Text

Radioactive Effluent Release Report for 2006
	ML071310444
Person / Time
Site:	River Bend
Issue date:	05/01/2007
From:	Lorfing D; Entergy Nuclear Operations
To:	; Document Control Desk, NRC/NRR/ADRO
References
	RBFI-07-0072, RBG-46691
	Download: ML071310444 (78)
	v • d • e

May 1,2007 US. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852-2738

Subject:

Radioactive Effluent Release Report for 2006 River Bend Station - Unit 1 License No. NPF-47 Docket No. 50-458 File Nos.:

G9.5, G9.25.1.5 RBG-46691 RBFI 0072

Dear Sir or Madam,

Enclosed is a CD containing the River SS) Annual Radioactive Effluent Release Report for the period January 1, 2006, through December 31, 2006. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.3.

Also enclosed as the first page of the report is a copy of this transmittal letter.

Should you have any questions regarding the enclosed information, please contact Mr. Bill Fountain at (225) 381 -4625.

Sincerely,

enclosure

2006 A

~

A L

E F F L ~ E ~ ~

RELEASE RJ3PORT

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 2

TABLE OF CONTENTS PAGE I.

INTRODUCTION 4

II.

SUPPLEMENTAL INFORMATION A.

Regulatory Limits 4

B.

Effluent Concentration Limits 7

C.

Measurements and Approximations of Total Radioactivity 7 D.

Batch Releases 9

E.

Abnormal Releases 9

F.

Estimate of Total Error 9

III.

GASEOUS EFFLUENT

SUMMARY

INFORMATION 10 IV.

LIQUID EFFLUENT

SUMMARY

INFORMATION 10 V.

SOLID WASTE 10 VI.

RADIOLOGICAL IMPACT ON MAN 10 VII.

METEOROLOGICAL DATA 11 VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY 11 IX.

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY 11 X.

LIQUID HOLDUP TANKS 11 XI.

RADIOLOGICAL ENVIRONMENTAL MONITORING 12 XII.

LAND USE CENSUS 12 XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM) 12 XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 13 XV.

PROCESS CONTROL PROGRAM (PCP) 13 TABLES Table 1A Gaseous Effluent - Summation of All Releases 14 Table 1B Gaseous Effluent - Ground Level Releases 15 Table 1C Gaseous Effluent - Ground Level Batch Release 16

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 3

Table 1D Gaseous Effluent - Mixed Mode Continuous Releases 17 Table 1E Gaseous Effluent - Mixed Mode Batch Releases 18 Table 1F Radioactive Gaseous Waste Sampling and Analysis Program 19 Table 1G Maximum Individual Doses Due to Gaseous Releases 20 Table 2A Liquid Effluent - Summation of All Releases 21 Table 2B Liquid Effluent - Continuous Mode 22 Table 2C Liquid Effluent - Batch Mode 23 Table 2D Liquid Batch Information 24 Table 2E Radioactive Liquid Waste Sampling and Analysis Program 25 Table 2F Liquid Dose Summary 26 Table 3 Solid Waste and Irradiated Fuel Shipments 27 Table 4 Assumptions/Parameters for Doses to Member of the Public Inside Site Boundary 30 Table 5 Doses to Members of the Public on Site from Gaseous Releases 31 Table 6 Meteorological Data - Joint Frequency Tables 32 Table 7 Atmospheric Dispersion Factors 65 Process Control Program 66

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 4

I.

INTRODUCTION This is the annual Radioactive Effluent Release Report for the period of January 1, 2006, through December 31, 2006. This report is submitted in accordance with Technical Specification 5.6.3 of Appendix A to River Bend Station (RBS) License Number NPF-47.

II.

SUPPLEMENTAL INFORMATION A.

Regulatory Limits

1.

10CFR50, Appendix I Limits

a.

Fission and Activation Gases In accordance with Technical Requirement (TR) 3.11.2.2, the air dose due to noble gases released in gaseous effluent to areas at and beyond the SITE BOUNDARY shall be limited to:

DGamma-Air = gamma air dose from radioactive noble gases in millirad (mrad) n

=

3.17E-8 Mi (X/Q) Qi < 5 mrads/qtr i=1 < 10 mrads/yr DBeta-Air =

beta air dose from radioactive noble gases in millirad (mrad) n

=

3.17E-8 Ni (X/Q) Qi < 10 mrads/qtr i=1 < 20 mrads/yr

b.

Radioiodines (I-131 & I-133) and Particulate In accordance with Technical Requirement 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from radioiodines (I-131 and I-133), tritium (H-3) and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluent releases to areas at and beyond the SITE BOUNDARY shall be limited to:

DI&8DP =

Dose in mrem to the organ () for the age group of interest from radioiodine (I-131, I-133, tritium, and 8 day particulate via the pathway of interest.)

n

= 3.17E-08 (Fo)

Pi (X/Q) Qi and I=1 n

= 3.17E-08 (Fo)

Ri (D/Q) Qi and I=1

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 5

n D

= DI&8DP

< 7.5 mrem/qtr z=1 15 mrem/yr (above terms defined in the RBS ODCM)

c.

