ST-HL-AE-3552, Semiannual Radioactive Effluent Release Rept for First Half 1990

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Semiannual Radioactive Effluent Release Rept for First Half 1990
ML20059D329
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 06/30/1990
From: Mcburnett M
HOUSTON LIGHTING & POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-3552, NUDOCS 9009070002
Download: ML20059D329 (54)
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{{#Wiki_filter:. The Light c o mp a ny South Teman Project I lectric Generating Station P. O. Bos 289 Wadsworth. Tesas ??483 Houston Light.ing & Power __ August 29, 1990 ST-HL-AE-3552 File No.: G02 10CFR50.36a U. S. Nuclear Regulatory Commission Attentions Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unita 1 & 2 Docket Nos. STN 50-498, STN 50-499 Semlannual Radioactive Effluent Release Report for the First Half of 1990 Pursuant to the South Texas Project Electric Generating Station (STPEGS) Technical Specification 6.9.1.4 and 10CFR50.36a, attached is the Semiannual Radioactive Effluent Release Report for the first half of 1990. The report covers the period f rom January 1,1990 to June 30, 1990. If you should ha/e any questions on this matter, please contact Mr. C.A. Ayala at (512) 972-8628. <C NfS ~ M. A. McBurnett

Manager, Nuclear Licensing RAD /sgs

Attachment:

Semiannual Radioactive Effluent Release Report for the First Half of 1990. 4 O ( p,9 voc "' 'o o" o2 ss - e,a,- u _ niee _ m,_, _ o q

I ST.HL. AE.3552 Houston Lighting & Power Company File No.: G02 South Texas Project Electric Generating Station Page 2 cc:

  • Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 Houston, TX 77208
  • Ceorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 circle 75 Parkway
  • J. I. Tapia Atlanta, GA 30339 3064 Senior Resident inspector c/o U._S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Be11 port Lane P. O. Box 910 Be11 port, NY 11713 Bay City, TX 77414 D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.O.

Texas Department of Health 1615 L Street. N.W, 1100 West 49th Street Washington, DC 20036 Austin, TX 78704 D. E. Ward /R. P. Verret Central Power & Light company P. O. Box 2121 Corpus Christi, TX 78403 J. C. Lanier Director of Generation City of Austin Electric Utility 721 Bartot.1prings Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 7C296 I Note: The above copice distributed without the attachment, except as note:d by asterisk (*) l 1 - i Revised 12/15/89 L4/NRC/

l ~ l i a L i SOUTH ). E12CTRIC GENERATING l STATION SEMIANNUAL 1 l RADIOACTIVE l i EFFLUENT RELEASE REPORT 4 FOR FIRST HALF,1990 EM: ~ su w ou.

{ 1 O l v I HOUSTON LIGHTING AND POWER COMPANY SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT ONE LICENSE NO. NPF-76 AND SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT TWO LICENSE NO. NPF-80 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l JANUARY 1 THROUGH JUNE 30, 1990 Prepared by: Asif J Chemic Operat[ongandAnalysisManager Dafe $ 2 N' $Q Reviewed by: - ~- schnic Sa'rvi es Mana er Dite [')S9 90 Reviewed by: ,w_ _ m Plant Manage \\ Dat6 l l I

TABLE OF CONTENTS SUBJECT PAGE 1.0 Introduction 4 2.0 Supplemental Information for Effluent and Waste Disposal 4 2.1 Regulatory Limits 5 2.2 Maximum Permissible Concentrations 6 2.3 Average Energy (HeV/ Disintegration) 6 2.4 Hessurements and Approximations of Total Activity 6 2.5 Batch Releases 9' 2.6 Abnormal Releases 11 ~ 2.7 Estimate of Total Error 11 2.8 Solid Waste Shipments 12 2.9 Radiological Impact on Man 12 2.10 Meteorological Data 12 j 2.11 Lower Limit of Detection (LLD) 13 2.12 Dose to MEMBERS OF THE PUBLIC on Site 13 3.0 Technical Specification Reporting Requirements 13 3.1 Radioactive Waste Treatment System Design 13 Modifications Description 3.2 Inoperable Effluent Monitoring Instrumentation 13 Explanation i 3.3 Gas Storage Tank Curie Limit Violation Description 14 3.4 Unprotected Outdoor Tank Curie Limit Violation 1 Description 14 3.5 Abnormal Release Description 14 3.6 Radioactive Wes+.a Process Control Program Changes 14 i l 3.7 Offsite Dose Calculation Manual (ODCH) Changes 14 3 3.8 New Land Use Census Location (s) Identification 14 4.0 Revisions to Previoas Reports 14 k 4.1 Quarterly Composite Update 14 j l t

> _... ~ ~. _, _ _ _. l' 1 1 !'I i f l =- LIST OF-TABLES 1 PAGE Gaseous Effluents for 1990 15 let and.2nd. Quarters- [ i 1 Liquid Effluents for 1990 l 1st and 2nd Quarters 24- '{ Solid Waste and Irradiated Fuel. Shipments- .l 1st and 2nd Quarters, 1990 39 .i F L I. l-h ii 'i O )i l ,y i ? i l-i ? h h e i O! ? -; { i -2. - -,,.....-_-..-,....,._..__..._.. _,..-_. ~._ __. -_ _ _ /

... _ _ _ ~,.. _. _..... _.. l' j 1 l 4 1 6 i-i LIST OF APPENDICES l i i PAGE r I 1 i j Appendix A - Liquid Radioactive Waste Treatment System [ l l' Design Modification Description 42 c. ,~ Appendix B - Revised Liquid Effluent and Dose Accumulation-Sunnary for 1989, 3rd'and 4th Quarter' 47-i 1 t 1 i ? k ( h i r e 1 l t ? 5 t I e I L I v h ( f e h 3'-

\\_/ 1.0 Introduction This Semiannual Radioactive Ef fluent Release Report for the period January 1, 1990, through June 30, 1990, is submitted in accordance with Appendix A of License NPF-76 and NPF-80, Technical Specifications. A single submittal is made for both units which combines those sections that are common. Reparate tables of releases and release totals are included where separate processing systems exist. In accordance with Technical Specifications 6.9.1.4 the hourly meteorological data and assessment of radiation doses due to radioactive effluents shall be included in the Semiannual Radioactive Effluent Release Report submitted within 60 days af ter January 1 of each year, and therefore is not included in this report. Liquid quarterly composites for Strontium-89, Strontium-90 and Iron-55 for the 2nd quarter, 1990, will be updated in the next Semiannual Radioactive Effluent Release Report if appropriate. All assessments of radiation doses are performed in accordance with the STPEGS Offsite Dose Calculation Manual (ODCM). ( 2.0 Supplemental Information for Effluent and Waste Disposal Unit Number i Type PWR Houston Lighting & Pcwer Co. Docket No. 50-498 Power (MWT)- 3800 Cooling Water Source Initial Criticaltcy-(March 8, lo88) Main Cooling Reservoir Unit Number 2 Type: PWR Houston Lighting & Power Co. l Docket No. 50-499 Power (MWT)- 3000 Cooling Water Source: Initial Criticality-(March 12, 1989) Main Cooling Reservoir l I v l :

1 I j u 2.1 Regulatory Limits ] 2.1.1 Fissio, and activation gases The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the Site Boun3ary shall be limited to the following: a. During any calendar quarter Less than or equal to 5 1 mrads for gamma radiation and less than or equal to 10 1 mrada for beta radiation, and j l b. During any calendar years Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 3 mrads for beta radiation. 2.1.2 Iodines and Particulates, half-lives > 8 days i The dose to a Member of the Public from Iodine-131, Iodine-133, tritium, and all radionuclides in partic.ulate form with half-lives greater than 8 days in gaseous effluents ) released, from each unit, to areas at and beyond the Site Boundary shall be limited to the following: a. During any calendar-quarter: Less than or squal to 7.5 mrems to any organ and, b. During any calendar years Less than or equal to 15 mrems to any organ. 2.1.3 Liquid Effluents The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released, from each unit, to Unrestricted Areas shall be limited to During any calendar quarter to less than or equal to 1.5 a. mrems to the whole body and to less than or equal to 5 mrems to any organ, and b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ. OV o _3_ t j

