ML20138B500
| ML20138B500 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1996 |
| From: | Curtis J, Floyd E, Kay D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20138B498 | List: |
| References | |
| NUDOCS 9704290190 | |
| Download: ML20138B500 (38) | |
Text
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l COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
January 1, 1996 -
December 31, 1996 l
l Prepared By: )y1 Date: k'2- 97 E .V T. Floyd Radiation Protection Technician Reviewed By: OW 44 b. 'l-3-97
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Date:
O D. C. l@y Radiation Protection Supervisor Approved By: ) kt Date: Y/8[97
( J. R. Curtis Radiation Protection Manager 9704290190 970424 PDR ADOCK 05000445 R PDR
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l TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS l
1.0 INTRODUCTION
1.1 Executive Summary 2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Effluent Concentration Limits 2.3 Measurements and Approximations of Total Radioactivity 2.4 Batch Releases 2.5 Abnormal Releases 3.O GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 SOLID WASTES -
6.O RELATED INFORMATION 6.1 Operability of Liquid and Gaseous Monitoring Instrumentation 6.2 Changes to the Offsite Dose Calculation Manual 6.3 New Locations for Dose Calculations or Environmental Monitoring 6.4 Liquid Holdup and Gas Storage Tanks l 6.5 Noncompliance with Radiological Effluent Control Requirements 6.6 Resin Releases to the LVW Pond l
l 6.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment l Systems 6.8 Meteorological Monitoring Program 6.9 Assessment of Doses i
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l TABLE OF CONTENTS 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary I
7.2 Abnormal Batch Liquid and Gaseous Release Summary 7.3 Gaseous Effluents--Summation of All Releases 7.4 Gaseous Effluents--Ground Level Releases ,
7.5 Liquid Effluents--Summation of All Releases 7.6 Liquid Effluents 7.7 Doses From Liquid Effluents 1
7.8 Doses From Gaseous Effluents; Noble Gas Air Dose l 7.9 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Adult Age Group 7.10 Doses From Gaseous Effluents; Iodines, Particulates and
! Tritium, Teen Age Group 7.11 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Child Age Group ,
I l 7.12 Doses From Gaseous Effluents; Iodines, Particulates and I
Tritium, Infant Age Group ]
7.13 Solid Waste and Irradiated Fuel Shipments j l
l 8.0 ATTACIDENTS l
l 8.1 Offsite Dose Calculation Manual For TU Electric Comanche Peak Steam Electric Station Units 1 and 2, Revision 14
! 8.2 Joint Frequency Tables for 1996 1
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ACRONYMS AND ABBREVIATIONS CFR Code of Federal Regulations CPSES Comanche Peak Steam Electric Station ECL Effluent Concentration Limit LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste ODCM Offsite Dose Calculation Manual PET Primary Effluent Tanks REC Radiological Effluent Control SORC Station Operations Review Committee WMT Waste Monitor Tanks WWHT Waste Water Holdup Tanks l
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1.0 INTRODUCTION
This Annual Radioactive Effluent Release Report, for Comanche Peak Steam Electric Station Unit 1 and Unit 2, is submitted as required by Technical Specification 6.9.1.4 and Offsite Dose l
Calculation Manual (ODCM) Administrative Control 6.9.1.4 for the period January 1, 1996, through December 31, 1996. ,
1.1 Executive Summary l
l The radioactive effluent monitoring program for the year 1996 was conducted as described in the following report.
l The results of the monitoring program indicate the continued effort to maintain the release of radioactive effluents to the environment as low as reasonably achievable.
The total gaseous fission and activation activity
- released for 1996 was 25.18 curies. This is a decrease
! from the 1995 total of 28.32 curies and is due mainly to the planned release of the contents of three waste gas t decay tanks, pressurizer steam space releases and the cyclic release of noble gases detected on some of the primary plant ventilation stack samples. The total represents the second lowest total since startup of Unit 1.
Dose due to gaseous activity released increased to l 6.32E-2 mrem for 1996 from the 1995 dose of 3.25E-2 mrem.
l The increase was expected due to the planned waste gas decay tank releases and the noble gases from the stacks.
l The dose represents 2.11E-1% of the allowable limit.
Total activity (excluding tritium) released in 1996 in liquid effluents was 2.00E-1 curies. This is the second'
, lowest total activity since startup of Unit 1.
l Minimizing the introduction of water into the radwaste l processing system and reprocessing and treatment of water l continues to improve.
l l The total tritium activity released in 1996 in liquid I
effluents was 986 curies. This total is up from 1995's total of 840 curies.
The calculated whole body dose due to liquid effluents
! released in 1996 was 7.98E-2 mrem, up from 1995's dose of 7.65E-2 mrem whole body. The 1996 dose represents 1.33%
of the allowable limit.
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l During 1996, CPSES conducted three planned releases from the waste gas decay tanks. The contents of the three l tanks were released contributing 1.69 curies to the total I gaseous activity of 25.18 curies.
Liquid effluents released to Squaw Creek Reservoir t contributed to the concentration of tritium found in l Squaw Creek environmental water samples. During 1996, the tritium concentration in the reservoir peaked at 13,000 pCi/l for the second quarter and has decreased to 11,000 pCi/l based on fourth quarter samples. These levels are below reportable levels.
The CPSES meteorological system achievt.d a 93.5%
recoverable data rate for the joint frequency parameters required by Regulatory Guide 1.23 of wind speed, wind direction and delta temperature. All other parameters achieved a >90% recoverable data rate also.
There was one reportable event during 1996. During the pre-release permitting process a containment vent was compiled using the wrong chemistry gamma spectrum. The number used to identify the gamma spectrum was imprcperly entered into the pre-release calculation and resulted in improper radiological monitor setpoints. The improper setpoints were more conservative than would have been calculated if the proper spectrum had been used.
Therefore, the containment vent was monitored as required 1 and would have actuated alarms on the radiological l monitors providing an earlier indication of problems if l they had occurred. j During 1996 there were no Technical Specification /ODCM effluent radiation monitors out of service for >30 days.
There was considerable effort made to eliminate electrical noise problems, add updated firmwear and add smoothing algorithms to reduce spiking.
Revision 13 and 14 were made to the ODCM during 1996.
Revision 13 became effective on February 14, 1996, and )
Revision 14 became effective on October 1, 1996, i Revision 13 changed the requirements for the channel operational testing for the turbine building sump monitors and the auxiliary building sump monitor due to the change in monitor types from "inline" to " adjacent to line" monitors. Revision 14 added a new potentially radioactive liquid pathway to the waste water management system due to temporary systems (S/G cleaning) and the batch sampling requirements for the release of these j liquids. Revision 14 also provides clarification for the
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radiological sample analysis frequencies listed in the ODCM Table 3.12-1. No change was required in the environmental program due to this clarification.
