GNRO-2007/00023, Annual Radioactive Effluent Release Report (ARERR)

Annual Radioactive Effluent Release Report (ARERR)

ML071200166
Person / Time
Site:	Grand Gulf
Issue date:	04/30/2007
From:	Bottemiller C Entergy Operations
To:	Document Control Desk, NRC/NRR/ADRO
References
GNRO-2007/00023
Download: ML071200166 (27)

Text

Entergy Operations, Inc.

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-- Entwgy Waterloo Road P.0. Box 756 Port Gibson, MS 39150 Tel 601 437 6299 Charles A. Bottemiller GNRO-2007/00023 Manager Plant Licensing April 30, 2007 U.S. Nuclear Regulafory Commission Washington, D.C. 20555 ATTE NTI0N: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station (GGNS) 2006 Annual Radioactive Effluent Release Report (ARERR)

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29

Dear Sir or Madam:

Attached is the GGNS Annual Radioactive Effluent Release Report (ARERR) for the period January 1,2006 through December 31,2006. This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNS Technical Specification (TS) 5.6.3.

The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).

This letter does not contain any commitments. If you have questions or require additional information concerning these reports, please contact Mr. Richard Scarbrough at (601) 437-6978, or this office at (601) 437-6685.

Yours truly, CAB/MJ L attachments: 2006 Annual Radioactive Effluent Release Report cc: (See Next Page)

April 30, 2007 GNRO-2007/00023 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATTN: Dr. Bruce S. Mallet (w/2)

Regional Administrator, Region IV 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. Bhalchandra Vaidya, NRR/DLPM (WE)

ATTN: ADDRESSEE ONLY ATTN: U. S. Postal Delivery Address Only Mail Stop OWFN/ 0-7D1A Washington, DC 20555-0001

ENTERGY OPERATIONS, INC GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Jan~ary1,2006 - December 31,2006 env-t&ARERROl -1

TABLE OF CONTENTS SUBJECT PAGE INTRODUCTION 4 DETA1LED I NFORMA n 0N 5 A. Regulatory Limits 5

1. 10CFR20 Limits 5

a. Fission and Activation Gases 5

b. Radioiodines and Particulates 5

c. Liquid Effluents 5

2. 10CFR50, Appendix ILimits 6

a. Fission and Activation Gases 6

b. Radioiodines and Particulates 6

c. Liquid Effluents 6

3. 40CFR190 Limits 7 B. Effluent Concentrations 7

1. Airborne 7

2. Liquid 7 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8

1. For Fission and Activation Gases 8

2. For Particulates and Radioiodines 9

3. For Continuous Releases 9

4. For Batch Releases: Gases 9

5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10

1. Liquid 10

2. Gaseous 10 F. Unplanned Releases 11

1. Liquid 11

2. Gaseous 11 env-tdARERR01 - 2

TABLE OF CONTENTS (CONT'D)

SUBJECT PAGE G. Estimate of Total Error 11

1. Liquid 11

2. Gaseous 12

3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 12 I. Meteorological Data 12

1. Radioactive Effluent Monitoring Instrumentation Operability 12 K. Annual Sewage Disposal Summary 12 111. RADIAllON DOSE

SUMMARY

13 A. Water-Related Exposure Pathway 13 B. Airborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVEWASTE TREATMENT SYSTEM CHANGES 15 A. Offsite Dose Calculation Manual (ODCM) 15 B. Radioactive Waste Treatment Systems 15 LIST OF TABLES PAGE 1A Gaseous Effluents - Summation of All Releases 16 1B Gaseous Effluents - Elevated Releases 17 1c Gaseous Effluents - Ground-Level Releases - Continuous 18 1D Radioactive Gaseous Waste Sampling and Analysis Program 19 2A Liquid Effluents - Summation of All Releases 20 2B Liquid Effluents - Continuous and Batch Modes 21 2c Radioactive Liquid Waste Sampling and Analysis Program 22 3 Solid Radioactive Waste and Irradiated Fuel Shipments

-23 env-teC/ARERROl - 3

I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2006 is submitted in accordance with Offsite Dose Calculation Manual (ODCM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS) License No. NPF-29.

