ML20108C114
| ML20108C114 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1995 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCV-765-B, NUDOCS 9605060176 | |
| Download: ML20108C114 (150) | |
Text
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l l Georgia Power Cornpany 40 inverness Center Parkway Post Offce Box 1295 Birmingham. Alabama 35201 Telephone 205 877-7122 C. K. McCoy Georgia Power i Vice Presdent, Nuclear Vogtle Pro;ect the southern electnc system May 1, 1996
! LCV-765-B Docket Nos. 50-424 50-425 i
l U. S. Nuclear Regulatory Commission l . ATTN: Document Control Desk l Washington, D. C. 20555 l
VOGTLE ELECTRIC GENERATING PLANT 1995 ANNUAL REPORT - PART 2 i Gentlemen:
l 'In accordance with the applicable regulatory requirements, Georgia Power Company hereby submits Part 2 of the 1995 Annual Report of operating information.
The remainder of the 1995 reports not previously submitted are included.
Sincerely, l
. /Ml '
j C. K. McCoy i
l CKM/JLL/gmb Enclosure Annual Report - Part 2 xc: Georgia Power Company U. S. Nuclear Regulatory Commission Mr. J.B. Beasley, Jr. Mr. S. D.Ebneter, Regional Administrator Mr. M. Sheibani Mr. L. L. Wheeler, Licensing Project Manager, NRR.
Mr. M. C. Nichols Mr. C. R. Ogle, Senior Resident inspector, Vogtle NORMS State of Georgia American Nuclear Insurers
} Mr. J. L. Setser, DNR Mr. L. Cross i 060055 l
9605060176 951231 4 DR ADOCK 0500 I
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l VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 !
NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 1995 ANNUAL REPORT- PART 2 l
TABLE OF CONTENTS l
- 1. INTRODUCTION i
II. ANNUAL ENVIRONMENTAL OPERATING REPORT 111. ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT IV. ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
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I VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 1995 ANNUAL REPORT- PART 2
- INTRODUCTION j The Vogtle Electric Generating Plant Units 1 and 2 are powered by pressurized water reactors, each rated at 3565 megawatts thermal. It is located on the Savannah River in Burke County Georgia,34 miles southeast of Augusta. The Unit 1 operating license was received on January 16,1987 and commercial operation started on May 31,1987. Unit 1 l is operating in its seventh fuel cycle. Unit 2 received its operating license on February 9, t
1989, began commercial operation on May 19,1989. Unit 2 is operating in its fifth fuel cycle.
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11 VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 1995 ANNUAL REPORT- PART 2 ANNUAL E.NVIRONMENTAL OPERATING REPORT (NONRADIOLOGICAL)
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SPECIFICATION In'accordance with Section 5.4.1 of the Vogtle Electric Generating Plant (VEGP)
Environmental Protection Plan (Nonradiological), Appendix B to Facility Operating License Nos. NPF-68 and NPF-81, this report is submitted describing implementation of the Environmental Protection Plan for the calendar year 1995.
REPORTING REOUIREMENTS A. Summaries and Analyses of Results of Environmental Monitoring Activities for the !
Reponing Period !
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- 1. Aquatic Monitoring - Liquid efiluent monitoring was performed in accordance !
with National Pollutant Discharge Elimination System (NPDES) Permit GA
' 0026786; there was no additional requirement for aquatic monitoring during l 1995. Three minor NPDES permit noncompliance events were reported to the ' j State of Georgia during 1995. )
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- 2. Terrestrial Monitoring - Terrestrial monitoring is not required.
- 3. Maintenance of Transmission Line Corridors
- a. Corridor reclearing was conducted on the VEGP-Thalman 500-kV line in 1995. Maintenance work was performed with rotary mowers equipped with low ground pressure tires. In cultural resource areas, clearing was conducted by hand utilizing chain saws and brush axes where necessary.
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There was no herbicide usage associated with any corridor maintenance ;
during 1995.
1 There were no other transmission corridor maintenance activities conducted '
on VEGP-related transmission lines during 1995.
- b. There were no clearing or maintenance activities conducted within the Ebenezer Creek or Francis Plantation areas during 1995.
- c. Routine maintenance activities within the designated cultural properties along transmission line corridors were conducted in accordance with the Final Cultural Resources Management Plan.
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- 4. Noise Monitoring - There were no complaints received by Georgia Power Company during 1995 regarding noise along the VEGP-related, high-voltage transmission lines.
B. Comparison of the 1995 Monitoring Activities with Preoperational Studies, Operational Controls, and Previous Monitoring Reports These programs were not required because no nonradiological environmental monitoring programs were conducted during the reporting period beyond those performed in accordance with NPDES Permit No. 0026786 referenced in Section A above.
C. Assessment of the Observed Impacts of Plant Operations on the Environment There were no significant adverse environmental impacts associated with plant operations during 1995.
D. Environmental Protection Plan (EPP) Noncompliance and Corrective Actions There were no EPP noncompliances during 1995.
E. Changes in Station Design or Operations, Tests, or Experiments Made in Accordance with EPP Subsection 31 which Involved a Potentially Significant Unreviewed Environmental Question There were no changes, tests, or experiments in 1995 which involved a potentially significant unreviewed environmental question.
F. Nonroutine reports Submitted in Accordance with EPP Section 5.4.2 There were no nonroutine reports submitted in 1995.
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l Ill l VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 !
1995 ANNUAL REPORT- PART 2 i i
ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT :
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TABLE OF CONTENTS SECTION TITLE PAGE
1.0 INTRODUCTION
1-1 2.0
SUMMARY
DESCRIPTION 2-1 l 3.0 RESULTS
SUMMARY
3-1 4.0 DISCUSSION OF RESULTS 4-1 4.1 Airborne 4-4 l 4.2 Direct Radiation 4-6 4.3 Milk 4-8 4.4 Vegetation 4-9 l' 4.5 River Water 4-10 4.6 Drinking Water 4-12
! 4.7 Fish 4-15 l 4.8 Sediment 4-16 l
l 5.0 INTERLABORATORY COMPARISON PROGRAM 5-1 1 j
6.0 CONCLUSION
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t LIST OF TABLES TABLE TITLE PAGE ,
i 2-1
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2-2
! 2-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 2-7 ,
1 l 3-1 RADIOL .OGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
3-2 l 4-1 LAND USE CENSI RESULTS 4-3 l
5-1 INTERLABORATORY COMPARISON PROGRAM RESULTS 5-2
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LIST OF FIGURES FIGURE TITLE PAGE 2 TERRESTRIAL STATIONS NEAR SITE BOUNDARY 2-10 2-2 TERRESTRIAL AND AQUATIC STATIONS )'
WITHIN SIX MILES 2-11 2-3 TERRESTRIAL STATIONS BEYOND SIX MILES 2-12 2-4 DRINKING WATER STATIONS 2-13 i
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i ACRONYMS A2LA American Association of Laboratory Accreditation ASTM American Society for Testing and Materials CL Confidence Level EL Environmental Laboratory EPA Enviromnental Protection Agency GPC Georgia Power Company MDC Minimum Detectable Concentration MDD Minimum Detectable Difference NA Not Applicable NDM No Detectable Measurement (s)
NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile SRS Savannah River Site TLD Thermoluminescent Dosimeter i TS Technical Specifications VEGP Alvin W. Vogtle Electric Generating Plant i
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1.0 INTRODUCTION
The objectives of the Radiological Environmental Monitoring Program (REMP) are to ascertain the levels of radiation and concentrations of radioactivity in the environs of the Alvin W. Vogtle Electric Generating Plant (VEGP) and to assess any radiclogical impact upon the environment due to plant operation.
l The bases for such an assessment include appropriate comparisons between results obtained at control stations (locations where radiological levels are not expected to be significantly affected by plant operation) with those obtained at indicator stations (locations where it is anticipated that radiological levels are more likely to be affected by plant operation), and comparisons between results obtained during preoperation with those obtained during operation.
l The preoperational stage of the REMP started in August of 1981 when initial collections of samples were made. There was a phase-in period of a few years before the preoperational program was fully implemented. The transition from the preoperational stage to the operational stage hinged about initial criticality for Unit I which occurred on March 9,1987.
i l The REMP is conducted in accordance with Technical Specifications (TS) 6.7.4.g ;
l and Chapter 4 of the Offsite Dose Calculation Manual (ODCM). The REMP -
activities for 1995 are reported herein in accordance with TS 6.8.1.3 and ODCM 7.1. All dates in this report are for 1995 unless otherwise indicated.
1 l A summary description of the REMP is provided in Section 2_of this report; maps showing the sampling stations are keyed to a table indicating the direction and distance of each station from a point midway between the two reactors. An annual summary of the main laboratory analysis results obtained from the samples utilized for environmental monitoring is presented in Section 3. A discussion of the results, including assessments of any radiological impacts upon the .
environment and the results of the land use census and the river survey, is provided in Section 4. The results of the Interlaboratory Comparison Program are presented in Section 5. Conclusions are stated in Section 6.
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2.0
SUMMARY
DESCRIPTION l
A summary description of the REMP is provided in Table 2-1. This table portrays the program in the manner by which it is being regularly carried out. Table 2-1 is essentially a copy of ODCM Table 4-1 which delineates the program's requirements. Sampling locations required by Table 2-1 are described in Table 2-2 and are shown on maps in Figures 2-1 through 2-4. This description of the sample locations closely follows the table and figures in ODCM 4.2.
In accordance with ODCM 4.1.1.2.1, deviations from the required sampling schedule as set forth in Table 2-1 are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction or otherjust reasons. Any deviations are accounted for in the discussions for the particular sample types in Section 4.
All laboratory analyses were performed by Georgia Power Company's (GPC) ,
Environmental Laboratory (EL) in Smyrna, Georgia. Since 1987, the EL has been l accredited by the American Association of Laboratory Accreditation (A2LA) for radiochemistry. The A2LA is a nonprofit, nongovernmental, public service, membership society dedicated to the formal recognition of competent laboratories and related activities. Accreditation is based upon internationally accepted criteria for laboratory competence'.
- 1. ISO /IEC Guide 25,1990, " General Requirements for the Competence of Calibration 4 and Testing Laboratori.:s" 2-1 l
TABLE 2-1 (SilEET 1 OF 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Samnle Samnles and Samnle Locatians Collection Frequency ofAnnivsis i i
- 1. Direct Radiation Thirty nine routine monitoring Quarterly Gamma dose, quarterly stations with two or more dosimeters placed as follows:
An inner ring of stations, one in each meteorological sector in the general area of the site boundary; An cuter ring of stations, one in each meteorological sector at approximately 5 miles from i the site: and Specialinterest areas, such as population centers, nearby recreation areas, and control stations, t
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t TABLE 2-1 (SHEET 2 OF 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i Exposure Pathway Number of Representative Sampling and Type and Frequency ,
and/or Samole Samnles and Samnie Locations Collection Freauency ofAnalysis
- 2. Airborne Radioiodine and Samples from seven locations: Continuous sampler Radioiodine canister:
Particulates operation with sample I-131 analysis, weekly ,
4 Five locations cicse to the collection weekly, or site boundary in ditTerent . more frequently if Particulate sampler-.
sectors; required by dust Gross beta analysis (1) -
loading following filter change r A community having the highest and gamma isotopic calculated annual average analysis (2) ofcomposite ground-level D/Q: and (by location), quarterly Y
w A control location near a population center at a distance of about 14 miles.
- 3. Waterbome i
- a. Surface (3) One sample upriver Composite sample over Gamma isotopic analysis (2),
one month period (4) monthly. Composite for .
Two samples downriver tritium analysis, quarterly
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.j TABLE 2-1 (SHEET 3 OF 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and'or Samnie Samoles and Samole Locations Collection Freauency ofAnalysis
- b. Drinking Two samples at each of the two Composite sample of I-131 analysis on each sample nearest water treatment plants river water near the when the dose calculated for that could be affected by Intake ofeach water the consumption of the water plant discharges treatment plant over is greater than 1 mrem per '
two week period (4) year (5). Composite for Two samples at a control when I-131 analysis gross beta and gamma isotopic location is required for each analyses (2) on raw water, sample; monthly monthly. Gross beta, gamma composite otherwise; Isotopic and I-131 analyses and grab sample of on grab sample of finished finished water at water, monthly. Composite for each water treatment tritium analysis on raw and !
[ plant every two weeks finished water, quarterly.
or monthly, as appropriate.
- c. Sediment from One sample from downriver area Semiannually Gamma isotopic analysis (2),
Shoreline with existing or potential semiannually recreational value One sample from upriver area '
with existing or potential recreational value
- 4. Ingestion
- a. Milk Two samples from milking Biweekly Gamma isotopic analysis (2,7), .
animals (6) at control biweekly locations at a distance of about 10 miles or more
TABLE 2-1 (SilEET 4 OF 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Samole Samples and Samole Locations Collection Frequency ofAnalysis
- b. Fish At least one sample of any Semiannually Gamma isotopic analysis (2) commercially or recreationally on edible portions, important species near the semiannually plant discharge At least one sample of any commercially or recreationally important species in an area not influenced by plant discharges At least one sample of any During the spring Gamma isotopic analysis (2)
[ anadromous species near the spawning season on edible portions, annually -
plant discharge
- c. Grass or One sample from two onsite Monthly during the Gamma isotopic analysis (2,7),
Leafy locations near the site growing season monthly Vegetation boundary in different sectors One sample from a control
!osation at a distance of about 17 miles
TABLE 2-1 (SHEET 5 OF 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Airborne paniculate sample filters shall be analyzed fer gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.
(2) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.
(3) The upriver sample is taken at a distance beyond significant influence of the discharge. The downriver samples are taken in areas beyond but near the mixing zone.
(4) Composite sample aliquots shall be collected at time intervals that are very shod (e.g., hourly) relative to the compositing period (e.g., monthly) to assure obtaining a representative sample.
(5) The dose shall be calculated for the maximum organ and age group, using the methodology and l parameters in the ODCM.
(6) A milking animal is a cow or goat producing milk for human consumption.
(7) If the gamma isotopic analysis is not sensitive enough to meet the Minimum Detectable Concentration (MDC) for 1-131, a separate analysis for I-131 may be performed.
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TABLE 2-2 (SHEET 1 OF 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction Distance Sample Number Tvoe(1) Location (2) (miles)(2) Type (3) 1 I Hencock Landing Road N 1.1 D 2 i River Bank NNE 0.8 D 3 I Discharge Area NE 0.6 A 3 i River Bank NE 0.7 D 4 i River Bank ENE 0.8 D 5 I River Bank E 1.0 D 6 i Plant Wilson ESE 1.1 D 7 i Simulator Building SE 1.7 ADV 8 i River Road SSE 1.1 D 9 I River Road S 1.1 D 10 I Meteorological Tower SSW 0.9 A 10 1 River Road SSW l.1 D 11 1 River Road SW l.2 D 12 I River Road WSW l.2 AD 13 I River Road W l.3 D 14 i River Road WNW l.8 D 15 I Hancock Landing Road NW l.5 DV 16 I Hancock Lt.nding Road NNW l.4 AD 17 O Savannah River Site (SRS), River Road N 5.4 D 18 O SRS. n Area NNE 5.0 D 19 O SR3, Road '.13 NE 4.6 D 20 O SRS, T. o A.13.1 ENE 4.8 D 21 O SRS, Road A.17 E 5.3 D 22 O River Bank ESE 5.2 D 23 O River Road SE 4.6 D 24 O Chance Road SSE 4.9 D 25 O Chance Road near Highway 23 S 5.2 D l
26 O Highway 23 and Ebenezer Church Road SSW 4.6 D
! 27 O Highway 23 opposite Boll Weevil Road SW 4.7 D 28 O Thomas Road WSW 5.0 D i
29 O Claxton-Lively Road W 5.1 D 30 0 Nathaniel Howard Road WNW 5.0 D 31 O River Road at Allen's Chapel Fork NW 5.0 D 32 O River Bank NNW 4.7 D 33 O Hunting Cabin SE 3.3 D 35 O Girard SSE 6.6 AD 2-7
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TABLE 2-2 (SHEET 2 OF 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction Distance Sample l Number Type (1) Location (2) (miles)(2) Tspe (3) l 36 C GPC Waynesboro Op HQ WSW 13.9 AD i 37 C Waynesboro Substation WSW 6.7 DV 43 O Employee's Rec Area SW 2.2 D 47 C Oak Grove Church SE 10.4 D 48 C McBean Cemetery NW 10.2 D 80 C Augusta Water l l
Treatment Plant NNW 29.0 W(4) l 81 C Savannah River N 2.5 F(5)S(6) I l
j 82 C Sav River (RM 151.2) NNE 0.8 R i
83 i Sav River (RM 150.4) ENE 0.8 RS(6) l 84 O Sav River (RM 149.5) ESE 1.6 R
! 85 i Savannah River ESE 4.3 F(5) 87 i Beaufort-Jasper County Water Treatment Plant, l Beaufort, SC SE 74 W(7) j 88 I Cherokee Hill Water l Treatment Plant, I Port Wentworth, GA SSE 71 W(8) 98 C W. C. Dixon Dairy SE 9.8 M 99 C Boyceland Dairy W 20.9 M l
l TABLE NOTATIONS l (1) Station Types l C - Connol I - Indicator 0 - Other (2) Direction and distance are reckoned from a point midway between the two reactors. ;
(3) Sample Types !
A - Airborne Radioactivity D - Direct Radiation F - Fish M - Milk R - River Water S - River Shoreline Sediment W - Drinking Water V - Vegetation 2-8
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TABLE 2-2 (SHEET 3 OF 3)
RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS TABLE NOTATIONS (CONTINUED)
(4) The intake for the Augusta Water Treatment Plant is located on the Augusta Canal. The entrance to the canal is at River Mile (RM) 207 on the Savannah River. The canal efTectively parallels the river. The intake to the pumping station is about 4 miles down the canal and only a tenth of a mile from the river (across land).
(5) A 5 mile stretch of the river is generally needed to obtain adequate fish samples. Samples are normally gathered between RM 153 and 158 for upriver collections and between RM 144 and 149.4 for downriver collections.
(6) Sediment is collected at locations with existing or potential recreational value. Because high water, shifting of the river bottom, or other reasons could cause a suitable location for sediment collections to l become unavailable or unsuitable, a stretch of the river between RM 148.5 and 150.5 was designated for downriver collections while a stretch between RM 153 and 154 was designated for upriver collections. In practice, collections are normally made at RM 150.2 for dowariver collections and RM 153.3 for upriver collections.
(7) The intake for the Beaufort-Jasper County Water Treatment Plant is located at the end of a canal which
, begins at RM 39.3 on the Savannah River. This ir.take is about 16 miles by line of sight down the l canal from its beginning on the Savannah River.
(8) The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.
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l AUGUST A W At t R TRE ATMINI PL ANT E
ji i MMHM%Up sav4NNAs Rivin PLANT VEGP (
N Cond to Supptr Rino Water to Seeviert q
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I 3.0 -RESULTS
SUMMARY
In accordance with ODCM 7.1,2.1, summarized and tabulated results for all of the regular samples collected for the year at the designated indicator and control stations are presented in Table 3-1 in a format similar to that found in Table 3 of the Nuclear Regulatory Commission (NRC) Radiological Assessment Branch Technical Position, Revision 1, November 1979. Since no reportable occurrences l were called for during the year, the column entitled " Number of Reportable l Occurrences" has been excluded from Table 3-1. Results for samples collected at locations other than indicator or control stations or in addition to those stipulated i by Table 2-1 are discussed in Section 4 for the particular sample type.
Only the naturally occurring radionuclides which are found in the plant's effluent !
releases need be reported. The radionuclide, Be-7, which occurs abundantly in nature is also produced in the reactors. Minuscule quantities are found in the liquid releases. No other naturally occurring radionuclides have been found in the ,
plant's effluent releases. Hence, the radionuclides ofinterest for the samples !
monitoring liquid releases (river water, drinking water, fish and river shorehne :
sediment) are man-made radionuclides plus Be-7, while only man-made l radionuclides are ofinterest for the other REMP samples.
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TABLE 3-1 (SHEET I OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)
(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)
Airborne Gross Beta 10 21.1 No.12 21.4 20.7 Particulates 310 7-38 River Rd 8-32 9-31 (fCi/m3) (258/258) 12 miles (52/52) (52/52)
WSW Gamma Isotopic 24 f b Cs-134 50 NDM(c) NDM NDM Cs-137 60 NDM NDM NDM Airborne I-131 70 NDM NDM NDM Radioiodine 310 (fCi/m3) i Direct Gamma Dose NA(d) 12.0 No. 36 15.3 12.5 Radiation 80 9-17 GPC Op Hq 15-16 10-16 (mR/91 days) (64/64) 13.9 miles (4/4) (16/16)
WSW
- l
b b
G TABLE 3-1 (SI1EET 2 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 i Burke County, Georgia !
