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2008 Annual Radioactive Effluent Release Report (ARERR) - Corrected Copy
	ML091910482
Person / Time
Site:	Grand Gulf
Issue date:	07/09/2009
From:	Perino C; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GNRO-2009/00041
	Download: ML091910482 (27)
	v • d • e

{{#Wiki_filter:GNRO-2009/00041 Ju July 9,2009 u.s.

  .S . Nuclear Nuclear Regulatory Regulatory Commissi Commission Attn: Documentt ControlControl Desk Desk ashington, D Washington,         .C. 20555 D.C. 20555

SUBJECT:

Grand Gulf Nuclearr StationStation (GGNS) (GGNS) 20082008 Annual Radioactive Effluent Annual Radioactive Effluent Release Report (ARERR) - Corrected Corrected CopCopy Grand Grand Gulf Nuclear Station, Gulf Nuclear Station, Unit Unit 1 1 Docket Docket No. No. 50-416 50-416 License License No. No. NPF-29 9 REFERENCES :

REFERENCES:

RO-2009/00026, Grand

1. GNRO-2009/00026, Grand G*ulf Gulf Nuclear Nuclear Station Station (GGNS)

(GGNS) 2008 2008 Annualual Radioactive Effluent Release Radioactive Effluent Release Report Report (ARE (ARERR), Submitted Submitted AprilApril 28. 28, 2009 2009

==Dear

Dear Sir Sir or Madam :

==

or Madam: Attached is Attached is a a corrected corrected copy copy of the GGNS of the Annual Radioactive GGNS Annual Radioactive Effluent Effluent Release Release Report Report forfor the period the period January 1, 2008 through January 1,2008 through December 31, 2008 . This December 31,2008. report was This report was previously previously submitted via submitted via aa letter dated April letter dated April 28, 2009 (GNRO-2009/00026}. 28, 2009 (GNRO-2009/00026). The The corrected page is corrected page is page 14 and the corrected information is annotated with a revision bar. Specifically the page 14 and the corrected information is annotated with a revision bar. Specifically the 2008 2008 Airborne Effluent Dose Airborne Effluent (mrem) direct Dose (mrem) radiation as direct radiation as determined determined by thermol,uminescent by thermol*uminescent dosimeter (TLD} dosimeter quarterly totals (TLD) quarterly totals were were corrected corrected and the reported and the reported total value was total value changed was changed from from 2.72 .7 to 3.8 mrem. to 3.8 mrem . A A copy copy of the GGNS of the GGNS Offsite Offsite Dose Dose Calculation Manual was Calculation Manual was also also previously submitted previously submitted via the letter via the letter dated dated April 28, 2009 April 28, 2009 andand requires requires nono correction correction.. This letter does This letter does not ontain any not contain commitme any commitments. If you have e questions questions or or require require additional information concerning additional information concerning these these reports, please reports, please contact contact Mr. Mr. Richard Richard Scarbrough Scarbrough at (601) 437-6978 at (601) 437-6978 or Michael Larson or Michael Larson at (601) 437-668 at (601) 437-6685. Sincerel Sincerely,

                            -{dL c./... P-e<-,',n CLP/MJL CLP/MJL Attachmen

Attachment:

Annual Radioactive Effluentt Release Annual Radioactive Report - Release Report Corrected C

                                                                           - Corrected    Copyp cc:

cc: (See Next Page)

GNRO-2009/00041 Page 2 of 2 cc: NRC Senior NRC Senior Resident Resi Inspector Grand Gulff Nuclear Nuclear Station Station Port Gibson, MS 39150 39150 Commission U.S. Nuclear Regulatory Commission ATTN: Mr. Elmo E. E. Collins, Collins, Jr. Jr. (w/2) ( a Lamar Blvd, Suite 400 612 East ngton, TX Arlington, TX 76011-4005 76011-4005 uclear Regulatory U. S. Nuclear Regulatory Commission Commission Mr. Carl ATTN: Mr. Carl F. F Lyon, Lyon, NRR/ADRO/DORL NRR/ADRO/DORL (w/2)(w/ ATTN: ADDRESSEE ESSEE ONLY0 ATTN : U. ATTN: U . S. S. Postal Postal Delivery Delivery Address Address Only Only Mail Stop Mail Stop OWFN/8 OWFN/8 B1 B1 hington, DC Washington, DC 20555-0001 20555-0001

ENTERGY OPERATIONS, INC. GRAND GULF NUCLEAR STATION ANNUAL RADIOACTNE IOACTIVE EFFLUENTEFFLUENT RELEASE RELEASE REPORT i, 2008 January 1, 2008 -- December December 31, 2008 31,2008 rreoareaBy

                                                                `f 2--0 Copy Corrected Copy July 9,2009 July On Page 14 Only env-teclARERROY -- 1I env-tec1ARERR01

TABLE OF CONTENTS SU13JECT SUBJECT AGE PAGE 1.I. INTRODUCTION INTRODUCTION 44 11. II. DETAILED INFORMATION DETAILED INFORMATION 55 A. Regulatory Limits A. Regulatory Limits 55 1 . 10CFR20

1. 10CFR20 Limits Limits 55 a.

8. Fission and Fission and Activation Activation Gases Gases 55 b.

b. Radloiodlnes Radioiodines andand Particulates Particulates 55

c. Liquid

c. Liquid Effluents Effluents 5 5 2.

2. 10CFR50, Appendix II Limits 10CFR50, Appendix Limits 6 6

a. Fission

a. Fission and and Activation Activation Gases Gases 66

b. Radioiodines and

b. Radloiodines and Particulates Particulates 66

c. Liquid

c. Liquid Effluents Effluents 66 3.

3. 40CFR190 40CFR190 Limits Limits 77 B. Effluent Concentrations B. Effluent Concentrations 77 1 . Airborne

1. Airborne 77

2. Liquid

2. Liquid 77 C. Average C. Average Energy Energy 77 o.

D. Measurements Measurements and and Approximations Approximations of Total Activity of Total Activity 8$ 1 . For

1. For Fission Fission and and Activation Activation Gases Gases 8S

2. For 2.. For Particulates Particulates and and Radioiodines Radioiodlnes 99 For Continuous

3. For

3. Continuous Releases Releases 99

4. For Batch

4. For Batch Releases Releases:: Gases Gases 99

5. For

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

E. Batch Releases Batch Releases 10 10 1 . Liquid

1. Liquid 10 10

2. Gaseous

2. Gaseous 10 10 F. Unplanned Releases F. Unplanned Releases 11 11 1 . Liquid

1. Liquid 11 11 2.

2. Gaseous Gaseous 11 11 E I onv-r.WARRROY

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TABLEBLE OF 0 CONTENTS TS (CONT'D) (C01 T'D) SUBJECT SUBJECT PAGE PAGE G . Estimate G. Estimate of of Total Total Error Error 11 11 1 . Liquid

1. Liquid 11 11

2. Gaseous

2. Gaseous 12 12

3. Solid

3. Solid Radioactive Radioactive Waste Waste 12 12 H. SoUd H. Solid Radioactive Radioactive Waste Waste Shipments Shipments 12 12 I.1. Meteorological Meteorological DataData 12 12 JJ.. Radioactive Radioactive Effluent Effluent Monitoring Monitoring Instrumentation Instrumentation Operability Operability 12 12 K. Annual K. Sewage Disposal Annual Sewage Disposal Summary Summary 12 12 Ill III.. RADIATION DOSE RADIATION

SUMMARY

DOSE

SUMMARY

13 13 A. Water-Related A. Water-Related Exposure Exposure Pathway Pathway 13 13 B. Airborne-Related

8. Exposure Pathway Airborne-Related Exposure Pathway 13 13 IV.

IV. OFFSITE DOSE OFFSITE DOSE CALCULATION CALCULATION MANUAURAOIOACTIVE MANUAL/RADIOACTIVE WASTE WASTE TREATMENT TREATMENT SYSTEM SYSTEM CHANGES CHANGES 15 15 A. A. Offske Dose Calculation Offsite Dose Calculation Manual Manual (ODCM) (ODCM) 15 15 B. B. Radioactive Radioactive Waste Waste Treatment Treatment Systems Systems 15 15 LIST OF LIST OF TABLES TABLES PAGE PAGE I1A A Gaseous Effluents -- Summation Gaseous Effluents Summation of of All All Releases Releases 16 16 113 18 Gaseous Gaseous Effluents Effluents -- Elevated Releases Elevated Releases 17 17 IC 1C Gaseous Gaseous Effluents Effluents -- Ground-Level Ground-Level Releases Releases - - Continuous Continuous 18 18 ID 10 Radioactive Radioactive Gaseous Gaseous Waste Waste Sampling Sampling and and Analysis Analysis Program Program 19 19 2A 2A Liquid Liquid Effluents Effluents -- Summation Summation of of All All Releases Releases 20 20 213 28 Liquid Liquid Effluents Effluents -- Continuous Continuous and and Batch Batch Modes Modes 21 21 2C 2C Radioactive Radioactive Liquid Liquid Waste Waste Sampling Sampling and and Analysis Analysis Program Program 22 22 33 Solid Solid Radioactive Radioactive Waste Waste and and Irradiated Irradiated Fuel Fuel Shipments Shipments 23 23 ATTACHMENTS ATTACHMENTS PAGE PAGE Attachment Attachment'I -- NEI NEI Groundwater Groundwater Protection Protection Initiative Initiative Sample Sample Results Results 25 25 Attachment Attachment 11II -- Offs1te Offsite Dose Dose Calculation Calculation Manual Manual 26 26 .011wtsel"ER."I - 3