Liquid Effluent In accordance with Technical Requirement 3.11.1.2, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to UNRESTRICTED AREAS shall be limited to:

Di

=

Ai t Qi (DF) Dw and n

DTOTAL=

Di i=1 DTOTAL=

Total dose commitment to the organ () due to all releases during the desired time interval in mrem and DTOTAL Total Body

< 1.5 mrem/qtr

< 3 mrem/yr DTOTAL Any Organ

< 5 mrem/qtr

< 10 mrem/yr (above terms defined in RBS ODCM)

2.

40CFR190 Limits In accordance with Technical Requirement 3.11.4, 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:

25 mrem to the total body or any organ (except the thyroid) 75 mrem to the thyroid

3.

Miscellaneous Limits

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 6

a.

Technical Requirement 3.11.2.1 - Fission and Activation Gases In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be less than or equal to 500 millirems/year (mrem/yr) to the total body and less than or equal to 3000 mrem/yr to the skin:

DRTB =

Dose rate to the total body in mrem/yr n

=

Ki (X/Q) Qi < 500 mrem/yr and i=1 DRSKIN =

Dose rate to the skin in mrem/yr n

=

Li + 1.1Mi (X/Q) Qi < 3000 mrem/yr i=1 (above terms defined in RBS ODCM)

b.

Technical Requirement 3.11.2.1 - Radioiodine (I-131 & I-133) and Particulate In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioiodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to less than or equal to 1500 mrem/yr to any organ:

DRI&8DP = Dose rate to the organ for the age pathway group of interest from Radioiodines (I-131 & I-133), tritium, and 8 day particulate via the inhalation pathway in mrem/yr.

n

=

Pi (X/Q) Qi < 1500 mrem/yr i=1 (above terms defined in RBS ODCM)

c.

Technical Requirement 3.11.1.1 - Liquid Effluent In accordance with Technical Requirement 3.11.1.1, the concentration of radioactive material released in liquid effluent to UNRESTRICTED AREAS shall be limited to ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 7

dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 microcuries/milliliter total concentration.

d.

Technical Requirement 3.11.2.5 - Ventilation Exhaust Treatment System In accordance with Technical Requirement 3.11.2.5, the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses, due to gaseous effluent releases to areas and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31-day period.

e.

Technical Requirement 3.11.1.3 - Liquid Radwaste Treatment System In accordance with Technical Requirement 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.

B.

Effluent Concentration Limits

1.

Gaseous Releases The concentrations of radioactive gaseous releases are based on the dose rate restrictions in RBS Technical Requirements, rather than the Effluent Concentration Limits (ECL) listed in 10CFR20 Appendix B, Table 2, Column 1.

2.

Liquid Releases The Effluent Concentration Limits of radioactive materials in liquid effluent is limited to ten times 10CFR20, Appendix B, Table 2, Column 2.

C.

Measurements and Approximations of Total Radioactivity

1.

Gaseous Effluent

a.

Fission and Activation Gases Periodic grab samples are obtained from the Main Plant Exhaust Duct, Fuel Building Exhaust Vent and Radwaste Building Exhaust Vent. These samples are analyzed using high purity germanium detectors coupled to computerized pulse height analyzers. The sampling and analysis frequencies are described in Table 1F.

Sampling and analysis of these effluent streams provide noble gas radionuclide relative abundance that can then be applied to the noble gas

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 8

gross activity and gross activity release rate to obtain nuclide specific activities and release rates. The noble gas gross activity released within a specific time period is determined by integrating the stack monitor release rate over the considered time period. If no activity was detected between the stack grab sample and a significant increase in hourly averages was recorded, the nuclide relative abundance of the last sample (or the last similar event),

which indicated the presence of activity, was used to obtain nuclide specific activities. Correction factors for the monitors are derived and applied for each sampling period whenever noble gas radionuclides are detected in the effluent stream.

b.

Particulate and Radioiodine (I-131 & I-133)

Particulates, Iodine-131 and Iodine-133 are continuously sampled from the three release points using a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 1. Analysis is performed to identify and quantify radionuclides using high purity germanium detectors coupled to computerized pulse height analyzers. Given the nuclide specific activity concentrations, process flow rate, and duration of the sample; the nuclide specific activity released to the environment can be obtained. Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period.

Strontium-89 and Strontium-90 (Sr-89 and Sr-90) are quantitatively analyzed by counting by Scintillation techniques (Chrenkov counting). Gross alpha analysis is performed using a zinc sulfide scintillation counter.

c.

Tritium Tritium grab samples are obtained from the three release points at the specified frequencies listed in Table 1 using an ice bath condensation collection method. The collected sample is then analyzed using a Liquid Scintillation Counter. Given the tritium concentration, process flow rate, and time period for which the sample is obtained, the tritium activity released to the environment can be determined. Due to the frequency of sampling, it is assumed that the tritium is released to the environment at a constant rate within the time period for which the sample is obtained.

2.

Liquid Effluent Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 2. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high resolution germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined using a liquid scintillation counter. Strontium-89 and Strontium-90 are quantitatively analyzed by Scintillation techniques (Chrenkov counting). Iron-55 is counted with a liquid scintillation counter after digestion of the iron. Gross

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 9

alpha analysis is performed using a zinc sulfide scintillation counter.

Given the nuclide specific activity concentration and total volume of the tank that was released, the activity of each nuclide released to the environment can be determined.

D.

Batch Releases Liquid Effluents Batch releases and receiving stream flow from River Bend Station during the reporting period of January 1, 2006, through December 31, 2006 are shown in Table 2D.

