View source for ML091910482

{{Adams
| number = ML091910482
| issue date = 07/09/2009
| title = Grand Gulf Nuclear Station, Unit 1 - 2008 Annual Radioactive Effluent Release Report (ARERR) - Corrected Copy
| author name = Perino C L
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000416
| license number = NPF-029
| contact person = 
| case reference number = GNRO-2009/00041
| document type = Annual Operating Report, Environmental Report, Letter
| page count = 27
}}

=Text=
{{#Wiki_filter:Ju .S. Nuclear Regulatory Commissi t Control Desk ashington, D.C. 20555 REFERENCES
: cc: Sincerel CLP/MJL Attachmen 

==Dear Sir or Madam:==
This letter does not Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. Annual Radioactive RO-2009/00026, Grand Gulf Nuclear Station (GGNS) 2008 ual Radioactive Effluent Release Report (ARE Submitted April 28. 2009 ontain any commitme 9 r Station (GGNS) 2008 Annual Radioactive Effluent Corrected Cop Attached is a corrected copy of the GGNS Annual Radioactive Effluent Release Report for the period January 1, 2008 through December 31, 2008. This report was previously submitted via a letter dated April 28, 2009 (GNRO-2009/00026}. The corrected page is page 14 and the corrected information is annotated with a revision bar. Specifically the 2008 Airborne Effluent Dose (mrem) direct radiation as determined by thermol , uminescent dosimeter (TLD} quarterly totals were corrected and the reported total value was changed from 2.7 to 3.8 mrem. A copy of the GGNS Offsite Dose Calculation Manual was also previously submitted via the letter dated April 28, 2009 and requires no correction. e questions or require additional information concerning these reports, please contact Mr. Richard Scarbrough at (601) 437-6978 or Michael Larson at (601) 437-668 t Release Report - Corrected C p GN RO-2009/00041 July 9,2009 u.s.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 

==SUBJECT:==
Grand Gulf Nuclear Station (GGNS)2008 Annual Radioactive Effluent Release Report (ARERR)-Corrected Copy Grand Gulf Nuclear Station, Unit 1 Docket No.50-416 License No.NPF-29 

==REFERENCES:==

1.GNRO-2009/00026,Grand G*ulf Nuclear Station (GGNS)2008 Annual Radioactive Effluent Release Report (ARERR), Submitted April 28, 2009 

==Dear Sir or Madam:==
Attached is a corrected copy of the GGNS Annual Radioactive Effluent Release Report for the period January 1,2008 through December 31,2008.This report was previously submitted via a letter dated April 28, 2009 (GNRO-2009/00026).
The corrected page is page 14 and the corrected information is annotated with a revision bar.Specifically the 2008 Airborne Effluent Dose (mrem)direct radiation as determined by thermol*uminescent dosimeter (TLD)quarterly totals were corrected and the reported total value was changed from 2.7 to 3.8 mrem.A copy of the GGNS Offsite Dose Calculation Manual was also previously submitted via the letter dated April 28, 2009 and requires no correction.
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 Michael Larson at (601)437-6685.Sincerely,-{dLc./...P-e<-,',n CLP/MJL 

==Attachment:==

Annual Radioactive Effluent Release Report-Corrected Copy cc: (See Next Page)
NRC Senior Resi f Nuclear Station 39150 Commission E. Collins, Jr. ( a ngton, TX 76011-4005 uclear Regulatory Commission Mr. Carl F Lyon, NRR/ADRO/DORL (w/ ESSEE 0 ATTN: U. S. Postal Delivery Address Only Mail Stop OWFN/8 B1 hington, DC 20555-0001 GNRO-2009/00041 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S.Nuclear Regulatory Commission ATTN: Mr.Elmo E.Collins, Jr.(w/2)612 East Lamar Blvd, Suite 400 Arlington,TX76011-4005 U.S.Nuclear Regulatory Commission ATTN: Mr.Carl F.Lyon, NRR/ADRO/DORL (w/2)ATTN: ADDRESSEE ONLY ATTN: U.S.Postal Delivery Address Only Mail Stop OWFN/8 B1 Washington, DC 20555-0001 env-teclARERROY - I IOACTIVE EFFLUENT RELEASE i, 2008 - December 31, 2008 2-2--0 `f - - July On Copy ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION ANNUAL RADIOACTNE EFFLUENT RELEASE REPORT January 1, 2008-December 31,2008 rreoareaBy Corrected Copy July 9,2009 Page 14 Only env-tec1ARERR01-1 onv-r.WARRROY . 2 SU13JECT AGE 1. INTRODUCTION 4 11. DETAILED INFORMATION 5 A. Regulatory Limits 5 1. 10CFR20 Limits 5 a. Fission and Activation Gases 5 b. Radloiodlnes and Particulates 5 c. Liquid Effluents 5 2. 10CFR50, Appendix I Limits 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 $ 1. For Fission and Activation Gases S 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 E 2. Gaseous I 11 TABLE OF CONTENTS SUBJECT PAGE I.INTRODUCTION 4 II.DETAILED INFORMATION 5 A.Regulatory Limits 5 1.10CFR20 Limits 5 8.Fission and Activation Gases 5 b.Radioiodines and Particulates 5 c.Liquid Effluents 5 2.10CFR50, Appendix I Limits 6 a.Fission and Activation Gases 6 b.Radloiodines 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 o.Measurements and Approximations of Total Activity 8 1.For Fission and Activation Gases 8 2..For Particulates and Radioiodlnes 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.nv*t<<:lARERR01*2 
.011wtsel"ER
."I - 3 BLE 0 TS (C01 T'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 1. Meteorological Data 12 J. Radioactive Effluent Monitoring Instrumentation Operability 12 K. Annual Sewage Disposal Summary 12 Ill. RADIATION DOSE 

==SUMMARY==

13 A. Water-Related Exposure Pathway 13 B. Airborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 15 A. Offske Dose Calculation Manual (ODCM) 15 B. Radioactive Waste Treatment Systems 15 LIST OF TABLES PAGE I A Gaseous Effluents - Summation of All Releases 16 113 Gaseous Effluents - Elevated Releases 17 IC Gaseous Effluents - Ground-Level Releases - Continuous 18 ID Radioactive Gaseous Waste Sampling and Analysis Program 19 2A Liquid Effluents - Summation of All Releases 20 213 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 ATTACHMENTS PAGE Attachment I - NEI Groundwater Protection Initiative Sample Results 25 Attachment 11 - Offs1te Dose Calculation Manual 26 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.SoUd Radioactive Waste Shipments 12 I.Meteorological Data 12 J.Radioactive Effluent Monitoring Instrumentation Operability 12 K.Annual Sewage Disposal Summary 12 III.RADIATION DOSE 

==SUMMARY==
13 A.Water-Related Exposure Pathway 13 8.Airborne-Related Exposure Pathway 13 IV.OFFSITE DOSE CALCULATION MANUAURAOIOACTIVE WASTE 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 18 Gaseous Effluents-Elevated Releases 17 1C Gaseous Effluents-Ground-Level Releases-Continuous 18 10 Radioactive Gaseous Waste Sampling and Analysis Program 19 2A Liquid Effluents-Summation of All Releases 20 28 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 ATTACHMENTS PAGE Attachment'
-NEI Groundwater Protection Initiative Sample Results 25 Attachment II-Offsite Dose Calculation Manual 26 The and 6.12 Sol sm-tivelAMERRO1 - 4 ioac R) for accordance M), Section 5.6.3 of Grand Gulf Nuclear Station (G ring of radioactive effluents is referenced in ODCM Appendix A, Sections 6.11 Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with OOCM requirements. All effluent releases were within the concentration and total release lim specified by the ODCM. Projected offsite doses were within the dose limits specified by the OOCM. The summation of all gas while elevated releases a respectively. Table 10 describes the radioactive gaseous sampling and analysis program ted at GGNS. site Dose eases during ground-level releases are given in Tables I B e reporting period is en in Table 1A, d IC, The summation of all liquid releases during the reporting period is given in continuous and batch mode releases are given in Table 2B. Table 2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS. radioactive waste and irradiated fuel shipments during the reporting period are arized 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 inistrative Controls Section 5.6-3. able 2A, while I.INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR)for the period of January 1 through December 31, 2008 is submitted in accordance with OOsite Dose Calculation Manual (ODeM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS)License No.NPF-29.The monitortng of radioactive effluents is referenced in aDeM 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 aDCM requirements..
