ML20140E242
| ML20140E242 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/31/1996 |
| From: | Hughey W ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GNRO-97-00031, GNRO-97-31, NUDOCS 9704250166 | |
| Download: ML20140E242 (205) | |
Text
O Ent;rgy Operrtions,Inc.
hlf - PO. Box 756 Port Gbson, MS 39150 Tel 601437-6470 W.K.Hughey www Nuclear Safety & Regulatory Mas April 18, 1997 U.S. Nuclear Regulatory Commission Mail Station P1-37 Washington, D.C. 20555 Attention: Document Control Desk
Subject:
Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 1996 Grand Gulf Nuclear Station (GGNS) Annual Radioactive Effluent Release Report (ARERR)
GNRO-97/00031 Gentlemen:
Attached is the Grand Gulf Nuclear Station (GGNS) Annual
' Radioactive Effluent Release Report (ARERR). This report covers the period from January 1, 1996 through December 31, 1996.
l This report is submitted in accordance with the requirements of 10CFR50.36a (a) (2) and the GGNS Technical Specification (TS) 5.6.3. This report also complies with the GGNS Offsite Dose Calculation Manual (ODCM). Also included is the revised ODCM as required by GGNS TS 5.5.1 showing changes made to the ODCM in 1996.
If you have any questions or require additional information concerning this report, please contact Michael J. Larson at (601)437-6685, or this office.
l Yours truly, l
WKH/MJL/a s attachment: 1996 Annual Radioactive Effluent Release Report cc: (See Next Page) 9704250166 961231 1 #6 C2 ;/
l PDR ADOCK 05000416 9 yC U R PM b l 15lppppp[f5 250020
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1 April 18, 1997 GNRO-97/00031 Page 2 of 2 j i
cc: GGNS NRC Senior Resident (w/a) ,
Mr. R. B. McGehee (w/a) ]
Mr. N. S. Reynolds (w/a) ,
Mr. H. L. Thomas (w/o)
Mr. J. W. Yelverton (w/o) -
Mr. E. W. Merschoff (w/a)
Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Mr. J. N. Donohew, Project Manager (w/2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13H3 '
Washington, D.C. 20555 I
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l ENTERGY OPERATIONS, INC.
^
GRAND GULF NUCLEAR STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1,1996 - Decemher 31,1996 Prepared By: []k b / 92747 Reviewed By: // 7 m / 3-3l-9n Approved By: C. > / W la'- h 3
MMARERR9G1
1 1
TABLE OF CONTENTS SUBJECT PAGE ,
L INTRODUCTION 4 :
II. DETAILED INFORMAliON 6 A. Regulatory Limits 6 1.10CFR 20 Limits 6
- a. Fission and Activation Cases 6
- b. Radioiodines and Particulates 6
- c. Liquid Effluents 6 2.10CFR 50, Appendix I Limits 7 l
L
- a. Fission and Activation Gases 7
- b. Radiciodines and Particulates 7
- c. Liquid Effluents 7 j
- 3. 40CFR 190 Limits 8 i 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 Radiciodines 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 dwm M ARERR9G3
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i TABLE OF CONTENTS (CONT'D) l SUBJECT PAGE G. Estimate of Total Error 13
- 1. Liquid 13
- 2. Gaseous 13 i
- 3. Solid Radioactive Waste 13 l H. Solid Radioactive Waste Shipments 14
- 1. MeteorologicalData 14 J. Radioactive Effluent Monitoring Instrumentation Operability 14 K. AnnualSewage DisposalSummary 14 III. RADIATION DOSE
SUMMARY
14 A. Water-Related Exposure Pathway 14
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B. Airborne-Related Exposure Pathway 15 IV. OFFSITE DOSE CALCULATION MANUAL / RADIOACTIVE WASTE l TREATMENT SYSTEM CHANGES I 16 A. Offsite Dose Calculation Manual (ODCM) 16 i l
B. Radioactive Waste Treatment Systems 17
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LIST OF TABLES TABLE PAGE 1A Gaseous Effluents - Summation of all Releases 18 ;
IB Gaseous Effluents - Elevated Releases 20 l 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 O Attachment 1 - Liquid Radwaste Treatment System Modification 31 Q Attachment 11 - 1995 ARERR Corrected Page 43 O Attachment 111- Offsite Dose Calculation Manual, Revision 20 45 mannoa
I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 1
through December 31,1996 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. 4 1
1 Airborne discharges at GGNS are considered ground-level releases. Allliquid I and airbome 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 1
limits specified by the ODCM. l 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 ;
1 1B and 1C, respectively. Table 1D describes the radioactive gaseous sampling I
and analysis program implemented at GGNS.
The summation of allliquid releases during the reporting period is given in Table 2A, while conmious and batch mode releases are given in Table 28. Table 1
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.
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I. INTRODUCTION (CONT'D) i The annual summary of meteorological data (joint frequency distribution) will be ,
I maintained on site in a file that shall be provided to the NRC upon request. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls i Section 5.6.3.
1 1
This report contains a corrected page from the previous ARERR. The error was administrative and had no effect on the accuracy of reported data. This report contains a !
copy of Revision 20 to the GGNS ODCM.
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II. DETAILED INFORMATION A. Regulatory Limits
- 1. 10CFR 20 Limits
- a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary shall be such that:
Dtb = average total body dose rate in the current year (mrem /yr) l l
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= X/QI K Q;s g 500 mrem /yr D, = average skin dose rate in the current year (mrem /yr)
=X I(L +j 1.1 M;) Q; s 3000 mrem /yr where the terms are defined in the GGNS ODCM. j
- b. _Radioiodines and Particulates -The release rate limit for the sampling l 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 d'ii < 1500 mrem /yr i
where the terms are defined in the GGNS ODCM. l
- c. Liciuid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at l any time ten times the values specified in 10CFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x 104 microcuries/ml total activity.
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IL DETAILED INFORMATION (CONT'D)
- 2. 10CFR50, 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:
r D = air dose due to gamma emissions from noble gases
= 3.17 x 10-8 I M g X/Q'Q s5 mrad /qtr 3
s 10 mrad /yr D p= air dose due to beta emissions from noble gases 4
= 3.17 x 10 I gNgX/Q' Q, s 10 mrad /qtr 5 20 mrad /yr where the terms are defined in the GGNS ODCM.
- b. Radioiodines 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 gase'ous effluents shall be such that:
D = dose to an individual from tritium, I-131,1-133 and p
radionuclides in particulate form with half-lives greater than 8 days (mrem)
= 3.17 x 10-8 I Rg W' Q, s 7.5 mrem /qtr Any' Organ 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:
m DTau" IA iTau ott Q Fg] s1.5 mrem /qtrTotalBody i !=1 s 5 mrem /qtr Any Organ s 3 mrem /yr Total Body 510 mrem /yr Any Organ where the terms are defined in the GGNS ODCM.
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{7 DETAILED INFORMATION (CONT'D)
I':
y, . ... o 3. 40CFR190 Limits Doses are calculated for Fission and Activation Gases; Radiofodines and Particulates; and ' Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the - 3
- j. limits applied are: :
j ,
525 mrem /yr, Total Body or any Organ except Thyroid l 575 mrem /yr, Thyroid 0
s10 mrad y/qtr or s20 mrad y/yr, Fission and Activation Cases
- j. s20 mrad p/qtr or s40 mrad p/yr, Fission and Activation Gases
$15 mrem /qtr or $30 mrem /yr, any Organ, Iodine and Particulates
)
1 s3 mrem /qtr or s6 mrem /yr, Total Body, Liquid Effluents
- j. .
si0 mrem /qtr or s20 mrem /yr, any Organ, Liquid Effluents o
I 1 B. Effluent Concentrations j 4 1. Airbome i
- The Effluent Concentration Limit (ECL) of radioactive materials in gaseous effluents is limited by the dose rate restrictions given in Section II.A.1.a. In !
this case, the ECLs are actually ' determined by the dose factors in Table 2.1-1 )
- 2. Liquid The Effluent Concentration Limit (ECL) of radioactive materials in liquid .
I 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.
1 C. . Average Energy l
Not applicable for GCNS ODCM Appendix A. l I
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II. DETAILED INFORMATION (CONT'D) i D. Measurements and Approximations of Total Activity !
L The following discussion details the methods used. to measare and approximate total activity for the following:
i 1. Fission and Activation Gases 3. Particulates ,
- 2. Radiciodines 4. Liquid Effluents i
Tables 1D and 2C give sampling frequenciea and minimum detectable sensitivity i requirements for the analysis of gaseous -c i liquid effluent streams, respectively.
i Values in the attached tables given as zero do not necessarily imply that the t radionuclides were not present. A zaro 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
- I
, Kr-87 Xe-133m j Kr-88 Xe-135 Xe-133 Xe-138 4
Periodic grab samples from Station effluent streams are analyzed by a computerized pulse height analyzer system utilizing high-resolution germanium detectors.' (See Table 1D for sampling and analytical requirements.) Isotopic values thus obtained are used for dose release rate calculations due to effluent releases as given in Section 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 j is based on the effluent monitor readings. Monitors are assigned a cahbration
~
factor based upon the last isotopic analysis, using the following relationship:
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II. DETAIIJED INFORMATION (CONT'D) .
Cg =U+mg i
where ,
Cg= isotopic calibration factor for isotope i l
Ug= concentration ofisotope iin the grab sample in pCi/ml. I m = net monitor reading associated with the' effluent stream (determined at the time of grab sampling). l l
These calibration factors, along with the hourly effluent monitor values and !
flow rates, are entered into the laboratory computer where the release rates j 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.
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- 2. For Particulates and Radioiodines !
The radioiodines and radioactive materials in particulate form to be 4 considered are:
Mn Mo-99 Fe-59 l-131 Co-58 I-133 Co-60 Cs-134 Zn-65 Cs-13.7 Sr-89 Ce-141 Sr-90 Ce-144 Other radionuclides wkh half j lives greater than 8 days.
- 3. For Continuous Releases l
Continuous sampling is performed on the continuous release points (i.e.,
Offga=/Radwaste Building Vent, Containment Purge, Fuel Handling 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 radio etive 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 6,e M ARERR9G10
II. DETAILED INFORMATIO.N (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,
- " Radioactive Caseous Waste Sampling e id Analysis," (GGNS ODCM 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."
l In addition to releases from routine gaseous release points, one additional planned release resulted from operation of a temporary laundry facility during Refueling Outage 8 (October - November 1996 ). The release was evaluated as a ground level release and documented. It did not have a significant effect on the total release from the site,
- 4. For Batch Releases: Gases The processing of batch type releases (from Containment Purge) is analogous to that for continuous releases.
- 5. For Batch Releases: Liquid Effluents The radionuclides listed below are considered when evaluating liquid
- effluents:
f 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 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 dem arq/ARERR9611
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IL DETAILED INFORMATION (CONT'D) separated strontium and iron using liquid scintillation techniques. Gross alpha determinations are made using 2-pi gas flow proportional counter.
- ' Tritium is determined using distillation and liquid scintillation techniques.
Dissolved gases are determined employing grab sampling techniques and -
then counting on the pulse height analyzer rystem. Currently, Iron and Strontium analyses are performed by a qualified contract laboratory.
E. Batch Releases J
- 1. Liquid 1st 2nd 3rd 4th 1996
- Qtr Qtr Qtr Qtr TOTAL
] a. Number of releases 49 49 46 53- 197 Time Period (in minute.)
!- b. Total for all batches 14600 13892 13699 16877 l c. Max time for a batch 422 432 345 845
[ d. . Avg time for a batch 298 284 298. 318 i e. Min time for a batch 4 1 1 7
- 2. Gaseous
- No batch releases were made during the report period.
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F. Unplanned Releases
- 1. Liquid E
i No unplanned liquid releases occurred during the report period.
- 2. Gaseous Two unplanned releases occurred from the turbine building in 1996. On August 6 high winds forced open a smoke exhaust hatch. On September 26 a release occurred via an elevator shaft connecting Unit 1 and Unit 2. Each releaie ivas evaluated as a ground level release and documented. Neither release had a significant effect on the site release totals.
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IL DETAILED INFORMATION (CONT'D)
G. Estimate of Total Error
- 1. Liquid i
The maximum errors are collectively estimated to be Fission & Dissolved & 3
- Activation Tritium Entrained Cross i Products Cases Alpha l Sampling 26 % 26 % 26 % 26 % 1 Measurement 68 % 65 % 61 % 92%
TOTAL 73 % 70 % 66 % 95 % )
Sampling errors include uncertainty associated with mixing, representative n sampling and discharge volume. Measurement errors include uncertainty associated with instrument calibration and the preparation and counting of low-activity samples. Counting errors are based on measurements of blank samples and, for germanium detectors, the least-readily-detectable radioisotope. Calibration errors are calculated by summing the errors associated with the calibration of a particular instrument with a radioactive source.
i Total error is calculated by taking the square root of the sum of the squares of l the individual errors.
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- 2. Gaseous 1
The maximum errors (not including sample line loss) are collectively estimated i
to be 1
[ Fission &
Activation lodine ' Particulate Alpha Gross Products Tritium Sampling 32 % 23 % 22 % 22 % 23 %
Measurement 61 % 67 % 65 % 101% 62 %
l TOTAL 69 % 71 % 69 % 103 % 66 %
1
- Sampling errors include uncertainty associated with sample flow, vent flow and monitor calibration. 1 i j Measurement errors include uncertainty associated with instrument calibration i and preparation and counting oflow-activity samples. Measurement and total
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eriors are calculated by the same methods used for liquid effluents. !
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- 3. Solid Radioactive Waste See Table 3 for error terms.
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-__._._...._.__.-.____._______.___3 II. DETAILED INFORMATION (CONT'D) -
H. Solid Radioactive Waste Shipments ,
i See Table 3 for shipment information. ,
i I. . Meteorological Data l The annual summary (joint frequency distribution) will be maintained on site in a l file that chall 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 DisposalSummary There was no sewage disposal .in 1996.
- III. RADIATION DOSE
SUMMARY
f Indicated below is the annual summary of offsite doses attributable to GGNS during 1996.
Inspection of the values indicate that GGNS releases were within the 10CFR50, Appendix i I design objectives.
Since there are no other fuel cycle facilities within 8 km of GGNS,40CFR190 limits have l also been met during this period.
All parameters listed were calculated in accordance with the GGNS ODCM.
A. Water-Related Exposure Pathway l The values calculated in this section utilize the information provided in Tables 2A i- and 2B of this report and the calculational methodology of the ODCM.
l . Liauid Effluents L 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.
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IIL RADIATION DOSE
SUMMARY
(CONT'D) 1996 Liquid Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr TOTAL Whole Body 9.16E-03 2.05E-02 7.57E-03 3.42E-02 7.14E-02 Bone 1.08E-02 2.76E-02 1.07E-02 2.98E-02 7.89E-02 Liver 1.58E-02 3.48E-02 1.38E-02 j
5.08E-02 1.15E-01 Thyroid 3.37E-03 6.03E-03 3.74E-03 9.80E-03 2.29E-02 1
Kidney 4.37E-03 9.55E-03 4.23E-03 1.56E-02 3.37E-02 Lung 7.54E-03 1.23E-02 7.44E-03 1.26E-02 3.99E-02 Cl-LLI 4.82E-02 4.70E-02 2.87E-02 5.74E-02 7 31E-01 B. Airbome-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 beyond the site boundary provides assurance that offsite doses will not be substantially underestimated while attempting to provide an accurate dose calculation.
1 The most limiting location for a member of the public is used for the dose l calculations. I l
c Particulate, Radioiodine and Tritium i Organ dose rate from exposure to radiciodines, tritium and particulates are computed for an individual located at the site boundary. !
o I
Organ dose from exposure to radiciodines, tritium and particulates are computed ,
for an individuallocated in the southwest sector at a distance of 0.89 miles. This I 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 l 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 i calculation of organ dose and dose rate.
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III. RADIATION DOSE
SUMMARY
(CONT'D) l Noble Cases
)
Gamma and beta air dose and individual total body and skin dose rates from j exposure to a semi-infinite cloud of noble ges 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 y maximum instantaneous dose rates determined daily during the reporting period and would represent the maximum possible dose received by members of the public.
Direct Radiation a
Direct radiation dose is calculated by subtracting average doses measured by thermoluminescent dosimeter (TLD) badges located at control locations from average doses measured by TLD badges located near the site boundary. GGNS reported measured doses in 1996 as net exposure [ field reading - (transit + shield)]
normalized to 92 days. Previously, GGNS had reported measured doses as gross exposure. This reporting change did not affect the program since GGNS relies on compaiison of the indicator locations to the control as a measure of plant impact.
1995 Airborne Effluent Dose (mrem) 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr "IDTAL lodine, Tritium & Particulates 2.44E-02 3.31E-02 4.18E-02 3.57 & O2 1.35501 Fissionand ActivationGases Total Body dose, mrem /yr 3.07E02 2.45E-01 5.92E-02 6.79502 Skin dase, mrem /yr 5.86E-02 4.79501 1.13E-01 1.39501 Gamma Air dose
- 6.76E-03 1.64E-02 1.21E-02 5.3E-03 4.06E02 Beta 7.31E-03 1.83E02 1.31E-02 6.5E-03 4.52E-02 Air dose
- Direct Radiation 0 0 0 0 0
- Mensurement units are mrad IV. OFFFSITE DOSE CALCULATION MANUAI/ !
R.ADIOACTIVE WASTE TREATMENT SYSTEM CIIANGES A. Offsite Dose Calculation Manual (ODCM)
Three revisions to the ODCM were processed during the reporting period.
Changes are summarized below.
Revision 18: ,
e added Reverse Osmosis equipment to Liquid RadWaste Treatment diagram .
ametAntaasue
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. r IV.' OFFFSITE DOSE CALCULATION MANUAU RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES (CONT'D)
Revision 18:
l
. added a table showing deposition constants at the nearest residence in each meteorological sector .
l e made editorial changes to improve consistency between the Technical l Requirements Manual and the ODCM.
f Revision 19:
)
e modified sampling requirements for inoperable Offgas Pretreatment Radiation Monitor ;
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Revision 20-e
' implemented reductions in the Radiological Environmental Monitoring
]
Program j
. A complete copy of ODCM Revision 20 is included as Attachment 111.
B. Radioactive Waste Treatment Systems A reverse osmosis (RO) unit was used to treat Liquid Radwaste in 1996.
RO unit use was discontinued and all hardware subsequently removed from the plant. ODCM Specification 5.6.3.b. requires an evaluation of major changes to the Radwaste Treatment System. The evaluation is included as Attachment I.
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- TABLE 1A
.ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1
! EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 I
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES
, .................................................__ ........___ ............ ... 1 f _'
I j- JANUARt - JUNE 1996 i i l l
I 'l Unit 1 Quarter i Quarter IEr t Total 1 -)
....... ............_....... ............====__ - - . . . . . . _ . . . . . . . . . . _ . . . . . . . . . . .
IGrand Gulf Nuclear Station UNIT 11 1 1 2 i Error % ( )
. . . . . . . . . . - - - - - - - ----,... _ ................... .......... I
...._ .......... ... i A. Tission & Activation Gases 1
! I 1. Total release l C1 i 1.48E+011 3.75E+011 6.90E+011 j- l 2. Average release rate for period I uCi/ sect 1.89E+001 4.77E+001
.I 3. 4 of Technical specification limit I % i 1.35E-011 3.30E-011
, B. Iodinae' I 1. Total iodine-131 I ci i 0.00E+00l 9.49E 051 7.10E+011 I
- I 2. Average release rate for period i uC1/seci 0.00E+001 1.21E-051 t ......_........____............... ................____...............
i
- I 3. % of' Technical specification limit I % 1 0.00E+001 2.02E-021 1
C. Particulates f
( l.1. Particulates with half-lives >8 daysl C1 1 3.13E-061 1.31E-071 6.90E+011 j .........................._.............__..... ..........................__.....
l 2. Average release rate for period I uci/ sect 3.98E-071 1.67E-081
{
'....... ...a...,....... ................._...........................
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l 3. % of Technical specification limit I % 1 3.24E-041 1.43E-051 i_
1 4. Gross alpha radioactivity l C1 1 4.08E-081 2.02E-11I i ......................... ......_....._........... .................__
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D. Tritium
\ ... ......_...............__..-- _.........................._.................
-l 1. Total release i Ci l 1.73E+011 2.24E+011 6.60E+011 l I 2. Average release rate for period I uCi/ sect 2.20E+001 2.85E+001 l
l l 3. % of Technical specification limit I % l 3.25E-011 4.21E-011 l
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E. Tritium,radiolodines and particulates I 1. % of Technical specification limit I % l 3.26E-011 4.41E-011 I
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7 TABLE 1A ENTERGY OPERATIONS, INC.
( GRAND GULF NUCLEAR STATION UNIT 1 )
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 1
GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES JULY- - DECEMBER 1996 l l Unit I Quarter I Quarter IEst Totall l Grand Gulf Naclear station UNIT 11 1 3 1 4 I Error % I 4
.~.............................._-__..._........................................ l A. Tission & Activation Gases l-1. Total release i C1 1 2.64E+011 1.45E+011 6.90E+011 l-2. Average release rate for period I uC1/seci 3.36E+001.1.83E+001 l 3. % of Technical specification limit 1 % i 2.41E-011 1.07E.011 1
B. Iodines i 1. Total iodine-131 l' Ci i 1.16E-051 5,50E-041 7.10E+011 I 2. Average release rate for period I uC1/seet 1.48E-061 6.92E-051
-l 3. 4 of Technical specification limit l % i 2.62E-031 1.1SE-011 1 C. Particulates I 1. Particulates with half-lives >8 days! C1 1 6.57E-08l 2.64E.051 6.90E+011 i
l 2. Average release rate for period I uC1/seci 8.36E-09] 3.32E-061 !
I 3. % of Technical specification limit ! % i 1.36E-051 1.65E-031 i l 4. Gross alpha radioactivity l Ci i 1.41E-081 1.19E-091 l D. Tritium I 1. Total release 'l C1 1 2.91E+011 1.91E+011 6.60E+011 'l
..........u_. .............._._. ..................... ._. ...__...............
I 2. Average release rate for period i uC1/ sect 3.70E+001 2.40E+001
)
l 3. 4 of Technical specification limit I % l 5.4BE-011 3.59E-011 i l
1 E. Tritium,radiciodines and particulates
.... - =............__...._._.. ....................... _........-
l 1. % of Technical specification limit I % 1 5.51E-011 4.76E-011 I
i 1
I l
TABLE 1B ENTERGY OPERATIONS,INC.
GRAND GULF NUCLEAR STATION UNIT 1 l
JANUARY- DECEMBER 1996 l
l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 i
GASEOUS EFFLUENTS - ELEVATED RELEASES (Not Applicable - GGNS releases are considered ground-level) i I
l i
l !
l I
4 l
sn.,wqsntaanto
_. _.. _ _ .~__ _ _ . . _ _ . _ _ _ . . _. _ __ _ _ _
f s:
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TABLE 1C l- ENTERGY OPERATIONS, INC.
I GRAND GULF NUCLEAR STATION UNIT 1 j s
JANUARY-- JUNE 1996 i l
L EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 l-I i L
I GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES !
i
! CONTINUOUS MOL'E BATCH MODE
, 1 Nuclides Released- 1 Unit ! Quarter l Qunter i Quarter l Quarter l 1 I l- 1 1 2 1 1 1 2- I
...................................................._.........._...._........__. i
- 1. Fission gases !
l XE-133 I c1 I 6.93E+001 1.80E+011 0.00E+001 0.00E+00ls l KR-88 l- Ci 1 2.96E-011 6.87E-011 0.00E+001 0.00E+001 1 XE-135 I ci l'6.64E+001 1.64E+011 0.00E+001 0.00E+001 !
l XE-138 i C1 1 1.77E-011 4.12E-011 0.00E+001 0.00E+001 l l XE-135M l C1 l 7.82E 011 1.82E+001 0.00E+001 0.00E+001 l KR-85M l Ci 1 0.00E+001 1.55E.011 0.00E+001 0.00E+001 l 1 1 I l l I l Total for period i Ci i 1.40E+011 3.75E+011 0.00E+001 0.00E+001 l
.........._...............___ .............__..............__________ .... .____ 1
l' I-132 l C1 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 l I-133 i C1 1 0.00E+001 3.06E-051 0.00E+00l 0.00E+001 .
I I-134 i C1' I 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1 l~ I-135 i Ci f 0.00E+001 0.00E+001 0.00E+001 0.00E+001 j l l l I I I i j
)
i Total for period 1 C1 1 0.00E+001 1.26E-041 0.00E+001 0.00E+001 1
.......................____._.._ ................................___............ 1 l
- 3. Particulates l H+3 l C1 1 1.73E+011 2.24E+011 0.00E+001 0.00E+001 l Sr.89 l' Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1 Sr-90 l ci l 0.00E+001 0.00E+001 0.00E+001 0.00E+001 l CS-137 l C1 1 0.00E+001 1.31E-071 0.00E+001 0.00E+001 l- CO.60 1 Ci l 3.13E-061 0.00E+001 0.00E+001 0.00E+001 1 1 1 I I I l
-l Total for period I C1 1 1.73E+011 2.24E+011 0.00E+001 0.00E+001 l
4 i
I 4
i 1
- shsuMARERRS23 i
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1 i
! l l
L TABLEIC l-i ENTERGY OPERATIONS, INC.
l GRAND GULF NUCLEAR STATION UNIT 1 l 1
JULY - DECEMBER 1996 1 1
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 i
l~ i i
GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES l i
l.
CONTINUOUS MODE BATCil HQDE l i Nuclides Released i Unit i Quarter l Quarter i Quarter i Quarter l l' ...................................................................... .......
3 I I I I 1 4 1 3 1 4 l '
r J
- 1. Fission gases i XE-133 1 Ci i 1.23E+011 8.43E+001 0.00E*001 0.00E+001 l l. KR-88 1 Ci 1 5.26E-011 2.03E-011 0.00E+001 0.00E+001 j
- I XE-135 l Ci i 1.18E+011 5.23E+001 0.00E+001 0.00E+001 1 XE-138 i Ci l 3.16E-011 1.22E.011 0.00E+001 0.00E+001 j i XE-135M l C1 1 1.39E+001 5.36E.011 0.00E+001 0.00E+001 l l l l 1 1 l l Total for period l C1 l 2.64E+011 1.45E+011 0.00E+001 0.00E+00l 2.' Iodines l I-131 l Ci l 1.16E-05l 5.50E-04) 0.00E+001 0.00E+001 1 I-132. I C1 1 0.00E+001 4.45E.051 0.00E+001 0.00E+001 I l I-133- 1 C1 l 1.41E-05l 6.45E-051 0.00E+001 0.00E+001 i l I.134 I ci I 0.00E+001 0.00E+001 0.00E+001 0.00E+001 l l l I-135 i C1 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 l l i I I i i i I
'.l'..............._.....
Total for period. I C1 l 2.56E-051 6.59E-04) 0.00E+001 0.00E+001 3.'Particulates t ................................................................................
I 1 H-3 l Ci 1 2.91E+011 1.91E+01; 0. 00E+ 001 0. 00E4 001 i l Sr 89 l ci 1 0.00E400l 0.00E+006 0.00E+00l 0.00E+001 1 St-90 l Ci l 0.00E+00l 0.00E+001 0.00E+00l 0.00E+001 l 'l I-131 l _Ci l 6.57E-081 0.00E+001 0.00E+001 0.00E+001-l- MN-54 i Ci 1 0.00E+001 4.08E-061 0.00E+001 0.00E+001 l Co-60 l ci 1 0. 00E+ 001 1. 55E-051 0. 00E+ 00 l 0.00E+001 l -- l CR-51 l C1 1 0.00E+001 6.84E-061 0.00E+001 0.00E+001
! l l 1 1 I i l l Total for period l C1 1 2. 91E+011 1. 91E+011 0.00E+001 0.00E+00)
I 1
i 4
dwo-deg/ARERA96 22 i
I
d TABLE 1D ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM ,
1 l
Lower Limit of Gaseous Release Type Sampling Frequency Minimum Analysis Type of Activity Detection Frequency Analysis (LLD)
( cum!f A. (1)Radwaste Building 31 Days 31 Days Principal Ganuna lx10d Ventilation Exhaust Grab Sample (f) Emitters (b,e)
H3 lx10 d (2)Fuelllandling Area Continuous (d)(0 7 Days (c) 1 131 1x10-"
Ventilation Exhaust Charcoal Sample 1-133 lx10*
(3) Containment Continuous (d)(0 7 Days (c) Principal Gamma lx 10~"
Ventilation Exhaust Particulate Sampic Emitters (c)
(1 131, Others) i I
(4) Turbine Building Continuous (d)(0 31 Days Gross Alpha lx10-" l Ventilation Exhaust Composite Particulate Sample Continuous (d)(0 92 Days Sr-89, Sr-90 1x10-"
Composite Particulate Sample Continuous (0 Noble Gas Monitor Noble Gases lx10 d Gross Beta or Gamma B. (1) OfTgas Post Treatment 31 Days 31 Days Principal Gamma lx10 d l Exhaust, whenever Grab Sampic (O Emitters (e) there is flow ,
(2) Standby Gas !
Treatment A Exhaust, whenever there is flow (3) Standby Gas Treatment B Exhaust, whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Tabic 6.11.4-1.
dem-arvARrRR9623
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i 1
l l TABLE'2A i ENTERGY OPERATIONS,.INC.
GRAND GULF NUCLEAR STATION UNIT 1
< JANUARY - JUNE 1996 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES ,
I _____.... ______________________.__.......
l 1
i l Unit ! Quarter i Quarter IEst Totall 1 i 1. I 2 1 Error t i A. Fission & activation products l 1. Total. release (not including H3, i 1 l .
l l l gases, alpha) l C1 l 1.17E-02 8 1.13E-011 7. 30E+ 011
- 1.2. Average diluted concentration I i i i p i . during period I uC1/mi l 2.03E-071 2.97E-0/1 1 3. Percent of applicable limit I t i 1.66E-011 1.83E-011
, B. Tritium-l
[ t 1. Total release l Ci 1 4.14E+011 5.33E+011 7.00E+011 1 2. Average diluted concentration ! ! ! l l during period .
I uC1/ml i 1.17E-041 1.40E-041 l 3. Percent of applicable limit I t i 1.17E+001 1.40E+001 C. Dissolved and entrained gases
-l 1. Total release i C1 1 6.73E-OSl 1.21E-041 6.60E+011 l 2. Average diluted concentration. l l 1. l l .during period .
I uC1/ml i 1.91E-101 3.18E.101 i 3. Percent of applicable limit i t i 2.7 7E-031 4.7 3E-031 l
l- D, Gross alpha radioactivity l 1. Total release .I c1 1 0.00E+001 0.00E+001 9.50E+011 lE. Volume of waste (prior to dilution)! liters 1 5.01E+06) 4.70E+061 5.00E+001 l' IF. Volume of dilution water used I liters 1 3.48E+081 3.75E+081 5.00E+001 l
l- .1 I I
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i
TABLE 2A !
ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 JULY 4 DECEMBER 1996 I
LIQUID' EFFLUENTS-SUMMATION OF ALL RELEASES l Unit i Quarter I Quarter IEst Totall l l 3 1 4 i Error t I
'A. Fission & ectivation products.
1 1. Total release.inot including H3, 1 1 1 l l 1 gases, alpha) 1- C1 - l 9.48E-021 1.03E-011 7.30E+011 l-2. Average diluted concentration -1 I i l ,
I during period 'l uC1/ml 1 1.99E-071 2.11E-071
- l 3.' Percent of applicable limit I t i 1.01E-011 1.65E-011 B. Tritium i 1. Total release i ci . l 6.28E+011 5.89E+011 7.00E+011 1 2. Average diluted concentration l . I i i l during period I uCi/ml i 1.32E-041 1.21E-04l l l 3, Percent of applicable limit l 4 i 1.32E+001 1.21E+001 ,
t C. Dissolved and entrained gases i 1. Total release l Ci l 1.11E-041 8.86E-041 6.60E+011 l 2. Average diluted concentration i I . I I f during period i uC1/mi i 2.32E-101 1.82E-091 1 3. Percent of applicable limit i t i 3.39E-03l 2.72E-021 ,
D. Gross alpha radioactivity l 1. Total release l Ci 1 0.00E+001 0.00E+001 9.50E+011 l
lE. Volume of waste (prior to dilution)I liters i 4.63E+061 5.11E+061 5.00E+001 IF. Volume of dilution water used I liters i 4.73E+081 4.82E+081 5.00E+001
'l i
4,m-eg/ARERRS25
i TABLE 2B l ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION UNIT 1 JANUARY - JUNE- 1996 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES CONTINUOUS MODE BATCH MODE I. Nuclides Released i Unit i Quarter i Quarter i Quarter l Quarter i 1 1 1 1 1 2 1 1 1 2 i '
i strontium-89 i C1 1 0.00E+001 0.00E+001 0.00E+001 '.00E+001 l strontium-90 1 - Ci 1 0.00E+004 0.00E+001 0.00E+001 s .00E+001 i cesium-134 l Ci' I 0.00E+001 0.00E+001 0.00E+001 8.51E-061 ,
l .cosium-137 I ci I 0.00E+001 0.00E+001 0.00E+001 6.03E-051 l lodine-131 i Ci 1 0.00E+001 0.00E+001 0.00E+001 1.01E-04l '
I cobalt-58 i C1 1 0.00E+001 0.00E+001 1.87E-041 6.51E-04) l cobalt-60 l C1 1 0.00E+001 0.00E+001 1. 60E-021 1.75E-021 i fron-59 1 Ci 1 0.00E+001 0.00E+001 4.60E-051 1.12E-041 1 zine-65 I c1 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 i manganese-54 i C1 l'O.00E+001 0.00E+001 2.04E-031 1.88E-031 l chromium-51 1 C1 1 0.00E+001 0.00E+001 9.94E-031 8.27E-03)
'l zirconium-nlobium-95 -l Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 >
l- molybdenum-99 l C1 1 0.00E+001 0.00E+001 3.81E-061 0.00E+00t ,
I technetium-99m i C1 1 0.00E+001 0.00E+001 4.11E-061 0.00E+001 '
I barium-lanthanum-140 I ' Ci l 0.00E+001 0.00E+001 0.00E+001 0.00E+001 l ce rium-141 l Ci i 0.00E+001 0.00E+001 0.00E+001 3.47E-061 ;
-l- Cu-64 i C1 1 0.00E+001 0.00E+001 5.9BE-061 9.65E-061
- 1 I-133 I c1 1 0.00E+001 0.00E+001 0.00E+001 8.60E-061 I As-76 l C1 1.0.00E+001 0.00E+001 1.14E-041 0.00E+001 l Ag-110m i C1 1 0.00E+001 0.00E+004 0.00E+001 1.31E-051 l l- re-55 I Ci I 0.00E+001 0.00E+001 4.33E-02l 8.41E-021 i
l Total'for period labove) l Ci 1 0.00E+001 0.00E+004 7.17E-02l 1.13E-011 .
t l xenon-133- l C1 1 0.00E+001 0.00E+001 2.43E-051 1.02E-04l l xenon-135 I ci 1 0.00E+001 0.00E+001 4.30E-051 1.81E-051 i Xe-133m l Ci f 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1
4 7
danHni/ARERR96 26 P
t i TABLE 2B ENTERGY OPERATIONS, INC. '
GRAND GULF NUCLEAR STATION UNIT 1
!- c i ;
JULY . DECEMBER 1996 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES i
i LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES ,
______________________________________. _____ 3 CONTINUOUS MODE BATCH MODE I Nuclides Released i Unit l Quarter l Quarter ! Quarter I Quarter 1 1 i ! 3 1 4 1 3 1 4 I
( strontium-89. I Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 l l strontium-90 I c1 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 i cesium-134 I ci 1 0.00E+001 0.00E+001 0.00E+001 6.80E-051 l cesium-137 I c1 1 0.00E+001 0.00E+001 6.51E-061 4.69E-051
, i iodine-131 l Ci 1 0.00E+001 0.00E+001 1.56E-051 2.81E-04) 1 I cobalt-58 I ci 1 0.00E+001 0.00E+001 1.19E-041 1.31E-03) )
2 l cobalt-60 1 C1 1 0.00E+001 0.00E+001 1.22E-02l 2.02E-021 I iron-59 zine-65 I c1 1 0.00E+001 0.00E+001 8.73E-051 4.04E-04l 'l I 1 ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 1 1 l manganese-54 i C1 1 0.00E+001 0.00E+001 1.66E-031 3.60E-031 '
I chromium-51 l C1 1 0. 00E+ 001 0.00E+001 1. 81E-021 9.70E-031 f
I zirconium-niobium-95 i C1 1 0.00E+001 0.00E+001 0.00E+001 6.34E-061 3 I molybdenum-99 i C1 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001
- 1' technetium-99m I c1 1 0.00E+001 0.00E+001 0.00E+001 2.44E-06l i barium-lanthanum-140 i Ci 1 0.00E+001 0.00E+001 3.75E-061 0.00E+004 l cerium-141 i Ci 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 I
i l Cu-64 l 'Ci 1 0. 00E+ 001 0.00E+ 001 0. 00E+ 001 1.15E-04 l l As-76 i C1 1 0.00E+001 0.00E+001 2.89E-051 1.02E-051 1 Ag-110m 1 Ci 1 0.00E+001 0.00E4001 0.00E+001 5.41E-05l ,
- i. 1 Sb-124 I ci l 0.00E+001 0.00E+001 0.00E+001 3.00E-081 l
l Fe-55 i C1 1 0.00E+001 0.00E+001 6.26E-021 6.69E-021 l I
e 1 Total for period (abovel l Ci l 0.00E+001 0.00E+001 9.48E-021 1.03E-011
-I xenon-133 'f Ci 1 0.00E+001 0.00E+001 4.80E-051 8.55E-041
-l xenon-135 I c1 1 0.00E+001 0.00E+001 6.30E-051 3.15E-05) i l- Xe-133m i C1 1 0.00E+001 0.00E+001 0.00E+001 0.00E+001 !
