ST-HL-AE-4182, Semiannual Radioactive Effluent Release Rept for 920101 Through 920630

Semiannual Radioactive Effluent Release Rept for 920101 Through 920630

ML20114C122
Person / Time
Site:	South Texas
Issue date:	06/30/1992
From:	Jump W HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ST-HL-AE-4182, NUDOCS 9209010203
Download: ML20114C122 (30)

Text

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August 27, 1992 ST-HL-AE-4102 File No.:

G02 10CFRSO.36a U.

S.

Nuclear Regulatory Commission Attention:

Document control Desk Washington, DC 20555 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Semiannual Radioactive Effluont 11eJmis.e_ Report for the First Ilalf of 1992 Pursuant to the South Texas Project Electric Generating Station (STPEGS) Technical Specification 6.9.1.4 and 10CFR50.36a, attached is the Somiannual Radioactive Ef fluent Release Report for j

the first half of 1992.

The report covers the period from January 1, 1992 to June 30, 1992.

If you shoulci have any questions on this matter, please contact Mr.

C.

A.

Ayala at (512) 972-8628.

Ga t. k.

William J.

Jum General Manager, Nucl. car Licensing MKJ/ag

Attachment:

Semiannual Radioactive Effluent Release Report for the First Half of 1992.

01008 atLP\\92251001.1&2 A Subsidiary of flouston Industries incorporated 9209010203 920630 l1iI PDR ADUCK 05000498 R

PDR

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Houston Lighting & Power Compan>'

ST-HL-AE-418 '

South'Tru6 Project Electric Generating Station File No.I G32 Page 2 cet Regional-Administrator, Region IV Rufus S.

Scott ducloar Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 400 Houston Lighting & Power Company Arlington, TX 76011 P. O.

Box 61867 Houston, TX 77208 Georgo_ Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Oontor 1100 Circio 75 Parkway J.

I. Tapia Atlanta, GA 30339-3064 Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hundrie Commission 50 Bellport Lane P.

O.

Eox 910 Bollport, NY 11713 Bay City, TX 77414 D. K. Lacker J.:k.

Novman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C.

Texas Department of Health

-1615 L Street, N.W.

1100 West 49th Street Washington, DC 20036 Austin, TX 78756-3189 D. E. Ward /T. M. Puckett Contral Power and Light company P. O.

Box 2121 Corpus Christi, TX 78403 J. - C. - Lanier/M. B. Leo

. City of Austin Electric Utility; Department P.O.. Box 1088 Austin, TX-78767 K. J. Fiedler/M. T. Hardt-City Public Servico Board P.

O.

Box 1771 San Antonio, TX 78296

• NOTE::

The above copies distributed without attachments except if'noted by asterisk (*).

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Revised 10/11/91 L4/NRC/

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O HOUSTON LIGitTING & POVER COMPANY SOUTl! TEXAS PROJECT ELECTRIC GENERATING STATION UNIT ONE LICENSE NO. NPF-76 AND SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION UNIT TWO LICENSE NO. NPF-80 SEMIANNUAL RADI0 ACTIVE EFFLUENT-RELEASE REPORT JANUARY 1, THROUGil JUNE 30, 1992 Prepared by:

8 8 d~ 9M Chemica- 01% rations and And{ sis Manager Ddte Reviewed bys f

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TABLE OF CONTENTS SUBJECT PAGE Report Sunnary 3

I 1.0 Introduction 4

2.0 Supplemental Information tor Effluent and Waste Disposal 4

2.1 Regulatory Limits 5

2.2-Maximum Permissible Concentrations 6

-2.3 Average Energy (MeV/ Disintegration) 6 2.4 Hessurements and Approximations of Total Activity 7

2.5 Batch Releases 10 2.6 Abnormal _(Unplanned) Releases 12 a.

2.7 Estimate of Total Error 13 2.8 Solid Waste Shipments 13

()

2.9 Radiological Impact on dan 14 2.10 Meteorological Data 14 2.11 Lower Limit of Detection (LLD) 14 2.12 Dose to HEMBERS OF THE PUBLIC on Site 14 c'-

.3,0 Technical Specification Reporting Requirements 14 3.1 Ra'dioactive Waste Treatment System Design 14 Modifications Description 3.2 Inoperable Effluent Monitoring Instrumontation 14 Explanation f*

3.3 Gas Storage Tank Curie Limit Violation Description 15 PL 3.4 Unprotected Outdoor. Tank Curie Limit violation Description.

15 3.5 Abnormal (Unplanned) Release Description 15 3.0 Radioactive Waste Process Control Program Changes 15 3.7 Offsite Dose Calcul

.on Manual (ODCM) Changes 15 3.8-New Land Use Census Location (s) Identification 15 I

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LIST OF TABIMS l

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i-Gaseous Effluents-for 1992 10

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ist and 2nd-Quarters i

Liquid Effluents for 1992 1st and 2nd Quarters 21 t

4 Solid Waste and Irradiated Fuel Shipments j

lot and 2nd Quarters, 1992 26 l

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ltEPORT SUMMhB,y, O

This report summarizes the radioactive liquid and gaseous releases (effluents) from the south Texas Project Electric Generating Station for the first half of 1992.

The fit.L half of 1992 Semiannual Radioactive Ef fluent Release Report illustratos that all ef fluent releases were well below applicable limits and were consistent with results from previous reporting periods. The radioactive waste processing systems were operated properly and have performed their intended functions.

To protect the general public, guidelines have been established governing the release of radioactivity in liquid and gaseous effluents.

The Code of Federal Regulations, Title 10, Part 50, Appendix I provides guidelines for the Technical-Specifications which are part of the license authorizing operation. The South Taxas Project's Technical Specifications place restrictions on the release of radioactivity to the environment - and the resulting dose to the public.

All cadioactivity released was well below levels established by these guidelines.

The radioactive waste treatment systems at the South Texas Project are designed to collect and process liquid and gaseous wastes which contain radioactivity.