For 1996, the total volume of buried solid radwaste was 52.2 cubic meters, up from 14.8 cubic meters in 1995, mainly due to a two-unit outage year in 1996, and disposal of waste which had been placed in interim storage while the Barnwell disposal site was closed from July 1994 to July 1995. The total buried activity in 1996 was 1620 curies buried. The majority of buried solid waste volume comes from spent resins and filters at 33.2 cubic meters. Also, spent resins and filters were responsible for >99% of all the total activity buried.
Overall, the radioactive effluent monitoring program has been conducted in an appropriate manner to ensure the activity released and associated dose to the public has been maintained as low as reasonably achievable.
Information pertaining to the following areas is included in this report:
- A summary of the quantities of radic active liquid and gaseous effluents released from Unit 1 and Unit 2 during the reporting period in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.
- A summary of solid waste shipped from Unit 1 and Unit 2 l
in the format shown in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974, supplemented with three additional categories: class of waste (per 10CFR61), type of container (Strong Tight, HIC) and shipped and buried volumes and curies.
- An explanation of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days.
- A listing of new location for dose calculations and/or environmental monitorin~ identified by the Land Use Census.
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- A description of the events leading to liquid holdup l tanks or gas storage tanks exceeding Technical Specification limits.
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I e A list and description of abnormal releases of j radioactive material from the site to unrestricted areas. 1 I
o A description of secondary resin releases to the LVW I Pond.
1 e A description of major changes to radioactive waste i treatment systems (liquid, gaseous and solid) . i i
e An assessment of radiation doses due to the radioactive .
- liquid and gaseous effluents released from CPSES Unit 1 l l and Unit 2 in 1996.. '
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l e An assessment of radiation doses to the likely, most ,
exposed MCiBER OF THE PUBLIC from CPSES Unit 1 and Unit 2 releases and other nearby uranium fuel cycle sources, i including doses from primary effluent pathways and direct !
radiation, for the reporting period, to show conformance ;
with 40 CFR 190, " Environmental Radiation Protection Standards for Nuclear Power Operation."
e An assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the Site Boundary.
2.0 SUPPLEMENTAL _INFORMATION 2.1 Regulatory _ Limits The ODCM Radiological Effluent Control limits applicable to the release of radioactive material in liquid and gaseous effluents are described in the following sections.
t 2.1.1 Eission_and_ Activation Gases _(Noble _. Gases).
I The dose rate due to radioactive materials 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 whole body and less than or equal to 3000 mrems/yr to the skin, j i
The air dose due to noble gases released in i gaseous effluents, from each unit, to areas at and beyond the site bound 4 y shall be limited i' to the following:
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- a. During any calendar quarter: Less than l or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for ;
l beta radiation, and i
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- b. During any calendar year: Less than or 1 equal to 10 mrads for gamma radiation and i less than or equal to 20 mrads for beta >
radiation. ;
1 l 2.1.2 lodine-131,.. Iodine-133, Tritium ___and l Radioactive _ Material _in_ Particulate _ Form ;
The dose rate due to iodine-131, iodine-133,
- tritium and all radionuclides in particulate ;
l form with half lives greater than 8 days, i released in gaseous effluents from the site to l l areas at and beyond the site boundary, shall ;
be limited to less than or equal to 1500 .
l mrem /yr to any organ.
l The dose to a MEMBER OF THE PUBLIC from '
l iodine-131, iodine-133, tritium and all
! radionuclides in particulate form ' with half ,
- lives greater than 8 days, in gaseous- i l
effluents released, from each unit, to areas at and beyond the site boundary, shall be r limited to the following:
! l l a. During any calendar quarter: Less than l l or equal to 7.5'mrems to any organ, and j
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! b. During any calendar yeart Less than or
( equal to 15 mrems to any organ.
2.1.3 Liquidlffluents The concentration of radioactive material
- released in liquid effluents to unrestricted i
areas shall be limited to 10 times the concentrations specified in 10 CFR Part 20, l Appendix B, Table 2, Column 2 for l radionuclides other than dissolved or j entrained noble gases. For dissolved or i entrained noble gases, the concentration shall l be limited to 2.0E-4 pCi/ml total activity.
l The dose or dose commitment to a MEMBER OF THE l' PUBLIC from radioactive materials in liquid
- effluents released, from each unit, to
! unrestricted areas shall be limited:
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1 l a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and l b. During any calendar year to less than or l
equal to 3 mrems to the whole body and to l less than or equal to 10 mrems to any organ.
l 2.1.4 LVW_ Pond _ Resin _ Inventory The quantity of radioactive miterial contained in resins transferred to the LVW pond shall be limited by the following expression:
(264/V) E3 A /C < 1.0 3 3 i
excluding tritium, dissolved or entrained i noble gases and radionuclides with less than an 8 day half life, where: !
1 A3 = pond inventory limit for a single radionuclide j (Curies),
C3 = 10CFR20, Appendix B, Table 2 Column 2, concentration for a single radionuclide j (pCi/ml),
1 V = volume of resins in the pond (gallons), and 264 = conversion factor (pCi/Ci per l ml/ gal) l 2.1.5 Total _ Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to l releases of radioactivity and to radiation l from uranium fuel cycle sources shall be i limited to less than or equal to 25 mrems to
' the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
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2.2 Effluent _ Concentration _ Limits 2.2.1 Gaseous._ Effluents l l
, For gaseous effluents, effluent concentration l
limits (ECL) values are not directly used in release rate calculations since the applicable ,
limits are expressed in terms of dose rate at !
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l 2.2.2 Liquid _ Effluents
! The values specified in 10 CFR Part 20, l l Appendix B, Table 2, Column 2 are used as the l, ECL for liquid radioactive effluents released !
to unrestricted areas. A value of 2.0E-04 pCi/ml is used as the ECL for dissolved and ,
l entrained noble gases in liquid effluents. I 1 l l 2.3 Measurements _and_ Approximations of_ Total _ Radioactivity 1 1
Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance .
l with the sampling and analysis requirements of Tables 1 4.11-1 and 4.11-2, respectively, of the CPSES ODCM.
l 2.3.1 Liquid _ Radioactive _ Effluents l \
Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma
! spectroscopy, prior to release. Composite l samples were analyzed monthly and quarterly ;
for the Primary Effluent Tanks (PET), Waste ;
Monitor Tanks (WMT), Laundry Holdup and 1 Monitor Tanks (LHMT) and Waste Water Holdup ;
Tanks (WWHT). Composite samples were analyzed monthly for tritium and gross alpha radioactivity in the onsite laboratory using liquid scintillation and gas flow proportional l counting techniques, respectively. Composite I
samples were analyzed quarterly for Sr-89, Sr-l 90 and Fe-55 by a contract laboratory (Teledyne Brown). The results of the composite analyses from the previous month or quarter were used to estimate the quantities of these radionuclides in liquid effluents during the current month or quarter. The total radioactivity in liquid effluent d
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! releases was determined from the measured and estimated concentrations of each radionuclide present and the total volume of the effluent released during periods of discharge.
