ML20140G227
| ML20140G227 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/1996 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20140G224 | List: |
| References | |
| NUDOCS 9705080152 | |
| Download: ML20140G227 (43) | |
Text
.
1 4
i DOCKET NO. 50-483 i
u i
Umox Etscnue i
33 i
CALLAWAY PLANT i
l ANNUAL RADIOACTIVE EFFLUENT j
RELEASE REPORT i
JANUARY DECEMBER 1996 i
i d
- d-
,*M-l a.
E p.
4 iW 5
J h
t I
DR DO 05 0 83 R
pi-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT CALLAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY LICENSE NPF - 30 JANUARY - DECEMBER 1996
TABLE OF CONTENTS
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Measurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases j
l 3.0
SUMMARY
OF GASEOUS RADIOACTIVE EFFLUENTS 4.0
SUMMARY
OF LIQUID RADIOACTIVE EFFLUENTS 5.0 SOLID WASTES SHIPMENTS l
6.0 RELATED INFORMATION 6.1 Unplanned Releases I
6.2 Changes to the Process Control Program S.3 Changes to the Offsite Dose Calculation Manual j
l 6.4 Major Changes to Radwaste Treatment Systems 6.5 Land Use Census Changes 6.6 Inoperability of Effluent Monitoring Instrumentation 6.7 Instances of Liquid HoAdup Tanks or Waste Decay Tanks Exceeding Technical Specification Limits 7.0 METEOROLOGICAL DATA
8.0 ASSESSMENT
OF DOSES 8.1 Dose at the Site Boundary and Nearest Residence from Gaseous Effluents 8.2 Dose to the MEMBER OF THE PUBLIC 8.2.1 Dose at the Nearest Residence from Gaseous Effluents 8.2,2 Dose to the MEMBER OF THE PUBLIC from Activities Within the SITE BOUNDARY 8.3 Total Dose Due to the Uranium Fuel Cycle 8.4 Dose Due to Liquid Effluents
I TABLE OF COtCE?CS Table 1A Annual Summation of Gaseous Releases Table IB Annual Airborne Continuous and Batch Releases Table 2A Annual Summation of Liquid Releases Table 2B Annual Liquid Continuous ud Batch Releases Table 3 Solid Waste and Irradiated Fuel Shipments Table 4 Cumulative Joint Frequency Distributions Table 5 Dose at the SITE BOUNDARY and Nearest Resident Table 6 Dose to the MEMBER OF THE PUBLIC from Activities within the SITE BOUNDARY Table 7 ~
Total Dose Due to the Uranium Fuel Cycle Table 8 Dose Due to Liquid Effluents I
I I
I I
Il I
I I'
I
1.0 INTRODUCTION
i This Annual Radioactive Effluent Release Report is submitted in accordance with Section 6.9.1.7 of the Callaway Plant Technical Specifications.
1 The report presents a summary of radioactivity released in liquid and gaseous effluents, and solid waste shipped from the Callaway Plant during the period from January 1, 1996 to December 31, 1996.
The information is presented in the format outlined in Appendix B of Regulatory Guide 1.21, Revision 1, June 1974.
All liquid and gaseous effluents discharged during this reporting period were in compliance with federal regulations and the limits in Union Electric Administrative Procedure APA-ZZ-01003, Offsite Dose Calculation Manual (ODCM).
i l
2.O SUPPLEMENTAL INFORMATION 2.1 Reculatorv Limits Specified as follows are the Radiological Effluent Control (REC) j limits applicable to the release of radioactive material in liquid and gaseous effluents.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due to radioactive noble gases released in gaseous i
I effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, j
The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the esite boundary shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 5 mrad for i
gamma radistion and less than or equal to 10 mrad for beta radiation aad, b.
During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
2.1.2 Radiciodine, Tritium, and Particulates The dose rate due to Iodine-131 and 133, tritium and all radionuclides in particulate form with half-lives greater than eight (8) days released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to less than or equal to 1500 mrem /yr to any organ.
The dose to a member of the public from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, b.
During any calendar year:
Less than or equal to 15 mrem to any organ.
-1
I 2.1.3 Liquid Effluents The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the g
concentrations specified in Appendix B, Table II, Column 2 to 3
10CFR20.001 to 20.601 for radionuclic a. other than dissolved or r
entrained noble gases.
For dissolvt or entrained noble gases, the concentration shall be limited to 7 JE-04 microcuries/ml total activity.
The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the whole body and to 3ess than or equal to 10 mrem to any organ.
2.1.4 Uranium Fuel Cycle Sources T.ie 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 mrem to the total body or any organ, except the thyroid, which j
shall be limited to less than or equal to 75 mrem.
l 2.2 Maximum Permissible Concentrations l,
2.2.1 The maximum permissible concentration values specified in Appendix B, Table II, Column 2 to 10CFR20.001 to 20.601 are used to calculate release rates and permissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the limiting concentration for l.
dissolved and entrained noble gases in liquid effluents.
E 2.2.2 For gaseous effluents, maximum permissible concentrations are not utilized in release rate calculations since the applicable limits l
are based on dose rate at the site boundary.
The " Percent of Tech W
Spec Limit" for Table 1A is therefore not applicable to the Callaway Plant.
j 2.3 Averace Enerav 5 l This requirement is not applicable to the Callaway Plant radiological effluent monitoring program since the release rate limits for fission and activation gases in gaseous effluent are not based on the average energy of the radionuclide mixture.
2.4 Measurements and Acoroximations of Total Radioactivity Radionuclide concentrations in liquid and gaseous effluents were obtained by effluent sampling and radiological analysis in accordance with the requirements of Table 9.3-A and Table 9.6-A of i
APA-ZZ-01003, Offsite Dose Calculation Manual.
i Gamma spectroscopy was the primary analysis technique used to l
determine the radionuclide composition and concentration of liquid and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, Fe-55, and transuranic nuclides by an independent laboratory.
Tritium and gross alpha were measured for both liquid and gaseous ll;
i f
l effluents using liquid scintillation counting and gas flow proportional counting techniques, respectively.
1' The total radioactivity in effluent releases was determined from the measured' concentrations of each radionuclide present and the total i.
volume of effluents discharged.
2.5 Batch Releases Summary information relating to batch releases of gaseous and liquid effluents to the environment from the Callaway Plant during this a
year is presented below.
2.5.1 Liould t-PE.'.20D PERIOD UNITS JAN - JUN JUL - DEC Number of batch releases:
122 122 Total time period for batch Minutes 54702 58158 releases:
l Maximum time period for batch Minutes 1643 1205 releases:
4 Average time period for batch Minutes 448 477 releases:
Minimum time period for batch Minutes 11 2
releases:
Average Missouri River flow Cubic 105613 125902 during periods of effluent feet per release to the river: 1 second l
2.5.2 Gaseous PERIOD PERIOD I
UNITS JAN - JUN JUL - DEC Number of batch releases:
41 32 Total time period for batch Minutes 3536 23872 3
I releases:
?
Maximum time period for batch Minutes 445 8773 releases:
Average time period for batch Minutes 86 746 releases:
Minimum time period for batch Minutes 9
45 releases:
2.6 Unclanned Releases 2.6.1 Licuid Number of releases:
0 Total Activity released:
0.00 f
1 Letter, S. Ternes United States Department of the Interior - Geological Survey - Water Resource Division to B.
Holderness, Union Electric Company, dated January 17,1996.
. 4 y
r-
I 2.6.2 Gaseous Number of releases:
1 Total Activity released:
1.19 E-03 Ci 3.0 EUMMARY OF GASEOUS RADIOACTIVE EFFLUENTS 3.1 The quantity of radioactive material released in gaseous effluents during the year is summarized in Tables 1A and 1B.
During this year all gaseous effluents were considered as ground level releases.
4.0
SUMMARY
OF LIOUID RADIOACTIVE EFFLUENTS 4.1 The quantity of radioactive material released in liquid effluents during the year is summarized in Tables 2A and 2B.
During this year there was no cont:Lnuous release of liquid effluent from the plant.
5.0 SOLID WASTES 5.1 The quantities of radioactive material released in shipments of solid waste for burial and irradiated fuel transported from the site during the year are summarized in Table 3.
