ML20082V278
| ML20082V278 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1994 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20082V281 | List: |
| References | |
| NUDOCS 9505090159 | |
| Download: ML20082V278 (154) | |
Text
- - ' " ' ' ~
p , s i
i I
4 GEORGIA POWER COMPANY ;
VOGTLE ELECTRIC ' GENERATING PLANT - UNITS 1 AND 2 :
NRC DOCKET NOS.'50-424 AND 50-425 j FACILITY OPERATING LICENSE NOS. NPF-68 AND NPF-81 199fANNUAL REPORT - PART 2 l TABLE OF CONTENTS 'i I. INTRODUCTION l
II. ANNUAL ENVIRONMENTAL OPERATING REPORT ]
Ill. ANNUAL RADIOLOGICAL ENViltONMENTAL SURVEILLANCE REPORT IV. ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT ,
zi i
i 1
I l
^
9505090159 941231 PDR ADOCK 05000424 R PDR l'
a y b ..
l
'i
- s. .:
f.; I- j GEORGIA POWER COMPANY ~
VOGTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 - .
NRC DOCKET NOS. 50-424 AND 50-425
_ - . I FACILITY OPERATING LICENSE NOS NPF-68 AND NPF-81 :
I I
INTRODUCTION !
The Vogtle Electric Generating Plant Units 1 and 2 are powered by pressurized water - !
reactors, each rated at 3411 megawatts thermal. It is located on the Savannah River in .l 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 finh fuel cycle. Unit 2 received it: operating license on February 9, .
j 1989, began commercial operation on May 20,1989. Unit 2 is operating in its fourth fuel ;
cycle.
l i
q
_i 5
4 k
a
y .-
l
, lt II -
GEORGIA POWER COMPANY 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 ANNUAL ENVIRONMENTAL OPERATING REPORT (NONRADIOLOGICAL) i
-,=
x =c:
!s x
VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 ANNUAL ENVIRONMENTAL OPERATING REPORT (NONRADIOLOGICAL) 1994-SPECIFICATION in accordance with Section 5.4.1 of the Vogtle Electric Generating Plant (VEGP) Environmental Protecten Plan (Nonradiologpcal), Appendix B to Facility Operating License Nos. NPF48 and -
NPF-81, this report is submitted describing implementation of the Environmental Protection Plan for the calendar year 1994.
- - REPORTING REOUIREMENTS A. Summaries and Analyses of Results of the Environmental Monitoring Activities for the Reporting Period
- 1. Aquatic Monitonng - Liquid cHluent monitonng was p.fviiid in acceid :4 with National Pollutant Discharge Elinunation System (NPDES) Permit GA 0226786; there was no additional requirement for aquatic monitonng during 1994. One mmor NPDES Permit noncompliance evcat was reported to the State of Georgia during 1994.
- 2. Terrestrial Monitonng - Terrestnal monitonng is not required.
- 3. Maintenance of Transmission Line Corndors
- a. Corndor re cleanng was cW~I on the VEGP 'Ihalman 500 kV line in 1994.
Maintenance work was gifviiid with rotary mowers equipped with low ground pressure tires. In cultural resource areas, cleanng was conducted by hand utilizing chain saws and brush axes wie,re necessary.
Wre was no herbicide usage associated with any comdor man >*m during 1994.
Wre were no other transmission corndor maintenance actisitics conducted on VEGP-related transmission lines during 1994.
- b. Wre were no cleanng or maintenance activities Weai within the Ebenezer Creek or Francis Plantation areas during 1994.
- c. Routine maintenance activities within the designated cultural properties along transmission line corndors were conducted in accordance with the Final Cultural Resources Management Plan.
, ] 1
. U. S. Nuclear Regulatory Comunission Page Two i 4 Noise Monitoring - There were no complaints received by Georgia Power ;
Company during 1994 regarding noise along the VEGP-related high voltage ;
transmission lines. 1 i
B. Comparison of the 1994 Monitoring Activities with Preoperational Studies, l Operational Controls, and Previous Monitoring Repoets l
These programs were not required becase no nonradiological environmmtal monitonng programs were cW~i during the reporting penod beyond those performed in ,
accordance with NPDES Permit No. GA 0026786 referenced in Section A above. :
I C. An Assessaient of Observed Impacts of Plant Operation on the Environment f
r There were no significant adverse environmental impacts associated with plant operation in 1994. .
D. Environmental Protection Plan (EPP) Noncompliances and Corrective Actions j There were no EPP noncompliances during 1994.
E. Changes in Station Design or Operation, Tests, or Experiments Made in Accordance with EPP Subsection 3.1 which Involved a Potentially Significant Unreviewed ;
Environ ===tal Question
'nere were no changes, tests, or experiments in 1994 which involved a potatially ,
significant unreviewed environmental question. I F. Nonroutine Reports Submitted in Accordance with EPP Subsection 5.4.2 l There were no nonroutine reports submitted in 1994. l L
h i
i f,
i
.I
'III j GEORGIA POWER COMPANY !
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 '
-i s
ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT, f i
l 4
l i
l i
-t l
)
i l
I
V0GTLE ELECTRIC GENERATING PLANT RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT TABLE OF CONTENTS SECTION TITLE PAGE
1.0 INTRODUCTION
1-1 2.0
SUMMARY
DESCRIPTION 21 3.0 RESULTS
SUMMARY
31 4.0 DISCUSSION 0F RESULTS 41 4.1 Airborne 4-4 4.2 Direct Radiation 4-6 4.3 Milk 4-9 4.4 Vegetation 4-10 4.5 River Water 4-12 4.6 Drinking Water 4-14 4.7 Fish 4-17 4.8 Sediment 4-19 5.0 INTERLABORATORY COMPARIS0N PROGRAM 5-1
6.0 CONCLUSION
S 6-1 i
J
t LIST OF TABLES TABLE TITLE EASE 2-1
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2-?
22 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 2-7 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
3-2 4-1 LAND USE CENSUS RESULTS 4-3 5-1 PERFORMANCE EVALUATION PROGRAM RESULTS 5-2 ii
.3 r-LIST OF FIGURES FIGURE TITLE EAGE ,
2-1 TERRESTRIAL STATIONS NEAR SITE BOUNDARY 2 10 2-2 TERRESTRIAL AND A0 VATIC STATIONS WITHIN SIX MILES 2-11 2-3 TERRESTRIAL STATIONS BEYOND SIX MILES 2-12 2-4 DRINKING WATER STATIONS 2-13 1
iii J
E p
[D ACRONYMS A2LA American Association of Laboratory Accreditation ASTM American Society for Testing and Materials CFR Code of Federal Regulation CL Confidence level EL Environmental Laboratory EPA Environmental 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 TS Technical Specifications VEGP Alvin W. Vogtle Electric Generating Plant iv
l V0GTLE ELECTRIC GENERATING PLANT .
RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT
1.0 INTRODUCTION
l 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 radiological impact upon the environment due to plant operation.
The bases for such an assessment include 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.
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.
The REMP is conducted in accordance with Technical Specifications (TS) 6.7.4.g and Chapter 4 of the Offsite Dose Calculation Manual (ODCM). On January 1. 1994, the ODCM was amended and reorganized to accommodate implementation of the new 10CFR20 (Part 20 to Title 10 of the Code of Federal Regulations). May 21.1991. Although there were no essential changes to the REMP as a consequence of this amendment, there were changes to the Section Numbers along with a re wording of the text.
The REMP activities for 1994 are reported herein in accordance with TS 6.8.1.2 and ODCM 7.1. All dates in this report are for 1994 unless otherwise indicated.
e 1-1
_ _ _ _ _ _ _ _ - - - _ - _ _ _ _ - _ _ _ _ - _ _ _ _ - _ _ _ - - _ _ _ - _ _ _ _ _ - _m
e .
^
A summary description.of the REMP is provided in Section 2 of this 1 e report; maps showing the sampling stations are keyed to a table indicating the direction and distance of each station from a point i midway-between-the two reactors. An annual summary of the main :
laboratory analysis results obtained from the samples utilized for l environmental monitoring is presented in Section 3. A discussion 3 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 -l Interlaboratory Comparison Program are presented in Section 5. :
F Conclusions are stated in Section 6. i
.i T
r t
t
}
}
i
.i j
f I
1-2 :
i l
a 2.0.
SUMMARY
DESCRIPT!0N'
'f 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 21 is essentially a copy of. 0DCM !
Table ~4-1 which delineates the program's. requirements. Sampling. i I
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 'l 4.2. ;
6
.In accordance with ODCM 4.1.1.2.1, deviations from the required I sampling schedule as set forth in Table 2 1 are permitted if (
specimens are unobtainable due to r.azardous conditions, ~ ~
unavailability, inclement weather. equipment malfunction or other. !'
just reasons. Any deviations are accounted for in the discussions i for the particular sample types in Section 4. !
All laboratory analyses were performed by Georgia Power Company'_s j (GPC) Environmental Laboratory (EL) in Smyrna. Georgia. Since -
1987, the EL has been accredited by the American Association of l Laboratory Accreditation (A2LA) for radiochemistry. The A2LA is a {
nonprofit, nongovernmental. public service, membership society :
dedicated to the formal recognition of competent ' laboratories and f related activities. Accreditation is based upon internationally j accepted criteria for laboratory competence. ;
l l
l
- ]
i I
i I
2-1 l i
l 4
r - ~ . , ' . - .,*g ;.(
s ,~ ,
4 a
TABLE 2-1 (SHEET 1 0F 5)
SUMMARY
DESCRIPTION OF-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative ' Sampling and Type and Frequency Collection Freauency ~ of Analysis and/or Samole Samoles and Samole Locations Thirty nine routine monitoring Quarterly ~ Gamma dose, quarterly
- 1. Direct Radiation 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 outer ring of stations, one in each meteorological sector no at approximately 5 miles from 4 the site: and Special interest areas, such as population centers.-nearby' recreation' areas. and control stations.
i i
l
.._...__..-___._.._.._._____;..2.__..__...._2.__..._2...._..~__._.____....._.._ -....,_.-._u._~.........___..._..-_._:..__.._.__.e.2......2J
e TABLE 2-1 (SHEET 2 0F 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Representative Sampling and Type and Frequency-Exposure Pathway of Analysis Samoles and Samole Locations Collection Frecuency and/or Samole
- 2. Airborne Radiciodine and Samples from seven locations: Continuous sampler Radiciodine canister:
operation with sample I-131 analysis, weekly.
Particulates collection weekly, or Five locations close to the _
Particulate sampler:
site boundary in different more frequently if.
required by dust Gross beta analysis (1)-
sectors:
loading following filter change A community having the highest and gamma isotopic calculated annual average analysis-(2) of composite ground-level D/0: and (by location) quarterly m
Ja A control location near a population center at a distance of about 14 miles.
- 3. Waterborne One sample upriver Composite sample over- Gamma isotopic analysis (2),
i
- a. Surface (3) one month period (4) monthly. Composite for tritium analysis, quarterly; Two samples downriver F
i
--~,,a ..n-- , _ . _ . . _ . , _ - , - _ _ _ , ,_ __ _, _
4 -
TABLE 2-1 (SHEET 3 0F 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Representative Sampling and Type and:Fraquency Collection Frecuency of Analysis' and/or Samole Samoles and Samole-Locations
- 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 of each 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 en raw and' m
A plant every two weeks finished water, quarterly..
or monthly, as appropriate.
- c. Sediment from One sample from downriver area Semiannually Gamma isotopic analysis (2).
semiannually Shoreline with existing or potential recreational value One sample from upriver area i 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 D h-Time * * &*ww**- pir---4*-mys~*- w he *e *tew e -w 'ew--'-? +Ne*e -E- e T w' -m w'- '*tpe--w wt .c T-ps'*p1-Pt -tf y e-ym e4,t y =g et w n 4 wy--.eig-31,- w- my-mee -g,-syr,r*wer-'--W,w-tu-ire.'st-pw--*-+y1er-"? ei"f--'t+7 -t 'r W 1ttw 'e
- n, TABLE 2-1 (SHEET 4 0F S)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Representative Sampling and Type and Frequency Exposure Pathway Collection Frecuency of Analysis and/or Samole Samoles and Samole locations At ". east one sample of any Semiannually Gamma isotopic analysis (2)
- b. Fish on edible portions, commercially or recreationally semiannually important species near the 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 7
plant discharge One sample from two onsite Monthly during the Gamma isotopic analysis (2.7).
- c. Grass or monthly Leafy locations near the site growing season Vegetation boundary in different sectors One sample from a control location at a distance of about 17 miles
1 TABLE 2-1 (SHEET 5 0F 5)
SUMMARY
DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Airborne particulate sample filters shall be analyzed for 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 sarples, 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 signif; cant 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 short (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 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 1-131 may be performed.
2-6
, ?l; .
t an TABLE 3-1 (SHEET 2 0F 11) i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 Vogtle Electric Generating Plant, Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Type and Minimum Locations Annual Mean Locations Medium or Mean (b)-
Pathway Sampled Total Number Detectable Mean (b) Name Mean (b)
Range Distance & Range Range (Unit of of Analyses Concentration (MDC) (a) (Fraction) Direction (Fraction) (Fraction)
Measurement) Performed Milk Gamma Isotopic (pCi/1) 52 NDM NDM Cs-134 15 NA 18 NA NDM- NDM Cs-137 w
NDM NDM a Ba-140 60 NA NA- NDM NDM La-140 15 NDM NDM I-131 1 NA 52 Vegetation Gamma Isotopic (pCi/kg wet) 36
20-21 'Waynesboro .57-57 57-57
( 2/?.4 ) 16.7 miles (1/12) (1/12).
WSW.
" __ _ ______________ _ . ._ _ w
u---.
a 4
TABLE 3-1 (SHEET 3 0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SUMMAnY 700 1.994 Vogtle Electric Generating Plant. Docket Nos. 50-424 and 50-425 burke County Georgia Indicator' Location with Highest Control' Type and Minimum locations Annual Mean locations Medium or Mean (b)
Pathway Sampled Total Number Detectable Mean (b) Name Mean (b)
Distance & Range- -Range (Unit of of Analyses Concentration Range Performed (MDC) (3) (Fraction) Direction (Fraction) (Fraction)
Measurement)
River Water Gamma Isotopic (pCi/l) 24 124 (e) NDM NDM NDM Be-7 15 NDM NDM NDH Mn-54 w
NDM NDM NDM i Fe-59 30 15 NDM NDM NDM Co-58 NDM NDM NDM.
Co-60 15 30 NDM NDM NDM Zn-65 NDM NDM NDM Zr-95 30 NDM- NDM -NDM Nb-95 15 NDM NDM l-131 15 NDM 15 NDM- NDM NDM Cs-134-18 NDM NDM NDM Cs-137 60 NDM NDH NDM Ba-140
./
4 TABLE 3-1 (SHEET 4 0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 Vogtle Electric Generating Plant. Docket Nos. 50-424 and 50-425 Burke County Georgia Indicator Location with Highest Control Locations Annual Mean Locations Medium or Type and Minimum Mean (b)
Detectable Mean (b) Name. Mean (b)-
Pathway Sampled Total Number Range Distance & Range . Range (Unit of of Analyses Concentration (Fraction)' -(Fraction)
(MDC) (a) (Fraction) Direction Measurement) Performed NDM- NDM La-140 15 NDM No. 83 1258 257 Tritium 3000 1258 487-2130 Downriver 487-2130- 232-282 8
(4/4) 0.4 miles (4/4) (2/4) co a
3.51 No. 88 3.88 3.47 Gross Beta 4 Water Near 1.5-6.9. Port Went '2.4-5.8 1.8-6.1:
Intakes to 36-(23/24) Downriver -(11/12) (12/12)
Water 122 miles Treatment Plants (pCi/1)-
Gamma Isotopic 36 NDM NDM-Be-7 124 te) NDM NDM NDM NDM Mn-54 15 NDM NDM Fe-59 30 NDM NDM NDM NDM Co-58 15 NDM NDM Co-60 15 NDM
___-____;_____ _ ..._....-__.._...._._._.._-.._;.__._...____ _ _ , . . . _ , _ . . . . . _ . . . . . _ _ .,.,_.,._....,,.,._.._....___s
, , . z-
, .=
a TABLE 3-1 (SHEET 5 0F 11) l
- _ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994
' Vogtle Electric Generating Plant. Docket Nos. 50-424 and 50-425 Burke County. Georgia Indicator Location with Highest Control Type and Minimum Locations Annual Mean Locations-Medium or Mean (b) Mean (b)
Pathway Sampled Total Number Detectable Mean (b) Name Range Distance & Range Range (Unit of of Analyses Concentration (Fraction)
Performed (MDC) (a) (Fraction) Direction (Fraction)
Measurement)
NP/4 NDM NDM Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM NDM I-131 (f) 15 w NDH NDM di Cs-134 15 NDM NDM NDM NDM Cs-137 18 NDM NDM NDM Ba-140 60 NDM NDM NDM La-140 15 Tritium 3000 871- No. 88 897 NDM 12 587-1170 Port Went- 609-1170 (8/8) Downriver. (4/4) 122 miles 2.40 No. 80: 2.68 - 2.68 :
Finished Water Gross Beta 4 1,3-4.0 . Augusta 1.6-3.5 1.6-3.5-at Water 36 (11/12) (11/12)
Treatment (24/24) Upriver Plants 56 miles (pCi/1)
W--------.
- ._; .g I
TABLE 3-1 (SHEET 6 0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 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) of Analyses Concentration Range. Distance & Range ' Range (Unit of Performed (MDC) (a) (Fraction) Direction (Fraction) (Fraction)~
Measurement)
Gamma Isotopic 36 124 (e) NDM NDM NDM-Be-7 Mn-54 15 NDM N DM. NDM w
NDM 'NDM 4 Fe-59 30 NDH Co-58 15 NDM NDM .NDM Co-60 15 NDM NDM NDM~
Zn-65 30 NDM NDM NDM Zr-95 30 NDM NDM- NDM Nb-95 15 NDM NDM NDM Cs-134 15 NDM NDH NDM-Cs-137 18 NDM NDH NDM-Ba-140 60 NDM 'NDM NDM
ww<- -wi. u. . .nd_,.,__. ,m.owy,._.y., . , ,
ii TABLE 3-1 (SHEET 7.0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 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)
Concentration Range Distance & Range Range (Unit of of Analyses (Fraction)
Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction)
I-131 1 NDM NDM NDM 36 Tritium 2000 880 No. 87 907 131 oo 12 564-1190 Beaufort 654-1190 130-131 da (8/8). Downriver (4/4) (2/4) 112 miles Anadromous Gamma Isotopic-Fish 1 (pCi/kg wet) Be-7 655 (e) NDM NDM NA Mn-54 130 NDM NDM NA Fe-59 260 NDM NDM NA Co-58 130 NDM NDM NA Co-60 130 NDM NDM NA Zn-65 260 NDM .NDM- NA Cs-134 130 'NDM NDM NA' i
TABLE 3-1 (SHEET 8 0F 11) l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 Vogtle Electric Generating Plant. Docket Nos. 50-424 and 50-425 Burke County Georgia Indicator. Location with Highest Control-Type and Minimum Locations -Annual Mean Locations Medium or 'Mean (b)
Pathway Sampled -Total Number Detectable Mean (b) Name Mean (b)
Range Distance & Range Range (Unit of of Analyses Concentration Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) (Fraction)
- Fish Gamma Isotopic (pCi/kg wet) 8 NDM NDM w Be-7 655 (e) NDM e NDM Mn-54 130 NDM NDM NDM NDM-Fe-59 260 NDM NDM NDM NDM Co-58 130 NDM NDM NDM-Co-60 130 260 NDM NDM NDM Zn-65 130 NDM NDM NDM
- Cs-134 150 164.6 No. 81 199.5 199.5 Cs-137 27-329 Upriver 148-251 148-251 (3/3)- 4.7 miles (2/2) (2/2)-
g
,a TABLE 3-1 (SHEET 9 0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 Vogtle Electric Generating Plant. Docket Nos. 50-424 and 50-425' Burke County. Georgia Indicator . Location with Highest Control Minimum Locations Annual Mean Locations Medium or Type and .
Mean (b)
Detectable Mean (b) Name Mean (b)
Pathway Sampled Total Number Range Range Concentration Range Distance &'
(Unit of of Analyses (Fraction) Direction (Fraction) (Fraction)
Measurement) Performed (MDC) (a)
Sediment Gamma Isotopic (pCi/kg dry) 4 No. 83 1203 964 Be-7 655 (e). 1203 865-1540 Downriver 865-1540 '508-1420 (2/2) 0.6 miles _ (2/2) (2/2)
M Mn-54 42 (e) 31.6 No. 83 31.6 NDM 32-32 Downriver 32-32 (1/2) 0.6 miles '(1/2) 43.(e) 18.4 No. 83 18.4 NDM Co-58 18-18 Downriver 18-18 (1/2) 0.6 miles .(1/2)-
Co-60 70 (e) 85.2 No. 83 85.2 NDM-71-99 Downriver 71-99 (2/2) 0.6 miles (2/2) 51.4 No. 83 51.'4 - .NDM.
