ML20212B586
| ML20212B586 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/31/1986 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8703030594 | |
| Download: ML20212B586 (153) | |
Text
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') TABLE OF CONTENTS J
Page INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . i
- 1. Radioactive Effluent Release Report. . . . . . . . . . . . . 1 A. Effluent and Waste Disposal Report.. . . . . . . . . . . 3 B. Offsite Radiation Doces. . . . . . . . . . . . . . . . . 36 C. Meteorological Data. . . . . . . . . . . . . . . . . . . 81 D. Changes to the Offsite Doso Calculation Manual (ODCM). . . . . . . . . . . . . . . . . . . . . . 82
- E. Reactor Coolant System (RCS) Specific Activity . . . . . 83
- 2. Annual Personnel Exposure and Monitoring Report. . . . . . . 84
- 3. Steam Generator Tube Inspections and Maintenance . . . . . . 87
- 4. Relief Valve Challenges. . . . . . . . . . . . . . . . . . . 96 s
- 5. Changes, Tests, and Experiments. . . . . . . . . . . . . . . 97 A. Plant Modifications and Design Changes . . . . . . . . . 98 B. License Amendments . . . . . . . . . . . . . . . . . . . 117 C. Licensing Document Change Requests (LDCRs)
Approved During 1986 . . . . . . . . . . . . . . . . . . 130 D. Plant Tests. . . . . . . . . . . . . . . . . . . . . . . 140 E. Changes to Procedures. . . . . . . . . . . . . . . . . . 145 F. Setpoint Changes . . . . . . . . . . . . . . . . . . . . 146 O
-~ INTRODUCTION w./
Portions of the Annual Report of the Trojan Nuclear Plant for 1986 are submitted 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 eeports are included for ease of reference and completeness. The Trojan Nuclear Plant began the year operating at full power and, with the exception of one forced outage and three load reductions for mainte-nance and testing, remained at full power until April 2, at which time ! power was reduced to 73 percent due to excess regional hydroelectric power conditions on the northwest power grid. The February 8 reactor trip was determined to be the result of the high negative flux rate trip < setting being too conservative (too low) for proper system operation. j During cold weather, the cooling water to the circulating water pumps lube oil cooler decreased the temperature of the lube oil to the point that its viscosity was'so high as to cause a trip of the operating pump and a turbine runback, which resulted in a high negative flux rate trip of the reactor. The reactor was made critical and power operation resumed on the same day. On April 16, the turbine generator was removed from service and , preparation for the annual maintenance and refueling outage began. l The Plant refueling outage lasted 64 days, during which time refueling, i g c~g maintenance, and surveillance testing were performed. On April 24, the I () Plant entered Mode 6, refueling, and commenced unloading fuel from the reactor vessel. The core reload was completed May 8 with a total of 48 new fuel rods inserted into the core. On June 16, the Plant was made critical and low power physics testing was' commenced. The Plant synchro-nized to the power grid on June 18 for main turbine testing. A Plant trip occurred on June 19 when low power high flux trip setpoints were exceeded during turbine testing. On June 21, the Plant commenced power
- escalation, reaching 100-percent power on June 25.
- Primary-to-secondary leakage in the "C" steam generator had increased to j approximately 350 gallons per day (gpd) from first detection at the end of 1985. A steam generator maintenance program of eddy current testing, tube plugging, and tube specimen removal was successfully completed during the refueling outage af ter which the primary-to-secondary steam
!, generator tube leak rate was reduced to approximately 1 gpd; however, this was closely monitored throughout the remainder of the year with no indication of increased leakage. During the last portion of the year, the Plant maintained full power with the exception of three forced outages: on August 5, the Plant tripped on an inadvertent safety injection signal caused by failure of a steam generator pressure transmitter failure during a periodic instrument and control test; on September 1, following secondary side (main feedwater) systam high conductivity alarms, the turbine was taken offline and the reactor shutdown to find and plug condencer tubes; and on November 14, the turbine generator was tripped due to high vibration on the No. 1 main g/ turbine bearing, resulting in a reactor trip. In all three cases, equip-ment functioned normally and as expected and the Plant was returned to full power operation within a few days of the forced outage. i 1
The capacity factors for the year are as follows: Month Capacity Factor January 99.4 February 94.3 March 92.9 April 36.9 May 0.0 June 27.0 July 101.5 August 97.1 September 81.1 October 100.5 November 87.5 December 99.8 Overall 76.6 O l O 11
- 1. RADIOACTIVE EFFLUENT RELEASE REPORT
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N /, . Requirement Trojan Facility Operating License NPF-1, Appendix A, Technical Specifications 6.9.1.5.3 and 6.9.1.5.4 require:
" Routine Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
"The Radioactive Effluent Release Reports shall include a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 (Rev. 1), ' Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Cascous Effluents from Light-Water-Cooled Nuclear Power Plant', with data summarized on a quarterly basis following the format of Appendix B thereof.
"The Radioactive Effluent Release Reports may include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21 (Rev. 1), with data summarized on a quarterly basis following the format of Appendix B thereof. If the summary of the meteorological data is not included in the radicactive effluent release reports, it will be available for review at PGE's Corporate Office.
"The Radioactive Effluent Release Reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1) during the report period. All assumptions used in making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.
"The Radioactive Effluent Release Reports shall include a copy of all licens,ee event reports required by Specification 3.11.1.1 and 3.11.2.1.
"The Radioactive Effluent Release Reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).
"The Radioactive Effluent Release Reports shall include any changes to the PROCESS CONTROL PROGRAM or to the Offsite Dose Calculation s Manual (ODCM) made during the reporting period, as provided in Specifications 6.13 and 6.14."
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1 Report Complete d sta for the year 1986 h' ave been iriciaded, although the data for 2 the first t. months (January through June) have been previously reported. 1 i Y f 4 4' a
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1.A. EFFLUENT AND WASTE DISPOSAL REPORT Thia section contains a summary of the liquid and gaseous release limits; a listing of the maximum permissible concentrations of the isotopes released; a summary 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 > l summary of solid radioactive waste shipments. This section represents all. releases during the period January 1, 1986 through December 31, 1986. Data for January 1, 1986 through June 30, 1986 have been!
; previously reported. <
As per Technical Specification 3.3.3.11.b. the condenser air ejectob flow rate measuring device (FR-3100) is reported as inoperable during the
, period January 1, 1986 through December 31, 1986. ' As reported in the March 21, 1986 letter to J. B. Martin of USNRC, Region V, this flow rate has been measured every shift using rotometers FI-3111 or FE-3184. The repair and/or replacement of FR-3100 or the implementation of some other alternative is being aggressively pursued.
In 1986, very low level tritium contamination was detected in the storn and sanitary sewers at the Trojan Nuclear Plant. Tritium levels of i waters released off the Trojan site from the storm and sanitary sewer system were less than the maximum permissible concentration specified in Table 2, Column 2 of 10 CFR 20. The levels were also less than the V.S. l Environmental Protection Agency limit for community drinking water and l
- the Environment &i Technical Specification 3.12.1.b reporting level for
, radioactivity concentrations in environmental samples. The total tritium release from the storm and sanitary sewers wss <0.1 percent of those reported in the liquid release information tables. The Trojan Nuclear Planf is continuing to monitor the tritium levels in the storm and sanitary sewer systems. In July 1986, corrections were made to the volume curves for the Treated Waste Monitor Tank (TWMT) and the Dirty Waste Monitor Tank (DWMT) at l Trojan. The volume corrections cause less t' tan a 10 percent increase in l the volumes of liquid released from these tanks. This change is within j the reported error for liquid radioactive effluent releases. Further-more, the reported releases were sufficier.tly below the limits so that the possible 10 percent increase caused by the tank volume corrections did not cause any release limits to be exceeded. Therefore, the correc-tions to the volume curves for the TWMT and DWMT do not have a signifi-cant impact on the previously reported quantities of radioactivity I released through the liquid pathway or the corresponding offsite doses ! to the public. The term ND used through these tables means "Not Detectable". 3
L (D U TABLE 1.A-1 SUPPLEMENTAL INFORMATION January 1,1986 through June 30, 1986 REGULATORY LIMITS First Second Fission and Activation Cas Release Rate Limits Unit Quarter Quarter
- 1. Tech Spec 3,11.2.1(a), Instantaneous QTv i 1 Ci/see 2.42E-2 5.32E-2 2.0 Ky QTv i 1 Ci/sec 8.17E-2 1.66E-1 0.33 (Ly + 1.1 Ny)
- 2. Tech Spec 3.11.2.2, Quarterly Avera e QTv i 1 Ci/sec 9.17E-4 1.96E-3 50 E y QTv i 1 Ci/sec 2.13E-3 2.94E-3 25 M y ',
- 3. Tech Spec 3.11.2.4(1), Quarterly Average Requiring Use of the Gaseous Radwaste a Treatment System QTv i 1 Ci/sec 4.59E-4 9.80E-4 100 Ny QTv i 1 Ci/sec 1.06E-3 1.47E-3 50 My O
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O TABLE 1.A-2 SUPPLEMENTAL INFORMATION January 1, 1986 through June 30, 1986 REGULATORY LIMITS Caseous Iodine 131. Tritium, and Particulates First Second With > 8 Day T1/2 Limits Unit Ouarter Quarter
- 1. Tech Spec 3.11.2.1(b), Instantaneous QTv i 1 C1/sec 9.82E-3 3.62E-3
.67 Ri
- 2. Tech Spec 3.11.2.3, Quarterly Average QTv i 1 Ci/sec 6.583-5 2.43E-5 100 Ri
- 3. Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Caseous Radwaste Treatment System QTv i 1 Ci/sec 3.29E-5 1.21E-5 200 Ri e
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O TABLE 1.A-3 SUPPLEMENTAL INFORMATION January 1, 1986 through June 30, 1986 REGULATORY LIMITS Liquid Effluent Limits
- 1. Tech Spec 3.11.1.1 Instantaneous discharge concentrations Instantaneous less than the maximum permissible concentrations listed in 10 CFR Part
- 20. Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration is limited to 2 x 10-4 pCi/ml total activity.
- 2. Tech Spec 3.11.1.2 Gross release limit of 2.5 Ci per Quarterly Average quarter excluding tritium and
' dissolved noble gases. If this limit is exceeded, cumulative dose due to liquid effluents will be limited to 1.5 meem to the whole body and to 2.5 mrem to any organ, using isotope specific methodology in the plant offsite dose calculation manual (ODCM).
- 3. Tech Spec 3.11.1.3 The liquid radwaste treatment system Quarterly Average Requiring shall be maintained and used when Use of the Liquid Radwaste activity discharged (excluding tritium Treatment System and dissolved noble gas) would exceed 1.25 Ci/Qtr.
- 4. Tech spec 3.11.1.4 The quantity of radioactive material Temporary Storage Tank contained in temporary radwaste storage Activity Limit tanks is limited to 1 10 Ci excluding tritium and dissolved noble gases.
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l l TABLE 1. A-4 9i ; l SUPPLEMENTAL INFORMATION January 1, 1986 through June 30, 1986 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid MPC MPC Isotope (uci/ce) Isotope (uci/ce) Fluorine 18 8 x 10-4 Iodine 131 3 x 10-7 Chromium 51 2 x 10-3 Iodine 132 8 x 10-6 Manganese 54 1 x 10-4 Tellurium 132 2 x 30-5 Iron 55 8 x 10-4 Iodine 133 1 x 10-6 Cobalt 57 4 x 10-4 Cesium 134 9 x 10-6 Cobalt 58 9 x 10-5 Cesium 137 2 x 10-5 Iron 59 5 x 10-5 Cesium 138 3 x 10-6 Cobalt 60 3 x 10-5 Barium 140 2 x 10-5 Rubidium 88 3 x 10-6 Lanthanum 140 2 x 10-5 Strontium 89 3 x 10-6 Cerium 141 9 x 10-5 Strontium 90 3 x 10-7 Cerium 144 1 x 10-5 Zirconium 95 6 x 10-5 Alpha 3 x 10-8 Niobium 95 1 x 10-4 Unidentified 3 x 10-8 Molybdenum 99 4 x 10-5 Tritium 3 x 10-3 Technetium 99m 3 x 10-3 Krypton 85m 2 x 10-4 Ruthenium 103 8 x 10-5 Krypton 87 2 x 10-4 Ruthenium 106 1 x 10-5 Krypton 88 2 x 10-4 l Silver 110m 3 x 10-5 Xenon 131m 2 x 10-4 l Tin 113 8 x 10-5 Xenon 133 2 x 10-4 i Antimony 124 2 x 10-5 Xenon 133m 2 x 10-4 Antimony 125 1 x 10-4 Xenon 135 2 x 10-4 Xenon 135m 2 x 10-4 l Caseous l l Gaseous MPCs are not used in calculating technical specifications at l Troj an. O 7
O TABLE 1.A-5 SUPPLEMENTAL INFORMATION January 1, 1986 through June 30, 1986 AVERAGE ENERGY Effluent release limits are not based upon E, hence, reporting E is not required. j' MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Gaseous Releases Fission and Activation Gases: Gamma spectrometric analysis of gaseous grab samples define radionuclide distribution at least monthly on monitored gaseous release points. Using the known nuclide i ! distributions and peccess radiation monitor readings, the actual l quantities of gaseous releases are calculated. Iodines: Weekly composite filter and iodine cartridge samples are l analyzed by gamma spectroscopy to determine the concentration of particulate and iodine isotopes. Weekly composite samples are analyzed for beta and alpha emitting isotopes by ccunting with a gas flow proportional counter. Quarterly composite filters are analyzed for Sr-89/90 using gas proportional beta counting and chemical separation techniques when necessary. Tritium: Tritium is collected on dry silica gel in monthly composite samples and counted using liquid scintillation spectroscopy. Llauld Releases Fission and Activation Products: Gamma spectrometric analysis of each batch is performed. Weekly composite samples are maintained for continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations. Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques. b Dissolved and Entrained Gases: Gaseous isotopes are determined by b gamma spectrometric analysis of each batch and on a minimum frequency of once per month for continuous releases. 8
i TABLE 1.A-6 SUPPLEMENTAL INFORMATION January 1, 1986 through June 30, 1986 BATCH RRLEASES Unit Liquid Gaseous Number of Batch Releases 66 101 Total time period for Batch Releases Hours 291.4 1859 Maximum time period for Batch Releases Hours 25.4 108.8 Average time period for Batch Releases Hours 4.4 18.4 Minimum time period for Batch Releases Hours 0.3 0.3 Average dilution flow during Batch Releases CPM 29180 NA ABNO9 MAL RLEASES Number of Abnormal Releases 1 2 Total Activity Released C1 1.17E-S 3.19E0 l l l l 9 9
i -- N-s TABLE 1.A-7 Sheet 1 of 2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1986 through June 30, 1986 1 l l l l First Second Estimated FISSION AND ACTIVATION GASES Unit Quarter Quarter Error Total Activity Released C1 4.75E+2 2.46E+2 13.5El i Average Release Rate for Quarter pCi/sec 6.12E+1 3.14E+1 Percent of Limit: Tech. Spec. 3.11.2.1 (a) - 4.35E-1 3.08E-1 Instantaneous Tech Spec. 3.11.2.2 - 6.65E0 1.60E0 y_ Quarterly Average l Tech. Spec. 3.11.2.4.(1) - 1.33E+1 3.1980 Quarterly Average Requiring l, Processing IODINE 131 Total Iodine 131 Released C1 1.76E-4 3.80E-3 13.5El Average Release Rate for Quarter pC1/sec 2.27E-5 4.84E-4 PARTICULATES Total with Half-lives > 8 days C1 3.91E-5 2.46E-4 13.5El Average Release Rate for Quarter pCi/sec 5.04E-6 3.14E-5 Total Gross Alpha Released Ci 7.52E-6 1.08E-6 TRITIUM Total Released C1 1.68E0 1.47E+1 13.0El Average Release Rate for Quarter pCi/sec 2.17E-1 1.87E0 0 10
O TABLE 1.A-7 Sheet 2 of 2 IODINE 131. PARTICULATES WITH First Second Estimated
> 8 DAY T1/2 AND TRITIUM Unit Ouarter Quarter Error %
Total Released C1 1.68E0 1.47E+1 13.5El Average Release Rate for Quarter pC1/sec 2.17E-1 1.87EO Percent of Lirit: Tech. Spec. 3.11.2.1 (b) 4.89E-3 1.88E-1 Instantaneous Te~h. c Spec. 3.11.2.3 3.30E-1 7.70E0 Quarterly Average Tech. Spec. 3.11.2.4(2) 6.40E-1 1.54E+1 Quarterly Average Requiring
' Processing ,
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-- TABLE 1.A-8 Sheet 1 of 2 V GASEOUS EFFLUENTS CROUND LEVEL RELEASES January 1,1986 through June 30, 1986 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 1st Ouarter 2nd Quarter 1st Quarter 2nd Ouarter FISSION CASES Krypton 85m Ci 8.67E0 1.70E0 4.12E-1 1.49E-2 Krypton 85 Ci 9.15E-1 3.49E0 Krypton 87 C1 1.32E+1 2.3250 1.01E-2 7.13E-3 Krypton 88 C1 1.90E+1 3.39E0 3.81E-2 1.77E-2 Krypton 89 C1 Zenon 131m C1 1.37E0 2.34E0 Zenon 133m C1 1.85E0 4.18E-1 9.80E-1 7.20E-1 Zenon 133 C1 1:53E+2 7.19E+1 9.71E+1 1.18E+2 Zenon 12fm C1 6.14E+1 1.13E+1 2.21E-2 1.10E-2 2.20E+1 2.11E0 6.97E-1 Ianon 135 Ci 8.00E+1 Zenon 137 Ci 6.22E0 1.07E0 Zenon 138 Ci 2.74E+1 5.03E0 Argon 41 C1 1.04E0 1.52E-1 2.31E-1 3.89E-2 TOTAL FOR QUARTER Ci 3.72E+2 1.19E+2 1.03E+2 1.25E+2 0 12
O TABLE 1.A-8 Sheet 2 of 2 Continuous Mode Batch Mode Unit 1st Ouarter 2nd Quarter 1st Ouarter 2nd Quarter IODINES Iodine 131 Ci 1.65E-4 4.04E-4 1.08E-5 3.40E-3 Iodine 132 C1 1.86E-6 1.45E-7 5.60E-8 2.85E-5 Iodine 133 Ci 6.83E-5 1.60E-5 5.43E-6 1.16E-4 Iodine 134 Ci 3.36E-7 1.08E-8 Iodine 135 C1 1.49E-5 6.94E-7 6.68E-7 4.60E-5 TOTAL FOR QUARTER C1 2.50E-4 4.21E-4 1.70E-5 3.59E-3 PARTICULATES > 8 DAY T-1/2 Strontium 89 Ci 2.49E-5 6.55E-5 ND 1.02E-4 Strontium 90 01 8.07E-8 7.05E-7 ND 5.42E-5 Cesium 137 Ci 6.48E-8 2.97E-6 1.34E-8 5.28E-6 Cobalt 58 Ci 1.13E-5 1.23E-5 3.16E-8 Cobalt 60 Ci 2.59E-6 Ruthenium 103 Ci 3.17E-8 Niobium 95 2.73E-6 2.42E-7 TOTAL FOR QUARTER Ci 3.91E-5 8.17E-5 4.50E-8 1. 6 4 E-4 9 13 1 i
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{__. - . . . . . _ . - - . . . . . . - . . . . - - - - . . . . - - l 1' i i s- ; t. ' I e i TABLE 1.A-9 , P I d , I' GASEOUS EFFLUENTS ; ELEVATED RELEASES j l January 1, 1986 through June 30, 1986~ ! f 1. ! I i l , No Elevated Release Points . t i l i I l
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' l TABLE 1.A-10 , LIQUID EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1986 through June 30, 1986 EISSTON AND ACTIVATION PRODUCTS First Second Estimated Unit Quarter Quarter Error % Total Activity Released (excluding Ci 4.60E-2 8.47E-2 13.5E+1 gases, tritium, and alpha) Average Diluted Concentration pCi/ml 3.24E-9 5.43E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous % 9.79E-1 1.57E0 Tech Spec 3.11.1.2 - Quarterly Limit % 1.84E0 3.39EO Tech Spec 3.11.1.3 - Quarterly Limit % 3.67E0 6.78E0 Requiring Processing TRITIUM Total Released C1 1.17E+2 8.59E+1 13.0E+1 Average Diluted Concentration pCi/ml 8.24E-6 5.51E-6 Fraction of MPC % 2.75E-1 1.84E-1 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 4.02E-2 2.88E-2 13.5E+1 Average Diluted Concentration pCi/ml 2.33E-9 1.85E-9 Fraction of MPC % 1.42E-3 9.23E-4 CROSS ALPHA RADIOACTIVITY Total Activity Released Ci ND 3.11E-5 13.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.14E+7 1.13E+7 15.0E0 VOLUME OF DILUTION WATER Liters 1.42E+10 1.56E+10 tl.5E+1 9 15
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TABLE 1.A-Il Sheet 1 of 2 LIQUID EFFULENTS January 1, 1986 through June 30, 1986 i NUCLIDES RELEASED Continuous Mode Batch Mode Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Fluorine 18 Ci 6.49E-6 3.40E-6 Chromium 51 Ci 5.81E-3 Manganese 54 Ci 2.87E-4 6.29E-4 Ci ND 5.53E-3 4.08E-3 Iron 55 ND Ci 7.93E-6 Cobalt 57 Cobalt 58 Ci 5.77E-3 5.30E-4 2.60E-2 Iron 59 C1 2.45E-4 Ci 4.77E-4 1.01E-2 6.82E-3 Cobalt 60 Rubidium 88 Ci 5.48E-6 1.40E-4 3.67E-4 3.81E-5 5.12E-4 Strontium 89 C1 Ci 4.22E-5 7.41E-5 1.55E-6' 1.07E-4 Strontium 90 Ci 1.09E-3 Zirconium 95 1.85E-3 Niobium 95 C1 Ci 2.44E-5 Molybdenum 99 C1 2.60E-5 Technetium 99m Ci 1.11E-3 Ruthenium 103 Ci 2.65E-3 2.29E-3 Ruthenium 106 Ci 9.15E-5 1.49E-4 Silver 110m 2.63E-5 Tin 113 C1 1.40E-3 Antimony 124 C1 Ci 7.86E-4 6.62E-3 Antimony 125 Ci 2.33E-3 4.85E-3 4.84E-4 4.45E-4 Iodine'131 1.04E-5 Iodine 132 C1 3.57E-5 Tellurium 132 C1 16
O TABLE 1.A-ll Sheet 2 of 2 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Iodine 133 C1 2.19E-3 2.35E-4 1.16E-4 1.58E-5 Cesium 134 C1 1.53E-5 1.48E-4 7.51E-3 3.89E-3 Cesium 137 Ci 5.14E-5 3.07E-4 1.11E-2 5.93E-3 Cesium 138 C1 3.29E-6 Barium 140 Ci 4.39E-4 Lanthanum 140 Ci 6.7CE-4 4.19E-4 1.33E-3 Cerium 141 Ci 4.40E-5 Cerium 144 Ci 7.09E-4 3.31E-4 Unidentified Ci 8.26E-4 5.59E-4 TOTAL FOR QUARTER Ci 4.77E-3 1.29E-2 4.12E-2 7.19E-2 Krypton 85m Ci 2.23E-7 Xenon 131m Ci 2.37E-4 9.73E-5 Xenon 133 Ci 4.11E-4 3.82E-2 2.79E-2 Xenon 133m Ci 2.60E-4 3.57E-4 Xenon 135 C1 1.29E-4 9.92E-4 4.53E-4 Xenon 135m Ci i 1.30E-6 TOTAL FOR QUARTER Ci 5.40E-4 ND 3.97E-2 2.88E-2 e 17
- ,, TABLE 1.A-12 Sheet I of 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1986 through June 30, 1986 Activity Volume Estimate SOLID WASTE SHIPPED OFFISTE FOR BURIAL OR DISPOSAL During During Total (Not Irradiated Fuel) - Type of Waste 6 Months 6 Months Error %
- 1. Spent Resin, Filter Sludges, Evaporator 4.969 Ci 58.55 m3 25%
Bottoms, etc.
- 2. Dry Compressible Waste, Contaminated 6.067 Ci 96.53 m3 25%
Equipment, etc.