Any radiological releases from the plant are measured by installed plant radiation monitors which survey the unit vent and condenser air removal system for gaseous releases to the atmosphere, and the discharge line for liquid releases to the Main Cooling Reservoir (MCR).

These monitors and associated sample analyses provide a means to very accuretely determine the type and quantities of any radioactive materials which may be released to the environment.

The differences between this report and previous reporte are as follows:

The value of the applicable limits for radioectivity released are listed e

in the Summary Tables.

All Xe-133 radioactivity is included as continuous release mode.

All batch release times represent the actual period of releases.

-e Total liquid volume prior to dilt. tion is reported as total volume released l

and batch volume released.

During the first half of 1992 reporting periode No discharges were made from the Main Cooling Reservoir to the Colorado River.

No major design changes were made to the liquid, gaseous, or solid radioactive waste treatment systems.

Six radioactive shipments of dry active waste and rosin were made for processing / burial.

1 e

There were ne changes made to the Radioactive Waste Process Control O

Program or Offsite Dose Calculation Manual.

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-1.0 Introduction i

1 This Semiannual Radioactive Effluent Release heport for the period January 1, 1992, through June 30, 1992, is submitted in accordance with Appendix A of License NPF-76 and NPF-80, Technical Specifications, i

i l

A single submittal is made for both units which combines those r.wetions j

that are common.

Separate tables of releases and release totals are j

included where separate processing systems exist.

)

In accordance with Technical Specification 6.9.1.4 the hourly i

).

meteorological data and assessment of radiation doses due to radioactive effluents s>All be included in the Semlannual Radioactive Effluent Release l

l Report submitted within 60 days af ter January 1 of each year, and therefore is-not included in this report.

i Liquid quarterly composites for Strontium-89, Strontium-90 and Iron-55 for the 2nd quarter, 1992, will be updated in the next Semiannual Radioactive Effluent Release Report if required.

l All assessments of radiation doses are performed in accordance with the STPEGS Offsite Dose Calculation Manual (ODCM).

1 i

2.0 Supplemental Information for Effluent and Waste Disposal Unit Number 1 l

Type:

PWR Houston Lighting & Power Co.

L Docket No. 50-498

. Power (MVT)- 3800 Cooling Water Source:

' Initial Criticality-(March 8, 1988) l_

Main Cooling Recervoir j

l

.. Unit Number 2-Type ~ PWR.

Houston Lighting & Power Co.

Docket No. 50-499 Power (HVT)- 3800 Cooling Vater Source:

Initial Criticality-(March 12, 1989) i l

Main' Cooling Reservoir I

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O 2.1 Regulatory Limits 2.1.1 Fission and activation gases The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the Site Boundary shall be limited to the followings During any calendar quarter:

Less than or equal to 5 a.

mrads for gamma radiation and less than or equal to 10 mrada for beta radiation, and b.

During any calender year Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2.1.2 fodines and Particulates, half-lives > 8 days The doso to a Member of the Public from Iodine-131, I' dine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the Site O

Boundary shall be limited to the followings a.

During any calendar quarter:

Less than or equal t o 7.5 mrems to any organ, and b.

During any calendar year Lets than or equal to 15 mrems to any organ.

2.1.3 Liquid Effluents The dose or dose commitment to a Member of the Public from radioactive materials in liquid offluents releasede from each unit, to Unrestricted Areas shall be limited to:

a.

During any calendar quarter: Less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any orgte, and Less than or enual to 3 mrems b.

During any calendic va tra to the whole body anc to less than or equal to 10 mrens to any organ.

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i 2.2 Haximum Permissible Concentrations 2.2.1 Gaseous Effluents 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 ncble gases:

Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin, and b.

For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives breater than 8 days:

Less than or equal to 1500 mrems/yr to any organ.

2.2.2 Liquid Effluents The concentration of radioactive material released in 11guld effluents to Unrestricted Araas shall be limited to the concentrations specified in 10CFR Part 20, Appendix B. Table II, Column 2 f or radionuclides other than dissolved or entrained noble gases. 'For dissolved or entrained noble gases the. concentration shall be limited to 2.0E-04 micro

- curie /mL total activity.

2.3 Average Energy (HeV/ Disintegration)

The Average Energy (or E-bar) shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration for the isotopes other than Iodines, with half-lives greater than 15 minutes, making up at least 95% of the total non-lodine activity in the coolant.

E-bar (MeV/ Disintegration) 5.85E-01 Unit 1 2.92E-01 Unit 2 The average energy (E-bar) of thefradionuclide mixture'in releases

- of fission and activation gases follows:

E-bar (MeV/Dinintergration) 2.14E-01. Uni. i l

1.96E-01 Unit 2 LO.

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2.4 Heasurement and Approximations of Total Activity f

The following discussions detail the methods used to measure and approximate total activity for the followings a.

Fission and Activation Gases b.

Iodines c.

Particulates d.

Liquid Effluents Tables A3-1 and A4-1 of the STPEGS Offsite Dose Calculation Manual I

(ODCM) give sampling frequencies and lower limit of detection requirements for the analysis of liquid and gaseous effluent streams.

2.4.1 Gaseous Effluents 2.4.1.1 Fission and Activation Gases The following noble gases are considered in

-evaluating gaseous airborne discharges:

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Ar-41 Xe-131m Kr-83m Xe-133m Kr-85m Xe-133 Kr-85 Xe-135m Kr-87 Xe-135 l

Kr-88 Xe-137 Kr-89 Xc-138 Kr-90 2.4.1.2 Iodines and Particulates The-radic'odines and radioactive materials in particulate forms to be considered are Cr-51 Sb-124 H-3 Hn-54 I-131 Ho-99 Fe-59 I-133 Co-58 Cs-134 Co-60 Cs-135 Zn-65 Cs-137

~Sr-89 Ba-140 Sr-90

-Ce-141 Zr-95 Ce-144 Other nuclides with-

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half-lives greater than 8 days T

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2.4.1.3 Analytical Methods f

i a.

