ML20029B257
| ML20029B257 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1990 |
| From: | Cottle W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-91-00038, GNRO-91-38, NUDOCS 9103060316 | |
| Download: ML20029B257 (61) | |
Text
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~ r- ergy Ent rgy Opstat6ons,Inc.
Operations " W. T. Cottle March 1, 1991 U.S. Nuc1 car Regulatory Commission Mail Station PI-137 Wcshington, D.C. 20555 Attention: Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Dncket No- 50-416 License No. NPF-29 Semiannual Radioactive Effluent Release Rnport for the Period July 1, 1990 Through December 31, 1990 GNRO-91/00038 Gentlemen: Attached is the Entergy Operations Inc. Semiannual kadioactive Ef fluent Release Report for Grand Gulf Nuclear Station (GCMS) for the period July 1, 1990 through December 31, 1990. This report is submitted in compliance with the requirements of ICCFR50.36a(a)(2) and the GGNS Technical Specifications 6.9.1.8, 6.9.1.9, 6.13 and 6.14 Questions concerning this report shoald be directed to this office. Yours truly, cap Y"O, err; WTC/GWR/ams attachment: cc: (See Next Page) G9102263/SNLICFLk -1 p 9103o6o316 901r>' 7 - -cw, v f,
O i
<? l hatch 1, 1991 GNRO 91/00038 Page 2 of 3 cc: Mr. D. C. ilintr. (w/a)
Mr. J. Mathis (w/n) M r . R . 11 McGehee (w/a) Mr. N. S. Reynolds (w/n) Mr.11.1,. Thomns (w/o) Mr. Stewart D. Ebricter (w/n) Regtonni Adminintrntor , Lt.S. Nuclent Rc;;ulnt.ory Commiss ion ' Region II 101 Marietta St., N.W., Suito 2900 Atlanto, Georgin 30323 Mr. L. L. Kintner, Project Manager (w/n) Of fice of Nucicar Reactor Regulation 11.S. Nacionr Regulatory Commission Mall Stop 11D21 Washington, D.C. 20555 l l l I l G9102263/SNLICFLR - 2 1
t Grand Gulf Nuclear Station SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT July 1 - December 31, 1990 Prepared By: /D.Jd. 0 teu.o 6 / .!2-$ '?/ Reviewed By: __A _ .. / 2 -6~'P/ Approved By: hdrL (k.h 3_de,Gr._> / G- /2-4 / U SRER9012/SRESCHEM.fLR - i
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T 4 TABLE OF CONTENTS SUBJECT PAGE !
- 1. INTRODUCTION........................................................... I
- 11. O E TA I L E D I N F ORMAT 10N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 A. Re g u l a t o ry L i m i t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . 2
- 1. 10CFR20 Limits
- a. Fission and Activation Gases........................ 2
- b. Radioiodines and Particulates....................... 2
- c. Liquid Effluents.................................... 2
- 2. 10CFR50, Appendix ! Limits
- a. Fission and Activation Gases........................ 3
- b. Radiciodines and Particulates....................... 3
- c. Liquid Effluents.................................... 3
- 3. 4 0C F R 19 0 L i m i t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 B. Maximum Permi ss i bl e Concent rations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
- 1. Airborne.................................................. 4
?. Liquid.................................................... 4 C. A v e r a g e E n e rgy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 D. Measurements and Approximations of Total Activity............... 5
- 1. For fission and Activation Gases.......................... 5
- 2. For Particulates and Radiciodines......................... 6
- 3. For Continuous Releases................................... 6
- 4. For Batch Releases: Gases................................. 6
- 5. For Batch Releases: Liquid Effluents...................... 7 E. BatchReleases..................................................7
- 1. Liquid.................................................... 7
- 2. Gaseous................................................... 8 1
l F. Unp l anned Re l ea s es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8
- 1. Liquid....................... ............................. 8
- 2. Gaseous................................................... 8 SRER9012/SRESCHEM.FLR - ii 1
f TABLEOFCONTENTS(cont'd) l 1 l SUBJECT PAGE G. Estimate of Total Error......................................... 8
- 1. Liquid.................................................... 8
- 2. Gaseous................................................... 9
- 3. Solid Radioactive Waste................................... 9 H. Solid Radioactive Waste Shipments............................... 9
- 1. Meteorological Data............................................. 9 J. Radioactive Effluent Monitoring Instrumentation Operability ................................................... 10 K. Annu al Sewage Di s pos al Summa ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 111. 1990 R AD I A i10N DOS E S UMMAR Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 A. Water-Rel ated Exposu re Pat hways . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 8. Airborne-Related Exposure Pathways ............................ 11 IV. OFFSITE DOSE CALCULATION MANUAL / PROCESS CONTROL PROGRAM /
RADI0 ACTIVE WASTE TREATMENT SYSTEM CHANGES A. Offsite Dose Calculation Manual (0DCM)......................... 13 B. Process Control Program (PCP).................................. 13 C. Radioactive Waste Treatment Systems............................ 13 l l l l 1 l 1 l I SRER9012/SRESCHEM.FLR - iii l
t t LIST OF TABLES TABLE PAGE 1A Gaseous Effluents - Summation of All Releases............. 1A-1 IB Gaseous Effluents - Elevated Releases..................... 1B-1 1C Gaseous Effluents - Ground-Level Releases................. 1C-1 1D Radioactive Gaseous Waste Sampling and Analysis Program... 10-1 2A Liquid Effluents - Summation of All Releases.............. 2A-1 28 1.iquid Effluents - Continuous and Batch Modes............. 28-1 2C Radioactive Liquid Waste Sampling and Analysis Program.... 2C-1 3 Solid Radioactive Waste and Irradiated fuel Shipments.......... .................................. 3-1 4A Meteorological Data - July-September 1990........ 4A-1 to 4A-17 4B Meteorological Data - October-December 1990...... 4B-1 to 4B-17 4C Meteorological Data Summary . . . . . . . . . . . . . . . . . . . . . . 4C-1 to 4C-17 4D Cl assi ficat ion of Atmospheric Stabili ty. . . . . . . . . . . . . . . . . . . 4D-1 LIST OF ATTACHMEWl5
- 1. Annual Sewage Disposal Summary l
l SRER9012/SRESCHEM.FLR - iv
r t
- 1. INTRODUCTION This Semiannual Radioactive Ef fluent Release Report for the period of July 1 through December 31, 1990 is submitted in accordance with Section 6.9.1.8 of Appendix A to Grand Gulf Nuclear Station (GGNS) License No. NPF-29. That portion of Appendix A which refers to the monitoring of radioactive effluents, Sections 3/4-11 and 3/4-12, will hereafter be referred to as the Radiological Effluent Technical Specification (RETS).
Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environr:9nt were analyzed in accordance with the RETS requirements. All effluent releases were within the concentration and total release limits specified by the RETS. Projected offsite doses were within the dose limits specified by the RETS. The doses were projected using the methodology of the GGNS Offsite Dose Calculation Manual (0DCM). The summation of all gaseous releases during the reporting period is given in Table 1A, while elevated releases and ground-level releases for the reporting period are give,i in Tables 1B and IC, respectively. Table 10 describes the radioactive gaseous sampling and analysis program implemented at GGNS. The summation of all liquid releases during the reporting period is given in Table 2A, while continuous and batch mode releases are given in Table 28. Table 2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS, Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3. Meteoroiogical data is included in Tables 4A - 4C. Table 40 presents atmospheric stability classifications. SRER9012/SRESCHEM.FLR - 1 l. ___._-___m-__.-_.-._ _.._______-_m._
t
!!. DETAILED INFORMATION A. Regulatory Limits
- 1. 10CFR20 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:
Du, = average total body dose rate in the current year (mrem /yr)
=
XTQ r K. Q'. 3500 mrem /yr D, = average skin dose rate in the current year (mrem / year)
= X7Q r (L, + 1.1 M,) Q', 53000 mrem /yr where tte terms are defined in the GGNS ODCM.
- b. Radiciodines and Particulates - The release rate limit for the sampling perTod for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:
0,, = average organ dose rate in current year (mrem /yr)
= r,WP,Q'4 sl500 mrem /yr where the terms are defined in the GGNS ODCM.
- c. Liquid Ef fluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the reactors at the site shall not exceed at any time the values.
specified in 10CFR20, Appendix B, Table !!, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestrictad areas from all reactors at the site, shall be limited to 2 > 10" microcuries/mi moximum concentration. SRER9012/SRESCHEM.FLR - 2
t
- 2. 10CFRSO, Appendix ! 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
= 3.17 x 10~" r , M, XT7 Q s 5 mrad /qtr s10 mrad /yr D,, = air dose due to beta emissions from noble gas
= 3.17 x 10~" r , N. XTF Q s10 mrad /qtr s20 mrad /yr where the terms are defined in the GGNS ODCM.
- b. Radioiodines and Particulates - The dose to an individual Trom tritium, 1-131, 1-133 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:
D,, = dose to an individual from tritium, 1-131, 1-133 and radionuclides in particulate form with half-lives greater than 8 days (mrem)
= 3.17 x 10~" r , R, W' Q s7.5 mrem /qtr Any Organ s 15 mrem /yr Any Organ where the terms are defined in the GGNS ODCH.
- c. Liquid Effluents - The dose from radioactive materie b in liquid effluents shall be such thatt m
D,.o = r , (A,,.o E at i C,i F]i s1.5 mrem /qtr Total Body i=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. l l 1 SRER9012/SRESCHEM.FLR - 3
-. . - .- -.___ _~ . - _ - _ - - _ - - - . ,
e
- 3. 40CFR190 Limits Doses are calculated for fission and Activation Gases; Radiciodines and Particulatesi and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are 525 mrem /yr, Total Body or any Organ except Thyroid s75 mrem /yr, Thyroid s10 mrad y/qtr or s20 mrad y/yr, Fission and Activation Gases
, s20 mrad p/qtr or s40 mrad p/yr, Fission and Activation Gases s15 mrem /qtr or s30 mrem /yr, any Organ, lodine and Particulates s3 mrem /qtr or s6 mrem /yr, Total Body, Liquid Effluents s10 mrem /qtr or s20 mrem /yr, any Organ, Liquid Ef fluents B. Maximum Permissible Concentrations
- 1. Airborne TheMaximumPermissibleConcentration(MPC)ofradioactive o materials in gaseous effluents is limited by the dose rate restrictions of 10CFR20. In this case, the MPCs are actually determined by the dose factors in Table 2.1-1 of the GGNS ODCM.
- 2. Liquid The MPC of radioactive materials in liquid effluents is limited by 10CFR20, Appendix B, Table 11, Column 2. The MPC chosen is the most conservative value of either the soluble or insoluble MPC for each radioisotope.
C. Average Energy L Not applicable for GGNS RETS. < l l -SRER9012/SRESCHEM.FLR - 4 l l I,-- _ _ . ~ , . . . . , __ - . - . - _ . . . _ _ . _ _ . . . - .- - - --.
r
- 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
- 2. Radiciodines
- 3. Particulates
- 4. Liquid Effluents Tables 10 and 20 give sampling frequencies and minimum detectable sensitivity requirements for the analysis of gaseous and liquid effluent streams, respectively.