The total quantity and radioactivity reported in Table 3 for each waste type was for waste l
buried and includes wastes buried by waste reprocessors after volume 3
reduction. The activity and fractional abundance of each nuclide was determined for each waste type based upon radiochemical analysis by an independent laboratory.
The curie concentration of each E
nuclide listed in Table 3 was determined as the product of the E
fractional abundance and the total curies shipped. Those nuclides which comprise at least it of the total activity for a particular waste type are presented in Table 3.
6.0 RELATED INFORMATION 6.1 Unclanned Releases Unplanned releases are: 1) Inadvertent or accidental releases of radioactive material; 2) Releases of radioactive material via normal l
pathways without a release permit, proper authorization, or proper W
sampling and analysis; and 3) Releases which are conducted in such a manner as to result in significant deviation from the requirements of the release permit.
There was one unplanned release during the reporting period.
During 1996 the auxiliary boiler was operated with existing low l
levels of radioactive ccntamination. The auxiliary boiler was W
initially contaminated on April 3, 1995, during Refuel 7 as reported in the 1995 Annual Radioactive Effluent Release Report.
Routine isotopic analysis during 1996 occasionally identified low levels of Mn-54, Co-58, Co-60, and Sb-125 in the auxiliary boiler. This activity was determined to be from resuspension of radioactive material that had plated out in the system.
W The auxiliary boiler blowdown and area drains are routed to the liquid radwaste system to insure processing of any radioactive liquid effluent before being discharged from the plant.
A 10CRF50.59 evaluation was initiated to address operation of the
=
auxiliary boiler during 1996 with existing low levels of radioactive contamination. Dose calculations were performed based on isotopic analysis of auxiliary boiler contents and the estimated volume
-4
1 released for normal monthly operation and Reuel 8 operation. The calculations were performed in accordance with the methodology in APA-ZZ-01003, "Offsite Dose Calculation Manual" using the computerized Effluent Management System.
The 10CFR50.59 evaluation concluded that resulting doses to a member of the public from releases of radioactive material to the environment would be a small fraction of the Radioactive Effluent Controls (REC). dose limits. Therefore, continued operation of the auxiliary boiler would not pose any significant safety or environmental concerns.
The end-of-year evaluation for operation of the auxiliary boiler showed that the following activity was released to the environment
^
during 1996:
H-3 1.18E-03 Ci Mn-54 7.97E-07 Ci Co-58 2.65E-07 Ci Co 60 5.98E-06 Ci Sb-125 1.23E-06 Ci The maximum organ dose to a member of the public from these releases was calculated to be 1.28E-05 mrem which is negligible when compared to the quarterly and annual effluent control limits. As a result, the release of radioactive material from operation of the auxiliary boiler did not endanger the health or safety of the public or the environment.
The activity released from the auxiliary boiler during 1996 is reported in Table 1A and 1B and is also included in the annual dose calculations (see Section 8.0).
A description of this event along with the completed safety evaluations were documented in Suggestion Occurrence Solution (SOS) 96-0090 and 96-1348.
6.2 Changes to the Process Control Program There were no changes made to Administrative Procedure APA-ZZ-01011,
" Process Control Program Manual", during this year.
6.3 Changes to the Offsite Dose Calculation Manual f
Revision 6 of Administrative Procedure APA-ZZ-01003, Offsite Dose Calculation Manual (ODCM) was approved October 23, 1996.
The changes incorporated into revision 6 include the following:
- 1) Added liquid effluent dose factors for Ag-110m, Np-237, Pu-238, Pu-239/240, Pu-241, Am-241, Cm-242, and Cm-234/244 and 3'
Bioaccumulation Factors for Ag, Pu, Am, and Cm due to a change in the Liquid radwaste treatment process.
Removed airborne meat pathway dose conversion factors for Y-91m and Tc-99m due to half-lives of less than eight days.
- 2) Revised the description and methodology for performing the 31 day dose projection for liquid and gaseous effluents, f '.
I
- 3) Revised the maximum allowable background for liquid effluent monitor HB-RE-18.
- 4) Revised the definition of F.
in Section 3.2.1 and q in Section l
3.3.2.1 to clarify their use in the dose calculations. Edited E
equations 3.13 and 3.14 and added equation 3.15 to clarify calculation of dose from radionuclides other than noble gas in caeous affluents.
- 5) Added a description of the methodology for verifying the dose rate limit for gaseous effluents was not exceeded using unit vent and radwaste vent effluent samples.
- 6) Added a new table to describe the selection and use of atmospheric dispersion parameters during the preparation of the Annual Radioactive Effluent Release Report. Updated the Land l
Use Census reference to the current year for the unit vent and E
radwaste vent atmospheric dispersion parameter tables. There were no changes made to the receptor locations.
- 7) E'.inuated REC 9.0.1 and REC 9.0.2 from the ODCM due to redundancy with Technical Specification 3.0.1 and 3.0.2.
f) Revised REC Table 9.3-A to incorporate sampling and analysis l
requirements for TRU nuclides in liquid effluent.
Eliminated W
sampling of Fuel Building Exhaust from REC Table 9.6-A and the associated footnotes due to redundancy with unit vent sampling.
- 9) Revised the continuous sampling requirements for gaseous batch 5
release points and changed the tritium analysis frequency for Purges from weekly to " prior to each purge" to be consistent g
with plant design.
g
- 10) Revised environmental airborne, milk and vegetable sample location criteria on REC Table 9.11-A and footnotes 1 and 6, and eliminated footnote 3 to be less generic and more descriptive of the parameters used in determining the station locations. Revised description to use baseline airborne samples to trigger gamma isotopic analysis in footnote 4 to REC gg Table 9.11-A.
- 11) Revised REC 9.10 surveillance requirement and bases to i
eliminate liquid effluents from this surveillance. Revised REC 9.5 and REC 9.9 to eliminate exceptions for partially tested effluents being released in excess of the respective limit.
A complete copy of Administrative Procedure APA-ZZ-01003, Revision 6 is included as Attachment 1.
j 6.4 Maior Chances to Radwaste Treatment Systems During this reporting period two changes were implemented to the radwaste treatment systems. These were 1) addition of filtration and demineralization as a method for processing liquid waste streams (ORC meeting 1423) and 2) removal of bladders from the recycle g'
holdup tanks (ORC meeting 1415).
g]
6.4.1 FSAR Change Notice 94-061, approved on July 3, 1996, allows the use of a demineralization and filtration process in lieu of evaporation 3
to process some of the waste water generated in the plant. This gl change was implemented to simplify radioactive waste processing, reduce Low Level Radioactive Waste burial volume and reduce worker radiation exposure.
6 -
-.- _..- _.---.- --.-,._-_.-.~ ~ ~
l
^
l 4
j Depending on analysis of the waste stream, the wastewater may be t
processed using liquid waste charcoal adsorber, the waste evaporator condensate demineralizer, the waste evaporator condensate filter, i
the waste monitoring demineralizer or the waste monitor tank filter i
in any combination prior to being eventually sent to the discharge monitor tanks. All the above equipment is existing within the i
plant. No new piping changes were required to provide the necessary flow paths for processing. The only change is the use of new hybrid ion-selective resins that are effective in eliminating specific target nuclides from the waste stream that are major contributors to dose to the public from liquid effluents. At Callaway Plant Cs-treat hybrid resin is being used to remove cesium nuclides from the waste streams.
)
f The consequences or probability of an accident previously evaluated j
j in the FSAR is not increased by this processing method since existing piping and equipment were used. Also, the possibility of a malfunction of equipment important to safety of a different type than previously evaluated in the FSAR is not created by this d
operational change of the liquid radwaste system.
Per the FSAR, the liquid radwaste system is not safety related and its failure will not compromise any safety'related equipment. As stated in the safety evaluation for the change notice, there are no unreviewed i
safety questions as a result of this processing method change.
j
~
i i
While the estimated average activity released using this new piecess' is greater than that estimated in NUREG 0813, the offsite doses are expected to remain below the calculated dose in NUREG 0813 due to the removal of major dose contributors.