I. INTRODUCTION This Annual Radioactive ioac Effluent Release Report (ARERR) R) for for the period of January 1 through December 31, 2008 is submitted in accordance accordance with OOsite site Dose Dose Calculation Manual (ODeM), M), Section Section 5.6.3 5.6 .3 of of Grand Grand Gulf Gulf Nuclear Nuclear Station Station (GGNS) (G License No. NPF-29. The monitortng The ring of of radioactive radioactive effluents effluents isis referenced referenced in in aDeM ODCM Appendix Appendix A, A, Sections Sections 6.11 6.11 and 6.12. and 6.12 Airborne discharges Airborne discharges at GGNS are at GGNS are considered considered ground-level ground-level releases.. releases . AllAll liquid liquid and and airborne discharges airborne discharges to to the the environment environment werewere analyzed analyzed in in accordance accordance with with aDCM OOCM requirements . All requirements.. effluent releases All effluent releases were were within the concentration within the concentration and and total total release release limits lim specified specified by by the the aDCM. ODCM . Projected Projected offsite offsite doses doses were were within within the dose limits the dose limits specified specified byby the OOCM . theOOCM. The The summation summation of all gaseous of all gas eases during releases during thee reporting reporting period period is is given en inin Table Table 1A, 1A, while while elevated releases a elevated releases and ground-level ground-level releases releases are are given given inin Tables Tables 18 I B and d 1C, IC, respectively . Table respectively. Table 1010 describes describes the radioactive gaseous the radioactive gaseous sampling sampling and and analysis program analysis program implemented ted at GGNS . at GGNS. The The summation summation of of all all liquid liquid releases releases during during the the reporting reporting period period is is given given in able 2A, in Table while 2A, while continuous continuous and and batch batch mode mode releases releases areare given given inin Table Table 2B28.. Table Table 2C 20 describes describes the the radioactive radioactive liquid liqUid waste waste sampling sampling andand analysis analysis program implemented at program implemented at GGNS GGNS.. Sol Solid radioactive radioactive waste waste and and irradiated irradiated fuel fuel shipments shipments during during the the reporting reporting period period are are summarized arized in in Table Table 3. 3. The The annual annual summary summary of of meteorological meteorological datadata (joint (joint frequency frequency distribution) distribution) willwill be be maintained maintained on on site site in in a a file file that that shall shall be be provided provided to to the the Nuclear Nuclear Regulatory Regulatory Commission Commission (NRC) (NRC) upon upon request. request. The The option option toto maintain maintain meteorological meteorological data data onon site site is Is in in accordance accordance inistrative Controls with aDeM Administrative Controls Section Section 5.6-3 5.6.3.. sm-tivelAMERRO 1 -*4" ""..,.t.clARERR01

II. DETAILED INFORMATION A. Regulatory Limits 1.

1. 1 0C R limits 10CFR20

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:

                                        =average avers total  to body dose rate in the currenttyear                   (mre Dtb
                                        =XlQ L, K, Q :5 500I
                                                            . S;  500 mrem/yr mrem/yr year (mrem/yr) ve                    ose rate rate inin the the current current year year (mrem/yr)

D. = average skin dose

                                        =XlQ L, (L, + 1.1    1 .1 M, ) Q    I
                                                                             . 3000 mrem/yr S 3000     mrem/yr (mrem/yr) wh e the where    th terms terms are are defined   ed inin the the GGNS GGNS ODeM.

ODCM

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

that: Do = D. = average average organorgan dose rate in current dose rate ent year year (mrem/yr) (mremlyr)

                                        ==Ii Z' WP,Q',

P, 0", <

                                                            ~     1500 mre 1500mrem/yr where re the termss are       defined in are defined        in the the GGNS     C?t}CM .

GINS ODeM.

c. liquid Effluents -- The Liquid Effluents The concentration concentration of of radioactive radioactive materials materials released released in in quid effluents liquid effluen to unrestricted areas from the site shall not exceed at any time time ten times es the the values specified in values specified in 10CFR20, I OCFR20, Appendix Appendix B, B, Table Table 2, 2,

Column 2. CO 2. The concentration of The concentration of dissolved dissolved oror entrained entrained noble noble gases, gases t aced in released liquid effluents In liquid effluents to to unrestricted unrestricted areas areas from from all all reactors at the reactors at the ite, shall site, shall be be limited limited to to 2 2 xx 10'" 10-4 microcuriesiml microcuries/ml total total activity activity..

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It DETAILED INFORMATION (CONT'D)

2. 10CFR50, Appendix I Limits

8. Fission,n and and Activation Activation GasesGases -- The The dosedose from noble gases from noble gases in in Base gaseous effluents to areas at or beyond the site boundary boundary shall shall be be such that:

oy = air dose due to gamma emissions ons from from noble noble gases gases

                                =3.17)( 10'" L, M, XlQ'   X1Q. 0, Q, s 5 mrad/qtr     /qtr

s; 10 mrad/yr o~

ose due air dose due to beta emissions to beta emissions from noble gases from noble gases

                                 =3.177 xx 10'"

10-8 Z, N, X10' LI N, XlQ' q~ :s; < 1010 mrad/qtr mrad/qtr

                                                                      ~   20 mrad/yr 20    mradlyr where where thethe terms terms areare defined d       ed inIn the the GGNS GGNS ODCODCM.

b.

b. Rgdiolodines Radioiodine, and and P-prtigulates Particulates *- The The dose dose toto an individual from an individual from tritium, tritium, 1-131 1-131, 1-133 1-133 and and radioactive radioactive material material in in particulate particulate form form with with half-lives half-Uves greater greater thann 88 days days in gaseous effluents in gaseous effluents shall be such shall be such that that:

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

                                = 3.17
                                =   3.17 xx 10":£,

10'8 E, 8,1111' R, W' Q a. :5s 7.5 mrem/qtr Any 7.5 mrem/qtr Any Organ Organ S515m 15 mrem/yr yr Any Any Organ Organ where where thethe terms terms are are defined defined in in the the GGNSGNS ODCM. ODCM.

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

m DTau DTau =1: [Arrau I t

                                                 ,.1 F,

L\t. Cit F,] 51

                                                                         ~ 1.5 .5 mrem/qtr mrem/qtr Total Total Body Body
                                                                        <~ 55 mrem/qtr mrem/qtr Any Any Organ Organ
                                                                          ~

5 33 mremlyr mremlyr Total Total Body Body

                                                                           ~   10 mrem/yr 10 mrem/yr AnyAny Organ Organ ere the where         terms are the terms     are defined defined in    n the the GGNS GGNS ODCODCM.

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II. DETAILED INFORMATION (CONT'D)

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

are :

                                      <25 mrem/yr, TotalI Body s25                         Body oror anyy Organ Organ except except Thyroid
                                      <7 mrem/yr, s75         m/yr, Thyroid Thyroid s10 mrad y/qtr or s20 mrad        ad "f/yr, Y/yr, Fission Fission and and Activation Activation Gases Gases
                                      <20
                                      ~20    mrad ~/qtr mrad     P/qtr or or s40
                                                               <40 mrad mrad fl/yr, Plyr, Fission Fission and and A    ovation Gases Activation     Gases

515

                                      ~15    mremlqtr or mrem/qtr      or s30

530 mrem/yr, mrem/yr, any any Organ, Organ, Iodine Iodine and and Particulates Particulates

                                      <3  mrem s3 mrem/qtr       or <6 s6 mre mrem/yr,  r, Total   Body, liquid Total Body,             Effluents Liquid Effluents
                                      ~10      remiqtr or mrem/qtr     or s20

520 mre /yr, any mrem/yr, any Organ, Organ, liquid liquid Effluents Effluents B. Effluent Effluent Concentrations Concentrations I1.. Airborne ne The Effluent Concentration The Effluent Concentration limit (ECL) of Limit (Eel) of radioactive radioactive materials materials in in gaseous gaseous effluents effluents is is limited limited byby the dose rate the dose rate restrictions restrictions given in Section given in H .A.I .a. In Section II.A.1.a. this In this case, case, the the ECLs ECls are actually determined are actually determined by by the the dose dose factors factors inin Table Table 2.1-1 2.1-1 of of the the GGNSODCM GGNSODCM..

2.

2. Liquid Liquid The The Effluent Effluent Concentration Concentration Limit Limit (ECL)

(ECl) ofof radioactive radioactive materials materials in in liquid liquid effluents effluents is limited is limited by by ten ten times times the the values values inin 10CFR20, 10CFR20, Appendix Appendix 8, B, Table Table 2, Column 2. 2, Column 2. The The ECL Eel chosen chosen is is the the most most conservative conservative value value of of either the soluble either the soluble or or insoluble insoluble ECL Eel for for each each radioisotope radioisotope..

c. Average Energy Energy Not Not applicable applicable for for GGGNS S UDC ODeM : Appendix Appendix A.

