ML061000544
| ML061000544 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/27/2002 |
| From: | Rushton P Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 36010-C, Rev 11.2 | |
| Download: ML061000544 (24) | |
Text
Approved By '. Procedure Number Rev P. D. RushtoiE Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 1 of 24 PRB REVIEW REQUIRED OFFSITE DOSE CALCULATION MANUAL (ODCM)
IMPLEMENTATION AND CONTROL PROCEDURE USAGE REQUIREMENTS- SECTIONS Continuous Use: Procedure must be open and readily available at the work location. Follow procedure step by step unless otherwise directed.
Reference Use: Procedure or applicable section(s) available at the work location for ready reference by person performing steps.
Informal ion Use: Available on plant site for reference as needed. ALL Printed March 16, 2006 at 12:14
Approved By .. Procedure Number Rev P. D. Rushto gtleElectric Generathng Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 2 of 24 yNFORMATION USE 1.0 PURPOSE The purpose of this procedure is two fold: first, to define responsibilities within Plant Vogtle and Southern Nuclear Operating Company regarding the Radioactive Effluent Control Program and the Radiological Environmental Monitoring Program (REMP); and second, to provide operational guidance to the user of the manual.
2.0 DEFINITIONS 2.1 OFFSITE DOSE CALCULATION MANUAL The methodology for:
° Calculating dose to the public from liquid and gaseous effluents 0 Calculating liquid and gaseous radiation monitor setpoints to assure compliance with 10 CFR 20 Appendix B, Table 1 and Table 2.
0 Total dose calculations for 40 CFR 190 compliance.
The ODCM also includes:
° REMP.
O Radioactive Effluent Control Program.
2.2 BATCH RELEASE The discharge of liquid or gaseous waste of a discrete volume (e.x., waste monitor tank or gas decay tank).
2.3 CONTINUOUS RELEASE Discharge of liquid or gaseous waste from a volume or system that has an input flow during the continuous release (ex., steam generator blowdown or plant vent).
2.4 SAFETY FACTOR (SF)
A term used only for monitor setpoint calculation for both liquid and gaseous releases. It is a term used to incorporate a conservative margin in a setpoint calculations. This term is required by NUREG 0133.
Printed March 16,2006 at 12:14
Approved By Procedure Number Rev P. D. Rushtori Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 3 of 24 2.5 ALLOCATION FACTOR (AF, AG)
A term used only for monitor setpoint calculations during simultaneous liquid (AF) or gaseous (AG) releases. The term allows for the allocation of a site instantaneous limit to a specific release point. The sum of the allocation factors for either liquid releases or gaseous releases will not exceed 1.
2.6 EFFLUENT MANAGEMENT SYSTEM (EMS)
A software package utilized by the Canberra Industries to control, among other things liquid and gaseous effluents in accordance with 10 CFR parts 20 and 50. The EMS consists of four modules and one supplement.
- a. Data Base Maintenance
- b. Liquid Permit Processing
- c. Gaseous Permit Processing
- d. Annual Reports
- e. Extended Dose Processing (Supplement) 2.7 DISCHARGE POINT Any discharge that goes to the environment. It is also synonymous with effluent. (Ex.,
plant vent).
2.8 RELEASE POINT Any process that proceeds to a discharge point. (Ex., gas decay tank).
2.9 EFFLUENT CONCENTRATION LIMIT (ECL)
Concentration limit set by IOCFR20 Appendix B Table II for each radionuclide.
3.0 MODIFICATIONS TO THE ODCM 3.1 INITIATION OF A CHANGE Any change to the ODCM will be submitted to the Chemistry Manager in accordance with Procedure 00402-C, "Licensing Document Change Request". Sufficient detailed information shall be included to support the change without benefit of additional or supplemental information. Any change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.
Printed March 16, 2t)06 at 12:14
Approved By Procedure Number Rev P. D. Rushton Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Numbe.