1-131 53 (e) 51-51 Downriver 51-51 (1/2) 0.6 miles '(1/2)
TABLE 3-1 (SHEET 10 0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 Vogtle Electric Generating Plant. Docket Nos. 50-424 and 50-425 Burke County, Georgia Indicator Location with Highest Control Type and Minimum Locations Annual Mean Locations Medium or Mean (b) Mean (b)
Pathway Sampled Total Number Detectable Mean (b) Name Range Distance & Range Range (Unit of of Analyses Concentration Measurement) Performed (MDC) (a) (Fraction) Direction (Fraction) (Fraction) 180 239.5 No. 83 239.5 117.5 Cs-137 177-302 Downriver 177-302 104-131 (2/2) 0.6 miles (2/2) (2/2)
Y C
i i
_ . _ _ . . . _ _ . _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . M
~- ~
7;c ,
3
-i i
F' TABLE 3-1 (SHEET'11 0F-11) q RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 : ;
Vogtle Electric Generating Plant.. Docket Nos. 50-424 Land.50-425 Burke County, Georgia l i
.NOTAT10NS' -l
" D- , I
(
- a. The MDC is defined in ODCM_10.1. Except.as noted otherwise, the values. listed in this column are the detection _
i capabilities required by ODCM Table 4-3. The values listed' in :
this column are a' priori (before the. fact).MDCs. In-practice. l the a posteriori (after the fact) MDCs are generally much ;
lower than the values' listed. Any a posteriori MDC greater- l than'the value.l.isted in this column is discussed in Section j
- 4. ;
- b. Mean and range are based upon' detectable measure'ents m only. i The fraction of all measurements at.a specified location which. 1 is detectable is placed in parenthesis, i i
- c. No Detectable Measurement (s).
I
- d. Not Applicable.
- e. The EL has determined that this value may be routinely ;
attained under normal conditions. No value is provided in !
ODCM Table 4-3. ;
i
required to be performed on these samples when the dose ;
calculated from the consumption of water is less then~1 mrem j per year. ;
I i
P l 4
3-12 i
. , , . + ~ . . . . . , - . . . . - - . - - ,-...w. .., , , ,- ,.
a-3
.q i
4.0 -DISCUSSION OF RESULTS. i
?
An interpretation and evaluation, as appropriate, of the ~
l laboratory results for each type sample are included in this ;
section. Relevant comparisons were made between the difference in. t
~
- average values. for indicator and control stations and the , _ ;
calculated Minimum Detectable Difference (HDD) between these two groups at the 99 percent Confidence' Level (CL). The MDD was 1 determined using the standard Student's t test. A difference.in l' the average values which was less than the' MDD was considered to be statistically indiscernible.
l i{
Pertinent results were also compared with past results including; i those obtained.during preoperation. The results.were-examined.to !
perceive any trends. To provide perspective, a result might also l
' be compared with its Reporting Level- (RL) or Minimum Detectable l Concentration (MDC) whose nominal values are found in ODCH Tables .!
4-2 and 4-3. respectively. Attempts were made to explain any.high t radiological levels found in the samples. During the y' ear there !
were no failures in the laboratory l analyses'for any of the samples 1 :l 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 l 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 j incident in the spring of 1986. After operation commenced, short term impacts included abnormal releases from SRS-during 1987 and 1991. -1 i
All results were tested for conformance to Chauvenet's Criterionl' 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. No datum was excluded for failing Chauvenet's Criterion only. Any exclusions are discussed in this section l under the appropriate sample type.
i j
- 1. G. D. Chase and J. L. Rabinowetz, Princioles of Radioisotone Methodoloav. (Burgess Publishing Company, 1962), pages 87-90. i I
41 :
l l
I i
y - ,
}
s L
The annual land use census ~as required by TS 6.7.4.g(2) and ODCM 4.1.2 was conducted on March 28 and 29 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. A milk animal is a cow or goat producing milk for human consumption. Land within SRS was' excluded from the census. The census results are tabulated in Table'4-1.-
ODCM 4.1.2.2.1 requires a new controlling receptor in' ODCM 3.4.3.
if the land use _ census identifies a location that yields a greater calculated dose. An analysis of the survey's results showed that there was none.
ODCM 4.1.2.2.2 requires that whenever the land use census identifies a location 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 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 census.
The annual survey of the Savannah River downstream of the plant for approximately 106 miles was conducted on September 20 to identify those who use water from the river for purposes of drinking or irrigation. As in all previous surveys, no intakes for drinking water or irrigation were observed. This result was corroborated by information obtained from the Georgia Department of Natural Resources and the South Carolina Department of Health and Environmental Control; it was learned that no water withdrawal-permits for drinking water or irrigation purposes had-been issued-for the Savannah River during the year. The two water treatment-plants used as indicator stations for drinking water are located further downriver.
4-2 4
r- 7 TABLE 4-1 LAND USE SURVEY RESULTS Distance in Miles to Nearest Location in Each Sector SECTOR RESIDENCE MILK ANIMAL GARDEN N 1.2 *
- NNE * *
- NE * *
- EllE E
ESE 4.0 *
- SE 4.3 *
- SEE 4.6 * *-
S 4.3
- SSW 4.7 *
- SW 2.9 *
- WSW 1.2
- W 1.8 WNW 1.9
- NW 1.6 *
- NNW- 1.4 *
- None within S miles and outside the SRS.
4-3
N 4.1 Airborne In accordance with Tables 2-1 and 2-2, airborne particulates and. >
airborne radioiodine were collected at 5 indicator stations (Nos. ;
3, 7, 10. 12 and 16) which encircle the site and are on the site i 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 was continuously drawn in sequence through 3 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 were collected weekly. Each of the air-particulate filters was counted for gross beta activity. A gamma ;
isotopic analysis was performed quarterly on a composite of the air particulate filters for each station. Each charcoal canister was analyzed for I-131 by gamma spectroscopy. {
Although there were no f ailures during 1994 in' obtaining acceptable airborne particulate and radiciodine samples, there. ,
were three occasions when a station was not operating for periods ranging from 2 to 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />. However, the sample results in each !
of these cases were deemed to be acceptable since the results for !
the gross beta analysis were found to conform with Chauvenet's !
Criterion.
For the March.15 collection at Station 12, the power was off 2 .
hours to accommodate the Environmental Protection Division of the ,
State of Georgia while they installed an air cabinet for an air ;
monitoring station at this location.
The air pump was not running at Station 36 when the field team arrived on June 28: it had been off for 18.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. The fuse in ;
the transformer had blown as a consequence of bad weather. The pump was placed on another circuit.
The air pump was not running at Station 12 when the field team j arrived on November 29: it had been off for 45.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. No obvious ]
reason for the pump stoppage was found. The faulty pump was replaced. ;
}
As seen in Table 3-1, the average weekly beta activity during 1994 for the indicator stations was 0.2 fCi/m' less than that for the control station. However, this difference was not discernible, since it was less than the MDD, calculated as 1.8 fCi/m*. During the 7 year period from 1987 through 1993, the average weekly activity for the year at the indicator stations randomly varied from 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 44
??x ; -7 stations'over this entire 7 year period was about 0.1'fCi/m' greater than that for the control station. The overall average
- -weekly activity for the indicator stations during preoperation was ;
0.8 (Ci/m' greater than that for the control station.
The average weekly gross beta activity.in units of fCi/m3 for the indicator.. control and community stations during 1994 are compared 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 1994 120.1 20.3 19.8 ;
1993 21.2 21.4 20.3 j 1992 18.7 19.3 18.0 1991 19.3 19.2 18.6 ,
1990 19.6 19.4 18.8 i 1989 19.1 18.2 18.8 1988 24.7 23.7 22.8 1987 23.0 23.5 22.3 i Preop Overall 22.9 22.1 21.9 i Preop Range 18.1-28.1 18.3-26.5 18.3-26.5 The average weekly readings for 1994 are seen to be within the range of values found previously. No trends were recognized in j these data. -l During 1994, no man made radionuclides were detected from the gamma isotopic analysis of the quarterly composites of the air particulate filters. During 1987. Cs-137 was found in one indicator composite at a level off 1.7 fCi/m'. During preoperation. Cs-137 was found in an eighth:of the indicator composites and a seventh of the control composites with average levels of 1.7 and 1.0 fCi/m' respectively: the HDC for airborne Cs-137 is 60 fCi/m*. Also, during preoperations. Cs-134 was found in about 8 percent of the indicator composites the average level was 1.2 fCi/m*: its MDC is 50 fCi/m' Airborne 1-131 was not detected in any sample during 1994 as during previous years of operation. ~ During preoperation. positive I results were obtained only during the Chernobyl incident when levels as high as 182 fCi/n were oytained. The MDC and RL for airborne I-131 are 70 and 930 fC1/m . respectively, i
4-5
7_ ,
4.2 Direct Radiation ,
Direct (external) radiation is measured with' thermoluminescent dosimeters (TLDs). Two Panasonic 00-814 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 I stations comprising the inner ring (Nos. I through 16) are located near the site boundary, while those comprising the outer ring 1 (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. 331. the town of Girard (No. .
35), and the employees' recreational area (No. 43). '
As shown in Table 3-1, the average quarterly exposure of 12.3 mR I acquired at the indicator statier; (imer ring) was 0.2 mR greater -
than that acquired at the contron stations. This difference was i not discernible since it was le',s than the MDD of 0.9 mR. During !
the 7 year period from 1.987 through 1993, the average quarterly l 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 'i stations over this 7 year period was 0.03 mR less than 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 :
1994 ranged from 9.7 to 18.0 mR. with an average of 11.9 mR which l was 0.4 mR less than that found for the inner ring. There was no ;
discernible difference between the averages for the inner and the ,
outer ring, since the difference was less than the MDD of 0.7 mR. I For the 7 year period beginning in 1987, the average quarterly j 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. I average quarterly exposure for the inner ring stations over this 7 j year period was 0.5 mR greater than that for.the outer ring 1 stations. The overall average quarterly exposure for the inner )
ring stations during preoperation was 0.6 mR greater than that for '
j the outer ring stations.
I 4-6
~u.
6 l
i Listed below for the indicator, control and outer ring stations, are the average quarterly 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._ ,
i Period Indicator Control' Outer Rina ,
I 1994' 12.3 12.1 11.9 i 1993 12.4 12.4 12.1 1992 12.3 12.5' 12.1 1991 16.9 17.1 16.7- .
1990 16.9 16.6 16.3 a 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 ;
The average quarterly exposures in units of mR at.the special i interest areas for the same periods as given above are listed ;
below. These exposures are within the range of those acquired'at _
the other stations.
Period Station 33 Station 35 111 tion 43 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 16.7 17.4 1988 19.7 18.1 14.8 i 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- ,
There were 2 failures to obtain a measurement of the quarterly .
These occurred at Station 29 in'the third gamma dose during 1994.
quarter and at Station 22 in the fourth quarter. In addition the readings for.3 badges from different stations exposed during the i first quarter were deemed unacceptable. .:
f 4-7 i L
l T
-h
r; -g 7x
-t 4
e ,
During the visual inspection of the TLDs in the third quarter, the badges at Station 29 were discovered to be missing. The tree-upon I which they were lodged.had been removed. A search of the area- l failed to locate either of.the~ badges. Replacement badges were- ,
installed to measure the exposure during the remaining 6 weeks. of !
the quarter. The quarterly dose determined from the readings of ;
the replacement badges was. deemed unacceptable and excluded from ,
the data set since it failed the test for conformance with !
Chauvenets Criterion, j When the.TLDs were exchanged at the.end of'the fourth quarter.-the .i badges at Station 22 were missing. Theft is hypothesized. The _
badges for the next quarter were placed in a secure cage.
The. readings for TLDs 8A 14B and 36A for the first quarter were !
deemed unacceptable as each had a standard deviation greater than the self imposed limit of 1.4. Corsequently, only the readings ,
for the companion badges were used in determining the exposures l for the first quarter at these stations. -[4 The high standard deviations for TLDs 8A and 36A are. attributed to r water damage the seals in the plastic bags were found to leak. A careful examination of TLD 14B failed to reveal any apparent damage. Greater care is now being taken in handling the badges in the field.
The standard deviation limit of 1.4 was calculated using a. method2 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.
- 2. ASTM Special Technical Publication ISD. ASTM Manual on Presentation of Data and Control Chart Analysis. Fourth Revision.
Philadelphia, PA October 1976.
4-8
l
~4.3 Milk In accordance with Tables 2-l'and 2-2. milk samples were collected biweekly from two control stations, the W. C. Dixon Dairy (Station
- 98) and the Boyceland Dairy (Station 99). Gamma isotopic.and I-131 analyses were 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 sample is yet to be obtained during operation. As discussed in Section 4.0. no milk animals were'found in the 1994 land use census.
No man-made radionuclides were found from the gamma isotopic analysis of the milk samples.during 1994. 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/1, respectively.
During preoperation. Cs-134 was detected in one sample and in the first year of operation 2n-65 was detected in one sample.
1-131 was not detected in any of the milk samples during 1994. In 1990. 1-131 was reported in two samples but its presence was questionable due to large counting uncertainties. 1-131 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/1. respectively.
4-9
l n-0 e L
'I L '4.4 Vegetation 'l i
In accordance with Tables 2-1 and 2-2. gamma isotopic analysis was performed on each grass sample collected monthly.at two_ indicator !
stations which are located onsite near the site boundary in {
different meteorological sectors (Stations 7 and 15) and at one
{
control station located about 17 miles from the plant (Station i 37). ;
The results presented in Table 3-1 show that Cs-137 was the only 5 man-made radionuclide detected during 1994. . The average value of (
the two positive results found_at the indicator stations was_20.7 l pCi/kg wet which is less than the one positive result of 57.4 l pCi/kg wet found at the control station. .!
The average level of Cs-137 found in vegetation samples in units of pCi/kg wet along with the fraction of detectable measurements j at the indicator and control stations is shown below for each year l of operation and the period of preoperation. !
Indicator Stations '
Control Station l Period Averaae Fraction Averaae Fraction i 1994 20.7 0.083 57.4 0.833 l 1993 46.4 0.333 34.1 0.083 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 -
I 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' O.193 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.
i To enhance the statistical base for the indicator stations, samples were also collected on a trial basis during the year from a grass plot adjacent to Gate 1 at 1.2 miles in-the SW sector.
Positive results ranging from 30.4 to 48.6 pCi/kg wet were found in 4 of the 12 samples collected; the average positive result was 38.0 pCi/kg wet. Another trial grass plot located at.1.0 miles in the E sector, just north of Plant Wilson was started in December: -i a positive result was not found in the one sample collected. !
l 4-10 ,
l g---- --
o z j
g l
TABLE 2-2 (SHEET 1 0F.3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS l Station Direction Distance Sample Station Descriptive-Tvoe (3)
- Number Tvoe (1) -Location '(2) (miles) (2) 1 I Hancock Landing Road N 1.1 0
- 2. I River Bank NNE 0.8 D
[ Discharge Area NE 0.6 A 3 I 3 I River Bank NE 0.7 D 4 I River Bank ENE 0.8 0 5 1 River Bank E 1.0 D 6 I Plant Wilson ESE 1.1 0 7 I Simulator Building SE 1.7 ADV 8 I River Road SSE 1.1 0 9 I River Road S 1.1 0 10 1 Meteorological-Tower SSW 0.9 A 10 I River Road SSW 1.1 D 11 I River Road SW 1.2 D 12 I River Road WSW 1.2 AD 13 I River Road W 1.3 0 14 I River Road WNW 1.8 D.
15 I Hancock Landing Road NW 1.5 DV 16 I Hancock Landing Road NNW 1.4 AD 17 0 Savannah River Site (SRS). River Road N 5.4 0 18 0 SRS. D Area NNE 5.0 D 19 0 SRS. Road A.13 NE 4.6 0 20 0 SRS, Road A.13.1 ENE 4.8 D 21 0 SRS. Road A.17 E 5.3 0 22 0 River Bank ESE 5.2 0 23 0 River Road SE 4.6 0 24 0 Chance Road SSE 4.9 0 25 0 Chance Road near Highway 23 5 5.2 0 26 0 Highway 23 and Ebenezer Church Road SSW 4.6 0 27 0 Highway 27 opposite Boll Weevil Road SW 4.7 0 28 0 Thomas Road WSW 5.0 D 29 0 Claxton-Lively Road W 5.1 D 30 0 Nathaniel Howard Road WNW 5.0 D 31 0 River Road at Allen's Chapel Fork NW' 5.0 0 32 0 River Bank NNW 4.7 D 33 0 Hunting Cabin SE 3.3 D 35 0 Girard SSE 6.6 AD 2-7 l
4
]
v F'
TABLE 2 2 (SHEET 2 0F 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive. Direction- Distance - Sample:
Number Tvoe (1) location (2) (miles) (2) Tvoe'(3) n o 36 C GPC Waynesboro Op H0 WSW 13.9 AD 37 C Waynesboro Substation WSW 16.7 DV 43 0 Employee's. Rec Area SW 2.2 0 47 C Oak Grove Church SE 10.4 0 48 C McBean Cemetery NW 10.2 D 80 C Augusta Water Treatment Plant NNW 29.0 W(4) 81 C Savannah River N 2.5 F(5)S(6) 82 C Sav River (RM 151.2) NNE 0.8 R 83 I Sav River (RM 150.4) ENE 0.8 RS(6) 84 0 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.
Beaufort. SC SE 74 W(7) 88 I Cherokee Hill Water Treatment Plant.
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 TABLE NOTATIONS (1) Station Types C - Control I - Indicator 0 - Other (2) Direction and distance are reckoned from a point midway between the two reactors.
(3) Sample Types A - Airborne Radioactivity 0 - Direct Radiation F - Fish M - Milk R - River Water S - River Shoreline Sediment W - Drinking Water V - Vegetation 2-8
,1 l
i TABLE 2-2 (SHEET 3 0F 3) r L RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS ;
i 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, effectively parallels the river. . :
-The intake to the pumping station is about-4 miles down the canal and 7 only a tenth of a mile from the river (across land). j
'I
.(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 .l collections. ,
(6) Sediment is collected at locations with existing or potential recreational value. Because high water, shifting of the river 'l bottom. or.other reasons could cause a suitable location for sediment l collections to 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 downriver 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 intake is about 16 miles by line of sight down the ' canal j from its beginning on the Savannah River. J i
(8) The intake for the Cherokee Mill Water Treatment Plant is located on !
Abercorn Creek which is about one and a quarter creek miles from its i mouth on the Savannah River at RM 29. t r
}
a f
i f
i t
2-9 i
1 f
(
O
@.N !.!.0 i.
Y pm 1 .,- ~. -7. .
~~~.
,Jli 9 r) ---
y . . - . . .
'y
" 2 V,J.. .,O // I .
s s g;
~ 'g : .
c -
i i
? .*. \~Wa,_ >
i.
. p V#', N q. ,'! 1 Je;:
- - =
- . . . .s ,i.r- '/ . f. .
/
ag Il m
es a .
,!l'
, ..$1;.
, .r--- ... . .
i ggt i
, f. . t s 3 v.w . !
f
- i. 'y i rx
. ..g%
/. W
. . * ?- ~_ . .u ,
\ .
.* a .. -
. O .
j o
- . s
.1' -
, i, > @' , : '
- @ ' / %g,. ,
u ;
g--- .@ ...- . _ /- ,
C\ , ,'
s' .
,f. , w.
[i It
'] ,
) ., i t .) . .
~, .
s e
FIGURE 2-1 TERRESTRIAL STATIONS NEAR SITE BOUNDARY 2-10 t
n
' e .e I
i
- l
- \
e
o,..
- l l
. ~ % ' '-
l
.,, u. ,
0 1 4
[ ,. * * ** * = g h ^
l 1 i J' ,/ h WILES 1\\
1 y 's -l . /
/ i r 5' .95 31 -
ff e.:.
rjk= n, a
- @ g, ,
h~ -
V, - ,
~
- r. & -,
g g';,
.s, ' '
a 83 g3 4 4N U,, A m's g; '
\ '- % <
? *s-s
... u ' ,,..as a
/
x B4 s
- I k,
@ $, !}
4 g. '< #,
x- ., ..
..- g @'. .:< .', ',
@,n;
- r. ,/ .. @- p -
'sr , ,
pg ,.
w@ .
