ML021420334

Part B - Vogtle Electric Generating Plant - 2001 Annual Report

ML021420334
Person / Time
Site:	Vogtle
Issue date:	05/13/2002
From:	Beasley J Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML021420334 (182)

Text

VEGP ODCM CHAPTER 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 LIMITS OF OPERATION The following limits are the same for both units at the site. Thus, a single program including monitoring, land use survey, and quality assurance serves both units.

4.1.1 Radiological Environmental Monitoring The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 4-1.

4.1.1.1 Applicability This control applies at all times.

4.1.1.2 Actions 4.1.1.2.1 With the REMP not being conducted as specified in Table 4-1, submit to the Nuclear Regulatory Commission (NRC), in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations from the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, unavailability, inclement weather, equipment malfunction, or other just reasons. If deviations are due to equipment malfunction, efforts shall be made to complete corrective action prior to the end of the next sampling period.

4.1.1.2.2 With the confirmed1 measured level of radioactivity as a result of plant effluents in an environmental sampling medium specified in Table 4-1 exceeding the reporting levels of Table 4-2 when averaged over any calendar quarter, submit within 30 days a special report to the NRC.

The special report shall identify the cause(s) for exceeding the limit(s) and define the corrective action(s) to be taken to reduce radioactive effluents so that the potential annual dose to a MEMBER OF THE PUBLIC is less than the calendar year limits of Sections 2.1.3, 3.1.3, and 3.1.4. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in the special report.

When more than one of the radionuclides in Table 4-2 are detected in the sampling medium, this report shall be submitted if:

concentration(1) + concentration (2) +... >Ž1.o reportinglevel (1) reporting level (2)

When radionuclides other than those in Table 4-2 are detected and are the result of plant effluents, this special report shall be submitted if the potential annual dose to a MEMBER OF THE Defined as confirmed by reanalysis of the original sample, or analysis of a duplicate or new sample, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis.

4-1 Rev. 18

VEGP ODCM PUBLIC is equal to or greater than the calendar year limits stated in Sections 2.1.3, 3.1.3, and 3.1.4. This special report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be described in the Annual Radiological Environmental Operating Report. The levels of naturally-occurring radionuclides which are not included in the plant's effluent releases need not be reported.

4.1.1.2.3 If adequate samples of milk, or during the growing season, grass or leafy vegetation, can no longer be obtained from one or more of the sample locations required by Table 4-1, or if the availability is frequently or persistently wanting, efforts shall be made: to identify specific locations for obtaining suitable replacement samples; and to add any replacement locations to the REMP given in the ODCM within 30 days. The specific locations from which samples became unavailable may be deleted from the REMP. Pursuant to Technical Specification 5.5.1, documentation shall be submitted in the next Radioactive Effluent Release Report for the change(s) in the ODCM, including revised figure(s) and table(s) reflecting the changes to the location(s), with supporting information identifying the cause of the unavailability of samples and justifying the selection of any new location(s).

4.1.1.2.4 This control does not affect shutdown requirements or MODE changes.

4.1.1.3 Surveillance Requirements The REMP samples shall be collected pursuant to Table 4-1 from the locations described in Section 4.2, and shall be analyzed pursuant to the requirements of Table 4-1 and Table 4-3.

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.

Program changes may be initiated based on operational experience.

Analyses shall be performed in such a manner that the stated MINIMUM DETECTABLE CONCENTRATIONs (MDCs) will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may render these MDCs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

4.1.1.4 Basis The REMP required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways, and for those radionuclides, which lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the plant operation. The REMP implementsSection IV.B.2, Appendix I, 10 CFR 50, and thereby supplements the radiological effluent monitoring program by measuring concentrations of radioactive materials and levels of radiation, which may then be compared with those expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The detection capabilities required by Table 4-3 are within state-of-the-art for routine environmental measurements in industrial laboratories.

Rev. 18 4-2 4-2 Rev. 18

-C Exposure Number of Representative Samples and Sample Sampling and Type and Pathway Locations(I) Collection Frequency of and/or Sample Frequency Analysis 0~

1. DIRECT RADIATION -3L Direct Radia- Thirty-six or more routine monitoring stations, either Quarterly. Gamma dose tion(2) with two or more dosimeters, or with one instrument quarterly. 0.

for measuring and recording dose rate continuously, (Q) placed as follows: 0 m

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 3 sector at approximately 5 miles from the site. 0 The balance of the stations to be placed in special C,, interest areas such as population centers, nearby 2.

residences, schools, and in one or more areas to 0 serve as control stations.

2. AIRBORNE 3o Radioiodine Samples from 5 or more locations as follows: Continuous Radioiodine 3u and Partic- sampler operation Canister: 1-131 ulates Three or more samples from close to the three site with sample analysis weekly.

boundary locations, in different sectors. collection weekly, or more frequently Particulate One sample from the vicinity of a community having if required by dust Sampler: Gross the highest calculated annual average ground-level loading, beta radioactivity D/Q. analysis following filter change, and One sample from a control location, as, for example, gamma isotopic m CD a population center 10 to 20 miles distant and in the analysis of

.< composite (by 5.,I least prevalent wind direction.

0o location) 0"9 quarterly.(3)(4) 0)

Exposure Number of Representative Samples Sampling and Collection Type and Frequency of Pathway and Sample Locations(1) Frequency Analysis and/or Sample

3. WATERBORNE Surface(5) One sample upstream. Composite sample over 1- Gamma isotopic analysis month period.(6) monthly; composite for One sample downstream. tritium analysis quarterly.(4)

Drinking Two samples at each of the one to Composite sample of river 1-131 analysis on each three nearest water treatment plants water near intake at each sample when the dose that could be affected by discharges water treatment plant over calculated for the from the facility. 2-week consumption of the water period when 1-131 analysis is greater than 1 mrem per Two samples at a control location, is performed, monthly year. Composite for gross composite otherwise; and beta and gamma isotopic grab sample of finished analyses monthly.

water at each water Composite for tritium treatment plant every 2 analysis quarterly.(4)(7) weeks or monthly, as appropriate.(6)

Sediment from One sample from downstream area Semiannually. Gamma isotopic analysis Shoreline with existing or potential recreational semiannually.(4) value. I m

CD 5,

0 0

K

0':D 0C')

4. INGESTION 0 33 Milk Samples from milking animals in three locations within 3 Semimonthly. Gamma miles distance having the highest dose potential; if there are isotopic none, then one sample from milking animals in each of three analysis semi monthly.(4)(8) SD areas between 3 and 5 miles distance where doses are calculated to be greater than 1 mrem per year.(7) 9.

0 One sample from milking animals at a control location about 10 miles distant or beyond, and preferably in a wind 0) direction of low prevalence.

Fish At least one sample of any commercially and recreationally Semiannually. Gamma important species in vicinity of plant discharge area. isotopic analyses on 0 m

01 At least one sample of any species in areas not influenced edible by plant discharge. portions.(4) "~13 CD 00 At least one sample of any anadromous species in vicinity of During spring Gamma plant discharge. spawning isotopic season, analyses on edible portion.(4)

Grass or One sample from two onsite locations near the site Monthly during Gamma 3 t

Leafy boundary in different sectors. growing season. isotopic.(4)(8) 0 CD Vegetation k9 One sample from a control location about 15 miles distant. Monthly during Gamma growing season. isotopic.(4)(8) m CD

.8o 0 "0

0o

TABLE NOTATIONS CD C'D (1) For each sample location in this table, specific parameters of distance and direction sector from a point midway betw 8 the center of the two reactors, and additional description where pertinent, are provided in Table 4-4, and in Figure 4-1 through Figure 4-4 of this ODCM.

(2) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously, n o be used in place of or in addition to integrating dosimeters. For the purpose of this table, a thermoluminescent dosirr .

(TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimete 0.

Film badges shall not be used as dosimeters for measuring direct radiation.

(3) 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 all m for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yea <

mean of control samples, gamma isotopic analysis shall be performed on the individual samples. _

3 (4) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

0 (5) The upstream sample shall be taken at a distance beyond significant influence of the discharge. The downstream 2.

sample shall be taken in an area beyond but near the mixing zone. :3 (6) Composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the composi -u period (e.g., monthly) in order to assure obtaining a representative sample.

(7) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the 3 ODCM. 8 (8) Ifgamma isotopic analysis is not sensitive enough to meet the required MDC for 1-131, a separate analysis for 1-131' be performed. CD 0.

CD m 5 0

-U 0

--i C

Water Airborne Fish Milk Grass or Leafy Analysi Analysis Gses (L)iM3 Particulate or (pCi/kg, wet) (pCi/L) Vegetation

_pikwt LIGases (pCi/mn3 ) / _________ 1 (pCi/kg, wet) j H-3 2 E+4a Mn-54 1 E+3 3 E+4 Co Fe-59 4 E+2 1 E+4 CD Co-58 1 E+3 3 E+4 CD Co-60 3 E+2 1 E+4 Zn-65 3 E+2 2 E+4

_<5.

Zr-95 4 E+2 7 E+2 0 Nb-95 1-131 2 E+Ob 9 E-1 3 E+O 1 E+2 Cs-134 3 E+1 1 E+1 1 E+3 6 E+1 1 E+3 CD 0

Cs-137 5 E+1 2 E+1 2 E+3 7 E+1 2 E+3 0 3 E+2 0 Ba-140 2 E+2

_3.

La-140 1 E+2 4 E+2 0

B a

a. This is the 40 CFR 141 value for drinking water samples. If no drinking water pathway exists, a value of 3 E+04 pCi/L may be used.

b. If no drinking water pathway exists, a value of 20 pCi/L may be used.

Cn CD

3 "SD m CD OD "0

0 9b

H Minimum Detectable Concentration IMDC)a C.

Water Airborne Fish Milk Grass or Leafy Sediment Analysis (pCi/ Particulate or3 (pCi/kg, wet) (pCi/L) (pgi/kiwet (pCi/kg, wet)

(pCi/kg, dry)

Gases (pCi/m )

Gross Beta 4 E+0 1 E-2 H-3 2 E+3b C (D

cn Mn-54 1.5 E+1 1.3 E+2 2.6 E+2 0 Fe-59 3 E+1 0.

Co-58, Co-60 1.5 E+1 1.3 E+2 Zn-65 3 E+1 2.6 E+2 2.

Zr-95 3 E+1 3C Nb-95 1.5 E+1 1-131 1 E+0c 7 E-2 1 E+0 6 E+1 CD CD

-0 Cs-134 1.5 E+1 5 E-2 1.3 E+2 1.5 E+1 6 E+1 1.5 E+2 do 8 E+1 1.8 E+2 C)

Cs-137 1.8 E+1 6 E-2 1.5 E+2 1.8 E+1 0~

6 E+1 6 E+1 oi° Ba-140 0 La-140 1.5 E+1 1.5 E+1 CD

a. See the definition of MINIMUM DETECTABLE CONCENTRATION in Section 10.1. Other peaks which are 0 measurable and identifiable as plant effluents, together with the radionuclides in this table, shall be analyzed and reported in accordance with Section 7.1.

b. If no drinking water pathway exists, a value of 3 E+3 pCi/L may be used.

c. If no drinking water pathway exists, a value of 1.5 E+1 pCi/L may be used.

m

.D G) 0 OD 00

VEGP ODCM 4.1.2 Land Use Census A land use census shall be conducted and shall identify the following within a distance of 5 miles in each of the 16 meteorological sectors: the location of the nearest milk animal,' the nearest permanent residence, and the nearest garden of greater than 500 square feet producing broad leafy vegetation. Land within the Savannah River Site is excluded from this census.

4.1.2.1 Applicability This control applies at all times.

4.1.2.2 Actions 4.1.2.2.1 With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than values currently being calculated in accordance with Section 3.4.3, identify the new location(s) in the next Radioactive Effluent Release Report.

4.1.2.2.2 With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 4.1.1, add the new location(s) to the REMP within 30 days if samples are available. The sampling location, excluding control station location(s), having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from the REMP if new sampling locations are added. Pursuant to Technical Specification 5.5.1 submit in the next Radioactive Effluent Release Report any change(s) in the ODCM, including the revised figure(s) and table(s) reflecting any new location(s) and information supporting the change(s).

4.1.2.2.3 This control does not affect shutdown requirements or MODE changes.

4.1.2.3 Surveillance Requirements The land use census shall be conducted annually, using that information which will provide good results, such as a door-to-door census, a visual census from automobile or aircraft, consultation with local agriculture authorities, or some combination of these methods, as feasible. Results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

4.1.2.4 Basis This control is provided to ensure that changes in the use of UNRESTRICTED AREAS are identified and that modifications to the REMP are made if required by the results of this census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

2 Restricting the census to gardens of greater than 500 ft provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/y) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the Defined as a cow or goat that is producing milk for human consumption.

4-9 Rev. 18

VEGP ODCM following assumptions were made: (1) 20 percent of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage) and (2) a vegetation yield of 2 kg/m 2 was obtained.

4.1.3 Interlaboratory Comparison Program Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which satisfies the requirements of Regulatory Guide 4.15, Revision 1, February, 1979.

4.1.3.1 Applicability This control applies at all times.

4.1.3.2 Actions With analyses not being performed as required by Section 4.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report.

This control does not affect shutdown requirements or MODE changes.

4.1.3.3 Surveillance Requirements A summary of the results obtained as part of the required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

4.1.3.4 Basis The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2, Appendix 1,10 CFR 50.

Rev. 18 4-10 4-10 Rev. 18

VEGP ODCM 4.2 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Table 4-4, and Figure 4-1 through Figure 4-4 specify the locations at which the measurements and samples are taken for the REMP required by Section 4.1.1.

Rev. 18 4-11 Rev. 18

VEGP ODCM Table 4-4. Radiological Environmental Monitoring Locations Location Descriptive Location Direction Distance Sample Number (miles) Type(l) 1 River Bank N 1.1 D 2 River Bank NNE 0.8 D 3 Discharge Area NE 0.6 A 3 River Bank NE 0.7 D 4 River Bank ENE 0.8 D 5 River Bank E 1.0 D 6 Plant Wilson ESE 1.1 D 7 Simulator Building SE 1.7 D,V,A 8 River Road SSE 1.1 D 9 River Road S 1.1 D 10 Met Tower SSW 0.9 A 10 River Road SSW 1.1 D 11 River Road SW 1.2 D 12 River Road WSW 1.2 D,A 13 River Road W 1.3 D 14 River Road WNW 1.8 D 15 Hancock Landing Road NW 1.5 D,V 16 Hancock Landing Road NNW 1.4 D,A 17 Savannah River Site, River Road N 5.4 D 18 Savannah River Site, D Area NNE 5.0 D 19 Savannah River Site, Road A.13 NE 4.6 D 20 Savannah River Site, Road A.13.1 ENE 4.8 D 21 Savannah River Site, Road A.17 E 5.3 D 22 River Bank Downstream of Buxton ESE 5.2 D Landing 23 River Road SE 4.6 D 24 Chance Road SSE 4.9 D 25 Chance Road near Highway 23 S 5.2 D 26 Hihway 23 and Ebenezer Church SSW 4.6 D R4-. Rev.I1 4-12 Rev. 18

VEGP ODCM Table 4-4 (contd). Radiological Environmental Monitoring Locations Location Descriptive Location Direction Distance Sample Number I (miles) Type(1 )

27 Highway 23, opposite Boll Weevil SW 4.7 D Road 28 Thomas Road WSW 5.0 D 29 Claxton-Lively Road W 5.1 D 30 Nathaniel Howard Road WNW 5.0 D 31 River Road at Allen's Chapel Fork NW 5.0 D 32 River Bank NNW 4.7 D 35 Girard SSE 6.6 D,A 36 GPC Waynesboro Operating WSW 13.9 D,A Headquarters 37 Substation; Waynesboro, GA WSW 16.7 D,V 43 Employees Recreation Area SW 2.2 D 47 Oak Grove Church SE 10.4 D 48 McBean Cemetery NW 10.2 D 51 SGA School; Sardis, GA S 11.0 D 52 Oglethorp Substation; SW 10.7 D Alexander, GA 80 Augusta Water Treatment Plant NNW 29.0 W(2) 81 Savannah River N 2.5 F(3),S(4) 82 Savannah River (RM 151.2) NNE 0.8 R 83 Savannah River (RM 150.4) ENE 0.8 R,S(4) 84 Savannah River (RM 149.5) ESE 1.6 R Savannah River ESE 4.3 F(3) 85 Beaufort - Jasper Water Treatment SE 76.0 W(5 )

87 Plant; Beaufort, SC 88 Cherokee Hill Water Treatment SSE 72.0 W(6)

Plant; Port Wentworth, GA 98 W.C. Dixon Dairy SE 9.8 M 99 Boyceland Dairy W 20.9 M Rev. 18 4-13 4-13 Rev. 18

VEGP ODCM Table 4-4 (cont.) Radiological Environmental Monitoring Locations TABLE NOTATIONS (1) Sample Types:

A - Airborne Radioactivity D - Direct Radiation F - Fish M- Milk R - River Water S - River Shoreline Sediment W - Drinking Water (at water treatment plant)

V - Vegetation (2) The intake for the Augusta Water Treatment Plant is located on the Augusta Canal. The entrance to this 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 only 0.1 mile from the river (across land).

(3) About 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 RMs 144 and 149.4 for downriver collections.

(4) Sediment is collected at locations with existing or potential recreational value. High water shifting of the river bottom or other reasons could cause a suitable location for sediment collection to become unavailable or unsuitable. Thus, a stretch of river between RM 148.5 and 150.5 is designated for downriver sediment collections, while a stretch between RM 153 and 154 is designated for upriver collections. In practice, collections are normally made at RM 150.2 for downriver collections and at RM 153.3 for upriver collections.

(5) The intake for the Beaufort-Jasper 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 from its beginning on the Savannah River.

(6) The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek, which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.

Rev. 18 4-14 4-14 Rev. 18

VEGP ODCM Figure 4-1. Terrestrial Stations Near Site Boundary Rev. 18 4-15 4-15 Rev. 18

VEGP ODCM Figure 4-2. Terrestrial Stations and Aquatic Stations, 0-5 Miles Rev. 18 4-16 4-16 Rev. 18

VEGP ODCM Figure 4-3. Terrestrial Stations Beyond 5 Miles Rev. 18 4-17 4-17 Rev. 18

VEGP ODCM Figure 4-4. Drinking Water Stations Rev. 18 4-18 4-18 Rev. 18

VEGP ODCM CHAPTER 5 TOTAL DOSE DETERMINATIONS 5.1 LIMIT OF OPERATION In accordance with Technical Specification 5.5.4.j, the dose or dose commitment to any MEMBER OF THE PUBLIC over a calendar year, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

5.1.1 Applicability This limit applies at all times.

5.1.2 Actions With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 2.1.3, 3.1.3, or 3.1.4, calculations shall be made according to Section 5.2 methods to determine whether the limits of Section 5.1 have been exceeded. If these limits have been exceeded, prepare and submit a special report to the Nuclear Regulatory Commission within 30 days, which defines the corrective actions to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Section 5.1 and includes the schedule for achieving conformance with the limits of Section 5.1. This special report, as defined in 10 CFR 20.2203, shall also include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources (including all effluent pathways and direct radiation) for the calendar year that includes the release(s) covered by this report. This special report shall also describe the levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the limits of Section 5.1, and if the release condition resulting in violation of the provisions of 40 CFR 190 has not already been corrected, the special report shall include a request for variance in accordance with the provisions of 40 CFR 190 and including the specified information of 40 CFR 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

This control does not affect shutdown requirements or MODE changes.

5.1.3 Surveillance Requirements Cumulative dose contributions from liquid and gaseous effluents and from direct radiation shall be determined in accordance with Section 5.2. This requirement is applicable only under the conditions set forth above in Section 5.1.2.

5.1.4 Basis This control is provided to meet the dose limitations and reporting requirements of 40 CFR 190.

The control requires the preparation and submittal of a special report whenever the calculated doses from plant radioactive effluents exceed the limits of Section 5.1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design 5-1 Rev. 18

VEGP ODCM objectives of Appendix I and if direct radiation doses from the units, such as direct exposure from outside storage tanks, are kept small. The special report will describe a course of action which should result in the limitation of dose to a MEMBER OF THE PUBLIC for a calendar year to within the 40 CFR 190 limits. For the purposes of the special report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible with the exception that dose contributions from other uranium fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the special report with a request for variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(a)(4),

is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation as addressed in other sections of this ODCM. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle.

Rev. 18 5-2 Rev. 18

VEGP ODCM 5.2 DEMONSTRATION OF COMPLIANCE There are no other uranium fuel cycle facilities within 5 miles of the plant site. Therefore, for the purpose of demonstrating compliance with the limits of Section 5.1, the total dose to a MEMBER OF THE PUBLIC in the vicinity of the plant site due to uranium fuel cycle sources shall be determined as follows:

Dn = DL + DG + DD + DN (5.1) where:

D= the total dose or dose commitment to the total body or organ k, in mrem.

DL = the dose to the same organ due to radioactivity discharged from the plant site in liquid effluents, calculated in accordance with Section 2.4.1, in mrem.

DG = the dose to the same organ due to non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated for the controlling receptor in accordance with Section 3.4.3, in mrem.

DD = the direct radiation dose to the whole body of an individual at the controlling receptor location, due to radioactive materials retained within the plant site, in mrem. Values of direct radiation dose may be determined by measurement, calculation, or a combination of the two.

DN = the external whole body dose to an individual at the controlling receptor location, due to gamma ray emissions from noble gas radionuclides discharged from the plant site in gaseous effluents, in mrem. DN is calculated as follows (equation adapted from Reference 1, page 22, by re-casting in cumulative dose form):

DN =3.17x1O8X{ (X/Q),vP [K, .Qi (5.2) where:

7 s).

3.17 x le = a units conversion factor: 1 y/(3.15 x W0 i,= the cumulative release of noble gas radionuclide i from release pathway v (IxCi), during the period of interest.

= the total-body dose factor due to gamma emissions from noble gas radionuclide i (mremly)l(tC'rm3), from Table 3-5.

(X/Q)v = annual average relative dispersion factor for release pathway v, at the location of the controlling receptor, from Table 3-7 [s/mrj.

Rev. 18 5-3 5-3 Rev. 18

VEGP ODCM As defined above, DL and DG are for different age groups, while DD and DN are not age group specific. When a more precise determination of DTk is desired, values of DL and DG may be calculated for all four age groups, and those values used in equation (5.1) to determine age group specific values of DTk; the largest value of DTk for any age group may then be compared to the limits of Section 5.1.

5-4 Rev. 18

VEGP ODCM CHAPTER 6 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 6.1 REQUIREMENT FOR CALCULATION To support the reporting requirements of Section 7.2.2.3, an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY shall be performed as specified in Section 6.2, at least once per calendar year.

6.2 CALCULATIONAL METHOD For the purpose of performing the calculations required in Section 6.1, the dose to a member of the public inside the SITE BOUNDARY shall be determined at the locations, and for the receptor age groups, defined in Table 6-1. The dose to such a receptor at any one of the defined locations shall be determined as follows:

Dik =[DA + Ds + Dp]. Fo (6.1) where:

Dik = the total dose to the total body or organ k, in mrem.

DA = the dose to the same organ due to inhalation of non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated in accordance with Section 3.4.3, in mrem. The (X/QLvalue to be used is given for each receptor location in Table 6-1; depleted (X/Q) values may be used in calculations for non noble-gas radionuclides.

Ds = the dose to the same organ due to around plane deposition of non-noble-gas radionuclides discharged from the plant site in gaseous effluents, calculated in accordance with Section 3.4.3, in mrem. The (D/Q) value to be used is given for each receptor location in Table 6-1.

