ML20235V639
| ML20235V639 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/31/1988 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| References | |
| PGE-1015-88, NUDOCS 8903100264 | |
| Download: ML20235V639 (183) | |
Text
{{#Wiki_filter:an Nuclear ant ANNUAL REPORT OF TROJAN NUCLEAR PLANT FOR 1988 PORTLAND GENERAL ELECTRIC COMPANY PGE 1015-88 y;S3Ts0 $!'Ehk^c' g gt sagt;P42 g! 4 s\'
PCE 1015-88 ANNUAL REPORT OF TROJAN NUCLEAR PLANT FOR 1988 Docket 50-344 License NPF-1 PORTLAND GENERAL ELECTRIC COMPANY 121 S. W. Salmon Street Portland, Oregon 97204 O
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' i INTRODUCTION. ... .:. . . . . . . . . . . . . . . . . .. . . . . i.
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.1., Radioactive Effluent Release Report-, . . . . . . . . . . . . 1 Ir T'. A. Effluent and Waste Disposal Report. . .. . . . . . . . . . . 3 B. Offsite Radiation Doses . . . . . . . . 1
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dp C. Meteorological Data . . . . . . . . . . . . . . . . . . . 82-Changes td the Offsite Dose Calculation D. C Manual (ODCM) . . . . . . . . . . . . . . . . . . . . . . 83
'E. Reactor Coolant' System (RCS) Specific Activity. . . . . . 112 j ' ,' F. . Temporary Solid Radwaste Storage Area Report. . . . . . . 113 n-
- 2. Annual Personne1' Exposure and Monitoring Report . . . . . . . 11A
[.-- -[9-ss. Vi : ' Steam Generator Tube Inspections and Maintenance. '118-
- 3. . . . . . .
- 4. Relief Valve Challenges . . . .'. . . .. . . . . . . . . . 128-L- 5. ' Emergency Core Cooling System Performance , , . . . . . . . . 129
- 6. Changes Tests, and Experiments . . . . . . . . . . . . . . . 130 A. Plant Modifications and Design Changes. . . . . . . . . . 131 l-[1 t, q i, .
r i B. License Amendments. . . . . . . . . . . . . . . . . . . 149 C. Licensing Document Change Requests (LDCRs Approved During 1988) . . . . . . . . . . . . . . . . . . 163. D. Plant Tests . . . .. . . .. . . . . . . . . . . . . . . 172 g v, ' E. Changes'to Procedures . . . . . . . . . . . . . . . . . . 180 3-. F. Setpoint Changes. . . . . . . . . . . . . . . . . . . . . 181
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[ INTRODUCTION
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The Annual Report of the Trojan Nuclear Plant for 1988 is 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 reports are included for ease of reference and completeness.
SUMMARY
OF OPERATING EXPERIENCE IN 1988
'I The Trojan Nuclear Plant began the year operating at full power. On )
January 8, 1988, the reactor tripped due to a failed component in one of the overpower delta temperature (OPDT) channels. The component failed while another OPDT channel was in test thus satisfying the reactor protection logic requirements for a reactor trip. The failed component was replaced and all channels of OPDT returned to service. During this shutdown period, steam leaks were found on the 'B' and 'D' ) steam ~ generator secondary-side manways. These leaks and a leak in the component cooling water (CCW) supply to one of the Containment air coolers were repaired before startup on' January 13. The Plant experienced two load rejections on February 28 due to tripping I' of a 500-Kv intertie. Power was promptly returned to 100 percent. ( The 'B' centrifugal charging pump (CCP) developed a significant leak through its mechanical shaft seal on April S. The pump was removed from service, isolated to stop the leak, repaired and returned to service on April 7. A turbine runback on April 7 reduced power to 72 percent. The runback l was caused by loss of the generator stator cooling pumps due to loss of their electrical power. Power was restored to 100 percent. . On April 12, 1988, power reduction for the 1988 refueling shutdown was begun. , i Significant outage activities were as follows:
- Fuel unloading was completed on May 1 and an inspection of the reactor internals and reactor vessel for stray fuel pellets was preformed. No pellets were found. Refueling of the reactor was completed on May 13, 1988.
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- Work to install a new remote shutdown panel was completed.
- A new control room chiller system was installed.
- Damage to containment electrical cables was discovered in the.
vicinity of the reactor coolant pumps (RCPs). The damaged cables l were exposed to hot air from the RCP motor exhaust.+ The. worst i areas were near.the 'C' and 'D' pumps where several cable trays are located. The high temperatures caused the outer layer of insulation to become brittle.
- During inspection of the pressurizer surge line, the surge line piping was found to be in contact with a pipe whip restraint.
Evaluation of this finding led to performance of non-destructive examination of surge-line piping welds. Indications were found in welds on the surge-line elbow just below the pressurizer. The piping elbow containing these welds was removed and replaced. Subsequent examination of these welds revealed no cracks exis-ted. Pipe whip restraints on the surge line were modified to obtain the maximum permissible gap. Temperature detectors and motion detectors were installed to monitor the surge line during heatup and power operations and determine the significance of thermal stratifications.
- Large-bore pipe hanger and pipe whip restraint modifications were performed as part of the long-term large-bore Pipe Support Design Verification Program.
All outage work was completed and Plant heatup began on July 3, 1988. A final test to verify that the Plant can be maintained in hot standby and then cooled 50*F from the newly installed remote shutdown station was successfully performed during the Plant heatup. On July 10, the reactor achieved criticality. On July 11, low-power physics testing was completed, Mode 1 was entered and the Plant attained 100-percent power. On July 27, power was reduced to 50 percent for repair of an electrical ground on the 'A' feedwater regulating valve solenoid. On August 16 a reactor trip occurred on an RCS loop 'B' low-flow signal. At the time, reactor coolant loop 'B' flow transmitter FT-424 was out-of-service for calibration with its low-flow bistable tripped. Venting FT-424 caused a transient on a second loop 'B' flow transmitter, FT-425, which shares a common high-pressure pensing line. This caused the second transmitter to sense a loss of flow and trip its low-flow bistable. This satisfied the logic for a reactor trip on loop low-flow. All of the Plant's safety systems functioned as expected. The Plant returned to 100-percent power on August 17. O 11
On September 16, the reactor tripped on over-temperature delta tempera- . ture (OTDT). The bistable feeding OTDT for pressure transmitter PT-458 was tripped due to the PT-458 failure. While preparing to replace this ! transmitter, an Instrumentation and Control (I&C) Technician tripped the corresponding bistable for Pm 455, completing the two-out-of-four logic for OTDT reactor trip. The Plant remained in shutdown status while the following were resolved: a) Service water check valve (SW-2025) failure b) 'B' safety injection (SI) to RCS check-valve leak c) Pressurizer pressure and level transmitter discrepancies d) North main feed pump bearing / turning gear discrepancy e) Locked valves out of position f) Clams found in coolers and piping in the Service Water System Startup was begun on September 22 and the Plant returned to 100-rercent power on September 24. On September 24 a tube leak was detected on the 'A' train of the con-denser. Power was reduced to 55 percent to take the 'A' train of circu-lating water out-of-service. One leaking tube was plugged along with 18 others as a preventative measure. On October 16, a power reduction was begun in preparation for circulating water leak repairs. Power reached 57 percent and the 'A' circulating O water train was isolated and drained. The leak was found in 'A' condenser and was the result of leaking plugs installed earlier this cycle. The plus vendor had provided incorrect information on how to tighten the plugs; the ones that were installed loosened and began to leak. The plugs were correctly tightened and the Plant returned to 100-percent power. The Plant tripped on November 13 due to a failure of a feedwater regula-ting valve controller. This caused the valve to go fully open and resulted in a steam generator high water level trip. The cause of the failure was the power supply. Following the trip, a safety injection check-valve leak and a leak at the 'C' RCP flange were repaired prior to startup. On November 18, an extensive program of reconstitution and repair of fuel elements was begun and continued throughout December. This effort was slightly more than half completed at the end of the year. For the week ending December 20, the Plant established a record for the best (lowest) heat rate in Plant history. O iii
7; _____________-.______, l The monthly and overall Maximum Dependable capacity factors for the year are as follows: Maximum Dependable Month Capacity Factor January 82.3 February 101.0 . March 100.9 April 39.0 May -0.3 June -0.4 July 58.9 August 97.9 September 71.2 October 99.6 November 40.9 December 98.5 OVERALL 65.9 9 O' iv
- - _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________ __ ________ _________ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,
I T 1. RADIOACTIVE EFFLUENT RELEASE REPORT Rectilrement Trojan Facility Operating License NPF-1, Appendix A, Technical Specifica-tions 6.9.1.5.3 and 6.9.1.5.4, " Semiannual Radioactive Effluent Release Report", require:
" Routine Radioactive Effluent Release Reports covering the operation
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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 quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Culde 1.21 (Rev. 1), ' Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous 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 sunmary of the meteorological O data is not included in the radioactive 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 i making these assessments (e.g., specific activity, exposure time and j location) shall be included in these reports. j "The Radioactive Effluent Release Reports shall include a copy of all ,
licensee event reports required by Specification 3.11.1.1 and i 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, l The meteorological conditions concurrent with the releases of efflu- I ents shall be used for determining the gaseous pathway doses. The i 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 O
Manual (ODCM) made during the reporting period, as provided in Speci-fications 6.13 and 6.14". I I
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-ll Bevort Complete data for the year 1988 have been included, although the data for the first six months (January through June) have been previously reported.
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T 1.A EFFLUENT AND WASTE DISPOSAL REPORT (O
This section contains a summary of the liquid and gaseous release limits; a list 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 classified by path-way, gaseous or liquid, and type, continuous or batch; and a summary of solid radioactive waste shipments. This section represents all releases during the period January 1, 1988 through December 31, 1988. ata for January 1, 1988 through June 30, 1988 have been previously reported. The "ND" notation used in the following data tables indicates that no detectable activity was found when samples were analyzed using counting techniques which ensure compliance with the " Lower Limit of Detection" (LLD) values of Technical Specification Tables 4.11-1, " Radioactive Liquid Waste Sampling and Analysis Program", and 4.11-2, " Radioactive Caseous Waste Sampling and Analysis Program". The referenced "LLD" specifications are not used as limiting values for reporting activity; all measurable activity is reported. For gamma-emitting isotopes, all isotopes with measurable activity, together with those isotopes specified in Technical Specification Tables 4.11-1 and 4.11-2 are reported. In February 1988, it was discovered that Process Radiation Monitor (PRM)-2, the Auxiliary Building Vent Exhaust Monitor, might not receive representative effluent samples under all flow configurations. ('"% Modifications to the Auxiliary Building ductwork had been performed \_,) between October 1987 and January 1988. Immediate corrective actions were to (1) move the sampling probe further downstream, (2) develop conservative correction factore for the monitor based on testing, (3) restrict flow configurations known to cause non-representative samples, and (4) add extensions to the vent collection header and to the waste gas discharge header to produce a more uniform concentration across the duct. An effort is also under way to redesign the PRM-2 sampling probe. An investigation was initiated to determine if PRM-1 had a similar problem. A review of the 1988 effluent data shows that corrected releases from the Auxiliary Building vent exhaust account for 45 percent of the radio- l iodines and particulate with greater than 8-day half-lives and 52 per-cent of the radioactive noble gases. During 1988 gaseous releases were , less than 10 percent of Technical Specification limits and resulted in offsite doses of less than 2 percent of the Technical Specification design objective. On September 30, 1988, with the Plant at 100 percent power in Mode 1, the Plant received an engineering report evaluating tests which had been performed assessing the ability of PRM-1, Containment Monitoring System, to obtain a representative sample of exhausts through the Containment ventilation exhaust duct. The report indicated that PRM-1 will obtain a representative sample when the Containment purge exhaust system is operated (flow approximately 50,000 cfm) but that PRM-1 may not obtain a (Q_/ representative sample when using the hydrogen vent system (flow approximately 140 cfm). 3 l
l Immediate corrective action was to install a temporary modification for the sample probe for PRM-1 to sample directly from the "A" Train hydrogen vent duct. On a longer term basis, the design of the PRM-1 sampling system will be reviewed and modified as necessary to assure representa-tive sampling. The measurement error by PRM-1 during Containment pressure venting opera-tions through the hydrogen vent system was evaluated to determine its effect on overall Plant releases. A review of the data from the pressure venting operations before and after the temporary modification indicates that the PRM-1 readings may have been as much as 15 percent lower than the actual releases. However, the Containment pressure venting releases only account for approximately 24 percent of the total gaseous activity released. Therefore, a 15 percent error would have only had a 3.6 per-cent effect on the total gaseous activity released. As a result, the potential errors in the data would not have had a significant effect on the overall releases from the Plant and would have been within the previously reported estimated error. In addition, no Technical Specifi-cation release limits were exceeded, and there was not a significant impact on offsite doses. The following terms are used: Ey = Average total body dose factor due to gamma emissions, Ly = Average skin dose factor due to beta emissions, Ey = Average air dose factor due to beta emissions, Ey - Average air dose factor due to gamma emissions. R1 = Average dose factor for nuclides other than noble gases at the controlling exposure locations. 1 I i 1 9 4
TABLE 1.A-1 [~~}
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SUPPLEMENTAL INFORMATION i January 1, 1988 through June 30, 1988 REGULATORY LIMITS First Second Fission and Activation Gas Release Rate Limits Unit Quarter Quarter
- 1. Tech Spec 3.11.2.1(a), Instantaneous QTv < 1 Ci/sec 1.32E-1 1.66E-1 2.0 K y QTv < 1 Ci/sec 3.43E-1 4.16E-1 0.33 (Ly + 1.1 N y)
- 2. Tech Spec 3.11.2.2, Quarterly Average
/ QTv < 1 Ci/sec 4.55E-3 5.54E-3
(.)\ _ 50 N y QTv < 1 Ci/sec 3.64E-3 3.85E-3 25 M y
- 3. Tech Spec 3.11.2.4(1), Quarterly Average Requiring Use of the Gaseous Radwaste Treatment System QTv < 1 Ci/sec 2.27E-3 2.77E-3 100 N y I QTv < 1 Ci/sec 1.82E-3 1.92E-3 50 M y
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b TABLE 1.A-2 SUPPLEMENTAL INFORMATION l January 1, 1988 through June 30, 1988 REGULATORY LIMITS Gaseous Iodine 131. Tritium, and Particulate First Second With > 8 Day T1/2 Limits Unit Quarter Quarter
- 1. Tech Spec 3.11.2.1(b), instantaneous QTv < 1 Ci/sec 4.06E-2 2.30E-2
.67 Ri
- 2. Tech Spec 3.11.2.3, Quarterly Average QTV < 1 Ci/sec 2.72E-4 1.54E-4 100 Ri
- 3. Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Ventilation Exhaust Treatment System QTv < 1 Ci/see 1.36E-4 7.69E-5 200 Ri O
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TABLE 1. A-3 (v) SUPPLEMENTAL INFORMATION January 1, 1988 through June 30, 1988 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/mi total activity. ,
Tech Spec 3.11.1.2 Gross release limit of 2.5 Ci per 2. Quarterly Average quarter excluding tritium and dissolved noble gases. If this limit
,,- s is exceeded, cumulative dose due to i
-' ') liquid effluents will be limited to 1.5 mrem to the whole body and to 2.5 mrem to any organ, using isotope specific methodology in the plant offsite dose calculation manual (ODCM).
- 3. Tech Spec 3.11.1.3 The liquid radwaste treatment system Quarterly Average Requiring shall be maintained and used when Use of the Liquid Radwaste activity discharged (excluding tritium I Treatment System and dissolved noble gas) would exceed 1.25 Ci/Qtr.
- 4. Tech Spec 3.11.1.4 Tne quantity of radioactive material
' Temporary Storage Tank contained in temporary radwaste storage l
Activity Limit tanks is limited to i 10 Ci excluding tritium and dissolved noble gases. l l l l
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I l TABLE 1.A-4 1 SUPPLEMENTAL INFORMATION January 1, 1988 through June 30, 1988 i MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid (10 CFR 20, Appendix B Table II, Col. 2) MPC MFC Isotope (uci/ce) Isotope (uci/ce) j Fluorine 18 8 x 10-4 Iodine 131 3 x 10-7 'j Chromium 51 2 x 10-3 Iodine 132 8 x 10-6 i 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 10-0 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 Molybdenum ')9 4 x 10-5 Unidentified 3 x 20-8 Technetium 99m 3 x 10-3 Tritium 3 x 10-3 Ruthenium 103 8 x 10-5 Krypton 85m 2 x 10-4 Ruthenium 106 1 x 10-5 Krypton 87 2 x 10-4 Silver 110m 3 x 10-5 Krypton 88 2 x 10-4 Tin 113 8 x 10-5 Xenon 131m 2 x 10-4 Antimony 124 2 x 10-5 Xenon 133 2 x 10-4 Antimony 125 1 x 10-4 Xenon 133m 2 x 10-4 Antimony 127 3 x 10-6 Xenon 135 2 x 10-4 4 Xenon 135m 2 x 10-4 Caseous caseous MPCs are not used in calculating technical specifications at Trojan. O 8
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TABLE 1.A-5 LJ SUPPLEMENTAL INFORMATION January 1, 1988 through June 30, 1988 AVERAGE ENERGY Effluent release limits are not based upon E, hence, reporting E is not ' required. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Gaseous Releases Fission and Activation Gases: Gamma spectrometric analysis of gaseous grab samples define radionuclides distribution at least monthly on monitored gaseous release points. Using the known nuclide distributions and process radiation monitor readings, the actual quantities of gaseous releases are calculated. Iodines and Particulate: Weekly composite filter and iodine s cartridge samples are analyzed by gamma spectroscopy to determine the concentration of particulate and iodine isotopas. Weekly composite {' -- } samples are analyzed for 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 composi , samples and counted using liquid scintillation spectroscopy. Liquid Releases ! Fission and Activation Products: Gamma spectrometric analysis of each batch is performed. Weekly composite samples are maintained for continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations. Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques. Dissolved and Entrained Gases: Gaseous isotopes are determined by garna spectrometric analysis of each batch and on a minimum frequency of once per month for continuous releases.
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TABLE 1.A-6 SUPPLEMENTAL INFORMATION January 1, 1988 through June 30, 1988 BATCH RELEASES Unit Liquid Gaseous Number of Batch Releases 29 91' Total time period for Batch Releases Hours 128.2 2364.2 Maximum time period for Batch Releases Hours 21.8 221.8 Average time period for Batch Releases Hours 4.4 26.0. Minimum time period for Batch Releases Hours 0.1 0.8 AveraSo dilution flow during Batch Releases GPM 28370 NA ABNORMAL RLEASES Number of Abnormal Releases 0 2 Total Activity Released Ci NA 6.32E0 O l O l 10 1 m.... . . . , _ . . _ _ . _ _ . . _ . _ _ _ . ._
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,r-Y I i TABLE 1.A-7 Sheet 1 of 2
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i GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES l January 1, 1988 through June 30,' 1988 First. Second Estimated' FISSION AND ACTIVATION GASES Unit Quarter Quarter Error (%) Total Activity Released Ci' 6.13EF1 1.45E+2 13.5El Average Release Rate for Quarter pCi/sec 7.80E0 1.84E+1 Percent of Limit: Tech. Spec. 3.11.2.1 (a) - 9.30E-3 8.13E-2 Instantaneous Tech Spec. 3.11.2.2 - 2.12E-T 4.74E-1 Quarterly Average Tech. Spec. 3.11.2.4.(1) - 4.25E-1 .9.49E-1 Quarterly Average Requiring Processing IODINE 131 Total Iodine 131 Released Ci 8.00E-5 7.51E-4 13.5El Average Release Rate for Quarter pCi/sec 3.02E-5 9.55E-5 PARTICULATE Total with Half-lives > 8 days Ci 2.93E-7 1.74E-4 13.5El Average Release Rate for Quarter pCi/sec 3.72E-8 2.22E-5 Total Gross Alpha Released Ci 1.76E-7 1.58E-8 TRITIUM Total Released Ci 6.56E0 1.91E+1 13.0E1 Average Release Rate for Qua'rter pCi/sec 8.34E-1 2.43E0 0 11
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TABLE 1.A-7 Sheet 2 of 2 IODINE 131 PARTICULATE WITH First Second Estimated
> 8 DAY T1/2 AND TRITIUM Unit Ouarter Quarter Error (%)
Total Released Ci 6.56E0 1.91E+1 13.5El Average Release Rate for Quarter pCi/sec 8.34E-1 2.43E0 Percent of Limit: Tech. Spec. 3.11.2.1 (b) 2.49E-3 3.84E-2 Instantaneous Tech. Spec. 3.11.2.3 3.08E-1 1.58E0 l Quarterly Average Tech, Spec. 3.11.2.4(2) 6.16E-1 3.17E0 Quarterly Average Requiring Processing O\ O 12
/Y TABLE 1.A-8 Sheet 1 of 2
.. t GASEOUS EFFLUENTS GROUND LEVEL RELEASES January 1, 1988 through June 30, 1988 NUCLIDES RELEASED Continuous Mode Batch Mode' Unit 1st Quarter 2nd Quarter 1st Quarter ,2nd Quarter
. FISSION CASES Krypton 85m Ci 9.45E-2 2.29E-3 .1.87E-1 7.79E Krypton 85 Ci ND ND 6.73E-1 1.06EO Krypton 87 C1 2.14E-2 4.53E-3 . 2.4 8E-3. ND
' Krypton.88 Ci' 2.68E-2 5.21E-3 ND ND' Kanon 131m Ci ND ND 5.09E-1 1.04E0 Xenon 133m' Ci 2.25E-3 ND 2.35E-1 6.22E-l' I Xenon 133 Ci 2.94E+1 4.72E+1 2.71E+1 9.21E+1 O Xenon 135m Ci 1.49E-1 2.27E-1 2.00E-3 ND
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Xenon 135 Ci 2.39E0 2.56EO- 2.43E-1 '2.77E-1 Xenon 137 Ci 5.43E-2 9.97E-3 ND ND Xenon 138 Ci 6.57E-2 ~. 14E-2 ND ND Argon 41 Ci '1.82E-3 ND' 1.73E-1 5.69E-3 .l l TOTAL FOR QUARTER Ci 3.22E+1 5.00E+1 2.91E+1 9.51E+1 1 i i i l i i O 13 i
i TABLE 1.A-8 Sheet 2 of 2 Continuous Mode Batch Mode Unit 1st Ouarter 2nd Quarter 1st Quarter 2nd Ouarter ; IODINES Iodiac 131 Ci 8.00E-5 5.30E-4 8.55E-8 2.21E-4 Iodine 133 Ci 3.92E-4 3.23E-5 1.72E-7 ND TOTAL FOR QUARTER C1 4.72E-4 5.62E-4 2.5BE-7 2.21E-4 PARTICULATE > 8 DAY T-1/2 l Manganese 54 Ci ND ND ND ND Cobalt 58 Ci ND 1.25E-4 ND 4.19E-5 Iron 59 Ci ND ND ND ND i l Cobalt 60 Ci ND ND ND 4.27E-6 Zinc 65 Ci ND ND ND UD Strontium 89 Ci 2.92E-7 ND ND ND Strontium 90 Ci ND ND ND ND j Niobium 95 Ci ND ND ND 3.15E-6 Molybdenum 99 Ci ND ND ND ND Cesium 134 Cl ND ND ND ND Cesium 137 Ci 7.63E-10 ND ND ND Cerium 141 Ci ND ND ND ND Cerium 144 Ci ND ND ND ND TOTAL FOR QUARTER C1 2.93E-7 1.2SE-4 ND 4.93E-5 O' 14
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L ...., . TABLE 1.A-9 GASEOUS EFFLUENTS
* ' t ELEVATED RELEASES January 1, 1988 through June 30, 1988. .
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l No Elevated Re' lease Points s : P' e a
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TABLE 1.A-10 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1988 through June 30, 1988 l FISSION AND ACTIVATION PRODUCTS First Second Estimated Unit Quarter Quarter Error % Total Activity Released (excluding Ci 5.43E-2 5.11E-2 13.5E+1 I gases, tritium, and alpha) Average Diluted Concentration pCi/ml 3.31E-9 3.30E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous % 1.52E-1 1.72E0 Tech Spec 3.11.1.2 - Quarterly Limit % 2.17E0 2.04E0 Tech Spec 3.11.1.3 - Quarterly Limit % 4.34E0 4.09E0 Requiring Processing TRITIUM , Total Released Ci 3.80E+1 2.48E+2 13.0E+1 Average Diluted Concentration pCi/ml 2.32E-6 1.60E-5 Fraction of MPC % 7.72E-2 5.33E-1 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 1.11E-4 3.74E-2 3.5E+1 Average Diluted Concentration pCi/ml 6.79E-12 2.41E-9 Fraction of MPC % 3.40E-6 1.21E-3 GROSS ALPHA RADIOACTIVITY Total Activity Released Ci 7.40E-5 9.06E-6 i3.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.28E+7 1.03E+7 15.0E0 VOLUME OF DILUTION WATER Liters 1.64E+10 1.55E+10 11.5E+1 0, 16
7__ 1 I
/ \ TABLE 1.A-11 Sheet. 1 of 2
\_l LIQUID EFFLUENTS January 1, 1988 through June 30, 1988 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 1st Quarter 2nd Quarter 1st Ouarter 2nd Quarter Chromium 51 Ci ND ND ND 1.09E-2 Manganese 54 Ci ND ND 3.67E-4 1.87E-4 Iron 55 Ci 2.27E-3 2.83E-3 1.15E-2 1.74E-2 Cobalt 57 Ci ND ND 1.82E-5 ND Cobalt 58 Ci ND ND 6.45E-3 7.67E-3 Iron 59 Ci ND ND ND 3.85E-4 ,
Cobalt 60 Ci ND ND 1.98E-2 3.86E-3 Zinc 65 Ci ND ND ND ND g Strontium 89 Ci 7.88E-4 3.49E-4 3.17E-4 3.52E-5 Strontium 90 Ci ND 8.08E-5 1.45E-5 2.26E-6 Zirconium 95 Ci ND ND 1.20E-5 9.01E-4 Niobium 95 Ci ND ND 1.09E-4 1.33E-3 Molybdenum 99 Ci ND ND ND 6.92E-6 Technitium 99m Ci ND ND ND 7.54E-6 Ruthenium 103 Ci ND IID ND 1.21E-3 Ruthenium 106 Ci ND ND 7.96E-3 2.50E-3 Silver 110m Ci ND ND 3.61E-4 3.10E-4 Tin 113 Ci ND ND ND 6.17E-5 Antimony 125 Ci ND ND 2.18E-3 1.44E-4 Iodine 131 Ci ND 1.79E-5 6.26E-5 2.84E-5 Cesium 134 Ci ND ND 2.20E-4 4.76E-5 Cesium 137 Ci ND ND 5.01E-4 9.60E-5 Lanthanum 140 Ci ND ND 1.97E-5 1.22E-4 Cerium 141 Ci ND ND ND 1.53E-4 Cerium 144 Ci ND ND 1.27E-3 4.56E-4 Unidentified Ci ND ND 4.39E-6 ND A TOTAL FOR QUARTER Ci 3.06E-3 3.28E-3 5.12E-2 4.78E-2 17
i l 1 i TABLE 1.A-11 Sheet 2 of 2 1 NUCLIDES RELEASED DISSOLVED AND ENTRAINED CASES Continuous Mode Batch Mode Unit 1st Ouarter 2nd Ouarter 1st Ouarter 2nd Ouarter Krypton 87 Ci NO ND ND ND Krypton 88 Ci ND ND ND ND. Xenon 131m Ci ND ND ND 1.64E-3 ! Xenon 133m Ci ND ND ND 1.56E-5 Xenon 133 Ci ND ND 9.37E-5 3.57E-2 Xenon 135 Ci ND ND 1.76E-5 4.89E-7 Xenon 138 Ci ND ND ND ND i TOTAL FOR QUARTER Ci ND ND 1.11E-4 3.74E-2 0 1 i I i i l l l l O l 18 1 1 i
yy (g I TABLE A-12 Sheet 1 of 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 1, 1988 through June 30, 1988 i SOLID WASTE SHIPPED OFFSITE FOR Activity Volume Estinate BURIAL OR DISPOSAL (Not Irradiated During During Total-Fuel) - Type of Waste 6 Months 6 Months Error %
~1. Spent Resin, Filter Sludges, 416.7 Ci 10.87 m3 25%
Evaporator Bottoms, etc.
- 2. Dry Compressible Waste, 1.2 Ci 2.83 m3 25%
Contaminated Equipment, etc.
- 3. Irradiated Components, Control 0.000 0.00 ;
Rods, etc. Other 0.000 0.00
- 4. ,
EST2 MATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE s i i Nuclide
\M
- 1. See attached sheet.
