ML20206D370
| ML20206D370 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1998 |
| From: | Floyd E, Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| References | |
| NUDOCS 9905040081 | |
| Download: ML20206D370 (46) | |
Text
Log # TXX-99101 P9 File # 911 (clo) 1 C 10010 C -
10160 (clo) nlELECTRIC 953 (clo) 954 (clo)
Ref. # 10CFR50.36a(a)(2)
' c.tamesturry senior nce rmuent
& PrincipalNuclear Oficer Aprll 27,1ggg U. S. Nuclear Regulatory Commission Document Control Desk :
Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Gentlemen:
In accordance with Section 6.9.1.4 of the CPSES Unit 1 and 2 Technical Specif'i:..tlons (Appendix A to License Nos. NPF-87 and NPF-89) and the CPSES Offsitc Soce Calculation Manual (ODCM), enclosed is the Annual Radioactive Effluent Release Report which covers the reporting period from January 1,1998 through December 31,1998.
The tabular summaries of radioactive liquid and gaseous releases are provided in the format defined in Appendix B of Regulatory Guide 1.21, Rev.1, dated June,1974.
During this reporting period thei were no changes to the CPSES ODCM.
Sincerely, eB.%erry C.L.T By: dY#4 h Ro'geOb. Walker Regulatory Affairs Manager CLW/grj Enclosure c-- Mr. E. W. Merschoff, Region IV Mr. J. l..Tapia, Region IV (clo)
Mr. D. H. Jaffe, NRR (clo) ![
Resident inspectors, CPSES 9905040001 981231 i f/
PDR ADOCK 05000445' R peg COMANCHE PEAK SIEAM ELECTRIC STATION i} f Gi} } .
P.O. Box 1002 Glen Rose. Texas 76043 1002
l COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 AND 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l January 1, 1998 -
December 31, 1998 Prepared By: w Date: 'N' E. T. F16yd Radiation Protection Technician Reviewed By: [ t' -p- Date: ff S. E. Bradley Radiation Protectio upervisor Approved By: .
Date: [2 )
J. R. Curtis Radi(ationProtectionManager
U TABLE OF CONTENTS ACRONYMS AND ABBREVIATIONS
1.0 INTRODUCTION
1.1 Executive Summary 2.O 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 3.0 GASEOUS EFFLUENTS l
4.O LIQUID EFFLUENTS j 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 6.5 Noncompl3ance with Radiological Effluent Control Requirements 6.6 Resin Releases to the LVW Pond 6.7 Changes to the Liquid, Gaseous, and Solid Waste Treatment Systems j l
6.8 Meteorological Monitoring Program )
i 6.9 Assessment of Doses i
TABLE OF CONTENTS 7.0 TABLES 7.1 Batch Liquid and Gaseous Release Summary 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 7.8 Doses From Gaseous Effluents; Noble Gas Air Dose 7.9 Doses From Gaseous Effluents; Iodines, Particulates and Tritiura, 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 7.12 Doses From Gaseous Effluents; Iodines, Particulates and Tritium, Infant Age Group 7.13 Solid Waste and Irradiated Fuel Shipments 8.0 ATTACHMENTS 8.1 Joint Frequency Tables for 1998 I 11 l
ACRONYMS AND ABBREVIATIONS d
.CFR Code of Federal Regulations l
CPSES Comanche Peak Steam Electric Station ECL Effluent Concentration Limit LHMT Laundry Holdup and Monitor Tanks LVW Low Volume Waste l l
'ODCM Offsite Dose Calculation Manual 1 i
PET Primary Effluent Tanks -
I i
REC Radiological Effluent Control l SORC Station Operations Review Committee
_NMT . Waste Monitor Tanks WWHT Waste Water Holdup Tanks iii
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 Calculation Manual (ODCM) Administrative Control 6.9.1.4 for the period January 1, 1998, through December 31, 1998.
1.1 Executive _ Summary The radioactive effluent monitoring program for the year 1998 was conducted as described in the following report. 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.
A summation of all the radioactive gaseous releases to the environment during 1998 produced the following results:
- The total gaseous tritium released for 1998 was 77.5 Curies which is an increase from 58.5 Curies in 1997 and 43.9 Curies in 1996. l
- The total gaseous fission and activation activity (Noble q gas) released for 1998 was 1.6 Curies which is a decrease ]
from 2.6 Curies in 1997 and 25.2 Curies in 1996. There is )
an improvement in reducing the release of airborne radioactive fission and activation products to the environment.
- The total gaseous particulate activity released for 1998 was 3.09 E-06 Curies. This is an increase from previous j years but is an extremely small contributor to any dose to members of the public and has been maintained at 0 Curies for the last two quarters of 1998 and the first quarter of 1999.
- Gross alpha and iodine has continued at 0 Curies for 1998 matching the performance of 1997 and 1996. This is indicative of excellent fuel integrity.
- The calculated gamma air dose due to noble gases released during 1998 is 6.93 E-04 mrad which is an increase from 1997 which calculated out as 6.75 E-04 mrad but this represents only 0.00347% of the annual limit.
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The calculated beta air' dose due to noble gases released during 1998 is 4.07 E-04 mrad which is a decrease from 1997 which calculated out as 5.48 E-04 mrad but this represents only 0.00102% of the annual limit. (Note: Dose is nuclide specific therefore gamma air dose may increase ;
while beta air dose may decrease based on individual '
nuclides released.)
The total whole body dose due to gaseous radioactivity released based on I-131, I-133, H-3 (tritium) , and particulate nuclides for 1998 calculated out to be.0.11 mrem. This value is an increase from the 1997 whole body dose of 8.21 E-02 mrem. This increase.-is directly attributable to the increase in gaseous tritium released since tritium is responsible for >99% of the total gaseous dose.
Overall the gaseous radioactivity releases from comanche Peak are extremely well controlled and maintained ALARA.
All gaseous releases of nuclides are being reduced with the exception of tritium which is very hard to reduce.
Comanche Peak is well below all applicable limits for.
gaseous releases.
A ' summation ' of ' all the radioactive liquid releases to the environment during 1998 produced the following results: ,
l
- The total number of Curies of radioactive nuclides released in liquid effluents in 1998 was 669.24 Curies, j
'* Of the total Curies released, tritium accounted for 669 Curies while-all other nuclides released accounted for only 0.240 Curies. The total curies of tritium released j is down from the 1997 total of 1455 Curies and the 1996 l level of 986' Curies. The release total of all other j nuclides increased from the 1997 total of 0.114 Curies and 0.200 Curies in 1996.
- The total whole body dose due to liquid effluents calculated out at 9.91 E-02 mrem which is only 1.65% of the annual limit. Tritium accounts for >99% of the calculated total ' whole body dose with the Squaw Creek l Reservoir (SCR) concentration level being the controlling j factor. The SCR tritium level . for 1998 consistently l averaged a concentration of 11,000 pCi/l throughout the year.
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o The 1998 average SCR tritium concentration of 11,000 pCi/l I is 36.7% of the 30,000 pCi/l allowable limit for reportability.