Dp = the external whole body dose due to gamma ray emissions from noble gas radio nuclides discharged from the plant site in gaseous effluents, calculated using equation (5.2), in mrem. The (X/Q) values that are to be used are given for each receptor location in Table 6-1.

F0 = the occupancy factor for the given location, which is the fraction of the year that one individual MEMBER OF THE PUBLIC is assumed to be present at the receptor location [unitless]. Values of F, for each receptor location are included in Table 6-1.

Rev. 18 6-1 6-1 Rev. 18

VEGP ODCM Table 6-1. Attributes of Member of the Public Receptor Locations Inside the Site Boundary Location: Visitors Center, SE at 447 meters Age Group: Child Occupancy Factor: 4.57 x 10-4 (based on 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per year)

Dispersion and Deposition Parameters:

Parameter Ground-Level Mixed-Mode Undepleted (X/Q), s/m3 5.93 E-6 7.12 E-7 Depleted (X/Q), s/r 3 5.58 E-6 6.74 E-7 (D/Q), m 2 2.28 E-8 5.77 E-9 6-2 Rev. 1 6-2 Rev. 18

VEGP ODCM CHAPTER 7 REPORTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 7.1.1 Requirement for Regort In accordance with Technical Specification 5.6.2, the Annual Radiological Environmental Operating Report covering the REMP activities during the previous calendar year shall be submitted before May 15 of each year. (A single report fulfills the requirements for both units.)

The material provided shall be consistent with the objectives outlined in section 4.1 and section 7.1.2 of the ODCM, and in Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

7.1.2 Report Contents The materials specified in the following sub-sections shall be included in each Annual Radiological Environmental Operating Report:

7.1.2.1 Data The report shall include summarized and tabulated results of all REMP samples required by Table 4-1 taken during the report period, in a format similar to that contained in Table 3 of the Radiological Assessment Branch Technical Position (Reference 19); the results for any additional samples shall also be reported. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results; the missing data shall be submitted as soon as possible in a supplementary report. The results for naturally-occurring radionuclides not included in plant effluents need not be reported.

7.1.2.2 Evaluations Interpretations and analyses of trends of the results shall be included in the report, including the following: (as appropriate) comparisons with pre-operational studies, operational controls, and previous environmental reports; and an assessment of any observed impacts of the plant operation on the environment. If the measured level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 4-2 is not the result of plant effluents, the condition shall be described as required by Section 4.1.1.2.2.

7.1.2.3 Programmatic Information Also to be included in each report are the following: a summary description of the REMP; a map(s) of all sampling locations keyed to a table giving distances and directions from a point midway between the centers of the two reactors; the results of land use censuses required by Section 4.1.2; and the results of licensee participation in the Interlaboratory Comparison Program required by Section 4.1.3.

7.1.2.4 Descriptions of Program Deviations Discussions of deviations from the established program must be included in each report, as follows:

7-1 Rev. 18

VEGP ODCM 7.1.2.4.1 If the REMP is not conducted as required in Table 4-1, a description of the reasons for not conducting the program as required, and the plans for preventing a recurrence, must be included in the report.

7.1.2.4.2 If the MDCs required by Table 4-3 are not achieved, the contributing factors must be identified and described in the report.

7.1.2.4.3 If Interlaboratory Comparison Program analyses are not performed as required by Section 4.1.3, the corrective actions taken to prevent a recurrence must be included in the report.

Rev. 18 7-2 7-2 Rev. 18

VEGP ODCM 7.2 RADIOACTIVE EFFLUENT RELEASE REPORT 7.2.1 Requirement for Report In accordance with Technical Specification 5.6.3, the Radioactive Effluent Release Report covering the operation of the units during the previous calendar year of operation shall be submitted in accordance with 10 CFR Part 50.36a. (A single submittal may be made for Units 1 and 2. However, the submittal shall specify the releases of radioactive material in liquid and gaseous effluents from each unit and solid radioactive waste from the site.) The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units. The material provided shall be consistent with the objectives outlined throughout this ODCM and the Process Control Program (PCP) and in conformance with 10 CFR Part 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

7.2.2 Report Contents The materials specified in the following sub-sections shall be included in each Radioactive Effluent Release Report:

7.2.2.1 Quantities of Radioactive Materials Released The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in NRC Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with liquid and gaseous effluent data summarized on a quarterly basis and solid radioactive waste data summarized on a semiannual basis following the format of Appendix B thereof.

Unplanned releases of radioactive materials in gaseous and liquid effluents from the site to UNRESTRICTED AREAS shall be included in the report, tabulated either by quarter or by event.

For gamma emitters released in liquid and gaseous effluents, in addition to the principal gamma emitters for which MDCs are specifically established in Table 2-3 and Table 3-3, other peaks which are measurable and identifiable also shall be identified and reported.

7.2.2.2 Meteorological Data The report 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 of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

7.2.2.3 Dose Assessments The report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from each unit during the previous calendar year. Historical annual average meteorology or the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. This assessment of 7-3 Rev. 18

VEGP ODCM radiation doses shall be performed in accordance with Sections 2.1.3, 2.4, 3.1.3, 3.1.4, 3.4.2, 3.4.3, 5.1, and 5.2.

If a determination is required by Section 5.1.2, the report shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation; this dose assessment must be performed in accordance with Chapter 5. The report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in the report.

7.2.2.4 Solid Radwaste Data For each type of solid waste shipped offsite during the report period, the following information shall be included:

a. Waste volume,

b. Total curie quantity (specify whether determined by measurement of estimate),

c. Principal radionuclides (specify whether determined by measurement or estimate),

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),

e. Type of container (e.g., LSA, Type A, Type B, Large Quantity),

f. Solidification agent (e.g., cement, urea formaldehyde) and

g. Class of solid wastes (as defined by 10 CFR Part 61.)

7.2.2.5 Licensee Initiated Document Changes Licensee initiated changes shall be submitted to the Nuclear Regulatory Commission as a part of or concurrent with the Radioactive Effluent Release Report for the period in which any changes were made. Such changes to the ODCM shall be submitted pursuant to Technical Specification 5.5.1. This requirement includes:

7.2.2.5.1 Any changes to the sampling locations in the radiological environmental monitoring program, including any changes made pursuant to Section 4.1.1.2.3. Documentation of changes made pursuant to Section 4.1.1.2.3 shall include supporting information identifying the cause of the unavailability of samples.

7.2.2.5.2 Any changes to dose calculation locations or pathways, including any changes made pursuant to Section 4.1.2.2.2.

7.2.2.6 Descriptions of Program Deviations Discussions of deviations from the established program shall be included in each report, as follows:

Rev. 18 7-4 7-4 Rev. 18

VEGP ODCM 7.2.2.6.1 The report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why the inoperability of the liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.

7.2.2.6.2 The report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 5.5.12.

7.2.2.7 Major Changes to Radioactive Waste Treatment Systems As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation.1 The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional supplemental information;

c. A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license applications and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to individuals in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license applications and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and

h. Documentation of the fact that the change was reviewed and found acceptable by the PRB.

In lieu of inclusion in the Radioactive Effluents Release Report, this same information may be submitted as part of the annual FSAR update.

7-5 Rev. 18

VEGP ODCM 7.3 MONTHLY OPERATING REPORT This ODCM establishes no requirements pertaining to the Monthly Operating Report.

7.4 SPECIAL REPORTS Special reports shall be submitted to the Nuclear Regulatory Commission as required by Sections 2.1.3.2, 2.1.4.2, 3.1.3.2, 3.1.4.2, 3.1.5.2, 4.1.1.2.2, and 5.1.2.

Rev. 18 7-6 Rev. 18

VEGP ODCM CHAPTER 8 METEOROLOGICAL MODELS The models presented in this chapter are those which were used to compute the specific values of meteorology-related parameters that are referenced throughout this ODCM. These models should also be used whenever it is necessary to calculate values of these parameters for new locations of interest.

Note: Although Plant Vogtle has no pure elevated releases, the sections on elevated-mode calculations (8.1.2 and 8.2.2) are included for convenience in calculating mixed-mode values, and to preserve section number compatibility with the ODCMs of the other Southern Company nuclear power plants.

8.1 ATMOSPHERIC DISPERSION Atmospheric dispersion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations for each gaseous release point are as indicated in Table 3-4.

8.1.1 Ground-Level Releases Relative concentration calculations for ground-level releases, or for the ground-level portion of mixed-mode releases, shall be made as follows:

2=.032 Kr I (8.1) where:

(X/Q)G = the ground-level sector-averaged relative concentration for a given wind direction (sector) and distance (s/m3).

2.032 = (2/7c)" 2 divided by the width in radians of a 22.50 sector, which is 0.3927 radians.

8= the plume depletion factor for all radionuclides other than noble gases at a distance r shown in Figure 8-3. For noble gases, the depletion factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered.

K, = the terrain recirculation factor corresponding to a distance r, taken from Appendix A of Reference 15.

njk = the number of hours that wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed.

N= the total hours of valid meteorological data recorded throughout the period of interest for all sectors, wind speed classes, and stability categories.

8-1 Rev. 18

VEGP ODCM uj= the wind speed (mid-point of wind speed class j) at ground level (m/s).

r= the distance from release point to location of interest (m).

,_= the vertical standard deviation of the plume concentration distribution considering the initial dispersion within the building wake, calculated as follows:

2 "1/2 S zk 21r

= the lesser of OR (8.2)

Xzk 4i3(Uz)

G= the vertical standard deviation of the plume concentration distribution (m) for a given distance and stability category k as shown in Figure 8-1. The stability category is determined by the vertical temperature gradient AT/Az (°C/1 00 m).

3.1416 b= the maximum height of adjacent plant structure (55 m).

8.1.2 Elevated Releases Relative dispersion calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows:

_h2

2. 032K,r[knjkexp 2 uzk (8.3)

(x/Q)E= Nr k UjUzk where:

(X/Q)E = the elevated release sector-averaged relative concentration for a given wind direction (sector) and distance (s/mi).

8k= the plume depletion factor for all radionuclides other than noble gases at a distance r for elevated releases, as shown in Figure 8-4, Figure 8-5, and Figure 8-6. For an elevated release, this factor is stability dependent. For noble gases, the depletion factor is unity. Ifan undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by radioactive decay would be of little significance at the distances considered.

Rev. 18 8-2 8-2 Rev. 18

VEGP ODCM nJk = the number of hours that wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed.

uj= the wind speed (mid-point of wind speed class j) at the effective release height h (m/s).

h= the effective height of the release (m), which is calculated as follows:

h = hv + hpr - h, - c, (8.4) hV= the height of the release point (m).

ht= the maximum terrain height between the release point and the point of interest (m), from Table 8-1.

hpr = the additional height due to plume rise (m)which is calculated as follows and limited by hp,,r.):

hpr(max)-the lesser of: OR (8.6)

U(

d= the inside diameter of the vent (m).

CF =

31. d or Wo <a1.

the correction for low vent exit velocity (m), which is calculated as follows:

cvF=. OR (8.7) 0Sfor W=

u

>t1.5 Fm = the momentum flux parameter (m4/s2), which is calculated as follows:

S = the stability parameter:

Rev. 18 8-3 Rev. 18

VEGP ODCM

= 8.75 x 10- s72 for -0.5 < AT < 1.5

= 1.75 x le s72 for 1.5 < AT < 4.0

= 2.45 x 10c3 s-2 for AT > 4.0 All other symbols are as previously defined in Section 8.1.1.

8.1.3 Mixed-Mode Releases Relative dispersion calculations for mixed-mode releases shall be made as follows:

(X'Q)M = (I - E) .(XIQ)E+ E .(X/Q)G (8.9) where:

(X/Q)M = the mixed-mode release sector-averaged relative concentration for a given wind direction (sector) and distance (s/m3).

E= the fraction of hours during which releases are considered as ground-level releases, calculated as follows:

1.0 for w° < 1.0 uj E = 2.58-1.58. (wUjuj for l.O< 51.5 (8.10) 0.3-0.6- ,for.5< Wo 5.0 0 for W° > 5.0 uj All other symbols are as previously defined.

Rev. 18 8-4 Rev. 18

VEGP ODCM 8.2 RELATIVE DEPOSITION Plume depletion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous release elevations may be considered to be either at ground-level, elevated, or mixed-mode. Facility release elevations for each gaseous release points are as indicated in Table 3-4.

8.2.1 Ground-Level Releases Relative deposition calculations for ground-level releases, or for the ground-level portion of mixed mode releases, shall be made as follows:

2.55D K (D/Q)G g r InXk (8.11)

'DQ'=-Nr k where:

(D/Q)G = the ground-level sector-averaged relative deposition for a given wind direction (sector) and distance (m- 2).

2.55 = the inverse of the number of radians in a 22.50 sector

[= (2 n/16)-1]).

D9 = the deposition rate at distance r, taken from Figure 8-7 for ground-level releases (m-1 ).

nk = the number of hours in which the wind is directed into the sector of interest, and during which stability category k exists.

All other symbols are as defined previously in Section Section 8.1.

8.2.2 Elevated Releases Relative deposition calculations for elevated releases, or for the elevated portion of mixed-mode releases, shall be made as follows:

2.55K (D/)E NNr55K rkr Xnk Dk) (8.12) where:

(D/Q)E = the elevated-plume sector-averaged relative deposition for a given wind direction (sector) and distance (m- 2).

Dek = the elevated plume deposition rate at distance r, taken from Figure 8-8, Figure 8 9, or Figure 8-10, as appropriate to the plume effective release height h defined in Section 8.1.2, for stability class k (m-).

All other symbols are as defined previously.

Rev. 18 8-5 Rev. 18

VEGP ODCM 8.2.3 Mixed-Mode Releases Relative deposition calculations for mixed-mode releases shall be made as follows:

(D/Q)m = (1 - E) .(D/Q)E + E .(D/Q)G (8.13) where:

(D/Q)M = the mixed-mode release sector-averaged relative deposition for a given wind direction (sector) and distance (M-2).

E= the fraction of hours during which releases are considered as ground-level releases, defined in Section 8.1.3.

All other symbols are as previously defined.

8.3 ELEVATED PLUME DOSE FACTORS These factors are not required in effluent dose calculations for VEGP.

Rev. 18 8-6 8-6 Rev. 18

-4i CD Dit IN IN E ENE E ESE S SI IW SI W WNWNNW 0, 500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 8.7 5.7 1.4 5.8 5.7 3.5 1,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 16.7 13.4 3.3 10.4 11.8 6.8 --q CD 1,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 m.

2,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 CD 2,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 3,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 23.7 18.6 7.3 12.2 14.3 7.3 0~

0 3,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 CD 4,000 0.0 0.0 0.0 0.0 0.0 0.0 4.5 0.0 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 -u 5,000 0.0 0.0 0.0 0.0 0.0 0.0 11.1 0.0 0.0 4.7 24.7 18.6 7.3 12.2 16.9 7.3 C,,

"0O 6,000 0.0 0.0 0.0 0.0 0.0 0.0 11.1 0.0 0.0 4.7 26.8 18.6 7.3 12.2 16.9 7.3 CD C'D 7,000 0.0 0.0 0.0 7.8 0.0 0.0 11.1 0.0 3.6 4.7 26.8 18.6 7.3 12.2 16.9 7.3 C.

8,000 0.0 0.0 21.1 13.9 0.0 0.0 11.8 0.0 14.6 4.7 26.8 18.6 7.3 12.2 16.9 7.3 9,000 0.0 0.0 24.4 14.6 0.0 0.0 12.7 7.1 14.6 5.1 26.8 18.6 7.3 12.2 16.9 7.3 10,000 0.0 10.2 24.4 20.2 0.0 0.0 17.1 17.0 14.6 6.8 26.8 18.6 7.3 12.2 16.9 7.3 12,000 0.0 15.9 26.8 20.2 0.0 0.0 17.1 19.5 14.6 6.8 34.1 28.9 13.4 12.2 16.9 7.3 14,000 0.0 15.9 26.8 20.2 0.0 0.0 17.1 19.5 14.6 6.8 34.1 28.9 13.4 16.5 19.7 7.3 16,000 0.0 15.9 26.8 21.7 13.2 0.0 17.1 19.5 14.6 6.8 34.1 28.9 13.4 16.5 25.7 7.3 m

ci) 0 Data in this table are obtained from Reference 11. 0 CD 0 F.

5, Go

VEGP ODCM Figure 8-1. Vertical Standard Deviation of Material in a Plume (a)

Rev. 18 8-8 Rev. 18

VEGP ODCM This figure intentionally left blank.

Refer to the definition for Kr (terrain recirculation factor) in section 8.1.1 for applicable plant data.

Figure 8-2. Terrain Recirculation Factor (K1)

Rev. 18 8-9 Rev. 18

VEGP ODCM 1.0 i 0.7 zU nI 0.5 I-OA 0.%

0.2 0.1 0.1 1.0 10.0 100.0 200.0 PL.UME ThAV*t WSTrrANCU trKILoME1UR This graph is reproduced from Reference 5 (Figure 2).

Figure 8-3. Plume Depletion Effect for Ground Level Releases Rev. 18 8-10 8-10 Rev. 18

VEGP ODCM 1.0 03 0.7 Hil 111 21N i.-

0.3 L.2 0.1 0.1 "1A0 10.0 OlSTAINIE (KILOMElIRS)

I=.0 .Awe,, S This graph is reproduced from Reference 5 (Figure 3).

Figure 8-4. Plume Depletion Effect for 30-Meter Releases Rev. 18 8-11 8-11 Rev. 18

VEGP ODCM IAo OA

-0.8 0.7 0.3 0.2 0.1 0.1 1.0 10. 10. 200.0 PLUME TMAVEL DISTANCE (KILOMETERS)

This graph is reproduced from Reference 5 (Figure 4).

Figure 8-5. Plume Depletion Effect for 60-Meter Releases Rev. 18 8-12 8-12 Rev. 18

VEGP ODCM IA C.

1,0 I

I I 0.2 I

I 0.3 0.2 0.1 0.1 1. 10. 100.0 U0A PUIMETRAVEL DWlANCE IKILOMUFEUM This graph is reproduced from Reference 5 (Figure 5).

Figure 8-6. Plume Depletion Effect for 100-Meter Releases Rev. 18 8-13 8-13 Rev. 18

VEGP ODCM I . ...  ; -I-,-

II II II I I III I -* HIS., "

r

'a

&HIM au Ig

'U 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

This graph is reproduced from Reference 5 (Figure 6).

Figure 8-7. Relative Deposition for Ground-Level Releases Rev. 18 8-14 8-14 Rev. 18

VEGP ODCM L

I Figure 8-8. Relative Deposition for 30-Meter Releases Rev. 18 8-15 8-15 Rev. 18

VEGP ODCM I ";;;

I &Ill" I if'A L I-s NEUTRALNEUTRAL aw a

N au wi cc FI00I I 0.1 1.0 10O 100.0. M00.

PLUME TRAVEL DISTANCE (KILOMETERS)

This graph is reproduced from Reference 5 (Figure 8).

Figure 8-9. Relative Deposition for 60-Meter Releases 8-16 Rev. 18

VEGP ODCM S.. . . , . , . .

I ~ ~UNSTABLE (AB, E S NEEUTRAL (D)-,

a.

mU I

LE IEI1 CU,

[ R l io--

0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

This graph is reproduced from Reference 5 (Figure 9).

Figure 8-10. Relative Deposition for 100-Meter (or Greater) Releases Rev. 18 8-17 8-17 Rev. 18

VEGP ODCM CHAPTER 9 METHODS AND PARAMETERS FOR CALCULATION OF GASEOUS EFFLUENT PATHWAY DOSE FACTORS, Raipj 9.1 INHALATION PATHWAY FACTOR For the inhalation pathway, Raipj in (mrem/y) per (RCi/m 3) is calculated as follows (Reference 1, Section 5.3.1.1):

R.ipj = K,*(BR)a "(DFA)ao. (9.1) where:

K1 = the units conversion factor: 106 pCVi/Ci.

(BR)a = the breathing rate of receptor age group a, in m 3/y, from Table 9-5.

(DFA),j = the inhalation dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-7 through Table 9-10.

Rev. 18 9-1 9-1 Rev. 18

VEGP ODCM 9.2 GROUND PLANE PATHWAY FACTOR 2

For the ground plane external exposure pathway, Raipj in (m .mrem/y) per (jtCi/s) is calculated as follows (Reference 1, Section 5.3.1.2):

Raip==K 1 K2 .(SHF) (DFG)j -e-At (9.2) where:

K1 = the units conversion factor: 106 pCi/tCi.

K2 = the units conversion factor: 8760 h/y.

(SHF) = the shielding factor due to structure (dimensionless). The value used for (SHF) is 0.7, from (Reference 3, Table E-15).

(DFG)j = the ground plane dose factor for radionuclide i and organ j, in (mrem/h) per (pCi/m 2), from Table 9-15. Dose factors are the same for all age groups, and those for the total body also apply to all organs other than skin.

7= the radioactive decay constant for radionuclide i, in s-1. Values of 7 used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

t= the exposure time, in s. The value used for t is 4.73 x 108 s (= 15 y),

from (Reference 1, Section 5.3.1.2).

Rev. 18 9-2 Rev. 18

VEGP ODCM 9.3 GARDEN VEGETATION PATHWAY FACTOR For radionuclides other than tritium in the garden vegetation consumption pathway, Raipj in (m2.mrem/y) per (pCi/s) is calculated as follows (Reference 1, Section 5.3.1.5):

R,=ipj K, " r+ (DFL)au "(U"f e--" + UaSf (9.3) where:

K1 = the units conversion factor: 10e pCi/pCi.

r= the fraction of deposited activity retained on the edible parts of garden vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

Y, = the areal density (agricultural productivity) of growing leafy garden vegetation, in kg/mi, from Table 9-1.

k= the radioactive decay constant for radionuclide i, in s-'. Values of Xi used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

X= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-4, from Table 9-1.

(DFL)ij = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-11 through Table 9-14.

UaL = the consumption rate of fresh leafy garden vegetation by a receptor in age group a, in kg/y, from Table 9-5.

Uas = the consumption rate of stored garden vegetation by a receptor in age group a, in kg/y, from Table 9-5.

fL = the fraction of the annual intake of fresh leafy garden vegetation that is grown locally (dimensionless), from Table 9-1.

fg = the fraction of the annual intake of stored garden vegetation that is grown locally (dimensionless), from Table 9-1.

tL = the average time between harvest of fresh leafy garden vegetation and its consumption, in s, from Table 9-1.

t= the average time between harvest of stored garden vegetation and its consumption, in s, from Table 9-1.

Rev. 18 9-3 Rev. 18

VEGP ODCM 3

For tritium in the garden vegetation consumption pathway, Rapj in (mrem/y) per (pCi/rm ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground:

Raipj =1K, K3 '(DFL)0 -(UaLJL + UaSfg)0-*75.705)(9.4) where:

K(3 = the units conversion factor: 103 g/kg.

H= the absolute humidity of atmospheric air, in g/m 3, from Table 9-1.

0.75 = the fraction of the mass of total garden vegetation that is water (dimensionless).

0.5 = the ratio of the specific activity of tritium in garden vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

Rev. 18 9-4 9-4 Rev. 18

VEGP ODOM T~hl* Q-1 Mi.cnI.ll~nI.InL P~rnmeters for the Garden Veaetation Pathway Tnhhn 0-1 Mi-,-rpllnneous Parameters for the arden Veaetation Pathway ODCM VEGP The following parameter values are for use in calculating Raop for the garden vegetation pathway only. The terms themselves are defined in section 9.3.

