View source for ST-HL-AE-2769, Semiannual Radioactive Effluent Release Rept for 880308- 0630

{{Adams
| number = ML20153B674
| issue date = 06/30/1988
| title = Semiannual Radioactive Effluent Release Rept for 880308- 0630
| author name = Vaughn G
| author affiliation = HOUSTON LIGHTING &amp; POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000498
| license number = 
| contact person = 
| document report number = ST-HL-AE-2769, NUDOCS 8808310047
| document type = ENVIRONMENTAL MONITORING REPORTS(&amp;RADIOLOGICAL)-PERIODIC, TEXT-ENVIRONMENTAL REPORTS
| page count = 300
}}

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HOUSTON LIGHTING AND POVER COMPANY.
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT ONE LICENSE NO. NPF-76 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT MARCH 8. THROUGH JUNE 30, 1988 Prepared by:      0 %     E.( rd,#L                          6[l 88 Chem 1[ cal Op Potions and An lysis Manager       Dat'e Reviewed by:       / 41u i  8 m /1 Physics Manager A.'                 8!/8 $
He-                                             / Date Reviewed by:       &                                             /'I P)angEgineringManager                         ' Date Raviewed by:                          h 1L Pla      erations Ha   aer                       'Dat e '
Approved by    f.              L                                  jf/fM chn    1 Se vices Manager                     'Da tie Approved by:                        AJ                           ff2.L fE Plant Sup intendent ( ni      1)                  Date Approved by:                   e 6 J3 Plant ManageY Q                        Date>
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i l-l TABLE OF CONTENTS SUBJECT                                                             PAGE 1.0 Introduction                                                           6 2.0 Supplemental Information for Effluent and Waste Disposal               6 l      2.1  Regulatory Limits                                                 6 l
l           2.1.1   Fission and activation gases                              6 l           2.1.2   Fission and activation gases, lodines, particulates, l                   half-lives > 8 days                                       7 2.1.3   Iodines and Particulates, half lives > 8 days             7 2.1.4   Liquid effluents                                          7 2.2  Maximum Permissible Concentrations                                8 2.2.1   Liquid effluents                                          8 2.3  Average Energy (HeV/ Disintegration)                              8 i      2.4  Measurements and Approximations of Total Activity                 8 l
2.4.1   Gaseous Effluents                                         8 2.4.1.1 Fission and activation gases                      8 2.4.1.2 Iodines and Particulates                          9 2.4.1.3 Analytic Methods                                  9 2.4.2   Liquid Effluents                                         10 2.4.2.1 Analytic Methods                                 10 I
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h TABLE OF CONTENT 3 (CONT.)
SUtJECT                                                          PAGE 2.5   Batch Releases                                               11 2.5.1  Liquid                                                11
: a. Number of batch release                               11
: b. Total time period for batch releases                  11
: c. Maximum time period for a batch release               11
: d. Average time period for a baich release               11
: e. Minimum time period for a batch release               11 1 2.5.2  Gaseous                                               11
: a. Number of batch release                          11
: b. Total time period for batch releases             11
: c. Maximum time period for a batch release          11
: d. Average time period for a batch relea4e          11
: e. Minimum time period for a batch rolease          11 2.6   Abnormal Releases                                            12 ,
2.6.1  Liquid                                                12
: a. Number of releases                               12
: b. Total activity released                          12 2.6.2  Gaseous                                               12
: a. Number of releases                               12
: b. Total activity released                          12 y                                                               .-'-u_

f TABLE OF CONTENTS (CONT.)
SUBJECT                                                      PAGE 2.7   Estimate of Total Error                                  12 2.7.1   Liquid                                           12 2.7.2   Gaseous                                          12 2.7.3   Solid Radioactive Waste                          12 2.8   Solid Vaste Shipments.                                   13 2.9   Radiological Impact on Han                               13 2.10 Meteorological Data                                       13 2.11 Lower Limit of Detection (LLD)                            13 2.12 Doses to Hembers of the Public on Site                    13 3.0 Technical Specification Reporting Requirements                 13 3.1   Radioactive Waste Treatment System Design Modifications Description                                13 3.2   Inoperable Effluent Honitoring Instrumentation Explanation                                              14 3.3   Gas Storage Tank Curie Limit Violation Description       14 3.4   Unprotected Outdoor Tank Curie Limit Violation Description                                              14 3.5   Abnormal Release Description                             14 3.6   Radioactive Waste Process Control Program Changes        15 3.7   Offsite Dose Calculation Manual (ODCM) Changes           15 3.8   New Land Use Census Location (s) Identification          15
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LIST OF TASLES
* PAGE
,   Gaseous Effluents - Summation of all releases, Unit 1 - 1st and 2nd Quarters, 1988                                16' 4
Gaseous Effluents - Ground Level Release, Release Point 1 j   Unit 1 - 1st and 2nd Quarters, 1988                                         '
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Gaseous Effluents - Ground Level Release, Release Point 2                 .i 4   Unit 1 - 1st and 2nd Quarters, 1988                                19       !
Gaseous Effluents - Ground Level Release, Release Point 3                   .
;   Unit 1 - 1st and 2nd Quarters, 1988                                21       !
t Liquid Effluents - Summation of all releases, Unit 1 - 1st and 2nd Quarters, 1988                                23      i I
i Liquid Iffluents For Release Point 2, Uni; 1 - 1st and 2nd Quarters, 1988 j
24 4'                                                                              r a
Solic' Waste and Irradiated Fuel Shipments                         29 i
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LIST OF APPEND /CES-PAGE Appendix A - Optional Use of Filter Elements in Influent to vaste Monitor Tonks                       31 Appendix 5 - Increase in Waste Evaporator Concentrates Operational Levels                       40 Appendix C - Addition of Local Sampling for Waste Monitor Tanks D. E. F                           49 Appendix D - Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks       58 g         Appendix E - Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid 67 Appendix F - Addition of an Isolok Sampler for Spent Resin Discharge to Nobile Solidification Unit                                   76 l
1.0 Introduction This Semiannual Radioactive Effluent Release Report, for the period March 8, 1988, (initial criticality-Unit 1)to June 30, 1988 is submitted in accordance with Appendix A of License NPT-76. This report will not           -
include data for Unit 2 which is under construction. Separate tables of releases and release totals are included where separate processing systems exist.
In accordance with Technical Specifications 6.9.1.4 the annual summary of hourly meteorological data collected over the previous year shall be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days af ter January 1 of each year. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous affluents released from the unit or station and an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC duw to their activities inside the SITE BOUNDARY during the reporting period for the previous calendar year. Also included in this report shall be an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other     I nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation for the previous calendar year.
All assessments of radiation doses are performed in accordance with the l
STPEGS Offsite Dose Calculation Manual (ODCH).                               !
2.0 Supplemental Information for Effluent and Waste Disposal South Texas Project Electric Generating Station.
Houston Lighting and Power Co.
l Unit Number 1               Cooling Water Source:
Type:   PWR                 Hain Cooling Reservoir Docket No. 50-498           Power (HWT)- 3817 Initial Criticality-(March 8, 1988) 2.1    Regulatory Limits 2.1.1   Fission and activation gases The air dose due to noble gases released in gaseous            i effluents, from each unit, to areas at and beyond the Site     l Boundary shall be limited to the following
: a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and                             !
: b. During any calendar years Less than or equal to 10        i mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
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c 2.1.2 Fission and activation gases, iodines, particulates, half-lives > 8 days.
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Site Boundary shall be limited to the followings
: a. For noble gasee    Less than or equal to 500 mroms/yr to the whole body and less than or equal to 3000 arems/yr to the skin and
: b. For Iodine-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 mroms/yr to any organ.
2.1.3 Iodines and Particulates, half-lives > 8 days The dose to a Member of the Public from Iodine-131     Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 4 days in gaseous effluents released, from each unit, to areas at and beyond the Site Boundary shall be limited to the followings
: a. During any calendar quarter: Less than or equal to 7.5 mroms to any organ and,
: b. During any calendar years   Less than or equal to 15 mreme to any organ.
2.1.4 Liquid Effluents The dose or dose commitment to a Member of the Public from      i radioactive materials in liquid effluents released, from each  ;
unit, to Unrestricted Areas shall be limited to:               !
: a. During any calendar quarter to less than or equal to 1.5 mroms to the whole body and to less than or equal to 5 mrems to any organ, and                                  ,
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: 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.
                                                                                                     )

2.2                                      Haximum Fermissible Concentrations 2.2.1                                                                 Liquid Effluents The concentration of radioactive material released in liquid effluents to Unrestricted Areas shall be limited to the                                                                                     ;
concentrations specified in 10CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.                                                                          For dissolved or entrained noble             i gases the concentration shall be limited to 2.0E-04 micro                                                                                    I curie /mi total activity.                                                                                                                    !
2.3                                      Average Energy (MeV/ Disintegration) j The Average Energy (or E-bar) is not used at STPEGS to calculate releasw limits.                                                                                                                                                                                                    !
2.4                                     Measurement and Approximations of Total Activity
  ;                                                         The following discussions detail the methods used to measure and j
approximate total activity for the following
;                                                            a.                                     Fission and Activation Gases                                                                                                                                                 [
: b.                                       Iodines                                                                                                                                                                    ''
j                                                           c.                                      Particulates                                                                                                                                                                 ,
: d.                                      Liquid Effluents Tables A3-1 and A4-1 of the STPEGS Offsite Dose Calculation Manual                                                                                                                                                   l (ODCM) give sampling frequencies and minimum detectable concentration requirements for the analysis of liquid and gaseous                                                                                                                                                    !'
effluent streams.
(
1                                                           2.4.1                                                                 Gaseous Effluents                                                                                                                              !
i 2.4.1.1                                                                                     Fission and Activation Gases                                 l
)                                                                                                                                                                                                                   The following noble gases are considered in l
evaluating gaseous airborne discharges:
l Ar-41          Xe-131m Kr-83m         Xe-133m j                                                                                                                                                                                                                   Kr-85m         Xe-133                                        {
Kr-85          Xe-135m                                       i
;t                                                                                                                                                                                                                  Kr-87          Xe-135                                        i
!                                                                                                                                                                                                                   Kr-88          Xe-137                                        i d                                                                                                                                                                                                                   Kr-89          Xe-138                                        I l                                                                                                                                                                                                                   Kr-90
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2.4.1.2 Iodines and Particulates I
The radiciodines and radioactive materials in particulate forms to be considered are Cr-51            Sb-124    H-3                        '
Hn-54            I-131     C-14 Te-59            I-133     Ho-99 Co-58           Cs-134 Co-60           Cs-136 Zn-65           Cs-137 Sr-89           Ba-140 Sr-90           Co-141 Zr-95           Co-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 and 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. The particulate sample filters are also analyzed for gross alpha  :
on a gas-flow proportional counter. The filter samples are chemically processed to separate strontium for analysis using a gas-flow           ;
proportional counter.                             <
The radionuclide values obtained are used in conjunction with the gross noble gas release      :
rate monitoring data collected by the radiation   ,
monitoring system to estimate the release rate     I of each radionuclide in the effluent streams,
: b. Continuous Gaseous Releases                        l l
Periodic noble gas grab samples are taken from     l the continuous release points (i.e. the Unit vent and the condenser vacuum pump exhaust).
Continuous sampling for particulates and lodine is also performed on the ef fluent streams. They are analyzed for gross alpha, for gamma radionuclides, and strontium as described above for batch releases.
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2.4 2 Liquid Effluents                                                                                                            !
The radionuclides listed below are considered when evalvating liquid effluentsi                                                                                                          i H3               Y-90                                                              1-133                          l C14              Y-91m                                                             I-134-Na-24            Y-91                                                              1-135                          r P-32             Y-92                                                            Cs-134                           (
Cr-51            Y-93                                                            Cs-136                           i Mn-54            2r-95                                                           Cs-137                           [
Mn-56            Zr-97                                                           Cs-138                           '
I                  Fe-55            Nb-95                                                           Ba-139                           [
Fe-59            Mo-99                                                           Ba-140                           !
Co-58            Tc-99m                                                          Ba-141                           !
Co-60            Tc-101                                                          Ba-142                           i Ni-63            Ru-103                                                          La-140                           -
 !                 Ni-65            Ru-105                                                          La-142 i
Cu-64            Ru-106                                                         Co-141
 )                 Zn-65            As-110m                                                         Co-143                           i i                 Zn-69            Te-125m                                                         Co-144                           L Br-83            Te-127m                                                         Fr-143 Br-84            Te-127 f
l                                                                                                   Fr-144                           '
Br-85            Te-129m                                                        Nd-147                            (
j                  Rb-86            Te-129                                                         W-187 Rb-88            Te-131m                                                        Np-239 Rm-89            Te-131                                                            . LIQ (unidentitled)*          "
i Sr-89            Te-132                                                            . ALPHA (Gross Alpha)
St-90            1-130                                                             .Xe-133 Sr-91            1-131                                                            .Xe-135 Sr-92            I-132
* includes other gamma peaks                                                            i that are identified j
2.4.2.1  Analytic Methods                                                                                                  !
I l         2.4.2.1  a. Batch Liquid Releases l                                                                                                                                    f All liquid effluents are released as batches.
)                       Representative pre-release grab samples are                                                                  ;
i taken and analyzed in accordance with Table A3-1                                                             i of the ODCM. Radionuclide analyses are                                                                        !
3                       performed using the Gasuna Spectroscopy System,                                                              i
 !                     Aliquots of each pre-release sample are
{                      composited in accordance with the requirements                                                                (
l in Table A3-1 of the ODCM. Strontium                                                                          i determinations are made by performing a chemical                                                              i separation and counting *5e r.eparated                                                                        ;
radionuclides using the was-: flow Proportional                                                              ;
,                      Counting System. Gross alphu determinations are                                                               i made using the Gas-Flow Proportional Cou. ting                                                                I l
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System. Tritium concentrations are determined using Liquid Scintillation Counting techniques.
Iron determina", sons are made by performing a chemical separation and counting the separated radionuclide using the Liquid Scintillation Counting Systos. Dissolved and entrained gases are determined by counting grab samples on the Gamma Spectroscopy System.
The radionuclide concentrations obtained are 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 counting uncertainty associated with these measurements is accurate to tha SI significance level for the principle radions.lides released.
2.5 Batch Releases 2.5.1  Liquid                                Quarter 1     Quarter 2
: a. Number of releases:                   0              73
: b. Total time period for releases (min):                       0            3900
: c. Maximum time period for a release (min):                  0              68
: d. Average time period for a release (min):                  0              55
: e. Minimum time period for a release (min):                  0               7 2.5.2  Gaseous
: a. Number of releases:                    0              26
: b. Total time period for releases (min):                    0           31479
: c. Maximum time period for a release (min):                   0           10761       )
: 4. Average time period                                            l for a release (min):                   0            1211
: e. Minimum time period                                            l for a release (min):                   0               6 J

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1 2.6 Abnormal (Unplanc.-d) Releases e
2.6.1  Liquid                                Quarter i      Quarter 2-
: a. Number of c eleases:                   0'      __
2
: b. Total activity released (curies):                        0.000E+00      3.126E-02 2.6.2  Gaseous
: 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-measurt.7ents, based upon plant calibration practice is estimated to be +/- 0.08%.
: b. The average error associated with counting uncertainty is accurate to the 5% significance level.
2.7.2  Gaseous
: a. The maximum error associated with menitor readings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedures are collectively estimated to bei Fission and Activation Gases              Iodines        Particulates       Tritium 125%                     125%             1 25%              125%
: b. The average error associated with counting uncertainty is       ;
accurate to the 5% significance level for fission and           ;
activation gases, lodines, particulates and tritium.            I 2.7.3  Solid Radioactive Waste To date there have been no radioactive waste shipments to            I offsite burial facilities. Therefore percent error is not applicable.
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2.8   Solid Waste Shipments No radioactive waste shipments were made during this reporting period.
2.9   Radiological Impact On Man In accordance with Technical Specifications 6.9.1.4, this data shall be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year.
2.10 Meteorological Data In accordance with Technical Specifications 6.9.1.4, this data shall be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year.
2.11 Lower Limit of Detection (LLD)
The LLD (an a priori limit) is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability, and only a 5% probability of falsely concluding that a blank                    l observation represents a "real" signa!.
2.12 Dose to MEMBERS OF THE PUBLIC On Site i
In accordance with Technical Specifications 6.9.1.4, this data shall            i be submitted within 60 days af ter Jcnuary 1 of each year.                      I 3.0 Technical Specifications Reporting Requir .aants 3.1   Radioactive Waste Treatment System Design M 'ification Description The following is a list of Unit I liquid and solid radioactive waste            l treatment system design modifications initiated during this reporting period. No modifications were made to the gaseous                     I radioactive waste treatment system. These descriptions are                      I submitted to comply with Section 6.15 of the Technical l
Specifications.                                                                 '
3.1.1    Optional Use of Filter Elements in Influent to Waste Monitor Tanks (Appendix A) 3.1.2    Increase in Waste Evaporator Concentrates Operational Levels            l (Appendix B)

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l 3.1.3   Addition of Local Sampling for Waste Monitor Tanks D, E, F (Appendix C) 3.1.4   Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks (Appendix D) 3.1.5   Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid (Appendix E) 3.1.6   Addition of an Isolok Sampler for Spent Resin .         .. to Mobile Solidification Unit (Appendix F) 3.2 Inoperable Effluent Monitoring Instrumentation Explanation There were no inoperable liquid or gaseous effluent monitoring instrumentation not corrected within the time specified in Sections 3.3.3.10 or 3.3.3.11 of Technical Specifi-itions. This explanation is submitted to comply with reporting requirements of Section 6.9.1.4 of the Technical Specifications for Unit 1.
3.3 Gas Storage Tank Curie Limit Violation Description The quantity of radioactive materis1 in the RCS Vacuum Degassing System Storage Tank (s) did not exceed the limits set forth in Section 3.11.2.6 of Technical Specifications during this reporting period. This description is submitted to comply with Section 6.9.1.4 of the Technical Specifications for Unit 1.
3.4 Unprotected Outdoor Tank Curie Limit Violation Description The quantity of radioactive material in the Unprotected Outdoor Tank (s) df4 not exceed the limit set forth in Section 3.11.1.4 of Technical Specifications during this reporting period. This description is submitted to comply with Section 6.9.1.4 of the Technical Specifications for Unit 1.
3.5 Abnormal (Unplanned) Release Description The following is a list of abnormal releases of liquid waste from STPEGS Unit 1 to UNRESTRICTED AREAS that occurred during this reporting period.
Waste Monitor Tank IE        05/30/88 23:00 - 05/30/88 23:08 Waste Monitor Tank 1D        06/07/88 18:28 - 06/07/88 18:35 A description of the abnormal release for Waste Monitor Tank 1E is provided in the attached STPEGS Problem Report,' Appendix G. The supportive documentation for the problem report, which consisted of copies of logs, a copy of the surveillance package for the release and documentation of training, is not attached but shall be furnished on request. A description of the abnormal release for Waste Monitor Tank 1D is provided in the attached Licensee Event Report, Appendix H. These reports are submitted to comply with Section 6.9.1.4 of the Technical Specifications for Unit 1.
3.6 Radioactive Waste Process Control Program Changes A HL&P initiated editorial change to the Radioactive Waste Process Control Program (PCP) procedure (HL&P procedure OPGP03-ZO-0017) was completed on February 26, 1988. The change substituted the word "noncompressible" for "noncompactible" in all references to "noncompactible" receptacles. This change was to reflect the wording used in the Dry Active Waste Collection, Sorting and Segregation Procedure (OPGP14-WS-0010) and on the DAW receptacles.
Refer to attached copies of the Field Change Request and the Radioactive Waste Process Control Program Procedure pages 5 and 26 in Appendix I. The change did not reduce overall conformance of the solidified waste product to existing criteria for solid waste and because it was editorial in nature, it did not require PORC approval.
This notification of change is submitted to comply with Section 6.13.2 of the Technical Specifications for STPEGS Unit 1.
3.7 Offsite Dose Calculation Manual Change No changes were made to the Offsite Dose Calculation Manual (ODCM) during this reporting period. This description is submitted to comply with Section 6.14.2 of the Technical Specifications.
3.8 New Land Use Census Location (s) Identification No location (s) have been identified by the Land Use Census that yields a calculated dose or dose commitment greater than the values currently being calculated in accordance with Section 4.11.2.3 of the Technical Specification. This notification is submitted to comply with Section 3.12.2.a of the Technical Specification.
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EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS -- SUMMATION OF ALL RELEASES UNIT     QUARTER     QUARTER    EST. TOTAL 1           2      ERROR, %
A. FISSION AND ACTIVATION GASES
: 1. TOTAL RELEASE           CI         0.000E+00    0.971E+02  0.250E+02 l
: 2. AVERAGE RELEASE        UCI/SEC RATE FOR PERIOD                   0.000E+00    0.124E+02
: 3. PERCENT OF TECHNICAL    %
SPECIFICATION LIMIT               0.000E+00 l 0.458E-02 B. IODINES
: 1. TOTAL IODINE-131       CI          0.000E+00    0.000E+00
: 2. AVERAGE RELEASE 0.250E+02 l UCI/SEC RATE FOR PERIOD                    0.000E+00    0.000E+00
: 3. PERCENT OF TECHNICAL   %
SPECIFICATION LIMIT               0.000E400    0.000E+00 C. PARTICULATES
: 1. 2 ARTICULATES WITH     CI                                  0.250E+02 HALF-LIVES >8 DAYS                 0.000E+00    0.892E-01
: 2. AVERAGE RELEASE        UCI/SEC RATE FOR PERIOD                   0.bOGE+00     0.113E-01
: 3. PERCENT OF TECHNICAL   %
SPECIFICATION LIMIT               0.000E+0b     0.125E-01
: 4. GROSS ALPHA            CI j
RADIOACTIVITY                     0.000E+00     0.658E-01 D. TRITIUM i
: 1. TOTAL RELEASE              CI     0.000E+0C l 0.163E+00
: 2. AVERAGE RELEASE        UCI/SEC 0.250E+02 l RATE FOR PERIOD                   0.000E+00     0.207E-01
: 3. IERCENT OF TECHNICAL   %
SPECIFICATION LIMIT               0.000E+00     0.115E-04 16 -

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l FFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - GROUND LEVEL RELEASE RELEASE POINT:     1 (UNIT VENT)
CONTINUOUS MODE           BATCH MODE           l NUCLIDES         UNITS        QUARTER         QUARTER  QUARTER      QUARTEF ~~  l RELEASED                          1              2         1            2
                                                                                   ]
: 1. FISSION GASES
[ *41              CI         0.000E+00    0.873E+02  0.000E+00    0.93JE+01    I
_ pts 3M             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    l KR85               CI         0.000E+00    0.000E+00  0.000E+00    0 000E+00 KR87               CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 KR88               CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 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    '
x2131M             CI         0.000E+00    0.000E+00  0.000E+00    0.00CE+00 XE133M             CI         0.000E+00    0.000E+00  0.000E+00                 '
0.000E+00_
XE133              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 XE135M             CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 XW135              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 XE137              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 XE138              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 UNIDENT.           CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00    i TOTAL FOR                                                                       '
PERIOD             CI      '
(ABOVE)                       0.000E+00    0.873E+02  0.000E+00    0.986E+01    l I
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EFFLUENT AND WASTE DISPOSAL REPORT' GASEOUS EFFLUENTS - GROUND LEVEL-RELEASE RELE/SE POINT:     1 (UNIT VEN1)
CONTINUOUS MODE              BATCH MODE KUCLIDES         UNITS        QUARTER            QUARTER  QUARTER         QUARTEP.
 , RELEASED                             1              2         1                 2
: 2. IODINES Il31               CI         0.000E+00       0.000E+00  0.000E+00      0.000E+00 I133               CI         0.000E+00       0.000E+00  0.000E+00      0.000E+00 Il35               CI         0.000E+00       0.000E+00  0.000E+00      0.000E+00 TOTAL FOR PERIOD             CI (ABOVE)                       0.000E+00       0.000E+00  0.000E+00      0.000E+00
: 3. PARTICULATES C14                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 HN54               CI         0.000E+00       0.000E+00  0.000E+00 FE59 0.000E+0{_
CI         0.000E+00       0.000E+00  0.000E+00      0 . 0 0 0 E + 0','. ,
C058               CI         0.000E+00       0.000E+00  0.000E+00      0.000E+00 C060               CI         0.000E+00       0.000E+00  0.000E+00      0.000E+00 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       0.000E+00  0.000E+00     0.000E+00 SB124              CI         0.000E+00       0.000E+00  0.000E+03     0.000E+00 CS134              CI         0.000E+00       0.000E+00  0.000E+00     0.000E+00 CS136              CI         0.000E+00       0.000E+00  0.000E+00     0.000E+00 CS137              CI         0.000E+00       0.000E+00  0.000E+00     0.000E+00 BA140              CI         0.000E+00       C 000E+00  0.000E+00     0.000E+00 CE141              CI         0.000E+00       0.000E+00  0.000E+00     0.000E+00 CE144              CI         0.000E+00       0.000E+00  0.000E+00     0.000E+00 UNIDENT            CI         0.000E+00       0.336E-01  0.000E+00     0.557E-01 TOTAL FOR PERIOD             CI (ABOVE)                       0.000E+00       0.336E-01  0.000E+00     0.557E-01

EFFLUENT AND WASTE DISPOSAL REPORf GASEOUS EFFLUENTS - GROUND LEVEL RELEASE RELEASE POINT:   2 (MAIN STEAM LINE)
CONTINUOUS MODE           BATCH MODE NUCLIDES       UNITS         QUARTER         QUARTER  QUARTER      QUARTER RELEASED                         1              2         1            2
: 1. FISSION GASES AR41             CI          0.000E+00    0.000E+00  0.000E+00    0.000E+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    0.000E+00 KR87             CI          0.000E+00    0.000E+00  0.000E+00    L.000E+00 KR88             CI          0.000E+00    0.000E+00  0.000E+00  I 0.000E+00 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           CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 XE133            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 XE135M                                                                          )
CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00     '
XW135            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00     ,
XE137            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00     I XE138            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 UNIDENT.         CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00     i TOTAL FOR PERIOD           CI (ABOVE)                      0.000E+00    0.000E+00  0.000E+00    0.000E+00 l
l

EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - GROUND LEVEL RELEASE RELEASE POINT:     2 (MAIN STEAM LINE)
CONTINUOUS MODE           BATCH MODE NUCLIDES         UNITS         QUARTER         QUARTER  QUARTER      QUARTER RELEASED                           1              2         1            2
: 2. 10 DINES I131               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 I133               CI          0.00GS+00    0.000E+00  0.000E+00    0.000E+00 I135               CI          0.0002+00    0.000E+00  0.000E+00    0.000E+00 TOTAL FOR PERIOD             CI (ABOVE)                        0.000E+00    0.000E+00  0.000E+00    0.000E+00
: 3. PARTICULATES Cl4                CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 CR51               CI         0.000'd400    0.000E+00  0.000E+00    0.000E+00 MN54               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 FE59               CI         0.000E+00     0.000F+00  0.000E+00    0.000E+00 C058               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 C060               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 ZN65               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00
_SR89                CI          0.000E+00    0.000E+00  0.000E+09    0.000E+00 SR90               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 ZR95               CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 SB124              CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 CS134              CI   ,
0.000E+00    0.000E+00  0.000E+00    0.000E+00 CS136              CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 CS137              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 CE141              CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 CE144              CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 UNIDENT            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 TOTAL FOR PERIOD             CI (ABOVE)                       0.000E+00     0.000E+00  0.000E+00    0.000E+00 EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - GROUND LEVEL RELEASE RELEASE POINT:    3 (CONDENSER AIR REMOVAL)
CONTINUOUS MODE           BATCH HODE        I NUCLIDES        UNITS         QUARTER         QUARTER  QUARTER      QUARTER RELEASED                          1              2         1            2
: 1. FISSION GASES AR41               CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 KR83M              CI         0.000E+00    0.000E''O  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    0.000E+00 KR87               CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 KR88               CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 ,
KR89               CI         0.000E+00    0.000E+00  0.000E+00    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 j i    XE133M             CI         0.000E+00    0.000E+00  0.000E+00    0 000E+00  l XE133              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 i XE135M             CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 XW135              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00  l XE137              CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 XE138                                                                        l CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 UNIDENT.           CI         0.000E+00    0.000E+00  0.000E+00    0.000E+00 TOTAL FOR PERIOD             CI (ABOVE)                       0.000E+00    0.000E+00  0.000E+00    0.000E+00 P
EFFLUENT AND WASTE DISPOSAL REPORT GASEOUS EFFLUENTS - GROUND LEVEL RELEASE RELEASE POINT:     3 (CONDENSER AIR REMOVAL)
COMTINUOUS HODE               BATCH MODE NUCLIDES         UNITS         l  QUARTER         QUARTER       QUARTER      QUARTER
_ RELEASED                       i      1                   2        1            2
: 2. IODINES Il31               CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 Il33               CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 I135               CI            0.000E+00    0.000E+00      0.000E+G.-   0.000E+00 TOTAL FOR PERIOD              CI (ABOVE)                          0.000E+00    0.000E400      0.000E+00    0.000E+00
: 3. PARTICULATES C14                 CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 CRS1                CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 MN54                CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 FES9                CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 C058                CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 C060                CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 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    0.000E+00      0.000E+00    0.000E+00 SB124               CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 CS134               CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 CS136               CI            0.000E+00    0.000E+00      0.000E+00    0.000E+00 CS137               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 CE141               CI             0.000E+00    0.000E+00      0.000E+00    0.000E+00 CE144               CI             0.000E+00    0.000E+00      0.000E+00    0.000E+00 UNIDENT             CI             0.000E+00    0.000E+00      0.000E+00    0.000E+00 TOTAL FOR PERIOD              CI (ABOVE)                           0.000E+00    0.000E+00      0.000E+00    0.000E+00_

l l
l EFFLUENT AND WASTE DISPOSAL REPORT                                               I LIQUID EFFLUENTS -- SUMMATION OF ALL RELEASES UNITS      QUARTER       QUARTER    EST. TOTAL 1             2      ERROR, %-
A. FISSION AND ACTIVATION PRODUCTS
: 1. ' TOTAL RELEASE (EXCL. CI                                 0.500E+01 TRIT., GASES, ALPHA)             0.000E+00    0.122E+00
: 2. AVERAGE DILUTED        UCI/ML CONC. DURING PERIOD              0.000E+00    0.122E-07
: 3.      PERCENT OF            %
APPLICABLE LIMIT                 0.000E+00    0.609E+00 B. TRITIUM
: 1. TOTAL RELEASE          CI        0.000E+00    0.117+02    0.5 OE+01    '
l
: 2. AVERAGE DILUTED        UCI/SEC CONC. DURING PERIOD              0.000E+00    0.117E-05
: 3.      PERCENT OF            I APPLICABLE LIMIT                 0.000E+00    0.389E-01 C. DISSOLVED AND ENTRAINED GASES
: 1. TOTAL RELEASE          CI                                 0.500E+01     ,
0.000E+00    0.857E-03
: 2. AVERAGE DILUTED        UCI/SEC CONC. DURING PERIOD              0.000E+00    0.857E-10                l
: 3. PERCENT OF             %
APPLICABLE LIMIT                 0.000E+00    0.429E-04 D. GROSS ALPHA RADIOACTIVITY a
l  1. TOTAL RELEASE            l CI      l 0.000E+00 1 0.000E+00 l 0.500E+01   l l
E. VOLUME WASTE RELEASED      LITERS                                            l (PRIOR TO DILUTION)               0.163E+07    0.370E+07   0.800E-01 F. VOLUME DILUTION WATER USED DURING PERIOD                                                        {
Liters    0.100E+11    0.100E+11   0.100E+02     l I
I
"~. FLUENT AND WASTE DISPOSAL REPORT I.IQUID EFFLUENTS FOR RELEASE POINT:    2 (LIQUID WASTE)
CONTINUOUS MODE             BATCH MODE NUCLIDES       UNITS          QUARTER         QUARTER    QUARTER      QUARTER                                               I RELEASED                          1               7          1                                   2 i
H3               CI           0.000E+00     0.000E+00   0.000E+00    0.ll7E+02                                              {
C14              CI           0.000E+00     0.000E+00   0.000E+00    0.000E+00                                              l NA24             CI           0.000E+00    0.000E+00    0.000E+00    0.575E-05 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    0.175E-01 MN54             CI           0.000E+00     0.000E+00   0.000E+00    0.245E-02 MN56             CI           0.000E+00     0.000E+00   0.000E+00    0.000E+00 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    0.811E-03 C058             CI           0.000E+00    0.000E+00    0.000E+00    0.918E-01 C060             cf           0.000E+C0    0.000E+00 l
0.000E+00    0.200E-02 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                                             J 2N65             CI           0.000E+00    0.000E+00    0.000E+00    0.000E+00 ZN69             CI           0.000E+00    0.000E400    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             CI           0.000E+00    0.000E+00    0.000E+00    0.000E+00                                             i l
EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT:   2 (LIQUID WASTE)
CONTINUOUS MODE            BATCH MODE
* NUCLIDES       UNITS         QUARTER          QUARTER  QUARTER      QUARTER RELEASED                         1               2         1            2 RB86             CI          0.000E+00     0.000E+00  0.000E+00    0.000E+00 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 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 SR91             CI          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              CI          6.000E+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   0.000E+00    0.353E-02 ZR97             CI          0.000E+00    0.000E+00   0.000E+00    0.000E+00 NB95             CI          0.000E+00    0.000E+00   0.000E+00    0.333E-02 M099             CI          0.000E+00    0.000E+00   0.000E+00    0.000E+00 TC99M            CI          0.000E+00    0.000E+00   0.000E+00    0.194E-04 TC101            CI          0.000E+00    0.000E+00   0.000E+00    0.000E+00 l
i l
l l                                                                                                                        l

EFFLUENT AND VASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT:   2 (LIQUID WASTE)
CONTINUOUS HODE           BATCH MODE NUCLIDES       UNITS         QUARTER         QUARTER  QUARTER      QUARTER RELEASED                         1               2        1            2 RU103            CI          0.000E+00     0.000E+00 0.000E+00    0.000E+00 RU105            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 RU106            CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 AG110M           CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 TE125M           CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 TE127M           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 TEi29M           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  0.000E>00    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          0.000E+00    0.000E+00  0.000E+00    0.000E+00 Il31             CI          0.000E+00    0.000E+00  0.000E+00    0.696E-04 I132             CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 I133             CI          0.000E+00    0.000E+00  0.000E+00    0.214E-04 I134             CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 I135             CI          0.000E+00    0.000F+00  0.000E+00    0.000E+00 l
EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT:   2 (LIQUID WASTE)
CONTINUOUS HODE            BATCH MODE NUCLIDES       UdITS         QUARTER          QUARTER  QUARTER      QUARTER RELEASED                         1               2         1            2 LIQUID EFFLUENTS CS134            CI          0.000E+00     0.000E+00  0.000E+00    0.000E+00 CS136            CI          0.000E+00     0.000E+00  0.000E+00    0.000E+00 CS137            CI          0.000E+00     0.000E+00  0.000E+00    0.000E+00 CS138           1I           0.000E+00    0.000E+00   0.000E+00    0.000E+00 BA139            CI          0.000E+00     0.000E+00  0.000E+00    0.0GOE+00 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    0.000E+00 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    0.000E+00 PR143            CI          0.000E+00    0.000E+00   0.000E+00    0.000E+00 PR1,44           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 NP239            CI          0.000E+00    0.000E+00   0.000E+00    0.000E+00 i
i l
i I
                                                                              -I I
i EFFLUENT AND WASTE DISPOSAL REPORT LIQUID EFFLUENTS FOR RELEASE POINT:   2 (LIQUID WASTE)
CONTINUOUS MODE-          BATCH MODE NUCLIDES      UNITS         QUARTER         QUARTER  QUARTER. QUARTER    I RELEASED                        1              2         1            2 LIQUID EFFLUENTS
   . LIQ                                                                       <
(unident.)       CI          0.000E+00    0.000E+00  0.000E+00    0.236E-03 TOTAL FOR PERIOD          CI (ABOVE)                     0.000E+00    0.000E+00  0.000E+00    0.118E+02 I
XE-133          CI          0.000E+00    0.100E-25                           )
0.000E+00    0.857E-03   )
XE-135          CI          0.000E+00    0.000E+00  0.000E+00    0.000E+00 l
l 1
I i
1 i
l I
1

EFFLUENT AND WASTE DISPOSAL REPORT FROM 3/8/88 0:00 TO 6/30/88 23:00 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS No solid waste or irradiated fuel shipments were made during this reporting period.
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                                H           0              N/A SLUDGES, EVAPORATOR                                 CI          O BOTTOMS, ETC.
B. DRY COMPRESSIBLE WASTE, 3
CONTAMINATED EQUIP., ETC.                           M           0              N/A CI          O C. IRRADIATED COMPONENTS' 3
CONTROL RODS, ETC.                                 M            0              N/A CI           O D. OTHER 3
CI           O
: 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)
A.                1                                  %
2                                   %
3                                   1 4                                   %
5                                   %
6                                   %
B.               I                                   %
2                                   %
3                                   %
4                                   %
5                                   %
6                                   %
C.               1                                   %
2                                   %
3                                   %
4                                   %
5                                   %
6                                   %
D.               1                                   %
2                                   %
3                                   %
4                                   %
5                                   %
6                                   %
                                                             .. -    -         - _ _ - - _ . . - ,    . _ = _ _ - , _ . .    -
                                                                       ,,        , , ~ . . - - - - -  .--

I I
l EFFLUENT AND WASTE DISPOSAL REPORT FROM 3/8/88 0:00 TO 6/30/88 23:00 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
: 3. SOLID WASTE DISPOSITION (NOT IRRADIATED FUEL)
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION       DESTINATION O             SHIP                       N/A 0            AIR
: 4. CLASS OF SOLID WASTE N/A
: 5. TYPE OF CONTAINERS USED FOR SHIPl!ENT N/A
: 6. SOLIDIFICATION AGENT N/A B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
NUhBER OF SHIPMENTS MODE OF TRANSPORTATION       DESTINATION 0            SHIP                        N/A                                 >
0            AIR

v APPENDIX A Optional Use of Filter Elements in Influe'nt to Waste Monitor Tanks
: a. Attachment 1 - A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59.
: b. Attachment 2 - A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
: c. Attachment 3 - Documentation of the fact that the change was reviewed and approved by the Plant Operations Review Committee (PORC).
: d. Attachment 4 - Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.
: e. Attachment 5 - An estimate of the exposure to plant personnel as a result of the change,
: f. Attachment 6 - An evaluation of the change, which shows the predicted release of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that dif f er from those previously predicted in the License application and amendments.
: g. Attachment 7 - An evaluation of the change, which shows the expected maximum exposure to a member of the public in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments.
: h. Attachment 8 - 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.
i j
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APPENDIX A, ATTACHMENT 1 Optienal Use of Filter Elements in Influent to Waste Monitor Tanks l
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q.
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                                        ,
10CFR50.59 DETERMINATION REVIEW FORM                                                       !
b' #                                                                                                        =ase     / oi _z_
Cr q'"at'"9 Docueee %o             [CA /VD, //AM-8/.$V/ o . s,on           e      '.:         0 t use      .
LWPS               f?lraes Crec. oce ; , Proceev,4 (d P' ant Voc f<at>on              ( l Otrer CseCa ore i e Ouair, Aerated              t/Nonovate Aerated 1
Oces fPe sveiect Of ins rev.e* mvcive a charge to the f4CIsfy as 3escriCed n the FSARS
[                                       g j g            ( dyes        i# No BEC Cogmzant Engr S.gnarwre                                   Date                               l 2 Coes the !        bj     0t   $ rev. involve a Chan$e to the pt0CedVfes as desCf' bed 4 the FSAAS es     s No 4tt1C     2        fl>LA           o                          J 2feb R&V I O                                                r-gw<swes,Csse>eEng,s4at,e cate l
3 Oces the subject of this review ConovCt rests andor esperiments not described c the FSARS l
f'h /                 _
etAc,Jer              '''"         'h*     l BEC Cogn tant Engr S.geature                               ' Date 4     Coos :ee      ei r ef !Ns <es
* requis a Change to me TeCrwcal Specificaters'
                                  \           )      '
i
* Yes     i     No 1                o                             p h6 R8r yumes:Fs.eie Eng, ss raru,e.                                      care NC fe t 't!CCose fC ;ee 11) of more of Qwestices 1 :hru J 2re affirmative. the C'Q**.*3n! E*y "ee' r* P C'Cv'Je fecho Cal justification for tPG Droposed Change (s) and 3el'neate (Pe seC:'onts: Cl **e :J'+'s APais's AepCt1 and or Plant Techn<ai SceC fcatents; affected by the ot:CCied ceaege s'
                .u s fil O                     CaOCe 'or P*CCesed Change 5 //.S $ /A'/(9i /S f & /,(6 ) 7"O ffGW6 $$/N/AlY N Y                                                  S$
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ArTAcHu ant 1 as ssem es, NUMBER                     R EY.           '
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                    IP-3.200 N O.
1 INTEILDEPARTMENTAL PROCEDUR.ES                                                                             J 10CFR50.59 EVALUATIONS                                      PAGE                OF EFFECTIVE                                  !
teATE       11-20-87 l
ATTACHMENT IP-3.20o-3 lOCTR50.59 EVALUATION FORM - TYPICAL (Page 1 of 2)
DESCRIPTION Unit #
h PROCEDURE            h    PLANT MODIFICATION                     l[l     OTHER ORIGINATING DOCUMENT NO.      bk          . NbM d/$4l                                     REY.NO.
f TITLE       llU h 5      NilYSAS                                                                                  __
DESCRIPTION $ flo            YO ?YlD 1/@Sb?EV$82$ l YGYoY                                                                  ,
           %fc;2 -blow / .47Y $ SsHb / d7$2 -/96~4c 42 Rev. C . "73e NWaffek q pose elopw>di ksNa the . kite > luu.oAe1                               ~
oA de Mb yr LHsy
           ,6 CPRmCt* filks k odoEnl. "
z.u        an Does the subject of this revien involve a change to the facility as                                           _
described in the safety analysis report?
h        l_l Does the subject of this review involve a change to the procedures as                                         _
described in the safety analysis report?                                                                    l ., l Does the subject of this review propose the conduct of tests or                                      .,                      )
experiments not described in the safety analysis report?                                            l_l   h                  ;
Does the subject of this review require a change to the Plant                                        _        ...
Technical Specifications'                                                                      . l ,l     %                   l Does the proposed change, although not described in the safety                                                               )
analysis report, affect items or activities that are described                                       _                       )
in the safety analysis report?                                                                   l_l      h                  I (This form, when completed, shall be retained for the life of the plant.)
: b. , . .. .
            -ao suma ns, SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                  "EO/
INTERDEPARTMENTAL PROCEDURES IP-3.20Q         1 PAGE 37     OF   41 10CTR50.59 EVALUATIONS EFFECTIVE DATE 11-20-87 AIIf CHMENT IP-3.2OO-3 10CFR50.59 EVALUATION FORM - TYPICAL
*                                                   (Page 2 of 2)
If. any ansver is af firmative, perform an Unreviewed Safety Question evaluation.
If all answers are negative, no Unreviewed Safety Question evaluation is required.
Documentation of this review must be retained with the review package for the duration of the station license.
Note:    "Safety analysis report" includes the FSAR, safety analyses su*omitted to the NRC in support of their review of the application for an operating license and subsequent amendments to the operating license and other license commitments made to the NRC.
Documents Reviewed:
BEC        Rup        than.9e_ Re,vesY Leo          ~ No    I.z:u
                                         . n .         _
Prepared by:                        12 0         -       / SA k         lV((((*
Criginator                       Date           1 Concurrence                                        N    / L3           /id        4 Department Manager                       Date

I u.....,
I SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                                                    "NO' ' . '
gy.fERDE'PARNE PROCEDURES                                                IP-3.20Q               1           1 10CFR50 59 ETALUATIONS                                             PAGE 3I      OF         41 EFFECTIVE 11-20-87 A'l fACMMBT IP-3. 200-4                                                               l UNREVIEVED SAFETY OUESTION EVALUATION F0 H (Page 1 of 4)
Unreviewed Safety Question Evaluation # N ' h b d 9                                    Date Assigned h 3!8 [
h          Procedure Change                  b          Plant Modification                     l  l     Other BE.C. FSA/R Chaye Reg. 4gy 4 M 2 4.
Originating Document:                     NC[h M. OOM-h/64I                                       Rev. #      db rrit.Es               La) PS                 P= tere R s i
DESCRIPTICES          S HD                 $ ?$lb 7A3$9Y9h8$ l k Y e M d
* Y D D C.itnF9 k 9dsu-6i&f I- A ry 4 ea+ iArp -t9s Ec 4 e nev c "7% >hrk//afu;n q Fl/br elements 'msids de ,4/ke kusma s a c ti,e Pb7 LHS T $
CPRWC.~r C-llters is optiona).
be{eA MSAR refer eses t Fb7)
LHST d CPRLuc.T 4' hies A.      1. Does the subject of this evaluation 1
increase the probability of occurrence or the consequences of an accident or salfunction of equipment important to safety                                   _
previously evaluated in the safety analysis                                   l_l YES        h NO report?
e,,es, Then see no aec.idonti evalueb1 in +he PSAR whkk verwre tha Liewd M2<tMes.sskey Sv'il5vt i                              <                                       -           -
PbT. LHST ot- CPROJC T SIUans to be o,cerable .                                                                                   j ThmN [,cre               tks's dees. neb increase +4e oiNbsOk eG                                           <                     .
_0CQLhenut* e OP                 .L L M $d''tRBHC2 5 el- GM e2.                           tdebtf er AfEhuHh&%
: e. en, ;oned in,wLa d.swet.v ,oikaush cuLael L 4 b4M .
(This form, when completed, shall be retained for the duration of the license.)

N: '
m u.m o SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                         NO INTEIDEPARTMENTAL PROCEDURES                          IP-3.200         1 10CF150.59 EVALUATION 3                          PAGE 3I     0F  41 EFFECTIVE DATE 11-20-87 ATTACNwrMT IP-3.200-4               Evaluation No. k       N UNREVIEVED SAFETT GUESTION EVALUATION FOR.M
,,                                                (Page 2 of 4)
: 2. Does the subject of this evaluation create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis           .,
report?
l_l YEs          h No Basess b e L WS MO.Q_L HS T e t. C PRiilc7* S/Mi-s de uit 6.act ae sw. o,,embllk, a, vLa resck. iw.
           <%s i+ o > c u', de a hou-u, t ,oieveat m ancos, L & J
           }'E l83.% 42. A TG9dlcA'&Yi /t              W kt* 9 kVt/*b n Men                kdte*bW*@
I                     r 0$$       $f$f $ Y$ HDY CMN e Wde ,6B.$$/               /
                                                                            $0f'MM M $$Qf
: d. - a di.%.f , , .e +ln anv ,owvjoubs        -              -
evz/umb) &
A t=sn.
: 3. Does the subject of this evaluation reduce the margin of safety as defined in the basis for any          _
technical specification?                               l ,,l      YES    b NO sasess    Th e UlfPS /=b'r,1-,95r en CPelDc7~ MI/ki.s do nif'           .
las'ih~ +he 5 irfe. densk ls              el-1le Peachh not- de 1bev ,nnevth e, abewan t smatuusutrolla seierse os m&x&k kde 69/MMMk ?WY2bMS                        Pd9WPe i          3Y 6.N. ueMYS        -ft10nt Yl1e ND[
l.N$T 8kti CPRttt'*1~ Je set %tL TE a nieut%rek inalt aisLsitea*>ll;r><ce.
Ac h tn19k DNhr Ye~ M'ldadd* W                e RMU retHHenf~ lbePe' Acte Yk/ /
does, ah ,-eAxe de maram ss- sase'Iv as died in de besis  '
p r~
* n y Te e k k i St e O 5 c
* Y N Notes "Safety analysis report" includes the FSAR, safety analyss3 submitted to the NRC in support of their review of the application for an operating license and subsequent amendments to the operating license, and other license coenitments made to the NRC,

k) .    .
l
                    .ao     . s e s, j
!                    SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                  "'NO[
INTE1 DEPARTMENTAL PROCEDURES 17-3.20Q        1 10CFR50.59 EVALUATIONS                      PAGE N     OF 41 EFFECTIVE
                                                                                      *I" 11-20-87              )
ATTACNMENT IP-3.200-4           Evaluation No.         2.f  :
UNEEVIEVED SAFETY OUEETION EVALUATION FORM                              l (Page 3 of 4) l B. 1.               All of the above questions were answered 50, therefore the originating document does not involve an unreviewed safety question.
l
: 2.               One or more of the above questions were marked YES. therefore the originating document involves an unreviewed safety question. The originating document, as presented, shell NOT be implemented without prior approval of the NRC. Provide a            1 recommendation for disposition of the unreviewed safety question below.
RECOMMENDED DISPOSITICN                                                           1 1   <        hA l PREPARED BY:           Nd       4       Ah              / M2 ke          lkT I    ~ '7diIhR '                             DATE                   I REYIEVED BY              k                     b"       /                b COGNIZANT MAN GER                     DATE                   l APPROVED BY             (LDA                            /   C3- bN PLANTMANAGEk                        DATE REMARKS:
i
                                            .m 1
                                                                                                                )

APPENDIX A, ATTACHMENT 2 Optional Use of Filter Elements in Influent to Waste Monitor Tanks The Liquid Waste Processing System collects and processes radioactive liquid waste generated during plant operation and reduces radioactivity and chemical content to acceptable levels for discharge or recycling.
The Liquid Waste Processing System consists of the Waste Holdup Tank, which collects radioactive liquid from the Reactor Coolant Drain Tank and the Reactor Containment Building sumps, the Floor Drain Tank, which collects 11gulds from      s floor drains in the Mechanical Auxiliary Building, and the Condensate Polishing    '
Regenerative Waste Collection Tank, which collects radioactive laboratory          l drains, and serves as an alternate tank for floor drains. Also included in         l this system is the Laundry and Hot Shower Tank, which collects water from the hot shower facility.
These tanks are all equipped with eductors to ensure proper mixing prior to        l i
transfer. The liquid collected in these tanks may be processed in accordance    l with the Process Control Program.      This program selects the optimum processing mode, filtration, domineralization, evaporation, or a combination of the three. 1 After processing by one of these methods, the liquid is then collected in one of six Waste Monitor Tanks and analyzed prior to discharge.
The Liquid Waste Processing System waste evaporator also has the capability to     j produce reactor grade distillate which is collected in the Waste Evaporator Condensate Tank. This dist111 ate may also be processed as radioactive waste       ,
1 and discharged. Concentrates from the waste evaporator are processed in the        l Solid Wa.te Processing System. Any gaseous effluents produced are processed by     i the Gaseous Waste Processing System.                                               '
l The filters that were affected by this change were the Floor Drain Tank Filter, the Condensate Polishing Regenerative Waste Collection Tank Filter, and the Laundry and Hot Shower Tank filter.
These filters are downstream of their respective tank pumps and allow most of the particulate to be removed prior to processing via demineralization or evaporation. Early in plant life, filtration is frequently not necessary, vaste streams can be sent directly to the Waste Monitor Tanke prior to discharge, or processed via domineralization.
The ability to process waste streams with or without filtration will allow a much greater flexibility in processing waste early in plant life.
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APPENDIX A, ATTACHMENT 3 Optional Use of Filter Elements in Influent to Waste Monitor Tanks I

y b                                                                                       Anacasur 3                                                 l Plant Operations Review Committee                                                 OPGP03-2A-0004     {
Rev. 6 Page 15 of 15
* PORC REVIEW COVER SHIET                                              , /,
OPGP03-ZA-0004-1
(                                           (Page 1 of 1)
           $ ( Originating Document No.              FCR M /MN dM41                      Revision No. _ d                                     _
TITLE $(1)PS        Pi/Mnc                                                                                                   \
l The    PORC has reviewed this item and has determined that (check as appropriate):                                                                                                               !
It      does
                                      /does NOT involve an UNREVIEVED SAFETY QUESTION.
It,_ does oss NOT require a change to the Technical Specifications or the Operating License.
It      does and other licensingoesdocuments.
NOT deviate from the cosualtaents made in the FSAR, SER, It       does does M adversely impact plant nuclear safety.                                          ,
it _ does      !doesNOTadverselyimpactthehealthandsafetyofplant personnel or'ths public.
It       does
                                     /does NOT requirt, further review by the NSRB, the NRC, or other indiviouals/ groups.         NSRB _ NRC                      other, specify below.
REMARKS l
The PORC recommends this item fore
              '! -        APPROYAL       DISAPPROYAL              OTHER                              PORC MEETING NO Completed by                                                                                          b
                -                                                             DATE_
PORC Secretary                                                                                            j s;
l This form, when completed, shall be retained in accordance w1Ith the retention requirements of the originating documen..                                                                                       )
l I
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                                                                                                                                  ,                 l l
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APPENDIX A, ATTACHMENT 4 i
Optional Use of Filter Elements in Influent to Waste Monitor Tanks The Liquid Waste Processing System collects radioactive waste from various sources and processes this waste for discharge or recycle. Several different modes of processing waste streams are available including filtration, dominera11zation, and waste evaporation, and combinationslof these three methods. The optimum processing method is selected in accordance with the Process Control Program. This program chooess methods based on solid content and radiochemistry of the selected waste stream.
i In many cases, the waste stream does not require any method of processing prior to discharge. Early in plant life, many of the waste streams have low   I radioactivity concentrations and may be sent directly to the Wtste Monitor         '
Tanks for discharge. In order to extend filter life and provide more flexibility in processing, it is now allowable to process with or_without filtration based on the characteristics of the waste stream. Changes were         3 I
made to the Safety Analysis Report and the applicable Piping and Instrumentation Diagrams in order to allow Chemical Operations the choice of whether or not to use filtration downstream of the Floor Drain Tank, Condensate Polishing Regenerative Waste Collection Tank, and the Laundry and Hot Shower Tank. These changes are attached along with an overall flow diagram of the Liquid Waste Processing System. Also attached is the Engineering Support Request response that explains Support Engineering reasoning for this change.
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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION
    .                                       IOCFR50.59 DETERMINATION REVIEW FORM                                                        ,
G                                                                                                           = age      / of 0, Siratieg Doev,ver' Sc fdn'&     AhWGG ff6Xff
                                                                  //a,   /.:7.e 4                me , s.on N:             8         _
T tue      i FSAR OMVt;6 fsduf.t7' Nd. /.o.? 6                                                _
crec.cret i p,oceev,e wf piant vedicat.on                    i i cire, creci ore i , ovase, n iated  e           id sonquaity a rated e
1 Oces tre suciect :t to.s ,ev en .nveive a enarge to the racihty as :ese, iced n tee FSAA' (dye $    1 1 No p
8EC Cogn. tant Eng, Sqnatu,e                                   Date                                 '
2 coes the tu         j      th $ ,ev-    involve a CP46ge to the p,0Cedu,el al d45C,'bec en the FS     i Yes
  ,q                            v - a cA /01 tu                do                          *1 M3 /MP
(          i i No o                              jagaeipoes. ween,,64eate,e caie a    oce, ire ,2 ect 1    oi nes ,e.,e. emne,i, aso, e.,., meni, eo, ee.c,,eed e ine FSAR$
gf                                           g                  i      Yes   iy/ No SEC Cog ^itant Eng, S9natv,e                                    Date a    OCe5 !Po Sul     oct ie ,ev'e,       ,eque,e a enange to the Techn* Cal Specificat<PSS h
(hJ Q}$         q                        2L            &W
                               -jss esoces.ere' Eng, S$raivre                                    caie w ie       t ,5cces, te :re m o, me,e or w est.ori i rn,v a a,e an ,mati,e. tre c:ge.unt E ; ree, , o.
0,cuce teche. cati vst,ficat,on to, tre o,coosed changelst and :enceate tre sect'omisi et te ia'e',
A Fa')l l Aepc,1 and C, Plant Techn. cal $ cec f<aton(Si 4Mected Dy the 0,:cesed charge Si i
1
                .ustaf caScr 'o, D*ccesed Change O.             7Nr.s !/fMcr6 /5 M61)!//4tCAD To PROV/k~ Rft/Bt&/7y /4' 7)/S* CPia<A7/0A/
O f s'7/6 L/4Wa) lyMN ffKsSfig/dy fff;zyj, 7p~t;gy,/ /pfpg4) yrs /67 3ys'fgsy /ygsysfm , ffg .5sc,nsA) y. 2 iS 4fpgcfgp 1

