Text

Annual Rept of Trojan Nuclear Plant for 1985
	ML20154G211
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1985
From:	; PORTLAND GENERAL ELECTRIC CO.
To:	;
References
	PGE-1015-85, NUDOCS 8603070601
	Download: ML20154G211 (155)
	v • d • e

{{#Wiki_filter:. . _ _ _ _ _ _ _ _ _ _ ~ l PGE-1015-85 i i i ANNUAL REPORT OF TROJAN NUCLEAR PLANT 9 FOR 1985 Docket 50-344 License NPF-1 O I ) i PORTLAND CENERAL ELECTRIC COMPANY 121 S. W. Salmon Street ] Portland, Oregon 97204 0 .j-r t 8603070601 851231 i PDR ADOCK 05000344 R PDR 0 $

g TABLE OF CONTENTS k i 1. INTRODUCTION. 1-1 i 2. REPORTS i A. Radioactive Effluent Release Report. 2-1 l 1. Effluent and Weste Disposal Report. 2-2 2. Offsite Radiation Doses. 2-36 1 3. Meteorological Data. 2-81 i 4. Changes to the Offsite Dose Calculation [ ] Manual (ODCM) 2-82 B. Annual Personnel Exposure and Monitoring Report. 2-102 C. Steam Generator Tube Inspections and Maintenance. 2-105 j D. Relief Valve Challenges. 2-106 E. Changes, Tests, and Experiments. 2-107 I 1. Plant Modifications and Design Changes. 2-108 2. License Amendments... 2-124 3. Licensing Document Change Requests (LDCRs) Approved During 1985.. 2-136 4. Plant Tests. 2-143 5. Changes to Procedures. 2-149 6. Setpoint Changes. 2-150 1 L t m --er=+---r-e-rv -w-----rw-m-------,r----r---,-e r- -,---'. --i------

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1. INTRODUCTION The Annual Report of the Trojan Nucient Plant for 1985 is sutmitted in accordance with the requirements of Federal Regulations and Facility Operating 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 and, with the exception of several load reductions for maintenance and testing, remained at full power until March 9. A new " days on-line" generation record for the Plant was established. On March 9, an automatic reactor trip occurred when the main turbine tripped on high vibration. A pressure surge caused by main feedwater isolation resulted in a ruptured heater drain pump discharge pipe. With repairs completed, the Plant was returned to 100 percent power and remained steady-state until the annual maintenance and refueling outage commenced on May 2. The Plant refueling outage lasted 67 days, during which time refueling, maintenance, and surveillance testing was performed. Fuel unloading of the reactor vessel began on May 17 and core reloading was completed on June 9. The Plant was returned to power operation on July 7. During the refueling outage, the 10-year Inservice Inspection was begun, to be completed in 1986 and, if necessary, in 1987. l Full power operation was attained on July 17; however, the reactor tripped on July 20 due to a high temperature in the unit auxiliary (g) transformer. The Plant was returned to full power on July 25 and operated mostly at 100 percent through the remainder of 1985 with two exceptions. On August 26, a trip was caused by a short in a heat tracing circuit, and on September 24 a trip occurred due to a problem with a condensate demineralizer bypass valve circuit. Near the end of the year, primary / secondary leakage increased and was being closely monitored. During 1985, the Spent Fuel Pool storage racks were modified to accommodate 1408 fuel assemblies snd the computerized Card Key System was installed and declared operational. The capacity factors for the year are as follows: . Month Capacity Factor January 95.3 February 96.9 March 71.6 April 94.9 May 2.7 June 0.0 July 55.4 August 95.7 September 75.3 October 95.4 [ )/ November 97.9 \\~- December 97.5 Overall 73.0 l 1-1

1 I I 1 2.A RADI0 ACTIVE EFFLUErr am eAet REPORT This section contains the reports required by Technical Specifica-tion 6.9.1.5.4 of Trojan FOL MpF-1. Complete data for the year 1985 have been included, although the data for the first 6 months (January through June) have been previously reported. i l t 4 i l I l \\ l t 4 ( 2-1 I .s_,.

1 2.A.1 IFFLUENT AND id&STI DISP N f-REPORT 0 This section contains a summary of the liquid and gaseous release limits; a listing of the maatinum perialssible concentrations of the isotopes released; a sumanary of batch and abnormal release data; a summary of total 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 inadiated fuel shipments. During the year, the effluents released by the Trojan Nuclear Plant were well within the limits set forth in the Technical Specifications to the Plant's Facility Operating License. The data presented in this sectlen represent all releases during the period January 1, 1985 throash December 31, 1985. I I f 1 5 .a t l l l 2-2 i l

V TABLE 2.A.1-1 SUPPLEMENTAL INFORMATION January 1, 1985 through June 30, 1985 REGULATORY LIMITS 1st 2nd Fission and Activation Gas Release Rate Limits Unit Quarter Quarter 1. Tech. Spec. 3.11.2.1(a), Instantaneous 1 QTv i Ci/sec 1.60E-1 1.65E-1 2.0 ry 1 QTv i Ci/sec 4.07E-1 4.14E-1 0.33 (Cy+ 1.1 IT ) y 2. Tech. Spec. 3.11.2.2, Quarterly Average QTv i C1/sec 5.35E-3 5.48E-3 50 Ny QTv i Ci/sec 3.85E-3 3.88E-3 25 My 3. Tech. Spec. 3.11. 2. 4 (1), Quarterly Average Requiring Use of the Gaseous Radweste Treatment System QTV < Ci/sec 2.67E-3 2.74E-3 100 Ny QTv < 1 Ci/sec 1.92E-3 1.94E-3 50 M_y 2-3

O TABLE 2.A.1,2, SUPPLEMENTAL INFORMATION January 1, 1985 through June 30, 1985 REGULATORY LIMITS Gaseous Iodine 131, Tritium, and Particulates 1st 2nd With > 8 Day T4 Limits Unit Quarter Quarter 1. Tech. Spec. 3. ll.2.l(b) Instantaneous 1 {frv <~.67 E Ci/sec 8.88E-4 4.44E-3 2. Tech. Spec. 3.11.2.3 Quarterly Average 1 QTv 1 Ci/sec 5.95E-6 2.98E-5 100 E 3. Tech. Spec 3.11.2.4(2) Quarterly Average Requiring use of Ventilation Treatment System 1 OTv 'i Ci/sec 2.98E-6 1.49E-5 ~ 200 E O i-4

TABLE 2.A.1-3 LJ SUPPLEMENTAL INFORMATION Jaouary 1, 1985 through June 30, 1985 REGULATORY LIMITS LIQUID EFFLUENT LIMITS 1. Tech. Spec 3.11.1.1 Instantaneous discharge concentrations less Instantaneous than the maximum permissible concentrations listed in 10CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration is limited to 2 x 10 -4.ci/n1 total activity. 2. Tech. Spec 3.11.1.2 Gross release limit of 2.5 Ci per quarter e Quarterly average excluding tritium and dissolved noble gases. ( If this limit is exceeded, cumulative dose k due to liquid ef fluents will be limited to < l.5 nrem to the whole body and to < 2.5 crem to any organ,using isotope specific methodology in the plant offsite dose calculation manual (ODCM). 3. Tech. Spec. 3.11.1.3 The liquid radwaste trsatnent system shall (,n.tarterly average requiring be maintained and used when activity use of the liquid radwaste discharged (excluding tritium and dissolved treatment system noble gas) would exceed 1.25 Ci/Qtr. O 2-5

py ( ) J TABLE 2.A.1-4 Sheet 1 of 2 SUPPLEMENTAL INFOR&\\ TION January 1, 1985 through June 30, 1985 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid Isotope MPC (uci/ce) Chromium 51 2 X 10-3 Manganese 54 1 X 10-4 Iron 55 8 x 10-4 Cobalt 57 4 X 10-4 Cobalt 58 9 X 10-5 Iron 59 5 x 10-5 ,3 ( i Cobalt 60 3 X 10-5 \\_) Strontium 89 3 X 10-6 Strontium 90 3 X 10-7 Zirconium 95 6 X 10-5 Niobium 95 1 X 10-4 Molybdenum 99 4 X 10-5 Technetium 99m 3 X 10-3 Ruthenium 103 8 X 10-5 Ruthenium 106 1 X 10-5 Silver 110m 3 X 10-5 Tin 113 8 /. 10-5 Antimony 124 2X 10-5 Antimony 125 1 X 10-4 Iodine 131 3 *: 10-7 Iodine 132 8 X 10-6 Tellurium 132 2 X 10-5 Iodine 133 1 X 10-6 Cesium 134 9 X 10-6 Iodine 135 4 X 10-6 Cesium 136 6 X 10-5 Cesium 137 2 X 10-5 Barium 140 2 X 10-5 Lanthanum 140 2 X 10-5 Cerium 141 9 X 10-5 Cerium 144 1 X 10-5 ^< s v g 2-s m -

O TABLE 2.A.1-4 Sheet 2 of 2 Isotope MPC (t.Ci/ce ) Alpha 3 X 10-8 Unidentified 3 X 10-8 Tritium 3 X 10-3 Krypton 85m 2 X 10-4 Xenon 133 2 X 10-4 Xenon 133m 2 X 10-4 Xenon 135 2 X 10-4 Gaseous Gaseous MPC's are not used in calculating technical specifications at Trojan. O 2-7

~ l l ) TABLE 2.A.1-5 Sheet 1 of 2 SUPPLEMENTAL INFORMATION January 1, 1985 through June 30, 1985 AVERACE ENERGY Effluent release limits ate not based upon E, hence, reporting E is not required. MEASUREMENTS AND APPROXIMATIONS OF W AL RADIOACTIVITY l Caseous Releases Fission and Activation Gases: Gamma spectrometric analysis of gaseous grab sarples define radionuclide distribution at least monthly on monitored gaseous release points. Using the known nuclide distri-butions and procesJ radiation monitor readings, the actual quantities h of gaseous releases are calculated. I V i Iodines Weekly composite filter and iodine cartridge samples are analyzed by gamma spectroscopy to determine the concentration of par-i ticulate and iodine isotopes. Weekly composite samples are analyzed i for beta and alpha emitting isotopes by counting with a gas flow pro-portional counter. Quarterly composite filters are analyzed for Sr-89/90 using chemical separation and gas proportional beta counting using i chemical separation techniques when necessary. Tritiun: Tritium is collected on dr*' silica gel in monthly composite samples, and counted using liquid scintillation spectroscopy. Liquid Releases Fission and Activation Products: Cama spectromet fic analysis of each l batch is performed. Weekly composite samples att maintained for con-i tinuous releases and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites a.a prepared for both l batch and continuous releason for specified activity determinations. I l O m 2-8

O TABLE 2. A.1-5 Sheet 2 of 2 MEASURE 3tCITS AND APPROXI*tATIONS CF TOTAL RADIOACTIVITY (Continued) Liquid Releases Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques. Dissolved and Entrained Cases Gaseous isotopes are determined by ganma spectrometric analysis of each batch, and on a minimum frequency of once per conth for continuous releases. O O 2-9

O j TABI.E 2.A.1-6 l SUPPLEMENTAL INFORMATION ) ) January 1, 1985 through June 30, 1985 l 1 l BATCH RELEASES I Unit Liquid Caseous 1 Number of Batch Releases 63 82 i Total time period for Batch Releases Hours 289.2 2527 Maximum time period for Batch Releases Hours 21.5 711.8 Average time period for Batch Releases Hours 4.6 30.8 Minimum time period for Batch Releases Hours 0.6 0.6 Average dilution flow during Batch Releases GPM 28140 !!/A 1 1' j ABNORMAL RELEASES i I Number of Abnormal Releases 0 3 2 tal Activity Released C1 1.12E+1 i i 1

6 1

l 2-10

s (v) TABLE 2.A.1-7 Sheet 1 of 2 GASEOUS EFFLUENTS SUhMATION OF ALL RELEASES January 1,1985 through June 30, 1985 1st 2nd Estimated FISSIO!! AND ACTIVATION GASES Unit Ouarter Quarter Error % Total Activity Released C1 3.40E+2 2.77E+2 1 5El 3 Average Release Rate for Quarter uCi/sec 4.38E+1 3.53E+1 Percent of Limit Tech. Spec 3.11.2.1(a) Instantaneous 4.44E-2 1.34E-1 Tech. Spec 3.11.2.2 - Quarterly Average 1.14E0 9.10E-1 Tech. Spec. 3.11.2.4(1) Quarterly Average Fequiring / Processing 2.28E0 1.82E0 N_J ICDINE 131 Total Iodine 131 Released C1 2.44E-3 1.81E-3 13.5El Average Pelease Rate for Quarter pCi/sec 3.15E-4 2.31E-4 PARTICULATES Total with Half-Lives >8 days C1 2.03E-4 2.45E-5 1 5El 3 Average F41 ease Rate for Quarter DCi/see 2.62E-5 3.12E-6 Total Gross Alpha Released C1 1.30E-5 2.07E-5 TRITIUM Total Faleased C1 2.79E0 6.13E0 +3.0E1 Average Release Rate for Quarter uCi/sec 3.60E-1 7.01C-1 (A\\ \\ / 'm/ 2-!!

O , TABLE 2.A.1-7 Sheet 2 of 2 ICDINE 131, PARTICULATES WITil let 2nd Estimated >8 day T4, and TRITIUM Unit Quarter Quarter _ Error s Total Released C1 2.79 6.13 +3.5El Average Release Rate for Quarter uCi/sec 3.60E-1 7.81E-1 Percent of Limit Tech. Spec. 3.Ll.2.l(b) Instantaneous 1.26E-1 5.09E-2 Tech. Spec 3.11.2.3 Quarterly Average 6.04E0 2.62E0 Tech. Spec. 3.11.2.4(2) Quarterly Average Requiring Processing 1.21E+1 5.24E0 9 2-12

O TABLE 2.A.1-8 GASEOUS EFFLUENTS CROUND LEVEL RELEASES January 1, 1985 throuth June 30, 1985 Continuous Mode Batch Mode NUCLIDES RELEASED HIlli ist Quarter 2nd Quarter let Quarter 2nd Quartig FISSION GASES Krypton - 85m Ci 3.81E-2 1.99E-2 7.08E-2 1.115-2 Krypton - 85 Cl 1.06E0 1.69F0 Krypton - 87 Ci 7.94E-2 4.29E-2 3.02E-2 Krypton - 88 Ci 9.55E-2 5.03E-2 3.66E-2 Krypton - 89 Ci Ionon - 131m C1 1.15E-2 2.2350 1.5950 Zenon - 133m C1 1.00E-3 2.32E0 1.92E0 Zenon - 133 Ci 8.38t+1 5.46E+1 2.43E+2 2 12E+2 Ienon - 135m Ci 4.27E-1 2.40E-1 3.82E-2 Ionon - 135 CL 2.74E0 2.1950 2.7750 !. 6150 Zenon - 137 Ci 9.09E-2 5.37E-2 Ienon - 138 Ci 2.05E-1 1.04E-1 Acton - 41 Ci 3.71E-3 2.49E-1 2.76E-1 O V TOTAL FOR QUARTER Ci 8.75E+1 5.73E+1 2.52E+2 2.19E+2 IQDIMES Iodine - 131 C1 2.43E-3 1.29E-3 6.84E-6 5.21E-4 Iodine - 132 Ci 5.63E-8 1.96E-3 Iodine - 133 C1 2.98E-3 1.06E-3 2.32E-4 2.81E-6 Iodine - 135 C1 1.56E-7 5.12E-5 TOTAL FOR QUARTER Ci 5.41E-3 2.35E-3 2.90E-4 2.48E-3 PARTICULATES >8 DAY T1/s Strontium - 89 C1 1.36E-4 1.40E-8 4.87E-7 ND Strontium - 90 Ci 6.58E-5 1.03E-8

2. 3's E-1 ND Cesium - 137 Ci 8.69E-6 3.18E-8 9.32E-6 Cobalt - 60 C1 1.d4E-8 6.44E-6 70*.*AL FOR QUARTER CL 2.02E-4 8.71E-6 7.13E-1 1.58E-5 2-13

1 TABLE 2.A.1-9 CASEOUS EFFLUENTS ELEVATED RELEASES January 1, 1985 through June 30, 1985 No Elevated Release Points O l l l O 2-14 I

(O) TABLE 2.A.1-10 s_- LIQUID EFFLUENTS SU)01ATION OF ALL RELEASES January 1,1985 through June 30,195; 1st 2nd Estimated FISSION AND ACTIVATION PRODUCTS Unit Quarter Quarter _. Error % Total Activity Released (Excluding gases, tritium and alpha) Ci 7.57E-2 1.54E-1 13.5f +1 Average Diluted Concentration LCi/ml 5.29E-9 1.09E-0 Percent of Limit Tech. Spec. 3.11.1.1 - Instantaneous 6.03E-1 3.17E-1 Tech. Spec 3.11.1.2 Quarterly Limit t 3.03E0 6.15E0 Tech. Spec. 3.11.1.3 Quarterly Limit Requiring \\ Processing 4 6.06E0 1.23E+1 TRITIUM Total Released Ci 8.89E*1 6.07E+1 +3.0E+1 Average Diluted Concentration UC1/n1 6.22E-6 4.31E-6 Fraction of MPC 2.07E-1 1.44E-1 DISSOLVED AND E!PrRAINED CASES Total Activity Released Ci 5.28E-2 1.17E-2 +3.5E+1 Average Diluted Concentration uCi/mi 3.69E-9 0.27E-10 Fraction of itPC 1 1.05E-3 4.14E-4 GROSS ALPl!A RADIOACTIVITY Total Released Ci 3.82E-5 7.21E-5 13.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 0.20E+5 1.65E6 +5.0E0 VOLUME OF DILUTION WATER Liters 1.43E+10 1.41E10 +1.5E+1 0 2-15

p) ( TABLE 2.A.1-11 Sheet 1 of 2 ,v LIQUID EFFULENTS January 1, 1985 through June 30, 1985 Continuous Mode Batch Mode frJCLIDES RELEASED Unit let Quarter 2nd Quarter 1st Quarter 2nd Quarte Iodine - 132 Ci 1.64E-5 Chromium - 51 Ci 3.68E-3 Cobalt - 58 Ci 3.22E-3 1.11E-2 Cobalt - 60 C1 1.28E-2 3.68E-2 Iron - 59 C1 2.28E-4 3.23E-4 Manganese - 54 Ci 3.94E-4 1.57E-3 Zirconium - 95 Ci 5.04E-4 1.26E-3 Niobium - 95 Ci 1.17E-3 3.58E-3 Iodine - 131 Ci 1.53C-2 4.31E-3 Iodine - 133 Ci 1.60E-3 1.54E-4 Cesium - 134 C1 1.53E-3 1.11E-2 Cesium - 137 C1 2.15E-3 1.27E-2 Lar.thanum - 140 Ci 1.02E-2 7.37E-3 's_.- Antimony - 124 C1 1.33E-4 Antimony - 125 C1 2.02E-3 3.37E-3 J Ruthenium - 103 Ci 1.94E-4 9.46E-4 Cerium - 144 C1 1.89E-3 5.69E-3 Cobalt - 57 Ci 6.99E-6 1.19E-5 Ruthenium - 106 Ci 6.69E-3 1.80E-2 Strontium - 89 Ci IID ND 3.46E-4 1.54E-4 Strontium - 90 Ci ND ND 1.08E-5 3.33E-5 Tellurium - 132 Ci 2.80E-5 Unidentified C1 2.13E-6 2.88E-5 Silver - 110m C1 3.63E-5 5.57E-4 Iodine - 135 Ci 6.74E-5 Cerium - 141 Ci 6.36E-5 Tin - 113 Ci 6.97E-5 4.33E-5 Molybdenum - 99 Ci 5.53E-5 3.64E-5 l Technetium - 99m Ci 6.06E-5 3.82E-5 Barium - 140 Ci 7.29E-4 2.26E-3 i Cesium - 136 Ci 1.84E-4 3.47F-4 Iron - 55 Ci ND ND 1.41E-2 2.83E-2 TOTAL FOR QUARTER Ci ND 2.13E-6 7.57E-2 1.54E-1 (Continued) (v 2-16

O TABLE 2.A.1-11 Sheet 2 of 2 Continuous Mode Datch W3de NUCLIDES RELEASED tinit. 1st (Marter 2nd Ouarter 1st Quarter 2nd Quarter Xenon - 133 Ci 4.86E-2 1.07E-2 Xenon - 135 Ci 3.29E-3 9.13E-4 Xenon - 133m Ci 8.83E-4 4.82E-5 Krypton - 85m C1 2.19E-5 TOTAL FOR QUARTER C1 ND no 5.28E-2 1.17E.2 0 9 2-,,

O TABLE 2.A.1-12 Sheet 1 of 2 SOLID 'JASTE AND IREADIATED F*lAL SHIPNFJTS January 1, 1985 thronah June 30, 1985 I I Activity Volume Estimate SOLID WASTE SHIPPED OFFSITE FOR BURIAL GR DISPOSAL During During Total (Not Irradiated Fuel) - Tree of Waste _6 Months 6 Months Error % i 1. Spent Rosin, Filter Siudger, Evaporator 3487.161 Ci 57.773 m3 25% Bottoms, Filters Etc. 2. Dry Compressible Weste, Contaminated 8.615 Cl 120.431 m3 25% Equipment Etc. 3. Irradiated Components. Control Rods Etc. 0 0 4. Other 0 0 EST MATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WARTE 1 J_ Wuclide 1. See attached sheet. 2. See attached sheet. I 3. 4. SOLID WASTE DISPOSITION 9 - % r of Shi;s.its Mode of Transportation Destination 11 Exclusive Truck U.S. Ecolo8y, Inc. PO Box 638 j Richland WA 99352 I**AnIATED FUEL SHIPMENT DISPOSITION Wumber of Shloments Mode of Transportation Destination O N/A N/A \\ 2-18 i

TABLE 2.A.1-12 Sheet 2 of ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Category 1 CateRory 2 Total curies = 3487.161 Total curies = 8.615 Total Volume = 2 40 ft3 - 57.773 m3 Total Volume - 4252.5 ft3 = 120.431 m3 Nuclide Distribution (Cl) Nuclide Distribution (C1) H-3 4.851 H-3 0.542 C-14 0.872 C-14 0.001 Cr-51 0.193 Cr-51 0.036 Mn-54 5.960 Mn-54 0.081 Fe-55 193.561 Fe-55 2.913 Co-57 4.560 Co-58 0.656 Co-58 23.373 Fe-59 0.014 Ni-59 0.878 Co-60 2.037 Co-60 1378.112 Ni-63 1.018 Ni-63 1001.275 Sr-89 0.049 Sr-89 1.775 Sr-90 0.100 Se-90 35.670 Mb-95 0.025 Nb-95 0.018 Zr-95 0.024 Zr-95 0.009 Ru-103 0.005 Tc-99 0.002 Ru-106 0.241 Ru-106 0.087 Sb-125 0.037 Sb-125 2.179 Cs-134 0.276 I-129 0.004 Cs-136 0.005 T-131 0.006 Cs-137 0.354 Cs-134 202.806 Ba-140 0.021 Cs-137 614.960 co-144 0.138 Ba-140 0.004 Pu-241 0.042 Ce-144 8.993 Pu-238 0.042 Total 8.615 Pu-239/240 0.152 Am-241 0.088 Pu-241 6.687 Cm-242 0.024 Cm-243 0.020 Totai 3487.161 0 2-19

O TABLE 2. A.1-13 Sheet 1 of 2 SUPPLEMENTAL INFORMATION July 1, 1985 Through December 31, 1985 REGULATORY LIMITS Third Fourth Fission and activation Gas Releeee Rate Ll=lts Unit Quarter Quarter 1. Tech spec 3.11.2.1(a), Instantaneous QTv s 1 Ci/sec 1.15E-1 6.72E-2 2.0 Ey QTv i 1 CL/sec 3.025-1 2.075-1 0.33 (Lf + 1.1 B ) y 2. Tech Spec 3.11.2.2, Quarterly Average ( ) QTv i i Ci/sec 4.01E-3 2.45E-3 50 Ny QTv i 1 C1/see P.675-2 3.23E-3 25 My 3. Tech Spec 3.11.2.4(1), Quarterly Average Requiring Use of the Caseous Radweste Treatment System QTv s 1 CL/see 2.00E-3 1.22E-3 100 Ny QTv s 1 CL/see 1.145-3 1.61E-3 50 Ny O 2-20

O TABLE 2.A.1-13 Sheet 2 of 2 SUPPLEMENTAL IEFORMATICN July 1, 1985 Through December 31, 1985 RECVLATORY LIMITS Caseous Todine 131. Tritium, and Particulates Third Fourth With > 8 Day T1/2 Limits ,1hjjL, Quarter Quarter 1. Tech Spec 3.11.2.1(b). Instantaneous QTv s 1 CL/sec 4.64E-3 1.83E-2 .67 R1 2. Tech Spec 3.11.2.3, Quarterly Average QTv s 1 Ci/see 3.11E-5 1.23E-4 100 Ri 3. Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Caseous Radweste Treatment System QTv s 1 C1/sec 1.55E-5 6.14E-5 200 Ri O 2-21

- ~_-. l J \\ t TABLE 2.A.1-14 SUppLSMENTAL INFOMIATION July 1, 1935 Through December 31, 1935 REGULATORY LIMITS i: Lieuid Effluent Lt=lts 1. Tech Spec 3.11.1.1 Instantaneous discharge concentrations Instantaneous less than the seminum petwissible con-I centrations listed in 10 CFR part 20, [ Appendix 3. Table II, Column 2 for t radionuclides other than dissolved or I entrained noble gases. For dissolved or entrained noble gases, the con-i } centration is limited to 2 x 10 -4 wci/mi total activity. i I 2. Tech Spee 3.11.1.2 Gross release limit of 2.5 Ci per i Quarterly Average quarter ev:1uding tritium and dissolved noble gases. If this limit is exceeded, cumulative dose due to i j 11guld effluents will be limited to 1.5 area to the whole body and to i 2.5 area to any orgen, using lootope t } specific methodology in the plant Offsite Dose Calculation Nenual (00CN). ( 3. Tech Spee 3.11.1.3 The 11guld redweste treatment system l Quarterly Average Requiring shall be maintained and used when j Use of the Liquid Radweste activity discharged (emeluding tritium j Treatment System and dissolved noble gas) would exceed ( ) 1.25 C1/Qtr. l l ) 4. Tech Spec 3.11.1.4 The quantity of radioactive material i Temporary Storage Tank contained in temporary redweste storage l Activity Limit tanks is limited to i 10 C1 emeluding i tritium and dissolved noble gases. 4 i i { l i t 2-22

TABLE 2 A I-15 SUPPLEMENTAL INFORMATION July 1, 1985 Through December 31, 1985 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid MPC MPC Isotope (uCL/ce) Isotope (uC1/cci Chromium 51 2 x 10-3 Iodine 131 3 x 10-7 Manganese 54 1 x 10-4 Iodine 133 1 x 10-6 Iron 55 8 x 10-4 Cesium 134 9 x 10-6 Cobalt 58 9 x 10-5 Cesium 137 2 x 10-5 Cobalt 60 3 x 10-5 Cesium 138 3 x 10-6 Rubidium 98 3 x 10-6 Lanthanum 140 2 x 10-5 Strontium 89 3 x 10-6 Cerium 144 1 x 10-5 Strontium 90 3 x 10-7 Alpha 3 x 10-8 Zireccium 95 6 x 10-5 Unidentified 3 x 10-8 Niobium 95 1 x 10-4 Tritium 3 x 10-3 Molybdenum 99 4 x 10-5 Krypton 85m 2 x 10-4 Technetium 99m 3 x 10-3 Krypton 87 2 x 10-4 Ruthenium 103 8 x 10-5 Kryp*.on 88 2 x 10-4 Ruttenium 106 1 x 10-5 Zenon 131m 2 x 10-4 Silver 110m 3 x 10-5 Zenon 133 2 x 10-4 Antimony 124 2 x 10-5 Kenon 133m 2 x 10-4 Antimony 125 1 x 10-4 Zenon 135 2 x 10-4 Kenor.135m 2 x 10-4 Caseous Gaseous MPCs are not used in calculating technical specifications at Trojan. 9 2-23

/N ( ) v TABLE 2.A.1-16 SUPPLEMENTAL INFORMATION July 1, 1985 Through December 31, 1985 AVERAGE ENERGY Effluent release limits are not based upon E, hence, repor* irs i is not required. HILLSURENENTS AND APPROIIMATIONS OF TOTAL RADI0 ACTIVITY Caseous Releases Fission and Activation Cases: Camma spectrometric analysis of gaseous grab samples define radionuclide distribution at least monthly on monitored gaseous release points. Using the known nuclide distributions and process radiation monitor readings, the actual quantities of gaseous releases are esiculated. Todinest Weekly composite filter and iodine cartridge samples are analyzed by gamma spectroscopy to determine the concentration of (,_ j particulate and iodine isotopes. Weekly composite samples are \\_,/ analyzed for beta and alpha emitting isotopes by counting with a gas flow proportional counter. Quarterly composite filters are analyzed for Sr-89/90 using chemical separation and gas proportict.21 beta counting using chemical separation techniques when necesaary. Tritium: Tritium is collected on dry silica gel in monthly composite samples and counted using liquid scintillation spectroscopy. Limaid Releases Fission and Activation products: Gamma spectrometric analysis of each batch is performed. Weekly composite samp*es are maintained for continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly compositas are prepared for both batch and continuous releases for specified activity determinations. Tritium: Monthly composite samples are distilled and dolonized as necessary to remove contamination and counted by liquid scintillation techniques. Dissolved and Entrained Geses: Gaseous isotopes are determined by gamma spectrometric analysis of each batch and on a minimum frequency of once per month for continuous releases. /3 ) ~ 2-2f.