Parameter Value Reference Y4 2.0 kg/m 2 Ref. 3, Table E-15

,w 5.73 x 10-7 s 1 Ref. 1, page 33 (14-day half-life) fL 1.0 Ref. 1, page 36 fg 0.76 Ref. 1, page 33 tL 8.6 x 104 s Ref. 3, Table E-15 (1 day) thv 5.18 x 10 6 s Ref. 3, Table E-15 (60 days)

H 8 g/m 3 Ref. 3 Rev. 18 9-5 9-5 Rev. 18

VEGP ODCM 9.4 GRASS-COW-MILK PATHWAY FACTOR 2

For radionuclides other than tritium in the grass-cow-milk pathway, Rapj in (m .mrem/y) per (p.Ci/s) is calculated as follows (Reference 1, Section 5.3.1.3):

)QF O'Up Fi (DFL)au" fpfY, + (i e *fi) (9.5)

Raip.,, = K, +

where:

K1 = the units conversion factor: 106 pCi/pCi.

r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

S= the radioactive decay constant for radionuclide i, in s-'. Values of ý, used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

S= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s7', from Table 9-2.

QF = the cow's consumption rate of feed, in kg/d, from Table 9-2.

Up= the consumption rate of cow milk by a receptor in age group a, in L/y, from Table 9-5.

Fmi = the stable element transfer coefficient applicable to radionuclide i, for cow's milk, in d/L, from Table 9-6.

(DFL)jj = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-11 through Table 9-14.

fp = the fraction of the year that the cow is on pasture (dimensionless),

from Table 9-2.

fs = the fraction of the cow's feed that is pasture grass while the cow is on pasture (dimensionless), from Table 9-2.

Yp = the areal density (agricultural productivity) of growing pasture feed grass, in kg/m 2 , from Table 9-2.

Y, = the areal density (agricultural productivity) of growing stored feed, in kg/m2, from Table 9-2.

th= the transport time from harvest of stored feed to its consumption by the cow, in s, from Table 9-2.

9-6 Rev. 18

VEGP ODCM tf = the transport time from consumption of feed by the cow, to consumption of milk by the receptor, in s, from Table 9-2.

3 For tritium in the grass-cow-milk pathway, Raipo in (mrem/y) per (RCi/m ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground:

R aipj=KlK.1"3 "QF "Uap "Fmi "(DFL)ay "0.7" 0.5)f (9.6) where:

1K3= the units conversion factor: 103 g/kg.

3 H= the absolute humidity of atmospheric air, in g/m , from Table 9-2.

0.75 = the fraction of the mass of total vegetation that is water (dimensionless).

0.5 = the ratio of the specific activity of tritium in vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

Rev. 18 9-7 9-7 Rev. 18

VEGP ODCM Table 9-2. Miscellaneous Parameters for the Grass-Cow-Milk Pathway The following parameter values are for use in calculating Raipo for the grass-cow-milk pathway only. The terms themselves are defined in section 9.4.

Parameter Value Reference 5.73 x 10-7 s 1 Ref. 1, page 33 (14-day half-life)

QF 50 kg/d Ref. 3, Table E-3 fp 1.0 Ref. 1, page 33 fs 1.0 Ref. 1, page 33 Yp 0.7 kg/m 2 Ref. 3, Table E-15 Yý 2.0 kg/m 2 Ref. 3, Table E-15 th= 7.78 x 10 s Ref. 3, Table E-15 (90 days) tf 1.73 x 105 s Ref. 3, Table E-15 (2 days)

H 8 g/m 3 Ref. 3 Rev. 18 9-8 9-8 Rev. 18

VEGP ODCM 9.5 GRASS-GOAT-MILK PATHWAY FACTOR 2

For radionuclides other than tritium in the grass-goat-milk pathway, Raipj in (m .mrem/y) per (pgCi/s) is calculated as follows (Reference 1, Section 5.3.1.3):

Rr p =r + . i.(DFL f fpf') 1 (9.7)

RjKi*i + 2A)P)QF'i ap FMI. -(D'aij LA Y where:

K1 = the units conversion factor: 106 pCVi.Ci.

r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

= the radioactive decay constant for radionuclide i, in s-l. Values of ý used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

Xw = the rate constant for removal of activity on leaf and plant surfaces by weathering, in s-l, from Table 9-3.

QF = the goat's consumption rate of feed, in kg/d, from Table 9-3.

U= the consumption rate of goat milk by a receptor in age group a, in L/y, from Table 9-5.

Fm1 = the stable element transfer coefficient applicable to radionuclide i, for goat's milk, in d/L, from Table 9-6.

(DFL),ij = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-11 through Table 9-14.

fp = the fraction of the year that the goat is on pasture (dimensionless),

from Table 9-3.

fs = the fraction of the goat's feed that is pasture grass while the goat is on pasture (dimensionless), from Table 9-3.

yp = the areal density (agricultural productivity) of growing pasture feed grass, in kg/m 2, from Table 9-3.

feed, in Ys = the areal density (agricultural productivity) of growing stored 2, from Table 9-3.

kg/m th= the transport time from harvest of stored feed to its consumption by the goat, in s, from Table 9-3.

9-9 Rev. 18

VEGP ODCM tf = the transport time from consumption of feed by the goat, to consumption of milk by the receptor, in s, from Table 9-3.

3 For tritium in the grass-goat-milk pathway, Rapj in (mrem/y) per (jiCi/m ) is calculated as follows (Reference 1, Section 5.3.1.5), based on the concentration in air rather than deposition onto the ground:

R aipj =~ .K K3~ F u ap3*-U-F M

.-(DFL)a.0..75. 05) (9.8) 9H) where:

3= the units conversion factor: 103 g/kg.

H= the absolute humidity of atmospheric air, in g/m 3, from Table 9-3.

0.75 = the fraction of the mass of total vegetation that is water (dimensionless).

0.5 = the ratio of the specific activity of tritium in vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

Rev. 18 9-10 9-10 Rev. 18

VEGP ODCM Table 9-3. Miscellaneous Parameters for the Grass-Goat-Milk Pathway The following parameter values are for use in calculating Raipj for the grass-goat-milk pathway only. The terms themselves are defined in section 9-5.

Parameter Value Reference Xv 5.73 x 10 7 s1 Ref. 1, page 33 (14-day half-life)

QF 6 kg/d Ref. 3, Table E-3 fp 1.0 Ref. 1, page 33 fs 1.0 Ref. 1, page 33 Yp 0.7 kg/m 2 Ref. 3, Table E-15 Y. 2.0 kg/M 2 Ref. 3, Table E-15 thin 7.78 x 106 S Ref. 3, Table E-15 (90 days) tf 1.73 x 105 s Ref. 3, Table E-15 (2 days)

H 8 g/m 3 Ref. 3 Rev. 18 9-11 9-11 Rev. 18

VEGP ODCM 9.6 GRASS-COW-MEAT PATHWAY FACTOR 2

For radionuclides other than tritium in the grass-cow-meat pathway, Raipj in (m .mrem/y) per (gCi/s) is calculated as follows (Reference 1, Section 5.3.1.4):

Fu *"((DFL)... y +J ff)

+( -. f 99 RaiR J K IUap F "I FL j j" where:

K1 = the units conversion factor: 106 pCi/RCi.

r= the fraction of deposited activity retained on the edible parts of vegetation (dimensionless). The value used for r is 1.0 for radioiodines and 0.2 for particulates, from (Reference 3, Table E-1).

1 S= the radioactive decay constant for radionuclide i, in s- . Values of used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

W= the rate constant for removal of activity on leaf and plant surfaces by weathering, in s 1, from Table 9-4.

QF = the cow's consumption rate of feed, in kg/d, from Table 9-4.

U = the consumption rate of meat by a receptor in age group a, in kg/y, from Table 9-5.

F,= the stable element transfer coefficient applicable to radionuclide i, for meat, in d/kg, from Table 9-6.

(DFL)aj = the ingestion dose factor for receptor age group a, radionuclide i, and organ j, in mrem/pCi, from Table 9-11 through Table 9-14.

fp = the fraction of the year that the cow is on pasture (dimensionless),

from Table 9-4.

fs = the fraction of the cow's feed that is pasture grass while the cow is on pasture (dimensionless), from Table 9-4.

Yp = the areal density (agricultural productivity) of growing pasture feed grass, in kg/m2 , from Table 9-4.

Ys = the areal density (agricultural productivity) of growing stored feed, in kg/m 2, from Table 9-4.

thrn = the transport time from harvest of stored feed to its consumption by the cow, in s, from Table 9-4.

9-12 Rev. 18

VEGP ODCM tf= the transport time from consumption of feed by the cow, to consumption of meat by the receptor, in s, from Table 9-4.

For tritium in the grass-cow-meat pathway, RaIpj in (mrem/y) per (pACi/m 3) is calculated as follows (Reference 1, Section 5.3.1.4), based on the concentration in air rather than deposition onto the ground:

Rai-py= K, -K3 -QF - Uap -Ff, -(DFL)a, 0..750,5)(9.10) where:

1K3= the units conversion factor: 103 g/kg.

H= the absolute humidity of atmospheric air, in g/m 3, from Table 9-4.

0.75 = the fraction of the mass of total vegetation that is water (dimensionless).

0.5 = the ratio of the specific activity of tritium in vegetation water to that in atmospheric water (dimensionless).

and other parameters are as defined above.

Rev. 18 9-13 9-13 Rev. 18

VEGP ODCM Table 9-4. Miscellaneous Parameters for the Grass-Cow-Meat Pathway The following parameter values are for use in calculating Raipj for the grass-cow-meat pathway only. The terms themselves are defined in section 9-6.

Parameter Value Reference

%W* 5.73 x 10 7 S-1 Ref. 1, page 33 (14-day half-life)

QF 50 kg/d Ref. 3, Table E-3 fp 1.0 Ref. 1, page 33 fs 1.0 Ref. 1, page 33 Yp 0.7 kg/m 2 Ref. 3, Table E-15 Ys 2.0 kg/m 2 Ref. 3, Table E-15 thm 7.78 x 10 s Ref. 3, Table E-15 (90 days) tf 1.73 x10 6 s Ref. 3, Table E-15 (20 days)

H 8 g/m 3 Ref. 3 Rev. 18 9-14 9-14 Rev. 18

VEGP ODCM Table 9-5. Individual Usage Factors Receptor Age Group Usage Factor Infant Child Teenager Adult Milk Consumption Rate, Uap 330 330 400 310 (Lfy)

Meat Consumption Rate, U, 0 41 65 110 (kg/y)

Fresh Leafy Garden Vegetation 0 26 42 64 Consumption Rate, UaL (kg/y)

Stored Garden Vegetation 0 520 630 520 Consumption Rate, Uas (kg/y)

Breathing Rate, (BR)a 1400 3700 8000 8000 3

(m /y) I All values are from Reference 3, Table E-5.

Rev. 18 9-15 9-15 Rev. 18

VEGP ODCM Tahle 9-R* Stable Element Transfer Data Table 9-6 Stable Element Transfer Data Cow Milk Goat Milk Meat Element Fm (d/L)" Fm (d/L)+ Ff (d/kg)*

H 1.0 E-02 1.7 E-01 1.2 E-02 C 1.2 E-02 1.0 E-01 3.1 E-02 Na 4.0 E-02 4.0 E-02 3.0 E-02 P 2.5 E-02 2.5 E-01 4.6 E-02 Cr 2.2 E-03 2.2 E-03 2.4 E-03 Mn 2.5 E-04 2.5 E-04 8.0 E-04 Fe 1.2 E-03 1.3 E-04 4.0 E-02 Co 1.0 E-03 1.0 E-03 1.3 E-02 Ni 6.7 E-03 6.7 E-03 5.3 E-02 Cu 1.4 E-02 1.3 E-02 8.0 E-03 Zn 3.9 E-02 3.9 E-02 3.0 E-02 Br 5.0 E-02 5.0 E-02 2.6 E-02 Rb 3.0 E-02 3.0 E-02 3.1 E-02 Sr 8.0 E-04 1.4 E-02 6.0 E-04 Y 1.0 E-05 1.0 E-05 4.6 E-03 Zr 5.0 E-06 5.0 E-06 3.4 E-02 Nb 2.5 E-03 2.5 E-03 2.8 E-01 Mo 7.5 E-03 7.5 E-03 8.0 E-03 Tc 2.5 E-02 2.5 E-02 4.0 E-01 Ru 1.0 E-06 1.0 E-06 4.0 E-01 Rh 1.0 E-02 1.0 E-02 1.5 E-03 Ag 5.0 E-02 5.0 E-02 1.7 E-02 Sb 1.5 E-03 1.5 E-03 4.0 E-03 Te 1.0 E-03 1.0 E-03 7.7 E-02 1 6.0 E-03 6.0 E-02 2.9 E-03 Cs 1.2 E-02 3.0 E-01 4.0 E-03 Ba 4.0 E-04 4.0 E-04 3.2 E-03 La 5.0 E-06 5.0 E-06 2.0 E-04 Ce 1.0 E-04 1.0 E-04 1.2 E-03 Pr 5.0 E-06 5.0 E-06 4.7 E-03 Nd 5.0 E-06 5.0 E-06 3.3 E-03 W 5.0 E-04 5.0 E-04 1.3 E-03 Np 5.0 E-06 5.0 E-06 2.0 E-04

• - Values from Reference 3 (Table E-1) except as follows: Reference 2 (Table C-

5) for Br and Sb.

+ - Values from Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I, and Cs in goat milk, and Table E-1 for all other elements in cow milk, except as follows:

Reference 2 (Table C-5) for Br and Sb in cow milk.

9-16 Rev. 18

VEGP ODCM Table 9-7. Inhalation Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body [ Thyroid I Kidney Lung GI-LLI H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 No Data 1.81 E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.1OE-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41 E-05 8.39E-06 2.38E-06 No Data No Data 6.21 E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71 E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41 E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71 E-09 2.03E-10 8.79E-1 1 No Data No Data 5.80E-06 3.58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-1 1 6.91 E-1 1 5.13E-12 No Data 2.87E-1 1 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data No Data Br-84 No Data No Data 2.86E-07 No Data No Data No Data No Data Br-85 No Data No Data 1.46E-08 No Data No Data No Data No Data Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 All values are in (mrem/pCi inhaled). They are obtained from Reference 3 (Table E-10). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-124, or Sb-125.

9-17 Rev. 18

VEGP ODCM T~hl* Q--/(r*nntdV inhalation Dose Factors for the Infant Agie Group Nuclide Bone Liver T.Body Thyroid IKidney Lung GI-LLI Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.OOE-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91 m 2.91 E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Y-93 1.07E-07 No Data 2.91 E-09 No Data No Data 5.46E-05 1.1 9E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.OOE-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31 E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99m 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-1 03 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61 E-05 8.26E-03 1.17E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-1 25 No Data No Data No Data No Data No Data No Data No Data 1.42E-06 4.70E-07 1.1 6E-06 No Data 3.19E-04 9.22E-06 Te-125m 3.40E-06 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127m Te-127 1.59E-09 6.81 E-1 0 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-1 29m 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-1I 1.34E-1I 4.82E-11 1.25E-10 2.14E-06 1.88E-05 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 Te-31 m 7.62E-08 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 Te-131 9-18 Rev. 18

VEGP ODCM T~hlk _Q:-7 (rcnntdV_ Inhalation Dose Factors for the Infant AaCe Group Nuclide Bone Liver T.Body Thyroid Kidney Lung JgGI-LL1 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 1-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 1-133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 No Data 1.54E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21 E-07 1-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31 E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61 E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-1 37 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61 E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-1 1 No Data 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.OOE-05 4.OOE-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-1I 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 La-140 3.61 E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-1 1 No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.1 9E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.OOE-05 3.74E-06 4.99E-07 No Data 1.41 E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81 E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 Rev. 18 9-19 9-19 Rev. 18

VEGP ODCM Table 9-8. Inhalation Dose Factors for the Child Age Group NuclideI Bone Liver [_T. Body IThyroid __Kidney Lung GI-LLI H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4-17E-08 2.31 E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71 E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-1 1 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.1OE-06 No Data No Data 3.OOE-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51 E-06 No Data No Data 3.43E-04 1.91 E-05 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91 E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71 E-06 Ni-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21 E-06 2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41 E-06 Zn-69 1.81 E-1 1 2.61 E- 11 2.41 E-12 No Data 1.58E-1 1 3.84E-07 2.75E-06 Br-83 No Data No Data 1.28E-07 No Data No Data No Data No Data Br-84 No Data No Data 1.48E-07 No Data No Data No Data No Data Br-85 No Data No Data 6.84E-09 No Data No Data No Data No Data Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11E-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 All values are in (mrem/pCi inhaled). They are obtained from Reference 3 (Table E-9). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-124, or Sb-125.

9-20 Rev. 18

VEGP ODCM T~hlA .Q-R (nnntd'i_ Inhalation Dose Factors for the Child Aae Group Nuclide Bone Liver T.Body Thyroid IKidney Lung GI-LLI Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11 E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91m 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.1OE-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01 E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.OOE-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.OOE-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81E-13 9.41E-13 1.56E-11 No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41 E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21 E-05 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1 .16E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71 E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127m 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91 E-05 Te-129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 Rev. 18 9-21 9-21 Rev. 18

VEGP ODCM Table 9-8 (contd). Inhalation Dose Factors for the Child Age Group Nuclide Bone I Liver T.Body Thyroid I Kidney Lung GI-LLI Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 No Data 1.38E-06 1-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-07 1-132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 1-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 1-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 1-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-1 36 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81 E-05 9.78E-07 Cs-138 1.71 E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 No Data 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.OOE-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-1 1 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-11 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.1OE-05 La-142 3.50E-10 1.11E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31 E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-11 4.99E-12 8.1OE-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 Rev. 18 9-22 Rev. 18

VEGP ODCM Table 9-9. Inhalation Dose Factors for the Teenager Age Group Nuclide Bone Liver JT.Body_ Thyroid Kidney [ Lung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-08 8.95E-06 No Data No Data No Data 1.1 6E-05 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91 E-04 2.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.1 9E-05 Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-65 2.73E-1 0 3.66E-1 1 1.59E-1 1 No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data No Data Br-84 No Data No Data 5.41 E-08 No Data No Data No Data No Data Br-85 No Data No Data 2.29E-09 No Data No Data No Data No Data Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21 E-06 Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91 E-08 No Data No Data No Data 4.22E-1 7 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 Sr-91 1.10E-08 All values are in (mrem/pCi inhaled). They are obtained from Reference 3 (Table E-8). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-1 24, or Sb-1 25.

9-23 Rev. 18

VEGP ODCM Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 1.1 9E-09 No Data 5.08E-1 1 No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.OOE-08 No Data No Data 3.66E-05 6.99E-05 Y-91m 4.63E-1 1 No Data 1.77E-12 No Data No Data 4.OOE-07 3.77E-09 Y-91 8.26E-05 No Data 2.21 E-06 No Data No Data 3.67E-04 5.11 E-05 Y-92 1.84E-09 No Data 5.36E-1 1 No Data No Data 3.35E-06 2.06E-05 Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21 E-05 Mo-99 No Data 2.11 E-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99m 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-1 03 2.63E-07 No Data 1.1 2E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-11 No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01 E-03 1.20E-04 Rh-1 05 No Data No Data No Data No Data No Data No Data No Data Ag-110m 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41 E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127m 2.25E-06 11.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129m 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-1 1 4.12E-07 2.02E-07 Te-31 m 1.23E-08 7.51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Rev. 18 9-24 9-24 Rev. 18

VEGP ODCM Table 9-9 (contd). Inhalation Dose Factors for the Teenager Age Group Nuclide I Bone Liver I T.Body Thyroid Kidney Lung GI-LLI Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.1 4E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07 1-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 1-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 1-134 1.11 E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 1-135 4.62E-07 1.1 8E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.41 E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71 E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51 E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-1 1 Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11 E-04 2.53E-04 3.28E-05 No Data 1.51 E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41 E-08 No Data 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92E-06 2.21 E-05 Np-239 4.23E-08 3.99E-09 2.21 E-09 No Data 1.25E-08 8.11 E-06 1.65E-05 Rev. 18 9-25 9-25 Rev. 18

VEGP ODCM Table 9-10. Inhalation Dose Factors for the Adult Age Group Nuclide Bone T Liver T. BodyI Thyroid Kidney Lung GI-LLI H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01 E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.1 6E-04 1.33E-05 Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.OOE-07 1.54E-06 Cu-64 No Data 1.83E-10 7.69E-11 No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01 E-08 No Data No Data No Data 2.90E-08 Br-84 No Data No Data 3.91 E-08 No Data No Data No Data 2.05E- 13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data No Data Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41 E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.1 6E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 Sr-91 7.74_-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 All values are in (mrem/pCi inhaled). They are obtained from Reference 3 (Table E-7), except as follows: Reference 2 (Table C-1) for Rh-105, Sb-124, and Sb-125.

9-26 Rev. 18

VEGP ODCM Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 Y-90 2.61 E-07 No Data 7.01 E-09 No Data No Data 2.12E-05 6.32E-05 Y-91m 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81 E-05 Y-92 1.29E-09 No Data 3.77E-1 1 No Data No Data 1.96E-06 9.19E-06 Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91 E-06 No Data 6.77E-06 2.21 E-04 1.88E-05 Zr-97 1.21 E-08 2.45E-09 1.1 3E-09 No Data 3.71 E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31 E-05 1.30E-05 Mo-99 No Data 1.51 E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.1 OE-05 Tc-99m 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91 E-07 No Data 8.23E-08 No Data 7.29E-07 6.31 E-05 1.38E-05 Ru-105 9.88E-1 1 No Data 3.89E-1 1 No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.1 7E-03 1.14E-04 Rh-105 9.24E-10 6.73E-10 4.43E-10 No Data 2.86E-09 2.41 E-06 1.09E-05 Ag-110m 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Sb-124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 No Data 3.1OE-04 5.08E-05 Sb-125 8.26E-06 8.91 E-08 1.66E-06 7.34E-09 No Data 2.75E-04 1.26E-05 Te-125m 4.27E-07 1.98E-07 5.84E-08 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21 E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-1 29m 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131m 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 Rev. 18 9-27 Rev. 18

VEGP ODCM Table 9-10 (contd). Inhalation Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-1 32 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 1-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61 E-07 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 1-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 Cs-1 34 4.66E-05 1.06E-04 9.1OE-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.OOE-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21 E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91 E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91 E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91 E-09 No Data 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51 E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.1OE-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 Rev. 18 9-28 Rev. 18

VEGP ODCM Table 9-11. Ingestion Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 No Data No Data No Data 2.30E-05 Cr-51 No Data No Data 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.11 E-07 Mn-54 No Data 1.99E-05 4.51 E-06 No Data 4.41 E-06 No Data 7.31 E-06 Mn-56 No Data 8.18E-07 1.41 E-07 No Data 7.03E-07 No Data 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1 .14E-06 Fe-59 3.OBE-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05 Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.25E-05 Zn-65 1.84E-05 6.31 E-05 2.91 E-05 No Data 3.06E-05 No Data 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Data No Data No Data No Data Br-84 No Data No Data 3.82E-07 No Data No Data No Data No Data Br-85 No Data No Data 1.94E-08 No Data No Data No Data No Data Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07 Rb-89 No Data 2.86E-07 1.97E-07 No Data No Data No Data 9.74E-08 Sr-89 2.51 E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 Sr-90 1.85E-02 No Data 4.71 E-03 No Data No Data No Data 2.31 E-04 Sr-91 5.OOE-05 No Data 1.81 E-06 No Data No Data No Data 5.92E-05 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-14). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-1 24, or Sb-1 25.