The CPSES meteorological system achieved a 96.6% 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 ODCM required reportable event during 1998. This event involved the accident flow probe failure in the North Vent Stack Wide Range Gas Monitor. The probe failure was not discovered for seventeen days due to the lack of indications and a failure of personnel to notice the changed effluent release values due to the failed probe. Additional details of this event are discussed in Section 6.5.2 of this report During 1998 there were no Technical Specification /ODCM effluent radiation monitors out of service for >30 days.
There were no revisions to the ODCM during 1998.
For 1998, the total volume of solid radwaste buried was 15.9 cubic meters, up slightly from 14.1 cubic meters in 1997. The total buried activity in 1998 was 361 curies. The majority of the buried solid waste volume comes from spent resins and filters at 13.8 cubic meters. Also, spent resins and filters were responsible for >99% of all the total radioactivity 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 items is included in this report:
e A summary of the quantities of radioactive 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 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.
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- An explanation of why inoperable liquid or gaseous effluent monitoring instrumentation was not corrected within 30 days.
l e Changes to the ODCM in the form of a complete, legible copy of the' entire ODCM.
- A listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census. I e A description of the events leading to liquid holdup tanks or gas storage tanks exceeding Technical Specification limits.
e A list and description of abnormal releases of radioactive material from the site to unrestricted areas.
e A description of secondary resin releases to the LVW Pond, e A description of major changes to radioactive waste treatment systems (liquid, gaseous and solid).
o An assessment of radiation doses due to the radioactive liquid and gaseous effluents released from CPSES Unit 1 and Unit 2 in 1998.
l e An assessment of radiation doses'to the likely, most exposed MEMBER OF THE PUBLIC from CPSES Unit 1 and Unit 2 releases and other nearby uranium fuel cycle sources, including doses from I 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.O SUEELEMENTAL_INEORMATION 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.
2.1.1 Eission_and_ Activation _ Gases _INoble_Gasesl 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 4
r-than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr to the skin.
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal l to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation. j i
2.1.2 Iodine:131,_ Iodine-133, Tritium __and__ Radioactive Material _in_Earticulate_Eorm l
The dose rate due to iodine-131, iodine-133, tritium l and all radionuclides in particulate form with half j lives greater than 8 days, released in gaseous l' 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, iodine-133, tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released, from each unit, to areas at and beyond the site boundary, shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
2.1.3 Liquid _ Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 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.
5
r The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to unrestricted areas shall be limited:
- 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
- b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ. l 2.1.4 LVW_ Pond _. Resin _ Inventory The quantity of radioactive material contained in resins transferred to the LVW pond shall be limited by the following expression:
(264/V) E3 A /C < 1.0 3 3 excluding tritium, dissolved or entrained noble gases and radionuclides with less than an 8 day half life, where:
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),
V = volume of resins in the pond (gallons),
and 264 = conversion factor (pCi/Ci per ml/ gal) 2.1.5 Total _ Dose The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any crgan, except the thyroid, which shall be limited to less than or equal to 75 mrems. s 6
i
2.2 Effluent __ Concentration _Limita 2.2.1 Gaseouslffluents For gaseous effluents, effluent concentration limits (ECL) values are not directly used in release rate calculations since the applicable limits are expressed in terms of dose rate at the site boundary.
2.2.2 Liquidl ffluents The values specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 are used as the ECL for liquid radioactive effluents released to unrestricted areas. A value of 2.0E-04 gCi/ml is used as the ECL for dissolved and entrained noble gases in liquid effluents.
2.3 Measurementa_and_Approximationa_ofdotal_ Radioactivity Measurements of total radioactivity in liquid and gaseous radioactive effluents were accomplished in accordance with the sampling and analysis requirements of Tables 4.11-1 and 4.11-2, respectively, of the CPSES ODCM.
2.3.1 Liquid _ Radioactive _ Effluents Each batch release was sampled and analyzed for gamma emitting radionuclides using gamma spectroscopy, prior to release. Composite samples were analyzed monthly and quarterly for the Primary Effluent Tanks (PET), Waste Monitor Tanks (WMT),
Laundry Holdup and 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 counting techniques, respectively. Composite samples were analyzed quarterly for Sr-89, Sr-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 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.
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1 For batch releases of powdex resin to the LvW pond, samples were analyzed for gamma emitting radionuclides, using gamma spectroscopy techniques, prior to release. Composite samples were analyzed quarterly, for Sr-89 and Sr-90, by an offsite laboratory (Teledyne Brown) .
For continuous releases to the Circulating Water Discharge from the LVW pond, daily grab samples were obtained over the period of pond discharge. These q samples were composited and analyzed for gamma )
emitting radionuclides, 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).
2.3.2 Gaseous _ Radioactive _ Effluents Each gaseous batch release was sampled and analyzed for radioactivity prior to release, vor releases from Waste Gas Decay Tanks, noble (
- grab samples were analyzed for gamma emitting radianuclides using ,
gamma spectroscopy. For releases from the {
Containment Building, samples were taken using 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 the vent were used to estimate total radioactivity released during the subsequent purge. The results !
of the analyses and the total volume of effluent I released were used to determine the total amount of radioactivity released in the batch mode. !
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 I techniques, respectively. Continuous release pathways were' continuously sampled using radiciodine adsorbers and particulate filters. The radiciodine ,
adsorbers and particulate filters were analyzed weekly for I-131 and gamma emitting radionuclides using gamma spectroscopy. Results of the noble gas 8
F 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 alpha activity, in the onsite laboratory using the gas flow proportional counting technique. Quarterly composites of particulate filters were analyzed for Sr-89 and Sr-90 by an offsite laboratory (Teledyne Brown).
l
'2.4 Bat.chl eleases A summary of information for gaseous and liquid batch releases is included in Table 7.1.
2.5 Abnormal _ Releases Abnormal releases are defined as unplanned or uncontrolled releases of radioactive material from the site boundary.
No abnormal gaseous effluent release occurred during the period covered by this report.
A summary of information for gaseous and liquid abnormal releases is included in Table 7.2.
3.0, GASEOUSl EELUENTS 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.
4 .~ 0 LI-QUID _EEELUENTS-The quantities of radioactive material released in liquid effluents are summarized in Tables 7.5 and 7.6.
5.O SOLID _ WASTES The quantities of radioactive material released as solid effluents are summarized in Table 7.13, 9
L
r 6.O RELATED_INEORMATION 6.1 Operability _of_ Liquid _and_ Gaseous _ Monitoring _ Instrumentation ODCM Radiological Effluent Controls 3.3.3.4 and 3.3.3.5 require ,
an explanation of why designated inoperable liquid and gaseous monitoring instrumentation was not restored to operable status within thirty days.
During the period covered by this report, there were no instances where these instruments were inoperable for more than thirty days.
6.2 Changes to_the_Offalte_ Dose Calculation _Hanual During the period covered by this report, there were no revisions to the ODCM.
6.3 New_Lo cations _f or_ Dos e_ Calculations _or_ Environmental _ Monitoring 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 1998 Land Uue Census, no new receptor locations were identified which resulted in changes requiring a revision in current environmental sample locations. Values for the new nearest resident, milk animal, garden, X/Q and D/Q values were included in the 1998 Land Use Census.
6.4 Liquid _ Holdup _and_Gaa_ 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. Tecimical 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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6.5 Noncompliance _with_ Radiological _ Effluent _ Control _ Requirements This section provides a listing of events that did not comply with the applicable requirements of the Radiological Effluent Controls given in Part I of the CPSES ODCM. Detailed documentation concerning evaluations of these events and corrective actions is maintained onsite.
