Text

Radioactive Effluent Release Report for 2004
	ML051220168
Person / Time
Site:	River Bend
Issue date:	04/27/2005
From:	Lorfing D; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	G9.25.1.5, G9.5, RBF1-05-0074, RBG-46432
	Download: ML051220168 (111)
	v • d • e

Entergy Operations, Inc.

River Bend Station 5485 U.S. Highway 61 N

- Entergy St. Francisville, LA 70775 Tel 225 381 4157 Fax 225 635 5068 dlorfinientergy.com David N. Lorfing Manager-Licensing April 27, 2005 U.S. Nuclear Regulatory Commission Document Control Desk O\\'FN-P I -17 11555 Rockville Pike Rockville, MD 20852-2738

Subject:

Radioactive Effiluent Release Report for 2004 River Bend Station - Unit I License No. NPF-47 Docket No. 50-458 File Nos.: G9.5, G9.25.1.5 RBG-46432 RBFFI 0074 Ladies and Gentlemen:

Enclosed is the River Bend Station (RBS) Annual Radioactive Effluent Release Report for the period January 1, 2004, through December 3 1, 2004. This report is submitted in accordance with tile RBS Technical Specifications, Section 5.6.3.

Should you have any questions regarding the enclosed inforniation. please contact Mr. Michael J.

Boyle at (225) 381-4406.

Sincerely, Manager - Licensing DNL/dIin enclosure J:0-

Radioactive Effluent Release Report for 2004 April 27, 2005 RBG-46432 RBFI 0074 Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Resident Inspector PO Box 1050 St. Francisville, LA 70775 Mr. Michael K. Webb, Project Manager U.S. Nuclear Regulatory Commission M/S OWFN 0-7 Dl 11555 Rockville Pike Rockville, MD 20852-2738

2004 ANNUAL EFFLUENT RELEASE REPORT PREPARED BY: X1/3(. 4-18 William H. S 1, Senior Environmental Specialist REVIEWED BY:

REVIEWED BY: 4k/

o/o 9L Micha J. oyle / diation Protection Manager APPROVED BY: /(> -/ L/2/ /or Donald W. Vinci / General Manager Plant Operations

River Bend Sation 2004 Regulatory Guide 1.21 4/18/2005 TABLE OF CONTENTS PAGE I. INTRODUCTION 4 II. SUPPLEMENTAL INFORMATION A. Regulatory Limits 4 B. Effluent Concentration Limits 7 C. Measurements and Approximations of Total Radioactivity 7 D. Batch Releases 11 E. Abnormal Releases 12 F. Estimate of Total Error 12 III. GASEOUS EFFLUENT

SUMMARY

INFORMATION 13 IV. LIQUID EFFLUENT

SUMMARY

INFORMATION 13 V. SOLID WASTE 13 VI. RADIOLOGICAL IMPACT ON MAN 13 VII. METEOROLOGICAL DATA 13 VIII. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION OPERABILITY 14 IX. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION OPERABILITY 14 X. LIQUID HOLDUP TANKS 14 XI. RADIOLOGICAL ENVIRONMENTAL MONITORING 14 XII. LAND USE CENSUS 14 XIII. OFFSITE DOSE CALCULATION MANUAL (ODCM) 14 XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS 14 XV. PROCESS CONTROL PROGRAM (PCP) 18 TABLES Table I Radioactive Gaseous Waste Sampling and Analysis Program 8 Table 2 Radioactive Liquid Waste Sampling and Analysis Program 10 2

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 Table 3A Gaseous Effluent - Summation of All Releases 20 Table 3B Gaseous Effluent - Ground Level Releases 21 Table 3C Gaseous Effluent - Ground Level Batch Release 22 Table 3D Gaseous Effluent - Mixed Mode Continuous Releases 23 Table 3E Gaseous Effluent - Mixed Mode Batch Releases 24 Table 4A Liquid Effluent - Summation of All Releases 25 Table 4B Liquid Effluent - Continuous Mode 26 Table 4C Liquid Effluent - Batch Mode 27 Table 5 Solid Waste and Irradiated Fuel Shipments 28 Table 6 Maximum Individual Doses Due to Noble Gaseous Releases 31 Table 7 Maximum Individual Doses Due to Gaseous Releases 31 Table 8 Maximum Individual Doses Due to Liquid Releases 32 Table 9 Assumptions/Parameters for Doses to Member of the Public Inside Site Boundary 33 Table 10 Doses to Members of the Public on Site from Gaseous Releases 34 Table 11 Meteorological Data - Joint Frequency Tables 35 Table 12 Atmospheric Dispersion Factors 100 ATTACHMENT 1 - Radwaste Process Control Program (PCP) 3

River Bend Station 2004 Regulatory Guide 1.21 411S/2005 I. INTRODUCTION This is the annual Radioactive Effluent Release Report for the period of January 1, 2004, through December 31, 2004. This report is submitted in accordance with Technical Specification 5.6.3 of Appendix A to River Bend Station (RBS) License Number NPF-47.