9-29 Rev. 18

VEGP ODCM Table 9-11 (contd). Ingestion Dose Factors for the Infant Age Group Nuclide BoneI Liver T.Body [_ThyroidI Kidney Lung GI-LLI Sr-92 1.92E-05 No Data 7.13E-07 No Data No Data No Data 2.07E-04 Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 Y-91m 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06 Y-91 1.13E-06 No Data 3.01 E-08 No Data No Data No Data 8.1OE-05 Y-92 7.65E-09 No Data 2.15E-10 No Data No Data No Data 1.46E-04 Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41 E-08 No Data 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.OOE-08 No Data 1.24E-08 No Data 1.46E-05 Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05 Tc-99m 1.92E-09 3.96E-09 5.1OE-08 No Data 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05 Ru-1 05 1.36E-07 No Data 4.58E-08 No Data 1.OOE-06 No Data 5.41 E-05 Ru-106 2.41 E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E-04 Rh-105 No Data No Data No Data No Data No Data No Data No Data Ag-110m 9.96E-07 7.27E-07 4.81 E-07 No Data 1.04E-06 No Data 3.77E-05 Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 No Data No Data No Data No Data No Data No Data No Data Te-125m 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.11 E-05 Te-1 27m 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 No Data 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.1OE-05 Te-129m 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 Te-131 m 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 No Data 1.03E-04 Te-1 31 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.11 E-06 Rev. 18 9-30 Rev. 18

VEGP ODCM Table 9-11 (contd). Ingestion Dose Factors for the Infant Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81 E-05 1-130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 No Data 2.83E-06 1-131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 No Data 1.51 E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 No Data 2.73E-06 1-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 No Data 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 No Data 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.1OE-05 No Data 1.81E-04 7.42E-05 1.91 E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 Cs-1 37 5.22E-04 6.11 E-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91 E-06 Cs-138 4.81 E-07 7.82E-07 3.79E-07 No Data 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05 Ba-140 1.71 E-04 1.71 E-07 8.81 E-06 No Data 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Ba-1 42 1.84E-07 1.53E-1 0 9.06E-09 No Data 8.81 E-11 9.26E-1 1 7.59E-07 La-140 2.11 E-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-1 1 No Data No Data No Data 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.48E-08 No Data 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71 E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1 .13E-08 No Data 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-11 No Data 3.84E-11 No Data 4.93E-06 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05 Nd-147 9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05 W-187 Np-239 1.11E-08 9.93E-10 5.61E-10 No Data 1.98E-09 No Data 2.87E-05 9-31 Rev. 18

VEGP ODCM Table 9-12. Ingestion Dose Factors for the Child Age Group Nuclide Bone Liver T. Body _[Thyroid Kidney Lung GI-LLI H-3 No Data 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 Cr-51 No Data No Data 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.OOE-06 No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05 Fe-55 1.15E-05 6.1OE-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05 Co-58 No Data 1.80E-06 5.51 E-06 No Data No Data No Data 1.05E-05 Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.1 5E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41 E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84E-08 No Data 3.99E-06 Br-83 No Data No Data 1.71 E-07 No Data No Data No Data No Data Br-84 No Data No Data 1.98E-07 No Data No Data No Data No Data Br-85 No Data No Data 9.12E-09 No Data No Data No Data No Data Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31 E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 Rb-89 No Data 1.1 7E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.11 E-05 Sr-90 1.70E-02 No Data 4.31 E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-1 3). Neither Reference 2 nor Reference 3 contains data for Rh-1 05, Sb-124, or Sb-125.

9-32 Rev. 18

VEGP ODCM Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group Nuclide Bone Liver T.BodyI Thyroid Kidney Lung GI-LLI Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71 E-04 Y-90 4.11 E-08 No Data 1.1 0E-09 No Data No Data No Data 1.1 7E-04 Y-91 m 3.82E-10 No Data 1.39E-1 1 No Data No Data No Data 7.48E-07 Y-91 6.02E-07 No Data 1.61 E-08 No Data No Data No Data 8.02E-05 Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 Zr-97 6.99E-09 1.01 E-09 5.96E-1 0 No Data 1.45E-09 No Data 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05 Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.1 0E-05 Tc-99m 9.23E-1 0 1.81 E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1 .12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 No Data 2.81 E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21 E-05 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Ru-106 No Data No Data No Data No Data No Data No Data No Data Rh-105 5.39E-07 3.64E-07 2.91 E-07 No Data 6.78E-07 No Data 4.33E-05 Ag-110m No Data No Data No Data No Data No Data No Data No Data Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 1.1 4E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.1 OE-05 Te-125m 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 No Data 2.34E-05 Te-127m 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-127 4.71 E-07 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 Te-129m 4.87E-05 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-129 1.34E-07 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 No Data 1.01 E-04 Te-1 31 m 7.20E-06 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 No Data 4.36E-07 Te-131 8.30E-08 9-33 Rev. 18

VEGP ODCM Table 9-12 (contd). Ingestion Dose Factors for the Child Age Group T.Body Thyroid Kidney Lung GI-LLI Nuclide BoneI Liver Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06 1-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 1-132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 1-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-07 1-134 1-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 2.34E-04 3.84E-04 8.1OE-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-134 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-136 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Cs-137 Cs-138 2.28E-07 3.17E-07 2.01 E-07 No Data 2.23E-07 2.40E-08 1.46E-07 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-1 39 8.31 E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21 E-05 Ba-140 2.OOE-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07 Ba-141 8.74E-08 6.29E-1 1 4.88E-09 No Data 5.09E-1 1 3.70E-1 1 1.14E-09 Ba-142 1.01 E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 La-140 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31 E-05 La-142 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Ce-141 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-143 No Data 1.70E-04 Ce-144 2.08E-06 6.52E-07 1. 11 E-07 No Data 3.61 E-07 3.93E-08 11. 18E-08 1.95E-09 No Data 6.39E-09 No Data 4.24E-05 Pr-143 1.29E-10 3.99E-11I 6.49E-12 No Data 2.11 E-1 1 No Data 8.59E-08 Pr-144 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 Nd-147 2.79E-08 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 W-187 4.29E-07 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 Np-239 9-34 Rev. 18

VEGP ODCM Table 9-13. Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71 E-05 1.07E-05 No Data No Data No Data 2.32E-05 Cr-51 No Data No Data 3.60E-09 2.OOE-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.1 7E-06 No Data 1.76E-06 No Data 1.21 E-05 Mn-56 No Data 1.58E-07 2.81 E-08 No Data 2.OOE-07 No Data 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.1 6E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2.81 E-06 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.OOE-06 No Data No Data No Data 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1 .15E-07 5.41 E-08 No Data 2.91 E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.OOE-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 Br-83 No Data No Data 5.74E-08 No Data No Data No Data No Data Br-84 No Data No Data 7.22E-08 No Data No Data No Data No Data Br-85 No Data No Data 3.05E-09 No Data No Data No Data No Data Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41 E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-1 5 Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-90 8.07E-06 No Data 3.21 E-07 No Data No Data No Data 3.66E-05 Sr-91 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-12). Neither Reference 2 nor Reference 3 contains data for Rh-105, Sb-1 24, or Sb-1 25.

9-35 Rev. 18

VEGP ODCM Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung [ GI-LLI Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1 .13E-04 Y-91m 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 Y-91 2.01 E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 Y-92 1.21 E-09 No Data 3.50E-1 1 No Data No Data No Data 3.32E-05 Y-93 3.83E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91 E-08 No Data 3.OOE-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51 E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1 .15E-06 No Data 1.38E-05 No Data 1.08E-05 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07 Tc-99m 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Tc-101 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05 Ru-103 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 Ru-105 3.92E-06 No Data 4.94E-07 No Data 7.56E-06 No Data 1.88E-04 Ru-1 06 No Data No Data No Data No Data No Data No Data No Data Rh-105 2.05E-07 1.94E-07 1.1 8E-07 No Data 3.70E-07 No Data 5.45E-05 Ag-110m No Data No Data No Data No Data No Data No Data No Data Sb-124 No Data No Data No Data No Data No Data No Data No Data Sb-125 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05 Te-125m 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41 E-05 Te-127m 9.67E-06 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-127 1.58E-07 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05 Te-129m 1.63E-05 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data 2.45E-07 Te-129 4.48E-08 1.1 7E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131m 2.44E-06 1 .15E-08 8.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 Te-131 2.79E-08 9-36 Rev. 18

VEGP ODCM Table 9-13 (contd). Ingestion Dose Factors for the Teenager Age Group Nuclide Bone Liver T.BodyI Thyroid I Kidney Lung GI-LLI Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.OOE-05 1-130 1.03E-06 2.98E-06 1.1 9E-06 2.43E-04 4.59E-06 No Data 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 No Data 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1 .15E-06 No Data 3.18E-07 1-133 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 No Data 5.1OE-09 1-135 6.1OE-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Cs-1 38 7.76E-08 1.49E-07 7.45E-08 No Data 1.1 OE-07 1.28E-08 6.76E-1 1 Ba-139 1.39E-07 9.78E-1 1 4.05E-09 No Data 9.22E-1 1 6.74E-1 1 1.24E-06 Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.1 8E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 No Data 4.65E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-11 1.99E-11 9.18E-20 La-140 3.48E-09 1.71 E-09 4.55E-10 No Data No Data No Data 9.82E-05 La-142 1.79E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05 Ce-143 2.35E-09 1.71 E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31 E-05 Pr-144 4.30E-11 I1.76E-11 2.18E-12 No Data 1.01 E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Data 3.68E-05 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.22E-05 W-187 1.76E-09 1.66E-10 9.22E-1 1 No Data 5.21 E-10 No Data 2.67E-05 Np-239 9-37 Rev. 18

VEGP ODCM Table 9-14. Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91 E-06 No Data No Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51 E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01 E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91 E-08 No Data 2.1 OE-07 No Data 7.1 OE-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 Br-84 No Data No Data 5.21 E-08 No Data No Data No Data 4.09E- 13 Br-85 No Data No Data 2.14E-09 No Data No Data No Data No Data Rb-86 No Data 2.11 E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21 E-08 No Data No Data No Data 8.36E- 19 Rb-89 No Data 4.01 E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 All values are in (mrem/pCi ingested). They are obtained from Reference 3 (Table E-1 1), except as follows: Reference 2 (Table A-3) for Rh-1 05, Sb-1 24, and Sb-125.

Rev. 18 9-38 9-38 Rev. 18

VEGP ODCM Table 9-14 (contd). Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09E-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41 E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E- 11 No Data No Data No Data 1.48E-05 Y-93 2.68E-09 No Data 7.40E-1 1 No Data No Data No Data 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.1 OE-05 Mo-99 No Data 4.31 E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.1OE-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Rh-105 1.22E-07 8.86E-08 5.83E-08 No Data 3.76E-07 No Data 1.41 E-05 Ag-i 1Dm 1.60E-07 1.48E-07 8.79E-08 No Data 2.91 E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.30E-08 1.11E-06 6.79E-09 No Data 2.18E-06 7.95E-05 Sb-125 2.23E-06 2.40E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05 Te-125m 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.1OE-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-129 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-131 Rev. 18 9-39 9-39 Rev. 18

VEGP ODCM Table 9-14 (contd). Ingestion Dose Factors for the Adult Age Group Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71 E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 1-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 No Data 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51 E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31 E-06 Cs-134 6.22E-05 1.48E-04 1.21 E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51 E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11 E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01 E-08 7.91 E-09 4.65E-13 Ba-139 9.70E-08 6.91 E-1 1 2.84E-09 No Data 6.46E-1 1 3.92E-1 1 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.OOE-26 La-1 40 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21 E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01 E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61 E-08 3.01 E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 i1.17E-10I 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 Rev. 18 9-40 9-40 Rev. 18

VEGP ODCM Table 9-15. External Dose Factors for Standina on Contaminated Ground Tal 9............. ExenlDs atrsfrSadn nCotmntdGon Nuclide T. Body Skin Nuclide T. Body [ Skin H-3 0.00 0.00 Sr-91 7.10E-09 8.30E-09 C-14 0.00 0.00 Sr-92 9.00E-09 1.OOE-08 Na-24 2.50E-08 2.90E-08 Y-90 2.20E-12 2.60E-12 P-32 0.00 0.00 Y-91 m 3.80E-09 4.40E-09 Cr-51 2.20E-10 2.60E-10 Y-91 2.40E-1 1 2.70E-1 1 Mn-54 5.80E-09 6.80E-09 Y-92 1.60E-09 1.90E-09 Mn-56 1.1 OE-08 1.30E-08 Y-93 5.70E-10 7.80E-10 Fe-55 0.00 0.00 Zr-95 5.OOE-09 5.80E-09 Fe-59 8.OOE-09 9.40E-09 Zr-97 5.50E-09 6.40E-09 Co-58 7.OOE-09 8.20E-09 Nb-95 5.1OE-09 6.OOE-09 Co-60 1.70E-08 2.OOE-08 Mo-99 1.90E-09 2.20E-09 Ni-63 0.00 0.00 Tc-99m 9.60E-10 1.10E-09 Ni-65 3.70E-09 4.30E-09 Tc-101 2.70E-09 3.OOE-09 Cu-64 1.50E-09 1.70E-09 Ru-103 3.60E-09 4.20E-09 Zn-65 4.OOE-09 4.60E-09 Ru-105 4.50E-09 5.1OE-09 Zn-69 0.00 0.00 Ru-1 06 1.50E-09 1.80E-09 Br-83 6.40E-1 1 9.30E-1 1 Rh-105 6.60E-10 7.70E-10 Br-84 1.20E-08 1.40E-08 Ag-110m 1.80E-08 2.1OE-08 Br-85 0.00 0.00 Sb-124 1.30E-08 1.50E-08 Rb-86 6.30E-1 0 7.20E-10 Sb-125 3.10E-09 3.50E-09 Rb-88 3.50E-09 4.OOE-09 Te-125m 3.50E-1 1 4.80E-1 1 Rb-89 1.50E-08 1.80E-08 Te-127m 1.10E-12 1.30E-12 Sr-89 5.60E-13 6.50E-13 Te-127 1.OOE-11 1.10E-11 Sr-90 0.00 0.00 Te-129m 7.70E-10 9.OOE-10 All values are in (mrem/h) per (pCi/m 2 ). They are obtained from Reference 3 (Table E-6), except as follows: Reference 2 (Table A-7) for Rh-105, Sb-124, and Sb-125.

Rev. 18 9-41 9-41 Rev. 18

VEGP ODCM Table 9-15 (contdfl. External Dose Factors for Standina on Contaminated Ground Table 9-15 (contd).

Nuclide T.Body Skin Te-129 7.10E-10 8.40E-10 Te-131 m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.O0E-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.OOE-09 La- 140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.00 0.00 Pr-144 2.00E-10 2.30E-10 Nd-147 1.OOE-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.1OE-09 Rev. 18 9-42 Rev. 18

VEGP ODCM CHAPTER 10 DEFINITIONS OF EFFLUENT CONTROL TERMS The terms defined in this chapter are used in the presentation of the above chapters. These terms are shown in all capital letters to indicate that they are specifically defined.

10.1 TERMS SPECIFIC TO THE ODCM The following terms are used in the ODCM, but are not found in the Technical Specifications:

ACTION(S)

An ACTION shall be that part of a control that prescribes remedial measures required under designated conditions.

BATCH RELEASE A BATCH RELEASE is the discharge of wastes of a discrete volume. Prior to sampling for analyses, each liquid batch shall be isolated and then thoroughly mixed by a method described in the ODCM to assure representative sampling.

COMPOSITE SAMPLE A COMPOSITE SAMPLE is one which contains material from multiple waste releases, in which the quantity of sample is proportional to the quantity of waste discharged, and in which the method of sampling employed results in a specimen that is representative of the wastes released. Prior to analyses, all liquid samples that are to be aliquotted for a COMPOSITE SAMPLE shall be mixed thoroughly, in order for the COMPOSITE SAMPLE to be representative of the effluent release.

When assessing the consequences of a waste release at the pre-release or post-release stage, the most recent available COMPOSITE SAMPLE results for the applicable release pathway may be used.

CONTINUOUS RELEASE A CONTINUOUS RELEASE is the discharge of wastes of a non-discrete volume, e.g.,

from a volume within a system that has an input flow during the continuous release. To be representative of the quantities and concentrations of radioactive materials in CONTINUOUS RELEASES of liquid effluents, samples shall be collected in proportion to the rate of flow of the effluent stream or to the quantity of liquid waste discharged.

FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of surveillance requirements not to shall correspond to the intervals defined below, with a maximum allowable extension exceed 25% of the surveillance interval.

NOTATION FREQUENCY S (Once per shift) At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D (Daily) At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 92 days.

10-1 Rev. 18

VEGP ODCM SA (Semi-annually) At least once per 184 days.

R (Refueling) At least once per 18 months.

S/U (Startup) Prior to each reactor startup.

NA Not applicable.

P (Prior) Completed prior to each release.

GASEOUS WASTE PROCESSING SYSTEM A GASEOUS WASTE PROCESSING SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting Reactor Coolant System offgases from the Reactor Coolant System and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

LIQUID RADWASTE TREATMENT SYSTEM A LIQUID RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive materials in liquid effluents by systematic collection, retention, and processing through filtration, evaporation, separation and/or ion exchange treatment. This system consists of at least one collection tank, one evaporator or demineralizer system, one post-treatment tank and associated components providing for treatment flow and functional control.

MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS For the purposes of the ODCM, MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS include the following changes to such systems:

(1) Major changes in process equipment, components, structures, or effluent monitoring instrumentation as described in the Final Safety Analysis Report (FSAR) or as evaluated in the Nuclear Regulatory Commission staff's Safety Evaluation Report (SER) (e.g., deletion of evaporators and installation of demineralizers);

(2) Changes in the design of radwaste treatment systems that could significantly increase quantities of effluents released from those previously considered in the FSAR and SER; (3) Changes in system design which may invalidate the accident analysis as described in the SER (e.g., changes in tank capacity that would alter the curies released); or (4) Changes in system design that could potentially result in a significant increase in occupational exposure of operating personnel (e.g., use of temporary equipment without adequate shielding provisions).

Rev. 18 10-2 10-2 Rev. 18

VEGP ODCM 1

MEMBER(S) OF THE PUBLIC A MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupationaldose . This category may include persons who use portions of 2

the site for recreational, occupational, or other purposes not associated with the plant.

MINIMUM DETECTABLE CONCENTRATION The MINIMUM DETECTABLE CONCENTRATION (MDC) is defined, for purposes of the controls in this ODCM, as the smallest concentration of radioactive material in a sample that will yield a net count above system background and that will be detected with 95 percent probability, with only 5-percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation, the MDC for a given radionuclide is determined as follows (Reference 18):

where:

MDC = the a prioriMINIMUM DETECTABLE CONCENTRATION (jiCi per unit mass or volume).

2.71 + 3.29 R -

ts

+ tb MDC = t S

6 Y e-At E -V 2.22 x 10 Rb = the background counting rate, or the counting rate of a blank sample, as appropriate (counts per minute).

ts = the length of the sample counting period (minutes).

tb = the length of the background counting period (minutes).

E= the counting efficiency (counts per disintegration)

V= the sample size (units of mass or volume).

2.22 x 108 = the number of disintegrations per minute per liCi.

Y= the fractional radiochemical yield, when applicable.

= the radioactive decay constant for the given radionuclide (h-1).

Values of X used in effluent calculations should be based on decay data from a recognized and current source, such as Reference 20.

At = for effluent samples, the elapsed time between the midpoint of sample collection and the time of counting (h); for environmental samples, the elapsed time between the end of sample collection and the time of counting (h).

the definitions The italicized terms in this definition, which are not otherwise used in this ODCM, shall have assigned to them by 10 CFR 20.1003.

2 Except as delineated in other parts of 10 CFR chapter I.

10-3 Rev. 18

VEGP ODCM Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the MDC is defined as an a priori(before the fact) limit representing the capability of a measurement system, and not as an a posteriori(after the fact) limit for a particular measurement.

PRINCIPAL GAMMA EMITTERS The PRINCIPAL GAMMA EMITTERS for which the MINIMUM DETECTABLE CONCENTRATION (MDC) limit applies include exclusively the following radionuclides:

"* For liquid radioactive effluents: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs 134, Cs-1 37, and Ce-1 41. Ce-1 44 shall also be measured, but with an MDC of 5 x eiCVmL.

10-

"* For gaseous radioactive effluents: In noble gas releases, Kr-87, Kr-88, Xe-1 33, Xe-133m, Xe-135, Xe-138; and in particulate releases, Mn-54, Fe-59, Co-58, Co 60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

"* For environmental media: The gamma emitters specifically listed in Table 4-3.

These lists do not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report, the Annual Radiological Environmental Operating Report, or other applicable report(s).

SITE BOUNDARY For the purpose of effluent controls defined in the ODCM, the SITE BOUNDARY shall be as shown in Figure 4-1.

SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

UNRESTRICTED AREA The UNRESTRICTED AREA shall be any area access to which is neither limited nor controlled by the licensee, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM The VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents, by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters, for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. (Such a system is not considered to have any effect on any noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

Rev. 18 10-4 10-4 Rev. 18

VEGP ODCM 10.2 TERMS DEFINED INTHE TECHNICAL SPECIFICATIONS The following terms are defined in the Technical Specifications, Section 1.0. Because they are used throughout the Limits of Operation sections of the ODCM, they are presented here for convenience. In the event of discrepancies between the definitions below and those in the Technical Specifications, the Technical Specification definitions shall take precedence.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel, such that it responds within the required range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the required sensor, alarm, interlock, and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps, so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL OPERATIONAL TEST (COT)

A CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability of required alarm, interlock, and/or trip functions. The CHANNEL OPERATIONAL TEST shall include adjustments, as necessary, of the required alarm, interlock, and/or trip setpoints, so that the setpoints are within the required range and accuracy.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (p.CVg) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132,1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this 1,

calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109, Revision 1977.

MODE (or OPERATIONAL MODE)

An OPERATIONAL MODE shall correspond to any one inclusive combination of core vessel reactivity condition, power level, average reactor coolant temperature, and reactor with head closure bolt tensioning specified in Section 1.0 of the Technical Specifications fuel in the reactor vessel.

OPERABLE (or OPERABILITY)

OPERABILITY exists when a system, subsystem, train, component or device is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment its that are required for the system, subsystem, train, component or device to perform function(s) are also capable of performing their related support function(s).

10-5 Rev. 18

VEGP ODCM RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3565 MWt.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

10-6 Rev. 18

VEGP ODOM VOGTLE ELECTRIC GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL EFFECTIVE PAGE LISTING PAGE REV PAGE REV

...................... o.o.................oo.o..... .19 2-33 ................................................. 18

...................................................... 19 2-34 ................................................. 18 ii..................................................... 18 2-35 ................................................. 18 iv..................................................... 18 2-36 ................................................. 18

v. .................. ................ 18 2-37 ................................................. 18 2-38 ................................................. 18 vi ...................................................... 18 vii ...................................................... 18 2-39 ................................................. 18 2-40 ............................................... 18 viii .................................................... 19 ix..................................................... 18 2-41 ................................................. 18 x ..................................................... 18 2-42 ............................................... 18 1-1 ................................................... 18 2-43 ............................................ Deleted 18 2-44 ............................................ Deleted 2-1 ...................................................

18 2-45 ............................................ Deleted 2-2 .................................................

18 2-46 ............................................ Deleted 2-3 .................................................

18 2-47 ............................................ Deleted 2-4 .................................................

18 2-48 ............................................ Deleted 2-5 .................................................

18 2-49 ............................................ Deleted 2-6 ................................................. 18 18 3-1 ...................................................

2-7 ................................................. 18 2-8 .................................................... 18 3-2 .................................................

