ML20217H615

Annual Radioactive Effluent Release Rept,Jan-Dec 1997

ML20217H615
Person / Time
Site:	Grand Gulf
Issue date:	12/31/1997
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20217H604	List: ML20217H601 ML20217H615 ML20217H621
References
NUDOCS 9804300017
Download: ML20217H615 (30)

Text

i ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION ,

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT  ;

January 1,1997 - December 31,1997 I

Prepared By: gM 66 /424 46 i

Reviewed By: 42 7/k / 9-2/- 9r Approved By: L.  % / % n-si  ;

1  ;

lS84A88$l$$88$416 R PDR dwn-argfARERR9&I sA

TABLE OF CONTENTS SUBJECT PAGE

1. INTRODUCTION 4

11. DETAILED INFORMATION 6 A. Regulatory Limits 6 1.10CFR 20 Limits 6

a. Fission and Activation Gases 6

b. Radiciodines and Particulates 6

c. Liquid Effluents 6 2.10CFR 50, Appendix 1 Limits 7

a. Fission and Activation Gases 7

b. Radiciodines and Particulates 7

c. Liquid Effluents 7

, 3. 40CFR 190 Limits 8 B. Effluent Concentrations 8

1. Airborne 8

2. Liquid 8 C. Average Energy 8 D. Measurements and Approximations of Total Activity 9

1. For Fission and Activation Gases 9

2. For Particulates and Radioiodines 10

3. For Continuous Releases 10

4. For Batch Releases: Gases 11

5. For Batch Releases: Liquid Effluents 11 E. Batch Releases 12

1. Liquid 12

2. Gaseous 12 F. Unplanned Releases 12

1. Liquid 12

2. Gaseous 12 Q

chrm-arr/ARERR962

TABLE OF CONTENTS (CONT'D)

SUBJECT PAGE G. Estimate of Total Error 13

1. Liquid 13 I

2. Gaseous 13

3. Solid Radioactive Waste 13 '

H. Solid Radioactive Waste Shipments 14

1. Meteorological Data 14 J. Radioactive Effluent Monitoring Instrumentation Operability 14 K. Annual Sewage Disposal Summary 14 111. RADIATION DOSE

SUMMARY

14 A. Water-Related Exposure Pathway 14 B. Airborne-Related Exposure Pathway 15 IV. OFFSITE DOSE CALCULATION MANUAL / RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 16 A. Offsite Dose Calculation Manual (ODCM) 16 B. Radioactive Waste Treatment Systems 17 LIST OF TABLES TABLE PAGE 1 A Gaseous Effluents - Summation of all Releases 18 1B Gaseous Effluents - Elevated Releases 20 1C Gaseous Effluents - Ground-Level Releases 21 1D Radioactive Gaseous Waste Sampling and Analysis Program 23 2A Liquid Effluents - Summation of All Releases 24 2B Liquid Effluents - Continuous and Batch Modes 26 2C Radioactive Liquid Waste Sampling and Analysis Program 28 3 Solid Radioactive Waste and Irradiated Fuel Shipments 29 LIST OF ATTACHMENTS j Q Attachment 1 - Offsite Dose Calculation Manual, Revision 21 31 e . w m anows

.. . r . .

L INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31,1997 is submitted in accordance with Offsite Dose Calculation Manual (ODCM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS) License No. NPF-29.

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

Airbome 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 1B and 1C, respectively. Table 1D describes the radioactive gaseous sampling and analysis program implemented at GGNS.

The summation of all liquid releases during the reporting period is given in Table 2A, while continuous and batch mode releases are given in Table 2B. Table l

2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS.

Solid radioactive waste and irradiated fuel shipments during the reporting j l

period are summarized in Table 3.

l 1

)

dem*g/ARfAR96-4 L.

I. INTRODUCTION (CONT'D)

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

This report contains a copy of Revision 21 to the GGNS ODCM.