. . .a ,- ;.:
.-y;,
. . - ~
3 SS I -> - -
$' \ l a E. ,. /*
) .' i '
~l' r
. % s in . 91^ .
- t. *, D,4 .[r, ,
2g
, , . ^ "4*M -
- r, r * ,..o. x ,,, ,
a p r.-
(as ' Cn & A D
. #,y, #
~ 1. $< '*** :* %* I"'M . .'.m . , eW. .r '
F.GURE 2-2 TERRESTRIAL AND AQUATIC STATIONS WITHIN SIX MILES 2-11
, +,
l\
g
/ ,
g _
y D .
N R A
V4 R
t s ,
4 G '
- s S e
lb I
D R
- A s
' S A =
o 3 f.
/ '
'T E t 2
NL AT t G
\
s a
V 0
~
N N
f, .
l R
E D
N
. A
. X O 'E R L a O A
, m B u
- 1 S w
"}
~
E E
e {
s ' E ,
u
~
~
( %. A
}sc w le Wa h ')
f#
c l'
~
3 aAm .
,f~
\
- W -
t .
- /
s.
u n
1 o
s ga -
~
i# ~e aF $ * %G m-o~
~
aucusta nat:R TRaavutNT PLANT a
l h' .
,,y,,,,
river PL ANT VEGP(
.' l )
I const i. supiny ni ,
Water to Seewiort j
l' Wert4 asper County Weser Trussesseret Plant i
\
I Au, b GEORGI A
,,.s 8 ' ' 87\
... 1 km b
\
N 4 0 10 20 30 g 4 CMEROK EE HILL , p $
WATE R TRE ATWENT h PLANT h (PORT WENYWORTM) h SAVANNA T O FIGURE 2-4 DRINKING WATER STATIONS
. 2-13
1 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 I
reportable occurrences were called for during the year. the column L entitled " Number of Reportable Occurrences
- has been excluded fram Table 3-1. Results'for samples collected at locetions other than indicator or control stations or_in addition to those stipulated by Table 21 are discuesed in Section 4.for the particular sample type.
Only the naturally occurring radionuclides which are found in the plant's effluent releaser 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 of interest-
! for the samples monitoring liquid releases (river water, drinking water, fish and river shoreline sediment) are man made radionuclides plus Be-7, while only man-made radionuclides are of interest for the other REMP samples.
3-1
TABLE 3-1 (SHEET 1 0F 11)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
FOR 1994 -
Vogtle Electric Generating Plar.t. Docket Nos. 50-424 and 50-425 Burke County. Geor gia j
Indicator Location with Highest Control Type and Minimum Locations Annual Mean Locations Medium or. Mean (b) Mean (b)
Pathway Sampled Total Number Detectable Mean (b) Name of Analyses Concentration Range Distance & Range Range (Unit of (Fraction) (Fraction) l Measurement) Performed (MDC) (a) (Fraction) Direction Gross Beta 10 20.1 No. 3 20.6 20.3 Airborne 10-35 Particulates 312 8-36 Discharge 10-32 (fCi/m3) (260/260) 0.6 miles (52/52) (52/52)
NE w
4 Gamma Isotopic 24 50 NDM (c) NDM NDM Cs-134 Cs-137 60 NDM NDM NDM NDM NDP Airborne I-131 70 NDM Radiciodine 312 (fCi/m3)
Gamma Dose NA (d) 12.3 No. I 14.9 12.1 Direct Radiation 80 10-16 Han tan Rd 13-16 10-15 (mR/91 days) (64/64) 1.1 miles (4/4) (16/16)
N
~
ff During operation, Cs-137 has been the only man-made radionuclide ;
detected in vegetation samples. During preoperation as a '
consequence of the Chernobyl incident 1-131 was found in nearly all the samples collected (some at elevated levels) for a period of several weeks. During this period Cs-137 was also found in nearly all the samples collected, and Co-60 was found in one of the samples. !
i l
[
l 1
1 I
i 4-11 I
E o-4.5 . River Water _
Surface water was composited'from.the Savannah River at three [
locations using 1500 automatic samplers. ~Small-quantities were ,
collected at intervals not exceeding a few hours. River water samples collected by these machines were picked up monthly; quarterly composites were made from the monthly collections. .
The collection points consist of a control station (No. 82) which l is located about 0.4 miles upriverlof the plant intake structure'.~. t an indicator station (ho. 83) which is located about 0.4 miles .,!
downriver of the plant discharge structure. 'and a special station (No. 84) which is located approximately 1.3 miles downriver of the- t plant discharge structure. The increase in the radiological levels found in samples collected at the indicator station over those collected at the control station might be' attributed to the ,
plant radiological releases. The radiological levels found at the special station perhaps represent those for the river as a whole: [
the levels here might be attributed to plant releases as well as l to other sources.
A gamma isotopic analysis was conducted on each monthly j collection. As in' all previous years of operation, .there were no i radionuclides of interest detected in the river water samples .i collected during 1994 j A tritium analysis was performed on each quarterly composite. As i indicated in Table 3-1, the average level of 1258 pCi/l found at 3 the indicator station was 1001 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 2009'pci/1. At the ;
special' station, the results ranged from 406 to 971 pCi/l with an i average of 774 pCi/1. 'The MDC for tritium in river water is 3000 i pCi/1; the RL is 10 times greater. ;
i 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 l stations, and the total liquid releases of tritium from the plant. !
All of these values are in units of pCi/l except for the releases -
which are in units of Ci. !
l l
i t
l 4-12 :
i
s 9,y l i
l Ig.g. Soecial Indicator Control increase fiDR Releases 1994 774 1258 257 1001 2009 1052-1993' 616- 712 238 474 1526 761' I 1992 929 1064 371 693 714 1481 '
-1991 1298 1299 828 471 626 1094 1990- 1081 1142 392 750 766 1172 ,
918 a 1989 1268 1293 538 755- 518 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. Although the releases are sufficient to account for the.
increases in the levels at the indicator station over i those at the control station (except perhaps for the first.
two years of operation), there is not a good correlation '
between the releases and the increases.
- 2. The overall tritium level in the river has diminished as indicated by the lower levels at the special and control -[
stations over the past few years. ]
- 3. In the early years of operation, the tritium level at the special station was somewhat greater than that at the ;
indicator station; whereas in recent years, it has become-somewhat less. This indicates the contribution from other j tritium sources has diminished while plant releases have .!
become relatively more important.
j
- 4. There has been a discernible difference between the indicator and control stations only during 1988 and 1989. .!
This may be explained by the higher MDD values which l result from greater variability found in the quarterly >
tritium levels.
The annual whole body dose that the maximum individual (a child) i would receive from drinking water with an average tritium 'l concentration of 1001 pCi/l (the assumed plant contribution) was !
conservatively calculated to be 0.104. mrem or 3.5 percent of the 3 - ,
mrem limit for releases from one unit as stipulated by ODCM 2.1.3.
The annual downriver survey of the Savannah River to determine if I river water is being used for purposes of drinking or irrigation is discussed in Section 4.0. l l
P 4-13 -l 1
f
t i
4.6 Orinking Water i
Samples were 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 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 were made of river water which was composited near the intake of the' water treatment plant (raw drinking water) and of grab samples of '
finished drinking water: quarterly composites were made from the monthly collections. Gross beta and gamma isotopic analyses were conducted on each of the samples collected monthly. Tritium analysis was conducted on the quarterly composites. Although an 1 131 analysis was not required to be conducted on these' samples as the dose calculateo from the consumption of water is less than !
I mrem per year.(see ODCM Table 4-1), an 1-131 analysis was 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 i levels in units of pC1/1 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. (
Period Indicator Control Increase HDD ,
RAW ,
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 .e 1990 2.53 2.55 -0.02 0.72 3.05 0.12 0.85 i 1989 2.93 1988 2.67 3.04 -0.37 1.36 -
1987 2.20 5.50 3.30 4.4 ;
r 4-14 3
-)
I
.__--___.t
. - ~ . .. _ . . -- .,~
_ -. . . . - . . ~
< - y I
i Period Indicator Control increase- Ml FINISHED 1 1
?
1994 2.40 2.~ 68 -0.28 2.40 ;
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.
i 1990 2,08 1.92 0.16 0.58 1989 2.36 2.38 -0.02- 0.57 .j 1988 2.28' 2.35 -0.07 0.88 .;
1987 2.10 1.80 0.30 0.7 l No trend is recognized-from these data, in_1994 as in'all :l previous years of ' operation, there was no discernible difference !
between the average levels at the indicator and control = stations ;
for both raw and finished water since the MDD continued to be i greater than the difference. The MDC for gross beta in water is 4 pCi/1. j{
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 one positive result has been found._ !
since operation began: Be 7 was found at a' level of 68.2 pCi/1 in 'l the sample collected for September 1987 at Station 87. The MDC l assigned for Be-7 in water is 124.pCi/1. j 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 i at the indicator stations-over those at the control station, and q the calculated MDDs between these two station groups. 'The' average j 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 between December 22 and 25, 1991. !
Period Indicator Control Increase M ;
i RAW 1
1994 871 NDM NA NA !
1993 955 NDM NA NA ,
1992 1131 179 952 353 1991 1471 165 1306 834 .
i 1990 1320 266 1054 572 1989 2508 259 2249 1000 1988 2630 240 2390 580 1987 2229 316 1913 793
~
4-15 f
r = --- -
y u ;
Perlod' Indicator Control Increase '@D- 1 R FINISHED !
270 !
1994 880 131 749 1993. 993 NDM NA NA' !
1992 1162 211- 951 427 d 1991 1240 225 1015 647 i 1990 1299 404 895 1131 l 1989 2236 259 1977 627-1988 2900 270 2630 830-2406 305 2101 1007 1987 j The above tabulation shows a steady decline of the tritium levels f in the drinking water samples, both raw and finished since 1988.
No. detectable measurements (NDH) were made in the raw drinking water samples collected at the control ' station during 1994: values for the average increased level at the indicator stations and the l calculated HDD between the indicator and the control stations were. l thus not applicable (NA). There was a detectable difference between the indicator stations and the control station for ;
finished drinking water in 1994 as the increase between the two I station groups exceeded the MDD. Except for the finished drinking g water in 1990, there has been a detectable difference between the j two station groups during each year of operation for both raw'and i finished drinking water (whenever detectable measurements were j made for both station groups).
As indicated in Table 31, there were no positive results from the l I-131 analysis of the finished drinking water samples. Similar -t results were obtained in previous years of operation, The MDC and j RL for I-131 in drinking water are 1 and 2 pCi/1, respectively. j 9
4-16 i
=3 l
4.7 ^ Fish Table 2 1 calls for the collection of at least one. sample of any !
anadromous species of fish in the vicinity nof the plant discharge ~
during the spring spawning season, and for the semiannual :
collections of any commercially or recreationally important '!
L species in the vicinity of the plant discharge area and.in an area .
not influenced by plant discharges. Table 2 also calls for a - 3 gamma isotopic analysis on the edible portions'of each' sample .
collected. ;
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-structure I and the indicator station (No. 85) extends from about 1.4 to 7' miles downriver of the plant discharge structure. For anadromous 1 species, all collection points can be considered as' indicator i stations.
On March 22. American shad, an anadromous species. was collected.
in 1994 as in all but two previous years of operation, no positive i results for the radionuclides of interest were detected from the gamma isotopic analysis, in 1987 as well as in 1991. Cs 137 was !*
found in a single sample of American shad at minuscule-levels of 10 and 12 pCi/kg wet, respectively. J The dates and compositions of the semiannual catches at the l indicator and control stations were as shown below. l; Qalg Indicator- Control April 20 Largemouth Bass Largemouth Bass ,
Channel' Catfish !
November 16 Largemouth Bass Largemouth Ba'ss l As indicated in Table 3-1. Cs 137 was the only radionuclide of interest found in the semiannual collections, it has been found f in all but one of the 70 samples collected during operation. In .
Table 3-1. the average level at the indicator station is seen to ;
be 34.9 pCi/kg wet greater than that at the. control station. This. !
difference was not discernible. however, since it was less than the calculated MD0 of 546 pCi/kg wet.
]
1 i
i 4-17 1
'l i
-1
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.
lgar Indicator Control 1994 165 200 1993 360 84 1992 178 80 1991 105 211 1990 103 249 1989 117 125 1988 66 116 1987 337 119 No trend was recognized in these data. The MDC and RL for Cs-137 in fish are 150 and 2000 pCi/kg wet, respectively.
The only other radionuclide of interest found in fish samples during past years of operation was 1-131. 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.
4-18
I R '1 p:
D 4.8 Sediment l l
Sediment was: collected along the shoreline of the Savannah River _
on April 5 and_0ctober 4'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 islan indicator station located about 0.6 miles downriver of the plant discharge structure. _A gamma isotopic analysis was performed on each sample.
Listed below for each year of operation _are the' average levels in units of pCi/kg dry for. the radionuclides of interest found in the regular samples collected at_the indicator and/or control stations '!
along with the fractions of detectable meas,rements and the MDCs Each of these radionuclides is found in the plant's liquid i releases.
Xgar Indicator Fraction Control Fraction l Be 7 MDC-655 l 1994 1203 1.0 96' 1.0 1993 711 1.0 902 1.0 1992 2038 1.0 380 1.0 1991 826 1.0 427 1.0 1990 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 Mn 54 MDC-42 1994- 32 0.5 1989 18 0.5 1988 22 0.5 Co-58 MDC-43 1994 18 0.5 1992 124 0.5 1990 140 0.5 1989 135 1.0 1988 190 1.0 4-19
1 gar Indicator Fraction Control Fraction Co-60. MDC-70 1994 85 1.0 1993 66 1.0 1992 60 1.0 1991 113 0.5 1990 46 0.5 1989 46 1.0 1988 62 0.5 I-131. MDC-53 1994 51 0.5 1992 194 0.5 51 0.5 Cs 137 MDC=180 1994 240 1.0 118 1.0 1993 345 1.0 115 1.0 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 was recognized in the above data. The levels for 1994 are seen to be on the same order as those found previously. As in all previous years of operation, positive results for Be-7 and Cs-137 were found in each sample. Positive results were also found at the indicator station for each of the otner radionuclides detected during previous years of operation.
For Be-7, the average level at the indicator station is seen to be 239 pCi/kg dry greater than that at the control station; however, this difference is not discernible as it is less than the calculated MDD of 3951 pCi/kg dry. For Cs-137. the average level at the indicator station is 122 pCi/kg dry greater than that at the control station: this difference is less than the MDD of 445 pCi/kg dry and thus is not discernible. There continues to be no discernible difference between the indicator and control stations for both Be-7 and Cs-137 or for any other radionuclide of interest since operation began.
4-20 i
s-I
?
The. continuing presence of'Co-60 and the sometimes presence of Mn- l 54, Co 58 and 1-131-at the indicator. station (although at low _ -;
levels) are_ indicative of plant releases. Emeloying the ~
methodology' and parameters of NRC Regulatory 6uide l.109.. Revision" 'l '
1, October 1977, the annual whole body dose'to an . individual at-the indicator station by direct radiation from sediment with the' -i l
concentrations of these four radionuclides as found in 1994 was estimated to be approximately 2,7 microrem or about.0.09_ percent-
- of the 3 mrem limit for releases from one unit as stipulated by- ;
ODCM 2.1'.3. This extremely low dose..although calculable, poses ~
no measurable environmental or public health impact.
i l
l l
1 i
i i
'I i
i i
l l
l l
-]
1 4-21 i
7, i
k 5.0 INTERLABORATORY COMPARISON PROGRAM
' TS 6.7.4.g(3) requires participation in an interlaboratory ~
comparison program to ensure that independent checks are performed on the precision and accuracy of the measurements of radioactive- ;
materials in environmental sample matrices. As directed by ODCM .
4.1.3, the El performed analyses- on radioactive materials supplied j by the Performance Evaluation Program conducted by-the !
Environmental Protection Agency (EPA) at their Environmental Monitoring Systems Laboratory in:Las Vegas, Nevada. In past '
years, this program was known as the Intercomparison Studies '
(Crosscheck) Program. Reported herein, as required by ODCM
- 4.1.3.3 and 7.1.2.3 is a summary of the results of'the EL's participation in this program. ,
The Performance Evaluation Program was designed for_ laboratories involved with REMPs and includes environmental media and a variety 1 of radionuclides with activities which might be as low as j environmental levels. Simulated environmental samples are ;
distributed regularly to the participants who analyze the samples l and return the results to the EPA for statistical analysis and i comparison with known values and_with results obtained from other l participating laboratories. The EPA then provides each -l participant with documentation of its performance; this can be ,
helpful in identifying any instrument or procedure problems. l, The El analyzed the EPA supplied samples consistent with the ;
requirements of Table 2-1. Analyses were performed in a normal manner. Each sample was analyzed in triplicate as required by the !
program. Results obtained for the gross beta and gamma isotopic analyses of air filters, the gamma isotopic analysis of milk i samples, and the gross beta, tritium, 1 131 and gamma isotopic analyses of water samples are summarized in Table 5-1. )
Delineated in Table 51 for each of the environmental media are the type analyses performed. EPA's collection' dates, the known ,
values and expected precisions (one standard deviation) provided by the EPA, the average results obtained and reported by the EL i 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.
i I
5-1 1
)
.: 9 ; '
~
TABLE 5-1 (SHEET 1 0F 2)
PERFORMANCE EVALUATION PROGRAM RESULTS Expected Reported Standard Normalized Normalized-Radionuclide Date Known or Analysis Collected Value Precision Averace Deviation Deviation- Ranae Air Filters -(pCi/ filter) 56.0 10.0 56.00 1.73 'O.00 0.18 Gross Beta 08/26/94 5.0 18.67 0.58 1.27 0.12-Cs-137 08/26/94 15.0 Milk (pCi/1) 75.0 8.0 71.00 4.36 -0.87 0.59 1-131 09/30/94
{
59.0 5.0 61.00 1.73 0.69 .0.35 09/30/94 Cs-137 Water (pCi/1) 62.0 10.0 63.6/ 3.21- 0.29 0.35 Gross Beta 01/28/94 0.30 04/19/94 117.0 18.0 111.67 4.51 -0.51 10.0 5.0- 20.67 2.89 3.70 0.59 07/22/94 0.98-10/18/94 142.0 21.0 124.33 18.72 -1.46 23.0 5.0 27.00 2.65 1.39 0.59 10/28/94 4936.0 494.0 4710.00 98.49 -0.79 0.23' H-3 03/04/94 0.20 08/05/94- 9951.0 995.0 -9253.33 176.17 -1.21
TABLE 5-1 (SHEET 2 0F 2)
PERFORMANCE EVALUATION PROGRAM RESULTS Radionuclide Date Known Expected Reported Standard Normalized Normali :d or Analysis Collected Value Precision Averace Deviation Deviation Rance Co-60 04/19/94 20.0 5.0 22.67 2.08 0.92 0.47 06/10/94 50.0 5.0 54.33 6.81 1.50 2.02 10/18/94 40.0 5.0 38.33 0.58 -0.58 0.12 4 11/04/94 59.0 5.0 57.00 2.65 -0.69 0.59 I Zn-65 06/10/94 134.0 13.0 141.33 2.31 0.98 0.18 11/04/94 100.0 10.0 107.00 6.24 1.21 0.71 Ru-106 06/10/94 252.0 25.0 240.67 15.63 -0.79 0.73 T
I-131 02/04/94 119.0 12.0 117.33 1.15 -0.24 0.10.
10/07/94 79.0 8.0 78.67 1.15 -0.07 0.15 Cs-134 04/19/94 34.0 5.0 28.33 1.53 -1.96 0.35 06/10/94 40.0 5.0 36.33 0.58 -1.27 0.12 10/18/94 20.0 5.0 17.33 0.58 -0.92 0.12 11/04/94 24.0 5.0 24.00 3.00 0.00 0.71 Cs-137 04/19/94 29.0 5.0 30.33 1.53 0.46 0.35 06/10/94 49.0 5.0 50.33 4.51 0.46 1.12 10/18/94 39.0 5.0 40.67 0.58 0.58 0.12 11/04/94 49.0 5.0 53.33 3.51 1.50 0.83 Ba-133 06/10/94 98.0 10.0 87.33 2.08 -1.85 0.24 11/04/94 73.0 7.0 68.00 1.73 -1.24 0.25
\ .--_-- _____ ___ _- -
l l
The. normalized ' deviation from the known value provides a measure '
" of the central tendency of the1 data (accuracy). The normalized range is a measura of the dispersion of the data (precision). .ia ;
i 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 s
was established as the warning limit. The EL considers any value !
greater than the control limit as unacceptable. Investigations !
are undertaken whenever any value exceeds the warning limit or whenever a plot of the values indicates a trend. ;
t An investigation was undertaken due to the following conditions which may be noted from Table 5-1: ;
The control limit for the , normalized deviation was 1.
exceeded for the gross beta analysis in the water j sample collected on July 22: ,
- 2. The warning limit for the normalized range was exceeded for the gamma isotopic analysis of Co-60 for j the water sample collected on June 10: and l
- 3. The gamma isotopic analysis of Cs 137 in water ;
continues to show a positive bias.
r A visual inspection of the July 22 water sample for gross beta l analysis showed suspended solids. The solids would not dissolve [
in spite of vigorous shaking and stirring. The sample could not l be considered a homogeneous mixture or a saturated' solution. The :
undissolved material rendered inconsistent weights in the i analysis. The other samples did not contain undissolved solids.
