RBG-33465, Semiannual Radioactive Effluent Release Rept Jan-June 1990
| ML20059D057 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 06/30/1990 |
| From: | Cargill E, Fantacci C, Odell W GULF STATES UTILITIES CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RBG-33465, NUDOCS 9009060068 | |
| Download: ML20059D057 (33) | |
Text
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GULF STATES UTILITIES COMPANY RivlR 9tND ST ATION POST 08 FIC4 DOM 120 $1 FRANCt$VILLE. LOutbiANA 70716 AHi A COM 604 635 M94 346 0661 August 29 , 1990 RBG- 33465 File Nos. G9.5, G9.25.1.5
- U. S. Nuclear Regulatory Cminission i Document Control Desk Washington, D. C. 20555 Gentiment l 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, 1990. 'Ihis report is sultnitted in accordance with Technical Specification 6.9.1.8 of Appendix A to River Bend Station (RBS) License Number NPF-47.
Infonnation unavailable for this report will be provided in a future addendum.
Sincerely, p W. H. Odell v Manager-Oversight River Bend Nuclear Group Enclosure cc U. S. Nuclear Regulatory Counission (w/o ODCM Encl.)
611 Ryan Plaza Drive,' Suite 1000 Arlington, TX 76011 NRC Resident Inspector (w/o ODCM Encl.)
Post Office Box 1051 St. Francisville, LA 70775 k 0000 59
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RIVER BEND STATION, UNIT 1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT REPORT PERIOD: January 1, 1990 Through June 30, 1990
\ e REVIEWED BY N ~6T h C. WTantbTcTT hadiological Engineering supervisor APPROVED BY '14 E. M. Carg 17D1 ctor - RadlMogicaDrograms 1
1
e M B[ 2 ( F 0 3 m !B m i i PAGE I. INITODUCTION 1
II. SUPPLD4 ENTAL INFORMATIW 2 A. REGUIAERY LIMITS 2 B. MAXIMUM PERMISSIBLE CWCENTRATIONS 6 i C. AVERAGE DERGY 6
D. MEASURDENTS AIO APPROXIMATIONS OF i
WTAL RADIOPCTIVITY 6 E. BNIUI RELEASES F. 8 ABNORMP1 RELEASES G. 9 ESTIMATE OF WTAL ERROR 12 '
III. ,
GASB00S EFFLUENTS SUM 4ARY INIORMATION 13 IV. LIQUID EFFLUENTS SUM 4ARY INEVRMATION 13-V. SOLID WASTE 13 VI. RADIOIDGICAL IMPACT ON MAN 13 VII. METEORO10GICAL DATA 13 VIII.
RADIOACTIVE LIQUID EFFLUENT 10NITORING INSTRUMENTATICN OPERABILITY 13 IX.
RADIOACTIVE GASEOUS EFFLUENT ITNITORING INSTRUMENTATION OPERABILITY 14 X. LIQUID HOID UP TANFS 14 XI.
Rt.JIOIDGICAL ENVIRONMENTAL KNI'IORING 14 XII. LAND USE CENSUS 14 i
XIII.
OFFSITE DOSE CAICUIATICN MANUAL (CDCM) 14 XIV. MMOR CHANGES E RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREMNENT SYSTEMS , 14 XV.
PROCESS CCNTROL PROGRAM (PCP) 14 m
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t PAGE:
XVI. TABLES TABLE 1 PADIMCTIVE GASECUS WASTE SAMPLING AND ANALYSIS PEGRAM 15 TABLE 2 RADIOACTIVE LIQUID WAS7E SAMPLING AtO ANALYSIS PROGRAM 16 TABLE 3 GASEQUS EITWENTS - SUl4% TION W ALL RELEASES 17 TABLE 4 GASBOUS EITWENTS - CCNDITIONALLY ELEVATED RELEASES 19 TABLE 5 GASEQUS EETwnfrS - GROUND LEVEL RELEASES 22 TABLE 6 LIQUID EETLUDfrS - SUtHATION T ALL RELEASES 25 TABLE 7 SOLID WASTE AND IRRADIATED IUEL SHIPMENTS 30 Attactment It Offsite Dose Calculation Manual Changes 33
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l SEMIANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT FACILITY: River Bend Station, Unit 1 ,
LICENSEE: Gulf States Utilities REPORT PERIOD: January 1,1990 through June 30, 1990
- 1. INTRODUCTION Enclosed is the Semianridal Radioactive Effluent Release Report for the period of January 1, 1990 through June 30, 1990. This report is submitted in accordance with Technical Specification 6.9.1.8 of -
Appendix A to River Bend Station (RBS) License Number NPF-47. :
- 11.
