Text

Radioactive Effluent Release Report for 2010
	ML11126A148
Person / Time
Site:	River Bend
Issue date:	04/29/2011
From:	Lorfing D; Entergy Corp, Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RBF1-11-0072, RBG-47142
	Download: ML11126A148 (58)
	v • d • e

Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61N Entergy0 St. Francisville, LA 70775 Tel 225 381 4157 David N. Lorfing Manager-Licensing April 29, 2011 U.S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852-2738

Subject:

Radioactive Effluent Release Report for 2010 River Bend Station - Unit 1 License No. NPF-47 Docket No. 50-458 File Nos.: G9.5, G9.25.1.5 RBG-47142 RBF1-1 1-0072

Dear Sir or Madam,

Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for the period January 1, 2010, through December 31, 2010. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.3.

Should you have any questions regarding the enclosed information, please contact Mr. David Lorfing at (225) 381-4157.

Sincerely, DNL/wjf enclosure

Radioactive Effluent Release Report for 2010 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission (w/o Enclosure)

Region IV 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Resident Inspector (w/o Enclosure)

PO Box 1050 St. Francisville, LA 70775 Mr. Alan B. Wang, Project Manager U.S. Nuclear Regulatory Commission MS O-8G14 11555 Rockville Pike Rockville, MD 20852-2738

River Bend Station 2010 Regulatory Guide 1.21 Page 1 of 56 2010 ANNUAL EFFLUENT RELEASE REPORT PREPARED BY: / 3 4/z 7/1/

William H. Spell / Senior HP/Chem Specialist REVIEWED BY: 7 X2"7 Robert W. Heath / Manager - Chemistry REVIEWED BY: *, 4 6f 6/'rie' f'i//

Glenn Pierce / Radiation Protection Manager APPROVED BY: &;' l&5 ý911/

Eric Olson / Site Vice President

River Bend Station 2010 Regulatory Guide 1.21 Page 2 of 56 TABLE OF CONTENTS I. INTRODUCTION ................................................................................................ 4 II. SUPPLEMENTAL INFORMATION ........................................................................ 4 Ill. GASEOUS EFFLUENT

SUMMARY

INFORMATION ............................................ 11 Iv. LIQUID EFFLUENT

SUMMARY

INFORMATION ................................................ 11 V. SOLID W ASTE ........................................................................................................ 11 VI. RADIOLOGICAL IMPACT ON MAN (40CFR190) ................................................... 11 VII. METEOROLOGICAL DATA ................................................................................ 13 VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION O PERABILITY .......................................................................................... 13 IX. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY .......................................................................................... 14 X. LIQUID HOLD UP TANKS .................................................................................. 14 Xi. RADIOLOGICAL ENVIRONMENTAL MONITORING .......................................... 14 XII. LAND USE CENSUS ............................................................................................ 14 XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM) ............................................... 15 XIV. MAJOR CHANGES To RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS .............................................................. 15 XV. PROCESS CONTROL PROGRAM (PCP) .............................................................. 15 XVI. INDUSTRY GROUND WATER PROTECTION INITIATIVE (GPi) - FINAL GUIDANCE DOCUMENT (NEI 07-07) OBJECTIVE ANNUAL REPORTING ............................................................................................ 15 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ....................... 16 TABLE lB GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE .......... 17 TABLE IC GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE ................ 19 TABLE ID GASEOUS EFFLUENTS - MIXED MODE RELEASES - CONTINUOUS M ODE ...................................................................................................... 20 TABLE lE SUPPLEMENTAL INFORMATION ................................................................ 22

River Bend Station 2010 Regulatory Guide 1.21 Page 3 of 56 TABLE IF RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ............................................................................................... 23 TABLE 1G GASEOUS ANNUAL DOSE

SUMMARY

REPORT ........................................ 24 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES .......................... 25 TABLE 2B LIQUID EFFLUENTS - CONTINUOUS MODE ............................................. 26 TABLE 2c LIQUID EFFLUENTS - BATCH MODE ........................................................ 27 TABLE 2D SUPPLEMENTAL INFORMATION .............................................................. 28 TABLE 2E RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM ............................................................................................... 29 TABLE 2F LIQUID ANNUAL DOSE

SUMMARY

REPORT ............................................. 30 TABLE 3 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ................................. 31 TABLE 4 ASSUMPTIONS/PARAMETERS FOR DOSES To A MEMBER OF THE PUBLIC INSIDE SITE BOUNDARY ........................................................... 33 TABLE 5 DOSES To MEMBERS OF THE PUBLIC ON SITE ....................................... 34 TABLE 6 2010 YEAR METEOROLOGICAL DATA - JOINT FREQUENCY TABLES ......... 35 TABLE 7 ATMOSPHERIC DISPERSION AND DEPOSITION RATES FOR THE MAXIMUM INDIVIDUAL DOSE CALCULATIONS .................................... 44 TABLE 8 GROUNDWATER MONITORING WELL SAMPLE RESULTS ......................... 45

