ML12123A729
| ML12123A729 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/30/2012 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-12-085 1/2-ODC-3.01, Rev. 1, RTL# A9.621B | |
| Download: ML12123A729 (12) | |
Text
'Page 1 of 12)RTL#: A9.621B Beaver Valley Power Station Unit 1/2 1/2-ODC-3.01 ODCM: Dispersion Calculation Procedure and Source Term Inputs Document Owner Manager, Nuclear Environmental
& Chemistry Revision Number 1 Level Of Use General Skill Reference Safety Related Procedure Yes Effective Date 12/29/06 Page 2 of 12)Beaver Valley Power Station Procedure NubrODC 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 2 of 12 TABLE OF CONTENTS 1 .0 P U R P O S E ...................................................................................................................................
3 2 .0 S C O P E ...............
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3 3.0 REFEFERENCES AND COMMITMENTS
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3 3 .1 R e fe re n c e s ..........................................................................................................................
3 3 .2 C o m m itm e n ts .....................................................................................................................
4 4.0 RECORDS AND FORM S....................
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4 4 .1 R e c o rd s ..............................................................................................................................
4 4 .2 F o rm s ...............
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4 5.0 PRECAUTIONS AND LIMITATIONS
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4 6.0 ACCEPTANCE CRITERIA ..................................................................................................
4 7.0 P R E R E Q U ISIT E S .........................
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4 8 .0 P R O C E D U R E ....................................................................................................
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5 8.1 Summary of Dispersion and Deposition Methodology
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5 8.2 Summary of Source Term Inputs ...................................................................................
7 8.2.1 Liquid Source Term Inputs .....................
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7 8.2.2 Gaseous Source Term Inputs .........................................................................
7 ATTACHMENT A BV-1 AND 2 RELEASE CONDITIONS
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8 ATTACHMENT B LIQUID SOURCE TERM INPUTS ..............................................................
9 ATTACHMENT C GASEOUS SOURCE TERM INPUTS ............................................................
11 Page 3 of 12)Beaver. Valley Power Station Procedure Number: 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 1 3 of 12 1.0 PURPOSE 1.1 This procedure contains the basic methodology that was used for calculating dispersion (x/Q)and deposition (D/Q).1.1.1 Prior to issuance of this procedure, these items were located in Appendix A of the old ODCM.1.2 This procedure also contains the input parameters to the various computer codes used by the Licensee and its subcontractors for determination of the liquid and gaseous source term mixes.1.2.1 Prior to issuance of this procedure, these items were located in Appendix B of the old ODCM.2.0 SCOPE 2.1 This procedure is applicable to all station personnel (including subcontractors) that are qualified to perform activities as described and referenced in this procedure.
3.0 REFEFERENCES
AND COMMITMENTS
3.1 References
3.1.1 NUS-2173,Development Of Terrain Adjustment Factors For Use At the Beaver Valley Power Station, For the Straight-Line Atmospheric Dispersion Model, NUS Corporation, June 1978 3.1.2 NUREG/CR-2919, XOQDOQ: Computer Program For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear Power Stations, September, 1982 3.1.3 Regulatory Guide 1.23, Meteorological Measurement Program for Nuclear Power Plants 3.1.4 Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents In Routine Releases From Light-Water-Coded Reactors, Revision 1, July 1977 3.1.5 NRC Gale Code, 3.1.6 SWEC LIQIBB Code, 3.1.7 SWEC GAS1BB Code, 3.1.8 NUREG-1301, Offsite Dose Calculation Manual Guidance, Standard Radiological Effluent Controls for Pressurized Water Reactors (Generic Letter 89-01, Supplement No. 1)3.1.9 1/2-ADM-1640, Control of the Offsite Dose Calculation Manual Page 4 of 12)Beaver Valley Power Station Procedure Number: 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 1 4 of 12 3.1.10 1/2-ADM-0100, Procedure Writer's Guide 3.1.11 1/2-ADM-0101, Review and Approval of Documents 3.1.12 CR 05-01169, Chemistry Action Plan for Transition of RETS, REMP and ODCM.CA-19, Revise procedure 1/2-ODC-3.01 to change document owner from Manager, Radiation Protection to Manager, Nuclear Environmental
& Chemistry.