I l

{ chrm-are/ARERR9&S L

1 IL DETAILED INFORMATION A. Regulatory Limits

1. 10CFR 20 Limits

a. Fission and 9vation Gases - The release rate limit at any time for noble gases tu creas at or beyond the site boundary shall be such that:

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

= X/Q I K g gd s g500 mrem /yr D, = average skin dose rate in the current year (mrem /yr)

= X Q I;(L +g 1.1 M )g d si 3000 mrem /yr where the terms are defined in the GGNS ODCM.

b. Radioiodines and Particulates - The release rate limit for the sampling period for all radiciodines, 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 (mrem /yr)

=IW i P idi51500 mrem /yr where the terms are defined in the GGNS ODCM.

l

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

, any time ten times the values specified in 10CFR20, Appendix B, Table

! 2, Column 2. The concentration of dissolved or entrained noble gases, l released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x 10-4 microcuries/ml total activity.

t 1

I l

l chem-der /ARERR9H

)

II. DETAILED INFORMATION (CONT'D)

2. 10CFR50, Appendix I Limits

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

D = air dose due to gamma emissions from noble gases 4

= 3.17 x 10 IgMgX/Q'Q si 5 mrad /qtr s 10 mrad /yr Dp= air dose due to beta emissions from noble gases

= 3.17 x 10-8 I Ng X/Q'Qgs10 mrad /qtr s 20 mrad /yr where the terms are defined in the GGNS ODCM.

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

D = dose to an individual from tritium,1-131,1-133 and P

l radionuclides in particulate form with half-lives greater than 8 days (mrem) l = 3.17 x 10-8 I R; W' iQ s 7.5 mrem /qtr Any Organ l s 15 mrem /yr Any Organ where the terms are defined in the GGNS ODCM.

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

i m  :

DTau"EIAiTau I Atg Cjf Fg] s 1.5 mrem /qtr Total Body i t=1 s 5 mrem /qtr Any Organ s 3 mrem /yr Total Body s 10 mrem /yr Any Organ where the terms are defined in the GGNS ODCM.

chre seq /ARERR967

IL DETAILED INFORMATION (CONT'D)

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

s25 mrem /yr, Total Body or any Organ except Thyroid s75 mrem /yr, Thyroid

$10 mrad y/qtr or s20 mrad y/yr, Fission and Activation Gases s20 mrad p/qtr or 540 mrad p/yr, Fission and Activation Gases

$15 mrem /qtr or s30 mrem /yr, any Organ, Iodine and Particulates s3 mrem /qtr or s6 mrem /yr, Total Body, Liquid Effluents s10 mrem /qtr or s20 mrem /yr, any Organ, Liquid Effluents B. Effluent Concentrations

1. Airbome 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.

l 2. Liquid l 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. j i C. Average Energy l Not applicable for GGNS ODCM Appendix A.

(

dem-arg/ARIRR964 i

i 1

l II. DETAILED INFORMATION (CONT'D)

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

1. Fission and Activation Gases 3. Particulates

2. Radioiodines 4. Liquid Effluents Tables ID and 2C give sampling frequencies and minimum detectable sensitivity requirements for the analysis of gaseous and liquid effluent streams, respectively.

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

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

Kr-87 Xe-133m Kr-88 Xe-135 Xe-133 Xe-138 Periodic grab samples from Station effluent streams are analyzed by a i 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 ll.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:

l

...--m,

I II. DETAILED INFORMATION (CONT'D) l l C; =U+m j where l C; = isotopic calibration factor for isotope i l

l U; = concentration of isotope iin the grab sample in pCi/ml.

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

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

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

! Mr 54 Mo-99 Fe-59 I-131 Co-58 I-133 Co-60 Cs-134 Zn-65 Cs-137 l Sr-89 Ce-141 Sr-90 Ce-144 Other radionuclides with half l lives greater than 8 days.

3. For Continuous Releases l

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

j Offgas/Radwaste Building Vent, Containment Purge, Fuel Handling Area

l. Vent, Turbine Building Vent). Particulate materialis collected by filtration.

l Radiciodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify radioactive materials collected on the filters. Particulate filters are then analyzed for gross alpha and Strontium-89 and -90 as required.

Gross alpha determinations are made using 2 pi gas flow proportional counter. Strontium-89 and -90 values are obtained by chemical separation and subsequent analysis using liquid scintillation techniques. Tritium them+t/ARERR9H0

II. DETAILED INFORMATION (CONT'D) concentrations are determined using distillation and liquid scintillation techniques. During major operational occurrences, the frequency of sampling is increased to satisfy the requirements of footnote "c" of Table 1D, l .- " Radioactive Gaseous Waste Sampling and ' Analysis," (GGNS ODCM l

Appendix A, Table 4.11.2.1.2-1 [6.11.4-1]. Currently, Strontium analysis is performed by a qualified contract laboratory.

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."