The monitoring of radioactive effluents is referenced in ODCM Appendix A, Sections 6.11 and 6.12.

Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM. Projected offsite doses were within the dose limits specified by the ODCM.

The summation of all gaseous releases during the reporting period is given in Table lA, while elevated releases and ground-level releases are given in Tables 1B and lC, respectively. Table 1D describes the radioactive gaseous sampling and analysis program implemented at GGNS.

The summation of all liquid releases during the reporting period is given in Table 2A, while continuous and batch mode releases are given in Table 28. Table 2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS.

Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.

The annual summary of meteorological data (joint frequency distribution) will be maintained on site in a file that shall be provided to the Nuclear Regulatory Commission (NRC) upon request. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3.

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11. DETAILED INFORMATION A. Regulatory Limits

1. 10CFR2O Limits

a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary shall be such that:

Dtb = average total body dose rate in the current year (mrem/yr)

- I

= X/Q Ci Ki Q I 500 mrem/yr D, = average skin dose rate in the current year (mrem/yr)

- 1

= X/Q Ci (Li + 1.1M i ) Q j I3000 mrem/yr where the terms are defined in the GGNS ODCM.

b. Radioiodines and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:

Do = average organ dose rate in current year (mrem/yr)

= ci W Pi QIi I 1500 mrem/yr where the terms are defined in the GGNS ODCM.

c. Liauid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x microcuries/ml total activity.

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11. DETAILED INFORMATION (CONT'D)

2. 10CFR50, Appendix I Limits

a. Fission and Activation Gases - The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that:

D = air dose due to gamma emissions from noble gases Y

= 3.17 x lo-' Ci Mi x/Q'Qi I 5 mrad/qtr I 10 mrad/yr D = air dose due to beta emissions from noble gases P

= 3.17 x lo-' Ci NiX/Q' Qi I 10 mrad/qtr I 20 mrad/yr where the terms are defined in the GGNS ODCM.

b. Radioiodines and Particulates - The dose to an individual from tritium, 1-131,1-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:

D, = dose to an individual from tritium, 1-131,1-133 and radionuclides in particulate form with half-lives greater than 8 days (mrem)

= 3.17 x lo-' Ci Ri W Qi I 7.5 mrem/qtr Any Organ 5 15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:

m b a u = C [ATau C At, Cil FI ] I 1.5 mrem/qtr Total Body i I=1 2 5 mrem/qtr Any Organ I 3 mrem/yr Total Body I 10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

env-tWARERRO1 - 6

3. 40CFR190 Limits Doses are calculated for Fission and Activation Gases; Radioiodines and Particulates; and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:

525 mrem/yr, Total Body or any Organ except Thyroid 175 mrem/yr, Thyroid 110 mrad y/qtr or 120 mrad y/yr, Fission and Activation Gases 120 mrad p/qtr or 140 mrad p/yr, Fission and Activation Gases 115 mrem/qtr or 130 mrem/yr, any Organ, Iodine and Particulates 13 mrem/qtr or 16 mrem/yr, Total Body, Liquid Effluents 110 mrem/qtr or 120 mrem/yr, any Organ, Liquid Effluents B. Effluent Concentrations

1. Airborne The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section 1I.A.l.a. I n this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.

2. Liquid The Effluent Concentration Limit (ECL) of radioactive materials in liquid effluents is limited by ten times the values in 10CFR20, Appendix B, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope.

C. Average Energy Not applicable for GGNS ODCM Appendix A.

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11. DETAILED INFORMATION (CONT'D)

D. Measurements and Approximations of Total Activity The following discussion details the methods used to measure and approximate total activity for the following:

11Fission and Activation Gases I Particulates 11 Tables 1D and 2C give sampling frequencies and minimum detectable sensitivity requirements for the analysis of gaseous and liquid effluent streams, respectively.