The Mississippi River stream flow is obtained by averaging data from the U. S. Army Corp of Engineers website using flow gauge data at Tarbert Landing.

Gaseous Effluents There were no batch releases of gaseous effluents from River Bend Station during the reporting period of January 1, 2006, through December 31, 2006.

E.

Abnormal Releases There were no abnormal liquid or gaseous releases during the reporting period of January 1, 2006, through December 31, 2006.

F.

Estimate of Total Error

1.

Liquid The maximum error associated with sample collection, laboratory analysis, and discharge volume is collectively estimated to be:

Fission and Activation Products

+ 14.2%

Tritium

+ 14.2%

Dissolved and Entrained Noble Gases

+ 14.2%

Gross Alpha Radioactivity

+ 14.2%

2.

Gaseous The maximum errors (not including sample line loss) associated with sample flow, process flow, sample collection, monitor accuracy and laboratory analysis are collectively estimated to be:

Noble Gases

+ 37.0%

Iodines

+ 18.6%

Particulate

+ 18.6%

Tritium

+ 18.2%

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 10

3.

Determination of Total Error The total error (i.e., collective error due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.) is calculated using the following equation:

ET

=

((E1)2 + (E2)2 +...(En)2) where:

ET

=

total error E1, E2...En =

individual errors due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.

III. GASEOUS EFFLUENT

SUMMARY

INFORMATION Refer to the Table 1 series for Summation of All Releases and Nuclides Released, respectively. It should be noted that an entry of 0.00E+00 Curie (Ci) or microcurie/second (uCi/sec) in this section indicates that the concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 1F. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

IV. LIQUID EFFLUENT

SUMMARY

INFORMATION Refer to the Table 2 series for Summation of All Releases and Nuclides Released. It should be noted that an entry of 0.00E+00 Ci or uCi/ml in this section indicates that the concentration of the particular radionuclide was below the Lower Limit of Detection (LLD) as listed in Table 2D. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

V.

SOLID WASTE Refer to Table 3, for Solid Waste and Irradiated Fuel Shipments.

VI. RADIOLOGICAL IMPACT ON MAN (40CFR190)

An assessment was made of radiation doses to the likely most-exposed member of the public from River Bend and other nearby uranium fuel cycle sources (none within five miles). 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 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 11 Organ mrem Total Body 0.85 Skin 1.52 Thyroid 1.94 Other Organ 0.89 In addition, an assessment of doses was made for members of the public due to their activities inside the site boundary. Parameters and assumptions used to make this determination can be found in Table 4. The results of the calculations can be found in Table 5. The maximally exposed member of the public was the lawn service provider, which was conservatively calculated to have performed all work at the Generation Support Building during 2006. It should be noted that liquid effluent pathway dose was not considered since these individuals would not engage in activities that would allow exposure to this pathway.

VII. METEOROLOGICAL DATA See Tables 6 and 7 for the cumulative joint frequency distributions and annual average data for continuous releases. The meteorological recovery for 2006 was 94 %.

VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY In the period January 1, 2006, through December 31, 2006, there was one occasion where a channel described in Table 3.3.11.2-1 of Technical Requirement 3.3.11.2 was not restored to OPERABLE within the required time. On May 21, 2006, the flow rate measurement device for the cooling tower blowdown line (CWS-FE113) was out of service for more than 30 days.

The release of liquid radioactive effluents had already been suspended prior to May 21, 2006, and was not restored until after CWS-FE113 was repaired. CWS-FE113 was not repaired within 30 days due to an administrative issue. This issue has been entered into the RBS corrective action process to evaluate actions to prevent recurrence.

IX. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY The minimum number of channels required to be OPERABLE as described in Table 3.3.11.3-1 of Technical Requirement 3.3.11.3 were, if inoperable at any time in the period January 1, 2006, through December 31, 2006, restored to operable status within the required time.

Reporting of inoperable channels is therefore not required in this report.

X.

LIQUID HOLD UP TANKS The maximum quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any unprotected outdoor tank during the period of January 1, 2006,

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 12 through December 31, 2006 was less than or equal to the 10 curie limit as required by Technical Specification 5.5.8.b.

XI. RADIOLOGICAL ENVIRONMENTAL MONITORING During the reporting period January 1, 2006, through December 31, 2006, the only change to the Radiological Environmental Monitoring Program was moving the TLD C1 location from a stub pole to a telephone pole across the street in the same vicinity due to road construction on US Highway 61. Table 4.1 of the ODCM, Direct Radiation, TC1 will be changed in a 2007 revision.

XII. LAND USE CENSUS The land use census for the 2006 period was performed as required by Technical Requirement 3.12.2. The Land Use Census for 2006 was conducted in accordance with procedure ESP 051, as required by Technical Requirements Manual (TRM) (TR 3.12.2). The results of the Land Use Census will be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.

A garden census is not conducted pursuant to the note in the TRM (TRCO 3.12.2) that allows the sampling of broadleaf vegetation in the highest calculated average ground-level D/Q sector near site boundary in lieu of the garden census.

The milk animal census identified no milk animals within 8 km (5 miles) of River Bend site.

This information was verified by the County Agents from West Feliciana, East Feliciana and Pointe Coupee parishes.