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

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

l H-3 Sr-90 Mn-54 Mo-99 Fe-55 I-131 Co-58 Cs-134 Co-60 Cs-137 Fe-59 Ce-141 Zn-65 Ce-144 Sr-89 i

Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed using the computerized pulse height analysis system previously described. Aliquots of each pre released sample, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C. Strontium-89, 90 and Iron-55 values are obtained by chemical separation and counting the i

l 1

dwn arr/ARERR94>11

)

j

II. DETAll.ED INFORMATION (CONT'D) i separated strontium and iron using liquid scintillation techniques. Gross I 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 1 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 1st 2nd 3rd 4th 1997 4 Qtr Qtr Qtr Qtr TOTAL

a. Number of releases 19 24 31 20 94 i Time Period on nunutes)

b. Total for all batches 6115 7330 9227 5501

c. Max time for a batch 395 420 325 489

d. Avg time for a batch 322 305 298 275

e. Min time for a batch 290 180 0 3

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

F. Unplanned Releases

1. Liquid On April 19,1997 an unplanned liquid release occurred outside the Controlled Access Area (CA A) from the Plant Chilled Water system. A portion of the release entered the storm drain system. This portion of the release was treated as a liquid release and was evaluated for impact on Offsite Doses. The release evaluation was documented. The release did not have a significant effect on the site release totals.

l

2. Gaseous On March 13 and 18 and April 19,1997 three unplanned releases occurred outside the CA A from the Plant Chilled Water system. Each release was evaluated as a ground level release via evaporation for impact on Offsite Doses. The releases were evaluated for impact on Offsite doses and l documented. None of the releases had a significant effect on site release totals.

On November 25,1997 a liquid release occurred during hydrolazing activities.

The liquid portion of the release did not reach the storm drain system. The release was evaluated as a ground level release via evaporation for impact on Offsite Doses. The releases were evaluated for impact on Offsite doses and 4rm-arv4RL AR9tr12

II. DETAILED INFORMATION (CONT'D) documented. The release did not have a significant effect on site release totals.

G. Estimate of Total Error

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

Activation Tritium Entrained Gross Products Ga* Alpha l Sampling 26 % 26 % 26 % 26%

Measurement 68 % 65 % 61 % 92 %

TOTAL 73 % 70 % 66 % 95 %

Sampling errors include uncertainty associated with mixing, representative sampling and discharge volume. Measurement errors includa 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 sou rce.

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

2. Gaseous The maximum errors (not including sample line loss) are collectively estimated I to be Fission &

Activation lodine Particulate Alpha Cross l

Products Tritium Sampling 32 % 23 % 22 % 22 % 23 %

Measurement 61 % 67 % 65 % 101 % 62%

TOTAL 69% 71 % 69 % 103 % 66 %

i Sampling errors include ur. certainty associated with sample flow, vent flow

[ and monitor cahbration.

! Measurement errors include uncertainty associated with instrument calibration l 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.

dwo-are/ arf AR94!J

l II.

DETAILED INFORMATION (CONT'D)

L H.- Solid Radioactive Waste Shipments i' See Table 3 for shipment information.

l l

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 No reportable instances of inoperability occurred during the report period.

K. Annual Sewage Disposal Summary There was no sewage disposalin 1997.

III. RADIATION DOSE

SUMMARY

Indicated below is the annual summary of offsite doses attributable to GGNS during 1997.

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

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

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

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

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

f t

dase drg/ARERR9M4

IIL RADIATION DOSE

SUMMARY

,(CONT'D) 1997 Liquid Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL 4 Whole Body 4.84E-03 1.01E-02 1.13E-02 6.44E-03 3.26E-02 Bone 1.03E-02 1.02E-02 8.22E-03 2.46E-03 3.12E-02 Liver 1.03E-02 1.53E-02 1.50E-02 8.02E-03 4.87E-02 Thyroid 2.60E-03 3.05E-03 2.38E-03 3.01E-03 1.10E-02 ,

Kidney 2.70E-03 5.50E 6.13E-03 4.24E 1.86E-02 l Lung 6.59E-03 6.18E-03 4.27E-03 3.68E-03 2.07E-02 GI-LLI 1.22E-02 1.64E 6.76E-03 1.61E-02 5.14E-02 B. Airborne-Related Exposure Pathway The values presented in this section utilize information provided in Tables 1 A and 1C 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, locations within the site boundary were considered when selecting locations for dose calculations.

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

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

Particulate, Radiciodine and Tritium i

Organ dose rate from exposure to radiciodines, tritium and particulates are l

computed for an individuallocated at the site boundary. l l

Organ dose from exposure to radiciodines, tritium and particulates are computed i for an individuallocated in 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 / cow / milk 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.

chtmer/ARTRR9MS

l III. RADIATION DOSE

SUMMARY

(CONT'D)

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 distance 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 determined daily during the reporting period and would represent the maximum possible dose received by members of j the public.

Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosimeter (TLD) badges located at controllocations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 1997 as net exposure [ field reading - (transit + shield)]

)

normalized to 92 days.

1997 Airbome Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Iodine, Tritium & Particulates 4.60E02 3.89E-02 419L02 9.43E02 2.21E-01 Fission and Activation Cases Total Body dose, mrem /yr 2.48E-02 2.055-02 2.39E-02 2.00E-02 Skin dose, mrem /yr 4.70E-02 3.80E-02 4.02E-02 3.77E-02 Camma Air dose

• 5.91E-03 4.35E-03 5.99E-03 4.70E-03 2.09E-02 Beta 6.20E-03 4.46E-03 4.21E-03 4.96E-03 1.98E-02 Air dose

• Direct Radiation 0 0 0 0 0

• Measurement units are mrad IV. OFFFSITE DOSE CALCULATION MANUAI/

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

One revision to the ODCM were processed during the reporting period.

Changes are summarized below.

ciumWARERR9W6

IV. OFFFSITE DOSE CALCULATION MANUAI/

RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES (CONT'D)

Revision 21:

e re-instated fish sampling in the Radiological Environmental Monitoring Program at an annual frequency A complete copy of ODCM Revision 21 is included as Attachment 1.

B. Radioactive Waste Treatment Systems No major changes were made to the liquid or gaseous radwaste treatment systems in 1997.

l dwn-arr/ARERR9617

TABLE 1A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES )

JANUARY - JUNE 1997 l l Unit l Quarter l Quarter lEst Total l Grand Gulf Nuclear Station l l 1 l 2 l Error % l A. Fission & Activation Gases l 1. Total release l Ci l 1.25E+01l 8.94E+00l 6.90E+01l l 2. Average release rate for period l uCi/secl 1.59E+00l 1.14E+00l t

l 3. % of Technical specification limit l  %

l 1.18E-01l 8.69E-02l B. Iodines l 1. Total iodine-131 l Ci l 0.00E+00l 0.00E+00l 7.10E+01l l

l 2. Average release rate for period l uCi/secl 0.00E+00l 0.00E+00l l ......__......................__...........__.................. .. ...

l 3. % of Technical specification limit l  % l 0.00E+00l 0.00E+00l C. Particulates l 1. Particulates with half-lives >8 days l Ci l 1.45E-04l 4.33E-06l 6.90E+01l l 2. Average release rate for period l uCi/secl 1.86E-05] 5.51E-07l l 3. % of Technical specification limit l  % l 1.10E-02l 3.07E-04l ,

l 4. Gross alpha radioactivity l Ci l 8.43E-12l 1.64E-12l l D. Tritium l 1. Total release l Ci l 3.20E+01l 2.76E+01l 6.60E+01l l 2. Average release rate for period l uCi/secl 4.07E+00l 3.51E+00l l 3.-% of_ Technical specification limit l  % l 6.03E-01l 5.19E-01l I

E. Tritium, radioiodines and particulates

)

j l 1. % of Technical specification limit l  % l 6.14E-01l 5.19E-01l i

TABLE 1A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 199~/

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JULY - DECEMBER 1997 l l Unit l Quarter l' Quarter lEst Totall l Grand Gulf Nuclear Station l l 3 l 4 l Error % l A. Fission & Activation Gases l 1. Total release l Ci l 7.51E+00l 1.00E+01l 6.90E+01l l 2. Average release rate for period l uCi/secl 9.56E-01l 1.27E+00l l 3. % of Technical specification limit l  %

l 1.20E-01] 9.39E-02l B. Iodines l 1. Total iodine-131 l Ci l 1.14E-07l 7.87E-06l 7.10E+01l l 2. Average release rate for period l uCi/secl 1.45E-08l 1.00E-06l l 3.  % of Technical specification limit l  %

l 6.05E-05l 2.30E-03l i

k C. Particulates l 1. Particulates with half-lives >8 days l- Ci l 1.47E-06l 9.13E-06l 6.90E+01l l 2. Average release rate for period l uCi/secl 1.86E-07l 1.16E-06l l 3. % of Technical specification limit l  % l 1.52E-04l 7.63E-04l l 4. Gross alpha radioactivity l Ci l 0.00E+00l 0.00E+00l I

D. Tritium l 1. Total release l Ci l 2.97E+01l 6.66E+01] 6.60E+01l l 2. Average release rate for period l uCi/secl 3.77E+00l 8.47E+00l l 3.  % of Technical specification limit l  % l 5.58E-01l 1.25E+00l E. Tritium, radioiodines and particulates l 1.  % of Technical specification limit l  % l 5.59E-01l 1.26E+00l chamargMRERR9M9 I

l

]

l- TABLE 1B l ENTERGY OPERATIONS,INC.

