RBG-28747, Semiannual Radioactive Effluent Release Rept for Jan-June 1988

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Semiannual Radioactive Effluent Release Rept for Jan-June 1988
ML20153G178
Person / Time
Site: River Bend Entergy icon.png
Issue date: 06/30/1988
From: Booker J, Cargill E, Fantacci C
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RBG-28747, NUDOCS 8809080064
Download: ML20153G178 (32)
v • d • e


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I RIVER BEND STATION, UNIT 1 j i SDIIAWUAL RADIOACTIVE DTLUENT RELEASE REPORT REPORT PERIOD January 1,1988 'Ihrcugh June 30, 1988 ,

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! REVIDE:D BY I b h7 -

2 C. 3. Fantacci', Radiological Engineering Supervisor l

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/ I l APPPOVED BY M [

E. M. 9Ergill, Director - Radiological Programs f

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f TAB 2 OF (XNITNIS PAGE I. DEFODUCTION 1 II. SUPPLHE27tAL IN W R WTION A. REGJIA'IORY LDfITS 2 B. MAXDM1 PEmiISSIBLE CLNCEIERATICtJS 6 C. AVERAGE DERGY 6 D. MEASURD12ES AND APPRO.WIQ1S OF WIAL PADIO7CTIVI'IY 6 E. BA'IGI REEASES 8 F. ABNORRL RELEASES 9 G. ESTDRTE OF 'IUTAL ERFOR 9 III. GASEDUS EFFWDES SUM \RY INERWTION 10 IV. LIQUID EFFwDES SURRRY INNRWTION 10 V. SOLID WASTE 10 VI. RADIOILGICAL DIPACT ON PAN 10 VII. METEDFOIDGICAL DATA 10 VIII. PADIOlcrIVE LIQUID EH'LUDTP MONITORING INSTRUG2EATIQ1 OPEPABILITY 10 IX. P/OIOICTIVE GASEIUS EFFLUE*C' FEtiI'IORDKi INSITL'MD7PATICt1 OPEPABILITY l1 X. LICUID IIOID UP TM?YS 11 XI. PADIOILGICAL DNIIOtM2TfAL FX.11I'IORJKi 11 XII. LMO USE CDEUS 11 XIII. OnSITE DOSE CAICUIATION FWiUAL (0D04) 11 XIV. FWJOR CIWEES 'IO PADIGICTIVE LICUID, CASQU3 NO SOLID WASTE TREADtE2Tr SYSTE24S 11 XV. PROCESS 00!THOL PIOGPR4 (PCP) 11 L

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I PAGE XVI, 'DLRTys

. TABLE 1 RADIOM:TIVE GASEQUS WSIE SAMPLING AND M4ALYSIS PBOGPAM 12 TABLE 2 RADIOACTIVE LIQUID WGTE

, SAMPLING AND ANALYSIS PM) GRAM 13 a

'IABIE 3 GASECUS EM M - SUN RTION t OF ALL RELEASES 14 l i

TABE 4 GASECUS EFFLUENIS - GNDITICNALLY i E 2 VAT E RELEASES 16

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TABLE 5 GUE00S EETWEN15 - GBOUND .

4 IEVEL REEASES 19  !

i-1 TABIE 6 LIQUID EFFLUD7tS - SLMETICH OF ALL RELEASES 22

l t TABIE 7 SOLID h73rE AND IRRADIATED f

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FUEL SHIRENTS 26

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SEMIAftlUAL RADIQACTIVE EXTWENT RE MASE REPOhT FRCILITY: River Bond Station, Unit 1 IJCENSEE: Gulf States Utilities REPORF PERICD: January 1, 1988 through June 30, 1988 I. IN11YIXrrICN Enclosed is the Saniannual Fadioactivo Effluent Releaso Peport for l the period of January 1,1988 through June 30, 1988. 'Ihis report is l sulnittcd in accordance with Technical. Specificaticn 6.9.1.8 of l Appendix A to River Dend Station (RBS) License Ntrnber NPF-47.

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II. SUPPLEMENTAL INFORMATION A. Regulatory Limits

1. 10CFR20 Limit's
a. Fission and Activation Gases In ar.cordance with Technical Specification 3.11.2.1, the dose rate due to noble gases released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin:

DR TB

" 8" *

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= 3.15 x 10 I Kg (X/Q) Q 15 500 mrems/yr i=1 and DR skin

= D se rate to the skin in mrems/yr n _ .

= 3.15 x 10 I (Lg + 1.1Mg )(X/Q) Q1$ 3000 mrems/yr i=1 (above tarms defined in RBS ODCM).

b. Radioiodines and Particulates In accordance with Technical Specification 3.11.2.1, the dose rste due to Iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site to areas at and beyond the SI1I BOUNDARY shall be limited to less than or equal to 1500 mrems/yr to any organ:

DR I68DPt

= Dose rate to the organ t for the age group of interest from iodines, tritium, and 8 day particulates via the inhalation pathway in mrees/yr n ___

= I Pg (X/Q)D O i $ 1500 mrems/yr i=1 (above terms defined in RBS ODCM)

c. Liquid Effluents In accordance with Technical Specification 3.11.1.1, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved and entrained noble gases. For dissolved or entrained noble gases, the concentration shall bc limited to 2 x 10 microcuries/ml total activity.
2. 10CFR50, Appendix I Limits
a. Fission and Activation Gases In accordance with Technical Specification 3.11.2.2, the air dose due to noble gases released in gaseous effluents to areas at or beyond the SITE BOUNDARY shall be limited to:

