ML20206D637

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Annual Radioactive Effluent Release Rept Jan-Dec 1998. with
ML20206D637
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 12/31/1998
From: Hughey W
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-99-00035, GNRO-99-35, NUDOCS 9905040175
Download: ML20206D637 (31)
v • d • e


Text

6 O EntI rations, Inc.

l Port Gibson, MS 39150 1

Tel 601437-6470 l.

W. K. Hughey rI a Safety & Regdatuy Anars April 28, 1999 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 1998 Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR)

GNRO-99/00035 Gentlemen:

Attached is the Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR). This report covers the period from January 1,1998 through December 31,1998.

This report is submitted in accordance with the requirements of 10CFR50.36a'a)(2) and the GGNS Technical Specification (TS) 5.6.3. This report also complies with the GGNS Offsite Dose Calculation Manual (ODCM).

If you have questions or require additionalinformation concerning this report, please contact Gary C. Coker at (601) 437-2442, or this office.

Yours trul l

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'g % j attachment: 1998 Annual Radioactive Effluent Release Report

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1 9905040175 981231 PDR ADOCK 05000416 R PDRj l

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t GNRO-99/00035 Page 2 of 2 l cc: Ms. J. L. Dixon-Hernty, GGNS Senior Resident (w/a)

Mr. L J. Smith (Wise Carter) (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. E. W. Merschoff (w/a)

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite'400 Arlington, TX 76011 Mr. S. P. Sekerak, NRR/DLPM/PD IV 1 (w/2)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 13D18 11555 Rockville Pike Rockville, MD 20852-2378 l

p '

l GNRO 99/00035 bec: Mr. G. C. Coker (w/a)

Mr. M. J. Larson (w/a)-

File (LCTS/RPTS)(w/a)

File (Hard Copy) (w/a File (Central)(w/a)(3 )

ccmail:

Mr. C. A. Bottemiller (w/o)

Mr. R. N. Buckley (w/o)

Mr. R. W. Byrd (w/o)

Mr. L. F. Daughtery Mr. G. G. Davie (W3 - LIC) (w/o)

Mr. W. A.'Eaton (w/o)

Mr. D. L. Janecek (w/o)

Mr. M. R. Kansler (ECH) (w/o)  :

Mr. J. M. Lassetter (w/o) l Mr. J. C. Roberts (w/o)

Mr. J. E. Venable (w/o)

Mr. J. W. Yelverton (Ech) (w/o) I l

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e ESTERGY OPERATIONS,ISC.

GRASDGLLFHCLEARSTATION AXSUAL RADIOACTIVE EFFLGSTRELEASE REPORT January 1,1998-December 31,1998 hlWPnparedBy

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ReviewedBy J l IM hvedBy

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TABLE OF CONTENTS SUBJECT PAGE

l. INTRODUCTION 4 ll. DETAILED INFORMATION 5 A. Regulatory Limits 5 1.10CFR 20 Limits 5
a. Fission and Activation Gases 5
b. Radiolodines and Particulates 5
c. Liquid Effluents 5 2.10CFR 50, Appendix 1 Limits 6
a. Fission and Activation Gases 6
b. Radiolodines and Particulates 6
c. Liquid Effluents 6
3. 40CFR 190 Limits 7 B. Effluent Concentrations 7
1. Airborne 7
2. Liquid 7 1 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8
1. For Fission and Activation Gases 8
2. For Particulates and Radiolodines 9
3. For Continuous Releases 9
4. For Batch Releases: Gases 10
5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10
1. Liquid 10 j
2. Gaseous 10 F. Unplanned Releases 11
1. Liqu!d 11 .
2. Gaseous 11 i

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TABLE OF CONTENTS (CONT'D) t 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 Effiuent 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 MANUAURADIOACTIVE 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 1B Gaseous Effluents - Elevated Releases 18 1C Gaseous Effluents - Ground-Level Releases 19 1D Radioactive Gaseous Waste Sampling and Analysis Program 21 2A Liquid Effluents-Summation of All Releases 22 2B Liquid Effluents - Continuous and Batch Modes 24 -

2C Radioactive Liquid Waste Sampling and Analysis Program 26 l

3 Solid Radioactive Waste and Irradiated Fuel Shipments 27 l

env tec/ARERR90 3

1. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31,1998 is submitted in accordance with Offsite Dose Calculation Manual (ODCM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS) License No. NPF-29.

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

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

The summation of all gaseous releases during the reporting period is given in Table 1 A, while elevated releases and ground-level releases are given in Tables 18 and 10, respectively. Table 1D describes the radioactive gaseous sampling and analysis program ,

implemented at GGNS. )

1 I

The summation of allliquid releases during the reporting period is given in Table 2A, while j 4

continuous and batch mode releases are given in Table 28. Table 2C describes the I radioactive liquid waste sampling and analysis program implemented at GGNS.

Solid radioactive waste and irradiated fuel shipments during the reporting period are I l

summarized in Table 3. l l

J The annual summary of meteorological data (joint frequency distribution) will be i

maintained on site in a file that shall be provided to the NRC upon request. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3.