The anomalous result is concluded to be sample specific. l The activity values reported to the EPA for Co-60 in water for the- 1 June 10 collection were 49, 52 and 62 pCi/1. The range in the [
analysis results could not be attributed to sample preparation as l each sample is prepared in the same manner. The counting ;
variables such as. detector efficiency or count times, were the !
same when the 49 and 62 pC1/1 results were obtained. The quality control criteria for the instrumentation used to count the samples ,
was within established limits. The internal quality control for !
the sample matrix processed was within acceptance limits. The [
normalized range is seen to barely exceed the warning limits. L Further investigation is deemed to be unwarranted. ;
l 5-4 i
- a. -
L 3
~
The recovery of Cs-137 activity in water samples is trending high.
Eighteen out of.the last. twenty samples (going back to' April 17,-
'1990)~ have had positive normalized deviation values. The current efficiency curves-for the 3 gamma detectors were evaluated from'a mixture of 8 isotopes with a total of 13 energy values:(from 88 to.
1836 key) using a quadratic fit. For each.of-the 3 detectors the.
actual efficiency point at 661 key (the prominent gamma for Cs-137) fell above the calculated efficiency curve by.approximately
- 21. Because all values of the. normalized deviation' have been1 within.the warning limits since the start of 1987 and because the average value of the normalized deviation beginning with the April
-17. 1990 sample is only 0.68, the trend is not considered significant. Further investigation.is :eemed to be unwarranted.
5-5
1 F
6.0 CONCLUSION
S This report confirms the licensee's conformance with TS 6.7.4.g and Chapter of the ODCH during 1994. 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 increase in the level of tritium in river water and the presence of Co-60 and other man-made radionuclides in shoreline sediment at a short distance downriver from the discharge structure is indicative of plant releases. The consequent doses which were shown to be small fractions of the TS limits pose no measurable radiological impact to the environment or the public.
)
1 6-1 u
?
IV GEORGIA POWER COMPANY :
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 ANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT
7 VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOACTIVE EFFLUENT RELEASES SECTION TITLE PAGE i
1.0- Liquid Effluents 8 !
1.1 Regulatory Limits / Technical Specifications 8 l 1.1.1 Concentration Limits 8 l
{
1.1.2 Dose Limits 8 j i
1.2 Effluent Concentration Limit 8 l
- 1.3 Measurements and Approximations of Total 9 ,
Radioactivity i
! -l l 1.4 Liquid Effluent Release Data 11 l
l 1.4.1 Tables 11 j
- 1.4.2 Total Error Measurement 11
.l 4
1.5 Radiological Impact on Man Due to Liquid Release '12 l 1.6 Abnormal Releases 12 !
l !
1.7 River Flow 12- ;
Gaseous Effluents 2.0 34 )
a !
i 2.1 Regulatory Limits / Technical Specifications 34 4 ,
, j
i SECTION TITLE PAGE 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 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 i 2.4.1 Fission and Activation Gas 36 2.4.2 Radiolodines, Tritium and Particulate Releases 37 2.4.3 Gross Alpha Release 37 2.5 Gaseous Effluent Release Data 38 -
2.5.1 Methodology 38 2.5.2 Gaseous Batch Data 40 2.6 Radiologicalimpact Due to Gaseous Releases 40 2.7 Abnormal Releases 40 ,
] <
SECTION TITLE PAGE .
3.0 Solid Waste 81 3.1 Regulatory Limits / Technical Specifications 81 3.1.1 Use of Solid Radioactive Waste System 81 3.1.2 Reporting Requirements 81 3.1.3 Process Control Program (PCP) 81 3.2 Solid Waste Data 82 '
4.0 Changes to the Vogtle Electric Generating Plant 82 ODCM 4.1 Changes in the Radiological Environmental 83 Monitoring Program 1 5.0 Doses to Members of the Public inside The 83 Site Boundary 6.0 Major Changes to the Liquid, Gaseous and 88 I Solid Radwaste Treatment Systems 7.0 Meteorology 88 8.0 Inoperable Liquid or Gaseous Effluent 88 Monitoring Instrumentation 9.0 Tanks Exceeding Curie Content Limits 89 t
l VOGTLE ELECTRIC GENERATING PLANT ANNUAL REPORT PLANT RADIOA CTIVE EFFLUENT RELEASES TABLE LIST OF TABLES PAGE 1-2A Liquid Effluents - Summation of All Releases 13 Unit 1 ,
1-2AA Liquid Effluents - Summation of All Releases 14 Unit 1 ,
1-2B Liquid Effluents - Summation of All Releases 15 Unit 2 12BB Liquid Effluents - Summation of All Releases 16 Unit 2 !
1-2C Liquid Effluents - Summation of All Releases 17 ;
Site 1-2CC Liquid Effluents - Summation of All Releases 18 f Site '
1-3A Liquid Effluents - Unit 1 19 1-3AA Liquid Effluents - Unit 1 20 l i
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
s
y n
f
! l I
TABLE LIST OF TABLES PAGE $
i i
1-4A Individuals Doses Due to Liquid Releases 25 Unit 1 1-4AA - Individuals Doses Due to Liquid Releases 26 Unit 1 ;
1-4B Individuals Doses Due to Liquid Releases 27 Unit 2 l 1-4BB 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 42 Releases - Unit 1 ,
l 2-2AA Airborne Effluents - Summation of All 43 Releases - Unit 1 2-2B Airborne Effluents - Summation of All 44 Releases -Unit 2 i
2 2BB Airborne Effluents - Summation of All 45 Releases -Unit 2 l
l I
m i
TABLE LIST OF TABLES PAGE :
1 2-2C Airborne Effluents - Summation of All 46 Releases - Site 2-2CC Airborne Effluents - Summation of All 47 Releases - Site :
2-3A Gaseous Effluents - Mixed Mode Releases 48- !
Unit 1 ,
2-3AA Gaseous Effluents - Mixed Mode Releases 50 Unit 1 I 2-3B Gaseous Effluents - Mixed Mode Releases 52 ;
Unit 2 I 2-3BB Gaseous Effluents - Mixed Mode Releases 54 ;
Unit 2 2-3C Gaseous Effluents - Mixed Mode Releases 56 Site 2-3CC Gaseous Effluents - Mixed Mode Releases 58 ,
Site
{
2-4A Gaseous Effluents - Ground Level Release 60 Unit 1 3
2-4AA Gaseous Effluents - Ground Level Release 62 !
Unit 1 l
2-4B Gaseous Effluents - Ground Level Release. 64 .
Unit 2 1
2-4BB Gaseous Effluents - Ground Level Release 66 Unit 2 i
2-4C Gaseous Effluents - Ground Level Release 68 l Site i
1 4
TABLE LIST OF TABLES PAGE }
4CC Gaseous Effluents - Ground Level Release 70-Site 2-6A Air Doses Due to Noble Gases - Unit 1 72
2-6AA Air Doses Due to Noble Gases - Unit 1 73 2-6B Air Doses Due to Noble Gases - Unit 2 74 l
2-6BB Air Doses Due to Noble Gases - Unit 2 75 2-7A Individual Doses Due to Radiolodines, 76 Tritium, and Particulates in Gaseous Releases - Unit 1 2-7AA Individual Doses Due to Radiolodines, 77 l Tritium, and Particulates in Gaseous I Releases - Unit 1 '
2-7B Individual Doses Due to Radiolodines, 78 Tritium, and Particulates in Gaseous Releases - Unit 2 -
2-7BB Individual Doses Due to Radiolodines, 79 Tritium, and Particulates'in Gaseous Releases - Unit 2 2-8 Minimum Detectable Concentration - 80 Gaseous Sample Analyses Solid Waste and Irradiatsd Fuel Shipments 3-1 85 r
4-1 Dose to A Member of the Public Due to Activities 87 Inside The Site Boundary.
b i
V
1.0 Liquid Effluents 1.1 Re0ulatory Limits / Technical Specifications I
Concentration Limits 1.1.1 The concentration of radioactive material released in liquid effluents l
to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table ll, Column 2 for l radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1.0E-4 micro cunes/mi total activity. l
, i 1.1.2 Dose Limits )
The dose or dose commitment to a MEMBER OF THE PUBLIC from l radioactive materials in liquid effluents released, from each unit, to i UNRESTRICTED AREAS shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to ;
the whole body and to less than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.
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, i Table ll, Column 2. A tolerance factor up to 10 is selected to allow flexibility in the establishment of a practical monitor set point which j 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.
! i
- Further, for all the above radionuclides or categories of radioactivity, f the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B.
8 J
The method whereby the ECL fraction is used to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.
1.3 Measurements and Approximations of Total Radioactivity Prior to release of any tank containing liquid radwaste, and following the required recirculations, samples are collected and analyzed in accordance with Offset Dose Calculation Manual (ODCM) Table 2-3. A sample from each tank planned for release is analyzed for principal gamma emitters, I-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 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.
- 2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gases with computerized data reduction
- 3. Tritium unnthly 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 scintillation counting
- 6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation )
counting Gamma isotopic measurements are performed in-house in the radiochemistry lab using germanium detectors with resolution of 1.80 kev or lower. The detectors are shielded by four inches of lead. A liquid radwaste sarnple is typically counted for 2000-4000 seconds. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data of all significant peaks are determined, and a quantitative reduction or MDC 9
calculation is performed. The procedure ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative 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 on 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 and 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 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 rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor.
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 not permissible, appropriate warnings will be included on the computer screen. If the release is permissible, it is approved by the Chemistry Foreman on duty 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.
The post release printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual.
10
_ _ J
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,2-C, and 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 i 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 radioactivo materials released in liquid effluents.
1.4.2.1 Fission and activation total release was calculated from sample analysis ,
results and release point flow rates.
l 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.
Tank volumes and system flow rate 20 %
Sampling and statistical errors < 10%
Counting equipment calibration 10%
TOTAL ERROR 40%
1.4.2.3 Dissolved and entrained gases were calculated from sample analysis results and release point volumes.
Tank volumes and system flow rate 20 %
Sampling and statistical error 20%
Counting equipment calibration 10%
TOTAL ERROR 50 %
11 i
0 .
.1.4.2.4 Gross alpha radioactivity was calculated from sample analysis results and i release point volumes.
Tank volumes and system flowrates 20%
Sampling and statistical error 10%
Counting Equipment calibration' 10%
Compositing sample error 5%
TOTAL ERROR 45%
1.4.2.5 Volume of waste prior to dilution was calculated from level indicators on the tanks and pump discharge flow rates and times.
Level Indicator error 10%
Operator Interpretation of gauge 10%
TOTAL ERROR 20 %
1.4.2.6 Volume of dilution water used was calculated from flow rate indicators and pump discharge flow rates and times.
Flow rate indicator error 10%
Operator interpretation of gauge 10%
TOTAL ERROR 20%
1.5 Radiological impact on Man Due to Liquid Releases Doses to an individual due to radioactivity in liquid effluent were calculated in accordance with the Offsite Dose Calculation Manual. Results are ,
i presented in Table 1-4A,1-4AA for Unit 1 and 1-48,1-4BB for Unit 2, for all four quarters.
1.6 Abnormal Releases 1.6.1 There were no abnormal releases for this reporting period.
1.7 River Flow The average flow rate of the Savannah River for the Annual Effluent Report period was obtained from the Clark Hill Dam, Corp of Engineers Office. The average flow rate is 8949 cubic feet /sec.
12
--____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _J
TABLE 1-2 A GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENT RELEASE REPORT - 1994 ALL LIQUID EFFLUENTS UNIT : 1 STARTING : 1-JAN-1994 ENDING ; 30-JUN-1994 TYPE OF EFFLUENT UNITS QUARTER 1 OUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.26E-01 5.62E-02 40 TRITlUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.19E-07 2.41 E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 8. TRITIUM
- 1. ~.'OTAL RELEASE CURIES 1.18E+02 1.77E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.67E-04 7.61E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.22E-03 7.32E-04 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.72E-09 3.15E-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 1.15E+06 7.25E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 7.07E+08 2.32E+08 20
- Applicable limits are expressed in terms of dose. See Table 1-4A of this report 13
- a
TABLE 1-2AA GEORGIA POWER COMPANY -
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL LIQUID EFFLUENTS UNIT : 1 STARTING : 1-JUL-1994 ENDING : 31-DEC-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
.1. TOTAL RELEASE (NOT INCLUDING CURIES 8.16E-02 1.21E-01 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 3.86E-07 1.54E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 8. TRITIUM
- 1. TOTAL RELEASE CURIES 4.62E+01 1.03E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.18E-04 1.31 E-05 DURING PERlOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 9.98E-04 3.14E-04 50-
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 4.71 E-09 3.99E DURING PERIOD i
- 3. PERCENTAGE OF APPLICABLE LIMIT %
' D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 2.82E-06 45 i E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 6.68E+05 1.34E+06 20 F. VOLUME OF DILUTION WATER USED LITRE 2.11 E+08 7.87E+09 20
- Applicable limits are expressed in terms of dose. See Table 1-4AA of this report 14 j l
I
)
I TABLE 1-28 GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JAN-1994 ENDING : 30-JUN-1994 TYPE OF EFFLUENT UNITS OUARTER1 QUARTER 2 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 7.06E-02 7.67E-02 40 ,
TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.20E-07 2.82E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 3.06E+01 8.69E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.19E-05 3.20E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
i C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 3.16E-04 4.50E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 5.36E-10 1.66E-08 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 7.03E+06 7.07E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 5.83E+08 2.71 E+08 20
- Applicable limits are expressed in terms of dose. See Table 1-4B of this report 15
TABLE 1-2BB GEORGIA POWER COMPANY .
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL LIQUID EFFLUENTS UNIT : 2 STARTING : 1-JUL-1994 ENDING : 31-DEC-1994 TYPE OF EFFLUENT UNITS OUARTER3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 8.53E-02 2.56E-02 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION - uCi/ML- 2.21E-07 2.18E-07 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 4.26E+02 6.43E+01 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.10E-03 5.48E-04 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1,13E-02 7.16E-04 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.93E-08 6.10E-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 1.25E+06 3.19E+05 20 F. VOLUME OF DILUTION WATER USED LITRE 3.85E+08 1.17E+08 20
- Applicable limits are expressed in terms of dose. See Table 1-4ABB of this report 16
TABLE 1-2C !
GEORGIA POWER COMPANY I VOGTLE ELECTRIC' GENERATING PLANT r i
' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL LIQUID EFFLUENTS SITE !
STARTING : 1-JAN-1994 ENDING : 30-JUN-1994 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL ERROR % - -- i A. FISSION & ACTIVATION PRODUCTS
.e
. 1. TOTAL RELEASE (NOT INCLUDING CURIES 2.97E-01 1.33E-01 40 .;
TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.28E-07 2.63E-07 !
DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT % !
B. TRITIUM i
- 1. TOTAL RELEASE CURIES 1.49E+02 2.64E+02 40 i
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.14E-04 5.23E-04 DURING PERIOD [
i
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES l
- 1. TOTAL RELEASE CURIES 1.54E-03 5.23E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 1.18E-09 1.04E-08 !
DURING PERIOD 1
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY ,
- 1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 l E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 8.18E+06 1.43E+06 20 1 F. VOLUME OF DILUTION WATER USED LITRE 1.29E+09 5.03E+08 20 i
- Applicable limits are expressed in terms of dose. See Tables 1-4A and 1-4B of this report i
17
]
TABLE 1-2CC GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL LIQUID EFFLUENTS SITE STARTING : 1-JUL-1994 ENDING : 31-DEC-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING CURIES 1.67E-01 1.47E-01 40 TRITIUM, GASES, ALPHA)
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.79E-07 1.84E-08 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. TRITIUM
- 1. TOTAL RELEASE CURIES 4.72E+02 1.67E+02 40
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 7.90E-04 2.09E-05 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CURIES 1.23E-02 1.03E-03 50
- 2. AVERAGE DILUTED CONCENTRATION uCi/ML 2.06E-08 1.29E-10 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CURIES 0.00E+00 2.82E-06 45 E. WASTE VOL RELEASED (PRE-DILUTION) LITRE 1.92E+06 1.66E+06 20 F. VOLUME OF DILUTION WATER USED LITRE 5.96E+08 7.99E+09 20
- Applicable limits are expressed in terms of dose. See Tables 1-4A,1-4B ,1-4AA and 1-4BB of this report 18
i TABLE 1-3A ' .
Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994, j Liquid Effluents i
. Starting : 1-Jan-1994 ' Ending : 30-Jun-1994 .,
UNIT: 1 ;
i CONTINUOUS - . BATCH l NUCLlDE UNIT . QUARTER 1 QUARTER 2 OUARTER1 OUARTER2 H-3 CURIES 0.00E+00 0.00E+00 1.18E+02 1.77E+02 -l FISSION & ACTIVATION PRODUCT i Ag-110m CURIES 0.00E+00 0.00E+00 7.64E-04 1.85E-05 j Co-57 CURIES 0.00E+00 0.00E+00 3.77E-04 6.81 E-05 t Co-58 CURIES 0.00E+00 0.00E+00 2.35E-02 4.81 E-03 l' Co-60 CURIES 0.00E+00- 0.00E+00 1.97E-02 8.95E-03 Cr-51 CURIES 0.00E+00 0.00E+00 2.01E-03 _4.24E-05 .
Cs-134 CURIES 0.00E+00 0.00E+00 3.56E-03 1.05E-04 Cs-137 CURIES 0.00E+00 0.00E+00 5.07E-03 ' 1.33E-04 i Fe-55 CURIES 0.00E+00 0.00E+00 7.72E-02 3.00E-02 Fe-59 CURIES 0.00E+00 0.00E+00 4.64E-05 .0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 7.42E-04 1.29E-05 l-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 CURIES 0.00E+00 0.00E+00 5.71E-03 1.75E-03 ;
Nb-95 CURIES 0.00E+00 0.00E+00 1.24E-03 4.41 E-04 Nb-97 CURIES 0.00E+00 0.00E+00 1.54E-04 3.70E-05 1 Sb-124 CURIES 0.00E+00 0.00E+00 6.89E-04 0.00E+00 Sb-125 CURIES 0.00E+00 0.00E+00 8.41E-02 9.72E-03 i Sn-113 CURIES 0.00E+00 0.00E+00 0.00E+00 2.08E-05 !
Sr-89 CURIES 0.00E+00 0.00E+00 - 0.00E+00 3.25E-05 i Sr-90 CURIES 0.00E+00 0.00E+00 . 8.95E-07 1.14E-06 l Sb-122 CURIES 0.00E+00 0.00E+00 7.63E-06 .0.00E+00 1 Te-132 CURIES 0.00E+00 0.00E+00 1.10E-04 0.00E+00 !
- l. Zn-65 CURIES 0.00E+00 0.00E+00 5.98E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 4.44E-04 1.03E-04 !
Zr-97 CURIES 0.00E+00 0.00E+00 2.23E-06 0.00E+00 i Na-24 CURIES 0.00E+00 0.00E+00 5.42E-06 0.00E+00 !
Te-129m CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l TOTALS 0.00E+00 0.00E+00 2.26E-01 5.62E-02 i
DISSOLVED AND ENTRAINED GASES l Xe-133 CURIES 0.00E+00 0.00E+00 1.22E-03 7.32E-04 I Xe-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I TOTALS 0.00E+00 0.00E+00 1.22E-03 7.32E-04 G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 19
^'
i
f TABLE 1-3AA Vogtle Electric Generating Plant -
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 Liquid Effluents Starting : 1-Jul-1994 Ending : 31-Dec-1994 UNIT : 1 CONTINUOUS - BATCH NUCLIDE UNIT QUARTER 3 OUARTER4 OUARTER3 OUARTER4 H-3 CURIES 0.00E+00 0.00E+00 4.62E+01 1.03E+02 i
FISSION & ACTIVATION PRODUCT -
Co-57 CURIES 0.00E+00 0.00E+00 3.15E-05 1.57E-05 Co-58 CURIES 0.00E+00 0.00E+00 4.77E-03 9.42E-03
- Co-60 CURIES 0.00E+00 0.00E+00 6.19E-03 4.21E-03 Cr-51 CURIES 0.00E+00 0.00E+00 7.51E-04 1.12E-02 Cs-134 CURIES 0.00E+00 0.00E+00 ~ 2.01 E-03 2.08E-03 Cs-137 CURIES 0.00E+00 0.00E+00 2.09E-03 2.16E-03 Fe-55 CURIES 0.00E+00 0.00E+00 4.34E-02 7.25E-02 Fe-59 CURIES 0.00E+00 0.00E+00 3.93E-05 4.51 E-04 1-131 CURIES 0.00E+00 0.00E+00 6.71 E-04 1.88E-05 l-133 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ' .
