Latest revision as of 20:46, 16 March 2021

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Issue 2,Rev 2 to Beaver Valley Power Station Unit 1 Odcm
	ML20246K874
Person / Time
Site:	Beaver Valley
Issue date:	06/30/1989
From:	; DUQUESNE LIGHT CO.
To:	;
Shared Package
ML20246K847	List: ML20246K843; ML20246K868; ML20246K874; ML20247A141;
References
	PROC-890630, NUDOCS 8909060148
	Download: ML20246K874 (163)
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{{#Wiki_filter:Pj 'g a T Page.1 ] , y( .L y BV-1 DDCM Changes

      #  ~'                                       Issue 2, Revisi D                                   i I. Descriptio of BV-1 ODCM Changes-
               ..l. Page i:

This revision to the Table of Contents reflects the additior of the following ODCM Sections: A. Section 1.4, Liquid Radwaste Systent (See Justification 1) B. Section.2.4, Gaseous Radwaste Systeni (See Justification 1).

2. 'Page.vii:

This revision to the List of figures reflects the addition of the following ODCH Figures: . 1 A. Figure 1.4-1, Beaver Valley Power. Statiori . Unit 1

                               ' Liquid Radwaste System (See Justification 1)'

B. Figure 1.4a2, Beaver VMley Power Station Unit 2 Liquid Radwaste System (See Justification 11 C.-figure 2.4-1, Beaver Valley Power Station Units 1 and 2' Gaseous Radwaste System (See Justification 1) D. Figure 2.4-2, Beaver Valley Pcwer Station Units 1 and 2 Gaseous Effluent Release Points (See Justification 1). L

               .3. Page 1-5:

This revi~sion corrects the following Aypos to ODCM Equation 1.1-8: ; A. Show differentiation between the two f's.(See Justification 1) B. Add the division sign (See Justification 1)

4. Page~1-12: :

This revision reflects the redefining of Fg in equation 1.3-1 as - allowed by the NRC.(See Justification 1) -)

5. Fage 1-13 and 1-14:

This revision-corrects typos to the followina: 1 A. Equation 1.3-7, add a division sign between the brackets 1 (See Justification 1) i B. Equation 1.3-8, add a division sign between the brackets (See Justification 1) ) C. Add the words "from each reactor unit" to two places. A This ensures compliance with the current requirements of the

      'Q                        Technical Specifications (See Justification 2) 1 q

8909060148 890825 ! fDR ADocg 05000334 PFC k 1 c .. . . .

Page 2 BV-1 ODCM Changes j- Issue 2. Revision 2

  !*)  6. Pages 1-18 thru l-20:
                                                                                                      )

i This ravision reflects the addition of ODCM Section 1.4 regarding the Liquid Radwaste System. (See Justification 1) I' 7. Pages 2-14 and 2-16: { v i This revision corrects typos to the following ODCM equatiens: A. Equation 2.1-20, change the MHSP to HSP multiplier from 0.70 to 0.33 (See Justification 1) B. Equation 2.1-24, change the HHSP to HSP multiplier from 0.70 to 0,33 (See Justification 'l)

8. i' age 2-19; f This revision reflects addition of Reference (7). (See Justification 3)

9. Page 2-27:

This revision adds the words "from the site". This ensures compliance with the current requiremer.ts of tr.e Technical p) RJ Specifications. (See Justification 2)

10. Page 2-32:

This revision reflects iSar.ges to the particulate and icJine radionuclides :aix for the Unit i Venti 16 tion Vent and to cerrect a typn for Yb-135m in the Containment Vacuum Pumps. (See Justification 3)

11. Page 2-43:

This revision provides re-verified Pit values for the Beaver Valley Site (See Justification 1)

12. Paoes 2-40 and 2-50:

This revisioi adds the words "from each reactor unit". This ensures ccnnpliance with the current requirereents of the Technical ! Specifications. (See Justification 2) '

13. ,Pages ?-56 c,nd 2-57:

  ,e            Thir revision reflects the correction of the defi:.ition for the t                   I

( valus in the cow-meat pathway. (See Justification 1) f

                                                                                           ._ -- _ )

(-_ t-Page 3 (y~)s BV-1 ODCM Changes fisue 2. Revision 2

14. Psge 2 .60:

This revision corrects a typo regarding correct punctuation. (See Justification 2)

15. Page2-3:

This revision cdds the words "from each reactor unit". This ensures compliance with the current requireinents of the Techniccl Specifications. (See Justification 2)

                              'l 6. Pages 2-64 thru 2-82:

This revision provides re-verified R values for the Beaver Valley Site. (See Justification 1)

17. Pages 2-97 thru 2-99:

V This revision reflects the addition of GDCM Section 2.4 regarding the Gaseous Radwaste System. (See Justific& tion 1)

18. Pages 3-2, 3-4, 3<5, and 3-8:

Tnis revh, ion corrects types. (See Justification 2)

19. Page G-4:

This revision reflects changes to the particulate and iocine release fractions. (See Justification 3) l ('T V !

_{; x Page 4 BV-1 00CM Changes Issue 2, Revision Z II. Justification of BV-1 ODCM Changes

1. A -letter dated March 2, 1989' (from the NRC)' was received by Duquesne Light regarding acceptar;ce of the Offsite Dose Calculation Manuals. The NRC' acceptance of the BV-1 ODCM was based on a Technical Evaluation "eport (TER No. EGG-PHY-8194) provided by the Idaho National Engi.neering Laboratory.

As stated in the letter, minor concerns are delineated in Section 4 of the TER. In general, these concerns are considered typos or additions and-in no way impact any of the calculations currently being performed for dose contributions. However, one of thera concerns is regarding the inability to reproduce the ODCM R values for the cow-meat, cow-milk and goat-milk pathways when using the ODCM/NUREG 0133 methodology. These R .

                            . values (along with all other ODCM R. values) were re-validated VIA Calculation Package Na ERS-ATL-80-014. The results of this package showed that the R values for the three aforementioned pathways were in error.

Since the R . values in error do not involve the controlling receptor for gaseous release (i.e.; the controlling receptor is VIA the Inhalation, Ground and Vegetation pathways, not the pathways - subject _ to error) than these changes to the ODCM will nct adversely impact the accuracy or reliability of effluent dose calculations. ' . r)

 ' t,

2. As rcquested by letters ND3NSM:3431, ND1NSM:3522, and NDlNSM;3652, Technical Specifications were required to be verified in all plant imnlemnting procedures, As pcrt of this effort, wording errors / typos were identified in various sections of the ODCM. This revision corrects the anomalies identified during the verification effort. .

3. A; delinened ir. ?ctter NDlSHP:776, dated February 12, 1988 (BVPS. l ODCM Table 2.2. 2, Appendix B) e series of apparent' discrepancies were-identified between ODCM Table 2.2-2 and similar tables of the EVPS-2 F5AR. Evaluathn showed that apparent credit was given for con'cinuous filtration of GLCRS releases which is invalid at Urtit 1. Howev6., the ceiculation p6ckage on which the BVPS-2 FSAR expected rel?ase tables are hased, is correct (i.e.; no credit was taken for routint filtratien For Unit 1 releases). Except for revising the 09CM, no furtNr t;crrective action is necessary because the pcrticui6tes end iodines in the ODCli were not used for gaceous %ffluent alarm setpcint. Therefore, tM s change does not adversely impact the accurancy or reliability of setpoint calculations.

III. Conc)uding Statement nf BV-i ODCC Changes A 1. The above just*fications ensore that the EV-1 ODCM changes will .meintain d the levtl of radioactive effluent control required by 10 CFR Q ;06, 40 { CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CfR 50 and not ar.arersely imph . the Lccuracy or reliability of ef fluent dose, or setpoint cah. datiuro, { L _-- - - - - - .

I L O BEAVFR VALLEY POWER STATION UNIT NO. I OFF-SITE DOSE g CALCULATION MANUAL l 4 I ; L

=.:_-__-_--__--_-__.-._-_______-_________________

DUQUESNE LIGHT CO!!PANY

ODCM Review and Approval Sheet BV-1 ODCM Adtrin. Issue Rev. Pgs. RSC Review OSC Review Approv. Eff. No. No. I s.c d . Meeting No. Date Mr.eting No..! Data Sign. Date Date June Q,g* %g gygg J 30 i 2 Tftle BV-RSC- May BV-0EC- i ur.e i 12-89 25 13-89 15Q h[y 1989 1989 1989 1-1 thru 1-20 2-1 thru

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No. Issd. Sign. Date Review Date Sign. Date Date 0 TITLE PGS BV-RSC-11-87 BV-OSC-17-87

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                             .i thru viii   BV-RSC-12-87          June 12, 1987         -

7/24/87 1 -1 thru 1-17 BV-RSC-14-87 ~ 7[/6[18- )

                            ;2-I thru 2-96 'May 29, 1987 3 .1 thr': 3-14        gpp 4.1, 5-l' A-1 thru A-7 B-1 thru B-4 1       2-11       BV-RSC-38-87          BV-1-0SC-25-87             y      12/22/87

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Rev. l' Pgs. Tech. Rev. OSC Approv. Eff. W. Issd. Sign. Date Review Date Sign. .nate D ?. t e j Rev. 1 111 E M Y A1 V ~ "' 0"i J

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                         %,                                                     'DUQUESNE LIGHT COMPANY' Beaver Valley Power Station Unit.1
                                                                                      . Docket'No. 50-334 3
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i.y i BEAVER VALLEY POWER STATION UNIT 1 ll OFF-SITE DOSE CALCULATION MANUAL-l .;. (ODCM) i = - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ .__ . _ _ - !

BV-1 CDCM TABLE OF CONTENTS ['

     '[   'Section Title                                                                               Page Table of Contents                                                                   i List of Tables                                                                      11 List of Figures                                                                     vii Preface                                                                             vili I0  LIQUID EFFLUENTS                                                                    1-1 1.1   Monitor Alarm Setpoint Determination                                          1-1 1.2 Compliance With BVTS 3.11.1.1                                                   1-8 1.3 Compliance With 10 CFR 50 (Liquids)                                             1-11 1.4 Liquid Radwaste System                                                          1-18                   l6/89 2.0  GASEOUS EFFLUENTS                                                                   2-1 2.1 Monitor Alarm Setpoint. Determination                                           2-1 2.2 Compliance With 10 CFR 20 (Gaseous)                                             2-20 2.3 Compliance With 10 CFR 50 (Gaseous)                                             2-44 2.4 Gaseous Radwaste System                                                         2-97                   l6/89 3.0   RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM                                       3-1 I

y ) 4.0 INFORMATION RELATED TO 40 CFR 190 4-1 5.0 SITE BOUNDARY FOR GASEOUS AND LIQUID EFFLUENTS 5-1 Appendix A Summary of Dispersion Calculational Procedures A-1 Appendix B Inputs to GALE Code B-1 (~ i ISSUE 2 REVISION 2

           .T*
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$1 ,. m.                                         SV-1 0DCM n

List of Tables j'~'j . Table No. Title- Page No.

   .y 1.1-1       Liquid Source Terms                                                          1-6 1.2-1       Recirculation Times _ Required Before Sampling of                            1-10 Liquid Discharge Tanks 1,3-1       A g

Values for an Adult for the Beaver Valley Site 1-15

                .2.1-1      Radionuclides Mix for Gaseous Effluents-                                     2-17
               ,2.1-2       Monitor Detector Efficiencies.                                               2-18 2.2-1       Modes of Gaseous Release from Beaver Valley Site                             2-31 Vents for Implementation of 10'CFR 20 and 10 CFR 50 2.2-2       Radionuclides Mix for Gaseous Effluents from the                             2-32 Beaver. Valley Power Station, Unit 1 (Ci/Yr) 2.2-3       Distances of Limiting Maximum Individual Receptors to                        2-33 Release Points for Annual X/Q Values 2.2-4       Beaver Valley Site Containment Vents Annual Average,                         2-34 G ound Level, X/Q Values. For Continuous Ground
                           ' Level Releases, for Special Distances (Identified in Table 2.2-3) and Selected Control Locations.

2.2-5 Beaver Valley Site Ventilation Vents Annual Average, 2-35 Ground Level, X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control' Locations. 2.2-6 Beaver Valley Site Process Vent Annual Average, 2-36 Ground Level, X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control Locations. 2.2-7 Beaver Valley Site Turbine Building Vents Annual 2-37 Average Ground Level, X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control Locations. 2.2-8 BVPS-2 Decontamination Building Annual Average, 2-38 Ground Level X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control Locations.

    . s~~g U                                                  11                                         ISSUE 2 REVISION 2

BV-1 DDCM List of. Tables-(Continued) G Table No. Title- Page No. , lj ' h- _2.2-9 BVPS-2 Waste Gas Storage Vault Vent Annual Average, 2-39 Ground Level X/Q Values. For Continuous Ground L Level Releases, For Special Distances (Identified in L Table 2.2-3) and Selected Control Locations. 2.2-10 BVPS-2 Condensate Polishing Building Annual Average, 2-40 Ground Level X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control Locations. 2.2-11 Dose Factors for Noble Gases and Daughters 2-41 i 2.2-12 Dose Parameters for Finite Elevated Plumes, Beaver 2-42 Valley Power Station Site. 2.2-13 P Values for a Child for the Beaver Valley Site 2-43 1 2.3-1 Modes of Gaseous Release Form the Beaver Valley 2-63 Site Vents for Implementation of 10 CFR 20 and 10 CFR 50 2.3-2 R Values for the. Beaver Valley Site (Inhalation, 2-64 Adult) l 2.3-3 R Values for the Beaver Valley Site (Inhalation, 2-65 l( Teen) 2.3-4 R Values for the Beaver Valley Site (Inhalation, 2-66 Child) 2.3-5 R Values for the Beaver Valley Site (Inhalation, 2-67 Infant) 2.3-6 R Values for the Beaver Valley Site (Ground Plane) 2-68 2.3-7 R Values for the Beaver Valley Site (Vegetable, 2-69 Adult) l l 2.3 R Values for the Beaver Valley Site (Vegetable, 2-70 Teen) 2.3-9 R Values for the Beaver Valley Site (Vegetable, 2-71 Child) l

               ~2.3-10'           R Values for the Beaver '/ alley Site (Meat, Adult)                                                                                       2-72 2.3-11            R Values for the Beaver Valley Site (Meat, Tecn)                                                                                          2-73 2.3-12            R Values for the Beaver Valley Site (Meat, Child)                                                                                         2-74 L   -

lii ISSUE 2 REVISION 2 l l' _ . _ _ _ _ _ _ _ _ _ _ _ _____.___.________________________________a

ll l: BV-1.0DCM List of Tables (Continued)' [ -Table No. Title Page No. N 2.3-13 R Values for the Beaver Valley Site (Cow Milk, Adult) 2-75' 2.3-14 R Values for the Beaver Valley Site (Cow Milk, Teen) 2-76

      -2.3-15     R Values for the Beaver Valley Site (Cow Milk, Child)                                                       2-77 2.3-16     R Values for the Beaver Valley Site (Cow. Milk,                                                             2-78 Infant) 2.3-17. R Values for the Beaver Valley Site (Goat Milk,                                                             2-79.

Adult) 2.3-18 ' R Values for the Beaver Valley Site (Goat Milk, Teen) 2-80 1 2.3-19 R Values for the Beaver Valley Site (Goat Milk, 2-81 Child) 2.3-20 R Values for the Beaver Valley Site (Goat Milk, 2-82 Infant)' 2.3 Beaver Valley Site Process Vent Dispersion Parameters 2-83 (D76),m' , for Continuous Elevated Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 2.3 Beaver Valley Site Containment Vents Dispersion 2-84 Parameters (D/Q), m~ , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 2.3-23 Beaver Valley Site Ventilation Vents Dispersion 2-85

Parameter (D/Q), m , for-Continuous Ground Level l Releases > 500 Hrs /Yr or > 150 Hrs /Qtr l 2.3-24 Beaver Valley Site Turbine Building Vents Dispersion 2-86 Parameters (5),m' , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 2.3 -25 Beaver Valley Unit 2 Condensate Polishing Building 2-87 VentDispersionParameters(D7Q),m' , for Continous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 1 l l i O iv ISSUE 2 1 J l REVISION 2 1 i

BV-1 ODCR List of Tables (Continued)

             , Table No!     Title                                                                                                               Page No.

2,3-26 : Beaver Valley. Unit 2 Decontamination Building Vent 2-88

                                                                          ~   ~

Dispersion Parameter (ii[Q), m , for Continuous

                           . Ground Level Releases > 500 Hrs /Yr or >.150 Hrs /Qtr 2.3-27     Beaver Valley Unit 2 Waste Gas' Storage Vault Vent                                                                  .i-89 DispersionParameters(5),m' , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr 2.3-28     Beaver Valley Site Process Vent Dispersion Parameters                                                               2-90 (D/Q), m ', for Continuous Elevated Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Specia: Distances (Identified in Table 2.2-3) 2.3-29   Beaver Valley Site Containment Vents Dispersion                                                                     2-91 Parameters (D/Q), m~ , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) 2.3-30   Beaver Valley Site Ventilation Vente Dispersion                                                                     2 92 O                                                     -2
     -h~

Parameter (D/Q), m , for Continuous Ground Level Releases > 1500 Hrs /Yr or > -150 Hrs /Qtr for Special Distances-(Identified in Table 2.2-3) 2.3-31 Beaver Valley Site Turbine Building Vents Dispersion 2-93 Parameters (5),m~ for Continuous Gr. .nd Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) l .' i I 2.3-32 Beaver Valley Unit 2 Condensate Polishing Building 2-94

                                                                                                 -2 Vent Dispersion Parameter (D/Q), m , for Continous Ground Leval Releases > 500 Hrs /Yr or > 150 Hrs /Qtr l                              for Special Distances (Identified in Table 2.2-3) 2.3-33   Beaver Valley Unit 2 Decontamination Puilding Vent                                                                   2-95 DispersionParameter(D7Q'),m' , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) v                                                             ISSUE 2 REVISION 2 L                                                                                           _        _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

t i BV-l'0DCM List'of Tables (Continued)

q)v

Table No. Title. Page No.

              - 2,3    Beaver Valley Unit 2 Waste Gas Storage Vault Vent                          '2-96 Dispersion Parameter (D/Q),'m' , for Continuous. Ground Level Releases > 500 Hrs /Yr or >'150.. Hrs /Qtr for Special Distances (Identified'in Table 2.2-3) 3.0-1       Radiological Environmental Monitoring Program                                3-2 A-1.        Beaver Valley Site Release Conditions.                                       A-3 A-2        . Beaver Valley Site Containment Vents Dispersion                             A-4 Parameters (X/q), sec/m', for Ground' Level Releases
                           < 500 Hrs /Yr or < 150 Hrs /Qtr for Special Locations (Ide'ntified in Table 2.2-3)

A-3 . Beaver' Valley Sito Ventilation Vents Dispersion -A-5

                          -P.o smeters (X/q),.sec/m3 for Batch Ground Level
                          .Ar':2 2ses < 500 Hrs /Yr or < 150 Hrs /Qtr for Special L ations (Identified in Tabic 2.2-3)

A-4 Beaver Valley Site Process' Vent Dispersion Parameters ~ A-6

                          -(X/q), sec/m',-for Batch Elevated Releases 5 500 Hrs /Yr or 6 130 Hrs /Qtr for Special Locations (Identified in
                          . Table 2.2-3)

A-5 . Beaver Valley Site Process Vent Dispersion Parameters A-7 (5),sec/m',forBatchEle"atedReleases5500or 5 150 Hrs /Qtr for.0.5 mile intrements l l 1 I i l 1 !Q vi ISSUE 2 ) REVISION 2 I

                                                                          .-____--___.-__.--_--_____l-_-_-__-.-_-_-_-_---_- J

BV-1 ODCM act Of Figures (~ No. Title Page (_,)/ ~~" 1.4-1 Beaver Valley Power Station Unit 1 Liquid Radwaste System 1-19 1.4-2 Beaver Va?. ley Power Station Unit 2 Liquid Radwaste System 1-20 2.4-1 Beaver Valley Power Station Units 1 and 2 6/89 Gaseous Radwate System 2 2.4-2 Besver Valley Power Station Units l'and 2 Gaseous Effluent Release Points 2-99 3.0-1 Radiological Environmental Monitoring Program - Air Sampling Locations 3-6 3.0-2 Radiological Environmental Monitoring Program - TLD Locations -- Northwest Quadrant 3-7 3.0-3 Radiological Environmental Monitoring Program - TLD Locations -- Northeast Quadrant 3-8

                             -3.0-4  Radiological Environmental Monitoring Program -

TLD Locations -- Southeast Quadrant 3-9 r% () 3.0-5 Radiological Environmental Monitoring Program - TLD Locations -- Southwest Quadrant 3-10 3.0-6 Radiological Environmental Monitoring Program - Shoreline Sediment, Surface Water, and Drinking 3-11 Water Sampling Locations 3.0-7 Radiological Environmental Monitoring Program - Milk Sampling Locations 3-12 3.0-8 Radiological Environmental Monitoring Program - Foodcrop Sampling Locations 3-13 3.0-9 Radiological Environmental Monitoring Program - Fish Sampling Locations 3-14 l 1 L l

   <-ss
    ~s vii                      ISbUE 2 i-REVISION 2                           ,

1. I l

____-_-_-_-________-_____-_____.______D

BV-1 ODCM PREFACE O' This Offsite Dose- Calculation Manual (00CM) provides .the information and methodologies to be used by Beaver Valley Power Station Unit I (BVPS-1) to

        . assure- compliance -with        certain porticas of BVPS-1 ' operating. Technical Specification.       These portions are those related .to                                              liquid and gaseous radiological offluents. They are intended to show complianct 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 PWR's (NUREG-0472, . Draft)",    " Preparation           of                                    Radiological E f flu'ent                                           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 operating staff of BVPS-1 to assure compliance with Technical Specifications..

The ODCM has been prepared as generically as possible in order to minimize the need for futuro versions. However, some changes to the ODCH will be expected in the future. Any such changes will be. properly reviewed and approved as indicate.d in the Administrative Control Section, Specification 6.15.2 of the BVPS-1 Technictl' Specifications. l l O vili ISSUE 2 REVISION 2 L___-________-____----__-_-_--___-----_. _ _ - _ - _ _ _ _ _ _ - _ - _ _ - - - _ _ - - _ _ _ _ _ - _ _ - _ - - - - - _ _ _ - _ - - _ _ - _ - - - - - - - -

BV-1 ODCM 1.0 LIQUID EFFLUENTS [s)

 \- /

Beaver Valley Units 1 and 2 utilize the concept of a shared liquid radioactive waste system according t. NUREG 0133. This permits the mixing of liquid radwaste for processing a.d allocating of dose due to release se defined in Section 1.3. In Section 1.A effluent monitor setpoints for a conservative mix are based on thc individual Units' specific parameters, but effluent monitor setpoints for analysis prior to release permit use of the total dilution flow available at the Site. It must be noted differences exist between setpoint presentations of the radiation monitoring systems of BVPS-1 and BVPS-2. There is a conflict in setpoint terminology. Where BVPS-1 uses HIGH and HIGH-HIGH the BVPS-2 equivalents are ALERT and HIGH. Also thers is the difference that BVPS-2 l setpoints are -presented in pCi/ml rather than CPM as in BVPS-1. This I difference is due to software which applies a conversion factor to the raw data (CPM). -Note that the pCi/ml presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factors. Therefore, Unit 2 setpoints determined on analysis prior to release will be correct for properly controlling dose rate but the indicated pCi/ml value may differ from the actual value. 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 concentration; f'"T specified in 10CFR20, Appendix B Tabic II, Column 2 for radionuclides other (_) than dissolved or entrained noble gases or exceeds a concentration of 2 E-4 pCi/ml for dissolved or entrained noble gases. The methodology described in Section 1.1.2 is ar alternative method to be used to determine the monitor high-high alarn setpoint (HHSP). The methodology in Section 1.1.2 may be used for any bstch ..elease and shall be used when the total gamma activity concentration ot the liquid effluent prior to dilution exceeds 1.49E-4 pri/ml. This concentration is equivalent to the HHSP's of 1.69 E4 nepm and 8.46 E4 ncpm (net counts per minute) deriv-ed in Section 1.1.1 and allows for a tritium concentration up to 1.5E-1 pCi/mi. 1.1.1 Serpoint Determination Based on a Conservative Mix The high-high alarm setpoint for the Liquid Waste Effluent Monitor (LW-104) should be set at 1.69E4 ncpm and the high-high alarm setpoint for the Liquid Waste Contamination Monitor (LV-116) should be set at 8.46E4 ncpm. These setpoints are based on the following conditions: Source terms given in Table 1.1-1. These scurce terms have been generated from the computer code GALE, Revision 0 (NUREG-0017). The inputs to GALE are given in Appendix B. Dilution water flow rate of 15,000 gpm. A k-1-1 ISSUE 2 REVISION 2

BV-1 ODCM

Dischar:ge flow' rate prior to dilution of 50 gpm for the Liquid Waste Effluent Monitor (LW-104),

  -    3

.I l' d

Discharge flow rate prior to dilution of 10 gpm for the Liquid Waste Contamination Mor.itor (LW-116)

The above setpo!nts can be varied based on actual operating conditions resulting'ir changes in the disebarge and dilution flow rates as follows: HHSP = 56.3 F g, where: HHSP = Monitor high-high alarm setpoint above background (nepm) 56.3 = Propcetionality constant based on nominal flow conditions (56.3 = 1.69 E4 ncpm x 50 gpm + 1.5 E4 gpm for LW-104 or 56.3

                                   = 8.46 E4 ncpm x 10 gpm + 1.5 E4 gpm for LW-116).

F = Dilution water flow rate (gpm) BVPS-1 Cooling Tower Blowdown Rate (not including BVPS-2 Blowdown or the BV-2 release out through the Emergency Outfall Structure), f = Discharge flow rate prior to dilution (gpm) 1.1.1.1 The " mix" (radionuclides and composition) of the liquid effluent was fq determined as follows: V a. The liquid source terms that are representative of the " mix" of the liquid effluent were determined. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from Table 1.1-1.

b. The fraction of the total radios,:tivity in the liquid effluent comprised by radionuclides "1" (S ) for each individual radionuclides in the liquid effluent was determined by equation 1.1-2.

A S f (3,1,3) g I Ag i where: A j

                              =    Annual release of radionuclides "i" in the Jiquid effluent from Table 1.1-1.

1.1.1.2 The maximum acceptable total radioactivity concentration in pCi/ml of all radionuclides in the liquid effluent prior to dilutic,n (C ) was determined by: p 1-2 ISSUE 2 REVISION 2

.q-BV-1 ODCM r

C =

(1.1-3) g' ,. O fI i i MPC j where: F = ! Dilution. water flow rate (gpm) BVPS-1 Cooling Tower Blowdown Rate (not including BVPS-2 Blowdown or the BVPS-2 release out through the Emergency Outfall Structure)

                                             =     15,000 gpm f           ~=     Maximum acceptable discharge flow- rate prior to dilution
                                                 '(gpm)
                                             =     50    gpm for Lig"if Waste Effluent Monitor (LW-104)
                                             =     10    gpm for Liquid Waste Contamination Monitor (LV-116)

MPC = Liquid effluent radioactivity f concentration limit for radionuclides "1" (pCi/ml) from Table 1.1-1 or if not listed in Table-1.1-1, obtained from Reference 3. S g

                                             =     The    fraction      of     total      radioactivity                      attributed   to radionuclides "i" (from Equation 1.1-2).
~;                     1.1.1.3  The . maximum acceptable radioactivity concentration in pCi/ml of-radionuclides '"i" in the liquid effluent prior to dilution (C ) was

( . determined by: f Cg =S g Ct (1,1-4) 1.1.1.4 The calculated monitor count rate in nepm above background attributed to the radionuclides, C.R., was determined by: C.R. = I Cg Eg (1.1-5) i where: E. = Detection efficiency of the monitor for radionuclides "i" (cpm /pci/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from Reference 4. 1.1.1.5 The monitor high-high alarm setpoint above background (nepm) should be set 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 release from more than one source. p. b 1-3 ISSUE 2 REVISION 2

BV-1 ODCM 1.1.2 Setpoint Determination Based on Analysis Prior to Release i l .The following method. applies te liquid releases when determining the J

     ' O(N                setpoint for the maximum acceptable discharge flow rate prior to dilution L                          and the associated high-high alarm setpoint based on this, flow rate for the-

' Liquid Waste Effluent Monitor (LV-104) and the Liquid Waste Contamination Monitor (LW-116) during all operational conditions. l 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 I it. crease in tha mnitor alarm setpoint, the allowable discharge flow rate is reduced by the same factor. When the discharge flow rate is limited by the radwaste discharge pump rate capacity or by administrative selection rather than the allowable' flow rate l determined from activity concentration, the alarm setpoint will be proportionally adjusted based upon the excess dilution factor provided. 1.1.2.1 The maximum acceptable discharge flow rate (f) prior to dilution (in gpm) is determined by: f = C (1*I'0) I 1.25 I i MPC f p' where:

     't F                                      =                                     Dilution water flow rate, BVPS-1 Cooling Tower blowdown (gpm)

The dilution water flow rate may include the combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges ere administrative 1y prohibited. Cy = Radioactivity concentration of radionuclude "i" in the liquid effluent prior to dilution (pCi/ml) from analysis of the liquid effluent to be released. Note: If the radioactivity of a radionuclides is below the LLD value specified in Table 4.11-1 of. the BVPS-1 Technical Specifications, the radionuclides should not be included as a source term in this setpoint calculation. 1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response. MPC = The liquid effluent radioactivity concentration limit for f radionuclides "i" (pCi/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from Reference 3. O 1-4 ISSUE 2 REVISION 2

u BV-1 ODCM 1.1.2.2 The calculated monitor. count rate (in ncpm) above background attributed . . . _ . to the. radionuclides (C.R.) is determined by: i N -) C.R. = 1.25 I Cy Cf (1.1-7) I where: E f

                         =     The ' detection efficiency of the monitor for radionuclides "i" (cpm /pCf/ml) from Table 1.1-1 or if not listed in Table.l.1-1 from Reference 4.

1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor-response. 1.1.2.3 The liquid effluent monitor high-high alarm setpoint above background (nepm) should be set at the C.R. value adjusted by any excess dilution

            ' factor provided as defined in the following equation:

HHSP = C.R.f, (1.1-8) 6/89 f where: HHSP = Monitor high-high alarm setpoint above background Calculated monitor count rate (in nepm) from 1.1-7

  /'"3              C.R. =

V f = Maximum acceptable discharge flow rate prior to dilution determined by equation 1.1-6 f' = Actual maximum discharge flow rate to be maintained for the i discharge. The reduced value of f may be due to pump l 6/89 - limitations or administrative selection. 1-5 ISSUE 2 REVISION 2 s

4 "f(- " E

',)

Yl NC m ON/ _ ? I Ei 7 7 37 887 663 87 7 4567 888888888887. 7 80 TI C EEEEEEEEEEEEEEEEEE E EE EEEE EEEEEEE - E CC 3 7 00292467 4 7 2 04 7 7 1 0996 7 5 1 3 62 2 5 1 4 O EI A 082 01 7 1 3 582403 1 391 3 001 7 04 02 0627 TF m . . . . . . . EF p 1 8591 1 51 7 ' 1 295451 1 1 1 1 1 2 1 22 1 .3 7 51 DE c - (

3 (

l m M / R 1 34455546565 5 3545465 7 56656655557 E C - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - T p EEEEEEEEEEEEEEEEEEE - EEEEEEEEEEEE - E ( 21 8S931 32 3S43S22834 32 81 2 946222 1 E - C i R C U P _ O M S D _ I _ N} U

                     .Q I

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                          -     2

( 1 1 ) _ i E C L ( B _ A E T _ S A E 555544555553353554552 33253233553 1 2 L - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - E EEEEEEEEEEEEEEEEEE EEEEE EEEEEEEEEEE R 92 B57 6I 2 I 07 1 37 5 5 927 5 891 08001 1 4 00

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I m m m s

_ L . 9 m7 7 9901 1 1 2 2344567 00 r C 1 459803 3 691 99222 23333331 13 131 31 13 131 344 eL 1 1 1 1 1 1 1 1 1 h A3 U 5555 5 62 8889991 _ N - - - - - - - - - - - - - r n eeooprb r roceeee1 eeI eI I I s1 s s aaOO1

                                                                                         -   - -   -  -   -  -  -  -     - - - - - - - - - t O

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h*!_ i , gy.1 ODCf! REFERENCES J (' Liquid Effluent'tionitor Setpoints L' Q} 4 (1) '.' Beaver Valley Power- Station, Appendix I Analysis - Decket No. 50-334'and 50-412", Table 2.1.3. U (2) " Beaver Valley- Power Sta' tion, Appendix I Analysis - Docket No. 50-334 and 50-432",: Table 2.1.2'. (3) 10CFR20, Appendix B,. Table'.II, Column-2 and footnotes.

