ML20059D721

Semiannual Radioactive Effluent Release Rept for Jan-June 1990

ML20059D721
Person / Time
Site:	Waterford
Issue date:	06/30/1990
From:	Burski R ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
W3P90-1188, NUDOCS 9009070154
Download: ML20059D721 (27)

Text

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August 24, 1990 U.S. Nuclear Regulatory Commission  :

ATTN: Document Control Desk ~

Washington, _ D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Semiannual Radioactive Effluent Release Report 'l Gentlemen:

Enclosed is the subject report of effluent releases which encompasses the period of January 1 through July 31, 1990. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specifications (NUREG-1117) of Appendix A to Facility Operating License No. NPF-38 and 10CFR50.36a(a)(2), pursuant to 10CFR50.4.

If you have any questions, please contact Mr. L.W. Laughlin at (504) 739-6726. -i Very truly yours, RFB/LWL/ssf i Enclosure cc (w/ Enclosure): Mr. R .'D . Martle., NRC Region IV j NRC Resident Inspectors Office }

cc (w/o Enclosure): Messrs. D.L. Wiggir ton, NRC-NRR E.L. Blake-W.M. Stevenson R.B. McGehee 021La +

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TABLE OF CONTENTS  ;

i 1.0 SCOPE 2.0 SUPPLEMENTAL INIORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Hessurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Unmonitored Releases 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES 6.0 METEOROLOGICAL DATA 7.0 ASSESSMENT OF DOSES 8.0 RELATED INFORMATION l 8.1 Changes to the Process Control Program

{ 8.2 Changes to the Offsite Dose Calculation Manual l

l 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability I 8.5 Activity Released via Secondary Pathways 8.6 Missed Effluent Samples 8.7 Additional Information 9.0 TABLES l

10.0 ATTACHMENTS 1

W350897HP 1

i 1.0 SCOPE This Semiannual Radioactive Effluent Release Report is submitted as required by Waterford 3's Technical Specification 6.9.1.8. It covers the period from January 1,1990 through June 30, 1990. Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21.

The information contained in this report includes:

(1) A summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period;  ;

(2) A discussion regarding radioactive gaseous effluents released from .

identified and monitored secondary release paths during the reporting period; (3) An explanation of why certain instrumentation was not restored to operable status within the time specified in the ACTION statement, as per Waterford 3 Technical Specifications 3.3.3.10 and 3/4.3.3.11; and (4) A summary of missed samples that were required by Waterford 3 Technical Specification 4.11.1.1.1.

The summary of meteorological data and results from the assessment of radioactive doses due to the release of liquid and gaseous radioactive effluents will be included in the Semiannual Radioactive Effluent Rslease Report to be submitted within 60 days after January 1, 1991.

l W350897HP 2 1

2.0 SUPPLEMENTAL INFORMATION 2.1 Regvjatory Limits The Technical Specification Limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.

2.1.1 Fission and Activation Gases (Noble Gases)

The dose rate due to radioactive noble gases released in gaseous ef fluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, j The air dose due to noble gases released in gaseous effluents from the site to areas at or beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and.less than or equal to 10 mrad for beta radiation and, '

b. During any calendar years Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

2.1.2 Iodines; Particulates, Half Lives > 8 Days; and Tritium The dose rate due to Iodine-131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (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 mrem /yr to any organ.

W350897HP 3

6 The dose to a member of the public from Iodine 131 and 133, tritium, and all radionuclides in particulate form with half lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,

b. During any calendar year: Less than or equal to 15 mrem to any organ.

2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.

The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unre-stricted areas shall be limited to the followings

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equel. to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

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1 2.1.4 Uranium Fuel Cycle Sources The dose or dose commitment to any member of the public due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.

2.2 Maximum Permissible Conce'ntrations e

2.2.1 Fission and Activation Gases; lodines; and Particulates, Half Lives > 8 Days For gaseous effluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable limits are expressed in terms of dose race at the site boundary.

2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified in 10 CFR Part 20. Appendix B, Table II, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted aren boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents, i

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2.6 Average Energy 1

Average energy is not applicable to Waterford 3's Radiological Effluent Technical Specifications. E-Bars are not required to be calculated from effluent release data, l

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2.4 Measurements and Approximations of Total Radioactivity The quantification of radioactivity in liquid and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Tables 4.11-1 and 4.11-2 of the Waterford 3's Technical Specifications.

