafy Vegetables Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by Produce ) i Pasture Grass Yield (kg/m 2) o,y j Vegelsble Yield (kg/m 2) 2.0 Surface Density of Soil (kg/m2) 240.0 Animal Consumption Rates (kg/ day) , Water by milk cow 60.0 Water by milk goat 8.0 Water by beef 50.0 Pasture vegetation by milk cow 50.0 Pasture vegetation by milk goat 6.0 Pasture vegetation by beef 50.0 0 2-59
NEG EEEEE E EEEEE EEEEEE EE TTR 41316 9 45431 177472 86 ONO I 71619 1 72122 317325 99
. ~ D 5 5 5 44 44 TI 0 0 0 00 00 NO - - - - - - -
AR E E E ' EE EE FY 70000 7 70000 000012 08 NH _ IT_ 70000 7 70000 000012 31 D 53458 3 54568 565554 44 TI 00000 0 00000 000000 00 LO - - - - - - - - - - - - - - - - - - - UR EEEEE E EEEEE EEEEEE EE DY 95016 7 92431 162472 47 AH T 51219 1 53422 394141 65 53458 3 00000 0 54568' 00000 555554 44 000000 00 E - - - - - - - - - - - - - - - - - - - N EEEEE E EEEEE EEEEEE EE O 23016 6 29431 113841 25 B 61219 1 62422 315141 65 S T , , N , 54558 4 55568 565555 44 E , 00000 0 00000 000000 00 U G - - - - - - - - - - - - - - - - - - - 3 L N EEEEE E EEEEE EEEEEE EE 3 8 F U 34616 6 33231 100171 74 2 9 F L 1 E 52519 3 55122 363226 22 B. R D) 2 E IM T UE E R QR L A IM 53457 . 3 54568 565554 44 B U L( 00000 0 00000 000000 00 Q N - - - - - - - - - - - - - - - - - A . M EEEEE E EEEEE T 3 O I K EEEEEE EE 75022 7 72478 652351 47 R 0 F S_ 51212 1 53424 384141 65 S E S O D 53458 3 54568 565554 44 L 00000 0 00000 000000 00 AY - - - - - - - - - - - - - - - - - - - TD EEEEE E EEEEE EEEEEE EE OO 75016 7 72431 152351 36 TB . 51219 1 53422 384141 65 N T T G NO N N N N L OI E O E I I IT M I M R ON TP I T D I E SO PM A D T I MU N NE C NE A LT US O OS O OS N AP ) SN I I TE L I RM )T NO Y T TE K UU HA OC A A PNG L PNG C TS OO C H C MIN A MIN O LNN CG K N O ULI R ULI T UOO (( KL T L SET U SET S CCI LI A NNRA T NNRA E I TNNN IM P M OOOO L OOOO V REPOOO LM U E M ET RICHB. U RICHB I GLMIII A T _ S C ET S L ABUTTT THA - R I TPE D I TPE D ASPPP OOO - U X AMTON R AMTON D OTNMMM TCC S A HUATA L G HUATA N TEOUUU OM SR A A SR A GCSSS LGG - P GNBEG T GNBEG EE NNN ANN - X T NOERN O T NOERN N RVEOOO RII T _ E_ A ICTUI K RSM A ICTUI K RSM O U CCCC UDD I SYU TUU _ C NHEOM C C NHEOM T OFDTKK LLL I ISVPI I I ISVPI A PAOALL UCC - T RINXH T T RINXH G XEREII CXX - A DFIES A A DFIES I ELPMMM IEE _ .U U U R R - __Q Q Q R G _ _A A A I A we$ ,I
D 41557 76546 1 5 I 00000 00000 0 0 O - - - - - - - - - - - - R EEEEE EEEEE E E Y 44825 42944 4 8 H T 21852 73124 1 6 41557 76546 1 5 L 00000 00000 0 0 AY - - - - - - - - - - - - M TD EEEEE EEEEE E E O OO 34825 52834 4 7 R TB F 21852 63124 1 6
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3 E 8 LS . 9 IT 4 1 MN 2 E)
- R 0UM E 5LE B. T (FR 2 R F-A EEN T E U S A N L Q ODM E B DI( M A D U I L T R NQ D G I I OI E NN O H IL S IO S T T RI A ND ET D L OE TP E U IT AM T P Y TA HU A )
O A PNG S N N P H 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 HUATA EOUUT M O SR DGCSS ( P GNBEG NE NNE X NOERN AVEOOR E E ICTUI CCCU S K RSM NYU S O NHEOM OFDTKO D ISVPI IAOALP CRINXH TEREIX E IDFIES ALPMME T G G L A A I A R U R T E Q R O V A I T A oh
TABLE 2.B-25 THIRD QUARTER 1983
.' BATCH RELEASES DOSES FROH NOBLE GASES AT SITE BOUNDARY AND' RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mead) 7.2E-3 6.8E-3 Cansea Air Dose (mrad) 3.4E-3 2.2E-3 Beta + Canna Skin Dose (meem) -
5.0E-3 Gamma Total Body Dose (mram) - 2.0E-3 s (a) North sector at 663 meters. V [b] North sector at 692 meters. O 2-62
l TABLE 2.B-26 THIRD QUARTER 1983 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF < HIGHEST CONCENTRATION I I Site 'l' Boundary [a] ResidenceIDI Beta Air Dose (mrad) 1.7E-3 1.6E-3 i Gamma Air Dose (mrad) 9.1E-4 5.9E-4 ! Beta + Gamma Skin Dose (mrem) - 1.3E-3 Gamma Total Body Dose (mram) - 5.3E-4
- i
[a] North sector at 663 maters. [b] North sector at 692 meters. 2-63 O
?tV , w<
.. o
,y 9 p;c TABLE 2.B-27 e XJ THIRD QUARTER 1983
' DATCH + CONTINUOUS REIE.ASES _
j l DOSES FROM NOBLE GASES AT - l SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION , I J Site -l Boundary [a] ResidenceIDI
-s
' Beta Air Dose (mead) 8.9E-3 8.4E-3 t f
Gamma Air Dose (mrad) 4.3E-3 2.8E-3 ] i Beta + Gamma Skin Dose (arem) , 6.3E-3 'l
- Canna Total Body Dose (mrem) -
2.5E-3
~
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' 1
[alcMaximum site boundary location. ~ [b) Maximum residence location. O l U
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HEG 2173 5 11309 7 392036 0 441027 TTR 1428 7 14281 6 300368 3 365108 ONO I 3316 6 11529 3 228415 6 831842
~
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- A UT L 3426 6 14173 5 408257 0 964973 B LI .
B. FS) . 3316 8 2 11528 3 227414 6 831732 3 FFM 8 EFE E 9 OR L 1 S M-B UM( - A R OU - 6655 5 66657 5 777677 6 776676 Y E EM 0000 0 00000 0 000000 0 000000 T SI N - - - - - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEEEEE E A GA K 1968 5 15888 6 254795 5 250446 U H S 1927 7 16178 6 349234 2 325096 QM . OT 3316 8 11528 3 227415 6 841832 RA 3 F
)
8 SS EE SS 6655 5 66657 5 777677 6 776676 OA 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 1168 9 11888 4 294795 1 240446 L OO 1427 6 14178 6 309254 2 365096 B TB . . . . O 3316 8 11528 3 227415 6 831832 N
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Y N S_ N N N A ) O R_ O ) O O H S I E I S I ) I H R T T T R T S T T E P E P E P R P A T M M M T M E M P E U U E U T U N M S . S M S N E S O D NN 4 NN NN O M NN I N . OO 1 OO . OO I OO T A 9 CI 4 CI 5 CI T . CI P 0 L T 2 L TN 4 L TNP 5 _ L TNM N 6 IEP IEPO 0 IEPOM 0 . IEPOU O 1 NOLM T NOLMI 8 NOLMIU 5 NOLMIS I OSBU A OSBUT OSBUTS 4 OSBUTN T T I AS I ASP T I ASPN I ASPO A A TOTN R TOTNM A TOTNMO T TOTNMC C ATEO O ATEOU ATEOUC A ATEOU R L GC LT L GCS R GCS GCSK 0_ L O AEE AC_AEE N O AEE L NK L NL T HRVE ME_NRVEO T NRVEOL R__AEE HRVEOI E R C NU C E ISYU IS_NU N _ ISYU CC _NU HC_ISYU CCI TO_NU AT_ CCM OE_ OFDT M U 5 NS E RPAO OFD L AH_RPAOA OFDT L CS_ RPAOAH L OC_ISYU GE_ RPAOAA OFDTT 0_ DE IXER A T_ IXERE A KE_IXEREO A K S_ P X RS AS AELP T O TU_AELPM AO T O LS_ AELPHC T O LE_IXERED _ E, G( T E S __ N( T IS_ M( T IS__AELPMG M( 7&
- HEG 8583 2 97882 0 306821 7 922769 TTR 3272 7 00808 2 038690 8 ONO 648724 3 I 1195 7 55321 3 176331 6 311916 34 3 45 4 56 3 3 45 3 D 00 0 00 0 00 0 0 00 0 TI - - - - - - - - - - - -
NO EE E EE E EE E E EE E AR 05 2 67 7 40 4 3 82 8 FY 1200 2 00000 5 430009 0 940007 NH IT 1100 1 45000 4 870001 2 210005 6 3433 2 45334 3 464454 3 454443 D 0000 0 00000 0 000000 0 000000 TI - - - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 5507 0 97192 9 507054 5 423204 DY 6202 0 00203 1 238761 0 441841 AH .
- T 1135 1 65122 4 171343 1 414911 S
N - O 3432 2 45334 5 464454 3 454344 5 I 0000 0 00000 0 000000 0 000000 T E - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E S NC O 1570 6 27641 0 009864 4 928982 E IO B 6285 9 90106 1 237304 4 S DL . 249042 A U 1121 1 55162 8 171951 1 413218 3 E LE L CR E XU . R ES (O S P 3443 3 45434 3 465455 4 U SX 0000 0 454444 00000 0 000000 0 000000 O TE G - - - - - - - - - - - - - - - - - - - - - - J 9 U N N EE N EEEE E EEEEE E EEEEEi. E EEEEEE E U 0547 6 57258 8 4074h0 v 320155 N2 B. I T N UT LI FS) L 4261 1195 7 6 10807 55321 3 1 037 17 6339 e 87 l 748722 2 311916 2 O FFM C EFE E OR L 3 S M B 8 UM( 9 OU 3443 3 45434 3 s65455 i A 1 EM 0000 0 00000 0 454444 3 T u00000 C 000000 SI N - - - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEEEEE E E GA K 8601 1 93570 0 321604 4 961569 T M S 3472 7 09808 2 058699 8 668723 3 R M - A OT 1195 7 5532i 3 18633'. 6 U RA 311916 Q F
)
SS 3 EE SS 3443 3 45434 3 465455 4 454444 3 8 OA 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 8501 8 97570 9 301604 3 L OO 3272 6 921569 B 00808 1 038699 8 648723 TB . . O 1195 7 55321 3 176339 6 N 311916
)
Y N S N N N A ) O R O ) O O H S I E I S I ) I H R T T T R T S T T E P E P E P R P A T M M M T M E M P E U U E U T U N M S . S S N E S O D NN 4 NN M_ - NN O M NN I N . OO 1 OO . __ OO I OO T A 9 CI 4 CI 5_ CI T . CI P 0 L T 2 L TN 4 L TNP N 6 IEP 5 L TNM O NDLM IEPO 0 IEPOM 0 IEPOU 1 T NOLMI 8 NOLMIU 5 NDLMIS _ I _ OSBU A OSBUT OSBUTS 4 OSBUTN T _I AS ASP T
) A C
T_TOTN A_ATEU I R TOTNM A TOTNMO I ASPN I T TOTNMC ASPO O ATEOU ATEOUC ATEOU O GC GCS A_ L R_L _ LT GCS L R. L GCSK Q L E O_AEE T_ C NU HRVE C AC AEE N ME HRVEO IS NU CC O_AEE T_ HC_HRVEOL NU NK CCI TO AT R AEE HRVEOI NL R E_ N ISYU NU CCM U OFD ISYU M OC ISYU AH OFDT O E __ OFDT _ S O NS__ISYU E _RPAO L T RPAOA L CS.RPAOAH
. L GE S RPAOAA OFDTT P DE_IXER A TU IXERE A KE_IXEREO A K IXEREO
- X RS_ AELP T AO O ES AELPM T O LS_ T O LE AELPMG E AS_ G( T M( T IS__AELPMC M( T IS M( m:$
RNN - - - - - - - - - - - - - - - - - - - - - - - ERA EEEE E EEEEE E EEEEEE E EEEEEE E HEG 8810 1 01313 4 314242 3 D64562 3 TTR 3293 8 12918 2 059790 9 748825 3 _ ONO I 1195 7 55321 3 176331 6 311916 2
~
34 3 45 4 56 3 3 45 5 3 D 00 0 00 0 00 0 0 00 0 0 TI - - - - - - - - - - - - - - ND EE E EE E EE E E EE E E AR 08 3 71 0 71 6 5 96 2 3 FY 1200 2 02000 6 450009 0 940008 1 NH . . . IT 1100 1 45000 4 870001 2 210005 6 3455 2 45334 3 464454 5 454443 3 D 0000 0 00000 0 000000 0 000000 0 TI - - - - - - - - - - - - - - - - - - - - - - - LD EEEE E EEEEE E EEEEEE E EEEEEE E UR 5834 1 l1223 3 S19477 6 566015 5 DY 6203 0 2 258761 0 441941 AH l.2213 1 T 1135 1 65122 4 171343 1 414911 3 S N S O 3432 2 45334 5 464454 3 454344 3 E I 0000 0 00000 0 000000 0 000000 0 S T E - - - - - - - - - - - - - - - - - - - - - - - A GA N EEEE E EEEEE E EEEEEE E EEEEEE E E NC O 2823 9 51853 3 112405 6 163298 4 L IO B 6295 9 92116 2 258514 4 340142 9 E DL \ . . R U 1121 1 55162 8 171951 1 414218 3 LE S CR . U XU O ES U (O N P 3443 3 45454 3 465455 4 454444 3 I SX 0000 0 00000 0 000000 0 000000 0 T TE G - - - - - - - - - - - - - - - '- - - - - - - - 0 N N N EEEE E EEEEE E EEEEEE E FEEEEE E 3 O EE U 0864 5 61789 2 415805 5 461957 0
- C UT L 4272 7. , 12807 2 058697 8 798722 3 LI B. + FS) 1195 7 55321 3 176339 6 3 .1916 2 2 FFM H EFE E C OR L T S M B A UM(
A B OU 3443 5 45434 3 465455 4 454444 3 T EM 0000 0 00000 0 000000 0 000000 0 3 SI H - - - - - - - - - - - - - - - - - - - - - - - 8 AX I EEEE E EEEEE E EEEEEE E EEEEEE E 9 GA K 8038 0 09001 4 369029 0 002362 2 1 M S 3582 8 10918 2 078799 9 778824 3 M . . R OT 1195 7 56321 3 186339 6 311916 2 E RA T F R ) A SS U EE Q SS 3443 5 45434 5 465455 4 454444 3 OA 0000 0 00000 0 000000 0 000000 0 DG L - - - - - - - - - - - - - - - - - - - - - - - 3 AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 8838 7 01001 3 319029 9 062362 1 8 L OO 3282 7 12918 2 058799 8 748824 3 B O TB_ 1195 7 55321 3 176339 6 311916 2 N _ Y N N N - N A O O O O W I I I I H T T T T T P P P P A M M M M P U U U U N S S S N S O D NH NN NN O NN I N OD OO OO I OO T A CI CI CI T CI P L T L TN L TNP L TNM N IEP IEPO IEPOM IEPOU O N NOLM N NOLMI N NOLMIU N NDLMIS
. I O OSBU C OSBUT O OSBUTS O OSBUTN T I I A5 I I ASP I - I ASPN I _ I ASPO A T TOTt 4 T TOTNM T TOTNMO T _ TOTNMC C A ATEG A ATEOU A ATEOUC A ATEOU O C L GC LC L GCS CL GCS CL GCSK L O AEE AO AEE N O AEE NK O AEE NL L HRVE ML HRVEO L HRVEOL TL HRVEOI E l lU C I l lU CC H NU CCI A NU CCM R M ISYU NM ISYU OM ISYU M CM ISYU U NU OFD AU4 OFDT CU- OFDT GU- OFDTT S EM RPAO L t RPAOA L M RPAOAH L M RPAOAA L O DI XER A TI IXERE A KI IXEREO A KI IXEREO A P RX AELP T AX AELPM T LX- AELPMC T LX AELPMG T X AA O EA O IA- O IA - O E GM T MM T MM- T MM- T N&N l,
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O. ._. D 3244332 2 5 I 0000000 0 0 O - - - - - - - - - R ECEEEEE E E Y 3763027 1 5 H T 4144112 5 2 3244332 2 5 L 8000000 0 0
- AY - - - - - - - - -
M TD EEEEEEE E E S O OO 3469011 2 6 E R TB S F 4141111 3 1
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3L ES . 8E LT 1 9R IN 3 1 ME S U) RU 0LM B. EO 5FE - O 2 E L B A TU RN AI UT QN dC O (FR E-E N SSA OUM DO( E T R NS I+ OA H IG TH T C A T L A U N B P Y O ) O A I N P H T O H P S T M R A U E P S P NN / E OO M R CI E U L TNN R S IEPOO M O NNDLMII ( P OOSBUTT X II ASPP E E STOTNMM S RATEOUU O EL GCSS D MAEE NN BHRVEOO E UNU CCC G SISYU L A OFDTK A R RRPAOAL T E IIXEREI O V AAELPMH T A 7&
, IlIl'l
EEEEEE EE TTR 89483 6 86615 473458 88 ONO I 13344 7 18719 173134 33 D 5 5 5 55 55 TI 0 0 0 00 00 NO - - - - - - - AR E E E EE EE FY 50000 5 50000 000020 57 NH IT 10000 1 10000 000036 74 D 54468 3 54569 565655 44 TI 00000 0 00000 000000 00 LO - - - - - - - - - - - - - - - - - - - UR EEEEE E EEEEE EEEEEE EE DY 29483 1 22015 462380 62 AH T 19144 1 12319 152315 33 54468 3 54569 555655 44 00000 0 00000 000000 00 E - - - - - - - - - - - - - - - - - - - N EEEEE E EEEEE EEEEEE EE O 06983 2 441892 30 B 0.l115 39144 1 32419 116515 44 S T ' N 64568 4 65669 565665 45 E 00000 0 00000 000000 00 U G - - - - - - - - - - - - - - - - - - - 3 L N EEEEE E EEEEE EEEEEE EE 8 F U 77083 2 77815 494962 07 2 9 F L . 3 1 E 71444 2 73819 121541 19 R D) B. E IM 2 T UE R QR E A IM 54468 3 54569 565655 44 L U L( 00000 0 00000 000000 00 B Q N - - - - - - - - - - - - - - - - - - + A M I EEEEE E EEEEE EEEEEE EE T 4 O K 19475 1 12034 662268 52 R S . 3 F 19151 1 12313 142314 33 S E S O D 54468 3 54569 565655 44 L 00000 0 00000 000000 00 AY - - - - - - - - - - - - - - - - - - - TD EEEEE E EEEEE EEEEEE EE OO 19483 1 12015 462268 52 TB 19144 1 12319 142314 33 N T T G NO N N N N L OI E O E I I IT M I M R DN TP I T I E SO PM D A D T I MU N NE C NE A LT US
-O OS O OS H AP ) SN I RM NO Y
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)T HA OC L PNG C TS OO C H C MIN A MIN O LHh CG K H O ULI R ULI T U0O (( KL T L SET U SET S CCI LI A NNRA T NNRA E I TNNN IM P M GOOO L OOOO V REPOOO LH
- U RICHB U RICHB I GLMIII A T E- M ET S C ET S L ABUTTT TNA R- I TPE D I TPE D ASPPP OOO U X AMTON R AMTON D OTNMMM TCG S A HUATA L G HUATA N TEOUUU OM SR A A SR A GCSSS LGG P GNBEG T GNBEG -
NNN ANN X T NOERN O ICIUI T T NOERN N_EE RVEOOO RII E_A K RSM A - ICTUI K RSM O __ I SYU U CCCC UDD TUU _ C NHEOM C - NHEOM C_ISVPI OFDTKK LLL ISVPI T __ PAOALL UCC _I RINXH T _T A DFIES I A I T_RINXH G_ELPMMH _ A_XEREII CXX _ U _Q U Q A_DFIES U_ Q I R_ IEE R G _A A A_ R_ I A y,
- O D 52557 76656 2 5 I 00000 00000 0 0 O - - - - - - - - - -
R EEEEE EEEEE E E Y 37560 4 6 _ H 94.l41 . . _ T 49621 41492 9 4 52557 76656 2 5 L 00000 00000 0 0 AY - - - - - - - - - - M TD EEEEE EEEEE E E O OO 34141 57440 4 6 R TB F 49621 31482 9 4
)
3 E 8 LS i 9 IT 3 1 MN 3 E)
- R 0UM E 5LE B. T (FR O 2 E
L B R A U S A Q ODM EEN DIC F-T N E M A H U . I L T T NQ D G I R OI E NN O U IL S IO S O T RI F A ND ET D L OE TP E U IT AM T P Y TA HU A ) O A PNG S N N P H 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 HUATA EOUUT M O SR DGCSS ( P GNBEG NE NNE X NOERN AVEOOR E E ICTUI CCCU S K RSM NYU S O NHEOM OFDTKO D ISVPI IAOALP - CRINXH TEREIX E IDFIES ALPMME G T G L A A I A R U R T E Q R O V A I T A O xiy l l' ;
{ T_ABLE 2.B-34 O
- FOURTH QUARTER 1983 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] Residencelbl Beta Air Dose (mrad) 5.1E-2 4. 7E- 2 Gamma Air Dose (mrad) 1.8E-2 1.2E-2 Beta + Gamma Skin Dose (mrem) -
2.8E-2 Camma Total Body Dose (mrem) - 1.0E-2 [a] North sector at 663 meters. (b) North sector at 692 meters. el4 2-71
O TABLE 2.B-35 FOURTH QUARTER 1983 CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mead) 3.7E-3 3.4E-3 Gamma Air Dose (mead) 2.0E-3 1.3E-3 Beta + Gamma Skin Dose (mram) - 2.9E-3 Gamma Total Body Dose (mrem) - 1.2E-3 O _ (a) North sector at 663 meters. (b] North sector at 692 meters. 9 O 2-72
TABLE 2.B-36 O FOURTH QUARTER 1983 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] Residence [b]' Beta Air Dose (mrad) 5.5E-2 5.0E-2 Gamma Air Dose (mrad) 2.0E-2 1.3E-2 Beta + Gamma Skin Dose (mrem) - 3.1E-2 Gamma Total Body Dose (meem) - 1.1E-2 [a] Maximum site boundary location. (b] Maximum residence location. O 2-73
HEG 5566 6 06687 7 435693 4 435698 TTR 6969 9 83276 0 611106 1 611104 DNO . I 5631 2 12166 1 121661 1 121663 67 6 67 6 67 5 5 67.
