GNRO-2011/00030, Annual Radioactive Effluent Release Report (ARERR)

From kanterella
Revision as of 20:13, 10 July 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Annual Radioactive Effluent Release Report (ARERR)
ML111190097
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/28/2011
From: Perino C
Entergy Operations
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
GNRO-2011/00030
Download: ML111190097 (32)
v • d • e


Text

GNRO-2011/00030 April 28, 2011 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555

Subject:

Grand Gulf Nuclear Station (GGNS)2010 Annual Radioactive Effluent Release Report (ARERR)Grand Gulf Nuclear Station (GGNS), Unit 1 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, 2010 through December 31,2010.This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNSTechnicalSpecification (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.CLP\RRJ

Attachment:

1.Annual Radioactive Effluent Release Report cc: (See Next Page)

GNRO-2011/00030 2 of 2 cc: WITHOUT ATTACHMENT NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S.Nuclear Regulatory Commission Region Administrator, Region IV ATTN: Mr.Elmo Collins, Jr.612 Lamar Blvd, Suite 400 Arlin ton, TX 76011-41 U.S.Nuclear Regulatory Commission ATTN: Mr.Alan Wang, NRR/DORL Mail Stop OW FN/8B1 Washin ton, DC 20555-0001 1/00030 Attachment 1 Attachment 1 to GNRO-2011/00030 Annual Radioactive Effluent Release Report G , F NUCLEAR S ON January 1,2010-December 31,2010 s Reviewed By/env-teciARERR01

-1 Approved By TABLE OF CONTENTS SUBJECT L INTRODUCTION II.DETAILED INFORMATION PAGE 4 A.R O*1 Ily 5 1.Limits a.and Activation Gases b.Radioiodines, Tritium and Particulates c.Liquid cflucllls 10CFR50, Appendix I Limits a.Fission and Activation Gases b.R::trll1 illcl'les, Tritium and Particulates c.Liquid Effluents 3.40CFR190 Limits B.Effluent Concentrations 1.Airborne 2.Liquid C.Average Energy D.Measurements and Approximations of Total Activity 1.For Fission and Activation Gases 2.For Particulates and Radioiodines 3.For Continuous Releases 4.For Batch Releases: Gases 5.For Batch Releases: Liquid Effluents E.Batch Releases 1.Liquid 2.Gaseous F.Abnormal Releases 1.Liquid 2.Gaseous env-tec1ARERR01

-2 6 6 6 6 7 7 7 7 7 8 8 9 9 9 10 10 10 10 11 11 11 TABLE OF (CONT'D)SUBJECT G.Estimate of Total Error L Liquid 2.Gaseous PA(iE 12 12 12 3.Solid Radioactive Waste H.Solid:::tdif)::tdl WasteIt'll'<': L Mctcul.1 Data J.Radioactive Fffll1f'.n Monitoring K.Annual S,-, vVU 5'-'Dl;;;,pf)<.:::ll C'y III.RADIATION DOSE

SUMMARY

A.Water-Related Pathway B.Airborne-Related FXrlll'"IC Pathway.IUIClIli::llIUII 13 13 13 13 14 14 14 IV.OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A.Offsite Dose Calculation Manual (ODCM)B.Radioactive Waste Treatment Systems LIST OF TABLES 17 17 17 PAGE IA IB IC ID 2A 2B 2C 3 Gaseous Effluents Summation of All Releases Gaseous Effluents Elevated Releases Gaseous Effluents-Ground-Level Releases Continuous Radioactive Gaseous Waste Sampling and Analysis Program Liquid Effluents Summation of All Releases Liquid Effluents-Continuous and Batch Modes Radioactive Liquid Waste Sampling and Analysis Program Solid Radioactive Waste and Irradiated Fuel Shipments ATTACHMENTS Attachment I NEI Groundwater Protection Initiative Sample Results 18 19 20 21 22 23 24 25 PAGE 27 env-tec/ARERR01

-3 I.Annual Radioactive Effluent Report (ARERR)for the period of January I through J-'''''''''UL''

31, 20 I 0 is submitted in accordance with Technical Specifications, Section 5.6.3 of Gulf Nuclear Station (GGNS)No.NPF-29.The monitoring of radioactive

"""'''''"

in Offsite Dose Calculation Manual (ODCM)Appendix A, Sections 6.11 and 6.12.u'h.rvr14'J" O:LSC)larJges at GGNS are considered ground-level releases.All liquid and airborne to the environment were analyzed in accordance with ODCM requirements.