- 2. See attached sheet. l
- 3. 1
- 4. ;
SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 3 Exclusive Truck U.S. Ecology, Inc. PO Box 638 Richland WA 99352 IRRADIATED FUEL SHIPMENTS DISPOSITION , i Number of Shipments Mode of Transportation Dest.ination
~. O N/A N/A i l 19
TABLE A-12 Sheet 2 of 2 1 ! ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE
- 1. Nuclide Ci Nuclide ci H-3 2.436 Ru-106 0.000 C-14 0.300 Ag-110m 0.000 Cr-51 0.000 Sb-125 1.001 Mn-54 6.800 Cs-134 30.402 Fe-55 50.407 Cs-137 53.506 Co-58 36.000 Ce-144 0.300 Co-60 125.500 Pu-241 0.903 l
Ni-63 '106.500 Sr-89 0.600 Sr-90 2.000 Nb-95 0.000 Zr-95 0.000 TOTAL 416.655
- 2. Nuclide Ci Nuclide Ci 9
i H-3 0.027 Ru-106 0.004 { C-14 0.001 Ag-110m 0.010 Cr-51 0.000 Sn-113 0.000 Mn-54 0.014 Sb-125 0.014 Fe-55 0.387 Cs-134 0.001 , Co-58 0.095 Cs-137 0.004 Co-60 0.363 Ce-144 0.018 Ni-63 0.189 Pu-241 0.021 Sr-89 0.000 Sr-90 0.000 Nb-95 0.004 Zr-95 0.005 Ru-103 0.000 TOTAL 1.157 9 20 1
l.c' fl t-e r TABLE 1.A-13 Sheet 1 of 2
; g-SUPPLEMENTAL INFORMATION July 1, 1988 throu5h December 31,- 1988 REGULATORY LIMITS (CALCULATED)_
Third Fourth - s ' Fission and Activation Gas Release Rate Limits Unit _, Quarter Quarter
- 1. Tech Spec 3.11.2.1(a). Instantaneous 1' :Ci/see 1.65E-1 1.50E-1 QTv <
2.0 Ky 1 1 Ci/sec~ 4.19E-1 3.94E-1
-QTv <
0.33 (Ly.+ 1.1 Ny)
- 2. Tech Spec 3.11.2.2, Quarterly Average A Ci/sec. 5.48E-3 5.05E-3 QTv < 1
.L !]-
50 Ny QTv'< 1 Ci/sec 3.88E 3.85E _ 25 M y
- 3. Tech spec 3.11.2.4(1), Quarterly Average 1 Requiring Use of the Gaseous Radwaste Treatment System QTv < . 1 Ci/sec 2.74E-3 2.53E-3 100 N y QTv < 1 Ci/sec 1.94E-3 1.92E-3 50 M y r
O) ! 21 1 { 1
4 TABLE 1 A-13 Sheet 2 of 2 REGULATORY LIMITS Gaseous Todine 131. Tritium, and Particulate Third Fourth With > 8 Day T1/2 Limits Unit Quarter Quarter
- 1. Tech 3pec 3.11.2.1(b), Instantaneous QTv < 1 Ci/sec 4.98E-2 8.78E-3
.67 Ri
- 2. Tech Spec 3.11.2.3, Quarterly Average QTv < 1 Ci/sec 3.33E-4 5.88E-5 100 R1
- 3. Tech Spec 3.11.2.4(2), Quarterly Average Requiring Use of the Ventilation Exhaust Treatment System QTv < 1 Ci/see 1.67E-4 2.94E-5 i 200 Ri l
l l l O 1 i 22 l
1"" j' TABLE 1. A-14 J v SUPPLEMENTAL INFORMATION o July 1, 1988 through December 31, 1988 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 7g
( ) is exceeded, cumulative dose due to Y/ liquid effluents will be limited to 1.5 mrem to the whole body and to 2.5 mrem to any organ, using isotope specific methodology in the plant offsite dose calculation manual (ODCM).
- 3. Tech Spec 3.11.1.3 Tha 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 < 10 Ci excluding tritium and dissolved noble gases.
F) D 23 l l l
L TABLE 1.A-15 SUPPLEMENTAL INFORMATION July 1, 1988 through Decenber 31, 1988 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid (10 CFR 20, Appendix B, Table II, Col. 2) MPC MFC Isotope (uCi/ce) Isotope (uC1/cc) 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 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 Molybdenum 99 4 x 10-5 Unidentified 3 x 10-8 Technetium 99m 3 x 10-3 Tritium 3 x 10-3 Ruthenium 103 8 x 10-5 Krypton 85m 2 x 10-4 Ruthenium 106 1 x 10-5 Krypton 87 2 x 10-4 Silver 110m 3 x 10-5 Krypton 88 2 x 10-4 Tin 113 8 x 10-5 Xenon 131m 2 x 10-4 Antimony 124 2 x 10-5 Xenon 133 2 x 10-4 Antimony 125 1 x 10-4 Xenon 133m 2 x 10-4 Antimony 127 3 x 10-6 Xenon 135 2 x 10-4 Xenon 135m 2 x 10-4 l Gaseous Gaseous MPCs are not used in calculating technical specifications at Troj an. { i I O' 24 i i
k TABLE 1.A-16 ( }-
. SUPPLEMENTAL INFORMATION July 1, 1988 through December 31, 1988 AVERACE ENERGY:
Effluent release. limits are not based'upon E, hence, reporting E is not required. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Caseous Releases Fission and Activation Gases: Ganam spectrometric analysis of gaseous grab samples define radionuclides distribution at least monthly on monitored gaseous release points. Using the known nuclide distributions and process radiation monitor readings, the actual quantities of gaseous releases are calculated. s Iodines and Particulate: 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 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'sc2ntillation 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 bstch 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
- ges(_ of once per month for continuous releases.
V 25
Md 1 TABLE 1.A-17 SUPPLEMENTAL INFORMATION l July 1,1988 through December '41,1988 BATCH RELEASES Unit Liquid Gaseous 25 68 Number of Batch Relaases 1165.5 Total time period for Batch Releases Hours 92.9 Maximum time period for Batch Releases Hours 11.9 238.9 Average time period for Batch Releases Hours 3.7 41.6 Minimum time period for Batch Releases Hours 0.3 0.1 Average dilution flow during Batch Releases GPM 37140 NA ABNORMAL RLEASES 0 0 Number of Abnormal Releases Total Activity Released Ci NA NA O s O 26
t t
; j TABLE 1.A-18 Sheet 1 of 2 v
GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1988 through December 31, 1988 Third Fourth Estimated FISSION AND ACTIVATION CASES _. Unit Quarter Quarter Error (%) Total Activity Released Ci 6.72E+1 1.26Et2 13.5El Average Release Rate for Quarter pCi/sec 8.45E0 1.59E+1 Percent of Limit: Tech. Spec. 3.11.2.1 (a) - 1.05E-2 2.93E-2 Instantaneous Tech Spec. 3.11.2.2 - 2.18E-1 4.11E-1 Quarterly Average Tech. Spec. 3.11.2.4.(1) - 4.36E-1 8.22E-1
, Quarterly Average Requiring j Processing IODINE 131 Total Iodine 131 Released Ci 1.27E-4 1.92E-3 13.5El Average Release Rate for Quarter pCi/see 1.60E-5 2.42E-4 PARTICULATE Total with Half-lives > 8 days Ci 5.45E-5 2.42E-5 13.5El Average Release Rate for Quarter pCi/sec 6.86E-6 3.04E-6 Total Cross Alpha Released Ci 1.61E-7 1.30E-7 TRITIUM Total Released Ci 2.36E+1 1.51E+1 13.0El Average Release Rate for Quarter pCi/sec 2.97EC 1.90E0 m
! \
U 27
TABLE 1.A-18 Sheet 2 of 2 IODINE 131 PARTICULATE WITH Third Fourth Estimated
> 8 DAY T1/2 AND TRITIUM Unit Quarter Quarter Error (%)
Total Released Ci 2.36E+1 1.51E+1 13.5El Average Release Rate for Quarter pCi/sec 2.97E0 1.90E0 Percent of Limit: Tech. Spec. 3.11.2.1 (b) 6.05E-3 1.22E-1 Instantaneous Tech. Spec. 3.11.2.3 9.03E-1 3.28E0 Quarterly Average Tech. Spec. 3.11.2.4(2) 1.81E0 6.56EO Quarterly Average Requiring Processing O l O' 28 l
-- -----------u
L TABLE 1.A-19 Sheet 1 of 2
;)
CASEOUS EFFLUENTS I GROUND LEVEL RELEASES July 1, 1988 through December 31,'1988 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter FISSION CASES Krypton 85m C1 1.0BE-2 2.38E-2 1.09E-2 1.78E-2 Krypton 85. Ci ND ND 3.84E-1 6.15E-1 Krypton 87 Ci 1.99E-2 4.65E-2 3.01E-4 2.04E-3 Ci 2.47E-2 5.71E-2 3.45E-3 ND
~
Krypton 88 Xenon 131m Ci ND ND 1.41E-1 8.19E-1 Xenon-133m Ci ND 2.43E-3 1.55E-1= 3.47E-1 Ci 5.09E+1 7.73E+1 1.50E+1 4.45E+1 ( )' Xenon 133 Xenon 135m Ci 9.89E-2 2.27E-1 5.03E-4 8.99E-3 Xenon 135 Ci 1.03E-1 1.95E-1 2.68E-1 4.11E-1 Xenon 137 Ci 3.56E-2 1.06E-1 ND ND Xenon 138 Ci 4.49E-2 1.32E-1 ND ND
' Argon 41 Ci 3.95E-3 4.52E-2 8.62E-2 5.30E-1 TOTAL FOR QUARTER Ci 5.12E+1 7.81E+1 1.60E+1 4.73E+1 29
1 TABLE 1.A-19 Sheet 2 of 2 l i l NUCLIDES RELEASED f Continuous Mode Batch Mode Unit 3rd Ouarter 4th Quarter 3rd Ouarter -4th Quarter IODINES Iodine 131 Ci 1.26E-4 5.00E-4 7.81E-7 1.42E-3 Iodine 132 Ci ND 2.25E-7 ND ND Iodine 133 Ci 3.77E-4 1.98E-4 1.93E-7 2.17E-5 Iodine 135 Ci ND 7.01E-6 ND ND TOTAL FOR QUARTER Ci 5.03E-4 7.05E-4 9.74E-7 1.44E-3 PARTICULATE > 8 DAY T-1/2 AND TECHNICAL SPECIFICATION REOUIRED ISOTOPES Manganese 54 Ci ND ND ND ND Cobalt 58 Ci 1.82E-5 ND ND ND Iron 59 Ci ND ND ND ND Cobalt 60 Ci ND ND ND ND Zinc 65 Ci ND ND ND ND Strontium 89 Ci 2.05E-7 6.33E-7 ND 1.63E-05 Strontium 90 Ci 1.14E-07 1.78E-07 ND 7.00E-06 Niobium 95 Ci ND ND ND ND Molybdenum 99 Ci ND ND ND 1.08E-8 Cesium 134 Ci ND ND ND 2.18E-8 Cesium 137 Ci 4.62E-9 6.92E-9 ND 4.25E-8 Barium 140 Ci 2.68E-9 5.07E-9 ND ND Cerium 141 Ci ND ND ND ND Cerium 144 Ci ND ND ND ND Neodymium 147 Ci 3.60E-5 ND ND ND TOTAL FOR QUARTER Ci 5.45E-5 8.23E-7 0.00E+0 2.34E-5 9i 30
.: v . > ,
;,y * . :'-
.fn ,
y
. TABLE l'.A-20 -
1 GASROUS EFFLUENTS ELEVATED RELEASES July 1,-1988'through December 31,~ 1988 n
.h,
,j '
'i .
,lp
-l .a No Elevated Release Points d.
f_ 4 s t I i r7 e i h1 i'
.1 ss- 31 i i
X: ;, L : r '
' TABLE 1.A-21 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES July 1, 1988 through December 31, 1988 FISSION AND ACTIVATION PRODUCTS Third Fourth Estimated Unit Quarter Quarter Error %
Total Activity Released (excluding Ci 5.70E-2 3.82E-2 13.5E+1 gases, tritium, and alpha) Average Diluted Concentration pCi/ml 3.80E-9 2.25E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous % 1.05E-1 2.42E-1 Tech Spec 3.11.1.2 - Quarterly Limit % 2.28E0 1.53E0 Tech Spec 3.11.1.3 - Quarterly Limit % 4.56E0 3.06E0 Requiring Processing TRITIUM Total Released Ci 2.61E+1 6.31E+1 13.0E+1 Average Diluted Concentration pCi/ml 1.74E-6 3.71E-6 Fraction of MPC % 5.80E-2 1.24E-1 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 7.95E-5' 1.42E-3 i3.5E+1 Average Diluted Concentration pCi/ml 5.30E-12 8.35E-11 Fraction of MPC % 2.65E-6 4.18E-5 GROSS ALPHA RADIOACTIVITY Total Activity Released Ci 1.88E-5 3.45E-6 3.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.23E+7 9.20E+6 15.0E0 VOLUME OF DILUTION WATER Liters 1.50E+10 1.70E+10 il.5E+1 0; 32 l
N ; 18 f i v: 2 i
) -TABLE 1.A-22 Sheet 1 of 2 x]
LIQUID EFFLUENTS l i July 1, 1988 through December 31, 1988 ; m NUCLIDES RELEASED Continuous Mode Batch Mode Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter Chromium 51 Ci ND ND 5.32E-3 4.16E-3 Manganese 54 Ci ND ND 3.69E-4 3.50E-4 Iron 55 Ci 8.17E-3 8.65E-4 1.67E-2 1.53E-2' Cobalt 57 Ci ND ND 1.98E-5 1.22E-5 Cobalt 58 Ci ND ND 6.42E-3 4.77E-3 Iron 59 Ci ND ND -1.61E-4 1.30E-4 Cobalt 60 Ci' ND ND 6.72E-3 4.67E-3 Zinc 65 Ci ND ND ND ND l Strontium 89 C1 2.69E-4 2.67E-4 1.01E-4 6.99E-5 Strontium 90' Ci '1.30E-5 2.47E-4 9.91E-6 1.11E-5 i Zirconium 95 Ci ND ND '1.65E-3 7.14E-4 gs ' Niobium 95 Ci ND ND 3.13E-3 1 45E-3 ' Molybdenum 99 Ci ND ND ND 7.69E-6 Technitium 99m Ci ND ND ND 7.83E-6 i Ruthenium 103 Ci ND ND 9.64E-4 4.57E-4 Ruthenium 106 'Ci ND ND 4.61E-3 3.00E-3 Silver 110m Ci ND ND 8.32E-4 4.09E-4 Tin 113 Ci ND ND 1.82E-4 6.20E-5 Antimony 125 Ci ND ND 4.14E-4 2.79E-4 j Iodine 131 Ci ND 1.88E-5 ND 1.36E-4 I Cesium 134 Ci ND ND ND 4.41E-5 Cesium 137 Ci ND ND 8.86E-5 1.06E-4 -l Lanthanum 140 Ci ND ND 1.10E-5 8.51E-5 Cerium 141 Ci ND ND 2.62E-5 '2.16E-5 Cerium 144 Ci ND ND 6.53E-4 5.55E-4 Unidentified Ci ND ND ND ND TOTAL FOR QUARTER Ci 8.45E-3 1.40E-3 4.86E-2 3.68E-2 l 33
h
. TABLE 1.A-22 Sheet 2 of 2 NUCL1 DES RELEASED DISSOLVED AND ENTRAINED GASES Continuous Mode Batch Mode Unit 1st Ouarter 2nd Ouarter 1st Ouarter 2nd Ouarter Krypton 87 Ci ND ND ND ND Krypton 88 Ci ND ND ND ND Xenon 131m Ci ND ND 'JD ND j Xenon 133m Ci ND ND ND ND Xenon 133 Ci ND ND 7.95E-5 1.30E-3 Xenon 135 Ci ND ND ND 1.23E-4 Zenon 138 Ci ND ND ND ND TOTAL FOR QUARTER Ci ND ND 7.95E-5 1.42E-3 0'
j O. 34
1 TABLE 1.A-23 Sheet 1 of 2
,-s i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
\
' July 1, 1988 through December 31, 1988 l
SOLID WASTE SHIPPED OFFSITE FOR Activity Volume Estimate BURIAL OR DISPOSAL (Not Irradiated During During Total Fuel) - Type of Waste Six Months Six Months Error % Spent Resin, Filter Sludges, Evapo- 65.63 m8 25%
- 1. 9.8 Ci rator Bottoms, etc.
L 2. Dry Compressible Waste, Containment 1.3 Ci 32.34 m8 25% rator Bottoms, etc. 1
- 3. Irradiated Components, Control Rods, 0.000 0.00 etc.
- 4. Other 0.000 0.00 Estimate of Major Nuclide Distribution by Type of Waste Nuclide
- 1. See attached sheet.
f 2. See attached sheet. 3.
- 4. ,
Solid Waste Disposition Number of Shipments Mode of Transportation Destination 10 Exclusive Truck U.S. Ecology, Inc. PO Dox 638 Richland WA 99352 Irradiated Fuel Shipments Disposition Number of Shipments Mode of Transportation Destination 0 N/A N/A O 35
i l TABLE 1.A-23 Sheet 2 of 2 Oi 4 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE l
- 1. Nuclide Ci Nuclide Ci i
H-3 3.067 Ru-106 0.192 C-14 0.295 Ag-110m 0.006 I Cr-51 0.004 Sb-125 0.047 Mn-54 0.058 Cs-134 0.120 Fe-55 2.416 Cs-137 0.286 Co-57 0.004 Ce-144 0.030 Co-58 0.718 Pu-238 0.002 Co-60 1.309 Pu-239, 240- 0.003 i Ni-63 0.985 Pu-241 0.272 Sr-89 0.005 cm-242 0.004 Sr-90 0.004 Nb-95 0.003 Zr-95 0.006 Total 9.836
- 2. Nuclid_e Cl Nuclide Ci ,
H-3 0.420 Ru-106 0.040 C-14 0.139 Ag-110m 0.000 Cr-51 0.004 Sn-113 0.000 1 Mn-54 0.014 Sb-125 0.002 Fe-55 0.324 Cs-134 0.001 Co-58 0.069 Cs-137 0.000 - Co-60 0.148 Ce-144 0.018 ! Ni-63 0.068 Pu-238 0.000 Sr-89 0.000 Pu-239, 240 0.001 I Sr-90 0.000 Pu-241 0.044 Nb-95 0.003 cm-242 0.000 Zr-95 0.010 Ru-103 0.002 TOTAL 1.315 I l l O , 36 ( f I _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ - _ _ - _ _ _ _ . - _ _ _ _ _ _ -
1 I l I t-p 1.B- 0FFSITE RADIATION DOSES. ) k Offsite radiation doses from gaseous and liquid' effluents for 1988 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. Poses are' presented separately.for batch and continuous releases and.for noble gas, gaseous iodine, and particulate and liquid offluents. Exposure locations,are based on the land-use survey presented in the
~ Final Safety Aanalysis Report and the 1987 annual survey of agricultural-production.
l- ' l Models and assumptions used in performing the dose analyses for 1988 are - I- presented in Sections 11.2, " Liquid Waste Management. Systems", and 11.3, _ I
" Caseous Waste Management Systems", of the Trojan Final Safety Analysis Report. ..j
.)
l ,D i l? l l 1 O l 37
1 Sheet 1 of'2 [}
\sg TABLE 1.B-1 PARAMETERS USED IN CALCULATING DOSES FTtOM GASEOUS EFFLUENTS (First Half.1988)
-Parameter Value Accumulation and Decay Times (days)
Harvest of leafy vegetables to consumption by man 1.0 Harvest of pasture grass to consumption by animals 0.0 Harvest of stored feed to consumption by animals 90.0
. Harvest of produce to consumption by man 60.0 Animal butchering to consumption 20.0 Food ingestion by animal to milking 2.0 Accumulation time on ground 7,300.0 Human Consumption Rates (kg/yr)
Leafy vegetables by adult -64.0 Produce by adult 456.0 Meat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m 3/yr)
, 7, t Adult 8,000.0
\- 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 Fraction of Particulate Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulate Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m 2) l 240.0 Field Decay Half Life (days) 14.0 38 4
TABLE 1.B-1 Sheet 2 of 2 Parameter Value Agricultural Productivity (kg/m2) . Leafy veSetables 2.0 ) Pasture grass 0.7 Produce 2.0 Period of Lon5-Term Buildup for Activity in Soil (days) 7,300.0 l Fraction of Leafy Vegetables Crown in Garden of Interest 1.0 Fraction of Produce Crown in Garden of Interest 0.76 Fraction of Year Animal Crazes on Pasture 05 Fraction of Daily Feed that is Pasture Grass when Animal Crazes 1.0 e' 39 l
n- ---_ - _ _
; TABLE 1.B-2 <
Sheet.1 of 2 PARAMETERS USED IN CALCULATING DOSES FROM LIQUID EFFLUENTS Value Parameter 1st Otr. 1988 2nd Otr. 1988'
-Plant Dilution Flow Rate (gpm) 33,100. 31,200.
Columbia River Flow Rate (cfs) 97,303, 308,402. Dilution Factors Drinking water 1,320. 4,431. Swimming water 290. 975. Aquatic biota 290, 975. Shoreline sediment 290. 975. Irrigation water 1,320. 4,431. Milk and meat animal water 1,320. 4,431. Decay. Times (days) Discharge to drinking water 0.85 0.61 Discharge to swimming water 0.0 0.0-Discharge to aquatic blota consumption 1.0 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 Discharge to irrigation water withdrawal 0.85 0.61 Discharge to milk and meat animal water 0.85 0.61
-(s withdrawal Leafy vegetable harvest to consumption by man 1.
Produce harvest to consumption by man 60. Stored feed harvest to consumption by animals 90. Pasture grass to consumption by animals 0. Animal butchering to consumption 20. Food and water ingestion by cow / goat to 2. milking Accumulation Times (days) Shoreline sediment 7,300. Irrigated soll 7.300. Irrigated vegetables 60. Pasture grass 30. Adult Consumption Rates (kg/yr) Drinking water 730. Fish 21. Invertebrates (crayfish) 5. Irrigated leafy vegetables 64. Irrigated produce 456. I Cow's milk from irrigated pastureland 310. Coct's milk from irrigated pastureland 310. Meat from irrigated'pastureland 110. O 40 l l
I i I TABLE 1.B-2 Sheet 2 of 2 Value .{ Parameter 1st Otr. 1988 2nd Otr. 1988 ) l Annual Exposure Times (hr/yr) Swimming and boating 12. i Shoreline activities 12. l Irrigated pasture 2,190. Infant Consumption Rates (kg/yr) Drinking water 330. ; Cow's milk from irrigated pastureland 330. I Fraction of Year Animals Graze on Pasture 0.5 l Fraction of Year Crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14. Irrigation Rate (liters /m 2 -hr) 0.104 Fractional Concentration of Water in Soil (g/g) 0.2
'l Fraction of Leafy Vegetables crown in Garden of 1. j Interest l Fraction of Produce Crown in Garden of Interest 0.76 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water That is 0.'25 Initially Retained by Leafy Vegetables Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Grass Yield (kg/m2) 0.7 -
Vegetable Yield (kg/m2) 2. , Surface Density of Soil (kg/m2) 240. Animal Consumption Rates (kg/ day) Water by milk cow 60. Water by milk goat 8. Water by beef 50. l Pasture vegetation by milk cow 50. Pasture vegetation by milk goat 6. Pasture vegetation by beef 50. O 41 1
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AR EEEEE E EEEEE EEEEEE EE FY l0000 000032 NH l0000
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_ ~ D 54568 4 55668 565655 44 TI 00000 0 00000 000000 00 LO - - - - - - - - - - - - - - - - - - - UR EEEE6 E EEEEE EEEEEE EE DY 65799 3 63.l77 369792 85 AH . 3l377 2 33811 2418l4 11 T_ - . _
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54568 4 55568 565555 44 00000 0 00000 000000 00 E - - - - - - - - - - - - - - - - - - - N EEEEE E EEEEE EEEEEE EE O 95399 7 92677 08 B 3 6 4 6 8.l. 31777 2 33111 252114 21 5 _ T N 55568 4 56668 565555 44 E 00000 0 00000 000000 00 U G - - - - - - - - - - - - - - - - - - - _ 8 L N EEEEE E EEEEE EEEEEE EE U 55677 378265 53 3 8 F 9 F L 54099 l.
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D 425S7 76546 2 6 __ I 000S0 00000 0 0 O - - - - - - - - - - - - R EEEEE EEEEE E E Y 54690 55203 5 1 H . T 11132 31113 1 7 . 42557 76556 2 6 L 00000 00000 0 0 AY - - - - - - - - - - - - M TD EEEEE EEEEE E E O OO 44690 05223 4 0 R TB . F 11132 31193 1 7
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' E ET C VBUTTC M R TPE D IASPP E U AMTON LTNMMO R S HUATA EOUUT M O SR DGCSS (
P GNBEG NE NNE X NOERN AVEOOR E E ICTUI CCCU S K RSM NYU S O NHEOM OFDT'KO D ISVPI IAOALP CRINXH TEREIX E IDFIES ALPMME G T G L A A I A R
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[v\ TABLE 1.B-5 FIRST QUARTER 1988
. BATCH RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF
!< HIGHEST CONCENTRATION i.. Site . Boundary [a] ResidenceIDI .i' l Beta Air Dose (mrad) 1.3E-2 7.0E-3 Camma Air Dose (mrad) 5.0E-3 1.9E-3 Beta + Camma Skin Dose (mram) - 4.4E-3
- Gamma Total Body Dose'(mrem) .- 1.6E-3 (al' North sector at 663 meters.
i:-V (b] North ~' sector at 1000 meters. l J 44 4
1 i l I l TABLE 1.B-6 FIRST QUARTER 1988 CONTINUOUS RELEASES i l DOSES FROM NOBLE GASES AT 1 SITE BOUNDARY AND RESID2NCE OF HIGHEST CONCENTRATION Site Boundary [a] Residence [b] Beta Air Dose (mrad)- 1.6E-2 8.3E-3 Gamma Air Dose (mrad) 6.9E-3 2.5E-3 Beta & Gamma Skin Dose (mrem) - 6.0E-3 Gamma Total Body Dose (mrem) - 2.2E-S {a) North sector at 663 meters. - [b]. North sector at 1000 meters. O, I l 45 l l
- - - . _ . ,._-~ _ - - - - -
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1 l f [Y - TABLE I'.B-7' , i 1 Nm / ] .. FIRST QUARTER 1988
' BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT. .l
, SITE BOUNDARY AND RESIDENCE OF' HIGHEST CONCENTRATION i
l Site. Boundary [a] ResidenceIDI
' Beta Air Dose (mrad) 2.9E-2 1.5E-2
- Gamma Air Dose.(mrad) 1.2E-2 4.4E-3 +
Beta,+ Gamma Skin Dose-(mrem) - 1.0E-2 Gamma Total Body Dose (mram) - 3.8E-3 [a] Maximum site boundary location. [b]. Maximum residence location. l 1 46
_ I _ 1242 4 23737 7 762125 3 762121 6900 6 70000 7 810007 7 810006
~D ,- 0000 0 01000 0 010000 0 010000 TI - - ++ - - +++ - - +++ - - - - +++
ND EEEE E EEEEE E EEEEEE E EEEEEE E AR 4800 4 00000 0 700005 1 700001 FY- 2200 2 80000 8 500008 4 500002 NH- . . . . IT- 1200 1 13000 1 560008 9 560001 _ 6966 6 70778 6 8l8787 7 818787 D 0000 0 01000 0 0I0000 0 010000 TI - - - - - - - - - - - - - - - - - - - - - - - _ LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 3864 4 80124 8 309180 8 309189 DY 9235 8 70299 0 503375 6 503372 4 AH . . .
- T= 1222 6 23338 1 867121 4 867122 5
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S N O - 6976 6 70878 7 818788 7 818787 I - 0000 0 01000 0 010000 0 010000 T E - - - - - - - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E _ NC
- O 4818 8 40449 2 109959 7 109958 IO - B 6264 5 30182 6 103247 0 103241 S DL - . . . . .
