W3P87-1749, Semiannual Radioactive Effluent Release Rept for Jan-June 1987
| ML20237G596 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/30/1987 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| W3P87-1749, NUDOCS 8709020322 | |
| Download: ML20237G596 (24) | |
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Semiannual Radioactive Effluent Release Report !
January 1, 1987 - June 30, 1987 Waterford 3 SES Louisiana Power & Light 970902C322 070630 2 PDR ADOCK 0S00 H
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TABLE OF CONTENTS 1.0 SCOPE 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits j 2.2 Maximum Permissible Concentrations 1
2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Unplanned Abnormal 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 8.1 Changes to the Process Control Program 8.2 Changes to the Offsite Dose Calculation Manual 8.3 Unavailability of REMP Milk Sampling 8.4 Report of Technical Specification Required Instrument Inoperability 9.0 TABLES I
10.0 ATTACHMENTS 1 l
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1.0 SCOPE This Semiannual Radioactive Release Report is submitted as required by Louisiana Power and Light's Waterford 3 Technical Specification 6.9.1.8.
It covers the period from January 1, 1987 through June 30, 1987.
Included in this report is a summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period. The summary of meteorological data and results from the assessment of radiation doses due to the release of liquid and gaseous radioactive effluents will be included in the Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1, 1988.
Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21.
Other required information in this report includes an explanation of why certain instrumentation was not restored to operable status within the time specified in the ACTION Statement, as per Waterford 3 SES Tech- i nical Specification 3/4.3.3.11.
l 2.0 SUPPLEMENTAL INFORMATION l
1 2.1 Regulatory Limits i Specified as follows are the technical specification limits applicable to the release of radioactive material in liquid and gaseous effluents.
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2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive 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.
i 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 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and,
- b. During any calendar year: Less than or equal to 10 mrads .
for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.1.2 Iodines; Particulate, 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 l 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 mrems/yr to any organ. !
l The dose to a member of the public from Iodine 131 and 133, tri~ lum, and all radionuclides in particulate form with half ;
lives greater than eight (8) days in gaseous effluents l
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 mrems to any organ and, W350004H 3 I
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- b. During any calendar year: Less than or equal to 15 mrems 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 10CFR 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 l total activity.
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The dose or dose commitment to a member of the public from
! radioactive materials in liquid effluents released to 1
I unrestricted areas shall be limited:
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- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and less than or equal to 5 mrems to any organ, and l b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
l l 2.1.4 Uranium Fuel Cycle Sources l
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 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems) over the calendar year.
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2.2 Maximum Permissible Concentrations 2.2.1 Fission and Activation Gases; Iodines; and Particulate, 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 rate at the site boundary.
2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified in 10CFR20, Appendix B, Table II, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/ml is used as the MPC for dissolved and entrained noble gases in liquid effluents.
t 2.3 Average Energy i
This is not applicable to Waterford 3 SES's radiological effluent technical specifications.
l 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 SES Plant Technical Specifications.
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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 Reading Monitor Reading During Noble Gas Sampling 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 measured total radioactivity in gaseous effluents was determined from measured concentrations of each radionuclides present and the total volume discharged.
2.4.2 Iodines and Particulate Iodines and particulate discharged were sampled using a continuous sampler. Each week the charcoal cartridge and particulate filter were analyzed for gamma emitters using gamma spectroscopy. The determined radionuclides concentrations and effluent volume discharged were used to calculate the previous week's activity released.
Composites of the particulate samples were analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne Isotopes). Particulate gross alpha was measured weekly using alpha scintillation countirg techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled analysis was performed.
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1 e s Grab tritium samples for continuous and batch releases were analyzed monthly. The determined concentrations were used to estimate tritium activity in subsequent releases until the
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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 radionuclides concentrations in the previous week's releases. For batch releases, gamma analysis was performed on the sample prior to release.
For both continuous and batch releases, Sr-89, Sr-90, and j Fe-55 composite samples were analyzed quarterly by a contract laboratory (Teledyne Isotopes). Tritium and gross alpha composite samples were analyzed monthly using liquid scintil-lation and gas flow proportional techniques respectively.
