ML20138D692
| ML20138D692 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20138D697 | List: |
| References | |
| NUDOCS 9705010215 | |
| Download: ML20138D692 (43) | |
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5 TABLE OF CONTENTS j-Page No.
1.0 SCOPE 3
2.0 SUPPLEMENTAL INFORMATION 4
2.1 Regulatory Limits 4
2.2 Maximum Permissible Concentrations 6
4 2.3 Average Energy 7
j 2.4 Measurements and Approximations of Total Radioactivity 7
2.5 Batch Releases 9
3 l
2.6 Unplanned Abnormal Releases 9
i-l 3.0 GASEOUS EFFLUENTS 9
j 4.0 LIQUID EFFLUENTS 9
i 5.0 SOLID WASTES 9
6.0 METEOROLOGICAL DATA 10 a
7.0 ASSESSMENT
OF DOSES 11 l
7.1 Doses due to Gaseous Effluents 11 f
7.2 Doses due to Liquid Effluents 13 l
7.3 40 CFR Part 190 Dose Evaluation 13 7.4 Doses to Public Inside the Site Boundary 14 8.0 RELATED INFORMATION 15 8.1 Changes to the Process Control Program 15
[
8.2 Changes to the Offsite Dose Calculation Manual 15 1
8.3 Unavailability of REMP Milk Sampling 15 8.4 Report of Technical Specification Required Instrument inoperability 16 8.5 Activity Released via Secondary Pathways 20 8.6 Missed Effluent Samples 20 8.7 Major Changes to Radioactive Waste Systems 20 8.8 Additional Information 20 9.0 TABLES 21 10.0 ATTACHMENTS 21 1419HP 2
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1.0 SCOPE l
This Annual Radioactive Effluent Release Report is submitted as required by Waterford 3's Technical Specification 6.9.1.8. It covers the period from January 1,1996 through December 31,1996. Information in this report is presented in the format outlined in Appendix B of Regulatory Guide 1.21.
l The information contained in this report includes:
l (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 summary of the meteorological data collected during 1996.
l (3)
Assessment of radiation doses due to liquid and gaseous l
radioactive effluents released during 1996.
(4)
A submittal of changes to the Offsite Dose Calculation Manual and Process Control Program during this reporting period.
(5)
A discussion of why required radioactive effluent monitoring instrumentation was not returned to service within the time specified.
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2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits The Limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections. These limits are addressed in UNT-005-014, Offsite Dose Calculation Manual.
4 2.1.1 Fission and Activation Gases (Noble Gases) t The dose rate due to radioactive noble gases released in gaseous effluents 4
from the site to areas at and beyond the site boundary shall be limited to less than or equal to i
500 mremfyr to the totalbody; and 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.
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+ During any calendar quarter: Less than or equal to 5 mrad forgamma radiation; and 10 mrad forbeta radiation
+ During any calendar year: Less than or equal to I
10 mrad forgamma radiation; and 20 mrad forbeta radiation.
4 1419HP 4
2.1.2 lodines; Paiticulates with 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.
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 follow og:
+ During any calendar quarter: Less than or equal to 7.5 mrem to any organ; and
+ 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 ten times the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, 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 unrestricted areas shall be limited to the following:
+ During any calendar quarter to less than or equal to 1.5 mrem to the totalbody; and 5 mrem to any organ, and 1419HP 5
+ During any calendar year to less than or equal to 3 miem to the whole body; and l
10 mrem to any organ.
2.1.4
- Uranium Fuel Cycle Sources The dose or dose commitment to any member of the public due to releases l
of radioactivity and radiation from uranium fuel cycle sources over 12 consecutive months shall be limited to less than or equal to t
25 miem to the TotalBody or any organ l
l (except thyroid organ); and 75 mrem to the Thytoid t
2.2 Maximum Permissible Concentrations I
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l 2.2.1 Fission and Activation Gases; lodines; and Particulates, Half Lives > 8 l
l Days l
l 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.
r 2.2.2 Liquid Effluents l
Ten times the effluent concentration (EC) values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 pCi/miis used as the concentration limit for dissolved and entrained noble gases in liquid effluents.
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2.3 Average Energy This is not applicable to Waterford 3's Effluent Specifications. E-Bars are not required to be calculated from effluent release data.
2.4 Measurements and Approximations of Total Radioactivity l
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 5.3-1 and 5.4-1 of UNT-005-014, Offsite Dose Calculation Manual.
2.4.1 Fission and Activation Gases (Noble Gases)
For continuous releases, a ges grab sample was analyzed monthly for l
noble gases. Each week a Gas Ratio (GR) was calculated according to the l
following equation:
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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 l
determine noble gases discharged continuously for the previous week. For l
gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to release to determine noble gas concentrations in the l
batch. In all cases the total radioactivity in gaseous effluents was l
determined from measured concentrations of each radionuclide present and the total volume discharged.
2.4.2 lodines and Particulates lodines 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 emitters using gamma spectroscopy. The determined radionuclide concentrations and effluent volume discharged were used to calculate the previous week's activity released. The particulate samples were 1419HP 7
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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 subsequent releases until the next scheduled analysis was performed.
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 concentrations were used to determine radionuclide concentrations in the following week's releases.
For batch releases, gamma analysis was performed on the sample prior to release.
For both continuous and batch releases, composite samples were analyzed.
quarterly by a contract laboratory (Teledyne Isotopes) for Sr-89, Sr-90, and Fe-55. Samples were composited and analyzed monthly for tritium and gross alpha using liquid scintillation and gas flow proportional counting 1
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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2.5 Batch Releases A summary of information for gaseous and liquid batch releases is included in Table 1.
2.6 Unplanned / Abnormal Releases There were no Unplanned / Abnormal releases during this reporting period.
3.0 GASEOUS EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 1 A,1B, and 1C. Note that there were no elevated releases, since all Waterford 3 releases are considered to be at ground level. The estimated total error in % is based upon l
several statistical uncertainties due to sample counting, efficiency, volume, etc.
l 4.0 LIQUID EFFLUENTS 1
l l
The quantities of radioactive material released in liquid effluents are summarized in Tables t
l 2A and 2B. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.
5.0 SOLID WASTES l
The summary of radioactive solid wastes shipped offsite for disposal is listed in Table 3.
l For certain waste forms Waterford 3 is now using volume reduction services provided by l
Scientific Ecology Group, Inc. (SEG). These waste forms are identified in Table 3 and volumes reported reflect the volume of waste shipped offsite, not final disposal volumes.
Final disposal volumes for wastes compacted offsite are available upon request. The estimated total error in % is based upon several statistical uncertainties due to sample counting, efficiency, volume, etc.
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l 6.0 METEOROLOGICAL DATA l
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In Table 4, the hourly meteorological data from January 1,1996 through December 31, 1996, is presented in the form of a joint frequency distribution of wind speed, wind direction, and atmospheric stability. The Waterford-3 data recovery results by parameter are as l
follows:
Parameter Annual Data Recovery Rate l
Delta T 100.0 %
Wind Speed 100.0 %
Wind Direction 100.0 %
Overall
- 100.0 %
- Simultaneous occurrence of valid data for all three parameters.
Dispersion and deposition values were determined from the 1996 data and used in the assessment of doses due to gaseous effluents released from site during the 1996 period.
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7.0 ASSESSMENT
OF DOSES 1
7.1 Dose Due to Gaseous Effluents 7.1.1 Air Doses at the Site Boundary l
Air doses from gaseous effluents were evaluated at the closest offsite location that could be occupied continuously during the term of plant j
operation and that would result in the highest dose. This location was i
determined by examining the atmospheric dispersion parameters (x/Q's) at the closest offsite locations that could be continuously occupied during plant operation in each of the meter;rological sectors surrounding the plant.
The location that would have the highest dose would be that location l
having the most restrictive (largest) x/Q value.
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Based on actual meteorological data collected during 1996, this location i
was determined to be in the ENE sector at a distance of 966 meters (0.6 miles) from the plant. Doses were assessed at this location in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only beta and garama exposures in air due to noble gas. The results of these assessments for the year 1996 are summarized as follows:
l Beta air dose:
0.071 mrad Gamma air dose:
0.076 mrad l
The above Beta and Gamma air doses represent the following percentage l
of the Annual Dose limits:
0.36%
of the Beta air dose limit (20 mrad).
l 0.76 %
of the Gamma air dose limit (10 mrad).