D = e gamma air dose from radioactive nome Gamma-Air gases in mrad

= I M g(576)Q g 5 5 mrads/qtr g3 $ 10 mrads/yr D = Beta air dose from radioactive noble Beta-Air gases in mrad

= N g(576)Qg I 5 10 mrads/qtr g3 5 20 mrads/yr (above terms defined in RBS ODCM)

b. Radiciodines and Particulates In accordance with Technical Specification 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, and all radionuclides in particulate form with half-livos greater than 8 days, in gaseous effluents releases to areas at and beyond the SITE 300NDARY shall be limited to:

D = Dose in mrem to the organ (t) of a I68DPt specified age group from radioiodines, tritium, and 8 day particulates via the pathway of interest l

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= 3.17 x 10 I Rg (X/Q)D 0 1 i=1 and/or n

= -8 3.17 x 10 I Rg (D/Q) Q g i=1

!Lnd D = Dose in mrem to the organ (t) of a specified age group from radioiodines, tritium, and 8 day particulates froc all pathways n

= I D I68DPt I * *#'*#I9 #

z=1 5 15 mrems/yr (above terms defined RBS ODCM)

c. Liquid Effluents In accordance with Technical Specification 3.11.1.2, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS shall be limited to:

D = Total dose commitment to the organ (t)

TOTALt due to all releases during the desired time interval in mrem n

where: D =

TOTALt (Dta)i i=1 n n and Aitaty Qgg D,= I Dg = I i=1 iol (DF)g D, 1 i

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and D TOTAL 5 1.5 mrama/qtr Total Body 5 3 mrems/yr D

TOTAL I ~"#**"I9 #

ANY ORGAN

$ 10 mrems/yr.

I (above terms defined in RBS-0DCM) .

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3. 40CFR190 Limits In.accordance with Technical Specification 3.11.4, the annual  !

3 (calendar -year) dose or dose commitscut to any MEMBER OF THE 4

PUBLIC, due to releases of radioactivity 'and to' radiation ,

from uranium fuel cycle sources, st all be limited to

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. f i 5 25 mrems to the total body or any organ (except the thyroid) t i

5 75 mrems to the thyroid i

1 4. Miscellaneoue. Limits ,

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a. Ventilation Exhaust Treatment System  ;

In accordance with Technical Specification 3.11.2.5, the 3 VENTILATION EXHAUST TRFATMENT SYSTEM shall be used to  :

! reduce radioactive materials in gaseous waste prior to l J their discharge when the projected doses, due to gaseous  ;

j effluent releases to areas at and 'beyond the SITE i j BOUNDARY would exceed 0.3 mrem to any organ in a 31 day [

period. I L

j b. biquid Radwaste Treatment System  ;

-l In accordance with Technical Specification 3.11.1.3, the l

[ liquid radwaste treatment system shall be used to reduce  ;

1 the radioactive materials in liquid wastes prior to their  ;

discharge when the projected doses, due to the liquid  ;

i effluent, to UNRESTRICTED AREAS would exceed 0.06 arem to (

the total body or 0.2 mrem to any organ in a 31 day  !

period.

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B. Mcximus Parmissible Conctntrations

1. Gaseous Releases The RBS Radiological Effluents Technical Specifications (RETS) for gaseous releases are based on the dose rate restrictions of 10CFR20, rather than the Maximum Permissible Concentrations (MPC) Ifsted in 10CFR20 Appendix B, Table II, Column 1.
2. Liquid Releases The Maximum Permissible Concentration of radioactive materials in liquid effluents is limited by 10CFR20, Appendix B, Table II, Column 2. The MPC chosen is the most conservative value (i.e., the lowest) of either the soluble or insoluble MPC for each radionuc' _de.

C. Average Energy Not applicable to RBS RETS D. Measurements and Approximations of Total Radioactivity

1. Gaseous Effluents
a. Fission and Activation Gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent. These samples are analyzed utilizing high resolution germanium detectors coupled to computerized pulse ba*nht analyzers. The s ampling and analysis frequencies are described in Table 1. Sampling and analysis of these effluent streams provide noble gas radionuclide relative abundances which can then be applied to the noble gas gross activity and gross activity release rate to obtain nuclide specific activities and release rates. The noble gas gross activity released within a specific time period is determined by integrating the stack monitor release rate over the considered time period. An average correction factor of 0.015 has been utilized for this report period due to the infrequent detection of noble gas radionuclides in the effluent stream. If no activity was detected between stack grab samples and significant increase in hourly averages were recorded, the nuclide relative abundances of the last sample which indicated the presence of activity was utilized to obtain nuclide specific activities.

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b. Payticulates rnd Iodinto Particulates cnd iodinas era continuou21y scmpisd from each of the three release points utilizing a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 1. Analysis is performed to identify and quantify radionuclides utilizing high resolution germanium datectors coupled to computerized pulse height analyzers. Given the nuclide specific activity concentrations, process flow rate, and time which the sample covered; the nuclide specific activity released to the environment can be c>cained.

Due to the continuous sampling process, it 19 assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Sr-89 and Sr-90 are quantitatively anslyzed by counting the digested filter precipitate with a gas flow proportional counter. Gross alpha analysis is performed using a zine nulfide scintillation counter.

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c. Tritium Tritium grab samples are obtained from the three release points at the specified frequencies listed in Table 1 utilizing an ice bath condensation collection method.