River Bend Station 2010 Regulatory Guide 1.21 Page 4 of 56 I. INTRODUCTION This is the annual Radioactive Effluent Release Report for the period of January 1, 2010, through December 31, 2010. 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 I 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 I Ni (X/Q) Qi < 10 mrads/qtr i=1 < 20 mrads/yr b) Radioiodines (1-131 & 1-133) and Particulate In accordance with Technical Requirement 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from radioiodines (1-131 and 1-133), 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&*DP.t = Dose in mrem to the organ (rt) for the age group of interest from

River Bend Station 2010 Regulatory Guide 1.21 Page 5 of 56 radioiodine (1-131, 1-133, 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) 1 Ri- (D/Q) 0i and 1=1 n

D, X DI&8D~t < 7.5 mrem/qtr z= 1 r 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:

D = i Ait..AtI (DF) D, and n

DTOTALt = Di, i=1 DTOTALT = Total dose commitment to the organ (-t) 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)

River Bend Station 2010 Regulatory Guide 1.21P Page 6 of 56

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

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:

DRT= Dose rate to the total body in mrem/yr n

1 Ki (X/Q) Qi < 500 mrem/yr and i=1 DRsKJN= Dose rate to the skin in mrem/yr n

1 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 (1-131 & 1-133) 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 -r for the age pathway group of interest from Radioiodines (1-131 & 1-133), tritium, and 8 day particulate via the inhalation pathway in mrem/yr.

River Bend Station 2010 Regulatory Guide 1.21 Page 7 of 56 n _

1 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 dissolved or entrained noble gases, the concentration shall be limited to 2.OE-04 microcuries/milliliter total concentration.

d. Technical Requirement 3.11.2.5 - Ventilation Exhaust Treatment 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.

River Bend Station 2010 Regulatory Guide 1.21 Page 8 of 56

2. Liquid Releases The Effluent Concentration Limits of radioactive materials in liquid effluents are 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 IF.

Sampling and analysis of these effluent streams provide noble gas radionuclide relative abundance that can then be applied to the noble gas 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 (1-131 & 1-133)

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 1F. 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

River Bend Station 2010 Regulatory Guide 1.21 Page 9 of 56 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 (Cherenkov counting). Gross alpha analysis is performed using a zinc sulfide scintillation counter.

c. Tritium Tritium grab samples are obtained from the three gaseous release points at the specified frequencies listed in Table 1F 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.

d. Carbon-14 (C-14)

C-14 release details are discussed in Section VI.

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 2E. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high purity 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 (Cherenkov counting). Iron-55 is counted with a liquid scintillation counter after digestion of the iron. Gross alpha analysis is performed using a zinc sulfide scintillation counter. The activity of each nuclide released to the environment is determined from the nuclide specific concentration and total tank volume released.

River Bend Station 2010 Regulatory Guide 1.21 Page 10 of 56 D. Batch Releases

1. Liquid Effluents Batch releases and receiving stream flow from River Bend Station during the reporting period of January 1, 2010, through December 31, 2010 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.

2. Gaseous Effluents There were no routine batch releases of gaseous effluents from River Bend Station during the reporting period of January 1, 2010, through December 31, 2010.

E. Abnormal Releases Number of abnormal liquid releases: 0 Number of abnormal gaseous releases: 0 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 error (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%

lodines : + 18.6%

Particulate: + 18.6%

Tritium: + 18.2%

River Bend Station 2010 Regulatory Guide 1.21 Page I11of 56

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 = \((E 1 )L + (E2)L +

where:

ET = total error El, 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 "O.OOE+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 IF. 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 "O.OOE+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 2E. 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 (see summary below) 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

River Bend Station 2010 Regulatory Guide 1.21 Page 12 of 56 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.

Carbon-14 The bounding annual dose from C-14 was calculated using guidance from Regulatory Guide 1.21, Revision 2, and the methodology in Regulatory Guide 1.109, Appendix C and Appendix E. The C-14 source term of 11 curies was taken from the site calculation PR(C)-

359-3A, Gaseous Releases per NUREG-0016 Revision 1. Carbon-14 does not have dose factors associated with standing on contaminated ground; therefore, no ground plane dose was calculated. There is no milk pathway within five miles of River Bend Station so this pathway is not evaluated. RBS does not take credit for decay in the X/Q. This calculation assumes the inhalation, meat and vegetation pathways are at the site boundary in the sector with the highest X/Q. The dose from liquid effluents is not calculated as the dose contribution from C-14 is considered to be insignificant as indicated in Regulatory Guide 1.21 Revision 2. According to EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, 95% of the carbon released is in the form of carbon dioxide and this contributes the highest dose to man. The ingestion pathway specifically vegetation, is the most likely route of intake for man. An assumption has been made for gaseous releases that plants obtain all of their C-14 from carbon dioxide.

