ML21127A149

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ODCM: Dispersion Calculation Procedure and Source Term Inputs
ML21127A149
Person / Time
Site: Beaver Valley
Issue date: 12/29/2006
From:
Energy Harbor Nuclear Corp
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21127A168 List:
References
L-21-135
Download: ML21127A149 (12)
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Text

RTL#: A9.621B Beaver Valley Pow er Station Unit 1/2 1/2-0DC-3.0l 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

Prooedure Number.

Beaver Valley Power Station l/2-0DC-3.01

Title:

Unit: Levd Of Uae:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Numb<<:

1 2 nf 1?

TABLE OF CONTENTS 1.0 PURPOSE .................................................................................................................................... 3 2.0 SCOPE ......................................................................................................................................... 3 3.0 REFEFEREN"CES AND COMWTMEN"TS ................................................................................. 3 3.1 References .......................................................................................................................... 3 3.2 Commitments ..................................................................................................................... 4 4.0 RECORDS AND FORMS ............................................................................................................ 4 4.1 Records .............................................................................................................................. 4 4.2 Forms ................................................................................................................................. 4

- 5.0 PRECAUTIONS AND ~ATIONS ....................................................................................... 4 6.0 ACCEPTmCE CRITERIA ......................................................................................................... 4 7.0 PREREQUISITES ........................................................................................................................ 4 8.0 PROCEDURE .............................................................................................................................. 5 8.1 Summary of Dispersion and Deposition Methodology ........................................................ 5 8.2 Summary of Source Term Inputs ........................................................................................ 7 8.2.1 Liquid Source Term Inputs ................................................................................. 7 8.2.2 Gaseous Somce Term Inputs .............................................................................. 7 ATTACHMENT A BV-1 AND 2 RELEASE CONDffiONS ............................................................ 8 ATTACHMENT B LIQUID SOURCE TERM INPUTS ................................................................... 9 ATTACHMENT C GASEOUS SOURCE TERM INPUTS ............................................................. 11

Beaver Valley Power Station Procedure Nomber:

1/2-0DC-3.01

Title:

Unit: LevelOfUac:

1/2 General Skill Reference OOCM: Dispersion Calculation Procedure and Source Term Inputs R.evilioo: Page Numb<<:

1 3 nfl2 1.0 PURPOSE 1.1 This procedure contains the basic methodology that was used for calculating dispersion (:;JQ) 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 subcontractor s for determination of the liquid and gaseous source term nuxes.

1.2.1 Prior to issuance of this procedure, these items were located in Appendix B of the old OOCM.

2.0 SCOPE 2.1 This procedure is applicable to all station personnel (including subcontractor s) that are qualified to perform activities as descnbed and referenced in this procedure.

3.0 REFEFERENCES AND COMMITMENTS

3. I 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 Meteorologic al 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-C oded Reactors, Revision 1, July 1977 3 .1. 5 NRC Gale Code, 3.1.6 SWEC LIQIBB Code, 3.1.7 SWEC GASlBB 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. I) 3.1.9 l/2-ADM-164 0, Control of the Offsite Dose Calculation Manual

Prooedure Number.

Beaver Valley Power Station l/2-0DC-3.01 TIiie: Unit: Level OfUae:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revisioo: Page Number.

1 4 nf 1?.

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 ofRETS, REMP and ODCM CA-19, Revise procedure l/2-0DC-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-1 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 A1ly change to this procedure shall contain sufficient justification that the change will maintain the level of radioactive efiluent 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 efiluent dose or setpoint calculation.

6.1.1 All changes to this procedure shall be prepared in accordance with 1/2-ADM-0100<3,1.1o) and 1/2-ADM-1640.(3.t.9) 6.1.2 All changes to this procedure shall be reviewed and approved in accordance with 1/2 ADM-0101(3.1.11) and 1/2-ADM-1640.<3* 1.9) 1.0 PREREQUISITES 7.1 The user of this procedure shall be familiar with ODCM structure and content.

Beaver Valley Power Station Prooedore Number:

l/2-ODC-3.01 Ti&: Unit: Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Number:

1 5 nf12 8.0 PROCEDURE 8.1 Summary of DiS]ersion and Qewsition Methodology 8.1.1 Annual average and grazing season average values of relative concentration (XIQ) 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-1.111.(3.1.4) 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*1.2>

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 VV-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 fromPV-1/2, VV-1, VV-2, CV-1 and CV-2.