All effluent were within the concentration and total limits specified by the ODCM.Projected were within the dose limits specified by the ODCM.The summation of all gaseous releases during the reporting period is given in Table IA.Elevated are not applicable at GGNS as reported in Table lB.The summation of all ground-level gaseous release during the reporting period is given in IC.ID describes the radioactive gaseous sampling and analysisprogramimplemented at GGNS.The summation of all liquid releases during the reporting period is given in Table 2A The continuous and batch mode liquid releases are given in Table 2B.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.Groundwater Protection Initiative well sample tritium results not included in the AREOR are included as attachment 1.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.env-tec1ARERR01

-4 II.DETAILED INFORMATION 1.10CFR20 Limits a.current==rate in current year b.ODCM.

rate limit the C'...T"l""....llnrr in particulate form rate in current (mremlyr)=W Pi Q\:5 1500 mremlyr where the terms are defined in the GGNS ODCM.c.-The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not at any time ten times the values specified in lOCFR20, 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 to2x 10-4 microcuries/ml total activity.env-tec/ARERR01

-5 II.DETAILED INFORMATION (CONT'D)l J.lJlkJ\.<UUlA I a.D=air y The dose from noble gases in gaseous effluents to boundary shall be such that: (1""UVOY'Y'

"'-"UI>J,>JIV'I>J from noble 3.17 X M i X/Q'Qi 5 mradlqtr::;10 mradlyr=air due to beta emissions from noble gases::;20 mradlyr where the terms are defined in the GGNS ODCM.b.-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 p 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 10-8 Li R i W'Qi:S;7.5 mremlqtr Any Organ:s;15 mremlyr Any Organ where the terms are defined in the GGNS ODCM.env-teciARERR01

-6 c.

-The dose from radioactive materials in liquid effluents shall be such that: ill D Tau=L[A iTau L Cit F 1]:s;1.5 mremlqtr Total Body 1=1:s;5 mremlqtr Any Organ:s;3 mremlyr Total Body:s;10 mremlyr Any Organ where the terms are defined in the GGNS ODCM.

II.DETAILED IN}1'ORMATION (CONT'D)"'rtt"n"".,c contained in Sections exc:eotlon that the limits are: Total Body or any'5.75 mrem/yr, Thyroid'5.10 mrad y/qtr or'5.20 mrad Fission and'5.20 mrad p/qtr or'5.40 mrad'5.15 mrem/qtr or'5.30 mrem/yr, any Organ, Iodine and Particulates

'5.3 mrem/qtr or'5.6 mrem/yr, Total Body, Liquid LdJJU\."IL,J

'5.10 mrem/qtr or'5.20 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 ILA.1.a.In 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.env-lec1ARERR01

-7 II.DETAILED INI 4 0RMATION (CONT'D)D.Measurements and of Total details the methods used to measure and total activity Tables ID and give frequencies and Lower Limit of Detection requirements for the of and liquid effluent respectively.

Values in the attached tables as zero do not imply that the radio nuclides were not A zero that radionuclide was not present at levels than the shown in Tables1D and 2C.For some radionuclides, lower detection than may be when a radionuclide is measured below its detection limits, it is 1.For Fission and Activation Gases The following noble gases are considered in evaluating airborne discharges:

Kr-88 Xe-135 Xe-133 Xe-138 Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high-resolution germanium detectors.(See Table ID for sampling and analytical requirements.)

Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section ILA.I.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:

where C j::: isotopic calibration factor for isotope i U j concentration of isotope i in the grab sample in m=net monitor reading associated with the effluent stream (determined at the time of grab sampling).

env-tec/ARERR01

-8 II.DETAILED INFORMATION (CONT'D)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.If no activity is detected in the grab sample, the calibration defaults to a historical mixture of Kr-88, Xe-133, Xe-135m, Xe-135, and Xe-2.For Particulates and Radioiodines The radioiodines and radioactive materials in particulate form to be considered are: Zn-65 Mn-54 Fe-59 Co-58 Co-60 Sr-89 Sr-90 Mo-99 Cs-134 Cs-137 Cc-141 Cc-144 1-131 1-133 Other radionuclides with half lives greater than 8 days.3.For Continuous Releases Continuous sampling is performed on the continuous release points when releasing (i.e., 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 a 2-pi gas flow proportional counter.Strontium-89 and-90 values are obtained by chemical separation and subsequent counting analysis using gas flow proportional 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 1D,"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.

Carbon-14, C-14, activity of 9.5 Curies released per year in gaseous form was obtained from GGNS FSAR Table 11.3-9.C-14 curies are reported in Tables 1A and1C of this report as the release is considered continuous throughout the year.4.For Batch Releases: Gases The processing of batch type releases (from Containment Purge or Turbine Building Occasional Release Point)are analogous to that for continuous releases.en v-tec/A RERRO 1-9 II.when liquid ,:J'VL""LU.,"VL pi gas proportional counter.scintillation are"0""'''"

techniques and then counting on the pulse Currently, Iron and Strontium analyses are performed by a qualified contract laboratory.

