ML20215E088

Offsite Dose Calculation Manual

ML20215E088
Person / Time
Site:	Beaver Valley
Issue date:	06/09/1987
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20215E066	List: ML20215E062 ML20215E088
References
PROC-870609-01, NUDOCS 8706190251
Download: ML20215E088 (152)

Text

{{#Wiki_filter:_ () ) J BEAVER VALLEY POWER STAT;lQyj UNIT.NO. 2 i i i r> OFF-SITE DOSE l . CALCULATION MANUAL r I / D D 50 12 ~[ s'z ' P PDR i e

I DU1UESNE LIGHT COMPANY Beaver Valley Power Station Unit No. 2 { ' Socket No. 50-412 t E a q. 0FF-SITE DOSE CALCULATION MANUAL I' (ODCM) / 4 e r l l l s s s 5, /

/- BEAVER VALLEY UNIT NO, 2 0FFSITE DOSE CALCULATION MANUAL (ODCM) e DOCKET NO. 50-412 f J. DUQUESNE LICHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY 1

I TABLE OF CONTENTS Section Title Page I Table of Contents ii List of Tables vi List of Figures viii Preface ~ 1-1 1.0 LIQUID EFFLUENTS 1-1 1.1 Monitor Alarm Setpoint Determination 1-8 z; 1.2 Compliance with BVTS 3.11.1.1 1-12 ,l 1.3 Compliance with 10 CFR 50 (Liquids) i 2-1 2.0 GASEOUS EFFLUENTS 2-1 2.1 Monitor Alarm Setpoint Determination 2-14 2.2 Compliance with 10 CFR 20 (Gaseous) 2-45 ) 2.3 Compliance with 10 CFR 50 (Gaseous > ( i 1 3-1 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PA0G, RAM 4-1. 4.0 INFORMATION RELATED TO 40 CFR 190 A-1 Appendix A Summary of Dispersion Calculation Procedures B-1 Appendix B Inputs to GALE Code

l / List of Tables ~ Table Title-Page 11-5' 1.1-1 . Liquid Source Terms

1. 2-l '

Recirculation Times Required' before Sampling of Liquid' l-11 Discharge Tanks Values K for an' Adult for the Beaver Valley. Unit 2 1-15 1.3-1 Air 2-13 .2.1-1 Monitor Detector' Efficiencies 2.2-1 Modes of' ~ Gaseous Release. from Beaver Valley Power Station '2-25 Unit' 2 Vents for Implementation of 10. CFR 20 .2.2-2 ' Radionuclide Mix for Gaseous.Ef fluents from the Beaver Valley '2-26 Power Station Unit 2 (Ci/Yr) 2.2-3 Distances of Limiting Maximum Individual Receptors to Release 2-27 Points ' for Annual X/Q Values i ~' .( 2.2-4 BVPS-2 Elevated Release Vent Annual Average, Ground. Level, '2-28. ) X/Q Values.: For continuous Ground. Level Releasee,- For Special Distances (Identified 'inL rable' 2.2-3) and. Selected Control Locations. i 2.2-5 BVPS-2 Ventilation Vent Annual Average, Ground Level, X/Q 2-29 .V alues. For continuous. Ground Level Releases, For 'Special Distances - (Identified in Table 2.2-3) and Selected Control Locations. 2.2-6 BVPS-2 Process Vent Annual Average, Ground Level, X/Q Values. 2-30 For continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Contro1' Locations. -l 2.2-7 BVPS-2 Turbine Building Vent Annual Average, Ground Level, 2-31 X/Q Values. For continuous Ground Level Releases, For Special Distances -(Identified in Table 2.2-3) and Selected .I Control Locations. 1 2.2-8 BVPS-2 Decontamination Building Annual Average, Ground Level 2-32 X/Q Values. For continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control' Locations. 2.2-9 BVPS-2 Waste Gas Storage Vault Vent Annual Average, Ground 2-33 Level X/Q Values. For continuous Ground Level Releases, For I Special Dintances (Identified in Table 2.2-3) and Selected 3 Control Locations, ii l j ii

~ c l 1 I List of Tables'(continued) i lable Title Page 2,2-10 BVPS-2 Condensate Polishing Building Annual Average,' Ground 2-34 Level X/Q Values. For continuous. Ground Level Releases. For Special Distances (Identified in. Table 2.2-3) and Selected ? Control ' Locations.' s2.2-11 ' Dose Factors for Noble Gases and Daughters 2-35. ,l ~2.2-12 Dose Parameters ' for Finite Elevated Plumes, Beaver Valley 2. ' Power Station Unit 2 P t Values for an Inf ant for the Beaver Valley Power 2-37 2.2-13 i ' Station Unit 2 i 2.2-14 Beaver Valley Unit 2 Process Vent Dispersion Parameters 2-38 -l (D/Q),' mF, for Continuou.1. Elevated Releases > 500 Hrs /Yr 2 or > 150. Hrs /Qtr for Special Distances (Identified in Table '2.2-3)' LBeaver Valley Unit 2 Eletated Release Vent Dispersion' 2-39 1 ~ ' 2. 2-15 [. Parameter-(D/Q), m-2, for Continuous Mixed Mode Releases 0 > 500 Hrs /Yr'or > 150 HrseQtr for Special Distances (Identified. in Table 2.2-?) ^ .2;2-16 Beaver Valley Unit 2 Ventilation Vent - Dispersion Parameters 2.. (D/Q), nF. for Continuous Ground Level Releases > 500 Krs/Yr 2 or > 150 Hrs /Qtr for Special Distances (Identified in Table 2 '. 2-3 ) 2.2-17 Beaver. Valley Unit 2 Turbine Building Vent Dispersion 2-41 Parameter (D/Q), a-2, for Continuous Mixed Mode Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) 2,2-18 Beaver Valley Unit 2 Condensate Polishing Building Vent 2-42 Dispersion Parameter (D/Q), mF2, for Continuous Mixed Mode Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) i

(E List of Tables ~(continued) l Table Title Page ) 1 2.2-19 Beaver-Valley Unit 2 Decontamination Building Vent Disper-2-43 -] sion Parameter (D/Q), m-2, for Continuous Mixed Mode Re-leases > SGJ Hrs /Yr or > 150 Hrs /Qtr for 'Special Distances f (Identified in Table 2.2-3) 2.2-20 Beaver; Valley Unit 2 Waste Gas Storage Vault Vent Disper-2-44 l sion Parameter (D/Qi, m-2, for Continuous Mixed Mode Re-l leases > 500 Hrs /Yr or > 150 Hrs /Qtr. for Special Distances .l (Identified in Table 2.2-3) 2-72 2.3-1 Modes of Gaseous Continuous and Batch Release for the Beaver Valley Power Station Unit 2 Vents for Implementation of -[ 10 CFR 50 2.3-2 R Values fcr the Be.tver Valley Power Station (Inhalation, 2-73 Adult) 2-74 2.3-3 R Values; for the Beaver Valley Power Station (Inhalation, (. 2-75 2.3-4 R Values for the Beaver Valley Power Station (Inhalation, Child) 2-76 2.3-5 R Values for the Beaver Valley Power Station (Inhalation, Infact) 2.3-6 R Values for the Beaver Valley Power Station (Ground Plane) 2-77 2-78 2.3-7 R Values for the Beaver Valley Power Station (Vegetable, Adult) 2-79 2.3-8 R Values for the Beaver Valley Power Station (Vegetable, Teen) 2-80 2.3-9 R Values for the Beaver Valley Power Station (Vegetable, Child) 1 2.3-10 R Values for the Beaver Valley Power Station (Meat, Adult) 2-81 a 2.3-11 R Values for the Beaver Valley Power Station (Meat, Teen) 2-82 j 2.3-12 R Values for the Beaver Valley Power Station (Meat, Child) 2-83 i \\ f iv i i

( F l List'of Tables (continued) i LTable Title Page 2.3-13 R Values for the Beaver Valley Power Station (Cow' Milk, 2-84 Adult) 2.3-14 R Values for the Beaver Valley Power Station (Cow Milk, ,,2-85 Teen) 2.3-15 R Values for the Beaver Valley Power Station (Cow Milk, 2-86 Child) 2.3-16 R Values for the Beaver Valley Power Station (Cow Milk, 2-87 Infant) 2.3-17 R Values for the Beaver Valley Power Station (Goat Milk, 2-88 Adult) 2.3-18 R Values for the Beaver Valley Power Station (Goat Milk, 2-89 Teen) 2.3-19 R Values for the Beaver Valley Power Station (Goat Milk, 2-90 [') . Child) 2.3-20 R Values fo*. the Beaver Valley Power Station- (Goat Milk, 2-91 Infant) l '2.3-21 Beaver Valley

• Unit 2 Process Vent Dispersion Parameters 2-92 (D7Q), mF, for Continuous Elevated Releases > 500. Hrs /Yr or 2

> 150 Hrs /Qtr /' t' 2.3-22 Beaver Valley Unit 2 Elevated Release Vent Dispersion 2-93 Paramet'ers (D/Q), m72, for Continuous Mixed Mode Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 2.3-23 Beaver Valley Unit 2 Ventilation Vent Dispersion Parameter 2, (D/Q), m7, for Continuous Mixed Mode Releases > 5,00 Hrs /Yr l 2 l or > '150 Hrs /Qtr ' / 2.3-24' Beaver Valley Unit 2 Turbine Building Vent Dispersion 2-95 2 Parameters (D/Q), m7, for Continuous Mixed Mode Releases > 500 Fxs/Yr or > 150 Hrs /Qtr I 2.3-25 Beaver. Valley Unit 2 Condensate Polishing Building Vent 2-96 l Dispersion Parameters (D/Q), my2, for Continuous Mixed Mode Releases > 500 Hrs /Yr or > 150 Hrs /Qtr I. ,3. 1 1

'l List of Tables Title Page Table 2-97 2.3-26 Beaver Valley Unit 2 Decontamination Building Vent Dispersion Parameters (D/Q), mr2, for Continuous Mixed Mode Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 2.3-27 Beaver Valley Unit 2 Waste Gas Storage Vault Vent Dispersion 2-98 Parameters (D/Q), m-2, for Continuous Mixed Mode Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 3-2 3.0-1 Radiological Environmental Monitoring Program A-3 A-1 Beaver Valley Unit 2 Release Conditions l' -A-2 Beaver Valley Unit 2 Elevated Release Vent Dispersion A-4 Parameters (X/q), sec/m3, for Ground Level Releases < 500 Hrs /Yr or > 150 Hrs /Qtr for Special Locations (Identified in Table 2.2-3) A-5 A-3 Beaver Valley Unit 2 Ventilation Vent Dispersion Parameters ( X/q), sec/m, for Batch Ground Level Releases < 500 Hrs /fr ( or < 150 Hrs /Qtr for Special Locations (Identified in Table 2.2-3) A-6 A-4 Beaver Valley Unit 2 Process Vent Dispersion Parametera ( X/q ), sec/m, for Batch Elevated Releases < 500 or < 150 Hrs /Qtr Vi

( List of Figures Figure Title Page 3-6 3.0-1 Radiological Environmental Monitoring Program - Air Sampling Locations 3-7 3.0-2 Radiological Environmental Monitoring Program - TLD Locations -- Northwest Quadrant 3-8 3.0-L Radiological Environmental Monitoring Program - TLD Locations -- Northeast Quadrant ,] l 3-9 l 3. 0-4 Radiologicai 29i3ronmental Monitoring Program - I TLD Locations -- Sentha.stt Quadrant (' 3.0-5 Radiological Environmental Monitoring Program - 3-10 TLD locacions -- Southwest Quadrant 3-11 3.0-6 Radiological Environmental Monitoring Program - Shoreline Sediment, Surface Water, and Drinking Water i Sampling Locations ( Radiological Environmental Monitoring Program - 3-12 3.0-7 Milk Sampling Locations 3-13 3.0-8 Radiological Environmental Monitoring Program - Fooderop Sampling Locations 3-14 3.0-9 Radiological Environmental Monitoring Program - Fish Sampling Locations l i l l l l t vii i I 1 1 _j

/ PREFACE This Offsite Dose Calculation Manual (ODCM) ' provides the information and methodologies to be. used by Beaver Valley Power Station' Unit 2 (BVPS-2) to assure compliance with certain portions of BVPS-2 Technical Specifications. These portions are those related to liquid and gaseous radiological effluents. l They are in ended to show compliance with 10. CFR 20,.10 CFR 50.36a, Appendix I of 10 CFR 50, and 40 CFR 190. This ODCM is based on " Radiological Effluent Technical Specifications for PWRs '(NUREG-0471, Draf t )"., " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133)", and other inputs from the United States Nuclear Regulatory Commission - (USNRC). Specific plant procedures for implementation of this manual will be developed. These procedures will be utilized by the ope ating staf f of BVPS-2 to assure compliance with Technical Specifications. possible in order to The ODCM has been prepared as generically as minimize that need fcr future revisions. However, some changes to the ODCM will be ' expected in - the future. Any such changes will be properly reviewed. and approved as. indicated.in the Administrative Control Section, Specification 6.15.2. of the BVPS-2 Technical Specifications. [ \\ 1 1 .1-viii

1.0 LIQUID EFFLUENTS 1.1 Monitor Alarm Setpoint Determination This procedure determines the monitor high-high alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentra-tions specified in 10 CFR 20, Appendix B, Table II, Column 2 for radi-onuclides other than dissolved or entrained noble gases or exceeds a concentration of. 2 x 10~" pCi/ml for dissolved or entrained noble gases. The ucthodology described in Section 1.1.2 is an alternative method to be used to determine the monitor high-high alarm setpoint (HHSP). The methodology in Section 1.1.2 may be used for any batch release and shall be used when the total radioactivity concentration of the liquid effluent prior to dilution exceeds 2.97E-5 pCi/ml, excluding tritium, or 0.0628 pCi/ml including tritium. The concentration of 0.0628 pCi/ml (including tritium) is equivalent to the calculated nuclide mix IDISP of 5-r87 R~~10 nepm (net counts per minute above background) de-b rive 1 in Section 1.1.1, L g,g gg 7 1.1.1 Setpoint Determination Based on a Conservative' Mix The high-high alarm setpoint for the Liquid Waste Effluent ( Monitor (2SGC-RQIl00) sho'uld be set at.L 87t5 nepm. This set-point is based on the following conditions: ( )4 M c CC/a y

• Source terms given in Table 1. h l.

These source terms have been generated by using models and input similiar to NUREG-0017. The inputs are given in Appendix B.

• Dilution water flow rate of 7,800 gpm.

o Dischstge flow rate prior to dilution of 116 gpm for the Liquid Waste Effluent Monitor (2 SCC-RQIl00). The above setpoints can be varied based on act ual operating conditions resulting in the discharge and dilution flow rates as follows: qadC-7 8 F HHSP = (g,g_g) A 0 kc HHSP = Monitor high-high alarm setpoint above background (nepdf T 37<3 = Proportionality constant based on nominal flow condi-nepm x 116 gpm + 7.8 x 103 4 p' tions (87.3 5.87 x 103 = gPm) gj jg i i 1-1

i / F. = Dilution water. flow rate, BVPS-2 Cooling Tower blowdown rate (gpm). ( f = Discharge flow rate prior to dilution (gpm). ~ 1.1.1.1 The " mix" (radionuclides and compostion) of the liquid ef fluent was determined as follows: a. The liquid source terms that are representative.of the " mix" of the liquid effluent were determined. ' Liquid source terms are the radioactivity. level's of the radionuclides in the ef fluent ' from Table 1.1-1. b. The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (S ) for each individual radionuclide in the i i liquid effluent was determined by equation 1.1-2. l A-1 (1.1-2) Sg = --g 3 i Ag = Annual release of radionuclide "i" in the liquid effluent from Table 1.1-1_ (Ci/yr). '[ 1.1.1.2 The maximum acceptable total radioactivity concentra-tion in DCi/ml of all radionuclides in the liquid effluent prior to dilution (C ) was determined by: e I C = t 51 (3,t_3) g MPG { F = Dilution water flow rate (gpm), BVPS-2 Cooling Tower blowdown rate (this does not include BVPS-1 blowdown or the BVPS-2 release out / through the Emergency Outfield Structure). = 7,800 gpm f = Maximum acceptable discharge flow rate prior to dilution (gpm). 116 gpm for Liquid Waste Process Effluent Moni- = cor (2SGC-RQIl00). MCPi = liquid effluent radioactivity concentration limit for radionuclide "i" (pci/ml) from Table 1.1-1 or if not listed in Table 1.1-1, obtained from Reference 1. l ( ( 1-2 I-I L

( k F = Dilution water flow rate, BVPS-2 Cooling Tower blowdown rate (gpm). ~f = Discharge flow rate prior to dilution (gpm). 1.1.1.1 The " mix" (radionuclides and compostion) of the liquid ef fluent was determined as follows: a. The liquid source terms that are representative of the " mix" of the liquid effluent were determined. leiquid source terms are the radioactivity levels of the radionuclides in the ef fluent - from Table 1.1-1. b. The fraction of the total radioactivity in ' the "i" liquid effluent comprised by radionuclide (S ) for each individual. radionuclide in the i liquid. effluent was determined by equation 1.1-2. A. (1.1-2) Si= 3 i Ai = Annual release of radionuclide "i" in the liquid ef fluent' from Table 1.1-1 (Ci/yr). ( 1.1.1.2 The maximum acceptable tot al radioactivity concentra-tion ~ in pCi/mi of all radionuclides in the liquid effluent. prior to dilution (C ) was determined by: t I C =. S i (1,g_3) t fg Ni i F = Dilution water flow rate (gpm), BVPS-2 Cooling Tower blowdown rate (this does not include BVPS-1 blowdown). = 7,800 gpm f = Maximum acceptable discharge flow rate prior to dilution (gpm). 1 = 116 gpm for Liquid Waste Process Ef fluent Moni-tor (2SGC-RQIl00). MCPi = liquid effluent radioactivity concentration limit for radionuclide "i" (pci/ml) from Table 1.1-1 or if not listed in Table 1.1-1, obtained from Reference 1. t 1-2^ I

l = the fraction of total radioactivity attr'buted '/ Si to radionuclide "i" (from Equation 1.1-2) 1.1.1.3 The maximum acceptable radioactivity concentratien in pCi/ml of radionuclide "i" in the liquid effluent prior to dilution (Ci) was determined by: C (1.1-4) Ci=Si c 1.1.1.4 The calculated monitor count rate in nepm above back-ground attributed to the radionuclides, C.R., was determined'by: C.R. = E C E (1.1-5) i ii Ei = Detection efficiency of the monitor for radionuclide "i" (cpm /pCi/ml) from Table 1.1-1. 1.1.1.5 The monitor high-high alarm setpoint above background (nepm) should be set at the C.R. value. 1.1.2 Setpoint Determination Based on Analysis Prior to Release liquid releases when determin-The following method applies to [ ing the antpoint for maximum acceptable discharge flow rate prior to dilution and the associated high-high alarm setpoint z based on this flow rate for the Liquid Waste Ef fluent Monitor I (2SGC-RQ1100) during all operational conditions. The monitor alarm setpoint is set slightly above (a factor of 1.25) the count rate that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge flow rate is reduced by this same f ac-tor. 1.1.2.1 The maximum accept able discharge flow rate (f) prior to dilution (in gpm) is determined by: F f-i (1.1-6) l 1*25 E MPCi 4 F = Dilution water flow rate, BVPS-2 Cooling Tower blowdown (gpm). ) I 1-3 l i i a

= Radioactivity concentration of radionuclide "i" l' C i in the liquid effluent prior to dilution (pci/ ml) from ~ analysis of the liquid affluent to be released.* 1,25 = A factor to prevent spurious alasas caused by deviations in the mixture of radionuclides l which affect the monitor response. MPCi = The liquid effluent radioactivity concentration l limit for radionuclide "i" (pci/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from ) Reference 1. 1.1.2.2 The calulated monitor count rate (in nepm) above back-ground. attributed to the radionuclides (CR) is deter-j { mined by: l (1.1-7) I C.R. = 1.25 E CgE i 1 = The detection efficiency of the monitor for Ei radionuclide "i" (cpm /pci/ml) from Table 1.1-1. l. l 1.25 = A factor to prevent spurious alarms caused by L deviations in the mixture of radionuclides {p which' affect the monitor response. 1.1.2.3 The monitor high-high alarm setpoint above background (nepm) should.be s.et -at the C.R. value. Since only one tank can be released at a time, adjustment of this value is not necessary to compensate' for releases from more than one source. Note:

• If the radioactivity of a radionuclide is below the LLD value specified in Table 4.11-1 of the BVPS-2 Technical Specifications, the radionuclide should not be included as a source term in this setpoint calculation.

