ML20247A141

Issue 1,Rev 3 to Beaver Valley Power Station Unit 2 Odcm

ML20247A141
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-890630-01, NUDOCS 8909120051
Download: ML20247A141 (162)

Text

_

l- Page'1 BV-2 ODCM Changes

/~; Issue 1. Revision 3 L2

1. Description of BV-2 ODCM Changes

1. Page i:

This revision to the Table of Contents reflects the addition of the following ODCM Sections:

A. Section 1.4, Liquid Radwaste System (See Justification 1)

B. Section 2.4, Gaseous Radwaste System (See Justification 1)

2. 'Page vii:

This revision to the List of Figures reflects the addition of the following ODCM Figures:

A. Figure 1.4-1, Beaver Valley Power Station Unit 1 Liquid Radwaste System (See Justification 1)

B. Figure 1.4-2, Beaver Valley Power Station Unit 2 Liquid Radwaste System (56e Justification 1)

C. Figure 2.4-1, Beaver Valley Power Station Units I and 2 Gaseous Radwaste System (See Justification 1)

D Figure 2,4-2, Beaver Valley Power Station Units 1 and hn 2 Gaseous Effluent Release Points (See Justification 1)

3. Page 1-13:

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

4. P;;e 1-14:

This revision adds the words "from each reactor unit" to two places on this page. This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)

5. Pages 1-19 thru l-21:

1 This revision reflects the addition of ODCM Section 1.4 regarding the i Liquid Radwaste System. (See Justification 1) 1

6. Pages 2-15 and 2-17:

This revisien corrects typos to the following ODCM equations: I A. Equation 2.1-20, change the HHSP to HSP multiplier from 0.70 to

("))

t 0.33 (See Justification 1) ,

B. Equation 2.1-24, change the HHSP to HSP multiplier from 0.70 to l 0.33 (See Justification 1) 8909120051 890825 PDR ADOCK 05000334 R pop

l-Page' 2 l;,

l.W l  :.

b ,A jf^l\j BV ODCM Changes Issue 1.. Revision 3

7. Page 2-28:

This: revision adds'the words "from the-site". This ensures compliance with the currer.t requirements of the Technical Specifications.-(See Justification.2)-

8. Page 2-44:

.This revision provides re-verified P values for the Beaver Valley it Site.-(See Justification 1) 9' Pages 2-51 and 2-S2:

This revision adds'the words'"from each reactor unit". This ensures:

compliance with the, current requirements of the Technical

-Specifications. (See Justification 2)

10. Pages 2-58 and 2-59:

p) .

This revision reflects the correction of the definition for the t f.

value in the cow-meat pathway. (See Justification 1) '

11. Page 2-64:

This revision adds the words "from each reactor unit". This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)

12. Pages 2-66 thru 2-84:

This revision provides re-verified R values for the Beaver Valley '

Site. (See Justification 1) i

13. Pages 2-99 thru 2-101:

'This revision reflects the addition of ODCM Section 2.4 regarding the Gaseous Radwaste System. (See Justification 1) l

- 14. Pages 3-2, 3-4, 3-5, and 3-8:

This revision corrects typos. (See Justification 2) 1

's

e s 'Page.3 I BV-2 00CM Changes '

? [V . Issue:1, Revision 3 ll

'1 II. Justification of BV-2 ODCM Changes i' '

l. . A' letter dated March 2, 1989 (from ' the NRC) . was received by ' Duquesne-

-Light regarding acceptance of the Offsite Dose Calculation Manuals. The NRC acceptance of the BV-2 ODCM was'- based on a Technical Evsluation.

Report (TER No. EGG-PHY-8217) provided by the Idaho National Engineering L 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 these 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 No ERS-ATL-89-014. 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

.O; these changes - to the ODCM will not adversely impact the accuracy or reliability of effluent dose calculations.

2. As requested by letters ND3NSM:3431, NDIRSM:3522, and NDINSM:3652 Technical Specifications were required to be verified in all plant

. iinplementing procedures. As part 'of this effort, wording errors / typos were identified in various sections of the ODCM. This revision corrects the anomalies identified during the verification effort.

III. Concluding Statement'of BV-2 DDCM Changes

1. The above justifications ensure that the BV-2 DDCM changes will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculation.

LO

O l BEAVER VALLEY POWER STATION UNIT NO. 2 o OFF-SITE DOSE CALCULATION MANUAL 1

O

73 DUQUESNE LIGHT COMPANY.

s

=1 ODCM Review and Approval Sheet BV-2 ODCM 1

. l Admin.

Issue 'Rev. Pr:s . RSC Review OSC Review- Approv. Eff.

No. Issd. Meeting No. Date Meeting No.

No. Date Sign. Date Date 1 3' Title BV-RSC- May' BV-OSC- June gg/g7 June i 12-89 25 13-89 15 * . .. 30 thru 1989 1989 1989-viii 1-1 ,

thru i 1-21 $

t 2-1 thru 2-101 3-1 thru 3-14 4-1 5-1 A-1 thru A-7 B-1 thru B-2 RE 6.101-1 O

l

_ __m_____--.mm_,___m__-____.-___m_ m.___m__-___ . _ _ _ . . _ , . _ . _ _ . . _ _ . . _ _ _ _ _ .

DUQUESNE LIGHT COMPANY Nuclear Group

,x Review and Approval Sheet UNIT 2 - 0FFSITE DOSE CALCULATION MANUAL ISSUE 1 Rev. Pgs. Tech. Rev. OSC Approv. Eff.

No. Issd. Sign. Date Review Date Sign. Date Dste 1 TITLE PGS BV-RSC-11-87 BV-OSC-17-87 i thru viii BV-RSC-12-87 June 12, 1987 7/24/87 1-1 thru 1-18 BV-RSC-14-87 7//G/M 2-1 thru 2-98 May 29, 1987 3-1 thru 3-14 T/ $

4-1, 5-1 j A-1 thru A-7

~

B-1 and B-2 2 2-12 BV-RSC-38-87 BV-1-OSC-25-87 g 12/22/87 2-15 12/3/87 12/15/87

@ zPJ /2/z2/97 n/

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DUQL' ESSE. LIGHT C0!!PANY lleaver Valley Power Station Unit 2

. Docket-No. 50-412 O. -

4 i

BEAVER VALLEY POWER STATION UNIT 2

0FF-SITE DOSE CALCULATION MANUAL (ODCM) i-l l

l L .' .

l-

BV.2 ODCM TABLE OF CONTENTS

('- Section Title Py

\d-Table of Contents i List of Tables 11 List of Figures vid Preface viii 1 ~. 0 LIQUID EFFLUENTS ' 1-1 1.1 Monitor Alarm Setpoint Determination 1-1 1.2 Compliance With BVTS 3.11.1.1 1 1.3 Compliance With 10 CFR 50 (Liquids) 1-12 1.4 Liquid Radwaste System 1-19 l 6/89 2.0 GASEOUS EFFLUENTS 2-1 2.1 Monitor Alarm Setpoint Determination 2-1 2.2 Compliance With 10 CFR 20 (Gaseous) 2-21 2.3 Compliance WitL 10 CFR 50 (Gaseous) 2-45 2-.4 ' Gaseous Radwaste System 2-99 l 6/89 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-1

) 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 O i ISSUE 1 REVISION 3 1

4

2 BV-2 ODCM

-List of Tables

' Table No. Title Page No.

v .

1~.1-1 Liquid Source Terms 1-6,

'1.2-1 Recirculation Times Required Before Sampling of 1-11 Liquid Discharge Tanks 1.3-1 Ag Values for_an Adult for the Beaver Valley Site 1-16 2.1-1 Radionuclides Mix'for Gaseous Effluents 2-19 2.1-2 Monitor Detector Efficiencies, BVPS-2 2-20 2.2-1 Modes of Gaseous Release from Beaver Valley Power 2-32 Station' Unit 2 Vents for Implementation of 10 CFR 20

'2.2-2 Radionuclides Mix for Gaseous Effluents from the 2-33 g Beaver Valley Power Station, Unit 2 (Ci/Yr) l-2.2-3 Distances of Limiting Maximum Individual Receptors to 2-34 Release Points for Annual X/Q Values 2.2-4 Beaver Valley Site Containment 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.

2.2-5 Beaver Valley Site Ventilation Vents Annual Average, 2-36 Ground Level, X/Q Values. For Continuous Ground l

Level Releases For Special Distances (Identified in

! Table 2.2-3) and Selected Control Locations.

l.

2.2-6 Beaver Valley Site Process Vent Annual Average, 2-37 Ground Level, X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control Locations.

l

'2.2-7 Beaver Valley Site Turbine Building Vents Annual 2-38 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, 2-39 Ground Level X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selecteo Control Locations.

l LO 11 ISSUE 1 REVISION 3

BV-2 ODCML List of Tables (Continued)

Table No.

~

Title Page No.

} }()s E2.2-9 BVPS-2 Waste Gas Storage Vault Vent Annual Average, 2-40 l

Ground Level X/Q Values. For Continuous Ground

' Level Releases,.For Special' Distances-(Identified in Table 2.2-3) and Selected Control Locations.

2.2-10 BVPS-2 Condensate Polishing Building Annual Average,. 2-41 Ground Level X/Q Values. For Continuous Ground Level Releases, For Special Distances (Identified in Table 2.2-3) and Selected Control Locations.

l l 2.2-11 Dose Factors for Noble Gases and Daughters 2-42 2.2-12 Dose Parameters for Finite Elevated Plumes, Beaver 2-43 Valley Site.

2.2-13 P gT Values for a Child for the Beaver Valley Site 2-44 2.3-1 Modes of Gaseous Release From Beaver Valley Site 2-65

. Vents for Implementation of 10 CFR 20 and 10 CFR 50 2.3-2 R Values for the Beaver Valley Site (Inhalation, 2-66 Adult) l 2.3-3 R Values for the Beaver Valley Site (Inhalation, 2-67 Teen) 2.3-4 R Values ~for the Beaver Valley Site (Inhalacion, 2-68 Child) 2.3-5 R Values for the Beaver Valley Site (Inhalation, 2-69 Infant) 2.3-6 R Values for the Beaver Valley Site (Ground Plane) 2-70 2.3-7 R Values for the Beaver Valley Site (Vegetable, 2-71 Adult) 2.3-8 R Values for the Beaver Valley Site (Vegetable, 2-72 Teen) 2.3-9 R Values for the Beaver Valley Site (Vegetable, 2-73 Child) 2.3-10 R Values for the Beaver Valley Site (Meat, Adult) 2-74 2.3-11 R Values for the Beaver Valley Site (Meat, Teen) 2-75 2.3-12 R Values for the Beaver Valley Site (Meat, Child) 2-76 fii ISSUE 1 REVISION 3

EV-2 ODCM=

j..

b . ' List of Tables'(' Continued) 1 i

p N Table No. Title Page No. l H k.f ,.!

j. L 2.3-13 R Values for the Beaver Valley Site. (Cow Milk, Adult) 2-77 '

l 2.3-14 R Values for the Beaver Valley Site (Cow Milk, Teen) 2-78 2.3415 R Values for the Beaver Valley Site (Cow Milk, Child) 2-79 f 2.3-16 R Values for the Beaver Valley Site (Cow Milk, 2-80 {

Infant) .i

'2.3-17 R Values for the Etaise Valle; Site (Goat Milk, 2-81 ,j Adult) {

2.3-18 R Values for the Beaver Valley Site (Goat Milk, Teen) 2-82 l 2.3-19 R Values for the Beaver Valley Site (Goat Milk, 2-83 Child) 2.3-20 R Values for the Beaver Valley Site (Goat Milk, 2-84 Infant)  ;

I

~

2.3-21 Beaver Valley Site Pe: cess Vent Dispersion Paremeters 2-85 (D/Q), m' , for Continuous Elevated Releases > 500 Hrs /Yr.or > 150 Hrs /Qtr

(./

2.3-22' Beaver Valley Site Containment Vents Dispersion :2-86 Parameters (M),m-2, for Continuous Ground Level l Releases > 500 Ifrs/Yr or > 153 Hrs /Qtr .)

I 2.3-23 Beaver Valley Site Ventilation Vents Dispersion 2-87 i Parameter ( M ),.w' , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr ,

l 2.3-24 Beaver Valley Site Turbine Building Vents Dispersion 2-8B Parameters ( 5 ), m' , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr j 2.3-25 Beaver Valley Unit 2 Condensate Polishing Building 2-89 Vent Dispersion Parameters ( 5 ), m' , for Continous Ground Level Releases > 300 Hrs /Yr or > 150 Hrs /Qtr I

i O iv ISSUE 1 l

REVISION 3 l

+

(

BV-2 ODCM-List of Tables (Continued)

, d ,J Table No. _

Title Page No.

l -. .. .

Beaver. Valley. Unit 2 Decontamination Building Vent 2 3-26 2 Dispersion Parameter (D/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 2-91

~~

DispersionParameters(D[Q),m' , for Continuous Ground Level Releases.> 500 Hrs /Yr or > 150 Hrs /^tr 2.3-28 Beaver' Valley.' Site Process Vent Dispersion Parameters 2-92

-(D/Q), m' , for Centinuous Elevated Releases > 500-Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) 2.3-29 , Beaver. Valley Site Containment Vents Dispersion 2-93

-2 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 Vents Dispersion 2-94 m

Parameter (5[Q),m' , for Continuous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) 2.3-31 Beaver Valley Site Turbine Building Vents Dispersion 2-95 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) 2.3-32 Beaver Valley Unit 2 Condensate Polishing Building 2-96 Vent Dispersion Parameter (D/Q), m' , for Continous Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Qtr for Special Distances (Identified in Table 2.2-3) 2.3-33 Beaver Valley Unit 2 Decontamination Building Vent 2-97 Dispersion Parameter (D76), m' , for Continuous j Ground Level Releases > 500 Hrs /Yr or > 150 Hrs /Otr for Special Distances (Identified in Table 2.2-3}

I i

I y ISSUE 1  !

REVISIGN 3 1

1 L.__.__--___-_-____

BV-2 ODCM List.of Tables (Continued) f j: T (le No. Title Page No.

U .

Beaver Valley Unit 2 Waste Gas Storage Vault Vent 2.3-34 2-98  ;

Dispersion Parameter (D[Q), m -2 , 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 3-1 A-1 Beaver Valley Site Release Conditions A-3

A-2 Beaver Valley Site Containment Vents Dispersion A-4 s Parameters (X/q), sec/m', for Ground Level Releases 5 500 Hrs /Yr or 5 150 Hrs /Qtr for Special Locations (Identified in Table 2.2-3)

A-3 Beaver Valley Site Ventilation Vents Dispersion A-5 Parameters (X/q), sec/m' for Batch Ground Level Releases 5 500 Hrs /Yr or 5 150 Hrs /Qtr for Special Locations (Identified in Table 2.2-3)

A-4 Beaver Valley Site Process Vent Dispersion Parameters A-6 (5%),sec/m', for Batch Elevated Releases 5 500 Hrs /Yr or 5 150 Hrs /Qtr for Special Location (Identified in Table 2.2-5)

A-5 Beaver Valley Site Process Vent Dispersion Parameters A-7 (E%),sec/m',forBatchElevatedReleasesS500 Hrs /Yr or 5 1.50 Hrs /Qtr for 0.5 mile increments.

O vi ISSUE 1 REVISION 3

BV-2 ODCM

[ List Of Figures No. Title Page A. ,/' . .

1. 4 - 1~ Beaver Valley Power Station' Unit 1 Liquid Radwaste' System 1-20 1.4-2. Beaver Valley Power Station Unit 2 Liquid Radwaste System 1-21 6/89-2.4-1 -Beaver Valley Power Station Units 1 and 2 Gaseous Radwaste System 2-100 2.4-2 Beaver Valley. Power Station Units 1 and 2 Gaseous Effluent Release. Points 2-101 3.0-1 Radiological Environmental Monitoring Program -

Aix.. Sampling Locations 3-6 3.0-2 Radiological Environmental Monitoring Program -

TLD Locations -- Northwest Quadrant 3-7 3.0-3 Radiological E.wironmental Monitoring Program -

TLD Locations -- Northeast Quadrant 3-8 3.0-4 Radiological Environmental Monitoring Program -

TLD Locations -- Southeast Quadrant 3-9 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 -

Fooderop Sampling Locations 3-13 3.0-9 Radiological Environmental Monitoring Program -

Fish Sampling Locations 3-14 l

O vii ISSUE 1 REVISION .2

SV-2 ODCM PREFACE

- r" -

.This Offsite Dose Calculation Manual (ODCM) provides the information and f( methodologies to be used by Beaver Valley- Power Station Unit 2 .(BVPS-2) to assure compliance with certain portions of BVPS-2 Technical Specifications.

These portions are those related to liquid and gaseous radiological effluents.

They are- intended to show compliance with 10.CFR 20, 10 CFR 50.36a, Appendix I of 10 CFR 50, and 40 CFR 190.

This ODCM is based on " Radiological Effluent Technical Specifications for PWR's (NUREG-0472, Draft)", " Preparation of . Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133)", and other inputs from the United States Nuclear Regulatory Commission (USNRC). Specific plant procedures for implementation of this manual will be developed. These procedures will be utilized by the operating staff of BVPS-2 to assure compliance with Technical Specifications.

The ODCM has been prepared as generically as possible in order to minimize the need for future revisions. However, some changes to the ODCM will be expected in the future. Any such changes will be properly reviewed and approved as indicated in the Administrative Control Section, Specification 6.15.2 of the BVPS-2 Technical Specifications.

-s

%J

O viii ISSUE 1 REVISION 3

BV-2 ODCM 1.0 L_IQUID EFFLUENTS f - Beaver Valley Units 1 and 2 utilize the concept of a shared liquid

( radioactive waste system according to NUREG 0133. This permits the mixing of liquid radwaste for processing and allocating of dose due to release as defined in Section 1.3. In Section 1.1 effluent monitor setpoints for a conservative mix are based on the individual Units' specific parameters, but-effluent monitor setpoints for analysis prior to release permit usc 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 there is the difference that- BVPS-2 setroints are presented in pCi/ml rather than CPM as in.BVPS-1. This difference is due to software which applies a conversion factor to the raw data (CPM). Note that the pC1/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 alarm setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10 CFR r~s 20, Appendix B, Table 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 an alternative method to be used to determine the monitor HIGH alarm setpoint (HSP). The methodology in Section 1.1.2 may be used for any batch release and shall be used when the total gamma radioactivity concentration of the liquid effluent prior to dilution exceeds 2.97E-5 pCi/ml. This concentration is equivalent to a monitor response of 5.84E3 nepm (net counts per minute above background).

The HIGH setpoint derived in Section 1.1.1 of 2.38E-5 pC1/ml above background allows for a tritium concentration of up to 6.28E-2 pCi/ml. The I

setpoint was obtained by use of a conversion factor (CPM to pCi/ml) of 5.09E-9 determined for the nuclide mix. (See Reference 5) 1.1.1 Setpoint Determination Based on a Conservative Mix The HIGH alarm setpoint for the Liquid Waste Effluent Monitor (2SGC-RQII00) should be set at 2.97E-5 pCi/ml above background. This setpoint is based on the following conditions:

• Source terms given in Table 1.1-1. These source terms have been generated by using models and input similar to NUREG-0017. The inputs are given in Appendix B.

• Dilution water flow rate of 7,800 gpm.

O 1-1 ISSUE 1 REVISION 3

LV-2 ODCM Discharge flow rate prior to dilution of 116 gpm for the Liquid Waste Effluent Monitor (2SGC-RQIl00).

I' i .

(_).

• A software conversion factor (CPM to ECi/ml) of 5.09E-9 associated with

-Liquid Waste. Effluent Monitor (2SGC-RQIl00).

The above setpoints can be varied based on actual operating conditions resulting in the discharge and dilution flow rates as follows:

~

HSP = (1.1-1) f where:

HSP = Monitor HIGH alarm setpoint pCi/ml above background.

4.42E-7 r Proportionality constant based on nominal flow conditions (4.42E-7 = 2.97E-5 uCi/ml above background x 116 gpm + 7.8 E3 gpm)

F = Dilution water flow rate, BVPS-2 Cooling Tower blowdown rate (SPm).

f = Dischargs flow rate prior to dilution (gpm) 1.1.1.1 The " mix" (radionuclides and composition) of the liquid effluent was determined as follows:

,a

() a. The liquid source terms that are representative of the " mix" of the liquid effluent were dete rmir.ed. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from Table 1.1-1

b. The fraction of the total radioactivity in the liquid effluent comprised by radionuclides "i" (Sg ) for each individual radionuclides in the liquid effluent was determined by equation 1.1-2.

A S

g

= 1 (1.1-2)

I Af i

where:

A. = Annual release of radionuclides "1" in the liquid effluent from Table 1.1-1 (Ci/yr).

l l

l /"' i (N/

, 1-2 ISSUE 1 l REVISION 3 l

l 1

t .- - _ _ - _ _ - - _ - _ - _ _ _ _ - _ -

e BV-2 ODCM 1.1.1.2 ~The maximum acceptable total radioactivity conce'ntration in pC1/ml of' all radionuclides in the liquid effluent prior to dilution (C ) was t

(' determined by:

ks)

C = (1.1-3) 3 fI i MPC 4 where:

F = Dilution water flow rate (gpm), BVPb 2 Cooling Tower blowdown rate (not int.luding DVPS-1 blowdown or the BVPS-2 release out through the Emergency Outfall Structure)

= 7.,800 gpm f = Maximum acceptable discharge flow rate prior to dilution (gpn.) .

= 116 gpm for Liquid Waste Process Effluent Monitor (2SGC-RQIl00).

MPC = 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, obtained from Reference 1.

m S = Th9 fraction of total radioactivity attributed to

) radionuclides "i" (frem Equation 1.1-2).

1.1.1.3 The maximum acceptable radioactivity concentration in pCi/ml of radionuclides "1" in the liquid effluent piior to dilution (C g ) was determined by:

C f

=S g C (1.1-4) 1.1.1.4 The calculated monitor Display Value in pCi/ml ebove background attributed to the radionuclides, D.V., was determined by:

D.V. = 5.09E-9 I Cg Eg (1.1-5)

I where:

5.09E-9 = Conversion factor (CPM to pCi/ml), an average determined for the source term mix.

E.

= Detection efficiency of the monitor for radionuclides "i" (cpm /pCi/ml) from Table 1.1-1.

1.1.1.5 The monitor HIGH alarm setpoint above background (pCi/ml) should be set at the D.V. value.

1-3 ISSUE 1 l REVISION 3

BV-2 ODCM 1.1.2 Setpoint Determination Based on Analysis Prior to Release

. ("' The following method applies to liquid releases when determining'the setpoint for maximum acceptab h discharge flow rate prior to dilution and the associated HIGH alarm setpoint based on this flow rate for the Liquid

~ Waste Effluent Monitor (2SGC-RQIl00) during all operational conditions.

-The monitor alarm setpoint is set slightly above (a factor of 1.25) the concentration reading that results from the concentration of gamma emitting radionuclides in . order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allowable discharge-flow rate is reduced by 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 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 f =

c (1 1-f')

I 1.25 I i MPC f

where:

F = Dilution water flow rate, BVPS-2 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 from both plants are administrative 1y prohibited.

C f

= Radioactivity concentration of radionuclides "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-2 Technical Specifications, thn radionuclides should not be included as, a searce 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 g = The liquid effluent radioactivity concentration limit for radionuclides "i" (pCi/ml) from Table 1.1-1 or if not listed in Table 1.1-1 from Reference 1.

O 1-4 ISSCE 1 REVISION 3 f

BV-2 DDCM 1.1.2.2 The calculated monitor Display Valve (in VCi/ml) above background

' attributed to the radionuclides (D.V.) is determined by:

.j '\

'.(_,/ D.V. = (1.25) (5.09E-9) E C E 1 (1.1-7) i where:

E g

= The 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.

1.25 = A -factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor.

response.

5.09E-9 = Conversion factor (CPM to pC1/ml) an average determined for the source term mix.

1.1.2.3 The liquid effluent monitor HIGH alarm setpoint above background (pCi/ml) should be set at the D V. value adjusted by any excess dilution factor provided as defined in the following equation:

HSP = D.V. f (1,1-8)

~P where:

O) i s, HSP = Monitor HIGH alarm setpoint above background D.V. = Calculated monitor concentration reading (in pCi/ml) from 1.1-7 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 discharge. The reduced value of f' may be due to pump limitations or administrative selection.

l r

1-5 ISSUE 1 REVISION 3 t_____________

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BV-2 ODCB1 REFERENCES jq-Liquid Effluent tionitor Setpoints

.- \j

.(1) 10.CFR 20, Appendix B,' Table II, Column 2 and footnotes.

(2) Unit 2 DRF1S Isotopic Efficiencies, Calculation Package ERS-SFL-86-026.

-(3) Stone and Webster Computer Code, LIQ 1BB " Normal Liquid Releases from a

-Pressurized Water Reactor"

.(4) Isotopic Efficiencies (2SGC-RQIl00), Calculation Package ERS-JW-87-015 (5) Conversion Factor for 2SGC-RQIl00, Calculation Package ERS-WFW-87-021.

O 1-8 ISSUE 1 REVISION 3

_=-_---_-_______--_-____-__---__-__.-_---____-____--__ . _ _ - _ - _ -

BV-2 ODCM 1.2 Compliance with BVTS 3.11.1.1

/N Only nuclides for which activity concentrations are above LLD's specified in b'

Table 4.11-1 of Technical Specification 3.11.1.1 are considered to be present.

1.2.1 Batch Releases

1. 2.1.1' Pre-release The radioactivity content of each batch release will be determined prior to release in accordance with Table 4.11-1 of Beaver Valley Unit 2 Technical Specifications '(BVTS). In order to assure representative sampics, 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 2 (SVPS-2) will show compliance with BVTS 3.11.1.1 in the following manner:

The activity of the various radionuclides ir,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 i MDF (1.2-1).

/N (J where:

Conc g = concentration of radionuclides "i" at the unrestricted area, pCi/ml; C.

1

= 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 from both plants are administrative 1y prohibited)

The projected concentrations in ti.e unrestricted area are compared to the concentrations in Appendix B, Table II of 10 CFR 20. Before a release is authorized, Expression 1.2-2 must be satisfied.

If (Conc /MPC ) < 1 (1.2-2) where:

MPC f

= maximum permissible concentration of radionuclides "i" from Appendix B, Table II of 10 CFR 20, pCi/ml l

O 1-9 ISSUE 1 REVISION 3 L . _ _ - _ ___________-__-_ -

DV-2 CDCM The most common MPC g concentrations are listed in Table 1.1-1 and were taken

/^ss from Appendix B, Table II of 10 CFR 20.

.s

%J 1.2.1.2 Post-release The concentration of each radionuclides following release from the batch tank will be calculated in the unrestricted area in the following manner:

The average . activity of radionuclides "1" during the timt period of release is divided by the actual dilution flow during the period of release to obtain the ' concentration' in the unrestricted area. This calculation is shown in the following equation:

Cone g = ik tk (1.2-3)

ADF k

where:

Conc = the concentration of radionuclides "i" at the unrestricted area, during the. release period of time "k", pCi/ml; Note: Since discharge is from an isolated well-mixed tank at essentially a uniform rate, the difference between average and peak concentration within any discharge period is minimal.

A

!j C. = concentration of radionuclides "i" in batch release during time period "k", pCi/ml; V = v lume f tank released during time period "k", gal.

k ADF = actual volume of dilution flow during the time period of release "k", gal.

To show compliance with BVTS 3.11.1.1, the following relationship must hold:

I g(Coneg/MPC ) < 1 (1.2-4) 1.2.2 Continuous Continuous releases of liquid effluents do not presently occur at the BVPS-2.

l l

l r 1 O 1-10 ISSUE 1 REVISION 3 t _. _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

r BV-2 ODCM TABLE 1.2-1 r' 'c ' RECIRCULATION TIMES. REQUIRED BEFORE

, ) SAMPLING OF LIQUID DISCHARGE TANKS Namt Mark No. Approx. Recire. Time (by Operating Manual)' (hrs) a Liquid Waste Tanks 20WS-TK21A,B 8.3 Steam Generator Blowdown Hold Tanks" 2SGC-TK21A,B 33.3 SGC. Test Tanks 2SGC-TK23A,B 6.0

.a Not normally a direct source of discharge

,y b The times listed are those required for two recirculations of a full tank

( ) with one recirculation pump in operation. Partially full tank recirculation.