                     .(4) "Duquesne Light .Co., Beaver Valley Nuclear Plant,. Specification No. BVPS 414. Table V Nuclide Data, 5/30/74", Table 2 and Figure 1.

{

  'O                                                                           1-7                                  ISSUE 2 1

REVISION 2 )

h L l BV-1 ODCM l b =1.2 Compliance.with BVTS 3.11.1'.1 L . (7

 - ([

Only nuclides for which activity concentrations are above the LLD's specified in Table 4.11-1 of Technical Specification 3.11.1.1 are coasidered 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 1 Technical.

Specifications (BVTS). In order to assure' representative 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 accomplished by recirculating the tank contents for at least the time periods indicated in Table 1.2-1. The Beaver Valley Power Station Unit 1 (BVPS 1) will show l compliance with BVTS 3.11.1.1 in the following manner: The activity of the various radionuclides in the batch release, determined in accordance with Table 4.11-1, is divided by the minimum dilution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation: C R f Conc g = MDF (1.2-1)

  /N Q        where:

Concg = concentration of radionuclides "i" at the unrestricted area, pC1/ml; Cg = concentration of radionuclides "i" in the potential batch release, pCi/ml; R = release rate of the batch, gpm; MDF = minimum dilution flow, gpm. (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are administrative 1y prohibited) The projected concentrations in the unrestricted area are compared to the concentrations in Appendix B, Table II of 10 CFR 20. The most common MPC f concentrations are listed in Table 1.1-1 and were taken from Appendix B, Table II of 10 CFR 20. Before a release is authorized, Expression 1.2-2 must be satisfied. I f (Coneg/MPC ) s 1 (1.2-2) where: MPC. = maximum = permissible concentration of radionuclides "i" from Appendix B, Table II of 10 CFR 20, pCi/mi 1-8 ISSUE 2 REVISION 2

BV-1 ODCM 1.2.1.2 Postrelease L

 , r4

_,, The concentration of each radianuclide following release from the batch tank

      \*) ' '                     will be calt.ulated in thn unrestricted area in the following manner:

The average is divided by the actual dilution flow-activity of radionuclides "i" during the time perio during _the period r. f release to obtain the concentration in the ie shown in the following equation: unrestricted arsa. Thi calculation is Cone g=C ik tk (1.2-3) ADF k where: Conc = the E concentration of radionuclides "1" at the unrestricted area, during the release peried of time k, pCi/ml;

                                      . Note:

Since discharge is from an isolated well-mixed tank at essentially and a uniform rate, the difference between average peak minimal. concentration within any discharge period is C = ik c ncentration of radionuclides "i" in batch release daring time period k, pCi/ml; V = v lume tk f tank released during time period k, gal;

.[

ADF k

                                               =
   '%                                              actual volume release   k, gal. of dilution flow during the time period of-To show compliance with BVTS 3.11.1.1, the following relationsh2p .:.ust                               bold:

I g(Coneg/MPCf ) 5 1 (1.2-4) i 1.2.2 Continuous Continuous If they did releases of liquid etfluents do not presently occur at the BVPS. unrestricted area occurwould the concentration be calculated of various radionuclides in the using Equation 1.2-1 with C g, the concentration of isotope i in the continuous release. To show compliance with BVTS 3.11.1.1, Expression 1.2-4 must again hold. () 1-9 ISSUE 2 P,EVISION 2 {. I _ _ _ _ _ _ _ _ _ _ _ _ _ _

!?

BV-1 DCB1 as a.

                                                                                                                      -TABLE'1.2-I
                                                                                                                                                                              )
                                                                                                                                                                              .i
    ;fN                                                                                   RECIRCULATION TIMES REQUJRED BEFORE SAMPLING-0F' LIQUID' DISCHARGE TANKS 7

7 Name' , (by Operating Macual) Mark No. -Approx. Recire. Time d-1

                                                                                                                                                            ;(hrs)-

Laundry and. Contaminated -) 5hower Drain Tanke ILW-TK-6A & 6B '4.5" Low Level Waste Drain Tanks ILV-TK-3A & 3B 2, 5"

x. u High Level Waste, Drain Tanks

a ILV-TK-2A & 2B t

~^

Evaporator Test Tanks 8 ILW-TK-5A & SB 2' Steam Generator Drain Tanks ILW-TK-7A & 7B 11;5 8 Boron Recuvery; Test' Tank's 1BR-TC-2A & 2B 9.7 a From EVI'S-1 Operating Manual, Chapter 17, Section 4 b Derived from information in BVPS-1 Operating Manual, Chapter 8, Section 1 c Not normally e direct source of discharge d The tim's e listed with'one recirculation pump in operation.are those required for M recirculations of a ful Partially full tank recirculation times are -directly proportional occupied by the entrained Idq>. tid waste af ter isolation. to the fraction of the tank capacity l i 1-10 ISSUE 2 REVISION 2 u_ _ _ _ _ _ _ _ _ _ _ _ - - _ - - - - - - - - - - - - - - - - - - - - - - - - )

_ _ _ _ _ z ~ y,7 is-L L UV-1 ODC.'!

                                                         -1.3 Compliance yith 10 CFR 50 (1,icuidd                                          _

E6 Beaver ' Valley : Unitu 1 and 2. utilize

                                                                ' radioactive waske system according to NUREG 0133.the -concept of e shared liquid                                                       j q;jg)s                                                         .the _11guld. radwaste for processing.                                                                    This permits mixing of           I h
        '\-6;                                                    cannot accurncely be" ascribed                                                              Since'the resulting  effluent release to' a specific ter: tor unit, the treated-
                                                               . effluent releases are allocated as defined be?ow.

1. 3 ; l tumulation'of Doses The dose . contribution from the telease of 11gu e) effluents will be calculsted monthly summation; of the for each batd. relesse auring the mor)tb and a cumulative calendar month, current calendar cuarter, and the calendartotal. body' an

                                                                                                                                                                                 . year   to' _ da+.e .

The dose contribution will be: calculated using the following equatfor.: m b = UAF I A g I At C F i P=1 k k (1*3'1) where: D = I t'ne .cumulativa dose commitment to, the total body'or any organ, tr m from tin liquid effluents for the total time period I at k ' "#*" 5' kul At ' k thn length of the kth release over which C averaged for a11' liquid releases , hourr.; 1k c.nd'Fk "#* C. c

                                                                                 =                                 the
                                                                         ^*

10, i Jtaverage concentration of radionuclides, "i", in undiluted effluent during t i ne period At sni s.se uCi/ml; p from cny liquid A C I* the site relatel ingestion dose commitment factcr tu the total body or any organ.t and beta. emitter, crem+ml per hr-pC1;for each identified principal gam m = number of releases contributing to the cumulative dose, D T UAF = unit allocation factor. Provides apportionment of dose between Units 1 and 2. Normally set et 0.5 for each unit. (Murt total to 1.0) L. l; l

        '          ~

1-11 ISSUE 2 REVISION 2 s l _ _ . _ _ _ . _ _ _ _ _- - - - - - - - - - - - - - - - - - - - ~ " ~ ~

m

 +'    F;                                                                                             ;y
          >                                                                                           '1 i

BV-1 ODCM

F = the near . field average dilution. factor for C g during any k liquid effluent release. Defined as the rat io of the nerage l6/89 ([ undfluted liquid waste flow to the product of th9 everage flow from the site discharge structure during the report l period to unrestricted receiv!ng waters, times 3. -(? is the 6/89 ~I site specific applicable factw! 03- the mixing effect of the BVPS-1 discharge stru c ure).

                                   =             Waste Flow (3)(Dilution water flow)

The site specific applir.able factor of 3 results in a conservative estimate of the near field dilution fartor cased upon Ro;ulatory Guide 1.113 methodo)qy and is a f actor of ten below the lir it specified in NUREG-0133, Section 4.3 The dose factor A g was calculated for an adult for car.h isotope using the following ecuation frc.a NURF.G-0133. Ag = 1.14E3 (730/D + 21BF f)DF h (1.3-2) where: 1.14E5 = 1E6 pH 7. 1E3 m; x 1 yr yGi 1 3760 hr 3 130' = adult water consump:f on rat.3, liters /yr; D = far field dilution factor from !.he near ffsid area within one gaarter mile of the release point to the potable water intake for adult water consumption; 21 = adult fish consumption, kg/yr; i. BF = bioaccumulation factor for radicauclide "1" in fish frun I Table A-1 of Regulatory Guide 1.109 Rev. 13 pCi/kg per pCi/1, (if none, R.G. 1.109 Rev. 0);

                          =  dose conversion factor for radionu 14ta "1" for adults for a DF'T

, pcrticular organ t from Table E-11 of Regulatory Guide 1.109 i l Rev. 1, mrem /pC1, (If none, NUREG-0172 or R.G. 1.109 Rev. l 0). l l l l i b 1-12 ISSUE 2 REVISION 2 (

BV-1 ODCN A table of Ag values ~ft--an ahlt at the BVPS-1 are presented in Table 1.3-

 '[A]..s

1. The far field dilution facter (D ) for the BVPS is 200. '"his

                                                                                                                                                     .                  value is
                    ' boed on a total dilution factor cf 600 applic. ele to the Midland watw intahe 19ctittd 1.3 miles. downstream and en the oppos::e bank from the BVPS (ie. 200 = 500 + 3). The total dilution fastor of 600 represents a conservative fully mixed annual average condition. Since the hidland intake is loceted on the opposite bank and is below the water surface, essentially fully mixed c.onditions would havo 1.o exist for the radioactive effluent to be transported to the intake.

The vurulacive doses (from each reactor uxit) for a calendar quarter and a l6/89 calendr. year are compared to the following BVPS-1 Technical Specification 3.11.1.2 limits: For the calendar quarter, D 5 1.5 mrem total L N y (1.3-3) D 5 5 :arem any organ (1.3-4) For the calendar year, D 5 3 mrem total body (1.3-5) D 5 10 mrem any organ (1.3-6) g Tf any of the limits in Expressions 1.3-3 through 1.3-6 are exceeded a Special Report pursugnt to both Section IV.A of Appendix I of 10 CFR 50 and T.S. 3.11.1.2.a must ba filed with the NRC at the identified locations. 1.3.2 Projection of Doses (Liquids) Doses due to liquid releases shall be projected at least once per 31 days in

                     .accordance with EV-1 TS 4.11.1.3.1 and this section.                                                    The Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in each liquid waste batch prior to its discharge in accordance with BV-1 TS 3.11.1.3     when the projected doses due to liquid effluent releases from each                                                                                     6/89 reactor unit, when averaged over 31 days weul ' exceed 0.06 mrem to the total body or      0.2 mrem to any organ. Doses use' in the projection cre obtained according to equation 1.3-1. The 31-day dose projection shall be performed according to the follcwing equations:

When including pre-release data l 'A + B" (1 3-7) l D = + 33 - T d 1-13 ISSUE 2 REVISION 2 ; l l _ _ _ _ _ _ _ _ _ _ _._._______________________J

BV-1 ODCM When not including pre-release data

_i t' ) A (1.3-8) 6/89 V D = - 31 + C 31 _T, where: D 37

                                         =    Projected 31 day dose, mram A    =    cumulative dose for quarter, mrem B.   =    Projected cose from this release, mrem T    =    Current days into quarter Value.which may be used to anticipate plant trends, mrem C    =

O 1 0 1-14 ISSUE 2 l REVISION 2 i 1 l I l

    ,            '1               .
    +,                           E                                                          3y.1 ODCM TABLE 1.3-1 1

V) , t A h l'ALUES FC THE ADULT FOR THE ilEAVER VALLEY SITE (mrem /br per pCi/mi) NUCl.bE BONE LIVER T-BODY THYROID FIDNEY LUNG GI-LLI

                                                                                        ~                                      ~              '
                                                    ~ '~~~~~~            ~

I U-3 6!555-61 ~~5 555-bi~'3Ih55255~~3!fb5285 ~5.5655UI~~3$56E-55~~3If5E 65~

                                                 -C-14            3.13E 04 6 26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 Nn~24           4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.00E 02 9 08E 02 4.08E 02 P-32            4.62E 07 2 87E 06 1.79E 06 0 00E-01 0.00E-01 Or00E-01 5 19E 06 CR-51           0.00E-01 0.00E-O?.           1.27E 00 7.62E-01 2.81E-01              1.6?E 00 3.21E 02 MN-54           0.00E-01 4.38E 03 8 35E 02 0.03E-01                        1.30E 03 0.00E-01 .1.3dE 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 O2 0.00E-01 0 00E-01 2.54E 02 2 61E 02 FC-59           1.04E 03 2.45E 03 9.38E 02 0.00E-01 0.00E-01                         6.83E 02 8.15E 03

____---____________-__-__...._____________.____________-_._____________e_______ CO-57 0.00E-01 2 10E 01 3 50E 01 0.00E-01 0.00E-01 0.00E-01 5.33E 02 CD-58 0.00E-01 8.95E 01 2.01E 02 0.00E-01 0.00E-01 U.00E-01 1.81E 03 0.00E-01 2.57E 02 5 67E 02 0.00E-01 0.00E-01 0.00E-01 4,83E 07 f)N

                              -                   CD-60 NI-63           3.12E 04 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      1.00E 01       4.70E 00 0.00E-01 2 52E 01 0:00E-01 8.53E 02

____-___________--___________________-____________________-_-_____-____________ i ZN-65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.C0E-01 4.64E 04 ZN-69 4.93E 01 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.C Z-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 BR-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 0 00E-01 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 0.00E-01 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-0.1 0.00E-01 3.57E 03 SR-90 5 4BE 05 0.00E-01 1.34E 05 0 00E-01 0 00E-01 0 00E-01 1.58E 04 l 1.95E 03 SR-91 4.10E 02 0.00E-01 1 65E 01 0.00E-01 0.00E-01 0.00E-01 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-0A 0.00E-01 6.15E 03 l 0.00E-03 0.00E-01 1.61E-02 Y-91h 5.48E-03 0.00E-01 2.12E-04 0.00E-01 l 1:!!______8:595_??__?:295:91__2:2?g:gi__g ggg:gi__g:ggg:gi__g ggg:gi__4 geg g3_ _ l l b 1-15 ISSUE 2 REVISION 2

h + py

      ;p r in HV-1 ODC1 3,
                                                                                                      . TABLE 1.3-1

>%e(.) ; V ~A VALUES TOC THE ADULT FOR THE BEAVER VALLEY SITE ti (mrem /hr per pCi/ml) 'r ~ NdCLDE BONE LIVER T-BODY THYROIL KIDNEY LUNG GI-LL1 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 0.30E-01 0.00E-01 5.12E 03 ZR-95 2.53E-01 8.11E-02 5.49E-02 0.00E-01 1.2<E-01 0.00E-01 2.57E 02 ZR-97 1.40E-02 2.82E-03 1.~9E-03 0.00E-01 a.26E-03 0 00E 01~ 8.73E 72 NB-95 4.47E 02 2 40E-02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 16 NB-97 3.75E 00 9.48E-01 3.46E-01 0.00E-01 1.11E 00 0.'mE-01 3.50E 03 HO-99 0.00E-01 1.05E 02 2.00E 01 0.00E-01 2.30E 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 TC-101 C.23E-03 1.33E-02 1.30E-01 0.00E-01. 2 39E-01 6.79E-03 4.00E-14 RU+103 4.51E 00 0.00E-01 1.94E 00 0.00E-01 1.72E 01 0.00E-01 5.26E 02 f- s RU-105 3.75E-01 0.00E-01 1.48E-01 0.00E-01 4.85E 00 0.00E-01 2.29E 02 (s/ ) RU-106 6.70E 01 0 00E-01 8.48E 00 0.00E-01 1.29E 02 0.00E-01 4.34E 03 AG-110M 9.48E-01 8.77E-01 5.21E-01 0.00E-01 1 72E 00 0.00E 3.58E 02 SB-124 7.67E 00- 1.49E-01 3.12E 00 1.91r-o2 0.00E-01 6.13E 00 2.23E 02 SB-125 5.03E 00 5.62E-02 1.20E 00 5.11E-03 v.00E-01 3.88E 00 5.54E 01-TE-125M 2 57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.03E 04 TE-127M 6.49E 03 2 32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 TE-127 1.05E 02 3.78E 01 2 28E 01 7.81E 01 4.29E 02 0.00E-01 8.32E 03 TE-129M 1 10E 04 4 11E 03 1.74E 03 3 78E 03 4.60E 04 0.00E-01 5.55E 04 TE-129 3.0tE 01 1.13E 01 7.33E 00 2 31E 01 1 26E 02 0.00E-01 2.27E 01 TE-131M 1.66E 03 8 10E 02 6 75E 02 1.2BE 03 8.21E 03 0.00E-01 8.05E 04 TE-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.27E 01 0.00E-01 2.67E 00 TE-132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1 50E 04 0.00E-01 S.39E 04 TE-134 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 1.00E 02 3.35E 02 2.63E 05 2.19C 02 0.00E-01 1.61E 01 1-130 2.75E 01 8.10E 01 3.20E 01 6.87E 03 1.26E'02 0.00E-01 6.97E 01 1-131 1.51E 02 2 16E 02 1.24E 02 7.08E 04 3.71E C2 0.00E-01 5.70E 01-1-132 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 I-134 3.85E 00 1.05E 01 3.74E 00 1.81E 02 1.66E 01 0.00E-01 9.12E-03 V 1-16 ISSUE 2 REVISION 2

l '. BV-1 ODCH l

TABLE-1,3-1 Lv {4 s /

A ' VALUES FOR TiiE ADULT FOR THE BEAVER VALLEY SITE LT (mrem /hr per'pci/ml) NUCLDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI I-135 1.61E 01 4.21E 01 1.55E 01 2.78E 03 6.76E 01 0.01E-01 4.76E 01 CS-134 2.98E 05 ~7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 CS-136 3.12E 04 1.23E 05 8.86E 04 s .00E-01 6.85E 04 9 39E 03 1.40E 04 CS-137 3.82E 05 5.22E 05 3.42E 05 0.0tE-01 1.77E 05 5 89E 04 1.01E 04 CS-138 2.64E 02 5.22E 02 2.59E 02- 0.00E-01 3 84E 02 3.79E 01 2.23E-03' BA-139 9.69E-01 6.90E-04 2.84E-02 0.00E-01 6.45E-04 3 92E-04 1 72E 00 1 BA-140 2.03E O2' 2.55E-01 1.33E 01 0.00E-01 8.66E-02 1.46E-01 4.18E 02- l BA-141 4.71E-01 3.56E-04 1.59E-02 0.00E-01 3.31E-04 2.02E-04 2.22E-10 i BA-142 2 13E-01 2.19E-04 1.34E-02 0.00E-01 1.85E-04 1 24E-04 3 00E-19 LA-140 1.51E-01 7.59E-02 2.01E-02 0.COE-01 0.00E-01 0.00E-01 5.57E 03 r* LA-142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E 2.56E 01 f 2.02E-03 0.00E-01 8.26E-03 0.00E-01 6.80E 01 CE-141 2.63E-02 1.78E-02 ( ]}

          ~              -----------------_-----_-------------------------------------------------------

CE-143 4.64E-03. 3.43E 00 3.79E-04 0.00E-01 1 51E-03 0.00E-01 1 28E 02 CE-144 1.37E 00 5.73E-01 7.36E-02 0.00E-01 3.40E-01 0:00E-01 4.64E 02 i PR-143 5.54E-01 2.22E-01 2.75E-02 0 00E-01 1 28E-01 a.00E-01 2.43E 03 PR-144 1 81E-03 7.5'E-04 9.22E-05 0.00E-01 4.25E-04 0.00E-01 .2 61E-10 ND-147 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 0.00E-01 0.00E-01 8.10E 04

                         --___.-_--__ __---__---_------_ -------.. -----------------_-------------------                             )

NP-239 2.90E-02 2.85E-03 1.57E-03 0.00E-01 8.89E-03 0.00E-01 5.85E O2 I i

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1-17 ISSUE 2 REVISION 2

___-----_-_-_-_--___-_: _ .l

' E BV-1 ODCM 1 4 Liquid Radwaste System

                      'j                The . liquid radwaste system has the capability to control, collect, process,

(('~) store, recycle, and dispose of liquid radioactive waste generated as a result of plant operations, including anticipated operational occurrences. This system'also uses some of the components of the steam generator blowdown 6/89 systed for procusing. Simplified flow diagrams of the liquid radwaste systems for BV-1 and BV-2 are provided as Figures 1.4-1 and 1.4-2 respectively. Since the concept of a shared liquid radwaste system is used, then any liquid waste generated can be stored, processed and discharged from either BV-1 or BV-2. O 1 I O V 1-18 ISSUE 2 REVISION 2

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BV-1 DDCM I 2.0 Gaseous _ Effluents l

   /Df      _. Technical; specifications applicable                        .to-    dose rate apply to the site. The                                                                              q Lk        site' dose rate is due to the' summation of releases from both units.

Technical -specifications applicable to accumulated dose apply individually to each unit. Releases at the Beaver Valley Site may be ground level or ; elevated' in.' nature. All ground level releases are identified with a '

            . specific unit in the determination of site dose rate and' dose attributed to                                                                                                        !

that unit. Elevated releases from both units are considered to originate from a shared radwaste system and 'are discharged from a . common release ; point, -the Process Vent,'at the top of the Unit 1 cooling tower. At. Beaver i Valley the dose from the shared radwaste system via the Process Vent' is normally. apportioned equally to the Units. However a containment purge via the Process Vent shall be attributed to a specific unit. 2.1 Monitor Alarm Setpoint Determination Technical specifications for Beaver Valley require that the dose rate in unrestricted' areas due to nnble gas radionuclides in the gaseous effinent j released from the site sh 11 be limited to 5 500 mrem /yr to the total body j and to 5 3000. mrem /yr to the skin. q This section describes the methodology used to maintain the release of noble gas radionuclides within the Technical Specifications limits for. the site 1 and determines monitor setpoints for this unit. ] j The methodologies described in Sections 2.1.3 and 2.1.4 provide an alternate ')

 .-          means of determining monitor alarm setpoints that may be used when an analysis is performed prior to release.                                                                                                                                               l Control of the site. dose rate limit due to noble gases is. exercised by a total of eight effluent stream monitors, of which three are located in Unit                                                                                                          i 1   (alternates exists for these monitors), and five are located in Unit 2.

As previnusly noted, Unit 2 elevated releases are via the Unit 1 Process Vent. At this point -it is necessary to point out differences that exist between i the setpoint presentations of the radiation monitoring systems of BVPS-1 and BVPS-2. First there is a conflict'in setpoint terminology. Where BVPS-1 uses HIGH and HIGH-HIGH the BFPS-2 equivalents are ALERT and HIGH. The second difference is that the BVPS-2 setpoint 'is presented in pCi/cc rather j than' CPM as in 3VPS-1. This difference is due to software which applies a j conversion. factor to the raw data (CPM). The user is cautioned that the 1 pCi/cc presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factor. In practice setpoints determined for a calculated mix are correct for that mix. S,tpoints determined on analysis prior to release will be correct for y: operly controlling dose rate but the indicated pCi/cc value may differ i from the actual value. 2-1 ISSUE 2 REVISION 2 (

l BV-1 ODCM All effluent monitors specified herein have HIGH-HIGH (BV-1) or HIGH (BV-2) setpoints established at 3C percent of the site limit and except three ~

  ;/~'T           monitors noted below, HIGH (BV-1) or ALERT (BV-2) setpoints established at

(_) 10 percent of the site limit. Monitor Setpoint Specifications Based on Fraction of Site Limit Unit, Release Point 1 & Monitor Fraction of Site Limiting Dose Rate Unit 1, Ventilation Vent 30% (HIGH-HIGH) 10% (HIGH) RM-VS-101B (Alt. VS-109 CH #5) Unit 1, Containment Vent 30% (HIGH-HIGH) 10% (HIGH) RM-VS-107B (Alt. VS-110 CH #5) Units 1/2, Process Vent 30% (HIGH-HIGH) 10% (HIGH) RM-GW-10SB (Alt. GW-109 CH #5) Unit 2, Containment Vent 30% (HIGH) 10% (ALERT) 2HVS*RQ109B Unit 2, Ventilation Vent 30% (HIGH) 10% (ALERT) 2HVS-RQ101B Unit 2, Waste Gas Storage Vault 30% (HIGH) 0.1% (ALERT) 2RMQ-RQ303B Unit 2, Decontamination Building Vent 30% (HIGH) 0.3% (ALERT) (,--) 2RMQ-RQ301B l Unit 2, Condensate Polishing Building Vent 30% (HIGH) 0.6% (ALERT) 2HVL-RQ112B I Units 1/2, Turbine Building Vent < 0.1% (Unmonitored) With the monitor setpoints based on fractions of the site limit as defined above, the following criteria may be applied to determine that the dose rate due to noble gas released from the site complies with Technical Specifications:

The sito dose rate is less than 50% of the site limit when all monitors are below the HIGH (BV-1) and AI.ERT (BV-2) setpoints.
With all monitors below the ao.a.a1 HIGH-HIGH (BV-1) and HIGH (BV-2) setpoints, a combination of three HIGH (BV-1) or ALERT (BV-2) setpoint alarms indicate release may heve exceeded site limits.
To provide operational flexibility any one HIGH-HIGH (BV-1) or HIGH (BV-2), Containment, Ventilation, or Process vent monitor setpoint may be doubled to 60% of the Site limit if all other monitors in this group are held below the HIGH (BV-1) and ALERT (BV-2) setpoints.

2-2 ISSUE 2 REVISION 2

BV-1 ODCM From thismay rate limit condition any exceeded. have been one monitor alarm would indicate the site dose

'A

(~~h release may be batch or continuous in nature. (_, Batch refers to releases that are intermittent in radionuclides 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 of variations the releases normallywhich result in radioactive releases greater than 50% considered as continuous. Batch releases from these sources during normal operation, including anticipated operational occurrences, are defined as those which occur for a total of 500 hours or less in a calendar batch relative concentration value has been calculatedyear but notThemore than the guidelines provided in accordance with in NUREG-0324 for short-term release. If simultaneous lowest setpoint batch and contino-os release out of one vent occurs, use the 2.1.4. obtained at.srding to the following Sections 2.1.1 through 2.1.1 Setpoint Determination Based en and Containment Building Vent Releases a Calculated (Ground Mix for Ventilation Vent Releases) The calculated monitor count rate above background (C.R.), in ncpm, the monitoralarm HIGH HIGH-HIGH setpointalarm setpoint above background (HHSP), and the monitor above condition should be as follows: background (HSP) for each vent and operational CPM above Background 30% 10% SITE SITE ig")x PRIMARY LIMIT LIMIT MONITOR C.R. HHSP lisp Continuous Release Via The VS-101B 3.00E3 9.00E2 1 Ventilation Vent 3.00E2 Batch Release of Containment VS-101B 3.90E2 1.17E2 Purge Via the Ventilation 3.90E1 Vent Continuous Release Via The VS-107B 6.44E3 1.93E3 Containment Building Vent 6.44E2 Batch Release of Containment VS-107B 1.93E3 5.80E2 Purge Via the Containment 1.93E2 Building Vent When the primary monitor is 0.0.S. and technical specifications can be met for the respective utilized: alternate monitor, the following setpoints may be h

                      }                                                               2-3                             ISSUE 2 REVISION 2 l                                                                                                      _                             _ -  _ _ _ -

1 BV-1 ODCM CPM Above Background 30% 10%

,s                                                                                                  SITE                             SITE ALTERNATE                                 LIMIT

_( x_/

    )                                                  !!ONITOR    C.R.

LIMIT j HHSP HSP-Continuous Release Via The VS-109 1.47E3 Ventilation Vent 4.40E2 1. 4 7E2 CHANNEL 5 Batch Release of Containment VS-109 4.68E2 1.40E2 Purge Via the Ventilation CHANNEL 5 4.6BE1 ! Vent Continuous Release Vic The VS-110 3.38E3 1.01E3 Containment Building Veat 3.38E2 CHANNEL 5 Batch Release of Containtnent VS-110 1.01E3 l Purge Via the Containment 3.04E2 1.01E2 CHANNEL 5 Building Vent The setpoints were determined using the following conditions and information: Source terms given in Table 2.1-1. Thesa gaseous source terms were derived from Stone & Webster computer codes GASIBB (which :.s similar to l the NRC CODE GALE, NUREG-0017) and DRAGON - (for the containment vacuum pump sources). Table 2.1-1 does not include particulate and iodines, which are not used in site noble gas dose rate calculations. (/ S i x, Onsite meteorological December 31, 1980. data for the period January 1, 1976 through Discharge flow rate of 62,000 cfm for the Ventilation Vent (Continuous) Discharge flow rate of 92,000 cfm for the Ventilation Vent (Batch release of contaitmeat purge). Discharge flow rate of 49,300 cfm for the Containment Building Vent (Both continuous and batch release of contait.nent purge). i Information listed under References - Setpoints. Gaseous Effluent Monitor The calculation method given in Sections 2.1.1.1 through 2.1.1.7 was used to i derive the monitor setpoints for the following operational conditions: i Continuous release via the Ventilation Vent. i' Continuous release via the Containment Building Vent. Batch release of containment purge via the Ventilation Vent. j l Batch release of containment purge via the Containment Building Vent. I 2-4 ISSUE 2 REVISION 2

                                                                       - - - - - - - - - -                                                 --- a

BV-1 CDCM 2.1.1.1 The "m ix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:

a. The caseous source terms that are representative of the " mix" of the e

gaseous effluent were selected. Gaseous source terms ara the radioactivity of the noble' gas radionuclides in the effluent. Gaseous source terms can be obtained from Table 2.1-1.

b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclides "i" (S f

                                                                            ) for each individual noble gas radionuclides in the gaseous effluent was determined by:
                                                              ^1 i     I i

A' where: A = The total radioactivity or radioactivity concentration of f noble gas radionuclides "1" in the gaseous effluent from Table 2.1-1. 2.J.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

       -~g       exposure limit was calculated by:

0 Q' = (2.1-2) (X/Q) I Kg S *4 i wh9.re : (X/Q)"" = The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m') from Table 2.2-5.

                                = 1.03E-4 sec/m' for continuous releases.

(X/q)yy = The short term relative concentration of effluents released via the Ventilation Vent for any area at or beyond the 8 unrestricted area boundary for all sectors (sec/m ) from Table A-3 of Appendix A.

                                = 3.32E-4 sec/m' for batch release of containment purge.

O V 2-5 ISSUE 2 REVISION 2

s. BV-1 ODCB1 (X/Q)'" = The highest calculated annual average relative concentration of effluents released via the Containment Building Vent for p any area.at or beyond the unrestricted area boundary for all L sectors (sec/m') from Table 2.2-4.

                     -= 9. 24E-5 sec/m' for continuous releases (X/q)C# = The short term relative concentration of effluents released via the containment building vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m') from Table A-2 of Appendix A.
                     = 3.08E-4 sec/m' for batcli release of containment purge Kg       = The total whole body dose factor due to gamma emmissions from noble gas radionuclides "i" (mrem / year /pCi/m') from Table 2.2-11.

S g

                     = From equation (2.1-1) above.