Dose calculation results are summarized by quarters in Table 5.
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7.1.2 Maximum Organ Dose to the Critical Receptor I
The maximum organ dose to a MEMBER OF THE PUBLIC from I-131, 1-133, tritium, and all radionuclides in particulate form with half-lives greater.
than 8 days in gaseous effluents released to areas at and beyond the site l
boundary was determined for 1996.
An assessment of the maximum organ dose was performed for the critical receptor. The critical receptor was assumed to be located at the nearest residence to the plant having the most restrictive atmospheric dispersion (X Q) and deposition (D/Q) parameters. Furthermore, it was assumed that
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the receptor living at this residence consumed food products that were either raised or produced at this residence.
l Using land use census and meteorological data for 1996, the residence with the highest x/O and D/O values was determined to be in the NE sector at a distance of 1448 meters (0.9 miles) from the plant. The j
dose calculation was performed in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering the inhalation, ground plane exposure, and ingestion pathways. The maximum organ dose to the critical receptor was determined to be:
l 0.147 mrem to a child thyroid.
This represents 0.98 % of the Annual Organ Dose limit (15 mrem).
Dose calculation results are summarized by quarters in Table 5.
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I 7.2 Doses Due to Liquid Effluents l
The annual doses to the maximum exposed individual resulting from exposure to l
liquid effluents released during 1996 from Waterford 3 were:
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0.849 mrem to the Total Body.
1.182 mrem to the maximum exposed organ (Liver).
The above doses represent the following percentage of the Annual Dose limits:
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28.30 %
of the Total Body Dose Limit (3 mrem).
11.82 %
of the Organ Dose Limit (10 mrem).
Dose calculation results are summarized by quarter in Table 5. The doses were l
calculated in accordance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual.
7.3 40 CFR Part 190 Dose Evaluation in accordance with Waterford 3 Offsite Dose Calculation Manual, Section 5.5.2, dose evaluations to demonstrate compliance with Surveillance Requirements 5.5.1.a and 5.5.1.b of the ODCM, dealing with dose from the uranium fuel cycle, need to be performed only if quarterly doses exceed 3 mrem to the total body (liquid releases),
10 mrem to any organ (liquid releases),10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to any organ from radiciodines and particulates.
i At no time during 1996 were any of these limits exceeded; therefore, no evaluations were required.
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7.4 Doses to Public inside the Site Boundary The Member of the Public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee at Waterford 1 and 2 fossil fuel plants, located in the NW sector at a distance of approximately 670 meters (0.42 miles) from the plant.
Based on an assumed occupancy of 25% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week) and the fact that all employees are adults, the calculated doses were determined to be less than:
1.11E-02 mrem to the maximum exposed organ i
(Thyroid) i 1.21E-02 mrem to the Total body f
2.11E-02 mrem to the skin Doses were calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering only the inhalation and ground plane exposure pathways.
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I 8.0 RELATED INFORMATION 8.1 Changes to the Process Control Program Changes were made to the Process Control Program (PCP), procedure RW-001-210, during the reporting period. Revision 7 was done to change titles and make editorial corrections. A copy of the PCP is included in attachment 10.1 of this report.
8.2 Changes to the Offsite Dose Calculation Manual Changes were made to the Offsite Dose Calculation Manual (ODCM), procedure UNT-005-014, during the reporting period. Revision 5 was done to implement revisions to 10CFR20. Changes 1 and 2 were made to provide clarifications and for editorial corrections. A copy of the ODCM is included in Attachment 10.2 of this report 8.3 Unavailability of REMP Milk Samples l
Due to the unavailability of three milk sampling locations within five kilometers of the plant, Broad Leaf sampling is performed in accordance with ODCM Table 5.8-1. Milk l
is collected, when available, from the control location and two identified sampling locations as indicated in Waterford 3 Offsite Dose Calculation Manual, Attachment 6.14.
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8.4 Report of Required Effluent instrument inoperability ODCM Specification 5.6.1.b and 5.6.2.b require reporting in the Annual Radioactive Effluent Release Report of why designated inoperable effluent monitoring instrumentation was not restored to operability within the time specified in the Action Statement.
During the reporting period, there were four cases when instrumentation was not restored to operability within the time specified. These cases are described in the following sections.
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8.4.1 Monitor
l Circulating Water Discharge (CWD) Liquid Radiation Monitor (PRM-IRE-1900)
Time Required by Specifications to Restore Operability:
i 30 Days l
Period of inoperability:
0255 on 02/13/1996 to 1435 on 03/28/1996 (44 Days,11 Hours,40 Minutes)
Cause of inoperability:
The CWD radiation monitor was declared inoperable at 0255 on 2/13/96 due to loss of sample flow, it appears that sediment from the circulating
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water system had clogged the sample lines. A Cl was written by i
Operations.
l Reason Operability Not Restored Within Allotted Time:
I&C maintenance performed several flushes to the system using installed l
flush lines. These flushes did not restore sample flow. A new flow meter was calibrated and installed which did not correct the problem. The sample lines (piping) were replaced by maintenance. There were some delays in getting parts and materials on-site which delayed the monitor being returned to service within 30 days.
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8.4.2 Monitor; l
l Circulating Water Discharge (CWD) Liquid Radiation Monitor (PRM-IRE-1900)
Time Required by Specifications to Restore Operability:
i 30 Days Period of inoperability:
1300 on 04/12/1996 to 0839 on 07/25/1996 (103 Days,19 Hours,39 Minutes)
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i Cause of Inoperability:
The CWD radiation monitor was declared inoperable at 1300 on 04/12/1996 due to electronic spiking problems. Monitor spiking problems had been noted in the past and an electronics modification was planned to reduce spiking problems related to electronic noise. A Cl was written by Operations.
Reason Operability Not Restored Within Allotted Time:
I&C maintenance installed the electronics modification on this radiation monitor between 7/15/96 and 7/25/96. The radiation monitor was l
technically declared out of service and the required ACTIONS implemented. In actual practice, the monitor was functional when a spiking problem was not in progress and questionable readings and alarms were investigated when identified. Operations preferred to keep the monitor l
declared out of service until the modifications to correct spiking were l
complete. There were some delays in getting parts and materials on-site j
which delayed the monitor being returned to service within 30 days.
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8.4.3 Monitor
Dry Cooling Tower Sump #2 (DCTS#2) Liquid Radiation Monitor (PRM-IRE-6776)
Time Required by Specifications to Restore Operability:
4 30 Days Period of inoperability:
1600 on 04/10/1996 to l
1948 on 07/23/1996 (104 Days,3 Hours,48 Minutes)
Cause of inoperability:
The DCTS#2 radiation monitor was declared inoperable at 1600 on 04/10/1996 due to electronic spiking problems. Monitor spiking problems had been noted in the past and an electronics modification was planned to reduce spiking problems related to electronic noise. A Cl was written by Operations.
Reason Operability Not Restored Within Allotted Time:
I&C maintenance installed the electronics modification on this radiation monitor between 7/19/96 and 7/23/96. The radiation monitor was technically declared out of service and the required ACTIONS implemented. In actual practice, the monitor was functional when a spiking problem was not in progress and questionable readings and alarms were investigated when identified. Operations preferred to keep the monitor declared out of service until the modifications to correct spiking were complete. There were some delays in getting parts and materials on-site which delayed the monitor being returned to service within 30 days.
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8.4.4 Monitor
Dry Cooling Tower Sump #1 (DCTS#1) Liquid Radiation Monitor (PRM-IRE-6775)
Time Required by Specifications to Restore Operability:
30 Days l
Period of inoperability:
1030 on 05/18/1996 to l
1331 on 08/12/1996
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(86 Days,3 Hours,1 Minute) l Cause of Inoperability:
i The DCTS#1 radiation monitor was declared inoperable at 1030 on 05/18/1996 due to electronic spiking problems. Monitor spiking problems had been noted in the past and an electronics modification was planned to reduce spiking problems related to electronic noise. A Cl was written by Operations.
