Text

Annual Radioactive Effluent Release Report for 2014
	ML15126A098
Person / Time
Site:	River Bend
Issue date:	05/01/2015
From:	Clark J; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RBF1-15-0066, RBG-47562
	Download: ML15126A098 (114)
	v • d • e

Entergy Operations, Inc.

River Bend Station Enterga 5485 U.S. Highway 61 N St. Francisville, LA 70775 Tel 225-381-4177 Joseph A. Clark Manager-Regulatory Assurance May 1, 2015 U. S. Nuclear Regulatory Commission Document Control Desk 11555 Rockville Pike Rockville, MD 20852-2738 Washington, DC 20555 RBG-47562 RBF1-15-0066

Subject:

Annual Radioactive Effluent Release Report for 2014 River Bend Station - Unit 1 License No. NPF-47 Docket No. 50-458

Dear Sir or Madam,

Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for 2014 for the period January 1, 2014 through December 31, 2014. This report is submitted in accordance with the RBS Technical Specifications, Section 5.6.2 Should you have any questions regarding the enclosed, please contact Mr. Joseph Clark, at (225) 381-4177.

Sincerely, av JAC/tjb enclosure

Annual Radioactive Effluent Release Report for 2015 RBG-47562 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.

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

PO Box 1050 St. Francisville, LA 70775 Records Clerk Public Utility Commission of Texas 1701 N. Congress Ave.

Austin Texas 78711-13326 Mr. Alan Wang, Project Manager (w/o)

U.S. Nuclear Regulatory Commission MS O-8B1 11555 Rockville Pike Rockville, MD 20852-2738

River Bend Station 2014 Regulatory Guide 1.21 Report Page I of 91 RIVER BEND STATION 2014 ANNUAL EFFLUENT RELEASE REPORT REVIEWED BY: ~fl4&~Si-~

William H. Spell / Senior HP/Chem Specialist REVIEWED BY:

Robert W. / Manager - Chemistry (acting)

REVIEWED BY: K,< A Z...

Rick A. Leasure / Radiation Protection Manager (acting)

APPROVED BY: C*Q Carl E.'ch, Jr 7 eral Manager Plant Operations This report compiled by James F. Key, Jr. of Key Solutions, Inc.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 2 of 91 Table of Contents I. SUPPLEMENTAL INFORMATION .............................................................................. 4

11. GASEOUS EFFLUENT

SUMMARY

INFORMATION ............................................ 12 III. LIQUID EFFLUENT

SUMMARY

INFORMATION ................................................. 12 IV. SO LID W ASTE ................................................................................................................... 12 V. RADIOLOGICAL IMPACT ON MAN (40CFR190) ................................................... 13 VI. METEOROLOGICAL DATA ....................................................................................... 14 VII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION O PERA BILITY ................................................................................................................... 14 VIII. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION O PERA BILITY ................................................................................................................... 14 IX. LIQUID HOLD UP TANKS ............................................................................................ 14 X. RADIOLOGICAL ENVIRONMENTAL MONITORING .......................................... 15 XI. LAND USE CENSUS ....................................................................................................... 15 XII. OFFSITE DOSE CALCULATION MANUAL (ODCM) ............................................ 15 XIII. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATM ENT SYSTEM S .............................................................................................. 15 XIV. PROCESS CONTROL PROGRAM (PCP)................................................................... 17 XV. INDUSTRY GROUND WATER PROTECTION INITIATIVE (GPI) - FINAL GUIDANCE DOCUMENT (NEI 07-07) OBJECTIVE ANNUAL REPORTING ......... 17 TABLE IA GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ............................. 19 TABLE 1B GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE ...... 20 TABLE IC GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE ..................... 21 TABLE ID GASEOUS EFFLUENTS - MIXED MODE RELEASES - CONTINUOUS MODE .... 22 TABLE IF RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM .... 24 TABLE IG GASEOUS ANNUAL DOSE

SUMMARY

REPORT ................................................... 25 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES ................................. 26 TABLE2B LIQUID EFFLUENTS - CONTINUOUS MODE ........................................................ 27 TABLE 2C LIQUID EFFLUENTS - BATCH MODE ..................................................................... 28 TABLE 2D EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE ..................................... 30 TABLE2E RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM ......... 31 TABLE 2F LIQUID ANNUAL DOSE

SUMMARY

REPORT ....................................................... 32 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2014 YEAR SOLID WASTE AND IRRADIATED FUEL SHIPMENTS ..................................................... 33

River Bend Station 2014 Regulatory Guide 1.21 Report Page 3 of 91 TABLE 4 DOSES TO A MEMBER OF THE PUBLIC INSIDE SITE BOUNDARY ASSUMPTIONS/PARAMETERS ................................................................................. 36 TABLE 6 2014 YEAR METEOROLOGICAL DATA - JOINT FREQUENCY TABLES ............ 38 TABLE 7 ATMOSPHERIC DISPERSION AND DEPOSITION RATES FOR THE MAXIMUM INDIVIDUAL DOSE CALCULATIONS ..................................................................... 55 TABLE 8 GROUNDWATER MONITORING WELL SAMPLE RESULTS ............................. 56 ATTACHMENT 1 - PROCESS APPLICABILITY PROGRAM ....................................................... 91

River Bend Station 2014 Regulatory Guide 1.21 Report Page 4 of 91 This is the annual Radioactive Effluent Release Report for the period of January 1, 2014, through December 31, 2014. This report is submitted in accordance with Technical Specification 5.6.3 of Appendix A to River Bend Station (RBS) License Number NPF-47.