)
    . . -f-    ..
          @)                                  FSAR CHANGE REQUEST A      1. Of5CIPLINE
                                      @AN#4'd                     2. LOG NO.              /MS b      3. ORIGINATOR          f784/ 6 /44/                   4. DATE                J/'f/N8
: 5. THE LCT5 HA5 8EEN REVIEWED                       D YE5              MO
: 6. PRE 4PERATIONALTEST PROGRAM AFFECTED             D YE5              B'NO
: 7. SulMITTED 8Y(GROUP EG5)(DATE)     b                 -      MY S. AFFECTED SECTIONS OF FSAR (USE
* TO INDICATE SECTIONS CONTAINING LCT5 COMMITMENTS)
                        // p     777'/S fM!Stfx2 /\'ffk /C.Tf JdeECS?M$ AlL A M'Wf3/0M6
                                 /d Az'? P ll'/oe66 'WNG ^'a ^Wi.
i
: 9. DESCRIPTION OF CHANGE      fE6Te#4' A> 6E SE [#if INIli #M T ['V/#6
                  /S d f// Td R 6.V ,& & th ff/ M fftG S'b6 c'f C'WN ff fMC FCfflW Nft Z&fs:
                  /, MdB /-?t(q MatN 7dnt, ? LawDic'y' AnG /.NT J/i'h?A'                t     D/V< ,
J. Is's'.MsJd2 /NysifiMV d'cWCA'r41fttv/ /VAS76 atiZc 7ttvv' KW/i
                  '~Mi .5 (wentE t               Witi Ndse      5 'c c/J & /F Br[SG f/t icA'3 6F&aH&
: 10. JUSTIFICATION B f A 9tA w ri 7Ma oli ff Arf' sE RtTres C/>7?-wrL , Yuis                       (/wier;c:
ly/44. /kLayrs); f!G4Wsi/Tf AV !?*f Chb ^t'f M4' ff D'C .4g<;4/) H;4Sfc-r?<di.Sita'tj fyffiM , i#fA'd/3}' /'YPA'?)'4Vf/ ff'!ffM ffA'ffT'AfdWcf ,
O       11. DISCIPLINE REVIEW                                 REVIEW DUE DATE STARTUP            4N                          MECH.          N'N ARCH.              A/d                           NUC            b               =-
CONTROLS           AN                            PLANT DES.              d'M C/5                A/4                           P55G                   'W
  ,                 ELECT.            /V/7                           w555       _
4'd EQ               dN                             OTHER                 M/4
: 12. APPROVED 8Y                                                                      oste px Group w.)
: 13. APPROVED BY                                                                       o.te EDoo Chetig i
: 14. APPROVEDIY ma Cheitg )                                   o te O         is. **PaOviDiv               C/dl         (Pew t g l oV25/2 o te
: 16. DATE SUBMITTEDTO CLIENT:
m ues em                                                                         immic v %i

D..,
l STP FSAR he bulk of the radioactive liquids discharged by the Reactor Coolant Systen                         l (RCS) can be procer. sed and recycled by the Boron Recycle System (&RS).                 41         l Inputs into the LV?S from the BRS can be processed in the BRS prior to proces-sing in the LWPS. The capability exists to route this vaste to the condensate polishing regeneration vaste collection tank (CPRWCT) or floor drain tank (FDT) because of either unacceptable water chemistry or for crittua control                        <
purposes. This vaste is either off quality refueling water or off quality recycle holdup tank water. If the input is not processed in the BRS it will                        !
be processed in the LVPS and discharged.                                                      $3    i l
The LVPS is designed to monitor and release sufficient critiated water to con-trol tritium buildup in the plant.      Since the normal mode of the LWPS is pro-cesr. and discharge, there vill be no tritium buildup in the LVPS. The major-icy of other inputs to the LVPS cre normally lov activity; therefore, the bulk              D3 of the processing requirements for the LVPS are based on generally low activi-ty vastes.
39 The capability for handling evaporator concentrates as well is handling and storing spent demineralizer resins is also provided in the system.                                ~
i
                                                                                                        / '    l The capability exists to process high and lov total dissolved solida (TDS)               /          '
wastes from condensate polisher regeneration.       Both lov and high TDS wastes     ,
h3 can be discharged directly through the LVPS and the effluent radiation monitor to the CVS if processing is not required, High TDS wastes are touted to the i
CPRWCT and may be processed through the vaste evaporator and monitor tanks                          i prior to discharge to the CVS. Normally no LWPS processing is required.         LVES         $3     !
processing is only required in the case of primary to secondary leakage.                            '
Normal CPRV processing is in the neutralization basin.
Instrumentation and controls necesscry for the operation of the LVPS are lo-                        1 cated on a control board in the radvaste control room which is located within the Mechanical Auxiliary Building (MAB).                                                            l i
component locations are shown on Figure 1,2 26, Sheets 3 and 4, and Figure 1.2 38. Radioactive equipment is generally isolated in individual cubicles.             33 Process flow diagrams and piping and instrumen*ation diagrams (P& ids) are shown on Figures 11.2 1 through 11.2 12.                                                l39 11.2.2.1.1 Process and Equipment

== Description:==
he LWPS is provided to                         I collect and process BRS tritium control volume and non reactor grade liquid                           l vastes.      These include floor drains, equipment drains containing non reac-                       I tor grade water, laundry and hot shower drains, contaminated vastes from the                 l53 Condensate Polishing Regeneration System, and other non reactor grade sources,                       i Equipment in the LWPS includes the reactor coolant drain tank (RCDT), the RCDT pumps and HX, the vaste holdup tank (VHT), VHT filter, VHT pumps, WHT purification demineralizer and filter and two vaste evaporator condensate                39 l53 tanks (WECT). A list of equipment is given in Table 11.2 3. The VHT can be processed through either the LVPS waste evaporator or the BRS recycle evapora-tor. The BRS recycle evaporator is used only in the event the LVPS waste evaporator is not operational. Additional equipment includes a FDT and f!!-                          I
         +ee, laundry and hot shower tank (LHST) ed filter, CPRWCT =d film, vaste evaporator, vaste evaporator condensate (VEC) demineralizer and strainer, and six veste monitor tanks (VMT) and pumps.
11.2 2                      Amendment 53

  ..S.'.
      , . .                                         STP FSAR The VECTs provide extra storage capacity for the VMTs and can be discharged through the effluent radiation monito: to the CVS, Additional surge capacity p            is provided by two surge tanks located in the Fuel Handling Building (nib).         53 V           Processing consists of any of the following modes:
j
: 1. Filtration, evaporation, and domineralization 39
: 2. Filtration and evaporation
: 3. Filtration and desineralization 4     Filtration                                                                      53    <
{
The processing mode is determined by the quality of the liquid to be proces-                !
sed. The normal processing mode is expected to be one of the following                      I combinations: filtration, filtration and/or evaporation or filtration,                   55 evaporation and/or desineralization.
The vaste evaporator is a forced circulation crystallizer with a 30 gal / min          53    l distillate processing flovrate. In addition this evaporator can also be used                 l as a backup to the BRS recycle evaporator.                                                   )
l The LVPS waste evaporator is designed to operate on a batch basis and the                    {
contents are concentrated to opproximately 12 ve percent boric acid or 25 vt                  I percent sodium sulphate.
The vaste evaporator must be operated at a basic pH. Therefore the pH of the feed is adjusted as needed prior to transfer into the evaporator. Feed enters the discharge piping of the recirculation pump, is heated in the heating cle-ment and circulated through the vapor body. When the desired concentration is        39 achieved, as indicated by the evaporator density instrumentation, the concen-trate is pumped to the concentrate storage tank for eventual solidification' or directly to solidification bypassing the tanks.                                      53 Evaporator distillate is condensed and cooled in the distillate condenser and subcooler skid and further treated by the vaste evaporator condensate demin-eralizer or VHT purification demineralizer before transfer to one of the vaste         h3 monitor tanks.
The two largest sources of liquid volume to the LVPS are the Condensate Pol-l ishing System regeneration vaste and the equipment floor drains. The equip-                  '
mint floor drains represents a relatively continuous source to the LVPS where-as the condensate polishing system regeneration vaste is an infrequent high volume, short duration, batch source. he Condensate Polishing System regeneration vaste is a source to the LVPS only duritig periods of off normal operations when there is above normal primary to secondary leakage, or exces-sive fuel defects. At these times t.he regeneration vaste is directed to the CPRVCT as discussed in Section 10.4.6.2: during these periods the equipment and floor drains are directed to the FDT. Processing of this vaste in the CPRVCT is identical to the processing specified for vaste in the FDT. The system also provides the capability to discharge the3 condensate polishing regernation vaste 4rectly to the CVS if processing is not required.
(MW RM 7knMwMf MD .+e7 J4 woc ;%n dyp TC Laundry and hot shover orains are normally filtere: n.c-released. However,
  \         the vaste evaporator is capable of processing the laundry and hot shower vaste after addition of an antifoaming agent, if treatment of these vastes is requir-ed prior to their release.
11.2 3                      Amendment 55

[...~
                                                                                                      'j STP FSAR The RCDT collects deaerated, critiated leakoffs from inside the Containment         l39 and the contents are transferred by ^5 RCDT pumps through the RCDT heat exchanger (for cooling to less than 130*F) to the VHT. For the normal oper-ating mode, a level band is maintained automatically in the RCDT and the              39 system requires no operator action. In addition, the RCDT contents can be                      i transferred directly to the BRS for processing-                                       39 11.2.2.3.1.2 Processinz operation Inputs to the LWPS are segregated                    I according to their chemical makeup: detergent wastes are routed to the MST,                     l Condensate Polishing System contaminated regeneration vastes are routed to the CPRVCT, and sumps and gravity drains are routed to the FDT.
Three parallel modes of operation are available in the LVPS:
: 1.      High and low TDS waste streams from the Condensate Polishing System                     i demineralizer regeneration are collected in the CPRVCT or FTT. The regenerants are processed through the CP"""' " "T fil4ew waste                          l i
evaporator, and/or demineralizers, filters and sent to the VECTs or kHTs.
Discharge is to the CWS; the effluent radiation monitor is used to verify            f cceeptable activity levels. If the activity exceeds the setpoint, the             /'
flow is diverted back to the discharging tank for re processing. During          53 operation with no primary to secondary leakage, CPRV regenerants can be       39 discharged directly to the CVS using the LVPS discharge header and effluent radiation monitor. The normal flow path for CPRV is to the netralization basin. (See Section 10.4.6.)
: 2. MAB floor drains and contents of the RCDT may be processed through the kHT and filter. C;pability exists to process the low TDS waste and M*J floor drains in parallel. MAB floor drains are sent to the FDT and dF cleccSMr.
O               processed th'ough the auxiliary demineralizer, the VECD, and the filter.
: 3. The contents of the MST are normally transferred to a vaste monitor tank (kVT)-th = gh th: MST filt a after sampling. If sampling results show       53 high radioactivity concentrations, the MST contents can be processed through the waste evaporator after addition of an antifoaming agent. The contents of the FDT and CPRVCT can be transferred directly to the kHT,       39 processed through the vaste evaporator and the LVPS AD and VEC                         o demineralizers and VEC filter. The distillate from the vaste evaporator is routed to the kHTs or VECTs.
The contents of the kHTs are discharged to the CVS after sampling. A discharge permit will be issued for each release. The water being dis,      l2    53 charged from the LVPS to the CVS is monitored for radioactivity level.
In the event a higher radioactivity level than set is reached, the three way valve in the discharge line will divert the flow back to the kHT being discharged. The contents of the kHT: can be recirculated           39 through the auxiliary desineralizer and strainer if additional procassing is required.
O l'. 2 8                       Amendment 53

l
        <"*                                                  STP FSAR                                          l TABLE 11.2 3 (Continued)
EQUIPMENT PRINCIPAL DESIGN PARAMETERS O)
Special features:        Cartridge replacement accomplished by remote handling system. Replacement criteria of either high differential          l
,                                           pressure or time in service.                                  $3 Materials:
Housing: SS Filter element:     EICF Laundry and Hot Shower Tank Filter i
Function:     Removal of suspended sclids from contents of DIST.                           i Number:     1                                                                              1 Type:    Cartridge
                  . Design pressure, psi:          150 Design temperature, 'F:        200 Design flow, gal / min:        150                                                         i or et desia,u flew (cleerd psi; f
e                                              l39 J               M:ention;      ^0; reten: :n f:: p::1:1:: 5 zi::: : er larger-                       l2 l
Special features:      Cartridge replacement accomplished by remote handling              l system. Replacement criteria of either high differential        l pressure or time in service.                                        ;
l53
((CML    ,WCTE s NC AV6C 6/WA'SGE Mf AG ifbt'al'dD f@bf 7 ppg Fizyg,q
                                     @unt, if Rt747;cy a ,w,- gg,y g 74 py,,              -                  -
H:u:ing:    ES    PhtGKW(y Cp ;r,4yz (gyggy3 '                             ,
                                  - Filter :1:::nt:     5:CF Floor Drain Tank Filter                                                                   .
l Function-     Removal of suspended solids from contents of FDT.                            '
Number:     1 Type:    Cartridge Design pressure, psig:         150 Design temperature, 'F:        200 Design flow, gal / min:        150 11,2 31                       Amendment 53       ,

)
      < ** a                                                  STP FSAR TABLE 11.2 3 (Continued)
  #9                                         EQUIPMENT PRINCIPAL DESIGN PARAMETERS
  %.)
             -?P et d::ign f1:r ':1: n), p:1-               !
R:tenti:r-          99t ::tentier fer prti:le: 5 r!:rene er 1 r;; r Special features:             Cartridge replacement accomplished by remote handling system, Replacement criteria of either high differential pressure or time in service.
u_.__,_,         ,
Efl</N iYC7L=< &c~ R ffR f M M/Aff AM)' B6 AM wlyd
             ~ ' ' " ' ' ' ' '
W 7k/ /7/7f,e AhdMy /A; i y/7,t'474 /s /g:,7-
                                   -:w m g;     ::    W"'t'e RA' ms PadPM Mecesw4 C,r rgz
                                  = Filter :1:::r--     E!CF NMTS .
Vaste Holdup Tank Purification Demineralizer Filter Function:          Collection of resin fines from VHT purification demineralizer.
Number:          1 Type:        Cartridge Design pressure, psig:              1%
Design temperature, 'F:              200 Design flow, gal / min:              150 AP at design flow (clean), psi:              5 Retention:           98% retention for particles 5 mi rons or larger Special features:             Cartridge replacement accomplished by remote handling system. Replacement criteria of ei*her high differential pressure time in service.
Materials:
l Housing:    SS                                                       )
Filter elements:     EICF                                            ;
Condensate Polishing Regeneration Vaste Collection Tank Filter Function: Removal of suspended solids from contents of CPRVCT.
Number:          1 Type:        Cartridge l
Design pressure, psi:                150 1
i l
11,2 32                     Amendment 53  )
l 1

i  . . . .
l
        <  a.   .                                          STP FSAA TABLE 11.2 3 (Continued)                                  I EQUIPMENT PRINCIPAL DESIGN PARAMETERS 1
Design temperature, 'F:       200                                                         '
1 I
Design flow, gal / min:       150 39    !
                  !.? = i ;ign flew 'clesa), p;i;        5 P.:tentier-   ?!t retentier fer ;-rticl*= 5 e!cr^== ^* '- :-r                    l53    2 Special Features:      Cartridge replacement accomplished by remote handling system. Replacement criteria of either high differential           l pressure or time in service.                                 53
                ${?Q(YOf6* SS NffA OWBN& Mff 86 &l6D Rdbf NG R27tg                                          ;
Bew 5 Rtinfey /s ivor gg/im pg 7,,a p>gom                                 l 0..80M....fV. A%. OF 74NK gy,yrnyys, Tilter W;;nt:: -EICT l
STRAINERS                                                                                 ,
Pump Suction Strainers                                                                    i l
1 Function:    Duplex basket strainer to trap only large particles that could                '
cause pump damage and excessive filter loading. Strainers are       l39    l
(                            changed on high differential pressure and are not expected to contain significant concentrations of radioactivity. Are used on FDT, CPRVCT and IJIST pumps.
1 Number:    3                                                                              !
Type:    Basket Design temperature. 'F:       200 Design flow, gal / min:       100 AP at design flow (clean) psi:       0.5 l 39 Nominal rating, microns:       840 (40 mesh)
Materials:    SS 53 l
i O                                                                                                         l 1
11.2 33                   Amendment 53           l

P,, ,, ' o3com (09/a7)           soum 1txAs PROJECT ttretiac ctNtnAtNo sTAtow               i* PA E i ..si.
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ENGINEERING SUPPOM                                                  3. ESR NO. 4. REY. NO.
REQUEST                                                             /     A         ;
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                                                                                                   ? / 2.
: 9. REQUESTED COMPLEBON          10. REQUESTOR / PHONE /                11. SUPERM50R'S APPROVAL /
OATE                            ORGANIZATION                           DATE
           ~g ' g g 3 g .7 R C . D AELLEMB ACH l ~1oH                           ATQcuMOW 4                    i kiBo o / PEL                                                                       !
: 12. COMPONENT IDENTIFICATION (TAG NO. ETC.)
            'l R 2 0t N F R t o tA     FL ear' cmn Thuv., criu ,5 9                    14. ENC. SE' V Aodef
: 13. REFERENCE 00CUuENTS (INCLUDE REY. NO.)                                   1,5. RE/ ORC d #6fNeW 7R309F9OOO 9\                                                             16. DUE DATE C ee.. u 19 e 1
: 17. PROSLEM DESCRIPT10H Micacy F Ci P ' L TEP.           PLv6G          OF AFw            APPRoxl M TT3 "l'H E    loc G.c c G A.c o u ?,      op FL cW .
RECEIVED NOV 301987 O
: 15. SUCCESTIC RESOLUTICN                                                   .
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APPENDIX A, ATTACHMENT 5 Optional Use of Filter Elemhnts in Influent to Waste Monitor Tanks                                                          !
This change allows use of the Liquid Waste Processing System with or without                                                           -i the Floor Drain Tank Filter, the Laundry and Hot Shower Tank Filter, and the                                                             !
Condensate Polishing Regenerative Waste Collection Tank Filter. This simply allows flexibility in modes of processing waste streams and does not change the radiochemistry of these waste streams nor does it change the configuration of any plant equipment.                                                        Exposure to plant personnel should decrease as a result of this change, due to fewer filter changeouts required.                                                                          ,
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                                                                               ~
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I APPENDIX A, ATTACHMENT 6 Optional Use of Filter Elements in Influent to Waste Monitor Tanks This change allows flexibility in modes of processing radioactive waste streams, it does not change the amount of chemistry of liquid or gaseous waste streams in any way. Fever filter changeouts will be required in the plant during periods where these three filters are not used in the plant, resulting in less solid waste. However, this reduction of solid waste will be balanced by the increased change of more resin replacements when high solid waste streams are seen by the domineralizers.
I l
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   .                 -           - , _ , _ _ _ _ , _ _ _ _ . _ _______m _ _ _      _ _ _ _ . . . -

APPENDIX A, ATTACHMENT 7 Optional Use r   Filter Elements in Influent to Waste Monitor Tanks This notification simply allows flexibility in processing waste streams generated by the plant. It does not affect the amount or radiochemistry of these waste streams. This modification will not result in a change to the expected maximum exposures to a member of the public in the U!! RESTRICTED AREA and to the general population as previously estimated in the License application and amendments.
                                                                                .l J
i

1
:1 1
l
                                                                          -i APPENDIX A, ATTACHMENT P Optional Use of Filter Elements in Influent to Waste Monitor Tanks This item is not applicable. This is the initial reporting period for'the South Texas Project Electric Generating Station.                              '
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APPENDIX B Increase in Waste Evaporator Concentrates Operational Levels
: a.        Attachment 1 - A summary of the evaluation that led to the             v determination that the change could be made in accordance with 10CTR50.59.
: b.        Attachment 2 - A detailed description of the equipment, c omponent s ,
and processes involved and the interfaces with other plant systems.
: c.        Attachment 3 - Documentation of the f act that the change was reviewed and approved by the Plant Operations Review Committee (PORC).
: d.        Attachment 4 - Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental inf ormat ion.
: e.        Attachment 5 - An estimate of the exposure to plant personnel as a result of the change.
: f.        Attachment 6 - An evaluation of the change, which shows the predicted release of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments.
: g.         Attachment 7 - An evaluation of the change, which shows the expected maximum exposure to a member of the public in the UNRESTRICTID AREA and to the general population that differ from those previously estimated in the License application and amendments.
: h.         Attachment 8 - A comparison of the predicted releases of radioactive materials, in liquid and gaseous affluents and solid waste, to the actual release for the period prior to when the changes are to be made.
B
{
E r

APPENDIX B, ATTACHMENT 1 Increase in Waste Evaporator Concentrates Operational Levels 5
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION
                                                                                         ~I?"3*20Q Tol l
         ;         ,                IN,TERDEPARTMENTAL PROCEDURES s           .
jd                                        10CTR50.59 EVALUATIONS                         PACE           OF k       h!t
-;      up                                                                               Evrtcrtyt DATE      11-20-S7 ATTAc" ENT IP-3.200-3_            ATTACMDIT l 10CFR50.54 EVAlt1ATION FOUf                      ,
(Page 1 of 2)
                                                                                                                         . .r DESC?.I? TION U.it i         l
                                                                                                                }
13    FRecEcu?2                l[l FLA.ST XoDIEICATIcN      l[l c:xr.
CRIGINATISG ECCUMENT No.                I@n6 A       135 6                       ?ly.No f[jt_
TITLE         MAR    ' ll. 2. 2.l .l j ll 9. I.1.
J3
        .4
           ^
w      DESCRI? TION Lewt' " AtltoX1MMrw               a. lLWT FMar MtL L AM D2 u wr. FEOMT $2DivM _
SWFATE YO 'CfTIMM CfG CATICd&L_MGL% AS 92GFICQ IA) THe FCCESS CCHTCOL ((C60
                                                                                                                              ~
D9 P& II.t.t OF 792 sn A JAc inAhlhG "# To It WT. !Ef4ur CCAll AcD ce 25 WT. trfcrDr m#
00 th. satrAre II.4-2 of'rO THE"oPnmer SAR.,        cM<rlu:Al lectu As s&cIFIEb IN T1E twrs.s e_curetL Peock IftE - E2 Does the subject of this review involve a change to the faci;iiv as          '
described in the safety analysis report?
l[l     !]
Does the subject of this review involve a change to the precedures as described in the safety analysis report?                                              h       l]
Does the subject of this review prcpose the conduct of tests er                         ~
experiments not described in the safety analysis re;crt?                              ll      h Doe-s the subject of this review require a change to the Plant                         _
Technical specifications?
l_l     lJ_          ,
Dces the proposed change, althcugh not described in the safety                                             !
analysis report, affect items er activities that are described
    )l-b in the safety analysis' report?
l] Q (This f err., when ecmpleted, shall te retcined fer the lif e cf the plai.t . ) .
f I
* e          .

Si               -
NUMBER SOUTH TEXAS PRO.            JECT ELECTRIC GENERATING STATlqN                          R E Y.
,"i.;                                                                                                     .
N o.
ue                  *
                                               ' INTERDEPARTMENTAL PROCEDUR.ES                   1*5-3*20Q         1 e v .,
k.y[;p,g fif- c; loCTR50.59 IVALUATIONS                    PAGE 37      OF    41 8
4 EFFECTIVE UATE ll-20-S7
):e.
f)!                                                               ATTACHMENT IP-3.200-3 Vi ,.'
[if l.,[j 20CTMO.59 EVALUATION TORM       .
y                                                                         (Page 2 of 2) b
   .s vg I't.any answer is affircative, perform an Unreviewed Safety cuestien evaluttic:.
: 4.                                                                                                                                       :
If all ansvers are negative, r.o Unreviewed Safety Cuestica evaluation is
   } ,,
g           recuired.
3.
3.-
3                         Do:u..entation of this review sust be retained with the reviev pac'.t age fer the                           .
y                         duratica of the statien license.
1
 .)                       Note:
                                      "Safety analysis repert" includes the TSA?., safety analyses submitted :
  .{                                                                                                                      ;
the NRC in support cf their review ci the applicatien fer an cpe atir.g license and subsequer.: acendments to the c;trating license ar.d cther license ec .mitments rade to the NRC.
   ,s          _ ,        Dccusents Reviewed:
O '~
Sh k II.L.2../. II 4
 .*                      ___ $4STEb5 DESChPTitA MhyAL _y LUME 5,. HD 0104                                                                 ~
PQPO5 '10- DOG i,
Puot- %A - 002l h 60x   '     .S OLuf>lltTil t uR v G J
SAC,.uM2IEC L5                                          A l
Prepared by:                        _ _ _
I lM      -/  OY/8bO triginater                       g tatt Cencurrence:pf                                       WI#     /--       "l*
fB gy" Lo,[ar'tr.ent Manager                     rate
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NUMBER                  R E V*
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                                            NO.
h 'eg                                            INTERDEPARTXENTAL PROCEDURES                                  IP-3.20Q             1 vp
 'j                                                         10CTR50.59 EVALUATIONS PAGE 38          OF    41 9
* EFFECTIVE 44                                                                                                              OATE
 ;)
* 11-20-87
 ,.z                                                                                                                    *
* y                                                                        ATTACMMENT IP-3.200-4 O
f                                                          UNREVIEVED SAFETY OUESTION EVALUATION FORM            .
d                           '
(Page 1 of 4) 1 4
J Unreviewed Safety Question Evaluation # _ 06*0055'                           Date Assigned _ C32.lS8 3;
9
                           'h          Procedure Change                   l     l  Plant Modification                l[l         Other
 /
Originating Document:                   AHA46E         IX6F                                   Rey, #      #[\
TITLEt          Shk Il.2!).l.I . f l.'l. l 2. 2b .
   ;         .h
 ;        ,;               DESCRIPTION:                                                                                                         ^
f MAnt.G 'AP#cor# man t u 12 07. At0 err Actrt 4'fB of M h37. I'rtsgT 5ewA1.50lfATE J
                          % 'CPnMVM CPEVAWDAllDES AS WtnEb IV DC fPolcS$ foHTtCL PCCUM1 ' CM P6.                                                  -
                                                        \t
                           -$40,. AWo CHAMG                L'$ TO IX ;Vilb Vr fEME>K boett Acib tQ M in IMT~ frufNT _$COlW1 Syl,ffIt" TO "SPTlMun CNCADCNAl LEVGL's As MetsF1cb In TVG ACCCESS LCA)Teou MC 00 Pb Il%L OF THE SAe..
A. 1. Does the subject of this evaluation increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety                         .,
previously evaluated in the safety analysis                        ,],l        YES       h     No report?                                                                                ,
Bases:         Tum fours Attuo3 8A7tu Aucroraations er co To I6% NJAO,.7)ko IU T/f E Co/JtENT AATES STtGW NHrcM I5 TR4#5fFarfo Fcom THe wAsvr .py ceAret,THAov4tf
                         ]dF WA4ff EV AFCCATDtt. 6CTToM OtSt4AAGE PIAL #6 To rue (cutpT C ATF3 KrD446F T&Jf-j fdt\CEO THE ccMcEUTGATES 712M3rcL. Fv4/A. Tut C00TCNT% DF TdE toQtNT12Are3 3T,'Cs%tL TAAk Ak Tved foMcn our Gg ena&raATEs read 3fte Psmk th To Ee .SeucoGC - THear ARE
         .i a
W AttotthirS E/ALVATt3 /d TMG .5Mt LCHItH THI3 C9AAIGz w00th retACT, T4v3, pit _5 cyxwg
                         % +30T IMcCE%f TML PDcfA%ITtt                 J op occottr>Jcr or tv coNSECdfMCE) 0F N) A CC40esTT~
OR b1 ALFuyC. TION OF EQUtet'1Ch>T' IMPeATAT T0 3AFEtty (CEJe%Uaj Er AWATCb IN THE ~5AR. .
(This form, when completed, shall be retained foF the duration of the license.)