.z.
dweer/ARERR9627 m . - -
TABLE 2C ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAh{
Lower Limit of Liquid Release Type Sampling Frequency Minimum Analysis Type of Activity Detection Frequency Analysis (LLD)
(pCi'ml)(af A. Batch Waste Release 4 Prior to Release Each Prior to Release Principal Gamma 5x10 Tanks (c) Batch Each Batch Emitters (d)
I-131 lx104 Prior to Release One 31 Days Dissolved and lx10
Batch /M Entrained Gases (Gamma Emitters)
Prior to Release Each 31 Days H-3 1x10~5 Batch Composite (b)
Gross Alpha lx10 4 Prior to Release Each 92 Days St-89, Sr-90 5x10*
, Batch Composite (b) l 4
- Fe-55 1x10 1
B. SSW Basin (beror, blowdown) 4 Prior to Release Each Prior to Release Principal Gamma 5x10 Blowdown Each Batch Emitters (d) 1131 lx10*
l j NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1 1.
chess-drg/ARERR9QS
1 TABLES ENTERGY OPERATIONS, INC.
GRAND GULF NUCLEAR STATION SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS ;
JANUARY- DECEMBER 1996 A. Solid Waste Shipped Offsite for Burial or Disposal 1.
Estimate Type of Waste Unit 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total Error (%)
- a. Spent resins, filter, sludges, m' l.47E+01 3.85E+01 2.31E+01 6.51E+01 !
oil, evaporator bottoms, etc. 'Ci 1.82E+02 2.43E+02 3.83E+01 2.39E+03 7.2E+01 ;
- b. Dry compressible waste, m' 3.0E-01 3.2E+00 3.6E+00 1.16E+01 contaminated equipment, etc. 'Ci 8.9E-02 1.83E+00 2.61E+01 8.56E+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 identified above) 1st Qtr '2nd 3rd 4th Qtr Qtr Qtr
- a. Fe-55 70 % 63 % 70 % 69 %
Co-60 12% 18% 17% 15%
Mn-54 9% 9% 8% 7%
Cr-51 3% 4% 2% 3%
C-14 3% 3% 1% 3%
H-3 2% 1% 1% 2%
All Others 1% 2% 1% 1%
- b. Fe-55 68 % 70 % 61 % 74 %
Mn-54 14 % 13% 18% 13% '
Co-60 12% 16% 16%- 12%
Cr-51 5% <1 % 3% <1 %
All Others 1% <1% 2% <1 %
- c. N/A N/A N/A N/A N/A d.N/A N/A N/A N/A N/A ,
denHrr/ARERR9M.9
- i TABLE 3 l ENTERGY OPERATIONS, INC. j GRAND GULF NUCLEAR STATION l
S_OLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS I
- (CONT'D)
JANUARY- DECEMBER 1996
, A. Solid Waste Shipped Offsite for Burial or Disposal (Cont'd) 1
- 3. Solid Waste Disposition
- a. Resins were dewatered in steel liners or High Integrity Containers IIEAO according to the requirements of the GGNS PCP and ,
.! shipped to Barnwell, South Carolina, for burial. Some resin was i shipped to Scientific Ecology Group (SEG) of Oak Ridge, Tennessee, for volume reduction. SEG shipped reduced waste to Barnwell, South Carolina.' Reduced resin was dewatered and shipped in i liners and High Integrity Containers (LSA). No solidification agents or l absorbents were used. j
- b. DAW was packaged in 20'sealand containers and shipped to Scientific Ecology Group !,SEG) of Oak Ridge, Tennessee, for volume reduction. SEG shipped reduced waste to Barnwell, South Carolina. Reduced volume was used in providing l information given in A.1.b. j 1
- c. No hradiated components were shipped.
- d. No waste in this category.
- Number of Shipments Mode of Transportation pestination 6 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition) j Number of Shipments Mode of Transportation Destination None N/A N/A C. Annual Sewage Sludge Summary Averane Co-60 Averane Mn-54 Number of Shioments Total Gallons Activity (oCi/l) Activity (oCi/l)
No sewage was disposed of during 1996.
a wan,5m
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ATTACHMENT I LIQUID RADWASTE TREATMENT SYSTEM I MODIFICATION '
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i During the 1996 reporting period, GGNS temporarily altered the manner in which radioactive liquid wastes were processed. The alteration involved the use of an ultrafiltration unit in conjunction with a reverse osmosis system to process selected radioactive liquid wastes at GGNf. Although this moddication was only temporary in nature, and has since been discontinued,it was considered to be a " major change" to the GGNS (liquid) Radioactive Waste Treatment System. Consequently, the following information is submitted parsuant to Section 5.6.3.b of the Grand Gulf Nuclear Station Off-Site Dose Calculation Manual:
, 5.6.3.b(1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59:
The temporary installation of vendor supplied waste processing equipment in the GGNS Radwaste Building, and the subsequent use of this equipment to process liquid radioactive wastes at GGNS, was thoroughly evaluated and reviewed in accordance with GCNS proced ures and policies, including the requirements of 10 CFR 50.59. These reviews and evaluations, which
, concluded that installation and use of the vendor supplied waste processing equipment did not represent an Unreviewed Safety Question or an Unreviewed Environmental Question, were documented and retained in accordance with applicable site directives. In summary, the following determinations were made:
UFSAR Compliance with respect to Temporary Installation of Vendor Supplied Processing Equipment -The UFSAR description of the GGNS Liquid Radwaste System includes provisions for the !
temporary installation and use of vendor sepplied waste processing equipment. As such, it was determined thtt the temporary reverse osmosis ;
system could be installed and operated in the GGNS Radwaste System provided other applicable SAR requiremerits were adequately addressed.
UFSAR Compliance with respect to Radwaste System Design and Operation - Branch Technical Position ETSB 11-1 (NRC Regulatory 4 Guide 1.143) provides guidance and controls to ensure Radwaste System I equipment will be adequate to perform its intended waste processing I functions as well as minimize the potential for radioactive material releases !
resulting from equipment malfunctions or improper system operations. The GGNS UFSAR states that Radwaste System equipment will be designed and constructed in accordance with requirements of Branch Technical Position ETSB 11-1. Based on this UFSAR commitment, it was determined that any temporarily installed vendor supplied waste processing equipment would need to meet the requirements of this design document. Any deviations or exceptions to the contents of BTP ETSB 11-1 would need to be independently evaluated, justified, and approved.
w.wmmm
5_6.3.b(1) (continued)
UFSAR Compliance with respect to Liquid or Gaseous Radioactive Effluents - The GGNS UFSAR provides an estimate of the amount of ,
Curies to be introduced into the various radioactive waste processing l systems. Based on anticipated performance of various radioactive waste treatment systems, the UFSAR also provides an estimate of the amcunt of Curies that will be released to the environment from these waste treatment j systems. While the temporary installation and use of vendor supplied liquid I waste processing equipment would not alter the amount of Curies introduced into the various radioactive waste treatment systems, reviews ;
and evaluations were completed to ensure that the amount of Curies released from these systems would not be increased or adversely altered. l Since the Off-Gas (N64) System would not be affected by installation and use of the temporary liquid waste processing equipment, it was determined that radioactive material released from the gaseous radioactive waste treatment system would not be altered. However, prior to installation and i use of the temporary liquid waste processing equipment, reviews were !
conducted to determine what changes would occur with respect to liquid radioactive effluents. It was determined that the amount of Curies released to the environment from the liquid radioactive waste treatment system would decrease as a result of using the vendor supplied waste processing equipment.
This decrease was anticipated due to two major reasons. First, it was anticipated that a decrease in the total number of gallons released to the environment would occur as a result of improved effluent water quality resulting in maximizing waste water recycling. Second, it was anticipated that any waste water released to the environment would have a reduced ;
specific radioactivity level due to improved water processing capabilities.
Based on these assessments, it was determined that temporary installation and use of the vendor supplied processing equipment would not adversely impact the quantity or quality of liquid or gaseous radiological effluents.
UFSAR Compliance with respect to Liquid or Gaseous Radioactive Releases During Postulated Accidents - The GGNS UFSAR contains a summary of the anticipated radiological conditions occurring as a result of previously analyzed (postulated) accidents, including events that could occur involving waste treatment system equipment. An evaluation of the vender supplied waste processing equipment was completed to determine potential radiological impacts resulting from postulated failures or malfunctions involving the .emporary processing equipment. Based on this evaluation, it was determined that postulated radiologicalimpacts resulting chamarvAREARAM
1 1
3 5.6.3.b(1). (continued) from the installation and or use of the Ultrafiltration Unit, the reverse !
osmosis system, and the associated support equipment necessary to use this process were adequately bounded by accident scenarios previously analyzed and contained in the GGNS UFSAR. Based on these findings, installation and use of this equipment was determined to be acceptable.
i Additional evaluations were completed to assess the installation and use of
)
a high temperature dryer vessel. These evaluations determined that the ;
potential radiologicalimpacts associated with postulated failures of the ,
high temperature dryer were significantly higher than the radiological ' 1 impacts associated with the analyzed accident scenarios contained in the l UFSAR. Based on these evaluations, it was determined that the high temperature dryer vessel could not be installed at GGNS without increasing j the potential radiological impacts associated with liquid radioactive waste .I processing activities. Consequently, the high temperature dryer was not
]
used to process radioactive liquids at Grand Gulf Nuclear Station. ;
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5.6.3.b(2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information: l The Liquid Radioactive Waste Processing System in use at GGNS consists primarily of a filter-demineralizer vessel (using powdered resin) followed by a .
demineralizer vessel (using bead form anion and cation resins). While performance of this processing equipment meets UFSAR design aspects, improvements were desired in the area of effluent water quality and solid waste generation rates. These improvements would maximize re-use of processed liquid waste and minimize the volume of radioactive liquids ultimately released to the environment. In addition, the volume of solid radioactive wastes -
generated as a result of liquid waste processing could also be minimized with the new process, thereby minimizing costs associated with liquid waste processing activities conducted at GGNS.
The temporary installation and use of an ultrafiltration unit was considered to be preferable to the existing filter demineraliurs based on two factors. First, performance of the ultrafiltration unit was expected to be superior to the existing filter demineralizers and would improve effluent water quality with respect to )
the removal of radioactive and non-radioactive suspended solids. Second, the ultrafiltration unit would not produce any " secondary" solid waste, such as the ;
powdered resin wastes generated by the existing filter demineralizer units, thus .j significant operating cost reductions were anticipated as a result of the liquid j waste processing change. i i
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L p l 5.6.3.b(2) (continued) j
(
j The temporary installation and use of a reverse osmosis system was_ considered to be preferable to the use of bead resins with respect to the removal of -
l radioactive and non-radioactive dissolved solids. The reverse osmosis system l
was also very effective in removing organic impurities from the waste stream.
By improving the removal efficiencies for these types of impurities, the effluent water quality could be improved. With improved effluent water quality, the .
j processmi water could be recycled for re-use in the plant instead of being .
dischar;;ed to the environs. In the event in-plant water inventories prevented re- )
j use of tae processed water, the improved effluent water quality would result in J minim'. zing the amount of radioactive and non-radioactive impurities l
- u!Gnately released to the environment.
L .
1 L The original design of the GGNS liquid radioactive waste treatment L system, as described in the UFSAR, includes the provision to connect and use " temporary vendor processing equipment". By using these provisions, the temporary installation and use of a reverse osmosis system was conducted in a manner that did not impact the availability or operability of :
the permanently installed liquid radioactive waste processing equipment. ,
Throughout the term of deployment of the vendor supplied liquid waste ;
processing equipment, the permanently installed liquid waste processing }
equipment was maintained and operated in a manner consistent with information presented in the GGNS UFSAR.
The temporary installation and use of a reverse osmosis system was l considered to be a viable means ofimproving GGNS's liquid waste processing capabilities. These improvements were expected to maximize ,
waste water recycling and re-use, thereby minimizing the volume of waste water ultimetely released to the environment. Use of the temporary waste processing system commenced in the first quarter of 1996. While some ,
aspects of the anticipated process improvements were realized, due to i technical difficulties with the vendor supplied equipment, the temporary j reverse osmosis project was discontinued in the third quarter of 1996. ,
5.6.3.b(3) A detailed description of the equipment, components and processes involved and the interfaces with other plant systems:
The temporary waste processing equipment installed and used during the 1996 reporting period consisted of the following components:
- Pretreatment Tank,1500 gallon capacity, used as a storage and or surge ,
volume for the temporary system.
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5.63.b(3) (c:ntinurd)
- Centrifugal Pump, approximately 200 gpm, used to supply water from the i Pretreatment Tank to the Ultrafiltration Unit. A portion of this flow was recycled back to the Pretreatment Tank resulting in a net flow rate of approximately 50 gpm in the temporary waste processing equipment.
- Ultrafiltration Unit, approximately 50 gpm flow rate with filtration capability in the sub-micron range.
- Surge Tank, approximately 500 gallon capacity, used as a storage and surge volume for wastes passing through the Ultrafiltration Unit.
- Reverse Osmosis Supply Pump, approximately 50 gpm, provided a supply of water from the Surge Tank to the reverse osmosis unit.
- Reverse Osmosis Unit, approximately 50 gpm, consisting of a double pass un!hvhich ultimately passed the permeate (clean water) to permanently installed in-plant storage tanks. Concentrated wastes were either routed to the inlet of the reverse osmosis for re-treatment purposes or were routed through temporary charcoal beds and or demineralizer vessels.
- Clean-in-Place System, a sub-system consisting of small cleaning chemical storage tanks and pumps which were periodically used to clean the internal membranes in the reverse osmosis and Ultrafiltration Unit.
- Miscellaneous Support Equipment, such as sampling connections, computer control devices, a small chilled water unit, and electrical distribution equipment were also installed on a temporary basis to support operation of the vendor supplied waste processing equipment.
- Other items were originally included in the design of the temporary reverse osmosis system, such as a secondary " tubular" reverse osmosis for processing concentrated liquid wastes, a centrifuge for solids removal, and a dryer for complete drying of solid wastes. Due to technical difficulties with system design and operation, these components were never used to process radioactive wastes at GGNS.
The above listed components were temporarily installed in the GGNS Radwaste Building. Interconnections were provided to allow permanently installed Radwaste System pumps to supply radioactive liquid wastes to the temporarily installed Pretreatment Tank. Once waste water was in the Pretreatment Tank, the temporary equipment would be used to process the waste water.
- . =caran,u6
5.6.3.b(3) (continued)
After processing was completed by the vendcr supplied equipment, the waste water was returned to permanently installed Radwaste System i storage tanks through temporarily installed interconnecting piping. By I installing the temporary system in this manner, the availability and i operability of permanently installed liquid radioactive waste processing l equipment was not altered er diminished.
The temporary waste processing equipment was installed in a manner that I allowed CGNS personnel to select either the implent equipment or the .
vendor supplied equipment to process liquid radioactive wastes. The waste l processing accomplished by the vendor supplied equipment consisted of suspended solids removal or filtration (by the Ultrafiltration Unit) followed l by removal of dissolved solids (by the reverse osmosis system). The waste water processed by the vendor supplied equipment was returned to the permanently installed Radwaste System storage tanks where the water was sampled, analyzed, and dispositioned according to final water quality.
Interfaces between the temporarily installed waste processing equipment and other permanently installed plant equipment were as follows: l
- Temporary supply and return lines were installed to allow transfer of radioactive liquid wastes to and from the vendo: supplied processing equipment. These interconnections were arranged in a manner which i did not interfere with normal processing of liquid radioactive wastes using l permanently installed waste processing equipment.
- Compressed air services from in-plant compressors were temporarily provided to the vendor supplied processing equipment. The amount of air required was insignificant with respect to total capacity of the in-plant air compressors.
- Electrical power requirements necessary to operate the vendor supplied processing equipment was provided from existing electrical distribution equipment installed in the Radwaste and Water Treatment Buildings. The in-plant electrical distribution equipment utilized for this purpose was classified as "non-safety related" dwo-ner/ARERRWC
- 1 5,6.3.b(4)' An evaluation cf the ch ngt which shows the predicted reists:s cf -
i radioactive materials in liquid and gaseous effluents and or quantity ;
[ of solid waste that differ from those previously predicted in the license j application and amendments thereto:
ihe CGNS UFSAR provides an estimate of the Curie content of various Radwaste System storage tanks. These data are based on the projected activity levels of the reactor coolant and normal operatir.,n of various plant L . systems. It was determined that the temporary installation and use of vendor supplied waste processing equipment would not impact the amount
, of Curies entering the Radwaste System storage tanks from the various j reactor plant systems. However, use of the vendor supplied waste
, processing equipment could impact the distribution of these radioactive
! impurities within the various Radwaste System storage tanks.
The wastes rejected from the Ultrafiltration Unit contained concentrated amounts of (radioactive) suspended solids and the wastes rejected from the ;
severse osmosis system had concentrated levels of dissolved (radioactive) l solids. These waste streams were to be eventually dried using a high )
temperature dryer. By concentrating and drying the (radioactive) l impurities, the amount of Curies recycled to the plant for re use and the - I number of Curies released to the environment was anticipated to decrease. .l The total amount of Curies stored and retained within the Radwaste j Building was anticipated to increau. due to the increased specific activity ,
level of the dried radioactive solids. However, this increase would be limited to the high integrity container used to store the dried solids and the ;
anticipated conditions were determined to be bounded by information I presented in the GGNS UFSAR.. )
Due to technical difficulties associated with the design and operation of the i vendor supplied waste processing equipment, GGNS never installed or used !
the high temperature dryer for processing liquid radioactive wastes. Thus, as the vendor supplied waste processing equipment generated the waste ,
streams containing concentrated amounts of -(radioactive) impurities, these j waste streams were retumed to various permanently installed Radwaste l System storage tanks. The use of temporary vendor supplied charcoal beds l and or portable demineralizer vessels removed and retained a significant -I amount of these concentrated (radioactive) impurities. However, the charcoal and resin media used in these vendor supplied vessels, along with the retained radioactive impurities, were eventually transferred into the appropriate Radwaste System storage tanks.
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'5.6.3.b(4) . (c:ntinurd)
- Since these radioactive impurities were combined with the associated filter
- media, the total waste volume was above, and specific activity levels were 1 below, the conditions anticipated to be created by use of the high .
j temperature dryer. Thus, the end result was a radioactive waste product !
- that was not significantly different from and was bounded by the -
[ ' information presented in the UFSAR.
The volume of solid radioactive wastes generated as a result ofliquid 3 radioactive waste processing was anticipated to be reduced, and may have I
- been slightly reduced, through use of the vendor supplied waste processing i
equipment. This is primarily the result of not using the pcwdered resin filter
'demineralizers However the limited flow rate and mmimal run time j
associated with the vendor supplied equipment resulted in a retum to the
- use of the in-plant powdered resin filter demineralizer. This fact, combined ,
- with the increased use of resins and charcoalin the vendor supplied vessels, ;
essentially eliminated any reductions in solid radioactive waste volumes.
In summary, use of the vendor supplied waste processing equipment may have slightly reduced the specific activity level of waste water which was returned to the plant for re-use or released from the plant as environmental ;
- liquid discharges. In addition, use of the vendor supplied waste processing l equipment may have reduced the total volume ofliquid waste released to j the environment or may have even reduced the volume of solid radioactive
- waste generated at GGNS. However, the flow rate and total run time !
- - associated with the vendor supplied processing equipment was not sufficient to process all of the waste water generated at GGNS. Thus,
[ use of the temporary waste processing equipment did not significantly i reduce or alter any of the above referenced parameters. As stated above,
- use of the temporary vendor supplied waste processing equipment has been discontinued as of the third quarter of 1996.
t 5.6.3.b(5) An evaluation of the change which shows the expected maximum i exposures to MEMBERS OF THE PUBLIC in the UNRESTRICTED i AREA and to the general population that differ from those previously l estimated in the license application and amendmer.ts thereto:
4 p
, While the maximum exposures to members of the public in the unrestricted area and to the general population are continuously monitored and are well within the allowable ranges, GGNS strives to make improvements in this area. As stated above, GGNS changed the liquid waste processing method in an attempt to reduce the total number of gallons and total number of ,
Curies associated with the environmental discharges 'of radioactive liquids. !
l Based on these objectives, the maximum exposures to members of the public in the unrestricted area and to the general population were expected i to be reduced below those conditions currently existing as a result of the l I
operation of the Grand Gulf Nuclear facility.
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! 5.6.3.b(6) A c mpari:on cf the pridictrd relrrsts' of radiorctiva mitsritle,in '
t liquid and gaseous effluents and in solid waste, to the actual releases
. for the period before when the changes are to be made:
1.. ,
, CGNS did not use the temporarily installed vendor supplied liquid waste -
- processing equipment for a sufficient period of time to establish or
' i determine the exact impact this waste processing change would have had ;
I on the release of liquid or solid radioactive materials. However, the j 4
following expectations or predictions were associated with the installation and use of the vendor supplied liquid waste processing equipment:
, Gaseous Radioactive Material Releases: As stated above, the waste l processing change was limited to liquid radioactive waste processing .
3 methodologies and equipment. Thus, there were no anticipated changes j with respect to quantity or quality of gaseous radioactive material releases. l Llauld Radioactive Material Releases: As stated above, the total
- volume of radioactive liquids discharged to F.ie environment was predicted l to be reduced as a result of the change to *.he liquid waste processing l methodologies and equipment. This reduction was anticipated to be the l
! result ofimproved water processing capebilities in the liquid radioactive '
waste treatment system, resulting in maximizing the re-use or recycling of j
- the processed radioactive liquid wastes. In addition, with the improved -
- - water processing capabilities, any waste water that required discharge due to in-plant water inventories would also be of improved quality (i.e.,
reduced radioactivity content). Consequently, in addition to the anticipated 3, reduction in the total volume of water discharged to the environment, the l specific radioactivity level was expected to be reduced for any radioactive
{: liquid wastes ultimately released to the environment.
s Solid Radioactive Material Releases: As stated above, one of the I- primary objectives for installing and using the vendor supplied liquid waste
, processing equipment was to reduce the total volume of solid radioactive
- wastes generated as a result of the current method of processing
[ radioactive liquid wastes. The predicted reductions were limited to the total volume of solid radioactive wastes, however, and there was no conemrent expectation that the total number of Curies would be reduced.
!. The current method of processing radioactive liquid wastes at GGNS j i
makes extensive use of ion exchange resins to remove the (radioactive) !
! impurities from the liquid waste stream. Powdered resins are used in GGNS's filter demineralizer vessel and bead resins are used in GGNS
- radwaste system demineralizer. The volume represented by these resins
- actually account for a major percentage of the volume ~of solid radioactive wastes generated during the liquid radioactive waste processing activity.
The primary reason for anticipating a reduction in the volume of solid radioactive wastes was based on the fact that the vendor supplied liquid waste processing equipment reduced or essentially eliminated the use of f resins to process radioactive liquids. By eliminating the volume of solid
- radioactive wastes represented by the ion exchange resins, a significant i reduction can be anticipated in the volume of solid radioactive wastes F generated by the liquid radioactive waste processing activity, w arna m e
5.6.3.b(6) (continued)
The amount of radioactivity introduced into the liquid radioactive waste treatment system is a primarily a function of reactor coolant activity, plant design, and various system leakage, and is relatively independent of the methods used to process the liquid radioactive wastes. Thus, the total amount of radioactivity introduced into the GGNS liquid waste treatment system was not expected to be altered by the temporarily installed vendor supplied waste processing equipment. However, the temporary equipment was anticipated to be more effective in removing (radioactive) impurities from the liquid waste stream. Consequently, an increase was anticipated in the specific radioactivity levels associated with the solid radioactive wastes generated during the liquid radioactive waste processing activity. The increase in specific radioactivity was anticipated to be observed primarily in radioactive impurities with long half-lives since use of the vendor supplied waste processing equipment resulted in the providing a significc.nt amount of additional time for decay of shorter lived radioactive impurities.
As stated above, due to technical difficulties associated with the vendor supplied waste processing equipment, GGNS never used the high temperature dryer to process liquid radioactive wastes. Consequently, additionalion exchange resins and charcoal filter media were used in the vendor supplied liquid waste processing equipment. Thus, the anticipated reduction in the volume of solid radioactive wastes was never realized and the anticipated increase in solid waste specific activity levels was never experienced. The volume of solid radioactive wastes generated, and the 1 associated specific activity levels, did not significantly differ from those conditions present when using GGNS's permanently installed liquid waste processing equipment. i 1
5.6.3.b(7) An estimate of the exposure to plant operating personnel as a result of the change:
l GGNS personnel reviewed the anticipated exposures to plant operating l personnel resulting from instalbtion and use of the vendor supplied liquid waste processing equipment. Sasui on this review, the vendor supplied waste processing equipment was expected to result in a net decrease in radiation exposures to operating plant personnel. The expected decrease in radiation exposure was minor, and was primarily due to an anticipated reduction in the use (and corresponding maintenance) associated with the existing radwaste system filter demineralizer vessels. In addition, the vendor supplied liquid waste processing equipment was required to be shielded as necessary to keep in-plant general area radiation levels at or near normal background radiation levels.
Howcver, the vendor supplied liquid waste processing equipment was not able to process as much liquid waste as was anticipated, thus resulting in continued use of the in-plant filter demineralizer equipment. In addition, numerous maintenance items developed with the vendor supplied liquid waste processing equipment. Considering these items, radiation exposures them-err /ARERR%-41 A
5.6.3.b(7) (ceniinued) e to operating plant personnel remained at approximately the same level as before the liquid waste processing change was implemented. Consequently,
- ' GGNS did not obtain the anticipated reduction in radiation exposures to operating plant personnel associated with installation and use of the vendor i
supplied liquid waste processing equipment.
4 5.6.3.b(8) Documentation of the fact that the change (s) was(were) reviewed and found acceptable by the Plant Safety Review Committee:
A Safety Evaluation Form (Safety Evaluation No. 95-0090-R00) was reviewed and approved by the GGNS Plant Safety Review Committee (PSRC) on February 29,1996. This Safety Evaluation was prepared and
- presented for the operation of temporary vendor supplied reverse osmosis radioactive liquid waste filtration system. Documentation of the fact that the changes were reviewed and found acceptable by the Plant Safety .
Review Committee is provided by the PSRC Chairman's signature on the referenced Safety Evaluation.
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ATTACHMENT II 1995 ARERR CORRECTED PAGE MO dwn-err /ARERR94J
Attachment II CORRECTED PAGE 1995 ARERR l
II. DLTAILEP "NFORMATION (CONT'D) l l
l H. Solid Radioactive Waste Shipments l l
See Table 3 for shipment information.
I. 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 .
l No reportable instances of inoperability occurred during the report period. I K. Annual Sewage DisposalSummary l
There was no sewage dispo salin 1995. j l
III. RADIATION DOSE
SUMMARY
Indicated below is the annual summary of offsite doses attributable to GGNS during 1995. 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 Pathways The values calculated in this section utilize the information provid.ed in Tables 2A and 2B of this report and the cakulational methodology of the ODCM.
Liouid Effluents Total body dose and critical organ doses are computed for the maximum exposed individual. The maximum dose contribution from IIquid effluents is considered to occur in the adult age group via consumption of fish.
desHrg/ARERR96 44
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ATTACIIMENT III OFFSITE DOSE CALCULATION MANUAL
- i REVISION 20 l
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T OFFSITE DOSE CALCUIATION MANUAL f
GRAND GULF NUCLEAR STATION
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GRAND GULP, UNIT 1 Revision 20 - 07/96
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Revision No. 20 Date 07/96
' CRAND GYTLF Nf7N EED STATION !
OFFsTTE DORP cAfftff ATTO N MANTTht.
SAFETY RELATED I
i EV17.TTATTON APDLIFARTT, TTY q
' 1 EAFETY EVALUATION ENVTDonafENTAL EVA7.ffATION
[ W APPLICABLE [ ] APPLICABLE
[ ] NOT APPLICABLE [ M OT APPLICABLE 4
Reviewed / Approved: >U- -
/ 7" 8" 9 b Preparer-Date i
Reviewed / Approved: Ah / 9 I 9 f%
. Reviewer Q Date Reviewed / Approved: *
/ / I 1
" Chemistry superintendent ' Date
- Reviewed / Approved:
Q ger, Plant Operations
/ 7! h bate Reviewed / Approved: b- -' '
a / 7/5C[He C)(af P t Safety R'e iew Committee Date Reviewed / Approved: /
er er\PlantOperations '/ Date i !
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i GRAND GULF, UNIT 1 i Revision 20 - 07/96
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TNTRODUC"ffGN The Offsite Dose Calculation Manual (ODCM) describes the methodology and l parameters used in the calculation of offsite doses resulting from radioactive '
liquid and gaseous effluents, in the calculation of liquid and gaseous effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological i Environmental Monitoring Program. The ODCM also contains (1) - the Radioactive ;
Effluent Controls and Radiological Enviran=ntal Monitoring Programs required by !
Technical specification (TS) 5.5.4, and Technical Requirement 7.6.3.2, i (2) i descriptions of the information that is included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by TS 5.6.2 and 5.6.3, (3) a list and graphical description of the specific
" sample. locations for the Radiological Envirnnental Monitoring Program, and (4) diagrams of the liquid and gaseous radweste treatment systems, i
l ODCM Revision 20 incorporates the following change: '
l describes reductions in the Radiological Environer.nte3 Monitoring Program as allowed by ODCM 6.12.1 BASES and USNRC RG 4.8.
The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all appl $ cable areas. Computer software to perform the described calculations will be maintained current wit.h the ODCM.
Changes to the ODCM shall be accomplished as spacified in TS 5.5.1.
Records of reviews performed fo'r changes made to the ODCM shall be retained for the duration of the_ Unit Operating License.
