ML20094G929
| ML20094G929 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20094G925 | List: |
| References | |
| NUDOCS 9203050101 | |
| Download: ML20094G929 (26) | |
Text
,
4 Grand Gulf Nuclear Station SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT July 1 - December 31, 1991 1
Prepared By:
O. e t cuA
/ ilos lq 7
Reviewed By:
M.
MM
/ 4-/]-9 Q m.,
d 2
/.~.K-PL Approved By-
-s_
j l
I i
i 9203050101 911231 PDR ADOCK 05000416 R
PDR SRER901.2/SRREVFLR - 1 t - -- -
e TABLE OF CONTENTS SMBJECT PAGE I.
INTRODUCTION...........................................................
1.
II.
DETAILED INFORMATION...................................................
2 A.
Regulatory Limits.................................................
2 1.
10CFR20 Limits a.
Fission and Activation Gases.............................
2 b.
Radioiodines and Particulates............................
2 c.
Li q u i d E f f l ue n t s.........................................
2 2.
10CFR50, Appendix I Limits a.
Fission and Activation Gases.............................
3 b.
Radiciodines and Particulates............................
3 c.
L i q u i d E f f l ue n t s.........................................
3 3.
40CFR190 Limits...............................................
4 B.
Maximum Permissible Concentrations................................
4 1.
Airborne.....................................................
4 2.
Liquid........................................................
4 C.
Average Energy....................................................
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.
Batch Releases....................................................-
7 1.
Liquid........................................................
7-2.
Gaseous...........................-,...........................
8 F.
Unplanned Releases................................................
8 1.
Liquid........................................................
8 2.
Gaseous.......................................................
8 SRER901.2/SRREVFLR - ii
~..
TABLE OF CONTENTS (Continued)
SUR)ECT PAGE G.
Estimate of Total Error..........................................
8 1.
Liquid.......................................................
8 2.
Gaseous......................................................
9 3.
Solid Radioactive Waste......................................
9 H.
Solid Radioactive Waste Shipments................................
9 I.
Meteorological Data...............................................
9 J.
Radioactive Effluent Monitoring Instrumentation Operability.....
10 K.
Annual Sewage Disposal Summary..................................
10 III. 1991 RADIATION DOSE
SUMMARY
10 A.
Water-Related Exposure Pathways.................................
10 B.
Airborne-Related Exposure Pathways..............................
11 IV. OFFSITE DOSE CALCULATION MANUAL / PROCESS CONTROL PROGRAM /RADI0 ACTIVE WASTE TREATMENT SYSTEM CHANGES l
A.
Offsite Dose Calculation Manual (00CM)............................
12 b.
Process Control Program (PCP)....................................
12 c.
Radioactive Waste Treatment Systems.......................-.......
12
-SRER901.2/SRREVFLR - iii
LIST OF TABLES TABLE EAGE 1A Gaseous Effluents - Summation of All Releases............. lA-1 1B Gaseous Ef fluents - Elevated Releases.....................
18-1 1C Gaseous Ef fluents - Ground-Level Releases.................
10-1 10 Radioactive Gaseous Waste Sampling and Analysis Program...
10-1 2A Liquid Ef fluents - Summation of All Releases..............
2A-1 2B Liquid Ef fluents - Continuous and Batch Modes.............
2B-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 1991.......
4A-1 to 4A-17 4B Meteorological Data - October-December 1991......
4B-1 to 48-17
)
4C Meteorological Data Summary...................... 4C-1 to 4C-17 40 Classi fication of Atmospheric. Stability.... <.............
40-1
?
LIST OF ATTACHMENTS I.
Annual Sewage Disposal Summary II. Amended Table 3, January - June 1991 SRER901.2/SRREVFLR - iv
)
1.
INTRODUCTION This Semiannual Radioactive Effluent Release Report for the period of July 1 through December 31, 1991 is submitted in accordance with Section 6.9.1.8 of Appendix A to Grand Gulf Nuclear Station (GGNS) License No.
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 environment 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 (ODCM).
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 given in Tables 1B and IC, respectively.
Table ID 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 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.
Meteorological data is included in Tables 4A - 40.
Table 4D presents atmospheric stability classifications.
I SRER901.2/SRREVFLR - 1 a
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II.
DETAILED INFORMATIQN A.
Regulatory Limits 1.