     +',                                    *
                                              , u. ...m.s,
* S'o*!
SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                        *IP-3.20Q 1
INTERDEPARTMENTAL PROCEDURES                                                    ;
          *(     -
PAGE 39     OF   41 10CTR50.59 EVALUATIONS EFFECTIVE
* DATE 11-20-87
                                               -                                   ATTACHMENT IP-3. 200-4 '            Evafuation No. N M [ .
i i                                                                     UNREVIEVED SAFETY OUESTICN EVALUATION TORM (Page 2 of 4)                      -
: 2. Does the subject of this evaluation                                                 ,
create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis              _
report?                                                     l ,,l  YES    h. No Basest                           A lloW_5 (C4C Oft 2ATF_S .572t4aU cp UA TO W4          e T its du A4g d)HIGl                                                          '
Na dud, .*l 60 Aab ra# suksc ovENT YtM5Fft cp yp2?e teatrovttATEA nem T4
,                                               NAsre evAretArctL Formm OwHAehr 69sdl\ urco0H  7      ccacturckEs TLANWR. PLwp 1A 70 ine i                                               totuurt2 Arc srtuse rA%,, THitn0M (MLENr2 Arm Tn AMUM Gme I A 70 S E .*Sblt 0tFIEO,               ,
l
 \
:w  D                        ten aer Arr?ci AHu 54FGitt faATsD $sTErd act
                                                                         ,i      a            s     <
Doe 5 t Tc tgATr THr NAstaIL eTt/
J F J
F*tL M A ct:0ent CL m ALFuac.TigJ OF A 4 lFFiQt-Wt* *TtaPE thy) saa gt AL.vAnD ftEQC lA THG SAPGTu Ad AktstS         CieccT-l                                                                 4        '                                                                     i
: 3. Does the subject of this evaluation reduce the                                         l rnargin of safety as defined in the basis for any            ._
technical specification?                                   l_l YES       h    No .
f Basest     TH l3 dHAW4 AllAu).$ De 70 l6*)_ 61, 3NO, .M 0 rp yu r ce acy,47tATF5
 ,                                                                                                                 s i                                              GittAss race THr VIAsrc EtMOANtA. . T.uu rue svA3w svAttArct_ ntscunthe Popod4                     \
4 h                                                Adb    LCHLCNrkhTE"$ TILAd$ FETL Altre u A,, TD TW eeperarsstris ercut,# sant,Faa runeo           l bJT of 'fHe LCdlCd172 ATE 5 -57DLNs TWh. Pts (cylgaTe#TF3 Y L A.35 F i t fJ W l 6 TO i t~
 ,                                                                                               /                                                 I
                                               .$0LidiFIE4. THis CHAdGE ALLO 05 CurMut cArAArtoets TD e6T-bd chlMOA ofr/24rteH AL
,                                              twts A 3 .3rtcut tra > uTHE fac cr% ccorceu PotsstAm.kh te ct, noT n FFttT ash i
TEUInicAL $PR.sFttAT           6 Av5 P bst OtES ET Renact ~11)u MAQsts) of .5sr-ETtt A<h I
h                                              OgftMCO IN THC SAso.5 Fct. A'H3 TvcHivltAL 5(&::sftcA77cd.
 !r                                     . Notet      ''Saf ety analysis report" includes the TSAR, saf ety analyses submitted to the NRC in support of their review of the application fer an cperating license and subsequent amendments to the operating license, and other license ecm: itments made to the FRC.
}
4 i
4

l    '; . . ;,                   .
               ' mi, .u.a .m                                                               wuussa                nsv[
NO IP-3.20Q          1 SOUTH' TEXAS PROJECT ELECTRIC GENERATING STATION
      ..I                              INTERDEPARTMENTAL PROCEDURES 41 PAG't40        0F
                                          '10CTR50.59 EVALUATIONS                           EFFECTIVE DATE 11-20-87 I                                                                                                 .
Evaluation No. sf-ccSr
                   .                                               En IP-3.200 4 l                                           UyREVIEVED S ATETY OUESTION EVALUATION TORM         ,
                                            ~
(Page 3 of 4)
X            All of the above questions were answered NO. therefore the j                 B. 1.                     originating document does not involve an unreviewed saf ety question.
One or more of the above questions were carXed YES. therefore
: 2.                     the originating document involves an unreviewed safety question. The originating document, as presented, shall          NOT l
Provide a be inplemented without prior approval of the NRC.
l                                               recon:nendation f or disposition of the unreviewed safety
* l
'                                                question below.
I l
RECOMMENDED DISPCSITION                                                                       .
z .v. .
,   $YI                            .
i j         0lll$98 l                           PWM M 8                              CRIGINATCR DAE 6lf$       )       p@                  /            *!*W I
REVIEVED BY:                     ,                                         DATE, N W 'T NANAGER I                                                                                                             /
g A kt                      _/-          *I' APPROVEDBYtj/                               MANAGg                         DATE l
REMARKS:
\
1 (w) f S
1 W__

l l
t APPENDIX B ATTACHMENT 2 Increase in Waste Evaporator Concentrates Operational Levels The Liquid Waste Processing System collects and processes radioactive liquid   I waste generated during plant operation and reduces radioactivity and chemical content to acceptable levels for discharge or recycling.
The Liquid Waste Processing System consists of the Waste Holdup Tank, which    I collects radioactive liquid from the Reactor Coolant Drain Tank and the Reactor Containment Building sumps, the Floor Drain Tank, which collects liquids f ron floor drains in the Mechanical Auxiliary Building, and the       .
Condensate Polishing Regenerative Waste Collection Tank, which collects radioactive laboratory drains, and serves as an alternate tank for floor drains. Also included in this system is the Laundry and Hot Shower Tank, which collects water from the hot shower facility.
L These tanks are all equipped with eductors to ensure proper mixing prior to transfer. The liquid collected in these tanks may be processed in accordance with the Process Control Program. This program selects the optimum processing mode, filtration, domineralization, evaporation, or a combination of the three. After processing by one of these methods, the liquid is then collected in one of six Waste Monitor Tanks and analyzed prior to discharge.             [
The Liquid Waste Processing System waste evaporator also has the capability of ;
processing waste streams that have a high solid content. Concentrates collect in the bottom of the waste evaporator and are subsequently transferred to the Solid Waste Processing System for solidification. The waste evaporator can
[
process concentrates streams with up to 50% solids, however, based on the solubility of sodium tetraborate and the limits of waste evaporator and
~
1 associated piping heat tracing, sodium tetraborate concentrations are limited to 16%. This limit was originally 121, as documented in the Safety Analysis Report. The new limit is well within the capabilities of the system and will i
,    allow more economical processing of solid waste streams in the future.         ,
Also attached are copies of the changes to the Safety Analysis Report and the L
l   Process Control Program.
}
i I
i                                                                                   i
 ;                                                                                  i e

                     ~
    ,,,         .'.,                      .                 License Compliance Reviev
                ''"&                                                                                         0FG703-2A-0003 Rev. 7 L7CINSE COMPLIANCE RIVIEV F0PM       ~
Page 17 of 17 0FGF03-ZA-0003-1 d
(Page 1 of 1)
Crigir.atini; N,rv-t >b._  0),3   s,,.
                                                                  .- h. )1 S I                 Fevisico ib._ (h A Iitle M u h.o.o.i.i )i\.u.).1"vsgNU %                                          i
                                                                                                         '4         '
Ceck cre: ( ) Pr:cefare ( ) Plet )tdificaticn N oeer                           '
Oeck cre: N Q.ality-F41sted ( ) }ke Q2ality-Related
: 1. kes   the r3jnt (x)to    ()yescf this rrelev istive a chege to Om ft:ility s described in the n.G7
: 2. Ites
()mthe Nyes shject of this review imelve a chege to the pr:cstares as des:rited in th U.G7
: 3. Ides
                                @)m the ()yes r4 jet cf this miev c:ntxt tests a:xf/cr a:9eri::er.ts rat der.:rited in th U.G7 4
Ides the()yes rdjet cf this mies again a eht:ge to the inh!c4 Specificatie.s?
(4m
* e If c y cf the ab:ve q.estice.:
Safety Praicatico.               (01 tt :x4h #) an enfeof US, c::Tlete a:4 atta9. a 10CTFJC.!;
5.
Ices the adje:t of this mies np:ese t er ena*.a a pter.tial fin hauri, affnt fire p:cte:tico tal:W:; er *' 'catice, scerge::cy lightirg er cc:n:.icati=.s, er prete: tic. cf q                     tte cet.W.s for anterb;i ard cal:*n'+g safe sh:td:im is tie ever.t cf a fire?
(X)m, ( )yes - attah a Fire l'a:. 2rds Ivaluatica                                                  i 6.
kes  t?A r2 ject cf this revice npou-t er enata a ptattid rafielegi:a1 ha: Art to tre es imr:er.t?
                                                                                                                               ~
Nro, ( )yes - attn 5 a FAfic1cgic4 I:rtimr.e tal Pealuatica
* 7.
kes   tJe rdje:t cf this mies npnuzt er enate a pter.tial n=n-nfielegical haard to tte e:rtimrst.t?                                                                                        i Mm, ( )yes - attn 5 a lio-rafielegical I:rti:mv tal Realuatica
: 8.                                                                                                       !
kes tie adject cf this mies repnser.t er enate a pter.tial n./.M ce.:em?
Mm, ( )yes - attn 5 a D?A Realuatico 9.
Ns Nm,tte( se
                                       )y f et cf this miev repreust er creata a ptar.tial iM;strid safety. hrza      r   i?
                                             - atta:h c Irdastrial Safety Pealuati:n 10.thItes   the ::2je:t
                                 !belear  SecritycfPr:gra:7 this miev repreuzt er create a poter.tial to redxe tra c=..ittner.ts cf Mm, ( )yes - attx5 a Nrlear Security Realuatica 3
                  < MTJ IT M. h. b)D' I                                          IMI b d m it3?
* 71 YID C IT W                 A                                       1IF)k' 5J3)
           ..                                                                    Icz
                       ':his }UE, des cccpletaf, aht11 he ntabai fer th life cf th pict.
l l
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      ,.,          Auessnuasi                                                           NUMBER REV[
NO S6tAH TEXAS PROJECT ELECTRIC GENERATING STATION                            IP 1.19Q         0 (h                    .              INTERDEPARTME!TTAL PROCEDURES PAGE         12 OF    12        l l
EFFECTIVE                   ,
  .                                                                                     DATE         07/13/g7 CRANGE NOTICES FOR LICENSED DOCWiENTS                                               ,
i                                                                                                  ?                    I
                        ~
i
                           ~
ATTACHMENT IP.1.190 01 h
                      .                   CHANCE NOTICES FOR LICENSED DOCW.ENT FORM                                 a Change No.          1355
'                                                                                                        (1)      .     :
Date       3/10/8S (2)            l Organization
                 . Originator              (3)
TS/C0&A William F. Scott. II (.0 YD l                    Referenced Section or Specification of FSAR, ER, FFAR, TS, EP, SP, CDCM, or P (4)                      q;                                                           ,
  '                             TSAR 11.2.2.1.1&ll.h.l.22b
 ,           .!       Change Required: (5) i                                                                                                                     -
i                      The Lk7S vaste evaporator is designed to operate en a batch basis and the 1
contents are concentrated to the opticus operational levels as specified                        ,
l                                                                                                                       ,
in the Process Control Progran.
 ;                    Justification:
l                       Concentrations specified in FSAR are not consistent with concentrations in OPCP01-ZA-0021 (Radioactive Vaste Processing Cuidelines) which is referenced 3     .- 4~31  .
                                         .n  <ee ew.e u  , < n the pree... ceatrei Procrm.
:                                  (6)
'                                                                           Date Reviewed and Approved by Supervising Engineer Licensing      (7) 4 4
or Revieved and Approved by                              Date
]*                                                                                   ,(6) 4                                      (8)
 !                                                      Manager, Enviremental Assesscent/
;.                   9                                  Waste Management
!                    4'                                                                         b' j                    '' Change Contained or Appoved in A=end ent Number                        *
(9)       I 1
Verified by                                            Date l , '' . )0*                                                                                 (10) i  V'                                       (10) i a
I                        Ll\ PROC \IP 1.19Q f

p IP-1.19Q, Rev. O hh Justification continued (6) To protect the integrity of the LkTS evaporator the pH of the concentrates is maintained in the range which produces sodium tetraborate, not boric acid.
    %       g
    </
w G
(       I l us                                                                                         '
l
: m. ..     ..                         .                                                                                    ,
y~y
                                                                                               '          ~
The WECTs:providai extra acorage capacity 1for thelVMTs and ein be' discharged <
1~ 0 y1        through the effluent radiation monitor to the.CVS. Additional surge capacity:
Jg, - is provided byitvo surge tanks located in-the Fuel Handling Building (FH3). '                       53-Processing consists:of.any of the following modes:
: 1.        Filtration, evaporation, and demineralization
: 2.        Filtration and 4aporation
: 3.        Filtration'           eralization 4         Filtratie.n The processing c.                m.rsined by hs quality:of the liquid to be proces-sed. The nor=al ; -          .,ing code Jis expected ~co be one' of the following ;                                 '
co=binations: . filtra-ion, filtration and/or evaporation' or filtration,                            55-evaporation and/or demineralization,                                                        ,
The. waste evaporator is a forced circulation crystallizer with- a 30 gal /=in.                  53' distillate processing flovrate. In addition this evaporator can also be used                                         I as a backup to the BRS recycle evaporator.
The lVPS vaste evaporator is -designed to operate on a batch basis' and the. .
contents are concentrated to appmi           ntcl" 12 :-percent--bori<:-Md-or-2bwu --
0,w n bn- L.:M A s- Enc.c s w 7.,e c
pe ggmq ye, h,r.         p mum      (%'nt0 L.
4CCds          /$erGU, y
* The vaste evaporator must be operated at a basic pH. .. Therefore the pH of the fg.y      feed is c.djusted as needed prior to transfer into the. evaporator. Feed enters v
the discharge piping of the recirculation pu=p, is heated in' the heating ele-cent and circulated through the vapor body. Vnen the desired. concentration is                39             -
achieved, as indicated by the evaporator density instru=entation, :the concen-trate is p eped to the concentrate storage tank for eventual solidification,                     .
or directly to solidification bypassing the tanks.                                               :> 3 Evaporator distillate is condensed and cooled in the distillate condenser and
                                                                                         ~
subqooler skid and further treated by the vaste evaporator condensate decin-eralizer or EdT purification decineralizer before transfer to one 'of the vaste                 53                  i conitor tanks.                                                                                                       !
The two largest sources of liquid volu=e to the 1VPS are the Condensate Pol-ishing System regeneration vaste and the equipcent floor drains. The equip-                               -
                                                                                                                                   ~j ment floor drains represents 'a relatively continuous source to the UJPS vhere .                                     l as the condensate polishing system regeneration vaste is an infrequent-high volume, short-duration, batch source. The Condensate Polishinz System .
regeneration vaste is a source to the UJPS only during periods of               l: normal operations when there is above nor=al primary-to-secondary leakage, or exces-sive fuel defects. At these times the regeneration vaste is direc d to the CPRWCT as discussed in Section 10.4.6.2; during these periods the equipcent and floor drains are directed to the FDT. Processing of this vaste in the CPRWCT is identical to the processing specified for vaste in.the FDT. The system also provides the capability to discharge the condensate polishing regeneration vaste directly to the C'JS if processing is not required. ~
f.g    '   l.aundry and hot shower drains are normally filtered and released. However, Ms          the vaste evaporator is capable of processing the laundry and hot shower vaste
  \ ..          after addition of an antifeaming agent, if treatment of these vastes is requir-                                       i ed prior to their release.                                                                                            '
11.2-3                          Amend =ent 55 i

f.>. . ~
                                                                             ~
                                                               ,                                                     ^
t
            -       A                                                                                                        .
STP'FSAR I. 4 e.
Valves in contact with vaste strea=s are of a design that minimizes           "
     .-                           pockets or crud traps. Remote operated valves are used, where nec-essary, in high radiation areas.
1 f.
Piping is designed to provide a clean, free flowin5 path. Bend y                                 radius is a minimum of five pipe ' diameters for"all resin slurry pip.                    t if                                 ing. All resin slurry piping is provided with means for backflushint
: 3.                                and is sloped, where possible, to prevent settling in the pi; es.       ~
j                       g.
Vaste tanks have provisiens for conitoring level and ala:: ming poten-
   *.                             tial overflow conditions.            -
h.
Mixins and handling equipment are provided with redundant drives or
              -                   with ceans for manual operation, where necessary, f.*om luv radiation areas in the event of drive failures.                                      39          ,
h                         L.
{
Remote     control of the system and process is used to the naxi um prat.
ticable extent.
g                                control station, Control of the' system is accomplished from a centra *.
j.
y'                              Internal parts in contact with the vaste streams are designed to vichstand an integrated radiation exposure of 107 rads over the                            '
qL                               40 year design life, a
: k.      Provisiens for operator surveilla.:ce during cave: Ent of vaste con-Ifi$n1                  tainers are provided by use of closed-circuit television cameras and conitors.                                                                   as
  't l                      1.
In accordance with 10C/R50 App. A, General Design Criterion 63, radi- l39 ation conitors are provided in the S**?S control area. (See Secticn i
i 12.3 for further details.)                                                  49 j                    2. Types of Vaste The SWPS is designed to process these types of vaste by solidification and en- p9 capsulation, packaging or compaccion:
I
: a.      Expended bead type ion exchanger resins
: b.      Evaporator concentrates containing uF t:OcTI      % eM pI.Md(b.da n vekgmc;ces       .ic and               .
o&seght-peeeent-sodhuulfate Epto.,12;J A W fv u d d v c.
Miscellaneous liquids resulting from decontamination, laboratory wastes, and system cleaning
: d.      Expended liquid and air filter elements e.
Miscellaneous dry wastes including plant equipment and/or parts thereof
: 3. Quality Group Classification                                          .
fp
* Gy         The SWPS is classified as Non Nuclear Safety and ceets the requirements of Branch Technical Position (BTP) ETSBil-1, Rev. 1.                                        49              '
                                                                                                                  .s 11.4 2                       Amendment SE

%D                                   .
)$ f *.             I' E Vd                                                               Rsdioective Westh Processing Guidelines                    OPCP01-ZA-0021 Rev. 1 Page'4'of.4 p' '  .
                                               ,'3;2:4'.2'7The evaporator concentrates -should not be allowed to.
3 .,.                                                        exceed any of the following criteria prior to transfer to the Waste Evaporator. Concentrates Tank:
as   Specific Activity: 0.2 uCi/ce as total gamma activity b: Na SO2 4: 25% by weight s                                                        ic.^LNa3joj''.~iHybi'16%'byveight 2
    }
: d. Cl:   2000 ppm i
NOTE Items b and e are guidelines of OPGP03-ZO-0017 g                                           (Radioactive Vaste Process Control Program),
item d is for protection of the evaporator.
i 3         cs 3.2.4.3
 -[ $jj      '                                             If any of the above criteria stated in 3.2.4.2 are exceeded, dilution vill be used in the Vaste a                                                       Evaporator Concentrates Tank.
4.0 References                                                                                  ,
4.1    IPS?O7-ki-0001 Liquid Vaste Effluent Releases, Rev. 2 4.2    I?CP13-VL-0006 Laundry and Hot Shower Tank Operatien, Rev. I                     t 4.3 IPCP13-VL-0002 Condenst e Polishing Tank Operation,    Rev. Regeneration  Waste Collection            i 1
I 4.4   IPC?l3-VL-0032 Condensate Polishing Regeneration Waste Eatch Release,'Rev. 0                                          ' ~
4.5  IPCP13-VL-0003 Floor Drain Tank Operations, Rev. 1 4.6  IPCP13-VL-0001 Waste Holdup Tank Operations, Rev.      1 4.7   1PCP13-VL-0009 Vaste Surge Tank Operations, Rev. 0 4.8   OPGP03-ZO-0017 Radioactive Vaste Process Control Program, Rev.       1 5.0 Succort Documents                                                       .
dr Of#
               ''             None

                       .~'
N               ~;                    '
        . ." -        . , *. O -                       .
i.
L        ji,                                      Radioactive Vaste Process Control Program                                   OPGP03-ZO-0017
        .of                                               -
a4                                                              Rev. 1 Page 10 of 3B i'                                                                               '
: b. For resin'dewatered in HICs, L                                                                                                                      . acceptance criteria.
shall be f one percent'(1%) of the internal.
volume of the HIC.
                                 , e-5.1.3.10 The imple=enting . procedures f or. the processing and -
handling of contaminated resin are as follows:
a.
0?CP01-ZA-0021 (Radioactive Waste Processing Guidelines) b.
_                                                OPCP10-ZR-0001-(Deter =ination of Radioactive Waste Package Curie Content) c.
OFCP14-VS-0006 (Radioactive Vaste Package Transfer to Storage) 5.1.4    Evaporator Concentrates 5.1.t.1 The Liquid Vaste Processing System (LVPS) is designed to collect, transport, and process radioactive liquids either for release to the
       .cc Ei;                                                       environment or for solidification. Liquid vaste shall be concentrated in the LVPS evaporator prior to beirg transferred to a vendor for solidificatien.                                 ._
Evaporator influent consists principally cf either:
: a. 3eric Acid (H330
!                                                                                            4 ) containing liquids b.
Sodium Sulfate (Na           2 SO4 ) containing liquids
                                               .T.57IT4$2                                                  ~
l ''                                                           Borated vaste streams shall normally be processed through demineralizers for release to the environment. ['lltirE~a',t',e;1y7, bTratfd3~a st''e Mi'e'a.is' may
_b e _ p ro c e s s e d 'by;'e v3;io r a t i oh'1:i' t he "So d ium
* L                                                                          '
a;TetHboyg,'{N,a~$ikifiB~0'*.~.l*,7H{0)"f a vender for so                                                      orb"and transf erred I                                                                                              cation. Eerated vaste streans may orig'inate from the Floor Drain Tank Vaste Holdup Tank, Recycle Holdup Tank, or Laund: 7 and Hot Shower Tank.
5.1.4.3 Condensate Polishing Demineralizer regeneration l                                                             chemic,a1 wastes may be required to be processed
!                                                             through the LV?S in the event of primary to
!.                                                            secondary leakage. These regeneration solutions shall be transferred to the Condensate Polishing g.,,                                                      Regeneration Vaste Collection Tank and subsequently i;{j t,                                                        concentrated in the LVPS Evaporator to the Sodium Sulf ate form.
h l

:Lg 4. .        .,
     ,           ,..a. p      -
, -(         '.                           Radioactive Vaste' Process Control Proeram OPGP03-ZO-0017' L                                                                                                   _Rev. .I .   .
I'                                                  .
Page.11 of 38' 5.1.4.4      Each batch of evaporator con.centrates shall be
!                                                       sampled and'analyned to provide isotopic curie-
                                  '                     content _inJaccordance with IPCP07-ZS-0003 or' l                            ,.     '                   2PCP07-ZS-0005 (Local Sampling in MA3, FH3 and RC3).
Total activity of each. processed container shall'.be l                                                     . calculated'in accordance with.OPCP10-ZR-0001 I                                                       (Deter =ination of Radioactive Waste Package Curie              i Content).
1 5.1.4.5      In accordance with Technical Specifications Require =ents, .in at-least one (1) out of every ten
                       -                               (10) batches a test solidification is-perfor=ed.
The concentrates are transferred to the Vender Solidificatien Systen. If the test solidification l
i is acceptable as per Section 5.6 the concentrates are processed.in accordance vith the Vendor Process Control ?regrta Manual.
5.1.4.6      Following solidification, the container shall be classified and labeled in accordance with                .         i g'.                                              0?CP01-ZA-0026 (Classificatica and Shipment of Solid
           ^
Radioactive Waste). Verification that container-centents fer= a free standing cenolith, shall be.
performed in accordance with the Vendor Process               _
Control Program Manual. Folleving this verification                !
the container shall be weighed and placed in stcrage                !
per 0?CP14-VS-0006 (Radioactive vaste ?ackage Trarsfer to Storage).
5.1.4.7 A flev chart of the evaporator concentrates process                    I
* path is shovn in Addendu 4. 'A description and diagram of the. solidification process system and cc=ponent precess part=eters (i.e. flev, temperature, etc.) is provided in the Vendor Process
              .                                      Control Progran Manual.
                                        ,5[1.II8' The impleme: ting procedures for processing evaporator concentrates-are as follovs:
                                                                              ......-.-~..
: a. _OPCP01....TZA O,0,21..(Radioactive
                                                                 ,,                         Va....'
ste Processing
                                                          , Guidelines) 1 b.
OPCP10-ZR-0001 (Determination of Radioactive Waste Package Curie Content)
: c. OPCP14-VS-0006 (Radioactive Waste Package y .
c'. s                                                   Transfer to Storage) u d.
OPCP14-VS-0007 (Vaste Transfer to the iortable Solidification System) i

I l
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APPENDIX B, ATTACHMENT 3 Increase in Waste Evaporator Concentrates Operational Levels 1
4 1
l

        .e' 0       , .ar                                                                                                                                     A11AdlMPuT 3 h        -)
Plant Operations Review Committee h                                                                                                                                                           OPGP03-ZA-0004 Rev. 8 Page IS of 15 PORC REVIEW COVER SHEET                                                             i
_0PGP03-ZA-0004-1                    a (Page 1 of 1)    , Q,,y:{
                             . Originating Document No.                                                                              ..,.,
   $                                                                        (j $ GE %-COT Rev'ision No. ___                                                           ~~
f                              TITLE _ bO med e ISM , 5 AR) 1.%.9. I                                                               I , II.V l 2 M F
a                                                                                          , .          ,
k 3                             The FORC has reviewed this b
appropriate):                      item and has determined that (check as
:)                            It     does l
M
{                                           V does NOT involve an UNREVIEVED SAFETY QUESTICN                                                    .
j                            It _ does J loes   d     yb the Operating License.        require a change to the Technical S,aecifications or
  }"a                           It     does and other licensi g documents.does NOT deviate from the co=.titments                                                                , SER, made in the FSAR
  }.i (}_                      It      does       d
                                              ,[_ oe's NOT adversely impact plant nuclear safety.
{                          It      does l{                         personnel or_the V doespublic.NOT adversely impact the health and safety of plant It        ces
 )                                                does MF 1
individuals / groups. _/ NSR3e'                                                  _ NRC quire further review by the NSE3, the NRC, or oth
_ other, specify below.
REMARKS I
_1 8
i,                        __
                                        -r l
'                                    /                                                                                     -
The P RC recommends this item for:
APPRot'AL DISAPPROVAL                                                   OTHER
__ PORC KEETING NO._                'O Completed by_                 b PORC Secretary                                                      DATE F /0 - N y
This form, p!<
e               requirements of the originating document.when completed,                                                                                retention shall be retained 0 ,                                                      _ _ _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . . _

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                                                               \
APPENDIX B, ATTACHMENT 4 Increase in Vaste Evaporator Concentrates Operational Levels 1
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 " 7 ~." ~
                                                                                                           ~
Houston Lightina* & Power Company                       ATTACH MGlT 4 "'
           >y       g OFFICE MEMORANDUM
  /.             To       W.H. Humble                                         April 14, 1988 from     W.D. Markham f
Subicer  SAR Change #1355:   Sodium Tetraborate Concentrations SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION A SAR Change Request has been made involving a change in allowable sodium tetraborate concentrations in the waste evaporator concentrate stream from.to 12% to 16%. The vaste evaporator concentrates flovpath is as follows:
The concentrates in the bottom of the waste evaporator are discharged by the operator using the automatic Horton Process sequencer. This allows the operator to first, send the water remaining in the discharge piping from the last flush to the floor drain tank, second, 'the bottom concentrates are transferred to the concentrates storage tank by the concentrates transfer pump, third, the discharge piping is flushed with domin water to the ficor drain tank, lastly, the discharge piping is refilled with water and left on standby.
During this process, the following factors'must be considered in order to evaluate the proper operation of the system with up to 16% sodium tetraborate:
The waste evaporator is not affected by the concentration of sodium tetraborate. The elements necessary for safe operation are, pH maintained at
     , fy,      7-9, and chlorides kept within specification. At this pH the equilibrium O          equation for boron shifts to the sodium tetraborate side of the equation, which is desired in the vaste evaporator. The waste evaporator is capable of                   -
processing slurries of up to 50% concentrata. The discharge piping from the waste evaporator and including the concentrates storage tank is heat traced to 165 degrees F. This temperature is capable of supporting up to 16% sodium tetraborate with no solubility problems (see attached solubility curve).
Chem-Nuclear can solidify concentrates up to 20% sodium tetraborate with existing equipment.
The original 12% sodium tetraborate limit in the SAR appears to be taken from gg              the system description manual,and-1: on: cf ::'.'er:1 -examples-of-Y              .over-decerip ' a L Ae-S W The 16% limit is a safe one, and will also allow
[,.h            us to process solid waste more economically in the future.
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i APPENDIX B, ATTACHMENT 5                            I Increase in Waste Evaporator Concentrates Operational Levels          -
This change allows batching of concentrates in the warte evaporator as specified by the process control program. This allows more economical processing of waste streams that are processed through the waste evaporator. l This change will allow batching of up to 16% sodium tetraborate vice 12%
originally allowed by the safety analysis report. This change will not affect operation of any plant equipment. Solidification of these waste streams should not result in any additional exposure to plant personnel. The            )
radiation levels in the concentrates storage tank may increase due to the       1 increased concentration of sodium tetraborate but the decreased number of       '
transfers will offset any additional exposure that might result from this. No   '
additional exposure to plant personnel will result due to this modification.
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APPENDIX B, ATTACHMENT 6 Increase in Waste Evaporator Concentrates Operational Level, During processir.g of radioactive waste by waste evaporation, the ability to process concentrates of up to 16% sodium. tetraborate vice 12% as previously required by the SAR will allow more economical processing and may reduce the total amount of solid waste produced over the life of the plant.
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APPENDIX B, ATTACHMENT 7 Increase in Waste Evaporator Concentrates Operational Levels i
This change allows up to 16% sodium tetraborate in the concentrates stream l
produced by the waste evaporator. This allows more economical processing of solid waste over the life of the plant. .This change does not change expected maximum exposures to individuals in the UNRESTRICTED AREA and the general population from those previously estimated in the License application and       I amendments.                                                                     l I
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APPENDIX B, ATTACHMENT 8 Increase in Waste Evaporator Concentrates Operational Levels This item is not applicable. This is the initial reporting period for the South Texas Project Electric Generating Station.
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1 APPENDIX C                                  l Addition of Local Sampling for Waste Monitor Tanks D, E, F            1 i
: a. Attachment 1 - A summary of the evaluation that led to the determination that the change could be made in accordance with 10CFR50.59.
: b. Attachment 2 - A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
l 1
: c. Attachment 3 - Documentation of the fact that the change was reviewed l and approved by the Plant Operations Review Committee (PORC).         l
: d. Attachment 4 - Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental in f o rmat ion.                                                      ;
: e. Attachment 5 - An estimate of the exposure to plant personnel as a result of the change.
: f. Attachment 6 - An evaluation of the change, which shows the predicted ,
release of radioactive materials in liquid and gaseous effluents      '
and/or quantity of solid waste that differ from those previously predicted in the License application and amendments.
: g. Attachment 7 - An evaluation of the change, which shows the expected maximum exposure to a member of the public in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments.
: h. Attachment 8 - 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.
l APPENDIX C, ATTACHMENT 1 Addition of Local Sampling for Waste Monitor Tanks D, E, F A 10CFR50.59 Determination Review Form was completed by Support Engineering.
It was determined that there were no unreviewed safety questions and no-further action was required.
                          ~
10CFR50.59 EVALVATION FORM - TYPICAL o
(Page 1 of 2)
DESCRIPTION Unit #                           !
I   I PROCEDURE                                   g PL#IT MODIFICATION              I I   OTHER ORIGINATING 00ClMNT NO.                                      LIF,M - cl6-67                  REY.
TITLE                                                     @' ell ___
i DESCR1PT10N     O S EA A'f(6.0 $?I s Qt) sj l' D                      s       7*ikAT CCC4C 3AWLlNQ 86 PEAw?p'ED i~oit w& IJoht) ultrris 6fs75w tw ,7/s
                        %n      MG4                                                                                                    _
t Yes       No Does the subject of the review involve a change to the facility as                                               ~
                                                                                                                                         ;, : V-described in the safety analysis report?                                                                I    I   g / , ,g           ,
u1 -'
Does the subject of this review involve a enange to the procedures                                                  ,,-
t as described in the safety analysis report?                                                                   ,
I    i 4                  ,
Dods the subject of this review propose tne conduct of tests or experiments not described in the safety analysis report?                                                                     p' I    [                       t Does the subject of this review require a change to the Plant Technical Speci fica tion?                                                                                      _
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Does the proposed change, although not described in the sa fety analysis remrt, affect items or activities that are described                                                         ,               l in the safety analysis report?                                                                         I    I (V}p                l (This fom, when completed, shall be reta'ined for the life of the plant.)                                                             i 0191b/0106b                                                                             -
f

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   . ' ? ' , '. , '    ,                           .                            ,
10CFR50.59 EVALVATION FORM - TYP! GAL (Page 2 of 2)
If any answer is af finnative, perfonn an Unreviewed Safety Question evaluation.
If all answers are negative,.no Unreviewed Safety Question evaluation is requi red .
Documentation of this review must be retained with the review package for the                         -
duration of the station liccme.
Note:          "Safety analysis report" includes the FSAR, safety analyses submitted to the NRC in support of their review of the application for an operating license and subsequent anendnents to the operating license                     '
and other license comitments made to the NRC.
l Documents Reviewed:                                                                        -         -
y.%It% 777 spf oz.                                                                             ,
(263A) 777 6/ro c
                                                                                                              -.1 O     '
t Prepared by:             h        7)fM Ori gina ttr        ''
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Concurrence:                m            yua            /    /- 2/-8-l'               ,
Ocparunent Nnager                            Date i
r 4
Ol91b/0106b                                                       -'

                                                                                              ~-     -
10CFR50.59 EVALUAT10li FORM --TYPICAL 4
                                              ~(Page 1 of 2).
DESCRIPTION Unit i          k I   I PROCEDURE       g PLMT MODIFICATION               I I   OTHER                                  ,
ORIGINATING 00CltENT NO,        N6MJ -ollv6l'                    REY, TITLE              M2. Tc>         PII e 9 F'icC2-l b s
DESCRIPTION    Ac0 $ces           Fo/L tccat u-mru e C
Yes     N_o, o Does the subject of the review involve a chanSe to the facility as described in tae safety analysis report?
                                                                                                       /'        l i   i  g                      !
Does the subject of this review involve a change to the procedures as described in the safety analysis report?                                  I   I   r>4,,3 Does the subject of this review propose tne ccnduct of tests or_
M, ph , '5 l
experiments not described in the safety analysis report?                   _l    1
                                                                                                               ~
Does the subject of this review require a change to the Plant                                               i Technical Speci fica tion?                                                  I    l_ ds                      ;
i Does the proposed change, although not described in the safety analysis report, affect itcos or activities that are described in the safety analysis report?                          .                  I    l_  IM_p i
(This fom, when completed, shall be retained for the life of the plant.)                                      ,
l Ol91b/0106b                                                 /

>  . -; ; .., t  ,:                        .
10CFR50.59 EVALUATION FORM - TYPICAL
                                                    ~
(Page 2 of.2)'
If any answer is af fimative, perfona an Unreviewed Safety Question evaluation.
If all answers are negative, no Unreviewed Safety Question evaluation.is requi red .
Documentation of this review must be retained with the review MCkage for the                     -
duration of the station license.
Note:       "Safety analysis report" includes the FSAR, safety analyses submitted-to the NRC in support of their-review of the applicaticn for an operating license and subsequent amendnents to the oprating license-and other license comitments made to the NRC.
Documents Reviewed:                                                                           -
1:Grs-n.
                                                                                                     @3 O
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                                                              /       9)lg/g>3           ~
Ori gina tor                                   Date Concurrence:          #71
                               /        b Department Klaager
                                                              /     l///7/$$
Date Ol91b/Ol06b                                                   f f

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i APPENDIX C, ATTACHMENT 2                            l l
Addition of Local Sampling for Waste Monitor Tanks D, E, F             '
The Liquid Waste Processing System collects and processes radioactive liquid    i waste generated during plant operation and reduces radioactivity and chemical content to acceptable levels for discharge or recycling.
The Liquid Waste Processing System consists of the Waste Holdup Tank, which collects radioactive liquid from the Reactor Coolant Drain Tank and the         l Reactor Containment Building sumps, the Floor Drain Tank, which collects        i liquids from floor drains in the Mechanical Auxiliary Building, and the Condensate Polishing Regenerative Waste Collection Tank, which collects radioactive laboratory drains, and serves as an alternate tank for floor drains. Also included in this system is the Laundry and Hot Shower Tank, which collects water from the hot shower facility.
These tanks are all equipped with eductors to ensure proper mixing prior to transfer. The liquid collected in these tanks may be processed in accordance    l with the Process Control Program. This program selects the optimum processing mode, filtration, demineralization, evaporatton, or a combination of the        '
three. After processing by one of these methods, the liquid is then collected in one of six Waste Monitor Tanks and analyzed prior to discharge.
These tanks are all equipped with eductors to ensure proper mixing prior to     !
transfer. The liquid collected in these tanks may be processed in accordance with the Process Control Program. This program selects the optimum mode for processing, filtration, demineralization, evaporation, or a combination of the three. After processing by one of these methods, the liquid is then collected in one of six Waste Monitor Tanks and analyzed prior to discharge.
This change involved Waste Monitor Tanks D, E, and F. These tanks are located outdoors in the plant yard. Sampling these tanks was performed via three one inch drain valves, and contamination of personnel was likely. A sample sink with three common sample valves connected to these drain valves as an aid to sampling and to help reduce the likelihood of personnel contamination. See attached Field Change Requests and 10CFR50.59 Review Determination Forms for detail.
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                     > atas N soa ascussr                                                                                                                                                                                                                        I NEED TO HAVE NEW ISOLATION VALVES ADDED AT THE LOCAL sal 1PLE SINK.
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REVISE P&ID NO. 7R309F90021 #1 REV. 9 T0 fiAKE THE FOLLOWING CHANGES:                                                                                                                                                                  ,
* ISOLATION VALVES NL-1006, WL-1007 AND WL-1008                                                                                       >
WHICH WERE CLOSED ARE NOW TO BE -LO^KED (PEM.
* ADD NFW ISCLATION VALVES NL-1376, NL-1377 ,ANU R m T
                                                                                                                                                                                                      -WO'r k L % ~'?                                 ~
l WL-1378 AT THE LOCAL SAM:LE AND DRAIN SINK. ge"y Q no men aag                          '
C0 7h4%                          i SEE PAGES 2 ANL 3 0F THIS HFCR.                                                                                                                  *m5 b                 !
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o           e 10CFR50.59 EVALUAT10ll FORM - TYPICAL (Page 1 of 2)
DESCRIPTION Unit *          !
I  i PROCEDURE                                          i i   OTHER Q PLMT MODIFICATION ORIGINATING DOLLMNT NO.          Lif;i n - C l @ 7               REV.
TITLE                         f@e(_.
OESCR1PT1DN    CS?AAY(O.0$      I.&Qt)WisD
                                                                      ?
Tid A T CCC AL. Siqcq$t tbQ 85 PEAMw&O Foil 7112 tJcijin u/4s16                   Ws764'         t10 71/G Unn An64 Yes     No Does the subject of the review involve a change to the facility as                 ~
p,6 described in the safety analysis report?                                    I    I Q ,-
Does the subject of this review involve a enange to the procedures                    ,
as described in the safety analysis report?
Does the subject of this review propose tne conduct of tests or I    i
                                                                                                                         %gk$       g 3
experiments not described in the safety analysis report?                    l^7 gPg Does the subject of this r? view require a change to the Plant Technical Speci fica tion?
I     I
[5 Does the proposed enange, although not described in the sa fety analysis report, affect items or activities that are described in the safety analysis report?                                             l    I (This fom, den completed, shall be retained for the life of the plant.)                                 !
l 1
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0191b/0106b 1

  ,4 , , , -
10CFR50.59 EVALUATION FORM - TYPICAL (Page 2 of 2)
If any answer is af fi nnative, perfonn an Unreviewed Safety Question evaluation.
If all answers are negative, no Unreviewed Safety Question evaluation is requi red.
Documentation of this review must be retained with the review package for the auration of the station license.
Note:      "Safety analysis report" includes the FSAR, safety analyses submitted to the NRC 4 support of their review of the application for an operating license and subsequent amendnents to the operating license and other license cortnitments made to the NRC.
Documents Reviewed:
V3G/fb)777 Sbf oz.
426Zik) 777 6frOL                                                          -
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7 at A30N 80m af OcE sr                                                                                                                                          l OPERATIONS RE00ESTED TWAT Lncal (a'mi!NG LE PERF00FE0 FOR TWe                                                          l LIQUID WASTE (WL) SYSTEf1 IN THE YA00 AREA.
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6 10CFRS6.59 EVALVATION FORM - TYPICAL (Page 1 of 2)
DESCRIPTION Unit a          k I    i PROCEDURE                                      I     OTHER Q PLMT MODIFICATION                I ORIGINATING 00CtM NT N0,      Nf5VI-ollv6[                     REY.
TITLE               fcq2. Tc>     PkIo 9 F9 cCM b DESCRIPTION    Aro    WuM9      F0 /L Lec4L C 4,M #u ce Does the subject of the review involve a change to the facility as Yes     No
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described in Oe safety analysis report?
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Does the subject of this review imolve a change to the procedures as described in the safety analysis report?
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Does the subject o.5 this review propose the conduct of tests or experiaents not described in the safety analysis report?                   I     i_ Q)f           4 7
Does the subject of this review require a change to the Plant Technical Speci fica tion?                                                 i     I R.
Does the proposed change, although not described in the safety analysis report, affect items or activities that are described in the safety analysis report?                                            I     I   IA c (This fonn, een completed, shall be retained for the life of the plant.)
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0191e/0106b

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10CFR50.59 EVALVATION FORM - TYPICAL (Page 2 of 2)
If any answer is af fimative, perfom an Unreviewed Safety Question evaluation.
If all answers are negative, no Unreviewed Safety Question evaluation is requi red.
Documentation of tnis review must be retained with the review package for the curation of the station license.
Note:       "Safety analysis report" includes the FSAR, safety analyses submitted to the NRC in support of their review of the application for an operating license and subsequent amendnents to the operating license and other license conaitments made .to the NRC.
Documents Reviewed:
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                                                            /     4/6/SB Date l
Ol91b/0106b j

     . . . . . . . - . . - - . . . . - . . . _ . - _ . . . - - . .         - - . ~ . . ~ _ .        ~ . . . . . . .. . - . -_ .- . _. . . . -
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4 APPENDIX C, ATTACHMENT 3 i
,                                                     Addition of Local Sampling for Waste Monitor Tanks D, E, F                                ;
A PORC' Review was not required for this design change.                                                            i i
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APPENDIX C, ATTACHMENT 4 Addition of Local Sampling for Waste Monitor Tanks D, E F The Liquid Waste Processing System (LVPS) Waste Monitor Tanks provide a final collection point prior to discharge to insure all applicable limits are met.
There are six Waste Monitor Tanks, three are located in the Mechanical Auxiliary Building, three are located in the plant yard. Sampling of the outdoor tanks was difficult to perform due to the sample points consisting of 1" drain valves. Control of flow rate from these valves was difficult and the chances of personnel contamination was increased. A sample sink located on the catwalk above the Waste Monitor Pump Skid was added with three sample valves connected with stainless steel piping to the drain valves. This sink was much easier to access, provided reasonable flow rates for sampling, and greatly decreased the chances of personnel contamination. Each outdoor tank   !
may be sampled from a single point from a much safer location.
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APPENDIX C, ATTACHMENT 5 Addition of Local Sampling for Vaste Monitor Tanks D, E, F This change added a sample sink at the Waste Monitor Tank D, E, and F Pump Skid which allowed easier sampling and decreased the chances of personnel contamination. This change will not create any additional exposure to plant personnel as a result.
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APPENDIX C, ATTACHMENT 6 Addition of Local Sampling for Waste Monitor Tanks D, E, F                           p This change added a sample sink at the Waste Monitor Tank D, E, and F Pump skid and it does not change the amount of chemistry of any waste stream in the Liquid Waste Processing System. This modification does not change the amount                 l of liquid and gaseous effluents, and solid waste prediction in the License application and amendments.
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APPENDIX C, ATTACHMENT 7 Addition of Local Sampling for Waste Monitor Tanks D, E, F This modification added a sample sink at the Waste Monitor Tank D, E, F Pump skid and does not affect the amount or radiochemistry of any waste stream.
This modification will not result in a change to tne expected maximum exposures to a member of the public in the UNRESTRICTED AREA and to the general population as previously estimated in the License application and amendments.
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l                                       APPENDIX C, ATTACHMENT 8 3
I Addition of Local Sampling for Waste Monitor Tanks D,'E, F This item is not applicable. This is the initial reporting period for the    l South Texas Project Electric Generating Station.                                 ;
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l APPENDIX D Hodification to Level Indication Equipment for.
Vaste Evaporator Condensate Tanks
: a. Attachment 1 - A summary of the evalu. tion that led to the
,    determination that the change could be made in accordance with l    10CFR50.59.
l b. Attachment 2 - A detailed description of the equipment, components, l    and processes involved and the interfaces with other plant systems.
: c. Attachment 3 - Documentation of the fact that the change was reviewed l    and approved by the Plant Operations Review Committee (PORC).
: d. Attachment 4 - Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.
: e. Attachment 5 - An estimate of tho exposure to plant personnel as a l    result of the change.
l
: f. Attachment 6 - An evaluation of the change, which shows the predicted release of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments.
l g. Attachment 7 - An evaluation of the change, which shows the expected maximum exposure to a member of the public in the UNRESTRICTED AREA and to the general population that differ from those previously        i estimated in the License application and amendments.
l
: h. Attachment 8 - A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and solid waste, to the actual release for the period prior to when the changes are to be made.
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APPENDIX D, ATTACHMENT i                           j l
Modification to Level Indication Equipment for                 :
Waste Evaporator Condensate Tanks                       l A 10CFR50.59 Determination Review Form was completed by Support Engineering.
It was determined that there were no unreviewed safety questions and no      ;
further action was required. See attached forms for detail.
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;                            SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION
!                                        10CFR50.59 DETERMINATION REVIEW FORM E
;                                                                                                             Page   I    et   t L
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CnM< cne:( i Frececure ( ) Flant .YccJicanen                 Id0tner                                         i Chec< cre ( ) Cuahry Re'atec                l  Ncnquahty Related l
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: 1. Oces tre set t ect cl tris revie invcNe a change to the facilq as casenctc in tne FSAM                 I A
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: 2. Oces tne sut i nt ci tnis review invcive a change to the procedures as desceted in the FSARS           j kJ e C..dcwo                                                                     ''*''
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Cces tre sut nt i cf mis review rv,vire a change to the Teche.>caJ S;+cf.cacens?
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,                                provice technical justficaricn for t*e prcccsed change (s) and de4ceate me secticnist cl tre sat, Analysis Reccrt ander Flant Technical Specthcatents) atfMtec ty the prc;osed changeise p
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Jusufication fer Frcxsed Change:
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j                                j     ht&P Fespcnsitie Engr. Signature                                 ate 1
4 3                        3. Oces tre subject cl(Ns revi w conduct tests a-4cr er;+ntr,ents net ces:r.:ed in tne FSAR1 lf               ''
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0 4 Oces tre s K! ClINs review require a change to the TKhne Sm:5ca:ces?                                          ;
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il res:cnse to cne (1) er mere el questens 1 thru 4 are aff.rmatrve, t*e c:gnizant Engieces i;a -
)                                  previci (Khnical ust15 J   cation !ct the prcccs&d change (s) anc clAneate the sutients: ci tre mat 4 Analysis Repcrt and er Flant TKhnical ScMificaten(s) aff Kted by tne pt::osed changeis
!                       Justheatien fer Fr:rnsed Change:
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SOUTH TEXAS PROJECT ELEC.TRIC G' ENERATING STATION 10CFR50.59 DETERMINATION REVIEW FORM c
Faye     I  cf ]
Cr girati*g Cccurrent No.        fC/2. N4sP- 03r31.                     Re,is,en ne.
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: 2. Cces tre sut;xt ci tras rev ow invcive a charge to me pocMuros as C4scr.:e<:in me FSAR$
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APPENDIX D, ATTACHMENT 2 Modification to Level Indication Equipment for Vaste Evaporator Condensate Tanks The Liquid Waste Processing System collects and processes radioactive liquid waste generated during plant operation and reduces radioactivity and chemical content to acceptable levels for discharge or recycling.
The Liquid Waste Processing System consists of the Waste Holdup Tank, which collects radioactive liquid from the Reactor Coolant Drain Tank and the Reactor Containment Building sumps, the Floor Drain Tank, which collects liquids from floor drains in the Mechanical Auxiliary Building, and the Condensate Polishing Regenerative Waste Collection Tank, which collects radioactive laboratory drains, and serves as an alternate tank for floor drains. Also included in this system is the Laundry and Hot Shower Tank, which collects water from the hot shower facility.
These tanks are all equipped with eductors to ensure proper mixing prior to transfer. The liquid collected in these tanks may be processed in accordance with the Process Control Program. This program selects the optimum processing mode, filtration, domineralization, evaporation, or a combination of the three. After processing by one of these methods, the liquid is then collected in one of six Waste Monitor Tanks and analyzed prior to discharge.
These tanks are all equipped with eductors to ensure proper mixing prior to transfer. The liquid collected in these tanks may be processed in accordance with the Process Control Program. This program selects the optimum mode for processing, filtration, demineralization, evaporation, or a combination of the three. After processing by one of these methods, the liquid is then collected in one of six Waste Monitor Tanks and analyzed prior to discharge.
This change involved the level indication equipment for the Waste Evaporator Condensate Tanks. These tanks collect distillate from the waste evtporator and this water may be further processed as reactor makeup water or disposed of as liquid waste. Originally, the instruments were attached to atmosphere on the low pressure side of the transmitter, with the high pressure side connected to the tank bottom. Pressure changes in the vapor space at the top of the tank due to condensation in the plant vent header caused erroneous readings. The arrangement was modified to connect the low pressure side of the level transmitter to the vapor space at tha top of the tank, thus eliminating the effect of any pressure variations that might occur.
Attached are copies of the Field Change Requesta that authorized this change, along with the respective 10CFR50.59 Determination Review Form.
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SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION 10CFR50.59 DETERMINATION REVIEW FORM i
Page.j _ c#
or,ginating Cec. rrent No.                    N 6 M -O l d 61                      Revisica No.                                                       O i                           ire               Fc E.       Fof2-           Mz so 9 Fo so z.# I / * -z-Oneen ene:( i Prece:wre f i Plant Mec.hcatien                        ([Otner Cneca ene.(              Cualef Relatec         f f[Nce. quality R4'ated 1.
Cees tne sutjec: cf tnis review invclve a change to the facilty as cascncte n tne FSAA7
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        ...a-I SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION                                                        !
 !                             10CFR50.59 DETERMINATION REVIEW FORM                                                        !
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pa;. i   ef I cr>; cat,es cceeet No.            FC/2 /h38-03/3/ n ,is,en so.            e I t'e         NA/7              /e?MM bMA./fd WoA)f l
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[             CPtci cre:s i Precec6te L\1 Plant Meciheat:en C*MtCet:( l Cuahr/ RelatM             ()g Ncequahty Asiat>d
: 1. Oces (Pe $$tjMt Cf IFil review invcive a Change to the facdity 43 Cel0**H in (*e FSAR?
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: 2. Cces the sutikt cf this rev'e* invclve a enarge to the pecesures as C4ser:M in the *SAR$
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Anatylis EtC<rt anC Cr F'&nt TMhnical SC+C:hCaDColt) aff MtM ty the Gr;;<lM Cnanqe 16 Justication fe< Fr:c<se Change:
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APPENDIX D, ATTACHMENT 3 Modification to .tevel 2ndication Equipment for Waste Evaporator Condensate Tanks A l' ORC Review was not required for this design changw.
                                                                                                                                                                                         .)
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APPENDIX D, ATTACFMENT 4 Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks The     ate Evaporator Condensate Tank Condensate level instrument was or',tually installed with the low pressure side of the transmitter connected to atmosphere. This transmitter was calibrated based on atmos:here, however the vapor space at the top of the tank experiences pressure variations due to condensation of liquid in the plant vent header that is connected to this tank. This design change added piping to connect the low pressure side of the
  -level transmitter to the vapor space of the tank, thus eliminating the effect of any pressure variations that might occur in the tank. Two new isolation valves, one for each low pressure side line was also added. This change was documented in the applicable Field Change Request.
i 1
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APPENDIX D, ATTACHMENT S Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks This change allows proper level indication in the Waste Evaporator condensate Tank and will cause no additional exposure to plant personnel.
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                                                                      ~ ~ - - "#v~ ~~~-V '

APPENDIX D, ATTACHMENT 6 Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks This change allows proper level-indication in the Waste Evaporator Condensate Tank and it does not change the amount or chemistry of any waste stream in the Liquid Waste Processing System. This modification does not change the amount of liquid and gaseous effluents, and solid waste predicted in the License application and amendments.
1 l

APPENDIX D, ATTACHMENT 7 Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks This modification allows proper level indication.in the Waste Evaporator Condensate Tanks and does not affect the amount or radiochemistry of any waste stream. This modification will not result in a change to the expected maximum exposures to a member of the public .a the UNRESTRICTED AREA and to the general population as previously estimated in the License application and amendments.
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  - , - - - - ,    -,,               ,   ,      ...     - . . . - - , , - . . - - - . . - - ~ .-nw- ,+.   - --

APPENDIX D, ATTACHMENT 8-Modification to Level Indication Equipment for Waste Evaporator Condensate Tanks This item is not applicable. This is the initial reporting period for the South Texas Project Electric Generating Station.
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_ _ - _ . _ _ -. .__ _._,__- . . . - ~ , , , , -                .   . . _ - - _ _ _ _ _ _ _ _ , _ _ _ _ _ _ .        _ . . _ _ _ . _ . _ . . _ _ , , . - _ . _ _ . _    .... _

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APPENDIX E Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Wasta Process Systen Pump Seal Water Skid
: a. Attachment 1 - A summary of the evaluation that led to the determination that the change could be made in accordance with             I 10CFR50.59.
: b. Attachment 2 - A detailed description of the equipment, components,        l and processes involved and the interfaces with other plant systems.        J
: c. Attachment 3 - Documentation of the fact that the charge was reviewed and approved by the Plant Operations Review Committee (PORC).
: d. Attachment 4 - Sufficient detailed information to totally support the reason for the change without benefit of additional er supplemental in f o rmat ion ,
: e. Attachment 5 - An estimate of the exposure to plant personnel as a result of the change.
: f. Attachment 6 - An evaluation of the change, which shows the predicted release of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments.
l
: g. Attachment 7 - An evaluation of the change, which shows the expected       '
maximum exposure to a member of the public in the UNRESTRICTED AREA ar.d to the general population that dif fer f rom those previously estimated in the License application and amendments.
: h. Attachment 8 - A comparison of the predicted releases of radioactive materials, in liquid and gaseous offluents and solid waste, to the actual release for the period prior to when the changes are to be made.
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APPENDIX E, ATTACHMENT 1 Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid.
A 10CFR50.59 Determination Review. Form was completed by Support Engineering.
It was determined that there were no unreviewed safety questions and no further action was required. See attached forms for detail.
t t

