ML20058P859

Bvps,Units Odcm

ML20058P859
Person / Time
Site:	Beaver Valley
Issue date:	10/20/1993
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20058P855	List: ML20058P851 ML20058P859
References
PROC-931020, NUDOCS 9310250263
Download: ML20058P859 (350)

Text

D DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit 1 & Unit 2 Offaite Doce Calculation Manual k

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9310250263 931020  !'

PDR ADOCK 05000334 4,!

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BEAVER VALLEY POWER STATION l

UNIT NO. I and  !

UNIT NO. 2 t

, OFFSITE DOSE .

CALCULATION MANUAL ,

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1 I

i

G DunctSNt uGET CC0!PANY INCLUDED .

FOR i ODCM Review and Approval Sheet HISTORICAL PURPOSES BV-1 ODCM  !

Admin.

Issue Rev. Pgs. RSC Review OSC Review Approv. Eff.

No. No. Issd. Meeting No. Date Meeting No. Date Sign. Date Date 2 2 Ti r, l e BV-RSC- May BV-OSC- June Q,g]/ June i

12-89 25 13-89 G2fM 30 15 G

[,y[y 1989 1989 1989 ,

1-1 tbru l

1-20 i'

2-1 thru '

2 99  !

t 3-1 ,

tbru i 3-14 '

6-]

5-1 1

-6 A-1 tbru  !

A-7 B-1 l thru B4 HE 6.101-1 I

t. }

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DUQUESNE LIGilT COMPANY Nuclear Group INCLUDED ,

FOR HISTORICAL r Review and Approval Sheet .

PURPOSES ,

I UNIT 1 - 0FFSITE DOSE CALCULATION MANUAL l i

ISSUE 2 i

-i Rev. Pgs. Tech. Rev. OSC Approv. Eff.

No. Issd. Sign. Date Review Date Sign. Date Date 0 TITLE PGS BV-RSC-11-87 BV-OSC-17-87 i thru viii BV-RSC-12-87 June 12, 1987

f. . . . Y 7/24/87 l 1-1 tbru l-17 BV-RSC-14-87 g/6l67 l 2-1 thru 2-96 May 29, 1987 a 3-1 thru 3-14 -f p g  !

4,1, 5-1  !

A-1 thru A-7 t B-1 thru B-4 .;

1 2-11 BV-RSC-38-87 BV-1-OSC-25-87 ,v 12/22/87 2-14 12/3/87 12/15/87  ;

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'u?;IT 1 - 0FFSITE DOSE CALCULATION MA'.,'UAL I ISSUE 1 e

i Admin.

Rev. Pgs. Tech. Rev. OSC Approv. _Eff. l No. Issd. Sign. Date Review Date Sign. Date Date ,

i Rev. 1 111 O' '#*'

1-17,13,19 '~45 ~ "/" -P "' '7 2-12,13,

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1 14,15

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[ Rev. 2 1-4,1-5 ERS-SFL-85-031  !

1-6,1-16 ERS-ATL-86-008 2-2,2-2a BVPS-RSC-5-86 By-OSC-25-86 2-3,2-4 May 1, 1986 6/12/84 2-5,2-6 - <  !

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i DUQUESNE LIGHT CC.'!PANY FOR CDCM Review and Approval Sheet PURPOSES l

BV-2 CDCM j l

1 Admin.

Issue Rev. Pgs. RSC Review OSC Review Approv. Eff.

No. No. Issd. Meeting No. Date Meeting No. Date Sign. Date Date _

i 1 3 Tit le BV-RSC- May BV-OSC- June p/g7 June i 12-89 25 13-89 15 -

- 30 i thru 1989 1989 1989  !

viii i 1-1 thru  !

I 1-21 2-1 1 thru i 2-101 h

3-1 ,

thru 3-14 ,

4-1 5-1 A-1 i thru  !

A-7 B-1 thru B-2 ,

RE 6.101-1 I

l t DUQUESNE LIGHT COMPANY Nuciear Croup INCLUDED j FOR i HISTORICAL  !

Review and Approval Sheet PURPOSES  !

T UNIT 2 - 0FFSITE DOSE CALCULATION MANUAL l t

i ISSUE 1 I i

Pgs. Tech. Rev. OSC Approv. Eif.

Rev.

No. Issd. Sign. Date Review Date Sign. Date Date 'i l

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/% lb '1 2-1 thru 2-9a May 29, 1987 l 3-1 thru 3-14 &T  :

4-1, 5-1 A-1 thru A-7 B-1 and B-2 2 2-12 BV-RSC-38-87 BV-1-OSC-25-87 %J 12/22/87  !

?-15 12/3/87 12/15/87 l s e gut' i2/22/s2 t

i P

DUQUESNE LIGilT COMPANY Beaver Valley Power Station Unit 1 Docket No. 50-334 License No. DPR-66 Beaver Valle) Fover Station Unit 2 Docket No. 50-412 License No. NTF 73 BEAVER VALLEY POWER STATION UNIT 1 (BV-1)

BEAVER VALLEY POVER STATION UNIT 2 (BV-2) 0FFSITE DOSE CALCULATION MANUAL (ODCM)

ISSUE 3

BV-1 and 2 ODCM TABLE OF CONTENTS ,

h SECTION TITLE PAGE NO.

Table of Contents........... .............. ........ i List of Tables.... .... ............ ... .......... iii List Of Figures.... ........................... .... vi ODCM Equation Cross Reference....................... vii ODCM Table Cross Reference.................... ..... ix Preface........... ... ........ . ........ .. ... xi History Of ODCM Changes... .. . . . .. ... .. xii 1.0 LIQUID EFFLUENTS.. .... ...... ........ ............ 1-1 -

1.1 Alarm Setpoints.. .... ........... ............. 1-2 1.1.1 BV-1 Monitor Alarm Setpoint Determination... . 1-2 1.1.1.1 BV-1 Setpoint Determination Based On A Conservative Mix..................., ....... 1-2 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release...... ............ 1-5 1.1.2 BV-2 Monitor Alarm Setpoint Determination. ... 1-7 1.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix.. ................. ...... 1-7 1.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release... ............... 1-10 References For Liquid Alarm Setpoints............... 1-15 1.2 Compliance Vith 10 CFR 20 MPC Limits............ 1-16 D. 1.2.1 Batch Releases....... ........ .. ........... 1-16 1.2.2 Continuous Releases........................... 1-18 1.3 Compliance Vith 10 CFR 50 Dose Limits........... 1-21 1.3.1 Cumulation of Doses........ . .. . .... ... 1-21

1. 3. 2 Proj ec t ion O f Doses . . . . . . . . . . . . . . . . . ......... 1-23 1.4 Liquid Radvaste System......... .. .. .......... 1-27 2.0 GASEOUS EFFLUENTS................. . ............... 2-1 2.1 Alarm Setpoints........... ..................... 2-2 2.1.1 BV-1 Monitor Alarm Setpoint Determination..... 2-2 2.1.1.1 BV-1 Setooint Determination Based On A Calculated Mix (Ground Releases). ........ 2-5 -

2.1.1.2 BV-1 Setpoint Determination Based on Analysis Prior To Release (Ground Releases). 2-10 2.1.2 BV-2 Monitor Alarm Setpoint Determination..... 2-13 2.1.2.1 BV-2 Setpoint Determination Based On A Calculated Mix (Ground Releases)............ 2-13 2.1.2.2 BV-2 Setpoint Determination Based on l

Analysis Prior To Release (Ground Releases). 2-19 2.1.3 BV-1/2 Monitor Alarm Setpoint Determination... 2-22 2.1.3.1 BV-1/2 Setpoint Determination Based on A Calculated Mix-(Elevated Releases).......... 2-22 g- 2.1.3.2 BV-1/2 Setpoint Determination Based On F Analysis Prior To Release (Elevated Releases) 2-26 I

l Feferences For Gaseous Alarm Setpoints.............. 2-33 l

! i ISSUE 3

BV-1 and 2 ODCM TABLE OF CONTENTS SECTION TITLE PAGE NO.

l 2.2 Compliance Vith 10 CFR 20 Dose Rate Limits...... 2-34 2.2.1 Dose Rate Due To Noble Gases.................. 2-34 2.2.2 Dose Rate Due To Radioiodines And Particulates 2-41 2.3 Compliance Vith 10 CFR 50 Dose Limits........... 2-59 2.3.1 Dose Due To Noble Gases....................... 2-59 2.3.1.1 Cumulation of Doses......................... 2-59

2. 3.1. 2 Proj ec t ion O f Doses . . . . . . . . . . . ............. 2-65 2.3.2 Doses Due To Radiciodines And Particulates.... 2-66 2.3.2.1 Cumulation Of Doses.... .................... 2-66

2. 3. 2. 2 Proj ection Of Doses. . . . ........ ........... 2-78 2.4 Gaseous Radvaste System......................... 2-117 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 Computer Codes For Generation Of Source Terms.. ........ .. . .................. .... B-1 Appendix C ODCM Controls........ ...... .. .................... C-1 Appendix D Bases For ODCM Controls................ ...... ..... D-1 Appendix E Annual Reports.... .. . . ......... ........ ...... E-1 l

l ii ISSUE 3 l

BV-1 and 2 ODCM LIST OF TABLES TABLE NO. TITLE PAGE NO.

g LIQUID EFFLUENT TABLES 1.1-la BV-1 Liquid Source Term.... . ... ............... 1-12 1.1-lb BV-2 Liquid Source Term.. .... . ........ ......... 1-13 1.2-la BV-1 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks.. . . . .... .... . .... 1-19 1.2-1b BV-2 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks..... ............. ... .. .. . 1-20 1.3-1 Ag Values For An Adult For The Beaver Valley Site... 1-24 GASEOUS EFFLUENT TABLES 2.1-la BV-1 Radionuclide Mix For Gaseous Effluents. ....... 2-29 2.1-lb BV-2 Radionuclide Mix For Gaseous Effluents. .... ... 2-30 2.1-2a BV-1 Monitor Detector Efficiencies.............. .... 2-31 2.1-2b BV-2 Monitor Detector Efficiencies...... ... ....... 2-32 2.2-1 Modes Of Gaseous Release From Beaver Valley Site Vents For Implementation of 10 CFR 20 And 10 CFR 50.. 2-45 2.2-2a BV-1 Radionuclide Mix For Gaseous Effluents........ . 2-46 2.2-2b BV-2 Radionuclide Mix For Gaseous Effluents.......... 2-47 2.2-3 Distances Of Limiting Maximum Individual Receptors To Release Points For Annual X/0 Values.... ..... ... 2-48 g

ANNUAL AVERAGE X/0 VALUES FOR CONTINUOUS RELEASES (SPECIAL DISTANCES AND CONTROL LOCATIONS) 2.2 4 BV-1 And 2 Containment Vents (Ground Release)..... .. 2 49 2.2-5 BV-1 And 2 Ventilation Vents (Ground Release). ...... 2-50 2.2-6 BV-1 And 2 Process Vent (Elevated Release)........... 2-51 2.2-7 BV-1 And 2 Turbine Building Vents (Ground Release).. 2-52 2.2-8 BV-2 Decontamination Building Vent (Ground Release).. 2-53 2.2-9 BV-2 Vaste Gas Storage Vault Vent (Ground Release)... 2-54 2.2-10 BV-2 Condensate Polishing Building (Ground Release).. 2-55 DOSE FACTORS AND DOSE PARAMETERS FOR GASEOUS EFFLUENTS 2.2-11 Dose Factors For Noble Gases And Daughters. ...... 2-56 2.2-12 Dose Parameters For Finite Elevated Plumes, Beaver Valley Site.... ........... . .. .... ..... ... ... . 2-57 2.2-13 P Values For A Child For The Beaver Valley Site.... 2-58 3

MODES OF GASE0US RELEASES 2.3-1 Modes Of Gaseous Release Form The Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50. 2 79 iii ISSUE 3 i

BV-1 and 2 ODCM l l

LIST OF TABLES TABLE NO. TITLE PAGE NO.

R VALUES FOR BEAVER VALLEY SITE 2.3-2 Inhalation - Adult.......... ........................ 2-80 2.3-3 Inhalation - Teen.. ............... ...... .......... 2-81 2.3 4 Inhalation - Child......... ...... ...... ........... 2-82 2.3-5 Inhalation - Infant.................................. 2-83 2.3-6 Ground.................. . .......................... 2-84 2.3-7 Vegetation - Adult..... .......... ...... ........... 2-85 2.3-8 Vegetation - Teen.. .. ...... ... . ................. 2-86 2.3-9 Vegetation - Child...... ................ ........... 2-87 2.3-10 Meat - Adult........... . ..... ........... ......... 2-88 2.3-11 Meat - Teen..... ........ ......... ... ............. 2-89 2.3-12 Meat - Child........ .......... . ... .............. 2-90 2.3-13 Cow Milk - Adult............ ... .......... ..... ... 2-91 2.3-14 Cow Milk - Teen...... ........ ...................... 2-92 2.3-15 Cov Milk - Child.. ..... . ... ..... ........ ... 2-93 2.3-16 Cov Milk - Infant.... ...... ........................ 2-94 2.3-17 Goat Milk - Adult............... .................... 2-95 2.3-18 Goat Milk - Teen.. . . . ... ..... ........ ....... 2-96 2.3-19 Goat Milk - Child....... .. ....... .......... ...... 2-97 2.3-20 Goat Milk - Infant......... .................... .... 2-98 ANNUAL AVERAGE D/0 VALUES FOR CONTINUOUS RELEASES (CONTROL LOCATIONS) 2.3-21 BV-1 And 2 Process Vent (Elevated Release)........... 2-99 2.3-22 BV-1 And 2 Containment Vents (Ground Release)........ 2-100 2.3-23 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-101 2.3-24 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-102 2.3-25 BV-2 Condensate Polishing Building (Ground Release).. 2-103 2.3-26 BV-2 Decontamination Building Vent (Ground Release).. 2-104 2.3-27 BV-2 Vaste Gas Storage Vault Vent (Ground Release)... 2-105 ANNUAL AVERAGE D/0 VALUES FOR CONTINUOUS RELEASES (SPECIAL DISTANCES) 2.3-28 BV-1 And 2 Process Vent (Elevated Release)........... 2-106 2.3-29 BV-1 And 2 Containment Vents (Ground Release)........ 2-107 2.3-30 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-108 2.3-31 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-109 2.3-32 BV-2 Condensate Polishing Building (Ground Release).. 2-110 2.3-33 BV-2 Decontamination Building Vent (Ground Release).. 2-111 2.3-34 BV-2 Vaste Gas Storage Vault Vent (Ground Release)... 2-112 SHORT TERM X/0 VALUES FOR BATCH RELEASES 2.3-35 BV-1 And 2 Containment Vents (Ground Release)........ 2-113 2.3-36 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-114 2.3-37 BV-1 And 2 Process Vent (Elevated Release)........... 2-115 2.3-38 BV-1 And 2 Process Vent (Elevated Release)........... 2-116 iv ISSUE 3

BV-1 and 2 ODCM LIST OF TABLES TABLE NO. TITLE PAGE NO.

}

ENVIRONMENTAL MONITORING 3.0-1 Radiological Environmental Monitoring Program........ 3-4 DISPERSION CALCULATION PROCEDURES A:1.1 BV-1 And 2 Release Conditions. ........ ............ A-3 INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS B:1.la Inputs To GALE Code For Generation Of BV-1 Liquid Source Term Mixes....... ............... ........... B-2 B:1.1b Inputs To SVEC LIQ 1BB Code For Generation Of BV-2 Liquid Source Term Mixes... . .... ................ B-3 B:1.2a Inputs To SVEC GAS 1BB Code For Generation Of BV-1 Gaseous Source Term Mixes..... .................... . B4 B:1.2b Inputs To SVEC GAS 1BB Code For Generation of BV-2 Gaseous Source Term Mixes.. ......................... B-5 ODCM CONTROLS FOR INSTRUMENTATION, SAMPLING, AND ANALYSIS REQUIREMENTS C:1.1 Operational Modes...... .. ....................... . C-5 C:1.2 Frequency Notation........ .. .... .................. C-6 C:3.3-12 Radioactive Liquid Ef fluent Monitoring Instrumentation C-10 h Radioactive Liquid Effluent Monitoring Instrumentation C:4.3-12 Surveillance Requirements. .......................... C-12 Radioactive Gaseous Effluent Monitoring Instrumentation C-19 C: 3.3-13 C:4.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements............................ C-25 Radioactive Liquid Vaste Sampling And Analysis Program C-31 C:4.11-1 Radioactive Gaseous Vaste Sampling And Analysis Program C-38 C:4.11-2 Radiological Environmental Monitoring Program... C 48 C:3.12-1 ..

C:3.12-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples.... ................ .......... C-51 r-52 C:4.12-1 Maximum Values For The Lower Limits Of Detection (LLD)

FORMAT FOR JUR4UAL REPORT Environmental Radiological Monitoring Program Summary E-2 E:6.9-1 s ISSUE 3 l________ _ ___

BV-1 and 2 ODCM LIST OF FIGURES FIGURE NO. TITLE PAGE NO. j LIQUID EFFLUENT FIGURES 1.4-1 BV-1 Liquid Radvaste System............. ... ....... 1-28 1.4-2 BV-2 Liquid Radvaste System. ...... ... .. ....... 1-29 GASEOUS EFFLUENT FIGURES 2.4-1 BV-1 And 2 Gaseous Radvaste System...... ........... 2-118 2.4-2 BV-1 And 2 Gaseous Effluent Release Points.......... 2-119 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FIGURES 3.0-1 Air Sampling Locations. . .......................... 3-8 3.0-2 TLD Locations - Northwest Quadrant......... ........ 3-9 3.0-3 TLD Locations - Northeast Quadrant.. ......... .. .. 3-10 3.0 4 TLD Locations - Southeast Quadrant............ . ... 3-11 3.0-5 TLD Locations - Southwest Guadrant.... .... ........ 3-1?

3.0-6 Shoreline Sediment, Surface Vater, And Drinking Vater Sampling Locations.. .... . ................. 3-13 3.0-7 Milk Sampling Locations............... .. .......... 3-14 3.0-8 Fooderop Sampling Locations. .... .... ............. 3-15 3.0-9 Fish Sampling Locations. . ...... .. ..... ......... 3-16 SITE BOUNDARY FIGURES l

5-1 Site Boundary For Gaseous And Liquid Effluents...... 5-1 l

vi ISSUE 3

BV-1 and 2 ODCM ODCM EQUATION CROSS REFERENCE FOR LIQUID EFFLUENTS FROM: TO: FROM:

PREVIOUS CURRENT PREVIOUS BV--1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1. REV. 3 AND EARLIER AND LATER AND EARLIER 1.1-1 1.1( 1 )- 1 --

1.1-2 1.1(1)-2 --

1.1-3 1.1(1)-3 --

1.1-4 1.1(1)-4 --

1.1-5 1..(1)-5 --

1.1-6 1.1(1)-6 --

1.1-7 1.1(1)-7 --

1.1-8 1.1(1)-8 --

1.1(2)-1 1.1-1 1.1(2)-2 1.1-2 1.1(2)-3 1.1-3 1.1(2)-4 1.1-4 1.1(2)-5 1.1-5 1.1(2)-6 1.1-6 1.1(2)-7 1.1 7 1.1(2)-R 1.1-8 1.2-1 1.2-1 1.2-1 Thru Thru Thru 1.2-4 1.2-4 1.2-4 1.3-1 1.3-1 1.3-1 Thru Thru 7hru 1.3-8 1.3-8 1.3-8 l

l l

l D

vii ISSUE

i BV-1 and 2 ODCM j l

ODCM EQUATION CROSS REFERENCE  !

l FOR GASEOUS EFFLUENTS FROM: To: FROM:

i PREVIOUS CUEFE JT FREVIOUS <

BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER 2.1-1 2.1(1)-1 --

1 2.1-2 2.1 ( 1 )- 2 --

l 2.1-3 2.1(1)-3 --

2.1-4 ]:

2.1(1)-4 --

2.1-5 2.1(1)-5 --

l 2.1-6 2.1(1)-6 --

l 2.1-7 2.1(1)-7 -- 1 2.1-8 2.1(1)-8 --

l 2.1(2)-1 2.1-1 2.1(2)-2 2.1-2 2.1(2)-3 2.1-3 2.1(2)-4  ?.1-4 2.1(2)-5 2.1-5 2.1(2)-6 2.1-6 2.1(2)-7 2.1 7 l 2.1(2)-8 2.1-8 l 2.1-9 2.1 0 2.1-9 I Thru Thru Thru 2.1-16 2.1-16 2.1-16 2.1-17 2.1(1)-17 -

2.1-18 2.1(1)-18 2.1-19 2.1(1)-19 --

2.1-20 2.1(1)-20 -

2.1(2)-17 l 2.1-17 2.1(2)-18 l ' 1-18.

2.1(2)-19 l 2.1-19 2.1(2)-2n l 2.1-20 l

2.1-21 2.1-21 { ~' .1 - 21 Thru Thru l Thtu 2.1-24 2.1-24 l, 2.1-24 i

2.2-1 2.2-1 2.?-1 Thru Thru Thru 2.2-14 2.2-lo l 2.2-14 l

2.3-1 2.3-1 }  ? !1 Thru Thru  ! Thru 2.3-36 21-% l 2 3- %

l t  !

g iii ISSUE T

BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR LIQUID EFFLUENTS k

FROM: TO: FROM:

PREVIOUS CURRENT PREVIOUS BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER 1.1-1 1.1-la --

-- 1.1-lb 1.1-1 1.2-1 1.2-la --

-- 1.2-lb 1.2-1 1,3-1 1.3-1 1.3-1

)

ix ISSUE 3

BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR GASEOUS EFFLUENTS TO: FROM:

4 FROM: l PREVIOUS CURRENT PREVIOUS BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER 2.1-1 2.1-la --

2.1-lb 2.1-1 2.1-2 2.1-2a --

-- 2.1-2b 2.1-2 2.2-1 2.2-1 2.2-1 2.2-2 2.2-2a --

-- 2.2-2b 2.2-2 2.2-3 2.2-3 2.2-3 Thru Thru Thru 2.2-13 2.2-13 2.2-13 2.3-1 2.3-1 2.3-1 Thru Thru Thru 2.3-34 2.3-34 2.3-34 A-2 2.3-35 A-2 A-3 2.3-36 A-3 A-4 2.3-37 A-4 A-5 2.3-38 A-5 3.0-1 3.0-1 3.0-1 l

x ISSUE 3

BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR ODCM AFFENDICES FROM: TO: FROM:

PREVIOUS CURRENT PREVIOUS BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER A-1 A:1.1 A-1 (Unnumbered) B:1.la --

B:1.lb (Unnumbered)

(Unnumbered) B:1.2a --

-- B:1.2b (Unnumbered)

C:1.1 --

C:1.2 --

C:3.3-12 --

C:4.3-12 --

C: 3.3-13 --

C:4.3-13 --

C:4.11-1 --

C:4.11-2 --

C: 3.12-1 --

-- C:3.12-2 --

C: 4.12-1 --

E:6.9-1 --

)

xi ISSUE 3 i I

BV-1 and 2 ODCM PREFACE This OFFSITE DOSE CALCULATION MANUAL (ODCM) provides the information and methodologies to be used by Beaver Valley Power Station Unit 1 and Unit 2 (BV-1) I and (BV-2) to assure compliance with the Administrative Controls Section of the operating Technical Specifications. They are intended to show compliance with 10 CFR 20.106, 10 CFR 50.36a, Appendix I of 10 CFR 50, and 40 CFR 190.

This ODCM is based on the following United States Nuclear Regulatory Commission (USNRC) documents:

• NUREG-0472, Draft 7 for Rev. 3, September, 1982, Standard Radiological Effluent Technical Specifications For PVRs.

• NUREG-0133, October, 1978, Preparation Of Radiological Effluent Technical Specifications For Nuclear Power Plants.

• Generic Letter 89-01, January 31, 1989, Implementation of Programatic Controls For Radiological Effluent Technical Specifications In The Administrative Controls Section Of The Technical Specifications And The Relocation Of Procedural Details Of RETS To The ODCM Or To The PCP.

• NUREG-1301, April, 1991, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls For Pressurized Vater Reactors, Generic Letter 89-01, Supplement No. 1.

• Other miscellaneous inputs from the USNRC.

Specific plant procedures for implementation of this manual are included in the Radiological Control Manual (BVPS-RCM) and the Radiological Engineering Administrative Manual (REAM). These procedures are utilized by the operating staff to assure compliance with Technical Specifications and the Aopendix C CONTROLS of the ODCM.

The ODCM has been prepared as generically as possible in order to minimize the need for future versions. However, some changes to the ODCM may be necessary in the future. Any such changes vill be properly prepared, revieved, and approved as indicated in the Administrative Control Section of the Technical

- Specifications. An implementation procedure for control of the ODCM is included in the REAM. In summary, any ODCM changes vill be properly justified to ensure that ODCM changes vill maintain the level of radioactive effluent control rcquired 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.

I xii ISSUE 3

BV-1 and 2 ODCM HISTORY OF ODCM CHANGES (1) BV-1 ODCM, Issue 1 (Effective First Half, 1984)

This is the initial issue of the BV-1 ODCM, as prepared for implementation of the Radiological Effluent Technical Specifications (RETS).

Implementation of this manual was commensurate with Amendment No. 66 to the Unit 1 Technical Specifications as approved by the NRC on March 28, 1983.

(2) BV-1 ODCM, Issue 1, Revision 1 (Effective Second Half, 1984)

A description of the changes that vere implemented with this revision are as follows:

• Table 1.3-1 was revised to include liquid dose factors for nuclides presently identified at BVPS and not included in the original table.

• Equations 2.1-19 and 2.1-22 vere revised as approved at RSC Meeting No. BVPS-RSC-1-84 on January 31, 1984. The equations were revised to clarify flow rate terminology.

• Section 2.2.2 was revised to delete the food and ground pathways for gaseous dose rate calculations of I-131, tritium, and radionuclides in particulate form with half lives greater than 8 days.

• Table 2.2-13 was revised to include 7 organs rather than only the k maximum organ. Also, the receptor was changed from infant to child, and addition / deletion of nuclides to be consistent with the Technical Specifications and nuclides identified at BV-1.

(3) BV-1 ODCM, Issue 1, Revision 2 (Effective Second Half, 1986)

A description of the changes that were implemented with this revision are as follows:

" Frovide a flov based monitor setpoint adjustment factor in Section 1.1.2. This change makes Section 1.1.2 consistent with Section 1.1.1 and current procedures.

Revise the 31-day dose projection limits and methodology in Sections 1.3.2, 2.3.1.2, and 2.3.2.2. This change corrected the 31-day dose projection limits and changed the dose projection methodology to be consistent with proposed software.

• Revise the Gaseous Effluent Monitor Setpoints in Sections 2.1.1 and 2.1.2. They were revised due to pressure corrections determined for the detectors, changes in isotopic literature, and the addition of SPl!;G Channel 5 alternate monitor data. The calculations supporting this item are contained in Calculation Packages ERS-SFL-85-031 and ERS-ATL-86-008.

k xiii ISSUE 3 l

BV-1 and 2 ODCM j l

(4) BV-1 ODCM, Issue 2, (Effective Second Half, 1987)

BV-2 ODCM, Issue 1 Revision 1 (Effective Second Half, 1987)  ;

Vith the start-up of BV-2 in the second half of 1987, the BV-1 ODCM required revision and the BV-2 ODCM required initial implementation. A description of the changes are as follows:

• Produce functionally compatible BV-1 and BV-2 ODCMs which address site dose rate limits and meet regulatory requirements. Note that due to the scope of the revisions to the Unit 1 ODCM, it was re-issued as Issue 2.

Also, for clarity, the draft BV-2 ODCM previously submitted to the NRC was regarded as Issue 1 (historical) and operation of BV-2 began with Issue 1, Revision 1 of the BV-2 ODCM.

A shared liquid radvaste system, permitting mixing of vaste for processing, the sharing of dilution water, and the apportionment of dose according to NUREG-0133 vas incorporated into both ODCMs.

• A shared elevated gaseous radvaste system, permitting the mixing of gaseous radvaste and the apportionment of dose, according to NUREG-0133 was incorporated into both ODCMs.

• Separate ground level gaseous releases were maintained. The BV-1 ODCM was updated to incorporate the BV-2 five year meteorology base. Gaseous source terms were revised to that calculated for BV-1 in the BV-2 FSAR, and terms were added for calculation of a turbine building release.

The gaseous effluent monitor alarm setpoints of both ODCMs vere revised as required by revisions to meteorology, source terms, monitor I

efficiencies, and revised percentages of site dose rate limits.

• Formal justification was provided for use of the "T" factor in Containment Purge Dose Rate calculations. Whereas, the dose rate t'or a Containment Purge may be average over a time period not to exceed 960 minutes. Since the Containment air volume change time period is 60 minutes, then the maximum value for "T" is 16 (i.e., 960 minutes /

60 minutes = 16).

(5) BV-1 ODCM, Issue 2, Revision 1 (Effective Second Half, 1987)

BV-2 ODCM, Issue 1. Revision 2 (Effective Second Half, 1987)

Sections 2.1.3 and 2.1.4 of both ODCMs were changed to delete a note concerning noble gas nuclides as requested by a FRC letter dated July 14, 1987 titled Beaver Valley Unit 2 Offsite Dose Calculation Manual, ODCM (TAC 63996).

(6) BV-1 ODCM, Issue 2, Revision 2 (Effective First Half, 1989)

BV-2 ODCM, Issue 1, Revision 3 (Effective First Half, 1989)

A description of the changee that were implemented with this revision are as follows:

' Both ODCMs were revised for addition of Sections 1.4 and 2.4. This addition gives a description of and includes flow diagrams of the Liquid Radvaste System and the Gaseous Padvaste System. (See justification 1) l xiv ISSUE 3

BV-1 and 2 ODCM

• Correct the following typos to BV-1 ODCM Equation 1.1-8:  !

l A. Show differentiation between the two f's. (See Justification 1)

B. Add the division sign. (See Justification 1)

• Re-define Fkin equation 1.3-1 of both ODCMs, as allowed by the NRC. (See Justification 1)

• Correct typos to the following:

A. BV-1 ODCM equation 1.3-7, add a division sign between the brackets. l (See Justification 1)

B. BV-1 ODCM equation 1.3-8, add a division sign between the brackets. i (See Justification 1)

C. Add the vords "from each reacto. unit" to five places (Sections 1.7.1, 1.3.2, 2.3.1.1, 2.3.1.2, and 2.3.2.2) of both ODCMs. This ensures compliance sith the current requirements of the  !

Technical Specifications. (See Justification 2)

D. Equation 2.1-20 of both ODCMs, change the HHSP to HSP multiplier from 0.70 to 0.33. (See Justification 1)

E. Equation 2.1-24 of both ODCMs, change the HHSP to HSP multiplier from 0.70 to 0.33. (See Justification 1)

F. Correct punctuation in Section 2.3.2.1 of the BV-1 ODCH.

} (See Justification 2)

G. Correct typos in Table 3.0-1 of both ODCMs. (See Justification 2)

H. Correct typos in Figure 3.0-3 of both ODCMs. (See Justification 2)

• Add Reference (7) to Section 2 of the BV-1 ODCM. (See Justification 3)

• Add the verds "from the site" to Section 2.2.2 of both ODCMs. This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)

• Revise BV-1 ODCM Table 2.2-2 to change the particulate and iodine radionuclide mix for the Unit i Ventilation Vent and to correct a typo for Xe-135m in the Containment Vacuum Pumps. (See Justification 3)

• Provide re-verified P iT values for the Beaver Valley site in Table 2.2-13 of both ODCMs. (See Justification 1)

• Correct the definition for the t f(value in the cow-meat pathway in Section 2.3.2.1 of both ODCMs. See Justification 1) ,

• Provide re-verified R values for the Beaver Valley site in Tables 2.3-2 through 2.3-20 of both ODCMs. (see Justification 1) g

• Change the particulate and iodine release fractions in Appendix B of the BV-1 ODCM. (See Justification 3) xv ISSUE 3

BV-1 and 2 ODCM The justification used for Change (6) to the ODCMs are as follows:

1. A letter dated March 2, 1989 (trom the NRC) was received by Duquesne Light regarding acceptance of the Offsite Dose Calculation Manuals.

The NRC acceptance of the BV-1 and BV-2 ODCMs was based on Technical Evaluation Reports (TER No. EGG-PHY-8194 and EGG-PHY-8217) provided by the Idaho National Engineering 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 one vay 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 cov-meat, cov-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 F values in error do not involve the controlling receptor for gaseous release (i.e.; the controlling receptor is VIA the Inhalation, Ground, end Vegetation pathways, not the pathways subject to error) than these changes to the ODCM vill not adversely impact the accuracy or reliability of effluent dose calculations.

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

{

3. As delineated in letter NDISHP:776, dated February 12, 1988 (BVPS-1 ODCM Table 2.2-2, \ppendix B) a series of apparent discrepancies were identified betvcen ODCM Table 2.2-2 and similar tables of the BVPS-2 FSAR. Evaluation shoved that apparent credit was given for continuous filtration of SLCRS releases which is invalid at Unit 1. However, the calculation package on which the BVPS-2 FSAR expected release tables are based, is correct (i.e.; no credit was taken for routine filtration for Unit 1 releases). Except for revising the ODCM, no further corrective action is necessary because the particulates and iodines in the ODCM vere not used for gaseous effluent alarm setpoint.

Therefore, this change does not adversely impact the accuracy or reliability of setpoint calculations.

(7) BV-1 and 2 ODCM. Issue 3 (Tentative Effective Date, First Half 1992)

The combined ODCM, as implemented by ISSUE 3, contains the following changes:

" Prior to ISSUE 3, BV-1 and BV-2 had individual ODCMs that vere generically equal. In an effort to simplify the implementing documents, the ODCMs have been combined. This merger of the individual ODCMs vill 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 Part 50. Also, this nerger vill not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

xv1 ISSUE 3

i 4

BV-1 and 2 ODCM {

Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gaseous  ;

Effluents) to merge the BV-1 alarm setpoint calculations with the BV-2 s alarm setpoint calculations. For all practical purposes, when Tables, j Figures, and Equations vere transferred to the combined ODCM, the ,

I numbering was kept generically equal. The only exception to this are as follows:  !

- If a table was contained in both ODCMs, but each had data specific i to BV-1 or BV-2, then an a or b was added to the table. For I example, Table 1.1-1 was previously included in the BV-1 ODCM and l the BV-2 ODCM. These tables are nov numbered 1.1-la and 1.1-lb i

, denoting BV-1 and BV-2 respectively. A cross reference for ODCM tables is provided in the Table Of Contents.

- If an equation was contained in both ODCMs, but each had data f specific to BV-1 or BV-2, then a (1) or (2) vas added to the (

equation. For example, Equation 1.1-1 was previously included in  :

- the BV-1 ODCM and the BV-2 ODCM. These equations are nov numbered  !

1.1(1)-1 and 1.1(2)-1, denoting BV-1 and BV-2 respectively. A cross reference for ODCM equations is provided in the Table Of Contents.  ;

)

Revised Section 3.0 (Radiological Environmental Monitoring Program) to  !

list the program requirements from the Radiological Assessment Branch '

Technical Position (Revision 1, 1979).

Revised Section 4.0 (Information Related To 40 CFR 190) to provide

, clarified reporting requirements for the Special Report. The -

clarifications were taken from Generic Letter 89-01, Supplement No. 1  !

/ (NUREG-1301).

Revised Appendix A to transfer the Batch Release dispersion parameters from Appendix A (Tables A-2 through A-5) to Section 2.3 (Tables 2.3-35 l through 2.3-38). This revision was done for clarification. For example, all dispersion parameters are now included in one area of the ODCM.

i Added Appendix C: Procedural details for the Radiological Effluent Technical Specifications (RETS) were transferred from the Technical Specifications to Appendix C of the ODCM- per Generic Letter 89-01 and Generic Letter 89-01, Supplement No. 1 (NUREG 1301).

This Appendix also includes selected Definitions and Tables as delineated in the Technical Specifications (Section 1) and selected 7 Applicability and Surveillance Requirement statements as delineated in the Technical Specifications (Section 3/4 0). These were added to Appendix C for reference purposes, even though they are currently .

described in the Technical Specification. l Added Appendix D: The bases for ODCM Controls were transferred from the  !

Bases Section of the Technical Specificatient. to Appendix D of the ODCM per Generic Letter 89-01.

Added Appendix E: The Annual Radioactive Effluent Release Report and the Annual Radiological Environmental Report reporting requirements are listed in this appendix to the ODCM.

xvii ISSUE 3 l

l j

l BV-1 and 2 ODCM l l

i

• There are two differences (i.e., non-editorial changes) in this ODCM l revision when compared to the previous BV-1 and BV-2 Technical Specifications. These are the only changes that are identified by revision bars. These differences are as follovs: l l

First Difference:

There was a sentence removed in the LLD Standard Deviation Definitions delineated in Appendix C Tables 4.11-1 and 4.11-2. This \

sentence stated: "In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium in milk samples)."

It should be noted that this sentence was removed by justification of NUREG-0472. Rev. 2 (i.e., this revision to the NUREG removed the sentence from Tables 4.11-1 and 4.11-2). It should be noted that at BV-1 and 2, there are -no other radionuclides normally present in effluent samples. Howev r, there is applicability to environmental LLD calculations due to the existence of other radionuclides in environmental samples. This sentence, therefore, vill not be removed from Appendix C, Table 4.12-1.

Removal of the sentence from Appendix C, Tables 4.11-1 and 4.11-2 does not adversely impact the accuracy or reliability of current or past effluent LLD calculations. This change ma!ntains 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 Part 50, and does I not adversely impact the accuracy or reliability of effluent, dose, -

or setpoint calculations.

This change brings ODCM Appendix C, Tables 4.11-1 and 4.11-2 in generic agreement with NRC guidance (i.e., NUREG-0472) and industry standard.

Secona Difference:

f The frequency of the Radioactive Effluent Release Report was changed from Semi-Annual to Annual. This change is justified by Federal Register, Rules And Regulations (Vol. 57, No. 169, Monday, August <

31, 1992), where as; 10 CFR Part 50.36a(a)(2) states, in part:

"Each licensee shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months of operation...the time between rubmission of the raports must be no longer than 12 months..."

This change maintains 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 Part 50, and does not adversely impact the )/

accuracy or reliability of effluent, dose, or setpoint calculations.

xviii ISSUE 3

BU-l and 2 ODCM

SUMMARY

Per Generic Letter 89-01, the transfer of RETS procedural details fulfills the goal of the USNRC Policy Statement for Technical Specification improvements. It is not the USNRC's (or'DLC's) intent to reduce the level of radioactive effluent control. Rather, the intent is to provide programmatic controls for RETS (as delineated in Technical '

Specification 6.8.6) and allow for relocation of the procedural details ,

of the RETS to the ODCM. ,

t I

l xix ISSUE 3

BV-1 and 2 ODCM 1.0 LIQUID EFFLUENTS h BV-1 and BV-2 utilize the concept of a shared liquid radioactive vaste system according to NUREG 0133. This permits the mixing of liquid radvaste for processing and allocating of dose due to release as defined in Section 1.4. In Section 1.1, effluent monitor setpoints for a conservative j mix are based on the individual Units' specific parameters, but effluent I monitor setpoints for analysis prior to release permit use of the total dilution flow available at the site.

Differences exist between setpoint presentations of the radiation i monitoring systems of BV-1 and BV-2. There is a difference in setpoint terminology. Where BV-1 uses HIGH and HIGH-HIGH, the BV-2 equivalents are i ALERT and HIGH. Also, there is the difference that BV-2 setpoints are l presented in uCi/ml rather than epm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to the raw data (cpm).

Note that the uC1/ml presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factors.

Therefore, BV-2 setpoints determined on analysis prior to release vill be correct for properly controlling dose rate, but the indicated uCi/ml value may differ from the actual value.

16 l

l l

l l

l l

l l-1 ISSUE 3

l BV-1 and 2 ODCM 1.1 Alarm Setpoints f 1.1.1 BV-1 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH-HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2 E-4 uCi/ml for dissolved or entrained noble gases.

The methodology described in Section 1.1.1.2 is an alternative method to be used to determine the monitor HIGH-HIGH Alarm Setpoint (HHSP). The methodology in Section 1.1.1.2 may be used for any batch release and shall be used when the total gamma activity concentration of the liquid effluent prior to dilution exceeds 1.49E 4 uCi/ml. This concentration is equivalent to the HHSP's of 1.69 E4 ncpm and 8.46 E4 nepm (net counts per minute) derived in Section 1.1.1.1 ar.d allows for a tritium concentration up to 1.5E-1 uCi/ml.

1.1.1.1 BV-1 Setpoint Determination Based On A Conservative Mix The HIGH-HIGH Alarm Setpoint for the Liquid Vaste Effluent Monitor (RM-LV-104) should be set at 1.69E4 ncpm and the HIGH-HIGH Alarm Setpoint for the Liquid Vaste Contamination Ponitor (RM-LV-116) should be set at 8.46E4 ncpm. These setpoints are based on the following conditions:

Source terms given in Table 1.1-la. These source terms have been generated from the computer code GALE. Revision 0 (NUREG-0017). The inputs to CALE are given in Appendix B.

• Dilution water flow rate of 15,000 gpm.

Discharge flow rate prior to dilution of 50 gpm for the Liquid Vaste Effluent Monitor (RM-LU-104).

Discharge flov rate prior to dilution of 10 gpm for the Laundry and Contaminated Shover Drains Monitor (RM-LV-116).

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

• * ( ~

HHSP =

f where:

HHSP = Monitor HIGH-HlGH Alarm Setpoint above background (nepm).

56.3 = Proportionality constant based on nominal flow conditions (56.3 = 1.69 E4 ncpm x 50 gpm + 1. 5 E4 gpm f or RM-LV-104 o r 56.3 = 8.46 E4 ncpm x 10 gpm 2 1.5 E4 gpm for RM-LV-116).

1-2 ISSUE 3

BV-1 and 2 ODCM i F = Dilution water flow rate (gpm), BV-1 Cooling Tower Blovdovn Rate (not including BV-2 Blovdown or the BV-2 release out through the Emergency Outfall Structure).

f = Discharge flow rate prior to dilution (gpm).

1.1.1.1.1 BV-1 Mix Padionuclides The " mix" (radionuclides and composition) of the liquid effluent was determined as follows:

a. The liquid source terms that are representative of the " mix" of the liquid effluent were determined. Liquid source terms are the radioactivity levels of the radionuclides in the effluent from Table 1.1-la.

b. The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (S1 ) for each individual radionuclide in the liquid effluent was determined as follows:

A S

3 _-

i [1.1(1)-2]

IA i i

vhere:

Ag - Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from Table 1.1-la.

1.1.1.1.2 BV-1 Maximum Acceptable Concentration (All Radionuclides)

The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (C ) v s t

determined by:

C t =

F [1.l(1)-3]

3 f I i MPC; where:

F = Dilution water flow rate (gpm), BV-1 Cooling Tover Blovdown Rate (not including BV-2 Blowdown or the BV-2 release out through the Emergency Outfall Structure).

= 15,000 gpm f = Maximum acceptable discharge flow rate prior to dilution (gpm).

= 50 gpm for Liquid Vaste Effluent Monitor (RM-LV-104).

I

= 10 gpm for Laundry and Contaminated Shover Drains Monitor (RM-LV-ll6).

1-3 ISSUE 3 I

BV-1 and 2 ODCM MPCg = Liquid effluent radioactivity concentration limit for radionuclide "i" (uci/ml) from Table 1.1-la. If not I listed there, from Reference 1.1.3.

S - The fraction of total radioactivity attributed to 1

radionuclide "i", from Equation [1.1(1)-2].

1.1.1.1.3 BV-1 Maximum Acceptable Concentration (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uci/ml) of radionuclide "i" in the liquid effluent prior to dilution (C ) was determined by: 3 C 11 1(1) 41 C1=s3 t 1.1.1.1.4 BV-1 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the radionuclides, C.R., was determined by:

C.R. =

I C; Ei (1.l(1)-5]

1 where:

Eg = Detection efficiency of the monitor for radionuclide "i" (cpm /uCi/ml) from Table 1.1-la. If not listed there, from Reference 1.1.4 1.1.1.1.5 BV-1 Monitor HHSP The monitor HIGH-HIGH Alarm Setpoint above background (nepm) should be set at the C.R. value. Since only one tank can be released at a time, adjustment of this value is not necessary to compensate for release from more than one source.

k 1-4 ISSUE 3

BV-1 and 2 ODCM 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the l setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the Liquid Vaste Effluent Monitor (RM-LV-104) and the Laundry and Contaminated Shower Drains Monitor (RM-LV-116) during all operational conditions.

The monitor alarm setpoint is set slightly above (a factor of 1.25) the count rate that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allovable discharge flov rate is reduced by the same factor.

When the discharge flow rate is limited by the radvaste discharge pump rate capacity or by administrative selection rather than the allovable flow rate determined form activity concentration, the alarm setpoint vill be proportionally adjusted based upon the excess dilution factor provided.

1.1.1.2.1 BV-1 Maximum Acceptable Discharge Flov Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by:

f _-

F [1.1(1)-6)

C.

1 1.25 E I i MPC.

1 where:

F = Dilution water flow rate, BV-1 Cooling Tover Blowdown (gpm).

The dilution water flow rate may include the combined cooling tower blowdown flov from both units exiting the discharge structure (but excluding emergency outfall structure flov) when simultaneous liquid discharges are administrative 1y prohibited.

C = Radioactivity concentration of radionuclide "i" in the i

liquid effluent prior to dilution (uci/ml) from analysis of the liquid effluent to be released.

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

MPC, = The liquid effluent radioactivity concentration limit for 2

radionuclide "i" (uci/ml) from Table 1.1-la. If not listed there, from Reference 1.1.3.

l 1-5 ISSUE 3

BV-1 and 2 ODCM 1.1.1.2.2 BV-1 Monitor Count Rate

} The calculated monitor count rate (nepm) above background attributed I to the radionuclides (C.R.) is determined by: j C.R. = 1.25 I Cy E g [1.1(1) 7]

i vhere:  ;

l E. = The detection efficiency of the monitor for radionuclide I "i" (cpm /uCi/ml) from Table 1.1-la. If not listed there, from Reference 1.1.4.

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

! response.

l 1.1.1.2.3 BV-1 Monitor HHSP The liquid effluent monitor HIGH-HIGH Alarm Setpoint above background (nepm) should be set at the C.R. value adjusted by any excess dilution factor provided as defined in the following equation:

HHSP = C.R. f, [1.1(1)-8]

I vhere:

HHSP = Monitor HIGH-HIGH Alarm Setpoint above background.

C.R. - Calculated monitor count rate (nepm) from equation

[1.1(1) 7}.

f = Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(1)-6).

f' = Actual maximum discharge flow rate,to be maintained for the discharge. *he reduced value of f may be due to pump limitations or administrative selection.

D t

1-6 ISSUE 3 I

l i 1

BV-1 and 2 ODCM 1.1.2 BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor HICH 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 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2 E-4 uCi/ml for dissolved or entrained noble gases.

The methodology described in Section 1.1.2.2 is an alternative method to be used to determine the monitor HIGH Alarm Setpoint (HSP). The methodology in Section 1.1.2.2 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 uCi/ml. This concentration is equivalent to a monitor response of 5.84E3 ncpm (net counts per minute above background). The HIGH Alarm Setpoint derived in Section 1.1.2.1 of 2.97E-5 uCi/ml above background allows for a tritium concentration of up to 6.28E-2 uCi/ml. The setpoint was obtained by use of a conversion factor (cpm to uCi/ml) of 5.09E-9 determined for the nuclide mix. (See Reference 1.2.5) 1.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix The HIGH Alarm Setpoint for the Liquid Vaste Effluent Monitor (2SGC-RQIl00) should be set at 2.97E-5 uCi/ml above background. This setpoint is based on the follo"ing conditions:

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

Dilution water flow rate of 7,800 gpm.

Discharge flow rate prior to dilution of 116 gpm for the Liquid Vaste Effluent Monitor (2SGC-ROIL 00).

A software conversion factor (cpm to uCi/ml) of 5.09E-9 associated with Liquid Vaste Effluent Monitor (2SGC-ROIL 00).

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

HSP = 4.42E-7 E [1.1(2)-1]

f

• here:

HSP = Monitor HIGH Alarm Setpoint (uCi/ml) above background.

4.42E 7 - Proportionality constant based on nominal flow conditions (4.42E-7 = 2.97E-5 uci/ml above background x 116 gpm +

7.8 E3 gpm).

l 17 ISSUE 3

BV-1 and 2 ODCM F = Dilution water flow rate, BV-2 Cooling Tower Blowdown Rate (gpm).

P f = Discharge flow rate prior to dilution (gpm).

1.1.2.1.1 BV-2 Mix Radionuclides The " mix" (radionuclides and composition) of the liquid effluent was determined as follows:

a. The liqui. ource terms that are representative of the " mix" of the lic- ffluent were determined. Liquid source terms are the radioac ity levels of the radionuclides in the effluent from Table 1.1-lb.

b. The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (S3 ) for each individual radionuclide in the liquid effluent was determined as follows:

A S.

2 i [1 l(2)-2]

"EA. I 1

where:

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

I 1.1.2.1.2 BV-2 Maximum Acceptable Concentration (All Radionuclides)

The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (C ) vas determined by:

C t =

F [1.l(2)-3]

g I

fI i MPC.

1 where:

F = Dilution water flow rate (gpm), BV-2 Cooling Tower Blowdown Rate (not including BV-1 Blovdown or the BV-2 release out through the Emergency Ou all Structure).

= 7,800 gpm.

f = Maximum acceptable discharge flow rate prior to dilution (gpm).

= 116 gpm for Liquid Vaste Process Effluent Monitor (2SGC-ROIL 00).

I l-8 ISSUE 3

BV-1 and 2 ODCM 1

MPC3 = Liquid effluent radioactivity concentration limit for radionuclide "i" (uci/ml) from Table 1.1-lb. If not listed there, from Reference 1.2.1.

S. = The fraction of total radioactivity attributed to radionuclide "i", from Equation 11.1(2)-2].

1.1.2.1.3 BV-2 Maximum Acceptable Concentration (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide "i" in the liquid effluent prior to dilution (C ) was 3

determined by:

C C1=Si t II' I }^'I 1.1.2.1.4 BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to the radionuclides, D.V., was determined by:

D.V. = 5.09E-9 I Cg E g 11.l(2)-5]

1 where:

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

E = Detection efficiency of the monitor for radionuclide "i" g

(cpm /uCi/ml) from Table 1.1-1b.

1.1.2.1.5 BV-2 Monitor HSP The monitor HIGH A11rm Setpoint above background (uCi/ml) should be set at the D.V. value.

1-9 ISSUE 3

BV-1 and 2 ODCM 1.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH Alarm Setpoint based on this flow rate for the Liquid Vaste Effluent Monitor (2SGC-ROIL 00) 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 allovable discharge flow rate is reduced by the same factor.

When the discharge flow rate is limited by the radvaste discharge pump rate capacity or by administrative selection rather than the allovable flow rate determined form activity concentration, the alarm setpoint vill be proportionally adjusted based upon the excess dilution factor provided.

1.1.2.2.1 BV-2 Maximum Acceptable Discharge Flav Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by:

F [1.l(2)-6]

C.

1 1.25 I i MPC 3

where:

F = Dilution water flow rate, BV-2 Cooling Tower Blovdown (gpm).

The dilution water flow rate may include the combined cooling tower blevdown flov from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges from both plants are administratively prohibited.

C. = Radioactivity concentration of tadionuclide "i" in the 2

liquid effluent prior to dilution (uci/ml) from analysis of the liquid effluent to be released.