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11. DETAILED INFORMATION A. Regulatory Limits -

1, 10CFR 20 Limits

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

D. = average total body dose rate in the current year (mremlyr)

= FQ E K, Q[ s 500 mremlyr D. = average skin dose rate in the current year (mremlyr)

= X/Q L (L, + 1.1 M,) Q, s 3000 mremlyr where the terms are defined in the GGNS ODCM.

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

D. = average organ dose rate in current year (mremlyr)

= E W P,Q'i51500 mrem /yr where the terms are defined in the GGNS ODCM.

c. Liould Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any

, time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the d

site, shall be limited to 2 x 10 microcuries/mi total activity.

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11. DETAILED INFORMATION (CONT'D)
2. 10CFR50, Appendix 1 Limits
a. Fission and Activat!on Gases - The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that:

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

= 3.17 x 10 4 I, M, X/Q' Q, s 5 mrad /qtr s 10 mradlyr Og= air dose due to beta emissions from noble gases i

= 3.17 x 104 I, N[Q' Q, s 10 mrad /qtr s 20 mradlyr where the terms are defined in the GGNS ODCM, j

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

]

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

= 3.17 x 104 I, R W' Q, s 7.5 mrem /qtr Any Organ s 15 mremlyr Any Organ l where the terms are defined in the GGNS ODCM.

l l c. Liquid Effluents The dose from radioactive materials in 1; quid effluents shall be such that:

m Dr. m I (An., I At, C, F,] s 1.5 mrem /qtr Total Body i i=1 l

s 5 mrem /qtr Any Organ s 3 mremlyr Total Body

$ 10 mremlyr Any Organ where the terms are defined in the GGNS ODCM.

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

525 mremlyr, Total Body or any Organ except Thyroid s75 mremlyr, Thyroid s10 mrad y/qtr or s20 mrad ylyr, Fission and Activation Gases s20 mrad p/qtr or $40 mrad plyr, Fission and Activation Gases

<15 mrem /qtr or s30 mremlyr, any Organ, lodine and Particulates s3 mrem /qtr or s6 mremlyr, Total Body, Liquid Effluents s10 mremiqtr or 520 mremlyr, any Organ, Liquid Effluents B. Effluent Concentrations

1. Airborne The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section ll.A.1.a. In this case, the ECLs are actually determined by the dose factors in Table 2.1 1 of the GGNS ODCM.
2. Liquid The Effluent Concentration Limit (ECL) of radioactive materials in liquid effluents is limited by ten times the values in 10CFR20, Appendix B, Table 2, Column 2. The ECL chosen is the most conservative value of either the soluble or insoluble ECL for each radioisotope.

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

env-tec/ARERR90 1

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II. DEIA_lLED INFORMATlON (CONT'D)

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

1. Fission and Activation Gases 3. Particulates
2. Radiolodines 4. Liquid Effluents l

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

Values in the attached tables given as zero do not necessarily imply that the l radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables 'ID and 20. 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:

gmuumuuunummuuuuumummuuuma g Kr 87 Xe-133 Xe-135

" Kr 88 X. e-.133m 6 ..

,X,,e,-1,3,8, Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high resolution germanium detectors. (See Table 1D for sampling and analytical requirements.) Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section li.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:

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

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

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11. DETAlLED INFORhlATION fCONT'D_)

These calibration factors, along with the hourly effluent monitor values and flow rates, are entered into the laboratory computer where the release rates for ,

Individual radionuclides are calculated and stored. If no activity is detected in the '

grab ssmple, the calibration factor defaults to a historical mixture of Kr-88, Xe-133, Xe-135m, Xe-135, and Xe-138,

2. For Particulates and Radiolodines l

The radiolodines and radioactive materials in particulate form to be considered are:

l Zn 65 l-133 Mn-54 Cs-134 Fe-59 Cs-137 l Co-58 Ce-141 l Co-60 Ce-144 Sr-89 l-131 Sr 90 Other radionuclides with half I lives greater than.8 days.

3. For Continuous Releases l l

Continuous sampling is performed on the continuous release points (i.e., '

Offgas/Radwaste Building Vent, Containment Purge, Fuel Handling Area i Vent, Turbine Building Vent). Particulate material is collected by filtration.

Radiolodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and Strontium-89 and -90 as required. Gross alpha determinations are made using 2-pi gas flow proportional counter. ]

Strontium-89 and -90 values are obtained by chemical separation ai,d subsequent analysis using liquid scintillation techniques. Tritium concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the reaulrements of footnote "c" of Table 1D, " Radioactive Gaseous Waste Sampling and Analysis,"(GGNS ODCM Appendix A, Table 6.11.4-  ;

1. Currently, Strontium analysis is performed by a qualified contract laboratory. j Appendix A of Regulatory Guide 1.21 states "In estimating releases for periods when analyses were not performed, the average of the two adjacent data points spanning this period should be used."

in addition to releases from routine gaseous release points, one additional planned release resulted from the operation of a temporary laundry facility during 1 Refueling Outage 9 (April- May 1998). The release was evaluated as a ground level release and documented. j i

