ML20246K003

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Semiannual Radioactive Effluent & Waste Disposal Rept Jan- June 1989
ML20246K003
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 06/30/1989
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8909050333
Download: ML20246K003 (46)
v • d • e


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David W. Cockfield Vice President. Nuclear August 29, 1989-Trojan Nuclear Plant Docket 50-344 License NPF-1 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sir:

TROJAN NUCLEAR PLANT Semiannual Radioactive Effluent and Waste Disposal Report In accordance with Trojan Nuclear Plant Technical Specifications, attached.is the semiannual Radioactive Effluent and Waste Disposal Report for the period through June 30, 1989. This information will also be

-included in the 1989 Annual Operating Report.

Sincerely, y

Attachment c: Mr. David Stewart-Smith

-State of Oregon Department of Energy Mr. John B. Martin Regional Administrator, Region V U. S. Nucle.t Regulatory Commission Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant h

gg9oitok3 8*90630*Sie4 ,t R I 121 s w saimon street. Portand. Oregan 97204

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Requirement l

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 of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January 1 and July 1 of each year.

"The Radioactive Effluent helease 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 Caseous Effluents from Light-Water-Cooled Nuclear Power Plant',

with data summarized on a quarterly basis following the format of Appendix B thereof.

"The Radioactive Effluent Release Reports may include a summary of the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21 (Rev. 1), with data summarized on a quarterly basis following the format of Appendix B thereof, If the summary of the meteorological data is not included in the 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 making these assessments (e.g., specific activity, exposure time and location) shall be included in these reports.

"The Radioactive Effluent Release Reports shall include a copy of all licensee event reports required by Specification 3.11.1.1 and 3.11.2.1.

"The Radioactive Efflucat Eelease Reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.

The meteorological conditions concurrent with the releases of ef flu-ents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be pecformed 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 Manual (ODCM) made during the reporting period, as provided in Speci-fications 6.13 and 6.14".

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Complete data for the period from January 1989 through June 1989 have' been included.

2

A. EFFLUENT AND WASTE DISPOSAL REPORT lhis 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-m 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, 1989 through June 30, 1989.

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 Gaseous Waste Sampling and Analysis Program". The referenced "LLD"-

specifications are not used as limiting values for reporting activity; all measurable activity is reported. For smuma-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 factors 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, Containment Monitoring System, 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-iodines and particulate with greater than D-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.

As part of the investigation to determine if PRM-1 was receiving repre-sentative samples, testing was performed on the Containment ventilation exhaust duct. An internal analysis of the test results in conjunction with outside exports was completed on September 30, 1988. The analysis indicated that PRM-1 will obtain a representative sample when the Con-tainment purge exhaust system is operated (flow approximately 50,000 cfm) but that PRM-1 may not obtain a representative sample when using the hydrogen vent system (flow approximately 140 cfm).

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Immediate coirectise actfun was to install a temporary modification for m

the sample probe for 1 RM-1 to sample direct ly from the "A" Train hydrogen vent duct. On a longer term basis, the design of the PRM-1 sampling cystem 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 determino its effect en overall Plant releases. A review of the data from the proncure venting operations before and after the temporary modification indicates' s

that the PRM-1 readings may have been as much as 15 percent lowar thnn the actual relenses. However, the Containment pressure venting relences 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 vould not have had a significant effect en the overall rnleases from the Plant and would have been within the previous.jy reported estinated error. In addition no Technical Specifi-cation release limits were exceeded, end there was not a significant impact on offsite doses.

The following terr.s are used:

Ky = Average total body dose factor due to gamma emissions, Ey - Avgrage skin dose factor due te beta emissions, My = average air dose factor due to beta, emissions, E, = Average air dose factor due to gamma emissions,

, R1 = Average dose' f actor for nuclides other than noble gases at the controlling exposure location?.