TABLE 2.A.t_g7 SUPPLEMENTAL INFORMATION July 1, 1985 Through December 31, 1985 BATCH RELEASES Unli Liqui 4 Caseous Number of Batch Releases 56 88 Total time period for Batch Releases Hours 127.4 1512 Maxista time period for Batch Releases Hours 4.3 94.6 Average time period for Batch Releases Hours 2.3 17.2 Mininnam time period for Batch Releases Hours 0.3 0.5 Average dilution flow during Batch Releases CPM 28600 NA ABNORMAL RLEASES Number of Abnormal Releases 0 2 Total Activity Released Ci 1.54E0 0 2-25

/s (' TABLE 2.A.1-18 Sheet 1 of 2 l GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES July 1. 1985 Through December 31, 1985 Third Fourth Estimated FISSTON AND ACTIVATION GASES Unit Quarter Quarter Error Total Activity Released Ci 1.66E+2 2.78E+2 13.5El Average' Release Rate for Quarter pCi/sec 2.09E+2 3.51E+1 Percent of Limit: Tech Spec 3.11.2.1 (a) - 3.97E-2 1.12E-1 Instantaneous Tech Spec 3.11.2.2 - 6.00E-1 1.44E0 Quarterly Average Tech Spec 3.11.2.4.(1) - 1.20E0 2.87E0 Os Quarterly Average Requiring Processing IODINR 131 Total Iodine 131 Released Ci 4.14E-4 3.91E-4 A3.5El Average Release Rate for Quarter pCi/sec 5.22E-5 4.93E-5 l PARTICULATES f Total with Half-lives > 8 days Ci 2.01E-4 1.87E-6 13.5El Average Release Rate for Quarter pCi/see 2.53E-5 2.36E-7 l Total Cross Alpha Released C1 1.28E-5 9.80E-6 l TRITIUM l l Total Released Ci 7.51EO 7.50E0 3.0E1 Average Release Rate for Quarter pCi/sec 9.47E-1 9.46E-1 O 2-26

l Ol TABLE 2.A.1-18 Sheet 2 of 2 CASEQUS EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1985 Through December 31, 1985 IODINE 131. PARTICULATES WITH Third Fourth Estimated > 8 DAY T1/2 AND TRITIUM Unit Quarter Quarter Error Total Released Ci 7.51E0 7.50E0 13.5El Average Release Rate for Quarter Ci/sec 9.47E-1 9.46E-1 Percent of Limit: Tech Spec 3.11.2.1 (b) 2.04E-2 7.30E-3 Instantaneous Tech spec 3.11.2.3 3.05E0 7.71E-1 Quarterly Average Tech Spec 3.11.2.4(2) 6.10E0 1.54E0 Quarterly Average Requiring Processing l l l l l ( 2-27 l l

=_ O TABLE 2.A.1-19 Sheet 1 of 2 i GASEOUS EFFLUENTS GROUND LEVEL RELEASES July 1, 1985 ThrouEh December 31, 1985 WUCLIDES RELEASED Continuous Mode Batch Mode M L 3rd Quarter 4th Quarter 3rd Ousrter 4th Quarter FISSION GASES .i Krypton 85m C1 2.83E-2 1.33E0 3.62E-2 4.36E-2 Krypton 85 Ci 9.86E-1 4.63E-1 Krypton 87 Ci 5.79E-2 2.02E0 1.15E-2 2.32E-2 Krypton 88 Ci 4.88E-2 3.13E0 3.32E-2 3.40E-2 Krypton 89 Ci i Zenon 131m Ci 5.18E-2 3.51E-1 9.27E-1 Ienon 133m Ci 3.65E-1 7.09E-1 6.66E-1 Zenon 133 Ci 7.56E+1 1.56E+2 7.17E+1 7.68t+1 Zenon 135m C1 3.19E-1 8.16E0 2.83E-2 4.75E-3 Zenon 135 Ci 1.49E+1 2.44E+1 8.21E-1 1.55E0 Zenon 137 Ci 8.96E-3 8.25E-3 Ionon 138 Ci 1.34E-1 1.70E0 2.03E-2 ArEon 41 C_( 1.85E-2 5.79E-1 1.613-1 1.64E-2 TOTAL FOR QUARTER Ci 9.12E+1 1.98E+2 7.48E+1 8.06E+1 O 2-28

O TABLE 2.A.1-19 Sheet 2 of 2 CASEOUS EFFLUENTS GROUND LEVEL RELEASES July 1,1985 Through December 31, 1985 Continuous Mode Batch Mode Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Ouarter IODINES Iodine 131 Ci 4.098-4 3.33E-4 4.90E-6 5.83E-5 Iodine 132 Ci 1.34E-6 4.24E-7 1.69E-6 Iodine 133 Ci 4.17E-4 2.66E-4 7.86E-6 8.11E-5 Iodine 134 Ci 1.28E-6 9.31E-8 4.13E-7 Iodine 135 C1 2.11E-6 3.28E-6 9.81E-5 TOTAL FOR QUARTER Ci 8.31E-4 6.03E-4 1.28E-5 2.40E-4 PARTICULATES > 8 DAY T-1/2 Strontium 89 Ci 1.18E-4 ND 4.31E-7 7.56E-7 Strontium 90 Ci 5.61E-5 ND 2.08E-7 4.88E-7 Cesium 137 Ci 2.51E-5 2.25E-9 3.85E-8 1.11E-7 Cobalt 58 Ci 5.97E-9 2.64E-8 Cobalt 60 Ci 3.34E-8 Cesium 134 Ci 7.16E-8 Chromium 51 C1 1.27E-8 4.15E-8 Ruthenium 106 Ci 4.18E-7 Niobium 95 2.47E-8 TOTAL FOR QUARTER Ci 1.99E-4 2.25E-9 7.00E-7 1.87E-6 9 2-29

i i 1 6 TABLE 2.A.1-20_ i i ,1 GASIOUS EFFLUENTS ELEVATED RELEASES July 1, 1985 Through December 31, 1985 No Elevated Release Points i J i f I;- t 1 i f 5. l i i i j i 1 f I i i e r i I I r I I r J l i 3 4 5 I f a r b r 2 [ 1 ? i 5 1 I \\ 1 2-30 l 1 4

l TABLE 2.A,3_33 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1985 Through December 31, 1985 FISSION AND ACTIVITY PRODUCTS Third Fourth Estimated Unit Quarter Quarter _qrror % Total Activity Released (excluding Ci 8.70E-1 1.48E-1 3.5E+1 gases, tritium, and alpha) Average Diluted Concentration pCi/ml 5.92E-9 1.03E-8 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous 9.70E-1 6.91E-1 Tech Spec 3.11.1.2 - Quarterly Limit 3.48E0 5.92E0 Tech Spec 3.11.1.3 - Quarterly Limit 6.96E0 1.18E+1 Requiring Processing TRITIUM Total Released Ci 3.62E+1 7.91E+1 13.0E+1 Average Diluted Concentration pCL/mi 2.46E-6 5.49E-6 Fraction of MPC 8.21E-2 1.83E-1 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 1.30E-1 1.63E-1 13.5E+1 Average Diluted Concentration pCi/mi 8.87E-9 1.13E-8 Fraction of MPC 4.44E-3 5.64E-5 CROSS ALPHA RADIOACTIVITY Total Activity Released C1 1.21E-4 7.99E-5 3.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.43E+6 8.32E+6 15.0E0 VOLUME OF DILUTION WATER Liters 1.47E+10 1.44E+10 !1.5E+1 9 2-31 J

O TABLE 2.A.1-22 Sheet 1 of 2 i LIQUID EFFLUENTS July 1. 1985 Through December 31, 1985 WUCLIDES RELEASED Continuous Mode E?tch Mode M 3rd Quarter 4th Ouarter 3rd Quarter 4th Quarter Chromium 51 Ci 3.59E-4 Manganese 54 C1 1.93E-5 1.18E-3 9.31E-5 Iron 55 Ci 3.28E-4 1.16E-1 1.07E-2 1.13E-2 Cobalt 58 C1 1.59E-5 2.48E-3 8.52E-4 Cobalt 60 Ci 1.78E-4 3.26E-2 1.94E-3 Rubidium 88 Ci 5.77E-5 Strontium 89 Ci ND 3.14E-5 ND ND i Strontium 90 Ci ND 6.18E-6 4.81E-5 1.71E-5 Zirconium 95 Ci 6.32E-4 3.86E-6 Niobium 95 Ci 1.46E-3 1.18E-5 Molybdenum 99 Ci 2.41E-5 Technetium 99m Ci 2.54E-5 Ruthenium 103 Ci 3.22E-4 1.19E-5 Ruthenium 106 Ci 1.72E-2 1.79E-4 Silver 110m Ci 8.16E-4 1.23E-5 Antimony 124 Ci 3.97E-6 4 Antimony 125 Ci 3.99E-5 2.70E-3 2.40E-3 Iodine 131 Ci 1.35E-4 5.89E-4 1.18E-4 1.24E-3 Iodine 133 Ci 5.64E-4 1.74E-3 5.22E-6 2.15E-4 Cesium 134 I Ci 1.00E-4 8.11E-5 4.03E-3 3.93E-3 Cesium 137 Ci 5.95E-5 1.78E-4 4.75E-3 5.62E-3 Cesium 138 Ci 6.72E-7 l i 4 2-32

O TABLE 2.A.1-22 Sheet 2 of 2 LIQUID EFFLUENTS July 1, 1935 Through December 31, 1985 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 3rd Ouarter 4th Ouarter 3rd Quarter 4th Ouarter Lanthanum 140 Ci 4.73E-4 4.73E-4 Cerium 144 Ci 5.29E-3 6.24E-5 Unidentified Ci 5.67E-5 4.25E-4 5.21E-4 TOTAL FOR QUARTER Ci 1.19E-3 1.19E-1 8.57E-2 2.89E-2 Krypton 85m Ci 2.06E-4 3.36E-5 Krypton 87 Ci 3.98E-5 2.08E-6 Krypton 88 Ci 8.68E-5 7.72E-6 Ienon 131m Ci 3.97E-4 3.58E-4 Zenon 133 Ci 9.520-3 1.23E-1 3.54E-2 Zenon 133m Cl 9.23E-5 1.42E-3 3.18E-4 Zenon 135 Ci 2.64E-2 5.52E-3 9.11E-4 Zenon 135m gi 8.93E-2 1.05E-4 TOTAL FOR QUARTER Ci ND 1.268-1 1.30E-1 3.71E-2 5721k 2-33

( TABLE 2.A.1-23 Sheet 1 of 2 SUPPLEMENIAL INFORMATION j July 1, 1985 through December 31, 1985 Activity Volume Estimate SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL During During Total 4 (Not Irradiated Fuel) - Tree of Weste 6 Months 6 Months Error % 1. Spent Rosin Filter 31udges. Evaporator 15.033 Ci 83.898 m3 25% Bottoms, Filters, Etc. 2. Dry compressible Waste Contaminated 4.142 Ci 47.832 m3 25% Equi ment, Etc. P 3. Irradiated Components, Control Rods, Etc. 0 0 a 4. Other 0 0 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Ci Ci Euclide 1. See attached sheet. O 2. See attached sheet. 3. 4. l l SOLID WASTE DISPOSITIDW Number of Shionants Mode of Transoortation Destination 12 Exclusive Truck U.S. Ecology PO Box 538 Richland WA 99352 l IRRADIATED FUEL Shirriana DISPOSITION Wumber of Shionents Mode of Transportation Destination 0 N/A N/A i 4 !O l 2-34 l e-,, - ~ - - - - - - - -

TABLE 2.A.1-23 Sheet 2 of 2 ESTIMATE OF MAJOR NUCLID1 DISTRIBUTION BY TYPE OF WASTE Nuclide Ci 1. H-3 1.625 C-14 0.104 Cr-51 0.010 Mn-54 0.186 Fe-55 4.469 Co-57 0.006 Co-58 1.019 Co-60 2.540 Mi-63 1.270 Sr-89 0.041 Se-90 0.050 Nb-95 0.031 Zr-95 0.017 Ru-103 0.001 Ru-106 0.351 Ag-110m 0.006 Sb-125 0.041 I-131 0.028 Cs-134 0.771 Cs-137 1.357 Ba-140 0.010 Ce-144 0.566 Pu-241 0.534 2. H-3 0.459 C-14 0.001 Cr-51 0.112 Mn-54 0.029 Fe-55 1.050 Co-58 0.259 Co-60 0.743 Ni-63 0.372 Sr-89 0.006 l Sr-90 0.012 Nb-95 0.227 Zr-95 0.182 Ru-103 0.187 Ru-106 0.267 Sb-125 0.004 l Cs-134 0.022 i Cs-137 0.048 Ce-141 0.020 Ce-144 0.105 l Pu-241 0.037 l J l 2-35

1 0 2.A.2 0FFSITE RADIATION na!E! offsite radiation doses from gaseous and liquid effluents for 19?: are presented in this section. Included ars quarterly doses te individuals at locations of maximum actual expostre and quarterly doses to the 50-n11e population. Doses are pre',ented separ.Lely for batch and con-tinuous releases and for noble gr.s. gamer,us iodine and particulate, and 11guld effluents. Exposure locations are based en the land-use survey presented in the Updated FSAR. ;.nd the annual survey of agriculture production, effective October 1, 10e4 Models and assumptions used in performing the dose analyses for 1985 are presented in Sections.11.2 and 11.3 of the Trojan Updated FSAR. Addi- + tional assug tions are given in this section. i l t 4 4 t -l 1 J l l .j s i r 4 2-36 i i l -. -..,, -... -, - - -, = -. - - - - - - - - - - - -,,, - - -. ~. --,,.~.,,-.-,,_-..m- .-_w.,----------

7-~ TABLE 2.A.2-1 Sheet 1 of 2 PARAMETERS USED IN CALCULATING DOSES FROM CASEOUS EFFLUENTS (First Half 1985) 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 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m3/ye) Adult 8,000.0 l Infant 1,400.0 Animal Consumption Rates (kg/ day) Animal feed by meat 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 Particulates Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulates Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 2 Surface Density of Soil for Root Zone (kg/m ) 240.0 Field Decay Half Life (days) 14.0 O 2-37 1 m-r---,,

TABLE 2.A.2-1 Sheet 2 of 2 Parameter Value 2 Agricultural Productivity (kg/m ) Leafy vegetables 2.0 Pasture grass 0.7 Produce 2.0 Period of Long-Term Buildup for Activity in Soil (days) 7.300.0 Fraction of Leafy Vegetables Cro'.tn in Carden 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 Crazes 1.0 0 0 2-38

i i 73 TABLE 2.A.2-2 Sheet 1 of 2 PARAMETERS USED IN CALCULATING DOSg3 FROM LIQUID EFFLUENTS Value Parameter 1st Otr. 1985 2nd Otr. 1985 j Plant Dilution Flow Rate (spa) 29,100.0 28,400.0 Columbia River Flow Rate (cfs) 144,000.0 406,901.0 Dilution Factors Drinking water 2,219.0 6,428.0 Swimming water 488.0 1,414.0 Aquatic biota 488.0 1,414.0 Shoreline sediment 488.0 1,414.0 Irrigation water 2,219.0 6,428.0 Milk and seat animal water 2,219.0 6,428.0 Decay Times (days) Discharge to drinking water 0./4 0.58 Discharge to swimming water 0.0 0.0 Discharge to aquatic biota consumption 1.0 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 s Discharge to irrigation water withdrawal 0.74 0.58 -s l i Discharge to milk and meat animal water 0.74 0.58 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 i Cow's milk from irrigated pastureland 310.0 Coat's milk from irrigated pastureland 310.0 Meat from irrigated pastureland 110.0 l 2-39

f TABLE 2.A.2-2 Sheet 2 of 2 Value Parameter 1st Ote. 1985 2nd Ote. 1985 Annual Exposure Times (hr/yr) Swimming and boating 12.0 Shoreline activities 12.0 Irrigated pasture 2,190.0 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 (Weatharing) Half-Life (days) 14.0 2 Irrigation Rate (liters /m -hr) 0.104 Fractional Concentration of Water in Soil (g/g) 0.2 Fraction of Leafy Vegetables Crown in Carden of 1.0 Interest Fraction of Produce Crown in Garden of Interest 0.76 Irrigated soll Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Leafy Vegetables Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Crass 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 Pasture vegetation by milk goat 6.0 Pasture vegetation by beef 50.0 2-40

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11 TABLE 2.A.2-4 FIRST QUARTER 1985 POPULATION DOSE (50-MILE) FROM LIQUID EFFLUENTS (MAN-REM) EXPOSURE PATHWAY TOTAL BODY THYROID = - - - - _ _ _ _ _ _ _ _ AQUATIC DRINKING WATER 2.2E-04 8.9E-04 FISH CONSUMPTION 4.9E-02 7.8E-02 INVERTEBRATE CONSUMPTION 3.3E-05 4.3E-05 u EXPOSURE TO CONTAMINATED SEDIMENT 1.9E-05 1.9E-05 SWIMMING AND BOATING 1.6E-07 1.6E-07 IRRIGATION AND LIVESTOCK WATERING LEAFY VEGETABLE CONSUMPTION 4.8E-07 9.9E-06 PRODUCE CONSUMPTION 2.3E-06 2.6E-06 NEAT CONSUMPTION 1.6E-05 2.8E-05 MILK CONSUMPTION 1.7E-04 1.6E-03 EXPOSURE TO CONTAMINATED SDIL 1.6E-06 1.6E-06 TOTAL 5.0E-02 8.1E-02 AVERAGE DOSE (MREM / PERSON) 2.4E-05 3.9E-05 e O O O O

_ ~ I TABLE 2.A.2-5 4 FIRST QU.*.::TRR 1985 BATCH RELEASES I DOSES FROM NOBLE CASES AT ) SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION 1 Site Boundaryl*l ResidenceIDI i i 1 Beta Air Dose (arad) 9.5E-2 5.6E-2 Gamma Air Dose (mead) 3.3E-2 1.4E-2 i Beta + Gamma Skin Dose (aren) 3.3E-2 Gamma Total Body Dose (aren) 1.2E-2 e i [a] North sector at 663 meters. (b) North sector at 965 meters. i 1 l' I 6 1 I f i [ 2-43 l 1 l i

_ TABLE 2.A.2-6 FIRST QUARTER 1985 CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary (a] ResidenceIDI Beta Air Dose (mrad) 3.7E-2 2.2E-2 Camma Air Dose (mrad) 1.5E-2 6.25-3 Beta + Camma Skin Dose (meem) 1.4E-2 Camma Total Body Dose (mrem) 5.3E-3 [a] NNW sector at 674 meters. (b] NUW sector at 965 meters. O 2-44 i l l L

g TABLE 2.A.2-7 FIRST QUARTER 1985 BATCH + CONTINUOUS RELEASES 4 DOSES FRON NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF 4 HIGHEST CONCENTRATION Site Boundary [a] ResidencelDI Beta Air Dose (arad) 1.3E-1 7.7E-2 Gesuma Air Dose (arad) 4.9E-2 2.0E-2 i Beta + Gamma skin Dose (aren) 4.7E-2 Casuna Total Body Dose (aren) 1.7E-2 i (a) Maximum site boundary location. i (b] Maximum residence location. 1 i f t i l i t i 2-45 _ _ _.. _ ~. _ _ - _ _. _. _ _, _ _

TABLE 2.A.2-8 8 1 QUARTEP 1985 BATCH RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES 1 AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) ___=_ .===_ _-_-_ __ _= _ OTHER TOTAL ADULT INEANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS GARDEN (NNW SECTOR AT 965. METERS) AIR INHALATION 1.82E-05 1.82E-05 1.85E-05 2.22E-05 1.27E-04 1.83E-04 1.87E-05 EXPOSURE TO SOIL 1.82E-06 2.17E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 LEAFY VEGETABLE CONSUt1PTION 1.16E-05 1.16E-05 1.15E-05 3.20E-05 2.12E-04 0.0 1.21E-05 PRODUCE CONSUMPTION 6.03E-05 6.03E-05 6.02E-05 1.66E-04 6.49E-05 0.0 6.04E-05 TOTAL 9.19E-05 9.22E-05 9.20E-05 2.22E-04 4.06E-04 1.85E-04 9.29E-05 MEAT ANIMAL (NNW SECTOR AT 3379. METERS) AIR INHALATION 2.51E-06 2.51E-06 2.55E-06 3.06E-06 1.83E-05 2.65E-05 2.59E-06 EXPOSURE TO SOIL 1.98E-07 2.36E-07 1.98E-07 1.98E-07 1.98E-07 1.98E-07 1.98E-07 LEAFY VEGETABLE CONSUMPTION 1.47E-06 1.47E-06 1.46E-06 3.69E-06 2.33E-05 0.0 1.52E-06 o FRODUCE CONSUMPTION 7.70E-06 7.70E-06 7.69E-06 1.92E-05 8.20E-06 0.0 7.71E-06 MEAT CONSUMPTION 8.48E-07 8.48E-07 8.46E-07 1.08E-06 1.86E-06 0.0 8.51E-07 TOTAL 1.27E-05 1.28E-05 1.27E-05 2.72E-05 5.19E-05 2.67E-05 1.29E-05 MILK COW (NORTH SECTOR AT 8045. METERS 1 AIR INHALATION 8.09E-07 8.09E-07 8.22E-G7 9.87E-07 6.16E-06 8.95E-06 8.34E 77 EXFOSURE TO SOIL 4.48C-08 5.33E-08 4.48E-08 4.48E-08 4.48E-08 4.48E-08 4.48E-08 LEAFY VEGETABLE CONSUMPTION 4.26E-07 4.26E-07 4.26E-07 9.29E-07 5.36E-06 0.0 4.3SE-07 PRODUCE CONSUMPTION 2.25E-06 2.25E-06 2.25E-06 4.85E-06 2.36E-06 0.0 2.25E-06 MEAT CONSUMPTTON 2.89E-07 2.89E-07 2.88E-07 3.41E-07 5.17E-07 0.0 2.89E-07 COW MILK CONSUMPTION 7.19E-07 7.19E-07 7.15E-07 9.24E-07 8.44E-06 6.39E-05 7.37E-07 TOTAL 4.54E-06 4.55E-06 4.54E-06 8.07E-06 2.29E-05 7.29E-05 4.60E-06 MILK GOAT (SSE SECT 93 AT 2574. METERS) AIR INHALATION 2.21E-06 2.21E-06 2.24E-06 2.69E-06 1.59E-05 2.30E-05 2.27E-06 EXPOSURE TO SOIL 1.93E-07 2.29E-07 1.93E-07 1.93E-07 1.93E-07 1.93E-07 1.93E-07 LEAFY VEGETABLE CONSUMPTION 1.34E-06 1.34E-06 1.34E-06 3.51E-06 2.26E-05 0.0 1.39E-06 PRODUCE CONSUMPTION 7.02E-06 7.02E-06 7.01E-06 1.82E-05 7.51E-06 0.0 7.03E-06 MEAT CONSUMPTION 7.36E-07 7.36E-07 7.34E-07 9.62E-07 1.72E-06 0.0 7.38E-07 GOAT MILK CONSUMPTION 3.86E-06 3.86E-06 3.82E-06 5.70E-06 4.37E-05 3.30E-04 3.97E-06 TOTAL 1.54E-05 1.54E-05 1.53E-05 3.12E-05 9.16E-05 3.53E-04 1.56E-05