E U - 1242 4 23737 7 762125 3 762121 S LE - _ _ A CR _ E XU L ES - E (O - _ R P 6976 6 70878 7 818788 7 818787 _ SX 0000 0 01000 0 010000 0 010000 _ H TE G - - - - - - - - - - - - - - - - - - - - - - - 8 C N N EEEE E EEEEE E EEEEEE E EEEEEE E T EE A UT U L 4818 6264 8 5 40349 30182 2 6 l09959 l03247 6 0 109958 103241 _ B. B LI . . . . . . 1 FS) 1242 4 23737 7 762125 3 762121 8 FFM _ E 8 EFE L 9 OR B 1 S M A UM( T R OU 6976 6 70878 7 818788 7 818787 _ E EM 0000 0 01000 0 010000 0 010000 _ T SI N - - - - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEEEEE E _ A GA K 4718 8 45349 2 l99959 6 199958 _ U M S 6764 5 36182 6 l23247 0 123241 _ QM . . OT 1242 4 23737 7 772125 3 772121 3 RA 1 F
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9 SS EE SS 6976 6 70878 7 8l8788 7 818787 _ OA 0000 0 01000 0 0I0000 0 010000 DG L - - - - - - - - - - - - - - - - - - - - - - - EEEEEE E _ AY EEEE E EEEEE E EEEEEE E _ E TD- 4818 8 40349 2 l09959 6 109958 _ L OO- 6264 5 30182 6 l03247 0 103241 _ B - TB- . . . . O _
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- x. TI LO _
EEEE E EEEEE E EEEEEE E EEEEEE E UR 6534 3 20534 7 037927 7 007923 3 DY 8723 4 68370 2 473,032 9 473039 6 AH T 1222 6 33341 1- 766121 3 766121 4 S N O 3643 5 47545 4 585455 4 585455 4 I 0000 0 00000 0 000000 0 000000 0 T E- - - - - - - - - - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E S NC O 1589 3 40553 4 109741 5 109741 5 E IO ' S A U DL-B 5722 1242 4 2 98668 3 23848 9 979008._5 561124 2 979008 0 561129 3 E LE _ L CR _ E XU R ES (O S P _ 3'643 3 47545 4 585455 4 00000n 0 585455 4 000000 0 U SX 0000 0 00000 0 G TE G - - - - - - - - - - - - - - - - - - - - - - - - - U N N EEEE E EEEEE E EEEEEE E EEEEEE E 9 N EE U 1569 3 40353 5 109741 5 109740 5
- I UT L- 5722 2 98668 3 979068 5 979008 0 T LI -
B. N FS) - 1242 4 23848 9 561124 2 561129 3 1 O FFM - - C EFE E OR L 8 S M B 8 UM( A 9 OU 3643 3 47545 4 585455 4 585455 4 T 1 EM 0000 0 00000 0 000000 0 000000 0 SI ~ N - - - - - - - - - - - - - - - - - - - - - - - - - R AX~ I EEEE E EEEEE E EEEEEE E EEEEEE E E GA K 1569 3 41353 3 149741 5 149740 5 T M -S 5322 2 96668 3 919008 5 919008 0 R M 581124 2 581129 3 A DT 1342 4 24848 9 U RA Q F .~
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SS 1 EE SS 3643 3 47545 4 585455 4 585455 4 0 OA 0000 0 00000 0 000000 0 000000 0 DG L - - - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 1569 3 40353 3 109741 5 109740 5 L OO 5722 2 98668 3 979008 5 979008 0 B . TB - O 1242 4 23848 9 561124 2 561129 3 . N Y- N N N N A ) O O ) O ) O
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OSBUTN T T- I AS I ASP T. I ASPN T- I ASPO A A_ TOTN T TOTNM A= TOTNMO A. TOTNMC C - ATEO A ATEOU - ATEOUC ATEOU O R L GC L L DCS R _L GCS R L GCSK L O AEE A5 AEE N O- AEE NK O AEE NL T .HRVE N0 NRVEO T- HRVEOL TT HRVEOI - E C C NU CC M C N 'J CCI AC NU CCM - E .NU IT R _ .ISYU NC ISYU OE ISYU M OE- ISYU - U NS OFD AE OFDT CS- OFDT GS- OFDTT _ S _ E - RPAO L S RPAOA L - RPAOAN L RPAOAA L _ O DH IXER A T XERE A KH IXEREO A KH IXEREO A P RN AELP T AH AELPM T LN AELPNC T LN AELPMG T X AN- O EN O IN- O O E G( - T M( T M( - T IN_ M( - T I
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- 3600 3 47000 4 580004 4 580003 D- 0000 0 00000 0 000000 0 000000 TI - - ++ - - +++ - - +++- - - - +++-
NO EEEE E EEEEE E EEEEEE E EEEEEE E AR 7500 7 90000 9 810000 2 810004
- FY 2700 2 48000 4 170006 1 170000
- NH - -
IT - 1200 1 23000 2 560007 8 560001 3635 3 47444 3 585454 4 585454
- D 0000 0 00000 0 000000 0 000000 TI - - - - - - - - - - - - - - - - - - - - - - - -
LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 6534 4 20534 7 118927 7 118923 DY 8723 68370 2 473032 9 473039 AH . 4 T 1222 6 33341 1 766121 3 766121 S N _ S O _ 3643 5 47545 4 585455 4 585455 E I - 0000 0 00000 0 000000 0 000000 S T E - - - - - - - - - - - - - - - - - - - - - - - - A GA N EEEE E EEEEE E EEEEEE E EEEEEE E E NC O 1589 3 40654 5 219742 5 21?742 L IO B- 5722 2 98668 3 979008 5 979008 E DL = . R U 1242 4 23848 9 561124 2 561129 LE =_ S CR U XU G ES U (O N P 3643 3 47545 4 5E5455 4 585455 I SX 0000 0 00000 0 0D0000 0 000000 O T TE G - - - - - - - - - - - - - - - - - - - - - - - - l N N N EEEE E EEEEE E EEEEEE E EEEEEE E O EE U- 1569 3 40454 4 239742 5 219701 C UT L 5722 2 98668 3 979008 5 979008 B. LI - . 1 + FS) _ 1242 4 23848 9 561124 2 561129 FFM _ E HC EFEOR L T S M-B A UM( - A B OU - 3643 3 47545 4 585455 4 585455 4 T EM - 0000 0 00000 0 000000 0 000000 8 SI - N - - - - - - - - - - - - - - - - - - - - - - - - 8 AX - I EEEE E EEEEE E EEEEEE E EEEEEE E 9 GA K 1569 3 41454 4 259742 5 25974) 1 M S 5322 2 96668 3 919008 5 919008 M . . R OT 1342 4 24848 9 581124 2 581129 E RA T F R ) A SS U EE Q SS 3643 3 47545 4 585455 4 585455 OA - 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - - - - 1 AY- EEEE E EEEEE E EEEEEE E EEEEEE E E TD 1569 3 40454 4 219742 5 219741 t L OO 5722 2 98668 3 979008 5 979008 B TB O _ 1242 4 23848 9 561124 2 561129 H _ Y- - N N N N A O 6 O O H - I I I I H T T T T T - P P P P A M M M M P U U U U N S S S N S O D NN NN NN O NN I N OO OO OO I OO T A CI CI CI T CI P L T L TN L TNP L TNM N- IEP IEPO IEPOM IEPOU O N NDLM N NDLMI N HDLMIU N- NDLMIS I O OSBU O OSBUT O bSBUTS O- OSBUTN _ T I I AS I I ASP I E ASPN - I - I ASPO _ A - T TOTN T TOTNM T IOTNMO s - TOTNMC _ C A ATEO A ATEOU A ATEOUC 4 ATEOU O- C L GC LC L GCS C L GCS C L GCSK _ L O AEE AO AEE N O AEE NK O AEE NL _ L HRVE ML HRVEO L HRVEOL TL HRVEOI E NU C I NU CC H NU CCI A NU CCH _ R M ISYU NM ISYU OM ISYU M DM ISYU _ U NU OFD AU OFDT CU OFDT GU_ - OFDTT _ S EM RPAO L M RPAOA L M RPAOAH L M RPAOAA _ O DI IXER A TI IXERE A KI IXEREO A KI - IXEREO - P RX_ AELP T AX AELPM T LX AELPMC T LX AELPMG - X - AA_ O EA~ O IA O IA-E= GM- T MM~ T MM T MM-
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D 3364443 2 5 I 0000000 0 0 O - - - - - - - - - R EEEEEEE E E Y 9183743 6 3 H . T 873I249 2 1 3365443 2 6 _ L = 0000006 0 0 AY- - - - - - - - - - M TD- EEEEEEE E E S O OO. 9880700 9 4 E R TB . . S F 8535244 1 9 A - E ) 8L ES 8E LT 9R IN - 1 1 ME - 1 S U) _
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73559 4 76112 173637 32 D 50000 5 50000 000044 44 TI 00000 0 00000 000000 00 NO - ++++ - ++++ ++++- - - - _ AR EEEEE E EEEEE EEEEEE EE FY 30000 3 30000 000002 20 _ NH . . _ _ IT 90000 9 _ 90000 000012 32 D- 55679 5 56679 665555 44 TI - 00000 0 00000 000000 00 LO- - - - - - - - - - - - - - - - - - - - UR- EEEEE E EEEEE EEEEEE EE DY- 30812 9 04910 552331 06 AH- 2 . . . T- 72859 9 74112 163137 21 55579 4 56679 665555 44 00000 0 00000 000000 00 E - - - - - - - - - - - - - - - - - - - N EEEEE E EEEEE EEEEEE EE O 16612 2 18710 536431 17 B- . . . 72259 1 75512 173137 21 S T N 55579 5 56679 665555 44 E 00000 0 00000 000000 00 U G - - - - - - - - - - - - - - - - - - - 8 L N- EEEEE E - EEEEE EEEEEE EE 542420 2 8 F . 9 F U-L 02112 4 0841O. . 06 1 1 E 71159 9 72212 163137 21 B. R D) E IM - 1 T UE - R QR - E A IM 55677 5 5667B 665555 44 L U L( 00000 0 0000O 000000 00 B Q N - - - - - - - - - - - - - - - - - - - A M I EEEEE E EEEEE EEEEEE EE T K 742330 2 O R 00800 9 O.3936 06 0 F S_ 72863 9 74116 163137 21 S E S O - D -
- 55679 5 56679 665555 44
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00000 0 00000 000000 00 AY - - - - - - - - - - - - - - - - - - - TD EEEEE E EEEEE EEEEEE EE OO 00812 8 03910 542330 06 TB . . 72859 9 74112 163137 21
- - N
- T T G NO
- N N N N L OI E O E I I IT M I M R DN TP I T I E SO PM D __ A D T I MU N NE _ C NE A LT US O OS __
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A I A R U R T E _ Q R O V A I T A g (1 I M _- -
TABLE 1.B-14 SECOND QUARTER 1988 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF i HIGHEST CONCENTRATION Site
' Boundary [a] Residence [b]
Beta Air Dose (mrad) 2.9E-2 1,6E-2 Camma Air Dose (mrad) 9.7E-3 3.6E-3. Beta + Gamma Skin Dose (mrem) - 8.9E-3 Gamma Total Body Dose (mrem) - 3.0E-3 [a] North sector at 663 meters. i [b] North sector at 1000 meters. ; G 53
_e-i i
' .O 1. . ' TABLE 1.B-15 . Q3 ;-
I SECOND QUARTER 1988 CONTINUOUS RELEASES s DOSES FROM NOBLE CASES AT l SITE BOUNDARY AND RESIDENCE OF l HIGHEST CONCENTRATION. 1 l Site ! Boundary [a] ResidenceID3. Beta Air Dose'(mrad) 1.6E-2 8.7E-3 l Gamma Air. Dose (mrad) 6.6E-3 2.5E-3 Beta + Gamma Skin Dose (mrem) - 5.8E-3 l Gamma Total Body Dose'(mrem) - 2.lE-3 [a] North see. tor at 663 meters. l [b] Nort.h sector at 1000. meters. l
, -l A .
l i l 4 i l s 1 l 1 1 ( 54
TABLE 1.B-16 SECOND QUARTER 1988 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 4.6E-2 2.4E-2 Gamma Air Dose (mrad) 1.6E-2 6.1E-3 Beta + Gamma Skin Dose (mrem) - 1.5E-2 Gamma Total Body Dose (mrem) - 5.2E-3 [a] Maximum site boundary location. [b] Maximum residence location. O i l i I l
\
l O 55 l t - __ ._ . ___-___ _ _ -
~
- 4500 4 45000 4 560003 3 560 D- 0000 0 00000 0 000000 0 000
- - TI - - - ++ - +++ - - - +++- - -
NO EEEE E EEEEE E EEEEEE E EEE
- AR- 9400 4 68000 7 190005 8 850 FY 9400 10000 3 960003 3 0900 NH . 6 . .
IT 7600 8 22000 2 ~ 220001 1 320
- 3533 3 45444 3 565554 4 564
.D- 0000 0 00000 0 000000 0 0000 TI - - - - - - - - - - - - - - - - -
LO- EEEE E EEEEE E EEEEEE E EEE _ UR- 5489 9 18087 0 195852 9 9581 DY 1433 9 10681 6 169769 0 390 AH . . T 1621 4 32731 1 429511 4 421 1 S _ N : O 4543 3 45545 4 565555 4 565 I 0000 0 00000 0 000000 0 0000 T E - - - - - - - - - - - - - - - - GA - N EEEE E EEEEE E EEEEEE E EEE NC - O 8471 9 38056 8 193848 3 5538 IO - B 6443 4 30969 5 060404 3 2904 S DL - - E U - 8621 2 22636 7 321512 1 321 S LE - A CR - E XU - L ES E (O - ' - R P 4543 3 45545 4 565555 4 5655 SX 0000 0 00000 0 000000 0 0000 H TE G - - - - - - - - - - - - - - - - - - - - 7 C N N EEEE E EEEEE E EEEEEE E EEE 1 T EE U 4471 0 58756 9 493848 5 8538
- A UT L 7443 5 30869 5 060404 3 2904 B LI B.
FS) 8621 2 22636 7 321512 1 3215 1 8' FFM ~ ~ ' 8 EFE E 9 OR L 1 S M B UM( ~ : A R OU 4543 3 45565 4 565555 4 5'6 T E EM 0000 0 00000 0 000000 0 0000 T SI - N - - - - - - - - - - - - - - - - - - - - R AX I EEEE E EEEEE E EEEEEE E EEE A GA K 8871 0 55756 1 163848 4 5838 U M S 6543 5 34869 6 010404 3 2404 QM . OT 8721 2 22636 7 331512 1 3315 RA - 2 F
)
9 SS EE - - . = SS = 4543 3 45545 4 565555 4 5655 OA 0000 0 00000 0 000000 0 0000 DG L - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEE E TD 8471 9 38756 7 193848 3 5538 L OO 6443 4 30869 5 060404 3 2904 B TB O ' 8621 2 22636 7 321512 1 3215 N . ' _ ) Y N N S N A ) O O R O ) N S I ) I E I S H R T S T T T R T- E P R P E P E A= T M E M M M T P- E U T U U E S E S . S N M D M_ NN M NN 0 NN O N . OO OO 0 OO I . A 0 CI . CI 0 CI T 0 TN _ N 0 0 L IEP T 0 0 L IEPO 8 L TNP IEPOM 0 2 L IEP O 1 NDLM 9 NDLMI T NDLMIU 4 NOLMI I OSBU 1 OSBUT A OSBUTS OSB
- T T I AS I ASP I ASPN T I
- A A TOTN T TOTNM R TOTNMO A TOTNM C ATEO A ATEOU O ATEOUC ATEO O _ R L GC L L GCS T L GCS R L L O AEE AR AEE' N C AEE NK O AEE NL T HRVE MO HRVEO E HRVEOL TT RV E C MU C IT=NU CC NS NU CCI AC NU CCM R E ISYU NC ISYU O ISYU M OE ISYU U NS OFD OFDT
_ AE- CH OFDT GS OF S _ E RPAO L S- RPAOA L T RFAOAM L RPAO O- DH IXER A T - IXERE A KU IXEREO A KH XE _ P- RN AELP T AH AELPM T LO AELPMC T LS AELP _ X- AM O EN- O IS O IS _ E- G( T N( - T M( T M( _ um _ 'I
3500 3 46000 4 560003 3 560003 D 0000 0 00000 0 000000 0 000000 TI - - ++ - - - +++ - - +++- - - - +++- ND EEEE E EEEEE E EEEEEE E EEEEEE E AR 4100 8 12000 0 700001 7 910003 FY 6400 6 23000 3 720000 0 030000 NH . . . . IT 1300 1 49000 4 510003 3 610004
- 3533 2 46344 5 564454 4 564454
- D 0000 0 00000 0 000000 0 000000
- TI - - - - - - - - - - - - - - - - - - - - - - -
- LO EEEE E EEEEE E EEEEEE E EEEEEE E
- UR 4186 0 22966 7 000281 3 018212 DY- 2415 1 73672 1 722012 5 233035 AH- . . . .
T: 2362 1 59162 3 712134 8 812135 S N O 3543 3 46444 3 565555 4 565555 I 0000 0 00000 0 000000 0 000000 T E - - - - - - - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E S NC O- 7117 2 82949 7 200912 8 410915 E IO B 3453 4 93121 2 228483 2 638487 7 S DL - A U - 1342 4 39161 1 511914 2 511918 E LE - L CR - E XU = R ES - (O . S P = - 3543 3 46444 3 565555 4 565555 U SX = 0000 0 00000 0 000000 0 000000 G TE G - - - - - - - - - - - - - - - - - - - - - - - U N N EEEE E EEEEE E EEEEEE E EEEEEE E 8 N EE U _ 8197 3 12849 7 609910 8 8199l3 1 I UT L _ 5443 4 03121 227483 2 6374a7
- T LI .
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N FS) - _ 1342 4 49161 1 511914 2 511a B. O FFM . 1 C EFE OR E 8 S M L 8 UM( B 9 OU - 3543 3 45444 3 565555 4 565555 A 1 EM - 0000 0 00000 0 000000 0 000000 T SI N- - - - - - - - - - - - - - - - - - - - - - - - R AX I - EEEE E EEEEE E EEEEEE E EEEEEE E E GA K- 7197 3 80849 7 229910 8 449913 T M S- 5043 4 91121 2 247483 2 657487 R M - . , . A OT - 1442 4 31161 1 511914 2 511918 U RA - Q F
)
SS 2 EE - SS - 3545 3 46444 3 565555 4 565555
# OA - 0000 0 00000 0 000000 0 000000 DG - L - - - - - - - - - - - - - - - - - - - - - - - -
- AY- EEEE E EEEEE E EEEEEE E EEEEEE E E TD 7197 2 82849 7 209910 7 419913 L OO 5443 4 93121 2 227483 2 637487 B TB . . .
O _ 1342 4 39161 1 511914 2 511918 N - _ _ ) Y _ N N S N N A _ ) O O R O ) O H S I ) I E I S I H R T S T T T R T T E P R _ P E P E P _ A T M E _ M M M T M P E U T U U E U
- M S E S . S N M S
- D NN M NN 0 NN O NN
- N . OO OO 0 OO I . OO T
= A 0 CI . CI 0 CI T 0 CI 0 L T 0 L TN L TNP 0 L TNM N 0 IEP 0 _ IEPO 8_ IEPOM 2- IEPOU O 1 NOLM 9- NOLMI T NOLMIU 4- NDLMIS I OSBU 1 - OSBUT A OSBUTS - OSBUTN T TI AS - I ASP I ASPN T I ASPO A A TOTN T TOTNM R TOTNMO A TOTNMC C ATEO A ATEOU O ATEOUC ATEOU
_ O RL GC L L GCS T L GCS R L GCSK L O AEE AR AEE N C AEE NK O- AEE NL T HRVE MO HRVEO E HRVEOL TT HRVEOI AC,NU CCM
-. E C NU C IT- NU CC WS NU CCI
- R E ISYU NC ISYU O _ ISYU H OE ISYU
- U NS- OFD AE- OFDT CN OFDT GS- OFDTT
- 5 E RPAO L S RPAOA L T RPAOAH L - RPAOAA
- 1 DH IXER A T IXERE A KU IXEREO A KH IXEREO A
- P RH AELP T AH AELPM T LO AELPMC T LS- AELPMG
- X- AN- O EN- O IS O IS-
- E- G( - T M( - , T H( T M( -
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A- -
- 3500 3 45000 4 560003 3 5600 D 6000 0 00000 0 000000 0 0000 TI - ++ - - - +++ - - - +++- - - -
= NO EEEE E EEEEE E EEEEEE E EEEE AR 4500 4 71000 7 890006 5 7600 FY 4800 5 30000 6 680003 4 1200 NH . 1 IT 2900 2 63000 6 830004 4 9400 1 .
.)
~
- - 3533 2 45334 3 464454 3 4644
- - D 0000 0 00000 0 000000 0 0000 TI - - - - - - - - - - - - - - - - - - -
LO UR EEEE E EEE"EE E EEEEEE E EEEE 9565 0 31563 7 899033 6 6660 DY 3859 6 80404 7 181681 2 2246 AH - . T 3983 1 83213 4 133146 1 1431 2 ' S - N ' S O _ 3543 3 45444 3 565455 4 5654 E I 0000 0 00000 0 000000 0 00000 S T - E - - - - - - - - - - - - - - - - - - - - A GA N EEEE E EEEEE E EEEEEE E EEEE E NC O 4588 1 11899 3 393050 1 9630 L IO B 4896 9 30888 0 288588 6 8285 E DL - . ~ R U - 2963 6 63191 2 832126 3 8421 LE - S CR U XU O ES U (O - N P - 3543 3 45444 3 565455 4 5654 I SX 0000 0 00000 0 000000 0 0000 T TE G - - - - - - - - - - - - - - - - - - - - N N N EEEE E EEEEE E EEEEEE E EEEE 9 O EE U 5568 3 61799 3 092058 1 6620 1 C UT - L 4896 9 30888 0 388587 6 9285
- LI -
+ FS) - 2963 6 63191 2 832126 3 8421 B. FFM- -
l ' - 1 H EFE-
& C E T S OR M .-
A UM( L - B B OU - 3443 3 45444 3 565455 4 5654 A EM 0000 0 00000 0 000000 0 00003 T 8 SI N - - - - - - - - - - - - - - - - - - - - 8 AX I EEEE E EEEEE E EEEEEE E EEEE 9 GA K 4668 3 15799 3 382058 2 9220 1 M S 4196 9 35888 0 258587 6 8085 M . R OT 2163 6 63191 2 842126 3 8521 E RA - - ' T F R
~
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A SS U EE x Q SS 3543 3 45444 3 565455 4 5654 OA 0000 0 00000 0 000000 0 00000 DG L' - - - - - - - - - - - - - - - - - - - - 2 AY EEEE E EEEEE E EEEEEE E EEEE E TD 4568 1 11799 3 392058 0 9620 0 L OO 4896 9 30888 0 288587 6 8285 B TB __ O 2963 6 63191 2 832126,3 8421 N ' - Y - N N N N z A N H
- O I
T O I O I O I T T T T P P P' P
- A M M M M
- P U U U U
- S S S N S D NN NN NN O N N OO OO OO I O A CI CI CI T C L T L TN L TNP L N IEP IEPO IEPOM IEP O- N NOLM N NDLMI N NOLMIU N NOLMIS I O OSBU O OSBUT O OSBUTS O OSBUT T I I AS I I ASP I I ASPN I I A
- A T- TOTN T TOTNM T TOTNMO T TOTNM C A- ATEO A ATEOU A ATEOUC A ATEOU O CL GC LC L GCS C L GCS C L G L O AEE AO AEE N O AEE NK O AEE L- HRVE ML HRVEO L HRVEOL TL HRVE E NU C I NU CC N NU CCI A NU C f _ R- M ISYU NM ISYL OM ISYU M OM ISYU U- NU OFD AU OFDT CU OFDT GU OF S EM RPAO L M RPAOA L M RPAOAN L M RPAOA O DI =IXER A TI IXERE A KI IXEREO A KI IXERE P . RX AELP T AX AELPM T LX AELPMC T LX AELPMG X- AA O EA - O IA O IA E. - GM T MM T MM T MM
,s l uo tl l'
li Ii D 2264432 2 5 I 0000000 0 0 _ O - - - - - - - - - _ _ R EEEEEEE E E _ Y 6962047 6 7 _ H T 1128715 9 4
- 2244432 2 5 -
L - 0000000 0 0 AY- - - - - - - - - - M TD- EEEEEEE E E S O OO- 6463800 2 0 E R TB- _ S F - 1121611 4 2 _ A - _ E ) - _ 8L ES _ .. 8E LT _ - 9R IN - 1 ME U S U) 2 RU 0LM
- EO 5FE _
B. TU (FR RN E-1 E L B A AI UT QN DC N O E N SSA OUM DO( NS E T O+ OA C IG EH T SC A T L A U - N B P Y O ) O A I N P H T O H P S - T M R - A U E P S P NN / E - OO N R _ CI E U - L TNN R S IEPOO M O HNOLMII ( P DOSBUTT X II ASPP E E STOTNMM S RATEOUU O EL GCSS D _ MAEE NN _ BHRVEOO E
- UNU CCC G
- SISYU L A OFDTK A R RRPAOAL T E
_ IIXEREI O V _ AAELPMM T A l
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l I Sheet 1 of 2 id. TABLE 1.B-21 PARAMETERS USED IN CALCULATING DOSES FROM GASEOUS EFFLUENTS (Second Half 1988) 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 Aninal butchering to~ consumption 20.0 Food ingestion by animal to milking 2.0
' Accumulation time on ground 7,300.0 Human Consumption Rates (kg/yr)
Leafy vegetables by adult 64.0 Produce by adult 456.0 Heat by adult 110.0 Milk by adult 310.0 Milk by infant 330.0 Breathing Rates (m 3fyp) Adult 8,000,0
' %(- T Infant 1,400.0 Animal Consumption' Rates (kg/ day)
Animal feed by meat animal 50.0 Animal feed by milk cow 50.0 Animal feed by milk goat 6.0 Exposure' Periods During Growing Season (days) Leafy vegetables 60.0 l Pasture vegetation 30.0 Produce 60.0 h l Residential Structure Shielding Factor 0.7 Fraction of Particulate Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulate Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 1 Fraction of Iodine Deposited on Produce 1.0 l Surface Density of Soil for Root Zone (kg/m 2) 240,o i 1 . Field Decay Half Life (days) 14.0
\ .