6.5.1 Abnormal Gaseona_and_ Liquid _ Releases e None 6.5.2 Inoperable _ North _. Vent _ S t ack _ Rad _ Monitor _Due__t o AccidentLEroceas Flow _ Probe _Eailure On January 19,1998 it was discovered during a periodic review by Radiation Protection that the North and South Vent Stacks had significant differences in their respective release rate calculated values. During troubleshooting by I&C technicians it was determined that the accident process flow probe had failed approximately seventeen days earlier. Operations declared the monitor inoperable, a LCOAR was issued and special sampling was initiated in accordance with ODCM specified requirements for estimating primary plant ventilation stack and WRGM flow rates. Repairs were then implemented and completed on January 20, 1998.
This event involved an equipment failure which had no indication to alert operations personnel as to the failure. This stack component would only show a total failure of the accident flow probe, but would not provide indication for a " failed low" condition which is the cause of this event. Careful review of monitor trend values by all cognizant organization personnel will be required to prevent further occurrences of this type. A summary of this event is to be provided to cognizant personnel as training.
This event is reportable, based on NUREG-1022, Rev.1 criteria, because the special condition sampling should have been started on Jan 02, 1998 when the probe failed. Radiation Protection reviewed stack effluent data and associated dose calculations and determined that there were no negative impacts from 11
this event. The North Vent Stack PIG Monitor was operable, as were the South Vent Stack PIG and WRGM monitors, during this event and showed no abnormal trends.
6.6 Resin _Releasea_tcLthe_LVW_Eond A total of 380 ft 3 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 l 6.2.6.2, changes to the Radwaste Treatment Systems (liquid, j gaseous and solid) should be summarized and reported to the l Commission in the Annual Radioactive Effluent Release Report if j the changes implemented required a 10CFR50.59 safety J I
evaluation.
During this reporting period no such changes to Radwaste Treatment Systems were approved and implemented. l 6.8 Meteorological _ Monitoring _Erogram In accordance with ODCM Administrative Control 6.9.1.4, a summary of hourly meteorological data, collected during 1998, is retained onsite. This data is available for review by the !
NRC upon request. Joint Frequency Tables are included in l Attachment 8.1.
l 6.9 Assessment _of_ Doses )
6.9.1 Doses _Due_to_ Liquid _ Effluents l The doses to an adult from the fish and cow-meat 1 consumption pathways from Squaw Creek Reservoir were calculated 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 7.7.
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6.9.2 Dosea_Due_to_Gaseona_ 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 Dose _Due_to_Radiciodines J ritium_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 reau,lts 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 j yearly doses exceed two times the applicable quarterly or annual dose limits. At no time during 1998 were any of these limits exceeded, therefore no evaluations are required.
6.9.5 -Doses to a MEMBER __OF THE PUBLIC__Erom_ Activities Inside_the_ site Boundary Three activities are considered in this evaluation: j fishing on Squaw Creek Reservoir, recreation J activities at the CPSES employee recreational area l and site tours through the CPSES Visitors Center.
The highest dose occurred in the evaluation for fishing, resulting in a dose of 1.27E-4 mrem /yr.
The dose to a MEMBER OF THE'PUBLIC (fisherman) on
. Squaw Creek Reservoir was calculated based on fishing twice a week, five hours each day, six months per 13
i l
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 lake. !
The dose to a MEMBER OF THE PUBLIC engaged in recreational activities .at the- CPSES employee
-recreational park was calculated based on one visit l a week, five hours each day, six months per year. -
Pathways included in the calculation . were gaseous ,
inhalation, submersion and ground plane. i l
The dose to a MEMBER OF THE PUBLIC during site tours l through the CPSES Visitors Center was calculated based-on two visits per year, thirty minutes each j visit. Pathways . included in the calculation were I gaaeous inhalation and-submersion.
l All calculations were performed in accordance with 1 the methodology and parameters in the ODCM.
I I
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l SECTION 7.0 TABLES
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t E E S r 0 0 A a 0 0 R u L Q 0 0 R
R S
U 1_ 0 0 0 0 O r 0 0 E e + +
2 S t E E r 0 0 A a 0 0 7 G u Q O 0 2 E D -
L N T B A A
T D I
U Q
T L
H C
T A
B L
A M
R O
N B
A i i C C d d e e s s a a e e s l s l e e e e s R s R a a e y e y l t l t e i e i R v R v i i f t f t o c o c a A A d r r i e l s e
e l u b a b a q m t s m t i u o a u o L N T G N T A B
TABLE 7.3 GASEOUS _EEELUENTS_-SUMMATION _OE_ALL_ RELEASES Quarter Quarter Quarter Quarter Est. Total IUnits 1 2 3 4 Error, %
A. Fission and Activation Gases
- 1. Total release Ci 4.40E-01 1.61E-01 3.79E-01 6.18E-01 2.35E+01
- 2. Average release rate for pCi/sec 5.66E-02 2.04E-02 4.76E-02 7.78E-02 period
B. Iodines
- 1. Total Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Average release rate for pCi/sec 0.00E+00 0.00E+00 0.00E+00 0.00E+00 period
-limit (Organ Dose Rate)
C. Particulates
- 1. Particulates with half Ci 0.00E+00 3.09E-06 0.00E+00 0.00E+00 3.13E+01 lives > 8 days
- 2. Average release rate for pCi/sec 0.00E+00 3.93E-07 0.00E+00 0.00E+00 period
- 4. Gross alpha Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 radioactivity D. Tritium
- 1. Total release ~ Ci 7.52E+00 3.30E+01 2.31E+01 1.39E+01 2.38E+01
- 2. Average release rate for pCi/sec 9.67E-01 4.20E+00 2.90E+00 1.75E+00 period
' limit (Organ Dose Rate)
T-3
TABLE 7.4 GAS EOUS _EEFLUENTS _- - GROUND _ LEVEL _RELEAS E C Continuous Mode Batch Mode l
l Nuclides Released Units Quarter Quarter Quarter Quarter (
1 2 1 2
- 1. Fission and Activation Gases j I
1 Ar-41 Ci 0.00E+00 0.00E+00 1.89E-01 1.50E-01 Kr-85M Ci 0.00E+00 0.00E+00 9.73E-05 0.00E+00 l l
Kr-85 Ci 0.00E+00 0.00E+00 1.45E-01 0.00E+00 j l
Xe-133 Ci 0.00E+00 0.00E+00 1.06E-01 1.07E-02 j i
Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 1.25E-04 Total for period Ci 0.00E+00 0.00E+00 4.40E-01 1.61E-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 Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates H-3 Ci 7.49E+00 3.30E+01 2.63E-02 1.23E-02 Nd-147 Ci 0.00E+00 3.09E-06 0.00E+00 0.00E+00 Total for period Ci 7.49E+00 3.30E+01 2.63E-02 1.23E-02 T-4
TABLE 7.4 (con't.)