10CFR20 Limits i
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:
average total body doao rate in the current year (mrem /yr)
D
=
tb X/Q I K Q
5500 mrem /yr
=
g g
average skin dose rate in the current year (mrem /yr)
D,
=.
$3000 mrem /yr X/Q I (Lg + 1.1 M ) Q g
=
g where the terms are defined in the GGNS ODCM.
b.
Radjpiodines and Particulates - The release rate limit for the sampling period for all radiciodines, tritium and radioactive materials in particulatu form with half-lives greater than 8 days shall be such that:
D, = average organ dose rate in current year (mrom/yr)
IWP h $1500 mrem /yr
=
f g
y where the terms are defined in the GGNS ODCM.
c.
Licuid Ef fluents - The concentration of odioactive materials released in liquid effluents to unrestricted areas from the reactors at the site shall not exceed at any tn n the values specified in 10CFR20, Appendix B, Table II, Col an 2.
The concentration of dissolved or entrained noble gases,. released In liquid effluents to unrestricted,grens from all reactors at the site, shall be limited to 2 x 10 microcuries/ml maximum concentration.
SRE.R901.2/SRREVFLR - 2 iV.-
2.
10CFR50, Appendix I Limits Fission and Activation Gases - The dose from noble gases in a.
gaseous-effluents to areas at or beyond the site boundary shall be such that:
D = air dose due to gamma emissions from noble gases g
~
= 3.17 x 10 I M X/Q' Q 55 mrad /qtr f g g
'510 mrad /yr D =. air dose due to beta emissions from noble gas g
~0
= 3.17 x 10 I N X/Q' Q 510 mrad /qtr g g 1
$20 mrad /yr where the terms are defined in the GGNS ODCM.
b.
Radiolodines and Particulates - The. dose to an individual from tritium, I-131, 1-133 and_ radioactive material in particulate form with half-lives greater than 8 days in gaseous ef fluents -
shall se such that:
D = dose to an individual from tritium,-I-131, 1-133 and E
radionuclides in particulate form with half-lives greater than 3 days (mrem)
~
= 3,17 x 10 IR W' Q 57.5 mrem /qtr Any Organ g
g 1
515 mrem /yr Any Organ where the terms are-defined in-the GGNS ODCM.
c.
Liguld Ef fluents - The dose from radioactive materials in 11guld offlucats shall be such that:
m-DTau " Z1]AITau g
gg At C F } 51.5-mrem /qtr_ Total Body 1
i=1 55 mrem /qtr Any Organ.
53 mrem /yr Total Body; 510 mrem /yr Any Organ where the terms are defined in' the GGNS ODCH.
SRER901.2/SRREVFLR - 3
,-..- -._ _. - - ~..... - -.. - -. -. -. - -... -. -. -.. _.
I 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 mrem /yr, Total Body or any Organ except Thyroid 575 mrem /yr, Thyroid 510 mrad T/qtr or 520 mrad T/yr, Fission and ' Activation Gases
$20 mrad D/qtr or $40 mrad D/yr, Fission and Activation Gases-
$15 mram/qtr or 530 mrem /yr, any Organ, Iodine and Particulates 53 mrem /qtr or 56 mrom/yr, Total Body, Liquid Effluents 510 mrem /qtr or $20 mrem /yr, any' Organ, Liquid Effluents-D.
Maximum Permissible Concentrations 1.
Airborne The Maximum Permissible Concentration (HPC) of radioactive 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 timited by -
-10CFR20, Appendix B, Table II, Column 2.
The MPC chosen is the most-conservative value of either the soluble or' insoluble MPC for each radioisotope.
C.
Average Energy Not applicable for GGNS RETS.
1 s
i SRER901.2/SRREVFLR - 4 e
I 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 1D and 20 give sampling frequencies and minimum detectable sensitivity requirements for the analysis of gaseous and liquid effluent streams, respectively.
Values in the attached tables given as zero do not necessarily imply that the radionuclides were not present. A zero indicates that the radionuclide was not present at levels greater than the sensitivity requirements shown in Tables 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 airborne discharges:
Ar-41 Xe-131m Kr-85m Xe-133 Kr-85 Xe-133m Kr-87 Xc-135m Kr-88 Xe-135 K r-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 1D-for sampling and-analytlenl--
requirements.) Isotopic values thus obtained are used for dose release rate calculatiot.s due to_offluent releases as given in Section II.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.