_-__-_-_---__-_-_____----______--__-____ =_ - =_ _-__-_-_-_-_--______-_-__=_

_==____________- - - _ = = _ = _ = - O O O

I TABLE 2.A.2-9 01 QUARTER 1985 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) __=.. _ = = _

==-- GTNER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATNNAY SODY SKIN LUNG SONE THYROID TMYROID ORGANS _==--.... _ =... CARDEN CNW SECTOR AT 965. ETERS) --- _ _ = _ _. AIR INNAIATION 7.67E-04 7.67E-04 8.49E-94 1.99E-03 S.10E-03 1.01E-02 7.81E-84 EXPOSURE TO SOIL 5.59E-05 6.79E-05 5.59E-05 5.59E-05 5.59E-05 5.59E-05 5.59E-05 LEAFY VEGETABLE CONSINSPTION 2.06E-03 2.06E-03 2.06E-03 7.90E-03 5.27E-02 0.0 2.12E-03 PRODUCE CONSUMPTION 1.06E-02 1.06E-02 1.06E-02 4.09E-02 1.23E-02 0.0 1.06E-02 T:l;TAL 1.35E-02 1.35E-02 1.35E-02 5.0SE-02 7.31E-02 1.01E-02 1.35E-02 NEAT ANIMAL (NNW SECTOR AT 3379. ETERS) AIR INNAIATION 1.01E-04 1.01E-04 1.12E-04 2.62E-04 1.12E-03 1.40E-03 1.03E-04 EXPOSURE TO SOIL 5.90E-06 7.17E-06 5.90E-06 5.90E-06 5.90E-06 5.90E-06 5.90E-06 LEAFY VEGETASLE CONSUMPTION 2.24E-04 2.24E-04 2.24E-04 S.41E-04 5.57E-03 0.0 2.32E-04 w PRODUCE CONSUMPTION 1.16E-03 1.16E-03 1.16E-03 4.35E-03 1.33E-03 0.0 1.16E-03 MEAT CONSUMPTION 4.89E-05 4.89E-05 4.89E-05 1.13E-04 4.07E-04 0.0 4.93E-05 TOTAL 1.54E-03 1.54E-03 1.55E-03 5.5SE-03 S.43E-03 1.40E-03 1.55E-03 MILK COW (NNW SECTOR AT 8045. E TERS) AIR INNALATION 2.SSE-05 2.SSE-05 3.18E-05 7.44E-05 3.32E-04 4.15E-04 2.93E-05 EXPOSURE TO SOIL 1.27E-06 1.55E-06 1.27E-06 1.27E-06 1.27E-06 1.27E-06 1.27E-06 LEAFY VEGETABLE CONSUMPTION 5.10E-05 5.10E-C5 5.10E-05 1.84E-04 1.20E-03 0.0 5.26E-05 PRODUCE CONSUMPTION 2.64E-04 2.64E-04 2.64E-04 9.53E-04 3.02E-04 0.0 2.64E-04 MEAT CONSUMPTIDF 1.32E-05 1.32E-05 1.32E-05 2.71E-05 9.05E-05 0.0 1.33E-05 COW MILK CONSL.. .ON 4.06E-05 4.96E-05 4.06E-05 9.44E-05 2.18E-03 1.64E-02 4.35E-05 TOTAL 3.98E-04 3.99E-04 4.02E-04 1.33E-03 4.115-03 1.68E-02 4.04E-04 MILK GOAT (SSE SECTOR AT 2574. E TERS) ---__ =___ ___ _ _ = - - - - - AIR INNALATION S.41E-05 S.41E-05 9.31E-05 2.18E-64 9.18E-64 1.14E-03 S.57E-05 EXPOSURE TO SOIL 5.59E-06 6.79E-06 5.59E-96 5.59E-06 5.59E-06 5.59E-06 5.59E-06 LEAFY VEGETABLE CONSUMPTION 2.09E-94 2.99E-04 2.09E-64 7.93E-04 5.27E-03 0.0 2.16E-04 FRODUCE CONSUMPTION 1.0SE-03 1.00E-03 1.0SE-03 4.10E-03 1.24E-03 0.0 1.0SE-03 MEAT CONSUMPTION 4.24E-05 4.24E-85 4.24E-05 1.84E-84 3.82E-04 0.0 4.29E-05 GOAT MILK CONSUMPTION 2.80E-04 2.80E-94 2.80E-04 7.72E-04 1.16E-02 S.67E-02 2.95E-04 TOTAL 1.70E-03 1.76E-03 1.71E-03 6.00E-03 1.94E-02 S.78E-02 1.72E-03

l TABLE 2.A.2-10 B 1 QUARTER 1985 BATCH + CONTINUOUS RELEASES DOSES FROM CASEOUS EFTLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OTFSITE EXPOSURE LOCATIONS. (MREMI _ _ _ _ _ _ _ = -. _ _ _ _ _ _ _ _ _ _ = OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE TitYROID TilYROID ORGANS GARDEN MAXIMUM LOCATION AIR INHALATION 7.35E-04 7.85E-04 8.67E-04 2.01E-03 8.23E-03 1.03E-02 8.00E-04 EXPOSURE TO SOIL 5.77E-05 7.01E-05 5.77E-05 5.77E-05 5.77E-05 5.77E-05 5.77E-05 LEAFY VEGETABLE CONSUMPTION 2.07E-03 2.07E-03 2.07E-03 7.93E-03 5.29E-02 0.0 2.13E-03 PRODUCE CONSUMPTION 1.07E-02 1.07E-02 1.07E-02 4.11E-02 1.24E-02 0.0 1.07C-02 TCTAL 1.36E-02 1.36E-02 1.36E-02 5.10E-02 7.35E-02 1.03E-02 1.36E-02 MEAT ANIMAL MAXIMUM LOCATION AIR INHALATION 1.04E-04 1.04E-04 1.15E-04 2.65E-04 1.14E-03

1. 43 a'-0 3 1.06E-04 EXPOSURE TO SOIL 6.10E-06 7.41E-06 6.10E-06 6.10E-06 6.10E-06 6.10E-06 6.10E-06 LEAFY VEGETABLE CONSUMPTION 2.25E-04 2.25E-04 2.25E-04 8.45E-04 5.59E-03 0.0 2.34E-04 N

PRODUCE CONSUMPTION 1.17E-03 1.17E-03 1.17E-03 4.37E-03 1.34E-03 0.0 1.17E-03 S MEAT CONSUMPTIGN 4.97E-05 4.97E-05 4.97E-05 1.14E-04 4.09E-04 0.0 5.02E-05 TCTAL 1.55E-03 1.55E-03 1.56E-03 5.61E-03 8.48E-03 1.43E-03 1.56E- 03 MILK COW MAXIMUd LOCATION AIR INHALATION 2.96E-05 2.96E-05 3.26E-05 7.54E-05 3.38E-04 4.24E-04 3.01E-05 EXPOSURE TO SOIL 1.31E-06 1.60E-06 1.31E-06 1.31E-06 1.31E-06 1.31E-06 1.31E-06 LEAFY VEGETABLE CONSUMPTION 5.14E-05 5.14E-05 5.14E-05 1.85E-04 1.21E-03 0.0 5.30E-05 PRODUCE CONSUMPTION 2.66E-04 2.66E-04 2.66E-04 9.58E-04 3.04E-04 0.0 2.66E-04 MEAT CONSUMPTION 1.35E-05 1.35E-05 1.35E-05 2.74E-05 9.10E-05 0.0 1.36E-05 COW MILK CONSUMPTION 4.13E-05 4.13E-05 4.13E-05 9.53E-05 2.19E-03 1.65E-02 4.42E-05 TCTAL 4.03E-04 4.04E-04 4.07E-04 1.34E-03 4.13E-03 1.69E-02 4.09E-04 MILK GOAT MAXIMUM LOCATION AIR INHALATION 8.63E-05 8.63E-05 9.53E-05 2.21E-04 9.34E-04 1.16E-03 8.80E-05 EXPOSURE TO SOIL 5.78E-06 7.02E-06 5.78E-06 5.78E-06 5.78E-06 5.78E-06 5.78E-06 LEAFY VEGETABLE CONSUMPTION 2.10E-04 2.10E-04 2.10E-04 7.97E-04 5.29E-03 0.0 2.17E-04 PRODUCE CONSUMPTION 1.09E-03 1.09E-03 1.09E-03 4.12E-03 1.25E-03 0.0 1.09E-03 MEAT CONSUMPTION 4.31E-05 4.31E-05 4.31E-05 1.05E-04 3.84E-04 0.0 4.36E-05 COAT MILK CONSUMPTION 2.84E-04 2.84E-04 2.84E-04 7.78E-04 1.16E-02 8.70E-02 2.99E-04 TOTAL 1.72E 1.72E-03 1.73E-03 6.03E-03 1.95E-02 8.82E-02 1.74E-03 =_____-03

= ______=-

e O O

i 3 I 4 1 i i TABLE 2.A.2-Il FIRST GUARTER 1985 RATCH + CONTINUOUS RELEASES POPULATION DOSE (SS-MILE) FROM GASEOUS EFFLUENTS ] (MAN-REM) .i l EXPOSURE PATWWAY TOTAL BODY THYROID ] AIR SUBfERSION 4.7E-02 4.7E-02 i AIR INNALATION 3.0E-03 3.2E-02 w EXPOSURE TO SOIL S.6E-05 S.6E-05 i L LEAFY VEGETABLE CONSINIPTION 1.0E-04 2.4E-03 e PRODUCE CONSUMPTION 5.4E-04 6.1E-04 MEAT CONSUptPTION 2.4E-04 1.4E-03 MILE CONSUMPTION 2.9E-03 1.6E-01 I TOTAL 5.4E-02 2.4E-01 AVERAGE DOSE (PNtEN/ PERSON) 2.6E-05 1.2E-04 i l _===.............................. 4 1 1 1 3 I i 1 1 I l ?~ i ?

I TABLE 2.A.2-12 8 2 QUARTER 1985 DOSES FROM LIQUID EFFLUENTS (MREM) - - - -. =___--___--_----------_ _ - - _ - - - - - - - - _ _ _ _ - - - - - = - - - - _ _ _ OTHER TOTAL ADULT INTANT INTERNAL EXPOSURE PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS = _ = = _ _ __._ AQUATIC AT MAXIMUM LOCATION _ _ _ _ _ - - = - - _ DRINKING WATER 1.8E-05 1.8E-05 1.4E-05 1.8E-05 3.4E-05 7.2E-05 2.6E-05 FISH CONSUMPTION 1.2E-03 1.2E-03 1.8E-04 9.0E-04 1.2E-03 0.0 6.5E-04 INVERTEBRATE CONSUMPTION 1.6E-04 1.6E-04 3.8E-05 1.4E-04 1.6E-04 0.0 3.1E-04 EXPOSURE TO SHORELINE SEDIMENT 9.7E-07 1.1E-06 9.7E-07 9.7E-07 9.7E-07 0.0 9.7E-07 SWIMMING AND DOATING 5.0E-08 5.8E-08 5.0E-08 5.0E-08 5.0E-08 0.0 5.0E-08 AQUATIC TOTAL 1.4E-03 1.4E-03 2.3E-04 1.1E-03 1.4E-03 7.2E-05 9.9E-04 - - - - - - - - - - - - - - = - _ - - = - = - - - - - - ---------- AQUATIC AT AGRICULTURAL LOCATION c, --__--_ --- =_--- - DRINKING WATER 1.8E-05 1.8E-05 1.4E-05 1.8E-05 3.4E-05 7.2E-05 2.6E-05 FISH CONSUMPTION 2.6E-04 2.6E-04 4.0E-05 2.0E-04 2.7E-04 0.0 1.4E-04 INVERTEBRATE CONSUMPTION 3.4E-05 3.4E-05 8.4E-06 3.0E-05 3.5E-05 0.0 6.8E-05 EXPOSURE TO S'IORELINE SEDIMENT 9.7E-07 1.1E-06 9.7E-07 9.7E-07 9.7E-07 0.0 9.7E-07 SWIMMING AND BOATING 1.1E-08 1.3E-08 1.1E-08 1.1E-08 1.1E-08 0.0 1.1E-08 IRRIGATION AND LIVESTOCK WATERING EXPOSURE TO AGRICULTURAL SOIL 1.3E-05 1.5E-05 1.3E-05 1.3E-05 1.3E-05 0.0 1.3E-05 LEAFY VEGETABLE CONSUMPTION 3.8E-06 3.8E-06 1.8E-06 3.6E-06 1.6E-05 0.0 7.5E-06 FRODUCE CONSUMPTION 1.EE-05 1.8E-05 8.8E-06 1.8E-05 1.9E-05 0.0 3.4E-05 MEAT CONSUMPTION 5.4E-06 5.4E-06 1.IE-05 9.0E-06 6.3E-06 0.0 2.6E-04 MILK CONSUMPTION (COW) 2.3E-05 2.3E-05 8.7E-06 1.9E-05 4.8E-05 2.2 -04 8.6E-06 MILK CONSUMPTION (GOAT) 6.4E-05 6.4E-05 2.1E-05 5.3E-05 9.5E-05 3.1E-04 1.5E-05 AGRICULTURAL TOTAL EXCLUDING COW MILK CONSUMPTION 4.2E-04 4.2E-04 1.2E-04 3.4E-04 4.9E-04 3.8E-04 5.7E-04 EXCLUDING GUAT MILK CONSUMPTION 3.8E-04 3.8E-04 1.1E-04 3.1E-04 4.4E-04 2.9E-04 5.6E-04 =_= =--------=-_=-- _ _ - _ _ = = - __ ---__. _ - - - - = - - - -= _ -----_ ~ e O O

N TABLE 2.A.2-13 SECOND QUARTER 1905 POPUIATION DOSE (50-MILE) FRON LIQUID EFFLUENTS fF.AN-REM) EXPostRE PATIAdAY TOTAL 300Y TNYROID AQUATIC DRINKING WATER 7.2E-05 1.4E-04 FISN CONSUMPTION 1.1E-01 1.2E-01 INVERTEBRATE CONSINIPTIDIf 6.SE-05 6.9E-05 4 N EXPOSURE TO COIITAMINATED SEDIfENT 2.2E-05 2.2E-05 SWIINIING AllD BOATIlls 1.3E-07 1.3E-07 IRRIGATIDIf AIID LIVESTOCK MATERING LEAFY VEGETAstZ C00fSMION 2.9E-07 1.2E-06 PRODUCE COIISLNIFTIOli 1.4E-06 1.4E-06 MEAT CONSLMPTIcIl 7.5E-06 S.7E-06 MILK COISSUMPTIDIf 1.2E-04 2.6E-04 EXPOSURE TO COIITAMINATED SOIL 1.8E-06 1.8E-06 TOTAL 1.1E-01 1.2E-01 AVERAGE DOSE (INtEN/ pelts 0ll) 5.5E-05 5.7E-05 G e e

TABLE 2.A.2-14 SECOND QUARTER 1985 BATCH RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HICHEST CONCENTRATION Site Boundary [a] Residenee(b) Beta Air Dose (mead) 4.5E-2 2.5E-2 Cansna Air Dose (mrad) 1.6E-2 6.1E-3 Beta + Canuna Skin Dose (mram) 1.5E-2 Cansna Tota) Body Dose (mrem) 5.1E-3 (a] North sector at 663 meters. (b) North sector at 965 meters. O 2-52

. _ _ = t TABLE 2.A.2-15 SECOND QUARTER 1985 CONTINUOUS RELEASES I DOSES FRON NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION i e Site Boundarv[a] ResidenceIDI Beta Air Dose (arsd) 1.2E-2 7.0E-3 Casuna Air Dose (mead) 5.0E-3 2.0E-3 4 Beta + Gesuma Skin Dose (area) 4.6E-3 Gamma Total Body Dose (stem) 1.73-3 i [a] North sector at 663 meters. [b] North sector at 965 meters. O 4 1 .J I i i 2-53 I ,-.-._,r._-_ ,,_,._,..y-y,_ m,-,_.,.___.,_,y_._.

TABLE 2. A.2-16 l SECOND QUARTER 1985 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESICEGCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI ) Beta Air Dose (mrad) 5.7E-2 3.2E-2 Gamma Air Dose (mrad) 2.1E-2 8.1E-3 Beta + Gamma Skin Dose (arem) 1.9E-2 Camma Total Dody Dose (mrem) 6.9E-3 [a] Maximum site boundary location. [b] Maximum residence location. O O 2-54

i .1 TABLE'--.. A. 2-17 82 QUARTER 1985 BATCH RELEASES i DOSES FROM GASEOUS EFFLUENTS (EXCLUDING l NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) =- OTHER l TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS

=

- __ =-- GARDEN 4 (NNW SECTOR AT 965. METERS) AIR INHALATION 2.82E-04 2.82E-04 2.84E-04 2.82E-04 6.50E-04 6.06E-04 2.83E-04 EXPOSURE TO SOIL 1.07E-04 1.26E-04 1.07E-04 1.07E-04 1.07E-04 1.07E-04 1.07E-04 I LEAFY VEGETABLE CONSUMPTION 8.79E-05 8.79E-05 8.54E-05 8.96E-05 3.64E-03 0.0 9.40E-05 PRODUCE CONSUMPTION 4.42E-04 4.42E-04 4.29E-04 4.44E-04 5.62E-04 0.0 4.50E-04 I TOTAL 9.19E-04 9.38E-04 9.05E-04 9.23E-04 4.96E-03 7.13E-04 9.34E-04 MEAT ANIMAL l (SOUTH SECTOR AT 2735. METERS) AIR INHALATION 8.45E-05 8.45E-05 8.50E-05 8.45E-05 1.99E-04 1.87E-04 8.47E-05 i EXPOSURE TO SOIL 4.65E-05 5.45E-05 4.65E-05 4.65E-05 4.65E-05 4.65E-05 4.65E-05 J LEAFY VEGETABLE CONSUMPTION 2.93E-05 2.93E-05 2.82E-05 3.00E-05 1.57E-03 0.0 3.19E-05 N PRODUCE CONSUMPTION 1.44E-04 1.44E-04 1.38E-04 1.45E-04 1.96E-04 0.0 1.47E-04 l & MEAT CONSUMPTION 2.72E-05 2.72E-05 2.64E-05 2.74E-05 1.32E-04 0.0 2.78E-05 i u TOTAL 3.31E-04 3.39E-04 3.24E-04 3.33E-04 2.14E-03 2.33E-04 3.38E-04 4 MILK COW (SSE SECTOR AT 8045. METERS) = _ _ - - _ = = _ _ - - _ l AIR INHALATION 1.86E-05 1.86E-05 1.87E-05 1.86E-05 4.53E-05 4.31E-05 1.86E-05 1 EXPOSURE TO SOIL 7.60E-06 8.92E-06 7.60E-06 7.60E-06 7.60E-06 7.60E-06 7.60E-06 i LEAFY VEGETABLE CONSUMPTION 6.86E-06 6.86E-06 6.69E-06 6.98E-06 2.59E-04 0.0 7.30E-06 j PRODUCE CONSUMPTION 3.48E-05 3.48E-05 3.38E-05 3.49E-05 4.33E-05 0.0 3.54E-05 3 MEAT CONSUMPTION 6.58E-06 6.58E-06 6.45E-06 6.61E-06 2.38E-05 0.0 6.68E-06 COW MILK CONSUMPTION 1.72E-05 1.72E-05 1.61E-05 1.75E-05 4.89E-04 3.64E-03 1.85E-05 TOTAL 9.15E-05 9.29E-05 8.93E-05 9.22E-05 8.68E-04 3.69E-03 9.40E-05 1 MILK GOAT 4 (SSE SECTOR AT 2574. METERS 3

=====_ = _ -

J AIR INHALATION 1.14E-04 1.14E-04 1.14E-04 1.14E-04 2.67E-04 2.51E-04 1.14E-04 EXPOSURE TO SDIL 5.72E-05 6.71E-05 5.72E-05 5.72E-05 5.72E-05 5.72E-05 5.72E-05 .i LEAFY VEGETABLE CONSUMPTION 3.89E-05 3.89E-05 3.76E-05 3.98E-05 1.94E-03 0.0 4.21E-05 PRODUCE CONSUMPTION 1.93E-04 1.93E-04 1.85E-04 1.94E-04 2.56E-04 0.0 1.97E-04 4 MEAT CONSUMPTION 3.64E-05 3.64E-05 3.54E-05 3.66E-05 1.66E-04 0.0 3.71E-05 l GOAT MILK CONSUMPTION 2.05E-04 2.05E-04 1.80E-04 2.10E-04 9.47E-03 3.30E-02 2.26E-04 1 l TOTAL 6.44E-04 6.53E-04 6.10E-04 6.51E-04 7.15E-03 3.33E-02 6.74E-04 _-_ ___=- _ =___- -_-- __ =- ___ --------=_ _ r

TABl.E 2.A.2-18 82 QUARTER 1985 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = - - _ _ _ _ _ _ _ _ _ _ = - _ _ _ _ - - - - = = - _ _ ____=-. OTl!ER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID TilYROID ORGANS GARDEN (NNW SECTOR AT 965. METERS) AIR INHALATION 1.63E-04 1.63E-04 1.63E-04 1.64E-04 1.33E-03 1.60E-03 1.65E-04 EXPOSURE TO SOIL 6.56E-05 7.71E-05 6.56E-05 6.56E-05 6.56E-05 6.56E-05 6.56E-05 LEAFY VEGETABLE CONSUMPTION 6.81E-05 6.81E-05 6.53E-05 7.34E-05 1.12E-02 0.0 8.49E-05 PRODUCE CONSUMPTION 2.64E-04 2.64E-04 2.48E-04 2.68E-04 6.34E-04 0.0 2.74E-04 TOTAL 5.61E-04 5.72E-04 5.42E-04 5.71E-04 1.32E-02 1.67E-03 5.90E-04 MEAT ANIMAL (SOITTH SECTOR AT 2735. METERS) AIR INHALATION 4.09E-05 4.09E-05 4.09E-05 4.11E-05 3.44E-04 4.15E-04 4.15E-05 EXPOSURE TO SOIL 2.19E-05 2.57E-05 2.19E-05 2.19E-05 2.19E-05 2.19E-05 2.19E-05 LEAFY VEGETABLE CONSUMPTION 1.98E-05 1.98E-05 1.88E-05 2.15E-05 3.73E-03 0.0 2.54E-05 PRODUCE CONSUMPTION 7.20E-05 7.20E-05 6.69E-05 7.35E-05 1.96E-04 0.0 7.55E-05

d. MEAT CONSUMPTION 1.37E-05 1.37E-05 1.30E-05 1.39E-05 2.64E-04 0.0 1.45E-05 e

TOTAL 1.68E-04 1.72E-04 1.61E-04 1.72E-04 4.56E-03 4.37E-04 1.79E-04 MILK COW tSSE SECTOR AT 8045. METERS) AIR INHALATION 8.67E-06 8.67E-06 8.66E-06 8.72E-06 7.71E-05 9.33E-05 8.80E-06 EXPOSURE TO SOIL 3.28E-06 3.85E-06 3.28E-06 3.28E-06 3.28E-06 3.28E-06 3.28E-06 LEAFY VEGETABLE CONSUMPTION 4.02E-06 4.02E-06 3.88E-06 4.28E-06 5.61E-04 0.0 4.86E-06 PRODUCE CONSUMPTION 1.65E-05 1.65E-05 1.57E-05 1.67E-05 3.50E-05 0.0 1.70E-05 !! EAT CONSUMPTION 3.14E-06 3.14E-06 3.03E-06 3.17E-06 4.07E-05 0.0 3.26E-06 COW MILK CONSUMPTION 9.85E-06 9.85E-06 8.95E-06 1.04E-05 1.05E-03 7.92E-03 1.18E-05 TOTAL 4.55E-05 4.61E-05 4.35E-05 4.66E-05 1.76E-03 8.01E-03 4.90E-05 MILK GOAT (SSE SECTOR AT 2574. METERS) AIR INHALATION 5.27E-05 5.27E-05 5.26E-05 5.30E-05 ~ 4.43E-04 5.34E-04 5.34E-05 EXPOSURE TO SOIL 2.45E-05 2.88E-05 2.45E-05 2.45E-05 2.45E-05 2.45E-05 2.45E-05 LEAFY VEGETABLE CONSUMPTION 2.42E-05 2.42E-05 2.31C-05 2.61E-05 4.18E-03 0.0 3.05E-05 PRODUCE CONSUMPTION 9.17E-05 9.17E-05 8.59E-05 9.33E-05 2.30E-04 0.0 9.55E-05 MEAT CONSUMPTION 1.75E-05 1.75E-05 1.66E-05 1.77E-05 2.98E-04 0.0 1.83E-05 GOAT MILK CONSUMPTION 1.18E-04 1.18E-04 9.74E-05 1.24E-04 9.41E-03 7.10E-02 1.43E-04 TOTAL 3.28E 04 3.32E 3.00E-04 3.39E-04 1.46E-02 7.15E-02 3.65E-04 =_____________________________________-04 ________= e O O