Batch Gaseous Releases Pre-release grab samples from the plant containment atmosphere, prior to issuance of weekly permits, and pre-release grab samples l

-from the RCS Vacuum Degassing System are analyzed on a Gamma Spectroscopy System utilizing high purity germanium detectors (HPGe) for noble gas, iodine and particulate activity.

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-The radionuclide values obtained are used in conju'nction with the gross noble gas release rate monitoring data collected by the radiation monitoring _ system to estimate the release _ rate of each radionuclide in the effluent streams, b.

Continuous Gaseous Releases Periodic noble gas and tritium grab samples are taken from the continuous release points (i.e.

the Unit Vent and the condenser air removal system exhaust, secondary steam leakage and the 7,

MAB elevator machine room exhaust fan).

Continuous sampling for particulates and iodine is also performed en the effluent streams.

They are analyzed for gross alpha and gamma radionuclides, as described above for batch releases.

Strontium-89 and Strontium-90 analysis is performed by an offsite-laboratory.

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2.4.2 Liquid Effluentr.

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7[gj ihe radionucliden listo: t' low are considerad when ovaluating liquid effluents:

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H-3 Y-90

-133 Na-24 T-91m I-134 5

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Cr-51 Y-91 I-135 Qc Mn-54 Y-93 Cs-134 Ma-56 Zr-95 Cs-13L Fe-55 Zr-97 Cs-137 Fe-59 Nb-95 Cs-138 Cc~58 Mo-99

' -130 Co-60 Tc

,a-140 T

Ni-65

. 0 Ba-141 Cu-64 Ba-142 Zn-65 La-140 Zn-69 4.c 410m La-142 Br-83 Te-125m Ce-141 Br-84 Te-127m (s 143 Br-85 Te-127 Cc-144

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Rb-86 Te-129m fr-143 g

Rb-86 Te-129 Pr-144 Rb-89 To-131m Nd-147 Sr-89 Te-131 W-187

- Sr-90 Te-132 Np-239 Ur-91 I-130

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• Sr-92 I-131

. ALPHA (Gross Alpha)

I-132

,Xe-133

.Xe-135

• other identified radionuclides a

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/*M 2.4.2.1 Analytical Methods a.

Liquid Releases Liquid efflucnts that are processed by the liquid waste processing

• 1 are released as batches.

Liquid effluence that are due to primary to secondary leab:ge or other plant operations are released a2 continuous releases.

For batch releases, representative pre-release grab samples are taken and analyzed in accoadance with Table A3-1 of the ODCM.

For continuous releases, representative samples are collected weekly and analyzed.

Radionuclide analyses are performed using a Gamma l

Spectroscopy System.

A11guots of esch pre-I release batch sample and of representative samples for continuous releases are composited in accordance with the requirements in Table A3-1 of the ODCH. Gross alpha determinations are made using a Gas-Flow Proportional Counting f~s System.

Tritium concentrationa cre deter ined

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using Liquid Scintillation Countir.g techn: ques.

Dissolved and entreined gas contentrations are determined by counting grab samples on the Gamma Spectroscopy System.

Strontium 89 and 90 and Iron 55 determinations are performed by an offnite laboratory.

The radionuclide concentrations obtained re used with the flow total for each b:acN release, The error associated with the flow total is small in relation to the counting uncert.nty of the radionuclide concentration analysis. The average uncertainty associated with counting measurements is 5% or less at the 95% confidence level.

2.5 Batch Releases Liquid and gaseous-summaries are compiled from permits generated using tr-Muclear Data Effluent Management System and plant procedures.

Liquid batch releases are accounted for by individual permits. Gaseous batch releases aze accounted for tf weekly permits. Batch times represent the actual period of releases.

Since the only type bat!

release at STPEGS are ontainment building l

purges or pressure reliefs which are also monitored and quantified l (~T by the unit vent, the Xe-133 radioactivity released in this mode is l \\_ l also reported in the continuous release totals with all other containment building radioactivities being reported in the batch release totals.

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- 2. 5.1 - Liquid (Unit 1)

Quarter 1 Quarter 2 a.

Number of releases:

63 91 b.

Total time pr iod for releases (min)t 3307

___,5012 i

c.

Maximum time period for a release'(min):

64 74 c'.

Average time period

'for a release (min):

52 55 e.

Minimum' time period for a release (min):

0.05 46

2.5.2 Gaseous (Unit 1) a.

. Number of releases:

72 73

-1' lb.

Tots'1' time period

'h for releases (min):

6257 3954 c.

heximum time period for a release (min):

1488-2526,

d.

Average. time period

~F c a release (min):

-87 54 e.

Minimum tima period ~

for a release.(min):

3 2

2.5.3 Liquid-(Unit 2);

3,.

_a.

-Number of releases:

55 68 b.

Total' time = period.for releases (min):-

2779 3483

. Maximum time period' L

c, jn for a.rclease (min):

54 54 d.

Average-time period-for: a release (r in):

51 51 g/

e.

Minimum time period' for a release-(min):

20 0._0_7_

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2.5.4 Gaseous (Unit 2)

Quarter 1 Quarter 2 a.

Number of releases:

90 84 b.

Total time period for releases (min):

7519 3154-c.

Maximum time period for a release (min) -

2820 172 d.'

Average tire reriod for a release (min):

84 38 e.

Minimum time period for a release (min):

2-5 2.6 Abnormal (Unplanned) Releases 2.6.1 Liquid (Unit 1) a.

Number of releases:

0 0

..(b b.

Total actirity released (curies):

0.000E+00 0.000E+00 1

2.6.2 Gaseous-(Unit 1)

a. -Number of releases:

0

'O b.

. Total activity released-(curies):

0.000E+00 0.000E+00' 2.6.3 Liquid (Unit 2) a.