' D 00 0 00 0 00 0 0 00 TI - - - - - - - - - - - -
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0 SS EE SS 6755 5 67667 5 676676 5 676676 OA 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 5525 5 96531 7 434238 3 434233 L OO 6969 9 73276 0 611105 1 611103 B TB . . . O 5631 2 12166 1 121661 1 121663 N ' Y N N N N A ) O ) O ) O ) O H S I S I I S I N R E T R T S_ R T R T T P E P E P E P A T M T M T M T M P E U E U E U E U N M S M S M S N M S O D NN NN NN O NN I _ N . OO . OO . OO I . OO T A 9 CI CI CI _ 7 9 T 9 CI P - 0 L T 2 L TN 4 L TNP 4 L TNM - N 6 IEP 8 IEPO 1 IEPOM 1 IEPOU O 1 NOLM 4 NDLMI 5 NDLMIU 5 NOLMIS _ I OSBU OSBUT OSBUTS OSBUTN T T I AS T I ASP T I ASPN T I ASPO A C A TOTN ATEO A TOTNM ATEOU A_TOTNMO ATEOUC A TOTNMC ATEOU O O R L GC LR L GCS R L GCS R L GCSK O AEE AO AEE N O AEE NK O AEE NL L _ T HRVE MT HRVEO T HRVEOL TT HRVEOI E C NU C IC NU CC HC NU CCI AC NU CCM R E ISYU NE M ISYU OE ISYU OE ISYU U NS OFD AS OFDT CS OFDT GS OFDTT S E RPAO L RPAOA L RPAOAH L RPAOAA
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l 1 I i, i (D - 2,C METEOROLOGICAL DATA.
\
Meteorological data for 1983 are presented in this section. Inclue=a are quarterly joint frequency distributions of ground-level wind and atmos-pheric stability for batch and continuous releases. Also included are quarterly tables of atmospheric dispersion, deposition and depletion factors that have been calculated from these joint frequency distributions. Meteorological models and assumptions used in performing the analyses are presented in Section 2.3 of the Trojan Updated FSAR. e e (> P e 2-78
,m
( ) TABLE 2.C-1 TROJAN DISTANCES FOR CASEQUS EADICACTIVE EFFLUENT EVALUATION (meters) , Nearest Nearest Nearest Receptor Site Nearest Nearest Meat Milk Milk Direction Boundary Residence Carden Animal Cow Coat N 663 692 7884 7884 >8045 7884 NME 683 2694 3540 3701 3701 3701 NE 820 2731 4666 4666 >8045 5471 ENE 688 3438 3379 2253 7080 7080 E. 677 960 2414 2414 >8045 >8045 ESE 805 945 3701 4505 >8045 >8045 i SE 1006 3822 3862 5149 > 804 5- 4505 SSE 1b49 2079 1609 >8045 >8045 >8045 S 1332 1765 1609 2414 >8045 >8045 ! SSW 1241 1804 4183 5792 5632 3218 SW 1320 1609 1609 1609 5632 1931 WSW 1394 2518 2253 3218 5471 >8045 j W 951 1804 2896 2896 >8045 5632 WNW 1021 2765 2253 2253 2253 7562 NW 814 3267 6597 >8045 >8045 >8045 l NNW 674 768 >8045 4827 5149 5149 ) t0 v 2-79 )
0 8 9 9 9 9 9 9 9 9 9 0 0 0 0 9 8 0 0 0 0 0 0 0 0 0 0 1 1 1 1 0 0 5 - - - - - - - - - - - - - - - - 4 E E E E E E E E E E E E E E E E 9 8 5 1 7 5 5 7 6 5 2 6 7 3 5 4 1 7 6 3 1 2 6 6 4 2 5 5 1 7 4 1 0 8 8 9 9 9 9 9 9 9 9 0 0 0 9 9 8 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 0 5 - - - - - - - - - - - - - - - - 3 E E E E E E E E E E E E E E E E 6 1 0 4 4 5 2 4 5 5 4 9 5 0 4 0 2 1 9 4 2 3 9 9 6 3 7 7 2 1 6 2 0 8 8 8 9 9 9 8 8 8 9 9 9 0 9 8 8
. 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 5 - - - - - - - - - - - - - - - -
2 E E E E E E E E E E E E E E E E 2 7 4 9 7 5 4 5 0 4 2 3 2 6 0 2 4 1 1 6 3 5 1 1 1 5 1 1 4 1 1 3
)
S E L I 0 8 8 8 8 9 8 8 8 8 8 9 9 0 9 8 8 M . 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 ( 5 - - - - - - - - - - - - - - - - E 1 E E E E E E E E E E E E E E E E S E 4 4 7 4 5 1 9 9 1 0 4 6 2 3 0 6 A S . . . E A 8 3 2 1 7 1 2 2 2 1 2 2 9 3 2 6 E ) E E 3 L R w E w R T S M 5 7 8 5 8 8 8 8 8 3 8 9 9 9 9 8 7 N U / M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A D C O 7 - - - - - - - - - - - - - - - - L U E R E E E E E E E E E E E E E E E E P H S F 2 7 6 6 0 8 4 6 7 6 5 1 7 7 3 7 I ( . 2 R T E
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L C U A C L T U 3 A S 5 7 7 7 8 8 8 7 7 7 8 8 9 E H 8 V I 0 0 0 0 0 0 0 8 8 7 7 L 0 0 0 0 0 0 0 0 0 B 9 D 4 - - - - - - - - - - - - - - - - H 1 Q E E E E3 E E E E E E E E E E E E A A / D 5 8 4 0 6 5 5 2 2 4 5 9 T 8 1 6 J R X N . O E I 4 1 1 7 4 5 1 1 1 5 1 1 5 1 1 3 R T E H T R G H A A U U R O Q E D 5 7 7 7 7 8 7 7 7 7 8 8 8 9 8 7 7 V 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T A 3 - - - - - - - - - - - - - - - - S E E E E E E E E E E E E E E E E I 4 5 8 4 3 1 l 2 7 2 2 1 8 8 7 l 6 2 1 1 7 1 2 2 1 7 2 2 8 2 1 5 5 6 7 7 7 7 7 7 7 7 7 8 8 8 3 7 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 - - - - - - - - - - - - - - - - E E E E E E E E E E E E E E E E 0 9 8 0 5 2 4 5 7 1 2 5 5 5 8 3 1 3 2 7 1 2 4 3 2 1 3 3 1 4 2 8 5 6 7 7 7 7 7 7 7 7 7 8 7 8 7 7 6
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)
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E 1 E E3 E 5E 7 E E E E E E E E E E E1 E S E 7 8 8 3 8 6 6 5 A S l 2 0 7 E A 1 3 1 7 5 7 2 3 3 8 2 1 1 3 5 1 L E E ) L R 2 E w R T S w 5 0 0 1 1 1 1 1 0 0 1 2 2e2 1 0 8 N U M M 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A O / O 7 - - - - - - - - - - - - - - - - L U 1 R E E1 E 8E E4 E 8 E 5E E3 E 2E E1 E 7 E E E P N ( F 3 7 6 3 0 6 3 3 I . .
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O TABLE 2.C-4 1 1 TROJAN NUCLEAR PLANT j 157 QUARTER 1983 CONTINUOUG RELEASE l AVERACE X/O VALUES (DEC/Ma*3), DEPOSIT 10N (1/M**2) a PLukC DCPLETION FACTOR Af CFFEITE EXPODURE L CC A T I QtJS NCAREST NCAREST NE Aft EG7 SECTOR WINO ESTE NEARTST NCARECT MEAT M!LK MILK DIR. DIR. DOUNDARY RESIDEf4CC GARDEN A fJI M A L COW COAT N S X/O 1.4E-0G 1.3E 0C 4.0E-07 4.DC-07 3.9C-07 4.0E-07 D/G 7.9E-08 7.4E-08 1.1E-09 1 1E 09 1.1C-09 1.1C-09 PDF 0. Da 0.92 0.75 0. 75 0.75 0.75 NNE SSW X/G 5.4E 0G 7.6E 07 4.7E-07 4.4E-07 4 4E 07 4.4E-07 D/C 1.6E-08 1.6E-09 9 2E-10 8 SE-10 8 SE-10 8.5E-10 PDF 0.92 0. 84 0.82 0.82 0. 02 0.32 NE SW X/0 3.7E 0G 6.2E-07 2.3E-07 2.3C-07 1.1C-07 1.9C-07 D/C 6.6E 09 8.6E-10 2 GE-10 2 GE-10 9 BC-11 2.0C-10 PDF 0. 91 0. 84 0.80 0.80 0.75 0.78 ENE WSW X/0 3.6E 06 2.5E-07 2.6E-07 6.9E 07 7 6C-08 7.6C-08 D/G L.1E-09 2.7E-10 2,SE-10 8 4E 10 6,2C 11 6.2C-11 PDF 0.92 0.82 0. 82 0.85 . 0. 76 0.76 E W X/C 2.4C-0G 1.4E-0G 3.7E-07 3.7E-07 3.4C-08 3.4E 08 D/G 5.3E 09 3.QE-09 6.3E-10 6 3E-10 3.7C 11 3.7E-11 PDF 0. 92 0.90 0.85 0.85 0.75 0.75 ESE WNW X/G 2.4E-06 1.9E-0G 2.4E-07 1.8E 07 4.9C-08 4.9E-08 D/G 5.4E 09 4.1E-09 3 4E-10 2 4E 10 5 DE 11 5.DC-11 PDF 0. 91 0.90 0.82 0. 50 0.75 0.75 SE NW X/0 3.1E-0G 4.8E-07 4.7E-07 2.7E-07 1.3E-07 3.8C-07 D/G 7.2C-09 7.3E-10 7.2E-10 3 6E 10 1.5C-10 5.5C-10 PDF 0.90 0.81 0. 81 0.79 0. 75 0.80 SSE NNW X/0 1.3E-06 9.1E-07 1.3E 0G 1.3C-07 1.3C-07 1.3E-07 D/G 3.9E-09 2.6E-09 4.1E 09 2.4E-10 2 4 E 10 2.4E-10 PDF 0.87 0.86 0.87 0.75 0.75 0.75 S N X/C 1,4E-OG 9.0E-07 1.0E-06 5.8C-07 1 0E-07 1.0E-07 D/C 5.4E 09 3.3E-09 3.9E-09 1 9E-09 2 3E-10 k.3C-10 PDF 0.89 0.87 0. 88 0. 85 0.75 0.75 S5W NNE X/O 6.1E-07 3.5E-07 1.1E-07 7.0E-08 7.2C-08 1.5E-07 D/G 1.4E-09 7.7E-10 1.8E-10 1.0C-10 1.0E 10 2.8C-10 PDF 0.89 0.87 0. 81 0. 78 0. 78 0.83 SW NC X/G 2.1E-07 1.6E-07 1.6E-07 1.6C-07 2.2C 08 1.1E-07 D/C 4.2E-10 3.CE-10 3 DE-10 3 OE-10 2 SE 11 2.DC-10 PDF 0.89 0.87 0.87 0.87 0. 78 0.86 WSW ENE X/C 2.7C 07 9.6E-08 1.1E-07 6.7E-08 2.2C 08 1.3C-08 D/o 3.4E 10 1.0E 10 1.3E-10 6 7E 11 1 9C 11 9 4C-12 PDF 0.88 0.85 0. 85 0.83 0. 78 Q. is W E X/C 2.6E-07 7.6E-08 3.7E-08 3 7E-08 .DC-09 8.8C-09 D/G 5.5E-10 1.4E-10 6.2E-11 6 2C 11 a SC-12 1.3E-11 PDF 0.90 0.87 0. 84 0. 84 0. 75 0.78 WNW ESE X/0 E.5E-07 1.0E-07 1.4E-07 1 4E-07 1.4E-07 1.7E-08 D/G 1.4E-09 2.QE-10 2.9E-10 2 9E-10 2.9C-10 2.3E*11 PDF 0.90 D. 84 0.85 0.85 0.85 0. 75 NW SC X/c 3.7E-0G 3.8E 07 1.3E-07 9.SC-08 9 SC-08 9.5C-08 D/G 2.3E-08 1.7E-09 4.6E-10 3 2C-10 3.2C-10 3.2E-10 PDF 0. 01 0 83 0.77 0.75 O. 75 0.75 NNW SSE X/c 1,2E 05 9.9E 06 3.1E-07 6.4E-07 5.8E-07 5.8C-07 D/o 8.5E-On 6.9E 08 1.1E-09 2 7C-09 2 4C-09 2.4E-09 PDF 0 92 0 92 0.75 3. 79 0.79 0.79 9 2-82
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NCAREST NCAREGT NEAREST SECTOR WIND GITE NEARCST NEAREST MCAT MILK MILM ' DIR. DI R , BQuNDARY RELIDENCC GARDEN AfJIMAL CCW CCAT j N S X/O 1.3E.OG 1.2E-05 3.8E.07 3.8C-07 3.7E.07 3.8E-07 D/G 7.CE*08 6.6E-08 1.0E.09 1.0E.09 9 7C.10 1.0C-09 PDF 0. 92 0. 92 0.75 0. 75 0.75 0.75 NNE SSW X/O 5.3E*0G 7.5E.07 4.6C.07 4.4E-07 4.4E.07 4.4E-07 D/G 1.5E.08 1.5E.09 8.4E-10 7.8E 10 7.8E.10 7.8C-10 PDF O. 92 0.84 0. 82 0.82 0.82 0.82 NE SW X/0 2.GE.OG 4.8E.07 1.8E.07 1.8E.07 8.2E.08 1.4E.07 D/0 G.6E-09 8.6E.10 2.6E.10 2.6C-10 9.8E-11 2.0E 10 PDF 0 91 0.84 0.80 0.80 0. 75 0.78-ENC WCW X/c 3.1E 0G 2.1E-07 . 2.1E*07 5,7C 07 G.3C 08 6.3E.08 D/0 5.0E-09 2.2E.10 2.3E.10 6 9C-10 5.1E.11 5.1E-11 PDF 0. 92 0. 82 0. 82 0.85 - 0.76 0.76 E. W X/G 2.9E-0G 1.7E-0G 4.5E-07 4.5C-07 4.1E.08 4.1C-08 D/0 PDF
' 6.3E.00 O.92 3.6E-09 7.5E.10 7.5C 10 4.5E.11 4.5E.11
- 0. 90 0.85 0.85 0.75 0.75 ESE WNW X/O 1.2E OG 9.8E.07 1.2E-07 8.8C-08 2.3E 08 2.3E-08
/\ D/0 3.5E*09 2.7E.09 2.2E.10 1.6E-10 3.3E-11 3.3C-11
( PDF 0. 91 0.90 0.82 .O.80 0.75 0 75 GE NW X/O 2.4E-06 3.7E.07 3.6E.07 2.1E-07 1.DC-07 2.9E-07 D/O 6.8E.09 6.9E-10 6.8E410 3.5C.10 1.4C.10 5.2E.10 PDF 0.90 0.81 0. 81 0. 79 0. 75 0.80 SSE NNW X/O 1.2E-0G S.3E 07 1.2E.06 1.1C.07 1.1E.07 1.1E 07 D/0 4.6E 09 3.1E.09 4.8E-09 2.8E 10 2.8E-10 2.8E.10 PDF O.87 0.86 0. 88 0.75 0. 75 0.75 3 N X/0 1.2E*06 8.3E 07 9.5E.07 5.3E 07 9.1C-08 9.1E.08 D/0 6.7E.09 4.1E.09 4.8E-09 2.4C 09 2.9C-10 2.9E-10 PDF 0.89 0. 87 0.88 0.85 0.75 0. 75 SSW NNE X/O 1.0E.OG 6.0E-07 1.9E.07 1.2C-07 1.2E.07 2.7E-07 D/O 2.2E 09 1.2E-09 2.7E.10 1.5E 10 1.GE 10 4.2C-10 PDF 0.89 0.87 0. 81 0. 78 0. 78 0.83 SW NE X/O 2.0E 07 1.5E-07 1.5E.07 1.5E-07 2.2E.08 1.1E-07 D/0 4.GE.10 3.3E-10 3.3E-10 3.3E.10 3.1E.11 2.2C-10 PDF 0.89 0.88 0.88 0.08 0.78 0.86 WSW ENE X/O 1.2E.07 3.9E-08 4.7C 08 2.7E-08 8.5E.09 4.7E.09 D/0 3.3E 10 9.7E-11 1.2E.10 6 4E-11 1.8E-11 8.9C 12 PDF 0,88 0.85 0.85 0. 83 0.78 0.75 W E X/O 1.8E-07 5.1E-08 2.5E-02 2.5E 08 3.4C-09 5.90-09 D/0 4.8E 10 1.2E.10 5.5E.11 5.5C-11 5.9E.12 1.1E-11 PDF 0.90 0.87 0. 84 0.84 0.75 0. 78 WNW ESE X/0 7.8E.07 1.5E.07 2.0E.07 2.0E-07 2.0E-07 2.5E.08 D/0 1.8E.09 2.7E.10 3.8E-10 3.8E.10 3.8E.10 3.0E-11 PDF 0.90 0.84 0.85 0.85 0.85 0.75 NW SE X/O 3,9E-0G 4.0E-07 1.3E-07 1.0C-07 1.0E-07 1.0E.07 D/G 2.6E-08 1.9E-09 5 OE.10 3.5E.10 3 SE-10 3.5E 10 PDF 0. 91 0.83 0.77 0. 75 0. 75 0. 75 NNW SSE X/0 1.2E-05 9.7E-06 3.0E.07 G 3C-07 5.7E 07 5.7E.07 D/0 8.5E 08 6.9E-08 1.1E-09 2 7E-09 2.4E.09 2.4E 09 PDF 0. 92 0. 92 0.75 0.79 0.79 0.79
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1 l p Y TABLE 2.C-12 TROJAN NUCLEAR PLANT 2ND QUARTER 19E3 20NTINUOUS RELEAGE l AVERAGE X/0 VALUEG (GEC/M8m3), DEPOGITION (1/Ma*D) & PLUME DEPLETION FACIOR AT OFFSITE EXPOSURC LOCAT30NS W SECTOR NEARECT NEAREST NEARECT WIND GITE NEAREST NCARECT NEAT MILK MILK DIR. DIR. DQuNDARY REGIDENCE GARDEN ANIMAL COW COAT N S X/0 G.5E 00 6.1E-0G 1.8E-07 1.80-07 1.8E-07 1.8C-07 D/G 2.3E-08 2.2E-08 3.3E-10 3.3C 10 3.2E-10 3.3E-10 PDF 0.92 0.92 0. 75 0.75 0.75 0.75 NNC SGW X/O 5.6C-0G 7.9E-07 4.9E-07 4.6C 07 4.6E=37 D/0 1.5E 08 4.6E-07 1.5E-09 8.2E-10 7.6C-10 7.6C-10 7 EE-10 PDF 0.92 0.84 0. 62 0. 02 0.82 0.82 NE SW X/O 4.2E-0G 7.2E-07 2.7E-07 2.7E-07 1.3E-07 D/0 2.2E-07 7.1E-09 9.3E-10 2.8E-10 2.8C-10 1.1C-10 2.1E-10 PDF 0.91 0.84 0.80 0.00 0.75 0.78 ENE WSW X/O 2.9E-0G 1.9E-07 1.9E-07 5.1C-07 5.7C-00 D/G 6.4E 09 5.7C-08 2.8E-10 2.9E-10 8.9C-10 6.6E-11 6.6E-11 PDF 0.92 0.82 0. 82 0.85 - 0.76 0.76 E W X/0 2.4E-0G 1.4E-06 4.0E-07 4.0C-07 3.7C-08 D/O 6 4E-09 3.7E-08 3.6E-09 7.6E-10 7.6C-10 4.5E 11 4.5E-11 PDF 0.92 0.90 0.85 0. 85 0.75 0.75
-+s CSE WNW X/G 4.0E-0G 3.PE-05 3.9E-07 3.0C-07 7.6E-08
[ \ D/O 1.4E-08 7.6E-08 1.1E-08 9.1E-10 6.4E 10 1.3E-10 1.3E 10 ( ) PDF 0. 91 0.90 0. 82 0.80 0.75 0.75 v SE NW X/O 3.3E-0G 4.8E-07 4.7C-07 2.6C-07 1.3C-07 D/G 1.6E-08 3.8E 07 1.7E-09 1 GE-09 8.3C 10 3.4E-10 1.2E-09 PDF 0.90 0.81 0.81 0.79 0.75 0.80 SSE NNW X/O 1.3E-06 8.9E-07 1.3E-06 1.2E-07 1.2E-07 1.2E-07 D/O { 1.0E-08 7.0E-09 1.1E-08 6.SC-10 6.5E-10 6.5E-10 PDF O. 87 0. 8G 0.88 0.75 0.75 0.75 S N X/O 1.4E-06 9.0E-07 1.OE-06 5.6C-07 D/O 9.3E 08 9.3E-08 1.6E-08 1.OE-08 1.2E=08 5.8C-09 7.0E-10 7.0E-10 PDF O.80 0.87 0. 88 0.85 0.75 0.75 j BSW NNE X/0 1.0E-06 5.9E-07 1.7E-07 1.0E-07 1.1E-07 D/O 2.5E-07 ! 7 9E-09 4.2E-09 9.7E-10 5.4E-10 5.7E-10 1.5E-09 j FDF 0.89 0. 87 0. 81 0. 78 0.78 0.83 i l GW NE X/0 3. 3 E- 07 2.4E-07 2.4C-07 2.4E-07 3.0C-08 1.7E-07 l D/G 1.9C-09 1.4E-09 1.4E-09 1.4E-09 1.3E-10 9.2E-10 PDF 0.89 0.88 0.88 0. 88 0.78 0.86 WGW ENE X/G 3.3E-07 1.1E-07 1.3E-07 8.0C-08 2.7E-08 1.5E-08 D/O 1.4E-09 4.2E-10 5.1E-10 2.8C 10 7.7E-11 3.9C-11 PDF 0.88 0.85 0.85 0. 83 0.78 0.75 W E X/O 1.9E-07 5.4E-08 2.GE-08 2.6C-08 3.7E-09 D/G 6.3E-09 8.2E 10 2.1E-10 9.2E 11 9.2E 11 1.0E-11 1.9E-11 PDF 0.90 0.87 0. 84 0. 84 0.75 O.78 l WNw ESE X/O 5.8C-07 9.9E-08 1.4E-07 1.4E-07 D/G 1.4E-07 1.4E-08 l 3.0E-09 4.3E-10 6.2E-10 6.2E-10 6.2E 10 9.9E-11 1 PDF 0.90 0. 84 0.85 0.85 0.25 0.75 NW SE X/0 1.7E 0G 1.5E-07 5.0E-08 3.7C-0a 3.7E-08 3.7E-08 D/O 1.6E-08 1.2E-09 3.0E-10 2.1C-10 2.1C-10 2.1E 10 PDF 0. 91 0.83 0.77 0.75 0.75 0.75 NNW SSE X/0 S.4E-0G 4 4E-9G 1.3C-07 2.7C-07 2.4E-07 2.4C-07 D/O 3.7E*08 3.0E-08 4.7E-10 1.2C-09 1.0E-09 1.00-09 PDF 0. 92
- 0. 92 0.75 0.79 0.79 0.79 m
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. 2 . . 8 6 3 1 9 8 3 6 1 1 5 1 6 1 8 4 9 5 9 0 0 0 0 0 9 9 9 9 0 0 1 0 0 9 0 1 1 1 1 1 0 0 0 0 1 1 1 1 1 9 2 - - - - - - - - - - - - - - - -
E E E E E E E E E E E E E E E E 2 0 1 0 l 7 5 2 3 1 9 3 4 9 7
. . . . . 2 . .