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GRAND GULF, IDTIT 1 ii Revision 20 - 07/96
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- j E TAPLE OF CONTENTS fi 2A21 l MANUAL APPROVAL SimxT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . i IlffRODUCTION ................................................... ii 1
TABLE OF CONTENTS .... ......................................... iii
! ~ LIST OF FIGURES ................................................ iv 1
[ LIST OF TABLES ................................................. v LIST OF REFERENCES j
............................................. vi EFFECTIVE PAGES ................................................ vii i 1.0 - LIQUID IFFLUElfr8
- 1.1 Liquid Effluent Monitor Setpoints
, 1.1.1 Liquid Radweste Iffluent Line Monitors .......... L.0-1
{ 1.2 Dose calculations for Liquid Effluents i
1.2.1 Maximum Exposed Individual Model ............... 1.0-7 l
j' 1.2.2 Dose Proje tion ................................ 1.0-0 l 1.3 Liquid Radwaste Treatment System ......................... 1.0-15
. 2.0 GASEOUS EFFLUENTS i .
j 2.1 Gaseous Effluent Monitor Setpoints 2.1.1 Continuous Ventilation Monitors ................ 2.0-1 2.1.2 Text Deleted ................................... 2.0-3 2.2 Gaseous Effluent Dose Calculations
- 2.2.1 Unrestricted Area Boundary Dose ................ 2.0-7 2.2.2 Unrestricted Area Dose to Individual ........... 2.0-9 2.2.3 Dose Projection ................................ 2.0-10b 2.3 Meteorological Model 2.3.i Atmospheric Dippersion ......................... 2.0-24 2.3.2 Deposition ..................................... 2.0-25 2.4 Definitions of Gaseous Effluents Parameters .............. 2.0-27 2.5 Gaseous Radwaste Treatment System ........................ 2.0-35 2.6 Annual Dose Comunitment ................................... 2.0-36 2.6.1 Direct Radiation Dose Measurement .............. 2.0-36 3.0 RADIOLOGICAL ENVIRONMENTAL V4NITORING ,
3.1 Sagling Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 0 - 1 GRAND GULF, UNIT 1 iii Revision 17 - 03/95
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,' APPENDIX A - RADIOLOGICAL EFFLUMMT CONTR M A-O
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j RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMS l DEFINITIOhS A-2 1.1 GASEOUS RADNASTE TREA'DEENT (OFFGAS) SYSTEM 1.2 MEMBER (s) OF THE PUBLIC j 1.3 OFFSITE DOSE CALCULATION MANUAL (ODCM) l 1.4 PROCESS CONTROL PROGRAM (PCP) q 1.5 SITE BOUNDARY j 1.6 UNRESTRICTED AREA <
l 1.7 VENTILATION EXHAUST TREA'DGENT SYSTEM j I
SURVIILLANCE FREQUENCY NOTATION (DELETED) ............................A-4 MODES OF OPERATICEI (DELETED) .........................................A-5 APPLICAEILITY (DELETED) ..............................................A-6 ADMINISTRATIVE CONTROLS ..............................................A.S 5.6.2 Annual Radiological Environmental ,
Operating Report ...........................................A-9 1
5.6.3 Annure Radioactive Effluent Re'.dase Report .............................................A-10 i
GRAND GULF, UNIT 1 iiia Revision 17 - 03/95
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92.2 LIST OF TABLES i
4 Table Title Pace
- 1.2-1 Bioaccumulation Factors................................... 1.0-9 1.2-2 Ingestion Dose Conversion Factors For Adults.............. 1.0-10 1.2-3 Site Related Ingestion Dose Commitment Factor............. 1.0-13 2.1-1 Dose Factors for Rxposure to a Semi-infinite Cloud of Noble Gases...................................... 2.0-6 2.2-la Pathway Dose Factors for LCO 6.11.4 and section 2.2.1.b........................................ 2.0-11 2.2-1b Pathway Dose Factors for LCO 6.11.4 and Section 2.2.1.b........................................ 2.0-13 2.2-2a Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b............'............................ 2.0-15 2.,2-2b Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-17 2.2-2c Pathway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-19 2.2-2d Patihway Dose Factors for LCO 6.11.6 and Section 2.2.2.b........................................ 2.0-21 2.2-3,- Controlling Receptcra, Locations and Atmospheric 2.2-3a, Dispersion Parameters for LCOs 6.11.4, 6.11.5, 2.2-3b 6.11.6 and 6.11.8.......................................... 2.0-23 2.3-1 Deleted.................................................... 2.0-26 3.0-1 Air Sampler Collection Sites.............................. 3.0-2 3.0-2 Miscellaneous Collection Sites............................ 3.0-3 3.0-3 TLD Locations............................................. 3.0-4 GkAND GULF, IDTIT 1 v Revision 17 - 03/95
. . . . . ___ _. . _ -. . m_ _.. _ _ . . . _ _ _ _ _ _ _ _ _ ._ _ _ .. ._. _ ._ _
, i i
l 1
4 QDQi I TABLE OF CONTENTS 4
4 MM'fING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIltEMENTS ..... A-12 4
6.3 INSTRUMENTATION MONITORING INSTRUMENTATION 4
6.3.9 Radioactive Liquid Effluent Monitoring j 4
Instrumentation ............................... A-13 6.3.10 Radioactive Gaseous Effluent Monitoring Instrumentation ............................... A-18 ,
6.11 RADIOACTIVE EFFLUENTS LIQUID EFF1.UENTS 6.11.1 Concentration ................................... A-29 6.11.2 Dose / Total Dots ................................. A-34 6.11.3 Liquid Naste Treatment .......................... A-36 GASEOUS EFFLUENTS 6.11.4 Dose Rate ....................................... A-37 6.11.5 Dose - Noble Gases / Total Dose ................... A-42 6.11.6 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form / Total Dose .. A-44 6.11.7 Gaseous Radweste Treatment ...................... A-46 6.11.8 Ventilation Exhaust Treatment ................... A-47 6.12 RADIOLOGICAL ENVIRONMI3rrAL MONITORING 6.12.1 MONITORING PROGRAM AND i
INTERLABORATORY COMPARISON PROGRAM .............. A-48 6.12.2 LAND USE CENSUS ................................. A-59 GRAND GULF, UNIT 1 iiib kevision 17 - 03/95
i e
i 9E.2 TABLE OF CONTENTS h I B&gfd ............................................................... A-61 6.3 INSTRUMENTATION MONITORING INSTRUMENTATION 6.3.9 Radioactive Liquid Effluent Monitoring Instrumentation ............................... A-62 6.3.10 Radioactive Gaseous Effluent Monitoring l Instrumentation .................. 4 . ...... A-62 6.11 RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS 6.11.1 Concentration ................................... A-63 6.11.2 Dose / Total Dose ................................. A-63 6.11.3 Liquid waste Treatment .......................... A-66 GASEOUS EFFLUENTS 6.11.4 Dose Rate ....................................... A-66
. 6.11.5 Dose - Noble Gases / Total Dose ................... A-67 6.11.6 Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form / Total Dose .. A-69 6.11.7/ Gaseous Radweste Treatment and Ventilation 6.11.8 Exhaust Treatment ............................... A-71 6.12 RADIOLOGICAL ENVIROBOSNTAL MONITORING 6.12.1 MONITORING PROGRAM AND INTERLABORATORY COMPARISON PROGRAM .............. A-72 6.12.2 LAND USE CENSUS . ............................... A-73 GRAND GULF, UNIT 1 iiic Revision 17 - 03/95
i Q2G21 LIST OF FIGURES Ficure Title Pace 1.0-1 Example Calibration Curve for Liquid Effluent Monitor..... 1.0-6 1.3-1 Liquid Radwarte Treatment System........................... 1.0-16 l 2.3-1 Plume Depletion Effect for Ground-Level Releases.......... 2.0-31 2.3-2 Vertical Standard Deviation of Material in a Plume........ 2.0-32 2.3-3 Relative Deposition for Ground-Level Releases.............. 2.0-33 2.3-4 Open Terrain Recirculation Factor...................... .. 2.0-34 2.5-1 Gaseous Radweste Treatment System. . . . . . . . . . . . . . . . . . . . . . . . . 2. 0- 3 5e 3.0-1 Collection Site Locations, 0-5 Mile Area Map.............. 3.0-7 3.0-2 Collection Site Locations, General Area Map, 4 0-10 Mile Area Map.............. ......................... 3.0-8 1
i GRAND GULF, UNIT 1 iv Revision 17 - 03/95
92521
! LIST OF REFERENT *ES
- 1. Boegli, T. S., R.'R. Bellamy, W. L. Britz, and R. L. Waterfield,
" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133 (October 1978).
2
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor
- Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, U.S. NRC Regulatory Guide 1.109 (March 1976).
l 3. Calculation of Annual Doses to Man from Routine Releases of Reactor
. Effluents for the Purpose of Evaluating Compliance with 10CFR50,. Appendix I, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977).
a l 4. " Environmental Report,* Mississippi Power and Light Company, Grand Gulf Nuclear Station, Units 1 and 2.
+ 5. " Final Safety Analysis Report," Mississippi Power and Light Company, Grand i
Gulf Nuclear Station.
) 6. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effhants in Routine Releases from Light - Water - Cooled Reactors, U.S.
NRC Regulatory Guide 1.111 (March 1976). ,
1
- 7. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents'in Routine Releases from Light - Water - Cooled Reactors, U.S.
NRC Regulatory Guide 1.111, Rev. 1 (July 1977).
- 8. 'ge-Specific
+ Radiation Dose Conenitment Factors for a One-Year Chronic Intake, NUREG-0172, November 1977, i
- 9. EER 93-6246 "X/Q and D/Q Atmospheric Dispersion and Deposition , Factors".
- 10. NPE Calculation #XC-Q1111-G4002, Revision 0.
GRAND GULF, UNIT 1 vi Revision 17 - 03/95
. - - ~. - . . . . . ~ ~ . . . . - . . _ . ~ . . . , , . .. . . .,
i l
i DDCM LTET OF kmC_-i-iVE DAt:FC i PAGE REV PAGE MGL MIL , REV MCL ECL.
i 20 11 2.0-16 17 20 2.0-17 iii 17 17 iiia 2.0-18 17 17 2.0-19
, .iiib 17 17 liic 2.0-20 17 a
' 17 2.0-21 iv -
17 17 v 2.0-22 17 17 2.0-23 18 2.0-23a 17-vi 2.0-23b 17 17 2.0-24 vii 20 17 viia 2.0-25 17 20 2.0-26 1.0-1 17 17
! ~ 1.0-2 2.0-27 3 17 2.0 28 1.0-3 17 5 1.0-4 2.J-29 3 15 2 0-30
- 1.0-5 17 3 1.0-6 2.0-31 15 15 2.0-32 1.0-7 17 15 1.0-8 2.0-33 15 17 2.0-34 1.0-9 11 15 1.0-10 2.0-35 17 0 2.0-35a i 1.0-11 8 ;
11 2.0-36 1.0-12 0 20 .
1.0-13 2.0-37 20 2 !
!. 1,0-14 11 1.0-15 3.0 1 17 18 3.0-2
, 1.0-16 18 20 3.0-3 20 2.0-1 3.0-3a 29 17 2.0-2 17 2.0-3 3.0-4 20 l
' 2 3.0-5
'2.0-4 12 3.0-6 20 2.0-5 12 20 l 2.0-6 3.0-6a 20
' 0 3.0-6b 2.0-7 17 13 2.0-8 3.0-6c 20 17 3.0-6d 4 2.0-9 17 20 3,0 7 1
2.0-10 17 3.0-8 20 !
- 2.0-10m 17 20 2.0-10b 17 2.0-11 17 2.0-12 17 2.0-13 17 2.0-14 17
- 2.0-15 17 i GRAND GULF, UNIT 1 vii Revision 20 - 07/96
, . .-. - .. -. . . - - . ~ _ . . ._. ._. . -
QDCtf LIST OF EFFEC."fIVE PAGES PAGE REV PAGE REV MD MCL MCL 2EL.
Anpandix A A-0 17 A-34 '17 A-1 17 A-35 17 A-2 17 A-36 17 A-3 17 A-37 17 A-4 17 A-38 17 A-5 -
17 A*39 17 '
A-6 17 A-40 17 A-7 17 A-41 17 A-8 17 i A-42 17 A-9 17 i
' A-43 17 A-10 17 A-44 17 A-11 17 A-45 17 A-12 17 A-46 17 A-13 18 A-47 17 A-16 17 A-48 17 A-15 17 A-49 17 A-16 17 A-50 20 A-17 18 A-51 20 A-18 17 A-52 20 A-19 17 A-53 20 A-20 19 A-54 20
-A-21 17 A-55 17 A-22 17 A-56 17 A-23 +
17 A-57 17 A-24 18 A-58 17 A-25 18 A-59 20 A-26 18 A-60 20 A-27 18 A-61 17 A-28 17 A-62 17 A-29 17 A-63 17 A-30 17 A-64 A-31 17 17 A-65 17 A-32 17 A-66 A-33 17 17 A-67 17 A-68 17 A-69 17
. A-70 17 A-71 17 - ,
A-72 17 A-73 17 A-74 17 GRAND GULF, UNIT 1 viia Revision 20 - 07/96
1.O LIOUTS EFFLUENTS 1.1 Lisuid Effluane Monitor Setooints l 1.1.1 Lieuid Radwaste Effluent Line Monitors Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding ten times the concentration limits specified in 10CFR20, Appendix 3, Table 2, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of LCO 6.3.9, the alarm / trip i l
setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:
ef s C F+f (1) where l C= can times the effluent concentration limit (LCO 6.11.1) {
implementing 10CFR20 for the site, in pCi/ml.
e= The setpoint, representative of a radioactivity concentration in pCi/ml, of the radioactivity monitor measuring the radioactivity in the waste tank effluent line prior to dilution and subsequent releases the l setpoint, which is inversely proportional to the volumetric flow of the effluent line and directly proportional to the volumetric flow of the dilution stream plus -the waste tank effluent stream, represents 1 a value which, if exceeded, would result in concentrations exceeding ten times the limits of f 10CFR20 in the unrestricted area, 1
1 GRAND GULF, UNIT 1 1.0-1 Revision 17 - 03/95
i f= the waste tank effluent flow setpoint as measured at i the radiation monitor location, in volume per unit time, but in the same units as F, below.
F= the dilution water flow setpoint as measured prior to i i
- the release point, in volume per unit time.
4 At Grand Gulf Unit 1, the available dilution water flow (F) ,
e should be constant for a given release, and the waste t ek ;
i I flow (f) and monitor setpoint (c) are set to meet the condition of equation 1 for a given effluent concentration, C. The method by which this is accomplished is as follows:
Step 1) The isotopic concentration for a waste tank to be released is obtained from the sum of the measured concentrations as determined by the analysis required in ODCM Table 6.11.1-1:
4 e
Ec i g=gtcg+ c, + tc, a
+ c g +c g (2) where:
EC = the sum of concentrations C of each measured gamma I
- gg 9 j emitter observed by gansna-ray spectroscopy of the waste sangle.
3 c, = the concentration C,of gross alpha emitters in ,
i liquid waste'as measured 1n the monthly composite sasple.
I,C, = the measured concentrations of Sr-89 and Sr-90 in l liquid waste as obssrved in the quarterly composite
- sample . .
4 4
1 1
1
\
4
~
GRAND GULF, UNIT 1 1.0-2 Revision 17 - 03/95
1 4
C = the measured concentration of H-3 in liquid waste as determined from analysis of the monthly composite sample, 4
Cg = the concentration of Fe-55 in liquid waste as measured in the quarterly composite sample.
The C term will be inePeded in the analysis cf each waste
' tank batch to be released; terms for alpha, strontiums, tritium and iron are included if analysis of liquid waste has shown the presence of these isotopes.
4 Step 2) The measured radionuclide concentrations are used to
, calculate a Dilution Factor, D.F., which is the ratio of
, total dilution flow rate to waste tank effluent flow rate required to assure that can tiraes the limiting cancantration j of 10CFR20, Appendix B, Table 2, Column 2 are met at the point of discharge.
D.F. = [E i ) x S.F.
i EC g C C C C C i = [E 9+ "+E s, __
t, fj x g , y ,- (3) g EC IC, a EC, EC LC g g g where:
Cg = C , C,, C,, Ct and C g; measured concentrations as Terms C,, C,, C 1
defined in Step 1.
t "" f"
- included in the calculation as appropriate.
d t
1 . .
- GRAND GULF, UNIT 1 1.0-3 Revision 17 - 03/95 i
4 EC EC , EC,, EC,,Ect and EC g- g are ten times the limiting concentrations o1! the appropriate s
ra.dionuclide from 10CFR20, Appendix B, Table 2, J
Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.
- S.F - an administrative safety factor normally applied 1
at Grand Gulf which causes the calculated Dilution l Factor to be two (2) times larger than the dilution factor required for compliance with ten times 10CFR20 limits.
4 Step 3) The maximum permissible waste tank effluent flow rate prior to dilution, f ' ** "" * * *** "* ** #***' "
d the dilution flow rate, F' d
F + f F l f
d* D.F.
D.F.
d "" d (
where:
F = 9x mum expected dilution flow rate d
f " *** ** * ""* * * "*" # #"
- d j D.F. - Dilution Factor from Step 2.
NOTE: Equation 4 is valid only for D.F.>1; for D.F.si, the waste tank effluent concentration meets the limits of ten times the limiting concentrations of 10CFR20 without dilution, and f may take on any desired value.
d Step 4) The dilution flow rate setpoint for minimum dilution flow rate, F, and waste tank flow rate setpoint for maximum waste tank effluent flow rate, f, are calculated as follows:
F= Fd = 0.9 x minimum expected dilution flow rate (5) f=
0.9 x fd = 0.9 x calculated maximum waste tek flow rate for the stated release conditions. (6)
GRAND GULF, UNIT 1 1.0-4 Revision 15 - 01/94
- - .. - - . - . . - . . _- -. . - - . .- - .. - . . - - - _ ~ _
f Thus, if instrumentation indicates the dilution flow rate
- falls below the assumed flow rate of 90 percent of the
~
actual dilution flow, or if the waste tank effluent flow l
- rate exceeds 90 percent of the calculated maximum waste tank I effluent flow rate, the release is terminated (manually or ,
1 automatically).
] l Step 5) The radioactivity monitor secpoint may now be specified basea on the valusa cf cgg C , F, and f which were specified to provide compliance with ten times the limits of 10cFR20, Appendix B, Table 2, column 2. The monitor response is primarily to g= - radiation; therefore, the actual setpoint is based on I cg . The setpoint concentration, c ,, is determined as follows:
- f !
c* d EC (7)
=
f g 9 (gci/ml) a where f, is the actual (or maximum expected) waste tank eff?.uent flow rate. The value of c , (gci/ml) is used to determine the monitor setpoint (CPM) from a calibration curve similar to ODO( Figure 1.0-1.
NOTER Sef.yp.St adjustments are not required if the existing setpoint corresponds to a lower count rate than the calculated value. The actual monitor setpoint is determined from the measured concentration plus background for the detector. The setpoint contains a factor of conservatism, even if t'he calculated maximum waste tank flow rate is attainable, since the calculated rate contains the safety factor margin, waste tank effluent flow rate margin, and the dilution flow rate margin.' In practice, the actual waste tank offluent flow rate normally is many times less than the calculated tank flow rate, thus providing an additional conservatism during release.
GRAND GULF, UNIT 1 1.0-5 Revision 17 - 03/95 e
4
._ , - - - _ - - - - _ . . - _ _ . . . - _ - . - - - - - - - - - - - . ~ - - - - ~ - - - - - - - - ~
f i
Pierura 1.0=1 m*== la t'*miibeneion Neve f er Limild Rf fluant > tan 4 ter i
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m .__ -_ -
_% ..= u..,. i. .
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,, i1 1 i i i ii 1 1 i i iiiin c.- .
"E i
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i 1 i i t i i ii 1 1 i 1 1 m i
%. . .6 f ~_=,
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' $thKid EEPsJ : : i@M& -5= :
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r iii eo i sr.w *" -i i ,
zum wri -
a =- -1 i t i t.. m-H "
_ t. :.f..f' " {yi: 1- E 4.l . j H= 1 -
- IT4-Fi_: ~5f m.- 1 e---- ........n . . . m.p.=. .
3-t}. ..} . . p_._..
_ _ . - %_ _. . .. ._4. _ . 9_ ... .
! Z. il- __ - )j ..: ..O!!!.
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. . . i 15g ; ,,,1, ; ; -- .
1 . ..
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10 j;;11. . j.
10 Count Rate (Counts per Minute)
I 4
GRAND GULF, UNIT 1 1.0-6 Revision 15 - 01/94
1,2 Dose Calculations for Lieuid Effluents
) 1.2.1 Mari= = Exoosedrindividual Model I The dose contribution to the maximum exposed individual from i
all radionuclides identified in waste tank liquid effluents released to unrestricted areas is calculated for the purpose of implementing LCO 6.11.2, 6.11.3, and.TS 5.6.3 using the following expression:
m (1)
D At t C F) (millirem) (e)
Tau"fI iTau g[1 if g wheres A = Site-related ingestion dose commitment factor for iTau radionuclido 1, in millirem /hr per pCi/ml.
4 d
=K U BF gDF g F
]
Att = length of the time period over which Cgg and Fg ara i averaged for all waste tank liquid releases, in i
hours.
C il ;
= average e ncentration of radionuclide i observed in the undiluted waste tank liquid effluent during time period at fr m any liquid release from the t
waste tank, in pCi/ml. Concentrations are determined primarily from a gansna isotopic analysis l of the waste tank liquid effluent sample. For ,
Fe-55, Sr-89, Sr-90, H-3, the last measured value i l from the most recent monthly and quarterly composite- !
samples will be used in the dose calculation.
1 4 NOTE: LLD values are not used in dose calculations.
4 1
4 GRAND GULF, UNIT 1 1.0-7 Revision 17 - 03/95
. _ . _ . . __ ._ _ _ _ _ _ . _ ___ __ _. __ . _ _ . _ _ _ _ _ . _ _ _ . ~ . _ _ _
Fg = near field average dilution factor for Cgg during any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during i
release to the product of the average flow from the site discharge structure to unrestricted receiving waters times the applicable. factor of 2(II .
i
= averaae undiluted lianid waste flow average flow from site discharge x 2
- K = units conversion factor 1.14 x 10'
= 10 ggi x 10 31 + 8766 hg pC1 kg yr I
(3) 2 U, = adult fish consumption (21 kg/yr) .
EF g = Bicaccumulation factor for each nuclide, i, in fish, in pCi/kg per pCi/1 from ODCM Table 1.2-1.
DF g = Dose conversion factor for each nuclide, i, for i adults in preselected organ, Tau, in mrom/pci, from ODCM Table 1.2=2.
Calculated values of A f r radionuclides which might be Tau observed in liquid effluents are given in ODCM Table 1.2-3.
j 1.2.2 Dome Proimetion
, Doses from liquid effluents to UNRESTRICTED ARIAS are
! projected at least every 31 days as required by LCO 6.11.3.
These projections are made by averaging the doses (Dhu}
from previous operating history (normally the previous six months) which is indicative of expected future operations.
s GRAND GULF, UNIT 1 1.0-8 Revision 17 - 03/95 l
1 1
I
- _ . -. - _~ . .. . _ . = - - .. . .-.
b 4
i Tint.e 1.2-1 l BIDM CUMULP. TION FACTORS. (BFg ) I (pC1/kg per pC1/ liter) * ;
i FEEBENATER l M flag INVERTEBRATE
}
H 9.0E-01 9.0E-01 j C 4.EE+03 9.1E+03 NA 1.OE+02 2.0E+02 P 1.0E+05 2.0E+04 l CR 2.0E+02 2.0E+03 j
- MN 4.0E+02 9.0E+04 l i
FE 1.0E+02 3.2E+03 CO 5.0E+01 2.0E+02 NI 1.0E+02 1.0E+02 CU 5.0E+01 4.0E+02 ZN 2.OE+03 1.OE+04 4
BR 4.2E+02 3.3E+02 RB 2.OI+03 1.OE+03 SR 3.0E+01 1.0E+02 i Y 2.5E+01 1.0E+03 I !
ZR 3.3E+00 6.7E+00 i NB 3.OE+04 1.OE+02 j
MO 1.0E+01 1.0E+01 '
, TC 1.5E+01 5.0E+00 RU 1.0E+01 3.0E+02 RN 1.OE+01 3.OE+02 SB 1.0E+00 1.0E+01 TE 4.OE+02 6.1E+01 I 1.5E+01 5.0E+00 CS 2.0E+03 1.0E+03 RA 4.0E+00 e
LA 2.0E+02 I 2.5E+01 1.0E+03 I CE 1.0E+00 1.0E+03 I PR 2.5E+01 1.0E+03 ND 2.5E+01 1.OE+03 W 1.2E+03 1.0E+01
-NP 1.0E+01 4.0E+02 I
'
- Values in Table 1.2-1 are taken from Reference 3, Table A-1, except for SB which was taken from Reference 2, Table A-8.
I J
d i
GRAND GULF, UNIT 1 1.0-9
- Revision 11 - 06/88 e
- . _ _ . _ _ _ _ _ _ . . . _ . _ _ . . ~ - - - _ _ . . _ . _ _ _ _ - . . --___ _
i j
i 1
TAELE 1.2-2 i ;
I INGESTICa[ DppE CONVEREION FACTORS FOR ADULT 4 (DFg ) !
3 > (mrom per pe1 ingested) * '
j Page 1 of 'i l NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI.LLI
$ H 3 NO DATA 1.055 07 1.05E.07 1.055-07 1.05E.07 1.05E.07 1.05E.07 C 14 2.845 06 5.68E.07- 5.68E.07 5.68E.07 5.68E.07 5.68E.07 5.68E.07 NA 24 1.70E.06 1.70E.06 1.70I.06 1.70E.06 1.705-06 1.70E.06 1.70E-06 3
P- 32 1.93E.04 1.20E-05 7.46E.06 NO DATA NO DATA NO DATA 2.17E.05 h CR 51 NO DATA NO DATA- 1.59E.09 2.66E.09 5.863 10 3 53E.09 6.69E.07
- MN 54 NO DATA 4.57E.06 8.725 07 NO DATA 1.365 06 NO DATA i 1.40E.05 MN. 56 NO DATA 1.15E.07 2.04E.00 NO DATA '1.46E.07 NO DATA 3.67E.06 FE 55 2.75E.06 1.905-06 4.43E.07 NO DATA NO DATA 1.06E.06 1.09E.06 i FE 59 4.34I.06 1.02E.05 3.91E.06 NO DATA NO DATA 2.85E.06 3.40E.05 t CO 58 NO DATA 7.453 07 1.67E.06 NO DATA NO .*"'.TA NO DATA 1.51E.05 i
j CO 60 No DATA 2.14E.06 4.725 06 NO DATA NO DATA NI 63 NO DATA 4.02E-05 1.30E.04 9.01E.06 4.36E.06 NO DATA NO DATA NO DATA 1.385 06
} NI 65 5.28E.07 6.86E.00 3.13E.08 NO DATA NO DATA NO DATA 1.743 06 CU 64 NO DATA 8.33E.00 3.91E.08- NO DATA 2.10E.07 NO DATA 7.10E.06
- ZN 65 4.84E.06 1.54E.05 6.965 06 NO DATA 1.03E.05 NO DATA 9.705 06 i ZN 69 1.03E.00 1.97E.00 1.37E.09 NO DATA 1.28E.08 NO DATA BR 83 2.96E l NO DATA NO DATA 4.02E.08 NO DATA' NO DATA NO DATA 5.79E.08 BR 84 NO DATA NO DATA 5.21E.08 NO DATA NO DATA NO DATA 4.09E.13 BR 85 NO DATA NO DATA 2.14E.09 NO DATA NO DATA NO DATA LT E-24 j RB 86 NO DATA 2.11E.05 9.83E.06 NO DATA NO DATA NO DATA 4.16E.06 RB ,88 NO DATA 6.05E-08 3.215 00 NO DATA NO DATA
............................ ...................................................,65 NO DATA 8.3 19 l RB 89 NO DATA 4.01E.08 2.82E.08 NO DATA NO DATA NO DATA 2.33E.21 i SR 89 3.00E.04- NO DATA 8.84I.06 NO DATA NO DATA NO DATA 4.94E.05 l
i SR 90 7.58E.03 NO DATA 1.86E.03 NO DATA NO DATA NO DATA 2.195 04 ;
l SR 91 5.67E.06 NO DATA 2.29E.07 NO DATA NO DATA NO DATA SR 92 2.70E.05 {
- 2.15E.06 NO DATA 9.30I.08 NO DATA NO DATA NO DATA 4.263 05 Y 90 9.62E.09 NO DATA 2.58E.10 NO DATA NO DATA NO DATA l
Y 91M 9.09E.11 NO DATA 3.52E-12 NO DATA 04 1.02E.
NO DATA NO DATA 2.67E.10 Y 91 1.41E.07 NO DATA 3.77E.09 NO DATA NO DATA NO DATA 7.76E.05 Y 92 8.45E-10 NO DATA 2.47E.11 NO DATA NO DATA NO DATA 1.40E.05 1
- Values taken from Reference 3, Table E.11.
I 1
GRAND GULF UNIT 1 1.0 10 Revision 0 - 08/82
i i
4 i 1 1 s
TAELE 1.2-2 Wt4 =W i l
3 1---wear nner eaarvenefant FAeTnse FOR ArmLTS, (DF ) {
(arem per PC1 ingested) * !
i, i Page 2 of 3 i f i
NUCLIDE SONE LIVER T. BODY' TNYROID KIIMIIY Y 93 2.68E-09 NO DATA 7.40E-11 LUNG GI.LLI NO DATA NO DATA NO DATA S.50E-05 l ZR 95 3.04E-08 9.75E-09 6.60E-09 No DATA 1.53E-08 I
ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 3.09E-05 NO DATA. 5.12E-10 j
..................................................................NO NB 95 6.22E-09 3.46E-09 1.065-09 DATA 1.05E-04
-)
MO 99 NO DATA 3.42E-09 NO DATA- 2.10E { NO DATA' 4,312-06 8.20E-07 NO DATA S.76E-06 1
i NO DATA 9.99E-05 I TC 99M 2.47E-10 6.985 8.89E-09 NO DATA 1.065-08 TC101 2.545-10 3.66E-10 3.42E-10 4.13E 07 3.593-09 NO DATA 6.59E-09 1.87E-10 1.10E-21
, RU103 1.85E-07 NO DATA 7.978-08 NO DATA 7.065-07 NO DATA RU105 1.54E-08 NO DATA 6.08E-09 2.16E-05 ,
NO DATA 1.99E-07 RU106
....................................................NO
~2.75E-06 NO DATA 3.48E-07 DATA 9.42E-06 AG110M NO DATA 5.31E-06 NO DATA 1.78E-04 1.60E-07 1.48E-07 8.795-08 NO DATA 2.915-07 NO DATA 6.045-05 53124 2.80E-06 5.29E-08 1.11E-06 6.795-09 SB125+D 1.79E-06 0.0 2.18E-06 7.955-05 2.00E-08 4.26E-07 1.825-09 0.0 1.38E-06 1.973-05 SS126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 7.05E-07 55127 2.58E-07 5.65E 0.0 9.403-05 9.903-08 3.105-09 0.0 1.53E-07 5.905-05 TE125M 2.68E-06 9.71E-07 3.59E-07 0.065-07 1.093-0 TE127M .6.77E-06 2.42E-06 8.25E 5 NO DATA 1.07E-05 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.385-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 '4.29E-06 1.82E-06 3.95E-06 4.80E-0
..............................................................5 TE129' 3.14E-08 1.18E-08 7.65E-09 NO DATA 5.79E 05 2.41E 08 1.32E-07 NO DATA 2.371-08 !
TE131M '1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 TE131 1.97E-08 8.23E-09 6.22E-09 NO DATA 8.406 05 1.62E-08 8.63E-08 2.79E-09
..................................................................W.O TE132 2.52E-06 1.63E-06 1.53E-06 DATA 1.80E-06 1.57E-05 NO DATA 7.713-05 I'130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 I 131 4.16E-06 5.95E-06 NO DATA 1.925-06 i 3.41E-06 1.95E-03 I 132 2.03E-07 5.43E-07 1.02E.05 NO DATA 1.575-06 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E.06 I 134 1.06E-07 NO DATA 2.225 06 2.88E-07 1.032-07 4.99E-06 I 135 4.43E-07 1.16E-06 4.58E-07 NO DATA 2.51E-10 4,2SE-07 7.65E-05 1.86E-06 NO DATA 1.315-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 CS136 6.51E-06 2.57E-05 1.59E-05 2.59E.06 1.85E-05 NO DATA 1.43I.05 1.96E-06 2.92E-06
- Values taken from Reference 3, Table E-11, except for SB values which were taken from Reference 8, Table 4.
GRAND GULF. UNIT 1 1,o.11 Revision 11 06/08
j TAmti- 1.2-2 (Continuad) l
' int 2RSTION DOBE CONVrneION FACTORE FOR ADULTS, (DF )
g (mrom per pC1 ingested)
- Page 3 of 3
, NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI CS137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 j BA139 9.70E.00 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18t.-0$
BA141 4.71E-08 3.56E-11 1.59E.09 NO DATA 3.31E-11 2.02E-11 2.22E-17 i
4 BA142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 3 LA140 2.50E-09 1.26E-09 3.33E.10 NO DATA NO DATA LA142 NO DATA 9.25E-05 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7 18E-10 NO DATA 2.94E-09 NO DATA 4
CE143 1.65E-09 1.22E-06 1.35E-10 NO DATA 2.42E-0 5..
l i 5.375-10 NO DATA 4.54E-05 l CE144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA PR143 1.65E-04 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA PR144 3.01E-11 1.25E-11 1.53E-12 4.03E-05 NO DATA 7.05E-12 NO DATA 4.333-18 ND147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E.07 8.61E-08 3.01E-05 NO DATA NO DATA NO DATA
............................................................................ 2.82E.05 NP239 1.19E.09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E.05
- Values taken from Reference 3, Table E-11 GRAND GULF. UNIT 1 1.0-12 Revision 0 - 08/82
- . . - . -. . - - - - , . . - ~ . - _ . ~ . - ..-._. - - - _ _ _ ~ - . - -- - - - .-
E i' l l
T& ELE 1.2-3 ,
-i l- SITE EXIATED IMGEETIcar (arem/hr pernoEE pC1/ml), ccBe(ITNENT FACTOR. lAiTau)
Page 1 of 2 l f-l
- t NUCLIDE 500fE LIVER' T. BODY TRYEDID KIDNEY
..............................................................................GI-LLI _ LUNG f .H-3 'O.00E+00. 2.26E-01 2.26E-01 2.265-01 2.265-01 2.26E-01 2,26E-01
[ C-14 3.13E+04 6.265+03 6.26E+03 6.265+03 6.265+03 6.26E+03 6.26E+03 l
! Na-24 4.07E+02 4.075+02 4.075+02 4.073+02 4.07E+02 4.07E+02 P-32 4.62E+07 2.875+06 4.07E+0?
[ 1.793+06 0.00E+00 0.00E+00 0.00E+00 5.19E 06
[ Cr-51 0.00E+00 0.00E+00 1.27E+00 7.615-01 2.815 01 1.69E+00
[
Mn-54 0.00E+00 3.20E+02 j 4
4.385+03 8.35E+02 0.00E+00 1.30E+03. 0.00E+00 1.34E+04 i' Mn-56 0.00E+00 1.10E+02 1.95E+01 0.00E+00 1.40E+02 i
Fe 55 0.00E+00 3.51E+03 ;
6.583+02 4.55E+02 1.06E+02 0.00E+00- '0.00E+00 2.54E+02 2.61E+02 i i Fe-59 1.04E+03 2.44E+03 9.365+02 0.00E+00 0.00E+00
- i. Co-58 6.82E+02 8.14E+03 0.00E+00 8.92E+01 2.00E+02 0.00E+00 0.00E+00 0.00E+00 1.81E+03 j Co-60 0.00E+00 2.56E+02 5.65E+02 0.00E+00 0.00E+00 Ni-63 3.11E+04 2.16E+03 0.00E+00 4.81E+03 1.04E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 i Ni-65 1.26E+02 1.64E+01 7.495+00 0.00E+00 0.00E+00 0.00E+00 4.173+02 .:
i Cu-64 0.00E+00 9.975+00 4.683+00 0.00E+00 2.51E+01 En-65 2.32E+04 7.373+04 0.00E+00 8.50E+02
- 3.33E+04 0.00E+00 4.93E+04 0.00E+00- 4.64E+04
'En-69 '4.93E+01 9.43E+01 6.565+00 0.00E+00 6.13E+01 i
0.00E+00 1.42E+01 Br-83 0.00E+00 0.00E+00 4.04E+01 0.00E+00 0.00E+00 0.00E+00 i
! Er.84 0.00E+00 5.82k+01 !
0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00E+00 4.11E-04 Br-85 0.00E+00 0.00E+00 2.15E+00 0.00E+00 0.00E+00 0.00E+00 1.01E-15 l Rb-86 0.00E+00 ~1.01E+05 4.71E+04 0.00E+00 0.00E+00 Rb-88 0.00E+00 1.99E+04 !
0.00E+00- 2.90E+02 1.54E+02 0.00E+00- 0.00E+00 0.00E+00 4.00E-09 i Rb-89 0.00E+00 1.92E+02 1.35E+02 0.00E+00 0.00E+00 0.00E+00 1.12E-11' 1
- Sr-89 2.21E+04 0.00E+00 6.35E+02 0.00E+00 0.00E+00 0.00E+00 3.55E+03
, Sr-90 5.44E+05 0.00E+00 1.34E+05 0'00E+00
. 0.00E+00 0.00E+00 1.57E+04 4 Sr-91 4.07E+02 0.00E+00 1.64E+01 0.00E+00 0.00E+00 Sr-92" 1.54E+02 0.00E+00- 1.94E+03
]
-0.00E+00 6.68E+00 0.00E+00 0.00E+00 0.00E+00 3.06E+03 Y-90 5.76E-01 0.00E+00 1.54E-02 0.00E+00 0.00E+00 0.00E+00 6.10E+03
. Y-91m 5.44E-03 0.00E+00 2.11E-04 0.00E+00 Y-91 8.44E+00 0.00E+00. .0.00E+00 1.60E-02 0
0.00E+00 2.26E-01 0.00E+00 0.00E+C0 0.00E+00 4.64E+03
'Y-92 5.06E-02 0.00E+00 1.48E-03 0.00E+00 0.00E+00 0.COE+00 8.865+02 I
Y-93 1.60E-01 0.00E+00 4.43E-03 0.00E+00 0.00E+00 f Zr-95 2.40E.01 7.70E-02 0.00E+00 5.093+03 5.21E-02 0.00E+00 1.21E.01 0.00E+00 2.44E+02 i Zr-97 1.33E-02 2.685-03 1.22E-03' O.00E+00 4.04E-03 0.00E+00 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 0.00E+00 4
i Mo-99 2.463+02 0.00E+00 1.51E+06 0.00E+00 1.03E+02 1.96E+01 0.00E+00 2.34E+02 Tc-99m 8.87E-03 2.51E-02 0.00E+00 2.395+02 i.