Mn-54 CURIES 0.00E+00 0.00E+00 1.10E-03 1.72E-03 Nb-95 CURIES 0.00E+00 0.00E+00 1.35E-04 1.32E-03 Nb-97 CURIES 0.00E+00 0.00E+00 2.99E-05 0.00E+00 .
Sb-124 CURIES 0.00E+00 0.00E+00 7.68E-04 6.56E-04 3 Sb-125 CURIES 0.00E+00- 0.00E+00 1.86E-02 1.30E-02 Sr-89 CURIES 0.00E+00 0.00E+00 9.19E-06 4.77E-06 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .
Sb122 CURIES 0.00E+00 0.00E+00 9.04E-06 1.23E-04 -
Te-132 CURIES 0.00E+00 0.00E+00 9.21 E-06 1.52E-05 Zn-65 CURIES 0.00E+00 0.00E+00 1.99E-04 0.00E+00 Zr-95 CURIES 0.00E+00 0.00E+00 2.69E-05 7.32E-04 Ag-110m CURIES 0.00E+00 0.00E+00 6.54E-05 0.00E+00 Na-24 CURIES 0.00E+00 0.00E+00 1.31 E-05 0.00E+00 l La-140 CURIES 0.00E+00 0.00E+00 5.11 E-05 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce-143 CURIES 0.00E+00 0.00E+00 0.00E+00 1.37E-05 ,
Te-125m CURIES 0.00E+00 0.00E+00 5.16E-04 1.67E-03 i TOTALS 0.00E+00 0.00E+00 8.15E-02 1.21 E-01 DISSOLVED AND ENTRAINED GASES Ar-41 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe-133 CURIES 0.00E+00 0.00E+00 9.95E-04 3.14E-04 I Xe-135 CURIES 0.00E+00 0.00E+00 - 2.72E-06 0.00E+00 1 TOTALS 0.00E+00 0.00E+00 9.98E-04 3.14E-04 i
~I G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 2.82E-06 l
)
20 '
m
. TABLE 1-38 ,
, Vogtle Electric Generating Plant -
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 Liquid Effluents '
Starting : 1-Jan-1994 ' Ending : 30-Jun-1994 UNIT: 2 CONTINUOUS B!, iCH !
NUCLIDE UNIT QUARTER 1 QUARTER 2 OUARTER1 QUARTER 2 H-3 CURIES 3.67E-01 0.00E+00 3.03E+01 8.69E+01
'i FISSION & ACTIVATION PRODUCT Ag-110rn CURIES 0.00E+00 0.00E+00 1.82E-04 0.00E+00 t Co-57 CURIES 0.00E+00 0.00E+00 4.96E-05 8.84E-05 Co-58 CURIES 1.06E-03 0.00E+00 3.11 E-03 6.71E-03 Co-60 CURIES 2.80E-03 0.00E+00 5.05E-03 1.48E-02 ,
Cr-51 CURIES 0.00E+00 0.00E+00 4.03E-04 1.70E-04 Cs-134 CURIES 0.00E+00 0.00E+00 3.16E-04 2.03E-05 Cs-137 CURIES 0.00E+00 0.00E+00 4.57E-04 8.02E-05 '
Fe-55 CURIES 3.19E-03 0.00E+00 2.70E-02 4.85E-02 Fe-59 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 -
l-131 CURIES 0.00E+00 0.00E+00 1.16E-04 4.81E-06 ,
1-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 CURIES 1.17E-03 0.00E+00 9.02E-04 2.70E-03 Nb-95 CURIES 0.00E+00 0.00E+00 2.50E-04 8.20E-04 !
Nb-97 CURIES 0.00E+00 0.00E+00 1.22E-05 3.42E-05 Sb-124 CURIES 0.00E+00 0.00E+00 3.10E-04 0.00E+00 Sb-125 CURIES 0.00E+00 0.00E+00 2.41E-02 2.35E-03 i Sn-113 CURIES 0.00E+00 0.00E+00 4.64E-06 1.02E -)
St-89 CURIES 0.00E+00 0.00E+00 0.00E+00 1.62E-05 i Sr-90 CURIES 2.47E-05 0.00E+00 100E+00 5.05E-07 !
Sb-122 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 0.00E+00 Zn-65 CURIES 0.00E+00 0.00E+00 1.80E-05 1.49E-04 Zr-95 CURIES 0.00E+00 0.00E+00 1.01 E-04 2.72E-04 ;
Zr-97 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Na-24 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t Te-129m CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - l TOTALS 8.24E-03 0.00E+00 6.24E-02 7.67E-02 .
t DISSOLVED AND ENTRAINED GASES l Xe-133 CURIES 0.00E+00 0.00E+00 3.16E-04 4.48E-03 f Xe-135 CURIES 0.00E+00 0.00E+00 0.00E+00 2.18E-05 !
TOTALS 0.00E+00 0.00E+00 3.16E-04 4.50E-03 i
G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 21 ,
J
_j
TABLE 1-3BB !
. Vogtle Electric Generating Plant :
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 Liquid Effluents Starting : 1-Jul-1994 Ending : 31-Dec-1994 -
UNIT: 2 CONTINUOUS- BATCH
- NUCLIDE UNIT QUARTER 3 OUARTER 4 OUARTER3 OUARTER 4 .
H-3 CURIES 0.00E+00 0.00E+00 4.26E+02 ~ 6.43E+01 I FISSION & ACTIVATION PRODUCT Co-57 CURIES 0.00E+00 0.00E+00 9.80E-05 4.05E l Co-58 CURIES 0.00E+00 0.00E+00 7.61 E-03 1.36E-03 Co-60 CURIES 0.00E+00 0.00E+00 1.54E-02 2.29E ;
Cr-51 CURIES 0.00E+00 0.00E+00 1.54E-03 8.51 E-04 Cs-134 - CURIES 0.00E+00 0.00E+00 8.15E-04 2.04E-04 +
Cs-137 CURIES 0.00E+00 0.00E+00 8.36E-04 2.14E-04 Fe-55 CURIES 0.00E+00- 0.00E+00 4.61E-02 1.64E-02 zi Fe-59 CURIES 0.00E+00 0.00E+00 - 3.91E-05 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 6.65E-04 0.00E+00 1-133 CURIES 0.00E+00 0.00E+00 2.88E-06 0.00E+00 1!
Mn-54 CURIES 0.00E+00 0.00E+00 3.27E-03 5.63E-04 I
Nb-95 CURIES 0.00E+00 0.00E+00 5.70E-04 2.81 E-04 Nb-97 CURIES 0.00E+00 0.00E+00 5.38E-05 0.00E+00 ,
Sb-124 CURIES 0.00E+00 0.00E+00 2.81E-04 1.29E 1 Sb-125 CURIES 0.00E+00 0.00E+00 7.48E-03 3.11E-03 l Sr-89 CURIES 0.00E+00 0.00E+00 5.58E-05 7.03E-05 Sr-90 CURIES 0.00E+00 0.00E+00 6.12E-06 9.84E-07 [
Sb-122 CURIES 0.00E+00 0.00E+00 ' 2.32E-06 0.00E+00 t 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 a' Zr-95 CURIES 0.00E+00 0.00E+00 2.33E-04 1.03E Ag-110m CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Na-24 CURIES 0.00E+00 0.00E+00 2.12E-06 0.00E+00 !
La-140 CURIES 0.00E+00 0.00E+00 1.76E-04 0.00E+00 j Ce-141 CURIES 0.00E+00 0.00E+00 8.16E-06 0.00E+00 Ce-143 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te-125m CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ;
TOTALS 0.00E+00 0.00E+00 8.52E-02 2.56E-02 l
E Ar-41 CURIES 0.00E+00 0.00E+00 4.62E-06 0.00E+00 i Xe-133 CURIES 0.00E+00 0.00E+00 1.13E-02 7.16E-04 Xe-135 CURIES 0.00E+00 0.00E+00 7.06E-06 0.00E+00 TOTALS 100E+00 0.00E+00 1.13E-02 7.16E-04 4
G-ALPHA CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 22
TABLE 1-3C ~
Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 Liquid Effluents Starting : 1-Jan-1994 Ending : 30-Jun-1994 SITE -
CONTINUOUS BATCH NUCLlD UNIT QUARTER 1 QUARTER 2 OUARTER 1 QUARTER 2 H-3. CURIES 3.67E-01 0.00E+00 1.48E+02 2.64E+02 FISSION & ACTIVATION PRODUCT Ag-110m CURIES 0.00E+00 0.00E+00 9.46E-04 1.85E-05 Co-57 CURIES 0.00E+00 0.00E+00 4.27E-04 1.57E-04 Co-58 CURIES 1.06E-03 0.00E+00 2.66E-02 1.15E-02 Co-60 CURIES 2.80E-03 0.00E+00 2.48E-02 2.38E-02 Cr-51 CURIES 0.00E+00 0.00E+00 2.41E-03 2.12E-04 Cs-134 CURIES 0.00E+00 0.00E+00 3.88E-03 1.25E-04 Cs-137 CURIES 0.00E+00 0.00E+00 5.53E-03 2.13E-04 Fe-55 CURIES 3.19E-03 0.00E+00 1.04E-01 7.85E-02 Fe-59 CURIES 0.00E+00 0.00E+00 - 4.64E-05 0.00E+00 1-131 CURIES 0.00E+00 0.00E+00 8.58E-04 1.77E-05 l-132 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mn-54 CURIES 1.17E-03 0.00E+00 6.61E-03 4.45E-03 Nb CURIES 0.00E+00 0.00E+00 1.49E-03 1.26E-03 Nb-97 CURIES 0.00E+00 0.00E+00 1.66E-04 7.12E-05 Sb-124 CURIES 0.00E+00 0.00E+00 9.99E-04 0.00E+00 Sb-125 CURIES 0.00E+00 0.00E+00 1.08E-01 1.21 E-02 Sn-113 CURIES 0.00E+00 0.00E+00 . 4.64E-06 3.10E-05 Sr-89 CURIES 0.00E+00 . 0.00E+00 0.00E+00 4.87E-05 Sr-90 CURIES 2.47E-05 0.00E+00 8.95E-07 1.65E-06 Sb-122 CURIES 0.00E+00 0.00E+00 7.63E-06 0.00E+00 Te-132 CURIES 0.00E+00 0.00E+00 1.10E-04 0.00E+00 l Zn-65 CURIES 0.00E+00 0.00E+00 6.16E-04 1.49E-04 Zr-95 CURIES 0.00E+00 0.00E+00 5.45E-04 3.75E-04 Zr-97 CURIES 0.00E+00 0.00E+00 2.23E-06 0.00E+00 Na-24 CURIES 0.00E+00 0.00E+00 5.42E-06 0.00E+00 Te-129m CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTALS 8.24E-03 0.00E+00 2.88E-01 1.33E-01 DISSOLVED AND ENTRAINED GASES Xe-133 CURIES 0.00E+00 0.00E+00 1.54E-03 5.21 E-03 Xe-135 CURIES 0.00E+00 0.00E+00 0.00E+00 2.18E-05 TOTALS 0.00E+00 0.00E+00 1.54E-03 5.23E-03 G-ALPH CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 23
y ,
.I l
TABLE 1-3CC ,
Vogtle Electric Generating Plant j*
, ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 l .
Liquid Effluents ;
Starting : 1-Jul-1994 ' Ending : 31-Dec-1994 i SITE
- CONTINUOUS BATCH. I NUCLID UNIT QUARTER 3 OUARTER 4 OUARTER 3 OUARTER 4 l 7
H-3" CURIES 0.00E+00 0.00E+00 4.72E+02 1.67E+02 ;
i FISSION & ACTIVATION PRODUCT
~
Co-57 CURIES 'O.00E+00 ' O.00E+00 - 1.30E-04 - 1.98E-05 i
Co-58 CURIES - 0.00E+00 0.00E+00 1.24E-02 1.08E-02 j Co-60 CURIES 0.00E+00 0.00E+00 2.16E-02 6.50E-03 j Cr-51 CURIES 0.00E+00 0.00E+00 . 2.29E-03 1.21E-02 Cs-134 CURIES 0.00E+00 0.00E+00 2.83E-03 2.28E ;
Cs-137 CURIES - 0.00E+00 0.00E+00 2.93E 2.37E-03 Fe-55 CURIES 0.00E+00 0.00E+00 8.95E-02 - 8.89E-02 Fe-59 CURIES 0.00E+00 0.00E+00 7.84E-05 4.51E ]
l-131 CURIES 0.00E+00 0.00E+00 1.34E-03 1.88E-05 1 1-133 CURIES 0.00E+00 0.00E+00 2.88E-06 0.00E+00. j Mn-54 CURIES 0.00E+00 0.00E+00 4.37E-03 2.28E-03 ,
Nb-95 CURIES 0.00E+00- 0.00E+00 7.05E-04 1.60E-03 j Nb CURIES .0.00E+00- 0.00E+00 8.37E-05 0.00E+00 :
Sb-124 CURIES 0.00E+00- 0.00E+00 1.05E-03 7.85E-04 3 Sb-125 CURIES 0.00E+00 0.00E+00 . 2.61E-02 1.61E-02 i Sr-89 CURIES 0.00E+00 0.00E+00 6.50E-05 7.51E-05 Sr-90 CURIES 0.00E+00 0.00E+00 6.12E-06 9.84E-07 i Sb-122 CURIES 0.00E+00 0.00E+00 1.14E-05 1.23E-04 .!
Te-132 CURIES 0.00E+00 . 0.00E+00 9.21E-06 1.52E !
Zn-65 CURIES 0.00E+00 0.00E+00 1.99E-04 0.00E+00 ,
Zr-95 CURIES 0.00E+00 0.00E+00 2.60E-04 8.35E-04 Ag-110m CURIES Na-24 CURIES 0.00E+00 0.00E+00 0.00E+00
- 0.00E+00 6.54E-05
.1.52E-05 0.00E+00 '
0.00E+00
] ;
La-140 CURIES 0.00E+00 0.00E+00 2.27E-04 0.00E+00 Ce-141 CURIES 0.00E+00 0.00E+00 8.16E 0.00E+00 Ce-143 CURIES 0.00E+00 0.00E+00 0.00E+00 1.37E-05 .i Te-125m CURIES 0.00E+00 0.00E+00 5.16E-04 1.67E-03.
TOTALS 0.00E+00 0.00E+00 - 1.67E-01 1.47E-01 Ar-41 CURIES 0.00E+00 0.00E+00 ' 4.62E-06 0.00E+00 '
Xe-133 CURIES 0.00E+00 0.00E+00 1.23E-02 1.03E-03 Xe-135 CURIES 0.00E+00 0.00E+00 9.78E-06 0.00E+00 TOTALS 000E+QQ 0.00E+00 1.23E-02 1.03E-03 G-ALPH CURIES 0.00E+00 0.00E+00 0.00E+00 2.82E-06 24
)
TABLE 1-4A VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES JANUARY,1994 THROUGH JUNE,1994 i Y UNIT 1 l
~ CUMULATIVE DOSE PER QUARTER ORGAN ODCM ' UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 5.0 mrem 2.87E-02 5.75E-01 2.48E-03 4.95E-02 Liver 5.0 mrem 4.94E-02 9.89E-01 7.71 E-03 1.54E-01 T. Body 1.5 mrem 3.65E-02 2.44E+00 6.62E 4.42E-01 l Thyroid 5.0 mrem 2.09E-03 4.19E-02 3.90E-03 7.79E-02 Kidney 5.0 mrem 1.74E-02 3.49E-01 5.03E-03 1.01 E-01 ,
Lung 5.0 mrem 1.05E-01 2.10E+00 2.18E-02 4.36E-01 !
GI-LLI 5.0 mrem 1.42E-02 2.84E-01 7.38E-03 ,1.48E-01
'I l
CUMULATIVE DOSE PER YEAR l ORGAN .ODCM UNITS YEAR TO DATE % OF ODCM LIMIT LIMIT Bone 10.0 mrem 3.12E-02 3.12E-01 Liver 10.0 mrem 5.71 E-02 5.71 E-01 T. Body 3.0 mrem 4.32E-02 1.44E+00 Thyroid 10.0 mrem 5.99E-03 5.99E-02 Kidney 10.0 mrem 2.25E-02 2.25E-01 Lung 10.0 mrem 1.27E-01 1.27E+00 GI-LLI 10.0 mrem 2.16E-02 2.16E-01 l
l l I
25
)
i TABLE 1-4AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO LIQUID RELEASES July,1994 THROUGH December,1994 i UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF 1 i
LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone. 5.0 mrem 2.94E-02 5.89E-01 4.14E-02 8.29E-01 Liver 5.0 mrem 5.30E-02 1.06E+00 7.62E-02 1.52E+00 T. Body 1.5 mrem 3.97E-02 2.65E+00 5.74E-02 3.83E+00 i Thyroid 5.0 mrem 2.71 E-03 5.42E-02 3.59E-03 7.18E-02 ;
Kidney 5.0 mrem 1.85E-02 3.70E-01 2.77E-02 5.54E-01 !
Lung 5.0 mrem 5.97E-02 1.19E+00 4.93E-02 9.86E-01 !
GI-LLI 5.0 mrem 9.44E-03 ' 1.08E-01 1.24E-02 2.48E-01 4
CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM .
LIMIT LIMIT Bone 10.0 mrem 1.02E-01 1.02E+00 i Liver 10.0 mrem 1.86E 1.86E+00 ,
T. Body 3.0 mrem 1.40E-01 4.68E+00 Thyroid 10.0 mrem 1.23E-02 1.23E-01 ,
Kidney 10.0 mrem 6.86E-02 6.86E-01 ;
Lung 10.0 mrem 2.36E-01 2.36E+00 I
GI-LLI 10.0 mrem 4.34E-02. 4.34E-01 5
h i
1 TABLE 1-4B .I VOGTLE ELECTRIC GENERATING PLANT l ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT !
INDIVIDUAL DOSES DUE TO LIQUID RELEASES .