3.2 Commitments
3.2.1 None 4.0 RECORDS AND FORMS 4.1 Records 4.1.1 Any calculation supporting generation of dispersion, deposition, or. source term mixes shall be documented, as appropriate, by a retrievable document (e.g.; letter or calculation package) with an appropriate RTL number.4.2 Forms 4.2.1 None 5.0 PRECAUTIONS AND LIMITATIONS 5.1 This procedure contains the information that was previously contained in Appendix A and Appendix B of the previous BV-I and 2 Offsite Dose Calculation Manual.5.1.1 In regards to this, the Tables that were transferred from Appendix A and Appendix B to the appropriate ATTACHMENTS of this procedure will still contain a prefix denoting an "A" or "B".6.0 ACCEPTANCE CRITERIA 6.1 Any change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50, and not adversely impact the accuracy or reliability of effluent dose or setpoint calculation.
6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100(3 1'0)and 1/2-ADM-1640.<
3'9)6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2 ADM-0101 3'-1) and 1/2-ADM-1640.
3 1 97.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.
Page 5 of 12)Beaver Valley Power Station ProcedureNumber:
~1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 1 5 of 12 8.0 PROCEDURE 8.1 Summary of Dispersion and Deposition Methodology
8.1.1 Annual
average and grazing season average values of relative concentration (x/Q) and deposition (D/Q) were calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-line airflow (Gaussian) model described in RG-1.1 11(14)8.1.1.1 Undecayed and undepleted sector average x/Q and D/Q values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors.
8.1.1.2 For an elevated release, (i.e.; occurring at a height that is twice the height or more of a nearby structure) credit was taken for the effective release height which is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor.8.1.1.3 A building wake correction factor was used to adjust calculations for ground-level releases.8.1.1.4 Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site.(3 1 1 8.1.1.5 The methodology employed in the calculation of intermittent release X/Q and D/Q values is that described in NUREG/CR-2919.(3."2) 8.1.2 The site continuous gaseous release points that have been evaluated include the following:
8.1.2.1 PV-1/2: The Unit 1/2 Gaseous Waste/Process Vent attached to the Unit 1 natural draft cooling tower 8.1.2.2 CV-1 and CV-2: The Unit 1 Rx Containment/SLCRS Vented the Unit 2 SLCRS Filtered Pathway 8.1.2.3 JVW-1 and VV-2: The Unit 1 Ventilation Vent and the Unit 2 SLCRS Unfiltered Pathway 8.1.2.4 TV-2: The Unit 2 Turbine Building Vent 8.1.2.5 CB-2: The Unit 2 Condensate Polishing Building Vent 8.1.2.6 DV-2: The Unit 2 Decontamination Building Vent 8.1.2.7 WV-2: The Unit 2 Gaseous Waste Storage Tank Vault Vent 8.1.3 The intermittent releases are from PV-1/2, VV-1, VV-2, CV-1 and CV-2.
Page 6 of 12)Beaver Valley Power Station Procedure Number: 1/2-ODC-3
.01 Title: Unt: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 6 of 12 8.1.4 Only PV-1/2 was considered to be an elevated release with all other release points being treated as ground level releases.
A summary of the release characteristics and their locations is given in ATTACHMENT A.8.1.5 Onsite meteorological data for the period January 1, 1976 through December 31, 1980 were used as input for the annual-average calculations.
8.1.5.1 The grazing season was represented by a six-month period from May 1 through October 31 for each year of the 5-year meteorological data base. This grazing season corresponds reasonably well with the growing season.8.1.5.2 The data were collected according to guidance in NRC RG-1.233'1 3) as described in Section 2.3 of the BVPS-2 FSAR.8.1.5.3 The parameters used in the xJQ and D/Q calculations consist of wind speed, wind direction, and AT as an indicator of atmospheric stability.