Values in the attached tables given as zero do not necessarily ' imply that the radionuclides were not p esent. A zero indicates that the radionuclide was not present ct IcVels greater than the sensitivity requirements shown in Tables ID .ad 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 l
The following noble gases are considered in evaluating gaseous airborne discharges: Ar-41 Xe-131m Kr-85m Xe-133 Kr-85 Xe-133m Kr-87 Xe-135m Kr-88 Xe-135 Kr-89 Xe-138 Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high-resolution germanium detectors. (See Table ID for sampling and analytical requirements.) Isotopic values.thus obtained are used for dose release rate calculations due to effluent releases as given in Section 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 C, = V4 +m where C, = isotopic calibration factor for isotope i SRER90!2/SRESCHEM.FLR - 5 l l . . . __ - -. - -
e V, = 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). These calibration factors, along with the hourly effluent monitor l values and flow rates, are entered into the laboratory computer j where the release rates for individual radionuclides are i calculated and stored if no activity is detected in the grab 1 sample, the calibration factor for Kr-85 and the dose factor for Kr-89 are entered into the laboratory computer.
- 2. For Particulates and Radiciodines l The radioiodines and radioactive materials in particulate form to i be considered are:
Zn-65 1-133
- Cr-51 Cs-134
, Mn-54 Cs-136
- fe-59 Cs-137 Co-58 Ba-140 Co-60 Ce-141 Sr-89 Ce-144
- Sr-90 Other radionuclides Z r-95 with half-lives Sb-124 greater than 1-131 8 days.
- 3. For Continuous Releases Continuous sampling is performed on the continuous release points (i.e., Radwaste Vent, Containment Purge, fuel Handling Area Vent, i
Turbine Building Vent). Particulate material is collected by filtration. Radioiodines are collected by adsorption onto a charcoal filter. Periodically these filters are removed and analyzed on the pulse height analyzer to identify and quantify l- radioactive materials collected on the filters. Particulate - i filters are then analyzed for gross alpha and Strontium-89 and -90
- as required. Gross alpha determinations are made using a 1 2-pi gas-flow proportional counter. Strontium-89 and -90 values
! are obtained by clemical sep6 ration and subsequent analysis using 2-pi gas fIow proportlonal counters. During major operational o occurrences, requirements t1e frequency'c"f of footnote. of sampling Table 10, "isRadioactive increased Gaseous to satisfy the Waste Sampling and Analysis," (GGNS RETS, Table 4.11.2.1.2-1). , 1~
- 4. For Batch Releases -Gases-The processing of batch type releases (from Containment Purge) is analogous to that for continuous releases.
$RER9012/SRESCHEM.fLR - 6
- 5. For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:
H-3 Mo-99 Co-58 Tc-99m Co-60 1-131 fe-55 1-132 fe-59 l-133 Zn-55 1-135 Mn-54 Cs-134 Cr-51 Cs-137 Sr-89 Ba-140
- Sr-90 La-140 Nb-95 Cc-141 Zr-95 Ce-144 Representative pre-release grab samples are obtained and analyzed as required by Table 2C. Isotopic analyses are performed using the computerized pulse height analysis system previously described. Aliquots of each pre-released samp t, proportional to the waste volume released, are composited in accordance with the requirements of Table 2C. Strontium determinations are made by performing a chemical separation and counting the separated strontium using a 2-pi gas flow proportional counter. Gross alpha determinations are made using 2 pi gas flow proportional counters.
Tritium and Iron-55 concentrations are determined by using liquid scintillation techniques. Dissolved gases are determined employing grab sampling techniques and then counting on ;he pulse height analyzer system. E. Batch Releases
- 1. Liquid 3rd Quarter 1990
- a. Number of batch releases: 102
- b. Total time period for batch releases: 31,387 minutes
- c. Maximum time period for a batch release: 420 minutes
- d. Average time period for batch releases: 308 minutes
- e. Minimum time period for a batch release: 192 minutes 4th Quarter 1990
- a. Number of batch releases: 93
- b. Total time period for batch releases: 28,321 minutes
- c. Maximum time period for a batch release: 405 minutes
- d. Average time period for Latch releases: 305 minutes
- e. Minimum time period for a batch-release: 85 minutes -
SRER9012/SRESCHEM.fLR - 7
o
- 2. Gaseous 3rd & 4th Quarter 1990 No batch releases w rre made during this period.
- f. Unplanned Releases
- 1. Liquid 3rd & 4th Quarter 1990 No unplanned liquid release occurred during this period.
- 2. Gaseous 3rd & 4th Quarter 1990 No unplanned gaseous release occurred during this period.
G. Estimate of Total Error
- 1. Liquid The maximum errors are collectively estimated to be fission & Dissolved &
Activation Entrained Gross products, Tritiui Gases Alpha 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 include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Coanting errors are based on measurements of blank samples and, for germanium detectors, the 1 cast-readily-detectable radioisotope. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a rddioactive source. Total error is calculated by taking the square root of the sum of the squares of the individual errors. SRER9012/SRESCHEM.FLR - 8 l . __m- _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ __
t
- 2. Gaseous The maximum errors (not including sample line loss) are !
collectively estimated to be- ! fission & Activation Particu- Gross Gases lodine late. Alpha Tritium l 9.mpling 324 23% 22% 22% 23% . g arement 61% 67% 65'$ 101% 62% Total 69% 71% 69% 103% 66% Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration. Measurement errors include uncertainty associated with instrument calibration and preparation and counting of low-activity samples. Measurement and total errors are calculated by the same methods used for liquid.cffluents.
- 3. Solid Radioactive Waste See Table 3 for error terms.
H. Solid Radioactive Waste Shipments See Table 3 for shipment information, t I. Meteorological Data
- 1. Meteorological Data Recovery Rate 3rd Qtr.