II. SUPPLEMENTAL INFORMATION A. Regulatory Limits

1. 10CFR50, Appendix I Limits

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

DG...Air = gamma air dose from radioactive noble gases in millirad (mrad) n

= 3.17E-8 £ M; (X/Q) Qi < 5 mrads/qtr i=1 < 10 mrads/yr

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

= 3.17E-8 £ N; (X/Q) Qi < 10 nrads/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:

D1&8DP, = Dose in mrem to the organ (tc) for the age group of interest from radioiodine (1-131, 1-133, tritium, and 8 day particulate via the pathway of interest.)

n

= 3.17E-08 (F0 ) Pi, (X/Q) Qi and I=1 n

= 3.17E-08 (F.) E R., (D/Q) Qi and I=1 4

River Bend Station 2004 Regulatory Guide 1.21 4118/2005 n

D, = z DI&8DP, < 7.5 mrem/qtr z=1 < 15 mrem/yr (above terms defined in the RBS ODCM)

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

D = Ai At Qj (DF) Dw and n

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

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

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

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 5

River Bend Station 2004 Regulatory Guide 1.21 4118/2005 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:

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

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

= Z L; + L.IMi (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&8DpT = Dose rate to the organ X for the age pathway group of interest from Radioiodines (1-13 1 & I-133), tritium, and 8 day particulate via the inhalation pathway in mrem/yr.

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 2.0E-04 microcuries/milliliter total concentration.

6

River Bead Station 2004 Regulatory Guide 1.21 4/112005

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

e. Technical Requirement 3.11.1.3 - Liquid Radwaste Treatment System In accordance with Technical Requirement 3.11.1.3, the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses, due to the liquid effluent, to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 3 1-day period.

B. Effluent Concentration Limits I1. 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 IOCFR20 Appendix B, Table 2, Column 1.

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

C. Measurements and Approximations of Total Radioactivity I1. 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 1.

7

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 TABLE 1 Effluent and Waste Disposal Annual Report 2004 Year 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 l.OOE-04 Ventilation Exhaust Duct D. All Release Continuous W I-131 l.OOE-12 Types as listed Charcoal inA,B,&C Sample above I-133 1.OOE-10 Continuous W Principal Gamma Particulate Emitters (I-13 1, 1.OOE-l 1 Sample Others)

Continuous M Gross Alpha Composite 1.OOE-1 1 Particulate Sample Continuous Q Sr-89, Sr-90 Composite 1.OOE-1 1 Particulate Sample Continuous Noble Gas Noble Gases Monitor Gross Beta or l.OOE-06 Gamma W = At least once per 7 days M = At least once per 31 days Q = At least once per 92 days 8

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 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 (I-131 & I-133!

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

Due to the continuous sampling process, it is assumed that the radioactive material is released to the environment at a constant rate within the sampling period. Strontium-89 and Strontium-90 (Sr-89 and Sr-90) are quantitatively analyzed by counting by Scintillation techniques (Chrenkov counting). Gross alpha analysis is performed using a zinc sulfide scintillation counter.

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

2. Liquid Effluent Representative grab samples are obtained from the appropriate sample recovery tank and analyzed prior to release of the tank in accordance with the frequencies listed in Table 2. Analysis for gamma emitting nuclides (including dissolved and entrained noble gases) is performed using a high resolution germanium detector coupled to a computerized pulse height analyzer. Tritium 9

River Bend Station 2004 Regulatory Guide 1.21 4/18n205 concentration is determined using a liquid scintillation counter. Strontium-89 and Strontium-90 are quantitatively analyzed by Scintillation techniques (Chrenkov counting). Iron-55 is counted with a liquid scintillation counter after digestion of the iron. Gross alpha analysis is performed using a zinc sulfide scintillation counter.

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

TABLE 2 Efuent and Waste Disposal Annual Report 2004 Year 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 5.00E-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 Q Sr-89, Sr-90 5.OOE-08 Each Batch Composite

_ Fe-55 1.OOE-06 P = Prior to each radioactive release M = At least once per 31 days Q = At least once per 92 days 10

RverBendStaton 2004 Regulatory Guide 1.21 4/1 8)205 D. Batch Releases Liquid Effluents EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0 13 55 65 133 Total release time Uminutes 0.0 E+00 4.39E+03 1.95E+04 2.25E+04 4.64E+04 Maximum release time Vminutes 0.OOE+00 3.56E+02 4.46E+02 4.90E+02 4.90E+02 Average release time nminutes 0.OOE+00 3.38E+02 3.54E+02 3.47E+02 3.49E+02 Minimum release time rminutes 0. OOE+00 3. 11E+02 l.00E+00 0.OOE+00 0.OOE+00 OTR I QTR 2 OTR3 OTR4 Average Miss. River stream flow during ft 3 /

periods of release sec 650,022 657,429 431,859 587,870 of effluent into a flowing stream The Mississippi River stream flow is obtained by averaging data from the U. S. Army Corp of Engineers website using flow gauge data at Tarbert Landing.

Gaseous Effleunts There were no batch releases of gaseous effluents from River Bend Station during 2004.

EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0 0 0 0 0 Total release time minutes 0.00E+00 0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Maximum release time minutes 0.00E+00 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 Average release time minutes 0. 00E+00 0. 00E+00 0. OOE+00 0.OOE+00 0.OOE+00 Minimum release time minutes 0. OOE+00 10.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 11

River Bend Station 2004 Regulatory Guide 1.21 4/1812005 E. Abnormal Releases There were no abnormal releases during the reporting period of January 1, 2004, through December 31, 2004.

F. Estimate of Total Error

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

Fission and Activation Products : + 14.2%

Tritium : + 14.2%

Dissolved and Entrained Noble Gases : + 14.2%

Gross Alpha Radioactivity : + 14.2%

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

Noble Gases :+ 37.0%

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 = y((E-I) + (E2 ) +...(En)1 )

where:

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

12

River Bend Station 2004 Regulatory Guide 1.21 4112005 III. GASEOUS EFFLUENT

SUMMARY

INFORMATION Refer to the Table 3 series for "Summation of All Releases" and "Nuclides Released,"

respectively. It should be noted that an entry of "0.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 1. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

IV. LIQUID EFFLUENT

SUMMARY

INFORMATION Refer to the Table 4 series for "Summation of All Releases and Nuclides Released." 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 2. Also, any nuclide not appearing in the tables was < LLD for all four quarters.