V} l 2.2 Haximum Permissible Concentrations 2.2.1 Gaseous Effluents The dose rate due to radioactive materiale released in gaseous effluents from the site to areas at and beyond the Site Boundary shall be limited to the followirgs a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin and b. For lodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days Less than or equal to 1500 mrems/yr to any organ. j 2.2.2 Liquid Effluents The concentration of radioactive material released in 11guld effluents to Unrestricted Areas shall be limited to the concentrations specified in 10CFR Part 20, Appendix B, Table O. II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration shall be limited to 2.0E-04 micro curie /ml total activity. 2.3 Average Energy (HeV/ Disintegration) The Average Energy (or E-bar) shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coulant at the time of sampling) of the sum of the average beta and gamma energies per disintegration for the isotopes other than Iodines, with half-lives greater than 15 minutes, making up at least 95% of the total non-lodine activity in the coolant. E-bar (MeV/ Disintegration) 0.833 Unit 1 0.729 Unit 2 2.4 Measurement anc Approximations of Total Activity The followinF discussions detail the methods used to measure and approximate total activity for the followings a.. Fission and Activation Gases b. Iodines c. Particulates } d. Liquid Effluents l O Tables A3-1 and A4-1 of the STPEGS Offsite Dose Calculation Manual (ODCM) give sampling frequencies and minimum detectable concentration requirements for the analysis of liquid and gaseous effluent streams. 2.4.1 Gaseous Effluents 2.4.1.1 Fission and Activation Gases The following noble gases are considered in evaluating gaseous airborne discharges: Ar-41 Xe-131m Kr-83m Xe-133m Kr-85m Xe-133 Kr 85 Xe-135m Kr-87 Xe-135 Kr-88 Xe-137 Kr-89 Xe-138 Kr-90 2.4.1.2 Iodines and Particulates ) The radiclodines and radioactive materials in particulate forms to be considered are: Cr-51 Sb-124 H-3 Mn-54 1-131 Mo-99 Fe-59 I-133 Co-58 Cs-134 Co-60 Cs-136 Zn-65 Cs-137 Sr-89 ba-140 Sr-90 Ce-141 Zr-95 Ce-144 Other nuclides with half-lives greater than 8 days 2.4.1.3 Analytic Methods a. Batch Gaseous Releases Pre-release grab samples from the plant containment atmosphere, prior to issuance of weekly permits, and pre-release grab samples from the RCS Vacuum Degassing System are analyzed on a Gamma Spectroscopy System utilizing high purity germanium detectors (HPGe) for noble gas, iodine and particulate activity. O The radionuclide values obtaine6 are used in conjunction with the gross nob 10 gas release rate monitoring data collected by the radiation monitoring system to estimate the release rate of each radionuclide in the af fluent streams, b. Continuous Gaseous Releases Psriodic noble gas and tritium grab samples are taken from the continuous release points (i.e. the Unit Vent and the condenser vacuum pump exhaust). Continuous sampling for particulates and iodine is also performed on the affluent streams. They are analyzed for gross alpha and gamma radionuclides, as described above for batch releases. Strontium-89 and Strontium-90 analysis is performed by an offsite laboratory. 2.4.2 Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents: () H3 Y-90 1-133 Na-24 Y-91m I-134 Cr-51 Y-91 1-135 Mn-54 Y-93 Cs-134 Mn-56 Zr-95 Cs-136 Fe-55 Zr-97 Cs-137 Fa-59 Nb-95 Cs-138 Co-58 Mo-99 Ba-139 Co-60 Tc-99m Ba-140 Ni-65 Tc-101 Ba-141 Cu-64 Ru-105 Ba-142 Zn-65 Ru-106 La-140 Zn-69 Ag-110m La-142 Br-83 Te-125m Ce-141 Br-84 Te-127m Co-143 Br-85 Te-127 Co-144 Rb-86 Te-129m Pr-143 Rb-88 Te-129 Pr-144 Rb-89 Te-131m Nd-147 Sr-89 Te-131 V-187 Sr-90 Te-337. Fp-239 St-91 I-130 . LIQ

  • Sr-92 1-131

. ALPHA (Grces Alpha) i 1-132 .Xa~133 .Xe-135 O

  • includes other gamma peaks that are identified

! I ,f li

l l ~ s 2.4.2.1 Analytic Methods a. Batch Liquid Releases All liquid effluents are released as batches. Representative pre-release grab samples are taken and analyzed in accordance with Table A3-1 of the ODCM. Radionuclide analyses are performed using the Gamma Spectroscopy System. Aliquota of each pre-release sample are composited in accordance with the requirements l in Table A3-1 of the ODCM. Gross alpha determinations are made using the Gas-Flow Proportional Counting System. Tritium concentrations are determined using Liquid Scintillation Counting techniques. Dissolved and entrained gas concentrations are determined by counting grab samples on the Gamma Spectroscopy System. Strontium 89 and 90 and l Iron-55 determinations are performed by'an offsite laboratory. C r The radionuclide concentrations obtained are t used with the flow total for each batch release. The error associated with the flow total.is small in relation to the counting uncertainty of the radionuclide concentration analysis. The average uncertainty associated with counting measurements is 5% or less at the 95% confidence level. 2.5 Batch Releases 2.5.1 Liquid (Unit 1) Quarter 1 Quarter 2 Num'er of releases: 50 102 a. o b. Total time period for releases (min): 2693 6964 c.. Maximum time period for a release (min): 66 656 d. Average time period for a release (min): 54 68 ) e. Minimum time period 3 for a release (min): 51 2 ) I -9

i l jhGl 2.5.2 Gaseous (Unit 1) Quarter 1 Quarter 2 a. Number of releases: 69 55 b. Total time period for releases (min): 901 64179 c. Maximum time period for a release (min): 59 3896 d. Average time period for a release (min): 13 1167 i e. Minimum time period for 4, release (min)t. 3 3 2.5.3 Liquid (Unit 2) a. Number of releases: 69 94 b. Total time period for releases (min): _3666 5573 c. Maximum time period for a release (min): 62 177 d. Average time period for a release (min): 53 59 e. Minimum time period for a release (min): 22 4 2.5.4 Gaseous (Unit 2) a. Number of releases: 80 82 b. Total time period for releases (min): 3022 4701 c. Maximum time period for a release (min): 808 763 d. Average time period for a release (min): 38 57 e. Minimum time period for a release (min): 1 3 Ag.. _.

o l 1 ( 2.6 Abnormal (Unplanned) Releases 2.6.1 Liquid (Unit 1) Quarter 1 Quarter 2 a. Number of releases: 0 0 b. Total activity released (curies): 0.000E+00 0.000E+0 2.6.2 Gaseous (Unit 1) a. Number of releases: 0 0 b. Total activity relearad (curies): 0.000E+00 0.000E+00 2.6.3 Liquid (Unit 2) a. Number of releases: 0 0 b. Total activity released (curies): 0.000E+00 0.000E+0 gx \\s,) 2.6.4 Gaseous (Unit 2) a. Number of releases: 0 0 b. Total activity released (curies): 0.000E+00 0.000E+00 2.7 Estimate of Total Error 2.7.1 Liquid a. The maximum error associated with volume and flow measurements, based upon plant ca? ' nation practice is estimated to be +/- 0.08%. b. The average uncertainty associated with counting measurements is 5% or.less at the 95% confidence level. c. The error associated with dilution volume is estimated to be +/- 10%. A N g/ m 1 I 2.7.2 Gaseous a. The maximum error associated with monitor resJings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedures are collectively estimated to be Fission and Activation Gases 125% Iodines +25% Particulates 125% Tritium 125% b. The average uncertainty associated with counting measurements is 5% or less at the 95% confidence level for fission and activation gases, iedines, particulates and tritium. 2.7.3 Solid Radioactive Waste ) The error associated in determining the contents and volume of solid radwaste shipments is estimated to be +/- 5% significance levels and 1 1%, respectively. 2.8 Solid Waste Shipments A total of seven radioactive shipments of dry active waste and resin were made during the reporting period. A summary of the data is provided in the Solid Waste and Irradiated Fuel Shipments. Table. 2.9 Radiological Impact on Han (ref. Technical Specifications 6.9.1.4). This data shall be included in the Semiannual' Radioactive Effluent Release Report to be submitted within 60 days af ter January 1 of each year. 2.10 Meteorological Data This data shall be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days af ter January 1 of each year. OV. -