2.1.1.3 Q was also determined based upon the skin exposure lim 2t by: i 3000 t (X/Q) I (Lg + 1.1Mg) Sg (2.1-3) i A where: Lg = Tha skin dose factor due to beta emissions from noble gas radionuclides "i" (mrem / year /vCi/m') from Table 2.2-11. Mg = The air dose factor due to gamma emissions from noble gas radionuclides "i" (mrad / year /yCi/m8 ) from Table 2.2-11. 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, (mrem / mrad). (X/Q) = same as in Section 2.1.1.2. 2.1.1.4 The maximum ecceptable release rate in pCi/sec of noble gas radionuclides "i" in the gaseous effluent (Q g) for each individual noble gas radionuclides in the gaseous effluent was determined by: Qg =S g hg (2.1-4) p

2-6 ISSUE 2 REVISION 2

q< BV-1 ODCM (NOTE: :Use the lower of the Q values obtained in Sectioi 2.1.1.2 and 2.1.1.3) g l l - (~) The maximum acceptable radioactivity concentration pCi/cc of ncble gas

   .Q-     !2.1.1.5 radionuclides "i".in the gaseous effluent (Cg ) for each individual noble Fas i

l ;' . radionuclides In the gaseous effluent was determined by: o i

                                                 .C    = 2.12 E-3 Q i                                                    (2.1-5) l i          F where:

F = The maximum acceptable effluent flow rate at the point of l:. l release (cfm)

                                  = 62,000 cfm (Ventilation Vent)(I)
                                  = 49,300 cfm (Containment Building Vent)( )

2.12E-3 = Unit conversion factor (60'sec/ min x 3.53 E-5 ft'/cc). u 2.1.1.6 The calculated monitor count rate in nepm above background attributed to the noble gas radionuclides (C.R.) was determined by: C.R. n ICg Eg (2.1-6) i IN where: Eg = The detection efficiency of the . monitor for noble gas radionuclides "i" (cpm /pCi/cc) from' Table 2.1-2. 2.1.1.7 The monitor alarm setpoints above background were determined as follows: s i-

         '       a. The monitor HIGH-HIGH alarm HHSP setpoint above backgreurd (in nepm) was determined by:

HHSP = 0.30 C.R. (2.1-7)

b. The monitor HIGH alarm setpoint HSP above background (in nepm) was determined by:

HSP = 0.10 C.R. (2.1-8) NOTE: The values 0.3 for the HHSP and 0.1 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units. N. ISSUE 2 2-7 REVISION 2

BV-1 ODCM 2.1.2 Setpmint Determination Based on a Calculated Mix for Process Vent Releases (Elevated Releases) (/ ) The calculated monitor count rate above background (C.R.), in ncpm, t he monitor HIGH-HIGH alarm setpoint above background (HMSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition ; l are as follows: CPM Above Background 30% 10% SITE SITE PRIMARY LIMIT LIMIT MONITOR C.R. MHSP HSP

Continuous Release GW-108B 3.83E7 1.25E7 3.83E6
Batch Release of GW-108B 3.93E5 1.18E5 3.93E4 Decay Tanks
Batch Release of GW-108B 5.55E6 1.67E6 5.55E5 Containment Furge When the primary monitor is out of service and technical specifications can be met for the respective alternate monitor, the following setpoints may be utilized:

CPM Above Background 30% 10% (,o) SITE SITE

                                    ALTERNATE                   LIMIT       LIMIT MONITOR        C.R.        EHSP         HSP

Continuous Release GW-109 2.20E7 6.61E6 2.20E6 CHANNEL 5
Batch Release of GW-109 7.87E6 2.36E6 7.87ES Decay Tanks CHANNEL 5
Batch Release of GW-109 7.37E6 2.21E6 7.37E5 Containment Purge CHANNEL 5 The setpoints were determined usin; a calculated mix from the FSAR and discharge flow rate of 1450 cfm for the Process Vent.

The calculational method below was used to derive the monitor setpoints for the following operational conditions:

Continuous release via the Process Vent
Batch release of waste gas tank via the Process Vent
Batch release of containment purge via the Process Vent O

O 2-8 ISSUE 2 REVI5 ION 1

BV-1 ODCM 2.1.1.1 T!;e " mix" (noble' gases and composition) of the gasecas effluent was

                -determined as follows:

f~l 4 (_,/-

a. The gaseous source terms that are representative of the " mix" of the gaseous effluent were evaluated.

Gaseous source terms are the radioactivity of the noble gases radionuclides in the effluent. _The gaseous source. terms can be obtained from Table 2.1-1. i b. The frcction of the total radioactivity in the gaseous effluent comprised by noble gas radion'iclide "1" (Sj ) for each individual noble' gas rad _onuc;ide in the gaseous effluent was calculated by: ! A i S = 3 g (2.1-9) i where: A = The tota I radioactivity or radioactivity concentration of noble gas radionuclides "i" in the gaseous effluent from Table 2.1-1.

       ' 2.1. 2 '. 2 The maximum acceptable total release rate (in pCi/sec) of all noble gas radionuclides in the gaseous effluent (Q ) based upon the whole body exposure limit was determined by:

h

Ot
500 IV jSf (2.1-10) i where:

V y

The constant for noble gas radionuclides "1" accounting for the gamma radiation from the, elevated finite plume (mrem / year /pC1/sec) from Table 2.2-12. 2.1.2 3 Q was also determined based upon the skin exposure limit as follows: 3000 Ot * [Lj(X/Q)py + 1.1Bg]Sg (2.1-11) where: L. = The skin dose factor due to beta emissions from noble gas radionuclides "1" (mrem / year /pCi/m') from Table 2.2-11. 2-9 ISSUE 2 REVISION 2

  -                                                       BV-l'0DCM n The highest calculated annual average' relative. concentration.

(X/Q)PV of effluents releases via_the Process Vent for any area at or beyond the unrestricted area boundary for all sectors (,rN -ji (sec/m') from Table 2.2-6.

                                    ' = 2.31E-6 sec/m' (X/q)P" = The short- term relative concentration of effluents released-                                  the via the Process Vent for- any area at or beyond unrestricted area boundary        for all sectors (sec/m') from Table A-5 of Appendix A.
                                     = 1.07E-5 sec/m' B         = The constant for long term releases            (greater than 500-g.

hrs / year) for noble gas radionuclides "1" accounting for the gamma- radiation dose. from the elevated finite plume (mrad / year /pCi/sec) from Table 2.2-12, 2.1.2.4 The maximum acceptabic release rate (in pCi/sec) of noble gas radionuclides "i" in the gaseous effluent g(h)foreachindividualnoble gas radionuclides in the gaseous effluent was determined by: h=Sg h (2,1-12)

  %               (NOTE: Use the lower of the h values obtan 'd in Section-2.1.2.2 and 2.1.2.3) 2.1.2.5 The maximum acceptable radioactivity concentration (in pC1/cc)-of_ noble gas radionuclides "1" in the gaseous effluent (C ) for each individual noble gas radionuclides in the gaseous effluent was determined by:

C = 1 (2.1-13) i F where: 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-5 ft'/cc) F = The maximum acceptable effluent flow rate at the point of release (cfm)

                                     = 1450'cfm (Process Vent) 2.1.2.6       The calculated monitor count rate (in ncpm) above background attributed to 'the noble gas radionuclides (C.R.) was determined by:

O 2-10 ISSUE 2 REVISION 2

r L BV-1 ODCM l-C.R. = I Cf Eg (2.1-14) I 1

x. where:

.( ~'

E = The detection efficiency of the monitor for noble gas I radionuclides "i" (cpm /pCi/cc) from Table 2.1-2. ! 2.1.2.7 The monitor alarm setpoints above background were determined as follows:

a. The monitor HIGH-HIGH alarm setpoint (HHSP) above background (in ncpm) was determined by:

HHSP = 0.30 C.R. (2.1-15)

b. The monitor HIGH alarm setpoint (HSP) above background (in nepm) was determined by:

HSP = 0.10 C.R. (2.1-16) 2.1.3 Setpoint Determination Based on Analysis Prior to Release for Ventilation Vent and Containment Building Vent Release (Ground Releases) When the setpoints established using "the calculated mix" for ground releases do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Step 2.1.1. In this case, the results of sample anc ysis are used to datermine the source term " mix". This calculational method applies to gaseous releases

  ]      )

via the Ventilation Vent and via the Containment Building Vent when

   \- /          determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH alarm setpoint based on this flow rate for the Ventilation Vent Gas Monitor (VS-101B) and the Containment Building Gas Monitor (VS-107B) during the following operational conditions:

Batch release of containment purge via the Ventilation Vent
Batch release of containment purge via the Containment Building Vent 2.1.3.1 The maximum acceptable discharge ficw rate from containment vent or ventilation vent during purging is determined as follows:

a. The maximum acceptable gaseous discharge flow rate (f) from containment or ventilation vent (in cfm) during purging based upon the whole body exposure limit is calculated by:

o 2-11 ISSUE 2 REVISION 2

BV-1 ODCM 1.06 S T (X/q) I Ky C (2.1 - l'7 ) i where: 1.06 = 500 mrem /yr x 2.12 E-3 500 mrem /yr = dose rate limit 2.12 E-3 = unit conversion factor

                                                 = (60 sec/ min x 3.53 E-5 ft'/cc)

S = Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 2.1. To exceed 60% of the site limit from one release point, the remaining release point _ limits must be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit. T = Maximun valve for T is 16 based on the limiting restriction in T.S. 3.11.2.1.a where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16). See Reference (6). (X/q)" = The highest calculated short term relative concentration of ef fluents released via the Ventilation Vent for any area at i or beyond the unrestricted area boundary for all sectors (sec/ r') frorr Table A-3 of Appendix A.

                                = 3.32E-4 sec/m '

(X/q)cv = The highest calculated short term relative concentration of effluents released via the Containment Building Vent for areas at or beyond the unrestricted area boundary for all sectors (sec/m') from Table A-4 of Appendix A.

                                = 3.08E-4 sec/m 8 Kg      = The total whole body dose f actor due to gamma emissions from nobic gas radionuclides "i" (mrem / year /pCi/m') from Table 2.2-11.

C, = The undiluted radioactivity concentration of noble gas

radionuclides "i" in the gaseous source (pCi/cc) as determined by analysis of the gas to be released.

b. The flow rate (f) is also determined based upon the skin. exposure limit as follows:

j. .

2-12 ISSUE 2 ( l REVISION 2

p . BV-1 DDCM c 6.36S T 7 ,(X/q)-I (L g +.1.1M ) C i f (2.1-18) t N.

                      .there:

6.36 = 3000 mrem /yr x 2.12 E-3 3000 mrem /yr = dose rate limit 2.12 E-3 = unit conversion factor 2

                                                             = (60 sec/ min x 3.53 E-5 ft /cc)

Lg = The skin dose factor due to beta emissions from noble gas radionuclides "1" (mrem / year /pCi/m') from Table 2.2-11. Mg = The air dose factor due to gamma emissions from noble gas radionuclides "1" (mrad / year /pCi/m') from Table 2.2-11. (X/q) = Same as in Section 2.1.3.1.a.

c. The flow rate (f) is determined by selecting the smaller of the calculate:.' (f) values based on the whole body exposure limit (Section 2.1.3.1.a) and based on the skin exposure limit (Section 2.1.3.1.b).

The actual purge flow rate in cfm must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent. 2.1.3.2 The monitor alarm setpoints above background are determined as follows:

a. The calculated monitor HIGH-HIGH alarm setpoint (HHSP) above background (nepm) attributed to the noble gas radionuclides is determined by:

f I Cf E g HHSP = F' (2.1-19) where: f = The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1.3.1. F' = The maximum actual or design effluent flow rate (cfm) at the point of release.

92,000 cfm (Ventilation Vent -- design).II)

49,300 cfm (Containment Building Vent -- design).( ) C = The 1 undiluted radioactivity concentration of noble gas radionuclides "i" in the gaseous source (pCi/cc) as determined by analysis of the gas to be released. E = j The detection efficiency of the monitor for noble gas radionuclides "i" (cpm /pCi/cc) from Table 2.1-2. 2-13 ISSUE 2 REVISION 2

BV-1 ODCM

b. When a HIGH-HIGH set point has been calculated according to this section the monitor llIGH alarm setpoint above background (ncpm) is fm determined as follows:

HHSP x 0.33 = HSP (2.1-20) 6/89 2.1.4 Setpoint Determination Based on Analysis Prior to Release for Process Vent Releases (Elevated Releases) The following calculation method applies to gaseous releases via the Process Vent when the " calculated mix" does not provide adequate operational flexibility. This method is used to determine the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH alarm setpoint based on this flow rate for the BVPS-1 Gaseous Waste Gas Monitor (GW-108B) or alternate (GW-109 CH #5) during the following operational conditions:

Continuous release via the Process Vent
Batch release of waste gas decay tank via the Process Vent
Batch release of containment purge via the Process Vent 2.1.4.1 Determine the maximum acceptabic discharge flow rate for the release from the Process Vent for the analyzed mix,

a. The max! mum acceptable gaseous discharge flow rate (f) in cfm based upon the whole body exposure limit is determined by:

                                       '*I      ' C i i (2.1-21) g where:

1.06 = 500 mrem /yr x 2.12 E-3 500 mrem /yr = dose rate limit, whole body exposure 2.12 E-3 = unit conversion factor 8

                                    = (60 sec/ min x 3.53 E-5 ft /cc)

S = Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for ont release point under the alarm set point rules of Section 2.1. To exceed 60% of the site limit from one release point, the remaining release point limits must be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit. 2-14 ISSUE 2 REVISION 2

k BV-1 ODCM

                             '.' j =   The constant for noble gas radionuclides "i" accounting for the       gamma     radiation . from     the      elevated                   plume
    /~N                                 (mrem / year /pCi/sec) from Table 2.2-12.

Y.] ' ' C = The undiluted radioactivity concentration of noble gas f radionuclides "i" in the gaseous source (pCi/cc) as determined by analysis of the gas to be released.

b. Based.upon the skin exposure limit, (f) is calculated by:

6.36 S g I [Lj M )py + 1.1B g] C f (2.1-22) where: 6.3A = 3000 mrem /yr x 2.12 E-3 3000 mrem /yr = dose rate limit, skin exposure 2.12 E-3 = unit conversion factor

                                                        = (60 sec/ min x 3.53 E-5 f t'/cc)

Lg = The skin dose factor due to beta emissions from noble gas radionuclides "i" (mrem / year /pCi/m') from Table 2.2-11.

                                     = The highest calculated annual average relative concentration (X/Q)PV   of effluents released via the Process Vent for any area at or beyond      the unrestricted area borndary for all sectors l- g (sec/m') from Table 2.2-6.
                                     = 2.31E-6 sec/m'.

(X/q)P# = The short term relative concentration of effluents released via the Process Vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m') from Table A-5 of Appendix "A"

                                     = 1.07E-5 sec/m' B.      = The      constant for long-term releases         (greater than 500

hrs / year) for noble gas radionuclides "i" acceunting for the gamma radiation from the gamma radiation from the elevated finite plume-(mrad / year /pC1/sec) trom Table 2.2-12.

l c. Select the smaller of the calculated f values based on the whole body l exposure limit (Section 2.1.4.1.a) and based on the skin exposure limit i (Section 2.1.4.1.b). The actual discharge flow rate in (cfm) must be l maintained at or below this f value. 2.1.4.2 The monitor alarm setpoints above background are determined as follows: 1

a. The calculated monitor HIGH-HIGH alarm setpoint (HLiP) above background (nepm) attributed to the noble gas radionuclides is determined by:

l 2-15 ISSUE 2 REVISION 2 1

f 4 P.V-1 ODCM f - E C.1 E.1 g

        ,s , .                                                                                                     HHSP =          y,                           (2,1-23)
        +            $
 ,      't /

where: f = Tlte maximum acceptable gaseous discharge flow rate-(cfm) determined in Section 2.1.4.1. F' = The maximum actual or design effluent flow rate (cfm) at the point of release,

                                                                                                =     1450 cfm (Process Vent)

C j' = The undiluted radioactivity of noble gas radionuclides "i" in the gaseous source (pCi/cc) as determined by analysis.of the gas to be released. E y

                                                                                                =     The detection efficiency of the respective monitor GW-108B or GW-109 CH 5 for noble gas radionuclides "i" (cpm /pCi/cc) from Table 2.1-2.

b. When a- HIGH-HIGH set point has been calculated according to this Section the monitor HIGH alarm setpoint (HSP) above background (ncpm) is determined by:

HHSP x 0.33 = HSP (2.1-24). 6/89 l-I l (< ( 2-16 ISSUF 2 , REVihrGN 2 I. L _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ ___ _ _ f

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e BV-1 'JDCM REFERENCES Gasecus Effluent Monitor Setpoints O

 .Q.
           .~(1) "fleaver Valley Power Station, Appendix I Analysis - Docket No.

50-412", Table 2.1. 3. 50-334 and (2) " Beaver Valley Power Station, Unit 2 FSAR", Table 11.3-1 (3) "Duquesne Light Co., Beaver Valley Nuclear Plant,' Specification No. BVPS 414, Table V Nuclide Data, 5/30/7',", Table 1 arid Figure 1, Table 3, and Figure 2. (4) Gaseous 031. Effluent Monitor Efficiency Data; Calculation Package ERS-SFL (5) Unit 1/ Unit 2 Setpoints Calculation Package ERS-HHM-87-014. 3 (6) BVPS-l' ! 87-026. and BVPS-2 ODCM T Factor Justification; Calculation Package ERS-ATL-(72 Letter NDISHP:776, l dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B. 0/09 f I O i i 1 l l m 2 '9 ISSUE 2 REVISION 2

BV-1 ODCM 2.2 Compliance'with 10 CFR 20'(Gaseous)

 < /~                 2.2.1'                      Noble Gases
 '  Y.T.l                                                                                           .

The . dose rate in unrestricted areas resulting from noble gas effluents from the< site is limited to 500 mrem /yr to the total body and 3,000 crrem/yr to the skin. Site gaseous effluents are the total of Beaver Valley Unit I and. Unit 2 specific ground releases and a shared elevated release, the Process Vent. Based' upon NUREG-0123 the f ollowing b ssic expressions are t sed to show compliance with BVTS.3.11.2.1.a. l: I-[Vhgh +K(i 0)v iv) < 500 mrem /yr (2.2-1) 1 I ILt(X/Q), + 1.1Bg ] Q g, + [Lg + 1.1M f](5/Q)y Q gy 5 3000 mrem /yr (2.2-2) 4 i . where: Kg = the total body dose factor due to gamma emmissions for each icentifled noble gas radionuclides "i", mrem / year /pC1/m'.

                                                                  = the                     skin dose factcr due to beta emisaicns for each L'                                identified noble gas radionuclides "i", mrem / year /pCi/m'.
    ..                                            Mg              =                 the     air dose factor due to gamma emiusicie            for each identified ocble gas radionuclides "i", mrad / year /yC1/m'.
    '(V -

Vg = the constant for each identified nobis gas redionuclide "i" accounting for the garuna radiation from the elevated finite plume, irrem/ year /pCi/sec. E = the constant for long-tenn releases (greater than 500

hrs / year) for each identified nobis gas radionuclides "1" accounting for the gamma radiation from the elevated finite plume, mrad / year /pCi/sec.

1.1 = the ratio of the tissue to air absorption coefficients over the energy range c f the photon of interest, mrem / mrad. Q is = the release rate of noble gas radionuclides ">" in gaseous effluents from free-standing stack, pCi/sec. Qg = the release rate of nobic gas radient.clide "i" in gaseous effluents from all vant releases, pCi/sec.

                                                                  =                 the highest calculated annual average relative concentration (X/Q)8                          for any area at or beyond the unrestricted area boundary for elevated releases (sec/m').

2-20 ISSUE 2 REVISION 2

V '

          ?6                                       -BV-1 ODCU q.
                        . ___(X/Q)"' =. the -highest' calculated annual average relative concet.. ration'
      ?~*   ,                       for any' area at or beyond,the unrestricted. area boundary. f,r g$ ]                          ground level releases.(sec/m').
                'At the' Beaver Valley Site gaseous releases'may occur from:

c

1. .the. Containment Vents atop the~ containment domes

2. 'the Ventilation Vents stop the auxiliary buildings

3. the Process Vent atop the BVPS-1 cooling tower

4. the Turbine Building Vents

5. the BVPS-2 Condensate Polishing Building Vent

6. the BVES42 Decontamination Building' Vent

7. the SVPS-2 Waste Gas Storage Vault Vent Effluent from the Containment' Vents are assumed ground level in nature. At BVPS-1 the source of these reicases is the Supplementary Leak Collection and

   ,             Release System (SLCRS). 1At BVPS-2 the' source of these releases is normal auxiliary building ventilation.         It is also possible to release containment spurges from these vents. The Ventilation Vent Releases are ground level in nature. .At BVPS-1 the sources ofithese releases are containment purges . and l .-.            -normal. auxiliary building . vent ilation .        At BVPS-2 the sources of these releases are containment. purges and contiguoas areas ventilation.                                                          The LE( )-

Turbine Building Vents Releases are ground level in nature and the source.of 1, these releases.are the turbine building ventilat. ion. Release points 4, . 5, 6, and 7 above are not normally radioactive telease points. The Process Vent releases are elevated and the sources of these releases are the main c.ondenser air, ejectors and the waste gas decay tanks and containment vacuum. Noble. gas releases may normally occur from release points 1 through 3 above. To show compliance with site limits in 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 site'. Note that the expressions for release points 4, 5, 6, and 7- are included for use if radioactive releases via these' release points are identified in the future.

2-21 ISSUE 2 REVISION 2 l l

i BV-1 ODCM U For the. tal bodyfdose:

O' .. . . . . .

                                                                                                                                                                                                    +
 ' \g. ~           'I V Q                                                                                                                             + (X/Q) fg     ~+IKg j [(X/Q)           Qg                +~(X/Q)yy Q g                                          + (X/Q)g Qj                                                Q1 1      pv                              cv1                                                  vv1 -                            tv1                                          cv2
                                                                                                        +(X/d)cp                                                     '+

(5Td)vvg vv2 b. -+(X/Q)*"h~ I M Qi 2.

                                                                                                                                         +    (X/Q)dv     i b dv2 (X/Q),,y hg                                     ] 5 500 mrem /yr-                                                                   (2.2-3) wv2                                                                                                f. .
                         .For the skin dose:

I.[L(X3)py+ 3 1.1B]h g 3

                                                            + I g-[L1+1.1M][(576)cy                            1 h1         +(5)yy b g                                  -+

1 pv cyl vv1

(X/Q)tv i-b gy3

                                         + (X/Q)cvi bcv2 +(576)## Ihvv2 +(5Td)tv htv2 + (576)CP                                                i                                            i cp'2h (57)dy      1

( )wv i wv2 I' "# *!Y' ( ' ) dv2 where: Qg = release ~ rate of radionuclides "i" from the Process Vent, pv pCi/sec. Qg = release rate of radionuclides "i" from the BVPS-1 Containment cv1 Vent, pC1/sec.

                               'Q g           = release rate of radionuclides "i" from the BVPS-2 Containment cv2         Vent, pCi/sec.

Qg : release rate of radionuclides "i" from the BVPS-1 Ventilation vv1 Vent, pCi/sec. Qg ~= release rate of radionuclides "i" from the BVPS-2 Ventilation vv2 Vent, pCi/sec.

                                .Q g          = release rate of radionuclides "i" from the BVPS-1 Turbine tv1         Building Vent, pCi/sec.

Qg = release rate of radionuclides "1" from the BVPS-2 Turbine tv2 Building Vent, pCi/sec. E .{ L i

     ;O                                                                                                   2-22                                            ISSUE 2 REVISION 2 B                                                                 - - - - - - - - _ - _ - - - - -                 - _ - - - - - _          --_                  _                                       -

i BV-1 ODCM~ ! L l

                                                            -Q I                          = release rate of radionuclides "i" rrom the BVPS-2 Condenscte cp2-                     Polishing Building Vent, pC1/sec.
                                                            .Q                            = release rate                                       of     radionuclides                    "i"        from          the 'BVPS-2 f

dv2 Decontamination Sullding Vent, pCi/sec. ~. 1 . Qf = release rate of radionuclides "1" from the BVPS-2 Waste Gas l wv2 Ftorage Vault Vent, pC1/sec. i (X/Q)P"'= releases highest calculated from the Process annualVent, average sec/m*. relative concentration for (X/Q)"" = highest calculated annual average relative concentration for releases from the Containment Vent, sec/m*. (X/Q)"# = highest calculated annual at . rage reiative 8 concentration for releases from the Ventilation Vent, sec/m . I l (X/Q)*# =. highest calculated annual average relative concentration for- 8 releases for the Turbine Building Vent, sec/m . l (X/Q)cp =releases highest calculated annual average relative concentration for for the Condensate Polishing Building Vent, sec/m 8 , l

(X/Q)dv = highest calculated annual average relative concentration for.

releases for the Decontamination Building Vent, sec/m . 8 (X/Q)"" = highest; calculated annual average relative concentration for C releases for the Waste Gas Storage Vanit Vent, sec/m . 8 Note that the release rate for a containment purge is based on an averaged j release rate in pCi/sec for the entire purge (Not to exceed 960 min in j accordance with T.S 3.11.2.1). l All other terms remain the same as those defined previously. For the site, four potential modes of relaase are possible. The release

                                             . modes identify the various combinations of sources of radioactivity and their release points which are used to determine the contro11fug locations.                                                                                                                                  '

They are presented in Table 2.2-1. For Modes 1, 2, and 3, the controlling location for implementation of.EVTS 3.11.2.1.a is 0.35 miles NW. 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:

l 2-23 ISSUE 2 REVISION 2 - _ _ . . . _ . _ . - . _ . - - . - _ - - . . _ . . - - - - . - - _ _ - > . - _ - _ _ - . . - . - - _ - . _ _ _ . . _ - _ - - _ - . _ - _ . . - _ - . _ _ _ - . _ . _ _ _ __.-...--_._--.~_-....__-._.-._.--._--._J

BV-1 ODCff-

         +-'                    For the total body:

f1 , a.x

  ?/~'\                          .                                                  .                              .                                    .

( k,/. IVQ fg +-IKg [9.24E-5 Qg + 1.03E-4 Q

                                                                                            + 7.35u-5.Q g                                 + 9.24E-5 0 1 cv2
                                                                                                                                                                 +
                -i t-                 pv     i                  cyl                    vv1                                       tv1 1.03E-4 Q 3                    + 7.35E-5 Q g       + 9.24E-5 Q g          + 9.24E-5 Q g                                 + 7.35E-5 Q g        ]

vv2 tv2 dv2 .wv2 cp2 5 500 mrem /yr (2.2-5) For the skin:

                                                                   +E                                                                    + 1.03E-4 Q g          +

I [7.0E-10 Lg + 1.1B g] Qg [Lj + 1.1Mf] [9.24E-5 Q g 1 pv i evi vv1 7.35E-5 Q + 9.24E-5 Q + 1.03E-4 Q + 7.35E-5 Q + 9.24E-5 Q 1 +. 9.24E-5 Q v 7.35E-5 Q ] 5 3000 mrem /yr (2.2-6) For the release Mode 4, the controlling. location is 0.75 miles N. Inserting gm 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: IVQ + 4.99E-6 Q g + 4.26E-6 Q f + 3.95E-6 Q g + fg +EKg [3.95E-6 Q 1 pv i cv1 vv1 tv1 cv2 4.99E-6 Q f + 4.26E-6 Q g + 3.95E-6 Q + 3.95E-6 Q 1 + 4.26E-6 Q g ] vv2 tv2 dv2 wv2 cp2-5 500 mrem /yr (2.2-7) 2-24 ISSUE 2 O- REVISION 2

F .' > BV-1 ODCM V For the-skin: f (j / I [2.31E-6 Lg + 1.1B f] Qg

                                                                    +I    [L j + 1.1Mg] [3.95E-6 Qf
                                                                                                                                           + 4.99E-6 Q 1      +

1 pv 2 cv1 vv1 3.95E-6 Q + 4.99E-6 Q + 4.26E-6 Q + 4.26E-6 Q + 3.95E-6 Q , 3.95E-6 Q g + 4.26E-6 Q g 5 3000 mrem /yr (2.2-8) wv cp The determination of controlling location for impicmentation of BVTS 3.11.2.1.a for noble gases is a function of the following parameters:

1. radionuclides 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 radionuclides mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GAS 1BB which is similar to the NRC GALE code. Inputs were based on operating modet. of the respective plants. The code inputs utilized are presented in Appendix B. The source term is presented in Table 2.2-2 as a function 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 nearest vegetable 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, Containment Vent, Ventilation Vent, Turbine Building Vent, and if applicable for BVPS-2, Decontamination Building Vent, Waste Gas Storage Vault Vert, and the Condensate Polishing Building Vent release points to the special locations presented in Table 2.2-3. A description of their derivation is provided in Appendix A. For release modes, 1, 2, and 3, dose calculations were performed using the highest calculated site boundary X/Q values applicable to the release points involved and the projected radionuclides mix applicable to the release source. In that a simultaneous, continuous elevated release- could contribute to the dose at a given location, the selection of the two highest sector X/Q values at the site boundary considered this contribution. Fror f these results, the distance and sector associated with the highest

           \,                        calculated site boundary dose were selected as the controlling location.

2-25 ISSUE 2 REVISION 2

l BV-1 ODCM 1 For Modes 1, 2, and 3, the controlling location is 0.35 mile.s NW. In Mode 1, the dominant release is the auxiliary building ventilation (Ventilation lA ) 1 Vent in Unit I and Containment Vent in Unit 2). In Modes 2 and 3, the dominant release is containment purge from the respective Ventilation Vent or Containment Vent. For release Mode 4, a similar evaluation was performed. Long-term annual average X/Q values were calculated at the mid-point of the 10 standard distances listed in Tables 2.2-4 through 2.2-10. In that a simultaneous, ground level release could centribute to the dose at a given location, the selection of the two highest X/Q values at the controlling distance considered this contribution. Since the two maximum X/Q values occurred, in the 0.5 - 1.0 mile radial band, the controlling distance was selected at 0.75 miles. From the calculated dose results, the controlling sector was shown to be North. In this Mode, the dominant release is containment purge via the process vent. Neither of the :ontrolling receptor locations are presently inhabited. Values for K, g Lg and M, g which were used in the determination of the controlling receptor location and which are to be used in 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 1E6 to convert picocuries" to microcuries' for use in Table 2.2-11. Values for V yand B for y the finite plume model can be expressed as shown in Equation 2.2-9 and 2.2-10. Values were calculated using the NRC code RABFIN _ [d at the site boundary location which would receive the highest total dose from combined Process Vent, Ventilation Vent and Turbine Building Vent and Containment Vent releases These values are presented in Table 2.2-12 and calculated from the following relation: K III 'jk^11 aM 1 ( B f =7jk1d u j

"'}

where: I = the results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of wind speed (u ) and atmospheric stability class "k" for a particular wind direction. K = a numerical constant representing unit conversions.

                                =      (260 mran)(radians) (m') (transformation)            16 sectors (sec)(Mev)(C1)                   27 radians 1E-6 Ci       3.15E7 sec pCi yr ,
    'r

( 2-26 ISSUE 2 REVISION 2

BV-1 ODCM

= -2.1E4 mrad (m')-(transformation)/yr(Mev)(pCi).

n stance from the release point to the receptor location,

 .(}            r d

te () - meters. u = the mean wind spt,d assigned to the "j" th wind speed class,. meters /sec. f p'= the joint frequency of occurrence of the "j" th wind speed class and kth stability class (dimensionless). A = the number of photons of energy corresponding to the "1" th 7f energy group emitted per transformation of the "i" th radionuclides, number / transformation. E = the energy assigned to the "1" th energy group, Mev. 1 p = the energy absorption coefficient in air for photon energy H ,y meters" . The V g factor is computed with conversion from air dose to tissue depth . dose, thus: III 'jk A1gua 1 e'"T d Vj = 1.1.K7.jk1 u. ( '

                                                                                               ~
                                                                                                   )

d j D where: p = the tissue energy absorption coefficient for photons of T energy E , cm ajgg, 1 T e issue ensi y ness a en represent ttie total d body dose (5gm/cm2 ).

1. 1 = the ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem / mrad.