GRAND GULF NUCLEAR STATION UNIT 1 JANUARY- DECEMBER 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 GASEOUS EFFLUENTS - ELEVATED RELEASES (Not Applicable - GGNS releases are considered ground-level) l l

i

.. m.,m,

)

l

( _

1 i

i TABLE 1C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 l JANUARY - JUNE 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 l

GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE l Nuclides Released l Unit l Quarter l Quarter l Quarter l Quarter l

..__._........._....._........._.___.._ ................._._.............___.... l l l l 1 l 2 l 1 l 2 j.

l

1. Fission gases l XE-133 l Ci l 5.78E+00l 4.12E+00l 0.00E+00l 0.00E+00l l KR-88 l Ci l 2.47E-01) 1.76E-01l 0.00E+00l 0.00E+00l XE-135 l Ci 5.53E+00 3.94E+00 1 0.00E+00l 0.00E+00l XE-138 l Ci 1.48E-01 1.05E-01 0.00E+00l 0.00E+00l l XE-135M l Ci 6.52E-01) 4.65E-01 0.00E+00l 0.00E+00l l KR-85M l Ci 3.48E-02l 0.00E+00 0.00E+00l 0.00E+00l l AR-41 l Ci l 1.01E-01l 1.27E-01 0.00E+00l 0.00E+00l I I I I I I I l Total for period l Ci l 1.25E+01l 8.94E+00l 0.00E+00l 0.00E+00l

2. Iodines l I-131 Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l I-132 Ci 0.00E+00 0 00E+00l 0.00E+00l'O 00E+00l l I-133 Ci 0.00E+00 0.00E+00l 0.00E+00l 0.00E+00 l I-134 Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00 l I-135 Ci ( 0.00E+00 0.00E+00l 0.00E+00l 0.00E+00) j l i I I I I )

l Total for period l Ci j 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l

3. Particulates

__.......___...____...............................__ ...........___...........__ )

l H-3 l Ci 3.20E+01l 2.76E+01l 0.00E+00l 0.00E+00l l Sr-89 l Ci 2.03E-07l 5.31E-07l 0.00E+00l 0.00E+00l l Sr-90 l Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l CO-58 l Ci 2.80E-06] 0.00E+00l 0.00E+00l 0.00E+00l l MN-54' l Ci l 4.07E-05l 1.59E-06l 0.00E+00l 0.00E+00l l CO-60 l Ci l 1.01E-04l 2.21E-06l 0.00E+00l 0.00E+00l l l l l l l l l Total for period l Ci l 3.20E+01l 2.76E+01l 0.00E+00l 0.00E+00l j ................____.......__..................._____..__ ......................

l

(

f thre49 ARERRW21 l

l I

i TABLE 1C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 JULY - DECEMBER 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 199*7 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE l Nuclides Released l Unit l Quarter l Quarter l Quarter l Quarter l l l l 3 l 4 l 3 l 4

- l

1. Fission gases l XE-133 l Ci 2.96E+00 4.66E+00l 0.00E+00l 0.00E+00l l l KR-88 l Ci 1.26E-01 1.99E-01 0.00E+00l 0.00E+00l l XE-135 l Ci 2.83E+00 4.45E+00 0.00E+00l 0.00E+00l  ;

j XE-138 l Ci 7.58E-02 1.19E-01 0.00E+00l 0.00E+00l l l l XE-135M Ci 3.34E-01) 5.25E-01 l 0.00E+00l 0.00E+00l l AR-41 l Ci 1.19E+00l 6.13E-02 0.00E+00l 0.00E+00l i i c I I I I J l Total for period l Ci l 7.51E+00l 1.00E+01l 0.00E+00l 0.00E+00l

_____........___..._________....__.......__................____ ................ 3

! 2. Iodines l .... ..___ .. .............__................__.__........._____..____........._

l I-131 l C1 1.14E-07 7.87E-06l 0.00E+00l 0.00E+00l l I-132 l Ci 0.00E+00 0.00E+00l 0.00E+00l 0.00E+00l l I-133 l Ci 2.33E-06 4.21E-05l 0.00E+00l 0.00E+00l l I 134 l Ci 0.00E+00 l 0.00E+00l 0.00E+00l 0.00E+00l l I-135 l Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l l l l l l l Total for period l Ci l 2.44E-06l 5.00E-05l 0.00E+00l 0.00E+00l