Indicator Location with liighest Control !
Medium or Type and Minimum Locations Annual Mean Locations l Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b) i (Unit of ofAnalyses Concentration Range Distance & Range Range ;
Measurement) Performed (MDC)(a) (Fraction) . Direction (Fraction) (Fraction)
- t Milk Gamma Isotopic (pC /l) 52 l Cs-134 15 NA NDM NDM Cs-137 18 NA NDM NDM ,
Ba-140 60 NA NDM NDM-w La-140 15 NA NDM NDM Cs I-131 1 NA NDM NDM l 52 Vegetation Gamma Isotopic (pCi/kg wet) 36 I-131 60 NDM NDM NDM ,
Cs-134 60 NDM NDM NDM f Cs-137 80 57.8 No. 37 179.0 179.0 55-60 Substation 179-179 179-179 (2/24) 16.7 miles (1/12) (1/12)
WSW i
i
TABLE 3-1 (SHEET 3 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with liighest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)
(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)
River Water Gamma Isotopic (pCi/l) 24 Be-7 124 (e) NDM NDM NDM Mn-54 15 NDM !.~uM NDM Fe-59 30 NDM NDM NDM w Co-58 15 NDM NDM NDM E Co-60 15 NDM NDM NDM Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM NDM Nb-95 15 'NDM NDM NDM l-131 15 NDM NDM NDM Cs-134 15 NDM NDM NDM Cs-137 18 NDM NDM NDM Ba-140 60 NDM NDM NDM La-140 15 NDM NDM NDM Tritium 3000 597 No. 83 597 236 8 304-1150 Downriver 304-1150 180-333 (4/4) 0.4 miles (4/4) (3/4)
TABLE 3-1 (SHEET 4 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Loca: ion with Ilighest Control Medium er Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)
(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed iMDC)(a) (Fraction) Directicn (Fraction) (Fraction)
Water Near Gross Beta 4 3.06 No. 80 4.90 4.90 Intakes to 36 0.5-6.6 Augusta 23-8.8 23-8.8 Water (24/24) Upriver (12/12) (12/12)
Treatment 56 miles Plants
, (pCi/l)
Gamma Isotopic Y
m 36 Be-7 124 (e) NDM NDM NDM Mn-54 15 NDM NDM NDM Fe-59 30 NDM NDM NDM Co-58 15 NDM NDM NDM Co-60 15 NDM NDM NDM Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM NDM l-131 (f) 15 NDM NDM NDM Cs-134 15 NDM NDM NDM Cs-137 18 NDM NDM NDM Ba-140 60 NDM NDM NDM La-140 15 NDM NDM NDM
4 TABLE 3-1 (SHEET 5 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)
(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)
Tritium 3000 917 No. 88 987 201 12 634-1230 Port Went 737-1230 201-20I (8/8) Downriver (4/4) (1/4) 122 miles Finished Water Gross Beta 4 2.74 No. 88 2.84 232 i
\** at Water 36 1.4-43 Port Went 1.4-4.3 0.7-3.6
- Treatment Downriver (12/12) (12/12)
(24/24)
Plants 122 miles (pCi/1)
Gamma Isotopic 36 Be-7 124 (e) NDM NDM NDM Mn-54 15 NDM NDM NDM Fe-59 30 NDM NDM NDM Co-58 15 NDM NDM NDM '
Co-60 15 NDM NDM NDM Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM NDM -
t
TABLE 3-1 (SilEET 6 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia f
Indicator Location with flighest Control Medium or Type and Minimum Locations Annual Mean Locations Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)
(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction)
Cs-134 15 NDM NDM NDM Cs-137 18 NDM NDM NDM Ba-140 60 NDM NDM NDM La-140 15 NDM NDM NDM .
Y
Tritium 2000 847 No. 88 941 279 12 527-1200 Port Went 678-1200 279-279 l (8/8) Downriver (4/4) (1/4) 122 miles i
Anadromous Gamma Isotopic Fish I (pCi/kg wet) Be-7 655 (e) NDM NDM NA j Mn-54 130 NDM NDM NA Fe-59 260 NDM NDM NA Co-58 130 NDM NDM NA ,
t
i ,
TABLE 3-1 (SHEET 7 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator - Location with Highest Control Medium or Type and Minimum Locations Annual Mean Locations !
Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)'
(Unit of ofAnalyses Concentration Range Distance & Range Range Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) 3 Co-60 130 NDM NDM NA !
, Cs-134 130 NDM NDM NA Cs-137 150 NDM NDM NA w
do Fish Gamma Isotopic ,.
(pCi/kg wet) 7 Be-7 655 (e) NDM NDM NDM .
Mn-54 130 NDM NDM NDM Fe-59 260 NDM NDM NDM Co-58 130 NDM NDM- NDM [
Zn-65 260 NDM NDM NDM Cs-134 130 NDM NDM NDM Cs-137 150- 125.1 No. 85 125.1 %.I i 31-286 Downriver 31-286 22-250 (3/3) 4.1 miles (3/3) (4/4)
i t
TABLE 3-1 (SHEET 8 OF 9)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia ,
Indicator Location with Ifighest Control Medium or Type and Minimum Locations Annual Mean Locations
- Pathway Sampled Total Number Detectable Mean (b) Name Mean (b) Mean (b)
(Unit of ofAnalyses Concentration Range Distance & Range Range ,
Measurement) Performed (MDC)(a) (Fraction) Direction (Fraction) (Fraction) i Sediment Gamma Isotopic (pCi/kg dry) 4 Be-7 655 (c) 1865 No. 83 1865 1575 1500-2230 Downriver 1500-2230 1430-1720 (2/2) 0.6 miles (2/2) (2/2) w Co-58 43 (e) 42.4 No. 83 42.4 NDM U 42-42 Downriver 42-42 (1/2) 0.6 miles (1/2)
Co-60 70 (e) 267 No. 83 267 NDM 172-361 Downriver 172-361 (2/2) 0.6 miles (2/2)
Cs-134 150 NDM NDM NDM Cs-137 180 357 No. 83 357 123 257-457 Downriver 257-457 122-124 (2/2) 0.6 miles (2/2) (2/2)
l TABLE 3-1 (SilEET 9 OF 9)
ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia NOTATIONS 1
- a. The MDC is defined in ODCM 10.1. Except as noted otherwise, the values listed in this column are the detection capabilities required by ODCM Table 4-3. The values listed in this column are a priori (before the fact) MDCs. In practice, the a posteriori(afler the fact) MDCs are generally lower than the values listed. Any a posteriori MDC greater than the value listed in this column is discussed in Section 4.
- b. Mean and range are based upon detectable measurements only. The fraction of all measurements at a specified location which is detectable is placed in parenthesis.
- c. No Detectable Measurement (s).
- d. Not Applicable.
- e. The EL has determined that this value may be routinely attained under normal conditions. No l value is provided in ODCM Table 4-3.
- f. Item 3 of ODCM Table 4-1 implies that an I-131 analysis is not required to be performed on these samples when the dose calculated from the consumption of water is less then 1 mrem per year.
l l
l l
l 3-10
4.0 DISCUSSION OF RESULTS An interpretation and evaluation, as appropriate, of the laboratory results for each type sample are included in this section. Relevant comparisons were made between the difference in average values for indicator and control stations and the calculated Minimum Detectable Difference (MDD) between these two groups at the 99 percent Confidence Level (CL). The MDD was determined using the standard Student's t-test. A difference in the average values which was less than the MDD was considered to be statistically indiscernible.
l Pertinent results were also compared with past results including those obtained i during preoperation. The results were examined to perceive any trends. To provide perspective, a result might also be compared with its Reporting Level (RL) or Minimum Detectable Concentration (MDC) whose nominal values are found in ODCM Tables 4-2 and 4-3, respectively. Attempts were made to explain any high radiological levels found in the samples. During the year there were no failures in the laboratory analyses for any of the samples in attaining the MDCs required by ODCM Table 4-3.
Unless otherwise indicated, any reference made in this section to the results of a previous period are results which have been purged of any obvious extraneous short term impacts. During preoperation, these included the nuclear weapons test in the fall of 1980 (apparently the last in a series of atmospheric tests conducted on mainland China over a 9 year period), abnormal releases from the Savannah River Site (SRS), and the Chernobyl incident in the spring of 1986. After operation commenced, short term impacts included abnormal releases from SRS during 1987 and 1991.
A significant component of the Cs-137 which has often been found in various samples over the years and continues to be found is attributed to the numerous nuclear weapons tests which were conducted prior to preoperation.
2 All results were tested for conformance to Chauvenet's Criterion to flag any values which might differ from the others in its set by a relatively large amount.
Identified outliers were investigated to determine reason (s) for' deviation from the norm. If due to an equipment malfunction or other valid physical reason, the
- anomalous result was deemed non-representative and excluded from the data set.
- 2. G. D. Chase and J. L. Rabinowetz, Principles of Radioisotope Methodology, (Burgess
- Publishing Company,1962), pages 87-90.
4-1
f l
No datum was excluded for failing Chauvenet's Criterion only. Any exclusions are discussed in this section under the appropriate sample type.
An annual land use census as required by TS 6.7.4.g(2) and ODCM 4.1.2 was conducted on March 28 to determine the locations of the nearest permanent residence, milk animal and garden of greater than 500 square feet producing broad
! leaf vegetation in each of the 16 meteorological sectors within a distance of 5 miles; the locations of the nearest beef cattle in each sector was also determined.
l A milk animal is a cow or goat producing milk for human consumption. Land l within SRS was excluded from the census. To accommodate scheduling, a second land use census was conducted during 1995 on December 12-13. The censi rewits are tabulated in Table 4-1.
l l ODCM 4.1.2.2.1 requires a new controlling receptor in ODCM 3.4.3, if the land I use census identifies a location that yields a calculated dose greater than that l currently being calculated. An analysis of the March 28 census results showed there was none. However, a new controlling receptor (a child in the SSW sector at 4.7 miles receiving dose via the inhalation, ground plane, cow meat and vegetation pathways) was identified from the results of the December 12-13 census. 4 I
ODCM 4.1.2.2.2 requires that whenever the land use census identifies a location j which would yield a calculated dose (via the same ingestion pathway) 20 percent greater than that from a current indicator station, the new location must become a REMP station (if samples are available). None of the gardens from either census
! yielded a calculated dose 20 percent greater than that for any of the current indicator stations for vegetation. No milk animals were found in the censi.
l The annual survey of the Savannah River downstream of the plant for
> approximately 104 miles was conducted on September 19 to identify those who l
use water from the river for purposes of drinking or irrigation. As in all previous surveys, no intakes for drinking water or irrig; tion were observed. This result was corroborated by information obtained from the Georgia Department of Natural Resources on September 22 and the South Carolina Department of Health and l
Environmental Control on October 25; it was confirmed that no water withdrawal permits for drinking water or irrigation purposes had been issued over this stretch
! of the Savannah River . The two water treatment plants used as indicator stations for drinking water are located further downriver.
i J
4-2
. .. . . . . _ ..- . , . . . - . ~ _ . - . - - ... _ _ _ - . .
1 l
i i
TABLE 4-1 j LAND USE CENSI RESULTS Distance in Miles to Nearest Location in Each Sector SECTOR RESIDENCE MILK ANIMAL BEFF CATTLE GARDEN March 28 N 1.2 * * * !
NNE * * * * ;
NE * * *
- ENE-
- E * * *
- ESE 4.2 * *
- SE 4.3
- 4.9
- SSE 4.6 4.6 * -
S 4.3
- 4.6
- SSW 4.7
- 4.4
- i SW 2.9
- 5.0
- WSW l.2
- 2.8 * +
W l.9 * *
- WNW l.8
- 2.2
- NW l.6
- 4.8 5.0 NNW l.4 * *
- December 12-13 ,
i N * * *
- I NNE * * *
- l
-NE * * *
- ENE * * *
- E * * *
- ESE 4.2 * *
- SE 4.3
- 4.9
- SSE 4.6
- 4.6
- S 4.3 * *
- SSW 4.7
- 4.7 4.7 SW 2.9
- 5.0
- WSW l.2
- 2.6 4.8 W 3.7 *
- 4.3 WNW l.8 * *
- NW 1.6
- 1.8 3.9 NNW l.4 * * *
- None within 5 miles and outside the SRS.
i i
l 4-3
I l
4.1 Airborne :
In accordance with Tables 2-1 and 2-2, airborne particulates and airborne radiciodine are collected at 5 indicator stations (Nos. 3,7,10,12 and 16) which encircle the site and are on the site periphery, at a nearby community station (No.
35), and at a control station (No. 36) which is about 14 miles from the plant. At these locations air is continuously drawn in sequence through a Gelman Type A/E glass fiber filter and a SAIC CP-200 charcoal canister in sequence to retain airborne particulates and to adsorb airborne radioiodine, respectively.
The filters and canisters are collected weekly. Each of the air particulate filters is counted for gross beta activity. A gamma isotopic analysis is performed quarterly on a composite of the air particulate filters for each station. Each charcoal canister is analyzed for I-131 by gamma spectroscopy. i During the exposure periods associated with the collections made on July 18 & 25 and August 8, several stations were not operating for a short time due to power outages which were nominally caused by severe weather. The hours each affected station was down are as follows. '
Affected Station July 18 July 25 August 8 No. 3 2.0 0.9 2.5 No. 7 3.3 1.0 2.5 No.10 6.6 4.3 2.5 No.12 3.3 0.9 2.5 l No.16 2.1 No. 36 1.0 i
The gross beta results for the affected samples were tested for conformance with Chauvenet's criterion. The results for Station 16 on July 18 and for Station 3 on July 25 failed the test; these results were therefore deemed unrepresentative and excluded from the data base.
As seen in Table 3-1, the average weekly beta activity during 1995 for the indicator stations was 0.4 fCi/m greater than that for the control station.
However, this difference was not discernible, since it was less than the MDD, 3
l calculated as 2.0 fCi/m . During the 8 year period from 1987 through 1994, the average weekly activity for the year at the indicator stations randomly varied from 3 3 1.0 fCi/m greater than to 0.6 fCi/m less than that for the control station. The average weekly activity for the indicator stations over this entire 8 year period 4
4-4
3
. exceeded that for the control station by less than 0.1 fCi/m . The overall average 3
weekly activity for the indicator stations during preoperation was 0.8 fCi/m greater than that for the control station.
The average weekly gross beta activity in units of fCi/m' for the indicator, control
~
an d community stations during 1995 are compared below with those during the previous years of operation, with the entire preoperation period (which began in September 1981 for the air monitoring stations) and with the range of annual averages during preoperation.
Period Indicator Control Community 1995 21.I' 20.7 20.7 1994 20.1 20.3 19.8 1993 .21.2 21.4- 20.3 l 1992 18.7 19.3 18.0
- j. 1991 19.3 19.2 18.6 1990 19.6 19.4 18.8 1989 19.1 18.2 18.8 1988 24.7 23.7 22.8 1987 23.0 23.5 22.3 Preop Overall 22.9 22.1 21.9 Preop Range 18.1-28.1 18.3-26.5 18.3-26.5 l The average weekly readings for 1995 are seen to be within the range of values found previously. No trends were recognized in these data.
During 1995, no man-made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. During 1987, Cs-3 137 was found in one indicator composite at a level of 1.7 fCi/m . During preoperation, Cs-137 was found in an eighth of the indicator composites and a l seventh of the control composites with average levels of 1.7 and 1.0 fCi/m',
l respectively; the MDC for airborne Cs-137 is 60 ICi/m'. Also, during '
preoperations, Cs-134 was found in about 8 percent of the indicator composites; 3
the average level was 1.2 fCi/m ; its MDC is 50 fCi/m' As during previous years of operation, airborne I-131 was not detected in any sample during 1995. During preoperation, positive results were obtained only during the Chernobyl incident when levels as high as 182 fpi/m' were obtained.
The MDC and RL for airborne I-131 are 70 and 900 fCi/m , respectively. ;
l i
4-5
m _ _ _ -_._._. _ _ _ _ _ . _ _ _ . _ . _ _ _ _ _ _ _
i
! 4.2 Direct Radiation ;
Direct (external) radiation is measured with thermoluminescent dosimeters !
(TLDs). Two Panasonic UD-814 TLD badges are placed at each station. Each badge contains three phosphors which are composed of calcium sulfate (with thulium impurity) crystals. The gamma dose at each station is nominally based upon the average readings of the phosphors from the two badges. The two badges for each station are sealed in a thin plastic bag for protection from moisture while ;
in the field. The badges are nominally exposed for periods of a quarter of a year (91 days).
]
Two TLD stations are established in each of the 16 meteorological sectors about ,
the plant forming two concentric rings. The stations comprising the inner ring (Nos. I through 16) are located near the site boundary, while those comprising the outer ring (Nos.17 through 32) are located at distances of about 5 miles. The 16 stations forming the inner ring are designated as the indicator stations. Each of the 4 control stations (Nos. 36,37,47 and 48) is over 10 miles from the plant. Special interest areas consist of a hunting cabin (No. 33), the town of Girard (No. 35), and the employees' recreational area (No. 43).
As shown in Table 3-1, the average quarterly exposure acquired at the indicator stations (inner ring) during 1995 was 0.5 mR less than that acquired at the control
! stations. This difference was not discernible since it was less than the MDD of 1.0 mR. During the 8 year period from 1987 through 1994, the average quarterly exposure for the year at the indicator stations randomly varied from 0.7 mR greater than to 0.5 mR less than that for the control stations. The average quarterly exposure for the indicator stations over this period has been virtually the same as y that for the control stations. The overall average quarterly exposure for the indicator stations during preoperation was 1.2 mR less than that for the control stations.
The quarterly exposures acquired at outer ring stations during 1995 ranged from 9.8 to 19.5 mR, with an average of 12.3 mR which was 0.3 mR greater than that found for the inner ring. There was no discemible difference between the averages for the inner and the outer ring, since the difference was less than the MDD of 0.7 mR. For the 8 year period beginning in 1987, the average quarterly exposure for the year at the inner ring stations varied from 0.2 to 0.9 mR greater than that at the outer ring stations. The average quarterly exposure for the inner ring stations over j this 8 year period was 0.5 mR greater than that for the outer ring stations. The i
overall average quarterly exposure for the inner ring stations during preoperation j was 0.6 mR greater than that for the outer ring stations.
4-6
i i i I
Listed below for the indicator, control and outer ring stations, are the average ganicily exposures in units of mR obtained during each year of operation, the entire period of preoperation (which began in August 1981 for TLD stations), and the range of annual averages obtained during the calendar years of preoperation.
Period Indicator Control Outer Ring 1995 12.0 12.5 12.3 1994 12.3 12.1 11.9 1993 12.4 12.4 12.1 I
1992 12.3 12.5 12.1 1991 16.9 17.1 16.7 1990 16.9 16.6 16.3 1989 17.9 '18.4 17.2 1988 16.8 16.1 16.0 1987 17.6 17.9 16.7 Preop Overall 15.3 16.5 14.7 Preop Range 15.1-16.9 14.1-18.2 12.5-16.2 i The average quarterly exposures in units of mR at the special interest areas for the same periods as given above are listed below. These exposures are within die -
- range of those acquired at the other stations. l Period Station 33 Station 35 - Station 43 1995 13.3 13.5 12.3 1994 12.6 13.6 12.0 1993 12.9 13.3 12.1 1992 12.8 13.5 12.0 1991 17.3 19.6 17.0 1990 16.8 18.9 16.2 1989 21.2 18.7 17.4 1988 19.7 18.1 14.8 1987 21.3 18.5 15.2 Preop Overall 16.6 15.1 15.3 Preop Range 13.6-19.9 12.6-17.6 13.9-25.0 i
' Although, there were no failures at any station in obtaining a measurement of the quarterly gamma dose during 1995, the reading for TLD 32A for the third quarter was deemed unacceptable as it had a standard deviation greater than the self imposed limit of 1.4. Consequently, the reading for the companion badge only was used to determine the exposure for the third quarter at this station.
4-7
No reason was found for the high standard deviation for TLD 32A for the third quarter. It was visually inspected under a microscope; the glow curve and test results for the anneal data and the element correction factor were reviewed.-
The standard devirtion limit of 1.4 was calculated using a method' developed by the American Society for Testing and Materials (ASTM). The calculation was based upon the standard deviations obtained with the UD-814 badges during 1992.