For radionuclides analyzed in composite samples, the measured concentrations of the previous composite were used in deter-mining concentrations in liquid effluents.
The measured total radioactivity in liquid effluent releases was determined from the measured concentrations of each radio-nuclide present and the total volume of the effluent discharged.
2.5 Batch Releases The summarization of information for gaseous and liquid batch releases is included in Table 1.
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2.6 Unplanned Abnormal Releases ,
No unplanned abnormal releases occurred during the period covered by this report.
3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables IA, 1B, and IC. Note that there are no elevated releases at Waterford 3 SES.
4.0 LIQUID EFFLUENTS The quantities of radioactive material released in liquid effluents are summarized in Tables 2A and 2B.
5.0 SOLID WASTES A summary of radioactive solid wastes shipped offsite for disposal is listed in Table 3.
6.0 METEOROLOGICAL DATA The summary of the hourly meteorological data for this reporting period will be included in the Semiannual Effluent Release Report to be submitted within 60 days after January 1, 1988.
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 after January 1, 1988.
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8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program There were no changes to the Process Control Program for the period this report covers.
8.2 Changes to the Offsite Dose Calculation Manual i
l There were no changes to the Offsite Dose Calculation Manual for the period this report covers.
8.3 Unavailability of REMP Milk Samples j Due to the unavailability of three milk sampling locations within l five kilometers of the plant, Broad Leaf sampling is performed in 1
accordance with Technical Specification Table 3.12-1. Milk is collected, when availabie, from the control location and three identi-fied sampling locations as indicated in ODCM, Table 2 and Table 3.
8.4 Report of Technical Specification Required Instrument Inoperability Technical Specification, Limiting Condition for Operation (LCO),
3.3.3.11 requires the reporting in the Semiannual Effluent Release Report of why designated inoperable instrumentation was not restored to operability within the time specified in the ACTION Statement.
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8.4.1 Monitor
Waste Gas Holdup System Hydrogen Monitor and Oxygen Monitors Period of Inoperability: 3/21/85 - 6/30/87 (At end of reporting period monitors were still inoperable)
Time Required by Technical Specifications to Restore Operability: 30 days Cause of Inoperability:
Due to initial design problems excess amounts of moisture were l allowed to leak into both the Beckman 0 2 and Delphi H and 0 2 2 analyzer systems. Replacement of the analyzers and modification of the sample system was implemented during this period. While this was being done the system remained out of service.
i Reason Inoperability Not Restored Within Allotted Time:
Extensive hours were spent attempting to restore these analyzers to operable status. Several analyzer cells were replaced, the solenoid and regulator were repaired, and the i sample pump was both repaired and replaced. After these i l
l efforts failed to return the monitor to service, a station modification was initiated to replace the analyzer cells with !
less moisture sensitive models and to completely redesign the sample line condensate drain system.
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This modification entailed work in several areas of the plant and on four different systems. All existing piping and electronics associated with the Waste Gas Holdup System Hydrogen and Oxygen Monitors was essentially scrapped and redesigned.
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Work included re-routing all sample lines in the Laundry Room, modifying the existing drain header, and fabrication of a new drain header to tie into the Vent Gas Collection Header.
Re-routing of the Gas Surge Header Sample line and fabrication ;
of its drain was performed in Safeguards Room B. On Gas Decay-Tank A a new separator and drain line on.the Waste Gas Collec-tion Discharge Header was added to the second low point.
Actual work-on the Gas Analyzer Panel consisted of (1) adding l 12 new solenoid valves in the sample inlets; (2) modifying the panel to accommodate the new exo-sensor units; (3) installing a new pump and its associated tubing; and (4) wiring of all new and relocated components.
While testing the system, the Gas Decay Tank "C" sample line was found to be crossed with the Gas Surge Tank sample line.
Due to greater pressure in the Gas Decay Tank than that of the Gas Surge Tank the sampling pump diaphragm was blown.