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II. DETAILED INFORMATION (CONT'D) D. Measurements and and ApApproximations of Total Activity low The following discussion details details the the methods methods used used toto measure measure aand approximate total activity for the following: Fission and Activation Gases Particulates Radioiodines Liquid Effluents Table 10 and Tables nd 2C 20 give give sasampling frequencies ies and minimum detectable and minimum se detectable sensitivity requirem requirements for the analysis for the analysis of of aas gaseouss and and liquid liquid effluent effluent streams, streams, respective respectively. Valueses in in the the attached tables given attached tables given as zero do as zero do not not necessarily necessarily im imply that the radionuclides radionuclides werewere not not present present... A zero indicates A zero indicates that that the radionuclide was the radionuclide not present was not present at at levels levels greater greater than than the the sensitivity sensitivity requirements requirements shown shown in in Tables Tables 1010 and and 2C. For 2C. For so radionuclides, lower some radionuclides, detection limits lower detection limits than than required required maymay be be readily readily achievable; achievable; ionuclide is when a radionuclide is measured measured below below its its stated stated detection detection limits, limits. it it is reported. is reported. 1.

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

discharges: Kr-87 Xe-133 Xe-135 Kr-88 Xe-133m Xe-138 Periodic Periodic grab grab samples samples from Station effluent from Station effluent streams streams are are analyzed analyzed by by aa computerized computerized pulse pulse height height analyzer analyzer system system utilizing high-resolution germanium utilizing high-resolution germanium detectors detectors.. (See (See Table Table 10 1 D for for sampling sampling and and analytical requirements.) Isotopic analytical requirements.) Isotopic values values thus thus obtained obtained are are used used for dose release for dose release rate calculations due rate calculations due to effluent to effluent releases releases as as given given in Section IIIt.A.1. in Section .A.I . of of this this report. report. OnlyOnly those radionuclides that those radionuclides that re detected are detected are used in are used in this computation. During this computation. During thethe period period betwe between grab samples, samples, the amount of the amount of radioactivity radioactivity released released is is based based on on the the effluent effluent monitor monitor readings readings.. Monitors Monitors are assigned aa calibration are assigned calibration factorfactor based based upon upon the the last last isotopic isotopic analysis, analysis, using using the the following relationsh following relationship: C. = U ere where I C,t = C = isotopic isotopic calibration calibration factor factor for isotope i for isotope U, = concentration nc tion ofof isotope isotope i1 in in the grab sample the grab sample in pCi/ml. in IJCi/ml. m =net net monitor monitor readi associated with reading associated the effluent with the effluent stream stream (determinedroad atat the timetime of of grab sampling) . grab sampling). enwteclARERR01 env-'ecIARERR01 -*8 8

II. DETAILED DETAILED INFORMATION INFORMATION (CONT'D) These calibration These factors, along calibration factors, along with with the the hourly hourly effluent effluent monitor monitor valuesvalues and and flow fl W rates, are rates, entered into are entered into the the laboratory laboratory computer computer where where the release rates the release rates forfor individual radionuclides are individual radlonuclides are calculated calculated and and stored. stored .. If If no no activity activity is is detected detected in in the th grab sample, grab sample, the the calibration factor defaults calibration factor defaults to to aa historical historical mixture mixture of of Kr-88, Kr-88, Xe-X 133, Xe-135m, 133, Xe-1 35m, Xe-1 Xe-135,35, and and Xe-1 38 .. Xe-138. 2.. Forr Particulates Particulates and nd Radioiodines Radioiodines The radloiodines The radioiod and radioactive and materials in radioactive materials in particulate particulate form form to be consideredonsid are: Zn-65 1-133 Mn-54 Cs-134 Fe-59 Cs-137 Co-58 Ce-141 C0-60 Ce-144 Sr-89 1*131 Sr-90

3. For Continuous Releases Releases ntinuous sampling Continuous sampling is performed on is performed on the the continu continuous release points (i.e.,

Offgas/Radwaste building Offgas/Radwaste Vent, Containment Building Vent, Containment Purge, Purge, Fuel Handl Fuel Handling Area Vent, rbine Building Turbine Building Vent). Vent). Particulate Particulate material material is is collected collected by filtra by filtration . Radioiodines are Radioiodines are collected collected by by adsorption adsorption onto onto a a charcoal charcoal filte filter. Periodically these filters filters are are removed removed and and analyzed analyzed on on the pulse height the pulse height analyzer analyzer to identify and quantify radioactive quantify radioactive materials materia's collected collected on on the the filters. filters. Particula Particulate filters are then filters are then analyzed for analyzed gross alpha for gross and Strontium-89 alpha and Strontium-89 and and -90

                                                                                             -90 as  as required required. Gross alpha       lph determinations are determinations       are made made using using 2-pi 2-pi gas gas flow flow proproportional counter. Strontium...89 and and -90
                                -90 values values are are obtained obtained by    chemical separation by chemical         separation and    and subse SUbsequent analysis using using liquid liquid scintillation scintillation technique techniques. Tritium concentrations are determined                             ed using distillation distillation and and liquid liquid scintillation    techniq scintillation techniques.                 - ing major During       major operational operational occurrences, occurrences, the  the frequency frequency of  of sampling sampl.ing is               aced to is increased              satisfy the to satisfy    the requirements requirements of  footnote "c" offoo*tnote    "c" of of Table Table 10,10, "Radloactiv "Radioactive Gaseous Waste             aste Sampling Sampling and    and Analysis,"

Analysis," (GGNS (GGNS ODCMODCM Appendix Appendix A, A, Table Table 66.11.4-1).

                                                                         .11 .           Currently,ntly, Strontium Strontium analysis analysis is  is erformed by performed      by aa qualified qualified contract contract laborato laboratory.

4. For For Batch Batch Releases Releases:: Gases Gases The e processing processing of of batch batch type type releases releases (from (from Containment Containment Purge Purge or or Turbine Turbine Building Building Occasional Occasional release Point) are Release Point) are analogous analogous to to that that for for continuous continuous releases releases..

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II. DETAILED INFORMATION (CONT'D)

5. Foror Batch Batch Releases:

Relea iqu Effluents Liquid The radionuclides !ides Ilisted below are considered ed when when evaluating evaluatina liquid I effluents: H-3 Sr-90 Mn-54 Mo-99 Fe-55 1-131 Co-58 Cs-134 C0-60 08-137 Fe-59 0e-141 Zn-65 Ce-144 Sr-89 Representative pre-release Representative pre-release grab ab samples samples areare obtained obtained andand analyzed analyzed as as required required by Table by Table 2C. Isotopic analyses 2C. Isotopic ana ses are are performed performed usingusing the the computerized computerized pulse pulse height analysis height analysis system system pr iously described. previously described. Aliquots Aliquots ofof each pre-released each pre-released proportional to sample, proportional to the waste volume volume released, released, are composited in are composited in ordance with accordance with the the requ requirements nts of of Table Table 20. 2C. Strontium-89, Strontium-89, 90 90 and and Iron-55 Iron-55 val values es are obtained by are obtained by chemical chemical separation separation and and counting counting thethe separated separated strontium strontium and iron and iron using using liquid liquid scintillation scintillation techniques. techniques. GrossGross alpha alpha determinations determinations are are madede using using 2-pi 2-pi gas flow proportional gas flow counter.. Tritium proportional counter Tritium isis determined determined using using distillation and distillation and liquid liquid scintillation scintillation techniques. Dissolved gases techniques. Dissolved gases are determined are determined employing grab employing grab samplingsampling techniques techniques andand then then counting counting on on the the pulse pulse height height analyzer system analyzer system.. Currently,Currently, IronIron and and Strontium Strontium analyses analyses areare performed performed by by aa qualified qualified contract contract laboratory. laboratory. E. Batch Releases Releases

1. !quid Liquid

                           -- --------     -----~        ... _---

i1st st Qtr Qtr 2nd 2nd Qtr Qtr 3rd Qtr 3rd Qtr 4th 4th Qtr Qtr Year Year

a. 8.. Number Number of of releases releases 61 61 78 78 87 87 86 86 312 312 Time Period Tlrvw Period in in rninutes) minutes ,. ........ : :,.'

a Total bb b. Total forfor all batches all batches 1 .96E+04 1.96E+04 2.50E+04 2.50E+04 2.78E+04

2. 78E+04 2.73E+04 2.73E+04 '9 .9'7E+04 9.97E+04 c . Max

c. Max timetime for for a a batch batch 4.25E+02 4.25E+02 4.16E+02 4.16E+02 4.30E+02 4.30E+02 4.30E+02 4.30E+02 4.30E+02 4.30E+02 edcd.. Min Avg val time Av T. time for for aa batch batch 3.21 E+02 3.21E+02 3.20E+02 3.20E+02 33.20E+02

                                                                                                     .20E+02       3.17E+02 3.17E+02      3  .20E+02 3.20E+02 e8.. Min    time for Min time     for a a batch batch           2.53E+02 2.53E+02       2.60E+02 2.60E+02      11.10E+02
                                                                                                     .10E+02       2.30E+02 2.30E+02      11.10E+02
                                                                                                                                    .10E+02 2.

2. Gaseo Gaseous 8 No batch releases No batch releases were made during were made during the the report period .

report period.