2.4.1 Fission and Activation Gases (Noble Gases)

For continuous releases, a gas grab sample was analyzed monthly for noble gases. Each week a Gas Ratio (GR) was calculated according to the following equation:

GR = Average Weekly Noble Gas Monitor Readina Monitor Reading During Noble Gas Sampling

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The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases discharged continuously for the  !

previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the batch.

In all cases the total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclide present and the total volume discharged.

2.4.2 Iodines and Particulates Iodines and particulates discharged were sampled using a continuous sampler which contained a charcoal cartridge and a particulate filter. Each week the charcoal cartridge and particulate filter were analyzed for gamma emittats using gamma spectroscopy. The. determined radionuclide concentrations and effluent volume dischargcd vert . sed to calculate the previous week's activity released.

i W350897KP 6

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1 The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Isotopes).

Particulate gross alpha activity was measured weekly using alpha scintillation counting techniques. The determined activities were used to estimate effluent concentrations in e subsequent releases until the next scheduled analysis was pe rfo rmed .

Grab samples of continuous and batch releases were analyzed monthly for tritium. The determined concentrations were used to estimate tritium activity in subsequent releases until the next scheduled analysis was performed.

2.4.3 Liquid Effluents For continuous releases, samples were collected weekly and analyzed using gamma spectroscopy. The measured concentra-tions were used to determine radionuclide concentrations in the previous week's releases. For batch releases, gamma i analysis was performed on the sample prior to release.

For both continuous and bat;h re; eases, composite samples were analyzed quarterly by a cont ract laboratory (Teledyne Isotopes) for Sr-89, Sr-99, and l'e-55. Samples were composited and analyzed monthly for ;ritiva and gross alpha using liquid scintillation and gas flow proportional counting techniques, respectively. For radionuclides measured in the composite samples, the measured concentrations in the composite samples from the previous month or quarter were used to estimate released quantities of these isotopes in liquid effluents during the current month or quarter.  !

The total radioactivity in liquid effluent releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent discharged.

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W350897HP 7

f 2.5 Betch Releases The summarization of information for gaseous and liquid batch releases is included in Table 1.

2.6 Unmonitored Releases On May 7, 1990, an unplanned, unmonitored release of radioactivity occurred during draining of the Auxiliary Boiler. At no time were any Technical Specificatien dose limits exceeded.

Description of Event:

On May 7, 1990 an unplanned radioactive release was made from the Auxiliary Boiler Sump to the Metal Waste Pond. This is not an approved or monitored radioactive release path as per Technical Specification Table 4.11-1. As soon as the possible contamination of the Auxiliary Boiler Sump was realized, the release was terminated and the sump was sampled. Samples from the Auxiliary Boiler Sump indicated Xe-133 activity of 2.2E-7 pCi/ml which is well below the aikowable concentration of 2.0E-4 pCi/ml (Technical Specification 3.11.1.1).

Cause of Event:

On May 3,1990, the Demineralized Water Storage Tank (DWST) was discovered to be contaminated with Xe-131 and Xe-133. A sampling 1 program, initiated to determine if other secondary water sources j were contaminated, revealed that the Primary Water Storage Tank (PWST) and the Condensate Storage Tank (CST) were also contaminated with radioactive noble gases. Operational restraints resulting from this contaminatic.: vere not adequately and formally addressed to the : 1 A

Operations and Health Physics Shift personnel.

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On May 7,1990, the Auxiliary Boiler was drained from 100% to 15%

level to the Auxiliary Boiler sump. Due to contamination of CST water, the Auxiliary Boiler contained Xe-133 activity of 7.27E-7 pCi/ml. When the Auxiliary Boiler was drained, the contaminated water was transferred to the Auxiliary Boiler Sump. The Auxiliary Boiler Sump pumps continued to operate automatically thereby releasing contaminated water to the Metal Waste Pond through an unmonitored release point. The root cause of the release was poor communications. ,

When activity exists in normally non-radioactive systems or tanks, operations should contact Healta Physics when any liquids are to be pumped off-site. This had not been formally addressed to the Operations / Health Physics personnel prior to this event. The pumping of the Auxiliary Boiler Sump to the Metal Waste Pond was terminated when Health Physics learned that the event wac in progress. The Metal Waste Pond was sampled and indicated no activity. The total ,

estimated activity released to the Metal Waste Pond was 9.6 pC1.