This event also identified other problems with the system which required correction.
Design changes have been made to uncross the lines and install a pressure switch to prevent any subsequent over-pressurization. The pump was replaced and new wiring.was installed. Additional moisture traps, pressure regulators, valves and pressure indicators have been installed.
A detailed test procedure was prepared and approved. Testing of the system was successfully completed in early December of.
1986 and the system was placed "in-service". Operational checks were performed on the system after the plant returned to the operating mode following a refueling outage. The operational checks demonstrated that while the piping and sample tubing changes proved beneficial, the analyzers themselves proved unreliable due to inherent design problems. Therefore, the Waste Gas Hydrogen and Oxygen Monitoring System could not be returned to operable status.
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4 Based on the non-performance of the present analyzers, a new I Waste Gas Monitoring Panel consisting of sample conditioners, I proven analyzers and controls will be designed and installed. l The analyzers to be used in this panel were selected based on !
their successful performance in similar service at other plants. At this time, the modifications necessary for installing the new panel are being designed and constructed. l 1
Testing will commence immediately following the completion of l construction. The analyzer system will be returned to operability upon successful completion of testing. The system is expected to be returned to operability during the first half of 1988 following the second refueling outage.
l 9.0 TABLES l l
l 1 Batch Release Summary 1A Semiannual Summation of all Releases by Quarter - All Airborne Effluents I 1
IB Semiannual Airborne Continuous Elevated and Ground Level Releases 1C Semiannual Airborne Batch Elevated and Ground Level Releases 2A Semiannual Summation of All Releases by Quarter - All Liquid l Effluents ;
i 2P Semiannual Liquid Continuous and Batch Releases ;
3 Solid Waste Shipped Offsite for Disposal l
10.0 ATTACHMENTS None W350004H 12
TABLE 1 (1 of 1)
REPORT CATEGORY : MTCH RELEASE SUPetARY RELEASE POINT : ALL TYPE OF RELEASE l MICH LIQUID AND OASE00S PERIOD START TIE i'
- 0:00 FRS = 12:00AM JANUARY 1 1987 PERIOD E2 TIE : 4343:59 FRS = !!:59PM JtfE 30,1987 1
LIQUID RELEASES NLMBER OF RELEASES : 104 TOTAL TIE FOR ALL RELEASES : 27901.0 MIWTES MIIM TIE FOR A RELEASE : 362.0 MI WTES AVERAGE TIE FOR A RELEASE : 268.3 MIWTES MINIM TIE FOR A RELEASE : 123.0 MIWTES AVERADE STREAM FLOW 877801.3 GPM GASEOUS RELEASES NLMBER OF RELEASES : 24
! TOTAL TIE FOR ALL RELEASES : 15480.0 MIWTES MIIM TIE FOR A RELEASE : 2990.0 MINUTES AVERAGE TIE FOR A RELEASE : 645.0 MI W TES MINIM T!E FOR A RELEASE : 1.0 MIWTES 1
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TABLE 1A (1 of 1)
REPORT CATEGORY : SEMIANAL SlMtATION OF E RELEASES BY QUARTER TYPE OF ACTIVITY : E AIR 90RE EFFLUENTS REPORTINGPERIOD : QUARTER 81 APO QUARTER I 2
- UNIT QUARTER 1 QUARTER 2 :EST. TOTAL:
- H0lRS ! HOURS : ERROR I :
TYPE OF EFFLLENT .: 1-2160 :2161-4344 :
A. FISSION M ACTIVATION PRODUCTS
- 1. TOTAL RELEASE : CURIES : 3.49E 02 1.90E 03 : 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 2.23E 01 : 1.22E 02
- 3. PERCENT OF APPLICABLE LIMIT % : N/A N/A :
B. RADIO!0 DIES
- 1. TOTAL 100!E-131 :CtRIES : 6.75E-04 1 4.43E-05 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 4.32E-05 2.83E-06
- 3. PERCENT OF APPLICABLE LIMIT : % : N/A : N/A C. PARTIClLATES
- 1. PARTIClLATES(HALF-LIVES)8 DAYS) : CURIES
- 1.20E-04 1 2.94E-05 1.50E O!!