JANUARY,1994 THROUGH JUNE,1994 J
UNIT 2 CUMULATIVE DOSE PER QUARTER ;
ORGAN ODCM UNITS QUARTER % OF QUARTER % OF ;
LIMIT ODCM- ODCM 1 2 LIMIT LIMIT l Bone 5.0 mrem 4.29E-03 8.59E-02 1.36E-03 2.72E-02 <
Liver 5.0 mrem 6.00E-03 1.20E-01 4.16E-03 8.33E-02 T. Body 1.5 mrem 4.59E-03 3.06E-01 3.37E-03 2.25E-01 l Thyroid 5.0 mrem 5.46E-04 1.09E-02 2.27E-03 4.54E-02 1 Kidney . 5.0 mrem 2.19E-03 4.37E-02 2.78E-03 5.56E-02 ;
Lung 5.0 . mrem 2.73E-02 5.45E-01 ' 6.57E-03 1.31 E-01 l
GI-LLI 5.0 mrem 5.38E-03 1.08E-01 5.91 E-03 1.18E-01 CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % OF ODCM ;
LIMIT LIMIT Bone 10.0 mrem 5.65E-03 5.65E-02 Liver 10.0 mrem 1.02E-02 1.02E-01 T. Body 3.0 mrem 7.96E-03 2.65E-01 Thyroid 10.0 mrem 2.82E-03 2.82E-02 Kidney 10.0 mrem 4.96E-03 4.96E-02 Lung 10.0 mrem 3.38E-02 3.38E-01 GI-LLI 10.0 mrem 1.13E-02 1.13E-01 I
l 27 i l
l
I l
TABLE 1-4BB ,
VOGTLE ELECTRIC GENERATING PLANT ;
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l' INDIVIDUAL DOSES DUE TO LIQUID RELEASES JULY,1994 THROUGH DECEMBER,1994 ;
l UNIT 2 l
CUMULATIVE DOSE PER QUARTER ;
ORGAN ODCM UNITS QUARTER % OF QUARTER .% OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT -
Bone 5.0 mrem 143E-02 2.86E-01 3.77E-03 7.54E-02 j Liver 5.0 mrem 3.88E-02 7.76E-01 8.03E-03 1.61 E-01 i' T. Body 1.5 mrem 3.23E-02 2.15E+00 6.33E 4.22E-01 Thyroid 5.0 mrem 1.55E-02 3.10E-01 1.66E-03 3.32E-02 ,
Kidney 5.0 mrem 2.20E-02 4.40E-01 3.70E-03 7.40E-02 l Lung 5.0 mrem 3.90E-02 7.81 E-01 8.86E-03 1.77E-01 j GI-LLI 5.0 mrem 2.08E-02 4.16E-01 3.15E-03 6.30E-02 !
i CUMULATIVE DOSE PER YEAR i ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT LIMIT l Bone 10.0 mrem 2.37E-02 2.37E-01 Liver 10.0 mrem 5.70E-02 5.70E-01 -
T. Body 3.0 mrem 4.66E-02 1.55E+00 Thyroid 10.0 mrem 2.00E-02 2.00E-01 ,
Kidney 10.0 mrem 3.07E-02 3.07E-01 ;
Lung 10.0 mrem 8.17E-02 8.17E-01 i GI-LLI 10.0 mrem 3.52E-02 3.52E-01 l
r L
i i
28 l w _ __ . _ _ _ _ _ _ . _ _ . . . - __ . . ~ . . . , _ . ,. .__m. ..
t l
l l
TABLE 1-5 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT JANUARY,1994 - DECEMBER 31,1994 i
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/ml 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/ml Cs-134 3.06E-08 uCi/ml Cs-137 4.51 E-08 uCi/ml Ce-141 6.99E-08 uCi/ml ,
Ce-144 2.95E-07 uCi/ml ,
1-131 5.97E-08 uCi/mi ,
Xe-133 9.11 E-08 uCi/mi Xe-135 4.27E-08 uCi/ml Fe-55 1.00E-06 uCi/ml ,
Sr-89 5.00E-08 uCi/ml Sr-90 7.00E-09 uCi/ml H-3 2.00E-06 uCi/ml Gross Alpha 7.00E-08 uCi/ml 29
TABLE 1-6A GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 1 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1994 ENDING: JUNE,1994 LIQUID RELEASES Number of Releases -
61 Total Time For All Releases 11511.28 minutes Maximum Time For a Release 783.00 minutes Average Time For a Release 188.71 minutes Minimum Time For a Release 2.28 minutes GASEOUS RELEASES Number of Releases: 85 Total Time For All Releases 8607.67 minutes Maximum Time For A Release 714.00 minutes Average Time For A Release 101.27 minutes ;
Minimum Time For A Release 6.00 minutes !
4 4
30 1 1
TABLE 1-6AA GEORGIA POWER COMPANY l VOGTLE ELECTRIC GENERATING PLANT- UNIT 1
)
BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JULY,1994 ENDING: DECEMBER,1994 l
l LIQUID RELEASES '
Number of Releases 54 Total Time For All Releases 8552.00 minutes Maximum Time For a Release 321.00 minutes l Average Time For a Release 158.37 minutes !
Minimum Time For a Release 37.00 minutes l I
l GASEOUS RELEASES Number of Releases: 90 Total Time For All Releases 63052.78' minutes Maximum Time For A Release 8655.00 minutes Average Time For A Release 700.59 minutes Minimum Time For A Release 2.92 minutes 1
31
TABLE 1-6B GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JANUARY,1994 ENDING: JUNE,1994 i
LIQUID RELEASES Number of Releases 32 Total Time For All Releases 5468.00 minutes Maximum Time For A Release 357.00 minutes -
Average Time For A Release 170.88 minutes Minimum Time For A Release 39.00 minutes GASEOUS RELEASES :
Number of Releases 37 ;
Total Time For All Releases 17021.08. minutes
~
Maximum Time For a Release 4887.00 minutes Average Time For A Release 460.03 minutes Minimum Time For A Release 10.00 ' minutes 1
l l
32 l
TABLE 1-6BB GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNIT 2 BATCH RELEASE
SUMMARY
OF ALL RELEASES STARTING: JULY,1994 ENDING: DECEMBER,1994 LIQUID RELEASES Number of Releases 36 Total Time For All Releases 7161.62 minutes Maximum Time For A Release 585.00 minutes Average Time For A Release 198.93- minutes Minimum Time For A Release 51.00 minutes GASEOlis RELEASES Number of Releases 36 Total Time For All Releases 26283.58 minutes Maximum Time For a Release ,
7402.90 minutes Average Time For A Release 730.10 minutes Minimum Time For A Release 25.92 minutes 33
I 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 i 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 areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and
- b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.1.3 Dose To Any Organ 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 i any organ.
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
i
)
34
p 2.1.4 Total Fuel Cycle Dose Commitment (40CFR190)
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 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 iodine's. During this reporting period, there were no continous radioactive releases through the condenser air ejector and steam packing exhauster system vents.
Unless required more frequently under certain circumstances samples are collected as follows:
- 1. Noble gas samples are collected by grab sampling at least monthly.
- 2. Tritium samples are collected by grab sampling.at least monthly. Tritium grab samples are taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded. Also tritium grab samples are taken at least once per 7 days from the Unit 1 Plant Vent, whenever spent fuel is in the Spent Fuel ;
Pool (Unit 1 Plant Vent Only) t
- 3. Radiciodine samples are collected from the sample stream through l a charcoal cartridge over a 7 day period. i
- 4. Particulates are collected from the sample stream through a :
particulate filter over a 7 day period.
- 5. The 7-day particulate filters above are analyzed for gross alpha activity.
35
- 6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly composite sample is analyzed for Sr-89 and Sr-90.
Batch Waste Gas Decay Tank releases are analyzed for iodine's, particulates, and noble gases before each release. In addition, the containment atmosphere is analyzed for tritium on at least 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.
2.4 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses follow:
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
)
l period represented by the collected sample. !
Instantaneous dose rates due to noble gases and due to radiciodines, tritium, and particulates are calculated (with computer assistance). Calculated l 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 for each release period. Air dose calculation methodology is presented in the ODCM.
36
t 2.4.2 Radiolodines, Tritium and Particulate Releases l Released quantil!es 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.
l After each quarter, the particulate filters from each vent are combined, fused, and a strontium separatiu." .s performed. If Sr-89 or Sr-90 is not detected, MDC's 1 are calculated. Strontium concentrations are input to the composite file of the '
computer to be used for release dose rate and individual dose calculations.
Tritium samples are obtained at least monthly from each vent by bubbling the sample stream through a water trap. The tritium concentration in waier '
is converted to tritium concentration in air and this value is input into the composite file of the compuer 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 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 individual doses due to radioiodines, 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. CumW.ive 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 i
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.
37
r 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 2-2A, 2-2AA, 2-28, 2-288, 2-2C, 2-2CC, 2-3A, 2-3AA, ' 2-3B, 2-3BB, 2-3C, 2-3C C, 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, iodine's, 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 we have no curie limits for gaseous releases.
Applicable lirnits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radiciodines, 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.
Gross alpha radioactivity is reported in Table 2-2A,2-2AA,2-2B, and 2-2BB as curies released in each quarter.
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,2-6B, 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,2-7B, 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 perameter 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 1
v
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 calculated 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 from sample and 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 %
2.5.1.4 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,1-6B, and 1-6BB. '
i 2.6 RadiologicalImpact Due to Gaseous Releases Dose rates due to noble gas relet fere 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 2-688.
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 two unplanned releases for this reporting period.
Personnel air lock doors were open concurrently on Unit 1 on 8-30-1994 for about 15 minutes. This may have caused an unmonitored release from the containment to the control building. There was an open permit for the containment purge during this period. Using the sample from that permit dose and dose rates were calculated for this 15 minute period ( Permit # 940281.027. The total curie released from 40
- - - _ _ _ ___ _ _______ _._-- - A
i i
i this release was 1.91E-05. No ODCM limits were exceeded. DC 1-94-0140 was initiated l for this incident.
t i
During the end of Unit 1 refueling outage (10-10-1994) turbine building vent monitor showed particulate activities in the weekly sample collection. Upon investigation the ;
activity may have come when primary and secondary manways were open ,
simultaneously during that period. No gaseous activities were found. Also there was no primary to secondary leak since the unit was in refueling outage. Release permit 940331-G was generated for this period. Total curie released from this release was j 4.28E-08. No ODCM limits were exceeded. DC 1-94-0290 was initiated for this incident. i i
i i
t l
I I
i l
41
o ,
o:
l TABLE 2-2A GEORGIA POWER COMPANY l VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994' l ALL AIRBORNE EFFLUENTS :
UNIT: 1 .
l STARTING : 1-JAN-1994 ENDING : 30-JUN-1994 TYPE OF EFFLUENT UNITS ' QUARTER 1 QUARTER 2 EST. TOTAL l ERROR % ;
A. FISSION & ACTIVATION PRODUCTS j i
- 1. TOTAL RELEASE CURIES 5.43E+00 2.13E+00 50 i i'
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.98E-01 2.71E-01 '
- 3. PERCENTAGE OF APPLICABLE LIMIT % .i B. RADIOlODINES l 1
- 1. TOTAL IODINE-131 CURIES 2.71E-06 1.58E-05 100 -l
- 2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec . 3.49E-07 2.01 E-06 ' i i
DURING PERIOD i
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- i C. PARTICULATES l ;
1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 4.45E-08 1.58E-07 90 1
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.72E-09 2.01 E-08 !
- 3. PERCENTAGE OF APPLICABLE LIMIT .% l D. TRITIUM !
- 1. TOTAL RELEASE CURIES 1.16E+01 3.29E+01 40 l l
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.49E+00 4.18E+00 l
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 9.72E-06 3.24E-04 90 l i
- Applicable limits are expressed in terms of dose. See Tables 2-6A and 2-7A of this report 4 42 l i
i
. m. _ . _ - - _ - , - . ., . . . - . , - .. - , . _ _ _
TABLE 2-2AA GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL AIRBORNE EFFLUENTS UNIT : 1 STARTING : 1-JUL-1994 ENDING : 31-DEC-1994 TYPE OF EFFLUENT UNITS QUARTER 3 OUARTER4 EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 2.21E+01 1.80E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.78E+00 2.26E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 1.02E-04 1.27E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.28E-05 ' 1.60E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.92E-06 8.08E-07 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.42E-07 1.02E-07
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 2.61E+01 2.19E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.28E+00 2.76E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 5.94E-06 1.54E-06 90
- Applicable limits are expressed in terms of dose. See Tables 2-6AA, and 2-7AA of this report 43
i, l
1 i
-TABLE 2-2B - .;
GEORGIA POWER COMPANYL.
. l VOGTLE ELECTRIC GENERATING PLANT l t
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 i
. ALL AIRBORNE EFFLUENTS - !
UNIT: 2 i STARTING : 1-JAN-1994 ~ ENDING : 30-JUN-1994 ;
' TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOTAL j ERROR % ;
A. FISSION & ACTIVATION PRODUCTS !
s 1
- 1. TOTAL RELEASE CURIES 1.11E+01 1.41E+01 50 :
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.43E+00 1.79E+00 !
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOIODINES
- 1. TOTAL LODINE-131 CURIES ~2.11 E-05 6.11E-04 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.71E-06 7.77E-05 ;
DURING PERIOD l i
- 3. PERCENTAGE OF APPLICABLE LIMIT % .. i C. PARTICULATES ,
- 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 1.49E-06 6.53E-05 90 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.92E-07 8.31 E-06 _
'l
- 3. PERCENTAGE OF APPLICABLE LIMIT % !
D.TRITlUM !
i
- 1. TOTAL RELEASE CURIES 1.89E-01 1.72E+01 40
'I
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.43E-02 2.19E+00 l
-j
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 1.09E-05 1.79E-05 90 l
1
'i
- Applicable limits are expressed in terms of dose. See Tables 2-6B and 2-7B of this report l
44 ]
'I '
TABLE 2-2BB GEORGIA POWER COMPANY t VOGTLE ELECTRIC GENERATING PLANT f ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL AIRBORNE EFFLUENTS UNIT : 2 STARTING : 1-JUL-1994 ENDING : 31-DEC-1994 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOTAL ~
ERROR %
A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 2.38E+01 1.87E-01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.99E+00 2.35E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 2.57E-05 1.52E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.23E-06 1.91 E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 3.98E-06 3.40E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.01E-07 4.28E-06
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 5.40E+00 3.06E+00 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.79E-01 3.85E-01
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 8.89E-04 1.31 E-06 90
- Applicable limits are expressed in terms of dose. See Tables 2-6BB, and 2-78B of this report of this report 45
}
7;p m
TABLE 2-2C
' GEORGIA POWER COMPANY
- VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL AIRBORNE EFFLUENTS -
SITE -
STARTING : 1-JAN-1994 ENDING : 30-JUN-1994
- TYPE OF EFFLUENT UNITS QUARTER 1. QUARTER 2 _EST. TOTAL ERROR %
A. FISSION & ACTIVATION PRODUCTS .
- 1. TOTAL RELEASE CURIES 1.65E+01 1.62E+01 50
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.13E+00 2.06E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- B. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 2.38E-05 6.27E-04 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.06E-06 7.97E-05 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES .
1.PARTICULATES(HALF-LIVES >BDAYS) CURIES 1.53E-06 6.55E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.97E-07 5.84E-03
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 1.18E+01 5.01E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.52E+00 6.37E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 4. GROSS ALPHA RADIOACTIVITY CURIES 2.06E-05 3.42E-04 90
- Applicable limits are expressed in terms of dose. See Tables 2-6A,2-6B, 2-7A., and 2-7B of this report 46
TABLE 2-2CC GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1994 ALL AIRBORNE EFFLUENTS SITE STARTING : 1-JUL-1994 ENDING : 31-DEC-1994 TYPE OF EFFLUENT UNITS OUARTER3 OUARTER 4 A. FISSION & ACTIVATION PRODUCTS
- 1. TOTAL RELEASE CURIES 4.59E+01 3.67E-01 50 ,
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.77E+00 4.62E-02
- 3. PERCENTAGE OF APPLICABLE LIMIT %
- 8. RADIOlODINES
- 1. TOTAL IODINE-131 CURIES 1.28E-04 2.79E-05 100
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.61E-05 3.51E-06 DURING PERIOD
- 3. PERCENTAGE OF APPLICABLE LIMIT %
C. PARTICULATES 1.PARTICULATES(HALF-LIVES >8 DAYS) CURIES 5.90E-06 3.48E-05 90
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.42E-07 4.38E-06
- 3. PERCENTAGE OF APPLICABLE LIMIT %
D. TRITIUM
- 1. TOTAL RELEASE CURIES 3.15E+01 2.50E+01 40
- 2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.96E+00 3.14E+00
- 3. PERCENTAGE OF APPLICABLE LIMIT % '
- 4. GROSS ALPHA RADIOACTIVITY CURIES 8.95E-04 2.85E-06 90
- Applicable limits are expressed in terms of dose. See Tables 2-6AA,2-6BB,2-7AA, and 2-788 of this report.
47
- - _ .~. _ - . . _ _ _ .
y .
.i i
i i
TABLE 2-3A (PAGE 1 OF 2) i 1/OGTLE ELECTRIC GENERATING PLANT-i
. ANNUAL EFFLUENTS - MIXED MODE l JANUARY,1994 THROUGH JUNE,1994 UNIT 1 l
NUCLIDES i RELEASED UNIT CONTINUOUS MODE BATCH MODE j
- 1. Fission y" z,'*YQ; QUARTER QUARTER QUARTER QUARTER ,
Gasses a 1 2 1 2 t Xe-135M Ci 0.00E+00 0.00E+00 3.61 E-03 0.00E+00 !
Ar-41 Ci 0.00E+00 0.00E+00 1.16E-01 1.64E-01 !
Xe-135 Ci 0.00E+00 0.00E+00 1.07E-04 - 0.00E+00 i Xe-133M Ci 0.00E+00 0.00E+00 1.88E-03 3.08E-03 Xe-133 Ci 4.86E+00 6.85E-01 4.49E-01 1.25E+00 Xe-131M Ci 0.00E+00 0.00E+00 1.11 E-03 2.35E-02 TOTAL FOR Ci 4.86E+00 6.85E-01 5.72E-01 1.44E+00 i PERIOD ,
- 2. lodine's 1-131 Ci 2.71 E-06 1.58E-05 0.00E+00 0.00E+00 1-133 Ci 0.00E+00 3.38E-05 0.00E+00 0.00E+00 -!
TOTAL FOR Ci 2.71 E-06 4.95E-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.
l 1
48 l
TABLE 2-3A (PAGE 2 OF 2) i VOGTLE ELECTRIC GENERATING PLANT ,
ANNUAL EFFLUENTS - MIXED MODE JANUARY,1994 THROUGH JUNE,1994 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE ;
- 3. Particulates QUARTER QUARTER QUARTER QUARTER 1 2 1 2 Sr-89 Ci 0.00+00 1.44E-07 0.00E+00 0.00E+00 Sr-90 Ci 4.45E-08 1.40E-08 0.00E+00 0.00E+00 TOTAL FOR Ci 4.45E-08 1.58E-07 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 9.72E-06 3.24E-04 0.00E+00 0.00E+00 H-3 Ci 1.16E+01 3.28E+01 3.63E-02 9.98E-02 [
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. ;
49
W TABLE 2-3AA (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1994 THROUGH DECEMBER,1994 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission >
QUARTER QUARTER QUARTER QUARTER Gasses 3 4 3 4 Ar-41 Ci 0.00E+00 0.00E+00 9.83E-01 1.39E-01 Kr-85M Ci 0.00E+00 0.00E+00 4.04E-03 0.00E+00 Xe-135 Ci 5.96E-01 0.00E+00 4.59E-03 1.28E-03 Xe-133M Ci 0.00E+00 0.00E+00 6.92E-02 0.00E+00 Xe-133 Ci 5.92E+00 0.00E+00 1.27E+01 3.95E-02 Xe-131M Ci 1.75E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR. Ci 8.27E+00 0.00E+00 1.38E+01 1.80E-01 PERIOD
- 2. lodines 1-131 Ci 9.52E-05 1.27E-05 7.19E-06 0.00E+00 1-133 Ci 1.55E-05 0.00E+00 1.84E-07 0.00E+00 TOTAL FOR Ci 1.11 E-04 1.27E-05 7.37E-06 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.
50 1 ,
TABLE 2-3AA(PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JULY,1994 THROUGH DECEMBER ,1994 UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates , QUARTER . QUARTER QUARTER QUARTER 3 4 3 4 Cr-51 Cl 0.00E+00 7.65E-07 0.00E+00 0.00E+00 Co-58 Ci 9.39E-07 0.00E+00 0.00E+00 0.00E+00 Co-60 _
Ci 9.81 E-07 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 1.92E-06 7.65E-07 0.00E+00 0.00E+00 PERIOD '
G-ALPHA Ci 5.94E-06 1.54E-06 0.00E+00 0.00E+00 H-3 Ci 2.52E+01 2.17E+01 8.91 E-01 2.03E-01 ,
l
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
51
TABLE 2-3B (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1994 THROUGH JUNE,1994 -
i UNIT 2 i
NUCLIDES
-RELEASED UNIT CONTINUOUS MODE BATCH MODE 4
- 1. Fission
^
<g QUARTER QUARTER . QUARTER QUARTER l Gasses . 1 2- 1 2 ~
Xe-135M Ci 1.73E-01 0.00E+00 0.00E+00 0.00E+00 l Ar-41 Ci 0.00E+00 0.00E+00 2.90E-02 8.31 E-02 I
Xe-135 Ci 0.00E+00 0.00E+00 1.69E-03 1.69E-02 Xe-133M Ci 0.00E+00 0.00E+00 9.70E-03 4.82E-02 Xe-133 Ci 9.17E+00 8.61 E+00 1.71 E+00 5.37E+00 -
Xe-131M Cl 0.00E+00 0.00E+00 3.63E 9.57E-04 Kr-85 Ci 0.00E+00 0.00E+00 1.87E-02 7.73E-03 +
TOTAL FOR Ci 9.34E+00 8.61 E+00 1.80E+00 5.52E+00 PERIOD
- 2. lodine's 1-131 Ci 2.11 E-05 5.96E-04 0.00E+00 0.00E+00 1-133 Ci 4.39E-05 3.72E-04 0.00E+00 0.00E+00 TOTAL FOR Ci 6.50E-05 9.68E-04 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.