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11. DETAILED INFORMATION (CONT'D)
4. For Batch Releases: Gases The processing of batch type releases (from Containment Purge)is analogous to that for continuous releases.
5. For Batch Releases: Llquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:

H-3 l Sr-90 l Mn-54 l Mo-99 E Fe 55 l 1131 l Co-58 l Cs-134 l Co-60 l Cs-137 l Fe-59 l Ce-141 l Representative pre release grab samples are obtained and analyzed as required by Table 20. 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 i accordance with the requirements of Table 20. Strontium 89,90 and Iron-55 l 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 1998 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL
a. Number of releases 29 37 15 11 92 E Time Period ( a minuteel Ir E b. Total for all batches I 8223 9944 4611 3657 E c. Max time for a batch I 390 640 320 315 B d. Avg time for a batch l 284 269 307 278 l e. Min time for a batch l 4 7 282 2
2. Gaseous No batch releases were made during the report period, enaecanunnu.so
11. DETAILED INFORMATION (CONT'D)

F. Unplanned Releases

1. Liquid On September 17,1998 a leaking relief valve was discovered in the Turbine Building Cooling Water (TBCW) System. This relief valve discharges to the storm drain system. The leak was sampled and analyzed for radioactivity. The leak rate was measured at approximately 220 ml/ min. Duration estimate was based on routine surveillance of system volume losses. The TBCW system contains tritium at a concentration of approximately 6.5E-05 Ci/mi. This storm drain pathway discharges to Hamilton Lake. Hamilton Lake communicates with the Mississippi River. The leak was evaluated and documented as a liquid radwaste release. The l release did not have a significant effect on the site release totals.
2. Gaseous On February 3,1998 the Turbine Building exhaust gaseous release point was unmonitored for approximately six hours due to lack of a representative sample.

Moisture on a sample filter for the period resulted from ventilation system maintenance. Continuous samples collected before and after the six-hour period were satisfactory. Other indicators of the release rate including process radiation monitor readings and samples collected before and after the period were used to estimate the release rate. The evaluation of the unmonitored release period was documented. The release did not have a significant effect on the site release totals.

G. Estimate of Total Error

1. Liquid The maximum errors are collectively estimated to be Fission &

Activation Tritium 0;csolved & Entrained Gross Products Gases Alpha Sampling 26% 26% ~

26% 26%

l Measurement l 68% 65% 61 % 92% '

l TOTAL l 73% 70% 66% 95%

Sampilng errors include uncertainty associated with mixing, representative I sampling and discharge volume Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples Counting errors are based on measurements of blank samples and, for germanium detectors, the least-readily-detectable radioisotope.

Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.

Total error is calculated by taking the square root of the sum of the squares of the individual errors, enwtee/ARERR96 11

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11. DETAILED INFORMATION (CONT'D)
2. Gaseous The maximum errors (not including sample line loss) are collectively estimated to be n Gross Products lodine Particulate Alpha Tritium l Sampling 32% 23% 22% 22% 23%  !

l Measurement l 81 % 67% 65% 101 % 62%

l TOTAL l 69% 71 % 69% 103% 66Y 1

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 oflow-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.

1. Meteorological Data The annual summary (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 A thirty-day Limiting Condition for Operation (LCO) for the Liquid Radwaste Dilution Flow Rate Measurement instrument was exceeded on May 12,1998. The inoperability resulted from a system drainage of the primary dilution source, Circulating Water (CW) blowdown. CW system drainage is a routine outage activity of varying duration. In this case, the required restrictions were put into place to suspend further liquid radwaste discharges when the thirty day LCO expired. The dilution flow rate measurement instrument was returned to service when the CW System was refilled. During this time, the alternate measurement device for dilution flow rate, Discharge Canal flow rate, was Inoperable.

K. Annual Sewage Disposal Summary There was no sewage disposalin 1998.

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lli. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 1998.

Inspection of the values indicate that GGNS releases were within the 10CFR50, Appendix 1 design objectives.

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

All parameters listed were calculated in accordance with the GGNS ODCM. l A. Water-Related Exposure Pathways l The values calculated in this section utilize the information provided in Tables 2A and 2B of this report and the calculationas methodology of the ODCM.

, Liould Effl9eh Total body dooa 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.

1998 Liquid Effluent Dose (mrem) h 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Whole Body 7.13E-3 6.60E-3 3.97E-3 2.68E-3 2.04E-2 Enne 3.25E-3 6.34E-3 3.46E-3 1.88E-3 1.49E-2 gr 9.02E-3 1.16E-2 5.78E-3 3.59E-3 3.00E 2 Thyroid 5.85E-3 3.76E-3 1.36E-3 1.30E-3 1.23E-2 Kidney 6.03E-3 5.27E-3 2.49E-3 1.83E-3 1.56E-2 Lung 711E-3 6.03E-3 2.22E-3 1.73 E-3 1.71 E-2 Gl.LLI 1.46E-2 1.89E-2 4.90E-3 2.15E-3 4.06E 2 l B. Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1 A and 10 of this 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 boundary, locr.tlons within the site boundary were considered when selecting locations for dose calculations.