The actual change-in effluent concentrations-will not be significant enough to cause dose estimates or effluent limits to be exceeded.
While some radionuclides in the discharge have increased above the i
original estimate, all discharges continue to be at a small fraction i
of the regulatory limits.
This process change was-implemented in August of 1996.
i-i G.4.2 The second modification included removing the bladder from the j
inside of the Recycle Holdup Tanks, THE02A/B, and modifying the tank vent to accommodate a vacuum breaker. Due to a leak in the bladder l'
_that could not.be foundc water accumulated on-the top of the 1
i bladder. This water has caused part of the bladder to sink. Which i
in turn, blocked the pump suction.
)
I The safety evaluation for this modification determined there was no increase in the' consequences of an accident evaluated in the FSAR.
f The modification did not affect the structural integrity of the tank, piping or other components that may lead to uncontrolled leakage. The equipment associated with this modification does not j
interface with equipment important to safety. Therefore, there was L
no unreviewed safety question associated with this modification.
i 4
i Per the Environmental Evaluation, this modification did not result in the creation of a new release pathway, since the Radwaste Building HVAC exhaust is currently a monitored pathway to the environment.
In addition, the modification did not create a new or j
different type of pollutant. The gaseous releases from the radwaste building are controlled by the Offsite Dose Calet.lation Manual to ensure releases are within regulatory limits.
The removal of the bladders allowed dissolved gases in the RCS blowdown to the RHUT to be vented directly to the radwaste building i
l 1
The removal of the bladders allowed dissolved gases in the RCS letdown to the RHUT to be vented to the radwaste building ventilation system.
Two different source terms were evaluated assuming normal plant operations to determine the changes in noble gas activity released.
The first case assumed a normal RCS activity with no fuel defects and the second case assumed RCS activity with failed fuel. While E
both cases resulted in an increased release of fission and g
activation gaseous activity over the year, the increase would be a small fraction of the total gaseous activity released during a year and will not be significant enough to cause effluent limits to be exceeded.
As a result of this change there was no significant change to plant personnel exposure.
The first RHUT bladder was removed in July, 1996 and the second RHUT bladder was removed in February, 1997.
L_nd Use Census Chances 6.5 a
The 1996 Land Use Census identified a change in the location of the nearest resident yielding the highest calculated dose commitment.
l The previously identified nearest resident moved and the house was g
demolished. The new nearest resident is located 1.9 miles NNW of the plant.
6.6 Inocerability of Effluent Monitorino Insti'amentstion All effluent rr.anitoring instrumentation was OPERABLE within the limits specified in FSAR Chapters 16.3.3.6 and 16.3.3.7B during the year.
6.7 Instances of Licuid Holduo Tanks or Waste Gas Decav Tanks Exceedina Technical Soecification Limits All liquid tanks and waste gas decay tanks were within limits specified in FSAR Chapters 16.11.1 and 16.11.3 during the reporting period.
Il I!
Il I
i i
l 7.0 METEOROLOGICAL DATA The on-site meteorological data for this reporting period is presented in Table 4 The data is presented as Cumulative Joint Frequency Distributions of wind speed and wind direction by atmospheric stability class for the 10 and 60 meter tower elevations. Valid data recovery for 1996 was greater than 90% for all required parameters.
8.0 ASSESSMENT
OF DOSES Assessment of doses to the maximum exposed individual from gaseous and liquid effluents released was performed in accordance with Administrative Procedure APA-ZZ-01003 as described in the following sections.
For all effluents released from the Callaway Plant during this year, the annual dose to the maximum exposed individual was less than 2% of the Radiological Effluent Control Limits presented in Section 2.1 of this report.
8.1 Dose at the Site Boundarv from Gaseous Effluents The dose at the Site Boundary was due to plume exposure from noble gases, ground plane exposure, and inhalation.
It was conservatively assumed that a hypothetical maximum exposed individual was present at the Site Boundary location with the most limiting atmospheric dispersion (based on actual meteorological conditions for the year).
Dose was conservatively calculated using a child as the critical age group.
The dose from gaseous effluent at the Site Boundary for 1996 is presented in Table 5.
8.2 Dose to the MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC was considered to be a real individual, not occupationally associated with the plant, who uses portions of the plant site for recreational or other purposes not associated with plant operation. This individual's utilization of areas both inside and outside the Site Boundary was characterized for this calculation.
To evaluate total dose from the Uranium Fuel Cycle to any MEMBER OF THE PUBLIC, the critical MEMBER OF THE PUBLIC within the Site Boundary, and the Nearest Resident were each evaluated.
8.2.1 Dose at the Nearest Resident from Gaseous Effluent The dose to the Nearest Resident was due to plume exposure from noble gases, ground plane exposure, and inhalation and ingestion.
Dose was calculated at the nearest actual residence with the most limiting atmospheric dispersion (based on actual meteorological conditions for the year).
It was conservatively assumed that each ingestion pathway (meat, milk, and vegetation) existed at this location. Dose was conservatively calculated assuming the child as the critical age group. Dose from activities within the Site Boundary was negligible and not included in this calculation.
The doses to the Nearest Resident for 1996 are presented in Table 5.
I l
-9
1I 8.2.2 Dose to the MEMBER OF THE PUBLIC from Activities within the Site Boundary Based on existi.2g land use within the Site Boundary, the MEMBER OF THE PUBLIC with the highest dose was a farmer.
Dose from farming
)
activities within the Site Boundary was due to direct radiation exposure, plume exposure from noble gases, ground plane exposure.
and inhalation.
The current tenant estimates spending 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working within the Site Boundary area.
Dose was calculate.1 using the adult farmer as the critical age group.
Dose to the MEMBER OF THE PUBLIC from activities within the Site Boundary is presented in Table 6.
8.3 Total Dose Due to the Uranium Fuel Cycle Since there are no other Uranium Fuel Cycle facilities within 8 kilometers of the Callaway Plant, the total dose to the most likely exposed MEMBER OF THE PUBLIC resulted from direct radiation exposure 4
and radioactive effluents from the Callaway Plant itself.
Therefore, Dose from mining, fuel fabrication, and waste disposal were not included in this calculation.
Since dose via liquid releases was conservatively evaluated, reasonable assurance exists that no real individual received a significant dose from radioactive liquid release pathways.
J Therefore, only dose to individuals from airborne pathways and dose resulting from direct radiation were considered in this assessment, i
The total dose to the MEMBER OF THE PUBLIC (Table 7) was the sum of the dose due to activities within the Site Boundary (Table 6) and the dose due to gaseous effluents at his residence.
It was assumed that each food ingestion pathway exists at his residence. Dose was calculated using the adult famer as the critical age group.
The total dose from the Uranium Fuel Cycle is presented in Table 7 8.4 Dose Due to Licuid Effluents Dose due to liquid effluents assumed contributions from the maximum exposed individual's consumption of fish and recreational activities. An adult was considered to be the maximum exposed individual in this assessment.
Since there are no potable water intakes within 50 river miles of the discharge point to the Missouri River, the potable water pathway was not included in the dose assessment. Therefore, dose contribution from fish consumption accounted for 95% of the total dose from liquid effluents discharged to the river.
Dose from recreational activities contributed the additional 5%.
It is conservatively assumed the hypothetical maximum exposed individual obtained his entire annual fish intake from near the plant discharge.
Total dose due to liquid effluents from Callaway Plant during the h
year is presented in Table 8.