No locations were identified in 2006 that would yield a calculated dose or dose commitment greater than those currently calculated in Requirement TSR 3.11.2.3.1.

The County Agents also confirmed that there was no commercial harvesting of crawfish within the five-mile radius downstream of RBS. This is data is collected to further support the possibility of removing invertebrates from the liquid dose conversion factors. This information represents two consecutive land use census periods that show crawfish consumption from the waters immediately affected by RBS does not occur. RBS conservatively uses the invertebrate pathway although not required by NUREG-0133 liquid dose factor methodology for fresh water nuclear power plants.

XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the ODCM in 2006.

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 13 XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Engineering has performed a review of the IDEAS database to evaluate design changes completed or partially completed during 2006 involving the subject systems. These design changes were then reviewed to determine if there have been any major changes to the subject systems. The review was based on a major change being defined as a modification which affected the method of processing or the effluent from the system. Also, to be a major change the change must have affected the USAR.

The Engineering Requests completed during this time period primarily consisted of administrative changes, parts equivalencies or approval of alternate parts with enhanced performance characteristics, and setpoint changes. The administrative changes primarily consisted of drawing/document corrections. Equivalencies or enhanced alternate parts involved replacement valves and pump seals. The setpoint change on a pump discharge pressure setpoint was to eliminate nuisance alarms and reflect the actual operating point of the pump on its pump curve. These changes did not modify any radioactive waste system major component such that the processing method or effluent was changed. These changes also had no affect on the method of processing solid, liquid or gaseous waste and did not affect the isotopic composition or the quantity of liquid, solid, or gaseous waste as described in the USAR.

In conclusion, no design changes were completed during the specified time period that constituted a major change to the liquid, solid or gaseous radwaste treatment systems.

XV. PROCESS CONTROL PROGRAM (PCP)

The 2006 changes to the PCP were editorial in nature. There were no changes made that affect the shipping, handling and disposal of radioactive wastes from River Bend Station. The changes are summarized on Page 1 of 11 of EN-RW-105, a copy of which is in Attachment 1 of this report.

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 14 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 2.07E+02 4.61E+02 4.18E+02 3.68E+02 1.45E+03

2. Avg. Release Rate uCi/sec 2.66E+01 5.86E+01 5.26E+01 4.62E+01 4.61E+01

3. % Applicable Limit % (1) 1.57E+00 3.94E+00 7.34E+00 3.86E+00 8.35E+00 Iodine-131

1. Total Release Ci 4.41E-03 1.72E-02 4.35E-03 4.29E-03 3.02E-02

2. Avg. Release Rate uCi/sec 5.68E-04 2.18E-03 5.48E-04 5.40E-04 9.59E-04

3. % Applicable Limit % (2) 1.91E+00 7.63E+00 1.86E+00 1.88E+00 6.61E+00 Particulates Half Life >= 8 days

1. Total Release Ci 1.73E-03 1.55E-03 1.01E-03 1.73E-03 6.02E-03

2. Avg. Release Rate uCi/sec 2.23E-04 1.97E-04 1.27E-04 2.18E-04 1.91E-04

3. % Applicable Limit % (2) 2.67E-01 2.99E-01 5.14E-01 4.61E-01 7.68E-01 Tritium

1. Total Release Ci 1.60E+01 9.95E+00 3.23E+00 1.14E+01 4.06E+01

2. Avg. Release Rate uCi/sec 2.06E+00 1.27E+00 4.06E-01 1.43E+00 1.29E+00

3. % Applicable Limit % (2) 2.25E-01 2.22E-01 9.32E-02 1.68E-01 3.53E-01

1)

Either the gamma air dose limit of 5 mrads/qtr or beta air dose limit of 10 mrads/qtr (T.R. 3.11.2.2.a), which ever is most limiting.

2)

The % of applicable limit is determined by comparing the dose contribution to the critical organ limits of TRM 3.11.2.3

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 15 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1B GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 2.21E+01 1.24E+01 1.57E+01 9.13E-01 5.11E+01 XE-133M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-135 Ci 8.74E+00 2.89E+01 6.62E+01 3.24E+01 1.36E+02 XE-135M Ci 1.14E+00 7.39E-01 2.36E+01 8.20E-01 2.63E+01 Totals for Period... Ci 3.20E+01 4.21E+01 1.05E+02 3.41E+01 2.14E+02 Iodines I-131 Ci 2.88E-05 3.20E-04 3.82E-06 4.83E-05 4.01E-04 I-133 Ci 1.16E-04 1.16E-04 3.88E-05 2.85E-04 5.56E-04 Totals for Period... Ci 1.45E-04 4.36E-04 4.27E-05 3.33E-04 9.57E-04 Particulates Half Life >= 8 days CE-141 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-57 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-58 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CO-60 Ci 0.00E+00 0.00E+00 0.00E+00 7.25E-07 7.25E-07 CR-51 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 NB-95 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN-65 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period... Ci 0.00E+00 0.00E+00 0.00E+00 7.25E-07 7.25E-07 Tritium H-3 Ci 2.28E+00 2.76E+00 1.24E+00 1.75E+00 8.03E+00

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 16 Totals for Period... Ci 2.28E+00 2.76E+00 1.24E+00 1.75E+00 8.03E+00 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1C GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-135 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-135M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period... Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Iodines

- No Nuclide Activities **........................................