Parameter % Data Recovery 50m Wind Direction 100.00 50m Wind Speed 100.00 10m Wind Direction 99.09 1 10m Wind Speed 100.00 Temperature- 100.00 Dew Point- 100.00 Delta T 100.00 Precipitation 100.00 SRER9012/SRESCHEM.FLR - 9
,- -rsw-=-y=.. m -g + w .,er.c.. , -,..w , . ae - -
, I
)
l 4th Qtr. Parameter % Data Recovery 50m Wind Direction 100.00 50m Wind Speed 100.00 10m Wind Direction 100.00 10m Wind Speed 100.00 Temperature 100.00 Dew Point 93.57 Delta T 99.91 Precipitation 100.00
- 2. Meteorological data for the period of the report is included in Tables 4A through 4C.
J. Radioactive Effluent Monitoring Instrumentation Operability No reportable instances of inoperability occurred during the report period. K. Annual Sewage Disposal Summary Table 3, Section C, summarizes the 1990 sewage sludge shipments. Attachment 1 is the report submitted to the State of Mississippi. III 1990 RADIA110N DOSE
SUMMARY
Indicated below is the annual summary of offsite doses attributable to GGNS during 1990, inspection of the values indicate that GGNS releases were within the 10CFR50, Appendix ! 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 00CM. A. Water-Related Exposure Pathways The values calculated in this section utilize the information provided in Tables 2A and 2B of this report and the calculational methodology of the 00CM. , 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. SRER9012/SRESCHEM.FLR - 10 L -
o 1990 Liquid Effluent Dose (mrem) Annual 1st Otr 2nd Otr 3rd Otr 4th Otr Total __ Whole Body 1.89E-02 9.34E-03 9.12E-03 5.20E-02 8.94E-02 Bone 1.42E-02 8.72E-03 7.34E-03 7.59E-02 1.06E-01 Liver 2.70E-02 1.45E-02 1.51E-02 1.45E-01 2.02E-01 Thyroid 4.95E-03 6.02E-04 2.19E-03 3.37E-04 8.08E-03 Kidney 8.50E-03 4.27E-03 4.03E-03 2.78E-02 4.46E-02 Lung 3.30E-03 2.66E-03 2.45f-03 2.87E-02 3.71E-02 GI-LLI 3.31E-02 1.81E-02 5.33E-02 4.12E-01 5.17E-01 B. Airborne-Related Exposure Pathways The values presented in this section utilize information arovided in Tables 1A and 1C of this report and the calculational metlodology of the ODCH. Doses and dose rates are computed for locations at the site boundary or at unrestricted areas within the site boundary. The use of unrestricted areas within the site boundary as controlling receptor locations provides. assurance that offsite doses will not be substantially underestimated, as well as determining the radiation dose from gaseous effluents to members of.the public due to their activities inside the site boundary. Particulate, Radiciodine and Tritium Organ doses from exposure to radiciodines, tritium and particulates are computed for an individual located in the south sector at a distance of 0.5 miles. This location corresponds to one of the two onsite GGNS gardens. Pathwcys considered in the dose calculations are inhalation, ground plane, grass / cow / milk, grass / cow / meat and vegetation. For a particular radionuclide, the maximum dose factor obtainable from a combination of age groups and organs is used in the calculation of organ dose. SRER9012/SRESCHEM.FLR - 11
l 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 west-northwest sector at a distance of 0.75 miles.
- This controlling location corresponds to the highest annual average i
atmospheric dispersion for an unrestricted area inside the site boundary (Hamilton Lake). The total body and skin doses reported below are derived from the quarterly average of the maximum instantaneous dose rates determined daily during the re)orting period and would represent the maximum possible dose received />y members of the public onsite. 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, 1990AirborneEffluentDose(mrem) Annual 1st Otr 2nd Otr 3rd Otr 4th Otr Total 1 lodine, Tritium & Particulates 6.19E-03 1.35E-03 1.53E-01 8.90E-02 2.50E-01 Fission and Activation Gases (Total Body
- j. dose) 1.17E-01 1.21E-01 8.27E-01 2.07E-01' l.27E+00 (Skindose) 2.07E-01 2.12E-01 1.66E+ M 3.69E-01 2.45E+00 Gamma
- Air dose
- 2.95E-02 2.95E-02 2.24E-02 1.56E-02 9.70E-02 Beta Air dose
- 1.88E-02 1.81E-02 2.39E-02 1.08E-02 7.16E-02 Direct Radiation 0.4 0.0 0.7 0.5 1.60E+00
- Measurement units are mrad SRER9012/SRESCHEM.FLR - 12 l
t t IV. OFFSITE DOSE CALCULATION MANUAL / PROCESS CONTROL PROGRAM /RADIDACTIVE WAS1E TEATHENT SYSTED3TAELT~'
- A. Offsite Dose Calculation Manual (00CM)
No changes were made during the report period. B. Process Control Program (PCP) No changes were made during the report period. C '. Radioactive Waste Treatment Systems No major changes were made during the report period. SRER9012/SRESCHEM.FLR - 13 l
I l - I
. TABLE 1A
- EFFLUENT AND t*ASTE DI5POSAL SEMIAtsfUAL REPORT 1990 i
i GASEOUS ErrLUENTS.5UP94ATION Or ALL RELEASES
' JULY - DECEMBER 1990 l 1 i Unit l Quarter i Quarter IEst Tota 11
. .. . . .... ,r l Errer 4 l UNIT il 3 6 IGrand Gulf Nuclear .Station . ... .. .... ... .. .. .. . ..
l 1 1 I A. rission & Activation Cases .. .. . ... ... . ... .... ......... ....... . I 1. Total release l Ci I 9.02E+011 1.42E+0il 6.90E+0il l 2. Average release rate.for period I uCi/soci 1.15E+0il 1.81E+001 ...... 1 3. V of Technical specification li=.it I
% l 4.45E.011 3.13E.011 ,
B, Iodines
. . . . .. . ~ .