-Number of releases:

0 0

b.

Total _ activity released (curies):

0.000E+00 0.000E+00

- 2.6.4 Gaseous-(Unit 2)'

a.

Number of releases:

0 0

b.

Total activity released-(curies):-

-0.000E+00 0.000E+00 4

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-1 2.7 Estimate of Total Error I

2.7.1 Liquid a.

The maximum error associated with volume and flow measurements, based upon plant calibration practice is estimated to be +/- 1.277%,

1 b.

The-average uncertainty associated with counting measurements is 5% or less at-the 95% confidence level, c.

The error associated with dilution volume is estimated to be +/- 10%.

2.7.2-Gassous a.

The maximum error associated with monitor readings, sample flow, vent flow, sample collection, monitor calibration and laboratory procedures are collectively estimated to be

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Fission and Activation Games 125%

l Iodinos

+25%

Particulates

+25%

1 Tritium

_25%.

+

b..

The average uncertainty associate' with counting measuremen's le 5% or less at the 95% confidence level for fissio..

activation gases, iodinos, particulates

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and. tritium.

2. 7. 3.

Solid Radioactive Waste The error associated _in-determining 1the contents _and volume of solid radwaste shipments is estimsted-to be +/- 5%.and

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1'1%, respectively.

2.8 Solid Waste Shipments

' A total of 6 radioactive shipments of dry ac '.ive waste and resin l

. ere made during the-repr ting 1 period..A summary of the data.is w

provided in the Solid Waste and Irradiated Fuel Shipments Table;

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-2.9 Radlological-Impact on Han (ref. Technical Specifications 6.9.1.4)

This data shall be included in the Semiannual Radioactive Effluent Release Peport to be submitted within 60 days after January'l of each year.

2.10.Heteorological Data This data shall be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days af ter January 1 of I

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 $%. probability of falsely concluding that a blank observation represents a "real" signal.

2.12 ' Dope to HEMBERS OF THE PUBLIC'On Site l.

In accordance with Technical Specifications 6.9.I'.4, this data shall l-be submitteu within 60 days af ter January 1 of each year.

. 3.0 Technical Specification Reporting Requirements 3.1 Radioactive Waste Treatment System Design Modification Description (ref. Technical-Specifications 6.15)

No major design-modifications were made to the solid, liquid, or gaseous radioactive waste treatment systems during this reporting period.

.. i 3.2 Inoperable ~ Effluent Monitoring Inst umentation Explanation (ref.

Technical Specifications 6.9.1.4)

Explanations of why inoperable liquid and/or gaseous effluent monitoring instrumentation were not corrected within the time specified in Sections 3.3.3.10 or 3.3.3.11 of Technical Specifications are as follows:

3.2.1

. Condenser Vacuum Pump Vide Range Gas Monitors y

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.NIRA-RT-8027/N2RA-RT-8027 Condenser; Vacuum Pump Vide Range Gas Monitors process flow channels N1RA-RT-8027A and N2RA-RT-8027A vere removed from lO3 service on Nov aber 1, 1988, at 0100.

Since the problems with the monitors were not repaired within 30 days, tho following-is provided as an explanation.

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The Condenser Vacuum Pump Wide Range Gas Monitors NIRA-RT-8027 and N2RA-RT-8027 have similar_ problems with the process fluid stream-In both cases, the actual process flowrate is less than the designed process flowrate.

Plant Modifications89-066 and 89-067 have been completed to reroute the condenser vacuum exhausts to the resnective unit vent.

Placing these exhaust paths in service is contingent

_upon USNRC approval of a change to Technical Specifications which was originally.subritted on June 26, 1991 and_.

subsequent change to the Offsite Dose Calculation Manuai.

3.3 Gas Storage Tank Curie Limit Violation Description (ref. Technical Specifications 6.9.1.4)

The RCS Vacuum Degassing System was not used during this reporting period.

Therefore, the quantity of radioactive material in the RCS "acuum Degassing System Storage Tanks did not exceed the L11mits set

[

forth in Section 3.11.2.6 of Technical Specifications.

3.4 Unprotected' Outdoor Tank Curie Limit-Violatica Description (ref.

Technieni ugecifications 6.9.1.4) f(

Therelare no Unprotected _ Outdoor.Tankc at STPEGS.

.3.5 Abnormal (Unplanned) Release Description (ref. Technical Specification 6.9.1.4)

No abnormal releases from STPEGS Unit 1 or Unit 2 to UNRESTRICTED

AREAS occurred during this reporting period.

'3. 6 Radioactive Waste Process-Control Program Changes (ref. Technical Specifications 6.13.2)'

There were no. changer to the Radioactive Waste Process Control Program (PCP) during this reporting period.

-~

3.7 Offsite Dose-Calculation Manual Change (ref. Techn! cal

. Specifications 6.14.2.a)

No changes were made to the Offsite Dose Calculation Manual (ODCM) during'this reporting period.

3.8 New Land Use Census-Location (s)-Identification-(ref. Technical Specifications 3.12.2.a)

'The Land Use Census was not conducted during the report period.

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'E GASEOUS EFFLUENTS FOR 199?