V. SOLID WASTE Refer to Table 7, for "Solid Waste and Irradiated Fuel Shipments."

VL RADIOLOGICAL IMPACT ON MAN (40CFR190)

An assessment was made of radiation doses to the likely most-exposed member of the public from River Bend and other nearby uranium fuel cycle sources (none within five miles). The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources, shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

Total Body = 8.81E-02 mrem Skin = 5.39E-02 mrem Thyroid = 1.30E-01 mrem Other Organ = 8.85E-02 mrem 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 9. The results of the calculations can be found in Table 10. The maximally exposed member of the public was the National Guard, which was stationed on site during 2004. 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.

VIL METEOROLOGICAL DATA See Tables 11 and 12 for the cumulative joint frequency distributions and annual average data for continuous releases. The meterological recovery for 2004 was 96.2%.

13

River Bend Station 2004 RegulatoryGuide 1.21 41192005 VIIL 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, 2004, through December 31, 2004, restored to operable status within the required time.

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

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, 2004, through December 31, 2004, 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, 2004, through December 31, 2004 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 in radiological environmental monitoring locations during the reporting period January 1, 2004, through December 31, 2004.

XIL LAND USE CENSUS The Land Use Census, as required by Technical Requirement 3.12.2, did not identify any location(s) that would yield a calculated dose or dose commitment greater than the values calculated. In addition, the milk animal census identified no milk production for human consumption within 8 km (5 miles) of River Bend Station.

XIIL OFFSITE DOSE CALCULATION MANUAL (ODCM)

No changes were made to the ODCM in 2004.

XIV. MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS Engineering has performed a review of the Integrated Document Electronic Access System (IDEAS) database to evaluate design changes completed or partially completed during 2004 involving the subject systems. These design changes were then reviewed to determine if there 14

River Bend Station 2004 Regulatory Guide1.21 4/18/2005 have been any major changes to the subject systems. The review was based on a major change being defined as a modification that affected the method of processing or the effluent from the system. Also, to be a "major change" the change must have affected the USAR.

The Engineering Requests completed during this time period primarily consisted of administrative changes and parts interchangeability evaluations. Two evaluations were performed, one providing evaluation of Offgas System operation without the Offgas Preheater in service, and the second evaluating a leak seal repair for a head gasket on Offgas Preheater N64-EBOOlB. Neither evaluation had an impact on method of processing, system effluent, or on the USAR. A nuclear change was performed to replace the level instrumentation on the Waste Sludge Tank, WSS-TK14. Although the USAR was affected by this change, there was no impact on the processing method or system effluent. As a result, these modifications do not constitute major changes.

Nuclear change ER-RBS-2002-0528 was implemented to allow the use of leased liquid radwaste processing equipment. The leased processing equipment was placed in service in October 2004. Because the leased equipment can be used as an alternative to, or in combination with our existing liquid radwaste equipment, and the ability to use our existing liquid radwaste equipment as originally installed has been maintained, it could reasonably be concluded that this modification does not constitute a major change per the criteria above.

However, given the scope of the modification and the preferential usage of the leased equipment, engineering is categorizing this modification as a major change with the following information provided for inclusion in the Annual Radioactive Effluent Release Report to address the reporting requirements of TR 5.10.1.

A. 10CFR50.59 Evaluation Summary The objective of the radioactive liquid waste (radwaste) system is to collect, monitor, and process for reuse or disposal all potentially radioactive liquid wastes in a controlled manner so that the operation or availability is not limited. The radwaste system has the capacity and capability of processing the anticipated quantities and activities of liquid wastes resulting from normal operation. The installation of the ultra filtration unit and interconnecting piping will reinforce the capabilities of the radwaste system. The ultra filtration unit and interconnecting piping is designed to the same codes and standards as the existing liquid radwaste system.

Enhancement of liquid radwaste processing capability does not affect the quantity or characteristics of the fluid being processed by the radwaste system. This change does not affect the frequency of postulated accidents or malfunctions, the consequences of postulated accidents or malfunctions, introduce a new or different accident or malfunction, or affect design basis limits for fission product barriers. A review of analyzed radioactive releases was performed and it is concluded that this modification is bounded by existing radioactive release evaluations.

B. Reason for Change The existing liquid radwaste system has limited capability to remove organic material and provide filtration. As a result, the ion exchange resins become fouled, effectively reducing their capacity. Additionally, the walnut shell filters require polyelectrolyte injection to enable efficient removal of particles from the process stream. The location of the polyelectrolyte injection relative to the filters provides inadequate time for proper mixing and coagulation, which results in carryover of the poly and the solids to the demineralizers. In addition, variations in the inlet stream composition make determination of the optimum quantity of 15

River Bend Stafion 2004 Regulatory Guide 1.21 4/18/2005 polyelectrolyte for each batch impractical. The walnut shells also provide an environment that promotes bacterial growth. Sloughing off of the organic matter also results in downstream resin fouling. Radwaste Operations and Chemistry have expended major efforts to improve liquid waste processing performance in terms of both run time and quality of water produced.

However, the lack of filtration and effective organic removal limit result in higher generation of solid waste for radwaste processing than that typical in the industry.