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l Reason Operability Not Restored Within Allotted Time:
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l&C maintenance installed the electronics modification on this radiation monitor between 8/6/96 and 8/12/96. The radiation monitor was technically declared out of service and the required ACTIONS implemented. In actual practice, the monitor was functional when a spiking problem was not in progress and questionable readings and alarms were investigated when identified. Operations preferred to keep the monitor declared out of service until the modifications to correct spiking were complete. There were some delays in getting parts and materials on-site L
which delayed the monitor being returned to service within 30 days.
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l 8.5 Activity Released Via Secondary Pathways 8.5.1 The following secondary release paths were continuously l
monitored for radioactivity:
+ The Hot Machine Shop Exhaust (AH-35),
+ Decontamination Shop Exhaust (AH-34),
+ The RAB H&V Equipment Room Ventilation system Exhaust (E-41 A and E-41B); and
+ The Switchgear/ Cable Vault Area Ventilation System (AH-25).
Continuous sampling for these areas is maintained in order to demonstrate the operability of installed treatment systems and to verify integrity of i
l barriers separating primary and secondary ventilation systems. Sampling for these areas was limited to continuous particulate and iodine sampling
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and monthly noble gas grab sampling, The activity released via these secondary pathways resulted from routine operations and remained below significant levels.
8.6 Missed Effluent Samples:
No gaseous or liquid effluent samples were missed during this reporting period.
8.7-Major Changes to Radioactive Waste Systems During the repotting period, no Major Changes were made to any Radioactive Waste Systems.
8.8 Additional Information The most recent Reactor Coolant System E-Bar calculation was 0.814 MeV/ Disintegration from a sample obtained on December 23,1996. Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.
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9.0 TABLES 1
Batch Release Summary.
1A Annual Summation of all Releases by Quarter - All Airborne Effluents.
1B Annual Airborne Continuous Elevated and Ground Level Releases.
1C Semiannual Airborne Batch Elevated and Ground Level Releases.
l 2A Annual Summation of All Releases by Quarter - All Liquid Effluents.
j 2B Annual Liquid Continuous and Batch Releases.
3 Solid Waste Shipped Offsite for Disposal.
4 Joint Frequency Distribution of Meteorological Data.
5 Dose Calculation Results for 1996.
l 10.0 ATTACHMENTS I
10.1 Copy of Process Control Program (PCP) Procedure RW-001-210, Revision 7 (14 sheets) l 10.2 Copy of Offsite Dose Calculation Manual (ODCM) Procedure, UNT-005-014, Revision 5.
(157 sheets) l l
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TABLE 1 (1 c)f 2) l l
BATCH RELEASE
SUMMARY
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l Batch Release Summary information for 1996 Report Period.
Batch Release Summary Report Category
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Release Point All Type of Release Batch Liquid and Gaseous Period Start Time 01-jan-1996 00:00:00 Period End Time 2 31-dec-1996 23:59:59 I
Liquid Releases Number of Releases 138 Total Time for All Releases 1 37606.0 Minutes Maximum Time for a Release 322.0 Minutes Average Time for a Release 272.5 Minutes I
Minimum Time for a Release :
77.0 Minutes Average Stream Flow 799119.2 GPM Gaseous Releases Number of Releases 21 Total Time for All Releases :
3692.0 Minutes Maximum Time for a Release 4
643.0 Minutes Average Time for a Release 175.8 Minutes Minimum Time for a Release 5.0 Minutes l
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TABLE 1 (2 c)f 2)
BATCH RELEASE
SUMMARY
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Batch Release Summary information for 1996 by Quarter.
i Report Category
- Batch Release Summary Release Point
- All Type of Release
- Batch Liquid and Gaseous Period Start Time 01-jan-1996 00:00:00 Period End Time 31-dec-1996 23:59:59 i
Liquid Releases i
Qtr 1 Ocr 2 Otr 3 otr 4 Number of Releases 38 43 34 23 Total Time for All Releases 10490.0 11709.0 9229.0 6178.0 Minutes Maximum Time for a Release 307.u 322.0 305.0 322.0 Minutes Average Time for a Release 276.1 272.3 271.4 268.6 Minutes Minimum Time for a Release 244.0 77.0 228.0 154.0 Minutes Average Stream Flow i
743753.2 846124.2 828032.6 760848.7 GPM Gaseous Releases Otr 1 Otr 2 Otr 3 Qtr 4 Number of Releases
?
5 3
8 5
Total Time for All Releases e 667.0 539.0 1648.0 839.0 Minutes Maximum Time for a Release :
198.0 186.0 643.0 271.0 Minutes Average Time for a Release 133.4 179.3 206.0 167.8 Minutes Minimum Time for a Release :
.47.0 172.0 5.0 70.0 Minutes i
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TABLE 1 A (1 c)f 1)
ANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL AIRBORNE EFFLUENTS Gaseous Release Summary information for 1996 j
Report Category Summation of All Releases Type of Activity All Airborne Effluents Period Start Time 01-jan-1996 00:00:00 Period End Time 31-dec-1996 23:59:59 Est. Total Type of Ef fluent Units Qtt 1 Otr 2 Qtr 3 Otr 4 Error %
A.
Pission and Activation Cases
- 1. Total Release Curies 3.01e-01 2.59e+00 3.40e+01 4.33e+01 1.50e+01
- 2. Average Release Rate for Period uCi/sec 3.83e-02 3.29e-01 4.28e+00 5.44e+00 l
- 3. Percent of Applicable Limit n/a n/a n/a n/a l
B.
Radioiodines l
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- 1. Total Iodine-131 Curies 0.00e+00 0.00e+00 4.74e-07 0.00e+00 1.50e 01 l
- 2. Average Release Rate for Period uCi/sec 0.00e+00 0.00e+00 5.96e-00 0.00e400 1
- 3. Percent of Applicable Limit n/a n/a n/a n/a C. Particulates i
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- 1. Particulates (Half-lives > 8 Days) Curies 9.75e-07 1.11e-06 1.19e-06 1.90e-06 1.50e+01
- 2. Average Release Rate for Period uC1/sec 1.24e-07 1.41e-07 1.49e-07 2.39e-07
- 3. Percent of Applicable Limit n/a n/a n/a n/a
- 1. Gross Alpha Radioactivity Curies 3.27e-06 4.15e-06 6.65e-06 5.43e-06 1.50e+01 D. Tritium i
- 1. Total Release Curies 3.54e+01 7.16e+00 1.37e+01 3.37e+01 1.50e+01 l
- 2. Average Release Rate for Period uCi/sec 4.50e+00 9.10e-01 1.72e+00 4.24e+00
- 3. Percent of Applicable Limit n/a n/a n/a n/a I
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TABLE 1B j
(1 c)f 1)
ANNUAL AIRBORNE CONTINUOUS ELEVATED AND GROUND LEVEL RELEASES i
l Gaseous Release Summary information for 1996
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l Report Category Airborne Continuous Elevated and Ground Level Releases.
, Totals for Each Nuclide Released.
Type of Activity Fission Gases, Iodines, and Particulates Period Start Time : 01-jan-1996 00:00:00 Period End Time
- 31-oec-1996 23:59:59 i
Elevated Releases Ground Releases j
Nuclide Units Otr 1 Otr 2 Otr 3 Otr 4 Qtr 1 Otr 2 Otr 3 Otr 4 l
Fission and Activatio. Gases Ar-41 Cu '.es 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.62e+00 0.00e+00 Xe-133 C ries 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.48e-01 6.56e+00 3.04e+01 Xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.28e-01 1.29e+01 0.00e+00 1
Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.68e+00 2.81e+01 3.04e+01 1
Radiciodines 1
I-131 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.74e-07 0.00e+00 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.74e-07 0.00e+00 1
1 Particulates l
H-3 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.53e+01 7.03e+00 1.20e+01 3.33e+01 l
Mn-54 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.81e-08 3.53e-10 0.00e+00 0.00e+n0 Co-58 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+0u 1.72e-07 2.58e-08 7.71e-07 0.00e+00 Co-60 Curies 0.00e+00 0.00e+00 0.00e+00
'0e+00 4.41e-07 2.14e-06 0.00e+00 3.50e-07 Cs-137 Curies 0.00e+00 0.00e+00 0.00e+00 0.u0e+00 2.75e-07 5.80e-07 4.15e-07 1.55e-06 Ba-140 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.76e-07 0.00e+00 0.00e+00 Gralpha Curies 0.00e+t1 0.00e+00 0.00e+00 0.00e+00 3.27e-06 4.15e-06 6.65e-06 5.43e-06 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.53e+01 7.03e+00 1.20e+01 3.33e+01 l
I l
1 l
TABLE 1C (1 c)f 1) l ANNUAL AIRBORNE BATCH ELEVATED AND GROUND LEVEL RELEASES Gaseous Release Summary information for 1996 Report Category
. Airborne Batch Elevated and Ground Level Releases.