- 3. Irradiated Components, Control Rods, etc. 0 0
- 4. Other 0 0 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide
- 1. See attached sheet.
l () 2. See attached sheet. 3. I 4. SOLID WASTE DISPOSITION
- Number of Shipments Mode of Transportation Destination 10 Exclusive Truck U.S. Ecology Inc.
l P.O. Box '38 i Richland, UA 99352 i ~ IRRADIATED FUEL SHIPMENTS DISPOSITION Number of Shipments Mode of Transportation Destination l l 0 N/A N/A i 4 i f i O 18 t
1 TABLE 1.A-12 Page 2 of 2 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE
- 1. Nuclide Ci Nuclide Ci H-3 0.856 Ru-103 0.001 C-14 0.100 Ru-106 0.054 Cr-51 0.001 Ag-110m 0.001 Mn-54 0.050 Sb-125 0.014 Fe-55 0.478 I-131 0.300 Co-58 0.818 Cs-134 0.459 Co-60 0.605 Cs-136 0.002 Ni-63 0.302 Cs-137 0.768 Sr-89 0.040 Ba-140 0.036 Sr-90 0.046 Ce-144 0.019 Nb-95 0.002 Pu-241 0.015 Zr-95 0.002 TOTAL 4.969
- 2. Nuclide Ci Nuclide Ci H-3 0.330 Nb-95 0.283 C-14 0.008 Zr-95 0.221 Cr-51 0.517 Ru-103 0.078 Mn-54 0.063 Ru-106 0.213 Fe-55 1.387 Sn-113 0.002 Co-57 0.032 Sb-125 0.116 Co-58 0.903 Cs-134 0.093 Fe-59 0.002 Cs-137 0.170 Co-60 0.933 Ce-141 0.008 Ni-63 0.471 Ce-144 0.139 Sr-89 0.025 Pu-241 0.020 Sr-90 0.053 TOTAL 6.067 i
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TABLE 1.A-13 Sheet 1 of 2
/ SUPPLEMENTAL INFORMATION July 1, 1986 through December 31, 1986 REGULATORY LIMITS Third Fourth Fission and Activation Cas Release Rate Limits Unit Ouarter Quarter
- 1. Tech Spec 3.11.2.1(a), Instantaneous QTV < 1 Ci/sec 9.07E-2 1.58E-1 2.0 Ky QTV < 1 Ci/sec 2.68E 1 4.12E-1 0.33 (Ly + 1.1 Ny)
- 2. Tech Spec 3.11.2.2, Quarterly Average QTv < 1 Ci/sec 3.26E-3 5.31E-3 50 N y QTv < 1 Ci/sec 3. 48 E- 3 3.88E-3
(/ 25 My
- 3. Tech Spec 3.11.2.4(1), Quarterly Average l
Requiring Use of the Gaseous Radwaste Treatment System QTv < 1 Ci/sec 1.63E-3 2.65E-3
- 100 N y QTv < 1 Ci/sec 1.74E-3 1.94E-3 l
50 M y l 0326z i , l s b i 20 ! I
TABLE 1.A-13 Sheet 2 of 2 SUPPLEMENTAL INFORMATION July 1, 1986 through December 31, 1986 REGULATORY LIMITS Caseous Iodine 131. Tritium, and Particulates Third Fourth With > 8 Day T1/2 Limits Unit Quarter Quarter
- 1. Tech Spec 3.11.2.1(b), Instantaneous QTV < 1 Ci/sec 4.86E 3 3.91E-3
.67 Ri
- 2. Tech Spec 3.11.2.3, Quarterly Average QTv < 1 Ci/sec 3.26E-5 2.62E-5 100 Ri
- 3. Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Caseous Radwaste Treatment System QTV < 1 Ci/see 1.63E-5 1.31E-5 200 Ri 9
21
f TABLE 1.A-14 SUPPLEMENTAL INFORMATION July 1, 1986 through December 31, 1986 REGULATORY LIMITS Liquid Effluent Limits l
- 1. Tech Spec 3.11.1.1 Instantaneous discharge concentrations Instantaneous less than the maximum permissible concentrations listed in 10 CFR Part 20, Appendix B; Table II, Column 2, I for radionuclides other than dissolved 3 . or entrained noble gases. For dissolved or entrained noble gases, the concentration is limited to 2 x 10-4 pCi/ml total activity.
- 2. Tech Spec 3.11.1.2 Gross release limit of 2.5 Ci per Quarterly Average quarter excluding tritium and i dissolved noble gases. If this limit is exceeded, cumulative dose due to liquid effluents will be limited to
- 1.5 meem to the whole. body and to
- 2.5 meem to any organ, using isotope 1 specific methodology in the plant offsite dose calculation manual (ODCM).
- 3. Tech Spec 3.11.1.3 The 11guld radweste treatment system Quarterly Average Requiring shall be maintained and used when
( Use of the Liquid Radwaste activity discharged (excluding tritium i Treatment System and dissolved noble gas) would exceed j '1.25 Ci/Qtr.
- 4. Tech Spec 3.11.1.4 The quantity of radioactive material Temporary Storage Tank contained in temporary radwaste storage Activity Limit tanks is limited to 1 10 Ci excluding tritium and dissolved noble gases.
N 22 ,
TABLE 1.A-15 SUPPLEMENTAL INFORMATION July 1, 1986 through December 31, 1986 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid MPC MFC Isotope (uci/cc) Isotope (uci/ce) Fluorine 18 8 x 10-4 Indine 131 3 x 10-7 Chromium 51 2 x 10-3 Iodine 132 8 x 10-6 Manganese 54 1 x 10-4 Tellurium 132 2 x 10-5 Iron 55 8 x 10-4 Iodine 133 1 x 10-6 Cobalt 57 4 x 10-4 Cesium 134 9 x 10-6 Cobalt 58 9 x 10-5 Cesium 137 2 x 10-5 Iron 59 5 x 10-5 Cesium 138 3 x 10-6 Cobalt 60 3 x 10-5 Barium 140 2 x 10-5 Rubidium 88 3 x 10-6 Lanthanum 140 2 x 10-5 Strontium 89 3 x 10-6 Cerium 141 9 x 10-5 Strontium 90 3 x 10-7 Cerium 144 1 x 10-5 Zirconium 95 6 x 10-5 Tungsten 187 6 x 10-5 Niobium 95 1 x 10-4 Alpha 3 x 10-8 Niobium 97 9 x 10-4 Unidentified 3 x 10-8 Molybdenum 99 4 x 10-5 Tritium 3 x 10-3 Technetium 99m 3 x 10-3 Krypton 85m 2 x 10-4 Ruthenium 103 8 x 10-5 Krypton 87 2 x 10-4 Ruthenium 106 1 x 10-5 Krypton 88 2 x 10-4 Silver 110m 3 x 10-5 Xenon 131m 2 x 10-4 Tin 113 8 x 10-5 Xenon 133 2 x 10-4 Antimony 124 2 x 10-5 Xenon 133m 2 x 10-4 Antimony 125 1 x 10-4 Xenon 135 2 x 10-4 Xenon 135m 2 x 10-4 Caseous Caseous MPCs are not used in calculating technical specifications at Troj an. I O 23
TABLE 1.A-16 SUPPLEMENTAL INFORMATION (} ( ,) July 1, 1986 through December 31, 1986 AVERAGE ENERGY Effluent release limits are not based upon E, hence, reporting E is not required., MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Gaseous Releases Fission and Activation Gases: Gamma spectrometric analysis of $ gaseous grab camples define radionuclide distribution at 1 cast monthly on monitored gaseous release points. Using the known nuclide distributions and process radiation monitor readings, the actual quantitles of gaseous releases are calculated. Iodines: Weekly composite filter and iodine cartridge samples are , analyzed by gamma spectroscopy to determine the concentration of particulate and iodine isotopes. Weekly composite samples are analyzed for beta and alpha emitting isotopes by counting with a gas flow proportional counter. Quarterly composite filters are analyzed for Sr-89/90 using gas proportional beta counting and chemical separation techniques when necessary. Tritium: Tritium is collected on dry silica gel in monthly composite samples and counted using liquid scintillation spectroscopy. Liquid Releases Fission and Activation Products: Gamma spectrometric analysis of each batch is performed. Weekly composite samples are maintained for continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations. Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques. Dissolved and Entrained Cases: Gaseous isotopes are determined by gamma spectrometric analysis of each batch and on a minimum frequency of once per month for continuous releases. O 24
TABLE 1.A-17 SUPPLEMENTAL INFORMATION July 1, 1986 through December 31, 1986 BATCH RELEASES Unit Liquid Caseous Number of Batch Releases 50 71 Total time period for Batch Releases Hours 154.5 1327.4 Maximum time period for Batch Releases Hours 13.9 57.0 Average time period for Batch Releases Hours 3.1 18.7 Minimum time period for Batch Releases Hours 0.3 0.6 Average dilution flow during Batch Releases CPM 28000 NA ABNORMAL RLEASES Number of Abnormal Releases 0 3 Total Activity Released Cl 0 5.95E0 0 1 1 25
("'N TABLE 1.A-18 Sheet 1 of 2 N~ Y CASEOUS EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1986 through December 31, 1986 Third Fourth Estimated FISSION AND ACTIVATION CASES Unit Quarter Quarter Error Total Activity Released C1 1.17E+2 7.50E+1 13.5El Average Release Rate for Quarter pCi/see 1.48E+1 9.46E0 Percent of Limit: Tech. Spec. 3.11.2.1 (a) - 5. 98E- 2 1.17E-2 Instantaneous Tech Spec. 3.11.2.2 - 4.53E-1 2.43E-1 Quarterly Average Tech. Spec. 3.11.2.4.(1) - 9.06E-1 4.86E-1 Quarterly Average Requiring Processing IODINE 131 Total Iodine 131 Released Ci 2.14E-3 2.65E-4 13.5El Average Release Rate for Quarter pCi/see 2.70E-4 3.34E-5 PARTICULATES Total with Half-lives > 8 days C1 1.94E-5 1.52E-4 13.5El Average Release Rate for Quarter pCi/sec 2.45E-6 1.92E-5 Total Gross Alpha Released Ci 3.35E-6 1.20E-6 TRITIUM Total Released Ci 7.89E0 5.11E0 13.0E1 Average Release Rate for Quarter pCi/sec 9.95E-1 6.44E-1 l A
^
O 26
TABLE 1.A-18 Sheet 2 of 2 GASEQUS EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1986 through December 31, 1986 IODINE 131, PARTICULATES WITH Third Fourth Estimated
> 8 DAY T1/2 AND TRITIUM Unit Quarter Quarter _ Error Total Released Ci 7.89E0 5.11EO !3.5El Average Release Rate for Quarter pCi/sec 9.95E-1 6.44E-1 Percent of Limit:
Tech. Spec. 3.11.2.1 (b) 8.19E-2 1.65E-2 Instantaneous Tech. Spec. 3.11.2.3 3.06E0 2.46E0 Quarterly Average Tech. Spec. 3.11.2.4(2) 6.11E0 4.92E0 Quarterly Average Requiring Processing i l I l l [ I l 27
TABLE 1.A-19 Sheet 1 of 2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES July 1, 1986 through December 31, 1986 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter , FISSION CASES Krypton 85m Ci 8.32E- 1 1.47E-2 8.23E-4 1.91E-3 Krypton 85 Ci ND ND 5.67E-1 5.22E-1 Krypton 87 Ci 2.37E-2 2.502-2 ND ND Krypton 88 Ci 1.19E0 3.19E-2 ND ND Xenon 131m Ci ND ND 7.87E-1 5.30E-1 Kenon 133m Ci ND 1.15E-3 2.12E-1 1.20E-1 i Xenon 133 Ci 5.37E+1 5.07E+1 4.99E+1 2.23E+1 Xenon 135m Ci 9.55E-2 1.21E-1 ND ND Xenon 135 C1 9.08E0 2.79E-1 2.68E-1 6.33E-2 Xenon 137 Ci ND 1.34E-2 ND ND Xenon 138 Ci 3.03E-2 5.57E-2 ND ND Argon 41 Ci ND 6.56E-3 2.78E-1 2.21E-1 TOTAL FOR QUARTER Ci 6.50E+1 5.12E+1 5.20E+1 2.38E+1 i 28 [
f Sheet 2 of 2 TABLE 1.A-1_9, CASEOUS EFFLUENTS CROUND LEVEL RELEASES July 1, 1986 through December 31, 1986 Continuous Mode Batch Mode Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter IODINES Iodine 131 Ci 2.13E-3 2.64E-4 1.16E-5 9.24E-7 Iodine 133 Ci 1.95E-4 3.94E-5 2.99E-6 1.83E-7 Iodino 135 C1 1.24E-7 ND ND ND TOTAL FOR QUARTER Ci 2.34E-3 3.03E-4 1.46E-5 1.11E-6 PARTICULATES > 8 DAY T-1/2 Strontium 89 Ci 4.10E-8 1.03E-4 ND ND Strontium 90 Ci 2.00E-8 4.92E-5 ND ND Cesium 134 Ci 6.95E-6 ND ND ND Cesium 137 C1 1.24E-5 4.10E-9 ND ND TOTAL FOR QUARTER Ci 1.94E-5 1.52E-4 ND ND O 29
Ei - -
- p. ,
j t.,'. j , , ps g
- TABLE 1.A-20 i-p l , CASEOUS EFFLUENTS ELE'IATED RELEASES
/ July 1, 1986 through December 'J1,1986
..T
't Na Elevated Release Points
,t j '~.y e
'l
- x. 3 e
d P 1 i \ ... P ' i I g g 0 i F l' y
% J f, I-4 1 -
t 11
- \
4 ; *; l' N t 4
*
- I s g
l? I k O
\
l
- r
\
\
l . i
1 TABLE 1.A-21 LIQUID EFFLUENTS SUKMATION OF ALL RELEASES July 1, 1986 through December 31, 1986 FISSION AND ACTIVATION PRODUCTS Third Fourth Estimated Unit Quarter Quarter Error %_ Total Activity Released (excluding Ci 8.77E-2 4.59E-2 3.5E+1 gases, tritium, and alpha) Average Diluted Concentration pCi/ul 6.59E-9 3.04E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous % 3.72E-1 2. 44E- 1 Tech Spec 3.11.1.2 - Quarterly Limit % 3.51E0 1.85E0 Tech Spec 3.11.1.3 - Quarterly Limit % 7.02E0 3.70E0 Requiring Processing TRITIUM Total Released Ci 2.13E+1 1.85E+1 13.0E+1 Average Diluted Concentration pCi/ml 1.60E-6 1.22E-6 Fraction of MPC % 5.33E-2 4.07E-2 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 7.22E-3 1.52E-2 3.5E+1 .kv=*%ge Diluted Concentration pCi/ml 5.43E-10 9.98E-10 Fraction Of MFC % 2.71E-4 4.99E-4 GROSS ALPHA RADIOACTIVITY Total Activity Released Ci 3.36E-5 2.67E-4 13.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.25E+7 1.30E+7 15.0E0 VOLUME OF DILUTION WATER Liters 1.33E+10 1.52E&l0 11.5E+1
'O 31
TABLE 1.A-22 Sheet 1 of 2 LIQUID EFFLUENTS July 1, 1986 through December 31, 1986 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 3rd Quarter 4th Ouarter 3rd Quarter 4th Quarter Chromium 51 Ci ND ND 3.44E-3 ND Manganese 54 Ci ND ND 9.36E-4~ 4.76E-4
~
Iron 55 Ci ND 1.31E-3 7.90E- 4 1.21E 2 Cobalt 57 Ci ND ND 3.95E-5 3.84E-5 Cobalt 58 Ci 2.97E-4 2.86E-5 1.04E-2 4.93E-3 Iron 59 Ci ND ND 2.55E-4 ND Cobalt 60 Ci ND ND 2.74E-2 1.01E-2 Strontium 89 Ci 2.36E-4 ND 5.22E-5 1.69E-4 Strontium 90 Ci ND ND 1.57E-5 7. 55 E-5 Zirconium 95 Ci ND ND 2.86E-3 7.22E-4 Niobium 95 Ci ND ND 6.11E-3 1.82E-3 a Ruthenium 103 Ci ND ND 1.86E-3 3.03E-4 Ruthenium 106 Ci ND ND 1.43E-2 8.16E-3 S11ver 110m Ci ND ND 2.22E-3 1.41E-3 Tin 113 Ci ND ND 2. 46E- 4 6.28E-5 Antimony 124 Ci ND ND 3.77E-4 ND Antimony 125 Cl ND - ND 6.10E-3 1. 7 2 E- 3 Iodine 131 Ci 2.01E-4 ND 1.19E-4 9.02E-5 O 32
Sheet 2 of 2 TABLE 1.A-22 LIQUID EFFLUENTS July 1, 1986 through December 31, 1986 NUCLIDES RELEASED Continuous Mode Bat 6h Mode Unit 3rd Quarter 4th Ouarter 3rd Quarter 4th Quarter Iodine 133 Ci 1.74E-4 ND ND 2.18E-5 Cesium 134 Ci 8.13E-4 ND 1.15E-3 3.95E-4 Cesium 137 Ci 1. 48E- 3 ND 2.13E-3 7.74E-4 Lanthanum 140 Cl ND ND 3.19E-5 ND Cerium 144 Ci ND ND 2.55E-3 1.10E-3 Tungsten 187 Ci ND ND ND 8.46E-5 Unidentified Ci ND ND 1.09E-3 1.28E-6 TOTAL FOR QUARTER Ci 3.20E-3 1.34E-3 8.45E-2 4.46E-2 O Xenon 133 Ci ND ND 7.16E-3 1.51E-2 Kenon 133m Ci KD ND ND 5.79E-5 Kenon 135 Ci 2.81E-5 ND 3.25E-5 1.62E-5 TOTAL FOR QUARTER Ci 2.81E-5 ND 7.19E-3 1.52E-2 l ( O 33 l l
Page 1 of 2 TMLE 1. A-23
) SOLID WASTE AND IRRADIATED FUEL SHIPMENTS July 1, 1986 through December 31, 1986 SOLID WASTE SHIPPED OFFSITE FOR Activity Volume Estimate BURIAL OP DISPOSAL (Not Irradiated During During Total Fuel) - Type of Waste 6 Months 6 Months Error %
- 1. Spent Resin, Filter Sludges, 612.090 Ci 51.54 m3 25%
Evaporator Bottoms, etc.
- 2. Dry Compressible Waste, 1.547 Ci 42.74 m3 25%
Comtaminated Equipment, etc.
- 3. Irradiated Components, Control 0 0 Pods, etc.
- 4. Other 0 0 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide
- 1. See attached sheet.
/ ~' . 2. See attached sheet.
t
\m/
3. 4. SOLID WASTE DISPOSITION Number of Shioments Mode of Transporation Destination 7 Exclusive Truck U.S. Ecology, Inc. P.O. Box 638 Richland, WA 99352 IFRADIATED FUEL SHIPMENTS DISPOSITION l Number of Shipments Mode of Transportation Destination 0 N/A N/A n . ! V 34 l -
TABLE 1.A-23 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE
- 1. Nuclide Ci Nuclide Ci H-3 1.264 Ru-103 0.005 C-14 0.608 Ru-106 0.245 C.r-51 0.010 Ag-110m 0.039 Mn-54 3.030 Sn-ll3 0.005 Fe-55 20.044 Sb-125 1.101 Co-57 0.278 Cs-134 58.733 Co-58 0.801 Cs-137 216.568 Ni-59 0.912 Ce-144 0.758 Co-60 156.182 U-235 0.001 l Ni-63 147.661 U-238 0.031
! Sr-89 0.012 Pu-241 0.748. I Sr-90 2.984 Mb-95 0.047 Zr-95 0.020 Tc-99 0.003 TOTAL 612.090 , 1
- 2. Nuclide Ci Nuclide Ci H-3 0.103 Ru-106 0.170 l C-14 0.004 Ag-110m 0.001 Cr-51 0.039 Sn-113 0.001 Mn-54 0.019 Sb-125 0.007 Fe-55 0.360 Cs-134 0.017 Co-58 0.156 Cs-137 0.044 Co-60 0.241 Ce-141 0.003 Ni--63 0.122 Ce-144 0.053 Sr-39 0.026 Pu-241 0.011 Sr-90 0.014 l Nb-95 0.052 I
Zr-95 0.060 Ru-103 0.044 TOTAL 1.547. G 35
1.B. OFFSITE RADIATION DOSES V(T Offsite radiation doses from gaseous and liquid effluents for 1986 are presented in this section. Included are quarterly doses to individuals at locations of maximum actual exposure and quarterly doses to the 50-mile population. Doses are presented separately for batch and continuous releases and for noble gas, gaseous iodine and particulate, and liquid effluents. Exposure locations are based on the land-use survey presented in the Updated FSAR and the 1985 annual survey of agricultural production. Models and assumptions used in performing the dose analyses for 1986 are presented in Sections 11.2 and 11.3 of the Trojan Updated FSAR. i D 2 O 36 l
g-~s TABLE 1.B-1 Sheet 1 of 2 V PARAMETERS USED IN CALCULATING DOSES FROM GASEOUS EFFLUENTS (First Half 1986) 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 Foad ingestion by animal to milking 2.0 Accumulation time on ground 7,300.0 Human Consumption Rates (kg/yr) Leafy vegetables by adult 64.0 Produce by adult 456.0 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m 3/yr) Adult 8,000.0 Infant 1,400.0 Animal Consumption Rates (kg/ day) Animal feed by seat animal 50.0 Animal feed by milk cow 50.0 Animal feed by milk goat 6.0 Exposure Periods During Growing Season (days) Leafy vegetables 60.0 Pasture vegetation 30.0 Produce 60.0 Residential Structure Shielding Factor 0.7 Fraction of 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 Surface Density of Soil for Root Zone (kg/m 2) 240.0 Field Decay Half Life (days) 14.0 37
TABLE 1.B-1 Sheet 2 of 2 Parameter Value Agricultural Productivity (kg/m 2) 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 Grown in Garden of Interest 1.0 Fraction of Produce Grown in Garden of Interest 0.76 Fraction of Year Animal Grazes on Pasture 0.5 Fraction of Daily Feed that is Pasture Grass when Animal Grazes 1.0 0 G 38
r
.s '
TABLE 1.B-2 Sheet 1 of 2 PARAMETERS USED IN CALCULATING DOSES FROM LIQUID EFFLUENTS Value Parameter 1st Otr. 1986 2nd Qtr. 1986 Plant Dilution Flow Rate (spm) 28,900.0 31,500.0 Columbia River Flow Rate (cfs) 299,702.0 423,006.1
, 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 meat animal water 2,219.0 6,428.0 Decay Times (days)
Discharge to drinking water 0.62 0.58 Discharge to swirains 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 0.62 0.58 Discharge to milk and meat animal water ,
0.62 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 l milking l { Accumulation Times (days) l 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 milk from irrigated pastureland 310.0 Meat from irrigated pastureland 110.0 0 39 l -.- , - - , - _ . - _ _ - _