This limit serves as a flag to evoke an investigation. To be conservative, readings with a greater standard deviation are deleted since the high standard deviation is interpreted as an indication of a suspect TLD.
4.3 Milk l- !
l In accordance with Tables 2-1 and 2-2, milk samples are collected biweekly from two control stations, the W. C. Dixon Dairy (No. 98) and the Boyceland Dairy (No. 99). Gamma isotopic and I-131 analyses are performed on each sample.
Milk has not been available from an indicator station (a location within 5 miles of the plant) since April 1986 when the cow from which milk was being obtained went dry and was subsequently removed from the area. The availability of milk within 5 miles of the plant was meager throughout preoperation and an adequate location is yet to be obtained during operation. As discussed in Section 4.0, no
! milk animals were found in the 1995 land use census.
No man-made radionuclides were found from the gamma isotopic analysis of the milk samples during 1995. During preoperation and each year of operation ;
through 1991, Cs-137 was found in 2 to 6 percent of the samples at levels ranging from 5 to 27 pCi/1. The MDC and RL for Cs-137 in milk are 18 and 70 pCi/l, respectively. During preoperation, Cs-134 was detected in one sample and in the i first year of operation, Zn-65 was detected in one sample.
1-131 was not detected in any of the milk samples during 1995. In 1990, I-131 was reported in two samples but its presence was questionable due to large counting uncertainties. I-131 was not detected during other years of operation.
During preoperation, positive I-131 results were found only during the Chernobyl incident when the levels ranged from 0.53 to 5.07 pCi/1. The MDC and RL for I-131 in milk are 1 and 3 pCi/l, respectively.
l 3. ASTM Special Technical Publication ISD, ASTM Manual on Presentation of Data and
- Control Chart Analysis, Fourth Revision, Philadelphia, PA, October 1976.
4-8 1
I I
4.4 Vegetation In accordance with Tables 2-1 and 2-2, gamma isotopic analysis is performed on each grass sample collected monthly at two indicator stations which are located onsite near the site boundary in different meteorological sectors (Nos. 7 and 15) and at one control station located about 17 miles from the plant (No. 37).
The results presented in Table 3-1 show that as usual Cs-137 was the only man-made radionuclide detected during 1995. The average value for the two positive results found at the indicator stations was 121.2 pCi/kg wet less than the one positive result found at the control station. It was determined by a modified t-test calculation that this difference was not discernible.
The average level of Cs-137 found in vegetation samples in units of pCi/kg wet along with the fraction of detectable measurements at the indicator and control stations is shown below for each year of operation and the period of preoperation.
Indicator Stations Control Station Period Average Fraction Average Fraction 1995 57.8 0.083 179.0 0.083 1994 20.7 0.083 57.4 0.083
! 1993 46.4 0.333 34.1 0.083 l 1992 38.1 0.250 144.0 0.083 1991 35.3 0.208 62.4 0.083 1990 30.0 0.083 102.0 0.167 1989 9.7 0.042 0.0 0.000 1988 38.7 0.280 0.0 0.000 1987 24.4 0.318 61.5 0.250 Preop 54.6 0.573 43.7 0.193 The results for 1995 are seen to be a little greater but on the smne order as those found previously. No trend was recognized in these data. The MDC and RL for Cs-137 in vegetation samples are 80 and 2000 pCi/kg wet, respectively.
To enhance the statistical base for the indicator stations, samples continued to be collected on a trial basis during the year from two additional grass plots; one is in the E sector at 0.9 milesjust north of Plant Wilson, the other is in the SW sector at 1.2 miles adjacent to Gate 1. Positive results ranging from 24.6 to 167 pCi/kg wet were found in 5 of the 12 samples collected at the Plant Wilson location; the average positive result was 63.4 pCi/kg wet. Only one of the 12 samples collected at the Gate I location had a positive result which was 63.7 pCi/kg wet.
4-9
During operation, Cs-137 has been the only man-made radionuclide detected in vegetation samples. During preoperation as a consequence of the Chernobyl incident, I-131 was found in nearly all the samples collected (some at elevated levels) for a period of several weeks. During the preoperation period, Cs-137 was also found in nearly all the samples collected and Co-60 was found in one of the samples.
4.5 River Water i
Surface water is composited from the Savannah River at three locations using l ISCO automatic samplers. Small quantities are collected at intervals not l exceeding a few hours. River water samples collected by these machines are l picked up monthly; quarterly composites are made from the monthly collections.
l The collection points consist of a control station (No. 82) which is located about
! 0.4 miles upriver of the plant intake structure, an indicator station (No. 83) which l is located about 0.4 miles downriver of the plant discharge structure, and a special L
. station (No. 84) which is located approximately 1.3 miles downriver of the plant discharge structure. A discernible increase in the radiological levels found in samples collected at the indicator station over those collected at the control station might be attributed to plant radiological releases. Radiological levels monitored at the special station might represent those for the river as a whole (plant releases combined with those from other sources.)
A gamma isotopic analysis is conducted on each monthly collection. As in all l previous years of operation, there were no gamma emitter radionuclides ofinterest detected in the river water samples collected during 1995, A tritium analysis is performed on each quarterly composite. As indicated in Table 3-1, the average level found at the indicator station was 361 pCi/l greater than that found at the control station. However, this difference was not discernible since it was less than the calculated MDD of 766 pCi/l and on this basis the increase is not attributed to plant releases. At the special station, the results ranged from 364 to 1040 pCi/1. The MDC for tritium in river water is 3000 pCi/l; the RL is 10 times greater.
Listed below for each year of operation are the average tritium levels found at the special, indicator and control stations, along with the increase in the average level at the indicator station over that for the control station, the MDD between these two stations, and the total liquid releases of tritium from the plant. All of these values are in units of pCill except for the releases which are in units of Ci.
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Year Special Indicator Control Increase MDD Releases 1995 699 597 236 361 766- 968 1994 774 1258 257 1001 2009 1052 1993 616 712 238 474 1526 761 l 1992 929 1064 371 693 714 1481 1991 1298 1299 828 471 626 1094 1990 1081 1142 392 750 766 1172 1989 1268 1293 538 755 518 918
! 1988 1430 843 427 416 271 390 1987 1411 680 524 156 416 321 l
The following observations are noted regarding the above data tabulation.
1, The curies of tritium released by the plant (Releases) increase the overall tritium level in the river and these releases could account for the increases in the levels found at the indicator station over those at the control station. However, for all the years except 1988 and 1989, the increases are less than the MDD and are therefore considered non-discernsba.
- 2. There was a discernible difference between the indicator and control stations only during 1988 and 1989.
- 3. There is not a good correlation between the releases and the increases.
- 4. The overall tritium levels in the river have generally diminished during the past few years as compared with those during the early years of operation.
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- 5. In 1987 and 1988, the tritium level at the special station was somewhat j greater than that at the indicator station; whereas in recent years the level at the special station has become less than or is about the same as that at !
the indicator stations. This indicates that the contribution from other tritium sources has diminished while plant releases have become a larger percentage of the total source. i The annual downriver survey of the Savannah River to determine if river water is being used for purposes of drinking or irrigation is discussed in Section 4.0.
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4.6 Drinking Water Samples are collected at a control station (No. 80), the Augusta Water Treatment Plant in Augusta, Georgia, which is located about 56 miles upriver, and at two indicator stations (Nos. 87 and 88), the Beaufort-Jasper County Water Treatment l Plant near Beaufort, South Carolina and the Cherokee Hill Water Treatment Plant near Port Wentworth, Georgia, which are respectively located approximately 112 and 122 miles downriver. These upriver and downriver distances in river miles are the distances from the plant to the point on the river where water is diverted to the intake for each of these water treatment plants.
At each of the water treatment plants, monthly collections are made of river water which is composited near the intake of the water treatment plant (raw drinking water) and of grab samples of finished drinking water; quarterly composites are made from the monthly collections. Gross beta and gamma isotopic analyses are conducted on each of the samples collected monthly. Tritium analysis is conducted on the quarterly composites. Although an I-131 analysis is not required to be conducted on these samples as the dose calculated from the consumption of water is less than 1 mrem per year (see ODCM Table 4-1), an I-131 analysis is conducted on each of the grab samples of the monthly collections of finished water since a drinking water pathway exists.
- Listed below for each year of operation are the average gross beta levels in units of pCi/l found in the monthly collections for raw and finished drinking water at the indicator and control stations, along with the increases in the average levels for the indicator stations over those for the control station, and the calculated MDD between these two station groups.
RAW Penod Indicator Control Increase MDD l 1995 3.06 4.90 -1.84 1.30 1994 3.51 3.47 0.04 1.24 1993 3.17 2.83 0.34 1.09 1992 2.73 2.70 0.03 0.96 1991 2.83 3.08 -0.25 2.47 1990 2.53 2.55 -0.02 0.72 1989 2.93 3.05 -0.12 0.85 l 1988 2.67 3.04 -0.37 1.36 1987 2 20 5.50 -3.30 4.40 4-12 l
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4 FINISHED Penod Indicator Control Increase MDD l 1995 2.74 2.32 0.42 0.72 l 1994 2.40 2.68 -0.28 2.40 l 1993 2.23 2.30 -0.07 2.23 1992 2.09 1.67 0.42 0.44 1991 1.90 1.53 0.37 0.47 ;
1990 2.08 1.92 0.16 0.58 j 1989 2.36 2.38 -0.02 0.57 l 1988 2.28 2.35 -0.07 0.88 1987 2.10 1.80 0.30 0.7 No trend is recognized from these data. In all previous years of operation, there was no discernible difference between the average levels at the indicator and control stations for both the raw and the finished water since the MDD was greater i than the difference. In 1995, a discernible difference was found in the average results for raw water between the two station groups. The higher result was found for the control station. No significance is perceived from this finding. The MDC for gross beta in water is 4 pCi/1.
I As indicated in Table 3-1, there were no positive results for the radionuclides of interest from the gamma isotopic analysis of the monthly collections. Only oiic positive result has been found since operation began; Be-7 was found at a level of 68.2 pCi/l in the sample collected for September 1987 at Station 87. The MDC assigned for Be-7 in water is 124 pCi/1.
As indicated in Table 3-1, there were no positive results from the I-131 analysis of the finished drinking water samples. Similar results were obtained in previous years of operation. The MDC and RL for I-131 in drinking water are 1 and 2 pCi/1, respectively.
Listed below for each year of operation are the average tritium levels found in the quarterly composites of raw and finished drinking water in units of pCi/l collected at the indicator and control stations, along with the increases in the average levels at the indicator stations over those at the control station, and the calculated MDDs between these two station groups. The average levels at the indicator stations for 1991 and 1992 have been purged of the impact of the inadvertent release at SRS of 7500 Ci of tritium to the Savannah River about 10 miles downriver of VEGP l between December 22 and 25,1991.
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! Period Indicatar Control Increase MDD l 1995 917 201 716 NA i 1994 871 NDM NA NA 1993 955 NDM NA NA 1992 1131 179 952 353 1991 1471 165 1306 834 1990 1320 266 1054 572 1989 2508 259 2249 1000 1988 2630 240 2390 580 1987 2229 316 1913 793 l.
FINISHED l Period Indicator Control Increase MDD 1995 847 279 568 NA 1994 880 131 749 270 1993 993 NDM NA NA 1992 1162 211 951 427 1991 1240 225 1015 647 1990 1299 404 895 1131 1989 2236 259 1977 627 1988 2900 270 .2630 830 1987 2406 305 2101 1047 The above tabulations show that in recent years, the tritium levels in the drinking water samples, both raw and finished, at the indicator stations have become less than half those found during the first three years of operation.
From Table 3-1, it may be seen that a detectable measurement of tritium was found in only one of the samples collected at the control station during 1995 for both raw and finished drinking water. A modified t-test that compared the single positive result from the control station with the average result from the indicator stations was employed to determine if there was a discernible difference between the two data groups for both the raw and finished drinking water. It was determined that there was no discernible difference in either case. A MDD cannot be determined with the modified t-test calculation; therefore, not applicable (NA) is entered in the MDD columns above for both raw and finished drinking water.
I The above data tabulations show that except for the finished drinking water in l 1990, there has been a detectable difference between the two station groups for -
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both raw and finished drinking water during every previous year of operation (whenever detectable measurements were made for both station groups). l l
i 4.7 Fish Table 2-1 calls for the collection of at least one sample of,any anadromous species [
of fish in the vicinity of the plant discharge during the sprmg spawnmg season, ,
l and for the semiannual collections of at least one sample of any commercially or -
recreationally important species in the vicinity of the plant discharge area and in j an area not influenced by alant discharges.. Table 2-1 also calls for a gamma '
l isotopic analysis on the ec ible portions of each sample collected. {
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As stated in Table 2-2 a stretch of the river of about 5 miles is generally needed to obtain adequate fish samples. For the semiannual collections, the control station (No. 81) extends from approximately 2 to 7 miles upriver of the plant intake j structure and the indicator station (No. 85) extends from about 1.4 to 7 miles !
downriver of the plant discharge structure. For anadromous species, all collection points can be considered as indicator stations.
On March 22, American shad, an anadromous species, was collected. In 1995 as
! in all but two previous years of operation, no positive results for the radionuclides l l ofinterest were detected from the gamma isotopic analysis. In 1987 as well as in l 1991, Cs-137 was found in a single sample of American shad at minuscule levels '
of 10 and 12 pCi/kg wet, respectively.
The dates and compositions of the semiannual catches at the indicator and control stations during 1995 were u shown below, j i
Data Indicator Control :
April 18 Channel Catfish Largemouth Bass !
Largemouth Bass Redear Sunfish
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l November 3 Channel Catfish Channel Catfish Largemouth Br 4 As indicated in Table 3-1, Cs-137 was the only radionuclide ofinterest found in the semiannual collections. It has been found in all but one of the 77 samples collected during operation. In Table 3-1, the average level at the indicator station is seen to be 29.0 pCi/kg wet greater than that at the control station. This difference is not discernible, however, since it is iess tbn the calculated MDD of ,
309 pCi/kg wet.
Listed below for each year of operation are the average levels of Cs-137 in units of pCi/kg wet found in fish samples at the indicator and control stations. !
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! YCat Indicator Control
- 1995 125 96 l 1994 165 200 l 1993 360- 84 l 1992 178 80 1991 105 211 1990 103 249 1989 117 125 I 1988 66 116 i 1987 337 119 No trend is recognimi in these data. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg wet, respectively.
The only other radionuclide ofinterest found in fish samples during past years of operation is I-131. In 1990, it was found in one sample at both the indicator and control stations at levels of 13 and 12 pCi/kg wet, respectively; in 1989, it was found in one sample at the indicator station at a level of 18 pCi/kg wet.
4.8 . Sediment Sediment was collected along the shoreline of the Savannah River on April 3 and October 3 at Stations 81 and 83. Station 81 is a control station located about 2.5 miles upriver of the plant intake structure while Station 83 is an indicator station located about 0.6 miles downriver of the plant discharge structure. A gamma isotopic analysis was performed on each sample.
l Listed below for each year of operation are the average levels in units ofpCi/kg l dry for the radionuclides ofinterest found in the regular samples collected at the l l indicator and/or control stations along with the fractions of d etectable measurements and the MDCs. Each of these radionuclides is found in the plant's liquid releases.
j Be-7, MDC=655 1
! Xcar Indicatnr Fraction Control Fraction l
- 1995 1865 1.0 1575 1.0 ,
1994 1203 1.0 964 1.0 .l l 1993 711 1.0 902 1.0 1992 2038 1.0 380 1.0 1991 826 1.0 427 1.0 !
1990 1 465 1.0 545 1.0 1989 1300 1.0 415 1.0 1988 970 1.0 810 1.0
,. 1987 987 1.0 543 1.0 i
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l Mn-54, MDC=42
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Yggt Indicator Fraction Control Fraction 1994 32 0.5 NDM 0.0 1989 18 0.5 NDM 0.0 1988 22 0.5 NDM 0.0 Co-58, MDC=43 Ygar Indicator Eraction Control Fraction 1995 42 0.5 NDM 0.0 1994 18 0.5 NDM 0.0 1992 124 0.5 NDM 0.0 1990 140 0.5 NDM 0.0 l 1989 135 1.0 NDM 0.0 1988 190 1.0 NDM 0.0 Co-60, MDC=70 Ygat Indicator Fraction Control Fraction i 1
1995 267 1.0 NDM 0.0 1994 85 1.0 NDM 0.0
! 1993 66 1.0 NDM 0.0 l 1992 60 1.0 NDM 0.0 1991 113 0.5 NDM 0.0 1990 46 0.5 NDM 0.0 1989 46 1.0 NDM 0.0 1988 62 0.5 NDM 0.0 1-131, MDC=53 Year Indicator Fraction Control Fraction 1994 51 0.5 41 0.5 1992 194 0.5 20 0.5 l
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Cs-137, MDC=180
.Y. car Indicator Fraction Control Fraction 1995 357 1.0 123 1.0 1994 240 1.0 118 1.0
- 1993 345 1.0 115 1.0 l 1992 259 1.0 111 1.0 1991 246 1.0 100 1.0 1990 155 1.0 140 1.0 1989 230 1.0 125 1.0 1988 175 1.0 175 1.0 1987 209 1.0 111 1.0 No trend is recognized in the above data. As in all previous years of operation, positive results for Be-7 and Cs-137 were found in each sample. Although Mn-54
, and I-131 were not detected during 1995, higher levels were found for Co-60 and l Cs-137.
l For Be-7, the average level at the indicator station is seen to be 290 pCi/kg dry greater than that at the con *rol station; however, this difference is not discernible as it is less than the calculated MDD of 2735 pCi/kg dry. For Cs-137, the average level at the indicator station is 234 pCi/kg dry greater than that at the control station; this difference is less than the MDD of 3182 pCi/kg dry and thus is not l discernible. There continues to be no discernible difference between the indicator l and control stations for both Be-7 and Cs-137 and thus their presence at the indicator station is not attributed to plant releases.
The continuing presence of Co-60 and the sometimes presence of Mn-54 and Co-
, f 8 at the indicator station (although at low levels) and their absence at the control l
station are indicative of plant releases. The radiological impact to the public due to those radionuclides which were detected during 1995 (Co-58 and Co-60) was l assessed by employing the methodology and parameters of NRC Regulatory
! Guide 1.109, Revision 1, October 1977, to estimate the annual whole body dose to an individual by direct radiation from sediment with the concentrations of these radionuclides as found at the indicator station, and comparing this estimated dose with the 3 mrem limit for liquid releases from one unit as stipulated by of ODCM 2.1.3. The dose was estimated to be approximately 6.9 microrem or about 0.23
- percent of the limit. This extremely low dose, altnegh calculable, poses no I measurable environmental or public health impact.
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! 5.0 INTERLABORATORY COMPARISON PROGRAM 1
TS 6.7.4.g(3) requires partici pation in an interlaboratory comparison program to ensure that independent chec:cs are performed on the precision and accuracy of the I measurements of radioactive materials in environmental sample matrices. In I conformance with ODCM 4.1.3, the EL conducts analyses on radioactive materials i supplied by the Performance Evaluation Program managed by the Environmental-Protection Agency (EPA) at their Environmental Monitoring Systems Laboratory in Las Vegas, Nevada. In past years, this EPA program was known as the Intercomparison Studies (Crosscheck) Program. Re ported herein, as required by l
ODCM 4.1.3.3 and 7.1.2.3 is a summary of the resu ts of the EL's participation in the EPA program.
The EPA program was designed for laboratories involved with REMPs and
, includes environmental media and a variety of radionuclides with activities which
! might be as low as environmental levels. Simulated environmental samples are distributed regularly to the participants who analyze the samples and return the results to the EPA for statistical analysis and comparisons with known values and with results obtained from other participating laboratories. The EPA then arovides each participant with documentation ofits performance; this can be helpfu in identifying any instrument or procedure problems.
The EL analyzes the EPA supplied samples consistent with the requirements of Table 2-1. Analyses are performed in a normal manner. Each sample is analyzed in triplicate as required by the program. Results obtained during 1995 for the gross beta and gamma isotopic analyses of air filters, the gamma isotopic analysis of milk samples, and the gross beta, tritium, I-131 and gamma isotopic analyses of water samples are summarized in Table 5-1.
Delineated in Table 5-1 for each of the environmental media are the type analyses l performed, EPA's collection dates, the known values and expected precisions l
provided by the EPA, the average results obtained and reported by the EL along with the standard deviations of these results, and the normalized deviations and the normalized ranges from the known results. The normalized deviations and normalized ranges were also provided by the EPA.