3/27/2002 CONTROL 41 of 24 3.2 REPORTING REQUIREMENTS Any change to the ODCM must be included with the Radioactive Effluent Release Report for the period for which the change occurred in accordance with Procedure 00152-C, "Federal And State Reporting Requirements". Documentation to the fact the changes to the ODCM have been found acceptable to the PRB will be included in the Radioactive Effluent Release Report.
3.3 STYLE GUIDE Any changes to the ODCM will be accompanied by a bar in the right hand margin of the affected pages. Clearly indicating the area of the page that was changed, and shall indicate the date (e.g. month/year) the change was implemented.
3.4 EFFECTIVE DATE Any modification to the ODCM will become effective after it has been reviewed by the Plant Review Board (PRB) and approved by the General Manager Nuclear Plant (GMNP). If the change involves a reduction in the Q.A. Program Commitment, Prior approval by the U.S. NRC will be required (Procedure 00402-C, "Licensing Document Change Request").
4.0 DEPARTMENTAL RESPONSIBILITIES TO SUPPORT THE ODCM 4.1 OPERATIONS 4.1.1 Review release forms for compliance with Technical Specifications/ODCM and authorize the release.
4.1.2 Will notify the Chemistry Department of process and effluent radiation monitor alarms.
4.2 ENVIRONMENTAL AFFAIRS - CORPORATE 4.2.1 Provide VEGP with meteorological data to be used for effluent calculations.
4.2.2 Coordinate implementation of the REMP (chapter 4 of ODCM) in cooperation with the GPC Environmental Laboratory.
4.2.3 Write Annual Radiological Environmental Operating Report in accordance with Section 7.1 of ODCM and Technical Specification 5.6.2.
4.3 CHEMISTRY 4.3.1 Sample and analyze liquid and gaseous effluents.
4.3.2 Determine radiation monitor setpoints for liquid and gaseous effluents.
Printed March 16, 2306 at 12:14
Approved By . Procedure Number Rev P.D usti ogtde Electrc ~~enera A 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 5 of 24 4.3.3 Perform dose calculations for liquid and gaseous effluents.
4.3.4 Prepare and/or assemble Radioactive Effluent Release Report.
4.3.5 Prepare pre and post release data sheets for liquid and gaseous effluents.
4.3.6 Will base radiochemical methods used for the analysis of effluents on a nationally recognized source such as ASTM, "Standard Methods of Water and Waste Water Analysis", or HASL-300.
4.3.7 Will maintain and follow a Quality Assurance Program that is in compliance with Regulatory Guide 4.15. (Procedure 31000-C, "Chemistry Quality Assurance And Control Program").
4.3.8 Dose calculations will be based on dose and meteorological methodology described in the ODCM and measured effluent data.
4.3.9 Will revise ODCM as necessary.
4.4 ENGINEERING 4.4.1 Advise Chemistry of any proposed changes to the liquid or gaseous processing system that could result in an increased dose to the public.
4.4.2 Perform evaluations to determine if proposed modification to an effluent treatment system is acceptable.
5.0 EXPRESSION OF RESULTS OF MEASUREMENTS The following describes the handling of results to ensure uniform notation for numerical values to be used in effluent data and semiannual reports.
5.1 UNITS 5.1.1 Activity - the units for activity will be the microcurie ([tCi) or Curie (Ci).
5.1.2 Concentration - the units for concentration should be [ICi/ml for liquids and [tCi/c(c for gases.
5.1.3 Release rate - the unit for a release rate is jtCi/sec.
Printed March 16, 2006 at 12:14
Approved By Procedure Number Rev P.Rushtoii D. -NVogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 6 of 24 5.2 ERROR ANALYSIS 5.2.1 Counting Statistics - counting statistics should be included in the records of measurements. The error should be that of the 1.96 a (95%) confidence level.
5.2.2 Significant figures - numerical values should be rounded off to 3 significant figures.
When adding or subtracting, the number with the fewest decimal places, not necessarily the fewest significant figures, puts the limits on the number of places that may be carried in the sum or difference. When numbers are multiplied or divided together, the results should be rounded off to contain the same number of significant figures as are present in the factor with the fewest number of significant figures.