I. SUPPLEMENTAL INFORMATION A. Regulatory Limits

1. 10CFR50, Appendix I Limits a) Fission and Activation Gases In accordance with Technical Requirement (TR) 3.11.2.2, the air dose due to noble gases released in gaseous effluent to areas at and beyond the SITE BOUNDARY shall be limited to:

DGamma-Air = gamma air dose from radioactive noble gases in millirad (mrad) n 3.17E-8 I Mi (X/Q) Q0 < 5 mrads/qtr i=1 < 10 mrads/yr DBeta-Air = beta air dose from radioactive noble gases in millirad (mrad) n

= 3.17E-8 I Ni (X/Q) Qj < 10 mrads/qtr i=1 < 20 mrads/yr b) Radioiodines (1-131 & 1-133) and Particulate In accordance with Technical Requirement 3.11.2.3, the dose to a MEMBER OF THE PUBLIC from radioiodines (1-131 and 1-133), tritium (H-3) and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluent releases to areas at and beyond the SITE BOUNDARY shall be limited to:

DI&8DPt = Dose in mrem to the organ (-r) for the age group of interest from radioiodine (1-131, 1-133, tritium, and 8 day particulate via the pathway of interest.)

River Bend Station 2014 Regulatory Guide 1.21 Report Page 5 of 91 n

= 3.17E-08 (Fo) Y- PiT (X/Q) Qi and i=1 n

= 3.17E-08 (Fo) X Ri, (D/Q) Qi and i=1 n

D, = X DI&sDP- < 7.5 mrem/qtr z=1 r 15 mrem/yr (above terms defined in the RBS ODCM) c) Liquid Effluent In accordance with Technical Requirement 3.11.1.2, the dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluent released to UNRESTRICTED AREAS shall be limited to:

Di = A., At Oi (DF) D, and n

DTOTALT X Di, i=1 DTOTALT = Total dose commitment to the organ (-u) due to all releases during the desired time interval in mrem and DTOTAL Total Body < 1.5 mrem/qtr

< 3 mrem/yr DTOTAL Any Organ < 5 mrem/qtr

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

River Bend Station 2014 Regulatory Guide 1.21 Report Page 6 of 91

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:

DR-m= Dose rate to the total body in mrem/yr n

= I Ki (X/Q) QO <500 mrem/yr and i=1 DRsK]N= Dose rate to the skin in mrem/yr n

I L, + 1.lM, (X/Q) Q <*3000 mrem/yr i=1 (above terms defined in RBS ODCM)

b. Technical Requirement 3.11.2.1 - Radioiodine (1-131 & I-133) and Particulate In accordance with Technical Requirement 3.11.2.1, the dose rate due to radioiodines, tritium, and all radionuclides in particulate form with half-lives greater than 8 days released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to less than or equal to 1500 mrem/yr to any organ:

River Bend Station 2014 Regulatory Guide 1.21 Report Page 7 of 91 DRI&8DPt = Dose rate to the organ -ufor the age pathway group of interest from Radioiodines (1-131 & 1-133), tritium, and 8 day particulate via the inhalation pathway in mrem/yr.

n DRI&SDpN = X 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.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 8 of 91 B. Effluent Concentration Limits

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

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

River Bend Station 2014 Regulatory Guide 1.21 Report Page 9 of 91

b. Particulate and Radioiodine (1-131 & 1-133)

Particulates, Iodine-131 and Iodine-133 are continuously sampled from the three release points using a particulate filter and charcoal cartridge in line with a sample pump (stack monitor pump). These filters and charcoal cartridges are removed and analyzed in accordance with the frequencies specified in Table 1F. Analysis is performed to identify and quantify radionuclides using high purity germanium detectors coupled to computerized pulse height analyzers. Given the nuclide specific activity concentrations, process flow rate, and duration of the sample, the nuclide specific activity released to the environment can be obtained. Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Strontium-89 and Strontium-90 (Sr-89 and Sr-90) are quantitatively analyzed by counting by gas flow proportional 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 No Nickel-63 was quantified in 2014.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 10 of 91

2. Liquid Effluent Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 2E. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high purity germanium detector coupled to a computerized pulse height analyzer. Tritium concentration is determined using a liquid scintillation counter.

Strontium-89 and Strontium-90 are quantitatively analyzed by scintillation techniques (Cherenkov counting). Iron-55 is counted with a liquid scintillation counter after digestion of the iron. Gross alpha analysis is performed using a zinc sulfide scintillation counter. The activity of each nuclide released to the environment is determined from the nuclide specific concentration and total tank volume released.

D. Batch Releases

1. Liquid Effluents Batch releases and receiving stream flow from River Bend Station during the reporting period of January 1, 2014, through December 31, 2014 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, 2014, through December 31, 2014.

E. Abnormal Releases There were no liquid abnormal releases in 2014. The releases reported in the groundwater monitoring section are not expected to be detectable outside the site boundary.

There was one potential abnormal gaseous release.

River Bend Station 2014 Regulatory Guide 1.21 Report Page I11of 91 During rounds on 5/11/2014, an operator determined that the direction of airflow between the Turbine Building and C-Tunnel was from the Turbine Building into C-Tunnel, and the expected direction of airflow should be from C-Tunnel into the Turbine Building. The investigation revealed there was an inlet screen associated with the Normal Switchgear ventilation louver that was clogged contributing to the incorrect flow. Maintenance was performed on filters and louvers to correct the situation. In addition, future cleaning of the filters and louvers were combined into one preventative maintenance task.

The significance of air flowing from the Turbine Building into the C-Tunnel is the potential of an unmonitored release pathway 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. Nevertheless a conservative estimate of the activity released and the potential worst case dose to a member of the public demonstrated that if the activity in C-Tunnel had been released from the Normal Switchgear Building for an entire year, any dose to the public would be a small fraction of the typical annual effluent dose. The estimated activity and the potential dose impact are reported in the Table 1 series.