The normalized deviation from the known value provides a measure of the central tendency of the data (accuracy). The normalized range is a measure of the dispersion of the data (precision). An absolute value of 3 standard deviations for the normalized deviation and for the normalized range was established by the EPA as the control limit. An absolute value of 2 standard deviations was established as the warning limit. The EL considers any value greater than the control limit as i unacceptable. Investigations are undertaken whenever any value exceeds the warning limit or whenever a plot of the values indicates a trend. ;
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1 TABLE 5-1 (SHEET I OF 2)
INTERLABORATORY COMPARISON PROGRAM RESULTS .
t Radionuclide Date Known Expected Reported Standard Normalized Normalized ;
or Analysis Collected Value Precision Aserage Deviation Deviation Panoe Air Filters (pCi/ filter)
Gross Beta 08/25/95 86.6 10.0 89.00 3.00 0.42 035 Cs-137 08/25/95 25.0 5.0 30.00 3.00 1.73 0.71 Milk (pCi/l) 1-131 09/29/95 99.0 10.0 9833 5.69 -0.12 0.65 Cs-137 09/29/95 50.0 5.0 49.00 1.00 -035 0.24 Water (pCi/I)
Gross Beta 01/27/95 5.0 5.0 9.00 1.00 139 0.24 5.0 -1.64 035 '
07/21/95 19.4 14.67 1.53 10/27/95 24.8 5.0 3133 4.b 2.26 0.95 H-3 03/10/95 7435.0 744.0 7033 33 257.16 -0.94 038 1 08/04/95 4872.0 487.0 4530.00 121.24 -1.22 0.29 h
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_ _ . _ _ _ . - _ - _ _ _ _ - .___- . _ _ _ _ - - _ - - - - . _ - - _ _ _ -.r -->n,, ~ - - - - - ~ , ~ . - . , r>.~.- , - - --- __ -a_ -r
i TABLE 5-1 (SHEET 2 OF 2)
INTERLABORATORY COMPARISON PROGRAM RESULT 3 Radionuclide Date Known Expected Reported Standard Normalized Normalized or Aa=1vsis Collected Value Precision Average Deviation Des tation R= nee Co 06/09/95 40.0 5.0 38.67 4.04 -0.46 0.83 i1/03/95 60.0 5.0 58.00 4.00 -0.69 0.95 Zn-65 06/09/95 76.0 8.0 8033 10.50 0.94 2.05 11/03/95 125.0 13.0 12633 635 0.16 0.50 !
l-131 02/03/95 100.0 10.0 95.67' 3.06 -0.75 035 l 10/06/95 148.0 15.0 151.67 5.69 0.42 0.43 ,
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Cs-134 06/09/95 50.0 5.0 44.00 2.65 -2.08 0.59 i iI/03/95 40.0 5.0 34.00 3.46 -2.08 0.71 j Cs-137 06/09/95 35.0 5.0 40.00 6.08 ' l.73 1.57 I
11/03/95 49.0 5.0 5133 1.53 0.81 035 i
Ba-133 06/09/95 79.0 8.0 72.00 436' -1.52 9.59 t
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An investigation was undertaken due to the following conditions which may be !
j noted from Table 5-1: >
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- 1. The warning limit for the normalized deviation was exceeded for the gross beta analysis of the water sample collected on October 27;
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! 2. The warning limit for the normalized range was exceeded for Zn-65 in the gamma isotopic analysis of the water sample collected on June 9; l 3. The warning limit for the normalized deviation was exceeded for Cs-134 in !
l the gamma isotopic analysis of the water samples collected on June 9 and l l November 3; and
- 4. A downward trend was indicated from plots of Cs-134 found from the gamma :
isotopic analysis of water samples.
L The EPA water samples for beta analysis generally produce approximately 20 :
milligrams of solid material. The efficiency of the sample is determined from a !
calibration curve which represents the milligrams of solid material from the sample versus the efliciency. The curve used to obtain the efficiency for the EPA )
sample of October 27 did not give a proper fit for the milligrams ofinterest. The l curve has been reevaluated. Quality Control samples processed after the curve's i reevaluation provided acceptable activity recovery.
The EPA samples for gamma isotopic analysis are diluted to produce four separate one liter marinellis. The samples are counted and statistically analyzed. The three ,
samples with the overall best precision are reported to the EPA. The June 9 :
sample with the Zn-65 was analyzed in this manner. One of the analysis results was determined to be suspect. The remaining three samples were reported to the >
EPA. The samples in the future will be counted on at least two different detectors to rule out any suspect analysis.
The EPA stated that there were problems with the analysis of Cs-134 and that laboratories using commercial standards for calibration of their gamma counting systems may experience problems with coincidence summing of the primary energy peak for Cs-134. The energy peak is 604 key. The concentration of the standards used did not produce the adequate summing effects.
The activity for Cs-134 in water is trending low. This indicates a likely problem with the background correction factors. The background correction factors for the gamma counting systems need to be evaluated as the detectors were relocated to a different room in 1994. The background of the room will be evaluated and new correction factors determined.
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6.0 CONCLUSION
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l This report confirms the licensee's conformance with TS 6.7.4.g and Chapter 4 of the ODCM during 1995. It shows that all data were carefully examined. A summary and discussion of the results of the laboratory analyses for each type sample collected were presented.
The presence of Co-60 and other man-made radionuclides at low levels in i shoreline sediment at a short distance downriver from the discharge structure and their absence at the u priver location suggests plant releases. The consequent dose which was shown to x a small fraction of the ODCM limits, poses no measurable radiological impact to the environment or the public.
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IV VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 1995 ANNUAL REPORT- PART 2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
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ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES i
SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Limits / Technical Specifications 8 1.1.1 Concentration Limits 8 1.1.2 Dose Limits 8 1.2 Effluent Concentration Limit 8 1.3 Measurements and Approximations of Total 9 Radioactivity 1.4 Liquid Effluent Release Data 11 1
1.4.1 Tables 11 1.4.2 Total Error Measurement 11 1.5 Radiological Impact on Man Due to Liquid Release 12 1.6 Abnormal Releases 12 1.7 River Flow 12 2.0 Gaseous Effluents 34 2.1 Regulatory Limits / Technical Specifications 34
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l SECTION TITLE PAGE j 2.1.1 Dose Rate Limit 34 2.1.2 Air Dose Due to Noble Gas 34 2.1.3 Dose to Any Organ 34 l
2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) 35 2.2 Release Points of Gaseous Effluents 35 2.3 Sample Collection and Analysis 35 2.4 Total Quantities of Radioactivity, Dose Rates 36 and Cumulative Doses 2.4.1 Fission and Activation Gas 36 2.4.2 Radiolodines, Tritium and Particulate Releases 36 l
2.4.3 Gross Alpha Release 37 2.5 Gaseous Effluent Release Data 38 2.5.1 Methodology 38 l
l 2.5.2 Gaseous Batch Data 40 2.6 Radiological Impact Due to Gaseous Releases 40 2.7 Abnormal Releases 40 2
3ECTION TITLE PAGE 3.0 - Solid Waste 80 3.1 Regulatory Limits / Technical Specifications 80 3.1.1 Use of Solid Radioactive Waste System 80 3.1.2 Reporting Requirements 80 3.1.3 Process Control Program (PCP) 80 3.2 Solid Waste Data 81 4.0 Changes to the Vogtle Electric Generating Plant 81 ODCM l
4.1 Changes in the Radiological Environmental 82 i Monitoring Program !
l 5.0 Doses to Members of the Public inside The 82 Site Boundary 6.0 Major Changes to the Liquid, Gaseous and 90 Solid Radwaste Treatment Systems 7.0 Meteorology 90 8.0 Inoperable Liquid or Gaseous Effluent 90 Monitoring Instrumentation l l
9.0 Tanks Exceeding Curie Content Limits 91 )
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VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES TABLE LIST OF TABLES _ PAGE 1-2A Liquid Effluents - Summation of All Releases 13 Unit 1 ;
i 1-2AA Liquid Effluents - Summation of All Releases 14 l Unit 1 1-2B Liquid Effluents - Summation of All Releases 15 Unit 2 l l
1-2BB Liquid Effluents - Summation of All Releases 16 I Unit 2 l 1-2C Liquid Effluents - Summation of All Releases 17 Site 1-2CC Liquid Effluents - Summation of All Releases 18 )
Site 1-3A Liquid Effluents - Unit i 19 1-3AA Liquid Effluents - Unit 1 20 1-3B Liquid Effluents - Unit 2 21 1-3BB Liquid Effluents - Unit 2 22 1-3C Liquid Effluents - Site 23 1-3CC Liquid Effluents - Site 24 4
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j TABLE UST OF TABLES PAGE 4 ,
! 1-4A Individuals Doses Due to Liquid Releases 25 Unit 1 1-4AA Individuals Dosos Due to Liquid Releases 26 Uc!t1 1-4B Individuals Doses Due to Liquid Releases 27 Unit 2 1-488 Individuals Doses Due to Liquid Releases . 28 Unit 2 1-5 Minimum Detectable Concentration - 29 Liquid Sample Analysis 1-6A Batch Release Summary of All Releases 30 Unit 1 1-6AA Batch Release Summary of All Releases 31 )
Unit 1 l 1-6B Batch Release Summary of All Releases 32 Unit 2 1-6BB Batch Release Summary of All Releases 33 Unit 2 2-2A Airborne Effluents - Summation of All 41 Releases - Unit 1 2-2AA Airborne Effluents - Summation of All 42 Releases - Unit 1 2-2B Airbome Effluents - Summation of All 43 Releases -Unit 2 5
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TABLE LIST OF TABLES PAGE l
l l 2-288 Airbome Effluents - Summation of All 44 '
Releases -Unit 2 2-2C Airborne Effluents - Summation of All 45 Releases - Site 2-2CC Airborne Effluents - Summation of All 46 Releases - Site j 2-3A Gaseous Effluents - Mixed Mode Releases 47 Unit 1 l
l l 2-3AA Gaseous Effluents - Mixed Mode Releases 49 !
Unit 1 1 1
l 2-3B Gaseous Effluents - Mixed Mode Releases 51 i
! Unit 2 l
2-3B8 Gaseous Effluents - Mixed Mode Releases 53 I
- Unit 2 i 2-3C Gaseous Effluents - Mixed Mode Releases 55 Site
! 2-3CC Gaseous Effluents - Mixed Mode Releases 57 Site 2-4A Gaseous Effluents - Ground Level Release 59 Unit 1 2-4AA Gaseous Effluents - Ground Level Release 61 Unit 1 t
2-4B Gaseous Effluents - Ground Level Release 63 i I Unit 2 1
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TABLE LIST OF TABLES PAGE 2-4BB Gaseous Effluents - Ground Level Release 65 '
Unit 2 2-4C Gaseous Effluents - Ground Level Release 67 Site 2-4CC Gaseous Effluents - Ground Level Release 69 Site 2-6A Air Doses Due to Noble Gases - Unit 1 71 l
2-6AA Air Doses Due to Noble Gases - Unit 1 72 1
2-6B Air Doses Due to Noble Gases - Unit 2 73 2-6BB Air Doses Due to Noble Gases - Unit 2 74 2-7A Individual Doses Due to Radiolodines, 75 Tritium, and Particulates in Gaseous Releases - Unit 1 2-7AA Individual Doses Due to Radiolodines, 76 l Tritium, and Particulates in Gaseous '
Releases - Unit 1 2-7B Individual Doses Due to Radiolodines, 77 Tritium, and Particulates in Gaseous Releases - Unit 2 2-78B Individual Doses Due to Radiolodines, 78 Tritium, and Particulates in Gaseous l Releases - Unit 2 2-8 Minimum Detectable Concentration - 79 Gaseous Sample Analyses 3-1 Solid Waste and Irradiated Fuel Shipments 84 4-1 Dose to A Member of the Public Due to Activities 89 !
Inside The Site Boundary 7
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1.0 Liquid Effluents j 1
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1.1 Regulatory Limits / Technical Specifications l l
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1.1.1 Concentration Limits I The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations i specified in 10 CFR Part 20, Appendix B, Table ll, Column 2 for I radionuclides other than dissolved or entrained noble gases. For j dissolved or entrained noble gases, the concentration shall be i limited to 1.0E-4 micro curies /mi total activity. l 1.1.2 Dose Limits j l
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 l body and to less than or equal to 10 mrems to any organ.
1.2 Effluent Concentration Limit (ECL)
ECL values used in determining allowable liquid radwaste release rates and concentrations for principal gamma emitters,1-131, tritium, ,
Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table 11, Column 2. A tolerance factor up to 10 is selected to allow flexibility in the establishment of a practical monitor set point which could accommodate effluent releases at concentrations higher than the ECL values stated in 10 CFR 20, Appendix B, Table 2, Column 2.
For dissolved or entrained noble gases in liquid radwaste, the ECL is 1E-04 uCi/ml total activity.
For gross alpha in liquid radwaste, the ECL is 2.0E-09 uCi/ml.
l Further, for all the above radionuclides or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.
8
1 The method utilizing the ECL fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.
l 1.3 Measurements and Approximations of Total Radioactivity l
Prior to the release of any tank containing liquid radwaste, and following the required recirculations, samples are collected and analyzed in accordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3. A sample from each tank planned for release is analyzed for principal gamma emitters,1-131, and dissolved and entrained noble gases by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample
- taken from the tanks which are released. Liquid radwaste sample analyses are
- performed as follows
MEASUREMENT FREQUENCY METHOD
- 1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.
l 2. Dissolved or entrained Each Batch Gamma Spectroscopy l noble gases with computerized data reduction
- 3. Tritium Monthly Distillation and Composite liquid scintillation counting
- 4. Gross Alpha Monthly Gas flow proportional Composite counting
- 5. Sr 89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or l scintillation counting
- 6. Fe-55 Quarter 1y Chemical separation l Composite and liquid scintillation counting Gamma isotopic measurements are performed in-house in the radiochemistry lab using germanium detectors with a resolution of 1.80 kev or lower. The detectors are shielded by four inches of lead. A liquid radwaste sample is typically counted for 2000-4000 seconds. /. Deak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and a quantitative reduction or MDC calculation is performed. This ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10, i.e., Mn-54, Fe-59, Co-58, Co-60,2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative 9
b i
calculations, corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, branching ratio and MDC calculations, are made based on the counts at the location in the spectrum where the peak for that !
radionuclide would be located, if present. ,
- Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.
The radionuclide concentrations determined by gamma spectroscopic analysis of a ,
sample taken from a tank planned for release in addition to the most current sample !
analysis results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55 are used along with the corresponding ECL values to determine the ECL fraction for the tank planned for release. This ECL fraction is then used, with appropriate safety factors, tolerance factors, along with the minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) are not exceeded. '
! A monitor reading in excess of the calculated setpoint results in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow l rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.
1 Radionuclide concentrations, safety factors, dilution stream flow rate, ;
and liquid effluent radiation monitor calibrations are entered into the !
computer and a pre-release printout is generated. If the release is i not permissible, appropriate wamings will be displayed on the computer screen. If the release is permissible, it is approved by Chemistry and sent to the Operations Department for approval and processing. When the release is completed, the necessary data from the release (i.e., release volume, etc.) are transferred from
- the Operations Department to the Chemistry Department. These data are input to the computer and a post-release printout is generated, q The post release printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated j doses to an individual. l l
I l i
l 10
}
1.4 Liquid Effluent Release Data 1.4.1 Tables Regulatory Guide 1.21 Tables 2A,2B, and 2-C are found in this report as Tables 1-2A,1-2AA,1-2B,1-2BB,1-2-C, and 1-2-CC. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.
1.4.2 Total Error Measurement The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid effluents.
l 1.4.2.1 Fission and activation total release was calculated from sample analysis results and release point flow rates.
Sampling and statistical error 10%
Counting Equipment Calibration 10%
Tank Volumes and System Flow Rates 20%
TOTAL ERROR 40%
1.4.2.2 Total Tritium release was calculated from sample analysis results and release point volumes.
Sampling and statistical errors 10%
Counting equipment calibration 10%
Tank volumes and system flow rate 20%
TOTAL ERROR 40%
1.4.2.3 Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Sampling and statistical error 20%
Counting equipment calibration 10%
Tank volumes and system flow rate 20%
TOTAL ERROR 50 %
11
l l- 1.4.2.4 Gross alpha radioactivity was calculated from sample analysis results and l rejecse point volumes.
l L Sampling and statistical error 10%
Counting Equipment calibration 10%
Tank volumes and system flowrates 20%
Compositing sample error 5%
TOTAL ERROR 45%
l l 1.4.2.5 Volume of waste prior to dilution was calculated from level indicators on I the tanks and pump discharge flow rates and times.
Level Indicator error 10%
Operator Interpretation of gauge 10%
- TOTAL ERROR 20%
i 1.4.2.6 Volume of dilution water used was calculated from flow rate indicators l and pump discharge flow rates and times.
l l Flow rate indicator error 10%
Operator interpretation of gauge 10%
TOTAL ERROR 20%
i l
1.5 Radiological Impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated i in accordance with the Offsite Dose Calculation Manual. Results are presented in Table 1-4A,1-4AA for Unit 1 and 1-4B,1-4BB for Unit 2, for all four quarters.
l 1.6 Abnormal Releases
\
l 1.6.1 There were no abnormal releases for this reporting period. l 1.7 River Flow l
The average flow rate of the Savannah River for the Annual Effluent l Report period was obtained from the Clark Hill Dam, Corp of i
Engineers Office. The average flow rate is 9841 cubic feet /sec.
f l
i 12
l l
TABLE 1-2 A GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENT RELEASE REPORT - 1995 ALL LIQUID EFFLUENTS UNIT : 1 STARTING : 1-JAN-1995 ENDING ; 30-JUN-1995 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.19E-01 2.86E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.18E-07 1.93E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM l
- 1. TOTAL RELEASE CURIES 1.36E+02 5.59E+01 40 )
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.92E-04 3.77E-04 l DURING PERIOD l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- l C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 7.09E-04 0.00E+00 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.09E-09 0.00E+00 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 6.90E+05 4.20E+05 20 F. VOLUME GF D:LUTION WATER USED LITRE 2.29E+08 1.48E+08 20
- Applicable limits are expressed in terms of Dose. See Table 14A of this report 13
I TABLE 1-2AA GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL LIQUID EFFLUENTS i UNIT: 1 STARTING : 1-JUL-1995 ENDING : 31-DEC-1995 l
TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL l
ERROR %
! A. FISSION & ACTIVATION PRODUCTS l
l 1. TOTAL RELEASE (NOT INCLUDING CURIES 5.66E-02 4.36E-02 40 TRITIUM. GASES, ALPHA) l 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.62E-07 2.75E-07 DURING PERIOD l 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 1.68E+02 1.94E+02 40 l 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.78E-04 1.22E-03 l DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 7.56E-05 1.94E-03 50 l 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.50E-10 1.22E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 2.78E-03 2.41 E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) UTRE 1.04E+06 4.61 E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 2.15E+08 1.58E+08 20
- Apphcable hmits are expressed in terms of Dose. See Table 1-4AA of this report 14
TABLE 1-28 l GEORGIA POWER COMPANY l VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 l ALL LIQUID EFFLUENTS ,
! UNIT: 2 l STARTING : 1-JAN-1995 ENDING : 30-JUN-1995 i TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 7.56E-02 1.68E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION UCi/ML 2.66E-07 1.72E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM l
- 1. TOTAL RELEASE CURIES 1.62E+02 3.55E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 5.71 E-04 3.64E-04 i
DURING PERIOD l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.49E-03 6.56E-04 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.25E-09 6.72E-09 DURING PERIOD !
- 3. PEl?CENTAGE OF APPLICABLE LIMIT %
l D. GROSS ALPHA RADIOACTIVITY !
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 8.11E+05 2.78E+05 20 l F. VOLUME OF DILUTION WATER USED LITRE 2.83E+08 9.73E+07 20
- Apphcable limits are expressed in terms of Dose. SeeTable 1-48 of this report l
15
i TABLE 1-2BB GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT '
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL LIQUID EFFLUENTS UNIT : 2 l
STARTING : 1-JUL-1995 ENDING : 31-DEC-1995 TYPE OF EFFLUENT- UNITS QUARTFR3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 3.30E-02 2.35E-02 40 TRITIUM. GASES, ALPHA) l
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.94E-07 4.51E-07 DURING PERIOD l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM l
- 1. TOTAL RELEASE CURIES 1.16E+02 1.01E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML ' 1.03E-03 1.94E-03 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.86E-05 0.00E+00 50 l
- 2. AVERAGE DILUTED CONCENTRATION uCl/ML 1.66E-10 0.00E+00 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
1
! D. GROSS ALPHA RADIOACTIVITY l 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 l
E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 3.50E+05 1.88E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 1.12E+08 5.19E+07 20
.