Values in the attached tables given as zero do not necessarily imply that the radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables 1D and 2C. For some radionuclides, lower detection limits than required may be readily achievable; when a radionuclide is measured below its stated detection limits, it is reported.

1. For Fission and Activation Gases The following noble gases are considered in evaluating gaseous airborne discharges:

[Kr-87 I Xe-133 1 Xe-135 I IKr-88 1 Xe-133m I Xe-138 I Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high-resolution germanium detectors. (See Table 1D for sampling and analytical requirements.) Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section II.A.1. of this report.

Only those radionuclides that are detected are used in this computation. During the period between grab samples, the amount of radioactivity released is based on the effluent monitor readings. Monitors are assigned a calibration factor based upon the last isotopic analysis, using the following relationship:

Ci = Ui +m where Ci = isotopic calibration factor for isotope i Ui = concentration of isotope i in the grab sample in pCi/ml.

m = net monitor reading associated with the effluent stream (determined at the time of grab sampling).

env-tWARERRO1 - 8

These calibration factors, along with the hourly effluent monitor values and flow rates, are entered into the laboratory computer where the release rates for individual radionuclides are calculated and stored. I f no activity is detected in the grab sample, the calibration factor defaults to a historical mixture of Kr-88, Xe-133, Xe-l35m, Xe-135, and Xe- 138.

2. For Particulates and Radioiodines The radioiodines and radioactive materials in particulate form to be considered are:

1 Other radionuclides with half I

3. For Continuous Releases Continuous sampling is performed on the continuous release points (Lea, Offgas/Radwaste Building Vent, Containment Purge, Fuel Handling Area Vent, Turbine Building Vent). Particulate material is collected by filtration.

Radioiodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and Strontium-89 and -90 as required. Gross alpha determinations are made using 2-pi gas flow proportional counter. Strontium-89 and -90 values are obtained by chemical separation and subsequent analysis using liquid scintillation techniques. Tritium concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table lD, "Radioactive Gaseous Waste Sampling and Analysis,"

(GGNS ODCM Appendix A, Table 6.11.4-1). Currently, Strontium analysis is performed by a qualified contract laboratory.

4. For Batch Releases: Gases The processing of batch type releases (from Containment Purge) is analogous to that for continuous releases.

env-tec/ARERROl- 9

11. DETAILED INFORMATION fCONTD]

5. For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:

Fe-59 I Ce-141 Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed using the computerized pulse height analysis system previously described. Aliquots of each pre-released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C.

Strontium-89, 90 and Iron-55 values are obtained by chemical separation and counting the separated strontium and iron using liquid scintillation techniques. Gross alpha determinations are made using 2-pi gas flow proportional counter. Tritium is determined using distillation and liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on the pulse height analyzer system. Currently, Iron and Strontium analyses are performed by a qualified contract laboratory.

E. Batch Releases

1. Liquid

2. Gaseous No batch releases were made during the report period.

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11. DETAILED INFORMATION [CONT'D)

F. Unplanned Releases

1. Liquid

a. Number of Releases: 2

b. Total Activity Released: 9.55E-01 Ci On Mar 2, 2006, an unplanned release of Turbine Building Cooling Water (TBCW) occurred.

Calculated activity released was 4.28E-7 Curie.

On April 12, 2006 an unplanned release from the Liquid Radwaste System occurred.

Calculated activity released was 9.55E-01 Ci. The dose and specific activities are included in the applicable sections of this report.

2. Gaseous

a. Number of Releases: 0

b. Total Activity Released: O.OOE+OO Ci G. Estimate of Total Error

1. Liquid The maximum errors are collectively estimated to be as follows:

Measurement OO/ 6.80E+01 6.50E+01 6.10E+01 9.20E+01 TOTAL O/o 7.30E+01 7.00E+01 6.60E+01 9.50E+01 i

Sampling errors include uncertainty associated with mixing, representative sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples and, for germanium detectors, the least-readily-detectable radioisotope. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

Total error is calculated by taking the square root of the sum of the squares of the individual errors.

env-WARERR01 - 11

11. DETAILED INFORMATION (CONT'D)

2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be as follows:

Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration.