1 For batch releases of powdex resin to the LVW l pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite samples were analyzed quarterly, for Sr-89 and l Sr-90, by an offsite laboratory (Teledyne l Brown),
l i For continuous releases to the Circulating
- Water Discharge from the LVW pond, daily grab l samples were obtained over the period of pond i discharge. These samples were composited and j analyzed for gamma emitting radionuclides, j l
using gamma spectroscopy techniques.
Composite samples were also analyzed for tritium and gross alpha radioactivity using liquid scintillation and gas flow proportional !
counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-90 and Fe-55 by a contract laboratory (Teledyne Brown).
t l 2.3.2 Gaseous _RadioactiveuEffluents Each gaseous batch release was sampled and
! analyzed for radioactivity prior to release.
! For releases from Waste Gas Decay Tanks, noble l gas grab samples were analyzed for gamma emitting radionuclides using gamma i spectroscopy. For releases from the
! Containment Building, samples were taken using l charcoal and particulate filters, in addition to noble gas and tritium grab samples, and analyzed for gamma emitting radionuclides prior to each release with the exception of Containment vents made as a precursor to a Containment purge. In these cases, samples collected and analyzed as a prerequisite to l the vent were used to estimate total l
l radioactivity released during the subsequent !
purge. The results of the analyses and the ,
total volume of effluent released were used to l determine the total amount of radioactivity ;
released in the batch mode.
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! For continuous effluent release pathways, noble gas and tritium grab samples were collected and analyzed weekly for gamma emitting radionuclides by gamma spectroscopy and liquid scintillation counting techniques, respectively. Continuous release pathways J were continuously sampled using radioiodine
- adsorbers and particulate filters. The l radiciodine adsorbers and particulate filters
- were analyzed weekly for I-131 and gamma l
emitting radionuclides using gamma spectroscopy. Results of the noble gas and tritium grab samples, radiciodine adsorber and particulate filter analyses from the current week and the average effluent flow rate for the previous week were used to determine the total amount of radioactivity released in the continuous mode. Monthly composites of particulate filters were analyzed for gross j l
' alpha activity, in the onsite laboratory using ;
the gas flow proportional counting technique, i i
l Quarterly composites of particulate filters l were analyzed for Sr-89 and Sr-90 by an ;
l offsite laboratory (Teledyne Brown). i 1
2.4 Batch Releases l
A summary of information for gaseous and liquid batch i releases is included in Table 7.1.
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2.5 Abnormal._ Releases l Abnormal releases are defined as unplanned or l uncontrolled releases of radioactive material from the l site boundary. 4 l
No abnormal gaseous effluent release occurred during the l period covered by this report. !
l A summary of information for gaseous and liquid abnormal l releases is included in Table 7.2.
3.O GASEOUS _ EFFLUENTS The quantities of radioactive material released in gaseous effluents are summarized in Tables 7.3 and 7.4. All releases of radioactive material in gaseous form are considered to be ground level releases.
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1 4.O LIQUID EFFLUENTS
- The quantities of radioactive material released in liquid l effluents are summarized in Tables 7.5 and 7.6.
5.0 SOLID WASTES !
The quantities of radioactive material released as solid effluents are summarized in Table 7.13.
l 6.O RELATED INFORMATION i
6.1 Operability __.of_ . Liquid __and__ Gaseous _ Monitoring Instrumentation l ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 require an explanation of why designated inoperable i liquid and gaseous monitoring instrumentation was not I restored to operable status within thirty days.
During the period covered by this report, there were no instances where these instruments were inoperable for I more than thirty days. I i
- 6.2 Changes _to the.Offsite Dose Calculation Manual During the period covered by this report, there were two revisions to the ODCM. In accordance with the ODCM Administrative Control 6.14.c, the changes are submitted !
in the form of a complete copy of the entire ODCM. The l ODCM, current as of December 31, 1995, is contained in l Attachment 8.1. The changes included in these revisions i are summarized below: l l Revision _13,. effective February _14,._1996 -
o This revision was required to support the design modification of two radiation monitors on the turbine building sumps effluent lines and one radiation monitor on the auxiliary building sump effluent line which were replaced with adjacent-to-line type detectors. The new detectors do not have
! flow through them and therefore the requirement to test the flow, as part of the quarterly Digital Channel Operational Test, was deleted.
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l i Revision.14,_ effective _ October _1,_1996 -
e This revision added a generic potentially radioactive liquid pathway to the Waste Water Management System from temporary systems (e.g.,
Steam Generating Secondary Side Cleaning Tanks).
e This revision added the batch sampling requirements '
for temporary systems to allow for control, treatment, disposal or release of liquid effluents i
from these temporary systems.
e This revision clarified the existing listing of l sample analysis frequencies for selected environmental samples listed in ODCM Table 3.12-1.
The frequencies clarified reflect the actual analysis frequencies that were already being performed.
l 6.3 New_ Locations _f or_Do s e_ Calculations __or_ Environmental l
Monitoring ;
l ODCM Administrative Control 6.9.1.4 requires any new locations for dose calculations and/or environmental monitoring, identified by the Land Use Census, to be +
included in the Annual Radioactive Effluent Release Report. Based on the 1996 Land Use Census, no new l receptor locations were identified which resulted in
- changes requiring a revision in current environmental l
sample locations. Values for the new nearest resident, milk animal, garden, X/Q and D/Q values were included in the 1996 Land Use Census.
6.4 Liquid _ Holdup _and_ Gas _ Storage Tanks ODCM Administrative Control 6.9.1.4 requires a description of the events leading to liquid holdup or gas storage tanks exceeding the Technical Specification limits. Technical Specification 3.11.1 limits the quantity of radioactive material contained in each unprotected outdoor tank to less than or equal to ten ,
curies, excluding tritium and dissolved or entrained noble gases. Technical Specification 3.11.2.2 limits the quantity of radioactive material contained in each gas storage tank to less than or equal to 200,000 curies of noble gases (considered as Xe-133 equivalent). These limits were not exceeded during the period covered by this report.
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i 6.5 Noncompliance._._with _ Radiological _ Effluent _ Control !
Requirements i This section provides a listing of events that did not [
comply with the applicable requirements of the I t
Radiological Effluent Controls given in Part I of the CPSES ODCM. Detailed documentation concerning ;
evaluations of these events and corrective actions is >
i maintained onsite. I i
6.5.1 Abnormal _ Gaseous _and_ Liquid _ Releases '
I e None -l 6.5.2 Failure _to_ Sett Monitor _Setpoints ;
l For the year 1996, there was one instance of l failure to set monitor setpoints as required in the ODCM. i I
, On August 10, 1996, a routine containment vent .
i pre-release permit was processed. During the !
data entry of the gamma spectrum number an incorrect number was used. The incorrect i number, by chance, contained containment vent j spectrum data, but not the correct data. This i was not caught during the review and the
! permit was used to perform a containment vent.