All effluent releases were within the concentration and total release limits specified by the aDCM.Projected offsite doses were within the dose limits specified by theOOCM.The summation of all gaseous releases during the reporting period is given in Table 1A, while elevated releases and ground-level releases are given in Tables 18 and 1C, respectively.
Table 10 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 20 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 aDeM Administrative Controls Section 5.6.3.""..,.t.clARERR01
*"
env-focIARERROI - 5 1. 1 0C R wh Radioiodines and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in pa form with half-lives greater than 8 days shall be such that: D. e re avers ve th = Z' terms are 
= average organ dose rate to liquid Effluents - The concentration of radioactive materials released in quid effluen time CO 1.1 P, 0", < 1500 mre s are defined in the GINS C?t}CM. tyear (mre :5 500 mrem/yr ose rate in the current year (mrem/yr) 3000 mrem/yr ed in the GGNS ODCM ent year (mremlyr) es the values specified in I OCFR20, Appendix B, Table 2, 2. The concentration of dissolved or entrained noble gases, aced in liquid effluents to unrestricted areas from all reactors at the ite, shall be limited to 2 x 10-4 microcuriesiml total activity. II.DETAILED INFORMATION A.Regulatory Limits 1.10CFR20 limits 8.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: D tb=average total body dose rate in the current year (mrem/yr).=XlQ L, K, Q I S;500 mrem/yr D.=average skin dose rate in the current year (mrem/yr).=XlQ L, (L,+1.1 M,)Q I S 3000 mrem/yr where the terms are defined in the GGNS ODeM.b.Radioiodine, 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)=Ii WP,Q',1500mrem/yr where the terms are defined in the GGNS ODeM.c.Liquid 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 t released In liquid effluents to unrestricted areas from all reactors at the site, shall be limited to2x 10'" microcuries/ml total activity.*n-;.t.cIARERR01
*$ 
*nv-t*aARERR01 
-6 where the terms are d D DTau , n and Activation Gases - The dose from noble gases in Base boundary shall be X1Q. 0, ere the terms are defined ose due to beta emissions from noble gases 515m 7 x 10-8 Z, N, X10' q < 10 mrad/qtr ons from noble gases /qtr < 20 mrad/yr ed in the GGNS ODC b. Rgdiolodines and P-prtigulates - The dose to an individual from tritium, 1-131 1-133 and radioactive material in particulate form with half-lives greater n 8 days in gaseous effluents shall be such that 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 E, 8,1111' Q:5 7.5 mrem/qtr Any Organ where the terms are defined in the yr Any Organ GNS ODCM. liquid Effluents - The dose from radioactive material liquid effluents shall be such that: F, 51.5 mrem/qtr Total Body < 5 mrem/qtr Any Organ 5 3 mremlyr Total Body 10 mrem/yr Any Organ n the GGNS ODC It DETAILED INFORMATION (CONT'D)2.10CFR50, Appendix I Limits 8.Fission and Activation Gases-The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that: o=air dose due to gamma emissions from noble gases y=3.17)(10'" L, M, XlQ'Q, s 5 mrad/qtr:s;10 mrad/yr o*air dose due to beta emissions from noble gases=3.17 x 10'" LI N, XlQ':s;10 mrad/qtr20 mradlyr where the terms are defined In the GGNS ODCM.b.Radioiodine, and Particulates
*The dose to an individual from tritium, 1-131, 1-133 and radioactive material in particulate form with half-Uves greater than 8 days in gaseous effluents shall be such that: D p=dose to an individual from tritium, 1-131 t 1*133 and radionuclides in particulate form with half-lives greater than 8 days (mrem)=3.17 x 10":&#xa3;, R , W'a.s 7.5 mrem/qtr Any Organ S 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 D Tau=1:[Arrau t L\t.Cit F,]1.5 mrem/qtr Total Body I ,.15 mrem/qtr Any Organ3 mremlyr Total Body10 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.tlnv*leclARERR01
*6 env-teclARERROY - 7 2. Liquid <25 <7 Not applicable for G Effluents accordi spectively I Body or m/yr, Thyroid <20 mrad P/qtr or <40 mrad Plyr, Fission and A :515 mremlqtr or :530 mrem/yr, any Organ, Iodine and Particulates 
<3 mrem remiqtr or :520 mre Effluent Concentrations I . ne Energy The Effluent Concentration limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section H.A.I.a. In this case, the ECLs are actually determined by the dose factors in Table 2.1-1 of the GGNSODCM. S UDC: <6 mre ad Y/yr, Fission and Activation Gases r, Total Body, Liquid Effluents 
/yr, any Organ, liquid Effluents The Effluent Concentration Limit (ECL) of radioactive materials in liquid effluents is limited by ten times the values in 10CFR20, Appendix 8, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope. Appendix , ioiodines g to equations con tiara that the limits applied are: y Organ except ovation Gases II.DETAILED INFORMATION (CONT'D)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: s25 mrem/yr, Total Body or any Organ except Thyroid s75 mrem/yr, Thyroid s10 mrad y/qtr or s20 mrad"f/yr, Fission and Activation Gases mrad or s40 mrad fl/yr, Fission and Activation Gases mrem/qtr or s30 mrem/yr, any Organ, Iodine and Particulates s3 mrem/qtr or s6 mrem/yr, Total Body, liquid Effluents mrem/qtr or s20 mrem/yr, any Organ, liquid Effluents B.Effluent Concentrations 1.Airborne The Effluent Concentration Limit (Eel)of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section II.A.1.a.In this case, the ECls are actually determined by the dose factors in Table 2.1-1 of the GGNSODCM.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 Eel chosen is the most conservative value of either the soluble or insoluble Eel for each radioisotope.
c.Average Energy Not applicable for GGNS ODeM Appendix A.enll-ItlciARERR01
*,
enwteclARERR01 - 8 Table requirem so 1. For Fission low ere and Ap nd 2C give sa for the analysis of aas es in the attached tables given as zero do not necessarily im radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables 10 and 2C. For radionuclides, lower detection limits than required may be readily achievable
; ionuclide is measured below its stated detection limits, it is reported. details the methods used to measure a d Activation Gases The following noble gases are considered in evaluating gaseous airborne discharges
: C. = U nc net monitor readi road at ies and minimum detectable se s and liquid effluent streams, respective Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high-resolution germanium detectors. (See Table 1 D 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.I. of this report. Only those radionuclides that re detected are used in this computation. During the period betwe 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 relationsh C, = isotopic calibration factor for isotope I tion of isotope 1 in the grab sample in pCi/ml. associated with the effluent stream time of grab sampling). II.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:
Fission and Activation Gases Radioiodines Particulates Liquid Effluents Tables 10 and 20 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 10 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 Xe-133 Xe-135 Kr-88 Xe-133m 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 10 for sampling and analytical requirements.)
Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section It.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:
where C t=isotopic calibration factor for isotope i U,=concentration of isotope i in the grab sample in IJCi/ml.m=net monitor reading associated with the effluent stream (determined at the time of grab sampling).
env-'ecIARERR01
*8 
.--t-1ARERR01 DETAILED INFORMATION (CONT'D) These calibration factors, along with the hourly effluent monitor values and fl rates, are entered into the laboratory computer where the release rates for individual radionuclides are calculated and stored. If no activity is detected in th grab sample, the calibration factor defaults to a historical mixture of Kr-88, X 133, Xe-1 35m, Xe-1 35, and Xe-1 38. The radioiod ntinuous sampling is performed on the continu Offgas/Radwaste building Vent, Containment Purge, Fuel Handl rbine Building Vent). Particulate material is collected by filtra Radioiodines are collected by adsorption onto a charcoal filte filters are removed and analyzed on the pulse height analyzer quantify radioactive materials collected on the filters. Particula analyzed for gross alpha and Strontium-89 and -90 as required determinations are made using 2-pi gas flow pro and -90 values are obtained by chemical separation and subse using liquid scintillation technique distillation and liquid scintillation techniq occurrences, the frequency of sampling is of footnote "c" of Table 10, "Radloactiv (GGNS ODCM Appendix A, Table 6.11. erformed by a qualified contract laborato For Batch Releases: Gases r Particulates nd Radioiodines and radioactive materials in particulate form Releases e processing of batch type releases (from Containment Purge or Turbine Building Occasional release Point) are analogous to that for continuous releases. ed -ing major operational aced to satisfy the requirements aste Sampling and Analysis," ntly, Strontium analysis is onsid W filters are then lph II.DETAILED INFORMATION 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 radlonuclides are calculated and stored..If no activity is detected in the grab sample, the calibration factor defaults to a historical mixture of Kr-88,133, Xe-135m, Xe-135, and Xe-138..2..For Particulates and Radioiodines The radloiodines and radioactive materials in particulate form to be considered are: Zn-65 Mn-54 Fe-59 Co-58 C0-60 Sr-89 Sr-90 1-133 Cs-134 Cs-137 Ce-141 Ce-144 1*131 3.For Continuous Releases Continuous sampling is performed on the continuous release points (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 materia's collected on the filters.Particulate filters are then analyzed for gross alpha and Strontium-89 and-90as 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 sampl.ing is increased to satisfy the requirements offoo*tnote"c" of Table 10,"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 or Turbine Building Occasional Release Point)are analogous to that for continuous releases.tlnv--ltlc1ARERR01
*IJ 
*m, , t*&ARERftO1 - fO or Batch Relea ab samples are obtained and analyzed as required ses are performed using the computerized pulse iously described. Aliquots of each pre-released volume released, are composited in nts of Table 2C. Strontium-89, 90 and Iron-55 es are obtained by chemical separation and counting the separated strontium and iron using liquid scintillation techniques. Gross alpha determinations are de 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. Representative pre-release by Table 2C. Isotopic ana height analysis system pr proportional to ordance with the requ val Releases !quid 2. Gaseo No batch releases were made during the report period. 8 !ides I iqu ed when evaluatina I i st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year a a. Number of releases 61 78 87 86 312 T. Tlrvw Period in rninutes) bb Total for all batches 1.96E+04 2.50E+04 2.78E+04 2.73E+04 '9.9'7E+04 c c. Max al time for a batch 4.25E+02 4.16E+02 4.30E+02 4.30E+02 4.30E+02 d . Avg v time for a batch 3.21 E+02 3.20E+02 3.20E+02 3.17E+02 3.20E+02 e. e. Min Min time for a batch 2.53E+02 2.60E+02 1.10E+02 2.30E+02 1.10E+02 II.DETAILED INFORMATION (CONT'D)5.For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:
H-3 Mn-54 Fe-55 Co-58 C0-60 Fe-59 Zn-65 Sr-89 Sr-90 Mo-99 1-131 Cs-134 08-137 0e-141 Ce-144 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 20.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----------
..._---8.Number of releases Time Period in minutes b.Total for all batches c.Max time for a batch d.Av time for a batch 8.Min time for a batch 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year 61 78 87 86 312 ,.........::,.''''1.96E+04 2.50E+04 2.78E+04 2.73E+04 9.97E+04 4.25E+02 4.16E+02 4.30E+02 4.30E+02 4.30E+02 3.21E+02 3.20E+02 3.20E+02 3.17E+02 3.20E+02 2.53E+02 2.60E+02 1.10E+02 2.30E+02 1.10E+02 2.Gaseous No batch releases were made during the report period.tlnv-ttICIARERR01
*10 DETAILED IN enwteclARERROI - 11 id b. Tota mber o 2. Gaseous Actin eleases: 0 Released: O.OOE+00 C bar of Releases: 3 b. Total Activity Released: 1.02E-1 C! On March 19, 2008, one Turbine Building smoke exhaust hatch was found opened Calculated activity released was 2.32E-03 Ci. The dose and specific activities are included in the applicable sections of this re tin November 17, 2008, Turbine Building smoke exhaust hatches were opened to vent smoke following a fire. Calculated activity released was 5.38E-04 C1. The dose and specific activities are included in the applicable sections of this report. On August 21, 2008, a Kr-85 gas source was found to be broken on receipt inspection. Calculated activity released was 9.91 E-02 Ci. The dose and specific activities are included in the applicable sections of this report. Estimate of Total Error I Liquid The maximum errors are collectively estimated to be as folio 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- 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 w calibration of a particular instrument with a radioactive source. s: Total error is calculated by taking the square root of the sum of the squares of the individual errors. Fission & Activation Products Tritium Dissolved 
& Entrained Gases Gross Alpha Sampling % 2.60E+01 2.60E+01 2.60E+01 2.60E+01 Measurement 
% 6.80E+01 6.50E+01 6.1 OE+01 9.20E+01 r- TOTAL % 7.30E+01 7.OOE+01 6.60E+01 9-50E+01 II.DETAILED INFORMATION (CONT'D)F.Abnormal Releases 1.Liquid a.Number of Releases: b.Total Activity Released: 2.Gaseous a.Number of Releases: b.Total Activity Released: o O.OOE+OO Ci 3 1.02E-1 Ci On March 19, 2008, one Turbine Building smoke exhaust hatch was found opened.Calculated activity released was 2.32E-03 Ci.The dose and specific activities are included in the applicable sections of this report.On November 17, 2008, Turbine Building smoke exhaust hatches were opened to vent smoke following a fire.Calculated activity released was 5.38E-04 Ci.The dose and specific activities are included in the applicable sections of this report.On August 21 t 2008, a Kr-85 gas source was found to be broken on receipt inspection.