~'

times are directly proportional to the fraction of the tank capacity occupied by the entrained liquid waste after isolation. Values were derived from information in BVPS-2 Operating Manuals 2.17 1 and 2.25.1.

)

,n A.

1-11 ISSUE 1 REVISION 3 t=____ _ _ l

BV-2 ODCM

~

1.3 Compliance With 10 CFR 50_(Liquids) f"T -Beaver Valley. Units l' and 2 utilize the concept 'of a shared liquid

() '

~

~

radioactive waste system according to NUREG 0133. This ' permits mixing of the liquid radwaste for processing. Since the resulting effluent release cannot accurately be ascribed to. a specific reactor unit, the treated effluent releases'are allocated as defined below.

1.3.1- Cumulation of Doses The dose contribution from the release of liquid effluents will be.

~

L calculated montnly for each. batch release during the month, and a cumulative i summation of the total body and organ doses will be maintained for each L calendar month, current calendar. quarter, and the calendar year to date.

The dose contribution will be calculated using the following equation:

m D = UAF I f

A h k1=I.atk .Cg Fk (1.3-1) where:

= the cumulative dose commitment to the total body or any D*

organ, t, from the liquid effluents .for the' total time period m

I Atk*

k=1 At = the. length of the kth release over which C g and F ##"

( k averaged for all liquid releases, hours; k

Cg = the average concentration of radionuclides, "i", in undiluted liquid effluent during time period At fr m any liquid k

release, VCi/ml; A = the site related ingestion dose commitment factor to the I*

total body or any organ t for each identified principal gamma and beta emitter, mrem.m1 per hr-vCi; m = number of releases contributing to the cumulative dose, D UAF = unit allocation factor. Provides apportionment of dose between Units 1 and 2. Normally set at 0.5 for each unit.

(Must total to 1.0)

I i

.Cf 1-12 ISSUE 1 1

l REVISION 3 1 i

l 1

L1 - - -- . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _

BV-2 ODCM Y

F k

= .the near- ' field average dilution factor for C g during.any y

lfN liquid effluent release. Defined as the ratio of the average l 6/89

-Q undiluted liquid waste flow during release to the product of the average flow from the site discharge structure during the I report period to unrestricted receiving waters times 3. (3 OIO9

l. is the site specific applicable factor for the mixing effect

'of the BVPS-2 discharge structure).

l.

= Waste Flow l (3)(Dilution water flow) l The site specific applicable. factor of 3 results in a conservative estimate

-'of the near field dilution factor based upon . Regulatory -Guide 1.113 methodology and is better than a factor of ten below the limit specified in

- NUREG-0133, Section 4.3.

i The dose. factor A h was calculated for an adult for each isotope using the following equation from NUREG-0133.

A g = 1.14E5 (730/D,+ 21BFf )DFit ( .3-2) where:

1.14E5 = 1E6 pCi x 1E3 ml x 1 yr pCi 1 8760 hr 730 = adult water consumption rate, liters /yr; D = far field dilution factor from the near field area within one quarter mile of the release point to the potable water intake for adult water consumption; 21 = adult ah consumption, kg/yr; BF f

= bioaccumulation factor for radionuclides, "i" in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1, pCi/Kg per pCi/ liters, (if none, R.G. 1.109 Rev. 0);

DF'*

= dose conversion factor for radionuclides "i" for adults for a particular organ r from Table E-11 of Regulatory Guide 1.109 Rev. 1, mrem /pCi, (If none, NUREG-0172 or R.G. 1.109 Rev. 0).

I 1-13 ISSUE 1 REVISION 3 w__. _ _ _ _ - - _ - _ _ - _ . - ._ ___ -__-__--_ _ __- ___ __-____-_______ __-____-__-_ ____--_-_-___--_ - - _ __-

BV-2 ODCM 1

A table of A g values for an adult at the BVPS-2 are presented in Table 1.3-

1. The far field dilution factor (D ) for the BVPS is 200. This value is

~

based on a total dilution factor of 600 applicable to the Midland water intake located 1.3 miles downstream and on the opposite bank from the BVPS (ie. 200 = 600 + 3). The total dilution factor of 600 represents a conservative fully mixed annual average condition, Since the Midland intake is located on the opposite bank and is below the water surface, essential fully mixed conditions would have to exist for the radioactive effluent to be transported to the intake.

The cumulative doses (from each reactor unit) for a calendar quarter and a l6/89 calendar year are compared to the following BVPS-2 Technical Specification 3.11.1.2 limits:

For the calendar quarter, D s 1.5 mrem total body (1.3-3)

D 5 5.0 mrem any organ (1.3-4)

For the calendar year, D 5 3.0 mrem total body (1.3-5)

D s 10.0 mrem any organ (1.3-6) m If any of the limits in Expressions 1.3-3 through 1.3-6 are exceeded a Special Report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and T.S. 3.11.1.2.a must be 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 oice per 31 days in accordance with BV-2 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-2 TS 3.11.1.3 when the projected doses due to liquid effluent releases from each reactor unit when averaged over 31 days, would exceed 0.06 mrem to the total 6/89 body or 0.2 mrem to any organ. Doses used in the projection are obtained according to equation 1.3-1. The 31-day dose projection shall be performed according to the following equations:

When including pre-release data A+B (1.3-7)

D =

)+

37

_ T_( j I

i l

1 l

O 1-14 ISSUE 1 REVISION 3 l

_ _ _ _ _ - _ _ 1

c 2

BV-2 ODCM t

When not including pre-release data ,

73 "N .(1.3-8) 6b)- D 31

= -

.T.

(31) + C where:

D 31

= Projected 31 day dose, mrem A = Cumulative dose for quarter, mrem B '= Projected dose from this release, mrem T = Current days into quarter C = Value which may.be used to anticipate plant. trends, mrem-O

-0 0 1-15 ISSUE 1 REVISION 3

J" 1 av-; 00Cn

,.en .

. TABLE 1.3-1 (Page 1).

( v )' ..

A gg VALUES FOR THE ADULT-FOR THE BEAVER VALLEY SITE ..

(mrem /hr per pCi/ml) l THYROID KIDNEY LUNG- GI-LLI FONE LIVER T-BODY NUCLDE 2.70E-01 2 70E-01 2.70E-01 2.70E-01 2 70E-01------- ------

2.70E-01 .

H-3 0 00E-01 6 26E 03 6 26E 03 6.26E 03 l 3 13E 04 6.26E 03 6.26E 03 6 26E 03 4.08E 02 C-14 4.08E 02 4.08E 02 4.08E 02 NA-24 4.0BE 02 4.08E 02 4.08E 02 J

---

_----- ------- --_ - --- --------- 0 00E-01 0 00E-01 0 00E-01 5 19E 06 i P-32 4.62E 07 2.S7E 06 1 79E 06 1 69E 00 3.21E 02 H 0.00E-01 0.00E-01 1.27E 00 7.42E-01 2.81E-01 CR-51 0.00E-01 4 38E 03 8.35E 02 0 00E-01 1.30E 03 0 00E-01 1 34E 04 l MH-54 -- --- --------------------- -.

...--------------------- ---- ------- -- 3 52E 03  !

NN-56 0 00E-01 1J.10E 02 1495E 01 0

---

1 00E-0 1.40E 02 0.00E-01 2.54E 02 2 61E 02  :

0 00E-01 0.00E-01 FE-55 6.59E 02 4.56E 02 1.06E 02 0.00E-01 4.83E 02 8.15E 03 FE-59 1 04E 03 2.45E 03 9.38E 02 - 00E-01 - - - - . . . .------- ------.---------

1

---

------- -------- --- --, 0.00E-01 5 33E 02 CD-57 0.00E-01 2 10E 01 --1 3.50E 0 0 00E-01 0.D)E-01 0 00E-01 1.81C 03' 2.01E 02 0.00E-01 0.00E-01 1

)

(/ CO-58 0.00E-01 8.95E 01 0.00E-01 0 00E-01 4.83F 03- l CD-60 0 00E-01 2.57E 02 5.67E 02 0.00E-01 ---- ---------- - ------------ ------

NI-63

---

-- ---- ------------------ 00E-01 3 12E 04 2 16E 03 1.05E 03

0. 0 00E-01 0 00E-01 4.51E 02 0.00E-01 4.17E 02  :

1 65E 01 7.51E 00 0 00E-01 0 00E-01 NI-65 1 27E 02 0 00E-01 2 52E 01 0 00E-01 8 53E 02 i CU-64 0 00E-01 1 00E 01 4.70E 00

---

--- ------ ------ -- --- ------- E-01 4.93E 04 0 00E-01 4.64E 04 ZN-65 2 32E 04 7 37E 04 3.33E 04 0 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 ZN-69 4.93E 01 9.43E 01 6.56E 00 0 00E-01 5 82E 01 j 0.00E-01 4.04E 01 0.00E-01 0.00E-01 BR-83 0.00E-01

---

-----------------0.00E-01 -------- ------

4.11E-04 0.00E-01 0 00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 BR-84 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 BR-85 0.00E-01 0 00E-01 0.00E-01 0.00E-01 1.99E 04 ,

RB-86 0.00E-01 1.01E 05 4.71E 04 -- -- -------------------------- -- ---

---

------ -------------- ---------- 0.00E-01 0.00E-01 0.00E-01 4.00E-09 i

RB-68 0.00E-01 2.90E 02 1.54E 02 0.00E-01 1.12E-11 1.92E O2 1.35E 02 0.00E-01 0.00E-01 ,

RB-89 0.00E-01 0.00E-01 0 00E-01 3.57E 03 l SR-89 2.22E 04 0.00E-01 6.39E 02 0 00E-01 1

--_-------5.48E _ -_------ ------ -_---- 1.58E 04 1.34E-- 05

-- 0E-01 0.00E-01 0.00E-01 05 0.00E-01 00 1.95E 03 SR-90 0.00E-01 1 65E 01 0.00E-01 0.00E-01 0.00E-01 SR-91 4.10E 02 0.00E-01 0.00E-01 0.00E-01 3.0BE 03 SR-92 1.5GE 02 0.00E-01 6.72E 00 -- --

0 00E-01---------------15E 03 l

---

- --------------------- 0.00E-01 6 5.80E-01 0.00E-01 0.00E-01 1.55 E-02----- 1 61E-02 Y-90 0.00E-01 0.00E-01 0.00E-01 5.48E-03 0.00E-01 2.12E-04 Y-91M 0.00E-01 2 27E-01 0 00E-01 0 00E-01 0.00E-01 4.68E 03 Y-91 8.50E 00 U

1-16 ISSUE 1 REVISION 3

s l

BV.2 ODCM 7/l TABLE 1. 3_1 ( Pa ge 2 )

L-] .

A VALUES 'FOR TIIE ADULT FOR THE BEAVER VALLEY SITE it (mrem /hr per pCi/ml)

NUELDE . BONE LIVER T-BODY THYROID K I DNE 1r LUNG GI-LLI~

Y-92 5.09E-02 0.00E-01 1.49E-03 0.00E-01 0 00E-01 0.00E-01 8.92E 02-

' Y-93 1.62E-01 0.00E-01 4.46E-03 0.00E-01 0.00E-01 0.00E-01 5.12E 03 ZR-95 2.53E-01 8.11E-02 5.49E-02 0.00E-01 1.27E-01 0.00E-01 2.57E 02 ..

ZR-97 1.40E-02 2.82E-03 1.29E-03 0.00E-01 4.26E-03 0.00E-01 8.73E 02 NB-95 4.47E 02 2.40E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06.

NB-97 3.75E 00 9.48E-01 3.46E-01 0.00E-01 1 11E 00 0.00E-01 3.50E 03 MD-99 0.00E-01 1.05E 02 ~2.00E 01 0.00E-01 2.3BE 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 9.23E-03 1.33E-02 -1.30E-01 0.00E-01 2 39E-01 6.79E-03 4.00E-14

/~N RU-103 4.51E 00 0.00E-01 1.94E 00 0.00E-01 1.72E 01 0.00E-01 5.26E 02'

(_) RU-105 3.75E-01 0.00E-01 0.00E-01 1.48E-01 8.48E 00 0.00E-01 0.00E-01 4.85E 00 1 29E 02 0.00E-01 0.00E-01 2.29E 02 4.34E 03 RU-106 6 70E 01 AG-110M 9.48E-01 8.77E-01 5.21E-01 0.00E-01 1.72E 00 0.00E-01 3.58E O2 SB-124 7.87E 00 1.49E-01 3.12E 00 1.91E-02 0.00E-01 6.13E 00 2.23E 02 SB-125 5.03E 00 5.62E-02 1 20E 00 5 11E-03 0.00E-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 2.43E 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 3.7BE 03 4.60E 04 0.00E-01 5.55E 04 TE-129 3.01E 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 1.08E 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  ?.67E 00 TE-132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.39E 04 1.96E O2 0.00E-01 3.44E-02 l TE-134 3.10E 01 2.03E 01 1.25E 01 2 71E 01 I-129 1.19E 02 1.02E 02 3 35E 02 2.63E 05 2.19E 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 02 0.00E-01 5 70E 01 I-132 7.37E 00 1.97E 01 6.90E 00 6.90E O2 3.14E 01 0.00E-01 3.71E 00 1-133 5.16E 01 0.97E 01 2 74E 01 1.32E 04 1.57E 02 0.00E-01 8.06E 01 l I-134 3.85E 00 1.05E 01 3 74E 00 1.81E 02 1.66E 01 0.00E-01 9.12E-03 I J

I 1_17 ISSUE 1 REVISION 3 L--____ - -_ . - . - - _ _ - _ _ _ _ _ _ _ _ _ . _ _ _ -_. _ _ _ _ . -

BV_2 ODCM fN ' TABLE 1-.3-1 (Page 3) s

%s)1 A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE it (mrem /hr per pCi/ml)

NUCLDE BONE LIVER T-BODY THYRDID KIbNEY LONG GI-LLI I-135 1.61E 01 4.21E 01 1.55E 01 2.78E 03 6.76E 01 0.00E-01 4.76E 01 CS-134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04' 2.24E 04 CS-136 3.12E 04 1.23E 05 8.86E 04 0.00E-01 6.85E 04 9.39E 03 1 40E 04 CS-137 3.82E 05 5.22E 05 3.42E 05 0.00E-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 BA-140 2.03E 02 2.55E-01 1.33E 01 0.00E-01 8.66E-02 1 46E-01 4.18E O2

.BA-141 4.71E-01 3.56E-04 1.59E-02 0 00E-01 3.31E-04 2.02E-04 2.22E-10 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 0.00E-01 0.00E-01 0.00E-01 5.57E 03

_\-

.i 7-}g LA-142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E-01 2.5(T 01 CE-141 2.63E-02 1.7PE-02 2.02E-03 0.00E-01 8.26E-03 0.00E-01 6 80E 01 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 PR-143 5.54E-01 2.22E-01 2.75E-02 0 00E-01 1 28E-01 0.00E-01 2.43E 03 PR-144 1.81E-03 7.53E-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 02

)

1_18 ISSUE 1 )

REVISION 3

1 BV-2 ODCM 1.4 Liquid Radwaste System r)

(.,,/

The liquid radwaste system has the capability to control, collect, process, 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 system for processing.

6/89 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.

?

I 3

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1-19 ISSUE 1 REVISION 3

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.BV-2 ODCM

~2.0 Gaseous Effluents

<~# Technical Specifications applicable to dose rate apply to the site. The k,,) ' site dose rate is due -to the summation of release 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 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 LTechnical specifications for Beaver Valley require that the dose rate in unrestireted areas due to noble gas radionuclides in the gaseous effluent released from the site shall be limited to 5 500 mrem /yr to the total-body and to 5 3000 mrem /yr to the skin.

This section describes the methodology user' to maintain the release of noble gas radionuclides within the Technical specifications limits for the site and determines monitor setpoints for this unit.

The methodologies described in Sections 2.1.3 and 2.1.4 provide an alternate means of determining monitor alarm sespoints that may be used when an

.O analysis is performed prior to release.

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 1 (Alternates exists for these monitors), and five are located in Unit 2.

As previously 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 the setpoint presentations of the radiation monitoring systems of BVPS-1 and BVPS-2. First there is a conflict in setpoint terminology. k'here BVPS-1 uses HIGH and HIGH-HIGH the BVPS-2 equivalents are ALERT and HIGH. The second difference is that the BVPS-2 setpoint is presented in pCi/cc rather than CPM as in BVPS-1. This difference is due to software which applies a conversion factor to the raw data (CPM). The user is cautioned that the 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.

Setpoints determined on analysis prior to release will be correct for properly controlling dose rate but the indicated VCi/cc value may differ from the actual value.

O 2-1 ISSUE 1 REVISION 3 6- - ..-_____ - - - _ - _ - _ - _  !

BV-2 ODCM All effluent monitors specified herein have HIGH-HIGH (BV-1) or HIGH (BV-2) setpoints established at 30 percent of the site limit and except three

- (~ , 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 & 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-108B (Alt. GW-109 CH #5)

Unit 2, Containment Vent 99% (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 f- Unit 2, Decontamination Building Vent- 30% (HIGH) 0.3% (ALERT) 1( s) 2RMQ-RQ301B Unit 2, Condensate Polishing Building Vent 30% (HIGH) 0.6% (ALERT) 2HVL-RQ112B 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 site dose rate is less than 50% of the site limit when all monitors are below the HIGH (BV-1) and ALERT (BV-2) setpoints.

With all monitors below the normal HIGH-HIGH (BV-1) and HIGH (BV-2) setpoints, a combination of three HIGH (BV-1) or ALERT (BV-2) setpoint alarms indicate releases may have 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.

,,, \

.s 2-2 ISSUE 1 REVISION 3 l

L 1

l EV-2 ODCM

• From this condition any one monitor alarm would indicate the site dose

, rate limit may have been exceeded.

(

( ,) A 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 variations which result in radioactive releases greater than 50%

of the releases normally considered as continuous. Bctch releases from

.these sources during normal operation, including anticipated operational occurrences, are defined as those which occur for a total of 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> or less in a calendar year but not more than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> in any quarter. The batch relative concentration value has been calculated in accordance with the guidelines provided in NUREG-0324 for short-term release. If simultaneous batch and continuous release out of one vent occurs, use the lowest setpoint obtained according to the following Sections 2.1.1 through 2.1.4.

2.1.1 Setpoint Determination Based on a Calculated Mix for Ventilation Vent, Containment Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and Waste Gas Storage Vault Vent Releases In the table below, column one gives the calculated monitor count rate above background (C.R.) in net counts per minute and column two provides the equivalent monitor indication (D.V.) in net pCi/cc associated with the limiting annual dose rate for the Site (i.e., 500 mrem /yr whole body or 3000 mrem /yr beta skin). The HIGH alarm setpoint (HSP) in pCi/cc above

,-s, background, and the ALERT alarm setpoint (ASP) in pC1/cc above background

() for each vent and operational condition should be as follows:

pCi/cc Above Background 30% 10%

SITE SITE C.R. D.V. LIMIT LIMIT (NCPM) pCi/cc HSP ASP

• Continuous Release Via The Ventilation Vent 8 26E3 3.01E-4 9.04E-5 3.01E-5

• Patch Release of Containment Purge Via the Ventilation Vent 1.13E3 4.13E-5 1.24E-3 4.13E-6

• Continuous Release Via The Containment Vent 4.32E3 1.06E-4 3.17E-5 1.06E-5 Eatch Release of Containment  !

purge via the Containment Vent 2.09E3 4.05E-5 1.21E-5 4.05E-6 j l

1 2-3 ISSUE 1 REVISION 3 j l

w-___-_____

BV-2 ODCM uCilcc Above Background

!n.

~

I SITE 3 0".

SITE C.R. D.V. LIMIT LIMIT (NCP!Q pC1/cc HSP ASP >

Coctinuous Release via the Condensate Polishing Bldg.

Vent 2.89E4 1.61E-3 4.82E-4 9.63E-6 L

Continuous Release via the l Decontamination Building Vent 5.66E4 3.15E-3 9.44E-4 9.44E-6

• Continuous Release via the Waste Gas Storage Vault Vent 8.03E5 2.24E-2 6.71E-3 2.24E-5

• Alert Setpoint from Section 2.1, Fraction of Site Limiting Dose Rate.

The setpoints were determined using the following conditions:

• Source terms given in Table 2.1-1. These gaseous source terms were derived from Stone & Webster computer ccdes GASIBB (which is similar to the NRC Code GALE, NUREG-0017) and DRAGON 4 (for the containment vacuum pump sources). Table 2.1-1 does not include particulate and fodines, which are not used in site noble gas dose rate calculations. The 7s Containment Building Purge radionuclides mix was utilized for the purposes of determining an alarm setpoint for the Ventilation Vent on

[' ') the basis of the proximity of the contiguous areas. The Decontamination Building and Condensate Polishing Building ventilation exhaust are not expected to be radioactive. Ilowever, for purposes of determining an alarm setpoint, it is conservatively assumed that Xe-133 is in the ventilation exhaust at concentrations that would result in the appropriate dose rate limits. The Waste Gas Storage Vault ventilation exhaust is also not normally radioactive, llowever, the monitor alarm setpoint is based on the assumption that the ventilation exhaust radionuclides spectrum is similar to the gaseous inventory in the system housed by the waste gas storage vault. This spectrum is listed in Table 2.1-1 under radioccti gasecus waste system.

• Unsite meteorological data for the period January 1, 1976 through December 31, 1980.

• Discharge flow rate of 23,700 cfm for the Ventilation Vent (Continuous)

• Discharge flow rate of 53,700 cfm for the Ventilation Vent (Batch release of containment purge).

• Discharge flow rate of 59,000 cfm for the Containment Vent (Both continuous and batch release of containment purge).

I t%

~,

2-4 ISSUE 1 REVISION 3 l

L. -_ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

BV-2 ODCM Discharge flow rate of 30,536 cfm for the Condensate Polishing Building j Vent.

• Discharge flow rate of 12,400 cfm for the Decontamination Building t )

Vent.

Discharge flow rate of 2,000 cfm for the Waste Gas Storage Vault Vent.

The calculation method given in Sections 2.1.1.1 through 2.1.1.7 was used to l derive the high-high alarm setpoints for the Ventilation Vent Gas Monitor l (2HVS-RQ 101B), Elevated Release Vent Gas Monitor (2HVS*RQ 109B), Condensate l Polishing Building Vent Gas Monitor (2HVL-RQ 112B), Decontamination Building Vent Gas Monitor (2RMQ-RQ 301B), and Waste Gas Storage Vault Vent Gas Monitor (2RMQ-RQ 303B) during the following operational conditions:

Continuous release via the Ventilation Vent

• Continuous release via the Ccatainment Vent

• Batch release of containment purge via the Ventilation Vent

• Batch release of containment purge via the Containment Vent

• Continuous release via the Condensate Polishing Building Ventilation Vent exhaust

• Continuous release via the Decontamination Building Ventilation Vent exhaust 7-~

(~-

• Continuous release via the Waste Gas Storage Vault Ventilation Vent exhaust 2.1.1.1 The " mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:

a. The gaseous source terms that are representative of the " mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flowrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent. Gaseous source terms can be obtained from Table 2.1-1 and Section 2.1.1.

b. The fraction of the total radios:tivity in the geseous effluent comprised of noble gas radionuclides "1" (Sj ) for each individual noble gas radionuclides in the gaseous effluent was determined by:

A.

S.=

1 I A.

(2.1-1) 1 i

l l

O 2-5 ISSUE 1 l REVISION 3

BV-2 ODCM where:

Ag = The radioactivity concentration of noble gas radionuclides "i" (fwj in the gaseous effluent from Table 2.1-1 and Section 2.1.1.

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

500 Qt *

(2'I'2)

(X/Q) I K1 S1 i

where:

(X/Q) y = The- highest calculated annual average relative concentration s

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)" = The short term 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 A-3 of Appendix A.

. n)

(

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

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

= 9.24E-5 sec/m for continuous releases 3

(X/q)'# = The short term relative concentration of effluents released via the containment 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/m3 for batch release of containment purge (X/Q)cp = of The highest calculated annual average relative concentration effluents released via the Condensate Polishing Building l Vent for any area at or beyond the unrestricted area boundary I for all sectors (sec/m') from Table 2.2-10.

= 7.35 E-5 sec/m2 for continuous releases.

I 1

l O 2-6 ISSUE 1 REVISION 3 l

l L: - . _ _ _ _ - .

i

BV-2 ODCM

-(X/Q)dy = The . highest calculated annual average re'.ative concentration of effluents released via the Decontamination Building Vent

, rm for- any area at or beyond the unrestricted area boundary for

()- all sectors (sec/m') from Table 2.2-8.

= 9.24 E-5 sec/m' for continuous releases.

-(X/Q)# = The' highest calculated annual average relative concentration of effluents released via the Waste Gas Storage Vault Vent-for any area at or beyond the unrestricted area boundary for all sectors (sec/m a) from Table 2.2-9.

= 9.24E-5 sec/m' for continuous releases.

K g

= The 1ctr.1 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).

2.1.1.3 h.wrsalsodeterminedbasedupontheskinexposurelimitby:

t 3000 gt " (X/Q) I (L 1 + 1.1M ) Sg (2.1-3) f 1

'I where:

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

Mg = The air dose factor due to gamma emissions from noble gas radionuclides "i" (mrad / year /pCi/m') 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 acceptable release rate in pCi/sec of noble gas radionuclides "i" in the gaseous effluent (h)foreachnoblegasradionuclide g in the gaseous effluent was determined by:

h=Sghg g (2.1-4) l O 2-7 ISSUE 1 REVISION 3 i

l i

l l

b_. . _ _ _ _ _ _ _ _ _ . _ _ . _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _

-BV-2 ODCM NOTE: Use the lower of the.Q values obtained in Section 2.1.1.2 and 2.1.1.3

- ( ,)

-2.1.1.5. The maximum acceptable. radioactivity ~ concentration' pCi/cc of noble gas radionuclides "1" in.the gaseous effluent (C g) for each individual noble gas radionuclides in the gaseous effluent was determined by:

C = 2.12E-3h i (2.1-5) i F where:

F = The maximum acceptable effluent flow rate at the point of-release (cfm) as listed in Section 2.1.1.

2.12E-3 = Unit conversion factor (60 sec/ min x 3.53 E-5 ft*/cc).

'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. = I Cf Eg (2.1-6) i where:

Eg = The detection efficiency of the monitor for noble gas radionuclides "i" (cpm /pC1/cc) from Table 2.1-2.

.( n) 2.1.1.7 The monitor alarm setpoints above background were . determined as follows;

a. The monitor HIGH alarm HSP setpoint above background (in pCi/cc) was detsrmined by:

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

E i ave

b. The monitor ALERT alarm setpoint ASP above background (in pCi/cc) was determined by:

ASP = FR x C.R. (2.1-8)

E i ave where:

FR = Fraction of limiting dose rate for the respective radiation monitor (from Sectf.on 2.1).

E g gy, = The C.R. of equation (2.1-6) divided by the sum of the C for f

the respective mix.