W I;
A
TABLE 1A SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 1 AND 2,1996 FIRST SECOND EST TOTAL UNITS QUARTER QUARTER ERROR % (a) p TYPE OF EFFLUENT A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 1.57E+01 2.56E+01 20
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.00E+00 3.25E+00
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A I
B. RADIOlODINES CURIES 7.25E-05 0.00E+00 23
- 1. TOTAL IODINE-13i
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 9.22E-06 0.00E+00
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES
- 1. PARTICULATE (HALF-LIVES > 8 DAYS)
CURIES 0.00E+00 1.13E-07 30
- 2. AVERAGE FFI FASE RATE FOR PERIOD uCi/SEC 0.00E+00 1.44E-08
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A
- 4. GROSS ALPHA RADIOACTT/ITY CURIES 5.92E-07 1.98E-07 D. TRITIUM
- 1. TOTAL RELEASE CURIES 3.34E+01 1.31E+01 14
- 2. AVERAGE FF1 FASE RATE FOR PERIOD uCi/SEC 4.25E+00 1.66E+00
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A
(
(a) Safety Analysis Calculation 87-063-00, January 6,1988 I
I I
Page 1 of 2 E
TABLE l A (continued)
SEMIANNUAL SUMMATION OF GASEOUS RELEASES ALL AIRBORNE EFFLUENTS QUARTERS 3 AND 4,1996 THIRD FOURTH EST TOTAL E
TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a) 3 A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CURIES 7.92E+00 9.57E+01 20
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 9.96E-01 1.20E+01
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A B. RADIOIODINES
- 1. TOTAL IODINE-13i CURIES 0.00E+00 7.46E-06 23
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 0.00E+00 9.38E-07 I
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A C. PARTICULATES 1
- 1. PARTICULATE (HALF-LIVES > 8 DAYS)
CURIES 1.71E-07 1.31E-05 30 1
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 2.15E-08 1.65E-06
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A
=
- 4. GROSS ALPHA RADIOACTIVITY CURIES 2.56E-07 LO7E-06 D. TRITIUM
- 1. TOTAL RELEASE CURIES 1.12E+01 2.98E+01 14
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 1.4IE+00 3.75E+00
- 3. PERCENT OF TECH SPEC LIMIT N/A N/A (a) Safety Analysis Calculation 87-063-00, January 6,1988 I'
I' I
Page 2 of 2 I
TABLE 2A i
SEMIANNUAL SUMMATION OF LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS 1 AND 2,1996 FIRST SECOND EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)
A'. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE [NOTINCLUDING TRITIUM, GASES, ALPHA]
CURIES 7.93E-04 1.16E-03 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.07E-09 2.64E-09
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRITIUM
- 1. TOTAL RELEASE CURIES 3.07E+02 4.05E+02 14
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.02E-04 9.26E-04
- 3. PERCENTOF APPLICABLE LIMIT N/A N/A C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 3.88E-03 6.91E-03 27
- 2. AVERAGE DILUTED CONCFNTRATION DURING PERIOD uCi/ML 1.01E-08 1.58E-08 D. GROSS ALPHA RADIOACTIVITY
~
~
- 1. TOTAL RELEASE CURIES 5.71E-04 1.26E-03 29 E. WASTE VOLUME RELEASED (PRE-DILUTION)
GAL 4.%E+06 6.12E+06 10 F. VOLUME OF DILUTION WATER USED GAL 9.64E+07 1.09E+08 10
)
(a) Safety Analysis Calculation 87-063-On, January 6,1988 J
(
Page 1 of 2 s
(
1 TABLE 2A (continued)
SEMIANNUAL SUMM ATION OF LIQUID RELEASES EI l
ALL LIQUID EFFLUENTS 3
QUARTERS 3 AND 4,1996 THIRD FOURTH EST TOTAL TYPE OF EFFLUENT UNITS QUARTER QUARTER ERROR % (a)
A. FISSION AND AC71VATION PRODUCTS
- 1. TOTAL RELEASE [NOTINCLUDING TRITIUM, GASES, ALPHA]
CURIES 3.80E-02 7.32E-01 20
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.25E-08 1.80E-06
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B. TRTI1UM
- l. TOTAL RELEASE CURIES 3.42E+02 1.15E+02 14
- 2. AVERAGE DILUTED CONCENTRATION a,
gl DURING PERIOD uCi/ML 6.53E-04 2.84E-04
- 3. PERCENT OF APPLICABLE LIMIT N/A N/A B
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.14E-02 1.33E-02 27
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.17E-08 3.27E-08 I
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 8.51E-03 1.41E-02 29 E. WASTE VOLUME RELEASED (PRE-DILUTION)
GAL 6.30E+06 4.93E+06 10 F. VOLUME OF DILUTION WATER USED GAL 1.32E+08 1.02E+08 10 (a) Safety Analysis Calculation 87-063-00, Januarv 6,1988 I
I I
Pa,e 2 u,2 I
TABLE 1B-SEMIANNUAL AIRBORNE CONTINUOUS AND BATCII RELEASES GROUND LEVEL RELEASES FISSION GASES IODINES, AND PARTICULATES QUARTERS 1 AND 2,1996 CONTINUOUS RELEASES BATCH RELEASES FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER
- 1. FISSION GASES AR-41 CURIES 0.00E+00 0.00E+00 1.49E-01 5.40E-02 XE-133 CURIES 1.47E+01 2.10E+01 6.67E-02 4.89E-02 XE-135 CURIES 5.88E-01 1.24E+00 1.08E-02 1.43E-03 XE-135M CURIES 0.00E+00 0.00E+00 5.32E-02 1.13E-04 XE-131M CURIES 0.00E+00 3.20E+00 1.15E-07 1.23E-03 KR-85 CURIES 0.00E+00 0.00E+00 1.20E-01 0.00E+00 KR-87 CURIES 0.00E+00 0.00E+00 0.00E+00 7.21E-05 XE-133M CURIES 0.00E+00 0.00E+00 0.00E+00 2.60E-04 KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 7.90E-06 KR-88 CURIES 0.00E+00 0.00E+00 0.00E+00 2.llE-05 TOTAL FOR PERIOD CURIES 1.53E+01 2.55E+01 4.00E-01 1.06E-01
- 2. IODINES 1-131 CURIES 0.00E+00 0.00E+00 7.25E-05 0.00E+00 1 132 CURIES 0.00E+00 0.00E+00 2.43E-07 0.00E+00 1-133 CURIES 0.00E+00 0.00E+00 1.38E-04 0.00E+00 I-134 CURIES 0.00E+00 0.00E+00 2.%E-08 0.00E+00 I-135-CURIES 0.00E+00 0.00E+00 9.56E-12 0.00E+00 TOTAL FOR PERIOD CURIES 0.00E+00 l 0.00E+00 2.11E-04 0.00E+00
- 3. PARTICULATES CO-60 CURIES 0.00E+00 1.13E-07 0.00E+00 0.00E+00 ALPHA CURIES 5.92E-07 1.98E-07 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 5.92E-07 3.llE-07 0.00E+00 0.00E+00
- 4. TRITIUM H3 CURIES 7.82E+00 1.27E+0'l 2.56E+01 3.24E-01 Page 1 of 2
TABLE IB (continued)
SEMIANNUAL AIRBORNE CONTINUOUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 3 AND 4,1996 CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER
- 1. FISSION GASES i
AR-41 CURIES 1.25E+00 5.43E-01 4.71E-01 5.26E-01 XE-133 CURIES 5.15E+00 2.20E+01 2.79E-01 6.36E+01 XE-135 CURIES 6.68E-01 2.03E+00 1.31E-02 9.47E-03 XE-135M CURIES 0.00E+00 2.63E-02 2.02E-04 0.00E+00 XE-131M CURIES 0.00E+00 0.00E+00 1.88E-03 3.48E-02 KR-85 CURIES 0.00E+00 0.00E+00 8.68E-02 6.08E-02 KR-87 CURIES 0.00E+00 2.63E-03 1.86E-05 0.00E+00 XE-133M CURIES 0.00E+00 0.00E+00 4.27E-04 6.97E-01 KR-85M CURIES 0.00E+00 3.64E-02 0.00E+00 0.00E+00 KR-88 CURIES 0.00E+00 3.50E-01 1.27E-03 0.00E+00 XE-138 CURIES 0.00E+00 0.00E+00 3.42E-04 2.96E-04 XE-137 CURIES 0.00E+00 5.83E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 7.07E+00 3.08E+01 8.54E-01 6.49E+01 I
- 2. IODINES I-131 CURIES 0.00E+00 7.46E-06 0.00E+00 0.00E+00 l-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I-133 CURIES 0.00E+00 1.24E-05 0.00E+00 0.00E+00 I-134 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 0.00E+00 1.98E-05 0.00E+00 0.00E+00 I,
- 3. PARTICULATES CO-60 CURIES i.71E-07 5.98E-06 0.00E+00 0.00E+00 l'
CE-141 CURIES 0.00E+00 7.37E-07 0.00E+00 0.00E+00 W
CO-58 CURIES 0.00E+00 3.45E-06 0.00E+00 0.00E+00 MN-54 CURIES 0.00E+00 7.97E-07 0.00E+00 0.00E+00 SB-125 CURIES 0.00E+00 1.23E-06 0.00E+00 0.00E+00 l
CE-144 CURIES 0.00E+00 9.53E-07 0.00E+00 0.00E+00 W
ALPHA CURIES 2.56E-07 1.07E-06 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 4.27E-07 1.42E-05 0.00E+00 0.00E+00
Pago 2 of 2 I
.. _ _. _ _ ~ _. _... _ _ _..... _ _ _ _ _. _.. _ _. _ _ _ _. _ -. _ _. _ _ _ _. _,
[
TABLE 2B
~
i SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED i
QUARTERS 1 AND 2,1996 i
I CONTINUOUS RELEASES BATCH RELEASES I
I FIRST SECOND FIRST SECOND NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER l
- 1. ALL NUCLIDES j
ALPHA CURIES 0.00E+00 0.00E+00 5.71E-04 1.26E-03 CO-60 CURIES 0.00E+00 0.00E+00 3.99E-04 6.77E-04 H3 CURIES 0.00E+00 0.00E+00 3.07E+02 4.05E+0?