The lower level winds (35 ft) and AT (150-35 ft) were used for all release points except the Process Vent which required the use of 500 ft winds and AT (500-35 ft) which are representative of the release height (510 ft).8.1.6 The annual average and grazing season x/Q and D/Q values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and nearest meat animal.8.1.6.1 In the case of the Process Vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum X/Q and D/Q values.8.1.6.2 The distances of the limiting maximum individual receptors from the radioactive release points are given in ATTACHMENT E (Table 2.2-3) of 1/2-ODC-2.02.
8.1.6.3 The continuous release annual average X/Q values at the special locations for the Containment Vents, Ventilation Vents, Process Vent, Turbine Building Vents, Decontamination Building Vent, Waste Gas Storage Vault Vent, and Condensate Polishing Building Vent are given in ATTACHMENT F (Tables 2.2-4 through 2.2-10) of 1/2-ODC-2.02.
Continuous release annual average X/Q's for these same release points are also given at ten incremental downwind distances of 0-5 miles.8.1.6.4 Continuous release D/Q values for these same release points are given in ATTACHMENT K (Tables 2.3-21 through 2.3-27) of 1/2-ODC-2.02 for the same 0-5 mile incremental distances, and in ATTACHMENT L (Tables 2.3-28 through 2.3-34) of 1/2-ODC-2.02 for the special locations.
8.1.6.5 Due to their location adjacent to the Containment Building, the Decontamination Building and Gaseous Waste Storage Tank Vault X/Q's and D/Q's are the same as the Containment Vent x/Q's and D/Q's.
Page 7 of 12)Beaver Valley Power Station roceure N :ODC 3 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 7 of 12 8.1.6.6 Likewise, the Turbine Building Vent X/Q's and D/Q's apply to the Condensate Polishing Building as well due to its location adjacent to the Turbine Building.8.1.7 ATTACHMENT M (Tables 2.3-35 through 2.3-38) of 1/2-ODC-2.02 contain short term yJQ values for batch releases originating from the Containment Vent, Ventilation Vent, and Process Vent releases respectively.
8.1.7.1 The values in these tables are based on 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> per year of Containment and Ventilation Vent purges and 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> per year of Process Vent purges.8.2 Summary of Source Term Inputs 8.2.1 Liquid Source Term Inputs 8.2.1.1 Inputs to the NRC Gale Code used for generation of BV-1 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B: la).8.2.1.2 Inputs to the SWEC LIQ1BB Code used for generation of BV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B: Ib)8.2.2 Gaseous Source Term Inputs 8.2.2.1 Inputs to the SWEC GAS 1BB Code for generation of BV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a)8.2.2.2 Inputs to the SWEC GAS 1BB Code for generation of BV-2 Gaseous Source Term Mixes are shown in ATTACHIENT C (Table B:2b)
- Page 8 of 12)Beaver Valley Power Station Procedure Number: 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM. Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number:_1 8 of 12 ATTACHMENT A Page 1 of 1 BV-I AND 2 RELEASE CONDITIONS TABLEA.I VV-1 CV-1 RX PV-1/2 GASEOUS TV-2 TURBINE VENTILATION CONTAINMENT/
WASTE/PROCESS BUILDING VENT VENT (PAB SLCRS VENT VENT EXHAUST)VV-2 SLCRS CV-2 RX UNFILTERED CONTAINMENT/
PATHWAY SLCRS FILTERED PATHWAY TYPE OF RELEASE GROUND LEVEL GROUND LEVEL ELEVATED GROUND LEVEL Long TermAnd Long Thm And Long Term And Long Term And Short Term ShortTerm Short Term ShortTerm ReleasePointHeight 26 47 155 33 (in)Adjacent Building 19 44 155 33 Height (m)Relative Loca tion To E. Side OfPimary Top Center Of Atop Cooling Tower Turbine Building Adjacent Structures Auxliary Bldg Containment Dome Exit Velocity(n/sec)
