ML20041B113
| ML20041B113 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/16/1982 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13323A239 | List: |
| References | |
| PROC-820216, NUDOCS 8202230284 | |
| Download: ML20041B113 (103) | |
Text
{{#Wiki_filter:. . - .- ._ . . . . .. . .. . . . _ . __ t i 1 4 1 4 4 0FFSITE DOSE CALCULATION MANUAL SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2&3 i r i 4 l t l i t i Rey, 6 l 8202230204 820219 2-16-82 PDR ADOCK 05000361 PDR p .- i
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ODCM TABLE OF CONTENTS
.P,a g LIST OF FIGURES ...................................................... 11 LIST OF TABLES ....................................................... iii INTRODUCTION ......................................................... iv 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints ........................ 1-1 1.1.1 Batch Release Setpoint Determination ............. 1-2 1.1.2 Continuous Release Setpoint Determination ....... 1-8 1.2 Dose Calculations for Liquid Effluents . . . . . . . . . . . . . . . . . . . 1-16 1.3 Representative Sampling................................... 1-19 2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints ...................... 2-1 2.1.1 Plant Stack ..................................... 2-1 2.1.2 Condenser Evacuation System ..................... 2-2 2.1.3 C o n t a i nme nt P u r ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-3 2.1.4 Waste Gas Header................................. 2-5 2.2 Ga seous E f fluent Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-31 2.2.1 Noble Gases ..................................... 2-31 2.2.2 Radioiodines and Particulates ................... 2-32 .
2.3 Gaseous Effluent Dose Calculation ....................... 2-34 2.3.1 Noble Gases ..................................... 2-34 l 2.3.1.1 Historical Meteorology ................ 2-34 l 2.3.1.2 Concurrent Meteorology ................ 2-35 2.3.2 Radioiodines and Particulates ................... 2-37 2.3.2.1 Historical Meteorology ................ 2-37 2.3.2.2 Concurrent Meteorology ................ 2-39 i l 3.0 P R OJ E C T ED DOS ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.1 L i q u i d Do s e P r o j e c t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.2 Gaseous Dose Projection .................................. 3-1 i l 4.0 OPERABILITY OF EQUIPMENT ....................................... 4-1 5.0 R ADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 i Rev. 6 2-16-82
ODCH LIST OF FIGURES Figure Title Page 1-1 Calibration Curve for the Radwaste Discharge Line M on i t o r ( 2 /3 RT-7 813 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-13 1-2 Calibration Curve for the Neutralization Sump Discharge M on i t o r ( 2 RT -7 817 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-14 1-3 Calibration Curve for the Turbine Plant Area Sump Monitor (2RT-7821)...................................... 1-15 2-1 Calibration Curves for the Plant Stack Airborne 2-9 thru Honitor (2/3 RT-7808)................................... 2-11 2-2 Calibration Curves for the Containment Purge 2-12 thru and Plant Vent Stack Wide Range Monitor (2RT-7865-1).... 2-14 2-3 Calibration Curves for the Containment Purge 2-15 thru and Plant Vent Stack Wide Range Monitor (3RT-7865-1).... 2-17 2-4 Calibration Curve for the Condenser Air Ejector 2-18 and Gas Monitor (2RT-7818).................................. 2-19 2-5 Calibration Curves for the Condenser Air Ejector 2-20 thru Wide Range Monitor (2RT-7870-1 ) . . . . . . . . . . . . . . . . . . . . . . . . . 2-22 2-6 Calibration Curves for the Containment Airborne 2-23 thru H on i t o r ( 2 RT-7 8 0 4 -1 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-25 2-7 Calibration Curves for the Containment Airborne 2-26 thru Monitor (2RT-7807-2).................................... 2-28 2-8 Calibration Curve for the Waste Gas Header Monitor 2-29 and (2/3 RT-7814)........................................... 2-30 4-1 SONGS 2&3 Radioactive Liquid Waste Treatment Systems ... 4-2 4-2 SONGS 2&3 Radioactive Gaseous Waste Treatment Systems .. 4-3 4-3 SONGS 2&3 Solid Waste Handling ......................... 4-4 i 5-1A Terrestrial Radiological Environmental Monitoring Points ...................................... 5-8 l 5-1B Terrestrial Monitoring Radiological Environmental l Monitoring Program...................................... 5-9 5-2 control Stations for the Radiological Environmental Monitoring Program ....................... 5-10 5-3 Oceanographic Monitoring for the Radiological Environmental Monitoring Program ....................... 5-11 0215$2