Potential Reportable Event #90-022 documents this release event.

Corrective Action:

Immediate ccrrective actions were to stop pumping water f om the Auxiliary Boiler Sump to the Metal Waste Pond. The ssap was then aligned to pump to the Turbine Building Industrial Waste Sump, an allowed and monitored radioactive release point. All further radio-active water discharges were made via the Turbine Building Industrial Waste Sump.

Actions Taken to Prevent Recurrence:

Operations Daily Instructions were updated to address large quantity discharges of water from secondary / tertiary systems other than through the TBIWS to be sampled prior to discharge and diverted to the TBIWS if activity detected. Standing Instruction #90-02 was ,

initiated on May 17, 1990 to address this requirament. A permanent plant procedure is being developed and will be approved prior to I

April 1, 1991.

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3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables IA, IB, and IC. Note that there were no elevated releases, since all Waterford 3's releases are considered to be at ground level. The estimated total error it % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc. Detailed statistical evaluations of error are not required as per Regulatory Guide 1.21.

4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B. The estimated total error in % is based ,

upon several statistical uncertainties due to sample counting, efficiency, volume, etc. Detailed statistical evaluations of error are not required as per Regulatory Guide 1.21.

5.0 SOLID WASTES The summary of radioactive solid wastes shipped offsite for disposal is listed Table 3. The estimated total error in % is based upon several  ;

statistical uncertainties due to sample counting, efficiency, volume, j etc. Detailed statistical evaluations of error are not required as per Regulatory Guide 1.21.

6.0 METEOROLOGICAL DATA The summary of the hourly meteorological data for this reporting period will be included on the Semiannual Effluent Release Report to be submitted j within 60 days after January 1, 1991.

7.0 ASSESSMENT OF DOSES The summary of doses due to gaseous and liquid effluents for this reporting period will be included in the Semiannual Effluent Release Report to be '

submitted within 60 days af ter January 1,1991.

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8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There were no changes to the Process Contro'. Program for the period covered by this report.

8.2 Changes to the Offsite Dose Calculation Manual There were no changes to the Offsite Dose Calculation Manual for the period this report covers.

8.3 Unavailability of REMP Milk Samples, Due to the unavailability of three milk sampling locations within five kilemeters of the plant, Broad Leaf sampling is performed in  !

accordance with Technical Specification Table 3.12-1. Milk is collected, when available, from the control location and three identified sampling locations as indicated in Waterford 3 Offsite Dose Calculation Manual, Table 2 and Table 3.

8.4 Report of Technical Specification Required Instrument Inoperability I

Technical Specifications 3.3.3.10 and 3.3.3.11 require the reporting, j in the Semi-annual Radioactive Effluent Release Report, of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION statement. During the reporting period, there was one case when instrumentation was not restored to operability within the time specified by Technical Specifications. This case is described in the following section.

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8.4.1 Monitor

Waste Gas Holdup System Noble Gas Activity Monitor Time Required by Technical Specifications to Restore Operability: 30 days Period of Inoperability: 12/06/89 to 01/05/90 (30 days and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)

Cause of Inoperability:

The cause for Gaseous Waste Management (GWM) system effluent monitor to be declared inoperable was due to equipment com-ponent malfunction. The in-line filter regulator did not operate as designed. Operations declared the GWM Radiation monitor out-of-service on '12-06-89 at 1438. No effluent releases were made from the Waste Gas Holdup system during the period that the GWM Radiation monitor was out of service, Reason Operability Not Restored Within Allotted Time:

Work began on GWM Radiation monitor on 12/08/89 and continued up until 01/05/90. Delays were encountered due to the neces-sity of ordering replacement parts. Further delays were encountered due to a procedure revision required to properly retest the monitor. A functional test was satisfactorily completed and the GWM Radiation monitor was declared operable