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TABLE A-1 PART A-1 SUPPLEMENTAL INFORMATION January 1, 1989 through June:30, 1989 I

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/see 1.50E-1 1.85E-1 'I q 2.0 Ky QTv~< 1 Ci/sec 3.822-1 4.48E-1 0.33 (Ly + 1.1 N y) )

)

2..-Tech Spec 3.11.2.2, Quarterly P.verago l 1

QTv <. 1 C1/sec 5.05E-3 6.0SE-3 l

- l 50 N y-

.QTv < 1_ Ci/sec 3.775-3 3.92E-3 25 M y I

3. Tech Spec 3.11.2.4(1), Quarterly Average Requiring Use.of the Gaseous Radwaste I Treatment System I

QTV < , 1 Ci/sec 2.53E-3 3.04E-3 100 N y QTV < 1 Ci/see 1.89E-3 1.96E-3 50 M y 1

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L PART.A-2 p, SUPPLEMENTAL INFORMATION

. January 1-, 1989 through June 30,,1989 3

RECULATORY LIMITS

p. <

n Gm eous Iodine 131. Tritium, and Particulate First' Second tdith > 8 Day T1/2 Limits, Unit -Quarter Quarter

1. , Tech spec 3.11.2.1(b), Instantaneous QTV < 1 Ci/sec 3.81E-2 7.58E-3'

.67 Ri-

2. ' Tech Spec 3.11.2.3, Quarterly Average QTv < l' C1/see 2.55E-4 5.08E-5 100 Ri 3.- Tech Spec 3.11.2.4(2), Quarterly Average

' Requiring.Use of the Ventilation Exhaust Treatment System-QTv < 1 Ci/see 1.28E-4 2.54E-5.

200 Ri

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TABLE A-3 i

pART A-3 SUPPLEMENTAL INFORMATION January 1, 1989 through June 30, 1989

. REGULATORY LIMITS {

Liquid Effluent Limits i

1. Tech Spec 3.11.1.1 Instantaneous discharge concentrations i o Instantaneous less than the maximum permissible  ;

concentrations listed in 10 CPR Part  !

20, Appendix B. Table II, Column 2, for j radionuclides other than dissolved or I I

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 i Quarterly Average quarter excluding tritium and dissolved noble gases. If this limit is i exceeded, cumulative dose due to liquid j effluents will be limited to 1.5 mrem j to the whole body and to 2.5 mram to j 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 l Quarterly Average Requiring shall be maintained and used when l Use of the Liquid Radwaste activity discharged (excluding tritium )

Treatment System and dissolved noble gas) would exceed  ;

1.25 Ci/Qtr. i

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. l l

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, PART A-4 SUPPLEMENTAL INFORMATION

' January 1.-1989 through June 30, 1989 MAXIMUM PERMISSIBLE CONCENTRATIONS Liquid =

MPC MPC

.. . Isotope (uCi/cc) Isotope (vCi/cc)

L Fluorine'18 8 x 10-4 lodine 131 3 x 10-7 Chromium 51 L2 x 10-3 lodine 132 '8-x 10-6 Manganese 54 11 x 10-4 Tellurium,132E 2 x.10-5'

-1ron 55 8 x 10-4 ' Iodine 133 1 x 10 Cobalt 57' 4 x 10 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 s1 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 Caseous Caseous MPCs are not used-In calculating technical specifications at Trojan, i

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c'*- i TABLE A-5

'PART A-5 SUPPLEMENTAL INFORMATION January 1, 1989 through June 30, 1989 AVERAGE ENERGY Effluent release limits are not based upon E, hence, reporting E is not 7,. 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 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 scintillation spectroscopy.

Liquid Releases.

Fission and Activation Products: Gamma spectrometric analysis of each batch is performed. Weekly composite samples are maintained for continuous releases, and the composites are analyzed for specific nuclides as required. Monthly and quarterly composites are prepared for both batch and continuous releases for specified activity determinations.

Tritium: Monthly composite samples are distilled and deionized as necessary to remove contamination and counted by liquid scintillation techniques.

Dissolved and Entrained Gases: Gaseous isotopes are determined by gamma spectrometric analysis of each batch and on a minimum frequency of once per month for continuous releases.