The collected sample is then analyzed utilizing a Liquid Scintillation Counter. Given the tritium concentration, process flow reta _and time period for which the sample is obtained, the trttium activity released to the environment can be deterained. Due to the frequency of sampling, it is assumed that the tritiva is released to the environment at a consta.,t rate within the time period for which the sample is obtained

2. Liquid Effluents Representative grab samples are obtained from tls appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 2.

Analysis for gamma emitting nuclides (includjng dissolved and entrained noble gases) is performed utilizing a high resolution germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined utilizing a Liquid Scintillation Counter. Sr-89 and Sr-90 are quantitatively analyzed by counting the precipitate with i a gas flow proportional counter. Fe-55 is counted with a Liquid Scintillation Counter after digestion of the iron.

Gross alpha analysis is performed using a zinc sulfide i scintillation counter. 1 Given the nuclide specific activity concentration and total volume of the tank that was released, the activity of each i nuclide released to the environment can be determined. '

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- E. Batch Ralsescs

1. Liquid 1st Quarter 1988
a. Number of batch releases  : 128
b. Total time period for batch releases  : 815.03 hr
c. Maximum time period for batch releases  : 7.57 hr a
d. Average time period for batch releases  : 6.37 hr
e. Minimum time period for a batch release  : 3.47 hr
f. Average stream flow during periods of 3

release of effluent into a flowing stream : 730,000 ft /sec ,

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2nd Quarter 1988 '

j a. Number of batch releases  : 61

b. Total time period for batch releases  : 383.48 hr
c. Maximum time period for batch releases  : 8.17 hr  ;
d. Average time period for batch releases  : 6.29 hr

) e. Minimum time period for a batch release  : 0.07 hr j . f. Average stream flow during perioc's of l 3

5 release of effluent into a flowing stream : 393,000 ft /see i

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2. Gaseous ,

a 1 During this reporting period all gaseous releases were I l considered continuous releases, and no batch releases I i occurred.

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F. Abn:rmal R31ersss There were no abnormal releases during this reporting period. ,

.. G. Estimate of Total Error

1. Liquid The 'saximum error associated with sample collectior, laboratory snelysis, and discharge volume are collectively estimated to be:

Fission and Activation Products : 1 14.2%

Tritium : 1 14.2%. ,

Dissolved and Entrained Noble Gases : + 14.2%

Gross Alpha Radioactivity : 1 14.2%

2. Gaseous The maximum errors (not including sample line loss) associated with sample flow, process flow, sample collec*. ion, monitor accuracy and laboratory analysis are collectively estimated to be:

Fission and Activation Gases : 1 37.0%

Iodines : 1 18.6%

Particulates : 1 18.6%

Tritium : 1 18.2%

3. Determination of Tocal Error The total error (i.e., collective error due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.) is calculated using the following equation: ,_

E + (E 2) + *** IE n)

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E T

" ****1 #*'

E,E2 ... E, g

= individual errors due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.

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l III. GASEQUS EFFLUENTS

SUMMARY

INFORMATION Refer to Tables 3, 4 and 5 for Summation of All Releases and Nuclides Released, respectively. It should be noted that an entry of "0.00E>00" Ci or uCi/sec in this section dooa not indicate the absenca of a radionuclide; but, rather, indicatas that the i concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 1.

IV. LIQUID EFFLUENTS

SUMMARY

INFORMATION Refer to Table 6 for Summation of All Releases and Nuclides Released.

It should be noted that an entry of "0.00E+00" Ci or uCi/ml in this section does not indicate the absence of a radionuclide; Lat, rather, indicas s that the concentration of the petticular radionuclide was below the Lower Limit of Detection (LLD) as listed in Tab'.e 2. ,

V. OLID WASTE Rei~er to Table 7 VI. RADIOLOGICAL IMPACT ON MAN hic information will be piovided in the ,nd-of-year report as '

described in Techrical Specification 6.9.1.8.

i VII. METEOROIAGICAL DATA Thin information will be provided in the end-of-year report as described in Technical Specification 6.9.?.8.

VIII. RALI0 ACTIVE LIQUID EFFLUENT MONITORING IN!sFrtUMENTATION OPEPABILITY he minimum number of chennels required to be OPERABLE as described in Table 3.3.7.10-1 of Technical Specification 3.3.7.10 were, if inoperable at any time in the perisi 1/1/88 through 6/30/88, restored to operable status within the required time. Reporting of tt e inoperable channels in this : 6 port is, theref"re, not required.

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. IX. RADI0 ACTIVE G/SFOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY The m%imum number of channels required to be OPERABLE as described in Table 3.3.7.11-1 of Technical Specification 3.3.7.11 were, if inoperable at any time in the period 1/1/88 through ti/30/88, restored to operable status within the required time. Reporting of these inoperable channels in this report is, therefore, not required.

X. LIQUID HOLD UP TANKS The maximum quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected outdoor tank during the period of 1/1/8b through 6/30/88 was less than or equal to the 10 curie limit as required by Technical Specification 3.11.1.4. .

XI. RADIOLOGICAL ENVIRONMENTAL MONITORING There were no changes an sampling locations for the Radiological Environmental Monitoring Program (REMP) d'aring the reporting period 1/1/88 through 6/30/83.

XII. TAy0 USE CENSUS This it. formation will be presented in the end-cf-year report. The Land Use Censes results will be available in September 1988.

XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the Offsite Dose Calculation Mt.tual (ODCM) during the reporting period 1/1/88 through 6/30/88.