Particulates Half Life >= 8 days CO-60 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ZN-65 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period... Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tritium

- No Nuclide Activities **........................................

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 17 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 1D GASEOUS EFFLUENTS - MIXED MODE RELEASES - CONTINUOUS MODE REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 KR-85M Ci 8.11E-01 1.06E+01 8.80E+00 5.14E-01 2.07E+01 KR-87 Ci 1.03E+00 9.16E+00 0.00E+00 2.45E+00 1.26E+01 KR-88 Ci 1.58E+00 1.18E+01 0.00E+00 1.68E+00 1.50E+01 XE-131M Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 XE-133 Ci 4.12E+01 1.09E+02 3.50E+00 1.24E+01 1.66E+02 XE-133M Ci 7.41E-01 3.23E+00 0.00E+00 0.00E+00 3.97E+00 XE-135 Ci 7.40E+01 1.46E+02 1.53E+02 1.36E+02 5.08E+02 XE-135M Ci 4.80E+01 9.97E+01 1.48E+02 1.45E+02 4.40E+02 XE-137 Ci 4.18E+00 1.12E+01 0.00E+00 1.52E+01 3.06E+01 XE-138 Ci 3.17E+00 1.81E+01 0.00E+00 2.08E+01 4.20E+01 Totals for Period... Ci 1.75E+02 4.19E+02 3.13E+02 3.33E+02 1.24E+03 Iodines I-131 Ci 4.39E-03 1.69E-02 4.35E-03 4.24E-03 2.98E-02 I-133 Ci 2.22E-02 2.28E-02 4.36E-02 3.69E-02 1.25E-01 Totals for Period... Ci 2.66E-02 3.97E-02 4.80E-02 4.11E-02 1.55E-01 Particulates Half Life >= 8 days BA-140 Ci 6.73E-04 5.02E-04 3.87E-04 9.53E-04 2.51E-03 CE-139 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CE-141 Ci 0.00E+00 1.80E-06 0.00E+00 0.00E+00 1.80E-06 CO-58 Ci 0.00E+00 0.00E+00 4.12E-06 1.47E-05 1.88E-05 CO-60 Ci 0.00E+00 1.08E-05 3.83E-05 5.10E-05 1.00E-04 CR-51 Ci 0.00E+00 0.00E+00 0.00E+00 4.83E-05 4.83E-05 CS-134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CS-137 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 MN-54 Ci 0.00E+00 0.00E+00 4.28E-05 2.62E-05 6.90E-05 SR-89 Ci 1.04E-03 1.02E-03 5.37E-04 6.31E-04 3.24E-03 SR-90 Ci 1.53E-05 1.04E-05 4.09E-07 4.60E-06 3.07E-05 ZN-65 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period... Ci 1.73E-03 1.55E-03 1.01E-03 1.73E-03 6.02E-03 Tritium H-3 Ci 1.37E+01 7.19E+00 1.99E+00 9.65E+00 3.26E+01 Totals for Period... Ci 1.37E+01 7.19E+00 1.99E+00 9.65E+00 3.26E+01

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 18 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE Table 1E REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0 0 0 0 0 Total release time minutes 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Maximum release time minutes 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Average release time minutes 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Minimum release time minutes 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 19 TABLE 1F Effluent and Waste Disposal Annual Report 2006 Year RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Sampling Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (LLD) uCi/ml A. Main Plant Exhaust Duct M

Grab Sample M

Principal Gamma Emitters H-3 1.00E-04 1.00E-06 B. Fuel Building Ventilation Exhaust Duct M

Grab Sample M

Principal Gamma Emitters H-3 1.00E-04 1.00E-06 C. Radwaste Building Ventilation Exhaust Duct M

Grab Sample M

Principal Gamma Emitters 1.00E-04 D. All Release Types as listed in A, B, & C above Continuous W

Charcoal Sample I-131 I-133 1.00E-12 1.00E-10 Continuous W

Particulate Sample Principal Gamma Emitters (I-131, Others) 1.00E-11 Continuous M

Composite Particulate Sample Gross Alpha 1.00E-11 Continuous Q

Composite Particulate Sample Sr-89, Sr-90 1.00E-11 Continuous Noble Gas Monitor Noble Gases Gross Beta or Gamma 1.00E-06 W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 20 Table 1G GASEOUS DOSE

SUMMARY

Release ID: 1 All Gas Release Points Coefficient Type: Historical

I&P DOSE LIMIT ANALYSIS===============================================

Age Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Q1 - T.Spec Any Organ CHILD THYROID 1.80E-01 7.50E+00 2.40E+00 Q2 - T.Spec Any Organ CHILD THYROID 6.11E-01 7.50E+00 8.14E+00 Q3 - T.Spec Any Organ CHILD THYROID 1.85E-01 7.50E+00 2.46E+00 Q4 - T.Spec Any Organ CHILD THYROID 1.88E-01 7.50E+00 2.50E+00 Yr - T.Spec Any Organ CHILD THYROID 1.16E+00 1.50E+01 7.75E+00