E.Batch Releases 1.Liquid 4th Qtr 9 101 2.Gaseous No batch releases occurred during the report period.env-tecIARERR01-10 II.F.Abnormal 1.a.Number Releases: b.Total Released: o O.OOE+OO Ci a.Number Releases:Total H f'TlH1TH 5.26E-Ol Ci env-tec/ARERR01-11 TBV, iodine and particulate, I&P, sampler was back into the sample stream so the sample collected for two to This is contrary to ODCM Table 6.11.4-1 requirements for The filter and were analyzed on 7/6/10 and results were in the Results were compared with results from samples before and after the affected The concentrations from the samples compared were used for worst case ac'tl1Yt"t Estimated total particulate and iodine activity released was 4.00E-Ol Ci.Doses and are included in the applicable of this report.On 3/11/10, a small amount of oil was noticed on the TBV Particulate filter.The filter and associated cartridge were changed out and analyzed.The samples had collected for 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> from 3/9/10 to 3/11/10 when the oil was observed.A second set of sample media was in place in the alternate sample location which was also changed out and analyzed.Results from both sets of filters and cartridges were combined and the higher concentrations from each were used as a worst case estimate of the release concentrations.

Estimated total particulate and iodine activity released was 1.26E-Ol Ci.Doses and specific activities are included in the applicable sections of this report.

G.II.DETAILED INFORMATION (CONT'D)Total Error I.Liquid The maximum errors are collectively estimated to be as follows: Tritium 2.60E+Ol 6.50E+Ol 7.00E+Ol Dissolved&Entrained 2.60E+Ol 6.IOE+OI 6.60E+OI Gross 2.60E+Ol 9.20E+OI 9.50E+OI Sampling errors include uncertainty associated with mixing,representativesampling and 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 detectable radioisotope.

Cal ibration 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.2.Gaseous The maximum errors (not including sample line loss)are collectively estimated to be as follows: Fission&Activation Products 3.20E+Ol 6.lOE+Ol 6.90E+Ol Iodine 2.30E+OI 6.70E+Ol 7.lOE+0l Particulate 2.20E+Ol 6.50E+Ol 6.90E+Ol Al ha 2.20E+Ol l.OlE+02 1.03E+02 Gross Tritium 2.30E+Ol 6.20E+Ol 6.60E+Ol 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 Estimated Total Error for all Waste Types:+/-25%.Sampling errors include uncertainty associated with mixing and representative sampling.env-tecIARERR01-12 II.H.L<:irllrVl,4>lnra.

Waste:snJlpUlents

........r'r1r.,nr\ln'llnl wind was....r,::,r1Anr\ln'll-.t stability class was was Data or Joint Distribution) to the NRC upon requefit.J.K.Annual:,,\e\W::Hre Disposal;:')UffiI10ay'V occurred during reporting period.env-tec/ARERR01-13 III.RADIATION DOSE

SUMMARY

below the annual summary offsite doses attributable to GGNS of the values indicate that GGNS releases were within the 10CFR50, Appendix I Since there are no other fuel this JU\Vjl.'U'"",,, within 8 km of GGNS, 40CFR190 limits were also met A.Water-Related

,-,v"n'J r'L"U C'",J1[P'Pathways The calculated in this section utilize the information provided in Tables 2A and 2B of and the calculation methodology of the ODCM.Total body dose and critical organ doses are computed for the maximum""V'J,:".:U individual.

The maximum dose contribution from liquid effluents is considered to occur in the adult age group via consumption of fish.Kidney Lung GI-LLI Whole Body 2010 Li uid Et11uent Dose mrem)Otr 2nd Otr 3rd Otr 4th Otr 2.36e-03 1.61e-02 3.65e-04 1.25e-03 4.15e-03 1.18e-03 4.45e-03 6.84e-04 1.92e-03 7.66e-04 3.51e-04 1.98e-03 2.61e-02 9.02e-04 2.76e-03 1.03e-03 2.91e-03 8.82e-04 2.90e-04 1.36e-03 3.17e-02 1.15e-03 5.50e-03 2.8ge-03 2.22e-02 9.22e-04 2.14e-03 TOTAL 2.0ge-2 5.54e-2 3.73e-3 3.31e-2 5.17e-3 4.12e-2 2.92e-2 B.Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and1C of this report and the calculation methodology of the ODCM.Carbon-14 doses were calculated using Electric Power Research Institute, EPRI, methodology and calculation software which was validated on site using Regulatory Guide 1.109.Dose and dose rates are computed for locations at 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, two fishing lakes, the recreational vehicle laydown area, and the GGNS Energy Services Center locations were also evaluated.

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.

Doses for a Member of the Public are computed based on land use census and the most limiting location is used.During routine operations the dispersion and deposition factors used for dose calculations are from historical annual average meteorological data.env-teciARERR01-14 III.RADIATION DOSE

SUMMARY

(CONT'D)The maximum organ dose to a MEMBER OF THE PUBLIC (critical receptor)from radioiodines, tritium and particulates was calculated for report the most recent land use census and dispersion and deposition parameters from 2010 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.It 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.