(' l-l' \\ 1-4

l k g E )l 2 8887888888 N,m 7838887580770087855567EEEEEEEEEEEEEEEEEEE i OY/ EEEEEEEEE EE 000000000000000000000000000000000 I Ci 1 064901 441 580726 9376 TNC CE u 830283943 0 TC s 1 181 1 2623 14 1 3131 883521 21 412314 EI/ EI p DF e ~ F( E .) . l m 34455546005067553454546547'5665665 / _i EEEEEEEE00E0EEEEEEEEEEEEEEEEEEEEE C ( 21 8S931 3 2 33S431 S2283423281 2946 m U m .i C P S . M M S R E 1 T m E 1 5 C 1 R 1 U m E O L S m B A D T I UQ I L ES Ei 4 5 4' 53455905057633655554561 4326233 + A) EEEEEEEEE0EOEEEEEEEEEEEEEEEEEEEEE LC 000000000000000000000 E( R 000000000 0 253319152332408356029 05351 6299 7 AA 1 21611325 3 285221 228525917264393 Li UN NA m ED mm m m 1 1 2234456 m5779901 I ~ L 9 992222233333333333 45980334568901 11 1 11 1 1 11 11 1 1 1 C 1 U 5555562888888999911 N rneeooprrrbb rrt oceeeeeI eeI eIII sI s CMFFCCNBBBRRSSSMTTTTTT TT T C C O I DAR

!;1 t ay g E) ,l 2 m 88780557' 8880 7787's60 NOY/ ICi EEEE EEEEEE - EEEE .E TNC 000000000000 0000000 ~ CEp 5307 559337 6229 2 EI/ TC m 1192 331 11 1 771 1 3 EI p DF c F( E ) I _m N,' - m50555355545520555503 / i C EO5EEEEEEEEEE0EEEE0E u ( 2 2223336I 8II 941 S 3 i u ) C [i d P e S M u M n R g i E t T no E C C 6 ( R 1 U 1 O S 1 D 1 I U E Q L I a B L \\ e A E u T SA) Ei 22667667666767676662 - - - - - - - - - - - - - - - - - - - + LC E( EEEEEEEEEEEEEEEEEEEE R 00000000000000000000 21340640007272066365 Li AA 22986343442828482225 U NN A E w D m I m L 7700 H 363613434 m C 3344011 355000044444 m U 1 1 11 9999991 11 1 11 1 11 3 N O s aaaYYYY rb uuhh eeerrH I CBBL ZNRRRRCCCPP DA R T v_ m

m i I ( BEAVER VALI cY ODCM REFERENWS Liquid Ef fluent Monitor Setpoints 110 CFR 20, Appendix B, Table II, Column 2. 2. A. Technology, Letter No. 2505-31, dated June 1, 1984. G 3 Stone and Webster Computer Codes:, (i) CASIBB " Normal Gaseous Releases from a Pressurized Water Reactor" - NU144. (ii) LIQ 1BB " Normal Liquid Releases from a Prespurized Water Reactor - NU143. ( 1-7

( - 1.2 Compliance with BVTS 3.11.1.d Only nucliden, for which acuivity concentrations are abe e 11D's speci-fied in. Table 4.11-1 of Te chnical Specification 3.11.1.1 are consid-ered to be present. 1.2.1 Batch Releases 1.2.1.1 Pre-Release The radioactivity content of each batch release will be determined prior to release in accordance with Table 4.11-1 of Beaver Valley Unit 2 Technical Speci-fications (BVTS). In order to assure represent ative samples, at least two tank volumes of entrained fluid from each tank to be discharged shall be recirculated through the mixing eductors. This will be - acc om-plished by recirculating the tank contents for at least the time periods indicated in Table 1.2-1. The Beaver Valley Power Station Unit 2 (BVPS-2) will show compliance with BVTS 3.11.1.1 in the followir g man-ner: The. activity of the various radionuclides in' the batch release, determined in accordance wich' Table 4.11-1, is divided by the minimum dilution flow to obta.in the .- ( ' concentration at the unrestricted area. This calcula-tion is shown in the following equation: Ci R (1.2-1) Conc = i MDF i where: Conci = concentration of radionuclide "i" at the unrestricted area, pCi/ml. = concentration of radionuclide "i" in the Ci potential batch release, pCi/ml. R = release rate of the batch, gpm (maximum release rate = 116 gpm). MDF = cooling tower blowdown rate, gpm (minimum dilution flow = 7,800 gpm). Before a release is authorized, Expression 1.2-2 must be satisfied. The projected concentratioas in the unrestricted area are compared to the concentrations in Appendix B, l [ Table II of 10 CFR 20: 4 e 1-8 1 4

I I, (Conei/MPC;) < 1 (1.2-2) I where: maximum permissible concentration of radionu-l'"(* i = clide "i" from Appendix B, Table II of 10 CFR 20,_pCi/ml. The most common MPCi conce st rations are listed in Table 1.1-1 and were taken from Apper dix B, Table 11 of 10CFR20. 1.2.1.2 Post-Release The concentration of each radionuclide following release from the batch tank will be calculated in the unrestricted area in the following manner: T.he average activity of radionuclide "i" during the time period of release is divided by the actual dilu-tion flow during the period of release to obtain the concentration in the unrestricted area. This calcula-tion is shown in the following equation: ik k (1.2-3) ( Concik, where: l Concik* = the concentration of radionuclide "i" at the unrestricted area, during the release period of time "k", pCi/ml. = concentration of radionuclide "i" in batch Cik release during time period "k", pCi/ml. V = volume of tank released during time period tk "k", gal. ADF = actual volume of dilution flow during the k time period of release "k", gal. To show compliance with BVTS 3.11.1.1, the following relationship must hold: I,(Concik/MPCg) < 1 (1.2-4) 1

• Since discharge is from an isolated well-mixed tank at essentially a uniform

( i rate, the difference between average and peak concentration within any dis-charge period is minimal. 1-9

i' ?' l 'I 1.2.2 _C_.'nt inuou s C'ntinuous releases of liquid af fluents do not presently occur l at'the BVPS-2. l i i 9 1 4 l'.,' . } 1; r t 4 'I ) Y I 1 ( 'i s 1-10 ( a, t j I _ -. ~

/ TABLE 1.2-1 I RECIRCULATION "IMES REQUIRED BEFORE SAMPLIhG OF LIQUID DISCHARGE TANKS Approximate b Name Recirculation Time (by Operating Manual) Mark No. (hours) tiquid Waste Tanks 2LWS-TK21A,B 8.3 a Steam Generator Blowdown Hold Hold Tanks 2SGC-TK21A,B 33.3 a SGC Test Tanks 2SGC-TK23A,B 12.0 o Not normally a direct source of diecharge. a ( The. times listed are those required for two recirculations of a full tank b with one recirculation pump in operation. Partially full tank recirculation times"Te directly proportional to the fraction of the tank capacity occupied by the entrained liquid waste after isolation. 4 1 1 A' st 1-11

I i 1.3 Compliance with 10 CFR 50 U.iquids) 1.3.1 Cumulation of Doses The dose contribution from the release of' liquid effluents will ~ be-calculated monthly for each batch release during the month, and a cumulative summation - of the total body and organ doses will be maintained. for each calendar month, current calendar quarter, and the calends.r year to date. The dose contribution will be calculated using - the following equation: I i m at C F) (I'3"I) r"E(Air k=l k ik D k i i where: l D = the cumulative dose commitment to the total body or any l

organ, r, from the liquid effluents for the total time r

period m E-Atk' "#8" k = 1. j Atk = the length of the kth release over which Cik k ) and F are averaged for all liquid releases, hours 1 f Cik.= the average concentration of radionuclide, i, in undi- ) luted liquid efftuent during time period At from any { 1 k liquid release, pCi/mi l Air ".the site related ingestion dose commitment factor to. the total body or any organ r for each ide'ntified principal gamma and beta emitter, mrem-m1 per hr-uCi m = number "of ru eases contributing to the cumulative dose, Dr i,g during i F = the near field average dilution factor for C k any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the i product of the average flow from the site discharge structure to unrestricted receiving waters times 3. (3 is the site specific applicab,le factor for the mixing effect of the BVPS-2 discharge structure.) Y tk 3 ADFk are defined in Equation 1.2-3. where V and ADFk tk The site specific applicable factor of 3 represents a conservative estimate of the near field dilution factor i 1-12 m r a u i- - - - -

E / based upon Regulatory Guide. -l.113 methodology and is a factor of ten below the limit specified in NUREG-0133, S etion'4.3. O The dose factor.A was calculated for an adult for each isotope using the f [ lowing equation from NUREG-0133: 5 (730/D, + 21BF() DFir L (1.3-2) Air = 1.14x10 I where: m 1.14 x105 196 pci 3 x 10,m1'x 1 vr W T

• bib $ hr 730

= adbi~t vater consumption rate, liters /yr. D, = dilution factor from the near field area within one quarter mile; of the-release point to the potable water intake for adult pater consumption. 21 = adult fish consumption, kg/yr. BF; = bioaccumulation factor for radionuclide i in fish from Table A-1 'of Ref,ulatory Guide 1.109 Rev. 1, pCi/lfg per pCi/ liters. l = dose conversion factor for' radionuclide i for adults ') DFir for a particular organ r from ' Table E-11 ' of Regula-tory Guide 1.109 Rev. 1, mrem /pCi. for an adult at BVPS-2 are presented of - A 5 values A table b The far field dilution factor (D,) for 1.3 in' Table BVPS-r, is 182. This value is based on a total dilution factor of 545 applicable to the Chester, West Virginia, water intake located 7.1 miles downstream (i.e., 182 = 545 + 3). The cumulative doses for a calendar quarter are compared to one-half the design objective doses for the total body and any organ and to the design objective doses for a calendar year. q The following relationships should hold for BVPS-2 to show com-8 pliance with BVPS-2 Technical Specification.3.11.1.2: i For the calendar quarter, j ) Dr< 1.5 mrem total body (1.3-3) D < 5.0 mrem any organ (1.3-4) r For the calendar year, ( 1-13 1

l D < 3.0 mrem total body (1.3-5) ( r D C 10.0 iarem any organ (1.3-6) r The quarterly limits given above represent one-half the annual design objective of Section II. A of Appendix I of 10 CFR 50. If any of the limits in Expressions 1.3-3 through 1.3-6 are exceeded, a special report pursuant to Section IV.A of Appendix I of 10 CFR 50 must be filed with the NRC. 1.3.2 Projection of Doses Doses resulting from the release of liquid effluents will be projecte.1 once per month based upon past operating history data for BVPS-2. The doses will be projected using. Equation 1.3-1 with F now based upon the minimum dilution flow (MDF) as g Equation 1.2-1 rtther ADF. Cik is based upon given k in the projected releases for the remainder of the calendar quar-ter. If the sum of the accumuisted dose to date for the quar-ter and the projected dose for the remainder of the quarter-exceeds 25% of the annual limits, then the appropriate liquid radwaste sub-system will be used. ( l 1-14 l

'[ TABLE 1.3-1 VALUES FOR THE ADULT FOR THE A ir BEAVER VALLEY UNIT 2 (MREM /HR PER MICRO-CI/ML) Nuclide Bone Liver T-Body Thyroid Kidney Lung GI-LLI H 3 0.00E-0) 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 C 14 3.13E 04 6.26E 03 6.26E 03. 6.26E 03 6.26E 03 6.26E 03 6.26E 03 NA 24 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 P 32 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.19E 06 CR 51 0.00E-04 0.00E-01 1.27E 00 7.62E-01 2.81E-01 1.69E 00 3.21E 02 MN 54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 MN 56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.52E 03 FE 55 6.59E 02 4.56E 02 1.06E 02 0.00E-01 0.00E-01 2.54E 02 2.61E 02 FE 59 1.04E 03 2.45E 03 9.38E 02 0.00E-01 0.00E-01 6.83E 02 8.15E 03 CO 57 0.00E-01 2.10E 01 3.50E 01 0.00E-01 0.00E-01 0.00E-01 5.33E 02 CO 58 0.00E-01 8.95E 01 2.01E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 CO 60 0.00E-01 2.57E 02 5.67E 02 0.00E-01 0.00E-01 0.00E-01 4.33E 03 NI 63 3.12E 0'6 2.16E 03 1.05E 03 0.00E-01 0.00E-01 0.00E-01 4.51E 02 NI 65 1.27E 02 1.65E 01 7.51E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 CU 64 0.00E-01 l'.00E 01 4.70E 00 0.00E-01 2.52E 01 0.00E-01 8.53E 02 ZN 65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 (" ZN 69 4.93E Oi 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 BR 83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 BR 84 0.00E-0, 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 BR 85 0.00E-0* 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 1.01E-15 RB 86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 RB 88 0.00E-01 2.90E 02 1.54E 02

0. 00 E-0,1 0.00E-01 0.00E-01 4.00E-09 RB 89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 SR 89 2.22E 04 0.00E-01 6.39E 02 0.00E-01 0.00E-01 0.00E-01 3.57E 03 SR 90 5.48E 05 0.00E-01 1.34E 05 0.00E-01 0.00E-01 0.00E-01 1.58E 04 SR fl 4.10E 02 0.00E-01 1.65E 01 0.00E-01 0.00E-01 0.0GE-01 1.95E 03 SR 92 1.55E~02 0.00E-01 6.72E 00 0.00E-01 0.00E-01 0.00E-01 3.08E 03 Y 90 5.80E-01 0.00E-01 1.55E-02 0.00E-01 0.00E-01 0.00E-01 6.15E 03 Y 91M 5.48E-03 0.00E-01 2.12E-04 0.00E-01 0.00E-01 0.00E-01 1.61E-02 Y 91 8.50E 00 0.00E-01 2.27E-01 0.00E-01 0.00E-01 0.00E-01 4.68E 03 Y 92 5.09E-02 0.00E-01 1.49E-03 0.00E-01 0.00E-01 0.00E-01 8.92E 02 Y 93 1.62E-01 0.00E-01 4.46E-03 0.00E-01 0.00E-01 0.00E-01 5.12E 03 l

I .i 1-15 i i

l l l (' TABLE 1.3-1 (Continued) 1 VALUES FOR THE ADULT FOR THE A ir BEAVER VALLEY UNIT 2 (MREM /RR PER MICRO-CI/ML) j l Nuclide Bone Liver T-Body Thyroid Kidney Lung CI-LLI f 1 ZR 95 2.53E-01 8.11E-02 5.49E-02 0.00E-01 1.27E-01 0.00E-01 2.57E 02 ZR 97 1.40E-02 2.82E-03 1.29E-03 0.00E-01 4.26E-03 0.00E-01 8.73E 02 ] NB 95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 i NB 97 3.75E 00 9.48E-01 3.46E-01 0.00E-01 1.11E 00 0.00E-01 3.50E 03 MO 99-0.00E-01 1.05E 02 2.00E 01 0.00E-01 2.38E 02 0.00E-01 2.43E 02 TC 99M 8.97E-03

2. 54E-02 3.23E-01 0.00E-01 3.85E-01 1.24E-02 1.50E 01 l

TC101 9.23E-03 1.33E-02 1.30E-01 0.00E-01 2.39E-01 6.79E-03 4.00E-14 RU103 4.51E 00 0.00E-01 1.94E 00 0.00E-01 1.72E 01 0.00E-01 5.26E 02 RU105 3.75E-01 0.00E-01 1.48E-01 0.00E-01 4.85E 00 0.00E-01 2.29E 02 RU106 6.70E 01 0.00E-01 8.48E 00 0.00E-01 1.29E 02 0.00E-01 4.34E 03 AG110M 9.48E-01 8.77E-01 5.21E-01 0.00E-01 1.72E 00 0.00E-01 3.58E 02 TE125M 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.03E 04 TE127M 6.49E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 TE127 1.05E 02 3.78E 01 2.28E 01 7.81E 01 4.29E 02 0.00E-01 0,32E 03 TE129M 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.55E 04 TE129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 TE131M 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.05E 04 [ \\ TE131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.27E 01 0.00E-01 2.67E 00 1E132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.39E 04 TE134 3.10E 01 2.03E 01 1.25E 01 2.71E 01 1.96E 02 0.00E-01 3.44E-02 I 129 1.19E 02 1.02E 02 3.35E 02 2.63E 05 2.19E 02 0.00E-01 1.61E 01 I 130 2.75E 01 8.10E 01 3.20E 01 6.87E 03 1.26E 02 0.00E-01 6.97E 01 l'131 1.51E 02 2.16E 02 1.24E 02 7.08E 04 3.71E 02 0.00E-01 5.70E 01 I 132 7.37E 00 1.97E 01 6.90E 00 6.90E 02 3.14E 01 0.00E-01 3.71E 00 1 133 5.16E 01 8.97E 01 2.74E 01 1.32E 04 1.57E 02 0.00E-01 8.06E 01 1 134 3.85E 00 1.05E 01. 3.74E 00 1.81E 02 1.66E 01 0.00E-01 9.12E-03 1 135' 1.61E 01 4.21E 01 1.56E 01 2.78E 03 6.76E 01 0.00E-01 4.76E 01 CS134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 l CS136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.39E 03 1.40E 04 l CS137 3.82E 05 5.22E 05 3.42E 05 0.00E-01 1.77E 05 5.89E 04 1.01E 04 l CS138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 BA139 9.69E-01, 6.90E-04 2.84E-02 0.00E-01 6.45E-04 3.92E-04 1.72E 00 BA140 2.03E 02 2.55E-01 1.33E 01 0.00E-01 8.66E-02 1.46E-01 4.18E 02 BA141 4.71E-01 3.56E-04 1.59E-02 0.00E-01 3.31E-04 2.02E-04 2.22E-10 (. ) 1-16 l l

f TABLE 1.3-1 (Continued)

VALUES FOR THE ADULT FOR THE A ir BEAVER VALLEY UNIT 2 (MREM /HR PER MICRO-CI/HL) Nuclide Bone Liver T-Body Thyroid Kidney Lung GI-LLI BA142 2.13E-01 2.19E-04 1.34E-02 0.00E-01 1.85E-04 1.24E-04 3.00E-19 LA140 1.51E-01 7.59E-02 2.01E-02 0.00E-01 0.00E-01 0.00E-01 5.57E 03 LA142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E-01 2.56E 01 CE141 2.63E-02 1.78E-02 2.02E-03 0.00E-01 8.26E-03 0.00E-01 6.80E 01 CE143 4.64E-03 3.43E 00 3.79E-04 0.00E-01 1.51E-03 0.00E-01 1.28E 02 CE144 1.37E 00 5.73E-01 7.36E-02 0.00E-01 3.40E-01 0.00E-01 4.64E 02 FR143 5.54E-01 ,2.22E-01 2.75E-02 0.00E-01 1.28E-01 0.00E-01 2.43E 03 PR144 1.81E-03 7.53E-04 9.22E-05 0.00E-01 4.25E-04 0.00E-01 2.61E-10 ND147 3.79E-01 4.38E-01 2.62E-02 0.00E-01 2.56E-01 0.00E-01 2 10E 03 W 187 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.QpE-01 0.00E-01 8.10E 04 NP239 2.90E-02 2.85E-03 1.57E-03. 0.00E-01 8.89E-03 0.00E-01 5.85E 02 SB124 8.01E 01 1.51E-01 3.17E 00 1.94E-02 0.00E-01 6.22E 00 2.27E 02 SB125 2.38E 01 4.79E-01 1.08E 00 3.96E-01 0.00E-01 0.00E 2.97E 02 i l 1 1-17

f 2.0 GASEOUS EFFLUENTS 2.1 Monitor Alarm Setpoint Determination l This procedure determines the monitor high-high alarm setpoint that indicates if the dose rate in the unrestricted areas due to noble gas l radionuclides in the gaseous effluent released from the site exceeds 250 mrem / year to the whole body or exceeds 1500 mrem / year to the skin. Two alarm setpoint determinations are required for each of the tl5ree i gaseous effluent monitors; the high alarm setpoint (HSP) anc 'he high-high alarm setpoint (HHSP). The HSP of each monitor indicates when the dose rate from effluent measured by the monitor exceeds the fol-lowing respective dose rates: HSP Dose Rate (mrem / year) Limit Whole Fraction of Limiting Dose Rate (FR) Monitor Body Skil Elevated Release Vent Gas 25.0 150 0.1 Monitor 2HVS*RQIl09G Ventilation Vent Monitor 50.0 300 0.2 [ 2HVS-RQIl016 t Waste Gas Storage Vault 0.5 3 0.002 Vent Monitor 2RMQ-RQI303 Decontamination Bldg. Vent 1.5 9 0.006 Monitor 2RMQ-RQI301. Condensate Pol. Bldg. Vent 3.0 18 0.012 Monitor 2HVL-RQI112 Process Vent Monitor (BVPS-1) 20.0 120 0.08 RM-GW-108 A&B < 0.001 Turbine Building Vent i Total 100 600 0.4 The HSP of each monitor is chosen based on expected releases from the monitored pathway. If all monitors are alarming simultaneously at the HSP, the combined HSP indicates when the dose rate from effluents measured by all monitors exceed at least 40 percent of the applicable dose rate limit. BVPS-1 Process Vent release HSP will be assigned a BVPS-2 contribution of 20 mrem / year whole body dose rate and 120 g 2-1

[ mrem / year skim dose rate. The HSP and HHSP for the Proc tss Vent moni-tor will be calculated by BVPS-1 using BVPS-1 ODCM methciology. The HHSP of each monitor indicates when the dose rate from ef fluent measured by that monitor is 60 percent of or greater tran the applic-able Technical Specification dose rate limit. The HSP alarm indicates the assigned fraction of limiting dose rate has been exceeded but that that the release is less than 60 percent of the dose rate limit. Ac-cordingly, one HHSP or two simultaneous HSP alarms will indicate when j the effluent dose rate from the respective releases amy have exceeded the applicable dose rate limits. The methodologies described in Sections 2.1.3 and 2.1.4 provide an ' of determining monitor high-high alarm setpoints that alternate means may be used when an analysis is performed prior to release. For a simultaneous batch and continuous gaseous release from one vent, calculate the setpoint for each type of release and use the lowest detpoint obtained. Batch refers to' releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment ventings and purges, and systems or components with infrequent use. Batch releases may be due to operational variations which result in radioactive releases greater than 50.% of the releases normally considered as continuous. Batch releases from these sources during normal operation, including anticipated operational occur-rences, are defined as those which occur for a total of 500 hours or ( .I less in a calendar year but not more than 150 hours in any quarter. The batch relative concentration value has been calculated in accord-ance with the guidelines provided in NUREG-0324 for short-term re-lease. 2.1.1 Setpoint Determination Based on a Calculated Mix for Ventila-tion Vent, Elevated Release Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and Waste Gas Storage Vault Vent Releases The calculated monitor count rate above background (C.R.), in nepm, associated with the limiting annual dose rate (i.e., 250 1 mrem whole body or 1500 mrem beta skin), the high-high alarm setpoint above background (HHSP), and the high alarm setpoint above background (HSP) for each vent and operational condition should be as follows: i C.R. HHSP HSP a I Continuous Release via the Ventilation Vent 4.05E3 2.43E3 8.10L! s Batch Release of Containment ~ Purge via the Ventilation 5.55E2 3.33E2 1.11E2 1 1 Vent l 1 2-2

i [' O. Continuous Release via the Elevated Release Vent (Containment Vent) 2.28E3. 1.36E3 2.27E2 Batch Release of Containment Purge via the Elevated Re-lease Vent (Containment Vent) 1.05E3 ~6.27E2 1.05E2 Continuous Release via the e Condensate Polishing Bldg. 1.45E4 8.68E3 1.73E2 ) Vent

• Continuous Release via the Decontamination Building 2.83E4 1.70E4 1.70E2 Vent Continuous Release via the

' Waste Gas Storage Vault Vent 4.03E5 2.42E5' 8.05E2 The setpoints'were determined using the following conditions: H e Source terms given 'in Table 2.2-2. The Decontamination Building and Condensate Polishing Building ventilation ex-haust are'not expected to be radioactive. However, for alarm ' set point, it is conserva-purposes of-determining an tively assumed that Xe-133 is in the ventilation exhaust at [- ' hat would result in the appropriate dose q~ concentrations t rate limits. The Waste Gas Storage Vault ventilation exhaust is also not normally radioactive. However, the monitor alarm setpoint is based on the assumption that che ventilation exhaust radionuclide spectrum is similar to the gaseous inventory in the system housed by the vaste gas storage vault. This spectrum is listed in Table 2.2-2 under radioactive gaseous waste system. o Discharge flow rate of 23,700 cfm for the Ventilation Vent (continuous).

• Discharge flow rate of 53,700 cfm for the Ventilation Vent (batch release of containment purge).
• Discharge flow rate of 59,000 cfm for the Elevated - Release Vent (Containment Vent) (both-continuous and batch release of containment purge).
• Discharge flow rate of 30,556 cfm for the Condensate Polish-ing Building vent.

e Discharge flow rate of 12,400 cfm for the Decontamination Building vent. I 2-3 1

i

• Discharge flow rate of 2,000 *fm for the Waste Gas Storage

~ [ Vault vent. The calculation method given in Sections 2.1.1.1 through 2.1.1.7 was used to derive the hieh-high alarm setpoint for the Ventilation Vent Gas Monitor (2HV S-RQIl01 ), Elevated Release Vent Gas Monitor (2HVS*RQ11090), Condensate Polishing Building Vent Gas Monitor (2HVL-RQ1112), Decontamination Building Vent Gas Monitor (2RMQ-RQ1301), and Waste Gas Storage Vault Vent Gas Monitor (2RMQ-RQ1303) during the following operational condi-tions: Continuous release via the Ventilation Vent

• Continuous release via the Elevated Release Vent (Contain-ment Vent)

Batch release of containment purge via the Ventilation Vent

• Batch release of containment purge via the Elevated Release Vent (Containment Vent).
• Continuous release via the Condensate Polishing Building ventilation vent exhaust.

Continuous release via the Decontamination Building ventila- / ' I tion vent exhaust.

• Continuous release via the Waste Gas Storage Vault ventila-tion vent exhaust.