XIV. MAJOR C)* NGES TO RADIOACTIVE _ LIQUID, GASEOUS, AND SCI,ID k'ASTE

_TREATML S '.,YSTEMS There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems (or the period of 1/1/88 through 6/30/88.

a XV. PROCESS CONTROL PROGRAM (PCP)

No changes were cade to the RBS Process Cont':1 Progra:n (PCP) for the ,

pe 'vi 1/1/88 through 6/30/88.  :

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TAin.E I RADI0 ACTIVE TASE0tf5 MASTE SAMPtING AND ANAL.Y5t%_PPOGRAM _

Minimum ~~~~iike iindi ut Sampling Analysis Type of Detectson (I1!!)

seaseous Release Type Frrouency frequcncy Activity Analysis (uci/ml)

-4 Principal Ganma Emitters lx10 A. Main Plant M Exhat st Duct Grab Sample M -6 M Principal Ganea Daitters lx10-B. Fuel Building Ventilation Grab Sample M -6 if-3 lx10 Exhaust Duct

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L Hadwaste Building M Principal Gonna Emitters Ix10-4 Ventilation Grab Sample M

Exhaust Duct ,

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-I2 All Release Types Continuous W I-131 lx10 D.

as listed in A,B, Charcoal -10 Sample I-133 lx10 C above.

-II Continuous W Pr'ncipal Gamma Emitters 1x10 Particulate (I-131,Others)

Sample

-II Continuous M Gross Alpha lx10 Compos,te Particulate Sample

-II Continuous Q SR-89, SR-90 1x10 Cotposite Particulate -

Sample W= At least once per 7 days M= At least once per 31 days Q= At least once per 92 days 4 l u._,. . , _ ___..-__ _.___m -.... . . . _ - , _ _ _ _ _ = - - - - . _

. .__ _ _ . . . , _ , _ . . . _ _ _ . _ _ . . . _ . - , _ , . , , , m ._ _ -_ . , ._- . _ __ _

L TABLE 2 RADI0 ACTIVE LIGl!D WASTE SAMPLING AND ANALYSIS PROGRAM

" Lower Limit Minimum of. Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis (uC1/ml)

A. Batch Waste P P Principal Gama 5x10~7 Release Each Batch Each Batch Emitters; except 1 (Liquid for Ce-144 5x10*6  ;

Radweste _ _ _

I Recovery l 1 Sample I-1J1 1x10-6 Tanks)

P M Dissolved and 1x10-5 l

J One Batch /M Entrained Gases i I (Gama Emitters)

' 1x10-5 P M H-3 j Each Batch Composite l Gross Alpha 1x10'7 i

P Q Sr-89, Sr-90 5x10-8 Each Batch Composite i

Fe.55 1x10-6  ;

I P = Prior to each radioactive release  !

M = At lesst once per 31 days Q = At least once per 92 days l h

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'mB2 3 Effluesit and Maste Disposal Seuni-Annual 14@ ort 1988 Year namarma Mfluents - Sussumtion of All blamaan 1/2 Quarters l l Est.

Unit Guarter 1 l

] Quarter 2 .

{ 'lbtal Error, % ,

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A. Noble Gases

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1. 'Ibtal release ci 1 .65E+00 ' O.00E+00 3.70E+01
2. Average release rate !uCi/sec 2.09E-01 ! 0.00E+00 for period  ? '

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3. Percent of technical  % 5.42E-02 0.00E+00 specification linit (1)

B. Iodines I-131 l

1. 'Ibtal I-131 and I-133 Ci 2.70E-05 1.24E-04 1.86E+01 l I-133 l l Ci 3.58E-04 1.12E-03 " 1.86E+01 l I-131
2. Average relcase rate , _uCi 3.43E-06 1.57E-05 for period '

see I-133 4.54E-05 ? 1.42E-04 u

3. I-131 + I-133 contriba-  %

l tion percent of techni- 1.52E+00 ; 6.81E+00 l l cal specification limit  ! j C. Particulates i

1. Particulates with half- Ci i g lives of > 8 days 7.95E-05 l (2) 1.86E+01 l i
2. Average release rate uCi/ soc ,

l l l for period , 1.01E-05 l (2)  !

i l i l } 3. Percent of technical  % ' ' l i

! I specification limit 1.93E-01 (2)  ;

i i 4 i l l 4. Gmus 4.'lpha Ci

! ., ,r g oagg,vity ,

! 0.00E+00 ! 0.00E+00_l 4

i l 1 Est. l Unit l l Querter Quarter ' 'Ibtal I l l 1 2 Error, % ;l '

D. Tritiun l l l

1. Total release C1 2.89E-01 1.19E+00l1.82E+01
2. Average relcano rato uCi/sec 3.67E-02 ' 1.51E-01 for period
3. Percent of technical  % 1.06E-03 4.36E-03 l specification limit (1) Gama airdose limit of 5 mrads/qtr (T.S.3.11.2.2.a) .

j (2) tiot availabic for subnission at this tine, supplmental report to follow.

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4 'mBIE 4 Effluent aryl Maste Di&1 Seal-Annual Report 1988 Year Gaseous Effluents - Conditionally Elevated Releases 1/2 Quarters 1

Continuous Mode Batch Modo ,

i Nuclides Released Unit ! Quarter 1 Qaarter 2 Oaarter 1 Quarter 2

1. Fission Gases i

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I I f Argon-41 i Ci 0.00E+00 ' O.00E+00 N/A N/A ,

Krypton-85m Ci ' O.00E+00 0.00E+00 l N/A N/A a  !