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TABLE A PART A-6 l[

SUPPLEMENTAL INFORMATION

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-January 1, 1989 through June 30, 1989 BATCH RELEASES

-Unit Liquid Gaseous Number of' Batch Releases 27 61 Total time period for Batch Releases Hours. 144.0 2047.6

' Maximum time period for Batch Releases Hours 12.5. 435.4 Average time period for Batch Releases Hours- 5.3 3 3 . 6 -.

Minimum time period for Batch Releases Hours 0.6

-0.3 Average dilution flow during Batch Releases GPM :32512 N/A*

ABNORMAL RLEASES Number of Abnormal Releases 0 3 Total Activity Released Cl N/A* 4.91

  • N/A = Not Applicable i

A-8

'o TABLE A-7 Sheet 1 of 2 PART B-1 CASE 003 EFFLUENTS SUMMATION OF ALL RELEASES Janubey 1, 1989 through .funo 30, 1989 First Oecond Estimated F1SSiON A13D ACTIVATION CASES Unit Ouarter Quarteg Er ror _

Total Activity Released Ci 1.43E+1 2.28E+2 13.5El Avarege Release Rate for Quarter pCi/ser. 1.84E+1 2.90E+1 Per?.ent of Limit:

Tech. Spet. 3.11.2.1. (a) - 3.44E-2 1.49E-1 Instantaneous o

Tech Spec. 3.11.2.2 - 4.89E-1 7.35E-1 Quarterly Average

[ Tech. Spe:. 3.11.0.4.(1) - 9.79E-1 1.41E-0 f Quarterly Average Requiring I I Processing 10 DIKE 131 l

Total: Iodine 131 Relesced Ci 9.13E-5 3.83E-3 +3.5El Average Release Rate for Quarter pCi/sec 1.17E-5 4.87E-4 PARTICULATE f Total with Half-lives > 8 days C1 4.77E-7 6.01E-5 13.5Ei f Average Release Rate for QJarter pCi/3ec 6.13E-S 7.65E-6 Total Gross Alpha Released Ci 6.18E-8 2.31E-7 TEITIUM Total Released Ci 6.38E0 2.SSE+1 13.0E1 Average Release Rate fcr Quarter pCi/sec 8.20E-1 3.28E0 1

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TABLE A-7 Sheet 2 of 2 IODINE 131, PARTICULATE W7.TH First Second Estimated

> 8 DAY T1/2 AND TRITIUM _ Unit Quarter Ouarter Error Total Released Ci 6.38E0 2.58E+1- 13.5El Average Release Rate for Quarter pCi/sec 8.20E-1 3.28E0 Percent of Limit:

Tech. Spec. 3.11.2.1 (b) 3.99E-3 1.66E-1 Instantaneous Tech. Spec. 3.11.2.3 3.22E-1 6.49EO Quarterly Average Tcch. Spec. 3.11.2.4(2) 6.44E-1 1.30E+1 Quarterly Average Requiring i Procasuing A-10

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TABLE A-8 Sheet 1 of 2

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PART B GASEOUS EFFLUENTS GROUND LEVEL RELEASES January'1, 1989 through June' 30, 1989' l ';y NUCLIDES RELEASED Continuous Mode ' Batch Mode Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter.

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-- FISSION GASES-Krypton 85m Ci 5.46E-02 .4.03E-03 '1.62E-02' 3.72E-03 Krypton 85 _ Ci - ND ND 1.92E+00 3.90E+00.

Krypton 87 Ci 9.23E-02 7.23E-03 9.28E-03 1.21E-03 Krypton'88 Ci 1.21E-01 9.18E-03 1.42E-02 .4.87E-03

- Kenon'.131m Ci ND ND 1.39E+00 1.64E+00 Zenon 133m Ci 4.97E-01 1.57E-03 3.09E-01 8.93E-01:

Kenon 133 Ci 9.72E+01 8.56E+01 3.86E+01 1.36E+02 Xenon 135m Ci 5.23E-01' 3.39E-02 1.75E-02 ND-Zenon-135- Ci 1.42E+00 3.98E-02 3.38E-01 3.90E-01 Ienon 137 Ci 1.77E-01 9.78E-03 ND ND Ienon 138 -Ci 2.55E-01 1.96E-02 ND ND Argon 41 Ci 9.67E-03 4.20E-04 1.59E-01 2.28E-02 TOTAL FOR QUARTER Ci 1.00E+02 8.57E+01 4.28E+01 1.43E+02-A-Il

TABLE A-8 Sheet 2 of 2 NUCLIDES RELEASED Continuous Mode Batch Mode Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Ouarter -

10 DINES Iodine 131 Ci 8.99E-05 1.92E-03 1.41E-06 1.90E-03 Iodine 132 Ci 1.10E-07 ND ND ND L Iodine 133 Ci 3.59E-05 5.79E-04 3.37E-07 3.29E-05 Iodine 135 Ci 2.79E-07 ND ND ND TOTAL FOR QUARTER Ci 1.26E-04 2.50E-03 1.75E-06 1.93E-03 PARTICULATE > 8 DAY T-1/2 AND TECHNICAL SPECIFICATION REQUIRED ISOTOPES Manganese 54 Ci ND ND ND ND Cobalt 58 Ci ND 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 4.32E-07 1.26E-07 ND 2.95E-05 Strontium 90 Ci 3.12E-08 1.11E-07 ND 1.67E-05 Niobittm 95 Ci ND ND ND 1.35E-05 Molybdenum 99 Ci ND ND ND ND Cesium 134 Ci ND ND ND ND Cesium 137 Ci 1.36E-08 2.10E-07 ND ND Barium 140 Ci ND ND ND ND Cerium 141 Ci ND ND ND ND Cerium 144 Ci ND ND ND ND Neodymium 147 Ci ND ND ND ND TOTAL FOR QUARTER Ci 4.77E-07 4.47E-07 0.00E+00 5.97E-05 l

t A-12 l

,-.  ;... i TABLE A-9 PART B 3 GASEOUS EFFLUENTS ELEVATED RELEASES January 1, 1989 through June 30, 1989

.i

.No Elevated Release Points i

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TABLE A-10 s PART C-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES January 1, 1989 through June 30, 1989 FISSION AND ACTIVATION PRODUCTS First Second Estimated Unit Ouarter Quarter Error %

Total Activity Released (excluding C1 3.08E-2 4.68E-2 13.5E+1 gases, tritium, and alpha)

Average Diluted Concentration pCi/mi 1. 9 7 E- 9 3.39E-9 Percent of Limit Tech Spec 3.11.1.1 - Instantaneous  % 2.37E-1 1.69E0 Tech Spec 3.11.1.2 - Quarterly Limit  % 1.23E0 1.87E0 Tech Spec 3.11.1.3 - Quarterly Limit  % 2.47E0 3.74E0 Requiring Processing TRITIUM Total Released Ci 5.29E+1 5.39E+1 13.0E+1 Average Diluted Concentration pCi/mi 3.39E-6 3.91E-6 Fraction of MPC  % 1.13E-1 1.30E-1 DISSOLVED AND ENTRAINED CASES Total Activity Released Ci 4.38E-3 2.90E-4 13.5E+1 Average Diluted Concentration pCi/ml 2.80E-10 2.10E-11 Fraction of MPC  % 1.40E-4 1.05E-5 CROSS ALPHA RADIOACTIVITY Total Activity Released Ci 1.38E-5 1.91E-5 13.0E+1 UNDILUTED VOLUME OF WASTE RELEASED Liters 1.17E+7 6.03E+6 15.0E0 VOLUME OF DILUTION WATER Liters 1.56E+1U 1.38E+10 11.5E+1 A-14 1

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. TABLE A-11 Sheet 1 of.2-p PART C-2 I

LIOUID EFFLUENTS-January 1, 1989 through June 30, 1989 e

NUCLIDES RELEASED Continuous Mode Batch Mode

~ Unit, 1st Ouarter- 2nd Quarter 1st Ouarter 2nd Ouarter Chromium 51 .Ci ND ND 5.25E-04; 5.53E-03 Manganese 54; Ci ND ND 2.41E-04 3.48E-04 Iron SS Ci 5.99E-03. 9.13E-04 1.15E-02 -1.22E-02 Cobalt'57' Ci- ND ND 4.53E-06 8.70E-06 Cobalt 58 Ci' ND ND 1.26E-03. 9.20E-03