. Totals for Each Nuclide Released.
Type of Activity Fission Gases, lodines, and Particulates Period Start Time. 01-jan-1996 00:00:00 Period End Time 31-dec-1996 23:59:59 Elevated Releases Ground Releases Nuclide Units Qtr 1 Qtr 2 Otr 3 Otr 4 Otr 1 Otr 2 Otr 3 Otr 4 Fission and Activation Gases Ar-41 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.50e-01 1.55e-01 1.21e-01 2.86e-01 Kr-85 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.44e-01 0.00e+00 Kr-85m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 7.64e-04 Xe-131m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.66e-02 2.13e-01 Xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.45e-01 7.39e-01 4.94e+00 1.21e+01 Xe-133m Curles 0.00e+00 0.00ed30 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.65e-02 9.86e-02 Xe-135 Curies 0.00e+00 0.00e+00 0.00e.00 0.00e+00 6.26e-03 1.71e-02 9.68e-02 1.06e-01 Total for Period curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.01e-01 9.12e-01 5.90e+00 1.28e+01 Radiciodines None Particulates H-3 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.30e-01 1.26e-01 1.68e+00 3.42e-01 Total for Period Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.30e-01 1.26e-01 1.68e+00 3.42e-01 i
l 1
i l
t i
\\
i l
i
TABLE 2A (1 c>f 1)
ANNUAL SUMMATION OF ALL RELEASES BY QUARTER ALL LIQUID EFFLUENTS Liquid Release Summary information for 1996 Report Category e Summation of All Re. eases Type of Activity All Liquid Effluents Period Start Time 01-jan-1996 00:00:00 Period End Time 31-dec-1996 23:59:59 Est. Total Type of Effluent Units Otr 1 Qtr 2 Qtr 3 Qtr 4 Error %
A.
Fission and Activation Products
- 1. Total Release (Not Including Tritium, Gases, and Alpha Curies 1.98e-01 2.89e-01 2.98e-01 3.24e-02 1.50e+01
- 2. Average Diluted Concentration During Period uCi/sec 5,36e-10 6.89e-10 7.18e-10 8.48e-11
- 3. Percent of Applicable Limit n/a n/a n/a n/a B. Tritium
- 1. Total Release Curies 2.61e+01 1.60e+02 2.77e+02 5.45e+01 1.50e+01
- 2. Average Diluted Concentration During Period uCi/sec 7.07e-08 3.81e-07 6.68e-07 1.43e-07
- 3. Percent of Applicable Limit n/a n/a n/a n/a C. Dissolved and Entrained Gases
- 1. Total Release Curies 2.44e-03 5.03e-02 6.14e-02 2.22e-02 1.50e+01
- 2. Average Diluted Concentration During Period uCi/sec 6.60e-12 1.20e-10 1.40e-10 5.81e-11
- 3. Percent of Applicable Limit n/a n/a n/a n/a D. Gross Alpha Radioactivity
- 1. Total Release Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.50e+01 E. Waste Volume Released (Pre-Dilution) Liters 7.69e+06 9.18e+06 1.17e+07 1.04e+07 1.50e+01 j
F. Volume of Dilution Water Used Liters 3.69e+11 4.20e+11 4.15e+11 3.82e+11 1.50e+01
[
l TABLE 2B (1 c)f 1)
ANNUAL LIQUID CONTINUOUS AND BATCH RELEASES Liquid Pelease Summary information for 1996 Report Category
? Liquid Continuous and Batch Releases.
- Totals for Each Nuclide Peleased.
l Type of Activity All Radionuclides i
Period Start Time
- 01-jan-1996 00:00:00 Period End Time t 31-dec-1996 23:59:59 Continuous Releases Batch Releases Nuclide Units Otr 1 Otr 2 Qtr 3 Otr 4 Qtr 1 Qtr 2 Otr 3 Qtr 4 I
All Nuclides H-3 Curies 3.29e-02 5.68e-02 7.72e-02 3.81e-02 2.60e+01 1.60e+02 2.77e+02 5.44e+01 Na-24 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.11e-05 1.26e-04 2.13e-05 0.00e+00 Sc-46 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.71e-04 0.00e+00 0.00e+00 Cr-51 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.27e-03 5.15e-03 8.86e-03 1.48e-04 Mn-54 Curies 9.51e-07 2.23e-07 0.00e+00 0.00e+00 2.03e-03 7.65e-03 5.44e-03 1.16e-03 re-55 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.19e-01 8.54e-02 7.30e-03 2.92e-03 Fe-59 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 9.98e-05 2.92e-04 5.84e-04 0.00e+00 Co-57 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.49e-04 3.48e-05 1.77e-04 5.18e-05 Co-58 Curies 5.84e-06 0.00e+00 4.39e-07 1.37e-06 3.69e-02 2.91e-02 1.95e-01 1.82e-02 Co-60 Curies 1.20e-05 0.00e+00 0.00e+00 0.00e+00 6.41e-03 2.02e-02 2.24e-02 5.07e-03 Zn-65 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 3.63e-06 0.00e+00 j
Kr-85 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.06e-03 8.99e-03 1.42e-03 3r-89 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.37e-05 1.64e-04 0.00e+00 0.00e+00 Sr-90 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.37e-06 1.64e-05 0.00e+00 0.00e+00 Sr-92 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.54e-05 0.25e-05 1.11e-04 1.21e-05 Zr-95 Curies 2.82e-06 0.00e+00 0.00e+00 0.00e+00 4.57e-03 3.77e-02 9.31e-03 4.70e-04 Zr-97 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.03e-06 8.06e-05 0.00e+00 Nb-95 Curies 3.88e-06 0.00e+00 0.00e+00 0.00e+00 8.98e-03 7.70e-02 1.89e-02 1.12e-03 Nb-97 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.88e-05 3.35e-04 7.75e-05 9.98e-05 Ru-103 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.55e-05 0.00e+00 Ag-110m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.18e-04 4.01e-03 2.60e-03 2.21e-04 Sn-113 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.93e-04 1.92e-03 5.75e-04 1.61e-05 Sb-122 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.74e-04 0.00e+00 Sb-124 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 4.88e-04 3.30e-04 1.82e-03 4.04e-05 Sb-125 Curies 0.00e+00 1.88e-06 0.00e+00 0.00e+00 1.28e-02 1.36e-02 2.36e-02 2.36e-03 I-131 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 8.43e-04 7.15e-04 2.25e-05 5.57e-06 I-132 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0,00e+00 0.00e+00 1.35e-05 0.00e+00 1-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.44e-04 5.86e-04 3.18e-05 0.00e+00 1-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.72e-05 0.00e+00 0.00e+00 xe-131m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.04e-04 1.30e-03 2.51e-04 Xe-133 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.81e-03 4.68e-02 5.06e-02 2.02e-02 Xe-133m Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 1.90e-04 3.34e-04 2.96e-05 Xe-135 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.27e-04 6.9&e-04 1.61e-04 2.91e-04 Cs-134 Curies 2.03e-05 1.06e-05 1.21e-05 2.25e-06 1.51e-03 3.55e-04 1.03e-04 2.17e-04 Cs-137 Curies 3.82e-05 2.91e-05 3.09e-05 1.18e-05 1.97e-03 8 27e-04 8.19e-05 2.52e-04 La-140 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 5.37e-05 c.77e-05 2.78e-04 1.52e-05 Ce-141 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 J.00e+00 3.54e-05 0.00e+00 Ce-144 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 0.00e+00 2.63e-03 4.55e-04 0.00e+00 W-187 Curies 0.00e+00 0.00e+00 0.00e+00 0.00e+00 6.06e-05 0.00e+00 0.00e+00 0.00e+00 Total for Period Curles 3.30e-02 5.69e-02 7.73e-02 3.81e-02 2.62e+01 1.60e+02 2.70e+02 5.45e+01 i
i i
TABLE 3 (1 of 8)
.,~7SMMSTE SHlWE60FFSITE FO'R DISPOSAE 7
~
Lx-._. & _ _LD. U..._RiN..G__P_ER..IO_D_DF_IO1_ /._0_1/OS_T. H_ R_.O a
lhdividdilSilifsisiX Y ~T u_e.u-a._m aa <_a.um_i. ~
~'
' "Y'
~
.mmuuw.m ac. _ w 4.=a_..