SUMMARY
Gaseous release totals were a maximum of 7.4% of the quarterly whole body and critical organ technical specification limits. Liquid ;
releases were a maximum of 1.1% of their quarterly whole body and critical organ technical specification limits.
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. i II. SUPPLEMENTAL IhTORMATION A. Regulatory Limits ,
- 1. 10CTR20 Limits
- a. Fission and Activation Gases in dose accordance with Technical Specification 3.11.2.1, the rate due to noble gases released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY ahall be limited to less than or equal to_ 500 =
mrems/yr to the total body and less than or equal to 3000 mrams/yr to the skin: i DR = '
TB Dose rate to the total body in arems/yr '
n .
3.15 x 10 I Kg (X/Q) Q 15 500 mroms/yr i=1 and DR
akin D se rate t the skin in mrems/yr n
=
3.15 x 10 I (L + 1,1g )(X/Q) Q 51 3000 mroms/yr i
i=1 (above terms defined in RBS ODCM).
- b. Radiciodines and Particulates in accordance with Technical Specification 3.11.2.1, the dose rate due to iodine-131, iodine-133, tritium, and all radionuclides than in particulate form with half-lives greater 8 days released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to less than or equal to 1500-mrems/yr to any organ:
DR =
I&8DPt D se rate to the organ t for the age group of interest from iodines, tritium, and 8 day particulates via the inhalation pathway in arems/yr n .
= I P g(FQ)D S i 5 1 00'mrems/yr i=1 (above terms defined in RBS ODCM)
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- c. Liquid Effluents In accordance with Technical Specification 3.11.1.1, the concentration of radioactive material released in liquid effluents to Uh* RESTRICTED 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 be 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 SI'II BOUNDARY shall be limited tot Dg =
,,,,,gg, The gamma air dose from radioactive noble gases in mrad n
I Mg (X/Q) Q g 5 5 mrads/qtr 1,1 $ 10 mrads/yr D
Beta-Air Beta air dose from radioactive noble gases in mrad n
= I Ng (X/Q) Qg 5 10 mrads/qtr l
i=1 $ 20 mrads/yr !
(above terms defined in RBS ODCM) b.
Radiciodines and Particulates In accordance dose to with Technical Specification 3.11.2.3, the a MEMBER OF THE PUBLIC from iodine-131, iodine-133, and all radionuclides in particulate form j with half-lives greater than 8 days, in gaseous effluents releases to areas at and beyond the SITE BOUNDARY shall be limited tot D =
I&8DPt Dose in mrem to the organ (t) of a specified age group from radiciodines, tritium, and 8 day particulates via the
_ pathway of interest i
I 3
i n J
=
3.17 x 10'8 I R, g (X/Q)n Q g i=1 and/or '
l n
=
3.17 x 10'O I Rg (D/Q) Q g i=1 i
and e
D, Dose in area to the organ (t) of a specified age group from radioiodines, tritium, and 8 day particulates from all pathways n
= 1 D I&8DPt 3 7.5 mroms/qtr z=1 515 aress/yr (above terms defined RBS ODCM)
- c. Lieufd 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, g
= AftAt O f (DF) D, n '
TOTALt
1 D it i=1 D
TOTALt Total dose commitment to the organ (t) due to !
all releases during the desired time interval in mrom r 1
9 4
l and D i
TOTAL $ 1.5 mrems/qtr Total Body ,
5 3 mrems/yr i
D TOTAL $ $ mrems/qtr Any Organ '
3 10 mrems/yr '
(above terms defined in RBS ODCM)
- 3. 40CFR190 Limits In accordance with Technical Specification 3.11.4, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to:
$ 25 mrems to the total body or any organ (except the .
thyroid)
$ 75 mrems to the thyroid
- 4. Miscellaneous Limits
- a. Ventilation Exhaust Treatment System In accordance with Technical Specification 3.11.2.5, the l VENTILATION EXHAUST TREt'rMENT SYSTEM shall be used to 1 reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a period, 31 day
- b. Liquid Radwaste Treatment System In accordance with Technical Specification 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses, due to -the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrom to the total body or 0.2 mrem to period. any organ in a 31 day
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B. Maximum Permissible Concentrations
- 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) listed 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 11, Column 2. The MPC chosen is the most .
conservative value (i.e., the lowest) of either the soluble '
or insoluble MPC for each radionuclide.