NOBLE GAS DOSE LIMIT ANALYSIS=========================================

Dose Limit % of Period-Limit (mrad) (mrad) Limit Q1 - T.Spec Gamma 7.83E-02 5.00E+00 1.57E+00 Q2 - T.Spec Gamma 1.97E-01 5.00E+00 3.94E+00 Q3 - T.Spec Gamma 3.67E-01 5.00E+00 7.34E+00 Q4 - T.Spec Gamma 1.93E-01 5.00E+00 3.86E+00 Yr - T.Spec Gamma 8.35E-01 1.00E+01 8.35E+00 Q1 - T.Spec Beta 9.71E-02 1.00E+01 9.71E-01 Q2 - T.Spec Beta 2.11E-01 1.00E+01 2.11E+00 Q3 - T.Spec Beta 3.16E-01 1.00E+01 3.16E+00 Q4 - T.Spec Beta 1.90E-01 1.00E+01 1.90E+00 Yr - T.Spec Beta 8.13E-01 2.00E+01 4.07E+00

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 21 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 2.23E-02 5.52E-03 6.67E-03 4.70E-03 3.92E-02

2. Avg. Diluted Conc. uCi/ml 1.69E-08 4.38E-09 4.28E-09 2.97E-09 6.84E-09

3. % Applicable Limit % (1) 4.17E-02 1.06E-02 1.90E-02 3.43E-03 9.57E-02 Tritium

1. Total Release Ci 1.94E+01 2.57E+01 4.07E+01 1.37E+01 1.01E+02

2. Avg. Diluted Conc. uCi/ml 1.47E-05 2.04E-05 2.61E-05 8.67E-06 1.74E-05

3. % Applicable Limit % (1) 1.83E-04 3.73E-04 1.15E-03 1.08E-04 1.52E-03 Dissolved and Entrained Gases

1. Total Release Ci 1.61E-02 5.00E-02 9.30E-02 3.40E-02 1.93E-01

2. Avg. Diluted Conc. uCi/ml 1.22E-08 3.97E-08 5.96E-08 2.15E-08 3.36E-08

3. % Applicable Limit % (2) 6.10E-03 1.98E-02 2.98E-02 1.08E-02 1.68E-02 Gross Alpha Radioactivity

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Volume of liquid waste liters 8.29E+05 1.29E+06 3.10E+06 8.39E+05 6.06E+06 Volume of dil. water liters 1.32E+09 1.26E+09 1.56E+09 1.58E+09 5.73E+09 (1)

The most limiting dose compared to the total body and critical organ limits of TRM 3.11.1.2.a.

(2)

Technical Requirement 3.11.1.1 limit of 2.00E-04 uCi/ml for dissolved and entrained noble gases in liquid effluent.

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 22 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2B LIQUID EFFLUENTS - CONTINUOUS MODE REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

- No Nuclide Activities **........................................

Tritium

- No Nuclide Activities **........................................

Dissolved and Entrained Gases

- No Nuclide Activities **........................................

Gross Alpha Radioactivity

- No Nuclide Activities **........................................

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 23 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 2C LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AG-110M Ci 0.00E+00 1.06E-04 0.00E+00 0.00E+00 1.06E-04 CE-141 Ci 2.65E-04 1.29E-04 7.19E-05 1.65E-04 6.30E-04 CO-58 Ci 1.57E-04 0.00E+00 2.68E-06 2.67E-05 1.86E-04 CO-60 Ci 8.79E-03 1.36E-03 1.82E-03 9.53E-04 1.29E-02 CR-51 Ci 1.58E-03 5.74E-04 6.33E-05 8.04E-04 3.02E-03 FE-55 Ci 4.78E-03 1.79E-03 3.39E-03 0.00E+00 9.96E-03 FE-59 Ci 2.46E-04 0.00E+00 0.00E+00 5.15E-05 2.98E-04 I-131 Ci 8.59E-05 4.97E-05 0.00E+00 7.90E-05 2.15E-04 I-133 Ci 6.83E-06 0.00E+00 0.00E+00 6.57E-05 7.25E-05 LA-140 Ci 4.91E-04 4.84E-04 4.46E-04 8.75E-04 2.30E-03 MN-54 Ci 5.27E-03 7.79E-04 7.76E-04 4.45E-04 7.27E-03 MO-99 Ci 3.06E-05 0.00E+00 0.00E+00 2.40E-05 5.45E-05 NA-24 Ci 1.15E-07 0.00E+00 0.00E+00 0.00E+00 1.15E-07 NB-95 Ci 7.51E-05 3.93E-05 4.49E-06 0.00E+00 1.19E-04 NB-97 Ci 5.25E-05 0.00E+00 0.00E+00 0.00E+00 5.25E-05 NP-239 Ci 0.00E+00 1.11E-04 0.00E+00 0.00E+00 1.11E-04 RU-103 Ci 4.33E-05 0.00E+00 0.00E+00 0.00E+00 4.33E-05 SB-124 Ci 1.92E-05 0.00E+00 0.00E+00 0.00E+00 1.92E-05 SB-125 Ci 5.11E-05 0.00E+00 0.00E+00 0.00E+00 5.11E-05 SR-85 Ci 0.00E+00 0.00E+00 2.04E-06 7.17E-06 9.20E-06 SR-91 Ci 0.00E+00 0.00E+00 0.00E+00 6.44E-05 6.44E-05 SR-92 Ci 0.00E+00 4.36E-05 0.00E+00 0.00E+00 4.36E-05 TC-99M Ci 3.54E-05 0.00E+00 0.00E+00 2.63E-05 6.17E-05 Y-92 Ci 6.27E-05 0.00E+00 9.13E-05 1.10E-03 1.25E-03 ZN-65 Ci 2.20E-04 3.04E-05 0.00E+00 2.16E-05 2.72E-04 ZR-95 Ci 2.75E-05 1.68E-05 0.00E+00 0.00E+00 4.43E-05 ZR-97 Ci 0.00E+00 1.12E-05 0.00E+00 0.00E+00 1.12E-05 Totals for Period... Ci 2.23E-02 5.52E-03 6.67E-03 4.70E-03 3.92E-02 Tritium H-3 Ci 1.94E+01 2.57E+01 4.07E+01 1.37E+01 1.01E+02 Totals for Period... Ci 1.94E+01 2.57E+01 4.07E+01 1.37E+01 1.01E+02 Dissolved and Entrained Gases XE-131M Ci 0.00E+00 7.18E-04 0.00E+00 0.00E+00 7.18E-04 XE-133 Ci 9.01E-03 2.57E-02 3.20E-02 1.39E-02 8.06E-02 XE-133M Ci 4.24E-04 9.89E-04 9.79E-04 5.70E-04 2.96E-03 XE-135 Ci 6.71E-03 2.26E-02 6.01E-02 1.95E-02 1.09E-01 Totals for Period... Ci 1.61E-02 5.00E-02 9.30E-02 3.40E-02 1.93E-01 Gross Alpha Radioactivity