1 7 3 2 2 7 1 2 2 1 1 1 3 1 7 1 5 9 9 0 0 0 9 9 9 9 0 0 0 0 0 9 9 0 0 1 1 1 0 0 0 0 0 1 1 1 1 0 0 1 - - - - - - - - - - - - - - - - E E E E E 5 E E E E E E E E E E 9 9 9 2 0 2 9 4 7 6 5 2 2 8 4 6 2 1 9 7 6 2 3 5 5 2 5 4 1 4 2 4 5 8 8 9 9 9 8 8 8 8 3 9 9 9 ? 8 8
- 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 - - - - - - - - - - - - - - - -
E E E E E E E E E E E E E E E E 2 3 6 8 4 3 5 6 8 2 8, - 7 0 9 6 9 1 1 6 4 3 1 2 3 3 l 3 3 1 3 1 2 H RD OI Tl E E E E U u W W PC H E t r S E S 5 H s H J H EE N H H E E E S S S 5 S u u U 'N H CR EI RD S 1 l l1ll l l
i Ui ks TABLE 2.C-16 TROJAN NUCLEAR PLANT 2ND QUARTER 1983 HAfCH RELEAGED AVERACE X/O VALUES CECC/Ha*3). D E P O CI T I C fJ C .1/ M a
- 1' ) 8 PLUMC DEPLETION FACTCR AT OFFSI1C EXPCSURC LOCATIONS NCAREST NEAHEST NEARCCT GECTOR WIND SITE NEAREST NEARECT MCAT MILV MILK DIH. DA R. DOUNDARY RESIDENCC GARDEN ANIMAL CCW GCAT N- S X/O 6.7E 06. 6 3E.06 1.9E-07 1.DC=07 1.80 07 D/0 1.9C.07' 2.5E 08. 2.3E.08 3.5C 10 3.5C*to 3.4C.10 3.5E.10 PDF 0.92 0. 92 0.75 0.75 0.75 0.75 NNC -SSW X/0 5.6E=06 7.9E-07 4.9E.07 4.6E 07 4.6C.07 4.6E.07 D/0 1.5E-08 1.5E.OU 8.7E.10 8 1E 10 8. a f:.10 8.1E.10 PDF 3.92 0. 84 0, 82 0,82 0.82 0.82 NE CW X/O 3.1Z 00 5.4E=07 2.0E-07 2.0E.07 9.4C-08 D/O 6.1E.09 1.GE-07 8.0E.10 2.4C.10 2.4E.10 9.1E.11 1.8E.10 PDF' O.91 0. 84 0.80 0.80 0.75 0.78 ENE WSW X/O 2.42-06 1.SE=07 1.GE.07 4.2E.07 4.SC.08 4.EC-08 D/G '5.9E*00 2.0C 10 2.7C.10 8.1E.10 6.00 11 6.0C-11 PDF O. 92 0. 82 0.82 0.85 .
0.76 0.76 C W. X/0 1.8E.0G- 1.1E.0G 2.9C.07 2.DC.07 2.7C.08 D/G 5,0E 2.7E-08 2.9E.09 6.0C.10 6.0C-10 3.EE.11 3,GE.11 PDF 0. S2 0.90 0.85 0.85 0.75 0.75 CSE WNW X/O 4.0E 06 3.2C 0G 3.9C.07 2.9C.07 7.6E-08 7.6E-08 [D D/S PDF-1.4E.08 9.91 1,1E.08
- D. 90 8.9E.10 0,82 6.3E.10
- c. 80
- 1. a
' E .10 D. 75 1.3E.10 O.75 SE NW X/0 3.1E*0G 4.5C.07 4.4E.07 P..EE-07 1.2E.07 3.5E=0F
-D/0 1.6E.08 1.6E-09 1.6E 09 6.1E.10 3,3E.10 1.2E.09 PDF 0.90 0. 81 0. 81 0. 79 0. 75 0.80
, SSC NNW X/O j.2F.06 8.3E.07 1.2E.06 1.1E.07 1.1C.07 1.1E 07 D/G 1.04 08 7.0E 09 1.1C.08 6.5E.10 6.5E-10 G.5E-10 PDF f. 87 0,86 0.88 0.75 0.75 0.75 5 4 X/G 1.3E.0G 8.fE=07 9.7E.07 5.3E.07 8.7C 08 8.7E=08 n/O 1.6E-08 9.8E.09 1.1E.08 5.7C 09 6.8E.10 G. 8E .10 PDF O.89 0. 87 0.88 0.85 0.75 0.75 SSW NNE X/0 1.0E.06 6.0E-07 1.7C.07 1.1E=07 1.1C.07 2.5C=07 D/0 8.2E.09 4.3E 09 1.0C.09 5.6E.10 5.9C-10 1.EE-09 PDF 0.89 0. 87 0. 81 0.78 0.78 0.83 SW NE X/G 2.2E-07 1.6E.07 1.6C.07 1.GE.07 2.0C.08 D/G 1.7E-09 1.1E=07 1.2C 09 1,2C-09 1.23 09 1.1Es 10 8.1E.10 PDF 0.89 0. 88 0. 88 c. 88 0.78 0.86 WSW ENE X/c 3.2E.07 1.1E.07 1.3C 07 7,8E 08 2.EE-08 1.5E 08 D/0 1.3E 09 3.9C.10 4.7C.10 2.6C-10 7.1E.11 3.EE.11 PDF 0.80 0.85 0.85 0.83 0.78 0.75 W E X/0 1.8C-07 5.2E.08 2.6C 08 2.GCr08 3.6C.09 D/G 7.8E.10 6.2E-09 2 DC-10 8.8E.11 8.8Ecli 9.5E-12 1.8E.11 PDF 0. 90 0. 87 0. 84 0.84 0.75 0.78 WNW ESE X/0 5.2E-07 9.OE.08 1.2E.07 1.2E-07 1.2E 07 1.3E 08 D/G 2.6E-09 3.8E.10 5.9C 10 5.4C 10 5.4E 10 4.3E-11 PDF 0.90 0. 84 0.85 0.85 0.85 0.75 NW SC X/O 1.SE.0G 1 4C.07 4 3C.08 3.2E 08 3.2E.00 3.2E 08 D/G 1.5E.08 1.1E.09 3.DC-10 2.1E.10 2.1E.10 2.1 E .10 PDF 0. 91 0. 83 0.77 0.75 O. 75 0.75 NNh SCC X/O 5.2C-06 4 3E.00 1.2C 07 2.6C 07 2.4C.07 2.4E-07 D/0 3.9E 08 3.2C-08 5.0C-10 1.2E.09 1.10 09 1.1E-09 PDF 0. 92 0. 92 0.75 0.79 0.79 0.79 2-103
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=
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.J l I i i i i i I i 1 M e >=
>= A E 8 et @ M @ e.e aw M w=e ea ** *=s s=* 1 C >= >= Q. E i *C @ ed e M M em e= na ea ** - 3 C 50 C Q I >= 53 Q Q =Mw a U #S O as c3 La o o o C3 o A i >=
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& Q l >= Q W Z l W Z l
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WeQ o i WmQ u i ; eWd Z l so W .J Z l j af a: O W aC C4 o W + iD O Z D 1 o @ CS o o o cm o o a 1 go 3 = 'O 1 oOooooeooo i l M (n Cr i i WW Cf a
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>= Q '8 >= Q l-W Z l W Z l 80 M i #G M i 3 3 W o c cs cs M cs o o o o o I ew W cs o cs o c cs o c o c o 1 o k Z l L Z l 6= c 8 >= c t WZ 8 WZ l WA Z l WA Z l WWE C 3 kWC C a M M 4oe >= W cs M es=e@an @ edo o o a @ ( o no >= W e eg o Cseweg e o o o e i N
>= *N D = 0M >= *N D Z e IM e 80 Z $ =J M
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Z w e= M Z ooM@NNPewooo1@ Z 6* W M Z ococcoNoocol N 044 Q lN C 4 *C Q l I a Q >= 6 O >= 1 WQQ U f WQQ U i eW a Z l m W =J Z l ec r.g C W <C r4 o W
$Q 3 = D i o O o o o cD o o e o 1 (Q 3 Z 3 i es to o o o o cs e o o I in W Cf 1 I dA CF 3 i
>= at W sal I AOe e N oth.a.o.e.o.o.o O i )m= =C W W I aA N. o 40. cs e. o. e. o o. o 1 e . .
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RD) - 5705000000 0-00112357030- L I L 1I TI T FES- 1 t 0 0 1 1 2 3 5 7 0113 0._- A IMH FES 1 t 11 .- A E/ - l - - - - - - - - - - _ T L T E/ - l - - - - - - - - - I BDD 1 T P t.- A4161111111l HS( - C3570500000> - 1 3_ 0 I TPM A4161111111l - O T i BDD NS( C3570500000> - T AtN . - TII I O 0001123570 YE 3ANN TII I O 0001123579 SWW J _ 1 - SWW J - 1 - i ,' (Il lll
f 0 0 0 0 0 0 0 0 0 0 1 1 1 1 0 0 5 - - - - - - - - - - - - - - - - 4 E E E E E E 1E E E E E E E E E E 7 0 6 9 8 9 2 3 9 5 8 7 9 6 0 9 1 8 4 3 4 6 6 4 1 6 3 2 4 1 3 0 8 8 8 9 9 9 9 9 9 9 0 0 0 0 9 9 0 0 0 0 0 0 0 0 0 0 1 1 1 1 0 0 5 - - - - - - - - - - - - - - - - 3 E E E E E E E E E E E E1 E E E E 4 4 2 8 4 8 8 8 7 3 5 8 8 2 2 1 1 1 6 4 6 9 8 6 2 9 5 3 6 2 4 0 8 8 6 8 9 8 8 8 9 9 9 0 0 9 9 9 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 5 - - - - - - - - - - - - - - - 2 E E E'- E E9 E 1E E E E E E E E E E 1 2 9 1 6 4 7 3 5 2 2 1 4 7 2 2 1 1 6 1 1 1 9 4 1 9 6 1 3 6
) -
S E L . I 0 8 8 8 8 8 8 8 8 8 9 9 9 9 9 9 8 M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 ( 5 - - - - - - - - - - - - - - - - E 1 E 2 3 7 E E E E1 E E E E E E E E E E E 4 2 2 9 0 0 1 0 3 2 6 4 S A 4 4 3 2 1 2 3 2 2 9 3 2 1 2 6 1
) E 3 L N E M R .
T M 5 7 7 8 8 8 8 8 8 4 8 9 9 9 9 8 8 N 3E / M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A 8S C O 7 - - - - - - - - - - - - - - - - L 9A E R E E1 E E E E E E E E E E E E E E P 1E S F 1 5 5 6 9 7 9 4 5 7 7 6 8 7 6 8 L ( 1 R RE E 1 1 9 5 3 5 8 7 5 2 8 5 3 5 1 3
- A ER S C C.
E T E N O'. 2 E L L RS C AU U UO N QU U L A V A T S 5 I 7 0 7 0 7 0 0 7 8 0 7 70 7 07 8 8 8 9 3 8 8 0 0 0 0 0 0 0 0 0 N D 4 - - - - - - - - - - - - - - - - B N DI 9 E E E E E1 E E E E E E E E E E E A A RT / D 2 2 9 5 2 8 7 2 2 9 2 6 2 6 6 T J IN X N O HO I 2 2 1 1 7 1 1 1 1 5 1 1 7 1 3 7 R TC E N T G N A N R O E D 5 7 7 7 7 . 7 70 7 0 70 7 80 8 0 8 08 80 8 0 7 V 0 0 0 0 0 0 0 0 A 3 - - - - - - - - - - - - - - - - E E1 E E E E E E E E E E E E E E 1 7 6 4 5 9 4 7 6 0 8 1 9 6 1 3 3 2 1 1 2 2 2 1 7 3 1 1 1 5 1
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5 7 7 7 7 7 7 7 7 7 7 8 8 8 8 8 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 - - - - - - - - - - - - - - - - E 9 8 3 E E E E0 E E E E E E E E E E E 9 8 6 0 8 3 5 0 9 2 2 8 4 4 4 3 2 4 5 4 2 1 4 3 1 3 9 1 5 6 , 6 6 7 7 6 6 7 7 7 7 8 8 8 7 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 - - - - - - - - - - - - - - - - E 0 E1 E 1E E E 1E E E E E E E E E E 2 2 3 7 1 7 2 3 1 2 5 3 1 1 1 9 7 1 1 8 6 2 1 9 6 9 2 4 5 6 6 6 6 6 6 6 6 6 6 7 7 7 7 6 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 - - - - - - - - - - - - - - - - E E E E E E E E E E E E E E E E 1 3 5 3 4 7 7 5 2 4 4 8 2 9 3 2 5 5 5 4 3 5 5 4 3 1 6 5 4 5 1 2 (%) N RG OI TT E E E E N H H H PC N E N S E S S H S N H N EE N H N E E E S S S S S H W H N N CR EI RD [S l
2 2 3 3 3 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 - - - - - - - - - - - - - - - - 4 E 3 6 E E 1E E8 E E E E E E E4 E E 0E E 6 6 2 7 9 6 8 3 3 7
'6 3 3 1 1 4 9 1 1 3 1 4 2 6 3 5 0 l 2 2 2 2 2 1 1 1 2 2 3 3 2 2 2 I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 - - - - - - - - - - - - - - - -
3 E 0 E8 E 0E E9 7E 4 E E E E E E E E E E 5 8 3 3 6 3 5 0 4 2 1 5 5 2 2 7 1 2 2 6 1 7 4 1 5 9 0 1 1 2 2 2 1 1 l 1 1 2 2 3 2 1 1 1 1 1 1 1 1 1 I 1 1 1 1 1 1 1 1 5 - - - - - - - - - - - - - - - - 2 E E1 E 2E3 E E 9 E4 E E E E E E E E E 9 8 2 3 2 0 4 4 9 0 7 1 1 9 5 4 1 2 5 4 1 3 1 8 1 1 1
)
S E L I 0 l 1 1 l 1 1 1 0 0 l 2 2 2 2 1 1 M I 1 1 I 1 1 1 1 1 I 1 1 1 1 1 1 ( 5 - - - - - - - - - - - - - - - - E 1 E 6 7 3 E E E E3 E 2 4 E E E E E E1 E E E E 8 3 9 5 4 1 6 5 2 S A 4 2 2 1 1 3 6 1 1 2 7 3 2 4 2 4 E
) L 2 E M R .