C. Average Energy Not applicable to RBS RETS D. Measurements and Approximations of Total Radioactivity
- 1. Gaseous Effluents l
- a. Fission and Activation Gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building Exhaust Vent and Radwaste l Building Exhaust Vent. These samples are analyzed t
utilizing high resolution germanium detectors coupled to computerized pulse height analyzers. The sampling 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. If no activity was detected between stack grab samples and significant i 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. On April 24, 1990, the Offgas Pretreat Radiation Monitor reading increased from approximately 70 uCi/sec. to 442 uCi/sec. It was
- determined by control rod manipulations that a pin-hole.
leak had occurred. Correction factors for the monitors .
are derived and applied for each sampling period whenever noble gas radionuclides are detected in the effluent stream.
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- b. Particulates and Iodines Particulates and iodines are continuously sampled from each of the three tr2 ease points utilizing a particulate filter (stack and charcoal cartridge in line with a sample pump (
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 detectors coupled to computerized specific pulse height analyzers. Given the nuclide activity concentrations, process flow rate, and time which the sample covered; the nuclide specific activity released to the environment can be obtained.
Due to.the continuous sampling process, it is assumed that the radioactive material is released to the environment period. Sr-89 at a constant rate within the sampling . ,
and Sr-90 are quantitatively analysed by '
counting the digested filter precipitate with a gas flow proportional counter. Gross alpha analysis is performed using a zine sulfide scintillation counter,
- c. Tritium Tritium grab samples are obtained from the three release points at the specified frequencies listed in Table 1 utilizing The an ice bath condensation collection method.
i collected sample is thou analyzed utilizing a Liquid ,
Scintillation Counter.
l process Given the tritium concentration.
i flow rate, and
.is obtained, the tritium activity time period for which the sample released to the environment can be determined. Due to the frequency of i sampling, it is assumed that the tritium is released to the environment at a constant rate within the time period for which the sample is obtained.
- 2. Liquid Effluents Representative grab samples are obtained from the 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 (including dissolved and entrained noble gases) is performed utilizing a high resolution height germanium detector coupled to a computerized pulse analyzer. Triti~m concentration is determined t
utilizing a Liquid Scintillation Counter. Sr-89 and Sr-90 l aregas a quantitatively analyzed by counting the precipitate with l flow proportional counter. Fe-55 is counted with a
- L' quid Scintillation Counter after digestion of the iron.
Gross alpha analysis is performed using a zinc sulfide scintillation counter.
Given the nuclide specific activity concentration and total volume of the tank that was released, the activity of each nuclide released to the environment can be determined.
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E. Batch Releases
- 1. Liquid 1st Quarter 1990
- a. Number of batch releases : 51
- b. Total time period for batch releases : 373.3 hr
- c. Maximum time _ period for batch releases : 8.33 hr
- d. Average time period for batch releases : - 7.38 hr
- e. Minimum time period for a batch release : 5.08 hr-
- f. Average stream flow during periods of, release of effluent.into a flowing stream : 768' 000 L f t 3/sec .
2nd 0uarter 1990-
- a. Bumber of batch releases : 64 j
- b. Total time period for-batch releases : 473.00 hr
- c. Maximum time period for batch releases. ': 9.72 hr
- d. Average time period for_ batch releases : -7.39 hr
- e. Minimum time period for a batch release' : 0.35 hr
- f. Average stream' flow during periods of release of effluent into a flowing stream : 938,000 ft 3/sec-
- 2. Gaseous All gaseous releases to River Bend Station are considered continuous releases.
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e F. Abnonnal' Releases .
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- 1. Liquid ,
1st Quarter 1990 ,
- a. Number of releases : 1
- b. Total ac".vity released : 4.76x10'0 Curies ,
t 2nd Quarter 1990 ,
.a. Number of releases .
- 0.
- b. Total activity released' : 0' Curies [
2., Gaseous ,
let Quarter 1990 ,
- a. Ntznber of releases .
- 0- .
- b. ' Total activity released : O curies" j i
2nd Quarter 1990. ;
- a. Ntznber of releases . O.