ODCM LIST OF TABLES Table Title Page 1-1 Dose Commitment Factors Ai ............................ 1-18 2-1 Dose Factors for Noble Gas and Daughters . . . . . . . . . . . . . . . 2-42 2-2 Dose Parameters Pik .................................... 2-43 2-3 controlling Location Factors ........................... 2-44 2-4 Dose Parameters Rt for WNW Sector ...................... 2-45 thru 2-47 2-5 Dose Parameters R t fo r }@[ S e c t or . . . . . . . . . . . . . . . . . . . . . . . 2-48 thru 2-51 2-6 Dose Parameter Rt for NNW Sector ....................... 2-52 thru 2-55 2-7 Dose Parameter Rg for ![ Sector . . . . . . . . . . . . . . . . . . . . . . . . . 2-56 2-8 Dose Parameter Ri for NNE Sector ....................... 2-57 2-9 Dose Parameter Rt for}i(Sector j ........................ 2-58 2-10 Dose Parameter Ri fo r EN E S ec t o r . . . . . . . . . . . . . . . . . . . . . . . 2-59 2-11 Do-' Parameter R i f o r E[ S e c t o r . . . . . . . . . . . . . . . . . . . . . . . . . 2-60 2-12 Dose Parameter Rt fo r ES E Se c t o r . . . . . . . . . . . . . . . . . . . . . . . 2-61 thru 2-62 2-13 Parameters Used to Calculate Rg ........................ 2-63 5-1 Radiological Environmental Monitoring 5-2 thru Sample Locations ....................................... 5-7 i l l iii Rev. 6 2-16-82
INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL is a supporting document of the RADIOLOGICAL EFFLUENT TECilNICAL SPECIFICATIONS (NUREG 0472). The ODCH describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents. It also calculates the liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains a list of the sample locations for the radiological environmental monitoring program. The ODCM will be maintained at the Station for use as a document of acceptable methodologies and calculations to be used in implementing the technical specification. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology. 1 iv Rev. 4 1-29-82
1.0 LIQUID EFFLUENTS' 1.1 Liquid Effluent Monitor Setpoints (3.11.1.1) Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B Table II, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of specification 3.11.1.1, the alarm / trip setpoints for liquid-effluent monitors and flow measurement devices are set to assure that the following equation is satisfied: cR-F+R $C (9_j)
.where:
C= the effluent concentration limit implementing 10CFR20 for the 1 site, in pCi/ml. t c= the setpoint, representative of a radioactivity concentration in p Ci/ml , of the radioactivity monitor measuring the radioactivity in the waste effluent line prior to dilution and i subsequent release. i f l 1-1 Rev. 4 1-29-82 l
R= the permissible waste effluent flow rate at the radiation monitor location, in volume per unit time in the same units as for F. F= the dilution water flow in volume per unit time. The available dilution water flow (F) is constant.
= 207,500 gpm/ pump (x no. of ciro pumps to be run)
Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative valves shall be periodically reviewed based on actual release data (including, for example, any saltwater discharge of the component cooling water heat exchanger and revised in accordance with the Unit Technical specifications.- 1.1.1 Batch Release Setpoint Determination i The waste flow (R) and monitor setpoint (c) are set to ! meet the condition of equation (1-1) for a given effluent concentration, C. The method by which this is accomp-lished is as follows: Step 1) The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the measured concentrations in the tank (or sump) as determined by analysis. I-2 Rev. 4 1-29-82
C = I Cg1+ g C, + C 3 + C t* Fe (1-2) Where: C = The total concentration {Cgg = The concentration for each radionuclide, i, in the gamma spectrum. C,p The Fe-55 concentration as determined in the previous quarterly composite sample. C, = The gross alpha concentration determined in the previous monthly composite sample. C3 = The Sr-89 and 3r-90 concentrations as determined
- in the previous quarterly composite sample.
t l Ct= The H-3 concentration as determined in the previous monthly composite sample. i 1-3 gey, 4 1-29-82 _ . .~ _ - - _ _ _ _ _ _ _ ,
t-Step 2)- The adjustment factor A, for each batch tank (or sump) is determined using: A= EC d
+C 3
+ C t
+
a . +C re (1-3) i MPC g HPC MPC M PC, MPCp , 3 t HPCgt HPC3, HPCg , = the limiting concentrations of the appropriate HPCye, MPC a radionuclide from 10CFR20, Appendix B. Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-4p ci/mt total activity. Step 3) The radioactivity monitor setpoint may now be specified based on the values of TC g g, F, A and R to provide compliance with the limits of 10CFR20, Appendix B Table II, Column
- 2. The monitor setpoint (cpm) is taken from the applicable calibration curve (Figure 1-1 for 2/3 RT-7813, Figure 1-2 for 2RT-7817) to correspond to the calculated monitor limit C,.