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

MPC. = Tho liquid effluent radioactivity concentration limit for radionuclide "i" (uCi/ml) from Table 1.1-lb. If not listed there, from Reference 1.2.1.

p 1-10 ISSUE 3

BV-1 and 2 ODCM 1.1.2.2.2 BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background  !

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

D.V. = (1.25) (5.09E-9) E C. 1 E.

1 l1.1(2)-7]

3 where:

E g

= The detection efficiency of the monitor for radionuclide "i" (cpm /uci/ml) from Table 1.1-1b. If not listed there, from Reference 1.2.4.

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

5.09E Conversion factor (cpm to uCi/ml), an average determined for the source term mix.

1.1.2.2.3 BV-2 Monitor HSP The liquid effluent monitor HIGH Alarm Setpoint above be.ckground (uC1/ml) should be set at the D.V. value aajusted by any excess dilution factor provided as defined in the following equatien:

HSP = D.V. f, [1.l(2)-8]

E b-where:

HSP = Monitor HIGH Alarm Setpoint above background.

D.V. - Calculated monitor concentration reading (uC1/ml) from equation [1.1(2)-7).

f = Maximum acceptable discharge flow rate prior to dilution determined by equation 11.1(2)-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.

1-11 ISSUE 3

I BV-1 and 2 ODCM TABLE 1.1-la BV-1 LIQUID SOURCE TERM A

i i DETECTION -

ANNUAL RELEASE

" i EFFICIENCY NUCLIDE (Ci)** (uCi/ml)*** (cpm /uCi/ml)****

Cr-51 9E-5 2E-3 1.07E7 i Mn-54 2E-5 1E-4 8.80E7 Fe-55 BE-5 BE-4 5.20E3 Fe-59 5E-3 5E-5 '

9.02E7 Co-58 7.7E-4 9E-5 1.19E8 Co-60 1.0E-4 3E-5 1.72E8 Np-239 SE-5 1E-4 5.14E7 Br-83 6E-5 3E-6 1.36E6 Rb-86 IE-5 2E-5 7.57E6 Sr-89 2E-5 3E-6 7.84E3 Sr-91 1E-5 SE-5 1.27E8 Mo-99 3.90E-3 4E-5 2.42E7 Te-99m 5.37E-3 3E-3 9.00E7 Te-127m 1E-5 5E-5 5.34E4 '

Te-127 3E-5 2E-4 4.17ES Te-129m 7E-5 2E-5 5.37E6 Te-129 SE-5 8E-4 1.91E7 I-130 2.5E-4 3E-6 3.10E8 Te-131m 9E-5 4E-5 1.39E8 '

I Te-131 2E-3 --

1.09E8 I-131 6.027E-2 3E-7 1.06E8 Te-132 1.15E-3 2E-5 1.17E8 I-132 5.38E-3 BE-6 2.75E8 I-133 5.769E-2 1E-6 1.01E8 I-134 IE-5 2E-5 2.43E8 >

Cs-134 3.80E-3 9E-6 2.06E8 I<135 1.338E-2 4E-6 1.22E8 Cs-136 1.90E-3 6E-5 3.02E8 Cs-137 2.70E-3 2E-5 7.65E7 i Ba.140 1E-5 2E-5 5.21E7 La-140 1E-5 2E-5 1.74E8 H-3 1.60E+2 3E-3 OE0 All Others* 4E-5 1E-7 OE0 TOTAL

• 1.60E-1 -- --

i

• Excluding Tritium and Entrained Noble Gases

• • Reference (1.1.2) l *** Reference (1.1.3)

• • • • Reference (1.1.4) 1-12 ISSUE 3

--.--- ._ , _ ~-

BV-1 and 2 ODCM TABLE 1.1-lb BV-2 LIQUID SOURCE TERM E

y A

l MPC DETECTION ANNUAL RELEASE i EFFICIENCY NUCLIDE (Ci)*** (uci/ml)** (cpm /uCi/ml)*+**

Cr-51 1.00E-4 2E-3 2.01E7 Mn-54 2.50E-5 1E 4 1.27E8 Fe-55 1.30E-4 8E-4 -*

Fe-59 6.50E-5 SE-5 1.26E8 Co-58 1.10E-3 9E-5 1.82E8 Co-60 1.60E-4 3E-5 2.38E8 Np-239 3.20E-5 1 E-- 4 1.65E8 Br-83 2.90E-5 3E-6 2.42E6 Br-84 5.90E-9 --

1.38E8 Rb-86 3.70E-5 2E-3 1.04E7 Rb-88 0.0 --

4.84E7 Sr-89 2.20E-5 3E-6 1.83E4 Sr-90 8.50E-7 3E-7 -*

Sr-91 5.30E-6 SE-5 1.04E8 Mo-99 2.30E-3 4E-5 4.47E7 Tc-99m 2.10E-3 3E-3 1.40E8 Te-125m 1.90E-6 1E 4 3.94E5 Te-127m 2.10E-5 SE-5 1.26E5 Te-127 2.50E-5 2E 4 2.43E6 Te-129m 8.20E-3 2E-5 6.53E6 Te-129 5.30E-5 8E-4 1.96E7 I-130 2.30E 4 3E-6 5.18E8 l Te-131m 5.20E-3 4E-5 2.85E8 Te-131 9.40E-6 --

1.88E8 I-131 1.00E-1 3E-7 1.96E8 Te-132 7.80E-4 2E-3 1.76E8 I-132 2.30E-3 8E-6 4.22E8 I-133 6.50E-2 1E-6 1.73E8 I-134 4.60E-6 2E-5 4.06E8 Cs-134 3.00E-2 9E-6 3.25E8 I-135 9.20E-3 4E-6 1.71E8 Cs-136 3.90E-3 6E-5 4.28E8 Cs-137 2.20E-2 2E-5 1.28E8 Ba-140 9.30E-6 2E-5 7.50E7 La-140 8.40E-6 2E-5 3.0BE8

• Insignificant

• • Reference (1.2.1)

• • • Reference (1.2.3)

• • • • References (1.2.2) and (1.2.4) 1-13 ISSUE 3

BV-1 and 2 ODCM TABLE 1.1-1b (continued) l BV-2 LIQUID SOURCE TERM  !'

i'  !

Eg i A

i MPC DETECTION ANNUAL RELEASE i EFFICIENCY- f NUCLIDE (Ci)*** (uCi/ml)** (cpm /uci/ml)****' +

I Y-90 6.00E-7 2E-5 -* r Y-91m 3.60E-6 3E-3 1.59E8 f Y-91 4.40E-6 3E-5 3.55E5 Y-93 3.00E-7 3E-5 2.03E7 -

Zr-95 4.00E-6' 6E-5 1.35E8 i Nb-95 4.00E-6 1E-4 1.33E8 '{

Ru-103 2.70E-6 8E-5 1.71E8 .i Ru-106 8.20E-7 1E-5 -*  ;

Rh-103m 2.70E-6 1E-2 -* p Rh-106 8.20E-7 --

. 5.~ 65E7 ~ f 7.75E7- 1 Ce-141 4.00E-6 9E-5 Ce-143 8.60E-7 4E-5 1.20E8 Ce-144 2.60E-6 IE-5 1.87E7 Pr-143 2.30E-6 SE-5 1.63E0 ,.

Pr-144 2.60E-6 -- 3.40E6.  ;

H-3 5.50E+2 3E-3 0.0  !

.5 t

V

-t 9

I t

i i

'?

i i

l

.i e

• Insignificant j

• • Reference (1.2.1)

• • • Reference (1.2.3) ,

• • • • References (1.2.2) and (1.2.4) j 1-14 ISSUE.3 l

1

BV-1 and 2 ODCM REFERENCES .,

BV-1 LIQUID EFFLUENT MONITOR SETPOINTS i

I 1.1.1 " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412"; Table 2.1.3  ;

1.1.2 " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412"; Table 2.1.2 l 1.1.3 10 CFR 20, Appendix B, Table II, Column 2 and footnotes 1.1.4 "Duquesne Light Co. , Beat er Valley Nuclear Plant, Specification No. BVPS 414, Table V Nuclide Data, 5/30/74"; Table 2 and Figure 1 .i L;

REFERENCES  !

BV-2 LIQUID EFFLUENT MONITOR SETPOINTS 1.2.1 10 CFR 20, Appendix B, Table II, Column 2 and footnotes .

'I 1.2.2 Unit 2 DRMS Isotopic Ffficiencies; DLCo Calculation Package No.

• ERS-SFL-86-026 1.2.3 Stone and Vebster Computer Code LIQ 1BB; "

Normal Liquid Releases From A .Y Pressurized Vater Reactor" 1.2.4 Isotopic Efficiencies For 2SGC-RQIl00; DLCo Calculation Package No.

ERS-JVV-87-015 1.2.5 Conversion Factor for 2SGC-RQIl00; DLCo Calculation Package No.  ;

ERS VFW-87-021 h

1 i

I 1-15 ISSUE 3 ,

-. -, .- . -- - - - ...e- c , ,-

BV-1 and 2 ODCM 1.2 Compliance L'i th 10 CFR 20 MPC Limits (ODCM Appendix C CONTROL 3.11.1.1) l 1.2.1 Batch Releases 1.2.1.1 Pre-Release The radioactivity content of each batch release vill be determined prior to release in accordance with ODCM Appendix C, Table 4.11-1. In order to assure representative samples, at least two tank volumes of entrained fluid from each tank to be discharged shall be recirculated through the mixing eductors. This vill be a complished by recirculating the tank contents for at least the time periods indicated in Table 1.2-la and 1.2-lb. 8V-1 and BV-2 vill show compliance with ODCM Appendix C CONTROL 3.11.1.1 in the following manner:

The activity of the various radionuclides in the batch release, determined in accordance with ODCM Appendix C, Table 4.11-1, is divided by the minimum dilution flov to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:

Conc.

Ci R 1 [1.2-1]

" MDF where:

Coney = Concentration of radionuclide "1" at the unrestricted area (uCi/ml).

k C. = Concentration of radionuclide "i" in the potential batch release (uCi/ml).

R = Release rate of the batch (gpm).

MDF = Minimum dilution flov (gpm). (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are administratively prohibited).

The projected concentrations in the unrestricted area are compared to the concentrations in Appendix B, Table II of 10 CFR 20. The most common MPC. concentrations are listed in Table 1.1-la and 1.1-lb and were taken*from Appendix B, Table II of 10 CFR 20. Before a release is authorized, Expression [1. 2- 2 ] mus t be satisfied.

E.

I (Conci /MPC.) 1 $1 [1.2-2]  ;

where:

MPC. = Maximum permissible concentration of radionuclide "i" l (uci/ml) from Appendix B, Table II of 10 CFR 20.  ;

i 1-16 ISSUE 3

BV-1 and 2 ODCM 1.2.1.2 Post-Release l The concentration of each radionuclide following release from the batch tank vill be calculated in the unrestricted area in the following manner:

The average activity of radionuclide "i" during the time period of release is divided by the actual dilution flov during the period of release to obtain the concentration in the unrestricted area. This calculation is shown in the following equation:

Cone y p' _~ ik tk l1.2-3]

ADF p where:

Concik = The concentration of radionuclide "i" (uci/ml) at the unrestricted area, during the release period of time k.

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.

C. = Concentration of radionuclide "i" (uci/ml) in batch release 1

during time peirod k.

V g = Volume of tank released during time period k (gal).

ADF p' = Actual volume of dilution flow during the time period of release k (gal).

To show compliance with ODCM Appendix C CONTROL 3.11.1.1. the following rela'ionship must hold:

Ei (Coneg/MPCg ) $ 1 [1.2-4]

l 1-17 ISSUE 3

BV-1 and 2 ODCM 1.2.2 Continuous Releases Continuous releases of liquid effluents do not presently occur at BV-1 or BV-2. If they did occur, the cancentration of various radionuclides in the unrestricted area vould be calculated using l'quation [1.2-1] vith C ik' the concentration of isotope i in the continuous release. To show compliance with ODCM Appendix C CONTROL 3.11.1.1, Expression [1.2-4] must again hold.

N l 1-18 ISSUE 3

BV-1 and 2 ODCM TABLE 1.2-la BV-1 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS l

APPROXIMATE RECIRCULATION NAME MARK NO.

TIME (BY OPERATING MANUAL)

(hours)

Laundry And Contaminated 1LV-TK-6A & 6B 4.5 Shover Drain Tanks Lov Level Vaste Drain Tanks ILV-TK-3A & 3B 2.5" C

High Level Vaste Drain Tanks 1LV-TK-2A & 2B 6" a

Evaporator Test Tanks ILV-TK-5A & 5B 2 Steam Generator Drain Tanks ILV-TK-7A & 7B 11.5" Boron Recovery Test Tanks 1BR-TK-2A & 2B 9.7 l

• From BVPS-1 Operating Manual, Chapter 17, Section 4.

b Derived from information in BVPS-1 Operating Manual, Chapter 8, Section 1.

C Not normally a direct source of discharge.

d 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 vaste after isolation.

1-19 ISSUE 3

BV-1 and 2 ODCM TABLE 1.2-1b BV-2 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS k .

I l

APPROXIMATE RECIRCULATION NAME MARK NO.

TIME" (BY OPERATING MANUAL) hours) l 1

Liquid Vaste Tanks 2LVS-TK21A,B 8.3 I Steam Generator Blowdown 2SGC-TK21A,B 33.3 Hold Tanks SGC Test Tanks 2SGC-TK23A,B 6.0 l

l l>

^ The times listed are those required for two recirculations of a full tank with one recirculation pump in operationT~~ Partially full tank recirculation times are directly proportional to the fraction of the tank capacity occupied by the entrained liquid vaste after isolation. Values were derived from D information in BVPS-2 Operating Manuals 2.17.1 and 2.25.1.

1-20 ISSUE 3

BV-1 and 2 ODCM 1.3 Compliance With 10 CFR 50 Dose Limits (0DCM Appendix C CONTROLS 3.11.1.2 And 3.11.1.3) h BV-1 and 2 utilize the concept of a shared liquid radioactive vaste system according to NUREG 0133. This permits mixing of the liquid radvaste for processing. Since the resulting effluent release cannot accurately be ascribed to a rpecific reactor unit, the treated effluent releases are allocated as defined below.

1.3.1 Cumulation Of Doses (ODCM Appendix C CONTROL 3.11.1.2)

The dose contribution from the release of liquid effluents vill be calculated monthly for each batch release during the month and a cumulative summation of the total body and organ doses vill be maintained for each calendar month, current calendar quarter, and the calendar year to date. The dose contribution vill be calculated using the following equation:

DT = UAF I A; I* otp C g pF [1.3-1]

1 k=1 where:

DT = The cumulative dose commitment to the total body or any organ.

T, from the liquid effluents for the total time period m

I otp~ (mrem) k-1 otp = The length of the kth release over which Cgp' and Fp are ave; aged for all liquid releases (hours).

Cg = The average concentration of radionuclide, "i" (uCi/ml), in undiluted liquid effluent during time period ot fr m any liquid k

release.

A'T = The site related ingestion dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter (mrem-m1 per br-uCl).

m = Number of releases contributing to the cumulative dose, D.

UAF = Unit allocation factor. Provides apportionment of dose betveen BV-1 and BV-2. Normally set at 0.5 for each unit. (Must total to 1.0).

F p' = The near field average dilution factor for C during any liquid effluent release. Defined as theratibyof the average undiluted liquid vaste flov to the product of the average flow from the site discharge structure during the report period to unrestricted receiving waters, times 3. (3 is the site specific applicable factor for the mixing effeet of the BV-1 and BV-2 discharge structure).

= Vaste Flov (3)(Dilution Vater Flow) 1-21 ISEUE 3

BV-1 and 2 ODCM j 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 a factor of 10 below the limit specified in NUREG-0133, Section 4.3.

l The dose factor A ,was calculated for an adult for each isotope using the f ollowing equktion f rom NUREG-01?3.

Ag = 1.14E5 (730/Dy + 21BF j)DF; 11.3-2]

vhere:

1.14E5 = 1E6 gCi x 1E3 ml x 1 yr uCi 1 8760 hr 730 = Adult water consumption rate (liters /yr).

D = Far field dilution factor from the near field area within 1/4 mile of the release point to the potable water intake for adult water consumption.

21 = Adult fish consumption (kg/yr).

BF = Bioaccumulation factor for radionuclide "i" in fish from i

Table A-1 of Regulatory Guide 1.109 Rev. 1 (pCi/kg per pCi/1). If none, from Regulatory Guide 1.109, Rev. O.

DF = Dose conversion factor for radionuclide "i" for adults for a iT particular organ T from Table E-11 of Regulatory Guide 1.109 Rev. 1 (mrem /pCi). If none, from NUREG-0172 or Regulatory Guide 1.109, Rev. O.

A table of A. values for an adult at BV-1 and BV-2 are presented in Table 1.3-1.**

The far field dilution factor (D ) for BV-1 and BV-2 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 BV-1 and BV-2 (i.e., 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 belov the water surface, essentially fully mixed conditions vould 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 calendar year are compared to ODCM Appendix C CONTROL 3.11.1.2 as follows:

For the calendar quarter, D $ 1.5 mrem total body 11.3-3]

D ,3 5 mrem any organ 11.3-4]

l 1-22 ISSUE 3

BV-1 and 2 ODCM For the calendar year, h D f 3 mrem total body [1.3-5]

D $ 10 mrem any organ 11.3-6]

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 Technical Specification 6.9.2f must be filed with the NRC at the identified locations.

1.3.2 Projection Of Doses (ODCM Ap_gendix C CORTROL 3.11.1.3)

Doses due to liquid releases shall be projected at least once per 31 days in accordance with ODCM Appendix C CONTROL 3.11.1.3 and this section.

The Liquid Radvaste Treatment System shall be used to reduce the radioactive materials in each liquid vaste batch prior to its discharge, when the projected doses due to liquid eff.luent releases from each reactor unit, when averaged over 31 days vould exceed 0.06 mrem to the total 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-telease data.

[1.3-7]

D 31 - A+B 31 + C Vhen not including pre-release data, r- [1.3-8]

D -

6 1+C 31 T

where:

D Projected 31 day dose (mrem).

A 37 == Cumulative dose for quatter (mrem).

B - Projected dose from this release (mrem).

T = Current days into quarter.

C = Value which may be used to anticipate plant trends (mrem).

6 P

1-23 ISSUE 3

BV-1 and 2 ODCM TABLE 1.3-1 A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE lt (mrem /hr per uci/ml)

NUCLIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 C-14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 Na-24 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 P-32 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.19E 06 Cr-51 0.00E-01 0.00E-01 1.27E 00 7.62E-01 2.81E-01 1.69E 00 3.21E 02 Mn-54 0.00E-01 4.38E 03 8.35E 02 0.00E-01 1.30E 03 0.00E-01 1.34E 04 Mn-56 0.00E-01 1.10E 02 1.95E 01 0.00E-01 1.40E 02 0.00E-01 3.52E 03 Fe-55 6.59E 02 4.56E 02 1.06E 02 0.00E-01 0.00E-01 2,54E 02 2.61E 02 Fe-59 1.04E 03 2.45E 03 9.38E 02 0.00E-01 0.00E-01 6.83E 02 8.15E 03 Co-57 0.00E-01 2.10E 01 3.50E 01 0.00E-01 0.00E-01 0.00E-01 5.33E 02 Co-58 0.00E-01 8.95E 01 2.01E 02 0.00E-01 0.00E-01 0.00E-01 1.81E 03 Co-60 0.00E-01 2.57E 02 5.67E 02 0.00E-01 0.00E-01 0.00E-01 4.83E 03 Ni-63 3.12E 04 2.16E 03 1.05E 03 0.00E-01 0.00E-01 0.00E-01 4.51E 02 Ni-65 1.27E 02 1.65E 01 7.51E 00 0.00E-01 0.00E-01 0.00E-01 4.17E 02 Cu-64 0.00E-01 1.00E 01 4.70E 00 0.00E-01 2.52E 01 0.00E-01 8.53E 02 Zn-65 2.32E 04 7.37E 04 3.33E 04 0.00E-01 4.93E 04 0.00E-01 4.64E 04 Zn-69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 Br-83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 Br-84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 Br-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 Rbbb bbbhb h 9bb bh k b$k bh b$bbh b[ b bbb bk b.bbb bk 4 bbh- 9 Rb-89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 Sr-89 2.22E 04 0.00E-01 6.39E 02 0.00E-01 0.00E-01 0.00E-01 3.57E 03 br-9b b hk bb b bbb bk k 34b b5 b bbb b$ b bbb b$ b bbb bk k bbb b4 Sr-91 4.10E 02 0.00E-01 1.65E 01 0.00E-01 0.00E-01 0.00E-01 1.95E 03 Sr-92 1.55E 02 0.00E-01 6.72E 00 0.00E-01 0.00E-01 0.00E-01 3.08E 03 h9b b bbb b5 b$bbb bk k$bbb bh b$bbk bk b$bbb b$ b bbb b$ 6 kbb bb Y-91m 5.48E-03 0.00E-01 2.12E-04 0.00E-01 0.00E-01 0.00E-01 1.61E-02 Y-91 8.50E 00 0.00E-01 2.27E-01 0.00E-01 0.00E-01 0.00E-Oi 4.68E 03 Y-92 5.09E-02 0.00E-01 1.49E-03 0.00E-01 0.00E-01 0.00E-01 8.92E 02 Y-93 1.62E-01 0.00E-01 4.46E 03 0.00E-01 0.00E-01 0.00E-01 5.12E 03 Zr-95 2.53E-01 8.11E-02 5.49E-02 0.00E-01 1.27E-01 0.00E-01 2.57E 02 kr-9h bbh bh h bhE bb h9bb b bbb b$ 4 h6b b b bbb b b bb2 Nb-95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06

__ ____I - _. I _ ___ I $___I _ ___I _ __ I - --_I _

1-24 ISSUE 3

BV-1 and 2 ODCM TABLE 1.3-1 A

it VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE l (mrem /hr per uC1/ml)

NUCLIDE B0NE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Mo-99 0.00E-01 1.05E 02 2.00E 01 0.00E-01 2.38E 02 0.00E-01 2.43E 02 Tc-99m 8.97E-03 2.54E-02 3.23E-01 0.00E-01 3.85E-01 1.24E-02 1.50E 01 Tc-101 9.23E-03 1.33E-02 1.30E-01 0.00E-01 2.39E 01 6.79E-03 4.00E-14 Ru-103 4.51E 00 0.00E-01 1.94E 00 0.00E-01 1.72E 01 0.00E-01 5.26E 02 Ru-105 3.75E-01 0.00E-01 1.48E-01 0.00E-01 4.85E 00 0.00E-01 2.29E 02 Ru-106 6.70E 01 0.00E-01 8.48E 00 0.00E-01 1.29E 02 0.00E-01 4.34E 03 Ag Sb-124 m 9 48 b8 bb b 7.87E 00 1.49E-01 3.12E 00 1.91E-02 0.00E-01 6.13E 00 2.23E 02 b bbh b 2b bb b bbb b bbbbh Sb-125 5.03E 00 5.62E-02 1.20E 00 5.11E-03 0.00E-01 3.88E 00 5.54E 01 Tekhbm hbhEb 9bbbb2 b kkb bh h.h2b bh k b4k hk b bbb hk k b b b4 Te-127m 6.49E 03 2.32E 03 7.90E 02 1.66E 03 2.63E 04 0.00E-01 2.17E 04 Te-127 1.05E 02 3.78E 01 2.28E 01 7.81E 01 4.29E 02 0.00E-01 8.32E 03 Te-129m 1.10E 04 4.11E 03 1.74E 03 3.78E 03 4.60E 04 0.00E-01 5.55E 04 Te-129 3.01E 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 1.28E 03 8.21E 03 0.00E-01 8.05E 04 Te-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.27E 01 0.00E-01 2.67E 00 k Te-132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.39E 04 Te-134 3.10E 01 2.03E 01 1.25E 01 2.71E 01 1.96E 02 0.00E-01 3.44E-02 kh9 k k9h bh k bhE b b5b bh h bhb bb h k9h bh b bbb bk k 6kb bk I-130 2.75E 01 8.10E 01 3.20E 01 6.87E 03 1.26E 02 0.00E-01 6.97E 01 I-131 1.51E 02 2.16E 02 1.24E 02 7.08E 04 3.71E 02 0.00E-01 5.70E 01 kbh hbhbbb 9hEb 6 9bb bb 6$9bb bh b$kkE b bbbbb bbb I-133 5.16E 01 8.97E 01 2.74E 01 1.32E 04 1.57E 02 0.00E-01 8.06E 01 I-134 3.85E 00 1.05E 01 3.74E 00 1.81E 02 1.66E 01 0.00E-01 9.12E-03 6bb 4hEb bEb hh8hb hhb b bbk b 4 6hb Cs-134 2.98E 05 7.09E 05 5.79E 05 0.00E-01 2.29E 05 7.61E 04 1.24E 04 Cs-136 3.12E 04 1,23E 05 8.86E 04 0.00E-01 6.85E 04 9.39E 03 1.40E 04 bs bh b 8hh bb b hhk b5 b$4 b b bbb b b5 589bb4 bbb4 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 02 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 4b $bkb h 59k bh 2 b h bh b Obb bk b bok bk b bbk bk 5 bhb b$

La-142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E-01 2.56E 01

$ _-- $ -_- $ - -- _ _.$ $ __ I_ -_.I - -_$ --

1-25 ISSUE 3

l BV-1 and 2 ODCM j TABLE 1.3-1 j A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem /hr per uCi/ml) l NUCLIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Ce-143 4.64E-03 3.43E 00 3.79E-04 0.00E-01 1.51E-03 0.00E-01 1.28E 02 Cc-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 P- 8bb bbb4 9hhbb5 b bbb bk 4 bbb bb b bbb bk h 6[b kb Nd-147 3.79E-01 4.38E-01 2.62E-02 0.00E-01 2.56E-01 0.00E-01 2.10E 03 V-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 B.89E-03 0.00E-01 5.85E 02 1-26 ISSUE 3

BV-1 and 2 ODCM 1.4 LIQUID RADVASTE SYSTEM

( The liquid radvaste system has the capability to control, collect, process, store, recycle, and dispose of liquid radioactive vaste generated as a resul t of plant operations, including anticipated operational occurrences. This system also uses some of the components of the steam generator blevdown system for processing.

Simplified flow diagrams of the liquid radvaste 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 radvaste system is used, then any liquid vaste generated can be stored, processed and discharged from either BV-1 or BV-2.

k t

1-27 ISSUE 3

BV-1 and 2 ODCM FIGURE 1.4-1 BV-1 LIQUID PADWASTE SYSTEM STREAM STREAM F LOW COLLECTION, TREATMENT, C. DISCH ANGE evPS-2 No. HATE COOUNG

l. CONT SUMP 40GPD TOWER HIGH - LE VE L 1,1QUtu E VAPO R ATOR BLOWDOWN

2. AUX BLDG SUMP 2OOGPD ^S E ,JASTE TEST 7,800 G P M p

DRA

- EV,* ,FLTOR - T AN K $ (2)

3. L AB DR AINS 400GPO TANG (2) a ,

,(

5000 GAL 3,000 G AL 4 R.P. S A MPLES 35GPD C Lt G i' TOWER

5. MISC. SOURCES 660GPD i OLOW DOWN STEA'1 15,000 GPM

6. MISC. SOURC E S 40GPO CENERA1T)R

_ BLOWDOlIN

< BV P S - 1 E.-2 7 SG PRE FILTER IOGPO TANKS (2) COMBINED BACK WASH 30,0W cal, O t SCH A RGE 50 GPM POINT DORON TEST TANMS (2) 14,500 G AL P URIFIC AT ION CS ION BORON BOR(14

8. CVCS LETDOWN 60GPM ION EXCH ANGER 500# EXCHANGER RECOVERY EVAPOR ATORS(2)

DE G A SIFIL. R -

T A N K S(2) --

15GPM (B VP S - 1)

D F

• 10' 2,10

/H9 DF : lO,2,10 i 195,000 103 ALL DCEPT I GAL I O' I DVPS-2"3 PURIF IC A T IO N CS ION STEAM CVCS LETDOWN iN E XCH ANGER 500 # GENERATOR E X CH ANGEF1 -

9 (BVPS-2) 60GPM --

• DEGASIFIER BLOWDOWN OF 10, 2,10 OF a lO,2,0 0 EVAPORATOR

/ HR

10. BVPS-1 TUR DINE 7,2 OOGPD NO COLLECTION OR T R E ATMENT OLDG DRAINS E nvlRON u C N T DISCHARGES TO BVPS-1 (evPS-i nRD COOLING TOWER NOTES: DRAINAGE BLOWDOWN AND ENVIRONMENT

4. INPUT TO OVPS 2 STE AM GENER ATOR pqSCil ARGE POINT)

BLOWDOWN EVAPOR ATOR IS NOT USE D DURING NORM AL B ASE LOADED OPER ATIONS SEE SEC 11.2.I FOR DISCUSSION.

ISSUE 3 1-28 O - _ O &

BV-1 FIGURE 1.4-2 DV-2 LIQUID RAIMASTE SYSTEM ST3kAM STREAM A COLLECTION, TREATMENT, L DISCH ARGE BVPS-1 B V PS -l COOL I N G EVAPORATOR TOWER BLOWDOWN

1. CONT SUMP 40GPO FEED PUMPS l$,000 GPM

2. AUX BLOG SUMP 200 GPD WASTE Ligo]p WASTE BVP S+2 DR AINS ,

• WASTE TEST 100 GPM ,

COOLING

~

TOWER

. 3. MISC SOURCES 700 GPD TANMS(2) EVAPORATOR TANK S (2)

OR 8 LO W DOW N

4. R.P S A MPLES 35GPD STEAM S. L AB DRAINS 400 GPD B0 DOWN _

HOLD TANKS BVPS-16 -2 CONDENSATE DEMIN 2,685 GFD (2) 50.000 G AL COMBINED

6. RINSE WASTE COOLING TOW E R 0

OISCHARGE 7' BVPS-2 TURBtNE 7,200 GPO NO COLLECTION OR TRE ATMENTi si E N VIR ON M E NT POINT BUILDING DRAINS - (BVPS-2 YARD DR AIN AGE DISC H ARGE PolNT )

N0TES:

1. NO STE AM GENER ATOR BLOWDOWN IS DISCHARGED.

2. THE WASTE EVAPOR ATORS AR E ACTU ALLY TITt.ED STE AN GEN E R ATOR BLOWDOWN EVAPOR ATOR$.

3. DECONTAMIN Afl0N FACTORS STATE D ARE FOR EVArsM ATOR DISCHARGES TO BVPS- 2 SYSTEM INCLUDING THE CLE AN UP ION EXCHANGEHS. COOLING TOWER

4. THERE IS NO EXPECTED INPUT FROM DVPS 1 EVAPORATOR BLOWDOWN AND ENVIRONMENT FEED PUMPS DURING NORM AL BASE LOADED OPERATION.

OPER ATIONS IS DISCUSSEDIN SECTION 88 2.1.

S TURDINE DUeLDING DR AINS ARE PROCESSED OY THE Lioulo WASTE SYSTEM UPON HIGH ACitvlTY.

ISSUE 3 1-29

BV-1 and 2 ODCM 2.0 GASEOUS EFFLUENTS ODCM Appendix C CONTROLS applicable to dose rate apply to the site. The site dose rate is due to the summation of releases from both units. ODCM l Appendix C CONTROLS 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 radvaste system and are discharged from a common release point, the Process Vent, at the top oi the BV-1 cooling tower. At BV-1 and BV-2, the dose from the shared radvaste 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.

D i

2-1 ISSUE 3

BV-1 and 2 ODCM 2.1 Alarm Setpoints l 2.1.1 BV-1 Monitor Alarm Setpoint Determination ODCM Appendix C CONTROL 3.11.2.1 require that the dose rate in unrestricted areas due to noble gas radionuclides in the gaseous effluent released from the site shall be limited to $ 500 mrem /yr to the total body and to $ 3000 mrem /yr to the skin.

This section descr2bes the methodology used to maintain the release of noble gas radionuclides within ODCM Appendix C CONTROL 3.11.2.1 for the site and determines monitor setpoints for BV-1.

The methodologies described in Section 2.1.1.2, 2.1.2.2, and 2.1.3.2 provide an alternate means of determining monitor alarm setpoints that may be used when an analysis is performed prior to release.

Control of the site dose rate limit due to noble gases is exercised by a total of 8 effluent stream monitors, of which 3 are located in BV-1 (alternates exists for these monitors), and 5 are located in BV-2. As previously noted, BV-2 elevated releases are via the BV-1 Process Vent.

Differences exist between the setpoint presentations of the radiation monitoring systems of BV-1 and BV-2. First, there is a difference in setpoint terminology. Where BV-1 uses HIGH and HIGH-HIGH the BV-2 equivalents are ALERT and HIGH. The second difference is that the BV-2 setpoint is presented in uCi/cc rather than cpm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to D the BV-2 raw data (cpm). The presentation is technically correct user only is for cautioned that the uCi/cc 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 vill be correct for properly controlling dose rate, but the indicated uCi/cc value may differ from the actual value.

All effluert monitors specified herein have HIGH-HIGH (BV-1) or HIGH (BV-2) Alarm Setpoints established at 30 percent of the site limit, and except 3 monitors noted belov, HIGH (BV-1) or ALERT (BV-2) Alatm Setpoints established at 10 percent of the site limit.

k 2-2 ISSUE 1

BV-1 and 2 ODCM Monitor Setpoint Specifications Based on Fraction Of Site Limit UNIT, RELEASE POINT AND MONITOR FRACTION OF SITE LIMITING DOSE I Unit 1, Ventilation Vent 30% (HIGH-HIGH) 10% (HIGH)

RM-VS-101B (Alt. RM-VS-109 CH #5)

Unit 1, Containment Vent 30% (HIGH-HIGH) 10% (HIGH)

RM-VS-107B (Alt. RM-VS-110 CH #5)

Units 1/2, Process Vent 30% (HIGH-HIGH) 10% (HIGH)

RM-GV-108B (Alt. RM-GV-109 CH #5)

Unit 2, Containment Vent 30% (HIGH) 10% (ALERT) 2HVS*R0109B Unit 2, Ventilation Vent 30% (HIGH) 10% (ALERT) 2HVS-R0101B Unit 2, Vaste Gas Storar uit Vent 30% (HIGH) 0.1% (ALERT) 2RMO-R0303B Unit 2, Decontamination Building Vent 30% (HIGH) 0.3% (ALERT) 2RM0-R0301B Unit 2, Condensate Polishing Building Vent 30% (HIGH) 0.6% (ALERT) 2HVL-R0112B Units 1/2, Turbine Building Vent < 0.1% (Unmonitored)

Vith 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 ODCM Appendix C CONTROL 3.11.2.1:

• The site dose rate is less than 50% of the site limit when all monitors are belov the HIGH (BV-1) and ALERT (BV-2) Alarm Setpoints.

• Vith all monitors below the normal HIGH-HIGH (BV-1) and HIGH (BV-2)

Alarm Setpoints, a combination of 3 HIGH (BV-1) or ALERT (BV-2) Alarms indicate releases may have exceeded site limits.

To provide operational flexibility any 1 of the 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) Alarm Setpoints.

From this condition any 1 monitor alarm would indicate the site dose rate limit may have been exceeded.

I 2-3 ISSUE 3

BV-1 and 2 ODCM A release may be batch or continuous in nature. Batch refers to releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment ventings and purges, and systems or components with inftequent use. Batch releases may be due to operational variations which result in radioactive releases greater than 50% of the releases normally considered as continuous. Batch releases from these sources during normal operation, including anticipated operational 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 2.1.1.1 through 2.1.3.2.

k l

1 l

l I

h 24 ISSUE 3

BV-1 and 2 ODCM 2.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix For Ventilation Vent And Containment Building Vent Releases (Ground Releases)

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

BV-1 ALARM SETPOINTS FOR GROUND RELEASES cpm AB0VE BACKGROUND (P) PRIMARY

• 30% 10%

MONITOR SITE SITE (A) ALTERNATE LIMIT LIMIT MONITOR C.R. HHSP HSP

• Continuous Release Via The (P)RM-VS-101B 3.00E3 9.00E2 3.00E2 BV-1 Ventilation Vent (A)RM-VS-109(5) 1.47E3 4.40E2 1.47E2 Batch Release Of Containment (P)RM-VS-101B 3.90E2 1.17E2 3.90E1 Purge Via The BV-1 Ventila- (A)RM-VS-109(5) 4.68E2 1.40E2 4.68E1 tion Vent Continuous Release Via The (P)RM-VS-107B 6.44E3 1.93E3 6.44E2 BV-1 Containment Building (A)RM-VS-110(5) 3.38E3 1.01E3 3.3BE2 Vent

• Batch Release Of Containment (P)RM-VS-107B 1.93E3 5.80E2 1.93E2 l Purge Via The BV-1 Contain- (A)RM-VS-110(5) 1.01E3 3.04E2 1.01E2 ment Building Vent

• Vhen the primary monitor is out of service, and ODCM Appendix C I CONTROL 3.3.3.10 can be met for the respective alternate monitor, the alternate setpoints may be utilized.

The setpoints were determined using the following conditions and information:

• Source terms given in Table 2.1-la. These gaseous source terms were derived from Stone & Vebster computer codes GASlBB (which is similar l to the NRC CODE GALE, NUREG-0017) and DRAGON 4 (for the containment vacuum pump sources). Table 2.1-la does not include particulates and iodines, which are not used in site noble gas dose rate calculations.

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

l l Discharge flow rate of 62,000 efm for the BV-1 Ventilation Vent

! (Continuous).

l l Discharge flow rate of 92,000 cfm for the BV-1 Ventilation Vent

! (Batch ' lease of containment purge).

l b l

l 2-5 ISSUE 3 l

l 1

BV-1 and 2 ODCM

" Discharge flow rate of 49,300 cfm for the BV-1 Containment Vent (Both continuous and batch release of Containment Purge).

I

• Information listed under Beferences - Gaseous Effluent Monitor Setpoints.

The calculation method given in Sections 2.1.1.1.1 through 2.1.1.1.7 was used to derive the monitor setpoints for the following operational conditions:

Continuous release via the BV-1 Ventilation Vent.

• Continuous release via the BV-1 Containment Building Vent.

Batch release of BV-1 Containment Purge via the BV-1 Ventilation Vent.

Batch release of BV-1 Containment Purge via the BV-1 Containment Building Vent.

2.1.1.1.1 BV-1 Mix Radionuclides 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 vere selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.

k Gaseous source terms can be obtained from Table 2.1-la.

b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (S. for each individual noble gas radionuclide in the gaseous efflubn)t was determined by:

A S.

1 i [2.1(1)-1]

• E A,

• i vhere:

A = The total radioactivity or radioactivity concentration of j

noble gas radionuclide "i" in the gaseous effluent from Table 2.1-la.

2.1.1.1.2 BV-1 Maximum Acceptable Release Rate (k' hole Body Exposure)

The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (O ) based upon the whole body t

exposure limit was calculated by:

500 [2.1(1)-21 0 - (X/0) E K. 1 S.

I i D

2-6 ISSUE 3

BV-1 and 2 ODCM where:

1 (X/0)" = The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond t I boundary for all sectors (sec/m3)he unrestricted from area Table 2.2-5.

3

= 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 3

(sec/m ) from Table 2.3-36.

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

(X/0)'" - The highest calculated annual average relative concentration of effluents released via the Containment Building Vent for any area at or beyond the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-4.

- 9.24E-5 sec/m3 for continuous releases.

(X/q)C" - The short term relative concentration of effluents released via the containment building vent for any area at or beyond the 3unrestricted area boundary for any sectors (sec/m ) from Table 2.3-35.

= 3.08E 4 sec/m for batch release of containment purge.

Kg =

The total whole body dose factor due to gamma 3 emissions from noble gas radionuclide "i" (mrem / year /uCi/m )

from Table 2.2-11.

S g

= From equation 12.1(1)-1] above.

2.1.1.1.3 BV-1 Maximum Acceptable Release Rate (Skin Exposure) 0 was also determined based upon the skin exposure limit by:

0 3000 t = (gjg) 7 (g, , 1,1g,) 3,

[2.l(1)-3]

i 1 1 g

vhere:

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

radionuclide "i"(mrem / year /uci/m3 ) from Table 2.2-11.

M. = The air dose factor due to gamma, emissions from noble gas radionuclide "i"(mrad / year /uCi/m#) from Table 2.2-11.

I 2-7 ISSUE 3

BV-1 and 2 ODCM 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, l (mrem / mrad).

(X/0) = Same as in Section 2.1.1.1.2.

2.1.1.1 4 BV-1 Maximum Acceptable Release Rate (Individual Radionuclide)

The maximum acceptable release rate (uci/sec) of noble gas radionuclide "i" in the gaseous effluent (0 ) for each individual 3

noble gas radionuclide in the gaseous effluent was determined by:

Og=Sg O t

[ 2.1 ( 1 )- 4 )

(NOTE: Use the lover of the 0 values obtained in Section 2.1.1.1.2 and 2!1.1.1.3.)

2.1.1.1.5 BV-1 Maximum Acceptable Concentrations (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uci/cc) of noble gas radionuclide "i" in the gaseous effluent (C;) for each individual noble gas radionuclide "i" in the gaseous etfluent was determined by:

. - Oi C.

1 = [2.1(1)-5]

7 where:

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

= 62.000 cfm (BV-1 Ventilation Vent)

= 49,300 cfm (BV-1 Containment Building Vent) 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-3 ft3 jcc),

l I

2.1.1.1.6 BV-1 Monitor Count Rate l The calculated monitor count rate (nepm) above background attributed l l to the noble gas radionuclide (C.R.) was determined by. l i ,

i C.R. =IC [2.1(1)-6)J Eg 3

1 where:

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

D 2-8 ISSUE 3

BV-1 and 2 ODCM 2.1.1.1.7 BV-1 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:

a. The monitor HIGH-HIGH Alarm Setpoint above background (ncpm) was determined by:

HHSP = 0.30 C.R. [2.1(1)-7)

b. The monitor HIGH Alarm Setpoint above background (ncpm) was determined by:

HSP = 0.10 C.R. {2.1(1)-8)

NOTE: The values 0.3 for the HHSP and 0.1 for the HSP are fractions of the total radioactivity concentration that may be released via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units.

4 4

2-9 ISSUE 3

BV-1 and 2 ODCM i

l 2.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release For Ventilation Vent And Containment Building Vent Releases (Ground  ;

} Releases) i Vhen the setpoints established using "the calculated mix" for ground 1 releases do not provide adequate flexibility for operational needs, the method described belov may be used in lieu of that set forth in Step 2.1.1.1. In this case. the results of sample analysis are used to determine the source term " mix." This calculational method applies to ,

gaseous releases via the Ventilation Vent and via the Containment Building Vent when determining the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HlGH Alarm Setpoint based on this flow rate for the Ventilation Vent Gas Monitor (RM-VS-101B) and the Containment Building Gas Monitor (RM-VS-107B) during the following operational conditions:

• Batch release of Containment Purge via the BV-1 Ventilation Vent.

Batch release of Containment Purge via the BV-1 Containment Building Vent.

2.1.1.2.1 BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from Containment Vent or Ventilation Vent during purging is determined as follows:

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

1.06 S T (2.l(1)-17]

f " (X/q) IK C;1 1

where:

1.06 = 500 mrem /yr x 2.12E-3 500 mrem /yr = dose rate limit 2.12E-3 = unit conversion factor (60 sec/ min x 3.53E-5 ft /cc)

S = Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 2.1.1. To exceed 60% of the site limit from one release point, the temaining release point limits must  !

be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit. ,

i l

T = Maximum valve for T is 16 based on the limiting restriction in ODCM Appendix C CONTROL 3.ll.2.1.a where the dose rate for a containment purge may be averaged over a time pe:iod not to exceed 960 minutes. (As

) containment air volume change time period is 60 minutes; T = 960/60 = 16). See Reference 2.1.6.

.?-10 ISSUE 3

BV-1 and 2 ODCM (X/q)"" = The highest calculated short term relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 de unrestr M ed area boundary for all sectors (sec/m ) from Table 2.3-36.

= 3.32E 4 sec/m (X/q)'" = The highest calculated short term relative concentration of effluents released via the Containment Building Vent for areas at or beyond the unrestricted area boundary for all sectors (sec/m3) from Table 2.3-37.

3

= 3.08E-4 sec/m K = The total whole body dose factor due to gamma e 1

from noble gas radionuclide "i" (mrem / year /uCi/m 3) missions from Table 2.2-11.

C = The undiluted radioactivity concentration of noble gas 3

radionuclide "i" in the gaseous ource (uCi/cc) as determined by analysis of the r. to be released.

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

6.36 S T [2.1(1)-18]

f _- (X/q) E (Lg + 1.1M;) C; where:

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

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

L.

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

M. = The air dose factor due to gamma emissions from I

noble gas radionuclide "i" (mrad / year /uCi/m ) from Table 2.2-11.

l (X/q) = Same as in Section 2.1.1.2.1.a.

c. The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit I

(Section 2.1.1.2.1.a) and based on the skin exposure limit (Section 2.1.1.2.1.b). The actual purge flow rate (cfm) must be l

maintained at or below this calculated (f) value or the discharge cannot be made from the vent.

I i 1

2-11 ISSUE 3 l

BV-1 and 2 ODCM 2.1.1.2.2 BV-1 Honitor Setpoints l The monitor alarm setpoints above background are determined as follows:

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

fIC Eg g [2.1(1)-19]

HHSP = ,

F where:

f = The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1.1.2.1.

E = The maximum actual or design effluent flow rate (cfm) at the point of release.

= 92,000 cfm (BV-1 Ventilation Vent -- design)

= 49,300 cfm (BV-1 Containment Vent -- design)

C, = The undiluted radioactivity concentration of noble gas 1

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

E = The detection efficiency of the monitor for noble gas 2

radionuclide "i" (cpm /uci/cc) from Table 2.1-2a.

b. Vhen a HIGH-HIGH set point has been calculated according to this section, the monitor HIGH Alarm Setpoint above background (ncpm) is determined as follows:

HSP = HHSP x 0.33 [2.1(1)-20]

I 2-12 ISSUE 3

BV-1 and 2 ODCM 2.1.2 BV-2 Monitor Alarm Setpoint Determination See Section 2.1.1 for a description of Monitor Alarm Setpoint Determinations.

l 2.1.2.1 BV-2 Setpoint Determination Based On A Calculated Mix For Ventilation Vent, Containment Vent, Condensate Polishing Building Vent, Decontamination Building Vent. and Vaste Gas Storage Vault Vent Releases The table below gives the calculated monitor count rate above background (C.R.) in ncpm, and provides the equivalent monitor indication (D.V.) in net uCi/cc associated with the most limiting site dose rate limit (i.e.. 500 mrem /yr Total Body or 3000 mrem /yr Skin).

The HIGH alarm setpoint (HSP) in uCi/cc above background, and the ALERT alarm setpoint (ASP) in uCi/cc above background for each vent and operational condition should be as follows:

BV-2 ALARM SETF01NTS FOR GROUND RELEASES uCi/cc ABOVE BACKGIOUND 30%

• SITE SITE C.R. D.V. LIMIT LIMIT MONITOR ncpm uCi/cc HSP ASP

' Continuous 2HVS-R0101B 8.26E3 3.01E-4 9.04E-5 3.01E-5 Release {

Via The BV-2 Ventilation Vent Batch Release Of 2HVS-R0101B 1.13E3 4.13E-3 1.24E-3 4.13E-6 Containment Purge Via The BV-2 Ventilation Vent

' Continuous 2HVS*R0109B 4.32E3 1.06E 4 3.17 E- 5 1.06E-5 Release Via The BV-2 Containment Vent

• Batch Release Of 2HVS*R0109B 2.09E3 4.05E-5 1.21E-5 4.05E-6 Containment Purge Via The BV-2 Containment Vent

' Continuous 2HVL-R0112B 2.89E4 1.61E-3 4.82E 4 9.63E-6 Release Via The BV-2 Condensate Polishing Building Vent

" Con t ir.uous 2RMO-R0301B 5.66E4 3.15E-3 9.44E 4 9.44E-6 Release Via The BV-2 Decontamination Building Vent

• Continuous 2RMO-R0303B 8.03E5 2.24E-2 6.71E-3 2.24E-5 Felease Via The BV-2 Vaste Gas Storage Vault Vent

• Alert Setpoint from Section 2.1.2 Fraction Of Site Limiting Dose Rate.

2-13 ISSUE 3

BV-1 and 2 ODCM The setpoints were determined using the following conditions:

• Source terms given in Table 2.1-1b. These gaseous source terms vere l

derived from Stone & Vebster computer codes GAS 1BB (which is similar to the NRC CODE GALE, NUREG-0017) and DRAGON 4 (for the containment vacuum pump sources). Table 2.1-lb does not include particulates and iodines, which are not used in site noble gas dose rate calculations.

The Containment Building Purge radionuclide 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. However, 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 Vaste Gas Storage Vault ventilation exhaust is also not normally radioactive.

However, the monitor alarm setpoint is based on the assumption that the ventilation exhaust radionuclide spectrum is similar to the gaseous inventory in the system housed by the vaste gas storage vault. This spectrum is listed in Table 2.1-lb under Gaseous Vaste System.

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

• Discharge flow rate of 23,700 cfm for the BV-2 Ventilation Vent (Continuous).

I

• Discharge flow rate of 53,700 cfm for the BV-2 Ventilation Vent (Batch release of containment purge).

Discharge flow rate of 59,000 cfm for the BV-2 Containment Vent (Both continuous and batch release of containment purge).

• Discharge flow rate of 30,556 cfm for the BV-2 Condensate Polishing Building Vent.

Discharge flow rate of 12,400 cfm for the BV-2 Decontamination Building Vent.

• Discharge flov rate of 2,000 cfm for the BV-2 Vaste Gas Storage Vault Vent.

The calculation method giver 2 .1 Sections 2.1.2.1.1 through 2.1.2.1.7 was used to derive the a; arm setpoints for the Ventilation Vent Gas Monitor (2HVS-R0101B), Containment Vent Gas Monitor (2HVS*R0109B),

Condensate Polishing Building Vent Gas Monitor (2HVL-R0112B),

Decontamination Building Vet Gas Monitor (2RMO-RQ301B), and Vaste Gas Storage Vault Vent Gas Monitor (2RMO-R0303B) during the following operational conditions:

• Continuous release via the BV-2 Ventilation Vent.

l Continuous release via the BV-2 Containment Vent.

2-14 ISSUE 3

BV-1 and 2 ODCM

• Batch release of BV-2 Containment Purge via the BV-2 Ventilation Vent.

• Batch release of BV-2 containment Purge via the BV-2 Containment Vent.

• Continuous release via the BV-2 Condensate Polishing Building Vent.

• Continuous release via the BV-2 Decontamination Building Vent.

• Continuous release via the BV-2 Vaste Gas Storage Vault Vent.

2.1.2.1.1 BV-2 Mix Radionuclides The " mix" (noble gas radionuclides ano composition) of the gaseous effluent was determined as follows:

a. The gaseous source terms that are representative of the " mix" of i the gaseous effluent vere selected based on the relative stream composition and volumetric flovrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent, i Gaseous source terms can be obtained from Table 2.1-lb.

b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (S ) for each individual noble gas radionuclide in the gaseous efflue,nt was determined by:

A S i 12.l(2)-1]

fA i vhere:

A g = The radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from Table 2.1-lb.

2.1.2.1.2 BV-2 Maximum Acceptable Release Rate (Whole Body Exposure)

The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (O ) based upon the whole body t

exposure limit was calculated by:

0 500 12.1(2)-2]

t =

(X/0) EKg S 3 i

vhere:

(X/0)yy = The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5.

3

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

l 2-15 ISSUE 3

BV-1 and 2 ODCM (X/q)vv = The short term relative concentration of effluents released via the Ventilation Vent for any atea at or beyond the unrestricted area boundary for all sectors  ;

3 (sec/m ) from Table 2.3-36.