2.1.1.1 The " mix" (noble gas radionuclides and composi+. ion) of ~ the gaseous effluent was determined as follows: / l representative a. The gaseous source terms that are of the " mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flowrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from Table 2.2-2 and Section 2.1.1. b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionu-clide "i" (S ) for each individual noble gas 4 radionuclide in the gaseous effluent was deter- ~ mined by: A-l (2.1-1) S; = 7 g, I 1 2-4 I

the ra 'ioactivity concentration of noble gas [ Ai = radioniclide "i" in the gaseous effluent f rom T ble 2.2-2 and Section 2.1.1. 2.1.1.2 The maximum acceptable total release rate in pCi/sec of all noble gas radionuclides in the gaseous effluent (Qg) based upon the whole body exposure limit was calculated by: (2*l~2) 9 " (X/Q Kg ; t S 1 where X/Q for each case is given below: / ~ (X/Q)y = the highest calculated annual average rela-tive concentration of ef fluents released via the Ventilation Vent for any area at or be-yond the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5 and Table 3 A-3 of Appendix A. 3 for continuous releases. = 1.03 E-4 sec/m t (X/9)v/= 3.32 E-4 sec/m for batch release of contain-3 ment purge. (. (X/Q)m = the highest calculated annual average rela-tive concentration of ef fluents released via the Elevated Release Vent (Containment Vent) for any area at or beyon1 the unrestricted 3 area boundary for all sectors (sec/m ) from Table 2.2-4 and Table A-2 of ippendix A. 3 for continuous releases. 9.24 E-5 sec/m v= (X/9)m = 3.08 E-4 sec/m for batch release of cont,ain-3 ment purge. (X/Q)e = the highest calculated annual average rela-tive concentration of effluents released via the Consensate Polishing Building Vent for any area at or beyond the unrestricted area 3 boundary for all sectors (sec/m ) from Table 2.2-10. 3 for continuous releases. ='7.35 E-5 sec/m (X/Q)d = the highest calculated annual average rela-tive concentration of effluents released via the Decontamination Building Vent for any area at or beyond the unrestricted area ( 2-5

boundary for all sectors (sec/m3)from Table f' 2.2-8. 3 for continuous releases. 9.24 E-5 sec/m <= (X/Q)w = the ' highest. calculated annual average rela-tive concentration of effluents released via the Waste Gas Storage Vault Vent for any area at or.beyond the unrestricted area boundary-3 for all sectors (sec/m ) fr.,m Table !.2-9. i 3 for continuous releases. v= 9.24 E-5 sec/m K- = the total' whole body dose factor due to gamma i emissions from noble'. gas radionuclide "i" 3 (mrem / year /pCi/m ) ' from Table 2.2-11. s was also' determined based upon the skin exposure 2.1.1.3 -Qg limit by: (2.1-3) t " L X/ 41 ?- ( i 1.1 M l Si i 1 L. = the skin dose factor due to beta emissions from 3 radionuclide "i" - (mrem / year /pQi/m ) noble gas from Table 2.2-11. Mi = the air dose factor due to gamma emissions from 3 noble gas radionuclide "i" - (mrad / year /pci/m ) from Table 2.2-11. 1.1 = the ratio of the tissue to..ir. absorption coef-the energy range of the. photon of ficients over interest, (mrem /arad). (X/Q) = Same as in Section 2.1.1.2. 2.1.1.4 The maximum acceptable release rate in pCi/sec of noble gas radionuclide "i" in the gaseous effluent (Q.) for each noble gas radionuclide in the gaseous. ef luent was determined by: i"Si 9 (2.1-4) t NOTE: Use the lower _of,the Qg values obtained. in Sections 2.1.1.2 and 2.1.1.3. 2-6 i \\ \\ l

() 2.1.1.5 The. maximum. acceptable radioactivity. concentration 2Ci/cc of noble gas radionuclide '"i" in the gaseous nffluent (C ) for each ' indiv' dual noble gas radionu-i c.1.ide in the gaseous ef fluent. was determined by: a -2.12 E-3 Qi (2.1-5) C.= 1 F the maximum acceptable effluent flow ' rate F a at the point V release (c fm) as listed in ~ Section 2.1.1. 2,12 E-3 = unit conversion. factor (60 sec/ min x 3.53 E-5 ft3 /cc ). 2.1.1.6 The calculated monitor count rate in ncpm above Lback-ground attributed to the noble gas radionuclide. (C.R. was determined by: .(2.1-6) l C.R. = E C Eii 1 = the detection ef ficiency of the monitor tor. noble Ei gas radionuclide "i" (cpm /pci/cc) from Table 2.1-1. ( ..I 2.1.1.7 The monitor alarm setpoints above background were determined as follows: i a. The monitor high-high alarm HHSP setpoint above background (in nepm) was determined by: HHSP = 0.60 C.R. (2.1-7). b. The monitor high alarm setpoint HSP above back-ground (la nepm) was determined by: HSP = FR x C.R. (2.1-8) where: FR = Fraction of limiting dose rate for respec-tive radiation monitor (from Section 2.1). 2.1.2 Setpoint Determination Based on Analysis Prior to Release When the setpoints established using "the calculated ' mix" do not provide adequate flexibility for operational needs, the ( 2-7 I l

met Sod described below may be used in lieu of that set forth in Settion 2.1.1. In this case, the results of sample analysis used to determine ties appro riate nuclide mix. This ca'lcu-a r t. lational method applies when determining the setpoint for the ma.rimum acceptable discharge flow rate and the associated high-high alarm setpoint based on respective vent flow rate during the following operational conditions: e Batch release of containment purge vi. the Ventilation Vent

• Patch release of containment purge via the Elevated Release Vent (containment vent).

NOTE: If the radioactivity of a noble gas radionuclide is below the llD value specified in Table 4.11-2 of the BVPS-2 Technical Specifications, the noble gas radionu-clide should ~ not be included as a source term in this I setpoint calculation. 2.1.2.1 The maximum acceptable discharge flow rate from the Elevated Release Vent or Ventilation Vent during purg-ing is determined as follows: The maximum acceptable gaseous discharge flow rate a. (f) in efm from the Elevated Release Vent (Con-tainment Vent) or Ventilation Vent during purging based upon the whole body exposure limit is calcu-lated by: 0.318 T (2.1-9) fn ( X/ 91 ?. K Gii 1 where (X/q) fo-each case considered,is given below. 0.318 = 250 mrem /yr x 2.12 E-3 x.0.6 f where: 250 mrem /yr = dose rate limit { 2.12 E-3 = unit' conversion f actor factor to - account for simultaneous 0.6 = releases from other vents. (X/9)y= the highest calculated short-term rela-j tive concentration of effluents released via the Ventilation Vent for any area at or beyond the unrestricted area boundary / 2-8

l / for all sectors (sec/m3) from Table A-3 of Appendix A. 3 3.32 E-4 sec/m = (X/q)m= the highest calculated short-term rela-tive concentration of ef fluents released via the Elevated Release Vent (Contain-beyond the ment Venti for areas at or unrestricted area boundary for all sec-tors (sec/m ) from Table A-2 of Appendix 3 A. 3.08 E-4 sec/m3 = the total whole body does factor due to K = i gamma emissions from noble gas radionu-3 clide "i" (mrem / year /pCi/m ) from Table 2.2-11. e = the undiluted radioactivity concentration of noble Ci gas radionuclide "1" in the gaseous source (uci/cc) as determined by analysis of the gas to be released. T = maximum value for T is 16 based on the limiting restriction in T.S. 3.11.2.la where the dose rate for a containment purge may be averaged over a time period ( to exceed 960 minutes (as containment air volume not change time period is 60 minutes; T = 960/60 = 16) b. The flow rate (f) in cfm is also determined based as follows: uport the skin exposure limit (2 1-10) f " ( X/ 41 ?t i ti ) Gi 1 1 i 1 where: 1.91 = 1500 mrem /yr x 2.12 E-3 x 0.6. 1 1500 mrem /yr = dose rate limit. unit conversion factor. i 2.12 E-3 = 1 0.6 = factor to account for simultan-i eous releases from other f events. 1 the skin dose factor due to beta emis-L = i sions from noble gas radionuclide "i" l (mrem / year /uci/m ) from Table 2.2-11. 3 l 2-9 a

l l i f = the air. dose factor due to gamma emis-f Mi sions from noble gas' radionuclide "i" (mrad / year /pci/m ) from Table 2.2-11. 3 X/Q = Same as in-Section 2.1.2.1.a. c. The' flow rate (f) is determined by selecting the smaller of the ' calculated (f) values based on the whole body exposure limit (Section 2.1.2.1.a) and l based on the skin exposure = limit (Section 2.1.2.1.b). The actual purge -flow rate in efm must be maintained at or below this calculated (f) value or the. discharge.cannot be made from the vent. i 2.1.2.2 The monitor alarm setpoints above background are de ~ termined as follows; a. The calculated ' monitor high-high alarm setpoint (HHSP) above background (nepm). attributed to the noble gas radionuclides is determined by: fICEii (2*I~II) I HHSP = F .f = the maximum acceptable containment purge flow ' (. rate (cfm) determined in 'Section 2.1.2.1. ) F' = the '.aximum actual or design effluent flow rate (cfm) at the point of release. i = 23,700 cfm Ventilation Vent. = 51,500 cfm Elevated. Release Vent (Cont ainment Vent) = the undiluted radioactivity concentration of noble Ci gas radionuclide "i" in the' gaseous source (uci/cc) as determined by analysis of the gas to be released. Ei = the detection efficiency of the monitor for noble gas radionuclide "i" (cpm /pci/cc) from Table 2.1-1. b. The monitor high alarm setpoint* (HSP) above back-- l ground (nepm) is determined by: HSP (Ventilation Vent) = 0.333 x HHSP HSP (Elevated Release) = 0.166 x HilSP k f 2-10 4 .i

This is based on definition provided on page 2-1 that the IDlSP is set at 60% of the dose rate limit and. the HSP for Ventilation Vent and Elevated Release Vent (Containment Vent) is. 20% and 10%, i respectively. e e I v ) J 'li l i, o I e I 2-11 l .. j

-i BEAVER VALLEY l' NIT 2 ODCM REFERENCES i l Gaseous Ef fluent Monitor Setpoints DA Technology, Letter No. 2505-31, dated June 1, 1984. i

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2.2 Compliance with 10 CFR 20 (Gaseous)

] I2.2.1 Nobl,e Gases The dose rate in unrestricted areas resulting from noble gas effluents is ~1imited to 500 mrem /yr to the total body and 3,000 mrem /yr to'the skin. Based ~ upon NUREG-0133 the' following basic expressions are used to show compliance with BVTS 3.11.2.1.a. ' E (V h, + K (X/Q)y h y) < 500 mrem /yr x 0.5-(2.2-1) i i i i i Q v) < 3000. mrem /yr x 0.5 (2.2-2) E ((L ( X/Q)s + 1.1B{)Q, + (Li + 1.1M )(X/Q)y i i i i i where: e = the total body dose factor due to gamma ' emissions. for Ki each identified noble gas radionuclide "i,": mrem / year / - 3 DCi/m. t- = the ' skin ' dose ~ factor 'due to beta emissions for each L i identified noble gas ' radionuclide "i," ' arem/ year /pCi/ - 3 m. M- = the air dose factor due to gamma emissions for each i identified noble gas radionuclide "i," mrad / year /pci/ . (-' l' 3, = the constant for each identified noble gas radionu-Vi clide 'fi" accounting for ' the gamma radiation from the elevated finite plume, mrem / year /pci/sec. ) = the constant for long-term releases (greater than '500 Bi hrs / year) for each identified. noble gas radionuclide " i" accounting for the gamma radiation from the ele-vated finite plume, mrad / year /uCi/sec. i 1.1 = the ratio of the tissue to air absorption coef ficients - over the energy range of the photon of interest, mrem / l 1 mrad. Q, =. the release rate of noble gas radionuclide "i" in gas-i ' eous ef fluents from free-standing stack, pCi/sec. 1 l ~ Qy = the release rate of noble gas radionuclide "i" in i gaseous effluents - from all vent releases, pCi/sec. (X/Q), = the highest calculated annual average relative concen-tration for any area at or beyond the unrestricted 3 area boundary for elevated releases (sec/m ), I- ] 2-14 i j

(X/Q)y = the highest calculated annual average relative conc en-tration for any are:a at or beyond the unrestric{ed area boundary for ground level or mixed mode releasas (sec/m3), 0.5 = an administrative value used to account for releases from BVPS-2, assuming simultaneous releases from BVPS-1. i At the. Beaver Valley Power Station Unit 2 (BVPS-2) gaseous 1 l releases may occur from: l I 1. the Elevated Release Vent atop the containment dome 2. the Ventilation Vent atop the auxiliary building t 3. the Process Vent atop the BVPS-1 cooling tower 4. the Turbine Building Vent j I + 5. the Condensate Polishing Building Vent l 6. the Decontamination Building Vent 7. the Waste Gas Storage Vault Vent ( Effluent 'from the Elevated Release Vent are assumed ground level in nature. The source of these releases is normal j auxiliary building ventilation. It is also possible to release containment purges from this vent. The Ventilation Vent Rele ases are ground level in nature and the sources of these releases are containment purges. The Turbine Building Vent relect, is ground level in nature and the source of this release is the turbine building ventilation. Release points 5, 6, and 7 above are not normally radioactive release points. The Process Vent releases are elevated and the sources of these the main condenser air ejectors and the waste gas releases are decay tanks and containment vacuum. Noble gas releases may normally occur from release points 1 through 4 above. To show compliance with BVTS 3.11.2.1.a, Expressions 2.2-1 and 2.2-2 are now expressed in terms of the actual ' release points for the BVPS-2. Note that the expressions for the nonradioactive release points 5, 6, & 7 are .ncluded for use if radioactive releames via these release points are ide.ntified in the future. For the total body dose: ( 2-15

UL ,f , 5) +EK((X/Q)cv9i + (X/Q)yy Qi (X/4)tv O - + + EVQiii ii i pv-cv vv tv )<250 mrem /yr - ( X/Q)cp i + IX/9)dy i + (X/9)wv i cp. dv wy (2.2-3). .For'the skin dose: 1.1B )h + E (1.i+ 1.1M{)((X/Q)cv i i i i + (X/Q)yy i + E (h ( X/Q)py+ i i cv vv 1 pv l (X/Q)tv Qi + IX/Q)cp.Qi + (X/Q)dv 9i + (X/Q)wy Qi ).<1500. mrem /yr tv cp dv wv (2.2-4) where: ' release rate of radionuclide' "1" fron the Process Q_ = ipv Vent ', pCi/sec. release' rate of radionuclide "i" from - the Elevated. -.I Qi = cv Release Vent, UCi/sec. release rate of radionuclide "i" from the Ventilation Qi = .vv Vent, pCi/sec. release' rate of radionuclide "i" from the Turbine Qi = tv Building Vent', UCi/sec. release rate of radionuclide "i" from the Condensate Qi = cp Polishing Building Vent, pCi/sec. release rate of radionuclide "i" from the Decontamina-Qi = dv tion Building vent,.pCi/sec. release rate of radionuclide "i" from the Waste Gas Qi = wv Storage Vault Vent, pCi/sec. (X/Q)py highest calculated annual average relative concentra- = 3 ' ): tion for releases from the Process Vent, sec/m. 2-16 i

q-(X/Q)cy = highest calculated annual av erage, relative concentra-tion for releases from the Ele *ated -Release Vent, 3 sec/m, (X/Q)yy " highest calculated annual average relative concentra-3 . tion for releases from the Ventilation Vent, sec/m. (X/Q)tv = highest calculated annual average relative concentra,, tion for releases for the Turbine Building Vent, 3 sec/m, calculated annual average relative concentra- - (X/Q)cp = highest tion ~for releases for the Condensate Polishing Building Vent, sec/m3, - (X/Q)dv = highest calculated annual aver age relative concentra-tion for releases for the Decontamination Building 3 Vent, sec/m, ( .(X/Q),y = highest calculated annual average relative concentra-tion for'. releases for the Waste Gas Storage. Vault ) 3 Vent, sec/m. All other terms remain the same as those defined previously. For BVPS-2, four potential modes of release are possible. The release edes identify the various combinations of sources of , radioactivity and their velease points which/ are used. to determine the controlling toc at ions. They are presented in Tab 2.2-1. For Modes 1, 2, and 3, the controlling location for implementation of BVTS 3.11.2.1.a is 0.35 miles. NW of Unit No. 2's containment building edge. Inserting the appropriate x/Q's from Tables 2.2-4 through 2.2-10 for this location, Expressions 2.2-3 and 2.2-4 become: / For the total body: + 7.35 x 10-5

• E V h;pv+ E(K;(9.24 x 10-5 h

+ 1.03 x 10-4 h + gt icv vv tv. 3 ) l 9.24x10-5h +9.24x10-5hg +7.35x10-5h ) < 250 mrem /yr i i 1 dv wv cp ) (2.2-5) i 2-17

f For the skin: + I (L + 1.1M )(9.24 x 10-59 + I;(7.0 x 10-10L +1.1B)Qi t i i t cv pv + 7.35 x 10-5 g. + 9.24 x 10-3 Qt 1.03 x 10-4Qi dv + vv tv 9,24 x,10-5 Qy + 7.35 x 10-5 qi -) < 1500 mrem /yr wv cp (2.2-6) For the release Mode 4,. the controlling location is 0.75 miles N. Inserting the appropriate x/Q's from Tables 2.2-4 through 2.2-10 for this location, Expressions 2.2-3 and 2.2-4 become: For the total body: +EK(3.95x10-6 Q + 4.99 x 10-6.Q + 4.26 x 10-6 q I 'E V Qiii ii + 4.26'x 10-6 Q )<250 mrem /yr +3.95 x 10-6Q + 3.95 x 10-6 q dv vv cp (2.2-7) For the skin: E (L + 1.1M )(3.95 x 10-69 , 4,99 x to-6q E;(2.31 x 10-6L+1.1B)Qi + i t i vv t cv pv + 4.26 x 10-6 qt ) 3.95 x 10-6 Qi + 3.95 x 10-6 + 4.26 x 10-6 Q Q +dv i we cp tv < 1500 mrem /yr (2.2-8) The determination of con. trolling location for implementation of BVTS 3.11. 2.1. a for noble gases is a function of the foll.owing parameters: ( 2-18 i

l. radionuclide mix and their isotopic release rate ( 2. release mode 3. meteorology. The incorporation of these three parameters into Expressions 2.2-3 and 2.2-4 resulted in the expressions for the controlling locations as presented in Expressions 2.2-5 through' 2.2-8. The radionuclide mix used to determine controlling locatiens was based upon source terms calculated with the Stone & Webster Engineering Corporation computer, code GASIBB which is similar to the NRC CALE code with inputs based upon the present operat-presented in Appen-ing mode of BVPS-2. The GAS 1BB inputs are dix B. The source term is presented in Table ' 2.2-2 as a func-tion of release type and release point. The X/Q values utilized in the equations for implementation of BVTS 3.11.2.1.a are based upon the maximum long-term annual average X/Q in the unrestricted area. Table 2.2-3 presents the distances from the release points to the nearest unrestricted area for each of the 16 sectors as well as to the nearesc vege-table garden, cow, goat, and beef animal. Tables 2.2-4 through 2.2-10 present the long-term annual average (X/Q) values for the Process Vent, Elevated Release Vent, Ventilation Vent, Turbine Building Vent, Decontamination Building Vent, Waste Gas ] I Storage Vault Vent, and the Condensate Polishing Building Vent ] release points from BVPS-2 to the special locations presented in Table 2.2-3. A description of their derivation is provided in Appendix A. For each release mode, the two or three highest site boundary utilized in ecmjunction X/Q values for each release point were with the radionuclide mix and release rate for each release point to determine the controlling location. Since elevated releases occur from BVPS-2, their maximum X/Q value may not decrease with distance (i.e., the site boundary may not have the highest X/Q values). Therefore, long-term annual average X/Q values were calculated at the mid point of the 10 standard distances as given in Tables 2.2-4 through 2.2-10. The highest two or three X/Q values for each release point at a distance greater than the site boundary wre used in conjunction with tne radionuclide mix to determine the controlling location. For each release mode, a particular combination of release point nuclide mix and meteorology dominate in the' determination of the controlling location. For Release Modes 1, JJ, and7/r, the controlling receptor location is at the site boundary. The respective dominapt release point is the Elevated Release Vent. For Release Mode 7, the controlling receptor location is at a distance greater than the site boundary. The respective k 2-19 k

t dominant release point is r.he Ventilation Vent. Neither of the (' controlling receptor ocations are presently inhabited. M, which were used is the deter- .md K,'Li Values for i i mination of the controlling receptor location and which are to be used by BVPS-2 ir. Expressions 2.2-5 through 2.2-8 to show compliance with BVTS 3.11.2.1.2, are presented in Table 2.2-11. Values taken from Table B-1 of - NRC Regulatory Guide 1.109, Revision 1, were multiplied by 106 convert picocuries 'to to microcuries for' vee in Table 2.2-11. for the finite plume model.can be ~ Values. for vi and Bi expressed as shown in Equation 2.2-9 and 2.2-10. Values were calculated using the NRC code RABFIN at the site boundary $.oca-tion which would receive the highest total dose from combined Process Vent, Ventilation Vent and Turbine Building Vent and Elevated Release Vent releases. These. values are presented in Table 2.2-12 and calculated from the following relation: fik Agiu,E 1 7 K B.'= III 1 .rd jk1 "j i where: I' = the results of numerical integration over the plume spa-tial distribution of the airborne activity as defin.:d by the meteorological condition of wind speed (uj) and -1 parcicular wind atmospheric stability class "k" for a direction. K ,= a numerical constant representing unit conversions. 3 250 mrad (radians) (m ) (transformation). 16 sectors _ sec(Mev>lG1) IA radians 10-6 [ x 3.15 x 107 yC. mrad (m ) (transformation)/yr(Mev)(pci). 3 4 = 2.1 x 10 = the distance from the release point to the receptor loca-rd tion, meters. = the mean wind speed assigned to the jth wind speed class, u) meters /sec. ] fjk = the joint frequency of occurrence of the jth wind speed class and kth stability class (dimensionless). number of photons of energy corresponding to the ich Agi = the energy group emitted per transformation of the ith radio-nuclide, number / trans f ormation. j [ 2-20 i

1 1 l i \\ [ Et = the energy. assigned to the Ith energy group, Mev. n the enirgy 'absor coefficient in air for photon energy l't, meters gtion p, J J The Vi factot is computed with conversion from air dose to i tissue depth doce, thus: j D 1 t f Atip,E 1 -p TTd I K ik 1 e y,, g,3 g3 Clg (2.2-10) f 1 rd "j l l 'where: 1 =.the tissue energy absorption coefficient fcr photons. of UT E, em /gm. energy t taken to represent the total = the tissue densitg) thickness T d body dose (5gm/cm m l':, 1.1 = the. ratio of the tissue ' to air absorption' coef ficients l over the energy range of photons of interest, mrem / mrad. -l j 9 ? S.2 -Ra'dioiodine and Particulates 3 i The dose rate in unrestricted areas resulting from the of / inhalation of I-131, tritium, and all radionculdies in particu-if y) 1ste form (excluding C-14) with half lives 'greate than 8 days released in gaseous' effluents shall be limited to 1,500 mrem /yr - to any organ. Based upon NUREG-0133, the following basic ex-1 pression is used to show compliance with BVTS 3.11.2.1.b: 1 s i i ig((X/Q),Qi, + (X/Q)yQiy] < 1,500 mrem /yr x 0.5 (2.2-11) EP where:

3 Pg7 = dose parameter for any organ T for each identified radio-nuclide "i", mrem /yr per pCi/m3; i

Qi, = the release rate of radionuclide "i," in gaseous efflu-j ents from elevated releases, pCi/sec. 1 i Qy the release rate of radionuclide "i" in gaseous effluents = i from ground level releases, pCi/sec. i (X/Q)s = the highest calculated annual average relat ive concen-tration for any area at or beyond the undrestricted 3 area boundary for elevated releases, sec/m ; 'k i t 2-21 2

i 3 l1 '[ (X/Q), = the highest calculated annual average relative concen- [ 'tration for any area at or beyond the unrestricted 3 area boundary for ground level r'eleases, sec/m - an administrative value used to account for simultane-0.5 = ous release from BVPS-1 and BVPS-2. Releases may occur from any of the BVPS-2 vents in the release - modes listed in Table 2.2-1. 'To show :ompliance 'with BVTS. 3.11.2.1.b, Expression 2.2-11 is now expri.ssed in terms of the actual release points for BVPS-2: h + (X/Q)yyh + (X/Q)tv i i7((X/Q)pyh pv cv i i + (X/Q)cp i + EP i + (X/Q)cy i vv tv cp ( X/Q) dv.9i + (X/Q)wyQi -) < 750 mrem /yr (2.2-12) dv y 't where: (X/Q)py = highest calculated annual average relative concentra-3 tion ' for teleases from the Process Vent, sec/m ; (X/Q)cy = highest calculated annual averaFe relative concentra-tion for releases from the Elevated Release Vent (con- ~ 3 'tainment vent), sec/m ; (~X/Q)yg highest calculated annual average relative concentra-3 tion for releases from 'he Ventilation Vent, sec/m ; (X/Q)c; highest calculated annual average relative - concentra-tion for releases from the Turbine Building Vent, 3 sec/m. (X/Q)cp highest calculated annual average relative concentra-tion for releases from the Condensate Polishing Build-3 ing Vent, sec/m ; (X/Q)d; highest calculated annual average relative concentra-tion for releases from the Decontamination Building 3 Vent, -sec/m ; { (X/Q),p highest calculated annual average relative concentra-tration for release from the Elevated ' Release Vent 3 (containment vent), sec/m ; 2-22