O O O TABLE 2.A.2-19 92 QUARTER 1985 BATCH + CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (""E"!_ __=- =__ - __ ______ ___ __....-..=== OTHER I TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS = -= GARDEN MAXIMUM LOCATION =_ 1 AIR INHALATION 4.45E-04 4.45E-04 4.47E-04 4.46E-04 1.98E-03 2.21E-03 4.48E-04 EXPOSURE TO SOIL 1.73E-04 2.03E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 LEAFY VEGETABLE CONSUMPTION 1.56E-04 1.56E-04 1.51E-04 1.63E-04 1.48E-02 0.0 1.79E-04 i PRODUCE CONSUMPTION 7.06E-04 7.06E-04 6.77E-04 7.12E-04 1.20E-03 0.0 7.24E-04 TOTAL 1.48E-03 1.51E-03 1.45E-03 1.49E-03 1.82E-02 2.38E-03 1.52E-03 MEAT ANIMAL MAXIMUM LOCATION AIR INHALATION 1.25E-04 1.25E-04 1.26E-04 1.26E-04 5.43E-04 6.02E-04 1.26E-04 EXPOSURE TO SOIL 6.84E-05 8.02E-05 6.84E-05 6.84E-05 6.84E-05 6.84E-05 6.84E-05 LEAFY VEGETABLE CONSUMPTION 4.91E-05 4.91E-05 4.70E-05 5.15E-05 5.30E-03 0.0 5.73E-05 i Y PRODUCE CONSUMPTION 2.16E-04 2.16E-04 2.05E-04 2.19E-04 3.92E-04 0.0 2.22E-04 $ MEAT CONSUMPTION 4.09E-05 4.09E-05 3.94E-05 4.13E-05 3.96E-04 0.0 4.23E-05 l TOTAL 4.99E-04 5.11E-04 4.85E-04 5.05E-04 6.70E-03 6.70E-04 5.17E-04 MILK COW MAXIMUM LOCATION . ----..---..--=_ __ AIR INHALATION 2.73E-05 2.73E-05 2.74E-05 2.73E-05 1.22E-04 1.36E-04 2.74E-05 l EXPOSURE TO SOIL 1.09E-05 1.28E-05 1.09E-05 1.09E-05 1.09E-05 1.09E-05 1.09E-05 l LEAFY VEGETABLE CONSUMPTION 1.09E-05 1.09E-05 1.06E-05 1.13E-05 8.20E-04 0.0 1.22E-05, PRODUCE CONSUMPTION 5.13E-05 5.13E-05 4.95E-05 5.16E-05 7.83E-05 0.0 5.24E-05 MEAT CONSUMPTION 9.72E-06 9.72E-06 9.48E-06 9.78E-06 6.45E-05 0.0 9.94E-06 f COW MILK CONSUMPTION 2.70E-05 2.70E-05 2.51E-05 2.79E-05 1.54E-03 1.16E-02 3.03E-05 j TOTAL 1.37E-04 1.39E-04 1.33E-04 1.39E-04 2.63E-03 1.17E-02 1.43E-04 MILK GOAT I MAXIMUM LOCATION AIR INHALATION 1.67E-04 1.67E-04 1.67E-04 1.67E-04 7.10E-04 7.85E-04 1.67E-04 EXPOSURE TO SOIL 8.17E-05 9.59E-05 8.17E-05 8.17E-05 8.17E-05 8.17E-05 8.17E-05 LEAFY VEGETABLE CONSUMPTION 6.31E-05 6.31E-05 6.07E-05 6.59E-05 6.12E-03 0.0 7.26E-05 PRODUCE CONSUMPTION 2.85E-04 2.85E-04 2.71E-04 2.87E-04 4.86E-04 0.0 2.92E-04 l NEAT CONSUMPTION 5.39E-05 5.39E-05 5.20E-05 5.43E-05 4.64E-04 0.0 5.54E-05 { GOAT MILK CONSUMPTION 3.23E-04 3.23E-04 2.77E-04 3.34E-04 1.39E-02 1.04E-01 3.69E-04 TOTAL 9.72E 9.85E-04 9.10E-04 9.90E-04 2.18E-02 1.05E-01 1.04E-03 ._..._ -04 1 - ____=.............--........ -............ 1 1

I TABLE 2.A.2-20 SECOND QUARTER 1985 BATCH + CONTINUOUS RELEASES POPULATION DOSE (50-MILE) FROM GASEOUS EFFLUENTS (MAN-REM) _=- EXPOSURE PATHWAY TOTAL BODY THYROID _____ :__- ---- -- ___= AIR SUBMERSION 2.4E-02 2.4E-02 AIR INIMLATION 3.4E-03 1.5E-02 N EXPOSURE TO SOIL 6.7E-04 6.7E-04 LEAFY VEGETABLE CONSUMPTION 3.1E-05 1.7E-03 cn PRODUCE CONSUMPTION 1.5E-04 2.1E-04 !! EAT CONSUMPTION 2.3E-04 1.1E-03 MILK CONSUMPTION 2.5E-03 1.2E-01 TOTAL 3.1E-02 1.6E-01 AVERAGE DOSE (MREM / PERSON) 1.5E-05 7.7E-05 - _ = _==- _ _ = _ - - _ G e e O ~ O

1 O TABLE 2.A.2-21 Sheet 1 of 2 i PARANETERS USED IN CALCULATING DOSES FRON GASEOUS EFFLUENTS (Second Half 1985) Parameter Value Accumulation and Decay Times (days) Harvest of leafy vegetables to constssption 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 Estes (m fye) 3 Adult 8,000.0 Infant 1,400.0 l Animal Consumption Rates (kg/ day) ,j Animal feed by seat animal 50.0 l Animal feed by milk cow 50 0 Animal feed by milk goat 6.0 Exposure Periods During Crowing Season (days) Leafy vegetables 60.0 Pasture vegetation 4 30.0 Produce 60.0 i Residential Structure Shielding Factor 0.7 Fraction of Particulates Initially beyosited on Leafy Vegetation 0.2 Fraction of Particulates Initially Deposited on Produce 0.2 i Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m ) 240.0 2 i Field Decay Half Life (days) 14.0 i

O 2-59 1

t i

1 TABLE 2.A.2-21 Sheet 2 of 2 Parameter Value 2 Agricultural Productivity (kg/m ) Leafy vegetables 2.0 Pasture grass 0.7 Produce 2.0 Period of Long-Term Buildup for Activity in soil (days) 7.300.0 Fraction of Leafy Vegetables Crown in Garden of Interest 1.0 Fraction of Produce Crown in Carden of Interest 0.76 Fraction of Year Animal Crazes on Pasture 0.5 Fraction of Daily Feed that is Pasture Crass when Animal Grazes 1.0 0 O 2-60

TABLE 2.A.2-22 She:t 1 of 2 PARAMETERS USED IN CALCULATING DOSES O FRON LIQUID EFFLUENTS Value Parameter 3rd Otr 1985 4th Otr 1985 Plant Dilution Flow Rate (spm) 29,308.7 28,725.2 Columbia River Flow Rate (cfs) 131,649.0 144,794.0 Dilution Factors Drinking water 2,016.0 2,262.0 Swimming water 444.0 498.0 Aquatic biota 444.0 498.0 i Shoreline sediment 444.0 498.0 Irrigation water 2,016.0 2,262.0 Milk and meat animal water 2,016.0 2,262.0 i Decay Times (days) Discharge to drinking water 0.76 0.74 Discharge to swimming water 0.0 0.0 Discharge to aquatic biota consumption 1.0 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 Discharge to irrigation water withdrawal 0.76 0.74 Discharge to alik and meat animal water 0.76 0.74 withdrawal Leafy vegetable harvest to consumption by man 1.0 Ov 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 pastureland 310.0 Goat's alik 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 2-61

TABLE 2.A.2-22 Sheet 2 of 2 O Value Parameter 3rd Otr 1985 4th Otr 1985 Infant Consumption Rates (kg/yr) Drinking water 330.0 Cow's alik from irrigated pastureland 330.0 Fraction of Year Animals craze on Pasture 0.5 Fraction of Year crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14.0 2 Irrigation Rate (liters /m -hr) 0.104 Fractional Concentration of Water in Soil (g/s) 0.2 Fraction of Leafy Vegetables Crown in Carden of 1.0 Interest Fraction of Produce Crown in Carden of Interest 0.7 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by Leafy Vegetables Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by Produce 2 Pasture Crass Yield (kg/m ) o,7 2 Vegetable Yield (kg/m ) 2.0 2 Surface Density of Soil (kg/m ) 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 5511k.286 2-62

_~ _.. TABLE 2.A.2-23 i 0 3 QUARTER 1985 1 l DOSES FROM LIQUID EFTLUENTS (MREM) 1 1 i l; OTNER j TOTAL ADULT INFANT INTERNAL j EXPOSURE PATNWAY BODY SKIN LUNG SONE THYROID THYROID ORGANS AQUATIC AT MAXIM (Nt TION DRINKING WATER 3.0E-05 3.0E-05 2.6E-05 3.1E-05 3.4E-05 4.8E-05 5.8E-05 FISH CONSUMPTION 1.4E-03 1.4E-03 2.1E-04 1.1E-03 1.4E-03 0.0 8.6E-04 INVERTE8 RATE CONSIDIPTION 1.9E-04 1.9E-04 5.8E-05 1.8E-04 1.9E-04 0.0 7.1E-04 EXPOSURE TO SNORELINE SEDI!ENT 1.0E-05 1.2E-05 1.0E-05 1.0E-05 1.0E-05 0.0 1.0E-05 SWIMMING AND 80ATING 1.0E-07 1.1E-07 1.0E-07 1.0E-07 1.0E-07 0.0 1.0E-07 AQUATIC TOTAL 1.6E-03 1.6E-03 3.1E-04 1.3E-03 1.6E-03 4.8E-05 1.6E-03 Y e AQUATIC AT AGRICULTURAL LOCATION w DRINKING WATER 3.0E-05 3.0E-05 2.6E-05 3.1E-05 3.4E-05 4.8E-05 5.8E-05 FISH CONSUMPTION 3.0E-04 3.0E-04 4.7E-05 2.3E-04 3.0E-04 0.0 1.9E-04 INVERTEBRATE CONSUMPTION 4.2E-05 4.2E-05 1.3E-05 3.9E-05 4.3E-05 P.0 1.6E-04 EXPOSURE TO SNORELINE SEDIfENT 2.3E-06 2.7E-06 2.3E-06 2.3E-06 2.3E-06 4.0 2.3E-06 1 SWIMrtING AND 80ATING 2.2E-08 2.3E-08 2.2E-08 2.2E-08, 2.2E-08 0.G 2.2E-08 IRRIGATION AND LIVESTOCK WATERING =_ i EXPOSURE TO AGRICULTURAL SOIL 3.0E-05 3.6E-05 3.0E-05 3.0E-05 3.0E-05 0.0 3.0E-05 I LEAFY VEGETA8LE CONSUMPTION 5.7E-06 5.7E-06 3.4E-06 6.2E-06 7.8E-06 0.0 2.0E-05 PRODUCE CONSUMPTION 2.8E-05 2.8E-05 1.7E-05 3.1E-05 2.8E-05 0.C 8.9E-05 i MEAT CONSUMPTION 9.5E-06 9.5E-06 2.9E-05 2.0E-05 9.7E-06 0.0 7.7E-04 MILE CONSUMPTION (COW 1 3.1E-05 3.1E-05 1.4E-05 2.7E-05 3.5E-05 8.3E-05 1.9E-05 MILE CONSUMPTION (GOAT 3 8.4E-05 8.4E-05 3.3E-05 7.1E-05 8.9E-05 1.5E-04 2.6E-05 l 1 AGRICULTURAL TOTAL EXCLUDING COW MILK CONStMPTION 5.4E-04 5.4E-04 2.0E-04 4.6E-04 5.5E-04 2.0E-04 1.3E-03 = EXCLUDING GOAT MILE CONSUrtPTION 4.8E-04 4.9E-04 1.8E-04 4.2E-04 5.0E-04 1.3E-04 1.3E-03 1 i j j.

I TABLE 2.A.2-24 THIRD QUARTER 1985 POPUIATION DOSE (50-MILE) FROM LIQUID EFTLUENTS (MAN-REM)

==__. EXPOSURE PATHWAY TOTAL BODY THYROID

____

AQUATIC DRINKING WATER 1.2E-04 1.4E-04 FISH CONSLHPTION 1.3E-01 1.3E-01 INVERTEBRATE CONSUMPTION 8.5E-05 8.5E-05 7 EXPOSURE TD CONTAMINATED SEDIMENT 5.2E-05 5.2E-05 g SWIMMING AND SOATING 2.6E-07 2.6E-07 IRRIGATION AND LIVESTOCK WATERING LEAFY VEGETABLE CONSUMPTION 4.4E-07 6.0E-07 FRODUCE CONSUMPTION 2.1E-06 2.1E-06 MEAT CONSLMPTION 1.3E-05 1.3E-05 MILE CONSUMPTION 1.6E-G, 1.9E-04 EXPOSURE TO CONTAMINATED SOIL 4.4E-06 4.4E-06 TOTAL 1.3E-01 1.3E-01 AVERAGE DOSE (MREM / PERSON) 6.4E-05 6.4E-05 .=__. _ _=_._= _ M e O O

i TABLE 2.A.2-25 THIRn QUARTER 1985 BATCH RELEASES DOSES FRON NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION SLte BoundarYI8I Residenet!bI Beta Air Dose (mead) 2.1E-2 1.2E-2 Gamuna Air Dose (arad) 7.6E-3 3.1E-3 Bets + Gesuna Skin Dose (aren) 7.5E-3 Gamma Total Body Dose (area) 2.7E-3 l [a] East sector at 677 meters. [b] East sector at 965 meters. I i I l i t 2-65 h

_ TABLE 2.A.2-26 THIRD QUARTER 1985 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HICHEST CONCENTRATION Site Boundary (a) p.,to.ne.(b) Beta Air Dose (arad) 2.7E-2 1.1E-2 Camma Air Dose (mead) 1.3E-2 3.8E-3 Beta + Canuna Skin Dose (mrom) 9.0E-3 Camma Total Body Dose (mrom) 3.4E-3 [a] ENE sector at 688 meters. (b) East sector at 965 meters. O O 2-66

-_- - _.-. -- - - -. - = - - i TABLE 2.A.2-27 THIRD QUARTER 1945 i BATCH + CONTINUOUS RELEASES l Dosts FRon mosLE casts AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION site BoundaryI*I Residenselb) ] Beta Air Dose (arad) 4.8E-2 2.35-2 I Camma Air Dose (arad) 2.1E-2 6.9E-3 i Beta + Gamma Skin Dose (area) 1.75-2 Gemma Total Body Dose (area) 6.15-3 c \\ [a} Maximum site boundary location. l (b) Maximum residence location. l l l l 1 l l J 4 l i i t j i i 2-67 I ) I

TABLE 2.A.2-28 83 QUARTER 1985 BATCH RELEASES DOSES FROM GASEOUS EFTLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) .= TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY B3DY SKIN LUNG BONE THYROID THYROID ORGANS --- =--_ ---=- GARDEN (NNW SECTOR AT 965. METERS)

==---- AIR INHALATION 1.31 E -J 5 1.31E-05 1.32E-05 1.41E-05 1.70E-05 1.19E-05 1.31E-05 EXPOSURE TO SOIL 4.83E-07 5.68E-07 4.83E-07 4.83E-07 4.83E-07 4.83E-07 4.83E-07 LEAFY VEGETABLE CONSLMPTION 5.43E-06 5.43E-06 5.43E-06 1.11E-G5 3.68E-05 0.0 5.48E-06 PRODUCE CONSUMPTION 2.91E-05 2.91E-05 2.90E-05 5.83E-05 3.01E-05 0.0 2.91E-05 T^TAL 4.81E-05 4.82E-05 4.81E-05 8.39E-05 8.43E-05 1.23E-05 4.82E-05 MEAT ANIMAL (SOUTH SECTOR AT 2735. METERS 1

-=_ __

AIR INHAIATION 3.89E-06 3.89E-06 3.91E-06 4.17E-06 5.0E0-06 3.57E-06 3.89E-06 EXPOSURE TO SOIL 2.41E-07 2.84E-07 2.41E-07 2.41E-07 2.41E-07 2.41E-07 2.41E-07 u LEAFY VEGETABLE CONSLHPTION 2.05E-06 2.05E-06 2.05E-06 4.87E-06 1.77E-05 0.0 2.0BE-06 s FRODUCE CONSUMPTIOh 1.09E-05 1.09E-05 1.09E-05 2.56E-05 1.14E-05 0.0 1.09E-05 $ MEAT CONSLMPTION 1.29E-06 1.29E-06 1.29E-06 1.59E-06 2.34E-06 0.0 1.29E-06 !..at 1.84E-05 1.84E-05 1.84E-05 3.64E-05 3.68E-05 3.82E-06 1.84E-05 MILK COW (SSE SECTOR AT 8045. METERS 1 AIR INHALATION 1.16E-06 1.16E-06 1.16E-06 1.24E-06 1.53E-06 1.09E-06 1.16E-06 EXPOSURE TO SDIL 3.55E-08 4.18E-08 3.55E-08 3.55E-08 3.55E-08 3.55E-08 3.55E-08 LEAFY VEGETABLE CONSLMPTION 5.18E-07 5.18E-07 5.17E-07 9.33E-07 2.83E-06 0.0 5.21E-07 FRODUCE CONSLMPTION 2.78E-06 2.78E-06 2.77E-06 4.93E-06 2.85E-06 0.0 2.78E-06 MEAT CONSLMPTION 4.12E-07 4.12E-07 4.11E-07 4.55E-07 5.66E-07 0.0 4.12E-07 COW MILK CONSUMPTION 1.00E-06 1.00E-06 9.95E-07 1.17E-06 5.28E-06 3.57E-05 1.01E-06 TCTAL 5.90E-06 5.91E-06 5.90E-06 8.76E-06 1.31E-05 3.62E-05 5.92E-06 MILK GOAT (SSE SECTOR AT 2574. METERS) _==---- AIR INHALATION 6.85E-06 6.85E-06 6.89E-06 7.34E-06 8.93E-06 6.29E-06 6.85E-06 EXPOSURE TO SOIL 2.68E-07 3.15E-07 2.68E-07 2.68E-07 2.68E-07 2.68E-07 2.68E-07 LEAFY VECETABLE CONSL3PTION 3.03E-06 3.03E-06 3.02E-06 6.16E-06 2.04E-05 0.0 3.06E-06 FRODUCE CONSUMPTION 1.62E-05 1.62E-05 1.62E-05 3.24E-05 1.68E-05 0.0 1.62E-05 MEAT CONSLMPTION 2.21E-06 2.21E-06 2.20E-06 2.53E-06 3.37E-06 0.0 2.21E-06 GOAT MILK CONSLMPTION 1.11E-05 1.11E-05 1.10E-05 1.37E-05 4.97E-05 3.28E-04 1.12E-05 l 1 - THAL 3.96E-05 3.97E-05 3.95E-05 6.24E-05 9.95E-05 3.35E-04 3.98E-05 1 ___-=-- O O t

1 TABLE Y.'A.2-29 83 QUARTER 1985 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE CASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS .'""E"' OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS _ _ = GARDEN (NNW SECTOR AT 965. METERS) CIR INHALATION 3.83E-04 3.83E-04 3.97E-04 5.93E-04 6.26E-04 5.13E-04 3.84E-04 EXPOSURE TO SOIL 1.05E-04 1.23E-04 1.05E-04 1.05E-04 1.05E-04 1.05E-04 1.05E-04 LEAFY VEGETABLE CONSUMPTION 5.31E-04 5.31E-04 5.25E-04 1.90E-03 2.87E-03 0.0 5.37E-04 PRODUCE CONSUMPTION 2.83E-03 2.83E-03 2.81E-03 9.94E-03 2.91E-03 0.0 2.85E-03 TLTAL 3.85E-03 3.87E-03 3.83E-03 1.25E-02 6.51E-03 6.18E-04 3.88E-03 MEAT ANIMAL ESOUTH SECTOR AT 2735. METERS) AkRINHALATION 1.74E-04 1.74E-04 1.80E-04 2.69E-04 2.88E-04 2.38E-04 1.74E-04 EXPOSURE TO SOIL 6.69E-05 7.81E-05 6.69E-05 6.69E-05 6.69E-05 6.69E-05 6.69E-05 LEAFY WEGETABLE CONSUMPTION 3.22E-04 3.22E-04 3.19E-04 1.19E-03 1.81E-03 0.0 3.26E-04 N P20 DUCE CONSUMPTION 1.72E-03 1.72E-03 1.70E-03 6.24E-03 1.77E-03 0.0 1.73E-03 $ MEAT CONSUMPTION 8.33E-05 8.33E-05 8.07E-05 1.75E-04 1.83E-04 0.0 8.50E-05 e TOTAL 2.37E-03 2.38E-03 2.35E-03 7.95E-03 4.12E-03 3.05E-04 2.38E-03 MILE COW (SOUTH SECTOR AT 8045. METERS) AIR INHALATION 2.96E-05 2.96E-05 3.07E-05 4.59E-05 5.04E-05 4.23E-05 2.97E-05 EXPOSURE TO SOIL 9.98E-06 1.17E-05 9.98E-06 9.98E-06 9.98E-06 9.98E-06 9.98E-06 LEAFY VEGETABLE CONSL'MPTION 5.02E-05 5.02E-05 4.97E-05 1.80E-04 2.72E-04 0.0 5.08E-05 FRODUCE CONSUMPTION 2.68E-04 2.68E-04 2.65r-04 9.43E-04 2.75E-04 0.0 2.70E-04 MEAT CONSUMPTION 1.46E-05 1.46E-05

1. 42L -05 2.82E-05 2.95E-05 0.0 1.48E-05 COW MILK CONSUMPTION 4.39E-05 4.39E-05 4.06E-05 9.62E-05 4.56E-04 3.26E-03 4.65E-05 l

TOTAL 4.16E-04 4.18E-04 4.10E-04 1.30E-03 1.09E-03 3.31E-03 4.22E-04 MILK GOAT (SSE SECTOR AT 2574. METERS 1 [RINHALATIbN 2.15E-04 2.15E-04 2.22E-04 3.32E-04 3.56E-04 2.94E-04 2.15E-04 EXPOSURE TO SOIL 6.26E-05 7.32E-05 6.26E-05 6.26E-05 6.26E-05 6.26E-05 6.26E-05 LEAFY VEGETABLE CONSUMPTION 3.17E-04 3.17E-04 3.13E-04 1.13E-03 1.71E-03 0.0 3.21E-04 TRODUCE CONSUMPTION 1.69E-03 1.69E-03 1.67E-03 5.93E-03 1.74E-03 0.0 1.70E-03 MEAT CONSUMPTION 9.33E-05 9.3JE-05 9.09E-05 1.79E-04 1.87E-04 0.0 9.50E-05 GOAT MILK CONSUMPTION 5.97E-04 5.97E-04 5.35E-04 1.29E-03 3.70E-03 2.52E-02 6.40E-04 TOTAL 2.98E-03 2.99E-03 2.90E-03 8.92E-03 7.76E-03 2.56E-02 3.04E-03 __=------ 1

a TABLE 2.A.2-30, 83 QUARTER 1985 BATCH + CONTINUOUS RELEASES DOSES TROM GfsEOUS ErrLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREMI OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE

THYROID THYROID ORGANS

=__ GARDEN MAXIMUM LOCATION AIR INHALATION 3.96E-04 3.96E-04 4.10E-04 6.07E-04 6.43E-04 5.25E-04 3.97E-04 EXPOSURE TO SOIL 1.05E-04 1.24E-04 1.05E-04 1.05E-04 1.05E-04 1.05E-04 1.05E-04 LEAFY VEGETABLE CONSUMPTION 5.36E-04 5.36E-04 5.30E-04 1.91E-03 2.91E-03 0.0 5.42E-04 PRODUCE CONSUMPTION 2.86E-03 2.86E-03 2.84E-03 1.00E-02 2.94E-03 0.0 2.88E-03 TOTAL 3.90E-03 3.92E-03 3.88E-03 1.26E-02 6.59E-03 6.30E-04 3.93E-03 MEAT ANIMAL MAXIMLM LOCATION AIR INHALATION 1.78E-04 1.78E-04 1.84E-04 2.73E-04 2.93E-04 2.42E-04 1.78E-04 EXPOSURE TO SOIL 6.71E-05 7.84E-05 6.71E-05 6.71E-05 6.71E-05 6.71E-05 6.71E-05 LEAFY VEGETABLE CONSLHPTION 3.24E-04 3.24E-04 3.21E-04 1.19E-03 1.83E-03 0.0 3.28E-04 7 PRODUCE CONSUMPTION 1.73E-03 1.73E-03 1.71E-03 6.27E-03 1.78E-03 0.0 1.74E-03 MEAT CONSUMPTION 8.46E-05 8.46E-05 8.20E-05 1.77E-04 1.85E-04 0.0 8.63E-05 uo TOTAL 2.39E-03 2.40E-03 2.37E-03 7.99E-03 4.16E-03 3.09E-04 2.40E-03 MILK COW MAXIMUM LOCATION AIR INHA!ATION 3.08E-05 3.08E-05 3.19E-05 4.71E-05 5.19E-05 4.34E-05 3.09E-05 EXPOSURE TO SOIL 1.00E-05 1.17E-05 1.00E-05 1.00E-05 1.00E-05 1.00E-05 1.00E-05 LEAFY VEGETABLE CONSUMPTION 5.07E-05 5.07E-05 5.02E-05 1.81E-04 2.75E-04 0.0 5.13E-05 FRODUCE CONSUMPTION 2.71E-04 2.71E-04 2.68E-04 9.48E-04 2.78E-04 0.0 2.73E-04 MEAT CONSUMPTION 1.50E-05 1.50E-05 1.46E-05 2.87E-05 3.01E-05 0.0 1.52E-05 COW MILK CONSUMPTION 4.49E-05 4.49E-05 4.16E-05 9.74E-05 4.61E-04 3.30E-03 4.75E-05 TCTAL 4.22E-04 4.24E-04 4.16E-04 1.31E-03 1.10E-03 3.35E-03 4.28E-04 MILK GOAT MAXIMLM LOCATION ____= AIR INHALATION 2.22E-04 2.22E-04 2.29E-04 3.39E-04 3.65E-04 3.00E-04 2.22E-04 EXPOSURE TO SOIL 6.29E-05 7.35E-05 6.29E-05 6.29E-05 6.29E-05 6.29E-05 6.29E-05 LEAFY VEGETABLE CONSLMPTION 3.20E-04 3.20E-04 3.16E-04 1.14E-03 1.73E-03 0.0 3.24E-04 PRODUCE CONSUMPTION 1.71E-03 1.71E-03 1.69E-03 5.90E-03 1.76E-03 0.0 1.72E-03 MEAT CONSUMPTION 9.55E-05 9.55E-05 9.31E-05 1.82E-04 1.90E-04 0.0 9.72E-05 GOAT MILK CONSUMPTION 6.08E-04 6.08E-04 5.46E-04 1.30E-03 3.75E-03 2.55E-02 6.51E-04 TOTAL -03 _______ ---- 3.02E 3.03E-03 2.94E-03 8.98E-03 7.86E-03 2.59E-02 3.08E-03 O O O