Procedure Numb<<:

Beaver Valley Power Station l/2-ODC-3.01

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Unit: Level OfUae:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Tenn Inputs Revision: Page Number:

1 6 of12 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-1.23<3-I 3 ) as described in Section 2.3 of the BVPS-2 FSAR 8.1.5.3 The parameters used in the XIQ 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 XIQ 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 XIQ 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 l/2-0DC-2.02.

8.1.6.3 The continuous release annual average XIQ 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 l/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 l/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 l/2-0DC-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 Vauh XIQ's and D/Q's are the same as the Containment Vent XIQ's and D/Q's.

Beaver Valley Power Station Prooedure Number:

l/2-ODC-3.01

Title:

Unit: LevaOfUse:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: Page Nwnba-:

1 7 nf12 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 ATTACHM ENT M (Tables 2.3-35 through 2.3-38) of l/2-ODC-2 .02 contain short term x/Q 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 Containme nt 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 Sumnuuy of Source Term Inputs 8.2.1 Liqyid Sow:ce Term Inputs 8.2.1.1 Inputs to the NRC Gale Code used for generation ofBV-1 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:la).

8.2.1.2 Inputs to the SWEC LIQlBB Code used for generation ofBV-2 Liquid Source Term Mixes are shown in ATTACHMENT B (Table B:lb) 8.2.2 Gaseous Source Tenn uwuts 8.2.2.1 Inputs to the SWEC GASlBB Code for generation ofBV-1 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B:2a) 8.2.2.2 Inputs to the SWEC GASlBB Code for generation ofBV-2 Gaseous Source Term Mixes are shown in ATTACHMENT C (Table B :2b)

Procedure Number:

Beaver Valley Power Station 1/2-ODC-3.0l

Title:

Unit: LevelOfUse:

1n. General Skill Reference OOCM: Dispersion Calculation Procedure and Source Term Inputs R.evili.on: Page Number.

I 8 nfl2 ATTACHMENT A Page I of I BV-1 AND 2 RELEASE CONDmONS TABIEA:1 W-1 CV-lRX PV-1/2 GASEOUS TV-2 TURBINE VENTILATION CONTAINMENf/ WASIB/PROCESS BUILDING VENT VENT(PAB SLCRSVENT VENT EXHAUS1)

W-2 SLCRS CV-2RX UNFILTERED CONTAINMENI'/

PATHWAY SLCRS FILTERED PATHWAY TYPE OF RELEASE GROUND LEVEL GROUND LEVEL FLEVA1ED GROUND LEVEL LoogTennAm LoogTenn.Am LoogTenn.Am ~TennAm SlutTenn Slut:Tenn SlutTenn ShnTenn R.eleaePootff3glt 26 47 155 33 (m)

~Buldiog 19 44 155 33 He;glt(m)

Relativel..oca tm To E Side OfPrimary Tq,Cam-Of Aiq)~T<Mtr ~ B i nlctir-g

~Strucnre; Auxilimy Bklg Ccnainumlbre

&it Vooat)(m'sec) NA NA 9.4 NA Irtaml.Snd NA NA 0.25 NA Dianrter(m)

BuiktingG\Er }(JOO 1(00 NA NA Sectinll Area(nf)

Purge~ 32 32 74 NA (b::uwyear)

I\JgeUmim 8 8 NA NA (m'release)

  • Awfied 1o Sh:11:Tmn ca1a daricm crly

Beaver Valley Power Station Prooedmc Number.

1/2-ODC-3.01

Title:

Unit: Level Of Use:

1/2 General Skill RefereDce ODCM: Dispersion Calculation Procedure and Source Term Inputs R.ovilioo: Page Number.