.( Qi long-term release rate of radionuclide "i" from the = pv Process Vent, i i/sec; Qi long-term release rate of radionuclide "i" from the = cv Elevated Release Vent (Containment Vent), pCi/sec; I Qi long-tern release rate of radionuclide "i" from the ~ vv Ventilation Vent, pCi/sec; ( ( ) Qi long-term release rate of radionuclide "i" from the l = tv Turbine Building Vent, pCi/sec; i I Qi long-term release rate of radionuclide "i" from the = cp Condensate Polishing Building vent, pCi/sec; ' ) l Qi long-term release rate of radionuclide "i" from the = dv Decontamination Building Vent, pCi/sec; Qi long-term release rate of radionuclide "i" from the = ( wv Waste Gas Storage Vault Vent, DCi/sec; All other terms are the same as th;se defined previously. The Condensate Polishing Building Vent, Decontamination Build-ing Vent, and Waste Gas Storage Vault Vent are not normal radi-oactive release points. These release points are included only for use if radioactive releases via these vents a,re identified in the future. In the calculation to show compliance with BVTS 3.ll.2.1.b only the inhalation pathway is considered for BVPS-L i were calculated Values of the organ dose parameters, Pi T using methodology given in NUREG-0133. For the child age group, the following equation was used for all nuclides. The Pi, values are presented in Table 2.2-13. l T 9 = 3.7 x 10 DFAg (2'. 2-13 ) Pi .k 2-23 -__)

where: ( 3 9 = breathing rate of child (3,700 m /yr) x unit con-3.7 x 10 vers.on factor (106 pCi/pci). = the organ inhalation dose factor for a child from DFAi Table 6 of USNRC NUREG-0172, Nov. 1977, for organ t, nuclide "i", in units of mrem /pCi. For relcase modes 1 througi 4, the controlling location is the site boundary, 567 meters IM. Expression 2.2-12 becomes: (7.00x10-10 Q + 9.24 x 10-5 Q + 1.03 x 10-4 Q + 7.35 x 10-5 E P i i T pv cv vv + 7.35 x 10-5 Q + 9.24 x 10-5 Q + 9.24 x 10-5 Qi )<750 mrem /yr Qi (2.2-14) The determination of the controlling location for implementation of j BVTS 3.11.2.1.b for radioiodines and particulates is a function of the same three ~ parameters as for noble gases plus a fourth, the actual ( receptor pathways. The incorporation of these parameters into Expres-sion 2.2-12 results in the respective equations for each release made at the controlling locations. 7ae radionuclide mix was again based upon the source terms calculated using the GAS 1BB Code. GAS 1BB inputs are presented in Appendix B. The mix and the source terms are pre-sented in Table '!. 2-2 as a function of release type and release point. f In the determination of the controlling site boundary for each release mode, the highest two site boundary and actual receptor X/Q values for each release point were utilized in conjunction with the radionuclide mix and the release rate for each release point to determine the con-trolling location. The P.; values are presented in Table 2.2-13. 7 The X/Q values in Expression 2.2-14 were obt ained from Tables 2.2-4 through 2.2-10. A description of the derivation of the X/Q and the D/Q values is pro-vided in Appendix A. ( 2-24 t i

f TABLE 2.2-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY POWER STATION UNIT 2 VENTS FOR IMPLEMENTATION OF 10 CFR 20 Release Point Mode 1 Mode 2 Mode 3 Mode 4 BVPS SVPS-2 Main Cond. Same as Same as Same as 2 Process Vent (pv) Air Ejector, Mode 1 Mode 1 Mode 1 and Containment Waste Gas, Containment Purge Vacuum. I Turbine Same as Same as Same as BVPS-2 Turbine Bldg. Vent (tv) Building Mode 1 Mode 1 Mode ! Exhaust -~~ ~~~ I Containment ~~~ BVPS-2 Ventilation Vent (vv) Purge BVPS-2 Elevated Aux. Bldg. Same as Same as. Same as 1 Release (Contain-Ventilation Mode 1 Mode 1 and Mode 1 Containment ment Vent) (cv) Purge { 1 l BVPS-2 Condensate Polishing Bldg. Vent (cp) BVPS-2 Decontam I ination Bldg. Vent (dv) I BVPS-2 Waste Gas Storage Vault Vent (wv)

• Not normally a radioactive release point IContinuous ground level meterology is applicable 2 Continuous elevated meterology is applicable

( 2-25

g ^ ) e m v r 0 i s e 22 1 0 0 t uem f 00 0 0 + cot e - + + E' EE E E 0230003020000000000000000000 a est t ) osa s r t R i aWy o 200O8080000000000000000070 n Y dG S h 01 m / a S e I R ( V C s ( s e 2 c T T s o I N t p ) r N E nm m P 43622052644657556667866 U V eu r 431 mP e 00000000000000000000000000 ro N S n T EEEEEEEEEEEEEEEEEEEEEEEEEE O S im 7928013294932754746496769400 I E au g t A O nc o 3377531 21 4161 42841 1 741 364800 n T C t u n e T R . oa L V S P CV ( e s R a EW e l O P r ) e /o m R Y rt r 1 001 02211 1 01 1 2 2 E ec e 00000000000000 0 d L ns e T - + + - + - - - + - + - - - e L i nj EEEEEEEEEEEEEE E A aeE g 72624706308361 00000000000000 t av V Md n 8278522216203000000000000 e nr o 211 R oi L l E CA ( E VA r 2 E o B t 2 n 6 E e 2 m+2 H T V E 2 L M n B O n ) o A R t o m i T F n gi r 54444555354554 4 t ee ent e 00C00000000000 0 a S nV ni a T - - - - - - - - - - - - - - l EEEEEEEEEEEEEE2149217507000000000000 E i T i idl t bli g 9 7 3 1 5.l N b n U ud uun o 31 21 311 832429608000000000000 E rg rit n e L Tl iB e L V F B V ( F a i E v SU d O t e E n n ) g m r S d e y o m A eV r gi r 1 00001 1 11101 03 3 44455644 G t ant e 00000000000000 0 00000000 u ae iia T - + + + + - - - + - + - + - p R vs ldl EEEEEEEEEEEEEE E EEEEEEEE l 6070007 80308000 e O ea ili g 295382396251 b El uun o 4121 311833421 4060062161 21 300 F l e xit n n X e AB e L a I R V ( c M t n E e D m I L ) n C t n m ia U ngo r N eni e 521 63 1 11 1 5 6 2223342201 O mit T 00000 000 0 0 0 0000000000 t I nd a - - + - - - - + - - - - - - - - + + n EEE E E E EEEEEEEEEE o D il l t EEEEE C 02640400706005425702805 04.l. 3. l. A aii r R t ut o 2 nB n h 416540778020020200732713231 o e S C V ( e e MM M 47 1 335578 d MM 234580499033 1 i 35578933333331333335655891 1 44 c - - - - - - - - - - - - - 1 1 1 1 1 - - - - - - -. l 8888881 11 1 1 1 1 u RRRRRREEEEEEE - - - - - OONERRSS - R m N KKKKKKXXXXXXX1I 1I 1CCMFSSCCCA ~. _a

lIl l! s de 51 02 201 8 3693 5033 t 9696 2562 2636 3985 gn 2,4,7 5, 9,6,9,6, 4,4,4,4, 6, 5, 3, 2, i a n e 22 1 1 1 1 1 21 22 3311 d t v l e l i d E u i B e d 7988 6752 931 1 6523 s S R n 2300 5733 822 0 5034 tn E u 5,6,7 7 7 5,8,4, , 2, 2, 3, 5,6,4,1 1 e r 22 1 1 1 21 22 3311 m U o ~ n L G i A a V t / e 956 0904 7 028 601 4 n Q d t t 1 02 01 26 8630 6967 o C 2,6,4,9, 4,5,6,6, 1,5,4,7, S 9, 6, 5, l a A m e 327 41 31 2222 4343 2 L a v U i l A N n E S N A P t d 281' 5790 37 46 8509 V A R a n 544 6797 511 4 8075 B O e u 1 8,7,' - 2,5,2,7, 2,3,4,4, 0,6,5,9, d g r 427 41 31 2222 4343 n n F M o a i ) G d l S 1 R i T e 8 3 5~1 0986 90 722 S u E d E t 1 347 0946 51 036 P B V - 8,2,- - 5, 8, 2, B g 4,0,5,6, 2,8,8,1 M a n ( t v a e 4606 4250 53 205 21 1 e y i S o l 2 h .r h 1 T G E t ra s N ed i O l d 1604 5597 63 940 nwn l I k P i n 5762 6627 1 9 245 eou o eTo P - 6,9,- - 5, 9, 4, w b M u 6,2,7,8, 2,8,7,9, S r 4606 4259 52 205 t g es E o 21 1 ene tt A G 2 bit an li si EL t os no E d no ep 3 R e 6 8 84 90 1 51 t 2 9 44 39 4 92 iC o d 2 O a - - 5, - 9, - 8, 2, 5, 5, - 3, 15, - - o t ne p1 os 7 2 o e 7 6 55 33 5 54 r-e Ca 2 T w v eS s e S C l t P a .dl 2 m E R E nV e sne L O k_ eBl t ar A P i d 1 5 93 77 2 88 c e n B T l T E M n 4 6 25 44 8 1 3 er i gd 0, - 7, 0, 3, 3, - 1, , 5, - - eh onn 1 . pi u C u - - 7, htd t nt d o E o R r 7 7 55 33 5 54 munel r G mooesi g L orrV au A rf g eB r f sl e U n d D e e 31 18 291 3 2093 5055 I d t 2605 21 63 7636 391 8 d rs eeh d eoernt 4,4,9 6, 9,6,9,9, 3,5,4,4, 6,5,4,2, erf c io V r a D G e 22 1 11 1 1 3222 331 1 ru orb I a v 'u s t rerl N l sanPh ul I e E aee t TA l emmeo U a d 3444 9758 871 1 6544 m ih M b M t n 2027 7733 31 20 5066 eatl)) ert l1 2 6,7,7 6, 9,5,8,7, 1 3,2,3, 5,6,4,4, ranoa(( I e u A e r 22 1 11 1 1 3222 331 1 a ot X g o ec o M V G ss et : ea2l s se b ee G 1 620 al t al s N d I e 3274 1 252 4640 T t 1 3 2_9 571 1 5276 8782 eeicb a 6644 l rniae I a 4633 5689 0,2,5,6 e Ul cl M y v rd pi e 1 1 1 I r e ef pl r L a l d t oap d E na pd F n uvesan o 9228 671 2 7491 01 78 o e gi u O u S B ) 7944 4006 8636 4065 rl d so 6755 geeeir E 2 5744 5677 8 0,4,5 s g C e d ( mmmae 1 1 N t n oooesy A i u rrrl ar fff eea T S o S r 0500 5555 0555 5055 rl d I G ) 7399 4775 57 39 81 54 6866 s s s en D 1 6544 5556 89 4, 5 eeed ru ( c c ce o 1 nnntdb aaaan t t t vue r s s s eot o E iiil ri wnc E E E E W W W W T DDDEGS nd t oie NEN SES SWS NWN O DwS NNNE EESS SSSW WWNN N

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8636 2146 4209 1006 t t_ r t r 50 2520 7565 8080 5276 01 13 5265 45 21 11 0000 1 1 S s N I 0000 9285 9000 0000 O T 05 6356 5166 991 2 6006 A 6842 8676 91 16 4245 ) O 21 11 0000 01 23 6496 C 44 ? 1 1 3 L m cO s 0000 0513 0000 0000 / L eR e 50 891 8 4130 0895 5005 4198 0898 2576 67 23 sT l 7 O m 3211 1000 1 1 24 7088 N i 34 22 - C 0 n E 0000 0007 0000 0000 1 D i 05 4974 0269 9439 2000 ( C n 2633 3019 4946 3001 xT SL i 4222 11 10 1 135 9540 E o 33 231 EE t US a AD o '2 4 5 4 3371 0872 0000 L c 7235 VN L 50 8450 8474 1 4 3.'7 Q l 23 5333 1 1 11 2247 1 1 23 A 1 341 /) o t3 r ,2 n 8014 9 5 1'1 4350 0000 t L o 05 6681 4949 8383 4606 V 22 7444 21 21 2350 5057 E2 C EE e 1451 1 LL h nA 0290 5040 1 040 0000 B t NT o 50 8697 6153 1 896 0282 ON 12 1665 3333 4494 1 996 U t 1 3572_ RI s 1 + G e ,E n 0005 8696 7300 0000 D c EI a 7865 0184 7815 01 08 GF t 05 AI s 8019 6555 6763 9230 1 2 4924 RT i 11 1 1 1 - 1 4 EN D VE 7500 5928 0004 AD 2 I 5864 8 2 T 9618 5022 7999 3326 2 .( 50 E US O1 3221 1111 1124 0068 m A 2 1 22 L NE 9000 0000 C B A AN 0000 5192 T A ) T - 5 3803 9957 9003 5007 NI 0 3420 8566 9168 1914 TS 0 112 6275 ED 21 11 1 1 VL NI - e 0600 0201 1 000 0000 TA 6970 8393 7703 2 s. EC ic 51 1 NP ee 3792 2669 5939 5002 ME sn 111 1409 IS Rd 1 44 3 2 ATR OF t - 720 1240 7100 0000 m NO 5337 0754 C ail 242 9,975 u ena S MAm 661 1626 5627 3005 ( 1 1 1441 TE s NS r 0054 0042 00 000 EA o 1 62 VE t L p kt 6462 1 197 45 EE e l a 3021 9093 - 867 c C SR c i o A e MG 5200 1 300 19 1 81 EL R LE 0 7 40 00 0 00 RE a k 0 0 93 90 2 40 EV l 51 - - L u l w - 8 - 90 07 - 7 D d i o ED i MC 1 0 01 33 5 90 3 TN v AU i ~ ER n - n 0200 6208 0100 0000 VO d LG I - ee 8945 1 976 4393 7700 S gb r 2672 6666 3639 5043 E eld 11 1 496 2U eaa 1 41 1 - O VtG SU n VI 0208 5181 5830 0000 PN N t ny 5025 4174 7323 8742 BT ed O i ur 2508 5322 2226 7820 1 2493 C S oa 1 1 B R OF wncr E E E E W W W W nd - oieo NEN SES SWS NWN D wSt NNNE EESS SSSW WWNN / u

0000 61 61 '5 0 0 0 @ 1 ]5 @ 7378 7363 8700 4001 50 4620 7565 8093 0683 45 21 1 1 0000 01 1 3 6386 11 S 0000 3008 0000 0000 N 05 0209 8398 5638 6006 O 9952 8676 0228 0993 m I 44 T 21 11 0000 11 23 7517 1 2 AC L s 0000 0203 0000 0000 O e 50 1 283 7463 6762 4006 L l 8399 0898 2690 4434 O i 34 R m 321 1 1 000 11 25 8329 23 TN n ) C 9771 45 04 7769 0000 O i 05 6844 3020 5061 4756 3 mD n 1 1 11 1236 0891 / E o 33 4222 1 231 cT i eC t L c 2934 0948 361 9 0000 sE a 7 E o 50 5671 9484 2674 2418 0 23 6333 1 1 11 2248 3605 - S L 1 351 1 D l N o ( t 5991 1532 4080 0000 xA r ) n 05 7903 6050 0634 7560 E - C 22 8454 2222 3361 7861 S3 o 1 1 462 U2 L e V t 01 1 1 6953 8800 0000 A2 h E 50 7350 8275 4246 5002 / B t 1 2 3776 3333 451 6 6302 QL o 1 1 3703 1 1 xA ,T se EI n 0000 7978 6700 0000 LN c V a 7272 5539 5847 3008 ED t 05 LE s 2220 6565 7887 0042 1 2 6265 I i 1 1 21 11 11 DF D NI ON 9086 7957 3683 0000 UT N-5 RE 50 9240 71 33 0341 2904 I 01 4322 1 1 11 2236 3651 GD 1 231 2 ,( 2 E E AE 0000 0720 0000 0000 GS L RC - 5 6965 6667 7047 5001 B EN 0 A VA 0 7853 1 788 2404 1 1 20 21 1 1 1 11 23 7486 T AT 11 S LI U - e 0500 0470 8000 0000 AD NL i c 9924 8621 3974 0600 NA s n AI ee 5700 8770 6252 881 1 C Rd 1 65 3 1 21 2 1 47221 TE NP V t - 684 9489 0800 0000 ES R ail 002 9681 1084 7681 NO ena OF ham 771 1 727 6730 4878 1 2 1 441 I s T r 0090 0002 00 000 AS o I S p kt 8567 9038 58 224 LE t TA e l a 9122 9203 - 958 NE c i o EL e MG 5201 1 31 0 1 9 1 91 VE R R 2 l 0 8 00 00 0 00 - L a k 4 2 38 04 3 00 SE u l w - - 2 8 - 00 30 - 2 60 - - PV d i o VE i MC 1 0 1 1 34 6 05 1 3 BL v i N n n 0600 6471 5800 0000 D d U I - ee 0696 6624 6074 0604 O eld R gb r 5773 6777 3752 8823 1 2 1 468 G eaa 1 51 2 VtG S ^ O 0300 8031 8720 0000 U U ed N t ny 2220 7839 2861 5805 I i ur 5631 6332 3220 4934 2 3503 T S oa 1 1 1 1 N B OC R nd - O wncr E E E E W W W W F oieo NEN SES SWS NWN DwS t NNNE EESS SSSW WWNN

6000 07 66 5471 51 39 50 4070 0384 587 8 9389 8151 2765 6697 7765 45 01 1 1 1000 0000 0000 S N O 05 6000 0016 47 00 11 45 I 9981 831 4 705 2 5900 8787 T 44 9287 2886 781 9 ~ AC 01 1 1 1000 001 0 0000 OL L s 50 0000 0007 0400 0639 O e 0393 3683 1 361 2804 1 802 1 698 9 R l 34 2400 71 1 N m 1 1 22 1 1 1 0 101 1 1 000 e T i z O i ) i 0000 0000 0000 1 000 m C n 3 D 05 8782 9667 831 6 411 5 i 4786 1341 3024 71 20 xa mE cC o 11 22 21 11 11 11 01 11 m / T n 33 eE i s sL t Q E a 7 S c 50 1 982 3059 7674 4499 / o 9662 8208 4556 8864 X 0D L 23 1 233 2221 21 1 1 1 11 1 tn 1 NA l e ( ) r 6785 7098 71 7 6 0003 v x o 3 t 05 5237 6075 31 73 5539 t E2 o 22 2354 3322 3212 2221 n S - n e U C m L2 n VE h 2702 0856 81 23 8766 i A e 6069 a 2740 9115 t L t 50 3410 /A o 1 2 5576 6444 4333 3332 n QB o XT t c sN s 0000 0000 0000 0900 EI e 0000 0000 0000 0070 e S c 05 7838 6473 9330 381 2 r AD n 2922 81 59 4099 2010 e h LI t 86 7 7876 8444 6005 w EE a 11 EF s s 6 T D 0000 0000 0000 0900 n RI i 0061 0000 0000 0450 o EE 001 3 0004 1 000 2568 i DN TD 50 1 513 1744 51 98 7007 t 0 2 a 3 V( 01 3400 7279 8957 8006 c 2 AI o 2 E E 21 11 1 1 l L LS 9595 4800 0000 7245 y B EE A ,C 8763 2073 6007 4083 r 2101 1270 9008 1 201 a T N EA - 5 0000 0043 7113 0000 d GT 0 n RI 0000 0000 0660 0000 u AS 0 o 23 ED b V A - e 0055 0000 0000 0030 eN AL t LI ic 9952 0097 1205 9379 i AC s n 7805 3287 3893 4505 s UE ee NP Rd 6600 81 79 6534 2206 t 1 NS a A TO t - 741 7050 61 78 2371 s R 8602 0649 0568 e NF ail 21 6 u E ena s MAm 261 21 37 6333 221 1 l a V 1 S r v SE o EA p 0000 0007 20 354 Q SS t x CE e kt 1 357 7735 76 602 /Xx OL c l a 9437 8523 - 132 RE e i o PR R MG 1 1'01 241 0 02 000 tne - E a 0 0 00 00 0 60 V 2D l ST u k 1 4 36 94 2 48 - 21 41 - 4 7 - - s 7 PA B l w - - 6 2 s VV i i o BE v MC 1 1 1 1 32 1 01 ec L i o n n 0040 0000 0000 0340 r E d S I - ee 2979 0099 61 05 9376 P U eld 7600 3683 7693 4504 O gb r U eaa 66 9 81 77 3334 2206 1 N Vt G I _ e TN 2000 0000 O ed 881 1 6256 0006 9378 C t ny 0211 3470 4402 2300 i ur 0000 0002 7651 0000 R S oa O B 0000 0000 5760 0000 F -nd - wncr E E E E W W W W oieo NEN SES SWS NWN DwS t NNNE EESS SSSW WWNN ~

0000 5482 6000 0000 8957 3257 6450 9008 50 3520 7565 8082 7979 ^ S 45 21 11 0000 01 13 5275 1 1 NO T 0000 11 96 0000 0000 I A 7787 7277 2375 6005 C 05 7842 8676 0217 7069 w L 44 211 1 0000 11 23 65 u6 O 2 1 L 0000 O s R e 0000 0958 0000 s T l 4550 6241 3273 402 8 N i 50 6299 0898 2688 0018 _C 34 3211 1000 11 24 8208 _O m 23 ) n 3 D i 5828 2382 3043 2000 mE cC n 05 4743 3010 5059 8768 / T sL i 33 4222 11 11 1235 9660 eE o 231 E t 7 S a 0D o 5649 7615 7749 0000 c 1 N L 50 1 560 8484 1 550 4696 A 23 6333 1 1 11 2248 2354 x l s 1 341 g () o 3 r E2 n 8953 5077 4600 0000 S - t U o 05 1 792 5049 9418 5232 A 22 8444 2221 2360 6409 L2 C 1 1 461 VE e L h /A 0445 5941 9300 0000 QB t XT o 50 7928 7164 2046 5489 ,N 1 2 2675 3333 4305 3588 t 11 3682 LI s 1 E e EE n 0009 2621 3100 0000 VD c 3317 1323 9009 8 LI a 541 F t 05 DI s 01 29 6565 7875 3405 12 5044 NT i 1 1 211 1 1 UN D 7 OE 61 67 6326 0000 RD GI 6804 1 2 2839 61 22 81 13 1894 3 ( 50 ^. ES 01 4221 1111 1 235 1 1 72 2 1229 2 ~ E GE L AC 0000 A EA 0000 2852 0000 B RN T VT - 5 AS 0 41 25 9534 9041 6007 I 0 4631 9677 0270 31 25 11 13 6375 2111 11 LD AUL NI - e 0400 0569 7000 0000 NA 'AC ic 8683 7206 2988 9504 E

s. n TP ee 4736 5779 6040 6429 29

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54 3 21 2 1 E VR GF t - 433 8556 0300 0000 ~ O N ail 782 9289 0711 9590 ena DS MAm 661 1 726 6639 3437 I, 11 1441 LE s I S r 0080 0004 00 000 UA o L p kt 4368 8028 05 702 BE t E' E e l a 7122 9103 - 818 NR c i o I e MG 5201 1310 1 9 1 91 B L' R 0 9 00 00 0 00 RE TE a k 3 2 27 19 1 00 UV l L u l w - 8 - 00 38 - 0 5 - - 1 2 d i o - D i MC 1 11 33 6 02 1 3 SN v PU i 0000 VO d BR n n 0700 9566 4300 G I - ee 0392 4201 6788 9500 eld S gb r 4713 6777 3640 6461 1 2 1 41 7 U eaa 1 51 2 O VtG UN I T ed 0061 7180 771 0 0000 N t ny O i ur 5264 071 4 2949 4457 C S oa 0098 6343 3225 6034 1 2472 B 1 1 R OF -nd - wncr E E E E W W W W oi e o NEN SES SWS NWN DwSt NNNE EESS SSSW WWNN 6m

0000 67 93 8000 0000. 8636 2146 4209 5006 50 2520 7565 8080 5276 45 21 1 1 0000 01 13 5265 1 1 S NO I 0000 9285 9000 0000 T 6356 5166 991 2 6006 A 05 6842 8676 9116 4245 s CO 44 21 11 0000 01 a.3 6496 1 1 L L O s 0000 0513 00n0 0000 R e 8918 41 30 0895 6005 T l 50 41 98 0898 2576 6723 N i ) O m 34 3211 1000 1 1 ^.4 7088 22 3 C m n /D i cE 0000 0007 0000 0000 4974 0269 9439 2000 eT sC n 05 2633 3019 4946 3001 E o 1 1 1 0 1 1 35 9540 7 L i 33 4222 231 E t 0S a 1 c