=
U1+m where C
=
isotopic calibration factor for isotope i p
SRER901.2/SRREVFLR - 5
concentration of isotope i in the grab sample in pCi/ml.
U
=
g not monitor reading associated with the effluent stream m =
(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 y
the release rates for individual radionuclides are calculated and stored. If no auv 41*: is detected in the grab sample, the calibration factor def aults to a historical mixture of Kr-88, Xe-133, Xe-135m, Xe-135, and Xe-138, 2.
For Particulates and Radiolodines The radiciodines and radioactive materials in particulate form to be considered are:
Zn-65 I-133 Cr-51 Cs-134 Mn-54 Cs-136 Fe-59 Cs-137 30-58 Ba-140 Co-60 Ce-141 Sr-89 Ce-144 Sr-90 Other radionuclides Zr-95 with half-lives Sb-124 greater than I-131 8 days.
3.
For Continuous Releases Continuous sampling is performed on the continuous release points (i.e., Rt 3 waste Vent, Containment Purge, Fuel llandling Area Vent, Turbine Building Vent).
Particulate material is collected by filtration.
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 a 2-pi gas flow proportional counter..
Strontium-89 and -90 values are obtained by chemical separation and subsequent analysis using 2 pi gas flow proportional counters. During major operational occurrences, the frequency of sampling is increased to satiafy the requirements of footnote "c" of-Table 1D, "Radior cive Gaseous Waste Sampling and Analysie," (GGNS RETS, Table 4.11.7. 2-1).
4.
For Batch Releases: Gases The processing of batch type releases (from Containment Purge) is analogous to that for continuous releases, b
SRER401.2/SRREVFLR - 6
)
1 5.
For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid effluents:
11 - 3 Mo-99 Co-58 Tc-99m Co-60 1-131 Fe-55 I-132 Fe-59 I-133 Zn-65 I-135 Mn-54 Cs-134 Cr-51 Cs 137 Sr-89 Ba-140 Sr-90 La-140 Nb-95 Cc-141 Zr-95 Co-144 Representative pre-release grab samplesLaro 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, proportionai ;o the waste volume released, are composited in accordance with the requirements of Table' 20.
Strontium determinations are made by performing a chemical separation an3 counting the separated strontium using a 2-pi gas flow l
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 sampiing techniques and then counting on the pulse height analyzer system.
E.
Batch Releases 1.
Liquid 3rd Ouarter 1991 a.
Number of batch releases: 84 b.
Total-time period for batch releases:-
25,607 minutes c.
Maximum time period for a batch release:
328 minutes d.
Average time 14eriod for batch releases:
305 minutes Minimum time period for-a batch release:
.247 minutes c.
4th Ouarter 1991 a.
Number of batch releases: 75 b.
Total time period for batch releases:
-22,722 minutes c.
Maximum time period for a batch release:
'420 minutes
_d.
Average time period for batch' releases:
303 minutes Minimum time period for a batch release:
90 minutes.
o.
SRER901.2/SRREVFLR r
2.
Gaseous 3rd & 4th Ouarter 1991 No batch releases were made during this period.-
F.
Unplanned Releases 1.
Liquid 3rd & 4th Ouarter 1991 No unplanned 11guld release occurred during this period.
2.
Gaseous 3rd & 4th Ouarter 1991 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 Tritium 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. Counting errors are based on measurements of blank samples and, for germanium detectors,-
-the Icast-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.
SRER901.2/SRREVFLR - 8
2.
Gaseous The maximum errors (not including sample line loss) are collectively estinated to be Fission &
Activation Gross Gases Iodine Particulate Alpha Tritium Sampling 32%
23%
22%
22%
23%
Measurement 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 effluents.
3.
Solid Radioactive Waste See Table 3 for error terms.
11.
Solid Radioactive Waste Shipments See Table 3 for shipment information.
I.
Meteorological Data 1.
Meteorological Data Recovery Rate' 3rd Qtr.
Parameter
%. Data Recovery 50m Wind Direction 99.64 50m Wind Speed 99.64 10m Wind Direction 99.64 10m Wind Speed 99.64 Temperature' 99.64 Dew Point-98.01 Delta T 99.64 Precipitation 99.64 SRER901.2/SRREVFLR - 9
4th Qtr.