( on 01/05/90 at 1838. 4

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W350897HP 12

,e 8.5 Activity Released via Secondary Pathways Secondary release paths previously identified and discussed in previous semi-annual effluent release reports were continuously monitored for radioactivity. The areas monitored were: 1) the Hot Machine Shop Exhaust (AH-35), 2) Decontamination Shop Exhaust (AH-34), 3) the RAB H&V Equipment Room Ventilation System Exhaust (E-41A and E-41B); and 4) the Switchgear/ Cable Vault Area Ventilation System (AH-2$). Continuous sampling for these areas is maintained in order to demonstrate the operability of installed treatment systems and to verify integrity of barriers separating primary and secondary ventilation systems. Sampling for these areas was limited to continuous particulate and lodine sampling and monthly grab noble gas sampling. The activity released via these secondary pathways resulted from routine operations and remained below significant levels. No corrective actions are required.

8.6 Missed Effluent Samples On July 3, 1990 at 0815, the batch release sample for Waste Condensate Tank B, Release Permit #LB-90045, was discovered to be missing when preparing to perform the monthly composite sample for the Liquid ,

Waste Management System. Waterford 3 Technical Specification 3/4.11.1 f states that a compocite sample of each batch release from a particular system shall be analysed for tritium and gross alpha monthly and for  ;

Sr-89, Sr-90, and Fe-55 quarterly. All other samples from the Liquid Waste Management system for the month of June, 1990 were saved for

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the composite analysis. The composite sample for June, 1990 was  !

prepared using the remaining samples. Analysis for Tritium and gross alpha were performed on this composite. Also, the quarterly composite was prepared with this composite then shipped to a contract laboratory .

for Sr-89, Sr-90 and Fe-55 analysis. (License Event Report 90-010 will be the primary documentation of this occurance and is forth-coming).

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The root cause for this missed effluent sample is personnel error.

The Health Physics Technician did not store the sample in its normal location for compositing after completion of the gamma analysis, nor did he perform an adequate shift turnover to identify the sample storage status. Contributing causes were that the sample was probably not clearly labeled and was disposed of by storing the sample amongst other similar containers which were being used for special sampling.

The corrective action taken to prevent recurrence was to review proper handling of liquid effluent samples that will be used for i composite analysis with Health Physics Technicians. Additionally, a procedure for liquid effluent sampling is being developed which will address clear labeling of liquid effluent samples used for composite analysis.

The effect of the missing sample is being evaluated. Results of the evaluation will be supplied in future reporting.

8.7 Additional Information The most recent Reactor Coolant System E-Bar calculation yielded results of 1.46376 McV/ Disintegration from a sample obtained on December 19, 1989. Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.

9.0 TABLES 1 Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents IB Semiannual Airborne Continuous Elevated and Ground Level Releases IC Semiannual Airborne Batch Elevated and Ground Level Releases 2A Semiannual Summation of All Releases by Quarter - All Liquid Effluents 2B Semiannual Liquid Cortinuous and Batch Releases 3 Solid Waste Shipped 0.'fsite for Disposal 4 Not Used (Reserved for Meteorological Data) 10.0 ATTACHMENTS ,

NONE l W350897HP 14

l TABLE 1 (1 of 1)

REPORT CATEGORY MTCH RELEAE SUPWRY ELEASE POINT I ALL TYPE OF RELEA E t BATCH LIQUID AND GAE 0JS PERIOD START TIE 0:00 ms = 12:00AM JWJARY 1,1990 PERIOD END TIE t 4343159 g a lits 9PM JLHE 30. !??0 LIQUID RELEASES NL99ER OF RELEASES  : 51 TOTAL TIE FOR ALL ELEASES t 12606.0 MlWTES MAllMUM TIE FOR A RELEASE 307.0 MIWTES AVERADE TIE FOR A RELEASE t 247.2 MlWTES MINIM TIE FOR A RELEASE 184.0 MlWTES

1. ERAGE STREAM FLOW t 793406.3 OPM GASEOUS RELEL.d PO SER OF RELEASES 3 TOTAL TIE FOR ALL RELEASES 1 1304.0 MlWTES MAllful TIE FOR A RELEASE : 647.0 MlWTES