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

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

ParticulateJ@diolodine and Tritium Organ dose rate from esposure to radiolodines, tritium and particulates are computed for an individual located at the site boundary, env4ea/ARERR98 13

!ll. RADIATION DOSE

SUMMARY

LQONT'D)

Organ dose from exposure to radiolodines, tritium and particulates are computed for an individual located la the southwest sector at a distance of 0.89 miles. This location corresponds to a residence beyond the site boundary. Pathways considered for use in the organ dose calculations are inhalation, ground plane, grass / cow / meat and vegetation. There is no grass /cowImilk pathway within five miles of GGNS.

Dose factors for the age group receiving the maximum dose are used in the calculation of organ dose and dose rate.

Noble Gases Gamma and beta air dose and Individual total body and skin dose rates from exposure to a semi-infinite cloud of noble gas are computed for a location in the southwest sector at a distar.ce of 0.85 miles. This location corresponds to the highest annual average atmospheric dispersion for a location at the site boundary.

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

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 1998 as net exposure (field reading - (transit + shield)] normalized to 92 days.

l

' 1998 Airborne EfRuont Dose (nnm)~ <

l l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l TOTAL l l lodine, Tritium & Particulates 1.03E-1 5.19E-2 4.91 E-2 5.71 E-2 2.61 E-1 Fission and Activation Gases l

Total Dody Dose Imremlyr) 5.41 E-2 3.29E-2 2.20E 2 2.30E-2 l Skin Dose (mremlyr) 1.11 E-1 6.72E-2 4.20E-2 4.40E-2 Gamma 7.13E-3 4.19E-3 5.43E-3 4.P3E-3 2.16E 2 Air Dose

  • Seta 7.97E-3 l 4.68E-3 5.87E-3 5.23E-3 2.37E 2 Air Dose
  • l Direct Radiation l 0 l 0 l 0 l 3.00E-01 3.00E-01 l
  • Measurement units are mrad i

('

env tec/ARERR00. H

I IV. OFFFSITE DOSE CALCULATION MAftVA_L!

RADIOACTIVE WASTE TREATMENT tiYSTEM CHANGES A. Offsite Dose Calculation Manuet (ODCM)

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

B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems in 1998.

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. i TABLE 1A 1 ENTERGY OPERATIONS, INC. l GRAND GULF NUCLEAR STATION UNIT 1 l

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY-JUNE 1998 (

I I

l Unit l Quarter l Quarter lEst Totall l

i l Grand Gulf Nuclear Station UNIT 1l l 1 l 2 l Error % l <

................................................................................ j A. Fission & Activation Gases 1 i

I

................................................................................ 1 4

l 1. Total release l Ci l 1.58E+01l 7.92E+00l 6.90E+01l j

............................................... ................ ............... j l 2. Average release rate for period l uCi/secl 2.02E+00l 1.01E+00l t

...................................................................... l l 3. % of Technical specification limit l  % l 1.43E-01l 8.37E-02l  !

...................................................................... t B. Iodines '

j 1. Total iodine-131 l Ci l 1.20E-05l 6.22E-05l 7.10E+01l {

l l 2. Average release rate for period l uCi/secl 1.53E-06l 7.91E-06l l l

l 3. % of Technical specification limit l  % l 2.97E-03l 1.31E-02l l

...................................................................... l 1

i C. Particulates 1 i

l 1. Particulates with half-lives >8 daysl Ci l 1.31E-061 2.79E-05l 6.90E+011  !

l 2. Average release rate for period l uCi/secl 1.67E-071 3.55E-06l )

l 3. % of Technical specification limit l  % l 1.36E-04l 1.85E-03l I l

l 4. Gross alpha radioactivity l Ci l 0.00E+00l 0.00F+00l 4 i

D. Tritium  ;

r l l l 1. Total release l Ci l 7.25E+01l 3.60E+01l 6.60E+01l l l

l uCi/secl 9.22E+00l 4.58E+00l l 2. Average release rate for period  ;

...................................................................... a l 3. % of Technical specification limit l  % l 1.36E+001 6.78E-01l l 1

[

E. Tritium,radiciodines and particulates l 1. % of Technical specification limit l  % l 1.37E+00l 6.93E-01l l l

i 1

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TABLE 1 A 1

ENTERGY OPERATIONS, INC. I l

GRAND GULF NUCLEAR STATION UNIT i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JULY-DECEMBER 1998 l l Unit l Quarter l Quarter lEst Totall l Grand Gulf Nuclear Station UNIT 1l l 3 l 4 l Error % l A. Fission & Activation Gases I

........................................................................ ,...... i l

l 1. Total rele7se l Ci l 1.19E+01l 1.06E+01l 6 90E+01l l 2. Average release rate for period l uti/secl 1.51E+00l 1.35E+00]

l l 3. % of Technical specification limit l  % l 1.09E-01l 9.67E-02l B. Iodines l 1. Total iodine-131 l Ci l 1.55E-07] 0.00E+00l 7.20E+01l l 2. Average release rate for period l uCi/sec) 1.97E-08l 0.00E+00l l 3. % of Technical specification limit l  % l 3.20E-05l 0.00E+00l l