Parameter
% Data Recovery 50m Wind Direction 99.18 50m Wind Speed 99.18 10m Wind Direction 100.00 10m Wind Speed 100.00 Temperature 100.00 Dew Point 95.88 Delta T 98.64 Precipitation 98.37 2.
Meteorological data for the period of the report is included in Tables 4A through 40.
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 1991 sewage sludge shipments.
Attachment I is the report submitted to the State of Mississippi.
III. 1991 RADIATION DOSE
SUMMARY
Indicated below is the annual summary of offsite doses attributable to GGNS during 1991.
Inspection of the values indicate that GGNS releases were within the 10CFR50,' Appendix I design objectives.
Since there are no other fuel cycle fac111 tics 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 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 ODCM.
Liquid Effluents Total body dose and-critical organ doses are computed for the maximum exposed Individual.
The maximum dose contributaan from 11guld effluents is considered to occur in the adult age group via consumption of fish.
l l
SRER901.2/SRREVFLR - 10
.-..u.-.._-,-,..-.
1991 Liquid Effluent Dose (mrem) 1st QLr 2nd Qtr 3rd Qtr 4th Qtr Total Whole Body 4.60E-02 1.24E-02 7.09E-03 1.01E-02 7.56E-02 Bone 9.84E-02 2.42E-02 2.80E-02 1.45E-02 1.65E-01 Liver 1.11E-01 4.03E-02 2.61E-02 3.35E-02 2.11E-01 Thyroid 5.67E-04 5.74E-04 4.57E-04 5.15E-04 2.11E Kidney 1.69E-02 7.12E-03 2.09E-03 7.42E-03 3.35E-02 Lung 3.72E-02 9.78E-03 1.12E-02 4.07E-03 6.23E-02 GI-LLI 1.60E-01 1.09E-01 4.21E-02 -1.53E-01 4.64E-01.
B.
Airborne-Related Exposure Pathways The values presented in this section utilize information provided in Tables 1A and IC of this report and the calculational methodology of the ODCM. Doses and dose rates are computed for locations at the alte 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 ef fluents to members of the 'public due to their activities inside the site l
boundary.
Particulate, Radiofodine 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 correspands to one of the_ two onsite_ GGNS-gardens. Pathways 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. organL dose.
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 atmospheric dispersion for an unrestricted area inside the site boundary-(ilamilton-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 reporting period.and would represent the maximum possible dose received by members of the public onsite.
SRER901.2/SRREVFLR - 11
7 Direct Radiation Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosiroter (TLD) badges located at control locations from average doses measured by TLD badges-located near the' site boundary.
1991 Airborne Effluent Dose (mrem) 1st Qtr 2nd Qtr 3r_d Qtr 4th Qtr Total Iodine, Tritium &
Particulates 1.79E-03 5.40E 4.36E-02 8.81E-01 9.80E-01 Fission and Activation Gases (Total Body dose) 2.92E-02 1.79E-01 1.21E-01 1.69E-02 3.46E-01 (Skin dose) 5.12E-02 3.21E-01 2.13E-01 3.40E-02 6.19E-01 Gamma Air dose
- 4.79E-03 9.71E-03 3.80E-03 2.40E-03 2.07E-02 Beta Air dose
- 2.93E-03 6.21E-03 3.26E-03 2.70E-03 1.51E-02.
Direct Radiation 0.2 0.2 1.8 0.1 2.3
- Measurement units are mrad IV.
OFFSITE DOSE CALCULATION MANUAL / PROCESS CONTROL PROGRAM /RADIDACTIVE WASTE TREATMENT SYSTEM CHANGES A.
Q11 site Dose Calculation Manual (LDQB]
No changes. wore made during the report period, i
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.
SRER901.2/SRREVFLR - 11
TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1991 GASEOUS EFFLUENTS _ SUMMATION OF ALL RELEASES JULY
- DECEMBER 1991 l
l Unit 1 Quarter i Quarter IEst Totall IGrand Gulf Nuclear Station UNIT 11 1
3 l
4 l Error % l A.
Fission & Activation Gases 1
1.
Total release l
Ci
! 9.11E+001 1.09E+011 6.90E+011 I
2.
Average release rate for period i uCi/sec) 1.16E+001 1.39E+001 i
3.
% of Technical specification limit I 1 7.26E-021 4.82E-021 B.
Iodines l
1.