2.2.2 Iodine-131, Tritium, and Radionuclides in Particulate Form (Tl > 8 Day) The dose rate in unrestricted areas resulting from the of inhalation of I-131, tritium, and all radionuclides in part.iculate form (excluding C-14) with half lives greater than 8 days released in gaseous effluents from the 6/89 site shall be limited to 1,500 mrem /yr to any organ. Based upon NUREG-0133, the following basic expression is used to show compliance with BVTS 3.11.2.1.b: IP it I IO)s is + )v iv l ' *#**!Y# ' i I 2-27 ISSUE 2 REVISION 2 ! ___--____-___--_-_a

BV-1 ODCM where:

        / ' ~ .-                                               P         = dose        parameter     for   any organ   't   for each identified 1*

radionuclides "i", mrem /yr per pC1/m'; Q is = the release rate of radionuclides "i", in gaseous effluents from elevated releases, pCi/sec. Q.# = the release rate of radionuclides "i",.in gaseous effluents frem ground level releases, VCi/sec.. (X/Q)s =- the highest calculated annual average relative concentration at the unrestricted area boundary for elevated releases, sec/m'; (X/Q)#

                                                                         =   the highest ca7;-Lated annual average relative concentration at the unrestriu.ed area boundary for ground level releases, sec/m 8 ;

Note: The. dispersion parameters specified in Section 2.2.2 are limited to the site boundary as defined above. Releases may occur.from any of the site vents in the release modes listed in Table 2.2-1. To show compliance with BVTS 3.11.2.1.b, Expression 2.2-11 is now expressed in terms of the actual release points for the site. I1 P.T ((X/Q)Pv I i g h

                                                                              +(5[d)cv h    i y
                                                                                                   + (X/Q)vv ih   i
                                                                                                                    + (X/Q)t# ihM + (5[6)'# hi M
                     +

(X/Q)vv h i +(576)t# hi ts'2 + (5[6) P ih + (X/Q) hI + (X3 "# h wv2 1 vv2 cp2 dv2 5 1500 mrem /yr (2.2-12) where: (XI6)Pv = highest calculated annual average relative concentration fc h ases f m & P m ess Ve m se @ '- (57Q)" = highest calculated annual average relative concentration for releases from the Containment Vents, sec/m'; (X/Q)## = highest calculated annual average relative concentration for releases from the Ventilation Vents, sec/m'; (576) " = highest calculated annual average relative concentration for releases from the Turbine Building Vents, sec/m'; (X/Q)cp =releases highest calculated annualCondensate from the BVPS-2 average relative concentration Polishing for Building Vent, sec/m';

2-28 ISSUE 2 REVISION 2

IF BV-1 ODCM i (X/Q)d# = highest calculated l annual average relative concentration for releases from the BVPS-2 Decontamination Building Vent. JLk L[- ;f sec/m3 ; (X/Q)"" = highest' calculated annual average relative concentration;for telease from'the BVPS-2 Waste Gas. Storage Vault, sec/m';- Q g_ =-long-term release rate of radionuclides "i" from.the Process pv Vent, pCi/sec; Qg = long-term release rate,of radionuclides "i" from the BVPS-1 cv1 Containment Vent, pCi/sec; Q = .long-term release rate of radionuclides "i"-from the BVPS-2 cv2- Containment Vent,-pC1/sec; Q

                         .g
                                   =           long-term release rate of radionuclides "i" from the BVPS-1 vv1             Ventilation Vent, pCi/sec; Q. g
                                   =           -long-term release rate of radionuclides     "1" from the BVPS-2 vv2             Ventilation Vent, pCi/sec; Qg       =-         .long-term release rate of radionuclides "i" from the BVPS-1 tv1             Turbine Building Vent, pCi/sec; Qg       =           long-term release rate of radionuclides "i" from the BVPS-2 1- s                       tv2             Turbine, Building Vent, pC1/sec;

', \ = long-term release rate of radionuclides "1" from the

                         -Q g.

cp2 Condensate Polishing Building Vent, pCi/sec; Qg =- long-term release rate of radionuclides "1" from the i dv2 Decontamination Building. Vent, pCi/sec; o 1 [ Qg = long-term release rate of radionuclides "i" from the Waste Gas wv2 Storage Vault Vent,.pCi/sec; l l All other terms are the same as those defined previously. The Turbine Building Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and Waste Gas Storage Vault Vent are not normal . radioactive release points. These release points are included only for use if radioactive releases via these vents are identified in the future. In the calculation to show compliance with BVTS 3.11.2.1.b only the inhalation pathway is considered. Values of the organ dose parameters, Pg , were calculated using methodology T given in NUREG-0133. For the child age group, the following equation was used for all nuclides. The Pg , values are presented in Table 2.2-13. t O 2-29 ISSUE 2 l REVISION 2

I BV-1 ODCM~ P

                                                                 = 3.7E9 DFA S

(2.2-13) 1 t where: 3.7E9 =- breathing rate of child (3,700 n'/yr) x unit conversion f actor . (IE6 pCi/pCi) . DFA 3 the organ inhalation dose factor for a child from Table 6 of i f t USNRC NUREG-0172, Nov. 1977, for organ t, nuclide "i", in units of mrem /pCi. For release modes 1 through 4, the controlling location is the site boundary, 0.35 miles NW. Expression 2.2-12 becomes: IP g [7.00E-10 Q g + 9.24E-5 Q f + 1.03E-4 Qg + 7.35E-5 Q f + 9.24E-5 i i pv cyl vv1 tv1 Q + 1.03E-4 Q + 7.35E-5 Q + 7.35E-5 Q f + 9.24E-5 Q + 9.24E-5 4 Qf $ 1500 mrem /yr .(2.2-14) wv2 The determination of the controlling location for implementation of BVTS 3.,11.2.1.b for radiciodines and particulate is a function of the same three parameters as- for noble gases plus a fourth, the actual receptor pathways. The incorporation of. these pt.rameters into Expres.sion 2.2-12 results in the

respective equations for each release mode at the site boundary controlling locations. The radionuclides mix was again based upon the source terms presented in Table 2.2-2 as a function of release type and release point. In the determination of the controlling site boundary for each release mode, the highest two site boundary X/Q values for each release point were utilized in conjunction with the radionuclides mix and the release rate for each release point a determine tne controlling location. The P values are presented in Table 2.2-13. The X/Q values in Expression 2.2-14 were obtained from Tables 2.2-4 through 2.2-10. a description of the derivation of the X/Q values is provided in Appendix A. l 2-30 ISSUE 2 REVISION 2 E_-____________._____. '

t y 7, BV-1 ODCM TABLE 2.2-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS

 . P-                                                                            FOR IMPLEMENTA110N OT 10 CFR 20 AND 10 CFR 50

( .-

Release Point' Mode 1 Mode 2 Mode 3 Mode 4 L' .BVPS BVPS-2 8 Main Cond. Air Same as Same as Same as Ejector, Waste Mode l' Process Vent ~ (pv). Mode 1 Mode 1 and Gas, Contain- Containment ment Vacuum Purge BVPS-1 Ventilation 2 Aux B)dg. Containment Same as Same as Vent-(vv1) Ventilation Purge' Mode 1 Mode 1 BVPS-1 Containment: Leakage Same as Same as' Same as Vent (cyl) Collection Mode 1 Mode 1 and Mode 1 Exhaust Containment Purge' BVPS-1 Turbine Bldg.8 . Turbine Bldg Same as Same as Same as Vent (tv1) Exhaust

Mode 1* Mode 1* Mode 1*

BVPS-2 Ventilation 8 Contiguous Containment Same as Same as Vent (vv2) Areas Purge' Mode 1 Mode 1 BVPS-2 Containment 2 Aux. Bldg. Same as Same as . Same as Vent (cv2). Ventilation Mode 1 Mode 1 and Mode 1 Containment Purge 8 BVPS-2 Turbine Bldg.2 Turbine Eldg Same as Same as Same as Vent (tv2) Exhaust

Mode 1* Mode 1* Mode 1*

             .BVPS-2 Condensate *                                                               *                                                 *      *

Polirhing Bldg. Vent ,

(cp2) BVPS-2 Decontamination 1 * * *

Bldg. Vent (dv2)

BVPS-2 Waste Gas! * * *

Storage Vault Vent

             .(wv2)
              *Not normally a radioactive release point Note:                               For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.

2 Continuous ground level meteorology is applicable 2 Continuous elevated meteorology is applicable

Mode' established by purge from one unit, all cther release points remain same

               ' as Mode L 2-31                                                  ISSUE 2 REVISION 2

e m v r 0 i s e 2 2 1 0 t u e mT 00 0 0 0

                                                                       +                                                             +

c ot e - + - E a e s t t E E E E osaWa yo s r 02 3 0003 02 0000000000000000000

i
d G Sh 01 2 000808000000000000000007 0

       )         a                 S R        R                  (

Y

I C ( 1 s* T t p* T N n m) I E eum 4 3 1 4 3 62 2 03 2 644 65 7 5 5 6667 866 00000000000000000000000000 N V mP r U n e - - - - - - - - - - - - - - - - - - - - - - - - - - S i mT E E E E EE E EE EE E EEEEE EEE E E E EEE N O S E a u t u g 7 92

                                                . 8 0. l 3 2 949 3 2. 7. . 5. 47 464. 1967 3 3 7 7 5 3 1 2 1 4 1 61 42 84 694 00 1 7 41 3 64 800 I C                 n c n T O                oa o A R               CVL T P                         (

S R E W r) O P / om rt r 1 001 02 2 1 1 1 01 1 2 2 Y e ce 000 00000000000 0 E n s eT - + + - + - - - + - + - - - E L i nj E EEEEEE EEE E E E E L a eE g 7 2 6 2 47 063 083 61 00000000000000 A Md n . . V n r o 2 1 1 82 7 85 Z2 2 1 62 03 000000000000 oil R CA( E 2 V M - A C 2 E D B O 2 n) E t om 54 4 4 4 5 5 5 3 54 5 5 4 4 1 E i i e n gi r 0

 - L   T     n e e nt e               00000000000000 V   B       iV niaT                      - - - - - - - - - - - - - -                               E B   A   M   b         idl              EEEE EEEEEE E EEE T   O R

r .bl i ugri t n g 9 7 3 l 5 1 2 l

                                                    . . . .           492 1 7 5 07 0 0 0 0 0 0 0 0 0 0. C.

F Td u u n o 3 1 2 1 3 1 1 83242 9608000000 . 00000 l TB eL S B V( T N E U L F n n) F o y r gi r om 0 0001 1 1 1 1 01 02 2 2 2 23 3 4 22 E i 1 0 00000000 t a nt e 00000000000000 - - - - - - - - S at ii aT - + + + + - - - + - + - + - E EEE E EEEE U l nl dl E EEEEE EE EEE EEE 03 08 000 O i eil i g 2 95 3 82 3 962 5 l 1 6 07 0007 3 . E t V xit n . . . 6 1 2 1 3 00 S n u un o 4 1 2 1 3 1 1 83 3 4 2 1 4 060062 1 A e AB eL G V V( R O F

X I t ) t m M n e mn* r e ge r 2 l 1 2 1 4 1 1 1 3 1 3 2 3 4 4 4 45 5 64 4 01 E m emnT 0O000000 000000 0 0000000000 D nt T ni - - + - - - - - + - - - - - - - - - - - - - - + I i n i d t EE EEEEE E E EE EEE E E EEE E EEEEE L a e gal r 25 1 447 4 9 95 005 2 00005 42 5 7 02 8 05 . C t V nt i o . . . U n on uh 2 1 65 2 47 884 7 1 1 1 02 007 3 2 7 1 3 2 3 1 2 N o L oBS O C ( C ( I D A R e mm m 4 7 3mm5 5 7 893 3 3 3 3 3 3 3 31 3 d 1 3 3 5 5 7 81 2 3 45 i 1 1 1 33 8 04 99 03 3 4 1 1 5 65 5 39 1 1 1 l 8888881 1 1 1 1 1 c - - - - - - - - - - - - - - - - - - -oon - e- r- r- s- sC

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E U u o r 5 6,7 7 22 7 5,8,4, 1 1 1 1

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n e m L G n A i V a t Q d 7028 601 4 n e 956 0904 696 7

t 1 02 01 26 8 630 o X 1 5 4,7, C l a a v 9, 6, 5, - 2 6, 4, 9, 4,5,6,6, , , L 41 31 22 22 4343 2 g A m e 32 7

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U i S i N n E F d N A V l A 57 90 37 46 8509 B i t d 281 8 07 5 u a n 544 6 7 97 51 1 4 R 0,6,5,9, d B O e u 1

                                   , 8, 7,     -  2 5,2,7,            2 3,4,4,
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22 22 4343 a g r 42 7 41 31 n

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d S s E 0986 90 7 22 P i T e 8351 51 036 V l t 1 347 0946 o E M a 4,0,5 6, 2,8,8,1, - 8 2,- - 5, 8, 2, B P ( t v , 5 3 205 e a e 4606 4250 1 21 1 h . e S o l 2 t r t T C E e a N nw s I k d 1 604 5597 63 940 e o n O l 662 7 1 9 24 5 eT e P i n 5762 5, 9, 4, M u 6,2,7,8 2 ,8, 7 9, ,

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                                       /                                                                r r        i                                                                o yo           C                                                                t U                                                               c d t oc                   2 31 344 41                  2233333                     a B a             r     000000000000000
                                                 -++++++++++++++

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                                   , e p     EEEEEEEEEEEEEEE 67 1 27 6651 421 234 e

s 591 8488 o t s r y 51 . . . 694651. . . d oo 7 1 1 D : 1 1 92231 1 88 TD / : m d e e r t o s b i l e h T e d i l mm 335578 m c u mn i 355739033333331 1 n o 88888

                                                 - - - - 891  a - 1 1- 1                                                   rr rrr rr ee ee eeer y.

i d m. K t. ' KKKKKXXXXXXXA f,; R l I!

BV-1 ODCH j'~'\ ; TABLE 2.2-12

  %l DOSE PARAMETERS FOR FINITE ELEVATED PLUMES BEAVER VALLEY SITE

V B , V B I Totali Body Gamma i Air Total Body Gamma Air Dose Rate Dose Rate Dose Rate Dose Rate Noble Gas mrem /yr mra d/yr . mrem /yr mrad /yr pC1/sec pCi/sec pCi/sec pCi/sec Radionuclides Kr-83m 3.19E-10 1.75E-8 4.58E-8 3.96E-5 Kr-85m 7.81E-5 1.16E 4 4.70E-4 7.06E 4 Kr-85 1.55E-6 2.35E-6 5.54E-6 8.40E-6 Kr-87 5.13E-4 7.74E 4 1.45E-3 2.14E-3 Kr-88 1.39E-3 2.09E-3 4.09E-3 6.16E-3 Kr-89 7.99E-4 1.20E-3 1.25E-3 1.88E-3 Xe-131m 1.64E-5 2.47E-5 1.67E-4 3.09E 4 Xe-133m 1.38E-5 2.11E-5 1.32E-4 2.61E-4 Xe-133 1.05E-5 1.56E-4 1.54E-4 2.76E 4 Xe-135m 2.41E-4 3.66E-4 6.21E-4 9.50E 4 Xe-135 1.41E-4 2.12E-4 6.96E-4 1.05E-3 Xe-137 6.00E-5 9.05E-5 9.66E-5 1.46E-4 Xe-138 8.11E-4 1.22E-3 2.22E-3 3.34E-3

() Ar-41 1.02E-3 1.53E-3 2.68E-3 4.02E-3 l

                  *The listed dose parameters are for radionuclides that may be detected in gaseous effluents.

1 V and B values used to implement Modes 1, 2, anc 3 of Section 2.2.1. (10CFR20) 2 B values.used to implement Modes 1, 2, 3, and 4 of Section 2.3.1. (10CFR50) f V g and B, values to' implement Mode 4 of Section 2.2.1. (10CFR20) and to implement monitor serpoint. determinations of Section 2.1.2 and 2.1.4 O ISSUE 2 2-42 REVISION 2 _ = _ _ _

i 1 3V 1 ODCl!

                                                  -Table 2.213 E                              P VALUES FOR A CHILD FOR T H B BVER VA11E7 SITE I                                if '

(ares /yr per uC1/en meter) Nuclide Bone Liver f. Body Thyroid Eidney ' Lung GI-LLI 1H-3 . 0.00b00 1.12bO3 1.12bO3 1.12bO3 1.12bO3 1.12bO3 1.12bO3 2P-32 2.60b061.14b05 9.88b04 0.00b00 0.00D00 0.00D00 4.22bC4 b 3Cr51 0.00b00 0.00D001.54bO2 8.55b012.43b011.70b041.08bO3 4Mn54 0.00b004.29b049.51bO30.00D001.00D041.58b062.29b04 5Fe-59 2.07b04 3.34b041.67b04 0.00b00 0.00D001.27b06 7.07b04 60057 0.00D009.03bO21.07E+030.00b000.00D005.07b051.32b04 70058 0.00b001.77bO3 3.1Sb03 0.00D00 0.00b001.11b06 3.44b04 80060 0.00b001.31b04 2.26b04 0.00D00 0.00b00 7.07b06 9.62b04 9Zn-65 4.25b041.13b05 7.03b04 0.00D00 7.14D04 9.95b051.63004 10lb-86. 0.00b001.98b051.14b05 0.00D00 0.00D00 0.00D00 7.99bO3 11Sr-89 5.99h05 0.00b001.72b04 0.00D00 0.00b00 2.16b061.67b05 12St90 1.01b000.00D006.44b060,00D000.00b001.48bO73.43b05 r 13 E 91 9.14b05 0.00b00 2.44b04 0.00b00 0.00b00 2.63b061.64b05 h V 14 Zr 95. L1.90b05 4.18bO( 3.70D04 0.00b00 5.96b04 2.23b06 6.11b04 15lb-95 2.35bO(9.16bO36.550030.00D008.62bO36.14b053.70D04 16Nb-97 4.290017.70E-023.60F020.00D008.550023.42bO32.78b04 6/89 17Ho-99 0.00b001.72D024.26b010.00D003.92bO21.35b051.27b05 18 Tc-99a- 1.78 b 03 3.46b 03 5.77b02 0.000 00 5.07 bO2 9.51bO2 4.81b03

              - 19 Ro-103' 2.79 b 03 0.00b 00 1.07bO3 0.00b 00 7.03bO3 6.62b 05 4.48 b04 20 Ru-106 .1.36 b 05 0.00 D00 1.69b 04 0.00b 00 1.64b05 1.43b07 4.29b 05 21 Ag-110s 1.69h041;14b04 9.14bO3 0.00b00 2.12004 5.46D061.00D0; 22Sb-124 5.74b047.40bO22.00b041.26bO20.00D003.24b061.64b05 23Sb-125 9.64b04 7.59bO2 2.07b04 9.10b010.00b00 2.12b06 4.03b04 24 fe-127a 2.49b 04 8.55 b O3 3.02b O3 6.07b O3 6.36 b04 1.48b 06 7.14b 04 25fe-129s 1.92b046.85bO33.04bO36.33bO35.03b041.76b061.82b05 26I-131        4.81b04 4.81b04 2.73b041.62bO7 7.68b04 0.00b00 2.64bO3 27I-133        1.66b04 2.03b04 7.70D03 3.85b06 3.38bO( 0.00b00 5.4BbO3 28Ce-134 6.51b051,0lb062.25b050.00 BOO 3.30b051.21b053.85bO3 29Ca-136 6.51bo41.71b051.16b05 0.00b00 9.55b041.45b04 4.16bO3 30Ce137 9.07b05 8.25b051.28D05 0.00D00 2.82b051.04b05 3.62bO3 31Ba-140 7.40b04 6.48b014.33bO3 0.00b00 2.11b011.74b061.02b05 32La-140 6.44D02 2.25bO2 7.55b010.00D00 0.00b301.83b05 2.26b05 33Ce-141 3.92b041.95b04 ?.90D03 0.00b00 B.55bO3 5.44b05 5.66b04 34Ce-144 6.77b06 2.12b06 3.61b05 0.00 BOO 1-17b061.20bO7 3.89b05 CalculatedperODCHequation2.2-13 2-43                                                                 ISSUE 2 REVIS mu 2 r

I BV-1 ODCM j

         '2.3 Compliance with 10 CFR 50 (Gaseous)                                                                                                                                                             ;

D- At the c3eaver Valley Site all elevated gaseous releases are considered to

  .\                      originate from a shared radwaste system. The effluent from both Units are mixed and; discharged from a common release point, the process vent, at the'                                                                                                        l top of the Unit _1 cooling tower. The resulting dose for the purpose of                                                                                                             !

implementing 10 CFR 50 is normally apportioned equally to each unit. The j only exception would be a containment purge via the process vent. The resulting. dose shall be attributed to the cop.tibuting reactor unit. Since this operation is expected to be rare, equations are shown throughout this section with the apportionment set at 0.5. 2.3.1- Noble Gases-2.3.i.1 Cumulation of Doses Section II.B.1 of Appendix I of 10 CFR 50 (BVTS 3.11.2.2) limits the releases of gaseous effluents from each reactor .such that the estimated j annual gamma air dosw is limited to 10 millirad and th beta air dose is j limited to 20 millirad. In addition, BVTS 3.11.2.4 require use of radwaste l system if air doses when averaged over 31 days exceed 0.2 mrad for gamma and 0.4 mrad for beta. dased upon NUREG-0133, the air dose limits in the unrestricted area due to noble gases released in gaseous effluents are defined by the following expressions: ; 1 During any calendar quarter, for gamma radiation:

 '. (                         3.17E-8 I        Mg [(X/Q)yQ g + (XTq)y ggy) + (B Qgh+bqg h]                                                   s 5 mrad, (2.3-1) i During any calendar quarter, for beta radiation:

3.17E-8 I N g (X/Q)yQgy + (X/q)yggy + (X/Q),Qis # (U4)s91s 5 10 mrad,

i . ^ (2.3-2) During any calendar year, for gamma radiation: ! l

                                                                   + (X[q')y ggy)                                                          s 10 mrad,                                                         j 3.17E-8 I     Mg [(X/Q)yQ g                                  + [B Qgis+bqg g]
                                         ~

(2.3-3) During any calendar year, for beta radiation: ; J 3.17E-8 I N g (X/Q)yQgy + (X/q)yg g + (X/Q),Qg , + (X/q),qi , s 20 mrad, I (2.3-4) !

G ; Q 2-44 ISSUE 2 l REVISION 2

                                                                                                                                                                                             - -------._ _ .N

V E o BV-1 ODCM

When averaged over 31 days, for the gamma radiation projection:

l l _ v A}'

 -y. 3.17E-8 I M g[(X[Q)Q h + (Xj9)v h]    9 + [B Qf is + b gg g)                  5 0.2 mrad, i_

(2.3-5) Averaged over 31 days, for the beta radiation projection: 1 3.17E-8 I N g (X/Q)yQ g + (X/q)ygg + (X/Q),Qg + (X/q),q $ 0.4 mrad (2,3-6) t where: My = the air dose factor due to gamma emissions for each identified noble gas radionuclides "i", mrad /yr per pCi/m'; N = the air dose factor due to beta emissions for each identified I noble gas radionuclides "i", mrad /yr per pCi/m'; (X/Q)# = the annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term vent releases (greater than 500 hrs / year), sec/m'; (X/q)# = unrestricted the relative concentration for areas at or beyond the area boundary for short-term vent releases (u (equal to or less than 500 hrs / year), sec/m'; (X/Q)8 = the annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term fres standing stack releases (greater than 500 hrs / year), sec/m*; (X/q)* = the relative concentration for areas at or beycad the unrestricted area boundary for short-term free standing stack releases (equal to or less than 500 hrs / year), sec/m*; g, = release of noble gas radionuclides "1" in gasecut effluents j for short-term stack releases (equal to or lest, than 500 hrs / year), pCi; qIV = release of noble gas radionuclides "1" in gasecas effluents i for short-term vent releases (equal to or less than 500 hrs / year), pCi; Q = release of noble gas radionuclides "i" in gaseous offluents for long-term free standing stack releases (greater than 500 hrs / year), pCi;

                       = release of noble gas radiont::lide "i" in gaseous effluents Q ".         for long-term vent releases (greater than 500 hrs / year), pCi; 2-45                                       ISSUE 2 REVISION 2

l .I

~'

BV-1 ODCM

                           'B           = the      constant ,for long-term releases (greater than' 5t ';

I' hrs / year) for.each identified nob; e gas radionuclim "1" f% ' accounting' for the gamma radiation f rom the e?evated L .iite l if ' plume, mrao/yr per pCi/sec;_ L b = the constant for short-term releases (equal to or less than l 500 hrs / year) for each Mentified noble gas radio.caclide _ " i" accounting for the gamma radiation from the eles>ted finite plume, wrad/yr per pC1/sec; 1. p 3.17E-8 = the inverse of the number of seconds in a yesr. NUREG 0133 permits el$ninating the short-term relevse term and short-term meteorological terms in the determination of doses whe. short term releases are sufficiently random in both time of 6ay +nd duration te be represented by annual average dispersion conditions. This special consideration is applied in expressions 2.3-1 through 2.3-6, however a summary of the "real time" meteorological data coupled with the correspond 1>g releases shall be included in the Semi-Annual Radioactive Effluent Release Report. Short-term releases are also evaluated annually in computer codes technically consistant with X0QD0Q and GASPAR for inclusion in the Annual Radiological Environmental Report. The incorporation of this option .and the release modes of Table 2.3-1 results in the following expressions to show complianew with 10 CFR 50 fot [- the calendar quarter or year. For Release Modes 1, 2, 3, and 4 During sny month, calendar quarter, or yeat: Gamma Radiation

                               ~
                                     ,_                  __                            ]       0.2 mrad (per 31 dt.ys) 3.17E-0 I Mj [(X/Q) Q j             + (X/Q) Q j        ] + 0.5 B jj Q      '$    5.0 mrad (per quarter) i                      cv                  vv              py ,

10.0 mrad (per year) (2.3-7) Beta Radiation

                                 ~
                                                                                            ~

0.4 mrad (per 31 days) 3.17E-8 I N j (X/Q) Q j + (X/Q) Q j + 0.5 (X/Q) Q j $ 10.0 mrad (per quarter) i , cv vv py, 20.0 mrad (per year) (2.3-8) where: (X/Q)'# = annual average relative concentration for releases from the Containment Building Vent, sec/m*;

2-46 I6 SUE 2 REVISION 2 i l i

                                                                                               . . _ - - . . . _ _ . _ _ . _      -._.m_ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ . . .

BV-1 ODCM (X/Q)"V~= annual average relative concentration for releases from the Ventilation Vent, sec/m 8;

 . --{)

(O

                                                  = annus1 average relative concentration for releases from the (X/Q)PV          Process Vent, sec/m'-

(X/Q)'# = annual average-relative concentration for releases from-the Turbine Building Vent, sec/m*; Rg = release of radionuclides "i" from the Containment- Building cv Vest, pCi; Q.g

                                                   = release of radionuclides "1"                                                                     from the Ventilation Vent, pCi; vv Qg            = release c f radionuclides "i" from the Process Vent, sci; PV Qg            = release of radionuclides                                                                       "1"  from the Turbine Building Vent, tv         . pCi;.

For modes 1, 2, 3, and 4 the controlling location is 0.35 miles NW. Substitution of the appropriate X/Q values into Expressions 2.3-7 and 2.3-8 results in the following: Release Modes 1, 2, 3, and 4 [~') . During any month, calender q'4arter or year:

\_/

Gamma Radiation - - 3.17E-8 I M [9.24E-5Q g 4 1.03E-4Q g + 7.35E-5Q g ] + 0.5 B gg Q i , ,,, cv vv tv pv_ 0.2 mrad (per 31 days)

                                                                             $ 5.0 mrad (per quarter)                                                                                                                  (2.3-9) 10.0 mrad (per year)

Beta Radiation - - 3.17E-8 I N g 9.24E-5Q g + 1.03E-4Q g + 7.35E-5Q g + (0.5) 7.0E-10Q i _ cv vv tv pv, 0.4 mrad (per 31 days) 5 10.0 mrad (per quarter) (2.3-10) 20.0 mrad (per year) (- O). 2-47 ISSUE 2 REVISION 2

2 s BV-1 ODCM Hi. ' lhe determination'of'the controlling locations for implementation of 10 CFR [ 50 is a function of,the fo1*owing parameters: \ff (( .

                                  -(1) radionuclides mix and their. isotopic release
                                  '(2) release mode

(3) meteorology.

Jrhe incorporation of these parameters into Expressions 2.3-7 and 2.3-8 resulted in the expressions for the controlling locations as presented in Expr2ssions 2.3-9 and '2.3-10. The radionuclides mix was based upon source terms calculated using tne NRC GALE Code (inputs presented in Appendix B) and is presented in Table 2.2-2 as a function of release type and release point.

                                . As. in' Section                                  2.2.1,                            for.each release' mode, the two highest boundary X/Q values for each release point and release duration were utilized in
                                - conjunction _'with the radionuclides mix and telease.for each release point to
                                . determine the centro 11ing site boundary location.                                                                                           Since elevated . releases occur from the BVPS site 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 distances, greater than the site boundary, were also considered in conjunction with the radionuclides mix to determine the controlling location. These values of X/Q were obtained for the midpoint of
                                 . the 10 standard distance intervals previously presented in- Tables 2.2-4 through 2.2-10.

For' each release mode a particular combination of release point mix and

meteorology dominates in the determination of the contro111ng' location. For g release modes 1, 2, 3, and 4, the controlling release is the Ventilation Vent. For release mode ~ 3, the controlling release, is the Containment Building Vent. Values -for M g and N, j which were used in the determination of the controlling location and which are to be used by BVPS-1 in Expressions (2.3-

9) and (2.3-10) to show compliance with 10 CFR 50 were presented ~ in' Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109, Revision I

were multiplied by 1E6 to convert from picocuries" to microcuries for use in Table 2.2-11. In the determination of the controlling location for Modes 1, 2, 3, and 4, Tables 2.2-4 through 2.2-7 are utilized for X/Q values. The B f values to be utilized are the same values which were presented 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-1 to show compliance with Technical Specification 3.11.2.2: 2-48 ISSUE 2 REVISION 2 4 , h _ ___m.__m__._m__.____.________m.m_m_____.___ _ _ _ _ _ _ _ _ . . _ _ _ _

u- ,-. _ __ - __ _. 1 BV-1 ODCM

                                                      - For the calendar quarter:

i Dg 6 5 mrad (2.3-11) [N/ D 5 10 mrad (2.3-12) 3 For-the calendar year: Dg 5 10 mrad (2.3-13) Dg 5 20 mrad (2.3-14) where: D = the air dose from gamma radiation, mrad. 7 D = the air dose from beta radiation, mrad. 3 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 2.3-11 through 2.3-14 are exceeded, a special report pursuant _to both Section IV.A of Appendix I of 10 CFR 50 and Technical Specification 3.11.2.2.a must be filed with the NRC at the identified locations. In addition, BVTS.3.1.2.4 requires that the gaseous radwaste system must be used to reduce radioactive niaterials in that waste when projected doses from each reactor unit when averaged over 31 days exceed any of the following: l 6/89

    -D                                                                                    D s 0.2 mrad                              (2.3-15) 7 D 5 0.4 mrad                              (2.3-16) 3 2.3.1.2                      Projection of Dos-s (Noble Gas)

Doses due' to gaseous releases from BVPS-1 shall be projected at least once per 31 days in accordance with BVTS 4.11.2.4 and this section. (See also Section 2.3.2.2 P_rojection of Doses). The Gaseous Radwaste Treatmer.t System and the Ventilation Exhaust Treatment System shall be used to reduce

                                                      - radioactive      materials in gaseous waste prior to their discharge in accordance with BVTS 3.11.2.4 when the projected gaseous effluent air dose due to gaseous effluent releases from each reactor unit, when averaged over             6/89 31 days, would exceed 0.2 mrad for gamma radiatlon and 0.4 mrad for beta radiation.       (See also Section 2.3.2.2 Projection of Doses for additional specifications). The doses used .ni            the 31-day dose projection will be calculated using Expressions 't.3-9 and 2.3-10 as appropriate. The 31-day dose projection shall be performed according to the following equations:

When including pre-release data

                                                                                                     ~
                                                                                              "A + B D    =            ( )                             '

37 T 2-49 ISSUE 2 REVISION 2

! BV-1 ODCM I When not including pre-release data

7 ., I A '~ D 31 _T,J C31) + C (2 > 18) Where: D 33

                                          =    Projected 31 day dose, mrad A      =    Cumula+3ve dose for quarter, mrad D      =    Projected dose from this release, mrad T      =    Current days into quarter C      =    Value which may be used to anticipate plant trends, mrad 2,3.2    Radiciodine and Particulate l

2.3.2.1 Cumulation of Doses Section IIC of Appendix I of 10 CFR 50 (BVTS 3.11.2.3 and 3.11.2.4) limits the release of radiciodines and radioactive material in particulate form irom eac' reactor such that estimated dose or dose commitment to cn 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 requiret. the use of gaseour radwaste treatment system when the projected dose due to gaseous effluent releases from each reactor unit, when averaged over 31 6/89 dcys, would exceed 0.3 mrem to any organ. Based upon NUREG"0133, the dose to an organ of an individual from radioiodines and particulate, and radionuclides other than noble gases with half-lives greator than 8 days in gaseous effluents released to unrestricted areas, can be determined by the i following expression: During any month, calendar quarter or year: 0.3 mrem (per 31 days) 3.17E-8 I R."[W"Q'" + w*q " + W"Q'V + w"qfV) $ 7.5 mrem (per quarter) i 15.0 mrem (per calendar year) (2.3-19) where:

                                             = release of radionuclides "i" for long-term free standing stack Q'*         releases (greater than 500 hrs /yr), pCi;
                                             = release of radionuclides "i" for long-term vent releases Q'Y (greater than 500 hrs /yr), pCi; g,        = release of radionuclides "i" for short-term free standing g

stack releases (equal to or less than 500 hrs /yr), pCi; q iv

                                             = release of radionuclides "i" for short-term vent releases (equal to or less than 500 hrs /yr), pCi; 2-50                                                   ISSUE 2

( REVISION 2

BV-1 ODCM W

                                                                                        = dispersion parameter for estimating dose to an individual at the controlling location for long-term free standing stack
   ,i,q                                                                                        releases (greater than 500 hrs /yr);                                                                                                                                                                                           1
         -.l                                                                                                  8
                                                                                        = sec/m for the inhalatiun pathway, (5[Q)s'                                                                                                                                                                                           !
                                                                                        = met'ers'8 for'the food and ground plane pathway, (D/Q)si                                                                                                                                                                            !