3.19E-01 0.00E+00 3.81E-01 1.23E-02 1.48E+01 j Tc-101 9.12E-03 1.31E-02 1'. 2 9E - 01 0.00E+00 2.37E-01
- . Ru-103 4.43E+00 6.72E-03 3.95E-14 0.00E+00 1.91E+00 0.00E+00 1.693+01 0.00E+00 5.17E+02 Ru-105 3.69E-01 'O.00E+00 1.46E-01 0.00E+00 4.76E+00 0.00E+00 2.26E+02 '
4
- -
- Calculated from Equation 8. ;
1 GRAND GULF. UNIT 1 1.0-13 Revision 2 05/84
I Thau 1.2-3 (continued)
?
SITE RELATED IMt1ESTION DOSE Cope (I'tMENT FACTOR. (AiTau)
(arem/hr per pC1/ml).
Page 2 of 2 L
t NUCLIDE EONE LIVER T. RODY TRYROID KIDNEY LUNG l GI-LLI ,
l Ru-106 6.583+01 'O.00E+00 8.33E+00 0.00E+00 1.275+02 0.00E+00 4.26E+03 l Ag-110m 8.81E-01 8.15E-01 4.84E-01 0.00E+00 1.60E+00 0.00E+00 3.30E+02 Sb-124 6.70E+00 1.273-01 2.665+00 1.63E-02 0.00E+00 Sb-125 4.29E+00 5.22E+00 1.90E+02 4.79E-02. 1.02E+00 4.36E-03 0.00E+00 3.30E+00 4.72E+01 Sb-126 2.75E+00 3. 60L O2 9.94E-01 1.69E-02 0.005400 Sb-127 6.18E-01 1.69E+00 2.25E+02 i 1.35E-02 2.373-01 7.42E-03 0.00E+ 0 3.66E-01 1.41E+02 .
Te-125m 2.575+03 9.30E+02 3.44E+02 7.72k+02 1.04E+04 0.00E+00 1.02E+04
! Te-127m 6.485+03 2.32E+03 7.905-02 1.66E+03 2.63E+04 0.00E+00 2.175+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.00E+00 0.31E+03 .
Te-129m 1.10E+04 4.11E+03 1.74E+03 3.783+03 4.60E+04 0.00E+00 5.54E+04 ;
Te-129 3.01E+01 1.13E+01 7.33E+00 2.31E+01 1.26E+02 0.00E+00 2.275+01 ~
Te-131m 1.665+03 8.10E+02 6.75E+02 1.285+03 8.21E+03 0.00E+00 8.04E+04 Te-131 1.895+01 7.885+00 5.963+00 1.55E+01 8.26E+01 Te-132 2.41E+03 1.56E+03 0.00E+00 2.675+00 1.475+03' 1.72E+03 1.50E+04 0.00E+00 7.385+04 I-130 2.71E+01 8.01E+01- 3.165+01 6.793+03 1.25E+02 0.00E+00 6.895+01 I-131 1.49E+02 2.14E+02 1.22E+02 7.00E+04 3.66E+02 0.00E+00 5.64E+01 I-132 7.29E+00 1.95E+01, 6.82E+00 6.82E+02 3.11E+01 0.00E+00 3.665+00 I-133 5.10E+01 8.873+01 ~2.70E+01 1.30E+04 1.55E+02 0.00E+00 7.975+01
~
I-134 3.81E+00 1.03E+01
- 70E+00
. 1.793+02 1.64E+01 0.00E+00 9.015-03 I-135 1,59E+01 4.17E+0E 1.54E+01 2.75E+03 Co-134 6.685+01 0.00E+00 4.70E+01 2.98E+05 7.093+D5 5.79E+05 0.00E+00 2.29E+05 7.61E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 0.00E+00 6.85E+04 Cs-137 9.38E+03 1.40E+04 3.82E+05 5.22E+05 3.42E+05 0.00E+00 1.77E+05 5.99E+04 '1.01E+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 0.00E+00 3.84E+02 Ea-139 9.29E-01 6.62E-04 3.795+01 2.235-03 2.72E-02 0.00E+00 6.19E-04 3.75E-04' 1.65E+00 Ea-140. 1.94E+02 2.44E-01 1.27E+01 0.00E+00 8.30E-02 Ea-141 4.51E-01 3.41E-04 1.40E-01 4.00E+02 1.52E-02 0.00E+00 3.17E-04 1.93E.04 2.13E-10 Ea-142 2.04E-01 2.10E-04 1.283-02 0.00E+00 1.77E-04
'La-140 1.50E-01 1.19E-04 2.87E-19 7.54E-02 1.99E-02 0.00E+00 0.00E+00 0.00E+00 5.54E+03 La-142 7.66E-03 3.40E-03 0.68E-04 0.00E+00 0.00E+00 '
Co-141 2.24E-02 1.52E-02 0.00E+00 2.54E+01 1.72E-03 0.00E+00 7.04E-03 0.00E+00 5.79E+01 Co-143 3.95E-03 2.92E+00 3.23E-04 0.00E+00 Ce-144 1.17E+00 1.29E-03 0.00E+00 1.09E+02 4.88E-01 6.27E-02 0.00E+00 2.90E-01 0.00E+00 3.95E+02 Pr-143 5.51E-01 2.21E-01 2.73E-02 0.00E+00 Pr-144 1.27E-01 0.00E+00 2.41E+03 1.80E-03 7.40E-04 9.15E-05 0.00E+00 4.22E-04 Nd-147 3,76E-01 4.35E-01 2.60E-02 0.00E+00. 2.59E-10 W 187 0.00E+00 2.54E-01 0.00E+00 2.09E+03 2.96E+02 2.47E+02 0.65E+01 0.00E+00 0.00E+00 0.00E+00 8.10E+04 Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 - 5.'75E+02 -
- Calculated from Equation 8.
I l
j I
GRAND GULF. UNIT 1 1.0-14 Revision 11 - 06/88
. _ . . _ _ _ __ . . . _ - _ . _ - _ _.._.... _ _ . - - . . ~ . .__ . ._ ._
1 1
1.3 Licruid Radwaste Treat ==nt System i
The essential components of the liquid radwaste treatment system are ;
indicated by an asterisk (*).
I 1
NOTES for Fiaure ODCM 1.3-1 !
I (1) The essentiti components outlined on the following page are those i necessary to collect, process and sample liquid radwaste prior to discharge to the environment.
l (2) only one of the following is required in order to process liquid waste.
- a. Equipment drain filter
- b. Floor drain filter !
- c. Equipment drain domineralizer
- d. Floor drain domineraliser
- e. Reverse osmosis Treatment system (3) The Waste surge Tanks may be used to replace the Waste Collection Tanks, i
e GRAND GULF, UNIT 1 1.0-15 Revision 18 - 02/96 l
I = F = = ? b 3 l = !I ,! E 3, g ,
ut !
si g a
( gj a
8' E g
8 V g ;
JL g
6"
- 5 V
E '
y' T c z g -
Tl l~
& c 1g" E _. -
- JL JL s)
So
! < > Na y
8 w5 w5 JL t gl 9 gl 9 >J s s -
, , i f'i JL JL JL 5-9 E ll g!
- , rg .
53
- ES 5- E- dl * !.5
!! 2
!5+s!
"8 3 3 = g5 s *-- Ee e 59 I
s S SE* ;
g ] te 9*
5 g a JL JL 3 gl g _ _
- -~
e g g e g r- --
i y a u y- 7!
g ! r-E! g!! l;1 8E lllg e
lea 1l, = r JL -
$55 Ik JL .
JL g
E !"8)
!si ;L l !
- 1 i s -
! g!*s! s i e Iliplsa!g*lgil:
- hi
!lill
~...
1 iI 9
i s d a g t
. . . . . - . . . ~ . . . . . . .
. . _ ~ . . . - . . . . . -
? l l' a
- i I
e 2.0 GASEOUS EFFLUENTS 2.1 timmaeus Effluent Manitor setnointa j 2.1.1 Continuous Ventilation Manfters For'the purpose of implementation of LCO 6.3.10, the alarm i-i setpoint level for continuous ventilation noble gas monitors will be calculated as follows:
l
- Sy - count rate (cym) above background of vent noble gas
- monitor at the alarm setpoint level PF x R TB or t
= the lesser of
} PF x R, x D,,
where i
- -- PF = product of allocation factor (AF) and safety factor I (SF) , normally set at 0.1 l
AF = allocation factor allowing for a total of four normal
}s
< effluent release points, normally set at 0.25 l s
SF = safety factor allowing for cumulative uncertainties l
' i j of measurements, normally set at 0.4 !
Dg = dose rate limit to the total body of an individual I l
, at the SITE BOUNDARY or at UNRESTRICTED AREAS inside the SITE BOUNDARY required to limit dose to 500 mres
! in one year l = 500 arem/yr J
D,, = dose rate limit to the skin of the body of an l
f individual at the SITE BOUNDARY or at IDOtESTRICTED i ARIAS inside the SITE BOUNDARY required to limit dose 1
i to 3000 mrom in one year t' = 3000 mrom/yr i
i i
i i i
l 1
1
!' GRAND GULF, UNIT 1 2.0-1 Revision 17 - 03/95 1
I d
-w
4
~
.R = count rate (cpe) per mrom/yr to the total body
=C+ [ X/Q EK g Q'g]
whert j i
$ C count rate (cpm) above background of the vent monitor corresponaing to grab sample radionuclide concentrations l X/Q = highest sector annual average atmospheric dispersion at the SITE BOUNDARY or at UNRESTRICTED AREAS inside
, the SITE BOUNDARY
= s.9 x 10'#* sec/m in the Su sector l K = total body dose factor due to gamma emissions from 3
i each noble gas radionuclide 1 (mram/yr per pC1/m )
from ODCM Table 2.1-1
. i Q' = rate of release of noble gas radionuclide 1 (pci/sec) from the release point R, = count rate (cpa) per arem/yr to the skin l
, = C + K/Q [Eg (Lg + 1.1 Mg ) Q'g] ;
L g - skin dose factor due to beta emissions from isotope i (mres/yr per pC1/m ) from ODCM Table 2.1-1 i
l 1.1 = mrom skin dose per arad air dose s
Mg = air dose factor due to gamma emissions from isotope 1 (arad/yr per pCi/m ) free ODO( Table 2.1-1
- The highest annual average X/Q for the GGNS SITE BOUNDARY or UNRESTRICTED ARRAS inside the SITE BOUNDARY is at the SITE BOUNDARY, (SN sector, 0.85 miles). This value is taken from ODCM Reference 9, Table 2, -
l l
1 1
i ., .
GRAND GULF, UNIT 1 2.0-2 Revision 17 - 03/95
i 2.1.2-i TEXT DELETED l i
I l
l 4
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9 GRAND GULF, UNIT 1 2.0-3 Revision 2 - 05/84
. . . - . .- -. ., . . - - . . . . ~ . -
5
)
NOTES For Section 2.1.1
- 1) The calculated setpoint values will determine the allowable bounds for the
, actual setpoint adjustments. That is, setpoint adjustments are not required to be performed if the axisting setpoint level corresponds to a count rate that is less than or equal to + 25% of the calculated value. If radionuclides are not detected in the grab sample, then the previously calculated setpoint may remain as the valid setpoint.
- 2) A more conservative setpoint may be calculated using the conservative Kr-89 4
total body dose factor. This method may be used'when there are no valid l
l 1sotopics available. The conservative setpoint will be calculated as
- follows
j sy= count rate (epm) above background of vent noble gas monitor at the alarm setpoint level *
=
PF' xD,xR" 7 t
, where:
PF =
product of allocation factor (AF) and safety f actor (SF') , normally set at 0.2 i i J
AF = allocation factor allowing for a total of four normal effluent release points, normally set at 0.25 SF' =
safety factor allowing for cumulative uncertainties of measurements, normally set at 0.8 i
] R " = conservative count rate per mrem /yr to the total body (xe-133 i detection, Kr-89 dose)
= (3.53E-5) (60)
E75 <x) (v) (K)
- The setpoint calculation based on a Kr-89 skin dose is not required because the setpoint based on a Kr-89 total body dose will always be more
- conservative.
1 i
i
}
GRAND GULF, UNIT 1 2.0-4 Revision 12 - 08/88
4 where:
X = Xe-133 volume efficiency factor of the detector system in gC1/cc/ cpm as det*nnined by the primary calibration
- v = maximum designac ventilation flow rate in cubic feet per minute (cfm) 3.53E-5 = conversion factor, ft per cc 60 - conversirn factor, seconds per minute K = total bx.ly dose factor for Kr-09, the most restrictive isotope, from Table 2.1-1
= 1.66E + 04 mrem /yr per pCi/m other variables as defined in section 2.1.1 l
l i
l l
l I
The instrument calibration precedures will include checks to ensure that the detector efficiency does not vary by more than 2 25%.
GRAND GULF, UNIT 1 2.0-5 Revision 12 - 08/88
l 4
Tinft 2.1-1 i DORE FA N DE FOR WYDOBf782 TO A SEMI-innal1x NtDD OF Nonf.F GAE2s Nuclide Y-Bodv**fK)i B-Skin ** (L)i Y-Air *(M)i B-Air *fN)i f Kr-85m 1.17E+03*** 1.465+03 1.23E+03 1.97E+03
)
Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 i
]
Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 l Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 l Xe-121m 9.15E+01 4.765+02 1.56E+02 ?. 11E+03 q Xe-133m 2.51E+02 9.94E+02 3.27E+02 '1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+01 1.05E+03 j Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.695+03 9.30E+03 3.28E+03 Values taken from Reference 3, Table B-1
- mrad - m8 pC1 - yr
.. mram - ma pC1 - yr
- 1.17E+03 = 1.17 x 10 GRAND GULF, UNIT 1 2.0 6 Revision 0 - 08/82
2.2 Gaseous Effluent Dose calculations 2.2.1 Unrestricted Area Botmeimev Dome Rate
- a. For the purpose of implementation of LCO 6.11.4.a, the dose rate at the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY due to noble gases shall be -
calculated as follows:
D tb " ***#*I* "" Y ** #* * ^ ""##*"" Y**#
(mrem /yr)
X/Q IK gQ'g D, = average skin dose rate in current year (mres/yr)
= X/Q Z (L g + 1. Mg ) Q'g ,
. radioactive materials in particulate form, with half-lives greater than eight days will be calculated for the purpose of implementation of LCO 6.11.4.b as follows: i D,= average organ dose rate in current year (mres/yr) I l
= IW P g Q' g where:
GRAND GULF, UNIT 1 2.0-7 Revision 17 - 03/95
.7 i
4 i W = controlling sector annual average atmospheric dispersion at the SITE BOUNDARY or UNRESTRICTED i AREAS inside the SITE BOUNDARY for the appropriate pathway
~*
l X76 = 8.9 x 10 sec/m for inhalation j
- and all tritium pathways or l
~
676 = 1.6 x 10' m for food and j ground plane pathways l
P = the total dose parameter for radionuclide 1, (mrom/yr per pCi/m ) for inhalation and all i 2 i tritium pathways and (m . mram/yr per pci/sec) for food and ground plane pathways, from Ocot
{
4 Tables 2.2-la-b l 1
- Q'g = rate of release of noble gas radionuclide i
] (pci/sec) from the release point i
$ Q'g - average release rate of isotope i of tritium, 1
' I-131, I-133 or other radionuclide in particulate
, form, with half-lives greater than eight (8) days in the current year (pci/sec) i i
4
'* The highest annual average X/Q for the GGNS SITE SOUNDARY or UNRESTRICTED AREAS inside the SITE BOUNDARY is at the SITE BOUNDARY,'in the SW sector I (0.85 miles). This value is taken from ODCM Reference 9, Table 2.
GRAND GULF, UNIT 1 2.0-8 Revision 17 - 03/95 ,
., ~. .. . .- ~ . . - . . . - . - - .
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2.2.2 tinrestricted Area Dose to individual
- a. For the purpose of implementation of LCO 6.11.5, the
+
air dose at the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY shall be determined as follows:
i J
1 i D = air dose due to gansna emissions from noble gas
]
, radionuclide 1 (mrad)
= 3.17 x 10' X/Q' Qg
?
where: 1 J
X/Q* = relative concentration for the SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY.
- S.9 X 10'
- sec/m Mg - air dose factor due to gansna emissions from noble gas radionuclide 1 (mrad /yr per gCi/m )
from ODCM Table 2.1-1 ,
The highest annual average X/Q for the GGNS SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY is at the SITE BOUNDARY, SW Sector, .85 miles. This value is taken frs 0:X34 :
Reference 9 Table 2.
GRAND GULF, UNIT 1 2.0-9 Revision 17.- 03/95
4
- l l Qg = cumulative release of radionuclide i of noble i
gas, tritium, I-131, I-133, or material in particulate fom over the period of interest (pC1)
~
Notes 3.17 x 10 is the inverse of the number of
! seconds per year, and D, = air dose due to beta emissions from noble gas I radionuclide 1 (mrad)
= 3.17 x 10"' IN g X3' o g i
where:
Ng = air dose factor due to beta emissions from noble gas radionuclide 1 (arad/yr per pCi/m ) from I ODCM Table 2.1-1 X/Q' = relative concentration the SITE BotDEDARY or at 4
} UNRESTRICTED AREAS within the SITE BOUNDARY. .
< = 8.9 x 10" sec/m 5
Og = cumulative release of radionuclide i'of noble I
gas, tritium, I-131, I-133, or material in particulate form over the period of interest (gCi)
The highest annual average X/Q for the GGNS SITE BOUNDARY or at UNRESTRICTED AREAS within the SITE BOUNDARY is at the SITE BOUNDARY, SW Sector, 0.85 miles. This value is taken-from ODCM Reference 9 Table 2.
GRAND GULF, UNIT 1 2.0-10 Revision 17 - 03/95
I i !
- i
, i 4 2.2.2 Unrestricted Area Dese to Individual 1
)
i radioactive materials in particulate form, with half-i lives greater than eight (8) days will be calculated for the purpos.e of implementation of LCO 6.11.6 as follows:
D = dose to an individual from tritium, I-131, I-133 and radionuclides in particulate form, with ,
half-life greater than eight days (mrem) -
~8
= 3.17 x 10 ER g W' Q g
where: l W' = relative concentration at a controlling location for an individual
~*
W= 8.3 x 10 sec/:n for inhalation and all tritium pathways or
~
D/Q' = 6.7 x 10 '* m" for food and ground plane pathways Rg = the total dose factor for radionuclide 1, (arem/yr per pCi/m ) for inhalation and all.
tritium pathways and (m . mrem /yr per pCi/sec) l 1
for food and ground plane pathways from Tables 2.2-2a - d I
- The highest annual average X/Q and D/Q at or beyond the SITE BOUNDARY is in the SW Sector (0.89 miles) . These values are for the controllirig offsite receptor. These values are taken from CDCM Reference 9 Table 2.
GRAND GULF, UNIT 1 2.0-10a Revist.on 17 - 03/95
. . . - . .. . . _ . . . . - . .. -. . - . . - . . - . . . . - ~ . _ .
2.2.2 nnrestricted Area Dose to individum1' Q
, 1 = cumulative release of radionuclide i of noble gas, tritium, I-131. I-133, or material in particulate form over the period of interest (pci)
- c. For the purpose of implementing TS 5.6.3, dose calculations will be performed using the above equations or with the substitution of average f
meteorological parameters (most limiting parameters will be used) which prevailed for the period of the report.
2.2.3 Dg33., ProiactM Domes from gaseous affluents to UNRESTRICTED AREAS are projected at least every 31 days as required by LCO 6.11.s.
These projections are made by averaging the doses (D , Dp, l D) p from previous operating history (normally the previous six months) which is indicative of future expected operations.
I r
GRAND GULF, UNIT 1 2.0-10b Revision 17 - 03/95 l
_ . _ ~- , ._m _ . _ _ _ . . _ . . . _ . . _ . _
i l
l TABLE 2.2-la i
PATHWAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (Pg )
Page 1 of 2
) AGE GROUP (INFANT) ( N.A. ) (INFANT)
ISOTOPE INH _m TION GROUND PLANE FOOD H-3 5.468E+02 0.000E+00 2.382E+03 C-14 2.646E+04 0.000E+00 2.340E+09 NA-24 1 356E+04 1.979E+07 1.542E+07 P-32 2.030E+06 0.000E+00 1.602E+11 CR-51 1.284E+04 7.864E+06 4.700E+06
. MN-54 9.996E+05 1.287E+09 3.900E+07 MN-56 7.168E+04 1.525E+06 2.862E+00 FE-55 8.694E+04 0.000E+00 1.351E+08 j FE-59 1.015E+06 4.562E+08 3.919E+08 CO-58 7.770E+05 6.194E+08 6.055E+07 CO-60 4.508E+06 5.172E+09 2.098E+08 NI-63 3.3885+05 0.000E+00 3.493E+10 NI-65 5.012E+04 4.930E+05 3.020E+01 CU-64 1.498E+04 -9.823E+05 3.807E+06 ZN-65 6.468E+05 7.907E+08 1.904E+10 ZN-69 1.322E+04 0.000E+00 3.855E-09 BR-83 3.808E+02 1.011E+04 9.339E-01 BR-84 4.004E+02 3.376E+05 1.256E-22 BR-85 2.044E+01 0.000E+00 H.000E+00 RS-86 1.904E+05 1.478E+07 .' 234E+10 RB-88 5.572E+02 5.3995+04 1.874E-44 RB-89 3.206E+02 2.075E+05 4.193E-53 SR-89 2.030E+06 3.560E+04 1.258E+10 SR-90 4.088E+07 0.000E+00 1.216E+11 SR-91 7.336E+04 3.587E+06 3.215E+05 SR-92 1.400E+05 1.233E+06 5.005E+01 Y-90 2.688E+05 7.583E+03 9.406E+05 Y-91M 2.786E+03 1.658E+05 1.876E 15 Y-91 2.450E+06 1.702E+06 5.251E+06 4 Y-92 1.266E+05 3.060E+05 1.026E+01 i Y-93 1.666E+05 3.620E+05 1.776E+04 ZR-95 1.750E+06 3.975E+08 8.257E+05 ZR-97 1.400E+05 4.921E+06 4.446E+04 NB-95 4.789E+05 2.291E+08 2.062E+08 MO-99 1.348E+05 6.6085+06 3.108E+08 TC-99M 2.030E+03 3.013E+05 1.646E+04 TC-101 8.442E+02 3.253E+04 1.423E-56 RU-103 5.516E+05 1.804E+08 1.055E+05 RU-105 4.844E+04 1.030E+06 3.204E+00 RU-106 1.156E+07 3.590E+08 1.445E+06 AG-110M 3.6685+06 3.649E+09 1.4F.2+10 GRAND GULF, UNIT 1 2.0-11. Revision 17 - 03/95
l l
1 TABtf 2.2-la (Continued)
PATHWAY DOSE FACTORS FOR Lc0 6.11.4 and SECTION 2.2.1.b, (Pg)
]
Page 2 of 2 AGE daMUP (INFANT) ( N.A. ) (INFANT)
ISOTOPE Twnt2 TION d#nNM PY1W FOOD
, TE-125M 4.466E+05 3.001E+06 1.508E+08 TE-127M 1.312E+06 1.395E+05 1.037E+09 TE-127 2.436E+04 4.704E+03 1.359E+05 TE-129M 1.680E+06 3.290E+07 1.392E+09 TE-129 2.632E+04 4.395E+04 1.678E-07 F TE-131M 1.988E+05 1.351E+07 2.288E+07
, TE-131 8.218E+03 4.9290+07 1.384E-30 TE-132 3.402E+05 7.098E+06 6.513E+07 I-130 1.596E*06 9.560E+06 8.754E+08 I-131 1.484E+07 2.985E+07 1.053E+12
- I-132 1.694E+05 2.075E+06 1.1885+02 I-133 3.556E+06 4.2595+06 9.601E+09 i I-134 4.452E+04 7.5785+05 8.402E-10 I-135 6.958E+05 4.210E+06 2.002E+07 CS-134 7.020E+05 3.282E+09 6.801E+10 j CS-136 1.345E+05 3.432E+08 5.795E+09 -
3 CS-137 6.118E+05 1.337E+09 6.024E+10 CS-138 8.754E+02 5.860E+05 2.100E-22 BA-139 5.096E+04 1.705E+05 2.874E-05
- BA-140 1.596E+06 3.352E+07 2.410E+08 RA-141 4.746E+03 6.762E+04 3.141E-44
, BA-142 1.554E+03 7.234E+04 0.000E+00
- i. LA-140 1.680E+05 3.114E+07 1.880E+05 LA-142 5.950E+04 1.269E+06 6.019E-06 CE-141 . 5.166E+05 2.199E+07 1.366E+07 CE-143 1.162E+05 3.753E+06 1.536E+06 i CE-144 9.842E+06 6.761E+07 1.334E+08
, PR-143 4.326E+05 0.000E+00 7.845E+05 i PR-144 4.284E+03 3.017E+03 1.171E-48
- ND-147 3.220E+05 1.441E+07 5.743E+05 I W-107 3.962E+04 3.915E+06 2.501E+06 NP-239 5.950E+04 2.023E+06 9.400E+04 Units: Inhalation 2and all tritium pathways - mrom/yr per pCi/m others - m . mrom/yr per gCi/sec
- Values based on standard NUREG-0133, Section 5.2.1 assumptions unless i otherwise indicated. -
l i
I I
GRAND GULF, UNIT 1 2.0-12 Revision 17 - 03/95 l
-- - . _ _ . . .. , - _ _ . . . - . .--.- . _.. _ . . . ~ _ - . . - . _ . - - . . . . . . _ - .,
I I
4 I T_ antr 2.2-1b PATMwAY DOSE FACTORS FOR LCO 6.11.4 and SECTION 2.2.1.b, (Pg)
Page 1 of 2
. AGE nantTP ( CHILD ) ( N. A. ) ( CHILD )
ISOTOPE INW1_f ATION Gnorn m pt.amrt naa/ANL/ MEAT H-3 1.125E+03 0.000E+00- 1.826E+02 C-14 3.5895+04 0.000E+00 2.991E+08 NA-24 1.610E+04 1.385E+07 1.345E-03 P-32 2.605E+06 0.000E+00 5.781E+09 CR-51 1.6983+04 5.506E+06 3.636E+05 MN-54 1.576E+06 1,K2ME+09 6.249E+06 MN-56 1.232E+05 1.0685+06 1.901E-51 FE-55 1.110E+05 0.000E+00 3.566E+08 FE-59 1.269E+06 3.204E+08 4.943E+08 CO-58 1.106E+06 4.464E+08 7.485E+07 CO-60 7.0675+06 2.532E+10 2.993E+08 >
NI-63 8.214E+05 0.000E+00 2.272E+10 NI-65 8.399E+04 3.451E+05 3.167E-51 CU-64 3.670E+04 6.876E+05 1.087E-05 ZN-65 9.953E+05 8.583E+08 7.801E+08 KN-69 1.0185+04 0.000E+00 0.000E+00 i BR-83 4.736E+02 7.079E+03 7.425E-57
, BR-84 5.476E+02 2.363E+05 0.000E+00 BR-85 2.531E+01 0.000E+00 0.000E+00 RB-86 1.983E+05 1.035E+07 4.536E+08 RB-88 5.624E+02 3.779E+04 0.000E+00 RB-89 3.452E+02 1.452E+05 0.000E+00 SR-89 2.157E+06 2.509E+04 3.756E+08 SR-90 1.010E+08 0.000E+00 8.111E+09 SR-91 1.739E+05 2.511E+06 4.128E-10 SR-92 2.424E+05 8.631E+05 2.724E-48 Y-90 2.679E+05 5.308E+03 3.806E+05 Y-91M 2.812E+03 1.161E+05 0.000E+00 Y-91 2.627E+06 1.207E+06 1.872E+08 Y-92 2.390E+05 2.142E+05 5.428E-35 Y-93 3.885E+05 2.534E+05 1.207E-07 ZR-95 2.231E+06 2.837E+08 4.763E+08 ER-97 3.511E+05 3.445E+06 5.471E-01 N5-95 6.142E+05 1.605E+08 1.738E+09 MO-99 1.354E+05 4.6265+06 1.915E+05 TC-99M 4.810E+03 2.109E+05 5.3945-18 TC-101 5.8465+02 2.277E+04 0.000E+00 RU-103 6.623E+05 1.265E+08 3.127E+09 RU-105 9.953E+04 '
7.212E+05 4.590E-25 RU-106 1.432E+07 5.0495+08 5.384E+10 AG-110M 5.4763+06 4.019E+09 5.259E+08 GRAND GULF, UNIT 1 2.0-13 Revision 17 -
03/95
_ . - - _ _ . . _ . . . - - m - _~__ . ._ _ . . . . _ . _ _ _ _ . _ _ _ . . _ . . . . . _ . . . . . . _ . _ _ . _ _ . . _ _ _ _ _ . _ . . . . _ . .
1 i
!t .
I TAaLT 2.2-1b (continued)
- PATintAY DOSE FACTORE FOR LCO 6.11.4 mnd l SECTION 2.2.1.b, (Pg)
Page 2 of 2 1
AGE MDotJP ( NT LD ) ( N. A. ) ( cMTLD )
ISOTOPE TW17 ATION GRONh PT = GRE/AML/ MEAT
- TE-125M 4.773E+05 2.1283+06 4.438E+08 l
! TE-127M 1.480E+06 1.083E+05 3.947E+09 i TE-127 5.624E+04 3.293E+03
- 1.254E-08 TE-129M 1.761E+06 2.30$E+07- 4.091E+09 TE-129 2~.549E+04 3.076E+04 0.000E+00 c TE-131M 3.078E+05 9.4598+06 7.656E+03 l 3.450E+07 0.000E+00
, TE-131 2.054E+03
- TE-132 3.774E+05 4.968E+06 7.274E+06 I-130 1.846E+06 6.692E+06 5.271E-04 i I-131 1.624E+07 2.0895+07 4.293E+09 l I-132 1.935E+05 1.452E+06 1.895E-57
- I-133 3.848E+06 2.981E+06 1.017E+02 I-134 5.069E+04 5.305E+05 0.000E+00 I-135 7.918E+05 2.9475+06 .9 .104E l CS-134 1.014E+06 8.0075+09 1.180E+09 CS-136 1.7095+05 1.702E+08 3.452E+07 8
CS-137 9.065E+05 1.201E+10 1.040E+09
! CS-138 8.399E+02 4.102E+05 0.000E+00 I' EA-139 5.772E+04 1.194E+05 0.000E+00 RA-140 1.743E+06 2.346E+07 3.420E+07 RA-141 2.919E+03 4.734E+04 0.000E+00 RA-142 1.643E+03 5.064E+04 0.000E+00 LA-140 2.257E+05 2.180E+07 4.284E+02 LA-142 7.585E+04 8.886E+05 0.000E+00 CE-141 5.439E+05 1.540E+07 1.0785+07 CE-143 1.273E+05 2.627E+06 1.963E+02 CE-144 1.195E+07 8.032E+07 1.476E+08 PR-143 4.329E+05 0.000E+00 2.815E+07 PR-144 1.565E+03 2.112E+03 0.000E+00 ND-147 3.282E+05 1.0035+07 1.174E+07 W-107 9.102E+04 2.740E+06 2.1765+00 NP-239 6.401E+04 1.976E+06 1.741E+03 3
Units: Inhalationgand all t.ritium pathways - mren/yr per pCi/m Others m , mren/yr per pCi/sec values base'd on standard NUREG-0133, Section 5.3.1 r.ssumpticus unless otherwise indicated.
- - Meat consumption assumed 75 percent beef and 25 percent muttoa.
j I
. . )
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GRAND GULF, UNIT 1 2.0-14 Revision 17 - 03/95 l
- . . .-. - -. - . . _ - . . . - - - - - - .. - .. - . - - ..- ~ - .