Total iodine-131 l
Ci
! 7.49E-051 1.86E-031 7.10E+011 l
2.
Average release rate for period I uCi/ sect 9.53E-06l 2.36E-041 i
3.
% of Technical specification limit l 1 3.75E-031 9.29E-021 C.
Particulates l
1.
Particulates with half _ lives >8 daysl Ci l 7.83E-03) 6.91E-05] 6.90E+01l l
2.
Average release rate for period l uCi/ sect 9.96E-041 8.79E-061 l
3.
% of Technical specification limit l i 9.63E_021 1.06E_011 I
4.
Gross alpha radioactivity l
Ci l 1.15E-111 1.82E-08l 4
D.
Tritium 1
1.
Total release i
Ci i 1.55E+001 1.93E+001 6.60E+01l
.I 2.
Average release rate for period I uCi/ sect 1.97E-011 2.45E-011 R
l 3.
t of Technical specification limit t i 1.34E-021 1.67E-021 E.
Tritium,radiciodines and particulates i
1.
% of Technical specification limit i 1
l 1.10E-011 1.23E-011 SRER901.2/SRREVFLR - 1
. =
TABLE 1B Grand Gulf Nuclear Station JULY - DECEMBER 1991 GASEOUS EFFLUENTS - ELEVATED RELEASES (Not Applicable - GGNS releases.are considered ground level)
I 1
j saEa901.-2/saaEvrta - 1 u
TABLE 1C F
Grand Gulf Nuclear Station UNZT - 1 JULY
- DECEMBER 1991 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1991 CASEOUS EFFLUENTS _ GROUND-LEVEL RELEASE CONTINUOUS MODE BATCH MODE I Nuclides Released i Unit l Quarter I Quarter l Quarter l Quarter i 1
l l
3 1
4 1
3 1
4 1
1.
Fission gases I
KR-85 i
Ci I 4,63E-011 0.00E+001-0.00E*001 0,00Et001 i
KR-69 i
Ci 1 6.36E-011 0.00E+001 0,00E+001 0.00E+001 XE-133 i
Ci I 3.38E+001 5,63E+ col 0.00E*001 0,00E*001 i
KR-88 i
Ci i 1.38E_011 1.82E-011 0.00E+001 0.00E+001-i XE-135 i
Ci i 3.69E+001 4.43E+001 0.00E+001 0,00E+001 1
XE-138 i
Ci i 1.31E-011 2.05E-011 0.00E+001 0,00E+001 1
XE-135M i
Ci I 6.19E_011 4.80E-011 0.00E+001 0.00E+001-1 AR-41 1
Ci 1 5,77E-021 0,00E+001 0.00E+001 0.00E+001 I
l l
1 l
l l
1 Total for period i
Ci I 9.11E+001 1.09E+011 0.00E+001 0.00E+001 2.
Iodines i
I-131 l
Ci 1 7.49E-051 1.84E-031 0.00E+001-0.00E4001 1
I-132 i
Ci
'l 0.00E+001 0.00E+001.0.00E+001 0.00E+001 I
I-133 i
Ci I 4.40E-051 9.94E-041 0.00E*001 0.00Ee001 l
I-134 i
Ci 1 0,00E+001 0.00E+001 0.00E+001 0.00E+001 I-135 i
Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1
I I
l I
l l
l Total for period l
Ci 1.19E-04l 2.84E-031 0.00E+001 0.00E+001 3.
Particulates 1
Ci 1 1,55E+001 1.93E+001 0.00E+001 0.00E*001 1
Sr-89 i
Ci 1 3.84E-061 8.68E-061 0.00E+001 0.00E*001 i
Sr-90 1
Ci I 6.42E-081 0.00E+001 0.00E+001.0.00E*006 i
CO-60 1
Ci
! 8.33E-051 7.82E_061 0.00E+001 0,00E+001 MN-54 I
Cl-l 6.30E-05i 7,67E-06l 0.00E+001 0.00E+001 CO-58 I
Ci 1 4.15E-051 0.00E+001 0.00E+001 0.00E+001 I
I-131 l
Ci 1 0.00E+001 1,60E-051 0.00E+001-0.00E+001 i
I-133 I
Ci 1 0.00E+001 2.89E-051 0.00E+001
- 0. 0 0E+ 0 0.1.