Krypton-85 Ci 0.00E+00 ' O.00E+00 N/A N/A l

Krypton-87 Ci 0.00E+00 0.00E+00 N/A N/A ,

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l Krypton-88 Ci 0.00E+00 0.00E+00 N/A N/A  !

j Xenon-133m Ci 0.00E+00 0.00E+00 N/A N/A '

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1 Xenon-133 Ci '

O.00E+00 0.00E+00 N/A N/A  !

J i i Xenon-139n Ci 0.00E+00 0.00E+00 N/A N/A 4

Xenon-135 Ci 1.65E+00 0.00E+00 N/A N/A [

l Xenon-137 Ci 0.00E+00 0.00E+00 N/A N/A l t

Xenon-138 Ci 0.00E+00 0.00E+00 N/A N/A '

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i unidentificd Ci N/A N/A N/A N/A '

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Tbtal for period Ci '

1.65E+00 1 0.00E+00 N/A 1 N/A 4

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Iodine-131 Ci 2.70E-05 1.24E-04 N/A ' N/A

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! Iodine-132 Ci O.00E+00 1 0.00E+00 N/A N/A I i

) Iodine-133 Ci 3.58E-04 '

1.12E-03 '

N/A '

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i Iodine-134 l Ci 0.00E+00 0.00E+00 N/A N/A

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j j Iodine-135 Ci ' O.00E+00 0.00E+00 l N/A N/A I

i  ! Total Ci ' 3.85E-04  ! 1.248-03 l N/A N/A 1

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l Continuous Mode Batch Mode  !

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Nuclides Released Unit Quarter 1 l Cuarter 2 Quarter 1- Quarter 2 l l i

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3. Particulates l

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Strontiun-89 Ci 5.80E-06 (1) N/A N/A l Strontiun-90 Ci 0.00E+00

) (1) N/A N/A l Cesiun-134 Ci 0.00E+00 0.00E+00 N/A N/A f

)

j Cesiun-137 Ci 0.00E+00 0.00E+00 N/A N/A i

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4 _ Bariun-lanthanun-140 Ci 0.00E+00 0.00E+00 N/A N/A 1

j Cobalt-60 Ci 0.00E+00 0.00E+00 N/A N/A j Chroniun-51 Ci 0.00E+00 0.00E+00 N/A N/A 1 i l Zirconium-niobium 95 Ci 0.00E+00 0.00E+00 '

N/A N/A l Zirc-65 Ci 0.00E+00 0.00E+00 N/A ' N/A  !

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s Iron-59 Ci 0.00E+00 0.00E+00 N/A '

N/A  !

i L I l j Manganese-54 Ci 7.30E-05 0.00E+00 N/A ' N/A i t

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1 Iodine-131 Ci 0.00E+00 0.00E+00 N/A N/A  :

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Coriun-141 Ci 0.00E+00 0.00E+00 N/A ' N/A  !

f Ceritn-144 Ci 0.00E+00 0.00E+00 N/A N/A i l

) k '

, Ccbalt-58 '

Ci 0.00E+00 0.00E+00 N/A N/A i

Silver-110m Ci

. l l 0.00E+00 0.00E+00 N/A N/A L

' I l telybdenum-99 Ci 0.00E+00 0.00E+00 N/A N/A l 1

. , , I

) unidentified Ci '

N/A N/A N/A N/A '

i i e

'Ibtal for pericxl Ci '

7.88E-05 t (1)  ! N/A  ! N/A l I

l

\

1 l

! l

i l

1 ,

Fr Continuous bede Batch Mxie Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 4.0 Tritiun

__ Hydrogen-3 Ci 2.24E-61 1.14E+00 N/A N/A (1) Not twailable for sulanission at this tine, sugimental report to follow.

Main Plant Exhaust Duct is considered a conditionauy elwated release point.

a e

TABIE 5 6 Effluent arvi Waste Disposal Semi-Anranal Itaport 1988 Year J

Camaram ELI'luents - Grourd Imvel klaaman 1/2 Quarters Continuous }% Batch Mode i  !

Nuclides Released l Unit Quarter 1 Quarth. 2 l Quarter 1 Quarter 2

1. Fission Gsses I , , I Argon-41 Ci 0.00E+00 0.00E+00 N/A N/A l

Krypton-85m Ci 0.00E+00 0.00E+00 N/A N/A Krypton-85 Ci 0.00E+00 O.00E+00 N/A N/A {

Kryp+cn-87 Ci 0.00E@0 0.00E+00 N/A N/A j Krypton-88 Ci 4 0.00E+00 0.00E+00 N/A N/A

? ,

s l

Xenon-133m Ci 0.00E+00 0.00E+00 N/A N/A i

! Xenon-133 Ci 0.00E+00 0.00E+00 N/A N/A k i

Xenon-135m Ci 0.00E+00 0.00E+00 N/A N/A l Xenon-135 Ci 0.00E+00 0.00E+00 N/A N/A i

I Xenon-137 Ci 0.00E+00 0.00E+00 N/A N/A ,

i i

Xenon-138 Ci 0.00E+00 0.00E+00 N/A N/A l , unidentified Ci N/A N/A N/A N/A l f l

l j 'Ibtal for period l Ci 0.00E+00 0.00E+00 1 N/A N/A l l t

2. Gaseous Icdines i

'l

'l l .1 ,, , ,

l Iodine-131 Ci 0.00E+00 0.00E+00 N/A N/A l

Icdine-132 Ci '