i (/) 2.11 Lower Limit of Detection (LLD) The LLD (an a praori limit) is defined as the smallest concentration of radioactive material in a sample that will yield a not count, above system background, that will be detected with 95% probability, and only a 51 probability of falsely concluding that a blank observation represents a "real" signal, 2.12 Dose to HEM 3ERS OF THE PUBLIC On Site In accordance with Technical Specifications.6.9.1.4, this data shall be submitted within 60 days af ter January 1 of each year. 3.0 Technical Specifications Reporting Requirements 3.1 Radioactive Waste Treatment System Design Hodification Description (ref. Technical Specifications 6.15) A Unit 2 liquid radioactive waste treatment system design modification was completed during this reporting period (Appendix A). No changes were made to Unit 1 solid, liquid, or gaseous radit.ative waste treatment systems or to Unit 2 solid or gaseous radioactive waste treatment systems. 3.2 Inoperable Effluent Monitoring Instrumentation Explanation (ref. Technical Specifications 6.9.1.4) Condenser Vacuum Pump Wide Range Gas Monitors N1RA-RT-8027 and N2RA-RT-8027 were removed from service on November 1, 1988 at 0100. Since the problems with the monitors were not repaired within 30 days, the following is provided as an explanation. The Condenser Vacuum Pump Wide Range Gas Monitors N1RA-RT-8027 and N2RA-RT-8027 have similar problems with the process fluid stream. In both cases, the actual process flowrate is less than the designed process flowrate and the fluid is humid air instead of a mixture of steam and air as expected. Plant Hodifications were written to redesign the output of the condenser to flow to the Unit Vent. This solution is expected to relieve N1RA-RT-8027 and N2RA-RT-8027 of the burden of being isokinetically sampled monitors and will elimf.nate the need for measurement of wet process and wet sample flows. Unit 1 Plant Hodification (89-066) installation has been scheduled ) for the end of September, 1990. The Unit 2 Plant Hodification i (89-067) is expected to be completed the middle of October, 1990. Operation is contingent upon implementation of the change to Technical Specification 3.3.3.11.

Y 3.3 Gas Storage Tank Curie Limit Violation Description (ref. Technical Specifications 6.9.1.4) The RCS Vacuum Degassing System was not used during this reporting period. 3.4 Unprotected Outdoor Tank Curie Limit Violation Description (ref.- Technical Specifications 6.9.1.4) There are no Unprotected Outdoor Tanks at STPEGS. 3.5 Abnormal (Unplanned) Release Description (ref. Technical Specifications 6.9.1.4) No abnormal releases of liquid waste from STPEGS Unit 1 or Unit 2 to UNRESTRICTED AREAS occurred during this reporting period. 3.6 Radioactive Waste Process Control Program Changes (ref. Technical Specifications 6.13.2) There were no changes to the Radioactive Waste Process Control Program (PCP) during this reporting period. O l (,/ 3.7 Offsite Dose Calculation Manual Change (ref. Technical Specifications 6.14.2.a) No changes were made to the Offsite Dose Calculation Manual (ODCM) during this reporting period, i 3.8 New Land Use Census Location (s) Identification (ref. Technical Specifications 3.12.2.a) l The Land Use Census was not conducted during the report period. 4.0 Revisions to Previous Reports 4.1 Quarterly Composite Updater 4 The Unit i fourth quarter 1989 quarterly composite analysis for Iron-55 added 1.19 E-3 mrem to the total body and 2.72 E-3 mrem to the applicable organ of the highest receptor. Applicable dose limits were not exceeded by this addition. (Appendix B)

a i a l l l GASEOUS EFFLUENT P FOR 1990 let and 2nd Quarter I 1 l l O !

SITE: South Texas Pr' lect Electric Generating Ctation UNIT: 1 YEAR: 1990 (3 \\-- EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS -- SUMMATION OF ALL RELEASES

UNITS :

QUARTER : QUARTER :EST. TOTAL: 1 2

ERROR, %:

A. FISSION AND ACTIVATION GASES $$$kbkkLRkLhkhk $ Ch $b$4hhEbh b$kh$kbh$bhhbhbh$

2. AVERAGE RELEASE
UCI/SEC: 0.588E+01 : 0.536E+01 :

RATE FOR PERIOD

3. PERCENT OF TECP.NICAL:
0.218E.02 : 0.198E-02 :

SPECIFICATION LIMIT : $'i$'ibiklibbiNE5bi' $"bi"'$'b95bk$b4$b$25hEb5'$'b$b5bE+bb'$

2. AVERAGE RELEASE
UCI/SEC: 0.122E-04 : 0.275E-04 :

g-- RATE FOR PERIOD

3. PERCENT OF TECHNICAL:
0.134E.04 : 0.303E-04 :

SPECIFICATION LIMIT : C. PARTICULATES

1. PARTICULATES WITH
CI
0.410E 05 : 0.393E-03 : 0.250E+02 :

HALF-LIVES > 8 DAYS :

2. AVERAGE RELEASE
UCI/SEC: 0.527E 06 : 0.500E-04 :

RATE FOR PERIOD $'3$~P[RbkhT bF T[bbNibALI'"k"'I'b$5ihk'b6 I'b$549k b4 I SPECIFICATION LIMIT :

4. GROSS ALPHA
Cl
0.113E-05 : 0.000E+00 :

RADI0 ACTIVITY D. TRITIUM

1. TOTAL RELEASE CI
0.108E+01 : 0.506E+01 : 0.250E+02 :
2. AVERAGE RELEASE
UCl/SEC: 0.139E+00 : 0.643E+00 :

RATE FOR PERIOD \\

3. PERCENT OF TECHNICAL:
0.771E-04 : 0.357E 03 :

SPECIFICATION LIMIT : l j

SITE: South Texas Project Elcctric Gen: rating Station UNIT: 1 YEAR: 1990 /'~ PAGE 1 0F 3 k EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 1 (UNIT VENT) CONTINV0VS MODE BATCH MODE NUCLIDES

UNITS :

QUARTER : QUARTER : QUARTER : QUARTER : RELEASED : 1 2 1 2

1. FISSION GASES AR41 CI
0.184E+01 : 0.000E400 : 0.316E+00 : 0.233E+00 :

KR83M CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

KR85M CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

KR85 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E400 :

KR87 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i KR88 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

KR89 CI

0.000E+00 : 0.000E+00 : 0.000E+0U : 0.000E+00 :

i KR90 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

XE131M CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i ) XE133M CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ ~ ~ XE 555""' 5 bi'" $ 'b$ 5h5 kIbi' $ 'b$ ih9kIbb' $ 'h$ hb 5kIbi'$ 'b$ hkbkIbb' $ XEi35M $ b5 $ bIbbbk bb b[bbbh bb $~b[bbbE bb b$bbbE bb l j XE135 CI

0.387E+01 : 0.000E+00 : 0.507E

......................................................-01 : 0.000E+00 : XE137 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i i XE138 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

j 1 UNIDENT. CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.283E-05 :

l PERIOD CI

0.430E+02 : 0.179E+02 : 0.271E+01 : 0.242E+02 :

(AB0VE) l i t i

~ SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR: 1990 s i r PAGE 2 0F 3 4 \\ EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS FOR RELEASE POINT: 1 (UNIT VENT) I I CONTINV0VS MODE BATCH MODE

NUCLIDES : UNITS : QUARTER : QUARTER :

QUARTER : QUARTER : i RELEASED : 1 2 1 2

2. 10 DINES 1131 CI
0.850E-04 : 0.762E-05 : 0.100E.04 : 0.209E-03 :

1133 CI

0.870E.04 : 0.283E-06 : 0.848E-05 : 0.947E-05 :
TOTAL."0R :

PERIOD CI

0.172E-03 : 0.791E-05 : 0.185E-04 : 0.218E-03 :

(AB0VE)

3. PARTICULATES

(-~ (

Cl4 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CR51 CI
0.000E+00 : 0.126E-04 : 0.000E+00 : 0.989E-04 :
MN54 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.119E-05 :

FE59 CI

0.000E+00 : 0.688E-06 : 0.000E+00 : 0.273E-05 ::
C058 CI
0.327E-05 : 0.203E-04 : 0.640E 07 : 0.230E-03 :

C060 CI

0.765E.06 : 0.184E-05 : 0.000E+00 : 0.159E-04 :

ZN65 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

SR89

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

SR90 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

ZR95 CI

0.000E+00 : 0.413E-06 : 0.000E+00 : 0.357E-05 :

SB124 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

CS134 CI

0.000E+00 : 0.000E+00 : 0.387E-08 : 0.000E+00 :

CS136 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ bSk37 $ bk $b$bbbEbb$b$bbbEbb$b$bbbEbb$b$bbbEbb$ s ................................f.......................................