REVISION 3

. i

l. _ _. _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _

BV-2 ODCM 2.1.2 Setpoint Determination Based on a Calculated Mix for Process Vent Releases (Elevated Releases)

,n

'( ) , The calculated monitor count rate' above background (C.R.), in nepm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are as follows:

30% 10%

SITE SITE PRIMARY- LIMIT LIMIT MONITOR C.R. HHSP HSP Continuous Release GW-108B 3.83E7 1.15E7 3.83E6 Batch Release of GW-106B 2.11E5 6.33E4 2.11E4 Decay Tanks Batch Release of GW-108B 5.38E6 1.16E6 5.38E5 Containment Purge When the primary nonitor is out of service and technical specifications can be met for the respective alternate monitor, the following setpoints may be utilized:

30% 10%

SITE SITE

,- ALTERNATE LIMIT LIMIT 4 MONITOR C.R. HHSP HSP x_-

• Continuous Release GW-109 CHANNEL 5 2.20E7 6.61E6 2.20E6

• Batch Release of CW-109 Decay Tanks CHANNEL 5 7.75E6 '2.32E6 7.75E5

• Batch Release of GW-109 Containment Purge CHANNEL 5 7.34E6 2.20E6 7.34E5 The setpoints were determined using 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 fo21owing 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 2.1.2.1 The " mix" (noble gases and composition) of the gaseous effluent was determined as follows:

2-9 ISSUE 1 REVISION 3 l

l t _ _ _ _ _ - - _

7;. .

4- i

'BV-2 ODCS!

k

~ a. The gaseousL s,urce t'erms that are representative of the " mix" of the  !

= gaseous effluet.t- were. evaluated. Gaseous . source terms are the radioactivity 'of the noble gases radionuclides in the effluent. The f'j's yy gaseous source. terms can be obtained from Table 2.1-1.

b. The fraction of the total radioactivity .in the gaseous' effluent comprise'd by noble gas radionuclides "i" (S 1

) for each. individual noble gas radionuclides in the gaseous effluent was calculated by:

Ag Sg = I A (2.1-9).

L i where:

= The total radioactivity or - radioactivity concenaa. ion of.

A{ 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:

y,IV500 t

g gS (2.1-10)

(~>g

( ' I where:

V = The constant for noble gas radionuclides "i" accounting for-f 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 I [L (X/Q) y + 1.1Bg]Sg (2.1-11) where:

L = The ' skin dose factor due to beta emissions from noble gas I

radionuclides "i" (mrem / year /pCi/m') from Table 2.2-11. l 4

(ww h 2-10 ISSUE 1 REVISION 3

I t

I

BV-2 ODCt!

l- = The highest calculated an.ual 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

(/ (sec/m') from Tabin 2.2-6.

= 2.31E-6 sec/m' (X/q)PV S 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 8) from Table A-5 of Appendix A.

= 1.07E-5 sec/m'

% B f

= The' constant for long term ~ releases (greater than 500 hrs / year) for noble gas radionuclides "i" 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 acceptable release rate (in pCi/sec) of noble gas radionuclides "1" in the gaseous effluent (h)foreachindividualnoble g gas radionuclides in the gaseous effluent was determined by:

h=Sghg g (2.1-12)

/O V (NOTE: Use the lower of the h values obtained in Section 2.1.2.2 and 2.1.2.3) 2.1.2.5.. The maximum acceptable radioactivity concentration (in pCi/cc) of noble gas radionuclides "1"'in the gaseous effluent (C g

) for each individual noble gas radionuclides in the gaseous effluent was determined by:

C =

i (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) 2-11 ISSUE 1 REVISION 3

BV-2 ODCM 2.1.2.6 The calculated mcnitor count rate-(in nepm) above background. attributed to the noble gas radionuclides (C.R.) was determined by:

(_,/ C.R. = I C E (2.1-14) where:

E g

= The detection efficiency of the monitor for noble gas 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 (PSP) above background (in ncpm) was determined by:

HSP = 0.10 C.R. (2.1-16) 2.1.3 Setpoint Determination Based on Analysis Prior to Release (Ground Releases)

When the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method described below may

()

f-s be used in lieu of that set forth in Section 2.1.1.

results of sample analysis are used to determine the appropriate nuclide In this case, the mix. This calculational method applies when determining the setpoint for the maximum acceptable discharge flow rate and . the associated high alarm setpoint based on respective vent flow rate during the following operational conditions:

• Batch release of containment purge via the Ventilation Vent

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

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

A U 2-12 ISSUE 1 REVISION 3

p BV-2 ODCM

'1.06 S.T f , (X/q) I K g C (2.1-17)

/~ i

' N)N -

where:

1.06 = 500 mrea/yr x 2.12 E-3 500 mrem /yr = dose rate limit, whole body exposure 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 setpoint rules of Section 2.1. To exceed 60% of the site limit from one release point, the remaining release point 1imits- must be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit.

T = Maximum' value for T is 16 based on the limiting restriction in TS 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 4)

(X/q) " = The highest calculated short term relative concentration of c effluents released via the Ventilation Vent for any area at i or beyond the unrestricted area boundary for all sectors (sec/m3 ) from Table A-3 of Appendix A.

= 3.32E-4 sec/m 3 (X/q)## = The highest calculated short term relative concentration of effluents released via the Containment Vent for areas at or beyond the unrestricted area boundary for all sectors (sec/m') from Table A-2 of Appendix A.

= 3.08E-4 sec/m 8  !

K,^ = The total whole body dose factor due to gamma emissions from noble gas radionuclides "1" (mrem / year /pCi/m') from Table 2.2-11.

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

O 2-13 ISSUE 1 REVISION 3

b BV-2.ODCM 6.36S T 1

l f = (X/q) I (L. + 1.1M.) C. (2.1-18)

'l 1 1 L  ;\ i

[ Y.

where:

6.36 = 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 ft3 /cc)

L.* = The skin dose factor due to beta emissions from noble gas radionuclides "i" (mrem / year /pCi/m 3

) from Table 2.2-11.

M.

= The air- dose factor due to. gamma emissions from noble gas radionuclides "i" (mrad / year /pC1/m 3

) 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 calculated (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 alarm setpoint (HSP) above background (net pCi/cc) attributed to the noble gas radionuclides is determined by:

f I C. E

. 1 i HSP = ( ~

}

F' E lae where:

f = The maximum acceptable containment purge 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.

= 23,700 cfm Ventilation Vent.

= 59,000 cfm Containment Vent Cg = The undiluted radioactivity concentration of noble gas radionuclides "i" in the gaseous source (pCi/cc) as determined by the analysis of the gas to be released.

E = The detection efficiency of the monitor for noble gas f

radionuclides "1" (cpm /pCi/cc) from Table 2.1-2.

2-14 ISSUE 1 REVISION 3

l' b BV-2 ODCM I

E. = The C.R. of equation (2-.1-6) divided by the sum of the C. for i an

• E the respective mix.

L ,

(. NOTE: To enable maintaining a constant conversion factor from CPM to pCi/cc in the Digital Radiation Monitoring System software, the

" calculated mix" is used rather than the analysis mix to calculate y, above. This does not cause any change in the function of Eg the monitor setpoint to properly control dose rate. However the monitor indicated VCi/cc value may differ from the actual value.

b. When a HIGH setpoint has been calculated according to this section, the monitor alert alarm setpoint (ASP) above background (net pCi/cc) is determined as follows:

HSP x 0.33 = ASP (2.1-20) l6/89 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 G,scous Waste Gas Monitor (GW-108B) or alternate (GW-109 CH #5) during the following operational conditions:

• Continuous release via the Process Vent

,c3

\)

• 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 acceptable discharge flow rate for the release from the Process Vent fer the analyzed mix.

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

o  !

.\

2 15 ISSUE 1 REVISION 3 l

l 4

l

BV-2 CDCM 1.06-S f;. g,IV C g (2.1-21).

i

("\

V where:

1.06 = 500. mrem /yr x 2.12 E-3 l 500 mrem /yr = dose rate limit, whole body exposure 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. om release point' under -the alarm setpoint 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 l site dose rate Ifmit.

Vg = The constant for noble gas radionuclides "1" accounting for the gamma radiation from the elevated plume (mrem / year /pCi/sec) from Table 2.2-12.

C = The undiluted radioactivity concentration o f. noble gas f

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

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

6.36 S f

I [LflX/Q) + 1.1B j C g f

(2.1-22) 1 where:

6.36 = 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 ft'/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 annus1 average relative j (X/Q)E# concentration of offluents released via the Process Vent for any area at or beyond the unrestricted area boundary for all ,

sectors (sec/m') from Table 2.2-6.  !

l

= 2.31E-6 sec/m'.

l 1

( -

2-16 ISSUE 1 REVISION 3

BV-2 ODCM

.(X/q)pv ='The 'short term relative concentration of effluents releaced via the Process Vent- for any area' at or beyond- the-r7 unrestricted area boundary for all sectors (sec/m') from h )? .- Table A-5 of Appendix "A"

= 1.07E-5 sec/m' B

y = The constant for long-term' releases (greater than 500' hrs / year) for noble gas radionuclides "i" accounting- for the gamma radiation from the ' elevated finite plume (mrad / year /pCi/sec) from Table 2.2-12.

c. Select the smaller of the calculated f-values based on the whole body exposure limit (Section 2.1.4.1.a) and based on the skin exposure limit (Section 2.1.4.1.b). The actual _ discharge flow rate in (cfm)-must be maintained at or below this f value.

2.1.4.2 The monitor alarm setpoints above background are determined as follows:

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

E i i HHSP F. (2.1-23) where:

(% = The maximum acceptable gaseous discharge flow rate (cfm) t,

'~) .f 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)

Cg = 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. = The detection efficiency of the respective monitor GW-108B or 1

GW-109 CH 5 for noble gas radionuclides "i" (cpm /pci/cc) from Table 2.1-2.

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

HHSP = 0.33 x HSP (2.1-24) l6/89 O

2-17 ISSUE 1 REVISION 3

BV-2 ODCM REFERENCES f\ (1) Gaseous Effluent Monitor Efficiency Data; Calculation Packages ERS-SFL - (f.

.031'and:ERS-SFL-86-026.

(2)-Unit 1/ Unit- 2 0DCM ' Gaseous Alarn Setpoint' Determinations;. Calculation Package ERS-HHM-87-014.

, .(3)." Beaver Valley Power Station, Unit 2 FSAR," Table'11.3-2.

.(4) BVPS-1 and BVPS-2 ODCM.T Factor-Justification; Calculation Package ERS-ATL-87-026.

. jG.

V

.C) 2-18 ISSUE 1 REVISION 3 i

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4 BV-2 ODCM

'2.2 Compliance with 10 CPR 20 (Gaseous)

~x 2.2.1' Noble Gases

&j The dose rateLin unrestricted areas resulting from noble gas effluents from the site is limited'to 500 mrem /yr to the total body and 3,000 mrem /yr to the skin. Site gaseous effluents are the total of Beaver Valley. Unit-1 and i Unit 2 specific ground releases and a shared elevated release, the Process Vent. Based upon NUREG-0133 the following basic expressions are used to show compliance with BVTS 3.11.2.1.a.

E[Vh,+K(X/Q)y fg f h ] <fy 500 mrem /yr (2.2-1) i I

f L(576)s+

i Bf ] h g, + [Lf + 1.1M f](576)v h fv 5 3000 mrem /yr (2.2-2)

.l where:

K = the total body dose factor due to gamma emmissions for each I

identified noble gas radionuclides "i", mrem / year /pCi/m'.

L I

= the skin dose factor due to beta emissions for each identified noble gas radionuclides "i", mrem / year /pCi/m'.

7- ; Mg = the air dose factor due to gamma emissions for each s_

identified noble gas radionuclides "i", mrad / year /pCi/m'.

V.

= the constant for each identified noble gas radionuclides "i" accounting for the gamma radiation from the elevated finite plume, mrem / year /pC1/sec.

B. = the constant for long-term releases (greater than 500 hrs / year) for each identified noble gas radionuclides "i" 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 of the photon of interest, mrem / mrad.

Q 3 = the release rate of noble ges radionuclides "i" in gaseous effluents from free-standing stack, pC1/sec.

Q fy = the release rate of noble gas radionuclides "1" in gaseous effluents from all vent releases, pCi/sec.

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

A 2-21 ISSUE 1 REVISION 3

h L

l.

BV-2 ODCM l the highest calculated annual average relative concentration

, _ _ _(X/Q)"'=

! cri for any area at or beyond the unrestricted area boundary for

- (,,,[ ground level releases (sec/m').

At the Beaver Valley Site gaseous releases may occur from:

1. the Containment Vents atop the containment domes

2. the Ventilation Vents atop 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 BVPS-2 Decontamination Building Vent

7. the BVPS-2 Waste Gas Storage Vault Vent Effluent from the Containment Vents are assumed ground level in nature. At BVPS-1 the source of these releases is the Supplementary Leak Collection and Release System (SLCRS) . At BVPS-2 the source of these releases is normal auxiliary building ventilation. It is also possible to release containment purges from these vents. The Ventilation Vent Releases are ground level in nature. ,t BVPS-1 the sources of these releases are containment purges and A

gs normal auxiliary building ventilation. At BVPS-2 the sources of these

(',) releases are containment purges and contiguous areas ventilation. The Turbine Building Vents releases are ground level in nature and the source of these releases are the turbine building ventilation. Release points 4, 5, 6, and 7 above are not normally radioactive release points. The Process Vent releases are elevated and the sources of these releases are the main ,

condenser 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.

1 O 2-22 ISSUE 1 REVISION 3

_-__ - - _ _ - - _ -_m

H f e BV-2 ODCM' For:the total body dose:

f( . . . . .

$.j IVQ gf +IKg g [(X/Q)cv Q .+.(X/Q) Q + (X/Q) y Q + (X/Q) y Q +

+ .+-

(X/Q)vv ih. vv2

+(576)t# h'N2 i (7Q)CP1 92 h +(7Q)dv h dv2 i

, (X/Q) y h ) s 500 mrem /yr .(2.2-3)

For.the skin dose:

+ @)yyh.

I f[L[(576)py+ 1.1B3 ] h g '+ If [Lg + 1.1M g1 -[(576),y h g g

+

pv cv1 vv1-

+

(X/Q)*# htv1 + (X/Q)'# h I cv2.

+(576)"h I vv2 +(5/6)*# Q I tv2 + (5[d)CPi cp2- h

.(X/Q)dy O i

• dv2 wv2 py

'(J 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 evi Vent, UC1/sec.

9 Qg = release rate of radionuclides "1" from the BVPS-2 Containment cv2 Vent, pCi/sec.

Q *.

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

Qg = 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.

-k 2-23 ISSUE 1 REVISION 3

U BV-2 ODCM o .

L  !

'Q g = release rate -of rad'ionuclide."i" from~the BVPS-2' Condensate W

k)p .cp2 Polishing Building Vent, pCi/sec.

L Qg = release: rate of radionuclido "i" from the BVPS-2 Lg dv2 Decontamination Building _ Vent, pCi/sec.

!'? .

Q- g ' = release rate of radionuclides "i" from the BVPS-2-Waste Gas wv2 Storage Vault Vent, pCi/sec.

(X/Q)pv = highest calculated annual average relative concentration for releases from the Process Vent, sec/m'.

(X/Q)'" = highest calculated annual average relative concentration for-releases from the Containment Vent, sec/m'.

(X/Q)## = highest calculated annual average relative concentration for releases from the Ventilation Vent, sec/m'.

.(X/Q)*V = highest calculated annual average relative concentration for:

- releases for the Turbine Building Vent, sec/m'.

(X[Q)cp = highest calculated annual average relative concentration for releases-for the. Condensate Polishing Building Vent, sec/m'.

(X/Q)dv = highest - calculated annual average relative concentration for releases for the Decontamination Building Vent, sec/m'.

(X/Q),y = highest calculated annual average relative concentration.for releases for the Waste Gas Storage Vault Vent, sec/m'.

. Note that the release rate for a containment purge is based on an averaged release rate in pCi/sec for the entire purge (not to exceed 960 min.. in accordance with TS 3.11.2.1).

All other terms remain the same as those defined previously.

For the site, four potential modes of reler.se are possible. The release modes identify the various combinations of soarces of radioactivity and their release points which are used to determine the controlling locations.

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

O 2-24 ISSUE 1 REVISION 3

[f +

i ,

BV-2 ODCM

'For the total body:

r^y ' E V Qggg.

pv

+IKg g [9.2E-5 Qg :

cv1

'+ 1.03E-A Q g vv1

+ 7.35E-5 Q g + 9.24E-5 Q f cv2 O

.(j. tv1 1' .. . .. . . .

1.03E-4 Q g + 7.35E-5 Q g

+ 9.24E-5 Q g + 9.24E-5 Q g + 7.35E-5'Qg . ]

vv2 tv2 dv2 wv2 cp2 i' 5 500 mrem /yr (2.2-5)

For the skin:

If [7.0E-10 Lg + 1.1B g] Qg '+ I [L + 1.1M ]g [9.24E-5 Q g + 1.03E-4 Q g +

pv cv1 vv1 7.35E-5 Q g. + M4 g tv1 cv2 vv2 tv2 dv2 9.24E-5 Q g + 7.35E-5 Q ] $ 3000 mrem /yr ;2.2-6)

'For the re. ... Mode 4, the controlling location is 0.75 miles N. Inserting the appropriate X/Q's from Tables 2.2-4 through 2.2-10 for this location, Expressions 2.2-3 and 2.2-4 become:

C y\ For the total body:

IVQ jgg +IKg g [3.95E-6 Qg + 4.99E-6 Q g + 4 26E-6 Q g + 3.95E-6 Q g +

pv cv1 vv1 tv1 cv2 4.99E-6 Q + 4.26E-6 Q g + 3.95E-6 Q g + 3.95E-6 Q g + 4.26E-6 Q g ]

vv2 tv2 dv2 wv2 cp2 5 500 mrem /yr (2.2-7) .i For the skin:

I g.[2.31s-6 Lg + 1.1B g] Qg +Ig [L g + 1.1M ] [3.95E-6 Q f

+ 4.99E-6 Q g + i pv cv1 vv1 ,

3.95E-6 Q g + 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 inrem/yr (2.2-8) wv cp 2-25 ISSUE 1 REVISION 3

BV-2 ODCM The determination of controlling location. for implementation 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 modes 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 si 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 g-)s

(_ if applicable-for BVPS-2, Decontamination Building Vent, Waste Gas Storage Vault Vent, and the Condensate Polishing Building Vent release points to the special 11ocations 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 I 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 C is contribution. From these results, the distance and sector associated with the highest calculated site boundary dose were selected as the controlling location.

For Modes 1, 2, and 3, the controlling location is 0.35 miles NW. In Mode 1, the dominant release is the auxiliary building ventilation (Ventilation Vent in Unit 1 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.  ;

i' l

l 2-26 ISSUE 1 REVISION 3 l

L L__ _ __--__

q.

BV-2 ODCM For release .tlode 4 .a similar evaluation was performed.' Long-term annual' average X/Q values were calculated at_ the mid point of the- 10 standard p distances listed in Tables 2 2-4 through 2.2-10. In that a simultaneous, V ground level release cculd contribute to the doso 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 controlling receptor locations are presently inhabited.

l~

L 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, 1

~1 Revision 1, were multiplied by 1E6 to convert picoeuries to microcuries' for use .in Table.2.2-11.

Values for Vg and Bf for 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 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 f., calculated from the follcwing relation:

K III jk li"a 1 i " "Fd 3 I "3 (* )

l 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 mrad) (radians) (m') (transformation) 16 sectors sec(Mev)(Ci) 2n radians 1E-6 Ci 3.15E7 see pCi yr

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

t 2-27 ISSUE 1 REVISION 3 l

e_________________

~

BV-2 CDCM r

d.

= the distance from the release point to the receptor' location, -

meters

\ ,y.

l the mean wind speed assigned to the "j" th wind speed class,

~

u =

meters /sec.

f jk

= the joint frequency of occurrence of the "j" th wind speed class and kth stability class (dimensionless);

A g

= the number of photons of energy corresponding to the "1" th energy group emitted per transformation of the "i" th radionuclides, number / transformation.

E = the energy assigned to the Ith energy group, Mev.

f 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:

V = 1.1 K III 'jk 11"eA 1 e'"T d f jk1 q (2.2-10) where:

g)

('_

p = the tissue energy absorption coefficient for photons of T 2 energy E y, cm /gm.

T = the tissue density thickness taken to represent the 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 (Ti > 8 Day)

The dose rate in unrestricted areas resulting from tha of inhalation of I-131, tritium, and all radionur_lides in particulate form (excluding C-14) with half lives greater than 8 days released in gaseous effluents from the site shall be limited to 1,500 mrem /yr to any organ. Based upon NUREG-0133, 6/89 the following basic expression is used to show compliance with BVTS 3.11.2.1.b:

IPf f7[G/Q)s is +

)v iv l ' ****IY# ( '

~)

i o 2-28 ISSUE 1 REVISION 3

y l0 .

l BV-2 ODCM p.

1 L 'where:

P = dose parameter for . any organ T .for each identified h() radionuclides "i", mrem /yr per pCi/m';

Q, g

= the release . rate of radionuclides "i", in gaseous effluents from elevated releases, pCi/sec.

Qa;v

= the release rate of radionuclides "i", in gaseous offluents from ground level releases, pCi/sec.

l (X/Q)s = the highest calculated annual average relative concentration H at the unrestricted area boundary for elevated releases, sec/m';.

(X/Q)y = the highest calculated annual average relative concentration at the unrestricted area boundary for ground level releases, sec/m';

-Note: The dispersion paremeters specified in Section 2.2.2 are l 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.

1, IPg h [(X/Q)py h g +(7Q)cv i " *" I " I p cv1 vv1 tv1 cv2 V.

+ (X/Q)yy Q i + + /I dv Oi

. + G/Q)tv 0 1 *2 }CP i cp2 dv2 wv2

< 1500 mrem /yr (2.2-12)

I where:

1 (X/Q)PV =releases highest from calculated annual average relative concentration for the Process Vent, sec/m';

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

releases from the Containment Vents, sec/m';.

(X/Q)" = highest calculated annual average relative concentration for releases from the Ventilation Vents, sec/m';

(X/Q)*# = highest calculated annual average relative concentration for releases from the Turbine Building Vents, sec/m';

(X/Q)CP = highest calculated annual average relative concentration for releases from the BVPS-2 Condensate Polishing Building Vent, l q sec/m';

1 -V l 2-29 ISSUE 1 i

REVISION 3 l

l w _:_-______-_

f BV-2 ODCM L

n , ~

p<

(X/Q)dj = highest calculated annual' average relative concentration for f-~y1 releases from the BVPS-2 Decontamination Building Vent,

(>f sec/m';

L

' (X/Q)"Y = highest calculated annual average relative concentration for release 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; Qj = long-term release rste of radionuclides "i" from the BVPS-1 cv1 Containment Vent, pCi/sec; Qg = long-term release rate of radionuclides "i" from the BVPS-2 cv2 Containment Vent, VCi/sec; Q*.

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

= long-term release rate of radionuclides "i" from the BVPS-1 tv1 Turbine Building Vent, pC1/sec; Qg = long-term release rate of radionuclides "i" from the BVPS-2 tv2 Turbine Building Vent, pC1/sec; Qg = long-term- release rate of radionuclides "i" from the cp2 Condensate Polishing Building Vent, pCi/sec; Qg = long-term release . rate of radionuclides "1" from the dv2 Decontamination Building Vent, pCi/sec; Q3 = long-term release rate of radionuclides "i" from the Waste Gas wv2 Storage Vault Vent, pCi/sec;_

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 I 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.

O 2-30 ISSUE 1 REVISION 3

EV-2 DDCM Values of the organ dose parameters, Pg , were calculated using methodology t

_- o given in NUREG-0133. For the child age group, the_ following equation was

~ R Qg used for all nuclides. The Pg , values are presented in Table 2.2-13.

t P = 3.7E9 DFA g (2.2-13) where:

3.7E9 = breathing rate of child (3,700 m*/yr) x unit conversion factor (IE6 pCi/'pci).

DFA. =- the organ inhalation dose factor for a child from Table 6 of 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 gg [7-.00E-10 Q g + 9.24E-5 Q g + 1.03E-4 Q j + 7.35E-5 O g + 9.24E-5 t pv cv1 vv1 tv1 hg + 1.03E-4h g +7.35E-5h g +7.35E-5h g +9.24E-5h g + 9.24E-5 cv2 vv2 tv2 cp2 dv2 Q $ 1500 mrem /yr (2.2-14)

The determination of the controlling lor.ation 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 parametcrs into Expression 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 to determine the controlling location.

The P g values are presented in Table 2.2-13.

t The X/Q values in Expression 2.2-14 were obtained from Tables 2.2-4 through 2.2-10.

t -

l 2-31 ISSUE 1 REVISION 3 t ____ _ __ _ _

1 BV-2 ODCM TABLE 2.2-1 b MODES OF_ GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS

.FOR IMPLEMENTATION OF 10 CFR'20 AND 10 CFR 50-e O"i .

Release Point Mode'l Mode 2 Mode 3 Mode 4 h

BVPS-1 BVPS-2 8 Main Cond. Air Same as Same as Same as Process Vent (py) Ejector, Waste- ;iode.1- Mode 1 Mode 1 and.

Gas, Contain- , Containment' ment Vacuum 2 Purge BVPSti Ventilation 2' -Aux. Bldg. Containment' Same as Same as Vent. . (vvi) - . Ventilation Purge 8 Mode 1 Mode 1 BVPS-l' 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. 2 Turbine Bldg Same as Same as Same as Vent (tvi):

Exhaust

• Mode 1*- Mode 1* . Mode 1*'

BVPS-2 Ventilation 2

_ 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 Pu'rge'~

BVPS-2 Turbine Bldg.2 Turbine Bldg Same as 1same as Same as Vent-(tv2) Exhaust

• Mode 1* Mode 1* Mode 1*

BVPS-2' Condensate * * * *

• Polishing' Bldg. Veno (cp2).

.BVPS-2' Decontamination 2 * * *

• Bldg. Vent (dv2)

-BVPS-2 Waste Gas * * * *

• Storage Vault Vent (wv2)

• Not. nornwily a _ radioactive relesse 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

• Continuous elevated meteorology is applicable 8

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

as Mode 1.

2-32 ISSUE 1 REVISION 3

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t - 684 9489 7681 LS ait 002 9681 1 084 I E ene -

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BV-2 ODC11 TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES BEAVER VALLEY SITE

• y I B l2 V 3 3 B

I, Total Body Camma Air- Total Body.

i Camma Air i Dose Rate Dose Rate Dose Rate Dose Rate Noble. Gas arem/yr mrad /yr' mrem /yr mrad /yr '

Radionuclides pCi/sec pC1/sec pCi/sec' pCi/see 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 2.19E-3 Kr-88 1.39E-3 2.09E-3 4.09E-3 6.16E-3 Kr-89 7.99E 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 1.542-4 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

.9.66E-5 1.46E-4 Xe-137 6.00E-5 9.05E-5

.- Xe-138 8.11E-4 1.22E-3 2.22E-3 3.34E-3 Ar-41 1.02E-3 1.53E-3 2.6BE-3 4.02E-3

• 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, and 3 of Sectien'2.2.1. (10CFR20)

'2 Bg. values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1. (10CFR50)

- Vg and B values to implement Mode 4 of Section 2.2.1. (10CFR20) and to .

implement monitor setpoint determinations of Section 2.'.2 and 2.1 4 O

2-43 ISSUE 1 REVISION 3

BV-2 00CM Table 2.2-13 0 P VALUESFORACHILDFORTHEEEAVERVALLEYSlfE 17 (area /rr per uCi/c: meter) -

Nuclide- Bone- Liver f. Body Thyroid Eidner- Lung GI-LLI 1H-3 0.00b00 1.12b O3 1.12bO3 1.12bO3 1.12b O3 1.12b O3 1.12bO3 2P 2.60D061.14b059.88b040.00D000.00D000.00D004.22904 jk .