C. Detailed Equipment Description and Interfaces with other Plant Systems River Bend Station has implemented modifications to enable the use of leased liquid radwaste processing equipment. The leased liquid radwaste processing equipment can be used as an alternative to, or in combination with our existing permanently installed liquid radwaste processing equipment.

The leased liquid radwaste processing equipment selected uses reverse osmosis as the ultra filtration method. The equipment consists of two redundant pretreatment trains containing an inlet strainer, ozone injection system, backwashable granular activated carbon (GAC) filters, and backwashable, 1 micron rated particulate filters. The inlet strainers are intended to remove large particles and/or debris. The ozone injection system will provide for oxidation of organic material and to change the oxidation state of particulate iron present in the process stream, improving the ease of removal via filtration. The GAC filters provide removal of any residual organics that were not oxidized by the ozone injection, removes any residual ozone present in the process stream, and removes particulates on the order of 6 micron and larger. The backwashable 1 micron filters remove smaller particulates from the process stream. Each pretreatment train has the capacity to simultaneously process water from the LWS system at a rate of 75 gpm.

Downstream of the pretreatment portion of the system is a single train, reverse osmosis (RO) skid and final polishing demineralizer. The RO skid is a two-pass unit that removes the remaining insoluble material and the bulk of the soluble impurities from the process stream.

The final polishing demineralizer removes any remaining ionic species not removed by the reverse osmosis process. The RO skid and demineralizer can process liquid waste at a rate of 75 gpm. Typically during normal load periods, both floor drain and waste collector (equipment drain) streams will be processed via vendor pretreatment and the RO skid. This processing will be performed on a batch basis. During high load periods, such as outages, or to maximize available storage capacity, floor and waste collector water can be simultaneously processed by the pretreatment portion of the system. The lower quality floor drain water will typically be sent to the RO for final processing, with the waste collector water being sent to the existing LWS demineralizers for final processing. An isolation valve was added to the Recovery Sample Tank Inlet Header to facilitate simultaneous operation of the RO skid and the existing LWS demineralizers.

An additional demineralizer vessel is being leased to provide the ability to use the residual ion exchange capacity in discharged condensate demineralizer resin. This discharged resin will be transferred to this additional demineralizer vessel, and be used to process the waste water from the RO skid. The waste water from the RO skid is referred to as "brine," and this additional demineralizer is referred to as the "brine demin." Use of residual condensate demin resin capacity provides significant reduction in solid waste generation from radwaste processing.

The treated water from either the RO or from the LWS Demineralizers is directed to the 16

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 Recovery Sample Tanks. Each tank is recirculated, sampled and directed to either the Condensate Storage Tank, collector tanks for reprocessing, or discharged.

Media backwashes and exhausted carbon and ion exchange resins are directed to the radwaste backwash tank, LWS-TK7.

The added interfaces with plant systems to enable use of the leased liquid radwaste processing equipment are as follows:

Liquid Radwaste

Waste stream supply via connections to the Waste Collector Tank and Floor Drain Collector Tank pump discharge piping.

Pretreatment return to the Liquid Radwaste Demineralizer inlet crosstie piping.

RO polishing demineralizer discharge to the Recovery Sample Tank Inlet Header.

eBackwash transfer piping from vendor inlet strainers, granular activated carbon filters, and recirculation tank (interim point for filter backwash stream) to the radwaste backwash tank, and from the brine demin to the radwaste backwash tank.

. Brine demineralizer supply piping from the vendor recirculation tank skid.

Radwaste Building Floor and Equipment Drains

Brine demineralizer process effluent and vendor skid drains.

Condensate Makeup, Storage and Transfer

A connection to the condensate system was made to provide demineralized water for filling, flushing, and backwashing vendor equipment.

Condensate Demineralizer

. Piping from the Condensate Demineralizer resin transfer line to the brine demineralizer.

Service Air

Service air was supplied to the vendor skid area for operation of air operated valves, facilitating strainer and filter backwashes, and skid area general use.

Radwaste Building Ventilation

The discharge of the vendor ozone skid reaction tanks is connected to the radwaste tank vent header, and is directed to the Radwaste Building Ventilation Filter Trains.

480 VAC Power

Electrical power from 480-Volt switchgear NJS-SWGlR is provided to the vendor power distribution panel.

D. Differences in Predicted Releases or Quantity of Solid Wastes 17

River Bend Station 2004 Regulatory Guide 1.21 411812005 Because the the original liquid radwaste treatment system has been maintained, there was no change in the predicted releases of radioactive materials in liquid or gaseous effluents or the quantity of solid wastes different from those previously predicted in licensing basis documents.

E. Unrestricted Area Exposure Because the original liquid radwaste treatment system has been maintained, there was no change in the expected maximum exposure to a member of the public in the unrestricted area different from those previously predicted in licensing basis documents.

F. Comparison of Predicted Releases to Actual Releases Because the the original liquid radwaste treatment system has been maintained, there was no change in the predicted releases of radioactive materials in liquid or gaseous effluents or the quantity of solid wastes different from those previously predicted in licensing basis documents.

It is possible that when the RO is used, there could be a reduction of solid waste and some types of liquid effluent released.

G. Plant Personnel Exposure There is no overall plant personnel exposure change anticipated as a result of using the leased reverse osmosis equipment.

H. Documentation of Review per TR 5.8.2 The Engineering Request was reviewed and approved per the requirements of TR 5.8.2 as documented by Onsite Safety Review Committee (OSRC) approval on the 10CFR50.59 evaluation included with ER-RB-2002-0528-000. The evaluation, #2003-025, was approved in OSRC meeting #2003-037 and dated December 11, 2003.

