ML20101L787
| ML20101L787 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/11/1995 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20101L737 | List: |
| References | |
| PROC-951011, NUDOCS 9604040217 | |
| Download: ML20101L787 (315) | |
Text
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O BEAVER VALLEY POWER STATION UNIT NO. I and UNIT NO. 2 OFFSITE DOSE O
CALCULATION MANUAL l
CONTROLLliD
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RTL A9.621B Form RE 6.101-03 (10/95)
DUQUESNE LIGHT COMPANY BV-1 and 2 ODCM Cooy Holders BV-1 and 2 ODCM Issue No. 3 Revision No. i.
Effective Date s o - t i Controlled Copies Unit I Control Room (NSS) No. 1 HP Manager No. 2 Unit 2 Control Room (NSS) No. 3 Emuent Control (SHPS) No. 4 Unit 1 Rad Operations Director No. 5 Licensing No. 6 Unit i Ooerations Manacer No. 7 Unit 2 Ooerations Manager No. 8 Ooerations Procedure Group No. 9 I&C Procedures Group No. 10 Unit 1 Ooerators Console No. 11 Unit 2 Ooerators Console No. 12 Uncontrolled Copies FA-DEP GRP) No. I NRC Resident Insocetor No. 2 No. 3
' ODCM Historical File No. 4 ;
RE File 6.10102 No. 5 Document Control (RTL A9 621B) No. 6 ;
ARERR File No. 7 No. 8 No. 9 i Emuent Control Offsite Use (SHPS) No. 10 l REMP Administrator No. II !
No. 12 I DLC-OA No. 13 j Emuent Control Offsite Use (HPS) No. 14 l No. l No.
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RTL A9.621B Form RE 6.10101 (10/95)
O DUQUESNE LIGHT COMPANY j BV-1 and 2 ODCM Review and An.oroval Sheet OSC Review Plant Manager or Issue Rev. Pages - RSC Review and Approval Designee Approval Eff.
No. No. Issued Meeting No. Date Meeting No. Date Sign. Date Date tw4a5 '*'*8 Title BV-RSC- BV-OSC- /ch/h ' I"!'88 3 1 i 95-18 40-95
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U j nv i 1-22 thns j 1-24 j A-3 i
B-1 thru
- B-5 C-1 Ox thru C-4 i
C-19 i thru !
C-22 C-25 thru C-55 D-1 thru ;
D-9 E-1 thru E-5 F-1 thru F-17 O CONTROLLED COPY No_4 [
DUQUESNE LIGHT COMPANY BV-1 And 2 ODCM Review And Approval Sheet Issue Rev. Pgs RSC Review OSC Review Admin. Anomy. Eff.
No. No. Issd. Meeting No. Date Meeting No. Date Sign. Date Date 3 N/A i-xx BV-RSC-95-12 7/12/95 BV OSC-29-95 7/20/95 ,71f 95 8/4/95 1-1 thru l-31 2-1 thru 2 122 31 thru 3-16 41 5-1 A-1 thru A-3 B1 thru B-5 C-1 thru C-56 D-1 thru D-8 I E1 thru E-4 I
1 RE 6.101-1
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I j DUQUESNE LIGHT C0!!PANY INCLUDED l (3
's FOR ODCt! Review and Approval Sheet HISTORICAL PURPOSES BV-1 ODCM l
Admin.
Issue Rev. Pga. RSC Review OSC Review Approv. Eff.
No. No. Issd. Meeting No. Date Meeting No. Date Sign. Date Date l
f .. Q 627/g9 June 12-89 2 h
thru viii 1989 1989 1989 1-1 I thru 1-20
- 2-1 thru
! 2-99 3-1 thru 3-14 4-1 l 5-1 l l
A-1 thru A-7 l
B-1 l
thru l B-4 1
I RE 6.101-1 f~x l
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DUQUESNE LIGHT COMPANY Nuclear Group INCLUDED FOR HISTORICAL Review and Approval Sheet UNIT 1 - 0FFSITE DOSE CALCULATION MANUAL ISSUE 2 Rev. Pgs. Tech. Rev. OSC Approv. Eff.
No. Issd. Sign. Date Review Date Sign. Date Date 0 TITLE PGS BV-RSC-11-87 BV-0SC-17-87 i thru viii BV-RSC-12-87 June 12, 1987
- f. _ v 7/24/87 1-1 thru 1-17 BV-RSC-14-87 2-1 thru 2-96 May 29, 1987 7[/6[67 l
3-1 thru 3-14 gpg 4,1, 5-1 A-1 thru A-7 B-1 thru B-4 1 2-11 BV-RSC-38-87 BV-1-0SC-25-87 y 12/22/87 2-14 12/3/87 12/15/87 y 2-%A' /2/2Z/b7 !
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D'JQUESSI LIGHT COM?ASY suclear services U.i:
INCLUDED o FOR
- 1 Review and Accreval Sheet PURPOSES UNIT 1 - OFFSITE DOSE CALCULATION M.GUAL ISSUE 1 Admin.
Rev. Pgs. Tech. Rev. OSC Approv. Eff.
No. Issd. Sign. Date Review Date Sign. Date Date Rev. 1 iii O# 'M b -
1-17,18,19 /545-FFM-P*-/7 ,
2-12,13, 14,15
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2-19,2-65 J.W. Wenkhous and 2-82 May 2, 1986 b
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/ 's FC)l4 O HISTORICAL ODCM Review and Approval Sheet PURPOSES BV-2 ODCM Admin.
Issue Rev. Pgs. RSC Review OSC Review Approv. Eff.
No. No. Issd. Meeting No. Date Meeting No. Date Sign. Date Date 1 3 Title BV-RSC- May BV-OSC- June /pj/g7 June 1 89 25 13-89 15 * . ,
30 thru 1989 1989 1989 viii 1-1 '
thru 1-21 2-1
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, thru (w ) 2-101 3-1 thru 3-14 4-1 5-1 A-1 thru A-7 !
B-1 thru B-2
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RE 6.101-1 l t_s/
DUQUESNE LIGHT COMPANY Nuclear Group FOR Review and Approval Sheet HISTORICAL PURPOSES UNIT 2 - 0FFSITE DOSE CALCULATION MANUAL ISSUE 1 Rev. Pgs. Tech. Rev. OSC Approv. Eff.
No. Issd. Sign. Date Review Date Sign. Date Date 1 TITLE PCS BV-RSC-11-87 BV-0SC-17-87 i thru viii BV-RSC-12-87 June 12, 1987 7/24/87 1-1 thru l-18 BV-RSC-14-87 7/M/3 7 2-1 thru 2-98 May 29, 1987 I 3-1 thru 3-14 fe/ S M 4-1, 5-1 A-1 thru A-7 B-1 and B-2 2-12 2 BV-RSC-38-87 BV-1-OSC-25-87
%J 12/22/87 2-15 12/3/87 12/15/87 / i
@ t fdA' /2/22/57 l l
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j DUQUESNE LIGHT COMPANY ;
i i Beaver Valley Power Station Unit 1 i
. Docket No. 50-334 I i
License No. DPR-66 j- Beaver Valley Power Station Unit 2 .
4 Docket.No. 50-412 i License No. NPF-73 ;
i i
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d BEAVER VALLEY POWER STATION UNIT 1 (BV-1)
BEAVER VALLEY POWER STATION UNIT 2'(BV-2) 0FFSITE DOSE CALCULATION MANUAL (ODCM) 4 1
s 4 !
i 1
ISSUE 3
! Revision 1
- i. ,
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,m. - -- . - - - . -s ,
BV-1 and 2 ODCM TABLE OF CONTENTS SECTION TITLE PAGE NO.
f~% ,
\ ,) Table Of Contents................................... i List Of 7 ables...................................... iii List Of figures..................................... vii ODCM Equation Cross Reference....................... viii ODCM Table Cross Reference.......................... x Preface............................................. xiii History Of ODCM Changes............................. xiv 1.0 LIQUID EFFLUENTS.................................... 1-1 l 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............................ 17 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 With 10 CFR 20 EC Limits............. 1-16 1.2.1 Batch Releases.... ........................... 1-16 1.2.2 Continuous Releases........................... 1-18 fS
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'~/ 1.3 Compliance With 10 CFR 50 Dose Limits........... 1-21 1.3.1 Cumulation Of Doses........................... 1-21 1.3.2 Projection Of Doses........................... 1-23 1.4 Liquid Radvaste System.......................... 1-27 1.4.1 BV-1 Liquid Radvaste System Components........ 1-28 1.4.2 BV-2 Liquid Radvaste System Components........ 1-29 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 Setpoint 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 Analysis Prior To Release (Ground Releases). 2-19 O O i ISSUE 3 Revision 1
BV-1 end 2 ODCM TABLE OF CONTENTS SECTION TITLE PAGE NO.
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 2.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release (Elevated Releases) 2-26 References For Gaseous Alarm Setpoints.............. 2-33 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 Limita........... 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 Projection Of Doses......................... 2-65 2.3.2 Doses Due To Radioiodines And Particulates.... 2-66 2.3.2.1 Cumulation Of Doses......................... 2-66 2.3.2.2 Projection Of Doses......................... 2-78 2.4 Gaseous Radvaste System......................... 2-117 2.4.1 BV-1 Gaseous Radvaste System Components....... 2-118 2.4.2 BV-2 Gaseous Radvaste System Components....... 2-119 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....... 3-1 4.0 INFORMATION RELATED TO 40 CFR 190................... 4-1 5.0 SITE BOUNDARY FOR GASE0US 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 Appendix F ODCM Control Procedure Matrix....................... F-1 O
11 ISSUE 3 Revision 1
-- - . , - . , ~ . - . - . - - -- -~ _ ~ . _ . --. . ..
BV-1 and 2'0DCM LIST OF-TABLES l
T '
l TABLE NO. TITLE PAGE NO.
l LIQUID EFFLUENT TABLES 1.1-la BV-1 Liquid Source Term.............................. 1-12 1.1-1b BV-2 Liquid Source Term.............................. 1-13 ;
1.2-la BV-1 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks............................... 1-19 l 1.2-1b BV-2 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks............................... 1-20 ,
1.3-1 'A Values For An Adult For The Beaver Valley Site... 1-24 l h GASEOUS EFFLUENT TABLES 2.1-la BV-1 Radionuclide Mix For Gaseous Effluents.......... 2-29 ;
2.1-1b BV-2 Radionuclide Mix For Gaseous Effluents.......... 2-30 l 2.1-2a BV-1 Monitor Detector Efficiencies................... 2-31 i l 2.1-2b BV-2 Monitor Detector Efficiencies................... 2-32' l l 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 i 2.2-2b BV-2 Radionuclide Mix For Gaseous Effluents.......... 2-47 p 2.2-3 Distances Of Limiting Maximum Individual Receptors l' f To Release Points For Annual X/0 Values.............. 2-48 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 i
'2.2-7 'BV-1 And 2 Turbine Building Vents (Ground Release)... 2 l 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 i 2.2-12 Dose Parameters For Finite Elevated Plumes, Beaver j Valley Site..................... .................... 2-57 2.2-13 P Values For A Child For The Beaver Valley Site.... 2-58 h
MODES OF GASEOUS 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 O
iii ISSUE 3 Revision 1
BV-1 znd 2 ODCM 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 - Adu1t......................................... 2-88 2.3-11 Heat - Teen.......................................... 2-89 2.3-12 Heat - Chi 1d......................................... 2-90 2.3-13 Cow Hilk - Adult..................................... 2-91 2.3-14 Cow Hilk - Teen...................................... 2-92 2.3-15 Cow Milk - Chi 1d..................................... 2-93 2.3-16 Cow 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 DISTAMCES1 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 (GrounJ Release)... 2-109 2.3-32 BV-2 Condensate Polishing Building (Grotnd 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 Rele:se)... 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 e
iv ISSUE 3 Revision 1
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 BV-1 And 2 Release Conditions........................ A-3 INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS B:la Inputs To GALE Lode For Generation Of BV-1 Liquid Source Term Mixes.................................... B-2 B:1b Inputs To SVEC LIQ 1BB Code For Generation Of BV-2 Liquid Source Term Mixes............................. B-3 B:2a Inputs To SVEC GAS 1BB Code For Generation Of BV-1 Gaseous Source Term Mixes............................ B-4 B: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
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j C:3.3-12 Radioactive Liquid Effluent Monitoring Instrumentation C-10 C:4.3-12 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements............................ C-12 C:3.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation C-19 C:4.3-13 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements............................ C-25 C:4.11-1 Radioactive Liquid Vaste Sampling And Analysis Program C-31 C:4.11-2 Radioactive Gaseous Vaste Sampling And Analysis Program C-38 C:3.12-1 Radiological Environmental Monitoring Program........ C-48 C:3.12-2 Reporting Levels For Radioactivity Concentrations In Environmental Samples................................ C-51 C:4.12-1 Maximum Values For The Lover Limits Of Detection (LLD) C-52 FORMAT FOR ANNUAL REPORT E:6.9-1 Environmental Radiological Monitoring Program Summary E-2 pl
\~s v ISSUE 3 Revision 1
i BU-1 end 2 ODCM I
1 LIST OF TABLES i TABLE NO. TITLE PAGE NO.
ODCM CONTROLS PROCEDURE MATRIX F:la BV-1 Liquid Effluent Monitor Surveillance &_ ............ F-2 F:1b BV-2 Liquid Effluent Monitor Surveillances................. F-3 F:2a BV-1 Gaseous Effluent Monitor Surveillances................ F-4 F:2b BV-2 Gaseous Effluent Monitor Surveillances................ F-5 F:3 BV-1 and 2 Liquid Effluent Concentration Surveillances..... F-7 F:4 BV-1 and 2 Liquid Effluent Dose Surveillances.............. F-8 loh F:5 BV-1 and 2 Liquid Effluent Treatment Surveillances......... F-9 F:6 BV-1 and 2 Gaseous Effluent Dose Surveillances............. F-10 F:7 BV-1 and 2 Gaseous Effluent Air Dose Surveillances......... F-11 F:8 BV-1 and 2 Gaseous Effluent Particulate and Iodine......... F-12 Dose Surveillances..............................
F:9 BV-1 and 2 Gaseous Effluent Treatment Surveillances........ F-13 lh F:10 BV-1 and 2 Total Dose Surveil 1ances........................ F-14 F:11 BV-1 and 2 REMP Surveillances.............................. F-15 F:12 BV-1 and 2 Land Use Census Surveillances................... F-16 F:13 BV-1 and 2 Interlaboratory Comparison Program.............. F-17 O
vi ISSUE 3 Revision 1
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BV-1 and.2 ODCH LIST OF FIGURES s
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( )s FIGURE NO. TITLE PAGE NO. I LIQUID EFFLUENT FIGURES 1.4-1 BV-1 Liquid Radvaste System......................... 1-30 1.4-2 BV-2 Liquid Radvaste System......................... 1-31 GASEOUS EFFLUENT FIGURES
\ l l 2.4-1 BV-1 And 2 Gaseous Radvaste System.................. 2-121 !
2.4-2 BV-1 And 2 Gaseous Effluent Release Points.......... 2-122 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FIGURES i l 3.0-1 Air Sampling Locations.............................. 3-8 I 3.0-2 TLD Locations - Northwest Quadrant.................. 3-9 3.0-3 TLD Locations - Northeast Qeadrant.................. 3-10 3.0-4 TLD Locations - Southeast Quadrant.................. 3-11 3.0-5 TLD Locations - Southwest 0ur.drant.................. 3-12 3.0-6 Shoreline Sediment, Surface Water, And Drinking i Vater Sampling Locations............................ 3-13 i 3.0-7 Milk Sampling Locations............................. 3-14 i 3.0-8 Fooderop Sampling Locations......................... 3-15 )
3.0-9 Fish Sampling Locations............................. 3-16 )
7-~g SITE BOUNDARY FIGURES j
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l 5-1 Site Boundary For Gaseous And Liquid Effluents...... 5-1 !
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v vii ISSUE 3 Revision 1
BV-1 and 2 ODCM ODCM EQUATION CROSS REFERENCE FOR LIQUID EFFLUENTS l
FROM: T0: FROM: ,
PREVIOUS CURRENT PREVIOUS l BV-1 ODCH 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(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)-8 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 Thru 1.3-8 1.3-8 1.3-8 1
l 1
0 1 viii ISSUE 3 Revision 1 l
I- .I BV-1 and.2 ODCM ODCM EQUATION CROSS REFERENCE
'FOR GASEOUS EFFLUENTS FROM: T0: 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 2.1-1 2.1(1)-1 --
2.1-2 2.1(1)-2 --
l 2.1-3 2.1(1)-3 --
L 2.1 2.1(1)-4 --
l 2.1-5 2.1(1)-5 --
- j. 2.1-6 2.1(1)-6 --
2.1-7 2.1(1)-7 --
2.1-8 2.1(1)-8 --
2.1(2)-1 2.1-1 2.1(2) .2.1-2 2.1(2)-3 2.1-3 2.1(2)-4 2.1-4:
2.1(2)-5 2.1-5 2.1(2)-6 [
2.1-6 2.1(2)-7 . 2.1-7 2.1(2)-8 2.1-8 2.1-9 2.1-9 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 2.1(1)-18 --
2.1-19 2.1(1)-19 --
2.1-20 2.1(1)-20 --
2.1(2)-17 2.1-17.
2.1(2)-18 2.1-18.
2.1(2)-19 2.1-19 2.1(2)-20 2.1-20 2.1-21 2.1-21 2.1-21 Thru Thru Thru 2.1-24 2.1-24 2.1-24 2 . '2-1 2.2-1 2.2-1 j Thru Thru- Thru i 2.2-14 2.2-14 2.2-14 l 2.3-1 2.3-1 2.3-1 Thru Thru Thru i
!- 2.3-36 2.3-36 2.3-36 I 1
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i ix ISSUE 3 Revision 1 i
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BV-1 cnd 2 ODCM ODCM TABLE CROSS REFERENCE FOR LIQUID EFFLUENTS FROM: TO:
O FROM:
FREVIOUS CURRENT FREVIOUS BV-1 ODCH BV-1 AND 2 ODCH 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 O
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9 x ISSUE 3 Revision 1
BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR GASE0US EFFLUENTS f i
FROM: T0: FROM:
PREVIOUS PREVIOUS CURRENT BV-l'ODCM BV-1 AND 2'0DCM- BV-2 ODCM' ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3. 1 AND EARLIER AND LATER -AND EARLIER 2.1-1 2.1'-la --
-- 2.1-1b 2.1-1.
2.1-2 2.1-2a --
-. 2.1-2b 2.1-2~
2.2-1 2.2-1 2.2-l' 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 O. A-3:
A-4 2.3-36 2.3-37
- A-3 A-4 A-5 2.3-38 A-5 3.0-1 3.0-1 3.0-1 1
1 O I i
xi ISSUE 3 Revision 1
BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR ODCM APFENDICES FROM: T0: 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 A-1 (Unnumbered) B:la --
B:1b (Unnumbered)
(Unnumbered) B:2a --
B: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 --
F:la --
F:1b --
F:2a --
F:2b --
F:3 --
F:4 --
F:5 -- N15 F:6 --
F:7 --
F:8 --
F:9 --
F:10 --
F:11 --
F:12 --
F:13 --
O l
xii ISSUE 3 Revision 1 l 1
1 l
l
BV-1 and 2 ODCM 1
l PREFACE l
,/m. '
O This 0FFSITE DOSE CALCULATION MANUAL (0DCM) provides the information and methodologies to be used by Beaver Valley Power Station Unit 1 and Unit 2 (BV-1) 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 or 10 CFR 20.1302 as appropriate, 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: l
' 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. l
' Generic Letter 89-01, January 31, 1989, Implementation Of Programmatic I Controls For Radiological Effluent Technical Specifications In The I 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.
A i )
- Other miscellaneous inputs from the USNRC.
Specific plant procedures for implementation of this manual are included in the Health Physics Manual (BVPS-HPM) and the Radiological Engineering Administrative Manual (REAM). These procedures are utilized by the operating staff to assure compliance with Technical Specifications and the Appendix 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 required by 10 CFR 20.106 or 10 CFR 20.1302 as appropriate, 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.
G xiii ISSUE 3 Revision 1
BV-1 and 2 ODCM HISTORY OF ODCM CHANGES (1) BV-1 ODCM, Issue 1 (Effective January, 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 October, 1984)
A description of the changes that were 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 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 July, 1986)
A description of the changes that were implemented with this revision are as follows:
- Provide a flow 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 SPING Channel 5 alternate monitor data. The calculations supporting this item are contained in Calculation Packages ERS-SFL-85-031 and ERS-ATL-86-008.
O xiv ISSUE 3 Revision 1
BV-1 and 2 ODCM i
(4) BV-1 ODCM, Issue 2, (Effective ~ July, 1987) 1 p BV-2 ODCM, Issue 1, Revision 1 (Effective July, 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 ODCH, it was-re-issued as Issue 2.
Also, for clarity, the draft BV-2 ODCH 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 ODCH. F
'A shared ' liquid radvaste system, permitting mixing of vaste for i processing, the sharing of dilution vater, and the apportionment of dose-according to NUREG-0133 was 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
- vas incorporated into both ODCHs. l
- Separate ground level gaseous releases were maintained. The BV-1 ODCM. '!
vas 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.
.p
- The gaseous effluent monitor alarm setpoints of both ODCMs were revised ,
g as required by revisions to raeteorology,- source terms, monitor 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. Vhereas,.the dose rate for 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 minutest 60 minutes = 16).
(5) BV-1 ODCM, Issue 2, Revision 1 (Effective December, 1987)
BV-2 ODCM, Issue 1, Revision 2 (Effective December, 1987)
Sections 2.1.3 and 2.1.4 of both 0DCMs were changed to delete a note l concerning noble gas nuclides as requested by a NRC letter dated July 14, 1987 titled -Beaver Valley Unit 2 - Offsite Dose Calculation l 1
(6) BV-1 ODCM, Issue 2. Revision 2 (Effective June, 1989)
BV-2 ODCM, Issue 1, Revision 3 (Effective June, 1989)
A description of th'e changes that were implemented with this revision are' I 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
,g Radvaste System and the Gaseous Radvaste System. (See justification 1) xv ISSUE 3 Revision 1 i
BV-1 and 2 ODCM
- Correct the following typos to BV-1 ODCM Equation 1.1-8:
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 ODCits, as allowed by the -
b7C. (See Justification 1)
- Correct typos to the following:
A. BV-1 ODCM equation 1.3-7, add a division sign between the brackets.
(See Justification 1)
B. BV-1 ODCM equation 1.3-8, add a division sign between the brackets.
(See Justification 1)
C. Add the words "from each reactor unit" to five places (Sections 1.3.1, 1.3.2, 2.3.1.1, 2.3.1.2, and 2.3.2.2) of both ODCMs. This ensures compliance with 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 ODCH. (See Justification 3)
- Add the words "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 values for the Beaver Valley site in Table 2.2-13 of both ODCMs. (See Justification 1)
- Correct the definition for the t value in the cow-meat pathway in Section 2.3.2.1 of both ODCMs. g(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)
- Change the particulate and iodine release fractions in Appendix B of the BV-1 ODCM. (See Justification 3) xvi ISSUE 3 .
Revision 1
BV-1 and 2 ODCM l l
The justification used for Change (6) to the ODCHs are as follows:
s 1. A letter dated March 2, 1989 -(from the NRC) was received by Duquesne Light regarding acceptance of~ the Offsite Dose Calculation Manuals.