SITE: South Texas Project Electric G:nerating Station UNIT: 1 YEAR: 1990 -/) PAGE 3 0F 3 \\/ EFFLUENT AND WASTE DISPOSAL REPORT GASE0US EFFLUENTS FOR RELEASE POINT: 1 (UNIT VENT) CONTINUOUS MODE BATCH MODE

NUCLIDES
UNITS :

QUARTER : QUARTER : QUARTER QUARTER RELEASED : 1 2 1 2

3. PARTICULATES (CONTD)

) BA140 Cl

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ bkkki $ bh $ b$bbbE bb $ b$bkbb bb $ b$bbbb bb $ b$bbbb bb $ bhikk $ bi $ b$bbbE bb $ b$bbbk bb b$bbbk bb $ b$bbbk bb $ \\ UNIDENT. Cl

0.000E+00 : 0.842E.06 : 0.000E+00 : 0.392E.05 :

) TOTAL FOR : PERIOD CI

0.403E-05 : 0.367E.04 : 0.679E-07 : 0.356E.03 :

f-~) (AB0VE) ( j l \\ t I

SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 EFFLUENT AND WASTE DISPOSAL REPORT bkhEbbh khh[bEkkh $ bbkkkkibk bF ALL RELEASES $ bhikh $ hbkkhER $hbkkkER $Ehk$ kbkkl$ 1 2

ERROR, %:

A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CI
0.530E+01 : 0.231E+02 : 0.250E+02 :

l

2. AVERAGE RELEASE
UCl/SEC: 0.681E+00 : 0.293E+01 :

RATE FOR PERIOD

3. PERCENT OF TECHNICAL:
0.252E-03 : 0.109E-02 :

SPECIFICATION LIMIT : $k$kbkk[kbbiNEkhi $ bi $ b$bbbE bb $ b$46hh$bh $ b$hhbE bh $

2. AVERAGE RELEASE
UCl/SEC: 0.000E+00 : 0.593E-06 :

RATE FOR PERIOD $ h$ PERbEhi bF kkbHhibkl$k $ b$bbbE bb $ b$6hhE b6 $ SPECIFICATION LIMIT : C. PARTICULATES

1. PARTICULATES WITH
Cl
0.212E-04 : 0.191E-04 : 0.250E+02 :

HALF-LIVES > 8 DAYS :

2. AVERAGE RELEASE
UCI/SEC: 0.272E-05 : 0.243E-05 :

RATE FOR PERIOD

3. PERCENT OF TECHNICAL:
0.299E-05 : 0.266E-05 :

SPECIFICATION LIMIT :

4. GROSS ALPHA CI
0.261E-05 : 0.000E+00 :

RADI0 ACTIVITY D. TRITIUM $~i$~ibikLRbLkSE"'$~~bi"'$'b$49hk+b5'$'b$hi6E+bi'$'b$i5bh+bi'I

2. AVERAGE RELEASE
UCI/SEC: 0.639E+00 : 0.287E+00 :

RATE FOR PERIOD

3. PERCENT OF TECHNICAL:
0.355E-03 : 0.159E-03 :

SPECIFICATION LIMIT : i _ --

SITE: South Texas Project Electric Generating Station j UNIT: 2 YEAR: 1990 l i (T ] \\ PAGE 1 0F 3 i EFFLUENT AND WASTE DISPOSAL REPORT bkhkbbb[FhlbbkTbhbRRklEkhkPbikT: 1 (UNIT VENT) I CONTINV0VS MODE BATCH MODE

NUCLIDES : UNITS : QUARTER :

QUARTER : QUARTER : QUARTER : RE!. EASED : 1 2 1 2 .................................................................. ~..

1. FISSION GASES

$~'kkki '$ bi"'$'b$bbbE bb'$'h$bbbE bb'$~b$hhkE+bb'$~b$bb9k bb $ ) $ Kkbbk $ bk $ b$bbbk bb $ b bbbh bb $ b$bbbh bbb bbbE bb $ $ Kkbbk $ bk $ b$bbbk bb $ b$k6bk$bk $ b$bbbh bb $ b$kkhk5bh $ KR85

Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$'~KR8h~ '$~~bi '$'b$bbbEIbb'$'b$bbbk bb'I'b$bbbk bb'$'b$bbbb+bb'$ /x KR88 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

y ) v

KR89 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
KR90 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
XE131M CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
XE133M Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.161E.01 :
XE133
Cl

. s.427E+01 : 0.160E+02 : 0.721E+00 : 0.482E+01 :

XE135M Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

1 XE135 C!

0.434E 01 : 0.148E+01 : 0.746E-02 : 0.199E+00 :

IX553i i Ci '66665I66'i6!6665I66'i656665I66'I'6!6665I66'i i XE138 Cl

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

I"0Ai65AT!ICi '6!6665I66'I'6!6665I66'I'66665I66'I'6!6665I66'i i

TOTAL FOR :

PERIOD CI

0.432E+01 : 0.175E+02 : 0.983E+00 : 0.558E+01 :

(ABOVE) v i l

SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 ]' PAGE 2 0F 3 1 EFFLUENT AND WASTE DISPOSAL REPORT hkhbbbbhhh[bbhibhbRRELEkhEPbkhT:1 (UNIT VENT) CONTILJ0VS MODE BATCH MODE

NUCLIDES
UNITS :

QUARTER : QUARTER : QUARTER : QUARTER : RELEASED : 1 2 1 2 1

2. 10 DINES

$b.bbbEbb$b$b6bEbb$bbbbkbb$b$$bhk$bb'$ $ iib $ $ b$ 1133

Cl
0.000E+00 : 0.169E 0.000E+00 : 0.612E-05 :

.........................................-04

TOTAL FOR :

PERIOD

Cl
0.000E+00 : 0.205E-04 : 0.000E+00 : 0.718E 05 :

(ABOVE)

3. PARTICULATES r-'

Cl4

Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

(,) CR51

Cl
0.000E400 : 0.000E+00 : 0.000i+00 : 0.000E+00 :
HN54
Cl
0.000E+00 : 0.c00E+00 : 0.000E+00 : 0.1400-05 :

FE59

Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
C058
Cl
0.433E.06 : 0.547E.05 : 0.849E.07 : 0.348E-05 :

C060

Cl
0.000E400 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
ZN65
Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
SR89
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
SR90
Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : a.000E+00 :

l $ kR9b $ bf $ b bbbE bb $ b$bbbE bb b$bbbE bb $ b$bbbk bb $

SB124
Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CS134 Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

CS136 Cl

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

/)'

CS137 Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

l (_ - 22 l

t SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 s PAGE 30F-3 EFFLUENT AND WASTE DISPOSAL REPORT i GASE0US EFFLUENTS FOR RELEASE POINT: 1 (UNIT VENT) CONTINV0 tis MODE BATCH MODE NUCLIDES

UNITS :

QUARTER -: QUARTER : QUARTER : QUARTER RELEASED : 1 2 1 2

3. PARTICULATES (CONTD)

BA140 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

CE141

CI
0.000E+00 : 'O.000E+00 : 0.000E+00 : 0.000E+00 :

bh$kk $ b5 $ b$bbbk bb $ b$bbbEIbb $ b$bbbh bb $ b$b7ih5bb $ UNIDENT. CI

0.189E-04 : 0.000E+00 : 0.178E.05 : 0.000E+00 :

f-~3 PERIOD CI

0.193E-04 : 0.547E-05 : 0.187E.05.: 0.136E.04 :

(,,/ (AB0VE) k O I l f o LIQUID EFFLUENT FOR 1990 t ist and 2nd Quarter l l LO SITE: South Texas Project Electric Generating Statien UNIT: 1-YEAR: 1990 () EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS -- SUMMATION OF ALL RELEASES

UNITS :

QU.SRTER : QUARTER : EST. TOTAL: t -I 2

ERROR, %:

A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (EXCL.:

CI

0.758E.01 : 0.540E+01 : 0.500E+01 :

TRIT., GASES, ALPHA): 2.' AVERAGE DILUTED

UCI/ML : 0.409E-09 : 0.291E-07 :

CONC. DURING PERIOD :

3. PERCENT OF
'O.266E-02 : 0.974E-01 :

APPLICABLE LIMIT B. TRITIUM

1. TOTAL RELEASE
CI
0.630E+02 : 0.631E+02 : 0.500E+01 :
2. AVERAGE DILUTED
UCI/ML : 0.341E-06 : 0.340E-06 :

fw CONC, DURING PERIOD : (_)

3. PERCENT OF
0.362E+00 : 0.362E+00 :

APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES $k$hbkkLRhlEkhh $ bi $ b$kbbh bb $ b$53kh bb $ b$hbbh bk $

2. AVERAGE DILUTED
UCI/ML : 0.568E-09 : 0.708E-09 :

CONC. DURING PERIOD :