Measurement errors include uncertainty associated with instrument calibration and preparation and counting of low-activity samples. Measurement and total errors are calculated by the same methods used for liquid effluents.

3. Solid Radioactive Waste See Table 3 for error terms.

H. Solid Radioactive Waste Shipments See Table 3 for shipment information.

I. Meteorological Data The data recovery for the reporting period was 97.1%. The predominant wind direction was from the South-Southeast approximately 8.5% of the time. The predominant stability class was class "E" approximately 31.3% of the time. Average wind speed during the reporting period was approximately 4.4 miles per hour.

The annual meteorological data (Hourly Average Data or Joint Frequency Distribution) will be maintained on site in a file that shall be provided to the NRC upon request.

3. Radioactive Effluent Monitoring Instrumentation Operability No reportable instances of inoperability occurred during the reporting period.

K. Annual Sewage Disposal Summary There were no sewage disposals in 2006.

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111. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 2006. Inspection of the values indicate that GGNS releases were within the 10CFR50, Appendix Idesign objectives.

Since there are no other fuel cycle facilities within 8 km of GGNS, 40CFR190 limits have also been met during this period.

All parameters listed were calculated in accordance with the GGNS ODCM.

A. Water-Related Exposure Pathways The values calculated in this section utilize the information provided in Tables 2A and 28 of this report and the calculational methodology of the ODCM.

Liquid Effluents Total body dose and critical organ doses are computed for the maximum exposed individual. The maximum dose contribution from liquid effluents is considered to occur in the adult age group via consumption of fish.

2006 Liquid Effluent Dose (mrem)

Liver I 6.82E-03 I 3.52E-02 I 2.83E-02 I 3.48E-02 I 1.05E-01 Thyroid I 6.82E-04 I 5.48E-03 I 1.04E-03 I 6.44E-04 I 7.79E-03 Kidney 2.63E-03 2.15E-02 1.41E-02 2.15E-02 5.95E-02 Lung 1.34E-03 4.15E-03 2.50E-03 8.16E-04 8.83E-03 GI-LLI 1.13E-03 7.00E-02 2.64E-02 2.54E-02 1.22E-01 Whole Body 5.08E-03 1.64E-02 1.72E-02 1.68E-02 5.55E-02 B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculational methodology of the ODCM. Dose and dose rates are computed for locations a t the site boundary or at unrestricted areas beyond the site boundary. Because members of the public may, on occasion, be found within the site boundary, locations within the site boundary were considered when selecting locations for dose calculations.

Consideration of site boundary locations as well as unrestricted areas within and beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation.

The most limiting location for a member of the public is used for the dose calculations.

During routine operations the dispersion and deposition factors used for dose calculations are from historical annual average meteorological data.

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111. RADIATION DOSE

SUMMARY

ICONT'D)

Organ Dose The maximum organ dose to a MEMBER OF THE PUBLIC (critical receptor) from radioiodines, tritium and particulates was calculated for this report using the most recent land use census and dispersion and deposition parameters from 2006 meteorological data. The critical receptor residence was determined to be located in the southwest sector at a distance of 1432 meters (0.89 miles) from the plant. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass/cow/meat and vegetation. There is no grass/cow/milk pathway within five miles of GGNS. I t was assumed that the age group receiving the maximum dose lived at the residence and that the receptor consumed food products that were raised or produced at the residence.

Averaae Total Bodv and Skin Dose Rate Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the south sector at a distance of 0.40 miles. This location corresponds to the highest annual average atmospheric dispersion factor for a location at an unrestricted area within the site boundary.

The total body and skin dose rates reported are the quarterly average of the maximum instantaneous dose rates determined daily during the reporting period and would represent the maximum possible dose rate received by members of the public.