Calculated activity released was 9.91 E-02 Ci.The dose and specific activities are included in the applicable sections of this report.G.Estimate of Total Error 1.Liquid The maximum errors are collectively estimated to be as follows: Sampling 0/0 Measurement 0/0 TOTAL&deg;A.Fission&Activation Products 2.60E+01 6.80E+01 7.30E+01 Tritium 2.60E+01 6.50E+01 7.00E+01 Dissolved&Entrained Gases 2.60E+01 6.10E+01 6.60E+01 Gross AI ha 2.60E+01 9.20E+01 9.50E+01 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 ofactivity 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*tecIARERR01
*11 em-teclARERROI - 1 2 Me ror H. Solid Radio ement errors reparation and are calcul See Table 3 for shipme ologica dude uncertainty associated with sample flow, vent flow and 3. Solid Radioactive Waste ee Table 3 for error terms, e Waste Shipmen information. ne loss) are collectively estimated to nclude uncertainty associated with instrument calibration rating of low-activity samples. Measurement and total the same methods used for liquid effluents. ata recovery for the reporting period was 99.5%. The predominant wind direction was from the North-East approximately 10.7% of the time. The predominant stability class was class "D" approximately 32.3% of theme. Average wind speed during the reporting period was approximately 4.5 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. Radioactive Effluent Monitoring instrumentation opera No reportable instances of inoperability occurred during the reporting period. Annual Sewage Disposal Summary There were no sewage disposa R1. Fission & Activation Products Iodine Particulate AI ha Gross Grow Tritium M Sam Bling 3.20E+01 2.30E+01 2.20E+01 2.20E+01 2.30E+01 Measurement 
% 6.10E+01 6.70E+01 6.50E+01 1.41E+42 6.20E+01 01 TO TAL OTAL % 6.90E+Oi 7.14E+41 6.90E+01 . i.03E+02 6.60E+01 II.DETAILED INFORMATION (CONT'D)2.Gaseous The maximum errors (not including sample line loss)are collectively estimated to be as follows: Fission&Activation Products 3.20E+01 6.10E+01 6.90E+01 Iodine 2.30E+01 6.70E+01 7.10E+01 Particulate 2.20E+01 6.50E+01 6.90E+01 AI ha 2.20E+01 1.01E+02 1.03E+02 Gross Tritium 2.30E+01 6.20E+01 6.60E+01 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 The predominant wind direction was from the North-East approximately 10.7%of the time.The predominant stability class was class"0" approximately 32.3%of the time.Average wind speed during the reporting period was approximately 4.5 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.J.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 2008.t'ln,,*ttlclARERR01
*12 
&--teclARERR01 - I$ re are no other fuel cycle facilities within 8 lam of GINS, 44CFR194 wring ter-Related Exposure Pathways The values calc of this report a ody dose and critical organ doses are computed for the maximum exposed individual. The maximum dose contribution from liquid effluents considered to occur in the adult age group via consumption of fish. Airborne-Related Exposure Path The values presented in this section utilize information provided in Tables I A and I C of is report and the calculational methodology of the ODCM. 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 the site boundary were considered when selecting locations boundary, lace for dose calcu The most led were calculated in accordance with the GGNS ODCM ations. locati th During routine operations lions are from ted in this section utilize the information provided in T e calculational methodology of the ODCM Consideration of site haunch beyond the site boundary ated on for a ays locations as well as unrestricted areas within and vides assurance that offsite doses will not be substan ing to provide an accurate dose calculation. and 2 public is used for the dose calculations. dispersion and deposition factors used for dose al annual average meteorological data. ZVUO U uid Effluent nose mrem I I I it Qtr 2nd Qtr 3rd Qtr 4th Qtr Qtr TOTAL Bone 3.89E-02 1.88E-02 5.17E-42 1.04E-01 2.15E-01 Liver 1.19E-01 4.47E-02 7.61 E-02 2.16E-01 4.57E-01 Thyroid 4.72E-03 6.03E-03 2.91 E 2.57E-03 1.60E-02 Kidney 7.40E-02 2.58E-02 4.58E-02 1.41 E-01 2.88E-01 Lung 3.47E-03 4.89E-03 4.84E-03 3.51 E-03 1.67E-02 GI-1.1.1 t Whole Body 1.44E-01 5.31 E-02 4.76E-02 2.01E-02 . 6.17E-02 4.05E-021 1.60E-01 1.04E 4.15E-0011 2.i9E-01 III.RADIATION DOSE 

==SUMMARY==
Indicated below is the annual summary of offsite doses attributable to GGNS during 2008.Inspection of the values indicate that GGNS releases were within the 1 OCFR50, Appendix I design 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 ODeM.A.Water-Related Exposure Pathways The values calculated in this sectionutilizethe information provided in Tables 2A and 28 of this report and the calculational methodology of the ODeM.Liquid Effluents Totalbodydose 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.2008 Liquid Effluent Dose (mrem)<-1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL 80ne 3.89E-02 1.88E-02 5.17E-02 1.04E-01 2.15E-01 Liver 1.19E-01 4.47E-02 7.61E-02 2.16E-01 4.57E-01 Thyroid 4.72E-03 6.03E-03 2.91E-03 2.57E-03 1.60E-02 Kidney 7.40E-02 2.58E-02 4.5SE-02 1.41E-01 2.88E-01 Lung 3.47E-03 4.89E-03 4.84E-03 3.51E-03 1.67E-02 G'-LLI 1.44E-01 4.76E-02 6.17E-02 1.60E-01 4.15E-01 Whole Body 5.31E-02 2.01E-02 4.05E-02 1.04E-01 2.19E-01 B.Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and 1C of this report and the calculationa' methodology of the ODeM.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.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 wilt 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.
env-teclARERRO I -14 organ dose to a MEMBER OF THE PUBLIC (critical receptor) fro Iculate ositio e at a distance of 1432 Bred for use in the organ dose calculations are in getation. There is no med that the age group receiving the ma t the receptor consumed food products that cons ea GGNS. It was as residence and the residence 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 644 mete miles) from the plant. This location corresponds to the highest annual average atmospheric dispersion factor for a location at an unrestricted area within the site oundary. 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 2008 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 surement units are mrad Total Bodv and Skin Dose Rate Direct radiation dose is calculated by subtracting average doses measured thermoluminescent dosimeter (TLD) badges located at control locations from average doses measured by TAD badges located near the site boundary. GGNS reported measured doses in 2008 as net exposure normalized to 92 days. Correc ways mono mane, in five mile dose lived at the e raised or produced Iodine, Tritium & Particulat 1.65E-01 5.77E-03 2.95E-02 1.71 E-02 2.18E I I Percent of Limit 2.20E+00 7.70E-02 3.94E-01 2.28E-01 1.45E _~_ 1_ _ _ 00 Total Percent of Limit Skin Dose Rate (mrern/yr)
Percent of Limit Gamma Air Dose* Percent of Limit Air Do e* Percent of Limit --- 2008 Airborne Effluent Dose (mre m): 1st Qtr 2nd Qtr ~ 3rd Qtr 1.28E-01 0.026% 4.40E 0.015% 0.010% 9.66 1.93E+00 6.OOE-02 6.OOE-01 E-01 I 2.46E 0.059% 5. 3E-02 1.11 E+00 2.45E-02 2.45E-01 0.049% 0.017% 6.62E-02 1.32E+00 3.36E-02 3.36E-01 1.03E-01 TOTAL E+00 O.OOE+00 1.10E+0 3.80E d Page III.RADIATION DOSE 

==SUMMARY==
 (CONT'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 2008 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.