I 1. Total' iodine-131 . . ..... l Ci l 3. 83E-041- 1. 24E.041 7.10E+ 0il. I 1. Average release rate for period I uCi/seci 4.87E.051 1.56E-051
.... ~... ....
l . 3. 4 of Technical specification I N t I % l 1. 9 2E-0 21 6. 2' 't.0 3 l
. - . . .. ... . . . . .... ~.--. ......
C. Particulates . . . . . . . . . . . . . - . . . - . . . . . - . . . . . - - . 1 1. Particulates -with half lives)8 daysl Ci l 1.68E 041 8.29E-041 6.90E+0il . . . _ . - . . . . . . ~ . .
. . - . . . ~ . . . . . . '
I 2. Average release rate for period i uC1/seci 2.13E.051 ... 1.05E.041 . ...
. . . . .. . . . . ... .. . . ... ~. .. . ,
! .3. % of ~ Technical specification limit l
% 1 8.62E 031 1.59E.021 .
.~..... . .
l 4. Gross alpha radioactivity l Ci l 6.59E-0SI 2.17E.081 > D. Tritium - .- .......... .... ..... . ... - l_1. Total release . 'l Ci I 7.37E. oil'5.83E.011 6.60E+0il .... _. L I 172.= Average release rate for period . I uCi/ sect 9.3BE.021 7.42E.021 . . . ... i . 3. %_of Technical specificationzlimit I % l 6.38E 031 ' 05E-031 .. E. Tritium,radiciodines .. .... and.. .. .. .-particulates l ' 1. % of: Technical specification limit-l % 1 1.50E.02) 2.10E.021 . . . r I l SRER9012/SRESCHEM.fLR-TIA - 1 l [-._ _ . - . . _ . _ _ _ _ . _ . _ , _ _ _ _ _ _ _ _ _ , _
4 TABLE IB Grand Gulf Nuclear Station GASE0US EFFLUENTS - ELEVATED RELEASES (NotApplicable-GGNSreleasesareconsideredgroundlevel) k h SRER9012/SRESCHEM.FLR-TlB - 1 i:
$ ewy ys.n- g- v,>er-q PT +--PT'sJwyme - --w auw %ris e -'y.i pen-.-9i,a.m .s. p .es3,-m..mc.-- '-g.,.w.4..,qp,vy-g - -m--w p. . s a -s av r s.4-'gt---* m r +r 4
_. . - - . _ . , . _ _ - - - - - -- - _ - - - - - _ ~ - e TABLE iC' Crand Gulf Nuc1 Car station UNIT 1 JULY - DECEMBER 1990 ETTLUENT AND WASTE DISPOSAL SEHIANNUAL REPORT 1990 CASEOUS ErrLUENTS-GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE
.. ........................................... i Unit i Quarter I Quartor i Quactor ! Quartor l 1 Nuclides Released l l 3 i 4 1 3 1 4 I l
- 1. Tisnion gases Ci l 1.23E+001 5.84E+001 0.00E+001 0.00E+001 I KR-89 I l XE-135 l Ci l 4.14E+011 1.06E+001 0.00E+001 0.00E+001 I r-18 l Ci 1 5.89E+001 2.19E-011 0.00E+001 0.00E+001 XE-133 l ci j 3.33Z+011 6.52E+001 0.00E&001 0.00E+001 l
1 XE-133H I ci 1 2. 97E-021 1. 21E. oil 0. 00E+001 0. 00E 6 001 XE-135H I ci I 7.40E+001 3.45E-oil 0.00E+001 0.00E*001 1 XE-130 l Ci j 0.00E+001 4.64E.021 0.00E+001 0.00Et001 I AR-41 l Ci j 0.00E+001 9.43E-021 0.00E+001 0.00E+001 l l KR-85H l Ci 1 5.03E-041 0.00E+001 0.00E+001 0.00E+001l l l l l I I 1 Total for period Ci l 9.02E+011 1.42E+0il 0.00E+001 0.00E+001 I
- 2. Iodines l Ci 1 3.83E.041 1.23E-041 0.00E+001 0.00E+001 I I.131 I I-132 l Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1 I-133 i Ci l 2.38E-041 1.58E-051 0.00E+001 0.00E+001 1 I.134 l Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E6001 1 I-135 l Ci 1 0.00E+001 0.00E+001 0.00E4001 0.00E+001I i l I i l i
i Total for period I Ci I 6.20E.041 1.39E-041 0.00Et001 0.00E+001
- 3. Particulatec H-3 l Ci l 7.37E-011 5.83E-011 0.00E+001 0.00E+001 '
I 1 Sr-89 l C1 1 3.49E-071 3.10E-061 0.00E+001 0.00E+001 l Sr-90 i Ci l 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1 l l CO-60 l ci l 1.72E-051 3.95E-05] 0.00E+001 0.00E+001 l CS-137 i Ci l 6.30E-071 0.00E+001 0.00E+001 0.00E+001 l i CR-51 l Ci l 1.05E.041 5.51E-05] 0.00E+001 0.00E+001 i l MN-54 i ci ! 5.51E-06) 3.49E-051 0.00E+001 0.00E+001 ! Ci l 5.94E-071 1.16E-061 0.00E+001 0.00E+001 I-131 l l l 1 I-133 i ci l 2.58E.061 0.00E+001 0.00E&001 0.00E+001 l CE-144 i Ci l 8.56E-061 0.00E+00i 0.00E+001 0.00Et001 ! l CO-50 i Ci l 7.39E-071 2.62E-051 0.00E+001 0.00E+001 NA-24 l Ci l 1.54E-061 7.18E-061 0.00E+001 0.00E&001 i Ci l 2.51E-051 6.83E-041 0.00E+001 0,00E+001 i TC-99M l l CS-134 i Ci l 1.'06E.071 0.00E+001 0.00E+001 0.00Et001 i TE-59 i Ci l 0.00E+001 1.89E-061 0.00E+001l 0.00E+001l l I I I 1 l Total for period I ci I 7.37E-01) 5.84E.011 0.00E*001 0.00E+001