The containment vent was monitored.by the vent stack monitors but due to the incorrect spectrum data the monitors were . set to an incorrect-value for the alert and high alarm setpoints. The values for the setpoints were j actually set more conservative than they would
- have been if the correct spectrum data had l been used. No limits were exceeded and no problems were encountered during the containment vent.
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( The following corrective actions have been l taken: ,
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- Procedure STA-603 " Control of Station i Radioactive Effluents" was revised to include a two-number identifying system for gamma spectrums used for effluent permitting. There is a nine-digit
" Sample ID" and a four-digit effluent l
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number used for permitting. Both numbers are recorded on the permit to avoid confusion and distinguish between the correct numbers to be used.
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- Procedure RPI-704
- Pre-Release Processing For Radioactive Effluent Releases" was revised to clarify which spectrum number l is used as identified in STA-603.
- The individuals involved in the pre-release permitting and review were counseled on the importance of proper self-verification.
1 At no time was the health or safet - of the ;
public in question. There were : -
limits exceeded and the release was monitored at all )
times. The effluent radiation monitors were i set at conservative values and should have !
provided the proper response if a problem had I
been indicated.
1 6.6 Resin _ Releases _to..the_LVW 3ond A total of 924 ft3 of resin was transferred to the LVW pond during the period covered by this report. The results of the sample analyses indicate no radioactive material was transferred to the pond.
6.7 Changes _to_the_ Liquid,_ Gaseous _and_ Solid _ Waste _ Treatment Systems In accordance with the CPSES Process Control Program, Section 2.2a, major changes to the Radwaste Treatment Systems (liquid, gaseous and solid) shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which changes were reviewed by i the SORC.
During this reporting period no design modifications were approved or implemented involving major changes to Radwaste Treatment Systems.
6.8 Meteorological _ Monitoring _ Program In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 1996,.is retained onsite. This data is available for review by the NRC upon request. Joint Frequency Tables are included in Attachment 8.2. l 13 i
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. 6.9 Assessment of_ Doses l 6.9.1 Doses..Due.to. Liquid _ Effluents The doses to an adult from the fish and cow-meat consumption pathways from Squaw Creek Reservoir were calculated in accordance with l the methodology and parameters in the ODCM.
l The results of the calculations are summarized on a quarterly and annual basis in Table 7.7.
l 6.9.2 Doses _Due_to_ Gaseous.. Effluents The air dose due to gamma emissions and the air dose due to beta emissions were calculated using the highest annual average atmospheric dispersion factor at the Site Boundary location, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Table 7.8.
6.9.3 Dos e _Due_ to _ .Radiciodines , _ _ Tritium _ . and Particulates The doses to an infant, child, teen and adult from radiciodines and particulates, for the pathways listed in Part II, Table 2.4 of the ODCM, were calculated using the highest dispersion and deposition factors, as appropriate, in accordance with the methodology and parameters in the ODCM. The results of the calculations are summarized on a quarterly and annual basis in Tables 7.9 through 7.12.
6.9.4 40CER190._ Dose _ Evaluation ODCM Radiological Effluent Control 3.11.4 requires dose evaluations to demonstrate compliance with 40 CFR Part 190 only if the calculated quarterly or yearly doses exceed two times the applicable quarterly or annual dose limits. At no time during 1996 were any of these limits exceeded, therefore no evaluations are required.
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6.9.5 Doses __to--_a__ MEMBER __OF___THE _PUBLIC From Ac tivities _ Ins ide _ theJit e_B oundary
, Three activities are considered in this evaluation: fishing on Squaw Creek Lake, recreation activities at the CPSES employee i recreational area and site tours through the CPSES Visitors Center.
The highest dose occurred in the evaluation for fishing, resulting in a dose of 1.95E-3 mrem /yr. The dose to a MEMBER OF THE PUBLIC (fisherman) on Squaw Creek Lake was calculated l based on fishing twice a week, five hours each 1
, day, six months per year. Pathways included
, in the calculation were gaseous inhalation and '
submersion. Liquid pathways are not considered since all doses are calculated at
, the point of cirewater discharge into the 1 lake.
i The dose to a MEMBER OF THE PUBLIC engaged in ,
, recreational activities at the CPSES employee 4
recreational park was calculated based on one visit a week, five hours each day, six months
- per year. Pathways included in the calculation were gaseous inhalation, submersion and ground plane.
i The dose to a MEMBER OF THE PUBLIC during site I tours through the CPSES Visitors Center was calculated based on two visits per year, thirty minutes each visit. Pathways included f in the calculation were gaseous inhalation and submersion.
All calculations were performed in accordance with the methodology and parameters in the l ODCM.
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Table 7.1 BATCILLIQUID_AND_ GASEOUS _R ELEASE _
SUMMARY
Quarter _1 Quarter. 2 Quarter _3 Quarter _4 A. Liquid _ Releases _AlLSources Number of Batch Releases 2.40E+01 2.10E+01 1.80E+01 2.00E+01 Total Time Period for Batch Releases (min) 7.50E+03 8.10E+03 5.93E+03 6.44E+03 Maximum Time Period for a Batch Release (min) 4.43E+02 4.74E+02 4.55E+02 4.48E+02 Average Time Period for a Batch Release (min) 3.13E+02 3.86E+02 3.29E+02 3.22E+02 Minimum Ti e Period for a Batch Release (min) 3.00E+00 4.80E+01 6.10E+01 4.00E+01 Average Stream Flow During Periods of Release (f t3/s) N/A N/A N/A N/A B. Gaseous _ Releases h ources Number of Batch Releases 4.10E+01 3.60E+01 3.80E+01 3.40E+01 Total Time Period for Batch Releases (min) 1.43E+04 1.38E+04 1.37E+04 1.28E+04 Maximum Time Period for a Batch Release (min) 7.21E+02 7.21E+02 4.41E+02 7.21E+02 Average Time Perhd for a Batch Release (min) 3.51E+02 3.86E+02 3.62E+02 3.77E+02 Minimum Time Period for a Batch Release (min) 8.00E+01 2.31E+02 2.34E+02 2.20E+02 T-1
I TABLE 7.2 ABNORMAL _ BATCH LIQUID _AND_ GASEOUS _RELEASZ_
SUMMARY
Quarter 1 Quarter 2 Quarter _3 Quarter _4 A. Liquids Number of Releases 0 0 0 0 Total Activity Released, Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B. Gases ;
Number of Releases 0 0 0 0 Total Activity Released, Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 T-2
._- - , . . .. . .- - - . - __.. .. -. .-= . .. -
l TABLE 7.3 GASEOUS _ EFFLUENTS--SUMMATION _OF_ALL. RELEASES Units Quarter Quarter Quarter Quarter Est. Total 1 2 3 4 Error. %
l A. Fission and Activation Gases .