' Iron 59 Ci ND ND 2.92E-05 .1.28E-04 Cobalt 60' Ci' FD :ND 5.25E-03 6.05E-03 Zinc 65 Ci - ND ND ND ND Strontium 89 Ci 1.60E-04 2.03E-05 8.61E-06 ND Strontium 90. Ci- 1.43E-06 3.93E-05~ 3.10E-06 2.27E-05 Zirconium 95 lCi ND ND 1.67E-04 1.10E-03 Niobium 95 Ci ND ND '5.33E-04 -1.75E-03 Molybdenum 99' Ci ND ND 4.72E-06' 7.76E-06 Technitium 99m 'Ci ND ND 4.80E-06 7.90E-06 Ruthenium.103 Ci ND ND 2.17E-05 8.85E-04

. Ruthenium 106 Ci ND -ND 3.26E-03 3.36E-03 Silver 110m Ci ND ND 6.17E-04 1.61E-03 Tin 113 Ci ND ND 3.02E-05 8.49E-05 Antimony.125 Ci ND ND 3.13E-04 4.18E-04 Iodine 131 Ci 7.83E-06 9.56E-05 3.01E-0A 2.22E-04

. Iodine 133 Ci' ND ND 6.78E-06 ND Cesium 134 Ci ND 3.33E-05 2.74E-05 3.80E-04 Cesium 137 Ci ND 7.92E-05 7.39E-05 5.31E-04 Lanthanum 140 Ci ND ND 3.37E-06 1.31E-04 Cerium 141 Ci ND ND ND 2.08E-04

' Cerium 144 Ci ND ND 4.56E-04 1.35E-03 Tungsten 187- Ci ND ND ND 6.31E-05 Unidentified Ci ND ND ND ND TOTAL FOR QUARTER ~ Ci 6.16E-03 1.18E-03 2.46E-02 4.56E-02 A-15

-TABLE A-11 Sheet'2 of 2 f-.

NUCLIDES RELEASED DISSOLVED AND ENTRAINED GASES-Continuous Mode Batch Mode Unit 1st Ouarter .2nd Ouarter let Ouarter 2nd Ouarter Krypton 87 Ci ~ND ND ND ND Krypton 88 Ci ND ND ND ND Xenon 131m Ci ND ND ND ND Xenon'133m Ci ND ND ND ND Xenon 133 Ci ND ND 6.63E-04 2 . 90 E-04 '-

Xenon 135 Ci- ND ND 3.72E-03 ND-Xenon 138- Ci :ND ND ND. ND-

.. TOTAL FOR QUARTER Ci ND ND 4.38E-03' 2.90E-04 A-16

l

  • l TABLE A-12 Sheet 1 of 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l.

January 1, 1989 through June 30, 1989 SOLID WASTE SHIPPED OFFSITE FOR Activity Volume Estimate l BURIAL OR DISPOSAL (Not Irradiated During During Total Fuel) - Type of Waste Six Months Six Months Error %

1. Spent Resin, Filters, Sludges, 437.9 Ci 70.63 m3 25%

Evaporator Bottoms, etc. ,

1

2. Dry Compressible Waste, Contam- 3.2 C1 116.88 m3 25%

inated Equipment, etc.

3. Irradiated Components Control 0.000 0.00 Rods, etc.
4. Other 0.000 0.00 ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE Nuclide
1. See attached sheet.
2. See attached sheet.

3.

4.

SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 9 Exclusive Truck U.S. Ecology, Inc.

P. O. Box 638 Richland WA 99352 5 Exclusive Truck Allied Nuclear, Inc.

2025 Battelle Blvd.

Richland WA 99352 A-17

7 k.