TC-99M l
Ci 1 4.59E-031~0.00E+001 0.00E+001 0.00E+001
- 1 CR-51 1
Ci
) 1.67E-03):0,00E+001-0,00E+001;0.00E+001 1
AS-76 i
Ci I 4.28E-041_-0.00E+001 0,00E+001.0 00E+00i NA-24 1
C1
-l 8.47E-041 0,00E+001 0.00E+001 0,00E+00)
RU-106 i
Ci i 6.57E-051-0.00E+001 0,00E+001 0.00E+001 l-MO-99 I
Ci 1 4.49E-051 0.00E+001 0.00E+001 0.00E+001.
1 I
l l
l
(
l l Total for period i
Ci i 1.5eE*001 1.93E+001 0.00E+001 0.00E*001
- SRER901.2/SRREVFLR - 1
4 1
IMLE ID l
Grand Gulf Nuclear Station 4
l RADIDACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM
~
Lower Limit Lower Limit of Detection Gaseous Minimum Type of of Detection (Worst Cano)
Release Sampling Analysis Activity Required,(LLD)Capabiligy Typo Frequency Frequency Analysis (pci/ml)
(pci/ml)
A.
(1) Radwasto M
M Principal 1E-04 1.5E-07 Building Grab Samplo Gamma i
b.o Ventilation Emitters j
Exhaust 11 - 3 1E-06 1.8E-10 1
d c
(2) Fuel Continuoun y
I-131 1E-12 6.0E Handling Charcoal Area Samplo Ventilation I-133 1E-10 9.0E-13 Exhaust d
e Continuous y
Principal 1E-11 9.6E-13 (3) Containment Particulate Gamma Ventilation Samplo Emitters" i
Exhaust.
(1-131, Others) i d
(4) Turbino Continuoun M
Gross Alpha 1E-11 1.8E-14 Building Composit o Ventilation Particulate Exhaust Gample d
Continuoun Q
Sr-89, 1E-11 1.1E-14
' Composite Sr-90 Particulato Samplo Continuous -N$bleGas Noble Oases 1E-06 4.4E-07 Monitor Gross-Beta or Gamma Note Footnotes indicated are Ifsted in GGNS Technical Specifications, Table 4.11.2.1.2-1.
r
[
l SRER901.2/SRREVFLR - 1 L
.---_.-,r,--,'.--,-,m__m
.-,--_,,,._..m,
.--.y--_,,m....-
._,,-._,w----.m..-..,
,,----,,..-,..r-
-,--,-.,-,~,....,,,m
-.~.-. -. -,.
i j
)
1ABLE ID (Continuedl Grand Gulf Nuclear Station i
RADioAcTiyE GAstovs WAsTr. san!'1,1NG AND_ ANALYSIS _llo.rdAH
\\
l Lower Limit Lower Limit of Detection Gascous Minimum Type of of Detection (Worst Case)
Roleaso Sampling Analysis Activjty Required,(LLD)Capab111gy Typo Frequency Frequency Analysis (pci/ml)
(pCf/ml) i B.
(1) Offgas Post H-M Principal IE-04 S.92-05 Treatment Grab Sample Gamma
- Exhaust, Em i t.t o r s" whenever thero is i1.sw (2) Standby Gas Treatment A
- Exhaust, whenever thoro is flow (3) Standby Gas Treatment B l
- Exhaust, i
whenever i
thoro is flow t
i i
Note:
Footnotes indicated are listed in GGNS Technical Specifications, Table 4.11.2.1.2-1.
i SRER901.2/SRREVFLR - 2
._._,,_._,__._.-_,._...,_.2,_...__._._.__...,..__._.,,___._._.
.... _,,.. _ _.. n, _ _,., _.,_,, _,,_. _,_, _. _
TABLE 2A 1
Grand Gulf Nuclear Station JULY - DECEMBER 1991 i
- LIQUID CFFLUENTS-SUMMATION OF ALL RELCASES I
Unit i Quarter i Quarter IEst Totall l
l 3
1 4
i Error s l A.
Fission & activation products i
1.
Total release (not including H3, I
l l.
l l
i i
gaces, alpha) l Ci l 1.63E-01) 7.66E-021 7.30E+011 1 2.
Average diluted concentration i
i l
i I
during period I uCi/mi l 2.43E-071 1.33E-071 1
3.
Percent of applicable limit l
l 6.92E-021 1.71E-011 B.
Tritium i
1.