3Cr-51 0.00b00 0.00D001.54bO2 8.55b012.43b011.70D041.08bO3 4Mn 0.00b004.29b049.51bO30.00D001.00bO(1.58b062.29D04 5Fe-59 ' 2.07b04 3.34b041.67b04 0.00D00 0.00D001.27b06 7.07b04 6Co-57 0.00b009.03bO21.07t+030.00D000.00b005.07b051.32b04 700 0.00b001.77bO33.16bO30.00D000.00D001.11b063.44b04 ~

8 00-60 ' ' O.00b001.31b04 2.26b04 0.00b00 0.00b00 (.07b06 9.62D04 9In-65 4.25b041.13b05 7.03b04 0.00D00 7.14b04 9.95b051.63b04 10lb-86 0.00b001.98b051.1(b05 0.00b00 0.00b00 0.00b00 7.99D03 11Sr-89 5.99b05 0.00b001.72b04 0.00D00 0.00b00 2.16bo61.67b05 12Sr-90 -1.01bO8 0.00D00 6.44b06 0.00b00 0.00D001.48bO7 3.43b05 13T-91 9.14b050.00b002.44b040.00b000.00 BOO 2.63b061.84b05 14Zr-95 1.90D054.16b043.70D040.00D005.96b042.23b066.11b04 15lb-95 2.35bO( 9.1BbO3 6.55bO3 0.00D00 8.62bO3 6.14b05 3.70D04 16Rb-97 4.29E-017.70E-02 3.60bO2 0.00b00 8.55E-02 3.42bO3 2.78b04 6/89 17Mo-99 0.00b00 1.72D 02 4.26b01 0.00D 00 3.92 D02 1.35 b 05 1.27b 05 18fe-99: 1.78E-033,48bO35.77E-020.00D005.07E-029.51bO24.81bO3 19Rn103 2.79b030.00b001.07bO30.00D007.03bO36.62b054.4Bb04 20 Ru-106 1.36b050.00D001.69b040.00D001.84b051.43bO74.29b05 21 Ag-110s 1.69b041.14b04 9.1(bO3 0.00b00 2.12b04 5.48b061.00b05 22Sb-124 5.74b047.40bO22.00D041.26bO20.00D003.2(b061.6(b05 23Sb-125 9.84b047.59b022.07b049.10b010.00b002.32b064.03b04 24 fe-127a 2.49D04 8.55bO3 3.02bO3 6.07bO3 6.36b041.4Bb06 7.11b04 25 fe-129s 1.92b04 6.85 bO3 3.04bO3 6.33b O3 5.03 b04 1.76 b 06 1 & b 05 261-131 4.81b04 4.81b04 2.73b041.62D07 7.88b04 0.00D00 2.84b03 27 b133 1.66b042.03D047.70D033.85b063.3BbO(0.00b005.4BbO3 28Ce-134 6.51b051.01b06 2.25b05 0.00b00 3.30b051.21b05 3.85bO3 29Ce-136 6.51b041.71b051.16b05 0.00D00 9.55b041.45b04 4.1BbO3 ll 30Ce-137 9.07b05 8.25b051.28b05 0.00b00 2.82b051.04b05 3.62bO3 l 31Ba-140 7.40b04 6.46b014.33bO3 0.00b00 2.11b011.74b061.02b05 32La-140 6.4(b O2 2.25 b O2 7.55 b 01 0.00b 00 0.00D 00 1.83b 05 2.26 b 05 33Ce-141 3.92b041.95D042.90D030.00b008.55D035((b055.66b04 34Ce-144 6.77b06 2.12b06 3.61b05 0.00D001.17b061.20bO7 3.89b05 CalenlatedperODCMequation2.2-13 2-44 ISSUE 1 REVISION 3

BV-2 ODCM

'2.3 Compliance with 10 CFR 50 (Gaseous) l f

l -r s At the Beaver 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

! top of the Unit I cooling tower. The resulting dose for the. purpose. of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception would'be a containment purge via the process vent. The resulting dose shall be attributed to the contributing reactor unit. Since this op e stion is expected to be rare, equations are shown throughout this

-section with the apportionment set at 0.5..

2.3.1 Noble Gases 2.3.1.1- Cumulation of DosesSection 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 annual gamma air dose is limited to 10 millirad and the beta air dose is-limited to 20 millirad. In addition, BVTS 3.11.2.4 requires use of radwaste system-if air doses when averaged over 31 days exceed 0.2 mrad for-gamma and 0.4 mrad for beta. Based upon NUREG-0133, the air dose limits .in the unrestricted area due to noble gases released in gaseous effluents are defined by the following expressions:

Puring any calendar quarter, for gamma radiation:

r~s Q

3.17E-8 I Mg [(X/Q)yQgy + (X/q) q g] + [B Q gg, + b qg g] 5 5 mrad, 1 .

(2.3-1)

During any calendar quarter,.for beta radiation:

3.17E-8 I N g (X/Q) Qg + (X/q) qg + (X/Q),Qg , + (X/q),q 5 10 mrad, (2.3-2)

During any calendar year, for gamma radiation:

3.17E-8 I M [(X/Q) Qg + ( 5 )y gg] + [B Qg h + bggg ,] 5 10 mrad, i

(2.3-3)

During any calendar year, for beta radiation:

3.17E-S I N (X/Q)yQg + (X/q) gg + (X/Q),Qg + (X/q),q 5 20 mrad, (2.3-4) 2-45 ISSUE I REVISION 3

BV-2 ODCSI When averaged over 51 days, for the gamma radiation projection:

3 ,. -.

j 3.17E-8 I Mg [(X/Q) Qh + (X/q) qg] + [B Qg+bq3 g] 5 0.2 mrad, i

(2.3-5)

Averaged over 31 days, for the beta radiation projection:

3.17E-8 Ng (X/Q) Qh + (X/q)yqh + (X/Q),Qh + (X/9)s9 h 5 0.4 mrad (2.3-6) where:

.M g = the air dose factor due to gamma emissions for each identified noble gas radionuclides "i", mrad /yr per UCi/m ; 8 N' = the air dose factor due to beta emissions for each identified 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)y = the relative concentration for areas at or beyond the

,q unrestricted area boundary for short-term vent releases Q (equal to or less than 500 hrs / year), sec/m';

(X/Q)s = the annual average relative concentration for areas at or beyond the unrestricted area boundary for long-term free standing stack releases (greater than F00 hrs / year), sec/m 8; (X/q)* = the relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases (equal to or less than 500 hrs / year), sec/m*;

g,y = release of noble gas radionuclides "i" in gaseous effluents for short-term stack releases (equal to or less than 500 hrs / year), pCi; gh = release of noble gas radionuclides "i" in gaseous effluents for short-term vent releases (equal to or less than 500 hrs / year), pCi; Q is = release of noble gas radionuclides "i" in gaseous effluents for long-term free standing stack releases (greater than 500 hrs / year), pCi; Q, = release f n ble gas radionuclides "i" in gaseous effluents h for long-term vent releases (greater than 500 hrs / year), VCi; r~s 2-46 ISSUE 1 REVISION 3

BV-2 ODCM B

g

= the constant for long-term releases (greater than 500 hrs / year) for-ecch identified noble gas radionuclides "i" y- g - accounting for the gamma radiation from the elevated finite T ,/ plume, mrad /yr per uCi/sec; by = the constant .for short-term releases (equal to or less than 500 hrs / year) for each identified noble gas radionuclides "1" accounting for the gamma radiation from the elevated finite plume, mrad /yr per pCi/sec; 3.17E-8 = the inverse of the number of seconds in a year.

'NUREG 0133- permits eliminating the short-term release term and short-term meteorological terms in the determination of doses when short term releases are .sufficiently random in both time of day and duration to be represented by annual average dispersion conditions.

This special consideration is applied in expressions 2.3-1 through 2.3-6, howev'er, a summary of the "real time" meteorological data coupled with the corresponding . releases shal'1 be included in the Semi-Annual Radioactive Effluent Release Report.

Short-term releases are also evaluated in computer codes technically consistent with XOQD0Q 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 compliance with 10 CFR 50 for 47-s) the calendar quarter or year.

For Release Modes 1, 2, 3, and 4 During any month, calendar quarter, or year:

Gamma Radiation (mrad) 3.17E-8 I +

j Mj [(X/Q)cvQ.i + (X/Q)vvQ i + (X/Q)tvQ i + (X/Q)cpQ i + (X/Q)dvO'i dv 0.2 mrad (per 31 days)

(X/Q) ,Q f

) + 0.5 B fg Q 5 5.0 mrad (per quarter) (2.3-7) wv pv, 10.0 mrad (per year) r 2-47 ISSUE 1 REVISION 3 i

L .. .. - - _ . _ _ - - _ . _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - . _ _ _ . _ - _ _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _ . - - _ _ _ _ _ _ _ - - . - _ _ _ _ _ _ _ _ - _ - . _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - - _ _ _ _ _ - _ - _

BV-2 ODCM-Beta Radiation (mrad)

~

. ,m

( 3.17E-8 I N g (FQ)cyQ g + M)vyQ g + M )tyQ i + M)cp 01 cp

- +

)dv01 dv

+

i cv- vv tv

~

0.4 mrad (per 31 days)

(X/Q) Q g ~+ 0.5 (X/Q) yQ g 5 10.0 mrad (per quarter) (2.3-8) wv pv 20.0 mrad (per year) where:

= annual average relative concentration for releases from the (X/Q)'Y Containment Vent, sec/m';

(X/Q)" = annual average relative concentration for releases from the Ventilation Vent, sec/m*;

(X/Q)PV = annual average relative concentration for releases from'the P m ess Ve m se @ 8-(X/Q) # = annual average relative concentration for releases from the Turbine Building Vent, sec/m';

annual average relative concentration for releases from the (X/Q)cp =. Condensate Polishing Building Vent, sec/m*;

(X/Q)dy = annual average relative concentration-for releases from the Decontamination Building Vent, sec/m';

(X/Q)# = annual average relative concentration for releases from the Waste Gas Storage Vault Vent, sec/m 8; Qg = release of radionuclides "1" from the Containment Vent, pCi; cv Qg = release of radionuclides "i" from the Ventilation Vent, pCi; vv Q-g

= release of radionuclides "i" from the Process Vent, pCi; PV Qg = release of radionuclides "i" from the Turbine Building Vent, j tv pCi; i

Qg = release of radionuclides "i" from the Condensate Polishing )

l cp Building Vent, pCi; Qg = release of radionuclides "i" from the Decontamination Building dv Vent, pCi;

[

Qg = release of radionuclides "i" from the Waste gas Storage Vault ]

wv Vent, pC1.

2-48 ISSUE I REVISION 3 L__--_----=------------------------------------_------------- - - - - - - - - - - - - - - -- 2

c BV-2 ODCM

~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

,ai results in the following:

l

\ ] Release Modes 1, 2, 3, and 4 During any month, calendar quarter or year:

Gamma Radiation (mrad) t-l 3.17E-8 I M g + 1.03E-4Q g + 7.35E-5Qg . + 7.35E-5Q g + 9.24E-5Q g +

1 _ g[9.24E-5Q ev vv tv cp dy 0.2 mrad (per 31 days) 9.24E-5Q g ] + 0.5 B Qgg 5 .5.0 mrad (por quarter) (2.3-9) wv pv_ 10.0 mrad (per year)

Beta Radiation (mrad) 3.17E-8 I N g 9.24E-5Q g + 1.03E-4Q g + 7.35E-5Q g + 7.35E-5Q g + 9.24E-5Q g +

1 _

cv vv tv cp. dv 0.4 mrad (per 31 days) 9.24E-5Q g + (0.5) 7.00E-10Q g 5 10.0 mrad (per quarter) (2.3-10) wv p v,_ 20.0 mrad (per year)

The determination of the controlling locations for implementation of 10 CFR

,_ 50 is a function of the following parameters:

(1) radionuclides mix and their isotopic release (2) release mode (3) meteorology.

The incorporation of these parameters into Expressions 2.3-7 and 2.3-8 resulted in the expressions for the controlling locations as presented in Expressions 2.3-9 and 2.3-10. The radionuclides mix was based upon source terms calculated using the Stone and Webster Engineering Corporation Computer Code GAS 1BB which is similar to the 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.

2-49 ISSUE 1 REVISION 3

BV-2 ODCM As' in Section 2.2.1, -for each release mode,-the two highest boundary X/Q p s values for.~each release point andJ. release duration were utilized in je .-- conjunction with the radionuclides mix and release for each releass point.to determine the controlling 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 nuclide mix and meteorology dominates in the determination of the -controlling receptor:

location. For. release modes 1, 3, and 4, the-controlling release is'the~

Containment Vent. While for release mode'2, the controlling release is the Ventilation Vent.

Values for M g and N, which were used in the determination of the f

controlling receptor location and which are to be used by BVPS-2 in l Expressions 2.3-9 and 2.3-10 to show compliance with 10 CFR 50 are presented in Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109,

-I Revision 1 ,y were multiplied by 1E6 to convert from picoeuries to microcuries for use in Table 2.2-11.

In the determination of the controlling receptor location for Modes 1, 2, 3,

• and 4, Tables ~2.2-4 through 2.2-7 are utilized for X/Q values. The B g

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 salues is presented in Appendix A.

The following relationship should hold for BVPS-2 to show compliance with Technical Specification 3.11.2.2:

For the calendar quarter:

Dg 5 5 mrad (2.3-11)

D 5 10 mrad 3

(2.3-12)

For the calendar year:

D7 5 10 mrad (2.3-13}

Dg 5 20 mrad (2.3-14) where:

Dg = the air dose from gamma radiation, mrad.

Dg = the air dose from beta radiation, mrad.

2-50 ISSUE 1 REVISION 3

BV-2 ODCM-

'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

~s 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 materials in that waste when projected doses from each-reactor unit, when averaged over 31 days exceed any of the following: 6/89 D 5 0.2 mrad 7 (2.3-15)

Dg 5 0.4 mrad (2.3-16) 2.3.1.2 Projection of Doses (Noble Gas)

Doses due to gaseous releases from BVPS-2 shall be projected at lear,t once per 31 days in accordance with BVTS 4.11.2.4 and this section. (See also Section 2.3.2.2 Projection of Doses). The Gaseous Radwaste Treatment 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 l6/89 31 days would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. (See also Section 2.3.2.2 Projection of Doses for additional specifications). The doses used in the 31-day dose projection will be calculated using Expressions 2.3-9 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 T _ ( 1) + C (2.3-17)

D 31 " -

When not including pre-release data D = ---

31 + C (2.3-18) 31 ,T.

Where:

D = r jected 31 day dose, mrad 31 =

A Cumulative dose for quarter, mrad B = Projected dose from this release, mrad T = Current days into quarter C = Value which may be used to anticipate plant trends, mrad l

l' O

V 2-51 ISSUE 1 REVISION 3

L 1

l .' BV-2 ODCM L 2.3.2 RJ diciodine and Particulate

i. fm 2.3.2.1 Cumulation of Doses

'ij Section IIC of Appendix I of 10'CFR 50 (BVTS 3.11.2.3 and 3.11.2.4) limits l' the release of radiciodines and. radioactive material in particulate form from each reactor such that estf. mated dose or- dose commitment in any calendar year to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. In addition,-BVTS 3.11.2.4 requires the use of gaseous radwaste treatment system when l

projected doses due to . gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. Based upon 6/89 NUREG-0133, the dose to an organ of an individual from radiciodines and particulate, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas, can be determined by the following expression:

During any month, calendar quarter or year:

0.3 mrem (per 31 days) 3.17E-8 I Rg [W Os n + "s9 1s + w 0 9 7.5 mrem (per quarter) i v h + "v h] < 15.0 mrem (per calendar year)

(2.3-19) where:

Qg = release of radionuclides "i" for long-term free standing stack g . releases (greater than 500 hrs /yr), pCi; i'

= release of radionuclides "i" for long-term vent releases Q

(greater than 500 hrs /yr), pCi; g,g

= release of radionuclides "i" for short-term free standing stack releases (equal to or less than 500 hrs /yr), pCi; qiv = release of radionuclides "1" for short-term vent releases (equal to or less than 500 hrs /yr), pCi; W = dispersion parameter for estimating dose to an individual at 8

the controlling location for long-term free standing stack releases (greater than 500 hrs /yr);

= sec/m' for the inhalation pathway, (X[Q),;

= meters 2 for the food and ground plane pathway, (D[Q) ;

W ,

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

= sec/m' for the inhalation pathway, (5) ;

2-52 ISSUE 1 REVISION 3

i tD i -BV-2 ODCM

= meters m'for the food and ground plane pathway, (D[Q)y;

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

= sec/m' fortheinhalationpathway,(5[q),;

2

= meters for the food and ground plane pathway,.(D/q)3; .

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

3

= sec/m fortheinhalationpathway,(5[q)y;

= meters ~2 for the food and ground plane pathway, (D[q') ;

3.17E-8 = the inverse of the number of seconds in a year; R

gt = the dose factor for each identified radionuclides "i" for the organ "t" of interest, mrem /yr per pCi/sec per m'* or mrem /yr f~ per pCi/m'.

Radionuclides and particulate may be released fro. any of the BVPS-2 vents in the release modes identified in Table 2.3-1. As described previously in Section 2.3.'1.1 at Beaver Valley Unit 2, NUREG 0133 permits use of long term annual averge dispersion calculations which with the release modes of Table 2.3-1 results in the following expressions to show compliance with BVTS 3.11.2.3 and BVTS 3.11.2.4. For a particular organ, Expression 2.3-19 becomes: .

3.17E-8 I R.*

0.5 W Q. +W cv Q.i +W vv Q.i +W Q vi

+W cpQi +W dv 0i +

i PV 1 py dy 0.3 mrem (per 31 days)

W $ 7.5 mrem (per quarter) (2.3-20)

"Y Q'wv _

15.0 mrem (per calendar year)

[

(

2-53 ISSUE 1 REVISION 3

BV-2 ODCM where:

( n') W = dispersion parameter for releases from the Process vent; Pv-

' ,1 W = dispersion parameter for releases from the Containment Vent;

-W yy

.= dispersion parameter for releases from the Ventilation Vent; W g= dispersion parameter' for releases from the Turbine Building Vent; W = dispersion parameter for releases from the Condensate cp Polishing Building Vent; W = dispersion parameter for releases from the Decontamination dy Building Vent; W

= dispersion parameter for releases from the Waste Gas Storage Vault Vent; Q1 = release of radionuclides "i" from the Process Vent, pCi; pv Q

f

= release of radionuclides "1" from the Elevated Release Vent, cv pCi; Qg = release of radionuclides "i" from the Ventilation Vent, pCi; vv

-I Qg = release of radionuclides "i" from the Turbine Building Vent, tv pCi; Qg = release of radionuclides "1" from the Condensate Polishing cp Building Vent, pCi; Qg = release of radionuclides "i" from the Decontamination Building dv Vent, pCi; Q *.

= release of radionuclides "i" from the Waste Gas Storage Vault wv Vent, pCi.

The Turbine Building Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and Waste Gas Storage Vault Vent are not norma; radioactive release points. These release points are included only for use if radioactive release via these vents are identified in the future.

In determining the dose at a particular location, dispersion parameter W, is a function of the pathway. For the food and ground plane pathway, W is in terms of D/Q. If the inhalation pathway is considered, W is in terms of X/Q. Incorporation of the various pathways into Expression 2.3-20 results in the following expression for a particular organ:

!^

2-54 ISSUE 1 REVISION 3

BV-2 ODCM 3.17E-8 I [R h +R hM

+R h

+R g ] [0.5 W Q g +W y Qg +W yy Qj +W Q f

+

1 G. V B pv cv vv tv

~

. ,~

Wcp01 +E + I+ it [0.5 (X/Q) yQ 3 +

,- dv01 wv91 + (X/Q)cyQ g + (W Q)yyQ j cp dv wv I pv cv vv 0.3 mrem (per 31 days)

(X/Q)tv01 + (X/Q)cpQ1 0

+ (U Q)dv 1 + C'W )wv 0 1] s 7.5 mrem (per quarter) tv cp dv wv ,

15.0 mrem (per year)

(2.3-21) where:

R h

= dose factor for organ "t" for radionuclides "i" for the ground

.G plane exposure pathway, mrem /yr per pCi/sec per m"8; Rg = dose factor for organ "t" for radionuclides "i" for either the M cow milk or goat milk pathway, mrem /yr per pCi/sec per m z; R

h

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

R h

= dose factor for organ "t" for radionuclides "i" for the meat B pathway, mrem /yr per pCi/sec per m z; s'~

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

It should be noted that W W y, W ,W y, W dv, and Wwy in Expression ep' 2.3-31 are in terms of D/Q(m 2),

Values of the dose factor, Rh , were calculat d using the methodology of NUREG-0133. The following equations were used for all nuclides except tritium:

R h = K'(BR), (DFAg ), (mrnm/yr per pCi/m') (2.3-22) y where:

K' = a constant of unit conversion IE6 pCi/pCi;

= the breathing rate of the receptor of age group (a), in (BR)#

m'/yr; O 2-55 ISSUE 1 REVISION 3

, .1 I BV-2 ODCM-

= 'the- organ inhalation dose factor for ogran "t" for the (DFA.t)a i receptor of age group (a) for the "i" th radienuclide, in mrem /pCi. Inhalation dose factors (DFAh) by organ for the various. age' groups are. given in Table E-7 through E-10 of Regulatory Guide 1.109. Rev. 1 or Tables 5 through~8 of NUREG-0172.

.The breathing rates (BR), used for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 3.109.

Age Group (a) Breathing Rate (m'/yr)

Infant 1400 Chi d 3700 Teen 8000 Adult 8000 h g = K'K" (SF)DFGg[(1 - e' i )/A ] g(m:-mrem /yr per pCi/sec)

R where:

K' .=- a constant of unit conversion 1E6 pCi/pci; K" = a censtant of unit conversion, 8760 hr/ year; O k g

= the decay constant for the "i" th radionuclides, sec~1; t = the exposure time, 4.73E8 sec (15 years);

DFG y* = the ground plane dose conversion factor for organ "t" for the "1" th radionuclides (mrem /hr per pCi/m 2). A tabulation of DFG g values is presented in Table E-6 of Regulatory Guide 1.109;

'SF = the shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is used.

R = Q g F(Uap)F (r)(DFL ff (1 - fpsf )e' i h -1.t if gt ) [PS +

M 1 +1 m it a Y Y p 3 (m*-mrem /yr per pCi/sec) (2.3-24) 2-56 ISSUE 1 REVISION 3

m. .

i +

BV-2 ODCM fi j

where:

1 fN K = a constant of unit conversion, IE6 pCi/pCi;

(). .Q = the animals' consumption rate, in kg/ day (wet weight);

F.

U ap .

= the receptor's' milk consumption rate, for age (a), in liters /yr; Y = the agricultural productivity b'y unit area of pasture P. feed grass, in kg/m*;

Y = the agricultural productivity by unit area of stored g

feed, in kg/m";

=

F, the stable element transfer coefficients, in days / liter; L

r = fraction of deposited activity retained on animals feed grass; (DFLg ), = the maximum organ ingestion dose factor for the "i" th-radionuclides for the receptor. in age group (a), in mrem /pCi. Ingestion dose factors (DFLh)a .f r 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 = the decay constant for the "i" th radionuclides, in f

sec ~2; A = the decay constant for removal of activity on leaf and plant surfaces by weathering 5.73E-7 sec~2 (corresponding to a 14 day half-life);

t = the transport time from pasture to animal, to milk, to f

receptor, in sec; t = the transport time from pasture, to harvest, to animal, h

to milk, to receptor, in sec; f = fraction of the year that the animal is on pasture 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.

2-57 ISSUE 1 REVISION 3 i

BV-2 ODCM Parameter Value Table f r (dimensionless) 1.0 for radiciodine E-15

( 0.2 for particulate Each Stable element E-15 F,(days / liter) E-1 (Cow Milk) 6/89 E-2 (Goat Milk)

U aP (liters /yr) - Infant 330 E-5 Child 330 E-5 Teen 400 E-!

Adult 310 E-5 (DFLh)a (mrem /pCi) Each radionuclides E-11 to E-14 2

Y p (kg/m ) 0.7 E-15 2

Y, (kg/m ) 2.0 E-15 t

f (seconds) 1.73E5 (2 days) E-15 t

h (see nds) 7.78E6 (90 days) E-15 Qp (kg/ day) 50 E-3 f 0.5 P

f, 1.0 _

g For goat's milk, all values remain the same except for QFwhich is 6 kg/ day.

~

t

• Q ff ih -1 t iI it K. F(Uap)F (r)(DFL ) ' P * + (1 - fP*f )e ]e B

Xf+l f y it a Y Yg (m2 -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 from 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 f f E-15 and U which is obtained from Table E-5. The values as obtained 6/89 from RegulatoryaPGuide 1.109, are as follows:

l l

O  !

l 2-58 ISSUE 1 REVISION 3 ]

l

BV-2 0DCM Parameter Value Table 7] Ff (days /kg) Each stable element E-1 GI tg (seconds) 1.73E6 (20 days) E-15 6/89 Uap (kg/yr) - Infant 0 E-5 Child 41 E-5 Teen 65 E-5 Adult 110 E-5 Man is considered to consume two types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:

it = K' [ ](DFL ) [U f e +Ufe h)

V Yy (13+A) it a aL ag (m8 -mrem /yr per pCi/sec) (2.3-26) where:

K' = a constant of unit conversion IE6 pC1/pCi; L =

U, the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr;

% S U, = the consumption rate of stored vegetation by receptor in age

_(\ group'(a) in kg/yr; f = the fraction of the annual intake of fresh leafy vegetation grown locally; f = the fraction of the annual intake of stored vegetation grown 8 locally; t = the average time between harvest of leafy vegetation and its g

consumption, in seconds; t the average time between harvest of stored vegetation and its h

consumption, in seconds; Y

y

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

and all other factors are defined previously.

Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109.

~

2-59 ISSUE 1 REVISION 3

- ____- - -__ - _ _ _____-_-. -_ __ _ _ - __ _ _ -__- -__ - _ _ _ _ - - - - _ __ -_ -- - _ -_-_-_- - ___-__- __ _ _1

w g~ y _ _ y-SV-2 ODCM Parameter. Value Table d r (dimensionless) L1 .0 for radiciodines E-15

(*'J' O.2 for particulat'es E-15

.(DFLit)a (mrem /PCI) Each Radionuclides E-11 to E U (kg/yr) - Infant 0 E-5

-a Child 26 E-5 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

-- 1. 0 E-15 f{(dimensionless)

F g.(dimensionless) 0.76 E-15 tp (seconds) 8.6E4 (1 day) E-15 5.18E6 (60 days) E-15 t{ (seco4.c.8)

Yg (kg/m*)L 2.0 E-15 For. tritium the parameter W for the food pathway is based upon X/Q. The ground plane path v.11s not appropriate for tritium.' Therefore, the left-n hand portion' ot Expression 2.3-20 may be expressed for purposes of implementation of 40 CFR 190, discussed in Section 4.0, as:

-]

For tritium:

3.17E-8 (RTT +R R +R ) [0.5 (X/Q) QT + (X/Q) QT + (X/Q) QT +

TT V

Tt Tt pv cv . vv M B I (X/Q) y Q.7 +

(X/Q)cp0T + ( IO)dv Tdv + (X/Q)wy Q T j ( .3-27) tv cp wv where:

R = dose factor for organ "t" for tritium for the milk pathway, T

M mrem /yr per pCi/sec';

R = dose factor for organ "t " for tritium for the vegetable TT V pathway, mrem /yr per pCi/m';

R dose factor for organ "t" for tritium for the beef pathway, Tt mrem /yr per pCi/m';

B R = dose factor for organ "t" for tritium for the inhalation I

I pathway, mrem /yr per pCi/m'.

L is used to show compliance with 40 CFR 190, as discussed l Expression ~2.3-27 rs in Section 4.0.

l' 2-60 ISSUE 1 REVISION 3 i

. _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ .b

BV-2'ODCM l~

TheJ concentration of tritium in milk is based on the airborne concentration rather than the' deposition.. Therefore, the R Tt is based on.[X/Q]:

g{

M

' ,~ ~~j 8

Tg = K'K'"F,Qp U (b7Lg) [0.75(0.5/H)] (mrem /yr per pCi/m )

R (2.3-28) where:

K'"

= a. constant of unit conversion, 108 gm/kg; H = absolute humidity of the atmosphere in gm/m ; 8 0.75 = the fraction of total feed that is water; 0.5 = 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 used is 8 grams / meter8 .