Air Dose From Gamma and Beta Emissions Air doses from gaseous effluents were calculated for this report using dispersion parameters from the 2006 meteorological data. The highest dispersion factor for an unrestricted area was in the south sector within the site boundary, 644 meters (0.40 miles) from the plant.

Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosimeter (TLD) badges located at control locations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 2006 as net exposure normalized to 92 days.

2006 Airborne Effluent Dose (mrem)

I I

• Measurement units are mrad env-te/ARERROl - 14

IV. OFFSITE DOSE CALCULATION MANUAL/

RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. Offsite Dose Calculation Manual (ODCM)

No revisions to the ODCM were processed during the reporting period.

B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems in 2006.

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TABLE 1A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Fission and Activation Gases

2. Avg. Release Rate uCi/sec 2.263+00 6.933+00 1.003+01 1.143+01 7.683+00

3. Percent of TS Limit % 3.593-01 8.193-01 1.153+00 1.463+00 1.903+00 Iodine-131

1. Total Release Ci 2.573-04 1.883-02 2.743-04 3.223-04 1.963-02

2. Avg. Release Rate uCi/sec 3.303-05 2.393-03 3.443-05 4.053-05 6.233-04

3. Percent of TS Limit % 3.623-02 2.653+00 3.863-02 4.543-02 1.38E+OO

2. Avg. Release Rate uCi/sec 1.873-06 8.533-06 9.883-06 5.373-06 6.433-06

3. Percent of TS Limit % 6.433-03 1.573-01 1.993-02 1.473-02 9.903-02 r

I 2. Avg. Release Rate uCi/sec

3. Percent of TS Limit %

7.623-01 3.903-02 5.083-01 2.633-02 4.633-01 2.423-02 7.053-01 3.693-02 6.093-01 6.323-02 Gross Alpha Radioactivity

1. Total Release Ci 1.963-07 2.633-07 1.893-07 3.563-07 1.003-06

2. Avg. Release Rate uCi/sec 2.523-00 3.343-08 2.383-08 4.473-08 3.183-00 env-t@z/ARERROl - 16

TABLE 1B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNlT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2006 (Not Applicable - GGNS Releases Are Considered Ground-Level) env-t.ARERRO1 - 17

TABLE 1C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS AR-41 Ci 1.16E+01 1.463+01 1.78E+01 4.llE+01 KR- 8 5M Ci 1.25E+00 3.733+00 9.023+00 2.373+01 KR-87 Ci O.OOE+OO 0 .OOE+OO 0.003+00 2.103-03 KR-88 Ci 4.723-03 5.923-01 4.22E-02 9.253-01 XE-133 Ci 3.433-01 1.103+00 1.543-01 2.903+00 XE-135 Ci 2.543+00 9.643+00 1.31E+01 6.893+00 XE-135M Ci 1.84E+00 2.113+01 3.033+01 1.53E+01 XE-138 Ci 2.383-03 3.643+00 9.03E+00 4.883-04 Totals for Period.. . Ci 1.76E+01 5.443+01 7.943+01 9.083+01 Iodines 1-130 Ci O.OOE+OO 1.903-05 0.003+00 O.OOE+OO 1.903-05 1-131 Ci 2.573-04 1.883-02 2.743-04 3.223-04 1.963-02 1-132 Ci 1.493-04 1.963-02 2.583-03 1.953-03 2.43E-02 1-133 Ci 8.823-04 2.043-02 2.323-03 1.843-03 2.553-02 1-134 Ci 0.003+00 0.003+00 2.583-03 1.073-03 3.653-03 1-135 Ci 6.103-04 1.793-02 3.913-03 2.153-03 2.453-02 Totals for Period . . . Ci 1.903-03 7.683-02 1.173-02 7.333-03 9.773-02 Particulates Half Life >= 8 days BA-140 Ci 0.003+00 0.003+00 8.983-06 4.993-06 1.403-05 CO-58 Ci O.OOE+OO 0.003+00 2.833-06 2.813-07 3.113-06 CO-60 Ci 1.213-05 2.053-05 2.453-05 7.713-06 6.483-05 CR- 51 Ci O.OOE+OO 3.083-05 3.653-05 1.163-05 7.893-05 CS-137 Ci O.OOE+OO 1.123-06 0.003+00 O.OOE+OO 1.123-06 MN-54 Ci 0.003+00 1.743-06 O.OOE+OO 7.293-07 2.473-06 NP-239 Ci O.OOE+OO 7.013-06 4.733-06 7.243-06 1.903-05 RU-106 Ci 0.003+00 O.OOE+OO O.OOE+OO 5.183-06 5.183-06 SR-89 Ci 2.413-06 5.813-06 1.003-06 4.983-06 1.423-05 T o t a l s for Period . . . Ci 1.453-05 6.703-05 7.853-05 4.273-05 2.033-04 Tritium H-3 Ci 5.923+00 3.993+00 3.683+00 5.603+00 1.923+01 I ALPHA Ci 1.963-07 2.633-07 1.893-07 3.563-07 1.003-06 env-WARERR01 - 18