Average Total Body 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 644 meters (0.40 miles)from the plant.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 2008 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 2008 as net exposure normali%ed to 92 days.2.39E-01 1.40E+OO O.OOE+OO 1.10E+OO 3.80E+OO*Measurement units are mrad en v-tec/A RERRO1-14 Corrected Page July 9,2009 en,-WIARERRO1 - OFFSITE DOSE CALCULATION MANUAL! RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES Offsite Dose Calculation Manual LODCMJ Revision 36 to the ODCM was issued during the reporting perio are summarized below. evision 36: Adds Table 2.2-I.b, "Pathway Dose Factors for LCO 6.111.4 and Section 2.2.1.b, (Pi)", for age group "Child". Changes note for section 2.2.1.b to use Child Inhalation Pi values from table Radioactive Waste Treatment_
Systems No major changes were mad , 2008. The changes e liquid or gaseous radwaste treatment systems i IV.A.nMan Revision 36 to the aDCM was issued during the reporting period.The changes are summarized below.Revision 36: Adds Table 2.2-1.b."Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1..b, (Pi)".for age group"Child".Changes note for section 2.2..1.b to use Child Inhalation Pi values from table 2.2-1 b..B..Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems in 2008.tJntl-tIJClARERR01
*15 env-teclARERROY - 16 REPORT FOR 2008 cent BLE 1A ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES u its Fission Ci 3.29E+00 2.40Z+00 1 Rol Avg. Release Rate uCi/sec 3. Percent of TS Limit % t 4.43E+O 1.40E+01 3.21E+00 Total Release Avg. Release t 1.18Z-02 3.73E-04 1.29E+00 02 QTR 1 QTR 2 QTR 3 -------- QTR -------- Activation Gases .75E+02 6.47E+01 8.76E+01 1.16E+02 .22E+01 8.24E+00 1.10E+01 1.45E+01 93e+00 1.11E+00 1.32E+00 2.052+00 di 131 389-03 1.42E-04 1.36E-03 9.11E-04 19E-03 1.81E-05 1.71E-04 1.15E-04 05Z+00 3.11Z-02 2.96E-01 1.99E-01 TABLE 1A ENTERGY OPERATIONS, INC.GRANO GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES REPORT FOR 2008 Unit..Qn 1 Q'1'R 2 Q'l'R 3 QTR 4 YZAR Fi**ion.nd Activ.t.ion G****1.'1'ot..l aele...Ci 2.Avq.R.I****Rate uCi/.ec 3.Percent of'1'8 LiJD.it , 1.158+02 2.2211+01 1.93.+00 6.418+01 8.248+00 1.111:+00 8.161:+01 1.1011+01 1.32B+00 1.168+02 1.4511+01 2.058+00 4 438+02 1.408+01 3.2111+00 Iodine-131 1.Tot..l Relea.e Ci 2.Avq.ReI****Rate uCi/.eo 3.Percent ofT.LiJD.it , 9.38B-03 1.19B-03 2.05&#xa3;+00 1.42B-04 1.811:-05 3.11B-02 1.36B-03 1.711:-04 2.96B-Ol 9.11B-04 1.15B-04 1.99B-01 1.181:-02 3.738-04 1.29B+00 Particul.1:e.
Halt'Life>-8 day.1.Total Rel.a.e Ci 2.Avq.Rele***Rat.uCi/**c 3.Percent of'1'8 Limit , 9.13B-05 1.161:-05 1.14B-Ol 3.61B-05 4.591:-06 1.65B-02 7.751:-06 9.761:-07 6.25B-02 1.56B-05 1.911:-06 7.131:-03 1.51B-04 4.771:-06 1.00B-01 1.Tot.al R.I....Ci 2.Avq.Rel.a**Rat.uCi/**c 3.Percent of TS , Trit.iua 3.298+00 2.40B+00 4.19B-01 3.05B-01 4.038-02 2.941:-02 2.8511+00 3.5911-01 3.4911-02 1.77'&+00 2.23'&-01 2.17B-02 1.03B+01 3.26B-01 6.32B-02 Gross 1.Total Rele...Ci 2.218-08 0.008+00 1.77B-08 1.4811-08 5.412-08 2.Avq.ReI****Rate uCi/.ec 2.818-09 O.OOB+OO 2.23B-09 1.87.-09 1.73B-09 tllJv-tacIARERR01
*IS env-feclARERRO! - 1 7 TABLE 1 B ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPOR GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2008 (Not Applicable - GGNS Releases Are Considered Ground-Level) tlnv-t"clARERR01
.." (Not Applicable
-GGNS Relea.e.Are Considered Ground-Level) 
--t.clARERROY - 1 8 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS TABLE I ENTERGY OPERATIONS, INC, GRAND GULF NUCLEAR STATION UNIT Totals 253 41 ci O.OOZ+00 0.00z+ 58 ci 2.7 60 OOE+00 3.92E-06 5.11E- O.OOE+00 0.00E+00 O.00E+00 8.12E 2E-06 2.05E-09 00Z+00 O.OOE+00 5.69E-08 .00X+00 4.78Z-06 O.OOZ+00 O.OOZ+00 4.78E- 5SE-06 6.32E-06 O.OOE+00 0.00Z+00 3.93Z-06 O.OOE+00 .42E-06 0.00X+00 0.002+00 O.OOE+00 -------- --------
13E-05 3.61Z-05 7.75Z-0 Alpha Radioactiv REPORT FOR 2008 u QTR 1 Fission a d QTR tivation Gas*