3. PERCENT OF
0.568E-03 : 0'708E-03 :

APPLICABLE LIMIT i b$bRbbhklPHkRkbibkbhkV}hh $k$kbhklRELkkbh $ bi $b$bbbhbb$b$bbbhbb$b$kbbkbi$ E. VOLUME WASTE RELEASED : LITERS : 0.246E+07 : 0.496E+07 : 0.800E-01 : (PRIOR TO DILUTION) F. VOLUME DILUTION WATER : LITERS : 0.185E+12 : 0.185E+12 : 0.100E+02 :

USED DURING PERIOD *

/ N,%)

  • Dilution water volumes have been adjusted to reflect the reservior volume as defined in the ODCM. Volume used-in previous reports. used a conservative volume which was controlled in the Radiation Monitoring System Computer.

m

L SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR: 1990 PAGE 10F 5 EFFLUENT AND WASTE DISPOSAL REPORT-i r i LIQUID EFFLUENTS FOR RELEASE POINT: 2 i j CONTINU0US MODE BATCH MODE-a i NUCLIDES : UNITS : QUARTER : QUARTER QUARTER :- QUARTER : I RELEASED : 1 2 1 2

~

t. H3 CI

0.000E+00 : 0.000E+00 : 0.630E+02 : 0.631E+02 :

C14

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

NA24

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

{ P32 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

CR51 CI

0.000E+00 : 0.000E+00 : 0.278E-02 : 0.889E+00 :
MN54 CI
0.000E+00 : 0.000E+00 : 0.365E-02 : 0.820E-01 :
MN56
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

FESS CI

0.000E+00 : 0.000E+00 : 0.295E-01 : 0.000E+00 :

FE59 CI

0.000E+00 : 0.000E+00 :-0.476E-03 : 0.860E-01 :

C058 CI

0.000E+00 : 0.000E+00 : 0.230E-01 : 0.388E+01 :

C060

CI
0.000E+00 : 0.000E+00 : 0.892E-02 : 0.247E+00 :

NI63

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
HI65
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

CU64 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

ZN65 CI

0.000E+00 : 0.000E+00 : 0.533E-04 : 0.318E.02 :
ZN69
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BR83 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BR84

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BR85 Cl

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

SITE: South Texas Project Electric Generating Station UNIT:.1 YEAR: 1990 PAGE 2 0F 5 EFFLUENT AND WASIE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 2 i t CONTINV0VS MODE BATCH MODE

NUCLIDES UNITS :

QUARTER : QUt ?R : QUARTER : QUARTER : RELEASED : 1 i ) 2 LIQUID EFFLUENTS (CONTD) $ Rbb6 $ bk $b$bbbkbb$b$bbbkbb$b$bbbkhbb$b$bbbkhbb$ RB88 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

RB89 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ bRb9 $ bi $b$bbbkhbb$b$bbbkhbb$b$bbbkhbb$b$bbbkhbb$ SR90

Cl
0.000E+00 : 0.000E+00 : 0.320E-04 : 0.000E+00 :

SR91

Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

SR92 Cl

0.000E+00 : 0.000E+00-: 0.000E+00-: 0.000E+00 :
Y90 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

Y91M CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
Y91
Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
Y92
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
Y93 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

ZR95 CI

0.000E+00 : 0.000E+00 : 0.899E-03 : 0.380E-01 :

$ kR9h $ b$ $ b$bbbh bb $ b bbbh bb $ b$bbbh bb $ b$kh5h5bb $

NB95 CI
0.000E+00 : 0.000E+00 : 0.176E 02 : 0.663E

.................................................................-01

M099 Cl
0.000E+00 : 0.000F+00 : 0.000E+00 : 0.198E-04 :
TC99M Cl
0.000E+00 : 0.000E+LO : 0.000E+00 : 0.201E-04 :
TC101 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

l SITE:_ South Texas Project Electric Generating Station UNIT: 1 YEAR: 1990 ( PAGE 3 0F 5 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 2 CONTICM iDDE BATCH MODE

NUCLIDES
UNITS :

QUARTER : QUARTER : QUARTER : QUARTER : RELEASED : 1 2 1 2 LIQUID EFFLUENTS (CONTD) $ Rhib3 $ bi $ b$bbbh bb $ b$bbbk bb $ b$bbbE bb $ b$bbbh bb $ RU105 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

RV106 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
AG110M CI
0.000E+00 : 0.000E+00 : 0.317E-04 : 0.124E-01 :

4

TE125M CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ TE$27M $ bh $ b$bbbh bb $ b$bbbh bb $ b$bbbh bb b$bbbk bb $ (

TE127 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE129M CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE129 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE131M CI
0.000E+00 : 0.000E+00 : 0.000E400 : 0.000E+00 :
TE131 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE132 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

1130 CI 000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 : 1131

CI
0.000E+00 : 0.000E+00 : 0.690E-04 : 0.173E-02 :

1132

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

1133 CI

0.000E+00 : 0.000E+00 : 0.919E-05 : 0.513E-04 :

l 1134

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

/~'s. 1135

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i\\_) 1 I 1 1

l SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR: 1990 O PAGE 4 0F 5 O EFFLUENT AND WASTE DISPOSAL REPORT LIQVID EFFLUENTS FOR RELEASE POINT: 2 CONTINUOUS MODE BATCH MODE

NUCLIDES : UNITS :

QUARTER : QUARTER : QUARTER QUARTER : RELEASED : 1 2 1 2 LIQUID EFFLUENTS (CONTD)

CS134
CI
0.000E+00 : 0.000E+00 : 0.345E-04 : 0.253E-03 :
CS136
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E-00 :.
CS137 CI
0.000E+00 : 0.000E+00 : 0.205E-03 : 0.334E-03 :

i

CS138 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BA139 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

( BA140

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ BAi45 '~'$~~bi $~b$bbbb+bb$'b$bbbb+bb'$'b$bbbE+bb$b$bbbk+bb'$

BA142 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

LA140 CI

0.000E+00 : 0.000E+00 : 0.247E

.....................................................-04 : 0.102E-02 : LA142

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CE141 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CE143 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CE144 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.436E-03 :

PR143 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

PR144 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

ND147 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
W187 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

f-') \\>

NP239 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

b.

\\ I SITE:- South Texas Project Electric G:nerating Station UNIT: 1 YEAR: 1990 PAGE 5 0F 5 / EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 2 CONTINU0US H0DE BATCH MODE

NUCLIDES : UNITS :

QUARTER : QUARTER : QUARTER : QUARTER :

RELEASED :

1 2 1-2 LIQUID EFFLUENTS (CONTD) . LIQ CI

0.000E+00 : 0.000E+00 : 0.433E 02 : 0.864E-01 :
TOTAL FOR :

PERIOD CI

0.000E+00 : 0.000E+00 : 0.631E+02 : 0~685E+02 :

(AB0VE)

~
XE-133 CI
0.000E+00 : 0.000E+00 : 0.102E+00 : 0.130E+00 :

g-(sg /

XE-135
Cl
0.000E+00 : 0.000E+00 : 0.298E-02 : 0.636E-03 :

n v _

SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 l ( EFFLUENT AND WASTE DISPOSAL REPORT 4 x LIQUID EFFLUENTS -- SUMMATION OF ALL-RELEASES

UNITS :

QUARTER : QUARTER :EST. TOTAL: 1 2

ERROR, 16 :

A. FISSION AND ACTIVATION PRODUCTS $ k$ hbh h Rh[hkhh (Ekbl$$ bk $ b$hhhk$bk $ b$h9kh bk $ b bbbh bk TRIT., GASES, ALPHA):

2. AVERAGE DILUTED
UCI/ML : 0.120E-09 : 0.211E-09 :

CONC. DURING PERIOD :

3. PERCENT OF
0.416E-03 : 0.124C-01 :

APPLICABLE LIMIT B. TRITIUM- $k$kbhkLRhlkkhh $ bk $ b$bhkh bh $ b$[bbh bh $ b$hbbh bk $

2. AVERAGE DILUTED
UCI/ML: 0.362E-06 : 0.102E-05 :

CONC. DURING PERIOD : I s l i

3. PERCENT OF
0.364E+00 : 0.408E+00 :

l APPLICABLE LIMIT l C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CI
0.510E

.........................................-02 : 0.150E+01 : 0 000E+01 : 7 l

2. AVERAGE DILUTED
UCI/ML : 0.276E-10 : 0.811E-08 :

CONC DURING PERIOD :