1. 4 RAGE TIE FOR A ELEASE 434.7 MlWTES MINIMlm TIE FOR A RELEASE 57.0 MlW13 i

W350897HP 15

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t TABII 1 A (1 of 1)

REPORT CATE00RY t SEMIAMIAL SMTION OF ALL RELEASES BY OVARTER TYPE OF ACTIVITY I ALL AIR 90RE EFFLUENTS IIPORT!W) PERIOD I OVARTEli 41 MD QUARTER 4 2 I UNIT IQUARTER 1 80VARTER 2 IEST.TOTAlt t iHOURS IW.RS 1 ERROR %

TYPE OF EFFLUENT t i 1-2160t2161-4344 I A. FIS$10N AM) ACTIVAtt0N PRODUCTS

1. TOTAL RELEASE CURIE 5 t 9.83E 02 1.29E 03 1 1.50E Ott

2. AVERAGE RELEASE RATE FOR FERIOD IUC1/SEC 1 1.26E 02 1.65E 02 I

3. PERCENT OF @PLICABLE LIMIT t  % i N/A I N/A t

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B. RAD 1010 DIES

1. TOTAL 10 DIE-131 ICURIES 4.64E-04 8 3.40E-05 1.50E Olt

2. AVERAGE RELEASE RATE FOR PERIOD IUCl/SEC i 5.97E-05 t 4.42E-06 1

3. PERCENT OF APPLICABLE LIMIT  % i N/A I N/A 1 C. PARTICtLATES

1. PARTIC 1 ATES(HALF-LIVES)B DAYS) ICURIES t 1.12E-07 1 7.68E-06 1.50E 01:

2. AVERAGE RELIASE RATE FOR PERIOD IUC1/SEC 1.44E-09 i 9.78E-07 1

3. PERCENT OF APPLICABLE LIMIT t 1 N/A I N/A t

4. GROSS ALPHA RADI0 ACTIVITY ICtRIES  : 1.57E-05 t 3.27E-05 t D. TRITIUM

l. TOTAL RELEASE ICtRIES I 8.51E 01 4.07E 01 1.50E 01:

2. AVERAGE RELEASE RATE FOR PERIOD tVCl/SEC 1.10E 01 5.10E 00 t

3. PERCO G OF APPLICABLE LIMIT 1 N/A I N/A 1 W350897HP 16

TABII 1B (1 of 1)

PEPORT CATEGORY t SEM1496.14L AIRBORE CONTlWJOUS ELIVATED AND OROUND LEVEL. RELEASES. TOTALS FOR EACH WJCLIDE RELEASED.

TYPE OF ACilVITY  : FIS$10N CASES,10 DIES, AND PARTICULATES PENRTING PERIOD QUARTER # 1 AND PJARTER # 2 I (LEVATED RELEASES 1 VM PILEASIS I UNIT 10VARTER 1 19)ARTER 210VARTER 1 10VARTER 21 IHOURS IHOURS tH0VRS IH0VRS WCLIDE 1 1216012161-4344t 1-216012161-4344:

FISSIONCASES XE-133  : MIES : 0.00E41 0.00E41 8.10E 02 1.27E 03 XE-135  : CURIES I 0.00E-01 0.00E41 1.99E 01 2.46E 01 1 TOTAL FOR PERIOD 1 CLRIES : 0.00E-0110.00E-01 8.30E 02 1.29E 03 :

10 DIES 1-131  : CWlES 0.00E-01 0.00E41 4.64E-04 8 3.40E-05 1-133 I CURIES 0.00E4110.00E418 4.35E45 0.00E-01 TOTAL FOR PERIOD . 0. RIES : 0.00E-01 0.00E-01 15. 8E44 8 3.48E-05 ,

PARTICULATES H-3  : C W lES 0.00E-01 0.00E-01 8 8.51E 01 1 4.07E 01  :

(0-58  : CURIES 0.00E41 0.00E-01 1 1.12E-07 0.00E41 1 0 ALPHA CURIES 0.00E-01 0.00E-01 1 1.Y/E-05 t 3.27E-05 :

IR42 CWlES I 0.00E-01 1 0.00E41 1 0.00E-01 1 7.68E46 :

TOTAL FOR PERIOD t CURIES I 0.00E-0110.00E-0118.51E 01 14.07E 01 W3508971[P 17

e TABLE IC (1 of 1) '

t i

REPORTCATEGORY  : SEMIAWJAL AIR 90RE BATCH ELEVATED AND OROUND I LEVEL RELEASES. TOTALS FOR EACH NILIDE RELEASED.

