Text

Submittal of Radioactive Effluent Release Report for 2011
	ML12124A256
Person / Time
Site:	River Bend
Issue date:	04/30/2012
From:	Clark J; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RBF1-12-0060, RBG-47237
	Download: ML12124A256 (87)
	v • d • e

SEntergy Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61N St. Francisville, LA 70775 Tel 225-381-4177 Joseph A. Clark Manager-Licensing April 30, 2012 U. S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852-2738 RBG-47237 RBF1-12-0060

Subject:

Radioactive Effluent Release Report for 2011 River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for the period January 1, 2011, through December 31, 2011. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.3.

No commitments are contained in this letter. Should you have any questions regarding the enclosed information, pleap contact Mr. Joseph A. Clark, at (225) 381-4177.

JAC/wjf Enclosure

Radioactive Effluent Release Report for 2011 RBG-47237 Page 2 of 2 cc:

U.S. Nuclear Regulatory Commission (w/o Enclosure)

Region IV 1600 E. Lamar Blvd.

Arlington, TX 76011-4511 NRC Resident Inspector (w/o Enclosure)

PO Box 1050 St. Francisville, LA 70775 Ms. Tracie Lowrey Public Utility Commission of Texas 1701 N. Congress Ave.

Austin, TX 78711-3326 Mr. Alan Wang, Project Manager U.S. Nuclear Regulatory Commission MS 0-8B1 11555 Rockville Pike Rockville, MD 20852-2738

River Bend Station 2011 Regulatory Guide 1.21 Page I of 64 2011 ANNUAL EFFLUENT RELEASE REPORT P(A-jl4J 1134 PREPARED BY:

REVIEWED BY:

J J

William H. Spell / Senior HP/Chem Specialist Kenneth S. Hallaran / Manager - Chemistry REVIEWED BY:

Greg P. Hackett / Radiation Protection Manager APPROVED BY:

Richard E. Gadbois / General Manager Plant Operations

River Bend Station 2011 Regulatory Guide 1.21 Page 2 of 64 TABLE OF CONTENTS I.

INTRODUCTION............................................................................................

4 II.

SUPPLEMENTAL INFORMATION...........................................................

4 III.

GASEOUS EFFLUENT

SUMMARY

INFORMATION..........................

12 IV.

LIQUID EFFLUENT

SUMMARY

INFORMATION................................

12 V.

SOLID W ASTE..............................................................................................

12 VI.

RADIOLOGICAL IMPACT ON MAN (40CFR190).................................

12 VII. METEOROLOGICAL DATA...................................................................... 13 VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY..........................................

13 IX.

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY..........................................

14 X.

LIQUID HOLD UP TANKS.........................................................................

14 XI.

RADIOLOGICAL ENVIRONMENTAL MONITORING.......................

14 XII. LAND USE CENSUS....................................................................................

15 XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM)..........................

15 XIV. MAJOR CHANGES TO RADIOACTIVE

LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEM S..............................................................................................

15 XV. PROCESS CONTROL PROGRAM (PCP)................................................

16 XVI. INDUSTRY GROUND WATER PROTECTION INITIATIVE (GPI) - FINAL GUIDANCE DOCUMENT (NEI 07-07)

OBJECTIVE ANNUAL REPORTING.............................................

16 TABLE IA GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES............................................................................................

17 TABLE IC GASEOUS EFFLUENTS - GROUND RELEASES -

BATCH M ODE.....................................................................................

19 TABLE ID GASEOUS EFFLUENTS - MIXED MODE RELEASES -

CONTINUOUS MODE.......................................................................

20

River Bend Station 2011 Regulatory Guide 1.21 Page 3 of 64 TABLE 1E SUPPLEMENTAL INFORMATION...............................................

22 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 RELEA SES............................................................................................

25 TABLE 2B LIQUID EFFLUENTS - CONTINUOUS MODE.............................

26 TABLE 2C LIQUID EFFLUENTS -BATCH MODE.........................................

26 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 2011 YEAR METEOROLOGICAL DATA - JOINT FREQUENCY TABLES....................................................................

35 TABLE 7 ATMOSPHERIC DISPERSION AND DEPOSITION RATES FOR THE MAXIMUM INDIVIDUAL DOSE CALCULATIONS........................................

........................................ 52 TABLE 8 GROUNDWATER MONITORING WELL SAMPLE RE SU LTS..................................................................................................

53 ATTACHMENT 1 PROCESS CONTROL PROGRAM..........................................

64

River Bend Station 2011 Regulatory Guide 1.21 Page 4 of 64 I. INTRODUCTION This is the annual Radioactive Effluent Release Report for the period of January 1, 2011, through December 31, 2011.

This report is submitted in accordance with Technical Specification 5.6.3 of Appendix A to River Bend Station (RBS) License Number NPF-47.

I1. 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 X7 i=1 Mi (X/Q) Oi

< 5 mrads/qtr

< 10 mrads/yr DBeta-Air = beta air dose from radioactive noble gases in millirad (mrad) n

=

3.17E-8 I i=1 Ni (X/Q) Qi

< 10 mrads/qtr

< 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:

Dl&8DPT

= Dose in mrem to the organ (T) for the age group of interest from

River Bend Station 2011 Regulatory Guide 1.21 Page 5 of 64 radioiodine (1-131, 1-133, tritium, and 8 of interest.)

n day particulate via the pathway

= 3.17E-08 (Fo)

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

= 3.17E-08 (Fo) n D-T

= I DI&8OPt z=1 n

I Ri (D/0) Oi 1=1 and

< 7.5 mrem/qtr

< 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, At Qi (DF) D, and n

DTOTAL I

Di i= 1 DTOTALT = Total dose commitment to the organ (T) due to all releases during the desired time interval in mrem and DTOTAL DTOTAL Total Body Any Organ 1.5 mrem/qtr 3 mrem/yr 5 mrem/qtr 10 mrem/yr (above terms defined in RBS ODCM)

River Bend Station 2011 Regulatory Guide 1.21 Page 6 of 64

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:

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

=

I Li + L.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&SDPT =

Dose rate to the organ T 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 2011 Regulatory Guide 1.21 Page 7 of 64 n

I 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 2011 Regulatory Guide 1.21 Page 8 of 64

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 1F.

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 IF. 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)

River Bend Station 2011 Regulatory Guide 1.21 Page 9 of 64 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 IF 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.

e. Nickel-63 Upon reviewing recent River Bend Station solid radwaste disposal information, the decision was made to analyze for Nickel-63 in the gaseous and liquid effluent pathways. In the fourth quarter 2011, Nickel-63 was quantified in the Fuel Building composite stack samples. An additional aliquot was counted which confirmed the result. A subsequent sample was also analyzed for Iron-55 producing results less than the minimum detectable concentration. A second verification sample has not been analyzed for Nickel-63.

Since final verification cannot be made prior to the submittal of this report, Nickel-63 is included in the gaseous curie and dose calculations for 2011. Nickel-63 was not detected in the liquid effluent composite sample.

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

River Bend Station 2011 Regulatory Guide 1.21 Page 10 of 64 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.

A spot-check was made for Nickel-63 with liquid scintillation method in the third quarter 2011. The result was less than the minimum detectable concentration.

D. Batch Releases

1. Liquid Effluents Batch releases and receiving stream flow from River Bend Station during the reporting period of January 1, 2011, through December 31, 2011 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, 2011, through December 31, 2011.

E. Abnormal Releases Number of abnormal liquid releases: 1 In December 2011, a positive tritium sample result was confirmed for a groundwater monitoring sample from well PZ-01 located near the Field Administration Building.

The result was 48,244 pCi/L. No gamma emitters or hard-to-detect radioisotopes were detected. This release is discussed in more detail in Section XVI.

Number of abnormal gaseous releases: 1 On September 15, 2011, it was identified that a potential unmonitored release pathway could be occurring due to the fact that the Turbine Building ventilation at the 67-foot elevation was positive with respect to the C-Tunnel.

The C-Tunnel discharge is through the Normal Switchgear Building, which is not a monitored gaseous release point.

It is not known for certain if activity was actually released via this building vent. An effluent dose calculation was performed that demonstrated that if the activity in C-Tunnel was actually released from the Normal Switchgear Building for an entire year, any dose to the public released via this pathway would be

River Bend Station 2011 Regulatory Guide 1.21 Page I I of 64 less than 10 percent of normal effluents and is considered insignificant per Regulatory Guide 1.109.

The probable cause of the C-Tunnel being more negative than the Turbine Building was determined to be a severely degraded intake filter. Maintenance was performed on the filter correcting the flow imbalance from the Turbine Building 67' into the C-Tunnel. Additional long-term maintenance practices were reviewed and revised.

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%

Iodines

+ 18.6%

Particulate: + 18.6%

Tritium: + 18.2%

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)L

+ (E2)L +...(En)L) where:

ET = total error El, E 2...En = individual errors due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.

River Bend Station 2011 Regulatory Guide 1.21 Page 12 of 64 II.

GASEOUS EFFLUENT

SUMMARY

INFORMATION Refer to the Table 1 series for the summation of gaseous releases. 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 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 the summation of liquid releases. It should be noted that an entry of "0.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 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 (C-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

River Bend Station 2011 Regulatory Guide 1.21 Page 13 of 64 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 7.80E-02 Skin 7.62E-02 Thyroid 1.30E-01 Other Organ 7.85E-02 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+00 (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 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 2011 was 96.8 %.

VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY The 2011 Technical Requirements Manual (TRM) 3.3.11.2 instrumentation Limited Condition of Operation was reviewed to see if RBS had entered Action E.2. Two entries into Action E.2 were found for Technical Requirement 3.3.11.2 occurring on February 2, 2011, and July 24, 2011. Each entry declared CWS-FE-113 (Cooling Tower Blowdown

River Bend Station 2011 Regulatory Guide 1.21 Page 14 of 64 Line Flow Element) inoperability. No liquid radwaste discharges occurred during either of the times that Action E.2 was entered.

CWS-FE-113 had repeated cases of intermittent alarms from low flow indications in the Auxiliary Control Room flow recorder. Troubleshooting was performed, using station surveillance test procedures, to determine the cause of the alarms. Due to the intermittent nature of the alarms, it was difficult determining the exact cause of the low flow indications. A continuation of intermittent alarms led to an extensive investigation and troubleshooting process for the entry dated July 24, 2012. A number of issues were identified and corrected which led to a significant improvement in CWS-FR113 (flow recorder) performance.

The probable cause for the erratic readings was eventually determined to be poor conduction caused by corrosion and weak connections in the analog circuit. The circuit has been in service since plant startup, and parts of the circuit are located in a dark, damp, sometimes underwater, environment which most likely accelerated the corrosion at the connections. No additional issues have been documented since the repairs were completed.

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, 2011, through December 31, 2011, 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, 2011, through December 31, 2011 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, 2011, through December 31, 2011.

River Bend Station 2011 Regulatory Guide 1.21 Page 15 of 64 XII.

LAND USE CENSUS The Land Use Census was not conducted in 2011. The next scheduled land use census as required by Technical Requirements Manual (TRM) (TR 3.12.2) is in 2012.

XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the ODCM in 2011.

XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Engineering performed a review of the Asset Suite database to evaluate non-administrative design changes completed or partially completed during 2011 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 USAR.

The Engineering Changes (EC's) to liquid, solid or gaseous radwaste systems implemented during this time period were:

EC 1382 "Install Fan Belt Guards over Belts and Pulleys of N64-PNLPLOO1 and 2" - this engineering change did not affect the method of gaseous radwaste processing as the guard was installed on the exterior of the component as a personnel safety measure and did not change the function, capacity or other parameter of the component and did not affect the USAR.

EC 23473 "De-Activate Auxiliary Control Room Alarms Associated with Deferred Equipment" - this engineering change did not affect the method of liquid or solid radwaste processing as the alarms were associated with equipment deferred during construction and not discussed in the USAR.

No EC 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 either the liquid, solid or gaseous radwaste treatment systems.

River Bend Station 2011 Regulatory Guide 1.21 Page 16 of 64 XV.

PROCESS CONTROL PROGRAM (PCP)

The PCP (EN-RW-105) was revised in 2011. The changes were editorial in nature. A copy is in Attachment 1.

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. The sample results for 2011 are located in Table 8.

In December 2011, a positive groundwater sample was confirmed in monitoring well PZ-01.

Only tritium (48,245 pCi/L/4.82E-05 uCi/mL) was identified in the sample.

Followup sampling has also been around this general concentration.

This was the first positive groundwater sample since RBS began sampling to support the NEI groundwater protection initiative in the third quarter 2007.

Voluntary communications to State and Local stakeholders was performed as required by NEI 07-07. A multi-disciplinary team was assembled to investigate and determine the source of the tritium. As of the writing of this annual report the source has not been determined.

Once the source is determined, procedures or measures will be adopted to prevent recurrence of this or similar incidents as applicable. Additional monitoring wells are being installed and buried piping inspections are being performed to identify the source and determine followup actions.

The estimated dose to the public is less than the 10CFR50 Appendix I levels. It is estimated that it will take approximately 16 years for the activity detected in monitoring well PZ-01 to leave the owner controlled area and to reach the Mississippi River.

The current understanding of the groundwater hydrology is that this activity will flow via the Upland Terrace aquifer to the Mississippi River alluvial aquifer and into the Mississippi River and will not affect offsite wells in the vicinity of River Bend Station.

The nearest known drinking water supply that could be affected by the activity detected in PZ-01 is many miles downstream in the Mississippi River below Baton Rouge, LA. Due to the significant dilution volume of the Mississippi River, it is highly unlikely that the concentration of tritium detected in well PZ-01 will have any meaningful impact offsite.