~
! TABLE 21-2a l
PATHWAY DQSE FACTORS FOR LCQ 6.11.6 AND
. SECTION 2.2.2.b, (R )
$ Page 1 of 2
- Af2E MAUP ( INFANT ) ( N.A. ) ( INFANT ) ( IMFANT ) ( ihmMT )
ISOTOPE I'K"4 7* 0.000E+00 l
j -H-3 6.po s2 0.000E+00 2.382E+03 0.000E+00 i
- C-14 2.L!6Y+04 0.000E+00 2.340E+09 0.000E+00 0.000E+00 i NA-24 1.064E+04 ~ 1.385E+07 1.542E+07 0.000E+00 0.000E+00 l P-32 2.030E+06 0.000E+00 1.632E+11 0.000E+00 0.000E+00 3 CR-51 1.284E+04 5.5065+06 4.700E+06 0.000E+00 0.000E+00 i MN-54 9.996E+05 1.625E+09 3.900E+07 0.000E+00 0.000C+00 1 i MN-56 7.168E+04 1.068E+06 2.862E+00 0.000E+00 0.000E+00 FE-55 8.694E+04 0.000E+00 1.351E+08 0.000E+00 0.000E+00 l
! FE-59 1.015E+06 3.204E+08 3.919E+08 0.000E+00 0.000E+00 j' CO-58 7.770E+05 4.464E+08 6.055E+07 0.000E+00 0.000E+00 l t CO-60 4.508E+06 2.532E+10 2.098E+08 0.000E+00 0.000E+00 l 4 NI-63 3.388E+05 0.000E+00 3.493E+10 0.000E+00 0.000E+00 l 4
NI-65 5.012E+04 3.451E+05 3.020E+01 0.000E+00 0.000E+00 ;
i CU-64 1.498E+04 6.876E+05 3.0075+06 0.000E+00 0.000E+00 j EN-65 6.468E+05 8.583E+08 1.904E+10 0.000E+00 0.000E+00 ZN-69 1.322E+04 0.000E+00 3.855E-09 0.000E+00 0.000E+00
- .BR-83 3.8085+02 7.079E+03 9.3393-01 0
- 000E+00 0.000E+00 l l ER-84 4.004E+02 2.363E+05 1.256E-22 0.000E+00 0.000E+00 l l- ER-85 2.044E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00
- 1. RE-86 1.904E+05 1.035E+07 2.234E+10 0.000E+00 0.000E+00 i l RE-88 5.572E+02 3.7795+04 1.874E-44 0.000E+00 0.000E+00 1
- RE-89 3.206E+02 1.452E+05 4.193E 0.000E+00 0.000E+00 4
! SR-89 2.030E+06 2.509E+04 1.258E+10 0.000E+00 0.000E+00 I SR-90 4.088E+07 0.000E+00 1.2163+11 0.000E+00 0.000E+00 )
SR-91 7.336E+04 2.511E+06 3.215E+05 0.000E+00 0.000E+00 J SR-92 1.400E+05 8.631E+05 5.005E+01 0.000E+00 0.000E+00 Y-90 2.688E+05 5.300E+03 9.406E+05 0.000E+00 0.000E+00 Y-91M 2.786E+03 1.161E+05 1.876E-15 . 0.000E+00 0.000E+00 Y-91 2.450E+06 1.207E+06 5.251E+06 0.000E+00 0.000E+00 ,
Y-92 1.266E+05 2.142E+05 1.026E+01 0.000E+00 0.000E+00 i Y-93 1.666E+05 2.534E+05 1.7765+04 0.000E+00 0.000E+00
- i ZR-95 1.750E+06 2.8375+08 8.257E+05 0.000E+00 0.000E+00 ZR-97 1.400E+05 3.445E+06 4.446E+04 0.000E+00 0.000E+00 I NE-95 4.7885+05 1.605E+08 2.062E+08 0.000E+00 0.000E+00 MO-99 1.340E+05 4.626E+06 3.100E+08 0.000E+00 0.000E,00 TC-99M 2.030E+03 2.109E+05 1.646E+04 0.000E+00 0.000E+00 TC-101 8.442E+02 2.277E+04 1.423E-56 0.000E+00 0.000E+00 RU-103 5.516E+05 1.265E+08 1.055E+05 0.000E+00 0.000E+00 RU-105 4.844E+04 - 7. 212E+0 5 - 3.204E+00 0.000E+00 0.000E+00 RU-106 1.156E+07 5.049E+08 1.445E+06 0.000E+00 0.000E+00 AG-110M 3.668E+06 4.019E+09 1.461E+10 0.000E+00 0.000E+00
)
GRAND GULF, UNIT 1 2.0-15' Revision 17 - 03/95
_ _ _ _ _ . . . _ . . _ . __ . - _ _ _ . _ . - . _ . _ . _ _ _ . . _ _ _ . _ .._._.._._..._-,___.,.m. .-_m.. . . . . . . ,_
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l TAmt.F 2.2 2a (Cont 4 mmd)
PATHWAY DQSE FACTORS FOR LCO 6.11.6 ANQ SECTION 2.2.2.b, (R )
g Page 2 of 2 AGE aantfp ( INFANT ) ( N.A. ) ( imiFaNT ) ( uwidrf ) ( INFANT )
ISOTOPE TWAY ATION nenNn Pf mm MS/ CON / MILK M S/ CON / MEAT VEGETATION TE-125M 4.466E+05 2.128E+06 1.5085+08 0.000E+00 0.000E+00 TE-127M 1.312E+06 1.083E+05 1.037E+0p 0.000E+00 0.000E+00 TI-127 2.436E+04 3.293E+03 1.359E+05 0.000E+00 0.000E+00 TE-129M 1.680E+06 2.305E+07 1.392E+09 0.000E+00 0.000E+00 TE-129 2.632E+04 3.076E+04 1.6785-07 0.000E+00 0.000E+00 TE-131M 1.9me2+05 9.459E+06 2.288E+07 0.000E+00 0.000E+00 TE-131 8.218E+03 3.450E+07 1.384E-30 0.000E+00 0.000E+00 TL-132 3.402E+05 4.9685+06 6.513E+07 0.000E+00 0.000E+00 I-130 1.596E+06 6.692E+06 8.754E+08 0.000E+00 0.000E+00 I-131 1.484E+07 2.0895+07 1.053E+12 0.000E+00 0.000E+00 I-132 1.694E+05 1.452E+06 1.1883+02 0.000E+00 0.000E+00 I-133 3.556E+06 2.981E+06 9.601E+09 0.000E+00 0.000E+00 I-134 4.452E+04 5.305E+05 8.4025-1C 0.000E+00 0.000E+00 '
I-135 6.9583+05 2.9475+0G 2.002E+07 0.000E+00 0.000E+00 CS-134 7.028E+05 8.007E+09 6.001E+10 0.000E+00 0.000E+00 CS-136 1.345E+05 1.702E+08 5.795E+09 0.000E+00 0.000E+00 CS-137 6.1185+05 1.201E+10 6.024E+10 0.000E+00 0.000E+00
. CS-138 -8.764E+02 4.102E+05 2.180E-22 0.000E+00 0.000E+00 BA-139 5.096E+04 1.194E+05 2.8745-05 0.000E+00 0.000E+00 BA-140 1.596E+06 2.346E+07 2.410B+08 0.000E+00 0.000E+00 RA-141 4.746E+03 4.734E+04 3.1415-44 0.000E+00 0.000E+00 RA-142 1.554E+03 5.064E+04 0.000E+00 0.000E+00 0.000E+00 LA-140 1.680E+05 2.180E+07 1.880E+05 0.000E+00 0.000E+00
-LA-142 5.950E+04 8.886E+05 6.019E-06 0.000E+00 0.000E+00 CE-141 5.166E+05 1.540E+07 1.366E+07 0.000E+00 0.000E+00 CE-143 1.162E+05 2.627E+06 1.5365+06 0.000E+00 0.000E+00 CE-144 9.842E+06 8.032E+07 1.334E+08 0.000E+00 0.000E+00 PR-143 4.3265+05 0.000E+00 7.845E+05 0.000E+00 0.000E+00 PR-144 4.284E+03 2.112E+03 1.171E-48 0.000E+00 0.000E+00
-ND-147 3.220E+05 1.009E+07 5.743E+05 0.000E+00- 0.000E+00 W-187 3.962E+04 2.740E+06 2.501E+06 0.000E+00 0.000E+00 NP-239 5.950E+04 1.9765+06 9.400E+04 0.000E+00 0.000E+00 Units: Inhalation 2and all tritium pathways - mrom/yr per pCi/m others - m . mres/yr per pC1/sec values based on standard NUEEG-0133, Section 5.3.1 assumptions unless otherwise indicated. ,
' GRAND GULF, UNIT 1 2.0-16 Revision 17 - 03/95
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4 TAnLE 2.2-2b I PATHWAY DOSE FACTORS FOR LCO 6.11.6 ggg l SECTION 2.2.2.b, (Rg)
. I i Page 1 of 2 j i
AGE GROUP ( CHILD ) ( N.A. ) ( ENTLD ) ( CHILD ) ( CHILD )
ISOTOPE INH _1Y1 TION GROrwn pt2mm ame/ COW /MTLK CDC/ COW / MEAT VEGETATION i H-3 1.125E+03 0.000E+00 1.570E+03 2.341E+02 4.008E+03 i C-14 3.589E+04 0.000E+00 1.195E+09 3.834E+08 8.894E+08 NA-24 1.610E+04 1.385E+07 8.853E+06 1.725E-03 3.729E+05 l P-32 2.605E+06 0.000E+00 7.775E+10 7.411E+09 3.366E+09 I i CR-51 1.698E+04 5.506E+06 5.398E+06 4.661E+05 6.213E+06 i MN-54 1.576E+06 1.625E+09 2.0975+07 8.011E+06 6.648E+08
, MN-56 1.232E+05 1.068E+06 1.865E+00 2.437E-51 2.723E+03 l
- FE-55 1.110E+05 0.000E+00 1.118E+08 4.571E+08 8.012E+08 1.269E+06 3.204E+08 2.025E+08 6.338E+08 6.693E+08 FE-59 l 4 CO-58 1.106E+06 4.464E+08 7.080E+07 9.596E+07 3.771E+08 l i
CO-60 7.0675+06 2.532E+10 2.391E+08 3.838E+08 2.095E+09
. NI-63 8.214E+05 0.000E+00 2.964E+10 2.912E+10 3.949E+10 NI-65 8.399E+04 3.451E+05 1.909E+01 4.061E-51 1.211E+03 CU-64 3.670E+04 6.876E+05 3.502E+06 1.393E-05 5.159E+0S 3
ZN-65 9.953E+05 8.583E+08 1.101E+10 1.000E+09 2.164E+09
- ZN-69 1.018E+04 0.000E+00 1.1235-09 0.000E+00 9.8935-04 l
! BR-83 4.736E+02 7.079E+03 4.399E-01 9.519E-57 5.3695+00 J BR-84 5.476E+02 2.363E+05 6.508E-23 0.000E+00 3.8223-11 BR-85 2.531E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00
- RB-86 1.983E+05 1.035E+07 8.804E+09 5.816E+08 4.584E+08 RB-88 5.624E+02 3.779E+04 7.150E-45 0.000E+00 4.374E-22 RB-89 3.452E+02 1.452E+05 1.715E-53 0.000E+00 1.642E-25 SR-89 '2.157E+06 2.509E+04 6.618E+09 4.815E+08 3.593E+10 4 SR-90 1.010E+08 0.000E+00 1.117E+11 1.040E+10 1.243E+12 SR-91 1.739E+05 2.511E+06 2.878E+05 5.292E-10 1.157E+06 I- SR-92 2.424E+05 8.631E+05 4.134E+01 3.492E-48 1.378E+04
> Y-90 2.679E+05 5.308E+03 9.171E+05 4.879E+05 6.5$3E+07 Y-91M 2.812E+03 1.161E+05 5.198E-16 0.000E+00 1.737E-05 2
Y-91 2.627E+06 1.207E+06 5.1995+06 2.400E+08 2.484E+09 Y-92 2.390E+05 2.142E+05 7.310E+00 6.959E-35 4.5765+04
, Y-93 3.885E+05 2.534E+05 1.573E+04 1.547E-07 4.482E+06 ZR-95 2.231E+06 2.837E+08 8.786E+05 6.106E+08 8.843E+08 ZR-97 3.511E+05 3.445E+06 4.199E+04 7.015E-01 1.248E+07 NB-95 6.*142E+05 1.605E+08 2.287E+08 2.228E+09 2.949E+08 1 MO-99 1.354E+05 4.626E+06 1.738E+08 2.456E+05 1.647E+07
' 1.474E+04 5.255E+03 TC-9971 4.810E+03 2.109E+05 6.915E-18 TC-101 5.54GE+02 2.277E+04 5.593E-58 0.000E+00 4.123E-29 RU-103 6.623E+05 1.265E+08 1.108E+05 4.009E+09 3.971E+08 RU-105 9.953E+04 - 7.212E+05 2.493E+00 5.885E-25 5.981E+04 i RU-106 1.432E+07 5.049E+08 1.437E+06 6.902E+10 1.159E+10 l AG-110M 5.476E+06 4.019E+09 1.678E+10 6.7422+01 2.581E+09 i
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b GRAND GULF, UNIT 1 2.0-17 ,
Revision 17 - 03/95
. ._. . . . _ _ . . - - . - _ _ ., .. ~. .__ - - - - ._. .. .
1 T_ mare 2.2-2b (continued)
PATHWAY DOSE FACTORS FOR LCO 6.11.6 Al{p l SECTION 2.2.2.b, (Rg )
Page 2 of 2 AGE GROUP ( CHILD ) ( N.A. ) ( ENTLD ) ( CHILD ) ( CHILD )
ME INHafATION GROF 1htm PfMW MC/ COW /MiiX GRS/ COW / MEAT VEGETATION TE-125M 4.773E+05 2.128E+06 7.377E+07 5.690E+08 3.506E+08 TE-127M 1.480E+06 1.083E+05- 5.932E+08 5.060E+09 3.769E+09 i l .TE-127 S.624E+04 3.293E+03 1.191E+05 1.607E-08 3.903E+05 TE-129M 1.761E+06 2.305E+07 7.961E+08 5.245E+09 2.460E+09 TE-129 2.549E+04 3.076E+04 6.166E-08 0.000E+00 7.204E-02 TE-131M 3.078E+05 9.459E+06 2.244E+07 9.815E+03 2.163E+07 TE-131 2.054E+03 3.450E+07 8.489E-32 0.000E+00 1.349E-14 i TE-132 3.774E+05 4.968E+06 4.551E+07 9.325E+06 3.111E+07 I-130 1.846E+06 6.692E+06 3.845E+08 6.758E-04 1.370E+08 I-131 1.624E+07 2.0095+07 4.333E+11 5.503E+09 4.754E+10 4
I-132 1.935E+05 1.452E+06 5.129E+01 2.429E-57 7.314E+03 i I-133 3.848E+06 2.981E+06 3.945E+09 1.304E+02 8.113E+08 a
I-134 5.069E+04 5.305E+05 3.624E-10 0.000E+00 6.622E-03 s I-135 7.918E+05 2.947E+06 8.607E+06 1.039E-14 9.973E+06
- CS-134 1.0143+06 8.0075+09 3.715E+10 1.513E+09 2.6I1E+10 CS-136 1.7095+05 1.702E+08 2.773E+09 4.426E+07 2.2475+08
- CS-137 9.06f E+0f, 1.201E+10 3.224E+10 1.334E+09 2.392E+10
, CS-138 8 . 3 9 fiE+ 0 2 4.102E+05 5.528E-23 0.000E+00 9.133E-11 RA-139 5.77'tE+64
. 1.194E+05 1.231E-05 0.000E+00 2.950E+00 RA-140 1.743E+06 2.346E+07 1.171E+08 4.384E+07 2.767E+08 4
RA-141 2.919E+03 4.734E+04 1.210E-45 0.000E+00 1.605E-21 RA-142 1.643E+03 5.064E+04 0.000E+00 0.000E+00 4.105E-39 LA-140 2.257E+05 2.180E+07 1.894E+05 5.492E+02 3.166E+07 j LA-142 7.585E+04 8.886E+05 2.904E-06 0.000E+00 1.582E+01
! CE-141 5.439E+05 1.540E+07 1.361E+07 1.382E+07 4.082E+08 l CE-143 1.273E+05 2.627E+06 1.488E+06 2.516E+02 1.364E+07
, CE-144 1.195E+07 8.032E+07 1.326E+08 1.893E+08 1.039E+10 1 PR-143 *4.329E+05 0.000E+00 7.754E+05 3.609E+07 1.575E+08 i PR-144 1.565E+03 2.112E+03 2.040E-50 0.000E+00 3.8295-23 ND-147 3.282E+05 1.009E+07 5.712E+05 1.505E+07 9.197E+07
< W-187 9.102E+04 2.740E+06 2.420E+06 2.790E+00 5.300E+06
- NP-239 6.401E+04 1.976E+06 9.130E+04 2.232E+03 1.357E+07
' 3 j Units: Inhalation 2and all tritium pathways - mrea/yr per pCi/m others - m . mrom/yr per pCi/sec i
i Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise
- indicated.
~
l 1
i j
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GRAND GULF, UNIT 1 2.0-18 Revision 17 - 03/95
_ _ _ . . _ . . ._ . _ . . . .- . ._. . _ _ _ , . _ _ . . . ~ ~ _ _ -.
t i
TAatr 2.2-2e j PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND I
SECTION 2.2.2.b, (R )
Page 1 of 2 AGE donUP (TEENAdfD) ( N.A. ) (Turunnen) (TerunctD) (1miMAGER)
- ISOTOPE INunf2 TION GROrnm prium non / COW /MILit ann / COW / MEAT VEGETATION H-3 1.272E+03 0.000E+00 9.941E+02 1.938E+02 2.588E+03 C-14 2.600E+04 0.000E+00 4.8595+08 2.040E+08 3.690E+08 NA-24 1.3765+04 1.385E+07 4.255E+06 1.004E-03 ~ 2.389E+05
, P-32 1.888E+06 0.000E+00 3.153E+10 3.931E+09 1.601E+09 CR-51 2.096E+04 5.506E+06 8.387E+06 9.471E+05 1.0311+07 4 MN-54 1.984E+06 1.625E+09 2.875E+07 1.43G +07 9.320Et09 !
i MN-56 5.744E+04 1.068E+06 4.856E 01 8.302E-52 9.451E+02
~
FE-55 1.240E+05 0.000E+00 4.454E+07 2.382E+08 3.259E+08 FE-59 1.528E+06 3.204E+08 2.861E+08 1.171E+09 9.895E+08 CO-58 1.344E+06 4.464E+08 1.095E+08 1.942E+08 6.034E+08 CO-60 8.720E+06 2.532E+10 3.621E+08 7.600E+08 3.230E+09
- NI-63 5.800E+05 0.000E+00 1.182E+10 1.519E+10 1.606E+10 NI-65 3.672E+04 3.451E+05 4.692E+00 1.305E-51 3.966E+02 i CU-64 6.144E+04 5.876E+05 3.293E+06 1.713E-05 6.465E+05 ZN-65 1.240E+06 S.583E+08 7.315E+09 8.688E+08 1.471E+09 ZN-69 1.584E+03 0.000E+00 1.760E-11 0.000E+00 2.067E-05 BR-83 3.440E+02 7.079E+03 1.790E-01 5 .~0665 - 57 2.911E+00
- BR-84 4.328E+02 2.363E+05 2.877E-23 0.000E+00 2.2515-11
) BR-85 1.832E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 1.904E+05 1.035E+07 4.746E+09 4.101E+08 2.772E+08 RB-88 5.456E+02 3.779E+04 3.086E-45 0.000E+00 3.168E-22 RB-89 3.520E+02 1.452E+05 9.774E-54 0.000E+00 1.247E-26 SR-89 2.416E+06 2.509E+04 2.674E+09 2.545E+08 1.513E+10 SR-90 1.000E+08 0.000E+00 6.612E+10 8.049E+09 7.507E+11 4 SR-91 2.592E+05 2.511E+06 2.409E+05 5.794E-10 1.291E+06 i SR-92 1.192E+05 8.631E+05 2.277E+01 2.516E-48 1.012E+04 i Y-90 5.592E+05 5.308E+03 1.074E+06 7.470E+05 1.025E+08 Y-91M 3.200E+03 1.161E+05 5.129E-18 0.000E+00 2.285E-07
- Y-91 2.936E+06 1.207E+06 6.475E+06 3.910E+08 3.212E+09 Y-92 1.648E+03 2.142E+05 '2.828E+00 3.522E-35 2.360E+04 Y-93 5.792E+05 2.534E+05 1.312E+04 1.688E-07 4.983E+06 ZR-95 2.6885+06 2.837E+08 1.201E+06 1.092E+09 1.253E+09
- ZR-97 6.304E+05 3.445E+06 4.225E+04 9.231E-01 1.673E+07
~
NB-95 7.512E+05 1.605E+08 3.3383+08 4.251E+09 4.551E+08 j MO-99 2.688E+05 4.626E+06 1.023E+08 1.892E+05 1.293E+07 TC-99M 6.128E+03 2.109E+05 1.055E+04 6.471E-18 5.011E+03 TC-101 6.672E+02 2.277E+04 3.287E 0.000E+00 3.229E-29 RU-103 7.832E+05 1.205E+08 1.513E+05 7.162E+09 5.706E+08 RU-105 9.040E+04 -7.212E+05 '1.263E+00 3.900E-25 4.039E+04 RU-106 1.6085+07 5.049E+08 1.799E+06 1.130E+11 1.484E+10 AG-110M 6.752E+06 4.0195+09 2.559E+10 1.345E+0F 4.031E+09 i 1
GRAND GULF, UNIT 1 2.0-19 Revision 17 - 03/95
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Tant.E 2.2-2e (Criti m ad) !
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PATNWAY DOSE FACTOR.S FOR LCO 6.11.6 AND SECTION 2.2.2.b, (Rg) l Page 2 of 2
. AGE amoup (Tewmaen) ( N,A. ) (1 aaaen) h. aiarn; ( Tisiawst )
ISOTCPE INW17ATION GRON n PT WR ame/ CON /Mii.x ann / COW / MEAT ViudiATION TE-125M 5.360E+05 2.128E+06 8.863E+07 8.941E+08 4.375E+08 TE-127M 1.6565+06 1.083E+05 3.420E+08 3.815E+09 2.236E+09 TI-127 8.080E+04 3.293E+03 9.572E+04 1.689E-08 4.180E+05 TE-129M 1.976E+06 2.305E+07 4.602E+08 3.966E+09 1.508E+09 TE-129 3.296E+03 3.076E+04 2.196E-09 0.000E+00 3.418E-03 i TE-131M 6.200E+05 9.4595+06 2.5295+07 1.447E+04 3.248E+07 -J i TE-131 2.336E+03 3.4F0E+07 2.879E-32 0.000E+00 6.099E-15 i TE-132 4.632E+05 4.9685+06 8.581E+07 2.300E+07 7.818E+07 I-130 1.488E+06 6.692E+06 1.742E+08 4.005E-04 8.276E+07 I-131 1.464E+07 2.089E+07 2.195E+11 3.645E+09 3.140E+10 I-132 1.512E+05 1.452E+06 2.242E+01 1.389E-57 4.262E+03
- I-133 2.920E+06 2.981E+06 1.674E+09 7.234E+01 4.587E+08
- I-134 3.952E+04 5.305E+05 1.583E-10 0.000E+00 3.8545-03 I-135 6.200E+05 2.947E+06 3.777E+06 5.963E-15 5.832E+06 CS-134 1.128E+06 2.007E+09 2.310E+10 1.231E+09 1.671E+10 .
CS-136 -1.936E+05 1.702E+08 1.759E+09 3.671E+07 1.7085+08
, CS-137 8.480E+05 1.201E+10 1.781E+10 9.634E+08 1.3485+10 CS-138 8.560E+02 4.102E+05 3.1495-23 0.00CI+00 6.9355-11 ,
RA-139 6.464E+03 1.194E+05 7.7415-07 0.000E+00 2.4725-01 RA-140 2.032E+06 2.346E+07 7.483E+07 3.663E+07 2.130E+08 1 RA-141 3.2885+03 4.734E+04 4.9225-46 0.000E+00 8.6995-22 l BA-142 1.912E+03 5.064E+04 0.000E+00 0.000E+00 2.269E-39 LA-140 4.872E+05 2.180E+07 2.291E+05 0.689E+02 5.104E+07 LA-142 1.200E+04 8.886E+05 2.574E-07 0.000E+00 1.868E+00 CE-141 6.135E+05 1.540E+07 1.696E+07 2.252E+07 5.404E+08 CE-143 2.552E+05 2.6273+06 1.671E+06 3.695E+02 2.040E+07 CE-144 1.3365+07 8.032E+07 1.655E+08 3.089E+08 1.326E+10 PR-143 4.832E+05 0.000E+00 9.553E+05 5.817E+07 2.310E+08 PR-144 1.752E+03 2.112E+03 1.2385-53 0.000E+00 3.097E-26 ND-147 3.720E+05 1.009E+07 7.116E+05 2.452E+07 1.424E+08 W-187 1.768E+05 2.740E+06 2.646E+06 3.989E+00 7.839E+06 NP-239 1.320E+05 1.976E+06 1.060E+05 3.387E+03' 2.0975+07 Units: Inhalation 2and all tritium pathways arem/yr per pci/m others - a . mrem /yr per pCi/sec values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.
l I
GRAND GULF, UNIT 1 2.0-20 R'evision 17 - 03/95 l
..m .~- . _ .m. _ ._ _ . _ . _ . _ . _ ._ .. _ . _ . _ _ _ _ . _ _ _ . - . _ _ _ . _ _ . . _ _ _ . . _ . _ .
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1 e
~
I l Tint.m 2.2-2d i
i PATintAY fman Fac'fnme FOR tm g _ ii, g mun SECTION 2.2.2.b, (Rg)
I Page 1.of 2 I
{ AGE am-4 f ADtTLT ) ( M. A. 1 ( ifWTT.T ) f_@T ) ( ADtff.T )
tsararmeron aa . _. , or == naa /com/trrt.r gy4/M VIGITATICE
[ TiiMOPE 1.264E+03 0.000E+00 7.6293+02 3.2483+02 2.260E+03 i H-3 j C 14 1.8165+04 0.000E+00 2.634E+08 2.414E+04 2.2765+08 NA-24 1.024E+04 1.385E+07 2.4385+06 1.3565 03 2.690E+05 P-32 1.320E+06 0.000E+00 1.7095+10 4.6515+09 1.403E+09 i CR 51 1.440R+04 5.5065+06 7.1875+06 1.772E+06 1.1685+07 1 MN 54 1.400E+06 1.625E+09 2.5785+07 2.812E+07 9.585E+08 MN 56 2.024E+04 -1.0685+06 1.3285-01 4.9585 52 5.082E+02 j FI-55 7.2085+04 0.000E+00 2.5115+07 2.933E+08 2.096E+08 FE 59 1.0165+06 3.204E+08 2.3265+08 2.080E+09 9.875E+08 1 CO 58 9.280E+05 4.464E+08 9.565E+07 3.703E+08 6.252E+08 I CO-60 5.9685+06 2.532E+10 3.002E+08 1.413E+09 3.1393+09 NI-63 4.320E+05 0.000E+00 6.7295+09 1.884E+10 1.040E+10 l NI-65 1.232E+04 3.4515+05 1.2195+00 7.4053 52 2.0265+02 l CD-64 4.8965+04 6.8765+05 2.0315+06 2.3073-05 7.841E+05
- ZN 65 8.640E+05 8.583E+08 4.365E+09 1.132E+09 1.0095+09 i ZN 69 9.200E+C2 0.000E+00 5.2073-12 0.000E+00 1.2025-05 l
~
ER 83 2.4085+02 7.0793+03 1.3995 01 8;6485 57 4.475E+00 i
!* ER 84 3.1285+02 2.363E+05 1.6093-23 0.000E+00 2.4755 l l ER-85 1.280E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l RB-86 1.352E+05 1.035E+07 2.604E+09 4.914E+08 2.2175+08 i
RB 58 3.872E+02 3.7795+04 2.1395-45 0.000E+00 3.4283-22
. RB-89 2.560E+02 1.452E+05 5.5235 54 0.000E+00 1.3855 26 l- SR-89 1.400E+06 2.5095+04 1.451E+09 3.014E+08- 9.961E+09 SR-90 9.920E+07 0.000E+00 4.680E+10 1.244E+10 6.0465+11
! 1.451E+06
!: SR 91 1.912E+05 2.511E+06 1.3773+05 7.2333-10 1 SR-92 4.304E+04 8.631E+05 9.675E+00 2.3345-48 8.452E+03<
I- Y 90 5.0565+05 5.3083+03 7.5115+05 1.141E+06 1.410E+08 f Y-91M 1.520E+03 1.161E+05 1.7435-19 '0.000E+00 1.5273 08 Y 91 1.704E+06 1.2075+06 4.7265+06 6.231E+08 2.814E+09 l
i Y 92 7.352E+04 2.142E+05 9.7725-01 '2.6575-35 1.603E+04 3 Y-93 4.2165+05 2.534E+05 7.3885+03 2.0755 07 5.5175+06
! ZR-95 1.7685+06 2.8375+08 9.5875+05 1.903E+09 1.194E+09 ZR 97 5.232E+05 3.445E+06 2.7075+04 1.292E+00 2.1085+07 NB 95 5.0483+05 1.605E+08 2.7865+08 7.7485+09 4.7985+08 l 5.741E+07 2.3185+05 1.4263+07
- MD 99 2.480E+05 4.6265+06
! TC 99M 4.160E+03 2.1095+05 5.553E+03 7.4395-18 5.1873+03 8- TC-101 3.992E+02 2.2775+04 1.8135-58 0.000E+00 3.5025 29 RU-103 5.0483+05 1.265E+08 1.1895+05 1.229E+10 5.577E+08 i 3.294E+04
? RU 105- 4.8165+04 - 7.212E+05 5.2403 01 3.5335 25 i RU 106 9.360E+06 5.0495+08 1.320E+06 1.811E+11 1.2475+10 AG 110M 4.631E+06 4.0195+09 2.198E+10 2.523E+09 3.9795+09
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1 GRAND QULF, UNIT 1 2.0-21 Revision 17 - 03/95
!l
.g .
, . . .__ . . - - ~ _ . _ _ _ _ . . _ _ _ _ _ _ _ _ _. _
l TABLE 2.2-2d (Continued)
PATHWAY DOSE FACTORS FOR LCO 6.11.6 AND SECTION 2.2.2.b, (R )
'vage 2 of 2 AGE GROUP ( ADULT ) ( N. A. ) ( ADULT )# ( ADULT ) ( ADULT )
ISOTOPE INHALATION GROUND PLANE GRS/ COW / MILK GRS/ COW / MEAT VEGETATION TE-125M 3.136E+05 2.128E+0f 6.626E+07 1.460E+09 3.927E+08 TE-127M 9.600E+05 1.083E+05 1.860E+08 4.531E+09 1.418E+09 TE-127 5.736E+04 3.293E+03 5.278E+04 2.034E-08 4.532E+05 TE-129M 1.160E+06 2.305E+07 3.028I+08 5.698E+09 1.261E+09 TE-129 1.936E+03 3.076E+04 9.167E-10 0.000E+00 2.806E-03 TE-131M 5.560E+05 9.459E+06 1.753E+07 2.190E+04 4.428E+07 TE-131 1.392E+03 3.450E+07 1.578E-32 0.000E+00 6.575E-15 TE-132 5.096E+05 4.968E+06 7.324E+07 4.287E+07 1.312E+08 I-130 1.136E+06 6.692E+06 1.050E+08 5.272E-04 9.809E+07 I-131 1.192E+07 2.089E+07 1.388E+11 5.034E+09 3.785E+10 I-132 1.144E+05 1.452E+06 1.342E+01 1.816E-57 5.016E+03 I-133 2.152E+06 2.981E+06 9.891E+08 9.336E+01 5.331E+08 I-134 2.984E+04 5.305E+05 9.4915-11 0.000E+00 4.544E-03 I-135 4.480E+05 2.947E+06 2.217E+06 7.644E-15 6.731E+06 CS-134 8.480E+05 8.007E+09 1.345E+10 1.565E+09 1.110E+10 CS-136 1.464E+05 1.702E+08 1.036E+09 4.724E+07 1.675E+08 ,
CS-137 6.208E+05 1.201E+10 1.010E+10 1.193E+09 8.696E+09 !
CS-138 6.208E+02 4.102E+05 1.786E-23 0.000E+00 7.730E-11 BA-139 3.760E+03 1.194E+05 8.322E-08 0.000E+00 5.2255-02 BA-140 1.272E+06 2.346E+07 5.535E+07 5.917E+07 2.646E+08 BA-141 1.936E+03 4.734E+04 2.677E-46 0.000E+00 9.305E-22 j RA-142 1.192E+03 5.064E+04 0.000E+00 0.000E+00 2.463E-39 l LA-140 4.584E+05 2.180E+07 1.672E+05 1.385E+03 7.327E+07 i LA-142 6.32RE+03 8.886E+05 3.503E-08 0.000E+00 4.999E-01 l CE-141 3.616E+05 1.540E+07 1.253E+07 3.632E+07 5.097E+08 1 CE-143 2.264E+05 2.627E+06 1.149E+06 5.547E+02 2.758E+07 CE-144 7.776E+06 8.032E+07 1.209E+08 4.928E+08 1.112E+10 PR-143 2.808E+05 0.000E+00 6.923E+05 9.204E+07 2.748E+08 PR-144 1.016E+03 2.112E+03 6.716E-54 0.000E+00 3.303E-26 ND-147 2.208E+05 1.009E+07 5.231E+05 3.935E+07 1.853E+08 W-187 1.552E+05 2.740E+06 1.796E+06 5.912E+00 1.046E+07 NP-239 1.192E+05 1.976E+06 7.385E+04 5.152E+03 2.872E+07 Units: Inhalation2 and all tritium pathways - mram/yr per pCi/m Others - m . mrom/yr per pCi/sec Values based on standard NUREG-0133, Section 5.3.1 assumptions unless otherwise indicated.
GRAND GULF, UNIT 1 2.0-22 Revision 17 - 03/95
I l
l 4 TABLE 2.2-3 CONTROLLING RECEPTORS, LOCATIONS, AND ATMOSPHERIC DISPERSION PARAMETERS
- for LCO 6.11.5. 6.11.6, AND 6.11.8 NEAREST RESIDENCE, NEAREST SECTOR DIRECTION MILES ** D/Q x/Q D/Q GARDEN,
- MILES **
A N 0.92 6.3E-9 3.30E-6 >5 N/A B NNE 0.75 6.18E-9 2.95E-6 >5 N/A l
__C NE 0.66 6.1E-9 2.30E-6 4.78 2.18E-10 j D ENE 2.67 4.9E-10 2.00E-7 2.8 4.90E-10
, .E E 0.81 2.96E-9 1.60E-6 0.81 2.96E-09
)
F ESE 2.3 6.5E-10 2.57E-7 >5 N/A G SE 2.11 7.7E-10 3.10E-7 >5 N/A I H SSE 1.13 3.6E-9 1.40E-6 3.7 4.98E-10 J S 3.11 7.65E-10 4.95E-7 >5 N/A K SSW 2.17 1.3E-9 1.40E-6 2.17 1.30E-9 L SW 0.89 6.7E-9 8.30E-6 0.89 6.70E-9 l M WSW >5 N/A N/A >5 N/A N W >5 N/A N/A >5 N/A P WNW 4.78 2.3E-10 4.73E-7 4.78 2.30E-10 Q NW 35 N/A N/A >5 N/A R NNW 1.08 3.6E-9 2.60E-6 >5 N/A Table 2.2-3 based on 1995 Land Use Census, onsite gardens are not considered for the Land Use Census.
The most limiting age group, child, is assumed.
Values from ODCM Reference 9.
Distances shown are actual miles in each sector. In c.ses where dispersion parameters were not available for a location they were taken from tb2 closest distance interval to the plant.
N/A: No residence / garden within 5 miles.
GRAND GULF, UNIT 1 2.0-23 Revision 18 - 02/96
_ _ _ _ , _ _ , _ . . _ . . . _ . _ _ _ _ _ _ _ _ _ _ . _ - . . m.___...__,. ._,.-_____.m. _ _ __ _ _ _..__ _ ..
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9 TARM 2.2-3a 1
! SITE BOUNDARY ATNOSPHERIC DISPERSION PARAMETERS
- l for LCO 6.11.4 SITE BOUNDARY DISTANCE, SECTOR DIRECTION MILES ** x/Q D/Q l
j A N 0.79 4.1E-6 8.2E-9
?
! B NNE 0.66 3.6E-6 7.7E-9 j C NE 0.63 2.5E-6 6.6E-9
' 5.es-9 D ENE 0.63 2.0E-6 E E 0.55 1.9E-6 4.9E-9 i F ESE 0.55 2.0E-6 5.9E-9 I
G SE 0.51 2.8E-6 8.2E-9 l
H SSE 0.46 5.6E-6 1.6E-6 l '
l J S 0.61 5.sE-6 1.2E-s I
! K SSN 0.65 0.4E-6 1.0E-S
{- L SW 0.85 8.9E-6 7.2E-9 M WSW 1.07 8.4E-6 5.1E-9
[
l- N W 1.14 5.4E-6 3.4E-9
' l l P WNW 1.34 2.6E-6 1.9E-9 l
Q NW 1.37 1.6E-6 1.6E-9 j R NNW 1.02 2.05-6 4.03-9 1
I i The most limiting age group, infant, is assumed.
!
- Values from ODCM Reference 9.
$ ** Distances shown are actual miles in each sector.
I
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{ GRAND GULF, UNIT 1 2.0-23a Revision 17 - 03/95 l
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I TABLE 2.2-3b ADDITIONAL RECEPTOR LOCATIONS WITHIN THE SITE BOUNDARY l
l l
t SECTOR DIRECTION MILES DESCRIPTION x/Q D/Q i B NNE 0.5 Recreational 5.438E-6 1.204E-8 vehicle l
Laydown Area R NNW 0.5 Energy 8.422E-6 1.310E-8 Services Center' ;_
Q NW 0.75 Gin Lake' 3.958E-6 4.531E-9 P WNW 0.75 Hamilton Lake l 6.266E-6 5.215E-9 8
These locations occupy multiple sectors. In each case the SITE BOUNDARY locations used in the dose calculation was limiting.
i l.
I j- GRAND GULF, UNIT 1 2.0 23b Revision 17 - 03/95
. - - . _ . . - - .. =-. _ . - . - . . _ . . _ . . . . - . _ . . . - ._. ... - .. . . . . . - .