- 1. Total release C1 1.87E+01 2.94E+00 3.27E+00 2.70E-01 2.35E+01
- 2. Average release rate for pCi/sec 2.38E+00 3.74E-01 4.11E-01 3.40E-02 period
1imit (Total Body Dose Rate)
! 4. Percent of 00CM REC % 4.11E-04 5.66E-05 1.09E-04 9.16E-06 limit (Skin Dose Rate)
! B. Iodines l
- 1. Total Iodine-131 C1 1.45E-06 1.56E-08 0.00E+00 0.00E+00 1.43E+01 l 2. Average release rate for pCi/sec 1.84E-07 1.98E-09 0.00E+00 0.00E+00 i period
, 3. Percent of ODCM REC % 4.19E-04 4.52E-06 0.00E+00 0.00E+00 l limit (Organ Dose Rate)
C. Particulates 1 Particulates with half Ci 0.00E+00 0.00E+00 2.28E-06 0.00E+00 3.13E+01 lives > 8 days
- 2. Average release rate for pCi/sec 0.00E+00 0.00E+00 2.87E-07 0.00E+00 period
- 4. Gross alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l radioactivity l
- 0. Tritium
- 1. Total release Ci 9.06E+00 1.35E+01 1.25E+01 8.85E+00 2.38E+01
- 2. Average release rate for pC1/sec 1.15E+00 1.72E+00 1.57E+00 1.11E+00 l period
i l
l l
TABLE 7.4 GASEOUS _ EFFLUENTS - - GROUND _1EVEL J1ELEASES Continuous Mode Batch Mode l
l Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2
- 1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 3.52E-01 1.29E-01 i Kr-85M Ci 0.00E+00 0.00E+00 2.50E-01 0.00E+00 1 l Kr-85 Ci 0.00E+00 0.00E+00 4.47E-01 7.50E-01 I l
Kr-87 Ci 0.00E+00 0.00E+00 3.26E-01 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 4.70E-01 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 1.65E-03 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 1.24E-01 0.00E+00 Xe-133 Ci 7.92E+00 2.06E+00 6.16E+00 7.38E-03 1 1 Xe-135M Ci 0.00E+00 0.00E+00 5.46E-01 0.00E+00 l l
Xe-135 Ci 2.61E-01 0.00E+00 1.18E+00 0.00E+00 J
Xe-138 Ci 0.00E+00 0.00E+00 6.89E-01 0.00E+00 l .
Total for period Ci 8.18E+00 2.06E+00 1.05E+01 8.86E-01 l
- 2. lodines
, I-131 Ci 1.45E-06 1.56E-08 0.00E+00 0.00E+00 l
l l-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for period Ci 1.45E-06 1.56E-08 0.00E+00 0.00E+00
- 3. Particulates l
H-3 Ci 8.31E+00 1.35E+01 2.53E-01 2.60E-02
- Rb-88* Cf J.00E+00 0.00E+00 8.49E-04 0.00E+00 Total for period Ci 6.81E+00 1.35E+01 2.54E-01 2.60E-02
- Note: Half life < 8 days T-4 i
TABLE 7.4 (con't.)
GASEOUS EFFLUENTS--GROUND _ LEVEL RELEASES Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4
- 1. Fission and Activation Gases Ar-41 Ci 0.00E+00 0.00E+00 1.63E-01 1.22E-01 Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 1.14E-04 Kr-85 Ci 0.00E+00 0.00E+00 4.96E-01 1.19E-01 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 3.20E-02 0.00E400 5.36E-03 2.90E-02 Xe-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-135 C1 2.57E+00 0.00E+00 9.71E-05 8.39E-05 Xe-138 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total for period Ci 2.60E+00 0.00E+00 6.64E-01 2.70E-01
- 2. Iodines I-131 Ci 0.00E+00 0.00E+00 0 00E+00 0.00E+00 I-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
- 3. Particulates '
H-3 Ci 1.25E+01 8.82E+00 1.53E-02 3.58E-02 Co-58 C1 2.28E-06 0.00E+00 0.00E+00 0.00E+00 Total for period Ci 1.25E+01 8.82E+00 1.53E-02 3.58E-02 l
N l T-5
l l
I TABLE 7.5 ,
LIQUID _ EFFLUENTS - -SUMMATION _OF_ALL_ RELEASES I Units Quarter Quarter Quarter Quarter- Est. Total 1 2 3 4 Error. %
A. Fission and Activation Products
- 1. Total release (not Ci 4.38E-02 4.21E-02 2.74E-02 3.64E-02 3.03E+01 I including tritium, gases. alpha)
- 2. Average diluted pC1/ml 2.08E-09 1.62E-09 1.23E-09 1.73E-09 i concentration during )
period j
- 1. Total release C1 3.58E+02 1.57E+02 2.04E+02 2.67E+02 1.34E+01
- 2. Average diluted pC1/ml 1.70E-05 6.02E-06 9.18E-06 1.27E-05 concentration during period
- 1. Total release Ci 6.72E-04 1.75E-04 3.50E-02 1.39E-02 1.16E+01
- 2. Average diluted pCi/ml 3.19E-11 6.73E-12 1.57E-09 6.60E-10 i concentration during i period j
- 3. Percent of 00CM REC % 1.59E-05 3.37E-06 7.86E-04 3.30E-04 limit
..0. Gross Aloha Radioactivity l1.Totalrelease Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of waste released Liters 1.65E+06 1.66E+06 1.25E+06 1.38E+06 2.20E+00 (prior to dilution)
F. Volume dilution of water Liters 2.11E+10 2.60E+10 2.22E+10 2.10E+10 1.00E+01 used during period (Note 1) 4 i Note 1: The dilution volume reported is the total dilution volume during periods when effluent releases were !
- occurring. The additional dilution volume available when there are no effluent releases occurring is i not included, j T-6
?