XV. PROCESS CONTROL PROGRAM (PCP)

The following changes to the PCP (Nuclear Management ManuaIIENSIRW-105, Process Control Program) were implemented at RBS on October 1, 2004. These changes are either an enhancement or editorial in nature and did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes. A copy of the PCP is attached in Attachment 1. Below is a summary of the changes to the PCP:

Change to Section 1.0, Purpose - adding information for the PCP program

Changed reference section to identify only non-site references for this document

Added definition for Batch in Section 3.0

Changes/updates made in Section 4.0 (Responsibilities) & 8.0 (Commitment Cross-Reference)

Moved text about vendor taking title of waste from Section 5.2.2 to 5.2.1

Updated Section 5.4 to match each site's approval authority list for the PCP and changes

Added Section 5.5 to include vendor related requirements 18

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 a Updated procedure to match requirements of Nuclear Management ManuaVEN/AD-101, Procedure Process.

19

River Bend Station 2004 Regulatory Guide 1.21 4/1 &/2005 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 3A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 Fission and Activation Gases

1. Total Release Ci 1.72E+00 3.67E-01 4.96E+00 3.70E+01

2. Avg. Release Rate uCi/sec 2.19E-01 4.67E-02 6.24E-01 4.66E+00

3. % Applicable Limit % (1) 3.04E-02 6.50E-03 2.31E-02 5.59E-01 Iodine-131

1. Total Release Ci 1.69E-04 1.62E-04 1.72E-04 7.OOE-04

2. Avg. Release Rate uCi/sec 2.15E-05 2.06E-05 2.17E-05 8.80E-05

3. % Applicable Limit % (2) 7.19E-02 7.11E-02 7.33E-02 2.99E-01 Particulates Half Life >= 8 days

1. Total Release Ci 9.15E-04 6.14E-05 4.69E-05 2.52E-05

2. Avg. Release Rate uCi/sec 1.16E-04 7.81E-06 5.90E-06 3.17E-06

3. % Applicable Limit % (2) 5.63E-02 1.42E-02 1.55E-02 1.16E-02 Tritium

1. Total Release Ci 9.95E+00 1.98E+01 1.03E+01 6.55E+00

2. Avg. Release Rate uCi/sec 1.27E+00 2.52E+00 1.30E+00 8.24E-01

3. % Applicable Limit % (2) 1.65E-01 2.31E-01 1.61E-01 1.74E-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 20

River Bend Station 2004 Regulatory Guide 1.21 4/18/205 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 3B GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci 1.38E+00 2.95E-01 6.55E-02 0.OOE+00 1.74E+00 XE-133M Ci 0.OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 XE-135 Ci 3.37E-01 7.22E-02 1.60E-02 0.OOE+00 4.25E-01 XE-135M Ci 0.OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0.0OE+00 Totals for Period... Ci 1.71E+00 3. 67E-01 8.15E-02 0. OOE+00 2.16E+00 Iodines I-131 Ci 0.OOE+00 2.44E-06 0.OOE+00 1.28E-06 3.72E-06 I-133 Ci 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 Totals for Period... Ci 0.OOE+00 2.44E-06 0.00E+00 1.28E-06 3.72E-06 Particulates Half Life >= 8 days CE-141 Ci 0.OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-57 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 Ci 0.OOE+00 0.0OE+00 0. 00E+00 0.OOE+00 0. OOE+00 CO-60 Ci 0.OOE+00 0. OOE+00 0.OOE+00 5.69E-07 5.69E-07 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-s9 Ci 0.OOE+00 0.0OE+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-9s Ci 0.OOE+00 0.00OE+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 5.69E-07 5.69E-07 2.OEE+00 Tritium H-3 Ci 1.83E+00 2.06E+00 1.73E+00 2.26E+00 7. 87E+00 2_______

Totals for Period... Ci 1.83E+00 2. 06E+00 1.73E+00 2.26E+00 7.87E+00

.1 21

River Bend Station 2004 Regulatory Guide 1.21 4118/205 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 3C GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2004 Units QTR I QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases XE-133 Ci O.OOE+00 O.OOE+00 O. OOE+O0 0.OOE+00 O.OOE+00 XE-135 Ci O.OOE+00 O.OOE+00 0. OOE+O0 0. OOE+00 O.OOE+00 XE-135M Ci O. OOE+O0 O. OOE+00 O.OOE+00 O.OOE+O0 O.OOE+O0 Totals for Period... Ci 0. OOE+O0 O.OOE+00 0.OOE+O0 0. OOE+O0 0.OOE+00 Iodines

- No Nuclide Activities **

Particulates Half Life >= 8 days CO-60 Ci O.OOE+00 O.OOE+00 O.OOE+00 0. OOE+00 O.OOE+00 MN-54 Ci O.OOE+OO O.OOE+0O O.OOE+00 O.OOE+00 O.OOE+0O ZN-65 Ci O.OOE+OO. O.OOE+00 0. OOE+00 O.OOE+O0 O.OOE+OO Totals for Period ... Ci O.OOE+00 O. OOE+OO O.OOE+00 0.0 OE+O0 0.OOE+OO Tritium