_u. Ad
,;; Waste Type [Sourcey jil0Cl R6'if. (T pebfj
? Container [
W 3Wastep
,' Total {g.
ERROR l
' :9.a -. ~ i.
cw
~.~
t
~.
w,
.~c iProcessin
..a 3 (Waste 3 iContaineri.
Volume g
' ; Volume 1 o j Activity l.
i a
. r-
.a P.-..
l
~y 7
.s. Class V
,f(Ft3)y 1(M3);
((Curies)?
- g i
l (B)
A-U
x20 ft 1040 each, 58.9 2.68E-01 4 125 %
Non-Compacted Dry STP 2080 Total Activity Waste Shipped to SEG Corp for Volume Reduction.
(B)
A-U 8x8x20 ft 1040 each, 58.9 2.25E-01 4 125 %
i Non-Compacted Dry STP 2080 Total Activity Waste Shipped to SEG Corp for Volume Reduction.
(A)
A-U EL-210 202.1 5.723 3.47E+00 +
125%
Liquid Waste Management Poly-HIC Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
(A)
A-U EL-210 202.1 5.723 6.43E-01 +
125%
Liquid Waste Management Poly-HIC Resin Dewatered in a High Integrity Container (Bead i
Resin) Shipped for Burial.
A Activity determined by estimations l
0 Activity determined by measurements
l TABLE 3 (2 of 8) pjgar '~]s#06W5Te~isRIPF nDDFFslTEN, i
i dMDURING PERIOD OF..
R DisFpsE ~ ~
~ '
1 p# _.
m--
... - ~-.. ~.
.~
~..
1 m _ m_.__ _,,i_.___
_.01/0_1_/9._6_:TH__R_OU_G._H.~s_12._/3_1./9_6.:.m_x _,. J 1
..~p.m
~
- ~~r--e.w wwyn;m,ymy2my, n
(,- r
- y. ;
,v..,
ry.
,.:y,*
ndpg.
.,.,v.-~
w ividual Shipments (cont.[,y mp y~.m.m,'gm,eymy.~,yu. ~.u
. a m m a a x:.:.m =:.waa_a mm x
n ~.
- u. za=.m.aa _~a ww.:
w+.
l 1
i pWasteiType, Souh:e;b l10CFR61).: @ Type ofk (Containsr?
tWastei
? Total (
ERROR 4
pSyg - -
,t 4
met a t n::yy.
q~.
4 Volume ?
s 6%
W este,
Container S VVolumei' Mf)$(M3)c
%ffe; Processing'v - -
SActisityM a
. '. n:L 3 x
+?{
beQ. ;;+ 1eSj W(Ft3)>
f rW :-
av;L_.
$. dip 4 -
-JA>c%
7; Classy
(;g, M
2(Curies)v fM (A)
B EL-190 174.3 4.936 1.04E+02 +
25%
Resin Waste Management Poly-HIC Resin Dewatered in a High Integrity Container (Bead Resin) Shipped for Burial.
(A)
C EL-142 132.4 3.749 4.24E+01 r.
25%
Spent Cartridge Filters in a Poly-HIC High Integrity Container j
Shipped for Burial.
l l
l l
l l
l e Activity determined by estimations e Activity determined by measurements I
I
{
TABLE 3 I
(3 of 8) 4 1
IEE~"IsDOD W STElsHIPPED #FFSITE"FDR DISPUS CT ~ ~~l]
~
Mf"ODU.R_IN_s._P_8_R._I _D_l_D_Fl0N_0.1._/9..6.._?TH._R_ DUG _H,i_12_/3_1/.9._6
_i.
b d
- e
.. an J. +rmwefvwwwe- " * - * - -M
..M. - -
.nu. a.
au~xm e yprefe mauau ww.V 1S,. UM^ ARY. !BY"" J'- ~,AJO. R. WASTE'~*T. "YP.' E'Sx 1 '
t-mm cry-+v-fee;7: >1
- * - - - ~ * * - - ~
'-~r-v*--
~
wm*: n ina mir
-=a j
.u,+ -
-~~-
i
]
j (A)
Spend resins, Filter Sludges, Evaporator Bottoms, etc.
i j
(B)
Dry Compressible Waste, Contaminated Equipment, etc.
(C)
Irradiated Components, Control Rods, etc.
9 a
j (D)
Other.
i 1.,
7 t
eyw WhSTEl TYPE
- iWASTEE,
' TOTAL:
aERROR1 q:
^
- VOLUMEi
!A'CTNITY?
w
.(Cl)1
'(M3)
?
=1 i
4 (A) 20.10 1.51 E+02
-+ 25%
1 i
l (B) 117.81 4.94E-01
-+ 25%
4 i
)
i (C) 0.00 0.00E+00
-+ 25%
i 4
l l
(D) 0.00 0.00E+00
-+ 25%
4 I
i i.
TABLE 3 l
(4 of 8)
"ET~7SDO6VVAS_TifSHIPPEU'DF.FsiTEIFOR DiSPD$nC ~
R 1
e y, y i
uuea 7lD. URING..!. PERI.OD'OF 01/0_1/96._,TH_ROUG. H412/31/96. >.
l x-~-
1 i
t i
J
SUMMARY
J BY MAJOR. WASTE] TYPES (Cont'd)L 2
i
'RidIoE5fidis'6y MijdFWastiiTil_is7'?'u'!"_.c"a"",2muauna..sm& u_ _
" " " ~ ~ " ' ~ ~ " ~
w m_ um_ mmmm
_ _am.
ama j
}
I V: :4 ; {
G
!... ? :' l.,
.~.
.. ;;, < b....
,t
..?
,7 j
/NUCLlDE NAME1
' iCURIES
+ %LABUNDANCEi 6 WASTE-TYPE -
i,M n7 d
s
}
(A) i Co-58 3.49E+01 19.564 Fe-55 3.40E+01 19.050 Ni-63 2.46E+01 13.755 Cs-137 2.43E+01 13.633 Cs-134 2.00E+01 11.242 Co-60 1.23E+01 6.930 Ni-59 1.87E-01 0.105 Sr-90 1.23E-01 0.069 H-3 3.12E-02 0.017 Cm-242 4.32E-04 0.000 Pu-241 3.18E-04 0.000 Nb-94 3.39E-06 0.000 1-129 0.00E+00 0.000 Tc-99 0.00E+00 0.000 C-14 0.00E+00 0.000 TOTAL 1.51 E+02
_ _ _ _ _ _ _._. _ _ _ _ _.4 l
TABLE 3 (5 of 8) 4 F7FT"?sDC16W $TE sflIPPnd~DFFSITE NDR DiSPDs' F
,?
7
~
i E MDDRINGINERIODlDF O1/01N65NROUGHi12/flI961 7 *i I
i mm_ _m_._____
_ - _. _ _ ~ _...
. = -
d i
4 a
guW ?
SUMMARY
(BY; MAJOR: WASTE: TYPES l(Cont'd):
NiaT65GaldisWMijFrVissisV.ps?T!"f".S"3ET"W~?T~'.~"a.w?W~T:-.u~.~ww.~"T.u" j
w--
._ w.w uw
.w a
a-wa w
~c
.g q w' i';.
},.........,
<l :
's $.b!
.... N0:...