3. Particulates l H-3 l Ci 2.97E+01l 6.66E+01l 0.00E+00l 0.00E+00l l Sr-89 l Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l  !

l Sr-90 l Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l  ;

l CO-60 l Ci 1.47E-06l 7.14E-06l 0.00E+00l 0.00E+00l  !

l MN-54 l Ci 0.00E+00 1.98E-06l 0.00E+00l 0.00E400l ,

I .I I I i ;

. _______ ........__.......__. ..___.....____.........._______.................. i l Total for period- l Ci l 2.97E+01l 6.66E+01l 0.00E+00l 0.00E+00l shrerarr/AAIAA422

I TABLE 1D ENTERGY OPERATIONS, INC.

I GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Gascous Release Type Sampling Frequency Minimum Analysis Type of Activity Detection Frequency Analysis (LLD) hacimif A. (1) Radwaste Building 31 Days 31 Days Principal Gamma lx10*

Ventilation Exhaust Grab Sample (O Emitters (b,e) l H-3 1x10*

l l (2)FuelHandling Area Continuous (d)(0 7 Days (c) 1-131 1x10'"

l Ventilation Exhaust Charcoal Sample j I-133 1x104 '

f (3) Containment Continucus (d)(0 7 Days (c) Principal Gamma 1.:0~" ~

j Ventilation Exhaust Particulate Sample Emitters (c)

(I-131, Others) l (4) Turbine Building Continuous (d)(O 31 Days Gross Alpha l x10'"

Ventilation Exhaust Composite Particulate Sample Continuous (d)(0 92 Days St-89, Sr-90 1 x10-"

Composite Particulate Sample Continuous (0 Noble Gas Monitor Noble Gases lx10*

Gross Beta or Gamma B. (1) Offgas Post Treatment 31 Days 31 Days Principal Gamma 1x10 4

Exhaust, whenever Grab Sample (O Emitters (c)  !

there is flow (2) Standby Gas Treatment A Exhaust, whenever there is flow (3) Standby Gas Treatment B Exhaust, whenever there is flow i

l NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-1.

1

(

l

..wru, u

TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 JANUARY - JUNE 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997

} LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I 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 gases, alpha) l Ci 5.25E-02] 4.35E-02j 7.30E+01l

2. Average diluted concentration l during period l uCi/ml 3.21E-07 2.03E-07?

3. Percent of applicable limit l  % 9.04E-02 8.16E-02l B. Tritium l 1. Total release Ci l 3.67E+01l 4.48E+01l 7.00E+01l

' 2. Average diluted concentration l during period uCi/ml 2.24E-04 2.09E-04l

3. Percent of applicable limit  % l 2.24E+00l 2.09E+00l C. Dissolved and entrained gases l 1. Total release l Ci 9.68E-06l 9.40E-05l 6.60E+01l l 2. Average diluted concentration l l l j during period l uCi/ml 5.92E-11l 4.40E-10l l 3. Percent of applicable limit l  % 8.66E-04l 6.59E-03l 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 2.01E+06l 2.47E+06l 5.00E+00l lF. Volume of dilution water used l liters l 1.61E+08l 2.11E+0Bl 5.00E+00l chem +r/ARutA9624

TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 JULY - DECEMBER 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES l Unit l Quarter l Quarter lEst Total l l l 3 l 4 l Error % l A. Fission & activation products

1. Total release (not including H3, l '

l l gases, alpha) Ci l 2.10E-02 1.25E-02] 7.30E+01l

2. Average diluted concentration l i during period uCi/ml 6.31E-08 7.63E-08l l 3. Percent of applicable limit I  % 2.86E 02 1.20E-01l B. Tritium l 1. Total release l Ci l 4.54E+01 4.50E+01 7.00E+01l l 2. Average diluted concentration l l during period uCi/ml l 1.36E-04 2.74E-04 l 3. Percent of applicable limit l  % l 1.36E+00 2.74E+00l C. Dissolved and entrained gases l 1. Total release Ci 1.29E-05 0.00E+00l 6.60E+01l

2. Average diluted concentration l

during period l uCi/ml 3.88E-11 0.00E+00l l 3. Percent of applicable limit l  % 5.82E-04l 0.00E+00l 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 3.13E+06l 1.84E+06l 5.00E+00l lF. Volume of dilution water used l liters l 3.30E+08l 1.62E+08l 5.00E+00l ch,m-kr/ARERR425 l