TABLE 1.B-2 Sheet 2 of 2 Value Parameter 1st Otr. 1986 2nd Otr. 1986 Annual Exposure Times (hr/yr) Swimming and boating 12.0 Shoreline activities 12.0 Irrigated pasture 2,190.0 1 1 Infant Consumption Rates (kg/yr) Drinking water 330.0 Cow's milk from irrigated pastureland 330.0 Fraction of Year Animals Graze on Pasture 0.5 Fraction of Year crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14.0 Irrigation Rate (liters /m 2-hr) 0.104 Fractional Concentration of Water in Soil (g/g) 0.2 Fraction of Leafy Vegetables Grown in , Garden of 1.0 Interest Fraction of Produce Grown in Garden of Interest 0.76 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Leafy Vegetables Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Grass Yield (kg/m2) 0.7 f 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 Watar by beef 50.0 Pasture vegetation by milk cow 50.0 Pasture vegetation by milk goat 6.0 Pasture vegetation by beef 50.0 l 40 l l
~
N
/
TABLE 1.B-3 8 1 QUARTER 1986 DOSES FROM LIQUID EFFLUENTS (MREM) . i _ _ _ _ . _---= _ - =____ __ --- ._ -------- _ = = = _ _ . --- TOTAL ADULT INFANT INTERNAL EXPOSURE PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS
--------------- --------- _, -------- - _ _ _ _ _ = - _ - --------- _-__ ---------
AQUATIC AT MAXIMUM LOCATION
=
DRINKING WATER 3.9E-05 3.9E-05 3.5E-05 3.9E-05 5.4E-05 9.8E-05 3.7E-05 FISH CONSUMPTION 1.2E-03 1.2E-03 1.9E-04 9.8E-04 1.2E-03 0.0 4.5E-05 INVERTEBRATE CONSUMPTION 1.5E-04 1.5E-04 2.8E-05 1.3E-04 1.5E-04 0.0 6.9E-05 EXPOSURE TO SHORELINE SEDIMENT 2.3E-06 2.7E-06 2.3E-06 2.3E-06 2.3E-06 0.0 2.3E-06 SWIMMING AND BOATING 2.1E-08 1.5E-07 2.1E-08 2.1E-08 2.1E-08 0.0 2.1E-08 AQUATIC TOTAL 1.4E-03 1.4E-03 2.6E-04 1.1E-03 1.5E-03 9.8E-05 1.5E-04
------- ----- .- _. __==- _. _ = - - - - - - - - - -- ___ __ ; ==------= . = - - _ - _ -_ _--- _ - - _ - - - - - - - - - - -
i AQUATIC AT AGRICULTURAL LOCATION e DRINKING WATER 3.9E-05 3.9E-05 3.5E-05 3.9E-05 5.4E-05 9.8E-05 3.7E-05 FISH CONSUMPTION 2.7E-04 2.7E-04 4.2E-05 2.2E-04 2.8E-04 0.0 1.0E-05 INVERTEBRATE CONSUMPTION 3.3E-05 3.3E-05 6.1E-06 2.8E-05 3.4E-05 0.0 1.5E-05 EXPOSURE TO SHORELINE SEDIMENT S.1E-07 6.0E-07 5.1E-07 5.1E-07 5.1E-07 0.0 5.1E-07 SWIMMING AND BOATING 4.7E-09 3.2E-08 4.7E-09 4.7E-09 4.7E-09 0.0 4.7E-09 IRRIGATION AND LIW. STOCK WATERING EXPOSURE TO AGRICULTURAL SOIL 6.7E-06 7.9E-06 6.7E-06 6.7E-06 6.7E-06 0.0 6.7E-06 LEAFY VEGETABLE CONSUMPTION 5.6E-06 5.6E-06 3.5E-06 5.6E-06 1.7E-05 0.0 4.5E-06
- PRODUCE CONSUMPTION 2.8E-05 2.8E-05 1.8E-05 2.8E-05 2.8E-05 0.0 2.2E-05 MEAT CONSUMPTION 8.4E-06 8.4E-06 8.7E-06 8.9E-06 9.2E-06 0.0 5.9E-05 MILK CONSUMPTION (COW) 3.3E-05 3.3E-05 1.8E-05 3.0E-05 5.6E-05 2.3E-04 1.7E-05 MILK CONSUMPTION (GOAT) 8.7E-05 8.7E-05 4.2E-05 7.7E-05 1.1E-04 3.5E-04 3.5E-05 1 AGRICULTURAL TOTAL 1- EXCLUDING COW MILK CONSUMPTION 4.8E-04 4.8E-04 1.6E-04 4.1E-04 5.4E-04 4.4E-04 1.9E-04 EXCLUDING GOAT MILK CONSUMFTION 4.2E-04 4.2E-04 1.4E-04 3.6E-04 4.8E-04 3.3E-04 1.7E-04 J
l l
---------------- ..---------------------------==- _
==== -------,--------------=_ . --------------------
1 1 - -___________ _
TABLE 1.B-4 FIRST QUARTER 1986 POPULATION DOSE (50-MILE) FROM LIQUID EFFLUENTS (MAN-REM) _. ._ = _ .-.==--------------- EXPOSURE PATHWAY TOTAL BODY THYROID _ _ . - - = . ---------- - ---. -- --------__ ----__---- AQUATIC DRINKING WATER 1.5E-04 2.2E-04 , FISH CONSUMPTION 1.2E-01 1.2E-01 INVERTEBRATE CONSUMPTION 6.6E-05 6.7E-05 EXPOSURE TO CONTAMINATED SEDIMENT 1.1E-05 1.1E-05 SWIMMING AND BOATING 5.4E-08 5.4E-08 IRRIGATION AND LIVESTOCK WATERING LEAFY VEGETABLE CONSUMPTION 4.3E-07 1.3E-06 PRODUCE CONSUMPTION 2.1E-06 2.2E-06 MEAT CONSUMPTION 1.2E-05 1.3E-05 MILK CONSUMPTION 1.7E-04 3.0E-04 EXPOSURE TO CONTAMINATED SOIL 9.7E-07 9.7E-07 TOTAL 1.2E-01 1.2E-01 AVERAGE DOSE (MREM / PERSON) 5.7E-05 5.8E-05
= --------------------- ____. = _ -
- - - . --- ===_- --- __
O 8 O O O
TABLE 1.B-5 FIRST QUARTER 1986 O BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 4.3E-2 2.3E-2 Camma Air Dose (mrad) 1.6E-2 6.0E-3 Beta + Cama Skin Dose (mrem) - 1.4E-2 Gama Total Body Dose (mrem) - 5.1E-3 (a) East sector'at 677 meters. [b] East sector at 1000 meters. O G l l i l O 43
}
TABLE 1.B-6 FIRST QUARTER 1986 CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mead) 3.4E-1 1.8E-1 Gamma Air Dose (mrad) 4.4E-1 1.6E-1 Beta + Gamma Skin Dose (mrem) - 3.2E-1 Gamma Total Dody Dose (meem) - 1.5E-1 [a] North sector at 663 meters. [b] North sector at 1000 meters. ! till l 44 l
TABLE 1.B-7 FIRST QUARTER 1986 BATCH + CONTIhUOUS RELEASES l DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 3.8E-1 2.0E-1 Gamma Air Dose (mead) 4.6E-1 1.7E-1 Beta + Canna Skin Dose (mrem) - 3.3E-1 Ganna Total Sody Dose (mrem) - 1.6E-1 [a] Maximum site boundary location. [b] Maximum residence location. O I 45
TABLE 1.B-8 81 QUARTER 1986 BATCH RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) _-__ _------------- OTHER TOTAL ADULT INFANT INTERNAL BODY SKIN LUNG BONE THYROID THYROID ORGANS EXPOSURE LOCATION AND PATHWAY --------- --------- GARDEN (NNW SECTOR AT 1000. METERS)
----~.------------------------
AIR INHALATION 8.21E-06 8.21E-06 8.21E-06 8.22E-06 3.40E-05 3.73E-05 8.25E-06 4.67E-07 5.56E-07 4.67E-07 4.67E-07 4.67E-07 4.67E-07 4.67E-07 EXPOSURE TO SOIL 2.38E-04 0.0 3.03E-06 LEAFY VEGETABLE CONSUMPTION 2.71E-06 2.71E-06 2.70E-06 2.80E-06 1.25E-05 PRODUCE CONSUMPTION 1.24E-05 1.24E-05 1.24E-05 1.25E-05 2.03E-05 0.0 2.38E-05 2.39E-05 2.38E-05 2.39E-05 2.93E-04 3.77E-05 2.42E-05 TOTAL MEAT ANIMAL (NNW SECTOR AT 3400. METERS) 1.19E-06 1.19E-06 1.1CE-06 1.19E-06 5.12E-06 5.64E-06 1.20E-06 AIR INHALATION 5.16E-08 5.16E-08 5.16E-08 5.16E-08 EXPOSURE TO SOIL 5.16E-08 6.15E-08 5.16E-08 4.10E-07 4.10E-07 4.09E-07 4.20E-07 2.64E-05 0.0 4.45E-07 e LEAFY VEGETABLE CONSUMPTION 1.98E-06 m PRODUCE CONSUMPTION 1.97E-06 1.97E-06 1.97E-06 1.98E-06 2.84E-06 0.0 MEAT CONSUMPTION 3.77E-07 3.77E-07 3.76E-07 3.78E-07 2.14E-06 0.0 3.80E-07 4.00E-06 4.01E-06 3.99E-06 4.02E-06 3.65E-05 5.69E-06 4.05E-06 TOTAL MILK COW (NNW SECTOR AT 8000. METERS) AIR INHALATION 3.25E-07 3.25E-07 3.26E-07 3.26E-07 1.46E-06 1.61E-06 3.27E-07 1.14E-08 1.36E-08 1.14E-08 1.14E-08 1.14E-08 1.14E-08 1.14E-08 EXPOSURE TO SOIL 5.87E-06 1.27E-07 LEAFY VEGETABLE CONSUMPTION 1.19E-07 1.19E-07 1.19E-07. 1.21E-07 0.0 5.89E-07 5.89E-07 5.88E-07 5.90E-07 7.82E-07 0.0 5.91E-07 PRODUCE CONSUMPTION 1.13E-07 MEAT CONSUMPTION 1.12E-07 1.12E-07 1.12E-07 1.13E-07 5.02E-07 0.0 COW MILK CONSUMPTION 2.83E-07 2.83E-07 2.82E-07 2.88E-07 1.10E-05 8.25E-05 2.99E-07 1.44E-06 1.44E-06 1.44E-06 1.45E-06 1.96E-05 8.42E-05 1.47E-06 TOTAL MILK GOAT (NNW SECTOR AT 8000. METERS) AIR INHALATION 3.25E-07 3.25E-07 3.26E-07 3.26E-07 1.46E-06 1.61E-06 3.27E-07 EXPOSURE TO SOIL 1.14E-08 1.36E-08 1.14E-08 1.14E-08 1.14E-08 1.14E-08 1.14E-08 1.19E-07 1.19E-07 1.19E-07 1.21E-07 5.87E-06 0.0 1.27E-07 LEAFY VEGETABLE CONSUMPTION 5.91E-07 PRODUCE CONSUMPTION 5.89E-07 5.89E-07 5.88E-07 5.90E-07 7.82E-07 0.0 1.12E-07 1.12E-07 1.12E-07 1.13E-07 5.02E-07 0.0 1.13E-07 MEAT CONSUMPTION 1.35E-05 5.85E-07 G0AT MILK CONSUMPTION 5.65E-07 5.65E-07 5.59E-07 5.70E-07 9.97E-05 1.72E-06 1.72E-06 1.72E-06 1.73E-06 2.21E-05 1.01E-04 1.75E-06 . TOTAL O O O I . _ _ _ _ _ _ _ _ _
O O TABLE 1.B-9 C 81 QUARTER 1986 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) _==---------------
=--------- -____= _ - - - - - . --- ==--- _
----=___-
------------------==-- __ =__
OTHER TOTAL ADULT INFANT INTERNAL BODY SKIN LUNG BONE THYROID THYROID ORGANS EXPOSURE LOCATION AND PATHWAY --------- --------- 1 GARDEN (NNW SECTOR AT 1000. METERS) AIR INHALATION 3.91E-04 3.91E-04 4.00E-04 3.94E-04 8.12E-04 7.37E-04 3.92E-04 EXPOSURE TO SOIL 1.01E-05 1.19E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 LEAFY VEGETABLE CONSUMPTION 1.20E-04 1.20E-04 1.20E-04 2.02E-04 3.61E-03 0.0 1.24E-04 PRODUCE CONSUMPTION 6.09E-04 6.09E-94 6.09E-04 8.30E-04 7.26E-04 0.0 6.09E-04 TOTAL 1.13E-03 1.13E-03 1.14E-03 1.44E-03 5.16E-03 7.47E-04 1.14E-03 MEAT ANIMAL (NNW SECTOR AT 3400. METERS) AIR INHALATION 5.40E-05 5.40E-05 5.52E-05 5.44E-05 1.15E-04 1.06E-04 5.41E-05 EXPOSURE TO SOIL 1.14E-06 1.35E-06 1.14E-06 1.14E-06 1.14E-06 1.14E-06 1.14E-06 1.78E-05 1.78E-05 1.77E-05 2.70E-05 4.14E-04 0.0 1.83E-05
- c. LEAFY VEGETABLE CONSUMPTION 1.05E-04 9.16E-05
" PRODUCE CONSUMPTION 9.16E-05 9.16E-05 9.16E-05 1.17E-04 0.0 MEAT CONSUMPTION 1.71E-05 1.71E-05 1.71E-05 1.78E-05 4.40E-05 0.0 1.71E-05 TOTAL 1.82E-04 1.82E-04 1.83E-04 2.17E-04 6.79E-04 1.07E-04 1.82E-04 MILK COW (NNW SECTOR AT 8000. METERS)
AIR INHALATION 1.58E-05 1.58E-05 1.62E-05 1.59E-05 3.46E-05 3.21E-05 1.58E-05 2.47E-07 2.93E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 EXPOSURE TO SOIL 0.0 5.67E-06 LEAFY VEGETABLE CONSUMPTION 5.56E-06 5.56E-06 5.55E-06 7.57E-06 9.15E-05 PRODUCE CONSUMPTION 2.91E-05 2.91E-05 2.91E-05 3.45E-05 3.20E'05 0.0 2.91E-05 MEAT CONSUMPTION 5.47E-06 5.47E-06 5.47E-06 5.60E-06 1.13E-05 0.0 5.47E-06 COW MILK CONSUMPTION 1.31E-05 1.31E-05 1.31E-05 1.38E-05 1.74E-04 1.26E-03 1.34E-05 TOTAL 6.93E-05 6.94E-05 6.97E-05 7.77E-05 3.43E-04 1.29E-03 6.97E-05 l MILK GOAT (NNW SECTOR AT 8000. METERS) AIR INHALATION 1.58E-05 1.5BE-05 1.62E-05 1.59E-05 3.46E-05 3.21E-05 1.58E-05 EXPOSURE TO SOIL 2.47E-07 2.93E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 2.47E-07 LEAFY VEGETABLE CONSUMPTION 5.56E-06 5.56E-06 5.55E-06 7.57E-06 9.15E-05 0.0 5.67E-06 PRODUCE CONSUMPTION 2.91E-05 2.91E-05 2.91E-05 3.45E-05 3.20E-05 0.0 2.91E-05 MEAT CONSUMPTION 5.47E-06 5.47E-06 5.47E-06 5.60E-06 1.13E-05 0.0 5.47E-06 GOAT MILK CONSUMPTION 2.66E-05 2.66E-05 2.66E-05 2.80E-05 2.19E-04 1.55E-03 2.68E-05
. TOTAL 8.28E-05 8.28E-05 8.31E-05 9.18E-05 3.89E-04 1.58E-03 8.32E-05 t
TABLE 1.B-10 8 1 QUARTER 1986 BATCH + CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM)
- - - - - - - - - - - - - - - - - - _ _ _ _ = - . = - -------------------------= _ .__ : ..
OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS GARDEN MAXIMUM LOCATION AIR INHALATION 3.99E-04 3.99E-04 4.08E-04 4.02E-04 8.46E-04 7.74E-04 4.00E-04 EXPOSURE TO SOIL 1.06E-05 1.25E-05 1.06E-05 1.06E-05 1.06E-05 1.06E-05 1.06E-05 LEAFY VEGETABLE CONSUMPTION 1.23E-04 1.23E-04 1.23E-04 2.05E-04 3.85E-03 0.0 1.27E-04 PRODUCE CONSUMPTION 6.21E-04 6.21E-04 6.21E-04 8.43E-04 7.46E-04 0.0 6.21E-04 TOTAL 1.15E-03 1.15E-03 1.16E-03 1.46E-03 5.45E-03 7.85E-04 1.16E-03 MEAT ANIMAL MAXIMUM LOCATION AIR INHALATION 5.52E-05 5.52E-05 5.64E-05 5.56E-05 1.20E-04 1.12E-04 5.53E-05 EXPOSURE TO SOIL 1.19E-06 1.41E-06 1.19E-06 1.19E-06 1.19E-06 1.19E-06 1.19E-06 e LEAFY VEGETABLE CONSUMPTION 1.82E-05 1.82E-05 1.81E-05 2.74E-05 4.40E-04 0.0 1.87E-05 m PRODUCE CONSUMPTION 9.36E-05 9.36E-05 9.36E-05 1.19E-04 1.08E-04 0.0 9.36E-05 MEAT CONSUMPTION 1.75E-05 1.75E-05 1.75E-05 1.82E-05 4.61E-05 0.0 1.75E-05 TOTAL 1.86E-04 1.86E-04 1.87E-04 2.21E-04 7.15E-04 1.13E-04 1.86E-04 MILK COW MAXIMUM LOCATION AIR INHALATION 1.61E-05 1.61E-05 1.65E-05 1.62E-05 3.61E-05 3.37E-05 1.61E-05 EXPOSURE TO SOIL 2.58E-07 3.07E-07 2.58E-07 2.53E-07 2.58E-07 2.58E-07 2.58E-07 LEAFY VEGETABLE CONSUMPTION 5.68E-06 5.68E-06 5.67E-06 7.69E-06 9.74E-05 0.0 5.80E-06 PRODUCE CONSUMPTION 2.97E-05 2.97E-05 2.97E-05 3.51E-05 3.28E-05 0.0 2.97E-05 MEAT CONSUMPTION 5.58E-06 5.58E-06 5.58E-06 5.71E-06 1.18E-05 0.0 5.58E-06 COW MILK CONSUMPTION 1.34E-05 1.34E-05 1.34E-05 1.41E-05 1.85E-04 1 L4E-03 1.37E-05 TOTAL 7.07E-05 7.08E-05 7.11E-05 7.91E-05 3.63E-04 1.37E-03 7.12E-05 MILK GOAT MAXIMUM LOCATION v ------------------------------ AIR INHALATION 1.61E-05 1.61E-05 1.65E-05 1.62E-05 3.61E-05 3.37E-05 1.61E-05 EXPOSURE TO SOIL 2.58E-07 3.07E-07 2.58E-07 2.58E-07 2.58E-07 2.58E-07 2.58E-07 LEAFY VEGETABLE CONSUMPTION 5.68E-06 5.68E-06 5.67E-06 7.69E-06 9.74E-05 0.0 5.80E-06 PRODUCE CONSUMPTION 2.97E-05 2.97E-05 2.97E-05 3.51E-05 3.28E-05 0.0 2.97E-05 MEAT CONSUMPTION 5.58E-06 5.58E-06 5.58E-06 5.71E-06 1.18E-05 0.0 5.58E-06 GOAT MILK CONSUMPTION 2.72E-05 2.72E-05 2.72E-05 2.86E-05 2.32E-04 1.65E-03 2.74E-05 o TOTAL 8.45E-05 8.45E-05 8.48E-05 9.35E-05 4.11E-04 1.68E-03 8.49E-05 g O . O O
Q V TABLE 1.B-ll FIRST QUARTER 1986 BATCH + CONTINUOUS RELEASES POPULATION DOSE (50-MILE) FROM GASEOUS EFFLUENTS (MAN-REM)
--------------- _ . - _ _ _ _ _ - __ __ - - = - .
- =_ =__ _
EXPOSURE PATHWAY TOTAL BODY THYROID
. - - = - - - - - . _ - _ = = _ _ _ - - - . ---------- -_ _. _ = _ -
-=-
AIR SUBMERSION 4.5E-01 4.5E-01 AIR INHALATION 1.6E-03 3.5E-03 l EXPOSURE TO SOIL 1.5E-05 1.5E-05 LEAFY VEGETABLE CONSUMPTION 1.3E-05 1.7E-04 l
- PRODUCE CONSUMPTION 6.9E-05 7.4E-05 t
- MEAT CONSUMPTION 1.0E-04 1.9E-04 MILK CONSUMPTION 1.0E-03 1.2E-02 TOTAL 4.5E-01 4.6E-01 AVERAGE DOSE (MREM / PERSON) 2.2E-04 2.3E-04
- - _ _ _ = = - - _ - - - - - ___ - - _ . ___
E
TABLE 1.B-12 8 2 QUARTER 1986 DOSES FROM LIQUID EFFLUENTS (MREM)
--- .------------------ __---------------- ___ _ . - - - __=---= _- ==_____ _ __ _=_ __----------
OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS
.-- ------ --------- ----- =- ---------
AQUATIC AT MAXIMUM LOCATION DRINKING WATER 2.0E-05 2.0E-05 1.9E-05 2.2E-05 3.9E-05 8.7E-05 2.1E-05 FISH CONSUMPTION 8.8E-04 8.8E-04 1.4E-04 7.2E-04 9.4E-04 0.0 5.8E-04 INVERTEBRATE CONSUMPTION 1.2E-04 1.2E-04 3.0E-05 1.1E-04 1.2E-04 0.0 1.5E-04 EXPOSURE TO SHORELINE SEDIMENT 2.2E-06 2.5E-06 2.2E-06 2.2E-06 2.2E-06 0.0 2.2E-06 SWIMMING AND BOATING 4.3E-08 1.4E-07 4.3E-08 4.3E-08 4.3E-08 0.0 4.3E-08 AQUATIC TOTAL 1.0E-03 1.0E-03 1.9E-04 8.6E-04 1.1E-03 8.7E-05 7.6E-04
---------------------------- =- _ ==-------------- _--_ ___----------=_ ------------------------------------
$ AQUATIC AT AGRICULTURAL LOCATION DRINKING WATER 2.0E-05 2.0E-05 1.9E-05 2.2E-05 3.9E-05 8.7E-05 2.1E-05 FISH CONSUMPTION 1.0E-04 1.0E-04 1.7E-05 8.7E-05 1.1E-04 0.0 7.0E-05 INVERTEBRATE CONSUMPTION 1.4E-05 1.4E-05 3.5E-06 1.4E-05 1.5E-05 0.0 1.8E-05 EXPOSURE TO SHORELINE SEDIMENT 2.6E-07 3.0E-07 2.6E-07 2.6E-07 2.6E-07 0.0 2.6E-07 SWIMMING AND BOATING 5.2E-09 1.7E-08 5.2E-09 5.2E-09 5.2E-09 0.0 5.2E-09 IRRIGATION AND LIVESTOCK WATERING EXPOSURE TO AGRICULTURAL SDIL 3.4E-06 4.0E-06 3.4E-06 3.4E-06 3.4E-06 0.0 3.4E-06 LEAFY VEGETABLE CONSUMPTION 3.0E-06 3.0E-06 2.2E-06 4.1E-06 1.7E-05 0.0 3.2E-06 PRODUCE CONSUMPTION 1.4E-05 1.4E-05 1.0E-05 2.0E-05 1.5E-05 0.0 1.4E-05 MEAT CONSUMPTION 4.2E-06 4.2E-06 4.7E-06 4.8E-06 5.3E-06 0.0 3.8E-05 MILK CONSUMPTION (COW) 1.5E-05 1.5E-05 9.5E-06 1.5E-05 4.4E-05 2.5E-04 9.2E-06 MILK CONSUMPTION (GOAT) 3.9E-05 3.9E-05 2.1E-05 3.6E-05 7.3E-05 3.3E-04 1.8E-05 AGRICULTURAL TOTAL
. EXCLUDING COW MILK CONSUMPTION 2.0E-04 2.0E-04 8.1E-05 1.9E-04 2.8E-04 4.2E-04 1.9E-04 EXCLUDING GOAT MILK CONSUMPTION 1.8E-04 1.8E-04 7.0E-05 1.7E-04 2.5E-04 3.3E-04 1.8E-04
--------------------------------------------------==. _____ _--------. _---_. _------------------------------------
O O O -
l l TABLE 1.h-13 SECOND QUARTER 1986 POPULATION DOSE (50-MILE) FROM LIQUID EFFLUENTS (MAN-REM) EXPOSURE PATHWAY TOTAL BODY THYROID AQUATIC DRINKING WATER 8.0E-05 1.6E-04 FISH CONSUMPTION 4.5E-02 4.9E-02 INVERTEBRATE CONSUMPTION 2.8E-05 2.9E-05 EXPOSURE TO CONTAMINATED SEDIMENT 5.8E-06 5.8E-06 SWIMMING AND BOATING 6.0E-08 6.0E-08 IRRIGATION AND LIVESTOCK WATERING LEAFY VEGETABLE CONSUMPTION 2.3E-07 1.3E-06 PRODUCE CONSUMPTION 1.1E-06 1.1E-06 MEAT CONSUMPTION 5.9E-06 7.3E-06 i MILK CONSUMPTION 7.8E-05 2.4E-04 EXPOSURE TO CONTAMINATED SOIL 4.9E-07 4.9E-07 TOTAL 4.6E-02 4.9E-02 AVERAGE DOSE (MREM / PERSON) 2.2E-05 2.4E-05 ]
-----------------------------_=. ---_ _----------------------------------
O O Q
TABLE 1.B-14 SECOND QUARTER 1986 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 4.8E-2 2.5E-2 Gamma Air Dose (mrad) 1.5E-2 5.7E-3 Beta + Gamma Skin Dose (mrem) - 1.4E-2 Gamma Total Body Dose (mrem) - 4.8E-3 [a] North sector at 663 meters. ! [b] North sector at 1000 meters. O l \ I O 52
TABLE 1.B-15 SECOND QUARTER 1986 O CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY'AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 6.1E-2 3.3E-2 Gamma Air Dose (mead) 6.4E-2 2.4E-2 Beta + Gamma Skin Dose (mrem) - 4.8E-2 Gamma Total Body Dose (mrem) - 2.2E-2 [a] North sector at 663 meters. [b] North sector at 1000 meters. O . O 53
l l l _ TABLE 1.B-16 SECOND QUARTER 1986 BATCH + CONTINUCUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 1.1E-1 5.8E-2 Gamma Air Dose (mead) 7.9E-2 3.0E-2 Beta + Gamma Skin Dose (mrem) - 6.2E-2 l l Gamma Total Body Dose (mrem) - 2.7E-2 [a] Maximum site boundary location. [b] Maximum residence location. O 1 i 9 1 54
. 3 TABLE 1.B-17 82 QUARTER 1986 BATCH RELEASES DOSES FROM GASEQUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) .== --------------- ----------------------=__ __- ._. _ _ _
OTHER TOTAL ADULT INFANT INTERNAL BODY SKIN LUNG BONE THYROID THYROID ORGANS EXPOSURE LOCATION AND PATNWAY --------- _- == --------- ----- --- ---------
-----__--------------- u------ --------- ___
GARDEN (NNW SECTOR AT 1000. METERS) AIR INHALATION 1.35E-03 1.35E-03 1.39E-03 ~ 1.93E-03 6.26E-03 6.81E-03 1.36E-03 EXPOSURE TO SOIL 1.43E-04 1.69E-04 1.43E-04 1.43E-04 1.43E-04 1.43E-04 1.43E-04 1.42E-03 1.42E-03 1.42E-03 4.62E-03 4.79E-02 0.0 1.49E-03 LEAFY VEGETABLE CONSUMPTION 7.25E-03 PRODUCE CONSUMPTIOM 7.24E-03 7.24E-03 7.22E-03 2.38E-02 8.80E-03 0.0 TOTAL 1.02E-02 1.02E-02 1.02E-02 3.05E-02 6.31E-02 6.96E-03 1.02E-02 NEAT ANIMAL (SOUTH SECTOR AT 2700. METERS) 1.73E-04 1.73E-04 1.78E-04 2.48E-04 8.27E-04 9.04E-04 1.74E-04 AIR INHALA' ION 2.14E-05 2.14E-05 2.14E-05 EXPOSURE TO SOIL 2.14E-05 2.54E-05 2.14E-05 2.14E-05 2.09E-04 2.09E-04 2.09E-04 6.89E-04 7.18E-03 0.0 2.19E-04 LEAFY VEGETABLE CONSUMPTION 1.06E-03