NWAS,TE TYP.EL
";NUCLIDE NAME:L LCURIESj1.
i%~ ABUNDANCE 4 s s v
n
+
.c r>
.s-6 I
,i,,
s, V
4 j
4 J
(B)
Co-58 6.40E-02 12.98 Co-60 5.67E-02 11.50 Cs-134 4.72E-02 9.57 Cs-137 4.42E-02 8.97 Fe-55 1.78E-01 36.19 Mn-54 2.24E-02 4.53 Ni-63 6.29E-02 12.75 Nb-95 2.56E-03 0.52 Zr-95 1.29E-02 2.62 Sn-113 4.79E-04 0.10 Ce-144 1.30E-03 0.26 TOTAL 4.93E-01
1 i
i 1
i TABLE 3 1
(6 of 8) l i
1 t
w a w m n m +r
- - -. STE SH.lPPEDIDFFSITETFDR' DISP.OSAL?
C(J :77 SOLID;WA..--...
.- - -..__3%. M_UR_IN_G_P_E_RI_'D_IOF41. _/0.1./
S
..^.
,,i u
i a
.m _.a 5
f I,
a
!SUMMAR%B.YiMAJOR WASTE TYPESi(Cont'd);
- C t
j
,-,~d.g....,,,,,,
-,_ o....-
~
m.,----
- tiyType,
,,~,y
... m e,m,
~ w -sp,~~,,
O !.
.~<,,,,.;.y.,4
,s.
,.,x w ionuc_lides by Major Was Ra
~,
w v
.1
--w-aaa:x.aa.w zu:au a a:w a m.-.au.maaa w..
.aa.x 4
l v
s.. _
jN ddDEN N;~ES
$0RlES) *
(%IBUNDANdE wz'*-
W,qu t
g,,
,e,g
{WdSTE N $$
^
l
? s
,w i
,, w
.9
, #, g,
w
. c u-l.
t l
(C) 4 1
N/A 0.00E+00 0.000 f
i 1
TOTAL 0.00E+00 i
i f
3 l
n t
i I
i t
1 i
i t
5 4
4 4
l
l TABLE 3 (7 c,f 8) gm7.?~75MNXstE sHIPPMMF$iTEFDR DiSPDSXF.'.a
~
I,l T
T w
w..
_.X;, ;.
m3.D__UR_IN_G. PER_IO._D;O_F. 01_/01/96.T_H_R_O_U__G_H 112_/31_/96__1....
A
- ~
~
v-
. a
~ -
r 1
SUMMARY
BY MA"JOR WASTE (TYPES (Cont'd)j.
a g3 Scq-e. tyie
.ro fe,en-a gr -~t<w up%vap 7d. 'e,.e.rstb. ng.-
---u_y Major Was, caw + e7cee*>.-+p te Type
~^
p7.t y',a tg #wrwyw= +p.e3 77 n eperg-y g ew-2:,3 g
,,wy *v.
+t 334 esr y.._p i
Radionucli s
.. ' ~ M.
._u-.
w a=x.x:wkw...-a a :.na.m w : a.;~ a m d j
i,'
.) 6
.i..,,,.[..
+
m
.p,
).
..i....
.r--
5
.,.y..
e WASTE TYPE 1 TN, UCLIDE NAMEL... '. JCURIES!
H%' ABUNDANCE:
y
.e m,
y.1; ff q;,
4,
-- m
- ) k
- y/
A
's f
s (D)
N/A 0.00E+00 0.000 TOTAL 0.00E+00
TABLE 3 (8 of 8) 7,,
F m
iSOLID WASTEiSHIPPED OFFSITE FOR DISPOSAL 9
k
~.. ?DURING PER.. id.D OF 01/01/96:TH_RO~UG._ H_.1_2/._3. 1. /9.6,. i w
- - ~ - - -
l t
...-~.n
..nn,
,n
,p,.,.
T
. Solid: Waste Ds,spos,it, ion :. "
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n.,,,,
.,,,n awu n. a w.. -.a.,.a.wm.an.u.a.-u u a_' a: >.' x;aa.._,.
a.
l a.
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4
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M iSHIPMENTS:
+hTRANSPORTATION. )
N-4
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v r
5 l
4 Truck Bamwell, SC l
2 Truck Oak Ridge, TN 1
lifaliistsd'. Fuel Shii,rrients (Di506 sit'_o'n'T_i ~ "".._. T_m. ]
i
)
..ms _...
m.
m.
.t.
um _mm...m a NUMB.ER OF-1.
tDESTIN, ATION- -
< MODE:OFe e a
t l
'flSHIPMENTS) #
1;TRANSRORTATION?
i *. '.
~ "-
m......
m i
NONE N/A N/A l
l 1
1 1
I I
l i
.-.,~
.~
. ~ - ~ _ - -
.. _. -. ~..
- -. -. _... - ~.. - -
. ~
TABLE 4 (1 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA r
i l
i i Joint f requency distribution of wind speed and direction in hours 01-01-96 00:00to 12-31-96 23:59 Pasquill Class A I I
I I
Wind speed (M/S) at 10-m Level l
l Wind I
(Direction.22 _.50.51 _.75.76-1.0 1.1 _1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1-13 13.1-18.0 >18.0 Total I
l.......__...__
____...._..__.....____..........__....l l
N 0
0 0
0 4
0 5
12 7
0 0
0 20 i
i NNE O
O O
O O
3 7
6 0
0 0
0 16 l
l f
NE O
O O
O O
8 46 13 0
0 0
0 67 i
l l
ENE O
O O
O O
1 6
1 0
0 0
0 8
I I
E O
5 0
0 0
0 0
1 0
0 0
0 1
I I
ESE O
O O
O O
O 2
1 0
0 0
0 3
i I
i SE O
O O
O O
1 9
2 0
0 0
0 12 I
I SSE O
O O
O 1
2 27 12 2
0 0
0 44 l
l S
0 0
0 0
1 2
31 8
2 0
0 0
44 1
1 Ssw 0
0 0
1 0
3 6
6 1
0 0
0 17 i
j 1
SW 0
0 0
0 0
4 23 15 1
0 0
9 43 l
l WSW 0
0 0
0 0
1 3
4 0
0 0
0 8
i i
W 0
0 0
0 0
0 3
0 0
0 0
0 3
l l
WNW 0
0 0
0 0
1 3
2 1
0 0
0 7
i i
NW 0
0 0
0 0
0 2
12 5
0 0
0 19 l
1 NNW 0
0 0
0 0
5 7
18 8
0 0
0 38 l
l___.__________..
_.__.._.l l
8 Total 0
0 0
1 6
31 180 113 27 0
0 0
358 i
i l
I
(
l Number of calms for A
Stability:
0 l
I I
i l
l i
i l
l l
l l
l Joint frequency distribution of wind speed and direction in hours 01-01-96 00:00to 12-31-96 23:59 Pasquill Class B l I
i
[
l W i ne' Speed (M/S) at 10-m Level I
i Wind i
IDirection.22.50.51.75.76-1.0 1,1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1-13 13.1 _18.0 >18.0 Total I
g.__................-
_____...__.............I l
N O
O O
O 3
14 7
9 2
0 0
0 36 I
l NNE O
O O
O 4
4 2
4 0
0 0
0 14 l
l NE O
O O
1 3
19 37 7
0 0
0 0
67 l
1 ENE O
O O
O O
3 6
4 0
0 0
0 13 1
1 E
O O
O O
O O
1 0
0 0
0 0
1 l
l l
ESE O
O O
O O
O 2
0 0
0 0
0 2
I I
I S2 0
0 0
0 0
6 10 6
5 0
0 0
27 i
i SSE O
O O
1 0
5 21 1.2 4
0 0
0 43 i
i S
0 0
0 1
0 9
17 14 4
0 0
0 45 I
I SSW 0
0 0
1 2
8 7
6 0
0 0
0 24 l
l SW 0
0 0
0 4
P 24 10 1
0 0
0 47 l
j i
WSW 0
0 0
0 0
6 6
2 0
0 0
0 14 l
I W
0 0
0 0
2 6
6 0
0 0
0 0
14 i
l WNW 0
0 0
1 3
3 6
1 0
0 0
0 14 i
l NW 0
0 0
0 2
5 17 2
0 0
0 0
26 l
l NNW 0
0 0
0 1
5 9
10 4
0 0
0 29 l
l.............
.....)
i Total 0
0 0
5 24 101 178 87 21 0
0 0
416 I
I I
l l
Number of calms for B
Stability:
0 l
l 1
.I I
i
?