Total releace l
Ci j 4.44E+001-6.57E+001 7.00E+0)I I
- 2. Averago diluted concentration I
i I
l l
during period l uCi/mi l 6.62E-061 1.14E-051 1
3.
Percent of applicable limit l
l 2.21E-Oil'3.80E-01) i C.
Dissolved and entrained gases i
1.
Total release l
Ci 1 5. 73C-04 l
- 2. 57C-041 6.60E+011 l
2.
Average diluted concentration l
l l
l i
during period I uCi/mi l 8.56E-101 4.45E-101 4
1 3.
Percent of applicable limit I
l 8.56E-031 4.45E-031 D. Gross alpha radioac-ivity 1 - 1.
Total release l
Ci l 0.00E+001 0,00E+001 9.50E+011 5
4 IE. Volume of waste (prior to dilution)I liters l 8.90E+061 7.80E+061 5.00E+001 lF. Volume of dilution water used i liter.s l 6.61E+081 S.69E+081 5.00E+001 l
SdER901.2/SRREVFLR - 1
TABLE 2B Grand Gulf Nuclear Station JULY - DECEMBER 1991 LIQUID EFFLUENTS - CONTINUOUS AND BATCH HODES CONTINUOUS MODE BATCH MODE I
Nuclides Released i Unit i Quarter l Quarter l Quarter l Quarter I 1
l l
3 l
4 l
3 1
4 I
I strr'ntium-89 l
Ci 1 0.00E+001 0.00E+001 0.00E+001 9.01E-04l I
Ci l 0.00E+001 0.00C+001 0.00E+001 0.00E+001 l
coolum-134 i
Ci 1 0.00E+001 0.00E+00l 0.00E+001 0.00C+001 I
conium-137 i
Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1
lodine-131 l
Ci i n.00E+00l 0.00E+001 4.56E-061 0.00E+001 i
- obalt-58 i
Ci l 0.00E+00l 0.00E+001 5.10E 041 6.53E-04l I
Ci l 0.00E+00l 0.00E+00l 5.71E-031 1.11E-021 1
1ron-59 l
Ci l 0.00E+00l 0.00E+001 7.69E-051 5.64E-031 i
zinc-65 l
Ci l 0.00E+06l 0.u0C+001 0.00E+001 0.00E+001 I
Ci 1 0.00E+001 0.00E+001 4.15E-03l 1.52E-021 1
chromium-51 l
Ci l 0.00E+00l 0.00E+001-2.73E-02l 1.70E-021 l
- 1rconium-niobium-95 i
C1 1 0'.00E+00l 0.00E+001 0.00E+001 1.22E-041 l
molybdenum-99 i
Ci l 0.00E+00l 0.00E+00l 5.73E-05l 0.00E+001 l
technetium-99m l
Ci l 0.00E+00l 0.00E+001 1.88E-041 3.04E-051 l
barium-lanthanum 140 1
Ci 1 0.00E+00l 0.00E+00l 0.00E+001 0.00E+001 I
cerium-141 l
Ci l 0.00E+001 0.00E+001 0.00C+001 0.00E+001 i
Cu-64 i
Ci l 0.00E+001 0.00E+00l 8.80E-041 2.02E-041 l
I-133 i
Ci l 0.00E+001 0.00E+001 4.51E-061 0.00E+001 l
As-76 i
Ci l 0.00E+001 0.00E+00l 6.19E-04l 2.45E-051 1
'in-5 6 I
ci l 0.00E+00l 0.00E+001 0.00E+001 5.95E-061 i
Ag-110m l
Ci l 0.00E+00l 0.00E+00l 2.62E-06] 8.39E-061 l
Na-24 1
ci l 0.00E+00l 0.00E+001 2.35E-05l 9.27E-061 i
Sb-124 i
Ci l 0.00E+001 0.00E+001 0.00C+001 4.37E-051 i
Re-188 l
Ci l 0.00C+001,0.00E+001 2.48E-051 0.00E+001 1
Fe-55 l
Ci l 0.00E+00l 0.00E+00l 1.23E-011 2.57E-021 u-l Total for period (above)
I Cil 0.00E+001 0.00E+001 1.63E-01l 7.66E-021 l
xenon-133 i
Ci l 0.00E+00l 0.00E+001 7,41E-051 1.31E-041 1
xenon-135 i
Ci l 0.00E+001
- 0. 00E+001 4. 99E-04 l 1.26E-041 SRER901.2/SRREVFLR - 1
IABLE.2C Grand Gulf Nuclear Station-RADIDACTIVE L1001D WASTE SAMPLING AND ANALYSIS PROGEAM Lower Limit Lower Limit of Detection Liquid Minimum Type of of Detection (Worst Case)
Release Sampling Analysis Activity Required,(LLD)Capabiligy Type Frequency Frequency Analysis (pC1/ml)
(pCi/ml)
A.