#'t9012/SRESCHEM.fLR-TIC - 1
l l TABLE 10 Grand Gulf Nuclear Station 1 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANAlvSIS PROGRAM Lower Lower Limit of Limit of Detection Detection Gaseous Minimum Type of Required (Worst Case) Release Sampling Analysis Activity (LLO) Capabilit . Type frequency frequency Analysis (pCi/ml)" ( Cl/ml)"y A._(1) Radwaste M M Principal 1E-04 1.5E-07 Building Grab Sample Gamma Ventilation Emitters"*" Exhaust _ H-3 1E-06 1.8E-10 (2) Fuel Continuous" W* 1-131 1E-12 6.0E-13 Handling Charcoal Area Sample Ventilation 1-133 10-10 9.0E-13 Exhaust 1 Continuous" W" Principal 1E-11 9.6E-13 (3) Containment Particulate Gamma Ventilation Sample Emitters" Exhaust (1-131, Others) (4) Turbine Continuous d M Gross Alpha 1E-11 1.8E 14 Building Composite Ventilation Particulate Exhaust Sample l Continuous" Q S r-89, IE-11 1.1E-14 Composite Sr 90 . Particulate Sample Continuous Noble Gas Noble Gases 1E-06 4.4E-07 Monitor Gross Beta or Gamma
~
l l Note: Footnotes indicated are lis 3d in GGNS Technical Specifications, Table 4.11.2.1.2-1. SRER9012/SRESCHEM.FLR-T1D - 1
TABLE 10 (Continued) Lower Lower Limit of Lintit of Detection Detection Gaseous Minimum Type cf Required (Worst Case) Release Sampling Analysis Activity (LLD) Capability Type Frequency frequency Analysis (pCi/ml)" (pCi/ml)" B. (1) Offgas Post M M Principal 1E-04 5.4E-05 Treatment Grab Sample Gamma Exhaust, Emitters" whenever there is flow (2) Standby Gas Treatment A Exhaust, wheraver there is flow (3) Standby Gas Treatment B Exhaust, whenever there is flow Note: Footnotes indicated are listed in GGNS Technical Specifications, Table 4.11.2.1.2-1. SRER9012/SRESCHEM.FLR-T1D - 2 -( - m __ . _ _ _ _ --
N E-Grand Gulf Mmiame Station JUL'I - DEC#MREE 1990 l LIQUID %FFLUENTS-EUNGTION OF ALL RELEASES l l Un:lt 1 Quarter i Quarter (Est Toto 10: 1 J 3 l 4 l En'or % 0! A. Fission & activation pecducts i 1
-l 1, Total release (not including H3, I l l I I .I gases, alpha) l C1 l 1. 65E-011 3. 76E-011 7. 30E+011:
1 2. Average diluced concentration I l l I I diaring period J uC1/ml i 2.23E-071 5.26E-071 1 3. Percent of applicable lit.it l *% l 1.10E-011 3.67E-011
- 8. ' tritium 1 1. Total release l Ci l 5.08E+001 4'.00E+001 7.00E+011, i 1. Average diluted concentration i 1 l l l
.I during period I uC1/mi_l 6.88E-061 5.59E-06l !
l 3. Percent of applicable limit l *4 l 2.29E-011 1.86E-011 C. Dissolved and entrained gases l 1. Total release l C1 l 1.4117-031 1.99E-031 6.60E+011 1 2. Average diluted concentration I l l l I during period I uC? /mi l 1. 91E-09 I 2.78E-09l 1 1 3. Percent of applicable limit t ** 1 1.91E-021 2.78E-021 D. Gross alpha radioactivity 1 1. Total release l Ci I 0.00E+001 0.00E+001 9. 5 0E+011' lE. Volume of waste (prior to dilution)l liters l 1.09E+07l 9.84E+06l S.00E+00l IF.. volume of dilution water used I liters l 7.28E+081 7.05E+081 5.00E+001'
- Percentages of applicable limit based on 10CFR20, Appendix B, Table II, Column 2. ,
SRER9012/SRESCHEM.FLR-T2A - 1
TABLE 2B Grand Gulf Nuclear Station JULY - DECEMBER 1990 LIQUID EFFLUEtJTS - CONTINUOUS AND BATCH HODES CONTI!iUOUS HODE BATCH MODE I Nuclides Released i Unit l Quarter i Quarter I Quarter 3 i1 Quartor 4 Il I j 3 l 4 1 l 1 strontium-89 i Ci l 0.00E+001 0.00E+00l 0.00E+001 0.00E+001 i strontium-90 i C1 1 0.00E+001 0.00E+001.0.00E+001 0.00E+001 I cesium-134 i Ci l 0. 00E+001 0. 00E+001 6. 58E-061 5. 47E-051 i cesium-137 i Ci 1 0. 00E+001 0. 00E *00 l 2.38E-05l 2.46E-051 l iodine-131 1 Ci 1 0.00E+001 0.00E+001 6.64E-051 0.00E+001 l cobalt-58 l Ci 1 0.00Evcol 0.00E+001 3. 38E-04 l 4. 