- No Nuclide Activities **........................................

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 24 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE Table 2D REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 16 23 54 15 108 Total release time minutes 5.46E+03 8.01E+03 1.94E+04 5.48E+03 3.84E+04 Maximum release time minutes 4.50E+02 3.90E+02 8.46E+02 3.84E+02 8.46E+02 Average release time minutes 3.42E+02 3.48E+02 3.59E+02 3.65E+02 3.55E+02 Minimum release time minutes 4.50E+01 3.13E+02 2.96E+02 3.44E+02 4.50E+01 QTR 1 QTR 2 QTR 3 QTR 4 Average Miss. River stream flow during periods of release of effluent into a flowing stream ft3/sec 4.04E+05 4.07E+05 1.98E+05 4.37E+05

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 25 TABLE 2E Effluent and Waste Disposal Annual Report 2006 Year RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Type Sampling Frequency Minimum Analysis Frequency Type of Activity Analysis Lower Limit of Detection (LLD) uCi/ml A. Batch Waste Release (Liquid Radwaste Recovery Sample Tanks)

P Each Batch P

Each Batch Principal Gamma Emitters: except for Ce-144 I-131 5.00E-07 5.00E-06 1.00E-06 P

One Batch/M M

Dissolved and Entrained Gases (Gamma Emitters) 1.00E-05 P

Each Batch M

Composite H-3 Gross Alpha 1.00E-05 1.00E-07 P

Each Batch Q

Composite Sr-89, Sr-90 Fe-55 5.00E-08 1.00E-06 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 26 Table 2F LIQUID DOSE

SUMMARY

Report for: 2006 Release ID: 10 All Liquid Release Points Liquid Receptor

SITE DOSE LIMIT ANALYSIS================================================

Age Dose Limit Max % of Period - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - T.Spec Any Organ ADULT GILLI 2.09E-03 5.00E+00 4.18E-02 Qtr 2 - T.Spec Any Organ ADULT GILLI 5.36E-04 5.00E+00 1.07E-02 Qtr 3 - T.Spec Any Organ ADULT GILLI 9.69E-04 5.00E+00 1.94E-02 Qtr 4 - T.Spec Any Organ ADULT GILLI 1.73E-04 5.00E+00 3.47E-03 2006 - T.Spec Any Organ ADULT GILLI 4.81E-03 1.00E+01 4.81E-02 Qtr 1 - T.Spec Total Body ADULT TBODY 1.40E-04 1.50E+00 9.34E-03 Qtr 2 - T.Spec Total Body ADULT TBODY 3.73E-05 1.50E+00 2.48E-03 Qtr 3 - T.Spec Total Body ADULT TBODY 7.87E-05 1.50E+00 5.25E-03 Qtr 4 - T.Spec Total Body ADULT TBODY 1.15E-05 1.50E+00 7.69E-04 2006 - T.Spec Total Body ADULT TBODY 3.31E-04 3.00E+00 1.10E-02

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 27 TABLE 3 Effluent and Waste Disposal Annual Report 2006 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/06 to 12/31/06 A. Solid Waste Shipped for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste Units 12 Month Period Waste Class Estimated Error %

m3 7.00E+01 A

See Below Ci 1.28E+02 A

See Below m3 3.41E+00 B

See Below Ci 2.65E+02 B

See Below m3 0.00E+00 C

See Below Spent

Resins, Filter

Sludges, Evaporator Bottoms, etc.

Ci 0.00E+00 C

See Below m3 1.09E+03 A

See Below Dry Compressible

Wastes, Contaminated Equipment, Etc.

Ci 3.85E+00 A

See Below m3 0.00E+00 N/A N/A Irradiated Components, Control Rods, etc.

Ci 0.00E+00 N/A N/A m3 7.65E+01 N/A See Below Other (Water,

EHC, Waste Oil)

Ci 5.49E-01 N/A See Below Note: Volume considered being the total disposal volume of the container.

Radwaste Estimated Error %:

Waste types considered are processed solid waste (i.e. resin, filter media) and non-compactable /

compactable dry active waste.