...................................................................... l 1

C. Particulates l l

} 1. Particulates with half-lives >8 days l Ci l 0.00E+00l 0.00E+00l 6.90E+01l )

l 2. Average release rate for period l uCi/secl 0.00E+00l 0.00E+00l l 3. % of Technical specification limit l  % l 0.00E+00[ 0.00E+00l l 4. Gross alpha radioactivity l Ci l 0.00E+00l 0.00E+00l D. Tritium l i

l 1. Total release l Ci l 3.48E+01l 4.04E+01l 6.60E+01l I

\

[ 2. Average release rate for period l uC1/secl 4.42E+00] 5.14E+00l l l

............................................................ ~........

l 3. % of Technical specification limit l  % l 6.54E-01) 7.61E-01l E. Tritium,rac'iotodines and particulates

. [ 1. % of Technical specification limit l  % l 6.55E 01l 7.61E-01) )

env teo/ARERR98. f 7

(

l TABLE 1B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY- DECEMBER 1998 l

(Not Applicable -GGNS Releases Are Considered Ground-Level) i I

l l

l l

l i

{

N 4

i TABLE 1C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS- GROUND-LEVEL RELEASE JANUARY-JUNE 1998 CONTINUOUS MODE BRTCH MODE l Nuclides Released l Unit l Quarter l Quarter l Quarter l Quarter l l l l 1 l 2 l 1 l 2 l

............... ................................................................ 1

1. Fission gases I l

l XE-133 l C1 l 7.44E+00] 3.48E+00l 0.00E+00l 0.00E+00l l KR-88 l Ci l 2.61E-011 1.58E-01l 0.00E+00l 0.00E+00l l XE-135 l Ci l 7.19E+00l 3.34E+00l 0.00E+00l 6.00E+00l l XE-138 l Ci l 2.33E-011 2.22E-01l 0.00E+00l 0.00E+001 l XE-135M l Ci l 6.52E-011 4.02E-01l 0.00E+00l 0.00E+00l l KR-87 l Ci l 2.49E-02l 2.13E-02l 0.00E+00l 0.00E+00l l RR-41 l Ci l 3.95E-02l 1.07E-01l 0.00E+00l 0.00E+00l l KR-85M l Ci l 0.00E+00l 1.44E-03l 0.00E+00l 0.00E+00l l XE-137 l Ci l 0.00E+00l 1.83E-01l 0.00E+00l 0.00E+00l l l l l I l I l Total for period l Ci l 1.58E+011 7.92E+00l 0.00E+00l 0.00E+00l

2. Iodines l I-131 l Ci l 1.20E-05l 6.22E-05l 0.00E+00l 0.00E+001 l I-132 l Ci l 0.00E+00l 0.00E+00l 0.00E+00i 0.00E+00l l I-133 l Ci l 3.03E-05l 1.04E-05l 0.00E+00! 0.00E+00l l I-134 l Ci l 0.00E+00l 0.00E+00l 0.00E+G:4 0.00E+001 l I-135 l Ci l 0.00E+00l 0.00E+00l 0.00E+001 0.00E+00l l l l 1 l l l l Total for period l Ci l 4.24E-05l 7.26E-05l 0 00E+00l 0.00E+00l
3. Particulates l H-3 l Ci l 7.2SE+01l 3.60E+01l 0.00E+00l 0.00E+00l l Sr-89. I Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l Sr-90 l Ci l 0.00E+001 0.00E+001 0.00E+00l 0.00E+00l l C0-60 i Ci l 1.31E-06l 1.69E-05l 0.00E+00l 0.00E+00l l MN-54 l Ci l 0.00E+00l 6.80E-06] 0.00E+00l 0.00E+00l l CO-58 l C1 l 0.00E+00j 2.58E-07l 0.00E+00l 0.00E+001 l FE-59 l Ci l 0.00E+00l 2.19E-06] 0.00E+00l 0.00E+00l l CR-51 l Ci 1 0.00E+00l 1.78E-06l 0.00E+00l 0.00E+001 l l 1 l l l l l Total for period l Ci l 7.25E+01l 3.60E+01l o. aE+00l 0.00E+00l env.tec/ARERR90 e 10

1 TABLE 1C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPOR._I GASEOUS EFFLUENTS- GROUND-LEVEL RELEASE JULY- DECEMBER 1998 CONTINUOUS MODE BATCH MODE l Nuclides Released l Unit l Quarter l Quarter l Quarter l Quarter l l l l 3 l 4 1 3 l 4 l

1. Fission gases l XE-133 l Ci l 5.57E+00l 4.96E+00l 0.00E+00l 0.00E+00l j l KR 88 l Ci l 2.38E-01l 2.12E-01l 0.00E+00l 0.0M+00l j l XE-135 l Ci l 5.33E+001 4.75E+00l 0.00E+00j 0.00E+00l '

l l XE-138 l Ci l 1.43E-011 1.27E-01l 0.00E+00l 0.00E+00l l XE-135M l Ci l 6.27E-01l 5.60E-011 0.00E+00l 0.00E+00l l l 1 l l l 1 l l Total for period l C1 l 1.19E+01l 1.06E+01l 0.00E+00l 0.00E+00l