TABLE 7.6 '
LIQUID. EFFLUENTS Continuous Mode Batch Mode f
Nuclides Released Units Quarter Quarter Quarter Quarter 1 2 1 2 !
l H-3 Ci 0.00E+00 0.00E+00 3.58E+02 1.57E+02 Na-24 C1 0.00E+00 0.00E+00 2.33E-05 0.00E+00 l Cr-51 Ci 0.00E+00 0.00E+00 2.60E-03 1.76E-03 j Mn-54 Ci 0.00E+00 0.00E+00 8.94E-04 7.10E-04 Fe-55 Ci 0.00E+00 0.00E+00 1.13E-02 2.14E-02 Co-57 Ci 0.00E+00 0.00E+00 4.80E-05 1.17E-05 Co-58 Ci 0.00E+00 0.00E+00 1.26E-02 5.20E-03 Fe-59 Ci 0.00E+00 0.00E+00 7.36E-04 7.59E-04 Co-60 Ci 0.00E+00 0.00E+00 3.73E-03 1.13E-03 Zn-65 Ci 0.00E+00 0.00E+00 1.93E-05 0.00E+00 Sr-92 Ci 0.00E+00 0.00E+00 0.00E+00 1.93E-06 Nb-95 Ci 0.00E+00 0.00E+00 9.37E-04 1.05E-04 Zr-95 Ci 0.00E+00 0.00E+00 5.08E-04 8.76E-05 Nb-97 Ci 0.00E+00 0.00E+00 8.32E-05 3.97E-04 i Zr-97 Ci 0.00E+00 0.00E+00 0.00E+00 8.45E-06 Mo-99 Ci 0.00E+00 0.00E+00 1.50E 06 0.00E+00 ,
Tc-99M Ci 0.00E+00 0.00E+00 1.46E-06 0.00E+00 Ru-103 C1 0.00E+00 0.00E+00 2.90E-06 0.00E+00 Ru-105 Ci 0.00E+00 0.00E+00 7.00E-05 0.00E+00 Ag-110M C1 0.00E+00 0.00E+00 2.09E-04 2.81E-04 :
0,00E+00 '
Sn-113 Ci 0.00E+00 6.90E-05 0.00E+00 In-113M Ci 0.00E+00 0.00E+00 1.12E-04 0.00E+00 Sb-122 C1 0.00E+00 0.00E+00 5.03E-05 0.00E+00 Sb-124 Ci 0.00E+00 0.00E+00 8.42E-04 1.01E-03 Sb-125 Ci 0.00E+00 0.00E+00 5.86E-07 0.00E+00 Sb-126 Ci 0.00E+00 0.00E+00 3.64E-05 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 5.86E-07 0.00E+00 Cs-137 Ci 0.00E+00 0.00E+00 1.12E-06 3.59E-06 La-140 Ci 0.00E+00 0.00E+00 2.69E-06 0.00E+00 Ce-144 Ci 0.00E+00 0.00E+00 2.53E-05 0.00E+00 l Total for period Ci 0.00F+00 0.00F+00 3 58F+0? 1.57F+0?
l ;
( T-7 i
l l
[
TABLE 7.6 (continued)
LIQUID _ EFFLUENTS Continuous Mode Batch Mode l
l Nuclides Released Units Quarter Quarter Quarter Quarter I 1 2 1 2 i i
Ar-41 Ci 0.00E+00 0.00E+00 9.42L-0/ 0.00L+00 l
Xe-133 Ci 0.00E+00 0.00E+00 6.68E-04 1.69E-04 Xe-135 Ci 0.00E+00 0.00E+00 2.93E-06 6.09E-06 Total for period Ci 0.00E+00 0.00E+00 6.72E-04 1.75E-04 i
I l
l l
l l
i l 5 i !
i 1
4 i 1
I T-8 i
, - - . __. ~
l 1
l TABLE 7.6 (continued)
LIQUID _ EFFLUENTS i
Continuous Mode Batch Mode l
Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 H-3 Ci 0.00E+00 0.00E+00 2.04L+02 2.6/L+02 Na-24 Ci 0.00E+00 0.00E+00 0.00E+00 4.11E-06 Cr-51 C1 0.00E+00 0.00E+00 2.04E-04 9.72E-04 Hn-54 Ci 0.00E+00 0.00E+00 3.39E-04 7.11E-04 J
Fe-55 Ci 0.00E400 0.00E+00 1.96E-02 1.33E-02 Co-57
]
Ci 0.00E+00 0.00E+00 9.09E-07 2.34E-05 Co-58 C1 0.00E+00 0.00E+00 1.17E-03 3.26E-03 Fe-59 Ci 0.00E+00 0.00E+00 1.32E-04 8.16E-05 Co-60 Ci 0.00E+00 0.00E+00 8.34E-04 1.75E-03 ,
Nb-95 Ci 0.00E+00 0.00E+00 6.24E-05 1.19E-04 Zr-95 C1 0.00E+00 0.00E+00 6.81E-05 5.47E-05 l Nb-97 Ci 0.00E+00 0.00E+00 2.32E-04 0.00E+00 Zr-97 Ci 0.00E+00 0.00E+00 1.61E-06 1.89E-06 l Ag-110M Ci 0.00E+00 0.00E+00 4.50E-04 2.65E-04 Sn-113 Ci 0.00E+00 0.00E+00 5.09E-06 0.00E+00 In-113M Ci 0.00E+00 0.00E+00 6.15E-06 0.00E+00 Sb-122 Ci 0.00E+00 0.00E+00 2.11E-06 1.12E-04 l )
l Sb-124 Ci 0.00E+00 0.00E+00 5.32E-05 1.67E-03 Sb-125 Ci 0.00E+00 0.00E+00 4.28E-03 1.37E-02 Sb-126 Ci 0.00E+00 0.00E+00 0.00E+00 1.97E-04 l
. 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 2.69E-06 l
l Cs-134 Ci 0.00E+00 0.00E+00 0.00E+00 3.39E-05 Cs-137 Ci 0.00E+00 0.00E+00 0.00E+00 1.37E-04 La-140 Ci 0.00E+00 0.00E+00 0.00E+00 1.26E-05 Ce-141 Ci 0.00E+00 0.00E+00 0.00E+00 2.83E-06 Total for period Ci 0.00E+00 0.00F+00 2.04E+0? 7.67E+0?
l
! T-9 1
1
TABLE 7.6 (continued)
LIQUID _ EFFLUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter .
3 4 3 4 l
Xe-133M C1 0.00E+00 0.00L+00 5.52L-04 2.0ll-04 Xe-133 Ci 0.00E+00 0.00E+00 3.35E-02 1.35E-02 Xe-135 Ci 0.00E+00 0.00E+00 8.86E-04 1.71E-04 Total for period Ci 0.00E+00 0.00F+00 3.50E-02 1.39E- L TABLE 7.7 DOSES .FROM_ LIQUID _ EFFLUENTS _(mrem).