I CE-144 CURISS 0.00E+00 0.00E+00 3.81E-05 0.00E+00 I
PR 144 CURIES 0.00E+00 0.00E+00 3.81E-05 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 2.64E-04 4.46E-05 CS-137 CURIES 0.00E+00 0.00E+00 4.09E-05 2.52E-06 i
MN-54 CURIES 0.00E+00 0.00E+00 5.82E-06 1.40E-05 XE-133 CURIES 0.00E+00 0.00E+00 3.75E-03 6.55E-03 XE-133M CURIES 0.00E+00 0.00E+00 4.38E-05 0.00E+00 l
XE 135 CURIES 0.00E+00 0.00E+00 8.03E-05 5.83E-05 l
HF-181 CURIES 0.00E+00 0.00E+00 9.12E-07 0.00E+00 l
5 SB-125 CURIES 0.00E+00 0.00E+00 5.94E-06 7.37E-06 XE-131M CURIES 0.00E+00 0.00E+00 0.00E+00 2.93E-04 CE-14I CURIES 0.00E+00 0.00E+00 0.00E+00 4.40E-06 CO-57 CURIES 0.00E+00 0.00E+00 0.00E+00 1.73E-06 i
KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 4.43E-06 i
4 CR 51 CURIES 0.00E+00 0.00E+00 0.00E+00 1.39E-05 i
SR-89 CURIES 0.00E+00 0.00E+00 0.00E+00 3.91E-04 i
TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 3.07E+02 4.05E+02 l
l 5
I i
I
)
J i
1 I
Page 1 of 2 1
TABLE 2B (continued) e SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED N
i QUARTERS 3 AND 4,1996 CONTINUOUS RELEASES BATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNITS QUARTER QUARTER QUARTER QUARTER I-
- 1. ALL NUCLIDES E
ALPHA CURIES 0.00E H)0 0.00E+00 8.51E-03 1.41E-02 CO-60 CURIES 0.00E+00 0.00E+00 1.56E-02 2.29E-02 Il H-3 CURIES 0.00E+00 0.00E+00 3.42E+02 1.15E+02 CE-144 CURIES 0.00E+00 0.00E+00 1.05E-04 0.00E+00 PR-144 CURIES 0.00E+00 0.00E+00 1.05E-04 0.00E+00 CO-58 CURIES 0.00E+00 0.00E+00 5.18E-03 6.00E-01 W
CS-137 CURIES 0.00E+00 0.00E+00 4.86E-04 4.03E-04 MN-54 CURIES 0.00E+00 0.00E+00 2.09E-03 6.56E-03 XE 133 CURIES 0.00E+00 0.00E+00 1.09E-02 1.19E-02 l
XE-133M CURIES 0.00E+00 0.00E+00 4.55E-05 4.65E-05 W
. XE-135 CURIES 0.00E+00 0.00E+00 2.22E-04 1.49E-05 AR-41 CURIES 0.00E+00 0.00E+00 0.00E+00 3.35E-05 l
SB 125 CURIES 0.00E+00 0.00E+00 7.64E-03 1.85E-02 XE-131M CURIES 0.00E+00 0.00E+00 1.56E-04 1.28E-03 m
CO-57 CURIES 0.00E+00 0.00E+00 1.17E-04 1.19E-03 KR-85M CURIES 0.00E+00 0.00E+00 0.00E+00 9.43E-06 l
CR-51 CURIES 0.00E+00 0.00E+00 1.45E-04 4.40E-02 SR-89 CURIES 0.00E+00 0.00E+00 1.83E-03 0.00E+00 m
CS-134 CURIES 0.00E+00 0.00E+00 4.98E-05 2.71E-05 NB-95 CURIES 0.00E+00 0.00E+00 2.86E-06 8.03E-03 RU-106 CURIES 0.00E+00 0.00E+00 4.72E-04 9.96E-05 l
l-131 CURIES 0.00E+00 0.00E+00 3.59E-03 1.79E-02 W
I-133 CURIES 0.00E+00 0.00E+00 3.99E-04 1.01E-03 TC-99M CURIES 0.00E+00 0.00E+00 5.66E-05 4.36E-04 AG-110M CURIES 0.00E+00 0.00E+00 1.79E-05 7.77E-05 l
BE 7 CURIES 0.00E+00 0.00E+00 3.79E-07 0.00E+00 m
ZR-95 CURIES 0.00E+00 0.00E+00 3.10E-05 6.26E-03 AM-24 i CURIES 0.00E+00 0.00E+00 4.98E-08 1.38E-06 CM-242 CURIES 0.00E+00 0.00E+00 3.91E-08 7.38E-07 CM-243 CURIES 0.00E+00 0.00E+00 9.25E-08 2.27E-06 5
FE-55 CURIES 0.00E+00 0.00E+00 1.46E-07 0.00E+00 PU-238 CURIES 0.00E+00 0.00E+00 1.85E-07 3.49E-06 PU-239 CURIES 0.00E+00 0.00E+00 2.85E-08 5.37E-07 E
PU 241 CURIES 0.00E+00 0.00E+00 5.69E-05 1.25E-03 3
SR-90 CURIES 0.00E+00 0.00E+00 2.49E-05 8.89E-05 LA 140 CURIES 0.00E+00 0.00E+00 0.00E+00 3.30E-04 M O-99 CURIES 0.00E+00 0.00E+00 0.00E+00 1.52E-04 E
SB-124 CURIES 0.00E+00 0.00E+00 0.00E+00 5.57E-04 5
1-132 CURIES 0.00E+00 0.00E+00 0.00E+00 1.21E-04 FE-59 CURIES 0.00E+00 0.00E+00 0.00E+00 1.38E-03 EU 154 CURIES 0.00E+00 0.00E+00 0.00E+00 1.75E-04 RU-103 CURIES 0.00E+00 0.00E+00 0.00E+00 2.09E-04 5
SN-113 CURIES 0.00E+00 0.00E+00 0.00E+00 2.44E-04 TOTALS FOR PERIOD CURIES 0.00E+00 0.00E+00 3.42E+02 1.16E+02 E
Page 2 of 2
TABLE 3 SOLID WASTE & IRRADIATED FUEL SHIPMENTS j
1996 A.
SOLID WASTE BURIED (DOES NOT INCLUDE IRRADIATED FUEL)
- 1. TYPE OF WASTE PERIOD PERIOD EST. TOTAL UNITS JAN - JUN JUL - DEC BAROR M)
- a. Spent resins, filter sludges m8 4.2 11.4 evaporator bottoms,- etc.
Ci-4.8E+01 3.1E+01 125%
- b. Dry compressible waste, m8 7.3 35.5 contaminated equipment, etc.