AR-41 ci 4.12E+00 7.92E+00 3.57E+00 4.16E-01 1.60E+01 KR-85 ci O.OOE+00 O.OOE+00 9.91E-02 O.OOE+00 9.91E-02 KR-85H ci 4.47E+01 2.21E+01 7.82E+00 2.06E+00 7.67E+01 KR-87 ci 1.64Z-01 O.OOE+00 O.OOE+00 2.03E+00 2.20E+00 KR-88 ci 1.38E+01 9.11E+00 1.89E+00 1.01E+00 2.58E+01 KR-89 ci O.OOE+00 O.OOE+00 O.OOE+00 6.53E+00 6.53E+00 XIE-133 ci 6.63E+01 9.20E+00 1.02E+01 1.01E+01 9.58E+01 XE-133H ci 1.66E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.66E-01 XE-135 ci 1.08E+01 4.81E+00 1.26E+01 1.36E+01 4.18E+01 XE-135H ci 2.27E+01 9.84E+00 3.63E+01 2.27Z+01 9.15E+01 XE-137 ci 1.46E+00 O.OOE+00 O.OOE+00 2.87E+01 3.02E+01 XE-138 ci 1.07E+01 -------- 1.73Z+00 -------- 1.50E+01 -------- 2.84E+01 -------- 5.59E+01 Total* for Poriod... Ci 1.75Z+02 6.47Z+01 8.76E+ -------- 2.21E-06 1.01Z-05 O.OOZ+00 3.9 1.16Z-06 1.99E-05 3.98E-06 -------- 3.98Z-0 -------- TABLE 1C ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2008 Unit.Q'J.'R 1 QTR 2 Q'J.'R 3 Q'J.'R 4 YEAR Pission and Activation Gas**Aa-41 tal-IS KIt-85M m-81 KR-88 tal-BI D-133 XE-133M XlI-135 XE-135M D-131 XB-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 4.128+00 0.008+00 4.478+01 1.6411-01 1.3811+01 0.008+00 6.6311+01 1.66B-01 1.088+01 2.21Z+01 1.46Z+00 1.018+01 7 9211+00 0.0011+00 2.21&#xa3;+01 0.00&+00 9.1111+00 0.00&+00 9.201:+00 0.008+00 4.811:+00 9.848+00 0.001:+00 1.73Z+00 3.511:+00 9.91Z-02 7.82.+00 0.00.+00 1.89&+00 0.00&+00 1.021:+01 0.001:+00 1.26.+01 3.63&#xa3;+01 0.001:+00 1.50.+01 4.16&#xa3;-01 O.OOZ+OO 2.06&#xa3;+00 2.03&#xa3;+00 1.011:+00 6..53&+00 1.01&+01 0.00&+00 1..368+01 2.218+01 2.81&+01 2.84&+01 1.601:+01 9.9111-02 7.6711+01 2.208+00 2.58.+01 6.53&+00 9.58Z+01 1.661:-01 4.188+01 9.15&+01 3.021:+01 5.59&#xa3;+01 Total.fox Pexiod...Ci 1.75Z+02 6.41Z+01 8.76&+01 1.16Z+02 4.43Z+02 Iodin**1-131 1-133 1-135 Ci Ci Ci 9.38Z-03 9.861:-03 1.14S-04 1.42B-04 1.14B-03 1.62Z-03 1.36Z-03 5.26.-03 9.13Z-04 9.11Z-04 5.97B-04 1.20B-04 1.181:-02 1.69B-02 2.71.-03 Total.fox Period...Ci 1.94B-02 2.90B-03 7.538-03 1.63B-03 3.14Z-02 Paxticulat..>-8 day.-------CZ-141 CO-58 CO-60 Ca-51 CS-131 n:-59 MN-,54 ItO-106 Sa-89 ZH-65 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0.001:+00 0.001:+00 0.001:+00 0.001:+00 0.001:+00 2.72B-06 1.28B-06 0.008+00 8.12B-07 4.811:-06 4.58B-06 2.071:-06 1.22&#xa3;-06 2.36&-06 1..021:-05 7.21B-05 1.258-05 2..058-06 0.00&+00 8.671:-05 0.00&#xa3;+00 0.008+00 5.698-08 1.208-06 1.268-06 0.001&#xa3;+00 4.788-060.008+000.008+00 4.78B-06 1.581:-06 6..321:-06 0.001&#xa3;+00 2.211:-06 1.018-05 0.008+00 3.931:-06 O.OOB+OO 0.00&+00 3.931&#xa3;-06 9.04Z-06 5.238-06 4.42Z-06 1.16&#xa3;-06 1.998-05 O.OOB+OO O.OOB+OO O.OOB+OO 3.18B-06 3.98B-06
_...._--..-------_.....,-------
----...---!'ritiwa B-3 Ci 3.2911+00 2.40&+00 2.85B+00 1.77B+00 1.038+01!'otal. Period...Ci 3.29B+00 2.4011+00 2.85&+00 1.77.+00 1.03B+01 Gxo**Radioactivity ALPHA Ci 2.21.-08 0.00.+00 1.77&#xa3;-08 1.481:-08 5.47B-08 Toeals for Period...Ci env.teeIARERR01
*18 2.21B-08 O.OOZ+OO 1.77&#xa3;-08 1.48B-08 5.47&#xa3;-08 NOTE env-lecIARERR01 " 1 9 TABLE 1D ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Progra JANUARY - DECEMBER 2008 GGNS ODCM, Appendix 1.4- TABLE 10 ENTERGY OPERATIONS, INC..GRAND G NUCLEAR STATION UNIT 1 EFFLUENT AND TE DIS L ANNUAL REPORT Radioactive Gaseous aste Sampling and Analysis Program JANUARY-DECEMBER 2008 Gaseous Release Type A.(1)Radwaste Building Ventilation Exhaust (2)Fuel Handling Area Ventilation Exhaust (3)Containment Ventilation Exhaust (4A)Turbine Building Ventilalion Exhaust (4B)Turbine Building Occasional Release Point (when in service)B.(1)Offgas Post Treatment Exhaust, whenever there is flow (2)Standby Gas Treatment A Exhaust, whenever there is flow (3)Standby Gas TreatmentS Exhaust, 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 fb.e)H-3'-131 1-133 Principal Gamma Emitters (e)('-131, Others)Gross Alpha Sr-89, 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)*1x10....1X10'" 1x10-12 1)(10-10 1x10-11 1)(10-11 1 xi 0'" 1)(10'" 1x10'" NOTE: Footnotes indicated are listed in GGNS ODeM, Appendix A, Table 8.11.4-1. 