GASEOUS _EEELUENTS_-BROUND_ 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 1.72E-01 1.93E-01 Kr-85 Ci 0.00E+00 0.00E+00 1.79E-01 3.95E-01 Kr-88 Ci 0.00E+00 0.00E+00 2.98E-04 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 6.47E-04 Xe-133 Ci 0.00E+00 0.00E+00 2.78E-02 2.97E-02 Xe-135 Ci 0.00E+00 0.00E+00 1.12E-04 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 3.79E-01 6.18E-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 Total for period Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates H-3 C1 2.30E+01 1.39E+01 1.58E-02 1.49E-02 Total for period C1 2.30E+01 1.39E+01 1.58E-02 1.49E-02 T-5
TABLE 7.5 LIQUID _EEELUENTS--SUMMATION _OF_ALL_ RELEASES Units Quarter Quarter Quarter Quarter Est. Total 1 l 2 3 4 Error, %
A' Fission and Activation Products
- 1. Total release (not Ci 3.68E-02 9.68E-02 2.66E-02 6.77E-02 3.03E+01 including tritium, gases, alpha)
- 2. Average diluted pCi/ml 1.72E-09 6.12E-09 2.17E-09 4.38E-09 concentration during period
- 1. Total release Ci 2.35E+02 1.64E+02 6.34E+01 2.05E+02 1.34E+01
- 2. Average diluted pCi/ml 1.10E-05 1.04E-05 5.17E-06 1.33E-05 concentration during period
- 1. Total release Ci 1.16E-02 2.85E-04 5.50E-05 3.91E-04 1.16E+01
- 2. Average diluted pCi/ml 5.40E-10 1.80E-11 4.48E-12 2.53E-11 concentration during period '
- 3. Percent of ODCM REC % 2.70E-04 9.02E-06 2.24E-06 1.27E-05 limit D. Gross Alpha Radioactivity l 1. Total release Ci 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of waste released Liters 1.66E+06 8.97E+05 6.84E+05 7.64E+05 2.20E+00 (prior to dilution)
Liters 2.14E+10 1.58E+10 1.23E+10 1.55E+10 1.00E+01 lF.Volumedilutionofwater used during period (Note 1)
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 not included.
T-6
i TABLE 7.6 LIQUID EFELUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter i 1 2 1 2 H-3 Ci 0.00E+00 0.00E+00 2.35E+02 1.64E+02 Na-24 Ci 0.00E+00 0.00E+00 0.00E+00 4.26E-05 Cr-51 Ci 0.00E+00 0.00E+00 8.82E-04 1.56E-02 i
Mn-54 Ci 0.00E+00 0 00E+00 3.77E-04 1.80E-03 Fe-55 Ci 0.00E+00 0.00E+00 1.99E-02 1.29E-02 Co-57 Ci 0.00E+00 0.00E+00 4.75E-05 1.63E-04 Co-58 Ci 0.00E+00 0.00E+00 2.62E-03 3.50E-02 Fe-59 Ci 0.00E+00 0.00E+00 4.84E-05 1.09E-03 Co-60 Ci 0.00E+00 0.00E+00 2.43E-03 5.19E-03 Zn-65 Ci 0.00E+00 0.00E+00 2.27E-05 1.77E-04 Se-75 Ci 0.00E+00 0.00E+00 0.00E+00 8.21E-05 Sr-89 Ci 0.00E+00 0.00E+00 2.76E-05 4.25E-05 Nb-95 Ci 0.00E+00 0.00E+00 1.49E-04 2.36E-03 Zr-95 Ci 0.00E+00 0.00E+00 1.47E-05 1.45E-03 'l Mo-99 Ci 0.00E+00 0.00E+00 0.00E+00 1.06E-05 Tc-99M Ci 0.00E+00 0.00E+00 0.00E+00 1.03E-05 Ru-103 Ci 0.00E+00 0.00E+00 0.00E+00 1.72E-05 Ag-110M Ci 0.00E+00 0.00E+00 1.51E-04 5.34E-04 Sn-113 Ci 0.00E+00 0.00E+00 2.66E-05 1.98E-04 In-113M Ci 0.00E+00 0.00E+00 3.56E-05 3.93E-04 Sn-117M Ci 0.00E+00 0.00E+00 0.00E+00 1.21E-05 Sb-122 Ci 0.00E+00 0.00E+00 9.42E-06 8.61E-05 Sb-124 Ci 0.00E+00 0.00E+00 1.92E-04 1.35E-03 Sb-125 Ci 0.00E+00 0.00E+00 9.91E-03 1.77E-02 Sb-126 Ci 0.00E+00 0.00E+00 0.00E+00 5.95E-04 I-131 Ci 0.00E+00 0.00E+00 3.87E-06 0.00E+00 Te-131M Ci 0.00E+00 0.00E+00 8.50E-06 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 2.36E+02 1.65E+02 l
]
i T-7
1 r
TPI E 7. 6 (continued)
LIQUID _EEELUENTS Continuous Mode Batch Mode Nuclides Released Unith Quarter Quarter Quarter Quarter 1 2 1 2 f I
\
Xe-133 Ci 0.00E+00 0.00E+0v 1.15E-02 2.85E-04 '
Xe-135 Ci 0.00E+00 0.00E+00 8.81E-06 0.00E+00 Total for period Ci 0.00E+00 0.00E+00 1.16E-02 2.85E-04 l
i i
T-8
TABLE 7.6 (continued)
LIQUID _EEELUENTS Continuous Mode Batch Mode Nuclides Released Units Quarter Quarter Quarter Quarter 3 4 3 4 H-3 Ci 0.00E+00 0.00E+00 6.34E+01 2.05E+02' Cr-51 Ci 0.00E+00 0.00E+00 4.17E-04 2.53E-04 Mn-54 Ci 0.00E+00 0.00E+00 3.61E-04 1.45E-03 Fe-55 Ci 0.00E+00 0.00E+00 1.05E-02 2.56E-02 l Co-57 Ci 0.00E+00 0.00E+00 8.35E-05 3.54E-04 Co-58 Ci 0.00E+00 0.00E+00 7.54E-03 2.32E-02 Fe-59 Ci 0.00E+00 0.00E+00 2.96E-05 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 2.31E-03 6.36E-03 Zn-65 Ci 0.00E+00 0.00E+00 0.00E+00 7.18E-05 Nb-95 Ci 0.00E+00 0.00E+00 2.86E-04 2.97E-04 Zr-95 Ci 0.00E+00 0.00E+00 1.81E-04 1.11E-04 Mo-99 Ci 0.00E+00 0.00E+00 0.00E+00 7.25E-09 Tc-99M Ci 0 00E+00 0.00E+00 0.00E+00 7.07E-09 l Ag-110M Ci 0.00E+00 0.00E+00 1.75E-04' 1.89E-04 i Sn-133 Ci 0.00E+00 0.00E+00 0.00E+00 7.99E-08 In-113M Ci 0.00E+00 0.00E+00 0.00E+00 2.92E-07 Sb-124 Ci 0.00E+00 0.00E+00 2.95E-05 4.16E-05 Sb-125 Ci 0.00E+00 0.00E+00 4.72E-03 9.77E-03 Total for pe riod Ci 0.00E+00 0.00E+00 6.34E+01 2.05E+02 T-9