All of the remaining samples taken in support of the GPI were less than the Lower Limit of Detection as required in Technical Requirement 3.12.1 (Environmental LLDs) except for some gamma samples in the second quarter 2011. The failure to meet the required LLDs was due to equipment availability and laboratory capacity. Actions were taken to prevent reoccurrence of this situation.

River Bend Station 2011 Regulatory Guide 1.21 Page 17 of 64 TABLE 1A GASEOUS EFFLUENTS -

SUMMATION OF ALL RELEASES REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation

1. Total Release

2.

Avg. Release Rate

3.

% Applicable Limit Iodine-131

1. Total Release

2.

Avg. Release Rate

3.

% Applicable Limit Particulates Half Life

1. Total Release

2.

Avg. Release Rate

3.

% Applicable Limit Tritium

1. Total Release

2.

Avg. Release Rate

3.

% Applicable Limit Carbon-14

1. Total Release

2.

Avg. Release Rate

3.

% Applicable Limit Gases Ci uCi/sec

% (1)

Ci uCi/sec

% (2)

>= 8 days Ci uCi/sec

% (2)

2. 67E+01 3.44E+00 2.57E-01 2.64E-04 3.40E-05 1.60E-01 1.65E-04 2.12E-05

1. 09E-02 2.35E+01 2.98E+00 3.72E-01

4. 03E-04

5. 12E-05 1.73E-01

6. 02E-04 7.66E-05 3.52E-02

1. 17E+01 1.48E+00 1.26E-01 2.03E-04 2.56E-05

8. 68E-02 5.68E-04 7.14E-05

2. 01E-02 2.15E+O1

2. 70E+00 1.69E-01 4.17E-04 5.24E-05 1.77E-01 3.28E-04 4.12E-05 3.31E-02 8.34E+01 2.64E+00 4.62E-01 1.29E-03 4.08E-05 2.98E-01

1. 66E-03 5.27E-05 4.94E-02 Ci uCi/sec

% (2)

Ci uCi/sec

% (2) 5.50E+00 7.07E-01 1.80E-01 2.72E+00 3.50E-01

1. 15E+01 3.64E+00 4.63E-01 1.15E-01 2.74E+00 3.49E-01 1.56E+01 3.05E+00 3.84E-01 7.71E-02

2. 77E+00 3.48E-01 1.57E+01 3.08E+00 3.88E-01 8.27E-02 2.77E+00 3.48E-01 1.57E+01 1.53E+01 4.84E-01 2.27E-01

1. 10E+00 3.49E-01

2. 7 1E+0 1

1)

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

limit of 10

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 2011 Regulatory Guide 1.21 Page 18 of 64 TABLE 1B GASEOUS EFFLUENTS -

GROUND RELEASES -

CONTINUOUS MODE REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation XE-133 XE-133M XE-135 XE-135M Totals for Period...

Iodines 1-131 1-133 Totals for Period...

Particulates Half Life CE-141 CO-57 CO-58 CO-60 CR-51 CS-137 FE-59 MN-54 NB-95 NI-63 RU-103 RU-106 SR-89 ZN-65 Totals for Period...

Gases Ci Ci Ci Ci Ci Ci Ci Ci 5.97E-01 0.OOE+00 1.27E+00 3.50E-01 2.22E+00

0. OOE+00

0. OOE+00 2.52E+00

1. 06E+00

3. 58E+00

0. OOE+00

0. OOE+00 5.23E-01

4. 13E-01 9.36E-01

0. OOE+00 0 OOE+00 4.33E-01 3.64E-01 7.98E-01 5.97E-01

0. OOE+00 4.75E+00 2.19E+00 7.54E+00 4.79E-05 2.04E-06 0.OOE+00 0.00E+00 4.99E-05 3.94E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.94E-06 5.18E-05 2.04E-06 0.OOE+00 0.OOE+00 5.39E-05 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 8 days 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 4.94E-07 4.94E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0 0.0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.94E-07 4.94E-07 Tritium H-3 Ci 2.45E+00 1.55E+00 9.87E-01 1.08E+00 6.07E+00

River Bend Station 2011 Regulatory Guide 1.21 Page 19 of 64 TABLE IC GASEOUS EFFLUENTS GROUND RELEASES BATCH MODE REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation XE-133 XE-135 XE-135M Totals for Period...

Iodines 1-131 1-133 Totals for Period...

Particulates Half Life BA-140 CO-60 MN-54 SR-89 SR-90 ZN-65 Totals for Period...

Gases Ci Ci Ci Ci Ci Ci Ci

0. OOE+00

0. OOE+00 O.OOE+00 0. OOE+00 O.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00 0. OOE+00

0. OOE+00

0. 00E+00 0.OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.003E+00

0. OOE+00 0. 00E+00 0.OOE+00

0. 00E+00

0. OOE+00

>= 8 days Ci Ci Ci Ci Ci Ci Ci

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 Tritium H-3 Ci 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00

River Bend Station 2011 Regulatory Guide 1.21 Page 20 of 64 TABLE ID GASEOUS EFFLUENTS -

MIXED MODE RELEASES -

CONTINUOUS MODE REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation AR-41 KR-85 KR-85M KR-87 KR-88 XE-131M XE-133 XE-133M XE-135 XE-135M XE-137 XE-138 Totals for Period...

Iodines 1-131 1-133 Totals for Period...

Particulates Half Life BA-140 CE-139 CE-141 CO-58 CO-60 CR-51 CS-134 CS-137 FE-59 MN-54 RU-103 SR-89 SR-90 ZN-65 Totals for Period...

Gases Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.07E+00 5.38E-01 5.77E-01 0.OOE+00 6.10E-01 1.48E+00 0.OOE+00 0.OOE+00 6.90E-01 5.14E-01 0.OOE+00 0.OOE+00 1.09E+01 7.73E+00 8.39E+00 9.62E+00 3.82E-01 0.OOE+00 9.15E-01 0.OOE+00 2.45E+01 1.99E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.54E-01

0. OOE+00 3.84E+00 6.61E+00 0. OOE+00

0. OOE+00 1.08E+01 0.OOE+00 0.OOE+00 1.26E-01

0. OOE+00

0. OOE+00 0. OOE+00 9.54E-01 0. OOE+00 8.23E+00

1. 13E+01 0. OOE+00 0. OOE+00

2. 07E+01

0. OOE+00

2. 73E+00 5.77E-01

2. 09E+00

0. OOE+00

2. 51E+00

0. OOE+00

3. 07E+01

3. 60E+01 3.82E-01

9. 15E-01 7.59E+01 2.17E-04 4.OOE-04 2.03E-04 4.17E-04 1.24E-03 9.13E-04 3.02E-03 1.74E-03 2.87E-03 8.54E-03 1.13E-03 3.42E-03 1.94E-03 3.29E-03 9.78E-03

>= 8 days Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 7.48E-05 0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0.OOE+00

0. OOE+00 0. OOE+00 9.04E-05

0. OOE+00

0. OOE+00 3.14E-04 0. OOE+00

0. OOE+00

0. OOE+00'

0. OOE+00

2. 88E-04 6.79E-09

0. OOE+00 3.24E-04

0. OOE+00

0. OOE+00 2.44E-04 2.30E-07

0. OOE+00 1.81E-04

0. OOE+00

0. OOE+00 0. OOE+00 0.OOE+00

0. OOE+00

0. OOE+00 0. OOE+00 1.47E-04 8.70E-09

0. OOE+00

8. 94E-04 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0. OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 0 OOE+00

7. 69E-04

2. 46E-07

0. OOE+00 Ci 1.65E-04 6.02E-04 5.68E-04 3.27E-04 1.66E-03

River Bend Station 2011 Regulatory Guide 1.21 Page 21 of 64 GASEOUS EFFLUENTS -

REPORT FOR 2011 Units Tritium H-3 Ci TABLE ID (continued)

MIXED MODE RELEASES -

CONTINUOUS MODE QTR 1 QTR 2 QTR 3 QTR 4 YEAR 3.04E+00 2.09E+00 2.06E+00 2.01E+00 9.20E+00 Carbon-14 C-14 Ci 2.72E+00 2.74E+00 2.77E+00 2.77E+00

1. 10E+01

River Bend Station 2011 Regulatory Guide 1.21 Page 22 of 64 Table 1E SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS -

BATCH MODE REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0

0 0

Total release time minutes 0.00E+00 0.00E+00 0.00E+00 O.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.OOE+00 0.00E+00 0.00E+00 0.00E+00 Minimum release time minutes 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00

River Bend Station 2011 Regulatory Guide 1.21 Page 23 of 64 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 1.00E-04 H-3 1.OOE-06 B. Fuel Building M

M Principal Gamma Ventilation Grab Sample Emitters 1.00E-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 1.00E-10 Continuous W

Principal Gamma Particulate Emitters (1-131, 1.OOE-11 Sample Others)

Continuous M

Gross Alpha Composite 1.OOE-11 Particulate Sample Continuous 0

Sr-89, Sr-90 Composite 1.OOE-11 Particulate Sample Continuous Noble Gas Noble Gases Monitor Gross Beta or 1.OOE-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 2011 Regulatory Guide 1.21 Page 24 of 64 Table 1G GASEOUS ANNUAL DOSE

SUMMARY

REPORT I&P DOSE LIMIT ANALYSIS Age Dose Limit Max % of Period-Limit Group Organ (mrem)

(mrem)

Limit Q1 T.Spec Any Organ CHILD THYROID 2.63E-02 7.50E+00 3.51E-0l Q2 - T.Spec Any Organ CHILD THYROID 2.42E-02 7.50E+00 3.23E-01 Q3 - T.Spec Any Organ CHILD THYROID 1.38E-02 7.50E+00 1.83E-01 Q4 - T.Spec Any Organ CHILD THYROID 2.20E-02 7.50E+00 2.93E-01 Yr - T.Spec Any Organ CHILD THYROID 8.62E-02 1.50E+01 5.75E-01 Carbon-14 (Bounding calculation)

Qi - 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 Qi -

T.Spec Gamma 1.29E-02 5.OOE+00 2.57E-01 Qi -

T.Spec Beta 1.11E-02 1.OOE+01 1.11E-01 Q2 -

T.Spec Gamma 1.86E-02 5.OOE+00 3.72E-01 Q2 - T.Spec Beta 1.27E-02 1.OOE+01 1.27E-01 Q3 - T.Spec Gamma 6.31E-03 5.OOE+00 1.26E-01 Q3 - T.Spec Beta 3.67E-03 1.OOE+01 3.67E-02 Q4 -

T.Spec Gamma 8.45E-03 5.OOE+00 1.69E-01 Q4 -

T.Spec Beta 4.92E-03 1.OOE+01 4.92E-02 Yr -

T.Spec Gamma 4.62E-02 1.OOE+01 4.62E-01 Yr -

T.Spec Beta 3.24E-02 2.OOE+01 1.62E-01

River Bend Station 2011 Regulatory Guide 1.21 Page 25 of 64 TABLE 2A LIQUID EFFLUENTS -

SUMMATION OF ALL RELEASES REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation

1. Total Release

2.

Avg. Diluted Conc.

3.

% Applicable Limit Tritium

1. Total Release

2.

Avg. Diluted Conc.

3.

% Applicable Limit Gases Ci uCi/ml

% (1)

Ci uCi/ml

% (1) 9.61E-05 9.50E-11 1.08E-04 9.04E+00 8.94E-06

1. 23E-04 5.28E-03 5.22E-09

2. 61E-03 1.71E-04 1.21E-10 2.98E-05 1.20E+01 8.53E-06 2.08E-04 9.94E-03 7.07E-09 3.55E-03

1. 89E-04 1.30E-10 2.23E-05 7.17E+00 4.91E-06 8.40E-05 2.82E-03 1.94E-09 9.66E-04

0. OOE+00

0. OOE+00 4.56E-04 8.57E-11

6. OOE-05

2. 82E+01 5.30E-06 1.47E-04

1. 80E-02 3.39E-09 1.70E-03 Dissolved and Entrained Gases

1. Total Release Ci

2.

Avg. Diluted Conc.

uCi/ml

3.

% Applicable Limit % (2)

Gross Alpha Radioactivity

1. Total Release Ci Volume of liquid waste liters Volume of dil.

water liters O.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.05E+05 1.60E+06 1.09E+06 O.OOE+00 3.60E+06 1.01E+09 1.40E+09 1.46E+09 1.44E+09 5.31E+09 (1)

The most limiting dose compared limits of TRM 3.11.1.2.a.

to the total body and critical organ (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 2011 Regulatory Guide 1.21 Page 26 of 64 TABLE LIQUID EFFLUENTS 2B CONTINUOUS MODE REPORT FOR 2011 Units Fission and Activation Gases No Nuclide Activities Tritium

- No Nuclide Activities Dissolved and Entrained Gases No Nuclide Activities Gross Alpha Radioactivity No Nuclide Activities QTR 1 QTR 2 QTR 3 QTR 4 YEAR TABLE 2C

River Bend Station 2011 Regulatory Guide 1.21 Page 27 of 64 LIQUID EFFLUENTS BATCH MODE REPORT FOR 2011 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation CO-60 MN-54 Totals for Period...

Gases Ci Ci Ci 8.71E-05

8. 98E-06 9.61E-05 1.71E-04 0. OOE+00 1.71E-04 1.89E-04

0. OOE+00 1.89E-04

0. OOE+00 0.OOE+00

0. OOE+00

4. 47E-04 8.98E-06 4.56E-04 Tritium H-3 Ci 9.04E+00 1.20E+01 7.17E+00 0.OOE+00 2.82E+01 Dissolved and Entrained Gases XE-133 Ci XE-133M Ci XE-135 Ci Totals for Period...