V =.the . dispersion parameter for estimating the dose to an v individual at the controlling location for long-term vent releases (greater than 500 hrs /yr); I

                                                                                      -=sec/m'fortheinhalationpathway,(5[6)y; 8
                                                                                                                 ~

n' meters " for the food and ground plane pathway, (D/Q)y; w s

                                                                                        = dispersion parameter for estimating.the dose to an individual at the controlling location for short-term stack releases (equal to or less than 500' hrs /yr);

I 4 8

                                                                                        = sec/m for the inhalation pathway, (X/q)s;                                                                                                                                                                                           I j

i

                                                                                                                                                                                                                                                                ,                                                             J
                                                                                        = meters ~8                        for the food and ground plane pathway, (D/q),;

w = the dispersion parameter for estimating the dose 'to an ; indiv' dual at the controlling location for short-term vent j rutases (equal to or less than 500 hrs /yr); 8

                                                                                        = sec/m for the inhalation pathway, (X/q)y; 2      for the food and ground plane pathway, (D/q) ;                                                                                                                                                     j
                                                                                        = meters 3.17E-8 = the inverse of the number of seconds in a year;                                                                                                                                                                                                      j R.

IT

                                                                                        = the dose factor for ea b identi' ied radionuclides "1"                                                                                                                                           for the
                                                                                                                                                                                                                                                                                    ~8 or mrem /yr organ "t" of interest, mrem /yr per pCi/sec per m per pCi/m 8.

l 1 1 I I i b 2-51 ISSUE 2 REVISION 2 __ - . _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ - . - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ . - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____.----____-._._________________a

BV-1 ODCM

            . Radionuc1' ides and particulate-may be released from any of the BVPS-1 vents in the release modes identified in Table 2.3-1. As. described pt.viously~ in
  . [p     Section 2.3.1.1 at Beaver Valley Unit 1, NUREG 0133 permits use of long-term is _/      annual average dispersion calculations which with the release modes of Table 2.3-1 results in the following expr3ssions'to show compliance with BVTS (1            3.11.2.3 and BVTS 3.11.2.4.          For a particular- organ, Expression 2.3-19 becomes:                                                                                                           _

3.17E-8 I R it 0.5 Wpv Q.i 4 WcvQi +W vv Qi +W tvQi f 0.3 mrem (per 31 days) S 7.5 mrem (per quarter) (2.3-20) 15.0 mrem (per calendar year). where: W = dispersion parameter for releases from the Process vent; PV W = dispersion parameter for releases from the Containment ; Building Vent; W y = dispersion parameter for releases from the Ventilation Vent; W y = dispersion parameter for releases from the Turbine Building Vent; i Oy = release of radionuclides "i" from the Process Vent, pCi; f-~3 (%,/ ) pv l Qg = release of radionuclides ~"1" from the Containment Building cv Vent, pCi; l Q = release of radionuclides "i" from the Ventilation Vent, pCi; , vv 1 Qj = release of radionuclides "1" from the Turbine Building Vent, ! tv BCi; The Turbine Building Vent is not normally a radioactive release point. It ! is included only for use if a radioactive release is identified in the ; future. In determining the dose at a particular location, dispersion parameter U, is l a functior. of the pathway. For the food and ground plane pathway, W is in i terms of D/Q. If the inhalation pathway is considered, W is in terms of l X/Q. Incorporation of the various pathways into Expression 2.3-20 results ;

            .in the following expression for a particular organ:                                                                                               j

} t: O) ( s_- 2-52 ISSUE 2 REVISION 2 1 i

BV-1 ODCM

                                                                                + R.       +R                                             +W cvQi         +W    Q.             +W tv Q.i                      )

h y + R-n ) [0.5 Wpv i

                                                   ' 3.17E-8 I      [R it                                 .                       Q g            g         ng                       3                       ,                      vv 1,y                           ty
       -d                                                    +Rh[0,5(X/Q)py Q g pv
                                                                                                     + (X/Q) ,Q g cv
                                                                                                                              +  (X/Q)yyQ 1 vv
                                                                                                                                                      + (X/Q) ,Q 1           )

I tv , 0.3 mrem (per 31 days)' 5 7.5 mrem (per quarter) (2.3-21) 15.0 mrein (per year) where: R = dose factor for an organ "t" for radionaclide "i" for the h G ground plane exposure pathway, mrem /yr per pCi/sec per m~2; R dose . factor for an organ "t" for radionuclides "i" for either h M the cow milk or goat milk pathway, mrem /yr per pCi/sec per m'2; R h

                                                                        =          dose factor fcr an organ                     "t"   for radionuclides "i" for the V             vegetable pathway, mrem /yr per pCi/sec per m"',

R = dose factor for an organ "t" for radionuclides "i" for the meat-h B pathway, mrem /yr per pCi/sec per m 2;

                   -                                            R It
                                                                        =          dose factor for an organ                     "t"   for radionuclides "i" for the I             inhalation pathway, mrem /yr per pCi/m';

It should be noted that W py, Wcv, and W yy in Expression 2.3-21 are in terms of-D/Q(m 8). Values of the dose factor, Rh , were calculated using the methodology of NUREG-0133. The following equations were used for all nuclides except tritium: R = K'(BR), (DFAh)a (mrem /yr Per pC1/m ) 3 (2.3-22) h 7 where: - K' = a constant of unit conversion 1E6 pCi/pCi; (BR)a

                                                                                   =       the breathing rate of the receptor of age group (a), in m 3 /yr;

( 2-53 ISSUE 2 REVISION 2

                                                                                                                                                                 <        Y               "

q g ,,c, f{w-r ,4n g' p .y 4.. x :BV-If0DCMJ Qy.,!%li p 3.g y . '- ' y(; .3 L .it . . ., ,_ , N

                                                                                                                              /each organ.Yinhalatica : dose factor: for the receptor lof P'#                       '(DFAQ)(c= ' *'agef groupi'(a)-(for-?^the; "i"- :th. -radionuclides', . in-

" $g sb"b .i; k .' t :ht 4 M

yve

                                ; 3~R ,

a., ,

                                                                                                                              ' mrem /pCi? Inhalation. dose' factors (DFAl1)1by:               1       organ; for.
                                                                  , e s. ' ,

% < - i . the various. age' groups are given<.in Tab 1'e-E-7,through E - -j [(Q-[0 g Y' ,, 110 lof.' Regulatory: Guide l.109, Rev. I' orlTables 5 thronyu H hh > J8 of NUREG-0172.' y7y , - -

i.h,, , , .,. , , ..

                                                           ..'~The breathin.g frates ~f(B.R)a.cssed.:for                                  1                         'the various. age groups are. tabulated:
                                , %.o W p           M                                                    r,         .                                            .                 ,

vbelow,[aslgiven in Table -E-5 of 'the Regulatory Guide :1:109.

p. ,%.f' NM.J .j

                                                                                                                                                                                           ,                              .i 4:                                 .                                                                                                      ..                                            ..

Breathing' Rate (m'/yr)" 40; LAge Group (a)' '

I wr f,_'" *

                                           .. a bY e        >    n,
                                                                                             ,      i                      JInfant                                            '1400'                                     .a

,"'tY , ' r. . Child ~ '3700' . A: >

                                                                                                                          ' Teen                                               8000 hi, l.                                                    '

1 Adult'. 8000 .J Oh ; . t f .. R .= K'N". (SF)DFGg [(1:- e i )/1 ]J(m*-mrem f /yr.per pCi/sec) l (2.3-23) j A > ., 3;' Jwhere: {

  ;           . ,                                                                  'K'              =   ~ Ja constant'of unit conversion IE6 pCi/pCi; g
                                                    -                             ;K"              T='       .a constant/ of unit' conversion, 8760 hr/ year;
                                                                                                                                                                                                                         .i

y. +9p , '

j h ,

                                                                                                   .=        :the decay' constant.for the "i" th radionuclides, sec~2; o

6 at ~= the exposure time,.4.73E8 s'ec (15 years); .; i J p 'DFG gT = the groundplane dose conversion factor for organ "t" for the .j "i":th radionuclides' -(mrem /hr per pCi/m'). A tabulation .of ! DFGy values - is : presented in Table E-6 of Regulatory Guide !

                                                                                                                                                                                                                         .l  1 s                                                             .                                                1.109;                                                                                                     !
                                                                                                                                                                                                                             )

t SF = .the shielding factor (dimensionless). A shielding factor of .l 0.7 as, suggested in Table E-15 of Regulatory Guide 1.109 is ! c'-- used.

                                                                                                                                                                                          -1 t                              i 1

c, Q ff (1 - f f )e ih -1 gf t ! K, 7(Uap)F (r)(DFL PS RIt ) [Ps 4 9 773 > t M m it a Y Y ! it e.,,. 1'I+1W P S -j i D (m8 -mrem /yr per pCi/sec) (2.3-24) 't i -:,- f !

      - -; .A,'l                                '

j q! y. l 'fv- ); l j i 2-54 ISSUE 2 i e . REVISION 2 I n I[ > q [

i. M .

d i j

              .d k Q _                                   w.

,p9 g wx - - -m .) 9 , g , , BVel ODCM p, A , where: l

  ',                            K'       =    a constant of unit conversion, IE6 pC3/pCi; Q p.     =    the animals' consumption rate, in kg/ day (wet weight);

l U ap

                                         =    the -receptor's milk consumption rate, for age (a), in         !

liters /yr; l l Y_ = the agricultural productivity- by unit area of pasture , P feed grass, in kg/m 8; l Yg =- the agricultural productivity by - unit area of stored ;

..                                            feed, in kg/m*;                                                j i,

F, = the stable element transfer coefficients, in days / liter; ; r = fraction of deposited activity retained on animals feed l grass; j I

                                         =    the maximum organ ingestion dose factor for the "i" th (DFLh)&      radionuclides for the receptor in age group (a), in mrem /pC1. Ingestion dose factors (DFLg ), for the various age groups are given in Table E-11 through E-14 of Regulatory Guide 1.109 or Tables 1 through 4 of NUREG-0172.

[ -

                                'A g
                                         =    the decay constant for the "i" th radionuclides, in sec ~1;                                                        !

l = the decay constant for removal of activity on leaf and y plant surfaces by weathering 5.73E-7 sec ~1 1 (corresponding to a 14 day half-life); tg = the transport time from pasture to animal, to milk, to ; receptor, in sec; t h

                                         =    the transport time from pasture, to harvest, to animal, to milk, to receptor, in sec; f        =    fraction of the year that the animal is on pasture r                             P          (dimensionless);

f = fraction of the animal feed that is pasture grass while the animal is on pasture (dimensionless). Tabulated below are the parameter values used for cow's milk and their reference to Regulatory Guide 1.109. i 2-55 ISSUE 2 REVISION 2

BV-1 ODCM-Parameter Value Table r (dimensionless)~ 1.0 for radioiodine E-15

         ,I E-15 f (TN

'- ~, 0.2 for particulate Each Stable' element E-1-(Cow milk) F* (days / liter) 6/89 E-2 (goat milk) 330 E-5 U ap (liters /yr) - Infant Child 330 E-5 Teen 400 E-5 Adult 310 E-5 (DFLg), (mrem /pCi) Each radionuclides E-11 to E-14 Y (kg/m ) 0.7 E-15 Y, (kg/m ) 2 2.0 E-15 t 1.73E5 (2 days) E-15 f (seconds) _ t 7.78E6 (90 days) E-15 h (sec nds) Qp (kg/ day) 50 E-3 f 0.5 - P f, 1.0 _ For goat's milk, all values remain the same except for QFwhich is 6 kg/ day, k_)' Q ff ih -1 t if [ P S +'(1 - PS

R iT g, F(Uap)F (r)(DFL ) f f )e je B f it a Y Y 13 + 1,, 3 (m*-mrem /yr per pCi/sec) (2.3-25) where: F = the stable element transfer coefficients, in days /kg; f U = the receptor's meat consumption rate for age (a) in kg/yr; t = the average time from slaughter of meat animal to 6/89 f consumption, in sec; t = the transport time f rom crop field to receptor, in sec. h All parameter values are the same as the milk pathway parameter values except F which is obtained from Table E-1, t which is obtained from Table g f 6/89 E-15. and U ap which is obtained from Table E-5. The values as obtained from Regulatory Guide 1.109, are as follows:

   .p) 5 V

2-56 ISSUE 2 REVISION 2

                  =-__-__.-_-_-_____-__           _-

7 BV-1 ODCM Parameter- Value Table 1 (j 'Ff (days /kg) Each stable element E-1 ' %~ J l t 1.73E6 (20 days) E-15 6/89 f (seconds) U 0 E-5 ! ap (kg/yr) - Infant Chila 41 E-5' j Teen 65 E-5 -; Adult 110 E-5 j l

                                                        . Man is considered to consume two types of vegetation (fresh and stored) that                                         '

differ only in the time period between harvest and consumption; therefore: i

                                                                                                               -1 t       -1 t

(#) b 6 it = K' [ ](DFL ) [U f e ib+Ufe i h) ag V Yy (Af+k) it a 'a L i (m*-mrem /yr per pCi/sec) (2.3-26) ] l where: : i K' = a constant of unit conversion IE6 pCi/pCi; l L = the consumption rate of fresh leafy vegetation by the U, j receptor in age group (a), in kg/yr; i

g. 1

("' U = the consumption rate of stored vegetation by the receptor in age group'(a) in kg/yr;

                                                                                                                                                                             'j f       =       the fraction of the annual intake of fresh leafy vegetation grown locally;                                                                                  t i

f = the fraction of the annual intake of stored vegetation grown j 8 locally, i t g

                                                                       =       the average time between harvest of leafy vegetation and its consumption, in seconds; t p'    =       the average time between harvest of stored vegetation and its                                    ,

consumption, in seconds; Y y

                                                                       =       the vegetation area density, in kg/m*;

aid all other factors are defined previously. ; i Tabulated below are the appropriate parameter values and their reference to ] Regulatory Guide 1.109. 1 i 2-57 ISSUE 2 REVISION 2

                                   >v                                                                                                                                                                                                                                                                     .q BV-1 ODCM                                                                                        v Table-

^

Parameter' > TValue-y'Y - r F (dimensionless) - 1.0 for.radiciodines- E-15 0,2-for particulate' .

E-15 Each Radionuclides E-11 to E-14~ (DFLit)a.(mrem /pCi). Ub - (kg/yr) - Infant. 0 E-5 Child-

a' 26: E -Teen 42 E-5 Adult 64 E-5

U (kg/yr) - Infant. 0 E-5

                                                             .a                                                       '

Child 520 E-5 Teen- 630 E-5 Adult 520 E-5 fg-(dimensionless). 1.0 E-15 F' 0.76 E-15

                                                                  & (dimensionless) t (seconds ~)                                                                                                           8.6E4 (1 day)                          E-15 t                                                                                                                       5.18E6 (60 days)                       E-15 h (sec nds) i     4                                        Yy (hg/m 2)                                                                                                                       2.0                          E-15 As discussed in Section                                                                                                                  2.2.2,    for tritium the parameter W for the food pathway is based upon X/Q. The ground plane pathway is not appropriate for tritium.                                                                              Therefore, the left-hand portion of Expression 2.3-20 may be

_h V

                                     , expressed for purposes of implementation of 40 CFR 190, discussed in Section
                                      .4.0,:as:
                                     -For tritium:

3.17E-8 (RTT +R +R + Tt ) [0.5 (X/Q)p QTpv + (X/Q)cyQTcv

                                                                                                                                                            + lL t        Tt M-                 V         B        I (X/Q) QT       + (X/Q) QT      ]                                                                        (2.3-27) vv               tv where:

R = dose factor for organ "t" for tritium for the milk pathway, Tt M mrem /yr per pCi/sec8 ; R = dose factor for organ "t" for tritium for the vegetable Tt V pathway, mrem /yr per pC1/m*; R = dose factor for organ "t" for tritium for the beef pathway, Tt B mrem /yr per pCi/m8 ; P g = dose factor for organ "t" for tritium for the inhalation I pathway , mrem /yr per pCi/m' . l 2-58 ISSUE 2 REVISION 2

v y

                                                                              'BV-1 ODCM
     #                                                                                                                                                                                                           l

_. Expression' 2.-3-27 V . In Section;4.0. .is used.to show compliance with 40 CFR 190, as~ discussed, O

    . -[jI                      The ratherconcentration than'the deposition. of tritium'in     milk'is based Therefore,    the,R on the airborne concentration Nj.                                                                                                                             Tt3--'is based on [X/Q):

1

                                     ;RTt g_ =   K'K'"F,Q UF ap(DFLg ),[0.75(0.5/H)] (mrem /yr..per pCi/m8). -                                                                                                   i
                                                                                                                                                                                                              .1 (2.3-28) where:

K'"

==

a constant of unit conversion,.108 gm/kg; H- =

                                                                                                                                                                                                              .i absolute humidity of the atmosphere, in gm/m';                                                                                                             .
                                                                                                                                                                                                              .i 0.75 =          the fraction' of total feed that is water;                                                                                                                  !

J.5 =

                                                    .the     ratio of the specific activity of the feed grass water to the atmospheric water.

and' other parameters and values are the same as for R The value of H

h. j used is 8.g:ams/ meter'. M The concentration of tritium .in vegetation is . based on the airborne ~ !

concentration rether than the deposition. Therefore, the R is based on [X/Q]: l L S i' R.7, = K'K'" [U,f3 + U,f ](DFLg)a[0.75(0.5/H)] (mrem /yr per pCi/m') (2.3-29) { where all terms have been defined above. The

                         -ratherconcentration than the deposition. of tritium Therefore, in meat is the based R on its airborne concentration                                                                                   !

Tg is based on [X/Q]: R Tg = K'K'"F Q U7 F ap (DFLg),IO.75(0.5/H)] l (mrem /yr per pC1/m8 ) (2.3-30) j where all terms have been defined abov9. l l l 1 i 2-59 ISSUE 2 REVISION 2

                                                                                                   ._ _ - _ _ _ = - _ - . _ - _ _ - _               . - - _ _ _ - - _ - - . - ___-

q

a. .

BV-1 ODCM l Tc show compliance with .BVTS 3.11.2.3 and BYTS 3.11.2.4. Equation z 3-21 is= t , evaluated at the controlling pathway location. For release modes I through 4, 'the. controlling. location .is a residence 0.89 miles in the NW sector. [] Inserting appropriate'X/Q values from Tables 2.2-4 to 2.2-10 and D/Q values '! (f: from Tables 2.3-28 to 2.3-34, Expression 2.3-21 becomes- ! i Release Modes 1 through 4 Per month, calendar quarter or year: l0/09 3.17E-8.I f +R + 1.55E-8 [R h h ][(0.5)4.22E-10 Qg-pv + 1.56E-8 Q , + 1.56E-8 Qgvv ) G V ; Qg ]+Rg [(0.5) 7.30E-9 Og

                                                                            + 2.00E-3 Q g       + 2.71E-5 Q g                             + 2.22E-5 Q g :]

tv I pv cv vv tv' ! 0.3 mrem (per 31 days) 5 7.5 mrem (per quarter) (2.3-31) l 15.0 mrem (per year) j i For' tritium, for purposes of implementation of 40 CFR 190, as discussed in Section 4.0, Expression 2.3-28 reduces to: i 3.17E-B [RTT +Rg ][(0.5)7.30E-9 Qg + 2.00E-5 Q j + 2.71E-5 Q j ] V. I pv cv vv ) I (2.3-32)

  .m,                     The determination of a controlling locating for implementation of BVTS                                                                                             :

( -3.11.2.3 and BVTS 3 11.2.4 for radiciodines and particulate is a. function l of: ; (1) radionuclides mix nnd their isotopic release ! (2) release mode 1 (3) meteorology. . (4) exposure pathway ] (5) receptor's age l The incorporation of these parameters into Expression 2.3-19 results in the respective equations for each release mode at the controlling location. . In the determination of the controlling location for each release mode, the l radionuclides mix of radiciodines and particulate was based upon the source ; terms calculated using the GALE code. This mix was presented in Table 2.2-2 l as a function of release mode and release point. For the ground plane exposure pathway, all radionuclides (excluding H-3 and C-14) were considered in the dete mination of the controlling location. For the inhalation and food pathways H-3 and C-14 were also considered in determination of the , 4 controlling location. , l C i 2-60 ISSUE 2 l REVISION 2 , j

BV-1 ODCM I h > ;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.' .

                                                                                                                     ;l
   /',                           These' include cow milk, goat milk, beef and vegetable ingestion and.
                                . inhalation and ground plane exposure. An infant was assumed to be present            l at .all' milk. pathway locations. A child was assumed to be present at all l

vegetable garden and beef animal locations. The ground plane.and inhalation- ;

f exposure pathways were considered to be present at all locations. l 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

                               . milk, and g>at milk' pathways were selected. The organ dose was calculated:
                               .at'each of these' locations using the radionuclides mix and release of Table-2.2-2.      Based- upon these calculations, it was determined that' the controlling location ~for release modes 1 through 4 is the residence (vegetable garden)/ child pathway.

For release mode 1 through 4, the contre 111ng release point and mix is the j Ventilation Veat. : Tables 2.3-2 through 2.3-20 present gR values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways- for the infant, child, teen and adult age groups as appropriate to the pathways. These values were calculated using the methodology described in NUREG-0133 ; using a grazing period of 6 months. l p Ini the determination of the controlling location for release Modes 1 a 4") Tables 2.2-4 through 2.2-7 are utilized for the X/Q for releases from tde process vent, containment building vent, the ventilation vent, and the I turbine building /ent. Tables 2.3-28 through 2.3-34 are utilized for long .; term D/Q values from the process vent, containment building vent, the ventilation vent, and the turbine building vent. A description of .the derivation of the various X/Q and D/Q values is presented in Appendix A. j i

                                .Long-term .D/Q values for the process vent, cot.tainment building vent, the           l ventilation vent, and turbine building vent are provided for the midpoints            )

of 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., 4.0-4.5 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-1 to show compliance with BVPS Technical Specification 3.11.2.3. l For the calendar quarter: i i D 5 7.5 mrem to any organ (2.3-33) ; O 2-61 ISSUE ' I REVISION 2

t BV-1 ODCM L For'the ca?2ndar year: n D 5 15 mrem to any organ (2.3-34)

f )

i v where: D = the dose to any- organ from radiolodines and particulate, mrem. l The quar erly limits given above represent one-half the' annual design objective of Section IIC of Appe.ndix 1 of 10 CFR 50. If any of the limits of Expressions 2.3-33 and 2.3-34 are exceeded, a special report pursuant.to both Section IV.A of Appendix I of 10 CFR 50 and Technical Specification 3.11.2.3.a must be filed with the NRC at the identified locations. 2.3.2.2 Projection of Doses (Iodines and Particulate) Doses d te to gas ' us releases from the BVPS-1 shall be projected at least once also per 31 days in accordance with BVTS 4.11.2.4 and this section. (See Se: tion 2.3.1.2 Projection of Doses). The appropriate portions of the Ventilat ion Exhaust Treatment System shall be materials used to reduce radioactive in gaseous waste prior to their discharge in accordance with BVTS 3.11.2.4 when the projected doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any 6/89 organ. (See also Section 2.3.1.2 Projection of Doses for additional specifications). Doses resulting from the gaseous effluent release from each reactor unit, whenof radiciodines and particulate will be calculated for use in the 31-day dose projection using Expression (2.3-31). The 31-day dose prajection shall be performed according to the following equations: When.ircluding pre-release data n - A+B D 31 , T , ( '

When not including pre-release data

                                                                                                                                                                                                       ~
                                                                                                                                                                                                    'A D

where; 31 = d (31) + C (2.3-36) 3 = Projected 31 day dose, mrem 31 = A

Cumulative dose for quarter, mrem B Projected dose for this release, mrem T = Current days into quarter C = Value which may be used to anticipate plant trends, mrem 2-62 IFSUE 2 RrSISION 2

=x                                                                                                                                   n 7q                                                               ,                               ,,
                            .(      4
                                                                             'BV-1 DDCM
                                                                               -TABLE 2.3-l'
           ~

MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS

                                                           'FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 .

[u Release Point Mode'1 Mode 2 Mode 3 -Mode 4 8 BVPS-1:- BVPS Main Cond'.~ Air Same As ;Same as -Same as Process Vent (pv) Ejector, Waste Mode 1~- Mode 1 ' Mode 1 and Gas,.Contain-ment Vacuum . Containment-Purge.

                                                                                                                                     -l BVPS-1 Ventilation 2                     Aux.' Bldg.                                                            l cVent'(vv1).                                                    ' Containment Same as.           Same as Ventilation.            Purge

Mode 1 Mode 1 l

BVPS-1. Containment

LLeakage; S'me a as Vent (cyl) .. Same as Same as-Collection Mode'l . Mode l'and. .;

Exhaust Mode 1 Containment Purge' ( BVPS-1 Turbine Bldg.1 . Turbine Bldg Same as Same as i Vent (tv1) Exhaust *. Same as ! Mode 1* Mode 1* Mode 1* 1 BVPS-2 Ventilation 3 Contiguous Vent (vv2) Containment Same as .Same as Areas Purge 3 Mode 1 Mode 1 BVPS-2 Containment 2 Aux. Bldg. Same as I Same as Same as

                     . Vent . (cv2)                            Ventilation            Mode 1                                           j Mode I and       Mode 1 Containment-                      i i

8 Purge

  '('        .
               ~
                   .BVPS-2 Turbine Bldg.2                      Turbine BIdg           Same as       Same as                            )

Same as-

                   . Vent (tv2)                                Exhaust

Mode 1* j Mode 1* Mode 1* i i

BVPS-2 Condensate 2 * * *

                   . Polishing Bldg. Vent                                                                                   *

(cp2) { BVPS-2 Decontamination 2 * *

Bldg. Vent (dv2)
E!

BVPS-2 Waste Gas * * *

Storage Vault Vent
1 (wv2) I

                   *Not.normally a radioactive release point                                                                           !

Note: For the purpose of implementing 10 CFR 50, batch discharges may use .j continuous meteorology since short term meteorology is used at the time

                                     .of the annual report.                                                                             l 1

2 Continuous ground level meteorology is applicable Continuous elevated meteorology is applicable

                  ' Mode established by purge from one unit as Mode 1.                                                      , all other release points remain same i

i i 2-63 ISSUE 2 3 i REVISION 2 i

7 .. .

                                                                                                                                    -)
                                  ,                                                                                                 1 i

k

 .                                                                           EV-1 OKM                                                  l l

Table 2.3-2 RVAL"ESFOREEAVEBVALLEYSITE '! (area /yrperuti/euseter) i . Pathway: Inhalation ;

  <                                            AgeGroup: Adult                                                                         l

< l Iluellde Bone Liver I. Body thyroid Eldney Lung GI-LLI 1H-3 0.00E+001.26E+031.26E+031.26E+031.26E+031.26E+031.26E+03 2P-32 1.32E+067.71E+045.01E+040.00E+000.00E+000.00E+008.64E+04 g 3Cr-51 0.00!+000.00E+001.00E+025.95E+012.2EE+011.44E+043.32E+03 j r 4Mn-54 0.00E+003.961+046.30E+030.00E+009.64E+031.40E+067.74E+04 # 5Ee-59 1.12E+042.1EE+041.06H+040.00E+000.00E+001.02E+061.BBI+05 600-57 0.00'E+006.92E+026.71E+020.00E+000.00E403.70E+053.14E+04 ]

                                            -7C0-58      0.00E+001.5EE+032.07E+030.00!+000.00E+009.265+051.065+05                      l 8 00-60 ' O.00E+001.15E+041.46E+040.00E+000.00E+005.97E+062.85E+05                        )

9Zn-65 3.24E+041.03E*054.66E+040.00E+006.90E+048.64E+055.34E+04 l L 10Eb-56 0.00E+001.35E+055.90E+040.00E+000.00E+000.00E+001.66E+04 11St-89 3.04E+050.00E+008.72E+030.00E+000.00E+001.40E+063.50E+05 , 12St-90 9.92E+070.00E+006.10E+060.00E+000.00E+009.60E+061.22E+05 p 13Y-91 4.62E+050.00E+001.24E+040.00E+000.00E+001.70E+063.85E+05 l t / 14Zr-95 1.07E+053.44E+042.33E+040.00E+005.42H+041.77t+061.50E+05 15 lib-95 1.(1E+047.82E+034.21E+030.00E+007.7(E+035.05E+051.04E+05 : C/89

16Hb-97 2.22E-015.62E-022.05E-020.00E+006.541-022.40E+032.42E+02 , 1750-99 0.00E,001.21E+022.30E+010.00!+002.91E+029.12E+042.46t+05 ! 18fe-9?: 1.03E-052.91E-033.70E-020.00!+004.42E-027.64E+024.16t+03 19R-103 1.53E+030.00E+006.58E+020.00E+005.83E+035.05E+051.10E+05 l 20Ru-106 6.91E+040.00E+008.72E+030.00E+001.34E+059.36E+069.12E+05 l 1 21Ag-110 1.08E+041.00!+045.94E+030.00E+001.97E+044.63E+063.02E+05 ; j 22Sb-124 3.12E+045.89E+021.24E+C47.55E+010.00E+002.461+064.06H+05 23Sb-125 5.34E+045.95E+021.26E+045.40E+010.00E+001.74E+061.01E+05 ; 24fe-127 1.26E+045.77E+031.57E+033.29E+034.5EE+049.60E+051.50E+05 l 25fe-129: 9.76E+034.67E+031.5BE+033.44E+033.66E+041.16E+063.63E+05 26I-131 2.52E+043.5EE+042.05E+041.19E+076.13E+040.00E+006.22E+0S i 27I-133 8.64E+031.4BE+044.52E+032.1SE+062.58E+040.00E+008. BEE +03 ! 28Ce-134 3.73E+058.4BE+057.2EE+050.00E+002.875+059.76E+041.04E+04 ! 29Cs-136 3.90E+041.46t+051.10E+050.00E+008.56E+041.20!+041.17E+04 ' 30Cs-137 4.76E+056.21E+054.2EE+050.00E+002.22E+057.52E+048.40E+03 31Ba-140 3.90E+044.90E+012.57E+030.00E+001.61E+011.27E+062.1EE+05 32La-140 3.44E+021.74E+024.5BE+010.00E+000.00!+001.36E+054.5EE+05 33Cr-1(1 1.99E+041.3fE+041.53E+030.00!+006.26E+033.62E+051.20E+05 34Ce-144 3.43E+061.43E+061.84E+050.00E+008.4BE+057.7EE+068.16E+05 y l\ CalculatedperOEMequatien2.3-22 2-64 ISSUE 2 REVISION 2 = _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _

               ;t H g;                                                                                                                           i SV-1ODCE V                                                           'Tette2.3-3' pi "f RVALUESFOREEAVERVALLEYSITE (area /yrperuCi/enmeter)                                              j Pathway: Inhalation AgeGroup: Teen helide        Bone      Liver T. Body Thyroid Eidter       Luts GI-LLI 1 b3       0.00D00 1.27bO3 1.27bO3 1. 27bO3 1.27bO3 1.27bO3 1.27bO3                             ;