$ PRODUCE CONSUMPTION 1.06E-03 1.06E-03 1.06E-03 3.55E-03 1.30E-03 0.0 MEAT CONSUMPTION 6.84E-05 6.84E-05 6.81E-05 1.19E-04 5.43E-04 0.0 6.92E-05 1.53E-03 1.54E-03 1.54E-03 4.63E-03 9.86E-03 9.26E-04 1.55E-03 TOTAL MILK COW (NW SECTOR AT 5000. METERS)
AIR INHALATION 3.85E-05 3.85E-05 3.96E-05 5.51E-05 1.89E-04 2.07E-04 3.87E-05 EXPOSURE TO SDIL 4.46E-06 5.29E-06 4.46E-06 4.46E-06 4.46E-06 4.46E-06 4.46E-06 LEAFY VEGETABLE CONSUMPTION 4.50E-05 4.50E-05 4.49E-05 1.45E-04 1.50E-03 0.0 4.69E-05 PRODUCE CONSUMPTION 2.29E-04 2.29E-04 2.28E-04 7.47E-04 2.78E-04 0.0 2.29E-04 1.57E-05 1.57E-05 1.56E-05 2.62E-05 1.15E-04 0.0 1.59E-05 MEAT CONSUMPTION 2.08E-02 5.03E-05 COW MILK CONSUMPTION 4.64E-05 4.64E-05 4.59E-05 8.72E-05 2.76E-03 TOTAL 3.79E-04 3.80E-04 3.79E-04 1.06E-03 4.85E-03 2.10E-02 3.85E-04 MILK GOAT (NW SECTOR AT 5000. METERS) 0 AIR INHALATION 3.85E-05 3.85E-05 3.96E-05 5.51E-05 1.89E-04 2.07E-04 3.87E-05 4.46E-06 5.29E-06 4.46E-06 4.46E-06 4.46E-06 4.40E-06 4.46E-06 EXPOSURE TO SOIL 1.50E-03 4.69E-05 LEAFY VEGETABLE CONSUMPTION 4.50E-05 4.50E-05 4.49E-05 1.45E-04. 0.0 2.29E-04 2.29E-04 2.28E-04 7.47E-04 2.78E-04 0.0 2.29E-04 PRODUCE CONSUMPTION 1.15E-04 1.59E-05 MEAT CONSUMPTION 1.57E-05 1.57E-05 1.56E-05 2.62E-05 0.0 GOAT MILK CONSUMPTION 9.21E-05 9.21E-05 9.04E-05 1.77E-04 3.35E-03 2.50E-02 9.74E-05 o TOTAL 4.24E-04 4.25E-04 4.23E-04 1.15E-03 5.44E-03 2.53E-02 4.32E-04
.=__ =--------------------------------------------_
TABLE 1.B-18 82 QUARTER 1986 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM)
-------------------- ==____------------------------------- ---------- ___
- =-------------- ==___:__-------------
OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS GARDEN (NNW SECTOR AT 1000. METERS) AIR INHALATION 6.13E-04 6.13E-04 6.21E-04 6.20E-04 1.05E-03 8.60E-04 6.13E-04 EXPOSURE TO SOIL 3.04E-05 3.56E-05 3.04E-05 3.04E-05 3.04E-05 3.04E-05 3.04E-05 LEAFV VEGETABLE CONSUMPTION 1.93E-04 1.93E-04 1.92E-04 3.25E-04 4.56E-03 0.0 1.99E-04 PRODUCE CONSUMPTION 9.95E-04 9.95E-04 9.88E-04 1.41E-03 1.14E-03 0.0 9.99E-04 TOTAL 1.83E-03 1.84E-03 1.83E-03 2.38E-03 6.78E-03 8.90E-04 1.84E-03 MEAT ANIMAL (SOUTH SECTOR AT 2700. METERS) AIR INHALATION 1.20E-04 1.20E-04 1.22E-04 1.22E-04 2.09E-04 1.73E-04 1.20E-04 EXPOSURE TO SOIL 7.03E-06 8.25E-06 7.03E-06 7.03E-06 7.03E-06 7.03E-06 7.03E-06 LEAFY VEGETABLE CONSUMPTION 4.10E-05 4.10E-05 4.07E-05 7.16E-05 1.05E-03 0.0 4.25E-05
$ PRODUCE CONSUMPTION 2.10E-04 2.10E-04 2.09E-04 3.06E-04 2.45E-04 0.0 2.11E-04 MEAT CONSUMPTION 3.76E-05 3.76E-05 3.74E-05 3.99E-05 1.07E-04 0.0 3.78E-05 TOTAL 4.16E-04 4.17E-04 4.16E-04 5.46E-04 1.62E-03 1.80E-04 4.19E-04 MILK COW (SSW SECTOR AT 4200. METERS)
AIR INHALATION 3.12E-05 3.12E-05 3.17E-05 3.16E-05 5.49E-05 4.55E-05 3.13E-05 EXPOSURE TO SOIL 1.23E-06 1.44E-06 1.23E-06 1.23E-06 1.23E-06 1.23E-06 1.23E-06 LEAFY VEGETABLE CONSUMPTION 1.06E-05 1.06E-05 1.05E-05 1.59E-05 1.88E-04 0.0 1.08E-05 PRODUCE CONSUMPTION 5.53E-05 5.53E-05 5.50E-05 7.20E-05 6.12E-05 0.0 5.54E-05 MEAT CONSUMPTION 1.01E-05 1.01E-05 1.00E-05 1.05E-05 2.21E-05 0.0 1.01E-05 COW MILK CONSUMPTION 2.46E-05 2.46E-05 2.43E-05 2.65E-05 3.56E-04 2.59E-03 2.52E-05 TOTAL 1.33E-04 1.33E-04 1.33E-04 1.58E-04 6.83E-04 2.64E-03 1.34E-04 MILK GOAT (SSW SECTOR AT 4200. METERS) AIR INHALATION 3.12E-05 3.12E-05 3.17E-05 3.16E-05 5.49E-05 4.55E-05 3.13E-05 EXPOSURE TO SOIL 1.23E-06 1.44E-06 1.23E-06 1.23E-06 1.23E-06 1.23E-06 1.23E-06 LEAFY VEGETABLE CONSUMPTION 1.06E-05 1.06E-05 1.05E-05 1.59E-05 1.88E-04 0.0 1.08E-05 PRODUCE CONSUMPTION 5.53E-05 5.53E-05 5.50E-05 7.20E-05 6.12E-05 0.0 5.54E-05 MEAT CONSUMPTION 1.01E-05 1.01E-05 1.00E-05 1.05E-05 2.21E-05 0.0 1.01E-05 GOAT MILK CONSUMPTION 5.01E-05 5.01E-05 4.91E-05 5.40E-05 4.48E-04 3.18E-03 5.12E-05 - TOTAL 1.58E-04 1.59E-04 1.58E-04 1.85E-04 7.75E-04 3.22E-03 1.60E-04
------------------------------------------------------- =-_ _____---------------------------------------------------
O O O
( O b ( U V TABLE 1.B-19 82 QUARTER 1986 BATCH + CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREPl) __-------------- .---- =------ ---- _ - . ==__ ----=- = _ = = - -- OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS
------------------------------ --------- --------- _= -
GARDEN MAXIMUM LOCATION AIR INHALATION 1.96E-03 1.96E-03 2.01E-03 2.55E-03 7.31E-03 7.67E-03 1.97E-03 EXPOSURE TO SOIL 1.73E-04 2.05E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 LEAFY VEGETABLE CONSUMPTION 1.61E-03 1.61E-03 1.61E-03 4.94E-03 5.25E-02 0.0 1.69E-03 PRODUCE CONSUMPTION 8.24E-03 8.24E-03 8.21E-03 2.52E-02 9.94E-03 0.0 8.25E-03 TOTAL 1.20E-02 1.20E-02 1.20E-02 3.29E-02 6.99E-02 7.85E-03 1.20E-02 MEAT ANIMAL MAXIMUM LOCATION AIR INHALATION 2.93E-04 2.93E-04 3.00E-04 3.70E-04 1.04E-03 1.08E-03 2.94E-04 EXPOSURE TO SOIL 2.84E-05 3.36E-05 2.84E-05 2.84E-05 2.84E-05 2.84E-05 2.84E-05 LEAFY VEGETABLE CONSUMPTION 2.50E-04 2.50E-04 2.50E-04 7.61E-04 8.23E-03 0.0 2.61E-04
$ PRODUCE CONSUMPTION 1.27E-03 1.27E-03 1.27E-03 3.86E-03 1.54E-03 0.0 1.27E-03
, MEAT CONSUMPTION 1.06E-04 1.06E-04 1.05E-04 1.59E-04 6.50E-04 0.0 1.07E-04 TOTAL 1.95E-03 1.96E-03 1.96E-03 5.18E-03 1.15E-02 1.11E-03 1.97E-03 a MILK COW l MAXIMUM LOCATION j AIR INHALATION 6.97E-05 6.97E-05 7.13E-05 8.67E-05 2.44E-04 2.52E-04 7.00E-05 EXPOSURE TO SOIL 5.69E-06 6.73E-06 5.69E-06 5.69E-06 5.69E-06 5.69E-06 5.69E-06 LEAFY VEGETABLE CONSUMPTION 5.56E-05 5.56E-05 5.54E-05 1.61E-04 1.69E-03 0.0 5.77E-05 PRODUCE CONSUMPTION 2.84E-04 2.84E-04 2.83E-04 8.19E-04 3.39E-04 0.0 2.84E-04 MEAT CONSUMPTION 2.53E-05 2.58E-05 2.56E-05 3.67E-05 1.37E-04 0.0 2.60E-05 COW MILK CONSUMPTION 7.10E-05 7.10E-05 7.02E-05 1.14E-04 3.12E-03 2.34E-02 7.55E-05 TOTAL 5.12E-04 5.13E-04 5.12E-04 1.22E-03 5.53E-03 2 36E-02 5.19E-04 MILK GOAT j MAXIMUM LOCATION AIR INHALATION 6.97E-05 6.97E-05 7.13E-05 8.67E-05 2.44E-04 2.52E-04 7.00E-05 EXPOSURE TO SOIL 5.69E-06 6.73E-06 5.69E-06 5.69E-06 5.69E-06 5.69E-06 5.69E-06 LEAFY VEGETABLE CONSUMPTION 5.56E-05 5.56E-05 5.54E-05 1.61E-04 1.69E-03 0.0 5.77E-05 PRODUCE CONSUMPTION 2.84E-04 2.84E-04 2.83E-04 8.19E-04 3.39E-04 0.0 2.84E-04 MEAT CONSUMPTION 2.58E-05 2.58E-05 2.56E-05 3.67E-05 1.37E-04 0.0 2.60E-05 GOAT MILK CONSUMPTION 1.42E-04 1.42E-04 1.39E-04 2.31E-04 3.80E-03 2.82E-02 1.49E-04
- TOTAL 5.82E-04 5.84E-04 5.81E-04 1.33E-03 6.21E-03 2.85E-02 5.92E-04
1 1 TABLE 1.B-20 SECOND QUARTER 1986 BATCH + CONTINUOUS RELEASES POPULATION DOSE (50-MILE) FROM GASEOUS EFFLUENTS (MAN-REM)
=_-- . _ - - - - _ _ --- . ---
? I l EXPOSURE PATHWAY TOTAL BODY THYRCID
.= ---------- ----------
= - - _ = - - - - - _ _
l l AIR SUBMERSION 6.8E-02 6.8E-02 AIR INHALATION 9.5E-03 3.4E-02 EXPOSURE TO SOIL 3.8E-04 3.8E-04 LEAFY VEGETABLE CONSUMPTION 1.5E-04 3.6E-03 (n PRODUCE CONSUMPTION 7.6E-04 8.7E-04
- MEAT CONSUMPTION 6.6E-04 2.5E-03 MILK CONSUMPTION 7.2E-03 2.4E-01 m
TOTAL 8.6E-02 3.5E-01 AVERAGE DOSE (MREM / PERSON) 4.2E-05 1.7E-04' _=-- ._ ---------__
=__ .- .==------------------
e O O O 1
((") , TABLE 1.B-21 Sheet 1 of 2 PARAMETERS USED IN CALCULATING DOSES FROM GASEOUS EFFLUENTS (Second Half 1986) 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 ' O.0 Harvest of stored feed to consumption by animals 90.0 Harvest of produce to consumption by man 60.0 Animal butchering to consumption 20.0 Food ingestion by animal to milking 2.0 Accumulation time on ground 7,300.0 Human Consumption Rates -(kg/yr) Leafy vegetables by adult 64.0 Produce by adult 456.0 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m 3/yr) Adult- 8,000.0 Og , 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 Crowing Season (days) Leafy vegetables 60.0 Pasture vegetation 30.0 Produce 60.0 Residential Structure Shielding Factor 0.7 r Fraction of Particulates Initially Deposited on Leafy Vegetatior. 0.2 l l Fraction of Particulates Initially Deposited on Produce 0.2 l 1 Fraction of Iodine Deposited on Leafy Vegetation 1.0 l ( Fraction of Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m 2) 240.0 j Field Decay Half Life (days) 14.0 . n-I s_ I 59 i
TABLE 1.B-21 Sheet 2 of 2 Parameter Value Agricultural Productivity (kg/m )2 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 Loafy Vegetables Crown in Garden of Interest 1.0 U Fraction of Produce Grown in Garden of Interest 0.76 l Fraction ~of Year Animal Crazes on Pasture 0.5 Fraction of Daily Feed that is Pasture Grass when Animal Grazes 1.0 9 9 60
TABLE 1.B-22 Shtet 1 of 2 PARAMETERS USED IN CALCULATING DOSES
<"'S FROM LIQUID EFFLUENTS O
Value Parameter 3rd Otr 1986 4th Otr 1986 Plant Dilution Flow Rate (spm) 26,500.0 30,300.0 Columbia River F16w Rate (cfs) 141,364.0 124,910.0 Dilution Factors Drinking water 2,392.0 1,851.0 Swimming water 526.0 407.0 . Aquatic biota 526.0 407.0 Shoreline sediment 526.0 407.0 Irrigation water 2,392.0 1,851.0 Milk and meat animal water 2,392.0 1,851.0 Decay Times (days) Discharge to drinking water '0.74 0.78 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 0.74 0.78 Discharge to milk and meat animal water 0.74 0.78 withdrawal
- s. Leafy vegetable harvest to consumption by man 1.0 l \'
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 milk from irrigated pastureland 310.0 Meat from irrigated pastureland 110.0 Annual Exposure Times (hr/yr)
Swimming and boating 12.0 Shoreline activities 12.0 ( Irrigated pasture 2,190.0 61
TABLE 1.B-2_2- Sheet 2 of 2 O Value Parameter 3rd Otr 1986 4th Otr 1986 Infant Consumption Rates (kg/yr) Drinking water 330.0 Cot # b milk from irrigated pastureland 330.0 Fraction of Year Animals Graze on Pasture 0.5 Fraction of Year Crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14.0 Irrigation Rate (liters /m 2-hr) 0.104 Fractional Concentration of Water in Soil (g/g) 0.2 Fraction of Leafy Vegetables Grown in Garden of 1.0 Interest Fraction of Produce Grown in Garden of Interest 0.7 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by Leafy Vegetables Fraction of Isotope in Irrigation Water that is 0.25 Initially Retained by Produca Pasture Grass Yield (kg/m 2) o,7 Vegetable Yield (kg/m 2) 2.0 Surface Density of Soil (kg/m 2) 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 vegetetion by milk goat 6.0 Pasture vegetation by beef 50.0 9 62
TABLE 1.B-23 0 3 QUARTER 1986 D')SES FROM LIQUID EFFLUENTS (MREM) 1 OTHER TOTAL ADULT INFANT INTERNAL BODY SKIN LUNG BONE THYROID TNYROID ORGANS EXPOSURE PATHWAY --------- - - = - - -
-- -_ _ --------- __==_ _ _ _
4 AQUATIC AT MAXIMUM LOCATION_ - _ _ _ _ = - - =
= - - - - - - - _ _ _ _
4.1E-05 DRINKING WATER 1.7E-05 1.7E-05 1.5E-05 1.8E-05 2.0E-05 3.2E-05 -l 7.6E-04 7.6E-04 1.2E-04 6.4E-04 7.6E-04 0.0 3.0E-03 FISH CONSUMPTION 1.1E-04 5.0E-04 INVERTEBRATE CONSUMPTION 1.1E-04 1.1E-04 3.4E-05 1.0E-04 0.0 EXPOSURE TO SHORELINE SEDIMENT 8.3E-06 9.7E-06 8.3E-06 8.3E-06 8.3E-06 0.0 8.3E-06 SWIMMING AND BOATING 9.6E-08 5.9E-08 9.6E-08 9.6E-08 9.6E-08 0.0 9.6E-08 8.9E-04 8.9E-04 1.8E-04 7.7E-04 9.0E-04 3.2E-05 3.5E-03 AQUATIC TOTAL
-___=_ _----_---__----__--___- -- --__---___---__-- $ AQUAn ..f AGRICULTURAL LOCATION DRINKING WATER 1.7E-05 1.7E-05 1.5E-05 1.8E-05 2.0E-05 3.2E-05 4.1E-05 FISH CONSUMPTION 1.7E-04 1.7E-04 2.7E-05 1.4E-G4 1.7E-04 0.0 6.5E-04 INVERTEBRATE CONSUMPTION 2.4E-05 2.4E-05 7.6E-06 2.2E-05 2.4E-05 0.0 1.1E-04 EXPOSURE TO SHORELINE SEDIMENT 1.8E-06 2.1E-06 1.8E-06 1.8E-06 1.8E-06 0.0 1.8E-06 SWIMMING AND BOATING 2.1E-08 1.3E-08 2.1E-08 2:1E-08 2.1E-08 0.0 2.1E-08 IRRIGATION AND LIVESTOCK WATERING __---
EXPOSURE TO AGRICULTURAL SOIL 2.4E-05 2.8E-05 2.4E-05 2.4E-05 2.4E-05 0.0 2.4E-05 LEAFY VEGETABLE CONSUMPTION 3.2E-06 3.2E-06 2.0E-06 3.6E-06 5.7E-06 0.0 1.5E-05 PRODUCE CONSUMPTION 1.6E-05 1.6E-05 9.5E-06 1.7E-05 1.6E-05 0.0 6.7E-05 MEAT CONSUMPTION 5.9E-06 5.9E-06 2.2E-05 1.4E-05 6.1E-06 0.0 6.1E-04 I MILK CONSUMPTION (COW) 1.7E-05 1.7E-05 8.1E-06 1.6E-05 2.2E-05 6.6E-05 2.0E-05 MILK CONSUMPTION (GOAT) 4.6E-05 4.6E-05 1.8E-05 4.1E-05 5.2E-05 1.1E-04 1.6E-05 l AGRICULTURAL TOTAL 3.2E-04 1.4E-04 1.5E-03 l ) EXCLUDING COW MILK CONSUMPTION 3.0E-04 3.1E-04 1.3E-04 2.8E-04 i EXCLUDING GOAT MILK CONSUMPTION 2.7E-04 2.8E-04 1.2E-04 2.6E-04 2.9E-04 9.8E-05 1.5E-03 i
- - - _ _ _ . ' - - - _ -WW------------3mg3-g-----M----m--MW
"-M-------6_M_ - - - - - - - _ _ _-6M---
m------W-6-W----WMM--M-6---WW-MM---M__-_ _ . .
TABLE 1.B-24 THIRD QUARTER 1986 POPULATION DOSE (50-MILE) FROM LIQUID EFFLUENTS (MAN-REM)
---------------------------- = ----------- --_-----------------
EXPOSURE PATHWAY TOTAL BODY THYROID AQUATIC DRINKING WATER 6.8E-05 8.3E-05 FISH CONSUMPTION 7.2E-02 7.3E-02 INVERTEBRATE CONSUMPTION 4.8E-05 4.8E-05 EXPOSURE TO CONTAMINATED SEDIMENT 4.1E-05 4.1E-05
, SWIMMING AND BOATING 2.5E-07 2.5E-07 c-IRRIGATION AND LIVESTOCK WATERING LEAFY VEGETABLE CONSUMPTION 2.5E-07 4.4E-07 PRODUCE CONSUMPTION 1.2E-06 1.2E-06 MEAT CONSUMPTION 8.2E-06 8.4E-06 MILK CONSUMPTION 8.8E-05 1.2E-04 EXPOSURE TO CONTAMINA*ED SOIL 3.5E-06 3.5E-06 TOTAL 7.2E-02 7.3E-02 AVERAGE DOSE (MREM / PERSON) 3.5E-05 3.5E-05
-----------------------------== . ___---------------------------------
b O O - - - O --
TABLE 1.B-25 O THIRD QUARTER 1986 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mead) 1.1E-2 3.0E-3 Gamma Air Dose (mrad) 3.9E-3 7.9E-4 Beta + Camma Skin Dose (mrem) - 1.8E-3 Gamma Total Body Dose (mrem) - 6.7E-4 [a] NE sector at 820 meters. [b] ESE sector at 1300 meters. O O 65
TABLE 1.B-26 THIRD QUARTER 1086 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 2.0E-2 5.3E-3 Camma Air Dose (mrad) 1.3E-2 2.5E-3 l l Beta + Camma Skin Dose (nrem) - 5.2E-3 1 camma Total Body Dose (mrem) 2.3E-3 [a] ENE sector at 688 meters. [b] North sector at 1000 meters. O O 66
f TABLE 1.B-27 p THIRD QUARTER 1986
) BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION
-Site Boundary [a] ResidenceID}
Beta Air Dose (mrad) 3.0E-2 8.4E-3 Gamma Air Dose (mead) 1.7E-2 3.3E-3 Beta + Gamma kin Dose (mrem) - 7.0E-3 Gama Total Body Dose (rtrem) - 3.0E-3 [a] Maximum site boundary location. [b] Maximum residence location. O 67
TABLE 1.B-28 83 QUARTER 1986 BATCH RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS GAFDEN (SOUTH SECTOR AT 1900. METERS) AIR INHALATION 2.01E-06 2.01E-06 2.01E-06 2.02E-06 7.15E-06 7.53E-06 2.02E-06 EXPOSURE TO SOIL 8.53E-08 1.04E-07 8.53E-08 8.53E-08 8.53E-08 8.53E-08 8.53E-08 LEAFY VEGETABLE CONSUMPTION 7.30E-07 7.30E-07 7.30E-07 7.64E-07 8.68E-05 0.0 8.44E-07 PRODUCE CONSUMPTION 3.14E-06 3.14E-06 3.14E-06 3.14E-06 6.03E-06 0.0 3.15E-06 TOTAL 5.97E-06 5.99E-06 5.97E-06 6.01E-06 1.00E-04 7.61E-06 6.10E-06 MEAT ANIMAL (SOUTH SECTOR AT 2700. METERS) EXPOSURE TO SOIL 4.73E-08 5.74E-08 4.73E-08 4.73E-08 4.73E-08 4.73E-08 4.73E-08 LEAFY VEGETABLE CONSUMPTION 4.17E-07 4.17E-07 4.17E-07 4.35E-07 4.81E-05 0.0 4.80E-07 PRODUCE CONSUMPTION 1.81E-06 1.81E-06 1.81E-06 1.81E-06 3.41E-06 0.0 1.81E-06
$ MEAT CONSUMPTION 3.48E-07 3.48E-07 3.48E-07 3.49E-07 3.59E-06 0.0 3.52E-07 TOTAL 3.74E-06 3.75E-06 3.74E-06 3.76E-06 5.92E-05 4.29E-06 3.81E-06 MILK COW (SSW SECTOR AT 4200. METERS)
AIR INHALATION 2.66E-07 2.66E-07 2.66E-07 2.66E-07 9.70E-07 1.03E-06 2.67E-07 EXPOSURE TO SOIL 7.22E-09 8.77E-09 7.22E-09 7.22E-09 7.22E-09 7.22E-09 7.22E-09 LEAFY VEGETABLE CONSUMPTION 9.49E-08 9.49E-08 9.49E-08 9.77E-08 7.38E-06 0.0 1.04E-07 PRODUCE CONSUMPTION 4.45E-07 4.45E-07 4.45E-07 4.45E-07 6.89E-07 0.0 4.45E-07 MEAT CONSUMPTION 8.53E-08 8.53E-08 8.53E-08 8.54E-08 5.80E-07 0.0 8.59E-08 COW MILK CONSUMPTION 2.23E-07 2.23E-07 2.23E-07 2.28E-07 1.38E-05 1.04E-04 2.40E-07 TOTAL 1.12E-06 1.12E-06 1.12E-06 1.13E-06 2.35E-05 1.05E-04 1.15E-06 MILE GOAT (SSW SECTOR AT 4200. METERS) a ------------------------------ AIR INHALATION 2.66E-07 2.66E-07 2.66E-07 2.66E-07 9.70E-07 1.03E-06 2.67E-07 EXPOSURE TO SOIL 7.22E-09 8.77E-09 7.22E-09 7.22E-09 7.22E-09 7.22E-09 7.22E-09 LEAFY VEGETABLE CONSUMPTION 9.49E-08 9.49E-08 9.49E-08 9.77E-08 7.38E-06 0.0 1.04E-07 PRODUCE CONSUMPTION 4.45E-07 4.45E-07 4.45E-07 4.45E-07 6.89E-07 0.0 4.45E-07 MEAT CONSUMPTION 8.53E-08 8.53E-08 8.53E-08 8.54E-08 5.80E-07 0.0 8.59E-08 GOAT MILK CONSUMPTION 4.34E-07 4.34E-07 4.34E-07 4.40E-07 1.68E-05 1.26E-04 4.55E-07 g TOTAL 1.33E-06 1.33E-06 1.33E-06 1.34E-06 2.64E-05 1.27E-04 1.36E-06 O O O
n . . . b h v} d TABLE 1.B-29 33 QUARTER 1986 CONT 7900US RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) - - - - - = _ - _ . _ - ---------- .
. - = _ _ _ _ _ _ - - _ .= ____
OTHER ADULT INFANT INTERNAL TOTAL ORGANS BODY SKIN LUNG BONE . THYROID THYROID EXPOSURE LCCATION AND PATHWAY
= - - - - - - -- _--_----_
GARDEN (SOUTH SECTOR AT 1900. METERS) 3.30E-04 3.30E-04 3.30E-04 3.30E-04 1.25E-03 1.32E-03 3.31E-04 AIR INIA ION 9.37E-05 EXPOSURE TO SOIL 9.37E-05 1.10E-04 9.37E-05 9.37E-05' 9.37E-05 9.37E-05 1.28E-04 1.22E-04 1.33E-04 1.47E-02 0.0 1.50E-04 LEAFY VEGETABLE CONSUMPTION 1.28E-04 5.70E-04 PRODUCE CONSUMPTION 5.54E-04 5.54E-04 5.21E-04 5.51E-04 1.04E-03 0.0 1.11E-03 1.12E-03 1.07E-03 1.11E-03 1.71E-02 1.41E-03 1.14E-03 TOTAL MEAT ANIMAL (SOUTH SECTOR AT 2700.--__ METERS)
- _ = - -
7.22E-04 7.65E-04 1.89E-04 AIR INHALATION 1.88E-04 1.88E-04 1.88E-04 1.89E-04 5.23E-05 6.14E-05 5.23E-05 5.23E *5 5.23E-05 5.23E-05 5.23E-05 EXPOSURE TO SOIL 7.11E-05 7.74E-05 8.20E-03 0.0 8.68E-05 LEAFY VEGETABLE CONSUMPTION 7.45E-05 7.45E-05 3.35E-04 3.26E-04 3.26E-04 3.08E-04 3.25E-04 6.00E-04 0.0 PRODUCE CONSUMPTION 6.17E-05 6.17E-05 5.91E-05 6.15E-05 6.15E-04 0.0 6.36E-05
$ MEAT CONSUMPTION 7.03E-04 7.13E-04 6.79E-04 7.05E-04 1.02E-02 8.17E-04 7.27E-04 TOTAL .