Ci Gross Alpha Radioactivity

- No Nuclide Activities **

2.27E-03

0. OOE+00 3.01E-03 4.73E-03 1.38E-04

5. 07E-03

1. lOE-03

0. OOE+00 1.72E-03 0.OOE+00

0. OOE+00

8. 1OE-03 1.38E-04 9.81E-03 5.28E-03 9.94E-03 2.82E-03 0.OOE+00 1.80E-02

River Bend Station 2011 Regulatory Guide 1.21 Page 28 of 64 Table 2D SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS -

BATCH MODE REPORT FOR 2011 Number of releases Total release time Maximum release time Units QTR 1 18 QTR 2 29 QTR 3 20 QTR 4 0

YEAR 67 minutes 6.02E+03 minutes 4.OOE+02 1.07E+04 7.48E+03 0.OOE+00 2.42E+04 4.OOE+02 4.35E+02 0.OOE+00 4.35E+02 Average release time minutes Minimum release time minutes Average Mississippi ft 3/sec River stream flow during periods of release of effluent into a flowing stream 3.35E+02 3.67E+02 3.74E+02 0.OOE+00 3.61E+02 1.08E+02 3.27E+02 3.06E+02 0.OOE+00 1.08E+02 QTR 1 478,656 QTR 2 1,097,297 QTR 3 439,228 QTR 4 438,652

River Bend Station 2011 Regulatory Guide 1.21 Page 29 of 64 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.OOE-07 P

0 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 2011 Regulatory Guide 1.21 Page 30 of 64 Table 2F LIQUID ANNUAL DOSE

SUMMARY

REPORT Report for:

2011 Release ID:

10 All Liquid Release Points Liquid Receptor

=== SITE DOSE LIMIT ANALYSIS Age Group Dose (mrem)

Limit (mrem)

Max % of Limit Period -

Limit Organ Qtr 1 Qtr 1 Qtr 2 Qtr 2 Qtr 3 Qtr 3 Qtr 4 Qtr 4 2011 T.Spec T.Spec T.Spec T.Spec T.Spec T.Spec T.Spec T.Spec T.Spec Any Organ Total Body Any Organ Total Body Any Organ Total Body Any Organ Total Body Any Organ ADULT ADULT ADULT ADULT ADULT ADULT ADULT ADULT ADULT GILLI TBODY GILLI TBODY GILLI TBODY GILLI TBODY GILLI 7.24E-06 2.22E-06

4. 61E-06 3.30E-06 2.38E-06 1.39E-06

0. 00E+00

0. 00E+00 1.04E-05

5. 00E+00

1. 50E+00

5. OOE+00

1. 50E+00 5.00E+00

1. 50E+00

5. 00E+00

1. 50E+00 1.00E+01 1.45E-04 1.48E-04 9.22E-05 2.20E-04 4.75E-05 9.28E-05

0. 00E+00

0. 00E+00 1.04E-04 2011 T.Spec Total Body ADULT TBODY 4.90E-06 3.OOE+00 1.63E-04

River Bend Station 2011 Regulatory Guide 1.21 Page 31 of 64 TABLE 3 Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/11 to 12/31/11 A.

Solid Waste Shipped for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste Spent Resins, Filter Sludges, Evaporator

Bottoms, Etc.

Units 12 Month Period Waste Class Estimated Error %

m3 Ci m3 Ci m3 Ci

4. 88E+01

1. 01E+02

0. OOE+00

0. OOE+00 o.OOE+00 0. OOE+00 A

A B

B C

C

+/- 25%

Dry Compressible Wastes, m3 6.22E+02 A

+/- 25%

Contaminated Equipment Ci 6.30E-01 A

Etc.

Irradiated Components, m3 0.OOE+00 Control Rods, Etc.

Ci 0.OOE+00 Other m3 1.95E+01 A

+/- 25%

(Water,

EHC, Waste Oil, Ci 5.10E-02 A

etc.)

River Bend Station 2011 Regulatory Guide 1.21 Page 32 of 64 Effluent and Waste Disposal Annual Report 2011 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/11 to 12/31/11 Table 3 (continued)

2.

Estimates of Major Nuclides by Waste Stream

Resins, Filters, Evaporator Dry Compressible Wastes, Other Bottoms, Etc.

Contaminated Equipment, Etc.

Water, EHC, Waste Oil, Etc.

(Min 1%)

Isotope

% Abundance Curies Isotope

% Abundance Curies FE-55 49.135 4.96E+01 FE-55 56.055 3.53E-01 FE-55 56.081 2.86E-02 CO-60 35.621 3.60E+01 CO-60 39.436 2.49E-01 CO-60 39.319 2.01E-02 ZN-65 5.730 5.78E+00 MN-54 2.156 1.36E-02 MN-54 2.190 1.12E-03 NI-63 5.021 5.07E+00 MN-54 1.870 1.89E+00 CS-137 1.337 1.35E+00 No Control Rods, Etc. were shipped in 2011

3.

Solid Waste Disposition Number of Shipments 17 5

7 Mode of Transportation Truck Truck Truck Destination Energy Solutions (Bear Creek) -

Oak Ridge, TN Energy Solutions (Gallaher) -

Oak Ridge, TN Clive Disposal Facility (Containerized) -

Clive, UT B.

Irradiated Fuel Shipments Disposition Number of Shipments 0

Mode of Transportation N/A Destination N/A

River Bend Station 2011 Regulatory Guide 1.21 Page 33 of 64 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 dose pathway 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 2011.

(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 individuals will be the receptors for this pathway. For 2011, this conservative 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 2011 Regulatory Guide 1.21 Page 34 of 64 TABLE 5 DOSES TO MEMBERS OF THE PUBLIC ON SITE FROM GASEOUS RELEASES 2011 Critical Total Skin Dose Annual Organ Body Dose Annual Duration Dose Annual (mrem)

Factor Annual (mrem)

(mrem)

Alligator 3.15E-05 1.08E-04 1.80E-04 4.57E-03 Bayou Workers 4.30E-03 1.19E-02 2.09E-02 2.74E-01 staying onsite

River Bend Station 2011 Regulatory Guide 1.21 Page 35 of 64 Table 6 2011 Year Meteorological Data - Joint Frequency Tables

River Bend Station 2011 Regulatory Guide 1.21 Page 36 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE ALL STABILITY CLASSES FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

77 65 60 109 102 178 77 1

0 0

669 NNE 72 26 57 88 90 103 12 0

0 0

448 NE 84 48 45 85 85 67 19 0

0 0

433 ENE 56 69 53 79 61 63 17 0

0 0

398 E

55 72 62 67 37 16 1

0 0

0 310 ESE 31 48 54 101 59 44 3

0 0

0 340 SE 25 57 92 214 212 219 35 1

0 0

855 SSE 13 18 47 164" 180 277 164 8

0 0

871 S

16 27 41 139 161 289 262 14 0

0 0

0 949 SSW 24 27 54 100 94 99 89 4

0 0

491 SW 16 27 56 65 50 66 24 0

0 0

304 WSW 11 18 26 46 72 119 16 0

0 0

308 W

34 44 41 41 77 94 7

0 0

0 338 WNW 47 79 41 45 64 108 37 0

0 0

421 NW 64 85 64 69 59 102 95 7

0 0

545 NNW 72 99 66 59 62 158 129 8

0 0

653 TOTAL 697 809 859 1471 1465 2002 987 43 0

0 0

0 8333 NUMBER OF CALMS:

148 NUMBER OF INVALID HOURS:

279 NUMBER OF VALID HOURS:

8481 TOTAL HOURS FOR THE PERIOD:

8760

River Bend Station 2011 Regulatory Guide 1.21 Page 37 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS A FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

4 14 15 0

0 0

33 NNE 0

0 0

0 3

17 4

0 0

0 24 NE 0

0 1

0 8

13 5

0 0

0 27 ENE 0

0 2

2 9

15 2

0 0

0 30 E

0 0

1 6

9 5

0 0

21 ESE 0

0 0

6 10 14 1

0 0

0 31 SE 0

1 1

3 16 69 10 0

0 0

100 SSE 0

0 0

0 3

16 33 2

0 0

54 S

0

,0 0

0 0

17 44 1

0 0

62 SSW 0

0 1

0 0

1 12 1

0 0

15 SW 0

0 0

0 3

6 4

0 0

0 13 WSW 0

0 0

4 1

11 1

0 0

0 17 W

0 0

1 0

4 3

0 0

8 WNW 0

0 0

1 3

11 8

0 0

0 23 NW 0

1 0

2 1

1 14 2

0 0

21 NNW 0

0 1

1 3

6 10 2

0 0

23 TOTAL 0

2 8

25 77 219 163 8

0 0

502 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

502 TOTAL HOURS FOR THE PERIOD:

502

River Bend Station 2011 Regulatory Guide 1.21 Page 38 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS B FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS 30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 1

0 5

7 0

0 0

13 NNE 0

0 0

0 6

6 0

0 0

0 12 NE 0

0 0

0 3

4 0

0 0

0 7

ENE 0

0 0

1 6

3 0

0 0

0 10 E

0 0

1 0

2 1

0 0

4 ESE 0

0 0

3 4

3 0

0 0

0 10 SE 0

0 0

1 9

14 5

0 0

0 29 SSE 0

0 0

1 4

13 18 1

0 0

37 S

0 1

1 1

0 7

28 1

0 0

39 SSW 0

0 0

3 10 1

0 0

14 SW 1

0 0

1 1

4 4

0 0

0 11 WSW 0

0 0

0 1

10 3

0 0

0 14 W

0 0

2 6

1 0

0 0

9 WNW 0

0 0

8 3

0 0

0 11 NW 0

0 0

1 1

1 7

1 0

0 0

0 11 NNW 0

0 0

0 1

4 9

2 0

0 0

0 16 TOTAL 1

1 2

10 40 92 95 6

0 0

247 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

247 TOTAL HOURS FOR THE PERIOD:

247

River Bend Station 2011 Regulatory Guide 1.21 Page 39 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS C FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

2 8

3 0

0 0

13 NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

0 0

1 0

0 1

0 0

1 0

0 0

0 1

0 0

1 3

13 1

0 3

7 1

2 5

2 0

4 0

1 0

5 7

1 0

3 7

13 3

2 3

15 25 1

2 11 52 0

1 6

12 1

2 3

3 0

3 7

4 1

6 4

0 0

2 5

2 1

0 4

8 1

2 11 27 0

0 0

1 0

0 1

0 0

5 0

0 0

18 0

11 0

9 0

6 0

14 0

28 0

46 0

71 0

19 0

9 0

14 0

12 0

9 0

14 0

0 41 TOTAL 0

2 3

22 48 111 141 7

0 0

334 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

334 TOTAL HOURS FOR THE PERIOD:

334

River Bend Station 2011 Regulatory Guide 1.21 Page 40 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS D FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 NN N

EN ES S

SS SS S

WS WN Ný N

2 3

5 34 70 142 50 lE 1

3 14 31 55 61 7

E 3

5 9

33 30 28 13 1E 3

4 7

26 16 37 15 E

4 6

19 34 20 7

1 E

4 4

13 42 27 25 2

E 4

10 27 76 94 77 16 E

2 1

13 45 97 190 87 S

0 5

12 42 76 198 134 1W 2

7 14 32 66 79 55 1W 1

3 9

37 36 50 13 1W 0

2 6

29 51 75 8

W 2

4 9

22 56 74 5

1W 0

5 11 27 43 72 23 1W 0

3 8

33 45 88 64 1W 0

5 7

22 38 130 82 1

0 0

30.7 0

0 0

0 4

0 7

0 2

0 0

0 4

0 0

172 0

0 0

121 0

0 0

108 0

0 0

91 0

0 0

117 0

0 0

304 0

0 0

439 0

0 0

474 0

0 0

257 0

0 0

149 0

0 0

171 0

0 0

172 0

0 0

181 0

0 0

245 0

0 0

288 TOTAL 28 70 183 565 820 1333 575 22 0

0 0

0 3596 NUMBER OF CALMS:

2 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

3598 TOTAL HOURS FOR THE PERIOD:

3598

River Bend Station 2011 Regulatory Guide 1.21 Page 41 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS E FROM 1/01/11 0:00ý TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

4 4

15 35 20 9

2 0

0 0

89 NNE 5

3 19 38 20 6

0 0

91 NE 6

6 18 38 30 11 0

0 0

0 109 ENE 11 12 19 26 20 3

0 0

91 E

9 15 15 18 6

2 0

0 0

0 65 ESE 4

26 22 33 11 1

0 0

97 SE 8

26 46 103 76 43 1

0 0

0 303 SSE 0

9 22 85 65 35 1

0 0

0 217 S

7 9

16 80 81 56 4

0 0

0 253 SSW 9

13 30 59 26 10 0

0 0

0 147 SW 4

10 32 22 8

3 0

0 0

0 79 WSW.