O.00E400 0.00E+00 N/A N/A I i

, Iodine-133

~

Ci  ! 0.00E+00 0.00E+00 N/A N/A

, j l Iodine-134 Ci ' O.00E+00 l 0.00E+00 N/A N/A l l

! I i . l

, Iodino-135 '

Ci  ! 0.00E+00 ' O.00E+00 l N/A N/A l t ,

i i ,

i j 'Ibtal Ci 1 0.00E+00 , 0.00E+00 i N/A N/A l

4 l

)

i l ,

1 l L

l . ,

t l

l Continuous Mode Batch bbde Nuclides Released '

Unit Quarter 1 Quarter 2 ' Ouarter 1 ' Quarter 2 '

l 3. Particulates l

Strontium-89 Ci 0.00E+00 (1) N/A N/A l l l Strontium-90 Ci 0.00E+00 (1) N/A N/A l

l Cesium-134 Ci 0.00E+00 0.00E+00 '

N/A N/A l

Cesium-137 Ci 0.00E400 0.00E+00 N/A N/A Barium-lanthantrn-140 Ci 0.00E+00 0.00E+00 N/A N/A Cobalt-60 Ci 7.02E-07 0.00E+00 N/A N/A i

Chrcniun-51 Ci 0.00E+00 0.00E+00 N/A N/A Zirconium-niobiun-95 Ci 0.00E+00 0. 00E+00 N/A N/A ,

I Zine-65 '

Ci ,

0.00E+00 0.00E+00 N/A N/A l Iron-59 Ci 0.00E+00 0.00E+00 N/A N/A I Manganese-54 Ci 0.00E400 0.00E+00 N/A N/A  !

1 Iodine-131 Ci '

O.00E+00 0.00E+00 N/A N/A '

1 Iodine-132 Ci " 0.00E+00 '

l 0.00E+00 ?

i N/A N/A s

Iudine-133 Ci 0.00E+00 '

O.00E+00 N/A N/A Cerium-141 '

Ci '

O.00E+00 0.00E+00 N/A N/A o

Ceriun-144 Ci 0.00E+00 0.00E+00 ' N/A N/A

]

Cobalt-58 Ci 0.00E+0 L, 0.00E+00 '

N/A N/A l

Silver-110m Ci  !, 0.00E+00 O.00E-00 N/h

- _ N/A i ,

Mol.ybdenun- 99 Ci l 0.00E+00 0.00E+00 U/A N/A l l I ,

unidentificd "

Ci l N/A N/A N/A '

N/A '

i l  ! l l l Total for period Ci  ! 7.02E-07 (1) N/A i N/A j (

i t

i  !

, I I

1

Continuous Modo Batch Modo i i i I Nuclides Released  ! Unit '

Quarter 1 l Quarter 2 l Onrter 1 ! Quarter 2 '

4.0 Trititan l I l Ilydrogen-3 l Ci 6.48E-02 4.63E-02 N/A N/A f

(1) Not available for submission at this timo, supplcarental report to follow.

I'ucl Building Exhaust Vent and Radw2ste Buildirty Dduust Vent are considered ground level release points.

i d

i

't I

l l

1 1 1

I l

l

, ' DELE 6 Effluent ard Waste Dispceal Semi-Anraani Report 1988 Year Liquid Effluents - Susanation of All Ral-l l Est. l Unit Quarter Quarter Etal '

1 2 Error, t  ;

i A. Fission and activation products p I  ! i i ,

i l 1. 2 tal release (not in- Ci  ! 6.69E-02 ' 1.02E-01 1.42E+01 i

cluding tritium, gases, ,

alpha ' '

1 i J i i i

2. Average diluted concen- uCi/ml 1.08E-07 3.38E-07  !

tration during period j

l. , ,

t i '

! 3. Percent oi applicable  !  % i 5.35E+00 8.13E+00 l l limit (1) l l l l B. Tritium i 4

I l 1 I l  !

! 1. %tal reloase Ci 1.47E+00 l 1.16E+00 l 1.42E+01  !

I l 1

(

l l 2. Average diluted concen- l uC1/ml 2.37E-06 "l 3.87E-06 l '

tration during period l [

I t i 3. Percent of applicable  !  % ' 7.91E-02 ,' 1.29E-01 l

  • i  ! limit (2) { i l 1

! C. Dissolved and entrained gases  ;

2 _

4 i

' Ci i I ,

I (

j 1. M M release l

3.43E-03 ' 6.77E-04 ' 1.42E+01 l j

! i t 3 ,' ,

l i

i j 2. Averagedilutedconcen-luCi/ml  ! 5.53E-09 ! 2.2SE-09 'g '

l tration durim period ,

l  !

] 3. Percent of applicable  %

limit (3) 2.76E-03l1.13E-03l

, , j

I l

l I

1 1 1 1

1

)

Est. l

, l Unit Quarter Quarter '1btal l 1 2 Error, %

D. Gross alpha radioactivity l l l Ci

1. 2tal release O.00E+]0 0.00E+00 1.42E+01 a E. Volume of wasta released liters 7.65E+06 3.56E+06 8.73E-01 (prior to dilution)

F. Volure of diletion water liters 6.13E+08 2.97E+08 5.70E-01 i used during puiod l (1) Om quarter of 5 Ci annual limit (1.25 C1) for liquid releases except for tritium an! dissolved or entrained noble gases frcn 10CFR50 Appendix I.