B.- Total activity released : O curies: ;
f During the reporting l period 1-Jan-90 thru -304 un-90. RBS experienced one abnonnal liquid release. On 4/6/90 environmental ,
analysis- of the Sewage Treatnent Effluent L Canposite . sanple irdicated the presence of Cobalt-60 at an' average concentration. +
of 8.17 pCi/1. 'Ihe sanple .was a ccatposite- for the period of 3/25/90 thru 3/31/90. It- is estimated that. 4.76E-06 .Ci was. ,
. released via this pathway. -Inmediate sanples of the effluent on 4/6/90.and snbsequent grab. sanples and ccanposite ~ .sanples : showed no detectabic activity. through ~ the runainde,r of the reporting i period. _ Rosicw of the operating logs-'and systom. flows. plun discussion with the~ plant operators could not determine the root '
cause for this event.
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Estimate of Total Error
- 1. Liquid The maximun error associated with sample collection, laboratory estimated to be:unslysis, and discharge volume are collectively Fission and Activation Prod'sta. t i 14.2%
Trit. 8 days 7.111-01 (2) 1.86E+01
- 2. Average release rate uCi/sec for period __
9.02E-06 (2) 1 .
l l
- 3. Percent of technical I % l l I specification limit ! 4.61E-03 (2)
. i l l 4. Gross alpha Ci l l
l radioactivity ___' ___
l 0.00E+00 0.00E+00 15
9
.I Est.
Unit Quarter- ' Quarter ~ Total e 1 2 Error, %
D. Tritium
- 1. Total release Ci '8.39E+00 4.67E+00 '1.82E+01 F
- l
- 2. Average release rate = uCi/sec 1.06E+00 5.93E-01 ,
for period __
- 3. Percent of-technical % 3.89E 3.05E-02 specification limit l
(1) Gamma airdose limit of 5 mradi/qtr (T.S.3.11.2.2.a).
I (2) Not available for submission at this time, supplemental report to follow.
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-TABLE 4 Effluent and Waste Disposal Semi-Annual Report 1990 Year Gaseous Effluents - Conditionally Elevated Releases ~ 1/2 Quarters-Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 ;
- 1. Fission Gases l L
Argon-41 Ci- 0.00E+00 0.00E+00 N/A N/A i
Krypton-85m Ci 0.00E+00 2.60E+00 N/A N/A Krypton-85 Ci 0.00E+00 0.00E+00- N/A N/A 1 Krypton-87 Ci 0.00E+00 3.57E+00 N/A N/A Krypton-88 Ci 0.00E+00 0.00E+00 N/A N/A Xenon-133m Ci 0.00E+00 0.00E+00 N/A N/A ,
Xenon-133 Ci 0.00E+00 9.26E+00 N/A N/A i Xenon-135m Ci 0.00E+00 0.00E+00 N/A N/A Xenon-135 Ci 0.00E+00 1.77E+01 -N/A N/A !
Xenon-137 Ci 0.00E+00 0.00E+00 N/A N/A l;
Xenon-138 Ci 0.00E+00 0.00E+00 N/A N/A unidentified Ci N/A N/A N/A N/A 4
Total for period Ci 0.00E+00 '3.31E+01 N/A N/A
- 2. Gaseous Iodines Iodine-131 C1 1.10E-04 2.41E-02 N/A N/A ,
Iodine-132 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-133 C1 1.54E-03 7.93E-02 N/A N/A Iodine-134 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-135 Ci 0.00E+00 0.00E+00 N/A N/A -i Total Ci 1.65E-03 '1.03E-01 N/A N/A 17 I
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Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2
- 3. Particulates <
Strontium-89 Ci- 4.57E-06 (1) N/A N/A Strontium-90 Ci 0.00E+00 (1) N/A N/A Cesium-134 Ci 0.00E+00 0.00E+00 N/A N/A Cesium-137 Ci 0.00E+00 0.00E+00 N/A N/A Barium-140 Ci 0.00E+00 1.06E-04 N/A N/A Lanthanum-140 Ci 0.00E+00 0.00E+00 N/A N/A Cobalt-60 Ci 1.85E-05 0.00E+00 N/A N/A Chromium-51 Ci 1.64E-05 0.00E+00 N/A N/A Zirconium-95 Ci 0.00E+00 0.00E+00 N/A N/A Niobium-95 Ci 0.00E+00 0.00E+00 N/A N/A Zinc-65 Ci 0.00E+00 0.00E+00 N/A N/A Iron-59 Ci 0.00E+00 0.00E+00 N/A N/A Manganese-54 Ci 9.01E-06 0.00E+00 N/A N/A Iodine-131 Ci O.00E+00 0.00E+00 N/A N/A Cerium-141 Ci 0.00E+00 8.80E-06 N/A N/A Cerium-144 Ci 0.00E+00 0.00E+00 N/A N/A' Cobalt-58 Ci 2.26E-05 6.73E-06 N/A N/A Silver-110m Ci 0.00E+00 0.00E+00 N/A N/A Molybdenum-99 Cl 0.00E+00 0.00E+00 N/A N/A unidentified Ci N/A N/A N/A N/A Total for period Ci 7.11E-05 (1) N/A N/A 18
t
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' Continuous' Mode - Batch Mode !