4 10 13 11 16 15 0

0 0

0 69 W

11 13 17 16 8

5 1

0 0

0 71 WNW 9

16 14 13 15 11 1

0 0

0 79 NW 9

11 19 20 9

7 2

0 0

0 77 NNW 9

6 5

20 17 7

1 0

0 0

65 TOTAL 109 189 322 617 428 224 13 0

0 0

0 0 1902 NUMBER OF CALMS:

10 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

1912 TOTAL HOURS FOR THE PERIOD:

1912

River Bend Station 2011 Regulatory Guide 1.21 Page 42 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS F FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

15 12 17 24 2

0 0

0 70 NNE 12 4

14 16 2

0 0

0 48 NE 10 9

9 13 11 4

0 0

56 ENE 6

7 6

12 5

3 0

0 0

0 39 E

6 14 10 5

0 0

35 ESE 10 10 12 10 0

0 0

0 42 SE 5

13 14 26 10 3

0 0

71 SSE 7

6 7

26 7

7 0

0 0

0 60 S

5 8

8 14 2

0 0

0 37 SSW 8

6 7

7 1

0 0

0 29 SW 7

7 13 3

0 0

30 WSW 3

3 7

2 0

1 0

0 0

0 16 W

6 18 8

2 1

2 0

0 0

0 37 WNW 18 22 7

4 1

1 0

0 0

0 53 NW 11 22 18 11 3

1 0

0 0

0 66 NNW 13 21 11

.9 1

0 0

0 55 TOTAL 142 182 168 184 46 22 0

0 0

0 744 NUMBER OF CALMS:

24 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

768 TOTAL HOURS FOR THE PERIOD:

768

River Bend Station 2011 Regulatory Guide 1.21 Page 43 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS G FROM

'1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

30 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

NNE NE ENE E

ESE S E SSE S

SSW SW WSW W

WNW NW NNW 56 54 65 36 36 13 8

4 4

5 3

4 15 20 44 50 46 16 28 46 37 8

6 2

4 1

7 3

9 36 47 67 23 10 8

19 15 6

4 5

4 2

2 0

5 9

19 42 15 2

1 10 0

2 2

5 1

2 1

0 0

0 1

6 0

144 0

83 0

102 0

i1 0

88 0

29 0

20 0

18 0

13 0

10 0

13 0

7 0

29 0

65 0

111 0

165 TOTAL 417 363 173 48 6

1 0

0 0

0 1008 NUMBER OF CALMS:

112 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

1120 TOTAL HOURS FOR THE PERIOD:

1120

River Bend Station 2011 Regulatory Guide 1.21 Page 44 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE ALL STABILITY CLASSES FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 1

9 11 31 140 249 30 0

0 0

0 472 NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

3 9

21 36 145 240 6

1 3

7 25 30 116 250 21 1

2 9

24 54 98 179 73 0

3 9

26 48 110 89 46 1

2 8

30 37 176 439 113 1

6 7

23 44 162 316 38 1

5 14 25 37 195 368 80 2

8 4

33 62 218 516 141 1

3 9

34 54 197 240 53 1

5 8

28 80 191 78 17 0

2 14 32 74 216 115 4

3 2

6 32 69 207 119 4

0 0

5 17 32 121 101 33 3

2 5

18 24 102 161 50 3

4 6

18 30 127 253 72 0

3 28 14 11 2

5 17 7

3 0

0 5

10 0

0 2

0 1

0 0

0 1

0 0

0 1

0 0

460 0

458 0

469 0

346 0

817 0

600 0

730 0 1001 0

598 0

411 0

457 0

442 0

314 0

376 14 0

0 0

527 TOTAL 19 51 129 397 742 2521 3713 781 119 6

0 0 8478 NUMBER OF CALMS:

3 NUMBER OF INVALID HOURS:

279 NUMBER OF VALID HOURS:

8481 TOTAL HOURS FOR THE PERIOD:

8760

River Bend Station 2011 Regulatory Guide 1.21 Page 45 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS A FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 3

15 3

0 0

21 NNE 0

0 1

0 0

3 21 1

0 0

26 NE 0

0 0

6 18 1

1 0

0 0

26 ENE 0

0 0

9 20 13 1

0 0

0 43 E

0 0

0 1

1 6

11 6

1 0

0 0

26 ESE 0

0 0

1 1

11 50 23 4

0 0

0 90 SE 0

0 0

0 1

5 33 7

0 0

46 SSE 0

0 0

1 1

2 13 19 1

0 0

0 37 S

0 0

1 1

28 28 4

0 0

0 62 SSW 0

0 0

1 3

13 1

0 0

0 18 SW 0

0 0

0 2

1 5

1 0

0 0

0 9

WSW 0

0 0

9 9

2 0

0 0

0 20 W

0 0

1 2

5 1

0 0

9 WNW 0

0 0

0 1

5 8

10 2

0 0

0 26 NW 0

0 0

0 9

7 1

1 0

0 18 NNW 0

0 0

3 10 9

3 0

0 0

25 TOTAL 0

0 1

3 9

67 258 144 19 1

0 0

502 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

502 TOTAL HOURS FOR THE PERIOD:

502

River Bend Station 2011 Regulatory Guide 1.21 Page 46 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS B FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50.

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 1

11 3

0 0

15 NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

0 0

0 1

0 0

1 0

4 0

0 6

7 0

0 4

4 0

0 2

4 0

0 7

7 0

1 4

11 0

0 2

16 0

0 0

17 0

2 1

9 0

0 2

3 1

0 7

9 0

0 2

10 0

0 1

5 0

0 1

4 0

0 1

3 0

2 2

2 6

4 12 16 4

2 0

1 3

8 3

0 0

1 0

0 3

0 0

0 1

0 0

3 0

0 0

5 0

15 0

10 0

8 0

20 0

21 0

31 0

36 0

16 0

8 0

17 0

13 0

9 0

13 0

10 TOTAL 0

1 0

1 4

.41 124 68 8

0 0

0 247 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

247 TOTAL HOURS FOR THE PERIOD:

247

River Bend Station 2011 Regulatory Guide 1.21 Page 47 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS C FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

0 3

10 1

0 0

14 NNE 0

0 0

5 12 0

0 0

17 NE 0

0 0

6 5

2 0

0 0

0 13 ENE 0

0 0

3 3

1 1

0 0

0 8

E 0

0 0

6 4

0 0

0 10 ESE 0

0 0

0 4

6 15 1

0 0

26 SE 0

0 0

0 2

4 9

3 0

1 0

0 19 SSE

0.

0 0

3 28 10 0

0 0

0 41 S

0 0

0 2

32 23 3

0 0

0 60 SSW 0

0 0

5 14 9

1 0

0 0

29 SW 0

0 0

0 1

2 2

3 1

0 0

0 9

WSW 0

0 0

1 2

5 8

0 0

0 16 W

0 1

0 0

0 9

4 0

0 0

14 WNW 0

0 0

0 1

2 5

0 1

0 0

0 9

NW 0

0 0

1 0

2 5

5 1

0 0

0 14 NNW 0

0 0

1 17 17 0

0 0

0 35 TOTAL 0

1 0

2 10 64 173 75 8

1 0

0 334 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

334 TOTAL HOURS FOR THE PERIOD:

334

River Bend Station 2011 Regulatory Guide 1.21 Page 48 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS D FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

3 7

15 87 132 22 0

0 0

0 266 NNE 0

0 1

8 15 64 95 3

0 0

186 NE 0

2 1

14 13 32 43 6

2 2

0 0

115 ENE 0

0 3

10 24 28 43 32 26 1

0 0

167 E

0 2

6 7

20 25 24 10 10 1

0 0

105 ESE 0

1 2

9 15 68 99 45 7

0 0

0 246 SE 0

1 1

9 16 71 97 19 1

0 0

0 215 SSE 0

2 4

10 10 75 194 39 3

0 0

0 337 S

0 1

2 8

25 91 257 72 7

0 0

0 463 SSW 0

0 6

6 22 60 141 27 5

0 0

0 267 SW 0

1 2

8 29 81 37 11 1

0 0

0 170 WSW 0

0 4

8 28 103 67 2

0 0

212 W

0 0

1 8

28 105 71 1

0 0

214 WNW 0

0 0

7 14 58 62 18 1

0 0

0 160 NW 1

0 0

7 12 42 97 29 8

0 0

0 196 NNW 0

1 2

8 16 63 140 41 8

0 0

0 279 TOTAL 1

11 38 134 302 1053 1599 377 79 4

0 0 3598 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

3598 TOTAL HOURS FOR THE PERIOD:

3598

River Bend Station 2011 Regulatory Guide 1.21 Page 49 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS E FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS 150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

0 0

4 2

6 16 41 0

0 0

69 NNE 0

2 3

8 4

22 47 2

0 0

88 NE 0

0 3

3 4

23 65 6

0 0

104 ENE 1

1 2

4 15 18 51 13 0

0 0

0 105 E

0 0

0 8

12 20 23 13 3

0 0

0 79 ESE 0

1 2

8 8

36 155 28 0

0 0

0 238 SE 1

1 4

5 8

39 95 5

1 0

0 0

159 SSE 0

2 5

6 15 60 92 0

0 0

180 S

2 5

2 7

14 81 161 2

0 0

274 SSW 0

2 2

12 12 81 59 0

0 0

168 SW 0

2 3

12 18 56 17 0

0 0

108 WSW 0

0 4

7 19 54 11 0

0 0

95 W

2 0

1 10 15 44 16 1

0 0

89 WNW 0

0 2

2 9

11 9

1 1

0 0

0 35 NW 0

1 0

5 5

16 20 1

0 0

48 NNW 1

1 3

4 7

23 32 2

0 0

73 TOTAL 7

18 40 103 171 600.

894 74 5

0 0

0 1912 NUMBER OF CALMS:

0 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

1912 TOTAL HOURS FOR THE PERIOD:

1912

River Bend Station 2011 Regulatory Guide 1.21 Page 50 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS F FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

NNE NE ENE E

ESE SE SSE S

SSW SW WSW W

WNW NW NNW 0

0 0

2 0

1 0

0 1

0 0

2 1

0 0

1 0

0 1

3 0

0 5

12 16 4

14 29 5

11 44 5

16 24 4

8 13 5

20 58 4

16 46 5

14 13 9

20 16 5

19 9

8 16 4

8 21 7

11 15 7

3 17 4

0 16 13 3

11 21 0

0 0

0 4

0 0

12 0

0 13 0

0 6

0 0

0 1

0 0

34 0

0 53 0

0 68 0

0 61 0

0 42 0

0 99 0

0 72 0

0 34 0

0 50 0

0 40 0

0 33 0

0 39 0

0 40 0

0 30 0

0 35 0

0 37 TOTAL 4

3 11 59 84 246 324 36 0

0 0

0 767 NUMBER OF CALMS:

1 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

768 TOTAL HOURS FOR THE PERIOD:

768

River Bend Station 2011 Regulatory Guide 1.21 Page 51 of 64 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS G FROM 1/01/11 0:00 TO 12/31/11 23:00 PRIMARY SENSORS -

150 FOOT WIND SPEED (METERS/SECOND)

WIND

.22-

.51-

.76-1.1-1.6-2.1-3.1-5.1-7.1-10.1-13.1- >18 TOT.

DIR

.50

.75 1.0 1.5 2.0 3.0 5.0 7.0 10.0 13.0 18.0 N

1 1

2 1

5 18 24 1

0 0

53 NNE 0

1 2

1 12 37 32 0

0

'0 0

0 85 NE 0

1 2

6 8

32 68 0

0 0

117 ENE 0

1 4

6 10 20 34 0

0 0

75 E

0 0

3 7

11 43 10 2

0 0

76 ESE 0

0 2

5 4

28 55 4

0 0

98 SE 0

2 2

4 12 23 25 0

0 0

68 SSE 1

1 5

6 6

39 12 0

0 0

70 S

0 2

0 13 13 23 5

0 0

0 56 SSW 1

1 1

9 13 30 5

0 0

0 60 SW 0

2 2

5 22 33 10 0

0 0

74 WSW 0

2 5

13 17 17 4

0 0

0 58 W

1 1

3 8

14 30 6

0 0

0 63 WNW 0

0 3

3 4

27 8

0 0

0 45 NW 2

0 2

3 7

25 13 0

0 0

52 NNW 1

2 1

5 4

25 30 0

0 0

68 TOTAL 7

17 39 95 162 450 341 7

0 0

0 0 1118 NUMBER OF CALMS:

2 NUMBER OF INVALID HOURS:

0 NUMBER OF VALID HOURS:

1120 TOTAL HOURS FOR THE PERIOD:

1120

River Bend Station 2011 Regulatory Guide 1.21 Page 52 of 64 Table 7 ATMOSPHERIC DISPERSION AND DEPOSITION RATES FOR THE MAXIMUM INDIVIDUAL DOSE CALCULATIONS Analysis Location Ground Level Mixed Mode (meters)

Releases Releases Gamma air dose (3) 994 m

WNW CHI/Q - 421.0 CHI/Q - 33.1 and Beta Air Dose (Containment)

Maximum Receptor 994 m WNW CHI/Q - 421.0 CHI/Q - 33.1 (4)

Resident D/Q 50.3 D/Q

- 18.0 Garden Meat animal Immersion Milk animal (5) 7,000 m WNW CHI/Q -

3.58 CHI/Q -.870 D/Q 0.38 D/Q

-.223 Other on-site 115 m ENE CHI/Q -

5977.0 CHI/Q - 407.5 Receptors D/Q 529.7 D/Q 46.9 275 m N CHI/Q - 1644.0 CHI/Q - 169.1 D/Q 345.6 D/Q 68.4 2500 SW CHI/Q -

34.45 CHI/Q -

4.65 D/Q 3.35 D/Q 1.40 Notes:

(1) All CHI/Q = 10-7 sec/m 3 (2) All D/Q = 10-9 m-2 (3) Maximum offsite location (property boundary) with highest CHI/Q (unoccupied).

(4) Maximum hypothetical occupied offsite location with highest CHI/Q and D/Q.

(5) No milk animal within 5 miles radius, hypothetical location in worst sector.