52
TABLE 2-3B (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL EFFLUENTS - MIXED MODE JANUARY,1994 THROUGH JUNE,1994 UNIT 2 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates >
QUARTER QUARTER QUARTER QUARTER 1 2 1 2 1-131 Ci 0.00E+00 1.46E-05 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 1.34E-06 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 4.63E-08 0.00E+00 0.00E+00 Co-58 Cl 1.12E-06 4.25E-05 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 4.09E-07 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 1.95E-06 0.00E+00 0.00E+00 Co-60 Ci 3.70E-07 7.52E-07 0.00E+00 0.00E+00 Cs-137 Ci 0.00E+00 1.65E-06 0.00E+00 0.00E+00 OTHER Ci 0.00E+00 2.10E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 1.49E-06 6.53E-05 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 1.09E-05 1.79E-05 0.00E+00 0.00E+00 -
H-3 Ci 0.00E+00 1.69E+01 1.89E-01 3.00E-01 1
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
I 53
- I
- l TABLE 2-3BB (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT j ANNUAL EFFLUENTS - MIXED MODE JULY,1994 THROUGH DECEMBER,1994 i UNIT 2 .
~
NUCLIDES .
RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission g QUARTER QUARTER QUARTER QUARTER g pM Gasses 3' 4 3 4 '
Ar-41 Ci 0.00E+00 0.00E+00 3.88E-01 2.31 E-02 Kr-88 Ci 1.04E-01 0.00E+00 0.00E+00 C.00E+00 Kr-85M Ci 4.19E-01 0.00E+00 1.54E-03 0.00E+00 ;
Xe-135 Ci 2.31 E+00 0.00E+00 1.29E-01 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 6.84E-02 0.00E+00 !
Xe-133 Ci 1.04E+01 1.57E-01 9.90E+00 6.12E Xe-131M Ci 0.00E+00 0.00E+00 6.17E-03 . 0.00E+00 TOTAL FOR Ci 1.33E+01 1.57E-01 1.05E+01 2.92E-02 PERIOD
- 2. lodines 1-131 Ci 2.57E-05 1.47E-05 0.00E+00 ' 0.00E+00 '
l-133 Ci 1.66E-05 1.20E-05 0.00E+00 0.00E+00 TOTAL FOR Ci 4.23E-05 2.67E-05 0.00E+00 0.00E+00 PERIOD P
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See j Table 2-8 for typical minimum detectable concentrations.
l i
54 i
1 4 .
i i
TABLE 2-3BB (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT l
ANNUAL EFFLUENTS - MIXED MODE {
t JULY,1994 THROUGH DECEMBER ,1994 -
UNIT 2 ;
NUCLIDES !
RELEASED UNIT CONTINUOUS MODE BATCH MODE l
- 3. Particulates 's %a QUARTER QUARTER QUARTER QUARTER . i
- a -
3 4 3 4 ,
1-131 Ci 0.00E+00 4.78E-07 0.00E+00 0.00E+00 l Cr-51 Cl 0.00E+00 8.56E-06 0.00E+00 0.00E+00 l Be-7 Ci 0.00E+00 1.52E-06 0.00E+00 0.00E+00 ;
Zr-95 Ci 0.00E+00 5.11 E-07 0.00E+00 0.00E+00 !
Nb-95 Ci 0.00E+00 1.51 E-06 0.00E+00 0.00E+00 l Co-58 Ci 2.62E-06 1.10E-05 0.00E+00 0.00E+00 ;
Mn-54 Ci 1.82E-07 2.57E-06 0.00E+00 0.00E+00 l Cs-134 Ci 5.52E-07 0.00E+00 0.00E+00 0.00E+00 :
Co-60 Ci 3.28E-07 7.81 E-06 0.00E+00 0.00E+00 l Cs-137 Ci 3.01 E-07 0.00E+00 0.00E+00 0.00E+00 ;
TOTAL FOR Ci 3.98E-06 3.40E-05 0.00E+00 0.00E+00 PERIOD l G-ALPHA Ci 8.89E-04 1.31 E-06 0.00E+00 0.00E+00 j H-3 ' Ci 5.15E+00 3.05E+00 2.52E-01 6.23E-03 l 1
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
55 .
l i
TABLE 2-3C (PAGE 1 OF 2) i I
VOGTLE ELECTRIC GENERATING PLANT j ANNUAL EFFLUENTS - MIXED MODE l JANUARY,1994 THROUGH JUNE,1994 SITE I
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission y' ,
QUARTER QUARTER QUARTER QUARTER +
Gasses -
. 1 2 1 2 ;
Xe-135M Ci 1.73E-01 0.00E+00 3.61 E-03 0.00E+00 l Ar-41 Ci 0.00E+00 0.00E+00 1.45E-01 2.47E-01 Xe-135 Ci 0.00E+00 0.00E+00 1.80E-03 1.69E-02 l Xe-133M Ci 0.00E+00 0.00E+00 1.16E-02 5.13E-02 '!
Xe-133 Ci 1.40E+01 9.30E+00 2.16E+00 6.62E+00 Xe-131M Ci 0.00E+00 0.00E+00 3.74E-02 2.45E-02 i Kr-85 Ci 0.00E+00 0.00E+00 1.87E-02 7.73E-03 :
TOTAL FOR Ci 1.42E+01 9.30E+00 2.37E+00 6.96E+00 .
PERIOD
- 2. lodines ,
1-131 Ci 2.38E-05 6.12E-04 0.00E+00 0.00E+00 1-133 Ci 4.39E-05 4.06E-04 0.00E+00 0.00E+00 TOTAL FOR Ci 6.77E-05 1.02E-03 0.00E+00 0.00E+00 l PERIOD
- Zeroes in this table indicate that no radioactivity was'present above detectable levels. See I Table 2-8 for typical minimum detectableconcentrations. ]
l l
- 1 I
56
~
TABLE 2-3C (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - MIXED MODE JANUARY,1994 THROUGH JUNE,1994 SITE NUCLIDES c RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates '
QUARTER QUARTER QUARTER QUARTER 1 2 1 2 1-131 Ci 0.00E+00 1.46E-05 0.00E+00 0.00E+00 Cr-51 Ci 0.00E+00 1.34E-06 0.00E+00 0.00E+00 Sr-89 Ci 0.00E+00 1.91 E-07 0.00E+00 0.00E+00 Co-58 Ci 1.12E-06 4.25E-05 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 4.09E-07 0.00E+00 0.00E+00 Cs,134 Ci 0.00E+00 1.95E-06 0.00E+00 0.00E+00 Co-60 Ci 3.70E-07 7.52E-07 0.00E+00 0.00E+00 :
Sr-90 Ci '
4.45E-08 1.40E-08 0.00E+00 0.00E+00 Cs-137 Cl _ 0.00E+00 1.65E-06 0.00E+00 0.00E+00 OTHER Ci 0.00E+00 2.10E-06 0.00E+00 0.00E+00 TOTAL FOR Ci 1.54E-06 6.55E-05 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 2.06E-05 3.42E-04 0.00E+00 0.00E+00 H-3 Ci 1.16E+01 4.98E+01 2.26E-01 4.00E-01
- Zeroes in this table indicate thM no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
57
TABLE 2-3CC (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT i i
ANNUAL EFFLUENTS - MIXED MODE t JULY,1994 THROUGH DECEMBER,1994 SITE i
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission QUARTER QUARTER QUARTER QUARTER Gasses 3 4 3 4 '
Ar-41 Ci 0.00E+00 0.00E+00 1.37E+00 1.62E-01 ,
Kr-88 Ci 1.04E-01 0.00E+00 0.00E+00 0.00E+00 Kr-85M Ci 4.19E-01 0.00E+00 5.58E-03 0.00E+00 Xe-135 Ci 2.91 E+00 0.00E+00 1.33E-01 1.28E-03 Xe-133M Ci 0.00E+00 0.00E+00 1.38E-01 'O.00E+00 ;
Xe-133 Ci 1.63E+01 1.57E-01 2.26E+01 4.56E-02 Xe-131M Ci 1.75E+00 0.00+00 6.17E-03 0.00E+00 -
TOTAL FOR Ci 2.15E+01 1.57E-01 2.43E+01 2.09E-01 i PERIOD :
- 2. lodines 1-131 Ci 1.21 E-04 2.75E-05 7.19E-06 0.00E+00 1-133 Ci 3.21 E-05 1.20E-05 1.84E-07 0.00E+00 i TOTAL FOR Ci 1.53E-04 3.94E-05 7.37E-06 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 l
l l
58 {
i TABLE 2-3CC (PAGE 2 OF 2) ;
i VOGTLE ELECTRIC GENERATING PLANT .
ANNUAL EFFLUENTS - MIXED MODE JULY,1994 THROUGH DECEMBER ,1994 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE ;
- 3. Particulates , QUARTER QUARTER QUARTER t 3 4 3 ,
1-131 Ci 0.00E+00 4.78E-07 0.00E+00 0.00E+00 Cr-51 Cl 0.00E+00 9.32E-06 0.00E+00 0.00E+00 Be-7 Ci 0.00E+00 1.52E-06 0.00E+00 0.00E+00 Zr-95 Ci 0.00E+00 5.11 E-07 0.00E+00 0.00E+00 ;
Nb-95 Ci 0.00E+00 1.51 E-06 0.00E+00 0.00E+00 ;
Co-58 Ci 3.56E-06 1.10E-05 0.00E+00 0.00E+00 Mn-54 _Ci 1.82E-07 2.57E-06 0.00E+00 0.00E+00 Cs-134 'Ci 5.52E-07 0.00E+00 0.00E+00 0.00E+00 -
Co-60 Ci 1.31 E-06 7.81 E-06 0.00E+00 0.00E+00 ;
Cs-137 Ci 3.01 E-07 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 5.90E-06 3.48E-05 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 8.95E-04 2.84E-06 0.00E+00 0.00E+00 H-3 Ci 3.03E+01 2.48E+01 1.14E+00 2.09E-01 ,
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
i i
59 I
-l l
l TABLE 2-4A (PAGE 1 OF 2) l VOGTLE ELECTRIC GENERATING PLANT !
ANNUAL EFFLUENTS - GROUND MODE .
JANUARY,1994 THROUGH JUNE,1994 UNIT 1 NUCLIDES j RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission , y' ,
QUARTER QUARTER QUARTER QUARTER Gasses '
& 1 2 1 2 Xe-133 Ci 3.38E-05 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 3.38E-05 0.00E+00 0.00E+00 0.00E+00 PERIOD !
- 2. lodines 1-131 Ci 0.00E+00 - 0.00E+00 0.00E+00 0.00E+00 1-133 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 present above detectable levels. See Table 2-8 for typical minimum detectable concentrations.
1 i
l 60 i
TABLE 2-4A (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JAN,1994 THROUGH JUNE,1994 1
UNIT 1 NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates QUARTER QUARTER QUARTER QUARTER 1 2 1 2
^
Sr-90 Ci 1.34E-13 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 1.34E-13 0.00E+00 0.00E+00 0.00E+00 PERIOD G-ALPHA Ci 6.85E-11 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 7.04E-05 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 l
I l
1 61
k TABLE 2-4AA (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE
. JULY,1994 THROUGH DECEMBER,1994 ,
t UNIT 1 i NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 1. Fission QUARTER QUARTER QUARTER QUARTER Gasses 3 4 3 4 Ar-41 Ci 0.00E+00 0.00E+00 1.32E-05 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 0.00E+00 Xe-133 Ci 0.00E+00 0.00E+00 7.65E-07 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 1.40E-05 0.00E+00 PERIOD
- 2. lodines 1-131 Ci 0.00E+00 0.00E+00 1.12E-10 0.00E+00 1-133 Ci 0.00E+00. 0.00E+00 2.04E-10 0.00E+00 TOTAL FOR Ci 0.00E+00 0.00E+00 3.16E-10 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.
62
i l
l l
l TABLE 2-4AA (PAGE 2 OF 2) i VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JULY,1994 THROUGH DECEMBER ,1994 UNIT 1 NUCLIDES 1 RELEASED UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates % QUARTER QUARTER QUARTER QUARTER 3 4 3 4 Na-24 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Cl 0.00E+00 0.00E+00 0.00E+00 2.31 E-08 Co-58 Ci 0.00E+00 0.00E+00 0.00E+00 9.08E-09 Fe-59 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 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 4.67E-09 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 Zr-95 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 6.01 E-09 i TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 4.28E-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 5.16E-06 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
63
i r
i i
TABLE 2-4B (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE .l i
JANUARY,1994 THROUGH JUNE,1994 ;
UNIT 2 ,
t NUCLIDES l RELEASED UNIT CONTINUOUS MODE BATCH MODE j
- 1. Fission qgg~ y QUARTER QUARTER QUARTER QUARTER {
Gasses ~
1 2 1 2 ,
Ar-41 - Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .i Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
Kr-85M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 - l Xe-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 t Xe-133 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 ,
Xe-135 Ci' O.00E+00 0.00E+00 0.00E+00 - 0.00E+00 i Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 :
PERIOD )
- 2. lodines ;
l-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 :
1-133 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 i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical minimum detectable concentrations. :
Y t
I 64 i
I h
i i
,)
TABLE 2-4B (PAGE 2 OF 2)
VOG7LEELECTRIC GENERJ 'ING PLANT
, ANNUAL EFYLUENTS - GROUND MODE- .
ps L JANUARY,19N THROUGH JUNE,1994 i
~
UNIT 2 ' ,
, NUCLIDES i RELEASED UNIT CONTINUOUS MODE BATCH MODE <
- 3. Particulates % . QUARTER QUARTER QUARTER QUARTER ca dfM<ai 1 2 1 2 i Na-24 Ci 0. OE+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i Nb-95 l
Ci
- ll 0.00E+00
- ll 0.00E+00 0.00E+00 0.00E+00 -
1 Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 j 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 '
Zr-95 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 - ,
TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 -l PERIOD i G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '
H-3 Ci 0.00E400 -0.00E+00 0.00E+00 0.00E+00 i
Zeroes in this table indicate that no radioactivity was present above detectable levels. See ;
Table 2-8 for typical minimum detectable concentrati ans. !
65
w,, ----- ---
TABLE 2-4BB (PAGE 1 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE
\
JULY,1994 THROUGH DECEMBER,1994 UNIT 2, NUCLIDES l RELEASED UNIT CONTINUOUS MODE BATCH MODE ,
- 1. Fission 9hg ., QUARTER QUARTER QUARTER QUARTER l Gasses moi i ' 3 4 3 4' !
Ar-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 1 0.00E+00 0.00E+00 Kr-85M Ci 0.00E+00 0.00E+00 ' O.00E+00 0.00E+00 Xe-131M 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-133M di 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 Kr-87 Ci 0.00E+00 0' 00 0.00E+00 0.00E+00 TOTAL FOR Ci 0.00E+00 '
00 0.00E+00 0.00E+00 PERIOD
- 2. lodines !
I l-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l-133 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 present above detectable levels. See Table 2-8 for typical minimum detectable concentrations..
66
.- . _+n, n. . .. n --e 4 a
l
-i 1
. TABLE 2-4BB(PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT l
' ANNUAL EFFLUENTS - GROUND MODE l
JULY,1994 THROUGH DECEMBER ,1994 l
}
UNIT 2 ;
NUCLIDES ?
RELEASED . UNIT CONTINUOUS MODE BATCH MODE
- 3. Particulates J ~f QUARTER QUARTER QUARTER QUARTER
.~ n 3 4 3 4 l Na-24 Ci- 0.00E+00 0.00E+00 . 0.00E+00 0.00E+00 .j Cr-51 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 !
Fe-59 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 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 Sr-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I Zr-95 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 l TOTAL FOR Ci 0.00E+00 0.00E+00 0.090E+00 0.00E+00. .
PERIOD ;
G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l H-3 Ci 0.00E+00 ~0.00E+00 0.00E+00 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. 1
~
1 67 ,
l
TABLE 2-4C (PAGE 1 OF 2)
VOGTLE ELECTRIC GESERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JANUARY,1994 THROUGH JUNE,1994 SITE NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE '
- 1. Fission QUARTER QUARTER QUARTER QUARTER g,,,,, a y, ;' 9 ,
, , , y Ar-41 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 '
Kr-85M Ci 0.00Et00 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 3.38E-05 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 Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR Ci 3.38E-05 0.00E+00 0.00E+00 0.00E+00 PERIOD
- 2. lodines 1-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-133 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 present above detectable levels. See .
Table 2-8 for typical minimum detectable concentrations.
I 68
n TABLE 2-4C(PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE JANUARY,1994 THROUGH JUNE,1994 SITE
'i NUCLIDES ;
RELEASED UNIT CONTINUOUS MODE BATCH MODE ,
- 3. Particulates ,_,- ,, QUARTER QUARTER QUARTER QUARTER
%- 1 2 1 2 ,
Sr-89 Ci 0.00E+00 ' O.00E+00 0.00E+00 0.00E+00 Sr-90 Ci 1.34E-13 0.00E+00 0.00E +00 0.00E+00 )
G-ALPHA Ci 6.85E-11 0.00E+00 0.00E+00 0.00E+00 ;
l H-3 Ci 7.04E-05 0.00E+00 0.00E+00 0.00E+00 4
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See l
Table 2-8 for typical minimum detectable concentrations.
i i
69
- l L l TABLE 2-4CC (PAGE 1 OF 2) l VOGTLE ELECTRIC GENERATING PLANT l ANNUAL EFFLUENTS - GROUND MODE ;
JULY,1994 THROUGH DECEMBER,1994 :
SITE !
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE i
- 1. Fission ' y gg ' QUARTER QUARTER QUARTER QUARTER ;
l Gasses er WR 3 4 3 4 ~
Ar-41 Ci 0.00E+00 0.00E+00 1.32E 0.00E+00 Kr-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 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 0.00E+00 l Xe-133 Ci 0.00E+00 0.00E+00 7.65E-07 0.00E+00 Xe-133M Ci 0.00E+00 0.00E+00 0.00E+00 - 0.00E+00 i Xe-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
Kr-87 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i TOTAL FOR Ci 0.00E+00 0.00E+00 1.40E-05 0.00E+00 !
PERIOD i
- 2. lodines l l-131 Ci 0.00E+00 0.00E+00 1.12E-10 0.00E+00 l
l-133 ' Ci 0.00E+00. 0.00E+00 2.04E-10 0.00E+00 i TOTAL FOR Ci 0.00E+00 0.00E+00 3.16E-10 0.00E+00 i PERIOD ]
1
)
i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See i Table 2-8 for typical minimum detectable concentrations.
1 1
i I
70 l
g b
.i, TABLE 2-4CC (PAGE 2 OF 2)
VOGTLE ELECTRIC GENERATING PLANT ANNUAL EFFLUENTS - GROUND MODE ;
JULY,1994 THROUGH DECEMBER ,1994 UNIT 1 i
NUCLIDES RELEASED UNIT CONTINUOUS MODE BATCH MODE .
- 3. Particulates .
L;y y QUARTER . QUARTER QUARTER QUARTER l
.: - ~ , ,
3 4 3 4 l Na-24 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 -
Cr-51 Cl 0.00E+00 0.00E+00 0.00E+00 2.31 E-08 !
Co 58 Ci 0.00E+00 0.00E+00 0.00E+00 9.08E-09 Fe-59 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 i Mn-54 Ci 0.00E+00 0.00E+00 0.00E+00 4.67E-09 l '
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 :
Zr-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Co-60 Ci 0.00E+00 0.00E+00 0.00E+00 6.01 E-09 l TOTAL FOR Ci 0.00E+00 0.00E+00 0.00E+00 4.28E-08 ;
PERIOD l
G-ALPHA Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 H-3 Ci 0.00E+00 0.00E+00 5.16E-06 0.00E+00
-l
- Zeroes in this table indicate that no radic activity was present above detectable levels. See
- Table 2-8 for typical minimum detectable concentrations. j 71 l
i i
i TABLE 2-6A. '
VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES l JANUARY,1994 THROUGH JUNE,1994 i UNIT 1 CUMMULATIVE DOSE PER QUARTER !
TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF .l RADIATION LIMIT 1 ODCM 2 ODCM '
LIMIT LIMIT .i GAMMA 5.0 mrad 4.34E-05 8.68E-04 3.24E-05 6.47E-04 BETA 10.0 mrad 8.73E-05 8.73E-04 3.81E-05 3.81E-04 i
l 4
l CUMULATIVE DOSES PER YEAR (YEAR TO DATE) l TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 7.58E-05 7.5BE-04 )
BETA 20.0 mrad 1.25E-04 6.27E-04 l
I i
72
t i
I I
I l
I TABLE 2-6AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1994 THROUGH DECEMBER,1994 UNIT 1 l
CUMMULATIVE DOSE PER QUARTER TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF RADIATION LIMIT 3 ODCM 4 ODCM LIMIT LIMIT GAMMA 5.0 mrad 2.52E-04 5.03E-03 1.92E-05 3.83E-04 BETA 10.0 mrad 3.86E-04 3.86E-03 7.33E-06 7.33E-05 l CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 3.47E-04 3.47E-03 BETA 20.0 mrad 5.19E-04 2.59E-03 73
c .