(2) 10C m20, Appendix B, Table II, Column 2 MPC limit of 3.00E-03 uCi/ml.

t (3) Technical FFocification 3.11.1.1 limit of 2.0E-04 uCi/ml for dissolved or

! entrained noble gases in liquid effluents.

l l

I l

l l

. ., t l

Effluent and Maste Disposal Sani-Anriual Report 1988 Year G. YA= M Eff)unnts 1/2 Quarters I i

Continuous fede Batch Mode l 1 ,

i-  !

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 )

(

l l ifydrogen-3 Ci N/A N/A 1.47E+00 ' 1.16E+00 '

1 l Arsenic-76 Ci ' N/A N/A 1.42E-04 2.26E-04  !

4 Strontium-89 Ci N/A N/A 0.00E+00 (1) i l

a 8

Strontitrn-90 Ci N/A N/A 0.00E+00 (1) '

i ,

1

, Cesiun-134 '

Ci N/A N/A 0.00E+00 0.00E+00 i

.l Cesium-137 Ci N/A N/A 0.00E+00 0.00E+00 ,

Icdine-131 '

Ci '

N/A N/A 0.00E+00 0.00E+00 l I , ,  !

! 1 Iodine-132 Ci N/A N/A ' O.00E+00 0.00E+00 l i j Iodine-133 Ci N/A N/A 0.00E+00 ' O.00E+00  !

j i i I Iodine-134 '

Ci N/A N/A 0.00E+00 0.00E+00 ? i

! t 8

1 Iodine-135 Ci ' N/A 0.00E+00 0.00E+00 g N/A t l

l Sodiun-24 Ci '

N/A N/A 0.00E+00 0.00E+00  :

) i

]

Cobalt-58 Ci N/A  ! 1/A 2.13E-03 5.40E-04 , j n

l Cobalt-60 '

Ci ( N/A N/A 1.63E-02 2.37E-03 i

i i e i l l Iron 55 Ci N/A N/A 1.30E-02 J1) j 9

I ,

e l l l Iron-59 Ci N/A N/A 8.40E-04 0.00E+00 l l  !

[

i I Zine-65 Ci i

l N/A 1.25E-03 ll 3.27E-04 N/A i

] l l t i

a i ,

i -

Fangancse-54 Ci ' N/A 7.74E-03 l 9.26E-04 N/A l l ~

l u I I Panganese-56 Ci N/A N/A -

0.00E+00 1 0.00E+00 -

1 i i  !

j l Otratiun-51 Ci N/A N/A 3.76E-02 9.69E-02 ,

j l ,l ,

l

' Zirconitm-Niobitm-95' Ci

N/A N/A 0.00E+00 ! 0.00E+0,0 l ,

i e i I I i Molytdentm-99 Ci l N/A N/A ' 1.04E-04 j1.06E-04

, l }

! I i i

] Techniciutr-99m Ci j N/A  ! N/A 1.25E-01 1.34E-04 l Ccw er - 64 Ci N/A N/A l0.00E+00 1 0.00E+00

, l 1 I i  ! i

! l Tin - 113 '

Ci i N/A I. N/A 1 0.00E+00 1 0.00E+00 l I

t 4  :

l I

l -

l Continuous tbde Batch Mode I

i Nuclides Scleased Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 l l l l

Baritm-lanthanum-140 Ci N/A N/A 0.00E+00 0.00E+00 l

l Cerium-141 Ci N/A N/A 0.00E+00 0.00E+00 Cerium-144 Ci N/A N/A 0.00E+00 0.00E+00 Ci Antirony-122 N/A N/A 1.56E-05 0.00E+00 l

Antirony-124 Ci N/A N/A 1.26E-04 0.00E+00 Rhodium - 105 Ci N/A N/A 0.00E+00 0.00E+00 l

Brmine - 82 Ci '

N/A N/A " 0.00E+00 0.00E400 l 1

l' Neptunium - 239 Ci N/A N/A 0.00E+00 0.00E+00 Niobium - 97 Ci N/A N/A 4.65E-04 1.05E-04 '

Ci l l '1btal for period N/A N/ A l, 1.55E400 l 1.26E+00 l

l l

11 . Dissolvtri and Entrained c.m l

l Continuous 1bde Batch Fbde l l l l l ,

j l Nuclides Released  ! Unit Quarter 1 Cuarter 2 Quarter 1 Quarter 2 '

i i Argon 41 I Ci N/A N/A 0.00E+00 0.00E+00 l l Krypton-85m Ci N/A N/A 0.00E+00 0. 00E+00 l Krypton-85 Ci N/A N/A 0.00E+00 0.00E+00 Krypton-87 Ci N/A N/A 0.00E+00 0.00E+00 l

\ ,,

l.

l Krypton-88 Ci  ! N/A N/A 0.00E+00 0.00E+00 l l l l l Xemn-133m l Ci

N/A l N/A 0.00E+00 l 0.00E+00 ,.

Xenon-133 Ci N/A N/A i 1.57E-03 3.57E-04 l Xenon-135m '

Ci , N/A N/A 0.00E+00 0.00E+00 l A g l Xenor-135 Ci '

N/A N/A 1.86E-03 3.20E-04 i . ,

l l Xenon-137 Ci '

N/A  ! N/A 0.00E+00 0.00E+00 'l l l ,

l l Xenon-138 '

Ci  ; N/A '

N/A 0.00E+00 0.00E+00

! u I , ,,

l unidentified '

Ci l N/A '

N/A N/A j N/A ,

! i e i  !

l 'Ibtal for period '

Ci N/A L N/A 3.43E-03 ! 6.77E-04 l (1) Not available at this tire, supplmental report to follow.