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%

River Bend Station 2014 Regulatory Guide 1.21 Report Page 12 of 91 lodines : + 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= V((E1 )L + (E2)L +

where:

ET = total error El, E2 ...En = individual errors due to sample collection, laboratory analysis, sample flow, process flow, monitor accuracy, etc.

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 iF. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

III. LIQUID EFFLUENT

SUMMARY

INFORMATION Refer to the Table 2 series for the summation of liquid releases. It should be noted that an entry of "O.OOE+00" Ci or uCi/mI 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.

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

River Bend Station 2014 Regulatory Guide 1.21 Report Page 13 of 91 V. 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, NUREG-0016, and the methodology in Regulatory Guide 1.109. The C-14 source term of 11 curies was taken from the site calculation PR(C)-359-3A, Gaseous Releases per NUREG-0016 Revision 1.

Carbon-14 does not have dose factors associated with standing on contaminated ground; therefore, no ground plane dose was calculated. There is no milk pathway within five miles of River Bend Station so this pathway is not evaluated. RBS does not take credit for decay in the X/Q. This calculation assumes the inhalation, meat and vegetation pathways are at the site boundary in the sector with the highest X/Q.

The dose from liquid effluents is not calculated as the dose contribution from C-14 is considered to be insignificant as indicated in Regulatory Guide 1.21, Revision 2.

According to EPRI 1021106, Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents, 95% of the carbon released is in the form of carbon dioxide and this contributes the highest dose to man. The ingestion pathway, specifically vegetation, is the most likely route of intake for man. An assumption has been made for gaseous releases that plants obtain all of their C-14 from carbon dioxide.

Dose not including C-14:

Organ mrem Total Body 4.21E-02 Skin 2.60E-02 Thyroid 5.18E-02 Other Organ 4.22E-02 Bounding Dose from C-14 only:

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

River Bend Station 2014 Regulatory Guide 1.21 Report Page 14 of 91 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 34 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.

VI. METEOROLOGICAL DATA See Tables 6 and 7 for the cumulative joint frequency distributions and annual average data for continuous releases. The meteorological recovery for 2014 was 98.5 %.

VII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY The minimum number of channels required to be OPERABLE as described in Table 3.3.11.2-1 of Technical Requirement 3.3.11.2 were, if inoperable at any time in the period January 1, 2014, through December 31, 2014, restored to operable status within the required time.

VIII. 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, 2014, through December 31, 2014, restored to operable status within the required time.

IX. 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, 2014, through December 31, 2014 was less than or equal to the 10 curie limit as required by Technical Specification 5.5.8.b.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 15 of 91 X. RADIOLOGICAL ENVIRONMENTAL MONITORING There were no changes to the Radiological Environmental Monitoring Program during the reporting period January 1, 2014, through December 31, 2014.

XI. LAND USE CENSUS The Land Use Census for 2014 was conducted in accordance with procedure ESP-8-051, as required by the Technical Requirements Manual (TRM) (TR 3.12.2). The results of the Land Use Census will be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2. The attached Table 1 summarizes the results.

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

The milk animal census identified no milk animals within 8 km (5 miles) of River Bend site. This information was verified by the County Agents from West Feliciana, East Feliciana and Pointe Coupee parishes.

No resident census changes were noted.

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

The County Agents confirmed that there was no commercial harvesting of crawfish within the five-mile radius downstream of RBS. RBS conservatively uses the invertebrate pathway although not required by NUREG-0133 liquid dose factor methodology for fresh water nuclear power plants.

XII. OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the ODCM in 2014.

XIII. 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 2014 involving the subject systems (i.e. changes classified as evaluations or nuclear

River Bend Station 2014 Regulatory Guide 1.21 Report Page 16 of 91 changes). These design changes were then reviewed to determine if there have been any major changes to the subject systems. The review was based on a major change being defined as a modification which affected the method of processing or the effluent from the system. Also, to be a "major change" the change must have affected the Updated Safety Analysis Report (USAR).

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

EC-50174 TMOD ECN Rev. 0 - This was a change to reflect a new Engineering TMOD owner for TMOD EC-35300. TMOD EC-35300 was documented in the 2012 Annual Effluent Report input and determined that this change does not constitute a major change to either the liquid, solid or gaseous radwaste treatment systems.

The following TMOD ECNs were processed to provide changes to TMOD EC-41004. TMOD EC-41004 was documented in the 2013 Annual Effluent Report input and determined that this change does not constitute and major change to either the liquid, solid or gaseous radwaste treatment systems.

EC-54762 TMOD ECN Rev. 0 - This was a change to provide additional details regarding freeze protection methods for the remediation skid.

EC-50608 TMOD ECN Rev. 0 - This was a change to revise preventative maintenance statement in TMOD EC-41004.

EC-50177 TMOD ECN Rev. 0 - This was a change to provide a new Engineering TMOD owner for TMOD EC-41004.

EC-47305 TMOD ECN Rev. 0 - This was a change allowing a deviation from the provided requirements for hose installation in TMOD EC-45515. TMOD EC-45515 was documented in the 2013 Annual Effluent Report input and determined that this change does not constitute and major change to either the liquid, solid or gaseous radwaste treatment systems.

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 2014 Regulatory Guide 1.21 Report Page 17 of 91 XIV. PROCESS CONTROL PROGRAM (PCP)

There were two editorial changes to the PCP in 2014. A copy of that revision is attached to this report.

XV. INDUSTRY GROUND WATER PROTECTION INITIATIVE (GPI) - FINAL GUIDANCE DOCUMENT (NEI 07-07) OBJECTIVE ANNUAL REPORTING Ground water samples were taken in support of the GPI. These samples are not part of the Radiological Environmental Monitoring Program. The sample results for 2014 are located in Table 8.