Nuclides Released Unit Quarter l'- Quarter 2 Quarter 1 Quarter 2 -
4.0 Tritium l
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Hydrogen-3 -Ci 8.27E+00- -4.35E+00 N/A N/A Main Plant Exhaust Duct is conside' red a. conditionally elevated rele'ase. point.
(1) Not available for submission at this time, supplemental report ^ to follow.
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TABLE 5- t Effluent and Waste Disposal Semi-Annual Report 1990 Year 3 Gaseous Effluents - Ground Level Releases _1/2 Quarters Continuous Mode- Batch Mode t Nuclides Released Unit, Quarter 1 Quarter 2 Qearter 1 Quarter 2
- 1. Fission Gases ,
(
Argon :Ci 0.00E+00 0.00E+00 N/A N/A Krypton-85m Ci 0.00E+00 0.00E+00 N/A N/A Krypton-85 Ci 0.00E+00 0.00E+00 N/A N/A Krypton-87 Ci 0.00E+00 0.00E+00 N/A N/A-Krypton-88 C1- 0.00E+00 0.00E+00 N/A N/A ,
Xenon-133m Ci 0.00E+00 0.00E+00 N/A N/A-Xenon-133 -Ci 0.00E+00 1.67E+01 N/A- N/A Xenon-135m Ci '0.00E+00 0.00E+00 N/A N/A !
Xenon-135 Ci 0.00E+00 5.66E+00 N/A N/A r
Xenon-137 Ci 0.00E+00- 0.00E+00 N/A N/A Xenon-138 Ci 0.00E+00 0.00E+00 N/A N/A unidentified Ci N/A N/A N/A N/A Total for period Ci 0.00E+00 2.24E+01 N/A -N/A 1
L 2. Gaseous Iodines Iodine-131 Ci 0.00E+00 1.41E -N/A N/A-Iodine-132 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-133 Ci 0.00E+00 2.86E-04 N/A N/A Iodine-134 Ci 0.00E+00 0.00E+00 N/A N/A i Iodine-135 Ci 0.00E+00 0.00E+00 N/A N/A i Total Ci 0.00E+00 4.27E-04 N/A N/A 20
. u, o f
Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2
- 3. farticulates Strontium-89 Ci 0.00E+00 '(1) N/A N/A i
Strontium-90 .Ci 0.00E+00 -(1) N/A N/A Cesium-134 Cl 0.00E+00 0.00E+00 N/A N/A Cesium-137 Ci 0.00E+00 0.00E+00 N/A N/A Barium-140 Ci 0.00E+00 0.00E+00 N/A N/A Lanthanum-140 Ci 0.00E+00 0.00E+00 N/A N/A Cobalt-60 Ci 0.00E+00 0.00E+00 N/A N/A i
Chromium-51 Ci 0.00E+00 0.00E+00 N/A N/A Zirconium-95 Ci 0.00E+00 0.00E+00 N/A N/A Niobium-95 Ci 0.00E+00 0.00E+00 N/A N/A Zinc-65 Ci 0.00E+00 0.00E+00 N/A N/A Iron-59 Ci 0.00E+00 '0.00E+00 N/A N/A Manganese-54 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-131 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-132 Ci 0.00E+00 0.00E+00 N/A N/A Iodine-133 Ci 0.00E+00 0.00E+00 N/A N/A Cerium-141 Ci 0.00E+00 0.00E+00 N/A N/A Cerium-144 Ci 0.00E+00 0.00E+00 N/A N/A Cobalt-58 Ci 0.00E+00 0.00E+00 N/A N/A Silver-110m Ci 0.00E+00 0.00E-00 N/A N/A Molybdenum-99 Ci 0.00E+00 0.00E+00 N/A N/A l unidentified Ci N/A N/A N/A N/A l Total for period Ci 0.00E+00 (1) N/A N/A-l 21
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Continuous Mode - ; Batch Mode- '
Nuclides Released Unit- Quarter 1 Quarter 2- Quarter 1- Quarter 2- q
. 4.0 . Tritium .