1 9 of 12 ATTACHMENT B Page 1 of2 LIQUID SOURCE TERM INPUTS TABLEB: la INPUTS TO GALE CODE FOR GENERAT ION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PWRINPU fS VALUE Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor '

.800 Mass Of Primary Coolant (thousand lbs) 345.000 Percent Fuel With Cladding Defects .120 Primary System Letdown Rate {gpm) 60.000 Letdown Cation Demineralizer Flow 6.000 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.620 '

Mass Of Steam In &ch Steam Generator (thousand lbs) 6.772 Mass Of Liquid In &ch Steam Generator (thousand lbs) 97.000 Total Mass Of Secondary Coolant (thousand lbs) 1296.000 Mass Of Water In Steam Generator (thousand lbs) 291.000 Blowdown Rate (thousand lbs/hr) 33.900 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction 0.000 Radwaste Dilution Flow (thousand gpm) 22.500 BV-1 LIQUID WASIB INPUTS COLLECTION DELAY DECONTAMINATION FLOWRAIB FRACTION FRACTION TIME TIME FACTORS S1REAM (ga]/day) OFPCA DISCHARGE (days) (days) I Cs OTHERS Shim Bleed 1.32E4 1.000 0.000 11.260 7.220 1E7 1E7 1E7 Rate Equipment 6.00E2 1.000 0.000 11.260 7.220 1E7 1E7 1E7 Drains Clean Waste 7.50El 1.000 1.000 0.071 0.648 1E5 2E4 1E5 Input Dirty Waste 1.35E3 0.035 1.000 0.071 0.648 1E5 2E4 1E5 Input Blowdown 9.75E4 - 1.000 0.071 0.648 1E5 2E4 1E5 Untreated Blowdown 0.0 - - - - - - -

Procedure Number.

Beaver Valley Power Station 1/2-0DC-3.0l

Title:

Unit: Level Of Use:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Revision: PageNumb<<:

I IO nf12 ATTACHMENTB Page2 of2 LIQUID SOURCE TERM INPUTS TABLEB:lb INPUTS TO SWEC LIQ lBB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PWR INPUTS VAWE Thermal Power Level (megawat1s) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel With Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flow (million Ibs/1rr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand lbs) 2000.000 Mass Of Water In Steam Generator (thousand lbs) 298.000 Blowdown Rate (thousand lbs/hr) 22.300 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizcr Flow Fraction .700 Radwaste Dilution Flow (thou.sand gpm) 7.800 BV-2 LIQUID WASIB INPUTS COLLECTION DELAY DECONTAMINATION FWWRATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal/day) OFPCA DISCHARGE (hrs) (hrs) I CsRb OTHERS Cn:ntaimnent 40 1.000 1.0 35.5 6.2 1E3 lE4 lE4 Sump Auxiliary 200 0.100 1.0 35.5 6.2 IE3 1E4 1E4 Building Sump Miscellaneous 700 0.010 1.0 35.5 6.2 lE3 lE4 lE4 Somces Rx Plant 35 1.000 1.0 35.5 6.2 1E3 1E4 1E4 Samples LabDrains 400 0.002 1.0 35.5 6.2 1E3 1E4 1E4 Cond. Demin. 2685 1.IB-4 1.0 35.5 6.2 1E3 lE4 lE4 Rinse Water eves 60 - 1.0 1300 173 1E4 4E3 1E5 -

Turbine 7200 - 1.0 - - - - -

Bldg.Drains

Beaver Valley Power Station ProoedureNu mb<<:

l/2-0DC-3.01

Title:

Unit: Level OfUae:

1/2 General Skill Reference ODCM: Dispersion Calculati on Procedure and Source Term Inputs Revision: Page Numb<<:

1 11 nf 12 ATTACHMENT C

)