Dose not including C-14:

Organ mrem Total Body 1.17E-01 Skin 3.51E-01 Thyroid 1.18E-01 Other Organ 1.34E-01 Bounding Dose from C-14 only:

Organ mrem Total Body 9.39E-01 Skin 0.OOE+00 Thyroid 9.39E-01 Other Organ 4.70E+01 (Bone)

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 an employee staying at RBS during the week and is conservatively calculated to have stayed at least four days per week for 50 weeks. It should be noted that liquid effluent pathway dose was not considered since these

River Bend Station 2010 Regulatory Guide 1.21 Page 13 of 56 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 2010 was 97.5 %.

VIIL RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY Section TR 3.3.11.2 of the River Bend Technical Requirements Manual (TRM) addresses "Radioactive Liquid Effluent Monitoring Instrumentation" requirements and actions to be taken. CWS-FE 113 is identified TRM Table 3.3.11.2-1 as a Cooling Tower Blowdown Line Radioactive Liquid Effluent Monitoring instrument monitoring flow rate. Action B.2 of TR 3.3.11.2 addresses restoring inoperable channels to an operable status with a completion time of 30 days, and is applicable for instrument CWS-FE1 13. If the 30-day time frame is exceeded, Action E. 1 requires a suspension of the radioactive effluent release and Action E.2 requires an explanation as to why the inoperability was not corrected in a timely manner in the next Annual Radioactive Effluent Release Report. During the period from January 1, 2010, through December 31, 2010, RBS complied with this requirement and restored to operable status within the required time, except as noted in the following paragraph:

On August 23, 2010 @ 2300, a cooling tower blowdown water low-flow alarm per instrument CWS-FE 113 was received in the Auxiliary Control Room. No operator actions or activities were occurring that would have affected blowdown flow. Indicated flow on CWS-FE 113 lowered to approximately 2000 gallons-per-minute (gpm). Operators verified blowdown flow with another instrument (CWS-FR1 12) which indicated approximately 2500 gpm. Beginning on August 24, 2010, CWS-FE1 13 was vented and calibrated multiple times with no success keeping the low flow alarm cleared. After additional activities, the instrument was subsequently declared operable on September 21, 2010. A liquid radwaste discharge, released per plant procedures via the cooling tower blowdown line, was initiated on September 22, 2010, and continued until 0235 on September 23, 2010. There was no issue until a subsequent question arose later in the day on September 23, 2010, in regard to the testing performed on CWS-FE 113 prior to returning it to service [operable status]. After the question arose, CWS-FE 113 was administratively declared inoperable, the August 23, 2010, inoperability initiation time was re-instituted, and additional testing was performed with a surveillance test that checked the operability. The surveillance test was performed satisfactorily with no adjustments made. However, restoring the inoperability condition meant that the discharge that began on September 2 2 nd and ended early on September 23",

exceeded the 30-day time requirement for restoring inoperable channels to an operable status by 3-4 hours. After the additional testing, which confirmed the original operability declaration and supported that CWS-FE 113 performed its design function during the liquid radwaste discharge, CWS-FE 113 was again restored to an operable status early in the morning on September 24, 2010.

River Bend Station 2010 Regulatory Guide 1.21 Page 14 of 56 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, 2010, through December 31, 2010, 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, 2010, through December 31, 2010 was less than or equal to the 10 curie limit as required by Technical Specification 5.5.8.b.

XI. RADIOLOGICAL ENVIRONMENTAL MONITORING There were no changes to the Radiological Environmental Monitoring Program during the reporting period January 1, 2010, through December 31, 2010.

XII. LAND USE CENSUS The Land Use Census for 2010 was conducted in accordance with procedure ESP-8-051, as required by Technical Requirements Manual (TRM) (TR 3.12.2). 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 2010 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 data is collected to further support the possibility of removing invertebrates from the liquid dose conversion factors. This information represents four 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.

River Bend Station 2010 Regulatory Guide 1.21 Page 15 of 56 XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the ODCM in 2010.

XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Engineering has performed a review of the Asset Suite database to evaluate non-administrative design changes completed or partially completed during 2010 involving the subject systems (i.e. changes classified as evaluations or nuclear changes). 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 Updated Safety Analysis Report (USAR).

No engineering change was identified as being completed during this time period that modified any radioactive waste system major component such that the processing method or effluent was changed. Also no changes were identified affecting the method of processing solid, liquid or gaseous waste or 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 liquid, solid or gaseous radwaste treatment systems.