(6) Other onsite receptors (7) Revisions to X/Q and D/Q can be performed using NUREG/CR-2919, XOQDOQ, Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations

River Bend Station 2011 Regulatory Guide 1.21 Page 53 of 64 Table 8 Groundwater Monitoring Well Sample Results

River Bend Station 2011 Regulatory Guide 1.21 Page 54 of 64 GROUND WATER MONITORING SAMPLES (H-3) - RBS 3000 TRITIUM LLD (pCi/l)

LAB ID 20110355 20110356 20110357 20110358 20110359 20110360 20110361 20110363 20110364 20110365 20110366 20110367 20110368 20110369 20110892 20110893 20110894 20110895 20110896 LOCATION PZ-03 MW-100 MW-19 MW-104 MW-103 MW-102 MW-101 MW-18 MW-08 MW-102 MW-02 MW-02D MW-10 MW-06 MW-08 MW-19 MW-102 MW-103 MW-104 DATE 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/23/2011 3/23/2011 3/23/2011 3/23/2011 3/23/2011 3/23/2011 3/23/2011 6/22/2011 6/22/2011 6/22/2011 6/22/2011 6/22/2011

< 399

< 386

< 416

< 402

< 432

< 386

< 411

< 402

< 400

< 401

< 402

< 401

< 399

< 402

< 412

< 414

< 468

< 411

< 422

River Bend Station 2011 Regulatory Guide 1.21 Page 55 of 64 LLD (pCi/l) 3000 LAB ID LOCATION DATE TRITIUM 20110897 MW-18 6/22/2011

< 410 20110898 MW-102 6/22/2011

< 511 20110899 PZ-03 6/22/2011

< 408 20110900 MW-100 6/22/2011

< 452 20110909 MW-04 6/23/2011

< 414 20110910 MW-10 6/23/2011

< 409 20110912 MW-101 6/23/2011

< 396 20110913 MW-06 6/23/2011

< 395 20110914 MW-02 6/23/2011

< 445 20110915 DUP-MW-02 6/23/2011

< 399 20111330 MW-100 9/20/2011

< 620 20111331 PZ-03 9/20/2011

< 627 20111332 SW-102 9/20/2011

< 618 20111333 SW-103 9/20/2011

< 627 20111335 MW-02 9/21/2011

< 620 20111336 MW-02 eb 9/21/2011

< 621 20111337 MW-06 9/21/2011

< 622 20111338 MW-06 DUP 9/21/2011

< 615 20111339 MW-10 9/21/2011

< 648 20111340 MW-102 9/21/2011

< 649 20111341 MW-04 9/21/2011

< 667

River Bend Station 2011 Regulatory Guide 1.21 Page 56 of 64 LLD (pCi/I) 3000 LAB ID LOCATION DATE TRITIUM 20111342 MW-08 9/21/2011

< 645 20111343 MW-18 9/21/2011

< 656 20111344 MW-19 9/21/2011

< 647 20111345 SW-101 9/21/2011

< 649 20111346 SW-104 9/21/2011

< 661 20111602 MW-05 12/6/2011

< 674 20111603 MW-03 12/6/2011

< 670 20111604 MW-02 12/6/2011

< 687 20111605 MW-06 12/6/2011

< 639 20111606 MW-10 12/6/2011

< 671 20111607 MW-102 12/6/2011

< 671 20111608 MW-102 DUP 12/6/2011

< 672 20111630 PZ-01 DUP 12/6/2011 40,488 20111631 PZ-01 12/6/2011 40,617 20111632 MW-09 12/6/2011

< 637 20111633 PZ-03 12/6/2011

< 676 20111634 MW-100 12/6/2011

< 678 20111635 SW-101 12/6/2011

< 639 20111644 MW-07 12/7/2011

< 644 20111645 MW-08 12/7/2011

< 642 20111646 MW-20 12/7/2011

< 665

River Bend Station 2011 Regulatory Guide 1.21 Page 57 of 64 LLD (pCi/l) 3000 LAB ID LOCATION DATE TRITIUM 20111647 MW-18 12/7/2011

< 701 20111648 MW-19 12/7/2011

< 705 20111649 T-14 12/7/2011

< 669 20111650 MW-17 12/7/2011

< 704 20111651 MW-21 12/7/2011

< 668 20111652 PZ-02 12/7/2011

< 667 20111673-MW-12 12/7/2011

< 703 20111674 MW-14 12/7/2011

< 644 20111675 MW-15 12/7/2011

< 650 20111676 MW-15 DUP 12/7/2011

< 644 20111677 MW-11 12/7/2011

< 674 20111678 MW-01 12/7/2011

< 681 20111679 MW-13 12/7/2011

< 676 20111680 SW-103 12/7/2011

< 667 20111681 SW-104 12/7/2011

< 664 20111682 SW-102 12/7/2011

< 682 20111683 MW-16 12/7/2011

< 669 20111734 PZ-01 12/19/2011 48,016 20111735 PZ-01 DUP 12/19/2011 48,245 20111736 MW-04 12/19/2011

< 727

River Bend Station 2011 Regulatory Guide 1.21 Page 58 of 64 GROUND MONTORING WELL SAMPLES (GAMMA) - RBS LLD (pCi/I) 15 15 30 15 30 15 30 15 15 18 60 15 LAB ID 20110355 20110356 20110357 20110358 20110359 20110360 20110361 20110363 20110364 20110365 20110366 LOCATION PZ-03 MW-100 MW-19 MW-104 MW-103 MW-102 MW-101 MW-18 MW-08 MW-102 MW-02 DATE 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/22/2011 3/23/2011 3/23/2011 3/23/2011 3/23/2011 MN-54

8.22

10.64

< 10.56

6.90

< 8.66

< 9.16

< 8.73

< 8.74

< 5.81

< 7.16

< 8.23 CO-58

< 7.70

6.56

< 8.10

< 9.96

< 7.15

10.51

< 9.05

< 6.77

< 4.80

< 11.06

8.16 FE-59

< 21.12

< 18.21

< 15.97

< 15.48

< 15.65

19.77

< 10.42

< 20.95

< 8.12

< 16.08

< 16.49 CO-60

< 9.47

< 10.42

< 6.98

8.58

< 8.01

8.98

< 9.47

7.95

< 6.41

< 8.76

9.70 ZN-65

< 20.46

< 18.79

< 13.67

19.27

< 15.12

< 22.25

< 25.20

< 21.88

11.25

< 16.97

< 24.95 NB-95 ZR-95 1-131 CS-134 CS-137 BA-140 LA-140

< 7.75

< 10.19

7.82

< 8.22

< 10.53

8.68

< 9.60

< 12.86

< 7.12

< 10.27

9.85

< 16.57

< 14.69

< 11.41

< 16.37

< 12.95

< 10.28

< 16.53

< 16.29

10.91

13.71

< 15.44

< 14.95

< 14.81

12.95

< 10.50

< 14.57

< 14.97

14.70

< 14.12

< 8.70

< 14.66

< 14.27

< 8.23

< 7.61

8.31

12.35

< 8.19

< 8.69

10.54

< 8.22

7.22

< 9.57

< 10.81

< 7.34

< 10.57

< 5.88

< 11.84

< 7.92

6.53

< 8.08

< 7.00

< 7.87

9.02

< 10.50

< 38.03

45.54

35.78

29.90

< 37.59

< 47.71

40.53

< 36.57

27.94

< 43.18

< 47.04 13.82 14.82 14.82 11.00 14.65 13.28 11.81 10.69 12.35 12.36 12.94 20110367 MW-02D 3/23/2011

< 10.01

< 8.10

< 11.33

< 8.88

< 10.28

< 10.49

< 18.29

< 10.54

< 10.36

< 10.60

< 37.31

< 11.91

River Bend Station 2011 Regulatory Guide 1.21 Page 59 of 64 LLD (pCi/I)

LAB ID LOCATION 20110368 20110369 20110370 20110892 20110893 20110894 20110895 20110897 20110898 20110899 20110900 20110909 20110910 20110913 MW-10 MW-06 EB-final MW-08 MW-19 MW-102 MW-103 MW-18 MW-102 PZ-03 MW-100 MW-04 MW-10 MW-06 3

3 3

6 6

6 6/

DATE Ml 3/23/2011

/23/2011

/22/2011

/22/2011

/22/2011 5/22/2011

/22/2011

/23/2011

/23/2011 15 15 30 15 30 N-54 CO-58 "

FE-59 CO-60 ZN-65 7.52

< 8.98

< 12.98

< 9.44

< 20.40 11.71

< 8.27

< 21.39

< 7.69

< 19.49 5.04

< 4.89

< 16.31

< 5.42

< 14.53 11.02

< 11.15

< 20.93

< 7.90

< 27.00 7.90

< 7.54

< 16.32

< 8.50

< 18.58 2.91

< 3.12

< 6.04

< 2.96

< 6.10 12.04

< 13.70

< 39.49

< 12.78

< 29.02 5.88

< 8.11

< 16.07

< 7.28

< 16.95 3.53

< 3.75

< 7.02

< 3.72

< 7.40 12.13

< 7.61

< 23.81

< 9.64

< 25.31 3.49

< 3.85

< 7.36

< 3.62

< 8.20 6.98

< 17.78

< 22.04

< 9.43

< 22.86 11.96

< 13.69

< 27.18

< 10.95

< 21.75 10.46

< 10.80

< 39.82

< 14.93

< 24.66 15 NB-95

< 10.47

10.10

< 7.66

13.46

12.02

< 4.43

23.68

< 8.55

4.74

11.99

< 5.19

16.94

21.08

23.31 30 ZR-95

< 14.38

15.60

< 16.96

20.23

< 13.18

< 6.19

< 25.51

< 11.94

< 6.65

< 15.67

6.47

< 19.01

< 23.14

< 24.36 15 1-131

13.32

12.66

< 8.25

< 11.23

< 8.31

< 11.18

< 100.81

7.66

12.93

< 11.23

< 13.04

< 76.35

< 71.27

< 73.56

< 9.75

< 9,90

< 8.57

9.27

< 8.67

2.99

< 10.62

8.79

< 4.05

< 12.91

< 3.53

< 8.54

< 11.83

< 12.20

< 9.14

< 11.98

< 9.45

12.95

< 8.23

< 2.96

12.61

< 8.24

< 3.41

< 12.41

3.46

10.66

< 10.12

13.31

< 24.02

< 43.88

28.57

< 41.70

28.25

< 24.08

< 154.87

< 24.85

< 26.85

36.28

28.46

< 100.12

124.34

132.83 15 18 CS-134 CS-137 60 15 BA-140 LA-140

< 13.93

< 13.75

< 7.40

14.60

< 10.48

< 8.32

< 45.70

13.53

< 9.74

13.99

9.77

< 43.67

< 33.81

37.23

River Bend Station 2011 Regulatory Guide 1.21 Page 60 of 64 LLD (pCi/I)

LAB ID LOCATION 20110914 MW-02 20110915 MW-02 dup 20111330 MW-100 20111331 PZ-03 20111332 SW-102 20111333 SW-103 20111335 MW-02 20111337 MW-06 20111338 MW-06 DUP 20111339 MW-10 20111340 MW-102 20111341 MW-04 20111342 MW-08 15 DATE MN-54 6/23/2011 6/23/2011 9/20/2011 9/20/2011 9/20/2011 9/20/2011 9/21/2011 9/21/2011 9/21/2011 9/21/2011 9/21/2011 9/21/2011 9/21/2011

< 8.94

< 12.67

< 12.90

< 11.40

< 11.60

< 14.50

< 10.60

< 13.00

< 14.70

< 8.77

< 7.91

< 9.94

< 9.58 15 C0-58

< 11.34

12.50

< 9.11

11.90

9.45

14.30

< 11.50

< 11.60

< 11.00

< 11.40

< 9.65

< 10.50

< 8.63 30 15 FE-59 CO-60

28.08

< 11. 19

< 34.02

< 12.43

20.80

< 11.70

< 23.70

< 3.20

17.70

< 7.14

< 17.40

< 10.30

< 22.20

< 7.63

26.30

< 12.90

< 20.70

< 12.30

< 17.90

< 9.99

< 13.60

< 9.74

< 17.10

< 11.20

< 17.60

< 10.40 30 ZN-65

< 27.12

< 23.11

< 20.10

< 26.50

< 17.10

29.50

< 21.30

< 28.00

13.10

17.10

< 15.20

< 21.30

< 19.80 15 NB-95 23.36 23.01 9.73 11.40 10.40 12.50 14.40 14.80 13.30 8.21 7.49 8.76 9.66 30 ZR-95

17.42

< 15.83

< 13.60

< 20.60

< 15.90

< 22.50

18.00

< 21.00

18.00

19.70

15.20

15.40

14.90 15 1-131

73.42

< 80.13

10.90

< 8.97

< 10.20

11.60

10.10

< 12.80

< 11.90

10.80

< 10.30

< 9.75

10.10 15 CS-134

< 10.13

< 11.24

< 9.47

8.94

< 11.20

10.80

< 9.19

< 10.20

< 11.80

< 6.91

8.30

< 6.66

< 9.58 18 CS-137

< 9.92

< 14.76

< 11.70

< 9.39

< 11.80

< 14.00

13.70

< 13.60

11.90

< 10.60

9.06

< 10.30

11.20 60 BA-140

< 114.60

< 120.96

< 27.20

28.70

37.80

32.10

< 39.30

< 47.00

< 39.40

< 35.30

< 32.80

< 42.70

37.00 15 LA-140

< 41.86

33.04

< 11.60

< 13.70

< 9.90

< 14.20

< 9.30

< 14.30

< 13.60

< 14.10

13.70

3.56

12.20

River Bend Station 2011 Regulatory Guide 1.21 Page 61 of 64 LLD (pCi/I) 15 15 30 LAB ID LOCATION DATE MN-54 C0-58 FE-59 15 CO-60 30 ZN-65 15 NB-95 30 ZR-95 20111343 MW-18 9/21/2011

< 11.10

< 7.86

< 17.80

< 8.03 20111344 20111345 20111346 20111602 20111603 20111604 20111605 20111606 20111607 20111608 20111630 MW-19 SW-101 SW-104 MW-05 MW-03 MW-02 MW-06 MW-10 MW-102 MW-102 DUP PZ-01 DUP 9/21/2011 9/21/2011