Page 1 of2 GASEOUS SOURCE TERM INPUTS TAB1EB: 2a INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-1 GASEOUS SOURCE TERM MIXES BV-1 PWRINPUTS VALUE Thenna1 Power Level (megawatts ) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel With Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demincra1izer F1ow 5.700 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.600 Mass Of Steam In F.ach Steam Generator (thousand lbs) 8.700 Mass Of Liquid In F.ach Steam Gcnerntor (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand lbs) 2000.000 Mass OfWate:r In Steam Generator (thousand lbs) 298.000 Blowdown Rate (thousand lbs/hr) 52.000 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Cany-Over Fraction .010 Condensate Deminerali7.er Flow Fraction 0.000 Radwaste Dilution Flow (thousand gpm) 15.000 BV-1 GASEOUS WASIBIN PUTS VALUE There Is Not Qwtjnrnms St;riwing OfFull Letdown Flow Hold Up Time For Xenon (days) 39.000 Hold Up Time For Krypton (days) 2.000 Primmy Coolant Leak To Auxiliary Building (lb/day) 160.000 Anxiliary Building Leak Iodine Partition Factor 7.5E-3 Gas Waste System Particulate Release Fraction 0.000 Auxiliary Building Charcoiodine Rele.ase Fraction 1.000 Auxiliary Building Particu1ate Release Fraction 1.000 Containment Volume (million cu-ft) 1.800 Frequency Of Primary Coolant Degassing (times/yr) 2.000 Primary To Secondary Leak Rate (lb/day) 100.000 There Is A Kidney Filter Containment Atmospher e Oeannp Rate (thousand cfm) 2.000 Purge Time Of Containme nt (homs) 8.000 There 1s Not AComJenwe Deminemlizef Iodine Partition Factor (gas/liq) In Steam Generator 0.010 Frequency Of Omtaimne nt Building High Vol Purge (times/yr)* 4.000 C<mtainment Volume Purge Iodine Release Fraction 1.000 Ccmtain:ment Volume Purge Particulate Release Fraction 1.000 Steam Leak To Turbine Building (lbslhr) 1700.000 Fraction Iodine Released From Blowdown Tank Vent 0.000 Fraction Iodine Released From Main Condensate Air Eje.ctor 0.440 There Is Not AC.CVogenic Off Gas System

  • 2 cold and 2 hot ,purges

Beaver Valley Power Station Prooedore Numb<<:

l/2-ODC-3 .01 Thie: Unit Level OfU1e:

1/2 General Skill Reference ODCM: Dispersion Calculation Procedure and Source Term Inputs Reviaioo: Page Number.

1 12 nf 12 ATTACHM ENT C Page 2 of2 GASEOUS SOURCE TERM INPUTS TABLEB:2b INPUTS TO SWEC GASIBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PWR INPUTS VALUE Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel With Cladding Defects .120 Primaiy System Letdown Rate (gpm) 57.000 Letdown Cation Deminera1iz.er Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.600 Mass Of Steam In F.ach Steam Generator (thousand lbs) 8.700 Mass Of Llquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondmy Coolant (thousand lbs) 2000.000 Mass Of Water In Steam Generator (thousand lbs) 298.000 Blowdown Rate (thousand lbs/hr) 22.300 Primary To Secondary Leak Rate (lbs/day) 100.000 Fission Product Cany-Over Fraction .001 Halogen Cany;C)ver Fraction .010 Condensate Deminera1iz.er Flow Fraction .700 Radwaste Dilution Flow (thousand gpm) 7.800 BV-2 GASEOUS WASIBINP UTS VALUE There Is Not ()mtjnuoos Stripping Of Full Letdown Flow Hold Up Time For Xenon (days) 45.800 Hold Up Time For KryptOn (days) 2.570 Primary Coolant Leak To Auxiliary Building (lb/day) 160.000 Auxiliary Building Leak Iodine Partition Factor

  • 7.5E-3 Gas Waste System Particulate Release Fraction 0.000 Auxilimy Building Owcoiocline Release Fraction 0.100 Auxiliary Building Particulate Release Fraction 0.010 Containment Volume (million cu-ft) 1.800 Frequency Of Primary Coolant Degassing (times/yr) 2.000 Primary To Secondary Leak Rate (lb/day) 100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm) 20.000 Purge Time Of Containment (hours) 8.000 There ls Not A Condensate pernjoe.ralirer Iodine Partition Factor (gas/liq) In Steam Generator 0.010 Frequency Of Containment Building High Vol Purge (times/yr)* 4.000 Containment Volume Purge Iodine Release Fraction 1.000 Contaimnent Volume Purge Particulate Release Fraction 1.000 Steam Leak To Turbine Building (lbs/hr) 1700.000 Fraction Iodine Released From Blowdown Tank Vent 0.000 Fraction Iodine Released From Main C'.ondensate Air Ejector 0.270 There Is Not A Cryogenic Off Gas System
  • 2 cold and 2 hot purges
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