TABLE 1D ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY - DECEMBER 2006 Lower Limit Sampling Minimum Analysis Type of Activity Analysis of Detection Gaseous Release Type Frequency Frequency (LLD)

( uCi/ml)

A. (1) Radwaste Building 3 1 Days 3 1 Days Principal Gamma Ventilation Exhaust Grab Sample (f) Emitters (b,e) 1x104 H-3 1x10+

(2) Fuel Handling Area Continuous 7 Days (c) I-131 1x10-I2 Ventilation Exhaust (d)(f) Charcoal Sample 1-133 lxlolo (3) Containment Continuous 7 Days (c) Principal Gamma 1x10-I1 Ventilation Exhaust (dm Particulate Sample Emitters (e) (1-131, Others)

(4) Turbine Building Continuous 31 Days Gross Alpha 1x10-l1 Ventilation Exhaust Composite Particulate Sample Continuous 92 Days Sr-89, Sr-90 1x10-1 (d)(f) Composite Particulate Sample Continuous (f) Noble Gas Monitor Noble Gases Gross 1x10-6 Beta or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma 1x10~

Treatment Exhaust, Sample (9 Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10.~

Treatment A Sample (f) Emitters(e)

Exhaust, whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10~

Treatment B Sample (9 Emitters(e)

Exhaust, whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1.

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TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

1. Total Release Ci 8.153-04 5.163-02 1.043-02 4.513-03 6.743-02

2. Avg. Diluted Conc. uCi/ml 1.173-08 1.133-07 4.653-08 7.023-08 8.253-08

3. Percent of Limit  % 3.393-01 1.093+00 1.153+00 1.123+00 1.853+00 Tritium

2. Avg. Diluted Conc. uCi/ml

3. Percent of Limit  %

1.033-04 1.033+00 9.203-05 9.203-01 5.633-05 5.633-01 6.213-05 6.213-01 8.083-05 8.083-01 l Dissolved and Entrained Gases

1. Total Release Ci 2.023-03 1.393-02 5.083-03 5.883-04 2.163-02

2. Avg. Diluted Conc. uCi/ml 2.903-08 3.023-08 2.283-08 9.163-09 2.643-08

3. Percent of Limit  % 1.453-02 1.513-02 1.143-02 4.583-03 1.323-02 Volume of liquid waste liters 1.063+06 7.283+06 3.323+06 1.023+06 1.273+07 Volume of dil. water liters 6.873+07 4.523+08 2.203+08 6.323+07 8.043+08 env-tes/ARERROI - 20