The NRC acceptance of the BV-1 and BV-2 ODCMs vas 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 i the TER. In general, these concerns are considered typos or additions l and in one way impact any of the calculations currently being I performed for dose contributions. However, one of these concerns is ;
.regarding the inability to reproduce .the .ODCM R values for the cov- i 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 l re-validated VIA Calculation Package No. ERS-ATL-89-014. The results. '
of this package shoved that the R values for the three aforementioned i pathways were in error. Since the R values in error do not involve I the controlling receptor for gaseous release (i.e.; the' controlling receptor is VIA the Inhalation, Ground, and Vegetation pathways, not the pathways subject to error) than these changes to the ODCM vill E t adversely impact the accuracy or reliability of effluent dose !
calculations.
- 2. As requested by DLC letters ND3NSM:3431, ND1NSM:3522, and ND1NSM:3652 Technical Specifications were required to be verified in all plant implementing procedures. As part of this effort, wording errors / typos ;
vere identified in various sections of the ODCM. This revision j (o,)' 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, Appendix B) a series of apparent discrepancies were identified between ODCM Table 2.2-2 and similar tables of the BVPS-2 FSAR. Evaluation showed 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 i 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 (Effective August, 1995)
The combined ODCH, as implemented by ISSUE 3, contains the following changes:
- Prior to ISSUE 3, BV-1 and BV-2 had individual ODCMs that were generically equal. In an effort to simplify the implementing documents, the 'JDCMs have been combined. This merger of the individual ODCMs vill mair.tain the level of radioactive effluent controlrequiredby10CFRs/g 20.;302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part
- 50. Also,- this merger vill not adversely impact the accuracy or reli.bility of effluent, dose, or setpoint calculations.
s xvii ISS; Revision 1
BV-1 end 2 ODCM
' Revised Section 1.0 (Liquid Effluents) to show compliance with 10 CFR 20 Appendix B (20.1001 - 20.2401), Table 2, Col. 2 EC's. This includes the following:
- Revising the alarm setpoints for monitors (RM-LV-104, RM-LV-116, and 2SGC-R0100)
- Updating the BV-1 monitor detection efficiencies
- Updating discharge rate and dilution rate parameters for BV-1 and BV-2
- Adding the alarm setpoints for monitors (RM-RV-100, RM-DA-100, 2SVS-R0101, and 2SVS-R0102)
- Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gasecus Effluents) to merge the BV-1 alarm setpoint calculations with the BV-2 alarm setpoint calculations. For all practical purposes, when Tables, Figures, and Equations were transferred to the combined ODCM, the numbering was kept generically equal. The only exception to this are as follows:
If a table was contained in both ODCHs, but each had data specific to BV-1 or BV-2, then an a or b was added to the table. For example, Table 1.1-1 vas previously included in the BV-1 ODCM and the BV-2 ODCM. These tables are nov numbered 1.1-la and 1.1-1b 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 specific to BV-1 or BV-2, then a (1) or (2) was 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 vere 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 through 2.3-38). This revision was done for clarification. For exainple, all dispersion parameters are now included in one area of the ODCH.
- Added Appendix C: Procedural details for the Radiological Effluent Technical Specifications (RETS) were transferred from the Technical Specifications to Appendix C of the ODCH per Generic Letter 89-01 and Generic Let ter 89-01, Supplement No.1 (NUREG 1301).
O xviii ISSUE 3 Revision 1
- _ . . . -.. - . ... - - . - - - ._ . - - - . . . . .~ ,- - .
BV-1 and 2 ODCM This Appendix also includes ' selected Definitions and Tables as delineated in the Technical Specifications (Section'~1) and selected O Applicability and Surveillance Requirement' statements.as delineated'in !
V the Technical Specifications (Section 3/4 0).
Appendix C for reference purposes, even though they are currently These vere added to described in the Technical Specification.
. Added Appendix D: The bases for ODCM Controls were transferred from the i Bases Section of the Technical Specifications 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.
There are three differences (i.e., non-editorial changes) in this ODCM 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:
First Difference (LLD Definition Clarification): l There was a sentence removed in the LLD1 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' i 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 i BV-1 and 2, there are no other radionuclides normally present-in effluent samples. However, 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. s 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 maintains the level of radioactive effluent control required by 10 CFR 20.1302, 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.
- 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. ,
xix ISSUE 3 Revision 1 a .
-s,- ,_
BV-1 ond 2 ODCM
- i Second Difference (Change From Semi-Annual Report To Annual Report: '
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 submission of the reports must be no longer than 12 months..."
This change maintains the level of radioactive effluent control required by 10 CFR 20.1302, 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.
Third Dif ference (Implenaentation Of Neu 10 CFR 20):
The definition for HEMBER(S) 0F THE PUBLIC vas revised to agree with the definition in Nev 10 CFR 20.1003. '
The definition for UNRESTRICTED AREA vas modified from the definition that was in the Technical Specifications prior to transferring to the ODCH. This modification was necessary to ensure that the ODCM dose model for gaseous releases is not affected. The modification involved adding the following sentence: "For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any public road, railway, or watervay adj acen t to or crossing the site that is not occupied continuously by MEMBER (S) 0F THE PUBLIC".
The limits for liquid effluent concentration vere changed from 1 times Old 10 CFR 20 Appendix 3 (20.1 - 20.601), Table II, Col. 2 MPC's to 10 times Nev 10 CFR 20 Appendix B (20.1001 - 20.2401),
Table 2, Col. 2 EC's.
This limit vill now be referred to as the ODCM Effluent Concentration Limit (OEC).
For gaseous effluents, no changes were made to implement the New 10 CFR 20. As justification, when the utility adopted the RETS (1/1/84), compliance to 10 CFR 20 shifted from the HPC concept to the Unrestricted Area Dose Rate concept. The Dose Rate concept is the preferred method of controlling gaseous effluent release rate, and vill continue to be used in-lieu of the HPC or EC concept.
Changing to the OEC limit for liquid effluents accommodates needed
' operational flexibility to facilitate implementation of the Nev 10 CFR 20 requirements.
For information, the general intent of the New Part 20 is that radiation doses to members of the public not exceed 100 mrems per i year, which is more restrictive than the 500 mrems per year limit in l the Old Part 20, and that fuel cycle licensees also comply with 40 '
CFR 190. The New Part 20 does not include a requirement on limiting radioactivity concentrations in effluents, which is less restrictive than the Old Part 20.
xx ISSUE 3 ;
Revision 1 1
BV-1 and 2 ODCM The basic requirements for RETS (i.e.; nov the ODCM Appendix C Controls) are stated in 10 CFR 50.36a. These requirements indicate I~
that compliance with the RETS vill keep average annual releases of n'y) . radioactive material in effluents to small percentages of the limits specified in the Old 10 CFR 20.106 (Nev 10 CFR 20.1302). These requirements also indicate that operational flexibility is allowed (with considerations for public health and safety) which may temporarily result in releases higher than such small percentages, but still within the HPC limits specified in the Old 10 CFR 20.106.
The MPC's relate to an annual-dose of 500. mrem. Also, 10 CFR 50.36a indicates that when using -operational flexibility, best efforts shall. be exerted to keep levels of radioactive materials in
! effluents to ALARA as set forth in 10 CFR 50 Appendix I.
As stated in the Introduction to Appendix B .of the Nev 10 CFR 20, l- the liquid EC's are based on an annual dose of 50 mrem. Since a release concentration corresponding to a limiting dose rate of 500 mrem / year has been acceptable as a RETS limit for liquid effluents, it should not be necessary to reduce this limit by a factor of ten.
BV-1 and BV-2 has demonstrated that the use of'the MPC's associated with the Old 10 CFR 20.106 has resulted in calculated maximum
- individual doses to a member of the public that are small ,
! percentages of the limits of 10 CFR 50-Appendix I. Therefore. the use of the OEC's, which correspond to an annual. dose of SC9 mrem (i.e.; 10 times the Nev 10 CFR 20 EC's) should not have a negative impact on the ability to continue to operate within the limits of 10 CFR 50 Appendix I, and 40 CFR 190.
Operational flexibility is also necessary in establishing a basis i(m'] for effluent monitor setpoint calculations. As previously.
discussed, the EC's stated in the New 10 CFR 20 relate.to a dose of 50 mrem in a year. This is too restrictive to base effluent monitor setpoint calculations. For many liquid effluent release situations, the monitor background is high, which could result in a monitor setpoint that is approximately equal to the monitor background.
In summary, to accommodate operational flexibility needed for effluent releases, the limits associated with the liquid release concentration (i.e.; the OEC) are based on 10 times'the EC's stated in the New 10 CFR 20. . The multiplier of 10 is used because the l annual dose of 500 mrem (Old 10 CFR 20 MPC bases) is a factor of 10 l
higher than the annual dose of 50 mrem (Nev 10 CFR 20 EC bases).
Compliance with the 100 mrem dose limit of the New 10 CFR 20.1302 vill be demonstrated by operating within the dose limits of 10 CFR 50 Appendix I, and 40 CFR 190 (which are also ODCH Controls for l ' liquid and gaseous effluents). Implementation of the New 10 CFR 20 I for liquid effluents maintains the level of radioactive effluent control required by 10 CFR 20.1302, 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.
xxi ISSUE 3 ltO l U Revision 1 l
l
BV-1 cnd 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 Specification 6.8.6) and allow for relocation(as of delineated in Technical the procedural details gg of the RETS to the ODCM.
(8) BV-1 AND 2 ODCM, Issue 3, Revision 1 (Effective October, 1995)
A description of the changes that vere implemented with this revision are as follows:
- Index: Editorial changes vere made for clarity. (See justification 1)
- Section 1.0: Revised Nb-95 and Nb-97 dose factors in Table 1.3-1 due to changing the niobium bicaccumulation factor. (see justification 2)
- Appendix A: A change was made to Table 1.1 so that the letter A vould proceed the table number. (See justification 1)
' Appendix E: A descriptive paragraph was added at the front of this Appendix. Also, changes were made to the tables so that the letter B vould proceed the table numbers. (See justification 1)
- Appendix C: Descriptive paragraphs were added at the front of the Appendix (See justification 1). Removed the process flow rate operability and surveillance requirements for gaseous effluent radiation monitors 2RM0-R0301, 2RM0-R0303 and 2HVL-R0112 from Tables 3.3-13 and 4.3-13 (See justification 3). Added alternate system effluent flow rate measuring devices for the three gaseous effluent pathways to Tables 3.3-13 and 4.3-13 (See justification 4). Revised Surveillance Requirements 4.11.1.1.3 and 4.11.1.1.4 and notes e and g of Table 4.11-1 to clarify Turbine Building sump sampling requirements (See justification 5).
- Appendix D: Descriptive paragraphs were added at the front of the Appendix. (See justification 1)
- Appendix E: Desriptive paragraphs vere added at the front of the Appendix. (See justification 1)
- Appendix F: This is a new Appendix to the ODCM. It contains plant progedure references for Radiological Effluent Technical Specification (RETS) that were transferred from the Technical Specification Procedure Matrix. (See justification 1) xxii ISSUE 3 Revision 1
)
BV-1 and 2 ODCM The justification used for change (8) to the ODCM are as follows:
These changes are considered editorial in' nature. Therefore,' these (q j 1.
editorial changes vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, j
I and Appendix I to 10 CFR 50. Also the editorial changes vill not adversely impact the' accuracy or reliability' of effluent dose or setpoint calculation.
- 2. This change resulted from revising the bioaccumulation factor (BF) for niobium from the value posted in Table A-1 of Regulatory Guide 1.109, Revision 1, 1977 (30,000 pCi/kg per pCi/1). Since' this change in niobium BF (as documented and justified in Appendix A to Calculation Package No. ERS-ATL-83-027) merely removes the conservatism associated with organism uptake,- then the change vill. !
maintain the level of radioactive effluent control required by 10 !
CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 !
CFR 50. Also, removing the conservatism vill not adversely impact i the accuracy or reliability of effluent dose or. setpoint j calculation. i
- 3. This change removes the process- flow rate operability and i surveillance requirements for BV-2 Gaseous Effluent Radiation !
Monitors 2RM0-R0301, 2RM0-R0303 and. 2HVL-R0112 from Appendix C Tables 3.3-13 and 4.3-13. These items were removed from the ODCM by justification provided in Calculation Package No. ERS-ATL-90-021.
]
It should be noted that a safety analysis and a no significant hazards evaluation were prepared and approval on this change prior l to submitting it to the NRC via TSCR No. 2A-61 in 1992 However, the !
TSCR was withdrawn in 1993 in an effort to alleviate any further i l delays associated with approval of TSCR No. 1A-175/2A-37 (Generic Letter 89-01 implementation).
. Removal of.these items from the ODCM vill maintain the level of- .
l' radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part. l l 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also removal of i l these items vill not adversely impact the accuracy or reliability of l effluent dose or setpoint calculation. The following-is a summary of the justification.
- BVPS-1 and BVPS-2 is currently using, and vill continue to use l design (maximum) system flow rates in ODCM Dose & Dose Rate L Calculations, rather than those flow rates observed during normal .
l plant operation. I
' BVPS-2 UFSAR Section 11.3.3 indicates that the source term for these three pathways are not significant. These pathways are not
! included in UFSAR Tables 11.3-1 through 11.3-4 that list the
! expected and design releases for each potentially radioactive l pathway.
- 1 xxiii ISSUE 3
>0 Revision 1 l
BV-1 and 2 ODCM
- The DLC commitment to Regulatory Guide 1.97, Rev. 2 (Section 1.8-1 of the BVPS-2 UFSAR) is not affected. This RG applies to instrumentation used during and after postulated accident conditions. These three process flow rate instruments were not i used in any accidnet analysis, nor are they used to assess plant conditions during and following an accidnet.
- The DLC commitment to Regulatory Guide 1.21, Rev. 1 (Section 1.8-1 of the BVPS-2 UFSAR) is not affected. RG 1.21, Section C.2 (Location of Monitoring) states in part: "All maj or and potentially significant paths for release of radioactive material during normal reactor operation, including anticipated operational occurrences, should be monitored. Measurements of effluent volume, rates of release, and specific radionuclides should be made, insofar as practical .. " As previously stated, the three process flow rate instruments are located on effluent pathways that do not have a significant source term.
BVPS-2 UFSAR Sections 9.4.13 and 9.4.16 indicate that the building ventilation system for these three pathways are non-safety related and are not required to perform any safety-related function.
There is no effect to the Noble Gas Monitors located on these three pathways. The Noble Gas Monitors are still capable of performing their intended functions as described in BVPS-2 UFSAR Section 11.5.2.4.
- 4. This chsnge adds alternate system effluent flowrate measuring dev % s for the three BV-1 Gaseous Effluent Pathways to Appendix C Tables 3.3-13 and 4.3-13. A 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by adding the alternate measuring devices to Appendix C Tables 3.3-13 and 4.3-
- 13. This conclusion is based on the following:
There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety.
- There is no creation of a possiblity for an accident or malfunction of a different type than any evaluated previously.
There is no reduction in the margin of safety Also, since this change merely adds alternate measuring devices that meet the same surveillance requirements of the primary channel, then
,the change vill maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50. Also, addition of the alternate flow rate measuring devices vill not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
l xxiv ISSUE 3 Revision 1
l BV-1 and 2 ODCM l l I I L 5. This change to the ODCM clarifies Turbine Building sump sampling requirements and clarifies effluent related actions associated with
! detection of radioactivity in the secondary system. These
! (n)
V clarifications are documented and justified in Calculation Package No. ERS-ATL-95-006. Also, since these clarifications were shown to l
l meet the intent of NUREG-1301 (superceeding NUREG-0472) and the BVPS-1 and 2 UFSAR's, then the clarification vill maintain the level !
of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50. Also, the clarifications vill not adversely impact the accuracy or reliability j of effluent dose or setpoint calculation. :
i Also, a 10 CFR 50.59 safety evaluation has concluded that no unreviewed safety question is involved by clarifying these actions.
This conclusion is based on the following: ,,g
- There is no increase in the probability or consequences of accidents or malfunctions of equipment important to safety.
- There is no creation of a possiblity for an accident or malfunction of a different type than any evaluated previously.
There is no reduction in the margin of safety.
L) i l
l xxv ISSUE 3 l
l (g) Revision 1 1
~
j BV-1 and 2 ODCH i
.1.0 LIQUID EFFLUENTS-'
- BV-1 and BV-2 utilize the concept of a shared liquid radioactive vaste O. 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 r.1x are based on the individual Units' specific parameters, but. effluent j 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 monitoring' systems of BV-1 and BV-2. There is'a difference in setpoint terminology.: Where BV-1 uses HIGHand HIGH-HIGH, the BV-2 equivalents are ALERT and HIGH. . Also, there is the difference that BV-2 setpoints are.
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~ uCi/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, butLthe~ indicated uCi/ml value may differ from the actual value.
I t
i O :
1 i
H O 1 1-1 ISSUE 3 I
_e -r-- e, , - - - - r .en y 4
i BV-1 a.nd 2 ODCM
~
'l .1 Alarm Setpoints-1.1.1' BV-l' Monitor Alarm Setpoint Determination This procedure determines _.the monitor HIGH-HIGH ~ Alarm ~Setpoint*that A l indicates if the concentration. of radionuclides in-the liquid offluent-released from the site to unrestricted areas exceeds 10. times-the EC's specified in 10 CFR.20, Appendix- B (20.1001-20.2401), Table 2, Column.2 ,
for radionuclides other than . dissolved or entrained.. noble gases or.
exceeds a concentration of 2E-4 uCi/ml~ for dissolved or' entrained noble !
. gases (see Reference 1.1.5).
1 The methodology described in Section 1.1.1.2 is an alternative method to be used to determine the (RM-LV-104 or.RM-LV-116) monitor HIGH-HIGH Alarm Setpoint (HHSP). The methodology in Section 1.1.1~ 2' may be used for. any :
. H
-batch release:and shall be used when the respective total gamma activity 1 concentration of the liquid effluent prior to dilution' exceeds 4.26E-3 .I l' uCi/ml and 1.49E-2 uCi/ml. This concentration 'is equivalent'to-the L respective HHSP's derived in Section 1.1.1.1 and allows for respective j tritium concentrations up to 4.33E+0 uCi/ml and 1.52E+1 uCi/ml.
l 1.1.1.1~ BV-1 Setpoint Determination Based On A Conservative Mix The Alarm Setpoints for the liquid monitors'should be set at'the values L listed as follows: l BV-1 LIQUID MONITOR SETPOINTS cpm Above Background-N Monitor CR HHSP HSP
- Liquid Vaste Effluent ~ 'RM-LV-104 4.84E+5- 4.84E+5 3.39E+5.
Monitor
- Laundry And Contami- RM-LV-116 1.69E+6 1.69F+6 ~1.19E+6 *- #
nated Shower Drains i Monitor l
- Component Cooling /
RM-RV-100 2.57E+4' 2.57E+4 1.80E+4 Recirculation Spray Ex River Vater Monitor
- Aux Feed Pump Bay RM-DA-100- 1.22E+4 -1.22E+4 -8.55E+3 I
L ' Drain Monitor ,
- .The setpoints for RM-LV-104 and RM-LV-116 are based on'the-following conditions, however, the setpoint bases for RM-RV-100 and RM-DA-100 can 1 be found in Reference 1.1.5
- 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 GALE are given in Appendix B.
- Dilution water flow rate of 22,800 gpm - (15,000 gpm BV-1 + 7,800 gpm BV-2).
- Discharge flow rate prior to dilution of 35 gpm for the Liquid Vaste Effluent Monitor (RM-LV-104).
- Discharge flow rate prior to dilution of 15 gpm for the Laundry and y Contaminated Shower Drains Monitor (RM-LV-116).
1-2 ISSUE 3
BV-1 cnd 2 ODCM The above setpoints for (RM-LV-104 and RM-LV-116) can be varied based ^
on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows:
HHSP 743 F [1.1(1)-1]
f where:
HHSP - Monitor HIGH-HIGH Alarm Setpoint above background (nepm).
743 - Most restrictive proportionality constant based on nominal flow conditions:
743 - 4.84E+5 nepm x 35 gpm + 22,800 gpm (RM-LV-104) 1112 - 1.69E+6 nepm x 15 gpm + 22,800 gpm (RM-LV-116)
F - Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tover Blowdown Rate (not including release through the Emergency Outfall Structure).
, f - Discharge flow rate prior to dilution (gpm).
1.1.1.1.1 BV-1 Mix Radionuclides 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 vere determined. Liquid source terms are the radioacti"ity 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" (Sg ) for each individual radionuclide in the liquid effluent was determined as follows:
A S
g,IA g i [1.1(1)-2]
i where:
Ag - Annual release ci 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 ) **8 t
determined by:
C t-F [1.1(1)-3]
b i
fE y i OEC*
1-3 ISSUE 3 O
- -- .. . - . - . .~. ... - - - . . -- - - . - . . . - - . . . . . . . - - .
BV-1 cnd 2 ODCH ,
i where:~
I F .= Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling a O Tower Blowdown Rate (not including release through the Emergency Outfall Structure).
- 22,800 gpm - (15,000 gpm BV-1 + 7,800 gpm BV-2) f = Maximum acceptable discharge flow rate prior.to dilution i (gpm).
= 35 gpm for IJquid Vaste Effluent Monitor (RM-LV-104). ,
- 15 gpm for Laundry and Contaminated Shower Drains Monitor -
(RM-LV-116).
OEC g - The ODCM liquid effluent concentration limit for !
radionuclide "i" (uci/ml) from Table l.1-la. The OEC is !
set at 10 times the new 10 CFR 20, Appendix B'(20.1001- l 20.2401) Table 2, Col. 2 EC values. l 1
Sg - The fraction of total radioactivity attributed to ,
radionuclide "i", from Equation [1.1(1)-2].
1.1.1.1.3 BV-1 Maximum Acceptable Concentration (Individual Radionuclide) a The .vaximum acceptable radioactivity concentration (uci/ml) of radionuclide "i" in the liquid effluent prior to dilution (C g ) was determined by:
O Cg-Sg C t
[1.1(1)-4]
l 1.1.1.1.4 BV-1 Monitor Count Rate j The calculated monitor count rate (nepm) above background attributed to the radionuclides, C.R., was determined by:
C.R. - I C _g Eg -[1.1(1)-5]
i vhere:
E g - Detection efficiency of.the monitor for radionuclide "i" (cpm /uci/ml) from Table 1.1-la. .If not listed there, from j Reference 1.1.4.
1.1.1.1.5 BV-1 Monitor HHSP The monitor HIGH-HIGH Alarm Setpoint ,above background (neps) should be set at the C.R. value. Since only one tank can be released at a i time, adjustment of this value- is not necessary to compensate for y release from more than one source.
O 1-4 ISSUE 3
BV-1 rnd 2 ODCM 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release A !
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-HIGH Alarm Setpoint based on this flov <
rate for the Liquid Vaste Effluent Monitor (RM-LV-104) and the Laundry 1 and Contaminated Shower Drains Monitor (RM-LV-116) during all l 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 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.
1.1.1.2.1 BV-1 Maximum Acceptable Discharge Flow Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by f, F [1.1(1)-6]
Cg 1.25 E i OEC g where:
F - Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blovdown (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 administratively prohibited.
Cg - Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uci/ml) fron 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.
OECg - The ODCM liquid effluent concentration limit for radionuclide "i" (uCi/ml) from Table 1.1-la. The OEC is set at 10 times the nev 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values.