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SITE: South Texas Project Electric Generating Station UNIT: 1-

-YEAR:

1992 HOUSTON LIGHTING & POWER SEMIANNUAL SUMMATION 0F ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS Unit: 1 Starting :

1.Jan-1992 Ending : 30-Jun-1992 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION _& ACTt'..,< PRODUCTS

1. TOTAL RELEASE CURIES 9.329E+01 8.854E+01 25

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.186E+01 1.126E401

3. PERCENT OF LIMIT (2.70E+05 uCi/sec) %

4.394E-03 4.171E.03

1. TOTAL RADI0 IODINES CURIES 8.091E-04 8.534E.04 25

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.029E.04 1.085E-04

3. PERCENT OF LIMIT (4.00E-02 uCi/sec) %

2.573E.01 2.713E.01 L;e C. PARTICULATES L

1. PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.742E-05 3.916E-05 25 I

2. AVERAGE-RELEASE RATE FOR PERIOD uCi/Sec 2.215E-06 4.980E-06 b$PhkbkhkbF[khkh(bbbhbkubkhsec)k h$hbkh bk

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D. TRITIUM i

hkhhRkbhbhlkkhkRkkhFbkPERkbbuhkhhec k$bbbh+bb k hhhh bb

3. PERCENT OF LIMIT (1.80E+05 uCi/sec) %

5.586E-04 2.344E-03

• Gross Alpha Radioactivity for second gaarter 199? will be updated in the next

[

Semiannual Radioactive Effluent Release Report if required.

l 1^

,.I U

l 17 l

m 4

SITE: South Texas Project Electric Generating Station UNIT: 1-YEAR:

1992 i

)

REPORT CATEGORY

SEMIANNUA'. AIRBORNE GROUND LEVEL CONTINUOUS AND

+

BATCH RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.

TYPE OF ACTIVITY-

FISSION GASES, 10 DINES, AND PARTICULATES REPORTING PEPIOD.

QUARTER # 1 AND-QUARTER # 2 YEAR 1992 f"'Cbbiibbbbi'kbbE f"'BAkCbbbbh f

L UNIT

QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 NUCLIDES RELEASED l

l KR-85 CURIES 0.00E+00 0.00E+00 8.71E-01 5.69E-02 KR-85M CURIES 1.67E-02 0.00E+00 2.94E-02 3.20E-02 KR-87 CURIES 0.00E+00 0.00E+00 2.20E-05 0.00E+00 KR-88 CURIES 0.00E+00 0.00E+00 5.50E-03 4.05F-02 CURIES 0.00E+00 0.00E+00-3.51E-01 1.22E+00 XE-131M(I-XE-133 l

CURIES 8.67E+01 8.38E+01 0.00E+00 0.00E+00 XE-133M CURIES 0.00E+00 0.00E+00 4.59E-01 5.38E.01 XE-135 CURIES 2.93E+00 1.36E+00 l 5.73E-01 4.91E-01ll TOTAL FOR PERIOD l

CURIES l8.97E+01l8.51E+01l3.64E+00-l3.38E+00l

L-I-131 CURIES 3.27E-04 3.84E-04 1.75E-05 1.85E-05 l.

1-132 CURIES 1.20E-04 0.00Er00 1.82E-06 0.00E+00 I-133 CURIES 3.27E-04 4.43E-04

• 58E-05 7.86E..

TOTAL FOR PERIOD l

CURIES l7.75E-04l8.28E-0*l3.51E-0512.64E-05l PARTICULATES C0-58 CURIES 0.00E+00 1.01E-05 1.99E-07 0.00E+00 C0-60 CURIES-

-.l. 59E 1.19E-05 0.00E+00 C.00E+00 4

CS-134

. CURIES 5.59E-07 3.04E-06 0.00E+00 2.72E-06

-CS-137 CURIES 7.58E-07 5.99E-06 0.00E+00 3.51E-06 MN.54 CURIES 0.00E+00 1.08E.06 0.00E+00 0.00E+00 SB-125 CURIES 0.00E+00 C.16E-07 0.00E+00 0.00E+00 l

R TOTAL FOR PERIOD l

CURIES l1.72E-05l3.29E-05l1.99E-0716.23E-06l OTHER-H-3 l

CURIES l7.47L+00l3.28E+01l4.27E-01l3.10E-01l-TOTAL FOR FfRiOD l CURIES l-7.47E+00_l3.28E+01l4.27E-01l3.10E-01l o

l Xe133 radioactivity was continuously quantified by the nnit vent noble gas monitor.

l.

Xel33 release.s,of 4,54E+01 and 6.13E+01 Ci for the first and second quarters.

! t, respectively, were not included with the 5*tch releases.

I i

18 L

l

-.~ -

SITE: South Texas Project Electric Generating Station UNIT:.2

-YEAR:

1992 s

HOUSTON LIGHTING & POWER-SEMIANNU.il SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS Unit: 2 Starting :

1-Jan-1992 Ending : 30-Jun-1992 TYPE OF-EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. 10T ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.368E+01 1.038E+02 25

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.739F+00 1.320E+01

3. PERCENT OF LIMIT (2.70E+05 uCi/sec) %

6.443E-04 4.890E-03 B. RAD 1010 DINES

1. TOTAL RA01010 DINES CUR!EJ 1.23BE-05 5.460E-05 25

2. AVERAGE RELEASE RATE FOR PERIOD uti/Sec 1.574E-06 6.944E-06

3. PERCENT OF LIMIT (4,00E-02 uCi/sec) %

3.936E.03 1.736E-02

-(

AJ C. PARTICULATES

1. PARTICULATES(HALF-LIVES >8 DAYS)

CURIES 1.170E-07 0.000E+00 25

2. AVERAGE' RELEASE RATE FUR PERICD uCi/Sec 1.488E-08 0.000E+00

3. PERCENT OF LIMIT (3.00E-01 uCi/sec) %

4.960E-06 0.000E+00 k$bkbbhk[hhkkkbkbbkkhkhh bbRikk b k9hh bb b bbbh bb D. TRITIUM

1. TOTAL RELEASE' CURIES 1.735E+00 4.389E+00 25 hkhhRkbEkkLhkhEkAkhFbkPhRkbbubkhhec h$hb7hbl bbbhhbh i:~iiibisi6E~iisii~ii:iii;6i~ubi);;;i%~~~~~~~~i$iiii:ii-~~i$iiii:i'~~~~~~~~~~

• Gross Alpha Radioactivity for secoid quarter 1992 will be updated in the next j

Semiannual Radioactive Effluent Release Report if required.

i i

^

l t ('

s 19 L

'3

~

SITE: South Texas Project Electric Generating Station UNIT: 2 YEAR:

1992

()

REPORT CATEGORY

SEMIANNUAL AIRBORNE GROUND LEVEL CONTINUGUS AND

BATCH RELEASES. TOTAL 3 FOR EACH NUCLIDE RELEASED.