The concentration of tritium in vegetation is based on the airborne

. concentration rather than the depos.t. tion. Therefore, the R is based on-

[X/Q]:

L S

\

R TT

= K'K'" [U f + U,f ](DFLh)a[0.75(0.5/H)]

V (mrem /yr per pCi/m8 ) (2.3-29) where all terms have been defined above.

The concentration of tritium in meat is based on its airborne concentration rather that. the deposition. Therefore, the R is based on jX/Q):

Tg R

Tg = K'K'"FfpQ U,p ( mit)a[0.75(0.5/H)]

(mrem /yr per pCi/m8 ) (2.3-30) where all tc.rms have been defined above.

To show compliance with BVTS 3.11.2.3 and BVTS 3.11.2.4, Equation 2.3-21 is evaluated at the controlling pathway location. For release modes 1 through 4, the controlling location is a residence 0.89 miles in the NW sector.

Enserting appropriate X/Q values from Tables 2.2-4 to 2.2-10 and D/Q vrlues from Tables 2.3-28 to 2.3-54, Expression 2.3-21 becomes:

O v-2-61 ISSUE 1 REVISION 3

BV-2 ODC.T

, Release Modes 1 through 4 m Per month, calendar quarter or year) 1 j-v (mrem) 3.17E-8 I g [R h + 1.56E-8 Q cv + 1.56E-8 Q g +

+Rh ][(0.5)4.22E-10 Q pv G V vv 1.55E-8 Q I + 1.55E-8 Q I + 1.56E-8 Q I + 1.56E-8 Q*. ]+R. [(0.5)7.30E-9 Q I +

tv cp dv wv "1 pv 2.00E-5 Q g + 2.71E-5 Q g + 2.22E-5 Q g + 2.22E-5 Q g + 2.00E-5 Q g +

cv vv tv cp dv 0.3 mrem (per 31 days) 2.00E-5 Q g ] 5 7.5 mrem (per quarter) (2.3-31) wy 15.0 mrem (per year)

For tritium, for purposes of implementation of 40 CFR 190, as discussed in Section 4.0, Expression 2.3-27 reduces to:

3.17E-8 [RTt +Rg ][(0.5)7.30E-9 Qg + 2.00E-5 Q g + 2.71E-5 Q g +

V I pv cv vv 2.22E-5 Q g + 2.22E-5 Q 3 + 2.00E-5 Q g + 2.00E-5 Q g ]

tv cp dv wy (2.3-32)

(?)

The determination of a controlling locating for implementation of BVTS 3.11.2.3 and DVTS 3.11.2.4 tor radiciodines and particulate is a function of:

(1) radionuclides mix and their isotopic release (2) release mode (3) meteorology (4) exposure pathway (5) receptor's age 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 radionuclides mix of radiciodines and particulate was based upon the source terms calculated using the Stone and Webster Engineering Corporation Couputer Code GAS 1BB which is similar to the NRC GALE code. This mix was f presented in Table 2.2-2 as a function of release mode and release point.

For the ground plane exposure pathway, all radionuclides (excluding H-3 and l

C-14) were considered in the determination of the controlling location. For the inhalation and food pathways H-3 and C-14 were also considered in determination of the controlling location.

l l

1 l

l 2-62 ISSUE 1 REVISION 3 )

I

= .. - _ __ _ _ .-

~

LBV-2 0DCM In -the determinationLof the controlling location for.each release mode, all-of the exposure pathways, as. presented in Table 2.2-3, were. evaluated.

f'"\. These -include cow _ milk, goat' milk, beef and. vegetable ingestion and

(_ff inhalation and ground plane' exposure. An infant was assumed to be present at .all milk- pathway locations. A child was assumed to be present at,all

-vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present-at all locations.

For. the determination of the controlling location, the highest D/Q and X/Q values for each release point and release mode for the vegetable garden, cow

' milk, and . goat 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 controlling release point and mix is the Containment Vent.

Tables 2.3-2 through 2.3-20 present R values for the total body,.GI-tract, f

bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat mil'k, 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, s In the determination of the controlling location for release modes 1-4,

-( .

X/Q's listed in Table 2.2-4 through 2.2-10 were used. Tables 2.3-28 through 2.3-34 are utilized for long-term D/Q values. A description of the derivation of the various X/Q and D/Q values is presented in Appendix A.

Long-term D/Q values for the process vent, containment vent, the ventilation vent, turbine building vent, condensate polishing building vent, decontamination building vent, and waste gas storage vault 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., 4.5-5.0 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 'ocations of Table 2.2-3.

The following relationship should hold for BVPS-2 to show compliance with BVPS Technical Specification 3.11.2.3.

l For the calendar quarter:

l D 5 7.5 mrem to any organ (2.3-33) l l

() 2-63 ISSUE 1 l REVISION 3 l

- - - - . - . - - - - - - - - - - - - - - - - - - - - - - - - _ . - - - _ - - - - - - - - . _ - - - - _ - - - _ - - - A

BV-2 ObCM For the calendar year:

jr Ng D 5 15 mrem to any organ (2.3-34)

%J -

where:

-D = the dose to any organ t from radiciodines and. particulate,

' mrem.

The quarterly limits given above represent one-half the annual design objective of Section II.C of Appendix I 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 1 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 due to gaseous releases from the BVPS-2 shall be projected at least.

once per 31 days in accordance with BVTS 4.11.2.4 and this section. (See also Section 2.3.1.2 Projection of Doses). The appropriate portions of 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 projected doses due to gaseous effluent releases from each gjgg reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (See also Section 2.3.1.2 };ojection of Doses for additional specifications). Doses resulting from the gaseous effluent release of radioiodines and particulate will be calculated for use in the 31-day dose 7s projection using Expression (2.3-31). The 31-day dose projection shall be performed according to the following equations:

(_ )

When including pre-release data A+B D *

(2.3-35) 31 . T _(31) +

When not including pre-release dats D

33

=

[gr (31) + C (2.3-36) where:

D = Projected 31 day dose, mrem 33 =

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 l

l l 2-64 ISSUE 1 REVISION 3

d BV-2 '0*/CM -

LTABLE 2,3-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS

-[] FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50

~~

Release Point Mode 1 Mode 2 ' Mode 3 Mode 4 BVPS BVPS-2 2 Main Cond. Air Same as Same sa Same as

- Process Vent-(pv) Ejector, Waste Mode 1 Mode 1 Mode l'and Gas, Contain- Containment ment Vacuum Purge BVPS-1 Ventilation 2 Aux. Bldg. Containment Same as Same as Vent (vv1) Ventilation Purge 8 Mode 1 Mode 1 BVPS-1 Containment! Leakage Same as Same as Same as Vent-(cyl) Collection. Mode 1 Node 1 and Mode 1 Exhaust Containment Purge 2 BVPS-1' Turbine Bldg.2 Turbine Bldg Satie as. Same as Same as Vent-(tv1) Exhaust

• Mode 1* Mode 1* Mode 1*

' BVPS-2 Ventilation 2 Contiguous Containment. Same as Sama as Vent (vv2) Areas Purge 2 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 9(, s) Purge 8 BVPS-2 Turbine Bldg.2 Turbine Bldg Same as Same as Same as Vent (tv2) Exhaust

• Mode 1* Mode.1* Mode 1*'

' BVPS-2 Condensate 2 * * *

• Polishing Bldg. Vent (ep2)

BVPS-2 Decontamination 2 * * *

• Bldg. Vent (dv2)

BVPS-2 Waste Gas 2 * * *

• 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 8

Continuous elevated meteorology is applicable

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

(

2-65 ISSUE 1 REVISION 3

BV-2 ODCM-i Table 2.3-2 1 RVALUE.;FORBEAVERVALLEYSITE (aren/yrperuCi/cuseter)

' l'atbvar : Inhalation AgeGroup: Adult liuelide Bone Liver T. Body Thyroid Eidney Lung G1-LLI 1H-3 0.00E+001.26E+031.26E+031.26E+031.26t+031.26t+031.26E+03 2P 3Cr-51 1.32E+067.71E+045.01E+040.00E+000.00E+000.00E+008.64E+04 n 0.00E+000.00E+001.00E+025.95E+012.28E+011.44E+043.32E+03 4!!n-54' O.00E+003.96E+046.30E+030.00E+009.84E+031.40E+067.74E+04 5Fe-59 1.1BE+042.78E+041.065+040.00E+000.00E+001.02E+061.88t+05 6 00 0.00E+006.92E+026.7;E+020.00E+000.00E+003.70E+053.1(E+04 7 00-58 0.00E+001.58E+032.07t+030.00E+000.00E+009.28E+051.06E+05 6Co-60 0.00E+001.15E+041.48E+040.00E+000.00E+005.97H+062.85E+05 9Zn-65 3.2(E+041.03E+054.66E+040.00E+006.90E+048.64E+055.34E+04 10 Rb-66. 0.00E+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66E+04 11Sr-89 3.04E+050.00E+008.72E+030.00E+000.00E+001.40E+063.50E+0!

12St-90 9.92E+070.00E+006.10E+060.00E+000.00E+009.60E+067.22E+05 13Y-91 4.62E+050.00E+001.2(E+040.00E+000.00E+001.70E+063.85E+05 14Zr-95 1.07E+053.44E+042.33E+040.00E+005.42E+041.771+061.50E+05 15 lib-95 1.41E+047.82E+034.21E+030.00E+007.7(E+035.05E+051.04E+05 6/89 16 lib-97 2.22E-015.62E-022.05E-020.00E+006.54E-022.40E+032.42Et02 17ffo-99 0.00E+001.21E+022.30E+010.00E+002.91E+029.12E+042.48E+05 18te-99: 1.03E-032.91E-033.70E-020.00E+004.42E-027.64E+024.16E+03 19Ru-103 1.53E+030.00E+006.58E+020.00E+005.83E+035.05E+051.10E+05 20Ru-106 6.91E+040.00E+038.72E+030.00E+001.3(E+059.36!+069.12E+05

-21Ag-110 1.06E+04 1.00E $ 5.94E+03 0.00H+00 1.97E+04 4.63E+06 3.02E+05 22Sb-124 3.12E+045.89E+021.24E+047.55E+010.00E+002.4EE+064.06E+05 23$b-125 5.3(E+045.95E+021.26E+045.40E+010.00E+001.74E+061.01E+05 2(Te-127 1.26E+045.77E+031.57E+033.29E+034.5EE+049.60E+051.50E+05 25fe-129: 9.76E+034.67E+031.58E+033.44E+033.66E+041.16E+063.83E+05 261-131 2.52E+043.5BE+042.05E+041.19E+076.13E+040.00E+006.2EE+03 27I-133 8.64E+031.(BE+044.52E+032.15E+062.5BE+040.00E+008.8BE+03 280s-134 3.73E+058.48E+057.28E+050.00E+002.87E+059.76E+041.04E+04 19Cs-136 3.90E+041.46E+051.10E+050.00E+00B.56E+041.20E+041.17E+04 30Cs-137 4.7BE+056.21E+054.28E+050.00E+002.22E+057.52E+048.40E+03 31Ba-140 3.90E+0(4.90E+012.57E+030.00E+001.67E+011.27E+062.18E+05 32La-140 3.4(E+021.74E+024.5BE+010.00E+000.00E+001.36E+054.58E+05 33Ce-141 1.99E+0(1.35E+041.53E+030.00E+006.26E+033.62E+051.20E+05 34Ce-144 3.43E+061.43E+061.B(E+050.00E+008.4BE+057.78E+068.16E+05 y

CslenlatedperODCliequation2.3-22 2-66 ISSUE 1 REVISION 3

-BV-2 ODCM Table 2.3-3 EVALUESFORBEAVERVALLEYSITE (ares /yrperici/cuneter)

L Pathway: Inhalation L AgeGroup: Teen Nuc}1de Bene ' Liver T. Body Thyroid Eidner Lung GI-LLI l, 1E-3 0. 00b00 1. 27bO3 1.27E+03 1.27E+03 1.27bO3 1.27D03 1.27E+03 2P-32 1.69E+061.10D057.16b040.00D000.00D000.00b009.2BD04 g 3Cr-51 0.00b000.00E+001.35E+027.50b013.07b012.10E+043.00bO3 4Mn-54 0.00E+005.11b048.40D030.00b001.27b041.9BE+066.68b04 5Fe-59 1.59b04 3.70D041.43b04 0.00b00 0.00E+001.53b061.76b05 i 6Co-57 0.00b009.44bO29.20bO20.00b000.00b005.66+053.1604 7Co-5B 0.00D002.07bO32.7ED030.00b000.00D001.14b069.52b04 800-60 0.00b001.51b041.98b040.00b000.00b008./2bo62.59b05 92n-65 3.86b041.3&05 6.2m04 0.00 BOO B.64b041.hb36 4.66b04

! 10Rb-86 0.00b001.90D05 8.40D04 0.00D00 0.00D00 0.00b001.77b04 1

11 Sr-89 4.3&050.00b001.25E+040.00D000.00b002.42b063.71b05 12St90 1.08 BOB 0.00b006.68E+060.00b000.00E+001.65bO77.65b05 13 b91 6.61E+050.0@001.77b040.00b000.00D002.90064.09b05 O

V 14Ir-95 15Nb-95 1.46b05 4.58b04 3.15b04 0.00b00 6.74b04 2.69E+061.49b05 1.66b041.03b045.66bO30.00b001.00D047.51b059.6BE+04 16Hb-97 3.1(E-017.7EE-022.B&O20.00b009.12E-023.93b032.17E+03 '

17Mo-99 0.00D001.69bO23.22b010.00b004.11bO21.54b052.69b05 16fe-99: 1.35E-03 3.ESbO3 4.99bO2 0.00D00 5.76bO21.15bO3 6.13b03 19 h-103 2.10E+03 0.00h00 8.96bO2 0.00b00 7.43bO3 7.83b051.09b05 20 h-106 9.6@040,00D001.2@040.00D001.90D051.61bO79.60D05 21 ag-110s 1.36 b04 1.31b 04 7.99E+03 0.00D 00 2.50 b 04 6.75b06 2.73b05 22Sb-124 4.30D047.9&D21.6Bb049.76b010.00b003.3m063.98b05 23Sb-125 7.38b048.0BE+021.72b047.0&010.00b002.74b069.92h04 24Te-127 1.60b04 8.16bO3 2.1Eb03 4.38bO3 6.5@041.66D061.59b05 25te-123 1.39D04 6.5BbOS 2.25bO3 4.5EbO3 5.19b041.9Eb06 4.05b05 26I-131 3.5G04 4.91b04 2.64b041.46bO7 8.40D04 0.00b00 6.49E+03 271-133 1.22b04 2.05b04 6.22bO3 2.92b06 3.59b04 0.00b001.03b04 20Co-134 5.02b051.13b06 5.49b05 0.00D00 3.75b051.46b05 9.76D03 29Cs-136 5.15D041.9&O51.37b050.00b001.10b051.7Eb041.09b04 30Cs-137 6.70D05 8.4Bb05 3.11b05 0.00D00 3.04b051.21b05 8.4BbO3 31Ba-140 5.47b046.70E+013.52b030.00D002.28D012.03b062.29b05 32La-140 4.79bO22.36bO26.26b010.00D000.00b002.1@054.67D05 33Ce-141 2.84b041.90bO( 2.17bO3 0.00b00 8.88bO3 6.1@051.26b05 34Ce-144 4.89b062.02b062.62E+050.00D001.21b061.3&O78.6&05 CalculatedperODCMequation2.3-22 j i

2-67 ISSUE 1 REVISION 3 I

_ __-_--_______-_ ___ D

g p

l"

'BV-2 ODCM g 741e2.3-4 RVALUESFORBEAVERVALLifSITE l

larea/rrpersci/cuseter)

Pathwar: Inhalation AgeGroup: Child Nuclide Bone Liver 1. Sody' Thyroid Eldney Lung GI-LL1

' 1 b3 0.00E+00 1.12bO3 1.12bO3 1.12b O3 1.12bO3 1.12bO3 1.12E+03 2P-32 2.60D061.14b059.88b040.00D000.00D000.00D004.22b04 g 3Cr-51 0.00D000.00b001.54bO28.55b012A3E+011.70E+041.0BbO3 (Mn-54 ~0 .00E+00 4.29b04 9.51D03 0.00D001.00D041.58b06 2.29b0:1 5Fe-59 2.07b043.34D041.67b040.00E+000.00b001.27b067.07b04 6Co-57 0.00E+00 9.03b021.07bO3 0.00b00 0.00b00 5.07b051.32b04 700-58 0.00E+001.77bO33.16D030.00E+000.00D001.11b063.4(b04 800-60 0.00D001.31b042.26b040.00D000.00 BOO 7.07b069.62b04 9Zn-65 4.25b041.13b05 7.03b04 0.00b00 7.14b04 9.95b051.63b04 10Rb-86 0.00b001.98b051.1(b050.00E+000.00E+000.00D007.99bO3 11Sr-89 5.99b05 0.00b001.72b04 0.00E+00 0.00b00 2.16b061.67b05 12St-90 1.01 BOB 0.00E+00 6.4(b06 0.00b00 0.00D001.48bO7 3.43b05 13Y-91 9.14b050.00E+002.44b040.00b000.00D002.63b061.84b05

/}'

k 14Zr-95 15Nb-95 1.90b05 4.18b04 3.70b04 0.00D00 5.96bO( 2.23b06 6.11bO(

2.35D049.16bO36.55bO30.00b008.62bO36.1(b053.70D04 6/89 16Ib-97 4.29E-017.70E-02 3.60E-02 0.00b00 8.55E-02 3.42bO3 2.78b04 17Ho99 0.00b001.72D024.26b010.00D003.92bO21.35b051.27D05 18fc-99e 1.78E-033A8bO35.77E-020.00b005.07E-029.51bO24.81bO3 19Ru-103 2.7BbO3 0.00D001.07bO3 0.00b00 7.03E+03 6.62E+05 ( (BD04 20Ru-106 1.36b050.00D001.69b040.00b001.84b051.43D074.29b05 21 Ag-110e 1.69b041.14b04 9.14bO3 0.00D00 2.12b04 5.48b061.00D05 22Sb-124 5.7(b047.40bO22.00D041.26bO20.00b003.24D061.64b05 23$b-125 9.64b047.59bO22.07bO(9.10D010.00D002.32b064.03b04 24 fe-127a 2.49b04 8.55bO3 3.02bO3 6.07bO3 6.36b041.48b06 7.14b04 25 fe-129s 1.92b 04 6.85 b O3 3.04bO3 6.33b 03 5.03D 04 1.76b 06 1.82D 05 26I-131 4.81b05 lb042.73b041.62bO77.88b040.00D002.8(bO3 271-133 1.66bO(i )b04 7.70bO3 3.85b06 3.38D04 0.00D00 5AEb03 28Cs-134 6.51b051.01b06 2.25b05 0.00D00 3.30D051.21b05 3.85bO3 29Cs-136 6.51b041.71b051.16b050.00b009.55b041.45b044.18bO3 30Cs-137 9.07b058.25b051.28b050.00b002.82b051.0(D053.62bO3 31Ba-140 7.40D046.48b014.33bO30.00b002.11b011.74b061.02bo5 32La-140 6.44D02 2.25bO2 7.55b010.00b00 0.00b001.83b05 2.26b05 33Ce-141 3.92bO(1.95b042.90bO30.00b008.55bO35.44D055.66b04 34Ce-144 6.77b062.12D063.61b050.00D001.17b061.20bO73.89b05 CalculatedperODCMequation2.3-22 2-68 ISSUE 1 REVISION 3

l BV-2 ODCM l g . Table 2.3-5 RVALUESFORBEAVERVALLE!S!!E (area /rrpernCi/cuseter)

Pathwar: Inhalation AgeGroup: Infant helide Bone Liver f. Body Thyroid Eidney Lung GI-LLI

-1H-3 0.00 BOO 6.47bO26.47bO26.47bO26.47bO26.47bO26.47bO2 2P-32 2.03D061.12b057.7(b040.00E+000.00D000.00b001.61D04 3Cr 0.00b00 0.00D00 8.95b015.75b011.32b011.28b04 3.57bO2 I k 4Ha 0.00D002.53b044.98bO30.00b004.98bO31.00b067.06bO3 5Fe-59 1.36bO(2.35D049.48bO30.00b000.00D001.01b062.48b04 600-57 0.00b006.51bO26.41bO20.00b000.00b003.7Sb054.86bO3 700-58 0.00D001.22bO31.82bO30.00b000.00D007.77D051.11b04 800-60 0.00b00 8.02bO31.18b04 0.00D00 0.00b00 4.51b06 3.19b04 9In-65 1.93b046.26b043.11b040.00b003.25b046.47b055.14b04 10Rb-86 0.00D001.90D058.82b040.00D000.00b000.00D003.04bO3 11St-89 3.98D050.000001.14b040.00b000.00b002.03b066.40D04 12Sr-90 4.09bO70.00D002.59b060.00b000.00 BOO 1.12bO71.31b05 13T-91-- 5.88b050.00D001.57b040.00D000.00D002.45b067.03b04-C 14Zr-95 1.15b05 2.79D04 2.03b04 0.00b00 3.11b041.75b06 2.17b04 C) 15Nb-95 1.57b04 6.43bO3 3.78bO3 0.00D00 4.72D03 4.79b051.27bO(

6/89 16Hb-97 3.42E-017.29E-022.63E-020.00b005.70E-023.32bO32.69b04 17Ho-99 0.00>001.65bO23.23b010.00b002.65bO21.35b054.87bO(

18fe-99: 1.40bO32.88bO33.72bO20.00D003.11E-028.11bO22.03bO3 19Ru-103 2.02bO30.00b006.79bO20.00D004.2(bO35.52b051.61b04 20 h-106 6.66b 04 0.00D 00 1 2 04 0.00b 00 1.07 b 05 1.16b O7 1.64b 05 21 Ag-110s 9.98bO3 7.22bO3 5.00bO3 0.00b001.09b04 3.67b06 3.30b04 22Sb-124 3.79b04 5.56bO21.20D041.01bO2 0.00b00 2.65b06 5.91b04 23Sb-125 5.17b044.77bO21.09b046.23b010.00b001.6(b061.47b04 24 fe-127a 1.67b04 6.90bO3 2.07bO3 4.87bO3 3.75b041.31b06 2.73b04 25 fe-129e 1.41b04 6.09b03 2.23bO3 4.21bO3 3.18b041.68b06 6.90b04 26 1-131 3.79b044.44b041.96b041.4BbO75.18b040.00b001.06bO3 27I-133 1.32b041.92D045.60bO33.56b062.2(b040.00D002.16bO3 28Ce-134 3.96b05 7.03b05 7.45b04 0.00b001.90b05 7.97b041.33b03 29Cs-136 4.83b041.35b055.29b040.00b005.6(b041.18b041.43bO3 30Cs-137 5.49b056.12b054.55b040.00D001.729057.13b041.33bO3 31Ba-140 5.60b04 5.60D012.90bO3 0.00D001.3(bO11.60b06 3.84b04 32La-140 5.05bO22.00bO25.15b010.00b000.00b001.68b058.48b04 33Ce-141 2.77b041.67b041.93bO30.00b005.25bO35.17b052.16b04 34Ce-144 3.19b061.21D061.76b050.00b005.38b059.84b061.(8b05 y CalculatedperODCHequation2.3-22 2-69 ISSUE 1 REVISION 3

b BV-2'00CM:

$~ ' fable 2.3-6

-EVALUESF0EBEAVEEVALLEYSITE

-(sqseter-area /yrperiCi/sec)

.Patbver : Ground l

l hellde  : Bone Liver f. Body Thyroid Eidney Lung GI-LLI L. 1E-3 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00

?

'2P-32 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 jp 3 Cr-51 4.665+06 4.66E+06 4.66E+06 4.66t+06 4.66t+06 4.66t+06 4.66E+06

.4Ma-54 1.39E+091.39E+091.395+091.39E+091.395+091.39E+091.39E+09 5Fe-59 2.73E+082.73E+082.73E+082.73E+082.73E+082.73E+082.73E+08 60o-57~ 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 7C0-58 3.798+083.79E+083.795+083.7954083.79E+083.79E+083.79t+08 8 Co-60' 2.15E+102.15E+102.15E+102.15E+102.15E+102.15E+102.15E+10 l 9Zn-65 7.47t+087.47t+087.47t+087.475+087.47t+0B7.47E+087.475+08 10Rb-86 8.995+068.99E+068.995+068.99E+068.99E+068.99E+068.995+06 11Sr-89 2.16t+042.16t+042.16t+042.16E+042.16E+042.16E+042.165+04 12St-90 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 13 Y 91 1.07E+061.07b061.07E+061.07D061.075+061.07E+061.07E+06 14Zr-95 2.45E+082.45E+082.45E+082.45E+082.45E+082.45H+082.45E+08

\ 15lb-95' 1.37bO8137bO81.37 BOB 1.37bOS 1.37bO81.37 BOB 1.37 BOB 6/89 16Nb-97 0.00E+00 0.00b00 0.00b00 0.00b00 0.00b00 0.00E+00 0.00D00 17Ho-99 4.00E+064.00E+064.00E+064.00E+064.00E+064.00E+064.00E+06 18fe-99: 1.84b051.84b051.84b051.84E+051.84b051.84E+051.84b05 19Hu-103 1.08t+08 1.08bO8 1.08D08 1.08b06.1.0 Bbl ! 1.08bO8 1.08t+0B 20Ru-106 4.22 BOB 4.22bO8 4.22E+08 4.22 BOB 4.22908 4.22bO8 4.22bO8 21Ag-110s 3.44b093.44E+093.44E+093.44b093.44b093.44b093.Hb09 22Sb-124 0.00D000.00b000.00D000.00E+000.00b000.00E+000.00b00 23Sb-125 0.00b000.00D000.00D000.00D000.00E+000.00E+000.00b00 24 fe-127a 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17h04 9.17b04 25 fe-129s 1.98 D 07 1.98E+07 1.98b O7 1.98b O7 1.98 bO7 1.98b O7 1.98bO7

-26I-131 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 27I-133 2.45b062.45b062.454062.45b062.45b062.6b062.45b06 28Cs-134 6.86D09 6.86b09 6.86b09 6.86b09 6.36D09 6.86009 6.86b09 29Co-136 1.51E+0B 1.51 BOB 1.51 BOB 1.51 BOB 1.51bO81.51D081.51 BOB 30Cs-137 1.03b101.03D101.03D101.03D101.03D101.03D101.03b10 31Ba-140 2.05bO7 2.05D07 2.05bO7 2.05D07 2.05bO7 2.05bO7 2.05bO7 32La-140 1.92bO71.92bO71.92bO71.92bO71.92bO71.92bO71.92bO7 33Ce-1(1 1.37D071.37bO71.37bO71.37bO71.37bO71.37bO71.37bO7 34 Ce-144 6.96bO76.96bO76.96bO76.96bO76.96bO76.96E+076.98bO7 CalculatedperODCHequation2.3-23 2-70 ISSUE 1 REVISION 3

BV-2 00CM f.y Table 2.3-7

.RVALUESFORBEAVERVALLEYSITE (egmeter-ares /yrperuCi/sec)

, 'Pathwar: Vegetation AgeGroup: Adult Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-L51 1H-3 0.00E+00 2.26D03 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2P-32' 1.40bo9 8.74bO7 5.43b07 0.00D00 0.00b00 0.00b001.58 BOB j(

3Cr-51 0.00b000.00D004.64D042.78b041.02b046.16b041.17bO7 4Hn-54 0.00b003.13b085.97bO70.00b009.31bO70.00D009.59bO8 5Fe-59 1.26 BOB 2.96 BOB 1.14 BOB 0.00b000.00b008.28bO79.68bO8 600-57 0.00D001.17D071.95bO70.00D000.00D000.00D002.97 BOB 700-58 0.00b00 3.07b O7 6.89b 07 0.00b 00 0.00 b00 0.00E+00 6.23b06 8 Co-60 0.00E+001.67bO83.69b080.00b00n.00b000.00b003.14b09 92n-65 3.17 BOB 1.0lb094.56 BOB 0.00D006.75 BOB 0.00b006.36 BOB 10Rb-86 0.00b002.19 BOB 1.02 BOB 0.00D000.00b000.00D004.33D07 11Sr-89 9.97b090.00D002.86bO80.00b000.00b000.00b001.60D09