MILK COW (SSW SECTOR AT 4200. METERS) 4.61E-05 4.61E-05 4.60E-05 4.61E-05 1.79E-04 1.90E-04 4.63E-05 AIR INHALATION 7.81E-06 7.815-06 7.81E-06 7.81E-06 7.81E-06 EXPOSURE TO SDIL 7.81E-06 9.17E-06 1.23E-03 0.0 1.88E-05 LEAFY VEGETABLE CONSUMPTION 1.70E-05 1.70E-05 1.65E-05 1.74L-05 8.04E-05 8.04E-05 7.77E-05 8. 02E- 05 1.21E-04 0.0 8.17E-05 PRODUCE CONSUMPTION 1.52E-05 1.52E-C5 1.48E-05 1.52E-05 9.79E-05 0.0 1.55E-05 MEAT CONSUMPTION 1.74E-02 4.68E-05 COW MILK CONSUMPTION 4.23E-05 4.23E-05 3.90E-05 4.26E-05 2.31E-03 2.09E-04 2.10E-04 2.02E-04 2.09E-04 3.95E-03 1.76E-02 2.17E-04 TOTAL MILK GOAT (SSW SECTOR AT 4200. METERS) 1.90E-04 4.63E-05 4.61E-05 4.61E-05 4.60E-05 4.61E-05 1.79E-04 AIR INHALATION 7.81E-06 7.81E-06 7.81E-06 7.81E-06 EXPOSURE TO SOIL 7.81E-06 9.17E-06 7. 81 E- 06 1.88E-05 LEAFY VEGETABLE CONSUMPTION 1.70E-05 1.70E-05 1.65E-05 1.74E-05 1.23E-03 0.0 8.04E-05 8.04E-05 7.77E-05 8.02E-05 1.21E-04 0.0 8.17E-05 PRODUCE CONSUMPTION 1.52E-05 1.52E-05 1.48E-05 1.52E-05 9.79E-05 0.0 1.55E-05 MEAT CONSUMPTION 8.59E-05 2.09E-02 9.48E-05 GOAT MILK CONSUMPTION 8.67E-05 8.67E-05 7.68E-05 2.81E-03 2.53E-04 2.55E-04 2.40E-04 2.53E-04 4.45E-03 2.11E-02 2.65E-04 TOTAL
TABLE 1.B-30 03 QUARTER 1986 BATCH + CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) _ _ __ _ _ _ _ __,______________
-_-----_----___===. ---=_ _
OTHER TOTAL ADULT INFANT INTERNAL BODY SKIN LUNG BONE THYROID THYROID ORGANS EXPOSURE LOCATION AND PATHWAY -- --- --------- =--___ _ -----.--- = = _ _ GARDEN MAXIMUM LOCATION 3.32E-04 3.32E-04 3.32E-04 3.32E-04 1.26E-03 1.33E-03 3.33E-04 AIR INHALATION 9.38E-05 9.38E-05 EXPOSURE TO SOIL 9.38E-05 1.10E-04 9.38E-05 9.38E-05 9.38E-05 1.29E-04 1.29E-04 1.23E-04 1.34E-04 1.48E-02 J.0 1.51E-04 LEAFY VEGETABLE CONSUMPTION 1.05E-03 5.73E-04 PRODUCE CONSUMPTION 5.57E-04 5.57E-04 5.24E-04 5.54E-04 0.0 1.12E-03 1.13E-03 1.08E-03 1.12E-03 1.72E-02 1.42E-03 1.15E-03 TOTAL MEAT ANIMAL
)
l j MAXIMUM LOCATION _ =_ __-- 1.89E-04 1.89E-04 1.89E-04 1.90E-04 7.26E-04 7.69E-04 1.90E-04 AIR INHALATION 5.23E-05 5.23E-05 5.23E-05 5.23E-05 EXPOSURE TO SOIL 5.23E-05 6.15E-05 5.23E-05 7.49E-05 7.49E-05 7.15E-05 7.78E-05 8.25E-03 0.0 8.73E-05 i LEAFY VEGETABLE CONSUMPTION 6.03E-04 0.0 3.37E-04 PRODUCE CONSUMPTION 3.28E-04 3.28E-04 3.10E-04 3.27E-04 6.20E-05 6.20E-05 5.94E-05 6.18E-05 6.19E-04 0.0 6.40E-05 y MEAT CONSUMPTION TOTAL 7.07E-04 7.17E-04 6.83E-04 7.09E-04 1.03E-02 8.21E-04 7.31E-04 MILK COW f MAXIMUM LOCATION
---------------------_. _ = =
AIR INHALATION 4.64E-05 4.64E-05 4.63E-05 4.64E-05 1.80E-04 1.91E-04 4.66E-05 EXPOSURE TO SOIL 7.82E-06 9.18E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 LEAFY VEGETABLE CONSUMPTION 1.71E-05 1.71E-05 1.66E-05 1.75E-05 1.24E-03 0.0 1.89E-05 PRODUCE CONSUMPTION 8.08E-05 8.08E-05 7.81E-05 8.06E-05 1.22E-04 0.0 8.21E-05 1.53E-05 1.53E-05 1.49E-05 1.53E-05 9.85E-05 0.0 1.56E-05 MEAT CONSUMPTION 1.75E-02 4.70E-05 COW MILK CONSUMPTION 4.25E-05 4.25E-05 3.92E-05 4.28E-05 2.32E-03 TOTAL 2.10E-04 2.11E-04 2.03E-04 2.10E-04 3.97E-03 1.77E-02 2.18E-04 MILK GOAT ) { MAXIMUM LOCATION AIR INHALATION 4.64E-05 4.64E-05 4.63E-05 4.64E-05 1.80E-04 1.91E-04 4.66E-05 EXPOSURE TO SOIL 7.82E-06 9.18E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 7.82E-06 LEAFY VEGETABLE CONSUMPTION 1.71E-05 1.71E-05 1.66E-05 1.75E-05 1.24E-03 0.0 1.89E-05 8.08E-05 8.08E-05 7.81E-05 8.06E-05 1.22E-04 0.0 8.21E-05 PRODUCE CONSUMPTION 1.56E-05 NEAT CONSUMPTION 1.53E-05 1.53E.05 1.49E-05 1.53E-05 9.85E-05 0.0 i GOAT MILK CONSUMPTION 8.71E-05 8.71E-05 7.72E-05 8.63E-05 2.83E-03 2.10E-02 9.53E-05 ( > TOTAL 2.54E-04 ?.56E-04 2.41E-04' 2.54E-04 4.48E-03 2.12E-02 2.66E-04 I
\
)
O O J
. TABLE 1.B-31 THIRD QUARTER 1986 BATCH + CONTINUOUS RELEASES POPULATION DOSE (50-MILE) FROM GASEOUS EFFLUENTS (MAN-REM)
= _ _ _ - = _ = _ - _ = _ .
-__ =_ ___ ------ __
EXPOSURE PATHWAY TOTAL BODY THYROID AIR SUBMERSION 1.5E-02 1.5E-02 AIR INHALATION 3.8E-03 1.4F-02 EXPOSURE TO SOIL 3.9E-04 3.9E-04 u LEAFY VEGETABLE CONSUMPTION 4.1E-05 2.0E-03
"" PRODUCE CONSUMPTION 2.0E-04 2.7E-04 MEAT CONSUMPTION 3.1E-04 1.4E-03 MILK CONSUMPTION 3.3C-03 1.4E-01 TOTAL 2.3E-02 1.7E-01 - AVERAGE DOSE (MREM / PERSON) 1.1E-05 8.2E-05 I
9 4 TABLE 1.B-32 ( 8 4 QUARTER 1986 DOSES FROM LIQUID EFFLUENTS (MREM) OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS
== _---- __- --
.---------- =------ . __ _
AQUATIC AT MAXIMUM LOCATION DRINKING WATER 1.5E-05 1.5E-05 1.4E-05 1.8E-05 1.6E-05 2.3E-05 2.8E-05 FISH CONSUMPTION 1.8E-04 1.8E-04 3.6E-05 1.7E-04 1.9E-04 0.0 1.0E-03 INVERTEBRATE CONSUMPTION 3.8E-05 3.8E-05 2.6E-05 6.6E-05 3.8E-05 0.0 2.9E-04 . EXPOSURE TO SHORELINE SEDIMENT 3.4E-06 3.9E-06 3.4E-06 3.4E-06 3.4E-06 0.0 3.4E-06 SWIMMING AND BOATING 4.0E-08 5.6E-08 4.0E-08 4.0E-08 4.0E-08 0.0 4.0E-08 AQUATIC TOTAL 2.4E-04 2.4E-04 8.0E-05 2.6E-04 2.4E-04 2.3E-05 1.3E-03 _--------- ==- =----------------- _-----_ _------------- ___ ==-. .------------------- y AQUATIC AT AGRICULTURAL LOCATION w -_---_---__------ _ _ _ _ _ _ - - --_- DRINKING WATER 1.5E-05 1.5E-05 1.4E-05 1.8E-05 1.6E-05 2.3E-05 2.8E-05 FISH CONSUMPTION 4.1E-05 4.1E-05 7.9E-06 3.8E-05 4.1E-05 0.0 2.25-04 INVERTEBRATE CONSUMPTION 8.4E-06 8.4E-06 5.7E-06 1.5E-05 8.4E-06 0.0 6.4E-05 EXPOSURE TO SHORELINE SEDIMENT 7.4E-07 8.7E-07 7.4E-07 7.4E-07 7.4E-07 0.0 7.4E-07 SWIMMING AND BOATING 8.8E-09 1.2E-08 8.8E-09 8.8E-09 8.8E-09 0.0 8.8E-09 IRRIGATION AND LIVESTOCK WATERING EXPOSURE TO AGRICULTURAL SOIL 9.7E-06 1.1E-05 9.7E-06 9.7E-06 9.7E-06 0.0 9.7E-06 LEAFY VEGETABLE CONSUMPTION 2.2E-06 2.2E-06 1.9E-06 4.1E-06 3.0E-06 0.0 8.9E-06 PRODUCE CONSUMPTION 1.1E-05 1.1E-05 9.6E-06 2.0E-05 1.1E-05 0.0 4.0E-05 MEAT CONSUMPTION 4.0E-06 4.0E-06 1.4E-05 1.0E-05 4.1E-06 0.0 3.8E-04 MILK CONSUMPTION (COW) 8.9E-06 8.9E-06 6.7E-06 9.4E-06 1.0E-05 3.4E-05 1.5E-05 MILK CONSUMPTION (GOAT) 2.1E-05 2.1E-05 1.5E-05 2.2E-05 2.3E-05 6.1E-05 1.4E-05 AGRICULTURAL TOTAL - EXCLUDING COW MILK CONSUMPTION 1.1E-04 1.1E-04 7.9E-05 1.4E-04 1.2E-04 8.4E-05 7.7E-04 EXCLUDING GOAT MILK CONSUMPTION 1.0E-04 1.0E-04 7.1E-05 1.2E-04 1.0E-04 5.7E-05 7.7E-04
----_ ----- . _=---- _------------------- _ - - _ _ _ .
O t G
O ;[ '3 ( 't) l TABLE 1.B-33 FOURTH QUARTER 1986 POPULATION DOSE (50-MILE) FROM LIQUID EFFLUENTS (MAN-REM) EXPOSURE PATHWAY TOTAL BODY THYROID AQUATIC DRINKING WATER 5.9E-05 6.4E-05 FISH CONSUMPTION 1.8E-02 1.8E-02 INVERTEBRATE CONSUMPTION 1.7E-05 1.7E-05 EXPOSURE TO CONTAMINATED SEDIMENT 1.7E-05 1.7E-05. u SWIMMING AND BOATING 1.0E-07 1.0E-07 u IRRIGATION AND LIVESTOCK WATERING LEAFY VEGETABLE CONSUMPTION 1.7E-07 2.3E-07 PRODUCE CONSUMPTION 8.4E-07 8.4E-07 MEAT CONSUMPTION 5.6E-06 5.7E-06 MILK CONSUMPTICN 4.5E-05 5.6E-05 EXPOSURE TO CONTAMINATED SOIL 1.4E-06 1.4E-06 TOTAL 1.8E-02 1.8E-02 AVERAGE DOSE (MREM / PERSON) 8.6E-06 8.7E-06 O
TABLE 1.B-34 FOURTH QUARTER 1986 BATCH RELEASES DOSES FROH NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] Residence [b] Beta Air Dose (mrad) 9.1E-3 4.9E-3 Camma Air Dose (mead) 3.6E-3 1.3E-3 Beta + Camma Skin Dose (mrem) - 3.lE-3 Gamma Total Body Dose (mren) - 1.1E-3 [a] North sector at 663 meters. [b] North sector at 1000 meters. O 74
TABLE 1.B-35 FOURTH QUARTER 1986 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION SLte Boundary [a] ResidenceIDI Beta Air Dose (mead) 1.9E-2 1.0E-2 Gamma Air Dose (mrad) 7.OE-3 2.6E-3 Beta + Gamma Skin Dose (mrem) - 6.1E-3 Gamma Total Body Dose (mrein) - 2.2E-3 [a] North sector at 663 meters. [b] North sector at 1000 meters. O 1 O 75 6 h a ums
TABLE 1.B-36 FOURTH QUARTER 1986 ' BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 2.8E-2 1.5E-2 Camma Air Doso (mrad) 1.1E-2 4.0E-3 Beta + Camma Skin Dose (mrem) - 9.2E-3 Camma Total Body Dose (mrem) - 3.4E-3 [a] North sector at'663 meters. [b] North sector at 1000 meters. O l O 76
TABLE 1.B-37
~
04 QUARTER 1986 CONTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) ------- ~ -- =----- - - - - - - - - - - - - OTHER TOTAL ADULT INFANT INTERNAL BODY SKIN LUNG BONE THYROID THYROID ORGANS EXPOSURE LOCATION AND PATHWAY GARDEN (NNW SECTOR AT 1000. METERS)
. -_ = _ _ -_ __
1.12E-03 1.66E-03 1.48E-03 9.85E-04 AIR INHALATION 9.84E-04 9.84E-04 1.03E-03 4.62E-06 5.61E-06 4.62E-06 4.62E-06 4.62E-06 4.62E-06 4.62E-06 ) EXPOSURE TO SOIL 1.42E-03 6.08E-03 0.0 1.42E-03 LEAFY VEGETABLE CONSUMPTION 1.42E-03 1.42E-03 5.17E-03 7.58E-03 PRODUCE CONSUMPTION 7.58E-03 7.58E-03 7.58E-03 2.71E-02 7.73E-03 0.0 9.98E-03 9.98E-03 1.00E-02 3.39E-02 1.53E-02 1.13E-03 9.99E-03 TOTAL MEAT ANIMAL (NNW SECTOR AT 3400. METERS) 1.37E-04 1.37E-04 1.44E-04 2.31E-04 2.10E-04 1.61E-04 1.37E-04 AIR INHALATION 5.21E-07 5.21E-07 5.21E-07 5.21E-07 5.21E-07 EXPOSURE TO SDIL 5.21E-07 6.33E-07 1.71E-04 LEAFY VEGETABLE CONSUMPTION 1.70E-04 1.70E-04 1.70E-04 5.94E-04 6.97E-04 0.0 PRODUCE CONSUMPTION 9.12E-04 9.12E-04 9.12E-04 3.11E-03 9.3GE-04 0.0 9.12E-04 5.53E-05 5.53E-05 5.53E-05 9.97E-05 9.11E-05 0.0 5.53E-05
% MEAT CONSUMPTION 1.28E-03 1.28E-03 1.28E-03 4.04E-03 1.93E-03 1.61E-04 1.28E-03 TOTAL MILK COW (NORTH SECTOR AT 8000. METERS) ----
5.83E-05 4.83E-05 4.83E-05 4.83E-05 5.05E-05 8.12E-05 7.51E-05 AIR INHALATION 1.16E-07 1.16E-07 1.16E-07 1.16E-07 EXPOSURE TO SOIL 1.16E-07 1.41E-07 1.16E-07 4.46E-05 LEAFY VEGETABLE CONSUMPTION 4.45E-05 4.45E-05 4.45E-05 1.39E-04 1.62E-04 0.0 2.39E-04 2.39E-04 2.39E-04 7.29E-04 2.42E-04 0.0 2.39E-04 PRODUCE CONSUMPTION 2.89E-05 1.90E-05 MEAT CONSUMPTION 1.90E-05 1.90E-05 1.90E-05 2.70E-05 0.0 4.95E-05 4.95E-05 4.95E-05 8.72E-05 2.69E-04 1.82E-03 4.97E-05 COW MILK CONSUMPTION 4.00E-04 4.00E-04 4.02E-04 1.07E-03 7.76E-04 1.88E-03 4.00E-04 TOTAL MILK GOAT (NORTH SECTOR AT 8000. METERS) 4.83E-05 4.83E-05 5.05E-05 8.12E-05 7.51E-05 5.83E-05 4.83E-05 AkRINHALATkbN 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 EXPOSURE TO SOIL 1.16E-07 1.41E-07 LEAFY VEGETABLE CONSUMPTION 4.45E-05 4.45E-05 4.45E-05 1.39E-04 1.62E-04 0.0 4.46E-05 PRODUCE CONSUMPTION 2.39E-04 2.39E-04 2.39E-04 7.29E-04 2.42E-04 0.0 2.39E-04 1.90E-05 1.90E-05 1.90E-05 2.89E-05 2.70E-05 0.0 1.90E-05 MEAT CONSUMPTION 1.80E-04 2.31E-03 1.02E-04 GOAT MILK CONSUMPTION 1.01E-04 1.01E-04 1.01E-04 3.65E-04 4.52E-04 4.52E-04 4.54E-04 1.16E-03 8.71E-04 2.37E-03 4.52E-04 g TOTAL ___ _=_--_=_ _ --- _- ----------__ . - _ _----------- .
---------_. .-------__ _ _ =_ _ _ _ - _ _ _ _ ___---- . _
TABLE 1.B-38 4 QUARTER 1986 BATCH RELEAS"S DOSES rROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) _=--- -_ __ ____ ___---------------_ _ -------------- OTHER TOTAL ADULT INFANT INTERNAL EXPOSURE LOCATION AND PATHWAY BODY SKIN LUNG BONE THYROID THYROID ORGANS GARDEN (NNW SECTOR AT 1000. METERS) AIR INHALATION 3.59E-07 3.59E-07 3.59E-07 3.60E-07 2.14E-06 2.43E-06 3.62E-07 EXPOSURE TO SOIL 1.61E-08 1.95E-08 1.61E-08 1.61E-08 1.61E-08 1.61E-08 1.61E-08 LEAFY VEGETABLE CONSUMPTION 1.28E-07 1.28E-07 1.28E-07 1.35E-07 1.65E-05 0.0 1.50E-07 PRODUCE CONSUMPTION 5.40E-07 5.40E-07 5.40E-07 5.40E-07 1.09E-06 0.0 5.41E-07 TOTAL 1.04E-06 1.05E-06 1.04E-06 1.05E-06 1.97E-05 2.45E-06 1.07E-06 MEAT ANIMAL iggW SgCIgR AI_34pg. MgIgRS}__ AIR INHALATION 4.98E-08 4.98E-08 4.98E-08 4.99E-08 3.09E-07 3.53E-07 5.01E-08 EXPOSURE TO SOIL 1.82E-09 2.20E-09 1.82E-09 1.82E-09 1.82E-09 1.82E-09 1.82E-09 LEAFY VEGETABLE CONSUMPTION 1.84E-08 1.84E-08 1.84E-08 1.91E-08 1.86E-06 0.0 2.08E-08 y PRODUCE CONSUMPTION 8.20E-08 8.20E-08 8.20E-08 8.21E-08 1.44E-07 0.0 8.21E-08 m MEAT CONSUMPTION 1.58E-08 1.58E-08 1.58E-08 1.58E-08 1.41E-07 0.0 1.59E-08 TOTAL 1.68E-07 1.68E-07 1.68E-07 1.69E-07 2.46E-06 3.54E-07 1.71E-07 MILK COW . (NNW SECTOR AT 8000. METERS)
' AIRINHALAiibN 1.33E-08 1.33E-08 1.33E-08 1.33E-08 8.59E-08 9.83E-08 1.34E-08 EXPOSURE TO SOIL 3.94E-10 4.79E-10 3.94E-10 3.94E-10 3.94E-10 3.94E-10 3.94E-10 LEAFY VEGETABLE CONSUMPTION 5.11E-09 5.11E-09 5.11E-09 5.26E-09 4.06E-07 0.0 5.63E-09 PRODUCE CONSUMPTION 2.39E-08 2.39E-08 2.39E-08 2.39E-08 3.73E-08 0.0 2.39E-08 MEAT CONSUMPTION 4.58E-09 4.58E-09 4.58E-09 4.59E-09 3.18E-08 0.0 4.61E-09 COW MILK CONSUMPTION 1.20E-08 1.20E-08 1.20E-08 1.23E-08 7.61E-07 5.73E-06 1.30E-08 TOTAL 5.92E-08 5.93E-08 5.92E-08 5.97E-08 1.32E-06 5.83E-06 6.09E-08 MILK GOAT (NNW SECTOR AT 8000. METERS)
AIR INHALATION 1.33E-08 1.33E-08 1.33E-08 1.33E-08 8.59E-08 9.83E-08 1.34E-08 EXPOSURE TO SOIL 3.94E-10 4.79E-10 3.94E-10 3.94E-10 3.94E-10 3.94E-10 3.94E-10 LEAFY VEGETABLE CONSUMPTION 5.11E-09 5.11E-09 5.11E-09 5.26E-09 4.06E-07 0.0 5.63E-09 PRODUCE CONSUMPTION 2.39E-08 2.39E-08 2.39E-03 2.39E-08 3.73E-08 0.0 2.39E-08 MEAT CONSUMPTION 4.58E-09 4.58E-09 4.58E-09 4.59E-09 3.18E-08 0.0 4.61E-09 GOAT MILK CONSUMPTION 2.33E-08 2.33E-08 2.33E-08 2.37E-08 9.23E-07 6.91E-06 2.45E-08 - TOTAL 7.05E-08 7.06E-08 7.05E-08 7.11E-08 1.48E-06 7.00E-06 7.24E-08 O . O O
h O O O TABLE 1.B-39 84 QUARTER 1986 BATCH + C03rTINUOUS RELEASES DOSES FROM GASEOUS EFFLUENTS (EXCLUDING NOBLE GASES) AT MAXIMUM OFFSITE EXPOSURE LOCATIONS (MREM) -_-- __ -------------- OTHER ADULT INFANT INTERNAL TOTAL ORGANS BODY SKIN LUNG BONE THYROID THYROID EXPOSURE LOCATION AND PATHWAY _ - _ - _ . __ --__ __ _---- ----- _ _ - _ - --------- GARDEN MAXIMUM LOCATION 9.84E-04 9.84E-04 1.03E-03 1.66E-03 1.48E 1.12E-03 9.85E-04 kkR NH LATION 5.63E-06 4.64E-06 4.64E-06 4.64E-06 4.64E-06 4.64E-06 EXPOSURE TO SOIL 4.64E-06 6.10E-03 0.0 1.42E-03 1.42E-03 1.42E-03 1.42E-03 5.17E-03 LEAFY VEGETABLE CONSUMPTION 7.58E-03 7.58E-03 7.58E-03 2.71E-02 7.73E-03 0.0 7.58E-03 PRODUCE CONSUMPTION 9.98E-03 9.98E-03 1.00E-02 3.39E-02 1.53E-02 1.13E-03 9.99E-03 TOTAL MEAT ANIMAL MAXIMUM LOCATION 1.37E-04 1.37E-04 1.44E-04 2.31E-04 2.10E-04 1.61E-04 1.37E-04 f AIRINHALATIbN 6.35E-07 5.23E-07 5.23E-07 5.23E-07 5.23E-07 5.23E-07 l EXPOSURE TO SDIL 5.23E-07 6.99E-04 1.71E-04 1.70E-04 1.70E-04 1.70E-04 5.94E-04 0.0 LEAFY VEGETABLE CONSUMPTION 9.12E-04 9.12E-04 9,12E-04 3.11E-03 9.30E-04 0.0 9.12E-04 PRODUCE CONSUMPTION 5.53E-05 5.53E-05 5.53E-05 9.97E-05 9.12E-05 0.0 5.53E-05 U MEAT CONSUMPTION 1.28E-03 1.28E-03 1.28E-03 4.04E-03 1.93E-03 1.61E-04 1.28E-03 TOTAL MILK COW MAXIMUM LOCATION 4.83E-05 4.83E-05 5.05E-05 8.12E-05 7.52E-05 5.84E-05 4.83E-05 IRkNHkl.ATION 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 EXPOSURE TO SOIL 1.16E-07 1.41E-07 4.45E-05 4.45E-05 4.45E-05 1.39E-04 1.62E-04 0.0 4.46E-05 LEAFY VEGETABLE CONSUMPTION 2.39E-04 PRODUCE CONSUMPTION 2.39E-04 2.39E-04 2.39E-04 7.29E-04 2.42E-04 0.0 1.90E-05 1.90E-05 1.90E-05 1.90E-05 2.89E-05 2.70E-05 0.0 MEAT CONSUMPTION 4.95E-05 4.95E-05 4.95E-05 8.72E-05 2.70E-04 1.83E-03 4.97E-05 COW MILK CONSUMPTION 4.00E-04 4.00E-04 4.02E-04 1.07E-03 7.77E-04 1.89E-03 4.00E-04 TOTAL MILK GOAT MAXIMUM LOCATION 4.83E-05 4.83E-05 5.05E-05 8.12E-05 7.52E-05 5.84E-05 4.83E-05 AIR INHALATION 1.16E-07 1.16E-07 1.16E-07 1.16E-07 1.16E-07 EXPOSURE TO SOIL 1.16E-07 1.41E-07 4.46E-05 4.45E-05 4.45E-05 4.45E-05 1.39E-04 1.62E-04 0.0 LEAFY VEGETABLE CONSUMPTION 7.29E-04 2.42E-04 2.39E-04 PRODUCE CONSUMPTION 2.39E-04 2.39E-04 2.39E-04 0.0 1.90E-05 1.90E-05 1.90E-05 1.90E-05 2.89E-05 2.70E-05 0.0 MEAT CONSUMPTION 1.01E-04 1.01E-04 1.01E-04 1.80E-04 3.66E-04 2.32E-03 1.02E-04 GOAT MILK CONSUMPTION 4.52E-04 4.52E-04 4.54E-04 1.16E-03 8.72E-04 2.38E-03 4.52E-04 TOTAL
- o. - - - . -- ---___------_. --___--_--__--__---__--
s b _ _ _ _ _ .