Ci 2.6E-01 3.2E-01 125%
- c. Irradiated components, m8 0.0 0.0 control rods, etc.
Ci 0.00E+00 0.00E+00 125%
- d. Other ms 0.0 0.0 Ci 0.00E+00 0.00E+00 125%
- 2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (by Type of Waste)
... PERIOD PERIOD,
JAN - JUN JUL - DEC Percent Percent Nuclide Abundance Curies Abundance Curies a.--
Co - - - -
-'34.3%
1.6E+01 17.6%
5.4E+00 Ni-63 31.3%
1.5E+01 16.7%
5.1E+00 Cs-137 12.2%
5.3E+00 Cs - 13 4 - --- - - -
-- - B rM-- ---4.2E+00 Fe-55 8.4%
4.0E+00 60.8%
1.9E+01 Co-58 1.1%
5.2E-01 Mn -- --
1.4%
4.4E-01 b.
Co-58 58.2%
1.5E-01 58.2%
1.9E-01 4
.... _ pe.55-
- 16. 5% -
-- 4 c3E-02 16.5%
-5.3E-02 H-3 14.5%
3.8E-02 14.5%
4.6E-02 Cs-137 5.2%
1.4E-02 5.2%
1.7E-02
-Co-60
- --~
3,0%
7.9E-03 3.0%
9.6E-03 Pu-241 1.6%
4.2E-03 1.6%
5.1E-03 c.
s d.
PPgc 1 of 2
TABLE 3 (continufd)
SOLID WASTE & IRRADIATED FUEL SIIIPMENTS 1995.
- 3. SOLID WASTE DISPOSITION:
g 5'
Number of Mode of Class of Type of Shipments Transportati Destination Solid Waste Container g
on Shipped g
1 Cask Barnwell, SC B
LSA 1*
Cask Scientific C
LSA g
Ecology Group g
gl 5*
Cask Scientific A
LSA Ecology Group 32*
Truck Scientific A
LSA E
Ecology Group 1*
Truck F. W. Hake A
LSA Shipments sent to waste reprocessors for volume reduction before burial.
4.
SOLIDIFICATION AGENT:
None used.
D. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Mode of Shipments Transportation Destination I
I I
I I!
I I
I' Page 2 of 2
Union Electric - Callaway Plant Repon Date/ Time: 15-APR-199714:33:24.92 Meteorological Data Averages Using Hourly Averaged Data 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00
% GOOD UNITS VALUES DATA Stability Class A-G E
92 %
10 Meter Level:
Wind Speed Meter /Sec 3.41E+00 98%
Wind Direction Degrees 2.21E+02 97 %
Wind Direction Variability Degrees 1.26E+01 97 %
f.
Reference Temperature Degrees C 1.14E+01 97 %
Dewpoint Degrees C 5.07E+00 93 %
60 Meter Level:
Wind Speed Meter /Sec 5.33E+00 97 %
Wind Direction Degrees 2.20E+02 96 %
WindDirectionVariability -
Degrees 8.85E+00 97 %
Temperature Difference 60 - 10 Degrees C 1.16E-01 92 %
l i
Page 1 of 15
TABLE'4 (continued)
~
~
Union Electric - Callaway Plant Report DateHime: 15-APR-199714:33:46.52 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: A Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 4
0 0
0 0
4 NNE O
4 0
0 0
0 4
NE 0
3 0
0 0
0 3
ENE O
2 0
0 0
0 2
E O
6 2
5 0
0 13 ESE O
14 12 2
1 0
29 SE 1
21 26 2
0 0
50 SSE 3
13 11 7
2 0
36 i
S 2
23 21 7
1 0
54 SSW l
17 31 5
0 0
Sa SW 2
11 1
3 0
0 17 WSW I
2 0
1 0
0 4
W l
3 10 4
0 0
18 WNW l
7 20 6
0 0
34 NW l
3 9
5 0
0 18 NNW 2
9 4
0 0
0 15 TOT 15 142 147 47 4
0 355 Hours of Calm Data:
0 Hours ofInvalid Data:
6 i
I Page 2 of 15
Union Electric - Callaway Plant Report Date/ Time: 15-APR-199714:33:46.52 i
Meteorological Data Totals of Hours at Each Wind Speed & Direction l-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: B Wind Speed at 10.00 Meter Level (MPH) l
~
i l-3 4 8-12 13-18 19-24
>'.4
-TOTAL 1
4 l
N 1
4 7
0 0
0 12 T
l 1
NNE O
5 0
0 0
0 5
E O
2 1
0 0
0 3
l ENE O
2 5'
0 0
0 7
i i
i E
1 5
6 2
1 0
15 t
i ESE 1
10 5
1 0
0 17 SE 1
8 20 1
0 0
30 SSE 4
4 10 7
0 0
25 S
1 17 17 7
0 0
42 SSW 0
17 20 3
0 0
40 SW 2
11 1
2 0
0 16 i
WSW 2
7 1
1 0
0 11 1
W 0
14 14 3
1 0
32 i
l WNW l
18 19 10 1
0 49 NW l.
7 11 6
0 0
25 NNW 0
5 10 0
0 0
15 TOT 15 136 147 43 3
0
-344 Hours of Calm Data:
0 Hours ofInvalid Data:
4
-hje 3 of 15
TABLE 4 (continued)'
~
~~
~
Uaion Electric - Callaway Plant Report Date/ rime: 15-APR-199714:33:46.52 Meteorological Data 1
Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: C Wind Speed at 10.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
2 3
14 2
0 0
21 NNE 1
7 3
0 0
0 11 NE 2
13 1
1 0
0 17 ENE O
10 2
1 0
0 13 E
1 6
11 1
0 0
19' ESE O
6 7
2 0
0 15 4
SE 2
10 19 3
0 0
34 SSE 2
7 19 4
0 0
32 S
4 19 33 11 0
0 67 SSW 0
19 24 5
2 0
50 SW 3
13 8
1 0
0 25 WSW 0
13 9
1 0
0 23 W
2 14 19 8
2 0
45 l
WNW 2
23 24 10 1
0 60 NW 0
20 16 6
4 0
46 NNW 2
12 23 2
0 0
39 TOT 23 j
195 232 58 9
0 517 l
Hours of Calm Data:
0 Hours ofInvalid Data:
4 E1 Page 4 of 15
Union Electric - Callaway Plant Report Date/Fime: 15-APR-199714:33:46.52 4-4 i
j Meteorological Data Totals of Hours at Each Wind Speed & Direction t
l 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 J
Stability Class: D Wind Speed at 10.00 Meter Level (MPH) f 3
4 i
1, 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
17 90 124' 14 0
0 245 j
NNE 15 60 36 4
0 0
115 NT 20 77 30 1
0 0
128 i
ENE 8
68 47 4
0 0
127 E
4' 46 55 5
2 0
112 ESE 8
40 42 8
1 0
99 I
l SE 11 44 80 24 2
0 161 SSE 11 47 48-27 6
0 139 j
S 16 62 68
- 36 2
0 184 4
SSW 14 53 39 14 3
0 123 SW 14 42 23 9
4 0
92 WSW 20 37 27 13 14 1
112 I
W 17 54 70 50 8
0 199 WNW 17 85 160 81 4
1 348 i
NW 14 104 89 38 3
0 248 l
NNW 19 104 123 42 2
0 290 TOT 225 1013
-1061 370 51 2
2722 i
Hours of Calm Data:
1
}
Hours ofInvalid Data-75
)
2 Page 5 of 15 l
l w
r
-w-y T,+--
~ TABLE 4 } continued)^~
Union Electric - Callaway Plant Report Date/ Time: 15-APR-199714:33:46.52 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 4
Stability Class: E Wind Speed at 10.00 Meter Level (MPH) g 1.?