1

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 JANUARY - JUNE 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES CONTINUOUS MODE BATCH MODE l Nuclides Released Unit Quarter l Quarter l Quarter l Quarter l 1 2 l 1 l 2 l strontium-89 C1 0.00E+00 0.00E+00l 0.00E+00l 0.00E+00l strontium-90 ,

Ci l 0.00E+00 0.00E+00 0.00E+00l 0.00E+00l cesium-134 .l Ci 0.00E+00 0.00E+00 0.00E+00l 1.84E-05l l cesium-137 Ci 0.00E+00l 0.00E+00 0.00E+00l 2.05E-05l l iodine-131 , Ci j 0.00E+00l 0.00E+00l 0.00E+00l 3.39E-06l l

l cobalt-58 Ci 0.00E+00l 0.00E+00l 5.13E-05l 1.29E-04l l cobalt-60 Ci 0.00E+00l 0.00E+00l 3.04E-03l 4.03E-03l l iron-59 l Ci l 0.00E+00l 0.00E+00l 2.28E-05l 2.27E-05l l zinc-65 l Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l manganese-54 Ci 0.00E+00l 0.00E+00l 2.51E-04l 4.83E-04l l chromium-51 Ci l 0.00E+00l 0.00E+00l 1.36E-03l 6.43E-03l l zirconium-niobium-95 Ci 0.00E+00l 0.00E+00l 0.00E+00l 6.97E-06l l molybdenum-99 Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l technetium-99m Ci 0.00E+00l 0.00E+00l 0.00E+00l 1.67E-05l l barium-lanthanum-140 Ci '

O.00E+00l 0.00E+00 0.00E+00l 0.00E+00l l cerium-141 Ci 0.00E+00l 0.00E+00 0.00E+00l 0.00E+00l Cu-64 l Ci 0.00E+00 . 0.00E+00l 9.22E-06l 3.67E-06l As-76 l Ci 0.00E+00 0.00E+00 0.00E+00l 2.47E-04l Ag-110m l Ci 0.00E+00 0.00E+00 0.00E+00l 6.52E-05l Fe-55 l Ci 0.00E+00l 0.00E+00 4.77E-02l 3.20E-02l l

l Total for period (above) l Ci l 0.00E+00l 0.00E+00l 5.25E-02l 4.35E-02l l xenon-133 l Ci l 0.00E+00l 0.00E+00l 4.61E-06 9.10E-05l l xenon-135 l Ci l 0.00E+00l 0.00E+00l 5.07E-06 3.01E-06l l l Xe-133m l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l dwn-stofARERRS26

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 JULY - DECEMBER 1997 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES CONTINUOUS MODE BATCH MODE j Nuclides Released l Unit Quarter l Or.arter l Quarter l Quarter l l l 3 l 4 3 l 4 l l strontium-89 Ci 0.00E+00) 0.00E+00 0.00E+00l 0.00E+00l l strontium-90 Ci 0.00E+00: 0.00E+00 0.00E+00 0.00E+00l l cesium-134 Ci 0.00E+00 0.00E+00 3.30E-05 6.97E-06l l cesium-137 Ci l 0.00E+00 0.00E+00 4.82E-05 6.77E-06l l iodine-131 Ci l 0.00E+00l 0.00E+00 0.00E+00 0.00E+00l cobalt-58 Ci 0.00E+00 , 0.00E+00l 2.46E-05l 4.44E-05l l cobalt-60 Ci 0.00E+00 0.00E+00l 2.32E-03l 5.70E-03l iron-59 Ci 1 0.00E+00 0.00E+00l 0.00E+00l 0.00E+00l zinc-65 Ci 0.00E+00 l 0.003+00l 0.00E+00l 0.00E+00l l manganese-54 Ci 0.00E+00l 0.00E+00l 7.64E-05l 8.64E-04l l chromium-51 Ci , 0.00E+00l 0.00E+00l 7.51E-03l 6.31E-04l l zirconium-niobium-95 Ci 0.00E+00l 0.00E+00l 0.00E+00l 0.00E+00l l molybdenum-99 Ci 0.00E+00l, 0.00E+00l 0.00E+00l 0.00E+00l l technetium-99m Ci l 0.00E+00 0.00E+00l 0.00E+00 0.00E+00l l barium-lanthanum-140 Ci l 0.00E+00 0.00E+00l_0.00E+00 0.00E+00l l cerium-141 Ci l 0.00E+00 0.00E+00l 0.00E+00l 0.00E+00l l Cu-64 l Ci l 0.00E+00l 0.00E+00l 0.00E+00l 5.52E-06 l Fe-55 l Ci l 0.00E+00l 0.00E+00l 1.10E-02l 5.24E-03 Total for period (above) l l Ci l 0.00E+00l 0.00E+00l'2.10E-02l 1.25E-02l ,