NA NA 9.4 NA Internal Stack NA NA 0.25 NA Diameter(m)
Building Cross- 1600 1600 NA NA Sectional Area (rn 2)Purge Frequency*
32 32 74 NA (houls/year)
PurgeDurafion 8 8 NA NA*Applied to Short Term calcaations only Page 9 of 12)Procedure Number: yPower Station 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number:_ 1 9 of 12 ATTACHMENT B Page 1 of 2 LIQUID SOURCE TERM INPUTS TABLE B: 1 a INPUTS TO GALE CODE FOR GENERATION OF BV-I LIQUID BV-1 PWR INPUTS SOURCE TERM MIXES VALUE Thermal Power Level (megawatts)
Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpln)Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million Ibs/hr)Mass Of Steam In Each Steam Generator (thousand lbs)Mass Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand lbs)Mass Of Water In Steam Generator (thousand lbs)Blowdown Rate (thousand lbs/hr)Primary To Secondary Leak Rate (lbs/day)Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)2766.000.800 345.000.120 60.000 6.000 3.000 11.620 6.772 97.000 1296.000 291.000 33.900 100.000.001.010 0.000 22.500 BV-1 LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOW RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day)
OF PCA DISCHARGE (days) (days) I Cs OTHERS Shim Bleed 1.32E4 Rate Equipment Drains 6.00E2 1.000 1.000 1.000 0.035 Clean Waste 7.50E1 Input Dirty Waste 1.35E3 Input Blowdown 9.75E4 0.000 0.000 1.000 1.000 1.000 11.260 7.220 1E7 1E7 1E7 11.260 7.220 1E7 iE7 1E7 0.071 0:648 IE5 2E4 IE5 0.071 0.648 1E5 2E4 1E5 0.071 0.648 lE5 2E4 1E5 Untreated Blowdown 0.0 Page 10 of 12)Beaver Valley Power Station ProcCdure Number: 1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 1 10 of 12 ATTACHMENT B Page 2 of 2 LIQUID SOURCE TERM INPUTS TABLE B: lb INPUTS TO SWEC LIQ1BB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWR INPUTS VALUE Thermal Power Level (megawatts)
Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpm)Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/br)Mass Of Steam In Each Steam Generator (thousand lbs)Mass Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand lbs)Mass Of Water In Steam Generator (thousand lbs)Blowdown Rate (thousand lbs/hr)Primary To Secondary Leak Rate (lbs/day)Fission Product Carry-Over Fraction Halogen' Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)2766.000.800 385.000.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000.001.010.700 7.800 BV-2 LIQUID WASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOW RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day)
OF PCA DISCHARGE (Irs) (hrs) I CsRb OTHERS Contaimnent Sump Auxiliary Building Sump Miscellaneous Sources Rx Plant Samples Lab Drains Cond. Demin.Rinse Water CVCS Turbine Bldg.Drains 40 1.000 200 700 0.100 0.010 35 1.000 400 0.002 2685 1.1E-4 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0 35.5 35.5 35.5 35.5 35.5 35.5 1300 6.2 1E3 1E4 1E4 6.2 1E3 IE4 1E4 6.2 1E3 1E4 1E4 6.2 1E3 IE4 1E4 6.2 1E3 1E4 1E4 6.2 IE3 1E4 1E4 173 IE4 4E3 1E5 60 7200
- Page 11 of 12)Beaver Valley Power Station ProcedurCoNumber:
.1/2-ODC-3.01 Title: Unit: Level Of Use: 1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: I 1 11 of 12 ATTACHMENT C Page 1 of 2 GASEOUS SOURCE TERM INPUTS TABLE B:2a INPUTS TO SWEC GAS 1BB CODE FOR GENERATION OF BV-I GASEOUS SOURCE TERM MIXES BV-1 PWR INPUTS Thermal Power Level (megawatts)
Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpin)Letdown Cation Dernineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/hr)Mass Of Steam In Each Steam Generator (thousandlbs)