.9/21/2011 12/6/2011 12/6/2011 12/6/20i 1 12/6/2011 12/6/2011 12/6/2011 12/6/2011 12/6/2011

< 9.58

< 12.10

< 10.10

< 13.50

< 11.60

< 8.58

< 11.50

< 15.60

< 11.00

< 9.59

< 10.30

< 10.10

< 7.57

< 9.67

< 8.78

< 7.98

< 9.23

< 14.30

< 14.20

< 11.50

< 12.20

< 17.60

< 23.00

< 14.80

< 24.20

< 18.10

< 18.30

< 21.10

< 18.30

< 23.20

< 15.70

< 20.10

< 9.01

< 3.08

< 10.20

< 11.50

< 11.70

< 10.60

< 11.70

< 14.90

< 10.50

< 11.90

< 9.02

< 5.05

< 11.00

< 19.00

< 17.10

< 10.30

< 16.30

< 15.90

< 14.00

< 13.50

< 16.70

< 8.77

< 20.20

< 18.90

< 9.38

< 21.70

< 24.20

< 12.90

< 22.00

< 20.20

< 8.51

< 13.30

< 22.20

< 10.10

< 16.70

< 20.10

< 13.80

< 24.70

< 26.00

< 9.95

< 9.29

< 24.10

< 11.60

< 16.60

< 19.90

< 11.30

< 15.20 15 1-131

< 9.05

< 9.54

< 8.09

< 8.64

< 9.60

< 11.10

< 8.58

< 11.60

< 12.60

< 8.14

< 11.30

< 11.10 15 18 CS-134 CS-137

< 7.02

< 8.63

< 12.20

< 7.95

< 9.53

< 7.64

< 8.68

< 7.93

< 13.90

< 6.92

< 9.10

< 9.60

< 12.00

< 7.63

< 13.80

< 9.80

< 14.70

< 13.80

< 9.70

< 11.80

< 16.20

< 9.30

< 7.42

< 10.60

< 40.70

< 41.40

< 41.00

< 44.00

< 53.30

< 40.80

< 38.10

< 26.40

< 25.20

< 32.60

< 45.70

< 37.20

< 14.40

< 9.68

< 11.30

< 11.90

< 11.70

< 13.50

< 13.90

< 14.30

< 12.50

< 3.87

< 13.60

< 13.50 60 15 BA-140 LA-140 20111631 PZ-01 12/6/2011

< 10.20

< 11.60

< 15.10

< 7.12

< 13.70

< 12.80

< 18.10

< 11.70

< 9.17

< 11.50

< 29.20

< 3.77

River Bend Station 2011 Regulatory Guide 1.21 Page 62 of 64 LLD (pCi/I)

LAB ID LOCATION 20111632 20111633 20111634 20111644 20111645 20111646 20111647 20111648 20111649 20111650 20111651 20111652 MW-09 PZ-03 MW-100 MW-07 MW-08 MW-20 MW-18 MW-19 T-14 MW-17 MW-21 PZ-02 15 15 30 DATE MN-54 CO-58 FE-59 12/6/2011

< 8.22

< 7.44

< 15.60 12/6/2011

< 7.21

< 7.23

< 14.80 12/6/2011

< 7.58

< 7.45

< 12.10 12/7/2011

< 5.23

< 5.06

< 10.20 12/7/2011

< 4.60

< 4.99

< 10.10 12/7/2011

< 4.34

< 5.08

< 7.81 12/7/2011

< 5.95

< 6.72

< 11.00 12/7/2011

< 6.33

< 5.70

< 14.70 12/7/2011

< 4.95

< 5.27

< 11.50 12/7/2011

< 5.65

< 5.70

< 12.10 12/7/2011

< 5.39

< 5.01

< 8.26 12/7/2011

< 3.11

< 3.49

< 8.13 15 CO-60

< 8.65

< 6.44

5.16

< 4.54

4.64

< 4.76

< 5.59

< 4.48

< 3.79

4.43

< 4.06

3.23 30 15 30 15 ZN-65 NB-95 ZR-95 1-131 16.20

< 7.57

< 8.78

< 11.50 14.60

< 8.01

< 11.30

< 10.40 10.00

< 6.75

< 13.00

< 10.80 14.20

< 6.24

< 10.10

< 14.60 10.20

< 6.87

< 8.74

< 13.90 8.19

< 5.87

< 8.36

< 11.60 10.50

< 7.43

< 10.00

< 15.00 11.60

< 8.20

< 11.10

< 14.30 8.13

< 7.48

< 9.55

< 11.80 11.20

< 5.17

< 8.67

< 13.60 11.20

< 6.68

< 9.15

< 14.70 6.43

< 4.23

< 6.58

< 14.90 15 CS-134

< 6.16

< 7.49

< 5.33

5.63

< 4.35

< 4.58

< 5.90

< 6.01

4.64

< 4.98

< 4.24

< 3.24 18 CS-137

< 7.23

< 7.97

< 6.15

< 5.04

< 4.96

< 4.38

< 5.71

< 6.24

5.46

< 6.63

5.09

< 2.94 60 BA-140

< 35.00

< 36.00

< 29.50

< 33.90

< 35.00

< 29.70

< 30.70

< 32.10

< 33.90

< 32.80

30.10

30.10 15 LA-140

13.80

< 12.40

< 11.80

< 10.50

< 11.80

< 13.10

< 12.40

< 13.30

< 11.70

< 13.50

< 12.40

< 10.60 20111673 MW-12 12/7/2011

< 9.70

< 5.56

< 13.10

< 10.80

< 13.60

< 11.00

< 19.60

< 11.80

< 8.56

< 9.72

< 36.70

< 13.30

River Bend Station 2011 Regulatory Guide 1.21 Page 63 of 64 LLD (pCi/I)

LAB ID LOCATION 15 DATE MN-54 20111674 20111675 20111676 20111677 20111678 20111679 20111680 20111681 20111682 20111683 MW-14 MW-15 MW-15 DUP MW-11 MW-01 MW-13 SW-103 SW-104 SW-102 MW-16 12/7/2011 12/7/2011 12/7/2011 12/7/2011 12/7/2011 12/7/2011 12/7/2011 12/7/2011 12/7/2011 12/7/2011

< 7.67

< 9.64

< 7.56

< 8.48

< 6.44

< 6.11

< 2.84

< 2.91

< 4.99

< 5.56 15 CO-58

< 6.52

< 9.29

< 8.49

< 7.37

< 8.39

< 6.68

< 2.70

< 3.26

< 4.26

< 5.62 30 FE-59

< 13.10

< 14.40

< 19.90

< 13.50

< 11.70

< 12.70

< 5.66

< 7.69

< 9.84

< 11.30 15 CO-60 7.13 10.10 9.92 8.03 6.40 5.60 2.06 3.09 5.17 4.79 30 15 30 15 ZN-65 NB-95 ZR-95 1-131

< 9.87

< 6.59

< 12.10

< 9.34

< 19.50

< 12.10

< 18.20

< 14.40

< 14.70

< 8.58

< 16.90

< 13.80

< 18.10

< 5.68

< 16.50

< 12.00

13.40

< 8.20

< 12.10

< 9.30

< 13.30

< 7.16

< 11.20

< 14.30

< 5.16

< 3.63

< 5.59

< 14.20

< 5.48

< 4.16

< 6.73

< 14.80

< 10.70

< 6.80

< 7.47

< 13.50

< 9.68

< 6.27

< 11.00

< 14.90 15 CS-134

< 7.07

< 10.30

< 9.91

< 9.00

< 6.94

< 5.00

< 2.19

< 2.90

< 4.87

< 3.74 18 CS-137

< 5.89

< 11.10

< 8.52

< 7.71

< 7.83

< 5.76

< 2.64

< 2.94

5.67

< 5.15 60.

BA-140

< 32.00

48.60

< 48.40

< 34.50

< 39.00

< 44.00

< 22.70

< 31.30

<43.60

< 32.40 15 LA-140

< 12.50

< 4.22

< 14.30

< 13.30

< 13.90

< 13.60

< 8.45

< 9.69

< 13.10

< 11.60 20111736 MW-04 12/19/2011

< 9.93

< 9.07

< 16.90

< 11.10

< 29.50

< 12.40

< 20.00

< 8.81

< 12.60

< 11.40

< 39.70

< 11.70

River Bend Station 2011 Regulatory Guide 1.21 Page 64 of 64 Process Control Program

Procedure Contains NMM REFLIB Forms: YES El NO Z Effective Procedure Owner:

Mark L. Carver Governance Owner:

Mark L. Carver Date

Title:

Manager, Fleet Radwaste

Title:

Manager, Fleet Radwaste 11/11/11 Site:

HQN Site:

HQN Exception Site Site Procedure Champion Title Date*

ANO Jim Smith Manager, RP N/A BRP N/A N/A GGNS Tom Trichell Manager, RP 12/14/11 IPEC Reid Tagliamonte Manager, RP 12/14/11 JAF Eric Wolf Manager, RP PLP Chuck Sherman Manager, RP PNPS Jack Priest Manager, RP RBS Glenn Pierce Manager, RP VY David Tkatch Manager, RP W3 Darrell Newman Manager, RP (acting)

N/A NP N/A N/A N/A HQN Mark L. Carver Manager, Fleet Radwaste Site and NMM Procedures Canceled or Superseded By This Revision None Process Applicability Exclusion All Sites: LI Specific Sites: ANO El BRP El GGNS El IPECE] JAF EL PLP El PNPS LI RBS EL VY El W3 [] NP El Change Statement Editorial Change -

o Under the Site Applicability column for the NRC letters 1.98.091 and 1.88.078 listed in section 8.0, Vermont Yankee (VY) was changed to Pilgrim Nuclear Power Station (PNPS), ANO correction and addition of two VTY items o

Updated same ANO correction in Step 5.8 (1) and 5.8 (3)

JAF and IPEC effective date exceptions due to conditional site requirements within.step 5.8 [4]

TABLE OF CONTENTS Section Title Paae 1.0 PURPOSE.............................................................................

3

2.0 REFERENCES

3 3.0 DEFINITIONS........................................................................

6 4.0 RESPONSIBILITIES............................................................

9 5.0 DETAILS.............................................................................

10 6.0 INTERFACES.....................................................................

20 7.0 RECORDS........................................................................

20 8.0 SITE SPECIFIC COMMITMENTS.......................................

21 9.0 ATTACHMENTS.................................................................

21

1.0 PURPOSE The Process Control Program (PCP) requires formulas, sampling, analyses, test and determinations to be made to ensure that the processing and packing of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61 and 71, State Regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. The scope of a PCP is to assure that radioactive waste will be handled, shipped, and disposed of in a safe manner in accordance with approved site or vendor procedures, whichever is applicable. [GGNS UFSAR, Chapter 16B.1 / TRM - 7.6.3.8 paragraph 1]

1.1 The purpose of this document is to provide a description of the solid radioactive waste Process Control Program (PCP) at all the Entergy fleet sites. The PCP describes the methods used for processing, classification and packaging low-level wet radioactive waste into a form acceptable for interim on-site storage, shipping and disposal, in accordance with 10 CFR Part 61 and current disposal site criteria.

1.2 To ensure the safe operation of the solid radwaste system, the solid radwaste system will be used in accordance with this Process Control Program to process radioactive wastes to meet interim on-site storage, shipping and burial ground requirements.

1.3 This document addresses the process control program in the context of disposal criteria, on-site processing and vendor processing requirements.

1.4 The Process Control Program implements the requirements of 1 OCFR50.36a and General Design Criteria 60 of Appendix A to 10CFR Part 50. The process parameters included in the Process Control Program may include but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

1.5 This document does NOT address the requirements for 1 OCFR Part 61.56 (waste characteristics) for material sent to intermediate processors, because the final treatment and packaging is performed at the vendor facilities.

2.0 REFERENCES

[1]

EN-QV-104, "Entergy Quality Assurance Program Manual Control"

[2]

Title 49, Code of Federal Regulations

[3]

Title 10, Code of Federal Regulations, Part 20

2. 0 continued

[4]

Title 10, Code of Federal Regulations, Part 61

[5]

Title 10, Code of Federal Regulations, Part 71, Appendix H [QAPM, Section A.1.c]

[6]

Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, 11 May 1983

[7]

Disposal Site Criteria and License

[81 Waste Processor Acceptance Criteria

[9]

EN-LI-1 00, "Process Applicability Determination"

[10]

NRC Information and Enforcement Bulletins NRC Information Notice 79-19: Packaging of Low-Level Radioactive Waste for Transport and Burial.

NRC Information Notice 80-24: Low-Level Radioactive Waste Burial Criteria.

NRC Information Notice 80-32: Clarification of Certain Requirements for Exclusive-Use Shipments of Radioactive Materials.

NRC Information Notice 80-32, Rev. 1: Clarification of Certain Requirements for Exclusive-Use Shipments of Radioactive Materials.

NRC Information Notice 83-05: Obtaining Approval for Disposing of Very-Low-Level Radioactive Waste - 1 0CFR Section 20.302.

NRC Information Notice 83-10: Clarification of Several Aspects Relating to Use of NRC-Certified Transport Packages.

NRC Information Notice 83-33: Non-Representative Sampling of Contaminated Oil.

NRC Information Notice 84-50: Clarification of Scope of Quality Assurance Programs for Transport Packages Pursuant to 1 OCFR 50 Appendix B.

NRC Information Notice 84-72: Clarification of Conditions for Waste Shipments Subject to Hydrogen Gas Generation.

NRC Information Notice 85-92: Surveys of Wastes Before Disposal from Nuclear Reactor Facilities.

NRC Information Notice 86-20: Low-Level Radioactive Waste Scaling Factors, 10CFR 61.