T E 5 0 1 1 1 1 0 0 0 0 1 1 1 , 2 l 1 0 N 3E M M 1 1 1 1 1 1 1 1 A L 8S 9A
/
1 O 7 R E E E 2E 2E8 E E E E E
- - - - 41 E E E E E E 1
1 1 I 1 1 9 P 1E ( F 5 4 1 R RE L S E
- l. l. 0 3 0 4 1 5 S 7 3
- 1 8 7 4 3 1 2 4 3 9 2 1 6 1 7 1 A ER E C C. E T U N 2 L RS L A C AU A T E U U0 V S 5 0 0 0 0 1 0 0 9 0 0 1 1 1 1 0 0 L N QU I 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 B N Q D 4 - - - - - - - - - - - - - - - -
A N DI / E E1 E E E0 E E E E E E E E E E E T A RT D D 6 8 4 7 3 0 2 2 8 6 6 6 9 3 J IN N O HO E I 3 2 1 1 9 2 5 1 8 2 5 2 1 3 1 3 R TC G H T A H R H E O V D 5 0 0 0 0 0 0 0 9 9 0 0 1 1 1 0 0 A 1 1 1 1 1 1 1 0 0 1 1 1 1 1 1 1 3 - - - - - - - - - - - - - - - - E E E E E6 E E E E E E E E E E E 7 2 8 9 8
- l. 6 3 5 0 1 5 2 3 2 5 3 2 1 1 5 9 1 1 3 1 4 2 6 3 5 5 9 0 0 0 0 9 9 9 9 0 0 1 1 0 0 0 0 1 1 1 1 0 0 0 0 1 1 1 1 1 1 1 2 - - - - - - - - - - - - - - - -
E 0 E9 E 0E E5 E 6 E E3 E 0E E E3 E E E E 8 3 7 4 1 0 4 C. 1 5 5 3 4 1 2 2 2 6 1 7 4 1 6 9 5 9 9 9 9 9 9 9 9 9 9 0 0 0 0 9 9 0 0 0 0 0 0 0 0 0 0 1 1 1 1 0 0 1 - - - - - - - - - - - - - - - - E E E E E E E E E E E E E E E E 5 6 6 3 3 7 2 9 7 5 9 5 7 3 9 5 2 1 1 1 1 3 5 6 5 1 4 2 1 3 1 2 5 8 8 8 9 9 8 8 8 8 9 9 9 9 9 8 8 _ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 . 0 - - - - - - - - - - - - - - - - E E 0 E E0 E 1 E E E E E E E E E E E 6 3 3 0 4 6 8 3 0 4 0
. . 2 6 1 1 1 8 8 2 3 4 3 9 3 2 1 3 1 1 N
RO _ OI TT E E E E H H H H PC N E N S E S S H S H H H EE N N N E E E S S S S S H H H N N _ CR _ EI _ RD
A . TABLE 2.C-20 7ROJAN NUCLEAR PLANT THIRD SUARTER 1983 CONTINUOUS RELEASE AVERACE M/S VALUES (SEC/ Mas 33. DEPOSITION (1/M221) & PLUME DEPLETION FACTOR AT OFFSITE EXPOSURE LOCATIONS NEAREST NEAREST NEARES7 SECTOR WIND SITE NEAREST NEAREST MEAT MILK - MILK DIR. DIR. SOUNDARY RESIDENCE GARDEN ANIMAL COW 004T N S M/S 7,0E.06 .S.5E-08 1.9E.07 1.9E.07 1.92 07 D/S 3.1E.08. 1.9E.07 2.0E.04 3.1E.10 3.1E.10 3.0E.10 3.1E.10 PLF 0.92 0. 9E 0.75 0.75 0.75 0.75
, NNE SSW M/S 6.9E=0S 9 EE.07 5.8E-07 5.tE.07 e5.tE.07 *S.+E.07 D/S 1.3E-08 1.3E.09 7.tE-10 S.SE.10 S.SE.10 S.SE.10 PDF 0. 91 0.89 0.85 0. 5E 0.81 0. 3E NE SW M/G 5.tE.06 9.SE.07 3.5E.07 3.5E-07 1.7E.07 E. SE. 07 -
D/S 9.8E.09 1.3E-09 3.9E.10 3.9E.10 1.5E.10 E.9E.10 PDF 0. 91 0.55 0.50 0.80 0.75 0. 75 ENE WSW M/S -5.SE 05 3.8E.07 3.9E-07 .1.0E 06 1.1E.07 1.1E.07 D/S 1.0E.08 9.SE.10 9.8E.10 1.9E.09 1.1E.10 PDF 0. 9R 0.82 0. SE 0.85 -1.1E.10 0.78 0.75 E W M/S 9.tE.pS- 1.SE-05 7.1E.07 7.1E-07 S.tE 08 S.tt.05 D/S '1.1E.08 S.3E.09 1.3E.09 1.3E-09 7.5E.11 7.5E.11 PDF O.91 0. 90 0.85 0.85 0.75 0.75 ESE WNW M/A- 5.7E.OS- t.5E.08 5.5E.07 9.1E.07 1.1E-07 1.1E.07
/"%\* . D/S et.3E-08 1.SE 08 1.5E-09 1.1E=09 R.EE.10 2.RE-10 t i PDF 0. 91 0.90 0.81 0.80 0.75 0.75
-- SE NW 4/e 9.EE-OS 8.OE-07 5.9E.07 3.3E.07 1.SE-07 9.7E 07 D/S 3.1E.08 E.1E.09 E.1E.09 1.1E 09 t.tE.10 e1.3E-09 PDF 0. 90 0.81 0.51 0.79 0.75 0.50 SSE NNW M/S 1.5E.06 1.1E-06 1.SE.06 1.tE.07 1.tt.07 1.tE-07 D/S 1.3E=OS 5.9E-05 .1.tE-08 8.SE.10 .5.2E.10 S.1E.10 PDF 0.87 0.56 0.85 0.75 0.75 0.75 S .N M/S 1.5E.06 9.8E.07 1.1E.08 S.1E.07 9.8E-08 D/S 9.sE.05 1.SE 08 '9.5E.09 1.1E.08 .5.7E.09 S.5E.10 S.8E.10 PDF 0.49 0.87 0.88 0.55 0.75 0.75 SSW NNE M/S 7.1E 07 v.EE 07 1.EE.07 7.3E 08 7.SE.08 D/S 9.8E.09 1.SE.07 1.EE.09' 5.9E.10 3.3E.10 3.5E.10 9.tE.10 PDF 0.89 0.87 0.81 0.78 0.78 C. 83 SW NE M/S 3.1E.07 1.3E.07 1.3E.07 1.3E.07, 3.OE.08 1.SE.07 i D/S 1.5E 09 1.1E.09 1.1E.09 1.1E 09 1.0E.10 7.1E.10 PDF 0.59 0.88 0.88 0.88 0.78 0.85 WSW ENE M/S 1.SE.07 8.7E 08 1.0E.07 S.0E.08 1.9E.08 1.1E.05 D/S 7.9E.10 1.tE.10' 3.9E.10 1.5E-10 9.3L.11 E.1E.11 PDF 0.88 0.85 0.85 0.83 0.78 0.75 W- E M/S 3.3E-07 9.5E.08 9.SE-08 9.SE.08 S.5E.09 1.1E.08 D/S 1.1E.09 R.8E.10 1.EE-10 1.1E.10 1.3E.11 E.5E.11 PDF 0. 90 0.37 0.89 0.89 0.75 0.78 WNW ESE M/S 9.1E.07 7.ft-08 1.0E 07 1.0E.07 1.0E=07 1.1E 08 D/S 1.1E.09 3.0E.10 9.1E.10 9.EE-10 9.1E.10 3.3E.11 PDF 0. 90 0.84 0.85 0.85 0.85 0.75 NW SE M/S 1.3E-OS 1.EE 07 t.1E-08 3.1E-08 3.1E.08 3.1E.08 D/G 1.1E 05 8.EE.10 1.3E.10 1.SE.10 1.SE-10 1.SE.10 PDF 0. 91 0.83 0.77 0.75 0.75 0.75 NNW BBC M/S 1.9E-OS 1.tE-OS 5.EE-08 1.tE.07 1.3E.07 1.3E.07 D/S R.1E.08 1.7E.Os 2.7E-10 S.SE.10 S.1E 10 S.1E-10 PDF 0. 9E 0.92 0.75 0.75 0.79 0.79 2-110 m____ ____ ___ _
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5 3 2 1 1 6 9 1 1 2 7 1 8 5 2 5 5 0 0 0 0 0 9 9 9 9 0 0 l 1 0 0 0 1 1 1 1 1 0 0 0 0 1 1 I 1 1 1 1 2 - - - - - - - - - - - - - - - - E E E E E E E E E E E E E E E E 3 2 5 6 5
- l. 8 9 4 0 2 l 5 0 2 2 9 5 4 3 3 1 2 3 2 4 1 3 1 1 5 9 5 9 9 9 9 9 9 9 9 9 9 0 0 a 0 9 9 0 0 0 0 0 0 0 0 0 0 1 1 l 1 0 0 1 - - - - - - - - - - - - - - - -
E E E E E E E E0 E 3E E E E E 1 E E 3 5 3 4
- l. 7 2 6 0 6 3 6 5 2 1 1 1 1 4 5 7 6 1 3 1 5 3 1 2 5 8 9 9 9 9 8 8 8 8 9 9 0 0 9 8 8 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0 0 - - - - - - - - - - - - - - - -
E E E E E E E E E E E E E E E E 4 4 3 9
- l. 6 1 9 0 1 5 l 7 7 0 6
1 9 8 8 7 2 3 4 4 7 2 8 4 2 1 1 N RO OI TT E E E E H H H H PC M E N S E S S H S N H N EE N N N E E E S S 5 S S H H H N N CR EI RD
F. . .
?
TABLE 2.C-24 TROJAN NUCLEAR PLANT
. THIRD GUARTER 1983 AVERADE M/S VALUES CSEC MS OSITION C1/ MSS 2) &
l1 PLUME DEPLETZON FACTOR AT OFFSITE EXPOSURE LOCATIONS NEAREST ' NEAREST NEAREST SECTOR WIND SITE NEAREST NEAREST MEAT MILK MILK DIR. DIR. SOUNDARY RESIDENCE CARDEN' ANIMAL COW GOAT N S :M/S +7.SE-OS 7.1E=0S 1.1E.07 1.1E-07 1.1E.0? 1.1E-07 D/S- E.0E.08 1.SE.08 E.SE.10 E.8E.10 1.7E.10 E.SE.10 PDF 0. 98 0.91 0.75 2.75 0.75 0.75 NNE SSW X/S S.SE=OS S,7E.07 5.5E.07 5.1E.07 *5.SE.07 +5,RE-07 D/S 1,RE.08 1.EE.09 S.9E-10 S.tE-10 S.tE.10 S.tE-10 PDF O. 95 0.89 0.81 0.82 0.42 0.88. NE SW M/S W.3E-05 7.1E-07 1.SE.07 1.SE.07- 1.EE.07 1.1E-07 D/S 8,1E 09 1.1E-09 3.EE.10 3.2E.10 1,RE.10 4.tE.10 PDF. 0. 91 0.85 0.80 0.80 0.75 0.78 ENE WSW M/S S.5E.06 v.3E.07 4.tE-07 .1.2E.05 1 tE-07 1.tE.07 D/S 1.3E.OS 5,1E.10 5.EE-10 1.SE 09 1.2E-10 1.EE 10 PDF 0. 9E 0.82 0.81 0.85 - 0.78 0,75 E W M/S 4.0E-05 1.3E-05 S.1E-07 S.1E.07 5.9E.08 D/S 9 tE-09 5.9E-08 C.3E-OS 1.1E.09 1.1E.09 S,7E S.7E-11 PDF 0. 9R 0. 90 0.85 0.85 0.75 0.75 ESE WNW N/e S.SE.OS 5,tE.08 S.7E-07 5.1E-07 1.3E.07 1.3E-07
/ D/e ,1.SE.08 .1,0E.08 1.SE 09 1.1E.09 1 tE 10 2.9E.10 g PDF 0. 91 0.90 0.88 0. 50 0.75 0.75 s
SE NW M/S 4.1E.05 S.0E-07 5,9E.07 3.3E-07 1.SE.07 9.7E.07 D/S S.EE.OS 2.SE-09 R.EE.09 1.1E.09 9,5E-10 .1.SE.09 PDF 0.90 0.81 0.81 0,79 3.75 0.80 SSE NNW M/S 1.5E=0S 1.1E 06 .1.SE.05 1.tE-07 1.WE-07 1.tr.07 D/S 1.SE 08 1.0E 08 .1.5E.08 9.2E-10 39.2E-10 9.1E.10 PDF 0.87 0.35 0.88 0.75 0. 75 0.75 S N M/S .1.5E.06 9.5E.07 1.1E-OS 5.9E.07 9.tE 08 D/G 9.tE-04 1.7E-00 1.1E-08 1.EE-OS .S.EE-09 7,tE-10 7.tE-10 PDF 0.89 0.87 0,88 0.85 0. 75 0.75 SSW NNE M/S 5.SE-07 S.SE-07 7.EE-08 9.9E.08 t.SE.08 D/S 1.1E.07 3.5E.09 1 SE.09 9.3E-10 1.tE.10 2.5E-10 S.SE-10 PDF 0.89 0.87 0,81 0.78 0.74 0.83 SW NE M/e 2,3E.07 1.7E-07 1.7E-07 1,7E.07 1.3E-08 1.1E.07 O/e 1.1E-09 7.SE-10 7 SE.10' 7 SE.10 7.9E-11 5.1E.10 PDF 0.89 0.88 0.48 0.88 0, 78 0.86 WSW ENE X/a 7.5E.08 E.SE=08 3,0E-08 1.SE.08 5.SE-09 3.1E-09 D/S 3.2E.10 9.7E-11 1.2K.10 S.3E-11 1.SE.11 S.9E.11 PDF 0.88 0,85 0.85 0.43 0. 78 0.75 W E M/S 5.2E-08 1.5E.08 7,tE.09 7.9E 09 1.0E-09 1,SE.09 D/G 3.SE-10 9,1E.11 t,1E-11 W.1E-11 9.tE.12 S.tE.11 PDF O. 90 0,87 0.89 0.89 0. 75 0.78 WNW ESE M/e , 9.SE.07 S.7E-08 1.2E-47 1,2E-07 1.EE.07 1.tt-OS D/S 1.SE-09 E.EE.10 3.SE-10 3.SE.10 3.8E.10 2.0E 11 PDF 0. 90 0.89 0.85 0,85 0.85 0.75 NW SE X/8 1.3E.OS 1.3E-07 9.5E-08 3.5E.OS '
= 5E.08 3.5E 08 D/G 1.OE=0S 7.5E.10 1.0E-10 1.92-10 1,tE-10 1.tE.10 PDF 0. 91 0.83 0.77 0.75 0.75 0.75 NNW SSE X/a 1.SE-08 1.1E.05 S.2E.08 1.3E-07 1.2E.07 1.2E.07 D/G 1.1E-08 1.7E-08 1.7E-10 S.SE.10 5,9E.10 5.9E-10 PDF Q. 91 0.92 0.75 0.79 0.79 0.79 Cs 2-117
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- Z o
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aC e *C O N O N O W W 2 W 2 W W AW cocococccco C W AW ccMMcococom'N lAl M TI W M 2 2 faJ Z W H Q H A i W 2 W 2 i EQ M sa M 2 2 W c o c o cs o c o c c o ! o W cocNfNoccom to 1 2 L 2 H o H c WZ WZ WA 2 WA 2 HWE Q HLE c M M eC o m M W C3coccococo o eC o m H W cocMNmcCoco C H *N D 2 H aN 3 2 MM M JM = en 2 JM e s0 2 WMC M WMc ** Q QC Q QC H H M M ZWW M 2 eta c c o c o c o c o c 2HH M 2 c o e4@ 2 eo t t o c o N G 4C 4C Q o *C 4C Q MMmM @ Q M
>= Q >=
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aC22 HMM c 1 i
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8 8 9 9 9 9 9 9 9 0 0 0 0 0 9 9 0 0 0 0 0 0 0 0 0 1 1 1 1 1 0 0 5 - - - - - - - - - - - - - - - - 4 E E E E E E E E1 E E E E E E E E 6 2 4 6 4 0 6 3 6 9 4 4 7 7 2 1 1 7 4 3 4 5 4 2 7 2 - 1 1 5 2 9 0 8 8 8 9 9 9 9 9 0 0 0 0 0 0
'9 9 0 0 0 0 9 8 0 0 0 0 1 1 1 1 0 0 5 - - - - - - - - - - - - - - - -
~
3 E E E E E E E E E E E E E 1E E E 2 7 0 5 7 8 1 6 2 2 9 0 1 7 3
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2 1 1 6 4 5 7 6 3 - 1 4 1 2 8 3 1 0 8 8 8 8 9 9 8 8 9' 9 0 0 0 9 9 E 0 0 0 0 0 0 0 0 0 0 1 1 1 0 0 0 5 - - - - - - - - - - - - - - - - 2 E E E E E E E E E E E E E E E E 5 6 6 0 4 3 1 1 2 8 8 1 2 3 9 1 3 2 1 1 7 9 1 1 5 1 6 3 3 1 5 2
)
S E
=. .
L .
- I 0 8 8 8 8 8 8 8 8 8 9 9 0 0 9 8 8 M 0 0 0 0 0 0 0 0 0 0 0 1 1 0 0 0
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. R E u R ' .
T S M 5 7 7 8 8 8 8 8 8 8 8 9 9 9 9 B 7 N U / M 0 0 0 0 0 0 0 0 0 0 0 0 0 0 n 0 A O C O 7 - - - - - - - - - - - - - - - - L U E R E E E 1E E0 E8 E E1 E E E E E E E E P N S F 9 3 3 0 0 0 9 9 9 0 1 1 6 I ( . . . . 2 R T E 1 1 8 5 3 5 6 6 3 1 3 1 1 7 3 1
- A N S C C. E O E N L C U A ,
2 C L T - U 3 A S 5 7 7 7 7 8 7 7 7 8 8 9 9 9 8 8 7 E N 8 V. I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L 9 D 4 - - - - - - Y B N 1 Q E E E E E E E E1 E E E E E E E E A A / D 9 7 6 0 6 3 3 3 2 4 2 2 5 4 4 T J R X N . O E I 3 2 1 1 7 1 1 1 6 2 8 4 4 1 6 2 R T E W ' T R G N A U A W R O Q E D 5 7 7 7 7 7 7 7 7 8 8 8 9 9 8 7 7 V b 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 H A 3 - - - - - - - - - - - - - - - - T E E E E E E E E 1 E E1 E E E E E E 4 6 8 3 4 4 8 2 2 4 4 3 4 0 4 5 3 2 1 1 2 2 1 9 3 1 6 6 2 1 3 5 7 7 7 7 7 7 7 7 7 8 8 8 8 8 7 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 2 - - - - - - - - - - - - - - - - E E1 E E E E E E E E E E E E E E1 1 7 7 9 2 0 0 5 2 1 1 9 6 6 9 5 3 2 2 4 4 3 1 5 2 1 1 3 1 5 5 6 6 7 7 7 6 7 7 7 7 8 8 8 7 7 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 1 - - - - - - - - - - - - - - + - E E E E E E E E E E E E E E E E 9 4 7 0 9 0 1 4 3 1 4 6 6 2 4 3 1 1 9 8 6 1 9 6 3 1 5 3 3 1 4 1 5 6 6 6 6 6 6 6 6 6 7 7 7 7 7 6 6 0 0 0 0 0 0 0 0 0 0 0 0 G 0 0 0 0 - - - - - - - - - - - - - - - - E E E E E E E E E E E E E E E E 3 6 7 9 3 9 0 2 7 8 0 5 6 8 3 5 9 6 4 3 3 4 4 3 1 5 3 2 2 7 2 6 N RO _ OI _ TT PC E N E N E E S E S E W W W W EE S W S N W N CR N N N E E E S S S S S W W W N N EI RD {U
1 1 2 1 2 21 2 1 2 21 2 1 3 31 3 1 3 31 2 1 1 1 1 1 1 5 - - - - - - - - - - - - - - - - 4 E E E E E E 1E E E E E1 E E E E E 1 2 6 4 8 4 8 4 8 5 4 8 3 8 2 7 2 1 1 2 4 7 4 7 2 2 1 8 4 1 0 1 1 2 2 2 2 2 1 2 2 1 3 31 3 12 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 - - - - - - - - - - - - - - - - 3 E 4 2 E E E E2 E E E5 E 0 E E E E E E E 1 1 7 2 5 0 3 4 9 9
. B. .