River Bend Station made two NEI 07-07 voluntary notifications in 2014, which are being included here per NEI 07-07 Objective 2.4.c. The first notification occurred on January 8, 2014, when the bonnet on a temporary blow down line gate valve (RWS-0339-V8) cracked due to a few days of sub-freezing temperatures. This caused a circulating water/liquid radwaste discharge water mixture to leak onto the ground. A radioactive waste discharge was not in progress; however, due to the temporary piping configuration, a dead leg of radioactive water is sometimes present in the piping connected to the valve that ruptured. The exact volume released is unknown because the exact time the valve body failed is unknown. The volume released estimated to be between 100 and 1200 gallons and is based on times that workers were in the area and the observed leakage rate.

Actions were taken at the time of the leak to contain the water, and dams were successfully installed to prevent any water from reaching any storm drains. The spill was confined to the Owner Controlled Area. The water analysis indicated no gamma activity, and the maximum tritium sample value was 4.58E-06 uCi/ml.

Securing the Circulating Water System blow down stopped the leak and repairs weremade.

The second notification occurred on May 12, 2014 because of contaminated water leaking into the C-Tunnel. An Operator discovered a small amount of water (- 2 drips/minute) leaking into the C-Tunnel on the 67-foot elevation through a service water primary (SWP) piping penetration. The SWP is normally a radiologically clean system, and the water was sampled to determine if the service water pipe was leaking. The results indicated that the leak did not originate from the SWP system as was suspected so an additional sample was taken for radiological purposes.

Tritium was detected in the followup sample. The highest confirmed sample for tritium was 2.82E-05 uCi/ml. Tritium was the only radioisotope detected. Follow-up sampling and leak rate determinations indicated the tritium activity and leak rates varied and seemed to be affected by rainfall. Based on this information, it is believed that the water was coming from outside the C-Tunnel.

River Rend Station 2014 Regulatory Guide 1.21 Report Page 18 of 91 The only source of radioactive material capable of giving the activity level detected is two small-bore pipes in the overhead of C-Tunnel that have been used for liquid radwaste discharges. These pipes are approximately 16 feet above the SWP piping and have been out of service since 2012. The service water pipes and the liquid radwaste pipes are all below grade once they leave the C-Tunnel. It is possible the liquid radwaste pipes developed a leak below grade outside the building, and some remaining water leaked into the soil and moved down to the SWP pipe.

The water being detected is not in the nearest aquifer beneath the site, and the activity detected is not from a groundwater monitoring well. The bottom of the SWP line is about 11 feet above the water table.

Although likely insignificant, the potential offsite impacts for both events have been reviewed. The Upland Terrace Aquifer is the closest aquifer beneath the site. The Upland Terrace Aquifer is hydrologically connected to the Mississippi River Alluvial aquifer, and then to the Mississippi River, approximately two miles west of the facility. The site conceptual hydrology model indicates a down-gradient flow generally to the southwest from the CWS-MOV104 pit and C-Tunnel to the Mississippi River. River Bend Station site does not utilize ground water for drinking water use, and the nearest known drinking water user from the Mississippi River is many miles downstream below Baton Rouge, Louisiana. The most recent information River Bend Station has is all neighbors surrounding the station use the parish water supply for their primary source of drinking water. Intakes to the parish water supply are not downgradient of River Bend Station. Our geologist estimates that the activity detected in both events are not likely to be detected if they were to infiltrate to the Upland Terrace Aquifer and migrate to the Mississippi River due to decay, dilution and dispersion. Due to the significant dilution volume of the Mississippi River, there would not be any meaningful dose impact offsite. The potential annual dose for both events to a member of the public is estimated to be less than the 10 CFR 50 Appendix I dose limits.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 19 of 91 TABLE IA GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2014 Units QTR 1 QTR 2(3) QTR 3 QTR 4 YEAR Fission and Activation Gases

1. Total Release Ci 9.76E-01 7.17E-01 9.08E-01 7.19E+00 9.79E+00

2. Avg. Release Rate uCi/sec 1.26E-01 9.12E-02 1.14E-01 9.05E-01 3.11E-01

3. % Applicable Limit % 6.91E-02 4.83E-02 6.07E*02 1.63E-02 1.71E-01 Iodine-131

1. Total Release Ci 6.64E-05 5.20E-05 6.08E-05 7.44E-05 2.54E-04

2. Avg. Release Rate uCi/sec 8.55E-06 6.61E-06 7.65E-06 9.36E-06 8.04E-06

3. % Applicable Limit % (1) 2.82E-02 2.21E-02 2.59E-02 3.17E-02 5.41E-02 Particulates Half Life >= 8 days

1. Total Release Ci 1.86E-05 2.24E-05 2.22E-05 0.OOE+00 6.32E-05

2. Avg. Release Rate uCi/sec 2.39E-06 2.84E-06 2.79E-06 0.OOE+00 2.01E-06

3. % Applicable Limit % (2) 2.39E-05 2.74E-05 2.79E-05 0.OOE+00 1.48E-02 Tritium

1. Total Release Ci 5.06E+00 7.23E+00 3.24E+00 1.02E+01 2.57E+01

2. Avg. Release Rate uCi/sec 6.51E-01 9.19E-01 4.08E-01 1.28E+00 8.15E-01

3. % Applicable Limit % (2) 6.51E+00 9.OOE+00 4.08E+00 1.28E+01 1.77E-01 Carbon-14

1. Total Release Ci 2.73E+00 2.73E+00 2.77E+00 2.77E+00 1.10E+01

2. Avg. Release Rate uCi/sec 3.50E-01 3.49E-01 3.48E-01 3.48E-01 3.49E-01

3. % Applicable Limit % (2) 1.56E+01 1.56E+01 1.58E+01 1.58E+01 3.13E+01

1) Either the gamma air dose limit of 5 mrads/qtr or beta air dose limit of 10 mrads/qtr (T.R.