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2454 3371 0872 0000 xN L 50 8450 8474 1 437 7235 ( A l 23 5333 1 1 11 2247 1 1 23 1 341 S) o E3 r U - t L2 n 8014 951 1 4350 0000 A o 05 6681 4949 8383 4606 V2 C 22 7444 21 21 2350 5057 1 1 451 QE e / L h XB t A 0290 50.40 1 040 0000 ,T o 50 8697 6153 1 896 0283 L t EN 1 2 1665 3333 4494 1 996 1 3572 VI s 1 E e LD c E n 0005 8696 7300 0000 DI a 7865 0184 781 5 01 08 NF t 05 UI s 8019 6555 6763 9230 12 4924 OT i 1 1 111 1 RN D 8 GE D ,I 0000 0000 0000 0000 E( 5864 7500 5928 0004 2 s 2 3 AS 9618 5022 7999 3326 2 G 50 E RE 01 3221 11 11 1 124 0068 2 1 22 L EC B VN 0000 A AA T T 0000 51 92 9000 0000 LS 5 AI 0 3803 9957 9003 5007 UD 0 3420 8566 9168 1 91 4 N 21 11 11 2 6275 1 1 NL AAI - e 0600 0201 1 000 0000 6970 8393 7703 2 i c 51 1 GC NE s n IP ee 3792 2669 5939 5002 DS Rd 1 44 3 111 1409 2 LI R UO BF t - 720 1 240 71 00 0000 ail 242 9975 5337 0754 ena NOS MAm 661 1626 5627 3005 11 1 441 I E s TS r AA o NE t 0050 0042 00 000 IL p kt 6464 1 1 97 45 1 62 ME e l a 3022 9093 - 867 AR c i o T e MG 5201 1300 19 1 81 NL R OE 7 40 00 0 00 CV l EE a k 0 0 93 90 2 40 51 - - DI u l w - 8 - 90 07 - 7 d i o 2D i MC 1 0 01 33 5 90 3 - N v SU i PO d VR n n 0200 6208 01 00 0000 BG I - ee 8945 1 976 4393 7700 el d S gb r 2672 6666 3639 5043 1 1 1 496 U eaa 1 41 1 O VtG U N I 0000 0000 0000 0000 T ed 0208 51 81 5830 0000 N t ny O i ur 5025 41 74 7323 8742 C S oa 2508 5322 2226 7820 1 2493 B 1 1 ROF -nd - wncr E E E E W W W W oieo NEN SES SWS NWN D wS t NNNE EESS SSSW WWNN I

0000 6793 8000 0000 8636 21 46 4209 5006 565 8080 5 2 7. G. 50 2520 7 45 21 1 1 0000 01 13 5265 1 1 S NO 0000 9285 9000 0000 T 6356 5166 9912 6006 I 6 4245 A 05 6842 8676 91 1 CO 44 21 1 1 000? 01 23 6496 1 1 L L ) O s 0000 0511 0000 0000 3 R e 891 8 4130 0895 6005 mT l 50 41 98 0898 2576 6723 cO m 34 3211 1 000 11 24 7088 /N i 22 eC s n 7 E 0000 0007 0000 0000 D i 497 4 0269 9439 2000 0C n 05 2633 3019 4946 3001 - T 1 E o L i 33 4222 1 1 10 11 35 9540 231 xE t ( S a S D o 2454 3371 0872 0000 c EN L 50 8450 8474 1437 7235 UA L l 23 5333 1 1 11 2247 1 1 23 1 341 A) o V3 r Q2 n 801 4 9511 4350 0000 t / o 05 6681 4949 8383 4606 x2 C 22 7444 2121 2350 5057 1 1 451 ,E e LL h VA 0290 5 0 4'0 1 040 0000 EB t ET o 50 8697 6153 1896 0283 L t 1 1 2 1 665 3333 4494 1996 1 3572 U s 1 DN e OE n 0005 8696 7300 0000 UD c RI a 7865 01 84 7815 01 08 GF t 05 I s 801 9 6555 6763 9230 1 2 4924 ,T i 11 1 1 1 1 EN D 9 GE y AD RI 0000 0000 0000 0000 m_ 2 E( 5864 7500 5928 0004 3 3 AS 961 8 5022 7999 3326 2 V 50 E E 01 3221 1 11 1 11 24 0068 2 122 L LC B AN 0000 A UA T NT 0000 5192 9000 0000 NS 5 0 3803 995 7 9003 5007 AI D 0 3420 8566 91 68 191 4 21 1 1 11 2 6275 1 1 TNL VI - e 0600 0201 1000 0000 EA 6970 8393 7703 C i c 511 2 TE sn LP ee 3792 2669 5939 5002 US Rd 1 44 3 1 1 1 1409 2 A VR = EF t - 720 1 240 71 00 0000 O G ail 242 9975 5337 0754 ena ARS MAm 661 1 626 5627 3005 1 1 1 441 OE s TS r SA o E t 0050 0042 00 000 SL p kt 6464 1 1 97 45 1 62 AE e l a 3022 9093 - 867 GR c i o e MG 5201 1 300 1 9 1 81 EL R TE SV l 7 40 00 0 00 AE a k 0 0 93 90 2 40 51 - - WL u l w - 8 - 90 07 - 7 d i o 2D i MC 1 0 01 33 5 90 3 - N v SU i VR n n 0200 6208 01 00 0000 PO d BG I - ee 8945 1 976 4393 7700 eld S gb r 267 2 6666 3639 5043 1 1 1496 U eaa 1 41 1 O VtG U ^ N ~ I 0000 0000 0000 0000 T ed 0208 51 81 5830 0000 N t ny O iur 5025 4 1 74 7323 8742 C S oa 2$08 5322 2226 7820 1 2493 B 1 1 R OF -nd - wncr E E E E W W W W oi e o NEN SES SWS NWN D wSt NNNE EESS SSSW WWNN e

0000 54@3 2 ]1 8957 3257 6450 9008 50 3520 7565 8082 7979 S_ 45 21 11 0000 01 13 5275 1 1 NO T 0000 11 96 0000 0000 I A 7 787 7 27 7 237 5 6005 7069 C 05 7842 8676 0217 m L 44 21 11 o00U 11 23 65 06 O 1 2 ) L mR e 0000 9958 0000 0000 3 O s / T l 4550 0241 3273 ^ 008 cN i 50 6299 0898 2688 0018 eO m sC 34 3211 1 000 11 24 8208 23 n 7 D i 5828 2382 3043 2000 - E 5059 8768 0T 1 C n 05 4743 3010 xL i 33 4222 1 1 1 1 1 235 9660 E o 231 ( E t S a ED o 5649 761 5 7749 0000 S c UN L 50 1 560 8484 1550 4696 A l 23 6333 1 1 1 1 2248 2354 LA 1 341 V) o 3 r /2 n 8953 5077 4600 0000 Q-t 5232 X o 05 1 792 5049 9418 C 22 8444 2221 2360 6409 ,2 1 1 461 LE e EL h EA 0445 5941 9300 0000 VB t LT o 50 7928 71 64 2046 5489 DN 1 2 2675 3333 4505 3588 t 1 1 3682 NI s 1 U e RE n 0009 2621 31 00 0000 OD c 1 323 9009 7 331 GI a 5418 F t 05 ,I s 01 29 6565 7875 3405 1 2 5044 ET i 11 21 1 1 1 0 GN D 1 AE EI 6804 6167 6326 0000 RD 4 2 2 A 2839 61 22 81 1 3 1894 3 V( 50 N S 01 4221 1111 1 235 11 72 1 229 2 E LE L AC A NA 0000 2852 0000 0000 B UN T NT 5 4125 9534 9041 6007 AS 0 I 0 4631 9677 0270 31 25 1 1 13 6375 21 1 1 TD 1 1 NEL I - e 0400 0569 7000 0000 VA GC i c 8683 7206 2988 9504 NE sn IP ee 4736 5779 6040 6429 DS Rd 1 54 3 21 2 1429 2 LIR BF t - 433 8556 0300 0000 UO 9590 ail 782 9289 071 1 ena NS MAm 661 1 726 6639 3437 G 11 1441 I E s HS r IE t 0080 0004 00 000 SA o LL p kt 4368 8028 05 702 OE e l a 71 22 9103 - 818. PR c i o e MG 5201 1 31 0 1 9 1 91 EL R AV l 0 9 00 00 0 00 TE SE a k 3 2 27 1 9 1 00 15 - - - 00 38 - 0 NL u l w - - 2 8 E d i o DD i MC 1 1 1 33 6 02 13 NN v OU i R n n 0700 9566 4300 0000 CO d 2G I - ee 0392 4201 6788 9500 eld SS gb r 471 3 6777 3640 6461 1 2 1417 PU eaa 1 51 2 VO VtG BUN ~ I T ed 0061 7180 7710 0000 N t ny O i ur 5264 071 4 2949 4457 C S oa 0098 6343 3225 6034 1 2472 B 1 1 R OF -nd - wncr E E E E W W W W oieo NEN SES SWS NWN DwS t NNNE EESS SSSW WWNN lllli

'1 ) 3 m / r i o C rt U 233434333323433 J000000000000 m Aa r 00 ic + + v+ + + +++++++++ F' ie EEEEEEEEEEEEEEE a N p 8596758 n.3 3 6 3 1 t e 87 09081 4034272 es r 89 s B o y D / 21 11 2171 11 72143 t d n a e r u m l ( f fe suo ) "3 e m s / a r i g ro C n it u 131344422233333 i Ac 000000000000000 a r + + + + + + + + + + + + + + + d aF ie EEEEEEEEEEEEEEE1 0 e m M p 3327233673621 t me 9 2 7 1.'5 7 6 5 2 5 3 9 5 2 3 ~ as' r c S R G o y 113331 1 99 e E D / 11 16l1 t T d e H a d r GU m e ( b A e D y a D m NA ta ) 1 S '3 h 1 E t S r m 5 A o / 2 G t i s 3 e 2 c C d 2 E a U 33334322223433 i E L F 00000000000000 l L B r ++++++++++ + + + + c - EEEEEEEEEEEEEE u B O e i e A N sL p 964616239 n 64371 43730279018216 o o T D r R i O y 1 42 11921749371 d F n / i m a S k e r R S r O a ro ( T f CA e F ra E S s, O ) r2 D - m o-t0 / r i c1 yo C a f x d t U 2233333 23134441 000000000000000 oc e6 B a r - + + + + ++++++++++ s5 F ie EEEEEEEEEEEEEEE o l K p 234 671276651421 d7 ae 516946515918488 t s r 1511192231 188 d= oo y e TD / 71 m t2 ~- s0 er i-m m lE 6 ( e5 h T7 w e u d mm m i l 1335578 mm c 355789033333331 u 1 11 1 1 1 4 n 88888891 o rrrrrrreeeeeeer KKKKKKKXXXXXXXA i da R

3. te I' TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES SEAVER VALLEY POWER STATION UNIT 2* ~ l 3 3 i,2 yi Bi l' Vg B Total Body Gamma Air Total Body Gamma Air Dose. Rate - ' Dose Rate Dose Rate Dose' Rate j Noble Gas mrem /yr mead /yr mrem /yr mrad /yr i Radionuclides pCi/sec. pCi/sec pCi/sec, 'pci/sec Kr-83m 3.19-10 1.75-8 4.58-8 3.96-5 l Kr-85m 7.81-5 1.16-4 4.70-4 7.06-4 Kr-85 1.55-6 2.35-6 5.54-6 8.40-6 Kr-87 5.13-4 7.74-4 1.45-3 2.19-3 Kr-88 1.39-3 2.09-3 4.09-3 6.16-3 Kr-89 7,99-4 1.20-3 1.25-3 .1.88-3 Xe-131m 1.64-5 2.47-5 1.67-4 3.09-4 Xe-133m .1.38-5 2.11 '1.32-4 2.61-4' l Xe-133 1.05-5 1.56-5 1.54-4 2.76-4 Xe-135m 2.41-4 '3.66-4 6.21-4 9.50-4. Xe-135' 1.41 2.12-4 6.96-4 1.05-3 Xe-137 6.00-5 '9.05-5 9.66-5 1.46-4 { '( .Xe-138 8.11-4 1.22-3 2.22-3 .3.34-3 Ar-41 l'.02-3 1.53-3 2.68-3 4.02-3 i

• The listed dose parameters are for radionuclides that may be detected in gase-ous effluents.

i values used to implement Modes 1, 2, and 3 of Section 2.2.1. I V - and. B i i values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1. 2 B i and B; values to implement Mode 4 of Section 2.2.1. 3 V ( 2-36 i

TABLE 2.2-13 f VALt.ES FOR A CHILD FOR BuAVER hLLEY-POWER STATION UNIT 2 Pi 3 .l (mrem /yr per.UCi/m )- l NUCLIDE BONE LIVER T. B'0DY THYROID _ KIDNEY LUNC GI-LLI 0.00E-01 1.12E 03 '1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 l .H-3 CR-51' O 00E-01 0.00E-01 1.54E 02" 8.55E Ol' 2.43E 01 1.70E 04 1.08E 03 MN-54 0.00E-01 4.29E 04 9.51E'03 0.00E-01 1.00E 04 1.58E 06 2.29E 04 s ~ FE-59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E.04 C0-57.- 0.00E-01 9.03E'02 ~1.'07E 03 0.00E-01 0.00E-01 5.07E 05 1.32E 04 CO-58' O.00E-01 1.77E 03 3.16E 03 0. 00'E-01. '0.00E-01 1.11E 06 3.44E 04. CO-60 0,00E-01 1.31E 04 2.26E 04 0.00E-01 0.00E-01 7.07E 06 9.62E 04 ZN-65 4.26E 04 1.13E 05 7.03E 04' O.00E-01 7.14E 04 9.95E 05 1.63E 04 l SR-89 5.99E 05 0.00E-01 1.72E 04 0.00E-01 0.00E-01 2.16E 06 1.67E 05 SR-90 1.01E 08 0.00E-01 6.44E 06 0.00E-01 0.00E-01 1.48E 07 3.43E_05 ZR-95 l'.90E 05 4.18E 04 3.70E 04 0.00E-01 5.96E 04 2.23E 06 6.11E 04 'NB-95 2.35E 04 9.18E 03 6.55E 03 0.00E-01 8.62E 03-6.14E 05 3.70E 04 NB-97 -4.29E-01 7.70E-02 3.60E-02 0.00E-01 - 8'.55E-02 3.42E 03 2.78E 04 g. MO-99 0.00E-01 1.72E 02 4.25E 01 0.00E-01 3.92E 02 1.35E 05-1.27E 05 TC-99 4.96E 02 5.51E 02 1.98E 02 0.00E-01 6 48E 03 1.25E 06 2.87E 04- .AG-110M-1.69E 04 1.14E 04 9.14E 03 0.00E-01 2.12E 04 5.48E 06 1.00E 05 SB-124 5.74E 04 7.40E 02 2'.00E 04 1.26E 02 .0.00E-01 .3.24E 06 1.64E 05 l SB-125 9.84F 04 7.59E 02 2.07E 04 0.10E 01 0.00E-01 2.32E 06 4.03E 04 .l 1 1-131. 4.81E 04 4.81b.04 2.73E 04 1.62E 07 -7.88E 04 0.00E-01 2.84E 03 CS-134 6.51E 05 1.01E 06 2.25E 05 0.00E-01 3.30E 05 1.21E 05 3.85E 03 CS-137 9.07E 05 8.25E 05 1.28E 05 0.00E-01 2.82E 05 1.04E 05 3.62E 03 ~BA-140 7.40E 04 6.48E 01 4.33E 03 0.00E-01 2.11E Ol' 1.74E 06 1.02E 05 LA-140 6.44E 02 2.25E 02 7.55E 01 0.00E-01 0.00E-01 1.83E 05 2.26E 05 l CE-141 3.92E 04 1.95E 04 2.90E 03 0.00E-01 8.55E 03 5.44E 05 5.66E 04 I CE-144 6.77E 06 2.12E 06 3.61E 05 0.00E 1.17E 06 1.20E 07 3.89E 05 l ] ~( 2-37 1

ecn 0000 0000 0000 9622 e 1 206 2882 3621 5429 d 5227 41 63 741 3 674.l' is 2311 4634 21 1 1 eR w l a 700 0000 0090 8685 2 mR t m 026 9904 1 479 1 484 T ai 796 - 2331 6091 5745 9 Q en - / MA 2 161 3 21 1 0S e 1 RH X 0 ,5 ) 1) Q 3 /> - 2412 0065 83 903 D 2 kt 7 21 0 9460 09 274. 2341 - 000 ( r 7 o2 l a 551 i o SRRE MG 1 2 EYL T/B ESA MRT AH s R N r A0I o P0 - t 5D p N E e 0 1 63 08 0 87 4 O>I c k 6 0 62 1 7 7 39 14 - - 1 I F e l w - 4 - 44 45 - 3 SSI R io 1 RET MC 8 2 ESN l 3 2 PAE a SED u 2 m E ILI d a L DE( i B .R v A T S i T NLE d EC n 'VVF I EA e SLT l S S b 0000 0000 0000 9650 EDI an 4288 2982 4421 5424 6748 CED t e 3220 4362 5013 OT ed RAL gr 2315 4633 1 1 1 1 1 PVA ea EI VG 2LCEE T P I SS NU UOR UO YNF EI LT LN y AO r 0360 0400 0000 7470 a 0761 7806 841 1 7244 d 6670 3900 7067 3443 VC RR en EO t u 1 1 17 521 1 1 VF io A SB EB m dn irwo nt wc E E E E W W W W oe NEN SES SWS NWN DS NNNE EESS SSSW WWNN s w

e ~ c n 91 00 0638 521 5 3301 e 1 1 42 7506 9426 2269 d m 2 i 2202 2333 1 422 1259 1 ^ s 33 2 m e R 9 -0 1 X ) Q / l D a 705' 0000 0000 0000 ( R t m 1 5 5 2607 6628 6399 8293 9290 T ai 984 - 0515 SQ en R/ MA 1 1 31 2 1 1 1 2 21 1 ES TR EH MA0 R5 ~ A1) P 3 3981 0004 60 568 N 2 kt 9576 2859 62 476 O r I o2 l a 6406 0330 - 020 S io RRE MG 1 1 1 EYL P/B SSA I RT DH s N r ) 0I o T0 t N5D p E E e 5 2 07 43 6 50 5 V>I c k 5 8 51 36 .9 49 64 - - 3 - 33 96 - 5 1 F e l w - - 4 TSI R io 1 NET MC 2 ESN l 3 9 2 MAE a NED u 2 E ILI d L AE( i B TR v A N S i T OLE d CEC n ( VN I EA e TLT l N S b 5202 0635 561 5 3302 EDI an 0039 9506 0226 2205 VND t e x U ed 2298 3332 11 22 1 256 1 ~ EOL gr 2 SRA ea AGI VG E C LSE EUP ROS m U DNR EI O TTF AN VO EC y L r ER a 0000 0000 0940 0000 O d 4849 01 85 6595 61 65 2F en t u 5835 8730 0537 1 901 i o 21 66 31 1 1 1 2 3373 T I SB N I Y ELLAV R d E n V i r A wo E nt E E E E W W W W B wc NEN SES SWS NWN oe NNNE EESS sSSW WWNN DS -e h

ecn 91 00 0638 521 5 3301 e 1142 7506 9426 2269 d i 2202 2333 1 422 1 259 m 1 s 33 2 e R 2 -m 9 -0 la 705 0000 0000 0000 1 t m 455 2607 6628 6399 8293 9290 XR ai 884 - 051 5 T en . 2 1 1 1 2 21 1 i A 1 1 31 ,Q t )/ QS /R DH ( 0 S5) R1 3 E T>2 3981 0004 60 568 E kt 9576 2859 62 476 M r2 l a 6406 0330 - 020 A o io R E MG 1 1 1 1 ARL PYB/A NST OR s I HN r S I o R0 E0D p P5E e 5 2 07 43 6 50 6 S I c k 5 8 51 36 9 49 64 - 1 I> F e l w - - 4 3 - 33 96 - 5 D I R i o 1 ST MC 0 2 TEN l 4 S. 2 NSE a EAD u 2 E VEI d L L( i B NE v A ORS i T I E d TLC n AEN I LVA e IET l TLS b 5202 0635 561 5 3302 N I an 0039 9506 0226 2205 t e E 3. D VI ed 2298 3332 1 122 1 256 1 UL gr 2 2OA ea RI VG TGC I E NSP UUSO YUR ENO LI F LT AN VO y C r R a 0000 0000 0940 0000 ER d 4849 0185 6 5 9 5., 61 65 VO en AF t u 5835 8730 0537 1 901 i o 2166 31 1 1 1 2 3373 EB SB dn i r wo nt E E E E W W W W wc NEN SES SWS NWN E EESS SSSW WWNN oe NNI DS =

j ec 0000 0000 0000 0000 n 91 00 0639 531 5 3302 e 11 42 7506 9426 2259 d i 2202 2333 1422 1 259 1 s 33 2 e R 2 m l t a 705 0000 0000 1 000 9 a m 455 2607 6628 6380 ei 884 051 5 8293 9291 m m 0 Mn A 1 1312 1 1 1 2 21 1 1 R XT Q ,/ ) S QR a / H D ( 0) 3981 001 4 60 568 m 53 9576 2859 62 476 S1 - kt 6406 0330 23 020 R>2 l a E io 1 1 1 TR2 MG EO M E ARL RYB A/A s PST r R o NHN t O I p I0 e 5 2 18 44 7 60 7 S0D c k 5 8 51 36 9 49 64 33 96 5 1 R5E e l w 4 3 E I R i o 1 P>F MC 2 S I l m. 2 IST a DEN u 1 E SE d 4 L TAD i B NEI v 2 A EL( i T VE d RS n G E I NLC e IEN l DVA b 5202 0635 0615 3303 LET an 0039 9506 4226 2295 ILS t e U I ed 2298 3332 01 22 1 246 BDD gr 2 1 1 N ea EUL VG NOA IRI BGC R E USP TUSO 2URNO TI F IT y NN r UO a 0000 0000 0450 0000 C d 2925 1 603 3491 491 1 Y en ER t u 0447 8893 1635 8065 LO i o 2355 31 11 1 2 2352 LF SB A V m REVAEB dn irwo nt E E E E W W W W wc NEN SES SWS NWN oe NNNE EESS SSSW WWNN ^ DS 4

ec 0000 0000 0000 0000 n 91 00 0639 531 5 3302 e 11 42 7506 9426 2 2 5 9.. d i 2202 2333 1 422 1 259 .~ 1 s 33 2 e R 2 m ?- 0 1 l t a 705 0000 0000 1000 X am 455 2607 6628 6380 ei 884 - 051 8293 9291 7 Q Mn - 5 ) A 1 1 31 2 1 112 211 /DR ( TQ S/ RS ER TH 3981 0014 60 568 E M0) et 9576 2859 62 476 l 020 A53 l a 6406 0330 2 3.- R1 - io A>2 11 1 P MG R2 NO O - E e I RL SYB R/A s EST r PR o SNN t 60 T I p D0 e 5 2 18 44 7 8 0D c k 5 8' 51 36 9 49 1 T5E e l w 4 3 33 96 5 64. - N - I R io 1 E>F MC ~ 2 V I l 2_ ST a GEN u 2 m E NSE d 4 L IAD i B DEI v 2. A LL( i T IE d URS n I E I LC e ~ l NVA b 5202 0635 0615 3303 GEN an 0039 9506 4226 2295 IET HI S t e S I ed 2298 3332 01 22 1 246. 1 1 IDD gr 2 LN ea OUL VG POA RI EGC T E ASP SUS NO. EUR DNO NIF OT y ra 0000 0000 0450 0000 CN 2 C d 2925 1603 3491 4911 O en t u 0447 8893 1 635 8065 i o 2355 31 11 1 2 2352 TR IO NF SB U YE LLA 'V RE d V n ir A wo nt E E E E W W W W E wc NEN SES SWS NWN B oe NNNE EESS SSSW WWNN DS w

ilfl c 0000 0000 0000 0000 e n 91 00 0638 521 5 3301 e 1 1 42 7506 9426 2269 i 2202 2333 1 422 1 259 d 1 s 33 2 e R 2 m 9 l t a 705 0000 0000 0000 0 am 455 2607 6628 6399 1 ei 884 0515 8293 9290 X Mn A 1 1 31 2 11 1 2 211 ) R QT /Q D/ ~ ( S R SH R 3981 0004 60 568 E0) 9576 2859 62 476 1 E1 - kt 6406 0330 23 020 T53 l a 1 M>2 1 1 A i o RR2 MG AO P E RL NYB O/A s I ST r SR o t RHN e 5 2 07 43 6 50 E I p c k 5 8 51 36 9 49' P0 64 33 96 5 9 S0D I5E e l w 4 3 - 1 1 R i o D I >F MC 2 T I l 2 NST a 3 EEN u 4 E VSE d i L AD 2 B GEI v i A NL( d T IE DRS n L E I I LC e BVA b 5202 0635 5615 3302 l UEN an 0039 9506 0226 2205 ~ ET ed 2298 3332 11 22 1 256 N LS t e 1 O I gr 2 I DD ea TN AUL VG NOA I RI MGC A E TSP NUS OO CUR ENO DI F y T r 2N a 0000 0000 0940 0000 O d 4849 0185 6595 6165 TC en t u 5835 8730 0537 1 901 I i o 21 66 31 11 1 2 3373 NR UO SB F Y E L L A V R EVA dn E i r B nt E E E E W W W W wo wc NEN SES SWS NWN oe NNNE EESS SSSW WWNN DS f l(lI l l! l, l m

e c 0000 0000 0000 0000 n 91 00 0638 521 5 3301 '. 2 6 9 2 1 42 7506 9426 e 1 d i 2202 2333 1 422 1 259 ? 1 s 33 2 e R 2 -m 3 l t a 705 0000 0000 0000 0 am 455 2607 6628 6399 1 8293 9290 ei 884 - 0515 X Mn A 1 1312 1 11 2 211 ) R QT /QD/ s ( S R SH R 3981 0004 60 568 T53 kt 9576 2859 62 476_ E0) l a 6406 0330 23 020 E1 - M>2 io A MG 11 1 RR2 AO P E RL NYB O/A s IST r SR o ~ R H 'N t E I p P0 e 5 2 07 43 6 50 0 S0D c k 5 8 51 36 9 49 64 33 96 5 2 I5E e l w 4