SOUTH TEXAS PROJECT ELECTR.'O GENERATING STATION 10CFR50oS9 DETERMINATION REVIEW FORM O
Page      I   of        I s
Onginating Cocument No.            / - T - /2 5 7" - 0 4 A s'              Revision No.      00 Title         DELETF        t sAll)dR COPPLIED
                                                        /
FLD tJ (' PRE 550M           S t.Jr rc HES Check one:( ) Frecedure (Tplant Modificaten                  ( ) Other ChecP cne:( ) Cuajity Related           (Menquahty Re:ated                    -
1.
Oces tne subject cf this review invcive a change to the facility as descnbed in the FSAR7 hl h 6b A                                /                    l Chi      7 SEC Ccgnizant Engr.Tgnaturs                                    Oate 2.
Oces the subject cf this review invcive a change to the procedures as descnbed in the FSAR?
YGM C-.bw              o (Q sql s]            II ''              '
* HL&P Respcnsible Engr. Signature                                 Cate 3.
Oces the subject cf this review cenduct te'ts an6cr exp+nments net desenbed in the FSAR?
Jr'            Cb       m EEC Ccgnizant Engr. Sfnature 0                     /Cb?k7 I    '    '
Cate a
Cces tne subject cf this review require a change to the Technical Sp+c 5catens?
su        C'. . )c%                                            it{qls)            II    0'
* hl&P Fescensicle Engr. Signature                                 Cato l
Nets:
Il resLense to cne (1) cr mere cf quescens 1 thru 4 are affirmatue, the ccgnizant Engtreer 5,24 provice teshnica] justificar:cn for the prc::csed change (s) and dekneate the sect:en(s) cf the Safe:y Analysis Repcrt ancor Flant Technical Scec:licatien(s) affected by tne pre;osed changeist I
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Justif: cation fer Precosed Change:                          -
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DESIGN CHECKLIST (DCL)O Initiating Change Document No.
Title                                                  ,                                I f c T;n4F G Doc.: ly:tprG 1/nmn uppusD Fino r /WSNRf Ewe.wis Rev. oc        Page 1       Of 2 Start up 5ystem:              HLo S                Titie;    lico,s & cre Gusrpm This checklist must be attached to the initiating change document during the entire review and approval process up to the point ofissuance by Project Document Control. Reference PED-041.
AFFECTED 00CUMENi$ WHICH REQUIRE REVISION                   TURNED AFFECTED                       POTENTIALLY                          (uus. ;roy,e ,;,g( N""(' N -)                          TEP YES NO                AFFECTED DOCUMENTS oOCU..'ENT NO. (o R SEC7;ON)                 l REV. lY lN*
I      I Licensing Documents
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                         '                                                                                                     j       j
                       -         FSAR j      j
                      ,-         FHAR l       l ER
                       /'/       Technical 5pecifications                                                                      l      l (Plant)                                                                                       l Deficiency Evaluation                                                                            l      l
          -       ]'          Report (DER)                                                                                     l      l Design Criteria                                        -                                l         l      l System Descriptions                                                                     I        I      I    -
1         I      I Design Calculations                                                                    l         I      l l         l      l Specifications                                                                         l         l      l l         l      l
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ASME Design Specifications                                                                                   !     I
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_        _,           Stress Report                                                                                   l      l
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N 5 Package Z _[/ (Piping & Supports)                                                                                             l      l       l
__                    Penetration 5eals                                                                               !      I       '
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___                    Design Drawings l      l l
l l         l      l ORIG.
Date //
JECh)40          -       DATE          l'jPE      C                 DATE          E-)
5TP 1312 (11ees)

l 4
APPENDIX E, ATTACHMENT 2 Deletion of Vendor Supplied Flow and. Pressure Switches on Liquid Waste Process System Pump Seal Water Skid The Liquid Waste Processing System collects and processes radioactive liquid    )
wastes generated during plant operation and reduces radioactivity and chemical  i content to acceptable levels for discharge or recycling.                        l The Liquid Waste Processing System consists of the waste Holdup Tank, which     i collects radioactive liquid from the Reactor Coolant Drain Tank and the Reactor Containment Building sumps, the Floor Drain Tank, which collects        i liquids from floor drains in the Mechanical Auxiliary Building, the Condensate  1 Polishing Regenerative Waste Collection Tank, wnich collects radioactive laboratory drains, and serves as an alternate tank for floor drains.       Also included in the system is the Laundry and Hot Shower Tank, which collects water from the hot shower facility.
J These tanks are all equipped with eductors to ensure proper mixing prior to     l transfer. The liquid collected in these tanks may be processed in accordance with the Process Control Program. This program selects the optimum mode for processing, filtration, domineralization, evaporation, or a combination of the three. After processing by one of these methods, the liquid is then collected in one of six Weste Monitor Tanks and analyzed prior to discharge.
This change involved the seal water system which supplies seal water to the pumpa in the Liquid Waste Processing System.      Vendor supplied flow and pressure switches were supplied with the seal water pump and tank skid. These switchea supplied alarm functions that were redundant to pressure indication end flow indication and control provided in the remainder of the system. As a result, nuisance alarms were received at the Radwaste Control Panel whenever the system was operated. In order to solve this problem, the control and l
a2 arm functions of these vendor supplied switches were deleted. (See attached work documentation and 10CFR50.59 Review Determination Form) 1
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                                                                                                                                       \M W38     i SOUTH TEXAS PROJECT                                ces wo.
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ORIGINATING DISCIPLINE:                     ddM7~ROLS                                     TREND CODE:         6-/2 RESPONSIBLE' ENGINEER:                 A M MeuM                                                        DATE: y/e/T7 SEIS1IC CAT:             A                  PCLASS CF WORX TO BE PfM0mED:                h FSM CHMCE RfCUIRED:        YES h NO        SUILDINC MEA:        N88
       $7MTUP SYSTEMS /SUB SYSTEMS AFFECTED:            Mdb 8 ASIS OF CHANGE:[$k. /35*6                                 b xo.                 Ft. G M C 4 1tg                   MM                                bPUwCHLISTwo. UOLot-t03 CLIENT                                                       OTHEA CHANGE CATEGORY:               BACK CH/RCt            db                                 OTHER ALAR M Fu,Mc.TjoQ FROM TITLE OF CHANGE:             Dac r/on CPs ysNDeR SUPPUGb PLC H fMirCHGQ A&
PRES $ v R 5     fy) ITCHES CN           i~NS LWPc             PUMP st*AL VI,+ r;?R S <t b .
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PARTIAL PACKAGE:                  yts       %            SEQUENCE:             //#T DISCIPLINE CCORDINATION hp             No           b4                    10/ 3 0l$7                         A/M ELECfMCid. ECS                                      DATE            CIVIL ECS
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PtMT DESICW ECS N/A                                                 h                    k                      1-        t'l DATE            CGTROLS ECS                                    CATE E0 ECS                                              MIE             PSSC ECS                                       DATE APPROVALS:                                                                              ,_% LO O C h m e r m j CMG8xATIWC OISCIPLIkE ECS A}                     CATE  MIM7                 CmHCt% TICS CGTE COEIMAim W S**
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               ;JDZ1 F1ELO NOTIFICATION OF CHANGE COMPLETION:                                              FmMNCE fm PMTIN. CQiftETICN:
ORCMflATICH SICHArtFf                                       DATE ENGINEERING CLOSE-0UT:                                                         LMIT.jiE ECUIV4 LW:
2-3-FS 7*- C 486 CRIG2NATINC 01SCIPLINE ECS                                  DATE j   _     79 7
                                                    ,,          n,<,.-                -
STP12?9(10/t6) 0-30                               ,,,,    yr          L-   &'ggg..
                                                               . . . . 01
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CCP NO. I~ I~IS I ~ l   REV 0 0 SOUTH TEXAS PROJECT CONFIGURATION CONTROL PACKAGE CONTENTS REQUIRED-THIS REV.
: 1. DESIGN CHANGE BASIS                                                            YES@        NO
: 2. FSAR CHANGE REQUEST PACKAGE                                                     YESU        N0
: 3. tiATERIALS SHEET                                                               YES          NO @
: 4. DOCUMENTATION LIST                                                            YES           NO X-FCR'S INCCRPORATED INTO THIS PACKAGE:
X-FCR NOS.:           I e
e                                        *WW STP1281(8/85)030

SOUTH TEXAS ~ PRO' JECT DESIGN CHANGE BA$IS cce no. /-J-fS T~- 0485 cce u v.       00
     - ossearptICM & cHMCE pri       /       7 4 I
Information provided in the Design Change Basis is provided for information only to enhance the definition of the design change as provided in the attached drawings. Installation and QC verification is to be accomplished in accordance with the drawings only. No XFCR's will be accepted against the Design Change Basis.
T*H I s     CCP           ro     D5La rE is                      THE       cotlrRet.          AND nenen               t= vacrew:
Of      TMC     I"0L L o urNG     VENDO R      SUPPL /E p           tilt r % U M C /J r $        Ort Tt f                    PUMP L A!PS                $EAL        AI A 7~dR       SKID;                                                        L HIal-e_       ,
fis-s 4928                            NtaL-ers - s929 e         _
4930                                                     4.931 l
9932                                                     4933 4939                                                     4935 493(o                                                    4937 4 938                                                    4933 4940                                                     494/
49+2                                                   A 943
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BASIS OF CHANGE These switches are not interlocked with thier corresponding pump and therefore cause nuisance alarms.             The switches are also redundant to other oressure and ficw switches in the system.
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CCP NO.
I~         -0485             REV. 00 SOUTH TEXAS PROJECT IN TERIti
                                                                                                    ^
ORAVING CHANGE NOTICE                                  o w tw u sER        5 DEI  EV-
                                                                                         "O~  #               *   '
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REASON FOR CHANGE (Please ce specific)                                Nut t/7 />( E       Ac Aa Af s               l CENE RA rd b           By SK10 r roun rs b                   Pnergva g          Anp Pt o w swre ngs .
(REF.           enRs          is 58         AND 1595) .
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SOUTH TEXAS PROJECT                                            CD) NO       /-T-R7- O M S                                       Rgy, 00 INTERIM                                                                                                                * *V -
DRAWING CHANGE NOTICE                                                                                          SHEET      REY.
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1 SOUTH TEXAS PROJECT                      CCP NO.      I- J -IS I- 0486              REV. 0 0 j
OC" CCkV-IN TERIt1 ORAWING CHANGE NOTICE                            e w ig u nga         satt  uv.
W. W. M. MV.-l CCM ho.
(IOCN)
GR30 9242 2 SI                  2 10CM M 8ER                ISSUED CATE STMTUP SYSTD15 /(ffCTED:
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CCP NuM*ER: 1JFST0485 REY: 00                 DATE INI TI A TED: 030487        INITIATED ST: C.CTRAN           RESPONSIBLE ENT5?T: C03YA%LS
* MILCSTONE 1 : 000000               NEW COMPONENTS A00E0 TO EE580 OATA SASE                                               1492}001 MILESTONE 2: 080467                                                                                                ~                                       __                         j MILESTONE ) : OJ0537               MS PLACEO AGAIAST ALL AFFECTED COMPONENTS IN EE580 DATA SASE ALL AFFECTED CCMPONENTS COPIED FROM EE580 OATA SASE TO CCP FILE C d b /~         '[b/ -                                     1 MILESTONE 4 : 050547 MILLSTONC 5 : 000000 CCP FILE UPDATED TO REFLECT CMANGES                                                   CCP NU.                              RE3f. ()(7                 )
MILESTONE o: 0J0000                RLSPON516LE ENTITY IDENTIFIED eY J085ITEJ (NGINEERING NOTIFIED                                                                                      ;
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WORK ORDER RECEIVED ST ENGINEERING MILESTON! 7: 000000                EE5SO DATA B ASE UPDA T[D                                                                                                                           [
MILESTONE J : 90000G               CCP Voluto                                                                                                                                      *t a
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N1WL02C250     Os 5R *C N 5 WL IJF5T04SS        Rv OR 9EWLO202 00 C= 486 01 CH212 N1WLILP189 XXXXXX N1WLZLP710       N1WLO2C258 1 N1WLG2C258 2 ahte OPS AC*
C0       MM                                                                                                                                              't; NI                                                                                                                                                          1 V OELETLD           N1XM30T5tB      N1XM50T58C      N1XM30T5SG    NIXM30TSAA I
NIXM3075VA          N1XM10TSV8     N1XM10T5AG V N1XN10T5AC        N1XM1075tE      N1XM10T58F      N1XM10T5dG    NIXMIDTSAT      N1XM10T5A5 0
V N1XM1CTSAN        N1XMICTSAO                                                                        N1XM1DTSAV     N1 X M1015 AU NIXM1CTSA8      N1XM1CTSAC    NIXMIMT5AE      NIXM1HTSAF V NIXN1NTSAC        NIXM1MTSAF                                                                       N1XM1MTSAG      N 1 X;41 NY S A S N1XMIMR5023     DELETED-1                                                                                                    l 1 SPARE ---    SEE TERMINATION C ARD                                                                                                                             o 2 CHANGE 0 PER CCT 3365 N1WL4sC15t     dJ SR *C N 5 WL 9EWL4601 04 C= 4 8 5 01 CH312 N1WLZLP189 IJF5T04d5        RV OR        XXXXXX                                                 N1WLZLP710       N 1 WL 46C 15 E 1 N1WL46C15E 2 able OPS AC*
CD       Mn NI V OtLLTLD           N1XM30TSE8     N1XM30758C       N1XM30T5BG
                           'V N1MM10TSAQ                                                       N1XM30TSAA      N1XM3DT5VA         N1XM10TSV8 NIXMIDT5HE     N1XM10T58F       NIXMIDTSOC    N1XM10T5AT                                        N1XM10T5AG V N1XMICTSAN        N1XM1CT5A0     N1XM1CT5AD                                     N1XMIDT5A5          N1 XM10 TSA V  N1XMIDT5AU N1XM1CTSAC   N1XMlHT5At       N1XM1HT5AF V N1XMINT5AC         N1XM1MT54F                                                                       NIXM1HT5AG      N1XMINT5A8 N1XM1MR5023 DELETE 0-1 f $PAcf --- SEE TERMINA110N CARD                                                                                                                                 b 2 CHANCEO PER CCT 3365,FCR SE0951 N1bl40C25E     07 3R *CN 5 WL 95WL4601 Of C= 488 01 CN212 N1WLZLP189                                                                                                                  /
IJFST04?5         dV OR        XXXXXX                                                 N1WLZLP710       N1WL46C2SE 1 N1WL46C25E 2
                                                         *NLP OPS AC*
CO       MM Nt V DELETED           N1XN3CT588      NIXM)DT58C      N1XM30Y58G    N1XM30TSAA V NIXM10TSAQ        NIXM10TSEE      N 1XMI DT 5 8 F N1XM10T5sG N 1 X M 30 T $V A   NIXM10TSV8     NIXM10T5AG V NIXMICTSAN        N1XMICTSAD NIXM1DTSAT      N1 XM10 T5A 5       NIXMIDTSAV NIXM1CT5A4       M1XMICTSAC    N1XM1H15AE                                         N1XM10TSAU                                  i Y NIXHINTSAC        NIXM1MT54F      N1XM1MR5023                                   N1XM1HT5AF          N1XM1HTSAG     N1XM1NTSAS OELETED-1 1 SPAst --- SEE YtRMINATION CAND 2 CMANGED PER CCT 3365 N1WL47C15A     10 SR *C N 5 WL OEWL4701 01 C= 468 Of CH212 N1WLZLP189                                                                                                                   -
IJF5Td483        RV 04        XXXXXX       *MLP OPS AC*                               N1WLILP710      N1WL47C15A 1 N1WL47C15A 2                                                l' CD       MN
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N1 Y OtLETED           N1XM30T588     NIXM30T58C       NIXM30TSSG    N1 X M 3015 A A N1XM3075VA V NIXMIDT5AQ         N1XMIDTisE     N1XM10Y58F       NIXMIDTidG                                        N1XM10T5Y8     N1XM1DTSAC V NIXMICTSAN                                                       N1XM10TSAT      N1XM1075A5         N1XMID T5 A V N1XMIC TSAD    N1XMICTSAS       N1XM1CTSAC                                                       N1XM10TSAU                                 3 Y N1XMINTSAC         N1XMihTSAF                                     N1XM1H15AE      N1XM1HTSAF          N1XM1HYSAC NIXM1MR5023      DELETED-1                                                        NIXMINT5As
* 1 SPARE    ---
5tC TERMINATION CARD                                                                                                                            .
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14                                                                                                                                                          CCP NO./J-MEOM__ REv. 00' 2 CHANGE 0 PER CCT 33c5 NSWL47C254      07 SR *CN 5 WL OEWL4?O1 01 C= 431 01 CH212 N1WLILP189 IJF580485         RV OR          XXXXXX          *HLP UPS ace N1WLILP710     N 1WL 47C 2 5 A 1 N1 WL47C25 A 2 CO        NN NI V OtLETto             N1XM30T52R        N1XN30T50C N1XM30T55G  N1XM30754A     N1XM30TSVA V NIXMIDT54Q          NIXM10T5dE       N1XM10T5BF     N1XM10T5BG N1XM10T5VB        N1 XM 10 T5 AG V NIXNICT5AN                                                      N1XM10754T     N1XM10T5A$       N 1 X M10 T5 A V N1 XMIC T S AD   N1XM1CT5AO     NIXM1CT5AC  N1XM1MT54E                                        N1XM10TSAU V NIXMINTSAC          N1XM1M TS AF                                               N1XM1HTSAF       N1XM1HTSAG        N1XM1NTSAB 7*                                                                                                    N1XM1MR5023    DELETED-1 1 SPARi --- SEE TENMINATION CARD 2 CHANGc0 PER CCT 3365 N1WL47035A     07 54 *C N 5 WL           9EWL4701 Of C= 431 01 7+                                            1JF5T0435         RV DR           XXXXXX CN212 N1WLILP189     N1WLZLP710    N1WL 47C 354 1 N1WL47C35A 2
                                                                                               *eLP DPS AC
* CO         MN NI W DELLTLD             N1XM30T580        NIXM3DT5BC     N1XM30T56C  NIXM3DT5AA     N1XM30T5VA V NIXM10T5AC          N1XM10TiuE        N1XM10TSBF    N1XM10T5SG                                  N1XM10T5Vb        N1XM10T$AG V NIXMICT54N                                                       N1XM10T541     N1XM10T5A5      N1XMIUTSAY N1XMICT5A0        N1XM1CT5Ab    N1XM1CT5AC                                                     N1XMIDTSAU V NIXMINT5AC                                                      N1MM1HTSAE      N1XM1HTSAF      N1XM1HT5AG NIXMINTSAF        HIXM1M45023   OELETEO-1                                                     N1XMINTSAE 1 SPARE --- SEE TtRMINATION C ARD 2 CHANGEO PER CCT 3365 M1ul500151      II SR *C N $ WL 9 E W L5 0 01 04 C= 4ea of CH212 N1WLZLPIR9 1JF5TO435         RV DR          XXXXXX          *HLP OPS AC*                          N1WLZLP710    N1WL50C15T 1 N1WL50C15T 2 CO        VM N1 V OtLETED             NIXN30TSES        N1XM10T55C    N1XM30T5hG  N1XM 3075 A A  N1XM3DTSVA V NIMM10T5AQ          N1XM10T58E       N1XM10TSRF     N1XMIDT58G                                  N1XM10TSV5        N1XM10T5AG V NI XMIC T SA N                                                  N1XM10T5AT      N1XM10T5A5      N1XM10T5AV N1 XNIC T5 AD     NIXM1CT5AD    N1XM1CTSAC                                                    N1XM10TS AU Y NIXMINT5AC          N1XMIMT5AF                                  NIXM1MT5AE      N1XM1HTSAF      N1XM1HT5AG NIXM1MR5023    OELETEO-1                                                     N1XMINTSAB 1 SPARE --- SEL TERMINATION CARD 2 CHANGED PER CCT 3365,FCR SE0955 N1WLd2C15A     07 SR *{ N 5 WL 9EWLE201 00 C= 468 01 CN 312 N1WLILP189 1JF5T0415        RV 04          XXXXXX          *HLP OPS AC*                          N1WLZLP710     N 1 WL S 2C 154 1 N1WL82C154 2 CD        MM NK V UELETca              NIXM10T5de       N1XM30TSMC     N1XM3nT5BG  N1XM 30T S A A N1XM30TSVA V NIXN10T5AQ          N1XM10T580        NIXM10TSDF     N1XM10T58G                                  N1XM10T5VB        N1 XM 10 T S AG V NIXMICT5AN                                                       N1XM10TSA1     N1XM10T5A$       N I XMID T5 A V N1XM1C T S AO     N1XM1CTSAB    N1XMICT5AC   N1XM1HT54E                                        NIXM1075AU V NIXMINTSAC          N I XMIM T5 AF                                              N1XM1HT5AF       N1XM1HTSAG        NIXMINTSAS N1XM1MR5023   OELETED-1 1 5 PARE    ---
SEE TERMINATION C add 2 CHANGE 0 PER CCT 3365 END OF THE REPO4T e eee+++++++e++e++++++e++++++++++++++++
                                   *                                                                                             +
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                                                                                                                                 +
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SELECTED SY: MS1JFST0485 N1WLO2C255 1 05 SR *C N 5 WL 9EuLO202 00 C=                     2 01 CM212 N1WLZLP189     N1WLO2C255 1JF5T0435        TV DR          XXXXXX          *NLP OP5 AC*
CD        MM NE X1          nK                21         WH 1 SPARE --- DISCONNECT ALL WIRES N1WLO2025e 2 03 3R *C N 5 WL 9EWLO202 00 C=
1JF5T0415        Tv OR          XkXXXX 2 01 (N212 N1WLILP710     N1WLO2C25n
                                                                                             *HLP OPS AC*
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N1WL40C15E 1 05 SR *CN 5 WL 9EWL4601 04 C=                                  2 01 CH312 N1WLZLP189 1JFST0435                Tv OR            xXXXxx           *NLP OP5 AC*
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 "                                2 CHANCE 0 PER FCR 5000953,5U REu 86-385 N1WL46C+5E 2 05 54 *C N 5 WL 9EWL4601 04 C=
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                                                                      *HLP OPS AC*
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CD          NN NI X1           BK                   't         WH 01WL46C25E 2 03 13R           SPARE --- DISCONNECT ALL WIRLS
                                        *C N 5 WL DEWL4C01 01 C=
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CD         MM NI X1           DK                   21          WH 1 SPARE      ---
DISCONNECT ALL WIRES 01WL47C15A 1 04 SR aC N 5 W( 9EWL4701 01 C=                                 2 01 CN212 N1WLZLP189 1JF5T0485                 Tv OR           KmXXxx                                                  N1WL47C15A
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CD          NM NI X1           FK                   1          WH 1 SPARE      ---
OI5 CONNECT ALL WI RE S 01WL47C15A 2 08 SR *C N 5 WL                        9LWL4701 01 C=           2 01 CH212 N1WLZLP710 1JFST0435                 Tv 09           xxxXXx           *NLP OP5 AC*
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CO          NM NI X1           BK                  1           WH 1 SPARE --- DISCONNECT aLL WIRES                                                                             '
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N1WLJ2C15A 1 U3 1R *C N 5 WL 9EWL8201 00 C=               3 01 CH312 N1WLlLP189 N 1WL U 2C15 A l        1JF5T0435       Tv OR        xxxxxx       *HLP OPS ace l                            CD      NM NL
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SOUTH TEXAS PROJECT ELECTR'O GENERATING STATION 10CFR50.59 DETERMINATION REVIEW FORM Page    I   cf     )
b Onginatirg Cocument No.            1 - T - /2 5 T - 0 4 se '             RJvision No. OO Titfe         T)EwiT        VsAIOdd CuffuGD             FLCM / PRES 50M               StJ rrc HES Check one:( ) Precedure (dant Modificanen                  ( ) Other Check ene:( ) Cuahty Related           (#6nquahty Related 1.
Ocos tre subject of this review involve a change to the facility as descnted in the FSAR?
b lY Sk               du                /                  tc l2f      7 i
SEC Ccsnizant Engr.Tgnature                                   Cate 2.
Oces the subject cf tnis review invcive a enange to the crocedures as descr. bed in the FSAR?
NGa C. dem                                                    n(nl vi             ( )Yes       e i No HL&P Respcnsible Engt. Signature                              Cate
: 3.                  l Cees tre st.t    ect of this review cencuct tests ander exc+nments not desenbed in the FSA Gb         e EEC Cognizant Engr. Sig' nature Yb                  XfHk7 Cate 4
Cces tne subject cf this review require a change to the Technical SpeciSca cns?
LGuJ C. . ds_.,                                                               ( ) es      U it(i1I O MLAP Fescensitie Engr. Signavre                                Cate Nete:
                             ;f resocnse to cne (1) cr mere cf questons 1 thru 4 are afttmatue. tre cognizant Engireer 1sea:
crevice technical justficaton fer the cr:cesed change (s) and cehneate the secten(si et tne Safe:y Ana!ysis Pecert anc er Flant Techrucal SceciHcaten(s) affected by tne crecesec changeis
                 .'ustf; cat:en fer Fr::osed Change:
FO Fi1 t!CC62 C6 3L A

DESIGN CHECKLIST (DCL)
Initiating Change Document No.
Title                                                                                  I-7 p c 71.n gp q Doc.; Pat ?rG !/A&m D9pusD Feu r, PMituRf Sn mes Rev. oc         Page 1      Of 2 Start up 5ystem:        IJLo S

==Title:==
/ gy ,, ,5 Macr # G urren This checklist must be attached to the initiating change document during the entire review and approval process up to the point ofissuance by Project Document Control. Reference PED 041.
AFFECTED
                                                                  '              "      "'""        '   "0"                        '
POTENTIALLY                            (Must;rovide spet:fic Refeteace No)                     TVER YES NO                                                                                                                 To HL&P AFFECTED DOCUMENTS DOCU3.'!NT NO- (O R s!CT:O N)                  l RIV. lY lN l
d, licensing        Documents                                                                               l FSAR
              ,-        FHAR
* l
      -      ~//        ER Technical 5pecifications                                                                          l (Plant)                                                                                           l Deficiency Evaluation       -
Report (DER)                                                                                        l       l
                 /                                                                                                                   -
[      Design Criteria I        !       l System Descriptions                                                                         I        I       I I       I          i Design Calculations                                                                                  l      l          ,
l      l           !
Specifications                                                                                      l       l l       1
                /                                                                                                       I       I
{/        -
ASME Design Specifications                                                                                      l       I l       l Stress Report                                                                                       l       l
                ' N-5 Package                                                                                           !       !
l
   ~ ]/ (Piping & Supports) l l
Penetration Seals                                                                                   l       l l       l l       l I       i Design Drawings                                                                                     l       l l
l l       l ORIG.                           Date // ' / EG I
                                                    )hD       -         DATE      N T]PE        h                  DATE       ,          ;
I
 $TP 1332 (11,85}                                                                                                                        I

I l
I APPENDIX E, ATTACHMENT 3 Deletion.of Vendor Supplied Flow and Pressure' Switches on Liquid Waste Process System Pump Seal Water Skid ~
A PORC Review was not required for this design change.
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l APPENDIX E ATTACHHENT 4 Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid The Liquid Waste Processing System (LWPS) seal water system supplies seal water to the following pumps in the LWPS: Waste Evaporator Recirculation Pump, Waste Evaporator Auxiliary Feed Pump, Waste Evaporator Concentrates Transfer Pump, Condensate Polishing Regenerative Waste Collection Tank Pump, )
Laundry and Hot Shower Tank Pump, Spent Resin Sluice Pump, Waste Holdup Tank '
Pump, Spent Resin Transfer Pump, Floor Drain Tank Pump, Low Activity Spent Resin Transfer Pump, and the Low Activity Spent Resin Sluice Pump. Vendor    j supplied flow switches provided a low flow alarm and pump cutoff, and vendor i supplied pressure switches supplied a low pressure alarm. The low flow pump  !
cutoff was already controlled by field installed flow switches, the low pressure alarms were unnecessary. This arrangement resulted in nuisance      i alarms each time the system was secured. Adequate protection is provided by  I these field installed pressure switches making the vendor supplied switches unnecessary. These switches were removed by the associated work document.
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APPENDIX E, ATTACHMENT 5 Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid This change deletes nuisance alarms associated with flow and pressure switches in the LWPS seal water system. Adequate protection is still provided by field installed. flow switches. This change will not result in an additional exposure to plant personnel.
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I APPENDIX E, ATTACHMENT 6 Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid This change deletes nuisance alarms associated with the LWPS seal water system and it does not change the amount or chemistry of any waste stream in the Liquid Waste Processing System. Adequate protection is still provided by_
field installed flow switches in this system. This modification does not change the amount of liquid and gaseous effluents, and solid waste predicted in the License application and amendments.
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l l
l APPENDIX E, ATTACHMENT 7 Deletion     Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Scal Water Skid               l l
This modification deletes nuisance alarms associated with the LWPS seal water i system and does not affect the amount or radiochemistry of any waste stream. l Adequate protection is provided by field installed flow switches in this system. This modification will not result in a change to the expected maximum exposures to a member of the public in the UNRESTRICTED AREA and to the       l general population as previously est1 mated in the License application and    ,
amendments.                                                                   I l
l l

r-l APPENDIX E, ATTACHMENT 8 Deletion of Vendor Supplied Flow and Pressure Switches on Liquid Waste Process System Pump Seal Water Skid This item is not applicable. This is the initial reporting period for the South Texas Project Electric Generating Station.
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i

APPENDIX F r
Addition of an Isolok Sampler for Spent Rosin Discharge                  ,
to Hobile Colidification Unit
: a. Attachment 1 - A summary of the evaluation that led to the                i determination that the change could be made in accordance with 10CFR50.59.
. b. Attachment 2 - A detailed description of the equipment, components, I
and processes involved and the interfaces with other plant systems.
: c. Attachment 3 - Documentation of the fact that tre change was reviewed and approved by the Plant Operations Review Committee (PORC).
: 4. Attachment 4 - Sufficient detallad information tc tota,iy support the reason for the change without benefit of additional er supplemental information,
: e. Attachment 5 - An estimate of the exposure to plant personnel as a resu)t of the change.
: f. Attachment 6 - An evaluation of the change, which shows the predicted      !
release of radioactive materials in liquid and gaseous effluents and/or quantity of solid warte that differ from those previously predicted i.. the License application and amendments,
: g. Attachment 7 - An evaluation of the change, shich shows the expected maximum exposure to a member of the public in the UNRESTRICTED AREA and to the general population that differ from those previously estimat:d in the License application and amendments.
: h. Attachment 8 - A comparisen of the predicted releases of radioactive materials, in liquid and gaseous effluents and solid waste, to the actual release for the period prior to when the changes are to be made.