3. PERCENT OF
0.276E-04 : 0.811E-02 :

AFPLICABLE LIMIT D. GROSS ALPHA RADI0 ACTIVITY l l

1. TOTAL RELEASE CI
0.130E-04 : 0.000E+00 : 0.500E+01 :

1 E. VOLUME WASTE RELEASED : LITERS : 0.303E+07 : 0.461E+07 : 0.800E-01 : (PRIOR TO DILUTION) l F$VbLbMkbkLbhkbNWkkER$LkhERh$b$kbbhkh$b$kb5hkh$b$kbbhbh$ USED DURING PERIOD

  • t
  • Dilution water volumes have been adjusted to reflect the reservoir volume as defined in the 00CM. Volume used in previous reports. used a conservative volume which was controlled in the Radiation Monitoring System Computer..

l SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 P ij' PAGE 1 0F 7 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 1 i CONTINUOUS M0DE BATCH MODE i I 1

NUCLIDES
UNITS : QUARTER : QUARTER
QUARTER :

QUARTER i

RELEASED :

1-2 1 2-i 1

H3
CI
0.169E-01 : 0.849E-02 : 0.000E+00 : 0.000E+00 :
Cl4
CI
0.000E+00-: 0.000E+00 : 0.000E+00 : 0.000E+00 :

i $ N 2k $ bi $ b$bbbh bb $ b$bbbh bb $ b$bbbh bb $ b$bbbh bb $ ~! P32 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CR51 CI
0.000E+00 : 0.000E+00 : 0.000E+00': 0.000E+00 :

$ MN5k $ bk $ b$bbbk bb $ b$bbbh bb $ b$bbbh$bb $ b$bbbh bb $

MN56 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i FESS CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

FE59 CI

0.000E+00 : 0.000E+00~: 0.000E+00 : 0.000E+00 :

i

C058 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i

C060 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i

NI63 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

l

NI65 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
CU64 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i

ZN65 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

y N

ZN69
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

4 BR83

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

l ( t BR84 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

? i ...................................................................... i a 21

l f SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 p PAGE 2 0F 7 v EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 1 CONTINVOUS MODE BATCH MODE

NUCLIDES : UNITS :

QUARTER : QUARTER

.QVARTER :

QUARTER :

RELEASED :

1-2 1 2 LIQUID EFFLUENTS (CONTO) . LIQ CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TOTAL FOR :

PERIOD CI

0.169E-01 : 0.849E-02 : 0.000E+00 : 0.000E+00 :

(AB0VE) $ kE khb $ bk $b$bbbhbb$b$bbbEbb$b$bbbE$bb$b$bbbEbb$

XE-135 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00-:

I b V i -,--a,

SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 f-~ PAGE 3 0F 7 e EFFLUENT AND WASTE DISPOSAL REPORT 1 LIQUID EFFLUENTS FOR RELEASE POINT: 2 -l C("TINV0VS MODE BATCH H0DE NUCLIDES

UNITS :

QUAR'i;R : QUARTER : QllARTER : QUARTER : RELEASED 1 2 1 2 H3 CI

0.000E+00 : 0.000E+00 : 0.671E+02 : 0.190E+03 :

$ b$k $ b$ $ b$bbbh bb $ b$bbbh bb $ b bbbE bb $ b$bbbh bb $ NA24 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

P32 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

.....................................................-03 : 0.342E-03 : CR51 CI

0.000E+00 : 0.000E+00 : 0.191E HN54 CI
0.000E+00 : 0.000E+00 : 0.138E

.....................................................-03 : 0.732E-04 : /-'s (,)

HN56 CI
0.000E+00 : 0.000E+001: 0.000E+00 : 0.000E+00 :

FEbb $ bk $b$bbbEbb$b$bbbEbb$b$kkhk5bi$b$bbbEbb$ FE59 Cl- ': 0.000E+00 : 0.000E+00 : 0.882E-04 :.0.121E-03 : C058 CI

0.000E+00 : 0.000E+00 : 0.617E-02 : 0.417E-02 :

$ bb6b $ bk $b$bbbhbb$b$bbbhbb$b$bbbh5bb$b$hb2kbk$ NI63

Cl
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
NI65
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ bbbk $ b$ $ b$bbbh bb b$bbbh bb $ b$bbbk bb $ b$bbbE bb $ ZN65 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
ZN69
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BR83

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

(/) BR84

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

s__ BR85

CI
0.000E+00 : 0.000E400 : 0.000E+00 : 0.000E+00 :

1 , t

I" Q w _ K ,i SITE: South Texas Project Electric Generating Station ? UNIT: 2 YEAR: 1990 PAGE 4 0F 7 _is EFFLUENT AND WASTE DISPOSAL REPORT 5 s LIQUID EFFLUENTS FOR RELEASE PO!.NT: 2 x Lw CONTINU0US MODE BATCH MODE 9 g

NUCLIDES
UNITS : QUARTER :

QUARTER : QUARTER QUARTER : ? RELEASED : 1 2 1 2 7 LIQUID EFFLUENTS (CONTD) RB86 Cl

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00.:

i RB88 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
RB89 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

B jg SR89 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0,000E+00 :.

A. SR90 CI

0.000E+00 : 0.000E+00 : 0.000E+00-: 0.000E+00 :

i SR91

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
SR92
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

1

Y90
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

Y91M CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00-:

3 Y91 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

g g. Y92 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

= i $ h93 $~bi $b5bbbEhbb$b$bbbEbb$b$bbbkbb$b$bbbEbb$ $ kRb5 $ bi $b$bbbEbb$b$bbbEbb$b$2b8Ebk$b$ih6k5b4$ ZR97 CI

0.000E+00 : 0.000E+00 : 0.763E-06 : 0.000E+00 :

j-

NB95 CI
0.000E+00 : 0.000E+00 : 0.386E-04 : 0.309E.04 :

i

M099 CI
0.000E+00 : 0.000E+00 : 0.121E-05 : 0.000E+00 :
TC99M
CI
0.000E+00 : 0.000E+00 : 0.115E.05 : 0.000E+00 :

n C101 $ CI $0000h+00$0000E+00$0$000E+00$0$000E00$ i n

g @ g g /g y yy Q D1;g y[y g]QQ g.( % SITE: South Texas ~ Project Electric Genersting 5tttion I-UNIT: 12 YEAR: 1990 g PAGE 5 0F 7 EFFLUENT AND WASTE DISPOSAL REPORT LlQUID EFFLUENTS FOR RELEASE POINT: 2 CONTINU0US MODE BATCH MODE NUCLIDES : UNITS QUARTER : QUARTER : QUARTER QUARTER : RELEASED : 1 2 1 2 LIQUID EFFLUENTS (C0llTD). RU103 CI

0.000E+00 : 0.000E400 : 0.000E+00

$,G.90E+00 : -a RU105

CI
0.000E+00 : 0.000E+00 : 0.000E491 : 0.000E+00 :

Rbibb $ bi $b$bbbhbb$b$bbbhbb$b$bbbkOb.0.000kbb$

AG110M
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE125M
CI
0.000E+00 : 0.000E+00 : 0.000Ee00 : 0.000E+00 :

9

TE127H CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE127
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
TE129M
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ kEib9 $ bk $ b bbbh bb $ b bbbh bb $ b$bbbk bbb$bbbE bb $ $ kEibkM $ bk $ b$bbbk bb b$bbbk bb $ b$bbbh bb $ b$bbbh bb $ $ hkkbk bk $ b$bbbk bb $ b bbbh bb $ b$bbbh bb $ b$bbbhhbb $

TE132 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

1130 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

1131 CI

0.000E+00 : 0.000E+00 : 0.115E-04 : 0.126E-05 :

1132

CI
0.000E+00 : 0.000E+00 : 0.000E+00:: 0.000E+00 :

ikbb $ bk $ b bbbh bb $ b$bbbh bb $ b kkhk5bb $ b$bbbh bb $

~~iiii-~~~~~$~~bi-~~$~6$ibbi;6b$~b$66bi;bb$~b$bbbi;5b~$b$bb5iibb~;

$~~iii5-~~~~~$~~bi-~~$~6$bbbi;i6~$~b$6;bi;b5~;~b$bbbi;bb$~b$bbbi;b;

f' SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 /"T PAGE 6 0F 7 . (J EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT: 2 CONTINV0VS MODE BATCH MODE NUCLIDES

UNITS :

QUARTER : QUARTER : QUARTER : QUARTER : RELEASED : 1 2 1 2 .............c......................................... LIQUID EFFLUENTS (CONTD) $ bbkbk bk $ b$bbbh bb b$bbbh bb $ b$bbbh bb $ b$64kh$bh $ CS136 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ bbkbh $ b$ b bbbE bb b bbbk bb $ b bbbh bb $ b$bbbh bb