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II. DETAILED INFORMATION DETAILED IN (CONT'D) F. Abnormal Releases

1. Liquidid mber of

a. Number o Releases:

eleases: o0

b. Total

b. Tota Activity Actin Released:

Released : O .OOE+00 Ci O.OOE+OO C 2.

2. Gaseous Gaseous

a. Number bar of of Releases:

Releases: 33

b. Total

b. Total Activity Activity Released:

Released : 1 .02E-1 Ci 1.02E-1 C! On March On March 19,19, 2008, 2008, one one Turbine Building smoke Turbine Building smoke exhaust exhaust hatch hatch was was found found opened. opened Calculated activity Calculated activity released released was 2 .32E-03 Ci. was 2.32E-03 Ci . The The dose dose and and specific specific activities activities are are included in included in the the applicable applicable sections sections of of this this report. re tin November On November 17, 17, 2008, Turbine Building 2008, Turbine Building smokesmoke exhaust hatches were exhaust hatches were opened opened to to vent smoke vent smoke following following a a fire. fire. Calculated Calculated activity released was activity released was 5.38E-04 5 .38E-04 Ci.C1 . The The dose and dose and specific specific activities are included activities are included in in the the applicable applicable sections sections of this report. of this report. On August On August 21,21 t 2008, 2008, a a Kr-85 Kr-85 gasgas source source was found to was found to be broken on be broken on receipt receipt inspection inspection.. Calculated Calculated activity released was activity released 9 .91 E-02 was 9.91 Ci . The E-02 Ci. dose and The dose and specific specific activities activities are are included included in in the applicable sections the applicable sections of of this this report report.. G. Estimate of Total Estimate of Total Error Error I1. Liquid Liquid The maximum errors The maximum errors are are collectively collectively estimated estimated to to be be asas folio follows:s: Fission & Fission & Activation Activation Tritium Tritium Dissolved Dissolved & & Entrained Entrained Gross Gross Products Products Gases Gases Alpha AI ha Sampling Sampling % 0/0 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 r-Measurement Measurement % 0/0 6.80E+01 6.80E+01 6.50E+01 6.50E+01 6.1 OE+01 6.10E+01 9.20E+01 9.20E+01 TOTAL TOTAL°A. % 7 .30E+01 7.30E+01 7 .OOE+01 7.00E+01 6.60E+01 6.60E+01 9-50E+01 9.50E+01 Sampling Sampling errors errors include include uncertainty uncertainty associated associated with with mixing, mixing, representative representative sampling sampling andand discharge discharge volume volume.. Measurement Measurement errors errors include include uncertainty uncertainty associated associated with with instrument instrument calibration calibration and and thethe preparation preparation and and counting counting of of low-low-activity samples. samples. Counting Counting errors errors are are based based on on measurements measurements of of blank blank samples samples and, and, for for germanium germanium detectors, detectors, the the least-readily-detectable least-readily-detectable radioisotope radioisotope.. Calibration Calibration errors errors are are calculated calculated by by summing summing the the errors errors associated associated w with the calibration calibration ofof aa particular particular instrument instrument with with aa radioactive radioactive source source.. Total Total error error is is calculated calculated by by taking taking the the square square root root of of the the sum sum ofof the the squares squares of of the the individual individual errors errors.. enwteclARERROI env*tecIARERR01-* 11 11

II. DETAILED INFORMATION (CONT'D)

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

Fission & Fission & Activation Activation Grow Gross Gross Products Products Iodine Iodine Particulate Particulate AI ha AI ha Tritium Tritium SamBling R1. 3.20E+01 3.20E+01 2.30E+01 2.30E+01 2.20E+01 2.20E+01 2.20E+01 2.20E+01 2.30E+01 2.30E+01 Measurement % 6.10E+01 6.10E+01 6.70E+01 6.70E+01 6.50E+01 6.50E+01 1 .41E+42 1.01E+02 6.20E+01 6.20E+01 TOTAL OTAL % 6.90E+Oi 6.90E+01 7.14E+41 7.10E+01 6.90E+01 6.90E+01 i .03E+02

                                                                                                            . 1.03E+02      6.60E+01 6.60E+01 M01 dude uncertainty Sampling errors include         uncertainty associated associated with      sample flow, with sample    flow, vent vent flow   and flow and monitor calibration.

Me ement errors Measurement nclude uncertainty errors include associated with uncertainty associated with instrument instrument calibration calibration reparation and and preparation and countingrating of of low-activity low-activity samples. Measurement and samples. Measurement and total total ror are errors calcul are calculated the same by the same methods used for methods used for liquid liquid effluents effluents.. 3.

3. Solid Radioactive Solid Radioactive Waste Waste ee Table See Table 33 for error terms, for error terms.

H. H. Solid Radio Solid Radioactive e Waste Shipmen Waste Shipments See Table See Table 33 for shipme information for shipment information.. I. ologica Data Meteorological The data ata recovery recovery for the reporting for the reporting period period was 99.5°~.. The was 99.5% The predominant predominant windwind direction direction was was from from the the North-East North-East approximately approximately 10.7% 10.7% ofof the time. The the time. The predominant predominant stability stability class class was was class "D" approximately class "0" approximately 32.3% 32.3% ofof theme. the time. Average Average wind wind speed speed during during the the reporting period reporting was approximately period was approximately 4.5 4.5 miles miles per hour. per hour. The annual meteorological The annual meteorological data (Hourly Average data (Hourly Average Data or Joint Data or Frequency Distribution) Joint Frequency Distribution) will will be be maintained maintained onon site site in in aa file file that shall be that shall provided to be provided the NRC to the NRC upon upon request request.. J. Radioactive Radioactive Effluent Monitoring Instrumentation Effluent Monitoring instrumentation opera Operability No No reportable reportable instances instances of of inoperability inoperability occurred occurred during during the the reporting reporting period period.. K. Annual Annual Sewage Sewage Disposal Disposal Summary Summary There There werewere nono sewage sewage disposa disposals in 2008. em-teclARERROI t'ln,,*ttlclARERR01 -* 12 12

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 10CFR50, Appendix I design objectives. Since there re areare no no other other fuel fuel cycle cycle facilities facilities within within 88 kmlam of of GGNS, GINS, 40CFR190 44CFR194 limits have also been met during wring this period. All parameters listed led were were calculated calculated in in accordance accordance with with the the GGNS GGNS ODeM. ODCM A. ter-Related Exposure Water-Related Exposure Pathways Pathways The values The values calculated calc ted inin this this section section utilize utilize the the information information provided provided in in Tables T and 28 2A and 2 of this report of this report and a thee calculational calculational methodology methodology of of the the ODeM. ODCM Liquid Effluents Total body ody dose dose and and critical critical organ organ doses doses areare computed computed for for the the maximum maximum exposed individual. exposed individual . TheThe maximum maximum dose contribution from dose contribution from liquid liquid effluents effluents is considered considered to to occur occur in in the adult age the adult age group group viavia consumption consumption of fish. of fish. 2008 U uid Effluent ZVUO Liquid nose (mrem) Effluent Dose mrem I Bone 80ne I I it Qtr 1st Qtr 3.89E-02 3.89E-02 2nd 2nd Qtr Qtr 1.88E-02 3rd Qtr 3rd 1 .88E-02 5.17E-02 Qtr 4th Qtr 4th 5.17E-42 11.04E-01 Qtr Qtr

                                                                                               .04E-01 TOTAL TOTAL 2.15E-01 2.15E-01 Liver Liver               11.19E-01
                                              .19E-01        4.47E-02 7.61 4.47E-02              E-02 2 7.61E-02          .16E-01 2.16E-01        4.57E-01 4.57E-01 Thyroid Thyroid             4.72E-03 4.72E-03         6.03E-03        2.91 E 2.57E-03 6.03E-03 2.91E-03               2.57E-03         1 .60E-02 1.60E-02 Kidney Kidney              7.40E-02 7.40E-02        2.58E-02 2.58E-02 4.58E-02 4.5SE-02 11.41E-01.41 E-01      2.88E-01 2.88E-01 Lung Lung                3.47E-03 3.47E-03        4.89E-03 4.89E-03 4.84E-03 4.84E-03 3        .51 E-03 3.51E-03         1 .67E-02 1.67E-02 GI-1.1.1 G'-LLI              11.44E-01
                                              .44E-01        4.76E-02 4.76E-02 6.17E-02 6.17E-02 11.60E-01.60E-01       4.15E-0011 4.15E-01 t Whole Whole BodyBody      5.31   E-02 .