This dose is documented in the following table with C-14 organ doses added and critical organ dose displayed as a separate entry.Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the southwest sector at a distance of 1368 meters (0.85 miles)from the plant.This location corresponds to the highest annual average atmospheric dispersion factor for a location at or 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 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 2010 meteorological data.The highest dispersion factor for an unrestricted area was in the southwest sector at the site boundary, 1368 meters (0.85 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 2010 as net exposure normalized to 92 days.env-tec/ARERR01-15 Ill.is a naturally of carbon.Nuclear weapons testing in the and increased the amount of C-14 in the atmosphere.

C-14 is also incommercialnuclear reactors, but the amounts produced are much less than those vu,,,""',",'

naturally or weapons In recent years, the analytical methods for 14 Coincidentally the radioactive effluents from commercial plants have also decreased to the point that C-14 has emerged as a principal radionuclide in effluents.

The only dose pathway to a member of the public from C-14 release is through consumption of incorporates C-14 in form of carbon dioxide, C02, photosynthesis so were calculated based on C02 fraction.A C02 fraction of 95%was chosen based on EPRI Technical Report 1021106,"Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents".

Additionally, C02 is dispersed as a gas so atmospheric dispersion factors were applied.dose is calculated for maximum organ dose to a MEMBER OF THE PUBLIC and added to other organ dose for comparison to limits in the following table.env-tec1ARERR01

-16 III.RADIATION DOSE

SUMMARY

(CONT'D)*Measurement units are mrad IV.OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A.Offsite Dose Calculation Manual (ODCM)No revisions to the ODCM were issued during the reporting period.B.Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseousradwastetreatment systems in 2010.env-tec1ARERR01

-17 TABLEIA REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases 1.Total Release Ci 2.Avg.Release Rate uCi/sec 3.Percent of TS Limit 1.44E+02 1.85E+01 3.05E+OO 2.75E+02 3.50E+01 1.SOE+OO 7.17E+01 9.02E+OO 1.59E+OO 2.S2E+01 3.55E+OO 5.10E-01 5.19E+02 1.65E+01 3.47E+OO Iodine-131 1.Total Release Ci 2.Avg.Release Rate uCi/sec 3.Percent of TS Limit%1 S4E-03.37E-04 3.S2E-01 9.S2E-04 1.25E-04 2.04E-01 1.74E-05 2.1SE-06 3.61E-03 2.34E-05 2.94E-06 4.S5E-03 2.86E-03 9.0SE-05 2.97E-01 Particulates Half Life>=S aays 1.Total Release Ci 2.Avg.Release Rate uCi/sec 3.Percent of TS Limit 7.97E-06 1.03E-06 2.S5E-02 3.31E-05 4.21E-06 2.41E-02 3.47E-05 4.36E-06 1.29E-03 1.22E-05 1.54E-06 7.91E-03 S.SOE-05 2.79E-06 2.7SE-02 Tritium 1.Total Release Ci S.34E+00 4.90E+OO 5.77E+OO 4.34E+00 2.34E+01 2.Avg.Release Rate uCi/sec 1.07E+00 6.23E-01 7.26E-01 5.47E-01 7.40E-01 3.Percent of TS Limit%9.65E-02 5.66E-02 6.67E-02 5.03E-02 1.35E-01 Carbon 14 1.Total Release Ci 2.34E+OO 2.37E+OO2.39E+OO2.39E+OO 9.50E+OO 2.Avg.Release Rate uCi/sec3.01E-013.01E-013.01E-01 3.01E-01 3.01E-01 Gross Alpha 1.Total Release Ci 1.02E-OS 2.95E-OS 2.6SE-OS S.21E-OS 1.49E-07 2.Avg.Release Rate uCi/sec 1.31E-09 3.75E-09 3.37E-09 1.03E-OS 4.71E-09 en v-tec/A RERRO 1 18 env-teciARERR01

-19 TABLEIB ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 GASEOUS EFFLUENTS ELEVATED RELEASES JANUARY DECEMBER 2010 (Not Applicable GGNS Releases Are Considered Ground-Level)