4 TABLE A-12 Sheet 2 of 2 db' IRRADIATED FUEL SHIPMENTS DISPOSITION Number of Shipments Mode of Transportation Destination 0 N/A* N/A*

ESTIMATE OF MAJOR NUCLIDE DISTRIBUTION BY TYPE OF WASTE

1. Nuclide Ci Nuclide Ci H-3 3.236 Ru-106 1.121 C-14 0.370 As-110m 0.013 Cr-51 0.021 Sn-113 0.000 Mn-54 4.133 Sb-125 1.761 Fe-55 43.884 I-131 0.001 Co-57 1.200 Cs-134 17.972 Co-58 76.038 Cs-137 40.798 Fe-59 0.002 Ba-140 0.000 co-60 123.809 Ce-141 0.000 Ni-63 111.790 Ce-144 0.387 l Sr-89 0.001 U-235 0.000 Sr-90 10.081 Pu-238 0.016 Nb-95 0.012 Pu-239 0.018 Zr-95 0.013 Pu-241 1.206 Ru-103 0.003 Cm-242 0.000 Total 437.886
2. Nuclide Ci Nuclide Ci ,

H-3 1.302 Ru-106 0.058 C-14 0.426 Ag-110m 0.004  !

Cr-51 0.043 Sn-113 0.000 Mn-54 0.088 Sb-125 0.002 l Fe-55 0.468 I-131 0.000 Co-57 0.000 Cs-13 '- 0.012 Co-58 0.134 Cs-137 0 018 Fe-59 0.000 Ba-140 0.000 Co-60 0.183 Ce-141 0.000 Ni-63 0.082 Ce-144 0.031 Sr-89 0.237 U-235 0.000 Sr-90 0.000 Pu-238 0.000 Nb-95 0.037 Pu-239 0.000 )

Zr-95 0.029 Pu-241 0.044 Ru-103 0.014 Cm-242 0.000  !

l Total 3.212

  • N/A = Not Applicable i

A-18 I

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B. OFFSITE RADIATION DOSES Offsite radiation doses from gaseous and.11guld effluents for the first and second quarters of 1989 are presented in this section. Included.are quarterly doses to individuals at locations of maximum actual exposure asd quarterly doses to the 50-mile population. Doses are presented sapdrately for batch and continuous releases and for noble gas, gaseous

^

iodine, and particulate and liquid effluents.

Exposure locations are based on the land-use survey presented in the Final Safety Analysis Report and the 1988 annual s...:vey of agricultural production.

Models.and assumptions used in performing the dose analyses for 1989 are

< presented in Sections 11.2, " Liquid Waste Management Systems",.and 11.3,

" Gaseous Waste Management Systems", of the Trojan Final Safety Analysis Report.

5500k I

B-1

L 2

Sheet 1 of 2 TABLE B-1 PARAMETERS USED IN CALCULATING DOSES FROM CASEOUS EFFLUENTS (First Half 1989)

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 Hun.an 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 3/yr)

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 Growing Season (days)

Leafy vegetables 60.0 Pasture vegetation 30.0 Produce 60.0 Residential Structure Shielding Factor 0.7 Fraction of Particulate Initially Deposited on Leafy Vegetation 0.2 Fraction of Particulate Initially Deposited on Produce 0.2 Fraction of Iodine Deposited on Leafy Vegetation 1.0 Fraction of Iodine Deposited on Produce 1.0 Surface Density of Soil for Root Zone (kg/m 2 ) 240.0 i

Field Decay Half Life (days) 14.0 B-2

+

TABLE B-1 Sheet 2 of 2 l

Parameter Value Agricultural Productivity (kg/m 2)

Leafy vegetables 2.0 Pasture grass 0.7 Produce 2.0 Period of Long-Term Buildup for Activity in Soil (days) 7,300.0

.. Fraction of Leafy Vegetables Grown in Garden of Interest 1.0 Fraction of Produce Grown in Garden of Interest 0.76 Fraction of Year Animal Grazes on Pasture 0.5 Fraction of Daily Feed that is Pasture Grass when Animal Grazes 1.0 E-3

p 4 4

TABLE B Sheet 1 of.2' PARAMETERS USED IN CALCULATING DOSES FROM LIQUID EFFLUENTS' Value Parameter 1st Otr. 1989 2nd Otr. 1989 Plant Dilution Flow Rate (gpm) 31,800, 27,800.