= 3.32E 4 sec/m for batch telease of containment purge.

(X/0)C" = 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 )3 from Table 2.2-4.

3

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

(X/q)cv = released The shortvia term relative concentration of effluents the containment vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-35.

= 3.08E-4 sec/m for batch release of containment purge.

(X/0)CP = The highest calculated annual average relative concentration of effluents released via the Condensate Polishing Building Vent for any area at or beyond 3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-10.

3

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

(X/0)dv = The highest calculated annual average relative concentration of effluents released via the Decontamination Building Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-8.

3

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

(X/0)yy = The highest calculated annual average relative concentration of effluents released via the Vaste Gas Storage Vault Vent for any area at or beyond the 3 unrestricted area boundary for all sectors (sec/m )

from Table 2.2-9.

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

Ky = The total whole body dose factor due to gamma 3 emissions from noble gas radionuclide "i" (mrem / year /uci/m )

from Table 2.2-11.

S = From equation [2.l(2)-1].

i I

2-16 ISSUE 3

BV-1 and 2 ODCM 2.1.2.1.3 BV-2 Maximum Acceptable Release Rate (Skin Exposure) 0 was also determined based upon the skin exposure limit by: ,

0 3000 [2.1(2)-3]

" (X/0) I (Lg + 1.1Mg ) S g i

where:

Lg - The skin dose factor due to beta emissions from noble gas 3

radionuclide "i"(mrem / year /uci/m ) from Table 2.2-11.

My = The air dose factor due to gamma emissions 3

from noble gas radionuclide "i"(mrad / year /uci/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/0) - Same as in Section 2.1.2.1.2.

2.1.2.1.4 BV-2 Maximum Acceptable Release Rate (Individual Radionuclide)

The maximum acceptable release rate (uci/sec) of noble gas radionuclide "i" in the gaseous effluent (0 3 ) for each noble gas radionuclide in the gaseous etfluent was determined by:

Og=Sg O t

[2.1(2) 4]

(NOTE: Use the lover of the 0 values obtained in Section 2.1 2.1.2 and 2!1.2.1.3.)

2.1.2.1.5 BV-2 Maximum Acceptable Concentrations (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (C )g for each individual noble gas radionuclide in the gaseous effluent was determined by:

2.12E-3 0 1 C.

1 m

[2.1(2)-5]

p where:

F = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 2.1.2.1.

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

2-17 ISSUE 3 l

l

l BV-1 and 2 ODCM 2.1.2.1.6 BV-2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide (C.R.) vas determined by:

C.R. - ECg E g [2.1(2)-6)]

i vhere:

E. - The detection efficiency of the monitor for noble gas 2

radionuclide "i" (cpm /uci/cc) from Table 2.1-2b.

2.1.2.1.7 BV-2 Monitor Setpoints The monitor alarm setpoints above background were determined as follows:

a. The monitor HIGH Alarm Setpoint above background (uCi/cc) was determined by:

' * * * ( ~

HSP =

E}iave

b. The monitor ALERT Alarm Setpoint above background (uCi/cc) was determined by:

ggp , FR x C.R. 12.1(2)-8)

D E i ave where:

FR = Fraction of limiting dose rate for the respective radiation monitor (from Section 2.1.2).

E. = The C.R. of equation [2.1(2)-6] divided by the sum of 1 ""*

the C for the respective mix.

i D

2_18 ISSUE 3

BV-1 and 2 ODCM 2.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release (Ground Releases)

When the setpoints established using "the calculated mix" do not operational needs, the method I

provide adequate flexibility for described belov may be used in lieu of that set forth in Section 2.1.2.1. In this case, the results of sample analysis are used to determine the appropriate nuclide 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 BV-2 Ventilation Vent.

• Batch release of Containment Purge via the BV-2 Containment Vent.

2.1.2.2.1 BV-2 Maximum Acceptable Release Rate The maximum acceptable discharge flow rate from the Containment Vent or Ventilation Vent during purging is determined as follows:

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

l 1.06 S T [2.1(2)-17) l

, ~ (X/q)

K; C3 l

l vhere:

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

= (60 sec/ min x 3.53E-5 ft fcc) t l Up S = Percent of site dose rate released via this pathway.

to 60% of the site dose rate is permissible for one release point under the alarm setpoint rules of i I

Section 2.1.2. To exceed 60% of the site limit from one release point, the remaining release point limits must l 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 ODCM Appendix C CONTROL 3.11.2.1.a where the dose rate for a containment purge may be averaged l

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 2.2.4.

2-19 ISSUE 3 o --- _ ------ --- - - - - - - - - - - - - - - - - - - - - - - - - - _ - _ _ _ - _ _ _ _ _ _ _ _

EV-1 and 2 ODCM (X/q)yy = The highest calculated short term felative concentration of effluents released via the Ventilation the unrestricted area D Vent for any area at or beyond boundary for all sectors (sec/m3) from Table 2.3-36.

= 3.32E-4 sec/m (X/q)'" = The highest calculated 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 2.3-37.

7

= 3.08E-4 sec/m' Ky = The total whole body dose factor due to gamma "*

from noble gas radionuclide "i" (mrem / year /uCi/m 3*) *I S S i from Table 2.2-11.

C. = The undiluted radioactivity concentration of noble gas 2

radionuclide "i" in the gaseous source (uCi/ce) as determined by analysis of the gas to be released.'

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

6.36 S T [2.1(2)-18]

f " (X/q) I (L. I

+ 1.1M.)

1 C.1 where:

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

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

Ly - The skin dose factor due to beta emissions 3'* f noble gas radionuclide "i" (mrem / year /uci/m ) from Table 2.2-11.

M = The air dose factor due to gamma emissions from 3

noble gas radionuclide "i" (mrad / year /uCi/m3 ) from Table 2.2-11.

(X/q) = Same as in Section 2.1.2.2.1.a.

c. The flow rate (f) is determined by selecting the smaller of the calculated (f) values based on the whole body exposure limit (Section 2.1.2.2.1.a) and based on the skin exposure limit (Section 2.1.2.2.1.b). The actual purge flow rate (cfm) must be maintained at or below this calculated (f) value or the discharge cannot be made from the vent.

k 2-20 ISSUE 3

BV-1 and 2 ODCM 2.1.2.2.2 BV-2 Monitor Setpoints The monitor alarm setpoints above background are determined as l follows:

a. The calculated monitor HIGH Alarm Setpoint above background (net uCi/ce) attributed to the noble gas radionuelides is determined by:

f I C. E.

1 1

[2.1(2)-19]

3 HSP - '

E F i ave where:

f = The maximum acceptable containment purge flow rate (cfm) determined in Section 2.1.2.2.1.

F = The maximum actual or design effluent flow rate (cfm) at the point of release.

= 53,700 cfm (BV-2 Ventilation Vent -- design)

= 59,000 cfm (BV-2 Containment Vent -- design)

C 3

= The undiluted radioactivity concentration of noble gas.

radionuclide "i" in the gaseous source (uCi/ce) as determined by analysis of the gas to be released.

l E = The detection efficiency of the monitor for noble gas 3

radionuclide "i" (cpm /uci/cc) from Table 2.1-2b.

E = The C.R. of equation [2.1(2)-6] divided by the sum of

^V*

the C; for the respective mix.

NOTE: To enable maintaining a constant conversion factor from cpm to uCi/cc in the Digital Radiation Monitoring System software, the " calculated mix" is used rather than the analysis mix to calculate E. above. This does not cause any change in the function of* ^"*the monitor setpoint to properly control dose rate. However, the monitor indicated uCi/cc value may differ from the actual value.

b. When a HIGH Alarm Setpoint has been calculated according to this section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows:

ASP = HSP x 0.33 [2.1(2)-20]

2-21 1500E 3

BV-1 and 2 ODCM 2,1.3 BV-1/2 Monitor Alarm Setpoint Determination l See Section 2~1.1 for a description of Monitor Alarm Setpoint Determination.

2.1.3.1 BV-1/2 Setpoint Determination Baseri on A Calculated Mix For Process Vent Releases (Elevated Releases)

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:

BV-2 AND ALARM SETPOINTS FOR ELEVATED RELEASES cpm AB0VE BACKGROUND (P) PRIMARY

• 30% 10%

MONITOR SITE SITE (A) ALTERNATE LIMIT LIMIT MONITOR C.R. HHSP HSP

' Continuous Release (P)RM-GV-108B 3.83E7 1.15E7 3.83E6 (A)RM-GV-109(5) 2.20E7 6.61E6 2.20E6 Batch Release Of BV-1 Decay (P)RM-GV-108B 3.93E5 1.18E5 3.93E4 Tanks (A)RM-GV-109(5) 7.87E6 2.36E6 7.87E5 k

• Batch Release of BV-2 Decay (P)RM-GV-108B 2.11E5 6.33E4 2.11E4 Tanks (A)RM-GV-109(5) 7.75E6 2.32E6 7.75E5 Batch Release Of BV-1 (P)RM-GV-108B 5.55E6 1.67E6 5.55E5 Containment Purge (A)RM-GV-109(5) 7.37E6 2.21E6 7.37E5

• Batch Release Of BV-2 (P)RM-GV-108B 5.38E6 1.16E6 5.38E5 Containment Purge (A)RM-GV-109(5) 7.34E6 2.20E6 7.34E5

• Vhen the primary monitor is out of service, and ODCM Appendix C CONTROL 3.3.3.10 can be met for the respective alternate monitor, the alternate setpoints may be utilized:

The setpoints were determined using a calculated mix from the FSAR and discharge flow rate of 1450 cfm for the BV-1/2 Process Vent.

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

Continuous release via the BV-1/2 Process Vent.

Batch release of BV-1 or BV-2 Vaste Gas Decay Tank via the BV-1/2 Process Vent.

Batch release of BV-1 or BV-2 Containment Purge via the BV-1/2 I Process Vent.

7-22 ISSUE 3

BV-.1 and 2 ODCM 2.1.3.1.1 BV-1/2 Mix Radionuclides The " mix" (noble gas radionuclides and composition) of the giseous effluent was determined as follows'

a. The gaseous source terms that are representative of the " mix" of the gaseous effluent were evaluated. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.

The gaseous source terms can be obtained from Tables 2.1-la. and 2.1-lb.

b. The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (S3 ) for each individual noble gas radionuclide in the gaseous effluent was calculated by:

A S.

l "

i [2.1-9]

I A.

1 i

where:

A g - The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from Table 2.1-la and 2.1.lb.

2.1.3.1.2 BV-1/2 Maximum Acceptable Release Rate (Vhole Body Exposure)

The maximum acceptable total release rate (uci/sec) of all noble gas radionuclides in the gaseous effluent (0,) based upon the whole body exposure limit was determined by:

O t

• 500 [2.1.10)

Iv i s 3 where:

Vg m The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrem / year /uci/sec) from Table 2.2-12.

2.1.3.1.3 BV-1/2 Maximum Acceptable Release Rate (Skin Exposure)

O was also determined based upon the skin exposure limit as follows:

t 0 "

3000 12.1-11]

I [L.(X/0)pv + 1.lB.js.

1 i 1 3

\

~

4 2-23 ISSUE 3

wt -

BV-1 and 2 ODCM where: .

) Lj - The skin dose factor due to beta emissions 3 ff

• noble gas radionuclide "i"(mrem / year /uCi/m ) from Table 2.2-11.

(X/0)P" = The highest calculated annual average relative concentration of effluents releases via the Process Vent for any area at or beyond the unrestricted area bour.dary f or all sectors (sec/m 3) from Table 2.2-6.

= 2.31E-5 sec/m (X/q)E" = The short term relative concentration of effluents released via the Process Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-38.

= 1.07E-5 sec/m 3 B

y

= The constant for long term releases (greater than 500 brs/ year) for noble gas radionuclide "i" accounting for the gamma radiation dose from the elevated finite plume (mrad / year /uCi/sec) from Table 2.2-12.

2.1.3.1.4 BV-1/2 Maximum Acceptable Release Rate (Individual Radionuclide)

The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (03 ) for each individual D~ noble gas radionuclide in the gaseous effluent was determined by:

01=S1 O t

I2'1~l2I (NOTE: Use the lower of the 0 values obtained in Section 2.1.3.1.2 and 2!1.3.1.3.)

2.1.3.1.5 BV-1/2 Maximum Acceptable Concentrations (Individual Radionuclide)

The maximum acceptable radioactivity concentration (uCi/cc) of noble gas radionuclide "i" in the gaseous effluent (C for each individral noblegasradionuclideinthegaseouseffluentha)sdeterminedby:

C g, 2.1263 O i [2.1-13]

F vhere:

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

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

= 1450 cfm (BV-1/2 Process Vent)

D 2-24 ISSUE 3

BV-1 and 2 ODCH 2.1.3.1.6 BV-1/2 Monitor Count Rate The calculated monitor count rate (ncpm) above background attributed to the noble gas radionuclide (C.R.) was determined by: ,

C.R. = I C E 3 3

[2.1-14) 1 where: )

i E3 = The detection efficiency of the monitor for noble gas radionuclide "1" (cpm /uci/cc) from Table 2.1-2a and 2.1-2b.

2.1.3.1.7 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background vere determined as follows:

a. The monitor HIGH-HIGH Alarm Setpoint above background (nepm) was determined by:

HHSP = 0.30 C.R. [2.1-15]

b. The monitor HIGH Alarm Setpoint above background (ncpm) was determined by:

HSP = 0.10 C.R. [2.1-16]

l I

i l

l 2-25 ISSUE 3

'!Di*fM s BV-1 and 2 ODCM 2.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release For Process Vent Releases (Elevated Releases)

I The following calculation method applies to gaseous releases via the BV-1/2 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 BV-1/2 Gaseous Vaste Gas Monitor (RM-GV-108B) or alternate (RM-GV-109 CH #5) during the following operational conditions:

• Continuous release via the BV-1/2 Process Vent.

Batch release of BV-1 or BV-2 Vaste Gas Decay Tank via the BV-1/2 Process Vent.

Batch release of BV-1 or BV-2 Containment Purge via the BV-1/2 Process Vent.

2.1.3.2.1 BV-1/2 Maximum Acceptable Release Rate Determine the maximum acceptable discharge flow rate for the release from the Process Vent for the analyzed mix.

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

I f _- 1.06 S [2.1-21]

I v. C.

1 1 where:

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

- (60 set / min x 3.53E-3 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 2.1.3. 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 neces;ary margin below the site dose rate limit.

V. = The constant for noble gas radionuclide "i" accounting for 2

the gamma radiation from the elevated plume (mrem / year /uci/sec) from Table 2.2-12.

C; = The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uCi/cc) as

}

determined by analysis of the gas to be released.

2-26 ISSUE 3

BV-1 and 2 ODCM

b. Based upon the skin exposure 1. i m i t , (f) is calculated by:

6.36 S [2.1-22]

• L lL1 (X/0)py + 1.1B3 i C g where:

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

= (60 sec/ min x 3.53E-5 ft3,cc)

L I = The skin dose factor due to beta emissions from noble gas radionuclide "1" (mrem / year /uCi/m ) from Table 2.2-11.

(X/0)PV = The highest calculated annual average relative concentration of effluents released via the Process Vent for any area at or beyond the unrestricted area 3

boundary for all sectors (sec/m ) from Table 2.2-6.

= 2.31E-6 sec/m (X/q)PV = 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 3

(sec/m ) from Table 2.3-38.

= 1.07E-5 sec/m' B. = The constant for long-term releases (greater than 1

500 hrs / year) for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad / year /uci/sec) from Table 2.2-12.

c. Select the smaller of the calculated f values based on the whole body exposure limit (Section 2.1.3.2.1.a) and based on the skin exposure limit (Section 2.1.3.2.1.b). The actual discharge flow rate (cfm) must be maintained at or below this f value.

2.1.3.2.2 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follovs:

a. The calculated monitor HIGH-HIGH Alarm Setpoint above background (nepm) attributed to the noble gas radionuclides is determined ,

by:

fIC E g g (2.1-23] !

I 1 HHSP = '

F 2-27 ISSUE 3 i

BV-1 and 2.0DCM vhere:

f - The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1.3.2.1.

F - The maximum actual or design effluent flow rate (cfm) at the point of release.

= 1450 cfm (BV-1/2 Process Vent -- design)

Cf . The undiluted radioactivity of noble gas radionuclide "i" in the gaseous source (uCi/cc) as : determined by analysis of the-gas to be released.

E g - The detection efficiency of the respective monitor (RM-GV-108B) or (RM-GV-109 CH 5) for noble gas radionuclide-

"i" (cpm /uCi/cc) from Table 2.1-2a and 2.1-2b. ,:

b. When a HIGH-HIGH Alarm Setpoint has been calculated according to- .

this section the monitor HIGH Alarm setpoint above background (nepm) is determined by:

HSP = HHSP x 0.33 (2.1-24]

'T 4

l E 2-28 ISSUE'3 m

a BV-1 and 2 ODCM TABLE 2.1-la BV-1 RADIONUCLIDE MIX FOR GASE0US EFFLUENTS (Ci/yr)**

TURBINE CONTAINMENT VENTILATION BUILDING VENT VENT _

VENT PROCESS VENT j Long Term j And AUXILIARY TURBINE MAIN CONTAINMENT GASE0US' CONTAINMENT BUILDING BUILDING CONDENSER / 1ACUUM .UASTE-NUCLIDE BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM l Short Term Long Term Long Term Long Term Long Term Short Term Kr-83m 2.2E-02 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0- i Kr-85m 1.5E-01 1.9E+00 1.7E-04 1.2E+00 3.9E-03 7.3E l Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.4E-02 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 i Kr-88 2.4E-01 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 ';

Kr-89 4.7E-04 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 '

Xe-131m 7.4E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 1.3E+00-Xe-133m 8.9E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.9E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 2.'3E+01 i' Xe-135m 4.5E-03 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 7.0E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0  :

Xe-137 1.0E-03 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0  :

Xe-138 1.5E-02 1.1E400 9.7E-05 6.6E-01 1.2E-04 0.0 Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0 .

i

)

I i

-i

• Containment can be purged via Ventilation Vent, Containment Vent, or Process Vent

, ** Reference (2.1.2)

• • • Reference (2.1.8) 2-29 ISSUE 3

_ . _ _ _ _ _ _ _ _ _ _ _ __ _ _ __ __ _ _ ____ _ _ _ _ _ _ __._ _ _ _ _ j

BV-1 and 2 ODCM TABLE 2.1-1b BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS I (Ci/yr)**

TURBINE VENTILATION CONTAINMENT BUILDING l VENT VENT VENT PROCESS VENT Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE I BUILDING VENTILATION VENTII.ATION AIR EJECTOR PUMPS SYSTEM NUCLIDE

+ +++

Short Term Long Term Long Term Long Term Long Term Short Term ,

'I Kr-83m 4.0E-05 4.2E-01 3.9E-05 2. 7 E-01. 3.7E-04 0.0  ;

Kr-85m 1.4E-02 1.9E+00 1.7E-04 1.2E+00 3.9E-03 1.2E-02 {

Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.3E-06 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 4.1E-03 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 Kr-89 0.0 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0-Xe-131m 7.2E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 8.3E-01 Xe-133m 7.6E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.4E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-135m 0.0 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 2.4E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 Xe-137 0.0 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0 Xe-138 0.0 1.1E+00 9.7E-05 6.6E-01 1.2E-04 0.0 Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0 l

l l

l l

l

• Containment can be purged via Ventilation Vent, Containment Vent, or Process Vent

• • Reference (2.2.3)

' *** Reference (2.2.5) 2-30 ISSUE 3 o

BV-1 and 2 ODCM TABLE 2.1-2a BV-1 MONITOR DETECTOR EFFICIENCIES (cpm /uCi/cc, CORRECTED)*

FROCESS CONTAINMENT VENTILATION VENT VENT NUCLIDE VENT ALTERNATE PRIMARY ALTERNATE FRIMARY ALTERNATE PRIMARY MONITOR MONITOR MONITOR MONITOR MONITOR MONITOR RM-VS-109 RM-GV-108B RM-GV-109 RM-VS-107B RM-VS-110 RM-VS-101B Channel 5 Channel 5 Channel 5 Kr-83m -- --

2.57 E7 Kr-85m 9.80 E7 2.39 E7 9.00 E7 2.43 E7 5.16 E7 2.47 E7 3.56 E5 2.51 E7 5.04 E7 2.67 E7 Kr-85 3.88 E5 2.95 E7 6.78 E7 3.00 E7 9.60 E7 3.19 E7 Kr-87 7.38 E7 2.28 E7 Kr-88 1.14 E8 2.11 E7 1.05 E8 2.14 E7 5.16 E7 I 2.93 E7 1.28 E8 2.98 E7 9.59 E7 3.16 E7 Kr-89 1.39 E8 3.29 E7 1.34 E8 3.05 E7 1.23 E8 3.10 E7 9.87 E7 Kr-90 1.56 E7 2.07 E6 1.59 E7 2.94 E7 1.68 E7 ,J Xe-131m 2.25 E6 1.26 E7 1.94 E7 1.16 E7 1.97 E7 4.17 E7 2.09 E7^~ "

Xe-133m 1.33 E7 1.01 E7 1.24 E7 9.24 E6 1.26 E7 2.28 E7 Xe-133 6.15 E6-Xe-135m 7.15 E7 5.70 E6 6.58 E7 5.80 E6 1.51 E7 1.12 E8 2.91 E7 1.03 EB 2.96 E7 6.42 E7 3.14 E7 Xe-135 3.19 E7 Xe-137 3.16 E7 2.96 E7 2.91 E7 3.01 E7 1.05 E8 2.66 E7 1.06 E8 2.70 E7 7.35 E7 2.87 E7 Xe-138 1.15 E8 7.17 E7 3.00 E7 6.59 E7 3.05 E7 7.19 E7 3.23 E7 Ar-41 s h.1 1

• The listed detector efficiencies for the respective primary monitors (Victoreen) are corrected for the reduced pressures observed and documented during.

operation. Also listed are the alternate monitors (Eberline SPING Channel 5) efficiencies corrected for detector unique installation factors. (Pressure corrections are not required for the SPING Monitors.) See Reference (2.1.4) for additional information.

2-31 ISSUE 3

BV-1 and 2 ODCM TABLE'2.1-2b.  ;

i BV-2 MONITOR DETECTOR EFFICIENCIES  ;

(cpm /uC1/cc)* i

) t i

t VASTE GAS CONDENSATE STORAGE DECON . POLISHING VENTILATION CONTAINMENT VAULT BUILDING BUILDING  ;

NUCLIDE VENT VENT VENT VENT VENT 2HVS-RQ101B 2HVS-R0109B 2RM0-R0303B 2RMO-R0301B 2HVL-R0112B Kr-83m -- -- -- - -- e Kr-85m 3.20E7 5.83E7 3.20E7 3.20E7 3.20E7.

Kr-85 3.60E7 7.19E7 3.60E7 3.60E7 3.60E7 Kr-87 3.73E7 8.85E7 3.73E7 3.73E7 3.73E7  ;

Kr-88 3.05E7 6.80E7 3.05E7 '3.05E7 3.05E7 [

Kr-89 3.72E7 8.73E7 3.72E7 3.72E7 -3.72E7 ,

Kr-90 3.86E7 8.80E7 3.86E7 3.86E7 3.86E7 [

Xe-131m 2.44E7 4.61E4 2.44E7 2.44E7 2.44E7 Xe-133m 2.86E7 6.06E4 2.86E7 2.86E7 2.86E7 ,

Xe-133 1.80E7 2.94E7 1.80E7 1.80E7 1.80E7 Xe-135m 7.22E6 1.55E4 7.22E6 7.22E6 -7.22E6  !

Xe-135 3.86E7 7.48E7 3.86E7 3.86E7 3.86E7 l Xe-137 3.78E7 9.07E7 3.78E7. .3.78E7 3.78E7 l Xe-138 3.52E7 7 74E7 3.52E7 3.52E7 3.52E7 Ar-41 3.79E7 7.90E7 3.79E7 3.79E7 3.79E7 ,

i

?

.I l

i

'l l

l 1

i j

l

, i

\

• Reference (2.2.1) 2-32 ISSUE 3 1

J

BV-1 and 2 ODCM I REFERENCES BV-1 GASEOUS EFFLUENT MONITOR SETPOINTS 1

2.1.1 " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and j 50-412"; Table 2.1.3

- 2.1.2 " Beaver Valley Power Station, Unit 2 FSAR"; Table 11.3-1.  !

2.1.3 "Duquesne Light Co., Beaver Valley Nuclear Plant, Specification No. BVPS '

414, Table V Nuclide Data, 3/30/74"; Table 1 and Figure 1, Table 3, and Figure 2  ;

2.1.4 Unit 1 Gaseous Effluent Monitor Efficiency Data; DLCo Calculation Package  !,

No. ERS-$FL-85-031 2.1.5 Unit 1/ Unit 2 ODCM Gaseous Alarm Setpoint Determinations; DLCo ,

Calculation Package No. ERS-HHM-87-014  ;

2.1.6 BVPS-1 and BVPS-2 ODCM T Factor Justification; DLCo Calculation Package No. ERS-ATL-87-026 2.1.7 Letter ND15HP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, 4 Appendix B t r

2.1.8 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster 3 Calculation No. UR(B)-262 I

w i

REFERENCES BV-2 GASEOUS EFFLUENT MONITOR SETPOINTS 2.2.1 Unit 2 DRMS Isotopic Efficiencies; DLCo Calculation Package No. j i

ERS-SFL-86-026 s

2.2.2 Unit 1/ Unit 2 ODCM Gaseous Alarm Setpoint Determinations; DLCo l l Calculation Package No. ERS-HHM-87-014 5

2.2.3 " Beaver Valley Power Station, Unit 2 FSAR"; Table 11.3-2 3

2.2.4 BVPS-1 and BVPS-2 ODCH T Factor Justification; DLCo Calculation Package  !

No. ERS-ATL-87-026 2.2.5 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster _

l i

Calculation No. UR(B)-262- t 1

2-33 ISSUE 3 l

- - - ~ ~ ~ , . , . . , _ , e

BV-1 and ' oprM 2.2 Compliance Vith 10 CFR 20 Dose Rate Limits (ODCM Appendix C CONTROL l 2.11.2.1) 2.2.1 Dose Rate Due To Noble Gases I The dose rate in unr es t r ic ted areas resulting from noble gas effluents from the site is limited to 500 miem/yr to the total body and 3,000 mrem /yr to the skin. Site gascons effluents are the total of BV-1 and AV-2 specific ground roleascn and a shared elevated telease, the BV-1/2 Process Vent. Based upon NUREG 0133 the following basic expressions ale used to show compliance .ith ODCM Appendix C CONTROL 3.11.2.1.a.

I l V.0.

. 2 1s

+ 6 i(X/0)- O.

iv I < 500 nrem//r 12.2-1]

1

___ 1 2

g

(( L. (X/0)s 1.1B.]

I + i 0 is +

[L.1 1.1M.](X/0)s i O.av < 3000 mrem /yr

[2.2-2]

vhere:

K = The total body dose factor due to gamma emissions for each g

3 identified noble gas radionuclide "i", mrem / year /uci/m l

L =

The skin dose factor due to beta emissions for each identified noble gas radionuclide "i", mrem / year /uci/m .

M = The air dose factor due to gamma emissions for each 3

identified noble gas radionuclide "i", mrad / year /uci/m .

V. = The constant for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite pluee, mrem / year /uCi/sec.

B. = The constant for long-term releases (greater than 500 hrs /

1 year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad / year /uCi/ set.

1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mren/ mrad.

O. = The release rate of noble gas radionuclide "i" in gaseous is effluents from free-standing stack, uCi/sec.

0;, '

=

The release rate of noble gas radionuclide "i" in gaseous effluents from all vent releases, uCi/sec.

( X / 0" ) ,. = The highest calculated annual au rage relative concentration for any area at or heyond zthe unrestricted area boundary for l elevated releasce, (sec/m~).

2-34 ISSUE 3

BV-1 and 2 ODCM (X/0)y = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for ground level releases (sec/m3). l 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 BV-i Cooling Tower

4. The Turbine Building Vents

5. The BV-2 Condensate Polishing Building Vent

6. The BV-2 Decontamination Building Vent

7. The BV-2 Vaste Gas Storage Vault Vent Effluent from the Containment Vents are assumed ground level in nature.

At BV-1 the source of these releases is the Supplementary Leak Collection and Release System (SLCRS). At BV-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. At BV-1 the sources of these releases are Containment Purges and normal Auxiliary Building Ventilation. At BV-2 the sources of these releases are Containtrent 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 Vaste Gas Decay Tanks and Containment Vacuum Purr p s .

Neble gas releases may normally occut from release points 1 through 3 above. To show compliance vith the site limits of ODCM Appendix C CONTROL 3.ll.2.1.a, Expressions (2.2-1l and [2.2-2) are nov 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.

For The Total Body Dose Rate:

IV0i i

+ I.K.

1 1 [(X/0)cv O. g I

+

(X/0)vv 9. yyy t

+

(X/0)tv 0 i g + (X/0)cv 3 py I

O cv2

+

(X/0)" O*.

.v2

+ (X/0)tv O. tv2 + (X/0)CP 0 I g ')

i

+

(X/0)d# 0.'dv2

+

( X70 ).,,y 0 3 ) f 500 mrem /yr [2.2-3]

vv2 4

2-35 ISSUE 3

BV-1 and 2 ODCM For The Skin Dose Rate:

h I [L (X/0)py 3

+

1.1B3] 03

+I 3 [L3 + 1.lMil l(X/0) ,,03 + (X/0),y, i pv tv1 0 + + O. + +

i vvl (X/0)tv 0 i tv1 (X/0)"' O. cv2 1

+

( X /0 )'

'ev2 (X/0)tv O. tv2 I

(X/0) " 0I dv2 + (X/0)"" 9 'vv2 l < 3000 mrem /yr

+

(X/0)'E 0 i cp2 (2.2 4) where:

0 3

= Release rate of radionuc]ide "i" from the BV-1/2 Process pv Vent, UCi/sec.

t 0

3

= Release rate of radionuclide "i" from the BV-1 Containment cvl Vent, uCi/sec.

0 3

= Release rate of radionuclide "i" from the BV-2 Containment ev2 Vent, uCi/sec.

O *. = Release rate of radionuclide "i" from the BV-1 Ventilation vvl Vent, uCi/sec.

O *. = Release rate of radionuclide "i" from the BV-2 Ventilation vv2 Vent, uCi/sec.

h 0 3

= Release rate of radionuclide "i" from the BV-1 Turbine tvl Building Vent, uCi/sec.

0 3

- Release rate of radionuclide "i" from the BV-2 Turbine tv2 Building Vent, uCi/sec.

Og = Release rate of radionuclide "i" from the BV-2 Condensate ep2 Polishing Building Vent, uCi/sec.

Q *. = Release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent. uCi/sec.

O *.

= Release rate of radionuclide "i" from the BV-2 Vaste Gas vv2 Storage Vault Vent, uCi/sec.

(X/0)P" = Highest calculated annual average relative concentration for releases from the Process Vent. sec/m .

(X/0),y '

= Highest calculated annual average relative concentration for 3

releases from the Containment Vent, sec/m (X/0)yy = Highest calculated annual average relative c ncentration for 3

releases from the Ventilation Vent, sec/m

( X / 0 ) t ,',

= Highest calculated annual average relative ncentration for 3

releases for the Turbine Building Vent, set /m 1

2-36 ISSUE 3 I

BV-1 and 2 ODCM

( FO)cp = Highest calculated annual average relative concentration r releases for & BiL2 Conhnsate PolisMng BuMng 3

at, sec/m

= Highest calculated annual average telative concentration for (57 )dv releases for the BV-2 Decontamination Building Vent, sec/m .

3 (57 )yy = Highest calculated annual average relative concentration 3 I' releases for the BV-2 Vaste Gas Storage Vault Vent, sec/m .

l Note that the release rate for a containment purge is based on an I l averaged release rate in uCi/see for the entire purge (not to exceed l 960 min in accordance with ODCM Appendix C CONTROL 3.11.2.1).

All other terms remain the same as those defined previously.

For the site, 4 potential modes of release are possible. The release i modes identify the various combinations of sources of radioactivity and i 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 ODCM Appendix C CD'N l 3.11.2.1.a is 0.35 miles IN. Inserting the appropriate X/0's from l Tables 2.2-4 through 2.2-10 for this location, Expressions {2.2 l

[2.2 4] become:

For The Total Body Dose Rate:

IVGg3 +

IK [9.24E-5 O g g

+

1.03E 4 0; + 7.35E-5 0 3 + 9.24E-5 i pv i cv1 vv1 tv1 0

I

+ 1.03E-4 0 I + 7.35E-5 0*.

4 9.24E-5 0 I + 9.24E-5 0 I +

cv2 vv2 t '. 2 ds2 vv2 7.35E-5 0 ) $ 500 mrem /yr [2.2-5]

For The Skin Dose Rate:

E [L3 + 1.1M3 ] [9.24E-5 O g cvl + 1.03E-4

+

I [7.0E-10 L3 + 1.1B3 ] 03 pv i i 0 + 7.35E-3 0 + 9.24E-5 Q'. + 1.03E 4 0 + 7.35E-5 0. +

I vyl I tv1 cv2 I

'n 'tv2 9.24E-5 0 + 9.24E-5 0 + 7.35E-5 0 l 3 3000 nrem/yr for the release Mode 4, the controlling location is 0.75 miles M.

Inserting the appropriate X/O's from Tables 2.2 4 through 2.2-10 for this location, Expressions [2.2-3 and 2.2-4] become:

2-37 ISSUE 3

BV-1 and 2 opcM For The Total Body Dose Rate:

E V.O. +

EK. 13.95E-6 0. + 4.99E 6 0. < 4.26E-6 0.1 + 3.05E-6

-D .

1 I 1 pv 1

. I 1 cv1 1 - c1 tv1 Q.

+ 4.99E-6 0. 4 4.26E-6 0. + 1. % E #,

O *.

3.95E-6 0 +

cv2 l

tv2 *tv2 de2 vv2 4.26E-6 0 } $ 500 nrem/yr [2.2 7]

For The Skin Dose Rate:

I [ 2. 31E-6 L. +

1.1B.J1 0.

2

+

I lL. l 4

1.lM.J i {3.95E-6 0. + 4.99E-6 i evl l

pv i 0 *.

4 3.95E-6 0.# + 4 E-6 0 1 + 4.26E-6 0 4 4.26E-6 0'. +

vv1 cv2 "v2 'tv2 tvl 3.95E-6 0 5 4 3.95E-6 0, 4 4.25E-6 0'.

j < 3000 mrem /vt

~

~

dv vs cp 12.2-8]

The determination of controlling location for implementation of ODCM Appendix C CONTROL 3.11.2.1.a for noble gases is a function of the following parameters:

1. Radionuclide mix and their isotopic release rate

2. Release mode I 3. Meteorology The incorporation of those 3 parameters into Expr essions [ 2.2-3] and

[2.2-4] resulted in the expressions for the controlling locations as presented in Expressions [2.2-5 through 2.2-8].

The radionuclide mix used to determine controlling locations was based on source terms calculated with the Stone and Webster Engineering Corporation computer code GASIBB which in timilar to the NRC GALE code.

Inputs were based on operating modes of the recpective plants. The code inputs utilized are presented in Appendix B. The source term is presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point.

The X/0 values utilized in the equatians for implementation of ODCM Appendix C CONTROL 3.11.2.1.a are based upon the maximum long-term annual average X/0 in the unrestricted area. Table 2.2-3 presents the distances from the release points to the nearest unrestricted area for each of the 16 sectors as well as to the nearest vegetable garden, cow, goat, and beef animal Tables 2.2-4 through 2.2-10 present the long-term annual average (X/0) values for the Process Vent. Containment Vent. Ventilation Vent, Turbine Building Vent, and if applicable for BV-2, Decontamination Building Vent, Vaste Gas Storage Vault Vent, and the condensate Polishing Building Vent release points to the special locations presented in Table 2.2-3. A description of their dcrication is provided in Appendix A.

2-3R ISSUE 3 J

BV-1 and 2 ODCM For release modes 1, 2, and 3, dose calculations vere performed using the highest calculated site boundary X/0 values applicable to the release points involved and the projected radionuclide mix applicable to the release source. In that a simultaneous, continuous elevated release could contribute to the dose at a given location, the selection of the two highest sector X/0 values at the site boundary considered this 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 NV. In Mode 1, the dominant release is the Auxiliary Building Ventilation (BV-1 Ventilation Vent and BV-2 Containment Vent). In Modes 2 and 3, the dominant release is a Containment Purge from the respective Ventilation Vent or Containment Vent.

l For release Mode 4, a similar evaluation was performed. Long-term annual average X/0 values were calculated at the mid-point of the 10 standard distances listed in Table 2.2-4 through 2.2-10. In that a simultaneous, ground level release could contribute to the dose at a given location, the selection of the two highest X/0 values at the controlling distance considered this contribution. Since the two maximum X/O 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 a Containment Purge via the Process Vent. Neither of the controlling receptor locations are presently inhabited.

I Values for K., L , and M., which were used in the determination of the controllingEecehtorlocalionandwhicharetobeusedin Expressions [2.2-5] through [2.2-8] to show compliance with ODCM Appendix C CONTROL 3.11.2.1.2, are presented in Table 2.2-11. Values taken from Table B-1 of NRC Regulatory Guide 1 109, Revision-y , l vere multiplied by 1E6 to convert picoeuries ~7 to microcuries for use in Table 2.2-11.

Values for V and B. for the finite plume model can be expressed as shown in Equition [232-9) and [2.2-10]. Values were calculated using the NRC code RABFIN at the site boundary location which vould receive the highest total dose from combined Process Vent. Ventilation Vent, and Turbine Building Vent, and Containment Vent releases. These values are presented in Table 2.2-12 and calculated from the following relation:

jk Ay ; u, E1 I

I

[2.2-9]

B"K~djk1 1 r u.

3 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 vind 3 direction.

l 2-39 ISSUE 3 i

s i

1

. _ _ _ _ _ _ _ _ - . .. . . I

BV-1 and 2 ODCM K = A numerical constant representing unit conversions.

l = (260 mrad)(radians) (m3) (transformation) 16 sectors (sec)(Mev)(Ci) 2n radi E 3

L J 1E-6 Ci 3.15E7 secl 5 IIJ

= 2.1E4 mrad (m ) s - ransformation)/yr(Mev)(uci).

r d

= The distance from the release point to the receptor location, meters.

u) = The mean vind speed assigned to the "j" th vind speed class, meters /sec.

f.k3

= The joint frequency of occurrence of the "j" th vind speed class and kth stability class (dimensionless).

A)g = The number of ph - <v of energy corresponding to the "1" th energy grou; a per transformation of the "i" th radionuclide, .twnber/ t rans f orma t ion.

E y = The energy assigned to the "1" th energy group, Mev.

u = The energy bsorption coefficient in air for photon energy H y , meters The V. factor is computed with conversion f rom air dose to tissue d ?pth dose,*thus:

• I'I Y III jk li A "a EyI e ~"T T d (2.2-10]

i r djk1 u.

3 where:

u T

= The tissue energy, absorption coefficient for photons of energy E y, em"/gm.

T d

= The tissue ,, density thickness taken to represent the total body dose (5gm/cm').

1.1 = The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrea/ mrad.

k 2 40 ISSUE 3

BV-1 and 2 ODCM 2.2.2 Dose Rate Due To Radiciodines And Particulater The dose rate in unrestricted areas resulting from the of inhalation of I-131, tritium, and all radionuclides in particulate form (excluding C-14) with half lives greater than 8 da fr relered in gaseous effluents f rom the site shall be limited to 1,500 n'ren/ cr to any organ. Based upon NUREG-0133, the following basic expression is used to show compliance with ODCM Appendix C CONTROL 3.11.2.1.b:

EP g [(X/0)g O gg + (X/0)y O gy J $ 1,500 mren/yr [2.2-11]

1 where:

P h = Dose parameter for any organ T f or each identified radionuclide "i", mrem /yr per uC1/m3 0

4s

= The release rate of radionuclide "i", in gaseous effluents from elevated releases, uCi/sec.

0 I" = The release rate of radionuclide "i", in gaseous effluents trom ground level releases, uCi/sec.

(X/0) = The highest calculated annual average relative concentration at3the unrestricted area boundary for dlevated releases, sec/m (T/U)y = The highest calculated annual average relative concentration at the level releases, sec/m", unrestricted area boundary for ground NOTE: The dispersion parameters specified in Section 2.2.2 are limited to the site boundary as defined above.

Releases may occur from any of the site vents in the release modes listed in Table 2.2-1. To show compliance vith ODCM Appendix C CONTROL 3.11.2.1.b, Expression [2.2-11) is now expressed in terms of the actual release points for the site.

IP g7 [(X/0)py Og +

(X/0)cy O g +

(X/0)yy O g +

vvl + (X/0)tv O tv1 g

1 pv cv1

+ (X/0)cp 9.

+ +

(X/0)cv 0. g I (X/0)vv O. gI (X/0)ts 9. g i i + (X/0)dv Og + (X/0)yy 0 1 } $ 1500 mrem /yr l2.2-12]

where:

(X/0)P" = Highest calculated annual average relative 3concentration for releases from the Process Vent, sec/m

( FO) y = Highest calculated annual average relative toncentration for 3

releases from the Containment Vents, sec/m 2-41 ISSUE 3

BV-1 and 2 ODCM

( UI))., = Highest calculated annual average relative concentration for releases from the Ventilation Vents, sec/m 3

~

= Highest calculated annual avetage relative (XI0)t~

concentration,for releases for t h r> Tuthine Building Vents, sec/m"

= Highest calculated annual acetage relative concentration (X/0)'E for releases for the BV-2 Condensate Polishing Building 3

Vent, sec/m

= Highest calculated annual average relative concentration (X/0)dv for releases for- & BV-2 Decontamination BuilM ng 3

Vent, sec/m (X/0),,y = Highest calculated annual average relative concentration for release fr m the BV-2 Vaste Gas Storage Vault 3

Vent, sec/m Og = Long-term release rate of radionuclide "i" from the BV-1/2 pv Process Vent, uCi/sec.

0 = Long-term release rate of radionuclide "i" from the BV-1 1

cvl Containment Vent, uCi/sec.

= Long-term release rate of radionuclide "i" from the BV-2 O *. Containment Vent, uCi/sec.

cv2 Og = Long-term release rate of.radionuclide "i" from the BV-1 i

el Ventilation Vent, uCi/sec.

= Long-term release rate of radionuclide "i" from the BV-2 O '. Ventilation Vent, uci/sec.

vv2

= Long-term release rate of radionuclide "i" from the BV-1 O *.

tv1 Turbine Building Vent, uCi/sec.

O. = Long-term release rate of radionuclide "i" from the BV-2 tv2 Turbine Building Vent. uCi/sec.

0; = Long-term release rate of radionuclide "i" from the BV-2 cp2 Condensate Polishing Building Vent, uCi/sec.

0 = Long-term release rate of radionuclide "i" from the BV-2 3

dv2 Decontamination Building Vent, uri/vec.

= Long-term release rate of radionuclide "i" from the BV-2 Q *.

vv2 Vaste Gas Storage Vault Vent, uCi/wr.

All other terms are the same as those detined previoush 2~42 1SSUE 1

BV-1 and 2 ODCM The Turbine Building Vent, Condensate Polishing Building Vent, Decontamination Building Vent,. and Vaste Gas Storage Vault Vent are not normal radioactive release points. These release points are included only for use if radioactive teleases via these vents are identified in the future. In the calculation to show compliance with ODCM Appendix C CONTROL 3.11.2.1.b only the inhalation pathway is considered.

Values of the organ dose parameters, P. were calculated using methodology given in NUREG-0133. For the*T,hild c age group, the following equation was used for all nuclides. The P.*T, values ate presented in Table 2.2-13.

P g7 - 3.7E9 DFA y [2.2-13]

vhere:

1 3.7E9 = Breathing rate of child (3,700 a by r) y unit conversion factor (1E6 pC1/uCi).

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 NV.

Expression [2.2-12l becomes:

EP g [7.00E-10 0; + 9.24E-5 0 3 + 1.03E-4 0; + 7.35E-5 0 3 +

1 pv cv1 vv1 tv1 9.24E-5 9*. + 1.03E 4 0 I + 7.35E-3 0 I + 7.35E-3 0*. + 9.24E-5 cv2 vv2 M @

Oy + 9.24E-5 O g $ 1500 mre yr [2.2-14]

The determination of the controlling location for implementation of ODCM Appendix C CONTROL 3.11.2.1.b for radiciodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Expression [2.2-12] results in the respective equations for each release mode at the site boundary controlling locations. The radionuclide mix was again based upon the source terms presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point.

In the determination of the controlling site boundary for each release mode, the highest 2 site boundary X/O values for each release point vere utilized in conjunction with the radionuclide mix and the release rate for each release point to dete:mine the controlling location.

The P; values are presented Table 2.2-13.

4 2 43 ISSUE 3

BV-1 and 2 ODCM j The X/0 values in Expression (2.2-14) wer e obtained from Tables 2.2-4 through 2.2-10.

A description of the derivation of the X/0 calues is provided in

]

Appendix A. '

I l

2-44 ISSUE 3 i

BV-1 and 2 ODCM TABLE 2.2-1 MODES OP GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATIOfJ OF 10 CFR 20 At!D 10 CFR 50 RELEASE POINT MODE 1 MODE 2 MODE 3 MODE 4 BVPS BVPS-2 Main Cond. Air Same As Same As Same As Pr ocess Vent (pv) Ejector, Veste Mode 1 Mode 1 Mode 1 And Gas, Contain- Containment ment Vacuum Purge BVPS-1 Ventilation Aux. Bldg. Contagnment Same As Same As Vent (vv1) Ventilation Purge Mode 1 Mode 1 BVPS-1 Containment Leakage Same As Same As Same As Vent (cvl) Collection Mode 1 Mode 1 And Mode 1 Exhaust Contajnment Purge BVPS-1 Turbine Bldg. Turbine Bldg. Same As Same As Same As Vent (tv1) Exhaust

• Mode 1* Mode 1* Mode 1*

BVPS-2 Ventilation Contiguous Conta(nment Same As Same As Vent (vv2) Areas Purge' Mode 1 Mode 1 BVPS-2 Containment Aux. Bldg. Same As Same As Same As Vent (cv2) Ventilation Mode 1 Mode 1 And Mode 1 Contajnment Purge BVPS-2 Turbine Bldg. Torbing Bldg. Same As Same As Same As Vent (tv2) Exhaust

• Mode 1* Mode 1* Mode 1*

BVPS-2 Condensate * * *

• Polishing Bldg. Vent (cp2) 1

• BVPS-2 Decontamination * *

• Bldg. Vent (dv2)

BVPS-2 Vaste Gas I * * *

• Storage Vault Vent (vv2)

• 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.

1 Continuous ground level meteorology is applicable 2

Continuous elevated meteorology is applicable 3

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

. l 2 45 ISSUE 3

4 BV-1 and 2 ODCM TABLE 2.2-2a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS k (Ci/yr)**

TURBINE CONTAINMENT VENTILATION BUILDING VENT VENT VENT FROCESS VENT Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE NUCLIDE BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM Short Term Long Term Long Term Inng Tetm Long Term Short Term Kr-83m 2.2E-02 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-85m 1.5E-01 1.9E+00 1.7E-04 1.2E+00 3.9E-03 1.2E-02 Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E 00 7.2E-01 2.3E+02 Kr-87 5.4E-02 1.3E400 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 2.4E-01 3.8E+00 3.5E-04 2.4E400 5.0E-03 0.0 Kr-89 4.7E-04 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 Xe-131m 7.4E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 8.3E-01 Xe-133m 8.9E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.9E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-135m 4.5E-03 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 7.0E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 Xe-137 1.0E-03 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0 Xe-138 1.5E-02 1.1E+00 9.7E-05 6.6E-01 1.2E-04 0.0 I-131 1.2E-03 4.6E-02 6.5E-04 2.1E-02 4.7E-04 0.0 I-132 0.0 0.0 0.0 0.0 2.5E-06 0.0 1-133 2.0E-04 6.7E-02 8.7E-04 1.nE-02 8.4E-05 0.0 I-134 0.0 0.0 0.0 0.0 4.7E-07 0.0 I-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co-58 7.5E-04 6.0E-02 0.0 0.0 1.6E-05 0.0 Co-60 3.4E-04 2.7E-02 0.0 0.0 7.4E-06 0.0 Mn-54 2.2E-04 1.8E-02 0.0 0.0 4.9E-06 0.0 Fe-59 7.5E-05 6.0E-03 0.0 n.0 1.6E-06 0.0 Sr-89 1.7E-05 1.3E-03 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-06 2.0E-04 0.0 0.0 6.6E-08 0.0 Cs-134 2.2E-04 1.8E-02 0.0 0.0 4.9E-06 0.0 Cs-137 3.8E-04 3.0E-02 0.0 0.0 8.4E-06 0.0 C-14 1.0E+00 0.0 0.0 0.0 0.0 7.OE.00 Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0

• Containment can be purged via Ventilation Vent, Containment Vent, or Process "ent

+* Reference 2.1.2

• • • See Section 2.1.1.1 6

2 46 ISSUE 3

BV-1 and 2 ODCM TABLE 2.2-2b BV-2 RADInNUCLIDE MIX FOR CASFOUS EFFLUENTS (C1/yr)**

l TURBINE VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS VENT Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING COWDENSER/ VACUUM VASTE NUCLIDE BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM Short Term Long Term Long Term Long Term Long Term Short Termj Kr-83m 4.0E-05 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0  !

Kr-85m 1.4E-02 1.9E+00 1.7E-04 1.2E+00 3.9E-03 Kr-85 1.2E-02l 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 I Kr-87 5.3E-06 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-88 4.1E-03 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 l Kr-89 0.0 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 i Xe-131m 7.2E-01 1.3E-01 1.2E-05 8.0E -02 1.3E-02 8.3E-01 Xe-133m 7.6E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 i Xe-133 8.4E+01 3.6E+01 3.4E-03 2.3E401 1.9E-00 8.2E+00 1

! Xe-135m 0.0 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 2.4E-01 4.5E+00 4.2E 04 2.8E+n0 1.9E-02 0.0 Xe-137 0.0 2.1E-01 2.1E-05 1.3E 01 6.3E-06 0.0 Xe-138 0.0 1.1E400 9.7E-05 6.6E-01 1.2E-04 0.0 1-131 2.7E-05 4.6E-03 6.5E-04 2.1E-02 4.7E-04 0.0  !

I-132 0.0 0.0 0.0 n.0 2.5E-06 0.0 I-133 2.6E-06 6.7E-03 8.7E-04 3.0E-02 8.4E-05 0.0 I-134 0.0 0.0 0.0 0.0 4.7E-07 0.0 I-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co-58 7.5E-02 6.0E-04 0.0 0.0 1.6E-05 0.0 l Co-60 3.4E-02 2.7E-04 0.0 0.0 7.4E-06 0.0 Mn-54 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 0.0 i Fe-59 7.5E-03 6.0E-05 0.0 0.0 1.6E-06 0.0 l Sr-89 1.7E-03 1.3E-05 0.0 n.0 3.7E-07 0.0 Sr-90 3.0E-04 2.0E-06 0.0 0.0 6.6E-08 0.0 Cs-134 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 0.0 Cs-137 3.8E-02 3.0E-04 0.0 0.0 8.4E-06 0.0 C-14 1.0E+00 0.0 0.0 0.0 0.0 7.0E+00 Ar-41 2.5E+01 0.0 0.0 n.0 0.0 0.0

• Containment can be purged via Ventilation Vent, Containment Vent, or Process Ve:

• • Reference 2.2.3

• • • See Section 2.1.2.1 2 47 ISSUE 3

W W W BV-1 and 2 ODCM TABLE 2.2-3 l

DISTRJCES OF LIMITING MAXIMUM INDIVIDUAL RECEPIORS 'ID RELEASE POINTS FOR ANNUAL X/Q VALUES

• i (meters) l VEGETABLE MEAT DOWN- SITE BOUNDARY GARDEN ___

MILK COW MILK GOAT ANIMAL RESIDE 21T WIND SECIUR GROUND ELEV. GROUND ELEV. GROUND ELEV. GROUND ELEV. GROUND ELEV. GROUND ELEV.