3. ' -

D I R i o 1 >F MC 2 T I l 2 NST a EEN u 4 ~: E VSE d 4 L AD i B TEI v 2 i A LL( T UE d ARS n V E I LC e l GVA b 5202 0635 561 5 3302 EEN AET an 0039 9506 0226 2205 RI S t e O - I ed 2298 3332 1 122 1 256 1 TDD gr 2 SN' ea UL VG SOA ARI GGC E ESP TUS SO AUR WNO IF y 2T r a 0000 0000 0940 0000 N TO IC d 4849 01 85 6595 6165 N en UR t u 5835 8730 0537 1 901 i o 21 66 311 1 1 2 3373 O ~ YF SB ELLAV REVAE d B n i r wo nt E E E E W W W W wc NEN SES SWS NWN oe NNNE EESS SSSW WWNN l. DS

. (i 2.3 Comp *.iance with 10 CFR 50 (caseous) 2. 3'.1 Noble Cases 2. 3.1 '.1 ' Cumulation of Doses Section II.B.1 of' Appendix I of 10 CFR 50 (BvTS 3.11.2.2). limit s the releases of ' gaseous ef fluents from each reactor such thec the estimated annual gamma ~ ir dose is limited to 10 millirad and the beta air adose is limited to 20 millirad. In addition, ' BVTS 'f 3.11.2.4 requires. use of radwaste system if air doses when averaged over 31 days exceed 0.2 mrad for gamma and 0.4 mrad for beta. Based upon NREG-0133, the air dose limits in' the unrestricted area due to noble gases released in. gaseous ef fluents are defined by the l following expressions: .j '4 During any calendar quarter, for gamma radiation: (X/q)ytty} + (B Q s+ b qi,)) < 5 mrad, 3.17'x 10~0 ?[Mi l(X/Q)yQ y + ii i i 1-(2.3-1) .l During any calendar' quarter, for beta radiation: ( i g v, (yjq)vqiv) + (}f)s is+ (X/q)s9is) < 10 mead, 3.17 x 10-8 p y [(yjg)y 9 (2.3-2) j During any.alendar year, for gamma: radiation: ' 4 l + (B Q s+ Di9is)) < 10 mrad, 3.17 x 10-8 p[Mi [(X/Q)yQ y + (X/q)yqiv ii i 1 (2.3-3) I During any calendar year, for beta radiation: 9 s+ (X/q)s9is) < 20 mrad, 3.17 x 10-0 N(((X/Q),Qy + (X/q)yqiy]. + (X/Q)s i i (2.3-4)' { When averaged over 31 days, for gamma air radiation ~ projection: (X/q),qiy} + (B Q,+ b qi,)) < 0.2 mrad, 3.17 x 10-8 p.(Hi [(X/Q)yQ y + ii i 1 i 1 (2.3-5) ( 2-45 j

f[- averaged over ' 31 days, for beta air radiation projec-tion: + (X/Q),Q,+ (X/9)s9is } < 0.4 mrad 3.11 x.10-8. N;((x/Q)'yQy + (X )yqiy i i (2.3-6) where: M- .= the air dose factor due to gamma emissiu: i for each identified noble gas radionuclide 3 "i," mrad /yr per uCi/m ; = the air dose factor due to beta emissions for Ni radionuclide '"i," each identified noble gas 3 mrad /yr per pCi/m ; (X/Q)y = the annual ' average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases (greater 3 than 500 hrs / year), sec/m ; (X/9)y = the relative concentration ifor areas at or beyond the unrestricted area boundary for short-tern vent releases (equal to or.less (' than 500 hrs / year), sec/m ; 3 j. (X/Q)'s = the annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing stack 3 releases (greater than 500 hrs / year), sec/m ; the relative concentration for ' areas at or (X/9)s = beyond the unrestricted area boundary for short-term free standing stack releases 3 (equal to or less than 500 hrs / year), sec/m ; = release of noble gas radionuclide "i" in qi, gaseous effluents for short-term stack

• releases (equal to or less than 500 hrs /

year), UCi; = release-of noble gis radionuclide "i" in qiy gaseous effluents *for short-term vent releases (equal to or less than 500 hrs / year), pCi; Q, = release of noble gas radionuclide "i" in i gaseous effluents for long-term free standing stack releases (greater than 500 hrs / year), ~ ('- pCi; 2-46' j

( Qy = release of noble gas radionuclide "i" in i gaseous effluents for long-term vent releases (greater than 500 hrs /yr), pCi; = the constant for long-term releases (greater Bi than 500 hrs /yr) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, miad/yr per pCi/sec; = the constant for short-term releases (equal b i to or less than 500 hrs /yr) for each identi-f.'.ed noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad /yr per pCi/sec; 3.17 x 10-8 = the inverse of the number of seconds in a year. For BVPS-2, the various noble gas release modes, it.cluding both continuous and batch (i.e., long and short duration releases), are given in Table 2.3-1 for the release points discussed in Section 2.2-1. The NRC staff has indicated that it will allow licensees the option of eliminating the short-term release term and short-term meteorological terms from Expressions 2.3-1 thrc ugh 2.3-6 provided that at the time the licensee fi.le s his Annual Report, he calculates the doses resulting from the short-term releases using the meteorological data corresponding to the periods of short-term releases. At Beaver Valley Unit 2, this option will be exercised.. The Joint Frequency Distri-oution (JFDs) of wind speed and wind direction by stability class (as described in Regulatory Guide 1.23) for all short-term releases (i.e., containment purges) for a given quarter will be used to generate a short-term X/Q value and a short-term D/Q value for the quarter according to the guidance provided in Regulatory Guide 1.111. These values will be utilized in ' calculating the doses resulting from all short-term releases for that partiuclar quarter. The incorpora-tion of this option and the release modes of Table 2.3-1 results in the following expressions to show compliance with 10 CFR 50 for the calendar quarter or year. The doses for all four quarters will be summed to obtain the total annual dose resulting from sMrt-term releases. However, BVPS-2 will subsequently use actual release data and corresponding meteorology for each of these periods in computer codes technically consistent with XOQD0Q and GASPAR to demonstrate com-( pliance. 2-47

1 ( For Release Mode 1 During any month, calendar quarter, or year: ) 1 Gamma Radiation (mrad) l i + (X/Q)cp 3 p+ (X/Q)dv9 3.17 x 10-8 f[M ((X/Q)cv9i + (X/Q)tv9i + Q idv j 1 cv tv f 0.2 (per 31 days) i )< 5.0 (per quarter) (X/Q),yQ ]+BQii 10.0 (per year) (2.3-7) Beta Radiation (mrad) e 3.17 x 10-8 f N [(X/Q):v i + (X/Q)tyQi (X/Q)cp i + (X/Q)dv i i Q + Q 9 + 1 cv tv cp dv 0.4 (per 31 days) )<10.0(perquarter) ( X/Q)m.Qi + (X/Q)PyQ i ( wy pv 20.0 (per year) l (2.3-8) For Release Mode 2 During any month, calendar quarter or year: Gamma Radiation (mrad) 3.17 x 10-8 f(M ((X/Q)cyQi + (X/Q)yyQi + (X/Q)tv9i + (X/Q)cp i 9 + 1 cv vv tv cp 0.2 (per 31 days) )< 5.0 (per quarter) (X/Q)dv9i + (X/Q)wyQi l+BQii dv w p 10.0 (per year) (2.3-9) 2-48

i Beta Radiation (mrad) i N((X/Q)cv9i + (X/Q)yyQi + (X/Q)tv9i + (X/Q)cp i Q + 3.17 x 10-8 I i 1 cv vv tv cp 0.4 (per 31 days) f )<10.0(perquarter) (X/Q)dv9i + (X/Q)wyQ i + (X/Q)pyQi dv wv pv 20.0 (per year) (2.3-10) For Release Mode 3 During any month, calendar quarter or year: Gamma Radiation (mrad) 3.17 x 10-8 I[M ((X/Q)cv i + (X/Q)tv9i + (X/Q)cp i + (X/Q)dv i 9 Q 9 + 1 cv tv cp dv 0.2 (per 31 days) ) < 5.0 (per quarte'r) )+BQti (X/Q)wyQiwv pv 10.0 (per year) (2.3-11) Beta Radiation (mrad) N[(X/Q)cyQi + (X/Q)tv9i + (X/Q)cp i + (X/Q)dv9i + 3.17 x 10-8 I Q i dv 1 cv tv cp 0.4 (per 31 days) l )<10.0(perquarter) (X/Q)wyQi + (X/Q)PyQi vv pv 20.0 (per year) l (2.3-12) For Release Mode 4 During any scath, calendar quarter, or year: Gamma Radiation (mrad) 4 4 2-49 k

L y. t r ?[M-[(X/Q)cv9i + (X/Q)tv9i (X/Q)cp i + (X/9 3,17.x 10-0 9 + + 9 dv i i 1 cv tv cp dv 0.2 (per 31 days) A ( X/Q),yQi }'+ B'i i ) < 5.0 (per quarter) Q vv pv 10.0 (per year) 0 (2.3-13) Beta Radiation (mrad) ? N [(X/Q)cyQi + (X/Q)tyQi + (X/Q)cP9i + (X/Q)dv9i 3.17 x 10-0 i 1 cv v cp dv .4 (per 31 days) ).<10.0(perquarter) (X/Q),yQi + (X/Q)PyQi wy pv 20.0 (per year) i (2.3-14) where: annual average relative concentration for (X/Q)cy = releases from the Elevated Release Vent 3 ([, (Containment Vent), sec/m ; annual' average relative concentration for (X/Q)yy = 3 releases ~ from the Ventilation Vent, sec/m ; 8 annual average relative concentration for (XN)py= 3 releases from the Process Vent, sec/m ; average relative concentration for (X/Q)g[ = annual releases from the Turbine Building Vent, 3 sec/m ; annual average relative concentration for (X/Q)cp = releases from the Condensate Polishing 3 Building Vent, sec/m ; j ' (X /Q)dy,'= annual average relative concentrtion for releases from the Decontamination Building 3 i Vent, sec/m ; i {' (X/Q),y = annual average relative concentration for releases from the Waste Gas Storage Vault 3 Vent, sec/m ; ) 2-50 1

i l(' = release of radionuclide "i" from the Ele-Qi cv vated Release Vent (Containment Vent), UCi; = release of radionuclide "i" from the Venti-Qivv tion Vent, pCi; = release of radionuclide "i" from the Process Qi pv Vent, WCi. = release of radionuclide "i" from the Turbine Qi tv Building Vent, UCi; = release of radionuclide "i" from the Conden-Qicp sate Polishing Building Vent, pCi; = release of radionuclide "i" from the Decon-Qi dv tamination Building Vent, UCi; = release of radionuclide "i" from the Waste Qiwy Gas Storage Vault Vent, pCi. For mode 1, the controlling location is 567 meters NW. Substitution of the appropriate x/Q values into - {. Expressions 2.3-7 and 2.3-8 results in the following: Release Mode 1 During any month, calendar quarter or year: Gamma Radiation (mrad) -5 + 7.35 x 10-5 ;tv 3.17 x 10-8 I[M[9.24x10-5Q Q + 7.35 x 10 9 + cp 1 cv 0.2 (per 31 days) 9.24 x 10- Q ]+BQ ) < 5.0 (per quarter) S 9.24 x 10-5Q + dv vv pv 10.0 (per year) (2.3-13) ( 1 2-51 i 1

'l-Beta Radiation (mrad) ~ + 7.35 x 10-5q., 3.17 x 10-8 g;-N(9.24x10-5Q + 7.35 x 10-5Qi i cv tv cp. -7. # 0.4 (per 31 days) 4 9.24 ' x "10-5Q , + 9.24 x 10-5Q + Igx-10 Q;pv) < 10.0 (per quarter) dv wv 20.0 (per year)- (2.3-16) For mode 2, the controlling location is again 567 meters NW. Substitution of the appropriate X/Q values ined Expressions 2.3-9 nd 2.8-10 results in the fol- ' lowing: Release Mode 2 During any month', calendar quarter 'or year: 'Gansna Radiation (mrad) + 7.35'x 10-59 3.17 x 10-8.I[M(9.24x10-5Q + 1.03 x 10-4Qi i cv vv tv 0.7 (per 31. days) (. ) < 5.0 (per quarter) 7.35 x 10-SQg + 9.24 x 10-5Q + 9.24 x 10-5Q ] +'B Qii i ep dv wv pv 10.0,(per year) (2.3-17). Beta Radiation (mrad) 3.17 x.10-8 I N [9.24 x 10-5Qg + 1.03 x 10-4Q + 7.35 x 10- Sqi.tv+ 1 cv vv 7,cc F 'l0 + 9.24 x 10-5 ;dv+ 9.24 x 10-59 , g gi ] 7.35 x 10-5Q Q wv pv cp 0.4 (per 31 days) < 10.0 (per quarter) 20.0 (per year) (2.3-18) For mode 3, the controlling location is 567 meters NW. Substitution of the appropriate X/Q values into Expressions 2.3-11 and ' 2.3-12 results in the follow-i- ing: 2-52

I Gamma Radiation (mrad)

'+ 7.35 x '0-5qi + 7.35 x 10-SQi I(M[9.24,x10-5 3.17.x 10-8 E i Qi cv tv' cp 0.2 (per 31 days) + 9.24 x 10-5Q } +BQ ] < 5.0 (per quarter) 9.24 x 10-5Qidv vv pv 10.0 (per year) 1 (2.3-19) Beta Radiation (mrad) + 7.35 x 10-5Q + 7.35 x 10-59 +. N;(9.24x,10-5Qi .j 3.17 x'10-8.E i cv tv cp AO ll o6 0.4 (per 31 days) g,o 9.24 x '10-SQ - + 9.24 x 10-5Q + IM Q ]<10.0(perquarter) l ( dv wv pv 20.0 (per year) (2.3-20) For Mode 4, the controlling location is again 567 meters NW. Substitution of the appropriate X/Q values into Expressions 2.3-13 and 2.3-14 results in the following: 1 Release Mode 4 During any month, calendar quarter or year: Ganana Radiation (mrad) d -5 3.17 x 10-8 E [ M [9.24 x 10-5Q + 7.35 x 10-5Qi + 7.35 x 10 9 1 cv tv

cp 0.2 (per 31 days) 9.24 x 10-5Q

+ 9.24 x 10-5Qi }+BQii ) < 5.0 (per quarter) dv vv pv 10.0 (per year) (2.3-21) 2-53

R. 4 1 .f ' Beta Radiation (mrad) N(9.24x10-59 '+ 7.35 x 10-SQ + 7.35 x 10-59 3.17..x 10-8 E i 1 cv. tv cp-7,C TJ V "o 0.4 (per 31. days)~ 9.24 x-10-5Q + 9.24 x 10-59;wv+ 1 pag 99 -] < 10,o.(per quarter) dv pv 20.0-(per year) (2.3-22) The' determination of the controlling locations, for implementation of 10 CFR 50 is a function of the 'fol- ' lowing parameters: o, '(1).radionuclide mix and their isotopic. release (2) release mode (3) 'meteo'rology. . The incorporation of these parameters ' into ' Expressions 2.3-1 through 2.3-6 resulted in. the expressions for-presented in Expressions ~h' + the ~ controlling locations as 2.3-15..through 2.3-22. The radionuclide mix ~ was based .upon source terms calculated using; the Stone and Webster Engineering Corporation-Computer Code ' CASIBB which is similar to the NRC GALE Code (inputs pre-sented in Appendix B).and is. presented in Table 2.2-2 - as-a function of release type and release point.- For-each release mode,E the two or three highest. bound-ary X/Q1 values for each release point.and release duration were utilized in' conjunction with the radio-nuclide mix and release 'for each release point to determine the controlling site boundary location.- Since elevated releases occur from BVPS-2 and their maximum X/Q values may not-decrease with distance (i.e., the site boundary may not have ' highest, X/Q ' values),- the two highest X/Q values. for those dis- { tances, greater than the site. boundary, were Jalso considered in' conjunction with. the radionuclide mix to-l determine the - controlling location. These values of j X/Q were obtained for the midpoint of the 10 standard distance intervals previously presented in-Tables 2.2-4 through 2.2-10. l i ( l 1 1 l 2-54 r

particular combination of , ['. For each release mode a release point nuclide n tx and meteorology dominates.in l the determination of the controlling receptor loe'- tion. For release modeo 1, 3, and 4, the controlling l release is the Elevated Release Vent (Containment Vent). While for release mode 2, the controlling 1 release is the Ventilation Vent. were used in the I Values for Mi and Ni,, which f determination of the controlling receptor location and which are to be used by BVPS-2 in Expressions 2.3-15 j through 2.3-22 to show compliance with 10 CFR 50 are l l presented in Table 2.2-11. Values taken from Table B-f 1 of Regulatory Guide 1.1,09, Revision 1 were multi-l plied by 10 to convert from picoeuries to microcuries 6 for use in Table 2.2-11. j In the determination of the controlling receptor loca-0 tion for Modes 1, 2, 3, and 4, Tables 2.2-4 through 2.2-7 are utilized for X/Q values. The Bi values to l i be utilized are the same values which were present.ed in Table 2.2-12. A description of the derivation of the various x/Q values is presented in Appendix A. The following relationship should hold for BVPS-2 to [ show compliance with Technical Specification 3.11.2.2: l For the calendar quarter: Dy< 5 mrad (2.3-23) Dg < 10 mrad (2.3-24) For the calendar year: (2.3-25) D7 < 10 mrad Dg < 20 mrad (2.3-26) where: D = the air dose from gamma radiation, mrad. y S = the air dose from beta radiation, mrad. D The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Expressions 2.3-23 through 2.3-26 are exceeded, a i 2-55

. (' special report ' pursuant to Section IV. A of Appendix 1 of 10 CFR 50 mu4t be filed with the NRC. ( In addition, BVTS 3.1.2.4 requires that tae gaseous radwaste system must be used to reduce radioactive materials in that waste when projected doses ave raged over 31 days exceed any of the fr ming: Dy < 0.2 mrad (2.3-27) Dg < 0.4 mrad (2.3-28) I l 2.3.1.2 Projection of Doses Doses resulting from the release of gaseous ef fluents will be projected monthly based upon past operating l historical data for EVPS-2. The doses will be pro-jected using Expressions 2.3-7 through 2.3-14 as appropriate. Based upon the sum of the accumulated a doses to date for the quarter and projected doses for the remainder of the quarter, the appropriate gaseo is radwaste subsystem will be used. ( I d R i l 2-56 1

) I i t 2.3.2 Radiciodine and Particulates. g. .v 2.3.2.1 Cumulatf.on of Doses l Section IIC of Appendix 1 of 10 CFR 50 (BVTS 3.11.2.3 and 3.11.2.4) limits the release of ' radioiodines and-radioactive-material in particulate form from each -reactor such that estimated dose or dose commitment in i any calendar year to - an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. In addition, BVTS 3.11.2.4 requires the.use of gaseous radwaste treatment system over 31 days to any when projected doses, averaged organ from gaseous waste would exceed 0.3 mrem. Based upon NUREG4133, the. dose to an organ 'of an individual from radiciodines and particulates, and radionuclides other than noble gases with half-lives greater than 8 . days. in gase'ous effluents released to ' unrestricted can be'. determined by the following expression:

areas, During any month, calendar quarter or year:

0,3' mrem (per 31 days) I R (W,Q, + w,qi, + W Q y + w giy] < 7.5 mrem tp'er quarter) 3.17 x 10~8 ~ i i y i y i 15.0 mrem (per calendar year) j 1 '( 1 (2.3-29) i. 4 where: Q, = release of radionuclide "i" for long-term free. i standing stack' releases greater tha 500 hrs /yr), pCi; Qy = release of radionuclide "i" for long-term vent i I releases (greater than 500 hrs /yr), pCi-qi, = release of radionuclide "i" for short-term free standing stack releases (equal to or less than 500 hrs /yr), pCi; qiy = release, of isotope "i" for short-term vent releases (equal to' or less than 500 hrs /yr), 1 pCi; W, = dispersion parameter for estimating dose to an individual at the controlling location for long-term free standing stack releases (greater. than 500 hrs /yr); = sec/m3 for the inhalation pathway, (X/Q)s ( t 2-57 i t ...m...aa- - -..,....