2/3 HT - 7813
.8 F C,fp C < (1-4) m R3 A; + R2 A p + ... + R A Where:
'~* Rev. 4 1-29-82
L C efp = Effective gamma isotopic concentration at the monitor for the tank combination to be released (equal to I C ,g for single tank releases). 1 Rj ({Coi)1 + R2({Cg1)g + ...+Rn({Cg1)n
= (1-5)
Rj+R2 * *** + E n (E C g) j, (EC,g)2 etc. = The total gamma isotopic i i concentration of first tank, second tank, etc. l R j , R2 , etc. = The effluent flow rate from first tank, second. tank, etc. Values of R for each tank are as follows: Radwaste primary tanks R = 140 gpm/ pump (x no. of pumps to be run) Radwaste secondary tanks R = 140 gpm/ pump (x no. of pumps to be run) Primary plant makeup tanks R = 160 gpm/ pump (x no. of pumps to be run) Condensate monitor tanks R = 100 gpm/ pump (x no. of pumps to be run) 1-5 .Rev. 5 2-9-82
A j , A 2, etc. = /alue of A from equation (1-3) for first' l l tank, second tank, etc. , I The .8 is an administrative value used to account for the potential activity for other releases. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10CFR20, Appendix B. Table II, Column 2 from the site. NOTE: If Cm 3.C,pp then no release is possible. To increase C,, increase dilution flow F (by running more circulating water pumps in the applicable discharge structure), and/or decrease the effluent flow rates R ,j Rp, etc. (by throttling the combined flow as l , measured on 2/3 FI-7643), and recalculate C, using the new F R and equation (1-4). 1-6 Rev. 4 1-29-82
If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarm: should an inadvertant release occur. PRT - 7817 C, < - k (i - RA Where: EC g, A = The values of {Cgg and A (as defined i in Steps 1) and 2) above) for the neutralization sump. R = 400 gpm/ pump (x no. of sump pumps to be run). The .1 is an administrative value used to account for the potential activity from other releases. This , assures that the total concentration from all release l points to the plant discharge will not result in a release of concentrations exceeding the limits of ! 10CFR20 Appendix B. Table II, Column 2 from the site. 1-7 Rev. 4 1-29-82 N , ~ ~ -- - g, . r r
l NOTE: If C, < { Cgg then no release is possible. To increase C,, increase dilution flow F (by running more circulating water pumps), and/or decrease the effluent flow rate R (by throttling the flow as measured on 2FI 3772), and recalculate C,using the new F, R and equation (1-6). If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarm should an inadvertant release occur. 1.1.2 Continuous Release Setpoint Determination Step 1) The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown or turbine bailding sump) from the sum of the respective measured concentrations as determined by analysis: C={Cyg + Cq + Ct+C 3 + C, p (1-7) I-0 Rev. 4 1-29-82
where: C gt = the total gamma activity ( pC1/cc) associated with each radionuclide, i, in the weekly composite analysis for the release stream. 4 C, = The total measured gross alpha concentration (pCi/cc) determined from the previous monthly composite analysis for the release stream. Cpe = The total Fe-55 concentration as determined in the previous quarterly composite sample for the release stream. Ct= the total measured 11-3 concentration (p Ci/ce) determined from the previous monthly composite analysis for the release stream. C3 = the total measured concentration (p C1/cc) of Sr-89 and Sr-90 as determined from the previous quarterly composite analysis for the release stream. 1-9 gey, a 1-29-82