Columbia River Flow Rate (cfs) 130,997. 370,900.

- Dilution Factors Drinking water 1,848. 6,111.

Swimming water 406. 1,344.

Aquatic biota 406. 1,344.

Shoreline sediment 406. 1,344.

Irrigation water.. 1,848. 6,111.

Milk and meat animal water 1,848. 6,111.

Decay Times (days)

' Discharge to drinking water 0.76 0.59 Discharge to swimming water 0.0 0.0

-Discharge to aquhtic biota-consumption 1.0 .1.0 Discharge to deposition on shoreline sediment 0.0 0.0 Discharge to irrigation water withdrawal. 0.76 0.59 Discharge to milk and umat animal water 0.76 0.59 withdrawal

.. Leafy vegetable harvest to consumption by man 1.

Produce harveut 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.

E Irrigated produce 456.

Cow's milk from irrigated pastureland 310.

Goat's milk from irrigated pastureland 310.

Heat from irrigated pastureland 110.

B-4 i

I ? ,. . ;

..(

TABLE B-2 Sheet 2 of 2.

t-Value Parameter 1st Otr. 1989 2nd Otr. 1989 Annual Exposure Times (fir /yr)

Swimming and boating 12.

Shoreline activities' 12.

Irrigated pasture 2,190.

Infant Consumption Rates (kg/yr)

Drinking water- 330.

Cow's milk from irrigated pastureland 330.

Fraction of Year Animals Graze on Pasture 0.5 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 Leafy Vegetables Grown in Garden of 1.

Interest Fraction of Produce Grown in Garden of Interest 0.76 Irrigated Soil Self-Shielding Factor 2.5 Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Leafy Vegetables Fraction of Isotope in Irrigation Water That is 0.25 Initially Retained by Produce Pasture Grass Yield (kg/m2) 0.7 Vegetable Yield (kg/m2) 2.

Surface Density of Soil (kg/m2) 240.

Animal Consumption Rates (kg/ day)

Water by milk cow 60.

Water by milk goat 8.

Water by beef 50.

Pasture vegetation by milk cow 50.

Pasture vegetation by milk goat 6.

Pasture vegetation by beef 50.

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TABLE B-5 FIRST QUARTER 1989 BATCH RELEASES DOSES FROM NOBLE' GASES AT' SITE BOUNDARY AND RESIDENCE OF

, HIGHEST CONCENTRATION-u Site Boundaryla] Residencelb]

lJ l

Beta Air Dase (mrad) 2.3E-2 1.3E-2 Gamma Air Dose (mrad)- 7.8E-3 3.1E-3 Beta + Gamma. Skin Dose (mrem) -- 7.BE-3 Gamma Total Body Dose (mrem) 2.6E-3 t

la] NNW sector at 674. meters.

'lb] NNW sector at 1000 meters.

l-l l

1 B-8

TABLE B-6 FIRST QUARTER 1989 CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 5.3E-2 3.0E-2 Gamma Air Dose (mrad) 2.1E-2 8.2E-3 Beta + Gamma Skin Dose (mrem) -

1.9E-2 Gamma Total Body Dose (mrem) -

7.1E-3

[a] NNW sector at 674 meters.

(b) NNW sector at 1000 meters.

5500k B-9

A 1

TABLE B-7 FIRST QUARTER 1989 BATCH + CONTINUOUS RELEASES DOSES FROM NOBLE GASES AT SITE BOUNDARY AND RESIDENCE OF

, HIGHEST CONCENTRATION

\

Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) .7.6E-2 4.2E-2 l

Camma Air ?>ose (mrad) 2.9E-2 1.1E-2 Beta + Camma Skin Dose (mrom) -

2.7E-2 Gamma Total Body Dose (mrem) -

9.7E-3

[a] Maximum site boundary location.

[b] Maximum residence location.