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 2006 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AG- 110M Ci O.OOE+OO 5.753-05 1.113-05 1.013-05 7.873-05 BA-139 Ci 0.003+00 1.853-05 O.OOE+OO 0.003+00 1.853-05 BA-140 Ci 0.003+00 0.003+00 1.793-04 0.003+00 1.793-04 CE-141 Ci 0.003+00 5.293-05 8.363-06 2.133-06 6.343-05 CO-58 Ci O.OOE+OO 6.913-04 2.883-04 7.833-05 1.063-03 CO-60 Ci 7.003-05 2.143-03 1.653-03 1.043-03 4.893-03 CR-51 Ci 0.003+00 3.813-02 5.583-03 6.653-04 4.433-02 CS-134 Ci 1.103-05 0.003+00 3.163-05 6.383-06 4.903-05 CS-137 Ci 1.573-05 0.003+00 2.563-05 9.333-06 5.063-05 CU- 64 Ci O.OOE+OO 3.303-04 5.983-05 1.363-05 4.043-04 m-55 Ci 6.673-04 4.143-03 0.003+00 5.893-04 5.403-03 m-59 Ci 0.003+00 1.993-04 1.093-04 2.633-05 3.343-04 1-131 Ci 2.643-06 5.853-05 0.003+00 1.083-05 7.203-05 1-133 Ci 0.003+00 4.143-05 0.003+00 0 .OOE+OO 4.143-05 LA-140 Ci O.OOE+OO 4.663-04 9.183-04 1.693-04 1.553-03 MN-54 Ci 4.183-05 4.083-03 1.033-03 7.343-04 5.893-03 NB-95 Ci 0.003+00 3.223-05 1.133-05 0 . OOE+OO 4.353-05 NP-239 Ci O.OOE+OO 2.843-04 2.263-05 2.893-05 3.363-04 RU-103 Ci 0.003+00 1.573-05 0.003+00 0.OOE+OO 1.573-05 RU-106 Ci O.OOE+OO 0.003+00 O.OOE+OO 3.773-05 3.773-05 SB-125 Ci 6.893-06 0.OOE+OO 0.003+00 0.003+00 6.893-06 SR- 89 Ci O.OOE+OO 0.003+00 0.003+00 6.653-05 6.653-05 SR- 92 Ci 0.003+00 2.373-06 0.003+00 0 .OOE+OO 2.373-06 TC-99M Ci 0.003+00 9.443-05 5.823-06 0.003+00 1.003-04 TE-132 Ci 0.003+00 1.863-05 2.723-06 0 .OOE+OO 2.133-05 ZN- 65 Ci 0.003+00 8.283-04 4.553-04 1.033-03 2.313-03 ZN-69M Ci 0.003+00 9.173-06 6.393-06 0 .OOE+OO 1.563-05 ZR- 95 Ci 0.003+00 1.503-05 0.003+00 0.003+00 1.503-05 Totals for Period... Ci 8.153-04 5.173-02 1.043-02 4.523-03 6.743-02 Tritium 1 H-3 Ci 7.193+00 4.223+01 1.263+01 3.993+00 6.603+01 I Dissolved and Entrained Gases XE-131M Ci 0.003+00 O.OOE+OO 1.433-04 O.OOE+OO 1.433-04 XE-133 Ci 1.313-03 1.073-02 3.373-03 4.683-04 1.583-02 XE-133M Ci 2.683-05 5.893-05 4.183-05 0.003+00 1.283-04 XE-135 Ci 6.043-04 3.163-03 1.533-03 1.203-04 5.493-03 Totals for Period . . . Ci 2.023-03 1.393-02 5.083-03 5.883-04 2.163-02 Gross Aloha Radioactivitv

~

ALPHA Ci O.OOE+OO 1.073-04 1.433-05 O.OOE+OO 1.213-04 Totals for Period . . . Ci 0.003+00 1.073-04 1.433-05 0.003+00 1.213-04 env-tec/ARERROl - 2 1

TABLE 2C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY - DECEMBER 2006 Lower Limit Sampling Minimum Analysis Frequency Frequency Prior to Release Prior to Release Each Batch Each Batch Emitters (d) 1-131 Prior to Release 31 Days Dissolved and 1x10'~

One Batch /M Entrained Gases Prior t o Release 31 Days Each Batch Composite (b)