.12St-90 6.05b110.00b001.4Bb110.00D000.00D000.00D001.75b10 13T-91 5.11b060.00D001.37b050.00b000.00 BOO 0.00D002.81b09 14Zr-95 1.17b063.77b052.55b050.00D005.91b050.00b001.19b09 15Nb-95 1.42b057.92b044.26b040.00D007.63b040.00b004.81D08 6/89 16Nb-97 2.16E-065.46E-071.99E-070.00D006.37bO70.00b002.02E-03 17Ho-99 0.00b006.15b061.17b060.00D001.39bO70.00D001.43b07 18fe-99: 3.10D008.77b001.129020.00E+001.33bO24.30 BOO 5.19bO3

.19Ru-103 4.77b060.00b002.06b060.00D001.82bO70.00D005.57E+08 20Ru-106 1.93 BOB 0.00b002.44bO70.00D003.72 BOB 0.00b001.25b10 21Ag-110 1.05bO7 9.75b06 5.79b06 0.00D001.92bO7 0.00b00 3.98b09 22Sb-124 1.04bO81.96b064.11D072.51b050.00b008.07bO72.94b09 23Sb-125 1.37bO81.53b06 3.25bO71.39b05 0.00b001.05 BOB 1.50E+09 24fe-127: 3.49bO81.25 BOB 4.26bO7 8.92bO71.42b09 0.00 BOO 1.17b09 25 fe-129s 2.51D08 9.38bO7 3.96bO7 8.64bO71.05b09 0.00b001.27b09 26I-131 8.08bO71.16E+08 6.62bO7 3.79b101.98 BOB 0.00b00 3.05bO7 271-133 2.09b063.63b061.11b065.33 BOB 6.33b060.00D003.26b06 28Ce-134 4.67b091.11b10 9.06b09 0.00b00 3.59b091.19b091.94 BOB 29Cs-136 4.27D071.69b081.21 BOB 0.00D00 9.38bO71.29bO71.91bO7 30Ce-137 6.36b09 8.70b09 5.70D09 0.00b00 2.95b09 9.81 BOB 1.6EbO8 31Ba-140 1.29b081.61b05 8.42b06 0.00b00 5.49b04 9.24b04 2.65 BOB 32La-140 1.98b O3 9.97 b O2 2.62b O2 0.00D 00 0.00b00 0.00 b 00 7.32bO7 33Ce-141 1.97bo51.33b051.51D040.00D006.19b040.00b005.10bO8 3(Ce-144 3.29bO71.38bO71.77b06 0.00D00 8.16b06 0.00b001.11b10 111 unelides (except H-3) calculated per ODCH equation 2.3-26 y H-3calculatedperODCHequation2.3-29 2-71 ISSUE 1 REVISION 3 L - - _______ ____________ _

l:

BV-2 ODEM g-g Table 2.3-8 q )

V I VALUES FOR BEAVER VALLU SITE (sqseter-ares /yrperuCi/seel Pathway - Vegetation AgeGroup: Teen 4 Nuclide Bone Liver T. Body Thyroid lidney Lung GI-LLI 1H-3 0.00b002.59bO32.59bO32.59bO32.59bO32.59b032.59bO3 2P-32 1.61b09 9.98bO7 6.24D07 0.00D00 0.00b00 0.00D001.35b08 3Cr-51 0.00D000.00D006.17b043.0b041.35b048.81b041.0e.bO7 N 4En-54 0.00D00 4.54D08 9.01b07 0.00b001.36 BOB 0.00D00 9.32bO8 5Te-59 1.79 BOB 4.19bO81.62D08 0.00b00 0.00D001.32 BOB 9.90D08 600-57 0.00b001.79bO7 3.00bO7 0.00b00 0.00D00 0.00b00 3.33 BOB 700-58 0.00D004.36D071.00bO80.00b000.00D000.00D006.0lbOB 8Co-60 0.00D002.49bO85.60bO80.00D000.00b000.00D003.24bo9 9Zn-65 4.24b081.47b09 6.87bO8 0.00b00 9.42bO8 0.00b00 6.23E+08 10Rb-86 0.00D00 2.74 BOB 1.29b08 0.00D00 0.00D00 0.00D00 4.05bO7 11St-89 1.51b100.00b004.34D080.00b000.00b000.00D001.B0D09 12St-90 7.51b110.00b001.85b110.00b000.00D000.00D002.11D10 13 b91 7.84b06 0.00D00 2.10D05 0.00D00 0.00b00 0.00b00 3.21b09 14Zr-95 1.72b065.43b053.74b050.00b007.98D050.00b001.25D09 15lb-95 1.92b 05 1.07b 05 5.87b 04 0.00 D 00 1.03b 05 0.00D 00 4.56bO8 6/89 16Nb-97 2.00E-064.97E-071.81bO70.00D005.81E-070.00D001.19E-02 17Mo-99 0.00b00 5.65b061.08b06 0.00D001.2Sb07 0.00b001.01bO7 18Te-99: 2.74b00 7.64b00 9.90D010.00D001.14bO2 4.24b00 5.02bO3 19Ru-103 6.82b060.00D002.92b060.00b002.41bO70.00D005.70bO8 20Eu-106 2.38 BOB 0.00b003.90bO70.00D005.97bO80.00D001.4Bb10 21Ag-110 1.52bO71.43b078.72b060.00b002.74bO70.00b004.03b09 22Sb-124 1.54 BOB 2.84b066.02bO73.50D050.00b001.35 BOB 3.11b09 23Sb-125 2.14D08 2.34b06 5.01bO7 2.05b05 0.00b001.88 BOB 1.67b09 24Te-127 5.52 BOB 1.96bO8 6.56bO71.31 BOB 2.24b09 0.00b001.37b09 25 Te-129m 3.62D061.34bO8 5.73D071.17bO81.51b09 0.00D001.36b09 26I-131 7.69b071.08 BOB 5.78bO7 3.14D101.85D08 0.00b00 2.13b07 27l-133 1.94b063.29b061.00b064.59bOS5.77b060.00D002.49b06 28Cs-134 7.10b091.67b10 7.75D09 0.00b00 5.31b09 2.03b09 2.0SbO8 29Cs-136 4.38bO71.72 BOB 1.16 BOB 0.00b009.37bO71.48bO71.39bO7 30Ce-137 1.01b101.35b104.69b090.00b004.59b091.78b091.92D08 31Ba-140 1.38b081.69b058.90D060.00D005.74b041.14b052.13b08 32La-140 1.81D03 8.88bO2 2.36b02 0.00b00 0.00D00 0.00b00 5.10D07 33Ce-141 2.83b051.89D052.17b040.00b008.90D040.00b005.41 BOB 34Ce-144 5.27bO7 2.18bO7 2.83b06 0.00bC01.30bO7 0.00D001.33D10 All nuclides (except B-3) calculated per ODCM equation 2.3-26 y H-3calculatedperODCMegnation2.3-29 2-72 ISSUE 1 REVISION 3

7 s

BV-2'0DCM m "

- Table 2.3-9, i l[

[

]T 1 RVALUESFORBEAVERVALLEYS!!!;

k A

L (sgteter-area /yrperuCi/sec) l;" .'

Pathway: Vegetation AgeGroup: Child Nuclide; Bone Liver T. Body Thyroid lidney Lung GI-LL1

' 1 H-3 0.00b00 4.01bO3 4.01bO3 4.01bO3 4.0lbO3 4.01bO3 4.01bO3' 2P-32 3.37b091.58bO81.30bO80.00D000.00b000.00b009.32bO7~ g 3Cr-51: 0.00D00 0.00D001.17b05 6.50b041.78b041.19b05 6.21b06 -

4Mn-54 0.00D00 6.65bO81.77bO8 0.00b001.8Cb68 0.00Et00 5.58bO8 5Fe-59 3.9BbO8 6.43b08 3.20bO8 0.00b00 0.00h001.87bO8 6.70bO8 6Co-57 0.00D00 2.99bO7 6.04h07 0.00b00 0.00b00 0.00b00 2.45bO8 7C0-58 -0.00D006.44bO71.97bOS0.00D000.00b000.00D003.76bO8 8Co-60 0.00D003.78bO81.12b090.00D000.00b000.00b002.10D09 9Zn-65 '8.13bO82.17b091.35b090.00b001.36b090.00b003.80D06 10Rb-86 0.00D00 4.52bO8 2.78 BOB 0.00b00 0.00D00 0.00D00 2.91bO7 11St-89 3.60b100.00b001.03b090.00b000.00b000.00D001.39b09 12St-90 1.24b120.00E+003.15b110.00b000.00 BOO 0.00h001.67b10-13 Y-91 _ 1.86bO70.00D004.99D050.00b000.00b000.00D002.48b09 xN 14Zr-95 3.86b06 8.48b05 7.55b05 0.00D001.21h06 0.00D00 0.85 BOB

< 15Nb-95 4.11b051.60D051.14b050.00b001.50D050.00b002.96bO8 6/89 16Nb-97 3.65E-066.59E-073.08bO70.00D007.31bO70.00b002.03E-01 17No-99 -0.00b007.71b061.91D060.00D001,65bO70,00D006.32b06 18Te-99: 4.71b009.24b001.53bO20.00b001.34bO24.69b005.26bO3 19Hu-103 1.53bO7 0.00D00 5.90b06 0.00D00 3.86bO7 0.00D00 3.97bO8 20Ru-106 7.45b080.00b009.30bO70.00D001.01b090.00D001.16D10 21 Ag-110 3.21bO7 2.17bO71.73bO7 0.00D00 4.04bO7 0.00b00 2.51b09 22Sb-124 3.52bO84.57b061.23 DOS 7.77b050.00b001.95D062.20D09 23Sb-125 4.99bO83.85b061.05 BOB 4.63b050.00D002.78bO81.19D09 24 fe-127a 1.32D09 3.56 BOB 1.57bO8 3.16bO8 3.77b09 0.00b00-1.01b09 25 Te-129e 8.t.lb OB 2.35 b O8 1.31b OB 2.71b OS 2.47 b 09 0.00D 00 1.03b09 26I-131 1.43bO81.44 BOB 8.17bO7 4.76b10 2.36 BOB 0.00b001.28bO7 271-133 3.53b064.37b061.65b068.12bO87.28bo60.00D001.76b06 28Cs-134 1.60b102.63b105.55b090.00D008.15b092.93D091.42bO8 29Cs-136 8.24bO7 2.27bO81.47bO8 0.00b001.21 BOB 1.80bO7 7.96b06

, 30Ca-137 2.39b102.29b103.38b090.00b007.46b092.6Bb091.43b08 31Ba-140 2.77bO82.42bO71.62bO70.00D007.89b041.45b051.40bO8 32La-140 3.25bO31.13b03 3.83D02 0.00b00 0.00b00 0.00b00 3.16bO7 33Ce-141 6.56b053.27b054.86b050.00D001.43b050.00D004.08bO8  ;

34 Ce-1H 1.27 BOB 3.98bO76.78b060.00b002.21bO70.00b001.04b10 l All nuclides (except H-3) calculated per ODCM equation 2.3-26 y b3calculatedperODCdequation2.3-29 2-73 ISSUE 1 REVISION 3

- - _A

U g

b

-BV-2 00CM y

fabir2.3-10 1 .,b l

M RVALUESFORBEAVERVALLEYSITE

'(egmeter-ster /rrperuCi/aec)

Pathway: Meat

• AgeGroep: Adult Nuclide Bone Liver T. Body Thyroid tidney Lug GI-LLI 1 E3 0.00b00 3.25bO2 3.25bO2 3.25bO2 3.25bO2 3.25bO2 3.25bO2 2P-32 3.95b092.46bO81.53b080.00b000.00b000.00D004.44bO8 JL 3Cr-51 0.00D00 0.00b00 5.86bO3 3.50bO31.29bO3 7.78bO31.47D06

' ( Hn-54 0.00h006.49b061.24b060.00D001.93b060.00D001.99bO7 5Fe-59 2.14bO85.04 BOB 1.93b080.00D000.00D001.41D081.68b09 60o-57 0.00b004.0lb066.66b060.00b000.00b000.00b001.02908 700-58 0.00D001.42bO7 3.1Bb07 0.00D00 0.00D00 0.00b00 2.87 BOB 8 Co-60 0.00b005.12bO71.13bO80.00b000.00D000.00D009.61b08 9Zn-65 2.54E+0B 8.09bO8 3.66bO8 0.00b00 5 (1 BOB 0.00b00 5.10bO8 10lb-86 0.00b004.11 BOB 1.92bO80.00D000.00b000.00D008.11D07 11St-89 2.41bO8 0.00b00 6.92b06 0.00D00 0.00b00 0.00b00 3.87bO7 12Sr-90 8.41b090.00b002.06b090.00D000.00b000.00D002,43b08 13f-91 8.94b05 0.00D00 2.39b04 0.00b00 0.00b00 0.00b00 4.92bO8

) 14Zr-95 1.47b06 4.71b05 3.19b05 0.00D00 7.39b05 0.00 BOO 1.4Sb09 15Nb-95 1.89b061.05b06 5.64b05 0.00D001.04b06 0.00D00 6.37b09 6/89 16Nb-97 sssssssssssssssssssssssssss0.00b00sssssssss0.00b00sssssssss 17Mo-99 0.00D00B.51b041.62b040.00D001.93b050.00b001.97b05 18fe-99: 3.83b211.08b201.3BE-190,00D001.64E-195.30b21640b18 19 Ru-103 8.57bO70.00b003.69bO70.00h003.27 BOB 0.00b001.00b10-20Ru-106 1.97b090.00b002.49b080.00b003.80b090.00b001.27b11 21 Ag-110e 4.77D 06 4.41b 06 2.62b 06 0.00h00 8.67 b 06 0.00b00 1.80 D09 22Sb-124 0.00D000.00b000.00b000.00b000.00D000.00b000.00D00 23Sb-125 0.00b000.00b000.00D000.00D000.00D000.00D000.00b00 24fe-127 8.38D06 3.00 BOB 1.02bO8 2.14bO8 3.40D09 0.00b00 2.81b09 25 fe-129e 9.33b08 3.48 BOB 1.4B b08 3.21D 06 3.BBb09 0.00D00 4.70D 09 261-131 9.13b061.31bO7 7.48D06 4.28b09 2.24bO7 0.00D00 3.45b06 27I-133 3.12E-015.420011.65E-017.96b019.46b010.00b004.87E-01 28Cs-134 4.53b081.08b09 8.81bO8 0.00h00 3.4SbOB 1.16 BOB 1.89bO7 29Ce-136 1.02bO7 4.04bO7 2.91bO7 0.00b00 2.25D07 3.0Bb06 4.59b06 30Ce-137 5.90 BOB 8.06 BOB 5.28 BOB 0.00b00 2.74 BOB 9.10bO71.56D07 31Ba-140 2.44bO7 3.06b041.60D06 0.00h001.04b041.75b04 5.02bO7 32La-140 3.16bO21.59b024.21bO30.00 BOO 0.00b000.00b001.17bO3 33 Ce-141 1.16b047.83b038.8BbO20.00b003.64bO30.00D002.99bO7 34Ce-144 1.03b06 4.32b05 5.55b04 0.00b00 2.56b05 0.00D00 3.50bO8 All nuclides (except E3) calculated per ODCM equation 2.3-25 E3calculatedperODCMequation2.3-30 2-74 ISSUE 1 REVISION 3

t 1 BV-2 00CM Table 2.3-11

. ..n.~

b- -RVALUESFORBEAVERVALLEY'S1ft (egmeter-tres/yrperuCl/sec)

Pathway : Meet-AgeGroup: Teen Nuclide- Bone: - Liver T. Body Thyroid Kidney Lung GI-LL1 1H-3 0.00E+001.94E+021.94E+021.94E+021.94E+021.94E+021.94E+02-2P-32 -3.34E+092.071+0B1.29E+0B0.00E+000.00E+000.00l+002.80E+0B g 3 b51 0.00E+000.00E+004.69E+032.60E+031.03B+036.691+037.88t+05

'1 4Mn-54 0.00E+004.95E+069.81E+050.00E+00'1.48E+060.00E+001.01E+07 5 Fe 1.71E+0B4.00E+081.54E+080.00E+000.00E+001.26E+069.45E+08

-6Co-57 0.00E+003.22t+065.40E+060.00E+000.00E+000.00E+006.01E+07 7 00-58. 0.00E+00 1.09E+07 2.52E+07 0.00E+00 0.00E+00 0.00E+00 1.51E+08 8 Co-60 0.00E+003.97t+078.95E+070.00E+000.00E+000.00l+005.17t+08 9 Zn-65 1.79E+08 6.21E+0B 2.90E+0B 0.00E+00 3.97E+08 0.00E+00 2.63E+08 10Rb-86 0.00E+003,43E+081.61E+0B0.00E+000.00E+000.00E+005.0BE+07 11St-89 2.03E+080.00B+005.83E+060.00E+000.00E+000.00E+002.42E+07 12Sr-90 5.44t+090.00E+001.34E+090.00E+000.00E+000.00E+001.53E+0B

. 13Y-91 7.53E+050.00E+002.02E+040.00E+000.00E+000.00l+003.09E+0B 14Zr-95 1.188+06 3.71E+05 2.55E+05 0.00E+00 5.45E+05 0.00E+00 8.56E+08 A(/.. 15Nb-95 1.475+068.17t+054.50E+050.00E+007.92E+050.00E+003.49E+09 6/89-.

16Eb-97 sesssssssssssssssssssssssss0.00E+00sssssssss0.00Es00sssssssst 17Mo-99 0.00E+007.03E+041.34E+040.00E+001.61E+050.00E+001.26E+05 18fc-99: 3.04E-218.4BE-211.105-190.00E+001.265-194.71I215.57E-18

~19 Ro-103 6.985+07 0.00E+00 2.98E+07 0.00E+00 2.46E+08 0.00E+00 5.83E+09 20Bu-106 1.28E+090.00E+002.09E+080.00E+003.19E+090.00E+007.94E+10 21 Ag-110s 3.61E+06 3.42E+06 2.08E+06 0.00!+00 6.52E+06 0.00E+00 9.60E+0B 22Sb-124 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 23Sb-125 0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 24fe-127: 7.075+082.51E+088.41E+071.6BE+082.871+090.00E+001.76E+09 25fe-129 7.82E+082.90E+081.24Et0B2.52E+083.27E+090.00E+002.93E+09 1 26I-131 7.59E+061.06E+075.71E+063.10Et091.83E+070.00E+002.10E+06 l 27I-133 2.61E-014.42E-011.35E-016.17E+017.75E-010.00E+003.34E-01 28Cs-134 3.60E+088.48E+083.93E+080.00E+002.69E+081.03E+081.0$E+07 29Ce-136 7.985+063.14E+072.11E+070.00E+001.71E+072.69E+062.53E+06 30Ca-137 4.90E+086.51E+082.27E+080.00E+002.22E+088.61E+079.27t+06 31Be-140 2.02E+072.47E+041.30E+060.00E+008.38E+031.66E+043.11E+07 32La-140 2.60E-02 1.28E-02 3.40E-03 0.00E+00 0.00E+00 0.00E+00 7.33E+02 33Ce-!!! 9.72E+036.49E+037.46E+020.00E+003.06E+030.00E+001.86t+07 34 Ce-144 8.72E+05 3.61E+05 4.6BE+0( 0.00E+00 2.15E+05 0.00Et00 2.19E+08 Allnuclides(exceptE-3)calenlatedperDDCHequation2.3-25 Y Of - H-3calenlatedperDDCMequation2.3-30 2-75 ISSUE 1 REVISION 3

BV-2 ODCM.

y, .Tsble2.3-12 RVALUESFORBEAVERVALLEYSITE (eg meter-stes/yr per uCi/seel

' Pathway: Heat AgeGroup: Child Nuclide' Bone Liver T. Body thyroid Eiciner Lung GI-LL1 1 b3 0.00h002.34E+022.34b022.34bO22.34bO22.34bO22.36+02-

'2P 6.29b092.94E+082.43b080.00D000.00b000.00D001.74bO8 3Cr-51 0.00b00 0.00D00 7.31bO3 4.06bO31.11bO3 7.(Ib03 3.88b05 b

( Hn-54 0.00b005.66b061.51b060.00D001.59b060.00E+004.75E+06 5fe-59 3.04bO84.91bO82.45b080.00D000.00b001.42 BOB 5.12bO8 6Co-57 0.00D004.21b068.52b060.00E+000.00D000.00b003.45b07 7 00-58 0.00D001.28bO73.91bO70.00b000.00D000.00b007.45bO7 8Co-60 0.00b004.72bO71.39bO80.00b000.00b000.00E+002.61bO8 9Zn-65 2.68bO8 7.15bO8 4.44bO8 0.00b00 4.50bO8 0,00D001.25bO8 10Rb-86 0.00D00 4.87 BOB 2.99D08 0.00D00 0.00b00 0.00b00 3.13bO7 11Sr-89 3.85bO80.00D001.10bO70.00b000.00D000.00b001.(9bO7 12St-90 7.03b090.00E+001.76b090.00b000.00E+000.00E+009.47bO7 13 D91 1.42b060.00D003.81b040,00b000.00D000.00b001.90D08 O 14Zr-95 2.09b064.59b054.09b050.00D006.57b050.00D004.7Eb08 V 15Eb-95 2.5G+069.90D057.07b050.00b009.30D050.00D001.83b09 6/89 16Nb-97 ***************************0.00b00*********0.00D00*********

17Mo-99 0.00D009.79b042.42b040.00D002.09b050.00D008.09b04 18Tc-99: 5.33E-211.05b201.73bl90.00bC01.52E-195.31E-215.95b18 19Ra-103 1.26bO80.00D004.85bO70.00b003.18bO80.00D003.26b09 20Ru-106 3.12b09 0.00D00 3.89 BOB 0.00D00 4.21b09 0.00b00 4.85b10

.21 As-110m 5.99b 06 4.04D 06 3.23D06 0.00D 00 7.53D 06 0.00b00 4.81b OB 22Sb-124 0.00D000.00b000.00b000.00D000.00D000.00b000.00b00 23Sb-125 0.00b000.00b000.00 BOO 0.00b000.00b000.00D000.00D00 24 Te-127a 1.33b09 3.59b08 1.58b OB 3.19b O8 3.80D 09 0.00 b 00 1.08 b09 25 fe-129a 1.47 b 09 4.11b OB 2 29 b OB 4.75bO8 4.33 b 09 0.00D 00 1.80 D09 26I-131 1.41bO71.42bO78.04b064.68b092.32bO70.00b001.26b06 271-133 4.84b015.99E-012.27b011.11bO29.98b010.00b002.41E-01 28Cs-134 6.35bO81.04b092.20bO80.00D003.23bO81.16bO85.62D06 29Cs-136 1.38bO7 3.78bO7 2.45bO7 0.00b00 2.01bO7 3.00b061.33b06 30Cs-137 9.02bO88.63bO81.27bO80.00D002.81bO81.01bO85.40b06 31Ba-140 3.72bO73.26b062.17b060.00b001.06bO(1.94b041.89b07 32La-140 4.76bO21.66E-025.610030.00b000.00b000.00D004.63bO2 33Ce-141 1.83b049.13b031.36b040.00D004.00bO30.00D001.14bO7 34Ce-144 1.6(b06 5.15b05 8.77b04 0.00D00 2.85D05 0.00D001.34bO8 e

.Q All nuclides fercept H-3) calentated per DDCH equation 2.3-25 b3calculatedperODCHequation2.3-30 V

2-76 ISStJE 1 REVISION 3

I..

x >

'BV-2 00CM j

a 7able2.3-13 L J R VALDIS FOR BLAVER VALLEY S17E (sqseter-eree/yrperuCi/sec)-

Pathway:CowHill AgeGroup: Adult Nuclide~ Bone Liver'T. Body Thyroid Kidner Lung GI-LLI

-1H-3 0.00b00 7.63bO2 7.63b02 7.63bO2 7.63bO2 7.63bO2 7.63bO2 2P 1.45D109.01bO85.60bO80.00b000.00b000.00b001.63D09

-3Cr-51 0.00D00 0.00b00 2.38b041.42b04 5.24bO3 3.15b04 5.98t+06 ) k'

4Mn 0.00b00 5.95bP61.13b06 0.00D001.77b06 0.00b001.82bO7 5Fe-59 2.40bO7 5.63bO7 2.16bO7 0.00D00 0.00b001.57bO71.88 BOB 6Co-57 0.00b00 9.10b051.51b06 0.00D00 0.00b00 0.00b00 2.31bO7 -

700-58 0.00D003.67b068.22b060.00b000.00b000.00D007.43bO7.