60 I h. o Q_---._-.__-_.______._____
i i
)
l TABLE 1.B-21 Sheet 2 of 2 i Parameter Value A 5ricultural Productivity (kg/m 2) Leafy vegetables 2.0 Pasture grass 0.7 l Produce 2.0 1 Period of Long-Term Buildup for Activity in Soil (days) 7,300.0 1 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 Graras en Pasture 0.5 Fraction of Daily Feed that is Pasture Grass when Animal Crazes 1.0 l O l' 61 0 L__________
l TABLE 1.B-22 9 PARAMETERS USED IN CALCULATING DOSES Sheet 1 of 2 FROM LIQUID EFFLUENTS Value Parameter 3rd Otr 1988 4th Otr 1988 Plant Dilution Flow Rate (gpm) 29,900. 33,900. Columbia River Flow Rate (cfs) 109.094. 94,454. Dilution Factors Deinking water 1,638. 1,251. Swimming water 360. 275. l[ Aquatic bio *a c Shoreline sediment 360. 360. 275. 275. Irrigation water 1,638. 1,251. Milk and meat animal water 1,638. 1,251. Decay Times (days) Discharge to drinking water 0.82 0.87 Discharge to swimming water 0.0 0.0 Discharge to aquatic biote consumption 1.0 1.0 Discharge to deposition on shoreline sediment 0.0 0.0 Dischkege to irrigation water withdrawal 0.82 0.87 9 Discharge to milk and meat animal water withdrawal 0.82 0.87 Leafy vegetable harvest to consumption by man 1. Produce harvest to consumption by man 60. Stored feed harvest to consumption by animals 90. Pasture grass to consumption by animals 0. Animal butchering to consumption 20. Food and water ingestion by cow / goat to 2. milking Accumulation Times (days) Shoreline sediment 7,300. Irrigated soil 7,300. Irrigated vegetables 60. Pasture grass 30. Adult Consumption Rates (kg/yr) Drinking water 730. Fish 21. Invertebrates (crayfish) 5. Irrigated leafy vegetables 64. Irrigated produce 456. Cow's milk from irrigated pasturelt.nd 310. Goat's milk from irrigated pasture!.and 310. Heat from irrigated pastureland 110. O 62
i i l TABLE 1.B-22 Sheet 2 of 2. Value Parameter 3rd Otr 1988 Ath Otr 1988 , Annual Exposure Times (hr/yr) l Swimming and boating 12. Shoreline activities 12. Irrigated pasture 2,190. Infant Consumption Rates (kg/yr) Drinking water 330. , Cow's milk from irrigated pastureland 330. Fraction of Year Animals Graze on Pasture 0.5 i Fraction of Year Crops are Irrigated 0.5 Field (Weathering) Half-Life (days) 14. Irrigation Rate (liters /m 2-hr) 0.104 Fractional Concentration of Water in Soil (g/g) 0.2 Fraction of Leaf-/ 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 Produce Pasture Grass Yield (kg/m 2) 0.7 [ Vegetable Yield (kg/m 2) 2.0 Surface Density of Soil (kg/m 2) 240.0 Animal Consumption Rates (hg/ day) Water by milk cow 60. Water by milk goat 8. Water by beef 50. Pasture vegetation by milk cow 50. Pasture vegetation by milk goat 6. I Pasture vegetation by beef 50. 63 i
l L - - - AS- 53468 3 - 54579 665455 44 RNN- 00000 0 - 00000 000000 00 ERA- - - - - - - - - - - - - - - - - - - - - s HEG- EEEEE E - EEEEE EEEEEE EE TTR- 31646 4 36740 073662 83 ONO- . 7U - I - 32223 2 34558 773212 88
- D- 50000 5 50000 000055 55 -
- TI- 00000 0 00000 000000 00
- NO- - ++++ - ++++ ++++- - - - -
AR- EEEEE E , EEEEE EEEEEE EE -
- FY- 90000 9 90000 0000l6 40 -
- NH- . . -
IT- 20000 2 20000 000036 96 - D 55568 5 _ 56679 665655 55 _ TI 0 00000 000000 00 00000 _
- LO - - - - - - - - - - - - - - - - - - -
UR- EEEEE E EEEEE EEEEEE EE DY-AH-T- 10.l46 22223 6 4 14640 24458 021001 721512 76 76
- 55568 4 -
55579 665555 45 _ _ - 00000 0 00000 000000 00 E - - - - - - - - - - - - - - - - - -- N EEEEE E EEEEE EEEEEE EE 43246 5 42640 046002 18 O_ B_ 25723 1 21158 731112 19 S T - _ N - 55568 5 _ 56679 665565 55 - E 00000 0 _ 00000 000000 00 - U G - - - - - - - - - - - - - - - - - - - - - 8 L N EEEEE E - EEEEE EEEEEE EE 8 F U 12146 53 3 9 F L . 6 -
- l.6840 0 3.l.2 9 1 -
2 1 E 21323 6 - 22658 721192 87 V1 R D) B. E IM T UE R QR _ E A IM 55568 5 56678 665655 55 L U L( 00000 0 00000 000000 00 _ B Q N- - A M I EEEEE E EEEEE EEEEEE EE T 3 O R K S 11.l.90 6 15630 3 2.l.0 0 1 97 9 ~ 22229 6 24462 821512 76 L _ - S O D 55568 5 56679 665655 55 - L 00000 0 00000 000000 00 - AY - - - - - - - - - - - - EEEEE EEEEEE EE TD EEEEE E - OO- 11146 5 0 2.l.0 0 1 76 TB l.5640 _ 22223 6 24458 721512 76 _ N _ T T G NO _ N N N N L OI E O E I I IT M I_ M R ON TP I T I E SO PM D A D T I MU N NE C NE A LT US O OS O OS H AP ) SN _ I I L I RM )T NO Y T TE TE K UU HA OC _ A- A PNG L PNG C TS OO C _ N- C MIN A MIN O LNN CG K _ H- O ULI R ULI T UOO (( KL T L SET U SET S CCI LI A NNRA T NNRA E I TNNN IM P _ OOOO L OOOO V REPOOO LM _MU RICHB U RICHB I GLMIII A T _M ET S _ C ET S L ABUTTT THA E_I R U X TPE D AMTON I R TPE D AMTON D ASPPP OOO OTNMMM TCG S A HUATA L G HUATA N TEOUUU O M SR A A SR A GCSSS LGG _ _ P GNBEG T _GNBEG EE NNN ANN RVEOOO _ X T NOERN O T NOERN N RII - E A ICTUI T A ICTUI O U CCCC UDD V K RSM _ K RSM I SYU TUU OFDTKK _ C NHEOM C C NHEOM T LLL I ISVPI I I ISVPI A PAOALL UCC . T RINXH T T RINXH G XEREII CXX _ A DFIES A A DFIES I ELPMMM IEE _ U U U R R Q Q Q R G A A - A I A E . l - _
D_ 53658 77656 3 6 I 00000 00000 0 0 O - - - - - - - - - - - - R EEEEE EEEEE E E Y 69123 74930 1 0 - H - T 81919 18651 2 1 - 53658 77656 3 6 L 00000 00000 0 0 AY - - - - - - - - - - - - M _ TD EEEEE EEEEE E E _ O < OO 50123 1 0 R TB 7 4 9.I.0 F 82919 18651 2 1
)
8 E _ 8 LS 9 IT _ 4 1 MN . 2 E)
- R 0UM _
E 5LE B. T (FR 1 R F- _ A EEN T _ N E U S A _ L Q ODM E _ B DI( M _ A D U I L T R NQ D G I I OI E NN O H IL S IO S T T _ RI A ,. ND ET D L OE TP E U IT AM T P Y TA HU A ) O A PNG S N N P N MIN KNN I O H UMI COO M S T SAT OCI A R A NNTA T TNNT E P OONO SEPOON P RICOB ELMIIO M
/
E ET C VBUTTC R TPE D IASPP E U AMTON LTNMMO R S HUATA EOUUT M O SR DGCSS ( P GNBEG NE NNE E X NOERN AVEOOR __ E ICTUI CCCU S K RSM NYU S O D HHEOM OFDTKO iSVPI IAOALP CRINXH TEREIX E IDFIES ALPMME G T G L A A I A R U R T E Q R O V A I T A I
, , 1 1 i
I4 , e 'j l, ' d L;,1 - 1< g N' ,) L '1 j ,, TABLE 1.B-25
-]
- n- fa '
j p--Qlt "; THIP.D QUARTER 1988: o RATCH RELEASES.
?l%.}h
- \
lj ;;s ' , . . .\ H DOSES FROM, NOBLE GASES:AT t l ' SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION- ,
^\
b Site .
-Boundary [al. Residence [b]L !
!g
-\
. Beta' Air Dose (mrad) 6.8E-3' 3.1E-3 Gamma' Air Dose (mrad)- 2;6E-3 -8.3E-4 Beta + Ganem Skin Dose (mrem). --
2.0E-3 Gamma Total' Body Dose (mrem) - 7.1E 4 [a') ESE sector lat 805 meters.
~'
[b] ESE sector.at 1300 meters.
.ll s
3 66 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ .)
J TABLE 1.B'-26 THIRD QUARTER 1988 , CONTINUOUS RELEASES ,
~
-l' DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF l HIGHEST CONCENTRATION Site Boundary [a] Residence [b]
Beta Air Dese (mrad)' 1.9E-2 9.4E-3 Gamma Air Dose (mrad) 6.8E-3 2.3E-3 Beta + Gamma Skin Dosn (mrem) - 5.5E-3 Gamma Total Body Dose (mrem) - 2.0E-3 [a] ESE sector at 805 meters. [b] ESE sector at 1300 meters. O i O 67
I TABLE 1.B-27
- r~3 THIRD QUARTER 1988
( i' BATCH + CONTINUOUS RELEASES
' u) '
I' DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a} Residence [b]- Beta Air Dose (mrad) 2.6E-2 1.2E-2 Gamma Air Dose (mrad) 9.4E-3 3.2E-3 Beta + Gamma Skin Dose (mrem) - 7.4E-3 Gamma Total Body Dose (mren) - 2.7E-3 [a] Maximum site boundary location. [b] Maximum residence location.
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iI 7 : L . 6976 6 79767 5 707777 6 _ 707777 6 - AS- 0000 0 00000 d 010000 0 010000 0 - RNN- - - - - - - - - - - - - - - - - - - - - - - - - - ERA - EEEE E EEEEE E EEEEEE E EEEEEE E HEG 3915 5 72617 0 256099 4 256099 8 _TTR _ONO I' - 5160 3 2474 7 51646 8 82212 2 083332 441713 7 1 083336 0 441716 2 e - 6900 6 79000 7 700006 6 740005 5 - D 0000 0 00000 0 010000 0 910000 0 - TI - ++ - - +++ - - +++- - - +++- - - NO EEEE E EEEEE E EEEEEE E EEEEEE E AR 3900 4 32000 5 750009 8 750004 7 FY 8100 8 21000 2 980009 2 980000 0 NH- . IT- 1400 1 62000 6 240007 8 240001 1 . 6966 5 69667 6 707776 6 707776 6 _ D 0000 0 00000 0 010000 0 010000 0 TI- - - - - - - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 6999 1 02082 9 456624 6 4S6627 9 _ DY- 9191 2 01441 2 782472 2 782477 7 AH _. T 2444 1 12214 5 446711 3 446711 3 S - N O 6976 6 79767 6 707777 6 707777 6 I 0000 0 00000 0 010000 0 010000 0 _ T E - - - - - - - - - - - - - - - - - - - - - - - - - GA N- EEEE E EEEEE E EEEEEE E EEEEEE E NC O 3985 4 62417 9 256098 3 256098 7 IO B 5150 3 51646 7 083332 7 083336 0 S DL E U 2474 7 82212 '2 441713 1 441716 2 S LE A CR E XU - L ES - E (O - R P 6976 6 79767 6 707777 6 707777 6 SX 0G00 0 00000 0 010000 0 010000 0 H TE G - - - - - - - - - - - - - - - - - - - - - - - - - 8 C N N= EEEE E EEEEE E EEEEEE E EEEEEE E 2 T EE U- 3965 4 62317 9 256098 3 256097 7 A UT L 5150 3 51646 7 083332 7 083336 0 9 B LI B. FS) 2474 7 82212 2 441713 1 441716 2 1 8 FFM 8 EFE E 9 OR- . L 1 S M- _ UM( - - B R OU 6976 6 79767 6 707777 6 707777 6 _ A E EM 0000 0 00000 0 010000 0 010000 0 _ T T SI N- - - - - - - - - - - - - - - - - - - - - - - - - - R AX _ I EEEE E EEEEE E EEEEEE E EEEEEE E A GA _ K 3965 4 67317 9 296098 3 296097 7 _ U S _- _ M 5050 3 55646 7 083332 7 083336 0 QM _ OT _ 2574 7 82212 2 451713 1 451716 2 RA _ 3 F
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0 SS EE SS 6976 6 79767 6 707777 6 707777 6 OA 0000 0 00000 0 010G00 0 010000 0 DG L - - - - - - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEEEE E - E TD 3965 4 62317 7 256098 3 256097 7 L OO 5150 3 51646 7 083332 7 083336 0 B TB O 2474 7 82212'2 441713 1 441716 2 N
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Y N S N N N A ) O R O ) O ) O N S I E I S I S I H R T T T R T R T T E P E P E P E P A T M M M T M T M P E U U E U E U N M S . S M S N M S O D NN 0 NN NN O NN I N . OO 0 OO . OO I . OO T A 0 CI 2 CI 0 CI T 0 CI P 0 L T 3 L TN 0 L TNP 0 L TNM - N 3 IEP IEPO 0 IEPOM 0 IEPOU O 2 NOLM T NOLMI 8 NOLMIU 8 NDLMIS I OSBU A OSBUT OSBUTS OSBUTN T T I AS I ASP T I ASPN T I ASPO _ A A TOTN R TOTNM TOTNMO A TOTNMC C ATEO O ATEOU A_ ATEOUC ATEOU 9 O R L GC LT L GCS R L GCS R L GCSK L O AEE AC AEE N O AEE NK O AEE NL T HRVE ME HRVEO T HRVEOL TT HRVEOI E C NU CC HC AC NU CCM R E NU C ISYU IS_ N ISYU OE NU CCI ISYU M DE ISYU OFDTT U NS OFD AH OFDT CS OFDT GS S E RPAO L T RPAOA L RPAOAH L RPAOAA L O DE IXER A TU IXERE A KE IXEREO A KE IXEREO A P RS AELP T AO AELPM T LS AELPMC T LS AELPMG T X AS O ES O IS O IS O - E G( T M( , T M( T M( T - oe 11 lt
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3643 3 46444 3 474454 4 4744 D- 0000 0 00000 0 000000 0 0G00 TI - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEE UR 5987 9 41213 1 583183 4 5831 DY 0965 5 56258 1 522635 4 5226 _ AH _ T 1291 3 51581 2 131252 8 1312 S - N - O . 4643 3 46444 3 475454 4 4754 I 0000 0 00000 0 000000 0 0000 T E - - - - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEE S NC . O 5906 2 01779 8 281006 5 2810 E IO B 6995 8 16545 6 428691 1 4286 S DL . A U 9221 2 51181 1 134241 G 1342 E LE ' L CR E XU - R ES - (O . ' - ~ S U SX P _ 4643 3 0000 0 4 6 4'44 3 475454 4 4754 00000 0 000000 0 0000 G TE G - - - - - - - - - - - - - - - - - - - - U N N EEEE E EEEEE E EEEEEE E EEEE 9 N EE U 6985 1 11609 7 288895 3 2888 2 I UT L 6985 8 16545 6 427581 1 4275 T LI . .
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- I EEEE E EEEEE E EEEE2E E EEE E GA -
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SS 4643 3 46444 3 475454 4 4754 0 OA : 0000 0 00000 0 000000 0 0000 DG L - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEEE E TD 5985 1 01609 7 288395 3 2888 L OO 6985 8 16545 6 427581 1 4275 B TB O
- 9221 2 51181 1 134241 6 1342 N
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Y- - N S N . N A- ) O R O ) O ) H S I E I S I S N R T T T R T R T E P E P E P E A T M M M T M T P E U U E U E U M S . S M S N M S D . NN 0 NN NN O N N _ . OO 0 OO . OO I . O A 3 CI 2 CI 0 CI T 0 C 0 L T 3 L TN 0 L TNP 0 L N 3 IEP IEPO 0 IEPOM 0 IEP O 2 NOLM T NOLMI 8 NOLMIU 8 NOLMI OSBU A OSBUT OSBUTS OSBU I _ T _ T I AS I- ASP T I ASPN T I A A A TOTN R TDTNM A TOTNMO A TOTNM C ATEO O ATEOU ATEOUC ATEO O R L GC LT L GCS R L GCS R L G L O AEE AC AEE N O AEE NK O AEE NL T HRVE ME HRVEO T HRVEOL TT,HRVEOI E C NU C IS MU CC MC NU CCI AC=NU R __ E ISYU N - ISYU OE ISYU M OE ISYU U S _ O NS E DE RPAO OFD IXER A TU IXERE L AH-T RPAOA OFDT L CS RPAOAN OFDT L GS RPAO OF A KE IXEREO A KE IXEREO A _ - P RS KELP T AO AELPM T LS AELFMC T LS- AELPM
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__ I 9221 2 51181 1 134241 6 134242 7 4600 4 46000 4 570003 3 570003 D 0000 0 00000 0 000000 0 000000 TI - ++ - - - +++ - - - +++ - - - +++- NO EEEE E EEEEE E EEEEEE E EEEEEE E AR 8900 1 31000 4 780002 1 780000 FY 0900 1 26000 2 020004 5 020000 NH . . . IT 6200 6 31000 3 930001 1 930002 2 5643 3 46444 3 474454 4 474454 4 D 0000 0 00000 0 000000 0 000000 TI - - - - - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 5937 0 51423 2 584204 7 584202 DY 0975 6 56258 1 522645 4 522640 9 AH . T 1291 3 51581 2 131252 8 131254 9 S N S O 4643 3 46444 3 475454 4 475454 4 E I 0000 0 00000 0 000000 0 060000 S T E - - - - - - - - - - - - - - - - - - - - - - - - A GA N EEEE E EEEEE E EEEEEE E EEEEEE E E NC O 8916 3 11789 8 282116 7 282117 L IO 6995 8 16545 6 428691 1 428693 3 E DL B_ . . R U _ 9221 2 51181 1 134241 6 134242 7 LE S CR U XU O ES U (O N P 4643 3 46444 3 475454 4 475454 I SX , 0000 0 00000 0 000000 0 006000 T TE G - - - - - - - - - - - - - - - - - - - - - - - - N N N EEEE E EEEEE E EEEEEE E EEEEEE E 0 O EE U 9995 2 21619 7 289905 5 289906 3 C UT L 6985 8 16545 6 427591 1 427593 LI
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H EFE C OR E T S M L A UM( B B OU 4643 3 46444 3 475454 4 475454 A EM 0000 0 00000 0 000000 0 000000 T 8 SI _ N - - - - - - - - - - - - - - - 8 AX _ I EEEE E EEEEE E EEEEEE E EEEEEE E 9 GA _ K _ _ 8595 2 11619 7 209905 5 209906 1 M _ S _ 6585 2 19545 6 497591 1 497593 3 M . . R OT 9321 2 51181 1 134241 6 134242 7 E RA T F R ) A SS V EE O SS 4643 3 46444 3 475454 4 475454 4 OA 0000 0 00000 0 000000 0 000000 DG L - - - - - - - - - - - - - - - - - - - - - - - - 3 AY EEEE E EEEEE E EEEEEE E EEEEEE E E TD 8995 2 11619 7 289905 5 289906 9 L OO 6985 8 16545 6 427591 1 427593 3 B TB . . O 9221 2 51181 1 134241 6 134242 7 N Y N _ N N N A O _ O O O N I I I I H T T T T T P P P P A M M M M P U U U U N S S S N S O D NH NN NN O NN I N OD OO OO I OO T A CI CI CI T CI P L T L TN L TNP L TNM N IEP IEPO IEPOM IEPOU O N NOLM N NOLMI N NOLMIU N NOLMIS _ I O OSBU O OSBUT O OSBUTS O OSBUTN _ T I I AS I I ASP I I ASPN I I ASPO _ A_ - T TOTN T TOTNM T TOTNMO T TOTNMC C= A kTEO A ATEOU A 5TEOUC A TEOU _ O- C L GC LC L GCS C L GCS C L GCSK _ L= O AEE AO .AEE . N O EE NK O AEE NL _ - L HRVE ML- HRVEO L HRVECL TL bRVEOI _ E- NU C I NU CC H NU CCI A NU CCM R- M ISYU NM ISYU OM ISYU M OM ISYU OFDT CU OFDT GU OFDTT _ U-S- O-NU EM RPAO DI OFD IXER A L AU-TI M RPAOA IXERE A L M RPAOAH KI 5XEREO A L M RPAOAA KI kXEREO A P- RX AELP T AX AELPM T lX AELPMC T LX kELPMG _ X- AA O EA- O iA~ O IA _ E- GM T MM- T MM~ T MM y-
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- 65322 1 61746 573126 21
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TABLE 1.B-34 FOURTH QUARTER 1988 BATCH RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] Residence [b] . Beta Air Dose (mrad) 3.1E-2 1.7E-2 Gamma Air Dose (mrad) 1.3E-2 4.8E-3 Beta + Ganna Skin Dose (mrem) - 1.1E-2 Gamma Total Body Dose (mrem) - 4.2E-3 [a] North sector at 663 meters. [b] North sector at 1000 meters. O 75
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TABLE'1.5-35
,:iV)i '
FOURTH QUARTER 1988 CONTINUOUS RELEASF.S
. DOSES FRON NOBLE GASES AT
' SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION i
Site Bounderg[a] Residence!b] Beta Air Dose (mrad) 5.1E-2 2.7E-2 Gamma-Air Dose (mrad) 1.9E-2 .7.0E-3 Beta + Gamma Skin Dose (mrem). - 1.6E-2. Gamma Total Body Dose (mrem) - 5.9E-3 [a] North sector at 663 meters. [b] North sector at 1000 meters. o e e
- O 76
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TABLE 1.B-36 FOURTH QUARTER 1988 9 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AED RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidencelDI Beta Air Dose (mrad) 8.2E-2 4.3E-2 Gamma Air Dose (mrad) 3.2E-2 1.2E-2 Beta + Gance Skin Dose (mrem) - 2.7E-2 Gamma Total Body Dose (mrem) - 1.0E-2 (a) North sector at 663 meters. [b] North sector at 1000 meters. 9 l 77
fM l ( - 3500 3 36000 3 4600O2 2 46O0 D _ 0000 0 80000 0 0000S0 0 00P0 TI - ++ - - - +++ - - +++- - - - NO EEEE E EEEEE E NEEEEE E EEE
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3523' 2 46344 3 '465553 3 4655 D_ 0000 0 00000 0 000000 0 0000 TI . - - - - - - - - - - - - - - - - - - - - LO EEEE E EEEEE E EEEEEE E EEE UR 4541 9 47889 6 746047 8 7460
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1 8 EFE 9 OR E 1 S M-L UM( - . 1 B R OU - . 4543 3 56546 4 6 6 6'566 5 6665 A E EM - 0000 0 00000 0 000000 0 0000 T T SI - N - - - - - - - - - - - - - - - - - - - - R AX - ; EEEE E EEEEE E EEEEEE E EEEE A GA - k 2410 3 58163 3 560901 9 5609 U M - S- 0076 1 88224 1 028209 8 0282 QM - OT - 1531 2 16529 3 419428 6 4194 RA - 4 F
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8 SS EE ' SS 4543 3 56546 4 666566 5 6665 OA 0000 0 00000 0 000000 0 0000 DG L - - - - - - - - - - - - - - - - - - - - AY EEEE E EEEEE E EEEEEE E EEE E TD 2510 2 57163 2 540901 7 5609 OO 86224 008209 8 L B TB 0176 1 1 0.n
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I - 5117 1 81212 2 237371 9 237373 _ 3500 3 46000 4 470003 3 470003
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- 3523 2 36534 3 474454 3 474453
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LO EEEE E EEEEE E EEEEEE E EEEEEE E UR 0134 4 21426 5 215148 2 215145 DY 9341 9 28059 1 928935 9 928930 AH- . . T- 6118 2 11213 5 233397 1 233391 2 S N O - 3533 2 46434 3 475454 4 475454 3 I - 0000 0 00000 0 000000 0 000000 T E- - - - - - - - - - - - - - - - - - - - - - - GA N EEEE E EEEEE E EEEEEE E EEEEEE E S NC O _ 8171 4 81677 2 914321 8 914328 E IO B _ 0348 4 88747 9 021827 0 021824 S DL - . . . . . . A U .
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= FY 0400 0 94000 9 530000 0 5300
=
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.1.C METEOROLOGICAL DATA' i
. Meteorological data for 1983 are available'for revioW in:the PGE Corporate-L Office as per Technical Specification 6.9.1.5.4.." Semiannual Radioactive Effluent Release Report". ' Meteorological 1'models and assumptions used in performing the analyses.are presented in PGE-1021, "Offsite Dose.Calculae tion Manual",
82
i, i
)
O 1.D CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) jG 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 i the Semiannual' Effluent Release Report for the period l in which the change (s) was made and shall contain:
"a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental 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 change (s);
"b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; ar.d "c. documentation of the fact that, the change has been reviewed and found acceptable by the PRB."
Report Amendment 4 to the ODCM was issued in February 1988. This amendment corrected a number of typographical errors and added clarifications to the text of the document. The amendment also included information from the 1986 Land-Use Census, as well as the 1984 and 1985 Annual Effluent Reports. No change to either the method or models or to the determina-tion of any setpoints was created by this amendment. Pages 84 through 110 of this report contain the new pages of Amend-ment 4 to the ODCM with appropriate amendment lines. The documentation of Plant Review Board (PRB) review and approval of this amendment is included as Page 111. l O 83
V t The term F , the near field average dilutien fcette, is d:tsemin d es g follows for time period AT g:
, , liquid radioactive waste discharge volume total Plant discharge volume x Plant dilution factor The Plant dilution factor accounts for mixing effects of the dilution pipe. :This value is determined in accordance with WURgG-0133 Page 16,
.as equal to:
1000 cfs , 9, average total Plant discharge The average total Plant discharge of 23,803 spa is the historical 7 average for the years 1976-1985. The totin A gj. the ingestion dose factors for any organ, are tabulated ir. Table 2-1. For simplicity and conservatism, a single maximum organ-dose factor for each nuclide was calculated using the critical organ for each nuclide.- The following equation was used in calculating the ingestion dose factors: Ag = k, +U p BF g p, (2- ) W where A = composite dose parameter'for total body or maximum organ of an adult for nuclide i, in mesm/hr per pCi/ml 6 k, = conversion factor, 1.14 x 10' = 10 pci/pci x 10 ml/kg & 8760 hr/yr Ug = 730 kg/yr, adult maximum annual water consumption rate (from Regulatory Guide 1.109 Rev. 1, 10/77, Table 3-5) 6 Approved //hm 2-2 Amendment 4 84
-/
2.5 TECHWVCAL SPECIFICATION 6.9.1.5.4 4 This section describes the method that will be used to calculate doses from liquid effluents, as required by Technical Specification 6.9.1.5.4 (Semiannual Radioactive Effluent h iesse Report). 2.5.1 CENERAL METHODOLOGY The models and non-Plant / site-specific model parameters of Appendices A through F plus Regulatory Guide 1.109 (Rev. 1, 10/77) will be utilized to I3 compute doses from liquid effluents for this Technical Specification. Computer codes utilized in the calculations will be documented, verifled and controlled in accordance with written departmental or branch procedures. 2.5.2 PLANT / SITE-SPECITIC ASSUMPTIONS Hydrologic dilution factors will be based on actual river flow rates and effluent flow rates during the reporting period. Drinking water i and agricultural exposure pathways will assume dilution into the full river flow. Other exposure pathways will assume dilution into the Plant mixing zone, which is defined as that portion of the river from the Oregon shore to a point 300 ft from the end of the active region of the diffuser pipe. s 2-9 Amendment 4 Approved E-- -
~ '
(February 1988) 85
... 1 N
Ng .= sir dose factor due to gamma emissions for nuclide i, rad /yr per Ci/sec (note that these are:" air" rads not " tissue" ^
.f reds)
'%. t / .. q
'I
[, ,Qg = noble gas activity release rate of nuclide 1. C1/sec i L L 1- l io 1000 = constant, mead / rad or arem/ rem 13'l L, 1.1 = constant, the average ratio of tissue to air energy absorption 7* coefficients with the units of rem /" air" rad. The values of Eg , Lg, N g, and N pare listed in Table 3-1. Derivation of these values'is presented in Appendices A and C. The I-131, tritium, and particulate (Tg > 8 days) dose contributions may be dete1 mined using the following general equation: DI pc = 1000 I Rt x Qt ( 3-5 ) .. i
;o ' -
,,e
,,,, = dose rat. at contro1ung ..p.sure 1o.auon. me Rg = dose factor for nuclides other than noble gases at the control-ling exposure locations (as determined in the Annual Land Use census) for critical organ and age group, res/yr per Ci/sec l
Q =,I-131 and particulate activity released of nuclide i, C1. The values of R g are listed in Table 3-2. Derivation of these values is presented in Appendix 5. As noted in Appendix B, the Rg values of Table 3-2 are from the 1984 Land Use census, and these values are still appropriate as f, L determined by the 1986 Land Use Census. 3-2 Amendment 4 Approved , tm S - (February 1988) 86
l, I, = (1/Qg) [Qp Ng i
' 1.1 = constant, the average ratio of tissue to air energy absorption coefficients with the units of rem /" air" rad.
Rg I g= (1/Qy) [ Qy Kg = gansna total body dose factor for nuclide i, rem /yr per Ci/sec l Lg = beta skin dose factor for nuclide i, rem /yr per Ci/sec j l l N = gansna air dose factor for nuclide i, rad /yr per C1/sec (NOTE: these ; i are." air" rads not " tissue" rads.) Rg = particulate dose factor for nuclide i, rem /yr per Ci/see Iodines, particulate and tritium need not be included in the computations for the waste gas decay tanks since they are included in the Fuel and Auxiliary Building exhaust continuous release. Nuclides which regaire analysis of monthly or quarterly composite samples (eg, H-3 Sr-89, Sr-90) are not considered in the calculation required by Technical Specification 4.11.2.1.2 at the time of the release. When the results from these analyses are available, they will be used to confirm that those nuclides, averaged over the sample period, did not cause violation of Technical Specification 4.11.2.1.2. i 1 3-4 I Approved - # (February 1988) 87
3.4 TECHNICAL SPECIFICATION'3.11.2.3 This section will be used to demonstrate compliance with LCO 3.11.2
- 9t least once per 31 days.
3.4.1 METHOD 1 1 I 1 Method 1 utilizes the actual I-131, partleulate (T /2 > 8 days), and tritium releases to detemine compliance with LCO 3.11.2.3 as follows: 100Q,ig<1 (3-11) 13 where .J Eg = 1/Qy IQ yRg R = dose factor for nuclide i, rem /yr per Ci/sec from Table 3-2 Qy = I Q, = total I-131, tritiunt, and particulate release rate, Ci/sec O Q,i
= cumulative quarterly release rate of each I-131, particulate, and tritium nuclide i. Ci/see Nuclides which require analysis of monthly or quarterly composite samples (eg, H-3, Sr-89, Sr-90) are not considered in the calculation required by Technical Specification 4.11.2.3.1 overy 31 days. When the results of these analyses are available, they will be used'to confirm that those nuclides, averaged over the sample period, did not cause violation of Specification 4.11.2.3.1.. . .
3.4.2 METHOD 2 (Optional) Should the doom limits of LCO 3.11.2.'3 be exceeded using Method 1, a more accurate dose calculation may be made using the methodology speci-fled in Section 3.7 to demonstrate compliance. The base period meteorology specified in Appendix C will be used if current meteorology is not readily available. 3-6 O ' Amendment 4 l (February 1988) Approved /t1 88 l
l 3.7 TECHNICAI. SPECIFICATION 6.9.1.5.4 I This section describes the method that will be used to calculate doses from gaseous effluents, as required by Technical Specification 6.9.1.5.4 (Semiannusi Radioactive Effluent Release Report). 3.7.1 CENERAL METHODOLOGY The models and non-Plant / site-specific model parameters of Appendices A g
~
through F plus Regulatory Guide 1.109 (Rev.1,10/77) will 1:e utilized to compute doses from gaseous affluents for this Technical Specification. Computer codes utilized in the calculations will be documented, varified and controlled in accordance with written departmental or branch proce-dures. 3.7.2 Pt. ANT / SITE-SPECIFIC ASSUMPTIONS Meteorological dispersion and deposition factors will be based on hourly meteorological data from the Trojan meteorological monitoring system during the reporting period. Separate meteorological factors will be derived for batch and continuous releases. The meteorological model described in Appendix C will be used. Dose receptor locatiens will be based on the results of the Annual Land Use Census (required by Technical Specification 3.12.2) for the previous year except as described in 7 Section 3.1 and Appendix B. t 3-9 Amendment 4 (February 1988) Approved s t - i
~ i 7
4.2 GASEOUS EFFLUENT MONITORS This section will be used to ensure compliance with LCO 3.11.2.1. 4 . 2 .1- SETPOINT CALCULATIONS FOR NOBLE CAS EF7LUENT CHANNELS (PRMs.1C, v O
'ID. 2C. 6A. and'65) 4.2.1.1 Method 1 Maximum setpoint values for nc.ble gas effluent channels will be based on g l 'the most limiting nuclide where the noble gas dose factors and detector efficiencies are taken into account. The limiting release rate for each nuclide is the minimum of the release rates calculated by Equations 4-7 and 4-8.