5.31E-02 2.01E-02 2.01E-02 4.05E-021 4.05E-02 11.04E-01.04E 2.i9E-01 2.19E-01 B. Airborne-Related Airborne-Related Exposure Exposure Path Pathways ays The The values values presented presented in in this this section section utilize utilize information information provided provided in in Tables Tables I1AA and I C of and 1C of is report this report and and the the calculational calculationa' methodology methodology of of the the ODCM ODeM.. DoseDose andand dose dose rates rates are are computed for computed for locations locations at at the the site boundary or site boundary or at at unrestricted unrestricted areas areas beyond beyond the the site site boundary. boundary. Because Because members members of of the the public public may, may, onon occasion, occasion, be be found found within within the the site site boundary, boundary. lace locations within th the the site site boundary boundary were were considered considered whenwhen selecting selecting locations locations for for dose dose calcu ations . calculations. Consideration Consideration of of site site haunch boundary locations locations as as well well as as unrestricted unrestricted areas areas within within and and beyond beyond the the site site boundary boundary provides vides assurance assurance that that offsite offsite doses doses will wilt not not be be substan substantially underestimated ated while attempting ing to to provide provide an an accurate accurate dose dose calculation calculation.. The The most most limiting locati locationon for for aa member of the publicpublic is is used used for for the the dose dose calculations. calculations. During During routine routine operations operations the dispersion dispersion and and deposition depositionfactors factors used used forfor dose dose calculationslions are are from from historical al annual annual average average meteorological meteorological data. data. &--teclARERR01 - I$

III. RADIATION DOSE

SUMMARY

(CONT'D) Organ Dose The maximum organ organ dosedose to to aa MEMBER MEMBER OF OF THETHE PUBLIC PUBLIC (critical (critical receptor) receptor) from fro radioiodines, tritium and particulates was calculated Iculate for this report using the most recent land use census and dispersion and deposition ositio parameters from 2008 meteorological data. The critical receptor e residence was determined to be located in the southwest sector at at aa distance distance of 1432 meters (0.89 miles) from the plant. Pathways of 1432 ways cons Bred for considered for use use inin the the organ organ dose calculations are dose calculations are inhalation, in mono mane, ground plane, grass/cow/meat ea and vegetation. getation . There There is is no no grass/cow/milk pathway within in five five miles mile of GGNS . It GGNS. It was was asassumed med that that thethe ageage group group receiving receiving the ma the maximum dose lived dose lived atat the the residence and residence and thatt the receptor consumed the receptor consumed food food products products that that weree raisedraised oror produced produced the residence. at the residence Average Total Total Bodv Body and and Skin Skin DoseDose Rate Rate Individual total Individual total body body andand skinskin dose dose rates rates from from exposure exposure to to aa semi-infinite semi-infinite cloud cloud of of noble noble gas gas are are computed computed for for aa location location in in thethe south sector at south sector at a distance of a distance of 644 644 mete meters (0.40 miles) from the miles) from the plant. plant. This This location location corresponds corresponds to the highest to the highest annual annual average average atmospheric atmospheric dispersion dispersion factor factor for for a a location location at at an unrestricted area an unrestricted area within within the the site site oundary. boundary. The total The body and total body and skin dose rates skin dose reported are rates reported are the the quarterly average of quarterly average of the the maximum maximum instantaneous dose rates determined daily during the reporting period and would instantaneous dose rates determined daily during the reporting period and would represent represent the the maximum maximum possiblepossible dose dose rate rate received received by by members members of of the the public public.. Air Dose From Air Dose From Gamma Gamma and and BetaBeta Emissions Emissions Air Air doses doses from from gaseous gaseous effluents effluents were were calculated calculated for this report for this report using using dispersion dispersion parameters parameters from from the 2008 meteorological the 2008 meteorological data. data. The The highest dispersion factor highest dispersion factor forfor an an unrestricted unrestricted area was in area was in the the south south sector sector within within thethe site site boundary, boundary, 644 meters 644 meters (0.40 (0.40 miles) miles) from from the the plant. plant. Direct Direct Radiation Radiation Direct Direct radiation radiation dosedose is is calculated calculated by by subtracting subtracting average average doses doses measured measured by thermoluminescent dosimeter thermoluminescent dosimeter (TLD) (TLD) badges badges located located at at control control locations locations from from average average doses doses measured measured by by TAD TLD badges badges locatedlocated near near thethe site site boundary boundary.. GGNS GGNS reported reported measured doses measured doses in in 2008 2008 as as netnet exposure exposure normalizednormali%ed to to 9292 days. days. 2008 Airborne Effluent Dose (mrem): 1st ---Qtr ~ 2nd Qtr 3rd Qtr TOTAL Iodine, Tritium & Particulat Percent of Limit 1 .65E-01 2 .20E+00 I 5 .77E-03 2 .95E-02 I 7 .70E-02 _~_3 .94E-01 1_ _2.28E-01 1 .71 E-02 2.18E 1 .45E 00 Total 1 .28E-01 E-01 I 2 .46E Percent of Limit 0 .026% 0.059% 0 .049% Skin Dose Rate (mrern/yr) 4 .40E Percent of Limit 0 .010% 0 .015% 0 .017% Gamma Air Dose* 9 .66 5. 3E-02 6 .62E-02 1 .03E-01 Percent of Limit 1 .93E+00 1 .11 E+00 1 .32E+00 Air Do e* 6 .OOE-02 2 .45E-02 3 .36E-02 2.39E-01 Percent of Limit 6 .OOE-01 2 .45E-01 3 .36E-01 E+00 1.40E+OO OO.OOE+OO

                                                                                                             .OOE+00        11.10E+OO
                                                                                                                               .10E+0        33.80E+OO
                                                                                                                                               .80E surement units
                    *Measurement     units are are mrad mrad env-tec/A RERROI1 -14 Correc Corrected       d Page Page env-teclARERRO    - 14 July 9,2009

IV. OFFSITE DOSE CALCULATION MANUAL! RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES A. Offsite Dose CalculationnMan Manual LODCMJ Revision 36 Revision 36 to to the the aDCM ODCM was issued during was issued during the the reporting reporting period. perio TheThe changes changes are summarized are summarized below. below . evision 36: Revision 36: Adds Adds Table Table 2.2-1.b. 2.2-I .b, "Pathway "Pathway Dose Dose Factors Factors for for LCO 6.111 .4 and LCO 6.11.4 and Section Section 2.2 .1 ..b, 2.2.1 (Pi)", for b, (Pi)". for age age group group "Child".

                                                         "Child".

Changes note Changes note for section 2.2. for section 2.2.1 .b to

                                                          . 1.b  to use use Child Child Inhalation Inhalation Pi  values from Pi values  from table table 2.2-1 b..

B.. Radioactive Waste Radioactive Waste Treatment Treatment_ Systems Systems No major No major changes changes were mad, to thee liquid were made liquid or or gaseous radwaste treatment gaseous radwaste treatment systems systems in i 2008 2008.. en,-WIARERRO1 tJntl-tIJClARERR01-* 15

BLE 1A TABLE 1A ENTERGY OPERATIONS, ENTERGY OPERATIONS, INC. INC. GRAND GULF GRANO GULF NUCLEAR NUCLEAR STATION STATION UNIT UNIT 1 EFFLUENT AND EFFLUENT AND WASTE WASTE DISPOSAL DISPOSAL ANNUAL ANNUAL REPORTREPORT GASEOUS EFFLUENTS GASEOUS EFFLUENTS -- SUMMATION SUMMATION OF ALL RELEASES OF ALL RELEASES REPORT FOR REPORT FOR 2008 2008 u its Unit.. QTR 11 Qn QTR 22 Q'1'R QTR 33 Q'l'R QTR 4 QTR YZAR Fission .nd Activ.t.ion Fi**ion Activation G**** Gases t 1 aele...

1. '1'ot..l Rol Ci .75E+02 1.158+02 6 .47E+01 6.418+01 8 .76E+01 8.161:+01 1 .16E+02 1.168+02 44 .43E+O 438+02 Avg . R.I****

2. Avq. Release RateRate uCi/.ec uCi/sec .22E+01 2.2211+01 8 .24E+00 8.248+00 1 .10E+01 1.1011+01 1 .45E+01 1.4511+01 1 .40E+01 1.408+01 3 . Percent

3. Percent of of '1'8 TS LiJD.it Limit ,% 93e+00 1.93.+00 1 .11E+00 1.111:+00 1 .32E+00

1. 32B+00 2 .052+00 2.058+00 3 .21E+00 3.2111+00 di 131 Iodine-131

1. Total Relea.e Tot..l Release Ci 389-03 9.38B-03 1 .42E-04 1.42B-04 1 .36E-03 1.36B-03 9 .11E-04 9.11B-04 1 .18Z-02 1.181:-02

2. Avg . Release Rate uCi/.eo Avq.ReI**** 19E-03 1.19B-03 1 .81E-05 1.811:-05 1 .71E-04 1.711:-04 1 .15E-04 1.15B-04 3 .73E-04 3.738-04

3. Percent t ofT. LiJD.it , 05Z+00 2.05£+00 3 .11Z-02 3.11B-02 2 .96E-01

2. 96B-Ol 1 .99E-01 1.99B-01 1 .29E+00 1.29B+00 Particul.1:e. Halt' Life >- 8 day.