Step 2) The adjustment factor, B, for each release stream (steam generator blowdown or turbine building sump) is determined using: B= IC gg + C + C C, + C,p (1-8) 3 t MeC g MF5; MeC MeC, Mec t Fe Step 3) The setpoint for each continuous release radioactivity monitor may now be specified based on the respective values of TCg yg, F B and R to provide compliance with the limits of 10CFRSO, Appendix B. Table II, Column 2. The monitor setpoint (cpm) is taken from the applicable calibration curve (Figure 1-2 for 2RT-7817 and Figure 1-3 for 2RT-7821) to correspond to the calculated monitor limit, C a* 2RT - 7817 C,1 *l W (1_9) RB-Where: i icy g, B = values of EC yg and B (as defined in Steps 1 and 2 above) for the steam generator blowdown. 1 1-10 ! Rev. 4 1-29-82 l l
t R = 400 gpm where R is the effluent flow rate at the radiation monitor as defined in Step 2. The .1 is an administrative value to account for the potential activity in other release pathways. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10CFR20 Appendix B. Table II, Column 2 from the site. a NOTE: C, < {Cgy then no release is possible. To increase C m , increase the dilution flow F (by running more circulating water pumps), and/or decrease the effluent flow rate R (by throttling the flow as measured on 2FI-3772), and recalculate Cmusing the new values of F. R and equation (1-9). 2RT - 7821
.1F{Cgg - 0)
C, < RB I-Il Rev. 4 1-29-82
Where: ICyg, B = values of EC gg and B (as defined in i i steps 1) and 2) above) for the turbine building sump R = 50 gpm/ pump (x no. sump pumps to be run) The .1 is an administrative value to account for the potential activity in other release pathways. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10CFR20, Appendix B, Taole II, Column 2 from the site. NOTE: If 12, < {Cgg then no release is possible. To increase C , increase the dilution flow F (by m running more circulating water pumps) and recalculate Cm using the new value of F and equation (1-10). 1-12 Rev. 5 2-9-82
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1.2 Dose Calculation for Liquid Effluents (3.11.1.2) The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 3.11.1.2 using the following expression. (1-9) t *k kT { (At yCgy 1F)} where: A = the site related adult ingestion dose h committment factor to the total body or an organ, T, for each identified principal gamma and beta emitter, i, from Table 1-1 in mrem /hr per p C1/ml. C the average concentration of radionuclide, 1, 11 = in the undiluted liquid effluent during time period, At in p Ci/ml. y D7 = the dose commitment to the total body or an organ, T, from the liquid effluents for the time period. At y, in mrem. 1-16 Rev. 6 2-16-82
F1 = the near field average dilution factor for Cgi during the time period, At g. This factor is the ratio of the maximum undiluted liquid waste flow a during time period. At y, to the average flow from the site discharge structure to unrestricted receiving waters or
-, maximum liquid radioactive waste flow discharge structure exit flow At y = the length of the I th time period over which C gy and F 1 are averaged for all liquid releases, in hours.
i i l. t u , l~lI Rev. 6 j l 2-16-82 l . -- .- .
TAI 1E 1-1 DOT 00HI'DfNT FACIDRS. Ag (crurAr per pC1/ml) GI-Radio- Total lung LLI Bone Liver 'Ihyroid Kidney Nuclid [hly 2.80 E-1 2.80 E-1 2.80 E-1 2.80 E-1 2.80 E-1 11 - 3 2.80 E-1 1.88 E+6 P - 32 6.46 E45 1,67 E+7 1.04 E+6 3.30 1.20 7.40 1.40 E+3 Q - 51 5.60 2.11 E+3 2.17 EA N - 54 1.35 E+3 7.08 E+3 1.97 E4 2.03 Ed Fe - 55 8.24 E+3 5.12 EA 3.53 EA 8.M EA 1.90 E+5 5.30 E4 6.8 E+5 Fe - 59 7.27 EA 1.22 EA Co - 58 1.35 E+3 6.04 E+2 1.74 E+3 3 26 E4 Co - 60 3.83 E+3 3.23 E+5 Zn - 65 2.32 E+5 1.61 E+5 5.13 E45 3.43 E+5 1.28 E+2 Rb - 86 3.T E+2 6.48 E+2 8.00 E+2 Sr - 89 1.43-E42 4.99 E+3 3.55 E+3 Sr - 90 3.01 EA 1.23 E+5 8.90 E+1 4.90 E4 Y - 91 2.38 1.62 E+4 1.00 E+1 5.12 8.03 Zr - 95 3.47 5.51 Ed Zr - VI 8.14 E-2 8.80 E-1 1.80 E+1 2.70 E-1 2.49 E+2 2.46 E+2 1.51 E+6 Nb - 95 1.34 E42 4.48 E+2 1.28 E42 2.90 E42 2.7/ E42 m - 99 2.44 E+1 1.25 