. . . . l Hydrogen-3 Ci 1.24E-01 3.20E-01 N/A N/A' -[
i
-Fuel Building Exhaust Vent and Radwaste Building Exhaust' Vent are considered- I ground level release points.; 7 t
(1) Not. available for submission at this time, supplemental report 'to follow.' ',
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4 TABLE 6 Effluent and Waste Disposal Semi-Annual Report: -1990 Year Liquid Effluents - Summation of All Releases 1/2 Quarters
~
Est. !
Unit Quarter Quarter Total.
=1 2 Error, %
A. Fission and activation products .j
'1
- 1. Total release (not in-- Ci 1.11E-01 (4) 1.42E+01 cluding tritium, gases, alpha
- 2. Average diluted concen- uC1/ml- 9.77E-08. -(4) tration during period
- 3. Percent of applicable % 8.88E+00 .(4) limit (1) i B. Tritium
- 1. Total release Ci 4.31E+00 1.84E+01 l'.42E+01
- 2. Average diluted concen- .uti/ml 3.79E-06 1.22E-05 tration during period
- 3. Percent of applicable. % 1.27E-01' 4.06E-01 limit (2)
C. Dissolved and entrained gases h
- 1. Total release Ci 6.14E-04 5.80E-02 1.42E+01 3
- 2. Average diluted concen- uCi/ml 5.40E-10 3.84E-08 .
tration during period -
i
- 3. Percent of applicable % 2.70E-04 1.92E-02 limit (3) i 23
V, ,
, 1 a
~
6 %- :,
\ t .
Unit j, Quarter 'I Quarter ' : 'Ibtal ,
! 1 2- Error,.%'
D.; Gross alpha radioactivity i
.m_ _m
'1. 'Ibtal release. / Ci =. .0.00E+00 0.00E+00 1. 42E+01- -
= . . .
}
E. .: Volume of wasto released .l ' liters lf2.93E+06..l .3.65E+06 ,8.73E-01 I t
-(prior to; dilution) j
. F. Volume of dilution water liters ;1.14E+09 l'.51E+09 - 5.70E-011 used during period: l :
'(1)~ One quarter of -5 Ci annual limit (1.25 C1) for 11guld releases except- for -
tritium and dissolved or entrained noble gases frca 10CFR50 Appendix ~I.
-(2) . 10CFR20,~ Appendix B, Table II, Column _2 MPC limit'of 3.00E-03 uCi/ml.<
(3) . Technical Specification;3.11.1.1 limit of 2.0E-04 uCi/ml-for' dissolved or. I entrained noble gases in liquid effluents.. J (4) ' Not~ available at this time, supplemental report;to follow.,
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Effluent and Waste Disposal Semi-Annual Report 1990 Y;ar G. Liquid Effluents 1/2 Quarters
-- _. Continuous Mode Batch Mode
,..-= , , , ,
i i i i i Nuclides Released Unit Quarter 1 ' Quarter 2 Quarter 1 Quarter 2 l l
Hydrogen-3 N/A N/_A___j4.31E+00 1.84E+01 l i
4_ Ci i i i i j Arsenic-76 pC_i_ _ j___ N/A N/A- l 1.27E-04 7.38E+04 l
! Strontium-89 C_1 N/A N/A O.00E+00 (1) l .
i Strontium-90 0.00E+00 (1) l Ci _N/A N/A l l l l l Yttrium-92 C l N/A N,' A 0.00E+00 l 8.21E-04 j l
\
_.l_.-.i i
g i
i i Cesium-134 ,_
Ci N/A N/A 0.00E+00 ! 0.00E+00 l i i i i l- Cesium-137 l _Ci N/A N/A l 0.00E+00 0.00E+00 l l I . , I Iodine-131 ], _ Ci N/A N/A 0.00E+00 1.87E-03 li li i
l lodine-132 Ci N/ L N/A l 0.00E+00 0.00E+00 l l l lodine-133 ,y__Ci N/A N/A ' O.00E+00 3.26E-04 l ;
I i !