TYPE OF ACTIVITY t FISSION GASES.100lES. AND MRTINLATES REPORTINGPERIOD t MTER 91 AND MTER 9 2 I

I ELEVATED RELEASES I OROUW RELEASES I t UNIT IQUARTER 1 IMTER 2 INTER 1 INTER 2 :

HOURS IHOURS HOWS IHOURS NJCLIDE I I l-216082161-4344 1-216012161-4344:

FISSIONGASES i _ .. . -.

FR-85M i CUR!ES 0.00E-0110.00E-01 2.21E-01 7.84E46 i KR-85 CWlES : 0.00E-01 0.00E-0110.00E41 1.5N-02 KR-87 I C WIES 0.00E-01 1 0.00E-01 6.71E-02 1 0.00E-01 KR-80 t CW!ES 0.00E4! t 0.00E41 13.03E-01 10.00E-01 i XE-131M CURIES 0.00E-0110.00E4112.08E 00 1.33E-03 I

/E-133M CURIES : 0.00E-0110.00E-01 t 1.45E 00 t 1.88E-04 i ri-133 CWlES : 0.00E-0110.00E-01 1.45E 02 1.43E-02 XE 435  : CWlES 0.00E41 0.00E-0113.42E 00 1.35E-04:

ARW t CURIES 0.00E-01 1 0.00E-01 1 3.16E-01 1 0.00E-01 TOTALFORPERIOD t CW lES I 0.00E-01 1 0.00E-01 1.53E 02 3.17E-02 1 j

10 DINES N0E PARTICULATES l - --

H-3 CWlES 0.00E-01 0.00E41 15.90E-0210.00E-01 h'

1 W350897HP 18

i TABII 2A (1 of 1)

REPORT CATE00RY SEM1AWAL SUMA110N OF ALL RELEASES BY QUARTER TYPE (F ACTIVITf 8 ALL L10V!D EFFLUENTS REPORTINGPERIOD I QUARTER 4 1 AND QUARTER I 2 t UNIT 80VARTER1IQUARTER2 TEST.TOTALI I IHOURS IHOURS IERROR%

I l-216012161-4344 I TYPE OF EFFLtKNT A. FIS$10N AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING I t t t i TRIT!UM. 0ASES. ALPHA) ICURIES  : 1. !X-01 1 5.00E-02 1.50E Olt

2. AVERAGE D! LUTED CONCENTPATION

• I DLRING PERIOD IUCl/tt. I 6.84E-09 t 2.72E-09 1

3. PERCENT OF APPLICABLE LIMIT t t i N/A I N/A t B. TRITitM

1. TOTAL RELEASE ICtRIES 4.15E 01 1 8.70E 01 1 1.50E 01

2. AVERAGE DILUTED CONCENTRATION I i 1 i DLRING PERIOD #UCl/ft. I 2.50E-06 4.00E-06 8

3. PERCEN! 0F APPLICABLE LIMIT t  % i N/A 1 N/A i 1 C. DISSOLVED AND ENTRAIED OASES

1. TOTAL RELEASE ICURIES  : 8.74E-01 2.30E 00 1 1.50E Oil

2. AVERAGE DILUTED CONCENTRATION  :  :  :

DLRING PERIOD IUCl/ft. I 5.27E-08 1 1.00E-07

3. PERCENT OF APPLICABLE LIMIT I  % i N/A I N/A D. GROSS ALPHA RADIDACTIVITY

1. TOTAL RELEASE ICLRIES 0.00E-01 0.00E-01 1 1.50E 018 E. ESTE VOL RELEASED (PRE-DILUTION) 10AL i 1.5?E 07 1 6.17E 05 1.50E 01 F. VtU fE OF DILUTION E TER USED 10AL 4.37E 09 I 5.64E 09 1.50E 01:

~

l W350897HP 19

TABII 2B j (1 of 2) l PIPORT CATEGORY  : SEMIAWJAL LIQUID CONilWQVS AND BATCH RELEAES TOTALS FOR EACH NUCLIDE RELEASED. I TYPE OF ACTIVITY  : ALL RAD 10 WCLIDES ,

EPORTING PERIOD OVARTER # 1 AND QUARTER 8 2 1 CONT!WOUS RELEASES I BATCH RELEASES I I UNIT  : QUARTER 1 IQUARTER 2 QUARTER 1 IQVARTER 2 :

HOURS tH0lRS IHOURS HOURS t WCLIDE  : I l-216012161-4344 1-216012161-4344e i ALL NJCLIDES H-3 MIES 0.00E41 10.00E-01 14.15E 018 8.70E 01 NA-24  : CORIES I 0.00E-0110.00E-01 2.27E-05 0.00E41 :

CR-51  : CURIE; I 0.00E-01 0.00E-01 1.25E-0310.00E41 m-54  : MIES I 0.00E-0110.00E4112.81E-04 I 7.37E44 '

FE-55 ClRIES 0.00E-01 .,.00E-01 4.05E-03 8 1.llE42 FE-59 i ClRIES : 0.00E-01 0.00E-01 1 1.59E44 0.00E 01 CD-58 CLRIES : 0.00E-01 0.00E-01 1 4.41-02 3 5.31E-03 :

C0-60  : CLRIES I 0.00E-01 10.00E-01 2.56E-0316.20E-03 :

R9-88 CLRIES 0.0C(-01 1 0.00E-01 0.00E41 1 1.75E-03 SR-89  : ClRIES 0.00E-0110.00E-01 0.00E-0116.30E46 I l

SR-92 i CLRIES I 0.00E-01 : 0.00E-01 6.65E-0516.0X-051 IR-95  : CURIES 0.00E-01 0.00E-01 1 3.45E-04 I 4.17E-04 :

IR-97 I CURIES I 0.00E-0110.00E4116.35E-05 81.02E-04 te-95  : CURIES I 0.00E41 1 0.00E-01 1 7.24E44 1 1.01E-03 :

TC-99M CtRIES : 0.00E-01 0.00E-01 1.3CE v'4 1 0.00E-01 1 R0-106  : CLRIES I 0.00E-01 0.00E-01 0.00E-Oi I 5.59E-04 AG-110M t ClRIES 0.00C-01 t 0.00E41 1.43E 4 3 1 2.67E-03 1-131  : CURIES 0.00E-01 0.00E-01 6.52E-03 81.17E-04 1-133 i CURIES : 0.00E-01 0.00E-01 1 4.66E-05 1 0.00E-01 :

CS-134  : CURIES 0.00E-01 0.00E-0116.26E4315.37E-03

CLRIES 0.00E-0118.90E-03 9.07E43 i CS-137 0.00E-01 BA-140  : CURIES 0.00E-01 1 0.00E-01 8 2.66E-04 0.00E-01 :

LA-140 i CtRIES 0.00E-01 0.00E418 5.19E-0410.00E41 W-187 CURIES I 0.00E-01 10.00E-01 0.00E-01 6.81E-05 :

KR-85M I ClRIES 0.00E-01 : 0.00E-01 0.00E-0113.50E44 :

AR45 CURIES 0.00E-01 1 0.00E-01 3 8.20E-04 1.05E43 KR48 i CURIES t 0.00E-0110.00E41 0.00E-01 1.62E44 XE-131M i ClRIES I 0.00E-0110.00E-01 1.30E-02 1.67E-02 :

W350897HP 20

s

. -i,.

e TABLE 2B (2 of 2)

REPORT CATE0mV t SEM!AMAL Ll@Jl0 CONTIMJOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELIASED.