62E-031 l cobalt-60 l Ci 1 0.00E+001 0.00E+00l 1.09E-021 5.00E-021-l iron-59 i Ci l 0,00E+001 0.00E+001 5. 40E-04 l 8.10E-0 31 l zinc-65 I ci l 0. 00E+001 0. 00E+001 0. 00C+001 7. 62E-0$ 1 l manganese-54 l Ci 1 0.00E+001 0.00E+001 2.57E-031 4.07E-021 l chromium-51 l Ci l 1.00E+001 0.00F,+001 1.36E-Oil 2.39E-021 1 zirconium-niobium-95 l Ci 1 0.00E+001 0.00E+001 0. 00E+001 9. 49E-0 51 ' molybdenum-99 l Ci 1 0. 00E+001 0.00E+00 l 6. 20E-0 51 0. 00E+00 l! I l technetium-99m i Ci l 0.00E+001 0.00E+001 4.98E-05l 2.93E-051; barium-lanthanum-140 l Ci 1 0. 00E+001 0,00E+001 0. 00E+001 0. 00E+00 l-I I l cerium-161 l Ci 1 0,00E+001 0.00E+001 0. 00E+001 0. 00E+00 l l Cu-64 I ci I 0.00E+001 0.00E+001 4.25E-94l 1.02E-031 l I-133 i Ci l 0.00E+001 0.00E+00l 1. 6 5E-051 0. 00E+0 0 l ' As-76 1 Ci 1 0.00E+00l 0.00L+001 1. 57E-031 3. 08E-041 I i Mn-56 I Ci 1 0.00E+001 0,00Es00l 0.00E+001 1.48E-05l l Ag-110m l Ci l 0. 00E+001 '0. 00E4 001 5. 0 3E-051 4. 22E-051' i Na-24 i Ci 1 0. 00E+001 0.00Ev001 5. 29E 051 1.14E-05 li l Sb-104 i Ci j 0. 00E+001 0. 00E+0 01 0. 00E+001 9.14 E-0 51. I Sr-92 l Ci l 0.00E+00l 0.00E+001 9.57E-071 1.31E-061, i Fe-55 l Ci l 0. 00E+001 0. 00E+001 1.17E-0 21 2. 47E-011 l Total for period (; hove) l Cil 0. 00E+001 0. 00E+001 1. 65E-011 3.76E-011 1 xenon-133 I Ci 1 0.00E+001 0.00E+001 6.16E-041 1.93E-031 i xenon-135 l Ci 1 0.00E+001 0.00E+001 7.98E-041 6.06E-05l SRER9012/SRESCHEM.FLR-T2B - 1 l
.- . - - - . . -- .. -- = _
TABLE 2-C Grand Gulf Nuclear Station RADIDACTIVE LIQUID WASTE SAMPLING AND ANALYSIS DROGRAM
~
Lower Lower Limit of Limit of Detection Detection Liquid Minimum Type of Required (Worst Case) Release Sampling Analysis Activity (LLD) Capability Type Frequency Frequency Analysis (pCi/ml)" (pCi/ml)"
. A. Batch P P Principal Gamma SE-07 1.6E-07 Waste Each Each Emitters" Release Batch Batch ~~~
Tanks c 1-131 1E-06 2.3E-08 P M Dissolved and 1E-05 7.1E-08 One Entrained Gases Batch /M (gamma emitters)
.P M H-3 1E- 05 4.4E-06 Each Composite' Batch.
Gross Alpha 07 3.8E-08 P Q Sr-89, Sr-90 SE-08 2.6E-08 Each Composite" . Batch Fe-55 1E-06 1.4E-07 i_ B. SSW Basin. Principal Gamma SE-07 1.6E-07 (prior to Each~ Each Emitters olowdown) Blowdown Batch I-131 1E-06 2.3E-08 l o Note: Footnotes. indicated are listed in GGNS Technical Specifications, Table 4.11.1.1.1-1. SRER9012/SRESCHEM.FLR-T2C - 1 L t 1
TABLE 3 Grand Gulf Nuclear Station JULY - DECEMBER 1990 SOLID RADIDACTIVE WASTE AND 1RRADIATED FUEL SHIPMENTE A. Solid Waste Shipped Offsite for Burial or Disposal
- 1. Type of Waste 6 nionth Estimate Total Unit Period Error, %
- a. Spent resins, filter sludges, m' 7.14E+01 oil, evaporator bottoms, etc. *Ci 1.30E+03 7.2E+01
- b. Dry compressible waste, m' 2.48E+01 contaminated equipment, etc. *Ci 1.42E+00 6.9E+01
- c. Irra victed components, control m' None N/A rods, etc. *Ci
- d. Other m' Nor a N/A
*Ci
- Total curie quantity determined by measurement. Total volume used is burial container volume.
- 2. Estimate of major radionuclide comp >1 tion (by type of waste as
. identified above),
- a. Fe-55 70%
Co-60 19% Mn-54 -9% i All Others 2%
- b. Fe-55 81.4%
Fe-59 1.1% Co-60 7.2% Mn-54 10.3% All Others 0% - c. N/A N/A
- d. N/A N/A SRER9012/SRESCHEM.FLR-T3 - 1
- - - - ~ - _ _ _ _ ~ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ , . _ _ _ _ _ _ _ _ _
TABLE 3 (CONT'D) SOLID RADI0 ACTIVE WASTE AND 1RRADIATED FUEL SHIPMENTS (cont'd)
- 3. Solid Waste Disposition
- a. Resins were dewatered in steel liners or High Integrity Containers according to the requirements of the GGNS PCP and shipped LSA, i
- b. DAW was shipped to Scientific Ecology Grou) (SEG) of Oak Ridge, TN for volume reduction. SEG slipped the compacted waste te Barnwell, SC. Compacted burial volume was used in providing information given in A.1.b.