EA 4.61 E+1 1.UI E+2 4.08 E+2 lb - 103 1.03 E+5 lb - 106 2.01 E+2 1.59 E+3 3.UI E+3 2.85 E+3 5.91 E+5 Ag - 110m 8.61 E42 1.57 E+3 1.45 E+3 1.10 E+2 2.77 E+2 5.23 6.70 E-1 7.li E+3 Sb - 124 4.42 E+1 2.20 E+2 2.37 2.00 E-1 2.30 EA 1.94 E+3 Sb - 125 8.68 E42 Te - 125m 2.91 E+1 2.17 E+2 7.87 E+1 6.54 E+1 8.84 E+2 1.40 E42 2.23 E+3 1.84 E+3 Te - 127m 6.69 E+1 5.49 E+2 1.96 E42 4.67 E+3 Te - 129m 1.48 E+2 9.33 E+2 3 48 E+2 3.20 E+2 3.89 E+3 1.09 E+2 6.95 E42 6.81 E+3 Te - 131m 5.72 E+1 1.40 E42 6.88 E+1 1.46 E+2 1.27 E+3 6.25 E+3 Te - 132 1.24 E+2 2.40 E+2 1.32 E42 1.T E+5 5,36 E42 8.24 E+1 I - 131 1.79 E42 2.18 E+2 3.12 E+2 1.91 E+4 2.26 E+2 1.17 E42 I - 133 3.95 E+1 7.46 E+1 1.30 E+2 EA 5.27 E+3 1.75 E+3 2.85 E+2 Cs - 134 1.33 EA 6.84 E+3 1.63 2.83 1.57 E+3 2.16 E+2 3.21 E+2 Cs - 136 2.04 E+3 7.16 E42 E+3 1.20 E4 4.0/ E+3 1.35 E+3 2.32 E42 Cs - 117 7.85 E+3 8.71 E+3 2.0/ 7.00 E-1 1.18 3.39 E+3 In - 140 1.08 E+2 1.65 E+3 8.00 E-1 5.84 EA la - 140 2.10 E-1 1.rA 8.86 E+3 2.f4 E-1 3.43 2.32 1.08 Ce - 141 1.67 EA 4.94 E4 6.00 Ec1 4.47 E-2 2.00 E-1 Ce - 143 6.04 EA Ce - 144 9.59 1.99 E+2 7.47 E+1 4.43 E+1 1.08 E-2 7.13 E42 Np - 89 1.92 E-3 3.53 Fe2 3.47 E-3 I-lO Rev. 6 2-16-82
'd 1.3 Representative sampling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling. The methodology for mixing and sampling is described in S023 III - 5.4.1 Liquid Radwaste Sampling. 4 1 i i 4 i 19 Rev. 4 1-29-82 l
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2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effiuent Monitor Setpoints (3.11.2.1) Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data and revised in accordance with the Unit Technical Specifications. 2.1.1 Plant Stack - 2/3RT - 7808, 2RT-7865-1. 3RT-7865-1 For the purpose of implementation of Specification 3.11.2.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and . meteorological dispersion factor. The concentration at the detector is determined by using: i
' * ~
l (X Q) flo ate) ! where: C = the instantaneous concentration at the detector in pCi/cc F = Filter efficiency l l
= 1 for noble gases
= .995 for particulates
= .944 for iodine 2-l Rev. 6 2-16-82
.P = Line Plate Oute
= 1 for noble gases
= .43 for iodine and particulates for 2/3 RT-7808 HPC = the 10CFR Part 20 concentration for the limiting radionuclide present in sample analysis in p Ci/cc (i.e., smallest HPC) flow rate = the plant vent flow rate in cfm
= 83,000 cfm/ fan (x no. or fans to be run)
(X/Q) = 2.4 E-5 sec/m3 the annual average atmosphere dispersion 2120 = conversion of cfm to m 3f3ec
.45 is an administrative value used to account for potential activity from other gaseous release pathways The alarm setting is determined by using the calibration curve for the applicable Plant Stack Airborne Monitor (Figure 2-1 for 2/3RT-7808, Figure 2-2 for 2RT-7865-1 and Figure 2-3 for 3RT-7865-1). The alarm setpoint is the opm value corresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity for the monitor.
2.1.2 Condenser Evacuation System - 2RT - 7818 or 2RT - 7870-1 For the purpose of implementation of Specification 3.11.2.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and meteorological dispersion factor. 2-2 Rev. 6 < 2-16-82 i
T l l The concentration at the detector is determined by using: l l
* ~
(X/Q) f ow rate) where: C = the instantaneous concentration at the detector in pCi/cc ) M PC = t he 10CFR Part 20 concentration for the limiting radionuclide present in sample analysis in p C1/cc (i .e. , smallest MPC) flow rate a the condenser evacuation system flow rate jn cfm a 1,000 cfm (X/Q) = 2.4 E-5 sec/m3 the annual average atmosphere dispersion 2120 = conversion of cfm to m3/sec
.1 is an 'a'dministrative value used to account for potential activity from other gaseous release pathways.