5.2.3 Propagation of Error - data that contains an error term which is to be operated on should have the resultant error calculated in the following manner.
5.2.3.1 Addition/Subtraction - if a series of numbers are to be added or subtracted the error associated with the results is represented by:
aT = (a2 +b' + )
aT = total standard error a,b,c = standard error of the first, second and third term, etc.
Printed March 16, 21)06 at 12:14
Approved By Procedure Number Rev P. D. Rushtoi: Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Numbe 3/27/2002 CONTROL 7 of 24 Example:
The total number of Curies (and the standard error) released from the plant vent for each month are listed below, determine the total number of Curies released and the standard error for the quarter.
Jan. 10.1 +/- 0.3 Ci Feb. 3.6+/-0.1 Ci Mar. 2.3 +/- 0.2 Ci Solution:
Standard Error:
FT= (a2 +b2 +c2 ... )/2 T 0(.3)2 +(0.1)2 +(02)2]1/2
(=
aT = (0.14)1/2 aT= 0.37 Total Curies 10.1 + 3.6+2.3= 16.0 16.0 +/-0.37 5.2.3.2 Multiplication/Division (two terms)
The standard error associated with the product (A x B) or the quotient (A/fB) is determined by:
Multiplication:
T [(A) +( B ])2 Division:
aT =A-B[( +B ) + (c ]
Where: aT = total error Printed March 16, 2)06 at 12:14
Approved By - Procedure Number Rev P. D. Rushtoni - Vogtle Electric Generatingg-Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 8: of 24 Example Given:
Determine the counter efficiency if a known standard has a disintegration rate of 106 +/-6.0 dpm and the count rate was determined to be 45 +/-3.0 cpm.
Solution:
Total Standard Error for Counter Efficiency (A ) (B)]
cTT= A510[(B 2 l( 45) 106)2 aT = 0.037 Counter Efficiency:
E C.R.
D.P.M.
E 45 106 E=0.425 E = 0.425 +/-0.037 5.3 NUMERICAL VALUES Numerical results (including percentages) should be reported in external floating point form, using the letter "E" to denote the exponent to the Base 10. For example, 3.00%
should appear as 3.00 EOO%; 0.000325 should appear as 3.25E-04 and 157.6 should appear as 1.58E02. The term not detected or < MDC should not be used. If the activity in the sample is less than the maximum sensitivity of measurement, the value should be reported as less than the maximum sensitivity. For example, if the maximum sensitivity is 5.OOE-07 XCi/ml, the value should be reported as < 5.OOE-07 RiCi/ml.
Printed March 16, 006at 12:14
Approved By Procedure Nt mnber Rev P. D. RushtoBi Vogtle Electric Generating Plant AL 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 9 of 24 5.4 MINIMUM DETECTABLE CONCENTRATION 5.4.1 Gamma Ray Spectroscopy - any amount of radioactivity detected by the gamma ray spectroscopy system will be recorded and reported. Liquid and gaseous samples analyzed via gamma ray spectroscopy will have MDC's of at least those found in ODCM Table 2-3 and 3-3.
NOTE Vogtle does not do gross activity analysis. Therefore all MDC's are based on 5E-07 i[Ci/mL.
5.4.2 Gross Activity - Liquid Samples - any radiochemical analysis employing gross activity will have a MDC of < IE-07 [tCi/ml when screening for a liquid effluent sample.
6.0 RECORDS RETENTION 6.1 CHANGES TO THE ODCM AND IMPLEMENTING PROCEDURES Any change to the ODCM and any of its implementing procedures will be reviewed by the PRB and approved by GMNP prior to implementation. Therefore any revision to the ODCM or its implementing procedures will be available from Document Control after being reviewed by the PRB and approved by the GMNP.
NOTE Implementing procedure for the REMP is the responsibility of SNC Environmental Affairs group and/or the GPC Environmental Laboratory.
6.2 Effluent Data - effluent data (hardcopy) for each Effluent Release Report will be forwarded in accordance with Procedure 31045-C, "Chemistry Logkeeping, Filing And Record Storage".