NRC Information Notice 86-90: Requests to Dispose of Very Low-Level Radioactive Waste Pursuant 1 OCFR 20.302

2.0[10], continued NRC Information Notice 87-03: Segregation of Hazardous and Low-Level Radioactive Wastes NRC Information Notice 87-07: Quality Control of On-Site Dewatering/ Solidification Operations by Outside Contractors

[11]

NRC Information and Enforcement Bulletins (continued)

NRC Information Notice 89-27: Limitations on the Use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste NRC Information Notice 92-62: Emergency Response Information Requirements for Radioactive Material Shipments NRC Information Notice 92-72: Employee Training and Shipper Registration Requirements for Transporting Radioactive Materials NRC Generic Letter 89-01, "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program".

[12]

Nureg-0800 Standard Review Plan Section 11.4 Revision 2, Solid Waste Management Systems.

[13]

NRC Waste Form Technical-Position, Revision 1 Jan 24 1991.

[14]

NRC SECY 94-198 Review of Existing Guidance Concerning the Extended Storage of Low-Level Radioactive Waste.

[15]

EPRI TR-1 06925 Rev-1, Interim On-Site Storage of Low Level Waste: Guidelines for Extended Storage - October1996

[16]

NRC Branch Technical Position On Concentration Averaging And Encapsulation Jan 17 1995

[17]

Commitment Documents (U-2 and U-3)

IPN-99-079, "Supplement to Proposed Changes to Technical Specifications Incorporating Recommendations of Generic Letter 89-01 and the Revised 10 CFR Part 20 and 10 CFR Part 50.36a.

Appendix B Technical Specifications, Section 4.5 [IP, RECS ODCM Part 1]

3.0 DEFINITIONS

[1]

Batch - A quantity of waste to be processed having essentially consistent physical and chemical characteristics as determined through past experience or system operation knowledge by the Radwaste Shipping Specialist. A batch could be a waste tank, several waste tanks grouped together or a designated time period such as between outages as with the DAW waste stream. An isolated quantity of feed waste to be processed having essentially constant physical and chemical characteristics.

(The addition or removal of water will not be considered to create a new batch).

[2]

Certificate of Compliance - Document issued by the USNRC regulating use of a NRC licensed cask or issued by (SCDHEC) South Carolina Department of Health and Environmental Conservation regulating a High Integrity Container.

[3]

Chelating Agents - EDTA, DTPA, hydroxy-carboxylic acids, citric acid, carbolic acid and glucinic acid.

[4]

Compaction - The process of volume reducing solid waste by applying external pressure.

[5]

Confirmatory Analysis - The practice of verifying that gross radioactivity measurements using MCA are reasonably consistent with independent laboratory sample data.

[6]

Dewatered Waste - Wet waste that has been processed by means other than solidification, encapsulation, or absorption to meet the free standing liquid requirements of 1 COR Part 61.56 (a)(3) and (b)(2).

[7]

De-waterinq - The removal of water or liquid from a waste form, usually by gravity or pumping.

[8]

Dilution Factor - The RADMAN computer code factor to account for the non-radioactive binder added to the waste stream in the final product when waste is solidified.

[9]

Dry Waste - Radioactive waste which exist primarily in a non-liquid form and includes such items as dry materials, metals, resins, filter media and sludges.

[10]

Encapsulation - Encapsulation is a means of providing stability for certain types of waste by surrounding the waste by an appropriate encapsulation media.

[11]

Gamma-Spectral-Analysis - Also known as IG, MCA, Ge/Li and gamma spectroscopy.

[12]

Gross Radioactivity Measurements - More commonly known as dose to curie conversion for packaged waste characterization and classification.

3.0 continued

[13]

Homogeneous - Of the same kind or nature; essentially alike. Most Volumetric waste streams are considered homogeneous for purposes of waste classification.

[14]

Incineration - The process of burning a combustible material to reduce its volume and yield an ash residue.

[15]

Liquid Waste - Radioactive waste that exist primarily in a liquid form and is contained in other than installed plant systems, to include such items as oil, EHC fluid, and other liquids. This waste is normally processed off-site.

[16]

Low-Level Radioactive Waste (LLW) - Those wastes containing source, special nuclear, or by-product material that are acceptable for disposal in a land disposal facility. For the purposes of this definition, low-level radioactive waste has the same meaning as in the Low-Level Waste Policy Act, that is, radioactive waste not classified as high-level radioactive waste, transuranic waste, spent nuclear fuel, or by-product material as defined in section 11 e.(2) of the Atomic Energy Act (uranium or thorium tailings and waste).

[17]

Measurement of Specific Radionuclides - More commonly known as direct sample or container sample using MCA data for packaged waste characterization and classification.

[18]

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

[19]

Pregualification Program - The testing program implemented to demonstrate that the proposed method of wet waste processing will result in a waste form acceptable to the land disposal facility and the NRC.

[20]

Processing - Changing, modifying,,and/or packaging radioactive waste into a form that is acceptable to a disposal facility.

[21]

Quality Assurance/Quality Control - As used in this document, "quality assurance" comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component will perform satisfactorily in service.

Quality assurance includes quality control, which comprises those quality assurance actions related to the physical characteristics of a material structure, component, or system to predetermined requirements.

3.0, continued

[22]

Reportable Quantity Radionuclides (RQ) - Any radionuclide listed in column (1) of Table 2 of 49CFR Part 172.101 which is present in quantities as listed in column (3) of Table 2 of 49CFR Part 172.101.

[23]

Sampling Plan - A program to ensure that representative samples from the feed waste and the final waste form are obtained and tested for conformance with parameters stated in the PCP and waste form acceptance criteria.

[24]

Scaling Factor - A dimensionless number which relates the concentration of an easy to measure radionuclide (gamma emitter) to one which is difficult to measure (beta and/or alpha emitters).

[25]

Significant Quantity - For purposes of waste classification all the following radionuclide values SHALL be considered significant and must be reported on the disposal manifest.

Any value (real or LLD) for radionuclides listed in Appendix G to 1 OCFR20 (H-3, C-14, 1-129, Tc-99).

Greater than or equal to 1 percent of the concentration limits as listed in 1 OCFR Part 61.55 Table 1.

Greater than or equal to 1 percent of the Class A concentration limits listed in 1 OCFR Part 61.55 Table 2.

Greater than or equal to 1 percent of the total activity.

Greater than or equal to 1 percent of the Reportable Quantity limits listed on 49CFR Part 172.101 Table 2.

[26]

Solidification - The conversion of wet waste into a free-standing monolith by the addition of an agent so that the waste meets the stability and free-standing liquid requirements of the disposal site.

[27]

Special Radionuclides - The RADMAN computer code term for radionuclides listed in Appendix G to 10CFR20 (i.e., H-3, C-14,1-129 & Tc-99)

[28]

Stability - Structural stability per 1 OCFR61.2, Waste Form Technical Position, and Waste Form Technical Position Revision 1. This can be provided by the waste form, or by placing the waste in a disposal container or structure that provides stability after disposal. Stability requires that the waste form maintain its structural integrity under the expected disposal conditions.

3.0, continued

[29]

Training - A systematic program that ensures a person has knowledge of hazardous materials and hazardous materials regulations.

[30]

Type A Package - Is the packaging together with its radioactive contents limited to Al or A2 as appropriate that meets the requirements of 49CFR Part 173.410 and Part 173.412, and is designed to retain the integrity of containment and shielding under normal conditions of transport as demonstrated by the tests set forth in 49CFR Part 173.465 or Part 173.466 as appropriate.

[31]

Type B Package - Is the packaging together with its radioactive contents that is designed to retain the integrity of containment and shielding when subjected to the normal conditions of transport and hypothetical accident test conditions set forth in 10CFR Part 71.

[32]

Volume Reduction - any process that reduces the volume of waste. This includes but is not limited to, compaction and incineration.

[33]

Waste Container - A vessel of any shape, size, and composition used to contain the waste media.

[34]

Waste Form - Waste in a waste container acceptable for disposal at a licensed disposal facility.

[35]

Waste Stream - A Plant specific and constant source of waste with a distinct radionuclide content and distribution.

[36]

Waste Type - A single packaging configuration and waste form tied to a specific waste stream.

4.0 RESPONSIBILITIES

[1]

The Vice President Operations Support (VPOS) is responsible for the implementation of this procedure.

[2]

Each site Senior Nuclear Executive (SNE) is responsible for ensuring that necessary site staff implements this procedure.

[3]

The Low Level RadWaste (LLRW) Focus Group is responsible for evaluating and recommending changes and revisions to this procedure.

4.0, continued

[4]

Each site RP Department - Radwaste Supervisor / Specialist (title may vary at the site's respectively) has the overall responsibility for implementing the PCP and is responsible for processing and transportation is tasked with the day-to-day responsibilities for the following:

Implementing the requirements of this document.

Ensuring that radioactive waste is characterized and classified in accordance with 1 OCFR Part 61.55 and Part 61.56.

Ensuring that radioactive waste is characterized and classified in accordance with volume reduction facility and disposal site licensesand other requirements.

Designating other approved procedures (if required) to be implemented in the packaging of any specific batch of waste.

Providing a designated regulatory point of contact between the Plant and the NRC, volume reduction facility or disposal site.

Maintaining records of on-site and off-site waste stream sample analysis and Plant evaluations.

Suspending shipments of defectively processed or defectively packaged radioactive wastes from the site when the provisions of this process control program are not satisfied.

5.0 DETAILS An isotopic analysis SHALL be performed on every batch for each waste stream so that the waste can be classified in accordance with 10CFR61. The isotopic and curie content of each shipping container SHALL be determined in accordance with 49CFR packaging requirements. The total activity in the container may be determined by either isotopic analysis or by dose-rate-to-curie conversion.

5.1.

Precautions and Limitations

[1]

Precautions (a)

Radioactive materials SHALL be handled in accordance with applicable radiation protection procedures.

(b)

All radioactive waste must be processed or packaged to meet the minimum requirements listed in 10CFR Part 61.56 (a) (1) through (8).

5. 1[1], continued (c)

If the provisions of the Process Control Program are not satisfied, suspend shipment of the defectively processed or defectively packaged waste from the site. Shipment may be accomplished when the waste is processed / packaged in accordance with the Process Control Program.

(d)

The generation of combustible gases is dependent on the waste form, radioactive concentration and accumulated dose in the waste. Changes to organic inputs (e.g. oil) to waste stream may change biogas generation rates.

[2]

Limitations (a)

Only qualified personnel will characterize OFR package radioactive waste OR radioactive materials for transportation or disposal.

(b)

All site personnel that have any involvement with radioactive waste management computer software SHALL be familiar with its functions, operation and maintenance.

5.2.

Waste Management Practices

[1]

Waste processing methods include the following:

(a)

Present and planned practice is NOT to solidify or encapsulate any waste streams.

(b)

Waste being shipped directly for burial in a HIC (High Integrity Container) is dewatered to less than 1 percent by volume prior to shipment.

(c)

Waste being shipped directly for burial in a container other than a HIC is dewatered to less than 0.5 percent by volume prior to shipment.

(d)

IF solidification is required in the future, THEN at least one representative test specimen from at least every 10th batch of each type of radioactive waste will be checked to verify solidification.

(1)

WF any specimen fails to verify solidification, THEN the solidification of the batch under test SHALL be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined, and a subsequent test verifies solidification. If alternative parameters are determined, the subsequent tests shall be verified using the alternative parameters determined.

5.2[1](d), continued (2)

IF the initial test specimen from a batch of waste fails to verify solidification, THEN provide for the collection and testing of representative test specimens from each consecutive batch of the same type of waste until at least 3 consecutive initial test specimens demonstrates solidification. The process SHALL be modified as required to assure solidification of subsequent batches of waste.

[2]

Operation and maintenance of dewatering systems and equipment include the following:

(a)

Present and planned practice is to utilize plant personnel supplemented by vendor personnel or contracted vendor personnel, to operate AND maintain dewatering systems and equipment (as needed to meet disposal site requirements).

(b)

All disposal liners are manufactured by and purchased from QA-approved vendors.

[3]

ALARA considerations are addressed in all phases of the processes involving handling, packaging AND transfer of any type OR form of radioactive waste (dewatered or dry).

Resin, charcoal media, spent filter cartridges AND sludges are typically processed within shields. Sluiceable demineralizers are shielded when in service. Radiation exposure and other health physics requirements are controlled by the issuance of a Radiation Work Permit (RWP) for each task.

5.3.

Waste Stream Sampling Methods and Frequency

[1]

The following general requirements apply to Plant waste stream sampling:

(a)

Treat each waste stream separately for classification purposes.

(b)

Ensure samples are representative of or can be correlated to the final waste form.

(c)

Determine the density for each new waste stream initially or as needed (not applicable for DAW and filters).

(d)

Perform an in-house analysis for gamma-emitting radionuclides for each sample sent to an independent laboratory.

(e)

Periodically perform in-house analysis for gamma emitting radionuclides for comparison to the current data base values for gamma emitters. (The current database is usually based on the most recent independent laboratory results.)

(f)

Resolve any discrepancies between in-house results AND the independent laboratory results for the same or replicate sample as soon as possible.

(g)

Maintain records of on-site and off-site waste stream sample analysis and evaluations.

5.3, continued

[2]

When required, waste stream samples should be analyzed, re-evaluated and if necessary, shipped to a vendor laboratory for additional analysis. The same is true when there is a reason to believe that an equipment or process change has significantly altered the previously determined scaling factors by a factor of 10.

Specific examples include but are not limited to:

Changes in oxidation reduction methods such as zinc, injection, hydrogen water chemistry, Changes in purification methods including media specialization, media distribution, ion/cation ratios, Changes in fuel performance criteria including fuel leaks Other changes in reactor coolant chemistry.

Sustained, unexplained, changes in the routinely monitored Beta/Alpha ratios, as determined by Radiation Protection, When there is an extended reactor shutdown (> 90 days).