3-3 ................................................. 19 2-9 .................................................. 18 3-4 ................................................. 18 2-10 ................................................. 18 3-5 ................................................. 19 2-11 ................................................. 18 3-6 ................................................. 19 2-12 ................................................. 18 3-7 ................................................. 18 2-13 ................................................. 18 3-8 ................................................. 19 2-14 ................................................. 19 3-9 ................................................. 19 2-15 ................................................. 19 3-10 ................................................. 18 2-16 ................................................. 18 3-11 ................................................. 18 2-17 ................................................. 18 3-12 ............................................... 18 2-18 .................................................. 18 3-13 ............................................... 18 2-19 .................................................. 18 3-14 ............................................... 19 2-20 ................................................. 18 3-15 ............................................... 18 2-21 ................................................. 18 3-16 ............................................... 18 2-22 ................................................. 18 3-17 ............................................... 18 2-23 ................................................. 18 3-18 ................................................. 18 2-24 .................................................. 18 3-19 ............................................... 18 2-25 ................................................. 18 3-19a ............................................... 19 2-26 .................................................. 18 3-20 ............................................... 18 2-27 .................................................. 18 3-21 ................................................. 18 2-28 ................................................. 18 3-22 .................................................... 18 2-29 ............................................... 18 3-23 ............................................... 18 2-30 ................................................. 18 3-24 ............................................... 18 2-31 ................................................. 18 2-32 ................................................. 18 1 of 3 Rev. 19

VEGP ODCM PAGE REV PAGE REV 3-25 ..................................................... 18 4-17 ................................................. 18 3-26 ..................................................... 18 4-18 ................................................. 18 3-27 ..................................................... 18 4-19 ............................................ Deleted 3-28 ..................................................... 18 4-20 ............................................ Deleted 3-29 ..................................................... 18 5-1 .................................................. 18 3-30 ..................................................... 18 5-2 ................................................... 18 3-31 ..................................................... 18 5-3 ................................................. 18 3-32 ..................................................... 18 5-4 ................................................. 18 3-33 ..................................................... 18 6-1 .................................................. 18 3-34 ..................................................... 18 6-2 ................................................. 18 3-35 ..................................................... 18 6-3 .............................................. Deleted 3-36 ..................................................... 18 7-1 .................................................. 18 3-37 ..................................................... 18 7-2 ................................................. 18 3-38 ..................................................... 18 7-3 ................................................. 18 3-39 ..................................................... 18 7-4 ................................................. 18 3-40 ..................................................... 18 7-5 ................................................. 18 3-41 ..................................................... 18 7-6 ................................................. 18 3-42 ..................................................... 18 7-7 .............................................. Deleted 3-43 ..................................................... 18 8-1 .................................................. 18 3-44 .... ..................... 18 8-2 ................................................. 18 3-45 ......................... 18 8-3 ................................................. 18 3-46 ......... .... ........ 18 8-4 ................................................. 18 3-47 ..................................................... 18 8-5 ................................................. 18 3-48 ..................................................... 18 8-6 ................................................. 18 3-49 ..................................................... 18 8-7 ................................................. 18 3-50 ............................................ Deleted 8-8 ................................................. 18 3-51 ............................................ Deleted 8-9 ................................................. 18 3-52 ............................................ Deleted 8-10 ................................................. 18 3-53 ............................................ Deleted 8-11 ................................................ 18 3-54 ............................................ Deleted 8-12 ................................................. 18 3-55 ............................................ Deleted 8-13 ............................................... 18 Deleted 8-14 ............................................... 18 3-56 ............................................

3-57 ............................................ Deleted 8-15 ............................................... 18 3-58 ............................................ Deleted 8-16 ............................................... 18 4-1 ....................................................... 18 8-17 ................................................. 18 4-2 ....................................................... 18 8-18 ............................................ Deleted 4-3 ....................................................... 18 9-1 .................................................. 18 4-4 ....................................................... 18 9-2 ................................................. 18 4-5 ....................................................... 18 9-3 ................................................. 18 18 9-4 ................................................. 18 4-6 .......................................................

18 9-5 ................................................. 18 4-7 .......................................................

18 9-6 ................................................. 18 4-8 .......................................................

4-9 ....................................................... 18 9-7 ................................................. 18 18 9-8 ................................................. 18 4-10 .....................................................

18 9-9 ................................................. 18 4-11 .....................................................

18 9-10 .................................................... 18 4-12 .........................

18 9-11 ................................................ 18 4-13 .....................................................

4-14 ..................................................... 18 9-12 ................................................. 18 4-15 ..................................................... 18 9-13 ................................................. 18 18 9-14 ............................................... 18 4-16 ....................................................

2 of 3 Rev. 19

VEGP ODCM PAGE REV PAGE REV 9-15 ................................................. 18 9-34 ................................................. 18 9-16 ................................................. 18 9-35 ................................................. 18 9-17 ................................................. 18 9-36 ................................................. 18 9-18 ................................................. 18 9-37 ................................................. 18 9-19 ................................................. 18 9-38 ................................................. 18 9-20 ................................................. 18 9-39 ................................................. 18 9-21 ................................................. 18 9-40 ................................................. 18 9-22 ................................................. 18 9-41 ................................................. 18 9-23 ................................................. 18 9-42 ................................................. 18 9-24 ................................................. 18 9-43 ............................................ Deleted 9-25 ................................................. 18 9-44 ............................................ Deleted 9-26 ................................................. 18 9-45 ............................................ Deleted 9-27 .................................................. 18 10-1 ................................................. 18 9-28 .................................................. 18 10-2 ................................................. 18 9-29 ................................................. 18 10-3 ................................................. 18 9-30 ................................................. 18 10-4 ............................................... 18 9-31 ................................................. 18 10-5 ............................................... 18 9-32 ................................................. 18 10-6 ............................................... 18 9-33 ................................................. 18 10-7 ............................................ Deleted s:\vogtle\odcn*\Epi.doc i-iev. iti Rev. 19u 3 of 33

SOUTHERN NUCLEAR COMPANY VOGTLE ELECTRIC GENERATING PLANT- UNITS 1 AND 2 NRC DOCKET NOS. 50-424 AND 50-425 FACILITY OPERA TING LICENSE NOS. NPF-68 AND NPF-81 ANNUAL RADIOACTIVE EFFLUENTRELEASE REPORT FOR JANUARY 12001 TO DECEMBER 31, 2001 Page 1 of 84

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT - 2001 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Liquid Effluents 8 1.1 Regulatory Requirements 8 1.1.1 ConcentrationLimits 8 1.1.2 Dose Limits 8 1.2 Effluent ConcentrationLimit 8 1.3 Measurementand Approximations of Total 9 Radioactivity 1.3.1 Total Radioactivity Determination 9 1.3.2 Total ErrorEstimation 11 1.4 Liquid Effluent Release Data 12 1.5 RadiologicalImpact Due to Liquid Releases 12 1.6 Liquid Effluents - Batch Releases 12 1.7 Liquid Effluents - Abnormal Releases 12 2.0 Gaseous Effluents 34 2.1 Regulatory Requirements 34 2.1.1 Dose Rate Limits 34 Page 2 of 84

SECTION TITLE PAGE 2.1.2 Air Doses Due to Noble Gases in Gaseous Releases 34 2.1.3 Doses to a Member of the Public 34 2.2 Measurements and Approximation of Total 35 Radioactivity 2.2.1 Sample Collection and Analysis 35 2.2.2 Total Quantities of Radioactivity, Dose Rates and 35 Cumulative Doses 2.2.2.1 Fissionand Activation Gases 35 2.2.2.2 Radioiodines,Tritium, and ParticulateReleases 36 2.2.2.3 Gross Alpha Release 36 2.2.3 Total ErrorEstimation 36 2.3 Gaseous Effluent Release Data 38 2.4 RadiologicalImpact Due to Gaseous Releases 39 2.5 Gaseous Effluents - Batch Releases 39 2.6 Gaseous Effluents - Abnormal Releases 39 3.0 Solid Waste 71 3.1 Regulatory Requirements 71 3.1.1 Solid Radioactive Waste System 71 3.1.2 Reporting Requirements 71 3.2 Solid Waste Data 71 Page 3 of 84

SECTION TITLE PAGE 4.0 Doses to Members of the Public Inside the Site 76 Boundary 4.1 Regulatory Requirements 76 4.2 Demonstrationof Compliance 76 5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 80 5.1 Regulatory Requirements 80 5.2 Demonstrationof Compliance 80 6.0 MeteorologicalData 80 7.0 ProgramDeviations 80 7.1 Inoperable Liquid or Gaseous Effluent Monitoring 80 Instrumentation 7.1.1 Regulatory Requirement 80 7.1.2 Descriptionof Deviations 80 7.2 Tanks Exceeding Curie Content Limits 81 7.2.1 Regulatory Requirements 81 7.2.2 Descriptionof Deviations 81 8.0 Changes to the Vogtle Electric GeneratingPlant 81 Offsite Dose CalculationManual (ODCM) 8.1 Regulatory Requirement 81 8.2 Descriptionof Changes 81 9.0 Major Changes to the Liquid, Gaseous,or Solid 82 Radwaste Treatment System 9.1 Regulatory Requirements 82 9.2 Descriptionof Major Changes 83 9.3 Addendum to 2000 Report 84 Page 4 of 84

VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENTRELEASE REPORT- 2001 TABLE LIST OF TABLES PAGE 1-1A Liquid Effluents - Summation of All Releases Unit 1 13 (Quarters1, 2, 3, and 4) 1-1B Liquid Effluents - Summation of All Releases Unit 2 15 (Quarters1, 2, 3, and 4) 1-1C Liquid Effluents - Summation of All Releases Site 17 (Quarters1, 2, 3, and 4) 1-2A Liquid Effluents - Unit 1 (Quarters1, 2, 3, and 4) 19 1-2B Liquid Effluents - Unit 2 (Quarters1, 2, 3, and 4) 21 1-2C Liquid Effluents - Site (Quarters1, 2, 3, and 4) 23 1-3A Doses to a Member of the Public Due to Liquid 25 Releases Unit 1 (Quarters 1, 2, 3, and 4) 1-3B Doses to a Member of the PublicDue to Liquid 27 Releases Unit 2 (Quarters1, 2, 3, and 4) 1-4 Minimum Detectable ConcentrationLiquid Sample 29 Analysis 1-5A Liquid Effluents - Batch Release Summary Unit 1 30 1-5B Liquid Effluents - Batch Release Summary Unit 2 31 1-6A Liquid Effluents - Abnormal Release Summary Unit 1 32 Page 5 of 84

TABLE LIST OF TABLES PAGE 1-6B Liquid Effluents - Abnormal Release Summary Unit 2 33 2-1A Gaseous Effluents - Summation of All Releases - 40 Unit 1 (Quarters1, 2, 3, and 4) 2-1B Gaseous Effluents - Summation of All Releases - 42 Unit 2 (Quarters1, 2, 3, and 4) 2-1C Gaseous Effluents - Summation of All Releases - 44 Site (Quarters1, 2, 3, and4) 2-2A Gaseous Effluents - Mixed Mode Releases Unit 1 46 (Quarters1, 2, 3, and 4) 2-2B Gaseous Effluents - Mixed Mode Releases Unit 2 48 (Quarters1, 2, 3, and 4) 2-2C Gaseous Effluents - Mixed Mode Releases Site 50 (Quarters1, 2, 3, and 4) 2-3A Gaseous Effluents - GroundLevel Releases Unit 1 52 (Quarters1, 2, 3, and 4) 2-3B Gaseous Effluents - GroundLevel Releases Unit 2 54 (Quarters1, 2, 3, and 4) 2-3C Gaseous Effluents - GroundLevel Releases Site 56 (Quarters1, 2, 3, and 4) 2-4A Air Doses Due to Noble Gases in Gaseous Releases 58 Unit 1 (Quarters1, 2, 3, and 4) 2-4B Air Doses Due to Noble Gases in Gaseous Releases 60 Unit 2 (Quarters1, 2, 3, and 4) 2-5A Doses to a Member of the Public Due to Radioiodines, 62 Tritium, and Particulatesin Gaseous Releases Unit 1 (Quarters1, 2, 3, and 4)

Page 6 of 84

TABLE LIST OF TABLES PAGE 2-5B Doses to a Member of the Public Due to Radioiodines, 64 Tritium, and Particulatesin Gaseous Releases Unit 2 (Quarters1, 2, 3, and 4) 2-6 Minimum Detectable Concentration- Gaseous Sample 66 Analysis 2-7A Gaseous Effluents - Batch Release Summary Unit 1 67 2-7B Gaseous Effluents - Batch Release Summary Unit 2 68 2-8A Gaseous Effluents - Abnormal Release Summary 69 Unit 1 2-8B Gaseous Effluents - Abnormal Release Summary 70 Unit 2 3-1 Solid Waste and IrradiatedFuel Shipments 72 4-1 Doses to a Member of the Public Due to Activities 78 Inside the Site Boundary Page 7 of 84

1.0 Liquid Effluents 1.1 Regulatory Requirements 1.1.1 Concentration Limits In accordance with Technical Specification 5.5.4.b, the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited at all times to ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 1 E-04 gCi/ml total activity.

1.1.2 Dose Limits The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shall be limited as follows:

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 for determining the allowable liquid radwaste release rates and concentrations for the principal gamma emitters, 1-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10 CFR Part 20, Appendix B, Table 2, Column 2. A tolerance factor of up to 10 is utilized to allow flexibility in establishing practical monitor set points which can 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 1 E-04 giCVml total activity.

For gross alpha in liquid radwaste, the ECL is 2 E-09 gCi/ml.

For all the above radionuclides or categories of radioactivity, the overall ECL fraction is determined in accordance with 10 CFR Part 20, Appendix B. The method utilizing the ECL fraction to determine release rates and liquid radwaste effluent radiation monitor set points is described in Subsection 1.3 of this report.

Page 8 of 84

1.3 Measurements and Approximations of Total Radioactivity 1.3.1 Total Radioactivity Determination Prior to the release of any tank containing liquid radwaste, and following the required recirculations, samples are collected and analyzed in accordance with the Offsite Dose Calculation Manual (ODCM) Table 2-3 "Radioactive Liquid Waste Sampling and Analysis Program". A sample from each tank which is planned for release is analyzed for principal gamma emitters, 1-131, and dissolved and entrained noble gases by gamma spectroscopy. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from the tanks, which are released. Liquid radwaste sample analyses are performed as follows:

MEASUREMENT FREQUENCY METHOD

1. Gamma Isotopic Each Batch Gamma Spectroscopy with computerized data reduction.

2. Dissolved or entrained Each Batch Gamma Spectroscopy noble gases with computerized data reduction

3. Tritium Monthly Distillation and Composite liquid scintillation counting

4. Gross Alpha Monthly Gas flow proportional Composite counting

5. Sr-89 & Sr-90 Quarterly Chemical separation Composite and gas flow proportional or scintillation counting

6. Fe-55 Quarterly Chemical separation Composite and liquid scintillation counting Page 9 of 84

1.3.1 Total Radioactivity Determination cont'd Gamma isotopic measurements are performed using germanium detectors with a resolution of 2.1 keV or lower. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and a quantitative reduction or MDC calculation is performed. This ensures that the MDC's are met for the nuclides specified in ODCM Chapter 10 (i.e., Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 34, Cs-1 37, Ce-1 41 and Ce-1 44). 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 in the spectrum where the peak for that radionuclide would be located, if present.

Tritium, Gross Alpha, Sr-89, Sr-90 and Fe-55 are, in some cases, analyzed offsite.

ECL fraction is determined using radionuclide concentrations of a tank planned for release, the most current results available for tritium, gross alpha, Sr-89, Sr-90 and Fe-55 and the corresponding ECL values.

This ECL fraction is used, with appropriate safety factors, tolerance factors, and the minimum assured dilution stream flow to calculate maximum permissible release rates and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of the Offsite Dose Calculation Manual (ODCM) are not exceeded.

A monitor reading in excess of the calculated setpoint results in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the minimum assured dilution flow 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. Ifthe release is not permissible, appropriate warnings will be displayed on the computer screen. Ifthe release is permissible, it is approved by the Chemistry Department and sent to the Operations Department for approval and release. When the release is completed, the necessary data from the release (i.e., release volume, etc.) are provided by 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 the actual release rates, release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

Typically achieved liquid effluent sample analyses minimum detectable concentrations are reported in Table 1-4.

Page 10 of 84

1.3.2 Total Error Estimation The total or maximum error associated with the effluent measurement includes the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error is not suggested. The objective should be to obtain an overall estimate of the error associated with measurements of radioactive materials released in liquid effluents.

a. Fission and activation total release was calculated from sample analysis results and release point flow rates.

Sampling and statistical error 10%

Counting Equipment Calibration 10%

Tank Volumes and System Flow Rates 20%

TOTAL ERROR 40%

b. Total Tritium release was calculated from sample analysis results and release point volumes.

Sampling and statistical errors 10%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 40%

c. Dissolved and entrained gases were calculated from sample analysis results and release point volumes.

Sampling and statistical error 20%

Counting equipment calibration 10%

Tank volumes and system flow rate 20%

TOTAL ERROR 50%

d. Gross alpha radioactivity was calculated from sample analysis results and release point volumes.

Sampling and statistical error 10%

Counting Equipment calibration 10%

Tank volumes and system flowrates 20%

TOTAL ERROR 40%

Page 11 of 84

1.3.2 Total Error Estimation cont'd

e. 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%

f. Volume of dilution water used was calculated from flow totalizers and pump discharge flow rates and times.

Flow totalizer error 10%

Operator interpretation of gauge 10%

TOTAL ERROR 20%

g. Gross alpha, Sr-89, Sr-90, Fe-55 and H-3 radioactivity has an additional error associated with sample compositing.

Compositing sample error 5%

1.4 Liquid Effluent Release Data Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Tables 1-1A, 1-1 B, 1-1C, 1-2A, 1-2B and 1-2C. Data is presented on a quarterly basis as required by Regulatory Guide 1.21 for all four quarters.

1.5 Radiological Impact 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 presented in Table 1-3A for Unit 1 and 1-3B for Unit 2, for all four quarters.

1.6 Liquid Effluents - Batch Releases Batch release information for liquid effluents is presented in Table 1-5A for Unit 1 and Table 1-5B for Unit 2.

1.7 Liquid Effluents - Abnormal Releases There were no abnormal releases for this reporting period.

Page 12 of 84

TABLE I-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.15E-02 1.63E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.40E-07 6.79E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 1.31E+02 1.64E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.59E-04 6.83E-04

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 4.15E-04 0.00E+00 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.40E-09 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 1.21E-05 1.02E-06 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 5.67E+05 6.17E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 1.72E+08 2.39E+08 20 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 13 of 84

TABLE 1-lA Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.76E-02 9.87E-03 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 8.14E-08 5.00E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 1.69E+02 9.68E+01 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.82E-04 4.91E-04

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.09E-05 1.20E-05 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.05E-11 6.10E-11

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OQE+00 0.OOE+00 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 4.86E+05 3.42E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 2.16E+08 1.97E+08 20 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 14 of 84

TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2001 Ending : 30-Jun-2001 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 8.38E-02 1.70E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.84E-07 6.46E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 5.90E+02 2.74E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.30E-03 1.04E-03

~-------------------------------------------------------------------------------

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 4.11E-04 0.00E+00 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.04E-10 0.00E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 1.04E+06 5.57E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 4.54E+08 2.63E+08 20 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 15 of84

TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Summation of All Releases Unit: 2 Starting : l-Jul-2001 Ending : 31-Dec-2001 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 2.55E-02 8.14E-03 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.60E-07 1.38E-07

3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 4.79E+01 2.05E+01 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 4.89E-04 3.49E-04

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 0.OOE+00 0.00E+00 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 0.OOE+00 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.00E+00 0.00E+00 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.90E+05 1.53E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 9.77E+07 5.87E+07 20 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 16 of 84

TABLE 1-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Summation of All Releases Unit: Site Starting l-Jan-2001 Ending : 30-Jun-2001 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 1.25E-01 3.33E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 2.OOE-07 6.62E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 7.21E+02 4.37E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.15E-03 8.69E-04

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 8.26E-04 0.OOE+00 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.32E-09 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 1.21E-05 1.02E-06 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 1.61E+06 1.17E+06 20 F. VOLUME OF DILUTION WATER USED LITERS 6.26E+08 5.02E+08 20 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Page 17 of84

TABLE I-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Summation of All Releases Unit: Site Starting : l-Jul-2001 Ending : 31-Dec-2001 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 4.33E-02 1.80E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 1.38E-07 7.03E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 2.17E+02 1.17E+02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 6.90E-04 4.55E-04

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 1.09E-05 1.20E-05 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 3.47E-11 4.70E-11

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.OOE+00 0.00E+00 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 7.76E+05 4.94E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 3.13E+08 2.55E+08 20 Applicable limits are expressed in terms of dose.

See Tables l-3A and 1-3B of this report.