2. Iodines

)

l I-131 l Ci l 1.55E-07l 0.00E+00l 0.00E+001 0.00E+00l l l I-132 l Ci j 0.00E+00l 0.00E+00l 0.00E+001 0.00E+00l l I-133 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l I 134 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l I-135 l Ci 1 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l I I I I l l l Total for period l Ci l 1.55E-07l 0.00E+00l 0.00E+001 0.00E+001 I 3. Particulates l l

l H-3 l C1 l 3.48E+01l 4.04E+01l 0.00E+00l 0.00E+00l l Sr-89 l Ci l 0.03E+001 0.00E+00l 0.00E+00l 0.00E+00l l Sr-90 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l l 1 1 I I l l

l Total for period l Ci l 3.48E+01l 4.04E+01] 0.00E+00l 0.00E+001 en+tec/ARERR90 20

~

TABLE 1D l ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program  !

JANUARY- DECEMBER 1998 l

0

, Lower Limit ,

Sampling Minimum Analysis Type of Activity of Detection l Gas,eous Release Type Frequency Frequency Analysis (LLD)  ?

( pCl/ml)" j A. (1) Radwaste Building 31 Days 31 Days Principal Gamma  !

Ventilation Exhaust Grab Sample (f) Emitters (b.e) 1x104 ,

H-3 1X104 l

(2)FuelHandling Area Continuous 7 Days @ l-131 1x1042 Ventilation Exhaust (d)(f) Charcoal Sample 1-133 1x104' (3) Containment Continuous (d) 7 Days @ Principal Gamma 1x104 Ventilation Exhaust (f) Particulate Emitters (e)(1131, Sample Others)

(4) Turbine Building Continuous (d) 31 Days Gross Alpha 1x104 Ventilation Exhaust (f) Composite Particulate Sample

~dontinuous (d) 92 Days Sr-89, Sr-90 1x104 g (f) Composite Particulate Sample Continuous (f) Noble Gas Noble Gases Gross 1x104 Monitor Beta or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma 1x104 Treatment Exhaust, Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10d Treatment A Sample (f) Emitters (e)

Exhaust, whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10d Treatment B Sample (f) Emitters (e)

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

1 en+tec/ARERR90 21

p L .

f TABLE 2A l ENTERGY OPERATIONS, INC.

! GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JANUARY-JUNE 1998 l Unit l Quarter l Quarter lEst Total l l l 1 l 2 l Error % l A. Fission & activation products l 1.- Total release (not including H3, l l l l l l gases, alpha) l Ci l 2.19E-02l 4.55E-02l 7.30E+01l l 2. Average diluted concentration l l l l l during period l uCi/ml l 9.86E-08l 1.19E-07l l 3. Percent of applicable limit l  % l 5.71E-02l 5.41E-02l B. Tritium l 1. Total release l Ci i 8.28E+01l 7.43E+01l 7.00E+011 l 2. Average diluted concentration l l i l

-l during period l uCi/ml l 3.73E-04l 1.95E-04l l 3. Percent of applicable limit l  % l 3.73E+00l 1.95E+00l C. Dissolved and entrained gases l 1. Total release l Ci l 0.00E+00l 0.00E+00l 6.60E+01l  ;

l 2. Average diluted concentration l l l l l l during period l uCi/ml l 0.00E+00l 0.00E+00l ]

l 3. Percent of applicable limit l  % l 0.00E+00l 0.00;+00l

0. Gross alpha radioactivity l 1. Total release l Ci l 0.00E+00l 0.00E+00l 9.50E+01l lE. Volume of waste (prior to dilution)l liters l 2.84E+06l 3.21E+06l 5.00E+00l lF.. Volume of dilution water used l liters j 2.19E+08l 3.78E+63l 5.00E+00l I

I ens tec/ARERR90 22

r .

1

. i 1

TABLE 2A 1 ENTERGY OPERATIONS, INC. l GRAND GULF NUCLEAR STATION UNIT 1 l RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES JULY- DECEMBER 1998 j i

l Unit l Quarter l Quarter lEst Totall j l l 3 l 4 l Error % l j A. Fission & activation products l 1. Total release (not including H3, 1 l l l l l gases, alpha) l Ci } 1.05E-02l 5.08E-03l 7.30E+0!l l 2. Average diluted concentration l l l l l during period l uCi/ml l 6.59E-08l 5.24E-08l l 3. Percent of applicable limit l  % l 4.30E-02] 1.80E-02l B. Tritium l 1. Total release l Ci l 2.48E+01l 1.99E+01l 7.00E+01l l 2. Average diluted concentration l l l l l during period l uCi/ml l 1.56E-04l 2.06E-04l l 3. Percent of applicable limit l  % l 1.56E+001 2.06E+00l C. Dissolved and entrained gases l 1. Total release l Ci [ 0.00E+00l 2.22E-06) 6.60E+01l l 2. Average diluted concentration l l l l l during period l uC1/ml l 0.00E+00l 2.29E-11l l 3. Percent of applicable limit l  % l 0.00E+00l 3.27E-04l D. Gross alpha radioactivity l 1. Total release l Ci l 0.00E+00l 0.00E+00l 9.50E+01l lE. Volume of waste (prior to dilution)l liters l 1.56E+06l 1.05E+0615.00E+001 lF. Volume of dilution water used l liters l 1.58E+08l 9.58E+071 5.00E+00l en+tecl4, TERR 90