I t( 4 4 1 i l 1 1 TABLE 2.A.2-31 TNIRD OUARTER 1985 BATCM + CONTINUOUS RELEASES POPUi.ATION DOSE (50-MILE) FROM GASEOUS EFFLUENTS j (MAN-REM) l i EXPOSURE PATNWAY TOTAL 4 BODY TNYROID 1 AIR SUBIERSION 2.2E-02 2.2E-02 7 AIR INHALATION 4.6E-03 7.4E-03 ) N EXPOSURE TO SOIL 5.4E-04 5.4E-04 L LEAFY VEGETABLE CONSLSIPTION 1.1E-04 4.9E-04 PRODUCE CONSUMPTION 5.aE-04 6.0E-04 MEAT CONSUMPTION 3.8E-04 5.SE-04 MILK CONSUMPTION 4.3E-03 3.0E-02 TOTAL 3.3E-02 6.2E-02 1 AVERAGE DOSE (INtEN/ PERSON) 1.6E-05 3.GE-05 ) { i I i i I ) i 1 1 I e ] 4 1 I

I TnBLE 2.A.2-32 8 4 QUARTER 1985 DOSES FROM LIQUID EFFLUENTS (MREM) --=--- OTHER TOTAL ADULT iNTANT INTERNAL EXPOSURE PATHWAY BODY SKIN LUNG BONE THYRDID THYROID ORGANS =---- AQUATIC AT MAXIMUM LOCATION DRINKING WATER 5.5E-05 5.5E-05 5.1E-65 5.6E-05 7.6E-05 1.4E-04 5.1E-05 FISH CONSUMPTION 1.3E-03 1.3E-03 2.2E-04 1.1E-03 1.4E-03 0.0 6.0E-05 INVERTEERATE CONSLMPTION 1.9E-04 1.9E-04 1.0E-04 3.3E-04 2.0E-04 0.0 1.2E-04 EXF05URE TO SHORELINE SEDIMENT 1.7E-06 2.1E-06 1.7E-06 1.7E-06

1.7E-06 0.0 1.7E-06 SWIM'!ING AND BOATING 1.9E-08 2.1E-07 1.9E-08 1.9E-08 1.9E-08 0.0 1.9E-08 AQUATIC TOTAL 1.6E-03 1.6E-03 3.7E-04 1.5E-03 1.6E-03 1.4E-04 2.3E-04 N A L -QUATIC AT AGRICULTURAL LOCATION DRINKING WATER 5.5E-05 5.5E-05 5.1E-05 5.6E-05 7.6E-05 1.4E-04 5.1E-05 FISH CONSLMPTION 2.9E-04 2.9E-04 4.8E-05 2.4E-04 3.0E-04 0.0 1.3E-05 INVERTEBRATE CONSLMPTION 4.3E-05 4.3E-05 2.3E-05 7.2E-05 4.3E-05 0.0 2.6E-05 EXFOSURE TO SHORELINE SEDIMENT 3.9E-07 4.5E-07 3.9E-07 3.9E-07 3.9E-07 0.0 3.9E-07 SWIMMING AND BOATING 4.1E-09 4.7E-08 4.1E-09 4.1E-09 4.1E-09 0.0 4.1E-09 IRRIGATION AND LIVESTOCK WATERING EXPOSURE TO AGRICULTURAL SOIL 5.1E-06 5.9E-06 5.1E-06 5.1E-06 5.1E-06 0.0 5.1E-06 LEAFY VEGETABLE CONSUMPTION 7.3E-06 7.3E-06 5.3E-06 8.1E-06 2.1E-05 0.C 5.4E-06 PRODUCE CONSLMPTION 3.6E-05 3.6E-05 2.6E-05 4.0E-05 3.7E-05 0.0 2.6E-05 MEAT CONSLMPTION 1.3E-05 1.3E-05 1.2E-05 1.9E-05 1.4E-05 0.0 2.0E-05 MILE CONSLMPTION (COW) 4.2E-05 4.2E-05 2.6E-05 3.9E-05 7.1E-05 3.0E-04 2.4E-05 MILE CONSUMPTION (GOAT) 1.1E-04 1.1E-04 5.8E-05 9.7E-05 1.4E-04 4.6E-04 5.1C-05 AGRICUI.TURAL TOTAL EXCLUDING COW MILK CCNSLMPTION 5.6E-04 5.6E-04 2.3E-04 5.4E-04 6.4E-04 5.9E-04 2.0E-04 EXCLUDING COAT MILK CONSLMPTION 5.0E-04 5.0E-04 2.0E-04 4.8E-04 5.7E-04 4.4E-04 1.7E-04 l

M----- g_- _-g-__--- - - - _ _7 l O O O j

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1 TABLE 2.A.2-34 FOURTH QUARTER 1985 BATCH RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF llIGHEST CONCENTRATION SLte Boundary [a] Residencelb) Beta Air Dose (mrad) 3.6E-2 2.1E-2 Camma Air Dose (mead) 1.3E-2 5.3E-3 Beta + Camma Skin Dose (mram) 1.3E-2 Camma Total Body Dose (meem) 4.4E-3 [a] North sector at 663 meters. (b) North sector at 692 meters. l 2-74 l

TABLE 2.A.2-35 FOURTH QUARTEE 1985 CONTINUOUS EELEASES DOSES FRON NOBLE CASES AT SITE SOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION site Soundary[a] 3,,iq,nc,(b] Beta Air Dose (aced) 1.2E-1 6.8E-2 Casme Air Dose (mesd) 9.4E-2 3.7E-2 Beta + Gamma Skin Dose (area) 7.6E-2 Camma Total Body Dose (area) 3.4E-2 (a) North sector at 663 meteis. (b] North sector at 692 mete.rs. O 2-75

TABLE 2.A.2-36 FOURTH QUARTER 1985 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HICHEST CONCENTRATION Site Doundary[a] Residencelb) Beta Air Dose (mead) 1.6E-1 8.9E-2 Canna Air Dose (mead) 1.1g-1 4.3E-2 Beta + Canna Skin Dose (meem) 8.8E-2 Canna Total Body Dose (mrem) 3,9E-2 [a] North sector at 663 meters. (b) North sector at 692 meters. O 2-76

1 n O O" V TABLT W.A.2-37 84 QUARTER 1985 BATCH RELEASES DOSES FROM GASEOUS EITLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OITSITE EXPOSURE LOCATIONS (MREM) OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID DRGANS CARDEN (NNW SECTOR AT 965. ME'TERS) AIR INNALATION 3.32E-05 3.32E-05 3.44E-05 4.17E-05 2.09E-04 2.52E-04 3.36E-05 EXPOSURE TO SOIL 4.19E-06 4.97E-06 4.19E-06 4.19E-06 4.19E-06 4.19E-06 4.19E-06 LEAFY VEGETABLE CONS 12tPTION 2.50E-05 2.50E-05 2.48E-05 6.91E-05 1.28E-03 0.0 2.68E-05 FRODUCE CONSL?tFTION 1.23E-04 1.2,5E-04 1.22E-04 3.52E-04 1.64E-04 0.0 1.23E-04 TOTAL 1.85E-04 1.86E-04 1.85E-04 4.67E-04 1.65E-03 2.57E-04 1.88E-04 MEAT AM' MAL (NNW SECTOR AT 3379. ME'TERS) AIR INHAIATICN 4.54E-06 4.54E-06 4.71E-06 5.70E-06 2.98E-05 3.61E-05 4.60E-06 EXPOSURE TO SOIL .42E-07 5.23E-07 4.42E-07 4.42E-07 4.42E-07 4.42E-07 4.42E-07 LEATY VEGETABLE CONS 12tPTION 3.44E-06 3.04E-06 3.02E-06 7.69E-06 1.35E-04 0.0 3.23E-06 7 PRODUCE CDMSUMPTION 1.5'E-05 1.51E-05 1.50E-05 3.93E-05 1.95E-05 0.0 1.52E-05 3 MEAT CONSLhPTION

1. 59a.-0 6 1.59E-06 1.58E-06 2.17E-06 1.04E-05 0.0 1.61E-06 TDTAL 2.48E-04 2.48E-05 2.48E-05 5.53E-DS 1.95E-04 3.66E-05 2.51E-05 MILE CCW (NORTH SECTOR AT 8045. METERS)

AIR INHAIATION 1.60E-06 1.50E-06 1.66E-06 2.01E-06 1.10E-05 1.34E-05 1.62E-06 EXPOSURE TO SOIL 1.10E-07 1.3 7.-07 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.10E-07 LEAFY VEGETABLE CONSL?tFIION 9.40E-07 9.40L -07 9.36E-07 2.10E-06 3.37E-05 0.0 9.88E-07 FRODUCE CONSUPtPTION 4.77E-06 4.77E-L% 4.74E-06 1.08E-05 5.85E-06 0.0 4.78E-06 MEAT CONSL?tPTION 5.86E-07 5.86E-0) 5.83E-07 7.30E-07 2.78E-06 0.0 5.91E-07 COW MILK CONSLMPTION 1.55E-06 1.55E-06 1.52E-06 2.03E-06 6.24E-05 4.68E-04 1.65E-06 T^TAL 9.56E-06 9.58E-06 9.55E-06 1.77E-05 1.16E-04 4.81E-04 9.74E-06 MILE COAT (NNE SECTOR AT 3057. METERS) AIR INHAIATIDM 5.27E-06 5.27E-06 5.46E-06 6.61E-06 3.44E-05 4.17E-05 5.34E-06 EXPOSURE TO SOIL 3.06E-07 3.62E-07 3.06E-07 3.06E-07 3.06E-07 3.06E-07 3.06E-07 LEAFY VECETABLE CONSL?tPTION 2.72E-06 2.72E-06 2.70E-06 5.94E-06 9.40E-05 0.0 2.85E-06 FRODUCE CONSLMPTION 1.38E-05 1.33E-05 1.37E-05 3.05E-05 1.68E-05 0.0 1.38E-05 MEAT CONSLMPTICM 1.73E-06

1. 7.5 E-0 6 1.72E-06 2.13E-06 7.84E-06 0.0 1.75E-06 GOAT MILE CONSL?tPTION 9.16E-06 9.16E-06 8.91E-06 1.19E-05 2.12E-04 1.58E-03 9.55E-06 TOTAL 3.30E-05 3.31E-05 3.2SE-05 5.74E-05 3.66E-04 1.62E-03 3.36E-05

TABLE 2.A.2-38 84 CUARTER 1985 CONTINUOUS RELEASES DOSES FROM GASECUS EFTLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) OTHER TOTAL ADULT INFANT INTERNAL EXPOSGE LOCATION AND PATHWAY BODY SEIN LUNG EONE THYROID THYROID ORGANS =_ _ GARDEN tNNW SECTOR AT 965. METERS) AIR IMHA u TION 1.75E-03 1.75E-03 1.75E-03 1.75E-03 2.65E-03 2.07E-03 1.75E-03 EXPOS WE TO SOIL 7.12E-06 8.64E-06 7.12E-06 7.12E-06 7.12E-06 7.12E-06 7.12E-06 LEAFY VEGETABLE CONSLNPTION 5.01E-04 5.01E-04 5.01E-04 5.03E-04 7.21E-03 0.0 5.10E-04 FRODUCE CONSLNPTION 2.65E-03 2.65E-03 2.65E-03 2.65E-03 2.87E-03 0.0 2.65E-03 TOTAL 4.91E-03 4.91E-03 4.91E-03 4.91E-03 1.27E-02 2.07E-03 4.92E-03 MEAT ANIMAL INNW SECTOR AT 3379. METERS) T.IR INHAIATION 2.39E-04 2.39E-04 2.39E-04 2.39E-04 3.69E-04 2.91E-04 2.40E-04 EXPOSURE TO SOIL 7.73E-07 9.38E-07 7.73E-07 7.73E-07 7.73E-07 7.73E-07 7.73E-07 LEAFY VEGETABLE CONSLMPTION 7.46E-05 7.46E-05 7.46E-05 7.49E-05 8.03E-04 0.0 7.56E-05 E FRCDUCE CONSUMPTION 3.97E-04 3.97E-04 3.97C-04 3.97E-04 4.21E-04 0.0 3.97E-04 2 MEAT CCNSLMPTION 7.55E-05 7.55E-05 7.55E-05 7.55E-05 1.25E-04 0.0 7.56E-05 TOTAL 7.87E-04 7.88E-04 7.87E-04 7.88E-04 1.72E-03 2.91E-04 7.89E-04 EILE COW (NORTH SECTOR AT 8045. ME ERS) ---= AIR INMALATION 8.62E-05 8.62E-05 8.62E-05 8.63E-05 1.35E-04 1.08E-04 8.63E-05 EXPOSGE TO SOIL 1.97E-07 2.39E-07 1.97E-07 1.97E-07 1.97E-07 1.97E-07 1.97E-07 LEAFY VECETABLE CONSUMPTION 2.92E-05 2.92E-05 2.92E-05 2.93E-05 2.15E-04 0.0 2.95E-05 FRODUCE CONSUMPTION

1. 56 E-04 1.56E-04 1.56E-04 1.56E-04 1.63E-04 0.0 1.56E-04 MEAT CONSUMPTION 2.97E-05 2.97E-05 2.97E-05 2.97E-05 4.23E-05 0.0 2.97E-05 COW MILE CONSLMPTION 7.06E-05 7.06E-05 7.06E-05 7.07E-05 4.17E-04 2.85E-03 7.10E-05 T^TAL 3.72E-04 3.72E-04 3.72E-04 3.73E-04 9.72E-04 2.96E-03 3.73E-04 CILE GCAT (SSE SECTOR AT 2574. FITERS)

TIR INHALATION 1.31E-04 1.31E-04 1.31E-04 1.31E-04 2.01E-04 1.58E-04 1.31E-04 EXFCSURE TO SOIL 4.68E-07 5.68E-07 4.68E-07 4.68E-07 4.68E-07 4.68E-07 4.68E-07 LEAFY VECETABLE CONSLNFTION 4.00E-05 4.00E-05 4.00E-05 4.02E-05 4.81E-04 0.0 4.06E-05 FRODUCE CONSLMPTION 2.13E-04 2.13E-04 2.13E-04 2.13E-04 2.27E-04 0.0 2.13E-04 MEAT CONSWPTION 4.04E-05 4.04E-05 4.04E-05 4.04E-05 7.01E-05 0.0 4.05E-05 GCAT MILE CONS W PTION 1.96E-04 1.96E-04 1.96E-04 1.96E-04 1.18E-C3 8.10E-03 1.97E-04 TOTAL 6.20E-04 6.21E-04 6.20E-04 6.21E-04 2.16E-03 8.26E-03 6.23E-04 e O O

I p p ,a TABLE 2.A.2-39 84 QUARTER 1985 SATCH + C0hTINUGUS RELEASES DOSES FROM CASEOUS EFFLUENTS (EXCLUDING NOSLE GASES) AT MAXIMUM OFFSITE EXPOStaE LOCATIONS (MREM 3 OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATIOT AND PATHWAY 80DY SKIN LUNG BONE TNYRCY:: TNYROID ORGANS CARDEM MAXIMCM LOCATION CIR INMAIATION 1.78E-03 1.78E-63 1.78E-03 1.79E-03 2.86E-03 2.32E-63 1.78E-03 EXPOSURE TO SOIL 1.13E-05 1.36E-05 1.13E-05 1.13E-05 1.13E-05 1.13E-05 1.13E-05 LEAFY VEGETABLE CONSLMPTION 5.26E-04 5.26E-04 5.26E-04 5.72E-04 8.49E-03 0.0 5.37E-04 FRODUCE CONSUMPTION 2.77E-03 2.77E-03 2.77E-03 3.00E-03 3.03E-03 0.0 2.77E-03 TOTAL 5.09E-03 5.10E-03 5.09E-03 5.38E-03 1.43E-02 2.33E-03 5.11E-03 NEAT ANIMAL MAXIML?! LOCATION AIR INHALATICM 2.44E-04 2.44E-04 2.44E-04 2.45E-04 3.99E-04 3.27E-04 2.45E-04 EXFOSURE TO SOIL 1.21E-06 1.46E-06 1.21E-06 1.21E-06 1.21E-06 1.21E-06 1.21E-06 LEAFY VECETABLE CONSLMPTION 7.76E-05 7.76E-05 7.76E-05 8.26E-05 9.38E-04 0.0 7.88E-05 N FRCDUCE CONSUMPTION 4.12E-04 4.12E-04 4.12E-04 4.36E-04 4.40E-04 0.0 4.12E-04 b MEAT CONSUMPTION 7.71E-05 7.71E-05 7.71E-05 7.77E-05 1.35E-04 0.0 7.72E-05 e TOTAL 8.12E-04 8.13E-04 8.12E-04 8.43E-04 1.91E-03 3.28E-04 8.14E-04 r!ILX COW MAXIML?t LOCATION CIR INHAIATION 8.78E-05 8.78E-05 8.79E-05 8.83E-05 1.46E-04 1.21E-04 8.79E-05 EIFOSURE TO SOIL 3.07E-07 3.69E-07 3.07E-07 3.07E-07 3.07E-07 3.07E-07 3.07E-07 LEAFY VEGETABLE CONS 12tFTION 3.01E-05 3.01E-05 3.01E-05 3.14E-05 2.49E-04 0.0 3.05E-05 FRCDUCE CONSLMPTION 1.61E-04 1.61E-04 1.61E-04 1.67E-04 1.69E-04 0.0 1.61E-04 MEAT CONSL?tPTION 3.03E-05 3.03E-05 3.03E-05 3.C4E-05 4.51E-05 0.0 3.03E-05 C054 MILK CONSLT!PTION 7.21E-05 7.21E-05 7.21E-05 7.27E-05 4.79E-04 3.32E-03 7.27E-05 TOTAL 3.82E-04 3.82E-04 5.82E-04 3.91E-04 1.09E-03 3.44E-03 3.83E-04 CILK GOAT MAXIML?! LOCATION AIR INHALATION 1.36E-04 1.36E-04 1.36E-04 1.38E-04 2.35E-04 2.00E-04 1.36E-04 EXFOSLTE TO SOIL 7.74E-07 9.30E-07 7.74E-07 7.74E-07 7.74E-07 7.74E-07 7.74E-07 LEAFY VEGETABLE CONSIPtPTICM 4.27E-05 4.27E-05 4.27E-05 4.61E-05 5.75E-04 0.0 4.34E-05 FECCCCE CCMSL?!PTICM 2.27E-04 2.2iE-04 2.27E-04 2.44E-04 2.44E-04 0.0 2.27E-04 MEAT CONSL?tPTION 4.21E-05 4.21E-05 4.21E-05 4.25E-05 7.79E-C5 0.0 4.23E-05 GOAT MILE CONSt2fPTION 2.05E-04 2.05E-04 2.05E-04 2.08E-04 1.39E-03 9.68E-03 2.07E-c4 TOTAL 6.53E-04 6.54E-04 6.53E-04 6.78E-04 2.53E-03 9.88E-03 6.57E-04

W e O ' gessaws M : i.: 4 4 A d a.: A g 2000 :: 20 5! k.kk.kk.kk.k,k 3 m e ,=. ~ C g '{ h 5 -5" 2 l$ NN "t 8 8-8 8 O h* E3 EE 5 m e g E 5 a i 82 d tEs g 558 5~~ ~ -- htt w al5055hl 8 n --. gee 3 e s t _ y,; <<a 1g: -< O 2-80 e se

2.A.3 MTEOR0 LOGICAL DATA IIeteorological data for 1985 are available for review in the FOR Corporate Office as per Technical Specification 6.9.1.5.4 of FOL NPF-1. Meteorological models and assumptions used in performing the analyses are presented in POE-1021. "Offsite Dose Calculation IIanual". O O J-81

\\ 2.A.4 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) Trojan Technical Specification 6.15.2.A requires licensee-initiated changes to the ODCM be included in the Semiannual Effluent Release Report submitted to the NRC for the period in which the changes were made. Additional guidance is provided in Specification 6.15.2.A regarding the contents of the report on ODCM changes. This section contains the details of Amendment 2 (LDCR 84-23) and Amendment 3 (LDCR 85-18) to PGE-1021, "Offsite Dose Calculation Manual". Included is documentation that the. changes have been reviewed and found acceptable by the PRB, the Trojan Nuclear Plant safety evaluation check-list for both changes, the reasons for change, and those pages of the ODCM which were changed with each amendment. O l l O 2-82 i

ODCM Amsndmsnt 2 Documentation Page 1 of 6 Form E55-12 Estr 220-2 Rev. 1 LICERSIEG DOCUMINT CMABGE REQUEST i IACE/Date 84-21/12-21-84 EDC/ Data Z. Smitiation p97d A. Identification j grisinator M-\\I. L. Thale Dept. NSRD Telephone 226-8123 habject Updates to PCE-1021. Amendment i Schedule Beguirement Data December 31. 1984 Licensing Documents Affected: FEAR LTE X EEIP FSAR SCA SF B. Besson for Chante: See. Attachment A C. McEristion of ^ ~ e/ Proposed Esplacement Panas: See Attachment A II. maclear safety & Romulation Department Review A. In compliance with ERC/PCE requiremmata? Yes X Eo - attached { B. Safety Evalual tion (use attactument from EDP 100-5): O .F ro.ed z aef.u- ~ / 2.. / < < Rac dar Regulation Branch Date I l III. Connizant Ormanization amoroval* l Ormanisation amorove** Steamture Date u n.or of -n YJ MA/ /ff 14/"[k i PRB Chairman M Db 82.[c4 /PC/ Ger.. Mer. TNP lu i (2.-2a eJ. G 1

Attach review documentations if not formelly distributed for review.

(

- Indicate approval by "Yes" and rejection by "no".