1 Qg1 (4-7) 2K g Qg1 (4-8) 0.33(Lg + 1.1 Ng ) O -e Qg = limiting release rate for nuclide: 1, in C1/sec K g = total body. dose factor for nuclide 1, in res/yr per Ci/sec Lg = beta skin dose factor for nuclide l', in rea/yr per Ci/see . , , Ng = ganna air dose f actor for nuclide, in rad /yr per Ci/sec (NOTE: these are " air" rads, not " tissue" reds). " O 1.1 = constant, the average ratio of tissue to air energy absorption coefficients with the units of rea/" air" rad. Assumed flow rates for effluent pathways are listed in Table 4-1. Detec-tor efficiencies and limiting release rates are listed in Table 4-2. The
.O-Amendment 4
' 4-5 (February 1988)
' Approved eg _
90
f. l l Fp , = primary to secondary leak rate, Ib/hr .l
- o. .
( F, = shutdown steam flow rate, 86,000 lb/hr p, = density of steam (910 psia), 3.237E-2 g/cc. For a design basis steam generator tube rupture. 3 C = 6.9 pCi/s (
Reference:
Calculation TNP 83-06, Rev. 1) RCC Fpg = 250,000 lb/hr (
Reference:
Updated FSAR Page 15.6-7) l} Therefore b6 *
- For a small tube leak in conjunction with high coolant activity levels, C = .5 y a sference: a cu a n -6 RCS Rev. 1)
O v Fp, = 5.0 spd = 1.24 lb/hr (adjusted for RCS pressure) I (
Reference:
Calculation TMP 83-06, Rev. 1) l 1 Therefore b 6 " ' f Based on these results, the high alarm setpoint is set at 100 mR/hr and the alert setpoint is set at 10 mR/hr. I ( 1 4-11
^( ,
Approved nfi-_- v f _ Amendment 4 Ql (February 1988) 91 _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . )
. TABLE 4-4 1.;
l' HISTORICAL PARTICULATE RELEASES
'v Curies Released Year Ouarter. Sr-90 Total 1977 1 5.2E-4 1.3E-2 2 8.2E-5 1.3E-2 3 2.9E-5 1.2E-3 4 2.8E-5 3.7E-4 1978 1 2.7E-4 3.6E-3 2 7.9E-5 2.0E-3 4 3 7.8E-5 5.4E-4 s
4 5.2E-5 3.8E-4 1979 1 1.1E-5 5.3E-3 2 J.8E-5 4.4E-3 1 3 5.7E-5 8.4E-4 4 1.2E-4 9.3E-3 l I 1980 1 5.1E-6 1.4E-3 I 2 5.4E-5 1.1E-2 3 5.8E-5 6.9E-4 1 4 4.6E-6 8.1E-4 1.5E-2 l 1981 1 9.0E-6 1.4E-5 2.1E-2 fs ' 2 3 4 5.2E-6 1.1E-5 9.7E-4 2.0E-3 1982 1 2.6E-5 1.8E-3 2 4.5E-4 4.3E-3 3 3.6E-5 8.7E-4 4 3.7E-4 2.1E-3 l 1983 1 1.1E-4 2.4E-3 2 3.6E-4 9.4E-4 3 5.5E-5 4.6E-4 4 5.5E-5 5.0E-4 1984 1 8.2E-5 2.1E-3 2 8.7E-5 2.2E-3 3 7.4E-5 5.2E-4 4 5.1E-5 6.1E-4 , 8 1985 1 6.6E-5 2.0E-4
. 2 1.0E-8 2.5E-5 3 5.6E-5 2.0E-4 4 4.9E-7 1.9E-6 4
o s Amendment 4 (February 1988) y ' Approved ~iV /' --- -
/
l l 5.0 ENVIRONMENTAL MONITORINC l 1 i In accordance with Technical Specification 3.12.1, the radiological ! et.wironmental monitoring stations are listed in Table 5-1 with the radial _ mileage presented to the nearest 0.1 mile. The location of these O , l stations with respect to the Trojan Nuclear Plant is shown in Figures 5-1 l
)
and 5-2. I 1 1 O, I i 1 l f ( e i j
,,, _ ,d K 93 mem.rx me i
l APPF.NDII B [f l DERIVATION OF IODINE AND PARTICULATE DOSE FACTORS I
.l DOSE FACTOR R -]
The term Rg is based on the combination of: (a) inhalation, ground. plane, vegetable ingestion, meat ingestion and milk ingestion pathways which are present at the location of maximum potential dose (ie, the controlling exposure location), (b) annual average continuous release meteorology at the controlling location, (c) the most restrictive age group (child), and (d) the critical organ for each nuclide. The controlling exposure location is dependent upon land use. Therefore, the Annual Land Use census shall be reviewed annually to determine if any changes in land use will require modification of the ag values. The following general equation is used to calculate Rg values: O Rg = 10
~
[(Rfxx/Q,)+(R x D/Qg ) + (R xD/Q,)+(RfxD/Q)+(R , x D/Qg )} (E-1)
..re Rg = total dose factor for nuclide i, rem /yr per Ci/sec Rf=inhalationpathwaydosefactorfornuclidei, 3
mesm/yr per Ci/m R = ground plane pathway dose factor for nuclide i, meem/yr per Ci/m 2 _,,e ,a R = vegetable ingsstion 1.athway dose factor for nuclide i, menm/yr per Ci/m 2 _,,e ij O \
~
Amendment 4 ( e ruary 88) j Approved 94
R = meat ingestion pathway dose factor for nuclide i,
^
meem/yr per ci/m 2 _,,e , R = goat allk ingestion pathway dose factor for
^
2 nuclide i, mrem /yr per ci/m -see it x/Q = atmospheric dispersion factor for continuous c 3 releases at controlling exposure location, sec/m D/Q = atmospheric deposition factor for continuous releases at controlling exposure location, m~ 10" = constant, rem /mrom. l Thedosefactors,Rf,R,R,R,R were derived as follows-and are , listed in Table B-1. InhalationPathwayDoseFactorRf
^'
I Rg = 1012(BR) (DFA g ) (B-2) 10-where 10 = constant, pCi/Ci (BR) = breathing rato of the receptor of child age group = 3700 m /yr (Regulatory Guide 1.109, Rev. 1, 10/77, Table E-5) (DFA g
) = maximum organ inhalation dose factor for the receptor for nuclide i, in meem/pci (Regulatory Guide 14109, Rev. 1, 10/77, Table'E-9). The total body is considered as an organ in the selection of the DFA .g
~
Amendment 4 (February 1988) 95 Approved 1 I
-l V.
.f.
e = fraction-of deposited activity retained on goat's feed grass,
.s
) 1.0 for iodine,'O.2 for particulate (Regulatory Guide 1.109, 1(G-Rev. 1, 10/77, Table E-15) t g = transport time from pasture to goat,'to milk, to receptor, 1[73 x 10 sec (2 days) (Regulatory Guide 1.109, Rev. 1, 10/77, Table E-15) t h = transport time from pasture, to harvest, to' goat, 7.78 x 10 see (90 days) (Regulatory Guide 1.109. Rev. 1, 10/77, Table E-15) 10 = constant, PCi/Ci and all other terms have been previously defined.
In the case that the milk animal is a cow rather than a goat, appropriate parameter values will be taken from Regulatory Guide 1.109 (Rev. 1, 10/77). b V The concentration of tritium in milk is based on the allborne concen-tration rather than the deposition. Therafore, the R for tritium is based on x/Q: c (s-9) R _3 = (1012, c 1,3 ) r,Q,u,,(Dn.1)ro.75(0.5/n)r where all parameters have been defined previously. Determination of Contro111nz Exposure Location The controlling exposure location is that offsite location where the combination of existing pathways and annual average meteorology would indicate the maximum potential dose. That is, the controlling exposure. individual is assumed to breath the air at the nearest residence with the highest'x/Q value, to reside at the nearest residence with the highest j l D/Q value, and to obtain all the individual's vestables, meat, and milk from the production locations with the highest D/Q values. 1 B-8 Amendment 4 { (February 1988) Approved =w 96
l Table B-2 gives the land use distance data based on the Annual Land Use II3 Census for 1986. The annual average acteorology at each of these dis-tances was derived in Appendix C and is listed in Table C-3. Should i subsequent Annual Land Use Censuses indicate a change in Table B-2 which would affect the location of maximum potential offsite dose and cause any of the R gvalues presented in Table 3-2 to increase more than 25 per-cent, all the R values will be adjusted accordingly and incorporated ,, into the ODCM for use in the subsequent year. The location changes caused d5 by the 1986 Land Use Census resulted in a maximum increase of 2'4 percent for any of the 1984 R g values. For this reason, the Rg values i presented in Table 3-2 are still those determined from the 1984 Land Use Census. Table B-3 presents the land use distance data based on the 1984 Land Use Census.
~
- Amendment 4 (February 1988)
Approved / b =-- 97
- - a a
TABLE B-2 q
-s DISTANCES FOR CASEOUS RADIOACTIVE
~I[ ] EFFLUENT EVALUATION (meters)
FOR 1986 LAND USE CENSUS' ({ Nearest Nearest Hearest y
' Receptor. Site Nearest Nearest Meat Milk Milk l Direction ~ Boundary Residence Garden Animal Cow Goat N 663 1000 1000 >S000 >8000 28000 NNE 683 3900 3900 4300. >8000 4800
'NE 820- 2600 2900 2900 >B000 >8000 ENE 688' '3900 3900 3900 >8000 >8000 E 677 2100 2300 2300 >8000 28000 ESE 805 1300 2900 2600 >8000. >0000 SE 1006 4000 4000 4000 >8000 >8000 SSE. 1649 2300 2300 4800 >8000 >8000 m S 1332 1900 2300 3200 >8000' >8000 I SSW 1241 1400 1400 1400 >8000 4200
)
'~'
SW WSW 1320 1394 2400 2300 2400 3100 2400 >8000 >8000 3100 >8000 >8000 W 951 2700 3400 2700 >8000 >8000
, WWW 1021 2700 2700 2700 >8000 >8000 NW 814 1900 1900 1900 >8000 >8000 NNW 674 1000 1000 3200 >8000 >8000 NOTE: The distances presented in this table are based on the 1986 Land -
Use Census. " '
$? 1 Amendment 4 (February 1988)
Approved %s, -- 98 1 _ - - _ _ _ _ _ - _ _ - _ _ _ . . _ . _ _ _ . . - . = . -
TABLE B-3 7 DISTANCES FOR CASEOUS RADIOACTIVE EFFLUENT EVALUATION (meters)
~:
FOR 1984 LAND USE CENSUS If, Nearsst Nearest Nearest Receptor Site Nearest Nearest Meat Hilk Milk Direction Boundary Re,sidence Carden Animal Cow __ Goat N 663 965 6758 6758 >8045 6919 NNE 683 2574 3057 4344 8045 3057 NE 820 2735 2574 2574 5792 5792 ENE 688 2253 6919 2414 . >B045 >8045
'E 677 965 2414 2414 >8045 4183 ESE 805 2574 3379 3701 >8045 3701 SE 1006 3701 3862 6919 >8045 >BC45 SSE 1649 2253 2574 7723 >8045 2574 hh S 1332 1770 3379 2735 8045 >8045 SSW 1241 1609 4505 4023 7241 4344
{ SW 1320 2092 4023 3218- 5310 5471 WSW 1394 2253 4988 2414 5310 2414'
- W 951 2735 5632 3218 3218 >8045 g WWW 1021 2735 3701 3701 >8045 5310 NW 814 1931 1770 3701 6597 >8045 L
j \, NNW 674 965 965 3379 >8045 >B045 a . . NOTE: The distances presented in this table are based on the 1984 Land , Use Census. d;
, l i
l Approved L1 _-~
~
Amendment 4 91 l (February 1988) 99
APPENDIX C O METEOROLOGY ANNUAL AVERACE METEOROLOGY (Base Period) Annual average dilution factors (x/Q) were calculated according to Paragraph C.1.c of Regulatory Guide 1.111 (Rev. 1, 7/77) for ground-level releases. Annual average x/Q values adjusted for temporal variations in the airflow of the site are presented in Table C-1 as a function of distance and direction. These values are based on AT stability data and 30-ft wind data for the 200 ft-33 ft period September 1, 1972 through August 31, 1974. Annual average deposition (D/Q) values were calculated according to Paragraph C.3.b of Regulatory Guide 1.111 (Rev. 1, 7/77) for ground-level releases. Annual average D/Q values adjusted for temporal variations in the airflow of the site are presented in Table C-2 as a function of distance and direction. These values are O based on 33-ft wind dircetion data. Annual average X/ Q and D/Q values at distances measured from the center of the Containment to the closest site boundary, residence, garden, meat animal, milk cow and milk goat within a 5-mi16 radius of the Plant are given in Tables C-3 and C-4 for each of the 22-1/2 g degree radial sectors centered on the 16 cardinal compass directions. Table C-3 reflects the locations as determined with the 1986 Land Use Census while Table C-4 is for the locations as determined with the 1984 Land Use Census. As stated in Appendix B, the Rg values presented in Table B-3 are those determined from the 1984 Land Usa Census. l l l l C-1 O Approved gy/ - Amendment 4 (February 1988)
Model Annuni average atmospheric dilution factors, x/Q, were conservatively calculated for the Trojan site based on onsite data for the period September 1, 1972 through August 31, 1974 by assuming a ground-level release using Equation C-1. This equation assumes a uniform horizontal distribution within a 22-1/2 degree sector. Stability is based on AT data. Calms were distributed based on the directional frequency of winds in the 0.6 to 1.5 mph range and were assigned a wind speed of 0.3 mph. Limited vertical mixing also was accounted for due to the mixing depth which was taken as an average of 1000 meters for the Trojan site. Cal-culations of annual average x/Q values then were adjusted for temporal variations in the airflow of the site. [) y ijk [
, (C-1)
Q g i=1 j=1 N Q ijk where 2.032
/d =
if*j* :
" 5' (C-2)
(N) ijk zj"l*' [\ 2.032 a exp
= -0.5 (C-3)
) ijk sj"ix) =0 Z,3 ,
if 0.465L i o < 1.6L (C-4) Ah"( , I * (C-5)
= if 1.6L < og (N/ ijk Ib "i*'
= rslative ground-level concentration x normalized by
[] k source strength Q for sector k, sec/m C-2 Amendment 4 Approved __ e- m, (February 1988) 101 l
- l. . k) l f Y A
= relative ground-level concentration x normalized by
[/ ijk source strength Q for stability class j, wind speed: [.
- j. '( class i, and wind direction sect.or k, sec/m 3
, / o.5H 2)1/2 2+
I,3 ='(e,3 * / with the constraint that, I zj I f3 #z j I N = total observations for data period n gg = total observations for stability class j, wind speed class i, and wind direction sector k e,) = vertical stability parameter for stability class j, meters H = height of the containment, meters L = mixing height, 1000 meters x = downwind distance, meters u g = midpoint wind speed of wind speed class i, m/sec. The values of o,j are based on curves presented in Regulatory Guide 1.111 (Rev. 1, 7/77). C-3 O' - Amendment 4 Approved ( / w-- 102
Calculations of annual average D/Q values were made as follows: [D) _ c
=
8 d ,k (C-6) G l (Qjg vQ x where [D\ = relative deposition per unit area for sector k, a
-2
_, i bk x = downwind distance, meters d -1
. = relative deposition rate per unit downwind distance, m Q
fk = reistive frequency of wind direction into sector k, dimensionless. The values of D/Q are based on the curves for ground-level releases of Regulatory Guide 1.111 (Rev. 1, 7/77). Since the straight-line flow model does not considrar the temporal vari-ation in the airflow of the site region, terrain adjustment factors for thc Trojan site were developed from calculation based on 10-min averages of wind and AT data, a straight-line model (Equation C-1) and the meth-odology presented in the NUS Corporation Topical Report NUSPUF - A Sermented Plume Dispersion Protram for the Calculation of Averste Con-centrations in a Time-Dependent Meteoro1otical Regime, NUS-TM-260, (March , 1976). These values are based on AT I " " "" 200 ft-33 ft *
- 30-ft wind data for the period August 1, 1976 through July 31, 1977.
Terrain adjustment factors were determined for downwind distances to 5 miles north and south of the plant and to distances of 3 miles west and 3.5 miles east. For distances beyond the area of analysis or for those distances where the model indicated that the terrain adjustment factor would be less than 1.0, the terrain adjustment factor was conservatively I C-4 Amendment 4 (February 1988) G Approved #,_ '._ _ 103
s set to 1.0. These terrain adjustment factors have been included in the q'~'- x/Q and D/Q values presented in Tables C-1 through C-4. Table C-5 k presents the maximum terrain adjustment factors for each annular sector for the standerd population distances from 0.5 to 4.5 miles. QUARTERLY AVERAGE METEOROLOGY Meteorological data required for the compilation of the radioactive effluent release reports in Technical Specification 6.9.1.5.4 is cal-culated at the end of every calendar quarter using the NRC computer code IOQD0Q and the methodology of Regulatory Guide 1.111 (Rev. 1, 7/77). This methodology differs slightly from the base period meteorology models in that plume reflection is unnecessary and not considered (Equations C and C-4) in calculations of average dilution factors. Equation C-2 is Also, calms are therefore considered to apply for all values of o,3 distributed based on the directional frequency of winds in the 0.75 to 1.0 mph range rather than the 0.6 to 1.5 mph range. Otherwise, the models described for the base period annual average meteorology are identical to those used for quarterly calculations. 7m ( On C-5 Amendment 4 (February 1988) Approved -
~ 104
TASLE C-3 3 SASE PEE 10D ANWUAL AVERACE / E 0 (sec/m ) AND DEPOSITION (s-2) FACTDes AT SITE SOUNDAET AND OFFSITE EEPOSURE 14CATID98 FOR GROUND-LEVEL RELEASES (TROJAN 81TE DATA SEPTEMBER 1. 1972 . AUGUST 31, 1974)[a] _ FOR 1986 LAND USE CBBSUS tg Sector Wind Deerest Bearest Wearest Direc- Direc. Site Bearest peerest host Milk Milk
.11gL, ,,11gg[b] Dounderr Residence Carden _Asdaal_ Cow _fsgl ,,,,,,
N 8 t/Q 9.25-6ICI 5.65-638I 5.6E-6t c) <2.65-7 <2.65 7ICI <2.65-7183 D/Q 5.25-8 2.75-9 2.75-4 <7.25-10 47.25-10 cf.2E-10 uut SSW E/0 4.58-6 3.45-7 3.45-7 2.98-7 <1.25-7 2.58-7 D/Q 1.95-t 9.45-10 9.45-10 7.65-10 <2.55-10 6.3E-10 WE SW t/Q 1.85-6 3.4E 7 2.73-7 2.75-7 c5.85-8 <5.8E 8 D/0 5.35-9 7.2E-10 5.55-10 5.5E-10 <8.0E-11 <8.CE-11 Est usW g/Q 2.8E-6 1.75-7 1.75-7 1.75-7 ed.75-8 <a.75-8 D/Q 6.5E-9 2.4E-10 2.45-10 2.45-10 <5.3E-11 <5.3E-11 E W g/0 6.0E-6 1.25 6 1.15-6 1.18 6 <8.2E-8 <8.2E-8 D/0 1.3E-8 2.18-9 2.85-9 1.65-9 <8.5E-11 <8.5E-11 EsE WWW m/Q 6.93-6 3.55-6 1.15-6 1.35-6 <1.3E-7 <1.3E-7 D/Q 1.8E-8 8.5E-9 2.0E-9 2.5E-9 <1.75-10 <1.7E-10 SE NW m/Q 3.15-6 4.28 7 4.2E-7 4.25-7 <1.3E-7 <1.3E-7 D/0 1.25 8 1.1E-9 1.15-9 1.1E-9 <2.5E-10 <2.55-10 SSE I4M m/Q 1.3E-6 8.2E-7 8.28-7 2.85-7 <1.45-7 c1.4E-7 D/Q 6.5E-9 3.85-9 3.85-9 1.0E-9 <4.0E 10 ca.0E-10 3 3 t/Q 1.75-6 1.0E-6 8.25-7 4.85-7 <1.35-7 <1.3E-7 . D/Q 1.45-8 7.65-9 5.78-9 3.0E-9 c5.85-10 <5.85-10 $ SSW SWE z/O 8.65-7 7.85-7 7.88-7 7.8E-7I83 <5.85-8 1.55-7 D/0 5.75-9 a.58-9 4.5E-9 4.5E-9 <2.25-10 6.95-10 SW st n/0 S.7E-7 1.5E-7 1.55-7 1.55-7 <2.28-8 <2.25-8 D/Q 1.95-9 5.95-10 5.95-10
- 5.95-10 <5.85-11 <5.85-11 W5W Eut n/0 2.8E-7 1.2E-7 5.85-8 5.88-7 <1.35-8 <1.3E-8 D/Q 8.08-10 3.05-10 1.at.10 1.aE-10 <2.2E-11 <2.28-11 W E m/Q 1.0E-6 1.4E-7 9.1E 8 1.4E-7 <2.5E-8 <2.5E-8 D/0 2.3E-9 2.65-10 1.55-10 2.65-10 <2.95-11 <2.95-11 WWW ESE m/Q 1.0E-6 1.78-7 1.75-7 1.7E-7 <2.85-8 <2.8E-8 D/Q 3.2E-9 4.38-10 a.3E-10 e.3E-10 c4.4E-11 ca.at.11 WW SE t/Q 2.8E-6 8.48-7 8.4E-7 8 AE-7 47.2E-8 <7.2E.8 D/0 1 3E-8 3.35 9 3.3E 9 3.3E-9 <1.7E-10 cl.7E-10 NEW $$E m/Q 6.3E-6 3.9E-6 3.9E-6 6.0E-7 c1.78-7 41.7E-7 D/Q 4.0E-8 2.35-8 2.3E-8 2.6E 9 c5.08-10 <5.08-10 la) Exposure locations are based on the 1986 Land Use census.
Ibl Direction from which the wind blows.
^
[c] Controlling exposure location. 'O Amendment & Approved (rebruary 19es) e _ _ _ __ _ 105 I I L /
p. l} 1.
?*= = c-4 13 -
3 l -- DA8E PERIOD ANNUAL AVERACE 1/Q (sec/m ) AND DEP0817108 (m-2)
. /q t FACTORS AT FITE SOUNDARY AND OFFEITE REPOSURE LOCATIONS POE Ca0UuD-LEVEL RELEASEE (TROJA5 BITE DATA BEPfrJSEE 1.1972 - AUGUST 31, 1974)(m]
PCs 1984 LAND USE CEBSUS : Secter Wind Beerest Beerset Weerent
.Direc. Direc- Site tearest usarest meet ' Milk Bilk h _11mib) Sounderr Besidence Garden .Anigl. cow coat 5 8 9.25-6I83 5.65-6I83 m/Q 3.35-7 3.35-7 <2.65-7I83-~3.2E-7.
9/Q 5.25-8 2.75-8 9.9540 9.9540 <7.25-10 9.5E-10 Eus SSW m/Q 4.55-6 6.45-7 4.8E-7 2.9E-7 1.28-7.- 4.85-7
- D/0 1.95-8 2.05-9 1.55-9 7.65-10 2.55-10 1.55-9 NE BW 1/Q 2.85-6 3.0E-7 3.45-7 3.45-7 8.85-8 8.8E-8 D/0 5.3E-9 6.35-10 7.2840 7.2E-10 1.45-10 1.45-1C RBE WSW x/Q 2.8E-6 5.6E-7 5.9E-8 4.85-7 D/0 6.5E-9
<4.7E-8 <4.ft 8 9.35-10 6.95-11 8.05-10 <5.3E-11 <5.3E-11 E W m/0 6.0E-6' 3.65-6 9.7E-7 9.7E-7 48.25-8 3.68-7 D/Q 1.35-8 7.5E-9 1.65-9 1.6E-9 <8.55-11 4.8E-10 BSE nelW 6.95-6 1.3E-6 m/Q 8.45-7 7.2B-7 <1.35-7 7.2E-7 D/Q ' 1.85-8 2.55-9 1.5E-9 1.25 9 <1.75-10 1.2E.9 SE NW 1/Q 3.15-6 4.9E-7 4.5E-7 1.65-7 <1.35 7 <1.35 7 D/Q 1.2E-8 1.35-9 1.25-9 3.4540 <2.5540 <2.55-10 888 WW m/Q 1.35-6 8.25-7 6.6R-7 1.55-7 <1.45 e.6E-7I83 trQ 6.5E-9 3.85-9 3.0E-9 4.15-10 44.08-10 '3.0E-9 8 s x/0 1.75-6 1.25-6' 4.45-7 '(; 1.45-8 6.18-fiel 1.35-7 <1.35-7 -
D/0 8.95-9 2.75-9 4.0s-9 5.85-10 <5.85-10 0 88W NNE x/Q 8.65-7 6.5E-7 1.45-7 1.65-7 6.85-4 1.4E-7 D/Q 5.75-9 3.88-9 6.15-10 7.65-10 2.75-10 6.5E-10 SW NE 1/0 3.78-7 1.9E-7 5.95-8 8.45-8 4.05-8 3.95-8 D/Q 1.95-9 7.75-10 2.15-10 3.35-10 1.3840 1.28-10 WBW ENE m/Q 2.85-7 1.25-7 2.55-8 1.08-7 2.35-8 1.05-7 D/Q 8.05-10 3.0E-10 5.25-11 2.65-10 4.75-11 2.65-10 W E 3/Q 1.05-6 1.45-7 4.1E-0 1.0E-7 1.05-7 <2.55-8 D/0 2.3E-9 2.6E-10 5.35-11 1.75-10 1.7E-10 <2.9E-11 WWW ESE x/O 1.0E-6 1.75-7 9.95-8 1.0s-7 <2.8E-8 5.55 8 D/Q 3.25-9 4.3E-10 2.18-10 2.15-10 ca.4E-11 1.OE-10 WW" Et n/Q 2.85-6 8.4E-7 9.8E-7 2.6E-7 9.85-8 <7.2E-8 D/0 1.35-8 3.3E-9 3.9E-9 8.0E-10 2.58-10 cl.7E-10 NWW E88 6.3E-6 3.9E-6 m/Q 3.95 6I83 5.65-7 <1.75-7 <1.7E-7 D/Q 4.0E-8 2.35-8 2.35-8 2.45 <5.0540 <5.05-10 le) Exposure locations are bened on the 1984 Land Use Ceneum. (b] Direction from which the wind blows. (c] Contro111nt exposure location. [ ' ( ApprovedX M- -- v 106
TABLE C-5 g MAKIMUM ANNUAL SECTOR TERRAIN ADJUSTMENT FACTORS DERIVED FROM NUSPUF WITH BUILDING WAKE ADJUSTMENT DIVIDED BY NUSOUT FOR STANDARD POPULATION DISTANCES OF 0.5 MILE to 4.5 MILES Distance (miles) Receptor 0.5 1.5 2.5 3.5 4.5 Direction (805 m) (2414 m) (4023 m) (5633 m) (7242 m) W 1.0 0.9 0.9 0.8 0.7 NNE 1.1 1.1 0.9 0.7 0.6 NE 1.3 1.3 0.9 0.6 0.4 ENE 1.8 1.8 1.2 0.8 1.0I
- E 2.0 2.0 1.7 1.3 1.0I
- ESE 2.0 2.0 1.7 1.4 1.0I *I SE 1.3 1.4 1.3 1.1 1.0 SSE 1.0 0.9 0.9 0.8 0.7 S 1.0 0.8 0.9 0.8 0.8 SSW 1.0 0.9 0.9 0.9 0.8 SW 1.3 1.2 1.0 1.1 1.0 WSW 1.7 1.4 1.0 1.0 1.0I *I W 2.0 1.5 1.0 1.0 1.0I
- WNW. . 1.9 1.5 1.1 1.1 1.0I *I NW 1.4 1.4 1.1 1.1 1.0 NNW 1.1 1.1 0.9 0.8 0.8
[a] Beyond the area of analysis. Amendment 4 , Approved /--=
- (February 1988) 107
C i e v t0 a/ 0 4 4 7 4 6 1 4 0 lr e 1 0 0 0 0 R . d ) ' 6 6 7 7 e3 - - - - - t m 0 0 0 0 0 s / 1 1 1 1 1 uQc d xs e x x x x x A ( 3 9 0 0 6 4 1 2 7 1 Y S cr A no 7 7 7 7 E at 0 1 1 1 1 pc R ua 1 0 0 0 0 A cF L c TA O AN O 6 3 5 6 7 SI ) - - - - - RT S 3 0 0 0 0 0 OA U m 1 1 1 1 1 TE S / CR N Qc x x x x x AC E /e FE C xs 3 1 2 1 2 R ( N E 4 1 1 4 9 1 OE S
- I T U D SI RS D ] _ 1 E EW N b l . . . .