7 O
1-5 ISSUE 3
~ - - - . - - . . . - - - ..-.. - - -. .. ... - , ._ ~ . . - - . . . - ~ . _ - -. . . _ .
BV-1 cnd 2 ODCM 1.1.1.2.2 BV-1 Monitor Count Rate
-h The calculated _ monitor count rate (nepm) above background attributed
- to the radionuclides (C.R.) is determined by
C.R. = 1.25 I Cg Eg [1.1(1)-7]
I l
where:
^
.E g = The 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.
1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response. ed 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 where:
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 I determined by. equation-[1.1(1)-6].
f' ' - Actual maximum discharge flow rate,to be maintained for the discharge. The reduced value of f may be due to pump p limitations or administrative selection.
i l
O 1-6 ISSUE 3
BV-1 end 2 ODCM 1.1.2 BV-2 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds 10 times the EC's specified in 10 CFR 20, Appendix B (20.1001-20.2401), Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2E-4 uCi/ml for dissolved or entrained noble gases (see Reference 1.2.6).
The methodology described in Section 1.1.2.2 is an alternative method to be used to determine the (2SGC-RQ100) 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 9.55E-4 uCi/ml. This concentration is equivalent to a monitor response and HIGH Alarm Setpoint derived in Section 1.1.2.1 and allows for a tritium concentration of up to 2.19E+0 uCi/ml. The setpoint was obtained by use of a conversion factor of 5.09E-9 uCi/ml/ cpm 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 monitors should be set at the values listed as follows:
BV-2 LIQUID MONITOR SETPOINTS uCi/ml Above Background Monitor DV HSP ASP
- Liquid Vaste Effluent 2SGC-R0100 9.84E-4 9.84E-4 6.89E-4 Monitor
- Service Vater Monitor 2SVS-R0101 4.28E-5 4.28E-5 2.99E-5
- Service Vater Monitor 2SVS-R0102 4.28E-5 4.28E-5 2.99E-5 The setpoint for 2SGC-R0100 is based on the following conditions, however, the setpoint bases for 2SVS-R0101 and 2 SUS-R0102 can be found in Reference 1.2.6:
- Source terms given in Table 1.1-1b. These source terms have been generated by using models and input similar to NUREG-0017. The inputs are given in Appendix B.
- Dilution water flow rate of 22,800 gpm - (15,000 gpm BV-1 + 7,800 gpm BV-2).
- Discharge flow rate prior to dilution of 80 gpm for the Liquid Waste Effluent Monitor (2SGC-R0100).
- A software conversion factor of 5.09E-9 uCi/ml/ cpm associated with Liquid Vaste Effluent Monitor (2SGC-R0100).
The above setpoint for (2SGC-R0100) can be varied based on actual operating conditions resulting in the discharge and dilution flow rates as follows: "
O' 1-7 ISSUE 3
BV-1 cnd 2 ODCM 4
[1.1(2)-1]
HSP = 3.50E-6 f
F where:
HSP = Monitor HIGH Alarm Setpoint (uCi/ml) above background.
3.50E Proportionality constant based on nominal flow conditions:
3.50E-6 = 9.98E-4 net uCi/ml x 80 gpm + 22,800 gpm F = Dilution water flow rate, BV-1 plus BV-2 Cooling Tower Blovdown Rate (gpm).
f = Discharge flow rate prior to dilution (gpm).
1.1.2.1.1 BV-2 Hix Radionuclides 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 1.1-1b.
- 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:
C S A
i [1.1(2)-2]
g,IA t
where A g = Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from Table 1.1-1b.
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 )t was determined by:
C F [1.1(2)-3]
t- b i
fI i OEC g where:
F = Dilution water flow rate (gpm), BV-1 plus BV-2 Cooling Tower Blowdown Rate (not including release out through the y p Emergency Outfall Structure).
1-8 ISSUE 3
BV-1 cnd 2 ODCH
- 22,800 gpm - (15,000 gpa BV-1 + 7,800 gpm BV-2). , ,
f - Maximum acceptable discharge flow rate prior to dilution (gpm).
- 80 gpm for Liquid Vaste Process Effluent Monitor (2SGC-R0100).
OECg - The ODCH liquid effluent concentration limit for radionuclide "i" (uCi/ml) from Table 1.1-1b. The OEC is set at 10 times the nev 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values.
Sg - The fraction of total radioactivity attributed to radionuclide "i", from Equation [1.1(2)-2].
1.1.2.1.3 BV-2 Haximum Acceptable Concentration (Individual Radionuclide)
The maximum acceptable radioactivity concentration (uCi/ml) of radionuclide "i" in the liquid effluent prior to dilution (C g) was determined by:
C 1, t
[1.1(2)-4]
1.1.2.1.4 BV-2 Honitor 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 Eg [1.1(2)-5) i where:
5.09E-9 Conversion factor (uci/ml/ cpm), an average determined for the source term mix.
Eg - Detection efficiency of the monitor for radionuclide "i" (cpm /uci/ml) from Table 1.1-1b.
1.1.2.1.5 BV-2 Honitor HSP The monitor HIGH Alarm Setpoint above background (uCi/ml) should be w set at the D.V. value.
ISSUE 3 O
1-9
- - . . . . - . - . - . . . . . - ~ . _ _ - . - - - . - - - - . - . - . - - - _ - - . ~ .
BV-1 cnd 2 ODCM- ,
1.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release 4 ,
The following method applies to liquid releases when determining the O setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH Alarm Setpoint based on this' flow rate .
Monitor -(2SGC-RQ100) during all
.i
.for the Liquid Vaste . Effluent ,
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 radvasta discharge pump rate-capacity or by administrative- selection rather than the~ allowable flov' rate determined form activity concentration, the alarm setpoint t will be proportionally adjusted. based _upon the~ excess dilution. factor provided. 6/7 1.1.2.2.1 BV-2 Maximum Acceptable Discharge Flow Rate ;
E ,
The maximum acceptable discharge flow rate (f) prior to dilution ,
(gpm) is determined by:
l F [1.1(2)-6]
fg Cg 1.25 E where F. - Dilution water flow rate, BV-1 plus BV-2 Cooling Tower l Blovdown (gpa).
The dilution water-flow rate may include the' combined cooling tower blowdown flow from both units exiting the discharge structure (but excluding emergency outfall ,
' structure flow) when simultaneous liquid discharges from 1 both plants are administratively prohibited.
Og - Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uci/ml) from analysis of the liquid effluent to be released. i 1.25 - A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the 3onitor response.
OEC g - The ODCM liquid effluent concentration limit for radionuclide "i" (uci/ml) from Table 1.1-1b. The OEC is set at 10 times the new 10 CFR 20, Appendix B (20.1001-20.2401) Table 2, Col. 2 EC values. 'f O ISSUE 3 1-10
- - - , . _ . . ~ .
BV-1 and 2 ODCH 1.1.2.2.2 BV-2 Monitor Display Valuj The calculated monitor Display Value (uCi/ml) above background A attributed to the radionuclides (D.V.) is determined by:
D.V. - (1.25) (5.09E-9) I CgEg [1.1(2)-7]
vhere:
Eg - 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. e/if 5.09E Conversion factor (uci/ml/ cpm), 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 background (uCi/ml) should be set at the D.V. value adjusted by any excess dilution factor provided as defined in the following equation:
HSP - D.V. f, [1.1(2)-8]
I vhere:
HSP - Monitor HIGH Alarm Setpoint above background.
D.V. - Calculated monitor concentration reading (uCi/ml) from equation [1.1(2)-7].
f - Maximum acceptable discharge flow rate prior to dilution determined by equation [1.1(2)-6].
f - Actual maximum discharge flow rate,to be maintained for the discharge. The reduced value of i may be due to pump "
limitations or administrative selection.
l l
1-11 ISSUE 3 O!l l
l
. . - - . . - - - - . - . ~ . ~ . _ .. . - . . - . - . - . . - - . . . _ - . . - . - . . . - _ _ _
-BV-1 cnd 2 ODCM (l
TABLE 1.1-la l
BV-1 LIQUID SOURCE TERM 1 O
O Eg )( ,
'A DETECTION i
OEC - EFFICIENCY
' ANNUAL RELEASE i NUCLIDE (C1)** (uCi/ml)*** (cpm /uCi/ml)**** '
'l l Cr-51 9.00E SE-3 1.18E+7 !
Mn-54' 2.00E-5 3E-4 8.59E+7 S.00E-5 1E-3 '*****
.Fe-55 Fe-59 5.00E-5 1E-4 9.17E+7 i co-58 7.70E-4 2E-4' '1.16E+8 i I
Co-60 1.00E-4 '3E-5 1.73E+8 Np-239 5.00E-5 2E-4 8.49E+7 l Br-83 6.00E-5 9E-3 1.36E+6 1.00E-5 7E-5 *****
- - Rb-86 ,
2.00E-5' 8E-5 ***** l l Sr-89 Sr-91 1.00E-5 2E-4 6.97E+7'
'2E-4 2.84E+7 l Mo 3.90E-3
.Tc-99m 5.37E-3' 1E-2. 8.96E+7 1 Te-127m 1.00E-5 9E-5 4.09E+4- l Te-127- 3.00E-5 1E-3 1.38E+6 Te-129m 7.00E-5' 7E-5 4;02E*6 '
Te-129 5.00E-5 4E-3 1.12E+7. Mr l 1- I-130 2.50E-4 ~ 2E-4 3.08E+8 i Te-131m. 9.00E-5 8E-5 1.82E+8 i Te-131 2.00E-5 8E-4 1.20E+8 I-131 6.03E-2 1E-5 1.11E+8 Te-132 1.15E-3 9E-5 1.17E+8 l
I-132 5.38E-3 1E-3 2.66E+8. I I-133 .5.77E-2 7E-5 9.90E+7 I-134. 1.00E-5 4E-3 2.70E+8 Cs-134' 3.80E-3 9E-6 1.99E+8 I-135 1.34E-2 3E-4 :1.19E+8 Cs-136- 1.90E-3 6E-5 2.80E+8'
-Cs-137 2.70E-3 1E-5 8.01E+7
.Ba-140 1.00E-5 8E-5 4.37E+7 La-140 1.00E-5 9E-5 '2.00E+8 1.60E+2 1E-2 *****
H-3~
All Others* 4.00E-5 1E-7
- TOTAL
- 1.57E-1 l
- Excluding Tritium and Entrained Noble Gases 1
- Source Term for (RM-LV-104 and RM-LV-116) from Reference (1.1.2) !
- 0DCM Effluent Concentration Limit - 10 times the EC values of Reference (1.1.3) !
l
- Detection Efficiency for (RM-LV-104 and RM-LV-116) from Reference (1.1.4) y
.***** Insignificant 1-12 ISSUE 3 l i
BV-1 ond 2 ODCH TABLE 1.1-lb BV-2 LIQUID SOURCE TERM Eg A
A l DETECTION OEC ANNUAL RELEASE i EFFICIENCY NUCLIDE (Ci)*** (uCi/ml)** (cpm /uCi/ml)****
Cr-51 1.00E-4 SE-3 2.01E+7 Hn-54 2.50E-5 3E-4 1.27E+8 Fe-55 1.30E-4 IE-3 *****
Fe-59 6.50E-5 1E-4 1.26E+8 Co-58 1.10E-3 2E-4 1.82E+8 Co-60 1.60E-4 3E-5 2.38E+8 Np-239 3.20E-5 2E-4 1.65E+8 Br-83 2.90E-5 9E-3 2.42E+6 Br-84 5.90E-9 4E-3 1.38E+8 Rb-86 3.70E-5 7E-5 1.04E+7 Sr-89 2.20E-5 8E-5 1.83E+4 Sr-90 8.50E-7 SE-6 *****
Sr-91 5.30E-6 2E-4 1.04E+8 Ho-99 2.30E-3 2E-4 4.47E+7 Tc-99m 2.10E-3 1E-2 1.40E+8 Te-125m 1.90E-6 2E-4 3.94E+5 Te-127m 2.10E-5 9E-5 1.26E+5 Te-127 2.50E-5 1E-3 2.43E+6 Te-129m 8.20E-5 7E-5 6.53E+6 Te-129 5.30E-5 4E-3 1.96E+7 I-130 2.30E-4 2E-4 5.18E+8 Te-131m 5.20E-5 8E-5 2.85E+8 Te-131 9.40E-6 8E-4 1.88E+8 I-131 1.00E-1 1E-5 1.96E+8 Te-132 7.80E-4 9E-5 1.76E+8 I-132 2.30E-3 1E-3 4.22E+8 I-133 6.50E-2 7E-5 1.73E+8 I-134 4.60E-6 4E-3 4.06E+8 Cs-134 3.00E-2 9E-6 3.25E+8 I-135 9.20E-3 3E-4 1.71E+8 Cs-136 3.90E-3 6E-5 4.28E+8 Cs-137 2.20E-2 IE-5 1.28E+8 Ba-140 9.30E-6 8E-5 7.50E+7 La-140 8.40E-6 9E-5 3.08E+8
- Excluding Tritium and Entrained Noble Gses
- 0DCH Effluent Concentration Limit - 10 times the EC values of Reference (1.2.1)
- Source Term for (2SGC-R0100) from Reference (1.2.3)
- Detection Efficiency for (2SGC-R0100) from References (1.2.2) and (1.2.4) ,
- Insignificant )
1-13 ISSUE 3 9
BV-1 end 2 ODCM TABLE 1.1-1b (continu2d)
BV-2 LIQUID SOURCE TERM C)
O A E
$ )
l DETECTION OEC EFFICIENCY ANNUAL RELEASE i NUCLIDE (Ci)*** (uCi/ml)** (cpm /uCi/ml)****
Y-91m 3.60E-6 2E-2 -1.59E+8 Y-91' 4.40E-6 8E-5 3.55E+5 Y-93 3.00E-7 2E-4 2.03E+7 Zr-95 4.00E-6 2E-4 1.35E+8 4 Nb-95 4.00E-6 3E-4 1.33E+8 Ru-103 2.70E-6 '3E-4 1.71E+8-8.20E-7 3E-5 *****
Ru-106 2.70E-6 6E-2 *****
Rh-103m Rh-106 8.20E-7 -- 5.65E+7 ,
Ce-141 4.00E-6 3E-4 7.75E+7 l Ce-143 8.60E-7 2E-4 1.20E+8 l Ce-144 2.60E-6 3E-5 1.87E+7 l Pr-143 2.30E-6 2E 4 1.63E+0 Pr-144 2.60E-6 6E-3 3.40E+6 5.50E+2 1E-2 *****
H-3 TOTAL
- 2.40E-1 O
l
- Excluding Tritium and Entrained Noble Gses ,
- 0DCM Effluent Concentration Limit - 10 times the EC values of Reference (1.2.1)
- Source Term for (2SGC-R0100) from Reference (1.2.3)
- Detection Efficiency for (2SGC-R0100) from References (1.2.2) and (1.2.4) Y
- Insignificant 1-14 ISSUE 3
BV-1 end 2 ODCM REFERENCES BV-1 LIQUID EFFLUENT MONITOR SETPOINTS 4 1.1.1 " Beaver Valley Power Station, Appendix I Analysia - 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 1.1.3 10 CFR 20, Appendix B, (20.1001-20.2401) Table 2, Column 2 EC's 1.1.4 Isotopic Efficiencies For Unit 1 Liquid Process Monitors; DLCo Calculation Package No. ERS-SFL-92-039 1.1.5 Process Alarm Setpoints For Liquid Effluent Monitors; DLCo Calculation Packge No. ERS-ATL-93-021 8/W REFERENCES BV-2 LIQUID EFFLUENT MONITOR SETPOINTS 1.2.1 10 CFR 20, Appendix B, (20.1001-20.2401) Table 2, Column 2 EC's i
1.2.2 Unit 2 DRMS Isotopic Efficiencies; DLCo Calculation Package No.
ERS-SFL-86-026 1.2.3 Stone and Webster Computer Code LIQ 1BB; " Normal Liquid Releases From A Pressurized Vater Reactor" 1.2.4 Isotopic Efficiencies For 2SGC-R0Il00; DLCo Calculation Package No.
ERS-JVV-87-015 1.2.5 Conversion Factor for 2SGC-ROIL 00; DLCo Calculation Package No.
ERS-VFV-87-021 1.2.6 Process Alarm Setpoints For Liquid Effluent Monitors; DLCo Calculation Packge No. ERS-ATL-93-021 Y l l
1 l
I ISSUE 3 O
1-15 I
I
' BV-1 and 2 ODCM 1.2 Compliance With 10 CFR 20 EC Limits (ODCM Appendix C CONTROL 3.11.1.1) r 1.2.1 Batch Releases O] 1.2.1.1 Pre-Release The radioactivity content o'f each batch release vill be determined In l
prior to release in accordance with ODCM Appendix C, Table 4.11-1.
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 accomplished by recirculating the tank contents for at least the time periods indicated l in Table 1.2-la and 1.2-1b. BV-1 and BV-2 vill show compliance with ODCM Appendix C CONTROL 3.11.1.1 in the following manners l
The activity of the ve'ous radionuclides in the batch release, determined in accordant - 7 1 ODCM Appendix C, Table 4.11-1, is divided l
by the minimum diluticm flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation:
Cg R [1.2-1]
Cone y " MDF where:
Cone g - Concentration of'radionuclide "i" at the unrestricted area (uci/mD .
= Concentration of radionuclide "i" in the potential batch j Cg release (uci/ml). l R = Release rate of the batch (gpm).
I MDF = Minimum dilution flov (gpm). (May be combined BV-1/BV-2 flow when simultaneous liquid discharges are administratively prohibited).
a The projected concentrations in the unrestricted area are compared to the OEC's. Before a release is authorized, Expression (1.2-2] must'be satisfied.
I g (Cone /0EC g ) f 1
[1.2-2] ,
g h
where:
OEC g - The ODCM effluent concentration limit ofThe radionuclide (uCi/ml) from Table 1.1-la and 1.1-1b. OEC is set "i" at 10 times the new 10 CFR 20, Appendix B, (20.1001-20.2401) ,'
Table 2, Col. 2 EC values.
l l
l l
lO 1-16 ISSUE 3
BV-1 and 2 ODCM 1.2.1.2 Post R11re:sa 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 flow during the period of release to obtain the concentration in the unrestricted area. This calculation is shown in the following equation:
Y Conc ik -
ik tk [1.2-3]
ADF k
where:
Concik - unrestricted The concentration of radionuclide area, during the release"i"period (uci/ml) of at thek.
time Note: Since discharge is from an isolated vell-mixed tank at essentially a uniform rate, the difference between average and peak concentration within any discharge period is minimal.
C ik
= Concentration of'radionuclide "i" (uci/ml) in batch release during time peirod k.
V - V lume f tank released during time period k (gal).
tk ADF = Actual volume of dilution flow during the time period of k
release k (gal).
To show compliance with ODCH Appendix C CONTROL 3.11.1.1, the following relationship must hold: ,,
IS/12 I g(Concik/0ECg ) < 1 [1.2-4]
1-17 ISSUE 3 O
l BV-1 end 2 ODCM l l
1.2.2 Continuous Releases
- Continuous releases of liquid effluents do not presently occur at BV-1 or i BV-2. If they did occur, the concentration of various radionuclides in the unrestricted area vould be calculated using Equation [1.2-1] with Cik'
( the concentration of isotope i in the continuous release. To shov l compliance with ODCM Appendix C CONTROL 3.11.1.1, Expression'[1.2-4] must again hold.
1 .
1 i
1 l l l
. l l
O 1-18 ISSUE 3 l-i I
l
BV-1 cnd 2 ODCM TABLE 1.2-1c BV-1 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS APPR0XIMATE RECIRCULATION O
TANK DESCRIPTION MARK NO. TIME
- Laundry And Contaminated ILV-TK-6A/6B 2.5 hrs - (1200 gal)(2)/(16 gpm)
Shower Drain Tanks Lov Level Vaste Drain Tanks 1LV-TK-3A/3B 1.5 hrs - (2000 gal)(2)/(45 gpm)
High Level Vaste Drain Tanks ** 1LV-TK-2A/2B 3.4 hrs - (5000 gal)(2)/(50 gpm)
Evaporator Test Tanks 1LV-TK-5A/5B 1.4 hrs - (3000 gal)(2)/(73 gpm)
Steam Generator Drain Tanks 1LV-TK-7A/7B 17.2 hrs -(35000 gal)(2)/(68 gpm)
Boron Recovery Test Tanks 1BR-TK-2A/2B 9.7 hrs -(13,000 gal)(2)/(45 gpm)
O
- The times listed are those approximated 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.
- Not normally a direct source of discharge.
O 1-19 ISSUE 3
BV-1 and 2 ODCM TABLE 1.2-1b BV-2 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS O APPROXIMATE RECIRCULATION TANK DESCRIPTION MARK NO. TIME
- l Liquid Waste Tanks 2LVS-TK21A/21B 11.5 hrs - (10,000 gal)(2)/(29 gpm)
Steam Generator Blowdown 2SGC-TK21A/21B 25.8 hrs - (51,000 gal)(2)/(66 gpa)
Hold Tanks Steam Generator Blowdown 2SGC-TK23A/23B 9.1 hrs -(18,000 gal)(2)/(66 gpm)
Test Tanks O
I
- The times listed are those approximated 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.
1-20 ISSUE 3
i l BV-1 and 2 ODCM l
1.3 Compliance Vith 10 CFR 50 Dose Limits (ODCM Appendix C CONTROLS 3.11.1.2 And 3.11.1.3)
I /n :
l D) BV-1 and 2 utilize the concept of a shared. liquid radioactive vaste system according to NUREG 0133.
l This permits mixing of the liquid radvaste for processing. Since the resulting effluent release cannot accurately be ascribed to a specific reactor unit, the treated effluent releases are allocated as defined below.
1.3.1 Cumulation Of Doses (0DCM Appendix C CONTROL 3.11.1.2) i i
The dose contribution from the release of liquid effluents vill be l 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 Ag I"ot k Cik Fk [1.3-1]
i k-1 where:
DT = The cumulative dose commitment to the total body or any organ, from the liquid effluents for the total time period T, j m
-]
I at k I"#'*)
k=1
/N Q. otk - The length of the kth release over which Cik and Fk are averaged for all liquid releases (hours).
Cik - The average concentration of radionuclide, "i" (uci/ml), in undiluted liquid effluent during time period-ot from k any liquid release.
A gT - The site related ingestion dose commitment factor to the total body or any organ T for each identified principal gamma and beta emitter (mrem-ml per hr-uci).
m - Number of releases contributing to the cumulative dose, D .
UAF = Unit allocation factor. Provides apportionment of dose between BV-1 and BV-2. Normally set at 0.5 for each unit. (Must total to 1.0).
F k
- The near field average dilution factor for C during any liquid effluent release. Definedastheratibkof the average undiluted liquid vaste_flov to the product of the average flov
~
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 effect of the BV-1 and BV-2 discharge structure).
= Vaste Flov i (3)(Dilution Vater Flov) 1-21 ISSUL 3
BV-1 and 2 ODCM 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.
The dose factor A vas calculated for an adult for each isotope using thefollowingequkfionfromNUREG-0133.
Ah - 1.14E5 (730/D y+ 21BF )DF g h [1.3-2]
vhere:
1.14E5 - 1E6 pg 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 g = Bioaccumulation factor for radionuclide "i" in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1 (pCi/kg per pCi/1). However, if data was not available from that reference, it was obtained from Table 6 of UC RL-50564, Revision 1.