) TABLE 1.B-40 FOURTH QUARTER 1986 BATCH + CONTINUOUS RELEASES POPULATION DOSE (50-MILE) FROM GASEOUS EFFLUENTS (MAN-REM)
-- -.____________________ ----===_----.___________________
EXPOSURE PATHWAY TOTAL BODY THYROID AIR SUBMERSION 9.2E-03 9.2E-03 AIR INHALA1 ION 4.3E-03 6.5E-03
$ EXPOSURE TO SOIL LEAFY VEGETABLE CONSUMPTION 8.3E-06 9.4E-05 8.3E-06 3.4E-04 PRODUCE CONSUMPTION 5.0E-04 5.1E-04 MEAT CONSUMPTION 3.3E-04 4.6E-04 MILK CONSUMPTION 3.5E-03 2.0E-02 TOTAL 1.8E-02 3.7E-02 AVERAGE DOSE (MREM / PERSON) 8.7E-06 1.8E-05
- - - _ _ _ _ _ _ _ _ _ = - - _ _ _ _ - - - . _ - - - _ = _________________
O e O O O
1.C. METEOROLOGICAL DATA Meteorological data for 1986 are available for review in the PGE Corporate Office as required by Technical Specification 6.9.1.5.4. Meteorological models and assumptions used in performing the analyses are presented in PGE-1021. "Offsite Dose Calculation Manual".
\
l O - O 81
1.D. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
-(O)
# Requirement Trojan Facility Operating License NPF-1 Appendix A Technical Specification 6.15.2.A for changes to the ODCM requires:
"6.15.2.A Licensee initiated changes:
"1. Shall be submitted to the Commission by inclusion in the Semiannual Effluent Release Report for the period in which the change (s) was made and shall contain:
"a. sufficiently detailed information to totally j support the rationale for the change without benefit of additional or cupplemental informa-tion. Information submitted should consist of a package of those pages of the ODOM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluations justifying the char.ge(s);
"b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and "c. documentation of the fact that the change has
( been reviewed and found acceptable by the PRB." Report In 1986, there were no PGE-initiated changes to the ODCM. 4 l ) l iO 82 I.
1.E. REACTOR COOLANT SYSTEM (RCS) SPECIFIC ACTIVITY f% Requirement Trojan Facility Operating License NPF-1, Appendix A, Technical Specification 6.9.1.5 states:
"d. The results of specific activity analysis in which the primary
. coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis.while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit."
Report
-~s In 1986, there were no out-of-specification specific activity results to report.
O 83
- 2. ANNUAL PERSONNEL EXPOSURE AND MONITORING REPORT O Requirement-Trojan Facility Operating License NpF-1, Appendix A, Technical Specification 6.9.1.5 states:
" Reports required on an annual basis shall include:
"a. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 meem/yr and their associated man-rem exposure according to work and job functions, e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20%
of the individual total dose need not be accounted for. In the aggregate, at last 80% of the total whole body dose received from external sources shall be assigned to specific major work functions." Report
/N \
Table 2-1 lists the number of workers receiving exposures greater than 100 mesa per year and the total exposures by work and job function for the year'1986. The special maintenance category in Table 2-1 is for removal for testing of steam generator tubes. Requirement 10 CFR 20.408(b) requires: ! "a statistical summary report of the personnel monitoring l information recorded by the licensee for individuals for whom j personnel monitoring was either required or provided. . . indicating ! the number of individuals whose total whole body exposure recorded i during the previous calendar year was. . . (in various exposure l ranges)." i
- Report l Table 2-2 is the statistical report of radiation exposure required by 10 CFR 20.408(b) for the year 1986.
l l 4 84
TABLE 2-1 REPORT ON NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION No. of Personnel (>100 mrem) Total Man-Rem Station Utility Contract Station Utility Contract Work and Job Function Employees Employees Workers Employees Employees Workers REACTOR OPERATIONS & SURVEILLANCE Maintenance Personnel 4 0 28 2.25 0.00 8.76 Operating Personnel 32 0 0 9.53 0.00 0.00 Chem & RADCON Personnel 50 0 32 15.89 0.00 13.08 Supervisory Personnel 3 1 4 2.47 0.28 2.77 Engineering Personnel 3 5 2 1.31 1.89 1.13 ROUTINE MAINT. & INSERVICE INSPECTION Maintenance Personnel 87 9 312 40.51 2.74 177.52 Operating Personnel 2 0 0 0.76 0.00 0.05 Chem & RADCON Personnel 18 0 72 6.77 0.00 45.65 Supervisory Personnel 17 3 29 9.07 1.31 10.67 Engineering Personnel 7 21 23 2.55 12.97 20.78 SPECIAL MAINTENANCE Maintenance Personnel 0 0 37 0.00 0.00 19.91 Operating Fersonnel 0 0 0 0.00 0.00 0.00 C) Chem & RADCON Personnel 0 0 4 0.19 0.00 1.47 Supervisory Personnel 0 0 1 0.01 0.00 0.13 Engineering Personnel 0 0 1 0.03 0.00 0.15 WASTE PROCESSING Maintenance Personnel 0 0 2 0.31 0.00 1.54 Operating Personnel 0 0 0 0.10 0.00 0.00 Chem & RADCON Personnel 20 0 6 9.08 0.00 2.75 Supervisory Personnel 1 0 0 0.21 0.01 0.13 Engineering Personnel 0 0 0 0.03 0.00 0.00 REFUELING Maintenance Personnel 9 0 46 6.00 0.18 39.81 Operating Personnel 12 0 0 2.71 0.00 0.00 Chem & RADCON Personnel 10 0 15 5.35 0.00 5.14 Supervisory Personnel 6 0 4 1.65 0.04 1.34 Engineering Personnel 2 0 0 0.69 0.02 0.00 3 i l TOTAL i Maintenance Personnel 76 8 366 36.66 2.31 198.62 Operating Personnel 27 0 0 8.87 0.00 0.05 Chem & RADCON Personnel 55 0 103 26.74 0.00 54.46 1.21 11.64 O 30 Supervisory Personnel 18 4 9.58 Engineering Personnel 8 24 24 2.95 12.32 15.68 GRAND TOTAL 184 36 523 84.80 15.84 280.50 85
O TABLE 2-2 TROJAN PLANT WHOLE BODY EXPOSURE (REM) 1986 Number of People With No Exposure = 786 Exposure of at Least 0.001 and Less Than 0.099 Number of People = 560 Exposure of at Least 0.100 and Less Than 0.249 Number of People = 244 Exposure of at Least 0.250 and Less Than 0.499 Number of People = 234 Exposure of at Least 0.500 and Less Than 0.749 Number of People = 144 Exposure of at Least 0.750 and Less Than 0.999 Number of People = 66 { Exposure of at Least 1.)0O and Less Than 1.999 Number of People = 72 Exposure of at Least 2.000 and Less Than 2.999 Number of People = 1 Expasure 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 = 381.140 man-rem 9 86 l
. . = -. __ .- _
- 3. STEAM CENERATOR TUBE INSPECTIONS Requirement Trojan Facility Operating License BPF-1, Appendix A, Technical j Specification 6.9.1.5 states:
" Reports required on an annual basis shall include:
t "b. The complete results of steam generator tube inservice inspection performed during the report period (reference Specification 4.4.5.5.b)." Technical Specification 4.4.5.5.b. requires:
"The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed. This report shall include:
"1. Number and extent of tubes inspected.
"2. Location and percent of wall-thickness penetration for each indication of an imperfection.
"3. Identification of tubes plugged."
Report
- a. Program Sununary i
The May 1986 steam generator inspection program consisted of MIZ-18/SM-10 multi-frequency eddy current examinations as follows: ! 1. Examination through the first support from the hot leg af all active tubing in Steam Generators A and C.
- 2. Examination through the first support from the cold leg of all active tubing in Steam Generators A and C.
j 3. Selection of three tube pull candidates from Steam Generator C hot les based on results of the first support program.
- 4. Random pattern examination through the U-bend from the hot leg of approximately 3 percent of the active tubes in each of Steam Generators A and C.
- 5. Examination through the U-bend from the hot leg of the small radius Row 2 tubes in Steam Generators A and C.
- 6. Expansion of the Row 2 program to include Row 2 tubes in Steam Generator B, Row 3 and selected Row 4 tubes in Steam Generator C, and Row 2 and selected Rows 3 and 4 tubes in Steam Generator D.
87
I
- b. Results
- 1. Table 1.1 provides the number and extent of the tubes inspected in each steam generator.
- 2. Table 1.2 provides the location and percent of wall-thickness penetration for each indication of an imperfection (indications
<20 percent of the nominal tube wall thickness).
- 3. Table 1.3 is a list of tubes plugged and the basis for plugging as a result of the May 1986 steam generator inspection program.
The attached figures show the plugging patterns in each steam generator at the conclusion of the May 1986 outage. In addition, a plug was installed in Tube RIC9 in the "C" steam generator which had been the source of excessive primary-to-secondary leakage during the 1985-86 operating cycle and found to be missing during the inspection. This event was reported in our letter to the NRC (Withers to Martin) dated June 6, 1986.
- c. Classification 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
/
r l
TABLE 1.1 ( Q
SUMMARY
OF EXAMINATION SCOPE MAY 1986 Steam Number of Extent Cenerator Program Tubes Tested Tested
- A Hot 1 3291 H1:H 2 103 7C:H 3 205 7C:H A Cold 1 3293 C1:C B Hot 3 93 7C:H C Hot 1 3288 H1:H 2 103 7C:H 3 95 7C:H C Cold 1 3288 C1:C 3 8 7H:C 4 23 FL:C D Hot 3 68 7C:H 3 1 7C:H Total Tested = 13,859 NOTE: Program 1 = First support Program 2 = Random pattern program 3 - Row 2 Program 4 = Tubes neighboring pulled tubes
- H1:H = Entry from hot leg side, probe inserted to first support on hot leg side of U-bend.
7C:H = Entry from hot leg side, probe inserted through U-bend to seventh support on cold leg side. C1:C = Entry from cold leg side, probe inserted to first support on cold leg side of U-bend. 7H:C = Entry from cold leg side, probe inserted to seventh support on hot les side of U-bend. FL:C = Entry from cold leg side, probe inserted for full length of tube. 89
TABLE 1.2
SUMMARY
OF EXAMINATION RESULTS MAY 1986 Steam Generator A B C D Hot : Cold Hot Hot : Cold Hot Tubes Tested 3599 : 3293 93 3486 : 3319 69 Quantifiable Indications:
- 1. Tubes Exceeding Plugging Limit >= 40% 2: 0 0 0: 0 1
- 2. Degraded Tubes >= 20% < 40% 2: 0 0 2: 1 0
- 3. Imperfections < 20% 2: 4 0 13 : 2 0 0
O [ 90 l
TABLE 1.3 TUBE PLUGGING LIST MAY 1986 Steam Generator Tube Number Basis A R2/C1 U-Bend Indication A R2/C3 U-Bend Indication A R2/C5 U-Bend Indication A R2/C6 U-Bend Indication A R2/C7 U-Bend Indication - A R2/C8 U-Bend Indication A R2/C9 U-Bend Indication A R2/C10 U-Bend Indication A R2/C13 U-Bend Indication A R2/C15 U-Bend Indication A R2/C16 U-Bend Indication A R2/C17 U-Bend Indication A R2/C18 U-Bend Indication A R2/C20 U-Bend Indication A R2/C21 U-Bend Indication A R2/C22 U-Bend Indication A R2/C23 U-Bend Indication A R2/C24 U-Bend Indication U-Bend Indication l O A A A R2/C73 R2/C74 R2/C15 U-Bend Indication U-Bend Indication A R2/C76 U-Bend Indication A R2/C17 U-Bend Indication I A R2/C78 U-Bend Indication A R2/C79 U-Bend Indication A R2/C80 U-Bend Indication A R2/C81 U-Bend Indication A R2/C82 U-Bend Indication ! A RS/C40 >40% indication at hot les tube sheet A R33/C69 >40% indication at hot leg tube sheet C R2/C59 U-Bend Indication C R2/C71 U-Bend Indication C R2/C77 U-Bend Indication C R2/C78 U-Bend Indication C R2/C79 U-Bend Indication C R2/C82 U-Bend Indication i C R2/C92 U-Bend Indication i C R2/C94 U-Bend Indication l C R9/C65 Pulled Tube C R12/C63 Pulled Tube l C R25/C58 Pulled Tube [ I D R2/C37 >40% indication at hot les tube sheet 7-~ b 91
1 TROJAN NUCLEAR PLANT S/G A HOT / COLD LEG PLUGGED TUBES ELEVATION- TUBESHEET INSPECTION DATE-5/86 REPORT DATE-7/86 wo SS 80 75 70 ES t>O SS 50 45 40 35 30 25 20 SS to 5 L ot . r- - -- Tr __ _ , _ 7. I, 4 o.
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4 RELIEF VALVE CHALLENGES O Requirement Trojan Facility Operating License NPF-1 Appendix A. Technical Specification 6.9.1.5.c requires: Annual Report shall include. . . Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) or safety valves." Report In 1986, there were no challenges of the safety valves or power-operated relief valves. 10 1 i l l i 1 O 96
- 5. CHANCES. TESTS, AND RXPRRIMENTS O Requirement Federal Regulation 10 CFR 50.59 and the Trojan operating License NPF-1 require:
"(a)(1) The holder of a license. . .may (i) make changes in the facility as described in the safety analysis report.
(ii) make changes in the procedures as described in the safety analysis report, and (iii) conduct tests or experiments not described in the safety analysis report, without prior Commission approval, unless the proposed change, test or experiment involves a change in the technical specifications incorporated in the license or an unreviewed safety question.
"(b) . . .The licensee shall furnish. . . annually. . .a report containing a brief description of such changes, tests, and experiments, including a summary of the safety evaluation of each."
Report Section 5 of the Annual Report provides a description of changes, tests, and experiments completed in 1986 in accordance with 10 CFR 50.59, Including a summary of the safety evaluation for each. Also included in O Section 5, is a summary of changes to the technical specifications submitted to and approved by the NRC in accordance with 10 CFR 50.59 and 10 CFR 50.90. O 97
5.A PLANT MODIFICATIONS AND DESIGN CHANCES The following Plant modifications and design changes were compinted in 1986 and are being reported in accordance with 10 CFR 50.59. These modifications were evaluated, and it was determined that they did not: (a) increase the probability of occurrence of an accident or malfunction of the 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. Other design changes were partially completed during 1986, some to meet regulatory co.1mitments, and will be reported in future Annual Reports when all portions of the design changes are completed.
- 1. Plant Deslan channe 76-256 The original design at the Steam Seal System Unioader Valve MO-3603 control circuit was such that the valve could not be throttled.
I Plant Design Change 76-256 rewired the valve control circuit to i allow the valve to be throttled. l This modification did not involve a change to the Trojan Technical l Specifications or an unreviewed safety question.
- 2. Plant Desian Channe 77-152 When both service water (SW) pumps are in service, annunciator panot X-13 window 8-6 was lit. This alann provide! no useful information, as both pumps are normally operating. In addition, the associated circulating water blowdown valve interlock with the SW System was determined to be ineffective and provided unnecessary complicattor.
] to the circuitry. 1 Plant Design Change ??-152 deleted the alarm and associated circulating water blowdown valve interlock with the service water I pumps. River thermal dischargo limits are adequately monitored by existing indication and alarms. l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. ! 3. Plant Desian Chanan 18-063 I l It was discovered that installation of grout between various pipes and the walls they penetrated could result in exeossive stress on the pipo under cortain conditions. 98
Plant Design Change 78-063 corrected all identified deficiencies and eliminated the potential for excessive stresses. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 4 Plant Design Change 78-065 There was no method of monitoring the emergency diocol generator (EDC) diesci engine intake filter op as required by the ' manufacturer. Plant Design Change 78-065 installed permanent op gauges for each engine intako filter. This modification did not involvo a change to the Trojan Technical Specifications or an unreviewed safety question.
- 5. Plant Design change 78-084 The service water pumps gland seal drain lino did not drain I properly. This lino penetrated the pump room wall, had no check valvo, so water tight integrity of the room was lost.
Plant Design Chango 18-084 installed a length of pipe and a check valve on each service water pump subplate so that the gland seal leakoff is properly drained to the lower section of the Intako Structure. This modification did not involvo a change to the Trojan Technical Speelfications or an uncoviewed safety question.
- 6. plant tosinn Change 80-081 Due to increasing communication demands at Trojan, the existing Plant communication system was unable to perform adequately.
Plant Design Chango 80-081 provided a new solid-stato PBX located in the Technical Support conter (TSC) computer room. This modification did not involvo a change to the Trojan Technical Specifications or an unroviewed cofoty question.
- 1. Plant Dasinn Chango 81-057 The 125-V de battery breakers to buses Dio, D20, D30, and D40 had no position indication in the control room.
Plant Design Chango 81-057 installed an annunciator common to all four breakorn to inform operations personnot of an open battery breaker. O 99
i t y-ss This modification did not involve a change to the Trojan Technical ( } Specifications or an unreviewed safety question. C'
- 8. Plant Design Change 82-003 Contact common voltage to several annunciators was supplied from one logic card and field contact. Thus, failure of one logic card or field contact could have resulted in several inoperable annunciators as well as making troubleshooting of such a daisy chain configuration time consuming.
Plant Design Change 82-003 removed the daisy chain jumpers and rewired each annunciator on Pancis C11 and C21 such that it now supplies its own field common. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 9. Plant Design Change 82-076 The installation of gland seal piping to the heater drain pumps was incorrect. This resulted in improperly cooled and lubricated
- packing, which led to excessive pump leakage.
Plant Design Change 82-076 modified the packing box piping por vendor recommendation. One of two pressure control valvoo (PCVs) was replaced by a pressure differential control valvo (PDVC); the {N) y other was relocated in the new piping scheme. Thic modification did not involve a change to the Trojan Technical Specifications or an unreviewod safety question.
- 10. Plant Design Change 82-080 During outagen, bottled N2 gas was hauled into tho Main Steam Support Structure (MSSS) and bubbled into the steam generators (wnile in wet-layup) to promote mixing of water which improves water chemistry.
Plant Design Change 82-080 provided piping, valves, regulator, and temporary hosco from the bulk nitrogen (N2 ) system to the area to provido a N2 supply. This modification did not involve a change to the Trojan Technical Specifications or an unroviewed cafety question.
- 11. Plant Design Chongo 83-003 It la necessary to pin soveral feedwater system hangers when draining the system in order to procerve piping and pump integrity.
There wao no access to these hangero creating a personnel safety hazard. p) (J ~ 100
Plant Design Change 83-003 provided access platforms and ladders to hangers H-5, H-6, H-14, and H-20. Thig modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 12. Plant Design chante 83-008 Due to occasional breakdowns in the guardhouse search equipment, costly and slow personnel processing results were encountered.
Plant Design Change 83-008 rearranged the existing railings, turnstiles, and visitor badge issuo counter, and additional x-ray, metal detector, and explosive detector units were installed to form three search lines. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 13. Plant Design Chante 83-009 Residual Heat Removal (RHR) low pressure letdown valves 8734A and B are located in high radiation areas and therefore the operators are subject to excessive radiation in order to operate them. The installed manual remote operators did not work well because of the amount of torque required to operate the valve.
Plant Design Change 83-009 replaced the manual remote operators with motor operators. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 14. Plant Design chante 83-017 Poor access to certain valves was creating a personnel safety hazard during startup and normal Plant conditions. Often systems could not be vented or drained unless operators climbed and/or walked on piping.
Plant Design Change 83-017 provided access platforms and extended vent / drain lines to accessible locations. This modification did not involve a change to the Trojan Technical Specifications or an unroviewed safety question.
- 15. Plant Design Chant.e 83-019 It was determined that reactor coolant pump (RCP) operation woul1 be benefleial under certain accident conditions. Component cooling water (CCW) to the RCPs isolated on an safety injection (SI) initiated Containment Isolation Signal (CIS) requiring stopping the RCPs.
101
[t Plant Design Change 83-019 modified the CCW to RCP isolation valves control circuitry to provide (1) isolation in response to either hi-hi containment pressure or (2) any SI coincidence with a low CCW surge tank 1cvel. This modification did not involve a change to the Trojan Technical Specifications or an uncoviewed safety question.
- 16. Plant Desian Channe 83-025 The original design of the steam-driven auxiliary feedwater pump controls resulted in turbine overspeed when the turbine was chut down and then restarted from the control room without first realigning the valves locally.
Plant Design Change 83-025 replaced the existing control switch for MO-3170 (stop valve) on panel CO-5 with a similar switch that controls MO-3071 (trip and throttle valve). This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 17. Plant Desian Change 83-030 The spent fuel pool capacity was insufficient to provide adequate storage of spent fuel until a permanent offsite depository becomes available.
l Plant Design Change 83-030 provided for replacement of storago racks with high-density neutron absorbing spent fuel storage racks. i Removal of the cooling water system diffusion header was included in this work. This modification involved a change to the Trojan Technical Specifications and was approved by Amendment 88, dated June 8, 1984 (LCA 94).
- 18. Plant Design Chante 83-042 NRC letter dated July 8,1983, " Required Actions Based on the i Generic Implications of Salem Anticipated Transients without Scram (ATWS) Event", requested that reactor trip system reliability be
( improved by actuating the shunt trip coil from the automatic reactor protection system. Plant Design Change 83-042 installed the Westinghouse recommended reactor trip breaker automatic shunt trip. t This modification did not involve a change to the Trojan Technical l Specifications or an unreviewed safety question. O 102 I i L
- 19. Plant Design Change 84-009 Plant Design Change 84-009 addressed problems with spurious signals to the main turbine electrohydraulic control (EHC) panel. Included are nodifications associated with the turbino high vibration trip circuitry.
Plant Design Change 84-009 installed a 2- to 5-second time delay in the circuitry to provent spurious signals from tripping the turbino. This modification did not involve a change to the Trojan Technical Specifications or an uncoviewed safety question.
- 20. Plant Design Change 84-013 Inspection of the Service Water Lubrications Water System revealed that the upstream separator was plugged with river clams.
Plant Design Change 84-013 installed larger pump impollars in the lubricating water system pumps (P-180A and B) and added recirculation lines in order to increase the flow through the separators which will prevent the clam larva from attaching to low flow surfaces. This modification did not involvo a change to the Trojan Technical Specifications or an unreviewed safety question.
- 21. Plant Design Change 84-019 The transient time for the condensato conductivity element was too long to aid in the prevention of steam genorator contamination from a condensor tube leak.
Plant Design Change 84-019 made the local cation resin column and conductivity element temporarily installed by Work Order 8033 permanent. The existing raw water conductivity elements woro removed and the associated recorder utilized for the cation conductivity readings. This modification did not involvo a change to the Trojan Technical Specifications or an unroviewed safety question.
- 22. Plant Design Chanan 84-022 A number of circuits required for sofo shutdown following a Plant fire, shared fuses or brookers with other circuito como required and some not required for safe shutdown. This resulted in the potential for sofo shutdown circuit failure resulting from fire damage to associated circuits.
Plant Design Chango 84-022 provided isolation / protection for the affected circuits. O 103
/T This modification did not involve a change to the Trojan Technical
() Specifications or an unroviewed safety question.
- 23. Plant Design Change 84-023 The Appendix R. Associated Circuit Study, identified a number of cables that were not sized to withstand the overload or fault currents allowed by their protective devices.
Plant Design Change 84-023 decreased the breaker size and added additional fusing to provido protection to the affected circuits. This modification did not involve a change to the Trojan Technical Specifications or an uncoviewed safety question.
- 24. Plant Design change 84-026 The fan chiller motors that are required for cooling of the Emergency Coro Cooling System (ECCS) pump motors woro not environmentally qualified for the completo post-accident operation duration or were marginally qualified and had a very weak caso for material traceability.
Plant Design Chango 84-026 replaced eight oxisting sofoty-related fan cooler motors and installed run-hour maters on each one. ('~ This modification did not involvo a change to the Trojan Technical ( Specifications or an uncoviewed safety question.
- 25. Plant Declan Chanen 84-028 There was no permanently installed flow measuremont device on the neutralizing tank (T-126) dischargo pipo. Accurato flow measurement is needed while performing scheduled Plant dischargos.
Plant Design Change 84-028 installed a flow meter in the cuction piping to Pumps 129A and B. This modification did not involvo a change to the Trojan Technical Specifications or an unroviewed safety question.
- 26. Plant Donlan Channo 84-041 The narrow-rango Reactor Coolant System (RCS) pressuro indication availabio to the operator on panel C-19 did not provido required inf ormation.
Plant Design Chango 84-041 removed the narrow-range indication and provided a wide-rango RCS pressure indicator. This modification did not involvo a chango to the Trojan Technical Specifications or an unroviewed safety quostion, n v 104
- 27. Plant Design Change 84-046 The Containment high-range radiation and wide-rango pressure monitors had scales that increase from right to left, which is contrary to population stereotypes as identified by the Detailed Centrol Room Design Review (DCRDR).
Plant Design Change 84-046 modified the monitor scales so that they increase from left to right. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 28. Plant Design Channo 84-049 The control room received nuisance alarms from the high-level switches on the emergency diesel generator fuel oil day tank. This was due to:
- 1. Overlap of alarm and control setpoints.
- 2. Closing time of motor-operated valves in the fuel oil transfer system.
- 3. Setpoint drif t and dead band associated with level in:truments.
Plant Design Change 84-049 modified the level transmitters and changed the fuel oil transfer pump control logic to stop the pump when the fuel transfer valvos are no longer full open. This modification did not involvo a chango to the Trojan Technical Specifications or an unreviewed safety question.
- 29. Plant Dosinn Change 84-050 NRC IE Information Notico 84-013 identified a lack of indication of tripped motor overloads that preclude timely detection of motor failure. This situation existed for most Trojan motor circuits.
Plant Design Chango 84 050 altered the control circuit wiring such that all position indication will be lost if the overloads are tripped. This modification did not involvo a chango to the Trojan Technical Spoeifications or an unroviewed safety question.
- 30. Plant Denign Chango 84-058 Component cooling water motor operators for valvec HO-3293, HO-3341, and H0-3294 were found to not bo environmentally qualified.
O 105
,A Plant Design Change 84-058 replaced the operator and motor on MO-3293 and MO-3347 and the motor only on MO-3294 with qualified units. ' This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 31. Plant Design Change 84-064 The north condenser hot well level instrumentation read 10-in. to 12-in. too low due to being located u o close to the condensato pump suction.