TYPE OF ACTIVITY

FISSION GASES, 10 DINES, AND PARTICULATES l

REPORTING PLRIOD

QUARTER # 1 AND QUARTER # 2 YEAR 1992 l

CONTINUOUS MODE l

BATCH MODE l

UNIT

QUARiER 1 QUARTER 2 QUARTER 1 QUARTER 2 i NUCLIDES RELEASED l

l l

FIS39 GASES AR-41 CURits 0.0CE+00 0.00E+00 2.95E-01 6.92E-01 '

CURIES 4.76E-04 0.00E+00 0.00E+00 0.00E+00 XE-131M(2)

~

XE-133 CURIEj 1.30E+01 1.03E+02 0.00E+00 0.00E+00 XE-135 CURIES 3.81E-01 0.00E+00 0.00E+00 1.72E-04 kbhklkbRPkRibb bbRikk f k bkk bk i bbE bh f h$b5k bk b bhE b5 f 10 DINES 1-131 CURIES 8.33E-06 ' l.37E-05 2.65E-07 1.14E-05 1-133 CURIES 3.71E-06l1.09E-05 7.38E-08 1.86E-05 TOTAL FOR PERIOD l

CURIES l1.20E05l2.46E05l3.38E07l3.01E05l PARTICULATES h0hklFbRPkkkbb bbkkEh f i$ihk bh f b$bbk bb f 0$bbE bb b bbk bb f H-3 l

CURIES

!1.71E+00l3.97E+00l1.13E-02l4.14E-01l ibiii'ibi~PhRkbb fCbkkkS f k$hkk bb b$bhk b0 f k$bbk bh f k$kkk bk (25' Xc133 radioactivity was continuously quantified by the unit vent noble gas monitor.

Xel33 releases of I dt-01 and 5.17E 01 C; for the first and second quarters.

respect tvely,. we-oct included with the batch releases.

I 20

.- -. _....... - -. - ~...

4

• as t

gp g'i

' 7 7.

r L

I F

f -.

l-LIQUID EFFLUENTS t

FOR 1992 1

[-

1st and 2nd Quarters kh; M

T 3

t

[

f g@!

.~

[.'

1 21-3 m..+-..-ae-i.. -

-e.--eewe.

,,w+,

v.ev~.-w

.-v me,e wwm t r y -. ev v

..?

-w-e-

=g-+ + -

e de-*-

- ~ ~ -

SITE: South Texas Project Electric Generating Station UNIT: 1 YEAR:

1992-

>~'s HOUSTON LIGHTING & POWER V

SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS Unit: 1 Starting :

1 Jan-1992 Ending : 30-Jun-1992 TYPE OF EFFLUENT UNITS QUARTER !

QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT !?.CLUDING TRITIUM, GASES, ALM 1A)

CU?.iES 2,591E-01 1.996E 01 5

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.961E-08 2.843E-08

3. PERCENT OF MPC LIMIT (FRACTIONAL) 3.855E 01 3.825E-01 B. TRITIUM

1. TOTAL _RELP i CURIES 1.944E+02 2.512E+02 5

l

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uti/ML 4.473E-05 3.577E-05 I

' (V\\

3. PERCENT- 0F MPC LIMIT p.ou-03 ucve) %

1.491E+00 1.192E+00 b$bkkhbLhEbkbbkNhRkkNEfbkkkb t

l.

(('hhik['Rk[bkhE "bbRkkh~

k Ohkh bi~ h$hhbh bb "h

2. AVERAGE. DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.424E-08 5.024E-07

3. PERCENT OF LIMIT (2.00E.04 uti/ml) %

1.212E-02 2.512E-01 p

D. GROSS ALPHA RADI0 ACTIVITY i

I 1.-TOTAL RELEASE-CURIES 0.000F:00 0.000E+00 5

t-1 E. WASTE VOLUME RELEASED l,

1. TOTAL PRE-DILUTION VOLUME LITERS 3.151E+07 4.332E+07 1.3 l.

l

2. BATCH PRE-DILUTION VOLUME LITERS 2.952E+06 4.3E7E+06 1.3 h hbLbkh bF bk[bkkbh hkkhR bhEb LkhkRh k hkbhbh h bh2h bh kb G

22 l

m,_s---

,ii.

A

..uu.

a--

-.+4-4--;:: m J4.-

=

_.,A

.a SITE: South Texas Project Electric Generating Station UNIT: 1-YEAR:

1992 REPORT CATEGORY

SEMIANNUAL LIQUID CONTINUGUS AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED.

TYPE OF-ACTIVITY

ALL RADIONUCLIDES REPORTING PERIOD

QUARTER # 1 AND QUARTEP. # 2 YEAR 1992 lCONTINUOUSRELEASESl BATCH RELEASES l

UNIT

QUARTER 1 QUARTER 2 IQUARTER 1 I QUARTER 2 NUCLIOE l

l l-ALL NUCLIDES AG-110M CURIES 0.00E+00 0.00E+00 9.96E-04 6.54E-03 C0-57 CURIES 0.00E+00 0.00E+00 4.28E-04 3.65E-04 00-58 CURIES 0.00E+00 2.376-05 1.46E-02 3.37E-02 C0-60 CURIES 0.00E+00 1.73E-06 5.68E-02 1.02E-01 CR-51 CURIES 0.00E+00 0.00E+00 2.03E-04 2.76E-03 CS-134 CURIES 0.00E+00 0.00E+00 2.20E-02 1.14E-02 CS-136 CURIES 0.00E+00 0.00E+00 5.93E-05 2.70E-04 CS-137 CURIES 2.93E-06 0.00E+00 4.08E-02 1.48E-02 FE 55 CURIES 0.00E+00 0.00E+00 1.03E-01