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 7.70E-06 : 1.88E-06
- 3. PERCENT OF APPLICABLE LIMIT l N/A N/A
- 4. OROSS ALPHA RADI0 ACTIVITY l CURIES 3.67E-07 8 9.70E-06 1
O. TRITIUM
- 1. TOTAL RELEASE :CLRIES : 6.24E v0 4.66E 00 1.50E 01:
- 2. AVERAGE RELEASE RATE FOR PERIOD :UCI/SEC : 3.99E-01 2.98E-01 :
- 3. PERCENT OF APPLICABLE LIMIT % : N/A : N/A :
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TABLE IB (1 of 1)
REPORT CATE0mY : SEMIAf004. A!RSORE CONT!!WOUS ELEVATED AND GRuule
- LEVEL RELEASES. TOTALS FOR EACH NUCLIDE RELEASED.
TYPE OF ACTIVITY : FISSION GASES,10 DIES. AND PA.TTICtLATES REPORTING PERIOD : QUARTER 8 1 AND QUARTER I 2
- ELEVATED RELEASES : GROUND RELEASES :
- LNIT QUARTER 1 : QUARTER 2 : QUARTER 1 : QUARTER 2 :
- HOURS :H0tRS l HOURS HOURS :
NUCLIDE :' : 1-2160 :2161-4344 1-2160 :2161-4344 :
FISSION GASES j l
KR-85M : CURIES : 0.00E-01 : 0.00E-01 : 8.75E-01 : 2.89E N :
IE-133M : CURIES : 0.00E-01 : 0.00E-01 : 6.69E 0019.43E '
XE-133 : CLRIES : 0.00E-01 : 0.00E-01 13.11E 02 : 1.63E :
XE-135 : CURIES 0.00E-01 0.00E-01 4.25E 00 : 3.24E 01 :
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.00E-01 ! 3.23E 02 : 1.68E 03 : ,
10 DIES I-131 : CLRIES : 0.00E-01 : 0.00E-01 : 6.75E-04 : 4.43E-05 :
PARTICtLATES 1
I H-3 : CURIES : 0.00E-01 : 0.00E-01 6.21E 00 : 4.64E 00 :
CR-51 : CURIES : 0.00E-01 : 0.00E-01 : 3.26E-06 : 0.00E-01 :
C0-58 : CURIES : 0.00E-01 : 0.00E-01 1.51E-05 : 2.55E-05 :
RU-103 : CURIES : 0.00E-01 : 0.00E-01 : 1.93E-06 : 0.00E-01 :
CS-134 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.91E-07 :
CS-137 : CURIES : 0.00E-01 : 0.00E-01 0.00E-01 13.27E-06 :
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CLRIES : 0.00E-01 : 0.00E-01 : 3.67E-07 : 9.70E_06__
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.00E-01 : 6.22E 00 : 4.64E 00 a l
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I TABLE IC (1 of 1) l EPORT CATEGORY : SEMIAf00AL AIRBORE BATCH ELIVATED AND CROLND l'
- LEVEL RELEASES. TOTALS FOR EACH 10CLIDE RELEASED.
TYPE OF ACTIVITY : FISSION GASES 10 DIES. AND PARTICLLATES !
REPORTING PERIOD : QUARTER 8 1 AND QUARTER 8 2 !