1. Total Rel.a.e Ci 9.13B-05 3. 61B-05 7.751:-06 1.56B-05 1.51B-04

2. Avq. Rele*** Rat. uCi/ **c 1.161:-05 4.591:-06 9.761:-07 1.911:-06 4.771:-06

3. Percent of '1'8 Limit , 1.14B-Ol 1. 65B-02 6.25B-02 7.131:-03 1.00B-01 Trit.iua

1. Tot.al R.I.... Ci Ci 33.298+00

                                                       .29E+00     2 .40Z+00 2.40B+00    2.8511+00    1.77'&+00  1.03B+01

2. Avq. Rel.a** Rat. uCi/ **c 4.19B-01 3.05B-01 3.5911-01 2.23'&-01 3.26B-01

3. Percent cent of TS L~t , 4.038-02 2.941:-02 3.4911-02 02 2.17B-02 6. 32B-02 Gross ~ph. Ra~oactivit.y

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 env-teclARERROY tllJv-tacIARERR01-* 16 IS

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 (Not Applicable -- GGNS GGNS Relea.e. Releases Are Are Considered Considered Ground-Level) Ground-Level) env-feclARERRO! tlnv-t"clARERR01 -.. 17

TABLE 1C TABLE I ENTERGY OPERATIONS, ENTERGY OPERATIONS, INC. INC, GRAND GULF GRAND GULF NUCLEAR NUCLEAR STATION STATION UNIT UNIT 1 EFFLUENT AND EFFLUENT WASTE DISPOSAL AND WASTE DISPOSAL ANNUAL ANNUAL REPORT REPORT GASEOUS EFFLUENTS -- GROUND-LEVEL GASEOUS EFFLUENTS GROUND-LEVEL RELEASE-CONTINUOUS RELEASE-CONTINUOUS REPORT REPORT FOR FOR 2008 2008 u Unit. QTR 11 Q'J.'R QTR 2 QTR Q'J.'R 3 Q'J.'R 4 YEAR Fission a d Activation Pission and tivation Gas** Gas* AR-41 Aa-41 ci Ci 44.128+00

                                                      .12E+00      77 .92E+00 9211+00   3 .57E+00 3.511:+00       4 .16E-01 4.16£-01          1 .60E+01 1.601:+01 KR-85 tal-IS                          ci Ci         O .OOE+00 0.008+00         O .OOE+00 0.0011+00          9 .91E-02

9. 91Z-02 O .OOE+00 O.OOZ+OO 9 .91E-02 9.9111-02 KR-85H KIt-85M ci Ci 44.478+01

                                                      .47E+01       22.21£+01
                                                                        .21E+01       7 .82E+00 7.82.+00        2 .06E+00 2.06£+00          7 .67E+01 7.6711+01 KR-87 m-81                            ci Ci         11.6411-01
                                                      .64Z-01       O0.00&+00
                                                                        .OOE+00       O .OOE+00 0.00.+00        2 .03E+00 2.03£+00          2 .20E+00 2.208+00 KR-88 KR-88                           ci Ci         11.3811+01
                                                      .38E+01        9 .11E+00 9.1111+00        1 .89E+00 1.89&+00        1 .01E+00 1.011:+00         2 .58E+01 2.58.+01 KR-89 tal-BI                          ci Ci         O0.008+00
                                                      .OOE+00        O .OOE+00 0.00&+00         O .OOE+00 0.00&+00         66 .53E+00
                                                                                                          .. 53&+00    66.53&+00
                                                                                                                          .53E+00 XIE-133 D-133                           ci Ci         66.6311+01
                                                      .63E+01        9 .20E+00 9.201:+00        1 .02E+01 1.021:+01       11.01&+01
                                                                                                          .01E+01      99.58Z+01
                                                                                                                          .58E+01 XE-133H XE-133M                         ci Ci         11..66E-01 66B-01        O .OOE+00 0.008+00         O .OOE+00 0.001:+00       O0.00&+00
                                                                                                          .OOE+00      1 .66E-01 1.661:-01 XE-135 XlI-135                         ci Ci         11.088+01
                                                      .08E+01       44.811:+00
                                                                        .81E+00       1 .26E+01 1.26.+01       11 .36E+01
                                                                                                          . 368+01     4 .18E+01 4.188+01 XE-135H XE-135M                         ci Ci         22.21Z+01
                                                      .27E+01        9 .84E+00 9.848+00         3 .63E+01 3.63£+01        22.218+01
                                                                                                          .27Z+01      99.15&+01
                                                                                                                          .15E+01 XE-137 D-131                           ci Ci          1 .46E+00

1. 46Z+00 O .OOE+00 0.001:+00 O .OOE+00 0.001:+00 2 .87E+01 2.81&+01 3 .02E+01 3.021:+01 XE-138 XB-138 ci Ci 1 .07E+01 1.018+01 1 .73Z+00

1. 73Z+00 1 .50E+01 1.50.+01 2 .84E+01 2.84&+01 5 .59E+01 5.59£+01 Total*

Total. for fox Poriod . . . Pexiod ... Ci Ci 1 .75Z+02

1. 75Z+02 6 .47Z+01 6.41Z+01 88.76&+01

                                                                                         .76E+         1.16Z+02         4.43Z+02 Iodin**

1-131 Ci 9.38Z-03 1.42B-04 1.36Z-03 9.11Z-04 1.181:-02 1-133 Ci 9.861:-03 1.14B-03 5.26.-03 5. 97B-04 1.69B-02 1-135 Ci 1.14S-04 1. 62Z-03 9.13Z-04 1.20B-04 2.71.-03 Total. fox Period ... Ci 1. 94B-02 2.90B-03 7.538-03 1.63B-03 3.14Z-02 CZ-141 58 CO-58 CO-60 Ca-51 41 60 ci Ci ci Ci Ci Ci Paxticulat.. 253 O .OOZ+00 0.001:+00 2 .7 2.72B-06 4.58B-06 7.21B-05 Bal~ Li~. 0 .00z+ 0.001:+00 1.28B-06 2.071:-06 1.258-05

                                                                                 >- 8 day.

O0.001:+00

                                                                                         .OOE+00 O0.008+00
                                                                                         .00E+00 OOE+00 2E-06 1.22£-06 22 .05E-09
                                                                                         .. 058-06 3 .92E-06 00.001:+00
                                                                                                          .00E+00 88.12B-07
                                                                                                          .12E 2.36&-06 0.00&+00 5 .11E-0.001:+00 4.811:-06 1 .. 021:-05 8.671:-05 CS-131                          Ci             00Z+00 0.00£+00         O .OOE+00 0.008+00         55.698-08
                                                                                         .69E-08       1.208-06        1.268-06 n:-59                           Ci            .00X+00 0.001£+00        4 .78Z-06 4.788-06         O0.008+00
                                                                                         .OOZ+00      O0.008+00
                                                                                                          .OOZ+00      44.78B-06
                                                                                                                          .78E-MN-,54                          Ci             5SE-06 1.581:-06        66 .32E-06
                                                                         .. 321:-06   O0.001£+00
                                                                                         .OOE+00      22.211:-06
                                                                                                          .21E-06      1 .01Z-05 1.018-05 ItO-106                         Ci         00.008+00
                                                      .00Z+00       33.931:-06
                                                                        .93Z-06       OO.OOB+OO
                                                                                         .OOE+00      O0.00&+00
                                                                                                          .OOZ+00     33.931£-06
                                                                                                                          .9 Sa-89                          Ci          9.04Z-06         5.238-06            .42E-06 4.42Z-06       11.16£-06
                                                                                                          .16Z-06      1 .99E-05 1.998-05 ZH-65                          Ci         0O.OOB+OO
                                                      .00X+00       0O.OOB+OO
                                                                        .002+00       OO.OOB+OO
                                                                                         .OOE+00      33.18B-06
                                                                                                          .98E-06     33..98Z-0 98B-06
                                                    ~--..,-.-,--     _.... ..

Totals 13E-05 3 .61Z-05 7 .75Z-0

                                                             !'ritiwa B-3                             Ci          3.2911+00        2.40&+00         2.85B+00       1.77B+00          1.038+01
        !'otal.      ~or  Period... Ci          3.29B+00         2.4011+00        2.85&+00       1.77.+00         1.03B+01 Gxo** Alpha
                                                       ~ph& Radioactiv Radioactivity ALPHA                           Ci         2.21.-08        0.00.+00           1.77£-08       1.481:-08        5.47B-08 Toeals for Period ...           Ci         2.21B-08        O.OOZ+OO           1.77£-08       1.48B-08         5.47£-08

--t.clARERROY env.teeIARERR01 -* 18 18

TABLE 10 TABLE 1D ENTERGY OPERATIONS, ENTERGY OPERATIONS, INC..INC. GRAND G GRAND GULF NUCLEAR NUCLEAR STATION STATION UNIT UNIT 1 EFFLUENT AND EFFLUENT AND WASTE DISPOSAL TE DIS ANNUAL REPORT L ANNUAL REPORT Radioactive Gaseous Radioactive Gaseous Waste Sampling and aste Sampling and Analysis Analysis Program Progra JANUARY -- DECEMBER JANUARY DECEMBER 20082008 Lower Limit Sampling Minimum Analysis Type of ActiVity of Detection Gaseous Release Type Frequency Frequency Analysis (LLD) ( uCilml)* A. (1) Radwaste Building 31 Days 31 Days Principal Gamma Ventilation Exhaust Grab Sample (f) Emitters fb.e) 1x10.... H-3 1X10'" (2) Fuel Handling Area Continuous 7 Days (c) '-131 1x10-12 Ventilation Exhaust (d)(f) Charcoal Sample 1-133 1)(10-10 (3) Containment Continuous 7 Days (c) Principal Gamma 1x10-11 Ventilation Exhaust (d)(f) Particulate Emitters (e) ('-131, Sample Others) (4A) Turbine Building Continuous 31 Days Gross Alpha 1)(10-11 Ventilalion Exhaust (d)(f) Composite Particulate (4B) Turbine Building Sample Occasional Continuous 92 Days Sr-89, Sr-90 Release Point (d)(f) Composite (when in service) Particulate Sample Continuous (f) Noble Gas Noble Gases Gross 1xi 0'" Monitor Beta or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma 1)(10'" Treatment Exhaust, Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10'" Treatment A Sample (f) Emitters(e) Exhaust, whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma TreatmentS Sample (f) Emitters(e) Exhaust, whenever there is flow NOTE NOTE: Footnotes indicated are listed in GGNS GGNS ODCM, ODeM, Appendix Appendix A, Table 1 .4-8.11.4-1. env-lecIARERR01 " 19

                                                         "ABLE 2A TABLE2A ENTERGY ENTERGY OPERATIONS, OPERATIONS, INC. INC.