TABLEIC ENTERGY OPERATIONS, GRAND GULF NUCLEAR STATION UNIT 1 GASEOUS EFFLUENTS GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases AR-41 Ci KR-85M Ci KR-87 Ci KR-88 Ci KR-89 Ci XE-133 Ci XE-133M Ci XE-135 Ci XE-135M Ci XE-137 Ci XE-138 Ci Totals for Period...Ci I-131 Ci I-133 Ci I-135 Ci Totals for Period...Ci 2.43E+01 3.34E+00 5.58E+00 1.12E+00 3.44E+01 4.57E+01 6.23E+00 2.19E+00 5.18E-01 5.46E+01 1.31E+01 1.97E-01 6.37E-03 1.04E-01 1.34E+01 2.91E+01 5.42E+00 3.04E-02 5.81E-02 3.46E+01 O.OOE+OO O.OOE+OO 1.05E+01 O.OOE+OO 1.05E+01 1.82E+01 1.20E+02 8.10E-01 1.47E+00 1.40E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+00 1.16E+02 2.65E+00 2.74E+00 1.24E+02 7.15E+00 1.65E+01 8.55E+00 6.13E+00 3.83E+01 O.OOE+OO O.OOE+OO 2.53E+01 5.31E+00 3.06E+01 3.45E+00 8.02E+00 1.60E+01 1.08E+01 3.83E+01------------------------1.44E+02 2.75E+02 7.17E+01 2.82E+01 5.19E+02 Iodines 1.84E-03 9.82E-04 1.74E-05 2.34E-05 2.86E-03 2.49E-03 2.15E-03 1.18E-04 1.50E-04 4.91E-03 6.26E-04 3.24E-04 O.OOE+OO O.OOE+OO 9.50E-04---------------------_._-4.96E-03 3.46E-03 1.35E-04 1.73E-04 8.72E-03 Particulates Half Life>=8 days BA-140 Ci 2.19E-06 7.92E-06 2.35E-05 4.79E-06 3.84E-05 CE-141 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-58 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.09E-08 3.09E-08 CO-60 Ci O.OOE+OO 4.35E-06 7.22E-07 O.OOE+OO 5.07E-06 CR-51 Ci O.OOE+OO 9.01E-06 O.OOE+OO O.OOE+OO 9.01E-06 CS-136 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CS-137 Ci O.OOE+OO O.OOE+OO 6.61E-07 2.42E-07 9.03E-07 FE-59 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 Ci O.OOE+OO 3.31E-06 O.OOE+OO O.OOE+OO 3.31E-06 RU-106 Ci 2.68E-06 O.OOE+OO 3.72E-06 O.OOE+OO 6.39E-06 SR-89 Ci 3.11E-06 4.55E-06 6.09E-06 5.47E-06 1.92E-05 SR-90 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.68E-06 1.68E-06 ZN-65 Ci O.OOE+OO 3.95E-06O.OOE+OOO.OOE+OO 3.95E-06--------------------------------Totals for Period...Ci 7.97E-06 3.31E-05 3.47E-05 1.22E-05 8.80E-05 Other H-3 Ci 8.34E+00 4.90E+00 5.77E+00 4.34E+00 2.34E+01 C-14 Ci 2.34E+00 2.37E+00 2.39E+00 2.39E+00 9.50E+00 Gross Alpha Ci 1.02E-08 2.95E-08 2.68E-08 8.21E-08 1.49E-07 en v-tec/A RERRO 1-20 TABLEID OPERATIONS, INC.STATION UNIT I'JU"")'u,, Waste Sampling and Analysis Program JANUARY DECEMBER 2010 Gaseous Release Type A.(1)Radwaste Building Ventilation Exhaust (2)Fuel Handling Area Ventilation Exhaust (3)Containment Ventilation Exhaust (4A)Turbine Building Ventilation Exhaust (4B)Turbine Building Occasional Release Point (when in service)B.(1)Offgas Post Treatment Exhaust t whenever there is flow (2)Standby Gas Treatment A Exhaust t whenever there is flow (3)Standby Gas Treatment B Exhaust t whenever there is flow Sampling Frequency 31 Days Grab Sample (f)Continuous (d)(f)Continuous (d)(f)Continuous (d)(f)Continuous (d)(f)Continuous (f)31 Days Grab Sample (f)31 Days Grab Sample (f)31 Days Grab Sample (f)Minimum Analysis Frequency 31 Days 7 Days (c)Charcoal Sample 7 Days (c)Particulate Sample 31 Days Composite Particulate Sample 92 Days Composite Particulate Sample Noble Gas Monitor 31 Days 31 Days 31 Days Type of Activity Analysis Principal Gamma Emitters (b.e)H-3 1-131 1-133 Principal Gamma Emitters (e)(1-131 t Others)Gross Alpha Sr-89 t Sr-90 Noble Gases Gross Beta or Gamma Principal Gamma Emitters (e)Principal Gamma Emitters(e)

Principal Gamma Emitters(e)

Lower Limit of Detection (LLD)(uCilml)8 1x10-4 1X10-6 1x10-12 1x10-10 1x10-11 1 x1 0-11 1x10-11 1x10-6 1x10-4 b.An"l shall also be performed following startup from cold shutdown, or a THERMAL POWER exceeding 15 percent of the RATED THERMAL POWER within a one hour period.This requirement does not apply if: (1)routine analysis required by the Surveillance Requirements of Leo 3.4.8 shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3;and (2)the noble gas monitor shows that effluent activity has not increased more than a factor of 3.env-tec/ARERR01

-21 of be Actions fication status which the LLD an each dose or dose rate calculation low rate to the associated Conditions and LCO 6.3.10 may be for up to 1 87, Kr-88, Xe-133, Xe-133m, , and Mn-54, Fe-59,Co-58,Co-60, Zn-65, Mo-99, Cs-134, emissions.