Page 18 of 84

TABLE l-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents Unit: 1 Starting : 1-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 1

-3CRIES 00+0002-----------------------------------

H-3I CURIES I0.OOE+00 I 0.00E+00 I 1.31E+02 I 1.64E+02 I FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0.OOE+00 0. OOE+00 2.46E-06 1. 57E-06 CO-58 CURIES 0.OOE+00 0. OOE+00 1.72E-03 7.60E-04 CO-60 CURIES 0.OOE+00 0.OOE+00 1.47E-02 6. 64E-03 CR-51 CURIES 0. OOE+00 0. OOE+00 1. 30E-04 1. 85E-04 CS-134 CURIES 0. OOE+00 0. OOE+00 3 .53E-04 1. 05E-05 CS-137 CURIES 0. OOE+00 0.0 0E+00 5 .23E-04 4. 90E-05 FE-55 CURIES 0. OOE+00 0. OOE+00 1. 46E-02 5.72E-03 FE-59 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 1.71E-05 MN-54 CURIES 0. OOE+00 0. OOE+00 8. 78E-04 3 .32E-04 NB-95 CURIES 0. OOE+00 0. OOE+00 2.19E-04 3 05E-05 NB-97 CURIES 0. OOE+00 0. OOE+00 9. 12E-05 1. 92E-05 SB-124 CURIES 0. OOE+00 0 OOE+00 0.OOE+00 4 05E-05 SB-125 CURIES 0.OOE+00 0. OOE+00 1.75E-03 1. 55E-03 SR-89 CURIES 0. OOE+00 0 OOE+00 3.24E-05 3 .24E-05 SR-90 CURIES 0.0 0E+00 0.0OE+00 4. 59E-05 0. OOE+00 SR-92 CURIES 0. OOE+00 0. OOE+00 3.18E-06 5. 89E-06 TE-125M CURIES 0. OOE+00 0. OOE+00 6.45E-03 8. 18E-04 Y-93 CURIES 0. OOE+00 0.OOE+00 0. OOE+00 4. OlE-05 ZR-95 CURIES 0. OOE+00 0. OOE+00 5.78E-05 0. OOE+00 TOTALS I CURIES I 0.00E+00 I0.00E+00 I4.15E-02 I1.63E-02 DISSOLVED AND ENTRAINED GASES TOTALS I CURIES I 0.00E+00 I 0.00E+00 I 0.00E+00 I 0.00E+00 I G-ALPHA I CURIES I0.00E+00 I0.00E+00 I1.21E-05 I1.02E-06 I zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 19 of 84

TABLE 1-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 CONTINUOUS MODE I BATCH MODE NUCLIDE I UNIT QUARTER 3 QUARTER 4 IQUARTER 3 1QUARTER 4 H-3 I CURIES 0.OOE+00 I 0.00E+00 1.69E+02 9.68E+01 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 1.48E-06 CO-58 CURIES 0.OOE+00 0.OOE+00 5.09E-04 2.OOE-04 CO-60 CURIES 0.OOE+00 0.OOE+00 5.11E-03 3.71E-03 CS-134 CURIES 0.OOE+00 0.OOE+00 7.90E-05 0.OOE+00 CS-137 CURIES 0.OOE+00 0.OOE+00 2.01E-04 2.76E-06 FE-55 CURIES 0.OOE+00 0.OOE+00 9.87E-03 3.02E-03 FE-59 CURIES 0.OOE+00 0.OOE+00 3.74E-06 0.OOE+00 MN-54 CURIES 0.OOE+00 0.OOE+00 3.55E-04 3.53E-04 NB-95 CURIES 0.OOE+00 0.00E+00 0.OOE+00 4.52E-05 NB-97 CURIES O.OOE+00 O.OOE+00 2.16E-05 O.OOE+00 SB-124 CURIES O.OOE+00 O.OOE+00 1.58E-05 O.OOE+00 SB-125 CURIES O.OOE+00 O.OOE+00 1.41E-03 2.53E-03 SR-89 CURIES O.OOE+00 O.OOE+00 O.OOE+00 5.88E-06 SR-90 CURIES O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 CURIES O.OOE+00 O.OOE+00 5.83E-06 O.OOE+00 TOTALS I CURIES O.OOE+00 I O.OOE+00 I 1.76E-02 9.87E-03 DISSOLVED AND ENTRAINED GASES XE-133 I CURIES I O.OOE+00 O.OOE+00 I O.OOE+00 1.20E-05 TOTALS I CURIES I O.OOE+00 I O.OOE+00 I O.OOE+00 1.20E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 20 of 84

TABLE 1-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents Unit: 2 Starting : l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2

-3URIS 0.00+00000E2-----------------------------------

H-3 ICURIES I 0.OOE+00 I 0.OOE+00 I .90E+02 I2.74E+02 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0.OOE+00 0. OOE+00 4. 88E-06 0. OOE+00 CO-58 CURIES 0. OOE+00 0 OOE+00 2 .27E-03 1. 02E-03 CO-60 CURIES 0. OOE+00 0 OOE+00 1.45E-02 5. 92E-03 CR-51 CURIES 0. OOE+00 0. OOE+00 6. 89E-04 3.13E-04 CS-134 CURIES 0. OOE+00 0. OOE+00 1. 09E-03 6.73E-06 CS-137 CURIES 0. OOE+00 0. OOE+00 1.75E-03 4. 05E-05 FE-55 CURIES 0. OOE+00 0. OOE+00 9. 62E-03 8.84E-03 FE-59 CURIES 0.OOE+00 0. OOE+00 1.31E-05 0.OOE+00 1-133 CURIES 0.OOE+00 0. OOE+00 3.57E-05 0. OOE+00 MN-54 CURIES 0.OOE+00 o.OOE+00 1.24E-03 3 . 09E-04 NB-95 CURIES 0. OOE+00 0.OOE+00 3 .28E-04 2 . 16E-06 NB-97 CURIES 0. OOE+00 0.OOE+00 2 .65E-05 0. OOE+00 SB-122 CURIES 0. OOE+00 0. OOE+00 4. 65E-06 0. OOE+00 SB-124 CURIES 0. OOE+00 0.OOE+00 9. 91E-05 0. OOE+00 SB-125 CURIES 0. OOE+00 0. OOE+00 1. 02E-02 5. 51E-04 SR-89 CURIES 0.OOE+00 0. OOE+00 1.76E-04 1.12E-05 SR-90 CURIES 0.OOE+00 0. OOE+00 1. OOE-04 7.38E-07 SR-92 CURIES 0.OOE+00 o.OOE+00 6.31E-06 0. OOE+00 TE-125M CURIES 0. OOE+00 0. OOE+00 4.15E-02 0. OOE+00 ZR-95 CURIES 0. OOE+00 0.OOE+00 1.40E-04 0. OOE+00 TOTALS I CURIES I 0.00E+00 I 0.00E+00 I8.37E-02 I1.70E-02 DISSOLVED AND ENTRAINED GASES XE-133 CURIES I 0.00E+00 I 0.00E+00 3.73E-04 0 .00E+00 XE-135 CURIES 1 0.00E+00 1 0.00E+00 I3.83E-05 0.00E+00 TOTALS I CURIES I 0.00E+00 I 0.00E+00 I4.11E-04 I 0.00E+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 21 of 84

TABLE 1-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents Unit: 2 Starting l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE i BATCH MODE NUCLIDE I UNIT IQUARTER 3 QUARTER 4 IQUARTER 3 1QUARTER 4 H-3 I CURIES i 0.OOE+00 I 0.00E+00 I 4.79E+01 I 2.05E+01 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0 OOE+00 0. OOE+00 0 OOE+00 4.24E-06 CO-58 CURIES 0 OOE+00 0. OOE+00 3. 73E-04 8. 75E-05 CO-60 CURIES 0 .OOE+00 0. OOE+00 4. 19E-03 1. 69E-03 CR-51 CURIES 0 OOE+00 0. OOE+00 2. 05E-05 0 OOE+00 CS-134 CURIES 0. OOE+00 0. OOE+00 1. 26E-05 0 OOE+00 CS-137 CURIES 0. OOE+00 0 OOE+00 6. 67E-05 8. 06E-06 FE-55 CURIES 0. OOE+00 0. OOE+00 2. 04E-02 5. 03E-03 MN-54 CURIES 0. OOE+00 0.OOE+00 1. 53E-04 8. 89E-05 NB-95 CURIES 0.OOE+00 0 OOE+00 8. 71E-06 0. OOE+00 SB-124 CURIES 0. OOE+00 0.OOE+00 1. 03E-05 0. OOE+00 SB-125 CURIES 0. OOE+00 0. OOE+00 2. 84E-04 1.22E-03 SR-89 CURIES 0. OOE+00 0. OOE+00 8. 95E-06 5. 32E-06 SR-92 CURIES 0. OOE+00 0. OOE+00 2.49E-06 0. OOE+00 TOTALS I CURIES I 0.OOE+00 I 0.OOE+00 2.55E-02 8.14E-03 DISSOLVED AND ENTRAINED GASES I CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 22 of 84

TABLE 1-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents Unit: Site Starting l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT IQUARTER 1 IQUARTER 2 QUARTER 1 IQUARTER 2 H-3 I CURIES I 0.OOE+00 I 0.OOE+00 I 7.21E+02 4.37E+02 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0. OOE+00 0.OOE+00 7.34E-06 1. 57E-06 CO-58 CURIES 0. OOE+00 0.OOE+00 3 .99E-03 1.78E-03 CO-60 CURIES 0. OOE+00 0.OOE+00 2 . 92E-02 1.26E-02 CR-51 CURIES 0. OOE+00 0. OOE+00 8. 18E-04 4. 97E-04 CS-134 CURIES 0. OOE+00 0. OOE+00 1. 44E-03 1.72E-05 CS-137 CURIES 0. OOE+00 0. OOE+00 2 .27E-03 8. 95E-05 FE-55 CURIES 0.OOE+00 0. OOE+00 2. 42E-02 1.46E-02 FE-59 CURIES 0.OOE+00 0. OOE+00 1.31E-05 1.71E-05 1-133 CURIES 0.OOE+00 0.OOE+00 3.57E-05 0.OOE+00 MN-54 CURIES 0. OOE+00 0. OOE+00 2. 11E-03 6.41E-04 NB-95 CURIES 0. OOE+00 0. OOE+00 5.47E-04 3 . 27E-05 NB-97 CURIES 0. OOE+00 0. OOE+00 1. 18E-04 1.92E-05 SB-122 CURIES 0. OOE+00 0. OOE+00 4. 65E-06 0. OOE+00 SB-124 CURIES 0.OOE+00 0. OOE+00 9. 91E-05 4. 05E-05 SB-125 CURIES 0.OOE+00 0. OOE+00 1.19E-02 2. 1OE-03 SR-89 CURIES 0. OOE+00 0.OOE+00 2.08E-04 4.36E-05 SR-90 CURIES 0.OOE+00 0. OOE+00 1.46E-04 7.38E-07 SR-92 CURIES 0. OOE+00 0. OOE+00 9.49E-06 5. 89E-06 TE-125M CURIES 0.OOE+00 0. OOE+00 4.79E-02 8.18E-04 Y-93 CURIES 0. OOE+00 0. OOE+00 0. OOE+00 4. 01E-05 ZR-95 CURIES 0.OOE+00 0.OOE+00 1. 98E-04 0. OOE+00 TOTALS I CURIES 0.OOE+00 I 0.OOE+00 I 1.25E-01 3.33E-02 I DISSOLVED AND ENTRAINED GASES XE-133 CURIES 0.OOE+00 0.OOE+00 3.73E-04 0.OOE+00 XE-135 CURIES 0.OOE+00 0.OOE+00 3.83E-05 0.OOE+00 TOTALS CURIES I 0.OOE+00 I 0.OOE+00 I 4.11E-04 0.OOE+00 G-ALPHA CURIES I O.OOE+00 I 0.OOE+00 I 1.21E-05 I 1.02E-06 I zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 23 of 84

TABLE 1-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents Unit: Site Starting : l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDE I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 1QUARTER 4 H-3 I CURIES I 0.OOE+00 I 0.OOE+00 I 2.17E+02 1.17E+02 FISSION & ACTIVATION PRODUCTS CO-57 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 5.72E-06 CO-58 CURIES 0.OOE+00 0.OOE+00 8.82E-04 2.87E-04 CO-60 CURIES 0.OOE+00 0.OOE+00 9.30E-03 5.40E-03 CR-51 CURIES 0.00E+00 0.OOE+00 2.05E-05 0.OOE+00 CS-134 CURIES 0.OOE+00 0.OOE+00 9.16E-05 0.00E+00 CS-137 CURIES 0.OOE+00 0.OOE+00 2.67E-04 1.08E-05 FE-55 CURIES 0.OOE+00 0.OOE+00 3.03E-02 8.05E-03 FE-59 CURIES 0.OOE+00 0.O0E+00 3.74E-06 0.OOE+00 MN-54 CURIES 0.OOE+00 0.OOE+00 5.08E-04 4.41E-04 NB-95 CURIES 0.O0E+00 0.OOE+00 8.71E-06 4.52E-05 NB-97 CURIES 0.OOE+00 0.OOE+00 2.16E-05 0.OOE+00 SB-124 CURIES 0.OOE+00 0.OOE+00 2.61E-05 0.OOE+00 SB-125 CURIES 0.OOE+00 0.OOE+00 1.70E-03 3.75E-03 SR-89 CURIES 0.OOE+00 0.OOE+00 8.95E-06 1.12E-05 SR-90 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-92 CURIES 0.OOE+00 0.OOE+00 8.31E-06 0.OOE+00 TOTALS I CURIES I 0.OOE+00 I 0.OOE+00 I 4.31E-02 1.80E-02 DISSOLVED AND ENTRAINED GASES XE-133 I CURIES I 0.OOE+00 I 0.OOE+00 0.OOE+00 1.20E-05 I TOTALS I CURIES 0.OOE+00 I 0.OOE+00 I 1.09E+00 I 1.20E-05 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 1-4 for typical minimum detectable concentrations.

Page 24 of 84

TABLE 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 01-Jan-2001 Ending: 30-Jun-2001 Cumulative Doses per Quarter Organ ODCM Units Quarter  % of Quarter  % of Limit 1 ODCM 2 ODCM Limit Limit Bone 5.0 mrem 3.28E-02 6.57E-01 3.94E-04 7.89E-03 Liver 5.0 mrem 4.75E-02 9.49E-01 3.92E-03 7.84E-02 TBody 1.5 mrem 4.38E-02 2.92E+00 3.78E-03 2.52E-01 Thyroid 5.0 mrem 3.61E-02 7.23E-01 3.42E-03 6.83E-02 Kidney 5.0 mrem 9.43E-02 1.89E+00 3.63E-03 7.27E-02 Lung 5.0 mrem 4.88E-02 9.76E-01 6.72E-03 1.34E-01 GILLI 5.0 mrem 1.16E-01 2.32E+00 4.48E-03 8.97E-02 Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 10.0 mrem 3.32E-02 3.32E-01 Liver 10.0 mrem 5.14E-02 5.14E-01 TBody 3.0 mrem 4.76E-02 1.59E+00 Thyroid 10.0 mrem 3.96E-02 3.96E-01 Kidney 10.0 mrem 9.79E-02 9.79E-01 Lung 10.0 mrem 5.55E-02 5.55E-01 GILLI 10.0 mrem 1.20E-01 1.20E+00 Page 25 of 84

TABLE 1-3A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 1 Starting: 0l-jul-2001 Ending: 31-Dec-2001 Cumulative Doses per Quarter Organ ODCM Units Quarter  % of Quarter  % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 2.81E-03 5. 63E-02 6.50E-05 1. 30E-03 Liver 5.0 mrem 7.30E-03 1. 46E-01 1.43E-03 2. 87E-02 TBody 1.5 mrem 6. 04E-03 4. 02E-01 1.42E-03 9.48E-02 Thyroid 5.0 mrem 2. 86E-03 5. 72E-02 1.37E-03 2.75E-02 Kidney 5.0 mrem 4. 32E-03 8. 63E-02 1.38E-03 2.77E-02 Lung 5.0 mrem 6. 33E-03 1.27E-01 4.45E-03 8.90E-02 GILLI 5.0 mrem 3. 83E-03 7. 66E-02 1.92E-03 3. 85E-02 Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 10.0 mrem 3.61E-02 3.61E-01 Liver 10.0 mrem 6.01E-02 6.01E-01 TBody 3.0 mrem 5.50E-02 1.83E+00 Thyroid 10.0 mrem 4.38E-02 4.38E-01 Kidney 10.0 mrem 1.04E-01 1.04E+00 Lung 10.0 mrem 6.63E-02 6.63E-01 GILLI 10.0 mrem 1.26E-01 1.26E+00 Page 26 of 84

TABLE 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jan-2001 Ending: 30-Jun-2001 Cumulative Doses per Quarter Organ ODCM Units Quarter  % of Quarter  % of Limit 1 ODCM 2 ODCM Limit Limit 5.0 mrem 1.69E-02 3.38E-01 3 .39E-0 4 6.78E-03 Bone 5.0 mrem 3.50E-02 7.01E-01 5. 51E-0 3 1.10E-01 Liver mrem 2. 83E-02 1. 89E+00 5.37E-0 3 3.58E-01 TBody 1.5 Thyroid 5.0 mrem 1.05E-02 2. 1OE-01 5. 06E-0 3 1.01E-01 Kidney 5.0 mrem 2.40E-02 4. 80E-01 5.18E-0 3 1.04E-01 Lung 5.0 mrem 2. 84E-02 5.68E-01 6.10E-0 3 1.22E-01 5.0 mrem. 1. 92E-02 3.84E-01 5.76E-0 3 1.15E-01 GILLI Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 10.0 mrem 1.72E-02 1.72E-01 Liver 10.0 mrem 4.06E-02 4.06E-01 TBody 3.0 mrem 3.37E-02 1.12E+00 Thyroid 10.0 mrem 1.55E-02 1.55E-01 Kidney 10.0 mrem 2.92E-02 2.92E-01 Lung 10.0 mrem 3.45E-02 3.45E-01 GILLI 10.0 mrem 2.49E-02 2.49E-01 Page 27 of 84

TABLE 1-3B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO LIQUID RELEASES Unit: 2 Starting: 01-Jul-2001 Ending: 31-Dec-2001 Cumulative Doses per Quarter Organ ODCM Units Quarter  % of Quarter  % of Limit 3 ODCM 4 ODCM Limit Limit Bone 5.0 mrem 7. 84E-04 1. 57E-02 9. 80E-05 1.96E-03 5.0 mrem 1. 96E-03 3 . 92E-02 4. 07E-04 8.14E-03 Liver TBody 1.5 mreem 1. 61E-03 1.08E-01 3.71E-04 2 . 48E-02 5.0 mrem 9.35E-04 1. 87E-02 3.12E-04 6.25E-03 Thyroid 5.0 mrem 1.23E-03 2.46E-02 3.33E-04 6.66E-03 Kidney 5.0 mrem 1. 79E-03 3.58E-02 1. 89E-03 3.78E-02 Lung 5.0 mrem 1. 58E-03 3.17E-02 5.72E-04 1. 14E-02 GILLI Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 10.0 mrem 1. 81E-02 1. 81E-01 Liver 10.0 mrem 4.29E-02 4.29E-01 TBody 3.0 mrem 3.57E-02 1. 19E+00 Thyroid 10.0 mrem 1.68E-02 1.68E-01 Kidney 10.0 mrem 3 . 08E-02 3 . OBE-01 Lung 10.0 nirem 3. 82E-02 3. 82E-01 GILLI 10.0 mrem 2.71E-02 2.71E-01 Page 28 of 84

TABLE 1-4 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 MINIMUM DETECTABLE CONCENTRATIONS - LIQUID SAMPLE ANALYSES JANUARY 2001 - DECEMBER 2001 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of liquid radwaste samples.

RADIONUCLIDE MDC UNITS Mn-54 2.73E-08 pCi/mI Fe-59 8.33E-08 RCi/ml Co-58 3.78E-08 iCi/ml Co-60 6.76E-08 gCi/mI Zn-65 1.32E-07 RCi/mI Mo-99 4.31 E-07 RCi/ml Cs-1 34 3.06E-08 RCi/ml Cs-1 37 4.51 E-08 gCi/ml Ce-1 41 6.99E-08 pCi/ml Ce-144 2.95E-07 RCi/mI 1-131 5.97E-08 RCi/ml Xe-1 33 9.11 E-08 RCi/mI Xe-1 35 4.27E-08 plci/ml Fe-55 1.OOE-06 iiCi/ml Sr-89 5.OOE-08 gCi/ml Sr-90 7.OOE-09 pCi/ml H-3 2.OOE-06 pCi/mi Gross Alpha 7.OOE-08 RCi/mI Page 29 of 84

TABLE 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Batch Release Summary Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 NUMBER OF BATCH RELEASES 43 5726.58 MINUTES TOTAL TIME PERIOD FOR BATCH RELEASES 336.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 133.18 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 2.00 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE TABLE 1-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Batch Release Summary Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 29 NUMBER OF BATCH RELEASES 5056.62 MINUTES TOTAL TIME PERIOD FOR BATCH RELEASES 590.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 174.37 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 1.00 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE The average flow rate of the Savannah River at Augusta for the Radioactive of Engineers Effluent Release Report period was obtained from the U.S. Army Corps Savannah District Historic Data web page http://water.sas.usace.army.mil/tdis.html.

The average flow rate for 2001 was 4198 cubic feet per sec.

Page 30 of 84

TABLE 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Batch Release Summary Unit: 2 Starting l-Jan-2001 Ending : 30-Jun-2001 NUMBER OF BATCH RELEASES 47 TOTAL TIME PERIOD FOR BATCH RELEASES 9524.17 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 671.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 202.64 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE 2.50 MINUTES TABLE 1-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Batch Release Summary Unit: 2 Starting l-Jul-2001 Ending : 31-Dec-2001 NUMBER OF BATCH RELEASES 12 TOTAL TIME PERIOD FOR BATCH RELEASES 2128.58 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 297.98 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 177.38 MINUTES 67.38 MINUTES MINIMUM TIME PERIOD FOR A BATCH RELEASE The average flow rate of the Savannah River at Augusta for the Radioactive Effluent Release Report period was obtained from the U.S. Army Corps of Engineers Savannah District Historic Data web page http://water.sas.usace.army.mil/tdis.html.

The average flow rate for 2001 was 4198 cubic feet per sec.

Page 31 of 84

TABLE 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIES TABLE 1-6A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A RELEASE 0.00 MINUTES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIES Page 32 of 84

TABLE l-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting l-Jan-2001 Ending : 30-Jun-2001 NUMBER OF RELEASES 0 RELEASES 0.00 MINUTES TOTAL TIME FOR ALL RELEASE 0.00 MINUTES MAXIMUM TIME FOR A MINUTES RELEASE 0.00 AVERAGE TIME FOR A MINUTES RELEASE 0.00 MINIMUM TIME FOR A CURIES TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 TABLE 1-6B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Liquid Effluents - Abnormal Release Summary Unit: 2 Starting : l-Jul-2001 Ending : 31-Dec-2001 NUMBER OF RELEASES 0 RELEASES 0.00 MINUTES TOTAL TIME FOR ALL MINUTES RELEASE 0.00 MAXIMUM TIME FOR A MINUTES RELEASE 0.00 AVERAGE TIME FOR A MINUTES RELEASE 0.00 MINIMUM TIME FOR A CURIES ALL RELEASES 0. OOE+00 TOTAL ACTIVITY FOR Page 33 of 84

2.0 Gaseous Effluents 2.1 Regulatory Requirements The ODCM Specifications presented in this section are for Unit 1 and Unit 2.

2.1.1 Dose Rate Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. For noble gases, Less than or equal to 500 mrems/yr. to the whole body and less than or equal to 3000 mrems/yr. to the skin and,

b. For Iodine-1 31, for Iodine-1 33, 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 Doses Due to Noble Gases in Gaseous Releases 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 Doses to a Member of the Public The dose to a MEMBER OF THE PUBLIC from Iodine-1 31, Iodine-1 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following.

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ.

b. During any calendar year: Less than or equal to 15 mrems to any organ.

Page 34 of 84

2.2 Measurements and Approximations of Total Radioactivity 2.2.1 Sample Collection and Analysis Gaseous Effluents at the Vogtle Electric Generating Plant are currently confined to six paths: plant vents (Unit 1 and Unit 2), the condenser air ejector, the steam packing exhauster systems (Unit 1 and Unit 2), Radwaste Processing Facility and the DAW (Dry Active Waste Building).

Waste gas decay tanks are batch released through the Unit 1 plant vent. The containment purges are released through their respective plant vents.

All of the paths with the exception of the DAW and RPF can be continuously monitored for gaseous radioactivity. The RPF is equipped with an integrated type sample collection device for collecting particulates. Plant vent, containment, steam jet air ejector, steam-packing exhauster are equipped with an integrated type sample collection device for collecting particulates and iodines. Samples of the DAW are collected using portable monitoring equipment during periods of operation. During this reporting period, there were no continuous radioactive releases through the condenser air ejector and the steam packing exhauster system vents. There were no releases from the DAW. Batch Waste Gas Decay Tank releases are analyzed for noble gases before each release. The containment atmosphere is analyzed for noble gases prior to each release and for tritium at least on a monthly basis.

Sample analyses results and release flow rates 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.

With each release period and batch release, radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated, along with the percent of the ODCM limits for each release for the current quarter and year.

Typically achieved minimum detectable concentrations for gaseous effluent sample analyses are reported in Table 2-6.

2.2.2 Total Quantities of Radioactivity, Dose Rates, and Cumulative Doses The methods for determining release quantities of radioactivity, dose rates, and cumulative doses are as follows:

2.2.2.1 Fission and Activation Gases The released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample. Dose rates due to noble gases, radioiodines, tritium, Page 35 of 84

2.2.2.1 Fission and Activation Gases cont'd and particulates are calculated. Calculated dose rates are compared to the dose rate limits specified in ODCM 3.1.2 for noble gases, radioiodines, 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 with 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.

2.2.2.2 Radiolodines, Tritium and Particulate Releases The released quantities of radioiodines, tritium and particulates are determined using the weekly samples and release flow rates for the two plant vent release points.

After each quarter, the particulate filters from each plant vent are combined, for strontium analysis. Strontium concentrations are input to the composite file of the computer to be used for release dose rate and individual dose calculations.

Doses to a Member of the Public due to radioiodines, tritium and particulates are calculated for the controlling receptor, which is described in Table 3-7of the ODCM. Doses are calculated for each release period, and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative doses are compared to the dose limits specified in ODCM 3.1.4.

Current percent of ODCM limits are shown in this report for each release period.

2.2.2.3 Gross Alpha Release The gross alpha release is calculated each month by counting the particulate filters for each week for gross alpha activity. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is used for release calculations.

2.2.3 Total Error Estimation The total or maximum error associated with the effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed statistical evaluation of error are not suggested.