NOTE Per commitment #7245, the calculated dose from carbon-14 being released from the Plant Vent as CO2 is 5.8E-01 mrem for Bone and - 1.16E-01 mrem for any other organ. This is an annual dose based on a child at 2.092 Km in the WSW sector for the ground plane inhalation and vegetation pathways. This is also based on NUREG 017 which assumes - 8.0 curies per year of carbon-14 is released. This is not required to be included in the Effluent Release Report and is normally not included.
6.3 Software - any changes to software such as the effluent management system, gamma spectroscopy, and quality control package will be changed in accordance with Procedure 00410-C, "Control of Computer Software".
Printed March 16, 2006 at 12:14
Approved By Procedure Number Rev P. D. Rushtoni -VogtleElectricGeneratingPlant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 10 of 24 7.0 LIOUID RELEASES 7.1 LIQUID MONITOR SETPOINTS 7.1.1 Setpoint Calculations Setpoint calculations are performed to ensure compliance with 10 CFR 20 Appendix B Table II. The calculations are for the site and apply to all gamma emitting radionuclides detected by the gamma spectroscopy system and selected non gamma emitting nuclides.
The gamma emitting nuclides are measured before each release whereas the selected non gamma emitting nuclides are estimated based on composite samples from previous releases. The most recent composite analysis is used for this calculation.
Liquid setpoint calculation methodology is Section 2.3.
7.1.2 Monitor Safety Factor The safety factor for all liquid monitors should be 0.50. This factor can be changed in accordance with Procedure 36013-C, "EMS Data Base Control" by the laboratory supervisor as required. In no case will the S.F. exceed 0.75.
7.1.3 Allocation Factor The allocation factor for liquid releases need only be applied when there are simultaneous liquid releases. The allocation factor will be used to "allocate" the release limit to a specific discharge (effluent) point.
The sum of the allocation factors for the discharge of liquids or gaseous (effluent) points can never exceed 1. If no simultaneous releases of liquid waste monitor tanks are being made the allocation factor for both units may be used for that one tank discharge.
There are three methods of determining the allocation factors associated with a liquid.
They are:
- 1. I (where N is the number of release points).
- 2. An engineering judgment on the probable distribution of ECL fractions.
- 3. The ECL fraction of actual or estimated release points.
A F ECL (F,,)
(ECe )(F,) + (EcL2fct) ) + (ECL3)(F3)
Wherte AFn = allocation factor for any release point n Printed March 16, 2006 at 12:14
Approved By Procedure Number Rev P. D. Rushtoii : -VogtleElectric Generating Plant; 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 11. of 24 ECL - Effluent concentration limit Exam-3le (method 3)
Determine the allocation factor that should be allowed for stream 1. If the ECL fraction for stream I is 1.8 at a flow rate of 75 gpm and the ECL fraction for stream 2 is 0.6i at a flow rate of 200 gpm.
Solution:
-ECLn(F.)
A (ECL,)(Fl) +(ECL2)(F2 ) + (EC4)(F3)
AF- (1.8)(75gpm)
(1.8)(75gpnm) + (0.6)(200gpm)
AF1 = 0.53 7.1.4 Determination Of Liquid Monitor Setpoints Liquid monitor setpoints are determined by using the actual "mix" of radionuclides that will pass the monitor.
A conservative setpoint based on Cs-137 may be used as long as it is verified conservative to the "actual mix" setpoint prior to a release.
Monitors that are expected to see "clean" streams (steam generator blowdown, nuclear service cooling water, turbine building drain and control building sump) will also have default setpoints. The default high level alarm will be based on 10ECL of Cs-137 whereas the default alert alarm will be 2 E-06.
The response of these monitors will be relative to Cs-137 in units or cpm per [Ci/ml when using the fixed (default) gain factor approach. See attached appendix for example calculations.
Tolerance factor of up to 10 could be used in monitor setpoint calculations. Refer to Section 2.3.2 of ODCM for details.