The alarm setting is determined by using the calibration curve for the corresponding Ccndenser Evacuation System Monitor. The alarm setpoint_is the opm value corresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity _for the monitor. 2-3 gey, a 1-29-82
2.1.3 Containment Purge - 2RT - 7804-1 and 2R7-7807-2 For the purpose of implementation of Specification 3.11.2.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and meteorological dispersion factor. The concentration at the detector is determined by using: C < (.45) (2120) (K/Q)IM[C] f t) (2-3) where: C = the instantaneous concentration at the detector in p Ci/co MPC = the 10CFR Part 20 concentration for the limiting radionuclide present in sample analysis in pCi/cc. . (i.e., smallest MPC) flow rate = the containment purge flow rate in cfm i = 40,000 cfm full purge
= 2,000 cfm mini purge (X/Q) = 2.4 E-5 sec/m3 the annual average atmosphere dispersion 2120 = conversion of cfm to m 3f3 c FE = filter efficiency
=1 for noble gases
= .995 for particulates
= .944 for iodine
~
Rev. 6 2-16-82
P = line plate out
= 1 for noble gases
= .2 for iodine and particulates on 2RT-7804-1
= .22 for iodine and particulates on 2RT-7807-2
.45 is an administrative value used to account for potential activity from other gaseous release pathways.
The alarm setting is determined by using the calibration curve for the Containment Airborne Monitor (Figure 2-6 for 2RT-7804-1 and Figure 2-7 for 2RT-7807-2). The alarm setpoint is the cpm value corresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity for the monitor. 2.1.4 Waste Gas lleader - 2/3 RT-7814, 2/3 RT-7808 For the purpose of Specification 3.11.2.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent l flow rate and meteorological dispersion factor. Since the waste gas neader discharges to the plant vent stack, either 2/3 RT-7814 or 2/3 RT-7808 may be used to monitor waste gas header releases. 2/3 RT-7808 Whea plant vent stack monitor 2/3 RT-7808 is being used to monitor waste gas header releases, the setpoint determined by equation (2-1) will provide automatic termination of release from the waste gas header. 2-5 Rev. 6 2-16-82
Determine the maximum permissible waste gas header effluent flow rate corresponding to the vent stack monitor setpoint in accordance with the following: f< (.9) C F (2-4) k ki Where: f = waste gas header effluent flow rate F = plant vent stack flow rate used in equation (2-1) of the waste gas holdup {Cg = total gamma activity ( p Ci/cc) tank to be released, as determined from the pre-release sample analysis. The .9 is an administrative value to account for the potential activity from other releases in the same release pathway. 2/3 nr-7814 C i C < ( .9) ( 45) (2120) (,jq) (gyow rate) ( ~' ' Where: C = the instantaneous concentration at the detector in pC1/cc 2-6 Rev. 5 2-9-82 e
MPC = the 10CFR20 concentration for the limiting radionuclide present 1 in the sample analysis in pC1/cc (i.e., smallest MPC) j l l flow rate a the waste gas header flow rate in cfm
= 50 cfm (X/Q) 2.4 E-5 sec/m3 , the annual average atmosphere dispersion 2120 = conversion of cfm to m3 f ,,e The .45 is an administrative value to account for potential activity from other release pathways._
The .9 is an administrative value to account for potential activity from other gaseous releases in the same release pathway. The alarm setting is determined by using the calibration curve for the Waste Gas Header Monitor, Figure 2-8. The alarm setpoint is the cpm value corresponding to the concentration, C, which is conservatively assumed to be the isotope of greatest sensitivity for the monitor. NOTE: If C<{Cyg for the waste gas decay tank, then no release is possible. To increase C, decrease the waste gas effuent flow rate in accordance with: (.9) (.45 ( 0) MPC (flow rate) < (2-6) {C g (X/Q) 2-7 g,y, s 2-16-82
Where: flow rate = the maximum permissible waste gas effluent flow rate in cfm
.9, .45, 2120, HPC, X/Q are defined in equation (2-5)
{Cgg s total gamma activity (pCi/cc) of the waste gas holdup tank to be released, as determined from the pre-released sample analysis. Recalculate the monitor setpoint using the new flow rate and equation (2-5). If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms and yet assure an alarm should an inadvertant release occur. 1 2-8 Rev. 5 2-9-82
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