Batch P
P Principal SE-07
-1.6E-C7 Waste Each Each Gamma d
Release Batch Batch Emitters Tanks" 1-131 1E-06 2.3E-08 P
H Dissolved IE-05 7.1E-08 One and Batch /M Entrained Gases (gamma emitters)
P M
Each Composite Batch Gross 1E-07 3.8E-08 Alpha P
Q Sr-89, 5E-08 2.6E-08 Each Composite.
Sr-90 Batch re-55 1E-06 1.4E-07 B.
SSW Basin Principal SE-07 1.6E-07 (prior to Each Each-Gamma d
~
blowdown)
Blowdown Batch Emitters I-131 1E-06 2.3E-08 Note: Footnotes indicated are listed in GGNS Technical Specifications, Table 4.11.1.1.1-1.
SRER901.2/SRREVFLR - 1
b TABLE 3 Grand Gulf Nuclear Station JULY - DECEMBER 1991 SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SilIPMENTS A.
1211d Waste Shint dML;d ';r.. -tal or Disposal 1.
Type of Waste 6-Honth Estimato Total Unit Period Error. I a.
Spent resins,.fil ter sludges,
m
- 1. 0 2 r',+ 0 2 oil, evaporator bottoms, etc.
- Ci 1.94E+03 7.2E+01 3
b.
Dry compressibin waste, m
3.70E+00 contaminated equipment, etc.
- C1 6.92E400- 6.9E401 3
m None N/A c.
Irradiated components, control rods, etc.
- C1 3
d.
Other m
None N/A-
- Ci
- Total curie quantity determined by measurement.
Total volume used in burial container volume.
2.
Estimate of major radionuclido composition (by type of waste as identified above).
a.
Fe-55 65%
Co-60 14%
Hn-54 13%
Cr-51 5%
All Others 3%
b.
Fe-55 82%
Fe-59 1%
Co-6C 6%
Mn-54 7%
Cr-51 2%
All Others 2%
c.
N/A N/A d.
N/A N/A SRER901.2/SRREVFLR - 1
. - ~ _ _
TADLE 3 (Continued)
Grand Gulf Nuclear Station JULY - DECEMBER 1991 SOLID RADIDACTIVE WASTE AND 1RRADI ATED TUEL SillPMENTS 3.
Solid Wasto Disposition a.
Resins were dewatered in steel liners or liigh integrity Containers according to the requirements of the GGNS PCp and shipped to Darnwell, SC for burial. Some resin was shipped to Scientific Ecology Group (SEG) of Oak Ridge, TN for volumo reduction.
SEG shipped reduced wasto to Barnwell, SC.
Reduced volumn was used in providing information given in A.1.a.
i b.
DAW was packaged in 20' senlands or B-25 boxes and shfpped to l
f Scientific Ecology Group (SEG) of Oak Ridge, TN for volume reduction, 4
SEG shipped reduced waste to Darnwell, SC.
Reduced volume was used in-providing information given in A.1.b.
c.
No irradiated components woro shipped.
Number of Shluments Mode of Transportation Destination 3
20 Truck Barnwell, SC l
t i
D.
Irradiated Fuel Shloments (Disposition)
Number of Shipments linde of TransportatI D Destination
?
D None N/A N/A i
l C.
Annual Seware Sludre Summarv Total Average Co-60 Average Hn-54 Number of Shioments Gallons Activity (nC1/1.1 Activity (oC1/11 0
0 0
0 r
SRER901.2/SRREVFLR - 2 i
i
---.--..-.-,,--._-.-..,.-,wv,,-c..e,.--,,---.-,.s.,--,,......wyr-,.w.e,-.m.w,,..e.3,.--v,
,_.-.,w%,..,.,e-,4
.m r..w r,.
,,w,iw..,.",..-w.,m.,-.*
m,,..,.,,,+,v.<-