(1) (2)

N 670 579 413 2,623 2,423 - -

4,651 4,418 4,152 3,919 2,527 2,295 NNE 535 792 632 2,704 2,461 - -

6,276 6,033 2,848 2,605 2,639 2,461 NE 490 442 327 724 901 7,741 7,526 20,760 20,545 7,741 7,526 708 79' ENE 490 448 394 1,674 1,658 - -

6,824 6,671 - -

708 1,502 E 545 546 551 1,979 1,922 7,065 6,998 4,265 4,200 4,265 4,200 756 1,922 ESE 575 607 672 1,577 1,619 - -

2,865 2,899 1,577 1,619 1,577 1,650 SE 575 701 815 1,835 1,961 5,729 5,848 5,729 5,848 3,299 3,420 1,835 1,961 SSE 655 762 912 1,738 1,933 5,053 5,244 9,977 10,166 1,770 1,964 1,432 1,628 5 850 887 1,054 3,138 3,372 3,347 3,539 - -

2,253 2,487 2,189 2,423 Ssw 975 1,064 1,226 2,317 2,560 3,347 3,590 5,616 5,859 2,317 2,560 1,223 1,466 SW 1,435 1,439 1,574 2,221 2,439 - -

2,993 3,210 2,414 2,632 2,221 2,439 WSW 595 561 660 2,301 2,463 5,182 5,341 - - 2,446 2,608 2,301 2,463 W 685 640 681 3,556 3,635 5,118 5,195 - -

4,088 4,166 3,556 3,635 WNW 810 701 676 3,605 3,590 4,538 4,521 22,529 22,507 3,605 3,590 3,605 3,590 NW 655 567 482 1,464 1,415 - - 10,944 10,832 4,570 4,461 1,432 1,383 NIM 645 558 420 1,464 1,285 - -

15,450 15,262 3,959 3,774 1,143 1,253 NOTE:

• Distances for ground releases are measured from the centerpoint between the BV-1 and BV-2 Containment Buildings. Distances for elevated release are measured from the BV-1 Cooling Tower. Elevated release is applicable to the Process Vent. Ground release is applicable to all other release points. Site boundary ground releases: (1) BV-2 Turbine Building and Condensate Polishing Building.

(2) All other ground release points.

2-48 ISSUE 3

BV-1 and 2 ODCM TABLE 2.2-4 BV-1 AND 2 COtRAINM m T VEtRS ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR COJTINUCUS GROUND LEVEL RELEASES, FOR SPECIAL DISTANCES (IDE?RIFIED IN TABLE 2.2-3), AND SELECTED COTIPOL LOCATIONS (1E-7 sec/m )

INDIVIDUAL RECEPIORS DISTANCES 'IO 'nlE CONTROL IDCATIO4, IN MILES DLMN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-

'IOR DARY GARDEN COW GOAT MAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 125.0 12.80 --

5.360 6.27 13.50 233.0 39.5 18.70 11.80 7.68 5.82 4.240 3.480 2.660 2.280 NNE 50.2 6.92 -

2.040 6.42 7.16 148.0 26.8 10.80 6.62 4.60 3.44 2.690 2.190 1.830 1.560 NE 102.0 47.40 1.200 0.265 1.20 49.10 120.0 21.6 11.60 6.99 4.81 3.55 2.370 1.910 1.450 1.230 ENE 85.8 12.50 -

0.124 - 42.20 103.0 18.4 9.55 5.70 4.14 3.04 2.340 1.880 1.260 1.060 E 54.5 6.16 0.807 1.910 1.91 32.60 89.5 15.7 6.08 3.65 2.49 1.83 1.300 1.040 0.859 0.726 ESE 31.1 6.92 --

3.010 6.92 6.92 59.1 10.5 5.16 3.10 1.95 1.43 1.020 0.815 0.612 0.517 SE 27.8 6.70 0.994 0.994 2.74 6.70 65.9 12.0 5.89 3.54 2.41 1.77 1.160 0.931 0.768 0.649 SSE 24.1 6.68 1.030 0.372 6.50 9.01 67.2 12.0 5.46 3.30 1.91 1.41 0.997 0.803 0.665 0.563 S 27.5 3.40 3.090 - 5.57 5.81 99.9 17.5 6.77 4.11 2.84 2.10 1.490 1.200 0.999 0.848 SSN 23.8 6.31 3.700 1.740 6.31 19.30 110.0 19.9 7.83 4.80 3.33 2.48 1.940 1.580 1.190 1.020 SW 22.3 13.90 -

9.050 12.30 13.90 150.0 29.2 16.10 9.94 5.85 4.37 3.430 2.790 2.110 1.800 WSW 163.0 19.30 5.720 - 17.70 19.30 283.0 49.8 23.50 14.60 10.30 7.72 5.690 4.650 3.620 3.090 W 278.0 15.70 9.540 - 13.00 15.70 615.0 103.0 49.00 31.00 15.40 11.70 9.320 7.660 160 5.550 WNW 487.0 40.70 30.100 1.810 40.70 40.70 1290.0 203.0 92.10 59.20 40.60 31.20 25.000 20.700 1. 200 12 700 NW 924.0 194.00 -

8.660 40.50 200.00 1710.0 262.0 J23.00 79.80 55.00 42.30 34.000 28.200 19.400 10.100 NNW 302.0 63.00 -

1.720 15.40 92.30 547.0 86.4 40.80 26.20 17.60 13.50 10.100 8.35" 6 G60 5.660 ISSUE 3 a -- -- - - - - - - m12 49 - - a

BV-1 and 2 ODCM TABLE 2.2-5 BV-1 AND 2 VCfrILATION VENTS NEUAL AVERAGE, GROUND LEVEL, XA) VALUES FOR CONTINIJOUS GROUND LEVEL RELEASES, FOR SPECIAL DISTNJCES (IDDJTIFIED IN TABLE 2.2-3), AND SELECIED CONTROL tiX'IsTIONS (1E-7 sec/m )

INDIVIDUAL RECEPTORS DISTNJCES 'IO 11IE CONTROL LOCATIOJ, IN MILES DOWN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-TOR DARY GARDDJ COW GOAT MitL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 152.0 15.00 --

5.980 7.06 15.90 276.0 49.9 22.70 13.70 8.75 6.52 4.69 3.810 2.900 2.470 NNE 62.3 7.66 --

2.150 7.08 7.95 189.0 32.0 12.20 7.31 4.99 3.69 2.87 2.320 1.920 1.630 NE 132.0 57.90 1.240 0.269 1.24 60.20 156.0 24.8 12.70 7.51 5.09 3.73 2.47 1.980 1.500 1.270 ENE 110.0 13.60 -

1.270 - 50.40 135.0 20.6 10..] 6.01 4.31 3.14 2.41 1.930 1.290 1.080 E 67.8 6.66 0.828 1.990 1.99 38.80 116.0 17.7 6.57 3.86 2.61 1.90 1.34 1.070 0.883 0.774 ESE 38.0 7.64 -

3.200 7.64 7.64 76.7 11.9 5.59 3.29 2.05 1.49 1.05 0.842 0.630 0.531 SE 33.3 7.27 1.030 1.030 2.88 7.27 86.2 13.5 6.37 3.75 2.53 1.84 1.20 0.960 0.790 0.666 SSE 29.1 7.41 1.080 0.382 7.19 10.10 87.0 13.7 5.98 3.53 2.02 1.48 1.04 0.833 0.688 0.531 S 32.8 3.65 3.300 -- 6.10 6.38 127.0 20.3 7.56 4.48 3.04 2.23 1.57 1.260 1.050 0.885 SSW 28.7 7.08 4.040 1.850 7.08 22.90 140.0 23.6 8.87 5.28 3.60 2.66 2.07 1.670 1.260 1.070 SW 26.2 15.70 -

9.980 13.80 15.70 204.0 34.8 18.40 11.40 6.38 4.71 3.66 2.960 2.230 1.900 WSW 201.0 22.40 6.230 - 20.40 22.40 347.0 61.3 27.70 16.60 11.40 8.49 6.19 5.020 3.880 3.300 W 345.0 18.00 10.600 - 14.70 18.00 715.0 132.0 60.30 36.50 17.70 13.20 10.40 8.440 7.060 6.040 WrM 598.0 48.60 35.000 1.920 48.60 48.60 1410.0 269.0 120.00 73.00 48.50 36.40 28.70 23.400 15.900 13.600 NN 1030.0 262.00 -

9.520 47.80 271.00 1820.0 350.0 164.00 100.00 66.60 50.10 39.50 32.300 21.900 18.800 NNW 345.0 83.40 -

1.840 18.10 121.00 601.0 114.0 52.80 32.20 21.00 15.00 11.60 9.460 7.360 6.310 2-50 ISSUE 3

2 l

BV-1 and 2 ODCM TABLE 2.2-6 l

BV-1 AND 2 PROCESS VER ANNUAL AVERAGE, ELEVATED RELEASE, X/Q VALUES FOR CONTINUOUS GROUND LEVEL RELEASES, EUR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CCNTROL LOCATIOiS (IE-7 sec/m i l

INDIVIDUAL RECEPIDRS DISTANCES TO THE CONTROL LOCATION, IN MILES DChU-WIND SITE

• VEGE- MEAT SEC- DOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-TUR DARY CARDEN COW CGT MAL DDJCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 0.0082 6.720 -- 1.910 2.27 6.790 0.0289 23.1000 8.2700 5.32 2.56 1.91 1.480 1.200 0.996 0.846 NNE 0.0280 6.690 - 1.430 6.14 6.890 0.0175 14.5000 6.9800 5.47 3.27 2.69 1.770 1.430 1.290 1.100 NE 0.0110 .074 1.610 0.350 1.61 0.055 0.0069 0.1160 .2300 7.10 5.38 3.68 2.880 2.090 1.880 1.570 ENE 0.0110 9.090 - 1.770 - 0.525 0.0135 0.3310 7.2800 6.02 4.75 3.22 2.620 2.030 1.710 1.100 E 0.0360 8.300 1.240 2.870 2.87 8.300 0.0124 17.1000 7.8600 6.20 3.67 2.83 2.190 1.730 1.280 1.200 ESE 0.0420 11.600 -- 4.570 11.60 11.200 0.0208 12.7000 8.1400 4.78 3.00 2.20 1.360 1.160 0.830 0.737 SE 0.0750 7.890 1.230 1.230 3.05 7.890 0.4770 7.4000 7.5700 4.45 2.79 2.05 1.460 1.180 0.811 0.686 SSE 0.2060 7.390 1.160 0.357 7.20 9.770 0.3030 9.4400 6.9300 4.06 2.58 1.89 1.170 0.937 0.646 0.546 S 5.740 3.760 3.490 - 6.06 6.310 0.7960 8.5100 8.4900 4.98 3.37 2.47 1.380 1.110 0.774 0.655 SSW 7.640 3.610 2.140 0.872 3.61 5.820 26.1000 9.1000 4.0300 3.11 2.11 1.56 1.030 0.834 0.807 0.684 SW 6.500 3.900 - 2.560 3.47 3.900 36.1000 15.9000 4.9300 3.12 1.77 1.57 1.201 1.060 1.150 0.977 Wsw 0.126 4.350 1.420 - 3.98 4.350 0.3870 17.8000 4.9000 3.53 2.36 1.64 1.460 1.210 0.920 0.781 W 0.029 2.490 0.764 - 2.02 2.490 0.0147 8.7200 6.2300 3.68 2.50 1.84 0.741 1.120 0.851 0.795 hi s 0.033 2.530 1.780 0.163 2.53 2.530 0.0202 0.0549 0.0809 3.07 2.50 1.84 1.110 0.686 0.791 0.731 IM 0.007 0.074 - 0.305 1.67 0.073 0.0084 0.0650 0.1170 3.66 2.30 1.69 1.210 0.903 0.804 0.683 NNW 0.008 6.460 - 0.224 1.81 6.590 0.0135 6.7800 5.0200 2.96 1.93 1.49 1.050 0.849 0.705 0.599

• Elevated release X/Q value at site boundary location where ground level telease X/Qs maximize.

. - . _ _ _ _ _ _ _ _ _ _ M __ b

EV-1 and 2 ODCM TABLE 2.2-7 BV-1 AND 2 'IURBINE BUILDING VDES N24UAL AVERAGE, GRCOND LEVEL, X fQ VALUES FOR COtRINUOUS GROUND LEVEL RELEASES, FDR SPECIAL DISTNJCES (IDDJTIFIED IN TABLE 2.2-3), AND SELECTED COtCROL LOCATIO4S (IE-7 sec/m )

INDIVIDUAL RECEPIDRS DISTN4CES 'IO 'IIIE COUROL LOCATION. IN MILES DCWN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5'

'IOR DARY GARDEN CCM GO?T MAL 0.5 1.0 1.5 2.0 DENCE  ?.5 3.0 3.5 4.0 1.5 5.0 N 105.0 14.00 5.740 6.74 14.80 244.0 42.6 20.50 12.70 8.18 6.15 4.45 3.640 2.770 2.380 triE 102.0 7.37 -

2.130 6.83 7.64 161.0 28.8 11.40 6.94 4.79 3.56 2.78 2.250 1.870 1.590 NE ENE 96.6 51.90 84.1 13.20 1.230 1.280 0.268 -1.23 53.80 132.0 23.0 12.10 7.24 4.95 3.64 2.42 1.950 1.480 1.250 46.30 115.0 19.4 9.89 5.85 4.23 3.09 2.38 1.900 1.270 1.070 E 60.7 6.49 .829 1.980 1.98 35.70 99.2 16.6 6.32 3.75 2.55 1.87 1.32 1.060 0.871 0. 735 ESE 37.1 7.25 -

3.100 7.25 7.25 65.8 11.1 5.36 3.19 2.00 1.46 1.03 0.829 0.621 0.524 SE 41.8 7.06 1.020 1.020 2.85 7.06 73.5 12.6 6.12 3.64 7.47 1.81 1.18 0.945 0.779 0.658 SSE 34.0 7.16 1.010 0.384 6.96 9.69 74.2 12.7 5.71 3.41 1.97 1.45 1.02 0.81C 0.676 0.572 S 32.7 3.64 3.310 -- 6.00 6.27 109.0 18.6 7.13 4.29 2.94 2.17 1.53 1.230 1.020 0.866 SSW 29.7 6.73 3.890 1.800 6.73 20.90 120.0 21.3 8.31 5.0: 3.46 2.57 2.00 1.620 1.230 1.040 SW 24.1 14.00 -

9.550 13.10 14.80 174.0 31.2 17.20 10.40 6.10 4.54 3.54 2.870 2.170 1.850 WSW 159.0 20.80 6.010 -- 19.10 20.80 301.0 53.6 25.30 15.60 10.80 8.09 5.93 1.830 3.760 3.200 W 264.0 16.90 10.100 - 13.90 16.90 636.0 111.0 53.90 33.50 16.50 12.40 9.82 8.040 6. 760 5.790 RM 404.0 44.50 32.500 1.870 44.50 44.50 1310.0 218.0 104.00 65.40 44.20 33.60 26.70 22.000 15.000 12.900 is 735.0 216.00 -

9.100 43.90 222.00 1720.0 279.0 140.00 88.80 60.30 45.90 36.60 30.lu0 20.600 17.700 tc M 247.0 71.00 -

1.820 17.00 99.40 557.0 924.0 45.90 29.90 19.20 14.60 10.80 8.880 6.950 5.980 2-52 ISSUE 3

BV-1 and 2 ODCM TABLE 2.2-8 FOR INFORMATIOJ ONLY - USED IN CALCULATICN OF BV-2 COJTRIBUTION 10 SITE DOSE RATE LIMITS I BV-2 DECONTAMINATION BUILDING VDJT MEJUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS GROUND LEVEL RELEASES, EUR SPECIAL DISTRiCES (IDDJTIFIED IN TABLE 2.2-3), M1D SELECTED CONTROL LOCATIOJS (lE-7 secfm )

INDIVIDUAL RECEPIORS DISTANCES 10111E CONTROL LOCATION, IN MILES DOhT4-WIND SITE VEGE- MEAT l SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-TOR DARY GARDDJ COi GOAT MAL DDJCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 125.00 12.80 --

5.360 6.27 13.50 233.0 39.50 18.70 11.80 7.68 5.82 4.240 3.480 2.660 2.280 NNE 50.20 6.92 -

2.040 6.42 7.16 148.0 26.80 10.80 6.62 4.60 3.44 2.690 2.190 1.830 1.560 NE 102.00 47.40 1.20 0.265 1.20 49.10 120.0 21.60 11.60 6.99 4.81 3.55 2.370 1.910 1.450 1.230 ENE 85.80 12.50 -

1.240 - 42.20 103.0 18.40 9.55 5.70 4.14 3.04 2.340 1.880 1.260 1.060 E 54.50 6.16 0.807 1.910 1.91 32.60 89.5 15.70 6.08 3.65 2.49 1.83 1.300 1.040 0.859 0.726 ESE 31.10 6.92 --

3.010 6.92 6.92 59.1 10.50 5.16 3.10 1.95 1.43 1.020 0.815 0.612 0.517 SE 27.80 6.70 0.994 0.994 2.74 6.70 65.9 12.00 5.89 3.54 2.41 1.77 1.160 0.931 0.768 0.649 SSE 24.10 6.68 1.030 0.372 6.50 9.01 67.2 12.00 5.46 3.30 1.91 1.41 0.997 0.803 0.665 0.563 S 27.50 3.40 3.090 -- 5.57 5.81 99.9 17.50 6.77 4.11 2.84 2.10 1.490 1.200 0.999 0.848 SSW 23.80 6.31 3.700 1.740 6.31 19.30 110.0 19.90 7.83 4.80 3.33 2.48 1.940 1.580 1.190 1.020 SW 22.30 13.90 -

9.050 12.30 13.90 160.0 29.20 16.10 9.94 5.85 1.37 3.430 2.790 2.110 1.800 WSW 163.00 19.30 5.720 - 17.70 19.30 283.0 49.80 23.50 14.60 10.30 7.72 5.690 4.650 3.620 3.090 W 278.00 15.70 9.540 - 13.00 15.70 615.00 103.00 49.00 31.00 15.40 11.70 9.320 7.660 6.160 5.550 WNW 487.00 40.70 30.100 1.810 40.70 40.70 1290.00 203.00 92.10 59.20 40.60 31.20 25.000 20.700 14.200 12.200 NW 924.00 194.00 -

8.660 40.50 200.00 1710.00 262.00 123.00 79.80 55.00 42.30 34.000 28.200 19.400 16.700 NNW 302.00 63.00 -

1.720 15.40 92.30 547.00 86.40 40.80 26.30 17.60 13.50 10.100 8.350 6.560 5.660 2-53 ISSUE 3 g

E E E BV-1 and 2 CDCM TABLE 2.2-9 FOR INFORMATION ONLY - USED IN CALCULATION OF BV-2 CONTRIBUTION 'IO SITE DOSE RATE LIMITS BV-2 WASTE CAS STORAGE VAULT VENT At2;UAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR COfrINUOUS GROUND LEVEI4 RELEASES, FOR SPECIAL DISTANCES (IDDITIFIED IN TABLE 2.2-3), AND SELECTED COrirROL IOCATIONS (lE-7 sec/m )

INDIVIDUAL RECEPIORS DISTANCES 10 'IllE CONTROL LOCATION, IN MILES D0cN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-TUR DARY GARDEN COW , GOAT MAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 N 125.00 12.80 -

5.360 6.27 13.50 233.0 39.50 18.70 11.80 7.68 5.82 4.240 3.480 2.660 2.280 NNE 50.20 6.92 -

2.040 6.42 7.16 148.0 26.80 10.80 6.62 4.60 3.44 2.690 2.190 1.830 1.560 NE 102.00 47.40 1.20 0.265 1.20 49.10 120.0 21.60 11.60 6.99 4.81 3.55 2.370 1.910 1.450 1.230 CJE 85.80 12.50 -

1.240 - 42.20 103.0 18.40 9.55 5.70 4.14 3.04 2.340 1.880 1.260 1.060 E 54.50 6.16 0.807 1.910 1.91 32.60 89.5 15.70 6.08 3.65 2.49 1.83 1.300 1.040 0.859 0.726 ESE 31.10 6.92 --

3.010 6.92 6.92 59.1 10.50 5.16 3.1; 1.95 1.43 1.020 0.815 0.612 0.517 SE 27.80 6.70 0.994 0.994 2.74 6.70 65.9 12.00 5.89 3.54 2.41 1.77 1.160 0.931 0.768 0.649 SSE 24.10 6.68 1.030 0.372 6.50 9.01 67.2 12.00 5.46 3.30 1.91 1.41 0.997 0.803 0.665 0.563 S 27.50 3.40 3.090 -- 5.57 5.81 99.9 17.50 6.77 4.11 2.84 2.10 1.490 1.200 0.999 0.848 SSW 23.80 6.31 3.700 1.740 6.31 19.30 110.0 19.90 7.83 4.80 3.33 2.48 1.940 1.580 1.190 1.020 SW 22.30 13.90 -

9.050 12.30 13.90 160.0 29.20 16.10 9.94 5.85 4.37 3.430 2.790 2.110 1.800 WSW 163.00 19.30 5.720 - 17.70 19.30 283.0 49.80 23.50 14.60 10.30 7.72 5.690 4.650 3.620 3.090 W 278.00 15.70 9.540 - 13.00 15.70 615.00 103.00 49.00 31.00 15.40 11.70 9.320 7.660 6.460 5.550 WNW 437.00 40.70 30.100 1.810 40.70 40.70 1290.00 203.00 92.10 59.20 40.60 31.20 25.000 20.700 14.200 12.200 tM 924.00 194.00 -

8.660 40.50 200.00 1710.00 262.00 123.00 79.80 55.00 42.30 34.000 28.200 19.400 16.700 Nru 302.00 63.00 -

1.720 15.40 92.30 547.00 86.40 40.80 26.30 17.60 13.50 10.100 8.350 6.560 5.660 2-54 ISSUE 3

v l

1 BV-1 arxl 2 m)CM TABLE 2.2-10 FDR INFORMATION ONLY - USED IN CALCULATIO*! OF BV-2 CONTRIBUTION 'IU SITE DOSE RATE LIMITS BV-2 CONDENSATE POLISi!ING BUILDING VE24T ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS GROUND LEVEL RELEASES, FOR SPECIAL DISTNJCES (IDEFITIFIED IN TABLE 2.2-3), AND SELECTED COff1T40L LOCATIGJS (IE-7 sec/m )

INDIVIDUAL RECEPIDRS DISTNJCES 'IU TiiE COfirROL LOCATION, IN MILES DOWN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-

'IDR DARY GARDEN COW GGAT MAL DE13CE 0.5 1.0 1.5 2.0 ___2 . 5 3.0 3.5 4.0 4.5 5.9 N 105.0 14.00 -

5.740 6.74 14.80 244.0 42.6 h 50 12.70 8.18 6.15 4.45 3.640 2.770 2.380 NNE 102.0 7.37 -

2.130 6.83 7.64 161.0 28.8 11.40 6.94 4.79 3.56 2.78 2.250 1.870 1.590 NE 96.6 51.90 1.230 0.268 1.23 53.80 132.0 23.0 12.10 7.24 4.95 3.64 2.42 1.950 1.480 1.250 ENE 84.1 13.20 -

1.280 - 46.30 115.0 19.4 9.89 5.85 4.23 3.09 2.38 1.900 1.270 1.070 E 60.7 6.49 .829 1.980 1.98 35.70 99.2 16.6 6.32 3.75 2.55 1.87 1.32 1.000 0.871 0.735 ESE 37.1 7.25 --

3.100 7.25 7.25 65.8 11.1 5.36 3.19 2.00 1.46 1.03 0.829 0.621 0.524 SE 41.8 7.06 1.020 1.020 2.85 7.06 73.5 12.6 6.12 3.64 2.47 1.81 1.18 0.945 0.779 0.658 SSE 34.0 7.16 1.070 0.384 6.96 9.69 74.2 12.7 5.71 3.41 1.97 1.45 1.02 0.818 0.676 0.572 S 32.7 3.64 3.310 -- 6.00 6.27 109.0 18.6 7.13 4.29 2.94 2.17 1.53 1.230 1.020 0.866 SSW 29.7 6.73 3.890 1.800 6.73 20.90 120.0 21.3 8.31 5.03 3.46 2.57 2.00 1.620 1.230 1.040 SW 24.1 14.80 -

9.550 13.10 14.80 174.0 31.2 17.20 10.40 6.10 4.54 3.54 2.870 2.170 1.850 Wsw 159.0 20.80 6.010 - 19.10 20.80 301.0 53.6 25.30 15.60 10.80 8.09 5.93 4.830 3.750 3.200 W 264.0 16.90 10.100 - 13.90 16.90 636.0 111.0 53.90 33.50 16.50 12.40 9.82 8.040 6.760 5.790 WNW 404.0 44.50 32.500 1.870 44.50 44.50 1310.0 218.0 104.00 65.40 44.20 33.60 26.70 22.000 15.000 12.9t,'

tid 735.0 216.00 -

9.100 43.90 222.00 1720.0 279.0 140.00 88.80 60.30 95.90 36.60 30.100 20.600 17.700 nrm 247.0 71.00 -

1.820 17.00 99.40 557.0 924.0 45.90 28.90 19.20 14.60 10.80 8.880 6.950 5.980 2-55 ISSUE 3

_O_ O

I BV-1 and ' DDU" TABLE 2.2-11 DOSE FACTORS FOR NOBLE GASES AND DAUGHTEPS*

E. L. M. N.

1 1 1 1 TOTAL BODY GAMMA AIR BETA AIR NUCLIDE DOSE FACTOE SKIN DOSE FACTOR DOSE FACTnB DOSE FACTOR mrtm/yr mtem/yr m t rid /y t mrad /yr Per Per z Pr r Per uCi/m 3 uCi/m' ur:i,m 3

uCi/m 3 Kr-83m 7.56E-02 --

1.9?E401 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23F+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+nl 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Fr-88 1.47E+04 2.37E+03 1.52E.n4 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E403 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe 133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 X< !33 2.94E+02 3.06E+02 3.53E+02 1.03E+03 135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 l Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l

ll i

+The listed dose factors are for radionuclides that may be detected in gaseous effluents.

l 2-56 ISSUE 3

BV-1 and 2 ODCM TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES BEAVER VALLEY SITE

• l 1

V 1

B.I' 2

V.

2 B.3 2

NOBLE GAS TOTAL BODY GAMMA AIR TOTAL BODY GAMMA AIR NUCLIDE DOSE RATE DOSE RATE DOSE RATE DOSE RATE mrem /yr mrad /yr nrem/yr mrad /yr Per Per Per Per uCi/sec uCi/sec uCi/sec uCi/ set 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-4 1.20E-3 1.25E-3 1.88E-3 Xe-131m 1.64E-5 2.47E-5 1.67E 4 3.09E-4 Xe-133m 1.38E-5 2.11E-5 1.32E-4 2.61E-4 Xe-133 1.05E-5 1.56E-4 1. 54 E- 4 2.76E-4 Xe-135m 2.4]E-4 3.66E 4 6.21E-4 9.50E-4 Xe-135 1.41E 4 2.12E-4 6.06E-4 1.05E-3 Xe-137 6.00E-5 9.05E-3 9.66E-5 1.46E-4 Xe-138 8.11E-4 1.22E-3 2.22E-3 3.34E-3 Ar-41 1.02E-3 1.53E-3 2.68E-3 4.02E-3

• 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 Section 2.2.1 (10CFR20)

B; values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50)

V and B values to implement Mode 4 of Section 2.2.1 implement; i (10CFR20)andtol monitor setpoint determinations of Section 2.1.2 and 2.1.4 2-57 ISSUE 3

EV-! and 2 ONM Table 2.2-13

}

i VALUES FOR A Cii!LP FOR TFE FEAVER VALLEY SITE II Ittes/yr per uCi/cu reter) l i

hclide Bae Liver T. Body Thyroid Ei:!ney Lung GI-LL!

I i!-3 0.00b00 1.12E+03 1.12bO3 1.12bO3 1.12bO3 1.12bO3 1.12bO3 l 2 P-32 2.60D06 1.14b05 9.SBbC4 0.00b00 0.00D00 0.00b00 4.22b04 i 3 Cr-51 0.00b00 0.00D00 1.54bO2 8.55b01 2.43b01 1.70b04 1.0SbO3 4"n-54 0.00b00 4 29b 04 S.51bO3 0.00b00 1.00b04 1.5Eb06 2.29b04  ;

5 fe-59 2.07b04 . 34b04 1.67b04 0.00b00 0.00D00 1.27b06 7.07b04

)

6cc-57 0.00b00 9.03bO2 1.07bO3 0.00b00 0.00b00 5.07b05 1.32b04 7 Co-58 0.00b00 1.77bO3 3.16bO3 0.00b00 0.00b00 1.11b06 3.44b04 8 Co-60 0.00b00 1.31b04 2.26b04 0.00b00 0.00b00 7.07b06 9.62b04 9 3t-65 4.25b04 1.13b05 7.03b04 0.00b00 7.14b01 9.95b05 1.63b04 10 Eb-86 0.00b00 1.98b05 1.14b05 0.00b00 0.00b00 0.00D00 7.99bO3 11 Er-89 5.99b05 0.00D00 1.72bC4 0.00b00 0.00b00 2.16b06 1.67b05 12 Er-90 1.0lbOB 0.00b00 6.44b06 0.00b00 0.00b00 1.48b07 3.43b05 g 13T-91 9.14b05 0.00b00 2.44b04 0.00b00 0.00D00 2.63b06 1.64b05 y 14 Zr-95 1.90D05 4.18b04 3.70b04 0.00b00 5.96b04 2.23b06 6.11b04 15Nb-95 2.35b04 9.18bO3 6.55bO3 0.00b00 8.62bO3 6.14b05 3.70b04 16 Nb-97 4.29001 7.70F02 3.60F02 0.00b00 8.55E-02 3.42bO3 2.7Bb04 17Mo-99 0.00D00 1.72bO2 4.26b01 0.00b00 3.92bO2 1.35b05 1.27b05 18 Tc-99: 1.7E003 3.48003 5.77002 0.00b00 5.07F02 9.51bO2 4.81bO3 19 h-103 2.79bO3 0.00b00 1.07bO3 0.00b00 7.03bO3 6.62b05 4.4Eb04 20 Eu-106 1.36b05 0.00b00 1.69b04 0.00b00 1.84b05 1.43bO7 4.29b05 21 4 -110s 1.69b04 1.14b04 9.14bO3 0.00b00 2.12b04 5.48b06 1.00'b05 22 Sb-124 5.74b04 7.40bO2 2.00b04 1.26bO2 0.00b00 3.24b06 1.64b05 23Sb-125 9.64b04 7.59b02 2.07b04 9.10b01 0.00b00 2.32b06 4.03b04 24Te-127: 2.49b04 8.55bO3 3.02bO3 6.07bO3 6.36b04 1.4Bb06 7.14b04 25Te-129s 1.92b04 6.85bO3 3.04bO3 6.33bO3 5.03b04 1.76b06 1.82b05 26 I-131 4.81b04 4. Bib 04 2.73b04 1.62bO7 7.BBb04 0.00bD0 2.84bO3 27I-133 1.66b04 2.03b04 7.70bO3 3.85b06 3.3Bb04 0.00b00 5.48bO3 2BCe-134 6.51b05 1.01b06 2.25b05 0.00b00 3.30D05 1.21b05 3.85bO3 29 Cs-136 6.51b04 1.71b05 1.16b05 0.00D00 9.55b04 1.45b04 4.1EbO3 30Ce-137 9.07b05 8.25b05 1.2Eb05 0.00b00 2.82b05 1.04b05 3.62bO3 l

31 Ea-140 7.40b04 6.4Eb01 4.33bO3 0.00b00 2.11b01 1.74b06 1.02b05 32 La-140 6.44bO2 2.25bO2 7.55b01 0.00b00 0.00b00 1.B3b05 2.26b05 33Ce-141 3.92b04 1.95b04 2.90bO3 0.00 BOO B.55bO3 5.44b05 5.66b04 34 Ce-144 6.77b06 2.12b06 3.61b05 0.00b00 1.17b06 1.20bO7 3.29b05 Calculated per DDCd equation 2.2-13 l

ISSUE 3 l

2-58 l

BV-1 and 2 ODCM 2.3 Compliance Vith 10 CFR 50 Dose Limits (ODCM Appendix C CONTROLS 3.11.2.2 And 3.11.2.3) (Gaseous) l At the Beaver Valley site all elevated gaseous releases are considered to originate from a shared radvaste system. The effluent from both units are mixed and discharged from a common release point, the Process Vent, at the top of the Unit 1 Cooling Tower. The resulting duse for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception vould be a Containment Purge iia the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since this operation is expected to be rare, equations are shown throughout this section with the apportionment set at 0.5.

2.3.1 Dose Due To Noble Gases 2.3.1.1 Cumulation Of DosesSection II.B.1 of Appendix I of 10 CFR 50 (ODCM Appendix C CONTROL 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, ODCM Appendix C CONTROL 3.11.2.4 requires use of radvaste system if air doses when averaged over 31 days exceed 0.2 mrad for gamma and 0.4 mrad for be ta. 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:

During Any Calendar Quarter, For Gamma Radiation:

3.17E-8 I M; [(57 ),,0 ,, + ( Fq).,q;,,] + [B;0h + b;qg] $ 5 mrad 3

1 - -

[2.3-1]

During Any Calendar Quarter. For Beta Radiation:

3.17E-8 I N; (X/0)y0h, + (X/q)y qi ., + (X/0)sU n + (X/q)gq;s < 10 mrad 1 -

[ 7. 3-2 ]

During Any Calendar Year, For Gamma Radiation:

3.17E-8 I M; [(57 )y0 3,, + ( Eq~),,q;,,j +

(B;0; +

b;qis]- f 10 mrad 1 -

[2.3-3]

During Any Calendar Year. For Beta Radiation:

3.17E-8 I N; (XT ),,03,, + ( 57q ) ..q j 4 (fiU),0;g .

( Fq)gq;s-[j. 203 4)mrad 2

D 2-57 ISSUE 3

BV-1 and 2 ODCM Averaged over 31 Days, For The Gamma Radiation Projection:

l 3.17E-8 I M [ ( X / 0 ),,0g + (X/q)ygh,] + [B;0gg + bg qb l 3 0.2 mrad 1 -3 -

[2.3-5]

Averaged Over 31 Days, For The Beta Radiation Projection:

3.17E-8 I N; (X/0)y0 1y + (Uq)yqiy 4 < 0.4 mrad (UO)s0 is

• I 9}s91s [7.3-6) i - -

where:

M - The air dose factor due to gamma emissions for each 3

identified noble gas radionuclide "i" (mrad /yr per uCi/m3).

Ng = The air dose factor due to beta emissions for each identified n ble gas radionuclide "i" (mrad /yr 3

per uCi/m ).

- The annual average relative concen' ration for areas at or (XT )" beyond the unrestricted area boundary for 3 1ong-term vent releases greater than 500 hrs / year (sec/m' r.

( % )y = The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases 3

equal to or less than 500 hrs / year (sec/m ). {

1 (X/0)s = The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-s termhrs 500 f ree standing

/ year (sec/m 3)

. tad releases gream Gan

( 5 )s = The relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases equal te or less than 500 hrs / year 3

(sec/m ).

q. = Release of noble gas racionuclide "i" in gaseous effluents is for short-term stack releases equal to or less than 500 hrs / year (uci).

qg = Release of noble gas radionuclide "i" in gaseous effluents for short-term vent releases equal to or less than 500 hrs / year (uci).

O. = Pelease of noble gas radionuclide "i" in gaseous effluents for long-term free standing stack releases greater than 500 hrs / year (uCi).

= Release of noble gas radionuclide "i" in gaseous effluents O *.#

for long-tern vent releases greater than 500 hrs / year (uCi).

240 ISSUE 3

BV-1 and 2 ODCM B

y = The constant for long-term releases (greater than 500 hrs / year) for each identified noble gas radionuclide l "i" accounting for the gamma radiation from the elevated finite plume (mrad /yr per uCi/sec).

b. = The constant for short-term releases (equal to or less 1

than 500 hrs / year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad /yr per uCi/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], however, a summary of the "real time" meteorological data coupled with the corresponding releases shall be included in the Semi-Annual Radioactive Effluent Release Report.

Short-term releases are also evaluated annually in computer codes technically consistent with X00D00 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 conpliance with 10 CFR 50 l for the calendar quarter or year.

For Release Modes 1, 2, 3. And 4 During Any Month, Calendar Quarter. Or Year:

Gamma Radiation:

3.17E-8 I M3 [(X/0)ey0; + (X/0)yy0; + 0 0 +

1 cv vv (7./0)cp ;cp+ (X/0)dv g dv (X/0)yy0 3 J + 0.5 B g3 0

vv pv 0.2 mrad (per 31 days) [2.3-7)

$ S.0 mrad (per quarter) 10.0 mrad (per year)

D 2-61 ISSUE 3

BV-1 and 2 ODCM Beta Radiation:

3.17E-8 I N g (X/0)yy0 3 0 i (X/0)cv0 g cv

+

+ (X/0)cp 03 +

(X/0)dv 1 dv vv cp (X/0)yy0 g + 0.5 (X/0)py 0 3 0.4 mrad (per 31 days) [2.3-8]

< 10.0 mrad (per quarter) 20.0 mrad (per year) where:

(AM )cv = Annual aver ge relative concentration for releases from the Containment Building Vent (sec/m3).

(X/0)" = Annual average relative concentration for releases from the Ventilation Vent (sec/m ).

(X/0)E" - Annual average relative c neentration for releases from the Process Vent (sec/m3).

(X/0)tv = Annual verage relative concentration3 f r releases from the Turbine Building Vent (sec/m ).

Og = Release of radionuclide "i" from the Containment Building i cv Vent (uCl).

Og - Release or radionuclide "i" from the Ventilation Vent vv (uCi).

Og = Release of radionuclide "i" from the Process Vent pv (uCi).

Og = Release of radionuclide "i" from the Turbine Building tv Vent (uCi).

O. = Release of radionuclide "i" from the Condensate Polishing

'cp Building Vent (uci).

O f dv = Release of radionuclide "i" from the Decontamination Building Vent (uCi).

Og = Release of radionuclide "i" from the Vaste Gas Storage j vv Vault Vent (uCi).  ;

For Modes }, 2, 3, and 4 the controlling location is 0.35 miles NV.

Substitution of the appropriate X/0 values into Expressions [2.3-7) and

[2.3-8] results in the following:

4 2-62 ISSUE 3

BV-1 and 2 ODCM Release Modes 1, 2, 3, And 4 I During Any Month, Calendar Quarter, Or Year:

Gamma Radiation:

3.17E-8 I M [9.24E-3 O g + 1.03E 4 0 1 4 7.35E-5 O g + 7.35E-3 O g +

i cv vv tv ep 9.24E-5 O g + 9.24E-3 0 3 1 + 0.5 B i3O dv vv pv 0.2 mrad (per 31 days) [2.3-9]

$ 5.0 mrad (per quarter) 10.0 mrad (per year)

Beta Radiation:

3.17E-8 I N g 9.24E-5 O g + 1.03E-4 0 3 + 7.35E-5 O g + 7.35E-5 O g +

1 cv vv tv cp 9.24E-5 O g + 9.24E-5 0; + (0.5) 7.0E-10 O g dv vv pv 0.4 mrad (per 31 days) [2.3-10]

f 10.0 mrad (per quarter) 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) Radionuclide 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 radionuclide mix was based upon source terms calculated using the NRC GALE Code (inputs presented in Appendix B) and is presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point.

As in Section 2.2.1, for each release mode, the two highest boundary X/0 values for each release point and release duration were utilized in conjunction with the radionuclide mix and release for each release point to determine the controlling site boundary location. Since elevated releases occur from the BVPS site and their maximum X/0 values may not decrease with distance (i.e., the site boundary may not have highest X/0 values), the two highest X/0 values for those distances, greater than the site boundary, vere also considered in conjunction with the radionuclide mix to determine the controlling location. These h

F values of X/0 vere obtained for the midpoint of the 10 standatd distance intervals previously presented in Tables 2.2 4 through 2.2-10.

2-63 ISSUE 3

1 BV-1 and 2 ODCM For each release mode, a particular combination of release point mix and meteorology dominates in the determination of the controlling location. For Release Modes 1, 2, 3, and 4 the controlling release is the Ventilation Vent. For Release Mode 3, the controlling release is the Containment Building vent.

Values for M y and N controlling locatibn,whichwereusedinthedeterminationofthe and which are to be used by BV-1 and BV-2 in Expressions [2.3-9] and [2.3-10J to show compliance with 10 CFR 50 vere presented in Table 2.2-11. Values taken from Table B-1 of Regulatory Guide 1.109, yRevision 1 vere ~y multiplied by 1E6 to convert from picoeuries- to microcuries for use in Table 2.2-11.

In the determine ion of the controlling location for Modes 1, 2, 3, and 4, Tables 2.2-4 through 2.2-7 are utilized for X/0 values. The B y

values to be utilized are the same values which vere presented in Table 2.2-12. A description of the derivation of the various X/0 values is presented in Appendix A.

The following relationship should hold for BV-1 or BV-2 to show compliance with ODCM Appendix C CONTROL 3.11.2.2:

For The Calendar Quarter:

D $ 5 mrad [2.3-11]

DS$ 10 mrad [2.3-12]

For The Calendar Year:

I D $ 10 mrad [2.3-13]

Dg 3 20 mrad [2.3-14]

vhere:

D = The air dose from gamma radiation (mrad).

Dg = The air dose from beta radiation (mrad).

The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Expressions [2.3-11l through [2.3-14] are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM Appendix C CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations.

In addition ODCM Appendix C CONTROL 3.1.2.4 requires that the gaseous radvaste system must be used to reduce radioactive materials in that vaste when projected doses from each reactor unit when averaged over 31 days exceed any of the following:

D < 0.2 mrad [2.3-15] l Y-Dg $ 0.4 mrad [2.3-16]

I 2-64 ISSUE 3 l i

BV-1 and 2 ODCM l

2.3.1.2 Projection Of Doses (Noble Gas)

Doses due to gaseous releases from BV-1 and BV-2 shall be projected D at least once per 31 days in accordance with ODCM Appendix C CONTROL 4.11.2.4 and this section. (See also Section 2.3.2.2 l Projection Of Doses). The Gaseous Radvaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge in accordance with ODCM Appendix C CONTROL 3.11.2.4 when the projected gaseous effluent air dose due to gaseous effluent releases from each reactor unit, when averaged over 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 vill be calculated using Expressions j

[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 [2.3-17)

D 31 = T (31) + C Vhen Not Including Pre-Release Data, 1

D (31) + C .3-18]

31 -

where:

D31 = Pr jected 31 day dose (mrad).

A = Cumulative dose for quarter (mrad).

B = Projected dose f rom this release (mrad).

T = Current days into quarter.

l C = Value which may be used to anticipate plant trends (mrad).

l l

2-65 ISSUE 3

BV-1 and 2 ODCM 2.3.2 Dose Due To Radiolodines And Particulates j 2.3.2.1 Cumulation of Doses Section IIC of Appendix I of 10 CFR 50 (ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radioiodines and radioactive material in particulate form from each reactor unit such that estimated dose or dose commitment to an individual in an unrestricted area from all pathways of exposure is not in excess of 15 mrem to any organ. In addition, ODCM Appendix C CONTROL 3.11.2.4 requires the use of gaseous radvaste treatment system when the projected dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. Based upon NUREG-0133, the dose to an organ of an individual from radioiodines and particulates, 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:

3.17E-8 I R.IT [VsQ.is + v q.

s is

+ Vv0.iv + v vq.Iv]

3 0.3 mrem (per 31 days) [2.3-19)

$ 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:

O gg = Felease of radionuclide "i" for long-term free standing stack releases greater than 500 hrs /yr (uCi).

0,1

= Felease of radionuclide "i" for long-term vent releases greater than 500 hrs /yr (uCi).

q 3g - Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs /yr (uC1).

q;y = Release of radionuclide "i" for short-term vent releases equal to or less than 500 hrs /yr (uCi).

v = Dispersion parameter for estimating dose to an individual at the controlling location for long-term free standing stack releases greater than 500 hrs /yr.

3

= sec/m for the inhalation pathway, (M) .

-2

= meters for the food and ground plane pathway, (D7 ) .

V = The dispersion patameter for estimating the dose to >n individual at the controlling location for long-term vent releases greater than 500 hrs /yr.

= sec/m for the inhalation pathway, ( EU ) , .

= meters ~ for the food and ground plane pathway, ( D7U ),,

2-66 ISSUE 3

BV-1 and 2 ODCM v = Dispersion parameter for estimating the dose to an s

individual at the controlling location for short-term stack releases equal to or less than 500 hrs /yr.

3

= sec/m for the inhalation pathvay, (X/q)s.

= meters' for the food and ground plane pathway, (D/q)s' v = The dispersion parameter for estimating the dose to an y

individual at the controlling location for short-term vent releases equal to or less than 500 hrs /yr.

3

= sec/m for the inhalation pathway, ( Fq)y.

=

meters' for the food and ground plane pathway, (D/q)y.

3.17E-8 = The inverse of the number of seconds in a year.

Rg = The dose factor for each identified radionuclide "i" fI the organ "T" of , interest (mrem /yr per uCi/ set per m -2 or mrem /yr per uCi/m ').

Radionuclides and particulates may be released from any of the BV-1 and BV-2 vents in the release modes identified in Table 2.3-1. As described previously in Section 2.3.1.1, NUREG 0133 permits use of long-term annual average dispersion calculations which with the release modes of Table 2.3-1 results in the following expressions to show compliance with ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4. For a particular organ. Expression [2.3-19] becomes:

j _

3.17E-8 E R . 0.5 V 0 +V 0 +V 0 +V 0 + V 0 +

i IT pv 1 p .,

CV i n.

VV l yy tv i t/ CE I n

dv01 ""

dv vv 0.3 mrem (per 31 days) [2.3-20]

3 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:

i V = Dispersica parameter for releases from the Process Vent.

! pv l

V cy - Disr_rsion parameter for releases from the Containment Bus] ding Vent.

V., y = Dispersion parameter for releases from the Ventilation Vent.

V , = Dispersion parameter for releases from the Turbine Building Vent.

i I

l 2-67 ISSUE 3 i

BV-1 and 2 ODCM w

ep

- Dirnersion parameter for releases from the Condensate Polishing Building Vent. {

V dv = Dispersion parameter for releases from the Decontamination Building Vent.

V

" = Dispersion parameter for releases from the Vaste Gas Storage Vault Vent.

i py = Release of radionuclide "i" from the Process Vent (uCi).

O i - Release of radionuclide "i" from the Containment Building C"

Vent (uC1).

0 1, - Release of radionuclide "1" from the Ventilation Vent (uci).

O f

tv = Release of radionuclide "i" from the Turbine Building Vent (uci).

0 1

CE

- Release of radionuclide "i" from the Condensate Polishing Building Vent (uC1).

O ldv = Release of radionuclide "i" from the Decontamination Building Vent (uCi).

0 1

" = Release of radionuclide "i" from the Waste Gas Storage Vault Vent (uCi).

The Turbine Building Vent is not normally a radioactive release point.

It is included only for use if a radioactive release is identified in the future.

)

In determining the dose at a particular location, dispersion parameter V, is a function of the pathway. For the food and ground plane pathway, V is in terms of D/0 If the inhalation pathway is considered, V is in terms of X/0., Incorporation of the various pathways into Expression [2.3-20] results in the following expression for a particular organ:

3.17E-8 I [R. +R + R. +V g

ITg ig+ R 1 3 IT B ][0.5 VP "0 *.pv '"0 I cv +V""0I vv +

Vtv0i +V ty 'POi cp 4 V #O ds

+V "0. vv ]4 R.*T I

I

[0.5 (X/0)pv O i py

+ .

(X/0)evO.i + (X/0)vv9 1, (X/0)tv9 1

+ (X/0)cp0 i +

(X/0)dv0 3 + (X/0),,0;

}

dv vv 0.3 mrem (per 31 days) [2.3-21]

< 7.5 mrem (per quarter) 15.0 mrem (per year) 2-6B ISSUE 3

BV-1 and 2 ODCM vhere:

R gT "T"

G= ground plane exposure pathvayfor radionuelide "i" for the se f actor f or an organ (mrem /yr per uCi/sec per m -2).

R iry' - Dose factor for an organ "T" for radionuclide "i" for either the cow m uCi/see per m -2) ilk or goat milk pathway (mrem /yr per R "

iT = Dose factor for an organ "T" for radionuclide vegetable pathway (mrem /yr per uCi/see per m -2)i" . f r the R

3TB = Dose factor for an organ "T" for the meat pathway (mrem /yrfor perradionuclide uCi/see per m "i"2).

R iT7 = Dose f actor for an organ "T" for radionuclide 3 "I" for the inhalation pathway (mrem /yr per uCi/m ).

It should be noted that V V V , V and

,Vcp, V dv,/Q(m-V yy in Expression [2.3-21]pV,are C#,in " terms "of D ).

Values of the dose factor, R. were calculated using the methodology of NUREG-0133. The followiQ, equations were used for all nuclides except tritium:

iT7 = K'(BR) (DFAh)a

= mrem /yr per uCi/m 3 [2.3-22]

h where:

K' = A constant of unit conversion (1E6 pCi/uCi).

(BR)a The breathing 3 rate of the receptor of age group "a" (m /yr).

(DFA g )a - Each organ inhalation dose factor for the receptor of age group "a" for the "i" th radionuclide (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)a used for the various age groups are tabulated below, as given in Table E-5 of the Regulatory Guide 1.109.

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

Infant 1400 Child 3700 Teen 8000 Adult 8000 2-69 ISSUE 3

bV-1 and 2 ODCM t

iTg = K'K" (SF)DFGg [(1 - e i )f y

-m mrem /yr per uCi/sec [2.3-23] l where:

K' - A constant of unit conversion (1E6 pCi/uCi).

K" = A constant of unit conversion (8760 hr/ year).

i - The decay constant for the "i" th radionuclide (sec-1),

t - The exposure time (4.73E8 sec or 15 years).

DFG 3

- The groundplane dose conversion f actor9f or organ "T" for the "i" th radionuclide (mrem /hr per pCi/m'). A tabulation of DFG values is presented in Table E-6 of Regulatb[yGuide1.109.

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

t ~ i tg 0 (U ff (1 - ff )e- ih iT g-K'[i "P)F,(r)(DFLy v

3 )a! p S

2

- m -mrem /yr per uCi/sec [2.3-24j k

where:

K' = A constant of unit conversion (1E6 pCi/uCi).

Op =

The animal's consumption rate, vet weight (kg/ day).

U "E

- The receptor's milk consumption rate, for age "a" (liters /yr).

Y E

=

The agricultur al,,pr oduc tivity by uni t area of pasture feed grass (kg/m').

Y g

=

The agricultural 9pr oduc tivi ty by unit area of stored feed (kg/m').

F = The stable element transfer coefficients (days / liter).

r = Fraction of deposited activity retained on animals feed g r e.s s .

(DFL.**)^ = The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem /pCi). Ingestion dose factors for the various age groups are given in Table (DFLi E T) 11 through E-14 of Pegulatory Guide 1.109 or Tables 1 through 4 of !IUPEGA172.