The bioaccumulation factor for niobium (300 pCi/kg per pCi/1) was not obtained from either of the above references noted. It was otained from IAEA Safety Series No. 57. soff Justification for use of this value is documented in Appendix A to Calculation Package No. ERS-ATL-83-027.
DF IT = Dose conversion factor for radionuclide "i" for adults for a 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.iT The far field dilution factor (D )y 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 below the water surface, essentially fully mixed conditions vould have to exist for the radioactive effluent to be transported to the intake.
O 1-22 ISSUE 3 Revision 1
BV-1 and 2 ODCM i
i The cumulative doses (from each reactor unit) for a calendar quarter and
! r'] a calendar year are compared to ODCM Appendix C CONTROL 3.11.1.2 as
() follows:
For the calendar quarter, 1
l D f 1.5 mrem total body [1.3-3)
D73 5 mrem any organ. [1.3-4j For the calendar year, D f 3 mrem total body [1.3-5]
D f 10 mrem any organ [1.3-6]
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 (ODCh M pendix C CONTROL 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, s when the proj ec ted doses due to liquid effluent releases from each 1
) 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:
Vhen including pre-release data,
[1.3-7]. ;
31 + C D
31 - A+B T When not including pre-release data, j
[1.3-8] )
D A 31 + C 37 - T where:
D31 - Projected 31 day dose (mrem).
A - Cumulative dose for quarter (mrem).
B - Projected dose from this release (mrem).
T - Current days into quarter.
C - Value which may be used to anticipate plant trends (mrem).
b 1-23 ISSUE 3 Revision 1 i
BV_1 end 2 ODCM TABLE 1.3-1 A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE it (mrem /hr per uCi/ml)
NUCLIDE BONE LIVER T_ BODY THYR 0ID 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 0.00S_01 5.24E 01 0.00E_01 0.00E-01 0.00E-01 4.11E_04 Br-85 0.00E-01 0.00E_01 2.15E 00 0.00E-01 0.00E-01 0.00E_01 0.00E_01 Rb-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E_01 0.00E-01 1.99E 04 Rb-88 0.00E-01 2.90E 02 1.54E 02 0.00E_01 0.00E-01 0.00E-01 4.00E-09 Rb-89 0.00E-01 1.92E 02 1.35E 02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 Sr-89 2.22E 04 0.00E_01 6.39E 02 0.00E-01 0.00E_01 0.00E-01 3.57E 03 Sr-90 5.48E 05 0.00E_01 1.34E 05 0.00E-01 0.00E-01 0.00E_01 1.58E 04 Sr_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 Y_90 5.80E-01 0.00E_01 1.55E-02 0.00E-01 0.00E-01 0.00E-01 6.15E 03 Y-91m 5.48E-03 0.00E_01 2.12E-04 0.00E-01 0.00E_01 0.00E-01 1.61E-02 Y_91 8.'50E 00 0.00E_01 2.27E_01 0.00E-01 0.00E-01 0.00E-01 4.68E 03 Y_92 5.09E-02 0.00E_01 1.49E-03 0.00E-01 0.00E-01 0.00E-01 8.92E 02 Y_93 1.62E-01 0.00E_01 4.46E-03 0.00E-01 0.00E-01 0.00E_01 5.12E 03 ;
Zr-95 2.53E-01 8.11E_02 5.49E-02 0.00E-01 1.27E_01 0.00E-01 2.57E 02 l Zr_97 1.40E-02 2.82E-03 1.29E-03 0.00E-01 4.26E-03 0.00E_01 8.73E 02 Nb-95 4.47E 00 2.49E 00 1.34E 00 0.00E-01 2.46E 00 0.00E-01 1.51E 04,, f Nb-97 3.75E 02 9.49E-03 3.46E-03 0.00E-01 1.11E-02 0.00E-01 3.50E 01 1_24 ISSUE 3 Revision 1
BV_1 and 2 ODCM TABLE 1.3 1 l l
Ag VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem /hr per uCi/ml)
(,, )
x_-
NUCLIDE BONE LIVER T-B0DY 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-110m 9.48E-01 8.77E_01 5.21E_01 0.00E-01 1.72E 00 0.00E-01 3.58E 02
-Sb_124 7.87E 00 1.49E-01 3.12E 00 1.91E-02 0.00E-01 6.13E 00 2.23E 02 Sb_125 5.03E 00 5.62E-02 1.20E 00 5.11E_03 0.00E_01 3.88E 00 5.54E 01 Te-125m 2.57E 03 9.30E 02 3.44E 02 7.72E 02 1.04E 04 0.00E-01 1.03E 04 l 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 l Te-129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E_01 2.27E 01 1 Te_131m 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E.01 8.05E 04 i Te-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.27E 01 0.00E-01 2.67E 00 .
Te_132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.39E 04 l
(~'} Te-134 3.10E 01 2.03E 01 1.25E 01 2.71E 01 1.96E 02 0.00E-01 3.44E-02 l q ,) _______________________________________._____________.______________._____.__
\
I_129 1.19E 02 1.02E 02 3.35E 02 2.63E 05 2.19E 02 0.00E-01 1.61E 01 I-130 2.75E 01 8.10E 01 3.20E 01 6.87E 03 1.26E 02 0.00E_01 6.97E 01 ;
I_131 1.51E 02 2.16E 02 1.24E 02 7.08E 04 3.71E 02 0.00E_01 5.70E 01 I-132 7.37E 00 1.97E 01 6.90E 00 6.90E 02 3.14E 01 0.00E-01 3.71E 00 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 I-135 1.61E 01 4.21E 01 1.55E 01 2.78E 03 6.76E 01 0.00E_01 4.76E 01 l 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 l Cs-137 3.82E 05 5.22E 05 3.42E 05 0.00E_01 1.77E 05 5.89E 04 1.01E 04 Cs-138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 ;
Ba-139 9.69E-01 6.90E_04 2.84E_02 0.00E-01 6.45E-04 3.92E-04 1.72E 00 l 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_140 1.51E-01 7.59E-02 2.01E-02 0.00E-01 0.00E-01 0.00E_01 5.57E 03 La_142 7.71E-03 3.51E-03 8.74E-04 0.00E-01 0.00E-01 0.00E-01 2.56E 01 Ce-141 2.63E-02 1.78E-02 2.02E-03 0.00E-01 8.26E-03 0.00E-01 6.80E 01 V
1_25 ISSUE 3
BV-1 and 2 ODCM TABLE 1.3_1 A VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE h
(mrem /hr per uC1/ml)
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 Ce_144 Pr-143 1.37E 00 5.73E-01 7.36E-02 0.00E-01 3.40E-01 0.00E-01 4.64E 02 5.54E-01 2.22E-01 2.75E-02 0.00E-01 1.28E-01 0.00E-01 2.43E 03 Pr-144 Nd-147 1.81E-03 7.53E-04 9.22E-05 0.00E-01 4.25E-04 0.00E-01 2.61E.10 V-187 3.79E-01 4.38E-01 2.62E_02 0.00E-01 2.56E-01 0.00E-01 2.10E 03 2.96E 02 2.47E 02 8.65E 01 0.00E-01 0.00E-01 0.00E_01 8.10E 04 Np-239 2.90E-02 2.85E-03 1.57E-03 0.00E-01 8.89E-03 0.00E-01 5.85E 02 O
BV-1 and 2 0DCM 1.4 Liquid Radvaste System l The liquid radvaste system has the capability to control, collect, process,
/~') ' store, recycle, and dispose of liquid radioactive vaste generated as a
\~_/ result of plant operations, including anticipated operational occurrences.
This system also uses some of the components of the steam generator blovdown 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.
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l-27 ISSUE 3 4
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4
BV-1 end 2 ODCM 1.4.1 BV-1 Liquid R-dveste Systra Co3ponents 1.4.1.1 LV-TK-2A & 2B: High Level Vaste Drain Tanks There are two of these tanks, each tank has a capacity of 5,000 gallons. They are located on the northwest vall of the Auxiliary Building (elevation 735'). They receive liquid vastes from the vent and drain system with activity concentrations above 4E-4 uCi/ml.
1.4.1.2 LV-TK-3A & 3B: Lov Level Vaste Drain Tanks There are two of these tanks, each tank has a capacity of 2,000 gallons. They are located in the northwest corner of the Auxiliary Building (elevation 735'). They receive liquid vastes from the vent and drain system with activity concentrations less than 4E-4 uCi/ml.
1.4.1.3 LV-I-2: Liquid Vaste Demineralizer The main purpose of the demineralizer is to clean liquid vaste water of particulate and dissolved radioactive contaminants. There are four resin beds and a filter associated with this demineralizer. Each of the beds can be customized with different resins so that we can effectively remove chemical contaminants along with radioactive contaminants. Generally, beds 1 and 2 contain a Cation Resin and beds 3 and 4 contain a Mixed Bed Resin. This demineralizer is locateJ in the Decon Building (elevation 735').
1.4.1.4 LV-TK-7A & 7B: Steam Generator Drain Tanks There are two of these tanks, each tank has a capacity of 34,500 gallons. They are located in the Fuel Fool Leakage Monitoring Room (elevation 735'). They receive liquid vaste that has been processed through the liquid vaste demineralizer. Once this tank is full, it is put on recirculation through the demineralizer (for a minimum of two tank volumes) until the radioactivity concentration is acceptable for discharge.
1.4.1.5 RM-LV-104: Liquid Vaste Discharge Radiation Monitor This off-line gamma scintillator radiation monitor continuously analyzes liquid vaste as it is being discharged. The upper activity alarm on this radiation monitor has a setpoint that would indicate ve are approaching OEC limits for radioactive water leaving the site. If an upper activity alarm on this radiation monitor is received, it automatically terminates the discharge by closing the discharge line isolation valves.
1-28 ISSUE 3 l i
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1 BV-1 and 2 ODCM '
1.4.2- BV-2 Liquid Radvaste System Componerits 1.4.2.1 2LUS-TK21A & 218:' Vaste Drain Tanks O- :There are two.. of these tanks,. each tank- has a capacity of-10,000 gallons. They are located in the northeast corner of the Auxiliary Building (elevation 710'). They receive liquid vastes'from the vent and drain system.
1.4.2.2 2SGC-IOE21A & 21B:' Steam Generator Blowdown Cleanup Ion Exchangers The main purpose of the ion- exchangers ois to clean liquid vaste. vater of particulate and dissolved radioactive. contaminants through an. ion exchange process. There is a . resin bed, outlets strainer, and cleanup filter associated with'each of these ion exchangers. They.are located-in the Vaste Handling Building (elevation 722').
1.4.2.3 2SGC-TK23A & 23B: Steam' Generator Blovdown Test Tanks
.There are two of these tanks, each has a' capacity of 18,000 gallons.
They are located. in the Auxiliary Building-'(elevation 755'). They receive liquid vaste that has been- processed'through the' cleanup; ion exchangers. Once.this tank is-full, iti is put on recirculation'through the' cleanup ion exchanger;(for a minimum of two tank volumes) until the radioactivity concentration is acceptable.for-discharge..
1.4.2.4 2SGC-TK21A & 21B: Steam Generator. Blowdown Hold Tanks There are two of these' tanks, each has a capacity of.50,000 gallons.
They are located 'in the Vaste Handling. Building (elevation'722'). .
/~ These tanks are used to. store . liquid vaste .when ;the radioactive concentration. of the steam generator' blowdown ' test tank 'is- not acceptable for discharge.- The contents of this tank ~is then-processed through the Unit 1 or Unit 2 Liquid Radvaste Treatment System until the radioactivity concentration is acceptable for discharge.
1.4.2.5 .2SGC-RO-100: ' Liquid Vaste Effluent' Monitor This off-line gamma scintillator radiation monitor- continuously-
-analyzes liquid vaste as it is .being discharged. The upper activity-alarm on this radiation monitor has a setpoint that vould indicate ve are approaching OEC limits for radioactive-: vater leaving the site. If an upper activity alarm is received, it automatically terminates the discharge by closing the discharge line isolation valves.
l-29 ISSUE 3 O
- s
EV-1 and 2 Ot<M FIGURE 1.4-1 BV-1 LIQUID RADiaS'IE SYSTEM STREAM STREAM FLOW COLLECTION, TREATMEAT. E DISCHARGE evPS-2 No. RATE coating I. CONT SUMP 40GPD HIGN -LEVEL LIQUID EVAPORATOR BL N
ION EXCHANGER - TAMES 2
- 3. LAB DRAINS 400$PD AN 5 2 -
d b OF m 10 5,000 G AL
- 4. R.P. SAMPLES 35GPD lN G
_ ' TOWER S. MISC. SOURCES 6600PD a SLOWDOWN STEAN 15,000 GPM
- 6. MISC. SOURC E S 40GPD CENTRATOR 7 SG PRE FILTER lOGPD TANES 2 _
l ' 8vPS-l E.-2 BACK WASH 30,000 CAL COMOINED OISCMARGE SO GPM poigy 80 ROM TEST
- TANKS 2 14.500 GAL PURIFICATION l CS BOM BORON BORm
DFa10 *
- TANKS 2 - --
ISGPM
/HR DFslO 595,000 503ALL EXCEPTI GAL IO'I ,
BVPS-2883
' PURIFICATION CS lON STEAM i CVCS LETDOWN ION EXCHANGER GENERATOR 9- 60 pM SOO # EXCHA90GU (SVPS-2) '
OF 10 SIFIE R - ROwDOWN
{ / HR DFalO EVAPORATOR l 50. SveS-1 TuR8INE 7,2 OOGPD l aL G oRAINS NOTES: DISCHARGES TO BVPS-1 ENviRONisENT L INPUT TO BVPS-2 STEAM GENERATOR (SVPS-l YARD COOLING TOWER aLOwDOwN EVAPORATOR IS NOT USED DURING NORMAL BASE LOADED OPERATIONS.
DRAINAGE BLOWDOWN AND ENVIRONMENT DISCalARGE POINT)
- 2. IF RADICACTMTY IS DETECTED. TURBlNE BUILDING DRAINS CAN BE TRANSFERRED TO THE CHEMICAL WASTE SUMP AND TREATED AS LIQUlO WASTE.
i 1-30 ISSUE 3 O O O
O Of J BV-1 and 2 GCCM FIGURE 1.4-2 BV-2 LIGJID RADHASTE SYSTEM ST AM STR EAM L
AT COLLECTION, TREATMENT, L DISCH ACGE 8vPS-1 BVPS-ICOOteNG EVAPORATOR TOWER BLOWOOwee
- 1. CONT SUMP 40 GPD FEED PUMPS ISpOO GPM
- 2. AUX BLOG SUMP 2OO Go's WASTE WASTE LIQUID BVPS-2 DR AINS i r WASTE TEST 100 GPM , COOLING
~
- 4. R.R SAMPLES 3S GPO 7,000 GPM STEAM
- 5. LAB MAINS 400GPO SENERA M ,
m MM - , ,
TANKS 2 BVPS-l&-2 CONDENSATE DEMaN S0,000 GAL
- 6. 2,645 GPO COMBINED RINSE WASTE COOLING Own TO SVPS 2 TUR864E NO COLLECTION OR TREATM ENVIRONMENT DISCHARGE
- 7. {200 GPO
'"3 (8vPS-2 YARD ORAINAGE i OBSCHARGE POINT!
[
NOTESt L NO STEAM GENERATOR 8 LOWDOWN IS 9tSCHARGED.
- 2. TUR8lNC SUILDING ORAtNS ARE PROCESSED SY THE LIOut0 WASTE SYSTEM UPON HIGH ACitVITY.
DISCHARGES TO BVPS-2 1 COOLING TOWER !
BLOWDOWN AND ENVIRONMENT t
i 1-31 ISSUE 3 '
_ . . . . . ._.~. - . . _ _ . - . -.
BV-1 and 2 ODCM l
2.0 . GASEOUS EFFLUENTS t
l js{ ODCM Appendix C CONTROLS applicable to dose rate apply to the site.. The'
'l lQ site dose rate is due to the summation of releases from both units. ODCM.
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 i specific unit in the determination of site dose rate and dose attributed to !
that unit. Elevated releases from both units are considered to originate from a. shared radwaste system and are discharged from a common release ,
point, the Process Vent, at the top of the BV-1 cooling tover. At BV-1 and i 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 Pro:ess Vent shall be attributed to a specific' unit. {
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2-1 ISSUE 3 l
BV-1 and 2 ODCH 2.1 Alarm Setpoints 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 describes 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.
1 The methodologies described in Section 2.1.1.2, 2.1.2.2, and 2.1.3.2 I 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 f 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 epm as in BV-1. Thin l difference is due to BV-2 software which applies a conversion factor to j j
/O' the BV-2 raw data (cpm). The user is cautioned that- the uCf/cc l
d presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factor. In practice, l
setpoints determined for a calculated mix are correct for that mix.
Setpoints determined on analysis prior to release vill be correct for j i
properly controlling dose rate,,but the indicated uCi/cc value may differ from the actual value.
All effluent monitors specified herein have HIGH-HIGH (BV-1) or HIGF. l (BV-2) Alarm Setpoints established at 30 percent of the site limit, and except 3 monitors noted below, HIGH (BV-1) or ALERT (BV-2) Alarm l Setpoints established at 10 percent of the site limit.
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2-2 ISSUE 3 l
l
i BV-1 and 2 ODCH Honitor Setpoint Specifications Based On Fraction Of Site Limit 1
UNIT, RELEASE POINT AND HONITOR FRACTION OF SITE LIMITING DOSE RA 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 Storage Vault Vent 30% (HIGH) 0.1% (ALERT) 2RH0-R0303B Unit 2, Decontamination Building Vent 30% (HIGH) 0.3% (ALERT) 2RH0-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 ODCH Appendix C CONTROL 3.11.2.1:
- The site dose rate is less than 50% of the site limit when all monitors are below the HIGH (BV-1) snd 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.
2-3 ISSUE 3 l
l o
,_,si.-e6d 4 - 6 m - p... J a.5ma. _.i4_. *s: a e. -' ,way+ e. A-. .*-w A. m__..44 a mL BV-1 and 2 ODCM 1
A release may be batch or continuous in nature. Batch refers to releases ,
>= that are intermittent in. radionuclide concentrations or flov, such as l
\ releases from gas storage tanks, containment ventings and purges, and i k,)
s systems or components with infrequent use. Batch releases may be due to operational variations which result in radioactive releases greater than !
50% of the releases normally considered as continuous. Batch releases from these sources during normal operation, including anticipated ;
operational 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 l Sections 2.1.1.1 through 2.1.3.2.
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O 2-4 ISSUE 3
BV-1 and 2 ODCM 2.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix For Vkntilation 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 ABOVE 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 3.38E2 Vent
- Batch Release Of Containment (P)RM-VS-107B 1.93E3 5.80E2 1.93E2 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 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 GAS 1BB (which is similar 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.
- Discharge flow rate of 62,000 cfm for the BV-1 Ventilation Vent (Continuous).
- Discharge flow rate of 92,000 cfm for the BV-1 Ventilation Vent (Batch release of containment purge).
O 2-5 ISSUE 3 O
BV-1 cnd 2 ODCM 1
- Discharge flow rate of 49,300 cfm for the BV-1 Containment Vent (Both continuous and batch release of Containment Purge).
- O \
(. )
- Information listed under References - Gaseous Effluent Monitor Setpoints. !
The calculation method given in Sections 2.1.1.1.1 through 2.1.1.1.7 1 was used to derive the monitor setpoints for the following operational i conditions:
- Continuous release via the BV-1 Ventilation Vent. i
- Continuous release via the hV-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.
1 2.1.1.1.1 BV-1 Mix Radionuclides i 1
l The " mix" (noble gas radionuclides and composition) of the gaseous l effluent was determined as follows: I
- a. The gaseous source terms that are representative of the " mix" of I the gaseous effluent were selected. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent, l O Gaseous source terms can be obtained from Table 2.1-la.
N) b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (S ) for each individual 4
noble gas radionuclide in the gaseous effluent was determined by:
A S i [2.1(1)-1]
g,IA i
I ,
where:
A g = The total radioactivity or radioactivity concentration of noble gas radionuclide "i" in the gaseous effluent from Table 2.1-la.
2.1.1.1.2 BV-1 Maximum Acceptable Release Bate (Vhole Body Exposure)
The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (O )tbased upon the whole body exposure limit was calculated by:
0 500 [2.1(1)-2]
" (X/0) I Kg S i i
n
%s 2-6 ISSUE 3
BV-1 and 2 ODCM vheres (X/0)" - The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5.
= 1.03E-4 sec/m for continuous releases.
(X/q) " = The short term relative concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-36.
- 3.32E-4 sec/m3 for batch rel ase of containment purge.
(X/0)cv - 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 )3 from Table 2.2-4.
- 9.24E-5 sec/m3 for continuous releases.
(X/q)"" = The short term relative concentration of effluents released via the containment building vent for any area at or beyond the3unrestricted area boundary for any sectors (sec/m ) from Table 2.3-35.
- 3.08E-4 sec/m3 for batch release of containment purge.
Kg = The total whole body dose factor due to gamma 3emissions from noble gas radionuclide "i" (mrem / year /uci/m )
from Table 2.2-11.
Sg = From equation [2.1(1)-1] above.
2.1.1.1.3 BV-1 Maximum Acceptable Release Rate (Skin Exposure)
Og was also determined based upon the skin exposure limit by:
0 3000 [2.1(1)-3]
E " (X/0) I (Lg + 1.1M g) Sg i
where:
Lg = The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem / year /uci/m3 ) from Table 2.2-11.
Hg = The air dose factor due to gamma 3emissions from noble gas radionuclide "i"(mrad / year /uci/m ) from Table 2.2-11.
2-7 ISSUE 3 O
l l BV-1 end 2 ODCM t
i 1.1 - The ratie of the tissue to air absorption coefficients l- over the energy range of the photons of interest, O (mrem / mrad).
i b (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 )g for each individual noble gas.radionuclide in the gaseous effluent was determined by -
O.=S g g O t
[2.1(1)-4] ;
(NOTE: Use the lover of the 0 values obtained in E
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 effluent was determined by:
O g, 2.12E-3 0 1 [2.1(1)-5]
F where
(~ F = The maximum acceptable effluent flow rate at the point
- V} of release (cfm).
- 62,000 cfm (BV-1 Ventilation Vent)
= 49,300 cfm (BV-1 Containment Building Vent) 2.12E Unit conversion factor (60 sec/ min x 3.53E-5 ft3 fec), ;
2.1.1.1.6 BV-1 Monitor Count Rate The calculated monitor count rate (nepm) above background attributed to the noble gas radionuclide (C.R.) was determined by:
C.R. = I C3 Eg [2.1(1)-6)]
i where:
E g - The detection efficiency of the monitor for noble gas radionuclide "i" (cpm /uCi/cc) from Table 2.1-2a.
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d 2-8 ISSUE 3
BV-1 and 2 ODCH 2.1.1.1.7 BV-1 Honitor Setpoints The monitor alarm setpoints above background were determined as follows:
- a. The monitor HIGH-HIGH Alarm Setpoint above background (nepm) was determined by:
HHSP - 0.30 C.R. [2.1(1)-7)
- b. The monitor HIGH Alarm Setpoint above background (nepm) vas 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.