ELEVATED RELEASES : GROUND RELEASES
- UNIT : QUARTER 1 : QUARTER 2 : QUARTER 1 QUARTER 2 :
- HOURS : HOURS : HOURS ! HOURS )
MJCLIDE : : 1-2160 82161-4344 : 1-2160 :2161-4344 : I l
FISSION GASES 1
KR-85M CLRIES : 0.00E-01 : 0.00E-01 : 1.76E-02 : 1.60E-02 : I KR-85 : CtRIES : 0.00E41 : 0.00E-01 : 2.42E-01 : 2.86E 00 : l KR-88 : CURIES : 0.00E-01 : 0.00E-01 15.82E-03 : 0.00E-01 : i IE-131M : CURIES 0.00E-01 : 0.00E-01 : 2.00E42 : 3.21E 00 :
XE-133M : CLRIES : 0.00E-01 : 0.00E-01 : 3.61E-01 : 1.93E 00 :
IE-133 : CtRIES : 0.00E-01 : 0.00E-01 2.52E 01 : 2.16E 02 :
IE-135 : ClRIES ! 0.00E-01 : 0.00E-01 : 3.18E-01 : 1.26E 00 :
AR-41 : CURIES : 0.00E-01 : 0.00E-01 : 3.41E-03 0.00E-01 :
TOTAL FOR PERIOD : CLRIES : 0.00E-01 : 0.00E-01 : 2.62E 01 : 2.25E 02 :
10 DIES N0E PARTICLLATES H-3 : CLRIES : 0.00E-01 : 0.00E-01 : 2.89E-02 : 1.49E-02:
CO-58 : CLRIES : 0.00E-01 0.00E-01 : 4.27E-05 : 0.00E-01 :
CS-137 : CLRIES : 0.00E-01 : 0.00E-01 5.75E-05 : 0.00E-01 :
TOTAL FOR PERIOD : CLRIES : 0.00E-01 : 0.00E-01 2.90E-02 : 1.49E-021 W350004H 16
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1 TABII 2A (1 of 1) '
i REPORT CATE00RY ! SENIANAL SMATION OF ALL REL1ASES BY QUARTER TYPE OF ACTIVITY ALL LIQUID EFFLtENTS REPORTINGPERIOD QUARTER 91 M GUARTER I 2 8 (MIT 10UARTER 1 IQUARTER 2 IEST. TOTAL:
- IHOURS ! HOURS ERROR % :
TYPE OF EFFUENT I 1-2160 2161-4344 :
- A. FISSION Ale ACTIVATION PRODUCTS i
- 1. TOTAL RELIASE(NOT INCLUDING : :
TRITILM. GASES, ALPHA) ICLRIES 4.87E-01 1 1.18E-01 : 1.50E 01:
- 2. AVERAGE DILUTED CONCENTRATION : : I i :
DURING PERIOD IUCI/M. I 9.65E-09 2.79E-09 3
- 3. PERCENT OF APPLICABLE LIMIT : % N/A : N/A !
B. TRIT!lM
- 1. TOTAL RELEASE C1 RIES : 1.12E 01 6.58E 01 1.50E 01:
- 2. AVERACE DILUTED CONCENTRATION : :
DURING PERIOD IUCI/ft. I 2.23E-07 1.56E-06 1
- 3. PERCENT OF APPLICABLE LIMIT I % N/A : N/A l C. DISSOLVED M ENTRA!ED GASES
- 1. TOTAL RELEASE ICLRIES 6.00E 00 2.92E 00 t'1.50E 01
- 2. AVERAE DILUTED CONCENTRATION : : :
DlRIE PERIOD tUCI/M. I 1.21E-07 6.90E-08
- 3. PERCENT OF APPLICABLE LIMIT 1 N/A N/A D. 0ROSS ALPHA RADI0 ACTIVITY
- 1. TOTAL RELEASE :CLRIES : 1.30E-06 t 1.13E-05 1.50E O!!
E. WASTE VOL RELEASG (PRE-DILUTION) IGAL 7.46E 05 5.33E 05 t 1.50E 01:
F. VOLtfE CF DILUTICH WATER USED 80AL 1.3 1 10 1.12E 10 1 1.50E 01:
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TABLE 2B (1 of 2)
REPORT CATE0 CRY SEMIAIBURL LIQUID CONT!WOUS AW BATCH RELEASES
- TOTALS FOR EACH WCLIIE RELEASED.