L PO A [ k 3 4 9 0 8 O B S L oi 2 1 1 1 A I D T DN 6 A 8 l C 9 a ) I E 1 t c RC d e 0 5 6 9 8 EN R n s HE O i 4 4 3 2 1 . PD F W ( 8 SI 6 DS 9 ME 1 TR ] A a , T l .t n y S d qe 5 5 0 0 0 g E R nec 1rr 2 1 r e A 9 6 6 E WFe 1 1 n N P E c
) i e m e c 3 o ca n t ne e A ar) d tAs i . d e n 1s.e Dct r s e
r g a a ee ( r y
.R m e g n ( 0 v o io 0 2 5 3 6 a l Mt 0 7 0 4 8 o 1 4 3 3 6 l r a
o u e n t r n e o A M t W W c S W S l a
]
e N S S S W ( b ( S O -
$:?:n C* . 3m 3-
>E o2
- s ' i
'l
.S
1 APPENDTI F BASIS FOR CURIE RELEASE VALUES UTILIZED IN LIQUID EFFLUENT SURVEILLANCE REQUIREMENTS 1 This appendix demonstrates that Surveillance Requirement 4.11.1.2.1, Radioactive Effluents (Liquid) Dose, based on the total curies released ! (excluding tritium and dissolved gases), results in offsite doses significantly below the LCO limits of 1.5 mees total body / calendar quarter and 2.5 mrom to maximum organ / calendar quarter. Table F-1 presents the maximum calculated dose due to liquid effluents from Trojan for the period 1976-1985 (reference PCE-1015 dated March 1977 and PGE-1015 for 1978 through 1985). Columns 4 and 5 of Table F-1 show the offsite dose which would have resulted if Trojan had released 2.5 Ci in each of the quarters during 1976-1985. It can be seen that in no case would 2.5 meem to maximum g organ or 1.5 mrem total body have been exceeded. In fact, during the quarter with the highest seem/ci released factor, the offsite doses were
<10 percent of the LCO lists of 1.5 mees total body and 2.5 meem maximum organ.
I Amendment 4 F-1 (February 1988) 109 Approved S u - --
m2 d o 5 e s 2 22 2332 2322 2323 2222 f B e a - - - - - - - - o s2 e E] EE EEEE EEEE EEEE EEEE l o/l 2850 8307 3405 2367 2 aDne O. [c 4 1 t eR 1 29 4761 1344 5514 22 42 t o r e T a e h S 1 n Cd a e 1 22 2211 2222 2212 2222 g 5 s - - - - - - - - - - - - - - - - - - - re a EiEE EEEE EEEE EEEE EEEE Os2 e 47 87 0841 3609 6367 o/l 0. [c 7 3 . xDse 1 69 S611 7345 5219 324 2 a eR M r a
]
b [ e s o D
) 3 33 3444 4 4 33 3444 4333 yn - - - - - - - - - - - - - - - - - - -
d e E] EE EEEE EEEE EEEE EEEE or 1. [c 1 0 07 92 3371 3390 54 6 6 B m 1222 6111 ( 1 27 5663 31 11 l a t o T 1
- ]
F b bL A T E B [ D o e s na
) 2 33 2323 3333 3333 3333 ae E] EE EEEE EEEE EEEE EEEE gr 0893 3592 31 84 146 6 ra 1. [c 8 2 11 11 O( 1 57 1515 1111 1124 xa M s s e e s s a a
] g g a r d d
[ t dO e e e v v sr l o l o ae s sa r ed 1 11 1 11 12 2212 21 21 2121 l n - - - - - - - - - - - - - - - - - - - - s s ee EEEE EEEE EEEE EEEE EEEE i i Rl 5 883 854 9 3 1 7 9 87 6 1 7 4 08 d d a 61 1 9 9168 6808 1 091 557 4 d sC d e 2321 2227 4 915 6161 71 81 n n l g a a rn m m ui C r u u u i i D t t i i r r t t g g r n n t 1 234 1234 1234 1234 1234 i i O d d u u l l c c x n E I r 1 2 3 4 5 l a 8 8 8 8 8 ! e 9 9 9 9 9 e b 1 1 l I Y 1 1 1
$ag$" o
' Q 3Ex gm
- 8 k"hc } ,'
/
F: tin NSR-14 J.inuary 23, 1987 ) NSRP 220-2 ! Rev. 2 JWL-55-87M l 1 TRANSMITTAL FOR f/ PROVAL AND SICNATURE O" i LDCR No. 87-04 i Title PGE-1021 "Of f site Dose Calculation Manual", Amendment 4 Il Please indicate your approval af this LDCR by signing in the appropriate space below, indicate approval by "Yes" and rejection by "No", and route to the next signatory. Organization Approve Sitnature Manager of NSRD M3 AO //MC\ ub Manacer of NOAD h-= 5 6 ^r Plant Review Board \/m O m7h,, , - -
~ . - .n. .
e It is requested that conditiens for approval or reasons for rejection be attached to the LDCR. DJH/kal 0844W.586 c: LDCR Project File / Book w/ attach J. W. Lentsch w/ attach (for NSRD routing) 1 O 111
1.E REACTOR COOLANT SYSTEM (RCS) SPECIFIC ACTIVITY t
\
Requirement l Trojan Facility Operating License NPF-1,' Appendix A Technical Specificat. ion 6.9.1.5.d " Annual Reports", states: Reports required on an annual basis shall include: 1 "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 j radioiodine concentrations; (3) Clean-up system flow history starting 48 hours prior to the first sample in which the limit was exceeded; (4) Craph 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 r radioiodine limit." l Technical Specification 3.4.8, " Reactor Coolant System Specific Activity Limiting Condition for Operation", requires:
"The specific activity of the primary coolant shall be limited j to: l "a. 1 1.0 pCi/ gram DOSE EQUIVALENT I-131, and l
"b. 1 100/E pCi/ gram." l l
Report I In 1988, the Reactor Coolant System specific activity did not exceed the limits of Specification 3.4.8. j i l 1 i 1 i i k I n2 l 1
O l l O O
I (~') 1.F TEMPORARY SOLID RADWASTE STORAGE AREA REPORT (_/ ) Requirement i 1 Nuclear Regulatory Commission (NRC) Generic Letter 81-38, dated J November 10, 1981, provides for limited increases in storage capacity for low-level radwaste generated by normal reactor operation and maintenance. 1 Under its provisions, the storage capacity increases could be added if: -l l
"(1) . . . existing license conditions or Technical Specifications do not prohibit increased storage, (2) no unreviewed safety question exists, and (3) the proposed increased storage capacity does not exceed the generated waste projected for five years . . . "
Further, a report must be made to the Commission or as specified in the license. Report A safety evaluation was performed under the provisions of Title 10 to the Code of Federal Regulations, Part 50.59 (10 CFR 50.59) and determined that the Trojan Operating License and Technical Specifications did not prohibit temporary storage of radwaste within the guidelines of Generic ["') Letter 81-38, and that no unreviewed safety question existed. In addi-(s_ ,/ tion, the safety. evaluation set forth restrictions on the use of tempo-rary storage areas at Trojan. From August to December, a temporary radwaste storage area was estab-lished at Trojan between the protected area fence and the outer perimeter fence at the point where a railroad spur enters the protected area. This area was used to store slightly contaminated tube bundles and associated pipe from the retubing of the moisture separator reheaters. In December, the radwaste was shipped offsite for decontamination and disposal. i
\)
113
7y 2. ANNUAL PERSONNEL EXPOSURE AND MONITORING REPORT Requirement Trojan Facility Operating License NPF-1, Appendix A. Technical Specifi-cation 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 mrem /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 assessment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 20%
of the individual total dose need not be accounted for. In the aggregate, at'leart 80% of the total whole body dose received from external sources shall be assigned to specific major work functions." Report
,r N Table 2-1 lists the number of workers receiving exposures greater than 100
() mrem per year and the total exposures by work and jcb function for the year 1988. Special maintenance in 104 consisted of fuel reconstitution / repair, feedwater piping replacement, and pressurizer surge line elbow replacement. Requirement 10 CFR 20.407(b) requires:
"A statistical sunmary report of the personnel monitoring information recorded by the licensee for individuals for whom personnel monitoring was either required or provided. . . indicating the number of individuals whose total whole body exposure recorded during the previous calendar year was. . .(in various exposure ranges)."
Report l l l Table 2-2 is the statistical report of radiation exposure required by 10 CFR 20.407(b) for the year 1988. fh 1 Y 114 1
TABLE 2-1 Sheet 1 of 2
]
C REPORT ON NUMBER OF PERSONNEL AND MAN. REM BY WORK AND JOB FUNCTION Wo. 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 7 0 156 3.18 0.10 .81.32 Operating Personnel 25 0 0 8.47 0.00 0.03 Chemistry & Radiation 18 0 69 5.72 0.00 26.69 Control Personnel Supervisory Personnel 5 2 23 2.61 0.82 8.56 l
Engineering Personnel 2 11 5 1.36 3.08 2.30 ROUTINE MAINTENANCE & INSERVICE INSPECTION Maintenance Personnel 131 2 286 57.98 0.57 113.38 Operating Personnel 0 0 0 0.11 0.00 0.01 Chemistry & Radiation 25 0 38 9.66 0.00 21.17 Control Personnel 23.24 Supervisory Personnel 6 4 64 2.92 1.70 ()fEngineeringPersonnel 1 4 45 0.38 1.09 25.03
\)
SPECIAL MAINTENANCE Maintenance Personnel 1 0 27 0.57 0.00 14.36 0 0 0.03 0.00 0.00 Operating Personnel 0 Chemistry & Radiation 1 0 7 0.47 0.00 3.48 Control Personnel 3.34 Supervisory Personnel 0 0 10 0.18 0.00 Engineering Personnel 1 0 26 0.62 0.18 14.53 WASTE PROCESSING Maintenance Personnel 1 0 5 0.21 0.00 1.78 Operating' Personnel 1 0 0 0.57 0.00 0.00 Chemistry & Radiation 24 0 6 7.93 0.00 2.65 Control Personnel 0.34 } Supervisory Personnel 0 0 1 0.16 0.00 j 0 0 0.01 0.00 0.00 Engineering Personnel 0 REFUELING 10 0 18 3.87 0.00 7.92 l Maintenance Personnel Operating Personnel 1 0 0 0.43 0.00 0.00 Chemistry & Radiation 7 0 38 4.46 0.00 21.58 1 Control Personnel 7.13 b--)SupervisoryPersonnel 3 0 9 1.14 0.10 0.04 0.00 35.44 Engineering Personnel 0 0 19 l 115-l l l
l t l TABLE 2-1 Sheet 2 of 2 No. of Personnel (>100 mrem) Total Man-Rem ] Station Utility Contract Station Utility Contract j Work and Job Function Employees Employees Workers Empl3yees Employees Workers
]
TOTAL Maintenance Personnel 122 1 335 49.31 0.43 166.62 j operating Personnel 22 0 0 6.39 0.00 0.01 l Chemistry & Radiation 45 0 105 20.43 0.00 57.59 l Control Personnel l Supervisory Personnel 8 5 74 4.45 2.04 32.22 Engineering Personnel 3 8 87 1.48 2.77 57.43 GRAND TOTAL 200 14 601 82.06 5.24 313.87 O l t i l l Ol l 116 l 1 j
TABLE 2-2 TROJAN PLANT WHOLE BODY EXPOSURE (REM) (,__) 1988 l
%J Number of People With No Exposure = 1,117 Exposure of at Least 0.001 and Less Than- 0.099 Number of People = 567 Exposure of at Least 'O.100 and Less Than 0.249 Number of People = 291 Exposure of at Least 0.250 and Less Than 0.499 Number of People = 268 Exposure of at Least 0.500 and Less Than 0.749 Number of People = 140 Exposure of at Least 0.750 and Less Than 0.999 Number of People = 69 Exposure of at Least 1.000 and Less Than 1.999 Number of People = 73 Expocure of at Least 2.000 and Less Than 2.999 Number of People = 0 Exposure of at Least 3.000 and Less Than 3.999 Number of People = 0 Exposure of at Least 4.000 and Less Than 4.999 Number of People = 0 Exposure of at Least 5.000 and Less Than 5.999 Number of People = 0 Exposure of at Least 6.000 and Less Than 6.999 Number of People = 0
[)h
\.
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 cf at Least 11.000 and Less Than 11.999 Number of People = 0 Exposure of at Least 12.000 and Less Than 100.99t c.u.aber of People = 0 Total Plant Exposure = 401.170 man-rem A b 117
,-- 3. STEAM GENERATOR TUBE INSPECTIONS f i 1
\/'
Requirement j j j Trojan Facility Operating License NPF-1, Appendix A, Technical Specification 6.9.1.5, " Annual Reports" states: . Reports required on an annual basis shall include:
- b. ~The complete reruits of steam generator tube insarvice inspections performed.during the report period (reference Specification 4.4.5.5.b).
Technical Specificaijon 4,4.5.5.b., " Surveillance Requirements. Steam. Generator Tube S44 lo Selection and Inspection", requires: I The complete re.uzts 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.
,/'~'j 3. Identification of tubes plugged.
Report
- a. Program Summary The 1988 steam generator tube inspection program consisted of multi-frequency eddy current examinations as follows:
- 1. Full-length examination from the hot-leg of a 12 percent random pattern of tubes, as a minimum, plus tubes with previous degradation indications in Steam Generators A and D (random pattern program).
- 2. Examination through the U-bend from the hot-leg side of Row 2 and 3 tubes in Steam Generators A and D, plus several Row 4 tubes in Steam Generator D (Row 2 program).
- 3. Examination through the U-bend of selected tubes in Rows 8 through 12 of Steam Generators A and D as a supplemental examination to evaluate conditions discussed in NRC Bulletin 88-02 (North Anna program).
- 4. Examination through the first support from the hot- and cold-legs of all tubes in Steam Generator D (first support program).
.O 118
,' 1 1 1 L l i 1
- 5. Motorized Rotating Pancake Coil (MRPC) examination of top of l l tubesheet region of selected tubes in Steam Generator D I (MRPC program).
- 6. Full-length examination from the hot-leg of selected tubes in Steam Generator A to assess the effects of foreign material found i on the secondary side (foreign material program).
- b. Results
- 1. Table 3.1 provides the number and extent of the tubes inspected in each steam generator.
- 2. Table 3.2 provides the location and percent of wall-thickness penetration for each indication of an imperfection.
- 3. Table 3.3 is a list of tubes plugged and the basis for plugging as a result of the May 1988 steam generator inspection program.
Tne attached figures show the plugging patterns in each steam generator at the conclusion of the May 1988 outage.
- 4. Based on results from Steam Generators A and D relating to indications at or near the top of the tubesheet, data previously collected in Steam Generators A, B and C were reanalyzed for assessment of similar indications. The results of this reanalysis are summarized in Table 3.4.
- c. Classification The Inservice Inspection (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.
i 1 I 119 j
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'. T T , TABLE 3.'1 l 'l.\ ..
J [~"
SUMMARY
OF EXAMINATION SCOPE: MAY 1988' , \ l Steam' Number of Extent: Generator Leg Program Tubes Tested Tested
- A' Hot 1 466' FL:H 2 '160 - 7C:H '
. 3- 104 7C:H-6 11 FL:H D Hot ' 1- 418 FL:H 2 162 , '7C:H 3 117 7C:H 4 3263 1H:H 5 28 TS:H D Cold 4 3263 1C:C-l(>
1 S- ' TOTAL TESTED = 7992 NOTE: Program l'= Random pattern Program 2 = Row 2, 3 and 4 U-bends Program 3 =. North Anna program Program 4 = First support Program 5 = Tubesheet region Program 6 = Foreign material
'*. FL:H = Entry from hot-leg side, probe insert'ed for full y ,
length of tube. 7C:H = Entry from het-leg side, probe inserted to seventh support on cold-les side of U-bend. 1H:H = Entry from hot-leg side, probe inserted to first support on hot-leg side. TS:H = Entry from hot-leg side, probe inserted for full length of tubesheet, IC:C = Entry from cold-leg side, probe inserted to first support on cold-les side of U-bend. 1' l . 120 V.
l TABLE 3.2 i
SUMMARY
OF EXAMINATION RESULTS MAY 1988 Steam Generator A D Hot: Cold Hot: Cold
-Tubes Tested 715 : 466 3263 : 3263 Ouantifiable Indications:
- 1. Tubes Exceeding Plug- 2: 0 5: 0 ging Limit >= 40%
- 2. Degraded Tubes 2: 0 1: 0
>= 20% < 40%
- 3. Imperfections < 20% 3: 4 3: 4 Nonquantifiable Indications:
- 1. Distorted Bottom Roll O: 0 14 : 2
- 2. Distorted Indication 0: 0 0: 1
- 3. Ding 4 : 2 6 : 6
- 4. Dent 14 : 7 1: 3
- 5. Inside Diameter Variations 0: 0 2: 21
- 6. Not-Full Expandable into 0: 0 1: O.
Tubesheet ;
- 7. Variation 1: 6 13 : 18 i
Copper Indications:
- 1. Top of Tubesheet 118 : 35 662 : 188 l
- 2. Tube Support Plate 0: 4 7: 6 )
- 3. Other 0: 1 0: 0 U-Bend Tannent Indientions:
- 1. Slight Change 0: 0 3: 1 1 l
- 2. Significant Change 0: 1 5: 0 O
121 l
_ - _ - _ _ _ _ _ - _ _ - _ _ - _ _ = _ - - _ - - - _ - _ - _ - - . _
/~'$
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; TABLE 3.3 TUBE PLUGCING LIST ~
MAY 1988 Steam Generator Tube Number Basis
'A R2/C59 U-Bend Indication
>40% Indication A R3/C52 >40% Indication A R11/C86 36% Indication D R2/C75 U-Bend Indication D R2/C80 U-Bend Indication D R2/C83 U-Bend Indication D R2/C84 U-Bend Indication D R3/C6 >40% Indication L : D R3/C60 Distorted Indication'
( >40% D R11/C86 >40% Indication D R16/C27 >40% Indication D R17/C68 >40% Indication. D R23/C53 >40% Indication O 122 l
- _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ A
TABLE 3.4 j RESULTS OF REANALYSIS OF 1985/1986 DATA Number of Steam Generator Tubes Analyzed Possible Indications A-Hot 3298 0 A-Cold 3287 0 I B-Hot 3293 1 B-Cold 3293 0 C-Hot 3290 0 C-Cold 3298 0 O 123
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c-t- l 1
- 4. RELIEF VALVE CHALLENGES Requirement Trojan Facility Operating License NPF-1, Appendix A; Technical Specifica--
I tion 6.9.1.5.c, " Annual Reports", requires: Annual reports shall include. . ." Documentation of all challenges to the pressurizer power-operated relief valves (PORVs) or safety valves." Report in 1988, there were no challenges of the pressurizer safety valves or power-operated relief valves. 128
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- 5. EMERGENCY CORE COOLING SYSTEM (ECCS) PERFORMANCE Requirement Adaptation of the revised ECCS rule acceptance criteria (10 CFR 50.46)
Section (a)(3)(ii) requires submittal of annual reports of the nature _of-l changes or errors and the estimated effects on the limiting ECCS analysis. Report From the effective date of the rule October 17, 1988, to the end of 1988, there were no changes or errors that would affect the limiting.ECO3 l analysis. l O O 129
- 6. CHANGES. TESTS. AND EXPERIMENTS O
Requirement Federal _ Regulation 10 CFR 50.59 and the Trojan Operating License NPF-1 require:
"(a)(1) The holder of a license . . . may (1) 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 experi-ments not described'in the safety analysis report, without.
prior Commission approval, unless the proposed, change, test
.or experiment involves a change in the' technical specifica-tions incorporated in the license or an unreviewed safety question.
"(b)(2) The licensee shall submit . . . a report containing a brief description of any. changes, tests, and experiments, includ-ing a. summary of the. safety evaluation of each. . .
annually. . ." Report Section 6 of the Annual Report provides a description of changes, tests, and experiments completed in 1988 in accordance with 10 CFR 50.59, - including a summary of the safety evaluation for each. Also included in Section 6 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. a O 130
6.A PLANT MODIFICATIONS AND DESIGN CHANCES O The following Plant modifications and design changes were completed in 1988 and are being reported in ac'ccrdance with Title 10, Code of Federal Regulations, Part 50.59 (I.0 CFR 50.59)'. ~These modifications were evaluated, and it was deturmined 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 Final Safety Analysis Report (FSAR), (b) create the possibility of an accident or malfunction of a different type previously evaluated in the FSAR, 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 1988, some to meet regulatory commitments, and will be reported in future Annual Reports when all portions of the design changes are completed.
- 1. Plant Design Change 76-248 Hazardous chemicals are stored in the Dechlorination Building and a permanent emergency eyewash / shower station was needed to upgrade the level of personnel safety in the building and to comply with Plant Safety Procedure (P!)-3-29 " Storage, Use and Handling of Chemicals".
Plant Design Change 76-248 installed an emergency eyewash / shower in the southwest corner of the Dechlorination Building, with a O permanent water supply from the potable water system. This modification did not involve a change to the Trojan Technical or en unreviewed safety question.
- 2. Plant Design change 78-070 Modifications to todiation protection facilities in the Control ;
Building were v> quired to improve access controls, personnel circulation between the Control Building and the Auxiliary / Fuel Buildings, and optimLze radiation protection work space utilization. Plant Design Change 78-070 reorganized facilities and work spaces at elevation 45 feet in the Control Building, developed additional work spaces in the closed-off Control Building railroad bay, and reorganized work spaces at Control Building elevation 93 feet in areas previously occupied by the water sampling labs, instrument lab, and office cubicles. This modification did not involve a change to the Trojan Teclinical Specifications or an unreviewed safety question.
- 3. Plant Design Change 78-113 Westinghouse suggested four minor changes to improve reliability of the Digital Rod Position Indication System.
131
l Plant Design Change 78-113 provided capacitor replacement, printed circuit card guide removal, commonizing spring addition and a transformer phase check in the data cabinets. . This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 4. Plant Design Change 81-015 The pressure indication for the residual heat removal (RHR) pumps was improperly wired in that the pressure transmitter for one pump fed the other pump's pressure indicator.
Plant Design Change 81-015 changed the RHR pump discharge pressure wiring to a logical numbering sequence that eliminated the transmitter cross-connect problem. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 5. Plant Design Change 81-049 Trojan lacked apequate spacet' o process and store dry low-level radioactive waste and to process contaminated laundry.
Plant Design Change 81-049 involved construction of an addition to the Fuel Building for waste compa,cting, temporary dry waste storage, and handling of contaminated laundry. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 6. Plant Design Change 82-017 The process boiler was not used or certified for use, and the space was needed for use as a respirator cleaning and maintenance area.
Plant Design Change 82-017, removed the process boiler from the Fuel Building and installed respirator cleanint; and maintenance equipment. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 7. Plant Design Change 83-029 The main steam check valves and main steam isolation valves had a tendency to stick open when steam flow stopped due to packing-induced friction.
Plant Design Change 83-029 reduced the number of packing rings, adjusted the size of the lantern rings, and added a second counterweight to the main steam check valves in the 180' rotated location. O 132
This modification did not involve a change to the Trojan Technical [,_s} Specifications or an unreviewed safety question. v/
- 8. Plant DesiRn Change 83-044 The nuclear instrumentation system did not comply with Regulatory Guide 1.97, Revision 2.
Plant Design Change 83-044 installed an additional, qualified, neutron flux monitoring system. The system is independent of the cable spreading room with signals to C-160 for Appendix R purposes. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 9. Plant Design Change 84-034 The original dissolved oxygen analyzer lacked the reliability and i accuracy th.t newer instruments have.
Plant Design Change 84-034 installed a new multichannel oxygen analyzer in place of the individual analyzers for A and B condensate and feedwater pump discharges. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question, (n)
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- 10. Plant Design Change 84-035 A 10 CFR 50 Appendix R revision identified a shortage of-emergency lightlng in various areas of the Piknt required for safe shutdosm in the event of a fire.
Plant Design Change 84-035 installed emergency lighting in all areas as required by 10 CFR 50 Appendix R. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 11. Plant Design Change 84-062 Several personnel safety hazards associated with accessing various equipment in containment for performance of operational and maintenance activities were identified.
Plant Design Change 84-062 installed handrails and ladders to provide safe access to various equipment in containment. This modification did not involve a change to the Trojan Technical Specification or an unreviewed cafety question. l l r~"3
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- 12. Plant Design Change 84-073 High oxygen levels in the condensate storage tank (CST) contributed to elevated oxygen levels in the feed and condensate system.
Plant Design Change 84-073 modified the desassifier to allow processing CST water through a new heat exchanger. The modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 13. Plant Design Change 8A-086 Several raceways containing redundant safe shutdown cables required the installation of fire-rated wrapping systems as identified in a 10 CFR 50, Appendix R review.
Plant Design Change 84-086 installed the required cable wrapping systems. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 14 Plant Design Change 84-093 The steam generator water level indication system did not comply with the design criteria specified by Regulatory Guide 1.97. The wide-range level transmitters were not environmentally qualified and would fail if exposed to a harsh environment. Plant Design Change 84-093 provided environmentally qualified steam generator level indication by upgrading the narrow- and wide-range steam generator level indicating system to meet the requirements of Regulatory cuide 1.97. This modification did not involve a change to the Trojan Technical Specifications or an unrev8.e ed safety question.
- 15. Plant Design Change 84-096 The low suction pressure trips on the safety-related auxiliary feedwater pumps caused several spurious pump trips during simultaneous automatic starts of the pumps.
Plant Design Change 84-096 removed the low suction pressure trip and replaced it with a pump trip caused by low level in the condensate storage tank. This modification did not involve a change to the Trojan Technical ' Specifications or an unreviewed safety question. O 134
- 16. Plant Design Change 84-113 p.
f I x_/ The Trojan warehouse was undersized and did not provide an efficient work opsce. Plant Design Change 84-113 avpanded the office space to accommodate the entire warehouse office staff and provided additional space for expected staff increases. The modification also upgraded the fire protection system to protect the office space. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 17. Plant Design Change 84-121 The control scheme for motor-operated valves MD-8701 and MO-8702, Residual Heat Removal Suction from RCS Loop 4, was such that once either valve received a closed signal, it could not be stopped from going closed nor could it be reopened until it had gone full closed.
Plant Design Change 84-121 installed lockout switches for MO-8701 and MO-8702 to open contacts in the open and closed circuits. Momentarily going to lockout will clear the close, or open, signal and allows the operator to reposition the valves. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
\_/ 18. Plant Design Change 84-141 The Detailed Control Room Design Review identified that accidental actuation of the lower control board switches could occur, due to a lack of a guardrail along the main control boards from C18 to C19.
Plant Design Change 84-141 installed a guardrail from C18 to C19. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 19. Plant Design Change 85-023 Clogging of stator cooling water system filters has required power reductions on Plant outages to clean or replace the filter.
Plant Design Change 85-023 provided the ability to bypass the filter so that it can be. changed without power reductions or Plant outages. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. rm ( )
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- 20. Plant DeslRn Change 85-032 IE Bulletin 84-03 considered the potential for and consequences of a failure of the refueling cavity seal.
Plant Design Change 85-032 relocated the rod cluster control change fixture such that it cannot become uncovered and expose fuel contained therein in the unlikely event of a refueling cavity seal failure. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 21. Plant Design Change 85-042 This is a generic design change initiated to address control room and local panel annunciators that do not provide a meaningful alarm to the operators. Examples are: Demineralized Water System Trouble, Boron Sample Trouble, and Radwaste System Trouble.
Plant Design Change 85-042 revised several annunciator actuation signals such tha*. they are only present when an actual abnormal condition exists, rather than When the component cendition is in an alternate mode of operation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question,
- 22. Plant Design Chante 86-001 Plant Design Change 86-001 was a generic design change implemented to correct design deficiencies identified in 1986. The modifications performed per this design change returned piping, supports, and hangers to their original design requirements.
These modifications did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 23. Plant Des 1Rn Change 86-004 The Auxiliary Feedwater (AFW) System at Trojan was reviewed for potential reliability improvements. The review made several recommendations for improving the operability of the electric AFW pump.
Plant D.esign Change 86-004 relocated the source of power to the electric AFW pump auxiliary lube oil pump to ensure its operability. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 136
- 24. Plant Design Change 86-028 i
\ ,/ This is a modification concerning a security door, the details of which are Safeguards Information. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 25. Plant Design Change 86-032 Vital equipment cables were found unprotected and as such were not in accordance with the Trojan Security Plan.