: 1. Total Release, 2. Avg. Diluted Conc. 3. Percent of Limit Ci/ml REPORT FOR 2008 RERROI-20 "ABLE 2A ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT_ LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Total Release Ci Avg. Diluted Conc. uCi/ml Percent of Limit % 2.02E-01 7.02E-02 5.26E-02 4.62E-02 3.71E-01 3.87E-07 1.20E-07 6.66E-08 6.71E-08 1.43E-07 3.54E+00 1.34E+00 2.70E+00 6.95E+00 7.30E+00 itium 1.64E+01 2.30E+01 3.26E+01 .69E+01 9.90E+01 3.15E-05 3.95E-05 4.13E-05 .90E-05 3.83E-05 3.15E-01 3.95E-01 4.13E-01 .90E-01 3.83E-01 TABLE2A ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 IOACTIVE EF NT ANDE0 PO.L ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES RZPOR'1'FOR 2008 Units Q'fR 1 Q'1'R 2 Q'fR 3 Qft 4 YZAR Fi**ion.nd Aativ.tion 1.'fot.l..1....Ci 2.Avq.Diluted Conca uCi/a1 3.Liait , 2.02B-01 3.87Z-07 3.5411+00 7.028-02 1.20B-07 1.34B+00 5.26.-02 6.66.-08 2.7011+00 4 628-02 6.71Z-08 6.958+00 3.71.-01 1.43B-07 7.30Z+00'fritiua 1.'fotal..1....Ci 2.AVCJ.Diluted Conca uCi/at 3.P.rcentLimit t 1.6411+01 3.1511-05 3.151:-01 2.301:+01 3.958-05 3.958-01 3.26&#xa3;+01 4.1311-05 4.1311-01 2.69.+01 9.902+01 3.9011-05 3.83B-05 3.9011-01 3.832-01 Di**olv.d and 8ntrained G****1.'fot.1..1....Ci 2.Avq.Diluted ConCa uCi/a1 3. , 4.6311-03 5.60B-03 4.70B-03 8.8811-09 9.598-09 5.9511-0'4.442-03 4.80B-03 2.982-03 2.4411-03 3.54B-09 1.77Z-03 1.7411-02 6.728-09 3.3'11-03 Gro**Aiph.Radioaotivity 1.Total Rel.a.e Ci 0.008+00 0.008+00 O.OOB+OO 0.008+00 0.0011+00 Volumeliquid w**te liters 6.832+06 8.61B+06 9.64B+06 9.368+06 3.44B+07 Volume of di1.water liter.5.152+08 5.75&#xa3;+08 7.80&#xa3;+08 6.80B+08 2.558+09 env-tllclARERR01
*20 AG-110M AS-76 RA- CE-1 CO-58 CO-60 -51 37 cu- FE-5 FE-59 131 &--t-1ARERROY 
.2 1 TABLE 28 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS -CONTINUOUS AND BATCH MODES its QTR I QTR 2 QTR REPORT FOR 2008 U ------------------- 
---Fi3sion RU-106 SB-125 Ci O.OOE+00 SR-89 Ci 0-00E+00 S' -------- -------- d Activation Products 9.49E-04 1.08E-03 7.84E-04 5.03E-04 3.31E-03 1.89E-04 O.OOZ+00 1.05E-04 O.OOE+00 2.94E-04 3-68E-05 O.OOE+00 0.00Z+00 O.OOE+00 3.68E-05 31E-03 7.93E-04 6.14E-04 5.832-04 3.30E-03 .29E-03 5.87E-04 4.74E-04 6.16E-04 6.96E-0 7.73E-03 3.63E-03 5.66E-03 4.29E-03 2.13E-0 45E-01 2.53Z-02 1.50E-02 1.50X-02 2.00Z-01 OOE+00 O.OOE+00 5.31E-05 4.05Z-05 9.36E-05 .69E-04 O.OOE+00 5.34E-05 1.41E-04 1.06 56E-02 3.33E-02 2.30E-02 8.80E-03 9.07 .17E-04 O.OOE+00 O.OOE+00 2.07E-05 61E-04 1.58E-04 3.38E-05 1.97Z-05 8.18E- 05E-03 9.33E-04 1.22Z-03 8.02E-03 47E-03 1.69E-03 3.69Z-03 1.15E-OOE+00 0.00E+00 OOE+00 O.OOE+00 O.OOE+00 
.OOE+00 O.OOE+O 0z+00 O.OOZ+O Totals for Period... Ci 0-00E+00 O.OOE+00 nod Gass* 00Z+00 OOE+O 5E-06 O.OOE+00 O.OOE+00 0.00E+00 .OOE+00 O.OOE+00 O.OOE+O 2Z-03 2.76E-03 8.29Z-03 0.00Z O.OOE+00 O.OOE+ -------- --------
TABLE 2B ENTERGY OPERATIONS, INC.GRANO GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND OSAL ANN L REPORT LIQUID EFFLUENTS-CONTINUOUS AND BATCH MODES REPOR.T:fOR 2008 Unit..QTR 1 Q'l'R 2 QTR.3 Q'l'R 4 YEAR Pi**ion and Act.ivat.ion Product..AG-110M Ci 9 49B-04 1.011:-03 7.141:-04 5.031:-04 3.311:-03 AS-76 Ci 1.898-04 0.008+00 1.051:-04 0.00&#xa3;+00 2.94&-04 SA-140 Ci 3 681:-05 0 OOB+OO O.OOB+OO 0.001:+00 3.618-05 CB-141 Ci 1.31B-03 7.93B-04 6.14B-04 5.838-04 3.30B-03 CO-58 Ci 5.298-03 5.171:-04 4.14B-04 6.16B-04 6.968-03 CO-60 Ci 7.738-03 3.638-03 5.66B-03 4.29B-03 2.13B-02 CR.-51 Ci 1.458-01 2.531:-02 1.501:-02 1.501:-02 2.00B-01 CS-137 Ci 0.008+00 O.OOB+OO 5.31B-05 4.051:-05 9.36B-05 CO-64 Ci 8.69B-04 0.001:+00 5.341:-05 1.41&#xa3;-04 1.061:-03 FE-55 Ci 2.561:-02 3.33B-02 2.308-02 8.80B-03 9.078-02 FE-59 Ci 9.17&#xa3;-04 0.00&#xa3;+00 0.00&#xa3;+00 2.071:-05 9.388-04 I-13l Ci 1.618-04 1.511:-04 3.311:-05 1.97B-05 3.731:-04 I-133 Ci 0.008+00 4.731:-05 8.18B-06 0.00&#xa3;+00 5.54&-05 LA-140 Ci 3.81E-03 2.051:-03 9.33B-04 1.22B-03 8.02B-03 MIl-54 Ci 4.718-03 1.471:-03 1.68B-03 3.69B-03 1.15S-02 NB-95 Ci 3.05B-05 0.001:+00 0.001:+00 0.008+00 3.05S-05 NP-239 Ci 8.538-05 0.001:+00 O.OOB+OO O.OOB+OO 8.531:-05 RB-88 Ci 0.008+00 3.391:-04 0.008+00 3.58&#xa3;-04 6.971:-04 aO-l03 Ci 2.011:-05 0.001:+00 O.OOB+OO 0.001:+00 2.01B-05 aU-l06 Ci 3.008-04 O.OOB+OO O.OOB+OO O.OOB+OO 3.00B-04 SB-125 Ci O.OOB+OO 7.431:-06 2.341:-05 6.651:-05 9.73B-05 Sa-19 Ci O.OOB+OO 0.008+00 1.301:-03 1.971:-03 3.2711-03 SR.-90 Ci O.OOB+OO 0.001:+00 1.621:-05 1.091:-04 1.95B-04 SR.-92 Ci 5.35B-05 7.911:-05 3.381:-05 2.241:-05 1.90B-04 TC-99N Ci 1.17.-04 9.83B-06 5.651:-06 0.001:+00 1.938-04 TB-125M Ci 0.001:+00 0.001:+00 0.00&#xa3;+00 4.11B-04 4.17.-04 W-187 Ci 2.00B-05 O.OOB+OO 0.001:+00 0.001:+00 2.00B-05 ZN-65 Ci 4.59B-03 1.32&#xa3;-03 2.76B-03 8.29B-03 1.70B-02 ZN-S9N Ci 3.00B-04 0.001:+00 O.OOB+OO 0.001:+00 3.00B-04 ZR-95 Ci 8.24B-06 0.001:+00 0.001:+00 0.001:+00 8.241:-06........._.._...--.....--.._........_..---_...-----------.-...-----
for Period.Ci 2.021:-01 7.021:-02 5.261:-02 4.621:-02 3.71B-01 Tritiwa B-3 Ci 1.641:+01 2.301:+01 3.261:+01 2.691:+01 9.901:+01..---...........
_____4lIIIl___
---------_......-----Tot.ala for Period.Ci 1.64&+01 2.301:+01 3.261:+01 2.691:+01 9.901:+01 Dissolved and Bntrained Ga***XB-133 Ci 4.171:-03 4.55*.-03 3.97.-03 2.031:-03 1.471:-02 XB-133M Ci 2.01&-05 0.00&#xa3;+00 0.001:+00 1.181:-05 3.19S-05 XE-135 Ci 4.411:-04 1.05B-03 7.311:-04 3.981:-04 2.62S-03---_..........