TYPE OF ACTIVITY ALL RADIOWCLIOES REPORTINGPERIOD {
- GlMRTER 81 AW QUARTER 8 2 )
- CONT!WOUS RELEASES 1. BATCH RELEASES I LMIT tQUARTER 1 QUARTER 2 IQUARTER 1 IQUARTER 2 :
- H0lRS H0lRS IHOURS IH0lRS WCLIDE : I l-2160 82161-4344 8 1-2160 12161-4344 ALLt.*JCLIDES H-3 l NA-24 QRIES : 0.00E-01 : 0.00E-01 1 1.12E 01 16.58E 01 :
I CLRIES 0.00E-01 : 0.00E-01 1 1.10E44 1.07E-04 :
CR-51 m-54 : ClRIES I 0.00E-01 : 0.00E-01 13.14E-0210.00E-01 :
- CtRIES 0.00E-01 : 0.00E-01 5.45E-03 8 3.96E-03 FE-55 FE-59 CLRIES I 0.00E-01 0.00E-01 1.82E-01 1 3.27E-02 1 1
CLRIES 0.00E-01 10.00E41 I 4.00E-0313.09E-04 I CO-58 CD-60 CtRIES I 0.00E41 : 0.00E-01 ! 1.70E-01 : 3.15E-02 : }
ZlF65 1 CLRIES : 0.00E-01 : 0.00E-01 1 2.13E-02 1.99E-02 RB-88 C1 RIES ! 0.00E-01 8 0.00E-01 1 1.02E-03 : 7.25E-04 CtRIES SR-89 0.00E-01 : 0.00E-01 12.81E-04 I 0.00E-01 :
1 CLRIES 0.00E-01 : 0.00E-01 1 1.98E44
- 1.39E-03 :
SR-92 ZR-95 1 CLRIES : 0.00E-01 : 0.00E-01 : 2.96E-05 2 5.30E-05 : -
NB-95
- CtRIES I 0.00E-01 10.00E-01 1.03E-02 '1.57E-03
- CtRIES 0.00E-01 : 0.00E-01 1 1.90E-021 3.67E-03 i TC-99M RU-103 1 ClRIES : 0.00E41 0.00E-01 12.51E-0410.00E-01
- 1 QRIES 0.00E41 I 0.00E-018 7.86E-04 8 2.21E-05 AG-!!0M : CLRIES I-131 0.00E-01 1 0.00E-01 : 1.54E-03 . 99E-04 8 1-133 1
- CtRIES : 0.00E41 : 0.00E-01 : 1.89E-02 : 2.95E-03 :
1-135 ClRIES : 0.00E41 : 0.00E-01 13.54E-03 : 0.00E-01 CS-134 CtRIES 1 0.00E-01 1 0.00E41 1 4.37E-M ! 0.00E-01 :
- CURIES CS-136 0.00E-01 : 0.Out-01 12.01E4414.45E-03 8
- ClRIES 0.00E-01 1 0.00E41 1 0.00E-01 1.96E-04 8 1
CS-137 CURIES LA-140 0.00E41 10.00E41 1.55E-03 9.20E-03 :
CE-141
- ClRIES I 0.00E-01 10.00E-01 4.21E-041 1.39E-04 :
1 QRIES 0.00E-01 : 0.00E-01 : 1.43E-04 0.00E-01 I CE-144 W-187
- CLRIES : 0.00E-01 : 0.00E-01 1.22E43 1 0.00E-01
- CtRIES 0.00E-01 : 0.00E-01 7.04E-05 0.00E-01 :
KR-85M ClRIES 0.00E-01 1 0.00E-01 1 2.21E-04 1 3.90E-05 W350004H 18 l
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l TABLE 2B (2 of 2)
REPORTCATEGORY : SEMIAf80 t. LIQUID CONT! WOUS A W BATCH RELEASES
- TOTALS FOR EACH WCLIDE RELEASED.