This ist not mean TABLE2A ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS SUMMATION OF ALL RELEASES REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products 1.Total Release Ci 2.Avg.Diluted Cone.

3.Percent of Limit%5.98E-04 4.22E-09 1.93E-Ol 1.08E-02 2.40E-08 1.48E+00 1.67E-03 6.97E-09 6.15E-02 2.12E-03 3.32E-08 1.42E-Ol 1.52E-02 1.70E-08 9.74E-Ol Tritium 1.Total Release Ci 2.Avg.Diluted Cone.

3.Percent of Limit%9.94E+00 7.02E-05 7.02E-Ol 3.22E+Ol 7.19E-05 7.19E-Ol 1.16E+Ol 4.84E-05 4.84E-Ol 3.28E+00 5.12E-05 5.12E-Ol 5.70E+Ol 6.38E-05 6.38E-Ol Dissolved and Entrained Gases 1.Total Release Ci 2.Avg.Diluted Cone.

3.Percent of Limit%1.11E-03 7.83E-09 3.92E-03 1.36E-03 3.02E-09 1.51E-03 6.84E-04 2.86E-09 1.43E-03 2.21E-04 3.46E-09 1.73E-03 3.37E-03 3.77E-09 1.89E-03 Gross Alpha Radioactivity al Release ci O.OOE+OO O.OOE+OOO.OOE+OOO.OOE+OO O.OOE+OO Volume of liquid waste liters 1.76E+06 4.88E+06 2.89E+06 8.20E+05 1.04E+07 Volume of dil.water liters 1.40E+08 4.44E+08 2.36E+08 6.32E+07 8.83E+08 env-tec/ARERR01

-22 TABLE2B ENTERGY INC.GRAND NUCLEAR STATION UNIT 1 LIQUID EFFLUENTS CONTINUOUS AND BATCH MODES REPORT FOR 2010 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-II0M Ci1.59E-051.15E-05 O.OOE+OO 2.92E-05 5.66E-05 AS-76 Ci 1.53E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E-05 CO-58 Ci O.OOE+OO 2.81E-04 O.OOE+OO 1.06E-05 2.92E-04 CO-60 Ci1.44E-041.63E-03 9.44E-05 9.41E-04 2.81E-03 CR-51 Ci 3.14E-04 5.24E-03 O.OOE+OO 2.79E-05 5.58E-03 CS-137 Ci 1.93E-05 6.31E-05 O.OOE+OO O.OOE+OO 8.24E-05 CS-138 Ci O.OOE+OO 1.36E-05O.OOE+OOO.OOE+OO 1.36E-05 CU-64 Ci O.OOE+OO 7.09E-05 O.OOE+OO O.OOE+OO 7.09E-05 FE-55 Ci O.OOE+OO 5.84E-05 1.56E-03 5.98E-04 2.22E-03 FE-59 Ci O.OOE+OO 5.83E-05 O.OOE+OO 1.43E-05 7.26E-05 1-131 CiO.OOE+OOO.OOE+OO O.OOE+OO 3.60E-06 3.60E-06 1-133 CiO.OOE+OOO.OOE+OO O.OOE+OO 7.48E-06 7.48E-06 LA-140 Ci 5.24E-05 1.30E-04O.OOE+OOO.OOE+OO 1.82E-04 MN-54 Ci1.13E-051.40E-03 O.OOE+OO 3.39E-04 1.75E-03 NB-95 Ci O.OOE+OO 5.38E-06O.OOE+OOO.OOE+OO 5.38E-06 RU-I06 Ci O.OOE+OO 7.34E-05O.OOE+OOO.OOE+OO 7.34E-05 SB-125 Ci 5.65E-06 1.12E-04O.OOE+OOO.OOE+OO 1.18E-04 TC-99M Ci 2.98E-06 2.31E-05 1.27E-06 2.56E-06 2.99E-05 ZN-65 Ci 1.69E-05 1.60E-03 9.44E-06 1.50E-04 1.78E-03 ZN-69M Ci O.OOE+OO 8.90E-06O.OOE+OOO.OOE+OO 8.90E-06------------------------

Totals for Period...Ci 5.98E-04 1.08E-02 1.67E-03 2.12E-03 1.52E-02 Tritium H-3 Ci 9.94E+00 3.22E+Ol 1.16E+Ol 3.28E+00 5.70E+Ol--------------------------------