1 4
l i
TABLE 7.6 (continued) l LIQUID _EEELUENTS I
i Continuous Mode Batch Mode j l
l Nuclides Released Units Quarter Quarter Quarter Quarter ]
3 4 3 4 1
Xe-133 Ci 0.00E+00 0.00E+00 5.50E-05 3.91E-04 k Total for period Ci 0.00E+00 0.00E+00 5.50E-05 3.91E-04 i
I l1 TABLE 7.7 l l
I DOSES _EROM,1IQUID_EEFLUENTS _lmrem). l I
Orga'. Bone Liver Whole Thyroid Kidney Lung GI-LLI Body I l
Quarter 1 8.77E-05 2.77E-02 2.~6E-02 2.76E-02 2.76E-02 2.79E-02 2.91E-02 I i
% Limit 8.77E-04 2.77E-01 9.20E-01 2.76E-01 2.76E-01 2.79E-01 2.91E-01 per unit Quarter 2 7.38E-05 2.51E-02 2.51E-02 2.50E-02 2.50E-02 2.54E-02 4.15E-02
% Limit 7.38E-04 2.51E-01 8.36E-01 2.50E-01 2.50E-01 2.54E-01 4.15E-01 per unit Quarter 3 3.23E-05 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2.32E-02 2.52E-02
% Limit 3.23E-04 2.31E-01 7.70E-01 2.31E-01 2.31E-01 2.32E-01 2.52E-01 par unit r Quarter 4 8.81E-05 2.34E-02 2.33E-02 2.32E-02 2.33E-02 2.35E-02 2.58E-02
% Limit 8.81E-04 2.34E-01 7.77E-01 2.32E-01 2.33E-01 2.35E-01 2.58E-01 par unit l l
Total 2.82E-04 9.93E-02 9.91E-02 d.89E-02 9.99E-02 9.99E-02 1.22E-01 1998
% Limit 1.41E-03 4.96E-01 1.65E+00 4.94E-01 4.95E-01 4.99E-01 6.08E-01 per unit I
T-10
TABLE 7.8 DOSES _EROM_GASEO.US_EEFLUENTS Noble Gas Air Dose (mrad)
Air Dose (mrad) Gamma Air Beta Air Quarter 1 1.88E-04 1.06E-04
% Limit per unit 1.88E-03 5.31E-04 Quarter 2 1.46E-04 5.26E-05
% Limit per unit 1.46E-03 2.63E-04 ;
Quarter 3 1.69E-04 9.86E-05
% Limit per unit 1.69E-03 4.93E-04 Quarter 4 1.90E-04 1.50E-04 l
% Limit per unit 1.90E-03 7.51E-04 l Total 1998 6.93E-04 4.07E-04
% Limit pet unit 3.47E-03 1.02E-03 I
l l
l 1
l T-11 t ' > . - ..a ,.. ... . .. .. .
ljll llI)1 )
0 0 8 7 0 0 0 0 8 7 0 0 0 0 0 0 0 0 0 0 n + + - - + + + + - -
i E E E E E E E E E E k 0 0 9 9 0 0 0 0 9 0 S 0 0 2 1 0 0 0 0 2 1 0 0 3 2 0 0 0 0 3 1 I 3 2 2 1 2 1 2 2 2 1 L 0 0 0 0 0 0 0 0 0 0
, L - - - - - - - - - -
- E E E E E E E E E E I 1 7 2 8 7 1 8 0 1 0 G 4 2 8 8 9 3 1 9 6 2 6 4 2 1 1 1 1 7 6 2 3 2 2 1 2 1 2 2 2 1 0 0 0 0 0 0 0 0 0 0 g
E E E E E E E E E E n 1 7 2 8 7 1 8 0 1 0 u 4 2 8 8 9 3 1 9 6 2 m L u 6 4 2 1 1 1 1 7 6 2 i
S t T i 3 2 2 1 2 1 2 2 2 1 N r) y 0 0 0 0 0 0 0 0 0 0 E Tm e - - - - - - - - - -
U n E E E E E E E E E E L e d 1 7 2 8 7 1 8 0 1 0 E dr i 4 2 8 8 9 3 1 9 6 2 E nm K .
a( 6 4 2 1 1 1 1 7 6 2 9 E_ s ,
. S ep d 3 2 2 1 2 1 2 2 2 1 7 U t u i 0 0 0 0 0 0 0 0 0 0 O ao o - - - - - - - - - -
2 E E l r r
y E 1
E 7
E E E E E E E E 1 L S uG h 4 2 2
8 8 7 9
1 8 0 1 0 B A c T 8
3 1 9 6 2 T
A E_ i e 6 4 2 1 1 1 1 7 6 2 T M t g O rA R a e 3
0 2
0 2
0 1
0 2
0 1
0 2 2 2 1 Pt l y - - - - - -
0 0
0 0
l E F_ ,u od no E E E E E E E E E S sd NB 1
4 7
2 2
8 8
8 7
9 1 8 0 1 0 E eA 3 1 9 6 2 S
O n 6 4 2 1 1 1 1 7 6 2 i
D d o r 3
0 2
0 2
0 1
0 2
0 1 2 2 2 1 I 0 0 0 0 0 e - - - - - - - - - -
v E E E E E E E E E E i 1 7 2 8 7 1 8 0 1 0 L 4 2 8 8 9 3 1 9 6 2 6 4 2 1 1 1 1 7 6 2 0 0 8 7 0 0 0 0 8 8 0 0 0 0 0 0 0 0 0 0 e + + - - + + + + - -
n E E E E E E E E E E o 0 0 8 9 0 0 0 0 8 4 B 0 0 9 9 0 0 0 0 9 9 0 0 2 1 0 0 0 0 2 9 t t t t t ti ti ti ti ti i n i ;n i n i n i n n 1 mU 2 m'_3 mU 4 mU l mU a - i - i - i - i a8 i g r Lr r Lr r Lr r Lr t9 Lr r t e t e t e t e o9 e O O % p O % p O % p O % p T1 % p
0 0 8 7 0 0 0 0 8 7 0 0 0 0 0 0 0 0 0 0 n + + - - + + + + - -
i E E E E E E E E E E k 0 0 9 9 0 0 0 0 9 0 S 0 0 2 1 0 0 0 0 2 1 0 0 3 2 0 0 0 0 3 1 I 3 2 2 1 2 1 2 2 2 1 L 0 0 0 0 0 0 0 0 0 0 L - - - - - - - - - -
- E E E E E E E E E E I S 1 4 6 6 1 6 8 9 3 G
'. 9 2 1 2 5 3 0 5 5 7 4 3 2 2 1 1 9 7 2 3 2 2 1 2 1 2 2 2 1 -
0 0 0 0 0 0 0 0 0 0 g E E E E E E E E E E n 6 1 4 6 6 1 6 8 9 3 u 3 9 2 1 2 5 3 0 5 5 m L .