  • 23

1 TABLE 2B I ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 l 3

i RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT  :

LIQUID EFFLUENTS-CONTINUOUS AND BATCH MODES JANUARY-JUNE 1998 CONTINUOUS MODE BATCH MODE j l Nuclides Rt: leased l Unit l Quarter ! Quarter l Quarter l Quarter l ,

l l l 1 l 2 l 1 l 2 l l l strontium-89 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l  ;

l strontium-90 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l cesium-134 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00]

l cesium 137 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 2.59E-06l l l iodine-131 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+001  !

i cobalt-58 l l l Ci l 0.00E+00l 0.00E+00l 4.13E-05l 2.26E-04l <

l cobalt-60 l Ci l 0.00E+00l 0.00E+00l 3.43E-03l 4.82E-03l l iron-59 l Ci l 0.00E+00l 0.00E+00l 5.59E-05l 5.20E-04l l zinc-65 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 7.51E-05l l manganese-54 l Ci l 0.00E+00l 0.00E+00l 4.33E-04l 1.68E-03]

l chromium-51 l Ci l 0.00E+00l 0.00E+00l 1.59E-03l 6.14E-04l l l zirconium-niobium-95 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l- molybdenum-99 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l technetium-99m l Cl l 0.00E+001 0.00E+00l 0.00E+00l 0.00E+00l l barium lanthanum 140 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00]

l cerium-141 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l i

l Sb-125 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 4.89E 06l l Cu-64 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 2.91E-05l l Ag-110m l Ci l 0.00E+001 0.00E+00l 5.61E-06l 1.59E-05l l Fe-55 l Ci l 0.00E+00l 0.00E+00l 1.63E-02l 3.75E-02l l Total for period (above) l Ci l 0.00E+00l 0.00E+00l 2.19E-02l 4.55E-02l l xenon-133 l Ci l 0.00E+00l 0.00E+001 0.00E+00l 0.00E+00l l xenon-135 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l Xe-133m l Ci l 0.00E+00l 0.00E+00l 0.00E+001 0.00E+00l 1 i

I

)

I

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-CONTINUOUS AND BATCH MODES JULY- DECEMBER 1998 i

CONTINUOUS MODE BATCH MODE

[ Nuclides Released l Unit l Quarter ] Quarter ! Quarter l Quarter !

I 1 l 3 l 4 1 3 1 4 I l strontium 89 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00!

l strontium 90 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l cesium-134 l Ci l 0.00E+00l 0.00E+00) 2.99E-06l 3,30E-06l l cesium 137 l Ci l 0.00E+0Gl 0.00E+00l 2.24E-051 8.03E-06l l iodine-131 l C1 l 0.00E+00l 0.00E+00l 0.00E+00l 2.81E-06l l cobalt-58 l Ci l 0.00E+00l~0.00E+00l 6.51E-06l 0.00E+00l l cobalt-60 l Ci l 0.00E+00l 0.00E+00l 1.76E-03l 3.85E-04l l iron-59 i Ci l 0.00E+00] 0.00E+00l 1.32E-05l 0.00E+001 l zinc-65 l Ci I 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+001 l manganese 54 l Ci l 0.00E+00l 0.00E+00l 2.75E-04l 2.01E-05l l chromium-51 l Ci l 0.00E+00l 0.00E+00l 2.24E-04l 5.83E-05l l zirconium-niobium-95 l Ci 1 0.00E+001 0.00E+00l 0.00E+001 0.00E+00l l molybdenum-99 l Ci l 0.00E+00l 0.00E+00l 0.00E*00l 0.00E+00l ,

l technetium-99m l Ci l 0.00E+00l 0.C0E+00l 0.00E+00l 0.00E+00l l barium lanthanum-140 l Ci l 0.00E+00] 0.00E+00l 0.00E+00l 0.00E+001 l cerium-141 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l l

l Cu 64 l Ci l 0.00E+00l 0 00E+00l 0.00E+00l 1.01E-05l l l I-133 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 3.90E-06l l l Na-24 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 3.29E-05l

j Fe-55 l Ci l 0.00E+00l 0.00E+00l 8.21E-03l 4.55E-03l l

l Total for period (above) l Ci l 0.00E+00l 0.00E+00l 1.05E-02l 5.08E-03l l

l xenon-133 l Ci 1 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+001 l xenon-135 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 2.22E-06l l Xe-133m l Ci l 0.00F+00l 0.00E+00l 0.00E+00l 0.00E+00l l

enMec/ARERR90 25 i___________ .

i TABLE 2C ENTERGY OPERATIONS, INC.