3 1 4 2 1 4 7 1 7 1 4 4 2 1 6 2 0 1 1 2 2 2 2 1 1 1 2 3 3 3 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 5 - - - - - - - - - - - - - - - - 2 E 3 2 7 E E E E1 E 4E E4 E 3 E E E4 E2 E E E 1 4 4 2 6 3 5
)
6 2 7 4 3 8 1 2 1 2 8 7 4 2 1 5 S E L I 0 0 1 1 1 2 1 1 1 1 2 2 2 2 2 1 0 M 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 ( 5 - - - - - - - - - - - - - - - - E 1 E E E E E0 3E E 1E E2 E2 5E E E 5 E E E S E 6 3 9 1 0 5 1 3 A S . . 8 . E A 1 5 1 1 8 2 3 5 3 5 2 1 1 6 3 1 L E E ) L R 2 E M R T S M 5 0 0 1 1 1 1 0 0 0 1 2 2 2 1 1 0 N U M M 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A 0 / O 7 - - - - - - - - - - - - - - - - L U 1 R E E E 0E E2 6E 6E E E0 E 6E E1 E E E E 7 P N ( F 9 7 7 6 7 3 0 9 2 2 I .
- R T S E 4 1 6 3 2 6 1 1 1 1 6 5 3 2 9 4 A N E C C. E O U N 2 L C L A C A T E U 3 V S 5 9 0 0 1 1 0 0 0 0 1 1 1 2 1 0 9 L N 8 I 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 B 9 Q D 4 - - - - - - - - - - - - - - - -
A N 1 / E E E 5E9 E5 6E 5E E E E E E7 2E 6E E E4 T A D D 2 1 1 1 1 4 0 J R N . . . . O E E I 1 4 1 7 6 1 2 4 2 4 1 1 8 5 2 1 R T T R G A W N A U R E W O Q V D 5 9 0 0 0 0 0 0 0 0 1 1 1 1 1 0 9 A 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 H 3 - - - - - - - - - - - - - - - - T E E E E 5 E E E E E E E E E E E 4 9 5 3 2 3 6 3 4 3 7 8 2 3 7 2 6 1 6 2 1 1 3 4 6 4 6 2 2 1 8 4 1 5 9 9 0 0 0 0 0 9 0 0 1 1 1 0 0 9 0 0 1 1 1 1 1 0 1 1 1 1 1 1 1 0 2 - - - - - - - - - - - - - - - - E E E E E E E E8 3E 2E8 E2 6E E E E E 5 2 2 7 0 1 3 6 7 0 3 1 4 2 3 7 9 1 7 1 4 4 2 1 7 3 5 9 9 9 0 0 9 9 9 9 0 0 0 1 0 9 9 0 0 0 1 1 0 0 0 0 1 1 1 1 1 0 0 1 - - - - - - - - - - - - - - - - E 4 E1 E 3E 9E0 E E E E E E E E E E E 2 4 8 9 9 3 4 4 3 4 0 8 3 1 9 9 2 2 2 1 2 1 1 8 5 2 8 5 8 8 9 9 9 8 8 8 8 9 0 9 0 4 8 8 0 C 0 0 0 0 0 0 0 0 1 0 1 6 0 0 0 - - - - - - - - - - - - - - - - E 4 E0 E 5E 3 E7 E E E4 E 4E8 E2 9E 3E E E E 1 1 2 5 1 5 2 8 6 5 1 1 1 1 1 9 1 7 4 1 5 i N RO _ OI TT E E E W W W _ E W PC N E N S E S S W S N W N _ EE N N N E E E S S S S S W W W N N CR . EI 3 _ RD ';h l
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TABLE' 2.C-2 8 l 7ROJAN NUCLEAR PLANT 97H GUARTER 1983 CONTINUOUS RELEASE
'AVERADE M/S VALUES (SEC/ MSS 33, DEPOSITION [1/MSSR) &
PLUME DEPLETION FACTOR AT OFFSITE EXPOSURE LOCATIONS NEAREST NEAREST. NEAREST SECTOR WIND SITE NEAREST NEAREST MEAT MILK MILK DIR, DIR. SOUNDARY RESIDENCE CARDEN ANIMAL COW 00AT N S M/S. 1,3E.05 1.1E.05 3.5E-07 3.5E-07 3.tE.07 3.5E.07 D/e 7.3E=0S 6.SE.05 1.0E.09 1.0E.09 1.0E.09 1.OE.09 PDF O.91 'O.91 0.75 0.75 0.75 0. 75 NNE SSW M/S 8,SE.08 1.EE.08 7.3E-07 S.9E-07 S,9E-07 S.9E.07 D/e S.SE-08 1.SE.09 1.5E.09 1.tE.09 1.tE.09 1.tE.09 PDF 0. 91 0. 8% 0.81 0.81 0.81 .O.81 NE SW M/S V.SE.08 S 1E-07 3.0E-07 3,0E-07 1.9E.07 1,tE.07 D/e 8.1E.09- 1,1E.09 3,1E.10 3.1E.10 1.1E 10 1.YE.10
'PDF 0, 91 0.89 0,80 0.80- 0.75 0. 75 j ENE WSW M/8 5.1E 08 3.3E-07 3.tE.07 S.SE.07 1.0E.07 1,0E.07 D/8 S.1E.09 3.5E-10 3.7E.10 1.1E.09 8.EE-11 S.1E.11 PDF 0.91 0.81 0,51 0.85 . 0.75 0.78 E W M/e V.3E.08 1.5E 08 S.9E.07 S,9E.07 6.SE-05 S.SE-08 n/a 7.5E.09 t.3E-09 9,02 10 9,0E.10 5 tE.11 5.tE-11
.I 'D F 0,91 0,90 0.85 0.85 0. 75 _0. 75
/N ESE WNW H/S 9.SE 06 3.9E 08 9,7E.07 3.SE.07 9,1E.08 9.1E.03
-{+ L '/ S 1.tE-08 1.1E-08 9.1E.10 4.tE.10 1.3E.10 1.3E.10 PDF 0. 91 0.90 0.81 0.80 0,75 0. 75 SE NW M/e E.OE.04 9.3E-07 4.1E-07 1.tE 07 1.1E-07 3.9E-07 D/S 1.0E.08 1.0E.09 1.OE.09 5.1E.10 1.1E.10 7.SE.10 PDF 0.90 U. 81 0.81 0,79 0,75 0.80 9
SSE 'NNW M/S 1,1E.08 8.0E.07 1.1E 06 1.1E 07 1.1E.07 1.1E.07 D/S 5 tE.09 3.SE-09 5.7E 09 3.9E.10 3 tE.10 3,tE.10 PDF 0.57 0,88 0.88 0.75 0.75 0.75 S N M/S 8,0E.07 5.3E.07 S,0E.07 3.3E.07 5.tE-05 5.tE.08 D/S 5.1E.09 3.1E.09 3,SE.09 1.9E-09 1.3E.10 1.3E.10 PDF- 0.59 0.57 0.88 0.85 0.75 0.75 SSW NNE M/S '3.0E.07 1.7E-07 9.9E.08 3.0E.08 3.1E.05 7.3E 08 D/e 9.1E.10 9.9E.10 1.1E-10 S.3E.11 S,7E-11 1.SE.10 PDF 0.89 0.87 0. 51 0, 78 0. 78 0.83-SW NE M/S 1.tE.07 1,1E.07 1.1E.07 1.1E.07 1 tE.08 7.5E.08 D/G t.1E.10 1,9E-10 1.9E.10 1,9E.10 1.SE.11 1.0E-10 PDF 0.89 0.88 0. 88 0,88 0, 78 0.88 WSW ENE M/S 1.1E.07 3.3E-08 9.0E 08 1.1E.08 S,7E 09 3.SE-05 D/G t.3E.10 1,3E.10 1.5E-10 S.3E.11 1.3E.11 1.1E.11 PDF 0,88 0.85 0,85 0. 83 0.78 0.75 W E M/S 1,0E.07 5.7E.08 P.,7E=0S 1.7E 08 3,CE.09 4.3E.09 D/S 5,tE.10 1,9E 10 S.1E.11 S.1E.11 S.7E.11 1.3E.11 PDF 0,90 0.87 0.89 0.89 0.75 0. 78 l WNW ESE M/S 5.+E.07 9,tE.08 1.3E.07 1.3E-07 1.3E.07 1.tE.QS l D/e 1.9E.09 t.1E-10 5,9E.10 5.9E.10 5,9E.10 9.7E.11 PDF O.90 0.89 0.85 0.85 0.85 0,75 I NW SE M/S 1,3E.06 1,1E.07 7.3E.08 5.5E.SS 5,5E.08 5.5E 08 D/e 1.5E=0S 1.1E.09 1.9E.10 1.0E-10 1.0E.10 1.0E-10 PDF 0.91 0, 83 0.77 0.75 0.75 0.75 l l NNW SSE M/G S.EE.OS 7.0K.05 1.0E.07 9.3C-07 3.9E 07 3,9E.07 D/G S.SE 08 5.5E 08 S,7E.10 1.1E 09 1,9E.09 1.9C.09 PDF O.91 0. 91 0.75 0,79 0.79 0. 79 Ifi
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A E C E 3 U N 2 L 8 L A C 9 A T E U 1 V S 5 9 0 0 1 1 0 0 0 0 1 1 1 2 1 0 9 L N I 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 B R Q D 4 - - - - - - - - - - - - - - - - A N E / E E1E E E E E E E E E E E E L E T A T D D 2 4 7 5 8 0 5 5 1 6 4 9 9 3 0 J R N . . O A E I 1 4 1 6 5 1 3 4 2 7 1 2 3 3 2 1 R T U Q G A W N H R E W O T V D 5 9 0 0 0 0 0 0 0 0 0 1 1 2 1 0 9 4 A 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 3 - - - * - - - - - - - - - - - - E E E E E E E1 E E E1 E E E E 1E E 9 4 2 0 9 0 9 7 7 1 8 0 6 1 6 2 1 1 3 5 7 3 1 2 3 6 6 4 1 5 9 9 0 0 0 0 9 9 0 0 1 1 1 0 0 9 0 0 1 1 1 1 0 0 1 1 1 1 1 1 1 0 2 - - - - - - - - - - - - - - - - E E E E E E E E E E 1 E E E 1E E E 4 2 0 3 7 5 3 0 5 7 1 2 2 9 3 1 4 2 2 8 1 1 7 2 4 6 1 1 7 2 5 9 9 9 0 0 9 9 9 9 0 0 0 1 0 9 9 0 0 0 1 1 0 0 0 0 1 1 1 1 1 0 0 _ 1 - - - - - - - - - - - - - - - - E E 1 E E E E E E E E E 1E E E E E 2 3 3 6 4 9 7 9 3 3 1 1 2 8 _ 8 3 1 8 7 2 2 3 1 4 1 2 4 4 2 7 5 8 8 9 9 9 8 8 8 8 9 _ 0 9 0 9 8 8 0 0 0 0 0 0 0 0 0 0 1 0 1 0 0 0 0 - - - - - - - - - - - - - - - - - E E E E E E E E E E E E E E E E _ 2 0 1 3 8 6 7 0 1 1 0 8 5 3 4 0 _ 5 2 8 5 4 2 1 1 1 3 9 1 3 3 1 5 _ N _ RO _ OI TT PC E E E E W W W W N E N S E S S U S N W N _ EE N N N E E E S S S S S W W W N N CR - EI RD yh
( 6 (s " TABLE 2.C-32 TROJAN NUCLEAR PLANT l VTH GUARTER 1983'SATCH RELEASES AWERAGE M/G VALUES CSEC/Mem3), DEPOSITION (1/M882) & PLUME DEPLE7ZON FACTOR AT OFFBZTE EXPOSURE LOCATIONS l SECTOR - WIND NEAREST NEAREST NEAREST SITE NEAREST NEAREST ME*T MZLK MZLK l DIR. DZA. SOUNGARY RESZDENCE GARDEN ANZMAL COW 00AT l N S M/e 1.1E.05 1.1E-05 2.3E-07 3.3E.07 D/t 7.1E.08 3.EE-07 3.3E-07 E.7E.OS 1.0E-09 1.0E.09 9.3E-10 1.0E.39 PDF 0. 92 0. 92 0.75 0.75 0.75 0,75 NNE' SSW M/S 5.SE=0S 1.tE.05 '7.5E-OY 5.8E-07 S 8E.07 D/t. R.SE.08 R.SE.09 S.8E=O7 PDF 1.5E-09 1.3E.09 1.3K.09 1.3E.09 0.98 0. St 0.85 0.51 0.82 0.51 NE BW M/S t.8E.08 5.tE.07 3.1E-07 3.1E-07 D/t 7.5E.09 1.5E-07 2.5E=07 1.0E-09 3.1E.10 3.1E-10 .1.1E-10 E.3E.10 PDF 0.91 0. 5 + 0.80 0.80 0.75 0.78 ENE. W3W M/S 3.SE-OS E.tE-07 1.5E.07 S.SE-07 7 tE.08 D/a S.aE-09 3.0E-10 7.9E-OS PDF 3.1E.10 S.4E-10 S.9E S.9E-11 O.91 0.81 0. 8E 0.45 - 0.75 0.75 E W M/S 3. 3 E. 05 ' 2.0E.08 5.5E.07 5.5E-07 D/S S tE.09 5.0E-05 5.0E=08 ,
-3.5E.09 7.SE.10 7.SE-10 9.5E-11 9.5E.11 PDF O . 91 ~ 0.93 0.85 0.45 0.75 0.75 ESE WNW M/e' 5.3E-OS t.32.OS 5.EE.07 3.9E-07
/"* D/S 1.5E.08 9.9E.08 9.9E.08 F- 1.RE-Os 9.9E.10 7.0E-10 1.5E-10 1.SE.10 PDF 0, 91 0.90 0.88 0.80 0.75 0.75 SE NW M/S 3. 7E. 08 - 5.50 07 S.tE-07 3.0E-07 D/e 1.RE.08 1.tE.07 9.3E-07 1.1E-09 1.1E-09 S.0E.10 E.5E.10 9.0E-10 PDF 0, 90 O 81 0.81 0.79 0.75 0.80 f
SSE NMW M/S 1.3E-OS 9.3E.07 1.3E.OS 1.3E.07 1.3E=07 1.3E=07 D/S PDF '5.0E-09 0.87 t.0E.09 S.3E.09 3.7E-10 3.7E.10 3.7E-10 0.86 0.85 0.75 0.75 0.75 S N M/8- 8.7E-07 -5.7E.07 S.SE-07 D/S 3.SE.07 5.SE-04 5.SE.05 9.SE=09 3.0E-09 3 SE.09 1.7E.09 R.1E.10 1.1E.10 PDF 0.59 0.47 0.58 0.85 0.75 0.75 SSW NNE M/S 5.0E.07 E.9E.07 8.1E.05 5.0E.OS D/S 5 EE.05 1.RE-07 1.5E.09 8.1E.10 1. 9E.10 1.1E.10 1.1E.10 3.OE.10 PDF 0.89 0.87 0.51 0.78 0.75 0.53 SW NE M/S 1.5K.07 1.EE.07 1.SE.07 1.1E-07 1.SE.08 D/e t.0E.10 8.EE-OS 1.5E.10 1.SE.10 1.8E.10 1.7E.11 1.9E.10 PDF 0.89 0.55 0.85 0.88 0.75 0.85 WSW ENE M/S 1.4E-07 5.9E.03 .7,0E-08 *.0E-08 1.EE-OS D/S 7.1E-10 1.1E.10 5.5E.09
'R.5E.10 1.tE-10 3.9E.11 1.9E-11 PDF 0.88 0.85 0,85 0.33 0.75 0.75 W E M/S 1.5E.07 9.5E.08 2.EE.OS 1.1E.08 D/S 1.SE.10 6,7E-11 3.0E.09 5.1E 09 3.0E 11 3.0E.11 3 EE.12 S.1E 11 PDF 0.90 0.87 0. 8 + 0.89 0.75 0.78 WNW ESE M/e t.4E.07 7.3E-04 1.0K.07 1.0E-07 1.0E=07 D/t 4.1E-09 3.2E.10 1.0E.05 9 SE-10 t.SE.10 t.SE-10 3.SE.11 PDF 0,90 0. S + 0.'85 0.85 0.85 0.75 NW SE M/S 1.9E.05 1.SE.07 9.5E-OS 7.1E.08 7.1E-08 D/S 1.tE-08 7.1E.08 1.0E-09 1.7E.10 1.9E.10 1.9E.10 1.9E.10 PDF 0.91 0. 53 0.77 0.75 0.75 0.75 NNW SSE M/S' 9.2E.06 7.5E-OS 2.2E-07 t.SE.07 9.2E.07 D/e S.SE.08 9.2E 07
, 5.tE-08 E.5E.10 E.1E-09 1.3E-09 1.9E-09 PDF 0.92 0.92 0.75 0.79 0.79 i
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'A i 2.D ANNUAL PERSONNEL WIPOSURE AND MONITORING REPORT This section provides the tabulation of workers receiving exposures greater than 99 meem per year and their man-rem exposures according to work and job functions required by Technical Specification 6.9.1.5.a of Appendix A of Trojan FOL WPF-1. Table 2.D-1 is the exposure report by number 'of personnel, man-rem, and job function. Table 2.3-2 is the dose report by number of personnel versus dose level received. It should be noted that the numbers of people shown on Table 2.D-1 differ from the numbers on Table 2.D-2, since an individual's exposure may be charged to more than one work or job function. The special maintenance category in Table 2.D-1 includes steam generator eddy current testing, piping modifi-cations in the pressurizer relief line as well as other miscellaneous maintenance work not related to normal plant maintenance or refueling activities.
4 I I 2-136
TABLE 2.D-1 REPORT ON NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION
%/
No. of Personnel (>99 mrem) Total Man-Rem Station Utility Contract Station Utility Contract Work and Job Function Ecoloyees Employees Workers Employees Employees Workers REACTOR OPERATIONS & SURVEILLANCE Maintenance Personnel 5 3 4 1.60 1.22 0.87 Operating Personnel- 30 0 1 10.36 0.00 0.57 Chem & RADCON Personnel 18 0 15 6.20 0.00 4.27 Supervisory Personnel 0 0 3 0.13 0.02 2.76 Engineering Personnel 2 0 0 0.70 1.02 0.03 ROUTINE MAINT. & INSERVICE INSPECTION Maintenance Personnel 45 33 27 12.64 16.50 10.52 Operating Personnel 6 0 1 1.39 0.00 0.61 Chem & RADCON Parsonnel 4 2 11 1.72 0.91 4.57 Supervisory Personnel 2 0 10 0.43 0.02 7.27 Engineering Personnel . 3 5 1 1.52 3.10 0.23 SPECIAL MAINTENANCE - Maintenance Personnel 17 19 118 9.58 10.29 60.26 Operating Persennel 3 0 0 0.83 0.00 0.05 Chem & RADCON Personnel 20 2 8 9.46 1.49 2.66 (Q) Supervisory Personnel Engineering Personnel 3 0 7 0.68 0.01 2.86 1 2 0 0.31 0.67 0.09 WASTE PROCESSING Maintenance Personnel' O O O 0.07 0.09 0.49 Operating Personnel 0 0 0 0.44 0.00 0.02 Chem & RADCOM Personnel 18 8 8 13.94 3.31 3.51 Supervisory Personnel 0 0 0 0.01 0.00 0.03 Engineering Personnel 0 0 0 0.00 0.00 0.00 REFUELING { Maintenance Personnel 17 0 5 15.83 0.36 0.99 Operating Personnel 12 0 0 20.56 0.00 0.02 Chem & RADCOM Personnel 12 0 17 3.44 0.04 5.08 Supervisory Personnel 1 0 9 0.32 0.00 2.74 Engineering Personnel 1 1 0 0.61 0.36 0.00 TOTAL Maintenance Personnel 84 55 154 39.72 28.44 73.12 Operating Personnel 51 0 2 33.57 0.00 1.25 Chem & RADCON Personnel 72 12 59 34.76 5.74 20.08 Supervisory Personnel 6 0 29 1.56 0.05 15.66 Engineering Personnel 7 8 1 3.15 5.14 0.36 CRAND TOTAL 220 75 245 112.76 39.37 110.47 2-137 l
I TABLE 2.D-2 l TROJAN PLANT WHOLE BODY EXPOSURE (REM) 1983 a Number of People With No Exposure = 108 Exposure Greater Than 0.001 and Less Than 0.099 Number of People = 479 ] Exposure Greater Than 0.100 and Less Than 0.249 Number of People = 172 ! Exposure Greater Than 0.250 and Less Than 0.499 Number of People = 131 Exposure Greater Than 0.500 and Less Than 0.749 Number of People = 72 Exposure Greater Than 0.750 and Less Than 0.999 Number of People = 46 Exposure Greater Than 1.000 and Less Than 1.999 Number of People = 57 Exposure Greate? Than 2.000 and Less Than 2.999 Number of People = 9 Exposure Greater Than 3.000 and Less Than 3.999 Number of People = 3 Exposure Greater Than 4.000 and Less Than 4.999 Number of People = 0 Exposure Greater Than 5.000 and Less Than 5.999 Numbar of People = 0 Exposure Greater Than 6.000 and Less Than 6.999 Number of People = 0 Exposure Greater Then 7.000 and Less Than 7.999 Number of People = 0 Exposure Greater Than 8.000 and Less Than 8.999 Number of People = 0 Exposure Greater Than 9.000 and Less Than 9.999 Number of People = 0 Exposure Greater Than 10.000 and Less Than 10.999 Number of People = 0 , Exposure Greater Than 11.000 and Less Than 11.999 Number of People = 0 Exposure Greater Than 12.000 and Less Than 100.999 Number of People = 0 O 2-138
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-( 2.E ENVIRONMENTAL SURVEILLANCE REPORT In accordance with Section S.4.1 of the Trojan Operating License.