u 7 4 3 2 2 1 1 9 7 2 i
S t T i 3 2 2 1 2 1 2 2 2 1 N r y 0 0 0 0 0 0 0 0 0 0 _
E e - - - - - - - - - -
U T )m n E E E E E E E E E E _
L d 6 1 4 6 6 1 6 8 9 3 F der i K
3 9 2 1 2 5 3 0 5 5 -
F n 7 4 3 2 2 1 1 9 R a (m 7 2 0 s 1 S e p d 3 2 2 1 2 1 2 2 2 1 U t u i 0 0 0 0 0 0 0 0 0 0 7 O a o o - - - - - - - - - - 3 E r E E E E E E E E E E 1 E S l r y 6 1 4 6 6 1 6 8 9 3 L A u G h 3 9 2 1 2 5 3 0 5 5 T
B c T 7 4 3 2 2 1 1 9 7 2 i e A G_ t g T M r -
O aA 3 2 2 1 2 1 2 2 2 1 R P e 0 0 0 0 0 0 0 0 0 0 F n l y E
E E
E E E E E E E
,ee od S ho 6 1 4 6 6 1 6 8 9 3 E s WB 3 9 2 1 2 5 3 0 5 5 S e T 7 4 2 2 1 1 9 7 O n 3 2 i
D d _
o r 3
0 2
0 2
0 1
0 2
0 1
0 2
0 2
0 2
0 1
0 I e - - - - - - - - - -
i v E E E E E E E E E E 6 1 4 6 6 1 6 8 9 3 L 3 9 2 1 2 5 3 0 5 5 7 4 3 2 2 1 1 9 7 2 0 0 8 7 0 0 0 0 8 7 0 0 0 0 0 0 0 0 0 0 e + + - - + + v + - -
n E E E E E E E E E E o 0 0 9 6 0 0 0 0 9 3 B 0 0 0 0 0 0 0 0 0 0 0 0 3 2 0 0 0 0 3 1 t t t t t ti ti ti ti ti in in in in i n n 1 mU 2 mU 3 mU 4 mU l mU a - i - i - i - i a8 i g r Lr r Lr r Lr r Lr t9 Lr r t e t e t e t e o9 e O O % p O % p Q % p O % p T1 % p
0 0 8 7 0 0 0 0 8 7 0 0 0 0 0 0 0 0 0 0 n + + - - + + + + - -
i E E E E E E E E E E k 0 0 9 9 0 0 0 0 9 0 S 0 0 2 1 0 0 0 0 2 1 -
0 0 3 2 0 0 0 0 3 1 I 2 2 2 1 2 1 2 1 1 1 _
L 0 0 0 0 0 0 0 0 0 0 L - - - - - - - - - -
E E E E E E E E .
E E I 6 3 4 9 4 6 5 0 9 3 G 0 0 6 0 2 1 9 3 0 6 1 7 4 3 3 2 1 1 1 3 2 2 2 1 2 1 2 1 1 1 _
0 0 0 0 0 0 0 0 0 0 .
g E E E E E E E E E E n 6 3 4 9 4 6 5 0 9 3 u 0 0 6 0 2 1 9 3 0 6 m L 1 7 u 4 3 3 2 1 1 1 3 S i T t i 2 2 2 1 2 1 2 1 1 1 N r) y 0 0 0 0 0 0 0 0 0 0 E e - - - - - -
U Tm n E E E E E E E E E
E L e d 6 3 4 9 4 6 5 0 9 3 F dr i 0 0 6 0 2 1 9 3 0 6 F nm a(
K 1 7 4 3 3 2 1 1 1 3 E
1 s ,
1 S ep d 2 2 2 1 2 1 2 1 1 1
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E ao r y E E E E
E E
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4 1
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0 0 6 0 2 1 9 3 0 6 T
B c 1 7 4 3 3 2 1 1 1 3 A G_ ie t g T M rA O a 2 2 2 1 2 1 2 1 1 1 R Pd e 0 0 0 0 0 0 0 0 0 0 F l l y - - - - - - - - - -
od E E E E E E E 8 E E
,i ho 6 3 4 9 4 6 5 0 9 S sh WB 0 0 6 0 2 1 9 3 0 3
6 E eC S n 1 7 4 3 ~z 2 1 1 1 3 O i D d c r 2
0 2
0 2
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0 2
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0 I e - - - - - - - - - -
v E E E E E E E E E E -
i 6 3 4 9 4 6 5 0 9 3 _
L 0 0 6 0 2 1 9 3 0 6 _
1 7 4 3 3 2 1 1 1 3 _
0 0 8 7 0 0 0 0 8 7 _
0 0 0 0 0 0 0 0 0 0 e + + - - + + + + - -
n E E E E E E E E E E o 0 0 3 5 0 0 0 0 3 8 .
B 0 0 2 1 0 0 0 0 2 0 _
0 0 3 2 0 0 0 0 3 1 t t t t t ti ti ti ti ti in in in in i n n 1 mU 2 mU 3 mU 4 mU l mU a - i - i - i - i a8 i g r Lr r Lr r Lr r Lr t9 Lr r t e t e t e t e o9 e O Q t p O 4 p Q % p O % p T1 % p
0 0 8 7 0 0 0 0 8 7 0 0 0 0 0 0 0 C 0 0 n + + - - + + + + - -
i E E E E E E E E E E k 0 0 9 9 0 0 0 0 9 0 S 0 0 2 1 0 0 0 0 2 1 0 0 3 2 0 0 0 0 3 1 I 3 2 2 1 2 1 2 1 2 1 L 0 0 0 0 0 0 0 0 0 0 L - - - - - - - - - -
- E E E E E E E E E E I 0 7 0 0 1 8 2 1 5 2 G 2 4 6 4 5 6 5 0 4 8 -
8 5 3 2 2 1 1 1 8 2 3 2 2 1 2 1 2 1 2 1 0 0 0 0 0 0 0 0 0 0 g E E E E E E E E E E n 0 7 0 0 1 8 2 1 5 2 u 2 4 6 4 5 6 5 0 4 8 m L .
8 5 3 2 1 1 S i t
u 2 1 8 2 T
3 2 2 1 1 _
i 2 2 1 2 1 N y 0 0 0 0 0 0 0 0 0 0 -
E Tr )m e - - - - - - - - - -
U e n E E E E E E E E E E L r d 0 7 0 0 1 8 2 1 5 2 E
E dm n(
i K
2 8
4 5
6 4 5 6 1
5 0 4 8 _
a 3 2 2 1 1 8 2 E
2 s p ,
1 S e d 3 2 2 1 2 1 2 1 2 1
. U t u i 0 0 0 0 0 0 0 0 0 0 7 O a o o - - - - - - -
5 E r E E E E E E E E E E l r y 0 7 0 0 1 1
E S u G h 2 4 6 4 5 8
6 2
5 1
0 5
4 2
8 -
L A c T T B i e g 8 5 3 2 2 1 1 1 8 2 A G_ t T M rA O a 3 2 2 1 2 1 2 1 2 1 R P tn e 0 0 0 0 0 0 0 0 0 0 F l y - - - - - - - - - -
a od E E E E E E E E E E ho 0 7 0 0 1 8 2 1 5 s,fn S 2 WB 2 4 6 4 5 6 5 0 4 8 E e S nI 8 5 3 2 2 1 1 1 8 2 O i D d o r 3
0 2
0 2
0 1
0 2
0 1
0 2
0 1
0 2
0 1
0 I e - - - - - - - - - -
v E E E E E E E E E E i 0 7 0 0 1 B 2 1 5 2 L 2 4 6 4 5 6 5 0 4 8 8 5 3 2 2 1 1 1 8 2 0 0 8 7 0 0 0 0 8 7 0 0 0 0 0 0 0 0 0 0 e + + - - + + + + - -
n E E E E E E E E E E o 0 0 8 5 0 0 0 0 8 3 B 0 0 0 0 0 0 0 0 0 0 0 0 3 2 0 0 0 0 3 1 t t t t t ti ti ti ti ti i n in in in i n n 1 mU 2 mU 3 mU 4 mU l mU a - i - i - i - i a8 i g r Lr r Lr r Lr r Lr t9 Lr r t e t e t e t e o9 e O O % p Q % p Q % p O % p T1 % p
l TABLE 7.13 SOLID RADWASTE_AND_lRRADIATED_ FUEL _ SHIPMENTS i'
A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel) i
- 1. Type of waste Shipped Shipped Buried Buried m' Ci m2 Ci .