IV. Amendment Completion Document Date %E-/oal, BMwwd a )/al %5 /E L Jw Lad n/u/er .,,n,. I ESED 2-83 Date

ODCM Am:ndment 2 Docum ntation Page 2 of 6 BoF 100-5. Bev. o attachment A Feg. 1 of 4 YBwa meet.saa rurY saFuYr svumn05 onex 1. sY DSRO L OCR 1r4 - 2 3 Departamat Identification member IAt1 & Mp cl < k PFC /o2 i 1.0 3dentification and Descri ion of e M.e e.nel a.,,. 4 i (O sA Cole. ll G 4 s,e,a ! ) 2.0 Criteria for Determinias W Beed for Evaluatise Caos this thenge, test er esperiment represents 2.1 10 CFE 50,59 N A ebense to N Trojen Facility as described in Yes se W FSARt so 1 A ebense to Procedures as described in the F5AR Yes (ie, does it change en FIAR described syntes operation er administrative control. or thenge a ,erstem operation aneumed in en accident saalreLet) Yes 30 A test er esperiment which operates the facility in a menner not described in the FSAR and/or which could have en adverse effect on reactor esfetyt N t Yes so A change to W Technical Specificatione (Appe dim A or 3 of the Trojan suelear Plant License) er W license itselft 2.2 Environmental Technical Reeelfication 1.1 Yes to % A thenge to Trojan procedures or design edtish could effect the environment? 2.3 10 CFR 50.54fa)(3) I A change to SQAP et procedures which implement Yes Bo 30 apt 2.4 10 CFR 50.54fe) Yes Be X A change to the RERP or emerlency response equipment or procedures described in N 32377 l 2.5 10 CFR 50.54fe) Yes Bo Y A thenge to @ 8ecurity Plan or Safeguards contingency Plan or to equipment or Procedures described in the Security Flen or Safeguards contissancy Fleet Indicate h sections of the FSAR. Yestetical specifications. SQAP. 3E37. security Plan, or safeguards contingency Flen revisued t/ AS PM d*> b //-I ?VE/o3l C00 tan ) r%.es J t I h / Y! WI'f t [/ sisrature Date If the ensuer to all of N above questions is "no", en evaluation to not required. l 2-84

ODCM Am:ndment 2 Docum:ntation Page 3 of 6 i O LDCR 84-23 Attachment A REASON FOR CHANGE The specific reason for each change is listed below. The index numbers correspond to the side bar numbers in this attactuaent. 1. This change clarifies that nuclides which require analysis of monthly or quarterly composite samples (eg, H-3, Fe-55, Sr-89, Sr-90) are not considered in the MPC determination at the time of ligt;.id discharge. When the results of these analyses are available, the results will be used to confim that those nuclides averaged over the sample period did not cause a violation of Technical Specification 3.11.1.1. This change is identical to the clarification already existing in Technical Specification 3.11.2.1 (Gaseous Effluents). 2. Editorial corrections. DESCRIPTION OF CHANGE Proposed replacement pages are attached. 10 1 0 2-85

ODCM Amsndm2nt 2 Documentetion Page 4 of 6 [%M a /n/hrH 2.2 TactarIc4L iruncarror 3.n.s.1 This section will be used to demonstrate compliance with the Lindting Condition for operation (LCO) 3.11.1.1 by providing the calculational methods to use with the results of radioactive analysis required by Technical specification 4.11.1.1.1.. Once the results of a radioactive analysis are obtaLned, the fractional EPC(f) should be calculatad using ths equation: A f=1 ,,L.c (2-3) where [ l Ag - concentration of nuclide i in sample,,pci/ml MPCg = 10 CFR 20 Appendix B, *.*able II, Column 2 concentration limit for nuclide i, DCL/mi ~ The resulting fractional NFC must be adjusted for plant dilution using the following equation: C. f x F. F, (2-4) where ~ C = fraction of 10 CFR 20 timit F, = liquid radioactive wasted discharte flow rate prior to dilution, gym l l F = total plant dilution flow rate, gym l p Releases comply with Tec2mical BP*eification 3.11.1.1 if the value of C is 51.0. lWuelides which twquire analysis of monthly or quarterly composite samples / (eg, 5-3',,3r-49, 3r-90) are not considered in the calcul'ation required b I Fs CS ' '3.it. 1 Mgo Technical specification f. ". ).) ' at the time of the release. E en the f0"P*h ' results from thase anslyses are available, they will be used to confi that those nuclides, averaged over the sample period, did not cause S. II. t. violation of Technical Boecification e.;..i.).L. 2-86 l l

ODCM Amsndm:nt 2 Documentation ~ .E /. Page 5 of 6 t* t,- / pa c2 fis(W W S's GroundPlanePathwayFactorRf (10 )(8760)(SF)(DFC )[(1- [ }/ ) (B-3) R = g h.re 10 = constant, PC1/Ci 8760 = constant, hr/yr g = decay constant for nuclide i, sec-1 K t = exposure time, 4.73 x 10 sec (15 yr) (DFC ) = ground plane total body dose conversion factor for p g nuclide i, aree/hr per pCi/m2 (Regulatory Guide 1.109. Rev. 1 10/77. Table E-6) 1 ) (,/ SF = shielding factor for residential structures, 0.7. Vegetation Pathway Factor R Man is considered to consume two types of vegetation, fresh leafy vegetables and produce. The vegetaation dose factor combines these two pathways uring the following equation: f b Rg = 10 (c) fe (DFI.g) f a \\ 't. + U,f e -\\ th-v 12 (B-4) , vb # w '_ .here U = consumption rate of fresh leafy vegetation by the child receptor, 26 kg/yr (Regulatory Guide 1.109. Rev. 1, 10/77, Table R-5) O Ame.'- 1 2-87 ( emM 198!.) N

ODCM Am:ndment 2 Docum2ntation

.5 Page 6 of 6 9Y

( t/lwvA a 10 = constant, PCi/Ci D and all other terns have been defined previously. The concentration of tritium in meat is based on its airborne concen-tration rather than the deposition. Therefore, the for tritium is based on 1/Q: 3 = ( O b (10 )F Q,U,, M ) [0.75(0.5/H)] (b 7) g g where all terms have been defined previously. Crass-Coat-Hilk pathway Factor R _g g - N p s + CI' p s'* ~k k C 12 F ap h, Rg = 10 ( (r)(f,)(DFL ) e g ( k*w Ip Y, (B-8) where Q, = goat's consumption rate of feed, 6 kg/ day (Regulatory Guide 1.109, Rev. 1, 10/77, Table B-3) U = child receptor's milk consumption rate, 330 1/yr (Begulatory Quide 1.109. Rev. 1, 10/77 Table E-5) Y, = agricultural productivity by unit area of stored l feed, 2.0 kg/m2 (Eagulatory Guide 1.109 Rev. 1, 10/77, Table E-15) F, e stable element transfer coefficient for allk, in days /1 (Regulatory Quide 1.109, Rev. 1, 10/77 Tables E-1 { and E-2) ( O Am nt 1 2-88 ecemb 19 8!.)

ODCM Amtndment 3 Docum:ntation Page 1 of 13 Forn EBE-12 ustr 220-2 Ber. 1 LICEBSIEC DOCUIENT CHABCE REQUEST tact /Date 85-18 EDC/ Data I. faitiation A. Identification gg % e J. L. Thale Dept. NSRD Telephens 8123 Originator 3 to PGE-1021. "Offsite Dose Calculation Manual". Amendment gubject December 31, 1985 Schedule Dequirement Data Licensing Documents Affected: FSAR LTg XX EERP FEAR SCA SP 3* I***'" f*" See Attachment A Description of Name/ Proposed Eet lacement Paaes: See Attachment A C. puelear safety & Beauletion Department Eeview II. Yes XX so A. In compliance with WRC/PCE requirs ents? 3. Safety Evalus ion use attachment.? rom EDP 100-5): Attached t-(4 /t.3 /b ~ C. Approved Date sue segulation Branch ( ".'II. Cornizant Organizat on Approvale I Ortanization Amorove** Sirnature Dato l %'S Y$u ^ */15/TP f Manator of WEED C A y mlj 42Au/[g l A cw,4 ,, on ( h .M JF U (@f Plant General Mgr. du A / l e Attach review documentation if not formally distributed for review. So Indicata approval by "Yes" and rejection by "50". IT. Amendment rA' mpletion Date Document pre-1021, Amendment 3 2/13/86 O 2-w M /nu a-7 s r 2-89

ODCM An:ndment 3 Docum2ntation Pags 2 of 13 3DP 100-3. Rev. 1 Attactument A Page 1 of e . _ 0. _, us tt P LQCR ST~IV f Departamnt laantifisation Bumbee ru u N as**=8 h M *** *** b $ b 1.0 Identification and cri tion of Chan$ewish, s C $ Oose e P6-C 10 2 i *

O Co

^< w el 2.0 Criteria for Determining the need for tvaluation Does this change, test or esperiment represent 2.1 10 c7R 50.59 Yes 30 A change to N Trojan Facility as described in m rSaaf N & change to procedures as described in the FSAR Yes 50 (ie, does it change en FSAR described system operation or administrative control, or change a system operation assumed in an accident analysLaf) Yes Bo a test or experiment which operates the facL11ty in a*amener not described in the FSAR and/or which could have en adverse effect on reactor safety? Y A change to the Technical specifications Yes so (Appendix & or 3 of N Trojan Butlear Flant Licanee) or the ILeense itselff If yes, a detailed safety evaluation and sac approval is requitwo prior to Laplemmatation. 2.2 Envirormental Teetmical 2seeification 5.1 Wo 1 A change to Trojan procedures or deelga which Yes could effect the environment? 2.3 10 C7R 50.54falf51 Yes so A change to the suelear Quality Assurance ,r.gr.m. Yes to A deviatiora f ree W Wuclear Quality Assurance Program description. 2.4 10 crt 50.54(e) l Yes so A change to the EEIP or emergency response equipment or procedures described La the EEEFf I 2.5 10 CFR 50.54(n) Yes to d A change to the Security Plan er Safeguards contingency Plan or to equipment or procedures described in the Security Plan or Safeguards Contingency Plant Indicate the sections of the FSA2. Tectmical Specifications. 04 Program. 3137 uards Cont 1 sency Plan reviewed d E4 44

18. C Security Plan, er Saf Pi-c su r t c oku n ~~ =9M h

IAhh[ t f signature cate if the answer to all of the above questions La "no", en evaluation is not required. Othatvise, complete the applicable sections of Part 3. p 2-90

ODCM Amendment 3 Documentation Page 3 of 13 LDCR 85-18 Attachment A Page 1 of 1 REASON FOR CHANGE 1. Minor editorial corrections and revisions based on the 1985 Annual Land Use Census and use of new grid maps, i 2. Correction of round-off errors between Table 3-1 and A-1. I 3. Minor editorial changes to reflect that the results of the 1985 Annual Land Use Census did not result in modification of the Ri values (Iodine and particulate dose factors). DESCRIPTION OF CHANGE I Pecposed replacement pages are attached. l0 JLT/djh i 0644W.1285 O 2-91

-~ ,m TABLE 5-1 Sheet 1 of 6 SAMPLING LOCATIONS AND FREQUENCY BY TYPE Terrestrial Ariustic Radial Air Air Well Surf Shore Sample Location Mllente Direction Partic I-131 TLD' Von Milk Water Water Soll Anim ONSITE 1A - U. S. 30 & E-W Road 0.8 NW Q S/A to Prescott IB - U. S. 30 W of 0.5 WSW Q Containment IC - Cemetery on hill 0.7 SW Q 'W of Plant ID - Recreation Lake 0.7 S S/A 1E - S site boundary. 0.8 3 Q U. S. 30 at RR 1F - Meteorology tower 0.5 S W W Q 10 - S of Containment 0.1 SSE Q 20 %9 IX - Plant outfall 0.2 ESE Q

g o*[

8 II - K site boundary at M

4-440 W W Q HT o. Columbia River Cl r, IJ - RR & E-W road to 0.6 NNW Q w Prescott f2 o tyh/jy 0 20 - S of Plant on 0.4 SSE Q h Columbia River shore l D oo ~5 a

O O O-TABLE 5-1 Sheet 2 of 6 Teereshrta, Aquatic Radial Air Air Well Surf Shore Sample 1.ocation M11eate ' Direction Partic I-131 TLD Vet Milk Water Water Soll Anla ONSITE 21 - SE of Plant on 0.3 SE Q columbia River shore 22 - Between Recreation 0.4 SSW Q l Lake and U. S. 30

0. L:

wus.) 23 Recreation Lake nea + 5- -SW-Q , -W road to Plant E oi U5S 24 U. S. 30 S of E- -e-t M Q road to Prescott I w 64 - NW corner of 0.5 W Q w Reflection Lake ) _arcou o i t 2 - Rainter 3.8 NW W W g Mc yg $0 l 3 - Lindberg (Kelly Res.) 2.0 NNW Q Q /.fo Nid 4C - Prescott.(Jack Falls M M Q

- D oe residential area) 41 8

N 6B - coble (Neer Res.) &rS~ M W W Q Q g 24 17A - Beaver Homes (Kandle M SSW SN ocs Dalry) g a 19 - Portland 37.5 S W W SM /7M N 4t/t* fry

~. TABLR 5-1 St.eet 3 of 6 Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Hlleate Direction Partic'I-131 TLD Vem M11k Water Water soll Anla OREGON O,h 25 - Prescott (Shoreline) M N Q 26 - Dete Island ( 3 Q Erad) f,de Q( v.c 27 - Columbia City (Censman 4 eve S Q Road) O 4 ~7 28 - Shiloh Basin ( h SSW Q Road) Y /O 7 29 - Trenholm (Canaan N SSW Q Road) 30 - Shiloh Basin 5.0 SW Q (Whitney Road) se.% 10.1 31 - Aplary ( Road) 6-SW Q 3.x -%9 32 - Fern Hill (Lentz WSW Q Road) .g Yon}Yel et S*h ~ E. o. 33 - Aplary (Beys 5L Road) .Mbe@ WSW Q C 34 - Fern Hill (Lentz 5.0 W Q Road) ,arfI 35-Swedetown(Qfrir] 10.0 W Q Road) p = M4{ 36 - Rainter (Doan Road) 5.2 WuW Q g p e O O

O O O TABLE 5-1 Sheet 4 of 6 Terrestrial Atuatic Radial Air Air Well Surf Shore Sample Locatlon Mlleate Direction Partic T-131 TLD Vet Milk Water Water Soll Anim OREGON 37 - Delena (Lost Creek 10.0 WWW Q Road) Y.I 38 - Rainier (Highway 30) M NW Q 39 - Alston-Mayger Road NW Q

o8 56. Deer Island SSE Q

63-Renck Desey

8. W wNW SM 66 - St. Helens (Municipal

-le g MC y Water Supply) to,d' KS 6. g T S.O UI 68 - Winans Dairy 4,@- SW SN

w WASHINGTON o,2 11A - Kalama River Jh >-

SE Q (Coluabla River) ENE

? 8 113 - Kalama River (PUD 1.4 M

W W gg Substation) y E'% o 14 - Longview (Ocean de@' NNW W W m{ Beach Substation) gg S* 5 40 - Longview (RR) 4 NNW Q 41 - Eufaula T."' Q 6.4 8 42 - Kelso (near Hwy 4) 41P N Q JO 'VWir a D

TABLE 5-1 Sheet 5 of 6 Telrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mileage Direction Partic I-131 TLD Vet Milk Water Water Soll Anim WASHINGTON 43 - Lexington 10.3 N Q SA 44 - Kelso (N Haple Hill M NNE Q Road) 9.I 45 - Mt. Brynlon .Mbe4 HNE Q S*3 46 - Rose Valley 49tr NE Q 47 - Smith Mountain NE Q f.G n i 48 - Mt. Pleasant .5 re ENE Q 7.y 49 - Coble Mountain M ENE Q 50 - Kalama River 5.0 E Q (Fallert Road) 20 51 - Kalsve River 10.0 E Q $9 (Kalarna River Road) cog feQ o@ 52 - Kalama (China Carden M ESE Q ] E. Road) wg

10. 7 n

53 - Ross Peak M ESE Q w El ts 54 - Cloverdale 4=4 SE Q o E 55 - Woodland (Green 10.0 SE Q g Mountain Road) pg" 57 - Woodland (Dike Road) SSE Q O 0

3 U Y 0 TA,BI.E 5-1 Sheet 6 of 6 Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mlleere Directior partic T-131 TI.D Veg Hilk Water Water Soil Anim WASHINGTON /. (o $6 58 - Kalama (N of Port of 4,6- .aiEMF Q Kalt.ma Marina) l*T 61 6 59 - Kalama (S of Sports-Sv9 4 Q man Road)

l. L 60 - Kalama (N of

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TABLE A-1 NOBLE CAS DOSE FACTORS 6 Regulatory Guide 1.109 (Rev. 1. 10/77) pose Factors DFf DF DFS DFB K L H N g g-g g g g 6-air 6-skin Y-air y-body Y-body 6-skin S-air y-air (mrad /gg) (arem/yr) (arad/yg) (arem/yp) (res/yr) (res/yr) (rad /vr) (rad /vr) Nuclide igCl/m ) (PC1/m ) _{gCl/m ) _lpCl/m ) (C1/sec) (C1/sec) ICl/sec) (Cl/sec) 7.1

F Kr-83m 2.9E-4 0.0 1.9E-5 7.6E-8 Jr6E-4 0.0Et0 2.7Et0 AffE-1 s.9 Kr-85 2.0E-3 1.3E-3 1.7E-5 1.6E-5 1.5E-1 1.2Et1 It9Et1 1.6E-1 e.7 Kr-8Sm 2.0E-3 1.5E-3 1.2E-3 1.2E-3 1.1Ett 1.4Et1 4TSEt1 1.1Et1 J. i

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ODCM Amendment 3 Documentetion Ptgs 13 of 13 In %s '\\ Table B-2 sives the h land use distance data beced on the Annual ) fwt sit 4 Land Use censuc The annual average meteorology at each of these j distances was derived in Appendix C and is listed in Tabla C-3. Should subsequsnt,f.nnual Land Use Cencus' indicate a change in Table B-2 which wouldaffecttLolocationofnaximmpotentialoffsitedose,thevalues m m..,2.. will be M nd,pncorporated into the ODCM for use in the of R g subsequent, yotr (ie, the values of R used in 1935 will raflect the g exposure locations in the 19R4 Annual Land Use census). i For this evaluation, the ground dose controlling location is at the residence with the highect D/Q value, and the inhalation doce controllin, location is at the residenco with the highest 1/Q value, b i l 1 J l I Amendemnt 1 2-101 (December 1980

O 2.B AmfUAL Pen MNNEL EIPOSURE AND MONITORTWC REPORT This section provides the tabulation of workers receiving exposures greater than 99 meen per year and their man-res exposures according to work and job functions required by Technical Specification 6.9.1.5.s of Appendix A of Trojan FOL NPF-1. Table 2.5-1 is the exposure report by number of personnel, man-rem, and job function. Table 2.5-2 is the dose report by number of personnel versus dose level received. It should be noted that the numbers of people shown on Table 2.5-1 differ from the numbers on Table 7.B-2, since an individual's exposure may be charged to more than one work or job function. The special maintenance category in Table 2.B-1 includes replacement of the spent fuel racks, as well as other miscellaneous maintenance work not related to normal plant maintenance or refueling activities. I O 1 !!O l 2-102 i e

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TABLE 2.D-1 REPORT 05 NUMBER OF PERSONNE:. AND MAN-REM BY WORK AND JOB FUNCTION O I No. of Personnel 699 meen) Total Man-Rem Station Utility contract Station Utility contract Work and Job Punction Ensloyees EBeloyees Workers Employees Emploroes Ark 3E3_ REACTOR OPERATIONS & SURVEILLANCE daintenance Personnel 7 0 3 1.82 0.07 1.14 Operating Personnel 22 0 0 6.35 0.00 0.00 Chen & RADCON Personnel 23 0 34 8.15 0.05 13.79 Supervisory Personnel 2 1 4 0.60 0.33 2.41 Engineering Personnel 2 0 0 0.75 0.91 0.24 ROUTINE MAINT. & INSERVICE INSPECTION I Maintenance Personnel 70 66 152 35.74 32.48 103.80 O erating Personnel 17 0 0 4.38 0.00 0.00 P Chen & RADCON Personnel 30 2 70 11.64 0.22 36.99 Supervisory Personnel 7 9 4 2.57 3.82 2.07 Engineering Personnel 6 4 45 2.34 1.79 53.94 SPECIAL MAINTENANCE Maintenance Personnel 2 8 16 0.93 1.86 6.31 Operating Personnel 0 0 0 0.02 0.00 0.00 Chen & BADCON Personnel 4 0 0 1.50 0.00 0.37 Supervisory Personnel 0 0 0 0.08 0.13 0.06 Engineering Personnel 0 2 0 0.00 0.34 0.00 1 WASTE PROCESSING Maintenance Personnel 2 1 11 0.61 0.39 4.79 Operating Personnel 0 0 0 0.21 0.00 0.00 Chen & RADCON Personnel 31 2 19 18.60 0.69 8.71 Supervisory Personnel 0 0 0 0.05 0.00 0.01 i Engineering Personnel 0 0 0 0.00 0.00 0.00 REPUELING i Maintenance Personnel 16 12 11 14.27 14.20 2.65 Operating Personnel 12 0 0 6.02 0.00 0.00 Chen & RADCON Personnel 12 2 28 3.34 0.73 9.85 Supervisory Personnel 1 7 0 1.14 1.27 0.06 Engineering Personnel 0 0 0 0.18 0.08 0.06 TOTAL Maintenance Personnel 97 87 193 53.36 49.00 118.69 Operating Personnel 51 0 0 16.97 0.00 0.00 Chen & RADCON Personnel 100 6 151 43.22 1.69 69.70 Supervisory Personnel 10 17 8 4.44 5.55 4.61 Engineering Personnel 8 6 45 3.27 3.12 54.25 GRAND TOTAL 266 116 397 121.27 59.36 247.24 i i 2-103

i O TABLE 2.D-2 TROJAN PLANT WHOLE BODY EXPOSURE (REM) 1985 Number of People With No Exposure = 592 Exposure of at Least 0.001 and Less Than 0.090 Numbsr of People = 264 Exposure of at Least 0.100 and Less Than 0.749 Number of Peopla = 159 Exposure of at Least 0.250 and Less Tha.: 0.499 Number of People = 155 Exposure of at Least 0.500 ana Less Than 0.749 Number of People = 100 Exposure of at Least 0.750 and Less Than 0.999 Number of People = 68 Exposure of at Least 1.000 and Less Than 1.999 Number of People = 98 Exposure of at Least 2.000 and Less Than 2.999 Number of People - 8 Exposure of at Least 3.000 and Less Than 3.999 Number of People = 0 Exposure of at Least 4.000 and Less Than 4.999 Number of People = 0 Exposure of at Least 5.000 and Less Than 5.999 Number of People = 0 Exposure of at Least 6.000 and Less Than 6.999 Number of People = 0 Exposure of at Least 7.000 and Less Than 7.999 Number of People = 0 Exposure of at Least 8.000 and Less Than 8.999 Number of People = 0 Exposure of at Least 9.000 and Less Than 9.999 Number of People = 0 Exposure of at Least 10.000 and Less Than 10.999 Number of People = 0 Exposure of at Least 11.000 and Less Than 11.999 Number of People = 0 Exposure of at Least 12.000 and Less Than 100.999 Number of People = 0 Total Plant Exposure = 362.590 man-rem O 2-104

2.C STEAM CENERATOR TUBE INSPECTIONS 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 Specifications 4.4.5.1 through 4.4.5.5. During the 1985 refueling outage, an oddy current examina-tion of two steam generators ("B" and "C") was completed. The examination was conducted from the inlet and outlet sides of the two steam generators on all tubes full-length. The eddy current examination was conducted in accordance with USNRC Regulatory Guide 1.83, Revision 1, and Trojan Technical Specifica-tions. The eddy current examination was conducted with multifrequency inspection equipment. A total of three tubes were plugged in the "C" steam generator. The tubes were plugged due to pitting in the tube sheet region. 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 Specifications. O O 2-105

2.D RELIEF VALVE Cpar r m 3 NUEEG-0737. Item II.K.3.3 requires an annual report of pressurizer relief i and safety valve challenges. In 1985, there were no challenges of the i safety valves or power-operated relief valves. i 1 I I i I T P I i 1 ? i 4 i i l l l l i s I f i ? t f 4 5 i i I l' ) l l 2-106 1 i f t I .,-e- - - _,.~-. -. -..,. r,- ______n.,_,me_,_,,-._wv-

p 2.E CHANGES. TESTS. AND EIPIE m "TS V Federal Regulations (10 CFR 50.59) and the Trojan Facility Operating License NPF-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 Regulatory Cossaissica (WRC) approval, unless the proposed change, test, or experiment involves a change in the Technical specifications incorporated in the license or an unreviewed safety question. In accor-dance with 10 CFR 50.59, summaries of the changes performed and tests and experiments conducted in 1985 are provided, including summaries of the ~ safety evaluations. / 4 i O 2-107 Iu------

2.E.1 PLANT MODIFICATIONS AND DgSIGN CH_W as l The following Plant modifications and design changes were completed in 1985 and are being reported in accordance with 10 CFR 50.59. These modifications were evaluated, and it was detemined that they did not: (a) increase the probability of occurrence of an accident or malfunction of the equipment important to safety as previously evaluated in the Trojan Updated Final Safety Analysis Report (UFSAR), (b) create the possibility of an accident or malfunction of a different type previously evaluated in the UFSAR, or (c) reduce the margin of safety as defined in the basis for any Trojan Technical Specification. In addition, none of these modifications involved a change to the Trojan Technical Specifications. l Other design changes were partially completed during 1985 to meet regula-tory comunitments and will be reported in future Annual Reports when i noncommitted portions of the design are completed. Plant Deslan Chan=e 76-274 The existing overspeed govemor for the diesel-driven auxiliary feedwater pump diesel engine had too great a tolerance to cope with the small margin between overshoot and trip speed (1,300 rpm). Plant Design Change 76-274 replaced the overspeed governor with a fune-tional equipment device with closer tolerance and inernased the engine s overspeed trip setpoint to 1,400 rpm. l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 76-300 The originsi design of the boric acid evaporators provided two (2) canned i rotor concentrate pumps for each evaporator. Subsequent maintenance l difficulties with the canned pumps resulted in the replacement of one i pump on each evaporator with a centrifugal pump located off the evapora-tor skid in order to assess the acceptability of the pumps. Plant Design Change 76-300 provided for permanent installation of the pumps. l \\ l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 76-386 The original design of the waste-gas compressors' cooling water piping from Component Cooling Water System (CCWS) was a hard-pipe connection. This configuration hampered maintenance activities on the compressors. 1 Plant Design Change 76-386 installed piping unions on the CCW piping near the compressors to allow its removal. l l 2-108 -,--------_-,_m ,____._____mm_. - - _ _. _. _ - -., _

This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Chanze 76-442 The NRC radiological effluent Technical Specifications (Appendix I, 10 CFR 50) indicate that redundant oxygen analyzers should be installed in gaseous radwaste systems which are not designed to withstand a hydrogen explosion. Plant Design Change 76-442 installed two oxygen monitors in the common discharge of the waste-gas camp.essors. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 76-509 Safe access did not exist to the various main condenser vent valves located around the 69-ft level on the east side of the main condenser water boxes. Plant Design Change 76-509 provided catwalks to assure personnel safe access to the valves. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design chanze 76-561 Due to the amount of work performed on radioactive and/or contaminated components, there was an extreme need for facilities to handle the decontamination and maintenance of the components. Plant Design Change 76-561 provided the modifications to the hot machine shop and decontamination room facilities needed to decontaminate and work on contaminated equipment. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Chanze 77-009 The voltmeters on the front of nonpreferred 120-V a-c Buses Y01, YO2, and Y03 cabinets only indicated the voltage between a-c phases which was not representative of the nonpreferred instrument bus voltage. Plant Design Change 77-009 installed a voltmeter switch on the front of each panel which allows reading phase-to-phase and phase-to-neutral voltage. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 2-109