Totals for Period...Ci 9.94E+00 3.22E+Ol 1.16E+Ol 3.28E+00 5.70E+Ol Dissolved and Entrained Gases XE-133 Ci 7.33E-04 8.07E-04 3.94E-04 1.44E-04 2.08E-03 XE-135 Ci 3.74E-04 5.48E-04 2.90E-04 7.75E-05 1.29E-03--------------------------------Totals for Period...Ci 1.llE-03 1.36E-03 6.84E-04 2.2lE-04 3.37E-03 Gross Alpha Radioactivity ALPHA Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO----------------------------------------Totals for Period...Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO en v-tec/A RERRO 1-23 TABLE2C ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY DECEMBER 2010 Lower Limit Sampling Minimum Analysis Type of Activity of Detection liquid Release TypeFrequencyFrequency Analysis (LLD)(uCi/ml)(a)

A.Batch Waste Release Prior to Release Prior to Release Principal Gamma Tanks (c)Each Batch Each Batch Emitters (d)5x10-7 1-131 1X10-6 Prior to 31 Days Dissolved and 1x10-5 Release One Entrained Gases Batch 1M (Gamma Emitters)Prior to 31 Days H-3 1x10-5 Release Each Composite (b)Gross Alpha 1x10-7 Batch Prior to 92 Days Sr-89.Sr-90 5x10-8 Release Each Composite (b)Fe-55 1x10-6 Batch B.SSW Basin (BeforeBlowdown)

Prior to Prior to Release Principal Gamma Release Each Each Batch Emitters Cd)5x10-7 Blowdown 1-131 1x10-6 (b)A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged in which the method of sampling employed results in a specimen which is representative of the liquid released.(c)A batch release is the discharge of liquid wastes of a discrete volume.Before sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling (d)The principal gamma emittersforwhich the LLD specification applies exclusively are the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 env-teciARERR01

-24 OPERATIONS, GRANDGULFNUCLEAR STATION SOLID RADIOACTIVE WASTE AND IRRADIATED JANUARY DECEMBER 2010 A.SOILD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)a.Spent resins, filter sludges, m 3 8.15E+01 2.83E+00 O.OOE+OO+/-25%evaporator bottoms, etc.Ci1.58E+041.02E+03 O.OOE+OO b.Dry compressible waste, m 3 7.07E+02 O.OOE+OO O.OOE+OO+/-25°k contaminated equipment, etc.Ci 1.16E+00 O.OOE+OO O.OOE+OO c.Irradiated componants, m 3 O.OOE+OO O.OOE+OO O.OOE+OO+/-25%control rods, etc.Ci O.OOE+OOO.OOE+OOO.OOE+OO d.Other: oil drum sealand, mixed m 3 7.22E+00 O.OOE+OO O.OOE+OO+/-250/0 waste Ci 9.11 E-01 O.OOE+OO O.OOE+OO 2.Estimate of Major Nuclide Composition (by type of waste)a.Spent resins, filter sludges, evaporator bottoms, etc.None b.Dry compressible waste, contaminated equipment, etc.None c.Irradiated components, control rods, etc.None d.Other: oil drum sealand, mixed waste for volume reduction.

Isotope (greater than 0.10/0)Percent Curies Ni-63 3.43E-01 3.42E+00 Co-60 1.36E+01 9.15E+01 Cr-51 4.00E-02 2.04E+00 Cs-137 4.36E-01 1.43E+00 Fe-55 4.73E+01 7.92E+02 Fe-59 4.32E-02 1.43E+00 Mn-54 1.07E+01 9.00E+02 Sr-89 1.13E-01 1.39E-01 Zn-65*4.22E+00 5.59E+01 Sr-90 6.16E-01 5.03E-01 Pu-241 3.88E+OO C-14 2.71E+00 7.89E-01 env-tec1ARERR01

-25 3 OPERATIONS, INC.GRANDGULFNUCLEAR STATION UNIT 1 SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY DECEMBER 2010 (Cant)3.Solid Waste Disposition 1 2 12 5 Destination Name EnergySolutions, Clive Disposal ilit Containerized Waste EnergySolutions, Clive Disposal Facilit Bulk Waste Duratek, LLC Studsvik Ciy Clive Clive Oak Ridge Erwin UT UT TN TN A 199.4 Description 8/120 HIC ES-21 0 20'SEALAND ES-21 0 (solidification) 1 12 24 4 Poly HIC-RWCU-A Carbon Steel Liner-SRT 20FT Sealand Stainless Steel Liner CPS/RWCU-B B.Irradiated Fuel Shipments (Disposition) env-tec1ARERR01

-26 ATTACHl\lENT I NEI Groundwater Protection Initiative Sample Results JANUARY DECEMBER 2010 are collected MW;and observation nuclides and tritium per the>Jr,u,r"TYT requirements for ground water.All detectable.