3.11.2.2.a), which ever is most limiting.

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

3) Includes conservative estimate of abnormal release activity as discussed in Section I Part E of this report.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 20 of 91 TABLE 1B GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2014 Units QTR 1 QTR 2(l) QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 XE-133M Ci 0. 00E+00 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 XE-135 Ci 3. 31E-01 2. 31E-01 2. 90E-01 6.82E-01 1. 53E+00 XE-135M Ci 5. 79E-01 4. 03E-01 5. 07E-01 1. 19E+00 2. 68E+00 Totals for Period... Ci 9.09E-01 6.34E-01 7.96E-01 1.87E+00 4.21E+00 fodines 1-131 Ci 0. OOE+00 1.25E-06 0. OOE+00 0. OOE+00 1.25E-06 1-133 Ci 0. 00E+00 1. 39E-05 0. OOE+00 0. OOE+00 1. 39E-05 Totals for Period... Ci 0. OOE+00 1. 42E-05 0. OOE+00 0. OOE+00 1. 42E-05 Particulates Half Life >= 8 day*

CE-141 Ci 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CO-57 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0 OOE+00 CO-58 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CO-60 Ci 3. 33E-06 1. 85E-07 0. OOE+00 0. OOE+00 3. 52E-06 CR-51 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CS-137 Ci 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 FE-59 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 MN-54 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 NB-95 Ci 0 OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 NI-63 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 RU-103 Ci 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 RU-106 Ci 0. 00E+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 SR-89 Ci 0. 00E+00 8. 09E-07 0. OOE+00 0. OOE+00 8. 09E-07 ZN-65 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 3.33E-06 9.94E-07 0.OOE+00 0.OOE+00 4.33E-06 Tritium H-3 Ci 1. 16E+00 1.36E+00 5. 95E-01 4.81E-01 3. 60E+00 Totals for Period... Ci 2. 07E*00 1. 99E+00 1. 39E*00 2. 35E+00 7 .81E+00

1) Includes conservative estimate of abnormal release activity as discussed in Section I Part E of this report.

River Bend Station R2014Regulatory Guide 1.21 Report Page 21 of 91 I TABLE 1C GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 XE-135 Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 XE-135M Ci 0.OOE+00 0. OOE+00 0. 00E+00 0. OOE+00 0. 00E+00 Totals for Period... Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 Iodines 1-131 Ci 0.OOE+00 0 . OOE+00 0 .OOE+00 0. OOE+00 0. OOE+00 1-133 Ci 0.OOE+00 0. OOE+00 0. 00E+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 Particulates Half Life >= 8 day*

BA-140 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0 00E+00 CO-60 Ci 0. OOE+00 O.OOE+00 0. OOE+00 0. OOE+00 0. 00E+00 MN-54 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 SR-89 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 SR-90 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0 OOE+00 ZN-65 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Tritium H-3 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Totals for Period... Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Carbon-14 C-14 Ci O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

River Bend Station 2014 Regulatory Guide 1.21 Report Page 2-2 of 91 TABLE ID GASEOUS EFFLUENTS - MIXED MODE RELEASES - CONTINUOUS MODE Fission and Activation Gases AR-41 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 KR-85 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 KR-85M Ci 0. OOE+00 0. OOE+00 o.OOE+00 0.OOE+00 0. OOE+00 KR-87 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 KR-88 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.0OE+00 0. OOE+00 XE-131M Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 XE- 13'3 Ci 0. OOE+00 0. OOE+00 0. OOE+00 1. 16E+00 1. 16E+00 XE-133M Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 XE-135 Ci 6. 70E-02 8.33E-02 1. 12E-0 1 2.89E+00 3.16E+00 XE-135M Ci 0. OOE+00 O. OOE+00 o. OOE+00 1.26E+00 1.26E+00 XE-137 Ci 0. OOE+00 0 . OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 XE-138 Ci 0.0 0E+00 0 . OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 6.70E-02 8.33E-02 1.12E-01 5.32E+00 5.58E+00 Iodines 1-131 Ci 6.64E-05 5.07E-05 6. 08E-05 7.44E-05 2 .52E-04 1-132 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 1-133 Ci 5.05E-04 5. 40E-04 5. 04E-04 4.94E-04 2. 04E-03 1-135 Ci 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0. OOE+00 Totals for Period... Ci 5.71E-04 5.90E-04 5.65E-04 5.68E-04 2.29E-03 Particulates Half Life >= 8 days BA-140 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CE-139 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CE-14 1 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 CO-58 Ci 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 CO-60 Ci 9.84E-07 0. OOE+00 0.OOE+00 0. OOE+00 9. 84E-07 CR-51 Ci 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 CS-134 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 CS-137 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 FE-59 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 MN-54 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0. OOE+00.