.~

a, .*,

'matz 7 Effluent and Maste Dirposal Marinual Reprt 1988 Year Solid hate and Irradiated Maal 9tipnanta Repo % Perioi 01/01/88 to 06/01/88 Otr 1/2 A. Solid Wasta Shipped for Durial or Disposal (Not irradiated fuel) i 6-month ,, Waste i Est. 2btal

1. Type of wasto Unit _ Period Class Error, %

3

a. Spent resins, filter sludges m 7.00E+01 l A-U l cyt.porator bottms, etc. '

l Ci 1.16E+02 A-S 2.24E+01 1

b. Dry capressible waste, m3 2.09E+01 l N/A ' 2.87E+01 contxtinated equip, etc. Ci 4.43E-01 !
c. Irradiated cmponents, m3 0.00E+00 N/A 0.00E+00 control rods, etc. Ci 0.00E+00 '

) , I

d. Other (None) '

m3 l 0.00E+00l N/A l

Ci u 0.00E+00 l O.00E+00 ,l

?

a, , a, 2.

TYPE OF Spent Ecsins, filter i Dry cn:pressible l Irradiated CaTonents Other W16TE sludges, evaporator ' waste, contamin3ted control rods, etc. (!bnc) bottans, etc. etralp, etc.

, Principic H-3 1.31E-02 C-14 1.01E-01 N/A , N/A l l LRadiccuclides C-14 2.97E-01 l' Cr-51 7.09E-03 ' l l(Identify and Na-24 0.00E+00 Mn-54 9.98E+00

% Abundanec) Cr-51 3.63E+00 l Fe-55 5.92E+01 I

Mn-54 2.55E+01 Co-58 9.64E-04 t i

l Co-57 1.66E-02 Fe-59 1.45E-03 1 Co-58 4.52E+00 Co-60 2.78E+01 Fe-59 5.65E-01 Ni-63 3.93E-01 Zn-65 2.51E+00 '

Cc>-60 4.91E+01 Ni-63 1.03E+00 len-241 5.89E-02

]

t Cu-64 0.00E+00 l Pu-241 2.17E-04 Zn-65 4.37E+00 As-76 0.00E+00 l, Nb-95 5.15E-02 l' 1

e j Zr-95 0.00E+00 l j Mo-99 0. 00E+00 l Ag-110m 4.72E-02 Sn-113 1.23E-02 l

, Sb-122 0.00E+00 , s

? Sb-124 1.35E-01 '

I-131 0.00E+00  !

I-133 0.00E+00

'Ib-131m 0.00E+00 '

1

To-132 0.00E+00 Ba-140 0.00E+00 f Ia-140 0.00E+00 l l l Ce-141 0.00E+00 l L Cc-144 0.00E+00 l;

0.00E+00 4

,, W-187 l l

) I ,

14r-239 0.00E+00 l l

! l l Ch-242 1.81E-04 j 4

l Sc-46 0.00E+00 l; j Cm-244 1.44E-04 Am-241 1.48E-04 l n  !

, l Fe-55 1.07E+01 , l l

' j 1 Pu-241 8.83E-03 ll l 3.24E-04 Pu-238 ,

! l l Pu-239 2.38E-04 i j g '

0.00E+00

) l l TRU , l 1

l J

l i

l TYPE OF Spent Resins, filter l Dry cmpressible i Irradiated Caponental Other l' WMrrE sludges, evaporator waste, contaminated control rods, etc. (None)l bottms, etc. equip, etc. i

.. [

Abwe Determined 1 I i by:  !

A. naasurement B. estimation C C N/A , N/A C. measurement and correlation _

i TYPE OF Strong, Tight Liners Stroni, Tight Drun N/A N/A  !

NN i t

i SOLIDIFICATICN i N/A N/A N/A .  !

Cartent i

AGENT OR ABSORBANT l r

I

3. SCLID W6TE DISPOSITICN  ;

Nurber of Shipnents Mxle of Transportation Destinatico f 13 Truck, Exclusivo Use 04SI, Barnwell,  !

South Carolina  !

P i

B. IRRADINITD FUEL SilIIMNIS (Dispositico)  !

Nwber of Shinnents Mode of Transportation Destination  !

O N/A N/A i f

I h

L f

l I

I I

i i

i t

q

-2s-1

( A GU5P STATES UT1LETIE6 COMPANY

.m ..w swo est m u na m e u u.c s a m su.um, i w eer u en w na un August 31, 1988 RBG- 28747

-File Nos. G9.5. C9.25.1.5 U.S. Nuclear Regulatory Comunission Document Control Desk Washington. D.C. 20555 Gentlemen:

River Bend Station - Unit 1 Docket No. 50-458 Enclosed is_ the Semiannual Radioactive Effluent Release Report for the period of January 1 to, June 30, 1988. This report is subuitted in accordance with Technical Specification 6.9.1.8 of Appendix A to River Bend Station'(RBS) License Number NPF-47.

Information unavailable for this report will be provided in a future addendum.

Sincerely,

. f.

J.,E. Booker f J

, Manager-River Bend Oversight River Bend Nuclear Group JF.!!/LAE/ ch yo cc: U.S. Nuclear Regulatory Commeission 611 Ryan Plaza Drive. Suite 1000 Arlington, TX 76011 .

Senior Resident Inspector '

P.O. Box 1051 St. Francisv111e, LA 70775

_

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