Printed March 16, 2)06 at 12:14
Approved By Procedure Number Rev P. D. Rushtoll E 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 12 of 24 Monitor backgrounds are controlled such that the calculated high alarm setpoint is sufficiently above the background that the monitor would not be subjected to spuiious alarms Refer to the 34300 series of procedures for details on background handling.
7.2 BATCH RELEASES The contents of a tank will be recirculated as defined in 37000-C, "General Grab Sampling Techniques", before a sample is obtained. The sample will be drawn during the recirculation of the contents of the tank.
7.3 WASTE WATER RETENTION BASIN Discharges will not normally be made to the waste water retention basin if the concentration at the release point to the basin will result in a ECL fraction of greater than 10 for Appendix B Table II, of 10 CFR 20. Pre-release calculations for any such discharge will use the discharge flow rate of the WWRB pump. Final dose calculations will be based on the composite analysis.
7.4 DILUTION WATER Dilution water for a liquid release can be supplied from any of the normal sources of dilution such as tower blowdown and cooling tower makeup bypass line. NO CRED1T will be allowed for dilution water from any startup pond. Minimum of 12,000 GPM will be available for liquid releases.
7.5 PROJECTED LIQUID DOSE LIMITS Liquid releases may be made which will exceed the 31 day projected dose provided requirements of ODCM 2.1.4 are met. Doses due to anticipated plant operations will be included in these projections when necessary.
8.0 GASEOUS RELEASES 8.1 GASEOUS MONITOR SETPOINTS 8.1.1 Setpoint Calculations Setpoint calculations are performed to ensure compliance with 10 CFR 20 Appendix B, Table I. The calculations are for the site and are only for noble gases.
The gaseous setpoints are to be calculated for both the dose to the total body (TB) values and to the skin and to use the lesser of these two for the setpoint calculation. As a general rule, the dose to the total body will limit (control) the setpoint.
Printed March 16, 2006 at 12:14
Approved By . Procedure Nt mber Rev P. D. Rushtoni Vogtle Electric Generating Plant - 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Numbei 3/27/2002 CONTROL 13 of 24 The equations that represent these two limits are:
- 1. Total Body KQi - < 500inrem/ yr Q
Where:
K; = gamma dose factor to body of nuclide i Q = meteorological dispersion coefficient Q= release rate of nuclide i
- 2. Skin (Li + 1.1 Mj)Q 1- < 3000nrem / yr Q
Where:
Li = beta dose factor to skin of nuclide i i= gamma dose factor to air of nuclide i Q= release rate of nuclide i 8.1.2 Monitor Safety Factor The safety factor for all gaseous monitors should be 0.50. This factor can be changed in accordance with Procedure 36013-C, "EMS Data Base Control" by the laboratory supervisor as required. In no case will the S.F. exceed 0.75.
8.1.3 Allocation Factor The allocation factor will be used to "allocate" the dose limit to a release point. The sum of the allocation factors for the discharge (effluent) points from the site can never exceed 1.
The allocation factor can also be used to distribute the dose rate of processes "feeding" a discharge point. If this occurs, the sum of the allocation factors for the process stream cannot exceed the allocation factor of the discharge point.
There are three methods of determining the allocation factors associated with a gas. They are:
- 1. 1 (where N is the number of release points).
Printed March 16, 2006 at 12:14
Approved By Procedure Number Rev P. D. RushBy . Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 14 of 24
- 2. An engineering judgment on the probable distribution of dose rates.
- 3. The fraction of actual or estimated dose rates.
Example (method 3)
The dose rate for the plant vent is 3 mrem/yr and dose rate for the turbine building (due to a small leak) is 2 mrem/yr. Determine the A.F. for each of these discharge points.
Solution:
Total (lose rate = 3 mrem/yr + 2 mrem/yr Total dose rate = 5 mrem/yr A.F. for plant vent is thus:
A. F.=: 3 5
A.F. = 0.60 A.F. for turbine building A.F.= 2 5
A.F. = 0.40 An allocation factor of 0.05 will always be used as a minimum for the turbine building vent.