8Co-60 0.00D001.12bO7 2.46bO7 0.00b00 0.00b00 0.00D00 2.10 BOB 9Zn-65 9.80bO8 3.12E+091.41b09 0.00bO3 2.09b09 0.00b001.96b09 10Rb-66 0.00b00 2.19b091.02b09 0.00D00 0.00D00 0.00b00 4.32D08 11Sr-89 1.16b09 0.00b00 3.33bO7 0.00b00 0.00b00 0.00b001.86bO8 12St-90 3.16b100.000007.76b090.00b000.00h000.00b009.14bO8

'13 D91 - 6.78bO30.00b001.81bO20.00b000.00b000.00b003.73b06 14Zr-95 7 40bO2 2.37bO21.61bO2 0.00b00 3.72bO2 0.00b00 7.52h05 k -

15Nb-95 6.77b04 3.77b04 2.03b04 0.00b00 3.72b04 0.00D00 2.29b08 6/89 16Hb-97 2.81E-127.11b132.60E130.00D008.30E-130.00D002.62E09 17Ho-99 0.00D00 2.11bO7 4.0lb06 0.00b00 4.77bO7 0.00b00 4.88bO7 18Tc-99e- 2.83500 7.99b001.02bO2 0.00D001.21bO2 3.91b00 4.73bO3 19Ru-103 8.29602 0.00b00 3.57bO2 0.00b00 3.16bO3 0.00D00 9.68b04 20Ru-106 1.43b040.00D001.81bO30.00b002.77b040.00D009.27b05 21 Ag-110s 4.16bO7 3.84 bO7 2.28b O7 0.00D00 7.56b O7 0.00b 00 1.57b 10 22Sb-124 0.00b000.00D000.00D000.00D000.00b000.00D000.00D00 23Sb-125 0.00D000.00b000.00b000.00D000.00 BOO 0.00b000.00D00 247e-127: 3.44bO71.23bO7 4.19b06 8.79h061.40bO8 0.00D001.15bO8 257e-129: 4.95bO71.85bO7 7.84bo61.70bO7 2.07 BOB 0.00b00 2.49b08 26I-131 2.52bO8 3.60 BOB 2.06bO81.18b116.17bO8 0.00D00 9.50bO7 27I-133 3.29b06 5.72b061.75b06 8.41D08 9.99b06 0.00b00 5.1(b06 28Ce-134 3.89b09 9.27b09 7.58b09 0.00b00 3.00bo9 9.16 BOB 1.62 BOB 29Cs-136 2.23 BOB B.82b08 6.35bO8 0.00D00 4.91bO8 6.73bO71.00 BOB 30Cs-137 4.99b09 6.82b09 4.47b09 0.00D00 2.32b09 7.70bO81.32 BOB 31Ba-140 2.26bO7 2.87b041.49b06 0.00b00 9.74bO31.64b04 4.70bO7 32La-140 3.84b001.93b005.11E010.00b000.00D000.00b001.42b05 33Ce-141 3.99bO3 2.70D03 3.06bO2 0.00D001.25bO3 0.00b001.03bO7 34Ce-144 2.54b051.06b051.36b04 0.00b00 6.29b04 0.00b00 8.58bO7

,. All nuclides (except E 3) calenlated per ODCH equation 2.3-24 3r E-3calculatedperODCHequation2.3-28 2-77 ISSUE 1 REVISION 3

L

[

BV-2 ODCM-9'7 fable 2.3-14

~

RVALUESFORBEAVERVALLETSITE (sgmeter-ares /yrperuC1/seel Pathwar:CowMilt~

AgeGroup: feen Nuclide Bone Liver. T. Body Thyroid Kidner. Lung- GI-LLI 1H-3 0.00b00 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 2P-32 2.67b101.66b091.04b09 0.00D00 0.00b00 0.00b00 2.25b09 g 3Cr51 0.00D00 0.00b00 4.15b04 2.31b04 9.10bO3 5.93b04 6.97b06

'4Mn-54 . 0.00b00 9.91b061.96b06 0.00b00 2.95b06 0.00b00 2.03bO7 y 5Fe-59 4.18bO7 9.76bO7 3.77E+07 0.00E+00 0.00E+00 3.08bO7 2.31bO8 600-57 0.00D001.60D062.68b060.00E+000.00b000.00b002.96D07

'7Co-58 0.00b006.17b061.42bO70.00h000.00b000.00D008.51bO7 8Co-60 0.00b001.89E+074.26D070.00E+000.00b000.00b002.46 BOB

, 9Zh-65 -1.51b095.23b092.44b090.00b003.34b090.00b002.21b09 10Rb-86 0.00D00 3.99E+091.87b09 0.00b00 0.00b00 0.00D00 5.91bO8 ll 11St-89 2.14b090.00D006.12bO70.00b000.00 BOO 0.00b002.55bO8 12St-90 4.47b100.00b001.10b100.00E+000.00 BOO 0.00b001.25b09

.-- - 13Y-91 1.25b04 0.00D00 3.35bO2 0.00b00 0.00b00 0.00b00 5.11b06

't 14Zr-95 1.29b034.08bO22.81bO20.00D006.00bO20.00b009.42b05-15lb-95 1.16b056.41b043.53b040.00E+006.21b040.00b002.74 BOB 6/89 16Nb-97 5.13E-121.27E-124.65b130.00h001.49E-120.00b003.04bO8 17No-99 0.00D003.80bO77.25b060.00b00B.70bO70.00b006.81bO7 18te99: 4.90b001.37b011.77bO2 0.00b00 2.04bO2 7.59b00 B.9Eb03 19Ru-103 1.47bO30.00b006.30bO20.00b005.20bO30.00b001.23b05 20Ra-106 2.03b040.00 BOO 3.32bO30.00b005.0BD040.00 BOO 1.26b06 21 Ag-110m 6.87bO7 6.50b O7 3.95b O7 0.00b 00 1.24b OB 0.00 D00 1.83b 10 22Sb-124 0.00D000.00b000.00b000.00b000.00D000.00b000.00b00 23Sb-125 0.00b000.00D000.00b000.00b000.00b000.00D000.00D00 24fe-127: 6.34bO7 2.25bO7 7.54b061.51bO7 2.57D08 0.00b001.58 BOB 25 te-129 9.06bO7 3.36bO71.43b07 2.92bO7 3.79bO8 0.00D00 3.40 BOB 26 I-131 -4.57D086.39bO83.43 BOB 1.87b111.10D09'0.00b001.26bO8 27I-133 6.01b061.02bO7 3.11b061.(2b091.79bO7 0.00 BOO 7.71b06 28 Cs-134 6.76b091.5Sb10 7.38D09 0.00D00 5.06b091.93b091.98 BOB 29Ce-136 3.80 BOB 1.50D091.01b090.00D008.15 BOB 1.28 BOB 1.20 BOB 30Cs-137 9.05D091.20b104.19D090.00D004.10D091.59b091.71 BOB 31Ba-140 4.12bO7 5.05b04 2.65b06 0.00b001.71D04 3.39b04 6.35bO7 32La-140 6.89b003.39b009.0lb010.00b000.00D000.00D001.94b05 33Ce-141 7.32bO34.89bO35.62bO20.00b002.30bO30.00b001.40bO7 34Ce-144 4.67b051.93b052.51b040.00b001.15b050.00D001.17 BOB All neclides (except D3) calentated per ODCM equation 2.3-24 V D3ealculatedperODCHegntion2.3-28 2-78 ISSUE 1 REVISION 3

BV-2 ODCM'

.- Table 2.3-15 M( RVaLUESFORBEAVERVALLEYSITE leg seter-ares /yr per uti/see)

Patbver : Cow !!!!k Age Group : Child Nuclide Bone Liver f. Bodt' Thyroid lidney Lung GI-LLI 1 H-3 0.000001.57bO31.57bO31.57bO31.57D031.57D031.57D03 l

2P-32 3 Cr-51 6.59b103.09b092.54D090.00D000.00E+000.00b001.82E+09 0.00b000.00E+008.46D044.70b041.28b048.58b044.49b06 g

L 4 Ifn-54 0.00D001.48bO7 3.95b06 0.00b00 4.16b06 0.00D0f,1.24bO7 5Fe-59 9.70D071.57D08 7.82bO7 0.00D00 0.00D00 4.55D071.63D08 l

6Co 0.00D002.73b065.52E+060.00b000.00D000.00D002.24h07 700-58 0.00D00P.43E+062.89E+070.00b000,00b000.00b005.50bO7 8 Co-60 0.00E+002.94bO78.67bO70.00b000.00D000.00b001.63bO8 9Zn-65 2.95D097.87b094.89b090.00b004.96D090.00b001.38b09 10Rb-86 0.00b007.40E+094.55D090.00D000.00D00'0.00D004.76D06 11Sr-89 5.29b090.00b001.51E+080.00D000.00D000.00b002.05D06 12St-90 7.55b100.00 BOO 1.91b100.00b000.00D000.00b001.02b09-13Y-91 3.08b040.00b008.24D020.00b000.00b000.00D004.11b06 14 Zr 95 3.00D03 6.60E+02 5.88bO2 0.00b00 9.45bO2 0.00D00 6.89b05

'k . 15Nb-95 2.61b051.02b057.26b040.00D009.54D040.00D001.88 BOB 6/89 16 Nb-97 1.25b112.25b121.05b120.00D002.50E-120.00h006.9(E-07 17 Ifo-99 0.00b006.92bO71.71bO70.00D001.48D080.00b005.72D07 18 fe-99: 1.12b012.20b013.65bO20.00D003.20bO21.12b011.25b04 19 Ru-103 3.49bO3 0.00D001.34E+03 0.00D00 8.78D03 0.00b00 9.01b04 20Ru106 6.49b040.00b008.10bO30.00b008.76D040.00 BOO 1.01b06 21 Ag-110s 1.49 BOB 1.01bO8 6.05D07 0.00b001.87 BOB 0.00b001.20b10 22Sb-124 0.00b000.00b000.00D000.00b000.00b000.00D000.00D00 23Sb-125 0.00b000.00E+000.00b000.00b000.00D000.00b000.00D00 24 Te-127a 1.56b OB 4.21bO7 1.8Eb O7 3.74 D 07 4.46D 08 0.00b 00 1.271+08 25 fe-129s 2.23DOB 6.24bO7 3.47bO7 7.20b O7 6.56D 08 0.00D 00 2.72 D06 261-131 1.11D091.11b096.33bO83.68b111.83b090.00D009.92bO7 27 b i:3 1.46bO71.81bO76.83b063.36b093.01bO70.00b007.2BD06 28 Cs-134 1.56b10 2.56b10 5.40b09 0.00D00 7.03b09 2.85b091.38 BOB 29Ce-136 8.58 BOB 2.36h091.53b090.00D001.26b091.87bO88.29D07 30 Ce-137 2.18b102.09b103.08b090.00D006.80D092.45b091.31 BOB 31Ba-140 9.94bO7 8.71b06 5.80D06 0.00b00 2.84b04 5.19D04 5.04bO7 32La-140 1.65b015.77D001.94b000.00D000.00b000.00b001.61D05

.33Ce-141 1.80D048.99bO31.34b040.00D003.94bO30.00D001.12bO7 34Ce-144 1.15b06 3.61b05 6.15b04 0.00D00 2.00D05 0.00b00 9.41D07 All cuelides (except H-3) calculated per ODClf equation 2.3-24 V li-3 calculated per ODCt! equation 2.3-28 2-79 ISSUE 1 REVISION 3

N .

g

. .- fable 2.3-16

O 1

'RVALUESFORBEAVERVALLEYSITE (sg meter-erea/yr per uCi/sec)

Pathway:CowMilk AgeGroup: Infant l Nuclide~ Bone- Liver T. Body Thyroid Eldney Lung GI-LLI 1 b3 'O.00E+002.38bO32.36E+032.3SbO32.38bO32.3Sb032.32bO3 2P-32 1.36b117.99b095.27b090.00b000.00D000.00D001.84b09 3Cr-51 0.00b00 0.00D001.34b05 8.75b041.91b041.70b05 3.91b06 3

4 !!n-54 0.00b002.76bO76.25b060.00D006.11D060.00D001.01bO7 5fe-59 :1.81 BOB 3.16bO81.25b060.00D000.00b009.35bO71.51bO8 60057 0.00b006.36b061.03bO70.00 BOO 6.00b000.00D002.17bO7 7Co-58 0.00b001.89bO74.70bO70.00D000.00D000.00b004.70bO7 800-60 0.00D006.00bO71.42b080.00D000.00b000.00D001.43b08 9Zn-65 3.97D091.36b106.27b090.00b006.60D090.00D001.15b10 10Rb-86 0.00D001.88b109.2Bb090.00D000.00D000.00b00(.81D06 11Sr-89 1.01b10 0.00D00 2.89b08 0.00D00 0.00D00 0.00b00 2.07 BOB 12St-90 8.22b100.00b002.09b100.00D000.00D000.00D001.03b09

'13Y-91. 5.79b040.00D001.54bC30.00D000.00b000.00b004.15b06 14Zr-95 5.33b031.30bO39.22bO20.00D001.40bO30.00D006.47b05

\ 15 lib-95 4.87D05 2.0lb051.16b05 0.00b001.44b05 0.00b001.69D06 6/89.

16Nb-97 2.63b!!5.62E-122.03E-120.00b004.39b120.00b001.77b06 17 h-99 0.00D001.77D083.45bO70.00D002.64bO80.00b005.83bO7 18Tc-99m 2.34D014.82D016.21bO20.00b005.19bO22.52b011.40b04 19Ru-103 7.06bO30.00b002.36bO30.00b001.47b040.00b008.59b04 20Ru-106 1.34b050.00D001.67b040.00b001.5BD050.00b001.01D06 21 Ar-110m 2.75 BOB 2.01bO81.33bO8 0.00D00 2.88b08 0.00 BOO 1.04b10 22 Sb-124 0.00b000.00D000.00b000.00b000.00b000.00D000.00D00 23Sb-125 0.00b000.00D000.00D000.00b000.00D000.00b000.00D00 24 Te-127e 3.16bO8 1.05 b OB 3.83b O7 9.14b O7 7.79 b OB 0.00b00 1.2Eb08 25fe-129: 4.58b081.57bO87.06bO71.76bO81.15b090.00D002.74bO8 26I-131 2.31D09 2.72b091.20b09 8.95b113.16D09 0.00b00 9.72bO7 271-133 3.06bO7 4.49bC71.31bO7 8.17b09 5.28bO7 0.00D00 7.60D06 28Cs-134 2.51b10 4.69b10 4.73b09 0.00 BOO 1.21b10 4.95b091.27b08 29Cs-136 1.68b094.93h091.84b090.00b001.97D094.02 BOB 7.4SbO7 30Cs-137 3.4Bb104.07b102.89b090.00D001.09D104.43D091.27bO8 31Ba-140 2.05bO82.05b051.05bO70.00b004.86b041.26b055.02bO7 32La-140 3.45b011.36b013.50D000.00b000.00D000.00D001.60D05 33Ce-141 3.57b04 2.18b04 2.57bO3 0.00b00 6.72bO3 0.00b001.13bO7 34Ce-144 1.65b06 6.75b05 9.25b04 0.00D00 2.73b05 0.00b00 9.47bO7 All nuclides (except b3) calenlated per ODCM equation 2.3-24 y b3calculatedperODCHequation2.3-28 2-80 1SSUE 1 REVISION 3

T I

BV-2 ODCM Table 2.3-17.

R VALUES FOR M AVER VALLEY SITE

'(egseter-stes/yrperuCi/ sect Pathway.: Goat Hilk AgeGroup: Adult livelide Bone Liver f. Body Thyroid Eidney Lung GI-LLI 111-3 0.00b 00 1.56bO3 1. 56bO3 1. 56bO3 1.56bO3 1.56bO3 1.56bO3 2P-32 1.74b101.0Eb09 6.72 BOB 0.00b00 0.00D00 0.00D001.96b09 jL 3Cr-51 0.00D00 0.00b00 2.85bO31.70bO3 6.28bO2 3.78bO3 7.17b05 4Mn-54 0.00b00 7.14b051.36b05 0.00b00 2.12b05 0.00b00 2.19b06 5Fe-59 3.12b057.32b052.81b050.00b000.00b002.05b052.44D06 6C0-57 0.00b001.09b051.82b050.00b000.00D000.00b002.77b06 7C0-58 0.00D004.40D059.86b050.00D000.00D000.00D008.91b06 8Co-60 0.00D001.34b062.96b060.00D000.00D000.00b002.52bO7 9Zn-65 1.18b083.74bO81.69D080.00D002.50D080.00D002.36bO8 10Rb-86 0.00b002.63 BOB 1.22D080.00D000.00D000.00D005.18a+07 11Sr-89 2.43D09 0.00b00 6.99bO7 0.00b00 0.00b00 0.00b00 3.91bO8 p 12St-90 6.64b10 0.00D001.63b10 0.00D00 0.00b00 0.00D001.92b09 13Y-91 8.14D020.00b002.16b010.00b000.00b000.00b004.48D05

- () ' 14Zr-95 8.87b012.85b011.93b010.00b004.47b010.00b009.02D04 15Nb-95 8.13bO34.52bO32.43b030.00D004.47bO30.00b002.74b07 6/89 16Nb-97 3.38E-138.54bl43.128-140.00b009.96E-140.00b003.15E-10 17 Mo-99 0.00D00 2.53b06 4.81b05 0.00D00 5.72b06 0.00D00 5.66b06 18Tc-99: 3.39b019.59E-011.22b010.00D001.46b014.70E-015.67bO2 19Ru-103 9.95E+010.00D004.29b010.00b003.80bO20.00b001.16b04 20Ru-106 1.72bO3 0.00b00 2.18bO2 0.00b00 3.32bO3 0.00b001.11b05 21 Ag-110s 4.99b06 4.61b06 2.74006 0.00D00 9.07b06 0.00b001.8Eb09

- 22Sb-124 0.00b00 0.00b00 0.00D00 0.00b00 0.00D00 0.00b00 0.00b00

' 23Sb-125 0.00b000.00D000.00b000.00b000.00b000.00h000.00D00 24fe-127 4.13b061.48h06 5.03b051.05b061.68bO7 0.00D001.38bO7 25Te-129s 5.94b062.22b069.41b052.04b062.488+070.00 BOO 2.99bO7 261-131 3.02 BOB 4.32bO8 2.48bO81.42b117.40 BOB 0.00b001.14 BOB 271-133 3.95b066.87h062.09b061.0lb091.20bO70.00b006.17b06 28Ce-134 4.67bO81.11b099.09 BOB 0.00b003.60D081.199081.95bO7 29Cs-136 6.70bOS 2.65b091.90D09 0.00b001.47b09 2.02bO8 3.0lbO8 30Ce-137 1.50b10 2.05b101.34b10 0.00b00 6.95b09 2.31b09 3.96bO8 31Ba-140 2.74E+06 3.44bO31.79E+05 0.00E+001.17bO31.97bO3 5.64b06 32La-140 4.60E-012.32b016.13b020.00b000.00b000.00b001.70b04 33Ce-141 4.79b023.24bO23.68b010.00b001.51bO20.00D001.24b06 34Ce-144 3.05b 04 1.27 b 04 1., h03 0.00b 00 7.55 b O3 0.00b 00 1.03b O7 3r 111 nuclides (except H-3) calcu. ,ed per ODCM equation 2.3-24 b3calculatedperODCHequation2.3-28 ISSUE 1 2-81 REVISION 3

)h.

BV-? ODCM fable 2.3-1B l

RVALUESFORBEAVERVALLEYSITE (egmeter-ares /yrperuCi/sec)

Pathway:GoatHilk AgeGroup: feen-p Nuclide Bone Liver T. Body Thyroid Eidney Lung GI-LLI 1

1 F3 0.00b00 2.03bO3 2.03bO3 2.03b03 2.03b03 2.03bD3 2.03b03

! 2P-32 3.21b101.99b091.24b090.00D000.00b000.00bD02.70D09-3Cr-51 0.00D000.00D004.98b002.77bO31.09bO37.11bO38.37b05 .

N 4Hn-54 0.00D001.19b062.36b050.00D003.55b050.00b002.44b06 5Fe-59 5.44b051.27b064.90b050.00b000.00b004.00D053.00b06=

6Co-57 0.00b301.92b053.21b050.00b000.00b000.00b003.57b06 7Co-58 0.00D007.40D051.71b060.00b000.00b000.00b001.02E+07 8 Co-60 0.00b00 2.27b06 5.11b06 0.00b00 0.00D00 0.00b00 2.96bO7 9Zn-65 1.81 BOB 6.27bO82.93D080.00b004.01bO80.00D002.66bO8 10 Rb-86 0.00b00 4.79b08 2.25 BOB 0.00b00 0.00b00 0.00b00 7.09b07 11Sr-89 4.49b090.00D001.29b080.00E+000.00b000.00D005.35006 12Er-90 9.39b100.00b002.32b100.00b000.00D000.00b002.64b09 13Y-91 1.50bO30.00b004.01b010.00D00fr.00D000.00D006.14b05

\ -

14Zr-95 1.55bO2 4.90D013.37b010.00b00 7.19b010.00bhD 1.13b05 15Hb-95 1.39b047.69bO34.23b030.00D007.45bO30.00b003.29b07 6/89 16Nb-97 6.15b 13 1 53b13 5.57E-14 0.00 b00 1.79b 13 0.00b00 3.65E-09 1780-99 0.00b00 4.56b06 8.70b05 0.00b001.04bO7 0.00D00 8.17b06

'1B fe-99: 5.88b011.64b00 2.13b010.00b00 2.45b019.11E-011.08bO3 19Ru-103 1.77bO2 0.00D00 7.56E+010.00b00 6.24bO2 0.00b001.4Bb04 20Ru-106 2.44bO3 0.00D00 3.98bO2 0.00b00 6.10bO3 0.00b001.52b05 21 Ag-110s 8.24b06 7.80b06 4.75b06 0.00b001.49b0f 0.00D00 2.19b09 22Sb-124 0.00b000.00b000.00b000.00b000.00D000.00b000.00D00 23Sb-125 0.00b00 0.00b00 0.00D00 0.00b00 0.00D00 0.00b00 0.00b00 24fe-127 7.61b06 2.70Et06 9.05b051.81b06 3.0BbO7 0.00b001.90bO7 25 fe-129s 1.09bO7 4.03E+061.72b06 3.51bo6 4.55bO7 0.00b00 4.08bO7 261-131 5.46 BOB 7.67bO8 4.12 BOB 2.24b111.32b09 0.00b001.52 BOB 271-133 7.21b061.22bO7 3.73b061.71b09 2.15bO7 0.00b00 9.26b06 28 Cs-134 8.11 BOB 1.91b09 8.86 BOB 0.00D00 6.07bO8 2.32D08 2.38bO7 29Cs-136 1.14b09 4.49b09 3.02b09 0.00b00 2.44b09 3.85 BOB 3.61 BOB

, 30Cs-137 2.71b10 3.61b101.26b10 0.00b001.23D10 4.77b09 5.14bO8 31Ba-140 4.94b06 6.06bO3 3.18b05 0.00b00 2.05bO3 4.07bO3 7.62b06 32La-140 8.27b014.06E-011.08b010.00b000.00b000.00b002.33b04 33Ce-141 8.79bO2 5.81bO2 6.74b010.00b00 2.76bO2 0.00b001.6Bb06 34Ce-144 5.60D04 2.32b04 3.01bO3 0.00b001.39b04 0.00D001.41bO7

~

V All nuclides (except H-3) calculated per ODCH egnation 2.3-24 F3calculatedperODCHequation2.3-28 ISSUE 1 2-82 REVISION 3

--__.______________._-_---_-___a

p BV-2 ODCM

. Table 2.3-19.

RVALUESFOREEAVERVALLEYSITE tagseter-ares /yrperuCi/eec)

Pathway : Goat Milk Age Group : Child Euclide Bone liver T. Body Thyroid Eidney Lung 'GI-LLI 1H-3 0.00b00 3.20bO3 3.20E+03 3.20bO3 3.20bO3 3.20bO3 3.20bO3 2P-32 7.91b10 3.70E+09 3.05b09 0.00D00 0.00E+00 0.00b00 2.19b09 g 3Cr-51 0.00b000.00b001.02b045.64bO31.54bO31.03b045.39b05 4 Mn-54 'O.00D001.78b064.74b050.00b004.99b050.00b001.49b06 5 Fe-59 1.26b06 2.04D061.02b06 0.00b00 0.00b00 5.91b05 2.1Ib06 6C0-57 0.00b003.27b056.63D050.00b000.00b000.00b002.6Eb06 700-58 0.00D001.13E+06 3.46b06 0.00b00 0.00b00 0.00b00 6.60b06 8Co-60 0.00D003.53b061.04bO70.00b000.00D000.00b001.95bO7 9Zn-65 3.54 BOB 9.44bO85.87 BOB 0.00b005.95bO80.00b001.66D08 10Rb-86 0.00b00 8.88bO8 5.46bO8 0.00b00 0.00b00 0.00D00 5.71bO7 11Sr-89 1.11b10 0.00b00 3.1?bO8 0.00D00 0.00b00 0.00b00 4.30 BOB 12 St-90 1.59b110.00D004.02b100.00b000.00 BOO 0.00D002.14b09 13Y-91 3.70bO3 0.00b00 9.89b010.00b00 0.00D00 0.00D00 4.93b05

\ -

14Ir-95 3.60bO2 7.92b017.05b010.00D001.13D02 0.00D00 8.27b04 15 Nb-95 3.13D041.22b04 8.71bO3 0.00D001.14E+04 0.00b00 2.25bO7 16 Eb-97 1.49b122.70E-131.26E-130.00D002.99E-130.00b008.338-08 6/89 1750 0.00b008.30b062.05b060.00D001.77bO70.00b006.87b06 18fe-99: 1.35b002.65b004.39b010.00b003.84b011.34b001.51bO3 19 Rn-103 4.18bO20.00D001.61bO20.00D001.05bO30.00b001.0BE+04 20Hu-106 7.79b030.00D009.72bO20.00D001.05b040.00b001.21E+05 21Ag-110e 1.79bO71.21bO79.65b060.00b002.25bO70.00b001.44b09 22Sb-124 0.00b000.00b000.00b000.00b000.00D000.00D000.00b00 23Sb-125 0.00b000.00D000.00b000.00b000.00D000.00b000.00D00 24 fe-127e 1.BBbO7 5.05D06 2.23b06 4.48b06 5.35bO7 0.00b001.52bO7 25 fe-129e 2.6Sb 07 7.48 b06 4.16b 06 8.64b06 7.87 b O7 0.00D 00 3.27 b O7 26I-131 1.33b091.34b097.60 BOB 4.42b112.19b090.00D001.19b08 27 b 133 1.75b O7 2.17 b O7 8.20b 06 4.03 b 09 3.61b O7 0.00b 00 8.73b 06 28Cs-134 1.87b09 3.07b09 6.46bO8 0.00b00 9.52 BOB 3.42bO81.66D07 29Cs-136 2.58b09 7.08b09 4.5Bb09 0.00b00 3.77bo9 5.62 BOB 2.49b08 30Ce-137 6.54b10 '6.26b10 9.24b09 0.00E+00 2.04b10 7.34b09 3.92 BOB 31Ba-140 1.19bO71.05b06 6.96b05 0.00D00 3.40bO3 6.23bO3 6.04b06 32 La-140 1.96b006.920012.33b010.00 BOO 0.00D000.00b001.93b04 33 Ce-141 2.16bO31.0BbO31.60bO3 0.00b00 4.73b02 0.00b001.35b06 34Ce-144 1.38b05 4.33b04 7.37bO3 0.00b00 2.40D04 0.00b001.13b07 all nuclides (except H-3) calenlated per ODCH eguation 2.3-24 R-3calenlateiperDDCHegnation2.3-28 2-83 ISSUE 1 REVISION 3

e I:. i BV-2 ODCM 4

Table'2.3-20 RVALUESFORBEAVERVALLEYSITE (egmeter-ares /yrperuCi/see)

Pattvar : Goat Hill

' Age Group : Infant lluelide Bone Liver f. Body Thyroid Eidney Lung GI-LLI 1H-3 0.00D00 4.86D03 4.86bO3 4.86bO3 4.86bO3 4.86bO3 4.66bO3 2P-32 1.63E+119.59b096.32b090.00D000.00D000.00b002.21b09

.J (

3Cr-51 0.00b000.00b001.61b041.05b042.29D032.04D044.69b05 4Mn-54 0.00D00 3.31b06 7.50b05 0.00b00 7.33b05 0.00b001.21b06 I

5Fe-59 2.35b064.11b061.62b060.00b000.00b001.21b061.'96D06 600-57 0.00b00 7.64b051.24b06 0.00D00 0.00b00 0.00b00 2.60D06 7 C0 0.00D002.26b065.64b060.00b000.00D000.00D005.64D06 8Co-60 0.00D007.20D061.70D070.00b000.00D000.00D001.71bO7 9Zn-65 4.76D081.63b09 7.53b08 0.00b00 7.92bO8 0.00b001.36D09 10Rb-86 0.00D00 2.25b091.11b09 0.00D00 0.00D00 0.00b00 5.77bO7 11St-89 2.11D10 0.00E+00 6.06bO8 0.00b00 0.00D00 0.00b00 4.34bO8 12St-90 1.73D110.0GD00 4.39b10 0.00b00 0.00b00 0.00D00 2.16b09

( 13Y 6.94bO3 0.00b001.85bO2 0.00D00 0.00b00 0.00b00 4.56b05 14Zr-95 6.40D021.56bO21.11bO20.00b001.66bO20.00b007.77b04 15Nb-95 5.84b042.41h041.39b040.00D001.72b040.00D002.03bO7

, 6/89 16ib-97 3.16E-126.74b132.43b130.00b005.27E-130.00b002.13bO7 17Ho-99 0.00b002.12b074.14bo60.00b003.17bO70.00b006.99b06 IBTe-99: 2.81b00 5.79b00 7.46b010.00D00 6.23b013.03b001.6EbO3 19 In-103 8.47bO2 0.00000 2.83bO2 0.00b001.76bO3 0.00b001.03b04 20 Rn-106 1.60b04 0.00D00 2.00bO3 0.00b001.90D04 0.00b001.22b05 21 Ag-110s 3.30 D07 2.41b O7 1.60b O7 0.00b 00 .$.45b O7 0.00b00 1.25b 09 22Sb-124 0.00b000.00D000.00D000.00b00L.00b000.00b000.00D00 23Sb-125 0.00D000.00D000.00b000.00b000.00D000.00b000.00D00 24fe-127 3.80bO71.26bO7 4.59b061.10bO7 9.35bO7 0.00b001.53bO7 25 fe-129s 5.50 D 07 1.89 b O7 8.47b 06 2.11b O7 1.38 BOB 0.00b00 3.2Bb07 261-131 2.77b09 3.27b091.44b091.07b12 3.82b09 0.00b001.17bO8 27I-133 3.70bO75.39bO71.58bO79.80D096.34bO70.00D009.12b06 28Ca-134 3.02b095.62b095.680060.00b001.45b095.93b081.53bO7  ;

29Ca-136 5.03b091.48b105.52b090.00b005.90D091.21b092.25 BOB 30 Cs-137 1.04b111.22b118.66b09 0.00000 3.28b101.33b10 3.82bO8 31Ba-140 2.45bO7 2.45b041.26b06 0.00b00 5.83bO31.51b04 6.03b06 32La-140 4.14b001.63D004.191-010.00b000.00bD00.00b001.92b04 33Ce-141 4.29bO3 2.62bO3 3.0Bb02 0.00D00 8.07D02 0.00b001.35b06 34Ce-144 1.96b05 8.11b041.11b04 0.00b00 3.28b04 0.00D001.14D07 p

Allnuclides(exceptH-3)calenlatedperODCHeguation2.3-24 H-3calculatedperODCHequation2.3-28 ISSUE 1 2-84 REVISION 3

. l.