Plant Design Change 84-064 moved the lower tap farther from the condensato pump suction and installed additional instrument taps at required locations. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 32. Plant Design Change 84-068 The RHR, SI, centrifugal charging (CC), and Containment Spray (CS) pump motor lead terminations were terminated with Scotch 3M tape, which is only environmentally qualified to Division Operating Reactors (DOR) Culdelines, and has a quallfled life of 11 years.
Plant Design Change 84-068 replaced the motor lead terminations with replacements qualified to 10 CFR 50.49 standards. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 33. Plant Desian Chante 84-080 Admiralty brass tubes in low-prossure feedwater Heaters 3 and 4 were contributing toward the influx of corrosion products into the etnam generator.
Plant Design Chango 84-080 replaced the heaters with new heators tubed with Type 304 stainless stool. 1 This modification did not involvo a change to the Trojan Technical Specifications or an unroviewed safety question.
- 34. Plant Design change 84-083 As identified by the Fire Area Boundary Deviation and Rosolution Summary of the 10 CFR 50 Appendix R review, installation of a permanent 3-hr fire-rated cover on the Auxiliary Building 45-f t hoistway was required.
O 106
Plant Design Change 84-083 installed the required cover. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 35. Plant Design Change 84-092 Pressurizer level indication did not comply with Regulatory Guide 1.97 design criteria.
Plant Design Change 84-092 replaced the control room recorder and indicator with seismically qualified equivalents, changed the recorder power supply to a preferred source and isolated indication signals from non-Class 1E circuits. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 36. Plant Design Change 84-095 The pressure transmitters and motor-operated outlet isolation valves for the accumulators were not environmentally qualified per Regulatory Guide 1.97.
Plant Design Change 84-095 replaced one accumulator pressure transmitter per accumulator with an environmentally qualified equivalent transmitter. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 37. Plant Design change 84-100 The Appendix R review identified a number of redundant safe shutdown circuits in the same fire area.
Plant Design Change 84-100 involved the relocation of cables such that the affected cables were protected from radiant energy or routed through different fire areas. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 38. Plant Design change 84-101 Numerous control room indicators were not seismically qualified,by Regulatory Guide 1.97.
Plant Design Change 84-101 replaced 27 specified control room indicators with seismically qualified equivalents. O 107
This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 39. Plant Design Change 84-105 The Auxiliary Feedwater (AFW) inlet line flow indicating switches, relays, and trip reset push buttons were not qualified for operation in the potentially harsh Main Steam Support Structure (MSSS) environment.
Plant Design Change 84-105 replaced the unqualified components with environmentally qualified equivalents and relocated the relays and push buttons to a mild environment. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 40. Plant Design Change 84-106 The main steam isolation valves were subject to closure from spurious signals.
Plant Design Change 84-106 added a time delay relay to the main steam isolation signal circuitry in order to minimize spurious actuation. A time delay relay set for 0.5 seconds was added to the output of each train's logic circuitry. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 41. Plant Design Change 84-108 AFW pump turbine steam inlet valve position switches (ZS 145A-D),
AFW flow transmitters (FT-3043E-H), and main steam pressure transmitters (PT-515, 525, 535, 545) were installed in a qualified manner. Plant Design Change 84-108 replaced four terminal blocks with environmentally qualified terminal blocks and installed qualified conduit seals on the AFW flow and main steam pressure transmitters. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed cafety question.
- 42. Plant Design Change 84-110 The Oregon Department of Energy (ODOE) requested an upgrade of the Trojan telemetry system.
Plant Design Change 84-110 provided telemetry for Process Radiation Monitoro (PPMc)-2, -6; Area Radiation Monitors (ARMS)-15A, 23 in lieu of current channels. Pursuant to a subsequent request from the ODOE, the inpute to the tolemetry system were disconnected. 108
This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 43. Plant Design Change 84-115 The generator load megawatt meter was unreliable and inaccurate in the O to 200 megawatt range. This problem made the operator reluctant to use it for startup purposes.
Plant Design Change 84-115 replaced the analog meter with a new digital meter. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 44. Plant Design Change 84-118 LER 84-14 describes an event at Trojan that was a result of a high-pressure fitting failure at the incore instrument seal table.
Similar failures have also occurred at other nuclear plants. Plant Design Change 84-118 provided a new seal configuration for the seal table. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 45. Plant Design Change 85-006 The oil supply for a feedwater isolation valve (Whitakers) frequently did not meet cleanliness specifications. Leads had to be lifted on the pump control circuit to allow constant recirculation and filtration of the oil.
Plant Design Change 85-006 modified the pump control circuit wiring to allow the pump to run continuously when required. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 46. Plant Decign Change 85-018 Trojan's decouple switch circuit design precluded fire-induced circuit damage which could have prevented local control of certain safe shutdown equipment after decouple operation. However, a fire in various locations may have induced a control circuit fault that would blow the protecting fuse before decouple operation.
Plant Design Change 85-018 installed secondary fuses in the decouple switch circuitry for the B emergency dicael generator and the B and D service water booster pumps. O 109 i L
(N This modification did not involve a change to the Trojan Technical (_,) Specifications or an unreviewed safety question.
- 47. Plant Design Change 85-020 Adequate circuit coordination did not exist in buses D20 tnd D30, as required by 10 CFR 50, Appendix R, common power supply re uirements.
Plant Design Change 85-020 installed the fuses necessary to provide circuit coordination on buses D20 and D30. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 48. Plant Design Change 85-027 The 10 CFR 50 Appendix R Associated Circuits Review identified various circuits which lacked protection from an overload condition.
Plant Design Change 85-027 provided overload protection and replaced undersized cables to the identified circuits. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 49. Plant Design Change 85-031 The gravel surfaced lower parking lot at Trojan required extensive maintenance (approximately $5000 yearly). The same condition existed for the warehouse access road and receiving area.
Plant Design Change 85-031 provided an asphalt surface for the affected areas. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 50. Plant Design Change 85-500 The water pretreatment plant caustic storage tank (T-123) heater could not be operated as previously installed.
Plant Design Change 85-500 installed an additional relay per the manufacturer's recommendation which allows the heater to operate as designed. This modification did not involve a change to the Trojan Technical 2 Specifications or an unreviewed safety question.
- 51. Plant Design Change 85-507 Letdown line area radiation monitor RE6119 was located in an area r IN that is difficult to access for maintenance and calibration.
l l 110
Plant Design Change 85-507 relocated the detector to a new position approximately 8 f t east of its previous location. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 52. Plant Design Change 85-508 A potential existed for accidental overexposure due to lack of a personnel radiation barrier at Elevation 57 ft, O in, leading to the RHR pipe chase.
Plant Design Change 85-508 provided a grating at Elevation 57 ft, O in. to restrict access to the RHR pipe chase. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 53. Plant Design Change 85-509 A personnel hazard existed due to the installation of a temporary hose required to blowdown the Circulating Water System sample line strainers.
Plant Design Change 85-509 installed a permanent hard piped drain line not susceptible to whip or being blown off the piping connection. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 54. Plant Design Change 85-513 The heater drain tank pump low suction pressure trip instrument tubing tap was not located at the optimum location to protect the pump from low suction pressure operation.
Plant Design Change 85-513 relocated the instrument tubing to downstream of the suction valve. This modification did not involve a change to the Trojan Technical l Specifications or an unreviewed cafety question.
- 55. Plant Design Change 85-515 Dynamic transients were observed on the electric AFW pump recirculation piping during low flow conditions.
Plant Design Change 85-515 provided an additional pipe restraint to reduce the dynamic transients. O 111
~5 g This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 56. Plant Design Change 85-520 Previous design changes installed a new method of acid injection to the Circulating Water System but did not provide freeze protection.
Plant Design Change 85-520 installed blind flanges on the acid injection connections to the circulating water piping to eliminate the possibility of freezing in the line. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 57. Plant Design Change 85-523 The original alarm on the circulating water pump pit eyewash and shower station was not removed when an airhorn alarm system was installed.
Plant Design Change 85-523 removed the original light and alarm. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 58. Plant Design Change 85-526 In its previous location, the startup boiler chemical feed system blocked access to the boiler water storage tank level controls.
Plant Design Change 85-526 relocated the mixing tank and chemical additional pump to a more convenient location. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 59. Plant Design Change 85-528 Power supply breaker coordination problems existed for the main and unit auxiliary transformer cooling system which could have resulted in a single fault tripping the entire bank of cooling.
Plant Design Change 85-528 replaced power supply breakers as required to provide a selective tripping feature to the associated circuits. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. I O 112
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- 60. Plant Design Change 85-529 A hose and cable routing pathway was required through the 45 ft Containment access anteroom in order to eliminate a personnel safety hazard.
Plant Design Change 85-529 was used to provide for as-building of work which was completed per Temporary Modification 85-35. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 61. Plant Design Change 85-535 The personnel barriers in the electrical penetration area were classified as Seismic Category II/I and therefore must meet FSAR l Section 3.7 criteria.
Plant Design Change 85-535 upgraded the structure to meet Seismic Category II/I requirements. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 62. Plant Design Change 85-538 The process steam receiver tank pump, P-106, was not running most of the time, which caused a high conductivity alarm in the control room due to dissolved CO2 on the suction of the pump.
Plant Design Change 85-538 interlocked the alarm and the pump such that the alarm will not come in unless the pump is running. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 63. Plant Design Change 85-539 No indication existed to alert the control operator of contaminated water from the condenser hotwells being rejected to the CST. This had contributed to contaminating the CST with resin and circulating water.
Plant Design Change 85-539 relocated the condensate conductivity sample taps from their previous location to a point close to the discharge of the condensate pumps. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 113 l i I
s 64. Plant Design Change 85-540 t The double doors located in the control room vestibule served no useful purpose and constituted a personnel hazard. Plant Design Change 85-540 removed the double doors (Door 73). This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 65. Plant Design Change 85-542 The triax cables coming out of the incore flux detector drive units were exposed to traffic and were susceptible to damage as well as being a tripping hazard.
Plant Design Change 85-542 installed guards around the cables to protect them from damage. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 66. Plant Design Channe 85-549 The waste gas compressors occasionally induct water from the waste gas surge tank. This occurs when water level in the tank exceeds the level of the tank discharge nozzle.
Plant Design Change 85-549 interlocks the tank level switch with the compressor controls such that the compressor will not start, and will trip on a high tank level. l This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 67. Plant Design Change 85-556 No means existed to test the low pressure start on the standby lube oil pumps for the main feedwater pumps.
Plant Design Change 85-556 rewired the main feedwater pump lube oil pump control switches to allow testing and auto start of the standby lube oil pumps. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 68. Plant Design Change 85-562 The Westinghouse acoustic monitoring system for the steam generator feedwater inlet nozzles was ineffective and not used by operations.
O 114
Plant Design Change 85-562 disconnected and spared out all cables; abandoned panel C63 and all in-Containment components in place; and removed the control room display on panel C06. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 69. Plant Design Change 85-563 The emergency diesel generator air compressce starting crank did not have a designated storage location and was therefore difficult to locate at times.
Plant Design Change 85-563 provided a storage bracket located near the air compressor. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 70. Plant Design Change 86-017 The Trojan discharge diffuser pipe was struck by a commercial vessel on April 11, 1986, damaging a large section of piping and related supports.
Plant Design Change 86-017 replaced the damaged section of pipe and related supports as needed. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 71. Plant Design Change 86-511 A malfunctioning pressure switch in the condensato demineralizer system resulted in feedwater oscillations and Plant trip.
Plant Design Change 86-511 provided two new pressure switches - one switch for each of the two functions originally provided by the previous switch. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l l 72. Plant Design Change 86-520 The carbon steel pipe spool on the discharge of the bearing cooling water heat exchanger discharge was leaking and clamped to reduce leakage. Plant Design Change 86-520 replaced the Icaking spool piece with an equivalent sized stainless steel pipe spool. O 115
n ( This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 73. Plant Design Change 86-524 The bearing cooling water heat exchangers were experiencing a higher than expected corrosion rate.
Plant Design Change 86-524 added a sacrificial anode to the divider plate to reduce corrosion. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 74. Plant Design Change 86-536 Air leaks in the control room walls affected the capability to maintain a positive pressure in the control room as required by Standard Technical Specification (STS) 3/4.7.6.
Plant Design Change 86-536 constructed a wall partition above Door 68 and repaired a partiticn in the west wall. 7 This rodification did not involve a change to the Trojan Technical - cs Specifications or an unreviewed safety question. p kj 116
i g 5.B LICENSE AMENDMENTS In 1986, a total of 14 license amendments were issued by the NRC. Fifteen requests for license amendments [ License Change Applications (LCAs)] were submitted to the NRC for approval and five resulted in license amendments. Of 18 LCAs previously submitted, one was cancelled, and 10 received NRC 1 approval and have been issued. As of December 31, 1986, 15 LCAs had not yet been acted upon by the NRC. i
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73 TABLE 5.B-1 Sheet 1 of 8 AMENDMENTS TO THE TROJAN OPERATING LICENSE ISSUED IN 1986 For the following amendments, the NRC has 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 the amendment will not be inimical to the common defense and security or the health and safety of the public. Amendment Number Date Subject 109 02/10/86 This amendment clarified the definition of OPERABLE as used in the Trojan Technical Specifications. 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 f- 3 in connection with issuance of this amendment.
-' 110 03/03/86 Issuance of this amendment provided Technical Speci-(1) a revision of the fication Improvements by:
Surveillance Requirements for Axial Flux Difference, (2) deletion of the ACTION statement associated with the reportability of out-of-specification Reactor Coolant System (RCS) chemistry in accordance with the revised Licensee Event Report (LER) rule of 10 CFR 50.72 and 50.73, (3) a change to the fire pump diesel engine Surveillance Requirement, (4) a correction of inconsistencies in the Technical Specifications Design Features for the RCS volume, (5) a clarification of the identity of the low population zone in the Design Features, and (6) the inclusion of minor editorial corrections. l Portions of this amendment related to changes in recordkeeping, reporting, or administrative proce-dures or requirements. Accordingly, such portions of this amendment meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Other portions of this amendment relate to changes in surveillance requirements. These portions involve changes in the installation or use of a facility component located within the restricted area as defined in n) ( 10 CFR Part 20. The NRC has determined that the ! 118 l 1 -
TABLE 5.B-1 Sheet 2 of 8 Amendment Number Date Subject amendment involves no significant increase in the amounts, and no significant 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 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 categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR Section 51.22(b), no environ-mental impact statement or environmental assessment was required in connection with the issuance of the amendment. 111 03/04/86 This amendment was issued to provide clarification to the Surveillance Requirement for the Containment Ventilation Isolation System (CVIS) by identifying which of the Containment radiation monitoring channels must be included in system operability E verifications. This amendment involved a change in surveillance requirements. The NRC has determined that the amendment involved no significant 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 cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards 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 was required in connec-tion with issuance of this amendment. 112 03/10/86 This amendment incorporates Limiting Conditions for Operation and Surveillance Requirements for TMI-related items pursuant to NRC model Technical Specifications issued in Generic Letter 83-37. These additions include core exit thermocouples (CET) and Reactor Vessel Instrument System (RVLIS) in accordance with NUREG-0737. Item II.F.2. 119 K - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . - - - - - - - _ _ __________ _ _____ _
f\ b TABLE 5.B-1 Sheet 3 of 8 Amendment Number Date Subject 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 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 issuance of this amendment.
/\ 113 03/11/86 This amendment reflected changes made to the PCE ~- Nuclear Division Organization in that both the onsite and offsite (headquarters) Quality Assurance groups now report to the Manager, Nuclear Quality Assurance.
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.
114 03/12/86 Issuance of this amendment provided a number of improvements to the Trojan Technical Specifica-tions. Changes included: (1) a clarification of the reactor coolant pump (RCP) undervoltage trip setpoint and allowable value; (2) the addition of a reference to boration system rather than a single tank; (3) the elimination of possible confusion regarding rod position indication system channels; (4) an increased monitoring frequency of Axial Flux Difference (AFD) during inoperability; (5) a clari-fication of Component Cooling Water (CCW) and Service Water System (SWS) operability requirements; i ('d) and (6) various minor editorial corrections. I 120
TABLE 5.B-1 Sheet 4 of 8 Amendment Number Date Subject 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, changes in surveillance requirements and a change in administrative requirements. The NRC has determined that the amendment involves no significant 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 cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has bc..) 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. 115 05/29/86 This amendment was issued to revise the Technical Specification Limiting conditions for Operation for
" Movable Control Assemblies" with regard to electrical inoperability of control rods and provide more distinct ACTION statements consistent with the significance of the specific malfunction.
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 I be released offsite, and that there would be no I significant increase in individual or cumulative occupational radiation exposure. The Commission has l previously issued a proposed finding that this amendment involves no significant hazards considera-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). 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. l l 121 l l
r"' TABLE 5.B-1 Sheet 5 of 8 k Amendment Number Date Subiect 116 06/09/86 This amendment authorized the deletion of the fuel rod weight limit from Section 5.3.1 of the Trojan Technical Specifications. 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 l occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards considera-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). Pursuant to (,) (N 10 CFR 51.22(b), no environmental impact statement or environmental assessment needed to be prepared in connection with issuance of this amendment. 117 06/20/86 Issuance of this amendment revised the containment Spray System spray additive tank flow rate i Surveillance Requirement. This amendment involved a change in surveillance requirements and involved no significant hazards considerations. The NRC has determined that the amendment involves no significant 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 cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards 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 l 10 CFR 51.22(b), no environmental impact statement i or environmental assessment needed to be prepared in connection with issuance of this amendment. i . 122 1
TABLE 5.B-1 Sheet 6 of 8 Amendment Number Date Subject 118 07/25/86 This amendmert authorized revision of the reporting requirements related to the Action Statements in the Limiting Condition for Operation for primary coolant specific activity levels in accordance with guidance provided in NRC Ceneric Letter 85-19. portions of this amendment related to change in recordkeeping, reporting, or administrative proce-dures or requiremen's. Accordingly, such portions of this amendment meet eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Other portions of this amendment involve changes 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 significant 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 consideration and there has been no public comment on such finding. Accordingly, thi? amendment meets the eligibility criteria for categarical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmenta'. impact statement or environmental assessment needed to be prepared in connection with issuance of this amendment. 119 07/28/86 This amendment authorized the deletion of the Action Statement for Technical Specification Limiting Condition for Operation 3.4.10.1.d. The change ensures that in the event RCS structural integrity is degraded, structural integrity will be restored in lieu of performing an evaluation. 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 123
TABLE 5.B-1 Sheet 7 of 8 V[' 'i Amendment Number Date Subject previously issued a proposed finding that this amendment involves no significant hazards considera-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). 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. 120 09/30/86 This amendment clarified the title of Trojan Techni-cal Specification Limiting condition for Operation and Surveillance Requirement 3/4.7.5 and bases by specifying that the Trojan ultimate heat sink is the Columbia River with the cooling tower serving as the backup. This amendment related to changes in recordkeeping, reporting, or administrative procedores or require-
, I) ments. The Commission has previously published a k- / proposed finding that the amendment involves no significant hazards 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)(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. 121 10/29/86 This amendment authorized the addition of " fail-to-start" to the group of emergency diesel generator trips which are not automatically bypassed upon loss of voltage on the emergency bus and/or a safety injection actuation signal for Technical Specification Survell-lance Requirement 4.8.1.1.2.c.3.c). This amendment involved a change in a surveillance requirement. The NRC has determined that the amendment involves no significant 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 cumulative occupational radiation exposure. The Commission has previously published a proposed finding that the amend-ment involves no significant hazards consideration and l there has been no public comment on such finding. i 124 l
e TABLE 5.B-1 Sheet 8 of 8 Amendment Number Date Subject Accordingly, the amendment meets the eligibility cri-teria 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. 122 12/16/86 Issuance of this amendment revised Technical Specifica-tion Limiting conditions for Operation and Surveillance Requirements 3/4.4.1.1 and 3/4.4.1.2 with respect to the number of reactor coolant loops required to be in operation at low power and in Mode 3. A new surveil-Lance requirement was also added regarding control rod drive mechanisms. 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 signifi-cant increase in the amounts, and no significant change in the types, of any effluents that may be released g W 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 consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categori-cal exclusion set forth in 10 CFR 51.22(c)(9). 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. O 125
TABLE 5.B-2 Sheet 1 of 4 STATUS OF LICENSE CHANGE APPLICATIONS SUBMITTED TO AND UNDERGOING REVIEW BY THE NRC AS OF DECEMBER 31, 1986 LCA Date Number Submitted Subject and Status 117 01/30/85 Reactor Trip and ESFAS Instrumentation: Revises operability and testing requirements for the Reactor Trip System and Engineered Safety Feature Actuation System (ESFAS). Revision 1 of this LCA was sent to the NRC on September 23, 1985. Revision 2 of LCA 117, submitted to the NRC on July 3, 1986, reflected the following changes from the previous submittal: (1) withdraws proposed changes to the ESFAS which would have changed the Channel Functional Test from monthly to quarterly and increased the allowed outage time for ESFAS channels, (2) incorporates additional Westinghouse Owners Group and NRC guidance for proposed changes associated with WCAP-10271, and (3) expands the Significant Hazards Consideration consistent with (- s) discussions with the NRC to apply the "three factor test" for each proposed change. PGE letters of August 22, 1986 and October 17, 1986 provided additional clarification and agreed-upon changes to this LCA. 124 07/29/85 Containment Isolation Provisions and Leakage Rate Testing: Revises Containment leakage rate testing. Several changes are also included to the table listing Containment isolation valves. PCE letter of December 22, 1986 provided revised pages, submitted to expedite NRC review and appaoval. 126 08/16/85 Exclusion From LCO 3.0.4: Provides more operational flexibility by allowing entry into operational modes with selected equipment out-of-service. PGE letter of December 19, 1986 withdrew the portion of thic LCA regarding Reactor Coolant System (RCS) leakage, hydrogen analyzers, hydrogen recombiners, O hydrogen vent system and hydrogen mixing system. 126
l TABLE 5.B-2 Sheet 2 of 4 f LCA Date Number Submitted Subject and Status 127 09/30/85 CCW System Valve Surveillance: Revises surveillance requirements for Component Cooling Water System (CCW) valves to include specified signals for automatic valve closure, a change consistent with recommendations of NRC Ceneric Letter 83-10d. PCE letters of March 5, 1986 and December 12, 1986 provided clarification and final agreed-upon revision to this LCA. 128 09/10/85 Onsite Electrical Distribution Systems: Revises the operability requirements for onsite AC and DC electrical power distribution systems. 130 09/13/85 Revision to Technical Specification 6.8 Procedures: Reflects a more efficient manner for review and approval of Plant procedures by allowing administra-tive policies and procedures to be established, h implemented and maintained in accordance with the Nuclear Quality Assurance Program. This change is intended to reduce the emphasis placed on nonsig-nificant safety issues, therefore, enabling the Plant Review Board and Ceneral Manager to provide more thorough reviews of safety-related activities. Revision 1 of this LCA was submitted on August 7, 1986 to incorporate NRC comments. This revision added a new Technical Specification regarding Technical Review and Control. PGE letter of December 31, 1986 provided page corrections for this LCA pursuant to previous discussion with NRC staff members. 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) for operabili'.y of the Auxiliary Feodwater System in accordance with NRC letter of September 13, 1985. Revision 1 of this LCA is scheduled for submittal to the NRC in January, 1987. This revision will remove the provision for an interim water level to be main-tained during modifications to the Auxiliary 127
TABLE 5.B-2 Sheet 3 of 4 LCA Date Number Submitted Subject and Status Feedwater System and incorporate a final revised minimum level. 135 01/31/86 Hiscellaneous Technical Specification Corrections: Makes miscellaneous corrections to Technical Specifications 4.0.2, 4.4.6.1, 3.4.9.3, and Table 3.6-1. All changes are administrative in nature and make editorial improvements. PCE letter of May 16, 1986 forwarded pages of this LCA revised in accordance with discussions with NRC staff members. 137 02/18/86 Pressurizer Spray Differential Temperature Limit: Revises the maximum pressurizer spray water temperature differential. PCE letter of December 29, 1986 provided written O response to NRC questions regarding material properties of the pressurizer and the effects of postulated transients. 141 07/17/86 ECCS Pumps Required Discharge Pressure on Recirc Flow: Requests minor changes to the Surveillance Require-ments for ECCS pumps to reflect that differential pressures across the pumps must be measured vice discharge pressures to determine operability. (Amendment to be issued in January 1987.) 142 09/30/86 Control Room Habitability: Requests modifications regarding control room habit ability by proposing changes to (1) Chlorine Detection Systems, (2) SO2 Detection Systems, and (3) Control Room Emergency Votatilation System. 144 10/17/86 Mode Related Containment Isolation Valve Testing: Revises Trojan Technical Specifications to allow stroke-testing of selected Containment isolation valves in operating modes other than cold shutdown or refueling. 1: 8 (
TABLE 5.B-2 Sheet 4 of 4 LCA Date Number Submitted Subject and StatAs 145 10/28/86 Barton Transmitter Setpoint Changes: Requests changes to reflect the current setpoints for Barton transmitters replaced during the 1986 outage. The specific setpoints that were changed are the steam generator low-low level and pressurizer low-pressure reactor trip. 146 10/31/86 Rod Insertion Limits: Revises Trojan Technical Specifications 3.1.3.4,
" Shutdown Rod Insertion Limit", and 3.1.3.5,
" Control Rod Insertion Limit", to define fully withdrawn rods as >225 steps instead of 228 steps.
pCE letter of December 8, 1986 responded to NRC questions by submitting a change to the Significant Hazards Consideration for this LCA to quantify the reduction in excess shutdown margin expected by inserting all control rods to 226 steps. 147 10/31/86 Reactor Vessel Material Irradiation Surveillance Schedule: In order to maintain compliance with NRC regula-tions, changes are proposed to revise the reactor vessel material irradiation surveillance schedulo and address new 10 CFR 50, Appendix C, pressure-temperature limits. O 129
l 5.C LICENSING DOCUMENT CHANGE REQUESTS (LDCRs) APPROVED DURING 1986 Licensing Documents consist of various PGE Topical Reports and the Trojan Updated FSAR. Under 10 CFR 50.54 and 50.59, changes are permitted to these documents if a change to the Operating License or Technical Specifications does not result, if an unreviewed safety question is not created, or if there is no degradation of Plant security, decrease in effectiveness of the Emergency Plan, or reduction to the commitments in the QA Program description. The following is a summary of the Licensing Document Change Requests approved in 1986.