O O
2-9 ISSUE 3
1 BV-1 and 2 ODCM 2.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release For Ventilation Vent And Containment Building Vent Releases (Ground A . Releases)
- b. When the setpoints established using "the calculated mix" for ground releases do not provide adequate flexibility for operational needs, the method described below may be used in lieu of that set forth in Step 2.1.1.1. 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-HIGH Alarm Setpoint based on this flow rate for the Ventilation Vent Gas Monitor (RM-VS-101B) and i 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 j 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:
v 1.06 S T [2.1(1)-17]
I " (X/q) EKgC3 i
where:
1.06 - 500. mrem /yr x 2.12E-3 l 500 mrem /yr - dose rate limit !
2.12E-3 = unit conversion factor 3
= (60 sec/ min x 3.53E-5 ft /cc) 1 S = Percent of site dose rate released via this pathway. Up i 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 remaining release point limits must be correspondingly reduced or secured to provide the necessary margin below the site dose rate limit.
T - Maximum valve for T is 16 based on the limiting restriction in'0DCM Appendix C CONTROL 3.11.2.1.a where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes;
[V.) T - 960/60 = 16). See Reference 2.1.6.
2-10 ISSUE 3
BV-1 cnd 2 ODCM j i
(X/q)" - The highest calculated short term rel tive 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 2.3-36. l
- 3.32E-4 sec/m (X/q)cv - The highest released calculatedvia short term relative concentration l of effluents the Containment Building Vent for areas at or beyond3the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-37.
- 3.08E-4 sec/m ,
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.
Cg = 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.
- b. The flow rate (f) is also determined based upon the skin exposure limit as follows:
6.36 S T [2.1(1)-18]
I " (X/q) E (L3 + 1.1H g) Cg i
vhere:
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)
Lg - The skin dose factor due to beta emissions 3"* f noble gas radionuclide "i" (mrem / year /uCi/m ) from Table 2.2-11.
Hg - The air dose factor due to gamma emissions 3'* f noble gas radionuclide "i" (mrad / year /uci/m ) from Table 2.2-11.
(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 (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 maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
2-11 ISSUE 3 O
BV-1 and 2 ODCM
'2.1.1.2.2 BV-1 Honitor Setpoints The monitor alarm setpoints above background are determined as-O follows:
- a. The calculated monitor HIGH-HIGH Alarm Setpoint above background (nepm) attributed.to' the noble gav radionuclides is determined by:
fIC E g g [2.1(1)-19J
'I HHSP'- ,
F where:
f -.The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1.1.2.1.
- The maximum actual or design effluent flow rate (cfm) at F
the point of release.
- 92,000 cfm (BV-1 Ventilation Vent -- design)
- 49,300 cfm (BV-1 Containment Vent -- design)
Cg - 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.
E g - The detection efficiency of the monitor.for noble gas.
radionuclide "i" (cpm /uci/cc) from Table 2.1-2a.
- b. -When a HIGH-HIGH set point has been calculated according to this section, the monitor HIGH Alarm Setpoint above' background (nepm) is determined as follow': s HSP = HHSP x 0.33 [2.1(1)-20]
O 2-12 ISSUE 3
BV-1 end 2 ODCH 2.1.2 BV-2 Monitor Alera Satpoint Daterminstion 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 nepm, 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 SETPOINTS FOR GROUND RELEASES uCi/cc AB0VE BACKGROUND 30%
- SITE SITE C.R. D.V. LIMIT LIMIT MONITOR nepm 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 lh
' Batch Release Of 2HVS-R0101B 1.13E3 4.13E-5 1.24E-5 4.13E-6 Containment Purge Via The BV-2 Ventilation Vent
' Continuous 2HVS*R0109B 4.32E3 1.06E-4 3.17E-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
' Continuous 2RM0-R0301B 5.66E4 3.15E-3 9.44E-4 9.44E-6 Release Via The BV-2 Decontamination Building Vent
' Continuous 2RM0-R0303B 8.03E5 2.24E-2 6.71E-3 2.24E-5 Release 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
i BV-1 and 2 ODCM l i
The setpoints were determined using the following conditions:
(~S
- Source terms given in Table 2.1-1b. These gaseous source terms were !
1
( ,) 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 2.1-1b 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 vould 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 l vault. This spectrum is listed in Table 2.1-1b under Gaseous Vaste System. {
l
- 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). 1
- Discharge flow rate of 53,700 cfm for the BV-2 Ventilation Vent 1
(~]/
(,, (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). l
- 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 flow rate of 2,000 cfm for the BV-2 Vaste Gas Storage Vault Vent.
The calculation method given in Sections 2.1.2.1.1 through 2.1.2.1.7 was used to derive the alarm 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 (2RM0-R0301B), and Vaste Gas Storage Vault Vent Gas Monitor (2RM0-R0303B) during the following operational conditions:
- Continuous release via the BV-2 Ventilation Vent.
f3
- Continuous release via the BV-2 Containment Vent.
Iv) 2-14 ISSUE 3
BU-1 and 2 ODCM
- Batch release of BV-2 Containment Purge via the BV-2 V'entilation 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 Hix 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 were selected based on the relative stream composition and volumetric flovrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.
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 4
noble gas radionuclide in the gaseous effluent was determined by:
A S i [2.l(2)-1]
g,IA 1
1 where:
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 )tbased upon the whole body exposure limit was calculated by:
0 500 [2.l(2)-2]
E " (X/0) EKg S g i
where:
(X/0)"# - The highest calculated annual average relative concentration of effluents released via the Ventilation Vent for any area at or beyond3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-5.
- 1.03E-4 sec/m for continuous releases.
ISSUE 3 O
2-15 1
i a
BV-1 and 2 ODCM (X/q) " - The short term relative concentration of effluents released via the Ventilation Vent for any area at or
/'d beyond 3 the unrestricted area boundary for all sectors
(.,! (sec/m ) from Table 2.3-36.
- 3.32E-4 sec/m for batch release of containment purge.
(X/0)CV - The highest calculated annual average relative concentration of effluents released via the Containment Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-4.
- 9.24E-5 sec/m3 for continuous releases.
(X/q)"" - The short term relative concentration of effluents released via 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.
- The highest calculated annual average relative (X/0)CP concentration of effluents released via the condensate Polishing Building Vent for any area at or beyond3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-10.
3
- 7.35E-5 sec/m for continuous releases.
,y i
) (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) " - 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.
3
- 9.24E-5 sec/m for continuous releases.
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.
Sg - From equation [2.1(2)-1].
ry 2-16 ISSUE 3
BU-1 and 2 ODCM ,
I i
2.1.2.1.3 BV-2 Maximum Acceptable Release Rate (Skin Exposure) I O was also determined based upon the skin exposure limit by:
t 3000 [2.1(2)-3) l 0* * (X/0) E (Lg + 1.1Mg ) Sg i
l where Lg - The skin dose factor due to beta emissions from noble gas radionuclide "i"(mrem / year /uCi/m3 ) from Table 2.2-11.
Mg - The air dose factor due to gamma 3emissions 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 ) for each noble gas 4
radionuclide in the gaseous effluent was determinei by:
Og=Sg O t
[2.1(2)-4]
(NOTE: Use the lover of the 0 values obtained in t
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 ) for each individual noblegasradionuclideinthegaseouseffluenthasdeterminedby:
C g, 2.12E-3 0 1 [2.1(2)-5]
F vhere:
F = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 2.1.2.1.
3 2.12E Unit conversion factor (60 sec/ min x 3.53E-5 ft /cc).
ISSUE 3
'O 2-17
BV-1 and 2 ODCM i
2.1.2.1.6 BV-2 Monitor Count Rate ,
The calculated monitor count rate (nepm) above background attributed ;
[
-. to the noble gas radionuclide (C.R.) vas determined by:
[2.1(2)-6)]
C.R. = E Cg Eg i ,
where:
'* i E g - The detection efficiency of the monitor for noble gas-radionuclide "i" (cpm /uCi/ce) from Table 2.1-2b. ,
2.1.2.1.7 BV-2 Monitor Setpoints The monitor alarm setpoints above background were determined as follovs:
- a. The monitor HIGH Alarm Setpoint above background (uCi/cc) was. i determined by:
HSP = 0.30 C.R.
[2.1(2)-7] ,
E g ,y,
- b. The monitor ALERT Alarm Setpoint above background (uCi/cc) vas ,
determined by:
ASP -.FR x C.R.
[2.1(2)-8] ]
/G .E i ave where FR = Fraction of limiting dose rate for the respective radiation monitor (from Section 2.1.2).
E i ave = The C.R. of equation [2.1(2)-6] divided by the sum'of
-the Cg for the respective mix.
l O
2-18 ISSUE 3
Bif-1 and 2 ODCM )
l l
1 2.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release (Ground i Releases)
When the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method 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:
- 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(2)-17]
f " (X/q) IK gC g i
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 3
- (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 setpoint rules of Section 2.1.2. 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 i necessary margin below the site dose rate limit. I 1
T - Maximum value for T is 16 based on the limiting I restriction in ODCM Appendix C CONTROL 3.11.2.1.a where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes; T = 960/60 = 16). See Reference 2.2.4.
I l
2-19 ISSUE 3 i I
BV-1 and 2 ODCM (X/q)yy - The highest calculated short term relative m
concentration of effluents released via the Ventilation Vent for any area at or beyond3the unrestricted area (V) boundary for all sectors (sec/m ) from Table 2.3-36.
- 3.32E-4 sec/m (X/q)cv - The highest calculated short term relative concentration of ef fluents released via the Cor.tainment Vent for any area at or beyond 3the unrestricted area boundary for all sectors (sec/m ) from Table 2.3-37.
= 3.08E-4 sec/m 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.
l Cg - The undiluted radioactivity concentration of noble gas l radionuclide "i" in the gaseous source (uci/cc) as determined by analysis of the gas to be released,
- b. The flow rate (f) is also determined based upon the skin exposure limit as follows: ,
6.36 S T [2.1(2)-18] l f " (X/q) I (Lg + 1.1M 3) Cg i
n
(_,) where:
6.36 - 3000 mrem /yr x 2.12E-3 j 3000 mrem /yr - dose rate limit, skin exposure 2.12E-3 - unit conversion factor 3 i
- (60 sec/ min x 3.53E-5 ft /ce) f Lg
- The nobleskin dose factor"i"due gas radionuclide to/beta (mrem emissions year /uci/m from3) rom Table 2.2-11.
1 Hg = The air dose factor due to gamma emissions 3'" I noble gas radionuclide "i" (mrad / year /uCi/m ) 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 and based on the skin exposure limit (Section 2.1.2.2.1.a) The actual purge flow rate (cfm) must be (Section 2.1.2.2.1.b).
maintained at or below this calculated (f) value or the discharge cannot be made from the vent.
(3
,,Y 2-20 ISSUE 3
BV-1 and 2 ODCM 2.1.2.2.2 BV-2 Monitor Satpoints The follows:monitor alarm setpoints above background are determined as a.
The calculated monitor HIGH Alarm Setpoint above background (net uCi/cc) bys attributed to the noble gas radionuclides is determined fIC gE g HSP = [2.1(2)-19]
g F i ave where:
f
- The maximum acceptable containment purge flow rate (cfm) determined in Section 2.1.2.2.1.
F'
= The maximum the point actual or design effluent flow rate (cfm) at of release.
- 53,700 cfm (BV-2 Ventilation Vent -- design)
- 59,000 cfm (BV-2 Containment Vent -- design)
Cg -
The undiluted radicactivity concentration 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 monitor for noble gas radionuclide "i" (cpm /uci/cc) from Table 2.1-2b.
E i ave - The C.R. of equation [2.1(2)-6] divided by the sum of the Cg 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.
function of i "V*the monitor setpoint to properly control doseThis do rate.
from the However, the monitor indicated uCi/cc value may differ 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]
O 2-21 ISSUE 3
BV-1 end 2 ODCM 2.1.3 BV-1/2 Monitor Alarm Setpoint Determination
/ See Section 2.1.1 for a description of Monitor Alarm Setpoint
(]/ Determination. ,
1 2.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix For Process l Vent Releases (Elevated Releases) l The calculated monitor count rate above background (C.R.), in nepm, the l monitor HIGH-HIGH alarm setpoint above background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each operational condition are as follows: j BV-2 AND ALARM SETPOINTS FOR ELEVATED RELEASES 1
l cpm ABOVE 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 I (A)RM-GV-109(5) 2.20E7 6.61E6 2.20E6 1
- 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 l l
I
- Batch Release Of BV-2 Decay (P)RM-GV-108B 2.11E5 6.33E4 2.11E4 f'T (A)RM-GV-109(5) 7.75E6 2.32E6 7.75E5 V Tanks
- 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 Process Vent.
O V
2-22 ISSUE 3
BV-1 and 2 ODCH 2.1.3.1.1 BV-1/2 Hix Radionuclides i
The " mix" (noble gas radionuclides and composition) of the gaseous !
effluent was determined as follows: j
- a. The gaseous source terms that are representative of the " mix" of l the gaseous effluent were evaluated. Gaseous source terms are I the radioactivity of the noble gas radionuclides in the effluent. j The gaseous source terms can be obtained from Tables 2.1-la. and 2.1-1b.
- b. The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (S for each individual noblegasradionuclideinthegaseouseffludn)twascalculatedby:
A S i [2.1-9]
3,EA g 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 2.1.1b.
2.1.3.1.2 BV-1/2 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 ) tbased upon the whole body exposure limit was determined by:
O 500 [2.1.10]
tEvs 3 g i
where:
Vg - The cont t for noble gas radionuclide "i" accounting for the gamn 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)
Og was also determined based upon the skin exposure limit as follows:
0 3000 [2.1-11]
" E [L g(X/0)py + 1.1Bg]Sg ISSUE 3 9
2-23
_ _ _ . ~ _ . _ _ _ _ . . _ _
!! BV-1 and 2 ODCH
- where:
Lg = The skin dose factor due to beta emissions 3 I' "'
noble gas radionuclide "i"(mrem / year /uci/m ) from O;
l-Table 2.2-11.
(X/0)PV = The highest calculated annual average' relative concentration of. effluents releases via the Process Vent for any area'at or beyond 3the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-6.
I 2.31E-6 sec/m (X/q)PV =released The shortviaterm relative concentration the Process of effluents Vent for any area at or beyond 3 the. unrestricted-area boundary for all sectors (sec/m ) from' Table 2.3-38.
3
= 1.07E-5'sec/m .
Bg = The' constant for long term releases (greater than 500 hrs / 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 l gas for.each individual radionuclide-"i" in' the gaseous effluent (0 O noblegasradionuclideinthegaseouseffluentda)sdeterminedby:
O'=S g g O [2.1-12) t (NOTE: Use the lover 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 individual noblegasradionuclideinthegaseouseffluenthasdeterminedby:
C 2.12E-3 0 1 [2.1-13]
i= ,
where:
3 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-5 ft fee),
F = The maximum acceptable effluent flow rate at the point of release'(cfm).
= 1450 cfm (BV-1/2 Process Vent) 2-24 ISSUE 3 l
BV-1 and 2 ODCH 2.1.3.1.6 BV-1/2 Monitor Count Rate The calculated monitor _ count rate (nepm) above background attributed to the roble gas radionuclide (C.R.) was determined by:
C.R. - I Cg E g [2.1-14) i vhere:
Eg - The detection efficiency of the monitor for noble gas radionuclide "i" (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 were 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 (nepm) was determined by:
HSP - 0.10 C.R. [2.1-16]
O O
2-25 ISSUE 3 1
1
'BV-1 and 2 ODCM BV-l'/2 Setpoint Determination Based On Analysis Prior To Release For .I
'2.1.3.2 Process Vent Releases (Elevated Releases) ;
.}
d The following calculation-method applies to gaseous releases via the i BV-1/2 Process Vent when the " calculated mix" does not provide adequate ,
operational flexibility. This-method is used to' determine the setpoint l for the maximt.m acceptable discharge flow rate and the associated HIGH- j HIGH Alarm Setpoint based on this . flow rate for the BV-1/2 Gaseous !
i Waste 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' l 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 l Determine the maximum acceptable discharge flow rate for the release.
from the Process Vent for the analyzed mix. .l a .- The maximum acceptable gaseous discharge' flow rate (f) from the ~
Process Vent-(cfm) based. upon the. whole body exposure limit is I determined by: j i
hd f " 1.06 Iv cSi i
[2.1-21) i 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 3
. (60 sec/ min x 3.53E-5 ft fcc)
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 necessary margin below the site dose rate limit.
Vg = The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated plume (mrem / year /uCi/sec) from Table 2.2-12.
Cg = 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 limit, (f) is calculated by:
6.36 5 (2.1-22]
- I [Lg (X/Q)py + 1.1B gJ 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 3
- (60 sec/ min x 3.53E-5 ft /cc)
Lg - The skin dose factor due to beta emissions f noble gas radionuclide "i" (mrem / year /uCi/m 3'"
) 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 3 (X/q)Pv - 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 Bg - The constant for long-term releases (greater than 500 hrs / year) for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrad / year /uCi/see) from Table 2.2-12.
- c. Select the smaller of the calculated f values based nr. the whole body exposure limit (Section 2.1.3.2.1.a) ana 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 follows:
- a. The calculated monitor HIGH-HIGH Alarm Setpoint above background (nepm) attributed to the noble gas radionuclides is determined by:
fIC gE g [2.1-23]
HHSP -
I F l 2-27 ISSUE 3
BV-1 and 2 ODCM vhere:
T f = The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1.3.2.1.
F' = The maximum actual or design effluent ficw rate (cfm) at the point of release.
- 1450 cfm (BV-1/2 Process Vent -- design)
C = The undiluted radioactivity of noble gas radionuclide "i" in
- the gasaous source (uCi/cc) as determined by analysis of the gas to e 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]
O O
2-28 ISSUE 3
BV-1 and 2 ODCM TABLE 2.1-1s BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)**
O TURBINE CONTAINMENT VENTILATION BUILDING VENT VENT VENT PROCESS 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 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 Kr-85m 1.5E-01 1.9E+00 1.7E-04 1.2E+00 3.9E-03 7.3E-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 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 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 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 Ar-41 2.5E+01 0.0 0.0 0.0 0.0 0.0 lh 4
- Containment can be purged via Ventilation Vent, Containment Vent, or Process Vunt
- Reference (2.1.2)
- Reference (2.1.8) 2-29 ISSUE 3
BV-1 and 2 ODCM TABLE 2.1-lb BV-2 RADIONUCLIDE MIX FOR G.ASEGUS EFFLUENTS (Ci/yr)**
=( -
TURBINE VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS VENT Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE PUMPS SYSTEM !
NUCLIDE ' BUILDING VENTILATION VENTILATION AIR EJECTOR. '
Short Term Long Term- Long Term Long Term Long Term Short Term 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 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 l
.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 !
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 l
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
[)
\~s/
Xe-138 Ar-41 0.0 2.5E+01 1.1E+00 0.0 9.7E-05 0.0 6.6E-01 0.0 1.2E-04 0.0 0.0 0.0 i
- Containment can be purged via Ventilation Vent, Containment Vent, or Process Vent
- ** Reference (2.2.3) l
-0s *** Reference (2.2.5) 2-30 ISSUE 3 l
BV-1 and 2 ODCM TABLE 2.1-2a BV-1 MONITOR DETECTOR EFFICIENCIES (cpm /uCi/cc, CORRECTED)* l VENTILATION PROCESS CONTAINMENT Ol NUCLIDE VENT VENT VENT PRIMARY ALTERNATE PRIMARY ALTERNATE PRIMARY ALTERNATE MONITOR MONITOR MONITOR MONITOR MONITOR MONITOR RM-VS-101B RM-VS-109 RM-GV-108B RM-GV-109 RM-VS-107B RM-VS-110 Channel 5 Channel 5 Channel 5 Kr-83m -- -- -- -- -- --
Kr-85m 9.80 E7 2.39 E7 9.00 E7 2.43 E7 5.16 E7 2.57 E7 Kr-85 3.88 ES 2.47 E7 3.56 ES 2.51 E7 5.04 E7 2.67 E7 Kr-87 7.38 E7 2.95 E7 6.78 E7 3.00 E7 9.60 E7 3.19 E7 Kr-88 1.14 E8 2.11 E7 1.05 E8 2.14 E7 5.16 E7 2.28 E7 Kr-89 1.39 E8 2.93 E7 1.28 E8 2.98 E7 9.59 E7' 3.16 E7 Kr-90 1.34 E8 3.05 E7 1.23 E8 3.10 E7 9.87 E7 3.29 E7 Xe-131m 2.25 E6 1.56 E7 2.07 E6 1.59 E7 2.94 E7 1.68 E7 Xe-133m 1.26 E7 1.94 E7 1.16 E7 1.97 E7 4.17 E7 2.09 E7 Xe-133 1.01 E7 1.24 E7 9.24 E6 1.26 E7 2.20 E7 1.33 E7 Xe-135m 7.15 E7 5.70 E6 6.58 E7 5.80 E6 1.51 E7 6.15 E6 Xe-135 1.12 E8 2.91 E7 1.03 E8 2.96 E7 6.42 E7 3.14 E7 Xe-137 3.16 E7 2.96 E7 2.91 E7 3.01 E7 1.05 E8 3.19 E7 Xe-138 1.15 E8 2.66 E7 1.06 E8 2.70 E7 7.35 E7 2.87 E7 Ar-41 7.17 E7 3.00 E7 6.59 E7 3.05 E7 7.19 E7 3.23 E7 0
- 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.
O 2-31 ISSUE 3
- ~ . _ . .. - . . - - . - - .. - - . . _ _
BV-1 and 2 ODCM TABLE 2.1-2b r BV-2 MONITOR DETECTOR EFFICIENCIES '
O (cpm /uCi/cc)* ,
jd VASTE GAS CONDENSATE STORAGE DECON POLISHING VENTILATION CONTAINMENT VAULT BUILDING BUILDING VENT VENT VENT ~ VENT l NUCLIDE VENT 2HVS-RQ101B 2HVS-R0109B 2RM0-R0303B 2RM0-R0301B 2HVL-R01128 i
l Kr-83m -- --
3.20E7 5.83E7 3.20E7 3.20E7 3.20E7.
Kr-85m l 7.19E7 3.60E7 3.60E7 3.60E7 Kr-85 3.60E7 3.73E7 i
Kr-87 3.73E7 8.85E7 3.73E7 3.73E7 ,
l 3.05E7 3.05E7 .j l -Kr-88 3.05E7 6.80E7 3.05E7 8.73E7 3.72E7 3.72E7 3.72E7 Kr-89 3.72E7 3.86E7 Kr-90 3.86E7 8.80E7 3.86E7 3.86E7 t
2.44E7 4.61E4 2.44E7 2.44E7 2.44E7 Xe-131m 2.86E7 6.06E4 2.86E7 2.86E7 2.86E7 Xe-133m
-2.94E7 1.80E7 1.80E7 1.80E7 Xe-133 1.80E7 7.22E6 -1.55E4 7.22E6 7.22E6 7.22E6
-Xe-135m 7.48E7 3.86E7 3.86E7 3.86E7
! . Xe-135 3.86E7 3.78E7
! Xe-137 3.78E7 9.07E7 3.78E7 3.78E7 7.74E7 3.52E7 3.52E7 3.52E7 Xe-138 3.52E7 3.79E7 7.90E7 3.79E7 3.79E7 3.79E7 Ar-41 lO l-l
~
I l
l i
i l
l
- Reference (2.2.1) 2-32 ISSUE 3
- l. _ ~
BV-1 and 2 ODCM REFERENCES BV-1 GASEOUS EFFLUENT MONITOR SETPOINTS 2.1.1 " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 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, 5/30/74"; 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-SFL-85-031 l l
2.1.5 Unit 1/ Unit 2 ODCM Gaseous Alarm Setpoint Determinations; DLCo l Calculation Package No. ERS-HHM-87-014 !
2.1.6 BVPS-1 and BVPS-2 ODCH T Factor Justification; DLCo Calculation Package No. ERS-ATL-87-026 2.1.7 Letter NDISHP:776, dated February 12, 1988, BVPS-1 ODCM Table 2.2-2, Appendix B 2.1.8 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster Calculation No. UR(B)-262 0
- REFERENCES BV-2 GASE0US EFFLUENT MONITOR SETPOINTS 2.2.1 Unit 2 DRMS Isotopic Efficiencies; DLCo Calculation Package No.