CS138 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

i BA139

CI
0.000E400 :-0.000E+00 : 0.000E+00 : 0.000E+00 :

7-~s L] BA140

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BA141 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BA142 CI

0.000E+00.: 0.000E+00 : 0.000E+00 : 0.000E+00 :

LA140 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.129E-04 :

l $LAi42" "'$ bi $b$bbbkIbb$'b$bbbkIbb$'b$bbbE+bb$b$bbbk+bb'$ 1 CE141 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

l l CE143 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

CE144 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E400 :

PRk43 $ bk $ b$bbbE bb $ b$bbbE bb $ b$bbbE bb $ b$bbbh bb $ PR144 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

ND147 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

W187 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

NP2b9 $ b$ $ b bbbE bb $ b$bbbk bb $ b$bbbh bb $ b$bbbh bb $ s s

SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR: 1990 (T PAGE 7 0F 7 V EFFLUENT AND WASTE DISPOSAL REPORT l LIQUID EFFLUENTS FOR RELEASE POINT: 2 CONTINUOUS MODE BATCH' MODE i 1 1 L

NUCLIDES : UNITS : QUARTER' : QUARTER :

QUARTER : QUARTER : RELEASED : 1 2 1 2 LIQVIDEFFLUENTS(CONTD) . LIQ

CI
0.000E+00 : 0.000E+00 : 0.740E-03 : 0.344E.01 :
TOTAL FOR :

PERIOD CI

0.000E+00 : 0.000E400 : 0.671E+02 : 0.190E+03 :

(AB0VE) ( $ kh.$bb$ bk b$bbbhbb$b$bbbhbb$b$hbhh5bb$b$kk9hbk$ XE-135 CI

0.000E+00 : 0.000E+00 : 0.361E.04 : 0'131E-01 :

4 1 /.i s.

i OL SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ist and 2nd Quarter, 1990 O.

EFFLUENT AND WASTE DISPOSAL REPORT SOLID WASTE AND IRRADIATED FUEL SHPMENTS FROM 1/1/90 0:00 TO 6/30/90 23:00 A. Solid Waste Shipped off site for burial or disposal (not irradiated fuel) 6 Month. Est. Total 1. Type of Waste Unit Period Error % A. Spent Resins, Filter M 5.830 E + 00 N/A Sludges, Evaporator CI 7.960'E + 00 Bottoms, Etc. B. Dry Compressible Waste M 3.180 E + 01 N/A Contaminated Equip., Etc. CI 3.800 E Al C. Irradiated Components, M 0.000 E + 00' N/A Control Rods, Etc. CI 0.000 E + 00 D. Other M 0.000 E + 00 N/A-CI 0.000 E + 00 2. Estimate of Major Nuclide Composition (By Type of Waste) A. 1 Co-58 8.280 E + 01 % 2 Co-60 6.200 E + 00 % 3 Mn-54 3.500 E + 00 % 4 Ni-63 2.600 E + 00 % 5 Fe-55 1.800 E + 00 % 6 H-3 1.600 E + 00 % B. 1 H-3 4.620 E + 01 % 2 Cr-51 3.940 E + 01 % 3 Co-58 2.640 E + 01 % 4 Fe-55 6.800 E + 00 % 5 Nb 3.800 E + 00 % 6 Zr-95 3.400 E + 00 % l C. N/A N/A D. N/A N/A 1 ' l

(~ t EFFLUENT AND WASTE DISPOSAL REPORT i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FROM 1/1/90 0:00 to 6/30/90 23:00 3. Solid Waste Disposition (Not Irradiated Fuel) Number of Shipments tiode of Transportation Destination 7 - Truck Scientific Ecology Group Oak Ridge, TN f Chem-Nuclear Systems i Barnwell, SC j 4. Class of Solid Waste i Class A - Unstable i-5. Type of Containers Used for Shipment -j i Strong Tight, High Integrity Containers f 6. Solidification Agent I~'\\ N/A V B. Irradiated Fuel Shipment (Disposition) i Number of Shipments Mode of Transportation Destination --No Shipments made during this period-- ) f O.

l l O APPENDIX As RADIOACTIVE WASTE TREATMENT SYSTEM DESIGN MODIFICATION DESCRIPTION 0.

l. f RADWASTE TREATMENT SYSTEM DESIGN MODIFICATION An HL&P-initiated modification to the Liquid Radioactive Waste Treatment System for Unit 2 was completed on June 21, 1990. This description is submitted to comply ~1th Section-6.15 of the Technical Specifications for the South Texas Project Electric Generating Station Unit 2. 1. A summary of the evaluation that led.to the determination that the change could be made in accordance with 10CFR50.59, 2. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information. 3. A detailed description of the equipment, components, and processes involved and the interfaces with otherJplant systems. 4. An evaluation of the change, which shows'the predicted release of radioactive materials in liquid;and gaseous affluents and/or' quantity of solid waste that differ for those-previously predicated in the License Application and Amendments. 5. An evaluation of the change, which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License Application and ~ O Amendments. .i 6. A comparison of the predicted release of radioactive materials, in liquid and gaseous effluents and solid waste, to the actual releases for the period prior to when the changes are to be made. 7. An estimate of the exposure to plant personnel as a result of the change. 8. Documentation of the facts that the change was reviewed and approved by the Plant Operations Review Committee (PORC). l AV !

p J. RADWASTE TREATMENT SYSTEM DESIGN MODIFICATION 1. A summary of the evaluation that led to the determination that the change could be made in'accordance with 10CFR50.59. l A 10CFR50.59 Determination Review Form was completed by Support Engineering. The basis for the determination that there was not an i Unreviewed Safety Question is described below, t i The Laundry Drains are described in FSAR Section 9.3.3 and shown on FSAR Figure 9.3.3.5. Since the drains were initially designed to run to the Laundry and Hot Shower Tank (LHST) and the subject of this review does not change the deeign bases as described in FSAR Section 9.3.3, there is no impact to the system function / operability that result from the rerouting of the drains. There is an impact to FSAR Figure 9.3.3-5 as a result of revising P&ID-1 7Q069F90012 #2. The MAB Flooding Analysis and MAB Facility Response Analysis for Flooding and Spray Effects for rooms 067C, 107, and 110 were' 'f reviewed and not found to be impacted by this modification, i There is no impact to the SER and STP ER as a result of_this modification since the change is consistent with the description in the SER (Ref. 11.21, pg. 11-2). The Engineering Index for Penetration Seals was revised as a result of l moving a 4" line. A review of.the Fire Hazards Analysis Report (FHAR) Figures 3-14 and 3-30 show that. the two' penetrations effected were in a ] non-fire rated wall, not sealed for fire, and therefore, not impacting'the i FHAR. 'l Radiation sealing was provided in a penetration between a Radiation' Zone 5 f and a Radiation Zone 2, per FSAR Figure 12.3.2-8. No other radiation j shielding was required and FSAR Section 12.3.2 was not impacted. i 2. Sufficient detailed information to totally support the' reason for the change without benefit of additional or supplemental information: The Laundry and Hot Shower Tank (LHST), Condensate Polishing Regenerative -{ Waste Collection Tank (CPRWCT) and associated piping in the Liquid Waste Processing System have undergone several design changes during -f construction resulting in the LHST being seldom used and laundry and dry. e cleaning drains being routed to CPRWCT. The intent of the original plant design was to have laundry and dry cleaning drains routed to the LHST. l This modification rerouted the laundry and dry cleaning drains in Unit'2 to the LHST for the following reasons: 1 i a. LHST has a usable volume of 9300 gallons. This modification added f much needed volume to the LWPS. LHST may be discharged directly to l the reservoir and eliminates need for use of waste monitor tank space. l em This aids Chemical Operations in processing of radioactive 11guld i waste. f )