- Applicath hmits are expressed in terms of Dose. See Table 1-408 of tNs report l
16
TABLE 1-2C GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 l ALL LIQUID EFFLUENTS l SITE ,
l STARTING : 1-JAN-1995 ENDING : 30-JUN-1995
- TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR % ;
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.95E-01 4.54E-02 40 TRITIUM. GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.79E-07 1.85E-07 DURING PERIOD !
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 2.98E+02 9.14E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.80E-04 3.72E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 2.20E-03 6.56E 34 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 4.28E/J9 2.67E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 1.50E+06 6.98E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 5.12E+08 2.45E+08 20
- Appucable hmits are expressed in terms of Dose. See Table 1-4A and 1-4B of this report 17
TABLE 1-2CC GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL LIQUID EFFLUENTS j SITE '
STARTING : 1-JUL-1905 ENDING : 31-DEC-1995 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR % l A. FISSION & ACTIVATION PRODUCTS l
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 8.96E-02 6.71 E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.73E-07 3.19E-07 DURING PERIOD I
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM i
- 1. TOTAL RELEASE CURIES 2.84E+02 2.95E+02 40 l
- 2. AVERAGE DlLUTED CONCENTRAliON uCi/ML 8.65E-04 1.40E-03 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
I C. DISSOLVED AND ENTRAINED GASES I
- 1. TOTAL RELEASE CURIES 9.42E-05 1.94E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.87E-10 9.21 E-09 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 2.78E-03 2.41 E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 1.39E+06 6.49E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 3.27E+08 2.10E+08 20
- Applicable limits are expressed in terms of Dose. See Table 14AA and 1-488 of this report 18 l
l l
TABLE 1-3A Vogtle Electric Generating Plant l ANNUAL RADIOACTIVE EFFLUENT RELEASE REDORT-1995 Liquid Effluents Starting : 1-Jan-1995 Ending : 30-Jun-1995 UNIT : 1 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 1.36E+02 5.59E+01 FISSION & ACTIVATION PRODUCTS:
Be-7 CURIES 0.00E+00 0.00E+00 0.00E+00 2.30E-04 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 1.20E-04 0.00E+00 Co-58 CURIES 0.00E+00 0.00E+30 5.93E-03 1.82E-03 Co-60 CURIES 0.00E+00 0.00E+00 3.22E-02 2.44E-03 Cr-51 CURIES 0.00E+00 0.00E+00 2.82E-03 6.09E-04 Cs-134 CURIES G.00E+00 0.00E+00 9.96E-06 6.22E-05 Cs-137 CURIES 0.00E+00 0.00E+00 3.86E-05 6.20E-05 Fe-55 CURIES 0.00E+00 0.00E+00 6.26E-02 8.19E-03 Fe-59 CURIES 0.00E+00 0.00E+00 1.09E-04 0.00E+00 l 1-131 CURIES 0.00E+00 0.00E+00 8.65E-04 0.00E+00 1-132 CURIES 0.00E+00 0.00E+00 8.92E-05 0.00E+00 i Mn-54 CURIES 0.00E+00 0.00E+00 3.42E-03 4.90E-04 Nb-95 CURIES 0.00E+00 0.00E+00 1.09E-03 1.44E-04 Sb-122 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 CURIES 0.00E+00 0.00E+00 3.10E-04 1.67E-04 Sb-125 CURIES 0.00E+00 0.00E+00 7.58E-03 6.90E-03 Sn-113 CURIES 0.00E+00 0.00E+00 4.19E-05 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 5.07E-04 6.93E-06 Sr-90 CURIES 0.00E+00 0.00E+00 1.83E-05 0.00E+00 Te-125M CURIES 0.00E+00 0.00E+00 0.00E+00 7.46E-03 Te-129M CURIES 0.00E+00 0.00E+00 6.98E-04 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 8.44E-05 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 1.57E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 4.60E-04 5.02E-05 ;
TOTALS 0.00E+00 0.00E+00 1.19E-01 2.86E-02 i
DISSOLVED AND ENTRAINED GASES:
Xs-133 CURIES 0.00E+00 0.00E+00 6.41 E-04 0.00E+00 Xe-135 CURIES 0.00E+00 0.00E+00 6.84E-05 0.00E+00 TOTALS 0.00E+00 0.00E+00 7.09E-04 0.00E+00 l
l G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00
{
19
l ,
l TABLE 1-3AA Vogtle Electric Generating Plant ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 Liquid Effluents Starting : 1-Jul-1995 Ending : 31-Dec-1995 UNIT : 1 CONTINUOUS BATCH NUCLIDE UNIT OUARTER3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00 1.68E+02 1.94E+02 Fl%ON & ACTIVATION PRODUCTS:
Ca. ' 43 CURIES 0.00E+00 0.00E+00 9.85E-06 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 4.75E-05 1.41 E-05 Co-58 CURIES 0.00E+00 0.00E+00 3.59E-03 1.37E-03 Co-60 CURIES 0.00E+00 0.00E+00 1.13E-02 3.91E-03 Cr-51 CURIES 0.00E+00 0.00E+00 3.46E-04 1.16E-03 Cs-134 CURIES 0.00E+00 0.00E+00 6.46E-04 1.20E-04 Cs-137 CURIES 0.00E+00 0.00E+00 6.63E-04 1.71 E-04 Fe-55 CURIES 0.00E+00 0.00E+00 2.21 E-02 1.31 E-02 Fe-59 CURIES 0.00E+00 0.00E+00 0.00E+00 8.01 E-05 l-131 CURIES 0.00E+00 0.00E+00 6.92E-06 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 2.12E-03 8.50E-04 Nt>95 CURIES 0.00E+00 0.00E+00 3.92E-04 2.07E-04 Nb-97 CURIES 0.00E+00 0.00E+00 5.72E-05 0.00E+00 Rb-105 CURIES 0.00E+00 0.00E+00 0.00E+00 1.45E-05 Ru-103 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-122 CURIES n.00E+00 0.00E+00 3.52E-05 0.00E+00 Sb-124 CURIES t.00E+00 0.00E+00 1.74E-04 1.29E-04 Sb-125 CURIES 0.00E+00 0.00E+00 1.49E-02 2.23E-02 Sn-113 CURIES 0.00E+00 0.00E+00 1.62E-05 2.76E-05 Sr-89 CURIES 0.00E+00 0.00E+00 9.78E-06 7.61E-05 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 0.00E+00 8.15E-06 Zn-65 CURIES 0.00E+00 0.00E+00 1.80E-05 0.00E+00 Zr 95 CURIES 0.00E+00 0.00E+00 2.20E-04 6.82E-05 I TOTALS 0.00E+00 0.00E+00 5.66E-02 4.36E-02 j DISSOLVED AND ENTRAINED GASES: l Kr-87 CURIES 0.00E+00 0.00E+00 3.33E-05 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 4.23E-05 1.94E-03 TOTALS 0.00E+00 0.00E+00 7.56E-05 1.94E-03 l l
G-ALPHA CURIES 0.00E+00 0.00E+00 2.78E-03 2.41 E-06 l
l 20
TABLE 1-3B Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 l Liquid Effluents Starting : 1-Jan-1995 Ending : 30-Jun-1995 UNIT : 2 i
! CONTINUOUS BATCH NUCLIDE UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUAf(TER 2 l H-3 CURIES 0.00E+00 0.00E4 00 1.62E+02 3.55E+01 FISSION & ACTIVATION PRODUCTS:
Be-7 CURIES 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 7.46E-06 Co-57 CURIES 0.00E+00 0.00E+00 1.24E-04 0.00E+00 Co-58 CURIES 0.00E+00 0.00E+00 5.26E-03 1.10E-03 Co-60 CURIES 0.00E+00 0.00E+00 1.76E-02 1.41 E-03 Cr-51 CURIES 0.00E+00 0.00E+00 2.12E-03 6.53E-04 Cs-134 CURIES 0.00E+00 0.00E+00 9.62E-06 0.00E+00 Cs-15/ CURIES 0.00E+00 0.00E+00 2.51E-05 0.00E+00 Fe-55 CURIES 0.00E+00 0.00E+00 2.30E-02 4.39E-03 Fe-59 CURIES 0.00E+00 0.00E+00 3.13E-05 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 1.79E-03 6.84E-05 l-132 CURIES 0.00E+00 0.00E+00 3.41E-04 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 2.20E-03 2.10E-04 Nb-95 CURIES 0.00E+00 0.00E+00 3.61E-04 1.04E-04 Sb-122 CURIES 0.00E+00 0.00E+00 1.30E-05 0.00E+00 Sb-124 CURIES 0.00E+00 0.00E+00 1.07E-03 8.18E-05 Sb-125 CURIES 0.00E+00 0.00E+00 1.86E-02 2.98E-03 Sn-113 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 1.86E-04 0.00E+00 '
Sr-90 CURIES 0.00E+00 0.00E+00 1.42E-05 0.00E+00 Te-125M CURIES 0.00E+00 0.00E+00 0.00E+00 5.77E-03 Te-129m CURIES 0.00E+C0 0.00E+00 2.01E-03 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 4.32E-04 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 1.98E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 1.84E-04 6.25E-05 TOTALS 0.00E+00 0.00E+00 7.56E-02 1.68E-02 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 1.49E-03 6.47E-04 Xe-135 CURIES 0.00E+00 0.00E+00 0.00E+00 9.43E-06 TOTALS 0,00E+00 0.00E+00 1.49E-03 6 56E-04 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 21
TABLE 1-3BB Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 Liquid Effluents Starting : 1-Jul-1995 Ending : 31-Dec-1995 UNIT : 2 CONTINUOUS BATCH NUCLIDE UNIT QUARTER 3 QUARTER 4 QUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00 1.16E+02 1.01 E+02 FISSION & ACTIVATION PRODUCTS:
Ce-143 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 1.65E-05 5.09E-05 Co-58 CURIES 0.00E+00 0.00E+00 2.33E-03 2.06E-03 Co-60 CURIES 0.00E+00 0.00E+00 4.18E-03 5.58E-03 Cr-51 CURIES 0.00E+00 0.00E+00 4.31E-04 0.00E+00 Cs-134 CURIES 0.00E+00 0.00E+00 8.61 E-04 7.75E-05 Cs-137 CURIES 0.00E+00 0.00E+00 8.08E-04 6.66E-05 Fe-55 CURIES 0.00E+00 0.00E+00 1.10E-02 1.10E-02 Fe-59 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 7.69E-04 1.48E-03 Nb-95 CURIES 0.00E+00 0.00E+00 2.52E-04 2.45E-04 Nb 97 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rh-105 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 CURIES 0.00E+00 0.00E+00 1.40E-05 0.00E+00 Sb-122 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb-124 CURIES 0.00E+00 0.00E+00 9.51 E-05 9.56E-06 Sb-125 CURIES 0.00E+00 0.00E+00 1.22E-02 2.67E-03 Sn-113 CURIES 0.00E+00 0.00E+00 0.00E+00 1.83E-05 Sr-89 CURIES 0.00E+00 0.00E+00 1.6BE-05 2.00E-05 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 2.07E-06 Te-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 3.94E-05 1.72E-04 TOTALS 0,00E+00 0.00E+00 3.30E-02 2.35E-02 DISSOLVED AND ENTRA;NED GASES:
Kr-87 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 1.86E-05 0.00E+00 TOTALS 0.00E+00 0 00E+00 1.86E-05 0.00E+00 l G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 22
TABLE 1-3C Vogtle Electric Gens ating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 Liquid Effluents Starting : 1-Jan-1995 Ending : 30-Jun-1995 SITE CONTINUOUS - BATCH NUCLID UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 H-3 CURIES 0.00E+00 0.00E+00 2.98E+02 9.14E+01 FISSION & ACTIVATION PRODUCTS:
Be-7 CURIES 0.00E+00 0.00E+00 0.00E+00 2.30E-04 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 7.46E-06 Co-57 CURIES 0.00E+00 0.00E+00 2.44E-04 0.00E+00 Co-58 CURIES 0.00E+00 0.00E+00 1.12E-02 2.92E-03 Co-60 CURIES 0.00E+00 0.00E+00 4.98E-02 3.85E-03 Cr-51 CURIES 0.00E+00 0.00E+00 4.94E-03 1.26E-03 Cs-134 CURIES 0.00E+00 0.00E+00 1.96E-05 6.22E-05 Cs-137 CURIES 0.00E+00 0.00E+00 6.37E-05 6.20E-05 Fe-55 CURIES 0.00E+00 0.00E+00 8.56E-02 1.26E-02 Fe-59 CURIES 0.00E+00 0.00E+00 1.40E-04 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 2.66E-03 6.84E-05 l-132 CURIES 0.00E+00 0.00E+00 4.30E-04 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 5.62E-03 7.00E-04 Nb-95 CURIES 0.00E+00 0.00E+00 1.45E-03 2.48E-04 Sb-122 CURIES 0.00E+00 0.00E+00 1.30E-05 0.00E+00 Sb-124 CURIES 0.00E+00 0.00E+00 1.38E-03 2.49E-04 Sb-125 CURIES 0.00E+00 0.00E+00 2.62E-02 9.88E-03 Sn-113 CURIES 0.00E+00 0.00E+00 4.19E-05 0.00E+00 Sr-89 CURIES 0.00E+00 0.00E+00 6.93E-04 6.93E-06 Sr-90 CURIES 0.00E+00 0.00E+00 3.25E-05 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 0.00E+00 1.32E-02 Te-132 CURIES 0.00E+00 0.00E+00 2.71E-03 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 5.16E-04 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 3.55E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 6.44E-04 1 13E-04 TOTALS 000E+00 0.00E+00 1.95E-01 4.55E-02 DISSOLVED AND ENTRAINED GASES:
Xe-133 CURIES 0.00E+00 0.00E+00 2.13E-03 6.47E-04 Xe-135 CURIES 0.00E+00 0.00E+00 6.84E-05 9.43E-06 TOTALS 000E+00 0.00E+00 2.20E-03 6.56E-04 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
23
1 l
TABLE 1-3CC Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 Liquid Effluents Starting : 1-Jul-1995 Ending : 31-Dec-1995 SITE CONTINUOUS BATCH
, NUCLID UNIT QUARTER 3 QUARTER 4 OUARTER 3 QUARTER 4 H-3 CURIES 0.00E+00 0.00E+00 2.84E+02 2.95E+02 FISSION & ACTIVATION PRODUCTS:
Ce-143 CURIES 0.00E+00 0.00E+00 9.85E-06 0.00E+00 Co-57 CURIES 0.00E+00 0.00E+00 6.40E-05 6.50E-05 Co-58 CURIES 0.00E+00 0.00E+00 5.92E-03 3.43E-03 Co-60 CURIES 0.00E+00 0.00E+00 1.55E-02 9.49E-03 Cr-51 CURIES 0.00E+00 0.00E+00 7.77E-04 1.16E-03 Cs-134 CURIES 0.00E+00 0.00E+00 1.51E-03 1.98E-04 Cs-137 CURIES 0.00E+00 0.00E+00 1.47E-03 2.38E-04 Fe-55 CURIES 0.00E+00 0.00E+00 3.31E-02 2.41 E-02 Fe-59 CURIES 0.00E+00 0.00E+00 0.00E+00 8.01 E-05 l-131 CURIES 0.00E+00 0.00E+00 6.92E-06 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 2.89E-03 2.33E-03 Nb-95 CURIES 0.00E+00 0.00E+00 6.44E-04 4.52E-04 Nb-97 CURIES 0.00E+00 0.00E+00 5.72E-05 0.00E+00 Rh-105 CURIES 0.00E+00 0.00E+00 0.00E+00 1.45E-05 Ru-103 CURIES 0.00E+00 0.00E+00 1.40E-05 0.00E+00 Sb-122 CURIES 0.00E+00 0.00E+00 3.52E-05 0.00E+00 Sb-124 CURIES 0.00E+00 0.00E+00 2.69E-04 1.39E-04 Sb 125 CURIES 0.00E+00 0.00E+00 2.71E-02 2.50E-02 Sn-113 CURIES 0.00E+00 0.00E+00 1.62E-05 4.59E-05 Sr-89 CURIES 0.00E+00 0.00E+00 2.66E-05 9.61 E-05 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 2.07E-06 Te-132 CURIES 0.00E+00 0.00E+00 0.00E+00 8.15E-06 Zn-65 CURIES 0.00E+00 0.00E+00 1.80E-05 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 2.59E-04 2.40E-04 TOTALS 0.00E+00 0.00E+00 8.97E-02 6.71 E-02 DISSOLVED AND ENTRAINED GASES:
Kr-87 CURIES 0.00E+00 0.00E+00 3.33E-05 0.00E+00 l Xe-133 CURIES 0.00E+00 0.00E+00 6.09E-05 1.94E-03
, TOTALS 0.00E+00 0.00E+00 9.42E-05 1.94E-03 G-ALPH CURIES 0.00E+00 0.00E+00 2.78E-03 2.41 E-06 l
24
TABLE 1-4A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1995 THROUGH JUNE,1995 l UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 5.0 mrem 1.29E-03 2.58E-02 1.20E-03 2.40E-02 Liver 5.0 mrem 3.91 E-03 7.83E-02 2.29E-03 4.57E-02 T. Body 1.5 mrem 3.48E-03 2.32E-01 1.89E-03 1.26E-01 Thyroid 5.0 mrem 3.36E-03 6.71 E-02 9.60E-04 1.92E-02 Kidney 5.0 mrem 3.27E-03 6.54E-02 2.49E-03 4.98E-02 Lung 5.0 mrem 1.08E-02 2.16E-01 1.75E-02 3.51 E-01 GI-LLI 5.0 mrem 6.96E-03 1.39E-01 4.20E-03 8.40E-02 l
i CUMULATIVE DOSE PER YEAR l ORGAN ODCM UNITS YEAR TO DATE % OF ODCM
^
LIMIT LIMIT Bone 10.0 mrem 2.49E-03 2.49E-02 Liver 10.0 mrem 6.20E-03 6.20E-02
- T. Body 3.0 mrem 5.37E-03 1.79E-01 l Thyroid 10.0 mrem 4.32E-03 4.32E-02 Kidney 10.0 mrem 5.76E-03 5.76E-02 Lung 10.0 mrem 2.83E-02 2.83E-01 i GILLI 10.0 mrem 1.12E-02 1.12E-01 25 I
I l
l TABLE 1-4AA '
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REMRT INDIVIDUAL DOSES DUE TO LIQUID RELEASES July,1995 THROUGH December,1995 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM j LIMIT LIMIT Bone 5.0 mrem 1.29E-02 2.59E-01 3.08E-03 6.17E-02 Liver 5.0 mrem 2.79E-02 5.58E-01 9.36E-03 1.87E-01 1 T. Body 1.5 mrem 2.21 E-02 1.48E+00 8.25E-03 5.50E-01 Thyroid 5.0 mrem 5.31 E-03 1.06E-01 5.07E-03 1.01 E-01 Kidney 5.0 mrem 1.27E-02 2.53E-01 6.43E-03 1.29E-01 Lung 5.0 mrem 4.78E-02 9.56E-01 5.88E-02 1.18E+00 GI-LLI 5.0 mrem 1.21 E-02 2.41 E-01 1 1.06E-02 2.13E-01 i
CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone 10.0 mrem 1.85E-02 1.85E-01 Liver 10.0 mrem 4.35E-02 4.35E-01 T. Body 3.0 mrem 3.58E-02 1.19E+00 Thyroid 10.0 mrem 1.47E-02 1.47E-01 Kidney 10.0 mrem 2.48E-02 2.48E-01 Lung 10.0 mrem 1.35E-01 1.35E+00 i GI LLI 10.0 mrem 3.39E-02 3.39E-01 26
l l
l l
TABLE 1-4B VOGTLE ELECTRIC GENERATING PLANT \
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1995 THROUGH JUNE,1995
)
UNIT 2 1 1
CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 5.0 mrem 9.33E-04 1.87E-02 2.60E-04 5.21 E-03 Liver 5.0 mrem 3.14E-03 6.28E-02 6.52E-04 1.30E-02 T. Body 1.5 mrem 2.89E-03 1.93E-01 6.01 E-04 4.01 E-02 Thyroid 5.0 mrem 3.76E-03 7.52E-02 6.58E-04 1.32E-02
- Kidney 5.0 mrem 3.40E-03 6.80E-02 1.25E-03 2.50E-02 Lung 5.0 mrem 2.40E-02 4.80E-01 5.74E-03 1.15E-01
- GI-LLI 5.0 mrem 7.66E-03 1.53E-01 1.95E-03 3.91 E-02 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone 10.0 mrem 1.19E-03 1.19E-02 Liver 10.0 mrem 3.79E-03 3.79E-02 !