V TABLE 2-6B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES -
l JANUARY,1994 THROUGH JUNE,1994 UNIT 2 i
CUMMULATIVE DOSE PER QUARTER l TYPE OF ODCM UNITS QUARTER % OF QUARTER % OF 1 RADIATION LIMIT 1 ODCM 2 ODCM. l UMIT UMIT l
GAMMA 5.0 mrad 6.89E-05 1.38E-03 B.43E-05 1.69E-03 BETA 10.0 mrad 1.72E-04 1.72E-03 2.21E-04 2.21E-03 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM UMIT UNITS YEAR TO DATE % OF ODCM RADIATION UMIT GAMMA 10.0 mrad 1.53E-04 1.53E-03 \
BETA 20.0 mrad 3.93E-04 1.96E-03 74
- 7. .
TABLE 2-6BB VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT AIR DOSE DUE TO NOBLE GAS RELEASES JULY,1994 THROUGH DECEMBER,1994 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 2.57E-04 5.15E-03 3.99E-06 7.98E-05 BETA 10.0 mrad 4.37E-04 4.37E-03 3.62E-06 3.62E-05 CUMULATIVE DOSES PER YEAR (YEAR TO DATE)
TYPE OF ODCM LIMIT UNITS YEAR TO DATE % OF ODCM RADIATION LIMIT GAMMA 10.0 mrad 4.15E-04 4.15E-03 BETA 20.0 mrad 8.34E-04 4.17E-03 75
l i
TABLE 2-7A :i VOGTLE ELECTRIC GENERATING PLANT ,
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM ,
JANUARY,1994 THROUGH JUNE,1994 !
UNIT 1 'l
- CUMULATIVE DOSE PER QUARTER ,
ORGAN ODCM UNITS QUARTER .% OF QUARTER . % OF LIMIT 1 ODCM 2 ODCM i l
LIMIT - LIMIT Bone 7.5 mrem 2.01 E 2.68E-07 2.25E-08 3.00E-07 -!
. Liver T. Body 7.5 7.5 mrem mrem 5.25E-06 5.25E-05 7.00E-04 7.00E-04 1.49E-04 1.49E-04 1.99E-03 1.99E-03
]
j Thyroid 7.5 mrem 5.27E-05 7.03E-04 1.51 E 2.01 E-03 l Kidney 7.5 mrem 5.25E-05 7.00E-04 1.49E-04 1.99E-03 i Lung 7.5 mrem 5.25E-05 7.00E-04 1.49E-04 1.99E-03 ]
GI-LLI 7.5 mrem 5.25E-05 7.00E-04 1.49E-04 1.99E-03 !
h CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM ;
LIMIT LIMIT i Bone 15.0 mrem 4.26E-08 2.84E-07 ,
Liver 15.0 mrem 2.02E-04 1.34E-03 T. Body 15.0 mrem 2.02E-04 1.34E-03 >
Thyroid 15.0 mrem 2.03E-04 1.36E-03 Kidney 15.0 mrem 2.02E-04 1.34E-03 Lung 15.0 mrem 2.02E-04 1.34E-03 ,
GI-LLI 15.0 mrem 2.02E-04 1.34E-03 76
m I
TABLE 2-7AA VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM ;
JULY,1994 THROUGH DECEMBER,1994 UNIT 1 CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 3 ODCM 4 ODCM LIMIT LIMIT Bone 7.5 mrem 7.50E-07 1.00E-05 2.18E-08 2.91 E-07 Liver 7.5 mrem 1.19E-04 1.58E-03 9.93E-05 1.32E-03 >
T. Body 7.5 mrem 1.19E-04 1.58E-03 9.93E-05 1.32E-03 Thyroid 7.5 mrem 1.26E-04 1.68E-03 1.00E-04 1.34E-03 i Kidney 7.5 mrem 1.19E-04 1.58E-03 9.93E-05 1.32E-03 i Lung 7.5 mrem 1.19E-04 1.58E-03 9.93E-05 1.32E-03 :
GI-LLI 7.5 mrem 1.19E-04 1.58E-03 9.93E-05 1.32E-03 l
I CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM LIMIT ' LIMIT ,
Bone 15.0 mrem 8.15E-07 5.43E-06 ;
Liver 15.0 mrem 4.20E-04 2.80E-03 I T. Body 15.0 mrem 4.20E-04 2.80E-03 )
Thyroid 15.0 mrem 4.29E-04 2.86E-03 Kidney 15.0 mrem 4.20E-04 2.80E-03 i Lung 15.0 mrem 4.20E-04 2.80E-03 !
GI-LLI 15.0 mrem 4.20E-04 2.80E-03 i
7 l
i h
77
r~
TABLE 2-7B VOGTLE ELECTRIC GENERATING PLANT ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JANUARY,1994 THROUGH JUNE,1994 UNIT 2 CUMULATIVE DOSE PER QUARTER .
ORGAN ODCM UNITS QUARTER % OF QUARTER % OF LIMIT 1 ODCM 2 ODCM LIMIT LIMIT Bone 7.5 mrem 2.85E-07 3.80E-06 2.49E-06 3.31 E-05 Liver 7.5 mrem 1.14E-06 1.52E-05 8.06E-05 1.07E-03 T. Body 7.5 mrem 1.14E-06 1.52E-05 8.05E-05 1.07E-03 Thyroid 7.5 mrem 3.19E-06 ~ 4.26E-05 1.25E-04 1.67E-03 Kidney 7.5 mrem 1.15E-06 1.53E-05 8.06E-05 1.08E-03 Lung 7.5 mrem 1.15E-06 1.54E-05 8.06E-05 1.07E-03 :
GI-LLI 7.5 mrem 1.14E-06 1.52E-05 8.04E-05 1.07E-03 i
CUMULATIVE DOSE PER YEAR ORGAN ODCM UNITS YEAR TO DATE % of ODCM i LIMIT LIMIT I Bone 15.0 mrem 2.77E-06 1.85E-05 Liver 15.0 mrem 8.17E-05 5.45E-04 '
T. Body 15.0 mrem 8.16E-05 5.44E-04 Thyroid 15.0 mrem 1.28E-04 8.56E-04 Kidney 15.0 mrem 8.18E-05 5.45E-04 Lung 15.0 mrem 8.18E-05 5.45E-04 GI-LLI 15.0 mrem 8.16E-05 5.44E-04 l i
l 78
. - _ = . - . _ _ - . .. .-
i t
i TABLE 2-7BB l VOGTLE ELECTRIC GENERATING PLANT \
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM JULY,1994 THROUGH DECEMBER,1994 l 1
UNIT 2 ,
CUMULATIVE DOSE PER QUARTER ORGAN ODCM UNITS QUARTER % OF QUARTER % OF 4 LIMIT 3 ODCM 4 ODCM !
LIMIT LIMIT Bone 7.5 mrem 5.00E-07 . 6.67E-06 5.54E-06 7.39E-05 !
Liver 7.5 mrem 2.50E-05 3.33E-04 1.94E-05 2.59E-04 j T. Body 7.5 mrem 2.50E-05 3.33E-04 1.94E-05 2.59E-04 l Thyroid 7.5 mrem 2.69E-05 ' 3.59E-04 2.05E-05 2.74E-04 i Kidney 7.5 mrem 2.50E-05 3.33E-04 1.94E-05 2.59E-04 I Lung 7.5 mrem 2.50E-05 3.33E-04 1.97E 2.63E-04 l Gl-LLI 7.5 mrem 2.50E-05 3.33E-04 1.94E-05 2.59E-04 4
CUMULATIVE DOSE PER YEAR 1 ORGAN ODCM UNITS YEAR TO DATE % of ODCM ]
LIMIT LIMIT 'l Bone 15.0 mrem 8.81 E-06 5.88E-05 'l Liver 15.0 mrem 1.26E-04 8.40E-04 T. Body 15.0 mrem 1.26E-04 8.40E-04 Thyroid 15.0 mrem 1.76E-04 1.17E-03 Kidney 15.0 mrem 1.26E-04 8.41 E-04 Lung 15.0 mrem 1.26E-04 8.43E-04 Gl-LLI 15.0 mrem 1.26E-04 8.39E-04 l
79
TABLE 2-8 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES VOGTLE ELECTRIC GENERATING PLANT .
JANUARY,1994 THROUGH DECEMBER,1994 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 l 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 i Ce-141 8.62E-15* uCi/cc Ce-144 2.77E-14
- uCi/cc Sr-89 1.00E-13 uCi/cc Sr-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.
80
4 3.0 Solid Wasto '
.i
'3.1 Regulatory Limits /ODCM i
. The ODCM Limits presented in this section are for Unit 1 and Unit 2 and are :
stated in part.
l
-- 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 . ~
Process Control Program to meet shipping and transportation requirements during the transit, and disposal site requirements when received at the disposal !
site '
3.1.2 Reporting Requirements !
6.8.1.4 The Annual Radioactive Effluent Release Report covering the operation j of the units during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive 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 I to 10 CFR, Part 50. !
i 3.1.3 Process Control Program (PCP) i 6.12.2 i i
Licensee -initiated changes to the PCP .
I Shall be submitted to the Commission in the Radioactive Effluent Release Report j for the period in which the change (s) was made. ;
c There were no changes to the PCP in 1994.
]
y l
t 81
s 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 changes to the Vogtle Electric Generating Plant ODCM for the period January 1,1994 through December 31,1994.
The VEGP ODCM was revised and approved by the General Manager VEGP to be implemented Jan.1,1994. The major changes include implementation of 10 CFR 20 changes and format changes for the manual itself. A copy of the revised ODCM is attached as Attachment 1 to this report. !
i 4.0 of ODCM The Radiological Environmental Monitoring Program shall be conducted as specified in ODCM 4.1.1 and 4.1.2.
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. l In these instances, suitable alternative media and locations may be chosen for the particular pathway in questions and appropriate substitutions, if available, will be made within 30 days in the Radiological Environmental Monitoring Program given in the ODCM."
Pursuant to specification 6.13, submit in the next Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) 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 .
i The Action Statement for this requirement states in part:
82
]
i 1
- 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 Annual Radioactive Effluent Release Report. ;
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 location of concern within the site boundary are the Visitors Center :
and Plant Wilson. The activities at the Visitor Center consists of the .
occasional attendance at meetings and/or short visits for informational purposes. The activity at Plant Wilson consists of regular employment. .
There will be no radiation dose at these locations due to radioactive '
liquid effluents . Delineated in Table 4-1 for each of these locations I are the values of the basic data assumed in the dose assessment due .
to radioactive gaseous effluents. Listed in this table are: The distance 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,2-38, 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:
i 83 l j
P i
QUARTER 1 2 3 4 Mixed Mode 5.02E+01 6.36E+01 6.54E+01 4.43E+01 -
Ground Mode 0.00E+00 0.00E+00 6.00E-03 3.30E-02 The maximum doses in units of mrem accumulated by an individual MEMBER i OF THE PUBLIC due to their activities inside the site boundary during the reporting period were assessed to be as follows:
VISITOR CENTER Quader l and 2- Quader 3 and 4 Total Body 1.34E-07 3.39E-07 .
(Direct Radiation from Plume)
PLANT WILSON Quarter 1 and 2 Quarter 3 and 4 ,
Total Body 1.65E-05 4,15E-05 (Direct Radiation from Plume)
VISITOR CENTER Quader1 Quader 2 Quader 3 Quader 4 i
Maximum Organ 2.29E-07 7.25E-07 6.93E-07 3.10E-07 (Thyroid)
(Inhalation Ground Plane)
PLANT WILSON Quader 1 Quader 2 Quader 3 Quader 4 Maximum Organ 2.94E-05 8.99E-05 8.80E-05 4.13E-05 (Thyroid) 1 (Inhalation Ground Plane) l 84 l
m- ,
I f
f TABLE 3 EPPLUENT AND WASTE DISPOSAL SERNANNUAL REPORT (YEAR) -
SOLIO WASTE AND 1RRADIATED PUEL SHIPMENTS l 1
JANUARY 1,1994 THROUGH JUNE 30,1994 A. SOLIO WASTE SHIPPED OPPSITE POR BURIAL OR DISPOSAL (Not irredleted Puet) ,
- 1. Type of weste Unit 6-month Est. Total Period Error, %
e Spent rooms. fdter sludges. owsporator m3 9 871E+00 I bottorre. etc 0 1803E+01 10E+01 b Dry compressible weste. contammsted m3 1772E+01 equip etc. O' 2.149E*01 4 OE+01 e Irradated components, control m3 rods. etc Cs NONE NONE d Other(describe) m3 C6 NONE NONE
- 2. Est6mde of mejor muc16de composit6on (by type of weste),
a F&55 % 5192E+01 Co-60 % 1067E+01 Ni43 % 1328E+01 All others % 2 392E+01 b Fe-55 % 6229E+01 Co 58 % 1977E+01 NL63 % 7 704E+00 AA others % 2 026E+01
- c. t&A % N/A N/A % N/A N/A % N/A d N/A % N/A MA % N/A N/A % N/A
- 3. Solid Weste Disposition Number of Mode of pi Pnents ironsporteuen poet 6neuen 2 Tractor / Trader / Shielded Cesk Chem-Nuclear Systems, Inc. Bemwell. S C.
4 Tractor / Trader Scent #. Ecology Group Ook Ridge TN B. IRRADLATED PUEL SHIPMENTS (Dispor6en)
Number of Mode of Pipments Ironsportdion post 6 notion None None None ADDITIONAL INFORMATION REQUIRED BY TECH SPECS:
PJ M .No., Westpfless Jrtfamteme! $$PPL"2 gens $ 1helion_A.2*Jt91 RWS44401 A . Stable Type A LSA NONE RWS-94-002 A 8 table Type A LM NONE RVRS-94401 A . Unstable Steng ight LSA NONE RVRS44402 A . Unstate Stong Tght LSA NONE RVRS 94403 A - Unstatdo Ston0Tght LSA NONE RVRS44404 A Unstable Stang Tght LQ NONE 85
w_._.__-
TAELR 3 ;
t EPPLUENT ANO WASTE DetPotAL SERNANNUAL REPORT (YEAR) i scuo waste ANo iRRAceATED PUEL sNetsENTs t
. JULY 1,1994 THROUGH DECEMBER 31,1994.
A. 8000 WASTE SHIPPED OPPS8?E POR DURIAL OR DISPotAL (Not irred6sted Pust)
- 1. Tsye of weste Unst seenth Est. Total -
Period Error, % ' 'f a Spent resins, flitar sludges, suporetor m3 1481E+01 i bottoms etc Q 2998E+02 10E+01 !
b Dry compressitde waste, contammetod m3 8 977E+00 equip. etc 0 9 327E 02 4 OE+01
- c. Irradiated components, control m3 rods. etc. O NONE NONE j d Other(describe) m3 -(
0 NONE NONE !
I B
L Rettmate of make nuclide e "' (bytype of waste). :i e Fe 55 % 4 401E+00 Co 80 % 1342E+01 4 43 % 3 588E+01 f M ethers % 4 830E+01 !
b Fe-55 % 5 381E+01 !
Co-58 % 1423E+01 [
N#43 % 8 885E+00 I M others % 2 309E+01 c N/A % N/A :!
N/A % N/A N/A % N/A !
- d. N/A % N/A N/A %- N/A 1 N/A % N/A l
- 3. se46d weste 06sposet6en ,
k Number of Geode of 8884Peents ' Ireneportettee postnat6on .,
j 3 Tractor / Trailer /Shelded Cash Chem-Nuclear Systems. inc Barnwell, S.C. l 8 Tractor / Trader. Scentific Ecology Group Oak Rulge TM j 1 Tractor / Trader / Shielded Cask . Sceentific Ecology Group Oak Rutge TM 3 i
I S. litRADIATED PUEL SHIPtettfTS(Dispostion) ;
Number of htodo of Shipments I.rangottet6cn postlnation I f'
None None None I
t i
.f ADDITIottAL INFORetATiott REQUIRED SY TECH SPECS:
l ghyment.No WesttQ1pg lyptCeteLnef gh_ippinaQast gol@ cation Agorg RWS44403 A - Statwo Type A LSA NONE RWS 94404 A Stable Type A LSA NONE RWS94-005 A Stable Type A LSA NONE j i
1 l
RVRS 64405 A Unstatne Stang Taght LSA NONE I i
RVRS-94406 A - Unstable Stong Tght LSA NONE l RVRS 94407 A - Unstatne Ston0 Tight LQ NONE RVR$44-008 A- Unstable Stang Tght LSA NONE RVRS D4409 A Unstable Stong Tght LSA NONE RVRS S4410 A - Unstable Stong Tight LSA NONE RVRS44 011 A Unstatdo Stong Tight LSA NONE 86 1
.i
e I
Table 4-1 Vogtle Electric Generating Plant ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT - 1994 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Starting: 01-Jan-1994 Ending: 30-Jun-1994 Location Name Visitor Center Plant Wilson Distance (meters) 4.47e+02 1420 Sedor SE ESE X/Q(sec/m3) (1) 5.93E-06 9.45E-07 :
Depleted X/Q(sec/m3) (2) 5.58E-06 8.34E-07 D/Q(m2) (1) 2.28E-08 4.20E-09 X/Q(Sec/m3) (2) 7.12E-07 1.76E-07 Depleted X/Q(sec/m3) (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 i VISITOR CENTER UNITS QTR 1 QTR2 Total Q1 & QTR3 QTR4 Total Q3 &
Q2 Q4 i Total Body mrem 6.27E-08 7.17E-08 1.34E-07 3.23E-07 1.55E-08 3.39E-07 Dose Organ l Bone mrem 6.89E-08 8.61 E-08 1.55E-07 3.26E-08 3.02E-08 3.57E-06 Liver mrem 2.23E-07 6.13E-07 8.36E-07 6.72E-07 3.05E-07 9.77E-06 _
Tbody mrem 2.23E-07 6.12E-07 8.36E-07 6.72E-07 3.05E-07 9.77E ,
Thyroid mrem 2.29E-07 7.25E-07 9.53E-07 6.93E-07 3.10E-07 1.00E-06 Kidney mrem 2.23E-07 6.13E-07 8.36E-07 6.72E-07 3.05E-07 9.77E-07 ,
Lung mrem 2.23E-07 6.13E-07 8.36E-07 6.72E-07 3.05E-07 9.78E-07 GI-LLI mrem 2.23E-07 6.12E-07 8.35E-07 6.72E-07 3.05E-07 9.77E-07 PLANT WILSON ;
UNITS QTR 1 QTR2 Total Q1 & QTR3 QTR4 Total Q3 &
Q2 Q4 Total Body mrem 7.70E-06 8.78E-06 3.96E-05 1.90E 06 4.09E-05 1.65E-05 Dose _,
Organ Bone mrem 8.54E-06 1.09E-05 1.95E-05 4.04E-05 4.55E-06 4.50E-05 :
Liver mrem 2.89E-05 8.06E-05 1.10E-04 8.61 E-05 4.09E-05 1.27E-04 Tbody mrem 2.89E-05 8.06E-05 1.10E-04 8.61 E-05 4.09E-05 1.27E-04 Thyroid mrem 2.94E-05 8.99E-05 1.19E-04 8.80E-05 4.13E-05 1.29E-04 l Kidney mrem 2.89E-05 8.06E-05 1.10E-04 8.61 E-05 4.09E-05 1.27E-04 Lung mrem 2.89E-05 8.06E-05 1.10E-04 8.62E-05 4.09E-05 1.27E-04 GI-LLI mrem 2.89E-05 8.06E-05 1.10E-04 8.61E-05 4.09E-05 1.27E-04 87 3 I
1 l
l l
1 l
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 1994. j Solid Radwaste System ,
There were no major changes to the solid radwaste system in 1994.
Liquid Radwaste System ;
There were no major changes to the Liquid Radwaste Treatment System in 1994.
7.0 Meteorological Data 6.8.1.4 states in part: .
l 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 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 provided to the NRC upon request. ;
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 time specified in ODCM 2.1.1.2 and 3.1.1.2 respectively "
88 .
k-
l l
l l
I J
Inoperable Tech Spec. monitors are tracked on Limiting Condition of Operation (LCO) forms. The operators declare equipment operable and inoperable and monitors are considered inoperable if there are open LCO's for that monitor.
8.1 The LCO's initiated do not have to be reported for this report period !
since the LCO's initiated were closed within 30 day period. ,
9.0 Tanks Exceeding Curie Content Limits .
The Annual Radioactive Effluent Release Reports shall also include the following " ..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 . .
l 1
There were four outside temporary liquid tanks for radioactive liquids ,
during this reporting period. None of these tanks exceeded the Technical Specifications limit. Likewise, none of the plant's waste gas decay tanks ,
exceeded the Technical Specifications limit. !
t i
i s
I 89 l I
A
,,