4 2.3 Mateoroloaical undal 2.3.1 Atmogpharie Dinnersion The atmospheric dispersion for gaseous releases may be l
{' calculated using a ground level, wake-split fom of the 1
- 1 1
straight line flow model.
x/Q = atmospheric dispersion (sec/m*)
2.03 ok 1
rur
- where:
r = distance (a) frca release point to location of I interest 1
o = plues depletion factor at distance r frem ODcx Figure 2.3-1 u = wind speed at ground level (m/sec) l j k = open terrain recirculation factor at distance r, 1 l from ODCM Figure 2.3-4 (not used)
E = the lesser of (as + h s.) N or /3 a T
i
- where
a = vertical standard deviation (a) of the plume at
- distance r for ground level releases under the
, stabilitycategoryindicatedbyh,fromODCM I
Figure 2.3-2 k h = temperature differential with vertical separation (*K/100m)
! b - height of the reactor building = 53.3m l
I GRAllD GULF, IntIT 1 2.0-24 Revision 17 - 03/95
2.3.2 Deposition Relative d* Position per unit area for all releases is i calculated for a ground level release as follows:
D/Q = relative deposition per unit area (m" )
= 1 mil (D9) r where:
D = relative deposition rate at distance r for ground level releases from ODCM Figure 2.3-3 i
X/Q and D/Q values were calculated using the methodology of NUREG/CR-2919 3
"XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations".
3 GGNS gaseous releases are ground level.
Additional information ,a the X/Q and D/Q calculations can be found in j ODCM References 9 and 2 0.
I i i 4
i GRAND GULF,.' UNIT 1 2.0-25 Revision 17 - 03/95
i 1
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GRAND GULF, UNIT 1 2.0-26 Revision 17 - 03/95 l
. - - . . - . . - . _ _ . . . - . - - . - . _ . - . . . . ~ - ~ ~ ~ -
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d 2.4 Definitions of Gy eous Effluents Paramatars l
l b = height of reactor building (m) (2. 3 .1) l j C = count-rate of the station vent monitor corresponding to j grab samle radionuclide concentrations (2.1.1) i C' = count rate of station vent monitor corresponding to a 1.0
, gC1/ml concentration of Xe-133 (2.1. 2 )
j D = relative deposition rate for ground level releases from g
j Figure 2.3-3 (m-1) (2.3.2)
! D, = average organ dose rate in current year (arem) (2.2.1.b)
J
- D J p
=
dose to an individual from radiciodines and radionuclides in i particulate form, with half-life greater than eight days (area)
(2.2.2.b) 1 1
D, - average skin dose rate in current year (area) (2.2.1.a) t D tb
= average t tal body dose rate in current year (aram)
} (2.2.1.a) i
[ D p
- air dose due to beta emissions from noble gas radio-nuclide i (mrad) (2.2.2.a)
I j
D Y
= air dose due to gamma emissions from noble gas radio-nuclide i (mrad) (2.2.2.a) l D/Q = relative deposition per unit area (m-2) (2.3.2) a = plume depletion factor at distance r for appropriate stability class and effective height from Figures 2.3-2 and 2.3-3 (2.3.1)
F = fraction of current year elapsed at time of calculation (2.1.1) k - open terrain recirculation factor at distance r from Figure 2.3-1 (2.3.1)
GRAND GULF, UNIT 1
- 2.0-27 Revision 3 - 05/84
. _ . . _ _ _ _ _ _ . . . .__..______.__.-__.m . _ . _ _ . . _ . . __ _ ._. _ _ _ ._
l I
Y 2.4 nafini t ie= = of rs==eous Ef finants Parainators (continued) l 2
i j K = total body dose factor for Kr-89, the most restrictive isotope (mrem /yr per gCi/m3 ), from Table 2.1-1 (2.1. 2 ) 1
.l i
4 K
i
= total body dose factor due to gamma emissions from
- isotope 1 (mrom/yr per sci /m3 ) from Table 2.1-1 (2.1.1) ,
Dg = limiting dose rate to the total body based on the limit l
) of 500 mrom in one year. (2.1.1) i I
)
- - D as
= limiting dose rate to the skin based on the limit of 3000 mrem
- in one year. (2.1.1) i i
L =
skin dose factor for Kr-89, the most restrictive isotope (mres/yr per sci /m8) from Table 2.1-1 (2.1. 2 ) l 4
j L =
skin dose factor due to beta emissions from isotope 1 (wom/yr 1
per pCi/m s), from Table 2.1-1 (2.1.1) ,
1 g
- M =
air dose factor for Kr-89,-the most restrictive isotope I l
(mrad /yr per pCi/m8) from Table 2.1-1 (2.1.2)
I j M,g
=
air dose factor due to gamma emissions from isotope 1 (mrad /yr l
per pCi/m8) from Table 2.1-1 (2.1.1) I l
$ Ng =
air dose factor due to beta emissions from noble gas radionuclide 1 (mrad /yr per pCi/m8) from Table 2.1-1 (2.2.2.a)
P =
dose parameter for radionuclide i, (mrem /yr per gCi/m8) for inhalation from (m ' arem/yr per uCf./sec) for other pathways, a
from Table 2.2-1 (2.2.1.b).
O' g
= rate of ' release of noble gas radionuclide 1 (gCi/sec) (2.1.1)
~
Q =
average release rate for the current year (gci/sec) of isotope i of tritium, I-131, I-133 or other radionuclide in particulate form, with half-life greater than eight (8) days (2.2.1.b)
Qg =
cumulative release of radionuclide i of noble gas, tritium, I-131, I-133, or material in particulate form over the period of interest (gCi) (2.2.2.a) (2.2.2.b) l GRAND GULF, UNIT 1 2.0-28 Revision 5 - 01/85
- . .. . _ _ - . . _ - - . _ . _ . . . - . - _ . . . _. . _ . _ . . . ~ _ - _ - . . . . .
i i
2.4 Definitiaam of ammeous Effluents Paramatars (Continued)
{= assigned release rate value of, for example, 1.0 gCi/sec, Xe-133; related to definition of C' for the vent. (Note 3)
Rg = dose factor for radionuclide i, (mrem /yr per gCi/m8) or (m mrom/yr por pCi/sec)
=
R, count rate per mrom/yr to the skin. (2.1.1)
R * ## #* * *" *
- t Y* *
- R", - conservative count rate per mres/yr to the skin. (2.1.2)
R"t *
- I *~
detection, Kr-sp dose). (2.1.2) '
r - distance (m) from release point to location of interest for dispersion calculation. ( 2 . 3 .1)
GRAND GULF. UNIT 1 2.0-29 Revision 3 - 05/84
. - ~. ~. .- ._ .. - - . . - - . . . . - . .
l J
\
I i
i 2.4 Definitions of cameous Effluents Parameters (Continued) i S y
=
count rate of station vent noble gas monitor at alarm setpoint 4
level. (2.1.1) r .
vertical standard deviatien of the plume with building wake correction (m). (2.3.1) a . vertical standard deviation (m) of the plume at distance r for t
affectrive height under stability category indicated by T(m) from Figure 2. 3 -2. . (2 . 3.1)
T = temperature diffavantial with vertical separation (*K/100m).
(2.3.1) u . wind speed at greand level (m/sec). (2.3.1)
W -
controlling sector annual average atmospherie dispersion at the site boundary for the appropriate pathway (sec/m8). (2.2.1.b) w' -
relative concentration for unrestricted areas (sec/m ). s (2.2.2.b)
X/Q = atmospheaic dispersion (sec/m8) (2.3.1)
X/Q =
highest saccor annual average atmospheric dispersion at the unrestricted area bounda n (sec/m8) (2.1.1)
X70' = relative concentration for unrestricted areas (sec/m8)
(2.2.2.a) l GRAND GULF, UNIT 1 2.0-30 Revision 3 - 05/84 I
l L
Graph taken f. Reference 7 Figure 2 O I i
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@ 0.9
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r, PLUME TRAVEL DISTANCE (KILOMETERS)
---._---..-s.--- - - _ _ - -- --_~------..---.-x - - - - - - - - - - - - - - - - - . - - - - - - - - - . - -.--._.a. --
. . . . _ _ _ . . _ . _ - . . . . . . _ . _ . . . . . _ . _ . . _ _ _ . . _ . _ . . _ _ . . _ _ . _ . _ . _ . . ..._..__...__.._.._..__..__,_..m_._.m__ . _ _ _ . . _ > _ . .
I l
IAEl&LL M l grtieni standmed Deviatu n of Material in a Plume 1 (Letters denote Pasqua'.1 Stability Class)
! 1000 ,
i 1 , -
l 1 ;
\
e
/ / f l / / / ~
l / / ,a r r ,,
J ., /
\ j / /
/ /
, ! / /
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1 1 1 1
0.1 1.0 10 100 l
r, PLUME TRAVEL DISTANCE (KILOMETERS) i Tempeanne Cnemos Puemil S*l87 ynk Hauen ( T 1('X/100m) h Clanuncanan l
J
<gg A Exarusash unnable l'9 to al.i B 1,7 u .1.5 C Shpaly w h
.l.$ es 0.5 D M 45 to 1.3 g ,g;d,,y ,,,y, I3 y m
, ," O M" Graph taken from Reference 7, Figure 1 GRAND GULF, UNIT 1 2.0-32 Ravision 15 01/94 -
_ .....__..._...__._.-..-.__._....._....~.........._....__m.
....___.--___.___.__.___..._...._m.. _ _ _ . _ . _ .
k i
' Fimire 2.3-3 Relative Danesition for Ground-Laval Relammes i (All Atmospheric Stability Classes) l 10-3 - -
i j we i
i i
I -
- - m j
W 104 h \ '
2 .
- M %g
! W ;
, A.
i
- A W
p T &
$ \
j Z "N l,
1
.O
.g{10-5 ( *
- E s s
W N Q '
t W '
D N 8 3 j \
u %
s i
- 10-4 8 x i
10-7 0.1 1.0 10,0 100.0 200.0 r, PLUME TRAVEL DISTANCE (KILOMETERS)
Graph taken from Reference 7. Figure 6 GRAND GULF, UNIT 1 2.0-33 Revision 15 - 01/94
. . . _ _ . . _ - . . ._. ._._.....-.._...._.._..-_.__.__............-_.....,.._m. -
. _ . . _ - _ . . _ . . ~ . . . - . _ . _ . _ . -
i j
i.
i j M m e 2.3-4 Onan Terrain Racirculation Facter '
3
! -) l 1 -
1 4
4 J-I 1
l 1 s
j 3,
l l J !
3 i
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' 1 m
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i Graph taken fross Reference 6, Figure 2
! GRAND GULF, UNIT 1 2.0-34 Revision 15 - 01/94 i.
. . .. . ~ ._ _ . _ . _ . . . - . - _ . , _ _ . _ _ . . - . - . - . _ . . . _ _ _ _ . . _ . _ . _ _ . - . . . , _ . _
j 2.5 Gaseous Radwaste Treatment System The instruments required to be checked by LCO 6.11.7 to ensure that
! the GASEOUS RADWASTE TREA' DENT (Ofigas) SYSTEM is functioning are:
. l
, 1. Adsorber train bypass switch (IN64-HS-M611) l
- 2. Bypass valve indication (IN64-F045) ,
1 When the adsorber train bypass switch is in the TREAT position and j the bypass. valve indicates closed, the GASEOUS RADWASTE TREADENT
< (Offgas) SYSTEM is functioning.
+
- NOTES for ODCM Fiaure 2.5-1 ;
i I A flow diagram for the Gaseous Radwaste Treatment System is provided on the following page. Notes for the diagram are listed below.
(1) The charcoal beds are bypassed during rtartup until an, adequate dowpoint is obtained in the process stream.
(2) This pathway may be utilized for power levels s 5%.
(3) Standby Gas Treatment System not normally operated.
t GRAND GULF, UNIT 1 2.0-35 Revision 17 - 03/95
- . . . . .. . . - . . - -- - _ . _ . . - . _ _ ~ . . . . -. . -
Pierurs 2. 5 -1
(".m meous madwasta Treatment Svetam TO ArWortert
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GRAND GULF, UNIT 1 2.0-3Sa Revision 8 - 08/86
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4 2.6 anmini nome h 4cm.ne l If required, the annual (calendar year) dose or dose conunitment to l
any MIDGER OF THE PUBLIC will be calculated by summing the fol) i Tg i doses for the calendar year 4
Direct radiation dose e Liquid effluent dose (D )
- Noble gas dose (D , D ) -
g Particulate dose (Dp)
These calculations are required only 1,f the liquid or gaseous effluents exceed twice the limits of Lcos 6.11.2, 6.11.0 and 6.11.6. '
, 2.6.1 ni r c.e n d 4 m e 4 an m.. u.. .n r -- =e .
i Lcos 6.11.2, 6.11.5 and 6.11.6 require the determination of cumulative dose contributions to a MIDGER OF THE PUBLIC from direct radiation from the reactor units and from radwaste storage tanks. This requirement is applicable ,
only under conditions set forth in Action B.1 of the . L applicable Lco. This determination is made by the .
- utilization of direct radiation measurements from indicator thermoluminescent dosimeters (TLDs) located near the GGNS property line in eight*of the 16 meteorological i
sectors. ;
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, IT 1 2.0-36 Revision 20 - 07/96 s
Measurements from these TLDs represent the direct
- - radiation generated by the facility plus normal background
}
radiation. The locations ate identified in ODCM Table 3.0-3 by the following TLD numbers:
(
M-16 M-22 M-23
} M-19 M-25= M-17
- M-21 M-28 4
Control TLDs are also utilized to' differentiate between background radiation and direct radiation from the .,
, facility. The following two TLDs are designated as 4-controls based on the criterion that they are located ten miles or greaterefrom the facility. Exact locations are identified in ODO4 Table 3.0-3. .
M-14 M-33 The difference between the averaged quarterly rad'.ation awasurements of the indicator TLDs and the control TLDs repr=sents the direct radiation dose to a MEMBER OF THE PUBLIC from the operating facility. .
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l GRAND GULF, UNIT 1 2.0-37 Revision 20 - 07/96
~
1 3.0 RADIO 1DGICAL ENVI,tONMENTAL MONITORING 3.1 E=-14na Locations Sampling locations to :'ulfill the requirements of LCO 6.12.1, as described in ODCM Table 6.12.1-1, are identified in ODCM Tables 3.0-1 through 3.0-3 and show.1 on maps in ODCM Figures 3.0-1 and .
I 3.0-2. i l
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I N W , UNIT 1 3,0 1 Revision 17 - 03/95
... _. .- - . . . - - _ . ~ . _ _ . ._
i QQCM J:
Tamf.F 3_0-1 j ATD sAMotro cor.r.rerION sITrn 4
AIR EAMPLERE t
EUMagg FIGURE TLCATION
- ' AS-1 PG 3;0-2 Southeast bf GGNS at the Port Gibson City Barn
. .(Sector G Radius, 5.5 miles)
AS-3 61VA 3.0-2 NNE of GGNS on Hwy. 61, north of the Vic.k. burg Airport (Sector B Radius, 18 miles)
(sector H Radius, 0.5 miles) 1 1
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- 1 3.0-2 Revision 20 - 07/96
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MIENT.T.1MWAffE mf.t.R MTON ETTER Page 1 of 2 l-1 1
wTr.r emuor.we (muTunt. tocaTToNi- gIgggg
- ALCONT 3 . 0 - 2. '
QB9dND MATER -
- a. . ;
, PGNELL 3.0-1 PORT GIBSON WELLS - Taken from distribution system or one of_the
- five wells (Sector G Radius 5.'O ,
.a1.s) i construction Water Well 3.0-1 GGNS CONSTRUCTION WATER WELL - l Taken from distribution system J 4 or the well (Sector P Radius 0.4 miles)
- SURFACE MATER l
, ]
Upstream
!, 3.0-1 At-least 4500 ft upstream of the f GGNS discharge point into the
. Mississippi River to allow adequate mixing of the Mississippi and Big Black Rivers (sector Q-R, 1.8 miles)
Downstream 3.0-1
- At least 5000 ft dowcatream of the GGNS discharge point iato the l
Mississippi River near Radial Well No. 1 (Sector N, 1.6 na2 es) i MS River Downstream 3.0-1 Downstream of the GGNS discharge i:
i point (during a liquid radwaste i discharge) in the Mississippi j River near Radial Well No. 5 i .
(sector Q-P, 1.3 miles) 1 1
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i i GRAND GULF,. UNIT 1 3.0-3 Revision 20 - 07/96 1
4 a
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MISPFf.T1MEOf1S COT.T.WrTION STTER Page 2 of 2 I
)
ggQJJfENT SAMPT.FC FIGURE
)
SEDNAM 3.0-1 Downstream of the GGNL discharge point in the Mississip; i River near Hamilton Lake out;.at (Sector N, 1.6 miles)
SEDCONT 3.0-1 Upstream of the GGNS dis:harge point in the Mississippi River (Minimum of 100 ydd VEGETATION Broadleaf Vegetation 3.0-1 S of GGNS near former Training Center on Bald Hill Road (Sector J, 0.4 miles), or SSE of GGNS between the former training center and the IBBW Union Hall on Bald Hill Road (Sector H, 0.4 miles)
HQTE:
The above locations are gardens maintained by GGNS inside the SITE BOUNDARY. These two sampling sites exceed the requirements of LCO 6.12.1.
Alcorn State University SSW of GGNS (Sector K, 10.5 miles) when available, otherwise a location 15-30 km distant l
1 GRAND GULF, UNIT 1 3.0-3a Revision 20 - 07/96
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TLD IDCATIONS Page 1 of .1 i,
TLn No. IDCATION FIGURE SECTOR MILE M-01 Across the road from Lake 3.0-2 Claiborne entry gate E 3.5 3
M-07 AS-1 PG, Port Gibson City Barn 3.0-2 G 5.5 11-09 Warner Tully Y-Camp 3.0-2 D 3.b M-10 Grand Gulf Military Park 3.0-1 A 1.5 M-14 AS-3-61VA, Hwy. 61, north of 3.0-2 B. 18.0
, (CONTROL) Vicksburg Airport M-16 Meteorological Tower i
3.0-1 A 0.9 M-17 S Side, Grand Gulf Road 3.0-1 C 0.5 i )
M-19 Eastern SITE BOUNDARY I 3.0-1 E 0.5 property line, NNE of HWSA 1 a
M-21 Near former Training Center 3.0 J 0.4 Building, on Bald Hill Road 4 M-22 Former RR entrance crossing on 3.0-1 G 0 . 8.,
Bald Hill Road
, M-23 Gin Lake Road 50 yards north of 3.0-1 Q 0.5 Heavy Haul Road on power pole M-25 Radial Well Number 1 3.0-1 N- 1.6
, M-28 Former Glodjo residence 3.0-1 L 0.9 M-33 Newellton, Louisiana, Water 3.0-2 P 12.5 (CONTROL) Tower M-36 Curve on NW 608, point nearest 3.0-2 P 5.0
- GGNS at power pole
- a M-38 Lake Bruin State Park, entrance road 3.0-2 M -
9.5 M-39 St. Joseph, Louisiana, Aux. i 3.0-2 M 13.0 Water Tank M-40 Headley Drive, near River 3.0-2 M 2.3 Port entrance I
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GRAND GULF, UNIT 1 3.0-4 Revision 20 - 07/96 b
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TLD IMaTIONC Page 2 of 2 T1.D No. IDCATION FIGURE SECTOR MILE M-4B 0.4 miles South on Mont Gomer 3.0-2 K. 4.8 Road on west side M-49 Fork in Bessie Weathers Road / 3.0-2 l
H 4.5
.q Shaifer Road l M-50 -Panola Hunting Club entrance
- 3.0-2
. B 5.3
! M-55 Near Ingelside Karnac Ferry Road / \
3.0-2 D 5.0 I Ashland Road Intersection M-57 Hwy. 61, behind the Welcome *
- 3.0-2 F 4.5 i
to Port Gibson sign at Glensdale Subdivision M-94 Sector R near 3.0-1 R 0.8 Meterological tower 1
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OFFSITE DOSE CALCULATION MANUAL APPENDIX A RADICIAGICAL EFFLUENT ColfrROLS AND RADIOLOGICAL INVIR00 MENTAL MONITORING PF.0 GRAMS 1 l
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Revision 17 - 03/95
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G~,tAND GULF, UNIT 1 A.1 11evision 17 - 03/95
. . _ _ _ _ _ __ .____ _ _ _._ _ ___. _ _ . _ _ _ _ .m - _ . - ._ .
e 1.O DEFINITIONS i '
GASEOUS RADWASTE TREA'INENT (OFFGAS) SYSTEM 1.1 The GASEOUS RADWASTE TREATMENT (OFFGAS) SYSTEM is the system designed 1 and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity ,
. prior to release to the environment. ,
MEMBER (S) OF THE PUBLIC i 1.2 MEMBER (S) OF THE PUBLIC shall include individuals in a controlled or i
unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an 1
occupational dose.
OFFSI'I'E DOSE CALCOLATION MANUAL (ODCM) 1.3 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the
- calculation of gaseous and liquid effluent monitoring Alarm / Trip 4
Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive
' Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 5.5.4 and Technical Requirement
- 7.6.3.2 and (2) descriptions of the information that should be included in the Annual Radiological Enviran=antal Operating and Annual Radioactive Effluent Release Reports required by Technical
- Specifications 5.6.2 and 5.6.3. .
PROCESS CONTROL PROGRAM (PCP) 1.4 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be !
accomplished in such a way as to assure' compliance with 10CFR Parts 20, 61,.and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
)
/
GRAND GULF, UNIT 1 A-2 Revision 17 - 03/95
d i )
i SITE BCNM1ARY j 1.5 The SITE BOUNDARY shall be that line beyond which the land or property ;
is not owned, leased, or otherwise controlled by the licensee.
, UNRESTRICTED ARIA i 1.6 An UNRESTRICTED AREL shall be any artes, at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for the purposes of protection of individuals from exposure to radiation and radioactive c
- materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial casumercial, institutional, and/or recreational purposes. The UNRESTRICTED ARIA and SITE BOUNDARY are t
synonymous with the exception of areas over bodies of water.
VENTILATION EIHADST TREA'tMEIrf SYSTEM l l 1.7 A VIIrrIIATION IINADST TREA'IMENT SYSTEM is any system designed and ,
- installed to reduce gaseous radiciodine or radioactive material in i s particulate term in effluents by passing ventilation or vent erhaust gases through charcoal adsorbers and/or HIPA filters for the p'.trpose of removing iodines or particulates from the gaseous exhaust straan prior
. to the release to the envir - nt (such a system is not considered to (
l have ray effect on noble gas effluents). Engineered Safety Featute l 5 (ESP) atmospheric cleanup systems are not considered to be VElfrIIATION RIHAUST TREA'IMElrf SYSTEM ccuponents.
Additional Definitions are listed in. Technical Specification Section 1.1.
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i GRAND N , UNIT 1 A.3 Revision 17 - 03/95
. . ~ . - - . .- . . . . . . . . - . . - .-. .- . - . - . . - . . . . _ - . - . . . - - -
b 1
8 TABLE 1.1 SURVEILLANCE FREQUENCY NOTATION surveillance Frequencies are specified in individual LCOs. For more information see Technical specificaiton Section 1.4.
1
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I GRAND GULF, UNIT 1 A-4 Revision 17 - 03/95
.,y..__ . _ _ . . . _ ~ . _ . . . . - . _ _ , . _ . . _ _ _ . . . , _ . . . . . _ . _ _ _ _ . . . _ . . _ _ _ _ _ . . _ . - _ . _ . , . _ . . . _ . . . . _ . . . . _ _ _ . . . _ _ . _ . . . _ _ _ . . . _ _ .
i
. 2 1 .
i i-TABLE 1.2 i
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1 j Modes of operation are shown in Technical Specification Table 1.1-1 1.
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} GRAND GULF, INIT 1 A-5 Revision 17 - 03/95 i
(
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3.0 APPLICARILITY LIMITIno e m ITION FOR OPIr#1 TION (T.f0) 1 i
j See Technical Specification Section 3.0 for LCO Applicability.
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GRAND GULF, IMIT 1 A-6 , Revision 17 - 03/95
4 1
5 APPLICABILITY f
SURVIIt.t4weg REQUTn-wrS (SR)
) _
j See Technical Specification Section 3.0 for SR applicability, i
j GPM W, UNIT 1 A.7 Itevision 17 - 03/95
/.
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SECT 100f 5.O ADIENISTRATIVE COIrfROLS i
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J GRAND GULF, UNIT 1 A.3 Revision 17 - 03/95
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- i 5.0 kNii!Itmiv1VE U-i-. JE i
- -- ..r. minimnnit ar. wwyr r- -..r. opeman n,amenev s.s.2 1
Routine radiological environmental operating reports. covering the operatico of the unit during the previous calendar year shall be submitted before May 1 of each year.
The annual radiological envirar-antal operating reports shall include summarwe, l
i interpretations, and an analysis of trends of the results of the radiological j environmental surveillance activities for the report period, including a ccupariso.3 with preoperational studies, operational controls (as appropriate), and previous 1
i environmental surveillance reports and an assessment of the observed ispects of the plant operation on the environment. The reports shall also include the results of land use censuses required by LCO 6.12.2. If harmful effects or evidence of 1
irreversible damage are detected by the s:ocitering, the report shall provide an i analysis of the problem and a planned course of action to alleviate the problem.
' The annual radiological environmental operating reports shall include summarised and
' tabulated results in the format of Regulatory Guide 4.8, December 1975 of all l radiological environmental saspies taken during the report period.InDeviations from the event that the sampling program identified in ICO 6.12.1 shall be reported.
4 I
some results are not available for inclusion with the report, the repor*. shall be !
submitted noting and explaining the rences for the missing results. The missing l
data shall be submitted as soon as possible is a supplementary report. ,
l l The reports shall also include the following:
\
il a stamary descriptice of the radiological environmental monitoring program;
- 2) a map of all sampling locations keyed to a table giving distances and directions from one reactors 1
- 3) and the results of licensee (or offsite laboratory's) participation in the Interlaboratory Comparison Program, required by 140 6.12.1.
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' GRAND GULF, INrIT 1 A.9 Revision 17 - 03/95 4
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i 5.O ADMINISTRATIVE CGaG Ee
- .1 6.3 ANNtIAL RADINTIVE EFFLUElff REM 1eX REPORT
! A Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submaitted before May 1 of each year.
! a. The Radioactive Effluent Release Report shall include a susanary of the quantities
! of radioactive liquid and gaseous effluents and solid waste released from the
! unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting j- Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and j Gaseous Effluents frcan Light Water-Cooled Nuclear Power Plants," Revision 1, June 4
1974, with data sumanarised on a quarterly basis following the format of Appendix i
B thereof. For solid wastes, the format for Table 3 and Appendix B shall be
! supplemented with three additional categories: class of solid wastes (as defined by 10 CFR Part 61), type of container (e.g., Steel Liner, High Integrity Container) and SOLIDIFICATION Agent or absorbent (e.g., cement, urea j formaldehyde).
! The Radioactive Effluent Release Report shall include an annual summary of hourly i meteorological data collected over the previous year. This annual sumanary may be 4 either in the form of an hour by hour listing on magnetic tape of wind speed,
! wind direction, atmospheric stability, and precipitation (if measured), or in the i form of joint frequency distributions of wind speed, wind direction, and
. atmospheric stability.* This same report shall include an assessment of the
! radiation doses due to the radioactive liquid and gaseous effluents released from i the unit or station during the previous calendar year. This same report shall
! also include an assessment of the radiation doses from radioactive liquid and i
gaseous effluents to MERSERS OF THE PUBLIC due to their activities inside the
. SITE BOUNDARY during the reporting period. All assumptions used in making these 1 assessments, i.e., specific activity, esposure time, and location, shall be
! included in these reports. The meteorological conditions concurrent with the j time of release of radioactive materials in gaseous effluents, as determined by
- sampling frequency and measurement or historical annual average meteorological l conditions, shall be used for determining the gaseous pathway doses. '1he assessment of radiation doses shell be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCUIATION MANUAL (ODCM) .
The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed MEISER OF THE PUBLIC from reactor releases and other. nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, "Envircamental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev 1, October 1977 and NUREG - 0133.
The Radioactive Effluent Release Report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Report shall include any changes made during the reporting period to the OFFSITE DOSI CALCUIATION MANUAL (OD W), pursuant to Technical Specification 5.5.1, as well as any major change to Liquid, Gaseous, or Solid Radwaste Treatment Systems. It shall also include a listing of new locations for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant to LCO 6.12.2.
- In lieu of sukutission with the Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meterological data casite in a file that shall be provided to the NRC on request.
GRAND GULF, UNIT 1 A-10 Revision 17 03/95 l
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E . 0 inwTNIETomar'IVE ctMETROLS I 5.6.3 Annual unnroacrivE nyrimateT natumes RARQEI (Continued) i l The Radioactive Effluent Release Report shall also include the following: an i explanation as to why the inoperability of liquid or gaseous affluent monitoring instrumentation was not corrected within the time specified in LCOs 6.3.9 or
- 6.3.10, and description of the events leading to liquid holdup tanks exceeding i the limits of Technical Specification 5.5.8.b.
- b. Major changes to the Radioactive waste Treatment System (liquid, gaseous and l l
solid") shall be reported to the Cessaission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PSRC.
(1) A sununary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 30.59; n (2) Sufficient detailed informatien to totally support the reason for the change without benefit of additional or supplemental information; t
l (3) A detailed description of the equipment, crumpanants and processed involved
. and the interfaces with other plant systems; l (4s An evaluation of the change which shows the predicted releases of 1 radioactive materials in liquid and gaseous affluents and/or quantity of I i solid waste that differ from those previously predicted in the license l application and sme N ats thereto; (5) An evaluation of the change which showw the espected ==w4-= exposures to l y MEMBERS OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto; (6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the j,
period before when the changes are to be made; (7) An estimate of the exposure to plant operating personnel as a result of the change; and (8) Documentation of the fact that the change was reviewed and found acceptable
- i by the PSRC.
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" The information called for in this Specification may be subunitted as part of the y
next UFSAR update.
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4 SECTICII 6.0 LIMITING COIIDITICIIS FOIL OPERATICIt j AND 4'$
) SURVIILIANCE REQUIRMIElffS i
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l GRAND QULF, UNIT 1 A 12 ,
Revision 17 - 03/95
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t 6.3 INSTRUMENTATION
]
6.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4
LCO 6.3.9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 6.3.9-1 shall be OPERABLE with required alarm / trip l 4
setpoints set to ensure that the limits of LCO 6.11.1 are not exceeded. The alarm / trip setpoints of these channels shall be
' determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).
4 APPLICABILITY: At all times.
1 ACTIONS
........................................... NOTES--.--.-.......---..---.-..-..---.--..-
- 1. Separate Condition entry is allowed for each Channel.
- 2. The provisions of LCO 3.0.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME 3 A. One or more required A.1 Suspend release of Immediately channels inoperable. radiactive effluent via affected pathway.
--.--.----NOTES------------
Once required Action A.2 is entered the completion Time for Condition B or C can 1not be restarted by ,
reentering Required Action :
A.1.
A.2 Enter the condition Immediately referenced in Table 6.3.9 1 for the channel.
(continued) 1 GRAND GULF, UNIT 1- A-13 Revision 18 .
02/96 l
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i ACTIONS (continued)
CONDITION REQUIRED ACTIOtt COMPI.ETION TIME B. As required by Required 5.1 At least two independent Prior to each Action A.2 and referenced saeples are analysed in release. J in Table 6.3.9 1. accordance with LCO E.11.1. ,
M B.2 At least two technically Prior to each qualified members of the release.
Facility Staff ,
independently verify the i release rate calculations <
and discharge path valve line-up.
M B.3 Restore channel to 14 days operable.
C. As required by Required C.1 Estimate the flow rate for Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l Action A.2 and referenced the affected pathway during i in Table 6.3.9 1. actual releases. Pusy l curves may be used to estimate flow.
M C.2 Restore channel to 30 days operable. j l
l D. Required Action and D.1 Suspend release of Immediately associated Completion Time radiactive effluent via !
of Condition 5 or C not affected pathway.
met. )
M l D.2 Initiate action to explain Immediately why this inoperability was not corrected in a timely manner in the next Annual Radioactive Iffluont Release Report.
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j GRAND GULF, 13 FIT 1 A-14 Revision 17 - 03/95
4 SURVEILLANCE REQUIREME1rrs
...........................................NorES............................... ......
Refer to Table 6.3.9 1 to determine which SRs apply to each channel.
i SURVIILLANCE FREQUENCY l 4
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SR 6.3.9.1 .... ....-.............NCfrE.......................
4 For flow rate measurement devices a CKANNEL CHECK 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shall consist of verifying indication of flow during periods of release. A CHANNEL CHECK shall s be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days which batch relammes are made.
Perform CHANNEL CHECK. l l
l SR 6.3.9.2 Perform a source check, a qualitative assessment Prior to each of channal response when the channel sensor is release. !
esposed to a radioactive source. I i
1 SR 6.3.9.3 ..--..................NCPTE.....-.................
The CHANNEL FUNCTIONAL TEST shall also demonstrate 92 days that automatic isolation of this pathway and control room alarm annunciation occur if any of I the following conditions exists:
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- 1. Instrument indicates measured levels above the alarm / trip setpoint. !
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- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
J Perform CHANNEL FUNCTIONAL TEST.
(couts.nued) i GRAND GULF, UNIT 1 A.15 Revision 17 03/95
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4 SURVEILLANCE FFRQUENCY SR 6.3.9.4 Perform CHANNEL FUNC"fIONAL TEST. SI days SR 6.3.9.5 --- - -------------NOTE -.-- - ...............
The initial CHANNEL CALIBRATION shall be performed 12 months using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained fress suppliers that participate in ,
measurement assurance activities with NILT. These l standards shall permit es11 bracing the syst.e. v.6r its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
1 .............................................. ,
l Perform a CHANNEL CALIBRATION.
SR 6.3.9.6 Perfora a CHANNEL CALIBRATION 18 months 4
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. . i GRAND GULF, UNIT 1 A.16 Revision 17 - 03/95
TABLE 6.3.9-1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED MINIMUM FROM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT OPERABLE ACTION A.2 REOUIREMENTS l
- 1. GROSS RADIOACTIVITY' MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line 1 B SR 6.3.9.1 SR 6.3.9.2 SR 6.3.9.3 SR 6.3.9.5
- 2. FIDW RATE MEASUREPjENT DEVICES
- a. Liquid Radwaste Effluent Line 1 C SR 6.3.9.1 SR 6 3.9.4 SR 6.3.9.6
- b. Discharge Canal or Circulating Water Blowdown 1 C SR 6.3.9.1 SR 6.3.9.4 SR 6.3.9.6 GRAND GULF, UNIT 1 A-17 Revision 18 - 02/96
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i 6.3 INSTRIBERNTATION 1
6.3.10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTROMENTATION 1
l LCO 6.3.10 The radioactive gaseous effluent monitoring instrumentation channels i
- shown in Table 6.3.10 1 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of LCO 6.11.4 are not ,
, exceeded. The alarm / trip setpoints of these channels shall be !
determined in accordance with the OFFSITE DOSE CALCULATION MANUAL 1 (ODCM).
4 APPLICABILITY: As shown in Table 6.3.10 1 ACTICNS
! ...........................................NcyrES......................................
- 1. Separate Condition entry is allowed for each Channel.
- l 2. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.