T. Body 3.0 mrem 3.49E-03 1.16E-01 l Thyroid 10.0 mrem 4.42E-03 4.42E-02 Kidney 10.0 mrem 4.65E-03 4.65E-02 Lung 10.0 mrem 2.97E-02 ?.97E-01 j GILLI 10.0 mrem 9.61 E-03 l 9.61E-02 J
27
TABLE 1-4BB l VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JULY,1995 THROUGH DECEMBER,1995 l
UNIT 2 l
l CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone 5.0 mrem 1.29E-02 2.58E-01 1.63E-03 3.26E-02 I
Liver 5.0 mrem 2.65E-02 5.30E-01 6.40E-03 1.28E-01 T. Body 1.5 mrem 2.08E-02 1.39E+00 5.64E-03 3.76E-01 l Thyroid 5.0 mrem 3.59E-03 7.18E-02 3.60E-03 7.19E-02 l Kidney 5.0 mrom 1.11 E-02 2.22E-01 4.46E-03 8.91 E-02 Lung 5.0 mrom 4.05E-02 8.09E-01 1.12E-02 2.23E-01 GI-LLI 5.0 mrem 8.12E-03 1.62E-01 5.96E-03 1.19E-01 l
CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 10.0 mrem 1.57E-02 1.57E-01 l Liver 10.0 mrom 3.67E-02 3.67E-01 1 T. Body 3.0 mrem 2.99E-02 9.98E-01 Thyroid 10.0 mrem 1.16E-02 1.16E-01 Kidney 10.0 mrom 2.02E-02 2.02E-01 i Lung 10.0 mrom 8.14E-02 8.14E-01 GI-LLI 10.0 mrom 2.37E-02 2.37E-01 l
t l
28
i l
l '
l TABLE 1-5 l MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT JANUARY,1995 - DECEMBER 31,1995 l
l The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of liquid radwaste samples.
RADIONUCLIDE MDC UNITS Mn-54 2.73E-08 uCi/ml Fe-59 8.33E-08 uCi/mi Co-58 3.78E-08 uCi/ml Co-60 6.76E-08 uCi/ml Zn-65 1.32E-07 uCi/ml Mo-99 4.31 E-07 uCi/mi Cs-134 3.06E-08 uCi/ml Cs-137 4.51 E-08 uCi/ml l Ce-141 6.99E-08 uCi/ml j Ce-144 2.95E-07 uCi/ml 1-131 5.97E-08 uCi/ml Xe-133 9.11 E-08 uCi/mi Xe-135 4.27E-08 uCi/mi Fe-55 1.00E-06 uCi/mi Sr-89 5.00E-08 uCi/mi Sr-90 7.00E-09 uCi/mi H-3 2.00E-06 uCi/ml Gross Alpha 7.00E-08 uCi/mi 1
1 I
i I
l 29 l
f 1 TABLE 1-6A l GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 1
BA TCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1995 ENDING: JUNE,1995 i
LIQUID RELEASES l
Number of Releases 24 Total Time For All Releases 4970.00 minutes Maximum Time For a Release 405.00 minutes Average Time For a Release 207.08 minutes Minimum Time For a Release 52.00 minutes l GASEOUS RELEASES l Number of Releases: 91 Total Time For All Releases 11587.23 minutes Maximum Time For A Release 1137.98 minutes Average Time For A Release 127.33 minutes Minimum Time For A Release 10.00 minutes 4
30
TABLE 1-6AA l
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES
- STARTING
- JULY,1995 ENDING: DECEMBER,1995 l
l LIQUID RELEASES Number of Releases 32 l Total Time For All Releases 4880.00 minutes l
Maximum Time For a Release 323.00 minutes Average Time For a Release 152.50 minutes Minimum Time For a Release 48.00 minutes GASEOUS RELEASES Number of Releases: 105 Total Time For All Releases 17581.32 minutes Maximum Time For A Release 5824.00 minutes Average Time For A Release 167.44 minutes Minimum Time For A Release 8.00 minutes i i
l l
1 l
l 1
l l
l l
l 31 l l i
l l TABLE 1-6B GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1995 ENDING: JUNE,1995 l
l LIQUID RELEASES i
Number of Releases 22 l Total Time For All Releases 4790.00 minutes !
! Maximum Time For a Release 298.00 minutes l Average Time For a Release 217.73 minutes l Minimum Time For a Release 68.00 minutes l
GASEOUS RELEASES Number of Releases: 77 l Total Time For All Releases 42096.07 minutes l
Maximum Time For A Release 5684.92 minutes i Average Time For A Release 546.70 minutes Minimum Time For A Release 11.00 minutes l
l
{
32
TABLE 1-6BB GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JULY,1995 ENDING: DECEMBER,1995 LIQUID RELEASES Number of Releases 18 Total Time For All Releases 2400.18 minutes Maximum Time For A Release 277.00 minutes Average Time For A Release 133.34 minutoc Minimum Time For A Release 61.00 minutes GASEOUS RELEASES Number of Releases 19 Total Time For All Releases 3922.33 minutes Maximum Time For a Release 2441.92 minutes Average Time For A Release 206.44 minutes Minimum Time For A Release 46.92 minutes l
l 33 l
l
l l
l 2.0 Gaseous Effluents 2.1 ODCM Specifications The ODCM Specifications presented in this section are for Unit 1 and Unit 2.
2.1.1 Dose Rate Limit !
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 the following:
- a. For noble gases: Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,
- b. For lodine-131, for lodine-133, for tritium and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr. to any organ.
2.1.2 Air Dose Due To Noble Gas The air dose due to noble gases released in gaseous effluents, from each unit, to i areas at and beyond the SITE BOUNDARY shall be limited to the following: l
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.1.3 Dose To Any Organ 1
The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-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.
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
I f
34
t 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190) l 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 to any organ, except the thyroid, which shall be limited to less than or equal to l 75 mrems.
2.2 Release Points of Gaseous Effluents Gaseous Effluents at Vogtle Electric Generating Plant are currently confined to four paths: plant vents (Unit 1 and Unit 2) the condenser air ejector and steam packing exhauster systems (Unit 1 and Unit 2).
Waste gas decay tanks are batch releases and the waste gas decay tanks are released through the Unit 1 plant vent. Containment purges are released through their respective plant vents.
2.3 Sample Collection and Analysis All of the paths can be continuously monitored for gaseous radioactivity. Each is equipped with an integrated-type sample collection device for collecting particulates and iodines. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and steam packing exhauster system vents.
Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release. The containment atmosphere is analyzed for noble gases prior to each release and tritium at least on a monthly basis.
Sample analyses results and release flow rates from the release points form the basis for calculating released quantities of radionuclide specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year. This task is normally performed with computer assistance.
With each release period and batch release, radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated,
, along with percent of ODCM limits for each release for the current quarter and year.
l 35
2.4 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses are as follows:
2.4.1 Fission and Activation Gas The released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample.
Instantaneous dose rates due to noble gases, radiciodines, tritium, and particulates are calculated (with computer assistance). Calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radiciodines, tritium, and particulates. Dose rate calculation methodology is presented in the ODCM.
Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to gaseous releases. Air doses are calculated for each release period and cumulative totals are kept for each unit for the calendar quarter and year. Cumulative air doses are compared to the dose limits specified in ODCM 3.1.3. Current percent of the ODCM limits are shown on the printout j for each release period. Air dose calculation methodology is presented l in the ODCM. l 2.4.2 Radiolodines, Tritium and Particulate Releases Released quantities of radiciodines are determined from the weekly samples and release flow rates for the two release points. Radiciodines concentrations are determined by gamma spectroscopy.
Release quantities of particulates are determined from the weekly (filter) samples and release flow rates for the two release points. Gamma spectroscopy is used to quantify concentrations of principal gamma emitters.
After each quarter, the particulate filters from each vent are combined, fused, and a strontium separation is performed. If Sr-89 or Sr-90 is not detected, MDC's are calculated. Strontium concentrations are input to the composite file of the computer to be used for release dose rate and individual dose calculations.
1 36
1 l
l Tritium samples are obtained at least monthly from each vent by bubbling the sample stream through a water trap. The tritium concentration in water is converted to tritium concentration in air and this value is input into the composite file of the computer to be used in release, dose rate, and individual dose calculations. ,
Dose rates due to radiciodines, tritium, and particulates are calculated for a hypothetical child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be i the highest. Dose rates are calculated for each release point, for each release period, and the total dose rate from both release points are compared to the dose rate limits specified in ODCM 3.1.2 l Individual doses due to radiciodines, tritium and particulates are calculated for the controlling receptor, which for Vogtle Electric Generating Plant is a child exposed to the inhalation and ground-plane pathways. Individual doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative individual doses are compared to the dose limits specified in ODCM 3.1.4.
Current percent of ODCM limits are shown on the printout for each release period.
2.4.3 Gross Alpha Release The gross alpha release is calculated each month by counting the particulate filters for each week for gross alpha activity in a proportional counter by an offsite laboratory. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is input to the composite file of the computer and is used for release calculations.
t 37
l 2.5 Gaseous Effluent Release Data 2.5.1 Methodology Regulatory Guide 1.21 Tables 1 A,1B, and 1C are found in this report as Tables l 2-2A, 2-2AA, 2-28, 2-2BB, 2-2C, 2-2CC, 2-3A, 2-3AA, 2-3B, 2-3BB, 2-3C, 2-3CC, 2-4A,2-4AA,2-48,2-4BB,2-4C, and 2-4CC. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all quarters.
To complete table 2-2A,2-2AA,2-2B, and 2-2BB, total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each category for each quarter. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases.
Applicable limits are expressed in terms of dose. Noble gases are limited as specified' in ODCM 3.1.2, The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.
Dose rates due to noble gas releases and due to radiciodines, tritium, and particulates were calculated as part of the pre-release and post-release
~
permits on individual permits. No limits were exceeded for this reporting period.
1 Gross alpha radioactivity is reported in Table 2-2A,2-2AA,2-2B, and 2-2BB as curies released in each quarter.
l Limits for cumulative beta and gamma air doses due to noble gases are specified in ODCM 3.1.3. Cumulative air doses are presented in Table 2-6A 2-6AA,2-68, and 2-6BB along with percent of ODCM limits.
Limits for cumulative individual doses due to radioiodines, tritium and particulates, are specified in ODCM 3.1.4. Cumulative individual doses are presented in Table 2-7A,2-7AA, 2-78, and 2-78B along with percent of ODCM limits.
The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste.
38
Estimated errors are based on errors in counting equipment calibration, counting statistics, vent-flow rates, vent sample flow rates, non steady release rates, chemical yield factors and sample losses for such items as charcoal cartridges.
2.5.1.1 Fission and activation total release was calcu'a:ed from sample analysis results and release point flow rates.
Sampling and statistical error in counting 10%
Counting equipment calibration 10%
Vent flow Rates 10%
Non-steady release rates 20%
TOTAL ERROR 50 %
2.5.1.21-131 releases were calculated from each weekly sample:
Statistical error in counting 10%
Counting equipment calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 50 %
Non-Steady release rates 10% ;
Losses from charcoal cartridges 10% :
TOTAL ERROR 100 %
2.5.1.3 Particulates with half lives greater than 8 day releases were calculated 1 from sample and analysis results and release point flow rates.
l Statistical error at MDC concentration 10%
Counting equipment calibration 10% ,
Vent flow rates 10 % )
Vent sample flow rates 50% I Non steady release rates 10% l TOTAL ERROR 90 % l 2.5.1.4 Total tritium releases were calculated from sample analysis results and release point flow rates.
Water vapor in sample stream determination 10 %
Vent flow rates 10%
Counting calibration and statistics 10%
Non-steady release rates 10%
TOTAL ERROR 40%
39
2.5.1.5 Gross Alpha radioactivity was calculated from sample analysis results and release point flow rates.
Statistical error at MDC concentration 10%
Counting equipment calibration 10%
Vent flow rates 10%
Vent sample flow rates 50%
Non Steady release rates 10%
TOTAL ERROR 90 %
2.5.2 Gaseous Batch Data Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 1-6A ,1-6AA,1-68, and 1-6BB.
2.6 RadiologicalImpact Due to Gaseous Releases Dose rates due to noble gas release were calculated for the site in accordance with ODCM 3.4.1.1 Dose rates due to radiciodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.
As part of pre-release and post release on individual release permits, these dose rates were calculated. No limits were exceeded for this reporting period.
Cumulative air doses due to noble gas releases were calculated for ,
each unit in accordance with ODCM 3.4.2.These results are presented ;
in Tables 2-6A ,2-6AA, 2-6B, and 2-6BB.
Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.
2.7 Abnormal Releases There were no unplanned releases for this reporting period.
l 40
I l
l TABLE 2-2A GEORGIA POWER COMPANY I VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL AIRBORNE EFFLUENTS UNIT : 1 STARTING : 1-JAN-1995 ENDING : 30-JUN-1995 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR % l A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 3.79E+01 2.88E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.87E+00 3.66E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- l B. RADIOIODINES
- 1. TOTAL LODINE-131 CURIES 1.58E-05 2.62E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.03E-06 3.33E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT .%
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 0.00E+00 1.54E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.00E+00 1.96E-06
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 6.51E+01 6.75E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.37E+00 8.59E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 1.75E-13 1.92E-13 90
- Apphcable limits are expressed in terms of Dose. See Tables 2 6A and 2-7A of this report 41
i l
}
TABLE 2-2AA GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL AIRBORNE EFFLUENTS UNIT : 1 STARTING : 1-JUL-1995 ENDING : 31-DEC-1995 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 3.07E-01 3.91E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.86E-02 4.92E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- B. RADIOIODINES -
1
- 1. TOTAL IODINE-131 CURIES 1.95E-06 2.53E-06 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.45E-07 3.18E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- l C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 0.00E+00 1.66E-06 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 0.00E+00 2.09E-07
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D.TRITlUM j
- 1. TOTAL RELEASE CURIES 3.17E+01 5.14E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.99E+00 6.47E+00 l 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 3.40E-07 2.13E-13 90
- Applicable limits are expressed in terms of Dose. See Tables 2-6AA and 2-7AA of this report l
42 l
l t-TABLE 2-2B l
l GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL AIRBORNE EFFLUENTS UNIT : 2 l STARTING : 1-JAN-1995 ENDING : 30-JUN-1995 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.07E+03 2.03E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.38E+02 2.58E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT % *
- B. RADIOlODINES
- 1. TOTAL LODINE-131 CURIES 7.67E-04 3.73E-06 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCl/Sec 9.86E-05 4.74E-07 l DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >BDAYS) CURIES 2.22E-04 2.50E-06 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.85E-05 3.18E-07
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 8.17E+00 3.83E+00 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.05E+00 4.87E-01 I
l l 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 8.49E-14 1.39E-13 90
- Applicable limits are expressed in terms of Dose. See Tables 2 6B and 2-78 of this report a
l I
43
TABLE 2-2BB GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL AIRBORNE EFFLUENTS UNIT: 2 STARTING : 1 JUL-1995 ENDING : 31-DEC-1995 TYPE OF EFFLUENT UNITS OUARTER3 OUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS l 1. TOTAL RELEASE CURIES 7.55E-01 4.46E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 9.50E-02 5.61 E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOIODINES
- 1. TOTAL LODINE-131 CURIES 4.58E-06 2.12E-06 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.76E-07 2.67E-07 DURING PERIOD .
- I
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES l
1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 5.45E-06 2.77E-07 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.86E-07 3.48E-08
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.34E+01 3.57E+01 40
- 2. AVERAGE RELEASE RATE FOR PF,RIOD UCi/ Sea 2.94E+00 4.49E+00
- 3. PERCENTAGE OF APPLICAPAE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 2.68E-13 4.52E-07 90
- Appik:abie hmits are expressed in terms of Dose. See Tables 24BB ard 2-7BB of this report i
l O
l
i TABLE 2-2C GEORGIA POWER COMPANY t VOGTLE ELECTRIC GENERATING PLANT )
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 !
ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JAN-1995 ENDING : 30-JUN-1995 TYPE OF EFFLUENT UNITS QUARTER 1 CUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION !'RODUCTS
- 1. TOTAL RELEASE CURIES 1.11E+03 2.32E+00 50 !
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.43E+02 2.95E-01 !
- I
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 7.83E-04 2.99E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.01E-04 3.81 E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT % !
C. PARTICULATES t i
1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 2.22E-04 1.79E-05 90 l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.85E-05 1.60E-03 l I
- 3. PERCENTAGE OF APPLICABLE LIMIT % i D. TRITIUM
- 1. TOTAL RELEASE CURIES 7.33E+01 7.13E+01 40 l
- 2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 9.42E+00 9.07E+00 l 3. PERCENTAGE OF APPLICABLE LIMIT %
l 4. GROSS ALPHA RADIOACTIVITY CURIES 2.60E-13 3.31 E-13 90 l
- Applicable limits are expressed in terms of Dose. See Tatdes 2-6A 2-68,2-7A and 2-7B of this report 4
1 45 l
i ;
l l TABLE 2-2CC GEORGIA POWER COMPANY '
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1995 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JUL-1995 ENDING : 31-DEC-1995 l TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ,
l ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 1.06E+00 8.37E+00 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.34E-01 1.05E+00 !
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 6.53E 06 4.65E-06 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.22E-07 5.85E-07 DURING PERIOD :
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 5.45E-06 1.94E-06 90 i
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.86E-07 2.44E-07
- 3. PERCENTAGE OF APPLICABLE LIMIT % i D. TRITIUM
- 1. TOTAL RELEASE CURIES 5.51E+01 8.71 E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.93E+00 1.10E+01
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 3.40E-07 4.52E-07 90
- Applicable limits are expressed in terms of Dose. SeeTables 2-6AA. 24BB, 2-7AA and 2-7BB of this report 46
1 i
l TABLE 2-3A (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1995 THROUGH JUNE,1995 -
UNIT 1 l NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE l
- 1. Fission c g QUARTER QUARTER QUARTER QUARTER Gasses + % 1 2 1 2 Ar-41 Ci 0.00E+00 0.00E+00 1.42E-01 2.15E-01 Kr-85 Ci 0.00E+00 000E+00 0.00E+00 0.00E+00 Kr-85m Ci 1.43E-01 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0 00E+00 Xe-133 Ci 3.39E+01 0.00E+00 4.13E-02 7.12E-02 i Xe-133m Ci 6.08E-01 0.00E+00 0.00E+00 0.00E+00 l Xe-135 Ci 2.88E+00 0.00E+00 2.00E-03 1.34E-03 J Xe-135m Ci 1.39E-01 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 3.77E+01 0.00E+00 1.85E-01 2.88E-01 PERIOD l
- 2. lodine's 1-131 Ci 1.58E-05 2.62E-05 0.00E+00 0.00E+00 l l
l-133 Ci 3.48E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 1.93E-05 2.62E-05 0.00E+00 0.00E+00 l PERIOD l
l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
47 i
l l
TABLE 2-3A (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ,
l i
ANNUAL EFFLUENTS - MIXED MODE JANUARY,1995 THROUGH JUNE,1995 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates :. ::l i; QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Be-7 Ci 0.00E+00 1.56E-06 0.00E+00 0.00E+00
- Co-58 Ci 0.00E+00 2.46E-07 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-125m Ci 0.00E+00 1.36E-05 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 1.54E-05 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 1.75E-13 1.92E-13 0.00E+00 _0.00E+00 H-3 Ci 6.51 E+01 6.71 E+01 1.21 E-02 4.02E-01
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See l
Table 2-8 for typical minimum detectable concentrations.