4-7 8-12 13-18 19-24
>24 TOTAL N
35 101 43 2
0 0
181 NNE 30 53 30 0
0 0
113 NE 38 64 19 0
0 0
121 ENE 20 43 31 3
0 0
97 I
E 14
.i 58 20 6
0 1
109 i
l'l ESE 19 101 55 6
0 0
181 SE 23 144 134 22 1
0 324 SSE 19 144 178 35 10 0
386 S
21 95 140 29 0
0 285 SSW 23 58 44 9
0 0
134 5
SW 16 42 20 7
5 0
90 WSW 20 44 34 10 2
0 110 W
24 91 33 11 2
0 161 WNW 30 109 70 24 1
0 234 NW 36 125 68 13 1
0 243 NNW 30 98 74 12 0
0 214 TOT 398 1380 993 189 22 1
2983 Hours of Calm Data:
11 Hours ofInvalid Data:
13 I-Page 6 of 15 4
,l i
Union Electric - Callaway Plant Report Date/ Time: 15-APR-199714:33:46.52 i
Meteorological Data Totals of Hours at Each Wind Speed & Direction l-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 t
i Stability Class: F i
Wind Speed at 10.00 Meter Level (MPH) l 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
18 29 1
0 0
0 48 i
NNE 31 13 1
0 0
0 45 l
NE 40 8
0 0
0 0
48
)
ENE 40 15 0
0 0
0 55 i
i i
E 36 21 0
0 0
0 57 i
)
ESE 32 62 3
0 0
0 97 I
SE 25 132 41 0
0 0
198 l
SSE 16 104 21 0
0 0
141 I
l S
15 41 13 0
0 0
69 l
SSW 28 36 9
0 0
0 73 SW 20 41 10 0
0 0
71 i
WSW 17 17 5
0 0
0 39 W
19 19 2
0 0
0 40 WNW 17 31 1
0 0
0 49 NW 20 40 6
1 0
0 67 NNW 13 25 0
0 0
0 38 TOT 387 634 113 1
0 0
1135 i
Hours of Calm Data:
14 Hours ofInvalid Data:
12 i
Page 7 of 15
~
TABLE 4 (continued)
~
'~
Union Electric - Callaway Plant Report Date/ Time: 15-APR-199714:33:46.52 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: G Wind Speed at 10.00 Meter Level (MPH) g 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
16 14 0
0 0
0 30 NNE 34 11 0
0 0
0 45 NE 23 2
0 0
0 0
25 ENE 16 0
0 0
0 0
16 E
11 3
0 G
0 0
14 ESE 7
12 0
0 0
0 19 SE 15 41 3
0 0
0 59 SSE 12 28 14 0
0 0
54 S
19 8
0 0
0 0
27 SSW 10 19 3
0 0
0 32 SW 8
16 4
0 0
0 28 WSW 2
2 0
0 0
0 4
W 10 1
1 0
0 0
12 l
WNW 7
14 0
0 0
0 21 NW 8
10 0
1 0
0 19 i
NNW 13 14 0
0 0
0 27 TOT 211 195 25 1
0 0
432 Hours of Calm Data:
5 Hours of Invalid Data:
26 l'
Hours of Good Data:
8519 = 97.0% of Total Hours W
I Page 8 of 15
~
~
~
TA~BLE 4 (continued)
~
~
~
Union Electric - Callaway Plant Report Daterrime: 15-APR-199714:34:04.35 Meteorological Data Totals of Hours at Each Wind Speed & Direction 3
1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 l
Stability Class: A Wind Speed at 60.00 Meter Level (MPH)
I
)
1-3 4-7 8-12 13-18 19-24
>24 TOTAL 4
N 0
3 1
0 0
0 4
)
NNE 0.
2 1
0 0
0 3
NE 0
5 0
0 0
0 5
ENE O
O 1
0 0
0 1
l E
0 2
1 0
0 0
3 ESE 0
8 4
6 3
0 21 SE 1
9 20 8
1 0
39 i
SSE 0
13 20 5
1 1
40 S
1 15 19 4
7 1
47 SSW 1
8 31 14 4
4 62 1
SW 0
10 10 10 3
0 33 WSW 0
4 2
0 0
0 6
4 W
1 3
3 4
3 0
14 WNW 1
4 14 14 4
0 37 NW 0
2 9
5 5
1 22 NNW 0
1 9
0 0
0 10 TOT 5
89 145 70 31 7
347 Hours of Calm Data:
0 Hours of Invalid Data:
14 4
Page 9 of 15
TABLE 4 (continued)
Union Electric - Callaway Plant Report Date/ Time: 15-APR-199714:34:04.35 4
Meteorological Data Totals of Hours at Each Wind Speed & Direction Ii 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: B Wind Speed at 60.00 Meter Level (MPH) g 1-3 4-7 8-12 13-18 19-24
>24 TOTAL I:;
4 N
0 1
7 1
0 0
9 NNE O
4 2
0 0
0 6
NE O
1 4
0 0
0 5
ENE 0
2 1
1 0
0 4
E O
2 7
0 0
0 9
ESE O
4 6
3 1
0 14 SE 0
10 11 8
1 0
30 SSE O
5 19 5
0 0
29 l
S 0
6 13 3
6 0
28 SSW l
7 27 8
5 0
48 SW l
4 12 4
4 0
25 WSW 0
4 8
4 0
0 16 W
l 6
5 9
1 0
22 l
WNW 0
8 23 12 4
3 50 NW 0
7 17 5
3 1
33 NNW l
5 8
2 0
0 16 TOT 4
76 170 65 25 4
344 Hours of Calm Data:
0 Hours of Invalid Data:
4 I
Page 10 of 15
TABLE 4 (continued)
. Union Electric - Callaway Plant Report Daterrime: 15-APR-199714:34:04.35 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00/30 Stability Class: C Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 4
8 4
0 0
16 NNE 0
3 11 0
0 0
14 NE O
9 4
1 0
0 14 ENE 1
13 2
2 0
0 18 E
O 6
7 2
0 0
15 ESE O
7 13 2
1 0
23 SE O
5 17 7
2 0
31 SSE 2
3 18 6
1 0
30 S
0 9
25 11 1
0 46 SSW l
8' 30 20 7
4 70-SV/
1 5
7 7
3 1
24 i
WSW 0
7 12 3
0 0
22 W
0 4
18 18 6
3 49 WNW 1
16 14 18 5
2 56 NT 2
10 19 8
4 4
47 NNW 1
10 26 3
2 0
42 TOT' 9-119 231 112 32 14 517 Hours of Calm Data:
0 Hours ofInvalid Data:
4
(
Page 11 of 15
' TdBLE 4 (continued)
~
I Union Electric - Callaway Plant Report Date/ Time: 15-APR-199714:34:04.35 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: D Wind Speed at 60.00 Meter Level (MPH) g 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
5 50 93 50 12 0
210 NNE 1
54 62 22 5
0 144 NE 6
54 55 3
1 0
119 ENE 4
44 78 13 2
0 141 E
6 25 69 17 2
0 1l'9 ESE 3
29 45 19 6
1 103 SE 5
28 69 37 9
1 149 SSE 6
25 55 34 21 7
148 S
7 16 67 52 22 3
167 SSW 8
28 50 37 19 6
148 SW 6
23 31 17 8
3 88 WSW 5
13 33 27 12 14 104 W
10 26 54 98 49 16 253 WNW 5
40 87 94 43 5
274 NW 7
51 82 58 35 13 246 NNW 3
68 136 68 20 2
297 TOT 87 574 1066 646 266 71 2710 Hours of Calm Data:
0 11ours ofInvalid Data:
38 I
Page 12 of 15
TABLE 4 (continued)
Union Electric - Callaway Plant Report Dateffime: 15-APR-199714:34:04.35 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: E Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
4.