- ALL RADIOWCLIDES :
TYPE OF ACTIVITY REPORTING PERIOD : QUARTER I 1 AND QUARTER I 2 j i CONT!WOUS RELEASES : BATCH RELEASES
- UNIT : QUARTER 1 : QUARTER 2 QUARTER 1 0UARTER 2 :
- :H0lRS HOURS ! HOURS :H0tRS :
WCLIDE : 1-2160 82161-4344 1-2160 12161-4344 :
ALL NUCLIDES CONT!WED KR-85 : CLRIES 0.00E-01 : 0.00E-01 : 7.41E-03 : 1.64E-02 : ;
KR-88 : CtRIES : 0.00E-01 : 0.00E-01 : 6.21E-0510.00E-01 : :
l IE-131M : CLRIES : 0.00E-01 10.00E-01 : 1.75E-02 : 3.64E-02 : !
XE-133M : CLRIES : 0.00E-01 : 0.00E-01 3.72E-02 : 1.03E-02 XE-133 : CLRIES : 0.00E-01 : 0.00E-01 : 6.00E W 2.85E 00 :
IE-135M : CLRIES : 0.00E-01 : 0.00E-01 : 2.96E-04 : 0.00E-01 :
IE-135 ' : CtRIES : 0.00E-01 : 0.00E-01 : 1.29E-02 : 2.31E-03 : 1 SR-90 : CURIES : 0.00E-01 : 0.00E-01 : 0.00E-01 2.79E-05 :
G ALPHA : CLR!ES : 0.00E-01 : 0.00E-01 : 1.30E-06 : 1.13E-05 :
00-57 : CLR!ES : 0.00E-01 : 0.00E-01 3.44E-04 : 2.17E-04 : 1
- CtRIES : 0.00E-01 : 0.00E-01 : 6.51E-0312.29E-03 :
$8-124 SN-113 : CURIES : 0.00E-01 : 0.00E-01 : 5.35E-03 : 2.13E-03 :
NB-97 : CURIES : 0.00E-01 : 0.00E-01 : 3.24E-04 : 3.42E-04 :
SB-122 : CLRIES : 0.00E-01 10.00E-01 : 0.00E-01 : 1.97E-05 :
SC-46 : CtR!ES : 0.00E-01 : 0.00E-01 : 1.42E-04 0.00E-01 :
TOTAL FOR PERIOD : CURIES : 0.00E-01 : 0.00E-01 : 1.79E 01 : 6.89E 01 :
W35000411 19
4 #e 3 4
TABLE 3 (1 of 2)
- REGULATORY GUIDE 1.21 REPORT ***
SOLID WASTE SHIPPED OFFSITE FOR DISPOSAL ssDURING PERIOD FROM 1/1/87 TO 6/30/8788 CONTAINER CUBIC WASTE TYPE VOLUME FTs METERS CURIES- % ERROR (CI)
COMPACTED DRY 95' 80.7 1.4E+00 +/- 25%
ACTIVE WASTE
! NON COMPACTED 95 18.8 3.4E-02 +/- 25% ,
DRY ACTIVE WASTE LIQUID WASTE 182 30.9 3.4E+00 +/- 25%
MANAGEMENT SYSTEM SPENT RESIN SOLIDIFIED WITH CEMENT NON COMPACTED DRY 133 11.3 1.7E-02 +/- 25%
ACTIVE WASTE IN A B-25 OVERPACK CONTAINER 8: ESTIMATES OF MAJOR NUCLIDES BY WASTE TYPE **
WASTE TYPE NUCLIDE ABUNDANCE CURIES 1
COMPACTED DRY Mn-54 1.6% 2.2E-02 ACTIVE WASTE Fe-55 2.7% 3.7E-02 Co-58 28.0%- 3.8E-01 Co-60 3.1% 4.2E-02 Ni-59 .0% .0E+00 Ni-63 1.4% 1.9E-02 Nb-94 .0% .0E+00 H-3 1.4% 1.9E-02 C-14 .1% 1.3E-03 Sr-90 .0% .0E+00 To-99 .0% .0E+00 I-129 .0% .0E+00 Cs-134 17.2% 2.3E-01 Cs-137 44.5% 6.1E-01 Pu-241 .0% .0E+00
, Cm-242 .0% .0E+00 l
l NON COMPACTED Mn-54 1.7% 5.6E-04 DRY ACTIVE WASTE Fe-55 2.8% 9.3E-04 Co-58 30.5% 1.0E-02 Co-60 3.2% 1.1E-03 Ni-59 .0% .0E+00 Ni-63 1.5% 4.9E-04 H-3 1.4% 4.8E-04 W350004H 20