0 When there are changes to liquid waste processing, such as bypassing filters, utilizing filters or a change in ion exchange media.

0 When there are changes to the waste stream that could change the biogas generation rate.

[3]

The following requirements apply to infrequent or abnormal waste types:

(a)

Infrequent OR abnormal waste types that may be generated must be evaluated on a case-by-case basis.

(b)

The RP Department Supervisor / Specialist responsible for processing AND shipping will determine if the waste can be correlated to an existing waste stream.

(c)

IF the radioactive waste cannot be correlated to an existing waste stream, THEN the RP Department Supervisor / Specialist responsible for processing and shipping SHALL determine specific off-site sampling and analysis requirements necessary to properly classify the material.

[4]

Specific sampling methods and data evaluation criteria are detailed in EN-RW-104 for specific waste streams.

5.4.

Waste Classification

[1]

General requirements for scaling factors include the following:

(a)

The Plant has established an inferential measurement program whereby concentrations of radionuclides which cannot be readily measured are estimated through ratio-ing with radionuclides which can be readily measured.

(b)

Scaling factor relationships are developed on a waste stream-specific basis.

These relationships are periodically revised to reflect current independent lab data from direct measurement of samples. The scaling factor relationships currently used by the sites are as follows:

Hard to detect ACTIVATION product radionuclides and C-14 are estimated by using scaling factors with measured Co-60 activities.

Hard to detect FISSION product radionuclides and H-3, Tc-99 and 1-129 are estimated by using scaling factors with measured Cs-1 37 activities.

Hard to detect TRANSURANIC radionuclides are estimated by using scaling factors with measured Ce-1 44 activities. Where Ce-1 44 cannot be readily measured, transuranics are estimated by using scaling factors with measured Cs-1 37 activities. Second order scaling of transuranics is acceptable when Cs-137 and Ce-144 are not readily measurable.

[2]

General requirements for the determination of total activity and radionuclide concentrations include the following:

(a)

The activity for the waste streams is estimated by using either Gross Radioactivity Measurement OR Direct Measurement of Radionuclides. Current specific practices are as follows:

0 DAW - Gross radioactivity measurement in conjunction with the RADMAN computer codes, other approved computer codes or hand calculation.

Filters - Gross radioactivity measurement in conjunction with the FILTRK computer code, other approved computer codes or hand calculation.

All Other Waste Streams - Direct measurement of radionuclides in conjunction with the RADMAN computer codes, other approved computer codes or hand calculation.

(b)

Determination of the NRC waste classification is performed by comparing the measured or calculated concentrations of significant radionuclides in the final waste form to those listed in 1 OCFR Part 61.55.

5.5.

Quality Control

[1]

The RADMAN computer code provides a mechanism to assist the Plant in conducting a quality control program in accordance with the waste classification requirements listed in 1 OCFR Part 61.55. All waste stream sample data changes are written to a computer data file for future review and reference.

[2]

Audits and Management Review includes the following:

(a)

Appendix G to 1 OCFR20 requires conduct of a QC program which must include management review of audits.

(b)

Management audits of the Plant Sampling and Classification Program SHALL be periodically performed to verify the adequacy of maintenance sampling and analysis.

(c)

Audits and assessments are performed and documented by any of the following:

Radiation Protection Department Quality Assurance Department Qualified Vendors (d)

Certain elements of the Entergy Quality Assurance Program Manual are applied to the Process Control Program. [QAPM, Section A.1.c]

5.6.

Dewaterinc Operations

[1]

Processing requirements during dewatering operations include the following:

(a)

All dewatering operations are performed per approved Plant or vendor operating procedures and instructions.

(b)

Dewatering limitations and capabilities are verified by vendor Topical Reports or Operating and Testing Procedures.

[2]

Dewatered resin activity limitations include the following:

(a)

Dewatered resins will not be shipped off-site that have activities which will produce greater than 1.01E+8 rads total accumulated dose over 300 years. This is usually verified by comparing the container specific activity at the time of shipment to the following concentration limits for radionuclides with a half-life greater than five years:

10 Ci (0.37 TBq) per cubic foot.

350 uCi (12.95 MBq) per cubic centimeter

5.7.

Waste Packaging Waste in final form will be packaged in accordance with Title 10 and Title 49 of the Code of federal regulations and in accordance with current burial site criteria as is detailed in EN-RW-102.

5.8.

Administrative Controls

[1]

Information on solid radioactive waste shipped off-site is reported annually to the Nuclear Regulatory Commission in the Annual Radioactive Effluent Release Report as specified by the Offsite Dose Calculation Manual (ODCM) or Technical Specification.

[ANO1 Technical Specifications - 5.6.3] [ANO2 Technical Specifications - 6.6.3]

[WF3 Technical Specifications - 6.9.18] [GGNS ODCM - 5.6.3.c] [JAF Technical Specifications - 5.6.3] [PLP ODCM, Appendix A - IV. A].

[2]

All changes to the PCP SHALL be documented. All records of reviews performed SHALL be retained as required by the Quality Assurance Program. The documentation of the changes SHALL [GGNS UFSAR, Chapter 16B.1 /TRM -

7.6.3.8 paragraph 2]:

(a)

Contain sufficient information to support the change with appropriate analyses or evaluations justifying the change.

(b)

Include a determination that the change will maintain the overall conformance of the solidified waste product (if applicable) to existing requirements of Federal, State or other applicable regulations.

[31 All changes in the Process Control Program and supporting documentation are included in each site's next Annual Radiological Effluent Release Report to the Nuclear Regulatory Commission.

[ANO ODCM - L3.2.1.C] [VTY TRM 6.12]

[4]

The changes to EN-RW-1 05 SHALL become effective upon review and acceptance by the site's General Plant Manager except as listed below:

(a)

For Grand Gulf Nuclear Station, the changes to RW-105.SHALL be accomplished as specified in Grand Gulf Nuclear Station Technical Requirements Manual (TRM) Section 7.6.3.8. The changes SHALL become effective upon review and acceptance by the On-site Safety Review Committee (OSRC) and the approval of the GGNS Plant General Manager. [GGNS UFSAR, Chapter 16B.1 / TRM - 7.6.3.8 paragraph 2]

5.8[4], continued (b)

For River Bend Nuclear Station, the procedure approval along with changes to RW-1 05 SHALL be accomplished per the River Bend Nuclear Station Technical Requirements, Section 5.5.14.1. The changes SHALL become effective upon review and acceptance by approval from the River Bend Nuclear Station Plant Manager or Radiation Protection Manager. [RBS Technical Requirements -

5.5.14.1,5.5.14.2 & 5.8.2]

(c)

For Waterford 3, the procedure approval along with changes to RW-105 SHALL be accomplished per Waterford 3 Technical Specifications 6.13.2. The changes SHALL become effective upon review and acceptance by the Waterford 3 General Plant Manager. [WF3 Technical Specifications - 6.13.2.b]

(d)

For James A. FitzPatrick Nuclear Station, the procedure approval along with changes to EN-RW-1 05 SHALL be accomplished per the James A. FitzPatrick Station Technical Specifications, Section 5.6.3. The changes SHALL become effective upon review and acceptance through approval from the James A.

FitzPatrick Nuclear Station On-Site Safety Review Committee. [JAF UFSAR, Chapter 11.3.5]

(e)

For Vermont Yankee, Changes to the Process Control Program SHALL become effective after review and acceptance by the (OSRC) On-Site Safety Review Committee and the Site VP.

(f)

For IPEC, Changes to the Process Control Program SHALL become effective after final review and acceptance by the On-Site Safety Review Committee (OSRC).

5.9.

Vendor Requirements

[1]

Vendors performing radwaste services under 10CFR61 and 10CFR71 requirements will be on the Entergy Qualified Supplier's List (QSL). [QAPM, Section A.1.c]

[2]

Vendors performing radwaste services on-site are to comply with the following:

(a)

Dewatering and solidification services SHALL have a NRC-approved Topical Report or other form of certification documenting NRC approval of the processes and associated equipment/containers.

(b)

All vendor procedures utilized for performing on-site radwaste processing services (to assure compliance with 10 CFR Parts 20, 61 and 71, State Regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste) will be reviewed per the requirements of EN-LI-100, technically by the applicable site's Radiation Protection organization and only be accepted per the approvals specified in Section 5.8 [4].

5.9[2], continued (c)

All changes to vendor procedures for ongoing on-site radwaste services will be reviewed technically by the site's Radiation Protection organization and screened per the requirements of EN-LI-100. Significant procedural changes will require the approvals specified in Section 5.8 [4]. During screening, the level of significance for procedural changes on equipment and process parameters may warrant the full 10CFR50.59 documentation and approval process.

(d)

Plant management SHALL review vendor(s) topical reports and test procedures per applicable requirements in Section 5.8.

NOTE The PCP does not have to include the vendor's Topical Report if it has NRC approval, or has been previously submitted to the NRC.

(e)

Plant management review will assure that the vendor's operations and requirements are compatible with the responsibilities and operation of the Plant.

(f)

Training requirements and records listed in Section 5.10 also apply to contracted vendors.

5.10. Miscellaneous

[1]

Special tools and equipment (a)

Frequency of Use and Descriptions Required tools and equipment will vary depending on the specific process and waste container that is used. The various tools and equipment which may be required are detailed in specific procedures developed to govern activities described in this document.

[2]

Pre-requisites (a)

Maintenance of Regulatory Material Ensure that a current set of DOT, NRC, EPA and applicable State regulations, vendor processing facility and disposal site regulations and requirements are maintained at the site and are readily available for reference. The use of web based regulations is acceptable.

5.10[2], continued (b)

Representative Radionuclide Sample Data Ensure that representative radionuclide sample data is on file for each active waste stream. Unless operation conditions or changes in processing methods require increased sample frequency, data is considered to be current if it meets the requirements of EN-RW-104.

(c)

Initial and Cyclic Training A training program SHALL be developed, implemented and maintained for all personnel involved in processing, packaging, handling and transportation of radioactive waste to ensure radwaste operations are performed within the requirements of NRC Information Bulletin 79-19 and 49CFR Part 172.700

.through Part 172.704.

" Training requirements and documentation also apply to contracted on-site vendors.

NOTE Cyclic training is defined as within three years for DOT, and two years for IATA (d)

Specific employee training is required for each person who performs the following job functions [172.702(b)].

Classifies hazardous materials.

Packages hazardous materials.

Fills, loads and/or closes packages.

Marks and labels packages containing hazardous materials.

Prepares shipping papers for hazardous materials.

Offers or accepts hazardous materials for transportation.

Handles hazardous materials.

Marks or placards transport vehicles.

Operates transport vehicles.

Works in a transportation facility and performs functions in proximity to hazardous materials which are to be transported.

0 Inspects or tests packages.

5. 10[2] continued (e)

Cyclic training is defined as within three years for DOT & within two years for IATA.

Copies of training records are required for as long as a person is employed and 90 days thereafter. The records should include, as a minimum, the following:

Trainee's name and signature Training dates Training material or source reference Trainer's information 6.0 INTERFACES

[1]

EN-LI-100, "Process Applicability Determination"

[2]

EN-RW-104, "Scaling Factors"

[3]

EN-QV-104, "Entergy Quality Assurance Program Manual Control" 7.0 RECORDS

[1]

Documentation of pertinent data required to classify waste and verify solidification will be maintained on each batch of processed waste as required by approved procedures.

[2]

Documentation will also be maintained to ensure that containers, shipping casks, and methods of packaging wastes meet applicable Federal regulations and disposal site criteria. The records of reviews performed and documents associated with these reviews will be maintained as QA records.

I 8.0 SITE SPECIFIC COMMITMENTS Document Document NMM Procedure Site Applicability Section Section ANO ODCM L3.2.1.C 5.8 [3]

ANO ANO1 Technical Specifications 5.6.3 5.8 [1]

ANO ANO2 Technical Specifications 6.6.3 5.8 [1]

ANO RBS Technical Requirements 5.5.14 RBS RBS Technical Requirements 5.5.14.1 5.8 [3]

RBS 5.8 [4] (b)

RBS Technical Requirements 5.5.14.2 5.8 [4] (b)

RBS RBS Technical Requirements 5.8.2 5.8 [4] (b)

RBS WF3 Technical Specifications 1.22 WF3 WF3 Technical Specifications 6.9.18 5.8 [1]

WF3 WF3 Technical Specifications 6.13.2.b 5.8 [4] (c)

WF3 JAF ODCM 6.2.1 5.8 [1]

JAF JAF Technical Specifications 5.6.3 5.8 [1], 5.8 [4]

JAF JAF FSAR Chapters 7 and 5.8 [41 JAF 11 11759 - NRC IN 79-19 All WF3 GGNS UFSAR, Chapter 16B.1 /

7.6.3.8 1.0 GGNS TRM paragraph 1 GGNS ODCM 5.6.3.c 5.8 [1]

GGNS GGNS FSAR 11.4.5.S2 5.9 [2](a)

GGNS GGNS FSAR 11.4.2.3AS7 5.9 [2](a)

GGNS IPN-99-079 All IPEC Appendix B Technical Section 4.5, Specifications RECS ODCM IPEC Part 1 PLP Technical Specifications 5.5.15 5.8 [4]

PLP PLP ODCM Appendix A -

5.8 [1]

PLP IV. A NRC Letter 1.98.091 All PNPS NRC Letter 1.88.078 All PNPS VY Technical Specifications 6.4.H VY VY ODCM 10.1 5.8 [1]

VY VYTRM 6.12 5.8(3)

VY QAPM Section A.1.c All

Covered by directive as a whole or by various paragraphs of the directive.

9.0 ATTACHMENTS None

RBG-47237, Submittal of Radioactive Effluent Release Report for 2011

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