1. Possible Errors

a.

Volume

b.

Representative Sampling

c.

Instrument/Counting

d.

Dose to Curie Calculations

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 28

2. Volume Error Level indication for processed resins can be determined to +/- 0.5 inches. This correlates to approximately 1.0%. Container manufacturer stated design tolerance allows for 1.0%

deviation from container dimensions. Volume error is not applicable to dry active waste.

3. Representative Sampling Error Sampling error for processed resins is based upon obtaining a representative sample from the waste being processed using an iso-lock sampler. Sampling error from dry active waste is based upon obtaining a representative sample from the material being packaged. This error is estimated to be +/- 10% for all waste types, which is consistent with industry standards.

4. Instrument/Counting Error The error caused by sample geometry, counting time, sample activity and instrument background is estimated to be +/- 10%. The error for radiological survey instrumentation is estimated to be +/- 20%. This error is applicable to all waste types.

5. Dose to Curie Calculations Error The Dose to Curie method used to calculate activity suffers from analytical accuracy in that certain important parameters are neglected. These parameters are geometry of package, measuring instrument characteristics, build-up, internal attenuation effect, and external media attenuation. An activity correction factor is applied to provide adjustment for these factors.

This error is applicable to all waste types.

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 29 Effluent and Waste Disposal Annual Report 2006 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/06 to 12/31/06 Table 3 (continued)

2. Estimates of Major Nuclides by Waste Stream Resins, Filters and Evaporator Bottoms, etc.

(Min 1%)

Dry Compressible Wastes, Contaminated Equipment, etc.

(Min 1%)

Other Water, EHC, Waste Oil, etc. (Min 1%)

Isotope Abundance Curies Isotope Abundance Curies Isotope Abundance Curies H-3 2.023 7.95E+00 N/A N/A N/A N/A N/A N/A Mn-54 2.924 1.15E+01 Mn-54 4.647 1.79E-01 Mn-54 4.692 2.58E-02 Fe-55 72.291 2.84E+02 Fe-55 83.865 3.23E+00 Fe-55 83.578 4.59E-01 Co-60 16.677 6.56+01 Co-60 9.653 3.72E-01 Co-60 9.594 5.27E-02 Zn-65 3.899 1.53E+01 Zn-65 1.387 5.34E-02 Zn-65 1.412 7.75E-03 Determined by Measurement and Correlation.

Packaged in Strong, Tight Liners.

No Solidification Agent or Absorbent Used.

No Irradiated Components, Control Rods, etc. were shipped in 2006.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 15 Truck Energy Solutions - Oak Ridge, TN.

13 Truck Studsvik Processing Facility - Erwin, TN 1

Truck Studsvik RACE - Memphis, TN.

B. No Irradiated Components, Control Rods, Etc. were shipped in 2006.

Irradiated Fuel Shipments Disposition Number of Shipments Mode of Transportation Destination 0

N/A N/A

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 30 TABLE 4 Effluent and Waste Disposal Annual Report 2006 Year ASSUMPTIONS/PARAMETERS FOR DOSES TO A MEMBER OF THE PUBLIC INSIDE SITE BOUNDARY Error!

Bookmark not defined.MEMBER OF THE PUBLIC LOCATION DISTANCE(1)

METERS SECTOR DURATION (HR/YEAR)(2)

People Entering Site Without Consent Alligator Bayou 2500 SW 4.00E+01 Lawn Service Provider General Services Building 115 ENE 3.60E+02 National Guard Activity Center 994 WNW 0.00E+00(3)

RF-13 workers staying onsite Activity Center Trailer City 994 WNW 324(4)

(1) The approximate distances from main plant vent exhaust to location.

(2) Liquid pathways dose is not considered due to the nature of activities that individuals are engaged in.

(3) National Guard/State Police are being evaluated, if applicable, for dose while stationed on site as members of the public. The adult age group is the only age group considered in this category. No National Guard in 2006.

(4) Workers staying at the activity center for RF-13 refueling outage in 2006. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shifts /

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in trailer April 16 through May 12th, 2006. The adult age group is the only age group considered in this category.

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 31 TABLE 5 DOSES TO MEMBERS OF THE PUBLIC ON SITE FROM GASEOUS RELEASES 2006 Dose calc based on Durations Critical Organ Dose Annual (mrem)

Total Body Dose Annual (mrem)

Skin Dose Annual (mrem)

Annual Duration Factor Alligator Bayou 4.61E-05 2.21E-04 1.72E-04 4.57E-03 Lawn Service Provider 3.60E-02 1.74E-01 1.36E-01 4.11E-02 RF-13 workers staying onsite 3.48E-03 3.09E02 3.01E-02 3.70E-02 Delivery Driver 5.25E-03 2.51E-02 1.95E-02 1.43E-02

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 32 Table 6 Effluent and Waste Disposal Annual Report 2006 Year Meteorological Data - Joint Frequency Tables

River Bend Station 2006 ANNUAL EFFLUENT RELEASE REPORT 4/21/2007 33 RIVER BEND STATION JOINT FREQUENCY TABLE ALL STABILITY CLASSES FROM 1/ 1/06 0:00 TO 3/31/06 23:00 PRIMARY SENSORS - 30 FOOT WIND SPEED (METERS/SECOND)