Plant Desian Channe 77-144 No permanent lighting existed in either the " anti-C and waste-sorting room" or radweste storage area on the 93-ft level of the Fuel Building. There was also a shcetage of receptacles on the 93-ft level of the Fuel Building. Plant Design Change 77-144 installed lighting and receptacles as required to resolve this issue. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 77-155 A number of problems existed with the Reactor Coolant, System wide-range pressure recorder PR405. PR405 was a single-pen recorder not seismically quellfied and was not powered from a 1E source. Plant Design Change 77-155 installed a new seismically qualified recorder powered from a 1E source. The new recorder has one channel scaled from 0 to 3,000 psig and a second channel scaled from 0 to 750 psig to provide accurate indication at low pressure. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plart Desian Channe 78-022 The 93-ft level of the Fuel Building did not have a convenient location i in which to locate the reactor vessel stud cleaner during refueling. Plant Design Change 78-022 installed a removable platform in the cask wash pit at Elevation 93 ft to mount the stud cleaner on. I This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 78-038 It was identified that electrical and mechanical equipment located in the Main Steam Support Structure are exposed to adverse weather conditions which could have led to their failure. Plant Design Change 78-038 weatherproofed the 69-ft slab in the MSSS and approximately 120 electrical boxes were sealed to prevent damage. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 79-020 As a result of a pipe support survey, it was discovered that several supports which had been added or modified by a previous RDC contained j k discrepancies requiring correction. 2-110 l

Plant Design Change 79-020 provided modifications to the affected sup-ports in order to resolve the identified discrepancies and restore the supports to design requirements. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Chanze 79-035 The bushings and the hinge arms of the spent fuel pool doors did not have enough press fit to remain in the hinge arms during installation or removal of the door. Plant Design Change 79-035 modified the hinge arm bushing in order to eliminate the possibility of their loss into the spent fuel pool. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desixn Chante 79-040 The electrical penetration area is open directly to the environment and contains piping with primary coolant. Valve-packing leakage problems have resulted in unmonitored leaks of airborne activity. Plant Design Change 79-040 replaced the existing valves with hermetically sealed (ie, packless) valves which should ensure leak-tight operation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. . Plant Design Channe 79-085 The carbon steel vent line from the water plant acid storage tank (T-126) is susceptible to blockage from corrosion products caused by sulfuric acid fumes and airborne moisture in the pipe, l l Plant Design Change 79-085 replaced the acid tank vent including the overflow pipe to the neutralizing tank with ruseal polypropylene pipe. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l l Plant Design Change 79-105 Three-Mile Island action prescribed by NUREG-0737 required a Post-Accident Sampling System to provide for sampling the reactor coolant and the Containment atmosphere following severe core damage. l Plant Design Change 79-105 installed the required sampling system. l Although changes to the Trojan Technical Specifications were not neces-sary to perform this modification, a License Change Application was submitted and approved by the NRC as Amendment 106 pursuant to the NRC request in Generic Letter 83-37. It was determined that this change did l not involve an unreviewed safety question. 2-111

Plant Desian Channe 80-013 Boric acid storage tank pressure transmitters and indicators were located in the open passageway such that the ruel Building crane often hit them. Plant Design Change 80-013 relocated the transmitters and indicators such that they are not in the way of crane operations. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 80-021 The 12-kV electrical yard-loop Vault "A" was subject to total submergence in water due to the intrusion of ground water. Plant Design Change 80-021 extended underground service previously terminated in Vault "A" to a pad-mounted switching enclosure. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Chanze 80-069 The circulating water system pH could no longer be properly controlled with the originally installed acid injection system and acid injection lines corroded due to water mixing with acid. O~~' Plant Design Change 80-069 installed a new acid injection system adjacent to the cooling tower basin. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Chanze 80-086 Degradation of the diesel auxiliary feedwater pump batteries had occurred due to the use of commercial lead-acid batteries. Plant Design Change 80-086 replaced the battery charger, battery hold-down brackets, and tFr batteries with nickel-cadmium batteries of a higher capacity rating anu longer life. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l Plant Desian Change 81-018 The location of the reactor coolant pump vibration pickups exposed the probe and particularly the probe wiring to damage from working personnel. Plant Design Change 81-018 installed stainless steel protective boxes that covered each vibration pickup and its related wiring. 2-112

This modification did not involve a change to the Trojan Technical Specifications or an unreviewod safety question. Plant Design Chanze 81-064 The blowdown flow from the steam generators could not be adequately controlled or regulated due to the lack of flow indication. Plant Design Change 81-064 installed flow instrumentation for the individual steam generator blowdown lines. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-073 The flow transmitters used for one channel of auxiliary feedwater flow instrumentation were not environmentally qualified for service in the Main Steam Support Structure. Plant Design Change 81-073 replaced the existing units with transmitters qualified in accordance with NUREG-0588, Category I. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-094 The Residual Heat Removal System suction valves from the Rea: tor Coolant System, NO-8701 and MO-8702, normally have their power supply breakers " racked out" to satisfy Technical Specifications. " Racking out" the supply breakers cesulted in losing position indication for the valve. Plant Design Change 81-094 provided a separate power supply for valve position indication plus a status light for control power breaker position. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 81-106 i The 8-in. hydrogen vent Containment isolation valves MO-10005 through l MO-10012 were not qualified to withstand LOCA dynamic effects during closure. In addition, the motor-operated electric breaks were not environmentally qualified per Bulletin 79-013. The 4-in. chilled water Containment isolation valves and 8-in. valves identified above also had elastomeric seats which were extremely difficult to replace in the field. Plant Design Change 81-106 replaced all 12 valves with qualified replace-ments designed to have easily replaceable elastomeric or metal seats. i i l 2-113

This modification did not involve a change to the Trojan Technical ) Specifications or an unreviewed safety question. Plant Desian Channe 82-015 Spurious "lom-nozzle pressure" alarms were generated when the traveling screen systes shut down while in the automatic mode. Plant Det.lgn Change 82-015 replaced the screen drive control relay with a time-delay relay, utilizing solid-state timing to prevent the alarm. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 82-022 The original design of the main generator output breakers did not pr'<ent closing the breaker with the machine at standstill. Such an even* muld have caused the generator to act as a motor and excessive ove.. eating of the rotor within seconds. Plant Design Change 82-022 provided the necessary relr.rs on associated interlocks to prevent energizing the main generator '.om the offsite transmission grid. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 82-047 Plant Design Change 82-047 was a generic design change that was initiated to expedite repair; and reduce costs associated with pipe and pipe supports found to require modification during calendar year 1982. Each Design Change Package initiated under Plant Design Change 82-047 was provided with an individual safety evaluation. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. d Plant Desian Channe 82-050 The inability to monitor the Chemical and Volume Control System holdup tank (HUT) pressure contributed to collapse of the "B" HUT on May 27, 1982. The pressure transmitter was located in the inlet header such that it had a tendency to fill with water and generate erroneous pressure signals. Plant Design Change 82-050 provided pressure transmitters for each HUT. The transmitters provide an alarm and pump interlock function to prevent pumping the HUTS down to a low-pressure condition which could cause their collapse. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 2-114 . ~

Plant Design Chanze 32-052 The fuel transfer system manipulator crane had the following deficiencies: 1. Cripper engaging problems. 2. No safety circuit to prevent fuel damage when inserting an assembly. 3. A bridge positioning problem. Plant Design Change 82-052 provided the following improvements to the manipulator crane: 1. Installed a new pressurized gripper assembly. 2. Installed a 1,200-lb gripper-up safety circuit. 3. Installed a new 2,100-lb underload circuit. 4. Installed a bridge positioning camera and monitor. 5. Installed a catwalk and safety railing around the bridge drive motor. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Change 82-055 Analysis of the pressurizer relief system prompted by NUREG-0737 indicated that pir ng could have become overstressed as a result of 8 high-pressure transients which actuate the relief and/or safety valves. Plant Design Change 82-055 modified the safety and relief valves and pipe supports, and installed water slug diversion devices in the relief lines to remove the loop-seal fluid upon lifting of the relief valve. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Change 82-059 During the course of normal operation or shutdown, problems with piping and pipe supports are occasionally discovered, and design modification is necessary to correct the problem. Plant Design Change 82-059 is the second in a series of generic Plant design changes and resolved piping and pipe support problems discovered in 1983. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 2-115

Plant Desian Ch===e 82-062 The diesel auxiliary feedwater pump lube oil / engine heating system loss of circulating pump pressure switch was not connected to provide an alarm for the original design change. Plant Design Change 82-062 connects the alarm to an annunciator window in Panel C-160 with reflash to the control room. These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 82-063 The potential exists for the turbine-driven auxiliary feedwater pump turbine to be in standby, not ready for auto start, and without any alarms. This problem was identified in INPO-50gR 82-8. Plant Design Change 82-063 provided the necessary design change to ensure the condition of the trip and throttle valve, No-3071, is alarmed if abnormal. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 82-065 l In order to gain access to remove the "C" service water pump, it was necessary to remove the H&V ducting above the pump. The ducting was installed such that supports and a large amount of ducting had to be removed along with the supply dampeners to the "C" pump. This required the installation of blanks to ensure "A" and "B" pumps receive proper ventilation. I Plant Design Change 82-065 consisted of the addition of four flanges l located to provide for removal of the ducting without removal of the seismic class I duct supports, no matter which service water pump needed i to be removed. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channo 82-069 l The level switches for the reactor cavity sump were inaccessible for maintenance. Incore nuclear instrumentation tubing in the immediate area prevented access to the level switches. Plant Design Change 82-069 relocated the level switches to the opposite side of the reactor cavity sump to improve access. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 2-116

Plant Desixn Chanze 83-004 The Reactor Coolant System wide-range pressure transmitters PT-403 and PT-405 are powered from the same B Train power source. These trans-mitters provide input into the subcooling margin monitors, reactor vessel level indication, Overpressure Hitigation System, and Residual Heat Removal System valve interlocks, and thus, should be train separated. Plant Design Change 83-004 provided the appropriate train separation for the pressure transmitters and the inputs they supply. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Elant Design Channe 83-015 The Reactor Coolant System wide-range pressure inputs to the reactor vessel level indicating system could have been in error by up to 10 per-cent under accident conditions due to environmental influences on PT-403 and PT-405. Plant Design Change 83-015 installed two new Class 1 pressure trans-mitters outside containment which will, therefore, not be subjected to environmental errors. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Channe 83-024 This Plant Design Change provided for modifications to correct the effects of nonconformances found at the wall-roof slab interface in the Auxiliary Building, and for further investigation to identify and correct as necessary, any similar nonconformances that might have existed. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desitn Channe 83-038 The heater drain pump motors and condensate pump motors did not have ) internal electric space heaters to keep their windings dry when shut down. Plant Design Change 83-038 installed space heaters in these pump motors. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. giant Desixn Chanze 83-039 It was identified that 48 safety-related Limitorque motor-operated valves had been identified as having vendor-supplied space heaters connected to individual Class 1E control power circuits intended fer the control of the MOVs. Environmental qualification testing for the MOVs was conducted without power to the heaters. 2-117

Plant Design Change 83-039 disconnected the space heaters from the cir-CI cult where analysis identified such action was acceptable, and provided separate non-1E power supply to the valves requiring space heaters. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Chante 83-043 Tho pressurizer level sensing system was unreliable due to improper installation of the reference les condensing pots. Plant Design Change 83-043 replumbed the transmitter upper sensing lines. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Chante 83-053 As nor1mally configured, a high crankcase pressure signal would shut down the emergency diesel generator if received during the first 15 seconds during an auto start. Plant Design Change 83-053 modified the start circuitry to block any high crankcasa pressure signal inunediately on receipt of an AUTO START signal. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Chante 83-054 The reconsnended design change was the result of an environmental qualifi-cation review of solenoid valves for the Containment hydrogen analysis system sampling valves and reactor vessel head vent valves. The installed configuration of the valves at Trojan was not the same as the tested configuration. Plant Design Change 83-05a provided environmentally qualified disconnects on the affected valves. This modification did not involve a change to the Trojan Technical i specifications or an unreviewed safety question. Plant Desian Chante 83-059 The limit switches on the chilled water Containment isolation valves were found to not be environmentally qualified. Plant Design Change 83-059 replaced the limit switches with environmentally qualified equivalents. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 2-118

Plant Desixn Channe 84-007 The electronic portion of the cable spreading room fire detection / deluge actuation system was unreliable and difficult to maintain due to lack of vendor support. Plant Design Change 84-007 replaced the electronic portion of the detection / actuation system. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desinn Change 8?-008 The Appendix R Fire Protection Review required that assumptions be made in many cases about the type and size of fuses installed in the electrical distribution system and vendor-supplied equipment. Plant Design Change 84-008 provided verification of fuse type and size, and replacement of improper fuses where required. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Des 1Rn Channe 84-021 Freeze protection systems for the main steam pressure transmitters, auxiliary feedwater flow indication, and reactor vessel level indicating system pressure transmitter located in the Main Steam Support Structure did not have blown fuse indication. Plant Design Change 84-021 provided individual circuit blown fuse indication. This mod'"lcation did not involve a change to the Trojan Technical Specifications cc an unreviewed safety question. l l Plant Desian Chanze 84-030 A local pressure gauge was needed to verify the steam generator feed pump hydraulic trip had been reset. Plant Design Change 84-030 installed a permanent pressure gauge on each main feed pump control oil panel. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desir.n Change 84-031 It was identified that electrical train separation requirements were not met in control room Panel C-41. O 2-119

Plant Design Change 84-031 relocated components within Panel C-41 to provide the required train separation. This modification did not involve a change to the Trojan Technical specifications or an unreviewed safety question. Plant Dealen Ch==== S4-033 It was identified that 22 limit switches installed on air-operated control valves were not environmentally qualified. Plant Design Change 84-033 replaced the 22 limit switches with environmentally qualifted equivalents. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Ch==== 84-066 The main generator stator cooling system strainer (YST-1) tends to plus with copper oxide after the Plant has operated for several months. The plugging led to reduced flow and eventually, a forced reduction in power. Plant Design Change 84-066 installed a second strainer and its associated valves in parallel with YST-1. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Channe 84-070 During the fuse walkdown for RDC 84-008, high temperatures were noted in distribution panels Y01, Y02, and YO3. Plant Design Change 84-070 instal.4 fans on the panel cabinets to increase air circulation and lower internal ambient temperatures. This modification did not involve a change to the Trojan Technical specifications or an unreviewed safety question. Plant Desian Channe 84-072 Instrument and control personnel required both instrument air and domineralized water when working at the incore nuclear instrumentation seal table. The lack of connections in the seal table area required routing temporary hoses to the area from 93-ft Elevation each outase. Plant Design Change 84-012 routed permanent instrument air and dominera11:ed water into the seal table pit. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 2-120

Plant Desinn Change 84-075 Steam generator water level (SGWL) transmitter reference les heatup contelbuted significantly to the overall SGWL loop inaccuracy during postulated harsh environment conditions. Plant Design Change 84-075 insulated the SGWL transmitter reference legs to reduce the overall loop inaccuracy. This modification did r it involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desitn Chante 84-081 Calibration of the reactor vessel level indicating system in 1984 showed an increase in voiding over the 1983 calibration., The voiding suggested a problem with system leakage. Plant Design Change 84-081 conducted a pressure test to locate leaks, seal welded the leaking connections, and provided system modifications to prevent leaks. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Design Channe 84-088 The Appendix R analysis performed by PCE identified a problem with regard to loss of control of the steam generator power-operated relief valve due to a cable spreading room fire. Plant Design Change 84-088 installed a manual control station with a nitrogen supply to provide remote operation of these valves from outside the control room. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Des 1Rn Change 84-090 As a result of the Appendix R Review, a number of shutdown systems were identified which are redundant in the same fire area or were candidates for spurious operation within a given fire area. Plant Design Change 84-090 provided decouple switches for the affected circuits to ensure that they are available to perform their safe shutdown function. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 2-121

Plant Desian Ch===e 84-111 Wh11e disconnecting main feed pumps from their turbine drivers during maintenance outages, the heating and ventilation ducting over the turbine has to be disconnected and relocated to allow the upper turbine casing to be lifted to the turbine deck. Plant Design Change 84-111 modified the heating and ventilation ducting to allow removal of the turbine case without removing the heating and ventilation ducting. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. Plant Desian Ch===e 84-130 The electrical control switches for the Overpressure Mitigation System were not electrically separated as identified in a Trojan nonconfo mance report. i Plant Design Change 84-130 provided the required electrical separation for the overpressure Mitigation System. 1 This modification did not involve a change to the Trojan Technical i Specifications or an unreviewed safety question. Plant Desian Channe 84-131 The reactor vessel head guide stud storage racks were not capable of supporting the guide studs during a seismic event. Plant Design Change 84-131 replaced the existing rack with a new pennanent seismic Class I rack. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safet question. Plant Deslan Channe 85-013 011 splash in the emergency diesel generator diesel engine crankcase inadvertently tripped the high-pressure detector rendering the diesel inoperable. Plant Design Change 85-013 installed a splashguard plate between the crankcase pressure detector and the engine housing per the manufacturer's recommendation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 2-122

i Plant Desian Change 85-017 The Intake Structure traveling screen wash pumps exhibited extremely high { vibrations since installation. Plant Design Change 85-017 installed two lateral support ribs to change the pump resonance frequency per the manufacturer's recotunendation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O O 2-123

2.N.2 LICENSE "*"LTT3 In 1985, a total of nine license amendments were issued by the NBC. Threaty requests for license amendments [ License change Applications (LCAs)! were submitted to the NRC for spyroval, two resulted in license amendments and one was cancelled. Of eight LCAs previously submitted, six received NBC approval and have been issued. As of December 31, 1985, 18 LCAs had not yet been acted upon by the NBC. l 4 1 l t l 2-124

-_____._m l O T m ' 2.E.2-1 Sheet 1 of 7 AMENDHENTS TO THE TROJAN OPERATING LICENSE ISSUED IN 1985 Amendment -{ Raaber Data Sublect i 100 01/09/85 This amendment authorised the use of qualified individuals in dual role STA/Sao positions, thus ~ meeting the minimum shift staffing requirements of 10 CFR 50.54(m)(2). The NBC has detemined that this amendment meets the i eligibility criteria for categorical exclusion set . forth in 10 CFR 51.22(c)(10). pursual.t to 10 CFR 51.22(b) no environmental impact statement or environmental assessment needed to be prepared in connection with the issuance of this amendment. i i It has been concluded by the NBC 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 4 r conducted in compliance with the Commission's regu-lations and the issuance of this amendment will not i be inimical to the common defense and security or to the health and safety of the public. 1 101 02/05/85 Issuance of this amendment reflected the termination i of Trojan participation in the US/ International Atomic Energy Agency (IAEA) Safeguards program in l accordance with NRC written notification. This amendment involved changes to the license pur-j suant to 10 CFR parts 50 and 75 relating solely to safesuards matters, and did not involve any con-struction impacts. The amendment was confined 4 solely to administrative changes. Accordingly, this amendment meets the eligibility criteria for cate-j gorical exclusion set forth in 10 CFR 51.22(e)(12). j pursuant to 10 CFR 51.22(b), no environmental impact { statement or environmental assessment needed to be prepared in connection with issuance of this { amendment. The NBC has concluded thats (1) there is reasonable { assurance that the health and safety of the public i t will not be endangered by operation in the proposed l menner, and (2) such activities will be conducted in } compliance with the Consission's regulations and the I issuance of this amendment will not be inimical to t the cosumon defense and security or to the health and l safety of the public. 2-125 l ,w--.--_- ,--, _ _, ~. _,,,, - _,,- _ _,.y._

TABLE 2.E.2-1 Sheet 2 of 7 Amendment Number Date Subiect 102 02/06/85 This amendment provided requirements for operability, visual inspections, and periodic testing of mechani-cal snubbers and changes to the surveillance requirements for hydraulic anubbers. This amendment involved a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC has determined that the amendment involves no significant increase in the amounts, and no signifi-cant change in the types, of any effluents that may be released offsite, and that there would be no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards considera-tion rand there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needed to be prepared in connection with issuance of this amendment. 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 regu-lations, 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. 103 03/04/85 Issuance of this amendment allowed Plant operation in Modes 1, 2, and 3 with the boron injection tank (BIT) bypassed, eliminated, or reduced in boron concentration to a level as low as zero ppm. This amendment involved a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC has determined that the amendment involves no significant increase in the amounts, nor change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a 2-126

TABLE 2.E.2-1 sheet 3 of 7 Amendment Bumber Data Rubiect proposed finding that this amendment involves no significant hasards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needed to be prepared in connection with the issuance of Ahls amendment. It was concluded by the 33C that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed menner, and (2) such activities will be conducted in compliance with the Cossatssion's resu-lations, 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. 104 03/15/85 This amendment provided clarification of the sur-O veillance test requirement for the pressuriser power-operated relief valve (PORV) when used for low temperature overpressure protection. Also included in this amendment was a revised basis statement for thermal-hydraulic limits to account for the recent upflow modificatica in the lower reactor internals. This amendment involved a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR part 20. The BBC has determined that the amendment involves no significant increase in the amounts, and no signifi-l cant change in the types of any effluents that may j be released offsite, and that there would be no significant incrosse in individual or cumulative occupational radiation exposure. The Comunission previously published a proposed finding that this j amendment involves no significant hasards considers-tion and there has been no pub 11e cosusent on such finding. Accordingly, this amendment meets the eligibility criteria for categorical owelusion set forth in 10 CFR 51.22(e)(9). pursuant to 10 CFR 51.22(b), no environmental impact statement i or environmental assessment needed to be prepared in { connection with the issuance of this amendment. 2-127

TABLE 2.E.2-1 Sheet 4 of 7 AmendmSnt Number Date Subject The NRC 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. 105 04/04/85 This amendment incorporated Technical Specifications prepared in accordance with guidance provided in NRC Ceneric Letter 83-37. These Technical Specifi-cations reflect equipment added in response to NUREC-0737 for post-TMI safety improvem&uis. Equipment included were noble gas monitors (II.F.1.1); Containment high-range radiation monitors (II.F.1.3); Containment water level monitors (II.F.1.5); and sulfur dioxide detectors (III.D.3.4 - Control Room Habitability Requirements). This amendment involves a change in the instatistion or use of a facility component located within the restricted area ac defined in 10 CFR Part 20. The NRC has determined that the amendment involves no significant increase in the amounts, and no signif-leant change in the types, of any effluents that may be released offsite, and that there is no signifi-cant increase in individual or cumulative occupa-tional radiation exposure. The NRC has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categori:a1 exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmantal impact statement or environmental assessment needed to be prepared in connection with issuance of *ne amendment. The NRC concluded thats (1) there is reasonable assura*.co 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 Com.nission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. 2-128

_ _ _ _. _ _ _ _ _ _m i i I e i TABLE 2 E.2-1 Sheet 5 of 7 t i Amendment } Raher. Date subiact 106 04/24/85 This amendment approved Technical specifications on i overtime limits, for calibration of turbine trip } inputs for anticipated reactor trip (Generic Letter 82-16), and for post-accident sampling i l requirements (Generic Letter 83-37). These are all post-TNI safety improvements and are incorporated in accordance with guidance provided in the referenced Generic Letters. Also accomplished by this amend- { ment was an administrative change,that moved the j requirement for programs for (1) reducing leakage i to systems outside Containment, (2) in-plant radia-j tion monitoring, and (3) secondary water chemistry, i from the license conditions to the Technical specifications (section 6.8). This amendment involved changes in inspection or surveillance requirements and in the installation or use of a facility component located within the restricted area as defined in 10 CFR part 20. The NRC has determined that the amendment involved no O significant increase in the amounts, and no signifi-cent change in the types of any offluents that may be released offsite, and that there would be no significant increase in individual or cumulative occupational radiation exposure. The Comunission has previously issued a proposed finding that this amendment involves no significant hasards considers-tion and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). This amendment also relates to changes in recordkeeping, reporting or administrative procedures or requirements and accordingly meets the criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). pur-suant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needed to be prepared in connection with issuance of this amendment. The NBC concluded thatt (1) there is reasonable j assurance that the health and safety of too public i will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in I compliance with the Cosmission's regulations and the issuance of this amendment will not be inimical to l O the common defense and security or to the health and [ safety of the public, t 2-129

TABLE 2.E.2-1 Sheet 6 of 7 Amendment Number Date Sub3ect 107 10/04/85 This amendment reflected changes made to emergency diesel generator operation and testing in response to Generic Letter 84-15 concerns. This amendment involved a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The NRC has determined that the amendment involves no signifi-cant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there would be no significant increase in individual or cueulative occupational radiation exposure. The Commission has previously published a proposed finding that the amendment involves no significant hazards considera-tion and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needed to be prepared in connection with issuance of the amendment. The NRC has concluded that: (1) there is reasonable assurance that the health ar.d 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 the amendment will not be inimical to the common defense and security or to the health and safety of the public. 108 12/05/85 This amendment reflected cesanizational changes within PCE as well as clarified and better defined the membership requirements of the Trojan Nuclear Operations Board (TNOB). This amendment related to changes in recordkeeping, reporting, or administrative procedures or require-ments. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needed to be prepared in connection with issuance of this amendment. 2-130

I i TABLE 2.E.2-1 Sheet 7 of 7 l Amendment

- r Date Subiect The NBC has concluded that:

(1) there is reasonable i 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 the amendment will not be inimical to the comunon defense and security or the health and safety of the public. s A i .i j i I i 1 I i J l i i I 0 a 2-131 l i