XV. PROCESS CONTROL PROGRAM (PCP)

There were no changes to the PCP (EN-RW-105) in 2010.

XVI. INDUSTRY GROUND WATER PROTECTION INITIATIVE (GPI) - FINAL GUIDANCE DOCUMENT (NEI 07-07) OBJECTIVE ANNUAL REPORTING Ground water samples for gamma radiation and tritium were taken in support of the GPI.

These samples are not part of the Radiological Environmental Monitoring Program. There have been no positive groundwater samples since the NEI groundwater monitoring sampling began in the third quarter 2007. The Minimum Detectable Concentration (MDC) in all samples taken in support of the GPI is less than the Lower Limit of Detection as required in Technical Requirement 3.12.1 (Environmental LLDs). The sample results are located in Table 8.

River Bend Station 2010 Regulatory Guide 1.21 Page 16 of 56 TABLE 1A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 1. 02E+01 1. 92E+01 5. 85E+01 3. 26E+01 1 . 20E+02

2. Avg. Release Rate uCi/sec 1. 31E+00 2.44E+00 7. 36E+00 4. 11E+00 3. 82E+00

3. % Applicable Limit % (1) 9. 98E-02 2. 91E-01 5. 18E-01 5. 33E-01 7.21E-01 Iodine-131

1. Total Release Ci 1. 07E-03 2. 62E-03 1. 66E-03 4. 22E-04 5. 77E-03

2. Avg. Release Rate uCi/sec 1. 37E-04 3. 33E-04 2. 09E-04 5. 31E-05 1. 83E-04

3. % Applicable Limit % (2) 4 .58E-01 1. 15E+00 7. 51E-01 2. 62E-01 1. 28E+00 Particulates Half Life >= 8 days

1. Total Release Ci 3. 02E-04 9. 66E-04 8. 66E-04 3. 97E-04 2. 53E-03

2. Avg. Release Rate uCi/sec 3. 89E-05 1.23E-04 1. 09E-04 5. OOE-05 8. 02E-05

3. % Applicable Limit % (2) 1. 34E-01 3. 46E-01 2. 05E-01 5.42E-02 3. 62E-01 Tritium

1. Total Release Ci 4. 81E+00 6. 50E+00 3. 48E+00 4.13E+00 1. 89E+01

2. Avg. Release Rate uCi/sec 6. 18E-01 8. 27E-01 4. 38E-01 5. 20E-01 6. OOE-01

3. % Applicable Limit % (2) 1. 30E-01 1. 26E-01 9. 91E-02 2. 05E-01 2. 54E-01 Carbon-14

1. Total Release Ci 2.72E+00 2.74E+00 2.77E+00 2.77E+00 1. 10E+00

2. Avg. Release Rate uCi/sec 3. 50E-01 3.4 9E-01 3. 48E-01 3. 48E-01 3. 49E-01

3. % Applicable Limit % (2) 1. 15E+01 1. 56E+01 1. 57E+01 1. 57E+01 2. 71E+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 2010 Regulatory Guide 1.21 Page 17 of 56 TABLE lB GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT' FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 0.OOE+00 0.OOE+00 1.60E-01 0. OOE+00 1. 60E-01 XE-133M Ci 0.OOE+00 0.OOE+00 0.OOE+00 0 . OOE+00 0. OOE+00 XE-135 Ci 4.11E-01 2.75E+00 1.22E+00 3. 12E+00 7.50E+00 XE-135M Ci 3.45E-01 7.09E-01 7.92E-01 2. 62E+00 4.47E+00 Totals for Period... Ci 7.55E-01 3.46E+00 2.17E+00 5.74E+00 1.21E+01 Iodines 1-131 Ci 4. 92E-06 3. 92E-05 4.47E-05 1. 53E-05 1.04E-04 1-133 Ci 0. OOE+00 1. 42E-04 1. 91E-04 4.86E-05 3. 82E-04 Totals for Period... Ci 4. 92E-06 1.82E-04 2.36E-04 6.39E-05 4.86E-04 Particulates Half Life >= 8 days CE-141 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0 OOE+00 0. OOE+00 CO-57 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0 OOE+00 0. OOE+00 CO-58 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CO-60 Ci 2.21E-05 7.61E-05 7.60E-05 2 59E-06 1. 77E-04 CR-51 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0 OOE+00 0. OOE+00 CS-137 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 FE-59 Ci 0.OOE+00 0.OOE+00 0. 00E+00 0 00E+00 0 OOE+00 MN-54 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0 OOE+00 0. OOE+00 NB-95 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0 OOE+00 0. OOE+00 RU-103 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 RU-106 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 SR-89 Ci 0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 ZN-65 Ci 0.00E+00 0.OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 Totals for Period... Ci 2.21E-05 7.61E-05 7. 60E-05 2. 59E-06 1. 77E-04