2-70 ISSUF. 3

BV-1 and 2 ODCM i = The decay constant for the "i" th radionuclide (sec-1),

V = The decay constant for removal of activity on -y leaf and plant surfaces by veathering 5.73E-7 sec (corresponding to a 14 day half-life).

f = The transport time from pasture, to animal, to milk, to receptor (sec).

t h - The transport time from pasture, to harvest, to animal, to milk, to receptor (sec).

Ip = Fraction of the year that the animal is on pasture (dimensionless).

I s = 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.

Parameter Value Table r (dimensionless) 1.0 for radiciodine E-15 0.2 for particulates E-15 F* (days / liter) each stable element E-1 (cow milk)

E-2 (goat milk)

D U

• P (liters /yr) - infant 330 E-5 child 330 E-5 teen 400 E-5 adult 310 E-5 (mrem /pCi) each radionuclide E-11 to E-14 (DLF1)

Y 0.7 E-15 p (kg/m )

2 Ys (kg/m ) 2.0 E-15 1.73E5 (2 days) E-15 t

f (seconds) t 7.78E6 (90 days) E-15 h (seconds)

Op (kg/ day) 50 E-3 fp 0.5 --

f 1.0 --

s 1 For goat's milk, all values remain the same except for Op which is 6 kg/ day.

D 2-71 ISSUE 3 I

i BV-1 and 2 ODCM 0 (U ) ff -At t if l (1 - f f )e ih iT f(r)(DRg 7)aI +

I*

B" A +

g

= m -mrem /yr per uCi/sec [2.3-25]

vhere:

F g = The stable element transfer coefficients (days /kg).

U = The receptor's meat consumption rate for age "a" (kg/yr),

t f - The average time from slaughter of meat animal to consumption (sec).

t h = The transport time from crop field to receptor (sec).

All parameter values are the same as the milk pathway parameter values except F vh;ch is obtained from Table E-1, t which is obtained from TableEd5aniU vhichisobtainedfromTablbE-5. The values as obtained fromapRegulatory Guide 1.109, are as follows:

Parameter Value Table Ff (days /kg) each stable element E-1 t

f (seconds) 1.73E6 (20 days) E-15 U

ap (kg/yr) - infant 0 E-5 child 41 E-5 teen 65 E-5 adult 110 E-5 Man is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:

)

y = K' [,y . ](DLFu}a[U f e +Uf*

ag I

= m -mrem /yr per uti/sec [2.3-26]

vhere:

K' = A constant of unit conversion (IE6 pCi/uCi).

U ,L = The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr).

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

fg = The fraction of the annual intake of fresh leafy vegetation grown locally.

k 2 72 ISSUE 3

BV-1 and 2 ODCM f g- The fraction of the annual intake of stored vegetation grown locally.

k tg - The average time between harvest of leafy vegetation and its consumption (seconds).

t h - The average time between harvest of stored vegetation and its consumption (seconds).

Yy = The vegetation area density (kg/m ).

all other factors are defined previously.

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

Parameter Value Table r (dimensionless) 1.0 for radiciodines E-15 0.2 for particulates E-15 (DFL3) (mrem /pCi) each stable element E-11 to E-14 b

Ua (kg/yr) - infant 0 E-5 child 26 E-5 teen 42 E-5 adult 64 E-5 S

D U* (kg/yr) - infant 0 E-5 child 520 E-5 teen 630 E-5 adult 520 E-5 fg (dimensionless) 1.0 E-15 F (dimensionless) 0.76 E-15 tg (seconds) 8.6E4 (1 day) E-15 t

h (seconds) 5.18E6 (60 days) E-15 Yy (kg/m ) 2.0 E-15 As discussed in Section 2.2.2 for tritium, the parameter V for the food pathway is based upon X/0 The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression [2.3-20J 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 TT ) [0.5 (X/0) O T + (X/0)cy0 T

• M Tk' R TTB I pv cv (X/0)yy0 T +

(X/0)tv 0T vv +( 0)cp07 +

(W 0dv T +( 0)yy0 7 ]

vv cp dv vv

!2.3-27]

2 73 ISSUE 3

BV-1 and 2 ODCM vhere:

R = Dose factor for organ "T" for tritium for the milk 3

j Th pathway (mrem /yr per uCi/sec ).

R = Dose factor f or organ "T" for tritium for the vegetable 3

T3 pathway (mrem /yr per uCi/m ).

P = Dose f actor f or organ "T" for tritium for the beef 3 pathway (mrem /yr per uCi/m ).

P = Dose f actor for organ "T" for tritium for the inhalation I pathway (mrem /yr per uCi/m ).

Expression [2.3-27) is used to show compliance with 40 CFR 190, as discussed in Section 4.0.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R is based on [X/0): Th F

T g= K'K'"F 0 Um F ap(DLF.2T)a[0.75(0.5/H)]

= mrem /yr per uCi/m [2.3-28]

where:

K'" = A constant of unit conversion (1000 gm/kg).

H = Absolute humidity of the atmosphere (8 gm/m ).

0.75 = The fraction of total feed that is water.

0.5 = The ratio of the specific activity of the feed grass vater to the atmospheric water, and other parameters and values are the same as for R .

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the R is based on [X/0): Y R

TTy = K'K'"[U faL+Ufa g](DFL.I T)a [ 0. 75( 0. 5/H ) ]

= mrem /yr per uCi/m [2.3-29]

vhere all terms have been defined above.

The concentration of tritium in meat is based on its airbo: ne concentration rather than the deposition. Therefore, the R TT is based B

on [X/0):

4 2-74 ISSUE 3

BV-1 and 2 ODCM n

"T g= K'K'"F 0,Uf F ap(DFL.I T) a [ 0. 75 (0. 5 / H ) ]

- mrem /yr per uCi/m [2.3-30]

vhere all terms have been defined above.

To show compliance with ODCM Appendix C CONTROLS 3.11.2.3 and 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 NV sector. Inserting appropriate X/0 values from Tables 2.2 4 to 2.2-10 and D/0 values from Tables 2.3-28 to 2.3-34, Expression [2.3-21] becomes:

Release Modes 1 Through 4 Per Month, Calendar Quarter, Or Year:

3.17E-8 E g ][(0.5)4.22E-10 O g + 1.56E-8 O cy + 1.56E-8

[Rh+R G J pv Og + 1.55E-8 O g + 1.53E-8 O g + 1.56E-8 O g + 1.56E-8 vv tv I cp dv Og ]+R g [(0.5) 7.30E-9 O g + 2.00E-5 O g + 2.71E-5 O g vv I pv cv vv

+ 2.22E-5 O g + 2.22E-5 O g + 2.00E-5 O g + 2.00E-5 O g ]

tv cp dv vv 0.3 mrem (per 31 days) [2.3-31]

< 7.5 mrem (per quarter 15.0 mrem (per year)

For tritium, for purposes of implementation of 40 CFR 190, as discussed in Section 4.0, Expression [2.3-28] reduces to:

3.17E-8 [R +R TT ][(0.5)7.30E-9 Og + 2.00E-5 Og + 2.71E-5 Og +

J I pv cv vv 2.22E-5 O g + 2.22E-5 O g + 2.00E-3 O g + 2.00E-3 O g ]

tv cp dv vv

[2.3-32]

The determination of a controlling locating for implementation of ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4 for radiciodines and particulates is a function of:

(1) Radionuclide mix and their isotopic release (2) Release mode (3) Meteorology (4) Exposure pathway (5) Receptor's age The incorporation of these parametcrs into Expression [2.3-19] results in the respective equations for each release mode at the controlling location.

2-75 ISSUE 3 1

BV-1 and 2 ODCM In the determination of the controlling location for each release mode, the radionuclide mix of radiciodines and particulates was based upon the source terms calculated using the GALE code. This mix was presented in Tables 2.2-2a and 2.2-2b as a function of release mode and release point. For the ground plane exposure pathway, all radionculides (excluding H-3 and C-14) vere considered in the determination of the controlling location. For the inhalation and food pathways H-3 and C-14 vere also considered in determination of the controlling location.

Ir. the determination of the controlling location for each release mode, all of the exposure pathways, as presented in Table 2.2-3, were evaluated. These include cov milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathvay locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathvays were considered to be present at all locations.

For the determination of the controlling location, the highest D/0 and X/0 values for each release point and release mode for the vegetable garden, cov milk, and goat milk pathways were selected. The organ dose was calculated at each of these locations using the radionuclide mix and release of Tables 2.2-2a and 2.2-2b 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 Modes 1 thtough 4, the controlling release point and mix is the Ventilation Vent. {

Tables 2.3-2 through 2.3-20 present R. values for the total body, GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways. These values vere calculated using the methodology described in NUREG-0133 using a grazing period of 6 months.

In the determination of the controlling location for Release Modes 1-4, Tables 2.2-4 through 2.2-10 are utilized for X/0's Tables 2.3-28 through 2.3-34 are utilized for long term D/0 values. A description of the derivation of the various X/0 and D/0 values is presented in Appendix A.

Long-term D/0 values for the Process Vent, Containment Building Vent, the Ventilation Vent, Turbine Building Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and the Vaste 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., 4.0 4.5 mi., 4.5-5.0 mi.

The values appear in Tables 2.3-21 through 2.3-27. These values may be utilized if an additional special location arises different from those presented in the special locations of Table 2.2-3. q 2 76 ISSUE 3

BV-1 and 2 ODCM The following relationship should hold for BV-1 or BV-2 to show compliance with ODCM Appendix C CONTROL 3.11.2.2.

For The Calendar Quarter:

D $ 7.5 mrem to any organ [2.3-33]

For The Calendar Year:

D $ 15 mrem to any organ [2.3-34]

where:

D - The dose to any organ from radiciodines and particulates (mrem).

The quarterly limits given above represent one-half the annual design objective of Section IIC of Appendix I of 10 CFR 50. If any of the limits of Expressions [2.3-33) and [2.3-34] are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM Appendix C CONTROL 3.11.2.3.a must be filed with the NRC at the identified locations.

D D

2-77 ISSUE 3

BV-1 and 2 ODCM l 2.3.2.2 Projection of Doses (Radiciodines And Particulates)

Doses due to gaseous releases from BV-1 or BV-2 shall be projected at least once per 31 days in accordance with ODCM Appendix C CONTROL 4.11.2.4 and this section. (See also Section 2.3.1.2 Projection of Doses). The apptopriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge in accordance with ODCM Appendix C CONTROL 3.11.2.4 when the pr oj ec t ed doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (See also Section 2.3.1.2 Projection of Doses for additional specifications). Doses resulting from the gaseous effluent release of radiciodines and particulates vill be calculated for use in the 31-day dose projection using i Expression [2.3-31]. The 31-day dose projection shall be performed i according to the following equations- l J

Vhen Including Pre-Release Data, i

D A+B (31) +C [2.3-35]

31 =

T When Not Including Pre-Release Data, j l

D 31 = (31) + C l2.3-36) where:

D31 = Projected 31 day dose (mrem).

A = Cumulative dose for quarter (nrem).

B = Projected dose for this release (mrem).

l T = Current days into quarter.  ;

1 C = Value which may be used to anticipate plant trends (mrem). '

l 2 78 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR I IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT MODE 1 MODE 2 MODE 3 MODE 4 2 Same As BVPS BVPS-2 Main Cond. Air Same As Same As Process Vent (pv) Ejector, Vaste Mode 1 Mode 1 Mode 1 And Gas, Contain- Containment ment Vacuum Purge BVPS-1 Ventilation Aux. Bldg., Contajnment Same As Same As Vent (vv1) Ventilation Purge Mode 1 Mode 1 BVPS-1 Containment Leakage Same As Same As Same As Mode 1 Mode 1 And Mode 1 Vent (cv1) Collection Exhaust Contajnment Purge BVPS-1 Turbine Bldg. Turbine Bldg. Same As Same As Same As Vent (tv1) Exhaust

• Mode 1* Mode 1* Mode 1*

1 Same As Same As BVPS-2 Ventilation Contiguous Contajnment Vent (vv2) Areas Purge Mode 1 Mode 1 1 Same As BVPS-2 Containment Aux. Bldg. Same As Same As Vent (cv2) Ventilation Mode 1 Mode 1 And Mode 1 Contajnment Purge BVPS-2 Turbine Bldg.1 Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust

• Mode 1* Mode 1* Mode 1*

BVPS-2 Condensate Polishing Bldg. Vent (cp2)

BVPS-2 Decontamination

• Bldg. Vent (dv2)

I * * *

• BVPS-2 Vaste Gas Storage Vault Vent (vv2)

• 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 l time of the annual report.

l fContinuousgroundlevelmeteorologyisapplicable Continuous elevated meteorology is applicable 3

Mode established by purge from one unit, all other release points remain same as Mode 1 2 79 ISSUE 3 i

l i

l

EV-1 and 2 ODCM l

Table 2.3-2 RVALUESFOREEAVERVALLEY 'E I (stes/yr per uC1/cu seter)

Pathway : Inhalation Age Grrup : Adult liuelide Bone Liver T. Body Thyroid Eidney Lung GI-LLI 1 R-3 0.00Et00 1.26bO3 1.26bO3 1.26bO3 1.26bO3 1.26bO3 1.26bO3 2 P-32 1.32b06 7.71D04 5.0lb04 0.00D00 0.00b00 0.00b00 8.64b04 3 Cr-51 0.00D00 0.00b00 1.00E+02 5.95b01 2.28b01 1.44E+04 3.32bO3 4 Mn-54 0.00D00 3.96b04 6.30bO3 0.00b00 9.84bO3 1.40D06 7.74b04 5 Fe-59 1.1BE+04 2.76b04 1.06b04 0.00b00 0.00b00 1.02b06 1.BBb05 6 Co-57 0.00D00 6.92bO2 6.71bO2 0.00b00 0.00D00 3.70D05 3.14b04 7 Co-58 0.00b00 1.5Eb03 2.07bO3 0.00b00 0.00D00 9.2Sb05 1.06b05 8 Co-60 0.00D00 1.15b04 1.45b04 0.00D00 0.00b00 5.97b06 2.B5b05 9 In-65 3.24E+04 1.03D05 4.66b04 0.00b00 6.90b04 B.64b05 5.34b04 10 Rb-86 0.00 BOO 1.35b05 5.90b04 0.00b00 0.00b00 0.00b00 1.66t+04 11 Sr-89 3.04b05 0.00b00 8.72bO3 0.00D00 0.00D00 1.40D06 3.50b05 12 St-90 9.92bO7 0.00b00 6.10D06 0.00b00 0.00b00 9.60D06 7.22b05 13 Y-91 4.62b05 0.00b00 1.24b04 0.00b00 0.00D00 1.70b06 3.65b05 142r-95 1.0'b05 3.44b04 2.33b04 0.00b00 5.42b04 1.77b06 1.50D05 15 lib-95 1.41b04 7.82bO3 4.21bO3 0.00b00 7.74bO3 5.05b05 1.04b05 16 lib-97 2.22b01 5.62E-02 2.05b02 0.00D00 6.54002 2.40bO3 2.42bO2 17 Mo-99 0.00D00 1.21bO2 2.30b01 0.00b00 2.91bO2 9.12b04 2.42b05 18 Te-99: 1.03E-03 2.91003 3.70E-02 0.00b00 4.42E-02 7.64bO2 4.16bO3 19 Ru-103 1.53bO3 0.00b00 6.5BbO2 0.00D00 5.83bO3 5.05b05 1.10D05 20 Ru-106 6.91b04 0.00b00 8.72bO3 0.00b00 1.34b05 9.36b06 9.12b05 21 Ag-110 1.06b04 1.00b04 5.94bO3 0.00b00 1.97h04 4.63b06 3.02b05 22 St-124 3.12b04 5.89b02 1.24b04 7.55b01 0.00b00 2.4BluS 4.06b05 23 Sb-125 5.34b04 5.95bO2 1.26b04 5.40D01 0.00 BOO 1.74bOE 1.0lb05 24 Te-127: 1.26h04 5.77bO3 1.57bO3 3.29bO3 4.5Eb04 9.60D05 1.50D05 25 Te-129: 9.76b0J 4.67bO3 1.58bO3 3.44bO3 3.66b04 1.16b06 3.63b05 26 I-131 2.52b04 3.5Bb04 2.05b04 1.19bO7 6.13b04 0.00b00 6.26bO3 271-133 8.64bO3 1.4Eb04 4.52bO3 2.15b06 2.5Eb04 0.00b00 B.BSbO3 28 Ce-134 3.73b05 8.4Bb05 7.2Eb05 0.00b00 2.87b05 9.76b04 1.04b04 29 Cs-136 3.90b04 1.46b05 1.10b05 0.00b00 B.56b04 1.20b04 1.17b04 30 Ce-137 4.7Bb05 6.21b05 4.2Bb05 0.00b00 2.22D05 7.52b04 8.40bO3 31 Ea-140 3.90E44 4.90b01 2.57bO3 0.00D00 1.67b01 1.27b06 2.16b05 32 La-140 3.44bO2 1.74bO2 4.58b01 0.00D00 0.00b00 1.36b05 4.5Bb05 33Ce-141 1.99b04 1.35b04 1.53b03 0.00b00 6.26bO3 3.62b05 1.20b05 i 1

34 Ce-144 3.43b06 1.43b06 1.84b05 0.00b00 B.4Bb05 7.7Bb06 8.16b05 Calculated per ODCM equation 2.3-22 4 lEP E 3 2-80

EV-1 and 2 ODCM Table 2.3-3 g

R VALUES FOR EEAVER VALLEY SITE (tres/yrperUCi/cuseter)

Pathway : Inhalatien Age Group : Teen Nuclide Ecce Liver T. Body Thyroid lidney Lung GI-LLI 1 i!-3 0.00E+00 1.27bO3 1.27bO3 1.27bO3 1.27bO3 1.27bO3 1.27bO3 2 F-32 1.89b06 1.10D05 7.16b04 0.00b00 0.00b00 0.00D00 9.26b04 3 Cr-51 0.00D00 0.00b00 1.35bO2 7.50D01 3.07b01 2.10b04 3.00bO3 4 h-54 0.00b00 5.11b04 8.40bO3 0.00D00 1.27b04 1.9Bb06 6.6Eb04 5 fe-59 1.59b04 3.70D04 1.43D04 0.00D00 0.00E+00 1.53b06 1.78b05 6 Co-57 0.00D00 9.44bO2 9.20bO2 0.00D00 0.00D00 5.86b05 3.14D04 7 Co-58 0.00b00 2.07bO3 2.72D03 0.00b00 0.00 BOO 1.34b06 9.52b04 S Co-60 0.00b00 1.51b04 1.98b04 0.00b00 0.00b00 8.72b06 2.59b05 9 Zn-65 3.66b04 1.34b05 6.24b04 0.00b00 8.64D04 1.24b06 4.66b04 10 Rb-66 0.00b00 1.90D05 8.40b04 0.00D00 0.00b00 0.00D00 1.77b04 11 St-89 4.34b05 0.00D00 1.25b04 0.00D00 0.00b00 2.42b06 3.71b05 12 3r-90 1.0EbOB 0.00b00 6.6Eb06 0.00D00 0.00 BOO 1.65bO7 7.65b05 13 Y-91 6.61b05 0.00b00 1.77b04 0.00 BOO 0.00b00 2.94b06 4.09b05 14Zr-95 1.46b05 4.52b04 3.15b04 0.00 BOO 6.74004 2.69b06 1 49b05 l

15 Nb-95 1.56b04 1.03b04 5.66bO3 0.00b00 1.00b04 7.51b05 9.6Bb04 16 Nb-97 3.14F01 7.78b02 2.84bO2 0.00b00 9.12E-02 3.93bO3 2.17bO3 17 b-99 0.00b00 1.69E+0? 3.22b01 0.00D00 4.11bO2 1.54b05 2.69b05 15 Tc-99s 1.3Eb03 3.66003 4.99b02 0.00D00 5.76E-02 1.15bO3 6.13bO3 19 h-103 2.10bO3 0.00D00 8.96bO2 0.00D00 7.43b03 7.83b05 1.09b05 20 h-106 9.B4b04 0.00b00 1.24b04 0.00b00 1.90b05 1.61bO7 9.60b05 21 Ag-110s 1.35b04 1.31b04 7.99h03 0.00b00 2.50b04 6.75b06 2.73b05 22 Sh-124 4.30b04 7.94bO2 1.65b04 9.76b01 0.00b00 3.34b06 3.9Bb05 235b-125 7.35b04 8.05D02 1.72b04 7.04b01 0.00b00 2.74b06 9.92b04 24Te-127s 1.80D04 8.16bO3 2.1Eb03 4.36bO3 6.54D04 1.66b06 1.59b05 l

25Te-12Pa 1.39b04 6.5ED03 2.25bO3 4.5EbO3 5.19b04 1.95b06 4.05b05 1 26 I-131 3.54b04 4.91b04 2.64b04 1.46bO7 8.40b04 0.00b00 6.49b03 l 27 I-133 1.22b04 2.05b04 6.22bO3 2.92b06 3.59b04 0.00b00 1.03b04 l 2B Cs-134 5.02b05 1.13D06 5.49b05 0.00D00 3.75b05 1.45b05 9.76bO3 l 29 Cs-136 5.15b04 1.94b05 1.37b05 0.00b00 1.10b05 1.7Eb04 1.09b04 l 10 Cs-137 6.70b05 8.42b05 3.11b05 0.00b00 3.04b05 1.21b05 8.4BbO3 l

31 Ea-140 5.47b04 6.70bO1 3.52bO3 0.00D00 2.28b01 2.03b06 2.29b05 i 32 La-140 4.79bO2 2.36bO2 6.26b01 0.00b00 0.00b00 2.14b05 4.S7b05 i 33 Ce-141 2.84b04 1.90b04 2.17bO3 0.00b00 8.B6bO3 6.14b05 1.26b05 1

34 Ce-144 4.E9b06 2.02b06 2.62b05 0.00D00 1.21b06 1.34bO7 8.64b05 Calculated nr GCM epati:n 2.3-22 2-51

EV-1 and 2 ODCM Table 2.3-4 R VALDIS FOR E! AVER VALLEY SITI (tres/yr per . i/cu seter)

Pathway : Ithalation Age Group : Child Nuclide Bone Liver T. Body Thyroid tidney Lung GI-LLI 1 b3 0.00b00 1.12bO3 1.12bO3 1.12bO3 1.12bO3 1.12bO3 1.12bO3 2 P-32 2.60b06 1.14b05 9.88b04 0.00D00 0.00b00 0.00b00 4.22b04 3 Cr-51 0.00b00 0.00D00 1.54bO2 B.55b01 2.43b01 1.70b04 1.06bO3 4Mn-54 0.00b00 4.29b04 9.51bO3 0.00D00 1.00D04 1.58b06 2.29E+04 5 Fe-59 2.07b04 3.34b04 1.67b04 0.00D00 0.00b00 1.27b06 7.07b04 6Co-57 0.00b00 9.03bO2 1.07bO3 0.00b00 0.00b00 507b05 1.32b04 7 Co-5B 0.00b00 1.77bO3 2.16bO3 0.00b00 0.00b00 1.11h06 3.44b04 8 00-60 0.00b00 1.31b04 2.26b04 0.00b00 0.00b00 7.07b06 9.62b04 92n-65 4.25b04 1.13h05 7.03D04 0.00b00 7.14b04 9.95b05 1.63b04 10 Rb-B6 0.00b00 1.98b05 1.14b05 0.00D00 0.00b00 0.00b00 7.99bO3 11Sr-29 5.99b05 0.00b00 1.72b04 0.00b00 0.00b00 2.16b06 1.67b05 12 St-90 1.0lbO8 0.00b00 6.44b06 0.00D00 0.00D00 1.45bO7 3.43b05 13 F91 9.14b05 0.00b00 2.44b04 0.00b00 0.00D00 2.63b06 1.84b05 14 Zr-95 1.90D05 4.1Bb04 3.70D04 0.00h00 5.9fb04 2.23b06 6.11b04 l 15 Nb-95 2.35b04 9.15bO3 6.55bO3 0.00b00 8.62bO3 6.14b05 3.70b04 16 lib-97 4.29E-01 7.70E-02 3.60002 0.00b00 B.55bO2 3.42bO3 2.7Eb04 17 Mo-99 0.00D00 1.72bO2 4.26b01 0.00 BOO 3.92bO2 1.35b05 1.27b05 18 Tc-99 1.78b03 3.45E-03 5.77b02 0.00b00 5.07bO2 9.51bO2 4.BibO3 19 Eu-103 2.79bO3 0.00b00 1.07bO3 0.00b00 7.03D03 6.62b05 4.4Bb04 202u-106 1.36b05 0.00r+00 1.69D04 0.00D00 1.84b05 1.43bO7 4.29b05 21Ag-110s 1.69b04 1.14b04 9.14bO3 0.00b00 2.12b04 5.45b06 1.00b05 22 Eb-124 5.74b04 7.40bO2 2.00b04 1.26bO2 0.00b00 3.24b06 1.64b05 23Sb-125 9.64b04 7.59bO2 2.07b04 9.10b01 0.00D00 2.32b06 4.03b04 24Te-127: 2.49b04 8.55bO3 3.02bO3 6.07bO3 6.36b04 1.4Bb06 7.14b04 25Te-129s 1.92D04 6.8EbO3 3.04bO3 6.33bO3 5.03b04 1.76b06 1.B2b05 26I-131 4.81b04 4.81b04 2.73b04 1.62bO7 7.88b04 0.00b00 2.84bO3 27 1-133 1.66b04 2.03b04 7.70bO3 3.85b06 3.3Bb04 0.00b00 5.4BbO3 2B Cs-134 6.51b05 1.0lb06 2.25b05 0.00b00 3.30D05 1.21b05 3.85bO3 29Cs-136 6.51b04 1.71b05 1.16b05 0.00b00 9.55b04 1.45b04 4.12bO3 30 Ce-137 9.07b05 8.25b05 1.28b05 0.00b00 2.82b05 1.04b05 3.62bO3 31 Ba-140  ?.40D04 6.42b01 4.33b03 0.00b00 2.11b01 1.74b06 1.02b05 32la-140 6.44bO2 2.25bO2 7.55b01 0.00D00 0.00D00 1.83b05 2.26b05 33Ce-141 3.92b04 1.95b04 2.90bO3 0.00b00 B.55D03 5.44b05 5.66b04 34 Ce-144 6.77b06 2.12b06 3.61b05 0.00b00 1.17b06 1.20bO7 3.89b05 l

Calculated per ODCM equation 2.3-22 IEEE 3 2-82

M-1 and 2 ODCM Table 2.3-5 R VALUES FOR EEAVER VALLEY SITE (ares /yr per uCi/en seter)

Fathway: Inhalation AgeGrcup: Infant helide Bone Liver f. Body Thyroid lidney Lung GI-LLI 1 F3 0.00b00 6.47bO2 6.47bO2 6.47bO2 6.47:+02 6.47bO2 6.47bO2 2P-32 2.03b06 1.12b05 7.74b04 0.00b00 0.00b00 0.00b00 1.61b04 3Cr-51 0.00b00 0.00b00 8.95b01 5.75b01 1.32b01 1.28E+04 3.57bO2 4 Me-54 0.00D00 2.53b04 4.96bO3 0.00b00 4.98b03 1.00b06 7.06bO3 5 Fe-59 1.36b04 2.35b04 9.48bO3 0.00 BOO 0.00D00 1.01b06 2.4Bb04 6Co-57 0.00b00 6.51D02 6.41E+02 0.00b00 0.00b00 3.79b05 4.86bO3 7 Co-5B 0.00b00 1.22bO3 1.82bO3 0.00b00 0.00b00 7.77b05 1.11b04 8 00-60 0.00b00 8.02bO3 1.1Bb04 0.00b00 0.00 BOO 4.51006 3.19b04 9 2n-65 1.93b04 6.26b04 3.11b04 0.00D00 3.25b04 6.47b05 5.14b04 10 Rb-86 0.00D00 1.90b05 8.82b04 0.00000 0.00D00 0.00 BOO 3.04bO3 11St-89 3.9Bb05 0.00 BOO 1.14b04 0.00b00 0.00b00 2.03b06 6.40D04 12 Er-90 4.09bO7 0.00b00 2.59b06 0.00b00 0.00D00 1.12bO7 1.31b05 13 ES1 5.86b05 0.00b00 1.57b04 0.00b00 0.00b00 2.45b06 7.03b04 l 14Ir-95 1.15b05 2.79b04 2.03b04 0.00b00 3.11b04 1.75b06 2.17b04 15Nb-95 1.57b04 6.43bO3 3.7EbO3 0.00b00 4.72bO3 4.79b05 1.27b04 16 lib-97 3.42b01 7.291-02 2.63E-02 0.00b00 5.70F02 3.32bO3 2.69b04 17 M0-39 0.00 BOO 1.65bO2 3.23b01 0.00b00 2.65bO2 1.35b05 4.87b04 18 Tc-99: 1.40E-03 2.82E-03 3.72002 0.00b00 3.11b02 8.11bO2 2.03bO3 19 Ra-103 2.02D03 0.00b00 6.79bO2 0.00b00 4.24bO3 5.52b05 1.61b04 20 Ru-106 8.66b04 0.00b00 1.09b04 0.00b00 1.07b05 1.16bO7 1.64b05 21Ag-110s 9.9BbO3 7.22bO3 5.00bO3 0.00b00 1.09b04 3.67b06 3.30b04 22 Sb-124 3.79b04 5.56bO2 1.20b04 1.01bO2 0.00b00 2.65b06 5.91b04 23 Sb-125 5.17b04 4.77bO2 1.09b04 6,23b01 0.00b00 1.64b06 1.47b04 24fe-127: L67b04 6.90bO3 2.07bO3 4.87bO3 3.75b04 1.31b06 2.73b04 25Te-129s 1.41b04 6.09b03 2.23bO3 4.21bO3 3.1Bb04 1.6Eb06 6.90b04 26I-131 3.79b04 4.44b04 1.96b04 1.4BbO7 5.1Eb04 0.00b00 1.06bO3 1 27 I-133 1.32h04 1.92b04 5.60bO3 3.56b06 2.24b04 0.00b00 2.16bO3 28 Cs-134 3.96b05 7.03b05 7.45b04 0.00b00 1.90b05 7.97b04 1.33bO3 29 Ce-136 4.83b04 1.35b05 5.29b04 0.00b00 5 64b04 1.1Eb04 1.43bO3 30 Cs-137 5.49b05 6.12b05 4.55b04 0.00b00 1.72b05 7.13b04 1.33bO3 31 Ba-140 5.60b04 5.60b^1 2.90bO3 0.00b00 1.34b01 1.60h06 3.84b04 32 La-140 5.05bO2 2.00bO2 5.15b01 0.00b00 0.00b00 1.62b05 8.4Bb04 33 Ce-141 2.77b04 1.67b04 1.99bO3 0.00b00 5.25bO3 5.17b05 2.16b04  !

34 Ce-144 3.19b06 1.21b06 1.76b05 0.00b00 5.3Eb05 9.B4b06 1.4Bb05 I

Calculated per DDCM equation 2.3-22 IS5CE3 2-83 I

l EV-1 and 2 ODCM Table 2.3-6

{

R VALUES FOR EIAHR VALLIT SITI (eq meter-tres/yr per uCi/seel Fathvey : Grcund helide Scce Liver T. Body Thyroid IHney Lutg GI-LLI 1 b3 0.00b00 0.00b00 0.00h00 0.00D00 0.00b00 0.00b00 0.00b00 2 F-32 0.00D00 0.00D00 0.00b00 0.00D00 0.00b00 0.00D00 0.00b00 3 Cr-51 4.6Eb06 4.6Eb06 4.6Eb06 4.6Eb06 4.66b06 4.66D06 4.6Eb06 4 Ma-54 1.39b09 1.39bO3 1.39b09 1.39b09 1.39b09 1.39b09 1.39b09 5 Fe-59 2.73bO8 2.73b08 2.73 BOB 2.73bO8 2.73bO8 2.73b08 2.73bO8 6 00-57 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 7 Co-5B 3.79b08 3.79 BOB 3.79bO8 3.79b08 3.79bOS 3.79 BOB 3.79 BOB B Co-60 2.15b10 2.15b10 2.15bl0 2.15b10 2.15bl0 2.15b10 2.15b10 9 Zn-65 7.47bOS 7.47D06 7.47 BOB 7.47 BOB 7.47bO8 7.47bOS 7.47 BOB 10 Rb-86 8.93b06 8.99b06 B.99b06 S.99b06 8.99b06 8.99b06 8.99b06 11 St-89 2.16b04 2.lfb04 2.16b04 2.16b04 2.16b04 2.1Eb04 2.16b04 12 St-90 0.00b00 0.00b00 0.00D00 0.00D00 0.00b00 0.00b00 0.00D00 13 Y-91 1.07D06 1.07b06 1.07b06 1.07b06 1.07b06 1.07b06 1.07b06 14Ir-95 2.45bO8 2.45 BOB 2.45bO8 2.45 BOB 245b06 2.45b08 2.45 BOB 4

15 !ib-95 1.37bO8 1.37b08 1.37 BOB 1.37bO8 1.37 BOB 1.37 BOB 1.37b08 16 lib-97 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 17 Mc-99 4.00b06 4.00b06 4.00b06 4.00b06 4.00b06 4.00b06 4.00b06

!B tc-99a 1.B4b05 1.B4b05 1.84b05 1.84b05 1.84b05 1.84b05 1.84b05 19 h-103 1.0EbOS 1.0BbOB 1.0EbOS 1.06 BOB 1.08bO8 1.08bOS 1.0! BOB 20 h-106 4.22 BOB 4.22 BOB 4.22bOS 4.22bO8 4.22 BOB 4.22 BOB 4.22 BOB 21 Ag-110 3.44b09 3.44b09 3.44b09 3.44b09 3.44b09 3.44b09 3.44b09 22 Sb-124 0.00D00 0.00D00 0.00b00 0.00D00 0.00b00 0.0Cb00 0.00b00 23 Eb-125 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 0.00b00 0.00D00 24 Te-127 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 25te-129s 1.9EbO7 1.98bO7 1.9BbO7 1.9Eb07 1.98bO7 1.98bO7 1.96bO7 26 I-131 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 27 I-133 2.45b06 2.45b06 2.45b06 2.45b06 2.45b06 2.45b06 2.45b06 28 Cs-134 6.8Eb09 6.EEb09 6.BEb09 6.8Cb09 6.86b09 6.BEb09 6.8Eb09 29 Cs-136 1.51 BOB 1.51 BOB 1.51 BOB 1.51bO8 1.51 BOB 1.51D06 1.51 BOB 30 Ce-137 1.03b10 1.03b10 1.03b10 1.03bl0 1.03D10 1.03b10 1.03b10 31Ea-140 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 32 La-140 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 33Ce-141 1.37bO7 1.37bO7 1.37bO7 1.37bO7 1.37bO7 1.37!+07 1.37bO7 24 Ce-144 6.9fbO7 6.9EbO7 6.9EbO7 6.9f bO7 6.9EbO7 6.9CbO7 6.9EbO7 l

Calculated rer 0XM equation 2.3-23 IE!3 2-54

EV-1 and 2 OIQi Table 2.3-7 R VALUES FOR EEAVER VALLU SITE (sq teter tret/yr per uCi/ rec)

Fath e : Vegetation Age Group : Adult helide Sece Liver T. Eody Thyrcid lidney Lung GI-Li,I 1 E-3 0.00b00 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2 P-32 1.40D09 8.74D07 5.43b07 0.00D00 0.00D00 0.00D00 1.5EbOB 3 Cr-51 0.00b00 0.00D00 4.64b04 2.7f D04 1.02b04 6.16b04 1.17bO7 4 h-54 0.00D00 3.13 DOS 5.97bO7 0.00D00 9.31bO7 0.00b00 9.59 BOB 5 Fe-59 1.26bOS 2.96bO8 1.14bOS 0.00D00 0.00D00 8.28bO7 9.SBb08 6 Co-57 0.00b00 1.17bO7 1.95bO7 0.00D00 0.00b00 0.00b00 2.97 BOB 7 Co-58 0.00b00 3.07bO7 6.89bO7 0.00D00 0.00D00 0.00D00 6.23bOS 8 Co-60 0.00b00 1.67 BOB 3.69b06 0.00h00 0.00D00 0.00b00 3.14b09 9 In-65 3.17bO8 1.0lb09 4.56bO8 0.00b00 6.75bOS 0.00b00 6.36 BOB 10 Eb-86 0.00D00 2.19bOS 1.02 BOB 0.00b00 0.00b00 0.00b00 4.33bO7 11 St-69 9.97b09 0.00D00 2.66bO8 0.00b00 0.00b00 0.00b00 1.60b09 12 St-90 6.05b11 0.00b00 1.48b11 0.00D00 0.00b00 0.00b00 1.75b10 13 Y-91 5.11b06 0.00b00 1.37b05 0.00b00 0.00b00 0.00b00 2.B1D09 14Zr-95 1.17b06 3.77b05 2.55b05 0.00 BOO 5.91b05 0.00b00 1.19b09 15 Kb-95 1.42b05 7.92b04 4.26b04 3.00b00 7.83b04 0.00b00 4.i BOB 16 Kb-97 2.16b06 5.46bO7 1.99b07 0.00D00 6.37E-07 0.00b00 2.02E-03 17 Mo-99 0.00b00 6.lf b06 1.17b06 0.00b00 1.39b07 0.00D00 1.43bO7 18 Tc-99: 3.1Cb00 8.77b00 1.12b02 0.0Cb00 1.33bO2 4.30D00 5.19b03 19Eu-103 4.77b06 0.00D00 2.06b06 0.00b00 1.82bO7 0.00D00 5.57bO8 20 su-106 1.93bOS 0.00b00 2.44bO7 0.00 BOO 3.72bOS 0.00D00 1.25b10 21Ag-110s 1.05bO7 9.75b06 5.79b06 0.00b00 1.92bO7 0.00b00 3.9Bb09 22 St-124 1.04b08 1.96b06 4.11bO7 2.51b05 0.00b00 B.07bO7 2.94b09 23Eb-125 1.37 BOB 1.53b06 3.25bO7 1.39b05 0.00b00 1.05bO8 1.50b09 24 Te-127 3.49 BOB 1.25 BOB 4.26bO7 B.92bO7 1.42b09 0.00 BOO 1.17D09 25 Te-129s 2.51bO8 9.35bO7 3.9EbO7 B.64bO7 1.05b09 0.00b00 1.27b09 26 b131 B.08bO7 1.16 BOB 6.62bO7 3.79b10 1.9Eb06 0.00b00 3.05bO7 i

27 b133 2.09b06 3.63b06 1.11b06 5.33b08 6.33b06 0.00D00 3.26b06 28 Cs-134 4.67b09 1.11b10 9.08b09 0.00D00 3.59b09 1.19b09 1.94bO8 29 Ce-136 4.27bO7 1.69 BOB 1.21bO8 0.00b00 9.36bO7 1.29bO7 1.91bO7 l 30 Os-137 6.36b09 B.70b09 5.70D09 0.00b00 2.95b09 9.BibO8 1.6Bb08 l 31 Ea-140 1.29b06 1.61b05 B.42b06 0.00b00 5.49b04 9.24b04 2.65bOS 32 La-140 1.9BbO3 9.97bO2 2.63bO2 0.00b00 0.00b00 0.00b00 7.32E+07 33 Ce-141 1.97b05 1.33b05 1.51b04 0.00b00 6.19b04 0.00b00 5.1CbOS I 34 Ce-144 3.29bO7 !.3BbO7 1.77b06 0.00b00 S.16b06 0.00D00 1.11b10 All m ! ides (except E 3) calculated per UDCM e;;atitt 2.b 26 i F3 :alculated per 0XM e;uation 2.3-29 l IL~TE ' l 2 e5 1

1

EV-1 and 2 DDCH fable 2.3-B g

R VALUES FOR EEAVER VALLET SITE (sqseter-tres/yrperuCi/sec)

Pathway : Vegetation Age Group : Ieen Nuclide Bone Liver I. Ecdy Thyroid lidney Lung GI-LLI IH-3 0.00b00 2.59b03 2.59bO3 2.59bO3 2.59bO3 2.59bO3 2.59bO3 2 P-32 1. Sib 09 9.9BbO7 6.24bO7 0.00b00 0.00b00 0.00b00 1.35bO8 3 Cr-51 0.00D00 0.00b00 6.17b04 3.43b04 1.35b04 8.81b04 1.04bO7 4 Mn-54 0.00b00 4.54 BOB 9.01bO7 0.00b00 1.36 BOB 0.00 BOO 9.32 BOB 5 Fe-59 1.79 BOB 4.19b08 1.62 BOB 0.00b00 0.00b00 1.32bO8 9.90bO8 600-57 0.00b00 1.79bO7 3.00bO7 0.00b00 0.00b00 0.00b00 3.33 BOB 7 Co-58 0.00b00 4.36bO7 1.00bO8 0.00b00 0.00b00 0.00b00 6.0lbOB B Co-60 0.00b00 2.49 BOB 5.60bO8 0.00D00 0.00b00 0.00b00 3.24b09 9 2n-65 4.24 BOB 1.47b09 6.87 BOB 0.00b00 9.42 BOB 0.00D00 6.23 BOB 10 Rb-86 0.00b00 2.74 BOB 1.29 BOB 0.00b00 0.00b00 0.00b00 4.05bO7 11 Sr 89 1.51b10 0.00b00 4.34bO8 0.00b00 0.00D00 0.00 BOO 1.80b09 12 St-90 7.51b11 0.00b00 1.85b11 0.00b00 0.00b00 0.00b00 2.11b10 13 E 91 7.84b06 0.00D00 2.10b05 0.00 BOO 0.00b00 0.00b00 3.21b09 14 b -95 1.72b06 5.43b05 3.74b05 0.00b00 7.96b05 0.00b00 1.25b09 (

15 Nb-95 1.92b05 1.07b05 5.87b04 0.00b00 1.03b05 0.00b00 4.56bO8 16 Nb-97 2.00b06 4.97E-07 1.81E-07 0.00b00 5.81E-07 0.00b00 1.15b02 17 Mo-99 0.00b00 5.65b06 1.0Bb06 0.00b00 1.29bO7 0.00b00 1.0lbO7 18 Tc-99: 2.74b00 7.64b00 9.90b01 0.00b00 1.14bO2 4.24b00 5.02bO3 19 Hu-103 6.82b06 0.00b00 2.92b06 0.00b00 2.41bO7 0.00b00 5.70 BOB 20 Hu-106 2.38 BOB 0.00b00 3.90bO7 0.00b00 5.97 BOB 0.00b00 1.4Eb10 21 Ag-110 IXe07 1.43bO7 8.72b06 0.00b00 2.74bO7 0.00b00 4.03b09 22Sb-124 1.54 BOB 2.8(b06 6.02bO7 3.50b05 0.00b00 1.35 BOB 3.11b09 23 Sb-125 2.14 BOB 2.34b06 5.0lbO7 2.05b05 0.00b00 1.BBbOB 1.67b09 24Te-127: 5.52bO8 1.96 BOB 6.56bO7 1.31 BOB 2.24b09 0.00b00 1.37b09 25 fe-129: 3.62bO8 1.a4 BOB 5.73bO7 1.17 BOB 1.51b09 0.00b00 1.36b09 26I-131 7.69b07 1.08 BOB 5.7BbO7 3.14b10 1.65bOS 0.00b00 2.13bO7 27 I-133 1.9(b06 3.29b06 1.00b06 4.59b08 5.77b06 0.00b00 2.49b06 28 Cs-134 7.10b09 1.67b10 7.75b09 0.00b00 5.31b09 2.03b09 2.0BbO8 29 Cs-136 4.3Bb07 1.72bO8 1.16b08 0.00b00 9.37bO7 1.45bO7 1.39bO7 ,

30 Cs-137 1.01b10 1.35b10 4.69b09 0.00b00 4.59b09 1.78D09 1.92bO8 31 Ba-140 1.3EDOS 1.69b05 8.90b06 0.00b00 5.74b04 1.14b05 2.13DOB 32 La-140 1.81bO3 8.BEbO2 2.36bO2 0.00D00 0.00b00 0.00b00 5.10bO7 33Ce-141 2.83b05 1.BSb05 2.17b04 0.00b00 B.90b04 0.00b00 5.41 BOB .

34 Ce-144 5.27bO7 2.1BbO7 2.83b05 0.00b00 1.30bO7 0.00D00 1.33D10 I All cu:lides (except H-3) calculated per ODCM equation 2.3-26 li-3 calculated per ODr'M equation 2.3-29 IEEE 3 2-86 l

BV-1 and 2 ODCM Table 2.3-9 1

R VALUES FOR BEAVIR VALLET SI7E 1 (sqteter-stes/yrperuCi/sec)

Pathway : Vegetation Age Group : Child Nuclide Bone Liver T. Body Thyroid Eidney Lurg G1-LLI 1 b3 0.00b00 4.0lbO3 4.0lbO3 4.0lbO3 4.0lbO3 4.0lbO3 4.01bO3 2P-32 3.37b09 1.5BbO8 1.30bO8 0.00D00 0.00b00 0.00D00 9.32bO7 3Cr-51 0.00b00 0.00b00 1.17b05 6.50D04 1.7Eb04 1.19b05 6.21b06 4Mn-54 0.00b00 6.65bOS 1.77bO8 0.00b00 1.86bO8 0.00b00 5.5BD08 5 Fe-59 3.98bO8 6.43 BOB 3.20bO8 0.00D00 0.00b00 1.87b08 6.70 BOB 600-57 0.00b00 2.99h07 6.04bO7 0.00b00 0.00b00 0.00b00 2.45 BOB 7 Co-58 0.00b00 6.44bO7 1.97bO8 0.00b00 0.00b00 0.00b00 3.76bO8 8 Co-60 0.00b00 3.76bO8 1.12b09 0.00b00 0.00h00 0.00b00 2.10b09 9In-65 8.13bO8 2.17b09 1.35b09 0.00D00 1.36b09 0.00b00 3.80 BOB 10 Rb-86 0.00b00 4.52 BOB 2.75 BOB 0.00D00 0.00D00 0.00b00 2.91bO7 11 Sr-89 3.60b10 0.00D00 1.03b09 0.00b00 0.00b00 0.00b00 1.39D09 12Sr-90 1.24b12 0.00b00 3.15b11 0.00b00 0.00b00 0.00b00 1.67b10 13 091 1.66bO7 0.00D00 4.99b05 0.00 BOO 0.00b00 0.00b00 2.48b09 14 Zr-95 3.86b06 8.48b05 7.55b05 0.00 BOO 1.21b06 0.00D00 8.85bO8 15Nb-95 4.11b05 1.60b05 1.14b05 0.00 BOO 1.50b05 0.00b00 2.96bO8 16 Nb-97 3.65E-06 6.59E-07 3.0Eb07 0.00b00 7.31007 0.00E+00 2.03001 17Mo-99 0.00b00 7.71b06 1.91b06 0.00b00 1.65bO7 0.00b00 6.36b06 15Te-99: 4.71b00 9.24b00 1.53b02 0.00D00 1.34bO2 4.69b00 5.26bO3 19Eu-103 1.53bO7 0.00000 5.90b06 0.00D00 3.86bO7 0.00b00 3.97bO8 20 Ru-106 7.45bOS 0.00b00 9.30bO7 0.00 BOO 1.01b09 0.00b00 1.16b10 21Ag-110s 3.21bO7 2.17bO7 1.73b07 0.00 BOO 4.04bO7 0.00b00 2.56b09 22 Sb-124 3.52bO8 4.57b06 1.23b08 7.77b05 0.00b00 1.95 BOB 2.20b09 23Sb-125 4.99b08 3.85b06 1.05bO8 4.63b05 0.00D00 2.78 BOB 1.19b09 24Te-127 1.32b09 3.56bO8 1.57 BOB 3.16bO8 3.77b09 0.00b00 1.07b09 25Te-129: 8.41bO8 2.35bO8 1.31 BOB 2.71bOS 2.47b09 0.00 BOO 1.03E+09 i

tSI-131 1.43 BOB 1.44 BOB 8.17bO7 4.76b10 2.36bO8 0.00b00 1.28bO7 27I-133 3.53b06 4.37b06 1.65b06 8.12bO8 7.2Sb06 0.00b00 1.76b06 28Cs-134 1.60b10 2.63D10 5.55b09 0.00D00 8.15b09 2.93b09 1.42 BOB

, 29Cs-136 8.24bO7 2.27 BOB 1.47 BOB 0.00D00 1.21bO8 1.80bO7 7.96b06 30Ce-137 2.39b10 2.29b10 3.38b09 0.00b00 7.46b09 2.68b09 1.43bO8 l 31 Ba-140 2.77b08 2.42bO7 1.62bO7 0.00b00 7.59b04 1.45b05 1.40 BOB 32 La-140 3.25bO3 1.13bO3 3.83bO2 0.00b00 0.00b00 0.00b00 3.16bO7 33Ce-141 6.56b05 3.27b05 4.26b05 0.00b00 1.43b05 0.00b00 4.08bO8 34 Ce-144 1.27bO8 3.9BbO7 6.7Eb06 0.00b00 2.21bO7 0.00b00 1.04b10 F All nuclides (enept b3) calculsted per CDOM equation 2.3-26 b3 calculated nr OXM epation 2.3-29 ,

13i"! 3 l 2-87 l

37-1 a:d 2 ODCM l Table 2.2-10 R VALUIS FOR EIAVER VALLD SITE  !