- a. Spent resins / filters 1.36E+01 3.58E+02 1.38E+01 3.60E+02
- b. Dry active waste 1.64E+02 1.09E+00 2.14E+00 1.01E+00
- c. Irradiated components d. Other (oil / miscellaneous 2.97E+00 4.19E+00 liquida sent to processor for volume reduction)
TOTAL 1.80E+02 3.63E+02 1.59E+01 3.61E+02 Includes 104.2 m' 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 since some waste disposal occurs outside the twelve month time period in which shipments occurred.
I Dry active waste also includes some low-level radioactive resins that are handled and processed in a manner that is consistent with )
this waste stream.
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity Composition (by type of waste) (Ci)
- a. Spent resins / filters Mn-54 7,92 2.84E+01 Fe-55 29.90 1.07E+02 Co-58 9.00 3.22E+01 Co-60 21.57 7.72E+01 Ni-63 28.82 1.03E+02 C-14 0.02 7.76E-02 H-3 0.62 2.23E+00 Tc-99 LLD I-129 LLD Other* _2.15 7.70E+00 Total 100.00 3.58E+02
- Nuclides representing <1% of total shipped activity: Co-57, Ni-59, Zn-65, Sr-90, Nb-95, Cd-109, Sn-113, Sb-125, Cs-134, Cs-137, Ce-144, Pu-238, Pu-239/40, Pu-241, Am-241, Cm-242, Cm-243/244.
T-16
m l
TABLE 7.13 (Continued)
SOLID _.RADWASTE. AND_1RRADIATED FUEL SHIPMENTS
- 2. Estimate of Major Nuclide Nuclide % Abund. Activity Composition (by type of waste) (C1)
Co-58 5.34 5.83E-02 !
Co-60 8.77 9.58E-02 Ni-63 5.53 6.04E-02 Cs-137 2.59 2.83E-02 I C-14 0.55 5.95E-03 )
H-3 0.23 2.47E-03 l Tc-99 LLD '
I-129 LLD Other* .-.1.9 6 2J5E-02 Total 100.00 1.09E+00 l
- Nuclides representing <1% of total shipped ectivity: Be-7, Cr-51, Fe-59, -
Co-57, Ni-59, Sr-90, Nb-95, Zr-95, Sn-113, Sb-125, Cs-134, Ce-144, Pu-238, Pu-239/40, Pu-241, Am-241, Cm-242, Cm-243/44,
- 2. Estimate of Major Nuclide .
Nuclide % Abund. Activity Composition (by type of waste) (C1)
- c. Other - Oil / miscellaneous liquids Fe-55 1.43 5.99E-02 sent to processor for volume Co-60 13.75 5.76E-01 reduction Ni-63 82.55 3.46E+00 C-14 0.05 1.95E-03 H-3 0.92 3.87E-02 l Tc-99 LLD I-129 LLD ;
Other* 1.30. 5.4 6E_-J12 I Total 100.00 4.19E+00
- Nuclides representing <1% of total shipped activity: Mn-54, Co-57, co-58, Sr-90, Nb-95, Zr-95, Sb-125, Cs-134, Cs-137, Ce-144, Pu-238, Pu-239/40, Pu-241, Am-241, Cm-242, Cm-243/44.
T-17
TABLE 7.13 (Continued)
SOLID _RADWASTE_AND_ IRRADIATED _EUEL_ SHIPMENTS I l
z
- 3. Solid Waste Disposition (Mode of Transportation: Truck)
Waste Type Waste Container Number of Destination l Class Type Shipments ]
l
- a. Resin / filters B Poly
- HIC 2 Chem-Nuclear Barnwell,SC ,
1 C Poly
- HIC 2 Chem-Nuclear Barnwell,SC
- b. Dry active waste A Strong- 1 GTS Duratek tight Oak Ridge,TN A Strong- 3 AERC tight Oak Ridge,TN
- c. Other - Oil, A Strong- 1 GTS Duratek miscellaneous tight Oak Ridge,TN liquids !
- High Integrity Container i B. Irradiated Fuel Shipments (Disposition)
Number _of_ Shipments Mode _of_Transportatior. Destination 0 N/A N/A T-18
i I;
ATTACHMENT 8.1 4
Joint Frequency Tables for 1998
)
1 R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59 STABILITY CLASS: A ELEVATION: 10 m. l Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 13-18 19-24 >24 *
. TOTAL 4 4 10 7 0 0 22 N 1 ,
5 4 4 0 0 13 i NNE O I
2 5 0 0 0 9 NE 2 7 3 0 0 0 11 ENE 1 2 0 0 0 4 E 1 1 7 6 2 0 0 15 ESE O 11 37 16 1 0 65 SE O 16 38 15 0 0 69 SSE O 24 53 18 0 0 96 S 1 37 7 23 5 1 0 SSW 1 2 2 1 1 8 SW 1 1 5 0 0 0 5 WSW 0 0 0 3 1 0 5 W 0 1 0 0 0 0 3 WNW 2 1 0 8 13 2 0 23 NW ,
0 0 24 24 2 0 50 NNW 0 4 1 0 0 0 12 VARIABLE 7 8
447 Total 17 90 222 109 1 Periods of calm (hours): 13 Hours of missing data: 0
r R.G. 1.21 JOINT FREQUENCY TABLE
.T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION i PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59
. STABILITY CLASS: B ELEVATION: 10 m.
Wind Speed (mph) at 10 m. level Wind Direction 1-3 4-7 8-12 '13-18 19-24 >24 TOTAL 0 7 3 3 0 0 13 N.
O 9 4 4 0 0 17 NNE ,
4 11 4 1 0 0 20 NE 3 8 3 2 0 0 16 ENE E O 2 ~1 0 0 0 3 O 6 2 0 0 0 8 ESE 11 9 4 0 1 26 SE 1 O 17 -
25 13 0 0 55 SSE 0 14 38 34 8 0 94 I S ,
l a 9 36 20 6 0 71 SSW l 0 3 8 6 1 0 18 i SW ,
0 4 5 2 0 0 11 WSW 2 2 1 1 7 W 0 1 3 0 0 0 4 WNW 0 1 2 8 9 0 1 21 UW 1 0 4 16 17 1 1 39 NNW VARIABLE 14 1 0 0 0 0 15 l ,
Total 23 113 165 116 17 4 438 l1 Periods of calm (hours): 0 Hours of missing data: 1 t
. I t
l
I R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY I
i HOURS AT EACH WIND SPEED AND DIRECTION 1 l
l PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59 I
]
STABILITY CLASS: C i ELEVATION: 10 m.
l -______________ ___________________________________________________
Wind Speed (mph) at'10 m.. level l l
Wind TOTAL
^
Direction 1-3 4-7 8-12 13-18 19-24 >24 ]
5 11 7 6 5 35 N 1 1 6 4 6 0 0 21 !