- c. No irradiated components were shipped.
! Number of Shipments Mode of Transportation Destination i'* Truck Barnwell, SC
- Includes 14 shipments from SEG to Barnwell B. IrradiatedfuelShipments(Disposition 1 Number of Shipments Mode of Transportation Destination None N/A N/A C. Annual Sewage Sludge Summary Total Average Co-60 Average Mn-54
-Number of Shipments Gallons Activity (oCi/l) A:tivity (pCi/l) 2 76n0 59.52 28.83 SRER9012/SRESCHEM.FLR-T3 - 2
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TABLE 4A (CONT.) PERIO0 0F RECORD: 7/1/90, 000 -- 10/1/90, 000 PERCENT BAD DATA REPORT REPORT COVERS 2208 HOUR 5 H O U P. S PERCENT 50M OIREC TIO N 0. .00 SOM ~ WIND SPEED 0. .00 10M DIRECTION 20 91 10M WIND SPEED 0. .00 TEMPIRATURE 0, .00 DEW POINT 0. .00 DELTA T 0. .00 PRECIPITATION 0. .00 SRER9012/SRESCHEM.FLR-T4A - 17
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TABLE 4B (CONT.) PERIOD 0F RECORD: 10/1/90, 000 -- 1/1/91, 000 PERCENT BAD DATA R E PORT REPORT COVERS 2208 HOURS HOURS PERCENT 50M DIRECTION 0. .00 SOM WIND SPEED 0. .00 10M. DIRECTION 0. .00 10M WIND SPEED 0. . 00 TEMPERATURE 0. .00 DEW POINT 142. 6.43 OELTA T 2. .09 PRECIPITATION 0. .00 Q '9 SRER9012/SRESCHEM.FLR-T4B - 17
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TABLE 4C (CONT.) PER100 Of RECORD: 1/1/90, 000 -- 1/1/91, 000 PERCCNT BAD DATA REPORT REPORT COVER 5 8760HOURE HOURS PERCENT SOM DIRECTION 0. .00 50M WIND SPEED 0. .00 10M DIRECTION 20. .23 10M WIND SPEED 0. .00 TEMPERATURE. O. .00 DEV POINI 175. 2.00 CELTA T 0. .00 PRECIPITATION 0. .00 SRER9012/SRESCHEM.fLR-T4C - 17 l
4 f s TABLE 40 CLASSIFICATION Of A1H05PHERIC STABILITJ ti m ui, e. ..it '
.e* 7. ,.iv,. w I Clew 6f6mtion Cat H o,in
- 4%, sed enth he sht (Clicoed i E.ttremely unstable A 23.0 <- l .9 i Modersts!.y unstable B 20.0 l .9 to . l .7 S!!$tly unstabk C 15.0 .l.7 to .lJ Neutral D 10.0 .l.5 to 4J
$11$tly itable E $.0 4.5 to 1.5 Modmisly stable F 2.5 IJ to 4.0 Entremely stable C l .7 >4 .0 i
a StanLtd demtion of hontental wind dltr: tion fluctuation over a pned of 15 ininuits to I bout.The nlues shown are enragt for enh stability tlnurication, s SRER9012/SRESCHEM.fl.R-T40 - 1
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+ ATTACHMENT I ANNUAL SEWAGE DISPOSAL SumARy SRER9012/SRESCHEM.FLR - ATT I
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_ g Entergy Operwhe,ine, 8'O ika 319/s Of1S * '#3 *
- Te 60t 4.i 9360 Thomas L Reevoe, Jr.
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RECElv t:.D January 22. 1991 JAN 2 21991 Mi Eddie S. Fuente, Director Division of Radiological Health men t we M
- Hississippi State Department cf Health P. O. Box 1700 Jackson, Mississippi 39215-1700
SUBJECT:
Grand Gulf Nuclear Station Disposal of Sewage Sludge 1990 Annual Summary Report CEX0-91/ 00019 Dear Mr. Fuentet Entergy Operations, Inc. provides the attached sumary of sewage sludge shipments from the Grand Gulf Nuclear Station to the Vicksburg municipal sewage treatment lagoon between January 1, 1990 and December 31, 1990. If you need additional information, please contact Ms. R. R. Jackson at (601) 984-9366. Sincerely, bdct @. O ^ y .c w y. GHH/RRJ/smc attachment cca Mr. T. O. Hildebrandt Mr. C. R. Hutchinson File R&ES) File Central) [ 2 ] File Corporate) (All of the above w/ attachment) CIX01891/JRSFLR - 1
s ( @%e e?HH ilH l H H H H ill H H H H l H 6 H e l H H 6 H H H H H H H6HHHl H H H H H H H HlH 6 H H H6H H l H
', T fthA + 10 Mit SUNRARY REPORT OF 0006 $tt46l SLtett SIIIPEtis I YEAR tillmill6 01/01/90 Delh6 !!/31190 H H H 66 H H Hl Hill H Hil H H ililll Hil Hil HilllllilllllH H t HAeneal t H H H H H HilHAnnual ilHH H H 6 HlH 666 H ilille lH illlll H ilH 6l H shipseet icialActivity he. hte SailoH llotopt6
- ptill latersil b l 1 sternal DoH to 60 61.87 M00000 0.129164 M 0 ores 0.00217338% eru 1.467 W 0% uti 90 01 02/21/90 3B00 mn
- 4 < 39.63M000M Co 60 - 57.160MMM 0.1076290M ette 0.0017353700 ores t.07872H M uti 4 02 W/22/10 3BM nn 54 - 16.03M00000 0.235793000 oree 0.0039087530 ores 2.5457910 M sti Totalt 7.600
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