2P-32 - 1.69b061.10b05 7.16b04 0.00b00 0.00D00 0.00b00 9.28b04 4 3Cr 0.00b00 0.00b001.35bO2 7.50b013.07b012.10D04 3.90bO3 j 4Mn-54 0.00b00 5.11b04 8.40E+03 0.00b$01.27b041.9Bb06 6.68b04 5Fe-59 1.59E404 3.70D041.43b04 0.00b00 0.00D001.53b061.7BP05 l 60o-57 0 v0b00 9.44bO2 9.20bO2 0.00b00 0.00b00 5.86be5 3.14b04 7Co-58 0.00b00 2.07bO3 2.78bO3 '0.00b00 0.00D001.34b06 9.52b04

                                                                                                                            'I BCo-60 _0.00b001.51b041.9Eb04 0.00D00 0.00b00 8.72b06 2.59b05 j

1 9Zn-65 3.86h041.34b05 6.2(D04 0.00h00 B.64b041.24b06 4.66b04 10 Rb-86 0.00b001.90D05 8.40D04 0.00D00 0.00b00 0.00D001.77b04 . j 11St-89 4.34b05 0.00b001.25b04 0.00D00 0.00D00 2.42b06 7.71b05' : i 12Sr-90 1.08bO8 0.00D00 0.68b06 0.00b00 0.00DC} 1.65b67 7.65b05 13I-91 6.61b05 0.00b001.77b04 0.00b00 0.00b00 2.94b06 4.09b05 : 5 14Zr-95 1.46b05 4.58b04 3.15b04 0.00D00 6.7(b04 2.6Sb061.49b05 15Nb-95 1.86D041.03b04 5.66bO3 0.00D001.00D04 7,51905 9.66b04 6/89 16Nb-97 3.14b017.781-022.84E-020.00D009.12E-023.S3bO32.17bO3 17Mo-99 0.00b001.69bO2 3.22b010.00D00 4.11bO21.54b05 2.69b05 i 18Te-99: 1.3BbO33.66bO34.99b020.00b005.76E-021.15bO36.13bO3 19 h-103. 2.10bO3 0.00 BOO B.96bO2 0.00b00 7.43bO3 7.63b051.09D05 20Ru-106 9.84b040.00b001.24b040.00b001.90D051.61bO79.60b05 21 Ag-110s 1.38b041.31b04 7.99bO3 0.00b00 2.50D04 6.75b06 2.73b05 1 22Sh-124 4.30b047.94bO21.68b049.76b010.00D003.34b063.98D05 23Sb-125 7.3Eb048.08bO21.72b047.04D010.00b002.74b069.92D04 24 Te-127a 1.80b04 8.16bO3 2.18bO3 4.38bO3 6.54b041.66b061.59D05 25 te-129s 1.39b04 6.58bO3 2.25bO3 4.58bO3 5.19b041.9Bb06 4.05b05 1 26I-131 3.54b04 4.91b04 2.64b041.46bO7 8.40D04 0.00b00 6.49bO3 27I-133 1.22b04 2.05b04 6.22bO3 2.92b06 3.59b04 0.00b001.03b0f 28Ce-134 5.02b051.13b06 5.49b05 0.00bu0 3.75b051.46b05 9.76bO3 1 29Cs-136 5.15b041.94b051.37b05 0.00D001.10h051.78b041.09b04

                                                                                                                              .i 30Cs-137 6.70D058.48b053.11b050.00D003.04b051.21b058.4Bb03 31Ba-140 5.47D046.70D013.52bO30.00b002.2Eb012.03b062.29b05 32La-140 4.79bO2 2.36bO2 6.26b010.00b00 0.00b00 2.1(D05 4.27b05 33Ce-141 2.84D041.90D04 2.17D03 0.00D00 B.8EbO3 S.14D051.26b05                                   ;

1 34Ce-144 4.89b06 2.02b06 2.62b05 0.00b001.21b061.34bO7 8.64b05 CalculatedperODCMequation2.3-22 2-65 ISSUE 2 ! REVISION 2

i

a BV-1ODCM a e: Tatie2.3-4' l EVALUESFORSEAVERVALLEYSITE j (area /rrpernCi/enmeter) Pathwar : Inhalation i AgeGroup: Child' ! Nuclide . Bone' Lin t T. Body Thyroid E' iter Lung GI-LLI i 1 H-3 ' O.00E+001.12E+031.12E+031.12E+031.12E+031.12E+03'1.12E+03' I i 2P-32 2.60E+061.14E+059.88E+040.00E+000.00E+000.00E+004.22E+04 g' 3Cr 0.00E+00 0.00b001.54E+02 B.55b012.43E+011.70E+041.0BE+03 q 4Hn-54 .0.00E+004.29E+049.51E+030.00E+001.00E+041.56E+062.29E+04 5fe-59 2.07E+043.34E+041.67E+040.00E+000.00E+001.27E+067.07E+04 600-57 0.00E+009.03E+021.07E+030.00E+000.00!+005.07t+051.32E+04 7Co-5B 0.00b001.77D033.16bO30.00E+000.00b001.11b063.44E+04 .l 8C0-60 0.00E+001.31E+042.26E+040.00E+000.00E+007.07E+069.62E+04-9In 4.25b041.13b05 7.03b04 0.00E+00 7.14b04 9.95b051.63E+04 [ 10Rb-66 0.00D001.96b051.14bo50.00b000.00E+000.00b007.99903 , 11St-B9 5.95b050.00D001.72b040.00b000.00b002.16b061.67b05 12St-90 1.01b080.00D006.44b060.00b000.00b001.48bO73.43b05 13Y-91 9.14b05 0.00D00 2.44b04 0.00D00 0.00D00 2.63E+061.64b05 .l 14Ir-95 1.90D05 4.1Bb04 3.70E+04 0.00D00 5.96b04 2.23b06 6.11b04 .l '

   \     -

15Nb-95 2.35b04 9.16bO3 6.55bO3 0.00D00 8.62bO3 6.14b05 3.70D04 6/89 1 16Nb-97 4.2SE-017.70E-02 3.60E-02 0.00D00 8.551-02 3.42bO3 2.7Eb04 l

1720-99 '0.00D001.72bO24.26b010.00D003.92bO21.35b051.27b05 1BTc-99: 1.78bO33.4BbO35.77E-020.00b005.07E-02S.51bO24.81bO3 19En-103 2.79b03 0.00b001.07E+03 0.00E+00 7.03bO3 6.62b05 4.4Bb04 ; 20Ru-106 1.36b050.00E+001.69E+040.00b001.84b051.43bO74.2Tib05 j i 21 Ag-110s 1.69b041.14D04 9.14E+03 0.00b00 2.12b04 5.4Bb061.00b05 22Sb-124 5.7(b047.40D022.00E+041.26bO20.00E+003.24b061.64b05 23Sb-125 9.64b04 7.59D02 2.07b04 9.10b010.00D00 2.32b06 4.03b04 24 te-127a 2.49b04 8.55bO3 3.0ZbO3 6.07bO3 6.36E+041.4Bb06 7.14b04 i 25 fe-129a 1.92b04 6.65bO3 3.04bO3 6.33bO3 5.03b041.76D061.82b05 26I-131 4.81b044.61b042.73b041.62bO77.BBb040.00b002.64bO3 27I-133 1.66b04 2.03b04 7.70D03 3.85E+06 3 36b04 0.00b00 5.48bO3 28Ce-13( 6.51b051.01D062.25b050.00D003.30D051.21D053.85bO3 3 29Ce-136 6.51b041.71b051.10D05 0.00b00 9.55b041.45b04 4.1BbO3 30Cs-137 9.07b05 8.25b051.28b05 0.00b00 2.82b051.04b05 3.62bO3 31Ba-140 7.Gb046.4Bb014.33b030.00b002.11b011.74b061.02b05 32La-140 6.4b022.25bO27.55b010.00D000.00D001.83b052.26b05 33Ce-141 3.92b041.95b04 2.90D03 0.00D00 8.55bO3 5.44b05 5.66b04 I 34Ce-144 6.77D06 2.12b06 3.61b05 0.00D001.17b061.20bO7 3.89b05 V CalenlatedperDDCHequation2.3-22 1 2-66 ISSUE 2 REVISION 2

1 L li' nV-1ODCM-1 I'}/] 1Xf Iatie2.3-5' HVALUESFOREIAVIHVALLETSITE (area /yrperuCi/cuseter) Pithver: Inhalation AgeGroup-Infant helide Bone Liver T. Body thyroid Kidney Lung GI-LLI 1H-3 0.00E+006A7E+026.47E+026.47E+026.47t+026.47E+026.47E+02 2P-32 2.03E+061.12E+057.74E+040.00E+000.00E+000.00E+001.61E+04 3Cr-51 0.00E+000.00E+008.95E+015.75E+011.32E+011.2BE+043.57E+02 lL 4 Mn-54 .0.00E+002.53E+044.98E+030.00E+004.98E+031.00E+067.06E+03 5Fe-59 '1.36E+042.35E+049.4BE+030.00E+000.00E+001.01E+062.4BE+04 6Co-57 0.00E+006.51E+026.41E+020.00E+000.00E+003.79E+054.86E+03 7 Co-58 0.00E+001.22E+031.82E+030.00E+000.00E+007.775+051.11E+04 8Co-60 0.00E+008.02E+031.161+040.00E+000.00E+004.51E+063.19E+04 9Zn-65 1.93E+046.26t+043.11E+040.00E+003.25E+046.47E+055.14E+04 10Rb-86 0.00E+001.90E+058.82E+040.00E+000.00E+000.00E+003.04E+03 11Sr-89 3.985+050.00E+001.14E+040.00E+000.00E+002.03E+066.40Et04 12St-90 4.09E+070.00E+002.59E+060.00E+000.00E+001.12E+071.31E+05 13Y-91 5.88E+050.00E+001.57E+040.00E+000.00E+002d5E+067.03E+04 14Ir-95 1.15E+052.79E+042.03E+040.00E+003.11E+041.75E+062.17t+04 15Hb-95 1.57E+04 6.43E+03 3.72E+03 0.00E+00 4.72E+03 4.79E+051.27E+04 6/89 16Nb-97 3.42E-017.29E-022.631-020.00E+005.70E-023.32E+032.69E+04 17 Ho-99 0.00E+001.65E+023.23E+010.00E+002.65E+021.35E+054.67E+04 18Tc-99: 1.40E-032.BBE-033.72E-020.00E+003.11E-028.11E+022.03E+03 19Ru-103 2.02E+030.00E+006.79E+020.00E+004.24E+035.52E+051.61E+04 20Ru-106 8.6BE+040.00E+001.09E+040.00E+001.07E+051.16E+071.64E+05 21 Ag-110e 9.9BE+03 7.22E+03 5.00E+03 0.00Et00 1.09E+04 3.67E+06 3.30E+04 22Sb-124 3.79E+045.56E+021.20E+041.01E+020.00E+002.65E+065.91E+04 23Sb-125 5.17E+044.77t+021.09E+046.23E+010.00E+001.64E+061.47E+04 24 fe-127a 1.67t+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 25 fe-129s 1.41E+04 6.09t+03 2.23Et03 4.21E+03 3.1BE+04 1.68E+06 6.90E+04 26I-131 3.79E+044.44E+041.96E+041.4BE+075.18t+040.00E+001.06E+03 27I-133 1.32E+041.92E+045.60E+033.56E+062.24E+040.00E+002.16E+03 28Cs-134 3.96E+057.03E+057.45E+040.00E+001.90E+057.97E+041.33E+03 29Cs-136 (.83E+041.35E+055.2SE+040.00E+005.64E+041.1BF+041.43E+03 30 Cs-137 5.49E+056.12E+054.55E+040.00E+001.72E+057.13E+041.33!+03 31Ba-140 5.60E+045.60E+012.90E+030.00E+001.34E+011.60E+063.8@04 32La-140 5.05E+022.00E+025.15E+010.00E+000.00E+001.6BE+05 BABE +04 33Ce-141 2.77E+041.67E+041.99E+030.00E+005.25E+035.17E+052.1904 34 Ce-144 3.19E+061.21E+061.76E+050.00E+005.3BI+059.84E+061.4BE+05 y CalculatedperODCHequation2.3-22 2-67 ISSUE 2 REVISION 2

/,

o n I' EV-1CDCM Table 2.36 BVALUESFORBEAVERVALLEYSITE' (sqseter-stes/yrperuCi/sec). r-

                                                                                                                                                                                                                              ,                                 -s

,A Pathway-Ground

Unclide Bone Liver T. Body Thyroid Kidney Lung GI-LL1 1E 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 ,

c 2P-32 0.00E40 0.00E+00 0.00E40 0.00Z+00 0.00E+00 0.00E+00 0.00E+00 j( h 3Cr-51 4.66E+064.66E+064.66t+064.66E464.66E+064.66E+064.66t+06 c '4 Un-54 1.39E+09 1.39E+09 1.398+09 1.39E+09 1.39E 49 1.398+09 1.39E+09 Y 5fe-59 2.73848 2.73E46 2.73E+08 2.73848 2.73E+08 2,73E48 2.72E+08 6Co-57 0.00E40 0.00!40 0.00H+00 0.00E+00 0.00E+00 0.00E+00 0.00!+00 7Co-58 3.79148 3.79148 3.79E+08 3.79E48 3.79E+08 3.79E+08 3.79k08 8Co 2.15E+102.15E+102.15E+102.15!+102.15E+102.15E+102.15E+10'. 92n45 7.47E+08 7.47E48 7.47t+08 7.47t+08 7 ATE 481A78+08 7.47143 10 Rb46 8.99E46 8.99146 8.99E+06 8.99E46 8.99E46 8.39E46 8.99E+06

                      '11 Sr-89. ' 2.168+04 2.16E+04 2.16E+04 2.16E+04 2.16E44 2.16E+04 2.16E44 12St-90                                                        0.00E400.00E+000.00E400.00E+000.00E+000.00E+000.00E+00

13 T41 1.07E+06 1.07t+06 1.07E+ 06 1.078+06 1.07846 1.07E46 1.07E+ 06 i 14 Ir45 -2.45E+082A5E+0B2.45E+082.45E+082.45E+082.45E+082A5E+08 15Nb45 1.37t+081.37t+081.378+081.37E+081.371+081.378+081.37E+0B 6/89 16Hb-97 0.00E400.00!+000.001+000.00E+000.00E+000.00E+000.00E+00 17 Mo49 4.00E+064.00E+064.00E+064.00E+064.00E+064.001464.00E+06 18fe49: 1.84E+05 1.84E+05 1.84E+05 1.84E45 1. 84E+05 1. 84E+05 1.84E+05 19En-103 1.081+0B1.08E481.08E+081.088481.08I481.08E+081.08E+08 20Ru-106 4.22E484.22E+084.22E+084.22E+0B4.22E+0B4.22E+084.22E+08 21 Ag-110s 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 3.44E+09 22Sb-124 0.0C!+000.00E400.00E+000.00E+000.00E400.00E+000.00E+00 23Sb-125 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00!+00 0.00E40 24Te-127: 9.17E+049.178+049.17E+049.17E+049.17E+049.17t+049.17E44 25 fe-129s 1.98t+071.98E471.98E471.98E+071.981+071.98t+071.98E+07 26I-131 1.72E471.72E+071.72E+071.72E+071.72E+071.721471.72E+07 27I-133 2J5E+06 2.45E46 2.45E+06 2.45E+06 2.45E+06 2A5E+06 2.45E46 28Cs-134 6.86E+096.86E+096.86E+096.86t+096.661+096.66E+096.86E+09 29Cs-136 1.51E+081.51Ed81.51I481.51E+081.51E+081.51E+0B1.51E+08 30Cs-137 1.03E+101.03E+101.03E+101.03E+101.03E+101.03E+101.03E+10 31Ba-140 2.05E+072.0$E+072.05E+072.05E+072.05E+072.05E+072.05E+07 32La-140 1.92E+071.92E+071.92E+071.92E+071.92E+071.92E+071.92E+07 33Ce-141 1.37E+071.371+071.37E+071.37t+071.37E+071.37E+071.37E+07 34 Ce-144 6.96E+076.96E+076.96E+076.96E+076.96E+076.96E+076.96E+07 U

N CalculatedperDDCHequation2.3-23 2-68 ISSUE 2 REVISION 2 _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - _ _

Lg a , '( L Wif BV-1ODCM table 2.3-7 ph,. . . ,

   ,(e                                HVALUESFORBEAVERVALLEYSITE
                                      '(sqaeter-sten /yrperuti/see)                                                                        l
                                                                                                                                         .J Pathway-Vegetatfor.'

6 AgeGroup-Adult Nuclide ' Bone liver I. Body Thyroid Eidney Lung' G1-LLI i 1 F3 0.00b00 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2.2EbO3 'l 2P-32 1 A0b09 8.HbO7 5.43b07 0.00D00 0.00b00 0.00h001.58t+08 - j( ! 3Cr-51 0.00b000.00b004.64D042.7Bb041.02b046.16b041.17bO7 i 4Mn-54 0.00D00 3.13bO8 5.97bO7 0.00b00 9.31bO7 0.00b00 9.59 BOB ! 5Fe-59 1.26bOS2.96bOS1.14D080.00b000.00b008.2Bi+079.8EbO8 j 60o-57 0.00 BOO 1,17bO71.95bO7 0.00D00 0.00b00 0.00b00 2.97bO8 1 700-58 0.00b003.07bO76.89bO70.00b000.00b000.00b006.23 BOB j BCo-60 0.00b001.67bOS3.69bO80.00b000.00b000.00h003.14b09 1 92n-65 3.17bO81.01b09 4.56bOS 0.00b00 6.75 BOB 0.00b00 6.36 BOB ! 10Rb-86 0.00b00 2.19D081.02 BOB 0.00b00 0.00b00 0.00b00 4.33bO7 l I 11St-89 9.97b09 0.00D00 2.86bO8 0.00b00 0.00D00 0.00b001.S0b09 < 12St-90 6.0$b110.00D001.4Bb110.00D00 0.00D00 0.00b001,75b10 l r 13Y-91 5.11b06 0.00b001.37b05 0.00b00 0.00b00 0.00b00 2.81b09 14Ir-95 1.17b06 3.77b05 2.55b05 0.00b00 5.91b05 0.00b001.19b09 1A2D057.92b044.26b040.00D007.63b040.00b004.81 BOB 15Nb-95 6/89 16lb-97 2.16b065.465-071.99b070.00D006.37bO70.00b002.02bO3 17E0-99 0.00D006.15b061.17b060.00D001.39 BOT 0.00b001.43007 l 18te-99: 3.10b008.77b001.12bO20.00D001.33bO24.30D005.19bO3 l 19Ru-103 4.77b060.00b002.0CD060.00b001.82bO70.00b005.57 BOB .I 20 Hu-106 1.93b08 0.00b00 2A4D07 0.00D00 3.72b06 0.00b001.25b10 j 21 ag-110s 1.05bO7 9.75b06 5.79b06 0.00b001.92bO7 0.00b00 3.98b09 j 22Sb-124 1,04 BOB 1.96D06 4.11bO7 2.51b05 0.00b00 8.07bO7 2.Hb09 i 23Sb-125 1.37 BOB 1.53b06 3.25bO71.3Sb05 0.00D001.0! BOB 1.50b09 4 i 24fe-127: 3.49bO81.25bO8 4.26bO7 8.92bO71A2b09 0.00b001.17b09 25 te-129s 2.51bO8 9.3EbO7 3.96bO7 8.64bO71.05b09 0.00b001.27b09 26I-131 8.08bO71.1EbOB 6.62bO7 3.79b101.98bO8 0.00b00 3.05bO7 l 27I-133 2.09h06 3.63b061.11b06 5.33b06 F.33b06 0.00 BOO 3.26b06 2BCs-134 4.67b091.11b10 9.02b09 0.00b00 3.59b091.1Sb091.94 BOB 29Cs-136 4.27bO71.69 BOB 1.21 BOB 0.00D00 9.38bO71.29bO71.91bO7 30Ce-137 6.36D09 8.70D09 5.70D09 0.00D00 2.95b09 9.81 BOB 1.6EbOB j 1 31Ba-140 1.29DOB 1.61b05 8.42b06 0.00b00 5.49b04 9.24b04 2.65bO8 32La-140 1.98bO3 9.97D02 2.63D02 0.0Cb00 0.00D00 0.00b00 7.32bO7 1 33Ce-141 1.97b051.33b051.51b04 0.00b00 6.19b04 0.00 BOO 5.10 BOB 34Ce-144 3.29bO71.3BbO71.77b06 0.00D00 8.16b06 0.00b001.11b10 O Allnuclides(exceptH-3)calenlatedperODCHequation2.3-26 H-3 calculated per 305 equatien 2.3-29 y l 2-69 ISSUE 2 1 REVISION 2 ]

s<4 . q m- , y l

                                                                                            - W-1 ODCP.-
                                                                                                                                                         -)

Table 2.3 , [A 4y l

                                                                                 -RVALUISFORBEAVERVALLEYSITE                                                 !

l bf .(sqmeter-steelyrperuti/see) ( Pathv'ar: Vegetation Age Group : Teen 1 Nuclide Bone- Liver T. Body flyroid Kidney Lung GI-LLI ! l

1 H-3 ' .0.00b002.59bO32.59bO32.59b032.591.032.59D032.59bO3 1

                                                                                                                                                         .1 2P-32         1.61b099.98bO76.24bO70.00D090.00b000.00b001.35b06 0.00b00 0.00D00 6.17b04 3,43b041.35b04 8.81b041.04E+07                             -I k 3Cr-51                                                                                                    l 4Mn-54      0.00D00 4.54bO8 9.01bO7 0.00D001.36 BOB 0.00b00 S.32 BOB                                      :

5Fe-59 1.79bO84.19bO81.62bO80.00D000.00b001.32 BOB 9.90908 -l o ,

600-57 0.00b001.79b073.00l+070.00D000.00b000.00b003.33b06 i 7 Co - 0.00b00 4.36bO71.00bOS 0.00b00 0.00D00 0.00D00 6.01bO8 1 800-60 0.00b002.49 BOB 5.60bO80.00b000.00D000.00 BOO 3.24b09 9Zn-65 4.24 BOB 1.47b09 6.87 BOB 0.00b00 9.42bO8 0.00D00 6.23b06 l 10Rb-86 0.00b002.74bOS1.29bO80.00b000.00b000.00D004.05bO7 11Sr-89 1.51b10' 0.00D00 4.34 BOB 0.00b00 0.00b00 0.00b001.80D09 12St-90 7.51b110.00b001.85b110.000000.00b000.00D002.11b10 1 . 13f-91 7.84b06 0.00b00 2.10D05 0.00b00 0.00h00 0.00b00 3.21b09

   -                                             -14Zr-95        1.72b06 5.43b05 3.74b05 0.00b00 7.9Bb05 0.00b001.25b09 1--                                            15Nb 1.92b051.07b05 5.87b04 0.00b001.03b05 0.00b00 (.56bO8 6/89 16lb-97      2.00b064.97bO71.811-070.00b005.81E-070.00b001.19E-02 17No-99      0.00b00 5,65b061.08b06 0.00b001.29bO7 0.00D001.01D07 18fc-99: 2.74b00 7.64b00 9.90b010.00b001.14bO2 4.24b00 5.02bO3 19Ru103 6.82b06 0.00b06 2.92b06 0.00b00 2.41bO7 0.00b00 5.70bO8 20Ru-106 2.38 BOB 0.00b00 3.90bO7 0.00b00 5.97bO8 0.00D001.48D10 21 Ag-110s 1.52bO71.43bO7 8.72b06 0.00D00 2.74bO7 0.00b00 4.03b09 22Sb-124 1.54bO8 2.84b06 6.02bO7 3.50D05 0.00b001.35 BOB 3.11b09 23Sb-125 2.14b06 2.34b06 5.01bO7 2.05b05 0.00b001.88bO81.67b09                                             ;

24Te-127: 5.52 BOB 1.96bO8 6.56bO71.31bO8 2.24b09 0.00D001.37b09 25 fe-129s 3.62bO81.34bO8 5.73bO71.17bO81.51b09 0.00b001.36b09 l 26I-131 7.69bO71.0BbOB 5.78bO7 3.14b10115 BOB 0.00b00 2.13bO7 27I-133 1.94b06 3.29b061.00b06 4.59b06 5.77b06 0.00b00 2.49b06 L 28Ca-134 7.10b091.67D10 7.75b09 0.00D00 5.3tb09 2.03b09 2.08b06 29Ce-136 4.36bO71.72 BOB 1.16bO8 0.00 BOO 9.37bO71.48bO71.39bO7 30Ce-137 1.01b101.35b10 4.69b09 0.00b00 4.59b091.78b091.92D08 L 31Be-140 1.38bO81.69b058.90b060.00b005.74b041.14D052.13b08 32La140 1.81bO3 8.BBbO2 2.36bO2 0.00D00 0.00b00 0.00D00 5.10bO7 33Ce-141 2.83b051.89b052.17b040.00D00B.90D040.00b005.41bOS 34Ce-144 5.27bO7 2.18bO7 2.B3b06 0.00b001.30bO7 0.00D001.33b10 Allnuclides(exceptB3)calculttedperODCMequation2.3-26 3r E-3calculatedperODCHequation2.3-29 2-70 ISSUE 2 REVISION 2 f E__- _ - _ - - _ _ __ _ _ _ _ _ _ _ _ _ _ _ j

I i.f f '

i

                                                                .EV-1DDCH:

g fable 2.3-9 ) Q'V)'

                                                    ' R VALUES FOR BEaVIH VALLEY SITE:
                                                                                                                                        -l (sg seter-area /yr per utihee)                                                  -i Pathway: Vegetation Age Group : Child

)

Nuclide Bone Liver T.' Body Thyroid Eldney Lung GI-LLI 1H-3 0.00D00 4.01bO3 4.01bO3 4.01bO3 4.01bO3 4.0lbO3 4.01bO3 2P-32 3.37b091.58 BOB 1.30D08 0.00b00 0.00b00 0.00b00 9.32E+07 g < 3Cr-51 0.00b000.00E+001.17b056.50b041.78b041.19b056.21Et06 4Hn-54 0.00b00 6.65bO81.77 BOB 0.00b001.86bO8 0.00b00 5.58bO8 5Fe-59 3.98 BOB 6.43 BOB 3.20bO8 0.00b00 0.00b001.87bO8 6.70E+08 6Co-57 0.00b00 2.99bO7 6.04bO7 0.00E+00 0.00b00 0.00E+00 2.45 BOB -) 700-58 0.00b006.44bO71.97 BOB 0.00b000.00b000.00b003.76 BOB 3 8Co-60' O.00b00 3.78E+0B 1.12E+09 0.00b00 0.00b00 0.00b00 2.10b09 ! 8 9Zn-65 8.13bO8 2.17b091.35b09 0.00b001.36b09 0.00b')0 3.80H+08 10Rb-86 0.00b004.52bO82.78 BOB 0.00b000.00D000.00 BOO 2.91bO7 11Sr-89 3.60E+10 0.00b001.03b09 0.00b00 0.00b00 0.00b001.39E+09 l

                          - 12St-90       1.24b120.00b003.15b110.00b000.00b000.00b001.67b10 13 T 91      1.86bO70.00D004.99b050.00D000.00D000.00b002.48b09 14Zr-95      3.86b06 8.4Sb05 7.55E+05 0.00b001.21b06 0.00b00 8.85E+08 15lb-95      4.11b051.60D051.14b050.00b001.50b050.00b002.96bO8 6/89
                          - 16lb-97. 3.65E-066.59E-073.08E-070.00b007.31E-070.00h002.03b01                                            )

17Mo-39 0.00D007.71b061.91D060.00b001.65bO70.00b006.38b06

                          - 18fe-99: 4.71b009.24b001.53b020.00D001.34bO24.69b005.26bO3 19Ru-103 1.53bO7 0.00D00 5.90D06 0.00D00 3.66bO7 0.00b00 3.97bO8 20Rn-106 7.45 BOB 0.00E+00 9.30bO7 0.00D001.01b09 0.00b001.16b10 21 Ag 110e 3.21bO7 2.17bO71.73E+07 0.00b00 4.04E+07 0.00E+00 2.58b09 22Sb-124 3.52 BOB 4.57b061.23b08 7.77b05 0.00D001.95 BOB 2.20b09 23Sb-125 4.99b08 3.85b061.05bO8 4.63b05 0.00b00 2.78 BOB 1.19b09 24 fe-127a 1.32b09 3.56E+081.57bO8 3.16 BOB 3.77b09 0.00b001.07b09 25 te-129s 6.41bO8 2.35 BOB 1.31bO8 2.71 BOB 2.47bO3 0.00b001.03b09 26I-131       1.43b081.44 BOB 8.17bO7 4.76b10 2.36 BOB 0.00b001.28E+07 27I-133      3.53b06 4.37b061.65b06 8.12 BOB 7.28t+06 0.00E+001.76b06 28Cs-134 1.60b102.63D105.55b090.00b008.15b092.93D091.42b08 29Cs-136 8.24bO7 2.27 BOB 1.47 BOB 0.00D001.21 BOB 1.80bO7 7.96b06 30Cs-137 2.39b102.29b103.38b090.00b007.46b092.68b091.43b08 31 Ba-140 2.77 BOB 2.42bO71.62bO7 0.00b00 7.89bO( 1.45b051.40D06 32La-1(0 3.259031.13b63 3.83bO2 0.00b00 0.00b00 0.00D00 3.16bO7 33Ce-141 6.56b053.27b054.86b050.00b001.43b050.00b004.08bO8 4

34Ce-144 1.27 BOB 3.98bO7 6.78b06 0.00D00 2.21bO7 0.00b001.04b10 111nuelldes(exceptH-3)calenlatedperODCHequation2.3-26 y B-3 calculatd per ODCM equation 2.3-29 j 2-71 ISSUE 2 j miSin2 ;

y . ( ^' > m 3

~&

4 1V-1ODCH m a' A. .. p Table 2.3-10 JJ R

RVALUESFOREEAVERVALLEYSITE legseter-sten /yrpervCi/seel L I ', Pathear : 5 eat: k 'AgeGroup: Adult Nuclide Bone Liver f. Body Thyroid Ildner Lung GI-LLI 1H-3 0.00E+003.25E+023.25t+023.25E+023.25E+023.25E+023.25E+02

':                           2P-32       3.95E+092.46E+081.53E+0B0.00E+000.00E+000.00E+004.44E+08                j L-3Cr-51      0.00t+000.00E+005.86t+033.50t+031.29t+037.78E+031.47I+06 (Mn44       0.00!+006.49I+061.24t+060.00E+001.93E+060.00E+001.99t+07 5 Fe-59     2,14E+085.04E+081.93E+080.00E+000.00t+001.41E+081.681+09 6Co-57.. '0.00l+004.01t+066.66E+060.00E+000.00t+000.00E+001.02E+08 700-58      0.00E+001,42E+073.18E+070.00E+000.00E+000.00l+002.87E+0B 1

800-60: 0.00l+005.12E+071.13E+080.00E+000.00E+000.00E+009.61I+0B 9Zn-65 2.54t+0B8.09t+083.66t+080.00E+005.41E+080.00E+005.10l+08 10Ib-86 0.00E+004.11E+081.92t+080.00E+000.00l+000.00E+008.11E+07. 11Sr-89 2.41t+080.00E+006.92t+060.00t+000.00E+000.00E+003.871+07 12St-90 8.41E+090.00t+002.06E+090.00t+000.00l+000.00B+002.43E+08 13f-91 8.94t+050.00l+002.398+040.00E+000.00l+000.00l+004.92E+08 R . 14Zr-95 1.475+064.71E+053.191+050.00E+007.398+050.00t+001.49t+09 15Nb-95 1.89t+061.05E+065.64B+050.00l+001.04E+060.00t+006.37t+09 16Hb :::::::::::::::::::::::::0.00tt00::::::::0.00l+00:::::::::- 17Mo-99 0.00t+008.511+041.62I+040.00t+001.93t+050.00E+001.97E+05 18 fe-99: 3.83E-211.08E-201.36E-190.00t+001.645-195.30I216.40818 19 Hu-103 8.571+070.00l+003.698+070.00l+003.27I+0B0.00l+001.00l+10 20Hu-106 1.971+090.00E+002.49E+080.00E+003.80E+090.00E+001.271+11 21 Ag-110s 4.77t+06 4.41t+06 2.62E+06 0.00E+00 8.67E+06 0.00E+00 1.80E+09 22Sb-124 0.00E+000.00t+000.00t+000.00E+000.00E+000.00l+000.00E+00 23Sb-125 0.00l+000.00E+000.00E+000.00t+000.00!+000.00E+000.00t+00 24fe-127 8.38t+083.00l+0B1.02E+082.14t+0B3.40E+090.00E+002.81E+09 25 fe-129s 9.33t+0B 3.48t+08 1.481+08 3.21E+08 3.895+09 0.00E+00 4.70E+09 26I-131 9.13E+061.31t+077.4BE+064.28t+092.24t+070.00t+003.45E+06 27I-133 3.12E-015.428-011.651417.961+019.46E-010.00E+00 4.87E-01 28Ce-134 4.53E+081.08t+098.81t+0B0.00E+003.49E+081.168+081.89E+07 29Cs-136 1.02E+074.04t+072.91t+070.00E+002.25E+073.08E+064.598+06 30Ce-137 5.90E+088.061+085.28t+080.00!+002.74E+089.10E+071.56E+07 31Ba-140 2.44H+073.06t+041.60E+060.00l+001.04E+041.75E+045.02I+07 32La-140 3.161-021.591-024.21E-030.00E+000.00E+000.00E+001.17E+03 33Ce-141 1.16E+047.83H+038.88E+020.00!+003.64E+030.00E+002,99E+07 34Ce-144 1.03t+064.32f+055.55E+040.00E+002.56E+050.00E+003.50E+08 f*) ~ Y V Allnuclides(exceptH-3)calculatedperODCBequation2.3-25 H-3calenlatedperODCHequation2.3-30 L 2-72 ISSUE 2 l= - REVISION 2 l- .