48 1
I
i l
l TABLE 2-3AA (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ,
i ANNUAL EFFLUENTS - MIXED MODE JULY,1995 THROUGH DECEMBER,1995 UNIT 1 t
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH LSDE
- 1. Fission ~
+f, OUARTER QUARTER QUARTER QUARTER Gasses a ayn 3 4 3 4 Ar-41 Ci 0.00E+00 0.00E+00 2.16E-01 1.69E-01 ,
Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 6.38E-01 Kr-85m Cl 0.00E+00 0.00E+00 0.00E+00 1.07E-05 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 0.00E+00 3.02E+00 8.87E-02 7.71 E-02 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 3.18E-04 Xe-135 Ci 0.00E+00 0.00E+00 2.68E-03 1.45E-03 TOTAL FOR Ci 0.00E+00 3.02E+00 3.07E-01 8.86E-01 PERIOD
- 2. lodines 1-131 Ci 1.95E-06 2.53E-06 0.00E+00 0.00E+00 1-133 Ci 4.62E-06 3.45E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 6.57E-06 5.98E-06 0.00E+00 0.00E+00 PERIOD l
l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See i l Table 2-8 for typical minimum detectable concentrations.
i b i 49
TABLE 2-3AA(PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1995 THROUGH DECEMBER ,1995 UNIT 1 NUCLIDES r RELEASED UNIT CONTINUOUS MODE BATCH MODE <
I 3. Particulates ' ;; c ;, ,
QUARTER QU/.RTER QUARTER QUARTER
+% '
3 4 3 4 Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
l Co-58 Ci 0.00E+00 1.64E-06 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l TOTAL FOR Ci 0.00E+00 1.64E-06 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 3.40E-07 2.13E-13 0.00E+00 0.00E+00 H-3 Ci 3.16E+01 5.13E+01 4.36E-02 7.35E-02 l
- Zeroes in this table indicate that no radioactivity was present above detectable levels See Table 2-8 for typical minimum detectable concentrations.
l 50
TABLE 2x3B (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT j
ANNUAL EFFLUENTS - MIXED MODE JANUARY,1995 THROUGH JUNE,1995 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission Gasses
' *:j QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Ar-41 Ci 0.00E+00 0.00E+00 3.26E-01 1.64E-01 Kr-85 Ci 2.74E+00 0.00E+00 3.26E+01 1.55E-01 Kr-85m Ci 3.93E-01 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 1.43E+01 0.00E+00 1.30E+01 0.00E+00 Xe-133 Ci 5.17E+02 6.73E-02 3.89E+02 1.33E-01 Xe-133m Ci 5.90E+00 0.00E+00 2.23E+00 0.00E+00 Xe-135 Ci 6.33E+00 1.51 E+00 2.38E-02 3.27E-03 l Xe-135m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '
TOTAL FOR Ci 5.47E+02 1.58E+00 4.37E+02 4.55E-01 !
PERIOD
- 2. lodine's 1-131 Ci 7.49E-04 3.73E-06 0.00E+00 0.00E+00 1-133 Ci 1.59E-04 3.48E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 9.08E-04 7.21 E-06 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See ,
Table 2-8 for typical minimum detectable concentrations. !
1 51
TABLE 2-3B (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1995 THROUGH JUNE,1995 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates g' "gggggg' QUARTER QUARTER QUARTER QUARTER Wm 1 2 1 2 Be-7 Ci 1.47E-06 1.64E-06 0.00E+00 0.00E+00 Co-58 Ci 3.03E-05 8.61 E-07 7.28E-12 0.00E+00 Co-60 Ci 1.21 E-05 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 1.55E-05 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 5.62E-07 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 5.49E-07 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 3.17E-06 0.00E+00 0.00E+00 0.00E+00 Nb-95 Ci 2.40E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 7.22E-08 3.77E-09 0.00E+00 0.00E+00 Te-125m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 1.44E-06 0.00E+00 0.00E+00 0.00E+00 OTHER Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 6.76E-05 2.50E-06 7.28E-12 0.00E+00 PERIOD G-ALPHA Ci 8.49E-14 1.39E-13 0.00E+00 0.00E+00 H-3 Ci 6.30E+00 3.80E+00 1.66E+00 3.21 E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. ,
i l
I I
52 i
9 TABLE 2-3BB (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT -
ANNUAL EFFLUENTS - MIXED MODE JULY,1995 THROUGH DECEMBER,1995 UNIT 2 l i
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission 38 ' /* QUARTER QUARTER QUARTER QUARTER Gasses '?"- 3 4 3 4 Ar-41 Ci 0.00E+00 0.00E+00 1.02E-01 1.59E-02 ,
Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Kr-85m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 1.56E-03 !
Xe-133 Ci 0.00E+00 3.54E+00 2.50E-01 2.00E-01 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 8.97E-04 Xe-135 Ci 3.99E-01 7.04E-01 3.74E-03 2.00E-04 TOTAL FOR Ci 3.99E-01 4.24E+00 3.56E-01 2.19E-01 PERIOD
- 2. lodines I l-131 Ci 4.58E-06 2.12E-06 0.00E+00 0.00E+00 1-133 Ci 4.72E-05 1.42E-05 0.00E+00 0.00E+00 l TOTAL FOR Ci 5.18E-05 1.63E-05 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
TABLE 2-3BB (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1995 THROUGH DECEMBER ,1995 1 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates q . :, . QUARTER QUARTER QUARTER QUARTER
. : :: (~ 3 4 3 4 Be-7 Ci 5.07E-06 0.00E+00 0.00E+00 0.00E+00 Co-57 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 2.77E-07 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 2.20E-07 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 1.59E-07 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 5.45E-06 2.77E-07 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 2.68E-13 4.52E-07 0.00E+00 0.00E+00 H-3 Ci 2.33E+01 3.57E+01 6.79E-02 8.21 E-03
- Zeroes in this table indicate that no radioactivi'y was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
1 54
l 4
i TABLE 2-3C (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1995 THROUGH JUNE,1995 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission -
-: -l?; QUARTER QUARTER QUARTER QUARTER Gasses d 'n < 1 2 1 2 Ar-41 Ci 0.00E+00 0.00E+00 4.68E-01 3.79E-01 Kr-85 Ci 2.74E+00 0.00E+00 3.26E+01 1.55E-01 Kr-85m Ci 5.36E-01 0.00E+00 0.00E+00 0.00+-00 Xe-131 m . Ci 1.43E+01 0.00E+00 1.30E+01 0.00E+00 Xe-133 Ci 5.51 E+02 6.73E-02 3.89E+02 2.04E-01 Xe-133m Ci 6.51 E+00 0.00E+00 2.23E+00 0.00E+00 Xe-135m Ci 1.39E-01 0.00E+00 0.00E+00 0.00E+00 Xe-135 Ci 9.21 E+00 1.51 E+00 2.58E-02 4.61 E-03 TOTAL FOR Ci 5.84E+02 1.58E+00 4.37E+02 7.43E-01 PERIOD
- 2. lodines 1-131 Ci 7.65E-04 2.99E-05 0.00E+00 0.00E+00 '
1-133 Ci 1.62E-04 3.48E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 9.27E-04 3.34E-05 0.00E+00 0.00E+00 i PERIOD
\
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
55
i TABLE 2-3C (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1995 THROUGH JUNE,1995 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates f : , :. QUARTER QUARTER QUARTER QUARTER 1 's 1 2 1 2 Be-7 Ci 1.47E-06 3.20E-06 0.00E+00 0.00E+00 i Co-58 Ci 3.03E-05 1.11 E-06 7.28E-12 0.00E+00 l Co-60 Ci 1.21 E-05 0.00E+00 0.00E+00 0.00E+00 Cr-51 .
Ci 1.55E-05 0.00E+00 0.00E+00 0.00E+00 Fe-59 Ci 5.62E 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 5.49E-07 0.00E+00 0.00E+00 0.00E+00 Mn-54 Ci 3.17E-06 0.00E+00 0.00E+00 0.00E+00 Nb-95 Ci 2.40E-06 0.00E+00 0.00E+00 0.00E+00 Sr-89 Cl 7.22E-08 3.77E-09 0.00E+00 0.00E+00 Te-125m Ci 0.00E+00 1.36E-05 0.00E+00 0.00E+00 Zr-95 Ci 1.44E-06 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 6.76E-05 1.79E-05 7.28E-12 0.00E+00 PERIOD G-ALPHA Ci 2.63E-13 3.31 E-13 0.00E+00 0.00E+00 H-3 Ci 7.14E+01 7.09E+01 1.67E+00 4.34E-01 i
l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
l b
. . . - = _ _ - - . . - - . - - _ . - - . _ -- - _ . . . _
i TABLE 2-3CC (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT i
ANNUAL EFFLUENTS - MIXED MODE i
? JULY,1995 THROUGH DECEMBER,1995 i SITE l NUCLlD85 1
RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission QUARTER QUARTER QUARTER QUARTER
+ Gasses \;;\ ,4'\
yl f 3 4 3 4 l
. Ar-41 Ci 0.00E+00 0.00E+00 3.18E-01 1.85E-01 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 6.38E-01 Kr-85m Ci 0.00E+00 0.00E+00_ 0.00E+00 1.07E-05 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 1.56E-03 .
Xe-133 Ci 0.00E+00 6.56E+00 3.39E-01 2.77E-01 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 1.22E-03 Xe-135 Ci 3.99E-01 7.04E-01 6.42?-03 1.65E-03 TOTAL FOR Ci 3.99E-01 7.26E+00 6.63E+1 1.10E+00 PERIOD l
- 2. lodines l l-131 Ci 6.53E-06 4.65E-06 0.00E+00 0.00E+00 l-133 Ci 5.18E-05 1.77E-05 0.00E+00 0.00E+00 TOTAL FOR Ci 5.84E-05 2.23E-05 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
57 1
TABLE 2 3CC (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1995 THROUGH DECEMBER ,1995 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates ;%@ QUARTER QUARTER QUARTER QUARTER z :n 3 4 3 4 Be-7 Ci 5.07E-06 0.00E+00 0.00E+00 0.00E+00 Co-57 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 1.64E-06 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 2.77E-07 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Mn-54 Ci 2.20E-07 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 1.59E-07 0.00E+00 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Cl 5.45E-06 1.92E-06 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 3.40E-07 4.52E-07 0.00E+00 0.00E+00 H-3 Ci 5.49E+01 8.70E+01 1.12E-01 8.17E-02
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
58
l i
TABLE 2-4A (PAGE 1 OF 2) 1 VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JANUARY,1995 THROUGH JUNE,1995 '
UNIT 1 1
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission ; [3 Q,; QUARTER QUARTER QUARTER QUARTER Gasses <? ' '* 1 2 1 2 l Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- 2. lodines 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. !
l l
l
[
i 59
l l
I TABLE 2-4A (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT 1
ANNUAL EFFLUENTS - GROUND MODE JAN,1995 THROUGH JUNE,1995 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE -
BATCH MODE l
- 3. Particulates >
- QUARTER QUARTER QUARTER QUARTER M '- 1 2 1 2 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;
l i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See '
Table 2-8 for typical minimum detectable concentrations.
I i
a 1
60 l
._ _ _ _ . _ . _ _ _ _ _ . _ - - _ _ __ .-- ~ _ _ _ __ _ _ _ . _ _ _ __
i i
l l
l TABLE 2-4AA (PAGE 1 OF 2) l l
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1995 THROUGH DECEMBER,1995 l UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE )
- 1. Fission Rfihg g QUARTER QUARTER QUARTER QUARTER l Gasses 8 4% > 3 4 3 4 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1 Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0 00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
PERIOD l
- 2. lodines l l-133 Ci 0.00E+00 0.00E+00 0.00E+00 7.13E-10 BR-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR- Ci 0.00E+00 0.00E+00 0.00E+00 7.13E-10 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
61
l TABLE 2-4AA (PAGE 2 OF 2) i VOGTLE ELECTRIC GENERATING PLANT
- ANNUAL EFFLUENTS - GROUND MODE i
^
JULY,1995 THROUGH DECEMBER ,1995 l
UNIT 1 )
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE l
- 3. Particulates . c A% ' QUARTER QUARTER QUARTER QUARTER i
'm ? ", 3 4 3 4 NB-95 Ci 0.00E+00 0.00E+00 0.00E+00 1.22E-09 Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 1.36E-09 Co-58 Ci 0.00E+00 1.64E-06 0.00E+00 7.09E-09 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 1.55E-09 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 3.72E-09 Cs-137 Ci 0.00E+00 0.00E+00 0.00E+00 5.53E-10 TOTAL FOR Ci 0.00E+00 1.64E-06 0.00E+00 1.55E-08 PERIOD G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
l 1
l 4
62
1 N
i TABLE 2-4B (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE i
j JANUARY,1995 THROUGH JUNE,1995 l UNIT 2 l NUCUDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission QUARTER QUARTER QUARTER QUARTER
! Gasses Qy?g$k.
nd&w - 1 2 1 2 l Xe-135 Ci 0.00E+00 0.00E+00 4.37E-03 0.00E+00 l Xe-133m Ci 0.00E+00 0.00E+00 6.11 E-01 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 8.09E+01 0.00E+00 j Xe-131m Ci 0.00E+00 0.00E+00 1.85E+00 0.00E+00 l j Kr-85 Ci 0.00E+00 0.00E+00 4.44E+00 0.00E+00 l l TOTAL FOR 0.00E+00 Ci 0.00E+00 8.78E+01 0.00E+00
? PERIOD
- 2. lodines 1-132 Ci 0.00E+00 0.00E+00 2.94E-06 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 1.09E-07 0.00E+00 1-133 Ci 0.00E+00 0.00E+00 2.79E-07 0.00E+00 BR-82 Ci 0.00E+00 0.00E+00 3.83E-07 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 1.76E-05 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 2.13E-05 0.00E+00 ;
PERIOD l
l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See i Table 2-8 for typical minimum detectable concentrations.
63
i
- 1 i ,
I i
TABLE 2-4B (PAGE 2 OF 2) l 1
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE \
'. JAN,1995 THROUGH JUNE,1995 UNIT 2
} NUCLIDES j RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates ,;d; ; < QUARTER QUARTER QUARTER QUARTER
- ,<' 1 2 1 2 j Co-58 Ci 0.00E+00 0.00E+00 1.55E-04 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 1.55E-04 0.00E+00 PERIOD G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
H-3 Ci 0.00E+00 0.00E+00 2.06E-01 0.00E+00 i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See j Table 2-8 for typical minimum detectable concentrations.
64
TABLE 2-488 (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1995 THROUGH DECEMBER,1995 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission "& QUARTER QUARTER QUARTER QUARTER Gasses 3 4 3 4 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- 2. lodines 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 BR-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was sent above detectable levels. See l Table 2-8 for typical minimum detectable concentrations.
1
\
i 65
TABLE 2-4BB(PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1995 THROUGH DECEMBER ,1995 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates W 99 fret QUARTER QUARTER QUARTER 3 ww;, 3 4 3 Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
! Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
, TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ,
- H-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t
f
- Zeroes in thic table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
66
TABLE 2-4C (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JANUARY,1995 THROUGH JUNE,1995 j SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission . O'n QUARTER QUARTER QUARTER QUARTER Gasses "i* 1 2 1 2 Xe-135 Ci 0.00E+00 0.00E+00 4.37E-03 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 6.11 E-01 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 8.09E+01 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 1.85E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 4.44E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 8.78E+01 0.00E+00 PERIOD
- 2. lodines 1-132 Ci 0.00E+00 0.00E+00 2.94E-06 0.00E+00 1-135 Ci 0.00E+00 0.00E+00 1.09E-07 0.00E+00 1-133 Ci 0.00E+00 0.00E+00 2.79E-07 0.00E+00 BR-82 Ci 0.00E+00 0.00E+00 3.83E-07 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 1.76E-05 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 2.13E-05 0.00E+00 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See .
Table 2-8 for typical minimum detectable concentrations. l I
i 67
l 1 l
l TABLE 2-4C (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JAN,1995 THROUGH JUNE,1995 SITE NUCLIDES I RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates . :, - QUARTER QUARTER QUARTER QUARTER i
+ 3 2 1 2 Co-58 Ci 0.00E+00 0.00E+00 1.55E-04 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 1.55E-04 0.00E+00 PERIOD G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i H-3 Ci 0.00E+00 0.00E+00 2.06E-01 0.00E+00
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
i l
l l
l 68
l l l
i I
l l
TABLE 2-4CC (PAGE 1 OF 2)
VMTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1995 THROUGH DECEMBER,1995 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE l
- 1. Fission ;, ;.f QUARTER QUARTER QUARTER QUARTER Gasses '\ '::
3 4 3 4 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l l
Xe-133m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Xe-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 )
Xe-131m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PERIOD
- 2. lodines 1-133 Ci 0.00E+00 0.00E+00 0.00E+00 7.13E-10 BR-82 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-131 Ci 0.00E+00. 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 7,13E-10 PERIOD
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
i 69 l
TABLE 2-4CC (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT \
l ANNUAL EFFLUENTS - GROUND MODE JULY,1995 THROUGH DECEMBER ,1995 Siw NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates ~ >
QUARTER QUARTER QUARTER QUARTER
.M , 3 4 3 4 NBT5 Ci 0.00E+00 0.00E+00 0.00E+00 1.22E-09
' Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 1.36E-09 Co-58 Ci 0.00E+00 1.64E-06 0.00E+00 7.09E-09 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 1.55E-09 Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 3.72E-09 Cs-137 Ci 0.00E+00 0.00E+00 0.00E+00 5.53E-10 TOTAL FOR Ci 0.00E+00 1.64E-06 0.00E+00 1.55E-08 PERIOD G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
70
l !
. TABLE 2-6A 1
VOGTLE ELECTRIC GENERATING PLANT .
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT '
- AIR DOSE DUE TO NOBLE GAS RELEASES
- JANUARY,1995 THROUGH JUNE,1995 i
UNIT 1 l
i
- ' CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF l RADIATION LIMIT 1 ODCM 2 ODCM LIMIT LIMIT GAMMA 5.0 mrad 2.88E-04 5.77E-03 2.96E-05 5.92E-04 BETA 10.0 mrad 6.51E-04 6.51E-03 1.14E-05 1.14E-04 CUMULA71VE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 3.18E-04 3.18E-03 BETA 20.0 mrad } 6.63E-04 3.31E-03 71
l l
l TABLE 2-6AA j VOGTLE ELECTRIC GENERATING PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1995 THROUGH DECEMBER,1995 l
UNIT 1 CUMMULATIVE DOSE PER QUARTER 1 TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM LIMIT LIMIT GAMMA 5.0 mrad 2.99E-05 5.99E-04 3.93E-05 7.85E-04 j BETA 10.0 mrad 1.18E-05 1.18E-04 7.40E-05 7.40E-04 i i
i CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 3.87E-04 3.87E-03 BETA 20.0 mrad 7.49E-04 3. 74E-03 l
72
TABLE 2-6B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO hiOBLE GAS RELEASES JANUARY,1995 THROUGH JUNE,1995 UNIT 2 CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 1 ODCM 2 ODCM LIMIT LIMIT GAMMA 5.0 mrad 7.38E-03 1.48E-01 6.60E-05 1.32E-03 BETA 10.0 mrad 2.36E-02 2.36E-01 6.99E-05 6.99E-04 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIM."T UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 7.44E-03 7.44E-02 BETA 20.0 mrad 2.37E-02 1.18E-01 73
TABLE 2-6BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1995 THROUGH DECEMBER,1995 UNIT 2 CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM LIMIT LIMIT GAMMA 5.0 mrad 2.64E-05 5.29E-04 5.13E-05 8.26E-04 BETA 10.0 mrad 2.32E-05 2.32E-04 8.36E-05 8.36E-04 i
~m .q CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 7.51E-03 7.51E-02 BETA 20.0 mrad 2.38E-02 1.19E-01 74
j TABLE 2-7A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JANUARY,1995 THROUGH JUNE,1995 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 7.5 mrem 1.21 E-08 1.61 E-07 2.43E-08 3.25E-07 Liver 7.5 mrem 2.95E-04 3.93E-03 3.06E-04 4.08E-03 T. Body 7.5 mrom 2.95E-04 3.93E-03 3.06E-04 4.08E-03 Thyroid 7.5 mrem 2.96E-04 3.95E-03 3.08E-04 4.10E-03 Kidney 7.5 mrem 2.95E-04 3.93E-03 3.06E-04 4.08E-03 Lung 7.5 mrem 2.95E-04 3.93E-03 3.06E-04 4.08E-03 GI-LLI 7.5 mrem 2.95E-04 3.93E-03 3.06E-04 4.08E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrom 3.64E-08 2.43E-07 Liver 15.0 mrem 6.01 E-04 4.00E-03 T. Body 15.0 mrem 6.01 E-04 4.00E-03 Thyroid 15.0 mrem 6.04E-04 4.02E-03 Kidney 15.0 mrem 6.01 E-04 4.00E-03 Lung 15.0 mrem 6.01 E-04 4.00E-03 GI-LLI 15.0 mrem 6.01 E-04 4.00E-03 75
5 i
4 i
I.