River Bend Station 2010 Regulatory Guide 1.21 Page 18 of 56 Tritium H-3 Ci 1. 70E+00 1. 48E+00 1. 31E+00 2.13E+00 6. 63E+00 Totals for Period... Ci 1.70E+00 1. 48E+00 1 . 31E+00 2.13E+00 6. 63E+00

River Bend Station 2010 Regulatory Guide 1.21 Page 19 of 56 TABLE iC GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 XE-135 Ci 0. OOE+00 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 XE-135M Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Iodines 1-131 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 1-133 Ci 0 .OOE+00 0 . OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 0. 0OE+00 0. OOE+00 0 .OOE+00 0. OOE+00 0. OOE+00 Particulates Half Life >= 8 days BA-140 Ci 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0. 00E+00 CO-60 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 0. 00E+00 MN-54 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 0. OOE+00 SR-89 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 SR-90 Ci 0 . OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 0. OOE+00 ZN-65 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 0. OOE+00 Totals for Period... Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 Tritium H-3 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 Totals for Period... Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00

River Bend Station 2010 Regulatory Guide 1.21 Page 20 of 56 TABLE ID GASEOUS EFFLUENTS - MIXED MODE RELEASES - CONTINUOUS MODE REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 KR-85 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 0. OOE+00 KR-85M Ci 0. OOE+00 0. OOE+00 2.44E+00 0. OOE+00 2.4 4E+00 KR-87 Ci 0. 00E+00 0. 00E+00 9. 31E-01 0. OOE+00 9. 31E-01 KR-88 Ci 0. OOE+00 0. OOE+00 2. 23E-01 0. OOE+00 2. 23E-01 XE-131M Ci 0. OOE+00 0. 00E+00 0.OOE+00 0. OOE+00 0. OOE+00 XE-133 Ci 1. 62E-01 4. 23E-01 3. 88E+00 5. 57E-01 5. 02E+00 XE-133M Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 XE-135 Ci 5. 78E+00 7. 39E+00 2. 37E+01 1. 59E+01 5. 28E+01 XE-135M Ci 3.47E+00 7 .91E+00 1.41E+01 1. 04E+01 3. 58E+01 XE-137 Ci 0. OOE+00 0. OOE+00 3. 37E+00 0. OOE+00 3. 37E+00 XE-138 Ci 0. OOE+00 0 OOE+00 7.71E+00 0 OOE+00 7 71E+00 Totals for Period... Ci 9. 40E+00 1. 57E+01 5. 64E+01 2. 69E+01 1 . 08E+02 Iodines 1-131 Ci 1.06E-03 2. 58E-03 1. 62E-03 4. 07E-04 5.66E-03 1-132 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 1-133 Ci 1. 02E-02 2. 53E-02 1.24E-02 3. 02E-03 5. 09E-02 1-135 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 1. 12E-02 2.79E-02 1.40E-02 3.43E-03 5. 65E-02 Particulates Half Life >= 8 days BA-140 Ci 8. 80E-05 5. 23E-04 4. 88E-04 2. 05E-04 1.30E-03 CE-139 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CE-141 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CO-58 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CO-60 Ci 3. 71E-05 4 .12E-05 6. 54E-05 0. OOE+00 1. 44E-04

River Bend Station 2010 Regulatory Guide 1.21 Page 21 of 56 CR-51 Ci 0.0OE+00 0. OOE+00 0.00E+00 0.00E+00 0.OOE-i00 CS-134 Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CS-137 Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0 . OOE+00 FE-59 Ci 0.00E+00 0 . OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 MN-54 Ci 0.OOE+00 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 RU-103 Ci 0.OOE+00 0. OOE+00 0. 00E+00 0. OOE+00 0. OOE+00 SR-89 Ci 1.55E-04 3.13E-04 2.37E-04 1 90E-04 8. 93E-04 SR-90 Ci 1.52E-07 1.28E-05 0. OOE+00 0. OOE+00 1. 30E-05 ZN-65 Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 2.80E-04 8. 90E-04 7. 90E-04 3. 95E-04 2 . 35E-03 Tritium H-3 Ci 3.10E+00 5.02E+00 2.17E+00 2. OOE+00 1. 23E+01 Carbon-14 C-14 Ci 2.72E+00 2.74E+00 2.77E+00 2.77E+00 1.10E+01

River Bend Station 2010 Regulatory Guide 1.21 Page 22 of 56 Table 1E SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0 0 0 0 0 Total release time minutes 0.OOE+00 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 Maximum release time minutes 0.00E+00 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 Average release time minutes 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Minimum release time minutes 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00