Mass Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand lbs)Mass Of Water In Steam Generator (thousand lbs)Blowdown Rate (thousand lbs/hr)Primary To Secondary Leak Rate (bs/day)Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Dernineralizer Flow Fraction Radwaste Dilution Flow (thousand gpln)VALUE 2766.000.800 385.000.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 52.000 100.000.001.010 0.000 15.000 VALUE By-i GASEOUS WASTE INPUTS There Is Not Continuous StrippDing Of Full Letdown Flow Hold Up Time For Xenon (days)Hold Up Time For Krypton (days)Primary Coolant Leak To Auxiliary Building (lb/day)Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volmne (million cu-ft)Frequency Of Primary Coolant Degassing (times/yr)
Primary To Secondary Leak Rate (lb/day)There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfrn)Purge Time Of Containment (hours)There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq)
In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*
Contaimnent Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbs/hr)Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Cryogenic Off Gas System 39.000 2.000 160.000 7.5E-3 0.000 1.000 1.000 1.800 2.000 100.000 2.000 8.000 0.010 4.000 1.000 1.000 1700.000 0.000 0.440*2 cold and 2 hot purges (Page 12 of 12)Beaver Valley Power Station 1/2-ODC-3.d1 Title: Unit: Level Of se: 1/2 General Skill Reference-ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision:
Page Number: 1 1 12 of 12 ATTACHMENT C Page 2 of 2 GASEOUS SOURCE TERM INPUTS TABLE B:2b INPUTS TO SWEC GAS 1BB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS Tliennal Power Level (megawatts)
Plant Capacity Factor Mass Of Primary Coolant (thousand lbs)Percent Fuel With Cladding Defects Primary System Letdown Rate (gpmn)Letdown Cation Demineralizer Flow Number Of Steam Generators Total Steam Flow (million lbs/br)Mass Of Steam In Each Steam Generator (thousand Ibs)Mass Of Liquid In Each Steam Generator (thousand lbs)Total Mass Of Secondary Coolant (thousand lbs)Mass Of Water In Steam Generator (thousand lbs)Blowdown Rate (thousand lbs/br)Primary To Secondary Leak Rate (lbs/day)Fission Product Carry-Over Fraction Halogen Carry-Over Fraction Condensate Demineralizer Flow Fraction Radwaste Dilution Flow (thousand gpm)VALUE 2766.000.800 385.000.120 57.000 5.700 3.000 11.600 8.700 100.000 2000.000 298.000 22.300 100.000.001.010.700 7.800 VALUE BV-2 GASEOUS WASTE INPUTS There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days)Hold Up Tine For Krypton (days)Primary Coolant Leak To Auxiliary Building (lb/day)Auxiliary Building Leak Iodine Partition Factor Gas Waste System Particulate Release Fraction Auxiliary Building Charcoiodine Release Fraction Auxiliary Building Particulate Release Fraction Containment Volume (nillion cu-fl)Frequency Of Primary Coolant Degassing (times/yr)
Primary To Secondary Leak Rate (lb/day)There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm)Purge Time Of Containment (hours)There Is Not A Condensate Demineralizer Iodine Partition Factor (gas/liq)
In Steam Generator Frequency Of Containment Building High Vol Purge (times/yr)*
Containment Volume Purge Iodine Release Fraction Containment Volume Purge Particulate Release Fraction Steam Leak To Turbine Building (lbs/br)Fraction Iodine Released From Blowdown Tank Vent Fraction Iodine Released From Main Condensate Air Ejector There Is Not A Cryogenic Off Gas System 45.800 2.570 160.000 7.5E-3 0.000 0.100 0.010 1.800 2.000 100.000 20.000 8.000 0.010 4.000 1.000 1.000 1700.000 0.000 0.270*2 cold and 2 hot purges