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I CONDITION REQUIRED ACTION CCMFLETION, TIME i
A. One or more required A.1 Suspend release of Ismediately '
channels inoperabis. radiactive effluent via affected pathway.
QB l . . . . . . . . . . NcrrES . . . . . . . . . . . .
4 Once required Action A.2 is
- entered the Cospletion Time j for condition Referenced on '
- Table 6.3.10-1 can not be restarted by reentering )
- Required Action A.1. 1 J
l A.2 Enter the Condition Immediately referenced in Table 6.3.10 1 for the channel.
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- GRAND 00LF, UNIT 1 A.18 Revision 17 03/95 4
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- ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. As required by Required 8.1 Take grab samples during Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Action A.2 and referenced release, in Table 6.3.10 1.
M B.2 Analyse the above required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of l samples for gross taking the sangle ;
activity. !
M B.3 Restore channel to
) operable.
C. As required by Required C.1 Establish an alternate launediately Action A.2 and referenced means to collect samples in Table 6.3.10 1. required by Table 6.11.4 1.
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C.2 Restore channel to 30 days operable.
D. As required by Required D.1 Estimate flow rate. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> '
i Action A.2 and referenced in Table 6.3.10 1. M D.2 Restore channel to 30 days operable.
(continued) i t
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GRAND GULF, UNIT 1 A 19 Revision 17 - 03/95
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j . ACTIONS (continued)
CORIDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Place the inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Action A.2 and referenced channel in downscale trip.
in Table 6.3.10 1.
! O
...............NorE............
- With both required monitors
, inoperable take Required j Actions E.2.
2 E.2.1 Take grab samples during Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> release.
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E.2.2 Analyse the above Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of ,
required samples for taking the sample gross activity.
E.2.3 Restore channel to 30 days operable.
F. As required by Required F.1 Verify the offgas system is Ipunediately Action A.2 and referenced not bypassed, except for in Table 6.3.10 1. filtration system bypass during plant startups.
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. F.2.1 Verify by administrative Immediately means that the offgas post-treatment monitoring system is operable.
QB F.2.2.1 Verify by Immediately adutinistrative mee'e that the charcoal vault radiation monitor arts the main steam line radiation monitors are
, operable.
M F.2.2.2 Take grab sasples and Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and
, analyse. once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M thereafter F.3 Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> operable.
(continued)
GRAND GULF, UNIT 1 A-20 Revision 19 - 05/5 l
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AcrIONS (continued) ,.
CONDITION REQUIRED ACTION COMPLETION TIME G. As requf. red by Required G.1 Take grab samples during Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Action A.2 and referenced release.
in Table 6.3.10-1.
M G.2 Analyse the above required Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of l samples for gross taking the sample !
activity. .
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30 days l G.3 Restore channel to operable.
H. Required Actions and H.1 Suspend release of Inunediately associated Ceepletion radiactive effluent via 1 Timee of Condition 3,C,D,I this pathway, i or G not met.
M H.2 Initiate action to emplain Immediately why this inoperability was I not corrected in a timely' manner in the next Apnual Radioactive Effluen'. 2 Release Report. i I. Required Action and I.1 Se in RE3DE 3 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition F not met. M I.2 Be in IE3DE 4 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l
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GRAND GULF, UNIT 1 A-21 . Revision 17 - 03/95
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SURVIILIANCE REQUIREMElfrS
.........................................NcyrEs--.-------.....-......................
- 1. Refer to Table 6.3.10-1 to determine which SRs apply to each channel.
- 2. When a monitor is placed in an inoperable status solely for performance of required Surveillance's, entry into associated Conditions and Required Actions in accordance with LCO 6.3.10 may be delayed for up to I hour.
SURVEILLANCE FREQUENCY 1
SR 6.3.10.1 Perform CHANNEL CHICK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Perform CHANNEL CHICK.
SR 6.3.10.2 7 days d
l SR 6.3.10.3 -----------...---------NCrfE---...-----.--........
i 1. Not required to be performed in 3 ODES 1 and 2
- for the offgas pre treatment monitor if l
inaccessibile due to a high radiation area.
J j 2. Not required to be performed for the offgas pretreatment monitor when entering 3C053 3 and 4 from MODES 1 or 2 until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after entering BODE 3 or 4 if monitor was inaccessible due to a high radiation area.
Perform SOURCI CHICK , a qualitative assessment of channel response when the channel sensor is 31 days
' exposed to a radioactive source.
< SR 6.3.10.4 -------------------NCTTI-----------------------
The CHANNEL FUNCTIONAL TEST shall also riamanstrate the automatic isolatico capability of the instrumentation for this pathway and the control room alaza annunciation capabilii;y, if any of the i following conditions exists:
- 1. Instrument indicates measured levels above the alazz/ trip setpoint.
, 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode. -
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4 92 days t
. Perform CHANNEL FUNCTIONAL TEST.
(continued)
GRAND GULF, UNIT 1 A 22 Revision 17 -
03/95
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, suRvEI" E PrwIP=-r3 (continued) i SURVIILIJQtCE FREQUENCY j l
j SR 6.3.10.5 -----------------NCTTE-----------------
4 The CHANNEL FUNCTIONAL TEST shall also riammetrate
! that control room alarm annunciation occur if any of the following conditions exists:
- 1. Instrument indicates measured levels above the j alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 4. Instrument controls not set in operate mode.
92 days Perfarm CHANNEL FUNCTIONAL TEST.
SR 6.3.10.6 -----------------------NOTE-----------------------
Compare the measured flow rate to the espected design flow rate for existing plant conditions.
Pe r' < . - CHANNEL FUNCTIONAL TEST.
92 days SR 6.3.10.7 ---...-.----------- ---NOTE - ...---....----------
- 1. The initial CHANNEL N .TamaTION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using scandards that have been obtained from suppliers that
- participate in measurement assurance activities i with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent
- CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
- 2. The offgas pre-treatment and offgas post-treatment sensors will be calibrated for ar/hr or cpe from the calibration standard. The conversion to release rate will be performed during subsequent unit operation, but within one week.
Perform a CHANNEL CALIBRATION. 12 months SR 6.3.10.8 Perfora a CHANNEL CALIBRATION 18 months GRAND GULF, UNIT 1 A 23 Revision 17 - 03/95
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TABLE 6.3.10-1 L i
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM I MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRUMENT OPERABLE APPLICABILITY ACTION A.2 REOUIREMENTS
- 1. RADNASTE BUILDING VENTI'LATION MONITORING' SYSTEM
- a. Noble Gas Activity Monitor l Providing Alarm l' (a) B '
SR 6.3.10.1 l SR 6.3.10.3 SR 6.3.10.5 ,
, SR 6.3.10.7 '
- b. Iodine Sampler 1 (a) C i
- c. Particulate Sampler 1 (a) C SR 6.3.10.2
- d. Effluent System Flow Rate Measuring Device 1 (a) D SR 6.3.10.1 SR 6.3.10.6 SR 6.3.10.8
- e. Sampler Flow Rate Measuring Device 1- (a) D SR 6.3.10.1 FR 6.3.10.8
- 2. CONTAIPMENT VENTILATION MONITORING SYSTEM i
- a. Noble Gas Activity Monitor .
Providing Alarm 1 (a) B SR 6.3.10.1 SR 6.3.10.3 ;
SR 6.3.10.7 i l
GRAND GULF, UNIT 1 A-24 Revision'18 - 02/96
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TABLE 6.3.10-1 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONI'IVRING INSTRUMENTATION.
CONDITIONS REFERENCED FROM MINIMUM CHANNELS '
REQUIRED SURVEILLANCE INSTRIDfENT OPERABLE APPLICABILITY ACTION A.2 REOUIREMENTS
- b. Iodine Sampler 1 (a) C SR 6. 3.10.2
- c. Particulate Sampler . 1 (a)' C SR'6.3.10.2 i
- d. Effluent System Flow Rate l' (a) D SR 6.3.10.1 ,
Measuring Device SR 6.3.10.6
- e. Sampler Flow Rate 1 '(a) D SR 6 3.10.1 I Measuring Device SR 6.3.10.8 j i
- 3. TURBINE BLDG. VENTILATION MONITORING i SYSTEM f
- a. Noble Gas Activity 1 (a) B SR 6.3.10.1 Providing Alarm SR 6.3.10.3 ,
- c. Particulate Sampler 1 (a) C SR 6.3.10.2
- d. Effluent System Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.6 L SR.6.3.10.8 l
- e. Sampler Flow Rate 1 (a) D SR 6.3.10.1 ;
Measuring Device SR 6.3.10.8 GRAND GULF, UNIT 1 A-25 Revision 18 - 02/96 l j
TABLE 6.3.10-1 (Continued)
RADIOACTIVE GASEOl'S EFFLUENT MONITORING INSTRUMENTATION COND'~' IONS REFERENCED FROM MINIMUM CHANNELS REQUIRED SURVEILLANCE INSTRtNErr OPERABLE APPLICABILITY ACTION A.2 REOUIREMENTS
- 4. FUEL HANDLING AREA VENTILATION MONITORING SYSTEM
- a. Noble Gas Activity 1 (a) . B SR 6.3.10.1 Providing Alarn .
SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7
- b. Iodine Sampler 1 (a) C 3R 6.3.10.2
- c. Particulate Sampler 1 (a) C SR 6.3.10.2
- d. Effluent Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.6 SR 6.3.10.8
- e. Sampler Flow Rate 1 (a) D SR 6.3.10.1 Measuring Device SR 6.3.10.8
- 5. OFFGAS PRE-TREA'IMENT MONITOR
- a. Noble Gas Activity Monitor 1 (c) F SR 6.3.10.1 Providing Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7 GRAND GULF, UNIT 1 A-26 Revision 18 - 02/96 l.
a . . .
TABLE 6.3.10-1 (Continued)
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RADIOACTIVE GASEOUS EFFLUENT' MONITORING INSTRUMENTATION CONDITIONS REFERENCED FROM MINIMUM CHANNELS. REQUIRED SURVEILLANCE INSTRUMENT OPERABLE APPLICABILITY ACTION A.2 ' REOUIREMENTS
- 6. OFFGAS POST-TREA7NElfr MONITOR
- a. Noble Gas Activity Monitor Providing Alarm and Automatic Termination of Release . 2 (b) E SR 6.3.10.1 SR 6.3.10.3 >
- 7. ~ STANDBY GAS TREATMENT EXHAUST' MONITORING SYSTEM (A&B)-
- a. Noble Gas Activity Monitor 1/ system (a) G SR 6.3.10.1 '
Provding Alarm SR 6.3.10.3 SR 6.3.10.5 SR 6.3.10.7 GRAND GULF, UNIT 1 A-27 Revision 18 - 02/96
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Taaf.12 6.3.10 1 (conti mid)
RADIQACTIVI GASIOUS IFFLUElfr EMITORIE .'.'dSTRUMINTATION TABLE IKyrATION (a) At all times.
(b) During main condenser offgas treatment system operation.
(c) When.any steam jet air ejector (SJAI) is in operation.
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GRAND GULF, UNIT 1 A 28 Revision 17 - 03/95
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6.11 RADICACTIVE IFFLUENTS j 6.11.1 LIQUID EFFLUENTS CONCENTRATION l
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LCO 6.11.1 The concentration of radioactive material released in liquid q-effluents to UNRISIT.ICTED ARIAS shall be limited to ten times the effluent concentrations specified in lb CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained i noble gases. For dissolved or entrained noble gases, the l
concentration shall be limited to 2 x 10*4 microcuries/ml total activity.
I i APPLICABILITY: At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION, TIME A. The concentration of A.1 Restore the concentracios. Isumediately j radioactive material to within the above If.ritu.
released in liquid
- effluents to UNRESTRICTED 832 AREAS exceede the above
- limits. A.2 Declare the liquid rs.! fluent
) waste treatment eyeter.
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GRAND GULF, UNIT 1 A-23 Revision 17 - 03/95
SURVEILLANCE REQUIREMIartS SURVEILLANCE FREQUENCY SR 6.11.1.1 The radioactivity content of each batch of Per (ODCM) radioactive liquid waste shall be determined Table 6.11.1 1.
before release by sampling and analysis in accord-ance with (ODCM) Table 6.11.1-1.
SR 6.11.1.2 Post release analyses of samples composited f rom Per (ODCM) batch releases shall be performed in accordance Table 6.11.1 1.
with (ODCM) Table 6.11.1-1.
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l GRAND OULF, UNIT 1 A 30 Revibion 17 .03/95
i
' TABf2 6.11,1-1 RADIQ ETIVE LI MID WASTE EAMPLING AMD ANALYSIS PROGRAM ,
j I
Minimum Type of Lower Limit Liquid Release Sampling Analysis Activity of Detection l Type Frequency Frequency Analysis (LLD) l (sci /ml) (a) l A. Batch Waste Prior to Prior to Principal Csama 5x10*7 Release Release Release h .tters (d)
Tanka (c) Each Batch Rach Batch I-131 1x10-6
' l Prior to 31 days Dissolved and 1x10-5 Release Entrained Gases
- One Batch /M (Gesma emitters) 5 Prior to 31 days M3 1x10-5 i Release Cosposite(b) 4 Each Batch Gross Alpha 1x10*7 i Prior to 92 days Sr-SS, Sr 90 5x10*8
- Release Composite (b) sach Batch Fe-55 1x10-6 B. SSW Basin Prior to Prior to Principal Gamma 5x10*7 (before Release Release Emitters (d) i blowdown) Bach - Each Batch -
Blowdown I-131 1x10 6 1
1 GRAND GULF, UNIT 1 A-31 Revision 17 - 03/95
. _ . _ _ . - _ . . _ _ . _ . . _ . . . . . . . . . _ . _ _ _ _ . _ ~ . _ _ .. -_.__.._m._.._._ ___.m __.._~._.m.._..___
d 4 l 1
4 I
I Tint 2 E.11.1-1 (carie f =Ad)
RADIQACTIVE LIOUID WASTI SAMPLING AND ANALYSIS PROGRAM
! TABLI 1R7 RATION I
The LLD is the smallest concentration of radioactive material in a sample that
)
i a. i 4 will y1sid a not count (above system background) that will be detected with 95%
l probability with only 5% probability of falsely concluding that a blank
) observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
l 4.66 sb j LLD .
d i I e V e 2.22 x 106 y . exp(.xAg)
! where I LLD is the "a priori
- lower limit of detection as defined above (as gCi l per unit mass or volume). (current literature defines the LLD as the'l detection capability for the instrumentation only, and the MDC, minimum detectable concentration, as the detection capability for a j i giw a instrument, procedure, and type of sample.) i
- l sb is the standard deviation of the background counting rate or of the l
{ counting rate of a blank sample as appropriate (as counts per minute) j i
! I is the counting efficiency (as counts per disintegration)
V is the sample sise (in units of mass or volume) 2.22 x 10' is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection (or and of the sample collection period) and time of counting The value of ab used in the calculatice of the LIa for a particular me'surement a system should be based on the actual observed variance of the background counting rate or of the, counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
Typical values of I, V, Y and At should be used in the calculation.
It should be recognised that the LLD is defined as an & ggiggi (before the fact) )
limit representing the capability of a measurement system and not as & nosteriori !
(after the fact) limit for a particular measurement. l l
GRAND GULF, UNIT 1 A 32 Revision 17 - 03/95
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TABLE 6.11.1 1 (continumd)
RADIQA. M LIODID WASTE SAMPLING AMD ANALYSIS PROGRAM a
1 .
TABLE NOTATION (Continuad)
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of saspling esployed results in a specimen which is representative of the liquids released.
- c. A batch release is the discharge of liquid wastes of a discrete volume. Before j' sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
I
-d. The principal gasmia emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co 58, Co 60, 2n 65, Mo-99, Cs-134, Cs-137, Co-141, and Co-144 ' Itis list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and j i identifiable, together with the above nuclides, shall also be identified and reported.
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i GRAND GULF, UNIT 1 A-33 Revisica 17 - 03/95
~. _ _ _. _ _ . _ _ _ m _ _ . - ~ _ . ._ __ . . _ _ . . . . . _ .
l 6.11 RADICACTIVE IFFIDElfrS 6.11.2 LIQUID IFFUElfr DOSE LCO 6.11.2 The dose or does comunitment to a MESSER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED ARIAS shall bet
- a. 5 1.5 area to the total body and 5 5 mrom to any organ, during any calendar quarter, and
- b. 5 3 mrom to the total body and 5 10 arem to any organ, during any calandar year. l l
l APPLICABILITY: At all times. l ACTIONS
...........................................gKyrIE.......................................
- 1. The provisions of Specification 3.0.3 are not applicable.
- 2. Separate 6 dition entry is allowed for each of the above limits, l CONDITION REOUIRED ACTION CCEIPLETION TIME A. The calculated dose from A.1 Initiate action to prepare Isumediately the release of radioactiu and submit a Special Report materials in liquid within 30 days.
effluents greater than any of the abova limits. &EE A.2 Declare the liquid effuent waste treatment system inoperable.
(continued)
GRAND OULF, UNIT 1 A.34 Revision 17 03/95 4
- __ _ _ . . _ . _ _ _ _ _ _ . . . _ _ _._ m. _ _ _
c Y
i Ismediately The calculated doses fras 3.1 Initiate action to 3.
the release of radioactive calculate the direct materials in liquid radiatico contributicos effluents greater than from the reactor unit and twice any of the above from outside storage tanks limits. to 'D* ermine whether the l tot - 'anual dose or dose cook.mnt to any MEISER OF THE PUBLIC greater than:
4 1 a) 25 mrom to the total body or any organ,
- except the thyroid.
95 I b) 75 mrom to the I
thyroid.
am SURVIILLAIICE P3fvJIREMEIFFS i 4
80RVIILIABICE FREQUEllCY l
I 1
SR 6.11.2.1 Cumulative dose contributione freet liquid 31 days l
' effluents for the current calendar quarter and the 4
' current calendar year shall be determinad in accordance with the methodology and parameters of the ODOf.
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GRAND GULF, UNIT 1 A-35 Revision 17 - 03/95 1
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e 6.11 RADIOACrIVE IFFLUENTS 6.11.3 LIQQID EFFLUENT WASTE TREA'DEIWr a
i LCO 6.11.3 The liquid radwaste system shall be used to reduce the radioactive 4 materials in liquid wastes before their discharge when the projected-doses due to the liquid effluent to UNRESTRICTED AREAS would be >
l 0.06 mrem to the total body or > 0.2 area to any organ, in a 31. day j period.
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APPLICABILITY: At all times. ,
1
- ACTIONS i I 8
...........................................NOrES....................................... !
The provisions of Specification 3.0.3 are not applicable. !
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! CONDITION RBQUIRED ACTION COMPLNTION TIME ;
1 1
i j A. Radioactive liquid waste A.1 Initiate action to prepare Immediately l being discharged without and submit, a Special y treatment and in excess of Report within 30 days. l I
l the above limits.
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I SURVEILLANCE REQUIREMENTS SURVIILLANCE FREQUENCY SR 6.11.3.1 Doses due to liquid releases to UNRESTRICTED AREAS 31 days shall be projected in accordance with methodology and parameters in the ODCM.
l
................J......NorE.......................
Not required to be met when the projected dose less than or equal to the above limit. l Verify the liquid effluent waste treatment system is being used to reduce radioactive materials before discharge.
i GRAND GULF, UNIT 1 A.36 Revision 17 03/95 4
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4 i l 1 j 6.11 RADIQACTIVE EFFLUElrFS i
i t
i 6.11.4 GASEOUS IFFLUENTS - DOSE RATE 1
l 2
i LCO 6.11.4 The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be:
8
- a. For noble gases: 5 500 mres/yr to the total body and 5 3000 ,
7 mrom/yr to the skin, and )
l
- b. For all iodine-131, iodine-133, tritium and all radionuclides in i
particulate form with half lives greator than 8 days: 5 1500 !
ares /yr to any organ. i
- l r APPLICABILITY
- At all times, j 4
ACTIONS COMPLETION TIME CONDITION REQUIRED ACTION 1
j A. Dose rate exceeding the A.1 Decrease the release rate Yemediately j above limits. to within the above limit (s) .
i' hED 4
A.2 Declare the ventilation
- exhaust treatment system l inoperable.
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i GRAND GULF, UNIT 1 A 37 Revision 17 - 03/95 i
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l SURVEILLANCE REQUIREMIlfr5 SURVEILLANCE FREQUENCY SR 6.11.4.1 The dose rate due to noble gases in gaseous Per (ODCM) effluents shall be determined to be within the Table 6.11.4-1.
e above limits by obtaining representative saspies 4 and performing analyses in accordance with (CDCM) Table 6.11.4 1.
1 1
4 SR 6.11.4.2 The dose rate due to iodine-131, ic dine -133, Per (CDCM)
- tritium and to radionuclides in particulate form Table 6.11.4 1.
' with half lives greater than 8 days in gaseous effluents shall be determined to be within the abova limits by obtaining representative sosples
- and oerforming analyses in accordance with (ODCM) Table 6.11.4 1.
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4 GRAND GULF, UNIT 1 A-38 Revision 17 - 03/95
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TABLE 6.11.4-1 RADICACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit Gaseous Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis (LLD) -
(pC1/ml) (a)
A. (1) Radweste 31 days 31 days Principal Gasuna 1x10**
Building Grab Sample (f) Emitters (b,e) ventilation .
Exhaust H-3 1x10*6 (2) Fuel Handling Continuous (d) 7 days (c) I-131 1x10*12 Area Ventila- (f) Charcoal tion Exhaust Sample I-133 1x10 10 (3) Containment Continuous (d) 7 days (c) Principal Gesuna 1x10*11 ventilation (f) Particulate Emitters (e)
Exhaust Sasple (I-131, Others)
(4) Turbine Continuous (d) 31 days Gross Alpha 1x10"ll Building (f) Composite ventilation Particulate Exhaust Sample
. Continuous (d) 92 days Sr-89, Sr 90 1x10'11 (f) Composite Particulate Sample Continuous (f) Noble Gas Noble Gases 1x10-6 Monitor Gross Beta or Gamusa B. (1) Offgas Post 31 days 31 days Principal Gasana 1x10*4 Treatment Grab Sangle(f) Emitters (e)
Exhaust, whenever
~
there is flow (2) Standby Gas Treatment A Exhaust, whenever there is flow (3) Ctandby Gas Treatment B Exhaust, whenever there is flow See " Table Notation" which follows. ,
GRAND GULF, UNIT 1 A-39 . Revision 17 - 03/95
TinLE 6,11,4-1 Pant 4 mad)
RADInitTIVE niBe00S WASTE enweLING AND AM1 LYSIS PROGRAM TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will yield a not count (above system background) that will be detected with 95%
probability with only 5% probability of falsely concluding that a blank observation represents a "real' signal.
For a particular measurement system (which may include radiochemical separation):
4.66 sb ,
LLD =
I*V* 2.22 x 10'
- Y
- emp (-1At) where LLD is the "a priori" lower limit of detection na defined above (as gci per unit mass or volume). (current literature defines the LLD as the decoction capability for the instrumentation only, and the IEC, minierum detectable concentration, as the detection capability for a given instrument, procedure, and type of sample.)
ab is the stanAard deviation of the background counting rate or of the coupeir.g rate of a blank sosple as appropriate (as counts per minute)
I is the counting efficiency (as counts per disintegration)
[
t V is the sample sise (in units of mass or volumme) l 2.22 x 106 is the number of disintegrations per minute per microcurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide at is the elapsed time between masple collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
Typical values of I, V, Y and At should be used in the calculation.
It should be recognised that the lim is defined as an a agiggi (before the fact)
. . limit representing the capability of a essasurement system and not as a nosteriori (after the fact) limit for a particular measurement.
GRAND GULF, UNIT 1 A.40 Revision 17 - 03/95
l l
TABLE E.11.4-1 (cant 4nuadt omnicacrryg niaRODS WASTE *"*tTNG AND ANALYSIS PROGRAM TABLE NOTATION (Continued)
- b. Analyses shall also be performed following startup from cold shutdown, or a THERIEL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. This requirement does not apply its (1) routine analysis required by the Surveillance Requirements of LCO 3.4.8 shows that the DOSE EQUIVALIIrf I-131 concentration in the pramary coolant has not increased more than a factor of 3; and (2) the noble gee monitor showd enat effluent activity has not increased more than a factor of 3.
- c. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing or after removal from sampler. Sampling and analyses shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days f allowing each shutdown, startup or 'DEERMkL POWER changs exceeding 15 percent of RATED THERMAL POWER in one hour. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> e.re analysed, the corresponding LLD's may be increased by a factor of 10. 'ntis requirement does not apply if:
(1) routine analysis required by the Surveillance Requirements of LCO 3.4.8 shows that the DOSE EQUIVALEIrf I 131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
o
- d. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with ICOs 6.11.4 and 6.11.E. l
- e. The principal gassna emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr SS, Xe-133, Xe-133m, Xe 135, and Xe- ,
138 for gaseous emissions and th 54, Fe 59, Co 58, Co-60, En 65, Mo-99, Cs 134, I Cs 137, Co-141 and Co-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
- f. When a monitor is placed in an inoperable status solely for performance of required Surveillance's, entry into associated Conditions and Required Actions in accordance with LCO E.3.10 may be delayed for up to I hour.
GRAND GULF, UNIT 1 A-41 Revision 17 03/95
l
) -
6.11 PADICACTIVE EFFIDENTS 6.11.5 GASE005 EFFIRENT DOSE . NOBLE GASES a 4 .
LCO 6.11.5 The air dose due to noble gases released in gaseous effluents, from the site to areas at and beyond the SITE SOUNDARY ahall be:
- a. 5 5 mrad for gassa radiation and 514 mrad for beta radiation,during any calendar quarter and
- b. 510 mrad for gamma radiation and S 20 mrad for beta radiation during any calendar year.
APPLICABILITY: At all times.
ACTIONS
...........................................myrE3.......................................
- 1. ne provisions of Specification 3.0.3 are not applicable.
- 2. Separate Condition entry is allowed for each of the above limits.
CONDITION REQUIRED ACTION COMPLETION TIME A. The calculated air dose A.1 Initiate action to prepare Ismediately from the radioactive noble and submit,
- Special gases in gaseous effluents Report wit a 10 days.
greater than any of the above limits. AE!
A.2 Declare the ventilation exhaust treatment system inoperable, l
i (continued) l l
~
GRAND GULF, UNIT 1 A-42 Revision 17 - 03/95
4 B. The alculated doses from B.1 Initiate action to Isenediately the release of radioactive calculate the direct
, waterials in gaseous radiation contributions 1 effluents greater than from the reactor unit and twice any of the above frcza outside storage tanks limits, to determine whether the --
+ total annual does or dose comudtment to any MBSER OF THE FUBLIC gteater thans a) 25 mram to the total body or any organ, 4 except the thyroid.
l M
b) 75 ares to the thyroid.
l SURVEIf f *"CE 83_ _i --
as 4 SURVIILIANCE FREQUENCY
$ SR 6.11.5.1 Cumulative dose contributions for noble gases for 31 days the current calendar quarter and current calendar j year shall be determined in accordance with the
! methodology and parameters in the CDCM.
I
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- GRAND GULF, UNIT 1 A.43 mayisica 17 03/95 4
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6.11 RADIQACTIVE EFFLUENTS
?
6.11.5 GASEOUS UFFLUENT DOSE - IODINE.131, IODINE-133, TRITItat AND RADIONUCLIDES IN PARTICUIATE FORM I LCO 6.11.6 The dose to a MEMBER OF '!1EE PCf5LIC from iodine 131, iodine 133, l 1
tritium and radionuclides in particulate form with half. lives !
greater than 8 days in gaseous effluents released, from the site to !
areas at and beyond the SITF BOONDARY shall bei i
l a. S 7.5 ares to any organ during any calendar quarter, and
- b. 5 15 mram to any organ during any calendar year.
1 i
i APPLICABILITY: At all times. I
'I l ACTIONS i i 1
...........................................mcrrIs....................................... {
l 1. The provisions of Specification 3.0.3 are not applicable, j
- 2. Separate Condition entry is allowed for each of the above limits.
)
l
' CONDITION REQUIRED ACTION COMPLETICW TIME !
1 A. The calculated dose from A.1 Initiate action to prepare Isundiately the release of iodine.131, and submit, a Special iodine 133, tritium and Report within 30 days, radionuclides in particulate form, with &E half. lives greater than 8 days, in gaseous effluents A.2 Declare the ventilation
-greater than any of the exhaust treatment system above limits. inoperable. !
(continued)
GRAND QULF, UNIT 1 A . <, 4 Revision 17 - 03/95
i j
i
- i b -
t
- 3. The calculated doses from B.1 Initiate action to Isumediately 4 the release of ra/aoactive calculate the direct j materials in gast,ous radiation contributions
- affluents greater than fram the reactor unit sad twice any of the above front outside storage tanks l limits. to determine whether the total sanual dose or dose l
caustituent to any IstBER OF l TME FUBLIC greater thans l
- a) 25 aren to the total body or any organ, except the thyroid, i
l M
b) 75 mrom to the thyroid.
l
- l i aunVII" M -- - u -- as j EURVIILLANCE FREQUENCY
~
SR E.11.E.1 Cumulative dose contributions from iodine 131, 31 days
- iodine 133, tritiust and radionuclides in
! particulate form with half lives greater than 8 !
! days for the current calendar quarter and current
- calendar year shall be determined in accordance a.
with the methodology and parameters in the CDCM.
t t
j.
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a i
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GRAND GULF, UNIT 1 A 45 Revision 17 - 03/95 i
4
--. . ~ . _ - _ . . .- . _ _ . . _ _ . . _ . . - - -. . . - .-
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4 6.11 RADICACTIVE EFFIDE3rtS 6.11.7 GASEOUS RADWASTE TREATMElrf t
I' LCO- 6.11.7 De GASEOUS RADWASTE TRIA'DEENT (OFFGAS) SYSTEM shall be in operation.
APPLICARILITY: When the accc::: jet air ejector (SJAE) is in operation.
l
]
ACTIONS i ...........................................pCfrES....................................... !
ne provisions of Specification 3.0.3 are not applicable, j
....................................................................................... j 4
CONDITION REQUIRED ACTION COMPLETION TIME l
, A. Gaseous radwaste from the A.1 Restore treatment to this 7 days SJAE being discharged discharge.
i without treatment.
i 4 E. Required Action A.1 and 3.1 Initiate action to prepare Immediately
?- Associated Caspletion Time and submit a Special Report
- not met, to the Cosmission within f 30 days, i
i i
SURVEILLANCE REQUIREMENTS
, i SURVIII. LANCE FREQUINCY l 1
i i SR 6.11.7.1 Ensure that the GASEOUS RADWASTE TREATMEIrr 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />
! (OFFGAS) SYSTEM is operating.
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GRAND QULF, UNIT 1 A.46 Revision 17 - 03/95 1
ia
6.11 RADIOACTIVE BFFIRErrs 6.11.0 VENTIIATION EINADST TREATMENT SYSTEN LCO 6.11.8 The VIWrILATION SIMADST TREATMEart SYSTEM shall be used to reduce radioactive materials in gaseous waste before their discharge when
}
the projected dose due to gaseous affluent releases to areas at and j beyond the SITE BOUNDARY in a 31 day period would exceed 0.3 mrom to i any organ.
I t
i APPLICABILITY: At all times.
ACTIONS
..........................................3gyrgs.......................................
l The provisions of Specification 3.0.3 are not applicable.
! CONDITION REQUIRED ACTION COMPLrrION TIME i
A. Gaseous waste being A.1 Initiate action to prepare Immediately I
' and submit a special Report discharged without treatment and greater than to the Cossaission within the above limit. 30 days.
I l
SURVEILLANCE REQUIREMErfS SURVEILLANCE FREQUENCY 1
SR 6.11.8.1 Doses due to gaseous releases to areas at and 31 days beyond the SITE BOUNDART'shall be projected in accordance with the methodology and parameters in the ODOt.
&El
~ ~
.......................surrE...........--.-..-
- 1. Not required to be met when the ventilation exhaust treatment system is undergoing routine maintenance.
- 2. Not required to be met when the projected dose less than or equal to the above limit.
Verify the ventilation exhaust treatment system is operating.
ORAND GULF, UNIT 1 A.47 Revision 17 03/95 l
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- 6.12 RADIOLOGICAL ENVIVMAL tcNITORING 1
6 12.1 3 cati 1DRING P'AOGRAM 1,
LCO 6.12.1 The radiological environmental monitoring program shall be conducted i as specified in ODCM Table 6.12.1 1. The results of this program shall be validated by use of an Interlaboratory Comparison Program corresponding to samples required by ODQt Table 6.12.1 1.
j 4
APPLICABILITY: At all times.
4 i ACTIONS
...........................................N0T58...................-......-...........
I The provisions LCO 3.0.3 are not applicable.
l ......................................................................................
I I CONDITION REQUIRED ACTICM CGEPLETION TIME i
4 i
A. 'The radiological A.1 Initiate action to include Ismediately enviran=antal monitoring in the next annual program not being Radiological Environmental i
- conducted as specified in Operating Report, a ODCM Table 6.12.1 1. description of the reasons i for not conducting the
' gg program as required and the
- plans for preventing a i 4 The required recurrence. l Interlaboratory C w ison j j Program not performed.
B. The level of radioactivity B.1 Initiate action to prepare Immediately i as the result of plant and submit a special I
< effluent in an Report within 30 days, envirorumental sampling ;
medium at a specified location exceeding the reporting levels of 0D01 l Table 6.12.1 2 when i averaged over any calendar quarter.
(continued) l i
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GRAND GULF, IRIIT 1 A.48 Revision 17 03/95 1
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, ACTIONS fcontinued) l CONDITION REQUIRED ACTION COMPLETION TIME I
l C. Milk or broad leaf C.1 Initiate action to identify Isenediately l vegetation sampling is this changed location (s) in relocated from one or more the next Annual Radioactive 4 of the sample locations Effluent Release Report. ;
required by ODCM Table j j 6.12.1-1. &E2
} C.2 Add this location (s) to the 30 days i radiological envirarmeental
- monitoring program.
4 SURVEILLANCE REQUIREMElfrS SURVIILIANCE FREQUINCY 4
f SR 6.'12.1.1 Radiological enviran=antal monitoring sasples Per ODCM l shall be collected pursuant to CDQf Table 6.12.1-1 Table 6.12.1-1.
i from the locations given in the table and figures j, in the ODQt and shall be analysed pursuant to the 3 requirements of ODCM Tables 6.12.1-1 and 6.12.1-3.
i SR 6.12.1.2 Conduct an Interlaboratory Comparison Program and 366 days 4 include a susesry of the results in the Annual
! Radiological Enviran=antal Operating Report.
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4 j QRAND GULF, UNIT 1 A-49 Revision 17 - 03/95 4
TARYR E_12_1-1 OptnATinarat, RADInfMIcAL ENVIrrC- u mf. igUimi xi-Taar2 PRrrmaag Exposure Pathway Number of Samples (a) and/or Sanple Sangling and Type and Frequency and Locations Collection Frequency (a) ,
of Analysis.
AIRBORNE Radiciodine and Sanples from 3 locations: Continuous sampler Particulates operation with sample Radioiodine Cannister:
1 sample close to the SITE I-131; 7 days BOUNDARY having the highest collection per 7 days or as required by dust ,
calculated annual average loading, whichever is groundlevel D/Q. more frequent
- 1 sample from the vicinity of a _
comununity having the highest Particulate Sanplers calculated annual average Gross beta radio-groundlevel D/Q. activity following filter change (b), -
1 sangle from a control location composite (by location) 15-30 km (10-20 miles) distance (d) for ganana isotopic (c);
92 days DIRECT RADIATION (e) 16 stations with two or more 92 days dosimeters or one. instrument . Ganuna dose; 92 days for measuring and recording dose rate continuously. The stations will be placed in accessible sectors alternating between '
inner and outer ring locations *:
- 1) an inner ring of stations in ;
the general areas of the SITE BOUNDARY
- 2) an outer ring approximately 3 to 5 miles from the site. ,
8 additional stations should be placed in special interest areas ,
such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations.