'~ TABLE 2.E.2-2 Sheet 1 of 4 STATUS OF LICENSE CHANGE APPLICATIONS SUBMITTED TO AND UNDERGOING REVIEW BY THE NRC AS OF DECEMBER 31, 1985 LCA Date Number Submitted Subject and Status 99 01/27/84 Reactor Vessel Material Surveillance Program: Updates the reactor vessel material irradiation schedule and incorporates the new 10 CFR 50, Appendix G, pressure-temperature limit requirements. Revision 1 of this LCA (submitted on December 11, 1984), was rejected by the NRC and returned to PGE due to an error. Revision 2 of LCA 99, prepared in accordance with NRC letter of January 23, 1985, was submitted on July 12, 1985 and is undergoing NRC review. 113 11/29/84 Mode 3 Reactor Coolant Loop Operating Requirements: Requires operation of four reactor coolant loops in Mode 3 when any CRDMs are energized. In the event that less than four loops are in operation, a new surveillance require-O ment is added for de-energizing of all CRDMs every 12 hours. Revision 1 to this LCA was sent to the NRC on December 27, 1985. 117 01/30/85 Reactor Trip and ESFAS Instrumentation: Revises operability and testing requirements for the Reactor Trip System and Engineered Safety Feature Actua-tion System (ESFAS). Revision 1 of this LCA was sent to the NRC on September 23, 1985. PCE is currently preparing a revision of this LCA. 118 03/12/85 Technical Specification Improvements: Provides a number of improvements to the Trojan Technical Specifications. Changes include (1) clarification of undervoltage RCP trip setpoint and allowable values; (2) reference to boration system rather than a single tank; (3) elimination of possible confusion regarding rod position indication system channels; (4) increased moni-toring frequency of Axial Flux Difference (AFD) during inoperability; (5) clarification of Component Cooling Water (CCW) and Service Water System (SWS) operability requirements; and (6) various editorial corrections. By letter of August 22, 1985 PCE withdrew a portion of this LCA. This portion requested revision of Technical Specification 1.8 concerning Containment integrity. 2-132

TABLE 2.E.2-2 Sheet 2 of 4 LCA Date Number Submitted Subject and Status 120 04/19/85 Technical Specification Improvements: Clarifies the definition of OPgRABLE and revises the sur-veillance requirements for the Control Room Emergency Ventilation System (CREVS). Also included in this LCA was a request to clarify the ACTION statement associated with the Limiting condition of operation for structural integrity of the Reactor Coolant System. This portion of LCA 120, however, was withdrawn by PCE letter of November 8, 1985. 121 05/02/85 Technical Specification Improvements: Includes modifications to (1) revise the Surveillance Requirements for AIIAL FLUX DIFyERENCE (AFD), (2) delete the ACTION statement associated with reportability of out-of-specification RCS chemistry, and (3) make editorial corrections. By letter of September 6,1985 PCE provided clarification of the LCA in accordance with discussions with the NRC regarding interpretation of the AFD Surveillance Requirement. 122 06/14/85 Fire Pump Diesel Engine Surveillance, RCS Volume, and Low Population Zone: Allows for the performance of fire pump diesel engine inspection during operational modes, corrects the Reactor Coolant System (RCS) volume (now in agreement with that appearing in the Updated FSAR), and provides a new figure to more clearly depict the 2.5-mile Low Population Zone. 123 06/14/85 Bypass of Emergency Diesel Generator Fail-to-start Tript ( Adds " fail-to-start" to the group of emergency diesel ger.erator trips which are not to be automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection signal. 124 07/29/R5 Containment Isolation Provisions and Leakage Rate Testing Revises containment leakage rate testing. Several changes are also included to the table listing Containment isolation valves. 1 0 2-13J

3 i ) TABLE 2.E.2-2 Sheet 3 cf 4 l LCA Date Rmber Suhaitted Subleet ' Status E f j 125 08/07/05 TIBI Technical Specification Changes: f t t Incorporates TIII-related items pursuant to NBC model j Technical specifications issued in Generic Letter 83-37. i These additions include core exit thermocouples (CET) and Reactor Vessel Level Instrumentation System (IVLIS) in j accordance with EUREG-0737, Item II.F.2. l 126 03/16/85 Exclusion prom LCO 3.0.43 i I provides more operational flexibility by allowing entry i into operational modes with selected equipment out-of-service. (A sndment expected to be issued in April 1986.) 4 127 09/03/85 CCW System Valve Surveillance [ Revises surveillance requirements for Component Coeling j Water system (CCW) valves to incluJe specified signals for automatic valve closure, a change consistent with recom-1 mondations of NRC Generic Letter 83-104. 4 s i 120 09/10/85 Onsite Electrical Distribution Systems: I J l Revises the operability requirements for onsite AC and DC l { electrical power distribution systems. l j 129 09/13/85 Organisational Changes: l ) Reflects a change made to the POE Wuclear Division Organi-f l sation in that both the onsite and offsite (headquarters) ( 1 Quality Assurance organisations now report to the Manager. l Buclear Quality Assurance. (Amendment to be issued in { Nerch 1986.) i j 130 09/13/s5 Revision to Technical specification 6.8, procedures ~ Reflects a more efficient menner for review and approval ( l of plant procedures by allowing administrative policies ( 1 and procedures to be established, implemented and main-l { toined in accordance with the Nuclear Quality Assurance program. This change is intended to reduce the emphasis placed on nonsignificant safety issues, therefore, enabling the pts and General plenager to provide more i thorough reviews of safety-related activities. j t .t { 2-134 s i i

TABLE 2.E.2-2 Sheet 4 of 4 LCA Date Number Submitted Subject and Status 131 10/11/85 Containment Ventilation Isolation System - PRM-1E: Clarifies the surveillance requirement for the Containment Ventilation Isolation System (CVIS) by identifying, via reference, which of the containment radiation monitoring channels must be included in system operability verifications. 133 11/01/85 Inoperable Control Rods: Revises Technical Specification for " Movable Control Assembles" with regard to electrical inoperability of control rods and provides more distinct ACTION statements consistent with the significance of the specific malfunc-tion. PCE to provide additional clarification of this LCA in early 1986. (NRC expects issue of an Amendment in March 1986.) 134 10/29/85 Technical Specification 3.7.1.4 - CST Level: Increases the minimum water level to be maintained in the Condensate Storage Tank (CST) in accordance with NRC letter of September 13, 1985 regarding that desired for operability of the Auxiliary Feedwater System. l O 2-135 I

l q 2.E.3 LICENSING DOCUMENT CHANGE REQUESTS (LDCRs) j APPROVED DURING 1985 Licensing Documents consist of various pCE 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 Spect-fications does not result, if an unreviewed safety question is not created, or if there is no degradation to plant security, decrease in effectiveness of the Emergency plan, or reduction to the comunitments in the QA program description. The following is a summary of the Licensing Document Change Requests approved in 1985. LDCRI g4-04 Document: Radiation protection program, pCE-3005 Status: Approved April 12, 1985 and issued April 12, 1985 as Revision 3. Safety Evaluation: This LDCR was initiated to reflect various Company organisational changes as well as provide a general update of current practices / requirements. All changes made to this Topical Report are considered administrative in nature and have no effect on the Trojan Operating License and Technical Specifica-tions, nor do they involve any unreviewed safety or environmental questions. LQGE: 84-08 Document: Updated Final Safety Analysis Report, UFSAR 31ging: Approved August 28, 1985 and held for incorporation into the Updated FSAR (pending NRC approval of License Change Application 124). Safety Evaluation: Changes initiated by this LDCR clarify and update the FSAR, correcting discrepancies found between the UFSAR, the Trojan Technical Specifications, and 10 CFR 50. The revisions do not involve an unre-viewed safety or environmental question. pCE License Change Application (LCA) 124, submitted to the NRC on July 29, 1985, requests related revisions to the Trojan Technical Specifications. In accordance with 10 CFR 50.59, NRC approval of the LCA is required prior to implementation of this LDCR. O 2-136

LDCR: 84-09, Revision 1 Document: Trojan Nucleae Plant Security Plan, PGE-1017 Status: Approved February 27, 1985 and issued February 28, 1985 as Revision 9. 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. LQCE: 84-13 Document: Updated Final Safety Analysis Report UFSAR Status: Approved March 19, 1985 and issued as part of Amendment 3 to the Updated FSAR on July 1, 1985. Safety Evaluation: This change was ini*. lated to achieve consistency with the QA Program and the Nuclear Division Procedures (NDP 500-1) regarding the Trojan Nuclear operations Board (TMOB). This doea not result in a change to the Technical Specifications nor does it create an unreviewed safety or environmental question. LDCR: 84-19 Document: Environmental Qualification Program Manual for the Trojan Nuclear Plant PCE-1025 Status: Approved June 27, 1985 and issued July 8, 1985 as Amendment 2. Safety Evaluation: This amendment reflects the ongoing environmental qualification program efforts. All changes were administrative in nature and did not involve a change in the Technical Specifications incorporated in the Trojan Operating License or an unreviewed safety or environmental question. Any changes made in the facility, procedures, tests, or analyses as described in the original version of PCE-1025 have either received prior NRC approval pursuant to 10 CFR 50.59(c) and 10 CFR 50.90, or were effected without NRC approval cased 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 Subsection (f) or (h). O 2-137

~~ LDER: 84-20. Revision 1 \\~' Document: Updated Final Safety Analysis Report, UFSAR Status: Approved July 15, 1985 and held for incorporation in Amendment 4 to the Updated FSAR (scheduled for issue July 1986). Safety Evaluation: This LDCR was initiated to permit Plant operation with reduced service water flows through the Compo-nent Cooling (Jater (CCW) heat exchanger, other sys-tem flow requirements have also been revised as a result of Plant changes and reanalysis of specific compor.ents. These changes are based on maintaining the design heat removal rates; therefore, there is no reduction in the margin of safety provided by the design as described in the FSAR. The changes do not involve an unreviewed safety question and do not result in a significant hazard. LDCE: 84-22 Document: Inservice Inspection Program for the First 10-Year Interval, PGE-1032 Status: Approved March 22, 1985 and issued May 2, 1985. Safety Evaluation: This Topical Report defines the Trojan Nuclear Plant implementation of inservice inspection (ISI) require-monts as set forth in 10 CFR 50.55(g). The ISI Pro-gram was developed from an engineering review of Plant systems, components, and supports and is in compliance with the Trojan Technical Specifications. There are no unreviewed safety or environmental questions as a result of this LDCR. LDCR: 85-01 Document: Trojan Radiological Emergency Plan and Procedures Manual, PGE-1008 Status: Approved May 1, 1985 and issued May 9, 1985 as Amendment 6 to Chapters 3 through 7 (Trojan Radiological Emergency Plan). Safety Evaluation: Changes consist of clarification and revision of the information presented in the Trojan Radiological Emergency Plan. The Emergency Plan is not referenced O 2-138

in the Technical Specifications, except for the annual audit of the Plan required by the TNOB; there-fore, the Technical Specifications were not affected by this LDCR. The changes involve no unreviewed safety or environmental questions and did not affect any other licensing documents, conunitamnts, or criteria. The effectiveness of the Emergency Plan was not decreased and remains consistent with the standards of 10 CFR 50.47(b). LDCR: TNP 85-02 Document: Nuclear Division Headquarters Training Program, PGE-8009 Status: Approved July 12, 1985 and issued July 19, 1985 as Amendment 2. Safety Evaluation: The change initiated by this LDCR will further ensure that headquarters personnel are familiar with administrative orders and safety procedures in effect at Trojan prior to performing work onsite. This change is intended to help prevent accidents involving personnel and equipment and an improvement in training effectiveness. O LDCR: 85-03 Document: Updated Final Safety Analysis Report, UFSAR Status: Due to the volume of changes involved. LDCR 85-03 was divided into nine individual change requests to provide approval by chapter and/or section. The last change request was approved June 17, 1985 and Amendment 3 to the Updated FSAR was issued July 1, 1985. Safett_ Evaluation: Pursuant to 10 CFR 50.71(e), annual revision of the FSAR is required to assure that the information in the FSAR contains the latest material reflecting the design of the Plant. All changes initiated with this LDCR were editorial and/or administrative in nature and did not involve a change to the Technical Speci-fications or any unreviewed safety or environmental questions. Any changes made in the facility, proce-dures, tests, or analyses as described in the original FSAR have received prior NRC approval pur-suant to 10 CFR 50.59(c) and 50.90, or were effected O 2-139

O without NRC approval based on a separato safety / environmental evaluation pursuant to 10 CFR 50.59(a), or were requirsd by NRC request pursuant to 10 CFR 50.54(f) or (h). LDCR: 85-04 s Document: Trojan Nuclear Plant Spent Fuel Storage Rack Replacement Report, PGE-1037 Status: This proposed Amendment I was approved April 19, 1985. Safety Evaluation: This LDCR was initiated for the possibility that Spent Fuel Pool (SFP) reracking work would have to be halted prior to completion to allow for the 1985 refueling activities, and then resumed no less than 60 days following the last fuel removal from the reactor. The changes provided an evaluation of the effects on Plant operation and safety of conducting a refueling operation with between 6 and 11 (of 12) new spent fuel racks installed in the SFP. The Spent Fuel Modifications were completed prior to commencement of refueling operations, therefore eliminating the need for changes proposed by this LDCR and it was never implemented. LDCR: 85-05 Document: PCE Nuclear Quality Assurance Program, PCE-8010 Status: Approved April 22, 1985 and issued April 29, 1985 as Revision 10. 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 accident could be created. No reduction of comaltments described in the QA Program for safety-related com-ponents will occur. No unreviewed safety questions will result. Pursuant to 10 CFR 50.54(a)(3), Revi-sion 10 does not reduce commitments in the program description previously submitted to the NRC in Revision 9. O 2-140

j \\ LDCR: 85-06 Document: Regulatory Guide Policy Manual (RGPM) PGE-1028 Status: Approved June 20, 1985 and issued July 15, 1985 as Amendment 3. 1 Safety Evaluation: The Regulatory Guide Policy Manual (RGPM) establishes 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 new or revised Regulatory Guides. This Safety Evaluation and the IHPs are written based on full compliance with the Trojan Technical Specifications. Any resulting con-flicts are written as exceptions to the Regulatory Guides; therefore, no changes to the Technical Speci-fications are necessary. This LDCR has been deter-mined to involve no unreviewed safety questions or environmental mattee and does not have an effect on any other licensing documents, commitments, or criteria. LDCR: 85-07 Document: Trojan Nuclear Plant Security Plan, PCE-1017 Status: Approved June 19, 1985 and issued June 28, 1985 as Revision 10. 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. l LDCR: 85-09 Document: Trojan Nuclear Plant Security Plan, PGE-1017 1 Status: Approved September 30, 1961 and issued September 30, 1985 as Revision 11. 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. O 2-141 l 1

.~ ~. u ggg: 85-11 i Document: Updated Final Safety Analysis Report, UFSAR Status: Approved October 18, 1985 and held for incorporation in Amendment 4 to the Updated FSAR (scheduled for issue July 1986). Safety Evaluation: This LDCR was initiated to remove reference to temperature difference between the 33-and 500-ft level on the 500-ft meteorological tower, since only the 33-and 200-ft temperature difference is used to determine atmospheric stability. This change has no effect on the Technical Specifications and does not create an unreviewed safety or environmental specification. ggg: 85-13 Document: Environmental Qualification program Manual for the Trojan Nuclear Plant, PGE-1025 Status: Approved December 23, 1985 and issued December 31, 1985 as Amendment 3. i Safety Evaluation: Initiation of this LDCR represents progress made in the environmental qualification program. All changes were administrative in nature and did not involve a change in the Technical Specifications incorporated i in the Trojan Operating License or an unreviewed i safety or environmental question. Any changes made in the facility, procedures, tests, or analyses as described in the original version of M E-1025 have either received prior NRC approval pursuant to 1 l 10 CFR 50.59(c) and 10 CFR 50.90, or were effected i without NRC approval based on a separate safety / l environmental evaluation pursuant to 10 CFR 50.59(a), l or were required by NRC request pursuant to 10 CFR 50.54 Subsection (f) or (h). QCE: 85-18 Document: Offsite Dose Calculation Manual. PGE-1021 Status: Approved December 31, 1985 and scheduled for issuance I in February 1986 as Amendment 3. Safety F 'sluation: In accordance with Trojan Technical Specifica-tion 6.15.2, detailed information regarding changes made to the Offsite Dose Calculation Manual (ODCM) is included in the Radioactive Effluent Release Report and may be found in Section 2.A.4 of this document. 2-142

. _ _ ~ _. 2.E.4 PLANT TESTS I The following Plant tests were performed in 1985 and are reported in accordance with 10 CFR 50.59. Temporary Plant Test 113 Temporary Plant Test 113 was perforised to verify the proper functioning of the automatic gas analyzer. This test did not involve an unreviewed i safety question nor a change to the Trojan Technical Specifications. 4 i Temoorary Plant Test 114 4 Temporary Plant Test 114 was performed to verify proper operation of the Card Key Access System hardware and software for most door operations and conditions. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Tessorary Plant Test 115 i Temporary Plant Test 115 was perforised to verify the proper operation of the Card Key Access System hardware and software for most door opera-tions. Following completion of this test on a door, that door is con-sidered successfully transitioned to the new system. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. O Temporary Plant Test 116 Temporary Plant Test 116 was performed to verify the proper operation of perimeter zone alarm system hardware and software on the new Card Key Access System. Following completion of this tost on a zone, that zone was considered transitioned into the new Card Key Access System. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 117 1 Temporary Plant Test 117 was performed to evaluate and quantify possible l errors in the PERM iodine and particulate composite samplers. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. i Temporary Plant Test 118 i' Temporary Plant Test 118 was perforined to document all Class 2 hydro-static testing required by ASME Section XI, 1974 edition, including the E summer 1975 amendment. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. O 2-143

2 Temporary Plant Test 119 Temporary Plant Test 119 was performed to acquire data for evaluation of the voltage condition on the preferred buses Y-11, Y-13. Y-22, and Y-24. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 120 Temporary Plant Test 120 was performed to determine the feasibility of installing a filter in the condensate system downstream of the condensate demineralizers. This test did not involve an unreviewed safety question nor a change to the Trejen Technical Specifications. Temporary Plant Test 122 Temporary Plant Test 122 was performed to measure hydrogen buildup in a high integrity container filled with dewatered radioactive resin prior to shipment for burial. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 123 Temporary Plant Test 123 was performed to obtain the current throttle valve positions of certain service water components. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 124 Temporary Plant Test 124 performed a full stroke of the accumulator check valves. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 125 Temporary Plant Test 125 was performed to gather data on the AFW pump suction pressure transmitters to determine if excessive pump vibration, environmental conditions, or system hydraulic transients contribute to calibration drift or transmitter component damage. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 126 Temporary Plant Test 126 was performed to verify ground relay logic. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. O 2-144

Tensorary Plant Test 127 Temporary Plant Test 127 was performed to verify the transfer of feedwater supply to the steam generators from AFW directly to the main feedwater regulating valves without using the main feedwater bypass valves. This test did not involve an unreviewed safety question nor a change to the Trojen Technical Specifications. Temporary Plant Test 128 Temporary Plant Test 128 was performed to collect data on the thermal performance of the CCW heat exchangers to determine if required service water flow to the component cooling water heat exchangers can be reduced. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 129 Temporary Plant Test 129 was perfor1med to verify flow rate data for the "A" service water system while simulating emergency conditions. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 130 Temporary Plant Test 130 was performed to verify flow rate data for the "B" service water system while simulating emergency conditions. This O test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 131 Temporary Plant Test 131 was performed to verify that all stator cooling runback and alaria setpoints are set to the present General glectric recommendations. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 132 Temporary Plant Test 132 was performed to calibrate service water i Trains A and B annubar flow elements. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 133 Temporary Plant Test 133 was perforined to verify the diesel AFW pump time delay relay logic. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. 2-145

Temporary Plant Test 134 Temporary Plant Test 134 was performed to verify that the switchyard breaker failure scheme is functional prior to startup. This test does not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 135 Tamporary Plant Test 135 was performed to stroke test the Containment spray pump suction valves and discharge check valves. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 136 Temporary Plant Test 136 was performed to verify flow to the CCW heat exchanger for the projected low river level of 2.0 feet below Mean Sea Level. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 137 Temporary Plant Test 137 was performed to verify proper operation of the turbine-driven AFW pump. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 139 Temporary Plant Test 139 was performed to verify that the feedwater recirculation control modifications operate as designed. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 140 Temporary Plant Test 140 was performed to verify the manual operability of steam generator power-operated relief valves in the case of loss of control power. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 141 Temporary Plant Test 141 was performed to verify structural integrity and leak tightness of the Reactor Coolant System. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 142 Temporary Plant Test 142 was performed to provide information about temperature stratification in the pressurizer surge line. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. 2-146

- _.. = _ = ) Temporary Plant Test 143 i Temporary Plant Test 143 was performed to verify that both AFW pumps repeatedly started automatically from the standby, auto start mode and i achieved steady state flow conditions without tripping on low suction pressure. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temocrary Plant Test 146 Temporary Plant Test 146 was performed to optimize charging flow, reactor coolant pump seal flow and pressurizer level control. This test did not i involve an unreviewed safety question nor a change to the Trojan { Technical Specifications. l Temocracy Plant Test 147 Temporary Plant Test 147 (Section 9.1) was performed to verify that the PERM-6 moisture removal system functioned per design. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. i Temporary Plant Test les l Temporary Plant Taat 148 was performed to verify the diesel AFW pump time delay relay logic. This test did not involve an unreviewed safety O question nor a change to the Trojan Technical Specifications. Temporary Plant Test 149 Temporary Plant Test 149 was performed to verify the quantity of vacuum on the high, middle, and low gas channels. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Temporary Plant Test 150 Temporary Plant Test 150 was performed to verify the operation of the control circuitry for the feedwater isolation valve hydraulic system circulating pump. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. Tgeporary Plant Test 151 Temporary Plant Test 151 was performed to verify the practicality of a proposed change to Periodic Operating Test 2-4 test methodology, which determines leakage across SI accumulator check valves (CK 8956A-D). This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. l !O 2-147 i l I J

1 ) Temporary Plant Test 152 Temporary Plant Test 152 was performed to demonstrate the acceptability of LED type indicator lamps for use in control panel valve, pump and breaker indication circuitry. This test did not involve an unreviewed 1 safety question nor a change to the Trojan Technical Specifications. O 4 0 2-148

l l 2.E.5 CHANGES TO PROCEDURES Procedures described in the Trojan Updated FSAR are used by the Trojan Plant 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 1985, the following departments made changes to the safety-related procedures in accordance with 10 CFR 50.59, and concluded that none of the changes involved unreviewed safety questions: Trojan Nuclear Plant Nuclear Safety & Regulation Nuclear Plant Engineering Environmental Sciences Nuclear Plant Quality Assurance Fuel Operations Purchasing and Materials Management Corporate Records 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 procedural processes. A safety evaluation was conducted for each change, in accordance with O 10 CFR 50.59, and was reviewed and approved by the appropriate personnel. The review concluded that the probability of occurrence 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. O 2-149

2.E.6 SETPOINT CHANCES d The following setpoint changes were made in 1985 to instruments, alarms, relief valves, and other control and protective devices whose setpoints ) are described in the Updated FSAR and are reported in accordance with { 10 CFR 50.59: Plant Setooint Channe 84-14 The reactor coolant pump undervoltage relay trip setpoints were identified as being set 2 volts above the Technical Specification setpoint, but still meeting the allowable value (Specification 2.2.1. Table 2.2-1). The setpoint (168 percent) had been based upon a nominal bus voltage of 12-kV when in fact the nominal bus voltage should be 12.47-kV. License Change Application 118 was submitted to clarify this Limiting Safety Setting. Plant Setpoint Change 84-14 increased the trip setpoint voltage to ensure the setpoint is consistent with Technical Specifications. Plant Setooint channe 85-05 Plant Design Change 84-075 insulated the steam generator water level (SGWL) instrument reference legs. As a result, the reference leg heatup error was reduced from 6.23 percent to 1.22 percent (maximum). This reduction in the reference leg heatup error permitted a reduction in the overall error in the SGWL measurement. \\ The SGWL setpoint had been administratively controlled at a setpoint of 120 percent (the Technical Specification limit is 15 percent). Plant Setpoint change 85-05 lowered the SGWL low-low level trip setpoint to reduce the likelihood of spurious trips thereby increasing overall Plant reliability. The assigned setpoint of 115 percent will ensure that the reactor trip and AFW start will always occur before the safety analysis limit of 0 percent narrow-range instrument span and 5 percent Technical Specification limit are reached. Plant Setooint Chanze 85-10 Under certain conditions, after an automatic start of both auxiliary feedwater pumps, it was discovered that both trip on low-suction pressure. Plant Setpoint Change 85-10 increased the low-suction pressure trip time delay setting from 10 see to 28 sec. The pump manufacturer indicates that the pump can tolerate low-suction pressure for approximately 30 seconds without damage. LER 85-09 reported the trip of the diesel-driven auxiliary feedwater pump due to low-suction pressure. s 2-150

plant Setpoint change 85-15 The pressurizer level hi-trip bistablar (Instrument Numbers 459, 460, and 461) setpoint calibratio.. orift is higher than the expected allowance of 1 percent. ( Plant Setpoint Change 85-15 decreased the trip setpoint from 92 percent to 88 percent to ensure the trip will occur prior to 92 percent under i worst-case drift conditions. The Technical Specification setpoint is 193 percent. LER 85-06 reported the occurrence of discovering that the setpoint had exceeded the Technical Specification limit. Plant Setpoint Chanze 85-20 A review of the Control Room Operating Curves and Tables Manual (CROCTM) revealed that Figure 5.10 for the diesel AFW pump day oil tank volume was incorrect. Plant Satpoint Change 85-20 reset the diesel AFW pump day oil tank level switches to ensure the amount of diesel fuel oil available is consistent with Technical Specification requirements. Plant Setpoint Chants 85-22 The auxiliary feedwater pump suction pressure trip transmitters are located below the pump suction piping for both trains. This configuration yielded an erroneous suction pressure when the pipes were dry and the reference leg was not. Plant Setpoint Change 85-22 reset the respective pressure switch setpoints to compensate for the instrument les heights. LER 85-11 reported the discovery that this static head of water in the suction pressure transmitter piping was not included in the setpoint calculation. Plant Setpoint Chanze 85-24 The administrative limit for the condensate storage tank (CST) level has been changed to >70 percent to ensure the APW pumps will not trip on an l automatic start due to low-suction precsure. l Plant Setpoint Change 85-24 reset the CST low level on panel C-19 to activate at 75 percent in order to provide the operator time to correct the CST level prior to its reaching a level that could affect the operation of the AFW pumps. LER 85-09 described the discovery of this event and the trip of the diesel-driven auxiliary feedwatee pump due to low-suction pressure. O 2-151}}

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