1
- e. .== e TABLE 3 (2 Of 2)
C-14 .1% 3.2E-05 Sr-90 .0% .0E+00 Tc-99 .0% .0E+00 I-129' .0% .0E+00 Cs-134 17.8% 6.0E-03 Cs-137 91.1% 1.4E-02
[ Pu-241 .0% .0E+00 Cm-242 .0% .0E+00 LIQUID dASTE Mn-54 3.2% 1.1E-01 MANAGEMENT SYSTEM Fe-55 3.2% 1.1E-01 SPENT RESIN co-58 39.9% 1.4E+00 SOLIDIFIED WITH Co-60 3.7% 1.3E-01 CEMP4T Ni-59 .0% .0E+00 Ni-63 1.4% 4.9E-02 Nb-94 .0% .0E+00 Sb-124 1.6% 5.4E-02 l H-3 .9% 3.1E-02
( C-14 .1% 3.8E-03 i
Sr-90 .0% .0E+00 Tc-99 .0% .0E+00' I-129 .0% .0E+00 Cs-134 15.5% 5.3E-01 Cs-137 29.5% 1.0E+00 Pu-241 .2% 7.8E-03 Cm-242 .0% .0E-00 NON COMPACTED DRY Mn-54 1.6% 2.6E-04 ACTIVE WASTE IN A Fe-55 2.6% 4.3E-04 0-25 OVERPACK Co-58 31.5% 5.2E-03 CONTAINER Co-60 2.9% 4.8E-04 Ni-59 .0% .0E+00 Ni-63 1.3% 2.2E-04 Nb-94 .0% .0E+00 H-3 1.3% 2.2E-04 C-14 .1% 1.4E-05 Sr-90 .0% .0E+00' Tc-99 .0% .0E+00 I-129 .0% .0E+00 Cs-134 16.6% 2.7E-03 Cs-137 42.1% 7.UE-03 Pu-241 .0% '.0E+00 Ca-242 .0% .0E+00
- SOLID WASTE DISPOSITION
SUMMARY
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION O
BARNWELL 0 RICHLAND 8 TRUCK BEATTY 0 OTHER NUMBER OF TYPE OF TYPE MODE OF CLASS EHIPMENTS SHIPMENTS CONTAINER TRANSPORT DESTINATION A 5 LSA STRONG TIGHT TRUCK BEATTY A 3 LSA CASK TRUCK BEATTY W350004H 21
g
,' Refer: 10CFR50.36a
+ P. O. BOX 60340 LOUIS&1LiG POWER AN HT A/ 317 NEW BARONNE STREET ORLEANS, LOUISIANA 70160 *
(504)595 3100 UTI!iSNsysi[M August 27, 1987 W3P87-1749 A4.05 QA 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 l Semiannual Radioactive Effluent Releas.' Report l
l Enclosed is the subject report on effluent releases which covers the period of January 1 through June 30, 1987. This report is submitted per Section 6.9.1.8 in the Waterford 3 Technical Specifications (NUREG-ll17) of Appendix A to Facility Operating License No. ITF-38 and 10 CFR 50.36a(a)(2), pursuant to 10CFR50.4.
Very truly yours, Nuclear Safety and Regulatory Affairs Manager l KWC:GEW:pmb Enclosure l cc (w/ enclosure): R.D. Martin, NRC Region IV NRC Resident Inspectors Office cc (w/o enclosure): J.A. Calvo, NRC-NRR J.H. Wilson, NRC-NRR E.L. Blake W.M. Stevenson }gl 2f! : 'Y c' iM 1 .-c' N l !
"AN EQUAL OPPORTUNITY EMPLOYER"
l 1
USNRC-DS
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