8.1.4 Determination of Gaseous Monitor Setpoints Gaseous monitor setpoints are determined by using the actual "mix" of radionuclides passing the monitor. A conservative setpoint based on Kr88 may be used as long a: it is verified conservative to the "actual mix" setpoint prior to a release. It is also used during periods of no detectable activity in the gas effluent stream.
NOTE Conservative setpoint for ARE-0014 is based on Xe-133.
The alert alarm setpoints are set at no more than 50% of the high alarm setpoint. See attached appendix for example calculations.
Printed March 16, 2006 at 12:14
Approved By - Procedure Nu inber Rev P. D. Rushtori 0 ogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number i3/27/2002 CONTROL I 15 of 24 NOTE The setpoints for each monitor, even though conservative, must be reverified with each sample.
As with liquid samples, the philosophy of monitor setpoints is to ensure the gaseous effluents are within ODCM Specification limits. It is not the philosophy to try and monitor the contents of the gaseous stream.
Monitor backgrounds are controlled such that the calculated high alarm setpoint is sufficiently above the background that the monitor would not be subjected to spurious alarms. Refer to the 34300 series of procedures for details on background handling.
8.2 DOSE RATES AND CALCULATIONS Dose rates and dose calculations for noble gases, iodines, tritium, and particulates will be based on the most recent sample analysis of each group of these respective nuclides.
8.3 TIME OF RELEASE In order to justify the use of average annual meteorology for dose calculations, releases from containment purges and gas decay tanks shall be done randomly.
8.4 GASEOUS ADMINISTRATIVE LIMITS Gaseous releases may be made which will exceed the 31 day projected dose provided requirements of ODCM 3.1.5 are met. Dose due to anticipated plant operations will be included in these projections when necessary.
9.0 CONTROLLING RECEPTOR The controlling receptor will be determined by the data provided from the Land Use Census. The Land Use Survey will be completed annually by the GPC Environmental Laboratory: the results be assessed by SNC Environmental Affairs to determine the need for a new controlling receptor.
Printed March 16, 2006 at 12:14
Approved By . . . Procedure Number Rev P. D. Rushtoii - Vogtle Electric Generdating Plant ; -36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 16 of 24 If, by the Land Use Survey, a milk animal (cow or goat) is located within five (5) miles of the site and it is established that the animal may be milked for human consumption, dose calculations will be performed for a receptor at this location. Dose due to ground-plane and in inhalation pathways will be calculated; doses due to the vegetation pathway will be calculated if there is a garden at the location; doses due to meat animal (beef) pathway will be calculated if there are beef cattle at this location.
10.0 REFERENCES
10.1 J. S. Boegli, R. R. Bellamy, W. L. Britz, and R. L. Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants", NUREG-0133 (October 1978) 10.2 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, U.S. NRC Regulatory Guide 1.109, Rev. 1 (October 1977) 10.3 Vogtle Electric Generating Plant, Units 1 and 2, "Final Safety Analysis Report".
10.4 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U. S. NRC Regulatory Guide 1.1 11, Rev. 1 (July 1977) 10.5 Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, U. S. NRC Regulatory Guide 1.1 13, Rev. I (April 1977) 10.6 Glasstone, G. and Jordan, Walter H., Nuclear Power and Its Environmental Effects, 1980, American Nuclear Society Printed March 16.2006 at 12:14
Approved By Procedure Number Rev P. D. Rushto- Vogtle Electric GeneratIng Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 17 of 24 10.7 PROCEDURES 10.7.1 00402-C, "Licensing Document Change Request" 10.7.2 00152-C, "Federal And State Reporting Requirements" 10.7.3 31 000-C, "Chemistry Quality Assurance Program" 10.7.4 31045-C, "Chemistry Logkeeping, Filing And Record Storage" 10.7.5 36013-C, "EMS Data Base Control" 10.7.6 37000-C, "General Grab Sampling Techniques" END OF PROCEDURE TEXT Printed March 16, 2006 at 12:14
Approved By Procedure Number Rev P. D. Rushto: Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 18 of 24 APPENDIX:
EXAMPLE SETPOINT CALCULATIONS FOR EFFLUENT MONITORS FOR COMPLIANCE WITH 10 CFR 20 Appendix B Table I & II (All Calculations Based On the Methodology Listed In The VEGP ODCM)
- 1. Waste Monitor Tank Monitor (RE-001 8)
II. Monitor On Non Contaminated Streams III. Plant Vent Monitor (1-RE-12442C and 12444C)
IV. Turbine Building Vent (RE-12839C) Unit I and 2 V. Gas Decay Tank (ARE-00014)
VI. Containment Purge Monitor (RE-2565C)
VII. Radiation Processing Facility (RPF) Monitor (RE-1 6980A)
Printed March 16, 2306 at 12:14
Approved By 4Procedure Nu mber Rev P. D. Rushton VogtleElectricGeneratingPlant z& 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 19' of 24
,I. WASTE MONITOR TANK MONITOR (RE-0018)
Assumptions: (These parameters may change. Verify before calculating.)