'l TABLE 2-7AA VOGTLE ELECTRIC GENERATING PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM
- JULY,1995 THROUGH DECEMBER,1995 l
l UNIT 1 i
} LIMIT LIMIT j Bone 7.5 mrem 2.09E-09 2.79E-08 3.00E-08 4.00E-07 j Liver 7.5 mrem 1.43E-04 1.91 E-03 2.37E-04 3.16E-03 i T. Body 7.5 mrem 1.43E-04 1.91 E-03 2.37E-04 3.16E-03 i Thyroid 7.5 mrom 1.44E-04 1.91 E-03 2.37E-04 3.16E-03 l Kidney 7.5 mrem 1.43E-04 1.91 E-03 2.37E-04 3.16E-03
- Lung 7.5 mrom 1.43E-04 1.91 E-03 2.37E-04 3.16E-03 i GI-LLI 7.5 mrem 1.43E-04 1.91 E-03 2.37E-04 3.16E-03 i
CUMULATIVE DOSE PER YEAR l ORGAN ODCM UNITS YEAR TO DATE % of ODCM t l LIMIT LIMIT
! Bone 15.0 mrom 6.85E-08 4.57E-07 Liver 15.0 mrom 9.81 E-04 6.54E-03
) T. Body 15.0 mrem 9.81 E-04 6.54E-03
} Thyroid 15.0 mrom 9.84E-04 6.56E-03
{ Kidney 15.0 mrem 9.81 E-04 6.54E-03 i Lung 15.0 mrem 9.81 E-04 6.54E-03 j GI-LLI 15.0 mrom 9.81 E-04 6.54E-03 l
i i
i a
1 j
- 76 l
TABLE 2-7B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JANUARY,1995 THROUGH JUNE,1995 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 7.5 mrem 1.37E-05 1.82E-04 1.35E-08 1.80E-07 Liver 7.5 mrem 5.43E-05 7.24E-04 1.74E-05 2.32E-04 T. Body 7.5 mrem 5.42E-05 7.23E-04 1.74E-05 2.32E-04 Thyroid 7.5 mrem 1.11 E-04 1.48E-03 1.77E-05 2.36E-04 Kidney 7.5 mrem 5.44E-05 7.25E-04 1.74E-05 2.32E-04 Lung 7.5 mrem 5.80E-05 7.73E-04 1.74E-05 2.32E-04 GI-LLI 7.5 mrem 5.42E-05 7.23E-04 , 1.74E-05 2.32E-04 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT Bone 15.0 mrem 1.37E-05 9.13E-05 Liver 15.0 mrem 7.17E-05 4.78E-04 T. Body 15.0 mrem 7.16E-05 4.77E-04 Thyroid 15.0 mrem 1.29E-04 8.59E-04 Kidney 15.0 mrem 7.18E-05 4.79E-04 Lung 15.0 mrem 7.53E-05 5.02E-04 GI-LLI 15.0 mrem 7.16E45 4.77E-04 l
l 77
TABLE 2-7BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1995 THROUGH DECEMBER,1995 UNIT 2 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF l LIMIT 3 ODCM 4 ODCM LIMIT LIMIT l Bone 7.5 mrem 2.01 E-08 2.68E-07 1.91 E-07 2.54E-06 i Liver 7.5 mrem 1.06E-04 1.41 E-03 1.62E-04 2.16E-03 T. Body 7.5 mrom 1.06E-04 1.41 E-03 1.62E-04 2.16E-03 l Thyroid 7.5 mrem 1.07E-04 1.43E-03 1.62E-04 2.16E-03 l Kidney 7.5 mrem 1.06E-04 1.41 E-03 1.62E-04 2.16E-03 l Lung 7.5 mrem 1.06E-04 1.41 E-03 1.62E-04 2.16E-03 l GI-LLI 7.5 mrem 1.06E-04 1.41 E-03 1.62E-04 2.16E-03 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT UMlY Bone 15.0 mrem 1.39E-05 9.27E-05 Liver 15.0 mrem 3.39E-04 2.26E-03 T. Body 15.0 mrem 3.39E-04 2.26E-03 Thyroid 15.0 mrem 3.98E-04 2.65E-03 Kidney 15.0 mrem 3.39E-04 2.26E-03 Lung 15.0 mrem 3.43E-04 2.29E-03 GILLI 15.0 mrom 3.39E-04 2.26E-03 l
l l
i 78
l TABLE 2-8 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES l
VOGTLE ELECTRIC GENERATING PLANT l
JANUARY,1995 THROUGH DECEMBER,1995 1
The values in this table represent a priori Minimum Detectable Concentration (MDC) which are typically achieved in laboratory analyses of gaseous radwaste samples.
RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 uCi/cc Kr-88 2.53E-08 uCi/cc Xe-133 2.05E-08 uCi/cc Xe-133m 8.63E-08 uCi/cc Xe-135 7.12E-08 uCi/cc Xe-138 1.05E-07 uCi/cc l-131 7.93E-15' uCi/cc Mn-54 3.94E-14
- uCi/cc Fe-59 2.45E-14' UCi/cc Co-58 1.39E-14
- uCi/cc Zn-65 2.82E-14
- uCi/cc Mo-99 9.57E-14
- uCi/cc Cs-134 1.12E-14
- uCi/cc Cs-137 8. 71E-15' uCi/cc Ce-141 8.62E-15* uCi/cc Ce-144 2. 77E-14' UCi/cc Sr-89 1.00E-13 uCi/cc St-90 1.00E-13 uCi/cc H-3 9.00E-08 uCi/cc Gross Alpha 1.00E-13 uCi/cc Based on an estimated sample volume of 5.7E-08 cc's.
79 m
3.0 Solid Waste l
l 3.1 Regulatory Limits /ODCM The ODCM Limits presented in this section are for Unit 1 and Unit 2 and are stated in part.
3.1.1 Use of Solid Radioactive Waste System 10.2.1 Process Control Program Radioactive wastes shall be solidified or dewatered in accordance with the .
l Process Control Program to meet shipping and transportation requirements l l during the transit, and disposal site requirements when received at the disposal site. l 3.1.2 Reporting Requirements !
6.8.1.4 l
The Annual Radioactive Effluent Release Report covering the operation l of the units during the previous calendar year shall be submitted before May 1 of each year. The report shallinclude a summary of the quantities of radioactive l liquid and gaseous effluents and solid waste released from the unit. The material !
provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix l to 10 CFR, Part 50. l l 3.1.3 Process Control Program (PCP) ;
i l
6.12.2 Licensee - initiated changes to the PCP Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change (s) was made.
There were no changes to the PCP in 1995.
7 80
l l
l 3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.
4.0 Changes to the Vogtle Electric Generating Plant ODCM 6.13.2 There were no changes to the Vogtle Electric Generating Plant ODCM for the period January 1,1995 through December 31,1995.
4.0 of ODCM The Radiological Environmental Monitoring Program shall be conducted as specified in ODCM 4.1.1 and 4.1.2.
i Table Notation (1) states in part:
"It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.
In these instances, suitable alternative media and locations may be chosen l for the particular pathway in question and appropriate substitutions, if available, l will be made within 30 days in the Radiological Environmental Monitoring l Program given in the ODCM."
l Pursuant to specification 6.13, submit in the next Radioactive Effluent Release l
l Report documentation for a change in the ODCM including a revised figure (s) l and Table for the ODCM reflecting the new location (s), if any, with supporting information identifying the cause of the unavailability of samples for the pathway and justifying the selection of the new location (s) for obtaining samples, or the unavailability of suitable new locations.
4.1.2 of ODCM states in part:
"A Land Use Census shall be conducted . .
The Action Statement for this requirement states in part:
- a. " With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the
. value currently being calculated in ODCM 4.12.1 pursuant to specification 6.13. Identify the new location (s) in the next t
Annual Radioactive Effluent Release Report ".
1 81
4.1 Changes in the Radiological Environmental Monitoring Program -
For this reporting period, there has been no changes to the Radiological Environmental Monitoring Program.
5.0 Doses to Members of the Public inside the Site Boundary 6.8.1.4 states in part:
"This same report shall also include assessment of the radiation doses from radioactive -
liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the Site Boundary during the report period. All assumptions used in making these ,
assessments, i.e., specific activity, exposure time, and location shall be included in these )
reports". )
The locations of concern within the site boundary are the Visitors Center and Plant .j Wilson. The activities at the Visitor Center consist of occasional attendance at meetings i and/or short visits for informational purposes. The activity at Plant Wilson in the past has consisted of regular employment. However, during 1995, Plant Wilson was converted to a VEGP facility. In future effluent reports Plant Wilson will not be a location for doses to members to the public, but doses were calculated for the entire year 1995 to be in conformance with the ODCM. l l
l There will be no radiation dose at these locations due to radioactive liqu:d effluents.
Delineated in Table 4-1 for each of these locations are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents. Listed in this table are distances and directions from a point midway between the center of Unit 1 and the Unit 2 reactors, the dispersion and deposition factors for any releases from the plant vent (mixed mode) and from the turbine building (ground level), and the estimated maximum occupancy factor for an individual and the assumed age group of this individual.
The source term is not listed in Table 4-1. The source term is listed in Tables 2-3A,2-3AA,2-3B, and 2-3BB for the mixed mode releases. Similarly, it is listed in Tables 2-4A, 2-4AA,2-48, and 2-4BB for the ground level releases . The tritium releases in units of curies were as follows:
QUARTER 1 2 3 4 i Mixed Mode 7.31 E+01 7.13E+01 5.50E+01 8.71 E+01 Ground Mode 2.06E-01 0.00E+00 6.00E-03 0.00E+00 82
l l
The maximum doses in units of mrem accumulated by an individual MEMBER i l
OF THE PUBLIC due to their activities inside the site boundary during I the reporting period were assessed to be as follows: l l
l VISITOR CENTER Quader 1 and 2 Quader 3 and 4
\
l Total Body 3.46E-06 9.87E-08 l (Direct Radiation from Plume) l PLANT WILSON ,
Quarter 1 and 2 Quarter 3 and 4 l Total Body 4.24E-04 1.21 E-05 l (Direct Radiation from Plume)
. l l VISITOR CENTER \
l Quader 1 Quader 2 Quader 3 Quader 4 Maximum Organ 6.26E-06 8.31 E-07 6.40E-07 1.02E-06 l (Thyroid)
(Inhalation Ground Plane) l PLANT WILSON Quader 1 Quader 2 Quader 3 Quader 4 Maximum Organ 6.82E-04 1.09E-04 8.42E-05 1.34E-05 (Thyroid) l (Inhalation Ground Plane) l l
l 83
TABLE 3-1 i
l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY 1,1995 THROUGH JUNE 30,1995 l
l
! A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) l l
- 1. Type of waste Unit $4nonth Est. Total Period Error, %
- a. Spent resins, filter sludges, m3 2.349E+01 l evaporator bottoms, etc. Cl 1.047E+02 1.0E +01
- b. Dry waste, contaminated m3 5.745E+01 compressible equip, etc. Cl 1.402E+01 4.0E+01
- c. Irradated ccirpur-ras, control m3 rods, etc. Ci NONE NONE
- d. Other (desenbe) m3 1
, Cl NONE NONE i
l
- 2. Estimate of major nuclide composition (by type of waste).
l a. Fe-55 % 6.576E+00 l
Co-60 % 2.201 E+01 Ni-63 % 5.408E+01 All others % 1.733E+01
- c. N/A % N/A N/A % N/A l N/A % N/A
- d. N/A % N/A N/A % N/A N/A % N/A 4
84 t
l
l l
l l
- 3. Solid Waste Disposition Number of Mode of
! Shloments Transportation Destination I 4 Tracta/ Trailer / Shielded Cask Chem-Nuclear Systems, Inc.
Bamwell, S.C.
- 13 Tractor / Trailer Scientirm Ecology l Group, Oak Ridge
( TN.
, 8 Tnctor/ Trailer Arnerman Ecology l
Group, Oak Ridge TN.
1 Tractor /Traier/ Shielded Cask Scientire Ecology Group, Oak Ridge i
TN.
l B. IRRADIATED FUEL SHIPMENTS (Dispostion)
Number of Mode of Shioments Transom 1ation Destination None None None 85
i l
l ADDITIONAL INFORMATION REQUIRED BY TECH SPECS:
- I Shioment No. Waste Class Tvoe Container
( Shiocina Class Solidifcation Aaent l l RWS-95-001 A Stable Type A LSA' NONE ;
I RWS-95-002 A - Stable Type A LSA NONE RWS-95-003 8 Stable Type A LSA NONE l l
RWS-95-004 A - Stable Type A LSA NONE )
RVRS-95-001 A - Unstable Strong Tight LQ NONE RVRS-95-002 A - Unstable Strong Tight LQ NONE RVRS-95-003 A Unstabie Strong Tight LSA NONE RVRS-95-004 A Unstable Strong Tght LQ NONE RVRS-9S-005 A - Unstable Strong Tight LSA NONE I RVRS-95-006 A Unstable Strong Tight LQ NONE RVRS-95-007 A - Unstable Strong Tight LQ NONE RVRS-95-008 A - Unstable Strong Tight LSA NONE RVRS-95 009 A - Unstable Strong Tight LSA NONE i RVRS-95-010 A - Unstable Strong Tight LSA NONE RVRS-95411 A - Unstable Strong Tght LQ NONE RVRS-95-012 A - Unstable Strong Tght LSA NONE RVRS-95-013 A - Unstable Strong Tght LSA NONE RVRS-95-014 A - Unstable Strong Tight LSA NONE RVRS-95-015 A Unstable Strong Tight D.O.T. EXEMPT NONE RVRS-95-016 A - Unstable Strong Tight D.O.T. EXEMPT NONE RVRS-95-017 A Unstable, Strong Tight D.O.T. EXEMPT NONE RVRS-95-018 A - Unstable Strong Tight D.O.T. EXEMPT NONE RVRS-95-019 A - Unstable Strong Tght D.O.T. EXEMPT NONE RVRS-95420 A - Unstable Strong Tight D.O.T. EXEMPT NONE RVRS-95 021 A - Uristable Strong Tght D.O.T. EXEMPT NONE RVR S-95-022 A - Unstable Strong Tght D.O.T. EXEMPT NONE 86
TABLE 3-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS JULY 1,1995 THROUGH DECEMBER 31,1995.
A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)
- 1. Type of waste Unit 6-month Est. Total Period Error, %
- a. Spent resins, filter sludges, m3 4.936E+00 evaporator bottoms, etc. Ci 4.173E+01 1.0E+01
- b. Dry compressible waste, m3 6.626E+00 contaminated equip, etc. Ci 1.337E-01 4.0E+01
- c. Irradiated components, contJol m3 rods, etc. Ci NONE NONE
- d. Other (describe) m3 Ci NONE NONE
- 2. Estimate of major nuclidt composition (by type of waste).
- b. Fe-55 % 5,327E+01 Co-58 % 1.405E+01 N43 % 8.984E+00 All others 'A 2.371 E+01
- c. N/A % N/A N/A % N/A N/A % N/A
- d. N/A % N/A N/A % N/A N/A *A N/A i
87
a l
I
- 3. Solid Waste Disposition Number of Mode of Shloments Transportation Destination 1 Tractor / Trailer / Shielded Cask Chem-Nuclear Systems, Inc.
i Barnwell, S.C. '
l 3 Tractor / Trailer Scientific Ecology Group, Oak Ridge TN.
1 Tractor /Traile. American l Ecology, Oak l Ridge TN.
l B. IRRADIATED FUEL SHIPMENTS (Dispostion)
Number of Mode of l Shioments Tran.cortation Destination l
l None None None l ADDITIONAL INFORMATION REQUIRED BY TECH SPECS:
l l
Shioment No. Waste Class Tvoe container Shioning Class f Solidiicaten Aaent I RWS-95005 B . Stable Type A LSA NONE '
RVR S-95-023 A . Unstable Strong Tight D.O.T. EXEMPT NONE RVRS-95-024 A - Unstable Strong Ticht D.O.T. EXEMPT NONE :
RVRS-95-025 A Unstable Strong Tight LQ NONE RVRS-95 026 A Unstable Strong Tight LSA NONE i.
l l
l e
88
Table 4-1 Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1995 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Starting: 01-Jan-1995 Ending: 31-Dec-1995 Location Name Visitor Center Plant Wilson Distance (meters) 4.47e+02 1420 Sedor SE ESE X/Q(sedm3) (1) 5.93E-06 9.45E-07 Cepleted X/Q(sedm3) (2) 5.58E-06 8.34E-07 D/Q(m2) (1) 2.28E-08 4.20E-09 X/Q(Sedm3) (2) 7.12E-07 1.76E-07 Depleted X/Q(sedm3) (2) 6.74E-07 1.59E-07 D/Q(m2) (2) 5.77E-09 2.07E-09 Occupancy Factor 0.00046(4hr/yr) 0.228(2000hr/yr)
Age Group Child Adult VISITOR CENTER UNITS QTR 1 QTR2 Total Q1 & QTR3 QTR4 Total Q3 &
O2 Q4 Total Body mrem 3.40E-06 6.40E-08 3.46E-06 3.78E-08 6.08E-08 9.87E-08 Dose Organ Bone mrem 5.25E-06 6.38E-06 5.32E-06 3.76E-08 5.15E-08 8.91 E-08 Liver mrem 6.10E-06 8.26E-07 6.93E'-06 6.37E-07 1.02E-06 1.66E-06 Tbody mrem 6.10E-06 8.26E-07 6.93E-06 6.37E-07 1.02E-06 1.66E-06 Thyroid mrem 6.25E-06 8.31 E-07 7.08E-06 6.40E-07 1.02E-06 1.66E-06 Kidney mrem 6.10E-06 8.26E-07 6.94E-06 6.37E 07 1.02E-06 1.66E-06 Lung mrem 6.11 E-06 8.26E-07 6.94E-06 6.37E-07 1.02E-06 1.66E-06 GI-LLI mrem 6.10E-06 8.26E-07 6.93E-06 6.37E-07 1.02E-06 1.66E-06 PLANT WILSON UNITS G7R 1 QTR2 Total Q1 & QTR3 QTR4 Total Q3 &
Q2 Q4 Total Body mrem 4.17E-04 7.84E-06 4.24E-04 4.64E-06 7.45E-06 1.21E-05 Dose Organ Bone mrem 5.57E-04 7.87E-06 5.65E-04 4.64E-06 6.38E-06 1.10E-05 Liver mrem 6.69E-04 1.09E-04 7.77E-04 8.40E-05 1.34E-04 2.18E-04 Tbody mrem 6.69E-04 1.09E-04 7.77E-04 8.40E-05 1.34E-04 2.18E-04 Thyroid mrem 6.81 E-04 1.09E-04 7.90E-04 8.42E-05 1.34E-04 2.18E-04 Kidney mrem 6.69E-04 1.09E-04 7.77E-04 8.40E-05 1.34E-04 2.18E-04 Lung mrem 6.70E-04 1.09E-04 7.78E-04 8.40E-05 1.34E-04 2.18E-04 GI-LLI mrem 6.69E-04 1.09E-04 7.77E-04 8.40E-05 1.34E-04 2.18E-04 89
i 6.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 6.8.1.4 states in part:
The Annual Radioactive Effluent Release Report shall include " . . any major change to liquid, gaseous, or solid radwaste treatment systems pursuant to Specification 6.14 "
Gaseous Radwaste System There were no major changes to the gaseous radwaste system in 1995.
l Solid Radwaste System
' i There were no major changes to the solid radwaste system in 1995. '
Liquid Radwaste System There were no major changes to the Liquid Radwaste Treatment System in 1995.
l l 7.0 Meteorological Data l 6.8.1.4 states in part:
The Annual Radioactive Effluent Release Report to be submitted by May 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmosphere stability, and precipitation (if l measured), or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.
In lieu of submission with Annual Radioactive Effluent Release Report, the licensee has retained this summary of required meteorological data on site in a file that shall be 1 provided to the NRC upon request.
! 4 8.0 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 6.8.1.4 states in part that:
The Annual Radioactive Effluent Release Report shall also include the following:
..an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.. "
All inoperabi!ity of liquid and gaseous effluent monitors were corrected within the specified time for this reporting period.
90
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i 9.0 Tanks Exceeding Curie Content Limits The Annual Radioactive Effluent Release Reports shall also include the following:
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" . .and description of the events leading to liquid holdup tanks or gas storage tanks
(
exceeding the limits of Technical Specifications 3.11.1.4 or 3.11.2.6, respectively . . "
1 There were no temporary liquid hold up tanks for radioactive liquids or gas storage tanks during this reporting period.
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