(eqmeter-8,res/yrperUCi/tec)

Fathway : Meat Age Gr up : Adult helide Bc:e Liver T. Body Thyroid tid:ey Lung GI-LLI 1 H-3 0.00b00 3.25bO2 3.25bO2 3.25bO2 3.25bO2 3.25bO2 3.25E+02 2P-32 3.95b09 2.46 BOB 1.53bO8 0.00b00 0.00b00 0.00b00 4.44bOS 3 Cr-51 0.00D00 0.00b00 5.BEbO3 3.50bO3 1.29bO3 7.78bO3 1.47b06 4Mn-54 0.00D00 6.49b06 1.24b06 0.00b00 1.93b06 0.00D00 1.99bO7 5 fe-59 2.14 BOB 5.04bOS 1.93b08 0.00b00 0.00D00 1.41bOS 1.65b09 6 C0-57 0.00b00 4.01b06 6.66b06 0.00b00 0.00b00 0.00b00 1.02bO8 7 00-5S 0.00b00 1.42bO7 3.1BbO7 0.00D00 0.00D00 0.00D00 2.87 BOB B Co-60 0.00b00 5.12bO7 1.13bOS 0.00D00 0.00b00 0.00b00 9.61bO8 9 2n-65 2.54bO8 8.09b08 3.66 BOB 0.00b00 5.41b08 0.00b00 5.10 BOB 10 Eb-86 0.00b00 4.11bOS 1.92bOS 0.00 BOO 0.00b00 0.00D00 8.11bO7 11 Er-89 2.41 BOB 0.00b00 6.S2b06 0.00b00 0.00b00 0.00b00 3.87bO7 12 St-90 8.41b09 0.00b00 2.06b09 0.00b00 0.00b00 0.00b00 2.43b08 13T-91 B.94b05 0.00D00 2.39b04 0.00b00 0.00b00 0.00b00 4.92bO8 14 2r-95 1.47b06 4.71b05 3.19b05 0.00b00 7.39b05 0.00b00 1.49b09 15 Nb-95 1.89b06 1.05b06 5.64b05 0.00D00 1.04D06 0.00b00 6.37b09 16 Nb-97 ********************************* 0.00 b 00 *********** 0.00b 00 ***********

17 S-99 0.00b00 6.51b04 1.62b04 0.00000 1.93b05 0.00b00 1.97b05 18 Tc-99: 3.83b21 1.0BI-20 1.3EE-19 0.00D00 1.64E-19 5.30E-21 6.40b16 19 h-103 B.57bO7 0.00D00 3.69bO7 0.00b00 3.27b08 0.00D00 1.00bl0 20 h -106 1.97b09 0.00b00 2.49bOS 0.00b00 3.B0D09 0.00b00 1.27b11 21Ag-110 4.77b06 4.41E+06 2.62b06 0.00b00 8.67b06 0.00b00 1.80D09 22 Sb-124 0.00D00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 24 Te-127s B.3Eb08 3.00 BOB 1.02 BOB 2.14 BOB 3.40b09 0.00b00 2. Bib 09 25te-129: 9.33 BOB 3.4BDOS 1.4BbO8 3.21b08 3.89b09 0.00b00 4.70b09 26I-131 9.13b06 1.31bO7 7.4BD06 4.2Bb09 2.24bO7 0.00b00 3.45b06 27I-133 3.12E-01 5.42E-01 1.65b01 7.95b01 9.46I-01 0.00b00 4.87b01 28 Cs-134 4.53 BOB 1.0Bb09 8.81 BOB 0.00b00 3.49bO8 1.16bO8 1.89007 29 Cs-136 1.02bO7 4.04bO7 2.91bO7 0.00b00 2.25bO7 3.0Ebo6 4.59b06 30 Cs-137 5.90D08 B.06D08 5.25b08 0.00D00 2.74b08 9.10bO7 1.56bO7 31 Ea-140 2.44bO7 3.0Eb04 1.60b06 0.00b00 1.04b04 1.75b04 5.02bO7 32 La-140 3.16002 1.59002 4.21E-03 0.00b00 0.00b00 0.00b00 1.17bO3 33 Ce-141 1.16D04 7.83bO3 8.B!bO2 0.00D00 3.64bO3 0.00D00 2.99b07 34 Ce-144 1.03b06 4.32b05 5.55b04 0.00b00 2.56b05 0.00b00 3.50 BOB All tuclides (except b3) calculated ;er 00CM equation 2.3-25 E-3 calculated ;>er 00CM e;:atite 2.3-30 ISE"! :

2-BB

EV-1 and 2 ODCM Table 2.3-11 E VALUES FOR EEAVER VALLEY SITE l

(sq teter-tres/yr per UCi/ rec)

Pattvay : Meat Age Grcup : Iee:

Nuclide Ecce Liver T. Body Thyroid Eidney Lung GI-LLI I E-3 0.00E+00 1.94E+02 1.94E+02 1.94E+02 1.942+02 1.94E+02 1.94E+02 2 P-32 3.34E+09 2.07E+08 1.29E+0B 0.00E+00 0.00E+00 0.00E+00 2.80E+08 3 Cr-51 0.00E+00 0.00E+00 4.69E+03 2.60E+03 1.03E+03 6.69E+03 7.68E+05 4 Mn-54 0.00E+00 4.95E+06 9.81E+05 0.00E+00 1.4EE+06 0.00E+00 1.01E+07 5 Fe-59 1.71E+08 4.00E+0B 1.54E+0B 0.00E+00 0.00E+00 1.26E+0B 9.45E+0S 6 Co-57 0.00E+00 3.22E+06 5.40E+06 0.00E+00 0.00E+00 0.00E+00 6.01E+07 7 Co-58 0.00E+00 1.09E+07 2.52E+07 0.00E+00 0.00!+00 0.00E+00 1.51E+0S 8 Co-60 0.00E+00 3.97E+07 8.95E+07 0.00E+00 0.00E+00 0.00E+00 5.17E+08 9Zn-65 1.79E+08 6.21E+0B 2.90E+0B 0.00E+00 3.97E+0B 0.00E+00 2.63E+0B 10 Eb-86 0.00E+00 3.43E+0B 1.61E+0B 0.00E+00 0.00E+00 0.00!+00 5.0SE+07 11 St-89 2.03E+08 0.00E+00 5.83E+06 0.00E+00 0.00E+00 0.00E+00 2.42E+07 12 3r-90 5.44E+09 0.00E+00 1.34E+09 0.00E+00 0.00E400 0.00E+00 1.53E+08 13Y-91 7.53E+05 0.00E+00 2.02E+04 0.00E+00 0.00E+00 0.00!+00 3.09E+08 14 Zr-95 1.18E+06 3.71E+05 2.55E+05 0.00E+00 5.45E+05 0.00E+00 8.56E+08 15 Nb-95 1.47E+06 B.17E+05 4.50E+05 0.00E+00 7.92E+05 0.00E+00 3.49E+09 16 Eb-97 ********************************* 0.00E+00 *********** 0.00E+00 ***********

17 M -99 0.00E+00 7.03E+04 1.34E+04 0.00E+00 1.61E+05 0.00!+00 1.26E+05 IS ic-99: 3.04E-21 8.4BE-21 1.10E-19 0.00Et00 1.26E-19 4.71E-21 5.57E-18 19 Ru-103 6.9EE+07 0.00E+00 2.95E+07 0.00E+00 2.46E+08 0.00E+00 5.83E+09 20 Eu-106 1.2fI+09 0.00E+00 2.09E+08 0.00E+00 3.19E+09 0.00E+00 7.94E+10 21 Ag-110e 3.61E+06 3.42E+06 2.0BE+06 0.00E+00 6.52E+06 0.00E+00 9.60E+08 22 Eb-124 0.00E+00 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 23Sb-125 0.00!+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 24Te-127 7.07E+0B 2.51E+0B B.41E+07 1.6EE+08 2.87E+09 0.00E+00 1.76E+09 25 Te-129s 7.82E+08 2.90E+08 1.24E+0S 2.52E+08 3.27E+09 0.00E+00 2.93E+09 26I-131 7.59E+0B 1.06E+07 5.71E+0S 3.10E+c9 1.83E+07 0.00!+00 2.10E+06 27 l-133 2.61!-01 4.42E-01 1.35E-01 6.17E+01 7.75E-01 0.00E+00 3.34E-01 28 Cs-134 3.60E+0B 8.4fE+0B 3.93E+08 0.00E+00 2.69E+08 1.03E+0S 1.05E+07 29 Cs-136 7.9BE+06 3.14E+07 2.11E+07 0.00E400 1.7]I+07 2.69E+06 2.53E+06 30 Cs-137 4.90E+0S 6.51E+0S 2.27!+0S 0.00E+00 2.22E+08 6.61E+07 9.27E+06 31 Ea-140 2.02E+07 2.47E+04 1.3CE+06 0.0CE+00 8.3EE+03 1.66E+04 3.11E+07 32 La-140 2.60E-02 1.2SE-02 3.CI-03 0.00E+00 0.00E+00 0.00E+00 7.33E+02 33Ce-141 9.72E+03 6.49E+03 7.46E+02 0.00E+00 3.06E+03 0.00E+00 1.B6E+07 1 34 Ce-144 8.72E+05 3.61E+05 4.6fE+04 0.00E+00 2.15E+05 0.00E+00 2.19E+0B A!! tulides iene;t 03) :alculated per ODCM e;ati:n 2.3-25 E 3 :alculated per ODCM e;utien 2.3-30 IEEE :

2-89

El-1 and 2 O XM Table 2.3-12 R VALUES FOR EEA H R VALLU Sl!!

(sq ueter-aretlyr per uCliee:)

Fathway : Meat Age Group : Child Nuclide Bone Liver T. Body Thyroid tidney Lung GI-LL1 1 F3 0.00b00 2.34bO2 2.34bO2 2.34bO2 2.34bO2 2.34bO2 2.34bO2 2 P-32 6.29b09 2.94 BOB 2.43 BOB 0.00b00 0.00bd0 0.00b00 1.74 BOB 3 Cr-51 0.00b00 0.00b00 7.31bO3 4.06bOS .11bO3 7.41bO3 3.BBb05 4 Mn-54 0.00b00 5.6Eb06 1.51b06 0.00b"> 1.59b06 0.00b00 4.75b06 5 Fe-59 3.04 BOB 4.91bO8 2.45bO8 0.00bou 0.00b00 1.42 BOB 5.12 BOB 6 Co-57 0.00b00 4.21b06 B.52b06 0.00b00 0.00b00 0.00D00 3.45bO7 7 Co-58 0.00b00 1.2Eb07 3.91bO7 0.00b00 0.00b00 0.00b00 7.45bO7 8 Co-60 0.00b00 4.72bO7 1.39 BOB 0.00b00 0.00b00 0.00b00 2.61bO8 9 2n-65 2.6BbOB 7.15 BOB 4.44b08 0.00D00 4.50bO8 0.00b00 1.25 BOB 10 Eb-S6 0.00b00 4.87bO8 2.99b08 0.00b00 0.00b00 0.00D00 3.13b07 11 St-89 3.85bO8 0.00D00 1.10bO7 0.00b00 0.00b00 0.00b00 1.49bO7 12 St-90 7.03D09 0.00b00 1.7Eb09 0.00b00 0.00b00 0.00b00 9.47bO7 13 F 91 1.42b06 0.00b00 3.81b04 0.00D00 0.00b00 0.00 BOO 1.90 BOB 14 Zr-95 2.09b06 4.59b05 4.09b05 0.00b00 6.57b05 0.00b00 4.79bO8 15 Nb-95 2.54b06 9.90D05 7.07b05 0.00b00 9.30b05 0.00D00 1.83b09 16 Kb-97 ***** s************************** 0. 00 D00 * * * * * * * * * *

• 0. 00 b00 * * * * * * * * * *

• 17 Mo-99 0.00b00 9.79b04 2.42b04 0.00b00 2.09b05 0.00b00 8.09b04 18 fc-99: 5.33-21 1.05b20 1.73bl9 0.00b00 1.52bl9 5.31b21 5.95b18 19 Ru-103 1.26bO8 0.00b00 4.55bO7 0.00 BOO 3.1BbOB 0.00b00 3.26b09 20 Ru-106 3.12b09 0.00b00 3.89 BOB 0.00b00 4.21b09 0.00D00 4.85b10 1

21Ag-110s 5.99b06 4.04b06 3.23b06 0.00b00 7.53b06 0.00b00 4.81 BOB l 22 Sb-124 0.00D00 0.00D00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 l 23Sb-125 0.00D00 0.00D00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 l 24Te-127a 1.33b09 3.59bOS 1.5Sb08 3.19b0B 3.80D09 0.00b00 1.0Bb09 25 Te-129s 1.47b09 4.11b06 2.29 BOB 4.75 BOB 4.33b09 0.00D00 1.B0b09 26 1-131 1.41bO7 1.42bO7 8.04b06 4.6Eb09 2.32bO7 0.00b00 1.26b06 27 D133 4.64E01 5.99E-01 2.27E-01 1.11bO2 9.9BF01 0.00b00 2.411-01 28 Cs-134 6.35bO8 1.04b09 2.20bOS 0.00b00 3.23 BOB 1.16bOS 5.62b06 29 Cs-136 1.3SbO7 3.78b07 2.45bO7 0.00D00 2.0lbO7 3.00b06 1.33b06 30 Ce-137 9.02bOS 8.63 BOB 1.27bOS 0.00b00 2.BibOB 1.0lbO8 5.40b06 31 Ea-140 3.72bO7 3.26b06 2.17b06 0.00b00 1.06b04 1.94b04 1.BibO7 32 La-140 4.7Eb02 1.661-02 5.61003 0.00b00 0.00b00 0.00b00 4.63bO2 33 Ce-141 1.83b04 9.13bO3 1.3Eb04 0.00b00 4.00bO3 0.00b00 1.14bO7 34 Ce-144 1.64b06 5.15b05 8.77b04 0.00D00 2.E5b05 0.00D00 1.34bO8 All nuclides fex:ept H-3) calculated per O X M equatica 2.3-25 4 E-3 calculated per O MM equatien 2.3-30 El^

2-90

EV-1and2ODCM l

Table 2.3-13 E VALUES FOR EEAVER VAllII SITE (sqseter-sten /yrperUC1/sec)

Pathway : Ccv Milk AgeGroup: Adult Noelide Eene Liver T. Body Thyroid lihey Lung GI-LLI 1 b3 0.00b00 7.63bO2 7.63bM 7.63b02 7.63bO2 7.63bO2 7.63bO2 2 P-32 1.45b10 9.0lbOB 5.60bO8 0.00b00 0.00b00 0.00D00 1.63b09 3 Cr-51 0.00 BOO 0.00b00 2.38b04 1.42b04 5.24bO3 3.15b04 5.98b06 4 Mn-54 0.00b00 5.95b06 1.13D06 0.00b00 1.77D06 0.00D00 1.82bO7 5 Fe-59 2.40bO7 5.63bO7 2.16bO7 0.00D00 0.00b00 1.57bO7 1.BEb06 6 Co-57 0.00b00 9.10!+05 1.51b06 0.00b00 0.00h00 0.00b00 2.31bO7 7Co-58 0.00D00 3.67b06 8.22b06 0.00D00 0.00b00 0.00h00 7.43bO7 8 Co-60 0.00b00 1.12bO7 2.46bO7 0.00b00 0.00b00 0.00 BOO 2.10bO8 9 2n-65 9.80 BOB 3.12b09 1.41b09 0.00b00 2.09b09 0.00b00 1.96b09 10 Rb-86 0.00b00 2.19b09 1.02b09 0.00D00 0.00D00 0.00D00 4.32 BOB 11Sr-89 1.16b09 0.00b00 3.33bO7 0.00 BOO 0.00 BOO 0.00D00 1.86 BOB 12 Sr-90 3.16b10 0.00D00 7.76b09 0.00b00 0.00D00 0.00D00 9.1(b05 13 Y-91 6.78bO3 0.00b00 1.81bO2 0.00D00 0.00b00 0.00D00 3.73b06 142r-95 7.40bO2 2.37bO2 1.61bO2 0.00h00 3.72bO2 0.00 BOO 7.52b05 15 Nb-95 6.77b04 3.77b04 2.03b04 0.00b00 3.72b04 0.00b00 2.29 BOB 16 Nb-97 2.81b12 7.11013 2.60E-13 0.00b00 8.30E-13 0.00b00 2.62E-09 17 Mo-99 0.00b00 2.11bO7 4.01b06 0.00b00 4.77bO7 0.00b00 4.88bO7 18 Te-99: 2.83b00 7.99b00 1.02bO2 0.0Cb00 1.21bO2 3.91b00 4.73bO3 19 Ru-103 8.29bO2 0.00b00 3.57bO2 0.00b00 3.16bO3 0.00b00 9.66b04 20 in-106 1.43b04 0.00b00 1.81bO3 0.00b00 2.77b04 0.00b00 9.27b05 21 A;-110s 4.16bO7 3.84bO7 2.28b07 0.00b00 7.56bO7 0.00D00 1.57b10 22 Sb-124 0.00 BOO 0.00b00 0.00b00 0.00b00 0.00 BOO 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 0.00b00 0.00b00 24Te-127 3.44bO7 1.23bO7 4.19b06 8.79b06 1.40 BOB 0.00b00 1.15bO8 25 Te-129: 4.95bO7 1.85bO7 7.84b06 1.70bO7 2.07 BOB 0.00D00 2.49b06 26l-131 2.52 BOB 3.60 BOB 2.06bO8 1.1Bb11 6.17 BOB 0.00b00 9.50bO7 27 F133 3.29b06 5.72b06 1.75b06 8.41bO8 9.99b06 0.00D00 5.1(b06 28Cs-134 3.89b09 9.27b09 7.55b09 0.00b00 3.00D09 9.96 BOB 1.62 BOB 29 Cs-136 2.23D06 8.82 BOB 6.35bOS 0.00bF 4.91b05 6.73bO7 1.00 BOB 30 Cs-137 4.99b09 6.62b09 4.47b09 0.00b00 2.32b09 7.70b08 1.32b08 31 Fa-140 2.28bO7 2.B7b04 1.49b06 0.00D00 9.74bO3 1.64b04 4.70bO7 32 La-140 3.84b00 1.93b00 5.11001 0.00b00 0.00b00 0.00D00 1.42b05 33 Ce-141 3.99bO3 2.70bO3 3.06bO2 0.00b00 1.25bO3 0.00D00 1.03b07 1 34 Ce-144 2.54b05 1.06b05 1.36b04 0.00b00 6.29b04 0.00D00 8.5BbO7 All nuclides (except b3) esiculated per ODCE equtien 2.3-24 il-3 calculated per ODCM equatico 2.3-2B IEEE 3 2-91

EV-1 acd 2 ODCM Table 2.3-14 q

E VALUIS FOR EEAVIR VALLEY SITI (egmeter-eres/yrperuC1/sec)

Pathway : Ccv Milk ige Group : Teen Nuclide Bone Liver T. Body Thyroid lidney Lung Gl-LLI 1 li-3 0.00b00 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 2P-32 2.67b10 1.66b09 1.04b09 0.00b00 0.00b00 0.00D00 2.25b09

! 3Cr-51 0.00D00 0.00b00 4.15b04 2.31b04 9.10bO3 5.93b04 6.97b06 4 Mn-54 0.00b00 9.91b06 1.96b06 0.00b00 2.95b06 0.00D00 2.03bO7 5 fe-59 4.1Bb07 9.76bO7 3.77bO7 0.00 BOO 0.00D00 3.08bO7 2.31 BOB 6 Co-57 0.00b00 1.60b06 2.68b06 0.00b00 0.00b00 0.00000 2.tebO7 7Co-58 0.00 BOO 6.17bO3 1.42bO7 0.00b00 0.00b00 0.00b00 8.51bO7

, 8 Co-60 0.00b00 1.89bO7 4.26bO7 0.00b00 0.00D00 0.00000 2.46bO8 l 92n-65 1.51b09 5.23b09 2.44b09 0.00b00 3.34b09 0.00b00 2.21b09 10 Rb-86 0.00b00 3.99b09 1.87b09 0.00D00 0.00b00 0.00b00 5.91 BOB 11St-89 2.14b09 0.00D00 6.12bO7 0.00000 0.00b00 0.00b00 2.55 BOB 12 St-90 4.47b10 0.00b00 1.10bl0 0.00b00 0.00b00 0.00b00 1.25b09 13 T-91 1.25b04 0.00b00 3.35bO2 0.00b00 0.00b00 0.00 BOO 5.11b06 14 Zr-95 1.29bO3 4.08bO2 2.81bO2 0.00b00 6.00bO2 0.00b00 9.42b05 i 15 !ib-95 1.16b05 6.41b04 3.53b04 0.00b00 6.21b04 0.00b00 2.74bO8 16Nb-97 5.13b12 1.27I-12 4.65E-13 0.00b00 1.49012 0.00b00 3.04b08 17 Mc-99 0.00b00 3.80bO7 7.25b06 0.00b00 8.70bO7 0.00b00 6.81bO7 18 te-99: 4.90b00 1.37b01 1.77bO2 0.00b00 2.04bO2 7.59b00 8.9EbO3 19 Ra-103 1.47bO3 0.00D00 6.30bO2 0.00b00 5.20bO3 0.00b00 1.23b05 20 Eu-106 2.03b04 0.00D00 3.32bO3 0.00000 5.05b04 0.00D00 1.26b06 21 Ag-110s 6.87bO7 6.50b07 3.95bO7 0.00D00 1.24bO8 0.00b00 1.83bl0 22 Eb-124 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 0.00b00 23Sb-125 0.00D00 0.00D00 0.00b00 0.00D00 0.00b00 0.00b00 0.00D00 24 Te-127: 6.34bO7 2.25bO7 7.54b06 1.51bO7 2.57b06 0.00D00 1.5BbO8 25 te-129s 9.06bO7 3.36bO7 1.43bO7 2.92bO7 3.79b08 0.00b00 3.40 BOB 261-131 4.57 BOB 6.39b08 3.43 BOB 1.87b!1 1.10b09 0.00b00 1.26 BOB 27I-133 6.0lb06 1.02bO7 3.11b06 1.42b09 1.79bO7 0.00 BOO 7.71 BOB 28 Cs-134 6.76b09 1.59bl0 7.38b09 0.00D00 5.06b09 1.93b09 1.98 BOB 29Ce-136 3.80 BOB 1.50b09 1.0lb09 0.00D00 8.15bO8 1.2BbOB 1.20D08 30 Cs-137 9.05b09 1.20b10 4.19b09 0.00b00 4.10D09 1.59b09 1.71 BOB 31Ba-140 4.12bO7 5.0!b04 2.65b06 0.0.b00 1.71b04 3.39b04 6.35bO7 32 La-140 6.89b00 3.39b00 9.01001 0.00D00 0.00b00 0.00D00 1.94b05 33 Ce-141 7.32bO3 4.69bO3 5.62bO2 0.00b00 2.30bO3 0.00D00 1.40bO7 l

34Ce-144 4.67b05 1.93b05 2.51b04 0.00b00 1.15b05 0.00b00 1.17 BOB '

l All nuclides (ex:ept l'3) ca nulated per ODCM equation 2.3-24 il-3 calculated per CDCM equation 2.3-28

!$K! 3 2-92

i l

I EV-1and2ODCH  :

1 7able2.3-15 ,

RVALUESFORBEAVIIVALLEYSITE i l

[sqseter-stes/yrperuCi/sec) -l Patbvay:CesMilk f Age Group : Child j i

Nuclide Bone Lher T. Body Thyroid tidney Lung GI-LLI- l t

1H-3 0.00b00 1.57bO3 1.57bO3 1.57bO3 1.57b03 1.57bO3 1.57bO3 j 2P-32 6.59b10 3.09b09 2.54b09 0.00b00 0.00b00 0.00D00: 1.82b09 1 3 Cr-51 0.00b00 0.00b00 8.46D04 4.70D04 1.28b 04 - 8.58b 04 . 4.49 b06 j 4Mc-54 0.00D00 1.4Bb07 3.95b06 0.00D00 4.16b06 0.00b00 1.24bO7  :

5 Fe-59 9.70bO7 1.57 BOB 7.82bO7 0.00b00 0.00b00 4.55bO7 1.63bO8 j 600-57 0.00b00 2.73b06 5.52b06 0.00D00 0.00D00 0.00b00 2.24bO7

• 7Co-58 0.00D00 9.43b06 2.89bO7 0.00000 0.00b00 0.00b00 5.50bO7 0.00b00 2.94bO7 8.67bO7 0.00b00 0.00b00 0.00b 00 - f.63 b08 8 Co-60 'i 9 Zn-65 2.95b09 7.87b09 4.89b09 0.00D00 4.96b09 0.00 BOO - 1.38b09 ,

10 Eb-86 0.00 BOO 7.40b09 4.55b09 0.00b00 0.00b00 0.00b00 4.76bO8 i i

11St-89 5.29b09 0.00b00 1.51 BOB 0.00b00 0.000 00 ~0.00 D 00 2.05D08  !

12Sr-90 7.55b!0 0.00b00 1.91b10 0.00 BOO 0.00 BOO 0.00b00 1.02b09 l 13 Y-91 3.08b04 0.00b00 8.24bO2 0.00b00 0.00b00 0.00b00 4.11b06 l l 14Zr-95 3.00bO3 6.60bO2 5.88bO2 0.00b00 9.45bO2 0.00b00 6.89b05  ;

15 Nb-95 2.61b05 1.02b05 7.26b04 0.00b00 9.54b04 0.00b00 1.68bO8 j 16Nb-97 1.25b11 2.25b12 1.05b12 0.00D00 2.50b12 0.00 b00- 6.94E-07 17No-99 0.00b00 6.92bO7 1.71bO7 0.00D00 1.48bO8 0.00b00 5.72b07 18Tc-99: 1.12b01 2.20b01 3.65bO2 0.00b00 3.20bO2 1.12b01 1.25b04 19Ru-105 3.49bO3 0.00b00 1.34bO3 0.00b00 8.7BbO3 0.00b00 9.01b04 '

20Ru-106 .6.49b04 0.00b00 8.10bO3 0.00b 00 8.76b04 0.00 b 00 1.0lb06 '!

t 21Ag-110s 1.49bO8 1.0lbOB 8.05bO7 0.00b00 1.87bO8 0.00b00 1.20b10 22 Sb-124 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00 BOO 23 Sb-125 0.00000 0.00b00 0.00b00 0.00b 00 0.00b00 0.00 b 00- 0.00 b 00 -I 24fe-127s 1.56 BOB 4.21bO7 1.86bO7 3 7(bO7 4.46 bO8 :0.00b 00 1.27bO8 )

25fe-129s 2.23b08 6.24bO7 3.47bO7 7.20bO7 6.56 b O8 0.00b 00 2.72bO8 4

261-131- 1.11b09 1.11b09 8.33 BOB 3.68b11 1.83b09 0.00D00' 9.92bO7 27 b133 1.46bO7 1.81bO7 6.83b06 3.36b09 3.0lbO7 0.00b00 ' 7.28b06 I 28 Cs-134 1.56b10 2.56b10 5.40b09 0.00b00 7.93b09 2.85b09 1.38 BOB 29Cs-136 8.5BbOB 2.36b09 1.53b09 0.00b00 1.26b09 1.87 BOB 8.29h07- '

30Cs-137 2.18b10 2.09b10 3.0Bb09 0.00h00 6.80 D09 -2.45 b 09 1.31bO8 -l 4

{

31 Ba-140 9.94bO7 8.71b06 5.80b06 0.00b00 2.84b04. 5.19b04 5.04bO7 j 32 La-140 1.65b01 5.77b00 1.94b00 0.00D00 0.00b00 0.00 BOO 1.61b05.  !

1.80b04 8.99bO3 '

33Ce-141 1.34b04 0.00b00 3.94bO3 0.00b00 - 1.12bO7 -

34 Ce-144 1.15b06 3.61b05 6.15b04 0.00b00 2.00b05 0.00b00 9.41bO7 I  !

All nuclides (except b3) calculated per ODCM egnation 2.3-24 :i b3calculatedperODCMequation2.3-28 j 1530ES 2-93 i t

1

EV-1 and 2 ODCM Table 2.3-16 E VALUES FOR BEA HR VALLEY SI7E I (sqseter-trea/yrpersci/sec) i Pattvar : Cow Milk Age Group : infant helide Bone Liver T. Body Thyroid tidney Lung GI-LLI 1 F3 0.00b00 2.38bO3 2.38bO3 2.38bO3 2.38bO3 2.3BbO3 2.38D03 2P-32 1.36bil 7.99D09 5.27b09 0.00b00 0.00b00 0.00b00 1.84b09 3Cr-51 0.00b00 0.00b00 1.34b05 8.75b04 1.91b04 1.70D05 3.91b06 4 Mn-54 0.00b00 2.76bO7 6.25b06 0.00b00 6.11b06 0.00b00 1.01bO7 5 Fe-59 1.81 BOB 3.16bO8 1.25b08 0.00b00 0.00b00 9.35bO7 1.51 BOB 6 00-57 0.00b00 6.36b06 1.03bO7 0.00b00 0.00b00 0.00b00 2.17bO7 7 Co-58 0.00 BOO 1.89bO7 4.70bO7 0.00000 0.00b00 0.00b00 4.70bO7 8 Co-60 0.00D00 6.00bO7 1.42bOS 0.00 BOO 0.00b00 0.00b00 1.43bO8 9 In-65 3.97b09 1.36b!0 6.27b09 0.00D00 6.60b09 0.00D00 1.15b10 10 Rb-86 0.00b00 1.88b10 9.28b09 0.00D00 0.00D00 0.00b00 4.81 BOB 11 Er-89 1.0lbl0 0.00b00 2.89b08 0.00D00 0.00D00 0.00b00 2.07bOS 12 St-90 8.22b10 0.00b00 2.09b10 0.00b00 0.00b00 0.00b00 1.03b09 13Y-91 5.79b04 0.00D00 1.54bO3 0.00b00 0.00b00 0.00D00 4.15b06 14Zr-95 5.33bO3 1.30bO3 9.22bO2 0.00b00 1.40bO3 0.00b00 6.47b05 l 15 lib-95 4.87b05 2.0lb05 1.16b05 0.00b00 1.44b05 0.00b00 1.69b06 16 tib-97 2.63b11 5.62b12 2.03b12 0.00b00 4.39b12 0.00b00 1.77006 17 Mc-99 0.00b00 1.77bO8 3.45bO7 0.00D00 2.64 BOB 0.00b00 5.83b07 187c99: 2.34b01 4.82b01 6.21bO2 0.00D00 5.19bO2 2.52b01 1.40D04 19 Ru-103 7.06bO3 0.00D00 2.36bO3 0.00b00 1.47b04 0.00b00 8.59b04 20 h-106 1.34b05 0.00b00 1.67b04 0.00D00 1.5Bb05 0.00b00 1.0lb06 21Ag-110 2.75bO8 2.0lbO8 1.33bO8 0.00b00 2.88b08 0.00D00 1.04b10 22Sb-124 0.00b00 0.00 BOO 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 24 7e-127a 3.16bO8 1.05 BOB 3.83bO7 9.14bO7 7.79bO8 0.00D00 1.28 BOB 25 7e-129 4.58bO8 1.57bOS 7.06t+07 1.76bO8 1.15b09 0.00b00 2.74bO8 261-131 2.31b09 2.72b09 1.20b09 8.95b11 3.lBb09 0.00b00 9.72bO7 27I-133 3.0BbO7 4.49bO7 1.31bO7 8.17b09 5.28bO7 0.00b00 7.60D06 28Cs-134 2.51b10 4.69b10 4.73b09 0.00b00 1.21b10 4.95b09 1.27bOS 29 Ce-136 1.68b09 4.93b09 1.84b09 0.00b00 1.97b09 4.02bO8 7.49bO7 30 Cs-137 3.4 Bbl 0 4.07bl0 2.89bOS 0.00b00 1.09D10 4.43b09 1.27 BOB 31Ea-140 2.05 BOB 2.05b05 1.05bO7 0.00D00 4.86b04 1.26b05 5.02bO7 32 La-140 3.45b01 1.36b01 3.50b00 0.0Cb00 0.00b00 0.00b00 1.60D05 33 Ce-141 3.57b04 2.1Sb04 2.57bO3 0.00b00 6.72bO3 0.00b00 1.13D07 34 Ce-144 1.65b06 6.75b05 9.25b04 0.00b00 2.73b05 0.00b00 9.47bO7 l

All nuclides (except E 3) calculated per ODCM equatica 2.3-24 F3 calculated ;er ODCM equatien 2.3-28 155"i 3 2-94

M-1 and 2 ODCM Table 2.3-17 RVAWESFORBEAVERVALLEYSITE (sqmeter-stes/yrperuCi/sec)

Pathway : Ocat Milk Age Greup : Adult Nuclide Bone Liver T. Body Thyroid tidney Lung G1-LLI 1 F3 0.00b00 1.56bO3 1.56bO3 1.56bO3 1.56bO3 1.56bO3 1.56bO3 2P-32 1.74b10 1.06b09 6.72bOS 0.00b00 0.00b00 0.00D00 1.96b09 3 Cr-51 0.00D00 0.00b00 2.85bO3 1.70bO3 6.2Eb02 3.7BbO3 7.17b05 4Mn-54 0.00b00 7.14b05 1.36b05 0.00D00 2.12b05 0.00b00 2.19b06 5Fe-59 3.12b05 7.32b05 2.BlD05 0.00b00 0.00b00 2.05D05 2.44b06 6 Co-57 0.00b00 1.09b05 1.82b05 0.00b09 0.00D00 0.00b00 2.77b06 7 0o-58 0.00b00 4.40b05 9.86b05 0.00b00 0.00b00 0.00D00 8.91b06 8 Co-60 0.00D00 1.34b06 2.96b06 0.00b00 0.00b00 0.00D00 2.52bO7 9 Zn-65 1.!!bOS 3.7(BOB 1.69b08 0.00b00 2.50bO8 0.00b00 2.36bO8 10 Rb-86 0.00b00 2.63bO8 1.22 BOB 0.00 BOO 0.00 BOO 0.00D00 5.1EbO7 i

11St-89 2.43b09 0.00b00 6.99bO7 0.00b00 0.00b00 0.00b00 3.91bOS 12 Sr-90 6.64b10 0.00b00 1.63b10 0.00b00 0.00b00 0.00 BOO 1.92b09 13T-91 8.14bO2 0.00b00 2.18b01 0.00b00 0.00b00 0.00b00 4.48b05 14Zr-95 8.67b01 2.85b01 1.93b01 0.00b00 4.47b01 0.00b00 9.02h04 15 Nb-95 8.13bO3 4.52bO3 2.43bO3 0.00b00 4.47bO3 0.00b00 2.74bO7 16 Nb-97 3.3Sbl3 8.54E-14 3.12bl4 0.00b00 9.96b14 0.00b00 3.15b10 17 Mo-99 0.00b00 2.53b06 4.81b05 0.00b00 5.72b06 0.00D00 5.86b06 18 T -99: 3.39E-01 9.59b01 1.22b01 0.00D00 1.46b01 4.70001 5.67bO2 19 Ru-103 9.95b01 0.00D00 4.29b01 0.00b00 3.80bO2 0.00b00 1.16b04 20 Ru-106 1.72bO3 0.00D00 2.12bO2 0.00b00 3.32bO3 0.00 BOO 1.11b05 21 Ag-110s 4.99b06 4.61b06 2.74b06 0.00h00 9.07b06 0.00b00 1.8Bb09 22 Sb-124 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 0.00b00 235b-125 0.00b00 0.00 BOO 0.00D00 0.00b00 0.00b00 0.00b00 0.00b00 24 Te-127: 4.13b06 1.4Bb06 5.03b05 1.05b06 1.68bO7 0.00b00 1.3&bO7

25Te-129

5.94b06 2.22b06 9.41b05 2.04b06 2.4SbO7 0.00b00 2.99bO7 l 26 1-131 3.02D08 4.32b08 2.48 BOB 1.42bli 7.40bO8 0.00b00 1.14bO8 l 27I-133 3.95b06 6.87b06 2.0Sb06 1.0lb09 1.20bO7 0.00b00 6.17b06 28 Cs-134 4.67bOS 1.11b09 9.09bOS 0.00D00 3.60 BOB 1.19 BOB 1.95bO7 29 Cs-136 6.70bO8 2.65b09 1.90b09 0.00b00 1.47b09 2.02bOS 3.0lbOB l

30 Cs-137 1.50bl0 2.05bl0 1.34b10 0.00 BOO 6.95b09 2.31b09 3.96bO8 i

l 31 Ea-140 2.74b06 3.44bO3 1.79b05 0.00b00 1.17bO3 1.97bO3 5.64b06 32 La-140 4.60E-01 2.32E-01 6.13E-02 0.00b00 0.00b00 0.00b00 1.70b04 l 23 Ce-141 4.79bO2 3.24bO2 3.68b01 0.00b00 1.51bO2 0.00b00 1.24D06 l 34 Ce-144 3.05b04 1.27b04 1.64bO3 0.00b00 7.55bO3 0.00b00 1.03bO7 i P All tu lih s (ex:ept E 3) calculated ;er 0DCM equation 2.3-24 l E 3 calculated per ODCM equation 2.3-28 IEEEE :

2-95 I

l i

i EV-1and2ODCM fable 2.3-18 R VALUES FOR EEAVER VALLET SITE i

(sq seter-stes/yr per uC1/sec)

Pathway : Goat Milk AgeGrcup: Teen Nuclide Bone Liver T. Sody Thyroid Iidney Lung GI-lLI 1 H-3 0.00b00 2.03bO3 2.03bO3 2.03E+03 2.03bO3 2.03bO3 2.03bO3 2 P-32 3.21bl0 1.99b09 1.24b09 0.00b00 0.00b00 0.00b00 2.70D09 3 Cr-51 0.00D00 0.00E+00 4.9BbO3 2.77bO3 1.09bO3 7.11bO3 8.37b05 4 Mn-54 0.00D00 1.19b06 2.36b05 0.00b00 3.55b05 0.00b00 2.44b06 5 Fe-59 5.44b05 1.27b06 4.90D05 0.00b00 0.00D00 4.00b05 3.00b06 6 00-57 0.00b00 1.92b05 3.21b05 0.00D00 0.00b00 0.00b00 3.57b06 7 Co-58 0.00b00 7.40b05 1.71b06 0.00b00 0.00b00 0.00D00 1.02bO7 '

8 Co-60 0.00b00 2.27b06 5.11b06 0.00b00 0.00b00 0.00b00 2.96bO7 9 Zn-65 1.81 BOB 6.27 BOB 2.93b08 0.00b00 4.01bO8 0.00b00 2.66bO8 10 Eb-66 0.00b00 4.79 BOB 2.25bO8 0.00D00 0.00b00 0.00b00 7.09bO7 11St-89 4.49b09 0.00 BOO 1.2SbOB 0.00b00 0.00b00 0.00b00 5.35bO8 12Er-90 9.39b10 0.00 BOO 2.32b10 0.00000 0.00b00 0.00b00 2.64b09 13 0 91 1.50bO3 0.00D00 4.01b01 0.00b00 0.00b00 0.00b00 6.14b05 14Zr-95 1.55bO2 4.90D01 3.37b01 0.00b00 7.19b01 0.00D00 1.13b05 15Nb-95 1.39b04 7.69bO3 4.23bO3 0.00D00 7.45bO3 0.00D00 3.29bO7 16 Nb-97 6.15E-13 1.53b13 5.57bl4 0.00D00 1.79!-13 0.00b00 3.65009 17 Mo-99 0.00D00 4.56b06 8.70b05 0.00D00 1.04bO7 0.00 BOO 8.17b06 18 fc-99: 5.88001 1.64b00 2.13b01 0.00b00 2.45b01 9.11001 1.08bO3 19 h-103 1.77bO2 0.00b00 7.56b01 0.00b00 6.24bO2 0.00 BOO 1.4Eb04 20 h-106 '

2.44bO3 0.00D00 3.98bO2 0.00D00 6.10bO3 0.00D00 1.52b05 21Ag-110s 8.24b06 7.80D06 4.75b06 0.00b00 1.49bO7 0.00b00 2.19b09 22 Sb-124 0.00b00 0.00b00 0.00 BOO 0.00b00 0.00 BOO 0.00b00 0.00b00 23 Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00000 0.00h00 24fe-127: 7.61b06 2.70b06 9.05b05 1.81b06 3.0BbO7 0.00b00 1.90bO7 25 Te-129s 1.09bO7 4.03b06 1.72b06 3.51b06 4.55bO7 0.00b00 4.0EbO7 26I-131 5.4BDOB 7.67 BOB 4.12 BOB 2.24b11 1.32b09 0.00b00 1.52b06 27I-133 7.21b06 1.22bO7 3.73b06 1.71b09 2.15bO? 0.00b00 9.26b06 28Ce-134 8.11 BOB 1.91b09 8.86 BOB 0.00 BOO 6.07bO8 2.32 BOB 2.38bO7 29Ce-136 1.1(b09 4.49b09 3.02b09 0.00b00 2.44b09 3.65D08 3.61 BOB 30 Ce-137 2.71b10 3.61bl0 1.26D10 0.00D00 1.23b10 4.77b09 5.14D08 31 Ba-140 4.94b06 6.06bO3 3.18b05 0.00D00 2.05bO3 4.07bO3 7.62b06 32 La-140 8.27E-01 4.06b01 1.06b01 0.00D00 0.00D00 0.00D00 2.33b04 33 Ce-141 8.79bO2 5.87bO2 6.74b01 0.00b00 2.76bO2 0.00b00 1.68b06 >

34Ce-144 5.60D04 2.32b04 3.01bO3 0.00D00 1.39b04 0.00b00 1.41bO7 All cuelides (except b3) calculate:i per ODCM equation 2.3-24 b 3 calculated per ODCM equation 2.3-26 15~3 3 2-96

EV-1 and 2 ODCM isble 2.3-19 R VALUES FOR EEAVER VALLEY SITE (sq teter-tres/yr per UCl/sec)

Pathus; : Goat Milk Age Group : Child helide Bone Liver T. Body Thyroid tidney Lung GI-LLI 1 E-3 0.00b00 3.20bO3 3.20bO3 3.20bO3 3.20bO3 3.20bO3 3.20bO3 2 P-32 7.91b10 3.70D09 3.05b09 0.00b00 0.00b00 0.00b00 2.19b09

' Cr-51 0.00b00 0.00D00 1.02b04 5.64bO3 1.54bO3 1.03b04 5.39b05 4 Mn-54 0.00b00 1.78b06 4.74b05 0.00b00 4.99b05 0.00h00 1.49b06 5 Fe-59 1.26D06 2.04D06 1.02b06 0.00h00 0.00b00 5.91E+05 2.12b06 6 Cc-57 0.00b00 3.27b05 6.63b05 0.00b00 0.00b00 0.00b00 2.6Eb06 7 Co-5B 0.00b00 1.13b06 3.46b06 0.00b00 0.00b00 0.00b00 6.60D06 8 Co-60 0.00b00 3.53b06 1.04bO7 0.00D00 0.00b00 0.00b00 1.95bO7 92n-65 3.54bO8 9.44bO8 5.87bO8 0.00D00 5.95 BOB 0.00b00 1.66bO8 10 Eb-86 0.00D00 8.88bO8 5.46 BOB 0.00b00 0.00b00 0.00b00 5.71bO7 11 Sr-89 1.11b10 0.00b00 3.17bO8 0.00b00 0.00b00 0.00b00 4.30 BOB 12 St-90 1.59bli 0.00b00 4.02bl0 0.00b00 0.00b00 0.00 BOO 2.14b09 13 0 91 3.70bO3 0.00b00 9.89D01 0.00D00 0.00b00 0.00b00 4.93b05 14 Zr-95 3.60bO2 7.92b01 7.05b01 0.00D00 1.13bO2 0.00000 8.27b04 15 lib-95 3.13b04 1.22b04 8.71D03 0.00b00 1.14b04 0.00b00 2.25bO7 16 tib-97 1.49b12 2.70013 1.26013 0.00 BOO 2.991-13 0.00D00 8.33I-08 17 Mo-99 0.00b00 8.30D06 2.05b06 0.00b00 1.77D07 0.00000 6.87b06 IB Te-99: 1.35b00 2.65b00 4.39b01 0.00b00 3.84b01 1.34b00 1.51bO3 19 Eu-103 4.1SbO2 0.00b00 1.61D02 0.00 BOO 1.05D03 0.00D00 1.0!b04 20 Eu-106 7.79bO3 0.00D00 9.72bO2 0.00b00 1.05b04 0.00b00 1.21b05 21 Ag-110s 1.79bO7 1.21bO7 9.65b06 0.00b00 2.25bO7 0.00b00 1.44b09 22 Sb-124 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 23 Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 24 Te-127: 1.8EbO7 5.05b06 2.23b06 4.48b06 5.35bO7 0.00D00 1.52bO7 25 Te-129 2.68bO7 7.48b06 4.16b06 8.64b06 7.87bO7 0.00b00 3.27bO7 261-131  !.33b09 1.34b09 7.60bO8 4.42b11 2.19b09 0.00b00 1.19 BOB 27 b133 1.75bO7 2.17bO7 8.20b06 4.03b09 3.61bO7 0.00 BOO 8.73b06 28 Cs-134 1.87b09 3.07b09 6.4BbO8 0.00b00 9.52bO8 3.42bO8 1.66bO7 29 Cs-136 2.58b09 7.06b09 4.58b09 0.00b00 3.77b09 5.62bO8 2.49 BOB 30 Ce-!37 6.54b10 6.26b10 9.24b09 0.00b00 2.04bl0 7.34b09 3.92bO8 31 Ea-140 1.19bO7 1.05b06 6.96b05 0.00D00 3.4 S 03 6.23bO3 6.04b06 32 La-140 1.92b00 6.92I-01 2.33001 0.00D00 0.00b00 0.00b00 1.93b04 33 Ce-141 2.16bO3 1.0SbO3 1.60bO3 0.00b00 4.73bO2 0.00b00 1.35b06 1

34 Ce-144 1.3Sb05 4.33b04 7.37b03 0.00D00 2.40D04 0.00b00 1.13bO7 l

P All crlides (ex:ept ii-3) calculated per ODCM equation 2.3-24 E-3 calculated per ODCM e;uatics 2.028 IEi3 2-97

EV-1 and 2 ODCH Table 2.3-20 R VALUES FOR EIAVER VALLE7 SITE (59seter-aree/yrperuCi/sec)

Fathway : Goat Mill Age Group : Infant helide Bone Liver T. Body Thyroid Eidney Lung GI-LLI 1 E3 0.00b00 4 86bO3 4.86bO3 4.66bO3 4.B6bO3 4.86bO3 4.B6bO3 2 P-32 1.63b11 9.59b09 6.32b09 0.00b00 0.00b00 0.00b00 2.21b09 3 Cr-51 0.00b00 0.00b00 1.61b04 1.05b04 2.29bO3 2.04b04 4.69b05 4 Mn-54 0.00D00 3.31b06 7.50D05 0.00b00 7.33b05 0.00D00 1.21b06 5 Fe-59 2.35b06 4.11b06 1.62b06 0.00b00 0.00b00 1.21b06 1.96b06 6 Co-57 0.00D00 7.64b05 1.24b06 0.00b00 0.00b00 0.00b00 2.60D06 7 Co-58 0.00D00 2.26b06 5.64b06 0.00D00 0.00D00 0.00b00 5.64D06 8 Co-60 0.00b00 7.20b06 1.70bO7 0.00D00 0.00D00 0.00b00 1.71 BOT 9 Zn-65 4.76bOS 1.63b09 7.53 BOB 0.00b00 7.92bO8 0.00b00 1.38b09 10 Rb-B6 0.00D00 2.25b09 1.11b09 0.00b00 0.00b00 0.00b00 5.77bO7 11Sr-89 2.11b10 0.00D00 6.06 BOB 0.00D00 0.00b00 0.00b00 4.34bO8 12 Sr-90 1.73b11 0.00b00 4.39b10 0.00D00 0.00b00 0.00D00 2.16b09 13 E 91 6.94bO3 0.00b00 1.65D02 0.00 BOO 0.00b00 0.00b00 4.9Eb05 14 Zr-95 6.40D02 1.56bO2 1.11bO2 0.00b00 1.68bO2 0.00b00 7.77b04 15 Nb-95 5.64b04 2.41b04 1.39b04 0.00b00 1.72b04 0.00D00 2.03bO7 16 Nb-97 3.16012 6.74E-13 2.43F13 0.00b00 5.27F13 0.00b00 2.13007 17 Mo-99 0.00b00 2.12bO7 4.14b06 0.00b00 3.17bO7 0.00000 6.99b06 18Tc-99: 2.81b00 5.79b00 7.46b01 0.00b00 6.23b01 3.03b00 1.6BbO3 19 Ru-103 8.47bO2 0.00D00 2.83bO2 0.00D00 1.76bO3 0.00b00 1.03b04 20 Ru-106 1.60b04 0.00b00 2.00bO3 0.00b00 1.90b04 0.00b00 1.22b05 21 Ag-110m 3.30bO7 2.41bO7 1.60bO7 0.00D00 3.45bO7 0.00b00 1.25b09 22 Sb-124 0.00b00 0.00b00 0.0Cb00 0.00b00 0.00D00 0.00b00 0.00D00 23 Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 24Te-127: 3.80bO7 1.26bO7 4.5Sb06 1.10D07 9.35bO7 0.00b00 1.53bO7 25Te-129: 5.50bO7 1.89bO7 8.47b06 2.llbO7 1.38bO8 0.00b00 3.28bO7 26 I-131 2.77b09 3.27b09 1.44b09 1.07b12 3.82b09 0.00b00 1.17 BOB 27 I-133 3.70bO7 5.39bO7 1.5BbO7 9.80b09 6.34bO7 0.00b00 9.12006 28 Cs-134 3.02b09 5.62b09 5.68 BOB 0.00b00 1.45b09 5.93 BOB 1.53bO7 29 Cs-136 5.03b09 1.4Bb10 5.52b09 0.00D00 5.90D09 1.21b09 2.25 BOB 30 Cs-137 1.04b11 1.22bl1 8.66b09 0.00b00 3.2Bb10 1.33b10 3.82 BOB 31 Ba-140 2.45bO7 2.45b04 1.26b06 0.00D00 5.83bO3 1.51b04 6.03b06 32 La-140 4.14b00 1.63b00 4.19E-01 0.00b00 0.00b00 0.00b00 1.92b04 33Ce-141 4.29bO3 2.62bO3 3.0EbO2 0.00D00 B.07bO2 0.00b00 1.35b06 34 Ce-144 1.98b05 8.11b04 1.11b04 0.0C D00 3.2Eb04 0.00b00 1.14bO7 All nuclides !except E 31 calculated per ODCM equation 2.3-24 4 E 3 calculated per 0I0 equati:n 2.3-28 ISTE 3 2-98

E E E BV-1 and 2 ODCM TABLE 2.3-21 BV-1 AND 2 PROCESS Van' DISPERSIO4 PARAMETERS (D/Q)

FOR C04TINUOUS ELEVATED RELEASES >500 HRS /YR OR >150 HRS /QI'R (meters ~ )

DISTANCES 'IU 'IEE COJTROL IOCATIO4S, IN MILES SEC'IUR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 6.00E-10 8.60E-09 3.14E-09 1.76E-09 8.12E-10 5.70E-10 4.24E-10 3.29E-10 2.63E-10 2.15E-10 NNE 6.66E-10 5.64E-09 1.98E-09 2.55E-09 1.33E-09 1.07E-09 6.75E-10 5.23E-10 4.56E-10 3.74E-10 NE 1.03E-09 1.57E-09 1.32E-09 3.62E-09 2.63E-09 1.64E-09 1.23E-09 6.13E-10 7.85E-10 6.42E-10 ENE 1.13E-09 1.55E-09 3.69E-09 3.27E-09 2.31E-09 1.29E-09 1.21E-09 6.78E-10 6.72E-10 3.89E-10 E 1.35E-09 1.28E-08 4.09E-09 3.12E-09 1.91E-09 1.36E-09 1.01E-09 7.83E-10 4.15E-10 5.10E-10 ESE 9.82E-10 7.85E-09 4.40E-09 2.46E-09 1.47E-09 1.03E-09 5.65E-10 5.05E-10 3.25E-10 3.00E-10 SE 2.76E-09 6.41E-09 3.52E-09 1.97E-09 1.18E-09 8.27E-10 5.68E-10 4.40E-10 2.93E-10 2.43E-10 SSE 2.22E-09 4.66E-09 3.01E-09 1.68E-09 1.02E-09 7.14E-10 4.2SE-10 3.29E-10 2.19E-10 1.80E-10 S 3.00E-09 4.81E-09 3.76E-09 2.10E-09 1.36E-09 9.52E-10 5.12E-10 3.96E-10 2.68E-10 2.20E-10 SSW 1.44E-08 2.89E-09 7.83E-10 8.84E-10 5.70E-10 4.00E-10 2.55E-10 1.98E-10 1.84E-10 1.51E-10 SW 1.89E-08 5.55E-09 1.55E-09 8.71E-10 2.61E-10 3.94E-10 1.57E-10 2.50E-10 2.54E-10 2.08E-10 WSW 1.57E-09 6.63E-09 1.36E-09 1.04E-09 5.44E-10 2.39E-10 3.84E-10 2.98E-10 2.17E-10 1.78E-10 3.78E-10 2.95E-09 1.84E-09 1.03E-09 6.63E-10 4.66E-10 1.37E-10 2.68E-10 1.12E-10 1.75E-10 W

4.13E-10 3.09E-10 4.71E-10 7.35E-10 5.16E-10 1.93E-10 1.10E-10 1.12E-10 1.80E-10 hTM 4.54E-10 4.09E-10 2.86E-10 1.18E-09 7.04E-10 4.94E-10 3.37E-10 2.10E-10 2.09E-10 1.71E-10 FM 4.52E-10 2.05E-09 1.63E-09 9.12E-10 5.86E-10 4.13E-10 2.79E-10 2.16E-10 1.73E-10 1.42E-10 NNW 3.40E-10 2-99 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-22 BV-1 ANI) 2 CORAIIP1EFE VDES DISPERSIO1 PARAMETERS (D/6)

FOR CORI?UOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QIR (meters )

DISTR 4CES H) 'IIIE CORROL LOCATIO45, IN MILES SECIOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24 E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.66E-10 ENE 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 E 6.08E-08 1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 ESE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 SSE 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 S

4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SSW 2.61E-08 1.93E-10 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-10 4.18E-10 3.24E-10 2.35E-10 SW 3.06E-08 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 WSW 4.60E-08 7.97E-09 3.15E-10 1.13E-08 4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 W 6.49E-08 5.79E-10 4.75E-10 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 WIM 9.25E-08 1.21E-09 7.83E-10 6.41E-10 1.19E-07 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.10E-09 1.56E-09 tM 4.84E-10 3.59E-10 2.94E-10 5.22E-08 9.04E-09 3.79E-09 2.12E-09 1.28E-09 9.00E-19 6.25E-10 tem ISSUE 3 2-100

BV-1 and 2 ODCM TABLE 2.3-23 BV-1 AND 2 SITE VENTIIATIN VDES DISPERSION PARAMETERS (D/Q)

FOR CORINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRSAyrR (meters ~ )

DISTANCES TO THE COtHROL IDCATICNS, IN MILES SEC'IOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.66E-10 ENE 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 E 6.08E-08 1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 ESE 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 SE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SSE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 S 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 SSW 2.61E-08 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 sw 3.06E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 1.93E-10 WSW 4.60E-08 7.97E-09 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 W 6.49E-08 1.13E-08 4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 wtM 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 4.75E-10 tM 1.19E-07 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 1.21E-09 7.83E-10 6.41E-10 NNW 5.22E-08 9.04E-09 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 4.84E-10 3.59E-10 2.94E-10 2-101 ISSUE 3

I .