RU-103 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 SR-89 Ci 1. 42E-05 2.14E-05 2. 22E-05 0. OOE+00 5. 76E-05 SR-90 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 ZN-65 Ci 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 Totals for Period... Ci 1.52E-05 2.14E-05 2.22E-05 0.OOE+00 5.86E-05 Tritium H-3 Ci 3.90E+00 5.87E+00 2.65E+00 9.68E+00 2.21E+01 Totals for Period... Ci 3.97E+00 5.95E+00 2.76E+00 1.50E+01 2.77E+01 Carbon-14 C-14 Ci 2.73E+00 2.73E+00 2.77E+00 2.77E+00 1.10E+01

River Bend Station 2014 Regulatory Guide 1.21 Report Page 23 of 91 TABLE 1E SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0 0 0 0 0 Total release time minutes O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Maximum release time minutes 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Average release time minutes O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Minimum release time minutes O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

River Bend Station 2014 Regulatory Guide 1.21 Report Page 24 of 91 TABLE IF RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Sampling Minimum Type of Activity Lower Limit Type Frequency Analysis Analysis of Detection Frequency (LLD) uCi/ml A. Main Plant M M Principal Gamma Exhaust Duct Grab Sample Emitters 1.OOE-04 H-3 1.OOE-06 B. Fuel Building M M Principal Gamma Ventilation Grab Sample Emitters 1.OOE-04 Exhaust Duct H-3 1.OOE-06 C. Radwaste M M Principal Gamma Building Grab Sample Emitters 1.00E-04 Ventilation Exhaust Duct D. All Release Continuous W 1-131 1.OOE-12 Types as Charcoal listed Sample in A, B, & C 1-133 1.OOE-10 above Continuous W Principal Gamma Particulate Emitters (1-131, 1.OOE-11 Sample Others)

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

River Bend Station 2014 Regulatory Guide 1.21 Report Page 25 of 9 t TABLE IG 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 1.01E-02 7.50E+00 1.34E-01 Q2 - T.Spec Any Organ (1) CHILD THYROID 1.14E-02 7.50E+00 1.52E-01 Q3 - T.Spec Any Organ CHILD THYROID 6.40E-03 7.50E+00 8.54E-02 Q4 - T.Spec Any Organ CHILD THYROID 9.03E-03 7.50E+00 1.20E-01 Yr - T.Spec Any Organ CHILD THYROID 3.69E-02 1.50E+01 2.46E-01 Carbon-14 (Bounding calculation)

Q1 - T.Spec Any Organ CHILD BONE 1.17E+00 7.50E+00 1.56E+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 1.58E+01 Q4 - T.Spec Any Organ CHILD BONE 1.18E+00 7.50E+00 1.58E+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 Q1 - T.Spec Gamma 3.46E-03 5.OOE+00 6.91E-02 Q1 - T.Spec Beta 1.67E-03 1.OOE+01 1.67E-02 Q2 - T.Spec Gamma 2.42E-03 5.OOE+00 4.83E-02 Q2 - T.Spec Beta 1.18E-03 1.00E+01 1.18E-02 Q3 - T.Spec Gamma 3.04E-03 5.OOE+00 6.07E-02 Q3 - T.Spec Beta 1.48E-03 1.OOE+01 1.48E-02 Q4 - T.Spec Gamma 8.16E-03 5.OOE+00 1.63E-01 Q4 - T.Spec Beta 4.39E-03 1.OOE+01 4.39E-02 Yr - T.Spec Gamma 1.71E-02 1.OOE+01 1.71E-01 Yr - T.Spec Beta 8.72E-03 2.OOE+01 4.36E-02

1) Includes conservative estimate of abnormal release dose as discussed in Section I Part E of this report.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 26 of 91 TABLE 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

1. Total Release Ci 1.27E-03 1. 04E-04 1.33E-03 1. 06E-03 3. 77E-03

2. Avg. Diluted Conc. uCi/ml 1. 06E-09 7.28E-11 9.35E-10 7.58E-10 6.91E-10

3. % Applicable Limit % (1) 1. 39E-04 1. 75E-05 2.94E-04 2. 85E-03 2.33E-03 Tritium

1. Total Release Ci 7. 38E+00 1. 96E+00 2.13E+01 1.50E+01 4. 56E+01

2. Avg. Diluted Conc. uci/ml 6.13E-06 1. 37E-06 1.49E-05 1.08E-05 8.36E-06

3. % Applicable Limit % (1) 5. 74E-05 3.92E-06 1.23E-03 2. 23E-04 4.82E-04 Dissolved and Entrained Gases

1. Total Release Ci 4. 82E-04 7. 88E-05 1. 71E-03 5.56E-04 2.82E-03

2. Avg. Diluted Conc. uCi/ml 4. OOE-10 5. 52E-11 1.20E-09 3.99E-10 5. 18E-10

3. % Applicable Limit % (2) 2. 01E-04 2.76E-05 6.02E-04 2.OOE-04 2. 59E-04 Gross Alpha Radioactivity

1. Total Release Ci O.OOE+00 O.OOE+00 O.OOE-i00 O.OOE+00 O.OOE+00 Volume of liquid waste liters 7.55E+05 2.25E+05 8.07E+06 1.74E+06 1.08E+07 Volume of dil. water liters 1.20E+09 1.43E+09 1.42E+09 1.39E+09 5.44E+09 (1) The most limiting dose compared to the total body and critical organ limits of TRM 3.11.1.2.a.

(2) Technical Requirement 3.11.1.1 limit of 2.OOE-04 uCi/ml for dissolved and entrained noble gases in liquid effluent.

River Bend Station 21)14 Regulatory Guide 1.21 Report Page 27 of 91 TABLE 2B LIQUID EFFLUENTS - CONTINUOUS MODE REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products

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

Tritium

- No Nuclide Activities **

Dissolved and Entrained Gases

- No Nuclide Activities * .