Plant Design Change 86-032 was a " Safeguards" modification and provided for appropriate protection of the cables. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 26. Plant Design Change 86-035 The 15 V and 48 V direct current (de) power supplies in the solid state protection system short out, and all power is lost to the 15-V and 48-V buses if the neutral fuse in the a-c power supply is removed first during routine maintenance. Loss of power to these buses causes a reactor shutdown.
I' ) Plant Design Change 86-035 removed the neutral fuse which is not \m/ required for circuit protection, thereby eliminating the possibility of power loss during routine maintenance. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 27. plant Design Change 86-038 The Y0l. YO2, and YO3 electrical panels supply power to non-safety-related loads through various-sized circuit breakers.
Each circuit breaker has a fuse for which there was no apparent indication of continuity. Plant Design Change 86-038 provided blown-fuse indication for each fuse, relocated each fuse for easier access, and added additional fuse capacity for future loads. This modification did not involve a change to the Trojan Technical Specification or an unreviewed safety question.
- 28. Plant Design Change 86-041 As a result of the Main Feedwater Pung Recirculation Control Valve (CV-2976A and B)~ replacement, control problems were observed with j, various interacting systems.
/ i V 137
i i Plant Design Change 86-041 changed the recirculation control valve I circuit from modulating between open and closed setpoints of 4,000 and 8,000 gpm, to binary operation with a valve stroke time of not less than 9 seconds or greater than 30 seconds. q This modification did not involve a change to the Trojan Technical { Specifications or un unreviewed safety question.
- 29. Plant Design Change 87-034 The original Turbine Building flood relief louvers were not adequately designed to pass the 500,000 gallons per minute required to prevent ficoding of safety-related components in the event of a circulating water system pipe rupture.
Plant Design Change 87-034 replaced the flow restricting louvers with adequately designed panels, and As-Built Temporary Modification TM 87-045, which raised the height of flood dikes protecting safety-related equipment. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 30. Plant Design Change 85-510 Redundant pressure switches in parallel with existing pressure switches were required to improve the reliability of the main turbine d-c emergency bearing pump.
lf Plant Design Change 85-510 installed the necessary pressure switches as recommended by the turbine vendor. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 31. Plant Design Change 85-519 The cooling tower makeup pump motors were experiencing excessive vibration.
Plant Design Change 85-519 installed stiffeners to the motor supports to lower the motor vibrations to within acceptable limits. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 32. Plant Design Change 85-521 The Discharge and Dilution Structure sodium sulfite tank, T-169, was vented inside the building and, consequently, has contributed to the corrosion of the metal surfaces inside the building.
O 138
?: Plant Design Change 85-521 installed a blower and duct work to vent s" the tank outside the building. 4 e This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 33. Plant' Design Chanxe 85-530 The water retreatment plant caustic storage tank level transmitter
,was a bubble-type. indicator. .The moving air provided enough localized cooling to cause the tube to plus with crystallized soda.
Plant Design Change 85-530 removed the existing level 1 transmitter and replaced it with an ultrasonic level sensor and transmitter. This modification did not involve a change' to the' Trojan Technical Specifications or an unreviewed safety question.
- 34. Plant Design Change 85-541 The north condensate pump expansion joint had very small leaks that provided a source of oxygen inleakage to the condensate system.
Plant Design Change 85-541 replaced the defective expansion joint. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 35. Plant Desinn Change 85-543 The main turbine had a two-speed turning gear that caused overspeed trips when shifting from slow to fast speed.
Plant Design Change 85-543 eliminated the fast-speed circuitry. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 36. Plant DesiRn Chante 85-546 The secondary sample drain tank, T-135, to the condenser has been tagged closed for nine years. Temporary Modification 85-058 cut and capped the line to the condenser to eliminate it as a possible source of oxygen inleakage to the condenser.
Plant Design Change 85-546 revised the temporary modification to a permanent deletion. This modification did not involve a change to the Trojan Technical' Specifications or an unreviewed safety question. O 139
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- 37. Plant Design Channe 85-559 l i The waste gas surge tank LT-3147, relief valve PSV-4302, was welded into the piping, making maintenance difficult and time consuming.
Plant Design Change 85-559 provided flanges on both the inlet and discharge of the relief valve to facilitate easy removal and installation. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 38. Plant Design Change 85-565 The condensate pump suction strainers (F-119 A&B) were in need of replacement due to significant deterioration of the suction strainer screens.
Plant Design Change 85-565 provided for replacement of the suction strainer screens. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 39. Plant Design Change 86-503 The buildup of radioactive material in the vent collection header process radiation monitor (PRM-5) piping, resulted in an erroneous indication.
Plant Design Change 86-503 installed a spool piece in the piping to allow cleaning and reduction of background radiation effects upon the PRM-5 indication. This modification did not involve a change to the Trojan Technical Specifications or un unreviewed safety question.
- 40. Plant Design Change 86-506 Background noises in Containment make communications using the in-plant phone system difficult.
Plant Design Change 86-506 installed sound attenuation booths on the 93-foot and 45-foot levels of Containment. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 9 140
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- 41. Plant Design Change 86-521
'[ ~'N 1
~/ The chlorination System lacked sufficient purge and vent locations to ensure all portions are properly vented prior to maintenance.
Plant Design Change 86-521 provided additional purge and, vent capabilities and added a source of purge air from the instrument air system to aid in assuring proper evacuation of all chlorine gas from the system prior to maintenance. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 42. Plant Design Change 86-525 The Cooling Tower acid system had a single alarm light for sump level and emergency eyewash / shower operation. In addition, there was a need for a permanent sump pump to remove rain water from the sump.
Plant Design Change 86-525 provided two separate and different-colored alarm lights and an automatic sump pump. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 43. Plant Design Change 86-528 7..
! \ \x/ The Orbisphere dissolved oxygen monitor that analyzes concentrations on the feedwater pump discharge and condensate pump' discharges was difficult and time-consuming to calibrate.
Plant Design Change 86-528 installed an in-line calibration panel. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 44. Plant Design Change 86-532 Grab sampling of the feed and condensate system was disconnected and will not be used in the future; therefore, the grab sample equipment installed in the Water Analysis Laboratory of the Control Building could be removed to provide badly needed space.
Plant Design Change 86-532 removed the inert atmosphere glove box and associated piping and tubing. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l 1 f) 141 I l L r - - _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - -
- 45. Plant Design Change 86-537 Process Sampling System Valves SS-048, SS-054, and SS-60 are redundant valves that allowed back-leakage through the stems and j subsequent gas releases into the Auxiliary Building.
Plant Design Change 86-537 removed the redundant valves and capped the vacated lines. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 46. Plant Design Change 86-539 i
-The Turbine Building sump oil collection pump is air-operated and had a temporary hose supplying the air.
Plant Design Change 86-539 provided a permanent air line. This modification did not involve a change to the Trojan Technical Specificat' ions or an unreviewed safety question.
- 47. Plant Design Ch6nne 86-543 There were no interlocks to prevent the condensate demineralized low-pressure blower from attempting to provide more than one function at a time. ,
Plant Design Change 86-543 connected an interlock that places the backwash-handling system in a blowdown hold status whenever the blower is activated for demineralized backwashing. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 48. Plant Design Change 86-553 ,
The counting room on the 45-foot elevation of the Control Building had an air flow balance problem. This resulted in an air exchange of 1.2 air changes / hour, which was insufficient to expeditiously remove gas from the room when nitrogen gas transfer was in progress. Plant Design Change 86-553 changed the supply filter, exhaust registers, and balanced the air flows to provide 20 room air changes / hour under normal operation and 32 air changes / hour when transferring nitrogen. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 142
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. -49. Plant Dnsign Change 86-560 Warming of trapped water downstream of the electric AFW pump I
discharge check valve could have resulted in an overpressure f condition that could have prevented the valve from opening. Plant t,esign Change-86-560 installed a thermal bleeder orifice through the disk of the valve. This modification did not involve a change to the Trojan Technical specifications or an unreviewed safety question.
- 50. Plant Design Change 86-574 The boric acid evaporator concentrates' sample sink drains were run through a tygon tube to a nearby floor drain which-is collected in .i' the dirty waste drain tank.
Plant Design Change 86-574 installed a hard-piped drain from the sample sink to the Auxiliary Building drain tank inlet header. This modification did not involve a change to the Trojan Technical specifications or an unreviewed safety question.
- 51. Plant Design Change 86-578 An additional phone was needed on the dose assessment tablo at-the
- [- Emergency Operations Facility so that Plant parameters'could be obtained in an emergency when the display system is inoperative.
Plant Design Change 86-578 installed an in-plant phone system extension at the dose assessment table. This modification did not involve a change to the Trojan Technical Specifications-or an unreviewed safety question.
- 52. Plant Design Change 86-579 Due to excessive battery loading, the Plant process P-250 computer power supply had to be changed to a 480-V a-c bus and thus was interrupted each plant trip with the resultant loss of important trip assessment data.
Plant Design Change 86-579 installed an uninterruptible power supply to eliminate the loss of the P-250 computer on Plant trips. This modification did not involve a change to the Trojan Technical specifications or an unreviewed safety question. l O 143 l k
- 53. Plant Design Change 86-583 Temporary Modification TM-84-017 provided jumpers in the secondary sampling system to allow cross connecting various sample inputs to portable integrating samplers for long-term uonitoring of secondary system corrosion product transfer and condensate demineralized performance.
Plant Design Change 86-583 provided for As-building TM-84-017 and
.made the change permanent.
This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 54. Plant Design Change 86-589 Low background radiation levels on process radiation monitors (PRM)-16A through D were causing frequent detector failure alarms due to the time interval between detection of the absence of counts and activation of detector failure alarms being less than the time interval between detected counts.
Plant Design Change 86-589 changed the failure alarm circuitry delay from 5 seconds to 45 seconds. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. ll
- 55. Plant Design Change 86-592 A garden hose was being used to provide a source of water to the resin fill tank, T-212, located on the 93-foot level of the Auxiliary Building. The use of a garden hoso presented the potential of damage to surrounding electrical equipment.
Plant Design Change 86-592 provided the addition of a nozzle to the tank and a quick disconnect for the garden hose connection. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 56. Plant Design Change 86-598 There was a shortage of available circuits on the Plant outside access telephone system.
Plant Design Change 86-598 transferred several phone circuits from the outside access telephone system to the in-plant telephone system. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. O 144 L--_______--__--
- 57. Plant Design Change 86-600
.O- ' (_ I Plant Design Change 84-077 provided for installation of clean and-dirty radwaste filt'ers Which utilize service air for blowing the filter. canisters free of wster. The air was being supplied.by a temporary hose.
Plant Design Change 86-600 removed the air hose and installed a permanent hard-piped air supply. This modification did not involve a change to the Trojan Technical
, Specifications or an unreviewed safety. question.
- 58. Plant DesiRn ChanRe 87-504 Temporary Modification TM 86-080 installed sample lines from the condensate pump discharge lines to the west side of the main condenser, for use at the air inleakage monitoring station.
Plant Design Change 87-504 As-Builts the Temporary Modification and makes the installation permanent. This modification did not involve a change to the Trojan Technicci-Specifications or an unreviewed safety question.
- 59. Plant Design Change 87-505
.fN The Pressurizer Relief Tank temperature indiction range was not in compliance with Nuclear Regulatory Commission Regulatory Guide 1.97 \_-
guidance. Plant Design Change 87-505 expanded the temperature range from 50*F to 300*F. to 50*F to 350*F. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 60. Plant Design Change 87-508 Temporary Modification TM-86-090 changed the Plant Discharge British Thermal Unit Recorder TKR-6341, from a voltage to a current loop to improve instrument accuracy.
Plant Design Change 87-508 As-built TM-86-090 and makes the installation permanent. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. 145
- 61. Plant Design Change 87-512 The feed flow and steam flow signal source selector switches had h caused attenuation or elimination of the low-voltage d-c output, seriously affecting control of steam generator level.
Plant Design Change 87-512 replaced the switches with new switches that are more suited Lo the low d-c current application. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed sa'ety question.
- 62. plant Design Change 87-514 Moisture collected in the condenser off-gas flow transmitter sensing lines, rendering the system inoperable.
Plant Design Change 87-514 replaced the existing flow venturi with a ! new 3-inch tube (FE-3100), and relocated the flow transmitter to a higher elevation to prevent moisture collection. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 63. Plant Design Change 87-518 The main feedwater pump turbine rupture discs were subject to cutting, which resulted in sir inleakage into the condensers.
Plant Design Change 87-518 replaced the rupture discs with new discs made of a material less susceptible to cutting. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 64. Plant Design Change 87-520 The pressurizer spray valve leakoff was a hard-piped connection requiring cutting and welding whenever the spray valve bonnet was removed. The extra work increased worker exposure to radiation.
Plant Design Change 87-520 installed flanges in the leskoff line to facilitate rapid disconnection of the leakoff line. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 65. Plant Design Change 87-525 A.1986 American Nuclear Insurers inspection identified the need for '
access to fire protection system isolation Valve FP-244, which is located 10 to 15 feet above the floor. l 146
T Plant Design Change 87-525 provided a chain wrench operator for r" valve operation. g
\s-}/ --
This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question, j
- 66. Plant Design Change 87-527
' Additional test connections were required on'the instrument air lines to the isolation valves'in the main steam supply to the Terry Turbine Auxiliary.Feedwater pump. The test connections were required to support system pressure tests.
. Plant Design Change 87-527 provided the necessary test connections.
This modification did not involve a chango to the Trojan Technical
. specifications or an unreviewed safety question.
- 67. Plant Design Change 87-529 Main Steam Safety Valve p5V-2255 he:,d to be removed from the system j for repair.
Plant Design Change 87-529 provided for reinstalling the overseat drain line with the use of a socket welded union vice the previous l direct wold to the valve. i (~'} This modification did not involve a change to the Trojan Technical .{
\s,7 Specifications or an unreviewed safety question. ;
- 68. Plant Design Change 87-546 l
The isolation valves for the makeup water system neutralizing tank pH cell were located 50 feet from the instrumentation, and the ! valves leaked. Plant Design Change 87-546 installed new isolation valves near the l instrument. ! i This modification did not involve a change to the Trojan Technical ! Specifications or an unreviewed safety question. l 1
- 69. Plant Design Change 87-555 The Radwaste Annex monorail beam experienced excessive deflection a while under load, creating a safety hazard with the electrical hoist. !
Plant Design Change 87-555 added supports to the monorail beam and l modified the electrical pickup arm for the hoist. i i l This modification did not involve a change to the Trojan Technical ! Specifications or an unreviewed safety question. j gs i (_- 147
- 70. Plant Design Change 87-560 The 250-V d-c battery room exhaust fan used a plywood plenum wedged between the block wall of the battery room and the Turbine Building siding.
Plant Design Change 87-560 installed an aluminum housing around each fan to direct the exhaust to the ventilation louvers in the Turbine Building siding. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 71. Plant Design Change 87-561 The smoke exhaust ductwork from the Control Building 17-foot (cable spreading rov.n) and 61-foot (engineered safety features switchgear room) did not comply with Security Plan requirements at the interface with the protected areas.
Plant Design Change 87-561 modified the ducts in order to comply with the Security Plan. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 72. plant Design Change 88-507 The upgrading of the Plant telephone system required changes to the system power supplies.
Plant Design Change 88-507 rerouted several power supplies and provided an additional 120-V a-c circuit. This modification did not involve a change to the Trojan Technical Specifications or an unreviewed safety question. l 9' 148 l L--- - - - - - - - - - . - - - - - - ,
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6.B LICENSE AMENDMENTS In 1988, a total of' eleven license amendments were issued by the NRC. Ten requests for license amendments [ License Change Applications.(LCAs))- were submitted to the NRC for approval and five resulted.in license - -
. amendments. Of eleven LCAs previously submitted, six received NRC approval and have been issued (one of the previously submitted LCAs was only partially approved). As of December 31, 1988,- eleven LCAs had not yet.been acted upon by the NRC.
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TABLE 6.B-1 Sheet 1 of 8 (~ ' . t AMENDMENTS TO THE TROJAN OPERATING LICENSE ISSUED IN 1988 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 Subj ect 139 03/31/88 Amendment 139 revised the Trojan Technical Specification 3/4.10. "Special Test Exceptions". By extending the surveillance time period for the verification of control rod insertability during control rod worth and shutdown margin tests, from 24 hours to 7 days, the necessity for an additional trip during physics tests was eliminated. In addition to Amendment 139, PGE distributed a revision (not requiring prior NRC approval) to the
/"N Bases section 3/4.4.6.2 regarding Pressure k,,,) Boundary Leakage to add the requirement for cold shutdown following the occurrence of Pressure Boundary Leakage and to make the Bases consistent with the Definitions Section of the Technical l
Specifications. l This amendment involved a change in surveillance requirements for a facility component located within the restricted area as defined in Title 10 Code of Federal Regulations, Part 20 (10 CFR 20). The NRC 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 was no significant increase in individual or cumulative occupational radiation exposure. The Commission previously published a proposed finding that the amendment involved no significant hazards i consideration and there was no public comment on such finding. Accordingly, this amendment met 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 connection with the issuance of this amendment. , l 150 o
t ? l TABLE 6.B-1 Sheet 2 of 8 O I 4 Amendment Number Date Subject _ 140 04/11/88 Issuance of this amendment revised the Offsite and Facility Organization Charts for the Trojan i Technical Specifications to provide additional detail regarding various organizational changes. j This amendment related to changes in recordkeeping, reporting or administrative procedures or requirements. Accordingly, the amendment met 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 were required in connection with the issuance of this amendment. 141 05/03/88 Amendment 141 was issued to revise Trojan Technical Specification Section 3/4.7.3,
" Component Cooling Water System", to allow for operation in a " split-train" configuration with the interface isolation valves for one train normally closed and with all three Component Cooling Water (CCW) pumps maintained in an operable status. Until the completion of the CCW System upgrade, this configuration ensures a continuous flow of CCW to at least one train cf EUF equipment following a seismic event and will assure the availability of a CCW loop even with a single failure concurrent with a seismic evant.
Upon completion of modifications to Non-Seismic Category I flow path, a License Change Application (LCA) will be submitted t'o return to the original CCW 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 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 was no significant increase in individual or cumulative occupational radiation exposure. The Commission had previously published a proposed finding that the amendment involved no significant hazards consideration and there was no public comment on such finding. Accordingly, the 151 l
- - _a
f TABLE 6.B-1 Sheet 3 of 8 [h L )^. Amendment Number Date Subject amendment met 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 connection with the issuance of this amendment. 142 05/11/88 Issuance of Amendment 142 permits relief from Limiting Condition for Operatien (LCO) 3.0.4 for-the following Trojan Technical Specification Sections to allow entry into operational modes with selected equipment out-of-service, therefore providing more operational flexibility:: 3.2.4 - Quadrant Power Tilt Ratio 3.9.2 - Instrumentation (Refueling Operations) 3.9.7 - Crane Travel. Fuel Building 3.9.9 - Containment Ventilatj,on t System 3.9.11 - Storage Pool Water Level-
/"'N In addition, this amendment formally documented .(,,) changes to Appendix A, Technical Specification Section 6.9,-and Appendix B, Environmental Protection Plan Technical Specification Section 5.4, regarding written communication to the NRC, as authorized by the Commission (see Federal Register (51 FR 40303), November 6, 1986).
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 determined ths.t the amendment involved no significant increase in the anounts, and no significant change in the types, of any effluents that may be released offsite, and that there was no significant increase in individual or cumulative occupational radiation exposure. The Commission had previously published a proposed finding that the amendment involves no significant hazards consideration and ther e was no i public comment on such finding. Accordingly, the amendment met 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 i assessment was required in connection with the issuance of the amendment. f% s_ / l 152 i
-.M.
l TABLE 6.B-1 Sheet 4 of 8 I Amendment Number Date Subject 143 06/16/88 Issuance of Amendment 143 revised the operability and surveillance requirements for Trojan Technical Specification Section 3/4.3.3.10 " Radioactive Liquid Effluent Instrumentation," by adding two new instruments for monitoring steam generator blowdown liquid effluent radioactivity and flow rate. This amendment involved a change in the installa-tion or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC determined that the amendment involved no significant increase in the amounts, and no sig-nificant change in the types, of any effluents that may be released offsite, and that there was no significant increase in individual or cumula-tive occupational radiation exposure. The Commission had previously published a proposed finding that the amendment involved no significant hazards consideration and there was no public comment on such finding. Accordingly, the amend-ment met 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 connection with the issuance of this amendment. 144 06/22/88 Amendment 144 authorized the deletion of references to the Turbine Building 45-foot elevation as the location of remote shutdown monitoring instrumen-tation. The C-160 Panel was renamed the Remote Shutdown Station and relocated to the Control Building, 45-foot elevation. The objective of the replacement and relocation was to resolve a number of technical problems, including human engineering discrepancies and maintenance problems due to equipment accessibility and space limita-tions with the current panel and its Turbine Building location. This amendment involved a change in the installa-tion or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC determined that the amendment involved no O 153
TABLE 6.B-1 Sheet 5 of 8
,,m I i , N-]
Amendment Number Date Subject significant increase in the amounts, and no sig-nificant change in the types, of any effluents that may be released offsite, and that there was no significant increase in individual or cumula-tive occupational radiation exposure. The Commis-sion had previoucly published a proposed finding that the amendment involved no significant hazards consideration and there was no public comment on such finding. Accordingly, the amendment met 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 connee-tion with the issuance of this amendment. 145 06/23/88 Amendment 145 revised the means by which source range neutron flux instrumentation calibration is performed and changed the Trojan Technical Specification requirement from obtaining source-range nuclear instrument detector plateau curves to obtaining detector discriminator bias curves. 7-~3 (', ) This change is consistent with the manufacturer's recommendations for identifying degradation of the source-range preamplifier. This amendment involved a change in surveillance requirements. The NRC determined that the amer.d-ment 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 was no significant increase in indivi-dual or cumulative occupational radiation exposure. The Commission had previously published a proposed finding that the amendment involved no significant hazards consideration and there was no public comment on such finding. Accordingly, the amend-ment met 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 connection with the issuance of this amendment. 146 07/07/88 Issuance of Amendment 146 revised Trojan Technical Specification Section 6.3.1, " Facility Staff Qualifications", by re-titling the position of
, 's Radiation Protection Supervisor to Radiation protection Branch Manager.
() 154 l
TABLE 6.B-1 Sheet 6 of 8 l Amendment Number Date Subject The change, in addition to Amendment 140 Which previously omitted this editorial change, was made in order to establish consistency within the Trojan Technical Specifications. This amendment related to changes in record-keeping, reporting or administrative procedures or requirements. Accordingly, the amendment met 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 was required in connec-tion with the issuance of this amendment. 147 07/11/88 This amendment revised the surveillance require-ments for Trojan Technical Specification Section 2/4.6.1.1, " Containment Integrity", to be consis-tent with the content of the Westinghouse Standard Technical Specifications (W-STS). The surveillance periodicity for isolation barriers inside Contain-ment is now once per cold shutdown (but not more than once per 92 days). This amendment involved a change in surveillance requirements. The itRC determined that the amend-ment 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 was no significant increase in indivi-dual or cumulative occupational radiation exposure. The Commission previously published a proposed finding that the amendment would involve no significant hazards consideration and there was no public comment on such finding. Accordingly, the amendment met 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 connection with the issuance of this amendment. 148 07/14/88 Issuance of Amendment 148 revised the surveillance requirements for the safety injection accumulator isolation valves as related to Trojan Technical Specification Section 3/4.5, " Emergency coro Cooling Systems (ECCS)". Modification consists of O 155
l TABLE 6.B-1 Sheet 7 of 8 jS l Amendment Bumber Date Subsect a combination valve control / lock out switch located in the Control Room. With this configura-tien of locking out power to the control _ circuit of the valve operator, valve position indication will be retained to the accumulator isolation valves, thus providing-additional assurance that the' accumulator isolation valves will be in the correct position. This verification will be made at least once every 18 months during shutdown in accordance with Plant procedures. This amendment involved a change in the installa-tion or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC 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 was no significant increase in individual or cumula-tive occupational radiation exposure. The Commis-
~'
sion previously published a proposed finding that s, this amendment involved no significant hazards consideration and there was no public comment on such finding. Accordingly, the amendment met 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 the issuance of this amendment. 149 08/03/88 Amendment 149 deletes the Offsite and Facility Organization Charts from the Technical Specifica-tions in accordance with guidance provided in Generic Letter 88-06, " Removal of Organization Charts from Technical Specification Administrative Control Requirements", dated March 22, 1988. General organization requirements in addition to specific operational requirements are now used in place of these charts. This amendment related to changes in record-keeping, reporting or administrative proces _. as or requirements. Accordingly, the amendment met the eligibility criteria for categorical exclusion set O 156
TABLE 6.B-1 Sheet 8 of 8 O ! Amendment Number Date Subioct forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment was required in connection with the issuance of this amendment. O O 157
, l l 1 s
, TABLE 6.B-2 Sheet 1 of 5
%)
STATUS OF LICENSE CHANGE APPLICATIONS (LCAs) SUBHITTED TO AND UNDERGOING REVIEW BY THE NUCLEAR REGULATORY COMMISSION (NRC) AS OF DECEMBER 31, 1988 LCA Date Number Submitted Subject and Statur 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. PGE letters of December 22, 1986, February 26, 1987, and April 3, 1987 provided revised pages. NRC letter dated February 10, 1988 requested submittal of a revised Significant Hazards discussion to facilitate NRC review.
,_.s LCA 124. Revision 1 was transmitted to the NRC via PGE letter dated March 1, 1988.
(L_j) 142 09/30/85 Control Room Habitability: Requests modifications regarding control room habitability by proposing changes to the (1) Chlorine Detection Systens, (2) SO2 Detection Systems, and (3) Control Room Emergency Ventilation System. PGE letter of November 16, 1987 transmitted Revision 1 of this LCA. On April 14, 1988, revised pages were submitted to the NRC to incorporate comments and provide clarifications. 145 10/28/86 Barton Transmitter Setpoint Changes: Requests changes to reflect the current setpoints for Earton transmitters (replaced during the 1986 outage). The specific setpoints changed are the steam generator low-low level and pressurizer low-pressure reactor trip. l 158
TABLE 6.B-2 Sheet 2 of 5 e LCA Date Number Submitted Subject and Status Revision 1 of this LCA, incorporating additional information in the Significant Hazards Determina-tion, was submitted by PCE letter dated May 19, 1988. PCE letter dated December 30, 1988, forwarded LCA 145, Revision 2. This revision removed reference to the pressurizer low-pressure safety injection setpoint as a result of the submittal of LCA 171 on September 9, 1988. 151 12/24/87 Relocation of Fire Protection Technical Specifica-tions to PGE-1012: Removes those portions of the Trojan Technical Specifications that.are related to the Trojan fire protection program and relocates them to Topical Report PGE-1012, Volume I, " Trojan Nuclear Plant Fire Protection Plan - Program Description". This change would provide additional flexibility for modifying requirements within the provisions of Title 10 Code of Federal Regulations Part 50.59 (10 CFR 50.59) and is consistent with NRC guidance provided in Generic Later 86-10 dated April 24, 1986, regarding Implementation of Fire Protection Requirements. (Note: No changes have occurred since the submittal of the 1987 Annual Report.) l 159 11/09/87 Containment Ventilation Isclation System (CVIS): Revises Trojan Technical Specification 3.9.9,
" containment ventilation Isolation System", to resolve inconsistencies within the Technical Specifications.
Technical Specification 3.9.9 curently requires the CVIS to be operable at all times while in Mode 6; however, ' technical Specification 3.9.4 establishes operability requirements for the Containment Build-ing penetrations (including Containment ventilation isolation valves) as applicable in Mode 6 only When CORE ALTERATIONS or fuel movement inside the Containment is in progress. Additionally, the ACTION statement is revised to specify closing Containment Ventilation f penetrations if CVIS is inoperable. 159
_ - - _ _ _ _ _ _ - _ _ _ = _ _ - - _ . - _ _ _ _ _ - _ _ _ - - _ - _ _ - _ _ _ _ . _ _ - . - _ _ _ _ . - _ _ _ _ _ - _ __ _ - __ _-_ _ - - _ _ . b ; j-s TABLE 6.B-2 Sheet 3 of 5 N l LCA Date Number Submitted Subject and Status p NRC letter dated December 22, 1987, requested L re-review and revision of this LCA to address identified NRC concerns. On February 25, 1988 PGE forwarded response to NRC questions regarding this License Change Application as well as a revised Significant Hazards Consideration determination to incorporate these. responses. 161 11/20/87 Nuclear Fuel Upgrade /ECCS Reanalysis: This LCA rovises the Trojan Technical Specifications to include the effects of nuclear fuel-design changes, i.e., reconstitutable fuel assembly top nozzles and axial fuel blankets. A telephone call between pCE, Westinghouse and the NRC on March 4, 1988, responded to NRC questions, je~. NRC telephone call on April 5, 1988, requested a (j supplement to this LCA to address the environmental aspects of 10 CFR 51, " Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions". PGE letter of May 27, 1988, transmitted an Addendum to LCA 161, containing a summary of fuel assembly changes as referenced in LCA 161. NRC letter dated July 1, 1988, requested that a Trojan-specific analysis, based upon a postulated locked rotor event Which assumes fuel failure for fuel pins that exceed the departure from nucleate boiling (DNB) safety limit criterion, be included in the accident evaluation. In accordance with PCE letters of August 12.and December 16, 1988, this information is currently scheduled for submittal to the NRC in February 1989. 165 03/01/88 Fuel Enrichment Specifications: Requests the removal of the 3.5 weight percent Uranium-235 (U-235) enrichment limit on reactor fuel assemblies and increases the enrichment limit fcr the new fuci storage racks to 4.5 weight percent. 160
7 t TABLE 6.B-2 Sheet 4 of 5 l e1 l - LCA Date l Number Submitted Subject and Status . The NRC requested a supplement to this LCA to j address the environmental aspects of 10 CFR 51,
" Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions".