-...--.--...............-...-----..,...._----.......---...Tot.a.l.for Period.Ci 4.631:-03 5.60B-03 4.10B-03 2.441:-03 1.74S-02 Gro**Alpha Radioact.ivit.y ALPHA Ci 0.00&#xa3;+00 0.00.+00 O.OOB+OO 0.001&+00 0.00&#xa3;+00-----......-..-....._--_..-----....._.-,----.
Totals for Period.Ci 0.001:+00 0.00&#xa3;+00 O.OOB+OO 0.001:+00 0.00&#xa3;+00 e".,*ttJcIARERR01
*21 TABLE 2C ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT RADIOACTIVE EFFLUENT AND WASTE DISPOSAL. ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY -DECEMBER 2008 TABLE2C ENTERGV OPERATIONS, INC.GRANO GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE D POSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY-DECEMBER 2008 Liquid Release Type A.Batch Waste Release Tanks (e)B.SSW Basin (lkfore8kMdownt Sampling Frequency Prior to Release Each Batch Prior to Release One Batch 1M Prior to Release Each Batch Prtorto Release Each Batch Prior to Release Each Slowdown Minimum Analysis Frequency Prior to Release Each Batch 31 Days 31 Days Composite (b)92 Days Composite (b)Prior to Release Each Batch Type of Activity Analysis Principal Gamma Emitters (d)1*131 Dissolved and Entrained Gases (Gamma Emitters)H-S Gross Alpha Sr-age Sr-90 Fe-55 Principal Gamma Emitters (d)'-131 Lower Limit of Detection (lLD)(uClJml)(e) 5)(10-1 1X1()-8 1x10-5 1x10-5 1x10-1 5x10-7 1)(10" NOTE: Footnotes indicated are listed in GGNS ODCM.Appendix A, Table 6.11.1-1. 
: a. Spent resins, filter sludge evaporator bottoms, etc. b. Dry compressible waste, contaminated equipment, et c. Irradiated componants, control rods, etc. stimate No n Oth en v-teclARFRROf 
-2 3 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPO RT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 2008 SOILD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL dia omp TABLE 3 ENTERGY OPERATIONS, INC, GRAND GULF NUCLEAR STATION UNIT jor Nuclide Compositio ssible omp ent resins, filter sludges, evaporator bottoms, et None minated equip drum sealand, mixed waste for volume reductio TABLES ENTERGY OPE IONS, INC.GRAND GULF NUCL S TION UNIT 1 RADIOACTIVE EFFLUENT 0 SPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY-DECEMBER 2008 A.SOILD WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSALNOT IRRADIATED FUEL)1.Type of Wasta.Unit Class A Class B.Class C Est TO:I a.Spent resins, filter sludges, evaporator bottoms, etc.b.Dry compressible waste, contaminated equipment, etc.c.Irradiated c.omponants, control rods, etc.d.Other: 011 drum sealand, mixed waste m 3 7.65E+01O.OOE+OOO.OOE+OO Ci 6.39E+02 O.OOE+OO O.OOE+OO m 3 7.44E+02 O.OOE+OO O.OOE+OO Ci 2.47E+01 O.OOE+OO O.OOE+OO m 3 O.OOE+OO O.OOE+OO O.OOE+OO Ci O.OOE+OO O.OOE+OO O.OOE+OO m 3 O.OOE+OO O.OOE+OO O.OOE+OO Ci O.OOE+OO 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.Irradiatedcomponents,control rods, etc.None d.Other: oil drum sealand, mixed waste for volume reduction.
Isotope (greater than 0.010/0)Co-58 Co-60 Cr-51 Fe-55 Fe-59 Mn-54 Ni-63 Zn-65 C-14 tlnll-ItlcIARERR01
-23 Percent 4.13E-01 1.86E+00 2.79&+00 8.69E+01 1.01E+00 5.63E+00 3.60E-01 5.18E*01 3.30E..01 Curies 2.74E+00 1.24E+01 1.85E+01 5.76E+02 6.75E+OO 3.74E+01 2.39E+00 3.44E+00 2.19E+OO 
: 3. Solid Waste Dispostion e-tocIARERROY - TABLE 3 ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION UNIT RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY- DECEMBER 2008 (Coat} 199.4 ES-2 Js oficlifica- TABLE 3 ENTERGY OPERATIONS, INC.GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE UENT AND ASTE OISPOS NNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY-DECEMBER 2008 (Cont)3.Solid Waste Dispostion 1 10 4 1 7 Destinations Name Durat8k, LLC Duratek, LlC GTS Duratek-Gallaher Road Facility StudsviklRACE LLC Studsvik City Oak Ridge Oak Ridge Oak Ridge Memphis Erwin tate TN TN TN TN TN Mode of Trans ortatlo Southern Pines Hlttman Hittman Studsvlk Loistlcs Hittman NRC Class A A A A A A A Disposal Volume(ft A 3)96 202 1.280 1290 199.4 132.4 202 Description B-25 BOX RWE ES-210 20'SEALAND shielded sealand ES-21 0 (solidification)
EL*142 ES-210 (open top)Number of Containers 14 13 23 1 2 1 1 Waste Type Description DAW-U*NA B25 BOX BR*D-NASRT DAW-U*NA 20FT SL Shielded sealand PR*D-NA CPS/RWCU*B DAW-U-NA DAW-U-NA B.Irradiated Fuel Shipments (Disposition)
NUMBER OF SHIPMENTS MODE OF TRANSPORTATION None WA ent1-tflClARERR01
*24 DESTINATION N/A o-teclARERROI - NEI GPI Ground Water samples are collected from four onsite monitoring wells. Samples were analyzed for gamma emitting nuclides and tritium per the Radiological Environmental Monitoring Program requirements for groun ter. Results are shown in the table that follows. Mw- Groundwater Protection 11nitlative Sample Resin 02 0 TTACHMENT I tiurn Gamma Tritium MDA W-1026B <MDA <MDA <M 1W-1 <MDA <MDA <MDA <M Tritium Gamma Trit <MDA <MDA <MD <MDA <MDA 
<MDA <M tr tr tlnv-tfICIARERR01
*25 ATTACHMENT I NEI Groundwater Protection Initiative Sample Results NEI GPI Ground Water samples are collected from four onsite monitoring wells.Samples were analyzed for gamma emitting nuclides and tritium per the Radiological Environmental Monitoring Program requirements for ground water.Results are shown in the table that fonows.Well 10 1st Otr 1st atr 2nd Qtr 2nd Otr Tritium Gamma Tritium Gamma MW-1020B<MDA<MDA<MDA<MDA MW-1026B<MDA<MDA<MDA<MDA MW-1027B<MDA<MDA<MDA<MDA MW-11348<MDA<MDA<MDA<MDA Well 10 3rd Qtr 3rd Otr 4th Otr 4th Qtr Tritium Gamma Tritium Gamma MW-1020B<MOA<MDA<MDA<MDA MW-10268<MDA<MDA<MDA<MDA MW-10278<MDA<MDA<MDA<MDA MW-11348<MDA<MDA<MDA<MDA}}