- 1. LDCR 85-08 Document: Trojan Radiological Emergency Plan and Procedures Manual. PGE-1008 Status: Approved December 30, 1985 and issued March 24, 1986 as Amendment 7 to Chapters 1 and 2.
Safety Evaluation: The changes clarified and revised the information presented in the Trojan Radiological Emergency Plan. The Emergency Plan is not referenced in the fV ') Technical Specifications, except for the annual audit of the Plan required by the TNOB; therefore, 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, commitments, or cri-teria. The effectiveness of the Emergency Plan was not decreased and remains consistent with the standards of 10 CFR 50.47, 10 CFR 50, Appendix E. NUREG-0654, and Regulatory Guide 1.101, Revision 2.
- 2. LDCR 85-10 Document: Detailed Control Room Design Review (DCRDR) Summary Report, PGE-1041 Status: Approved January 9, 1986 and issued March 4, 1986 ac Volume 3 (Human Factors Design Input and Review Program)
Safety Evaluation: This LDCR was initiated to incorporate lessons learned in the Detailed Control Room Design Review. Volume 3 of this Topical Report details human factors conventions at the Trojan Nuclear Plant. O 130
This Topical Report was developed to help individual Nuclear Division managers, supervisors, and other employees to incorporate human factors criteria into the design and operational activition of the Trojan Nuclear Plant. The purpose of this document is to establish the controls and guidance for the review and evaluation of modifications, additions, and deletions to work-space, instrumentation, controls, procedures and other equipment from a human factors engineering point of view, and documentation of those reviews and evaluations. This LDCR is in compliance with the Trojan Technical Specifications. There are no unreviewed safety or environmental questions as a result of this LDCR.
- 3. LDCR 85-12 Document: Regulatory Guide Policy Manual (RCPM), PCE-1028 Status: Approved February 27, 1986 and issued March 7, 1986 as Amendment 4.
Safety Evaluation: The Regulatory Guide Policy Manual (RCPM) estab-lishes PCE's position on NRC Regulatory Guides which affect the operation, maintenance, refueling, and modifications of the Trojan Nuclear Plant. The changes to the RCPM incorporated subsequent comments as well as reflected In-Mouse Positions (IHPs) for new or revised Regulatory Culdes. The Safety Evalu-ation and the IHPs were written based on full com-pliance with the Trojan Technical Specifications. Any conflicts were identified as exceptions to the Regulatory Guides; therefore, no changes to the Technical Specifications were necessary. This LDCR has been determined to involve no unreviewed safety questions or environmental matters and did not have an effect on any other licensing documents, commitments, or criteria. l 4. LDCR 85-14 Document: Trojan Nuclear Plant Fire Protection Plan, PCE-1012
- Status
- Approved May 5, 1986 and issued May 29, 1986 as l Amendment 2.
l Safety Evaluation: This LDCR initiated a complete update of the May i 1983 version of PCE-1012 " Trojan Nuclear Plant Fire Protection Program", to eliminate conflicts, improve readability and format, and develop a matrix that addrescos regulations, commitments, and implementing 131
o O procedures. The content of Volume I (Program Description) was revised to reflect the current state of fire protection systems design. This amendment also notes the addition of a Volume II (10 CFR Appendix R Review). PGE-1012 serves as the fire protection plan for Trojan as referenced in Section 9.5.1 of the FSAR and is updated in accordance with requirements of 10 CFR 50.48(a) and 10 CFR 50.71(e).
- 5. LDCR 85-15 Document: Trojan Nuclear Plant Security Plan, PCE-1017 Status: Approved February 17, 1986 and issued February 28, 1986 as Revision 12.
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.
- 6. L,CR Q 86-02 Document: Trojan Radiological Emergency Plan and ?rocedures
- Manual. PGE-1008 l Status: Approved January 17, 1986 and issued August 29, 1986 j as Amendment 8 to Chapters 3 and 7.
l ! Safety Evaluation: Changes cons 1:sted of clarifleation and revision of ! the informat Dn presented in the Trojan Radiological ! Emergency Plan. The Emergency Plan is not refer- ! enced in the Technical Specifications, except for , the annual audit of the Plan required by the TNOB; i therefore, the Technical Specifications were not ! affected by this LDCR. The changes involvo no j unreviewed safety or environmental questions and did not affect any other licensing documents, commit-j ments, or criteria. The effectiveness of the ! Emergency Plan was not decreased and remains j consistent with the standards of 10 CFR 50.47(b). j 7. L.QC,R 86-03 Document: Evacuation Analysis Report for the Trojan Nuclear l Plant, PGE-1034 i Status: Approved January 27, 1986 and issued l February 28, 1986 as Amendment 2. lO 132
Safety Evaluation: This LDCR was initiated to: (1) change a reference to a figure in PGE-1008 (deleted by Amendment 7 of that document) to reference an identical figure in the Trojan Updated FSAR, and (2) delete any specific method that the U. S. Coast Guard would make notifications to boaters.
- 8. LDCR 86-04 Document: Updated Final Safety Analysis Report, UFSAR Status: Approved January 17, 1986 and issued as part of Amendment 4 to the Updated FSAR on July 1, 1986 Safety Evaluation: This LDCR was initiated to modify the exchange frequency for routine personnel radiation dosimeters (TLDs) from monthly to quarterly. This did not result in a change to the Technical Specifications nor did it create an unreviewed safety or environ-mental question.
- 9. LDCR 86-05 Document: Inservice Testing Program for Pumps and Valves, PGE-1022 Status: Approved August 15, 1986 and issued September 17, 1986 as Amendment 3.
Safety Evaluation: This LDCR involved a general revision to PCE-1022 to bring Trojan into conformance with ASME Code requirements or to satisfy exemptions allowed by the Code. Changes associated with the boron injection tank valves were evaluated and approved in the issuance of Trojan Operating License Amendment 103, dated March 4, 1985. All testing requirements mandated by the NRC up to and including the Safety Evaluation for inservice testing (IST) dated March 14, 1984 were incorpo-rated. PGE letter of May 18, 1984 committing to individually leak test Valves MO-8701 and MO-8702 (NRC concurrence letter dated June 5, 1984). The remaining changes were either editorial or were clarifications to improve and correct the description of the IST program. O 133
Based on the above evaluation of these changes, an [~'} - unreviewed safety question was not involved. ( ,j
- 10. LDCR 86-06 Document: Regulatory Guide Policy Manual (RCPM), PCE-1028 Status: Approved March 13, 1986 and issued March 18, 1986 as Amendment 5.
Safety Evaluation: The Regulatory Guide Policy Manual (RCPM) estab-lishes PCE's position on NRC Regulatory Guidos which affect the operation, maintenance, refueling, and modifications of the Trojan Nuclear Plant. The changes to the RCPM incorporate subsequent comments as well as reflect In-House Positions (IHPs) for new or revised Tegulatory Guides. This Safety Evalua-tion and the INPs are written based on full compli-ance with the Trojan Technical Specifications. Any conflicts were identified as exceptions to the Regulatory Guides; therefore, no changes to the Technical Specifications were necessary. This LDCR has been determined to involve no unreviewed safety questions or environmental matters and does not have an effect on any other licensing documents, commitments, or criteria. This amendment to the RGPM was issued to incorporate Revision 1 to Regulatory Guide 1.89. The revised IHP for this Reg. Guide references PCE-1025,
, Environmental Qualification Program Manual for the i Trojan Nuclear Plant, which describes the qualifica-tion program established to comply with new NRC i regulation (10 CFR 50.49) and associated guidance Regulatory Guide 1.89, Revision 1.
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- 11. LDCR 86-07 Document: Updated Final Safety Analysis Report, UFSAR Status: Due to the volume of changes involved, LDCR 86-07 l was divided into ten individual change requests to provide approval by chapter and/or section. The
- last change request was approved June 13, 1986 and Amendment 4 to the Updated FSAR was issued July 1, 1986.
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1 l i l l Safety Evaluation: Pursuant to 10 CFR 50. 71(c), 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 Specifications or any unreviewed safety or environ-mental questions. Any changes made in the facility, procedures, tests, or analyses as described in the original FSAR have received prior NRC approval pursuant to 10 CFR 50.59(c) and 50.90, or were effected without NRC approval based on a separate safety / environmental evaluation pursuant to 10 CFR 50.59(a), or were required by NRC request pursuant to 10 CFR 50.54(f) or (h).
- 12. LDCR 86-08 Document: Security Force Training and Qualification Plan, FGE-1024 Status: Approved April 24, 1986 and issued May 19, 1986 as Revision 5.
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.
- 13. LDCR 86-09 Document: PGE Nuclear Quality Assurance Program, PCE-8010 Status: Approved September 11, 1986 and issued October 1, 1986 as Revision 11.
Safety Evaluation: This revision represented resolution of results of the Annual Program Review and was administrative in nature. It did not lessen the review and approval authority for quality-related activities, nor pro-vide any relaxation of the QA Program or administra-tive controls such that any impact on accident occurrence probability, accident consequences, environmental considerations, or plant safety margins could occur. Since these changes were not equipment-related, no new accidents could be created. No weakening of the Operations Phase QA Program commitments previously made for safety-related components would occur. Therefore, no unroviewed safety questions resulted from this change. O 135
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- 14. LDCE 86-10 Document: Trojan Nuclear Plant Security Plan, PCI-1017 Status: Approved June 13, 1986 and issued June 19, 1986 as Revision 13.
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.
- 15. LRCE 86-11 Document: Trojan Radiological Emergency Plan and Procedures Manual, PGE-1008 Status: Approved September 24, 1986 and issued November 4, 1986 as Amendment 9.
Safety Evaluation: This amendment reflected revision of the RERP Exercise Schedule in accordance with FEMA guidance memorandum PR-1, dated October 1, 1985, which changed guidance on timing of off-hours exercises. The new guidance does not change the number of exercises, only the time of initiation changes. '
- 16. LRCE 86-12 Document: Updated Final Safety Analysis Report, UFSAR I
l Status: Approved September 10, 1986 and issued September 30, l 1986 as Amendment 5. i I Safety Evaluation: The annual update to the FSAR was submitted as i Amendment 4 (July 1, 1986). In that amendment, numerour changes were made to the description of l control room habitability. Because the schedule for l submittal of the annual update to the FSAR coincided with numerous changes occurring to the design, operation, testing, and analysis of CB-1, not all of the FSAR changes were included in the annual update. The remaining changes to the description of control i room habitability were initiated by this LDCR. With one exception, the changes were either adminis- !4 trative or were applications of new or revised analyses which are within the acceptance criteria of the SRp. The exception, tornado adssile protection of the CB-1 intake pipes, was addressed in the revision to FSAR Section 3.3. 136
Changes in this LDCR which are related to the Technical Specifications are addressed in LCA 142 (submitted September 30, 1986).
- 17. LDCR 86-13 Document: Radiation Protection Program, PGE-8005 Status: Approved October 15, 1986 and issued December 1, 1986 as Revision 4.
Safety Evaluation: This LDCR was initiated to reflect various Company organizational changes as well as provide a general update of current practices / requirements. All
- changes made to this Topical Report were considered administrative in nature and have no effect on the Trojan Operating License and Technical Specifica-tions, nor do they involve any uncoviewed safety or environmental questions.
- 18. LDCR 86-15 Document: Trojan Nuclear Plant Inservice Testing Program for Pumps and Valves, Second Ten-Year Interval, PGE-1048 Status: Approved August 15, 1986 and issued October 1, 1986 as a new document.
Safety Evaluation: This Topical Report describes the second ten-year interval for Inservice Testing for Pumps and Valves at Trojan. PGE-1048 was written to implement the requirements of the 1983 edition, summer 1983 addenda ASME Code Section XI. The previous 10-year a program (PCE-1022, Amendment 3) reflected the requirements of the 1980 edition, winter 1980 addenda, ASME Code Section XI. Only minor clerical changes were made from the 1980 edition to the 1983 edition of the Code. The program content has changed very little. Relief, which was granted by the NRC for specific Code requirements, expired May 20, 1986. These relief requests were reviewed, updated, and submitted for the second ten-year i interval through May 20, 1996 in the body of the i topical report. 1 0 137 l
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- 19. LDCR 86-16
(~'N Document: Operating Experience Review Program, PCE-1044 Status: Approved October 23, 1986 and issued November 21, 1986 as Amendment 1. Safety Evaluation: Revised Program to incorporate recent changes in NDP 100-13 and NDP 600-3. The primary change was to clarify responsibility for in-house experience review with Plant in accordance with NDP 600-3. Minor changes in OERP administra-tion with some format changes.
- 20. LDCR 86-17 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved November 7, 1986 and issued November 18, 1986 as Revision 14.
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 l not affected.
- 21. LDCR 86-18 Document: Nuclear Division Headquarters Training Program, PGE-8009 Status: Approved November 10, 1986 and issued December 2, 1986 as Amendment 3.
Safety Evaluation: This amendment incorporated editorial and adminis-trative changes to the Nuclear Division Headquarters Training Program (NDHTP) manual that accurately reflect the manner in which the training is con-ducted to improve rather than degrade training effectiveness.
- 22. LDCR 86-19 Document: Inservice Inspection Program for the Second 10-year Interval, PGE-1049 I ,, Status: Approved November 10, 1986 and issued December 19, 1986 ac a new document.
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! Safety Evaluation: Federal regulations require the Inservice Inspection Program at Trojan be updated every 10 years to is incorporate changes which have occurred in the ASME i Boiler and Pressure Vessel Code and which have been endorsed by the NRC. PCE-1049 contains the Inservice Inspection Program for the second 10-year interval which is based on the 1983 Edition with Summer 1983 Addenda of Section XI of the ASME Code.
This Topical Report for the second 10-year Inservice Inspection Program describes the examination and testing requirements for Class 1, 2 and 3 components and component supports at the Trojan Nuclear Plant. Changes to the Inservice Testing Program description in the FSAR are administrative in nature. The new 2 program .s based on a more current ASME Code which has been endorsed by the NRC.
- 23. LDCR 86-22 Document: Trojan Nuclear Plant Security Plan, PCE-1017 Status: Approved December 15, 1986 and issued December 19, 1986 as a Proposed Revision in response to 10 CFR 73 Rule Changes.
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 [ t l l l
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5.D PLANT TESTS { The following Plant tests were performed in 1986 and are reported in accordance with 10 CFR 50.59.
- 1. Temporary Plant Test 35 Temporary Plant Test 35 was performed to troubleshoot the main generator exciter power stabilizer. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 2. Temporary Plant Test 78 Temporary Plant Test 78 was performed to verify the proper operation of the differential pressure switch installed around the condensate demineralizer vessel inlet valves. This switch has been installed to prevent the vessel inlet valve ("A" valve) from opening with a high differential pressure across its seat. This will prevent large hydraulic shocks to the vessel. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 3. Temporary Plant Test 113 Temporary Plant Test 113 was performed to ensure the proper s functioning of a newly installed automatic gas analyzer. Func-tional testing of equipment related to the modification was also performed. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 4. Temporary Plant Test 118 Temporary Plant Test 118 was performed to document all Clacc 2 l hydrostatic testing required by ASME Section XI, 1974 edition,
! including the summer 1975 amendment. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 5. Temporary Plant Test 139 Temporary Plant Test 139 was performed to verify that the new feedwater recirculation flow control modifications operated as l desired. In addition, this test evaluated the effectiveness of l these modifications in alleviating extreme vibration and dynamic l
load problems. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 6. Temporary Plant Test 147 i
Temporary Plant Test 147 was completed to verify that the process O radiation monitor (PRM)-6 moisture removal system added will function as designed af ter it has been adjusted under dynamic 140 l
operating conditions, to adjust service water flow to E-509, steam . jet air ejector (SJAE) after condenser, to 24 gpm and to verify that all service water interlocks function per design. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 7. Temporary Plant Test 152 Temporary Plant Test 152 has been initiated to demonstrate the acceptability of LED type indicator lamps for use in control panel valve, pump, and breaker indication circuitry. This test shall span approximately 24 months. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 8. Temporary Plant Test 153 Temporary Plant Test 153 was performed to ensure that the steam-driven auxiliary feedwater pump drain condenser catchpot water temperature remains below an acceptable temperature without overflowing. This test also verified service water flow rates required by drain condensers. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 9. Temporary Plant Test 155 Temporary Plant Test 155 was performed to obtain data to develop the pump and motor curves for the "C" Train service water (SW) pump with the new 29-5/16-in stainless steel impeller which replaces the 29-in bronze impeller. Additionally, this test verified that the start (acceleration) time of the pump (SW - auto start conditions) conforms to Final Safety Analysis Report (FSAR) requirements, and determined the baseline data for service water inservice tests.
This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 10. Temporary Plant Test 156 Temporary Plant Test 156 was performed to functionally check the smoke generator installed in the electrical penetration area. The smoke generator has been installed to test out fire detectors. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 11. Temporary Plant Test 158 Temporary Plant Test 158 was performed to test the reset of the "B" l
Train AFW control valves (CV-3004 series) to the proper throttled position at power. This test simulated the AFW pump / steam pressure AP that is normally seen at 0-percent power when the valve positions are set at 100 psid between pump discharge and the main steam line. The valves thereby were properly throttled to provide adequate flow to each steam generator and still prevent a low suction pressure trip when both pumps auto start. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications. 141
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- 12. Temporary Plant Test 159 V)
Temporary Plant Test 159 was performed to reset the "A" Train AFW control valves. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 13. Temporary Plant Test 161 Temporary Plant Test 161 was performed to obtain data on the thermal performance of the component cooling water (CCW) heat exchangers and the hydraulic performance on the service water (SW) side of the heat exchangers. The data was used to determine if required SW flow to the CCW heat exchanger can be reduced. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 14. Temporary Plant Test 162 Temporary Plant Test 162 was performed to obtain data for the development of pump curves of the diesel fuel oil transfer pumps.
This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 15. Temporary Plant Test 164 Temporary Plant Test 164 was performed to functionally test the
- 1evel control system on the fifth, sixth, and seventh feedwater
(~'} x_ / heaters to aid in the determination of replacing any or all of the level control systems. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 16. Temporary Plant Test 165 Temporary Plant Test 165 was performed to functionally test portable recirculation systems which were procured to provide suitable layup conditions for feedwater heaters. This test did not involve an l unreviewed safety question nor a change to the Trojan Technical Specifications.
- 17. Temporary Plant Test 166 Temporary Plant Test 106 was performed to verify the proper movement and expansion of the Reactor Coolant System (RCS) and its components, including the steam generator hydraulic snubbers, to ensure unrestricted expansion and adequate hot clearances at the seismic and pipe whip restraints. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 18. Temporary Plant Test 168 Temporary Plant Test 168 was performed to functionally test electrical and instrumentation modifications made during the 1986 N -] outage to the Auxiliary Feedwater System. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
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- 19. Temporary Plant Test 169 Temporary Plant Test 169 was performed to test CB-1 in its emergency made which is designed to maintain the control room at 1/8-in, w.g.
relative to all control room boundaries with an outside makeup flow of no greater than 450 cfm. This test also verified unfiltered leakage into CB-1 was no greater than 10 cfm and measured control room pressure during simulated CB-1 and actual CB-1 operation during a toxic gas release. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 20. Temporary Plant Test 170 Temporary Plant Test 170 was performed to verify the flow rate of water being educted from the sodium hydroxide tank to the Containment Spray System while the pumps are operating on mini-recirculation back to the refueling water storage tank (RWST).
This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 21. Temporary Plant Test 171 Temporary Plant Test 171 was performed to verify safety injection pump discharge to the RCS cold legs following completion and modifications to the Kerotest 8822 series valves in accordance with Trojan Technical Specification Surveillance Requirement 4.5.2.f.2.
This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 22. Temporary Plant Test 172 Temporary Plant Test 172 was performed to monitor various signals in the speed control circuit of the steam and diesel-driven AFW pumps on recirculation and full flow. The objective was to identify the cause of pump discharge pressure oscillations. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 23. Temporary Plant Test 173 Temporary Plant Test 173 was performed to verify and balance safety injection pump discharge to the RCS hot legs following completion of i
modifications to the Kerotest 8816 series valves in accordance with Trojan Technical Specification Surveillance Requirement 4.5.2.g.2. This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 24. Temporary Plant Test 175 Temporary Plant Test 175 was started to ensure that the RCS is not experiencing any undue restraint to thermal expansion or contraction during heatup, initial power operation, and cooldown. This test 1
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! will span five heatups or cooldowns (whichever comes sooner). This test did not involve an unreviewed safety question nor a change to the Trojan Technical Specifications.
- 25. Temporary Plant Test 176 Temporary Plant Test 176 was performed to acquire pressure, flow, and temperature data on steam generator blowdown lines for steam generator blowdown system modifications. This test did not involve an unreviewed safety question nor a change to the Trojan Technical specifications.
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5.E CHANCES TO PROCEDURES \J 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 1986, the following organizations made changes to 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 Division Nuclear Safety & Regulation Nuclear Plant Engineering Nuclear Quality Assurance Fuel Operations Purchasing and Materials Management Changes to procedures were generally either administrative or technical in nature. Administrative changes consisted of title, organizational, and editorial changes, while technical changes were the result of system or component modifications, license amendments, or improvements in procedural processes. A safety evaluation was conducted for each change, in accordance with 10 CFR 50.59, and was reviewed and approved by the appropriate personnel. b 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. ( 145
i 5.F. SETPOINT CHANCES cm The following setpoint changes were made in 1986 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:
- 1. Plant Setpoint Change 86-01 The water treatment plant acid storage tank level was being j maintained below the Lo level alarm setpoint.
Plant Setpoint Change 86-01 changed the tank Lo level alarm setpoint from 30 percent to 14.2 percent.
- 2. Plant Setpoint change 86-02 The auto-start setpoints for the electric- and diesel-driven fire l
pumps overlapped such that they occasionally started at the same time rather than sequentially on decreasing fire main pressure. Plant Setpoint Change 86-02 adjusted the diesel fire pump auto start from 108 psig and decreasing to 106 psig and decreasing.
- 3. Plant Setpoint Change 86-03 l RDC 83-051 changed the system lineup putting the boron injection
. tank under charging pump head of approximately 2420 psig. This resulted in spurious nuisance alarms. Plant Setpoint Change 86-03 adjusted the alarm setpoint from 2400 psig to 2520 pois. This will alert the operator when pressure increases 100 poig above normal. ! 4. Plant Setpoint change 86-04 g The present power range rate trips were set more conservatively than 3 allowed by the Standard Technical Specification (STS) safety
- analyses and had resulted in an unnecessary reactor trip.
J Plant Setpoint Change 86-04' adjusted the power range rate trip setpoints to reduce the potential for Plant trips.
- 5. Plant Setpoint Change 86-05 l
The setpointo for the waste gas compressor moisture separator liquid level pot were set such that the watcr level could not be visually ! verified by use of the installed sight glass. Plant Setpoint Change 86-05 lowered the setpoint at which the valve opens and raises the icvel at which it closes, to ensure the switch operation is within the limits of the sight glass. 146
- 6. Plant Setroint Chante 86-06 The Plant BTU discharge alarm was set at a value too far below the required limit, which imparted unnecessary restrictions on thermal discharges.
Plant Setpoint Change 86-06 adjusted the BTU alarm from 70 to 76 million BTU /Hr.
- 7. Plant Setpoint Chante 86-07 The present Power Range Rate Trips were set more conservatively then allowed by the STS and had resulted in unnecessary reactor trips.
Plant Setpoint Change 86-07 adjusted the Power Range Rate Trips to a value closer to the maximum allowed by the STS, thus reducing the potential for Plant trips at rates of change within the design of the Plant.
- 8. Plant Setpoint Chante 86-09 The pressurizer pressure safety injection setpoint had been previously raised to account for inaccuracies associated with Westinghouse /Barton Lot 2 and Lot 4 transmitters.
Plant Setpoint Change 86-09 reduced the pressurizer pressure safety injection setpoint from 1835 psig to 1766 psig due to replacement of the affected transmitters.
- 9. Plant Setpoint Change 86-10 Steam generator water level trip setpoints had been previously raised 4 percont to account for inaccuracies associated with Westinghouse /Barton Lot 2 and Lot 4 transmitters.
Plant Setpoint Change 86-10 reduced the steam generator level trip setpoint from 15 percent to 11 percent due to replacement of the affected transmitters.
- 10. Plant Setpoint Chante 86-13 Reduced Reactor Coolant System (RCS) flow as measured by Periodic Engineering Test (PET)-7-4, required a change of the Loop A low flow bistable setpoints.
Plant Setpoint Change 86-13 increased the low ficw trip setpoint from 92.5 percent to 94.5 percent flow.
- 11. Plant Setpoint change 86-14 The reactor coolant loop Tavg imbalance for Cycle 9 was running routinely near the present setpoint.
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Plant Setpoint Change 86-14 increased the Tavg deviation alarm from b 3.5 degrees to 4.5 degrees to inform the control operator of a change from normal operating conditions.
- 13. Flypt Setpoint Change 86-15
'Abe previous mechanical overspeed trip setpoint for the turbine-driven auxiliary feedwater (AFW) pump resulted in excessive pressures at the discharge of the pump.
Plant Setpoint Change 86-15 decreased the mechanical overspeed trip setpoint from 5700 rpm to 5500 rpm to decrease the likelihood of overpressurizing the pump discharge piping. O O 148
1 W W MbytHW David W. Cockfield Vice President, Nuclear l February 27, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555
Dear Sir:
Annual Report Enclosed is a copy of Portland Conoral Electric Company's Annual Report for the Trojan Nuclear Plant for the calendar year 1986. Sincoroly, Enclosure
- c. Mr. David Kish, Acting Director State of Oregon (2)
Department of Energy Mr. John B. Martin Regional Administrator, Region V (1) U.S. Nuclear Regulatory Commission Mr. R. C. Bare NRC Resident Inspector (1) Trojan Nuclear Plant t i,1 l } // '.',l ' f( n ( b y 4 Ppr, tryj Ors 4 p_ f! O fj'M}}