River Bend Station 2010 Regulatory Guide 1.21 Page 23 of 56 TABLE iF RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Sampling Minimum Type of Activity Lower Limit Type Frequency Analysis Analysis of Detection Frequency (LLD) uCi/ml A. Main Plant M M Principal Gamma Exhaust Duct Grab Sample Emitters 1.OOE-04 H-3 1.00E-06 B. Fuel Building M M Principal Gamma Ventilation Grab Sample Emitters 1.OOE-04 Exhaust Duct H-3 1.OOE-06 C. Radwaste M M Principal Gamma Building Grab Sample Emitters 1.OOE-04 Ventilation Exhaust Duct D. All Release Continuous W 1-131 1.OOE-12 Types as listed Charcoal in A, B, & C Sample above 1-133 1.OOE-10 Continuous W Principal Gamma Particulate Emitters (1-131, 1.OOE-11 Sample Others)

Continuous M Gross Alpha Composite 1.00E-11 Particulate Sample Continuous Q Sr-89, Sr-90 Composite 1.OOE-11 Particulate Sample Continuous Noble Gas Noble Gases Monitor Gross Beta or 1.00E-06 Gamma W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days

River Bend Station 2010 Regulatory Guide 1.21 Page 24 of 56 Table 1G GASEOUS ANNUAL DOSE

SUMMARY

REPORT I&P DOSE LIMIT ANALYSIS Age Dose Limit Max % of Period-Limit Group Organ (mrem) (mrem) Limit Ql - T.Spec Any Organ CHILD THYROID 5.42E-02 7.50E+00 7.22E-01 Q2 - T.Spec Any Organ CHILD THYROID 1.22E-01 7.50E+00 1.62E+00 Q3 - T.Spec Any Organ CHILD THYROID 7.91E-02 7.50E+00 1.05E+00 Q4 - T.Spec Any Organ CHILD THYROID 2.91E-02 7.50E+00 3.88E-01 Yr - T.Spec Any Organ CHILD THYROID 2.84E-01 1.50E+01 1.89E+00 Carbon-14 (Bounding calculation)

Ql - T.Spec Any Organ CHILD BONE 1.16E+00 7.50E+00 1.55E+01 Q2 - T.Spec Any Organ CHILD BONE 1.17E+00 7.50E+00 1.56E+01 Q3 - T.Spec Any Organ CHILD BONE 1.18E+00 7.50E+00 1.57E+01 Q4 - T.Spec Any Organ CHILD BONE 1.18E+00 7.50E+00 1.57E+01 Yr - T.Spec Any Organ CHILD BONE 4.70E+00 1.50E+01 3.13E+01 NG DOSE LIMIT ANALYSIS Dose Limit % of Period-Limit (mrad) (mrad) Limit Ql - T.Spec Gamma 4.99E-03 5.OOE+00 9.98E-02 Ql - T.Spec Beta 3.47E-03 1.OOE+01 3.47E-02 Q2 - T.Spec Gamma 1.45E-02 5.0OE+00 2.91E-01 Q2 - T.Spec Beta 1.23E-02 1.OOE+01 1.23E-01 Q3 - T.Spec Gamma 2.59E-02 5.00E+00 5.18E-01 Q3 - T.Spec Beta 2.265-02 1.ODE+01 2.265-01 Q4 - T.Spec Gamma 2.66E-02 5.00E+00 5.33E-01 Q4 - T.Spec Beta 1.78E-02 1.OOE+01 1.78E-01 Yr - T.Spec Gamma 7.21E-02 1.00E+01 7.21E-01 Yr - T.Spec Beta 5.61E-02 2.00E+01 2.81E-01

River Bend Station 2010 Regulatory Guide 1.21 Page 25 of 56 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 1. 08E-05 1.64E-05 4. 78E-04 8. 59E-06 5.14E-04

2. Avg. Diluted Conc. uCi/ml 7.83E-12 1. 17E-l1 3.31E-10 6. 20E-12 9. 17E-11

3. % Applicable Limit % (1) 1. 03E-06 3. 30E-07 1. 33E-04 6.53E-07 3.06E-05 Tritium

1. Total Release Ci 1. 10E+01 2. 25E+00 2. 37E+01 6. 67E+00 4. 35E+01

2. Avg. Diluted Conc. uCi/ml 7. 32E-06 1. 61E-06 1. 64E-05 4.81E-06 7.77E-06

3. % Applicable Limit % (1) 1. 04E-04 4. 52E-06 6.54E-04 5.09E-05 2.58E-04 Dissolved and Entrained Gases

1. Total Release Ci 5. 80E-03 9. 94E-04 2.54E-02 9.42E-03 4. 17E-02

2. Avg. Diluted Conc. uCi/ml 4. 21E-09 7. 11E-10 1. 76E-08 6.80E-09 7.43E-09

3. % Applicable Limit % (2) 2. 1OE-03 3. 55E-04 8 .82E-03 3. 39E-03 3.72E-03 Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Volume of liquid waste liters 8.84E+05 1.90E+05 2.69E+06 7.15E+05 4.48E+06 Volume of dil. water liters 1.38E+09 1.40E+09 1.44E+09 1.39E+09 5.60E+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.OOE-04 uCi/ml for dissolved and entrained noble gases in liquid effluent.