-2 for the food and ground plane pathway, = meters ( (D/Q)si = the dispersior. paramater for estimating the 1, dose to an individual at the controlling loca-tion for long-term vent releases (greater than i 500 hrs /yr); 3 for the inhalation pathway, (X/Q)vi sec/m = -2 for the food and grou id plane pathway, = meters '(D/Q)y; t w, dispersion parameter for estimating the dos'e to = an individual at the controlling location for short-term stack releases (equal to or less :than 500 hrs /yr); sec/m3 for the inhalation pathway, (X/9)si = -2 for the food and groend plane pathway,' = meters (D/q)a; the dispersion parameter for estimating the dose w = y to an individual at the controlling location for short-term vent releases (equal to or less than {- 500 hrs /yr); sec/m3 for the inhalation pathvay, (X/q)vi = -2 for the food and ground plane pathway, = meters (D/q)y; 3.17 x 10~8 = the inverse of the number of seconds in a year; the dose factor for each identified radionuclide Ri = "i," of the organ of interest, mrem /yr per pCi/ -2 3 see per m or mrem /yr per pCi/m. Radionuclides and particulates may be released from any of the BVPS-2 vents in the release modes identified in, Table 2.3-1. As described previously in Section 2.3.1.1, at Beaver Valley Unit 2 ', for.each quarter, a short-term X/Q and a short-term D/Q value will be generated based upon the JFDs corresponding to all short-term releases for that quarter. These values will be utilized in calculating the doses from all short-term releases for that quarter. The doses for all four quarters will be summed to obtain the total annual dose resulting from short-term releases. The incorporation of this option and the release modes (.. of Table 2.3-1 results in the following expressions to 2-58 o

~ 3 s f, I ?b l show l. compliance with BVTS 3.11.2.3 and BVTS. 3.11.2.4. ' For a particular. organ, Expression 2.3-29. becomes: 3.17 x'10-8g ; [ypvgi ep i' p+ "dv9 + 9 i 9 +W 9 +W +W 1 pv cv -yv91 , g tv i ev 1 c dv vv tv 0.3 mrem-(per 31 days) W,yQ < 7.5 mrem (per-quarter) 15.0 mrem (per' calendar year) (2.3-30) i where: W = dispersion parameter for ' releases ' from. the Proc-r. py ess Vent;. L -= dispersion parameter f or releases-' from the Ele-Wey -vated Release Vent (Containment' Vent); W =. dispersion parameter, for rel' esses from the Ven-yy .tilationl Vent; W = dispersion parameter. f.)r releases from the Tur-tv bine Building Vent; W = dispersion paramete,r for releases from the Con-ep densate Polishing Building Vent; W = dispersion parameter for releases from the dy Decontamination Building Vent;. W = dispersion parameter for releases from-the Waste yy Cas Storage Vault Vent; } = release of radionuclide "i" from the Process Qipv Vent, DCi; = release of radionuclide "i" from the Elevated Qicv Release Vent, UCi; = release of radionuclide "i" from the Ventilation' f Qivv Vent, pct. l = release of radionuclide "i" from the Turbine Qitv Building Vent, UCi; e \\ 2-59 a

i 1 ]I = release of radionuclide "i" from the Condensate .] Qi cp Polishing Building Vent, DCi; = release of radionuclide i" from the Decontami-Qidv nation Building Vent, pCi; , j b = release of radionuclide "i" from the Waste Gas I ~ Qi l wv Storage Vault Vent, pCi; j l The Condensate Polish:.ng Building Vent, Decontamina-tion Building Vent, and Waste Gas Storage Vault Vent are not normal radioactive release points. These release points are included only for use if radioac-4 tive release via theae vents are identified in the future. In determining the dose at a particular location, W, )l is a function of the pathway. For the food and ground J plane pathway, W is in terms of D/Q. If the inhala-l tion pathway is considered, W is in terms of x/Q. l Incorporation of the rarious pathways into Expression 2.3-30 results in the following expression for a par-ticular organ: 3.17 x 10-8 I[(Ri+Ri+Ri + R;B )(WpyQi + WyyQi + pv cv vv E +WeyQi i G H V ( i + QI +Wdv9i "V + Qi Wtv9i CP tv cp dv wv i [(x/Q)pyQi + (x/Q)cyQi (x/Q)yyQi + (x/Q)tv9i + (X/9)cp i + 9 + R 1 pv cv vv tv cp i 0.3 (per 31 days) (X/Q)dv9i "V dv v 15.0 (per year) (2.3-31) where: Ri dose factor for an organ for radionuclide "i" = G for the ground plane exposure pathway, mrem /yr per pCi/sec per m-2; \\ 2-60 ./ a I f j

= release of radionuclide "i" from the Condensate [.. Qicp ' Polishing Building Vent, pCi; ' release of radionuclide "i" from the Decontami-Qidv nation Building Vent, pCi; release of radionuclide "i" from the Waste Cas Qi -a wv Storage Vault Vent, pCi; The Condens2te Polisning Building Vent, Decontamina-tion Building Vent, and Waste Gas Storage Vault Vent are not normal radioactive release points. These release points are included only for use if'radioac-tive release via tLese' vents are identified in the future. In determining the dose at a particular location, W, l as in Section 2.2.2, is a function of the pathway. For the food and ground plane. pathway, W is. in terms ,'j of D/Q. If the inhalation' pathway is considered, W is l in terms of X/Q. Incorporation. of the various path-ways into Fxpression ' 2.3-30 results in the following - expression for a particular organ: 3.17 x 10-8 E[(Ri+Ri+Ri+Ri )(WpyQi +WeyQi . yyQi +W + 1 G M V B pv cv vv +WwyQi + Q +WavQi +W WeyQi ep i tv cp dv wv i [(X/Q)pyQi + (X/Q)cyQi + (X/Q)yyQi + (X/Q)tv9i + (X/9)cp i 9 + R 1 pv cv vv tv cp 0.3 (per 31 days) 9 )) < 7.5 (per quarter) (X/Q)dv 1 + (X/Q)wyQi dv y 15.0 (per year) I (2.3-31) where: \\ = dose factor for an organ for radionuclide "i" l Ri G for the ground plane exposure pathway, mrem /yr l per UCi/sec per m-2; 1 i \\ 2-60 / ) i { k

s I .R; = dose factor for~ an organ for radionculide "i" M for_ either the cow milk ' or goat milk pathway, mrem /yr per pCi/sec ' per. m-2; = dose factor-for an organ for radionuclide "i" Ri V for the vegetable' pathway, mrem /yr per_pCi/sec l per'm-2; -s i R; - do s e ' f 6 : t o r for an organ for radionuclide '.' i" B-for the meat pathway, mrem /yr per - pCi/sec.' per -2; j m = dose f"ctor for ' an organ for radionuclide. "i" Ri 3 I- 'for the inhalation pathway, mrem /yr per pCi/m, It should be noted that W W Wyv s: py, eve W W dy, and W in Expression-W tve eps 2.3-31 are in terms of D/Q(m--2)w y. .t Values of th<3 dose f actor, _ Ri, were calculated using the methodology of NUREG-0133. The following equa-tions ' were used for all nuclides except tritium: 3 = K'(BR),(DFA ),(mrem /yr per UCi/m ) (2.3-32) R i i I (s l - )~ wherer i K' = a constant of unit conversion, 106 pCi/pci; l (BR), = the breathing rate of the receptor of age 3 group (a), in m /yr; l (DFA ), =_the maximum organ inhalation dose factor for i the receptor of age group (a) for the "ith" radionuclide, in mrem /pCi. The total body 1 is considered as an organ in the selection l of (DFAi)a. Inh a l a t ion '- dose factors l (DFAi)a for the various age groups are given in Table E-7 through E-10 of Regula-tory Guide 1.109. The breathing rates (BR)a - used for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109. 3 Age Group (a) Breathing Rate (m /yr) l Infant 1400 Child 3700 Teen 8000 ,( Adult 8000 ) i. 2-61

i I i i 1 I E 2 = K'K" (SF)DFGi[(1 - e~ i )/ A ] (m mrem /yr per pCi/sec) Ri i 1 G. (2.3-33) 8 K' = a constant of unit conversion, 106 pCi/pCi; K" = a constant of unit conversion, 8760 hr/ year; i the decay constant for the "ith" radionuclide, A = sec-l; 8 the exposure time, 4.73 x 10 sec (15 years); t = DFGi = "the groundplane dose conversion factor for the ith" radionuclide (mrem /hr per pCi/m2). A tabulation of DFGi values is presented in Table E-6 of Regulatory Guide 1.109; the shielding-factor (dimensionless). A c SF = shielding factor of 0.7 as ouggested in Table E-15 of Regulatory Guide 1.109 is used. (1 - f f,)e-A tih -A tg ff 9 (U,p) F,lr)(DE ),( p, je i p F R = + i K' i g Ai+A Y Y y p 3 e (m2 mrem /yr ner pCi/sec) (2.3-34) where: K' = a constant of unit conversion, 106 pCi/pci; Qp = the animals' consumption rate, in kg/ day (wet weight); U,p = the receptor's milk consumption rate, for age (a), in liters /yr; the agricultural productivity by unit area of Y = 2 pasture feed grass, in kg/m ; the agricultural productivity by unit area of Y = 3 2 stored feed, in kg/m ; the stable element transfer coefficients, in F, = days / liter; 2-62 i 1

l 1 i r = fraction of deposited ac t ivity retained on ant- [ mais feed grass; (DFL;), = the maximum organ ingestion dose factor for the "ith" radionuclide for the receptor in age group j (a), in mrem /pCi; j ) l A = the decay constant for the "ith" radionuclide, g in sec_ ; i A = the decay constant for removal of activity on y surfaces by weathering 5.73 x ~ plant leaf and (corresponding to a 14 day half- ,{ 10~7 sec life); tg = the transport time 'from pasture, to animal, - to milk, to receptor, in sec; = the transport' time from pasture, to harvest, to t h animal, to milk, to receptor, in see; f = fraction of the year that the animal is on pas-p ture (dimensionless); f, = fraction of the animal feed that is pasture grass while the animal is on pasture (dimension-(' less). ) Tabulated below are the paraine ter values used for cow's milk and their reference to Regulatory Guide 1.109. Parameter Value Table / r (dimensionless) 1.0 for radiciodine E-15 0.2 for particulates E-15 Fm (days / liter) Each Stable element E-1 330 E-5 ap (liters /yr) - Infant U Child 330 E-5 Teen 400 E-5 Adult 310 E-5 (DFLi)a (mrem /pCi) Each radionuclide E-11 to E-14 2) 0.7 E-15 1 p ((kg/m Y kg/m ) 2.0 E-15 2 Ys 5 (2 days) E-15 tg (seconds) 1.73 x 10 6 th (seconds) 7.78 x 10 (90 days) E-15 Qp (kg/ day) 50 E-3 f 0.5 j p 1.0 f. For goat's milk, all values remain the same except for \\ Qp which is 6 kg/ day. j \\ 1 f 2-63 l i a

'l f f, (1 - f f,)e-A t '

-A tg ih i

9(U,p)F(r)(DFL)(Y I. p p F

R le i- = K'

+ - A + A, f ia Y, B p p (m2 mrem /yr per pCi/sec) (2.3-35) where: = the stable element transfer. coefficients, in - -Ff ~ days /kg; U,p = the receptor's, meat; consumption rate for age; (a)'- in kg/yr; tg = the transport time from pasture to receptor, in .sec; t- = the transport time from crop field to. receptor, h in sec. All. parameter values ' are the same. as, the milk pathway , parameter values. except Fg which. is obtained-from Table E-1. of Regulatory Guide ' 1.109 and Ua which is obtained from Table E-5 of Regulatory ' Guide 1.109. ~f The values used are as follows: Parameter Value Table Fg (days /kg) Each stable element .E-1 0 E - Uap - (kg/yr) - Inf ant Child-41 E-5 . Teen 65 E-5 Adult 110 .E-5 Man is. considered to consume two typss of vegetation (fresh and stored) that dif fer only in the time period between harvest and consumption;.therefore: 7 --A t -A t (r) b ib+Ufe ih] R 8 = K' (Y ( A + A,))(DFL ) (U f e i ia aL ag V y i (m2 mrem /yr per pCi/sec) (2.3-36) I where: i K' = a constant of unit conversion, 106 pCi/pCi; (. 1 2-64 )

1 1 1 I consumption rate of fresh leafy vegetation ( .U,'.= the by the receptor in age group (a),.in kg/yr; -1 .U, = the consumption rate o f' stored vegetation by ') S receptor in age group (a) in kg/yra i i the fraction of the annual intake of fresh leafy 1 'f = vegetation grown locally;. the fraction of the annual intake of stored f = E vegetation grown locally; tg = the average. time between harvest of leafy vegetation and its consumption, in seconds; th = the average time between harvest of stored vegetation and its; consumption, in seconds, the vegetation area density, in kg/m2; Y = y and all other factors are defined previously. _j Tabulated below are the appropriate ' parameter values and their reference.to Regulatory Guide 1.109. Parameter Value-Table r.(dimensionless) 1.0 for radioiodines-E-15 j 0.2 for particulates E-15 (DFLi)a (mrem /pCl) Each radionuclide E-11 to E-14 UL (kg/yr).- Infant 0 E-5 a Child 26 E-5 Teen 42 E-5 Adult 64 E-5 US (kg/yr) Infant 0 E-5 a Child 520 E-5 Teen 630 E-5 Adult 520 E-5 ft (dimensionless) 1.0 E-15 0.76 E-15 g ((dimensionless) f 8.6 x 10 (1 day) E-15 4 t (seconds) t seconds) 5.18 x 106 (60 days) E-15 l t h Yy (kg/m ) 2.0 E-15 2 For tritium the parameter W for the food ^ pathway is ./ based upon y,/ Q. The' ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression 2.3-30 may be expressed for purposes of implementation of 40 CFR 190, discussed in Section 4.0, as: -(. I / .n-s

rate of fresh leafy vegetation Uh =- the consumption .by the receptor in age group (a), in'kg/yr;. U8 = the consumption rate. of stored. vegetation by . receptor in age groupL (a) -in kg/yr; ft = the fraction of the annual intake of fre'sh. leafy. vegetation grown locally;- a the fraction of-the annual intake of stored-f vegetation. grown locally;- ti = the. average time between harvest.2 of. leafy vegetation and its consumption, in seconds; th = the average time ;between-harvest o f, - ' stored-vegetation and its' consumption, _ in seconds;. 2 the vegetation area. density, in kg/m ;. Y = y . and all othier f actors are defined previously. -Tabulated below ' are the appropriate, parameter - values _ and. their reference to Regulatory Guide 1.109. l .- ( Parameter Value-Table r (dimensionless) 1.0 for,radioiodines .E-15 'O.2 for particulates E-15 l (DFL )a (mrem /pCi) Each radionuclide E-11 to-E-14 i 'UL (kg/yr) - Infant 0 E-5 a-Child 26 E-5

• J Teen 42 E-5 Adult

'64 E-5 US (kg/yr) - Infant 0 E-5 .i a Child 520 E-5 Teen 630 E-5 Adult 520 E-5 1.0 E-15 t ((dimensionless) f dimensionless) 0.76 E-15 fg t (seconds) 8.6 x 10 (1 day) E-15 q t th (seconds) 5'.18 x 106 (60 days) E-15 i 2 2.0 E-15 Yv (kg/m ) As discussed in Section 2.2.2, for tritium the para-i meter W for the food pathway is based upon X/Q. The ground plane pathway is not appropriate for tritium. Therefore, the lef t-hand portion of Expression-2.3-30 ,q may be expressed for purposes of implementation of 40 i CFR 190, discussed in Section 4.0, as: 2-65 4 j i

i[~ For tritlum: 3.17-'x 10~0 (R +R +R ^T)[(X/Q)pyQT (X/Q)cv9T + +R T y T y g cv. vv g B + JX$cp T + (X/Q)dv9T w T,y ' ( X/Q) gyQT 9 cp dv gy (2.3-37) .where: R = dose factor for an organ for tritium -for' the T 3 M milk pathway, mrem /yr per.pCi/sec. R = dose factor for'an organ for tritium for the T 3 'V vegetable p'athway, mrem /yr per pCi/m. =. dose factor for an organ for tritium for the .RT 3 B, beef pathway, mrem /yr per pCi/m ; RT. = dose factor for an organ for tritium for the 3 I inhalation pathway, mrem /yr per: pCi/m. . Expression 2.3-37 is used to show compliance with 40 h} CFR 190, as discussed in Section 4.0. The concentration of tritium in milk is based on the airborne concentration rather than' the deposition. is based on (x/Q}: Therefore, the RT M 3 K'K'"F,Qp,p(DFL ),(0.75(0.5/H)] (mrem /yr per pCi/m ) U i RTM (2.3-38) where: K'" = a constant of unit conversion, 103 gm/kg; 3 absolute humidity of the atmosphere, in gm/m ; H = 0.75 = the fraction of total feed that is water; the ratio of the specific activity of the feed 0.5 = grass water to the atmospheric water; and other parameters and values are the same as for Ri The value of H used is 8 grams / meter 3 M \\ 2-66 i

t i l h:. The concentration of tritium in vegetatio s is based on the airborne concentration rather than th( deposition. is based on [x/Q]: Therefore, the RT V R = K'K'" (U ft +.U,f )(DFL;),(0.75(0.5/H)] 8 T g y 3 (mrem /yr per UCi/m ) (2.3-39) where all terns have been defined above. The concentration of - tritium in meat is based on its airborne concentration rather than the deposition. is based on [x/Q]: Therefore, the RT B tj K'K'"F Qp,p (DFL ),(0.75(0.5/H)] U R g i TB 3 (mrem /yr per UCi/m ) (2.3-40) { where all terms have been defined above. To show compliance ~ with BVTS 3.11.2.3 and BVTS-3.11.2.4, Equation 2.3-31 is evaluated at the control- ) J ling pathway location. For release modes 1 through 4, the controlling location is. a residence. 0.89 miles in Inserting appropriate X/Q values from the NW sector. Tables 2.2-4 to 2.2-10 and D/Q' values from' Tables 2.2-14 to 2.2-20, Expression 2.3-31 becomes: Release Modes 1 through 4 Per month, calendar quarter or year) (mrad) l l ( 2-67

Q. + 1.56 x 10-8 q t }[4.22 x 10-10 q _.+.1.56 x 10-8 3.17 x 10~8 E([Ri +R t cv vv G V pv + 1.56 x 10-8 Q + 1. 56 x 10-8 qi j- + 1.55 x.10-8 Q + 1.55 x 10-8 Qt y t [7.30 x 10-9 Qi : + 2.00 x 10-5 Q+ 2.71 x 10-5 Q + 2.22 x 10-5. q +R cv vv-tv I pv 0.3 (per 31 days) '2.22 x 10-5.Q +.2.00'x 10-5Q + 2.00 x 10-5Q. )) < 7.5 (per quarter) dv wv. 15.0.(per year) cp (2.3-41) For tritium, for purposes of implementation of 40 CFR 190, as discussed in Section 4.0, Expression 2.3-37 reduces to: e i a + 2.00 x 10-5 Q + 2.71'x 10-5 q T)(7.30x10-9 Qi 3.17x.10-8(R +R T cv vv V I. pv + 2.00 x 10-5 Q + 2.00 x 10-5 qi. ] + 2.22 x 10-5 Q . + 2.22 x 10-5 Qi dv wv tv cp {q (2.3-42)

• i The determination of a controlling. location for imple- -

mentation of BVTS 3.11.2.3 and BVTS 3.11.2.4-for radioiodines and particulates is a function of: (1) radionuclide mix and their isotopic release (2) release mode (3) meteorology (4) exposure pathway .{ (5) receptor's age. I i 4 -\\ l 2-68

ii ( The incorporation of there parameters into Expression 2.3-29 results in the rispective equations for each release mde at the contr 11ing location. In the determination of the controlling location for each release mode, the radionuclide mix of radioio-j l dines and particulates was based upon the source terms i calculated using the Stone and Webster Engineering Corporation Computer Code GASIBB which is similar to the NRC GALE code. This mix was presented in Tabit l a function of release mode and release point. 2.2-2 as For the ground plane exposure pathway, all radionu-clides (excluding H-3 and C-14) were considered in the determination of the controlling location. For the inhalation and food pathways H-3 and C-14 were also considered in determination of the controlling loca-tion. In the determination of the controlling location for each release mode, all of the exposure pathways, as presented in Table 2.2-3, were evaluated. These in-clude cow milk, goat milk, beef and vegetable inge s-- tion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway l locations. A child was as sumed to be present at all vegetable garden and beef animal locations. The ( ground plane and inhalation exposure pathways were considered to be present at all locations. For the determination of the controlling location, the highest D/Q and X/Q values for each release point and release mode for the vegetable garden, cow mil k', and 1 goat milk pathways were selected. The organ dose was { calculated at eaqh of these locations using the radio-1 i nuclide mix and release of Table 2.2-2. Based upon these calculations, it was determined that the con-l trolling location for release modes 1 through 4 is the residence / child pathway. For release mde 1 through 4, the controlling release point and mix is the Elevated Release Vent (Contain-ment Vent). Tables 2.3-2 through 2.3-20 present ki values for the total body, GI-tract, bone, liver, kidney, thy- [ l roid, and lung organs for the ground plane, inhala-tion, cow milk, goat milk, vegetable, and meat inges-tion pathways for the infant, child, teen and adult ( 2-69 1 1 i

tion pathways for the infant, child, teen, and adult i: age groups as appropriate to the pathways. These values were calcul sted using the methodology described in NUREG-0133 usint a grazing period of 6 mont!.s. In the determinatlan of the. controlling location for release modes 1-4, x/Q's listed in Table 2.2-4 through 2.2-10 were used. Tables 2.2-14 through 2.2-20 are utilized for long-term D/Q values. A description of the derivation of the various X/Q and D/Q vrlues.is presented in Appendix A. Long-term D/Q values for the process vent, elevated release vent (containment vent), the ventilation vent, turbine building vent, condensate polishing building vent, decontamination building vent, and waste gas provided for the midpoints of storage vault vent are the following distances:

0. 0-0. 5 mi., 0. 5-1.0 mi., 1.0-1.5 mi., 1. 5-2.0 mi. -,

2.0-2.5 mi., 2.5-3.0 mi., 3.0-3.5 mi., 3.5-4.0 mi., 4.5-5.0'mi. The values appear in Tables 2.3-21 through 2.3-27. These values may be utilized if an additional special location arises different from those presented in the ( special locations of Table 2.2-3. The following relationship should hold for BVPS-2 to show compliance.with BVPS Technical Specification 3.11.2.3. For the calendar quarter: / -(2.3-43) Dy < 7.5 mrem to any organ - For the calendar year: (2.3-44) D'y < 15 mrem to any organ where: l Dy = the dose. to any organ Y from radioiodines and particulates, mrem. The quarterly limits given above represent one-half the annual design objective of Section IIC of Appendix I of 10 CFR 50. If any of the. limits of Expressions 2.3-43 and 2.3-44 are exceeded, a special report pur-suant to Section IVA of Appendix I of 10 CFR 50 nust be filed with the NRC. ( 2-70

. ) i 1 2.3.2.2 Projection of Doses ' [. - 1 I Doses. resulting from release of radioindines and par-ticulates. will. be projected msnthly aased upon 'past operating' history data for ' BVPS-2. The doses will be projected osing Expression 2.3-41.. Based upon the sum j of the acca:culated doses ' to date for the quarter and the; projected doses for the remainder ~ of the quarter,. the' appropriate. gaseous radwaste subsystem. will- 'be used. O 9 e t ,,'^

\\.