1 l
l TABLE 4 (2 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA 1
1 1
I I Joint frequency distribution of wind speed and direction in hours 01-01 96 00:00to 12-31 96 23:59 Pasquill Class C l l
l l
Wind Speed (M/S) at 10-m Level I
i i
Wind I
(
IDirection.22.50.51.75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 1.1-10 10.1-13 13.1-10.0 >18.0 Total I
i..__......... __..................___......._............_____....._.__...... ___.______.............. _____........;
l l
N O
O O
1 4
17 11 8
2 0
0 0
43 l
l l
NNE O
O O
O 3
9 3
3 1
0 0
0 19 l
l 1
NE O
O O
2 6
27 47 2
0 0
0 0
84 I
l ENE O
O O
3 1
4 13 6
0 0
0 0
27 l
i l
i E
O O
O O
O 2
1 2
0 0
0 0
5 I
(
)
ESE O
O O
O O
1 7
5 0
0 0
0 13 l
l l
SE O
O O
O 1
8 19 8
1 0
0 0
37 l
l SSE O
O O
4 3
16 29 18 0
0 0
0 70 i
[
l S
0 0
0 2
0 20 27 18 7
0 0
0 74 l
l l
SSW 0
0 0
1 4
9 14 14 4
0 0
0 46 l
l SW 0
0 0
0 3
12 22 7
0 0
0 0
44 i
l WSW 0
0 0
2 8
16 13 0
0 0
0 0
39 i
i W
0 0
0 2
5 18 7
0 0
0 0
0 32 l
l WNW 0
0 0
1 6
11 11 0
0 0
0 0
29 1
1 NW 0
0 0
1 3
3 8
2 1
0 0
0 18 I
I NNW 0
0 0
1 5
0 14 6
1 0
0 0
35 1
g..............................
___..............____.---.._.._.....___............I l
Total 0
0 0
20 52 181 246 99 17 0
0 0
615 I
i 1
1 Number of caltas for C Stability 0
l I
l l
I I
I I Joint f requency distribution of wind speed and direction in hours 01-01 96 00:00to 12-31-96 23:59 Pasquill Class D 1 1
I I
Wind freed IM/S) at 10-m Level l
l Wind i
IDirection.22.50.51.75.76-1.0 1.1 _1.5 1.6-2.0 2.1-3.0 3.1 5.0 5.1-7.0 7.1-10 10.1 13 13.1-10.0 >18.0 Total l
l_.....___....__............__..______ __........_....._.___.........._....._................... __............. __.;
l l
N O
2 4
8 28 48 52 102 39 0
0 0
283 I
i i
NNE O
O 1
E 20 33 50 36 9
0 0
0 155 l
l NE O
O 2
12 20 81 118 40 9
0 0
0 290 l
l i
ENE O
O O
6 9
28 68
'38 30 0
0 0
179 1
i E
O O
2 0
6 11 25 23 3
0 0
0 70 l
I ESE O
0 1
2 7
11 48 25 1
0 0
0 95 I
l SE O
1 2
7 10 16 70 44 5
0 0
0 163 1
i SSE O
1 2
5 9
53 141 62 4
0 0
0 277 1
1 I
S 0
0 3
6 12 53 114 69 17 3
0 0
277 1
I SSW 0
0 1
11 16 27 58 51 15 1
0 0
180 I
i i
SW 0
1 2
3 14 24 66 17 3
0 0
0 130 i
i i
WSW 0
0 2
13 16 38
- l 10 2
C 0
0 112 l
l W
0 0
1 12 19 30 21 5
1 0
0 0
89 1
t WNW 0
1 1
8 9
16 33 1
3 0
0 0
72 1
I NW 0
0 1
7 7
13 39 19 3
0 0
0 89 I
I NNW 0
0 1
12 13 34 74 55 34 0
0 0
223 I
g............._..........._......._.._...__
......_....................--_I I
Total 0
6 26 118 223 516 1016 597 178 4
0 0
2684 I
I I
I Number of calms for D
Stability:
0 I
I I
i 1
TABLE 4 1
(3 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA 4
'l l
I I
1 Joint f requency distrioution of wind speed and direction in hours 01-01-96 00:00to 12-31-96 23:59 Pasquill Class E I l
I l
Wind Speed (M/S) at 10-m Level I
i I
Wind l
l l Direction.22.50.bl.75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1-13 13.1-18.0 >18.0 Total I
l---------------------------------~~--~~---------~~--------~~--------------~~------------
~~~~--------------l l
N O
O 2
13 12 38 90 19 4
0 0
0 17e i
I NNE O
4 3
13 18 52 46 18 2
0 0
0 156 1
i NE O
O 2
16 21 90 112 16 9
0 0
0 266 l
l i
ENE O
3 5
1 20 45 54 1
3 0
0 0
130 l
l E
O 1
2 7
8 d'
50 0
0 0
0 0
114 l
1 ESE 0
2 2
13 3
61 1
0 0
0 0
104 l
l l
SE O
1 4
14 15 47 85 17 0
0 0
0 183 l
l SSE O
O 5
19 58 179 65 11 0
0 0
0 337 1
l S
0 0
7 27 49 104 81 7
2 0
0 0
277 l
l SSW 1
5 11 26 25 52 64 4
1 0
0 0
189 l
l SW 2
5 6
23 24 53 38 5
0 0
0 0
156 l
l WSW 0
6 8
31 22 31 10 2
0 0
0 0
110 I
W 1
2 7
31 23 19 0
0 0
0 0
0 91 l
t WNW 0
2 5
20 18 10 6
1 0
0 0
0 70 1
1 NW 0
1 5
12 16 38 15 2
0 0
0 0
89 I
(
NNW 0
2 3
8 13 34 56 12 3
0 0
0 131 l
l___________._.___
....__...__........._.......__............___.___...._......_......__.._._....l l
Total 4
34 77 280 345 868 841 116 24 0
0 0
2589 l
l l
l Number of calms for E
Stability:
0 I
I I
I I
i I
l Joint frequency distribution of wind speed and direction in hours 01-01-96 00:00to 12-31-96 23:59 Pasquill Class F l i
l I
1 Wind Speed (M/S) at 10-m Level l
I Wir.d l
l Direction.22.50.51.75.76-1.0 1.1-1.5 1.6-2.0 2.1-3.0 3.1-5.0 5.1-7.0 7.1-10 10.1-13 13.1-18.0 >18.0 Total I
l_.___..
._......I l
N 1
4 6
12 5
13 6
0 0
0 0
0 47 i
l NNE 1
4 7
11 8
9 1
0 0
0 0
0 41 I
t NE 2
3 6
13 11 30 5
0 0
0 0
0 70 l
I ENE O
2 7
10 7
14 3
0 0
0 0
0 43 I
I E
O 2
3 6
1 1
1 0
0 0
0 0
14 1
1 ESE 1
3 4
3 0
4 0
2 0
0 0
0 17 l
l SE 1
11 7
14 7
24 3
0 0
0 0
0 67 l
l SSE 1
7 10 27 60 49 2
0 0
0 0
0 156 i
l S
1 7
32 72 55 33 0
0 0
0 0
0 200 t
i SSW 1
10 31 70 40 11 4
0 0
0 0
0 167 i
l SW 3
18 25 37 13 11 1
0 0
0 0
0 108 I
I WSW 0
11 26 73 9
3 0
0 0
0 0
0 122 I
I W
1 10 28 46 13 1
0 0
0 0
0 0
99 l
l WNW 1
7 10 15 12 7
0 0
0 0
0 0
52 l
l NW 1
6 10 7
6 7
1 0
0 0
0 0
38 I
l NNW 2
3 3
9 2
5 3
0 0
0 0
0 27 I
g_.........._......_...........________................._.....................____......________
._..l t
Total 17 108 215 425 249 222 30 2
0 0
0 0
1268 i
i l
I Number of calms for F
Stability:
0 I
I l
i
. - - ~.
.. - ~..
l l
l l
TABLE 4 (4 of 4)
JOINT FREQUENCY DISTRIBUTION OF METEOROLOGICAL DATA l
I
(
l I
i l Joint frequency distribution of wind speed and direction in hours 01-01-96 00:00to 12-31 96 23:59 Pasquill Class G i l
1 l
Wind Speed (M/S) at 10-m Level I
l Wind i
22.50.51 _.75.76-1.0 1.1 _1.5 1.6-2.0 2.1 _3.0 3.1-5.0 5.1-7.0 7.1 _10 10.1-13 13.1-18.0 >19.0 l Direction.