BV-1 and 2 ODCM TABLE 2.3-24 BV-1 AND 2 TURBINE BUILDING VENTS DISPERSIGI PAPATTERS (D/Q) l FOR CONTIIRXXJS GROUND LEVEL RELEASES >500 IIRS/YR OR >150 HRS /QTR (meters- )

l DISTANCES TO 11IE CCNITOL LOCATIONS, IN MILES SECToa 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 l

N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 i

NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.66E-10 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6. 58E -10 5.39E-10 ENE 6.08E-08 1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 E

3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 ESE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SE 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 SSE 2.84E-08 1.96E-10 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 S

4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SSW 2.61E-08 1.98E-10 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 SW 3.06E-08 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 WSW 4.60E-08 7.97E-09 3.15E-10 1.13E-08 4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 W 6.49E-08 8.96E-10 5.79E-10 4.75E-10 WNW 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 1.21E-09 7.83E-10 6.41E-10 NW l.19E-07 2.07E-08 8.68E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 4.84E-10 3.59E-10 2.94E-10 NNW 5.22E-08 9.04E-09 3.79E-09 ISSUE 3 2-102

DV-1 ami 2 ODCM IRBLE 2.3-25 FOR INEDRMATIm OfLY BV-2 CONDE24 SATE POLISHItG BUILDI!G VErfr DISPERSICN PARAMETERS (D/ Q)

EUR COtfrINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /UTR (meters ~ )

DISTANCES 10 'IIIE COfrROL IOCATIONS, IN MILES SECTOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.60E-10 ENE 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 E 6.08E-08 1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 ESE 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 SE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SSE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 S 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 2.61E-08 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SSW 3.06E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 1.93E-10 SW 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 WSW 4.60E-08 7.97E-09 I

4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 W 6.49E-08 1.13E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 4.75E-10 l WtM 9.25E-08 1.60E-08 8.68E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 1.21E-09 7.83E-10 6.41E-10 i rM 1.19E-07 2.07E-08 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 4.84E-10 3.59E-10 2.94E-10 tem 5.22E-08 9.04E-09 l

l ISSUE 3 2-103 j

BV-1 and 2 ODCM TABLE 2.3-26 POR INWRMATIOf ONLY BV-2 DECOtRAMINATIOJ BUILDIt0 VENT DISPERSIO4 PARAMETERS (D/Q) mR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRSA7TR (meters ~ )

DISTANCES 'IO 'IEE CORROL IDCATIOiS, IN MILES 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 SEC'10R 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 N 4.46E-08 3.22E-10 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 NNE 4.66E-10 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 NE 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 ENE 7.77E-08 1.35E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 E 6.08E-08 1.05E-08 1.87E-10 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 ESE 3.23E-08 5.60E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SE 3.29E-08 5.70E-09 2.59E-09 t

1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 SSE 2.84E-08 4.92E-09 2.06E-09 1.96E-10 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 S 3.67E-08 6.37E-09 1.70E-10 1.39E-10 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 SSW 2.61E-08 3.24E-10 2.35E-10 1.93E-10 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 SW 3.06E-08 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 WSW 4.60E-08 7.97E-09 3.34E-09 1.87E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 W 6.49E-08 1.13E-08 4.72E-09 4.75E-10 l

3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 WrM 9.25E-08 1.60E-08 6.43E-09 7.83E-10 6.41E-10 J

8.68E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 1.21E-09 rM 1.19E-07 2.07E-08 4.84E-10 3.59E-10 2.94E-10 9.04E-09 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 tard 5.22E-08 1

i l

l ISSUE 3 2-104

- - - - - - - - .O_-_______-____-_______ _ _ _

g

BV-1 and 2 ODCM TABLE 2.3-27 mR IN WRMATION OILY BV-2 WASTE GAS S10PE E VAULT VENT DISPERSION PAPRIETERS (D3 )

NR C07FINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR (meters-2)

DISTRK'ES 10 TIIE CCNIROL IECATIONS, IN MILES SEC'IOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.66E-10 ENE 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 E 6.08E-08 1. 05 E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 ESE 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 SE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SSE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 S 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 SSW 2.61E-08 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SW 3.06E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 1.93E-10 WSW 4.60E-08 7.97E-09 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 W 6.49E-08 1.13E-08 4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 WrM 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 4.75E-10 NW 1.19E-07 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 1.21E-09 7.83E-10 6.41E-10 NtM 5.22E-08 9.04E-09 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 4.84E-10 3.59E-10 2.94E-10 2-105 ISSUE 3

BV-1 and 2 ODCM  ;

TABLE 2.3-28 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (D/0)

FOR CONTINUOUS ELEVATED LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(IE-9 meters ~ )

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N . 600 2.340 --

.572 .707 2.510 NNE .673 3.220 --

.524 2.920 3.220 NE .766 1.280 .660 .111 .660 1.200 ENE 1.010 5.080 -- .702 --

1.760  ;

E 1.370 4.420 .401 1.290 1.290 4.420 ESE .984 6.390 --

2.340 6.390 6.180 SE 11.000 3.680 .466 .466 1.300 3.680 SSE 7.060 3.220 .423 .105 3.140 4.320 S 5.780 1.540 1.410 -- 2.610 2.730 SSV 2.040 1.040 .578 .208 1.040 1.460 SV 1.610 1.120 --

.693 .979 1.120 USV 1.710 1.310 .370 --

1.190 1.310 V .377 .659 .138 -- .518 .659 I VNV 424 .746 .497 .029 .746 .746 NV- .447 425 --

.070 488 .422 NNV .340 1.840 --

.043 .545 1.92 4

9 4

2-106 ISSUE 3 ,

4

BV-1 and 2 ODCM TABLE 2.3-29 BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (D/0)

FOR CONTINUOUS GROLrND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANLES (IDENTIFIED IN TABLE 2.2-3)

(IE-9 meters ~)

INDIVIDUAL RECEPT 0RS 00VNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 25.40 2.05 --

.693 .847 2.19 NNE 18.80 2.02 --

.459 1.850 2.11 NE 63.40 29.30 .455 .078 455 30.40 ENE 65.90 8.92 --

.661 --

32.20 E 38.00 3.90 .382 1.020 1.020 22.70 ESE 17.10 3.56 --

1.380 3.560 3.56 SE 13.80 3.03 .350 .350 1.100 3.03 SSE 10.50 2.65 .317 .094 2.570 3.68 5 10.60 1.05 .934 --

1.860 1.95 SSV 5.59 1.26 .663 .266 1.260 4.42 SV 3.94 2.21 --

1.320 1.920 2.21 VSV 27.50 2.65 .596 --

2.380 2.65 V 31.60 1.23 .645 --

.960 1.23 VNV 39.10 2.23 1.490 .045 2.230 2.23 D NV 70.60 15.00 -

.276

.068 1.990 1.090 15.60 9.91 NNV 31.50 6.52 --

lb 2-107 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-30 BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (D/0)

FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(IE-9 meters ~)

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE SECTOR N 25.40 2.05 -- .693 .847 2.19 NNE 18.80 2.02 -- .459 1.850 2.11 NE 63.40 29.30 455 .078 .455 30.40 .

l ENE 65.90 8.92 -- .661 -- 32.20 E 38.00 3.90 .382 1.020 1.020 22.70 ESE 17.10 3.56 -- 1.380 3.560 3.56 i SE 13.80 3.03 .350 .350 1.100 3.03 l SSE 10.50 2.65 .317 .094 2.570 3.68 i S 10.60 1.05 .934 -- 1.860 1.95 SSV 5.59 1.26 .663 .266 1.260 4.42 SV 3.94 2.21 -- 1.320 1.920 2.21 USV 27.50 2.65 .596 -- 2.380 2.65 l V 31.60 1.23 .645 -- .960 1.23 VNV 39.10 2.23 1.490 .045 2.230 2.23 NV 70.60 15.00 -- .276 1.990 15.60 NNV 31.50 6.52 -- .068 1.090 9.91 I

l l

I l

l 1

I l

1 2-108 ISSUE 3 ]

l 4

i BV-1 and 2 ODCM l 1

TABLE 2.3-31 BV-1 AND 2 TURBINE BUILDING VENTS DISPERSION PARAMETERS (D/0) 1 k FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(1E-9 meters-2) l INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 20.20 2.05 -- .693 .847 2.190 NNE 34.90 2.02 -- .459 1.850 2.110 NE 54.20 29.30 455 .078 455 30.400 ENE 57.50 8.92 -- .661 --

32.200 E 38.10 3.90 .382 1.020 1.020 22.700 ESE 18.60 3.56 -- 1.380 3.560 3.560 SE 19.00 3.03 .351 .351 1.100 3.030 SSE 13.30 2.65 .318 .094 2.570 3.690 S 11.30 10.40 .934 -- 1.860 1.950 SSV 6.44 1.26 .664 .266 1.260 4.430 SV 3.95 2.21 -- 1.320 1.920 2.210 VSV 25.10 2.65 .597 -- 2.380 2.650 V 28.40 1.23 .646 -- .961 1.230 VNV 30.90 2.23 1.490 .045 2.230 2.230 D NV 56.10 14.90 6.53

.276

.068 1.980 1.100 15.500 9.920 I N!N 25.10 -

l i

l l

l 16 l

l I

l 2-109 ISSUE 3

BV-1 and 2 ODCH TABLE 2.3-32 FOR INFORMATION ONLY BV-2 CONDENSATE POLISHING BUILDING VENT DISPERSION PARAMETERS (D/0)

FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(IE-9 meters ~ )

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 20.20 2.05 --

.693 .847 2.190 NNE 34.90 2.02 --

459 1.850 2.110 NE 54.20 29.30 .455 .078 .455 30.400 ENE 57.50 8.92 -- .661 -- 32.200 E 38.10 3.90 .382 1.020 1.020 22.700 ESE 18.60 3.56 --

1.380 3.560 3.560 SE 19.00 3.03 .351 .351 1.100 3.030 SSE 13.30 2.65 .318 .094 2.570 3.690 S 11.30 10.40 .934 -- 1.860 1.950 SSV 6.44 1.26 .664 .266 1.260 4.430 SV 3.95 2.21 --

1.320 1.920 2.210 VSV 25.10 2.65 .597 -- 2.380 2.650 V 28.40 1.23 .646 --

.961 1.230 VNV 30.90 2.23 1.490 .045 2.230 2.230 NV 56.10 14.90 --

.276 1.980 15.500 NNV 25.10 6.53 --

.068 1.100 9.920 l

2-110 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-33 FOR INFORMATION ONLY BV-2 DECONTAMINATION BUILDING VENT DISPERSION PARAMETERS (D/0)

FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(IE-9 meters-2)

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 25.40 2.05 -- .693 .847 2.190 NNE 18.80 2.02 -- .459 1.850 2.110 NE 63.40 29.30 .455 .078 .455 30.400 ENE 65.90 8.92 -- .661 --

32.200 E 38.00 3.90 .382 1.020 1.020 22.700 ESE 17.10 3.56 -- 1.380 3.560 3.560 SE 13.80 3.03 .350 .350 1.100 3.030 SSE 10.50 2.65 .317 .094 2.570 3.680 S 10.60 1.05 .934 -- 1.860 1.950 SSV 5.59 1.26 .663 .266 1.260 4.420 SV 3.94 2.21 -- 1.320 1.920 2.210 USV 27.50 2.65 .596 -- 2.380 2.650 V 31.60 1.23 .645 -- .960 1.230 D

VNV 39.10 70.60 2.23 15.00 1.490 .045

.276 2.230 1.990 2.230 15.600 NV --

NNV 31.50 6.52 -- .068 1.090 9.910 I

2-111 ISSUE 3

BV-1 and 2 ODCM i

i TABLE 2.3-34 FOR INFORMATION ONLY BV-2 VASTE GAS STORAGE VAULT VENT DISPERSION PARAMETERS (D/0)

FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(IE-9 meters ~)

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE SECTOR BOUNDARY N 25.40 2.05 -- .693 .847 2.190 NNE 18.80 2.02 -- .459 1.850 2.110 NE 63.40 29.30 .455 .078 455 30.400 i ENE 65.90 8.92 -- .661 -- 32.200 E 38.00 3.90 .382 1.020 1.020 22.700 ESE 17.10 3.56 -- 1.380 3.560 3.560 SE 13.80 3.03 .350 .350 1.100 3.030 SSE 10.50 2.65 .317 .094 2.570 3.680 S 10.60 1.05 .934 -- 1.860 1.950 SSV 3.59 1.26 .663 .266 1.260 4.420 SV 3.94 2.21 -- 1.320 1.920 2.210 VSV 27.50 2.65 .596 -- 2.380 2.650 V 31.60 1.23 .645 -- .960 1.230 VNV 39.10 2.23 1.490 .045 2.230 2.230 NV 70.60 15.00 -- .276 1.990 15.600 NNV 31.50 6.52 -- .068 1.090 9.910 2-112 ISSUE 3  !

BV-1 and 2 ODCM TABLE 2.3-35 BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (X/0)

D FOR BATCH GROUND LEVEL RELEASES <300 HRS /YR OR <150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(sec/m )

INDIVIDUAL RECEPTORS

'DOVNVIND SITE VEGETABLE SECTOR

• BOUNDARY GARDEN MILK COV MILK G0AT MEAT ANIMAL RESIDENCE N 8.21E-5 8.38E-6 --

3.72E-6 4.34E-6 8.82E-6 NNE 3.04E-5 4.71E-6 --

1.40E-6 4.38E-6 4.87E-6 NE 4.59E-5 2.21E-5 6.05E-7 1.38E 7 6.03E-7 2.28E-5 ENE 3.72E-5 5.25E-6 --

5.66E-7 --

1.88E-5 E 2.93E-3 3.79E-6 5.15E 7 1.17E-6 1.17E-6 1.78E-5 ESE 2.47E-5 5.61E-6 --

2.34E-6 5.61E-6 5.61E-6 SE 2.14E-5 5.00E-6 8.13E-7 8.13E 7 2.03E-6 5.00E-6 SSE 2.21E-5 6.31E-6 1.11E-6 3.92E-7 6.13E-6 8.49E-6 S 2.15E-5 3.03E-6 2.76E-6 --

4.93E-6 5.14E-6 SSV 2.18E-5 6.58E-6 3.81E-6 1.82E-6 6.58E-6 1.78E-5 SV 1.82E-5 1.03E-5 --

6.67E-6 9.12E-6 1.03E-5 VSV 1.09E 4 1.29E-5 4.10E-6 --

1.19E-5 1.29E-5 V 1 4.9E 4 1.05E-5 6.55E-6 --

8.77E-6 1.05E-5 VNV 1.?lE-4 1.72E-3 1.28E-5 1.23E-6 1.72E-5 1.72E-5

) NV 3.082-4 6.13E-3 --

3.80E-6 1.36E-5 6.36E-5 NNV 1.80E 4 3.54E-5 --

1.35E-6 9.27E-6 5.29E-5 l

• Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Fecord: 1976 - 1980 l

2-113 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-36 BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (X/Q)

FOR BATCH GROUND LEVEL RELEASES <500 HRS /YR OR <150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(sec/m )

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR

• BOUNDARY MILK COV MILK GOAT MEAT ANIMAL RESIDENCE GARDEN _

N 9.75E-5 1.00E-5 --

4.21E-6 4.95E-6 1.06E-5 NNE 3.78E-5 5.11E-6 --

1.43E-6 4.72E-6 5.30E-6 NE 6.13E-5 2.70E-5 6.20E-7 1.40E-7 6.20E-7 2.81E-5 ENE 4.83E-5 5.58E-6 --

5.71E-7 --

2.24E-5 E 3.66E-5 3.99E-6 5.25E 7 1.19E-6 1.19E-6 2.10E-5 ESE 2.99E-5 6.13E-6 --

2.43E-6 6.13E-6 6.13E-6 SE 2.55E-5 5.29E-6 8.24E-7 8.24E-7 2.13E-6 5.29E-6 SSE 2.65E-5 6.72E-6 1.12E-6 3.95E-7 6.53E-6 9.22E-6 S 2.52E-3 3.14E-6 2.83E-6 --

5.29E-6 5.53E-6 SSV 2.60E-5 7.34E-6 4.15E-6 1.92E-6 7.34E-6 2.09E-5 SV 2.13E-5 1.18E-5 --

7.41E-6 1.04E-5 1.18E-5 VSV 1.34E 4 1.51E-5 4.46E-6 --

1.38E-5 1.51E-5 '

l V 1.77E 4 1.2SE-5 7.40E-6 --

1.02E-5 1.25E-5 VNV 2.33E-4 2.07E-5 1.49E-5 1.30E-6 2.07E-5 2.07E-5 NV 3.32E-4 8.57E-5 -- 4.24E-6 1.64E-5 8.85E-3 NNV 1.90E-4 4.69E-5 -- 1.45E-6 1.09E-5 6.75E-5 l

1 l

l

• Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980 2-114 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-37 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (X/0)

D FOR BATCH ELEVATED RELEASES <500 HRS /YR OR <150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)

(sec/m )

INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR

• BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 3.09E-9 3.30E-6 --

1.13E-6 1.34E-6 3.36E-6 NNE 2.85E-9 2.68E-6 --

6.52E-7 2.47E-6 2.68E-6 NE 2.02E-10 7.42E-9 5.44E-7 1.24E 7 5.44E-7 5.51E-9 ENE 1.02E-9 3.21E-6 -- 6.29E-7 -- 1.67E-9 E 2.15E-9 2.91E-6 4.96E-7 1.14E-6 1.14E-6 2.91E-6 LSE 6.90E-9 4.97E-6 --

1.95E-6 4.97E-6 4.81E-6 SE 2.91E-6 3.52E-6 6.02E-7 6.02E-7 1.43E-6 3.52E-6 SSE 4.91E-6 3.56E-6 6.53E-7 2.18E-7 3.47E-6 4.71E-6 S 2.41E-6 1.78E-6 1.65E-6 -- 2.84E-6 2.96E-6 SSV 4.83E-6 2.52E-6 1.50E-6 6.60E-7 2.52E-6 3.96E-6 SV 4.82E-6 2.75E-6 --

1.78E-6 2.44E-6 2.75E-6 VSV 5.77E-7 2.81E-6 8.79E 7 --

2.57E-6 2.81E-6 V 2.88E-9 1.68E-6 4.89E-7 --

1.37E-6 1.68E-6 VNV 3.40E-9 1.61E-6 1.13E-6 1.10E-7 1.61E-6 1.61E-6 NV 1.34E-9 3.31E-8 -- 2.03E-7 1.07E-6 3.10E-8 D NNV 1.52E-9 3.73E-6 --

1.73E-7 1.31E-6 3.81E-6 l

l

• Measured relevant to BV-1 natural draft cooling tower Period of Record: 1976 - 1980 2-115 ISSUE 3

BV-1 and 2 ODCM TABLE 2.3-38 BV-1 AND 2 PROCESS VDTP DISPERSION PARAMI?rERS (X/Q)

POR B/CICI ELEVATED RELEASES <500 IIRS/YR OR _<150 HRSKrrR*

(sec/m )

DISTANCES 'IO 'IllE COfrROL LOCATIWS, IN MILES SEC*IOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 2.75E-15 1.07E-5 4.10E-6 2.61E-6 1.51E-6 1.13E-6 8.84E-7 7.13E-7 5.93E-7 5.06E-7 tale 5.90E-17 5.39E-6 2.83E-6 2.19E-6 1.36E-6 1.13E-6 8.05E-7 6.51E-7 5.64E-7 4.81E-7 NE 4.45E-16 1.67E-8 7.39E-8 2.28E-6 1.72E-6 1.19E-6 9.28E-7 6.76E-7 6.34E-7 5.32E-7 ENE 1.92E-15 8.87E-8 2.60E-6 2. 21E -6 1.66E-6 1.13E-6 9.25E-7 7.23E-7 6.06E-7 3.82E-7 5.10E-6 2.77E-6 2.23E-6 1.44E-6 1.12E-6 8.74E-7 6.92E-7 5.11E-7 4.82E-7 E 1.84E-15 2.96E-13 5.26E-6 3.48E-6 2.04E-6 1.34E-6 9.93E-7 6.70E-7 5.76E-7 4.37E-7 3.83E-7 ESE 3.136-6 3.38E-6 1.99E-6 1. 31E-6 9.58E-7 7.14E-7 5.74E-7 4.32E-7 3.68E-7 SE 9.16E-8 3.32E-7 3.50E-8 4.86E-6 3.33E-6 1.95E-6 1.29E-6 9.42E-7 6.55E-7 5.24E-7 3.95E-7 SSE 4.12E-6 3.97E-6 2.34E-6 1.59E-6 1.17E-6 7.75E-7 6.24E-7 4.74E-7 4.00E-7 S 1.22E-7 4.77E-7 6.22E-6 2.84E-6 2.18E-6 1.48E-6 1.08E-6 7.83E-7 6.31E-7 5.62E-7 SSW 1.75E-5 6.89E-7 5.85E-7 2.08E-5 9.11E-6 3.47E-6 2.19E-6 1.25E-6 1.llE-6 8.19E-7 7.17E-7 SW 5.99E-7 5.07E-7 8.56E-8 9.35E-6 3.16E-6 2.29E-6 1.46E-6 1.01E-6 9.06E-7 7.52E-7 WSW 4.21E-6 2.49E-6 1.69E-6 1.25E-6 4.86E-7 7.68E-7 5.80E-7 5.48E-7 W 5.44E-17 4.52E-6 4.89E-7 5.66E-8 1.92E-6 1.59E-6 1.17E-6 7.75E-7 4.61E-7 5.28E-7 vaai 9.25E-18 1.44E-8 5.42E-7 4.60E-7 1.98E-8 8.37E-8 2.24E-6 1.46E-6 1.08E-6 8.09E-7 6.12E-7 tM 2.61E-16 6.48E-7 5.37E-7 4.56E-7 1.91E-15 3.91E-6 3.66E-6 2.15E-6 1.40E-6 1.08E-6 8.03E-7 tam 30, 1987.

• Transmittal via Stone and Webster Engineering Corp. letter 2DLS-29981 under J.O.12241 on January ISSUE 3 2-116

- - b _____ _ _k

BV-1 and 2 ODCM 2.4 GASEOUS RAD'n'ASTE SYSTEM The gaseous radvaste system has the capability to control, collect, process, store, recycle, and dispose of gaseous radioactive vaste generated as a result of plant operations, including anticipated operational occurrences.

A simplified flow diagram of the gaseous radvaste system for BV-1 and BV-2 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 radvaste system is used, then gaseous vaste generated can be stored, processed, and discharged from either BV-1 or BV-2.

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2-117 ISSUE 3 l

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BV-1 and 2 ODCM FIGURE 2,4-1 BV-1 AND 2 GASEOUS RADVASTE SYSTEM e

O IRom UMlf 2 91I005 WSTI SYSTEN (51milAR TO UNIT 1) To afm0Sf*IRI l -

I ,

C00b f own UNIT 1 Uhli 2 ll PRDILTIRS @S GA5 g CMPRISSOR COMPRESSCR

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- 9 CXYCIN ANALY1D bl- 1 d n 1 COPCD50R AIR EJECTOR tt e-DIM $ltlD RAtl Afl0H NONif 0R pud >b n & CONT AIPMINT WACUUM PUEPS >~

d RDCTOR C00LAMI 2-118 ISSUE 3

BV-1 and 2 ODCM FIGURE 2.4-2 BV-1 AND 2 GASEOUS EFFLUENT RELEASE POINTS D m Ohio RW" gggM' kWIW=EDE5ms- 2.

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FILI 82E FO!!ii a III:E :"3 gtgyg;g j Unit 1: Ve:tilat. : ie:t 73 feet : 24 meters

j. 0:it 1: C::taitnett / SlCF,5 yett 154 feet : 47 seters J. ,J :t 1 & 2: Fro:e:s ie:t 05 feet : 145 seters

4. I' nit 4: Ventilatic: Fe:t 65 feet : 25 meters v:lt 2: Cc:taitsett / ELCP.5 Ve:t 154 feet : 47 ,,t,73 g[~

O

~

6. Unit 2: Cenderrate Felishi:g Evilding Ver.t 80 feet : 24 meters

7. U:it 2: Waste Gas Etcrage Vault Ve:t 60 feet : 24 meters '

.. v:lt ,:: Dect:tas::stic: Euilding Ve t 83 feet : 24 seters 2-119 ISSUE 3

BV-1 and 2 ODCM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l The following program requirements are excerpts from the Radiological Assessment Branch Technical Position. Revision 1, 1979.

Table 3.0-1 contains the DLC site number, sector, distance, sample point description, sampling and collection frequency, analysis, and analysis frequency for various exposure pathvays in the vicinity of the Beaver Valley Power Station for the radiological environmental monitoring program.

Figures 3.0-1 through 3.0-9 show the location of the various sampling points. I PROGRAM REQUIREMENTS Environmental samples shall be collected and analyzed according to Appendix C, Table 3.0-1. Analytical techniques used shall be such that the detection capabilities in Appendix C. Table 4.12-1 are achieved.

The results of the radiological environmental monitoring are intended to  ;

supplement the results of the radiological effluent monitoring by verifying l that the measurable concentrations of radioactive materials and levels of l radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radiation and of radioactive materials in those exposure pathways and for l those radionuclides which lead to the highest potential radiation exposures of 1.Jividuals resulting from the station operation. The initial radiological environmental nanitoring program should be conducted for the first 3 years of commercial u,'eration (or other period corresponding to a I maximum burnup in the initial core cycle). Following this period, program changes may be proposed based ou operational experience.

The specified detection cr.pabili t i es are state-of-the-art for routine environmental measurements in industrial laboratories.  !

l j

Deviations are permitted from the required sampling schedule if specimens '

are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the g next sampling period. All deviations from the sampling schedule shall be I documented in the annual report.

The laboratories of the licensee and licensee's contractors which perform analyses shall participate in the Environmental Protection Agency's (EPA's)

Environmental Radioactivity Laboratory Intercomparisons Studies (Crosscheck) Program or equivalent program. This participation shall include all of the determinations (sample medium-radionuclide combination) that are offered by EPA and that also are included in the monitoring program. The results of analysis of these crosscheck samples shall be included in the annual report. The participants in the EPA crosscheck program may provide their EPA program code so that the NRC can review the 1 EPA's participant data directly in lieu of submission in the annual report. l l

3-1 ISSUE 3

BV-1 and 2 ODCM If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annual report.

The requirement for the participation in the EPA crosscheck program, or similar pr ogram, is based on the need for independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices as part of the quality assurance program for  ;

environmental monitoring in order to demonstrate the results are reasonably  ;

valid.

A census shall be conducted annually during the growing season to determine the location of the nearest milk animal and nearest garden greater than 50 square meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of 8 km (5 miles). Broad leaf vegetation sampling may be performed at the site boundary in a sector with the highest D/0 in lieu of the garden census. For elevated releases as defined in Regulatory Guide 1.111, Rev. 1, the census shall also identify the locations of all milk animals, and gardens greater than 50 square meters producing broad leaf vegetation out to a distance of 5 km (3 miles) for each radial sector.

If it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in ODCM dose calculations, a written report shall be i submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Fegional Office) within 30 days identifying the new location (distance and direction). Milk animal or garden locations resulting in higher calculated doses shall be added to the surveillance program as soon as practicable.

The sampling location (excluding the control sample location) having the lovest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the NRC in writing that they are no longer obtainable at that location. The results of the land-use census shall be reported in the annual report.

The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to " Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathvays (.! exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation contaminated by airborne radioiodine is a major potential source of j exposure. Samples from milk animals are considered a better indicator of '

radiciodine in the environment than vegetation. If the census reveals milk  ;

animals are not present or are unavailable for sampling, then vegetation j must be sampled. '

3-2 ISSUE 3 I

BV-1 and 2 ODCM The 50 square meter garden, considering 20% used for growing broad leaf vegetation 2(i.e., similar to lettuce and cabbage), and a vegetation yield of 2 kg/m , vill produce the 26 kg/yr assumed in Regulatory Guide 1.109, Rev. 1, for child consumption of leafy vegetation. The option to consider the garden to be broad leaf vegetation at the site boundary in a sector with the highest D/0 should be conservative and that location may be used to calculate doses due to radioactive effluent releases in place of the actual locations which would be determined by the census. This option does not apply to plants with elevated releases as defined in Peculatory Guide 1.111, Rev. 1.

The increase in the number of direct radiation stations is to better characterize the individual exposure (mrem) and population exposure (man-rem) in accordance with criterion 64 - monitoring radioactivity relea.ses, of 10 CFR Part 50, Appendix A. The NRC will place a similar amount of stations in the area between the two rings designated in Appendix C, Table 3.12-1.

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3-3 ISSUE 3 l I

DV-1 and 2 ODCM TNILE 3.0-1 RADIOLOGICAL EINIRCteiEI4TAL MCt4I'IORING PROGPRi DLC SNiPLING N4D COLLECTICt1 TYPE AND FRECUC4CY EXPOSURE PATIIWAY SITE 1 3 OF ANALYSES NO. SEC'IOR MILES SAMPLE POIITI' DESCRIPTIQ4 FREQUENCY AND/OR SAMPLE

1. AIRBOPliE Radiciodine Cartridge:

Radiciodine and 13 11 1.6 Ilookstown (Meyer's Farm) Continuous 0.6 shippingport (Cooke's Ferry sampler I-131 analysis weekly.

Particulates 30 4 Substation) operation w/

0.8 Midland (Midland Substation) Collection Particulate Sampler:

32 15 46.1 3 2.1 Industry at least Grossbetaanalysisgol-48 10 16.5 Weirton, WV4 (Weirton Water weekly. lowing filter change ;

Storage Tank) Gamma isotopic analysis on composite (by loca-tion) quarterly.

shippingport Boro (Post Office) Continuous Gamma dose quarterly.

2. DIRECT RADIATION 10 4 0.8 11 1.6 Meyer's Farm measurement 13 2.6 Hookstown with quarterly 14 11 3.3 Georgetown collection.

15 14 27 7 6.2 Brunton's Fann 28 1 8.7 Sherman's Farm 29B 3 8.1 Beaver County Hospital l

30 4 0.6 shippingport Boro (Cooke's Ferry) j 32 15 0.8 Midland Boro (Midland substation) 1 45 5 2.2 Raccoon Twp. (Mt. Pleasant Church) 45.1 6 2.0 Raccoon Twp. (Kennedy's Corner) 46 3 2.5 Industry (Church) 46.1 3 2.1 Industry (Tire Company) i

! 47 14 4.8 East Liverpool, 011 (Water Company) l 48 10 16.5 Weirton, WV (Water Company) 51 5 8.0 Aliquippa 59 7 1.1 Iron's Farn l

ISSUE 3 3-4

_ _ __ . A g . _ _ _ _ _ _

BV-1 and 2 000t TABLE 3.0-1 (continued)

RADIOLOGICAL E?NIIU@iErfrAL MCril'IORIFU PROGPAM l DLC SAMPLItG AND EXPOSURE PAT 1MAY SITE COLLECTION TYPE AND FREQUENCY AND/OR SAMPLE NO. SECIOR MILES SAMPLE POINT DESCRIPTIOi FREQUENCY OF ANALYSES l

DIRECT RADIATION 60 13 3.7 Haney's Farm Continuous Ganm3 dose quarterly.

(continued) 70 1 3.0 Western Beaver IIigh School measurement 71 2 5.6 Brighton Township School with quarterly 72 3 3.2 Logan School collection.

73 4 2.2 Potter Township School 74 4 6.8 Center Township (Comunity College) 75 5 4.3 Raccoon Twp. (Holt Road)

! 76 6 3.8 Raccoon hp. School 77 6 5.8 Raccoon Twp. (Green Garden Road) 78 7 2.3 Raccoon Twp. Municipal Building 79 8 4.6 Raccoon hp. ( Routes 18 & 151) 80 9 8.4 Raccoon Park 81 9 3.9 Southside School 82 9 7.1 Hanover Township Municipal Building Greene Township (Mill Creek Road) 83 10 4.5 84 11 8.5 Hancock County, WV (Children's llome) 85 12 5.8 llancock County, WV (Routes 8 & 30) 86 13 6.5 East Liverpool, OH (Cahill's) 87 14 7.0 Calcutta, OH 88 15 3.1 Midland Heights 89 15 4.7 Ohioville 90 16 5.2 Fairview School 91 2 3.7 Brighton hp. (Pine Grove & Doyle Roads) 92 12 3.0 Greene Township (Georgeto41 Road) 93 16 1.3 Midland (Sunset Hills) 94 8 2.4 Raccoon Ap. (McCleary Road) 95 10 2.4 Greene Township (McCleary Road)

ISSUE 3 3-5

BV-1 and 2 ODCM TABLE 3.0-1 ( continued)

RADIOLOGICAL ENVIRCMENTAL MONI'IORING PROGEM DLC septInc yo EXPOSURE PA111WAY SITE , a COLLECTION TYPE NO FREQUGCY NO.

1 MILES" SAMPLE POINT DESCRIPTION' FREQUENCY OF NmLYSES ANDcOR SMPLE SEC'IOR

3. WNTERORNE 5.0 Gamma isotopic analysis a) Surface (River) 49.1 4 Upsgream-invicinityofMontgomery composite monthly; tritium analy-Dam (ARCO Chemical Company, sample w/

formerly ARCO Polymers) sample col- sis on composite (by Downstream-Midland lection at location) quarterly.

2.1 14 1.3 least 6

mor Wly 4 14 1.3 Midland (Midland Water Treatment Composite I-131 analysis bi-b) Drinking Water weekly; gamma isotopic Plant) sample w 14 4.8 East Liverpool, Oli (East Liver- sample col- analysis on composite 5

pool Water Treatment Plant) lection at (by location) monthly; lesst pi- tritium analysis on com-weekly ~ posite (by location) c)Gtound Water None required Vicinity of BVPS Discharge Semi- Gamma isotopic analy-d) Shoreline 2A 13 0.2 annually. sia semi-annually.

Sediment Structure

4. INGESTION Searight's Dairy At least bi- Gamma isotopic and I-131 a) Milk 25 10 2.1 analysis on each sample.

• g weekly when

• 8 - -

1. "i" IS "'"

• 8 on pasture; at Windsheimer's Dairy 4 least monthly 96 10 10.3 at other times.

Downstream-in vicinity of BVPS Semi-annually Gamnu isotopic analysis.

2A 13 0.2 b) Fish Discharge Structure one sample of on edible portion.

49 3 4.7 Upstream-in vicinity of Montgomery available Dam species.

ISSUE 3 3-6

BV-1 and 2 OOCM TABLE 3.0-1 (continued)

RADICLOGICAL ENVIRONMENTAL MONI'IORING PROGRAM DLC SMiPLING AW EXPOSURE PATIMAY SI'IE 1 3 COLLECTION TYPE MJD FRF40ENCY AND/OR SAMPLE NO. SECIOR MILES SAMPLE POINT DESCRIPTION FREQUENCY OF ANALYSES

4. INGESTION (continued) c) Food Products 10 4 0.8 Three (3) locations within 5 niiles Annually at Gamma isotopic and I-131 (Leafy Vege- 15 14 3.3 of BVPS harvest analysis on edible tables) 46 3 2.5 time. portion.

48 10 16.5 One (1) location (Weirton, WV area) 1 Sector numbers 1-16 correspoad to the 16 cocpass direction sectors N - NIM.

"7 Distance (in miles) is as measured hom BVPS Unit 1 Containment Building.

All Sample Points, unless otherwise noted, are in the Commonwealth of Pennsylvania. naps showing the approximate locations of the Sample Points are provided as Figures 3.0-1 through 3.0-9.

This is a Control Station and is presumed to be outside the influence of BVPS effluents.

5A gamma isotopic analysis is to be performed on each sample when the gross beta activity is round to be greater than 10 times the mean of the Control Station sample.

6 Composite samples are obtained by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

7 Collection of Ground Water samples is not reuqired as the hydraulic gradient or recharge properties are directed toward the river because of the high terrain in the river valley at the BVPS; thus, station effluents do not affect local wells and ground water sources in the area.

8 These Sample Points will vat,f and are chosen based upon calculated annual deposition factors (highest).

l ISSUE 3 3-7

l BV-1 and 2 ODCM FIGURE 3.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM AIR SAMPLItJG LOCATIO"S runtwmat. w=ucwuna wcArious- r,n: <>m pr, taAnac N t.awwr.,er cm nr MRSml&SW12G -

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BV-1 and 2 ODCM FIGURE 3.0-2 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

TLD LOCATIONS - NORTHVEST QUADRANT I

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D 3-9 ISSUE 3

BV-1 and 2 ODCM FIGURE 3.0-3 )

l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD LOCATIONS - NORTHEAST GUADRANT .

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3-12 ISSUE 3

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BV-1 and 2 ODCM FIGURE 3.0-6 RADIOLOGICAL EINIRO4MDHAL MONI'IORING PROGRAM SilORELINE, SEDIMDR, SURFACE WATER, NJD DRINKING WATER SAMPLING LOCATIONS c p Moanionenv D*Hll I --. .-_.

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BV-1 and 2 ODCH FIGURE 3.0-7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i MILK SAMPLING' LOCATIONS LNV1F40BdWENTAL WONSTOftl$4J LDCATIOMS- FUlK N tawariar omwn

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-_____.___________O_________________.._____,,____,,___8______,___ _ _ . _ _ _h_ _

BV-1 and 2 ODCM 4.0 INFORMATION RELATED TO 40 CFR 190 Appendix C CONTROL 3.11.4.1 requires that when the calculated doses associated with the effluent releases exceed twice the limits of Appendix C i 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 CONTROL 3.11.2.3.b, calculations shall be made including direct radiation contributions from the units (including outside storage tanks, etc.) to determine whether the dose or dose commitment to any MEMBER OF THE PUBLIC from all facility releases of radioactivity and to radiation from uranium fuel cycle sources exceeds the limits of $ 25 mrem to the total body or any organ, except the thyroid, which is limited to j 75 mrem for a calendar year. If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Report pursuant to Technical Specification 6.9.2f. The following shall be included in the Special Report:

• Define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Appendix C CONTROL 3.11.4.1.

• Include the schedule for achieving conformance within the limits of Appendix C CONTROL 3.11.4.1.

• Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.

' Describe levels of radiation and concentrations of radioactive material involved, and the cause of exposure levels or concentrations.

• If the estimated dose (s) exceeds the limits of Appendix C CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.  ;

l 4-1 ISSUE 3

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BV-1 and 2 ODCM APPENDIX A

SUMMARY

OF DISPERSION CALCULATIONAL PROCEDURES Annual average and grazing season average values of relative concentration (X/0) and deposition (D/0) vere calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-line airflov (Gaussian) model described in NRC Regulatory Guide 1.111, Revision 1. Undecayed and undepleted sector average X/0 and D/0 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 vake 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/0 and D/0 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 tover, the Containment Vents, Ventilation Vents, Turbine Building Vents, the BVPS-2 Condensate Polishing Building Vent, Decontamination Building Vent, and Gaseous Vaste Storage Tank Vault Vent. The intermittent releases are from the Process Vent, Containment Vents, and Ventilation Vents. Only the process vent was considered to be an elevated release with all other release points being treated as ground level releases. A summary of the release characteristics and their locations is given in Appendix A, Table 1.1.

Onsite meteorological data for the period January 1, 1976 through December 31, 1980 vere 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 vere collected according to guidance in NPC Regulatory Guide 1.23 as described in Section 2.3 of the BVPS-2 FSAR. The parameters used in the X/0-D/0 calculations consist of vind speed, vind direction, and Sr as an indicator of atmospheric stability. The lover level winds (35 ft) and CT (150-35 ft) vere used for all release points except the process vent which required the use of 500 ft vinds and oT (500-35 ft) which are representative of the release height (510 ft).

The annual average and grazing season X/0 and D/0 values for the continuous and intermittent radioactive releases were calculated at the site boundary, nearest resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and nearest meat animal. In the case of the process vent releases, several of each receptor type were evaluated in each downwind sector to determine the maximum X/0-D/0 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/O values at the special locations for the Containment Vents.

Ventilation Vents. Process Vent. Turbine Building Vents, Decontamination Building Vent, Vaste Gas Storage Vault Vent, and Condensate Polishing Building g, Vent are given in Tables 2.2 4 through 2.2-10 respectively. Continuous release F

annual average X/O's for these same release points are also given at ten l

A-1 ISSUE 3

i BV-1 and 2 ODCM APPENDIX A

SUMMARY

OF DISPERSION CALCULATIONAL PROCEDURES (continued) incremental downwind distances. Continuous release D/0 values for these same e

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 Vaste Storage Tank Vault X/0's and D/O's are the same as the containment vent X/0's and D/0's. Likewise, the Turbine Building Vent X/O's and D/0's apply to the BVPS-2 Condensate Polishing Building as well due to its location adjacent to the Turbine Building.

Tables 2.3-35 through 2.3-38 contain short term X/0 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 and Ventilation Vent purges and 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> per year of Process Vent purges.

I i

4 l

2 l

l I

I Albersheim, S. R., Development Of Terrain Adjustment Factors For Use At the Beaver Valley Power Station For the Straight-Line Atmospheric Dispersion Model, NUS-2173, NUS Corporation, June 1978 Sagendorf, J. F., Goll, J. T. and Sandusky, V. F., X00D00: Computer Program For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear Power Stations, NUREG/CR-2919, U. S. Nuclear Regulatory Commission, September, 1982.

A-2 ISSUE 3

BV-1 and 2 ODCM APPENDIX A TABLE 1.1 I BV-1 AND 2 RELEASE CONDITIONS TURBINE VENTILATION CONTAINMENT PROCESS BUILDING VENT VENT VENT VENT l TYPE OF RELEASE GROUND LEVEL GROUND LEVEL ELEVATED GROUND LEVEL Long Term Long Term Long Term And And And Short Term Short Term Short Term Release Point 26 47 155 33 Height (m)

Adjacent Building 19 44 155 33 Height (m)

Relative Loca- E. Side Of Top Center Of Atop Cooling Turbine tion To Adjacent Primary Auxi- Containment Tower Building Structures liary Bldg Dome Exit Velocity NA NA 9.4 NA l (m/sec)

Internal Stack NA NA 0.25 NA Diameter (m) 1600 1600 NA NA Building Cross-7 Sectional Area (m )

Purge Frequency

• 32 32 74 NA (hours / year)

Purge Duration 8 8 NA NA (hrs / release) l

• Applied to Short Term calculations only A-3 ISSUE 3

BV-1 and 2 ODCM APPENDIX B INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS

1. Inputs To Gale Code For Generation Of BV-1 Liquid Source Term Mixes

2. Inputs To SVEC LIO1BB Code For Generation Of BV-2 Liquid Source Term Mixes

3. Inputs To SVEC GASIBB Code For Generation Of BV-1 Gaseous Source Term Mixes

4. Inputs To SWEC GASIBB Code For Generation Of BV-2 Gaseous Source Term Mixes D

D B-1 ISSUE 3

BV-1 and 2 ODCM APPENDIX B TABLE 1.la INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PVR INPUTS PVR Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 345.000 Percent Fuel Vith Cladding Defects .120 Primary System Letdovn Rate (gpm) 60.000 Letdown Cation Demineralizer Flov 6.000 Number Of Steam Generators 3.000 Total Steam Flow (million lbs/hr) 11.620 Mass Of Steam In Each Steam Generator (thousand lbs) 6.772 Mass Of Liquid In Each Steam Generator (thousand lbs) 97.000 Total Mass Of Secondary Coolant (thousand lbs) 1296.000 Mass Of Vater In Steam Generator (thousand Ibs) 291.000 Blowdown Rate (thousand lbs/hr) 33.900 Primary To Secondary Leak Rate (lbs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flov Fraction 0.000 Radvaste Dilution Flov (thousand gpm) 22.500 1

BV-1 LIQUID VASTE INPUTS COLLECTION DELAY DECONTAMINATION i

FLOV RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal / day) 0F PCA DISCHARGE (days) (days) I Cs OTHERS Shim Bleed 1.32E4 1.000 0.000 11.260 7.220 1E7 IE7 1E7 >

Rate Equipment 6.00E2 1.000 0.000 11.260 7.220 1E7 1E7 IE7 Drains clean vaste 7.50E1 1.000 1.000 0.071 0.648 1ES 2E4 1E5 Input Dirty Vaste 1.35E3 0.035 1.000 0.071 0.648 1E5 2E4 1E5 Input Blovdovn 9.75E4 --

1.000 0.071 0.648 1E5 2E4 1ES Untreated -- --

0.0 -- -

Blowdown 4

B-2 ISSUE 3

BV-1 and 2 ODCM APPENDIX '$

TABLE 1.lb INPUTS TO SVEC LIO1BB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PVR INPUTS PVR Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel With Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flov 5.700 Number Of Steam Generators 3.000 Total Steam Flov (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand Ibs) 8.700 Mass Of Liquid In Each Steam Generator (thousand Ibs) 100.000 Total Mass Of Secondary Coolant (thousand Ibs) 2000.000 Mass Of Vater In Steam Generator (thousand lbs) 298.000 Blovdown Rate (thousand Ibs/hr) 22.300 Primary To Secondary Leak Rate (Ibs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction .700 l Radvaste Dilution Flow (thousand gpm) 7.800 BV-2 LIQUID VASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOV RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal / day) 0F PCA DISCHARGE (hrs) (hrs) I CsRb OTHERS Containment 40 1.000 1.0 35.5 6.2 1E3 1E4 1E4 Sump Auxiliary 200 0.100 1.0 35.5 6.2 1E3 1E4 1E4 Building Sump Miscellaneous 700 0.010 1.0 35.5 6.2 1E3 IE4 1E4 Sources Rx Flant 35 1.000 1.0 35.5 6.2 1E3 1E4 1E4 Samples Lab Drains 400 0.002 1.0 35.5 6.2 1E3 1E4 1E4 Cond. Demin. 2685 1.1E 4 1.0 35.5 6.2 IE3 1E4 1E4 Rinse Vater CVCS 60 --

1.0 1300 173 IE4 4E3 1E5 Turbine Bldg. 7200 --

1.0 -- -- -- -- --

Drains B-3 ISSUE 3

BV-1 and 2 ODCM APPENDIX B TABLE 1.2a INPUTS TO SVEC GASIBB CODE FOR GENERATION OF BV-1 GASEOUS SOURCE TERM MIXES BV-1 PVR INPUTS PVR Thermal Power Level (megavatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coole.t (thousand Ibs) 385.000 Percent Fuel Vith Cl 3 ding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdovn Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flov (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand Ibs) 8.700 Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand lbs) 2000.000 Mass Of Vater In Steam Generator (thousand lbs) 298.000 Blovdown Rate (thousand lbs/hr) 52.000 Primary To Secondary Leak Rate (lbs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction 0.000 Radvaste Dilution Flov (thousand gpm) 15.000 BV-1 GASEOUS VASTE INPUTS There Is Not Continuous Stripping Of Full Letdown Flov Hold Up Time For Xenon (days) 39.000 Hold Up Time For Krypton (days) 2.000 Primary Coolant Leak To Auxiliary Building (lb/ day) 160.000 Auxiliary Building Leak Iodine Partition Factor 7.5E-3 Gas Vaste System Particulate Release Fraction 0.000 Auxiliary Building Charcolodine Release Fraction 1.000 Particulate Release Fraction 1.000 Containment Volume (million cu-ft) 1.800 2,000 Frequency Of Primary Coolant Degassing (times /yr)

Primary To Secondary Leak Rate (lb/ day) 100.000 There Is A Kidney Filter Containment Atmospncre Cleanup Rate (thousand efm) 2.000 Purge Time Of Contai. ment (hours) 8.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gas /lig) In Steam Generator 0.010 Frequency Of Containment Building High Vol Purge (times /yr)* 4.000 Containment Volume Purge Iodine Release Fraction 1.000 Particulate Release Fraction 1.000 Steam Leak To Turbine Building (1bs/hr) 1700.000 Fraction Iodine Released From Blovdown Tank Vent 0.000 Fraction Iodine Released From Main Condensate Air Ejector 0.440 There Is Not A Cryogenic Off Gas System l

• 2 cold and 2 hot purges B-4 ISSUE 3

BV-1 and 2 ODCM APPENDIX B l TABLE 1.2b INPUTS TO SVEC GASlBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PVR INPUTS PVR Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel Vith Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 '

Number Of Steam Generators 3.000 Total Steam Flov (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 i Mass Of Liquid In Each Steam Generator (thousand Ibs) 100.000 Total Mass Of Secondary Coolant (thousand lbs) 2000.000 '

Mass Of Vater In Steam Generator (thousand Ibs) 298.000 Blowdown Rate (thousand lbs/hr) 22.300 Primary To Secondary Leak Rate (lbs/ day) 100.000

~

Fission Product Carry-Over Fraction .001 '

Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction .700 Padvaste Dilution Flov (thousand gpm) 7.800 BV-2 GASEOUS VASTE INPUTS k '

There Is Not Continuous Stripping Of Full Letdown Flov Hold Up Time For Xenon (days) 45.800 Hold Up Time For Krypton (days) 2.570 Primary Coolant Leak To Auxiliary Building (Ib/ day) 160.000 '

Auxiliary Building Leak Iodine Partition Factor 7.5E-3 Gas Vaste System Particulate Release Fraction 0.000 Auxiliary Building Charcolodine Release Fraction 0.100 Particulate Release Fraction 0.010 Containment Volume (million cu-ft) 1.800 Frequency Of Primary Coolant Degassing (times /yr) 2.000 Primary To Secondary Leak Rate (1b/ day) 100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand efm) 20.000 Purge Time Of Containment (hours) 8.000 There Is Not A Condensate Demineralizer ,

Iodine Partition Factor (gas /lig) In Steam Generator 0.010 Frequency Of Containment Building High Vol Purge (times /yr)* 4.000 Containment Volume Purge Iodine Release Fraction 1.000 Particulate Release Fraction 1.000 Steam Leak To Turbine Building (lbs/hr) - 1100.000 Fraction Iodine Released From Blovdown Tank Vent 0.000 Fraction Iodine Released From Main Condensate Air Ejector 0.270 There Is Not A Cryogenic Off Gas System

• 2 cold and 2 hot purges B-5 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS l

CONTROLS: DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these CONTROLS.