Gross Alpha Radioactivity

- No Nuclide Activities **

River Bend Station 2014 Regulatory Guide 1.21 Report Page 28 of 91 TABLE 2C LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-I1OM Ci 0. OOE+00 0. 00E+00 0. 00E+00 2. 74E-06 2.74E-06 CO-58 Ci 0. OOE+00 0. 00E+00 0. 00E+00 2. 04E-05 2. 04E-05 CO-60 Ci 2. 05E-04 8. 54E-05 2.4 9E-04 4. 80E-04 1 . 02E-03 CR-51 Ci 0. OOE+00 0. 00E+00 0. 00E+00 2. 28E-04 2. 28E-04 CS-137 Ci 6. 04E-06 3 .21E-06 1.71E-06 0 00E+00 1. l0E-05 FE-55 Ci 9. 89E-04 0. OOE+00 0. 00E+00 0. 00E+00 9. 89E-04 FE-59 Ci 0. 00E+00 0. 00E+00 0. 00E+00 1. 22E-05 1.22E-05 1-132 Ci 0. OOE+00 0. 00E+00 0. OOE+00 1. 70E-06 1.70E-06 MN-54 Ci 1. 21E-05 1. OOE-05 0. 00E+00 2. 31E-04 2. 53E-04 MO-99 Ci 0. 00E+00 0. 00E+00 2 . 33E-04 0 00E+00 2. 33E-04 NA-24 Ci 0. 00E+00 0. 00E+00 8. 38E-04 0 00E+00 8. 38E-04 NB-95 Ci 0. 00E+00 0. 00E+00 0. 00E+00 3 60E-06 3. 60E-06 NB-97 Ci 0. 00E+00 0. 00E+00 0. 00E+00 4 .21E-06 4.21E-06 RH-105 Ci 0. 00E+00 0. 00E+00 0. 00E+00 7 .32E-05 7.32E-05 SB-125 Ci 4. 55E-05 5. 25E-06 0. 00E+00 0. 00E+00 5. 07E-05 TC-99M Ci 0. 00E+00 0. 00E+00 1. 27E-05 0 00E+00 1. 27E-05 ZN-65 Ci 1. 4 IE-05 0. OOE+00 0. 00E+00 0. 00E+00 1. 41E-05 Totals for Period... Ci 1.27E-03 1.04E-04 1.33E-03 1.06E-03 3.77E-03 Tritium H-3 Ci 7.38E+00 1.96E+00 2.13E+01 1.50E+01 4.56E+01 Totals for Period... Ci 7.38E+00 1.96E+00 2.13E+01 1.50E+01 4.56E+01 Dissolved and Entrained Gases XE-133 Ci 2.84E-04 4.77E-05 8.45E-04 2. 09E-04 1. 39E-03 XE-133M Ci 0. OOE+00 0. 00E+00 5. 92E-06 0. OOE+00 5. 92E-06 XE-135 Ci 1. 98E-04 3. 11E-05 8. 55E-04 3.48E-04 1. 43E-03

River Bend Station 2014 Regulatory Guide 1.21 Report Page 29 of 91 Totals for Period... Ci 4.82E-04 7.88E-05 1.71E-03 5.56E-04 2 . 82E-03 Gross Alpha Radioactivity

- No Nuclide Activities

River Bend Station 2014 Regulatory Guide 1.21 Report Page 30 of 91 TABLE 2D EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2014 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of release s 13 4 63 32 112 Total release tim e minutes 4.10E+03 1.25E+03 3.59E+04 9.0 3E+03 5. 03E+04 Maximum release t ime minutes 3.47E+02 3.43E+02 2.02E+03 3.6 3E+02 2. 02E+03 Average release t ime minutes 3.15E+02 3.12E+02 5.70E+02 2.8 2E+02 4. 49E+02 Minimum release t ime minutes 2.78E+02 2.70E+02 2.31E+02 1.0 0E+02 1. 00E+02 QTR 1 QTR 2 QTR 3 QTR 4 Average Mississip?pi River stream flow ft3/sec 560,778 634,802 373, 120 340,261 during periods of release of efflue nt into a flowing st ream.

River Bend Station 21)14 Regulatory Guide 1.21 Report Page 31 of 91 TABLE 2E RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Type Sampling Frequency Minimum Analysis Type of Activity Lower Limit of Frequency Analysis Detection (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 Entrained One Batch/M Gases (Gamma 1.00E-05 Emitters)

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

River Bend Station 2014 Regulatory Guide 1.21 Report Page 32 of 91 TABLE 2F LIQUID ANNUAL DOSE

SUMMARY

REPORT Report for: 2014 Release ID: 10 All Liquid Release Points Liquid Receptor

=== SITE DOSE LIMIT ANALYSIS Age Dose Limit Max % of Period - Limit Group Organ (mrem) (mrem) Limit Qtr 1 - T.Spec Any Organ ADULT GILLI 6. 89E-06 5. 00E+00 1.38E-04 Qtr 1 - T.Spec Total Body ADULT TBODY 2.95E-06 1. 50E+00 1.97E-04 Qtr 2 - T.Spec Any Organ ADULT GILLI 9. 32E-07 5.00E+00 1. 86E-05 Qtr 2 - T.Spec Total Body ADULT TBODY 2.49E-07 1.50E+00 1.66E-05 Qtr 3 - T.Spec Any Organ ADULT GILLI 2.74E-05 5. 00E+00 5.49E-04 Qtr 3 - T.Spec Total Body ADULT TBODY 2. 28E-05 1. 50E+00 1.52E-03 Qtr 4 - T.Spec Any Organ ADULT GILLI 1. 46E-04 5. 00E+00 2. 92E-03 Qtr 4 - T.Spec Total Body ADULT TBODY 1. 22E-05 1.50E+00 8.12E-04 2014 - T.Spec Any Organ ADULT GILLI 2. 47E-04 1.00E+01 2.47E-03 2014 - T.Spec Total Body ADULT TBODY 3. 64E-05 3. OOE+00 1.21E-03

River Bend Station S2014Regulatory Guide 1.21 Report Page 33 of 91 TABLE 3 Effluent and Waste Disposal Annual Report 2014 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/14 to 12/31/14 A. Solid Waste Shipped for Burial or Disposal (Not Irradiated Fuel)

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

Spent Resins, Filter m3 6.32E+01 A +/- 25%

Sludges, Evaporator Ci 2.97E+01 A Bottoms, Etc. m3 O.OOE+00 B Ci 0.00E+00 B m3 O.OOE+00 C ci O.OOE+00 C Dry Compressible Wastes, m3 6.88E+02 A +/- 25%

Contaminated Equipment Ci 2.99E-01 A Etc.