EV-1ODCM Table 2.3-11 NI EVALUESFOREIAVERVALLEYSITE (sq aeter-ares /yr per uC1/see) Pathway: Heat Age Group : Teen liuelide Bone Liver I. Body Thyroid Eidter Lung GI-LLI 1H-3 0.00E+001.94E+021.94E+021.94E+021.94E+021.94E+021.94E+02 2P-32 3.34E+092.07E+0B1.29E+080.00E+000.00E+000.00E+002.80E+08 h 3Cr-51 0.00E+000.00E+004.69E+032.60E+031.03E+036.6SE+037.80!+05 4 Mn-54 0.00H+004.95E+069.BIE+050.00E+001.4BI+060.00E+001.01E+07 5Fe-59 1.71E+08 4.00E+08 1.54E+08 0.00E+00 0.00E+00 1.265+08 9.45E4B 60o-57 0.00E+003.22E+065.40E+060.00E400.00E+000.00E+006.01E+0i i 7 C0-58 0.00E+001.09E+072.52E+070.00E+000.00E400.00E+001.51E48 800-60 0.00E+001.97E+078.95E+070.00E+000.00!+000.00!+005.175+08 9Zn-65 1.79E+086.21E+0B2.90!+080.00E403.97E+080.001002.63E+08 10Eb-86 0.00E+003.43E+081.61E+080.00E+000.00E+000.00E+005.0BE+07 11St-89 2.03E480.00E+005.83E+060.00E+000.00E+000.00E+002.42E+07 12Sr-90 5.44E49 0.00E401.34E+09 0.00E+00 0.00E40 0.00E+001.53E+08 n 13T-91 7.53E450.00E+002.02E+040.00E+000.00!+000.00!+003.09I+08 ('-) 14Zr-95 15 lib-95 1.18E+063.71E+052.55E+050.00E+005.45E+050.00E+00B.56E+08 1.47E468.17E454.50E450.00E+007.92E+050.00E+003.49149 6/89 16 lib-97 ***************************0.00E+00*********0.00E+00********* 17Mo-99 0.00E+007.03E+041.34E+040.00!+001.61E+050.00E+001.261+05 18Te-99: 3.04E-218.4EE-211.10E-190.00E+001.26E-194.71E-215.57E-18 19En-103 6.98E+070.00E+002.98E+070.00E+002.4EE+0B0.00E405.83E+09 20Ru106 1.28E+090.00!+002.09E+080.00Ev003.19E+090.00E+007.94E+10 21 Ag-110m 3.61E 4 6 3.42E+06 2.0BE+06 0.00E+00 6.52E+06 0.00E+00 9.60E4 8 22Sb-124 0.00E+000.00E+000.00E+000.00E+000.00E+000.00!+000.00E+00 23Sb-125 0.00E+000.00E+000.00E+000.00!400.00E+000.00!400.00E+00 24Te-127: 7.07E+082.51E+088.41E+071.6EE+082.87E+090.00E+001.7EE+09 25Te-129 7.82E+082.90E+081.2(E+082.52E+083.27E+090.00E+002.93E49 26I-131 7.59E+061.0EE+075.71E+063.10E+091.83E+070.00E+002.10E+06 27I-133 2.61E-014.42E-011.35E-016.17E+017.75E-010.00E+003.34I-01 28Ce-134 3.60E+0B8.48E+083.93E+080.00E402.69E+081.03E+081.05E+07 29 Cs-136 7.98E463.14E+072.11E+070.00E401.71E+072.69E+062.53146 30Cs-137 4.90E48 6.51E+08 2.27E+0B 0.00E+00 2.22E46 8.61E+07 9.27b06 31Ba-140 2.02E+072.47E+041.30E+060.00E+00B.3BE431.6fE443.11E+07 32La-140 2.60E-021.2BE-023.40E-030.00E+000.00E+000.00E+007.33E+02 33Ce-141 9.72E+036.49E+037.46E+020.00E+003.0EE+030.00E+001.86E+07 34 Ce-144 8.72E+053.61E+054.6BE440.00E+002.15E+050.00E+002.19E+08

   /,,\

Allcuelides(exceptH-3)calculatedperODCMequation2.3-25 Y H-3calculatedperODCMequation2.3-30 2-73 ISSUE 2 REVISION 2

  , ,<                  s                ,                                                                         -

T M "[. isS , r , , O , , EV-1ODCM

!?                y                                                                   table 2.3-12
                                                                           -RVALUESFORE!AVERVALLEYSITE (eg meter-stes/yr per uCi/sec)

Patbvar.: Heat AgeGrocP: Child L Nuclide Bre Liver T. Body' Thyroid' tidney Lung 'G1-LLI P 1 E '0.00h00 2.34bO2 2.34bO2 2.34bO2 2.34D02 2.34bO2 2.34bO2

                                                   ' 2P-32         6.29b09 2.94 BOB 2.43 BOB 0.00b00 0.00D00 0.00b001.74E+08 IU 3Cr-51       0.00b000.00b007.31bO34.06bO31.11bO37.41bO33.88E+05 4Mn-54       0.00E+005.66D061.51b060.00b001.59b060.00E+004.75b06-5Fe-59      .3.04 BOB 4.91bOS 2.45 BOB 0.00D00 0.00b001.42 BOB 5.12 BOB

[ 6Co-57 7Co-5B 0.00b00 4.21b06 8.52b06 0.00b00 0.00b00 0.00000 3.45bO7' 0.00E+001.28bO7 3.91bO7 0.00b00 0.00b00 0.00b00 7.45bO7 8Co-60 0.00b00 4.72bO71.39bO8 0.00b00 0.00D00 0.00b00 2.61E+0B 9In-65 2.66 BOB 7.15D08 4.44 BOB 0.00b00 4.50bO8 0.00b001.25bO8 - 10lb 0.00b00 4.87 BOB 2.99bO8 0.00D00 0.00b00 0.00b00 3.13b07 11Sr 3.85bO8 0.00b001.10bO7 0.00D00 0.00b00 0.00b001.0bO7-12St-90: -7.03b09 0.00b001.7Bb09 0.00D00 0.00b00 0.00b00 9.47bO7-13 E91 ' 1.42b06 0.00b00 3.81b04 0.00b00 0.00b00 0.00b001.90 BOB ; 14Ir-95 2.09b064.59b054.09b050.00D006.57b050.00b004.79 BOB;

                                                  - 15Hb-95' 2.5666 9.90b05 7.07b05 0.00b00 9.30D05 0.00b001.83b09 L

6/89 16Nb-97' :::::::::::::::::::::::::::0.00b00 :::::::: 0.00b00 :: * ::

17Mo-99 0.00D009.79b042.42b040.00b002.09b050.00b008.09b04

        -                                            18 Tc-99:' 5.33E-21 1.05b 20 1.73E-19 0.00b 00 1.52E-19 5.31E-21 5.95E-18
                                                   .19Ru-103 1.26 BOB 0.00b00 4.85bO7 0.00b00 3.18bO8 0.00D00 3.26b09 20Ru-106 3.12b090.00D003.89b060.00b004.21b090.00D004.85D10 21 Ag-110e 5.99b06 4.04b06 3.23b06 0.00b00 7.53b06 0.00 BOO 4.81bO8 22Sb-124 0.00b00 0.00D00 0.00b00 0.00D00 0.00D00 0.00D00 0.00b00 23Sb-125 0.00b000.00b000.00b000.00D000.00b000.00b000.00D00                                   4 24 fe-127s 1.33b 09 3.59 BOB 1.56b C8 3.19b O8 3.80D 09 0.00D 00 1.06 b 09 25te-129 1.47b09 4.11bO8 2.29 BOB 4.75 BOB 4.33b09 0.00D001.80D09 26I-131       IdibO71A2bO7 8.04b06 4.68b09 2.32bO7 0.00b001.26b06 27I-133       4.84E-015.995-012.27E-011.11bO29.98F010.00b002.41E-01 28Ce-134 6.35bO81.04b092.20bO80.00D003.23b081.16E+0B5.62b06 29Ce-136 1.38bO7 3.78bO7 2.45bO7 0.00b00 2.01bO7 3.00b061.?3b06 30Ce-137 9.02b085.63b081.27b080.00b002.81 BOB 1.01bO85A0b06 31Ba-140 3.72bO7 3.26b06 2.17b06 0.00D001.06b041.94b041.89bO7 32La140 4.76bO21.66b025.61E-030.00D000.00b000.000004.63b02
                                                  - 33 Ce-141 1.03b049.13bO31.36b040.00b004.00bO30.000001.14b07
                                                  - 34Ce-144 1.64b06 5.15b05 8.77b04 0.00D00 2.85b05 0.00b001.34bO8 All nuclides Iercept F3) calentated per ODCM equation 2.3-25                         U H-3calculatedperODCMequation2.3-30 2-74                             ISSUE 2
          "                                                                                                                     REVISION 2

H';y + - g , q r , , 3V-1ODCM [ A fable 2.313-I'\f ") RVALUESFORBEAVERVALLEYSITE l l (sqseter-aren/yrperuC1/seel 'i b _ I Patbvar:CowMilk ageGroup: Adult ; Nuclide -Bone Liver f. Sody thyroid Eidney Lung GI-LL1 L' 1H-3 0.00E+007.63E+027.63E+027.63E+027.63E+027.63E+027.63E+02 ; i 2P-32 1.45E+109.01E+085.60E+0B0.00E+000.00E+000.00E+001.63E+09 3Cr-51 0.00!+000.00E+002.38E+041.42E+045.24E+033.15E+045.98E+06 lL _l 4Mn-54 0.00E+005.95E+061.13E+060.00E+001.77E+060.00E+001.82E+07 5Fe-59 2.40E+07.5.63E+072.16E+070.00E+000.00E+001.57t+071.88E+08 , 6Co-57' O.00E+009.10E+051.51E+060.00E+000.00E+000.00E+002.31E+07 .j 7Co-58 0.00E+003.67E+068.22E+060.00E+000.00E+000.00E+007.43E+07 8Co-60' O.00E+001.12E+072.46E+070.00E+000.00E+000.00E+002.10E+08 l 9Zn-65 9.80!+083.12E+091.41E+090.00E+002.09E+090.00E+001.96F+09 10Ib-66 0.00E+002.19E+091.02E+090.00E+000.00E+000.00E+004.32E+08 j i 4 11St-89 1.16t+090.00E+003.33E+070.00E+000.00E+000.00E+001.865+08 126r-90 3.16E+100.00E+007.76E+090.00E+000.00E+000.00E+009.14E+08 13T-91 6.781+030.00E+001.81E+020.00E+000.00E+000.00E+003.73E+06 tl , O- 14Zr-95 15Nb-95 7.40E+022.37E+021.61E+020.00E+003.72E+020.00E+007.52E+05 6.77E+043.77E+042.03E+040.00E+003.72E+040.00E+002.29E+08 l l 6/89 1 16Nb-97 2.81E-127.11E-132.60E-130.00E+008.30E-130.00E+002.62E-09 17Ho-99 'O.00E+002.11E+074.01E+060.00E+004,775+070.00E+004.8BE+07 18fc-99 2.83E+007.99E+001.02E+020.00H+001.21E+023.91E+00(.73E+03 19Ru-103 8.29E+020.00E+0C3.57t+020.00E+003.16E+030.00E+009.68E+04 l 20Ru-106 1.43E+040.00E+001.81E+030.00E+002.77E+040.00E+009.27E+05 l 21ag-110 4.16E+073.84E+072.28E+070.00E+007.56E+070.00E+001.57E+10

                          -22Sb-124 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 23'Sb-125 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 24 fe-127s 3./.4E+07 1.23E+07 4.19E+06 8.79E+06 1.40E+08 0.00E+00 1.15E+08 25fe-129: 4.95E+071.85E+077.84E+061.70E+072.07E+080.00E+002.49E+08 26I-131      2.52E+083.60E+082.06H+081.1EE+116.17E+080.00!+009.50E+07 27I-133      3.29E+065.72E+061.75E+068.41E+0B9.99E+D60.00E+005.14E+06 1

28Ce-134 3.89E+099.27t+t97.58E+090.00E+003.00E+099.96E+081.62E+08 ' 29Cs-136 2.23E+088.82E+086.35E+080.00E+004.91E+086.73E+071.00E+08 30Ce-137 (.99E+096.82E+094.47E+090.00E+002.32E+097.70E+0B1.32E+08 31Ba-140 2.28E+072.87E+041.49E+060.00E+009.74E+031.64E+044.70E+07 32La-140 3.8(E4001.93E+005.11E-010.00E+000.00E+000.00E+001.42E+05 33Ce-141 3.99E+032.70E+033.06E+020.00E+001.25E+030.00E+001.03E+07 34Ce-144 2.54E+051.06E+051.36E+040.00Et006.29E+040.00E+008.58E+07 Allnuclides(exceptH-3)calculatedperDDCMeguation2.3-24 y H-3calculatedperODCHequation2.3-28 2-75 ISSUE 2 I I REVISION 2

.).

5 A' E . , , .

                                                                                                   . EV-1DDCM fable 2,3-14
;)U 1VALUISFOREEAVIRVALLEYSITE (eteeter-area /yrperUCi/seel Pathway:CowHilk L                                                            AgeGroup-feen Nuclide        Bone . Liver T. Body Thyroid' Ildney        Lung GI-LLI i-1 F3        0.00b00 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 2P-32       2.67b 10 1.6Sb 0s 1.04b 09 0.00D 00 0.00b 00 0.00b 00 2.25 b 09                 J[

3Cr-51 0.00b00 0.00b00 4.15b04 2.31bO( 9.10bO3 5.93b04 6.97b06

                                                         '4un-54      0.00b009.91b061.96b060.00b002.95bOS0.00h002.03bO7 5Fe-59      4.18bO7 9.76bO7 3.77bO7 0.00b00 0.00b00 3.08bO7 2.31 BOB 600-57      0.00b001.60D06 2.68b06 0.00D00 0.00D00 0.00b00 2.96bO7 7 Co-58 .0.00D00 6.17b06 1.42b O7 0.00b 00 0.00D 00 0.00b OO 8.51bO7 800 0.00b001.B9b07 4.26bO7 0.00E+00 0.00b00 0.00D00 2.46 BOB 9Zn-65      1.51b09 5.23b09 2.44b09 0.00D00 3.34b09 0.00b00 2.21b09 10 Hb-86     0.00b00 3.99EsJ 1.87b09 0.00D00 0.00b00 0.00b00 5.91 BOB 11St-89      2.14b09'0.00b00 6.12bO7 0.00b00 0.00b00 0.00b00 2.55 BOB 12 Sr-90     4.47b100.000001.10b100.00D000.00b000.00b001.25b09 13T-91       1.25b04 0.00100 3.35bO2 0.00b00 0.00D00 0.00D00 5.11b06
     .A)(                                                14Zr-95 15Nb-95 1.29bO34.0EbO22.81bO20.00E006.00bO20.00D009.42b05 1.16b056.41b043.53b040.00b006.21b040.00D002.74 BOB 6/89 16Eb-97      5.13E-121.27b124.65E-130.00D001.49b120.00D003.04E-08 17Ho-99      0.00b003.80bO77.25b060.00b008.70bO70.00b006.81bO7 18fc-99: 4.90b001.37bD11.77bO2 0.00b00 2.04bO2 7.59b00 B.92bO3 19Ra-103 1.47bO3 0.00D00 6.30bO2 0.00D00 5.20bO3 0.000001.23bo5 20Ru-106 2.03b040.00b003.32D030.00b005.0Eb040.00D001.2Eb06 21Ag-110 6.87bO7 6.50 BOT 3.95bO7 0.00b001.24bO8 0 00D001.83b10 22Sb-124 0.00b000.00D000.00D000.00D000.00D000.00D000.00h00 23Sb-125 0.00b000.00b000.00D000.00b000.00D006.00b000.00b00 24fe-127: 6.34bO7 2.25bO7 7.54b061.51bO7 2.57 BOB 0.00b001.5Bb06 25te-129: 9.06bO73.3EbO71.43D072.92bO73.79 BOB 0.00D003.40 BOB 261-131      4.57 BOB 639 BOB 3.43b081.87b111.10D090.00b001.26 BOB 27I-133      6.01b061.02bO7 3.!!b061.42b091.79bO7 0.00D00 7.71D06 28Cs-134 6.76b091.59b10 7.38b09 0.00D00 5.06b091.93b091.9BbOB 29Ce-136 3.80bO81.50b091.01b090.00D00B.15D0B1.2ED0B1.20 BOB 30Ce-137 9.05b091.2Cb10 4.19b09 0.00D00 4.10b091.59b091.71 BOB 31Ea-140 4.12bO7 5.05b04 2.65b06 0.00D001.71b04 3.39b04 6.35bO7 32La-140 6.89b003.39b009.01E-010.00b000.00D000.00 BOO 1.94b05 33Ce-141 7.32bO34.89bO35.62D020.00b002.30bO30.00D001.40bO7 34Ce-144 4.67b051.93b052.51b040.00D001.15b050.00D001.17 BOB All nuel"es (except H-3) calculated per ODCH equation 2.3-24                              V b3 cutclated per ODCH equation 2.3-28 2-76                           ISSUE 2 REVISION 2

4 ,, e . -i 374 ODOM - Tdle2.3-15' HVALDISFORBE1FERVALLEYSITE 1 (agmeter-ares /yrpersCl/see) Pathway:CowHilk AgeOrcup: Child. l-helide Bone- Liver' f. Body Thyroid lidney Lung GI-LLI 1H-3 2P-32. 0.00b00 1.57bO3' 1. 57bO3 1. 57bO3 1.57bO3 1. 57bO3 1.57bO3 6.59b103.09b092.54b090.00D000.00D000.00b001.82b09 3Cr-51 0.00b000.00b008.4Sb044.70D041.2Sb048.56b044.49b06 ' g 4 Hn-54 ' 5Fe-59 O.00D001.48D07 3.95b06 0.00b00 4.16b06 0.00D001.24bO7 9.70bO71.57bO8 7.82bO7 0.00b00 0,00b00 4.55bO71.63D08 600-57, 0.00b002.73b065.52b060.00D000.00D000.00D002.24bO7 7C058 800-60 0.00D009.43D062.89D070.00b000.00D000.00b005.50bO7 9 h-65 0.00b00 2.94bO7 8.67bO7 0.00D00 0.00b00 0.00D001.63bO8 10lb-86 2.95b09 7.87b09 4.89b09 0.00D00 4.96b09 0.000001.3ED09 0.00D007.40D094.55b090.00b000,00D000.00b004.76 BOB 11St-89 12fr-90 5.29b090.00b001.51bO80.00D000.000000.00b002.05bO8 131-91 7.55b10 0.00b001.91b10 0.00b00 0.00D00 0.00D001.02D09 14Zr-95 3.0Bb04 0.00b00 S.24bO2 0.00b00 0.00D00 0.00 BOG 4.11b06 3.00bO3 6.60bO2 5.8BbO2 0.00b00 9,45bO2 0.00b00 6.89D05 15lb-95 2.61b 05 1.02 b 05 7.26b 04 0.00D 00 9.54 b04 0.00b 00 1.88bO8 16 lib-S7 6/89 17Ho-99 1.25b112.25b121.05b120.00D002.50b120.00b006.96-07 0.00b00 6.92bO71.71bO7 0.00b001.48bO8 0.00D00 5.72 BOT 18fe-99: 1.12b012.20b013.65bO2 0.00b00 3.200021.12b011.25b04 19 h-103 3.49bO30.00D001.34bO30.00b008.78bO30.00D009.01D04 20 h-106. B.49b04 0.00b00 8.10bO3 0.00b00 8.76b04 0,00b001.01h06 21Ag-110: 1,49b081.01bO8 8.05bO7 0.001Q 1.87D08 0.00b001.20b10 22Sb-124 0.00b000.00D000.00D000.00bC90.00D000.00b000.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00D00 0.00D00 0.00D00 24Te-127 1.56bO8 4.21bO71.66D07 3.74bO7 4.46 BOB 0.00D001.27 BOB 25 Te-129a 2.23bO8 6.24bO7 3.47bO7 7.20bO7 6.56D06 0.00b00 2.72bO8 261-131 271-133 1.11D091.11b09 6.33 BOB 3.68D111.83b09 0.00D00 9.92bO7 1.4EbO71.81bO7 6.83b06 3.36b09 3.01D07 0.00b00 7.28D06 26Ce-134 1.56b10 2.56b10 5.4Db09 0.00b00 7.93b09 2.85b091.38bO8 29 Ca-136. B.58bO8 2.3Sb091.53b09 0.00b001.2Eb091.87b08 8.2SbO7 30Ce-137 I 2.18b!02.09b103.08D090.00b006.80D092.45D091.31bO8 31Be-140 9.94bO78.71b065.80D060.00D002.64D045.19b045.04D07 32La-140 1.65b015.77D001.94b00 0.00b00 0.00b00 0.00b001.61b05 33Ce-141 1.80b04 8.99bO31.34b04 0.00D00 3.94bO3 0.00b001.12D07 34 Ce-144 1.15b06 3.61b05 6.15b04 0.00D00 2.00b05 0.00b00 9.41bO7 O, Allnuclidea(exceptH-3)calculatedperODCHequation2.3-24

                   .E-3calculatedperDDCHescation2.3-28                                                            V 2-77                            ISSUE 2 REVISION 2 Q-_ _--_-                            - - - - - -              -            -   -

mc w >:

                                                                                                    -~                      = ' - - ~ ~ -     ~ --

y . ; , p

                                                                                      -Eb10DCE Table 2.3-16 RVALUESFORBEAVERVALLEYSITE (egmeter-area /yrperuti/see)
                                          -Pathway:CowMilk
                                          -AgeGroup: Infant Nuclide                      Bone    Liver T. Body Thyroid Eidney Lung GI-LLI 1 F3         0.00E+002.36bO32.3BE+032.3BbO32.3Bb032.36bO32.3EbO3 2P       1.36b117.99b09 5.27b09 0.00D00 0.00D00 0.00D001.64b09                                jg 3Cr-51       0.00b00 0.00b001.34E+05 8.75b041.91b041.70b05 3.91b06 4Hn-54       0.00D002.76bO76.25b060.00D006.11b060.00D001.01E+07 5Fe-59        1.81bD83.16bO81.25 BOB 0.00b300.00D009.35bO7'1.51bO8 600-57       0.00b006.3Eb061.03b070.00b000.00b000.00b002.17bO7 7Co-58       0.00E+001,89E+074.70E+070.00b000.00D000.00b004.70E+07 8Co-60       0.00b006.00bO71.429080.00b000.00D000.00 BOO 1.43bO8 9In-65       3.97b091.36b10 6.27b09 0.00b00 6.60D09 0.00 BOO 1.15b10 10Eb-86       0.00b001.68b10 9.16D09 0.00b00 0.00D00 0.00D00 4.81 BOB 11Sr-89        1.01b10 0.00b00 2.89bO8 0.00D00 0.00b00 0.00b00 2.07 BOB 12Er-90       8.22b100.00b002.09b100.00 BOO 0.00D000.00b001.03b09 f-                             13 b 91       5.79b040.00D001.54D030.00F000.00b000.00b004.15b06 14Zr-95       5.33b031.30bO39.22D020.00D001.40bO30.00D006.47D05 15Nb-95       4.87b05 2.01b051.16b05 0.00D001.44b05 0.00b001.69b08 6/89 16ab-97       2.63b115.62b122.03E-120.00D004.39b120.00b001.77b06 17Ho-99       0.00D001.77D003.(5bO70.00D002.64b080.00D005.83bO7 18Te-99: 2.34b01 LB2b016.21bO2 0.00D00 5.19bO2 2.52b011.40D04 19Ru-103 7.0fbO30.00E+002.36D030.00D001.47b040.00b008.59b04 20Ru-106 1.34b05 0.00D001.67b04 0.00D001.5Bb05 0.00b001.0$06 21 As-110e 2.75 BOB i.01bO81.33b08 0.00D00 2.8EDOB 0.00D001.04b10 22Eb-124 0.00E+000.00D000.00D000.00b000.00b00000b000.00D00 23Sb125 0.00b000.00b000.00D000.00D000.00b000.00b000.00D00 24fe-127 3.16 BOB 1.05 BOB 3.83bO7 9.14bO7 7.79 BOB 0.00D001.2EDOB 25fe-129 4.5EbOB 1.57 BOB 7.06D071.7CDOB 1.15b09 0.00b00 2.74 BOB 26I-131       2.31D092.72b091.20b098.95b113.1Eb090.00b009.72bO7 27 b!33       3.0Bb074.499071.31bO78.17bo95.2BbO70.00D007.60D06 28Cs-134 2.51b10 4.6Sb10 4.73b09 0.00b001.21b10 4.95 BOB 1.27 BOB 29Ce-136 1.6Eb09 4.93D091.64b09 0.00D001.97b09 4.02 BOB 7.49bO7 30Ce-137 3.4Eb!0 4.07b10 2.89D09 0.00D001.09b10 4.43b091.27 BOB 31Ba-140 2.05 BOB 2.05b051.05bO7 0.00b00 4.56D041.26b05 5.02bO7 32La-140 3.45b011.36b013.50D000.00D000.00D000.00D001.60D05 33Ce-141 3.57E+04 2.1Eb04 2.57bO3 0.00b00 6.72bO3 0.00b001.13bO7 34Ce-144 1.65b066.75b059.25b040.00b002.73b050.00D009.47bO7 Allcuelides(exceptE-3)calculatedperODCMeguatien2.3-24                                           y 03calculatedperODCEequation2.3-28 2-78                      ISSUE 2 REVISION 2

f, a h ! BV-1ODCE Table 2.3-17 j x., a RVALUESFORBEAVERVALLE7 SITE L (egmeter-ares /yrpernCl/sec) Pathwar-GoatHilk , AgeGroup: Adult l Nuclide Bone liver f. Body Thyroid Eidney Lung 01-LLI 1H-3 0.00E+001.56I+031.56E+031.56E+031.56t+031.56t+031.56t+03 2P-32 1.74E+101.08t+096.72E+080.00E+000.00E+000.00E+001.96E+09 JL 3Cr-51 0.00t+00 0.00!+00 2 65E+031.70E+03 6.2EE+02 3.7BE+03 7.175+05 4Hn-54 0.00E+007.14I4051.36t+050.00E+002.12E+050.00!+002.19E+06 j 5Fe-59 3.12t+057.32E+052.81E+050.00E+000.00E+002.05t+052.44E+06 6Co-57 0.00E+001.09E+051.82t+050.00E+000.00E+000.00E+002.77E+06 , 7 0o-58 ~ 0.00E+004.40E+059.668+050.00E+000.00E+000.00E+00B.91E+06 600-60 0.00E+001.34E+062.96E+060.00E+000.00E+000.00E+002.52t+07 ; 9Zn-65 1.18E+08 3.74t+081.69t+08 0.WE+00 2.50E+08 0.00E+00 2.36t+08 i 10 lb-86 0.00E+002.63t+081.22E+080.00E+000.00i+000.00i+005.18E+07 4 11Er-89 2.43E+090.00E+006.99t+070.00E+000.00E+000.00t+003.91E+0B 12St-90 6.64t+100.00l+001.63I+100.00E+000.00E+000.00!+001.92t+09 13E-91 8.14t+020.00l+002.165+010.00l+000.00E+000.00t+004.4BI+05 O 14Zr-95 15lb-95 8.67E+012.85B+011.93E+010.00E+004.47t+010.00l+009.02E+04 8.13E+034.52E+032.43E+030.00t+004.47I+030.00E+002.74E+07 6/89 l l 16Rb-97 3.38!-138.548-143.12I-140.00l+009.96E-140.00t+003.15E-10 17No-99 0.00E+002.53t+064.81t+050.00E+005.72E+060.00E+005.86E+06 18fc-99: 3.395-019.59E-011.22t+010.00i+001.46t+014.70E-015.67t+02 19Ru-103 9.95E+010.00E+004.2SE+010.00E+003.60E+020.00E+001.16I+04 20Ru-106 1.72E+030.00E+002.18t+020.00E+003.32t+030.00!+001.11E+05 21Ag-110 4.99E+06 4.61R+06 2.74E+06 0.00E+00 9.07t+06 0.00l+001.6El+09 22Eb-124 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 23Sb-125 0.00!+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 24 fe-127a 4.13E+06 1.48t+06 5.03E+05 1.05E+06 1.6BE+07 0.00E+00 1.3EE+07 ) 25 fe-129s 5.94E+06 2.22E+06 9.41E+05 2.0(E+06 2.48t+07 0.00E+00 2.99E+07 261-131 3.02E+084.32E+082.48t+081.42E+117.40E+080.00E+001.1(E+08 27I-133 3.95t+066.87t+062.09t+061.01E+091.20E+070.00E+006.178+06 28Ce-131 4.67t+081.11E+099.09E+080.00E+003.6CE+081.19E+0B1.95E+07 29Cs-136 6.70E+082.65t+091.90E+090.00E+001.47t+092.02E+0B3.01E+0B 30Ce-137 1.50E+102.05E+101.34E+100.00E+006.95E+092.31E+093.9EE+08 31Ba-140 2.74E+063.44E+031.79E+050.00E+001.17t+031.97E+035.6(E+06 32La-140 (.60E-012.32E-016.15E-020.00E+000.00E+000.00E+001.70E+04 33Ce-1(1 4.79E+023.24E+023.6EE+0!0.00E+001.51E+020.00E+001.2(I+06 34Ce-144 3.05E+041.27t+041.64E+030.00E+007.EEE+030.00E+001.03E+07 y

  \                                                         All nuclides (except H-3) calculated per ODCE equation 2.3-24 E-3calculatedperDDCEegnation2.3-28 2-79                     Issur 2 REVISION 2

_ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ._ .- _ _ _ _ _ .)