Tritium and gamma results are shown the table below.were than Reporting Levels of GGNS-ODCM table 6.<<MDA than minimum detectable activity)LOCATION DATE TRITIUM (pCi/L)GAMMA DW-Ol 10118/2010

<MDA DW-Ol 11117/2010 3,990<MDA DW-Ol 1217/2010<MDA DW-03 3117/2010 719<MDA DW-03 5127/2010<MDA<MDA DW-03 811112010 520<MDA DW-03 11118/2010 545<MDA DW-04 512712010<MDA<MDA DW-04 811112010 753<MDA DW-04 11117/2010 895<MDA DW-05 811112010<MDA<MDA DW-05 11/17/2010

<MDA<MDA DW-07 8/1212010 2,106<MDA DW-07 GG 8112/2010 2,695<MDA DW-07 9/8/2010 2,992<MDA DW-07 1011812010 2,863<MDA DW-07 11117/2010 3,273<MDA DW-08 811212010<MDA<MDA DW-08 11116/2010

<MDA<MDA MW-01 9/912010 973<MDA MW-01 10118/2010 686<MDA MW-Ol 11118/2010

<MDA<MDA MW-06 9/812010 741<MDA MW-06 10118/2010 713<MDA MW-06 11116/2010 666<MDA env-tec1ARERR01

-27 env-tec/AR£RR01

-28 ATTACHMENT I NEI Groundwater Protection Initiative Sample Results 2010 LOCATION DATE TRITIUl\l (pCi/L)GAMl\lA MW-07<MDA MW-07 6116/2010<MDA MW-07 6116/2010<MDA MW-07 8/12/2010<MDA MW-07 GG 8/12/2010<MDA MW-07 9/9/2010<MDA MW-07 GG 9/9/2010<MDA MW-07 10118/2010

<MDA M\V-07 GG 10118/2010

<MDA M\V-07 11/17/2010

<MDA MW-07 12/7/2010<MDA MW-07 GG 12/7/2010<MDA MW-09 3/16/2010<MDA<MDA MW-09 5125/2010<MDA<MDA MW-09 8/1112010<MDA<MDA MW-09 11116/2010

<MDA<MDA MW-1026B 5/26/2010<MDA<MDA MW-I026B 8/12/2010<MDA<MDA MW-I026B 11/17/2010

<MDA<MDA MW-I026B GG 11117/2010

<MDA<MDA MW-1026D 8/12/2010<MDA<MDA MW-I027B 5/26/2010<MDA<MDA MW-1027B 8/12/2010<MDA<MDA MW-1027B 11117/2010

<MDA<MDA MW-1043B 3/17/2010<MDA<MDA MW-1043B GG 3117/2010 294<MDA MW-1043B 5/26/2010<MDA<MDA MW-1043B 8/11/2010<MDA<MDA MW-I043B 11118/2010

<MDA<MDA MW-1045B 5/26/2010<MDA<MDA MW-1045B 811112010<MDA<MDA MW-1045B 11/16/2010

<MDA<MDA MW-1120 2/25/2010<MDA<MDA MW-1126 2/25/2010<MDA<MDA env-tecIAR£RR01

-29 A TT ACHl\1ENT I NEI Groundwater Protection Initiative Sample Results JANUARY DECEMBER 2010 (Cant)LOCATION DATE TRITIUlVI (pCi/L)GAMMA MW-1127 2/25/2010<MDA<MDA MW-I134B 2/25/2010<MDA<MDA MW-1134B 3/16/2010<MDA<MDA MW-1134B 5/26/2010<MDA<MDA MW-1134B 8/12/2010<MDA<MDA M\V-1134B 11/17/2010<MDA<MDA MW-14 3/17/2010<MDA<MDA MW-14 5/25/2010<MDA<MDA MW-14 GG 5/25/2010<MDA<MDA M\V-14 8/10/2010<MDA<MDA M\V-14 11/16/2010

<MDA<MDA MW-23 3/17/2010<MDA<MDA MW-23 5/27/2010<MDA<MDA MW-23 8/11/2010<MDA<MDA MW-23 11/17/2010<MDA<MDA MW-26 5/25/2010<MDA<MDA MW-26 GG 5/25/2010<MDA<MDA MW-26 8/11/2010<MDA<MDA MW-26 11/17/2010

<MDA<MDA OW-202 6/16/2010<MDA<MDA OW-202 6/16/2010<MDA<MDA OW-209B 5/26/2010 3,698<MDA OW-209B 6/16/2010 4,230<MDA OW-209B 8/13/2010 3,257<MDA OW-209B 9/8/2010 6,242<MDA OW-209B 10/17/2010 6,202<MDA OW-209B 11/17/2010 6,813<MDA OW-209B 12/8/2010 7,344<MDA GG Indicates duplicate sample.

Retrieved from "https://kanterella.com/w/index.php?title=GNRO-2011/00030,_Annual_Radioactive_Effluent_Release_Report_(ARERR)&oldid=1777591"