ERS-SFL-86-026 2.2.2 Unit 1/ Unit 2 ODCM Gaseous Alarm Setpoint Determinations; DLCo Calculation Package No. ERS-HHM-87-014 2.2.3 " Beaver Valley Power Station, Unit 2 FSAR"; Table 11.3-2 2.2.4 BVPS-1 and BVPS-2 ODCM T Factor Justification; DLCo Calculation Package No. ERS-ATL-87-026 l
l 2.2.5 Gaseous Releases From Containment Vacuum Pumps; Stone and Webster l Calculation No. UR(B)-262 0
2-33 ISSUE 3
BV-1 cnd 2 ODCH 2.2 Compliance Vith 10 CFR 20 Dose Rate Limits (ODCH Appendix C CONTROL 3.11.2.1)
) 2.2.1 Dose Rate Due To Noble Cases The dose rate in unrestricted areas resulting from noble gas effluents from the site is limited to 500 mrem /yr to the total body and 3,000 mrem /yr to the skin. Site gaseous effluents are the total of BV-1 and BV-2 specific ground releases and a shared elevated release, the BV-1/2 Process Vent. Based upon NUREG-0133 the following basic expressions are used to show compliance with ODCH Appendix C CONTROL 3.11.2.1.a.
I [V 0g3, + K (X/0)y g Ogy] < 500 mrem /yr [2.2-1]
i I [Lg(X/0), + 1.1B g] Oh> + I bi + 1*IMi](X/0)y Ogy f 3000 mrem /yr i
[2.2-2]
vhere:
Kg - The total body dose factor due to gamma emissions for each identified noble gas radionuclide "i", mrem / year /uci/m3 .
Lg - The skin dose factor due to beta emissions for each 3 identified noble gas radionuclide "i", mrem / year /uci/m .
Hg - The air dose factor due to gamma emissions for each p identified noble gas radionuclide "i", mrad / year /uC1/m3 .
Vg - The constant for each identified noble gas radionuclide "i" accounting.for the gamma radiation from the elevated finite plume, mram/ year /uci/sec.
Bg - The constant for long-term releases (greater than 500 hrs /
year) for each identified noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume, mrad / year /uCi/sec.
1.1 - The ratio of the tissue to air absorption coefficients over the energy range of the photon of interest, mrem / mrad.
O gs - The release rate of noble gas radionuclide "i" in gaseous effluents from free-standing stack, uCi/sec.
O gy - The release rate of noble gas radionuclide "i" in gaseous effluents from all vent releases, uCi/sec.
(f70)s - The highest calculated annual average relative concentration for any area at or beyond3 the unrestricted area boundary for elevated releases (sec/m ).
2-34 ISSUE 3 b
BV-1 cnd 2 ODCM (X76)y - The highest calculated annual average relative concentration for any area at or beyond the3unrestricted area boundary for ground level releases (sec/m ).
At the Beaver Valley site gaseous releases may occur from:
- 1. The Containment Vents atop the Containment Domes
- 2. The Ventilation Vents atop the Auxiliary Buildings I
- 3. The Process Vent atop the BV-1 Cooling Tover
- 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 Containment Purges and Contiguous Areas ventilation. The Turbine Building Vents Releases are ground level in nature and the source of these releases are the Turbine Building Ventilation. Release points 4, 5, 6, and 7 abom are not normally radioactive release points. The Process Vent releasu are elevated and the sources of these releases are the Main Condenser Air Ejectors and the Vaste Gas Decay Tanks and Containment Vacuum Pumps.
Noble gas releases may normally occur from release points 1 through 3 above. To show compliance with the site limits of ODCH Appendix C CONTROL 3.11.2.1.a, Expressions [2.2-1] 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:
IV0gg +IKg g [(X/0)cy O g + (X/0)yy O g + (X/0)gy O g + @ )cy i pv cvl vv1 tvl Og +( }"" I vv2 +I I tv 0g
- CP i cp2 b ev2 tv2 dv2 (576)yy O g ] $ 500 mrem /yr [2.2-3]
2-35 ISSUE 3 8 e
BV-1 and 2 ODCH For The Skin Dose Rate:
[y) Ib i )pv + 1.1Bg] Og pv +Ig [L g + 1.1H ) [(X76)cy O g g + @ ),y i evl ,
Og
+ (X/0)tv O i gyg
+
ev Ol ev2
- ( }"" I + (X/0)tv.0g
- y vv2 v2 (X/0)cp O g + (X/0)dv O l dv2 " I vv2 ep2 [2.2-4]
^
where:
Og = Release rate of radionoclide "i" from the BV-1/2 Process pv Vent, uCi/sec. <
i Og = Release rate of radionuclide "i" from the BV-1 Containment i cvl Vent, uCi/sec.
l Og - Release rate of radionuclide "i" from the BV-2 Containment j cv2 Vent, uCi/sec. !
l Og - Release rate of radionuclide "i" from the BV-1 Ventilation I vvl Vent, uCi/sec. l I
Og - Release rate of radionuclide "i" from the BV-2 Ventilation vv2 Vent, uCi/sec.
Og - Release rate of radionuclide "i" from the BV-1 Turbine tv1 Building Vent, uCi/sec.
Og = 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.
Og = Release rate of radionuclide "i" from the BV-2 l dv2- Decontamination Building Vent, uCi/sec.
Og = Release ratt of radionuclide "i" from the BV-2 Vaste Gas j l
vv2 Storage Vault Vent, uC1/sec. ;
= Highest calculated annual average relative3concentration i (576)PV for releases from the Process Vent, sec/m l - Highest calculated annual average relative3 concentration for (E76)C# releases from the Containment Vent, sec/m l
- (576)yy = Highest calculated annual average relative3 concentration for releases from the Ventilation Vent, sec/m (E70)tv = Highest calculated annual average relative concentration for releases for the Turbine Building Vent, sec/m 3 n 2-36 ISSUE 3 U
f .
BV-1 and 2 ODCH (576)cp = Highest calculated annual average relative concentration for releases 3for the BV-2 Condensate Polishing Building Vent, sec/m (iT6)dy = Highest calculated annual average relative concentration3 for releases for the BV-2 Decontamination Building Vent, sec/m .
(576),y - Highest calculated annual average relative concentration3 for releases for the BV-2 Vaste Gas Storage Vault Vent, sec/m .
. Note that the release rate for a containment purge is based on an averaged release rate in uCi/sec for the entire purge (not to exceed 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 modes identify the various combinations of sources of radioactivity and their release points which are used to determine the controlling locations. They are presented in Table 2.2-1. For Modes 1, 2, and 3, the controlling location for implementation of ODCH Appendix C CONTROL 3.11.2.1.a is 0.35 miles NV. Inserting the appropriate X/0's from Tables 2.2-4 through 2.2-10 for this location, Expressions [2.2-3] and
[2.2-4] become:
For The Total Body Dose Rate:
IV0 gg +EKg [9.24E-5 Og + 1.03E-4 O g + 7.35E-5 O g + 9.24E-5 i pv i evi vv1 tv1 Og + . 5E-5 O g + 9.24E-5 O g + 9.24E-5 ti +
ev2 vv2 7.35E-5 0 3 ] 3 500 mrem /yr [2.2-5]
For The Skin Oose Rate:
I [7.0E-10 Lg + 1.1B g] Og + E [L i + 1.1M g] [9.24E-5 Og + 1.03E-4 i pv i cv1 Og + 7.35E-5 O g + 9.24E-5 0 + 1.03E-4 0 + 7.35E-5 O g +
9.24E-5 O g + 9.24E-5 O g + 7.35E-5 O g ] 3 3000 mrem /yr For the release Mode 4, the controlling location is 0.75 miles N.
Inserting the appropriate X/0's from Tables 2.2-4 through 2.2-10 for this location, Expressions [2.2-3 and 2.2-4] become: l I
i 2-37 ISSUE 3 0
9
. . - - ~ ~ n.~ - . a. . - . - . - - . _ ~ - . ~ . - - ... .. ~ . - - . _ - .. . - . . . . ..
BV-1 and.2 ODCM For The Total Body Dose Rate:
[ . IV0 i
gg pv.
+EKg [3.95E-6 Og i cv1
+ 4.99E-6 O g vv1
+ 4.26E-6 O g tv1
+ 3.95E-6 Og + 4.99E-6 O'g + 4.26E-6 O g -+ 3.95E-6 O g + 3.95E-6 O g + ,
cv2 vv2 tv2 dv2 vv2 i
4.26E-6 O g ep2 ~
l For The Skin Dose Rates I [2.31E-6 Lg + 1.1B g] Og + E [Lj + 1.1M g] [3.95E-6 Og + 4.99E-6 -[
i pv i evi Og -C 3.95E-6 O g + " I vv2 I tv2- *
I tv1 y ev2 3.95E-6 O g -+ 3.95E-6 O g + 4.26E-6 O g -]: 3 3000 mrem /yr ,
dv- vv cp [2.2-8] ;
i The. determination -of controlling location 'for implementationfof 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 r
- 3. Meteorology O The incorporation of these 3 parameters into Expressions [2.2-3] and- )
- h. [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 Vebster Engineering- l Corporation computer code GAS 1BB vhich is similar.to the NRC GALE code. .
Inputs were based on operating modes .of the respective plants. The code inputs utilized are presented in - Appendix B. The ' source, term is presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point.
~
The X/0 values utilized in the equations 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'ench 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 derivation is provided in Appendix A.
i 1 2-38 ISSUE 3
\
1
\. .
,g - ,--.:n , ,
. r -n, , . .
BV-1 and 2 ODCH For release modes 1, 2, and 3, dose calculations were 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.
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/0 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.
Values for K , L , and M, which vere used in the determination of the controllinghecehterlocakionandwhicharetobeusedin Expressions [2.2-5] through [2.2-8] to show compliance with ODCH 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 l vere multiplied by 1E6 to convert picoeuries~1 109, Revisionto microcuries~g ,for use in Table 2.2-11.
Values for V, and B gfor the finite plume model can be expressed as shown in Equation [2.2-9) and [2.2-10J. 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:
B"K IEI jk ygA u, Eg I
[2.2-9]
i r} j k 1 u) where:
I
- The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the and atmospheric meteorological condition stability class "k" of vind speed for a particular vind d(u$)irection 2-39 ISSUE 3
. _ _ . . . _ _ _ _ _ _ _ . . . .-_....__.~.._m...- ..._.._...-.__._.~._._,--..._.___.-m - . . _ _ _
'BV-1 and 2-0DCM '
~K = A numerical' constant representing unit conversions.
= g60 mead)(radians) (m3 )-(transformation)' 16 sectors
~
, (sec)(Mev)(Ci) 2n radians j 1E-6 Ci 3.15E7 sec l uCi 'yr -
= 2 1E4 mrad (m )'(transformation)/yr(Mev)(uC1).
l rg _The distance from the release point to the receptor location' ,
I l meters. i l
=u 3
= The mean_vind speed assigned to the "j" th vind speed class, f
. meters /sec. f
] '
fdk'= T1.E joint frequency of occurrence of the "j" th vind speed class
_and kth stability class (dimensionless).
.Agg - The number'of photons of. energy corresponding to the "1" th p '
energy. group emitted per transformation'of the "i"'th radionuclide, number / transformation.
l-Eg = The energy assigned to the."1"_th energy group, Mev..
l u, - The energy,gabsorption _ coefficient-in air.-for photon energy H y , meters .
~
The V factor _is computed with conversion from-air dose to tissue depth dose,ithus: '
K E~E E fjk Ali "a Ey J , -u T.Td [2.2-10].
Vg_= 1.1 jk1 .u j where:
1 i
uT = The tissue energy 2absorptio'n coefficient for photons.
of: energy Et , em /ge.
T-d - The tissue density 2 thickness'taken to represent the total body
[ dose (5ga/cm ). l L 1.1 = The ratio of the tissue to air absorption coefficients over the-energy range of_ photons of interest; mrem / mrad.
i l-l l
l l
2-40 ISSUE 3 i 0
'\ :
.z
BV-1 and 2 ODCH 2.2.2 Dosa R7t2 Du; To R<diciodinas And Pnrticulates 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 days released in gaseous effluents from the site shall be limited to 1,500 mrem /yr to any organ. Based upon NUREG-0133, the following basic expression is used to show compliance with ODCM Appendix C CONTROL 3.11.2.1.b:
IPgT [(X/0), O ,g + (X/0)y Ogy] $ 1,500 mrem /yr [2.2-11]
i i
where:
P g - Dose parameter for any organ T for each identified 3
radionuclide "i", mrem /yr per uCi/n 0 - The release rete of radionuclide "i", in gaseous effluents 1s from elevated releases, uCi/sec.
O gy - The release rate of radionuclide "i", in gaseous effluents from grouno level releases, uCi/sec.
(E76)s - The highest calculated annual average relative concentration at 3the unrestricted area boundary for elevated releases, sec/m (5'/6)" - The highest calculated annual average relative concentration at the unrestricted 3
area boundary for ground level releases, sec/m NOTE: The dispersion parameters specified in Section 2.2.2 are limited to the site boundary as defined above.
Releases may occur from any of the site vents in the release modes listed in Table 2.2-1. To show compliance with ODCM Appendix C CONTROL 3.11.2.1.b, Expression {2.2-11] is nov expressed in terms of the actual -
release points for the site.
IP h [(X/0)py O g + (X/0)cy O g + (X/0)yy O g +
i pv cv1 vv1 + (X/0)tv o g tv1 (X/0)cy O g "" tv S tv2 '
Cp i dv ev2 vv2 cp2 Og + (276)yy O g ] 3 1500 mrem /yr [2.2-12]
vhere:
(576)pv - Highest calculated annual average relative 3concentration for releases from the Process Vent, sec/m (576)cy = Highest calculated annual average relative3 c neentration for releases from the Containment Vents, sec/m 2-41 ISSUE 3 0
h
BV-1 and 2 ODCM (276),V = Highest calculated annual average relative3 concentration for i releases from the Ventilation Vents, sec/m l l
A _
i (V )
(X/0)tv - Highest calculated annual average relative concentration3 f r releases for the Turbine Building Vents, sec/m (576)cp = Highest calculated annual average' relative concentration for releases 3for the BV-2 Condensate Polishing Building ,
Vent, sec/m l
( FQ)dv = Highest calculated annual average relative concentration for releases 3f r the BV-2 Decontamination Building:
Vent, sec/m (X/6)" = Highest calculated annual average relative concentration l for release,from the BV-2 Vaste Gas Storage Vault Vent, sec/m' 0 = Long-term releau rate of radionuclide "i" from the BV-1/2-3 pv Process Vent, uCi/sec. ;
Og - Long-term release rate of radionuclide "i" from the BV-l' cvl Containment Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-2 cv2 Containment Vent, uCi/sec.
Og - Long-term release rate of radionuclide "i" from the BV-1 vv1 Ventilation Vent, uCi/sec.
/
Og - Long-term release rate of radionuclide "i" from the BV-2 vv2 Ventilation Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-1 tvl Turbine Building Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-2 tv2 Turbine Building Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-2 cp2 Condensate Polishing Building Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-2 vv2 Vaste Gas Storage Vault Vent, uCi/sec.
All other terms are the same as those defined previously.
2-42 ISSUE 3
(\
4
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 releases 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, were calculated using methodology given in NUREG-0133. For thePi r,hild c age group, the following equation was used for all nuclides. The PM, values are presented in Table 2.2-13.
Pg - 3.7E9 DFAh [2.2-13]
vhere:
3 3.7E9 - Breathing rate of child (3,700 m /yr) x unit conversion factor (lE6 pCi/uCi).
DFA gT - The organ inhalation dose factor for a child from Table 6 of 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 [2.2-12] becomes:
EPH [7.00E-10 og + 9.24E-5 O g > 1.03E-4 O g + 7.35E-5 O g +
i pv cvl vv1 tv1 9.24E-5 0 + 1.03E-4 O g + 7.35E-5 O g + 7.35E-5 O g + 9.24E-5 0 + 9.24E-5 O g $ 1500 mrem /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.
_m In the determination of the controlling site boundary for each release mode, the highest 2 site boundary X/0 values for each release point vere utilized in conjunction with the radionuclide mix and the release rate for each release point to determine the controlling location.
The P h values are presented in Table 2.2-13.
2-43 ISSUE 3 0
i BV-1 and 2 ODCM
'The X/Q values in Expression. [2.2-14] vere obtained.from Tables 2.2-4 through 2.2-10.
4 A description of the derivation of the X/0 values is provided in
- Appendix'A.
J 4
.h a
1 i
a I
t I
4 I-e s
. 2-44 ISSUE 3 1
- .6 e
9a G
---n , ----m,,,,,nn-.-.,, ,-,-,,s..---,, - - , , -,,.n. -. , - . , - , . , . - > . . , , . , , . ----.--.~-,.-n- - -- - . . + - . - ,. - ----
BV-1 and 2 ODCM TABLE 2.2-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT MODE 1 MODE 2 MODE 3 MODE 4 0
2 BVPS BVPS-2 Main Cond. Air Same As 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 Vent (evi) Collection Mode 1 Mode 1 And Mode 1 Exhaust Contajnment Purge BVPS-1 Turbine Bldg.I Turbine Bldg. Same As Same As Same As Vent (tv1) Exhaust
- Mode 1* Mode 1* Mode 1*
BVPS-2 Ventilation I Contiguous Containment Same As Same As Vent (vv2) Areas Purgc Mode 1 Mode 1 1
BVPS-2 Containment Aux. Bldg. Same As Same As Same As Vent (ev2) Ventilation Mode 1 Mode 1 And Mode 1 Contajnment Purge BVPS-2 Turbine Bldg. Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust
- Mode 1* Mode 1* Mode 1*
l BVPS-2 Condensate * * *
- Polishing Bldg. Vent (ep2)
BVPS-2 Decontamination 1 * * *
- Bldg. Vent (dv2) 1 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 time of the annual report.
.fcontinuousgroundlevelr_eteorologyisapplicable 3
Continuous elevated meteorology is applicable Mode established by purge from one unit, all other release points remain same as Mode 1 2-45 ISSUE 3
. O f
BV-1 raoi 2 ODCM TABLE 2.2-2a .
BV-1 RADIONUCLIDE MIX FOR CASE 0US EFFLUENTS
.( Ci/yr)**
l O-
. TURBINE CONTAINMENT VENTILATION BUILDING VENT VENT VENT PROCESS VENT Long Term And
. AUXILIARY TURBINE MAIN CONTAINHENT GASEOUS CONTAINMENT -BUILDING BUILDING CONDENSER / VACUUM VASTE' NUCLIDE.. BUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS- . SYSTEM 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 Kr-85m- 1.5E-01' 1.9E+00 1.7E-04 1.2E+00 3.9E-03 1.2E-02 Kr-35. 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-8?- 5.4E-02. 1.3E+00 '1.1E-04 8.2E-01 7.8E-04s 0.0-Kr-88 0.4E-01: 3.8E+00 3.5E-04 2.4E+00 5.0E-03 0.0 Kr-89 4.7E-04' 1.2E 1.1E 7.7E-02 3.1E 0.0 Xe-131m L7.4E '1.3E-01 1.2E-05 8.0E 1.3E-02 8.3E-01 Xe-133m 8.9E-01 8.9E-01 8.1E .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 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 2.5E 0.0 0- I-133-I-134-2.0E-04 0.0' 6.7E-02 O.0 8.7E-04 0.0 .
- 0.0 ~
3.0E-02 0.0 8.4E-05 4.7E-07 0.0 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 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 0.0 1.6E-06 0.0 Sr-89' 1.7E 1.3E-03 0.0 0.0- 3.7E-07 0.0
'v 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.BE-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 7.0E+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 Vent
- Reference 2.1.2
'***See Section 2.1.1.1 2-46 ISSUE 3 m,
9 .
BV-1 and 2 ODCM I TABLE 2.2-2b BV-2 RADIONUCLIDE HIX FOR GASE0US EFFLUENTS (Ci/yr)** '
TURBINE VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS 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 Long Term Long Term Short Term Kr-83m 4.0E-05 4.2E-01 3.9E-05 2.7E-01 3.7E-04 Kr-85m 0.0 1.4E-02 1.9E+00 1.7E-04 1.2E+00 3.9E-03 Kr-85 1.2E-02 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 Kr-87 2.3E+02 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 Xe-131m 0.0 7.2E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 Xe-133m 8.3E-01 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 I-131 2.7E-05 4.6E-03 6.5E-04 2.1E-02 4.7E-04 I-132 0.0 0.0 0.0 0.0 0.0 2.5E-06 0.0 I-133 2.6E-06 6.7E-03 8.7E-04 3.0E-02 8.4E-05 I-134 0.0 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 Co-58 7.5E-02 0.0 6.0E-04 0.0 0.0 1.6E-05 0.0 Co-60 3.4E-02 2.7E-04 0.0 0.0 Hn-54 7.4E-06 0.0 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 Fe-59 7.5E-03 0.0 6.0E-05 0.0 0.0 1.6E-06 0.0 Sr-89 1.7E-03 1.3E-05 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-04 2.0E-06 0.0 0.0 6.6E-08 Cs-134 2.2E-02 0.0 1.8E-04 0.0 0.0 4.9E-06 0.0 Cs-137 3.8E-02 3.0E-04 0.0 0.0 C-14 8.4E-06 0.0 1.0E+00 0.0 0.0 0.0 0.0 7.0E+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 Vent
- Reference 2.2.3
- See Section 2.1.2.1 2-47 ISSUE 3 I
O .
O O BV-1 and 2 ODCM TABLE 2.2-3 DISTANCES OF LIMITING MAXIMUM IPOIVIDUAL RECEP1 ORS TO RELEASE POINTS EOR AttiUAL X/Q VAWES*
(meters)
VEGETABLE MEAT DG et- SITE BOLEOMtY GARDEN MILK CON MILK GQAT ANIMAL RESIDENT WIFO SECTOR GROLRO ELEV. GROLDID ELEV. GROWO ELEV. GROT 2iD ELEV. GROL2iD EIEV. GROUND ELEV.