- A-50
. Revision 20 - 07/96
I TABLE 6.12.1-1 (Contim_m d) s OPERATIONAL RADIOIAGICAL ENVIRC.NAL ruumini-TMn PROGRAM Exposure Pathway Number of Samples (a) and/or Sample Sangling and Type and Frequency and Locations Collection Frequency (a) of Analysis WATERBORNE ,
Surface 1 sample upstream .92 days Ganuna isotopic (c) and I sample downstream ;
tritium analyses; 92 days '
1 sample downstream 366 days during a Liquid Radwaste Ganuna isotopic (c) and Discharge tritium analyses; 366 days Ground Samples from 2 sources 366 days Gamma isotopic (c) and tritium; 366 days Sediwnt from i sample from downstream area 366 days Shoreline 1 sample from upstream area Ganana isotopic (c);
366 days INGESTION Milk - 1 manple from milking animals .92 days when required Ganuna isotopic (c) and within 8 km if milk is available conenercially. I-131; 92 days 1 control sample (only if indicator exists) > 8 km if milk is available
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i GRAND GULF, UNIT 1 A-51 Revision 20 - 07/96 i
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Tmarm g_12.1-1 (Cone 4nued)
OPRsATInarmr. RADinTMICAL ENVIE--1mL W-i 1uar fur 2 panr2nang
- :-,sure Pathway Number of Samples (a) Sampling and and/or sample and Locations Type and Frequency Collection Frequency (a) of Analysis Food Products 1 sasple of bre b leaf 92 days when available vegetation grown in one of. Ganuna isotopic (c) two different offsite locations and I-131: 92 days with highest anticipated annual average ground level D/Q if milk sampling is not performed 1 sample of similar 92 days when available vegetation grown 15-30 km Ganuna isotopic (c) distant if milk sampling is not and I-131: 92 days performed GRAND GULF, UNIT 1 A-52 Fevision 20 - 07/96 ,
t e _.m #-. _ _ _ _ _ . . _ .__.___mo..._..__-__.m____ _ . . _ _ _ _ _ _ -
______r.,_ _ _ _ _ __.__m_ _._ - ______ _ - . _ _ . _ m - -. n.r e-_ r - - _ _ _ _ _ v . -- - - - -
.- ,-.... - ~ . . . . . . - - ~ . . . . . ~ . , . _ . - . - - _. -.-n--_. _._n..- . - - . . _ - - u i
TART.D C 12_1-1 Wn t" 4 Mund )
ODWD RTI AMET, D AMTof fv1T f*17. ENVT DN-ilm i nt. MOhii IDR TNd DRodDEM TABLE NOTATION As described in the ODCM.
placed in an adjacent inner or outer location.If a location is not accessible, instruments may be a
specific parameters of distance and direction sector.from the centerline of one i
reactor, and additional description where pertinent, shall be provided for each
! and ODCM.
every saaple location in Table 6.12.1-1 in the table (s) and figure (s) in the
!- Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological
- Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous and equipment conditions, other legitimate seasonalreasons.
unavailability, malfunction of automatic sampling If specimens are unobtainable due to sampling equipment, malfunction, every effort shall be made to complete corrective action before the end of the next sampling period. All above deviations from the sampling schedule Operating Report. shall be documented in the Annual Radiological Envirewmental It is recognized that, at times, it may not be possible or. practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table (s) for the ODCM reflecting the new location (c) .
b Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air or water is greater than ten times the yearly mean of control samples for'any individual samples, medium, gamma isotopic analysis should be performed on the c
Gamma isotopic analysis means the identification and quantification of gamma-emitting facility, radionuclides that may be attributable to the affluents from the d
The purpose of this sample is to obtain background information.
GRAND GULF, UNIT 1 A-53 Revision 20 - 07/96
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i TAnfE 6.12.1-1 (Continued)
OPERATIONAL RADIOIDGICAL ENVIRONMENTAL MONiiGRING PROGRAM TAnfE NOTATION (Continued) e One or more instruments, such as a pressurized ion chamber, for measuring and recording integratingdose rate continuously may be used in place of, or in. addition to, dosimeters.
For the purposes of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a packet may be considered as two or more dosimeters. Film badges should not be used for measuring direct radiation.
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GRAND GULF, UNIT 1 A-54 Revision 20 - 07/96
TABLE 6.12.1-2 REPORTING 12VELS FOR RADIOACTIVITY CQgeCENIRATIQRS IN INVIROIWearrAL SAHFLES Reporting LeveleD water AirborneParticugate Fish Milk Food Products Analysis (pCi/1) or Gases (pCi/m ) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet)
H-3 2 x 10 NA NA NA NA Hn-54 1 x 10 MA 3 x 10 MA NA Fe-59 4 x 10 NA 1 X 10 NA NA Co-58 1 x 10 NA 3 x 10 MA NA Co-60 3 x 10 NA 1 x 10 MA NA En-65 3 x 10 MA 2 x 10 NA NA Er-Ita-95 4 x 10 NA NA NA NA I-131 2 0.9 NA 3 1 x 10 Cs-134 30 10 1 x 10 60 1 x 10 Cs-137 50 20 2 x 10 70 2 x to Ba-La-140 2 x 10 NA NA 3 x 10 NA
- For drinkgng water samples. 1his is a 40 CFR Part 141 value. If no drinking water pathway exists, a value ,
of 3 x 10 pCi/1 may be used.
b See BASES 6.12.1 for reporting requirements when multiple or unlisted radionuclides are detected.
GRAND GULF, UNIT 1 A-55 Revision 17 - 03/95
TABLE 6.12.1-3 pur- y_mme FOR THE IL== T mfTS OF DETECTION ('n lfa bl Airborne Particulate Broad Imaf '
Mater Fish Milk Vegetation Sediment orGag (pci/m ) (pci/kg, wet) (pci/1) (pci/kg, wet) (pci/kg, dry)
Analysis (pCi/1)
Gross beta 4 1 x 10' NA NA NA NA H-3 2 x 10 (d) MA NA NA NA NA ten-54 15 NA 1.3 x 10 2 NA NA NA Fe-59 30 NA 2.6 x 102 NA NA NA l
Co-58,60 15 NA 1.3 x 102 ga ya ya In-65 30 NA 2.6 x 102 NA NA NA r
Er-95 30 NA NA NA NA NA 15 NA NA NA NA NA 2-95 I-131 1 (c) 7 x 10-2 NA 1 60 NA Cs-134 15 5 x 10-2 1.3 x 102 15 60 1.5 x 102 ._
Cs-137 13 6 x 10-2 1.5 x 102 18 80 1.8 x 102 ,
60 NA NA 60 NA NA Ba-140 15 NA NA 15 NA NA j La-140 e
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GRAND GULF, UNIT 1 A-56 Revision 17 - 03/95 t
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e unt 2 6.12.1 3 (cont i m tad) 2 BGLII3E2M VAIRES FOR THI IDWER LIMIT 5 07 DETRCTION (LLD)
TABLE ACTATION t
- a. Acceptable detection capabilities for thermolustinescent desimeters used for environmental measurements are given in Regulatory Guide 4.13.
- b. Table 6.12.1-3 indicates acceptable detection capabilities for radioactive materials in environmental sagles. These deteccice capabilities are tabulated in terms of the lower limits of detection (LI&s) . The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a not count (above system background) that will be detected with 956 probability with only 56 probability of falsely concluding that a blank observation represents a "real* signal.
For a particular measurament system (which may include radiochemical separation) :
4.66 e b
I
- v e 2.22
- Y
- emp (-lat) where LLD is the "a priori" lower limit of detection as defined above (as pCi j per unit mass or volume) . (current literature defines the LLD as the i detection capability for the instrumentation only, and the acC, minta- detectable concentration, as the detection capability for a '
given instrument, procedure, and typs of sample.) i e is the standard deviation of the background counting rate or of the I b counting rate of a blank sagle as appropriate (as counts per minute)
E is the counting efficiency (as counts per disintegration)
V . is the sagle size (in units of mass or volume) 2.22 is the number of disintegrations per minute per picoeurie Y is the fractional radiochemical yield (when applicable)
- 1. is the radioactive decay constant for the particular radionuclide At is the elapsed time between sample collection (or and of the sample collection period) and time of counting The value of ab used in the calculation of the LLD for a particular measurement system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicated variance.
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GRAND GULF, UNIT 1 A 57 , Revision 17 03/95 l
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v1RfR E.12.1 3 (continuad) wavywne ymenes yon m towsm f mTTS OF DETSCTION fitn)
TARI2 MDTATION (Continued) i Typical values of I, V, Y and At should be used in the calculation.
It should be recognised that the LLD is defined as an a ggiggi (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Occasionally background fluctuations, unavoidable small sample sise, the presence of interfering nuclides, or other uncontrollable circumstances may render these IJJs unachievable. In such cases, the contributing factors should be identified and described in the Annual Radiological Envir - atal Operating Report,
- c. LLD f or drinking water samples. If no drinking water pathway exists, the LLD of gasuna isotopic may be used, 3
i d. If no drinking water pathway exists, a value of 3 x 10 pCi/1 may be used.
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l GRAND GULF, UNIT 1 A.58 Revision 17 - 03/95
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I 6.12 RADIOLOGICAL ENVIRONMENTAL MONITORING l
6.12.2 LAND USE CENSUS LCO 6.12.2 A land,use census shall be cu ducted and shall identify within a distance of 8 km (5 miles) the location in each of the I 16 meteorological me.ctors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m2 (500 ft2 )
producing broad leaf vegetation. Broad leaf vegetation, sampling may '
be performed at the SITE BOUNDARY in one of two different offsite locations with the highest predicted D/Os in lieu of the garden !
census.
APPLICABILITY: At all times.
ACTIONS
.......__.................................-NOTES--------- -----------------.-----------
The provisions of LCO 3.0.3 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. A land use census A.1 Initiate action to identify Immediately identifies a location (s) the new location (s) in the which yields a calculated next Annual Radioactive dose or dose commitment- Effluent Release Report.
greater than the values currently being calculated in LCO 6.11.6 B. A land use census B.1 Initiate action to identify Immediately identifies a location (s) these higher dose which yields a calculated location (s) in the next dose or dose commitment Annual Radioactive Effluent (via the same exposure
- Release Report.
pathway) 20 percent .
greater than at a location AND from which samples are currently being obtained B'. 2 Add these location (s) to 30 days in accordance with LCO the radiological 6.12.1.
environmental monitoring program.
GRAND GULF, UNIT 1 A-59 Revision 20 - 07/96
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I SURVEI!1ANCE REQUIREMENTS SURVEILIANCE FREQUENCY I SR 6.12.2.1 Conduct a land use census during the growing '
Once per 2 years season. The land use census shall verify the appropriateness of the sample location used to ,
fulfill the requirements of LCO 6.12.1 i L
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' T1 A-60
, Revision 20 - 07/96
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BASES FCE SECTION 5.0 LIMITING CCEDITICES FCE OPERATION 6
AND SURVEZY 2 AMCI R30tTEREIENTS d
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i GRAND GULF, UNIT 1 A 61 Revision 17 - 03/95 i
1 6.3 INSTRDMENTATICII 1
aseen 6.j., mAoIoacrivE I.Tocin Errtmner --uustian 1-m-m---imTrom 1
The LCO for radioactive liquid affluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid
- effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures ;
in the CDCat to ensure that the alarm / trip will occus before exceeding ten times the j effluent concentration limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General design Criteria 60, 63 and 64 of Appendix A to 10 CFR 50.
6.3.10 RADIQJcrIVE GARIOUS EFFIDENT RE2EITORIEG INSTERIENTATICE
{
The LCO for radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, gaseous effluents during actual or potential l releases. 'Ihose instruments that monitor the activity of gaseous affluents being released to the envirnament chall have their alarm / trip setpoints calculated in l accordance with the methods in the ODCM to ensure that the alaza/ trip will occur before exceeding the limits of 10 CFR Part 20. Other instruments that monitor offgas j processing, (i.e., Offgas Pre Treatment alonitor and Offgas Post Treatment tecnitor) are calibrated according to plant procedures. The OPERABILITT and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
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i GRA3ED 00LF, UNIT 2. A-62 Revision 17 - 03/95
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l 6.11 RADIQ&cTIVE EFFLUEFFS i
3 maegg 1
A I LIOUID IFFLDINTS I
! s.11.1 CONCENTRATION i
l This LCO is provided to ensure that the concentration of radioactive materials f released in liquid waste affluents to UNRESTRICTED AREAS will be less than ten times the effluent concentration values specified in Appendix 3, Table 2, Column 2 to 10 l
l CFR.20.1001 20.2402. It provides operational flexibility for releasing liquid ettluents in concentrations to follow the Section II.A and II.C design objectives of Appendix I to 10 CFR Part 50. ' mis limitation provides reasonable assurance that the
- levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, l to a MEMBER OF TNI FUBLIC, and (2) restrictions authorised by 20 CFR 20.1301(a) . The 2 concentration limit for dissolved or entrained noble gases is based upon the
- assumption that Ze-135 is the controlling radionuclide and its effluent concentration i
in air (submersion) was converted to an equivalent conoontration in water. This 140 l
does not affect the requirement to comply with the ====1 limitations of 10 CFR 20.1301(a).
l
- The results of pre release analyses and poet release analyses (of composited
+
samples) shall be used with the calculational methada and parameters in the 0D08 to l l, assure that the concentrations at the point of release are maintained within the l
! limits.
, The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs) . Detailed j discussion of the LLD, and other detection limits, can be found in:
! (1) MASL Procedures Manual, MARL-200
! (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative i Determination - Application to Radiochemistry,' Anal. Chem. 40, ses se l (1968).
(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"
j Atlantic Richfield Manford Ccepany Report AEM-2127 (June 22, 1972).
- S.11.2 DORE
! This LCO is provided to implement the requirements of Sections II.A, III.A and j IV.A of Appendix I, 10 CFR Part 50. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in 4 section IV.A of Appendix I which assure that the releases of radioactive material in i liquid effluents to UNRESTRICTED AREAS will be kept 'as low as is reasonably achievable.' Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is r== - =hle assurance that the s
operation of the facility will not result in radionuclido concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. 'the dose calculations in the CDQt implement the requirements in Section III.A of Appendix I that conforsmace with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual esposure of a MEREBER OF THE FUBLIC through appropriate pathways is unlikely to be substantially underestimated.
GRAND GULF, UNIT 1 A-63 ' Revision 17 - 03/95
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j RADIQACTIVE EFFIDENTS neus
)
s.ii.2 Dost (Continued)
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the i methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Ivaluating Ccagliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory j Guide 1.113, " Estimating Aquatic Dispersion of Effluent fremt Accidental and Routine Reactor Releares for the Purpose of Implementing Appendix I," April 1977.
f l This LCO, in conjunction with LCOs 6.11.5 and 6.11.6 is also provided to meet the l dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 20.1301(d).
Even if a site contained up to four reactors, it is highly unlikely that the ..
- resultant dose to a MBSER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if l the individual reactors remain within twice the dose design objectives of 10 CFR 50 j Appendix I, and the direct radiation doses frasi the units (including outside storage i tanks, etc. ) are kept small.
- Special Reportt l LCO 6.11.2 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR
! 50 Appendix I are exceeded.
4 If either the quarterly or the annual limit is exceeded, the report will:
I (1) identify the cause (s) for exceeding the limit (s),
! (2) define the corrective actions that have been taken to reduce the releases,
{ ud I
(3) define the corrective actions to be taken to ensure that future releases
- will be in compliance with the limits.
If a drinking water supply is taken from the receiving water body within three miles
, downstream of the plant discharge, the report shall also include:
(1) results.of radiological analyses of the drinking water source, and j (2) the radiological ispect on finished drinking water supplies with regard to j the requirements of 40 CFR 141.
j If the doses exceed the limits of 40 CFR 190, 25 mrens to the whole body or any organ, except the thyroid, which is limited to 75 mroms, the report shall:
1
- (1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, j (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiation exposure (dose) to a
', MEMBER OF 'mE PUBLIC frca uraniust fuel cycle sources, including all effluent pathways and direct radiation, for the caleadar year that includse the
. . release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material involved, (5) describe the cause of the exposure level or concentrations involved, j GRAND GULF, UNIT 1 A 64 Revision 17 - 03/95 1
i
RADIQACTIV5 EFFIDIIrfS i i
RAsas I
- 6.11.2 Dost (Continued) 4 (6) describe a course of action that should result in the limitation of the annual dose to a NENBER OF THE PUBLIC to within the 40 CFR 190 limits. ;
For the purposes of the report it may be assumed that the dose ecsunitment to the MEIBER OF THE PDELIC frcsi other uranium fuel cycle sources is
, negligible, with the exception that the dose distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be consids=d.
The special Report with a request for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203 (a) (4), is
-, considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is ccepleted. The variance only relates to the limits of 40 CFR 1
190, and does not apply in any way to other requiremente for dose limitations of 10 l
CFR 20, as addressed in LCOs 6.11.1 and 6.11.4. An individual is not considered a MEMBER OF ' DER PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
Demonstration of compliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 ran limit of 10 CFR 20.1301. ,
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GRAND GULF, UNIT 1 A 65 Revision 17 - 03/95 i
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a t
RADIQACTIVE EFFIRINTS maers l
1 6.11.3 LIQUID MASTE TREATMEarf The LCO that the appropriate portions of this systest be used when specified
. provides assurance that the releases of radioactive materials in liquid effluents
- will be kept "as low as is reasonably achievable." his I40 implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to
, 10 CFR Part 50 and the design objective given in Section II.D of W adix I to 10 CFR i Part 50. The specified limit governing the use of appropriate portions of the liquid
- radwaste treatment system were specified es = wisitable fraction of the dose design objectives set forth in Section II.A of App =adix I, 10 CFTA Part 50, for liquid effluents.
l Special Reports l LCO 6.11.3 requires preparation and submittal of a report in accordance with 10 CFR l 50.4 if radioactive liquid waste is being discharged without treatment and in excess
- of the limits. he report shall includes (1) an emplanation why liquid radweste was being discharged without treabnent,
.. (2) identification of any inoperable equipment or subsystems which resulted in liquid radwaste being discharged without treatment,
- (3) the reason for the inoperability (4) action (s) taken to restore the inoperable equipment to an OPenaarm status, (5) summary descriptions of actions taken to prevent a recurrence.
GASEOUS EFFLUENTS i
- 6.11.4 DORE BMW
\
) This LCO provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MERSER OF TME FUBLIC in an UNRRSTRICTED ARIA, either at or beyond the SITE BOMERY in excess of the design 1 objectives of W ad4w I to 10 CFR Part 30. This specification is provided to ensure i that gaseous affluents from all units on the site will be appropriately controlled.
! It provides operational flexibility for releasing gaseous affluents to satisfy the i Section II.A and II.C design objectives of AppanA4w I to 10 CFR Part 50. For MEsplERS
- OF THE PUBLIC who may at times be within the SITE 300MDART, the occupency of that MEMBER OF THE PUBLIC will usually be sufficiently low to e v a==te for the reduced i atmosphere dispersion of gaseous effluents relative to that for the SITE SOUNDARY.
} The calculational methods and parameters in the ODCM are used to assure that the dose
- rates are maintained within the limits. Examples of calculations fos such MERSERS OF
'IME PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The L specified release rate limits restrict, at all times, the corresponding dose rates above background to a MERSER OF THE PUBLIC at or beyond the SITE SOUNDARY to less 4
than or equal to 500 mrom/ year to the total body or to less than or equal to 3000 mrom/ year to the skin. These releases rate limits also restrict, at all times, the j corresponding thyroid dose rate above background to a child via the inhalation
- pathway to less than or equal to 1500 mresi/ year. This specification does not affect
! the requirement to comply with the annual limitations of 10 CFR 20.1301(a) .
$ The does rate due to radioactive gaseous effluents shall be determined in
. accordance with the methodology sad parameters of the CDQt.
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- GRAND GULF, UNIT 1 A-66 Revision 17 - 03/95
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d RADIO &cTIVE EFFIRElrfS I
4 RAREB 1
f 6.11.4 men m'n (Continued) i The required detection capabilities for radioactive materials in liquid waste l samples are tabulated in terms of the lower limits of detection (LIms) . Detailed
. discussion of the LLD, and other detection limits, can be found ins .
4 l l (1) HASL Procedures Manual, HAEL 300 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and Quantitative l Determination - Application to Radiochemistry," Anal. Cham. 40, 596 93 (1968).
(3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques,"
- Atlantic Richfield Hanford Company Report AEM 2537 (June 22, 1972).
i E.i1.5 DORE - NORLE GAREE
! This LCO is provided to implement the requirements of Sections II.3, III.A and
! IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements j, the guides set forth in Section II.B of Appendix Z. Se ACTICII statemaats provide i the required operating flexibility and at the same time implement the guides set
} forth in Section IV.A of W M4x I to assure that the releases of radioactive
- material in gaseous effluents to 055tESTRICTED AREAR will be kept 'as low as is
- reasonably achievable." j
)
- he Surveillance Requirements implement the requirements in Section III.A of 1 i Appendix I that conformance with the guides of Appendix I be shown by calculational
! procedures based on models and data such that the actual exposure of a m et OF THE i PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
I The dose calculations established in the ODChi for calculating the doses due to the j actual release rates of radioactive noble gases in gaseous effluents are consistent i with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses
- to Man from Routine Releases of Reactor. Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50,. Appendix I,' Revision 1, October 1977 and Regulatory
- Guide 1.111, " Methods for Estimating h=a=pharic Transport and Dispersica of Gaseous
- Effluents in Routine Releases from Light Mater Cooled Reactors," Revision 1, July 3
1977. The ODC3R equations provided for determining the air doses at and beyond the j SITE BOUNDARY are based upon the historical average atmospheric conditions.
]
1 This LCO, in conjunction with LCOs 6.11.2 and 6.11.5 is also provided to meet the
! dose limitation of 40 CFR 110 that has been incorporated into 10 CFR 1301(d) . Even if a site contained up to four reactors, it is highly unlikely that the resultant does to a MEISER OF '11tB PUBLIC will exceed the dose limits of 40 CFR 490 if the individual reactors remain within twice the does design objectives of 10 CFR 50
, Appendix I, and if the direct radiation doses from the units (including outside storage tanks, etc.) are kept maall.
GRAND GULF, UNIT 1 A.g7 Revision 17 - 03/95
RADIQJCTIVE EFFIDIrfS macre cosa wwm nieme (Continued) s.ii.s Special Report: )
LCO 6.11.5 requires preparation and submittal of a report in accordance with 10 CFR l 50.4 and as. defined in 10 CFR 20.2203 f a) (4), if the dose design objectives of 10 CFR 50 Appendix I are exceeded.
If either the quarterly or the annual limit is exceeded, the report will:
(1) identify the cause(s) for exceeding the limit (s),
(2) define the corrective actions that have been taken to reduce the releases, and (3) define the corrective actione to be taken to ensure that future releases will be in compliance with the limits.
If the doses exceed the limits of 40 CFR 190, 25 arens to thei whole body or any organ, except the P.hyroid, which is limited to 75 mress, the report shall (1) define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits, (2) include the schedule for achieving conformance with the above limits, (3) include an analysis that estimates the radiatica esposure (dose) to a MEbSER OF THE FUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive madtrial involved, (5) describe the cause of the esposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MEMame oy 1115 PUBLIC to within the 40 CFR 190 limits.
For the pugosos of the report it may be assumed that the does comeitsent to ,
the MEbSER OF TME FUBLIC front other uranium fuel cycle sources is negligible, with the exception that the dose distribution from other nuclear e fuel cycle facilities at the some site or within a radius of 8 kilometers must be eensidered.
The Special Report with a rdquest for a variance (provided the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in
. accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203 (a) (4) , is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.
The variance only relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitatiop4 of 10 CFR 20, as addressed in 140s 6.11.1
. . and 6.11.4. An individual is not consirared a men OF '!115 FUBLIC during any period l in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
Damanatration of compliance with the limits of 40 CFR 190 or with the design i objectives of Appendix ! to 10 CFR 50 will be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301.
GRAND GULF, UNIT 1 A.st Revision 17 - 03/95 i
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j 6.11.6 man - TODrum.121, toefun.122. TRITTint amn manimmat Tnan IN PARTIL"'T7 LATE FORat I'
This 140 is provided to impleasant the requirements of Sections II.C, III.A and l IV.A of Appendix I, 10 CFR Part 50. Se Limiting Conditions for Operation are the I guides set forth in Section II.C of kr"*tz I. The ACTION statements provide the i required operating flexibility and at the same time implement the guides set forth in
& Section IV.A of Appendix I to assure that the releases of rClicactive materials in j gaseous effluenLe to CNN.ISTRICTED AREAS will be kept "as low ce is reasonably achievable." The ODOE calculational methods specified in the S e eillance l Requirements implement the requirements in Section III.A. of Appendix I that 4 conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Mensame or agua yDBLIC through appropriate pathways is unlikely to be substantially underestimated, no ODCM
. calculational methods for calculating the doses.due to the actual release rates of j the subject materials are consistent with the methodology provided in Regulatory
- Guide 1.109, " Calculation of Ananal Doses to Man from Routine Releases of Reactor
, Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, a )
j Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating I i
Atmospheric Transport and Dispersion of Geseous Effluents in Routine Releases from i Light water-cooled Reactors," Revision 1, July 1977. These equations also provide j for determining the actual doses based upon the historical average atmospheric i conditions. The release rate specifications for iodine 131, iodine-133, tritium and i radionuclides in particulate form are darmad==t as the existing radionuclide pathway I
! to man in the areas at and beyond the SITE BOUNDARY. Se pathways which were f examined in the development of these calculations were: (1) individual inhalation of I airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation I with subsequent consumption by man, (3) deposition cato grassy areas where milk j animals and meat producing animals grase with consumption of the milk and meat by i man, and (4) deposition on the ground with subsequent exposure of man.
1 I his LCO, in conjunction with I40s 6.11.2 and 6.11.5 is also provided to meet the i dose limitation of 40 CFR 190 that has been incorporated into 10 CFR 1301(d) . Even
! if a site contained up to four reactors, it is highly unlikely that the resultant dose to a MERSER OF THE FUBLIC will exceed the dose limits of 40 CFR 190 if the l individual reactors remain within twice the dose design objectives of 10 CFR 50
- j. Appendix.I, and if the direct radiation doses from the units (including outside j storage tanks, etc.) are kept small, a
! Special Report:
LCO 6.11.6 requires preparation and submittal of a report in accordance with 10 CFR 50.4 and as defined in 10 CFR 20.2203 (a) (4), if the dose design objectives of 10 CFR
! 50 Appendix I are exceeded. -
s
! If either the quarterly or the annual limit is exceeded, the report wills i
. (1) identify the cause(s) for exceeding the limit (s),
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(2) define the corrective actions that have been taken to reduce the releases, i and
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(3) define the corrective actions to be taken to ensure that future releaises l will be in compliance with the limits.
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i i GRAND GULF, UNIT 1 A 69 ' Revision 17 - 03/95
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i i 6.11.6 DORE - IODYNE.131. TODTum.131. TRITTint me RADI0 mines IN PARTIt'UtAvE FORM LContinued)
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- If the doses exceed the limits of 40 CFR 190, 25 areas to the whole body or any 1 organ, except the thyroid, which is limited to 75 mrens, the report shall
) (1) define the corrective action to be taken to reduce subsequent releases to
- prevent recurrence of exceeding tne above limits,
! (2) include the schedule for achieving conformance with the above limits, 1
- (3) include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE FUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the l
' release (s) covered by this report, (4) describe the levels of radiation and concentrations of radioactive material involved, (5) describe the cause of the esposure level or concentrations involved, (6) describe a course of action that should result in the limitation of the annual dose to a MERSIR OF 'INE FUBLIC to within the 40 CFR 190 limits.
For the purposes of the report it may be assumed that the does ccomitment to the MEMBER OF THE FOBLIC from other uranium fuel cycle sources is negligible, with the exception that the does distribution from other nuclear fuel cycle facilities at the same site or within a radius of 8 kilometers must be considered.
The Special Report with a request for a variance (provided,the release conditions resulting in a violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203(4) (4), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is c g leted.
The variance only, relates to the limits of 40 CFR 190, and does not apply in any way to other requirements for dose limitations of 10 CFR 20, as addressed in LCOs 6.11.1 and 6.11.4. An individual is not considered a mesame OF THE FCSLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear ;
fuel cycle. ,
Demonstration of cespliance with the limits of 40 CFR 190 or with the design objectives of Appendix I to 10 CFR 50 will be considered to demoustrate cospliance with the 0.1 rem limit of 10 CFR 20.1301.
GRAND GULF, UNIT 1 A 70 Revision 17 - 03/95
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RADIQACTIyg EFFIRINTS ansEs 6.11.7 an r4 E.11.A tt1Catw1C RADWAsTE T**1'fwearf Run VENTIti'f* ION tvuarigt Town Twearr
'Ihe OPERABILITY of the GASICOS RADMASTE TREATMENT (OFFGAS) SYSTEN and the i VElfrILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for '
use whenever gaseous effluents require treatment before release to the environment.
The requirement that the appropriate portions of the system be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate ;
portions of the system were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 CFR 50, for gaseous effluents.
Special Report:
LCOs 6.11.7 and 6.11.8 require preparation and submittal of a report in accordance with 10 CFR 50.4 including:
(1) an explanation of why gaseous radwaste was being discharged without treatment, (2) identification of the inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, (3) the reason for the inoperability, (4) action (s) taken to restore the inoperable equipment to an OPERABLE status, 1
(5) susunary descriptions of action (s) taken to prevent a recurrence. .. ;
LCO 6.11.8 is not applicable to the Turbine Building ventilation exhaust unless filtration media is installed.
Instruments checked to ensure the GASSODS RADMASTE TREATMENT (OFFGAS) SYSTEM is functioning ares (1) Adsorber Train Bypass Switch (1N64-MS M611),
(2) Bypass Valve Indication (1N64-F045) .
When the Adsorber Train typass Switch is in the TREAT por' tion and the bypass valve indicates CLOSED, the GASEOUS RADMASTE TREA'IMENT (OFFGAS) SYSTEM is functioning.
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GRAND GULF, UNIT 1 A 71 Revision 17 - 03/95
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The radiological monitoring program required by this Lc0 provides measurements of radiation and of radioactive materials in those esposure pathways and for those i radionuclides, which lead to the highest potential radiation emposures of MBSERS OF l
THE'PUBLIC resulting from the station operation. This monitoring program implements
! Section IV.B.2 of W ad4= I to 10 CFR Part 50 acd thereby supplements the
< radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation us not higher then-expected on the basis of the effluent measurements and modeling of the environmental
- esposure pathways. The initially specified monitoring program will be effective for j at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational emperience.
l The detection capabilities required by Table 6.12.1-3 are state of-the art for ;
4 routine environmental measurements in industrial laboratories. It should be i recognised that the LID is defined as an *a priori" (before the fact) limit .
j representing the capability of a particular measurement. Analyses shall be performed ,
i in such a manner that the stated LEDs will be achieved under routine conditions.
l Occasionally background fluctuations, unavoidably small sasyle sines, the presence of )
{
interfering nuclides, or other uncontrollable circunstances may render these LEDs ;
i unachievable. In such cases, the contributing factors will be identified and l l
described in the Annual Radiological Environmental Operating Report.
1 For a more conglete discussion of the LID, and other detection limits, see the following (1) HASL Procedure Manual, H&BL;lAR (revised annually) .
i (2) Currie, L. A., " Limits for Qualitative Detection and Quantitative l Determination - Applicatica to Radiochemistry,8 Anal. cham. 40, 586-93
=
(1958). ,
4 (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," !
Atlantic Richfield Manford Company Report Amu 2527 (June 22, 1972). !
If milk or broadleaf vegetation sampling locations are relocated, the cause shall be reported in the next Annual Radioactive Effluent Release Report. Also, include in ,
this report, revised CDQt figure (s) and table (s) reflecting the new locations. 'Ihe t specific locations from which samples were unavailable may then be deleted from the radiological environmental monitoring program and the table (s) in the CDCM, provided the locations from which the replacement samples were obtained are added to the table (a) as replacement locations.
The requirement for participation in an approved Interlaboratory.L w ison Program is provided to ensure that independent checks on the precision and accuracy of the measures of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to da===trate that the results are valid for the purposes of Section IV.E.2 of Appendix I to 10 CFR Part 50.
GRAND GULF, tGrIT 1 A 72 (,dvision 17 - 03/95
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i 6.12.1 REMITORING PROGRAM (Continued) f Special Report:
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l LCO E.12.1 requires preparation and submittal of a report in accordance with 10 CFR l
-50.4 when:
(1) the level of radioactivity as a result of plant effluents in an environmental sampling medium at a specified location exceeds the reporting i level (s) in ODCM Table 6.12.1 2 when averaged over a calendar quarter, or ,
i >
j (2) more than one of the radio nuclides in 0D 3 Table 6.12.1 2 are detected in the saspling medium and
< - =aermelen fil + eencontration (2) + .. 21.0, or ,
l reporting level (2) i reporting level (1)
.! (3) radio nuclides other than those in CDGE Table 6.12.1-2 are detected, and
!- the potential annual dose to a Mamma Oy 'gign yDBLIC is equal to or greater than the calendar year limits of I40s 6.11.2, 6.11.5.and 6.11.6.
l The report shall (1) identify the cause(s) for ===anH ag the limit (s) , and (2) define the corrective actions to be taken to reduce radioactive offluents so the potential annual dose to a unama CF 't1ER yWLIC is less than the ;
calendar year limits of LCOs 6.11.2, 6.11.5 and 6.11.6. l The Special Report is not required if the measured level of radioactivity is not the result of plant effluents: however in such an event, the acadition shall be reported and :.dentified in the Annual Radiological Enviremmental Operating Report. ,
E.12.2 LAND USE CIESUS h is I40 is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of the census, he best information from door-to door survey, visual or aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant esposure pathways via leafy vegetables will be identified and monitored since a garden of this oise is the minimum required to produce the quantity (26 / year) of leafy vegetables assumed in Regulatory Guide 1.109 for consusption by a Id. To determine this minl== garden sise, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/ed. Specificaticas for broad leaf vegetation sospling in the Table E.12.1-1 shall be followed, including analysis of control semples.
GRAND GULF, UNIT 1 A 73 Revision 17 - 03/95
6.12 RADICI4X11 CAL INVIRf2ndINTAL RONITORING RASES 6.12.2 LAND USE CENSUS (Continued)
The land use census should utilise information which provides the best results, such as a door-to door survey, an aerial survey or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 5.6.2.
When the Land Use Census requires addition of sampling location (s)*to the Environmental Monitoring Program, the sempling locaticas(s) having the lowest calculated dose or dose commitments (s), via the same exposure pathway, may be deleted I from the monitoring program. This deletion may take place after October 31 of the 3 year in which this land use census was conducted.
I The new sampling location (s) shall be identified in the next Annual Radioactive Effluent Release Report including a revised figure (s) and table (s) for the ODCM.
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