24 63 40 0
0 131 NNE 5
26 73 23 1
0 128 NT 7-58 76
.7 0
-0 148 ENT 3
31 53 18 0
0 105 E
4 26 73 21 2
0 126 ESE 4-19 106 40 6
1 176 SE 1
19 119 108 14 0
261 SSE 3
11 110 187 29 14 354 S
-1 17 85 164 36 1
304 SSVV 1
18 49 107 19 5
199 SW 3
16 45 28 9
5 106 WSW l
23 46 29 10 7
116 W
1 21 57 76 15' '
5-175 WNW 3
17 63 83 21 3
190 NW 5
28 102 79 7
1 222 NNW 2
37 106 79 16 0
240 TOT 48 391 1226 1089 185 42 2981 Hours of Calm Data:
0 Hours of Invalid Data:
26 Page 13 of 15 e.
TABLE 4 (continued)
~
I Union Electric - Callaway Plant Report Date/ rime: 15-APR-199714:34:04.35 Meteorological Data Totals of Hours at Each Wind Speed & Direction 1-JAN-1996 00:00:00.00 to 31-DEC-1996 23:00:00.00 Stability Class: F Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N
0 5
17 5
0 0
27 NNE O
11 14 12 0
0 37 NE 2
15 23 3
0 0
43 ENE O
7 34 8
0 0
49 E
1 8
64 9
0 0
82 ESE 1
8 57 14 0
0 80 SE O
10 53 39 1
0 103 SSE 3
13 82 69 1
0 168 S
1 10 69 38 1
0 119 SSW 2
8 50 31 3
0 94 SW l
6 29 34 0
0 70 l
WSW 2
11 26 12 3
0 54 W
2 12 22 17 1
0 54 l'
WNW 0
10 12 12 0
0 34 NW 2
3 18 23 1
0 47 NNW 0
16 24 16 0
0 56 TOT 17 153 594 342 11 0
1117 Hours of Calm Data:
0 Hours ofInvalid Data:
44 gg I
Page 14 of 15
Union Electric - Callaway Plant Report Date/ Time: 15-APR-1997.14:34:04.35 i
t Meteorological Data Totals of Hours at Each Wind Speed & Direction l-JAN-1996 00:00:00.00 to 31-DEC-1996 2'3:00:00.00 Stability Class: G
. Wind Speed at 60.00 Meter Level (MPH) 1-3 4-7 8-12 13-18 19-24
>24 TOTAL i
N 0
9 5
4 0
0 18 NNE O
8 15 8
0 0
31 NE O
4 18 1
0 0
23 ENE 1
4 16 10 0
0 31 l
E 1
4
.16 3
0 0
24 f
ESE.
0 4
11 1
0 0
16 SE 1
2 13 5
0 0
21 i
SSE O
8 20 14 2-0 44 S
.0 11 23 17 6
0 57 i
SSW 0
5 20~
7 0
0 32 4
SW 0
4 16 12 0
0 32 WSW 0
8 9
4 0
.0 21 W
0 7
3 1
0 0
11 WNW 0
4 6
0 0
0 10 NW 0
0 4
4 1
0 9
NNW 0
2 8
6 0
0 16 TOT 3
84 203 97 9
0 396 Hours of Calm Data:
0 Hours ofInvalid Data:
67 Hours of Good Data:
8412 = 95.8% of Total Hours i
i Page 15 of 15
TABLE 5 DOSE AT THE SITE BOUNDARY AND TO THE NEAREST RESIDENT FROM GASEOUS EFFLUENTS SITE BOUNDARY NEAREST RESIDENT LOCATION: 1.40 km SSW LOCATION: 1.90 km WSW AGE GitOUP: CHILD AGE GROUP: CHILD ORGAN UNITS DOSE
% LIMIT (a)
DOSE
% LIMIT (b)
- 1. GAMMA AIR DOSE
- MRAD 2.58E-03 0.03 1.51E-03 N/A
- 2. BETA AIR DOSE
- MRAD 6.26E-03 0.03 3.68E-03 N/A
- 3. WHOLE BODY "*
MREM 2.31E-03 N/A 1.36E-03 N/A
- 4. SKIN *"
MREM 6.32E-03 N/A 3.71E-03 N/A
- 5. BONE "
MREM 1.39E-05 N/A 2.55E-05 0.00
- 6. LIVER "
MREM 2.31E-03 N/A 1.20E-02 0.08
- 7. TOTAL BODY "
MREM 2.31E-03 N/A 1.20E-02 0.08
- 8. THYROID "
MREM 2J6E-03 N/A 1.73E-02 0.12
- 9. KIDNEY **
MREM 2.31E-03 N/A 1.20E-02 0.08
- 10. LUNG **
MREM 2.51E-03 N/A 1.20E-02 0.08 ll GI-LLI **
MREM 2.31E-03 N/A 1.20E-02 0.08
- Dose from Noble Gases only
" Dose from Tritium, Radiciodines, and Paniculates only i
- Dose from Noble Gases plus Ground Plane dose (a) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 10 mrad gamma air dose and 20 mrad beta air dose.
(b) Annual dose limits of Offsite Dose Calculation Manual (APA-ZZ-01003) of 15 mrem to any organ from I-131.1-133, H-3 and particulate radionuclides with halflives greater than 8 days.
t Page1ofI
. ~ - _
.. - _.. ~. _ _ _...
h TABLE 6 1
DOSE TO THE MEMPER OF THE PUBLIC FROM ACTIVITIES i
Wi1HIN THE SITE BOUNDARY t
EFFLUENT DIRECT DIRECT TOTAL DOSE WITHIN RADIATION RADIATION DOSE THE SITE FROM THE FROM OUTSIDI FOR THE ORGAN UNITS BOUNDARY UNIT TANKS YEAR I. SKIN MREM 1.58E-03 N/A N/A 1.58E-03
- 2. BONE MREM 5.09E-06 8.79E-03 2.10E-03 1.09E-02
- 3. LIVER MREM 7.39E-04 8.79E-03 2.10E-03 1.16E-02
- 4. TOTAL BODY MREM 1.31E-03 8.79E-03 2.10E-03 1.22E-02
- 5. THYROID MREM 7.48E-04 8.79E-03 2.10E-03 1.16E-02
- 6. KIDNEY MREM 7.39E-04 8.79E-03 2.10E-03 1.16E-02
- 7. LUNG MREM 7.39E-04 8.79E-03 2.10E-03 1.16E-02
- 8. GI LLI MREM 7.39E-04 8.79E-03 2.10E-03 1.16E-02
)
l l
)
Page1ofI
TABLE 7 TOTAL DOSE DUE TO THE URANIUM FUEL CYCLE (MEMBER OFTHE PUBLIC)
DOSE FROM TOTAL DOSE DOSE ATTHE ACTIVITIES TO THE RESIDENCE WITHIN SITE MEMBER OF ORGAN UNITS LOCATION BOUNDARY THE PUBLIC
% LIMITS *
- 1. SKIN MREM 1.86E-03 1.58E-03 3.44E-03 0.01
- 2. BONE MREM 8.86E 1.09E-02 1.09E-02 0.04
- 3. LIVER MREM 3.45E-03 1.16E-02 1.5IE-02 0.06
- 4. TOTAL BODY MREM 4.13E-03 1.22E-02 1.63E-02 0.07
- 5. THYROID MREM 4.68E-03 1.16E-02 1.63E-02 0.02
/
- 6. KIDNEY
. MREM 3.46E-03 1.16E-02 1.51E-02 0.06
- 7. LUNG MREM 3.45E-03 1.16E-02 1.51E-02
~
0.06
- 8. GI LLI MREM 3.45E-03 1.16E-02 1.51E-02 0.06
- Annual dose limits from 40CFR190.10(a) of 25 mrem whole body,75 mrem to the thyroid, and 25 mrem to any other organ.
Page1ofI
. _. ~.
I TABLE 8 DOSE DUE TO LIQUID EFFLUENTS (MEMBER OF THE PUBLIC) 1996 l
l i
ORGAN UNITS DOSE LIMIT *
% LIMIT l
2
- 1. BONE MREM 6.14E-03 10.00 6.14E-02
- 2. LIVER MREM 1.10E-02 10.00 1.10E-01
- 3. TOTAL BODY MREM 9.59E-03 '
3.00 3.20E-01
- 4. THYROID -
MREM 2.14E-02 10.00 2.14E-01 4
- 5. KIDNEY MREM 5.61E-03 10.00 5.61E-02 l
- 6. LUNG MREM 3.91E-03 10.00 3.91E-02
- 7. GI-LLI MREM 1.66E-01 10.00 1.66E+00 e
i
)-
- Annual dose limits of APA-ZZ-01003, Section 9.4.1.1.
i I
i t
k Page1ofI
ATTACHMENT 1 APA-ZZ-01003, OFFSITE DOSE CALCULATION MANUAL, REVISION 6
_ _. _ _