NNE 5 l l
6 3 6 3 0 23 NE 5 9 3 1 0 0 15 ENE 2
- 5 0 0 0 11 E 1 5 2 0 0 0 20 ESE 2 16 12 7 0 0 31 SE 2 10 31 15 1 0 57 SSE 1 9 -
13 52 61 23 10 161 S ,
2 28 43 14 0 94 SSW 1 8 14 8 2 2 28 SW 0 2 2 0 0 5 i WSW 1 0 2 10 3 1 0 17 W 1 2 4 1 0 0 7 WNW 0 2 36 2 11 12 4 7 NW 0 7 13 4 2 33 NNW 0 7 2 0 0 0 0 20 VARIABLE' 18
_____________ .._________________..____________. _____...__..____.... 26 614 42 104 190 185 58 Total Periods of calm (hours): 1 Hours of missing data: 1 l
F i
I R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59 STABILITY CLASS: D ELEVATION: 10 m.
Wind Speed (mph) at 10 m. level Wind TOTAL Direction 1-3 4-7 8-12 13-18 19-24 >24 8 64 198 165 12 0 447 N
13 46 144 118 17 3 341 NNE 26 55 85 28 23 1 218 NE 53 55 16 $ 0 153 ENE 25 61 -38 5 0 0 123 E 19 33 83 20 0 0 0 136 ESE 118 183 48 2 0 377 l SE 26 5 105 _ 290 145 38 11 594 SSE 6 51 315 369 153 45 939 S ,
8 45 181 120 20 2 376 SSW 23 51 27 7 1 118 SW 9 27 23 11 0 0 66 WSW 5 19 23 4 0 0 48 W 2 4 11 48 21 5 0 89 WNW 35 73 80 22 3 220 '
NW 7 5 35 85 139 43 9 316 NNW 24 6 1 0 0 107 VARIABLE 76 855 1818 1297 346 75 4668 Total 277 Periods of calm (hours): 3 Hours of missing data: 2
R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59 STABILITY CLASS: E ELEVATION: 10 m.
Wind Speed (mph) at 10 m. level Wind >24 TOTAL Direction 1-3 4-7 8-12 13-18 19-24 11 2 0 0 34 N 5 16 32 0 0 0 52 NNE 5 15 16 7 0 0 0 27 NE 4 I
3 0 d 0 15 ENE 2 10 i 26 -1 0 0 0 35 l E 8 62 1 0 0 0 76 ESE 13 !
i 279 167 97 1 0 0 SE 14 185 31 1 0 480 SSE 22 _241 131 7 0 0 244 S 24 82 64 15 0 0 146 SSW 24 43 22 10 0 0 80 SW 20 28 9 3 0 0 42 WSW 20 10 9 1 1 0 35 W 12 12 6 8 0 0 44 WNW 13 17 36 3 0 0 105 NW 14 52 18 4 0 0 49 l NNW 7 20 3 1 0 0 85 VARIABLE 72 9
___________________________________________________2 691 86 0 1828 Total 279 770 Periods of calm (hours): 6 Hours of missing data: 1
R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY l
HOURS AT EACH WIND SPEED AND DIRECTION l
PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59 STABILITY CLASS: F ELEVATION: 10 m.
Wind Speed (mph) at.10 m. _ level i Wind TOTAL
. Direction 1-3 4-7 8-12 13-18 19-24 >24 l l
0 0 0 0 3 I l
N 1 2 4 0 0 0 5 NNE O 1 0 0 0 3 NE O 2 1 O O O O O ENE O O O 0 0 0 0 0 E O 0 0 0 0 5 ESE 3 2 22 6 0 0 0 35 SE 7 25 6 0 0 0 41 SSE 10 _
20 19 1 0 0 50 ,
S 10 33 22 2 0 0 87 SSW 30 8 14 0 0 0 38 SW 16 18 2 0 0 53 WSW 17 16 14 0 0 0 24 W 9 1 15 0 0 0 0 23 WNW 8 44 7 0 0 0 59 NW 8 0 0 0 0 17 NNW 7 10 0 0 0 0 27 VARIABLE 26 1
---_______________-_-____-_-_-_---------_-_----_-_-_--_-_.---______-_ 0 470 152 215 98 5 0 Total l Periods of calm (hours): 1 Hours of missing data: 0
1
____________________ ... _____,. L___________________________________
R.G. 1.21 JOINT FREQUENCY TABLE l
j T. U. ELECTRIC COMPANY 1
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01_JAN-98 00:00 TO 31-DEC-98 23:59 STABILITY CLASS: G ELEVATION: 10 m.
Wind Speed (mph) at 10 m. level Wind 1-3 4-7 8-12 13-18 19-24 >24 TOTAL
. Direction _____ __... __.
1 O O O O O N 0 O O O O O O O NNE O O O O O O O NE O O O O O O O ENE O O 0 0 0 0 0 E O 2 0 0 0 0 3 ESE 1 1 1 0 0 0 3 SE 1 0 1 0 0 3 SSE 1 1 0 4 1 0 0 0 5 S
8 7 0 0 0 20 SSW 5 7 3 0 0 0 14 SW 4 7 24 18 0 0 0 49 WSW 9 3 0 0 0 23 W 11 10 2 1 0 0 0 13 WNW 12 0 0 0 0 22 NW 10 0 0 0 5 NNW 1 3 1 2 0 0 0 0 12 VARIABLE 10 75 35 1 0 0 172 Total 61 e Periods of calm (hours): 4 Hours of missing data: 0
c R.G. 1.21 JOINT FREQUENCY TABLE T. U. ELECTRIC COMPANY HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD: 01-JAN-98 00:00 TO 31-DEC-98 23:59 l
STABILITY CLASS: ALL ELEVATION: 10 m.
Wind Speed'(mph) at 10 m. level !
l Wind 13-18 19-24 >24 TOTAL i Direction 1-3 4-7 8-12 16 98 233 184 18 5 554 N
23 82 192 132 17 3 449 NNE 41 92 105 35 26 1 300 NE 33 87 67 19 4 0 210 ENE 29 95 ,47 5 0 0 176 E _
52 178 31 2 0 0 263 ESE 51 340 345 76 3 1 816 ,
SE l
39 358 631 220 40 11 1299 j SSE t
~
43 208 609 490 184 55 1589 S
69 153 361 205 41 2 831 SSW 50 72 114 53 11 4 304 i SW I
50 81 80 20 0 0 231 WSW )
58 49 12 4 1 159 W 35 ,
l 51 60 30 5 0 183 l WNW 37 i
40 147 143 117 28 11 485 l NW 79 151 197 50 12 509 l NNW 20 43 10 2 0 0 278 VARIABLE 223 ---------
6 Total 851 2222 ,
3228 1799 431 10 8637 Periods of calm (hours): 28 Hours of missing data: 95 l