Appendix B - Part II, Environmental Protection Plan (Non-Radiological) Technical Specifications, the Annual Environmental Operating Report is submitted for 1983. Included are studies of the Columbia River, ter-restrial surroundings, and recreation lake. Where applicable, data are compared to results of studies conducted in previous years during preoperational and operational conditions. Environmental impacts, if any, are noted. A. Columbia River
- 1. Physical-Chemical Water quality Annitoring in the Columbia River for 1983 occurred during the lower flow-higher temperature months as described in the revised Trojan Environmental Protection Plan. Physical-chemical data and chlorophyll pigment concentrations indicate slight seasonal and cross-river differences similar to those noted in previous years. These differences respond to regional climatology and upstream influences. .
Operation of the Trojan power plant did not measurably affect levels of physical-chemical parameters or chlorophyll pigments in
/-~g the Columbia River in the summer and early fall of 1983.
\' )' 2. Fish Imoinaement Eulachon were again the dominant species present in traveling screen washwater. collections, with a total of 105 taken almost entirely in February. Similar to previous years, all of the impinged eulachon were spent; two species, eulachon and prickly sculpin, comprised nearly 93 percent of the total impinged fish.
Other species taken were seven three-spined stickleback, one smallmouth bass, and ono yellow perch. Relatively few freshwater clams were noted in the 1983 collections. The Trojan Intake Structure continues to show little potential for impact on the Columbia River fishes, and unless a change of fish behavior in the intake area occurs, impingement at Trojan will have little effect on local fish populations.
- 3. Fish Behavior Hydroacoustic data indicated no apparent concentration of fish near the di'fuser during the 1983 surveys. Total densities in 1983 were comparable to those of 1976-82; mean number of fish per 1,000 m3 ranted from 0.19 to 1.27 in the uprivar transects, 0.50 to 5.09 in the mixing-zone transects, and 4.48 to 8.09 in the downriver transects. Cross-river densities were greater' q along the Oregon and Washington shores than at mid-channel.
O 2-139
i In 1983, target densi' ties were compared during different tidal conditions as opposed to day / night comparisons. Results indicated no attraction to or avoidance of anadromous fishes to the mixing zone. B. Terrestrial Surroundings
- 1. Aerial Photography Aerial photography of vegetation near Trojan has been carried out since 197A. As in previous years, vegetation in the vicinity of the Trojan Nuclear plant generally remains in good condition.
Various anthropogenic sources were noted as causes for vegetation stress. These included logging, herbicide application, agricul-ture, and general urbanization factors. Vegetative stress from various natural sources were noted during the year from the serial photography and the summer ground truthing. These included natural decadence, insect infestations, and moisture stress. Based on lack of identifiable impacts which could be attributed
~
to the operation of Trojan and the clear stress caused by other anthropogenic and natural forces, it appe,ars all of these other factors greatly outweigh impacts which Trojan might be exerting on the surrounding environment.
- 2. Salt Drift - precipitation Chemical Composition f
Major ions present in the cooling tower pl' me u were measured as wet and dry precipitation at selected collection sites surround-ing the Trojan plant. Total precipitation deposition at each site was similar to deposition measured from 1974 through 1982. Rational wet and dry precipitation for 1983 had an average pH of 4.9. These pH values were not associated with the operation of Trojan. Operation of Trojan power plant did not measurably impact the quantity or quality of precipitation in the local environment except at the base of the cooling tower.
- 3. Birdo The bird population in the vicinity of the Trojan Nuclear plant was censused in May 1983. Fifty-four species were recorded with densities and community composition remaining similar to previous census years, 1974-82. These data indicate a stable bird assemblage in the Trojan region with only minor year-to-year variation.
No bird mortalities or unusual species were observed during weekly general project site surveys. Deleterious impacts to the local bird community are not evident from the operttion of the Trojan Nuclear plant. 2-140
- 4. Incidental Observations l \
Weekly project site ground surveys were conducted during regu-
~ \m/
larly scheduled field activities to document the occurrence of various unusual species or important events that could result in significant environmental impact. No unusual species or occur-rences were noted during these incidental observation surveys. C. Recreation Lake
- 1. Fish Comparison of the 1974-1983 catch data indicates the occurrence of a naturally fluctuating total fish population in the recrea-tion lake. Total catch per effort in numbers and biomass in 1982 and 1983 may indicate a decrease in the number of Centrarchids and perches and possible dominance of the Cyprinid rough fish, carp and goldfish. This succession of dominant fishes in a pond such as tha recreation lake is a natural ecological process and not a result of Plant operation. Sampling efforts will be intensified in 1984 to provide additional data for determining the status of the lake's biological community.
- 2. Benthic Invertebrates Similar to past years, three taxa (ie, Culicidae, Chironomidae, g~'s ,
and Oligochaeta) were the primary constituents of the recreation ('~' ) lake benthic fauna in 1983. Total densities of invertebrates in 1983 were somewhat lower than those of previous years, a reflec-tion of the decrease in numbers of Culicidae. Total densities were again consistently greater at Station 2 than at Station 1, and both stations showed winter high and summer low densities. D. Technical Specification Reports
- 1. EPP Noncompliance No EPP noncompliance were observed or reported during 1983.
Consequently, no corrective action was necessary.
- 2. Changes in Station Design or Operation No chantes in station design or operation occurred which signifi-cantly affected the Environmental Protection Prcgram. As such, there were no potentially significant unreviewed environmental issues.
- Noncoutine reports Six nonroutine reports were submitted to the NRC in accordance with Subsection 5.4.2 of the Trojan Operating License,
- s_ -
l 2-141 l
Appendix B, Part II. The reports, from the Plant General Manager to the Administrator, Region V, U.S. Nuclear Regulatory Commis- i sion, included:
- a. The oil discharge limit of 10 pounds per day was exceeded on January 25, 27, and 28, 1983. Between 262 and 900 pounds of oil were discharged into the Columbia River on the 25th, and 30 pounds and 12.3 pounds were discharged on the 27th and 28th, respectively. The discharges were reported to the NRC on February 23, 1983.
- b. The limits on suspended solids and Biological Oxygen Demand (BOD) in the sewage treatment plant discharged to the Colum-bla River were exceeded on June 22, 1983. A report was sub-mitted to the NRC on July 28, 1983,
- c. The pH limit of 6.0 to 9.0 was exceeded on the sewage treat-ment plant discharge to the Columbia River on October 19, 1983. The pH of 5.87 was reported to the NRC on November 8, 1983,
- d. The main outfall pH limit of 6.0-9.0 was exceeded on November 1, 1983. The pH level of 9.2 was documented and a report was submitted to the NRC on December 14, 1983. '
- e. The maximum 16*F 6T limit between the Plant service water inlet and the main outfall discharge was exceeded on Decem-ber 28, 1983. The 18'F AT was reported to the NRC on January 13, 1984.
- f. The main outfall pH limit of 6.0-9.0 was exceeded on Decem-ber 31, 1983. A recorded pH level of 4.0 was documented and reported to the NRC on January 13, 1984.
l ll 2-142
p i 2.F STEAM GENERATOR TUBE INSPECTIONS i i v Trojan Facility Operating License NPF-1, Appendix A, Technical Specifica-tion 6.9.1.5.b, requires an annual report of Steam Generator Tube Inservice inspections conducted in accordance with Technical Spe'cifications 4.4.5.1 ] through 4.4.5.5. During the 1983 refueling outage, an eddy current examina- ] tion of steam generator "A" was completed. The examination was conducted .) from the inlet side of the steam generator on 388 tubes full-length, and I 149 tubes around the U-bend. The eddy current examination was conducted in accordance with USNRC Regulatory Guide 1.83, Revision 1, and Trojan Technical Specifications. There were no reportable eddy current indications in the 537 tubes examined. The eddy current examination was conducted with multi-frequency inspection equipment.
)
i The ISI classification for the Trojan Nuclear Plant steam generators remains { in Category C-1, as noted in Paragraph 4.4.5.2 of the Technical Specification. No tubes were plugged as a result of this inservice inspection. O nv 2-143
2.G RELTEF VALVE CHALLEUGES O i I NUREG-0737, Item II.K.3.3 requires an annual report of pressurizer relief and safety valve challenges. In 1983, there were no challenges of the safety valves or power operated relief valves. U l 2-144
2,H CHANGES. TE3TS AND EXPERIMENTS f ~s, i Federal Regulations (10 CFR 50.59) and the Trojan Facility Operating License NPP-1 allow changes to be made to the facility as described in the safety analysis report and tests or experiments to be conducted which are not described in the safety analysis report, without prior Nuclear Re5ulatory Commission (NRC) approval, unless the proposed change, test, or experiment involves a change in the Technical Specifications incorpo-i cated in the license or an unreviewed safety question. In accordance l with 10 CFR 50.59, summaries of the changes performed and tests and experiments conducted in 1983 are provided, including sotaaarles of the safety evaluations. (v l 4 i 2-145
7' N) 2.H.1 PLANT MODIFICATIONS AND DESIGN CHANGES
\. J The following plant modifications and design changes were completed in 1983 and reported in accordance with 10 CFR 50.59. These modifications were evaluated, and it was determined that they did not: (a) increase the probability of occurrence of an accident or malfunction of the equip-ment important to safety, as previously evaluated in the Trojan Updated Final Safety Analysis Report (FSAR), (b) create the possibility of an accident or malfunction of a different type than previously evaluated in the FSAR, or (c) reduce the margin of safety as defined in the basis for any Trojan Technical Specification. Other design changes were partially completed during 1983 to meet regulatory commitments and will be reported in future annual reports when the non-committed portions of the design changes are completed.
Plant Design Change 76-038 Plant Design Change 76-03S was initiated to provide an improved permanent leak detection system to test both Containment personnel air lock seals. Plant Design Change 76-038 permanently installed an automatic leak rate monitor at the 93-ft elevation personnel air lock and installed a portable leak rate monitor at the 45-ft elevation personnel air lock. Circuit changes were made to install a seal-in relay to prevent the
, , , opening of the test line isolation valves on a containment isolation
( ; signal. This modification improved the capability to make the required frequent leak tests of the air lock seals. The modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 78-050 1 Plant Design Change 78-050 was initiated to remove the part-length control rods, since the NRC required that they not be used. The modification removed the eight part-length rod clusters from the reactor for storage in the spent fuel pool. Thimble plugs were installed in the eight affected fuel assemblies and anti-rotational devices were installed in the control rod drives to lock the lead screw in the full-out position. Changes to Technical Specifications were made to delete all references to s part-length rods. The part-length rods were never used; thus, their j elimination had no effect on reactor operations. The modification did ! not involve an unreviewed safety question. Plant Design Change 79-061 s k, P11nt Design Change 79-061 was initiated because of poor performance of the main feedwater isolation and bypass valves. 2-146 L _ _ _.__ _
Plant Design Change 79-061 modified the hydraulic actuators for the main feedwater isolation and bypass valves by replacing the spool-type solenoid valves with a more reliable design, 1 This modific ation improved the reliability of the main feedwater isolation und bypass valves. The change did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Plant Design Change 79-109 Plant Design (hange 79-109 was initiated to install monitors for radiation in steam releases to the atmosphere via the main steam power operated relief valves. Plant Design Change 79-109 installed radiation monitors on the four main stcam lines upstream and in close proximity to the main steam power operated relief valves and safety valve headers. This modification meets the requirements of Regulatory Guide 1.97, Revision 2, and improves the capability to detect primary-to-secondary system leakage. The design change does not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-026 Plant Design Change 80-026 was initiated to upgrade fire protection for the cable spreading room. 4 I Plant Desig,n Change 80-026 replaced the sprinkler system in the cable j spreading room with a three-zone deluge system and replaced the ioniza- ! tion fire detectors with a line detection system and an autcmatic actua- j tion system. This modification did not involve a change to the Trojan Technical Speci-fications or an unreviewed safety question. Plant Desinn Change 80-087 Plant Design Change 80-087 was initiated to meet the Technical Specifica-tion requirement for a visual inspection every 18 months of the battery cells for the diesel-driven fire pump. ! plant Design Change 80-087 replaced the batteries with clear sided batteries and installed new battery racks and a battery charger. This modification did not involve a change to the Trojan Technical Specifications or an unreviewod safety question. Pladt Design Change 80-102 plant Design Change 80-102 was initiated to reduce the likelihood of an uncontrolled discharge from the diesel-driven fire pump day tank due to fuel line breakage. 2-147
f Plant Design Change 80-102 relocated the isolation valve to the discharge i o point on the diesel oil day tank and added a protective covering to the fuel line, (v) l This modifi:ation did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-110 l Plant Design Change 80-110 was initiated because of wear grooves occurring in the skirt of the casing for the diesel-driven fire pump. Plant Design Change 80-110 installed wear rings in the casing. This modification did not involve any change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-082 I Plant Design Change 81-082 was initiated to improve breaker-to-buswork { connections in the 480-V MCC which serves the 100 hp service water i booster pumps. j 1 Plant Design Change 81-082 modified all Size 4 and larger motor starters by adding an additional set of bifurcated stabs to increase the contact surface area. 4'
/7 This modification reduced the likelihood of overheating and did not h
involve a change to the Trojan Technical Specifications or an unreviewed safety question, plant Design Change 81-100 plant Design Change 81-100 was initiated because the Containment hydrogen { recombiner power supplies were found to be unqualified for the environ- l ment they were in. l I Plant Design Change 81-100 relocated the power supplies from the ! electrical penetration area to the electrical switchgear rooms. l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. j Plant Design Change 82-018 j Plant Design Change 82-018 was initiated to correct a lack of indication t of water level in the filtet' accumulators on the nucti.n side of the waste gas compres.aor filter accumulai. ors. Plant Design Change 82-018 installed a sight glass on the accumulators. The modification will reduce the likelihood of radioactive gas release and damage to the compressor. i n
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2-143 l l
c-I No change to the Trojan Technical Specifications or an unreviewed safety question was involved. I Plant Design Change 82-028 i Plant Design Change 82-028 was initiated because of low flow of the l control Building's smoke exhaust system. r* ant Design Change 82-028 installed a new, larger exhaust fan which provides the required flow. This modification did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Plant Design Change 83-010 Plant Design Change 83-010 was initiated to prevent cycling of the control room emergency ventilation system if sensed concentrations of chlorine, sulfur-dioxide, or ammonia change due to varying wind conditions. Plant Design Change 83-010 provided a seal-in feature to the actuation circuits to prevent automatic reopening of ventilation system isolation dampers if the signal cleared temporarily. This modification did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Plant Design Change 83-023 Plant Design Change 83-023 was initiated to prevent blocking of sub-sequent actuation signals after the Containment ventilation isolation system reset button has been depressed with the isolation signal present. Plant Design Change 83-023 modified the control circuits to remove the reset capability when the isolation signals are present. No Technical Specification change or unroviewed safety question was involved. Plant Design Change 75-196 Plant Design Change 75-196 was initiated because the power supply to the process computer shifted phase angles during changeover of power supplies, which caused spurious alarms. Plant Design Change 75-196 changed the power supply to non-regulated motor control center B26. This modification results in a decrease in spurious alarms. This change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 2-149
Plant Design Change 76-054 I n
! Plant Design Change 76-054 was initiated because no method existed for monitoring the corrosion and sludge deposition in the circulating water system components.
Plant Design Change 76-054 installed a test heat exchanger for monitoring circulating water system corrosion and sludge deposition. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety questien. Plant Design Change 76-062 Plant Design Change 76-062 was initiated to provide test equipment in the mechanical room for testing electrical breakers. Plant Design Change 76-062 provided power from a Class 1E source and other services to the mechanical room. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-058 Plant Design Change 79-058 was initiated because piping in one of the pipe chases in the Auxiliary Building could produce high radiation levels
~T under certain operating conditions.
(b Plant Design Change 79-058 provided a locked barrier at the entrance to the pipe chase. This modification did not involve a change to the Trojan Technical { specifications or an unreviewed safety question. Plant Design Change 79-0d6_ l Plant Design Change 79-086 was initiated because the duct work on the Containment purge exhaust system was under-designed for the dynamic ; forces imposed by the exhaust fan discharge.
)
Plant Design Change 79-086 upgraded the welding and added reinforcing to the duct work, j This modification did not result in a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design /:hange 79-102 1 Plant Design Change 79-102 was initiated because of the discovery of several cracked ball bushings in pipe supports located in the Main Steam Support Structure. p k l i 2-150
Plant Design Change 79-102 replaced damaged bushings and revised lubrication schedules. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change.76-064 Plant Design Change 76-064 was initiated because dust and high temperatures were causing erratic counting room sample results. Plant Design Change 76-064 provided a filtered air supply to the counting room and a recirculating air conditioner. This modification did not involve a change to the Trojan Technical Specific 64ons or an unreviewed safety question. Plant Design Change 76-068 Plant Design Change 76-068 was initiated because the component cooling water surge tank levels could not be controlled effectively. Plant Design Change 76-068 installed an equalizing line between the two tanks with excess flow check valves to maintain train separation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 76-117 Plant Design Change 76-117 was initiated because the steam trap on the boric acid batch tank was too large for the amount of condensate. Plant Design Change 76-117 changed the steam trap from a 1 1/2-in, size to a 1/2-in. size. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 76-224 Plant Design Change 76-224 was initiated because the baron injection tank recirculation flow was 11 gpm versus 20 gpm listed in the FSAR. Plant Design Change 76-224 determined that the 11 gpm flow was acceptable and modified the low flos alarm setpoint. This modification has been reflected in the Updated FSAR. This modification did not involve a change to the Trojan Technical Specifi6ations or an unreviewed safety question. Plant Design Change 76-230 Plant Design Change 76-230 was initiated to provide protection to the flux thimble tubes when they are withdrawn, f 2-151
i 1 1 I
,, , Plant Design Change 76-230 provided a protective assembly.
- N.
This modification did not involve a change to the Trojan Technical
- Specifications or an unreviewed safety question.
Plant Design Change 76-291 Plant Design Change 76-291 was initiated because the installed instrument and service air compressors were of inadequate capacity. Plant Design Change 76-291 provided an additional compressor. I This modification did not involve a change t.o the Trojan Technical i Specifications or an unreviewed safety question. l l Plant Design Change 76-399 Plant Design Change 76-399 was initiated to improve access for removal of < a service water pump. Plant Design Change 76-399 provided access opening and ladders in the j Intake Structure.
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l This modification did not involve a change to the Trojan Technical i Specifications or an unre~ilewed safety question. { i p) (~ Plant Design Change 76-502 Plant Design Change 76-502 was initiated because no easy means existed to inject anti-foaming agents into the clean radwaste evaporator. Plant Design Change 76-502 provided a chemical injection pump and storage tank to inject the anti-foam agent.