• 0.00E+00 FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 3.50E-03 H-3 CURIES 3.37E-02 6.31E-02 1.94E+02 2.51E+02 1-131 CURIES 1.64E-06 1.77E-05 2.87E-03 6.14E-03 O

. I-133 CURIES 0.00E+00 2.08E-05 2.42E-04 0.00E+00 I-135 CURIES

-0.00E+00 0.00E+00 2.64E-05 0.00E+00 V

KR-85 CURIES 0.00E+00 0.00E+00-3.89E-03 5.95E-02 LA-140 CURIES 0.00E+00 0.00E+00 0.00E+00 2.22E-04 MN-54

- CURIES 1.43E-06 3.12E-06 9.69E-03 1.38E 02 M0-99 CURIES 0.00E+00 0.00E+00 6.02E-05 0.00E+00 NA-24 CURIES 0.00E+00 0.00E+00 5.09E-04 1.99E-06 NB-95 CURIES 0.00E+00 0.00E+00

-9.42E-04 6.77E-04 NB-97 CURIES 0.00E+00 0.00E+00 6.69E-05 4.02E-04 OTHER CURIES 0.00E+00 0.00E+00 1.57E-04 1.04E-04

- SB.124 CURIES 0.00E+00 0.00E+00 3.23E-05 2.08E-05

. SB-125 CURIES 0.00E+00 0.00E+00-4.79E-03 2.28E-03 SN-113 CURIES 0.00E+00 0.00E+00 8.69E-06 0.00E+00--

TC-99M CURIES 0.00E+00 0.00E+00 6.12E-05 0.00E+00 XE-131H CURIES 0.00E+00 0.00E+00 4.lPE-03 9.08E-02 XE-133--

CURIES-9.45E-06 2.98E-05 9.77E-02 3.38E+00 XE-133M CURIES 0.00E+CU 0.00E+00 1.06E-04 1.40E-02 XE-135 CURIES 0.00E+00 0.00E+00 2.10E-04 7.05E-04 7N 65 CURIES 0.00E+00 0.00E+00 1.33E-04 1.12E-04 ZR-95 CURIES 0.00E+00 0.00E+00 2.51E-04 2.23E-04 e

ZR-97 CURIES 0.00E+00 0.00E+00 0.00E+00 2.42E-04 TbhAbFbR3kRibb f CbRkEh f b$h7E bh f 6$hhk bh f k$9bh bh f h 55E bh f

• Iron-55 Radioactivity for second quarter 1992 will be updated in the next Semiannual Radioactive Ef fluent Release Report. if required.

23

SITE:

South Texas Project Electric Generating Station UNIT:

2 YEAR:

1992 HOUSTON LIGHTING & POWER SEMIANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS Unit: 2 Starting :

1.Jan-1992 Ending : 30-Jun-1992 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)

CURIES 3.297E-01 3.647E-01 5

2. AVERAGE DILU1ED CONCENT0ATION DURING PERIOD uCi/ML 9.247E-08 6.616E-08

3. PERCENT OF MPC LIMIT (FRAli;0NAL) 1.3EoE.01 1.425E-01 B. TRITIUM

-1.

TOTAL RELEASE CURIES 1.443E+02 1.191E+02 5

2. AVEP. AGE DILUTED CONCENTRATION

('

DURING PERIOD uCi/ML 4.047E-05 2.161E-05

3. PERCENT OF MPC LIMIT (3.cor-03 ucue) %

1.349E+00 7.203E-01 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 3.860E-02 2.169E-02 5

h5kVERkbEbkLbkhbbbbbkhkkkkkbb DURING PERIOD uCi/ML 1.074E-08 3.917E-09 h PhRbhbh bF Lkkkk (h bbE b4 ubi/ml) 5$bh4hbh k$958kbb D. GROSS ALPHA RADI0 ACTIVITY jfj'{ f(({'*{'---~~~-~~~~~~~~~~~~{fjj((-----'f}}}}- ff-~~f fff b b l E L E. WASTE VOLUME RELEASED l

l. TOTAL PRE-DILUTION VOLUME LITERS 2.503E+07 2.606E+07 1.3

2. BATCH PRE-DILUTION VOLUME LITERS 2.603E+06 3.251E+06 1.3 F. VOLUME OF DILUTION WATER USED LITERS 3.566E+09 5.512E+09 10

.r'% U. 24

SITE: South Texas Project Electric Generating Station . UNIT: 2-YEAR: 1992 l I REPORT CATEGORY

SEMIANNUAL LIQUID CONTINU0US AND BATCH RELEASES

TOTALS FOR EACH NUCLIDE RELEASED.

TYPElDF ACTIVITY

ALL RADIONUCilDES REPORTING PERIOD

QUARTER # 1 AND QUARTER # 2 YEAR 1992 I'bbkiibbbbb'kEbhkhkh f bkhbb kkbEkhEh~ f UNIT

QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 NUCLIDE-l l

ALL NUCLIDES AG-Il0M CURIF^ 0.0GC+00 0.00E+00 5.92E-04 1.14E-04 BE-7 CURit-0.00E+00 0.00E+00 0.00E+00 2.C;E-05 CE-144 CURIES 0.00E+00 0.00E+00 5.08E-05 0.00E+00 C0-57 CURIES 0.00E+00 0.00E400 8.35E-04

.6CE-03 C0-58 CURIES 0.00E+00 0.00E+00 1.24E-01 1.26E-01 C0-60 CURIES 0.00E+00 0.00E+00 7.00E-02 1.70E-01 CR-51 CURIES 0.00E+00 0.00E+00 2.13E-02 4.28E-03 CS-137 CURIES 0.00E+00 0.00E+00 4.24E-05