1 EV-1DDCH l Table 2.3-18 t VALl'IS FOR BEAVER VALLEY S1ft (egmeter-area /FrpernCi/sec) Fathear:GoatMilt AgeGroup: feen Nuclide Bone Liver 7. Sody Thyroid tidney Lung SI-LLI 1H-3 0.00b00 2.03bO3 2.03b03 2.05t+03 2.03bO3 2.03bO3 2.0$bO3 2P-32 3.21b!0199b091.24b09 0.00b00 0.00b00 0.00t+00 2.70b09 3Cr-51 0.00D00 0.00b00 4.98bO3 2.77bO31.09bO3 7.11bO3 8.37b05 , N 4En-54 0.00b001.19b06 2.36b05 0.00D00 3.55b05 0.00b00 2.44b06 5Fe-59 5.44bo51.27b06 4.90D05 0.00b00 0.00b00 4.00bo5 3.00b06 6Co-57 0.00b001.92b05 3.21b05 0.00b00 0.00b00 0.00b00 3.57b06 7Co-58 0.00D00 7.40b051.71b06 0.00b00 0.00D00 0.00 BOD 1.02bO7 8Co-80 0.00b002.21b065.11DD60.00b000.00b000.00b002.96b01 9In-65 1.81 BOB 6.27 BOB 2.93 BOB 0.00h004.01bO80.00b002.66t+08 10lb 0.00b00 4.79 BOB 2.25 BOB 0.00b00 0.00D00 0.00 BOO 7.09bO7 11Sr-89 4.49b090.00t+001.29 BOB 0.00b000.00D000.00b005.35t+0B 12Sr-90 9.39b100.00b002.32b100.00b000.00D000.00t+002.64D09 13 T-91 1.50bO3 0.00b00 4.01b010.00D00 0.00b00 0.00b00 6.14b05 14Ir-95 1.55bO2 4.90b013.37b010.00b00 7.19b010.00b001.13b05 15lb-95 1.39bO( 7.69b03 4.23bO3 0.00b00 7.45bO3 0.00b00 3.29t+07 6/89 16Bb-97 6.158-131.535-13 5.57bl4 0.00b001.79b13 0.00b00 3.658-09 17 50-99 0.00b004.56b068.70D050.00t+001.04bO70.00b00B.17b06 18fe-99: 5.BBE-011.64b002.13b010.00b002.45b019.11E-011.08D03 19Rn-103 1.7"bO2 0.00t+00 7.56b010.00b00 6.24bO2 0.00b001.48b04 20In-106 2.44bO30.00b003.9BbO20.00b006.10bO30.00b001.52t+05 21Ar-110 8.24b067.80b064.75b060.00b001.49t+070.00b002.19b09 22Eb-124 0.00!+000.00!+000.00b000.00b000.00D000.00E+000.00!+00 23Sb-125 0.00b00 0.00b00 0.0Db00 0.00b00 0.00b00 0.00h00 0.00E+00 24fe-127: 7.61b06 2.70E+06 9.05b051.61b06 3.0BbO7 0.00b001.90t+07 25 fe-129s 1.09D07 4.02h061.72b06 3.51b06 4.55bO7 0.00D00 4.06bO7 26I-131 5.4BbOB 7.67bC3 4.12 BOB 2.2@l11.32b09 0.00b001.52 BOB 27I-133 7.21h061.22b013.73b06 ?. 71t+09 2.15bO7 0.00b00 9.26b06 28Ce-134 8.11 BOB 1.91b09 6.B6D08 0.00b00 6.07 BOB 2.32 BOB 2.3BbO7 29Ce-136 1.14b094.49b093.02b090.00D002.44D093.85 BOB 3.61 DOE 30Ce-137 2.71b!03.61b101.26b100.0CE+001.23b104.77D095.14 BOB 31Be-140 4.Ht+06 6.06bO3 3.16b05 0.00b00 2.0!bO3 4.07bO3 7.62b06 32La140 8.27b014.065-011.05b010.00D000.00b000.00b002.33b04 33Ce-141 8.79bO25.87t+026.74b010.00b002.7Cb020.00D001.6ED06 34Ce-144 5.60b042.32b043.01bO30.00b001.39b0(0.00 BOD 1.(IbO7 U 111 nuclidee (except F3) caltnisted per ODCH equation 2.3-24 F3calenlatedperOKHegnation2.3-28 2-80 Issue 2 REVISION 2

I

              ,                                                        BV-1DDCH table 2.3-19 tV&LUESFORBl&VEETALLEYSitt (seseter-eres/arperuti/sec)'

Pathver:GoatHilt age Group :.Chlid loclide= Bone Liver f. Body Thyroid Eidner Lung GI-LLI 1H-3 0.00t+003.20t+033.70t+033.20E+033.20E+033.20l+033.20E+05 2 P-32 7.91b10 3.70t+09 3.65b09 0.00t+00 0.00E+00 0.00E+00 2.19b09 g 3Cr51 0.00i+00 0.00b001.02t+04 5.64t+031.54bO31.03E+H 5.39b05 4un-54 0.00b 00 1 1 b 06 4.74b 05 0.00E,00 (.99t+05 0.00l+00 1.49b 06 5Fe-59 1.26b062.04b061.02b060.00E+000.00D005.91b052.12b06 ) 600-57 0.00b00 3.27b05 6.63b05 0.00t+00 0.00b00 0.00D00 2.63b06 7 Co-56 0.00t+001.13bD63.4ft+060.00E000.00D000.00D006.60b06 8Co-60 0.00b003.53bo61.04bO70.00b000.00E+000.00b001.55E+07 9In-65 3.54bO8 9.44b06 5.67 BOB 0.00E+00 5.9Eb06 0.00h0J 1.63b06 10Rb-86 0.00E+00 8.8Bb06 5.46r+0B 0.00D00 0.00t+D0 0.00b00 5.71bO7 11Er-89 1.11b !D 0.00b 00 3.1 R 06 0.00l+00 0.00b 00 0.00b 00 4.30i+0B 12St-90 1.59b110.00b004.02b!00.00D000.00D000.00D002.1(L+09 13Y-91 3.70D030.00D009.89t+0!0.00D000.00D000.00b004.93t+05 14Ir-95 3.60t+02 7.92b017.05t+010.00D001.13t+02 0.00D00 B.27b04 15Bb-95 3.13E+041.22b04 8.71bO3 0.00t+001.14E+04 0.00b00 2.2FbO7 ) 6/89 16Nb-97 1.49E-122.70t-131.26b130.00b002.99E-130.00E+00B.33E-06 17B0-99 0.00D00 8.30D06 2.05b06 0.00D001.77bO7 0.00E+00 6.67b06 IBte-99: 1.3Eb00 2.6fE+00 4.39b010.00b00 3.64b011.3(b00.1.51bO3 19 h-103 4.1Bb02 0.00b001.61t+02 0.00b001.0!bO3 0.00b001.06b04 20 h-106 7.79b330.00D009.72bO20.00b001.05b040.00b001.21b05 21Ar-110 1.79t+071.21bO7 9.65b06 0.00t+00 2.2EE+07 0.00b001.4(b09 22Sb-124 0.00b000.00b000.00b000.00b000.00b000.00D000,00b00 l 23Sb-125 0.00f+000.00b000.00b000.00D000.00E+00V.00 BOD 0.00D00 l 24fe-127 1.BBbO7 5.05b06 2.23b06 4.4Eb06 5.3Eb07 0.00b001.52bO7 25 fe-129s 2.6BbO7 7.4Bb06 4.16b06 B.Mb061.67bO7 0.00D00 3.27bO7 l 21 F131 1.23b091 Mb09 7.60 BOB (.42b112.19b09 0.00D001.19b08 271-133 1.7Eb67 2.17bO7 B.20D06 4.03b09 3.61b07 0.00b00 B.73bD6 ! i 28Ce-134 1.87b093.07b096.4Eb060.00bb09,52 BOB 3.42b061.66D07 20Ce-136 2.5Bb09 7.0Eb09 4.56b09 0.00b60 3.77bD9 5.62 BOB 2.49 BOB 30Ce-137 6.54b10 6.26b10 9.2(b09 0.00F00 2.0(bl0 7.3(E+09 3.92 BOB 31Ea-140 1.19t+071.00D066.9Eb050.00E+003.40D036.23bO36.0(b06 32La-140 1.9Eb006.92E-012.33E-010.00b000.00D000.00D001.93b04 33Ce-141 2.1EbO31.0EbO31.60bO3 0.00D00 4.73bC2 0.00D001.3Eb06 34Ce-144 1.3Eb05 4.33DD( 7.37bO3 0.00b00 2.40bd 0.00b001.13D07 O allnuclides(exceptB-3)calculatedperDDCHequation2.3-24 E-3calculetedperDDCHegnetion2.3-2B 1ssuE 2 2-81 REVISION 2 l L_-- _ - ---_ _ - -_ _ _ _ _ _ __ _ _ _ _ _ _ l

i i 1 BV1DDCH j i y]

  .u-Table 2.3-20

j. IVALUESFORBEAVERVALLITSITE !

' j L (egmeterarea/yrperuCi/sec) Pathway:CoatHilk j ageGroup-Infant helide Bone Liver !. Body Thyroid lidney Lung G1-L1,I 1H-3 0.00D00 4.66E+03 4.B6bO3 4.86bO3 4.86t+03 4.86bO3 4.86bO3 l 2P-32 1.63D119.59t+096.32h090.00b000.00b000.00b002.21b09 g i 3Cr-51 0.00D00 0.00E+001.61b041.05b04 2.2SE+031.04b04 4.69t+05 -j 4Hn-54 0.00b00 3.31b06 7.50b05 0.00b00 7.33b05 0.00b001.21b06 j 5Fe-59 2.35b06 4.11h061.62b06 0.00b00 0.00b001.21b061.96b06 j 6Co-57 0.00E+007.64b051.24b060.00b000.00b000.00b002.60D06 7 00-5B 0.00D00 2.26b06 5.64bo6 0.00b00 0.00D00 0.00b00 5.64b06 ; 8Co-60 0.00b007.20D061.70D070.00b000.00t+000.00h001.71bO7 ! 9Zn-65 4.76b081.63b09 7.53 BOB 0.00b00 7.92 BOB 0.00b00.1.38b09 10Rb-86 0.00b00 2.25b091.11E+09 0.00b00 0.00b00 0.00b00 5.77bO7 11St-89 2.11b10 0.00b00 6.0Eb08 0.00b00 0.00b00 0.00b00 4.34bO8 'i l 12Sr-90 1.73b110.00b00 4.39b10 0.00b00 0.00b00 0.00b00 2.16b09 f- 13f-91 6.94bO3 0.00D001.B5bO2 0.00b00 0.00h00 0.00b00 4.9Bb05 l l 14Zr-95 6.40bO21.56bO21.11bO2 0.00D001.66t+02 0.00b00 7.77bo4 ! I 15lb-95 5.84b042.41b041.39b040.00D001.72b040.00 BOO 2.03bO7 6/89 l 16Nb-97 3.16b126.74b132.43E-130.00!+005.27E-130.00b002.13I-07 17Mo-99 0.00D00 2.12bO7 4.14b06 0.00b00 3.17bO7 0.00t+00 6.95b06 18fc-99: 2.Pib00 5.79b00 7.46b010.00b00 6.23b013.03b001.6Eb03 19 h-103 8.47bO2 0.00t+00 2.83bO2 0.00b001.76bO3 0.00b001.03b04 20En-106 1.60!+04 0.00D00 2.00bO3 0.00b001.90b04 0.00b001.22b05 21ag-110 3,30bO7 2.41bO71.60bO7 0.00D00 3.45bO7 0.00b001.25b09 22Sb-124 0.00b000.00D000.00b000.00b000.00b000.00b000.00b00 ; 23Sb-125 0.00D000.00D000.00b000.00b000.00b000.00b000.00D00 24fe-127: 3.80bO71.26bO7 4.59b061.10bO7 9.35bO7 0.00b001.53007 25 fe-129s 5.50 D 07 1.89b 07 8.47b06 2.11b O7 1.3Sb O8 0.00b 00 3.2Eb O7 { 26I-131 2.77b09 3.27b091.44b091.07b12 3.82b09 0.00b001.17bO8 27I-133 3.70D07 5.39bO71.52bO7 9.80b09 6 34bO7 0.00b00 9.12b06 l 2B Ca-134 3.02b09 5.62b09 5.6 Ebb 8 0.00D001.45b09 5.93 BOB 1.53bO7 l 29Cs-136 5.03b091.4Bb10 5.52b09 0.00b00 5.'d0bOS 1.21b09 2.25 BOB ! 30Ce-137 1.04b111.22b118.66b09 0.00D00 3.28b101.33b10 3.82bO8 31Ba-140 2.45bO72.45b041.26b060.00b005.83bO31.51h046.03b06 32La-140 4.14b001.63b00 4.19b010.00b00 0.00b00 0.00b001.92b04 l 33Ce-141 4.29bO3 2.62bO3 3.0EbO2 0.00D00 8.07bO2 0.00D001.35b06

      ,s                                                                      34Ce-144 1.9Bb05 8.11b041.11b04 0.00b00 3.28b04 0.00b001.14bO7                      y
   \                                                                             illn=clides(exceptH-3)calculatedperDDCHequation2.3-24 E-3calculatedper0DCHequation2.3-28 ISSUE 2 2-82                              REVISION 2   {

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81 22 1 1 1 1 1 5256775 TA C NE EL e 0 VE h 9999999990099090 R t 2 0000000001 1 001 01 S - - - - - - - - - - - - - - - - SD o - EEEEEEEEEEEEEEEE E E t 6527267 8041 431 82 CT 5 75621 4961 870071 1. . . . OA s . . . RV e 1 1 233321 1 2881 l 41 9 PE c . L n EE a 5 T t s 1 99999999909990' 0000000001 0001 1 0 09 I S SU i - 0 D - EEEEEEEEEEEEEEEE YU 48 299021 63564 963 EN 0 1 936045078538086 LI LT 1 31 1 3443337 11 1 32 1 AN VO 0 C 9999899999999009 R 1 0 E R 1 00000000000001 VO - - - - - - - - - - - - - - - - AF - EEEEEEEEEEEEEEEE E 047 585 1 61 9535395 B 5 66552846885691 00 . 0 85l 1 1 76442562442 5 ' 0099909998890000 0 1 1 0001 0000001 1 1 1

                                      -    EEEEEEEEEEEEEEEE 063352620497842 0 0         0601 387. 204857 554                                                 .         .

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_ ,mL 4 5 0000000000000000 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4

                             -       EE tEEEEEEEEEEEEE 1 4 9858559 0585939 0        996502583 7338785                   .         .

4 23564221 21 233573 0 0009000000000090 1 1 1 01 1 1 1 1 1 1 1 1 1 01 4

                              -      EEEEEEEEEEEEEEEE 027 1           64929445261 4
             ~       r      5        097001 1 393258928      . .                        .

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                     >  L            9999900000099999                                  00000 5                           2       000001                     1 1 1 1 1 r,U M C

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l o r EEEEEEEEEEEEEEEE 82407629481 091 98 O 2 SS t 0 022534321 7021 292 TA n . . 1 E NE o 2 1 1 221 8968581 1 221

       - L     EL       C V   B     VE B   A           R   e   0 T     T        h             999999,0001               9990999999 000000 NL        t   2        000000 EE                      - - - - - - - - - - - - - - - -

MV NE o - EEEEEEEEEEEEEEEE 1 97422556777 406 2 t I L 5 88461 441 29486681 A s . . . . TD e 1 1 1 3321 1 1 1 81 1 2342 N N OU c n s CO a 5 R t 999999999999999 9 EG s 1 0000000000000000 T i - - - - - - - - - - - - - - - - I S SU D - EEEEEEEEEEEEEEEE O 471 1 94966024 238 9 026637467 YU EN 0 23 25 7

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                                                                                  . 134683 1        336632 2221 LI LT AN            0 VO                    9988            89999999888 9 C        1        0000000000000000 R                       - - - - - - - - - - - - - - - -

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                                 -     EEEEEEEEEEEEEEEE AF 397 5 5002 7 207 307 4 E

5 7323067 9353 91 600 B 0 7 91 1 1 55464571 1 29 5 888888888888887 8 0 0000000000000000

                                 -     EEEEEEEEEEEEEEEE 6227 83947 1 609592 0        4437 02286606421 2                                             .

0 4577 63323234691 5 C r o E E E E W W W W t NEN S ES SWS NW N c e NNNEEESSSSSWWWNN S

/ 4 234531 21 1 1 1 23462 5 0000000000000000 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 4

                             -     EEEEEEEEEEEEEEEE 1 4 98585590585939 0       9965 025837338785 4       235642 21 21 233573 0

0009000000000090 4 1 1 1 01 1 1 1 1 1 1 1 1 1 01

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                             -     EEEEEEEEEEEEEEEE 6501 4 52 96 2872665 E >       e   0       1 303501 9801 .821 52 T       l                                                .       . .

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                  /        3       1 1 001 1 1 1 1 1 01 1 001 N s O r s      -      EEEEEEEEEEEEEEEE I h     n            7 476 94521 6256590 S       o    5       55 57 59547 064351 0 i

0 t 2 781 1 9564545881 29 E" .0 a P5 c S > o 5 3 I L 9999900000099999 2 D 000001 1 1 1 1 1 00000 M S 2 C - - - - - - - - - - - - - - - - - O D O 3 2 SE TS NA l r o - EEEEEEEEEEEEEEEE 82407 629481 091 98 02 2534321 7 021 292 EE t 0 1 E VL n . . . . .

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A O e 0 T I L h 9999999990999999 TE t 2 0000000001 000000 AV - - - - - - - - - - - - - - - - LE o - EEEEEEEEEEEEEEEE I L t 1 974 2 2 5567 774062 T 5 88461 441 2 9486681 ND s . . . . . EN 1 1 1 33 21 1 1 1 81 1 2342 VU i c O n ER a 5 TG t 9999999999999999 I SS s 1 0000000000000000 U i - - - - - - - - - - - - - - - - YO D - EEEEEEEEEEEEEEEE E U 471 1 94 966024 2389 LN 0 23 25 7 55026631 467 . . . . LI 1 336632 2221 234683 AT VN O 0 RC 99888 99999998889 E 1 0000000000000000 VR - - - - - - - - - - - - - - - - AO - EEEEEEEEEEEEEEEE E F 3 97 5 50027 207307 4 B 600 5 7323 067 935391: 0 7 91 1 1 55464571 1 2 9 5

                                 . 8888888888888878 0       0000000000000000
                               -    EEEEEEEEEEEEEEEE 6227 83 9471 609592 0       4437 .02286606421 2                      .

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                 ~               -        EEEEEE2EEEEEEEEE m                     09 71 64 y2 9445261 4 5          097001 1 393258928 r                                 .                . .                           .
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                    .h        3          11 001 1 1 1 1 1 1 1 1                                                             001 S                         - - - - - - - - - - - - - - - -

R0 - EEEE'EEEEEEEEEEEE E5 s 6501 4529628 72665 T1 e 0 1 303501 9801 821 52 . . . E > l M i 3 561 1 6442334561 1 6 A M - ' . R r A o n 0 ' . - P i 0099000000000990 r 1 1 001 1 1 1 1 1 01 1 001 N y , 3_ - - - - - - - - - - - - - - - - O/ s EEEEE2t8EEtEEE1t n I s _ 747694$71 625659e S r o 5 555759547064351'0 . Rh i - E t 2 761 1 9564545881 29 P0 a . S0 c I 5 o 5 4 D > L 9999900000099999 2 2 000001 1 1 1 1 1 00000 M - S l - - - - - - - - - - - - - - - - C 3 TS o - EEEEEEEEEEEEEEEE D Q O 2 NE ES t r 0 82407629481 091 98 022534321 7021 292 VA n . 1 E E o 2 11 221 8968581 1 221

           - L    GL      C                            -                                                -

V B NE B A I R e 0 T D h 9999999990999999 LL t 2 0000000001 000000 I E - - - - - - - - - - - - - - - - . UV o - EEEEEEEEEEEEEEEE BE t 1 9742 255677 74062 L 5 88461 441 29486681 . E s . . . . ND e 1 1 1 3321 1 1 1 81 1 2342 I N c BU n RO a 5 - UR t 99999999990 99999 TG s 1 0000000000000000 i - - - - - - - - - - - - - - - - ES D - EEEEEEEEEEEEEEEE TU 471 1 949660242389 I O 0 232575502663746 7 SU . . . . . . . N 1 33663222 21 234683 YI ET LN 0 LO 9988899999998889 AC 1 0000000000000000 V - - - - - - - - - - - - - - - - R - EEEEEEEEEEEEEEEE RO 397550027 207 3074 EF 5 7323067935391 600 . . V . . . A 0 791 1 1 55464571 1 29 E B 5 8888888888888878 0 0000000000000000

                                 -        EEEEEEEEEEEEEEEE 6227839471 609592 0           443702286606421                   .

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                           >          -    EEEEEEE2EEEEEEEE N         s          6501 452 962 87 2 665 O -     l e   0      1    303501 9801 821 52            . . .

I r S o i 3 561 1 6442 33 4561 1 6 R M - E r P y n 0 S/ i 0099 000000000990 I s 3 1 1 001 1 1 1 1 1 01 1 001 D r , - - - - - - - - - - - - - - - - h s - tEEEEEEEEECEEEEE T n 7 47 694521 6256590 N0 o 5 5557 5954706435 1 0 Y E0 i . . . . . . . . L V5 t 2 781 1 9564545881 29 5 N > a 2 O G c M - N o 5 3 N I S L 9999900000099999 C O DE 2 000001 1 1 1 1 1 00000 t0 I - - - - - - - - - - - - - - - - 0 2 LS l T I A o - EEEEEEEEEEEEEEEE A r 82407629481 091 98 G 1 E L B M R UE BL E t n 0 022534321 702 1 292. V A O GR o 2 1 1 221 8968581 1 221 B T F N C N I L I l E e 0 i S V h 9999999990999999 R I E t 2 0000000001 000000 0 LL - - - - - - - - - - - - - - - - .

                   #  O         o     -     EEEEEEEEEEEEEEEE PD        t          1 97 4225567 77 4 062 N        5      88461 441 29486681             . .                             .

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  .;     'j          The. gaseous radwaste system has the capchility to control, collect', process,
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A simplified. flow diagram of the gaseous radwaste system for BV-1 and BV-2 6/89 is provided as Figure 2.4-1. A diagram-showing the gaseous effluent release points' is provided as Figure 2.4-2. Since.the concept of a shared gaseous radwaste system.is used, then gaseous waste generated can be stored, processed 1 and. discharged from either BV-1 or BV-2.

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2-97 ISSUE 2 { REVISION 2 _ _____._______._____._____________________.__.________i

BV-1 DDCM , FIGURE 2.4-1 7 Beaver Valley Power Station Units 1 and 2 Gaseous Radwaste System

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                                                                                                                                                         '                 I          I DECATfM                               DECAYfM e                                                                      __.

DDYfM DECAYfM l FILfBS DECAYIM DECAffM I J a e 1 e 4 o a o a a a DEGASITID SWEEPGAS h DDSITIR lilAlfl0N AIR h exm Mtm h ; g MDtSOR AIR EJECTOR h j REACTOR W IAfl0N F f0R FllRCE h l C001M7 00NTAllMDtf UAT.E PlMPS h l Y 1 l 2-98 ISSUE 2 i REVISION 2

BV-1 00CM FIGURE 2.4-2 Beaver Valley Power Station Units 1 and 2 Gaseous Effluent Release Points l0hio River l I Io <. 7

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   @ Unit 2 Containment /SLCRS Vent
   @ Unit 2 Condensate Polishing Building Vent
   @ Unit 2 Waste Gas Storage Vault Vent
   @ Unit 2 Decontamination Building Vent                                                                    ;

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,l[ - Tab 1h 3.0-1'. contains :the. DLC- site number,. sector, distance sample point-1 V[= -

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1.:. frequency for various exposure pathways in the vicinity of the Beaver Valley

              ,                           Power. Stations (BVPS) for the radiological ~ monitoring program. Figures 3~0-         .

1 through,3.0-9 show the. location'of.th'e various~ sampling points.

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                  '4.0 IBTORMATION RELATED TO 40 CFR 190 Technical . Specification 3.11.4.1.a. requires that when the ca?culated doses
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  . ; (,,jI             . associated with- the ' effluent releases texceed twice                               the    limits   of Specifications                           3.11.1.2..a. 3.11.1.2.b, 3.11.2.2-.a, 3.11.2.2.b,.3.11.2.3.a, or 3.11.2.3.b, the licensae shall prepare and submit a Special Report to the' Commission: and . limit subsequent ' releases such that the dose or dose commitment to member (s).of tne public from all facility releases is limited to - 5 25 mrem to the total body, any organ (except.the thyroid, which is limited to ' 5 75 mrem) for a calendar . year.                                  The BVPS-1     Technical Specifications consider doses to members of the public due to the . operation of BVPS-1 but do not include doses due to BVPS-2, any ~ other part of the uranium fuel cycle, or direct shine from site reactors.                             If a Special Report to'the Commission is prepared by the licensee as required by Specification 3.11.4.1.a. the evaluation should address:

1) A determination of the maximum exposed member of the public.

2) A determination of the total dose to.this-person from all existing pathways and sources -of radioactive effluents. Where additional information on . pathways and nuclides is needed, the best available information will be used and documented.

3) A determination. of the dose resulting from direct radiation from_the site facilities.

Total body and organ doses resulting from liquid effluents from the BVPS SITE will be summed with the doses-resulting from releases of noble gases, [s radiodines, particulate, and tritium (excluding C-14). These doses will be bas-d upon' releases from the BVPS SITE.during the appropriate time period in which twice the unit specification was exceeded. Direct dose components due to skyshine will ts determined either by calculation, using methodology specified in NUREG-0133, or by actual measurement. The dose from both ; releases and direct radiation will be summed. l l l

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1 BV-1 ODCM' l APPENDIX A f T

SUMMARY

OF DISFERSION CALCULATIONAL PROCEDURES

                    -Annual' average and grazing season average values of relative concentration (X/Q) and deposition (D/Q) were calculated for continuous and intermittent gasecus releases of activity from the site according to the straight-line airflow (Gaussian) model described in NRC Regulatory Guide 1.111, Revision 1. Undecayed and undepleted sec:or average X/Q and D/Q values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual
                    -receptors.                                .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 is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor.                                                                   A building wake correction factor was used to adjust calculations for ground-level
                    ' releases. Airflow. reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site (Albersheim, 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 site continuous gaseous release points that have been evaluated include the process vent attached to the BVPS-1 natural draft cooling tower, the Containment Vents, Ventilation Vents, Turbine Building Vents, the BVPS-2 Condensate Polishing Building Vent, Decontamination Building Vent, and Gaseous Waste Storage Tank Vault Vent. The intermittent releases are from the Process Vent, Containment Vents, and Ventilation Vents. Only the process vent was considered g-- to be an elevated release with all other release points being treated as ground-t level releases. A summary of the release characteristics and their locations is given in Table A-1. Onsite meteorological data for the period January 1, 1976 through 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 October 31 for ecch . year of the 5-year meteorological data base. This grazing season corresponds reasonably well with the growing season. The data were collected according to guidance in NRC Regulatory Guide 1.23 as described in Sect ion 2.3 of the BVPS-2 FSAR. The parameters used in the 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 ft) were used for all release points except the process vent which required the use of 500-ft winds and AT (500-35 ft) which are representative of the release height (510 ft). O A-1 ISSUE 2 REVISION 2

BV-1 ODCM

                               -The annual-average and grazing season X/Q and D/Q values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest

![T resident,- nearest vegetable garden, nearest milk cow, nearest milk goat, and (_) nearest meat animal. In the case of the process vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum l, X/Q-D/Q values. The distances of the limiting maximum individual receptors from the radioactive release points are given,in Table 2.2-3. The continuous release annual. average X/Q values at the special locations for- the Containment Vents, Ventilation Vents, Process Vent. Turbine Building Vents, Decontamination Building Vent, Waste Gas Storage Vault Vent, and Condensate . Polishing Building Vent, are given in Tables 2.2-4 through 2.2-10 respectively. Continuous release annual average X/Q's for these same release pointc; are also given at ten incremental downwind distances. Continuous release D/Q values for these same release points are given in Tables 2.3-21 through 2.3-27 for the incremental distances and in Tables 2.3-28 through 2.3-34 for the special locations. Due to their location adjacent to the containment building, the BVPS-2 Decontamination Building and Gaseous Waste Storage Tank Vault X/Q's and D/Q's are the same as the containment vent X/Q's and D/Q's. Likewise, the Turbine Building Vent X/Q's and D/Q's apply to the BVPS-2 Condensate Polishing Building as well due to its location adjacent to the Turbine Building. Tables A-2 through A-5 contain short term X/Q values for batch releases originating from the 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. Albersheim, S. R., Development of Terrain Adjustment Factors for Use at the Beaver Valley Power Station for the Straight-Line Atmospheric Dispersion Model, NUS-2173, NUS Corporation, June 1978 Sagendorf, J. F., Goll, J. T. and Sandusky, W. F., XODQD0Q: Computer Program for tne Meteorological Evaluation of Routine Ef fluent Releases at Nuclear Power Stations, NUREG/CR-2919, U. S. Nuclear Regulatory Comission, September, 1982. O A-2 ISSCE 2 REVISION 2 _ _ _ _ _ _ _ - - _ _ _ _ J

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li:;;,, Io. f:} ' -APPENDIX B

                                                                                                                  !l L"t                                    ,
                                                              . INPUTS TO GALE CODE FOR GENERATION OF LIQUID SOURCE i"[
                                                          . INPUTS TO SWEC GAS 1BB FOR GENERATION OF GASEOUS -{S J'

l ? .i p.. (. y f'a n

                                           .'- l g..

d 1 l l B-1 ISSUE 2 REVISION 2

fy e '.. ' 4 y BV-1 ODCM

           -e                                           APPENDIX B'
              '(           . INPUTS TO GALE CODE FOR-GENERATION 0F LIQUID SOURCE TERM MIX (l/ ]+                                BEAVER VALLEY UNIT 1                                                     PWR Thermal power level.(megawatts)                                                           2766.000 i;              Plant' capacity factor                                                                          .800 Mass of primary coolant (thousand Ibs)'                                                     345.000 Percent. fuel with cladding defects                                                          .. 120 Primary system letdown rate (gpm)                                                            60.000 Letdown cation demineralized flow                                                              6.000-Number of steam generators                                                                     3'.000 f:                Total steam flow (million 1bs/hr)                                                            11.620 6.772
                     ~

l Mass of steam'in each steam generator (thousand Ibs) Mass of liquid in each steam generator (thousand Ibs) 97.000 Total mass of secondary coolant (thousand Ibs). 1296.000 Mass of water in steam generator (thousand Ibs) 291.000 Blowdown rate (thousand Ibs/hr) 33.900 Primary to secondary leak rate (1bs/ day) 100.000 Fission product carry-over fraction .001. i Halogen carry-over fraction .010 l Condensate demineralized flow-fracton 0.000 ; Radwaste dilution flow (thousand gpm) 22.500 l f .- j k I I i l 1 l l ( B-2 ISSUE 2 REVISION 2 , I i

N 2 NC

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                                                                                                         . APPENDIX B-
   ' ?'N .                INPUTS _TO SWEC CODE GASIBB FOR GENERATION OF GASEOUS' SOURCE TERM MIXES-a      "
          );

BEAVER VALLEY UNIT 1 PWR Thermal power' level' (megawatts) 2766.000 Plant' capacity factor .

                                                                                                                                                                     .800 Mass of primary coolant (thousand Ibs)                                                                                                          385.000 Percent fuel with cladding defects                                                                                                                  .120 Primary system letdown rate (gpm)                                                                                                                57.000 Letdown cation demineralized flow.                                                                                                                5.700 l                 Number of steam generators                                                                                                                        3.000 Total' steam flow (million Ibs/hr) 11.600-Mass of steam in each stesm. generator (thousand Ibs)                                                                                             8.700 Mass of liquid in each steam generator (thousand 3bs)                                                                                           100.000 Total-mass of secondary coolant (thousand Ibs)                                                                                                 2000.000 Mass of water in steam generator (thousand Ibs)                                                                                                 298 000 Blowdown. rate (thousand Ibs/hr)                                                                                                                 52.000-Primary to secondary leak rate-(1bs/ day)                                                                                                       100.000 Fission product carry-over fraction                                                                                                                 .001-Halogen carry-over fraction                                                                                                                         .010 Condensate demineralized flow fracton                                                                                                             0.000 Radwaste dilution flow (thousand gpm)                                                                                                            15.000 GASEOUS WASTE INPUTS There is not continuous stripping of full letdown flow D

Hold up time for xenon (days) 39.000 Hold up time for krypton (days) 2.000 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 charcolodine release fraction 1.000 particulate release fraction 1.000 6/89' Containment volume (million cu-ft) 1.800' Frequency of primary coolant degassing (times /yr) 2.000 Primary to secondary leak rate (1b/ day) 100.000 There is a kidney filter l Containment atmosphrere cleanup rate (thousand ef'm) 2.000 l Purge time'of containment (hours) 8.000 There is not a condensate domineralizer Iodine partition factor (gas / liq) 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 (Ibs/hr) 1700.000 Fraction iodine released from blowdown tank vent 0.000 Fraction iodine released from main condensate air ejector 0.440 There is not a cryogenic off gas system

                 *2 cold and 2 hot purge.
   .p.

d. B-4 ISSUE 2 l, REVISION 2 LL_----_._-_._-_-___._-___- - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ . - - - _ _ - - . _ _ - - - . _ _ _ .- _ _}}

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