TYPE OF ACTIVITY ALL RADIONJCLIDES REPORTINGPERIOD  : QUARTER 8 1 AND QUNtTER I 2 t(DNTINUQUSRELEASESI BATCH RELEASES I LNIT IEIARTER 1 QUARTER 2 IQUARTER 1 IQUARTER 2 :

H0$$ IHOURS HOURS HOURS NUCLIDE  : I l-216012161-43448 1-216012161-4344 ALL NUCLIES CONTINUED IE-133M I CURIES t 0.00E41 : 0.00E-01 9.05E-03 2.31E-02 IE-133 CURIES 0.00E-0116.61E-04 8.4141 2.24E 00 XE-135  : OJRIES 0.00E-0110.00E-01 5.91E-03 1.00E-02 (0-57 t CURIES I 0.00E-01 0.00E41 9.23E-05 t 1.31-05 :

SB-124  : CURIES 1 O. 00E-01 0.00E-01 1 4.30E-031 4.66E-04 :

SM-ll3  : CURIES 0.00E-01 : 0.00E-01 1 9.10E-05 5.59E-04 i 16-97  : CURIES 0.0(E-01 10.00E-018 8.87E-0512.62E45  !

SB-122 CURIES I 0.00E-01 0.00E-01 15.41E4415.71E-05 :

58-125  : CURIES 0.00E-01 0.00E41 3.02E-02 1.2X-02: ,

SB-126  : CURIES 0.00E-01 0.00E-01 1 1.20E44 0.00E 01 i TOTAL FOR PERIOD CURIES 0.00E-01 8 6.61E-04 4.25E 01 1 8.94E 01 1 4

'435089711P 21 4

. = ,.

TABLE 3 (1 of 3)

Solid Waste Shipped Offsite for Disposal During Period 01-01-90 thru 06-30-90 Container Waste Total  % i' Waste Type Volume ft3 Volume m3 Activity Ci Error Non Compacted Dry 1040ft3 147.4m3 0.878ci 125 Active Waste 95ft3 Before Volume Shipped to Reduction Scientific Ecology Group for volume reduction Resin Waste Manage- 182.4ft3 5.16m3 306ci 125 ment Resin dewatered  !

in a high integrity container Liquid Waste Manage- 181.7ft3 10.29m3 2.15ci 125 ment Resin Dewatered Waste Oil Shipped to 7.5 7.43m3 0.0094ci 125 Scientific Ecology Group for incineration i

• Waste volumes shipped for volume reduction do not reflect final burial waste volumes.

I W350897HP 22 i

l

l TABLE 3 (2 of 3)

Estimates of Major Nuclides By Waste Type Waste Type Nuclide Name  % Abundance Ci l

Non Compacted Dry Mn-54 2.7 2.37E-2 Active Water shipped Fe-55 33.2 2.91E-1 to Scientific Ecology 0o-58 9.26 8.13E-2 Group for Volume Co-60 8.63 7.58E-2 i reduction Ni-63 14.6 1.28E-1 Cs-134 11 9.66E-2 Cs-137 19.1 1.68E-1 Resin Waste Maaagement Mn-54 1.32 4.04 Resin Dewatered in a Fe-55 3.29 10.06 high integrity container Co-58 2.92 8.93 Co-60 3.69 11.29 Ni-63 13.7 41.92 CS-134 24.9 76.19 Cs-137 49.5 151.47 Liquid Waste Management Mn-54 3.045 6.55E-2 Resin Dewatered Fe-55 19.85 4.27E-1 Co-58 32.75 1.11E-1 Co-60 5.17 7.04E-1 Ni-63. 13.27 2.85E-1 Cs-134 11.12 2.39E-1 Cs-137 17.15 3.69E-1 Waste Oil Shipped to Mn-54 2.67 2.51E-4 Scientific Ecology Fe-55 32.7 3.07E-3 Group for incineration Co-58 9.13 8.58E-4 Ni-63 14.4 1.35E-3 Cs-134 10.8 1.01E-3 Cs-137 18.8 1.77E-3 W350897HP-. 23

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TABLE 3 (3 of 3)

Solid Waste Disposition Summary Number of Shipments Mode of Transportation Destination 7 Truck 4 Oak Ridge, TN  !

3 Barnwell, SC  !

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Type of Waste Class Shipments Type Container Mode Destination A 6 4-LSA Strong Tight Truck 4 Oak Ridge, TN 2-Type A 2 Barnwell, SC C 1 LSA HIC Truck Barnwell, SC Type A W350897KP 24

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