lodine-134 N/A N/A 0.00E+00 0.00E+00 l li {_ Ci \ i l lodine-135 Ci N/A
, N/A l 0.00E+00 1 0.00E+00 l l i ! ! ! l Sodium _ p__Ci N/A N/A 0.00E+00 7.83E-06 li i \ \
Cobalt-57 Ci _ fi/ L N/A 0.00E+00 6.38E-06 i j Cobalt-58 l Ci l N/A l N/A 9.76E-03 7.07E-03 l l 1 l r ,
l Cobalt-60 _q'-_-Ci l N/A l N/A 2.87E-02 '
, 3.01E-02 l i i i i i i l Iron-55 _,[ Ci l N]A l N/A 3.47E-05 (1) l
! , I l ,
Iron-59 N/A N/A 8.05E-03 4.50E-03 j
i
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l i \
l i
l Zinc-65 __ Ci N/A N/A 8.18E -8.02E-04 l l
l Manganese-54 l Ci N/A j N/A. 1.34E-02 1.392-02 l I I l i !
! Manganese-56 Ci l N/A N/A O.00E+00 ' O.00E+00 l l \ l \
l \
Chromium-51 N/A N/A l 4.76E-02 8.09E-02 l
d-i Ci !
i i
l i
i i
l i
i j Zirconium-95 Ci l N/A __ _N/A 6.92E-05 1.69E-04 l i , ,
i l Molybdenum-99 '
l o Ci N/A l N/A l 8.81E-05 i 8.34E-04 j
! ! l_ l l l Technicium-99m Ci N/A N/A 9.85E-05 l 5.45E-04 l Copper - 64 _j _ Ci j_ N/A J__ N/A _J 0.00E+00 l 0.00E+00 l l \ l l l \
i Tin - 113 J Ci ! N/A l N/A i 3.88E-05 l 8.30E-05 l 25
..- 4., .
G.(Cont'd) ,
Continuous Mode Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Lanthanum-140 Ci N/A N/A 1.76E-05 2.68E-03 i Cerium-141 Ci N/A N/A 0.00E+0') 5.43E-05
_ Cerium-144 Ci N/A N/A 3.80E-05 0.00E+00 Antimony-122 Ci N/A N/A 3.53E-04 0.00E+00' ;
Antimony-124 Ci N/A N/A 1.14E-03 8.59E-04 Ruthenium-103 Ci N/A N/A 0.00E+00 5.52E-06 Rhodium - 105 Ci N/A 'N/A 0.00E+00 0.00E+00-Bromine - 82 Ci N/A N/A 0.00E+00 0.00E+00 Neptunium - 239 Ci N/A N/A 0.00E+00 4.18E-04 Niobium - 95 Ci N/A N/A 3.36E-04 3.91E-04 Niobium - 97 Ci N/A N/A 2.89E-04 2.02E-03 Silver - 110m Ci N/A N/A 1.77E-05 4.00E-04 Strontium - 92 Ci N/A N/A 3.23E-06 -1.08E-04 i
Tungsten - 187 Ci N/A N/A 4.23E-05 1.41E-04 Tellurium - 132 Ci N/A N/A 0.00E+00 9.14E-05 Total for period Ci N/A N/A 4.42E+00 (1) l l (1) Not available at this time, supplemental report to follow.
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H. Dissolved and Entrained Gases i
Continuous Mode Batch Mode _
j Nuclides Released Unit Quarter 1 Ouarter 2 Quarter 1 Quarter 2 Argon 41 Ci N/A- N/A 0.00E+00 0.00E+00 Krypton-85m Ci N/A N/A 0.00E+00 0.00E+00 i Krypton-85 C1- N/A N/A 0.00E+00 0.00E+00 ;
Krypton-87 Ci N/A N/A 0.00E+00 0.00E+00 Krypton-88 Ci N/A N/A 0.00E+00 0.00E+00- !
Xenon-131m Ci N/A N/A 0.00E+00 1.45E-04 Xenon-133m Ci N/A N/A- 0.00E+00 1.26E-03 j Xenon-133 Ci N/A N/A- 2.48E-04 2.48E-02 !
Xenon-135m Ci N/A N/A 0.00E+00 0.00E+00 Xenon-135 Ci N/A N/A 3.66E-04 -3.18E-02 Xenon-137 Ci N/A N/A 0.00E+00 0.00E+00 Xenon-138 Ci N/A N/A 0.00E+00 0.00E+00 unidentified Ci N/A N/A- N/A N/A Total for period Ci N/A N/A 6.14E-04 5.80E-02 (1) Not available at this time, supplemental report to follow.