River Bend Station 2010 Regulatory Guide 1.21 Page 26 of 56 TABLE 2B LIQUID EFFLUENTS - CONTINUOUS MODE REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases

No Nuclide Activities **

Tritium

- No Nuclide Activities **

Dissolved and Entrained Gases

- No Nuclide Activities **

Gross Alpha Radioactivity

- No Nuclide Activities **

River Bend Station 2010 Regulatory Guide 1.21P Page 27 of 56 TABLE 2C LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases CO-60 Ci 1. 08E-05 1. 64E-05 4.78E-04 8.59E-06 5.14E-04 Totals for Period... Ci 1.08E-05 1. 64E-05 4.78E-04 8.59E-06 5. 14E-04 Tritium H-3 Ci 1.10E+01 2 . 25E+00 2. 37E+01 6. 67E+00 4. 35E+01 Totals for Period... Ci 1. 10E+01 2.25E+00 2. 37E+01 6. 67E+00 4. 35E+01 Dissolved and Entrained Gases XE-133 Ci 2.12E-03 2.18E-04 9. 31E-03 3. 97E-03 1.56E-02 XE-133M Ci 3. 92E-05 0. O0E+00 6. 29E-05 0. OOE+00 1 . 02E-04 XE-135 Ci 3. 64E-03 7. 76E-04 1. 61E-02 5. 45E-03 2. 60E-02 Totals for Period... Ci 5.80E-03 9. 94E-04 2. 54E-02 9. 42E-03 4.17E-02 Gross Alpha Radioactivity

- No Nuclide Activities

River Bend Station 2010 Regulatory Guide 1.21 Page 28 of 56 Table 2D SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 16 4 49 13 82 Total release time minutes 5.71E+03 1.23E+03 1.75E+04 4. 62E+03 2. 90E+04 Maximum release time minutes 3.94E+02 3. 77E+02 4. 03E+02 3. 96E+02 4. 03E+02 Average release time minutes 3.57E+02 3. 07E+02 3. 57E+02 3. 55E+02 3. 54E+02 Minimum release time minutes 3.37E+02 1. 68E+02 3. 14E+02 3. 21E+02 1. 68E+02 QTR 1 QTR 2 QTR 3 QTR 4 3

Average Mississippi ft /sec 777.311 746.846 466.152 301.087 River stream flow during periods of release of effluent into a ,flowing stream

River Bend Station 2010 Regulatory Guide 1.21 Page 29 of 56 TABLE 2E RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Sampling Minimum Type of Activity Lower Limit Type Frequency Analysis Analysis of Detection Frequency (LLD) uCi/ml A. Batch Waste P P Principal Gamma 5.OOE-07 Release (Liquid Each Batch Each Batch Emitters: except Radwaste for Ce-144 5.OOE-06 Recovery Sample Tanks) 1-131 1.00E-06 P M Dissolved and One Batch/M Entrained Gases 1.OOE-05 (Gamma Emitters)

P M H-3 1.OOE-05 Each Batch Composite Gross Alpha 1.00E-07 P Q Sr-89, Sr-90 5.OOE-08 Each Batch Composite Fe-55 1.OOE-06 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days

River Bend Station 2010 Regulatory Guide 1.21 Page 30 of 56 Table 2F LIQUID ANNUAL DOSE

SUMMARY

REPORT Report for: 2010 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 1. 61E-06 5. OOE+00 3. 22E-05 Qtr 1 - T.Spec Total Body ADULT TBODY 1.57E-06 1. 50E+00 1.04E-04 Qtr 2 - T.Spec Any Organ ADULT GILLI 8.43E-08 5. OOE+00 1. 69E-06 Qtr 2 - T.Spec Total Body ADULT TBODY 6. 97E-08 1. 50E+00 4. 65E-06 Qtr 3 - T.Spec Any Organ ADULT GILLI 1. 65E-05 5. OE+00 3. 30E-04 Qtr 3 - T.Spec Total Body ADULT TBODY 1. 06E-05 1. 50E+00 7. 07E-04 Qtr 4 - T.Spec Any Organ ADULT GILLI 7.96E-07 5.00E+00 1. 59E-05 Qtr 4 - T.Spec Total Body ADULT TBODY 7. 67E-07 1. 50E+00 5. lIE-05 2010 - T.Spec Any Organ ADULT GILLI 1. 08E-05 1.00E+01 1. 08E-04 2010 - T.Spec Total Body ADULT TBODY 8. 10E-06 3. 00E+00 2 . 70E-04