GRAND GRAND GULF NUCLEAR STATION GULF NUCLEAR STATION UNIT UNIT 1 RADIOACTIVE IOACTIVE EF EFFLUENT AND WASTE NT AND E DISPOSAL 0 PO .L ANNUAL ANNUAL REPORT REPORT_ LIQUID EFFLUENTS - LIQUID EFFLUENTS - SUMMATION SUMMATION OF OF ALL ALL RELEASES RELEASES REPORT FOR RZPOR'1' 2008 FOR 2008 Units Q'fR 1 Q'1'R 2 Q'fR 3 Qft 4 YZAR 11.. 2. 2. Total

                'fot.l .

Avg

                          .1....

Release, Avq.. Diluted Diluted Conc Ci Fi**ion .nd Aativ.tion Conca. uCi/a1 Ci/ml 22.02B-01

                                                        .02E-01 33..87E-07 87Z-07 77.028-02
                                                                      .02E-02 11.20B-07
                                                                      .20E-07 P~oduct.

5 .26E-02 5.26.-02 66.66.-08

                                                                                     .66E-08 4 .62E-02 4  628-02 6 .71E-08 6.71Z-08 33.71.-01
                                                                                                           .71E-01 1 .43E-07 1.43B-07 33.. Percent P.~cent of  o~ Limit Liait        ,        3 .54E+00 3.5411+00        .34E+00 11.34B+00      2 .70E+00 2.7011+00   6 .95E+00 6.958+00  7 .30E+00 7.30Z+00 itium
                                                             'fritiua

1. Total .

                'fotal   Release
                          .1....         Ci Ci          11.6411+01
                                                        .64E+01    22.301:+01
                                                                      .30E+01     33.26£+01
                                                                                     .26E+01    .69E+01 2.69.+01  99.902+01
                                                                                                           .90E+01

2. Avg AVCJ.. Diluted Diluted Conc Conca. uCi/at uCi/ml 33.1511-05

                                                        .15E-05     3 .95E-05 3.958-05      44.1311-05
                                                                                     .13E-05    .90E-05 3.9011-05 33.83B-05
                                                                                                           .83E-05

3. Percent P.rcent of Limit o~ Limit %t 33.151:-01

                                                        .15E-01     3 .95E-01 3.958-01      44.1311-01
                                                                                     .13E-01    .90E-01 3.9011-01 33.832-01
                                                                                                           .83E-01 Di**olv.d and 8ntrained G****

1. 'fot.1 . .1.... Ci 4.6311-03 5.60B-03 4.70B-03 2.4411-03 1.7411-02

2. Avq. Diluted ConCa uCi/a1 8.8811-09 9.598-09 5.9511-0' 3.54B-09 6.728-09

3. P.~c.nt o~ L~it , 4.442-03 4.80B-03 2.982-03 1.77Z-03 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 Volume o~ liquid 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£+08 7.80£+08 6.80B+08 2.558+09 RERROI-* 20 env-tllclARERR01 20

TABLE TABLE 2B 28 ENTERGY OPERATIONS, ENTERGY OPERATIONS, INC INC.. GRAND GRANO GULF GULF NUCLEAR NUCLEAR STATION STATION UNIT UNIT 11 RADIOACTIVE EFFLUENT RADIOACTIVE EFFLUENT AND AND WASTE DISPOSAL OSAL ANNUAL ANN L REPORT REPORT LIQUID LIQUID EFFLUENTS EFFLUENTS -CONTINUOUS

                                                         - CONTINUOUS AND                        AND BATCHBATCH MODES       MODES REPORT FOR REPOR.T    :fOR 2008 2008            U its Unit..          QTR QTR I1                  QTR 22 Q'l'R                     QTR 3 QTR.                 Q'l'R 4       YEAR Fi3sion and Pi**ion           d Act.ivat.ion Activation Products          Product..

AG-110M AG-110M Ci 99 .49E-04 49B-04 1 .08E-03 1.011:-03 77.141:-04

                                                                                                            .84E-04           55.031:-04
                                                                                                                                  .03E-04     3 .31E-03 3.311:-03 AS-76 AS-76                           Ci         11.898-04
                                                          .89E-04            O .OOZ+00 0.008+00                  11.051:-04
                                                                                                            .05E-04            O .OOE+00 0.00£+00       2 .94E-04 2.94&-04 RA-SA-140                          Ci         3-68E-05 3 681:-05             O0 .OOE+00 OOB+OO            0O.OOB+OO
                                                                                                            .00Z+00           O0.001:+00
                                                                                                                                  .OOE+00     33.618-05
                                                                                                                                                .68E-05 CE-1 CB-141                          Ci                 31E-03 1.31B-03              77..93E-04 93B-04            66..14E-04 14B-04           5 .832-04 5.838-04       3 .30E-03 3.30B-03 CO-58 CO-58                           Ci              .29E-03 5.298-03               5 .87E-04 5.171:-04                       .74E-04 44.14B-04               66..16E-04 16B-04    66.968-03
                                                                                                                                                .96E-0 CO-60 CO-60                           Ci         77.738-03
                                                          .73E-03            3 .63E-03 3.638-03                   5 .66E-03

5. 66B-03 44.29B-03

                                                                                                                                  .29E-03     22.13B-02
                                                                                                                                                .13E-0
              -51 CR.-51                          Ci                 45E-01 1.458-01              2      .53Z-02 2.531:-02                  1 .50E-02 1.501:-02              1 .50X-02 1.501:-02      22.00B-01
                                                                                                                                                .00Z-01 CS-13737                        Ci                 OOE+00 0.008+00               O .OOE+00 O.OOB+OO                   5 .31E-05

5. 31B-05 44.051:-05

                                                                                                                                  .05Z-05     99.36B-05
                                                                                                                                                .36E-05 cu-CO-64                           Ci               .69E-04 8.69B-04               O .OOE+00 0.001:+00                  5 .34E-05 5.341:-05              1 .41E-04 1.41£-04       11.061:-03
                                                                                                                                                .06 FE-5 FE-55                           Ci                 56E-02 2.561:-02              33.33B-02
                                                                                   .33E-02              2 .30E-02 2.308-02               8 .80E-03 8.80B-03       99.078-02
                                                                                                                                                .07 FE-59 FE-59                           Ci               .17E-04 9.17£-04               O .OOE+00 0.00£+00                   O .OOE+00 0.00£+00               2 .07E-05 2.071:-05       9.388-04 131 I-13l                           Ci                 61E-04 1.618-04               1 .58E-04 1.511:-04                  3 .38E-05 3.311:-05              1 .97Z-05

1. 97B-05 3.731:-04 I-133 Ci 0.008+00 4.731:-05 8 .18E-8.18B-06 0.00£+00 5.54&-05 LA-140 Ci 3.81E-03 05E-03 2.051:-03 9 .33E-04

9. 33B-04 1 .22Z-03 1.22B-03 88.02B-03

                                                                                                                                                .02E-03 MIl-54                          Ci           4.718-03                      47E-03 1.471:-03                  1 .69E-03 1.68B-03               33..69Z-03 69B-03    11.15S-02
                                                                                                                                                .15E-NB-95                           Ci          3.05B-05                       OOE+00 0.001:+00                 0 .00E+00 0.001:+00              0.008+00        3.05S-05 NP-239                          Ci          8.538-05                       OOE+00 0.001:+00                 O .OOE+00 O.OOB+OO                O.OOB+OO       8.531:-05 RB-88                           Ci           0.008+00               3.391:-04                 O .OOE+00 0.008+00                3.58£-04       6.971:-04 aO-l03                          Ci           2.011:-05              0.001:+00                      .OOE+00 O.OOB+OO               O0.001:+00
                                                                                                                                  .OOE+O       2.01B-05 RU-106 aU-l06                          Ci           3.008-04               O.OOB+OO                   O.OOB+OO 0z+00        OO.OOB+OO
                                                                                                                                  .OOZ+O       3.00B-04 SB-125 SB-125                          Ci Ci          OO.OOB+OO
                                                           .OOE+00            7.431:-06                 2.341:-05               6.651:-05      9. 73B-05 SR-89 Sa-19                           Ci Ci          0-00E+00 O.OOB+OO               0.008+00                   1.301:-03              1.971:-03      3.2711-03 S'