• 6.38E-06 FE-55 CURIES 0.00E+00 0.00E+00 5.'.2E-02 0.00E+00 FE-59 CURIES-0.00E+00 0.00E+00 1.45E~02 5.55E-03 H-3 CURIES 1.62E-02 5.78E-02 1.44E+02 1.19E+02 LA-140 CURIES 0.00E+00 0.00E+00 1.60E-05 4.15E-07 MN-54 CURIES 0,00E+00 0.00E+00 1.42E 02 3.14E-02 f]~

NA-24 CURIES 0.00E+00 0.00E+00 1.09E-05 1.28E-06 N8-95 CURIES 0.00E+0L 0.00E+00 9.40E-03 1.07E-02 NB-97 CURIES 0.00E+00 0.00E+00 1.06E-04 2.12E-04 OTHER CURIES 0.00E+00 0.00E+00 1.64E-05 0.00E+00 SB-124 CURIES-0.00E+00 0.00E+00 4.15E-03 1.48E-03 SB-125 CURIES 0.00E+00 0.00E+00 7.llE-03 6.04E-03 SN-ll3 CURIES 0.00E+00 0.00E+00 1.00E 1.34E-03 XE-133-CURIES 0.00E+00 0.00E+00 3.81E-02 2.16E-02 XE-133M. CURIES 0.00E+00 0.00E+00-2.39E-04 5.53E-05

XE-135 CURIES 0.00E+00 0.00E+00 2.08E-04 3.74E-05 ZN 65 CURIES 0.00E+00 0.00E+00 4.40E-04 7.45E-04 ZR-95 CURIES 0.00E+00 0.00E+00 4.75E-03

.5.llE-03 i$6hEbbih$hbEbhfi$4hEbhfk$59hbhf kbhkLFbkPERkbb fbbRiEh

• Iron-55 Radioactivity for second quarter 1992 will be updated in the next Semlannual Radioactive Effluent Rehase Report, if regired.

25

.. - -..... ~ - -...... -... - -.... - - -.. -. - -...... -.......; - - ~ -..- ~ - ~. -, .- -... _ ~... 4 4 d 5 J A 4 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (- 1st and 2nd Qur-ters, 1992 ? t-D 4 )F,' I f f f 3 p 9; m 26 t rev y 'gy w ve c- --m,*a-9w -e*t-~ 'w=rms-t'-r-- '*=w;wde-e w t'-*

• • -a*-"--

EFFLUENT AND WASTE DISPOSAL REPORT FROM 01/01/92 -0:00 TO 06/30/92 23:00 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS )- A. SOLID WASTE SHIPPED OFF SITE FOR 9URIAL OR DISPOSAL 1. TYPE OF WASTE UNIT 6 MONTH EST. TOTAL PERIOD ERROR I A. SPENT RESINS, FILTER SLUDGES, m3 2.09 E+01 + 1.00E+00 EVAPORATOR BOTTOMS, ETC. C1 2.69 E+01 + 5.00E+00 B. DRY COMPRESSIBLE WASTE, m3 3.22 E+00 + 1.00E+00 CONTAMINATED EQUIP., ETC.* Ci 1.16 E+00 + 5.00E+00 C. IRRADIATED COMFONENTS, CONTROL m3 0.00 E+00 N/A RODC. ETC. Ci 0.00 E+00 N/A D. OTHER** m3 2.83 E-03 N/A C1 2.71 E+00 N/A Two shipments of DAW sent for offsite volume reduction (1.18E+01 m, 7.34E-01 C1)

• • Other waste consisted of steam generator ahot peening residue shipped toge'.her with spent resins (shipment 2-92-0218) 2.

ESTIMATE OF MlL70R NUCLIDE COMPOSITION (BY TYPE OF WACTE) A. 1 Co60 2.18E+01 2 CoS8 2.17E+01 3 N163 1.91E+01 4 FtS5 1.50E+01 5 Nb95 7.80E+00 6 Zr95 3.20E+00 g l 7 Mn54-3.00E+00 8 Cs137 2.60E+00 9 Fe59 1.50E+00 10 Sb125 1.40E+00 11 Ca134 1.10E+00 B. I Fe5S 6.36E+01 2 CoS8 1.71E+01 3 Cr51 4.20E+00 4 Co60 4.20E+00 5 Ni63 3.30E+00 6 Nb95 2.10E+00 t Zr95 1.90E+00 8 Mn54 1.60E+00 9 Fa59 1.50E+00 C. N/A N/A D. I-Fe55 4.76E+01 2. Co60 2.80E+01 3. CoS8 1.79E+01 4 Mn54 3.20E+00 l l lO i 27 l L

EFFLUENT AND WASTE DISPOSAL REPORT t i FROM' 01/01/92 0:00 TO 06/30/92 23:00 . SOLID WASTE AND IRRADIATED FUEL SEIPMENTS 3. SOLID WASTE DISPOSITION (NOT IRRADIATED FUEL) NUMBER OF SHIPMENTS MODE OF TRAhJPORTATION DESTINATION

• 6 Truck

- Scientific Ecology Group, Inc. (SEG) j 1560 Bear Creek lid, i Oak Ridge, TN - Chom-Nuclear Systems (CNSI) Larnwell Waste Manage-ment Facilit, j Osborne Road Barnwell, SC - JS Ecology (USEN) Beatty Street Beatty, NV

• All shipments from STPEGS w2re either to SEG or CNSI.

However, SEG buried STPEGS waste at both CNSI and USEN. 4. CLASS OF SOLID WASTE AU, AS, C** 5. TYPE OF. CONTAINERS USED FOR SHIPMENT Strong-tight, High Integrity Centeiners, Type A casks. 6. SOLIDIFICATION AGENT N/A B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION --- NO SHIPMENTS MADE DURING THIS PERIOD ---

• • Class C waste based-on 1.00E-01 ft of steam generator shot peening residue chipped together witi. spent resins in a polyethylene high integrity container (shipment 2-92-0218) u.

l 28 ..}}