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Body ,
Quarter 1 5.90E-05 1.51E-02 1.50E-02 1.50E-02 1.50E-02 1.52E-02 2.38E-02 l
% Limit 5.90E-04 1.51E-01 5.01E-01 1.50E-01 1.50E-01 1.52E-01 2.38E-01
- per unit Quarter 2 8.90E-05 2.04E-02 2.03E-02 2.03E-02 2.03E-02 2.05E-02 2.14E-02 j
% Limit 8.90E-04 2.04E-01 6.77E-01 2,03E-01 2.03E-01 2.05E-01 2.14E-01 per unit Ouarter 3 5.89E-05 2.51E-02 2.51E-02 2.51E-02 2.51E-02 2.52E-02 2.56E-02 l
3 Limit 5.89E-04 2.51E-01 8.37E-01 2.51E-01 2.51E-01 2.52E-01 2.56E-01 per unit i Ouarter 4 4.20E-04 1.96E-02 1.94E-02 1.89E-02 1.91E 02 1.94E-02 2.02E-02 5 Limit 4.20E-03 1.96E-01 6.45E-01 1.89E-01 1. 91f.-01 1.94E-01 2.02E-01
- per unit Total 1996 6.27E-04 8.01E-02 7.98E-02 7.93E-02 7.95E-02 8.03E-02 9.10E-02 1
% Limit 3.13E-03 4.01E-01 1.33E+00 3.96E-01 3.98E-01 4.02E-01 4.55E-01 per unit l
T-10
._ -. . _ __ _ _ . _ . _ ___._ _._ _ .._. ._.__. ._ _ _. ~ __.._._ _ __ . _ _ . . - _ _ _ .
l l
l TABLE 7.8 l DOSES _FROM_ GASEOUS _ EFFLUENTS l
Noble Gas Air Dose (mrad)
Air Dose (mrad) Gamma Air Beta Air Quarter 1 3.00E-03 3.08E-03
% Limit per unit 3.00E-02 1.54E-02 Quarter 2 2.03E-04 4.24E-04 .
% Limit per unit 2.03E-03 2.12E-03 I
Quarter 3 6.77E-04 8.22E-04 l
% Limit per unit 6.77E-03 4.11E-03 Quarter 4 1.20E-04 6.94E-05 l % Limit per unit 1.20E-03 3.47E-04 l
Total 1996 4.00E-03 4.40E-03 l
l % limit oer unit 2.00E-02 1.10E-02 I
l I
l l
i k
l
! T-11
? I s' r TABLE 7.9 DOSES _EROM_ GASEOUS _EEELUENTS Iodines, Particulates and Tritium Adult Age Group, (mrem)
- I Organ Bone Liver Whole Thyroid- Kidney Lung GI-LLI Skin Body Otr-1 1.17E-06 7.73E-03 7.73E-03 8.26E-03 7.73E-03 7.73E-03 7.73E-03 3.20E-08 ,
i
% Limit 7.81E-06 5.15E-02 5.15E-02 5.51E-02 5.15E-02 5.15E-02 5.15E-02 2.14E-07 !
per Unit Otr-2 1.26E-08 1.15E-02 1.15E-02 1.15E-02 1.15E-02 1.15E-02 1.15E-02 3.45E-10 l
% Limit 8.41E-08 7.67E-02 7.67E-02 7.67E-02 7.67E-02 7.67E-02 7.67E-02 2.30E-09 per Unit Otr-3 9.16E-07 1.07E-02 1.07E-02 1.07E-02 1.07E-02 1.07E-02 1.07E-02 1.07E-06 i
% Limit 6.11E-06 7.11E-02 7.11E-02 7.11E-02 7.11E-02 7.11E-02 7.11E-02 7.16E-06 i per Unit ;
Otr-4 0.00E+00 7.54E-03 7.54E-03 7.54E-03 7.54E-03 7.54E-03 7.54E-03 0.00E+00
% Limit 0.00E+00 5.03E-02 5.03E-02 5.03E-02 5.03E-02 5.03E-02 5.03E-02 0.00E+00 i per Unit [
Total 2.10E-06 3.74E-02 3.74E-02 3.80E-02 3.74E-02 3.74E-02 3.74E-02 1.11E-06 j 1996 ,
% Limit 7.00E-06 1.25E-01 1.25E-01 1.27E-01 1.25E-01 1.25E-01 1.25E-01 3.69E-06 l per Unit i [
f t
i T-12 !
, I 4
i i
L
s TABLE 7.10 i
DOSES _FROM_ GASEOUS _EEELUENTS Iodines, Particulates and Tritium Teen Age Group, (mrem) t Or9an Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body ;
Otr-1 1.98E-06 8.88E-03 8.88E-03 9.68E-03 8.88E-03 8.88E-03 8.88E-03 3.20E-08 i t
% Limit 1.32E-05 5.92E-02 5.92E-02 6.45E-02 5.92E-02 5.92E-02 5.92E-02 2.14E-07 per Unit 7 Otr-2 2.13E-08 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 3.45E-10
% Limit 1.42E-07 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 8.81E-02 2.30E-09 per Unit Otr-3 9.16E-07 1.23E-02 1.23E-02 1.23E-02 1.23E-02 1.23E-02 1.23E-02 1.07E-06 .
% Limit 6.11E-06 8.17E-02 8.17E-02 8.17E-02 8.17E-02 8.17E-02 8.17E-02 7.16E-06 per Unit Otr-4 0.00E+00 8.67E-03 8.67E-03 8.67E-03 8.67E-03 8.67E-03 8.67E-03 0.00E+00 !
% Limit 0.00E+00 5.78E-02 5.78E-02 5.78E-02 5.78E-02 5.78E-02 5.78E-02 0.00E+00 per Unit Total 2.92E-06 4.30E-02 4.30E-02 4.38E-02 4.30E-02 4.30E-02 4.30E-02 1.11E-06 1996
% Limit 9.72E-06 1.43E-01 1.43E-01 1.46E-01 1.43E-01 1.43E-01 1.43E-01 3.69E-06 E Der Unit i
T-13 i
_ _ _ _ . _ _ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _ -__.______--______m__ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 7.11 DOSES _EROM_ GASEOUS _EEFLUENTS Iodines, Particulates and Tritium Child Age Group, (mrem)
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body Otr-1 4.70E-06 1.27E-02 1.27E-02 1.43E-02 1.27E-02 1.27E-02 1.27E-02 3.20E-08
% Limit 3.13E-05 8.48E-02 8.48E-02 9.51E-02 8.48E-02 8.48E-02 8.48E-02 2.14E-07 per Unit Otr-2 5.06E-08 1.89E-02 1.89E-02 1.89E-02 1.89E-02 1.89E-02 1.89E-02 3.45E-10
% Limit 3.37E-07 1.26E-01 1.26E-01 1.26E-01 1.26E-01 1.26E-01 1.26E-01 2.30E-09 per Unit Otr-3 9.16E-07 1.76E-02 1.76E-02 1.76E-02 1.76E-02 1.76E-02 1.76E-02 1.07E-06
% Limit 6.11E-06 1.17E-01 1.17E-01 1.17E-01 1.17E-01 1.17E-01 1.17E-01 7.16E-06 per Unit Otr-4 0.00E+00 1.24E-02 1.24E-02 1.24E-02 1.24E-02 1.24E-02 1.24E-02 0.00E+00 ,
% Limit 0.00E+00 8.28E-02 8.28E-02 8.28E-02 8.28E-02 8.28E-02 8.28E-02 0.00E+00 per Unit !