T J
APPENDIX F. ATTACHMENT 1 Addition of an Isolok Sampler for Spent Rosin Discharge to Nobile Solidification Unit L 10CFR50.59 Determination Review Form was completed by Support Engineerlag. '
It was determined that there vers no unreviewed safety questions and no      l further action was required.
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             ,                          10CFR50.59 EVALVATION FORM - TYPICAL Q
(Page 1 of ?)
DESCRIPTION Unit #           l 1    i  PRCCEDURE         t>(j PLMT M00:FICAT10N               I     i      CTHER ORIGINAilNG 00CtKHT NO. CLP               J - M - Fs T- o E4 q              PEY.             n TITLE A DOI TIOhJ          Or        icr o tM    SA M pt nt rD A SPrN~r Ax~cw nisc wn e c-         nno nr in c arm mu r                of caos e x        D isc on>ws c r H cuc- c.onAIemT7 On                 WWH 6UND              FL AN6 83 DESCRlPTION pan eins-                c;A m pt >>ut      C11 p pre n-v F OA                 k,t i a u m m .s        S G~iNL     rm c8 n R om               TC,    im &~~   M nn7-
_ GnL in t ,"~) C rt 77 DAl  i 1 A) / T ~
Yes        No Does the subject of the review involve a change to the facility as                                     -
described in the safety analysis report?                                                     I       i  I,kf 0.00 Does the subject of tnis review involve a enange to tne procedures                                       3 - *M S as described in the safety analysis report?                                                 i       i Q     ,n Does the subject of tnis review propose tne conduct of tests or experitnents not described in tne sa fety analysis report?                                   I        i M
                                                                                                                                    ~
uGM Does the subject of this review require a change to the Plant                                               F' *M 6 Technical Speci fica tion?                                                                    i       i Ooes the proposed change, although not described in the sa fety analysis remet, a ffect items or activities that are described in the safety analysis report?                                                               I       1 IM__
(This form, een completed, shall be retained for the life of the plant.)
I p
,      0191b/0106b                                                             /
n --      -
                                                                                     -,     - - - - +       g--           ,    m --

5         ~
10CFR50.59 EVALUATION FORM - TYPICAL (Page 2 of 2)             Q If any answer is afftmative, perfom an Unrevicwed Safety Question eva                     .
if allred.
requi         answers    are negative, no Unreviewed Safety Question          s evaluation i   ,
Documentation                 of this review must be retained with the ereview packag dCration of the station license.                                           .
Note:                                                                                              .
                              "Safety analysis report" includes the FSAR, safety analyses submi
                   ,          to the NRC in support of their review of the application for an and other license comitments made to the NRC. operating l                                -
Documents Reviewed:
fsme             S rc r. in.4.P ,>I.3      h/ A c _ ta ,s 8 7-m,tu     a Arnvea          ?,
m_
                                                                                                                       'I Prepared by:0S$1cu W          "
Ori gina tor h      %           /
4ln.l3A l
                                                                                ~0 ate Concurrence:                      ._          gos g Department Nnager
                                                        ,,-7       /
F- Z/ - /-f Date i
i Ol91b/0106b
>                                                                                 /

                                                                                              ""           ^"*k                 .
DESIGN CHECKLIST (DCL) 4 initiating Oange Document Na Title                                                                                           CCP 1 -M - FST- Ca ef 9 Doc.: ,gyppyyou op                 j3ct o g Sym pegy Rev. O            Page 1 of 2 Start up System:          1 WSo /

==Title:==
. So t.i r3 uartsnr .Sym This checklist must be attached to the initiating change document during the entire review and approval process up to the point of issuance by Project Document Control, Reference PED 041.
AnEcTED oocuMENT$WHICH REculRE REV AFFECTED                POTENTIALLY                     Wwst provkf t bDeCifiC ttfertott 60.)                 oTHER TOHOP YES             NO AFFECTED DOCUMENTS                                                         REV U TEo cisC.       v oocuMENT No lor sECTioN)
Licensing Documents
                   ,]                  FSAR l   Xj       FHAR (Appendix Bl*
                     ] [I              ER
                              )(       Technical Specifica tions (Prant) g    Deficiency Evaluation Report (DE R)
                   ~
l b               Design Criteria l                   I i         System Descriptions I            I                   i i       i Des gn Calculations                                                   I             !                   I 7             .
_J          Soecifications                                                                                          i              ,
I              :
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                   ] [__.          ASME Design S;ecifications                                                                                          I t
                   --                                                                                                                      i d bl            Stress Report                                                         _
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N 5 Package                                                                                                             i
                   ._               : c ng & Succortsi                                                  l              l                   l               l
                   -               Fe"etrat on Seats                                                            _
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c,A_3 2 9 p o s o 4 R #/              l     A D'                        !               ,
                            -      Des.gn Drawings 7M 9 69 al517 8 SW #>D                      3 p /ocN    WCWOED l            '
ws-les -w coo 7 R             *no c e' o Programat,c Rev.ew Requireo                    tus->cM- w 5'Ola                           A          l                 I l
ffi%  W 5 w s-9 r-Wer+ I /,                            M                       I       l Ong OhE" A                    Date s.2<r# E GSMv                        Da te j.pp.y PE[                         _ __ Da e O O y
CS AD 227 tA i818 871                                                                                                                             !

                     . ..        . . . . . .  .. .......,,,,m              , . . . , , , , ,                                                         ,
DESIGN CHECKLIST (DCL) Continued                                                                                           i R ev.            Pnt 2 cf 2 AFFECTED                 POTENTIALLY                  Ar ricTEo coCL' MENT $ wHICH REovlRE REV.                            TUR         o' tvwn om..a swita ,.v.,.x. m                   oTHER YES         NO AF FECTE0 00CUMENTS                                                                     ^'       '   '
cocVMENT ho lor SECTIONI             REv,                             Y         N m
I3
            -              Instrument index                                                                                                         '
Equipment index                                                                                '
                 -p kN a$ve Master Fife              Scg4974 fy,g 7,                        p,3          spyi pgwn
__,.  [         Setpoint List
      ,[ [                Supplier Dwgs..
Inst. Manuals, etc.                                                                                                     ,
          ~
                ~9
          -     ,&       Configura tion Control                                                                                  l PackaJes                                                                                                     7_ _
b                Des ;n Verification R, orts                                                                             l                   l V
r        HELS,.                                                                             l                   l I           I                   i l
ALARA                                                                  l           l                   l         I l            l                   l Tornaco Missile                                                                    l                   l
                                                                                                           \                    l       l F cccing Ana yses
* l                   l       l l           l                           l
_[              Internal Missile
* l            l                           j b                E;uipment Qualification
* g P e Coerationa! Texting l%       ,
WGCeCyres nesults 1           I                   I       I Start up Testing                                                      l            l                   l       l PrCc Mures. R esults                                                   j            j                   j b[
EE580 Data Base l            l
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I            I                   I       I Other (Scecifyl                                                        j                                                     -
j                   j       l
* Prograrnmat.c Review Requirec                                                         l            l                   l       l m
CS AD 22748 #8-13 gn

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exo92A (05/68)             SCUTH TEXA5 PROKCT ElICTRC CGERAUNG STAllCN co .3.m 10CFR50.59 EVALUATION FORM - TYPICAL (PAN 1 Cf 2)                   UNIT l       k CRIC:NADNC OCG' WEN    N.         'f d%              *
                                                                    # Y -U M REY. O
                                                       /
PRCCEDURE      Idil PLANT MCCIFICADCF             ECN          OTHER                          ,
py                   WS
                                                           'i?% 5_6 CESCRIP DCN          '"      Y'O E' Y')           W'NO             U       'M 213              UQ   >
: 1. CCES THE SUBJCT CF THE RD1EN IN'v%'vE A CiMCE To THE FACUTY AS                 ,\d              ,
I CESCRISED IN THE SATETr MALYSS REFCAT7                                         !es[e.';f#fl
: 2. CCES THE SUB ECT CF TdlS RSiE# INiR'vE A CiMcE TC Tr.E PRCCSURES AS CEICRISED IN THE SAFETf MALES REFCRT7                                  I
                                                                                              ."Ol'h I
w           i
: 2. CCES THE SUE ECT CF THIS R1"YEN FRCPCSE THE CCNCUCT CF TESTS CR                 ..%
CGER1WENTS NOT CESCCSG IN THE SATETr MALYSS REFCRT7                        I    IXAT#'d           l 4
m.y,f ss       -
4    CCES THE SUBJCT CF THIS ROiEN REGUlRE A CMMGE TO THE PUNT                                         1 TECHNICAL SPECACATICNS7 I             %        l
: 5. CCES THE FRCPCSED C4McE. ALTHCUCH NOT CEScilSED ;M THE Shuf                                       I ANALYSS RC-GT, AIFECT ITDJS CR ACTIMTIES THAT ME CESCREED                                        !
Q I    I                 l lN THE SATETt ANALYSS RS?CRT7
        !F MY ANSWER 15 AI7iRWAt',E. PERfCRW M UNTdNEE SAFTt CUESTICN EVALVATICN.-
i IF ALL ANSWERS ME NECATl'vE. NO UNREYEE SATETT CUESil:N EVALUATICN IS RECulR9.
THIS FCRW, wtiEN CC4dPLETED, SHALL BE RETAINED FCR THE UFE CF THE PLANT.                        l

otocS:s (05/88)
SOUTH TDAS PROXCT El.ECTRC CLNERAENC STAncN 10CFR50o59 EVALUATIONe FORM - TYPICAL (PAGE 2 CF 2)                                           I UNITY CRlGNATING CCGWENT NUV88                 N'I ~M - 5'#/AN                          REV.  -O OCCUuENTATICN CURATICN   Cf THE STATICNCf        THIS UCSSE.         RoiEN WUST. EE RETAJNED WiTH TriE RD1 NOTE:
                      *SATETY JNAL'rSS RE?CRT' INCLUCES THE FSAR, SAIITr ANAL'rTES SU5ula ir.9 THE NRC IN SUFFCRT Cf THIG RD1EN Cf THE AFFUCATICN FCR AN UCENSE        AND SUSSICUENT AMENOWENTS TO THE CFOATING UCENSE UC85Z CCWM11 VENTS MADE TO THE NRC.
CCGuENT3 RD1EAED:
EEA 4.<DF' -07%$
Se 5 2 /~. a .':. ,i. v.rc. ,, a t.< a.s ah INTGC4SCFt!HE CCCEiNATICH R:ECUlRED7                     0 'rts        G NO lF E., CRCLI AFFRCFFjATE CISCFi!NE. TrEN CSTAN THER CCN~UPRSCE (INJilAL)
CYL                 MECi                  .ELIC                !,hc EQ                OTHER        !
IMPACT TO OTHG CE?AATVENT7                    0 'rts          G NO ir m, THEN oENT:rn l
l-                                                              blia/d 3
                                                                    't                               '
pggp;pg9 9,7,. k,. b:kO ' ?EC',        c...lvf5YS5;j
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                            ,;!                 RESPCNSELE ENGNEIR                                        OA n.
c y cupp y          0l:         :. .     :. , s ' c .~v .* , %~ ?
                                                                                              / U!:IM WANAGER, SUFPCRT 8GNEO:NG                                     0 ATE                  l I
i

t APPENDIX F, ATTACHMENT 2 Addition of an Isolok Sampler for Spent Res.n Discharge to Mobile Solidification. Unit The Solid Waste Processing System collects and processes radioactive spent resins and concentratcs from liquid waste streams generated during plant           .
operations, and solidifies these wastes for shipment and burial.                  l The Solid Waste Processing System consists of the Concentrates Storage Tank       .
which stores evaporator concentrates, Spent Rosin Storage Tank which receives     '
spent resins from various plant domineralizers, resin.and concentrates
 ,                       transfer pumps which pump spent resins and concentrates streams to vendor         ;
 !                       solidification equipment.
This change involved addition of an Isolok sampler on the resin discharge piping to sample spent resins for activity prior to dewatering. Sampling was originally done by grab samples which afforded a greater yossibility for personnel cor.tamination and expcaure. Attached is the work documentation and
* the 10CFR50.59 Review Determination Form.                                         ,
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LQ) PROJECT ILECTRIC GENIOt. TING gT AffN COWlGURAT60N CONTROL PACKAGE COVER SHEET                                         '
_ Milestone 5.0/ Priority a                                                                                          cc, =o.
1.s.ps7.nja7
_ IWPLEWENTAT60N SCHEDULE (WILiffoNEl_                                                                                 00 ORIGINATING OlSCIPLINE:_                                                                                   )    Atv No.
Mechanical                                                                              Issut DATE RESPONSIBLE ENGINEER: _ Stan Chan /Kishin sElsWIC CA T.                                                                                     EXT.
Madhav 7603 N$                                                                                               OATE: _3-1-88
_ 04LA38 CF WoAK To at PERFOAWED 7                        . _ -
1     PsAm CHANGE msousato: O vEs                            O No suite   So4,,,                                                        _
MA8 Truck sav
                       -sTARTuP sysTrus/ sus sysTEWs Anterto: lWS01 C-BASIS OF CHANGE:
O cA m mo. __1 E ?a . 2175 FL-3514                        @ PCN(Accroved)  No. _                                     m O .suP,una -_           NA O cueNT -               NA O PUNCH Uri No . _ 102 l 2
                -                                                                  _ O ofwE -                            EsR 87-xx-026
_ CHANGE CATEGORY:- __ C 8ACX CHARGE-                                                NA O oTNEa -                 NA "ITLE OF CHANGE:
Addition of an isolok sampler for scent resine,discharq replacing Work to be done      ouick by disconnect hose connections anges.                                        with and blind fl rer                   _
FARTIAL PACKAGE:
O vas D No                   SEQUENCE:- Nnaa Ep H K S O>'                                 OlSCIPLINE COORDINATION
                                                               ~ % 26lEb ILICTMMAL EGb / //              -
nn
                                   \?!{0Wt CAT 3 2/Ald S                Cl L EGs
            '180 EC8 hs'j[%.m                                                      M(In/M u, % -                                            DATE PLANT otsiGN tas CAfthg3                WICHA"6CA%gd U
_ 3 9 c-
                                                                            # '    ~
L'     NA                   ~ oArt                      CowTmot sos
                                                                                                                       ~
                                                                                                                                                     ~ fO T Q g-EQ(Gs                                                                                                                                           CATE NA DATE NUCLEAR EGs APPROVALS:                                                                                                                                      OATE o
MiGINATING CISCIPUNE (Gsb                         9
                                                                               - QATE 3 2 b Y b P
30 JECT ENGINEEM _
                                                  ~
                                             . A > FX -                      ()                            __
CONptcymAT)oN CONTmot CooRotNATOR~
                                                         ~
                                                                        ~=      ~ OATE             M                         (tectees Wie coorcimatloal
                                                                                                 '          ~
4 DATE -
FI ELO NOTIFICATION OF CHANGE COMPLETION:
mtFtmtNCE Fom PAATLAL t MLETioN-ORGANIZATION stGMATURE                                                                            _
DATE ENGINEERING CLOSE OUT:
UNIT d h3UIVALEwT:
091GINAftNG Ot3CWUI=E EGs                                                                 -
CATE                           2-M- FST-0259 i*AO             2273       (s 12 s7)               '#
tacts             sT, un f 7%Qp' ,,pg REv              NprE               -                   "
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                                                                                                                                  ~"
4!t'ISS

i.
cce no. 1-M-FST-0249         Rtv. 00             l SOUTH TEXAS PROJECT
             ,                CONFIGURATION CONTROL PACKAGE CONTENTS l REQUIRED THIS REV.
: 1. DESIGN CHANGE BASIS                                           YES X                NO
: 2. FSAR CHANGE REQUEST PACKAGE                                   YES                  NO X
     ,3.~ MATERIALS SHEET                                               YES X                NO       ,
: 4. DOCUMENTATION LIST                                            YES Y                NO X-FCR'S INCORPORATED INTO THIS PACKAGE: N/A X-FCR NOS.:                       ,                        ,                              '
l 1
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DESIGN CHANGE BASIS CCP NO. _ 1-M-FST-0Pa?
CCP REV      00 BA$ls OF CHANGE                                            PAGE      1   OF _  3 The installation of an isolck sampler in the MAB truck bay will provide the capability to obtain representative resin samples prior to solidification.
This sampling capability is required by the NRC.
DESCRIPTION 0F CHANGE Information provided in the Design Change Basis is provided for information only to enhance the definition of the design change as provided in the attached drawings. Installation and QC verification is to be accomplished in accordance with the drawings only. No XFCR's will be accepted against the Design Change Basis.
: 1. Replace each quick disconnect fitting at the discharge of Yalves WS-0036 and WS0042 with 1 1/2" flanges and matching blind flanges per IDCN's to P&ID 9F05048 el and Isometric 7M369PWS278, Sht. A10.
: 2. F'odify and extend the existing piping at the discharge of Valve WS-0041 per IDCN's to P&ID 9F05048 il and Isometric 7M369PWS278, Sht. A10.
: 3. Modify existing pipe support for Line 1 1/2" WS-1035-WG7 per IDCN to Drawing WS-1035-HF5009. Add new support per IDCN to Drawing WS-1035-HF5010.
4    Refer to vendor drawing; Bechtel Log No. BF41002-00006-AXX and weld the flange connections to the adapter as per IDCN #7M369PWS278, Sht. A10.
Assemble sampler and adapter per vender drawing'; Bechtel Log No.
B F41002-00001 - AXX.
: 5. Mount Isolck Control Station HX-4151 (Ref vendor drawing; Bechtel Log No.
BF41002-00003-AXX) on the truck bay wall per IDCN to drawing SMIS-92-46054 and drawing 5Z01-92-45080, Sht. 68.
EO CHECKLIST IMPACT             O veS         G No CS AO 2266 (916 87)                                                                        )

   ,   ,                               nevrw tsmes acceset   .scroie os=soarins statica
* DESIGN CHANGE BASIS (Cont.)
CCP NO.              1-M-FST-0249 s
CCP REV.               -00 DESCRIPTION OF CHANGE                                        PAGE               2     OF     3
: 5. (Cont'd)
A. Install vendor supplied yellow and black tubes per vendor dfawing; Bechtel Log No. BF41002-00001-AXX from sampler to control station.
B. No permanent instrument or station air connection shall be installed
              ,          for the control station.                                                                       ,
i               6. Refer to vendor drawings Bechtel Log No. BF41002-00005-AXX and BF41002-00003-AXX to provide the 115 VAC-1PH-60HZ,1/2 AM electric supply 4
to controller.
NOTE: All existing material-quick disconnecting hose connections and welded pipe stubs - removed by this CCp shall be scrapped                                                  ,
4 1
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CS. AD 2286a (916 87)                                                                                           )
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                 .                 ..-          . .     -. __ - . _ - - - ,      . - - , - - -           - - , - - --i

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          ,                         SO U TH TEXAS P22JE CT ELECTOlc CCNEQ ATt%C st Ayg;g DESIGN CHANGE BASIS (Cont.)
CCP NO. 1-M-FST-0249 CCP REV. 00 DESCRIPTION OF CHANGE                                         PAGE     3   OF    3
                                                                              ~
: 7. Wl126 FbW EH2. $UPPLY TD dcryV-C u EE. 4 W K 415 i A5 Fo"od 2                                           ,
McLok 6 AMPLER.
lPAWEL                                     l
                                      .tTB i                 WW 1FU                  6K i
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SN NO N II A W ( % 5(,,WEVuLSD)
Ft ELD TD PRoy tpg A fo'. o " .t 2 " f o#e dA8ti V FAB RicA TE A MOuM D N v-2 2A C k e 'r 7~0 S o PPO IlT* 1*M E CC' ' E 9 CPBLE WH5H u o r J Al U35.
i No tE : Pen. 5 s:          Eme            9 Po o           /     3 ete, wies c,ucaoim                               .
l             (M.Opsy Es TG41bd G"                                   PLud gefRA14Wi- BLADE To se useo F~on Pod' '4 Atew op %pmeit,                                       is CAT.
A ,df 52 M-C CRtzo v. Ac.-                       l CS. AD.2286a (9 16 87)

SOtJTH TG M AO PatOJECT Ga CCTMSC GTHEM A T0 Pee CT A YSOpe CONFIGURATION CONTROL PACKAGE                                                                                                          " "a I-M-F5F#t#
MATERIAL SHEET                                                                    REV.      gb([
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* d(i'' A P I i        I (o 01 CEADM(117$5 P(JTE: OOLLA26 SHOULD iPoicATE WA IF NOT MPLICABUI.                                                                                                  e or .12

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(Page 1 of 21 OESCRIPTION Unit
* l l    i   PROCE DURE      IX)     PLMT M00!FICAT10N            I   i   OTHER ORIGINATING 00CtKNT WO. CC P             J - M - Fs F- O 'L4 q           REY.        &
TITLE A oor n os t         of      I c,o w n    sn m pi nz en A senir A remi.
DISC H n n L r~ n hJ O      A h~9LA r W m A;'1U T    O "~ CO U l r M     O )$r MA)Nh"C Y H CS c'     c,otynIEDT7 ON.S       LDVrH B U/VC        FL ANG s~S DE SCRIFT10N      pa,u ing-s          sn u p,,xjt      C,1 pnni,1rv i=op              Sctin u% ws            h t~iNr. n i e c n1 A it mo     TD     TH &~       Mennr Ar'L i D I .~- ) C /177 DN   I 1 A) ) [
Yes      No Does the subject of the review involve a change to the facility as                           -
described in the safety analysis report?                                             I     I  I,)(
O00 Does the subject of this review involve a enange to tne procedures                             J-zPb 8 as described in the safety analysis report?                                        I-      i Q, f V' Does the subject of tnis review propose tne conduct of tests or experitnents not described in tne safety analysis report?                           I      I  TM GOD Does the subject of this review require a enange to the Plant                                    7-2 68 Technical Speci fi;a tion ?                                                          i     i j4 Does the proposed change, although not described in the safety anal/ sii report, affect items or activities that are describec in the sifety analysis report?                                                      l t %
(This fom, een completed, shall be retained for the life of the plant.)
1 0191b/0106b l

l__0CFR50059 EVALUATION FCRM - TYPICAL (Page 2 of 2)
If any answer is af finnative, perfona an Unreviewed Safety Question evaluati                           .
If allred requi    answers
                  .         are negativc, no Unreviewd Safety Question evaluation is Documentation           of this review must be retained with the review package for duration of the station license.
Note:
                   "Safety analysis report" includes the FSAR to the NRC in support of their review of the application for an, safety analyse operating license and subsequent amendments to the operating license and other license comitments made to the NRC.
Documents Reviewed:
fSA 52       SE~c T-1O. 4. P , ) { . 3    h) >4 C-    65 amT1D,U3 u Ar 3tD&7e3               ,f,ffG 6 1
1 I
                                                                                                                           \
Prepared by:Ogjeu M%               d Origina tor '
Um          /        4/,z/g/
                                                                            '0 ate Concurrence:             ,
p_uw                   /    F- Z / - M' 9epartment Manager                                                        _
Date 0191b/0106b
_ . - - - ~

    -          i EOUTH TEXAS PEOJECT El.ECTOIC O EN ED ATING ST ATION                                        ,
DESIGN CHECKLIST (DCL)
Initiating Change Document No Title                                                                                               =qc p j . m - FST - OM 9 Doc.             A Oct r7DN OF         LSol. O k SAM ptG14 Rev. O                Page 1 of     2 Start-up System:            1 WSo /

==Title:==
.Sou d           turisnr- Sysm This checklist must be attached to the initiating change document during the entire review and approval process up to the point of issuance by Project Document Control. Reference PED . 041.
AmcTED ooCuMENTS MICH AEOul AE REV AFFECTED                   POTENTIALLY                      (MWit provde specific ref tf t9Ce 60.)                       oTHEP TO M t.& P YES               NO  AFFECTED DOCUMENTS                                                            REV AF ECTED oisC.        y ooCuMENT NO (OR SECTioN) l Licensing Documents
                       !    l      FSAR l%               F M AR ( Appendix B)
* l I      ER                                                                                                                        ,
y           Technical Specifications (Pfant)
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              -        -                                                                                                                                     1 g       Deficiency Evaluation Report (DCR) b                  Design Cotena
              -.-J A m        System Descriptions b[                Des gn Calculations                                                     !
                  .-                                                                                                                          l bb                 Soecifications               _                                                              _
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ASME Design
[ [-               SrecJacations                                                                                                  !
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SouTw Texas encarc7 rLecTalC CrNrCATIN3 STATCN in t ating Chan  Document N .
DESIGN CHECKLIST (DCL) Continued                                                                             i R ev.           Page 2 of 2 AnEcTEo coWMENTS WHICH REevlRE REV                                   I AFFECTED                  POT- iTIALLY           t w n orevio. e. cit < ro.< ne,ao )              OTHEn                  E YES           NO AFFECTE0 v0CUMENTS          og, vMENT No tor SECTioN)
REV,                          Y        N Instrument Index Equipment index k N7g $ve Master File Va                     5L54976 ry,o 2.                          23         '90"/c*8" "                 .J
[      Setpoint List
         .L @                 suppije, o.gs..
inst. Manuals, etc.
j Configuration Control Packages Design Verification Reports HELSA*
1 I
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                    ,__      Tore      %ssile l           F ooding Analyses
* l           l                         l l      l[         Internal %ssile
* Ecuipment Oualification
* _%               P'e Coerational Texting Procedures nesuits                                               l l
[      }          Start-uo Testing                                               ,
l Procedures Results                                             j
;                          E E580 Data Base                                                                              l l
Other iSoecifyl                                                                                                -  1 l      l l                                                                                                                                            l
* Programmat.c Review Recurred                                                                                   l i
j CS AO 227481818 87)

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     .                                                      SOUTH TEXAS PRCUECT                                                                                                            2-ELECTRIC GENERATING STATION                                                     1,PAGE E OF _ A                                         NONXbe-h73b6 JOB NO.14926 fgjpg FIELD CHANGE REQUEST CONTINUATION SHEET I
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0500 oce 14             (02/55) 2.03o-                                                                                   I PAGE       0F SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION J:ES::GN VIR::?:: CAT.~:0N ?O:RM COCUMENT TYPE / TITLE                F,aw du,uacie. RewesT OCCUMENT NO.                 Fea. L4xof-07%G                    REv. No.
uCo No. 9/A (l? APPUCABLE)
VERIFICABCN METHCD                     E DESIGN REV1Ew 0 AtTERNATE CALC.          O CuAuriCATiCN 7tsTinc
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osocs2A (cs/84)                                    SCUTH TDAS PRGECT E1ECTRC CENERAENG STADCN co-3.150 10CFR50.59 EVALUATION FORM - TYPICAL (PACE 1 CF 2)                                {
UN T i CRIG;NAT;NG 00CUVEN                               h. Yd                 ~ I-M-     ''2 d REY.      O C PRCCEDURE                   E PLANT MCCIRCAilCN                        U ECN          U OTHER n7tg                 IIC FL i
2% 5,E CESCRIPTiCN        ') ' "                             V'"     E N''       W'WW'             U'     ''''
213            v_c
: 1. CCES THE SUBJCT CF THE REMEN :N'vCC4 A CHMCE TO ThE FACUTY AS                                                  /
CESG8ED :N THE SAFETY MALYSS REPCRT7                                                               I
                                                                                                                      .\/["I
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: 2. CCES THE SUB4CT CF THIS EAEN INNCUd A CiMCE TO rnE PRCCECURES
                                                                                                                      . iV l %t.
AS CESG18ED IN ThE SAFETf MArtsS RE?tRTT                                                           I    !*
: 3. CCES THE SUBECT CF iblS REMEN PRCPCE THE CCNCUCT CF TESTS CR                                                         - . ,
EXPERlWENTS NOT CESGSED ;N THE SAFETr MAL'rSS FEPCRT7                                               I    18 ti3
                                                                                                                        ~'f'f \
4    CCES THE SUB4CT CF THIS REMEN RECUlRE A CHMGE TO THE PUNT TECHNICAL SPECFiCATICNS7                                                                            I    I M
: 5. CCES THE PRCPCSED CiMCE. ALTHCUCH NOT CESGBED ;N IFE SAFETY MAL'rSS RE?CRT, AFTECT ITEMS CR ACTIMTIES THAT ME CESGBED N THE SAFETf MAL'rSS REPCRT7                                                                       I   i         l' ' '
:e
       !F MY MS'AER IS AFFRWAll'vt. PERFCRW AN UNRDAEAED SAFETT CUESTICH EVALUATICN.-
if ALL MS'#ERS ARE NEGAll'vt. NO UNREYEAED SAre.if GUESilCH EVALUABCN IS RECU1 RED.
THIS FCRM, MIEN CCMPLETED, SHALL BE RETAJNED FCR THE UFE CF THE PLANT.