Irradiated Components, m3 O.OOE+00 Control Rods, Etc. Ci O.OOE+00 Other m3 5.42E+02 A t 25%

(Water, EHC, Waste Oil, Ci 5.39E+00 A etc.)

Note: Volume considered being the total disposal volume of the container.

Radwaste Estimated Error %:

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

1. Possible Errors

a. Volume

b. Representative Sampling

c. Instrument/Counting

d. Dose to Curie Calculations

2. Volume Error Level indication for processed resins can be determined to +/- 0.5 inches. This correlates to approximately 1.0%. Container manufacturer stated design tolerance allows for 1.0% deviation from container dimensions. Volume error is not applicable to dry active waste.

3. Representative Sampling Error

River Bend Station 2014 Regulatory Guide 1.21 Report Page 34 of 91 Sampling error for processed resins is based upon obtaining a representative sample from the waste being processed using an iso-lock sampler. Sampling error from dry active waste is based upon obtaining a representative sample from the material being packaged. This error is estimated to be +/-

10% for all waste types, which is consistent with industry standards.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 35 of 91 Effluent and Waste Disposal Annual Report 2014 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from 01/01/14 to 12/31/14 Table 3 (continued)

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

This error is applicable to all waste types.

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

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

(Min 1%) (Min 1%) (Min 1%)

Isotope % Abundance Curies Isotope % Abundance Curies Isotope % Abundance Curies MN-54 2.395 7.11E-01 CR-51 4.180 1.25E-02 MN-54 2.224 1.20E-01 FE-55 36.963 1.10E+01 MN-54 4.406 1.32E-02 FE-55 35.339 1.90E+00 CO-60 49.145 1.46E+01 FE-55 18.939 5.66E-02 CO-60 47.669 2.57E+00 ZN-65 5.106 1.51E+00 CO-58 2.542 7.60E-03 ZR-95 9.479 5.11E-01 CS-137 3.419 1.01E+00 CO-60 40.965 1.23E-01 CS-137 2.341 1.26E-01 ZN-65 1.366 4.09E-03 ZR-95 9.920 9.97E-02 NB-95 15.814 4.73E-02 Determined by Measurement & Correlation.

Packaged in Strong, Tight Liners.

No Solidification Agent or Absorbent Used.

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 30 Truck Energy Solutions (Gallaher) - Oak Ridge, TN 25 Truck Energy Solutions (Bear Creek) - Oak Ridge, TN B. Irradiated Fuel Shipments Disposition No Irradiated Components, Control Rods, Etc. were shipped in 2014

River Bend Station 2014 Regulatory Guide 1.21 Report Page 36 of 91 TABLE 4 DOSES TO A MEMBER OF THE PUBLIC INSIDE SITE BOUNDARY ASSUMPTIONS/PARAMETERS MEMBER OF LOCATION DISTANCE"'1 SECTOR DURATION THE PUBLIC METERS (HR/YEAR)1 21 People Entering Site Without Alligator Bayou 2500 SW 40 Consent National Guard Activity Center 994 WNW 0(3)

Workers staying Activity Center 994 WNW 1632141 onsite Trailer City Deer Hunters Activity Center 994 WNW 25615" (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 2014.

(4) Workers have been permitted to stay long term at the Activity Center Trailer City beginning April 10, 2007. Effective August 15, 2014, site management closed the Activity Center Trailer City and all trailers were removed. Going forward, trailers will be allowed 30 days prior to and must be removed 14 days following refueling outages. For 2014, 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 34 weeks, totaling 1632 hours0.0189 days 0.453 hours 0.0027 weeks 6.20976e-4 months . The adult age group is the only age group considered for this activity.

(5) Employees are allowed to deer hunt on company property. Since the hunters are spread out all over the site, those workers are conservatively evaluated at the activity center using occupancy information provided by the Bow Club. In 2014, hunter's dose is not greater than Trailer City.

River Bend Station 2014 Regulatory Guide 1.21 Report Page 37 of 91 TABLE 5 DOSES TO MEMBERS OF THE PUBLIC ON SITE FROM GASEOUS RELEASES 2014 Location Critical Organ Total Body Dose Skin Dose Annual Dose Annual Annual (mrem) Annual (mrem) Duration (mrem) Factor Alligator Bayou 2.11E-05 6.22E-06 1.02E-05 4.57E-03 Workers staying 1.79E-03 2.96E-04 4.82E-03 1.86E-01 onsite Deer 2.81E-04 4.65E-04 7.56E-04 2.92E-02 Hunters I

River Bend Station 2014 Regulatory Guide 1.21 Report Page 38 of 91 TABLE 6 2014 YEAR METEOROLOGICAL DATA - JOINT FREQUENCY TABLES

Rivet Rend Station 2014 Regulatory Guide 1.21 Report Page 39 of 91 RIVER BEND STATION JOINT FREQUENCY TABLE ALL STABILITY CLASSES FROM 1/01/14 0:00 TO 12/31/14 23:00 PRIMARY SENSORS - 30 FOOT WIND SPEED (METERS/SECOND)