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 5E-06 O0.001:+00

                                                                                                                                  .OOE+00      1.938-04 TB-125M                         Ci           0.001:+00             O0.001:+00
                                                                                   .OOE+00              0 .00E+00 0.00£+00                4.11B-04       4.17.-04 W-187                           Ci          2.00B-05                     .OOE+00 O.OOB+OO                  O .OOE+00 0.001:+00              O0.001:+00
                                                                                                                                  .OOE+O       2.00B-05 ZN-65                          Ci           4.59B-03               1.32£-03 2Z-03            2 .76E-03 2.76B-03               88.29B-03
                                                                                                                                  .29Z-03      1.70B-02 ZN-S9N                         Ci           3.00B-04               0.001:+00                  O.OOB+OO              00.001:+00
                                                                                                                                  .00Z         3.00B-04 ZR-95                           Ci           8.24B-06               0.001:+00                 O0.001:+00
                                                                                                             .OOE+00           O0.001:+00
                                                                                                                                  .OOE+        8.241:-06 Tot.a~a      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 nod Ga*** Gass* 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£+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£+00 0.00.+00 O.OOB+OO 0.001&+00 0.00£+00

                                                      ----- ...       ~-
                                                                             ~       - _- --------
                                                                                                                              --------        -------~

Totals Totals for for Period Period.. . . Ci Ci 0-00E+00 0.001:+00 O0.00£+00

                                                                                   .OOE+00                    00Z+00 O.OOB+OO                     OOE+O 0.001:+00       0.00£+00

&--t-1ARERROY e".,*ttJcIARERR01 .* 21 21

TABLE TABLE2C 2C ENTERGY OPERATIONS, INC. ENTERGV OPERATIONS, INC . GRAND GRANO GULFGULF NUCLEAR NUCLEAR STATION STATION UNIT UNIT 1 RADIOACTIVE EFFLUENT RADIOACTIVE EFFLUENT AND AND WASTE WASTE DISPOSAL. D POSAL ANNUAL ANNUAL REPORTREPORT RADIOACTIVE LIQUID RADIOACTIVE LIQUID WASTE WASTE SAMPLING SAMPLING AND ANALYSIS PROGRAM AND ANALYSIS PROGRAM JANUARY JANUARY --DECEMBER DECEMBER 2008 2008 Lower Limit Sampling Minimum Analysis Type of Activity of Detection Liquid Release Type Frequency Frequency Analysis (lLD) ( uClJml)(e) A. Batch Waste Release Prior to Release Prior to Release Principal Gamma Tanks (e) Each Batch Each Batch Emitters (d) 5)(10-1 1*131 1X1()-8 Prior to 31 Days Dissolved and 1x10-5 Release One Entrained Gases Batch 1M (Gamma Emitters) Prior to 31 Days H-S 1x10-5 Release Each Composite (b) Gross Alpha 1x10-1 Batch Prtorto 92 Days Sr-age Sr-90 Release Each Composite (b) Fe-55 Batch B. SSW Basin (lkfore8kMdownt Prior to Prior to Release Principal Gamma Release Each Each Batch Emitters (d) 5x10-7 Slowdown '-131 1)(10" NOTE: Footnotes indicated are listed in GGNS ODCM. Appendix A, Table 6.11.1-1.

TABLE 3 TABLES ENTERGY OPE ENTERGY OPERATIONS, INC, IONS, INC. GRAND GULF GRAND GULF NUCL NUCLEAR S STATION UNIT 1 TION UNIT RADIOACTIVE EFFLUENT RADIOACTIVE EFFLUENT AND 0 WASTE DISPOSAL ANNUAL REPORT SPOSAL ANNUAL REPORT SOLID RADIOACTIVE SOLID RADIOACTIVE WASTE WASTE AND IRRADIATED FUEL AND IRRADIATED FUEL SHIPMENTS SHIPMENTS JANUARY JANUARY -- DECEMBER DECEMBER 20082008 A. SOILD WASTE SOILD SHIPPED OFFSITE WASTE SHIPPED OFFSITE FORFOR BURIAL BURIAL OROR DISPOSAL DISPOSAL ~ NOT IRRADIATED FUEL)

1. Type of Wasta . Unit Class A Class B . Class C Est TO:I Erro~

a. Spent

a. resins, filter Spent resins, filter sludges, sludge m3 7.65E+01 O.OOE+OO O.OOE+OO evaporator bottoms, evaporator bottoms, etcetc.. Ci 6.39E+02 O.OOE+OO O.OOE+OO b.

b. DryDry compressible compressible waste,waste, m3 7.44E+02 O.OOE+OO O.OOE+OO contaminated equipment, contaminated equipment, etc.et Ci 2.47E+01 O.OOE+OO O.OOE+OO

c. Irradiated componants,

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

etc. Ci O.OOE+OO O.OOE+OO O.OOE+OO m3 O.OOE+OO O.OOE+OO O.OOE+OO

d. Other: 011 drum sealand, mixed waste Ci O.OOE+OO O.OOE+OO O.OOE+OO stimate of Major

2. Estimate jor Nuclide Nuclide Composition Compositio ( by type of waste) ent resins,

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

None None omp ssible waste, contaminated

b. Dry compressible minated equip equipment, etc.

No n None dia

c. Irradiated omp components, control rods, etc.

None

d. Oth Other: oil drum drum sealand, sealand, mixed mixed waste waste for volume reductio for volume reduction.

Isotope (greater than 0.010/0) Percent Curies Co-58 4.13E-01 2.74E+00 Co-60 1.86E+00 1.24E+01 Cr-51 2.79&+00 1.85E+01 Fe-55 8.69E+01 5.76E+02 Fe-59 1.01E+00 6.75E+OO Mn-54 5.63E+00 3.74E+01 Ni-63 3.60E-01 2.39E+00 Zn-65 5.18E*01 3.44E+00 C-14 3.30E..01 2.19E+OO en v-teclARFRROf -23 tlnll-ItlcIARERR01 - 23

TABLE 33 TABLE ENTERGY OPERATIONS, ENTERGY OPERATIONS, INC.INC . GRAND GULF GRAND GULF NUCLEAR NUCLEAR STATION STATION UNIT UNIT 1 RADIOACTIVE EFFLUENT RADIOACTIVE UENT ANDAND WASTE DISPOSAL ANNUAL ASTE OISPOS REPORT NNUAL REPORT SOLID RADIOACTIVE SOLID RADIOACTIVE WASTE WASTE AND AND IRRADIATED IRRADIATED FUEL FUEL SHIPMENTS SHIPMENTS JANUARY-- DECEMBER JANUARY DECEMBER 2008 (Coat} 2008 (Cont)

3. Solid

3. Waste Dispostion Solid Waste Dispostion Mode of Destinations Name City tate Trans ortatlo Southern 1 Durat8k, LLC Oak Ridge TN Pines 10 Duratek, LlC Oak Ridge TN Hlttman 4 GTS Duratek-Gallaher Road Facility Oak Ridge TN Hittman Studsvlk 1 StudsviklRACE LLC Memphis TN Loistlcs 7 Studsvik Erwin TN Hittman NRC Disposal Number of Description Waste Type Description Class Volume(ftA 3) Containers A 96 B-25 BOX 14 DAW-U*NA B25 BOX A 202 RWE ES-210 13 BR*D-NASRT A 1.280 20' SEALAND 23 DAW-U*NA 20FT SL A 1290 shielded sealand 1 Shielded sealand ES-2 ES-21 0 A 199.4 199.4 2 PR*D-NA CPS/RWCU*B Jsoficlifica -

(solidification) A 132.4 EL*142 1 DAW-U-NA A 202 ES-210 (open top) 1 DAW-U-NA B. Irradiated Fuel Shipments (Disposition) NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None WA N/A e-tocIARERROY ent1-tflClARERR01 -* 24

TTACHMENT II ATTACHMENT Groundwater Protection NEI Groundwater Protection Initiative 11nitlative Sample Sample Results Resin NEI GPI NEI GPI Ground Ground Water Water samples samples areare collected collected from from four four onsite onsite monitoring monitoring wells. Samples wells. Samples were were analyzed analyzed forfor gamma gamma emitting emitting nuclides nuclides and and tritium tritium per per the Radiological the Radiological Environmental Environmental Monitoring Monitoring Program Program requirements requirements forfor ground groun ter. Results water. Results are are shown shown in in the the table table that that fonows. follows . Well 10 1st Otr 1st atr 2nd Qtr 2nd Otrtr tiurn Tritium Gamma Gamma Tritium Tritium Gamma 02 0 MW-1020B <MDA <MDA MDA

                                                                        <MDA         <MDA W-1026B MW-1026B          <MDA
                                          <MDA       <MDA
                                                     <MDA                <M
                                                                        <MDA         <MDA 1W-1 MW-1027B           <MDA       <MDA                <MDA        <MDA MW-11348           <MDA
                                           <MDA       <MDA
                                                      <MDA               <MDA
                                                                          <MDA        <M
                                                                                      <MDA Well 10           3rd Qtr       3rd  Otr          4th Otr           tr 4th Qtr Tritium Tritium     Gamma Gamma              Trit Tritium     Gamma MW-1020B         <MDA
                                          <MOA       <MDA
                                                     <MDA               <MD
                                                                        <MDA         <MDA MW-10268         <MDA <MDA                      <MDA        <MDA Mw-MW-10278          <MDA <MDA                     <MDA
                                                                          <MDA        <MDA
                                                                                      <MDA MW-11348          <MDA <MDA                     <MDA
                                                                          <MDA        <M
                                                                                      <MDA o-teclARERROI tlnv-tfICIARERR01-

25}}

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