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Effluent and Waste Disposal- Semiannual Heport 1990 Year Solid Waste and Irradiated Puel Shipmts Reporting Period 01/01/89 to 06/30/89' Qtr 1/2 A. Solid Waste Shipped for Durial or Disposal (Not irradiated fuel)
. - . _ - . . _ . ~ - . - - - . .
1., Type of waste _ , Unit Period' Class Error, %
- a. Spent resins, filter sludges m3 L 5.29E+01 A-U. See evaporator bottms, etc. Ci 1.85E+01. Below
- b. Dry cmpressible waste, , m3 1.77E+01 A-U See-contaminated equip, etc. Ci 3.72E+00 Below
- c. Irradiated emponents, '
m 0.00E+00 N/A 0.00E+00 [
control rods, etc. Ci 0.00E+00 , j
- d. Other (None) m '0.00E+00 :N/A l Ci- 0# .J 0.00E+00 i Radwaste Error (%) Estimated Waste type considered are processc4 solid waste (i.e. resin, filter rnedia. ..) and Non-ccupactable/Ccopactable Dry Active Waste.
- 1. Possible Errors
- a. Volume i
- b. Representative Sampling j
- c. Instrument Counting
- d. dose to Curie calculations
- 2. Volume Error Radwaste contractor personnel have stated that leve1 indication can be determined to +-0.5 inches. This correlates to approximately 1.0%. Container i
manufacturer stated design allows 1.0% deviation frca dimensions. .
- 3. Sampling Error . .
Sampling error for process solid waste is based on mixing tank contents to :
produce unifom matrix. Sampling error for Dry Active Waste is based on l obtaining a representative sample frca the material being packaged. This arror is assumed to be 10%, which is consistent with Industry Standards.
4 Instrument Error The error caused by sample gcm etry, counting tine, sample activity ard instrument background is estimted by Chemistry. to be +-20%. The error for survey instninentation is estimat.M by Radiation Protection to be 4-10%.
- 5. Dose to Curie Calculations The Bowman Swindle curves are useo to calculate Dose to Curic activities.
The error caused by package gecmetrf, Isotopic percent abundance and personnel error is assurred to be +-25t which is consistent with Industry '
i Stancards.
- Volune considered total disposal volune of container.
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TYPE OF r Spent h Te 1'n E fT1't E DIY ' M 7ess~61'ti~ l IrraciiMEfECcanponents Other-WASTE sludges, evaporator 1 waste, contaminated --control lods, etc. (None)-
bottcans, etc., _ equip, etc. _ _
Percent - Percent Principle Isotope Abundance Isotopo Abundance .N/A N/A Radionuclides (Identity and Im-241- '
2.56E-04 C-14 - 1.70E+00- l.
% Abundance) C-14 2.03E-01 Co-601 . 6.23E+01 l Cm-242 1.51E-04 Cr - 1.00E+00 J Fe-55 2.18E+01 Cm-244 '-3.09E-04 Co-57: 8.95E-01 Mn 9.00E+00 Co-58 1.43E+01 -Ni 1.30E+00 Co-60 -3.57E+01 Zn-65 . '2.90E+00 Cr-51: 7.94E+00~ l 1
'Fe-55 1.65E+01 -j Fe-59 l'.22E+00- l I I
11- 3 2.34E+00 I-131 9.31E-05.
Mn-54 l 1.78E+01 Mo-99 i 7.09E-08 16-95i l-8.92E-02 Ni-63 l 1.17E-00 l l Pu-238 =l 5.65E-04
-Pu-239 '4.14E-04 l l Pu-241 1. 5')E-02 '
T.b-122 - 1.aoE-08 l l .l Sb-124 2.66E Zn-65 1.45E-00 Zr-95 1.41E 1 Abovo Detenninedl l -l' by: 1 A. neasurc. stent l .
-l B. estimation C , C N/A- N/A l C. measurcstent I
.,and correlation _____ ,_ _
TYPE OF Strong, Tight Liners Strong, Tight Drums' N/A N/A :i cot &AINER -
SOLIDIFICATION .i '
N/A N/A ~N/A .
AGENT OR Cement i
~l ABSORBANT _
l 3. SOLID WAS'1T DISPOSITION Number of Shipnents Mode of Transportation Destinationi 11 Truck Barnwell, S.C.
B. IRRADIATED FUEL SilIPMENTS (Disposition)
Number of Shiptents Mode of Transportation Destination 0 N/A N/A.
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