0xos28(03/88)
SOUTH TD:AS PROXCT ElICTR!C GDiOIATING STADON 10CFR50.59 EVALUATION FORA,                 TYPICAL (PAGE 2 CF 2)                          UNITp    I CRIGNATING CCCUMENT NUuSER                  I'M 'M'#/AN               REV. O       ".
OCCJuENTADCN Cf THIS REYEN WUST EE RETAJNID Wim E REYEW PACKAGE FCR THE CURAilCN Cf THE STAilCN UCENSE.
NOTE:
                  "S/JETY ANAL'GS RE?CRT' INCLUCES THE FSAR, SAIETY ANAL'rSES SUBulTIED 70 THE NRC IN SUPPCR7 Cf THIER REYE# CF THE APFUCAUCN FCR AN CfER UCENSE       AND SUBSECUENT AMENOWENTS 70 THE CFERAUNG UCENSE AND UCENSE CCuWTVENTS VADE TO THE NRC.
CCCJuENTS REYEWED:
F~c2. AG P' o73/4 fe ' d / ~. ..: n ,, s a :i.e aa,in h i
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iNTERC4SCPUNE CCCRCiNATICN REtXJ1REDf                        G No J 'f!3, CRC.E APPRCFRfATE C4SCPUNE, TM.N CSTAJN THER CCNCURRENCE (INlilAL)
CYt.               W ECM              ELIC         IJeC         EQ               OTHER      I IMPACT TO OTHER CE?ARTMENT7                C 'rES       3 NO
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                                                                               / U.! .'t'T2 MANAGER. 509PCRT ENGNEE?:NG                        0 ATE

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t APPENDIX F, ATTACHMENT 3                               l Addition of an Isolok Sampler for Spent Resin Discharge to Mobile Solidification Unit A PORC 1.eview was not required for this design change.
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APPENDIX F, ATTACHMENT 4 Addition of an Isolok Sampler for Spent Rosin Discharge to Mobile Solidification Unit J
The Solid Waste Processing System Isolok Sampler samples spent resin activity
                                            ~
prior to dewatering. This sampler was installed at the request of Chemical     l Operations to decrease chances of personnel contamination and exposure.        '
Previously, grab samples were taken to determine resin activity. This sampler-is located in the new truck bay convenient to transfer operations.             l l
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APPENDIX F ATTACHMENT 5                                                          ;
Addition of an Isolok Sampler for Spent Resin Discharge to Mobile Solidification Unit This change added an Isolok sampler in the new truck bay to sample spent resin prior to dewatering. Previously, sampling was accomplished via grab samples, a method which afforded a greater possibility for personnel contamination and exposure. This change will decrease the chances of contamination and reduce exposure in the sampling process.
This change will result in increased maintenance activities in the Mechanical Auxiliary Building in order to properly maintain the Isolok sampler, this added exposure will be offset by the ability to sample resin in a safer and more time efficient manner. The number of resin transfers and operation of plant equipment will not be affected by this change. No additional exposure will occur as a result of this modification.
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1 APPENDIX F ATTACHMENT 6 Addition of an Isolok Sampler for Spent Resin Discharge                                              ;
to Mobile Solidification Unit                                                      l 1
This change added an Isolok. sampler which provides a safer method of sampling                                   )
spent resin prior to solidification. This modification does not change the                                       .
amount of liquid and gaseous effluents, and solid waste predicted in the                                         l License application and amendments.
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I APPENDIX F, ATTACHMENT 7                             j Addition of an Isolok Sampler for Spent Rosin Discharge to Mobile Solidification Unit This modification added an Isolok sampler on the resin discharge piping to facilitate sampling of spent resin prior to solidification for shipment and    i b2 rial. This modification will not result in a change to the expected maximum erposures to a member of the public in the UNRESTRICTED AREA and to the l
ge1eral population as previously estimated in the License application and amendments.
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APPENDIX F, ATTACHMENT 8 l                                      Addition of an Isolok Sampler tor Spent Rosin Discharge to Mobile Solidification' Unit This item is not applicable. This is the initial reporting - period for. the South. Texas Project Electric Generating Station.
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s' 1  h STATION PROBL9 REPORT REGARDING PROBLEM REPORT NO. 880197 t
UNPLANNED RELEASE OF VMT lE en May 30, 1988 June 13 1988-5 t
t Prepared by:
t William F. Scott, II and l                                                                                                                                                                                                    Peggy Lofton Travis i
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Table of' Contents I.            ~ Descript' ion of Event.                                                                                                           I-L II.                 Causes of Event                                                                                                                   2 III.                 ' Analysis of Event                                                                                                                2 IV.                 Corrective Actions                                                                                                                2
                                         .V.              -Additional'Infor=ation                                                                                                            3,                                               'l A.        Previous Similar Events B.        Failed Cc=ponent-Identification.
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                                                                                                                 - -~ **
* I. Description of Event At the . time of the event on May 30, 1988, described in the following                 .
report, the South Texas Project Electric Generating Station was in Mode 5 at 150 F and approximately 400 psig. On this date at the time of the occurrence, Vaste Monitor Tanks (VMT) 1D and IE vere in reciretlation in accordance with IPCP13-VL-0005 (Vaste Monitor Tank (VMT) Operat;cns).
VMT IF was being filled f rem the Floor Drain Tank. The surveillance data package for VMT 1D vas received at 2255-hours by the Radvaste Control Roem for the release of VMT 1D as required by IPSP07-VL-0001 (Liquid Vaste Effluent Rerlease).
At approximately 2300 hours, the Chemical Operations Radvaste Centrol Room Operator (RVO) accidently placed VMT 1E Pu'p    m Diccharge Valve Hand Switch (1-VL-FV-5064A) 'in the "Discharge" position instead of the VMT ID Pump Discharge valve Hand Switch (1-VL-TV-5061A) as called.for in the procedure. This then allowed for the inadvertent disch,arge of VMT 1E instead of VMT 1D vhen the RVO placed the LV?S Discharge Header 3-Vay Valve (1-VL-FV-4077) in "Discharge" in accordance with IPCP13-VL-0005 (Vaste Monitor Tank (VMT) Operations). At 2308 hours, after the Radvaste Control Room Operator trainee had observed the incorrect Hand Switch in "Discharge", the RVO secured the discharge of VHT 1E. VMT 1E had been simpled in accordance with IPSP07-VL-0001 (Liquid Vaste Effluent Releases) prior to the discharge; bovever, the surveillance package had not been completed at that time.
Approximately seven hundred ninety-nine (799) gallons of water frem VMT 1E vere discharged to the Main Cooling Reservoir (MCR). The surveillance data package was subsequently completed in accordance with IPSP07-VL-0001 (Liquid Vaste Effluent Releases) after the discharge had occurred. Samples met the acceptance criteria established in Section 6.0 of IPSP07-VL-0001 (Liquid Vaste Effluent Releases). Analysis results were as follows:
Integrated Release by Nuclide uC3                                  uC1 H-3         4.87E+04                   Cr-51    3.66E+01 Mn-54       5.81E+00                   Fe-59    2.30E+00
,                              Co-58       2.74E+02                   Co-60    5.26E+00 Zr-95       3.02E+00                   Nb-95    2.19E+00                  .
The post-release off-cite dose calculations for the inadvertent release of VMT 1E vere within Technical Specification limits and were as follows:
Liquid Effluent Doses (mrem)
Whole Body:      0.0000 Highest Organ    0.0000 Organ:           Adult's GI-Track Receptor:        Little Robbins Slough

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No adverse impact to the environment occurred. The health and safety of
;                  the general public were not adversely affected.
II. Cause of Event Approximately 799 gallons of water from VMT 1E vere inadvertently discharged to the MCR vithout the required sampling being completed prior to discharge when the RVO accidentally placed VMT 1E Pu=p Discharge Valve Hand Switch (1-WL-FV-5064A) into "Discharge" instead of the VMT 1D Pump Discharge Valve Hand Switch (1-WL-TV-5061A) as per IPCP13-VL-0005 (Vaste Monitor Tank (VMT) Operations). A representative sample had been obtained for the 799 gallons that were_ Inadvertently discharged to the MCR although the analysis had not been completed at that time,
* The major causative f actor for this occurrence was cognitive personnel error.
Although the RVO had an approved procedure at ha,nd, it was inadequately followed. The RVC is a utility-nonlicensed operator.
Contributing to the major cause was the fact that there were two (2)
                                                                                  ~
VMT's in recirculation sL=ultaneously; thereby, allowing less visual distinction between the operating and non-operating trains and facilitating the possibility of an error on the part of the operator.
III. Analysis of Event The discharge of 799 gallons frem VMT 1E vithout the completed surveillance data package constituted an unplanned release as defined in Regulatory Guide 1.21 and, as such, vill be included in the next Semi-Annual Radioactive Effluent Release Report as per OPGP03-ZX-0007
  '               (Preparation of the Semi-Annual Radioactive Effluent Release Report).
Although analysis is required "a priori" in Table A3-1 of the Off-Site Dose Calculation Manual as referenced in Technical Specification 4.11.1.1.1,    quantification of the VMT IE release was completed shortly after discharge.
Thi cccurrence did not involve anr -lant safety systems; therefore, no safety consequences resulted frca the event. Subsequent monitorir.g of ti e
:t"; tion by plant pcrsonnel dete rnized that no adverse impacts to the envireament occurrec nor was the health and safety of the general public adversely affected.
IV. Corrective Actions Upon discovery, the RVO secured the discharge of VHT 1E and notified the Chemical Operations Foreman. The required surveillance data package for VMT 1E was completed af ter the discharge had occurred. No further remedial action is required.
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The responsible RVO on watch rece'ived individual counseling concerning the unmonitored release. This action was completed June 3, 1988. Crev briefings were initiated and subsequent corrective action items were assigned following a second occurrence on June 7,      1988. -They are as follows:                                                                   ,.
All Chemical Operations personnel shall receive an incident briefing in subsequent shif t turnover meetings.
This is the responsibility of the Chemical Operations &
Analysis Manager, T. E. Undervood, and shall be ec=pleted no later than June 20, 1988. Procedures IPCP13-VL-0005 (Vaste Monitor Tank (VMT) Operations)and IPSP07-VL-0,001 (Liquid Vaste Effluent Releases) have been revised to clarify requirements for independent valve lineup verification for all Vaste Monitor Tank discharges and to provide additional control of VMT's in recirculation or discharging to minimine the consequences of line-up errors. These revisions were approved by PORC on June 11, 1988, and pending cce=ent resolution vill become effective no later than June 17, 1988. This action shall be the responsibility of the C0&A Manager, T. E. Underwood The aforecentioned Division Manager assigned the above corrective action items has agreed to the action and the due date committed.
V. Additional Inf ormation No similar previous events have occurred.
The KPRDS history data base reveals no previous items.       The item was not applicable to NPRDS and was not reported in NPRDS.
Supportive documentation is attached.
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APracrvt0 0.et Iso Faseien UCENSEE EVENT REPORT (LER)                                                              5'''*****=
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south T vn. vnte 1                                                                                                                   015 ' o lo I o k h i A 1l0dnis 18144 eaa Uc-enitored Felence of Radioactive Ff floaa t Due to a Personnel Error (TElf Oa f t
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                                                                                                                                            .etaC0;t Charles A. Ayala - Supervising Licensing Engineer                                                                                        5 g p"            e,7 g ,                 ag7g CChartait paig Ling sea g asse CO one nt sa* Lust OllcaiHO ess T-se es eca t tip, Civil      S. l' t w   CO***0 % 4 % '             g.C        g'g . gg                               CAvlt 1 5't w     CC *044%f           "",       E I,   * ,',' 90 { I I           I t I              ! I I                                                          I          i i i              t I !
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At approximately 1828 hours on June 7, 1988, with the plant in cold shutdev (Mode 5), an unmonitored rtlease of 1504 gallons of lic.uid effluent o::urred due to an operator (utility - nonlicensed) inadvertently discharging the vr: ?
Vaste Monitor Tank (VMT).                               A subsequent analysis showed the release tc ce within procedural and Technical Specification requirements. The root cause of the event was personnel error. The responsible individual was counsele , and the incident was reviewed with others involved in radioactive effluent processing. Procedures have been revised to require independent verification of the valve lineup. An investigation into the need for human factors engineerin of the related control panels vill be performed.
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                                                                                           *         (93 muC6874 (scutatos, &-
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South Texas, Unit 1                       o l5 lo j o lo l 419 l 8  8 18 0 l3 l 6     -
Oi 0 0l2   0' Ol5 rm u -             . - - ..e - unn DESCRIPTION OF EVENT:
On June 7, 1988, with the unit in cold shutdown (Mode 5), Vaste Monitor Tanks (kHT) 1D, IE and IT vere in recirculation in accordance with the kHT Operations procedure. Two independent surveillance data packages were received at 1815 hours by the Radvaste Centrol Room for the re' lease of kt! 1E as required by the Liquid Vaste Effluent Release proced~re. At this time, the Liquid Waste Ef fluent Radiation Mcnitor (LVERM) was act operable due te internal contamination of the sa.ple cha.ber.           The Liquid Vaste Effluent Release procedure and Technical Specification 3.3.3.10 permit effluent releases to continue with the LVER.M inoperable, provided that the folleving actions are taken prior to the release:                                          -
: 1. At least two independent samples are analyzed in accordance with Tecnnical Specification 4.11.1.1.1, and
: 2. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.
At 1824 hours, the Mechanical Auxiliary Building Roving Operator (MAS Rover) opened t):e. manual isclation valves on the coc=en discharge line in accordance with the procedure. The Radvaste Control Roo= Operator (RVO) then inadvertently placed the kHT ID Pu=p Discharge Valve handsvitch in the "Discharge" position instead of the kHT 1E Pu=p Discharge Valve handsvitch, as required by the procedure. At 1828 hours the RWO placed the discharge header three-way valve handsvitch in "Discharge", which resulted in a discharge fr:-
kHT ID. Af ter the MAB Rover returned to the Radvaste Control Roc =, it was discovered that the vreng tank was lined up for discharge.                   The discharge va:
terminated at 1835 hours.
A total of 1504 gallons of water f rc= VMT ID was discharged te the Moi.;
Cooling Reservoir. Samples were collected from kHT ID for analysis at 1856 and 1857 hours. Although these samples were obtained after the discharge had occurred, since the tank had been in continuous recirculation since 0838 hours that day, they were representative of the water that had just been discharged from kMT ID. Subsequent analysis of the samples met the acceptance. criteria of the Liquid Waste Effluent Release procedure.
l NL.LER88036 l
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    **''                    LICENSEE EVEN s REP 2RT (LER) TEXT CONTINUATIOi, ,                      amowso m .o me +
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South Texas. Unit 1                        01510lo!0Il.!918      81 8 0l 3 l6 -
010      0h   O' Ols rurr er - - .      w. w ..e w mu ,, nn DESCRIPTION OF EVDIT (Cont. ):
The results of the analysis were as follows:
Integrated Release by Nuclide Sa=ple 1                                                 Sample 2 H-3          2.09E+03       microci                               1*F3E+03        micrcCi Mn-54        3.02E+03       micrcCi                               1.73E+03        miereci Co-58       8.60E+01        micrcC1                               5.48E+01        micrcCi Zr-95        6.83E+00       micrcC1                               5.69E+00        miereci Cr-51       2.93E+01        microci                               2.32E+01 ''microci Fe-59        1.98E+00       miereci                               not detected Co-60       2.32E+00        microci                               1.80E+00        =icreCi NE-95       6.03E+00        microci                               5.11E+00       micrcCi The post-release off-site dose calculations for the inadvertent release cf VM:
ID vere within Technical Specification limits and were as follevs:
Liquid Effluent Doses (crem)
Vhole Body:           0.0000 Highest Organ:        0.0000 Organ:                Adult's GI-Track Receptor:             Little Robbins Slough The NRC vas notifiec of the event at 0010 hours on June 8, 1988.
CAUSE OF EVENT:
The primary root cause of this occurrence was cognitive persennel error.
Although the RVO had an approved procedure at hand, it was inadequately followed. The RVO is a utility-nonlicensed operator.
A contributing factor was the fact that there vere three VMT's in recirculation simultaneously, alleving less visual distinction between the operating and non-operating trains. This increased the potential for an error on the part of the operator.
The inoperability of the LVERM created delays in the discharge of the VMT's and was partly responsible for the three tanks being in recirculation at the same time. The inoperability of the LVERM also created the condition, as a result of Technical Specification requirements, that required two independent sample analyses and independent verifications of the release rate calculations and flovpath lineup prior to discharge. These requirercents had not been met for VMT 1D.
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NL.LER88036
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION                                   a m over = =o >>w-eio.
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South Texas, Unit 1                        lo p l0 lo lo 141918         8l8 -
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CAUSE OF TVENT(Cont.):
While the liquid vaste effluent release procedure included the sampling and verification require =ents for a release with the LVERM out of service, the
                    =ethod for verification of the valve lineup was not clear. The.VMT operations procedure did not address these requirements.
ANALYSIS OF EVEh7:
1504 gallons of liquid vaste was discharged f re= kHT ID vhile the Liquid Vaste Effluent Radiation Monitor was inoperable, without first co=pleting tv sa=ple analyses and independently verifying the flow path lineup. This constituted a        '
violatien of Technical Specifications and, as such, is reportable under 1CCTR50.73(a)(2)(1)(3).
Subsequent analysis of the contents of ktT ID by plant personnel determined that the  release was within procedural and Technical Specification limits.
Therefore, there was no adverse i= pact to the envirer.=ent ner to the health and safety of the public.
CCRFICTIVE ACTICN:
1.
The discharge f rc= k?T ID as ter=inated i=::ediately upen discovery.
Representative samples of the tank contents were obtained, and the required analyses were perfor=ed.
2.
The RVO received individual counseling concerning the un=enitored release.
3.
Pers:nnel involved in the release of radioactive effluent: received a briefin en the incident.
4 In order te =inimize the potential for valve lineup errers, the kt!
operations and liquid vaste effluent release procedures have been revised to require independent valve lineup verification for VMT discharges, and to provide additional control of kHT's while in recirculation or discharge.      The procedure revision also incorporates an i= proved method for backflushing the LVERM. This should enhance and increase the' availability of the instru=ent for effluent discharges.
5.
An investigation into the need for human factors engineering of the related Radvaste Control Roe = panels vill be ce=pleted by Septe=ber 30, 1988.
NL.LER88036
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION                                           w =ovio o        .e aiw.4, g e e al g lg,,g paciuf f LAast til                               occa ei hUhS$ A Lll l                                                                                 (l A GuQha$$ 3 l$1                                       P6Cl (3) 4.-
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South Texas, Unit 1                          015 to l0 j o l 4l9 I 8 Bl8  -
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ADDITICNAL Ib70RMATICN:
A similar event occurred on May 30, 1988, when an Rk'O inadvertently released effluent f rem the wrong kHT. On that occasion, the LLTRM was in service so there was no violation of Technical Specifications, and the incider.: vas net reportable to the NRC. Corrective actions for that event were in progress but had not been completed when the event described in this LER occurred.
EL&P is conducting a separate investigation into the problem of inoperability of the LL'IRM.
l 1
1 NL.LER88036 M'**" "                                                                  _                                                                            __

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APPENDIX I 1
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i _    .--                       __

        "   hUCLEAR PLANT OPFRATIONS riant Procedures Docu,Titni Control CtAlg
[
g orGE03-zA-ooo2 Rev. 10 f                                                                 Rage 34 cf 31 Comtglied Copy No.               ~g          '
                                                        . FIELD CHANGE REQUEST FORM OPGP03-ZA-0002-4 (Page 1 of 1)
FIELD CHANGE No.                BB- 03 99              Unit Designator [] i [1, 2 pq Cc::. n Is this a One-Ti=e-Only Field Change *>4 No ( } Yes                                    {
m
                ?' Expiration Date              AJ/4                                                          ,
SECTION A - DESCRI? TION Procedure No.            OMPM L''C/9                     Revision Ho, 9                                                                  /
2 scedure Title A        Ansn      A rm'a* l'l]b RC'       bry:M lbHWL k20c;eAm QUALITY CLASSIFICATICN:                                                                            ~
                                                                                                                                      ~
M QUALITT-RILA"'ED [} NON QUALITY-RILADID A??ROVAL CLASSITICATION:                STATICN g y } DIVISION Descriptien of Change (s):
per oranies b( b/4# f M               "*/hu ct n4A cre e:                         "
70    ''s_bwrwem in .
* Rfccc->e.ccs lReasonfcrChange(s):                    O Co A E'U-e>M          Tb   tot',2b, Air,
* s                                                                                                             g i
nJ C/@P/d- tilS - mio / he v f}cnv.= /1b: 2 77-h _wnei \ '5b?nt%                  ACA S S # rr-A n ej $
Do you rece.w nd a Fernanen: Change? [ ] No N Yes                                                                 i' This 1: the        /3 7-      TOR agains: the :urrent revisien, other than "One-T! e-Cnly" FORs.                                                                                        l l
                        ?repared by-        /      / wb_,,           '
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                                                >                                           ::at e _2 /2 Sff>:
s                    McT:h2-T??ROVAL                                                             i'
                        *A;pr:ye:           h -S- . /-- /                                  Da:e 3 .t.v W Approved _       /T)(//jftf;jpn D N n ,itW      ' ervi. tor Date [ .2 f e %.
in d ' ted In: 'vidual (See Addendu. 3)                         '
iv
                                                           /
SECT:CN C - FINAL REVIr=' AND A??RCVA'
                       -NOTI:   .Cogni: ant DM review snail be :: pleted within 14 calendar ::y:
of :pproval in Section 3.                                                                                              ;
Permane.
Satisia:: cryChange       [] NO { } YES, Aut::atic Incorperation [] NO [} YII ;                                     l
() NO [} TIS                                                                             i Reviewed     'v
             *-                                                                          Date   ~~
              ,                                           Ccgnizant DM 1-i,            Approved by
              '                                                                          Date Flant Manager or Cogni: ant DM                                j 0                                                                                                      .
                   **     This signature is not required for field changes to NON Q Procedure:.
This signature not required for Divinica Procedures,                                                                 5
      )            0 Plant Manager signature required for Station Procedurcs, Department Manager signature required for Division Procedures.
This TORH, when cornpleted, shall be retained for the life of the p. ant.

           --                                  Fidienstiv7 Wastm Process control Program OPGP03-ZO-0017
      ._                                                                                               Rev. 1 Page 5 of 38 5.0 Procedure 5.1 Process Descriptic                                                         '
5.1.1     Dry Active Vsste 5.1.1.1   Dry Activa Vaste (DAV) is segregated upc: : 11ection into trasa receptacles equipped with poly bags, 4%
                                                          =arked      as potentia 1g1 g g sence:ta=i=ated or _ r : - -
                                                                                                    , potentially
_-... When full, the vaste is transported to the sorting area and ha:dled lfp in accordance with 0?C?!4 WS-0010 (Dry Active vaste Collectice, Sorting and Segregation).
5.1.1.2 In the sorti:g area, nese==pactible items, liquids a:d containers of liquids. shall be re ved f ec: the pote:tially co=ta:Imated and the pete=tially-u :::tanimated vaste. Liquids shall be handled in accordance with 0FC?10-ZO-0002 (Disposal of Radioactive Vaste Liquid). Reusable items shall be placed in ecstainers and the respensible divisitas                4 n:tified.
E ; W /.Ne:c rash=pactible   items shall.be placed i:      (Y.
re:epta:1es. The cc pa tible vaste is them baEged fer c: ;atties.                          l[
: a. C::pactible Vaste All centt:itated et petectially centanizated c:=pactible vaste shall be takes to a designated area, compressed into approved streng tight conta!=er:, sealed, labeled, veighed act surveyed it ace:rdance with 0?C?!4-VS-0:0 (0:-
Radicactive Vaste Ope:atiets) and the: ;1a:ed storage 1: a:: rdance with CPC?.'-VS-;;;5                       ;
(Radica:tive Vaste Package Transfer to Storate) 5.1.1.3 In the sceti:g area, cc       :actible and reusable items,        )
liquids  andp oclicuids 'd containers shall be removed frc: the acr weressief a
                                                                                                                      = (d,'@~
rp: t.... receptacle.
Liquids shall   jg6, be handled it accordance with OPCP10-ZO-0002 (Disposal cf Radica:tive Veste Liquids). Reusable ite=s shall be placed in ec tainers and the respo:sible divisions notified. Co= pac +ible vaste is then bagged for ec=pactics. Nonce:pactible vaste is placed in trash receptacles.
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           @.                                                  Erdie+ctive Wasta Pesest,s Centrol Fronram CPGP03-ZO-0017             ;
Rev. 1 4
Page 26 of 38 ADDDTDUM i
                                                                             'DAV TLOV CHART (Page 1 of 2) 4 Pete:tially                                                                                                  $wc:estwade.,
Net: staminated Pote:tially Centa:itated                                                                ~4; r : !!!:    lh[ C''
                                  *'a
                                  . ste Vaste                                                                  Certanimated
                                                                                                                                            ,  '.'a s e 1P f
v Transport to Sorti:g Area                                                                      ',
Tra: sport to Setti:g Area t
t v*es                                           _
N ::: pactible                                                                    '
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l                                                                                                                                     Reusable Items i
No No v
v*es                                                                                                          v Reusable            '   Yes Ite=s                                                                        Liquids, Liquids in containers No Tes v
lRecoveand
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                         ~ " ' '                                                                                                                           NC Liquids, Liquids                    g*. -~' ~, n~.a (Respcasible                                                                                             "
I in Contaisers             Yes     , Dispose of                                 +- I' 3Divisicas _         _
in Approved Manner                                                         v No Place in Trash v                                                                                 Receptacle to Avait Box Tilling Place in Yellow Poly 3ag For Compactics v
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8&o&1Iooy 7 ol SOUTH TEXAS PROJECT UNITS 1 F 2
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l                                                                                                                                                           Figure 11.212                                                                                                                                         Amendment 51                    _

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The Light company                                P.O. Ilox 1700 llouston, 'lixas 77001 (713) 228 9211     1 Ilougon lighting k Power           --   ~                  -. -       - - - - - - - - -
August 23, 1988 GT-HL-AE-2769 File No.:        G02 10CFR50.36a U. S. Nuclear Regulatory Commission Attention:     Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 Semiannual Radioactive Effluent Release Report for the First Half of 1988 Pursuant to the South Texas Project Electric Generating Station (STPEGS)
Unit 1 Operating License NPF-76 Appendix A Technical Specification 6.9.1.4 and 10CFR50.36a, attached is the Semiannual Radioactive Effluent Release Report for the first half of 1988.        The report covers the period from March 8, 1988 (date of initial criticality) to June 30, 1988.
If you should have any questions on this matter, please contact Hr. C.A. Ayala at (512) 972-8628.
Q                   s G. E. Vaughn VI.e President Nuclear Plant Operations GEV/CAA/n1

==Attachment:==
Semiannual Radioactive Effluent Release Report for the First Half of 1988, h
l NL.88.230.02
                           ^ "" "U          """"" '" ""      '"
J

T'
   !louston 1.ighting & Power Cornpan)
ST-HL-AE-2769 File No.: G01 Page 2 CCI
* Regional Administrator, Region IV               Rufus S. Scott Nuclear Regulatory Commission                    Associated General Counsel 611 Ryan Plaza Drive, Suite 1000                Houston Lighting & Power Company Arlington, TX 76011                              P. O. Box 1700 Houston, TX 77001
* George Dick U. S. Nuclear Regulatory Commission              INFO Vashington, DC 20555                             Records Center 1100 Circle 75 Parkway
* Jack E. Bess                                    Atlanta, Ga. 30339-3064 Resident Inspector / Operations c/o U. S. Nuclear Regulatory Commission          Dr. Joseph H. Hendrie P. O. Box 910                                    50 Be11 port Lane Bay City, TX 77414                               Be11 port, NY 11713 Don L. Garrison Resident Inspector / Construction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036                                                                   ,
1 R. L. Ranga/R. P. Verret Central Power & Light Company P. O. Box 2121 j
Corpus Christi, TX 78403 l
R. John Miner (2 copies)
Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 NOTE:     The above copies distributed without the attachment, except as noted by asterisk (*).
Revised 06/16/88 NL.DIST
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