(1) (2)
N 670 579 413 2,623 2,423 - - 4,651 4,418 4,152 3,919 2,527 2,295 535 792. 632 2,704
- 2,461 6,276 6,033 2,848 2,605 2,639 2,461 reiE - -
NE 490 442 327 724 901 7,741 7,526 20,760 20,545 7,741 7,526' 708 790 490 -448 394 1,674 1,658 - - 6,824 6,671 - -
708 1,562 ENE E 545 546 551 1,979 1,922 7,065 6,998 4,265 -4,200 4,265 4,200- 756 1,922-575 607 672 1,577 1,619 - - 2,865 2,899 1,577 1,619 1,577 1,650 ESE 575 701 815 1,835 1,961 5,729 5,848 5,729 5,848 3,299 3,420 1,835 1,961 SE 655 762 912 1,738- 1,933 5,053 5,244 9,977 10,166 1,770 1,964 1,432 1,628 SSE s 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 1,383 645 558 420 1,464 1,285 - - 15,450 15,262 3,959 3,774- 1,143 1,253 NNW' tore:
- Distances for ground releases are measured frosa the centerpoint between the BV-1.and BV-2 Containment Buildings. Distances for elevated release are measured frosa the BV-1 Cooling.1bwer. 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 DV-1 AND 2 CONTAINPENT VENIS AtNUAL AVERAGE, GROUND LEVE.L, X/Q VALUES EUR CINFINUQUS GROUND LEVEL RELEASES, FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECIED CCNIROL IDCATIONS (IE-7 sec/m )
INDIVIDUAL RECEPIORS DISTANCES 'ID THE CONTROL IOCATION, IN MILES DOWN-WIND SITE VEGE- MEAT SEC- BOLN- 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 DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 DAR1 GARDEN CON _ GOAT MAL 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 SSW 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 13.90 160.0 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 6.460 5.550 WNW 407.0 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 14.200 12.200 NN 924.0 194.00 -
8.660 40.50 200.00 1710.0 262.0 123.00 79.80 55.00 42.30 34.000 28.200 19.400 16.700 NNN 302.0 63.00 -
1.720 15.40 92.30 547.0 86.4 40.80 26.20 17.60 13.50 10.100 8.350 6.560 5.660 2-49 ISSUE 3 O O O
~
O ,
O O .
i BV-1 and 2 ODCM$
i
'IABLE 2.2-5 :
1 'i BV-1 Am 2 VENTIIATIG4 VENFS Al@luhL AVERAGE, GROUm LEVEL, XA) VALUES }
EUR CGfrIIEJOUS GRut2O LEVEL REIEhSES,~. EUR SPECIAL DIS 1RNCES &
- - (ID9FFIFIED IN ThBLE 2.2-3), Am SELECTED CCimt0L' LOCATIONS j (IE-7 secAn ) ~
IPOIVIDUAL RECEPIORS DISTRNCES 'IO ' HIE CGmtOL IOCATIN, IN MILES -
DG#i- j Wile SITE VEGE- . MEAT . .
.4.5-SEC- BOUN- 11BLE MILK MILK ANI-' RESI- . 0- 0.5- 1.0 -l'.5- 2.0- -2.5- 3.0- 3.5- 4.0 ' ;
TOR tmRY 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 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 i relE 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 i ENE 110.0 13.60 - ~ - -1.270 - 50.40 135.0 20.6 10.20 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 38.8d 116.0 17.7. 6.57 3.86' 2.61~ 1.90 1.34 1.070 0.383 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 .1.0'10 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 :
t S 32.8 13.65 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 r 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.C70 l 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.%0 2.230 1.900 i I -
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- ,
-l WNN 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 [
telW 345.0' 83.40 -
1.840 18.10 121.00 601.0 114.0" 52.80 32.20 21.00 15.80 11.60 9.460 7.360 6.310 i
2-50 ISSUE 3 :
. = _ - _ _ _ _ - _ _ _
BV-1 and 2 ODC14 TABLE 2.2-6 BV-1 AND 2 PROCESS VENT A!MIAL AVERAGE, ELEVATED RELEASE, X/Q VALUES EOR CONTINUOUS GROUND LEVEL RELEASES, FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CCNTROL IDCATICNS (IE-7 sec/h )
INDIVIDUAL iuM.t. nuts DISTANCES 'IO 'IEE CONTROL 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-
'IOR DARY GARDEN CCW GOAT MAL 4.5-DENCE 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 --
NNE 0.0280 6.690 - 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 NE 0.0110 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 ENE .074 1.610 0.0110 9.090 - 1.770 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 0.525 0.0135 0.3310 7.2800 6.02 4.75 3.22 2.620 2.030 1.710 1.100
, E ESE 0.0360 11.600 0.0420 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 SE 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 SSE 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 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 --
SSN 7.640 6.06 6.310 0.7960 8.5100 8.4900 4.98 3.37 2.47 1.380 1.110 0.774 0.655 SW 6.500 3.610 2.140 3.900 0.872 3.61
- 2.560 3.47 5.820 26.1000 9.1000 4.0300 3.11 2.11 1.56 1.030 0.834 0.80'.' a 684 WSW 0.126 4.350 1.420 - 3.900 36.1000 15.9000 4.9300 3.12 1.77 1.57 1.201 1.060 1.150 0.977 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 --
WNW 0.033 2.02 2.490 0.0147 8.7200 6.2300 3.68 2.50 1.84 0.741 1.120 0.851 0.795 NN 0.007 2.530 1.780 0.074 - 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 NNN 0.008 6.460 - 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 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 release X/Qs maximize.
2-51 ISSUE 3 e G #
O O O
~
t -
t
-BV-1 and 2 ODCM-
'[
'mBTE 2.2-7 i
BV-1 Ate 2 'IURBINE BUILDING VENIS AfGERL AVERAGE, GR0t2O TEVEL, X,/Q VALUES l
FOR CNTINJOUS GR0t2O LEVEL RELimSES,; PGt SPECIAL DIS'mNCES [
(IDENTIFIED IN 'MBLE 2.2-3), Ate SELECTED CGf!BOL IOCATIGIS ' t (IE-7 secAm ).
I!OIVIDUAL RECEPIORS . DIS'EANCES '10 'IHE CGf!BOL IOCATIN, IN MILES- ;
SEC- BOUN 'EhBLE 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 CON GQAT . MAL DENCE 0.5 1.0 1.5 2.0- 2.5 3.0 3.5 4.0 ~4.5 - 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 tele 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 i
l.
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 -l'.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 i 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.% 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 i 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 2.00i 1.620 m1.230 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 3.54l 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 8.0e '40 5.790
{ WNN 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 22.0& .500 12.900' 1
NN 735.0 216.00 -
9.100 43.90 272.00 1720.0 279.0 140.00 88.80 60.30 45.90 36.60 36 M 40.600 17.700-telw 247.0 .71.00 -
1.820'17.^0 99.40~ 557.0 924.0 45.90 28.90 19.20 14.60 10.80 8. boo' 6.950 5.980 1
2-52 ISSUE 3 i
i
--.___--_.._x - - - . - - - - _ , _ . - - _ _ - _ _ _ - - - _ - - _ _ . - - _ _ . . . _ - . _ _ _ _
__ _ - - _ _ _ _ _ _ _ _ _ - - - - - _ _ . _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ - - ____ _ _- - - -__.__-_ _ - r._w _, _a- _ _.,+r, x--
BV-1 and 2 ODCM TABLE 2.2-8 EOR INFORMATION ONLY - USED IN CALCULATIN OF BV-2 CONTRIBUTION 10 SITE DOSE RATE LIMITS BV-2 DEC0KIAMINATION BUILDING VENT ANNUAL AVERAGE, GROUND LEVEL, XM VALUES FOR CONTINUOUS GROUND LEVEL RELEASES, FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CONTROL IDCATIONS (IE-7 sec/m )
INDIVIDUAL RECEPTORS DISTANCES 'IO THE CONTROL IDCATIN, IN MILES DOW-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 GARDEN CCW 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 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 7.03 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 NNW 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 O O -
O --
1 O -
LO O BV-1 and'2 ODCM-s TABLE 2.2-9 .;
i EUR INEURMATION ONLY - USED IN CAILUIATION OF BV-2 00lf!RIBtFfICN *to SITE DOSE RA'!E LIMITS. [
, 2 BV-2 WASTE GAS STORAGE VAULT VENT AfeduhL AVERAGE, GROUlO LEVEL, XA) VALUES !
FOR 03ffINUOUS GROLEO LEVEL RELEASES,- EUR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), Als SELECTED CCNIROL IDCATICNS (IE-7 secAm )
ll IIOIVIDUAL RECEPIORS DISTANCES 'IO THE CCNFROL IDCATI(N, IN MILES DONN- ;
- 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- [
'!OR DARY GARDEN CON 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 tele 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 .2.37 3.910- 1.450 1.230 i ENE 85.80 12.50 -
1.240 - 42.20 '103.0 18.40 9.55- 5.70 4.14~ 3.04 2.340 .. 880 1.260- 1.060 i
. 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 30.50 5.16 '3.10 1.95 1.43 1.020 0.815 0.612 0.517 ,
5.89 _3.54 2.41 1.77 1.160 0.931 0.768 0.649 !
SE 27.80 6.70 0.994 0.994 2.74 6.70 65.9 12.00
, 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' O.803 0.665 0.563 i
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 l SSN 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 '
SN 22.30 13.90 -
9.050 12.30 13.90 160.0- 29.20l16.10- 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 :
'I 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 ~'
WNN 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 NN 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 ,
reiw 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 l t
i l '
- 2-54 ISSUE 3 i r
I I
~ _ _ - . _ _ . . - _ _ _ _ _ - _ _ - _ _ _ - - _ _ _ _ - _ _ _ _ - _ _ - _ _ . _ - _ _ _ - - . _ . _-__.. . - . . . ~ . . - - . . - ~ . _ _ . . _ _ __J
BV-1 and 2 ODCM TABLE 2.2-10 EUR INFORMATION ONLY - USED IN CALCUIATIN OF BV-2 CONTRIBUTICN 'IO SITE DOSE RATE LIMITS BV-2 CNDENSATE POLISHING BUILDING VENT ANNUAL AVERAGE, GROUND LEVEL, XA) VALUES EDR CONTINUOUS GROUND LEVEL RELEASES, EUR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECIED CONTROL LOCATICNS (IE-7 sec/a )
INDIVIDUAL RECEPIORS DISTANCES 'IO THE ONTROL' IOCATION, IN MILES DOWN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MIII ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-TOR DARY GARDEN CON GOAT MAL DENCE 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 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 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 12.900 NW 735.0 216.00 -
9.100 43.90 222.00 1720.0 279.0 140.00 88.80 60.30 45.90 36.60 30.100 20.600 17.700 NNW 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 O
BV-1 and 2 ODCM TABLE 2.2-11 LUSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- O V b i i i i TOTAL BODY GAMMA AIR BETA AIR NUCLIDE DOSE FACTOR SKIN DOSE FACTOR DOSE FACTOR DOSE FACTOR mrem /yr mrem /yr mrad /yr mead /yr
. Per Per Per Per uCi/m 3 uCi/m 3 uCi/m 3 uCi/m 3 Kr-83m 7.56E-02 --
1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.rjo+u3 Xe-131m 9.15E+01 4.76E+02 1.56E+02 7.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3. 06 E+ 0.' 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.3',; 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.
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 p.
, *The listed dose factors are for radionuclides that may be detected in gaseous effluents.
2-56 ISSUE 3 O e
BV-1 and 2 ODCM TABLE 2.2-12 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES BEAVER VALLEY SITE
- y i
1 B
i
,2 y i
3 B
i 3
9 NOBLE GAS TOTAI BODY GAMMA AIR TOTAL BODY GAMMA AIR NUCLIDE DOSE RATE DOSE RATE DOSE RATE DOSE RATE
, mrem /yr mrad /yr mrem /yr mrad /yr Per Per Per Per uCi/see uCi/see uCi/sec uCi/sec 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 1.54E-4 2.76E-4 Xe-135m 2.41E-4 3.66E-4 6.21E-4 9.50E-4 Xe-135 1.41E-4 2.12E-4 6.96E-4 1.05E-3 Xe-137 6.00E-5 9.05E-5 9.66E-5 1.46E-4 Xe-138 8.11E-4 1.22E-3 2.22E-3 3.34E-3 Ar-41 1.02E-3 1.53E-3 2.68E-3 4.02E-3 0
- The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
I Vg and B gvalues used to implement Modes 1, 2, and 3 of Section 2.2.1 (10CFR20) 2 Bf values used to implement Modes 1, 2, 3, and 4 of Section 2.3.1 (10CFR50) 3 V and B values to implement Mode 4 of Section 2.2.1 (10CFR20) and to imhlementmonitorsetpointdeterminationsofSection2.1.2and2.1.4 2-57 ISSUE 3 9
m h
- -- - - ~_- -- . .- . _- .- - .. .-.
i i
1
- BV-1and2ODCM 2
l Table 2.2-13
. 4 P VALUISFORACHILDFORTHEBlaittVALLIY$17I If (ares /yrpernC1/cuseter)
I i
hclide Bone Liver T. Body thyroid Ildney Lens GI-LLI 1H-3 0.00td0 1.12I43 1.12t+03 1.12tt03 1.12t+03 1.12843 1.12t+03
. 2P-32 2.60t+06 1.14Id5 9.88t+04 0.00!d0 0.00t+00 0.00140 4.22I44 1 3Cr-51 0.00840 0.00140 1.54t+02 8.55I+01 2.43t+01 1.70t+04 1.08t+03 I (Hn-54 0.00td0 4.29144 9.51t+03 0.00t do 1.00544 1.58t46 2.29I44 l 5Fe-59 2.07t+04 3.34I+04 1.67td4 0.00t+00 0.00t+00 - 1.271+06 7.07844 I
- i. 1 6Co-57 0.00l+00 9.03t+02 1.07I43 0.00t40 0.00!+00 5.07I45 1.32844 ,
7Co-58 0.00t+00 1.773+03 3.16td3 0.00I40 0.00t+00 1.111+06 3.44I44 l 8Co-60 0.00840 1.31144 2.26td4 0.00t+00 . 0.00t40 7.07I+06 9.62844 ,
~9Zn-85 4.25t+04 1.13Id5 7.03td4 0.00140 7.14I+04 9.95I+05 1.63td4 i 10Rb-86 0.00I40 1.981+05' 1.14I+05 0.00I40 0.00840 0.00t+00 7.998+03 11Er89 5.998+05 0.00I40 1.72I44 0.00t+00 0.00840 2.16t+06 1.671+05 ;
12St-90 1.01t+06 0.00t+00 6.44t+06 0.00t+00 0.00t+00 1.488+07 3.438+05 i 13Y 9.14t45 0.00100 2.44Id4 0.00t+00 0.00t+00 2.63846 1.84td5 14Zr-95 1.90td5 4.18t+04 3.70t+04 0.00t+00 5.96I+04 2.23t+06 6.11844 15Bb-95 2.35t+04 9.18td3 6.55t+03 0.00t+00 8.62t+03 6.14t+05 3.70144 1 16lb-97 4.29I-01 7.70E-02 3.60E-02 .0.00t+00 8.55I-02 3.42t+03 2.78t+04 d
17 h-99 0.00td0 1.72F+02 4.26t+01. 0.00t+00 3.92t+02 1.35Id5 1.27t+05 18fc-99: 1.781-03 3.481-03 5.771-02 0.00140 5.07I-02 9.51t+02 4.81843 19 h 103 2.79t+03 - 0.00I 40 1.07t+03 0.00t+00 7.03Id3 6.62I+05 4.48t+04 l 20 h-106 1.36t+05 0.00I40 1.69844 0.00140 1.64t+05 1.43I+07 4.29845 21As-110s 1.69144 1.14I+04 9.14I+03 0.00!+00 2.12t+04 5.46I+06 1.00t+05 22Sb-124 5.74t44 7.40t+02' 2.00I 44 1.26td2 0.00t+00 3.24346 1.64845 23Sh-125 9.64144 f.59td2 2.07144 9.10t+01 0.00td0 2.32t+06 4.03Id4 24fe-127s 2.49t+04 8.55t+03 3.02I43 6.07843 6.36td4 1.48I 4 6 7.14I44 25fe-129s 1.92844 6.85t+03 3.04143 6.33t+03 5.03t+04 1.76t+06 1.82t+05 26I-131 4.81t+04 4.811+04 2.73I+04 1.62847 7.88td4 0.00t+00 2.84t+03 27l-133 1.66144 2.03864 7.70t+03 3.85t+06 3.38544 0.00t+00 5.48t+03 28Cs-134 6.51I45 1.01I46 2.25t+05 0.00t+00 3.30t+05 1.21145 3.85td3 29Cs-136 6.51I44 1.71td5 1.16td5 0.00I40 9.55td4 1.45t+04 4.16t43 30Cs-137 9.07td5 8.25t+05 1.28145 0.00td0 2.82I45 1.04t+05 3.82163 31Ba-140 7.40t+04 6.48td1 '4.33Id3 0.00t+00 2.11I41 1.74t+06 1.02t+0i 32La-140 6.44I+02 2.25t+02 7.55t+01 0.00t+00 0.00t+00 1.83I+05 2.26I45 33Ce-141 3.92t44 1.95I+04 2.90l+03 0.00t+00 8.55t+03 5.44td5 5.66td4 34Ce144 6.77t46 2.12I46 3.61145 0.00I40 1.17t+06 1.20td7 3.898+05 CalculatedperODCWegnation2.2-13 ISSUI3 O 2-58 O .
i l
BV-1 and 2 ODCM 2.3 Crmplitnco Uith 10 CFR 50 Dosa Limits (0DCM Appendix C CONTROLS 3.11.2.2 And 3.11.2.3) (Gaseous)
(~ 7 At the Beaver Valley site all elevated gaseous releases are considered to Cl 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 dose for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The l only exception vould be a Contaiament Purge via the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since l 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 (0DCM Appendix C CONTROL 3.11.2.2) limits the releases of gaseous effluents from each reactor l 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 beta. Based upon NUREG-0133, the air dose limits in the i I
unrestricted area due to noble gases released in gaseous effluents are defined by the following expressions:
During Any Calendar Quarter, For Gamma Radiation:
,m 3.17E-8 E Mg [(X/0)y0 gy + (Eq)yqiy] + [B oi is + bg qi,] 35 During Any Calendar Quarter, For Beta Radiation:
3.17E-8 I N g (X/0)y0 gy + (X/q)yggy + (X/0)s0 3, + (X/q),qi s < 10 mead 1 -
[Y. 3-2 ]
During Any Calendar Year, For Gamme. Radiation:
3.17E-8 E Mg [(X/0)y0 gy +
(X/q),qiy] + (Bg10 , + bg qi,]- f 10 mrad i -
[2.3-3]
During Any Calendar Year, For Beta Radiation:
3.175-8 I N g (X/0)y0 gy + (X/q)yggy + (X/0),01s + (X/q),qi s < 20 mrad 1 -
[7. 3-4 ]
/"
2-59 ISSUE 3
BU-1 and 2 ODCH Averaged Over 31 Days, For The Gamma Radiation Projection:
3.17E-8 I Hg [(X/0)y0 gy + (X/q)yg gy] + [Bggo , + bg qis] < 0.2 mrad 1 - -
[2.3-3]
- l. Averaged Over 31 Days, For The Beta Radiation Projection:
3.17E-8 I N g (X/0)y0 gy + (X/q)yqiy + (X/0),0g , + (X/q),qi, < 0.4 mrad j i -
[7.3-6] .
where Hg - The air dose factor due to gamma emissions for each I identified n ble gas radionuclide "i" (mrad /yr !
3 l per uCi/m ).
! I l N,
= The air dose factor due to beta emissions for each '
identified n ble gas radionuclide "i" (mrad /yr 3
per uCi/m ).
(X/0)y - The annual average relative concentration for areas at or beyond the unrestricted area boundary for 31ong-term vent releases greater than 500 hrs / year (sec/m ).
l (X/q)y = The relative concentration for areas at or beyond the I unrestricted area boundary for short-term vent releases I equal to or less than 500 hrs / year (sec/m ).3 (X/0)s - The annual average relative concentration for areas at or beyond the unrestricted area boundary for long-l term free standing 3 stack releases greater than 500 hrs / year (sec/m ).
(X/q)s = The relative concentration for areas at or beyond the unrestricted area boundary for short-term free standing stack releases 3
equal to or less than 500 hrs / year (sec/m ).
q1, = Release of noble gas radionuclide "i" in gaseous effluents for short-term stack releases equal to or less than 500 hrs / year (uci).
qgy = Release of noble gas radionuclide "i" in gaseous effluents for short-term vent releases equal to or less than 500 hrs / year (uci).
O,g
= Release of noble gas radionuclide "i" in gaseous effluents for long-term free standing stack releases greater than 500 hrs / year (uci).
O gy - Release of noble gas radionuclide "i" in gaseous effluents for long-term vent releases greater than 500 hrs / year (uCi).
O 2-60 ISSUE 3
BV-1 and 2 ODCH I
l Bj- =.The constant for long-term releases (greater than 500 hrs / year) for each identified noble gas radionuclide O
1 "i" accounting for the gamma..' radiation from the elevated 1 V finite plume (mrad /yr per uCi/sec). -l bg - The constant for short-term releases (equal to or less than- 500- hrs / year) for .each, identified noble gas ~)
radionuclide "i" accounting for the gamma radiation from i the elevated finite plume (mrad /yr per uC1/sec). '
i 3.17E-8'- The inverse of-the number of seconds in a year. -j NUREG 0133 permits eliminating'.the short-term release term and short- l term meteorological terms-in the determination of doses when short-term l releases are sufficiently. random in both time-of day and duration to be j represented by annual average dispersion conditions. -
1' - . .
- This special consideration -is applied in Expressions [2.3-1] through j
.[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 alsos evaluated annually in computer codes i
technically consistent with' X00D00, and. GASPAR for. inclusion in the -
j
' Annual Radiological Environmental Report.- ;
1 The incorporation of this. option and :the release' modes of Table 2.3-1 results in the following expressions to' show compliance.with 10 CFR'50-for'the' calendar quarter or year.
I 1 For Release Modes 1, 2, 3, And 4 d
During Any: Month, Calendar Quarter, Or Year l
- l. Gamma Radiation:
3.17E-8-I Mg [(X/0)ey0 g + (X/0),y0 g + (X/0)cp0 g + @ )dv 03 dy i cv vv- -
cp .;
(X/0),y0 3 ] + 0.5 B ig o vv .pv g l
0.2 mrad (per 31 days) -[2.3-7] .
I f 5.0 mrad (per quarter) 10.0 mrad (per year) l i I LO 2-61 ISSUE 3
,- . __ __- _ _ _ - ~, ._ , - - _ . . _ __ _ _ _ . . . . _ ,
BV-1 and 2 ODCM Beta Radiation:
3.17E-8 I N g (X/0)cv01 + (X/0)yy0 1 + (X/0)cp0 1 + (X/0)dv 0g +
i cv vv cp dv (X/0)yy0 g + 0.5 (X/0)py0 g y
, 0.4 mrad (per 31 days) [2.3-8]
< 10.0 mrad (per quarter) 20.0 mrad (per year) where:
(276)cv - Annual average relative concentration3 for releases from the Containment Building Vent (sec/m ).
(276)" = Annual average relative concentration for 3 releases from the Ventilation Vent (sec/m ),
(X/0)pv = Annual average relative3 C "C'"*#"II " f # #*I**8'8 f#
- the Process Vent (sec/m ).
(iT6)tv = Annual average relative concentration for releases from the Turbine Building Vent (sec/m ).
Og = Release of radionuclide "i" from the Containment Building cv Vent (uci).
Og vv
= Release or radionuclide "i" from the Ventilation Vent O (uC1).
Og - Release of radionuclide "i" from the Process Vent pv (uci).
Og - Release of radionuclide "i" from the Turbine Building tv Vent (uci).
Og = Release of radionuclide "i" from the Condensate Polishing cp Building Vent (uci).
I Og - Release of radionuclide "i" from the Decontamination dv Building Vent (uci).
Og = Release of radionuclide "1" from the Vaste Gas Storage vv Vault Vent (uCi).
l l For Modes 1, 2, 3, and 4 the controlling location is 0.35 miles NV.