) * -

C3 en .O.e= .O = =O= O= O = O. . =.O . O =. .mo -OO ==O==* .O==.O= .O. .O .O.

~

t I I'5 4 4 9 $-t 0 8 8 8' l' 3 3-8 tal tel Im3 tal In3 Im1 in3 ta3 ena las in3 tal sa3 in3 W an2

.. A ". en 4 N O' O == N

\

[;

f. en. ' . e.=* . W 4.= e. . C. 4. .Om.ON.en. M*=sO. .

CN.=.===== PaC .= # e. en. N e. re. 4. .

' NJ~

4 N P'l @ f*'t en M N == N

. . M en

= O C COCOCOCO se .-

4 .O .O .C.a .O.=. .C.=.O.= a == a == .= .=

8 8 8 8 9 t I I e . I B-8 I 8 4 ' .s5-a=e I tal est W Bn1 tua an3 Im3 In3 Im3 te3 In3 an1 In1 Inl tal In3 -

NN@M- ja3 M M @ en N -- =lp e.4

=

C. -@ .; en. e.r=..enen M On a 4 4 r. N. #.s ==* e. eD. en. sp3

. . , *=. p=*. .=

30 in3 N 4 5 @ .a M N N N

• N N ==*

• N ** '

4 H IIC O* OOOOO -.

4 .C =O = .C .O. =c = C.

ca.= O.a.C.O==C .= a f- 8 8 B 9 I 8 I I I I I t 0 I t S - an3 Ina an3 W In1 W In3 '.a3 In3 In3 tal W In3 In3 en2 ta3 i

06 M M e M en e C so e O O @

en. ' N. N..==. N. e. O .O @* @a. e .e N. @e* . . 06 en O.* @. ==. .=* **

. M M en @ @ N en 4 P't M =* N N N == N N N b i w

'n 6 Cr

• O O e osonO O O O O O O O O O O

'M ====0CCw======.==*========

e. m.

n.

8 8 4 8 9 0 t a f-t i e i e t- e 9 In3 Ea3 an3 til In3 fa3 an2 Ba3 ta3 Ina En3 in3 Em3 an3 in3 sa3

- .r ,lr .g e 4 en s* == == en se en N en N 4 N M f*lNr== et Q W N. r=. N. N. O, 4. @. N. =*. en. en. e. M. CP.t -. .

,,,,,C n O.

.- M N

.= ==* M .a -@ == = == en en 4 en N == s*t '

t/' A. K g

w C C*

• • • O eOeO#5O Os g.=

sal O n

fan == O OCP= =* == O O==O== O Oe'= Oa .O ===.=.= OOO g = 8 8 8 6 8 8 8 8 8 I I I 4 s t 4

< 6 # 1 W In3 Inl In1 W In3 In3 Ea3 Im3 En3 W tal ina la3 In3 In3 C O #== 4 et @ M r==.a N O 4 Ose d 4 M g x O

(%

g a e en. N. O. 4. N. M. C. N. =*. en. o. e. 8"1 . . .@ == O.s .

== -

.= 6 M N en == == == == .= 80 r=* On 4 M N 4 en 4 4

• U

-D;a eat h.=

/; O 0 O 3

en

• O 96 OnUn96On e @te O O O O O O O en co

.C N g en N == 0 O C O O O O O == -=* == == == == == a.

• =.* 8 8 8 8 8 a 8 e t I I e I I t e N j

=,,,, 'N W wA CL.

O I gua in WW

.an1 = r=. sal In3 e NW@ WO In3 ** anB 4 MIn3 enIn3 4 W @ In3 an1 1

6e N M M 8 M m.= g/3

.> S, q

g g,3 g C. == . M. @. M. #.4 4. =*. O. 4".% . .r== @ 4. @. M. o. e.

30 O N eD == N N *= == == =* ** en N en @ r N en ,

p= m LP 6= <

ZW & C*

w3 .E CPn CPt e e cps Os On @* 06 O O e p. O CP6 O yw w N O O O O O O O O O ==

• O O == O =*

x 8 4 4 3 e a B 8 I 4 I e I 8 I i g/:

mO O $ In3 In3 In3 la! lal In3 la3 In3 tal la3 tal sa3 Ea3 la3 la3 ta3

& @ en N N N @ N 1D 0 4 ==

w g,,)s.a3 c(

i .-

e en. r=* en. @. N. *=.

. . 4 O.s @ == . . m.

. ri. 4 M == 80 N. O. O.r

= => W == == N M sat ri N == == N e a0 == == 4 == CP4 L4 U 3 C 8 en

&a.1 Lal W

• Ob Oh 04 04 On On On Oh CPn C Uh cps CPn O O 04 3.=

== t/; e == O O O O O O O O O == C O O == == O g/: D *=8 0 t t e I e I e 8 9 1 8 4 6 6 i Q R la3 In3 la3 in3 fa3 ta3 la3 Ln3 In3 tal la3 lal tal in3 In3 In3

>OD 4 eD N 05 cps O N == @ M en @ 4 Ch @ M t.=

ra.: =.a

,; O. ==. O.s M. @. O. 4. en. C. . co. en. M. co. O. eD. @.

3k =* M ** == 89 4 4 M f*l r*l r== == == === M N *

< E

>0 a O. Os cb 06 cm e ch e cps cps cps Os cps os C O cb x *= 0OOOOOOOOOOOO~~O ux $ e a e s e e a a e e a a e s a

>c 1 la3 la3 tal La3 Ia3 ta3 Lal W ga3 taa la3 ta3 ga3 ta3 la3 la3

<6 O4 r= en so en = @ - Os en M en M=ecm en t,.:

@@ . en en N EO 4. @. EO. e en. @. O.g . O. O.

tr,, en. . e . . e O GD en ** ==

• r. @ 4 4 N en @ N 4 4 N en

• O O 04 06 Os O CPS 04 Os se eD CP* O O O O O == == Q O O == O O O O O O *= == == ==

0 0 I e s I e I e e e a i e 1 0

$ ta3 la3 la3 la3 tal saa saa ta3 In3 In3 En3 r=. laa saa ta3 tal tal O@MMenN@ N 8O 4 Ch ep 4 N

.a

o. O. @. O. *=. f"). e. 'a=.N. O. 4. e. en. r= en. en. .O.?. .

O @ @ *=* ==* '= m N N M * . * ='a M 4 t M O tal la3 saJ 4a3 3 3 3 3 1

- zwz mwm m3m zaz

. u Z Z Z 143 w ta3 in tra ut t/3 t/) 333mZ 48 t/3

I 6

O*

OC en =ms == = .O - O.= C O O Oe===n

== == O O == .C==O==D.O O.t O w -

t 9 8 8 8 3 #-I I e 9 9 9 8 8 in - ta3 c

'i 0

ep laa N In3 @ Os ta3 ta3N nin3es Ea3NIn3 @ la3 OsMla3 menen ta3 tal in3 an34,.la3 Ea3

.eA. rat . N. @. M. M. N. O. en. O.s M. O.s N. == m. 4. O.=

4 N M 4 en M .= N -. = == == N M 4 g N .

. M e6 .g

=

0= .C = == O==O .O .O = ==O. O O .O

.O.=== =. O.=

= .O .O .O =. O - # O 4 8.O t t I N 8'.4 8 8 9 9 9 0 I 8 en! Sal a3 taa la3 W ta3 h3 ta3 la3 In3 la3 W *.a3 In3 In3  : I8I E

- e 4 Os eD en eD #s en Os O en e en Os M Os ON

=

Mg-O. - O.s O.s. @ en. O. N. en. e. M. M.. M. . 4*t W m. e. en.

4 NMe@ 4 NNmN~NMMenM g g O* O Os O OO .O .O .O.=.O s= =O == O

=O O.= O =

4 == =0Os O O. .

8 8 8 1 i 8 8 8 t i I 8 9 eI

'8 - tal tal la3 W In3 in3 In3 In3 In3 an3 Id h3 In3 ta3 W Ia3 N

=

O N N == @ 4 Os N Os e e en N @ .* 4 g

g "y y en. O. O.s.W C. C. ==. =.= M. e. M. N. en. en. e.s N. 80. -.

M 44hmnMMNNNM44n~4

=

^e A Ow

= O.'=O = ==O O== em c c.O *-

% ,g g e.t =

OO.=esOOs O == O O== O ==

O= .O =I I O 1 8 4 4 4 8 wo' i I f I 8 9 i

.n I in3 la3 In3 an3 in3 In3 Im3 tal an3 Int tal In3 In3 la*. Ia3 in3 g, e @ en O == 4 en.N es @ N sc > N @ @ en

== . op..N...= en. N.

g .e. O. . M. C. M. en. O. - *. O.s eD. C.

g A ==* M en @ == == @ 4 4 N M M 4 no @ =* ==* 4 p E le3 la g 6, a.C*

C*

M .O= == O eO Os O == O =O== O .O O O O O O Os e O

=========OO

4 p,.

• 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 c% e 3 in3 En3 tal laa le3 In3 In3 In3 Ina W h3 tal la3 In3 In3 la3 Z he m C m4m@ m 4 en N == @ N e @ an C C O .c o en. en. en. en.

e'==

. en. Os em. 4. m. O. @. 4. M. en. ==. O.

==d h@mmet 44D4n@ @mNm ,

'"8 -

saa en U

U O

N en N

N g,

g A e=3

• Os Os @ Os Os O O O O O a O==OsO eOosOs O O os O N

==

8""

g

• = O4 O0 OeO4Ot==I - 8==1==0 =8 8 8 4 4 8 A @'

m. g gn,3 g 0 I In3 Ina In3 ta3 en3 la3 an3 h3 Ina an3 an2 In3 taa en1 ans ta3 e N 4 O N @ N Os 4 ep == O Os == Os eD to N Eh an k 4.

M N p4 c C. O. N. N. en. M. 4. M. N. ==. W. C. N. ==. N. e. N.

g g gg O N ==* == N N em W us @ eD 'en W .* -=* N N =a g a g,,3 g U

"> E > taa EQ < = 8 O" *'

i= H # '

Z W sal

=.3 & N O'8'*

a OO s a'O'O'8'* e Oa Oa Oe*OaO'O O ==8'OC'*

s e a0 a0 e e*O O O

a gy 0 4

.In3 e g i,3 g u

• Osta3 M 4an! N In3 N enfa3 enIn3 @ la3 h3 la34la3 m r===N O@ In3NInt an3 la3 las ta3 4 e en. ID. e. 4, @. ==. 4 4. . N. O.s 4 80. @. @. eD. ==. .

" " " " " " N '" ** "" " ep == == N M 4 N g

2 ,E # ""

OD U .'*

U e e g u

• Os e Os Os e Os os Os e as os Os e Os e Os g,3 g y e

=8

== QQQOOOOOOCOOOOOO e s 4 e a a a e a a I 6 6 e s a m O 1 lal Int In3 la3 In3 In3 int ta3 In3 Ea3 ta3 tal sn3 In3 tea ta3 g3 o e m == == Os e e @ @ O N 4 N s"'t so m yp gg C. Ne M. N. en. ne en. en . O.. N. @. @.. r*n n. 4. @. n.

g=

• r") e") @ @ f") N N N N ==. N r"t .T @ (D f"s JH

<Z

• mmMMCmmmmm@@@ @ @ m g OOOOOOOOOOOOOOOO e # 8 9 3 0 t I 8 4 6 i e t i e yg 8 '8 3^8 3*8 L's saa taa in3 sa3 an3 in3 tal las an3 ta3 tal la3

> O e'"'l m N enen O O N N N O r== r") O ** 4 46 y eO. r==. ("%. N. M. C. @. r=. . m. d=1 . en. .f*1 O.s. ==* @. O. O.

g m == *= ==* en en 4 @ 4 en M == .= N Os O r==

en

• EO ep eD ED e to up ED to to to 80 eD EO r== eD C OOOOOOOOOOOOOOOO 8 8 8 e s e t a e I e I e e t 8 ta3 In3 ta3 In3 In3 In3 ta3 In3 le3 ts*. ta3 ta3 In3 ta3 saa ta3

• eo N N m op M ps e W == @ O e en as N O. 4 4. f*4 .h. O. N. N. W. eO. @. O. @, 4. N. ==.* N.

C 4 e N 5 4 M M t*8m N M 4 @ m .= m i l

b.

O tal sa2 tal taa 3 3 3 3

. a -

Z u) sn3 us en 3 in 32 U Z b'- la.1 In3 Ea3 En Er3 (D th M 3 3 ZZ e

tn

- - . - _ _ . - _ _ . _ _ _ _ . _ - - - _ - _ _ _ _ - . - - . - - - - _ . _ _ _ . __.__ _ _ _ - . _ . _ - - - _ _ _ . . . _ - - _ __ _ _ _. ---_:--._ . _ . - - . = __________.___-_-A

s t 4 O-en .O

= .= O .O. .O .O.O. C. O .O..O .C .O. O .= O .O. O .

e 0 0 0 g I e 3 I I- 0 9 8 ? I e-

/ /N -  :

s ina :n3 W W in3 :s3 W W an3 inn ont saa saa 3. inn int et 1/ * - @ N@ e N M (b N @ 9% m N e.

4 D)o/ en. M. N.-@. m. n. ED. C.=M. N m 4 @ N O.n m. (b. h. .n. en = eaP. rm 4 N m 4 e m N .= ==

.m' c* E CO .C .=

O .C .O .C = ,O .O O .C .O.==C O .C O

= .= .= O 4 g e - sia 8 8 8'8 8'S 9 4 6 8 4 4 9 8a3 m 8 Int ena W In3 Ist W In3 Int anB tea tal Im3 Im3 W ta3 W .Oee

== 4 d> e en e en en @* O. en e en ** m e to >

e.n sh. @. en. O. N. en. ED. e. r=. m. m. a0. r= e. en. 44 In3 C. NW' 4 N m en @ 4 N N - N .= N c"t M en re. M O. OO .O4> O. O.O.= et O

.g - g. . . O .O O=.O. O..O.O O 4 4 8 8 I 9 4 0 t40 0 I's t

" l WW dWWWWWWWWWWWWW N 4 gw y en. O O. #.sN% .=O.@.=. 4.. tb m.@em.*m* 4 en N @. N. en. eD. o.n N

. O.

n[

• m 4 4 N .m e n A N N N M 4 4 eO .= 4 w

• l.e.

• ' in

, .C -Op O

O e e .O. -O .O.e - O O .O - c .cCO- ee O

o 8 8 8 8 8 8 8 8 8 8~8 8 8 8 8 8 3 to g ,, en, 9 g a e @W 3 3 W W In3 f.3 In3 InB Im3 8 3 W sua an3 an2 ens anen O .=

p .e. O. .*. m. C m. en. O. ==. O.' eD. O. *=. ED. N. .. .= en. N.

&w " m c@--444Nmmen@--@ e 4 O K u'w 4 C e

O

• Os D. h g n .O = .O e etO=O ==.O=O == .O O .O

. O.O O O.= =O #5= O O .O

= .

s s s a e 8 8 4 4 4 4 8 4 4 4 4 e ,I h,,,,g"- C In1413e Int r= @In3@*ena* enan3 Nan3 =@ an1.Im3 N en @ In3an W Im3 W tal In3 Im3 g .O .e en. en. en. en. . en.en. 4. r=. O. @. t. m. en.

r*@.* . es O= O.-

g g- a

=

N n.--ee@dere .-Ne D. en U En A "g

• On e e st 0 h, -

W ,,,

W -

N 0 0 0 0 0 eC ------00

.C . O . . O .O.C osm0 e S. e r*

m. pg I Int in3 W W Sul Ant W Bu3 Inl lat W Is3 W W W In1 N g4 O.

6 eN4ON@ N 85 4 eD .= O - 0D a

g ww &

g O. O. N. N. en. m. 4. **.n N. .=. r=.

. O. N.. .es .=* O* #* N. e.s N. -

N N. y >f O N --NN-me@One--NN-S EE U ll>

3D 4 O P

[d 4 e.s N

• memmememeceememe OOOOOOOOO==0COOOO 4y a p 43 4 0 3 a a e 4 e a,e e a g

og O 8 WWWWWWWWWWWWWWWW' p w - Os r* ( N N en en @ r* M P= .a O @ N gg a en. se. e. 4. @. .=. .*. 4. ==. N. O.s 4. e. @. @. .sp .

gg =. - .= m M N a. == = == m == .* N M 4 W

>7 u C C Wu *

• t=,,, t) a.s . Os os et 96 as 06 as Os on es on ascm os cp Os aep .e. .

.= 0COCCOOOOOOOOOOO 8 8 8 8 6 8 8 6 8 I I e 8 8 A tal I.83 3 In3 taa In3 In3 In3 In3 tal ani yo yy 5

a m .in3= = Ch.In3 4 eIna @ @In3 O N fn3 4 N 8.8 m eD On ag g, O. N. m. N. en. r*. en. en. O. N. @. @. m. r. 4. @. c=.

49

.= mm@@ m N N N N .* N m 4 @ CD m

>Z O C*

y ps as to ce no Ch ch as e cm os Cm ao ao ao e Q

> ~ ,

.= 0COOOOOOOOOOOOOO 8 0 S S 8 9 0 0 8 4 4 0 0 8 3 0

$ WWWWWWWWWWWWWWWW

. m . - - - C O ~ ~O.sNM.en. o ~m.n.=.@o@e*

-a e O. O.

en. r*. m.

. N. m. O @. e r==. .

\ C Pm Oh .m. .= en en .$ @ 4 en r .=e N Os I

en

• EOEDEDe @ W @eDe eED WeDEDr*e O O000OOOOOOCOOOCO 8 e s s e a a e e a e e a e a e i laI In3 W In3 ama h3 Ina Ina taa In3 in3 la3 sat In3 h3 W

@ N N r== so m O? 4 r* .= @ O cm en om N O. 4. 3. m. r* .O. N. N. SD. @. @. O. @. et. N. .*. N.

N 4Nr*bhOONONm @ .'l8 O. W sa W W 3 3 3 r w in W in in 3 M ~

3t o

e EZZWWWMMMMM335mz z I.3 z 6

En

,s C-en .C= .O .O..O .O..O..O .O .O .O .C. O .O. C. . C 0 9 1 5 0 0 4 9 9 0 8 8 84 I I 4'

/%c . 8 an3 an3 an3 !al an2 In3 tai tal la3 tal ta3 ta3 la3 W W tal

$ - CN@ m N r= Ch Ch W N en en == 4

/

\ )g er.s - s.M N.@.n. m. e. o..N @n. tn.. r=. n. 4.en. cn. N.

x_s 4 ' N M .t en M .* N .* == == N m 4 @ N -

}1 g .,

m

.C..O. .C. O. .O. C. .C. O .C. O .C O O. O .C o E 8 8 8 8 8 9 9 4 5 6 9 i . I 8 9 t-

.t ** O '

I tal In. est W ant Ina ant In3 an3 tal ama tal an3 !al an3 in3 3'3 to"*

.* 4 ph 80 en e en en ab O en e en ch a*t es 3M l O. e.n o.s @ . en. C. N. en. en. m. r=. m. m. so. N. eo. en. mg 4 NmW@@N N-NwNMmWNM m .

s .

• ps OOOOmo

. og .C. .O..O. C .C..O .O. .O. .C.=O.== - C N -9 8 9 e f 8 I e t 8 I t t t I I i $ an3 tal est in3 W In3 M3 In3 an3 ta3 In3 tal In3 taa Ina la3 E O e N .= @ 4 > N Os 4 m 4 en N @ == 4

. s. - en. O. 4> . .* O. O. ==. . s*. cm. . . N. en. to. os.-N. so.

eam w m .t 4 em .* en M eiN N N f*t4 ae0.=4 CT IT C5 e w w en.

.c m O O Os es O O

===OO.===== O .O =O ==O== .O=O-O=*cmO cm O == o to t I I 8 3 I 4 4 I4 8 8 8 8 e a EO -I sat in3 In3 In3 la3 Ina an3 tar en3 eaa esa saa saa In3 in3 in3 saa en e @ en O == .1* en N es @ N 80 N N e H

343 g p

e. C. .=. m. O. c".t en. O. .=. O.* so. C. . so. N. .O N.@n. en e

E

• m en @ .* == @ 4. .t N f"l d'"I 4 en @ == .= *O

< E su: n.

< 0-

• .C.

C*

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<w The gaseous radwaste system has the capability to control, collect, process,

( _) store, recyclefand dispose of gaseous radioactive waste generated as a result of plant operations, including-anticipated operational' occurrences.

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 and discharged from either BV-1 or BV-2.

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2-99 ISSUE 1 REVISION 3

_ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ___ ___ _ _ _ _ _ __ _ _ _ _ _ -- _m--

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BV-2 ODCM FIGURE 2.4-2 Beaver Valley Power Station Units 1 and 2 Gaseous Effluent Release Points Ik

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2-101 ISSUE 1 REVISION 3

ge < r !'

'BV-2 ODCM 3.0 Radiological Evnironmental Monitoring Porgram f'~y Table.;3.0-1E contains. the DLC site number, s'ector, distance sampla point

( ,! description, sampling .and collection frequency, analysis, and ' analysis frequency; for various exposure pathways in .the vicinity of .the teaver Valley

~

Power Stations-. (BVPS) .for the radiological monitoring program ~. Figures 3.0-1'through 3.0-9;show the location of the various sampling points.

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-_.___x_-__- - _ , . .-

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BV-2 0DCM

-4. 0 1NFORMATION RELATED TO 40 CFR 190-

. Technical. Specification.

pq ,

. associated with; the 3.11.4.I'.a' requires that when the calculated' doses.

effluent releases exceed twice .the limits of

'g -

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, licensee shall prepare and submit a Special Report to the l.

Commission and limit- subsequent. releases such that the- dose or dose j ccamitment to member (s) of-the public from all facility releases is limited to < 25 mrem

i. .

limited to < 75to the total body, any' organ (except the~ thyroid, which is mrem) for a calendar year. The BVPS-2

! . Technical

' Specifications consider doses to members of the'public due to the operation of BVPS-2 but do not include dose due to BVPS-1, 'any other part of the uranium fuel cycle, or direct shine from site reactors.

to the Commission is prepared by the licensee as requiredIf by a Special Report Specifftation 3.11.4.a,-the evaluation should address:

3)

A determination of the maximum exposed member of the public.

2) A determination of the total dose to tihis person from all exist'ing 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, g radiciodines, particulate, and tritium (excluding C-14). These doses will-t]

b - be in based upon releases from the BVPS SITE during the appropriate time period which twice the unit specification was exceeded. Direct dose components due to skyshine will be 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.

.i

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BV-2 ODCM-APPENDIX A A

SUMMARY

OF DISPERSION CALCULATIONAL PROCEDURES L)'

Annua'l average and grazing season average values of relative concentration (X/Q)

.and deposition (D/Q) were calculated for continuous and intermittent gaseous releases of activity from- the site according to the straight-line airflow (Gaussian) model described in NRC Regulatory Guide 1.111, Revision 1. Undecayed and undepleted sector average X/Q and D/Q values were obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors. 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 Poliching Building. Vent, Decontamination Building Vent, and Gaseous Warte Storage Tank Vault Vent. The intermittent releases are from the Process Vent,.

Containment Vents, and Ventilation Vents. Only the process vent was considered

.p to be an elevated release with all other release points being treated as ground-Q 1evel 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 each 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 Section 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 cf 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 f t) which are representative of the release height (510 ft).

1 O

A-1 ISSUE 1 REVISION 3

- _ _ _ _ _ _ _ _ _ _ . - _ . _ _ _ _ _ - - - _ - - I

l-4 1 BV . ODCM i: 'Bae annual-average and grazing season X/Q and D/Q values for the continuous and l> . intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest f ( 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 E evaluated in each downwind sector to determine the maximum 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 l

Building Vent, Waste Gas Storage Vault Vent, and Condensate Polishing Building Vent, annualare givenX/Q's average in Tables 2.2-4 through 2.2-10 respectively. Continuous release for-these incremental downwind distances.

same release points are also given at ten 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 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> per year of Containment Vent purges, and Ventilation Vent purges and 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> per year of Process sg Albersheim, S. R.,

i Development of Terrain Adjustment Factors for Use at the Beaver Valley Power Station for the Straight-Line Atmospheric Dispetsion Model, NUS-2173, NUS Corporation, June 1978 Sagendorf, J. F., Goll, J. T. and Sandusky, W. F., XODQD0Q: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, NUREG/CR-2919, U. S.

September, 1982. Nuclear Regulatory Comission, O

A-2 ISSUE 1 REVISION 3

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• N m m =

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t QJ m.

60 6

O .Eo

• • O u w J w w 3 s e z w z m w a 3 3 3 6 m m 3 m 2 3 z ==

E z z w w w m m o e m 3 3 3 2 z ,e L

_ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ __ _ - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - ' - - ' - - - - ^ ' - - ' - ' - - -'

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

m BV-2'0DCM.

- APPENDIX B-

[.;- -INPUTS TO SWEC; CODES l LIQ 1BB AND GASIBB FOR GENERATION OF LIQUID AND.

-i (- ' GASEOUS SOURCE TERM MIXES.

%, F BEAVER VALLEY UNIT'2-PWR Thermal' power level (megawatts)

Plant capacity factore 2766.000

Nass of primary-coolant -(thousand lbs). .800 Percent

fuel with cladding defects 385.000'

' Primary l system letdown rate;(gpm). .120 Letdown cation domineralizer flow: '57.0005

' Number lof .stean generators . .5.700-

j. 3.000 Total ~ steam flow (million Ibs/hr) 11.600 Mass of steam in'esch steam generator (thousand Ibs)- 8.700 Mass of liquid in each. steam generator (thousand Ibs) 100'000 Total mass of secondary coolant (thousand Ibs) .

Mass of water in steam generator. (thousand Ibs). 2000.000 298.000-Blowdown rate'(thousand lbs/hr) . 22.300-

' Primary:to' secondary leak rate (1bs/ day) -

Fission' product carry-over fraction 100.000 Halogen carry-over fraction. .001

, Condensate demineralized flow fracton .010 Radwaste dilution flow (thousand gpm) .700 7.800 GASEOUS WASTE INPUTS-

, -w,

i. There is not. continuous stripping of full Ictdown finw QJ Hold up time for xenon (days)

Hold.up time for krypton (days) 45.800 2.570 Primary coolant leak to auxiliary building (Ib/ day) 160.000 Auxiliary building leak iodine partition factor Gas waste, system particulate release fraction. 7.5E-3 Auxiliary building charcolodine release fracticn 0.000 particulate release fraction 0.100 0.010 Containment volume (n.illion cu-ft) 1.800 Frequency of primsry coolant degassing (times /yr) 2.000 Primary.to secondary leak rate (Ib/ day)

There'is a kidney filter 100.000 Containment atmosphrere cleanup rate (thousand cfm) 20.000 Purge time of containment (hours) 8.000 There is not a condensate demineralized lodine partition factor (gas /lig) in steam generator 0.010 Frequency of containment building high vol purge (times / year) 4.000 Containment volume purge iodine release fraction 1.000 particulate release fraction 1.000 Steam leak to turbine building (1bs/hr) 1700.000 Fraction dodine released from blowdown tank vent 0.000 Fraction iodine released from main condensate air ejector 0.270 There is notta cryogenic off gas system B-1 ISSUE 1 i REVISION 3 C____--__--

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