l O b. Chemical Operations processes CPRWCT several times weekly. Lint from the laundry along with other impurities caused strainer clogging resulting in several change outs in order to achieve required-recirculation t'.me prior to sampling, j c. The CPRWCT receives floor drains during the Floor Drain Tank -I processing, and primary lab drains. Processing by evaporation may be required to adequately dispose of this waste. The detergent from the laundry drains complicates processing by evaporation due to foaming. 3. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems: This modification affects a portion of.the laundry and dry cleaning drain I piping (4" dia.) which is connected to-the chemical water header. The 1aundry and dry cleaning drain connected to the chemical waste header was I disconnected and the chemical waste header branch was capped. The laundry. and dry cleaning drain was then routed to existing laundry and hot shower drain header. This allows draining into the Laundry and Hot Shower Tank. 4. An evaluation of the change, which shows the predicted release of radioactive materia *.s in liquid and gaseous effluents and/or quantity of solid waste that dif ter for those previously predicted in the License Application and Amendments: O This modification affects a portion of the laundry and dry cleaning drain y connected to the Condensate Polishing Regenerative Waste Collection Tank. This drain was rerouted and connected to the Laundry and Hot Shower Tank. This modification does not change the amount of liquid and gaseous effluents, nor quantity of solid waste predicted'in'the License Application and Amendments. 5. An evaluation of the change, which shows the expected maximum exposure to individuals in the UNRESTRICTED AREA and to the. general population that differ from those previously estimated in the License Application and. Amendments: This modification affects the laundry and dry. cleaning drain connected to the Condensate Polishing Regenerative Waste Collection Tank. This drain was rerouted and connected to the Laundry and Hot Shower Tank. This modification will not result in a change to expected maximum exposures to individuals in the unrestricted area and to the' general population as ~ previously estimated in the License Application and Amendments. 6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and solid waste, to the actual releases for the period prior to when the changes are to be made: O 1 l i O This modification affects a portion of the laundry and dry cleaning drain connected to the Condensate Polishing Regenerative Waste Collection Tank. The drain was rerouted and connected to the Laundry and Hot Shower Tank. This modification does not change the amount of liquid and gaseous effluents, and solid waste. The predicted releases of radioactive l materials, in liquid and gaseous effluents and solid waste should be the same as the actual releases for the period prior to when the change was i made. 7. An estimate of the exposure to plant personnel as a result of the changes I This modification affects the laundry and dry cleaning drain, which was connected to the Condensate Polishing Regenerative Waste Collection Tank. This drain was rerouted and connected to the Laundry and Hot Shower Tank, j This change will potentially result in decreased exposure to plant I personnel. Use of Laundry and Hot Shower Tank for processing the laundry 1 and dry cleaning drains will reduce the handling of contaminated strainers at the CPRWCT due to lint, tape, and impurities from the laundry thereby reducing exposure. 8. Documentation of the fact that the change was reviewed and approved by the Plant Operationa Review Committee (PORC) A 10CFR50.59 Evaluation Form was completed by Support Engineering. It was () determined that there were no Unreviewed_ Safety Questions and a PORC Review was not required for this design change. I i i i O m..mm,,

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I g 94 .'r ,'h k j 4 f g 1 T m, JAPPENDIXLB:1LREVISED LIQUID? EFFLUENT e, ,q o a -B i ' u g ' ANDiDOSE ACCUMULATION!,' s 1 Y _: s - FOR1989-- o.. m1 ,m.sx s etu - 3rd and.;4th5 UARTERL - _. 9 - t Q cy ^. uam 1 t e ,g '., 4, :u n-1 _a ;. - g f Yi I. ) i 9 k f. ,y. > s _:. v. y f> ' = - t ;., .3 _;h'* t ../ ; ~ -d :;- -y ..( _,w; m-.:= l<L.f {7.,4...-Js. ie' 1- .e e.- r. t ; rc;'t + e' ' '. r -.y;. S A,. ,-:-[. ? 5 r 5 _1-a: ph- .: ; s., g - -'3i- >, g; jp, 9 I 5 pp t 1 17:. ~ 7 5.,. '4 W ) k { (. -t_ -d3 4 j 5 d n m i n 1 e. 1 i g I 1' Q fs t ...Y... ,,T. e*yL-ar i.'{ s i 4yl i k PA 1 .7~ r '.'f.' '(!, A i.-. i__. - y m; [ f[': _'t' s i ' - ;j 1

j.,.

b. N4 8t t l f.: i 3 l .,15

4.~ 5..-'i>.

11 I 2 .t - i y 1 g t47 - I I' j ,U,_'T'.' '.r I m(. 'n' 3 d +-_w y a r

T v' _

J.'> . a.5 : 4 e.!3

e. 3..

r. .j i s t , 4 3

SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR:1989 I EFFLUENT AND WASTE DISPOSAL REPORT-LIQUID EFFLUENTS -- SUMMATION OF ALL RELEASES-

UNITS :

QUARTER : QUARTER :EST. TOTAL: l 3 4

ERROR, %:

~~ A.FISSIONANDACTIVATIONPRbbbbiS 4

1. TOTAL RELEASE (EXCL.: CI
0.811F+00 : 0.212E+01 : 0.500E+01 :

TRIT., GASES, ALPHA): i i

2. AVERAGE DILUTED
UCI/ML : 0.451E-07 : 0.ll8E-06 :

CONC. DURING PERIOD :

3. PERCENT OF
0.225E+01 : 0.590E+01 :

APPLICABLE LIMIT .1

3. TRITIUM
1. TOTAL RELEASE CI
0.829E+02 : 0.590E+02 : 0.500E+01 :

]

2. AVERAGE DILUTED
UCI/ML : 0.461E-05 : 0.328E-05-:

CONC. DURING PERIOD :

3. PERCENT OF
0.153E500 : 0.109E+00 :

APPLICABLE LIMIT C. DISSOLVED AND ENTRAINED GASES $'i$'ibikE~RELkkk( $ bi ~$ b$3i7k+bb $ b$92bk$bI $ b$5bbk+bi $ $'2$'kVkR bk'bilbikb$bbi/M['I'b$iihk5bi'$'b$55bk5bb'$""""' CONC. DURING PERIOD :

3. PERCENT OF
0.883E-02 : 0.258E-02 :

APPLICABLE LIMIT D. GROSS ALPHA RADI0 ACTIVITY

1. TOTAL RELEASE
CI
0.573E-02 : 0.262E-02 : 0.500E+01 :

E. VOLUME WASTE RELEASED : LITERS : 0.827E+07 : 0.472E+07 : 0.800E-01 : (PRIOR TO DILUTION) F. VOLUME DILUTION WATER : LITERS : 0.180E+11 : 0.180E+11 : 0.100E+02 :

USED DURING PERIOD SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR:1989 EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS i

CONTINU0US MODE BATCH MODE

NUCLIDES : UNITS : QUARTER : QUARTER
QUARTER :

QUARTER : RELEASED : 3 4 3 4 i H3

CI
0.000E+00 : 0.000E+00 : 0.829E+02 : 0.590E+02 :
C14
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
NA24
CI
0.000E+00 : 0.000E+00 : 6.000E+00 : 0.000E+00':

P32

CI
0.000E+00 : 0.000E+00 : 0,000E+00 : 0.000E+00 :-

i CR51

CI
0.000E+00 : 0.000E+00 : 0.225E+00 : 0.461E+00 :
HN54
CI
0.000E+00 : 0.000E+00 :.0.949E-02 : 0.689E-01 :
MN56 CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

FESS

CI
0.000E+00 : 0.000E+00 : 0.794E-01 : 0.434E+00 :

FE59

CI
0.000E+00 : 0.000E+00 : 0.149E-01 : 0.399E-01 :
C058 CI
0.000E+00 : 0.000E+00-: 0.427E+00::-0.732E+00 :

i ..................................c....................__............. _l

C060
CI
0.000E+00 : 0.000E+00 : 0.199E-01 : 0.180E+00 :

NI63

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

NI65

CI
0.000E+00 : 0.000E+00 : 0.000E+00 :-0.000E+00 :
CU64
CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :
IN65 CI
0.000E+00 : 0.000E+00 : 0.371E-03 : 0.626E-02 :

ZN69

CI
0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BR83 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

BR84 CI

0.000E+00 : 0.000E+00 : 0.000E+00 : 0.000E+00 :

$ BR85 $ bi $b$bbbhbb$b$bbbkbb$b$bbbh$bb$b$bbbkbb$

7 V ' SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR: 1989

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATION FOR PERIODS: LIQUID: FROM 07/01/89 00:00- TO 12/31/89 23:00 APPLICABLE ESTIMATED AGE. LOCATION % OF. LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MR) (MREM) (M) (T0 WARD)

LIMIT, LIQUID TOTAL BODY 4.0SE-02 TEEN RECEPT 0R 3 1.4E+00 3 ~. 0 LIQUID GI-TRACT 1.72E-01 ADULT RECEPT 0R 3 1.8E+00 10.0 LAST ACCUMULATION FOR PERIODS:-

!IQUID: FROM 07/01/89 00:00 TO 12/31/89 23:00 llll EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM) LIQUID TOTAL BODY 3.5E.01' LIQUID B0NE 8.7E r - 50 .}}

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