Prior t o Release 92 Days Each Batch Prior t o Release Composite (b)

Prior to Release Fe-55 Principal Gamma I lxlo-b Each Blowdown Each Batch Emitters (d NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.

env-twARERR01 - 22

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2006 A. SOILD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

I I

~

Class Est. Total Error

1. Type of Waste Unit Class A Class B o,/

a. Spent resins, filter sludges, O.OOE+OO O.OOE+OO evaporator bottoms, etc. O.OOE+OO O.OOE+OO

b. Dry compressible waste, m3 O.OOE+OO O.OOE+OO contaminated equipment, etc. -

Ci O.OOE+OO O.OOE+OO

c. Irradiated componants, m3 O.OOE+OO O.OOE+OO control rods, etc.

-. -Ci O.OOE+OO O.OOE+OO I

d. Other: Dry compressible m3 3.75E+00 O.OOE+OO I.00E+01 8.83E+02 waste, contaminated equipment, 2.61 E+03 I.00E+01 Ci 2.1 6E+02 O.OOE+OO spent resins for volume reduction

2. Estimate of Major Nuclide Composition ( by type of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

1 Isotope (greater than 0.0G0) I Percent I Curies 1

b. Dry compressible waste, contaminated equipment, etc.

I I Isotope (greater than 0.01 %)

NONE Percent I Curies l

c. Irradiated components, control rods, etc.

I 1 Isotope (greater than 0.01%) Percent I Curies I env-teg'ARERRO1 - 23

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2006 (Cont)

d. Other: Dry compressible waste, contaminated equipment, spent resins for volume reduction.

Isotope (greater than 0.01%) I Percent I Curies CO-58 3.94E-02 1.88E+00 CO-60

_ _ _ _ _ ~ ~

3.67E+00 1.75E+02 Cr-51 1.20E-01 5.72E+00 CS-I34 1.49E-01 7.12E+00 CS-I37 1.58E-01 7.51 E+OO Fe-55 8.76E+01 4.17E+03 Fe-59 8.52E-02 4.06E+00 H-3 3.49E-02 1.66E+00 Mn-54 I 5.97E+00 I 2.85E+02 Ni-63 I 3.40E-01 I 1.62E+01 Sr-90 I 5.99E-02 I 2.85E+00 Zn-65 I 1.78E+00 I 8.47E+01

3. Solid Waste Dispostion Number of Mode of Destinations Name City Shipments State Transportation 11 Duratek, LLC OakRidge TN Truck I GTS Duratek-Gallaher Road Facility Oak Ridge TN Truck II 1 I RACE. LLC I MemDhis 1 TN I Truck 11 II 26 I Studsvik I Erwin I TN I Truck 11 env-tWARERRO1 - 24

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2006 (Cont)

3. Solid Waste Dispostion (Cont)

NRC Disposal Number of Description Waste Type Description Class Volume(ftA3) Containers A 96 B-25 BOX 8 DAW-U-NA B25 BOX A 199.4 210 LINER 8 BR-D-NA SRT 210 Powdex A 18 CPSIRWCU-B (Studsvik) 199.4 (Studsvik)

A 1 199.4 I 210 Liner I I I GAC Media A 202 RWE ES-210 3 BR-D-NA SRT (RWE liner)

A 1280 20' SEALAND 17 DAW-U-NA 20FT SL B 132.4 EL142 Poly HIC 1 RWCU-A A 1290 20' SEALAND 1 Oil Drum SEALAND DRTK Shielded A 1280 1 DRTK Shielded SEALAND SEALAND B. Irradiated Fuel Shipments (Disposition)

NUMBER OF SHIPMENTS 1 MODE OF TRANSPORTATION DESTINATION None N/A N/A C. Annual NUMBER OF AVERAGE Co-60 AVERAGE Mn-54 SHIPMENTS GALLONS ACTIVITY (pCi/kg) ACTIVITY (pCi/kg)

None N/A N/A N/A env-tes/ARERROl - 25