- No Nuclide Activities **

22

River Bend Station 2004 Regulatory Guide 1.21 4/18J2005 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 3D GASEOUS EFFLUENTS - MIXED MODE RELEASES - CONTINUOUS MODE REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci 0.OOE+00 0.OOE+00 0.OOE+00 7.57E-01 7.57E-01 KR-8S Ci 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 KR-85M Ci 0. OOE+00 0. OOE+00 2.92E-01 4. 06E+00 4.36E+00 KR-87 Ci 0. OOE+00 0. OOE+00 0.OOE+00 8. 65E+00 8. 65E+00 KR-88 Ci 0. OOE+00 0. OOE+00 0. OOE+00 1.21E+01 1.21E+01 XE-131M Ci 0.OOE+00 0. OOE+00 0. OOE+00 0. OOE+00 0.0OE+00 XE-133 Ci 0.OOE+00 .0.OOE+00 1.66E-01 5. 11E+00 5.27E+00 XE-133M Ci 0.OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 XE-135 Ci 8.2OE-03 0. OOE+00 3.44E+00 3 . 88E+00 7.33E+00 XE-135M Ci 0. OOE+00 0.OOE+00 9.78E-01 2.47E+00 3.45E+00 XE-137 Ci 0. OOE+00 0. OOE+00 0.OOE+00 0.OOE+00 0.00E+00 XE-138 Ci 0. OOE+00 0. OOE+00 o.OOE+00 0. OOE+00 0. 00E+00 Totals for Period... Ci 8.20E-03 0.OOE+00 4.88E+00 3.70E+01 4.19E+01 Iodines I-131 Ci 1.69E-04 1.59E-04 1.72E-04 6.98E-04 1.2OE-03 I-132 Ci 0.OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0.OOE+00 I-133 Ci 1.51E-03 1.22E-03 1.35E-03 9.88E-04 5.08E-03 I-135 Ci O.OOE+00 0. OOE+00 0.OOE+00 0. OOE+00 0.00E+00 Totals for Period... Ci 1.68E-03 1.38E-03 1.52E-03 1. 69E-03 6.28E-03 Particulates Half Life >= 8 days BA-140 Ci I3.88E-05 1.50E-05 0. OOE+00 0. OOE+00 1. 04E-04 CE-139 Ci t0.00E+00 0. 00E+00 O.OOE+00 0. OOE+00 0. OOE+00 CO-S8 Ci 9.S1E-05 0. 00E+00 O.OOE+00 0. OOE+00 9.51E-05 CO-60 Ci 2.16E-04 0.OOE+00 0. OOE+00 0.OOE+00 2.16E-04 CR-S1 Ci I0.OOE+00 0.OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 CS-134 Ci I 0.00E+00 0. OOE+00 0. OOE+00 0. OOE+00 O.OOE+00

0. 00E+00 CS-137 Ci I0.OOE+00 0.00E+00 0. OOE+00 0. OOE+00 O.OOE+00 FE-59 Ci I0.00E+00 0.00E+00 0. OOE+00 0. OOE+00 0. OOE+00 MN-54 Ci 7.87E-05 O.OOE+OO O.OOE+00 1. 1SE-05 9.02E-05 SR-89 Ci 3.91E-05 4.64E-05 4.69E-05 1.32E-05 1.46E-04 ZN-65 Ci 3.97E-04 O.OOE+00 O.OOE+00 0. OOE+00 3.97E-04 Totals for Period... Ci 9.15E-04 6.14E-05 4.69E-05 2.46E-05 1.05E-03 Tritium H-3 Ci iB.13E+00 1.78E+01 8.60E+00 4.29E+00 3. 88E+0l Totals for Period... Ci B.13E+00 1.78E+01 8.60E+00 4.29E+00 3. 88E+01 23

River Bend Station 2004 Regulatory Guide 1.21 4118/2005 EFFLUENT AND WASTE DISPOSAL REPORT SUPPLEMENTAL INFORMATION GASEOUS EFFLUENTS - BATCH MODE Table 3E REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 0 0 0 0 0 Total release time minutes 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0. 00E+00

0. OOE+00 Maximum release time minutes 0.00E+00 0. OOE+00 0. 00E+00 0.OOE+00 O.OOE+00 Average release time minutes 0.00E+00 0.00E+00 0.OOE+00 0. OOE+00 0.OOE+00 Minimum release time minutes 0.OOE+00 0. OOE+00 0. OOE+00 0.OOE+00 0.00E+00 24

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 4A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 Fission and Activation Gases

1. Total Release Ci 0.OOE+00 3.70E-02 3.16E-02 2.71E-02

2. Avg. Diluted Conc. uCi/ml 0.OOE+00 2.49E-08 2.14E-0B 2.77E-08

3. % Applicable Limit % (1) 0. 00E+00 5.42E-02 8.45E-02 2.09E-01 Tritium

1. Total Release Ci 0.OOE+00 1. 70E+01 5. 18E+01 3. 78E+01

2. Avg. Diluted Conc. uCi/ml 0.OOE+00 1.1SE-05 3.51E-05 3.85E-05

3. % Applicable Limit % (1) 0. OOE+00 1.15E-04 1.56E-03 l.99E-03 Dissolved and Entrained Gases

1. Total Release Ci 0.OOE+00 6.57E-04 5.30E-03 1.43E-02

2. Avg. Diluted Conc. uCi/ml 0. 00E+00 4.42E-10 3.59E-09 1.46E-08

3. % Applicable Limit % (2) 0.OOE+00 2.22E-04 1.80E-03 7.32E-03 Gross Alpha Radioactivity

1. Total Release Ci 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Volume of liquid waste liters 0.OOE+00 7.53E+05 2.97E+06 3.43E+06 Volume of dil. water liters 1.45E+09 1.48E+09 1.47E+09 9.77E+08 (1) The most limiting dose compared to the total body and critical organ limits of TRM 3.11.1.2.a.