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TABLE B-14 SECOND QUARTER.1989 3- BATCH RELEASES DOSES FROM NOBLE GASES AT'

, e-SITE BOUNDARE AND RESIDENCE OF HIGHEST CONCENTRATION.

Site Boundary [a] Residence [b]

Beta Air. Dose (mrad) 4.9E-2 1.9E-2 Gamma Air Dose (mrad) 1.6E 2 4.2E-3 Beta + Gamma Skin' Dose (mrem) -

1.1E-2 Gamma Total,. Body Dose (mrem)- -

3.5E-3 3 -r-la) East sector at 677 meters.

Ib] North sector at 1000 meters.

l I

B-17

. c.

e

- i i

a l

-TABLE B-15 SECOND QUARTER 1989 CONTINUOUS RELEASES DOSES FROM NOBLE CASES AT SITE BOUNDARY AND RESIDENCE OF HIGHEST CONCENTRATION Site Boundary [a] ResidenceIDI Beta Air Dose (mrad) 2.6E-2 1.1E-2 Gamma Air Dose (mrad) 8.9E-3 2.7E-3 Beta + Gamma Skin Dose (mrem) -

6.4E-3 Gamma Total Body Dose (mrem) -

2.3E-3 a

[a] East sector at 677 meters.

[b] North sector at 1000 meters.

B-18

h.

_\ ;'

.hi p

l .: TABIJ B-10 f' SE00ND QUARTER 1789 BATCH + CONTINUOUS RELEASES DOSES FROM WOBLE JASES AT SITE BOUNCARY AND RESIDENCE OF HIGHEST CONCENTRATION l

Site boimdaryla] Risi6cnceID3 Beta Air Dose (mrad) 7 . 5 E--2 3.0E-2 Ge:;rn Air Doro (mr ed) 2.5E-2 6. f)E- 3 Deta + Games Skin Doce (mrem) -

3.7E-2 GaSmna Total Body Dor.E (mresu) -

.5.tE-3

[a] Morimur. site boundary location.

Ib) Maximum residence location.

B-19

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e C. METEOROLOGICAL DATA Meteorological _ data for 1989 are available for review in the PGE Corporate Office.as per Technical Specification 6.9.1.5.4, " Semiannual Radioactive

-Effluent' Release Report". Meteorological models and assumptions ured in performing the analyses are presented in PGE-1021 "Offsite Dose Calcula-tion Manual".

C-1

6 ,.

1:

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D. CHANCES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)

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 1 Licensee' initiated changes:

"1. Shall be submitted to the Commission by inclusion in the Semiannual Effluent Release Report for the period in which the change (s) was made and shall contain:

"a. sufficiently detailed information to totally.-

3 support the rationale for the change without'

. benefit of additional or supplemental informa-tien. Information submitted should consist of a package of those pages.'of the ODCM 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; and "c. documentation of the fact that the change has-been reviewed and found acceptable by the PRB."

Report No amendments to the ODCM were made during the first'six months of 1989.

y I

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E. REACTOR COOLANT SYSTEM (RCS) SPECIFIC ACTIVITY Requirement K Trojan Facility Operating License NpF-1, Appendix A, Technical Specification 6.9.1.5.d, " Annual Reports",' states:

Reports required on an annual basis shall include:

L J "The results of specific activity analysis in which,the primarr coolant:exeseded.the;1imits of Specification 3.4.8. The following information shal1~be included: (1) Reactor power ~

. history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 radiciodine activity.was reduced to'less than ILmit.

Each result should include date and time of sampling and the radioiodine concentrations; .(3)-Clean-up system flow history, starting 48' hours prior to the first sample in Which the limit was' exceeded; (4) Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of.the specific. activity above the steady-state level;- and (5) The time duration when

.the specific activity of the primary coolant exceeded the radioiodine limit."

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 to:

"a. s 1.0 pCi/ gram DOSE EQUIVALENT I-131, and "b. 1 100/E pC1/ gram."

Report During the first six months of 1989, the Reactor Coolant System specific activity did not exceed the limits of Specification 3.4.8.

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