]
This modification did not result in a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 76-520 Plant Design Change 76-520 was initiated because of failure of the level switch for the waste gas compressor moisture separator level control due to the corrosive environment. Plant Design Change 76-520 replaced the level indicating system with a float switch system and a sight glass of corrosion resistant material. This modification did not result in a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 76-560 Plant Design Change 76-560 was initiated to upgrade Trojan fire V) protection to meet NRC requirements as defined in NUREG-75/087, Section 9.5.1. 2-152 ____ _ ____________ __ i
Plant Design Change 76-560 provided the modifications as described in PGE-1012 Trojan Nuclear Plant Fire Protection Program. The modifica-tions included the addition of fire detectors and decouple switches, con-version of the cable spreading room and electrical cable penetration area sprinkler systems to deluge systems, addition of smoke exhausters, fire dampers and fire doors. Changes to the Trojan Technical Specifications were made to specify the operability and service requirements for the modified systems. No unreviewed safety question was involved. Plant Design Change 76-583 q Plant Design Change 76-583 was initiated because the method of trans- l ferring chemicals from drums to the holding tanks was hazardous and inefficient. Plant Design Change 76-583 provided a pump and piping system for chemical transfers. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 77-033 Plant Design Change 77-033 was initiated because use of the overhead crane for multiple tasks in the turbine generator area was limiting outage work efficiency. Plant Design Change 77-033 installed a peru.anent monorail crane structure over the turbine main stop and control valves. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 77-096 Plant Design Change 77-096 was initiated because condensate demineralized isolation valves could not be readily reopened following system maintenance during plant operation. l j t Plant Design Change 77-096 installed pressure equalizing bypass lines around the isolation valves. This modification did not involve a change to tha Trojan Technical Specifications or an unreviewed safety question. . l Plant Design Change 77-130 Plant Design Change 77-130 was initiated because of a personnel safety hazard when climbing to read the reactor coolant pump oil levels. Plant Design Change 77-130 installed platforms to facilitate access to reactor coolant pump motor oil level indication and fill connections. O 2-153
This modification did not result in a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Des _ign Change 77-175 Plant Design Change 77-175 was initiated to prevent radioactive gas releases frota components in the Radioactive Gaseous Waste System. Plant Design Change 77-175 provided loop seals and isolation valves for open equipment drains in the Fuel and Auxiliary Buildings. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. P_lant Design Change 77-180 Flant Design Change 77-180 was initiated because of erratic main turbine control valve behavior during testing and power when the first stage pressure feedback circuit is put into service. Plant Design Change 77-180 modified the EHC circuits to correct this problem. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 78-035 Plant Design Change 78-035 was initiated because of high temperatures on the high voltcge bushing flanges and tetininal box. Plant Design Change 78-035 installed auxiliary cooling fans and ducting. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 78-062 Plant Design Change 78-062 was initiated because conduits penetrating the flood protection walls of the service water pump room were not sealed. Plant Design Change 78-062 provided the seals for the penetrations. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l Plant Design Change 78-083 Plant Design Change 78-083 was initiated because there was no ready access to the controls mounted near the front edge of the operator's console in the control room. Plant Design Change 78-083 provided doors or removable panels to provide maintenance access.
i l l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 78-108 - Plant Design Change 78-108 was initiated because disassembly of the CVCS valves, TCV-129 and LCV-112A, required cutting and rewelding leakoff lines. Plant Design Change 78-108 provided unions in the lines. This modification did not involve a change to the Trojan Technical 3 specifications or an unreviewed safety question. Plant Design Change 79-031 Plant Design Change 79-031 was initiated because of high radiation levels in a Zone II hallway from floor draits from the spent resin transfer pump and letdown heat exchanger. Plant Design Change 79-031 installed shielding in normal personnel access areas. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-037 Plant Design Change 79-037 was initiated because testing showed that the steam and pressure transmitters did net meet seismic design requirements. Plant Design Change 79-037 replaced the transmitters with a seismically qualified design. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. J Plant Design Change 79-044 Plant Design Change 79-044 was initiated because the seal water and discharge vent piping for the heater drain pump interfered with pump removal. Plant Design Change 79-044 installed unions and flanges in these lines. This modification did not involve a chat.ge to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-052 Plant Design Change 79-052 was initiated in response to IE Bulletin 79-02 related to the holding strength of anchor bolts. O 2-155 i
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1 L-_ - ._
3 Plant Design Change 79-052 provided for a modification of the deficient anchor bolts resulting from testing in an inspection. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-053 Plant Design Change 79-053 was initiated because the drain from the heater drain pump stuffing box was of inadequate capacity, plant Design Change 79-053 replaced the drain line with a larger line and seal-welded the pipe joints. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-108 Plant Design Change 79-108 was initiated because a personnel hazard existed when attaching clamp-on ammeters to the Control Building ventilation system heaters. Plant Design Change 79-108 installed permanent ammeters. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-028 Plant Design Change 80-028 was initiated to ensure fire separation for Train A and Train B equipment in the Control Building electrical switch-gear room. Plant Design Change 80-028 provided a new 3-hour fire barrier to separate l Train A and Train B equipment in the Control Building electrical switch-gear room. l This modification did r.ot involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-035 Plant Design Change 80-035 was initiated to modify masonry walls not meeting LER 79-15 resolution criteria. All such walls were' modified for compliance. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant DesiRn Change 80-063 Plant Design Change 80-063 was initiated because of misalignment of the 9 main inlet header to the condensate demineralizers which caused the inlet valves to bind. 2-156
Plant Design Change 80-063 realigned the piping and modified the supports. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-066 Plant Design Change 80-066 was initiated because seismic analysis showed the hold-up tank recirculating pump to be overstressed because of high nozzle loads. Plant Design Change 80-066 replaced the overstressed pump components with high- strength materials. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-092 Plant Design Change 80-092 was initiated because the original seismic recording system became obsolete due to lack cf spare parts and material support. This deficiency resulted in difficult, costly, and time consuming repairs when required. Plant Design Change 80-092 replaced the existing seismic time-history accelerograph system with a new state-of-the-art system which is functionally equivalent. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-003 Plant Design Change 81-003 was initiated because the solenoids on spent fuel pool purification valves CV-5075 and CV-5076 were not compatible with the control circuitry, this resulted in periodic failure of the valves to operate. Plant Design Change 81-003 replaced the valve solenoids and modified the calenoid mounting brackets. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-004 Plant Design Change 81-004 was initiated because radiation streaming was above acceptable limits in the vicinity of the fuel transfer tube in the Fuel Building facade aren when fuel transfer was in progress. Plant Design Change 81-004 provided additional lead shielding to reduce the radiation scatter through the 2-in. seismic gap between the Containment and Fuel Buildings.
?-157
This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-005 Plant Design Change 81-005 was initiated because the failure of both demineralized water transfer pumps while supplying makeup water to the spent fuel pool could have resulted in backflow from the spent fuel pool. Backflow could contaminate portions of the makeup water treatment system. Plant Design Change 81-005 added a check valve to the spent fuel pool makeup water supply line to seal off potentially hazardous backflow. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-008 Plant Design Change 81-008 was initiated beccuse the Containment spray pump recirculation flow indicators used during periodic surveillance testing were difficult to read due to flow oscillations. Plant Design Change 81-008 installed gauge snubbers in the sensing lines to the flow indicator differential pressure transmitter to dampen pressure pulsations and stabilize meter indication.
'This modification did not involve a chat.ge to the Trojan Technical Specifications or an unreviewed safety question.
Plant Design Change 81-048 Plant Design Change 81-048 was initiated because the instrument air and service air systems had a history of failing the local leak rate tests. The check valves located just inside Containment serve as the isolation boundary for the penetrations. These plug-type check valves collect rust and grit on the seat which allows the valves to leak. Plant Design Change 81-048 replaced the plug-type check valves with swing-type check valves. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-054 Plant Design Change 81-054 was initiated because the hinges and anchor bolts on the framework of bullet-proof doors were of insufficient size to support the weight of the door. Plant Design Change 81-054 replaced the hinges and anchor bolts with heavier duty components. 2-158
This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-090 Plant Design Change 81-090 was initiated because the Terry turbine for the auxiliary feedwater pump had experienced oil spillage problems. The oil level in the south pedestal reservoir rises and was flung out onto the turbine insulation, creating a fire hazard. Plant Design Change 81-090 implemented design improvements recommended by the vendor to eliminate oil spillage. l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l Plant Design Change 81-093 l Plant Design Change 81-093 was initiated because a high number of spurious alarms have been caused by weather conditions on a plant perimeter security zone. Plant Design Change 81-093 replaced the intrusion detection system in the affected zone with a more reliable system. This modification did not involve a change to the Trojan Technical ! Specifications or an unreviewed safety question. Plant Design Change 81-105 Plant Design Change 81-105 was initiated because the solenoid valves which supply air to the main steam isolation valves (MSIV) operators were not adequately protected. Plant Design Change 81-105 provided for fabrication and installation of protective covers for the MSIV and MSIV bypass solenoids. This modification did not involve a change to Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-109 Plant Design Change 81-109 was initiated because safety injection system flow indicators FI-928A&B did not have standard test connections !cr calibration. Plant Design Change 81-109 provided necessary changes in FI-928 AFB tubing and valves to allow for proper calibration of the instruments. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 2-159 O
Plant Design Change 82-009 [) is/ Plant Design Change 82-009 was initiated because original DBA sequencers had a reliability problem and required frequent surveillance testing. Plant Design Change 82-009 replaced the electro-mechanical sequencers with a combination of time-delay relays and auxiliary relays. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-027 Plant Design Change M2-027 was initiated because human factors review of the control room identified the potential for accidental operation of main control panel switches. Plant Design Change 82-027 provided for installation of guard rail on front of panel C-11 to prevent accidental switch setivation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-037 Plant Design Change 82-037 was initiated because excessive temperatures in core subcooling monitor microprocessor drawers have caused several g-') equipment failures. V Plant Design Change 82-037 added a second fan in accordance with Westinghouse recommendations and added ventilation louvers to the lower front portion of control panel. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-040 . 3 Plant Design Change 82-040 was initiated because MOVs 4005, 4300, 5672, 5673, and 5674 were incorrectly wired such that their position indication gave either improper CIS status light or local switch information. Plant Design Change 82-040 rewired the valve limit switches such that: (a) for a CIS status light to be lit the valve has to be fully closed, ) and (b) for local switch indication, intermediate valve indication (open and close lights lit) will be provided any time the valve is not fully opened or closed. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l
)
() 2-160 1 I _ - _ - _ _ - _ _ _ _ _ _ . i
Plant Design Change 82-046 Plant Design Change 82-046 was initiated to provide an argon cover gas connection to facilitate installation of a section of the 14-in. pressurizer surge line following removal of a thermal sleeve. The weld procedures used to reinstall this section of line required use of argon cover gas. There were no existing vents or drains in this section of pipe to apply the argon. Plant Design Change 82-046 installed a 3/4-in. socket weld half coupling on the 14-in. surge line between the two pipe cuts. Following completion of all welds on the 14-in. surge line, the half coupling was sealed using a piece of bar stock as a socket weld plug. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-048 Plant Design Change 82-0^8 was initiated when inspection of the process sample lines located in the electrical penetration area revealed possible support design deficiencies. Plant Design Change 82-048 modified the affected pipe supports, removing and adding supports as necessary to relieve undue stress and allow easier valve operation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-051 Plant Design Change 82-051 was initiated because the d-c lights in the control Building 93-ft lobby and stairwell area were powered from cables which pass through the cable spreading room and control room. These lights are needed for safe exit of the control room for major fires in the above two rooms. Plent Design Change 82-051 changed the power supply to the above d-c lights to cables which bypass the cable spreading room and control room. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-053 Plant Design Change 82-053 was initiated because the service water system piping did not have adequate tornado missile protection at Elevation i 61 ft of the Fuel Building. ) l Plant Design Change 82-053 installed two isolation valves, one on each I train of the service water supplies for emergency makeup to the spent l fuel pool. These valves are located at Elevation 45 ft of the Auxiliary { ) Building adjacent to the service water booster pump discharge. 2-161 L_____________ I
L h l L This modification did not involve a change to the Trojan Technical 7-Specifications or an unreviewed safety question. Plant Design Change 82-057 Plant Design Change 82-057 was initiated because no access was available to allow maintenance to the power bus tracks of the Containment polar crane trolley. l Plant Design Change 82-057 installed a steel platform with access ladders, lifelines, and rails for access to the power bus. This modification did not involve a change to the Trojan Technical 9'ecifications or an unreviewed safety question. Plant Design Change 82-060 l Plant Design Change 82-060 was initiated because 14 important pumps did not have run hour meters. Actual operating time was unknown, so mainte-nance had to be based on calendar interval. A pump having higher than average usage may not have received maintenance as promptly as the manufacturers recommendations. Plant Design Change 82-060 installed run hour maters on the affected pumps. This modification did not involve a change to the Trojan Technical [ Specifications or an unreviewed safety question. Plant Design Change 76-603 Plant Design Change 76-603 was initiated because of high airborne activity in the sample room when taking reactor coolant samples. Plant Design Change 76-603 installed sliding glass doors between the sample sink and the fume hood. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-039 Plant Design Change 79-039 was initiated because cooling loss to water-cooled turbine generator components might not be sensed in time to prevent generator damage. Plant Design Change 79-039 added alarm and recording equipment to monitor generator slot and winding cooling water outlet temperatures. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. ( 2-162
Plant Design Change 80-025 Plant Design Change 80-025 was initiated because the Turbine and Demineralized Building sumps, which could become contaminated, discharged to the oily water separator which, in turn, drained to the recreation lake. An unmonitored release to the environment could result. Plant Design Change 80-025 provided a pump to transfer the oily water separator effluent to the Discharge and Dilution Structure and added a radiation monitor. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Chenge 80-064 Plant Design Change 80-064 was initiated to reduce handling of argon bottles for supply to explosive detectors in the badge house. Plant Design Change S0-064 provided argon storage outside the badge house with piping to the explosive detectors. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 80-099 Plant Design Change 80-099 was initiated because the hydraulic pumps for the personnel airlocks were not protected by interlocks during refueling. This could result in damage to door mechanisms. Plant Design Change 80-099 installed switches to de-energize the hydraulic pumps. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-011 Plant Design Change 82-011 was initiated because of failure due to erosion of the extraction steam and heater drain lines to and from the feedwater heaters. Plant Design Change 82-011 provided replacement piping, in the eroded areas, with piping made of more erosion-resistant material. This modification did not involve a change to the Trojan Technical l l Specifications or an unreviewed safety question. I l Plant Design Change 82-030 l l Plant Design Change 82-030 was initiated because of failure of the check valves in the low pressure steam supply lines to the main feedwater pump turbine. 2-163 l
t Plant Design Change 82-030 removed the valve internals.
- This modification did not involve a change to the Trojan Technical j \s Specifications or an unreviewed safety question.
l^ Plant Design Change 82-039 Plant Design Change 82-039 was initiated because the pumps for the fish rearing facility trip upon initiating service water chlorination, which resulted in unacceptable water levels and aeration. Plant Design Change 82-039 modified the circuits to remove the chlorination interlock. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-077 Plant Design. Change 82-077 was initiated because there was no indication of actuation of the main generator and exciter field ground relay test switches. Plant Design Change 82-077 provided control room indication of the relay testing. , , This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 83-034 l Plant Design Change 83-034 was initiated because particulate material deposited between the shaft and sleeve in the stuffing box area of the heater drain pump made sleeve removal difficult. Plant Design Change 83-034 provided for an 0-ring groove in the sleeve to restrict the particulate deposit. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 76-527 Plant Design Change 76-527 was initiated to provide utility services for the guardhouse. Plant Design Change 76-527 provided stub-outs for storm sewers and sanitary cewers, and potable water to the guardhouse area. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. i 2-164 L_________-__
Plant Design Change 77-107 Plant Design Change 77-107 was initiated to increase tube life of the moisture separator reheaters. Plant Design Change 77-107 rerouted the first stage reheater scavenging flow to the cross-around pipe upstream of the moisture separator reheater and rerouted the second stage reheater flow to the first stage reheater feedline. These changes reduced reheater tube vibration. This modification did not involve a change to the Trojan Technical 1 Specifications or an unreviewed safety question. Plant Design Change 78-021 Plant Design Change 78-021 was initiated because excessive particulate in the seal flush water were causing an excessive failure rate of the mechanical seals of the clean waste receiver pumps. Plant Design Change 78-021 provided a filtered demineralized water ~upply s for flushing the pump seals. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 78-100 Plant Design Change 78-100 was initiated because there was no provision in the Intake Structure for access, near the river level, for removal of silt. Plant Design Change 78-100 provided trap doors near the river level for access. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 79-097 Plant Design Change 79-097 was initiated because no test capability existed for the alarm lights on the feedwater heater extraction drain control panel. Plant Design Change 79-097 installed the necessary switches and circuits to allow alarm testing. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 83-026 Plant Design Change 83-026 was initiated because water in the north main feedwater pump casing drain was backing up into the turbine causing rotor damage. 2-165 I L____________
y Plant Design Change 83-026 provided a steam trap in the drain header to G eliminate the water accumulation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed cafety question, l 1 l l O O 2-166
2.H.2 LICENSE AMENDMENTS 7-. i) In 1983, a total of eight license amendments were issued by the NRC. Nine requests for license amendments (License Change Applications (LCAs)] were submitted to the NRC for approval in 1983, all of which resulted in license amendments. Three previously submitted LCAs were revised, approved, and issued. Five LCAs are still undergoing review by the NRC. ? (_) em LJ 2-167
TABLE 2.H.2-1 Sheet 1 of 4 fg AMENDMENTS TO THE TROJAN OPERATING LICENSE ISSUED IN 1983 Amendment _ Number Date Subject 79 03/15/83 The amendment revised the frequency for audits of the facility Emergency and Security plans (and procedures) to at least once per 12 months. The changes were made to make Facility Operating License NPF-1 consistent with the regulations 10 CFR 50.54(t) and 10 CFR 73.40(d), respectively. The NRC has determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact. It has also been concluded that: (1) because the amendment does not involve a significant increase in the probability or conse-quences of an accident previously evaluated, does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is ( 'T reasonable assurance that the health and safety
\~ l of the public will not be endangered by cperation in the proposed manner, and (3) such activities will be conducted in compliance with the Com-mission's regulations, and the issuance of this amendment will not be inimical to the commen defense and the security or to the health and safety of the public.