Total i
l_.............__..... ___......___.__ ___._...__...__........._.____....___. ____.. ___..___......____......___.i i
N 4
6 4
4 1
0 0
0 0
0 0
0 19 I
I NNE 1
3 6
1 1
1 0
0 0
0 0
0 13 l
l NE 1
3 5
1 0
2 0
0 0
0 0
0 12 1
i ENE O
3 2
2 0
0 0
0 0
0 0
0 7
l l
E 1
1 3
1 0
0 0
0 0
0 0
0 6
i l
ESE 1
2 1
1 1
0 0
0 0
0 0
0 6
l 1
1 SE 2
6 6
5 6
4 0
0 0
0 0
0 29 l
1 I
l SSE 1
8 4
21 16 9
0 0
0 0
0 0
65 I
i i
S 8
11 23 48 25 6
0 0
0 0
0 0
121 l
l SSW 4
20 40 76 28 3
0 0
0 0
0 0
171 l
1 SW 3
20 46 44 8
0 0
0 0
0 0
0 121 1
I WSW 6
37 42 25 0
0 0
0 0
0 0
0 110 I
l W
12 23 26 15 3
0 0
0 0
0 0
0 79 I
l WNW 7
11 7
15 3
0 0
0 0
0 0
0 45 l
l NW 1
13 7
2 1
1 0
0 0
0 0
0 25 i
1 NNW 3
6 8
4 0
0 0
0 0
0 0
0 21 I
l____.___....__.__................__..........
_____________...____l l
Total 55 175 230 271 93 26 0
0 0
0 0
0 850 l
i l
l Number of calms for G
Stabilityt 4
l i
I t
I Total valid hours for all stabilities -
8784 Total invalid hours for all stab 111 ties =
0 l
L I
a 1
l I
l TABLE 5 (1 c>f 5!)
1 DOSE CALCULATION RESULTS FOR 1996 l
l l
DOSES DUE TO GASEOUS RADIOACTIVE EFFLUENTS I
Doses due to Noble Gases (mrad or mrem)
I i
organ Qtr 1 Qtr 2 Otr 3 Qtr 4 Year Total Total-body 7.8673e-04 1.8372e-03 5.9473e-02 8.7206e-03 7.0817e-02 Skin 1.1764e-03 3.5045e-03 9.9032e-02 1.9371e-02 1.2308e-01 Air Beta 3.7605e-04 2.3487e-03 4.2296e-02 2.6404e-02 7.1425e-02 Air Gamma 8.3134e-04 1.9817e-03 6.2975e-02 1.0247e-02 7.6035e-02 Doses due to Radioiodines/Particulates/ Tritium (mrem)
Age Group Adult Organ Qtr 1 Qtr 2 Qtr 3 Qtr 4 Year Total Bone 9.8351e-06 8.9274e-06 6.3485e-06 2.7164e-05 5.2275e-05 Liver 3.7049e-02 7.4949e-03 1.4343e-02 3.5244e-02 9.4131e-02 Total-body 3.7048e-02 7.4926e-03 1.4341e-02 3.5238e-02 9.4120e-02 Thyroid 3.7046e-02 7.4882e-03 1.4390e-02 3.5226e-02 9.4150e-02 Kidney 3.7047e-02 7.4905e-03 1.4340e-02 3.5232e-02 9.4110e-02 Lung 3.7047e-02 7.4891e-03 1.4333e-02 3.5229e-02 9.4104e-02 41-111 3.7047e-02 7.4885e-03 1.4339e-02 3.5227e-02 9.4102e-02 3*4a 8.8426e-06 4.6010e-06 S.2166e-06 1.6559e-05 3.3219e-05 Age G rou',s : Teen Orgar Qtr 1 Otr 2 Otr 3 Otr 4 Year Total Bot te 1.1465e-05 1.2430e-05 8.8798e-06 3.6364e-05 6.9138e-05 Liter 4.1984e-02 8.4962e-03 1.6256e-02 3.9946e-02 1.0668e-01 Tottl-body 4.1981e-02 8.4890e-03 1.6250e-02 3.9927e-02 1.0665e-01 Thy-old 4.1979e-02 8.4850e-03 1.6321e-02 3.9916e-02 1.0670e-01 Kids.ey 4.1981e-02 8.4888e-03 1.6251e-02 3.9926e-02 1.0665e-01 Lun; 4.1981e-02 8.4868e-03 1.6249e-02 3.9921e-02 1.0664e-01 GI -111 4.1980e-02 8.4854e-03 1.6248e-02 3.9917e-02 1.0663e-01 5xin 8.8426e-06 4.6010e-06 3.2166e-06 1.6559e-05 3.3219e-05 Age Group 1 Child organ Otr 1 Otr 2 Qtr 3 Qtr 4 Year Total Bone 1.6879e-05 2.4092e-05 1.7300e-05 6.6931e-05 1.2520e-04 Liver 5.7981e-02 1.1736e-02 2.2451e-02 5.5171e-02 1.4734e-01 Total-body 5.7974e-02 1.1720e-02 2.2440e-02 5.5128e-02 1.4726e-01 Thyroid 5.7972e-02 1.1717e-02 2.2577e-02 5.5121e-02 1.4739e-01 Kidney 5.7975e-02 1.1723e-02 2.2443e-02 5.5137e-02 1.4728e-01 Lung 5.7974e-02 1.1719e-02 2.2439e-02 5.5127e-02 1.4726e-01 G1-111 5.7973e-02 1.1717e-02 2.2438e-02 5.5121e-02 1.4725e-01 Skin 8.8426e-06 4.6010e-06 3.2166e-06 1.6559e-05 3.3219e-05 l
Age Group : Infant organ Qtr 1 Qtr 2 Qtr 3 Otr 4 Year Total Bone 1.6079e-05 2.2330e-05 1.6453e-05 6.2411e-05 1.1727e-04 Liver 2.6211e-02 5.3183e-03 1.0157e-02 2.4973e-02 6.6660e-02 Total-body 2.6202e-02 5.2984e-03 1.0142e-2.4921e-02 6.6564e-02
,t Thyroid 2.6201e-02 5.2969e-03 1.0443e-;
2.4916e-02 6.6858e-02 Kidney 2.6204e-02 5.3026e-03 1.0146e-02 2.4932e-02 6.6584e-02 Lung 2.6203e-02 5.2994e-03 1.0143e-02 2.4923e-02 6.6568e-02 Gi-111 2.6202e-02 5.2970e-03 1.0141e-02 2.4917e-02 6.6556e-02 Skin 8.8426e-06 4.6010e-06 3.2166e-06 1.6559e-05 3.3219e-05 i
1
TABLE 5 (2 of 2)
DOSE CALCULATION RESULTS FOR 1996 DOSES DUE TO LIQUID RADIOACTIVE EFFLUENTS Liquid Effluent Dose Totals Cumulative Dose Information for 1996 (mrem)
Age Group Adult Organ Otr 1 Qtr 2 Otr 3 Otr 4 Year Total Bone 2.7132e-01 3.8542e-01 1.9720e-01 6.6952e-02 7.2089e-01 i
Liver 4.5472e-01 2.9983e-01 3.2334e-01 1.0453e-01 1.1824e+00 Total-body 3.2976e-01 2.1382e-01 2.3210e-01 7.3277e-02 8.4896e-01 l
Thyroid 1.2383e-03 5.1200e-03 6.6914e-03 3.8710e-03 1.8921e-02 Kidney 1.5309e-01 1.0335e-01 1.1237e-01 3.7690e-02 4.0650e-01 Lung 5.2946e-02 3.7677e-02 4.1798e-02 1.5110e-02 1.4753e-01 l
Gi-111 1.5734e-02 1.8777e-02 1.7778e-02 6.3540e-03 5.8643e-02 l
I
}
4 1
i 1
i i
i 1
l 1
a 1
i ii l
ATTACHMENT 10.1 i
i j
Copy of PROCESS CONTROL PROGRAM (PCP)
PROCEDURE RW-001-210 Revision 7 (14 sheets)
..