THERMAL POVER 1.2 THERMAL POVER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED T!IERMAL POWER 1.3 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2652 HVt.

OPERATIONAL MODE 1.4 An OPERATIONAL MODE shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1.

ACTION 1.5 ACTION shall be those additional requirements specified as corollary statements to each principal CONTROL and shall be part of the CONTROLS.

f OPERABLE - OPERABILITY 1.6 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY vhen it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electric power sources, cooling or seal vater, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related safety function (s).

REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

l r

C-1 ISSUE 3

BV-1 and 2 ODCM l

AFFENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS (continued) i CHANNEL CALIBRATION l 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the  ;

channel output such that it responds with the necessary range and accuracy  !

to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other l indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL TEST 1.11 A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (uci/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, Revision 1, 1977 or Table III of TID 14844.

FREQUENCY NOTATION 1.21 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

4 C-2 ISSUE 3

i BV-1 and 2 ODCM l i

APPENDIX C  :

I ODCM CONTROLS l

CONTROLS: DEFINITIONS (continued) c 0FFSITE DOSE CALCULATION MANUAL (ODCM) 1.30 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology l and parameters used in the calculation of offsite doses resulting from -

radioactive gaseous and liquid effluents, in the calculation of gaseous  !

and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of '

the Environmental Radiological Monitoring Program. The ODCM shall also i contain (1) the Radioactive Effluent Controls and Radiological i Environmental Monitoring Programs required by Section 6.8.6 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent ,

Release Reports required by TS 6.9.1.10 and 6.9.1.11.  ;

4 GASEOUS RADVASTE TREATMENT SYSTEM 1.31 A GASEOUS RADVASTE TREATMENT SYSTEM is any system designed and installed l to reduce radioactive gaseous effluents by collecting primary coolant i system offgases from the primary system and providing for delay or holdup j for the purpose of reducing the total radioactivity prior to release to ,

the environment. .

t VENTILATION EXHAUST TREATMENT SYSTEM l i 1.32 VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed ,

to reduce gaseous radiolodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal l absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble j gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup j systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. .

PURGE-PURGING l i

1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration,- '

or other operating conditions, in such a manner that replacement air or  !

gas is required to purify the confinement.

VENTING j i

1.34 VENTING is the controlled process of discharging air' or gas from a .j l confinement to maintain temperature, pressure, humidity, concentration or 1 other operating conditions, in such a manner that replacement air or gas. l is not provided or required during VENTING. Vent, used'in system names, does not imply a VENTING process. ,

i

?

I C-3 ISSUE 3 I

- s

,,~,

BV-1 and 2 ODCM ,

APPENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS (continued)

MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l occupationally associated with the plant. This category does not include employees of the utility, its contractors, or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries and persons who traverse portions of the site as the consequence of a public highway, railway, or waterway located within the confines of the site boundary. This category does include persons who use portions of the site for recreational, occupational, or other purreses not associated with the plant.

SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. (See Figure 5-1)

UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

I C-4 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 1.1

}

OPERATIONAL MODES REACTIVITY  % RATED AVERAGE COOLANT MODE CONDITION, K THERMAL POWER

• TEMPERATURE ff

1. Power Operation 10.99 >5% >350*F

2. Startup >0.99 35% 2350*F

3. Hot Standby <0.99 0 >350*F

4. Hot Shutdown <0.99 0 350*F >T

>200*F AVE

5. Cold Shutdown <0.99 0 3200*F

6. Refueling ** <0.95 0 $140'F l

l g

• Excluding decay heat.

P ** Reactor vessel head unbolted or removed and fuel in the vessel. j l

l C-5 ISSUE 3 I

l l

BV-1 and 2 ODCM APPENDIX C ODCM CONTFOLS TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> V At least once per 7 days M At least once per 31 days 0 At least once per 92 days SA At least once per 184 days R At least once per 18 months S/U Prior to each reactor startup l

P Completed prior to each release N.A. Not applicable 4

C-6 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: APPLICABILITY 3.0.1 Compliance with the CONTROLS in the succeeding CONTROLS is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the CONTROL, the associated ACTION requirements shall be met.

3.0.2 Non-compliance with a CONTRO:. shall exist when the requirements of the CONTROL and associated ACTION requirements are not met within the specified time intervals. If the CONTROL is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a CONTROL is not met except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the CONTROL does not apply by placing it, as applicable, in:

1. At least HOT STANDBY vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN vithin the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUTDOWN vithin the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Vhere corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the

)

specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these requirements are stated in the individual CONTROLS.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the CONTROL are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them perrits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual CONTROLS.

C-7 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allovable extension not to exceed 25% of the surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute non-compliance with the OPERABILITY requirements for a CONTROL. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allovable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the CONTROL has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

1 C-8 ISSUE 3

g BV-1 and 2 ODCM ,

J APPENDIX C ODCM CONTROLS I

C0f7TROLS : RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3.3.3.9 In accordance with BV-1 and BV-2 Technical Specification 6.8'.6a, Item 1, the radioactive liquid effluent monitoring instrumentation channels shown in Appendix C, Table 3.3-12 shall be OPERABLE vith their alarm / trip setpoints set to ensure that the limits of Appendix C CONTROL ~3.11.1.1 are not exceeded. The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with Section 1.1.1 and 1.1.2 of this manual.

Applicability:

During releases through the flow path.

Action:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or correct the alarm / trip setpoint.

b. Vith one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Appendix C, Table 3.3-12 or g conservatively reduce the alarm setpoint. Exert a best effort to return the -

channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Fach radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Appendix C, Table 4.3-12.

l l C-9 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-12 BV-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Gross Activity Monitors Providing Automatic Termination of Release

a. Liquid Vaste Effluents Monitor (RM-LV-104) (1) 23 Liquid Vaste Contaminated Drain Monitor (RM-LV-116) (1) 23 b.

I

c. Auxiliary Feed Pump Bay Drain Monitor (RM-DA-100) (1) 24

2. Gross Activity Monitors Not Providing Termi. nation Of Release

a. Component Cooling-Recirculation Spray Heat (1) 24 Exchangers River Vater Monitor (RM-RV-100) 1

3. Flov Rate Measurement Devices Liquid Radvaste Effluent Line (1) 25 a.

(1) FR-LV-103/RM-LV-116 (2) FR-LV-104/RM-LV-104

b. Cooling Tower Blovdown Line (1) 25 j 1

(1) FT-CV-101 (2) FT-CV-101-1

4. Tank Level Indicating Devices (for tanks outside l plant building)

a. Primary Vater Storage Tank (BR-TK-6A) (1) 26

b. Primary Vater Storage Tank (BR-TK-6B) (1) 26

c. Steam Generator Drain Tank (LV-TK-7A) (1) 26 (1) 26

d. Steam Generator Drain Tank (LV-TK-7B)

C-10 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-12 (continued) l BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release

a. Liquid Vaste Process Effluent Monitor (2SGC-R0100) (1) 23

2. Gross Radioactivity Monitors Providing Alarm But Not Providing Termination Of Release None

3. Flow Rate Measurement Devices

a. Liquid Radvaste Effluent (2SGC-FS100) (1) 25

b. Cooling Tower Blovdown Line (2CVS-FT101) (1) 25

4. Tank Level Indicating Devices (for tanks outside l plant buildings)

None I

1 l

Ik i C-11 ISSUE 3 ,

I i

4

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-12 (continued)

ACTION STATEMENTS l

Action 23 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Appendix C SURVEILLANCE REQUIREMENT 4.11.1.1.1, and

2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving.

Otherwise, suspend release of radioactive effluents via this pathway.

Action 24 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are analyzed for gross radioactivity (beta or gamma) at a Lover Limit of Detection (LLD) of at least lE-7 uC1/ml.

Action 25 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathvay may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to estimate flov.

Action 26 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank.

C-12 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm And Automatic Termination Of Release

a. Liquid Radvaste Effluent Line D P(5) R(3) 0(1)

(RM-LV-104)

b. Liquid Vaste Contaminated D P(5) R(3) 0(1)

Drain Line (RM-LV-116)

c. Auxiliary Feed Pump Bay D D R(3) O(6)

Drain Monitor (RM-DA-100)

2. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Termination g Of Release

a. Component Cooling - D M(5) R(3) O(2)

Recirculation Spray Heat Exchangers River Vater Monitor (RM-RV-100)

3. Flow Rate Monitors

a. Liquid Radvaste Effluent Lines D(4) NA R 0 (1) FR-LV-103/RM-LV-116 (2) FR-LV-104/RM-LV-104

b. Cooling Tover Blowdown Line D(4) NA R 0 (FT-CV-101, 101-1) i l

l l

C-13 ISSUE 3 l

l

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)

BV-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

4. Tank Level Indicating Devices (for tanks outside plant buildings)

a. Primary Vater Storage Tank D* NA R 0 (BR-TK-6A)

b. Primary Water Storage Tank D* NA R 0 (BR-TK-6B)

c. Steam Generator Drain Tank D* NA R 0 (LV-TK-7A)

d. Steam Generator Drain Tank D* NA R 0 (LV-TK-7B) el I

• During liquid additions to the tank.

C-14 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)

BV-2 RADIOACTIVE LIQUID EFFLUENT MOPITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release

a. Liquid Vaste Process Effluent D P(5) R(8)(3) O(7)

(2SGC-R0100)

2. Flow Rate Measurement Devices

a. Liquid Radvaste Effluent D(4) NA R Q (2SGC-FS100)

b. Cooling Tower Blowdown Line D(4) NA R 0 (2CVS-FT101)

3. Tank Level Indicating Devices (for tanks outside plant buildings)

None D

C-15 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathvay and Control Room Alarm Annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Dovnscale failure.

3. Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm / trip setpoint.

2. Downstale failure.

3. Instrument controls are not set in operate mode.

(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards j that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages.

(Existing plants may substitute previously established calibration procedures for this requirement).

(4) CHANNEL CHECK shall consist of verifying indication of flov during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

(5) A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtain an upscale increase in the existing count rate to verify channel response.

I C-16 ISSUE 3

BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)

TABLE NOTATION (6) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs when the instrument indicates measured levels above the Alarm / Trip Setpoint.

The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Alarm Annunciation occurs if any of the following conditions exists:

1. Downscale failure.

2. Instrument controls are not set in operate mode.

(7) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation the of this pathvay and Control Room Alarm Annunciation occurs if instrument indicates measured levels above the alarm / trip setpoint.

(8) The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm l

Annunciation occurs if either of the following conditions exist:

l l 1. Downscale failure.

l Instrument controls are not set in operate mode.

2.

)

C-17 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3.3.3.10 In accordance with BV-1 and BV-2 Technical Specification 6.9.6a, Item 1, the radioactive gaseous effluent monitoring instrumentation channels shown in Appendix C, Table 3.3-13 shall be operable with their alarm / trip setpoints set to ensure that the limits of Appendix C CONTROL 3.11.2.1 are not exceeded. The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with Section 2.1 of this manual.

Applicability:

During releases through the flow path.

Action:

a. Vith a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which vill ensure that the limits of Appendix C CONTROL 3.11.2.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm / trip setpoint.

b. Vith one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Appendix C, Table 3.3-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the k, channel to operable status within 30 days, and if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. The provisions of Appendix C CONTROL 3.0.3 are not applicable. Il SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Appendix C, Table 4.3-13.

{

1 1

C-18 ISSUE 3 l

l I

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 BV-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION

1. Gaseous Vaste/

Process Vent System (RM-GV-108A&B)

a. Noble Gas (1)

• Radioactivity Rate 27,30***

Activity Monitor Measurement

b. Particulate (1)

• 32 Activity Monitor

c. System Effluent (1)

• System Flow Rate 28 Flow Rate Measurement Measuring Device (FR-GV-108)

d. Sampler Flov (1)

• Sampler Flov Rate 28 h

F Rate Measuring Device Measurement

2. Auxiliary Building Ventilation System (RM-VS-101A&B)

a. Noble Gas (1)

• Radioactivity Rate 29,30***

Activity Monitor Measurement

b. Particulate (1)

• 32 Activity Monitor

c. System Effluent (1)

• System Flow Rate 28 Flow Rate Measurement Measuring Device (FR-VS-101)

d. Sampler Flow (1)

• Sampler Flow Rate 28 Rate Measuring Measurement Device l

• During Releases via this pathway.

• • • During purging of Reactor Containment via this pathvay.

l C-19 ISSUE 3

BV-1 and 2 ODCM APPENDIX C i ODCM CONTROLS ]

TABLE 3.3-13 (continued)

BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION

3. Reactor Building /

Supplementary Leak Collection And Release System (RM-VS-107A&B)

a. Noble Gas (1)

• Radioactivity Rate 29,30***

Activity Monitor

b. Particulate (1)

• 32 Activity Monitor

c. System Effluent (1)

• System Flow Rate 28 Flow Rate Measurement Measuring Device (FR-VS-ll2)

d. Sampler Flov (1)

• Sampler Flow Rate 28 I Rate Measuring Measurement Device 1

l I

i I

l l

1 C-20 ISSUE 3

BV-1 ond 2 ODCM APPENDIX C ODCH CONTROLS TABLE 3.3-13 (continued)

BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 1 MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION _

1. Ventilation System (2HVS-R0101A&B)

a. Noble Gas 1

• Radioactivity Rate 29,30***

Activity Monitor Measurement

b. Particulate 1

• 32 Activity Monitor

c. Process Flov 1

• Process Flow Rate 28 Rate Monitor Measurement

d. Sampler Flov 1

• Sampler Flow Rate 28 i

Rate Monitor Measurement

2. Elevated Release (2HVS-R0109A&B) ,

t

a. Noble Gas 1

• Radioactivity Rate 29,30***

Activity Monitor Measurement ,

1

b. Particulate 1

• 32 Activity Monitor

c. Process Flov 1

• Process Flow Rate 28 ,

Rate Monitor Measurement

d. Sampler Flov 1

• Sampler Flow Rate 28 Rate Monitor Measurement

3. Decontamination Bldg.

Vent (2RM0-R0301A&B)

a. Noble Gas 1

• Radioactivity Rate 29 Activity Monitor Measurement

b. Particulate 1

• 32 Activity Monitor  :

c. Process Flov 1

• Process Flow Rate 28 Rate Monitor Measurement  ;

d. Sampler Flov 1

• Sampler Flov Rate 28 Rate Monitor Measurement 1

C-21 ISSUE 3 I

r

BV-1 cnd 2 ODCM {

APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued)

BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMEi31 OPERABLE APPLICABILITY PARAMETER ACTION l l

4. Condensate Polishing i Building Vent l (2HVL-R0112A&B) j l

a. Noble Gas 1

• Radioactivity Rate 29 -)

Activity Monitor Measurement

b. Particulate 1

• 32 Activity Monitor

c. Process Flov 1

• Process Flow Rate 28 j Rate Monitor Measurement j l

d. Sampler Flow 1

• Sampler Flow Rate 28 )

Rate Monitor Measurement ]

I S. Vaste Gas Storage Vault i (2RM0-R0303A&B) j

a. Noble Gas 1

• Radioactivity Rate 29 Activity Monitor Measurement

b. Particulate 1

• 32 Activity Monitor I

c. Process Flov 1

• Process Flov Rate 28 Rate Monitor Measurement

d. Sampler Flov 1

• Sampler Flov Rate 28 Rate Monitor Measurement  !

l C-22 ISSUE 3

i BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued)

ACTION STATEMENTS Action 27 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank :y be released to the environment provided that prior to initiating the release:

1. At least two independent samples of the tank's content are analyzed and at least two technically qualified members of the Pacility Staff independently verify the release rate calculations  !

and discharge valve lineup, or j

2. Initiate continuous monitoring with a comparable alternate !

monitoring channel. Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this technical specification requirement.

Otherwise, suspend releases of radioactive effluents via this pathway.

Action 28 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Action 29 Vith the number of chsnnels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided:

1. Grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or

2. Initiate continuous monitoring with a comparable alternate monitoring channel. Surveillance requirements applicable to the inoperable channel shall apply to the comparable alternate monitoring channel when used to satisfy this ODCM CONTROL requirement.

Action 30 APPLICABLE POR PURGES OF THE BV-1 REACTOR CONTAINMENT Vith the number of channels OPERABLE less than required by minimum Channels OPERABLE requirement, immediately suspend PURGING of Reactor Containment via this pathway if both RM-VS-104A and B are not operable with the purge / exhaust system in service.

C-23 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued)

ACTION STATEMENTS Action 30 APPLICABLE FOR PURGES OF THE BV-2 REACTOR CONTAINMENT Vith the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, immediately suspend purging of Reactor Containment via this pathway.

Action 32 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Appendix C, Table 4.11-2 or sampled and analyzed once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

1 C-24 ISSUE 3 l

BV-1 and 2 ODCM ,

i APPENDIX C ODCM CONTROLS TABLE 4.3-13 l

BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS t CHANNEL l CHANNEL SOURCE CHANNEL FUNCTIONAL !

INSTRUMENT CHECK CliECK CALIBRATION TEST  !

1. Gaseous Vaste/ Process Vent System  ;

(RM-GV-108A&B) j

a. Noble Gas Activity Monitor P P(4) R(3) 0(1) h

b. Particulate Activity Monitor V NA NA NA.  :

c. System Effluent Flov Rate P NA R 0 ,

Measuring Device (FR-GV-108) l

d. Sampler Flov Rate Measuring D* NA R 0 Device

2. Auxiliary Building Ventilation I System (RM-VS-101A&B) ,

t l

a. Noble Gas Activity Monitor D M(4), R(3) O(2)

P(4)***

b. Particulate Activity Monitor V NA NA NA i r

c. System Effluent Flov Rate D NA R 0 Measurement Device (FR-VS-101)

d. Sampler Flow Rate Measuring D NA R O' Device  :

3. Reactor Building / Supplementary Leak Collection And Release System (RM-VS-107A&B)

a. Noble Gas Activity Monitor D M(4), R(3) 0(2)

P(4)***

b. Particulate Activity Monitor V N/A N/A N/A

c. System Effluent Flow Rate D N/A R Q Measuring Device (FR-VS-112)

d. Sampler Flow Rate Measuring D N/A R 0 l Device t

• During releases via this pathway.

co*During purging of Reactor Containment via this pathway.

C-25 ISSUE 3 p

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS l t

TABLE 4.3-13 (continued) I i

BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING ,

INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL -

CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Ventilation System (2HVS-R0101A&B)

a. Noble Gas Activity Monitor D M(4), R(3)(6) 0(5) l P(4)*** ,

b. Particulate Activity Monitor V NA NA NA

c. Process Flow Rate Monitor D NA R 0 .

d. Sampler Flow Rate Monitor D NA R 0

2. Elevated Release (2HVS-R0109A&B)  ;

i

a. Noble Gas Activity Monitor D M(4), R(3)(6) O(5)

P(4)***

b. Particulate Activity Monitor V NA NA NA

c. Process Flov Rate Monitor D NA R 0

d. Sampler Flov Rate Monitor D NA R Q

3. Decontamination Bldg. Vent (2RMO-R0301A&B)

a. Noble Gas Activity Monitor D M(4) R(3)(6) 0(5)

b. Particulate Activity Monitor V NA NA NA

c. Process Flow Rate Monitor D NA R 0

d. Sampler Flow Rate Monitor D NA R 0

4. Condensate Polishing Building Vent (2EVL-R0112A&B)

a. Noble Gas Activity Monitor D M(4) R(3)(6) Q(5)

b. Particulate Activity Monitor V NA N/A NA

c. Process Flov Rate Monitor D NA R 0

d. Sampler Flov Rate Monitor D NA R 0 C-26 ISSUE 3

BV-1 ond 2 ODCM APPENDIX C  ;

ODCM CONTROLS TABLE 4.3-13 (continued)

BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST I

5. Vaste Gas Storage Vault (2RH0-R0303A&B)

a. Noble Gas Activity Monitor D M(4) R(3)(6) O(5)

b. Particulate Activity Monitor V NA NA NA

c. Process Flow Rate Monitor D NA R Q ,

d. Sampler Flow Rate Monitor D NA R 0 '

F e

f b

l C-27 ISSUE 3 o

i BV-1 and 2 ODCM  !

APPENDIX C l l

ODCM CONTROLS TABLE 4.3-13 (continued)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the ]

following conditions exist. ,

l

a. Instrument indicates measured levels above the alarm / trip setpoint.

b. Downscale failure.

c. Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exist:  ;

a. Instrument indicates measured levels above the alarm / trip setpoint.

b. Downscale failure,

c. Instrument controls not set in operate mode, t

(3) The initial CHANNEL CALIBRATION for radioactivity measurement i instrumentation shall be performed using one or more of the reference j standards certified be National Bureau of Standards or using standards that "

have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months.

This can normally be accomplished during refueling outages.

(4) A SOURCE CHECK may be performed utilizing the installed means or flashing the detector with a portable source to obtair, an upscale increase in the existing count rate to verify channel response.

(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if the instrument indicates measured levels above the ,

alarm / trip setpoint.

(6) The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm Annunciation occurs if either of the following conditions exist:

1. Downscale failure.

2. Instrument controls are not set in operate mode. -

i l

l C-28 ISSUE 3 j

BV-1 and 2 ODCM APPENDIX C l ODCM CONTROLS D CONTROLS: LIQUID EFFLUENT CONCENTRATION l

I 3.11.1.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 2 and 3, the concentration of radioactive material released at any time from the site (see Figure 5-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 uC1/ml total activity.

Applicability:

At all times.

Action:

a. Vith the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore the concentration within the above limits, and

b. Submit a Special Report to the Commission within 30 days in accordance with Technical Specification 6.9.2f.

c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

k SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid vastes shall be sampled and analyzed according to the sampling and analysis program of Appendix C, Table 4.11-l*.

4.11.1.1.2 The results of radioactive analysis shall be used in accordance with the methods of Section 1.2 of this manual to assure that the concentration at the point of release are maintained within the limits of Appendix C CONTROL 3.11.1.1.

4.11.1.1.3 Vhen the activity of the BV-1 secondary coolant is greater than IE-5 uCi/ml gross, grab samples shall be taken for each sump discharge from the turbine building and chemical vaste sumps. The sample shall be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml and recorded in plant records. Vater volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.

C-29 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (continued) l 4.11.1.1.4 When the activity of the BV-2 secondary coolant is greater than 1E-5 uCi/ml gross and the Turbine Building transfer pumps (2DBS-P42, 2DBS-P43, 2DBS-P44) are not pumping their sumps to the steam generator blovdown tank (2SGC-TK21B), grab samples shall be taken for each sump discharge from the turbine building. The sample shall be analyzed for gross activity at a sensitivity of at least lE-7 uCi/ml and recorded in plant records. Water volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.

4.11.1.1.5 Prior to the BV-2 Recirculation Drain Pump (s) (2DAS-P215A/B) discharging to catch basin 16, a grap sample vill be taken. The samples vill be analyzed for gross activity at a sensitivity of at least 1E 7 uCi/ml. Vater volume discharged shall be estimated from the r, umber of pump operations unless alternate flov or volume instrumentation is provided.

I el l

+ Radioactive liquid discharges are normally via batch modes. BV-1 and BV-2 Turbine Building Drains shall be monitored as specified in Appendix C l SURVEILLANCE REQUIREMENT 4.11.1.1.3 and 4.11.1.1.4. The BV-2 Recirculation drain pump discharge shall be monitored as specified in Appendix C SURVEILLANCE REQUIREMENT 4.11.1.1.5 respectively.

C-30 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS i

TABLE 4.11-1 I

RADIOACTIVE LIQUID VASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY LOVER LIMIT TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION (LLD)

(uCi/ml)*

A. Batch Vaste d P r ncipal Gamma E-7 h h f Release Tanks Each Batch Each Batch Emitters I-131 1E-6 P M Dissolved And IE-5 h

One Batch /M Entrained Gases (Gamma Emitters)

P M H-3 1E-5 h b Each Batch Composite Gross' Alpha IE-7 P 0 Sr-89, Sr-90 SE-8 h b Each Batch Composite D Fe-55 IE-6 g Principal Gamma SE-7 B.ContinuogE Grab Sample V c f Releases Composite Emitters I-131 lE-6 g IE-5 Grab Sample M Dissolved And Entrained Gases (Gamma Emitters)

Grab Sample E H H-3 1E-5 c

Composite Gross Alpha IE-7 g Sr-69, Sr-90 SE-8 Grab Sample 0 c

Composite Fe-55 1E-6 I

C-31 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-1 (continued)

TABLE NOTATION

a. The LLD is the smallest concentration of radioactive material in a sample that vill be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal, j For a particular measurement system (which may include radiochemical  !

separation): 1 1

LLD = 4.66 S l (E)(V)(2.22)(Y)b p T) where:

LLD is the lover limit of detection as defined above (as pCi per unit  ;

mass or volume);

s is the standard deviation of the background counting rate or of the cbuntingrateofablanksampleasappropriate(ascountsperminute);

E is the counting efficiency (as counts per transformation);

V is the sample size (in units of mass or volume);

2.22 is the number of transformations per minute per picoeurie; 1 Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; oT is the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples).

1 The value ofg s used in the calculation of the LLD for a detection g I

system shall b6 based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as i appropriate) rather than on an unverified theoretically predicted variance. Typical values of E. l V, Y and oT should be used in the p '

calculations.

The LLD is defined as an a priori (before the fact) limit representing the capability of a r na-Jrement system and not as a posteriori (after the fact) limit for a ~ticular measurement.

C-32 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS t TABLE 4.11-1 (continued)

TABLE NOTATION

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid vaste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released,

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

d. A batch release exists when the discharge of liquid vastes is from a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

e. A continuous release exists when the discharge of liquid vastes is from a non-discrete volume; e.g., from a volume of a system having an input flow during the continuous release. For BV-1, this is applicable to the Turbine Building drains and the AFV Pump Bay Drain System and chemical vaste sump, when the secondary coolant gross radioactivity (beta and gamma) is greater than 1E-5 uCi/ml. For BV-2, this is applicable to the Turbine Building I drains when the secondary coolant gross radioactivity (beta and gamma) is greater than lE-5 uCi/ml.

f. The principal gamma emitters for which the LLD specification vill apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are belov the LLD for the analyses should be reported as "less than" the nuclide's LLD, and should not be reported as being present at the LLD level for ths: nuclide. The "less )g than" values should not be used in the required dose calculations. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.

g. Vhenever there is primary to secondary leakage, sampling is done for Turbine )(

Building drain effluents by means of grab samples taken every four hours during the period of discharge and analyzed for gross radioactivity (beta and gamma) at a sensitivity of at least lE-7 uCi/ml and recorded in the plant records, along with the flow rate. Primary to secondary leakage is considered to be occurring whenever measurements indicate that secondary coolant gross radioactivity (beta and gamma) is greater than 1E-5 uCi/ml.

In addition, two (2) plant personnel shall check release calculations to verify that the limits of Appendix C CONTROLS 3.11.1.1 and 3.11.1.2 are not -

exceeded.

k C-33 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-1 (continued)

TABLE NOTATION

h. Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling vill be performed by means of a grab sample taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during pump operation.

1 4

C-34 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 4 and 5, the dose or dose commitment to MEMBER (S) 0F THE PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see Figure 5-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

Applicability:

At all times.

Action:

a. Vith the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases, and the D proposed corrective actions to be taken to assure the subsequent releases vill be within the above limits. (This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Vater Act).*

b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordante with Section 1.3 of this manual at least once per 31 days.

g

• Applicable only if drinking water supply is taken from the receiving water bod:.

within three miles of the plant discharge (three miles downstream only).

C-35 ISSUE 3

BV-1 and 2 ODCM i

APPENDIX C l ODCM CONTROLS CONTROLS: LIQUID RADVASTE TREATMENT SYSTEM 3.11.1.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the Liquid Radvaste Treatment System shall be used to reduce the radioactive materials in each liquid vaste batch prior to its discharge when the projected doses due to liquid effluent releases from the reactor unit (see Figure 5-1) when averaged over 31 days vould exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

Applicability:

At all times.

Action:

a. With liquid vaste being discharged without treatment and exceeding the limits specified, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2f a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason I for inoperability.

4

2. Action (s) taken to restore the inoperable equipment to operational status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 1.3 of this manual.

l C-36 ISSUE 3

I BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: GASEOUS EFFLUENT DOSE RATE 3.11.2.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 3 and 7, the dose rate in the unrestricted areas (see Figure 5-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be 3 500 mrem /yr to the total body and 3 3000 mrem /yr to the skin *, and

b. The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C'14) with half-lives greater than eight days shall be 3 1500 mrem /yr to any organ.

Applicability:

At all times.

Action:

a. Vith the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limits (s), and

b. Submit a Special Report to the Commission within 30 days pursuant to Technical Specification 6.9.2f.

c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with Section 2.2 of this manual.

4.11.2.1.2 The dose rate, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Appendix C Table 4.11-2.

• During containment purge the dose rate may be averaged over 960 minutes.

C-37 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-2 RADIOACTIVE GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM i

MINIMUM LOVER LIMIT OF  ;

SAMPLING ANALYSIS TYPE OF DETECTION (LLD)

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)^

A. Vaste Gas Storage P P Principal Gamma 1E-4 Tank Each Tank Each Tank Emittersg Grab Sample H-3 1E-6 B. Containment Purge P P b

Principal Gamma lE 4 b

Each Purge Each Purge Emitters Grab Sample H-3 1E-6 C. Ventilagion M M Principal Gamma 1E-4 Systems Grab Sample EmittersE

1. Unit 1 Ventila-tion Vent H-3 lE-6

2. Unit 1 Contain-ment /SLCRS Vent

3. Unit 1/2 Process Vent 4 Unit 2 Ventila-tion Vent

5. Unit 2 Contain-ment /SLCRS Vent

6. Unit 2 Decon.

Bldg. Vent

7. Unit 2 Vaste Gas Storage Vault Vent

8. Unit 2 Condensate Polishing Bldg.

Vent l

l l

C-38 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-2 (continued)

RADIOACTIVE GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM 4

MINIMUM LOVER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION,(LLD)

GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)

D. All Systems Continuous I

V I-131 1E-12 Listed Above Charcoal Which Produce Sample I-133 1E-10 Continuous Release Continuous I

V Principal Gamma IE-11 E

Particulate Emitters Sample (I-131, others) f Gross Alpha 1E-11 Continuous M Composite Particulate Sample Continuous f

0 Sr-89, Sr-90 1E-11 Composite Particulate Sample I Noble Gas Noble Gases 1E-6 Continuous Monitor Gross Beta And Gamma l

l ISSUE 3 l

C-39  ;

i

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-2 (continued) l TABLE NOTATION

a. The Lower Limit of Detection (LLD) is defined in Table Notation (a) of Appendix C, Table 4.11-1 of Appendix C CONTROL 4.11.1.1.

b. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POVER change exceeding 15% of RATED THERMAL POVER vithin a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. This requirement does not apply if (1) analysis shows that the Dose Equivalent I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

c. Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (from the appropriate ventilation release path) when the refueling canal is flooded.

d. Samples shall be changed at least once per 7 days and analyses shall be completed vithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15%

of RATED THERMAL POVER vithin a 1 hour- period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10.

This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more l than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

f. The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Appendix C CONTROLS 3.11.2.1, 3.11.2.2, and 3.11.2.3.

g. The principal gamma emitters for which the LLD specification vill apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present }/

at the LLD level for that nuclide. Vhen unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report. /

h. Only when this release path is in use. /

C-40 ISSUE 3

BV-1 and 2 ODCM APPEiiDIX C ODCM CONTROLS h

CONTROLS: DOSE-NOBLE GASES 3.11.2.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 5 and 8, the air dose from the reactor unit in unrestricted areas (see Figure 5-1) due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to 5 5 mrad for gamma radiation and

< 10 mrad for beta radiation.

b. During any calendar year, to 3 10 mrad for gamma radiation and

< 20 mrad for beta radiation.

Applicability:

At all times.

Actions

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission with in 30 days, pursuant to Technical Specification 6.9.2f, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases will be within the above limits,

b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with Section 2.3 of this manual at least once every 31 days.

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C 41 ISSUE 3 l

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: DOSE-RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES I i 3.11.2.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 5 and 9, the dose to MEMBER (S) 0F THE PUBLIC from radiciodines and radioactive materials in particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see Figure 5-1) shall be limited to the following:

a. During any calendar quarter to $ 7.5 mrem to any organ, and

b. During any calendar year to 3 15 mrem to any organ.

Applicability:

At all times.

Action:

a. Vith the calculated dose from the release of radiciodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases vill be within the above limits.

b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with Section 2.3 of this manual at least once every 31 days.

C-42 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS k

CONTROLS: GASEOUS RADVASTE TREATHENT SYSTEM 3.11.2.4 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the Gaseous Radvaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see Figure 5-1), when averaged over 31 days, would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge when the projected doses due to gaseous effluent releases from the reactor unit (see Figure 5-1) when averaged over 31 days would exceed 0.3 mrem to any organ.

Applicability:

At all times.

Action:

a. With gaseous vaste being discharged without treatment and in excess of the j

above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report which includes the following information.

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken 'o restore the inoperable equipment to operational status, and

3. Summary description of setion(s) taken to prevent a recurrence.

b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS _

4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 2.3 of this manual.

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BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS I

CONTROLS: TOTAL DOSE 3.11.4.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to 3 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to f 75 mrems.

Applicability:

At all times. I Action: i i

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Appendix C CONTROL 3.11.1.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.11.2.3a, or 3.11.2.3b, j calculations shall be made including direct radiation contributions from the 1 units (including outside storage tanks, etc.) to determine whether the above limits of Appendix C CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and inc3udes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation  ;

exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, '

including all effluent pathways and direct radiation, for the calendar year  ;

that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

b. The provisions of Appendix C CONTROL 3.n.3 are not applicable.

C 44 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.11.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Appendix C SURVEILLANCE 4.11.1.2.a, 4.11.1.2.b, 4.11.2.2.a, 4.11.2.2.b, REQUIREMENTS 4.11.2.3.a, and 4.11.2.3.b.

4.11.4.1.2 Cumulative dose contributions from direct radiation from the units (including outside storage tanks, etc.) shall be determined in accordance with Section 4 of this manual. This requirement is applicable only under conditions set forth in Action a. of Appendix C CONTROL 3.11.4.1.

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C 45 ISSUE 3

GV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.12.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 1, the radiological environmental monitoring program shall be conducted as specified in Appendix C, Table 3.12-1.

Applicability:

At all times.

Action:

a. Vith the radiological environmental monitoring program not being conducted as specified in Appendix C, Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.

b. Vith the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Appendix C, Table 3.12-1 exceeding the "

limits of Appendix C, Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to Technical Specification 6.9.2f which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Appendix C, Table 3.12-2 to be exceeded. This report is not required if the measured level of radioactive was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report.

When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

Concentration (1) Concentration (2)

Limit Level (1) + Limit Level (2) + . . . > 1.0

c. With milk or fresh leafy vegetable samples unavailable from the required number of locations selected in accordance with Appendix C C0!iTROL 3.12.2 and listed in the ODCH, obtain replacement samples. The locations from which samples were unavailable may then be deleted from those required by Appendix C, Table 3.12-1 and the nDCM provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, if available.

d. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

C-46 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS h

SURVEILLANCE REQUIREMENTS (continued) 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Appendix C, Table 3.12-1 from the locations given in the ODCM and shall be analyzed pursuant to be requirements of Appendix C, Tables 3.12-1 and 4.12-1.

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BV-1 and 2 ODCM APPENDIX C ,

ODCM CONTROLS TABLE 3.12-1 RADIOLOGICAL ENV1FONMENTAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHVAY NUMBER OF SAMPLES COLLECTION TYPE AND FREQUENCY (*)  ;

AND/0R SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS  ;

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1. AIRBORNE

a. Radiciodine 5 locations. Continuous opera- Each radiciodine l And tion of sampler canister.

Particulates 1. One sample from with sample col- l a control loca- lection at least Analyze for I-131; tion 10-20 weekly, miles distant Particulate sampler.

and in the least prevalent Analyze for gross (b);

beta weekly l

j vind direction.

Perform gamma isoto- l

2. One sample from pic analysis on vicinity of composite (by loca-community tion) sample at having the least quarterly.

highest calcu-lated annual average ground level D/0

2. DIRECT 40 locations. Continuous Gamma dose, RADIATION measurement with quarterly. l

> TLD or a pres- collection at i surized ion least quarterly.

chamber at each l location.

1 (a) Analysis frequency same as sampling frequency unless otherwise specified.

(b) Particulate samples are not counted for >24 hours after filter change.

Perform gamma isotopic analysis on each sample when gross beta is >10 times the yearly mean of control samples.

• • Sample locations are given on figures and tables in Section 3 of this manual.

C-48 ISSUE 3

BV-1 and 2 ODCM i APPENDIX C ODCM CONTROLS g

TABLE 3.12-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITOR *.NG FROGRAM SAMPLING AND EXPOSURE PATHVAY NUMBER OF SAMPLES COLLECTI3N TYPE AND FREQUENCY (#)

AND/0R SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS

3. VATERBORNE

a. Surface 2 locations. Composite

• sample Gamma isotopic collected over a analysis of each

1. One sample period not to composite sample; upstream. exceed 1 month.

Tritium analysis of

2. One sample composite sample at downstream. least quarterly.

b. Drinking 2 locations. Composite

• sample I-131 analysis of collected over a each composite period not to sample; e

exceed 2 weeks.

Gamma isotopic analy-sis of composite 1 sample (by location) monthly; f Tritium analysis of composite sample quarterly.

c. Groundvater N/A - No wells in lover elevations between plant and river.

d. Sediment From 1 location. Semi-annually. Gamma isotopic analy-Shoreline sis semi-annually.

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• Composite samples shall be collected by collecting an aliquot at intervals not exceeding two hours. )

++ Sample locations are given on figures and tables in Section 3 of this manual.

C 49 ISSUE 3 l

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APPENDIX C ODCM CONTROLS TABLE 3.12-1 (continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i

SAMPLING AND COLLECTION TYPE AND FREQUENCY I ")

EXPOSURE PATHVAY NUMBER OF SAMPLES AND/0R SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS

4. INGESTION

a. Milk 4 locations.IC) At least bi-veekly Gamma isotopic and when animals are I-131 analysis of

1. Three samples on pasture; at each sample, selected on least monthly at basis of other times.

highest poten-tial thyroid dose using milch census data.

2. One local large dairy.

b. bra 2 locations. Semi-annual. One Gamma isotopic sample of avail- analysis on edible able species. portions.

c. Food 4 locations. Annually at time Gamma isotopic Products of harvest, analysis and I-131 (Leafy 1. Three locations analysis on edible Vegetables) within 5 miles. portion.

2. One control location.

f"Analysisfrequencysameassamplingfrequencyunlessotherwisespecified.

c Other dairies may be included as control station or for historical continuity. These vould not be modified on basis of milch animal census.

• • Sample locations are given on figures and tables in Section 3 of this manual.

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE BROAD LEAF VATER OR GASES FISH MILK VEGETABLES ANALYSIS (pCi/l) (pCi/m ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET)

H-3 2E+4(*) . _ _ _ _ .

Mn-54 1E+3 3E+4 Fe-59 4E+2 1E+4 Co-58 1E+3 3E+4 Co-60 3E+2 1E+4 Zn-65 3E+2 2E+4 Zr/Nb-95 4E+2 I-131 2 0.9 3 1E+2 Cs-134 30 10 1E+3 60 1E+3 Cs-137 50 20 2E+3 70 2E+3 Ba/La-140 2E+2 3E+2 l

l h ( )For drinking water samples. This is a 40 CFR Part 141 value.

C-51 ISSUE 3 1

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.12-1 MAXIMUM VALUES FOR THE LOVER LIMITS OF DETECTION (LLD)a AIRBORNE PARTICULATE ANALYSIS VATER OR GAS FISH MILK FOOD PRODUCTS SEDIMENT (pCi/1) (pCi/m ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET) (pCi/kg, DRY)

Gross Beta 4 IE-2 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 c

Zr-95 30 e

Nb-95 15 b 60 I-131 l 7E-2 1 Cs-134 15 SE-2 130 15 60 150 Cs-137 18 6E-2 150 18 80 180 C

Ba-140 60 60 C

La-140 15 15 NOTE: This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported.

C-52 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.12-1 (continued)

TABLE NOTATION i

a. The LLD is the smallest concentration of radioactive material in a sample that vill be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD - 4.66 S (E)(V)(2.22)(Y)bexp(- AoT )

where:

LLD is the lover limit of detection as defined above (as pCi per unit mass or volume);

Sh is the standard deviation of the background counting rate or of the c5unting rate of a blank sample as appropriate (as counts per minute);

E is the counting efficiency (as counts per transformation);

V is the sample size (in units of mass or volume);

D 2.22 is the number of transformations per minute per picoeurie; Y is the fractional radiochemical yield (when applicable);

A is the radioactive decay constant for the particular radionuclide; oT is the elapsed time between sample collection (or end of the sample l

collection period) and time of counting (for environmental samples, not plant effluent samples).

The value ofhS used in the calculation of the LLD for a detection system shall b6 based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate ) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y and oT should be used in the calculations.

The LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.

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BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.12-1 (continued)

TABLE NOTATION

b. LLD for drinking vater.

c. If parent and daughter are totaled, the most restrictive LLD should be applied.

C-54 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - LAND USE CENSUS 3.12.2 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 2, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden

• of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. For elevated releases as defined in Regulatory Guide 1.111, (Rev. 1), July, 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.

Applicability:

At all times.

Action:

a. Vith a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Appendix C SURVEILLANCE REQUIREMENT 4.11.2.3, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the new location (s).

b. Vith a land use census identifying a milk animal location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) 20%

greater than at a location from which samples are currently being obtained in accordance with Appendix C CONTROL 3.12.1 prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The milk sampling program shall include samples from the three active milk animal locations, having the highest calculated dose or dose commitment. Any replaced location may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which vill provide the best results, such as by a door-to-door survey *+,

aerial survey, or by consulting local agriculture authorities.

• Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/0 in lieu of the garden census.

• • Confirmation by telephone is equivalent to door-to-door.

C-55 ISSUE 3

BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - INTERLABORATORY COMPARISON PROGRAM 3.12.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 3, analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program.

Applicability:

At all t;aes.

Action:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Report.

b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3.1 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report.

C-56 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS D BASES: INSTRUMENTATION 3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with Section 1 of this manual to ensure that the alarm / trip vill occur prior to exceeding the limits 3 of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 1 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive 1 materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with Section 2 of this manual to ensure that the alarm / trip vill occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the vaste gas holdup system. j D The OPERABILITY and use of this instrumentation is consistent with '

the requirements of General Design Criteria 60, 63, and 64 of l Appendix A to 10 CFR Part 50.  !

D-1 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: LIQUID EFFLUENTS 3/4.11.1.1 LIQUID EFFLUENT CONCENTRATION This CONTROL is provided to ensure that the concentration of radioactive materials released in Liquid vaste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site vill result in exposure within (1) the Section II. A design objectives of Appendix I, 10 CFR Part 30, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methot s described in International Commission on Radiological Protection (ICRP) Publication 2.

3/4.11.1.2 LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents vill be kept "as lov as is reasonably achievable." Also, for fresh water sites with drinking vater supplies which can be potentially affected by l plant operations, there is reasonable assurance that the operation of the facility vill not result in radionuclide concentrations in the finished drinking vater that are in excess of the requirements of 40 CFR 141. The dose calculations in the Section 1.3 of this manual implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 1.3 of this manual for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation Of Annual Doses To Man from Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance Vith 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose of Implementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

D-2 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: LIQUID EFFLUENTS (continued) i This CONTROL applies to the release of liquid effluents for Beaver Valley Power Station, Unit No. 1 or Unit No. 2. These units have shared radvaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

3/4.11.1.3 LIQUID VASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents vill be kept "as lov as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radvaste treat.nt system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, '.or liquid effluents. This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No. 2.

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D-3 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: GASEOUS EFFLUENTS 3/4.11.2.1 GASE0US EFFLUENT DOSE RATE This CONTROL is provided to ensure that the dose at anytime at the site boundary from gaseous effluents from all units on the site vill be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.

These limits provide reasonable assurance that radioactive material discharged in gaseous effluents vill not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual vill be sufficiently lov to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to 3 500 mrem / year to the total body or to $ 3,000 mrem /

year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to 3 1,500 mrem / year.

3/4.11.2.2 DOSE, NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.B, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROL implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents vill be kept "as lov as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in Section 2.3 of thic manual for calculating the doses due to the actual release

• es of idioactive noble gases in gaseous effluents are consistent sith the methodology provided in Regulatory Guide 1.109,

" Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance With 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, " Methods For Estimating Atmospheric Transport And Dispersion of Gaseous Effluents In Routine Releases From Light-Vater-cooled Reactors," Revision 1, July, 1977. The equations in Section 2.3 of this manual are provided for determining the air doses at tLe exclusion area boundary, and are based upon the historical average D-4 ISSUE 3 L __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: GASEOUS EFFLUENTS (continued) atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

This specifications applies to the release of gaseous effluents from Beaver Valley Power Station, Unit No. 1 or Unit No. 2.

3/4.11.2.3 DOSE, RADI0 IODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES This CONTROL is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Part 50. The CONTROLS are the guides set forth in Section II.C of Appendix I.

The ACTION statements provide the required operating flexibility and ,

at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents vill be kept "as lov as is reasonably achievable."

The calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The calculational methods in "

Section 2.3 of this manaual are for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses To Man From Routing Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance Vith 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111,

" Methods For Estimating Atmospheric Transport And Dispersion Of Gaseous Effluents In Routine Releases From Light Vater-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathvays which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides,

2) deposition of radionuclides onto vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. This CONTROL applies to radioactive material in particulate form and radionuclides other than noble gases released from Beaver Valley Power Station, Unit No. 1 or Unit No.2.

D-5 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: GASEOUS EFFLUENTS (continued) 3/4.11.2.4 GASEOUS RADVASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents vill be kept "as lov as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design obj ectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. This specification applies to gaseous radvaste from Beaver Valley Power Station, Unit No. 1 or Unit No. 2.

D-6 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROI S BASES: TOTAL DOSE 3/4.11.4 TOTAL DOSE r

This CONTROL is provided to meet the dose limitations of 40 CFR

[

Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The CONTROL requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources

( exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikley that the l

I resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storages tanks, etc.) are kept small. The Special Report vill describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to vithin :he 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or aithin a radius of 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR l

Patt 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until URC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any vay to the other requirements for dose limitation of 10 CFR Part 20, as addressed in CnNTROLS 3.11.1.1 and 3.11.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

h D-7 ISSUE 3

BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this CONTROL provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the Lighest potential radiation exposures of MEMBER (S) 0F THE PUBLIC resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program vill be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The detection capabilities required by Appendix C, Table 4.12-1 are state-of-the-art for routine environmental measurements in industrial laboratories. The LLD's for drinking water meet the requirements of 40 CFR 141.

3/4.12.2 LAND USE CENSUS This CONTROL is provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the monitoring programs are made if required by the results of this census. The best survey information from the door-to-door survey, aerial survey, or by consulting with local agriculture authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathvays via leafy vegetables vill be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.

3/4.12.3 INTERLABORATORY COMPARISON PROGRAE The CONTROL for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

D-8 ISSUE 3

BV-1 and 2 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT ANNUAL RADIOLOGICAL ENVIRONMENTAL REPnRT 6.9.1.10 Routine radiological environmental operating reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year and vill include reporting any deviations not reported under 6.9.2f vith respect to any Appendix C CONTROL.

The annual radiological environmental reports shall include:

• Summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillante activities for the report period, including a comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports, and an assessment of the '

observed impacts of the plant operation on the environment.

• The results of the land use censuses required by Appendix C CONTROL 3.12.2.

• If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the ptoblem and a planned course of action to alleviate the problem.

• Summarized and tabulated results in the format of Appendix E, Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be- submitted as soon as possible in a supplementary report.

A summary description of the radiological environmental monitoring

=

program.

A map of all sampling locations keyed to a table giving distances and directions from one reactor.

• The results of licensee participation in the Interlaboratory Comparison Program required by Appendix C CONTROL 3.12.3.

3 A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to both units.

E-1 ISSUE 3

DV-1 and 2 ODCM APPENDIX E ANNUAL REPORTS TABLE 6.9-1 EtWIRONMENTAL RADIOIOGICAL MONITORING PROGRMi SU.%\RY Name Of Facility Docket No.

Location Of Facility Reporting Period (County, State)

ALL INDICATOR LOCATIONS WI'Ill HIGHEST f LOCATIONS ANTE 1L MEMI CONTROL LOCATIONS MEDIUM OF PAT 1MAY TYPE AND 'IUIAL LOWER LIMITS OF ER OF SAMPLED N'JMBER OF # 1)b 1)b M4ALYSES DETECTION NNtE DISTANCE MEAN(1)b REPORTABLE (UNIT OF MEASUREMENT) PERFORMED (LLD) MEM4(h PRJG AND DIRECTION MEN FANG 4( h RMC OCCURREIiCES I

hominal Lower Limits Of Detection (LLD) as defined ist Table Notation a. of Table 4.11-1 of Appendix C CONTROL 3.11.1.1.

Mean and range based upon detectable measurement only. Fraction of detectable measurement at specified locations is indicated in parenthesis (1).

E-2 ISSUE 3

BV-1 and 2 ODCM APPENDIX E j ANNUAL REPORTS A131UAL REPORT ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.11 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted prior to April 1 of each year. This report is prepared and submitted in accordance with BVPS RCM Appendix 5, and at a minimum, shall contain the following:

• A summary of the quantities of radioactive liquid and gaseous effluent and solid vaste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June, 1974, " Measuring, Evaluating, And Reporting Radioactivity In Solid Vastes And Releases Of Radioactive Materials In Liquid And Gaseous Effluents From Light-Vater-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

An assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The assessment of radiation doses shall be performed in accordance with this manual.

• Any licensee initiated changes to the ODCM made during the 12 month period.

• Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPERABLE status within 30 days, and why the inoperability was not corrected in a timely manner. This applies to the liquid or gaseous effluent monitoring instrumentation channels required to be OPERABLE per Appendix C CONTROLS 3.3.3.9 and 3.3.3.10.

" Any ODCM Appendix C SURVEILLANCE REQUIREMENT deficiencies. This applies to monitoring, sampling and analysis and dose projection.

• The reasons when unusual circumstances result in LLD's higher than required by Appendix C, Table 4.11-1 and 4.11-2.

4 A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the site; however, for units with separate radvaste systems, the submittal shall specify the releases of radioactive material from each unit.

E-3 ISSUE 3

BV-1 and 2 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT (continued)

The following information for each type of solid vaste shipped offsite during the report period:

- container volume

- total curie quantity (determined by measurement or estimate)

- principal radionuclides (determined by measurement or estimate)

- type of vaste (e.g., spent resin, compacted dry vaste, evaporator bottoms)

- type of container (e.g., LSA, Type A, Type B, Large Quantity)

- solidification agent (e.g., cement)

- classification and other requirements specified by 10 CFR Part 61

• An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of vind speed, vind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of vind speed, vind direction, and atmospheric stability.

" An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

An assessment of the radiation doses from radioactive effluents to MEMBER (S) 0F THE PUBLIC due to theit activitiesAll inside the site assumptions boundary (Figure 5-1) during the report period.

used in making these assessments (e.g., specific activity, exposure time, and location) shall be included in these reports. The assessment of radiation doses shall be performed in accordance with Section 4 of this manual.

An assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards For Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. The SKYSHINE Code (available from Radiation Shielding Information Center, (0RNL)) is acceptable for calculating the dose contribution from direct radiation due to N-16.

l f

• If quantities of radioactive materials released during the reporting period are significantly above design obj ec t ives , the report must cover this specifically.

E-4 ISSUE 3

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