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

25

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 4B LIQUID EFFLUENTS - CONTINUOUS MODE REPORT FOR 2004 Units QTR I 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 **

26

River Bend Station 2004 Regulatory Guide 1.21 4/18n2005 EFFLUENT AND WASTE DISPOSAL REPORT TABLE 4C LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2004 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AG-li0M Ci 0. OOE+00 1.94E-04 4.67E-04 3. 02E-05 6.91E-04 CO-58 Ci O.OOE+00 1.88E-04 0.OOE+00 3.88E-05 2.27E-04 CO-60 Ci 0.OOE+00 8.13E-03 3.69E-03 4.80E-03 1.66E-02 CR-51 Ci 0.00E+00 5.26E-04 8.40E-05 5.72E-04 1.18E-03 FE-55 Ci 0. 00E+00 1.57E-02 2.34E-02 1.62E-02 5.53E-02 FE-59 Ci 0. OOE+00 4.33E-04 7.46E-06 4.39E-04 8.79E-04 I-131 Ci 0.OOE+00 0.OOE+00 6.22E-05 0.OOE+00 6.22E-05 LA-140 Ci 0.OOE+00 1. 02E-04 7.60E-05 0. OOE+00 1.78E-04 MN-54 Ci 0.OOE+00 9.80E-03 3.38E-03 4.86E-03 1. 80E-02 NB-95 Ci 0.OOE+00 0.OOE+00 0.OOE+00 3.14E-05 3.14E-05 NB-97 Ci 0.OOE+00 2.91E-04 5.59E-05 8.47E-06 3.55E-04 SB-124 Ci 0.OOE+00 0.OOE+00 0.0OE+00 1.27E-05 1.27E-05 SN-113 Ci 0. OOE+00 3.44E-05 5.31E-06 0. OOE+00 3.97E-05 SR-92 Ci 0. OOE+00 9.72E-05 7.70E-05 6.66E-06 1.81E-04 ZN-65 Ci 0.OOE+00 1.43E-03 3.66E-04 8.94E-05 1.88E-03 ZR-97 Ci 0.OOE+00 0.OOE+00 6.1OE-06 o.OOE+00 6.10E-06 Totals for Period... Ci 0.OOE+00 3.70E-02 3.16E-02 2.71E-02 9.57E-02 Tritium H-3 Ci 0.OOE+00 1.70E+01 5.18E+01 3.78E+01 1.07E+02 Totals for Period... Ci 0.OOE+00 1.70E+01 5.18E+01 3.78E+01 1.07E+02 Dissolved and Entrained Gases XE-131M Ci 0.OOE+00 0.OOE+00 0.OOE+00 5.83E-05 5.83E-05 XE-133 Ci 0.OOE+00 2.34E-04 3.31E-03 9.03E-03 1.26E-02 XE-133M Ci 0.OOE+00 0.OOE+00 0.OOE+00 1.33E-04 1.33E-04 XE-135 Ci 0.OOE+00 4.22E-04 1.99E-03 5.05E-03 7.46E-03 Totals for Period ... Ci 0.OOE+00 6.57E-04 5.30E-03 1.43E-02 2.02E-02 Gross Alpha Radioactivity

- No Nuclide Activities **

27

River Bend Station 2004 Regulatory Guide 1.21 4118/2005 TABLE 5 Effluent and Waste Disposal Annual Report 2004 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from January 1, 2004 to December 31, 2004 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 3.90E+01 A See Below Sludges, Evaporator Ci 1.04E+02 A Bottoms, Etc. m3 1.94E+00 B Ci 5.15E+01 B m3 1.50E+00 C Ci 5.77E+01 C Dry Compressible Wastes, m3 4.47E+01 A See Below Contaminated Equipment Ci 1.65E+01 A Etc.

Irradiated Components, m3 0.00E+00 N/A N/A Control Rods, Etc. Ci 0.OOE+00 Other m3 0.OOE+00 N/A See Below Ci 0.00E+00 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.

28

River Bend Station 2004 Regulatory Guide 1.21 4118/2005 Effluent and Waste Disposal Annual Report 2004 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from January 1, 2004 to December 31, 2004 Table 5 (continued)

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

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

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

This error is applicable to all waste types.

2. Estimates of Major Nuclides by Waste Stream Resins, Filters and Evaporator Dry Compressible Wastes, BottoMn, Etc. Contaminated Equipment, Other (Min 1%)Et.(i1%

Isotope % Etc(Min 1%)

Abundance(M 1%

Isotope % Isotope %

Abundance Abundance Mn-54 12.933 Mn-54 7.983 N/A N/A Fe-55 25.489 Fe-55 83.756 Co-60 42.369 CO-60 6.933 Ni-63 1.129 _

Zn-65 6.830 Cs-134 1.495 _

Cs-137 3.715 Ce-144 3.959 Determined by Measurement & Correlation.

Packaged in Strong, Tight Liners.

No Solidification Agent or Absorbent Used.

No Irradiated Components, Control Rods, Etc. were shipped in 2004.

29

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 Effluent and Waste Disposal Annual Report 2004 Year Solid Waste and Irradiated Fuel Shipments Reporting Period from January 1, 2004 to December 31, 2004 Table 5 (continued)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Truck Barnwell, SC 80 Truck Clive, UT B. No Irradiated Components, Control Rods, Etc. were shipped in 2004.