NRC letter dcted May 5, 1988, forwarded for PGE i information, the Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Ilearing relating to this LCA. On u gust 5, 1988, PGE submitted an Addendum to LCA 165 as a result of the NRC request that PGE review environmental considerations associated with an increase in nuclear fuel enrichment. NRC later dated October 6, 1988, forwarded for PGE information, a copy of the Notico of Environmental Assessment and Finding of No Significant Impact k relating to LCA 165. , 168 07/08/88 Miscellaneous Editorial Changes Incorporates various editorial corrections and clarifications into the Trojan Radiological j ' Effluent Technical Specifications (RETS). If9 08/12/83 Emergency Core Cooling System (ECCS) Check Valves: l Revises the surveillance requirements for the ECCS check valves in the Trojan Technical Specifica-tions. Specifically, this change requires adjust-ing the observed leakage rates through the ECCS
- f. heck valves when testing at lower-than-maximum differential precsure.
PCE letteE dated August 16, 1988, transmitted a ; replacement page for this LCA, to provide the conclusions of the safety and environmental evaluations performed for this LCA (inadvertently omitted from the original submittal). O' 161
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? TABLE 6.B-2 Sheet 5 of S I (,%) - -
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l l LCA Date . . I Sub.iect and Status ! Number Submittel_ 170 10/07/88 Revision to PGE-1017, Trojan Security Plan: Revises the Trojan Nuclear Plant Security Plan by allowing the use of dedicated observers in lieu of security officers to compensate for safeguards degradations pursuant to Nuclear Regulatory Commission (NRC) Regulatory. Guide 5.61, Revision 1 (November 1987), " Reporting of Safeguard Events", and NUREG-1045, " Guidance on the Application of Compensatory Safeguards Measures for Power Reactor Licensees (January 1984)". This LCA also describes the conformance of electrical cable penetrations in the control room floor to Part 73.55(c)(6) of Title 10, Code of Federal Regulations. PGE letter dated December 23, 1988, submitted an Errata to this LCA which moved the "Significant Hazards Consideration Determination" to an unclassified portion of the LCA. L 171 09/09/88 Pressurizer Low-Pressure Safety Injection Sotpoint: Revises the pressurizer low-pressure safety
$ ;, injection setpoint. This new setpoint is necessary to accomodate a change to a different transmitter design used to measure narrow-range pressurizer pressure.
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162 x _ _ - _ = _ _ - - - _ _ - _ - _ - _ - _ _ _ _ - - _ _ _ - - _ _ _ . - - - _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ _ - - _ _ _ _ - - _ _ . _ - _ _ _ _ _ - _ - _ ________-__________O
! I l I 1 1 /\ t i ) l %J ! 6.C LICiNSING DOCUMENT CHANGE REQUESTS (LDCRs) 1 APPROVED DURING 1988 Licersing Documents consist of various PGE Topical Reports and the Trojan FSAR. Under Title 10 Code of Federal Regulations, Part 50.54 and Part 50.59 (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 1988. LDCR: 87-20 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved February 9,1988 and issued February 26, 1988 as Revision 19. Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were imple-(~'} (s ,/ mented under Title 10 to the Code of Federal Regula-tions, Part 50.54(p) [10 CFR 50.54(p)]; therefore, the Trojan Operating License and Technical Specifications were not affected. LDCR: 87-21 Document: Environmental Monitoring Plan (Non-Radiological), PGE-1030 Status: Approved January 25, 1988 and will be issued upon approval of Federal Aviation Administration (FAA) Flight Paths. Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were imple-mented under Title 10 to the Code of Federal Regula-tions, Part 50.54(p) [10 CFR 50.54(p)]; therefore, the Trojan operating License and Technical Specifications were not affected. C\ 163
LDCR: 88-02 Document: Trojan Radiological Emergency Response Plan, PGE-1008 Status: Approved April 12, 1988 and issued April 15, 1988 as Amendment 13. Safety Evaluation: Changes consisted of clarification and revision of the information presented in the Trojan Radiological Emerrency Plan. The Emergency Plan is not referenced in the 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 criteria. The effectiveness of the Emergency Plan was not decreased and remains consistent with the standards of 10 CFR SC.47(b). LDCR: 88-03 Document: Trojan Security Force Training and Qualification Plan, PGE-1024 _ Status : ' Approved April 20, 1988 and issued 1 June 10, 1988 as Revision 6 Safety Evaluation: Changes to this document were not considered to be a degradation of Plan security and were implemented under 10 CFR 50.54(p); therefore, the Trojan Operating License and Technical Specifications were not affected. LDCR: 88-04 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved March 29, 1988 and issued April 20,1988 as Revision 20. Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were implemented under 10 CFR 50.54(p); therefore, the Trojan Operating License and Technical Specifications were not affected. O 164 l
-)
o i i l (; X LDCR: 88-05
'" . Document: Inservice Testing Program for Pumps and Valves,
- , Second 10-Year Interval, PGE-1048 Status
- Approved March 18, 1988 and issued April 18, 1988 as Revision 1.
Safety Evaluation: Changes' consisted of a general upgrade of the Inservice Testing (IST) Program including editorial
. corrections, clarifications, and additional testing requirements to provide greater assurance of equipment operability.
LDCR: 88-06 Document: Final Safety Analysis Report, FSAR Status: Approved March 8, 1988 and issued as a part of Amendment 7 to the FSAR on July 1, 1988. Safety Evaluation: This LDCR was initiated to expedite local leak rate testing and to reduce exposure time. The minimum test duration has been changed from i hour to 15 - minutes in accordance with American National Standards Institute (ANSI)/American Nuclear Society ( . Standard 56.8-1981, " Containment System Leakage Testing Requirements". LDCR: 88-07 Document: Nuclear Quality Assurance Program, PGE-8010 Status: Approved March 17, 1988 and issued Septemb'er 30, 1988 as Interim Change 187-2. Safety Evaluation: This LDCR was initiated to make the' Quality Assurance Program consistent with organizational reporting j changes for the Performance Monitoring and Event Analysis (PM/EA) Branch and the Corporate Security Department, and to resolve NRC concerns with Revision 11 to the Quality Assurance Program. l-l- 165
]!
1 I LDCR: 88-08 Document: Final Safety Analysis Report, FSAR Status: Due to the volume of changes involved, LDCR 88-08 was divided into nine individual change requests to provide approval by chapter and/or section. The last change request was approled June 13, 1988 and Amendment 7 to the FSAR was issued July 1, 1988. Safety Evaluation: Pursuant to 10 CFR 50.71(e), annual revision of the FSAR is required to assure that the information in the FSAR contains the latest material reflecting the design of the Plant. All changes initiated with this LDCR were editorial and/or administrative in nature and did not involve a change to the Technical Specifications or any unreviewed safety or environmental 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 20 CFR 50.59(a), cr were required by NRC request pursuant to 10 CFR 50.54(f) or (h). LDCR: 88-09 Document: Operating Experience Review Program, PCE-1044 Status: Approved March 30, 1988 and issued April 7, 1988 as Amendment 2. Safety Evaluation: This LDCR was initiated to reflect organizational changes and add additional approvals in the Operating Assessment Review (OAR) process. LDCR: 88-10 Document: Environmental Qualification Program Manual. PGE-1025 Status: Approved July 8, 1988 and issued August 31, 1988 as Amendment 5. O 166
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_l ' l<f+ . l hi[ Safety Evaluation: ' Topical: Report PGE-1025 is incorporated in Section- ! f( 3.11'of;the FSAR by reference. Changes-to this~ 0
' : c document were made in.accordance.withL10 CFR;50,71, l, which requires.that;the FSAR and' associated
. referenced licensing' document be maintained in anz 1 updated condition. These changes did not result'in? ,1 i
a change to the Technical Specifications;nor did they create an unreviewed safety or' environmental' a
>, . question.
q #, LDCR: 88-12
~ Document: Snubber Inservice Testing. Program, PGE-1050.
Status: ' Approved September-30, 1988 and issued November 10, 1988 as new document.. Safety Evaluation: This Topical Report.was created to combine alir mechanical.and, hydraulic snubber testing requirements and guidance into a. single document on Which testing procedures will be based. The contents of this document are' consistent with
. Technical. Specification requirements.
- - LDCR: 88-14 Document: Trojan Nuclear Plant Analyses of Pipe System.
Breaks Outside Containment,-PGE-1004 Status: Approved July 11, 1988(and issued December. 30,.1988'- as Amendment 5.
-Safety Evaluation: Topical Report PGE-1004.is incorporated in Sections
.3.6 and 3'.8 of'the FSAR by reference. Changes to this document were made in accordance'with PCE's Nuclear Division Procedures'and 10 CFR 50.71, which-require that the FSAR and associated referenced licensing document be maintained in an updated condition. These changes did not result'in a change to the Technical' Specifications nor did they create an unreviewedssafety or environmental question.
LDC2 was initiated to make numerous editorial changes and to incorporate Plant design changes including the new steam generator blowdown system.
=. k 167
LDCR: 88-15 Document: Nuclear Quality Assurance Program, PGE-8010 q l' Status: Approved May 5,1988 and issued September 30, 1988 as Interim Change 188-1. Safety Evaluation: This LDCR was initiated to reflect the organizational responsibility assignments that will exist after the reorganization of the Nuclear Quality Assurance Department (NQAD). LDCR: 88-16 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved June 6, 1988 and issued September 23, 1988 as Revision 21. Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were implemented under 10 CFR 50.54(p); therefore, the Trojan operating License and Technical Specifications were not affected. LDCR: 88-19 Document: Final Safety Analysis Report, FSAR Status: Due to the volume of changes involved, LDCR 88-19 was divided into nine individual change requests to provide approval by chapter and/or section. The last change request was approved October 17, 1988 and Amendment 8 to the FSAR was issued November 1, 1988. Safety Evaluation: Pursuant to 10 CFR 50.71(e), annual revision of the FSAR is required to assure that the information in the FSAR contains the latest material reflecting the design of the Plant. All changes initiated with this LDCR were editorial and/or administrative in nature and did not involve a change to the Technical Specifications or any unreviewed safety or environmental 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 20 CFR 50.59(a), or were required by NRC request pursuant to 10 CFR 50.54(f) or (h). 168
LDCR: 88-20 V f Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved July. 26, 1988 and issued October 6, 1988 as Revision 23. Safety Evaluation: Changes made to this document were not considered to be a degradation of. Plant security and were implemented under 10 CFR 50.54(p); therefore, the Trojan operating License and Technical Specifications were not affected. LDCR: 88-21 Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved September 1, 1988 and issued October 4, 1988 as Revision 22. Safety Evaluation: Changes made to this document were not considered to be a degradation of Plant security and were implemented under 10 CFR 50.54(p); therefore, the Trojan Operating License and Technical Specifications were not affected.
\
LDCR: '88-24 Document: Final Safety Analysis Report, FSAR Status: Approved September 21, 1988 and issued as a part of Amendment 8 to the FSAR on November 1, 1988. Saf'ety Evaluation: This LDCR was initated to create consistency between the Trojan Technical Specifications and the FSAR with regard to tabulations of Containment isolation valves. l. l l 169 ! {~ L o '
I LDCR: 88-25 i Document: Trojan Nuclear Plant Security Plan, PGE-1017 Status: Approved August 12, 1988 and issued September 13, 1988 as Revision 24. ; I Safety Evaluation: Changes made to this document were not considered l to be a degradation of Plant security and were j implemented under 10 CFR 50.54(p); therefore, the ! Trojan Operating License and Technical Specifica- l tions were not affected. 1 LDCR: 88-26 i Document: Trojan Radiological Emergency Response Plan, PGE-1008 > Status: Approved September 28, 1988 and issued September 30, 1988 as part of Amendment 14. Safety Evaluation: Changes consisted of clarification and revision of the information presented in the Trojan Radio-logical Emergency Plan. The Emergency Plan is not referenced in the Technical Specifications, except i for the annual audit of the Plan required by the j Trojan Nuclear Operations Board (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 criteria. The effectiveness of the Emergency i Plan was not decreased and remains consistent with the standards of 10 CFR 50.47(b). ] ' 1 l l 9 170 l l t- _ _ ____________-
)
t LDCR: 88-27 Document: ' Trojan Radiological Emergency Response Plan, lL PGE-1008
, Status: Approved September 22, 1988 and issued September 30, 1988 as part of Amendment 14.
Safety Evaluation: Changes consisted of clarification and revision of the information presented in the Trojan Radiological Emergency Plan. The Emerge.ncy Plan is not referenced in the 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' criteria. The effectiveness of the Emergency Plan was not decreased and remains consistent with the standards of 10_CFR 50.47(b).
LDCR: 88-28 Document: PGE Radiation Protection Program, PGE-8005 O Status: . Approved November 29, 1988 and issued January 31,
-Q~ ~ '1989 as Revision 5.
Safety Evaluation: This LDCR was initiated to provide current and improved guidance for the PCE Radiation Protection Program and to reflect organizational changes l 171 .__._1_.._ _ __.____ __ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .___
jaagg 6.D Plar.t' Tests ,
\)
The'following Plant tests were performed in 1988.and are reported in
~
accordance with Title'10, Code.of Federal Regulations,:Part 50.59.-
- 1. Temporary Plant Test 220 Temporary Plant Test 220 was performed to measure the output wave-
. form from various pressure transmitters to determine if sinusoid pressure transients are occurring in the Reactor Coolant System.
This test did not involve an unreviewed safety question'or a change to the Trojan Technical Specifications.
- 2. Temporary Plant Test 221 TemporaryLPlant Test 221-was' performed as part of the startup testing of the new Remote Shutdown Station to provide control of' software configuration during testing. This test did not' involve an unreviewed safety question or a change _ to- the Trojan Technical Specifications.
- 3. Temporary Plant Test 222 Temporary Plant Test 222 was performed to (1) record the as-received hardware and firmware configuration of the new Remote Shutdown f- s . Station.RPU-Al,-(2) check the RPU-Al power supply voltages and' I adjust if necessary, (3)-test the power supplies' auctioneering, and (4) test the RPU-Al power supplies' status annunciation. The~ test did not involve an unreviewed safety. question or a' change to the Trojan Technical Specifications.
- 4. Temporary Plant Test 223 Temporary Plant Test 223 was performed to (1) record the as-received hardware and firmware configuration of the new Remote Shutdown Station RPU-A2, (2) check the RPU-A2 power supply voltages and adjust if necessary, (3) test the power supplies' auctioneering, and
.' -(4) test the RPU-A2 power supplies
- status annunciation. The test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 5. Temporary Plant Test 224 .
Temporary Plant Test 224 was performed to (1) record the as-received hardware and firmware configuration of the new Remote Shutdown Station RPU-A3, (2) check the RPU-A3 power supply voltages and adjust if necessary, (3) test the power supplies' auctioneering, and (4) test the RPU-A3 power supplies' status annunciation. The test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. 1' R l 172
- 6. Temporary Plant Test 225 Temporary Plant Test 225 was performed to (1) record the as-received hardware and firmware configuration of the new Remote Shutdown Station RPU-A4, (2) check the RPU-A4 power supply voltages and adjust if necessary, (3) test the power supplies' auctioneering, and (4) test the RPU-A4 power supplies' status annunciation. The test did not involve an unreviewed safety question or a change to the Trojan Technict 1 Specifications.
- 7. Teenporary Plant Test 226 Temporary Plant Test 226 was performed to record the as-received hardware and firmware configuration of Remote Shutdown Station RPU-B1 and check RPU-B1 power supply voltages and adjust as required. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 8. Temporary Plant Test 227 Temporary Plant Test 227 was performed to (1) record the as-received hardware and firmware configuration of the new Remote Shutdown Station RPU-B2, (2) check the RPU-B2 power supply voltages and adjust if necessary, (3) test the power supplies' auctioneering, and (4) test the RPU-B2 power supplies' status annunciation. The test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 9. Temporary Plant Test 228 Temporary Plant Test 228 was performed to (1) record the as-received hardware and firmware configuration of the new Remote Shutdown Station RPU-B3, (2) check the RFU-B3 power supply voltages and adjust if necessary, (3) test the power supplies' auctioneering, and (4) test the RPU-B3 power supplies' status annunciation. The test i did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 10. Temporary Plant Test 229 Temporary Plant Test 229 was performed to record the as-received hardware and firmware configuration of Remote Shutdown Station OIU-A and check OIU-A power supply voltages. This test did not involve an unreviewed safety question or a change to the Trojan Technical l Specifications.
- 11. Temporary % st Tes,t 230 Temporary T2 ant Test 230 was performed to record the as-received hardware and firmware configuration of Remote Shutdown Station OIU-B and check OIU-B power supply voltages. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
l l 173 l m_
g 112.' Temporary Plant Test 2311 Temporary' Plant Test 231 was performed to record the as-received
- hardware:and firmware configuration of Remote Shutdown Station OIU-AFW'and check.0IU-AFW. power supply voltages. 'This. test
'did ! not involve an unreviewed safety question or a change to the, Trojan Technical; Specifications.
.13. Temporary ~ Plant Test 232 .
Temporary Plant Test 232 was performed'to. check the'C-160 panel power supply. voltages and adjust as necessary. This' test did not involve an'unreviewed s&fety question or a change to the . Trojan Technical. Specifications.
- 14. Temporary Plant Test 233 Temporary Plant. Test 233 was performed to document vendor-supplied.
software and load the software into the new' Remote. Shutdown Sta-tion. .This test did not involve an unreviewed safety question or a change'to the Trojan Technical Specifications.
- 15. Temporary Plant Test 234 Temporary Plant Test' 234.was performed to demonstrate operability of-the new Remote-Shutdown. Station excluding field inputs and outputs.
This test did not involve an unreviewed safety question or a' change
'O,D .to the Trojan Technical' Specifications.
- 16. Tentoorary Plant Test 235 -
Temporary. Plant Test 235 was. performed' to verify that field inputs and outputs are wired correctly to the new Remote Shutdown Station and to verify the. circuits interrupted by the Remote Shutdown Sta-tion: installation will perform their respective functions after restoration. This test did not involve an unreviewed safety ques-tion or a change to the , Trojan Technical Specifications.
- 17. Temporary Plant Test 237 Temporary Plant Test 237 was performed to tune the controllers in the Remote Shutdown Station enabling the' controllers to have the same characteristics as their counterparts in the control room.
This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. O 174
- 18. Temporary Plant Test 240 Temporary Plant Test 240 was performed to functionally test the new liquid radwaste demineralizers to verify design flowpaths and measure system flowrates and pressure drops. In addition the test was used to obtain baseline operating data for the system. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specification.
- 19. Temporary Plant Test 241 Temporary Plant Test 241 was performed to provide data acquisition for determining if piping system or components are contributing to pressure transmitter f ailures. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 20. Temporary Plant Test 242 Temporary Plant Test 242 was performed to verify that the modifica-tions to the moisture separator reheaters (MSRs) and tube bundles for the MSRs meet the vendor's performance guarantees. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 21. Temporary Plant Test 243 Temporary Plant Test 243 was performed to determine the accepta-bility of the Halon Fire Suppression System installed for the new Remote Shutdown Station. This test did not involve an unreviewed safety question or a change to the Trojen Technical Specifications.
.22. Temporary Plant Test 244 Temporary Plant Test 244 was performed to acquire system pressure data from pressurizer pressure channels using a fast response trans-ducer and to monitor transmitter and sensing line temperatures. The test also monitored transmitter / transducer output with P-250 com-puter for time-related comparison of signals. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 23. Temporary Plant Test 245 l
Temporary Plant Test 245 was performed to acquire baseline flow data associated with the electric auxiliary feedwater pump for comparison with the manufacturer's data to verify adequate system performance. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. O 175
I i
- 24. Temporary Plant Test 247 7
i ) V Temporary Plant Test 247 was performed to provide for pre- and post-operational testing of the Steam Generator Blowdown System and com-ponents to verify that performance meets design requirements and documentation. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 25. Temporary Plant Test 248 Temporary Plant Test 248 was performed to provide information ret;arding the imbedmont depth of rock bolts used for pipe whip restraints using ultrasonic testing methods. This test did not I
involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 26. Temporary Plant Test 249 Temporary Plant Test 249 was performed to demonstrate that the Plant can be maintained in Hot Standby conditions for at least 30 minutes from the Remote Shutdown Station using ON1-17 with the minimum shif t crew necessary for safe shutdown per Technical Specification 6.2.2.a.
The test also demonstrated that the Reactor Coolant System can be cooled down more than 50*F from the Remote Shutdown Station using ONI-17. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. A k 27. Temporary Plant Test 251 Temporary Plant Test 251 was performed to gather flow test data for determining the feasibility of supplying service water from the fire system pumps as described in Emergency Fire Procedure (EFP) 2, Revision 2. " Alternative Shutdown for Complete Loss of Service Water Caused by Fire". This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 28. Tempo.rary Plant Test 252 Temporary Plant Test 252 was performed to provide post-construction flushing of the new Steam Generator Blowdown System piping and verify miniflow capability of the new Steam Generator Blowdown Pump P-335. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 29. Temporary Plant Test 253 Temporary Plant Test 253 was performed to verify control room habi-tability following modifications affecting the Control Room Venti-lation System. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications. <
m 176
- 30. Temporary Plant Test 254 Temporary Plant Test 254 performed a leakage test of the control room boundary following modifications to the Control Room Ventila-tion System. This test did not involve an unreviewed safety ques-tion or a change to the Trojan Technical Specifications.
- 31. Temporary Plant Test 257 Temporary Plant Test 257 was performed to verify and document the post-installation baseline operational data for the Y26 and Y28 preferred inverters. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 32. Temporary Plant Test 258 Temporary Plant Test 258 was performed to verify and document the post-installation baseline operational data for the new station Batteries D11 and D12. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 33. Temporary Plant Test 259 Temporary Plant Test 259 was performed to acquire data to verify the ability of Process Radiation Moniter (PRM)- 1 to provide accurate, representative surveillance data of Plant gas releases with specific lineups of the Hydrogen Vent System and Containment Purge System.
This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 34. Temporary Plant Test 261 Temporary Plant Test 261 was performed to collect operating data to determine the amount of thermal stratification of the pressurizer surge line, and to determine the amount of movement in the surge line in relation to pipe whip restraints. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 35. Temporary Plant Test 262 Temporary Plant Test 262 was performed to monitor the 1-1/2-inch high pressure safety injection lines and the 3-inch normal and alternate charging lines to the Reactor Coolant System to gather data for determining if thermal stratification or cyclic transient exist in these lines. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
l
- 36. Temporary Plant Test 263 Temporary Plant Test 263 was performed to inspect pipe whip res- '
traints and adjacent pipe supports to evaluate potential contacts of the process piping with the pipe whip restraints. This test did not involve an unreviewed safety question or a change to the Trojan l Technical Specifications. i 177 l 1 1
- 37. Temporary Plant Test 264 l'v;l
' Temporary Plant Test 264 was performed to monitor the main feedwater piping inside containment for thermal stratification. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 38. Temporary Plant Test 265 Temporary Plant Test 265 was performed to verify the proper opera-tion of the Component Cooling Water System surge tank level instru-mentation following modifications. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 39. Temporary Plant Test 266 Temporary Plant Test 266 was performed t.o leak test the first-off and second-off check valves in the Safety Injection System in order to determine the valve leak rate for differential pressures greater than 150 psid. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 40. Temporary Plant Test 268 Temporary Plant Test 268 was performed to measure the discharge flow f; and pressure of the diesel and electric fire pumps at shutoff, (m,/ rated, and peak loads for determining the accuracy of flow meter FI-5953. The test was also used to verify that the pumps achieve the above requirements as required by the Technical Specifications.
This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 41. Temporary Plant Test 269 Temporary Plant Test 269 was performed to provide post-modification testing of all circuits interrupted or modified as a result of Appendix R identified deficiencies. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 42. Temporary Plant Test 271 Temporary Plant Test 271 was performed to establish baseline data for a proposed change in the testing configuration for the fire system main loop flow test. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
f3 4 4
% )
, 178 1 i L ____ _ _ _
- 43. TemporaLY Plant Test 272 Temporary Plant Test 272 was performed to provide testing and acceptance guidelines for the Emergency Operating Facility remote computercontrolled ventilation radiation monitor. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 44. Temporary Plant Test 273 Temporary Plant Test 273 was performed to obtain a process sample from the pressurizer pressure Transmitter PT-458 instrument line and to return the transmitter to service. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 45. Temporary Plant Test 274 Temporary Plant Test 274 was performed to ensure the sensing lines for pressurizer pressure Transmitter PT-457 are filled and to iden-tify sensing line fluid chemistry at the transmitter. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 46. Temporary Plant Test 277 Temporary Plant Test 277 was performed to verify the proper flows from the diesel and electric driven fire pumps. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
- 47. Temporary Plant Test 278 Temporary Plant Test 278 was performed to determine the potential for providing water flow from the Reflection Lake to the cooling tower basin. This test did not involve an unreviewed safety ques-tion or a change to the Trojan Technical Specifications.
- 48. Temporary Plant Test 290 Temporary Plant Test 290 was performed to measure the back-leakage for safety injection first-off, cold-les check Valve 894BC. This test did not involve an unreviewed safety question or a change to the Trojan Technical Specifications.
O 179 l
. _ _ _ _ _ _ _ _ _ _ - ]
.I 6.E CHANG"IS TO PROCEDURES
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1 l i 1 Procedures described in the Trojan Final Safety Analysis Report (FSAR) are used by the Trojan Plant Operating Staff and by vrrious offsite support organizations of Portland General Electric Company. These procedures are described in the Trojan FSAR, Section 13=.5, Plant Procedures, and Section 17.0, Quality Assurance. In 1988, the following j organizations nade changes to safety-related procedures in accordance with Title 10,' Code of Federal Regulations, Part 50.59 (10 CFR 50.59), and concluded that none of the changes involved unreviewed safety questions: Trojan Nuclear Plant N.Jelear Division , Nuclear Sofety & Regulation L Nuclear Plant Engineering Nuclear Quality Assurance Power and Fuels Contracts Corporate Security Corporate Records Chariges to procedurer 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. 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.
)
i
/*
180
o 6.F SETPOINT CHANGES The following setpoint changes were made in 1988 to instruments, alarms, ' relief valves, and other control and protective devices whose setpoints are described in the Final Safety Analysis Report (FSAR) and are reported in accordance with Title 10, Code of Federal Regulations, Part 50.59:
- 1. Plant Setpoint Change 88-01 4
Nonconform;nce Report NCR 87-427 identified a maximum Refueling Water Storage Tank (RWST) level transmitter inaccuracy of 4 percent. .: Plant Setpoint Change 88-01 increased RWST low-low level alarm set-point from 13 percent to 17 percent to account for the instrument error. This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 2. Plant Serpoint Change 88-09 Licensee Event Report LER 87-30 identified that the Component Cooling Water to Residual Heat Removal Heat Exchanger low flow alarm setpoints were less than the 5000 gpm required by the accident analysis.
l 1 - Plant Setpoint Change 88-09 increased the low flow alarm setpoints to 5000 gpm as required by the accident analysis. This setpoint change did not involve a change to the Trojan Technical Specifications or an unreviewed safety question.
- 3. Plant Setroint Change 88-10 Steam generator narrow-range level transmitter drift resulted in the -
high-high level turbine trip values being in excess of the Technical Specification allowable value. Plant Setpoint Change 88-10 decreased the high-high level turbine trip setpoint from 75 percent to 70 percent narrow-range level.
~
This setpoint change did not involve a change to the Trojan s Technical Specifications or an unreviewed safety question. r 181
- summe m
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IVWW C'
' David W. Cockfield Vice President, Nuclear March 1, 1989 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 one copy of Portland Ceneral Electric Company's Annual Report for the Trojan Nuclear Plant for the calendar year'1988. Sincerely, Enclosure c: Mr. William T. Dixon (2) State of Oregon Department of Energy Mr. John B. Martin (1) Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. R. C. Barr (1) NRC Resident Inspector Trojan Nuclear Plant Nf
$s41 Y fg (3 o'
*l 121 S W Salmon Street. Pomand. Oregon 97204 e_- _-}}