River Bend Station 2010 Regulatory Guide 1.21 Page 31 of 56 TABLE 3 Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/10 to 12/31/10 A. Solid Waste Shipped for Burial or Disposal (Not Irradiated Fuel)

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

Spent Resins, Filter m3 5.57E+01 A +/- 25%

Sludges, Evaporator Ci 1.71E+02 A Bottoms, Etc. m3 0.OOE+00 B Ci 0.OOE+00 B m3 2.69E+00 C Ci 9.34E+02 C Dry Compressible Wastes, m3 2.10E+02 A _ 25%

Contaminated Equipment Ci 5.24E+01 A Etc.

Irradiated Components, m3 0.OOE+00 Control Rods, Etc. Ci 0.00E+00 Other m3 1.46E+01 A _ 25%

(Water, EHC, Waste Oil, Ci 4.03E-02 A etc.)

River Bend Station 2010 Regulatory Guide L.21 Page 32 of 56 Effluent and Waste Disposal Annual Report 2010 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/10 to 12/31/10 Table 3 (continued)

2. Estimates of Major Nuclides by Waste Stream Resins, Filters, Evaporator Dry Compressible Wastes, Other Bottoms, Etc. Contaminated Equipment, Water, EHC, Waste Oil, Etc.

(Min 1%) Etc. (Min 1%)

(Min 1%)

Isotope % Abundance Curies Isotope % Abundance Curies Isotope % Abundance Curies FE-55 77.63 8.58E+02 MN-54 2.161 1.13E-02 MN-54 2.233 9.01E-04 CO-60 12.09 1.34E+02 FE-55 63.907 3.35E-01 FE-55 59.539 2.40E-02 NI-63 2.985 3.30E+01 CO-60 30.997 1.63E-01 CO-60 35.551 1.43E-02 ZN-65 2.82 3.12E+01 SR-90 2.604 2.88E+01 No Control Rods, Etc. were shipped in 2010

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 8 Truck Energy Solutions (Bear Creek)- Oak Ridge, TN 1 Truck Energy Solutions (Gallaher)-Oak Ridge, TN 9 Truck Clive Disposal Facility (Containerized) - Clive, UT 1 Truck Studsvik Processing Facility LLC - Erwin, TN B. Irradiated Fuel Shipments Disposition Number of Shipments Mode of Transportation Destination 0 N/A N/A

River Bend Station 2010 Regulatory Guide 1.21 Page 33 of 56 TABLE 4 ASSUMPTIONS/PARAMETERS FOR DOSES TO A MEMBER OF THE PUBLIC INSIDE SITE BOUNDARY MEMBER OF LOCATION DISTANCE(') SECTOR DURATION THE PUBLIC METERS (HR/YEAR)(2)

People Entering Site Without Alligator Bayou 2500 SW 40 Consent National Guard Activity Center 994 WNW 0(3)

Workers staying Activity Center 994 WNW 2400(')

onsite Trailer City (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 2010.

(4) Workers began staying at the Activity Center Trailer City beginning April 10, 2007 and have been permitted to stay long term. During refueling outages additional workers were on site for about 60 days. The long term indivduals will be the receptors for this pathway. For 2010, this estimate is based on 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per day, 4 days per week for 50 weeks, totaling 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months . The adult age group is the only age group considered for this activity.

River Bend Station 2010 Regulatory Guide 1.21 Page 34 of 56 TABLE 5 DOSES TO MEMBERS OF THE PUBLIC ON SITE FROM GASEOUS RELEASES 2010 Critical Total Skin Dose Annual Organ Body Dose Annual Duration Dose Annual (mrem) Factor Annual (mrem)

(mrem)

Alligator 1.32E-04 1.48E-05 2.80E-04 4.57E-03 Bayou Workers 1.11E-02 1.85E-02 3.41E-02 2.74E-01 staying onsite

River Bend Station 2010 Regulatory Guide 1.21 Page 35 of 56 Table 6 2010 Year Meteorological Data - Joint Frequency Tables

River Bend Station 2010 Regulatory Guide 1.21 Page 36 of 56 RIVER BEND STATION JOINT FREQUENCY TABLE ALL STABILITY CLASSES FROM 1/01/10 0:00 TO 3/31/10 23:00 PRIMARY SENSORS - 30 FOOT WIND SPEED (METERS/SECOND)