1 l xenon-133 l Ci 0.00E+00l 0.00E+00l 1.29E-05 0.00E+00l l l xenon-135 l Ci 0.00E+00 0.00E+00l 0.00E+00 0.00E+00l l Xe-133m Ci 0.00E+00 0.00E+00l 0.00E+00j 0.00E+00l l l  !

l i

drm+gMRl'RRb27

TABLE 2C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Liquid Release Type Sampling Frequency Minimum Analysis Type of Activity Detection Frequency Analysis (LLD)

(pCi/mh (af A. Batch Waste Release Prior to Release Each Prior to Release Principal Gamma 5x10~'

Tanks (c) Batch Each Batch Emitters (d) 1-131 1x10*

Prior to Release One 31 Days Dissolved and lx10

Batch /M Entrained Gases (Gamma Emitters)

Prior to Release Each 31 Days H-3 lx10-'

Batch Composite (b)

Gross Alpha lx10' Prior to Release Each 92 Days St-89, St-90 5x10*

Batch Composite (b)

Fe 55 1x10 4 1

B. SSW Basin (berm blowd nn) Prior to Release Each Prior to Release Principal Gamma 5x10-7 j Blowdown Each Batch Emitters (d) 1-131 lx104 f

)

NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1 1, i

l i chree,m/ARIRR%28 i

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY - DECEMBER 1997 A. Solid Waste Shipped Offsite for Burial or Disposal 1

1.

Estimate i Type of Waste Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total l Error (%)

a. Spent resins, filter,61udges, m' 7.33+01 3.06E+01 7.7E+00 6.8E+00 oil, evaporator bottoms, etc. )

• Ci 2.9E+01 9.33E+01 1.22E+02 2.36E+02 7.2E+01

b. Dry compressible waste, m' 2.11E+01 7.0E+00 1.4E+00 0.00E+00 contaminated equipment, etc. 'Ci 1.14E+00 9.31E-01 1.46E+00 0.00E+00 6.9E+01

c. Irradiated components, m*

control rods, etc. 'Ci None None None None N/A

d. Other m'

'Ci None None None None N/A

• Total curie quantity determined by measurement. Total volume used is burial container volume. All solid waste was Class "A" as defined by

! 10CFR Part 61.

2. Estimate of major radionuclide composition (by type of waste as l identified above) 1st Qtr 2nd 3rd 4th Qtr Qtr Qtr i a. Fe-55 68 % 65 % 70 % 68 %

Co-60 18% 15% 16% 15%

Mn-54 4% 12% 10% 10%

Cr-51 3% 4% 2% 2%

C-14 2% 2% <1 % 2%

H-3 2% 1% 1% 2%

All Others 3% 1% <1 % 1%

b. Fe-55 69% 60 % 59 % 61 %

Mn-54 15% 16% 16% 17%

Co-60 9% 17% 16% 14 %

Cr-51 4% 5% 6% 6%

All Others 3% 2% 3% 2%

c. N/A N/A N/A N/A N/A d.N/A N/A N/A N/A N/A 6,m-8,nfARL RR96 29

i l

l TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION l l

SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS (CONT' D) ,

JANUARY - DECEMBER 1997 -

1

)

A. Solid Waste Shipped Offsite for Burial or Disposal (CONT'D)

3. Solid Waste Disposition

a. Resins were dewatered in steel liners or High Integrity Containers ILSAO according to the requirements of the GCNS PCP and shipped to Barnwell, South Carolina, for burial. Some resin was shipped to Scientific Ecology Group (SEG) of Oak Ridge, Tennessee and Molten Metal Technologies (MMT) of Oak Ridge, Tennessee for volume reduction.

SEG and MMT shipped reduced waste to Barnwell. South l Carolina. Reduced resin was dewatered and shipped in liners and High Integrity Containers (I.SA). 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 j of Memphis Tennessee for volume reduction. SEG and F.W. Hake shipped reduced waste to Barnwell, South Carolina. Reduced volume was used in providing information given in A.1.b.

c. No irradiated components were shipped.

d. No waste in this category.

Number of Shipments Mode of Transportation Destination 2 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition) l j Number of Shipments Mode of Transportation Destination '

i None N/A N/A C. Annual Sewane Sludge Summary Averane Co-60 Averane Mn-54 Number of Shipments Total Gallons Activity (pCi/l) Activity (oCi/l)

No sewage was disposed of during 1997.

1 chrm-ery/ARIRR90.Jo J