Page 36 of 84

2.2.3 Total Error Estimation cont'd 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.

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.

a. 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%

b. 1-131 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%

c. 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%

d. 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%

Page 37 of 84

2.2.3 Total Error Estimation cont'd

e. 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%

2.3 Gaseous Effluent Release Data Regulatory Guide 1.21 Tables 1A, 1B, and 1C are found in this report as Tables 2-1 A, 2-1 B, 2-1 C, 2-2A, 2-2B, 2-2C, 2-3A, 2-3B, and 2-3C. Data are presented on a quarterly basis as required by Regulatory Guide 1.21.

To complete table 2-1 A, and 2-1 B, the total release for each of the four categories (fission and activation gases, iodines, particulates, and tritium) was divided by the number of seconds in the quarter to obtain a release rate in gCi/second for each category. However, the percent of the ODCM limits are not applicable because VEGP has no curie limits for gaseous releases. Applicable limits are expressed in terms of dose. Noble gases are limited as specified in ODCM 3.1.2. The other three categories (tritium, radioiodines, and particulates) are limited as a group as specified in ODCM 3.1.2.

Dose rates due to noble gas releases and due to radioiodines, tritium, and particulate releases were calculated as part of the pre-release and post-release permits. No limits were exceeded for this reporting period.

Gross alpha radioactivity is reported in Table 2-1A, and 2-1 B 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 2-4A, and 2-4B along with the percent of the ODCM limits.

Limits for cumulative doses to a Member of the Public due to radioiodines, tritium and particulates, are specified in ODCM 3.1.4. Cumulative doses to a Member of the Public are presented in Table 2-5A, and 2-5B along with percent of ODCM limits.

Page 38 of 84

2.4 Radiological Impact Due to Gaseous Releases Dose rates due to the release of noble gases were calculated for the site in accordance with ODCM 3.4.1.1. Dose rates due to radioiodines, tritium, and particulates in gaseous releases were calculated in accordance with ODCM 3.4.1.2.

Dose rates were calculated as part of pre-release and post release permits, 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 2-4A and 2-4B.

Cumulative doses to a Member of the Public were calculated for each unit in accordance with ODCM 3.4.3. These results are presented in Tables 2-5A and 2-5B.

Dose rates and doses were calculated using the methodology presented in the Vogtle Electric Generating Plant Offsite Dose Calculation Manual.

2.5 Gaseous Effluents - Batch Releases Other data pertinent to batch releases of radioactive gaseous effluent from Unit 1 and Unit 2 are listed in Table 2-7A and 2-7B.

2.6 Gaseous Effluents - Abnormal Releases Condition Report # 2001001003 was written on 4/25/2001 for an unplanned release that happened on 4/12/2001. This resulted with a loss of 25 psig of WGDT #4 (2-1902-V6-004) contents. Since no alarm came in on 2RE 12442C/1 2444C, no ODCM limits were exceeded. Also due to the fact that no samples were obtained during the incident, curie content of this incident could not be determined.

Page 39 of 84

TABLE 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.35E+00 6.54E+00 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.73E-01 8.32E-01

3. PERCENT OF APPLICABLE LIMIT  %*

• B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 1.24E-06 0.OOE+00 100

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.60E-07 0.OOE+00

3. PERCENT OF APPLICABLE LIMIT  %*

• C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 2.59E-06 2.14E-07 90

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.33E-07 2.72E-08

3. PERCENT OF APPLICABLE LIMIT  %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.00E+00 D. TRITIUM

1. TOTAL RELEASE CURIES 1.66E+01 4.53E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.14E+00 5.76E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 40 of 84

TABLE 2-1A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Summation of All Releases Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 6.64E-02 4.17E+00 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.35E-03 5.24E-01

3. PERCENT OF APPLICABLE LIMIT  %*

• B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 3.68E-06 1.83E-06 100

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.63E-07 2.30E-07

3. PERCENT OF APPLICABLE LIMIT  %*

• C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 1.79E-06 1.31E-06 90

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.25E-07 1.65E-07

3. PERCENT OF APPLICABLE LIMIT  %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.00E+00 D. TRITIUM

1. TOTAL RELEASE CURIES 5.82E+01 3.61E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.32E+00 4.54E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 41 of84

TABLE 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : l-Jan-2001 Ending : 30-Jun-2001 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 9.28E-02 2.30E-01 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.19E-02 2.92E-02

3. PERCENT OF APPLICABLE LIMIT  %*

• B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 9.36E-06 6.00E-07 100

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.20E-06 7.63E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 6.99E-06 3.55E-06 90

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.99E-07 4.51E-07

3. PERCENT OF APPLICABLE LIMIT  %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.00E+00 D. TRITIUM

1. TOTAL RELEASE CURIES 9.63E+00 1.93E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.24E+00 2.45E+00

3. PERCENT OF APPLICABLE LIMIT *

• Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 42 of 84

TABLE 2-1B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Summation of All Releases Unit: 2 Starting : l-Jul-2001 Ending : 31-Dec-2001 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 4.39E-02 6.29E-02 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 5.53E-03 7.91E-03

3. PERCENT OF APPLICABLE LIMIT  %*

• B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 2.33E-07 0.00E+00 100

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 2.93E-08 0.00E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 5.33E-06 1.10E-07 90

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 6.70E-07 1.39E-08

3. PERCENT OF APPLICABLE LIMIT  %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 2.73E+00 1.lE+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.44E-01 1.40E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 43 of 84

TABLE 2-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Summation of All Releases Unit: Site Starting : l-Jan-2001 Ending : 30-Jun-2001 TYPE OF EFFLUENT UNITS QUARTER 1 QUARTER 2 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.44E+00 6.77E+00 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.85E-01 8.61E-01

3. PERCENT OF APPLICABLE LIMIT  %*

• B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 1.06E-05 6.00E-07 100

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.36E-06 7.63E-08

3. PERCENT OF APPLICABLE LIMIT  %*

• C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 9.58E-06 3.76E-06 90

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.23E-06 4.78E-07

3. PERCENT OF APPLICABLE LIMIT  %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.OOE+00 0.OOE+00 D. TRITIUM

1. TOTAL RELEASE CURIES 2.62E+01 6.45E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 3.37E+00 8.21E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 44 of 84

TABLE 2-IC Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Summation of All Releases Unit: Site Starting l-Jul-2001 Ending : 31-Dec-2001 TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE CURIES 1.10E-01 4.23E+00 50

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 1.39E-02 5.32E-01

3. PERCENT OF APPLICABLE LIMIT  %*

• B. RADIOIODINES

1. TOTAL IODINE-131 CURIES 3.92E-06 1.83E-06 100

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 4.93E-07 2.30E-07

3. PERCENT OF APPLICABLE LIMIT  %*

• C. PARTICULATES

1. PARTICULATES(HALF-LIVES>8 DAYS) CURIES 7.12E-06 1.42E-06 90

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 8.95E-07 1.79E-07

3. PERCENT OF APPLICABLE LIMIT  %* *

4. GROSS ALPHA RADIOACTIVITY CURIES 0.00E+00 0.00E+00 D. TRITIUM

1. TOTAL RELEASE CURIES 6.09E+01 4.72E+01 40

2. AVERAGE RELEASE RATE FOR PERIOD uCi/Sec 7.66E+00 5.94E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• Applicable limits are expressed in terms of dose.

See Tables 2-4A, 2-4B, 2-5A, and 2-5B of this report.

Page 45 of 84

TABLE 2-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 FISSION GASES AR-41 CURIES 0.OOE+00 1.17E+00 5.72E-02 5.31E-02 XE-135 CURIES 0.OOE+00 2.34E-01 4.12E-04 0.OOE+00 XE-133 CURIES 0.OOE+00 5.07E+00 1 1.03E-02 4.02E-03 KR-85 CURIES 0.OOE+00 0.OOE+00 1 1.28E+00 0.OOE+00 TOTAL FOR PERIOD I CURIES 0.OOE+00 6.48E+00 I 1.35E+00 I 5.72E-02 IODINES 1-131 1 CURIES 1.24E-06 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 TOTAL FOR PERIOD I CURIES I 1.24E-06 I 0.OOE+00 0.OOE+00 I 0.OOE+00 PARTICULATES SR-89 CURIES 7.99E-08 2.14E-07 0.OOE+00 0.OOE+00 BE-7 CURIES I 2.51E-06 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD I CURIES I 2.59E-06 I 2.14E-07 I 0.OOE+00 0.OOE+00 H-3 I CURIES I 1.66E+01 I 4.53E+01 2.10E-02 6.01E-03 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 46 of 84

TABLE 2-2A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Mixed-Mode Level Releases Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 FISSION GASES AR-41 CURIES 0.OOE+00 0.OOE+00 6.05E-02 6.26E-02 XE-135 CURIES 0.00E+00 0.00E+00 I 0.OOE+00 2.01E-05 XE-133 CURIES 0.OOE+00 3.89E+00 5.87E-03 2.16E-01 TOTAL FOR PERIOD CURIES 0.OOE+00 I 3.89E+00 I 6.64E-02 I 2.78E-01 IODINES 1-133 CURIES 4.24E-05 9.42E-06 0.OOE+00 0.OOE+00 1-131 CURIES 3.68E-06 1.83E-06 0.OOE+00 0.00E+00 TOTAL FOR PERIOD I CURIES I 4.61E-05 1.12E-05 I 0.OOE+00 I 0.OOE+00 PARTICULATES SR-89 CURIES 2.05E-07 1.73E-07 O.OOE+00 0.OOE+00 BE-7 CURIES 1.59E-06 0.OOE+00 0.OOE+00 0.00E+00 CO-60 CURIES 0.OOE+00 1.14E-06 0.00E+00 0.OOE+00 TOTAL FOR PERIOD CURIES I 1.79E-06 1.31E-06 I 0.OOE+00 I 0.00E+00 H-3 CURIES I 5.82E+01 I 3.61E+01 I 1.38E-02 3.29E-02 zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 47 of 84

TABLE 2-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting : l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED UNIT IQUARTER 1 IQUARTER 2 IQUARTER 1 1QUARTER 2 1 FISSION GASES AR-41 CURIES 0.00E+00 0.OOE+00 3.72E-02 1.l1E-01 XE-135 CURIES 0.00E+00 0.OOE+00 2.34E-03 2.05E-03 XE-133 CURIES 0.OOE+00 0.00E+00 5.33E-02 1.l1E-01 TOTAL FOR PERIOD CURIES I 0.OOE+00 I 0.OOE+00 I 9.28E-02 2.24E-01 IODINES 1-133 CURIES 4.37E-05 0.OOE+00 0.00E+00 0.OOE+00 1-131 CURIES 9.36E-06 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES 5.31E-05 I 0.OOE+00 I 0.OOE+00 I 0.00E+00 PARTICULATES CR-51 CURIES 2.42E-06 0.00E+00 0.OOE+00 0.OOE+00 SR-89 CURIES 1.08E-07 1.14E-07 0.00E+00 0.OOE+00 BE-7 CURIES 7.49E-07 0.OOE+00 0.00E+00 0.OOE+00 CO-58 CURIES 1.27E-06 2.40E-07 0.OOE+00 0.OOE+00 CO-60 CURIES 2.22E-06 3.19E-06 0.OOE+00 0.00E+00 CS-137 CURIES 2.17E-07 0.OOE+00 0.00E+00 0.OOE+00 TOTAL FOR PERIOD CURIES I 6.99E-06 I 3.55E-06 I 0.OOE+00 I 0.OOE+00 H-3 CURIES I 9.59E+00 I 1.89E+01 I 3.87E-02 I 3.21E-01 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 48 of 84

TABLE 2-2B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Mixed-Mode Level Releases Unit: 2 Starting l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED UNIT 1QUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 1 FISSION GASES AR-41 CURIES 0.OOE+00 I 0.OOE+00 2.01E-02 2.62E-02 XE-135 CURIES 0.OOE+00 I 0.00E+00 I 3.56E-04 3.18E-04 XE-133 CURIES 0.OOE+00 I 0.OOE+00 I 2.34E-02 3.64E-02 TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 I 4.39E-02 6.29E-02 I IODINES 1-131 1 CURIES I 2.33E-07 I 0.OOE+00 I 0.OOE+00 I 0.00E+00 I TOTAL FOR PERIOD CURIES 2.33E-07 I 0.OOE+00 I 0.00E+00 I 0.00E+00 I PARTICULATES SR-89 CURIES 9.35E-08 1.10E-07 0.00E+00 0.OOE+00 BE-7 CURIES 2.18E-06 0.OOE+00 0.OOE+00 0.00E+00 CO-60 CURIES 3.05E-06 0.OOE+00 0.00E+00 0.OOE+00 TOTAL FOR PERIOD CURIES I 5.33E-06 I 1.10E-07 I 0.OOE+00 I O.OOE+00 I H-3 CURIES I 2.72E+00 I 1.lIE+01 I 8.40E-03 I 1.08E-02 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 49 of 84

TABLE 2-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED UNIT QUARTER 1 IQUARTER 2 IQUARTER 1 IQUARTER 2 1 FISSION GASES AR-41 CURIES 0.OOE+00 1.17E+00 9.44E-02 1.64E-01 XE-135 CURIES 0.OOE+00 2.34E-01 2.76E-03 2.05E-03 XE-133 CURIES 0.OOE+00 5.07E+00 6.36E-02 1.15E-01 KR-85 CURIES 0.00E+00 0.OOE+00 1.28E+00 0.00E+00 TOTAL FOR PERIOD CURIES 0.OOE+00 I 6.48E+00 I 1.44E+00 I 2.81E-01 IODINES 1-133 CURIES I 4.37E-05 0.00E+00 0.OOE+00 0.OOE+00 1-131 CURIES I 1.06E-05 0.OOE+00 0.00E+00 0.OOE+00 TOTAL FOR PERIOD I CURIES I 5.43E-05 I 0.00E+00 I 0.00E+00 I 0.00E+00 PARTICULATES CR-51 CURIES 2.42E-06 0.OOE+00 0.00E+00 0.OOE+00 SR-89 CURIES 1.88E-07 I 3.27E-07 0.OOE+00 0.00E+00 BE-7 CURIES 3.26E-06 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 CURIES 1.27E-06 2.40E-07 0.00E+00 0.OOE+00 CO-60 CURIES 2.22E-06 3.19E-06 0.OOE+00 0.OOE+00 CS-137 CURIES 2.17E-07 0.OOE+00 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES I 9.58E-06 I 3.76E-06 I 0.00E+00 I 0.OOE+00 I H-3 CURIES I 2.62E+01 I 6.42E+01 I 5.97E-02 3.27E-01 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 50 of 84

TABLE 2-2C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Mixed-Mode Level Releases Unit: Site Starting : l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE I I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 1 NUCLIDES RELEASED FISSION GASES AR-41 CURIES 0.OOE+00 I 0.OOE+00 8.07E-02 8.87E-02 I CURIES 0.00E+00 I 0.OOE+00 3.56E-04 3.38E-04 I XE-135 XE-133 CURIES 0.00E+00 I 3.89E+00.1 2.93E-02 I 2.52E-01 I CURIES I 0.OOE+00 3.89E+00 I 1.10E-01 I 3.41E-01 I TOTAL FOR PERIOD IODINES 1-133 CURIES 4.24E-05 9.42E-06 0.00E+00 0.00E+00 1-131 CURIES 3.92E-06 1.83E-06 0.OOE+00 0.OOE+00 TOTAL FOR PERIOD CURIES I 4.63E-05 1.12E-05 0.OOE+00 I 0.OOE+00 PARTICULATES CURIES 2.98E-07 2.84E-07 0.OOE+00 0.OOE+00 I SR-89 CURIES 3.77E-06 0.OOE+00 0.00E+00 0.00E+00 I BE-7 CURIES 3.05E-06 1.14E-06 0.00E+00 0.00E+00 I CO-60 TOTAL FOR PERIOD CURIES I 7.12E-06 1.42E-06 O.00E+00 I 0.OOE+00 I CURIES I 6.09E+01 I 4.72E+01 2.22E-02 4.37E-02 I H-3 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 51 of 84

TABLE 2-3A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED UNIT IQUARTER 1 [QUARTER 2 IQUARTER 1 IQUARTER 2 TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 52 of 84

TABLE 2-3A*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Ground Level Releases Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED I UNIT IQUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 1 TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 0.OOE+00 I 0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 53 of 84

TABLE 2-3B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Ground Level Releases Unit: 2 Starting l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE NUCLIDES RELEASED I UNIT IQUARTER 1 QUARTER 2 IQUARTER 1 IQUARTER 2 FISSION GASES XE-133 I CURIES I 0.OOE+00 I 0.OOE+00 0.OOE+00 I 5.47E-03 I TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 0.OOE+00 I 5.47E-03 I IODINES 1-132 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 3.57E-06 1-131 CURIES 0.OOE+00 0.OOE+00 0.OOE+00 6.00E-07 TOTAL FOR PERIOD CURIES 0.OOE+00 I 0.OOE+00 I 0.00E+00 4.17E-06 I H-3 I CURIES I 0.OOE+00 I 0.00E+00 I 0.OOE+00 3.57E-02 Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 54 of 84

TABLE 2-3B*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Ground Level Releases Unit: 2 Starting : l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED I UNIT IQUARTER 0 IQUARTER 0 IQUARTER 0 IQUARTER 0 1 TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.00E+00 I 0.00E+00 I 0.00E+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 55 of 84

TABLE 2-3C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jan-2001 Ending : 30-Jun-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED I UNIT IQUARTER 1 IQUARTER 2 JQUARTER 1 QUARTER 2 FISSION GASES XE-133 CURIES I 0.00E+00 I 0.OOE+00 I 0.OOE+00 5.47E-03 I TOTAL FOR PERIOD CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 5.47E-03 I IODINES 1-132 CURIES I 0.OOE+00 0.00E+00 0.OOE+00 3.57E-06 1-131 CURIES 0.OOE+00 0.00E+00 0.OOE+00 6.OOE-07 TOTAL FOR PERIOD CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 4.17E-06 I H-3 CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 3.57E-02 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 56 of 84

TABLE 2-3C*

Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents-Ground Level Releases Unit: Site Starting : l-Jul-2001 Ending : 31-Dec-2001 I CONTINUOUS MODE I BATCH MODE I NUCLIDES RELEASED I UNIT QUARTER 3 IQUARTER 4 IQUARTER 3 IQUARTER 4 I TOTAL FOR PERIOD I CURIES I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I 0.OOE+00 I Zeroes in this table indicate that no radioactivity was present at detectable levels.

See Table 2-6 for typical minimum detectable concentrations.

Page 57 of 84

TABLE 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2001 Ending: 30-Jun-2001 Cumulative Doses per Quarter Type ODCM Units Quarter  % of Quarter  % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 8.18E-06 1.64E-04 2.00E-04 4.00E-03 Beta 10.0 mrad 3.94E-05 3.94E-04 1.45E-04 1.45E-03 Cumulative Doses per Year Type ODCM Units Year to  % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 2.08E-04 2.08E-03 Beta 20.0 mrad 1.85E-04 9.24E-04 Page 58 of 84

TABLE 2-4A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 AIR DOSES DUE TO GASEOUS RELEASES Unit: 1 Starting: 01-Jul-2001 Ending: 31-Dec-2001 Cumulative Doses per Quarter Type ODCM Units Quarter  % of Quarter  % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 8.27E-06 1.65E-04 2.98E-05 5.95E-04 Beta 10.0 mrad 3.OOE-06 3.OOE-05 6.62E-05 6.62E-04 Cumulative Doses per Year Type ODCM Units Year to  % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 2.46E-04 2.46E-03 Beta 20.0 mrad 2.54E-04 1.27E-03 Page 59 of 84

TABLE 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2001 Ending: 30-Jun-2001 Cumulative Doses per Quarter Type ODCM Units Quarter  % of Quarter  % of of Limit 1 ODCM 2 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 5.41E-06 1.08E-04 1.59E-05 3.19E-04 Beta 10.0 mrad 2.69E-06 2.69E-05 7.59E-06 7.59E-05 Cumulative Doses per Year Type ODCM Units Year to  % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 2.14E-05 2.14E-04 Beta 20.0 mrad 1.03E-05 5.14E-05 Page 60 of 84

TABLE 2-4B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 AIR DOSES DUE TO GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2001 Ending: 31-Dec-2001 Cumulative Doses per Quarter Type ODCM Units Quarter  % of Quarter  % of of Limit 3 ODCM 4 ODCM Radi- Limit Limit ation Gamma 5.0 mrad 2.87E-06 5.75E-05 3.76E-06 7.52E-05 Beta 10.0 mrad 1.34E-06 1.34E-05 1.83E-06 1.83E-05 Cumulative Doses per Year Type ODCM Units Year to  % of of Limit Ending ODCM Radi- Date Limit ation Gamma 10.0 mrad 2.80E-05 2.80E-04 Beta 20.0 mrad 1.34E-05 6.72E-05 Page 61 of 84

TABLE 2-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jan-2001 Ending: 30-Jun-2001 Cumulative Doses per Quarter Organ ODCM Unit Quarter  % of Quarter  % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 5.40E-08 7.20E-07 5.06E-08 6.74E-07 Liver 7.5 mrem 1.07E-04 1.42E-03 2.91E-04 3.88E-03 TBody 7.5 mrem 1.07E-04 1.42E-03 2.91E-04 3.88E-03 Thyroid 7.5 mrem 1.08E-04 1.44E-03 2.91E-04 3.88E-03 Kidney 7.5 mrem 1.07E-04 1.42E-03 2.91E-04 3.88E-03 Lung 7.5 mrem 1.07E-04 1.42E-03 2.91E-04 3.88E-03 GILLI 7.5 mrem 1.07E-04 1.42E-03 2.91E-04 3.88E-03 Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 15.0 mrem 1.05E-07 6.97E-07 Liver 15.0 mrem 3.98E-04 2.65E-03 TBody 15.0 mrem 3.98E-04 2.65E-03 Thyroid 15.0 mrem 3.99E-04 2.66E-03 Kidney 15.0 mrem 3.98E-04 2.65E-03 Lung 15.0 mrem 3.98E-04 2.65E-03 GILLI 15.0 mrem 3.98E-04 2.65E-03 Page 62 of 84

TABLE 2-5A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 1 Starting: 01-Jui-2001 Ending: 31-Dec-2001 Cumulative Doses per Quarter Organ ODCM Unit Quarter  % of Quarter  % of Limit 3 ODCM 4 ODCM Limit Limit Bone 7.5 mrem 4.69E-08 6.25E-07 4.06E-07 5.41E-06 Liver 7.5 mrem 2.66E-04 3.55E-03 2.33E-04 3.10E-03 TBody 7.5 mrem 2.66E-04 3.55E-03 2.33E-04 3.10E-03 Thyroid 7.5 mrem 2.68E-04 3.57E-03 2.33E-04 3.11E-03 Kidney 7.5 mrem 2.66E-04 3.55E-03 2.33E-04 3.10E-03 Lung 7.5 mrem 2.66E-04 3.55E-03 2.33E-04 3.10E-03 GILLI 7.5 mrem 2.66E-04 3.55E-03 2.33E-04 3.10E-03 Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 15.0 mrem 5.58E-07 3.72E-06 Liver 15.0 mrem 8.97E-04 5.98E-03 TBody 15.0 mrem 8.96E-04 5.98E-03 Thyroid 15.0 mrem 9.00E-04 6.OOE-03 Kidney 15.0 mrem 8.97E-04 5.98E-03 Lung 15.0 mrem 8.97E-04 5.98E-03 GILLI 15.0 mrem 8.96E-04 5.98E-03 Page 63 of 84