A.F. = 0.9 S.F. = (0.75)
Release Rate (f) = 75 gpm Dilution Flow (F) = 12000 gpm 1OE.C.L. = IE-5 iiCi/mL (based on Cs-137)
The Monitor Gain Factor will be based on Cs-137.
Calculations:
Cf cE.C.EL.(AF)
F+j (I,: - 5)(12075gpin)(0.9) = I449E-04 75gpm
= 1.449E - 03x05(S. F.)
= 7.2.5E-04 (ptCi/ml (for High Alarm))
The alert setpoint will not exceed eighty (80) percent of the high alarm setpoint.
II. MONITORS ON NON CONTAMINATED STREAMS
- 1. Nuclear service cooling water monitor (RE-0020)
- 2. Steam generator blowdown monitor (RE-0021)
- 3. Turbine Building Drain Monitor (RE-0848)
All of the above monitors will have the high alarm set at IE-5 pCi/ml and the alert set at 2E-06 gCi/ml.
NOTE 1E-05 pCi/ml is 10ECL of Cs-137.
The Monitor Gain Factor will be based on Cs-I 37.
Printed March 16, ,006 at 12:14
Approved By Procedure Number Rev P. D. Rushtoii t -Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Numbet 3/27/2002 CONTROL 20 of 24 III. PLANT VENT MONITOR (1-RE-12442C and 12444C)
Assumptions:
A.G. = 0.59 S.F. = 0.5 Gas = Kr-88 Vent IFlow Rate = 7.08E07 cc (150,326 SCFM) ec The Gain Factor will be based on Kr-88.
X = 4.6 2 x1 0 -7 sec/ m3 Q
Calculations:
- a. first calculate maximum release rate (Q) of the noble gas for both the total body (T.B.) and for the skin.
(1) Total Body (T.B.)
KjQ *< 500(A. G.)(S. F.)
EQ Q < 500(A. G.)(S. F.)
vi K.-X EQ Q< 500(059)(0.50))
(1.47E + 04)(4.62E - 07)
Q* 2.177E+04 gCi/sec (2) Skin (Li + 1.1Mj)Q2E < 3000(A.G.)(S. F.)
Q< 3000(A.G.)(S.F.)
(4 +1.1M1 )X Printed March 16, .:006 at 12:14
Approved By -- i Procedure Number Rev P. D. Rushtoii vogtle Electric GTenerati~ng Plant A 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 21 of 24 Q< 3000(0.59)(0.5)
[2.37E + 03 + 1.1(1.52E + 04)](4.62E- 07)
Q< 1.02E+05 gCi/sec NOTE: The release rate associated with the T.B. is less than the release rate associated with the skin. The T.B. pathway is thus the controlling pathway.
(3) Determine the concentration (C) of Kr-88 F
C 2.17E+04,uCi/sec 7.08EO7cc/ sec C 3.O6E-O41uCi/cc (High Alarm)
Alert Alarm will be set at < fifty (50) percent of the High Alarm.