Total 5.66E-06 6.16E-02 6.16E-02 6.32E-02 6.16E-02 6.16E-02 6.16E-02 1.11E-06 1996
% Limit 1.89E-05 2.05E-01 2.05E-01 2.11E-01 2.05E-01 2.05E-01 2.05E-01 3.69E-06 i per Unit T-14 i
TABLE 7.12 DOSES _FROM_ GASEOUS EEELUENTS ,
Iodines, Particulates and Tritium Infant Age Group, (mrem)
Organ Bone Liver Whole Thyroid Kidney Lung GI-LLI Skin Body 4
Otr-1 9.22E-06 9.89E-03 9.89E-03 1.34E-02 9.90E-03 9.88E-03 9.88E-03 3.20E-08
% Limit 6.15E-05 6.60E-02 6.59E-02 8.97E-02 6.60E-02 6.59E-02 6.59E-02 2.14E-07 per Unit Otr-2 9.93E-08 1.47E-02 1.47E-02 1.47E-02 1.47E-02 1.47E-02 1.47E-02 3.45E-10
% Limit 6.62E-07 9.81E-02 9.81E-02 9.83E-02 9.81E-02 9.81E-02 9.81E-02 2.30E-09 per Unit Otr-3 9.16E-07 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.07E-06
% Limit 6.11E-06 9.09E-02 9.09E-02 9.09E-02 9.09E-02 9.09E-02 9.09E-02 7.16E-06 per Unit ,
Otr-4 0.00E+00 9.65E-03 9.65E-03 9.65E-03 9.65E-03 9.65E-03 9.65E-03 0.00E+00 l
% Limit 0.00E+00 6.43E-02 6.43E-02 6.43E-02 6.43E-02 6.43E-02 6.43E-02 0.00E+00 t per Unit Total 1.02E-05 4.79E-02 4.79E-02 5.15E-02 4.79E-02 4.79E-02 4.79E-02 1.11E-06 ,
1996
% Limit 3.41E-05 1.60E-01 1.60E-01 1.72E-01 1.60E-01 1.60E-01 1.60E-01 3.69E-06 per Unit T-15 t
TABLE 7.13 SOLID _RADWASTE_AND.lRRADIATED_ FUEL _ SHIPMENTS A. Solid Waste shipped offsite for Burial or Disposal l (Not Irradiated Fuel)
- 1. Type of Waste Shipped Shipped Buried Buried
- Ci m3 Ci j a. Spent resins / filters 3.32E+01 1.62E+03 3.32E+01 1.62E+03
- b. Dry active waste 4.04E+02 1,88E+00 1.90E+01 '2.14E+00
- c. Irradiated components l l d. Other (oil sent to 1.34E+01 9.23E-03 j processor for l
incineration)
TOTAL 4.51E+02 1.62E+03 5.22E+01 1.62E+03 Includes 194.7 m 3 of suspected clean trash sent to offsite processor for monitoring before final disposition.
Note: Shipped volumes and curies are not always equal to the buried volumes and curies due to some burials occurring outside the twelve month time l period in which the shipments occurred.
l Dry active waste also includes som low-level radioactive resins that are handled and processed in a manner that is consistent with this waste stream.
- 2. Estimate of Hajor Nuclide Nuclide % Abund. Activity Composition (by type of waste) (C1)
- a. Spent resins / filters Fe-55 40.04 6.49E+02 Ni-63 30.72 4.98E+02 Co-60 21.10 3.42E+02 Mn-54 3.67 5.96E+01 i Co-58 2.54 4.11E+01 l C-14 0.08 1.28E+00 H-3 0.06 9.66E-01 Tc-99 LLD I-129 LLO Other* _1.79 2.90E+01 Total 100.00 1.62E+03
- Nuclides representing <1% of total shipped activity: Be-7. Cr-51. Co-57, Fe-59. Ni-59. Zn-65.
Sr-89. Sr-90. Nb-95. Zr-95, Ru-106. Ag-110M. Sn-113. Sn-117M. Sb-124. Sb-125, I-131.
I T-16 i
i l
l l
l TABLE 7.13 (Continued)
SOLID _RADWASTE_AND_ IRRADIATED _EUEL_ SHIPMENTS I
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity Composition (by type of waste) (Ci) l
- b. Dry active waste Fe-55 45.33 8.54E-01 l Co-60 15.23 2.87E-01 Co-58 10.27 1.93E-01 H-3 9.34 1.76E-01 Ni-63 5.10 9.61E-02 Cs-137 3.69 6.96E-02 Mn-54 3.41 6.42E-02 l Nb-95 1.51 2.84E-02 Zr-95 1.40 2.63E-02 Cs-134 1.27 2.39E-02 Sb-125 1.03 1.94E-02 C-14 0.64 1.20E-02 l Tc-99 LLD 1-129 LLD Other* _L18 3.35E 02 Total 100.00 1.88E+00 l
l
- Nuclides representing <1% of total shipped activity: Cr-51. Co-57, Fe-59.
l Ni-59. In-65. Se-75. Sr-89. Sr-90. Nb-95, Zr-95. Ag-110M Sn-113. Sb-125.
Ce-144. Pu-238. Pu-239/40. Pu-241. Am-241. Cm-242. Cm-243/44.
1 l
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity l Composition (by type of waste) (Ci)
, c. Other - Oil sent to processor for Fe-55 72.40 6.68E-03
! incineration Co-60 8.87 8.18E-04 Co-58 7.55 6.97E-04 Cs-137 3.57 3.29E-04 Ni-63 3.31 3.05E-04 i Cs-134 1.62 1.49E-04
! C-14 1.29 1.19E-04 H-3 0.54 4.95E-05 i Tc-99 LLD 0-
! I-129 LLD Other* 0.85 7.85E:05 Total 100.00 9.23E-03 i
I
- Nuclides representing <1% of total shipped activity: Mn-54. Ni-59. Sr-90. Pu-238.
Pu-239/40. Pu-241. Am-241. Cm-242. Cm-243/44.
4 T-17
l i
l TABLE 7.13 (Continued)
SOLID _RADWASTE_AND_lRRADIATED_EUEL_ SHIPMENTS l
- 3. Solid Waste Disposition (Mode of Transportation: Truck)
Waste Type Waste Container Number of Destination Class Type Shipments
- a. Resin / filters A Poly
- HIC 2 Chem-Nuclear Barnwell.SC B Poly
- HIC 3 Chem-Nuclear i Barnwell.SC C Poly
- HIC 3 Chem-Nuclear Barnwell.SC
- b. Dry active waste A Strong-tight 7 SEG ,
Oak Ridge TN '
- c. Other (oil. included Strong-tight i with shipment to SEG) A 6 AERC l Oak Ridge TN
- High Integrity Container l
l B. Irradiated Fuel Shipments (Disposition)
Number of_ Shipments Mode _of_ Transportation Destination 0 N/A N/A ]
l i
e i
T-18 l
I l
l t
. -. _.