TABLE 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jan-2001 Ending: 30-Jun-2001 Cumulative Doses per Quarter Organ ODCM Unit Quarter  % of Quarter  % of Limit 1 ODCM 2 ODCM Limit Limit Bone 7.5 mrem 3.92E-07 5.23E-06 4.62E-07 6.16E-06 Liver 7.5 mrem 6.23E-05 8.30E-04 1.25E-04 1.66E-03 TBody 7.5 mrem 6.23E-05 8.30E-04 1.25E-04 1.66E-03 Thyroid 7.5 mrem 6.60E-05 8.79E-04 1.25E-04 1.67E-03 Kidney 7.5 mrem 6.23E-05 8.30E-04 1.25E-04 1.66E-03 Lung 7.5 mrem 6.22E-05 8.30E-04 1.25E-04 1.66E-03 GILLI 7.5 mrem 6.23E-05 8.30E-04 1.25E-04 1.66E-03 Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 15.0 mrem 8.54E-07 5.69E-06 Liver 15.0 mrem 1.87E-04 1.25E-03 TBody 15.0 mrem 1.87E-04 1.25E-03 Thyroid 15.0 mrem 1.91E-04 1.27E-03 Kidney 15.0 mrem 1.87E-04 1.25E-03 Lung 15.0 mrem 1.87E-04 1.25E-03 GILLI 15.0 mrem 1.87E-04 1.25E-03 Page 64 of 84

TABLE 2-5B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSES TO A MEMBER OF THE PUBLIC DUE TO RADIOIODINES, TRITIUM, AND PARTICULATES IN GASEOUS RELEASES Unit: 2 Starting: 01-Jul-2001 Ending: 31-Dec-2001 Cumulative Doses per Quarter Organ ODCM Unit Quarter  % of Quarter  % of Limit 3 ODCM 4 ODCM Limit Limit Bone 7.5 mrem 9.53E-07 1.27E-05 2.61E-08 3.48E-07 Liver 7.5 mrem 1.80E-05 2.40E-04 7.14E-05 9.52E-04 TBody 7.5 mrem 1.80E-05 2.40E-04 7.14E-05 9.52E-04 Thyroid 7.5 mrem 1.81E-05 2.41E-04 7.14E-05 9.52E-04 Kidney 7.5 mrem 1.80E-05 2.40E-04 7.14E-05 9.52E-04 Lung 7.5 mrem 1.80E-05 2.40E-04 7.14E-05 9.52E-04 GILLI 7.5 mrem 1.81E-05 2.41E-04 7.14E-05 9.52E-04 Cumulative Doses per Year Organ ODCM Units Year to  % of Limit Ending ODCM Date Limit Bone 15.0 mrem 1.83E-06 1.22E-05 Liver 15.0 mrem 2.76E-04 1.84E-03 TBody 15.0 mrem 2.76E-04 1.84E-03 Thyroid 15.0 mrem 2.80E-04 1.87E-03 Kidney 15.0 mrem 2.76E-04 1.84E-03 Lung 15.0 mrem 2.76E-04 1.84E-03 GILLI 15.0 mrem 2.76E-04 1.84E-03 Page 65 of 84

TABLE 2-6 VOGTLE ELECTRIC GENERATING PLANT RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 MINIMUM DETECTABLE CONCENTRATIONS - GASEOUS SAMPLE ANALYSES JANUARY, 2001 THROUGH DECEMBER, 2001 The values in this table represent a priori Minimum Detectable Concentrations (MDC) that are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE MDC UNITS Kr-87 1.82E-08 gCi/ml Kr-88 2.53E-08 gCi/ml Xe-1 33 2.05E-08 gCi/ml Xe-1 33m 8.63E-08 gCi/ml Xe-i 35 7.12E-08 gCi/mI Xe-138 1.05E-07 gCi/mi 1-131 7.93E-1 5* RCi/mI Mn-54 3.94E-1 4" pCi/ml Fe-59 2.45E-14* pCi/ml Co-58 1.39E-14" gCi/ml Co-60 1.75E-14" gCi/ml Zn-65 2.82E-1 4* gCi/ml pCi/mi Mo-99 9.57E-14*

Cs-1 34 1.12E-14" laCi/ml Cs-1 37 8.71E-15* giCi/mI Ce-141 8.62E-15* gCi/mI Ce-144 2.77E- 14* gCi/mI Sr-89 1.OOE-13 gCi/ml Sr-90 1.OOE-1 3 gCi/ml H-3 9.OOE-08 gCi/ml Gross Alpha 1.OOE-1 3 pCi/ml

• Based on an estimated sample volume of 5.7E+08 ml.

Page 66 of 84

TABLE 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Batch Release Summary Unit: 1 Starting : l-Jan-2001 Ending : 30-Jun-2001 GASEOUS RELEASES NUMBER OF BATCH RELEASES 58 TOTAL TIME PERIOD FOR BATCH RELEASES  : 7598.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE  : 1941.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES  : 131.00 MINUTES MINIMUM TIME FOR A BATCH RELEASE 15.00 MINUTES TABLE 2-7A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Batch Release Summary Unit: 1 Starting  : 1-Ju-2001 Ending : 31-Dec-2001 GASEOUS RELEASES NUMBER OF BATCH RELEASES 56 TOTAL TIME PERIOD FOR BATCH RELEASES  : 4783.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE  : 316.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES  : 85.41 MINUTES MINIMUM TIME FOR A BATCH RELEASE  : 39.00 MINUTES Page 67 of 84

TABLE 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Batch Release Summary Unit: 2 Starting : l-Jan-2001 Ending : 30-Jun-2001 GASEOUS RELEASES NUMBER OF BATCH RELEASES 53 TOTAL TIME PERIOD FOR BATCH RELEASES  : 35552.58 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE  : 10064.92 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES  : 670.80 MINUTES MINIMUM TIME FOR A BATCH RELEASE . 8.00 MINUTES TABLE 2-7B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Batch Release Summary Unit: 2 Starting  : l-Jul-2001 Ending : 31-Dec-2001 GASEOUS RELEASES NUMBER OF BATCH RELEASES 27 TOTAL TIME PERIOD FOR BATCH RELEASES  : 2029.00 MINUTES MAXIMUM TIME PERIOD FOR A BATCH RELEASE 112.00 MINUTES AVERAGE TIME PERIOD FOR BATCH RELEASES 75.15 MINUTES MINIMUM TIME FOR A BATCH RELEASE  : 14.00 MINUTES Page 68 of 84

TABLE 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting 1-Jan-2001 Ending : 30-Jun-2001 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES RELEASE 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A MINUTES MINIMUM TIME FOR A RELEASE 0.00 ALL RELEASES 0. OOE+00 CURIES TOTAL ACTIVITY FOR TABLE 2-8A Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Abnormal Release Summary Unit: 1 Starting : l-Jul-2001 Ending : 31-Dec-2001 NUMBER OF RELEASES 0 RELEASES 0.00 MINUTES TOTAL TIME FOR ALL MINUTES MAXIMUM TIME FOR A RELEASE 0.00 RELEASE 0.00 MINUTES AVERAGE TIME FOR A MINUTES MINIMUM TIME FOR A RELEASE 0.00 ALL RELEASES 0.OOE+00 CURIES TOTAL ACTIVITY FOR Page 69 of 84

TABLE 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting 1-Jan-2001 Ending : 30-Jun-2001 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES RELEASE 0.00 MINUTES MAXIMUM TIME FOR A RELEASE 0.00 MINUTES AVERAGE TIME FOR A RELEASE 0.00 MINUTES MINIMUM TIME FOR A TOTAL ACTIVITY FOR ALL RELEASES 0. OOE+00 CURIE TABLE 2-8B Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 Gaseous Effluents - Abnormal Release Summary Unit: 2 Starting : -Jui-2001 Ending : 31-Dec-2001 NUMBER OF RELEASES 0 TOTAL TIME FOR ALL RELEASES 0.00 MINUTES RELEASE 0.00 MINUTES MAXIMUM TIME FOR A AVERAGE TIME FOR A RELEASE 0.00 MINUTES RELEASE 0.00 MINUTES MINIMUM TIME FOR A ALL RELEASES 0. OOE+00 CURIES TOTAL ACTIVITY FOR Page 70 of 84

3.0 Solid Waste 3.1 Regulatory Requirements The ODCM requirements presented in this section are stated in part for Unit 1 and Unit 2.

3.1.1 Solid Radioactive Waste System 10.2.1 Process Control Program (PCP)

Radioactive wastes shall be solidified or dewatered in accordance with the PCP to meet shipping and transportation requirements during transit and disposal site requirements when received at the disposal site.

3.1.2 Reporting Requirements 12.1 PCP states in part:

The Radioactive Effluent Release Report, submitted in accordance with Technical Specification 5.6.3, shall include a summary of the quantities of solid radwaste released from the units, as outlined in Regulatory Guide 1.21.

3.2 Solid Waste Data Regulatory Guide 1.21, Table 3 is found in this report as Table 3-1.

Page 71 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 1 of 4 JANUARY 1, 2001 THROUGH JUNE 30, 2001 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period Error, %

a. Spent resins, filter sludges, m3 None evaporator,bottoms, etc. Ci None N/A

b. Dry compressible waste, contaminated m3 14.12 equip, etc. Ci 138.6 40

c. Irradiated components, control m3 rods, etc. Ci NONE N/A

d. Other (describe) m3 Ci NONE N/A

2. Estimate of major nuclide composition (by type of waste)

a. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A

b. Ni-63  % 29.5 Cs-137  % 26.7 Cs-134  % 20.9 All others  % 22.9

c. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A

d. N/A  % N/A N/A  % N/A Page 72 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 2 of 4 JANUARY 1, 2001 THROUGH JUNE 30, 2001

3. Solid Waste Disposition Number of Mode of shipments wransportat on 5 Tractor/Cask/Trailer Studsvik, Erwin TN 1 Tractor/Trailer AERC, Oak Ridge TN 3 Tractor/Trailer Duratek, Oak Ridge, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Mode of M------- n4. 4a Taa44nn44 ,",'i ga& hý&.= = ý Ww None None None ADDITIONAL INFORMATION REQUIRED BY ODCM:

Shipments to a Waste Processor Shipment No. Waste Class Tvoe ShiDpino Solidification Container Class Agent RVRS-01-001 B STRONG TIGHT LSA (2) NONE B STRONG TIGHT LSA (2) NONE RVRS-01-002 B STRONG TIGHT LSA (2) NONE RVRS-01-003 "AUNSTABLE STRONG TIGHT LSA (2) NONE RVRS-01-004 RVRS-01-005 "AUNSTABLE STRONG TIGHT LSA (2) /LQ NONE RVRS-01-006 "AUNSTABLE STRONG TIGHT LSA (2) NONE RVRS-01--007 B STRONG TIGHT LSA (2) NONE RVRS-01-008 A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-01-009 LQ STRONG TIGHT LQ NONE Page 73 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 3 of 4 JULY 1, 2001 THROUGH DECEMBER 31, 2001.

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

1. Type of waste Unit 6-month Est. Total Period Error,

a. Spent resins, filter sludges, m3 NONE evaporator bottoms, etc. Ci NONE

b. Dry compressible waste, contaminated m3 16.59 equip, etc. Ci 829.6 40

c. Irradiated components, control m3 NONE rods, etc. Ci NONE N/A

d. Other (describe) m3 Ci NONE N/A

2. Estimate of major nuclide composition (by type of waste).

a. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A

b. Ni-63  % 65.3 Fe-55  % 11.0 Co-60  % 7.81 All others  % 15.89

c. N/A  % N/A N/A  % N/A N/A  % N/A N/A  % N/A

d. N/A  % N/A N/A  % N/A N/A  % N/A Page 74 of 84

TABLE 3-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Units 1 and 2 Page 4 of 4 JULY 1, 2001 THROUGH DECEMBER 31, 2001

3. Solid Waste Disposition Number of Mode of Shipments ---- a .1n floa+tnAtion 2 Tractor/Trailer/Cask Studsvik, Erwin, TN 4 Tractor/Trailer Duratek, Oak Ridge, TN 10 Tractor/Trailer AERC, Oak Ridge, TN 2 Tractor/Trailer DSSI, Kingston, TN B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of mode of flaa44 .jn4-* awl Shipments None None None ADDITIONAL INFORMATION REQUIRED BY ODCN:

Shipments Sent Directly to Disposal at Barnwell, SC Shipment Waste Class Tone Shipping Solidification Volume (Direct No. Container Class Acent disposal only)

NONE Shipments to a waste processor:

Shipment Waste Class Shipping Solidification No. Container Class Acent RVRS-001-010 A UNSTABLE STRONG TIGHT LSA (2) /LQ NONE A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-01-011 NONE RVRS-01-012 A UNSTABLE STRONG TIGHT LQ B STRONG TIGHT LSA (2) NONE RVRS-01-013 NONE RVRS-01-014 A UNSTABLE STRONG TIGHT LQ A UNSTABLE STRONG TIGHT LQ NONE RVRS-01-015 NONE A UNSTABLE Type B LSA (2)

RVRS-01-016 NONE RVRS-01-017 A UNSTABLE STRONG TIGHT LSA (2)

A UNSTABLE STRONG TIGHT LSA (2) NONE RVRS-01-018 NONE RVRS-01-019 A UNSTABLE STRONG TIGHT LQ STRONG TIGHT LQ NONE RVRS-01-020 A UNSTABLE STRONG TIGHT LQ NONE RVRS-01-021 A UNSTABLE STRONG TIGHT LQ NONE RVRS-01-022 A UNSTABLE STRONG TIGHT LQ NONE RVRS-01-023 A UNSTABLE A UNSTABLE STRONG TIGHT LQ NONE RVRS-01-024 LQ NONE RVRS-01-025 A UNSTABLE STRONG TIGHT STRONG TIGHT LQ NONE RVRS-01-026 A UNSTABLE STRONG TIGHT LQ NONE RVRS-01-027 A UNSTABLE Page 75 of 84

4.0 Doses to Members of the Public Inside the Site Boundary 4.1 Regulatory Requirements ODCM 7.2.2.3 states in part:

"The 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; this assessment must be performed in accordance with Chapter 6. All assumptions used in making these assessments ( i.e., specific activity, exposure time, and location) shall be included in the report".

4.2 Demonstration of Compliance The location of concern within the site boundary is the Visitors Center. The activities at the Visitor Center consist of occasional attendance at meetings and/or short visits for informational purposes.

There will be no radiation dose at this location due to radioactive liquid effluents.

Delineated in Table 4-1 for this location are the values of the basic data assumed in the dose assessment due to radioactive gaseous effluents. Listed in this table are distance and direction 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 listed in Tables 2-2A, and 2-2B for the mixed mode releases.

Similarly, it is listed in tables 2-3A and 2-3B for the ground level releases.

Page 76 of 84

4.2 Demonstration of Compliance cont'd The maximum doses in units of mrem to a MEMBER OF THE PUBLIC due to their activities inside the site boundary during the reporting period were assessed to be as follows:

VISITOR CENTER Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total Body: 9.12E-09 2.70E-07 7.42E-09 2.08E-08 (Direct Radiation from Plume)

VISITOR CENTER Quarter 1 Quarter 2 Quarter 3 Quarter 4 Maximum Organ 3.11E-07 8.63E-07 6.79E-07 5.39E-07 (Thyroid) Quarters 1,2,3,4 (Inhalation Ground Plane)

Page 77 of 84

TABLE 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jan-2001 Ending: 30-Jun-2001 Page: 1 Location Name VISITOR CENTER Distance (kilometers) 4.47E-01 Sector SE Occupancy Factor 4.57E-04 (4 .0OE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 5.93E-06 Particulate X/Q (sec/m3) 5. 58E-06 Particulate D/Q (m-2) 2.28E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.12E-07 Particulate X/Q (sec/m3) 6.74E-07 Particulate D/Q (m-2) 5.77E-09 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 1 Quarter 2 Quarters Year to 1 and 2 Ending Date Total mrem 9.12E-09 2.70E-07 2.80E-07 2 . 80E-07 Body Dose Bone mrem 1.33E-08 1. 53E-07 1. 66E-07 1. 66E-07 Liver mrem 3.08E-07 8.62E-07 1. 17E-06 1. 17E-06 TBody mrem 3.08E-07 8. 62E-07 1. 17E-06 1.17E-06 Thyroid mrem 3.11E-07 8. 63E-07 1. 17E-06 1.17E-06 Kidney mrem 3.08E-07 8. 62E-07 1.17E-06 1.17E-06 Lung mrem 3.08E-07 8. 62E-07 1.17E-06 1.17E-06 GI-LLI mrem 3.08E-07 8.62E-07 1.17E-06 1.17E-06 Page 78 of 84

TABLE 4-1 Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2001 DOSE TO A MEMBER OF THE PUBLIC DUE TO ACTIVITIES INSIDE THE SITE BOUNDARY Unit: Site Starting: 01-Jul-2001 Ending: 31-Dec-2001 Page: 2 Location Name VISITOR CENTER Distance (kilometers) 4.47E-01 Sector SE Occupancy Factor 4.57E-04 (4.OOE+00 hr/yr)

Age Group CHILD Ground Level Releases:

Noble Gas X/Q (sec/m3) 5.93E-06 Particulate X/Q (sec/m3) 5.58E-06 Particulate D/Q (m-2) 2.28E-08 Mixed Mode Releases:

Noble Gas X/Q (sec/m3) 7.12E-07 Particulate X/Q (sec/m3) 6.74E-07 Particulate D/Q (m-2) 5.77E-09 Elevated Releases:

Noble Gas X/Q (sec/m3) N/A Particulate X/Q (sec/m3) N/A Particulate D/Q (m-2) N/A Units Quarter 3 Quarter 4 Quarters Year to 3 and 4 Ending Date Total mrem 7.42E-09 2.08E-08 2.82E-08 3.08E-07 Body Dose Bone mremn 8.35E-09 2.27E-08 3.11E-08 1.97E-07 Liver mrem 6.77E-07 5.38E-07 1.21E-06 2.38E-06 TBody mrem 6.77E-07 5.38E-07 1.21E-06 2.38E-06 Thyroid mrem 6.79E-07 5.39E-07 1.22E-06 2.39E-06 Kidney mrem 6.77E-07 5.38E-07 1.21E-06 2.38E-06 Lung mremn 6.77E-07 5.38E-07 1.21E-06 2.38E-06 GI-LLI mrem 6.77E-07 5.38E-07 1.21E-06 2.38E-06 Page 79 of 84

5.0 Total Dose from Uranium Fuel Cycle (40CFR190) 5.1 Regulatory Requirements ODCM 5.1 states in part that 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.

5.2 Demonstration of Compliance The requirements of 40CFR1 90 were met.

6.0 Meteorological Data ODCM 7.2.2.2 states in part:

The Radioactive Effluent Release Report 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 of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape; or in the form of joint frequency distributions of wind speed, wind direction and atmospheric stability.

In lieu of submission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.

7.0 Program Deviations 7.1 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 7.1.1 Regulatory Requirement ODCM 7.2.2.6 states in part that the report shall include deviations from the liquid and gaseous effluent monitoring instrumentation operability requirements included in Sections 2.1.1 and 3.1.1, respectively. The report shall include an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time requirement.

7.1.2 Description of Deviations The inoperability of liquid and gaseous effluent monitors was corrected within the specified time for this reporting period.

Page 80 of 84

7.2 Tanks Exceeding Curie Content Limits 7.2.1 Regulatory Requirements ODCM 7.2.2.6 states in part that the report shall include a description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications 5.5.12.

7.2.2 Description of Deviations There were no outdoor liquid hold-up tanks used for radioactive liquids during this reporting period. Limits for the gas storage tanks were not exceeded during this reporting period.

8.0 Changes to the Vogtle Electric Generating Plant Offsite Dose Calculation Manual (ODCM) 8.1 Regulatory Requirements ODCM 7.2.2.5 states in part that changes to the ODCM shall be submitted with the Radioactive Effluent Release Report. These changes may be due to changes in the radiological environmental monitoring program sampling locations as required by ODCM 4.1.1.2.3 or changes to dose calculation locations as required by ODCM 4.1.2.2.2. Land uses and dose calculation locations within five miles of VEGP must be determined by a land use census as required by ODCM 4.1.2.

8.2 Description of Changes There were changes made to the Vogtle Electric Generating Plant ODCM for the period January 1, 2001 through December 31, 2001. Revision 18 became effective August 2001. Revision 19 became effective November 2001. These changes are being submitted with The Radioactive Effluent Release Report in the form of a complete legible copy of the entire ODCM in accordance with Technical Specification 5.5.1 .c The Land Use Census was conducted December 11, 2001 by Georgia Power Company Environmental Lab personnel. The results of the census for 2001 require no changes to the REMP sampling locations or to the dose calculation locations.

Page 81 of 84

9.0 Major Changes to Liquid, Gaseous, or Solid Radwaste Treatment Systems 9.1 Regulatory Requirements ODCM 7.2.2.7 states in part:

As required by Sections 2.1.5 and 3.1.6, licensee initiated MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (liquid and gaseous) shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report covering the period in which the change was reviewed and accepted for implementation.

Note 1: In lieu of inclusion in the Radioactive Effluents Release Report, this same information may be submitted as part of the annual FSAR update.

PCP 12.1 states in part:

Licensee major initiated changes to the solid radioactive waste treatment system shall be reported to the Nuclear Regulatory Commission in the Radioactive Effluent Release Report for the period in which the change was implemented.

Page 82 of 84

9.2 Description of Major Changes Gaseous Radwaste System A new offsite gaseous release point was added with the upgrade of the liquid radwaste processing system infrastructure, the RPF, along with the Heating Ventilation and Air Conditioning (HVAC) system that supports it. The RPF is equipped with HEPA ventilation and radiation monitoring capability that supports this facility. However, none of the design criteria or release limits associated with the gaseous radwaste system changes.

Liquid Radwaste System Major changes to the liquid, gaseous and solid radwaste facilities are those that contribute to significant changes in release; i.e., either decreases or increases in release volume or activity/dose. This is to indicate that no major changes to the liquid, solid and gaseous radwaste systems occurred during the 2001 assessment period. With the design and installation of the Radwaste Processing Facility (RPF) significant structural, civil and support system changes occurred with regards to the infrastructure that supports liquid radwaste processing while the processing technologies, process design criteria, process efficiencies, and release goals remained unchanged during this period. All structural, civil, support and infrastructure changes were processed in accordance with existing plant administrative procedures and any incidental changes to the Updated Final Safety and Analysis report were appropriately made.

None of the infrastructure changes affected the design criteria and design parameters associated with the liquid radwaste processing system and these parameters remain unchanged from the previous assessment period.

Solid Radwaste System There were no major changes to the solid, liquid and gaseous radwaste systems in the 2001 assessment period.

Page 83 of 84

TABLE 1-lB Vogtle Electric Generating Plant RADIOACTIVE EFFLUENT RELEASE REPORT - 2000 Liquid Effluents - Summation of All Releases unit: 2 Starting l-Jul-2000 Ending : 31-Dec-2000 9.3 Addendum to 2000 Report- G-ALPHA TYPE OF EFFLUENT UNITS QUARTER 3 QUARTER 4 EST. TOT ERROR %

A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CURIES 9.03E-03 2.13E-02 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 9.49E-08 3.09E-07

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3. PERCENT OF APPLICABLE LIMIT  %*

• B. TRITIUM

1. TOTAL RELEASE CURIES 4.93E+01 2.05E+01 40

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 5.18E-04 2.98E-04

3. PERCENT OF APPLICABLE LIMIT  %*

• C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CURIES 6.67E-06 0.OOE+00 50

2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCi/ML 7.01E-11 0.00E+00

3. PERCENT OF APPLICABLE LIMIT  %*

• D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CURIES 0.00E+00 8.70E-06 45 E. WASTE VOL RELEASED(PRE-DILUTION) LITERS 2.40E+05 1.59E+05 20 F. VOLUME OF DILUTION WATER USED LITERS 9.49E+07 6.86E+07 20 Applicable limits are expressed in terms of dose.

See Tables 1-3A and 1-3B of this report.

Corrected for G-ALPHA 3 rd quarter 2000 Page 84 of 84