8 2-71

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31 1 1 1 1 1 1 1 11 1 11 11 1 1. 1 1 11 1 1 1 1 n i 00000000000000000000000000 n d EEEEEEEEEEEEEEEEEEEEEEEEEE i n 60000000000000000000000000 k a S 20000000000000000000000000 10000000000000000000000000 sya 31 665651 666655665611 444656 w 00000000000000000000000000 h t g n EEEEEEEEEEEEEEEEEEEEEEEEEE a u 60917630090744539600501 716 p L 20402960457700365100725267 m 101 1 95801911 559491 0091 71 37 u i t d 00000000000000000000000000 i 31 11 11 11 1 1 1 1 11 1 1 33761 1 1 1 1 1 r t i 2 o EEEEEEEEEEEEEEEEEEEEEEEEEE l l r 60000000000000008495000000 a y 20000000000000002411 000000.. T h I T 1000000000000000331 2000000 dn N a U N 31 31 1 1 411 114335444445451 35 y O y 00000000000000000000000000 a w I e T n EEEEEEEEEEEEEEEEEEEEEEEEEE h t 60300090000122377528752757 A d a 20800080000478395615852624 T i p = S K 09000600005751143622821 68 1 n. R os E i y 2 W 4311 333445551 46 t a 34443455111 00000000000000000000000000 aw O q 3 r l h P EEEEEEEEEEEEEEEEEEEEEEEEEE at 3 2 Y e 60578535000400096778760053 ha 7 E v 27975103000480097654442934 np E L i i 2 L L L r B A 173211 11 000370095431816411 r e A V oh T f t R 41575543444343545446 o 161 411 E 00000000000'000000000000000 3 A V ml A e l E n EEEEEEEEEEEEEEEEEEEEEEEEEs /a B o 02070040412713086523208093 i B 0301 002009604590275 6797994 Cpr O 01 01 0030394111611 928334313 - o R f r F epee S 34455544555555555533443555 E t 00000000000000000000000000 r/s U c y L a i EEEEEEEEEEEEEEEEEEEEEEEEEE / A r C 29377479805 mp V T 632864469140401 267808364285011 048280131 21 e R I r r G 1 8711 251 3731 11 931 36811 8218 m ep f s o r 34343444364432333343555335 y 00000000000000000000000000 s/ y t m d EEEEEEEEEEEEEEEEEEEEEEEEEE l B 609578591 942071 47851 707634 ie t o l u 2020046870232579550521 2558 nr um ad T hA 1 561 2145861 246851 1 2471 4211 n2 n i m I = sf = p eo u MMM u yo e 32498056901 55360791 3467 014 l s ar d at 3555668899990012233333444 vi wG i 11 11 1 1 1 1 1 1 1 11 h l NEOONBRR RBUUGEE SSSAEE n R u t e c ag u HPMFCCZRSSYZNRRATTIICCCBCC PA N m

y l11 ll!! i]' illI I x xx eg 311 1 111 11 1 111 11 L 11 111 11 1 1 L n i 000000000000000O000000000O n EEEEEEEEEEEEEEFEEEEEEEEEEE d i n 70000000000000000000000000 k a S 20000000000000000000000000 0000000000000000000000000 1 sya 666661676655766611545657 w 3100000000000000000000000000 h m-t g a n EEEEEEEEEEEEEEEEEEEEEEEEEE 333 p 70834140153802145700671 u 2 0 9 5 3 7 2 0 4 6 9 6 5.~8 6 7 6 9 0 0 4 7 2.~0 1 3 m ~ L ^ 101'l 181021 22771611 0011 1261 u ~ i t Y 11 111 1 111 11 1 337611 11 1 1 r i 3111 t d 00000000000000000000000000 i 2 o EEEEEEEEEEEEEEEEEEEEEEEEEE l l r 70000000000000008762000000 a ~ y 20000000000000003549000000 T h 0000000000000004412000000 d I T 1 n a NU 3141 114111 14335444445551 36 y O y 00000000000000000000000000 N a w I e T n EEEEEEEEEEEEEEEEEEEEEEEEEE h A d . 70700030000392003899504871 2_ t T i 202000600007949551 35710282 ap S K 010008000069712658331 3281 R . 1 n. os E i y 3 W 11441143344655146 t a 354434551 a w O 00000000000000000000000000 P l h 3 r EEEEEEEEEEEEEEEEEEEEEEEEEE at 4 L. 2 Y e 79097130000830015795337992 h a 7 E v 201605390005000315001 94680 np - E L i i 2 L L L B A 1 153211100041 001 864211861 2 r r e A V oh [ T f t R o 2~ 16141141585543444444545446 E 00000000000000000000000000 3 ml VA e EEEEEEEEEEEEEEEEEEEEEEEEEE l / E n i a B o 09090050480550380941249648 6488 C 08,05008030648183835201 B D r RO 0101 003041611 2911131556524 o f F repc S e E t 34454544555545555534343555 U c 00000000000000000000000000 r/s y L a i EEEEEEEEEEEEEEEEEEEEEEEEEE / A r 777819671 48979929483597863 mC V T U 22675567760460575040704226 e R I r r G l' 961 924137419192146191 821 8 m ep fo 34343444464432433343555355 ry y 00000000000000000000000000 s/ d t m o EEEEEEEEEEEEEEEEEEEEEEEEEE i 62 e n B 759378395775654884418711 n r l e 21 347923267169291 26243151 6 u m ae T hT 1 781 216816135817222651 3322 n2 n im I = sf = p eo u MMM u yo e a r d 32498056901 55360791 346701 4 l s wG i 355566889999001 2233333444 at vi 11 1 111 11 111 1 1 h l NEOONBRR RBUUGEE SSSAEE n t e c R u ag u HPMFCCZRSSYZNRRATTIICCCBCC PA N I[!!(l( lIIl ll!

31 1 1 1 1 1 1 11 1 11 1 1 1 1 11 1 1 1 1 1 1 1 n i 00000000000000000000000000 n EEEEEEEEEEEEEE d EEEEEEEEEEE2 n i 20000000000000000000000000 a k 0000000000000000000000000 S 1 0000000000000000000000000 s 1 ya 31 666651 676655766611 545657 w 0000000000000000000000000G h t g a EEEEEEEEEEEEEEEEEEEEEEEEEE 3786001 54439 p n u 20770640572331 L 10521 09014621 644470024 0741 m 1011 17 9021 2266151 1 001 1 11 51 u i t i 31 11 1111 11 1 1 1 1 11 337611 1 1 11 r . t 00000000000000000000000000 d i EEEEEEEEEEEEEEEEEEEEEEEEEE l 2 o l 20000000000000006224000000 a r 10000000000000000368000000 y T h d I T 10000000000000006613000000 r n N a D 1433544444545136 y L 31 411 1 41 1 1 00000000000000000000000000 a N O y w I e EEEEEEEEEEEEEEEEEEEEEEEEEE h T n A d 2000003000051 2425277 032137 ta 30833,58151 T i 1 000001 0000960 81 ~ p S K 0100070000587 126573392281 1 n. R os E iy 354434551 1 1 431 143344655146 t a 4 W aw 00000000000000000000000000 O l h P 3 r at 5 EEEEEEEEEEEEEEEEEEEEEEEEEE ha 7 2 Y e 380007600434031 14751 E L i 11 23731 900011 001 5880072491 np - E v 249471 i 2 L L L 000490018642118612 r B A 11 431 1 11 r e A V oh T f to R 585543544444545446 16141 141 00000000000000000000000000 3 E ml V E l A e EEEEEEEEEEEEEEEEEEEEEEEEE_6 /a E n 30596882060059 i 0007005091 B o B 06000020901937364986550397 C p r O 0202004051 91 221 1 21 41669736 o R f r F epe e S 34444443555444554533333545 E t s 00000000000000000000000000 y/ r U c L a i EEEEEEEEEEEEEEEEEEEEEEEEEE / C A r V T 21 9631 38734097903147471 258 mU 1 220466964 816420188481 6068 e r r R IG 1 427391 7131 63441 71253431 53 m e p f o r 34343445464433433343555335 y 00000000000000000000000000 s/ y t m d EEEEEEEEEEEEEEEEEEEEEEEEEE i e d o 428468291 l B 26076624233947931 li 1 8561 201 74465061 007621 2386 nr u m ah T 9913271162361 19332721 1 423 n2 hC 1 i n m I = sf = p eo u MMM u yo e ar d 32498056901 55360791346701 4 l s wG i 3555 66889999001 2233333444 at 1 1 1 1 1 1 1 11 1 1 1 1 vi NEOONBRR RBUUGEE SSSAEE n h l ag u HPMFCCZRSSYZNRRATT1I CCCBCC R u t e c PA N

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0 0000000000000000 5 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EEEEEEEEEEEEEEEE 826927 92693/551 4 r 3263380593971749 5 ~. 4 234531 21 11 1 23462 5 0000000000000000 4 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EFEEEEEEEEEEEEEE 498585590585939 1 s. 0 9 9 6 5 0 2.'5 8 3 7 3 3 8 7 8 5 4 23564221 21 233573 0 0009000000000090 2 4 1 1 1 01 1 1 1 1 1 1 11 1 01 m EEEEEEZEEEEEEEEE 29445261 4 n393258928 ,r 0? 71 64 097001 5 ) t Qq // 3 4471 533222344814 D s ( r h 5 0099000000000990 SR0 3 11 001 1 1 11 1 1 1 1 001 E5 T1 EEEE'EEEEEEEEEEEE E s 6501 452962872665 1303501 9801 821 52 M> e 0 A l R r i 3 561 1 6442334561 16 Ao M P r n 0 0099000000000990 O/ 3 11 001 1 1 11 1 011 001 N y i I s S r s EEEEEEEEEEEEEEEE Rh n 7476945216256590 5557595470643510 E o 5 P0 i S0 t 2 7811 9564545881 29 I5 a 4 D c o 5 9999900000099999 2 L TNS 2 000001 1 1 11 1 00000 5 3 EE l 9 2 VS o EEEEEEEEEEEEEEEE A r 82407629481 091 98 -2 0225343217021292 0 E GE t L NL n 22189685811221 B IE o ' 2 1 1 A DR C T L 0 9999999990999999 IL e UE h BV t 2 0000000001000000 .E EL o EEEEEEEEEEEEEEEE 974225567774062 N t 188461 441 29486681 ID 5 BN s RU e 1 11 332111 1811 2342 UO c TR n G a 5 9999999999999999 2 t 0000000000000000 S s 1 TU i IO D EEEEEEEEEEEENEEE 471 1 949660242389 NU 2325755026637467 UN 0 I YT 1 3366322221 234683 EN LO LC 0 9988899999998889 A 0000000000000000 VR 1 O RF EEEEEEEEEEEEEEEE 3975500272073074 E 7323067935391 600 V 5 AE 0 791 1 1 55464571 1 29 B 5 8888888888888878 0 0000000000000000 EEEEEEEEEEEEEEEE 6227839471 609592 0 443702286606421 2 0 457763323234691 5 ro E E E E W W W W NEN SES SWS NWN tc NNNEEESSSSSWWWNN es i fl L

0 0000000000000000 5 1 11 1 1 11 11 1 1 1 1 1 1 1 EEEEEEEEEEEEEEEE 27926937 551 4 82( !! 3263380593971 749 5 4 234531 21 11 123462 7h 5' 0000000000000000 4' 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EEEEEEEEEEEEEEEE 498585590585939 1 0 9965025837338.785 2 m 4 23564221 21 233573 ) ' 0 0009000000000090 Q~ / 4 1 1 1 01 1 1 11 1 1 1 1 1 01 D' ( EEEEEEEEEEEEEEEE r 0271 64929445261 4 097001 1 393258928 St 5 E q E/ 3 4471 533222344814 Ts E r Mh 5 0099000000000990 AR0 3 1 1 0011 1 1 1 1 1 1 1 001 A5 P1 EEEEEEEEEEEEEEEE s 6501 452962872665, 1 303501 9801 821 52 0 N> e O l 1 6 I r i 3 5611 6442334561 S o M R E r 'n 0 0099000000000990 P y i S/ 3 1 1 001 1 1 11 1 01 1 001 I s D r s EEEEEEEEEEEEEEEE h n 747694521 6256590 5557595470643510 T o 5 N0 i E0 t 2 781 1 9564545881 29 V5 a c 5 o 5 9999900000099999 1 G> N L IS 2 000001 1 1 1 1 1 00000 3 DE l 6 9 2 LS o EEEEEEEEEEEEEEEE IA r 82407629481 091 98 022534321 7021292 2 m E UE t 0 ~ L BL n B E o 2 11 2218968581 1 221 A GR C T N IL e 0 9999999990999999 HE h SV t 2 0000000001 000000 IE LL o EEEEEEEEEEEEEEEE e O t 1 974225567 774062 PD 5 88461441 29486681 N s E'J e 1 1 13321 1 11811 2342 TC c AR n SG a 5 9999999999999999 N' t 0000000000000000 ES s 1 DU i NO D EEEEEEEEEEEEEEEE 949660242389 OU 471 1 2325755026637467 CN 0 I 2T 1 3366322221 234683 N TO IC 0 9988899999998889 N 0000000000000000 UR 1 O - - - - - - - - - - - - - ~- - - YF EEEEEEEEEEEEEEEE 3975500272073074 E 7323067935391600 L 5 LA 0 791 1 1 55464571 129 V ~ 5 888888888'8888878 REV 0 0000000000000000 A EEEEEEEEEEEEEEEE E B 6227839471 609592 0 4437022866064212 0 457763323234691 5 ro E E E E W W W W NEN SES SWS NWN t NNNEEESSSSSWWWNN ce S

1 0 0000000000000000 a ^. 5 1 11 1 1 1 1 1 1 1 11 11 11 EEEEEEEEEEEEEEEE 826927926937551 4 3263380593971 749 5 ~ 4 234531 21 11 123462 5 0000000000000000' 1 11 1 1 11 1 1 1 1 1 1 1 1 1 4 EEEEEEEEEEEEEEEE s 49B585590585939 1 O 9965025837338785 L 2' 4 23564221 21 233573 m' 0 0009000000000090 ) 4 1 11 01 11 1 1 1 1 11101 Q EEEEEEEEEEEEEEEE / 0271649294452614 Dr 097001 1393258928 (.t 5 q S/ 3 4471 533222344814 R s E r Th 5 0099000000000990 EM0 3 1 1 001 11 1 1 1 111 001 A5 EEEEEEEEEEEEEEEE R1 A s 6501 452962872665 1 303501 98018215 2 0 P> e l N r i 3 5611 644233456116 + Oo M I S r n 0 0099000000000990 Ry i E/ 3 1 1 001 11 11 1 011 001 P s EEEEEEEE2EEEEEEE S r s 7476945216256590 Ih n 5557595470643510 D o 5 t 0 i T0 t 2 7811 956454588129 N5 ac 6 E _ o 5 9999900000099999_ 2 V> L GS 2 0000011 1 1 1100000 7 3 NE l 9 2 IS o EEEEEEEEEEEEEEEE 82407629481091 98 nW 2 DA r 0225343217021292 0 E LE t L IL n B UE o 2 1122189685811 221 A BR C T NL e 0 9999999990999999 OE h IV t 2 0000000001 000000 ~ TE EEEEEEEEEEEEEEEE AL 'o 974225567774062 N t 1 88461441 29486681 ID 5 MN s 1332l' 11 181 12342 AU e 1 1 TO c NR n OG a 5 9999999999999999 u C t 0000000000000000 ES s 1 DU i O D EEEEEEEEEEEEEEEE 949660242389 4711 2U 2325755026637467 N 0 TI 3366322221234683 IT 1 NN UO C 0 9988899999998889 Y 0000000000000000 ER 1 LO EEEEEEEEEEEEEEEE LF 3975500272073074 A 7323067935391 600 V 5 R 0 7911155464571 1 '2 9 E V A 5 8888888888888878 E 0000000000000000 B 0 EEEEEEEEEEEEEEEE 609592 6227839471 0 4437022866064212 5 0 457763323234691 ro E E E E W W W W NEN SES SWS NWN t NNNEEESSSSSWWWNN ce S

0 0000000000000000 5 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EEEEEEEEEEEEEEEE 826927926937 551 4 3263380593971 749 5 4 234531 21 1 1 123462 5 0000000000000000 4 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 EEEEEEEEEEEEEEEE 498585590585939 19965025837338785 0 4 23564221 21 233573 2 m 0 0009000000000090 4 1 1 1 01 1 1 1 1 1 1 1 1 1 01 ) Q EEEEEEEEEEEEEEEE / r 0271 64929445261 4 097001 1393258928 Dt 5 ( q / 3 4471 533222344814 R s E r Th 5 0099000000000990 EM0 3 1 1 001 1 1 1 1 1 1 1 1 001 A5 R1 EEEEEEEEEEEEEEEE A s 6501 452962872665 1 303501 9801 821 52 P> e 0 i l 1 6 N r i 3 5611 644233456l O o M I S r n 0 0099000000000990 R y i E/ 3 1 1 001 1 1 1 1 1 01 1 001 S r s EEEEEEEEEEEEEEEE o P s Ih n 747694521 6256590 5557595470643510 D o 5 0 i T0 t 2 7811 9564545881 29 N5 a 7 E c 2 V> o 5 9999900000099999 L TS 2 000001 11 1 11 00000 3 LE l 8 9 2 US o EEEEEEEEEEEEEEEE AA r 82407629481 091 98 022534321 7021 292 2 0 ~ E VE t L L n ~ B EE o 2 11 2218968581 1 221 A GR C T ARL e 0 9999999990999999 OE h TV t 2 0000000001000000 SE L o EEEEEEEEEEEEEEEE 974225567774062 1 S t 188461441 29486681 AD 5 GN s U e 1 1 1 3321 11 1 81 1 2342 EO c TR n SG a 5 9999999999999999 A t WS s 1 0000000000000000 U i 2O D EEEEEEEEEEEEEEEE U 471 1 949660242389 2325755026637467 TN 0 I I NT 1 3366322221 234683 UNO Y C 0 9988899999998889 ELR 1 0000000000000000 LO AF EEEEEEEEEEEEEEEE V 3975500272073074 7323067935391 600 5 RE 0 791 1 1 55464571 1 29 VA E 5 8888888888888878 B 0 0000000000000000 EEEEEEEEEEEEEEEE 6227839471 609592 0 443702286606421 2 0 4577633232346915 ro E E E E W W W W t NEN SES SWS NWN c NNNEEESSSSSWWWNN e S j o

le' t -3.0' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TableL 3.0-1 L contains ' the ~ DLC site number,. 5ector, : distance' -sample ~ point description,- sampling. and collection. frequency, analysis,' and I analysis frequency ~ for various exposure pathways in the vicinity of the. Beaver. Valley Power Utations (BVPS) ' for the radiological monitor-ing program. Figures - 3.0-1 through' 3.C-9 show. the location;' of the various' sampling points i 9 e 4 0 , I. e C o e i e e i l 4 3-1 l l

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4.0 INFORMATION RELATED TO 40 CFR 190 ( Technical Specification 3.11.l.a requires that when the calculated doses associated with the ef flu rnt releases exceed twice ' the limits of .11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, Specifications 3.11.1.2.a. a 3.11.2.3.a or 3.11.2.3.b, the licensee shall prepare and submit a Spe-cial Report to the Commission and limit subsequent releases such that the dose or dose commitment to member (s) of the public from all f acility releases is limited to < 25 mrem to the total body, any organ (except the thyroid, which is limited to < 75 neem) for a calendar I year. The BVPS-2 Technical Specifications consider doses to member s of the public due to the operation of BVPS-2 but do not include ar.y other part of the uranium fuel cycle or direct shine from the reactor. If a Special Report to the Commission is prepared by the licensee as required by Specification 3.11.4.a. the report should contain: 1. A determination of the maximum exposed member of the public. A determination of the total dose to this person from all existing 2. pathways and sources of radioactive effluents. Where additional information on pathways and nuclides is needed,* the best available information will be used and d'ocumented. 3. A determination of the dose resulting from direct radiation from the plant and storage f acilities. Total body and organ doses resulting from liquid ef fluents from BVPS -2 will be summed with the doses resulting from releases of noble gases, radioiodines, particulates, and tritium (excluding C-14). These dosas will be based upon releases from BVPS-2 during the appropriate ti e period in which twice the Specification was exceeded. Direct dose components due to skyshine will be determined either by calculation, using methodology specified in NUREG-0133, or by actuni measurement. The dose from both releases and direct radiation will be summed. ) 4-1 0 1 1

API.?NDIX A l

SUMMARY

OF DISPERSION CALCULATIONAL PROCEDURES i . Annual average and grazing season average values of relative j concentration (X/Q) and deposition (D/Q) were calculated for continuous and 1 intermittent gaseous releases of activity from the BVPS-2 site according to the straight-line airflow (Gaussian) model described in FRC Regulstory Guide 1.111, Revision 1. Undecayed and undepleted sector average x/Q and D/Q values were obt ained for each of sixteen 22.5-degree sectors at the [ site boundary and maximum individual receptors. For an elevated release, defined as occurring at a height that is twice the height or more of a nearby structure, credit was taken for the effective release height which l f is comprised of the physical release height plus momentum plume rise minus l t I i the terrain height at a given receptor. A building wake correction factor f was used to adjust calculations for ground-level releases. Airflow revers-l als were also accounted for by applying site-specific terrain recirculation j factors for both ground and elevted releases at the site (Albersheim, t 1978). The methodology employed in the calculation of intermittent release X/Q and D/Q values is that described in NUREG/CR-2919 (Sagendorf, et. al. 1982). The BVPS-2 continuous gaseous release points that have been eval-l l uated include the process vent attached to the BVPS-1 natural draft ccoling l ( tower, the elevated release point (containment vent), ventilatica vent, turbine building vent, condensate polishing building vent, decont autir at ion building vent, and the gaseous waste storage tank vault vent. The inter-l mittent releases are from the process vent, elevated release point (con-i tainment vent), and ventilation vent. Only the process vent was considered to be an elevated release with all other release points being treated as ~ ground-level releases. A summary of the release charr.:teristics and their locations is given in Table A-1. j Onsite meteorological data for the period January 1, 1976 through l December 31, 1980, were used as input for the annual-average calculations, The grazing season was represented by a six-month period from May 1 through i October 31 for each year of the 5 year meteorological data base. This j grazing season corresponds reasonably well with the growing season. The j data were collected according to guidance in NRC Regulatory Guide 1.23 as l described in Section 2.3 of the BVPS-2 FSAR. The parameters used in. the j X/Q-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 f t) were used for all release points except the process vent which required the use of 500-ft winds and AT (500-35 f t) which are representa-tive of the release height (510 f t). The annual-average and grazing season X/Q and D/Q values for the l 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. In the case of the \\ A-1 l f l. I

1 ( process vent releases, several of each receptor type were evaluated in each ^ downwind sector to deter cine the maximum X/Q-D/Q values. The distances of I the limiting maximum itdividual receptors from the radioactive release f points are given in Table 2.2-3. The continuc os release annual average X/Q l values at the special locations for the elevated release point (cont ainment ) vent), ventilation vent, process vent, turbine building vent, decontamina-tion building vent, waste gas storage vault vent, and condensate polishing building vent, are given in Tables 2.2-4 through 2.2-10 respectively. ) ] Continuous release annual average X/Q's for these same release points are also given at ten incremental downwind distances. Continuous release D/Q j values for these same release points are given in Tables 2.2-14 through 2.2-20 for the special locations and Tables 2.3-21 through 2.3-27 for the incremental distances. Due to their location adjacent to the containment building, the decontamination building and gaseous waste stor.' ge tank. vault X/Q's and D/Q's are the same as the containment vent X/Q's and D/Q's. Likewise, the turbine building vent X/Q's and D/Q's ap[ily to the condensate polishing building as well due to its location adjacent to the ' turbine building. Tables A-2 through A-4 contain short term X/Q values for batch releases originating from the elevated release point (containment vent), ventilation vent, and process vent releases, respectively. The values in these tables are based on 32 hours per year of containment and ventilation vent purges and 74 hours per year of process vent purges. l Albersheim, S.R., Development of Terrain Adjustment Factors for Use at the Beaver Valley Power Station for the Straight-Line Atmospheric Disper-sion Model, NUS-3173, NUS Corporation, June 1978 Sagendorf, J.F., Goll, J.T. and Sandusky, W.F. XODQDOQ: Computer Program for the Meteorological Evaluation of Routine Lifluent Releases at Nuclear Power Stations, NUREG/CR-2919, U.S. Nuclear Regulatory Commission, September, 1982. A-2

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l ( APPENDIX B INPUTS TO SW'O CODES LIQlBB AND GASIBB FOR GENERATION OF LIQUID AND GASEOUS ~ SOURCE TERM MIXES BEAVER VALLEY UNIT 2 PWR Thermal power level (megawatts) 2766.000 Plant capacity factor .800 Mass of.priaary coolant (thousand Ibs) 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 1bs/hr) 11.600 Mass of steam in each steam generator (thousand Ibs) 8.700 Mass of' liquid in each steam generator (thousand Ibs) 100.000 Total mass of secondary coolant (thousand Ibs) 2000.000 Mass of water in steam generator (thousand lbs) 298.000 Blow $own rate (thousand Ibs/hr) 22.300 Primary to secondary leak rate (1bs/ day) 100.000 Fission product carry-over fraction .001 Halogen carry-over fraction .010 Condensate demineralizer flow fraction .700 Radwaste dilution flow (thousand gpm) 7.800 GASEOUS WASTE INPUTS There is not contint aus stripping of full letdown flow l Hold up time for xenon (days) 45.800 Hold up time for krypton (days) 2.570 Primary coolant leak to auxiliary building (1b/ day) 160.000 Auxiliary building leak iodine partition factor 7.5E-3 Gas waste system particulate release fraction 0.000-Auxiliary building charcoiodine release fraction 0.100 particulate release fraction 0.010 Containment volume (million cu-ft) 1.800 Frequency of primry coolant degassing (times /yr) 2.000 Primary to secondary leak rate (1b/ day) 100.000 There is a kidney filter Containment atmosphere cleanup rate (thousand cfm) 20.000 Purge time of containment (hours) 8.000 There is not a condensate demineralizer Iodine partition factor (gas /lig) in steam generator 0.010 Frequency of containment building high vol purge (times / year) 4.000 Containment volume purge iodine release fraction 1.000 particulate release fraction 1.000 Steam leak to turbine building (1bs/hr) 1700.000 Fraction iodine released from blowdown tank vent 0.000 Fraction iodine released from main condensate air ejector 0.270 ( There is not a cryogenic off gas system B-1 m

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