I GRAND GULF NUCLEAR STATION UNIT 1 l

l l

RADICACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM l JANUARY- DECEMBER 1998 Lower Limit Sampling Minimum Analysis Type of Activity of Detection Liquid Release Type Frequency Frequency Analysis (LLD)

( pcumi)(a)*

l A. Batch Waste Release Prior to Release Prior to Release Principal Gamma Tanks @ Each Batch Each Batch Emitters (d) 5x10-7 1131 1X104 l

Prior to 31 Days Dissolved and 1 x10-5 Release One Entrained Gases l

Batch /M (Gamma Emitters)

Prior to 31 Days 11 4 in194 Release Each Composite (b) Gross Alpha 1x10 7

, Batch l Prior to 92 Days Sr-89. Sr-90 5x10 4 Release Each Composite (b) Fe 55 1x104 Batch B. SSW Basin w > Prior to Prior to Release Principal Gamma Release Each Each Batch Emitters (d) 5x102 Blowdown 1131 1x104 NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-1.

l r

l 1 l l

l l

env4eo/ARERait00 20 L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . _ . . . . . . . . . . . . . . . .. . . . . . . . . . . .

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS l JANUARY- DECEMBER 1998 l

l ESTIMATE l TYPE OF WASTE UNITS 18' QTR 2" QTR 3" QTR 4 QTR TOTAL ERROR (%)

RESIN MS 7.70 E-01 2.01 E+00 6.34 E-01 1.39 E-01 Cl 1.10 E+01 6.37 E+01 2.80 E+01 2.13E-02 7.2E+01 DAW M5 5.36 E+00 3.67 E+01 1.17 E+01 1.56 E+01 Cl 1.38 E-02 4.65 E-01 6.30 E --01 3.23 E -01 6.9E+01 IRR. COMP. M3 0 1.64 E+00 0 0 Ci 0 1.72 E+04 0 0 6.9E+01 m.._ ., .,..~ _ _

_ ___RADI,O_N U._C,.LI,D._E CO_M P. O,S_IT_IO N _%, , . . ,, . g. .,_, -

RESIN idQTR 2nd QTR 3'd QTR 4* QTR Co-60 31 17 11 58 Zr-95 2 <1 <1 1 Fe-55 56 68 84 28 Mn-54 6 5 4 8 Nb-95 1 <1 <1 <1 Ru-106 <1 8 <1 <1 ALL OTHERS 4 <1 <1 3

,_ , , , , . , __, - .. - _ _R A.D_IO _N.U_C_LI

_ D,. E,_C.O_M P.O_SITI.O_N,%...,.. ..__ .

DAW - GTS 1" QTR 2"' QTR 3'd QTR 4*QTR Co-60 10 10 10 10 Cr-51 6 6 6 6 Fe-55 70 70 70 70 Mn 54 13 14 13 13 All Others 1 1 1 1

._aw__<.~..__.___._~_~~,~..__...~..~._,.,~._.____,...~.

RADIONUCLIDE COMPOSITION %

l IRR. COM P. 1"QTR 2"d QTR 3'd QTR 4* QTR E Co-60 0 46 0 0 l Ni-63 0 2 ~~ 0 0 l Fe-55 0 50 0 0 l Mn-54 0 1 0 0

[ All Others 0 <1 0 0 envtec/ARERR90 21

f TABLES ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS (CONT'D)

JANUARY-DECEMBER 1998 i A. Solid Waste Shipped Off Site for Burial or Disposal

3. Solid Waste Disposition
a. Resins were dewatered in steel liners or High Integrity Containers ILSAO according to the requirements of the GGNS PCP and shipped to Barnwell, South Carolina, for burial. Some resin was shipped to Molten Metal )

Technologies (MMT) of Oak Ridge, Tennessee for volume reduction. l MMT shipped reduced waste to Barnwell, South Carolina. Reduced resin was dewatered and shipped in liners and High integrity Containers (LSA). No solidification agents or absorbents were used,

b. DAW was packaged in 20'sealand containers and shipped to Scientific Ecology Group (SEG) of Oak Ridge, Tennessee and F. W. Hake of Memphis, Tennessee, for volume reduction. SEG and F. W. Hake shipped reduced I water to Barnwell, South Carolina or Envirocare of Utah. Reduced volume was used in providing information given in A.1.b.

l

c. One shipment of control rod blades and fission chambers was made to Barnwell, South Carolina.

1

d. No waste in this category. l NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION _

30 Truck Barnwell, SC r

B. Irradiated Fuel Shipments (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None N/A N/A C. Annual Sewage Sludge Summary No sewage was disposed of during 1998.

AVERAGE Co-60 AVERAGE Mn-54 I NUMBER OF SHIPMENTS TOTAL GALLONS ACTIVITY (pCill) ACTIVITY (pCl/l) l l None '

N/A N/A N/A env tec/ARERR00 20

. . _ _ . _ .

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