Irradiated Fuel Shipments Disposition Number of Shipments Mode of Transportation Destination 0 N/A N/A 30

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 TABLE 6 Effluent and Waste Disposal Annual Report 2004 Year Maximum Individual Doses Due to Noble Gas Releases Critical Sector Critical Distance Gamma Dose* Beta Dose *

(mrad) (mrad) 1st Quarter WNW 994m 1.51E-03 3.04E-03 2nd Quarter WNW 994m 3.24E-04 6.50E-04 3rd Quarter WNW 994m 1.15E-03 1.19E-03 4th Quarter WNW 994m 2.80E-02 1.59E-02 Annual Total WNW 994m 3.10E-02 2.08E-02

All age groups equally exposed TABLE 7 Effluent and Waste Disposal Annual Report 2004 Year Maximum Individual Doses Due To Gaseous Releases (H3, Radioiodine (I-131 & 1-133) and Particulates)

Significant Organ Dose (mrem)

Critical Critical Critical Critical Critical Sector Distance Age Group Organ Dose 1st Quarter WNW 994m Child Thyroid 2.20E-02 2nd Quarter WNW 994m Child Thyroid 2.37E-02 3rd Quarter WNW 994m Child .Thyroid .87E-02 4th Quarter WNW 994m Child Thyroid 3.63E-02 Annual Total WNW 994m Child Thyroid 1.01E-01 31

River Bend Station 2004 Regulatory Guide 1.21 411/2005o TABLE 8 Effluent and Waste Disposal Annual Report 2004 Year Maximum Individual Doses Due to Liquid Releases Critical Receptor: Edge of Initial Mixing Zone JTotal Body Dose (mrem) Significant Organ Dose (mrem)

Critical Dose Critical Critical Dose Age Age Organ 1st Quarter Adult O.OOE+00 Adult GI Tract O.OOE+00 2nd Quarter Adult 2.1 IE-04 Adult GI Tract 2.71E-03 3rd Quarter Adult 3.57E-04 Adult GI Tract 4.25E-03 4th Quarter Adult 7.39E-04 Adult GI Tract 1.05E-02 Annual Total Adult 1.12E-03 Adult GI Tract 1.46E-02 32

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 TABLE 9 Effluent and Waste Disposal Annual Report 2004 Year ASSUMPTIONS/PARAMETERS FOR DOSES TO A MEMBER OF THE PUBLIC INSIDE SITE BOUNDARY MEMBER OF LOCATION DISTANCE(l) SECTOR DURATION THE PUBLIC METERS (HR/YEAR)( 2 )

People Entering Site Without Alligator Bayou 2500 SW 4.OOE+01 Consent National Guard Activity Center 994 WNW 4.80E+02(3)

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

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

(3) National Guard/State Police are being evaluated, if applicable, for dose while stationed on site as members of the public. The adult age group is the only age group considered in this category.

33

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 TABLE 10 Effluent and Waste Disposal Annual Report 2004 Year DOSES TO MEMBERS OF THE PUBLIC ON SITE FROM GASEOUS RELEASES 2004 Dose calc Critical Total Skin Dose Annual based on Organ Body Dose Annual Duration Durations Dose Annual (mrem) Factor Annual (mrem)

(mrem)

Alligator 4.84E-05 1.86E-05 3.15E-05 4.57E-03 B ay ou _ __ _ __ _ _ _ __ _ __ _ _ _ __ _ _ __ _ _

National 6.5 8E.03 1.63E-03 2.76E-03 5.48E-02 Guard 34

2004 Regulatory Guide 1.21 4118/2005 8

River Bend Station Table 11 Effluent and Waste Disposal Annual Report 2004 Year Meteorological Data - Joint Frequency Tables 35

River Bend Station 2004 Regulatory Guide 1.21 4/118/2005 RIVER BEND STATION JOINT FREQUENCY TABLE ALL STABILITY CLASSES FROM 1/ 1/04 0:00 TO 3/31/04 23:00 PRIMARY SENSORS - 30 FOOT WIND SPEED (METERS/SECOND)

WIND .22- .S1- .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 8 7 8 27 38 59 64 0 0 0 0 0 211 NNE 6 9 7 32 35 52 9 1 0 0 0 0 151 NE 8 8 3 14 46 73 7 0 0 0 0 0 159 ENE 8 26 11 18 21 33 19 0 0 0 0 0 136 E 7 23 12 20 18 11 0 0 0 0 0 0 91 ESE 2 7 9 22 34 57 3 0 0 1 1 0 136 SE 0 3 13 61 92 101 12 0 0 0 0 0 282 SSE 0 1 4 20 15 55 39 13 0 0 0 0 147 S 0 0 8 10 23 45 47 8 0 0 0 0 141 SSW 1 1 3 13 9 30 21 1 0 0 0 0 79 SW 0 2 6 10 12 13 3 0 0 0 0 0 46 WSW 4 7 5 4 10 25 3 0 0 0 0 0 58 W 4 11 8 8 15 18 5 0 0 0 0 0 69 WNW 9 16 15 11 5 16 21 0 0 0 0 0 93 NW 2 22 18 20 13 25 44 0 0 0 0 0 144 NNW 4 18 6 18 14 39 61 0 0 0 0 0 160 TOTAL 63 161 136 308 400 652 358 23 0 1 1 0 2103 NUMBER OF CALMS: 0 NUMBER OF INVALID HOURS: 81 NUMBER OF VALID HOURS: 2103 TOTAL HOURS FOR THE PERIOD: 2184 36

River Bend Station 2004 Regulatory Guide 1.21 4/18/2005 RIVER BEND STATION JOINT FREQUENCY TABLE STABILITY CLASS A FROM 1/ 1/04 0:00 TO 3/31/04 23:00 PRIMARY SENSORS - 30 FOOT WIND SPEED (METERS/SECOND)