80 04/27/83 The amendment added License condition 2.C.(10) regarding implementation of IAEA Safeguards at iroj an. Also included in the amendment, but unrelated to the license condition, was a revised table to Appendix B (Part I). This table was issued to correct a previous error in Amendment 62. The NRC has determined that the amendment does not authorize a change in effluent types or to-tal amounts nor an increase in power level, and will not result in any significant environmen-tal impact. It was further concluded that: (1) because the amendment does not involve a significant increase in the probability or conse-quences of an accident previously evaluated, b O 2-168 .~
TABLE 2.H.2-1 Sheet 2 of 4 Amendment Number Date Subject does not create the possibility of an accident of a type different from any evaluated previously, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commis-sion's regulations, and the issuance of this amendment will not be inimical to the common defense and the security or to the health and safety of the public. 81 07/08/83 This amendment revised the method for balancing the flow for the Reactor Coolant System cold-leg injection lines from the centrifugal charging and safety injection pumps, revised the minimum injection flow to 339 and 462 spm, respectively, and deleted the flow balance test for the hot-leg injection lines from the safety injection pumps. None of the changes involve a significant increase in the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any acci-dent previously evaluated, or involve a signifi-cant reduction in a margin of safety. Therefore, the Commission concluded that the amendment does not involve a significant safety hazards con-y sideration. The NRC has determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power l level and will not result in any significant l , environmental impact, and has concluded that- i (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and the security or to the health end safety of the public. 82 07/11/83 The amendment authorized operation with 22 fuel assemblies containing either three or five stain- l 1ess steci rods in place of fuel rods for Fuel I Cycle 6. 1 2-169
TABLE 2.H.2-1 Sheet 3 of 4 in i Amendment _ Number Date Subject The NRC has determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact, and concluded that: (1) there is reason-able assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. 83 08/30/83 The amendment clarified that the auxiliary hoist on the fuel manipulator crane in Containment is used for latching and unlatching of the control rod drive shaft and clarifies that the load test for the manipulator crane and auxiliary hoist is to be performed within 100 hours prior to core
,,_ unloading.
x- The NRC has determined that the amendment does not authorize a change in effluent types or total ( amounts nor an increase in power level, and will not result in any significant environmental impact. It has been concluded that: (1) there is reasonable assurance that the health and I safet,e of the public will not be endangered by operation in the proposed manner, and (2) such ; activities will be conducted in compliance with i the Commission's regulations, and the issuance of ' this amendment will not be inimical to the common defense and security or to the health and safety of the public. 84 11/01/83 The amendment allows plant heatup to the hot { standby operational mode for purposes of conduct-ing final'(hot) tests of the pressurizer safety i valves for up to 18 hours, provided that prelimi- I nary cold settings have been conducted before heatup, and allows entry to the hot standby mode or the startup mode to conduct final operability checks of main steam isolation valves, provided that preliminary operability has been demonstra-ted before entering hot standby. The amendment
,/~' also deletes a reporting requirement regarding
( inservice inspection and corrects the title of
~
l the NRC Regional Office. I 2-170
1 TABLE 2.H.2-1 Shnst 4 of 4 Amendment Number Date Subieet The NRC has determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact. It has been concluded that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. 85 11/22/83 This amendment revised paragraph 2.A of the Operating License to indicate that the facility is now described in the Updated Final Safety Analysis Report, as amended and supplemented in accordance with 10 CFR 50.71(c). The NRC has detenmined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental l impact. It has been concluded that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense an.d security or to the health and safety of the public. 86 12/27/83 This amendment made several changes to the off-site and onsite organization charts in the Trojan Technical Specifications. The NRC has determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact. It has been concluded by the NRC that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. 2-171
i TABLE 2.H.2-2 Sheet 1 of 2
,e STATUS OF L% CENSE CHANGE APPLICATIONS SUBMITTED TO
( AND UNDERGOING . REVIEW BY THE NRC AS OF DECEMBER 31, 1983 LCA Date , j Number Sub;nitted Subject and Status i 50 03/15/79 Appendix I Technical Specifications: Moves 10'CFR 50, Appendix I Technical Specifications from Appendix B of the Trojan Operating License to Appendix A; incorporates the latest NRC requirements for limiting conditions for operation and surveil-lance requirements for radioactive effluents and environmental monitoring. Revision 1 to this LCA was j sent to the NRC on 1/28/83 to incorporate changes ! discussed in a meeting held at Trojan on 3/23-25/82. During a telephone call on 8/18/83, PGE and NRC dis-
)
cussed the incorporation of minor changes to be sub-mitted as Revision 2 of the LCA, currently in preparation. 73 06/08/81 Snubber Surveillance: i Provides surveillance requirements for snubbers and incorporates operability requirements for mechanical f i} (/ snubbers. Revision 1 of this LCA was sent to the NRC on 3/30/83. A meeting was held at the PGE Corporate Offices on 8/23-24/83, at which time PGE agreed to revise and resubmit the LCA after resolution of cer-tain issues requiring additional information. Revi-sion 2 of this LCA is being prepared for submittal to the NRC. 94 08/01/83 Spent Fuel Sto;ege Esek Replacement: Allows the installation of and operation of the Plant with new high-density spent fuel storage racks with a capacity of 1,408 assemblies at 4.5-wt% enrichment, and to prohibit the movement of a spent fuel acsembly shipping cask 'ato the Fuel Building. In response to NRC questions, ?!avision 1 to this LCA was submitted i on 10/31/83. 95 10/14/83 Containment Spray Additive Tank Surveillance Testing: Provides the use of a more practical testing method of verifying flow from the Containment spray additive , tank. Undergoing review. 2-172
TABLE 2.H.2-2, Shaet 2 of 2 LCA Date Number Submitted Subject and Status 97 12/28/83 Operating Staff Organizational Changes: Permits qualified individuals to function in the dual roles of Senior Reactor Operator and Shif t Technical Advisor. Undergoing review. l O O 2-173
I 2.H.3 LICENSING DOCUMENT CHANGE REQUESTS (LDCRs) APPROVED DURING 1983 I Licensing Documents consist of various PGE Topical Reports and the Trojan Updated FSAR. .Under 10 CFR 50.54 and 50.59, changes are permitted to these documents if a change to the Operating License or Technical Speci-fications does not result, an unreviewed safety question is not created, or there is no degradation to Plant security or decrease in effectiveness of the Emergency Plan. The following is a summary of the Licensing Document Change Requests approved in 1983. LDCR: TNP 81-11 Document: Trojan Nuclear Plant Fire Protection Program, PGE-1012 l Status: Approved May 4, 1983 and issued May 26, 1983 as a complete revision. Safety Evaluation: The changes in this revision were administrative and/or editorial in nature and did not involve a change in the Technical Specifications or any unreviewed safety or environmental questions. Any changes made in the facility, procedures, tests, or analyses as described in the original FSAR or previ-
,< ous versions of PGE-1012 have either received prior \ NRC approval pursuant to 10 CFR 50.59(c) and 50.90, or were effected without NRC approval based on a separate safety / environmental evaluation pursuant to 10 CFR 50.59(a), or were required by NRC request pursuant to 10 CFR 50.54(f) or (h).
LDCR: TNP 82-12 2 Document: Nuclear Projects Quality Assurance Program for Opera-tions, NPQAP/0 Status: Approved May 2, 1983 and issued February 24, 1983 as Revision 7. Safety Evaluation: This revision was administrative in nature. It did not lessen the review and approval authority for quality-related activities nor provide any relaxation of the QA Program or administrative controls such that any impact on accident occurrence probability, accident consequences, environmental considerations and Plant safety margins could occur. There were no changes to the Technical Specifications as a result of this revision, nor did it involve any unreviewed
~]g safety or environmental questions.
, u] l 2-174
LDCR: TNP 82-14 Document: Description of the Siren Warning System for the Trojan Uuclear Plant, PGE-1033 Status: Approved February 4,1983 and issued March 10, 1983 Safety Evaluation: The Description of the Siren Warning System was pre-g viously included in the Trojan Radiological Emergency J Plan and Procedures Manual (PCE-1008) as Appendix 1B. Amendment 2 (November 1982) of PGE-1008, Chapters 1 and 2, deleted this Appendix. The effectiveness of the Troj in Radiological Emergency Plan has not been decreased and continues to meet the standards of 10 CFR 50.47(b); therefore, the generation of Topical Report PGE-1033 does not require NRC approval. 'This LDCR is administrative and editorial in nature and does not affect the Technical Specifications, nor does this involve any unreviewed safety or environmental questions. LDCR: TNP 82-15 Document: Evacuation Analysis Report for the Trojan Nuclear Plant, PGE-1034 Status: Approved March 4, 1983 and issued March 23, 1983 Safety Evaluation: The Evacuation Analysis Report was previously included in the Trojan Radiological Emergency Plan and Procedures Manual (PGE-1008) as Appendix IE. Amendment 2 (November 1982) of PGE-1008, Chapters 1 and 2, deleted this Appendix. The effectiveness o' the Trojan Radiological Emergency Plan has not been decreased and continues to meet the standards of 10 CFR 50.47(b); therefore, the generation of Topical Report PGE-1034 does not require NRC approval. This LDCR is administrative and editorial in nature and does not affect the Technical Specifications, nor does this involve any unreviewed safety or environ-mental quentians. LDCR: TNP 83-02, Revision 1 Document: Regulatory Guide Policy Manual, PGE-1028 Status: Approved July 12, 1983 and issued August 26, 1983 as Amendment 1 9 2-175
i Safety Evaluation: The Regulatory Guide Policy Manual (RGPM) establishes E d" PGE's position on NRC Regulatory Guides which affect the operation, maintenance, refueling, and modifica-tions of the Trojan Nuclear Plant. The changes.to the RGPM -incorporate subsequent comments as well as reflect in-house positions (IHPs) for revised or added Regulatory Guides. This Safety Evaluation and tha IHPs are written based on full compliance with the Plant Technical Specifications.- Any resulting conflicts are written as exceptions to the Regulatory Guides; therefore, no changes to the Technical Specifications are necessary. This LDCR has been determined to involve no unreviewed safety questions or environmental matter and does not have an effect on any other licensing documents, commitments, or criteria. LDCR: TNP 83-03 Document: Nuclear Projects Quality Assurance Program for Opera-tions, NPQAP/0-Status: Approved July 21, 1983 and issued July 29, 1983 as Revision 8. Safety Evaluation: This revision was administrative in nature. It did not lessen the review and approval authority for quality-related activities nor provide any relaxation of the QA Program or administrative controls such that any impact on accident occurrence probability, accident consequences, environmental considerations, or Plant safety margins could occur. Since these changes were not equipment-related, no new accidents could be created. No weakening of the Operations Phase QA Program commitments previously made for safety-related components occurred; therefore, no unreviewed safety questions resulted from this revision. LDCR: TNP 83-04 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved June 13, 1983 and issued June 15, 1983 as , replacement pages L Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were imple-mented under 10 CFR 50.54(p); therefore, the Trojan Operating License and Technical Specifications were not affected. 2-176 __ o
LDCR: TNP 83-05 Document: Trojan Radiological Emergency Plan and Procedures Manucl, PGE-1008 Status: Approved September 26, 1983 and issued September 30, 1983 as Amendment 3 to Chapters 1 and 2 (Trojan Radiological Emergency Plan) Safety Evaluation: The changes consist of clarification and revision of the information presented in the Trojan Radiological Emergency Plan. The Emergency Plan is not referenced in the Technical Specifications, except for the annual audit of the Plan required by the NRC; there-fore the Technical Specifications are not affected by this LDCR. The changos involve no unreviewed safety or environmental questions and have no effect on any other licensing documents, commitments, or criteria. The effectiveness of the Emergency Plan has not been i decreased and remains consistent with the standards I of 10 CFR 50.47(b). LDCR: TNP 83-06 { l Document: Updated Final Safety Analysis Report, UFSAR Status: Due to the volume of changes involved, LDCR 83-06 was divided into eight individual change requests to ) provide approval by chapter and/or section. The last . change requests were approved July 8, 1983 and l Amendment 1 to the Updated FSAR was issued July 20, 1983. Safety Evaluation: Pursuant to 10 CFR 50.71(e), an annual revision to the FSAR is submitted to assure that the information in the FSAR contains the latest material developed. All changes initiated with this LDCR are editorial and/or administrative in nature and do not involve a change to the Technical Specifications or any unreviewed safety or environmental questions. Any changes made in the facility, procedures, tests, or I analyses as described in the original FSAR have either received prior NRC approval pursuant to 10 CFR 50.59(c) and 50.90, or were effected without i NRC approval based on a separate safety / environmental l evaluation pursuant to 10 CFR 50.59(a), or were required by NRC request pursuant to 10 CFR 50.54(f) or (h). l O 2-177 I
l 4 l I r's~ l
;j .
LDCR: TNP 83-07 Document: Radiation Protection Program, PGE-8005 i Status: Approved September 28, 1983 and issued October 19, L 1983 as Revision 2 Safety Evaluation: Changes are made in the storage location and use' requirements for the Oregon State Health Division (OSHD) licensed portable gas' chromatography contain-ing tritium foils. Since the portable gas chromato-graphs are licensed by the OSHD rather than the USNRC, this change has no effect on the Trojan Tech-nical Specifications. This change also has no envi-ronmental impact or effect on any other licensing documents, commitments, or criteria. LDCR: TNP 83-09 Document: Trojan Nuclear Plant Security Force Training and Qualification Plan, PGE-1024 Status: Approved August 11, 1983 and issued August 12, 1983 as Revision 3 Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were imple- . mented under 10 CFR 50.54(p); therefore, the Trojan ! Operating License and Technical Specifications were not affected. LDCR: TNP 83-11 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved November 15, 1983 and issued in January 1984 ) as Revision 7 l Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were imple-mented under 10 CFR 50.54(p); therefore, the Trojan Operating License and Technical Specifications were not affected. ( x 2-178 1
l l 2.H 4 PLANT TESTS The following plant tests were performed in 1983 and are reported in accordance with 10 CFR 50.59: Temporary Plant Test 19 ) l Temporary Plant Test 19 was performed to determine the differential l pressure across the steam generator blowdown flow venturis to develop } curves for use in Plant calorimetric. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 20 ' 1 Temporary Plant Test 20 was performed to verify that the Component Cooling Water System can adequately supply the Containment air coolers and reactor coolant pumps under Design Basis Accident conditions. This ; test did not involve an unreviewed safety question or a change to the l Trojan Technical Specifications. l Temporary Plant Test 25 l Temporary Plant Test 25 was performed to test the ability of the con- l densate sample chiller to reduce the temperatures of the condensate l samples in the Condensate Demineralized Building to the required l temperature for analysis. This test did not involve an unreviewed Sg safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 29 Temporary Plant Test 29 was performed to preoperationally test the Post-Accident Sampling System. This test did not involve an unreviewed j safety question or a change to the Trojan Technical Specifications. ' i Temporary Plant Test 30 1 Temporary Plant Test 30 was performed to determine the effects of i operating various combinations of Fuel and Auxiliary Building ventila- l tion exhaust vents. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 42. Revision 1 Temporary Plant Test 42, Revision 1, was performed to functionally test the cable spreading room fire detection system. This test did not involve an unreviewed safety question or a change to the Trojan Tech-nical Specifications. l 2-179
Temporary Plant Test 45 Temporary Plant Test 45 was performed to provide directions for replac-ing and testing the 480V engineered safety feature load center under-voltage lockout relays. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 61 Temporary Plant Test 61 was performed to determine the acceptability of the automatic drain feature on the waste gas collection system moisture separators. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 67 Temporary Plant Test 67 was performed to verify operation of the auxiliary ventilation and smoke exhaust equipment for the Train "A" electrical distribution room in the Control Building. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 68 Tempor:ary Plant Test 68 was performed to functionally test control circuit modifications for the electric-driven auxiliary feed pump. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 70 Temporary Plant Test 70 was performed to verify that the diesel-driven fire pump battery meets the 1981 NFPA load test requiremcats. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 73 Temporary Plant Test 73 was performed to provide instructions for leak testing of the pressurizer power operated relief valve air accumula-toes. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 74 Temporary Plant Test 74 was performed to determine the dose rate in the vicinity of the gamma integrated dose charge converters. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 75 Temporary Plant Test 75 was performed to functionally test the modified main generator temperature monitoring system. This test did not involve , an unreviewed safety question or a change to the Trojan Technical Specifications. 2-180
Pss-
, Te_qporary Plant Test 76
} Temporary Plant Test 76 was performed to functionally test the newly 1 U . installed Post-Accident. Sampling System. This test did not involve an unreviewed safety question or a change to the Trojan Technical
-Specifications. ] ,
Temporary Plant Test 77_ l Temporary Plant Test 77 was performed to show that a main steam isola- ; tion valve, which failed to close without steam flow, would close with ' steam flow. .This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 78 Temporary Plant Test 78 was performed to verify the proper operation of the interlock installed to prevent the condensate demineralized inlet valve from opening with a high differential pressure. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications, l Temporary Plant Test 79 Temporary Plant Test 79 was performed to obtain performance data on the newly rewound condensate pump motor. This test did not involve an unreviewed safety question or a change to the Trojan Technical
. Specifications.
k Temporary Plant Test 82 Temporary Plant Test 82 was performed to test the newly installed deluge systems for the component cooling water and service water booster pump rooms. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Temporary Plant Test 85 Temporary Plant Test 85 was performed to verify the proper operation of the remote shutdown panel ventilation fan controls, indications, and fire damper interlock. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 1 2-181
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2.H.5 CHANGES TO PROCEDURES [, ' Procedures described in the Trojan Updated FSAR are used by the Trojan Plsnt Operating Staff and by various offsite support organizations of Portland General Electric Company. These procedures are described in the Trojan Updated FSAR, Section 13.5, Plant Procedures, and Section 17.0, Quality Assurance. In 1983, the following departments made changes to the safety-related procedures in accordance with 10 CFR 50.59, and con-cluded that none of the changes involved unreviewed safety questions: Trojan Plant Staff Generation Licensing & Analysis Nuclear Projects Engineering Electrical Maintenance & Construction Environmental & Analytical Services Management Support Services Nuclear Maintenance and Construction Quality Assurance Fuel Operat!ons Resident Engineer Nuclear Projects Administration Purchasing and Materials Management Changes to procedures were generally either administrative or technical in nature. Administrative changes consisted of title, organizational and editorial changes, while technical changes were the result of system or component modifications, license amendments, or improvements in procc-dural processes. A safety evaluation was conducted for each change, in gg } accordance with 10 CFR 50.59 and was reviewed and approved by the appro-priate personnel. The review concluded that the probability of occur-rence or consequences of an accident or equipment malfunction were not increased, there was no reduction in any plant safety margins, and the possibility of an accident or malfunction not previously evaluated was not increased. i 2-182
2.H.6 SETp0 INT CHANGES The following setpoint changes were made in 1983 to instruments, alarms, relief valves, and other control and protective devices as described in the Updated FSAR and are reported in accordance with 10 CFR 50.59: plant Setpoint Change 82-05 plant Setpoint Change 82-05 adjusted the setpoints of the water jacket heater control switch (TS 3081X) for the diesel-driven auxiliary feed-water pump so that the water jacket temperature as indicated on TI 3078X is maintained between 100*F and 120*F. previously, the control switch was set to activate the heaters at 100*F decreasing and deactivate the heaters at 120*F increasing. These setpoints resulted in the indicated temperature cycling between 90*F and 100*F. This change does not involve an unreviewed safety question or a change to the Trojan Technical Specifications. plant Setpoint Change 83-11 plant Setpoint Change 83-11 lowered the emergency diesel generator low lube oil pressure standby alarm from 10 psi to 6 psi. This change was made in order to facilitate soakback and idler gear bracket modifications which resulted in reduced oil pressure and increased flow. This change does not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Plant Setpoint Change 83-16 plant Setpoint Change 83-16 raised the boron injection tank high tempera-ture alarm from 185'F to 195*F. Since the heater control system main-tains the tank between 155'F and 185*F the high-temperature alarm was raised to 195'F so that it would actually indicate a higher-than-normal temperature. This change did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. Elant Setpoint Channe 83-17 plant Setpoint Change 83-17 raised the boron injection surge tank high- l temperature alarm from 189'F to 195'F. Since the heater control system l maintains the tank between 155'F and 190*F, the high-temperature alarm ' was raised to 195'F so that it would actually indicate a higher-than-normal temperature. This change did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. , 9 2-183
Plant Setpoint Change 83-20 Plant Setpoint Change 83-20 raised the low pressurizer pressure safety injection trip setpoint from 1770 psig to 1835 psig. This change was j necessary as a result of static temperature calibration checks by the ' pressure transmitter vendor which revealed excessive transmitter errors . during both abnormal and accident temperature conditions. This change I did not result in an unreviewed safety question or a change to the Trojan Technical Specifications. Plant Setpoint Change 8.3-21 Plant Setpoint change 8i-21 raised the narrow-range steam generator low-low level setpoint . rip to >19 percent span to ensure reactor trip and auxiliary feedwater pump start at the O percent narrow-range level. This change was necessar es a t;esult of static temperature calibration checks by the pressure c.ansmitter vendor"which revealed excessive trans-mitter errors at both abnormal and accident temperature conditions. This ! change did not recult in an unroviewed safety question or a change to the Trojan Technical Specifications. D 9. 2-184 l
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g . Portland General ElectricCompany Bart D Witws Vce Presdent e Febtuary 29, 1984 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. John B. Martin, Regional Administrator j U. S. Nuclear Regulatory Commission ). Region V Creekside Oaks Office Park 1450 Maria Lane, Suite 210 l Walnut Creek CA 94596-5368
Dear Mr. Martin:
A_nnual Report Enclosed are two copies of Portland General Electric Company's Annual Report for the Trojan Nuclear Plant for the calendar year 1983. Sincerely, i daWac, - Bart D. Withers Vice President Nuclear Enclosures c: Mr. Lynn Frank, Director E State of Oregon (2) Department of Energy @ Director $ 2: $i office of Inspection and Enforcement (1) U. S. Nuclear Regulatory Commission >O Director c3 Office of Management O (1) , and Program Analysis U. S. Nuclear Regulatory Commission Director Office of Nuclear Reactor Regulation (1) U. S. Nuclear Regulatory Commission s Document Control Desk (18) U. S. Nuclear Regulatory Commisalon \\ 1215 u Saman Sttet. Pcnand. O'egon T2C4}}