IV TURBINE BUILDING VENT (RE-12839C) Unit I and 2 Assumptions:
A.G.= 0.05 S.F. = 0.50 Gas =Kr-88 Turbine Building Flow Rate = 4.25E+05 cc/sec Alert Alarm will be set at < fifty (50) percent of the High Alarm the Gain Factor will be based on Kr-88.
X/QG = 2.55E-06 Calculations:
It has already been determined the T.B. pathway is the controlling pathway.
KLQ ' <500(A.G.)(S.F.)
Q
< 500(A.G. )(S. F.)
Ki -
Q< 50o(O.o5)(050)
(1.47E + 04)(255E - 6)
Q< 3.33E+2 p.Ci/sec Printed March 16, 2006 at 12:14
Approved By ., &Procedure Nnmber Rev P. D. Rushton Vogtle Electric Generating Plant 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 22, of 24 C--.
F
_ 3.33E + 02lCi/ sec C=--
- z. 25E + 05cc / sec C = 7 85E-04uCi/cc (High Alarm)
V. GAS DECAY TANK (ARE-0014)
Assumptions:
A.G. 0.2 S.F. = 0.5 Gain Factor will be based on Xe-133.
Gas = Xe-133 (Note: based on the efficiency of Xe-133 vs K-88, Xe-133 is more conservative).
Release Rate = 1.18 E + 04 cc/sec (25 SCFM)
-= 4. 62E - 07 sec/ mn3 Q
Calculations:
Q <_ 500(0.2)(05)
(2.94E + 02)(4.62E - 07)
Q* 3.58E+05 pCi/sec C=---
_3.68E +O5,clCi/sec C=-
- L.18E+04cc/sec C= 31.2 jCi/cc VI. CONTAINMENT PURGE MONITOR (RE-2565C)
Assumptions:
Assume 1/3 of the allowed activity released from the vent originates from the containment A.G.=: *
.59 0.2 3
Printed March 16, 2006 at 12:14
Approved By £N * ~ 4Procedure Number Rev P. D. Rushton : vogue Electric Generating Plant !' I 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 23 of 24 S.F. = 0.50 The Gain Factor will be based on Kr-88.
Flow Rate = 1.56E+06 cc/sec
-= 4.62x10-7 sec/rm3 Q
Calculations:
K, Q-- < 50q A. G.)(S. F.)
0 Q< -500(0.2)(050))
(1.47E +04)(4.62E-07)
Q< 7.:36E+03 gCi/sec C=--_Q C 7.36E+03flCi/sec L.56E+06cc/sec C = 4.72E-031 Ci/cc (High Alarm)
Alert Alarm will be set at < fifty (50) percent of the High Alarm.
Printed March 16, 2006 at 12:14
Approved By Procedure NL mber Rev P. D. Rushto l Vogtle Electric Generating PlantA 36010-C 11.2 Date Approved OFFSITE DOSE CALCULATION MANUAL (ODCM) IMPLEMENTATION AND Page Number 3/27/2002 CONTROL 24 of 24 VII. RADIATION PROCESSING FACILITY (RPF) MONITOR (RE-16980A)
Assumptions:
A.G.= 0.01 S.F = 0.5 Gain Factor Based on Co-60.
Limit at Site Boundary (DRk)= 1500 mrem/y to any organ.
Cobalt 60 was used as the basis for the particulate radionuclide.
The Inhalation Pathway, Child Age Group, T.Body, Co-60 = 2.26 E+4 [iCi/m3 (Raipj) was used.
Release Rate = 8.645 E+6 cc/sec (18200 CFM)
-= 7.78 E-8 Ground Level Release Dispersion Factors Table 3.7.
Q Calculations:
Q< (DRk)(SF)(AG)
(Raipj)(-)
Q Q< (1500)(0.5)(0.01)
(2.26E+4)(7.78E-8)
Q < 4.26E+3 tCi/sec C= Q C = Monitor Setpoint, F = Release Rate F
C- 4.26E+3 8.645E+6 C = 4.93 E-4 [tCi/cc Printed March 16, 2006 at 12:14