I Substitution of the appropriate X/0 values into Expressions [2.3-7] and
[2.3-8] results in the following:
l O
2-62 ISSUE 3
_ . - . .. . . - - ...-.-. - .. - . - - . ~ - _ _ ~ - - - _ - - ~. .. . . . - . ..
1 BV-1 and 2 ODCM' i
Release Modes 1,'2, 3, And 4 ,
During Any Month, Calendar Quarter, Or Year: .
Gamma Radiation:
i 3.17E-8 I Mg [9.24E-5 O g + 1.03E l. O g + 7.35E-5 O g + 7.35E-5 O g +
1 cv vv tv cp- ,
I 9.24E-5 Og . + 9.24E-5 O g ] + 0.5 B gg 0 dv vv pv 3 0.2' mrad-(per 31 days)- -[2.3-9]'
< 5.0 mrad (per quarter) !
10.0 mrad (per year) - ,
Beta Radiations ,
3.17E-8 E N g 9.24E-5 O g + 1.03E-4 O g + 7.35E-5 O g ( 7.35E-5 O g +
i cv vv tv cp ;
9.24E-5 O g + 9.24E-5 O g + (0.5) 7.0E-10 O g j dv vv pv -!
-j 0.4 mrad (per 31 days) [2.3-10]- ,
< 10.0 mrad (per quarter)'
~~
~
20.0 mrad (per year)'
The: determination of the controlling locations for implementation of. j 10 CFR 50 is a function of the'following parameters: -
(1) Radionuclide mix and their isotopic' release .l (2) Release mode (3) Meteorology The incorporation of these p'arameters into Expressions (2.3-7].and 1
[2.3-8] resulted in the. expressions for the controlling locations as 1 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 j 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, were also considered in conjunction with the radionuclide mix to determine the controlling location. These values of X/0 were obtained for the midpoint of the 10 standard i distance intervals previously presented in Tables 2.2-4 through 2.2-10. !
63 ISSUE 3
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 Mg and N,, which vere used in the determination of the controlling location and which are to be used by BV-1 and BV-2 in Expressions [2.3-9] and [2.3-10] 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, 1 Revision 1 were multiplied by 1E6 to convert from picoeuries- to microcuries-3 for use in Table 2.2-11.
In the determination of the controlling location for Modes 1, 2, 3, and 4, Tables 2.2-4 through 2.2-7 are utilized for X/0 values, The B values to be utilized are the same values which vere presented in1 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]
Dg f 10 mrad [2.3-12]
For The Calendar Year:
D f 10 mrad [2.3-13]
l Dg 3 20 mrad [2.3-14]
vhere:
)
D = The air dose from gamma radiation (mrad).
Dg - The air dose from beta radiation (nr-d).
The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the i limits of Expressions [2.3-11] through [2.3-14) are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM Appendix C CONTROL 3.11.2.2.a must be filed with the NRC at the identified locations.
1 In addition, ODCM Appendix C CONTROL 3.1.2.4 requires that the gaseous i 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 f 0.2 mrad [2.3-15]
Dg 3 0.4 mrad [2.3-16]
2-64 ISSUE 3 G
-- ~ . . . ~ . - . - - . . . . . . - - - . . - . - - . - . . . - . . _ . - . . . _ . . ~ , . - _ -
BV-1 and 2.0DCM 2.3.1.2 Projection Of Doses-(Noble Gas).
O Doses.due.-to gaseous releases from BV-1 and 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 2.3.2.2 Projection Of Doses). The . Gaseous Radvaste Treatment System'and'the L shall Ventilation Exhaust Treatment System be used to-. reduce radioactive materials:in gaseous vaste. prior .to their discharge in accordance with ODCM Appendix C CONTROL '3.11.2.4 'vhen 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
[2.3-9] and [2.3-10] as appropriate. The 31-day dose projection shall ,
be performed according to the following equations:
l When Including Pre-Release Data, u
. . i 4
A+B [2.3-17]
D 31 " - T-- (31) + C -
When Not Including Pre-Release Data, i l,
A [2.3-18]~ r
(
D 31 " T (31).+C 1
-where:-
D37 - Projected 31 day dose (mrad).-
4_ A = Cumulative dose for quarter (mrad).
B = Projected' dose from this release (mrad).
T = Current days into quarter.
C = Value which may be used to anticipate plant trends (mrad)..
1 0
2-65 ISSUE 3 l
BV-1 cnd 2 ODCM 2.3.2 Dose Due To Radioiodines And Particulates 2.3.2.1 Cumulation Of Doses Section IIC of Appendix I of 10 CFR 50 (ODCH Appendix C CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of radiciodines 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, vould 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 Rg .g [V 3 g0 , + v,q h + "v 0 gy +vggy]
y i
0.3 mrem (per 31 days) [2.3-19]
< 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:
O,g = Release of radionuclide "i" for long-term free standing stack releases greater than 500 hrs /yr (uci).
0"I - Release of radionuclide "i" for long-term vent releases greater than 500 hrs /yr (uCi).
qb - Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs /yr (uci).
qIV = 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, (V/0),.
- meters
-2 for the food and ground plane pathway, (D76),.
V
= The dispersion parameter for estimating the dose to an individual at the controlling location for long-term vent releases greater than 500 hrs /yr.
3
- sec/m for the inhalation pathway, (X/0)y.
- meters
-2 for the food and ground plane pathway, (D76)y.
2-66 ISSUE 3 j
BV-1 and 2 ODCH 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.
= sec/m for the inhalation pathway, (X/q),.
-2
. meters for the food and ground plane pathway, (D/q),.
vy - The dispersion parameter for ' estimating the dose to an individual at the controlling location for short-term vent releases equal to or less than 500 hrs /yr.
3
- sec/m for the inhalation pathway, (X7q)y.
-2
= meters for the food and ground plane pathway, (579 )y.
3.17E The inverse of the number of seconds in a year.
R'T = The dose"T" the organ factor for each of interest (mrem identified
/yr perradionuclide uCi/see per "i" m-2for or mrem /yr per uCi/m3 ).
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
.p
,g particular organ,. Expression [2.3-19} becomes:
3.17E-8 E R g 0.5 Vpy0g +V cv0g +V yy 03 +V tv0g
+V cp0g +
i pv cv vv tv cp
- dv0g +
"* I vy dv 0.3 mrem (per 31 days) [2.3-20] ,
< 7.5 mrem (per quarter) 15.0 mrem (per calendar year) where:
V py
- Dispersion parnmeter for releases from the Process Vent.
V - Dispersion parameter for releases from the Containment cv Building Vent.
W yy - Dispersion parameter for releases from the Ventilation Vent.
V tv
- Dispersion parameter for releases from the Turbine Building Vent.
b V
2-67 ISSUE 3
BV-1 and 2 ODCM V
cp
- Dispersion parameter for releases from the Condensate Polishing Building Vent.
V dv
- Dispersion parameter for releases from the Decontamination Building Vent.
V yy Dispersion parameter for releases from the Vaste Gas Storage Vault Vent.
O i py -
Release of radionuclid'2 "i" from the Process Vent (uCi).
0 1C " - Release of radionuclide "i" from the Containment Building Vent (uci).
0 1
y
- Release of radionuclide "1" from the Ventilation Vent (uci).
0 1tv - Release of radionuclide "i" from the Turbine Building Vent (uC1).
Oi cp
- Release of radionuclide "i" from the Condensate Polishing Building Vent (uC1).
0 1 -
Release of radionuclide "i" from the Decontamination Building Vent (uci).
0 1" - Release of radionuclide "i" from the Vaste Gas Storage Vault Vent (uCi).
The Turbine Building Vent is not normally a radicactive 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 l
t
( 3.17E-8 I [R gT +R +R +V cy 03 +V yy0g +
i G g3 g 3+ Rg7 B
][0.5 Vpy01 pv cv vv "tv 0g tv
+
cp0g cp
+VO d dv
+""I vy l* ITI[0 5 (X/0)py0 g
+ (X/0)cy0 g +( }"" I vv +I )tv 03 +
(X/0)cp0g +
ev y cp (X/0)dv0g "
dv vv 0.3 mrem (per 31 days) [2.3-21]
< 7.5 mrem (per quarter) 15.0 mru (per year) 2-68 ISSUE 3
l BV-1 and 2 ODCH l
l vheres l
R it - Dose factor for an organ "t" for radionuclide "i" for the ground plane exposure pathway (mrem /yr per uCi/see per m -2),
iTg - Dose factor for an organ "T" for radionuclide "i" for R
either the cow m uCi/see per m -2) ilk or goat milk pathway (mrem /yr per ity = Dose factor for an organ "T" for radionuclide R "
vegetable pathway (mrem /yr per uCi/sec per m-2)i" ,
for the R
gTB - Dose factor for an organ "T" for the meat pathway (mrem /yrfor perradionuclide uCi/see per m"i"2).
iTy = Dose factor for an organ "T" far radionuclide3 "i" R
for the inhalation pathway (mrem /yr per uCi/m ),
It should be noted that V ev, V , V V and V yy in Expression [2.3-21]pv,are V in "termstv,g o cp, Vdv,/0(m-D ).
Values of the dose factor, R vere calculated using the methodology of NUREG-0133. The follovidd, equations were used for all nuclides except tritium:
TI - K'(BR),(DFAg T),
- mrem /yr per uCi/m 3 [2.3-22]
A(j vhere:
K' . A constant of unit conversion (lE6 pCi/uCi).
'(BR), - The breathing 3 rate of the receptor of sge group "a" (m /yr).
(DF.Ag ), = Each organ inhalation "i" dosethfactor for the receptor of age radionuclide (mrem /pci).
group "a" for the Inhalation dose factors (DFA g by organ for the various age groups are given in Table 3)-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 (m3 /yr)
Infant 1400 Child 3700 Teen 8000 Adult 8000 2-69 ISSUE 3
BU-1 and 2 ODCH iTg - M " (SF)DFGgT[O - e k ) Ag ]
2
= m -mrem /yr per uCi/sec [2.3-23]
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 see or 15 years).
DFGH = The groundplane dose conversion factor2 for 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.
R 0 (U ff (1 - f f )e-A tih t if g7g , g, ap)p (r)(DFL gT),[ +
s g
. m (S
= m -mrem /yr per uCi/see [2.3-24]
where:
K' = A constant of unit conversion (1E6 pCi/uCi).
Op - The animal's consumption rate, vet weight (kg/ day).
U ap - The receptor's milk consumption rate, for age "a" (liters /yr).
Y P
= The agricultural2 productivity by unit area of pasture feed grass (kg/m ).
Y 3 - The agricultural 2 productivity 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 grass.
(DFLg T)" - The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem /pCi). Ingestion dose factors (DFL for the various age groups are given in TableI3)811 through E-14 of Regulatory Guide 1.109 or Tables 1 through 4 of NUREG-0172.
2-70 ISSUE 3
BV-1 and 2 ODCH_ l A
i - The_ decay constant for the "i" th radionuclide.(sec~1).
f b - The decay constant for removal of activity on.gleaf i and plant surfaces by weathering 5.73E-7.'sec~
(corresponding to aL14 day half-life).
t 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).
f p = 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 g
reference to Regulatory Guide 1.109.
Parameter ,
Value Table r-(dimensionless) 1.0 for radioiodine E-15 ;
s 0.2 for particulates E-15 1
[ ~F,(days / liter) each stable element E-1 (cow milk)
'E-2 (goat milk)
J' 3
330 E ;
.U ap (liters /yr) - infant child: '330- E-5 :
4 teen 400 E-5 i i, adult 310- E-5
- (DLF h l (arem/pci) a eac'h radionuclide E-11 to E-14 .
2 E-15 Y 0.7 p (kg/m )
2 E-15 Y, (kg/m ) 2.0 l t g (seconds) 1.73E5 (2 days) E-15 7.78E6 (90 days)- E-15
, th (seconds)
Op (kg/ day) 50 E-3 f 0.5 --
p f, 1.0 --
4- -For goat's milk, all values remain the same except for op which is 6 kg/ day.
1 LO i 2-71 ISSUE 3 :
i
l BV-1 and 2 ODCM 0 (U ff (1 - f f )e i h t ~At if j ITB"K + P)Ff (r)(DFL h)a! +
I*
= m -mrem /yr per uCi/sec [2.3-25]
vhere:
F f = The stable element transfer coefficients (days /kg).
U,p - The receptor's meat consumption rate for age "a" (kg/yr).
t g - 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 which is obtained from Table E-1, t Table E fI5 and U vhich is obtained from Table, which E-5. The is obtained values from as obtained fromapRegulatory Guide 1.109, are as follows:
Parameter Value Table Ff (days /kg) each stable element E-1 tf (seconds) 1.73E6 (20 days) E-15 Uap (kg/yr) - infant 0 E-5 child 41 E-5 teen 65 E-5 adult 110 E-5 Han is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore:
R ~itt -At gh y = K' l y ()
. ](DLFh)a[U,fge + U,3fe g ]
2
= m -mrem /yr per uci/sec [2.3-26]
where:
K' - A constant of unit conversion (lE6 pCi/uC1).
U ,b = The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr).
S Ua = 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.
2-72 O
ISSUE 3
[
BV-1 and 2 ODCM l
f I= The fraction of the annual intake of stored vegetation grown locally.-
n tg - The average time between harvest of leafy vegetation'and its j consumption (seconds). ,
th - The average time between harvest of stored vegetation and its consumption (seconds).
2 Yy - The vegetation area density (kg/m ),
i all other factors are defined previously.
! Tabulated below are the appropriate parameter values and their i reference to Regulatory Guide 1.109. , . -
Parameter Value Table r (dimensionless) 1.0 for radioiodines E-15 l 0.2 for particulates E-15 l
(DFLh)a (mrem /pCi) each stable element E-11 to E-14 U,b (kg/yr) - infant 0 E-5 l child 26 E-5 l- teen 42 E-5 adult 64 E-5 m S (kg/yr) - infant (y
U child teen 520 630 0 E-5 E-5 E-5 adult 520 E-5 fg (dimensionless) 1.0 E-15 l
! 0.76 E-15 FE (dimensi nless) l' tg (seconds) 8.6E4 (1 day) E-15 t
h (seconds) 5.18E6 (60 days) E-15 Yy (kg/m ) 2.0 E-15 i
As discussed in Section 2.2.2 for tritium, the parameter V for the food pathvay is based upon X/0. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression [2.3-20]
may be expressed for purposes of implementation of 40 CFR 190, ,
discussed in Section 4.0, as: '
For Tritium:
! 3.17E-8 (R 0 0 +
Tg+ RTg+ RTg+ RTr y ) [0.5 (X/0)py Tp+ (X/0)cy T cy l (X/0)yy0 T + (X/0)tv0Tvv+ (X/0)cp 07 cp vv
+ (X/0)dv 07 dv
+ (X/0) ,y0 7vv ) l I
[2.3-27]
2-73 ISSUE 3 1
BU-1 ond 2 ODCH vhere R = Dose factor for organ "T" for tritium for the milk TM pathway (mrem /yr per uCi/sec3 ).
R = D se factor for organ "T" f r tritium f r the vegetable Th pathway (mrem /yr per uCi/m3 ).
R = Dose factor for organ "T" for tritium for the beef T3 pathway (mrem /yr per uCi/m3 ),
Pg = Dose factor for organ "T" 3 f r tritium f r 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 RTT is based on [X/Q]: H P
= K'K'"F,0 7U,p(DLFgT),[0.75(0.5/H)]
= mrem /yr per uCi/m 3 [2.3-28]
vhere K'" - A constant of unit conversion (1000 gm/kg).
H = Absolute humidity of the atmosphere (8 gm/m3 ),
0.75 = The fraction of total feed that is water.
0.5 - The ratio of the specific activity of the feed grass water to the atmospheric water.
and other parameter's and values are the same as for Rg .
l The concentration of tritium in vegetation is based on the airborne i
concentration rather than the deposition. Therefore, the R* % s based on.[X/0):
b b R
Tg=K'K'"[U,fg + U f ](DFLg g ),[0.75(0.5/H)]
= mrem /yr per uCi/m 3 [2.3-29] l vhere all terms have been defined above.
The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the RTT is based on [X/0): B 2-74 ISSUE 3 O
_ - _ . _ _ . _ .- . _ . _ . ~_ - _ _ __ _-
BV-1 and 2 ODCM R
T g= K'K'"F f70 U,p(DFLg7),[0.75(0.5/H)]
O - mrem /yr per uCi/m [2.3-30]
(d where all terms have been defined above. l l
To show compliance with ODCH Appendix C CONTROLS 3.11.2.3 and 3.11.2.4, l Equation [2.3-21] is evaluated at the controlling pathway location. ,
For. Release Modes 1 through 4, the controlling location is a residence 1 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- l l
Release Modes 1 Through 4 1
Per Month, Calendar Quarter, Or Years 3.17E-8 E g [R g +R g ][(0.5)4.22E-10 O g + 1.56E-8 O cy + 1.56E-8 py Og + 1.55E-8 O g + 1.55E-8 O g + 1.56E-8 O g + 1.56E-8' vv tv I cp dv Og ]+Rh [(0.5) 7.30E-9 Og + 2.00E-5 Og + 2.71E-5 Og vv ,
vv I pv cv '
+ 2.22E-5 O g + 2.22E-5 O g + 2.00E-5 O g + 2.00E-5 O g ]
y 0.3 mrem (per 31 days) [2.3-31]
< 7.5 mrem (per quarter
~
15.0 mrem (per year) b] For tritium, for purposes of implementation of'40 CFR 190, as discussed in Section 4.0, Expression [2.3-28] reduces to:
2.00E-5 01 + 2.71E-5 Og +
3.17E-8 [RT%+ RTT I ][(0.5)7.30E-9 Og p +v cv vv 2.22E-5 O g + 2.22E-5 O g + 2.00E-5 O g + 2.00E-5 O g ] j tv cp dv vv j
[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 radioiodines and particulates is a function of:
(1) Radionuclide mix and their isotopic release (2) Release mode (3) Meteorology I
(4) Exposure pathway (5) Receptor's age The incorporation of these parameters into Expression [2.3-19] results in the respective equations for each release mode at the controlling location.
O 2-75 ISSUE 3
BU-1 cnd 2 ODCM In the determination of the controlling location for each release mode, the radionuclide mix of radioiodines 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 pathvay, all radionculides (excluding H-3 and C-14) were considered in the determination of the controlling location. For the inhalation and food pathways H-3 and C-14 vere also considered in determination of the l controlling location.
In the determir.ation of the controlling location for each release mode, all of the exposure pathways, as presented in Table 2.2-3, vere evaluated. These include cow milk, goat milk, beef and vegetable ingest 4.en and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathway locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways were considered to be present at all locations.
For the determination of the controlling location, the highest D/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 through 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, 4
O GI-tract, bone, liver, kidney, thyroid, and lung organs for the ground plane, inhalation, cow milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as appropriate to the pathways. These values were calculated using the methodology described in NUREG-0133 using a grazing period of 6 months.
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.
O 2-76 ISSUE 3 I
l 2
i BV-1 end 2 ODCH The following relationship should hold for BV-1 or BV-2 to show compliance with ODCM Appendix C CONTROL 3.11.2.3.
( For The Calendar Quarter:
D f 7.5 mrem to any organ [2.3-33]
For The Calendar Year:
- l. D f 15 mrem to any organ [2.3-34]
l l vhere:
D ,- The dose to any organ from radioiodines and particulates (mrem).
The quarterly ~ limits given above represent one-half the annual design objective of Section IIC of Appendix I of 10 CFR 50. If any.of the i
I 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.
l l
A l
l i
- O 2-77 ISSUE 3 i
BV-1 and 2 ODCM l l
l 2.3.2.2 Projection Of Doses (Radioiodines And Particulates)
Doses due to gaseous releases from BV-1 or BV-2 shall be projected at l least once per 31 days in accordance with ODCM Appendix C CONTROL 4.11.2.4 and this section. l (See also Section 2.3.1.2 '
Projection Of Doses). The appropriate portions of the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge in accordance with ODCM Appendix C CONTROL 3.11.2.4 when the proj ec ted doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, vould 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 radioiodines and particulates vill be calculated for use in the 31-day dose projection using Expression [2.3-31]. The 31-day dose projection shall be performed according to the following equations:
When Including Pre-Release Data, D
31 - A_ + B (31) + C [2.3-35]
T When Not Including Pre-Release Data, D = A (31) + C [2.3-36]
where:
D31 - Projected 31 day dose (mrem).
A = Cumulative dose for quarter (mrem).
B = Projected dose for this release (mrem).
T = Current days into quarter.
C = Value which may be used to anticipate plant trends (mrem).
O 2-78 ISSUE 3 1
BV-1 and 2 ODCM TABLE 2.3-1 MODES OF GASEOUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR )
IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 i
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 1 Same As Same As Same As BVPS-1 Containment Leakage Vent (cv1) Collection . Mode 1 Mode 1 And Mode 1 Exhaust Contajnment Purge BVPS-1 Turbine Bldg.1 Turbine Bldg. Same As Same As' _Same As Vent (tyl) 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
BVPS-2 Containment Aux. Bldg. Same As Same As Same As Vent (cv2) Ventilation Mode 1 Mode 1 And Mode 1 O Contajnment Purge l
BVPS-2 Turbine Bldg.1 Turbing Bldg. Same As Same As_ Eame As Vent (tv2) Exhaust *- Mode 1* Hode 1* Mode 1*
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 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
BV-1and2ODCH fable 2.3-2 HVALUESFORBIAVIIVALLEYSlft (ares /yrperuC1/cuseter)
Pathway: Inhalation i
AgeGroup: Adult Nue11de Bone Liver f. Body Thyroid tidney Lung GI-LLI 1H-3 0.00tt00 1.26bO3 1.26Et03 1.26bO3 1.26bO3 1.26bO3 1.261+03 l 2P-32 1.32b06 7.71b04 5.0lb04 0.00D00 0.00b00 0.00b00 8.64b04 3Cr-51 0.00b00 0.00b00 1.00!+02 5.95b01 2.281+01 1.44b04 3.32bO3 4Hn-54 0.00b00 3.96b04 6.30bO3 0.00 BOO 9.84t+03 1.40b06 7.74b04 5Fe-59 1.18b04 2.78b04 1.06b04 0.00D00 0.00!+00 1.02b06 1.88b05 6Co-57 0.00!+00 6.92t+02 6.71E+02 0.00!+00 0.00D00 3.70b05 3.14b04 700-58 0.00b00 1.58bO3 2.07bO3 0.00t+00 0.00b00 9.28b05 1.06b05 8Co-60 0.00!+00 1.15b04 1.4Bb04 0.00000 0.00D00 5.97b06 2.85b05 9Zn-65 3.24b04 1.03b05 4.66b04 0.00b00 6.90t+04 8.64b05 5.34b04 10Hb-86 0.00b00 1.35b05 5.90b04 0.00l+00 0.00D00 0.00t+00 1.66t+04 11Sr-89 3.04b05 0.00b00 8.72D03 0.00D00 0.00b00 1.40D06 3.50b05 12Sr-90 9.92bO7 0.00b00 6.10h06 0.00E+00 0.00b00 9.60t+06 7.22b05 13T-91 4.62b05 0.00b00 1.24t+04 0.00h00 0.00b00 1.70D06 3.85b05 14Zr-95 1.07b05 3.44b04 2.33b04 0.00h00 5.42b04 1.77b06 1.50b05 15lb-95 1.41b04 7.82bO3 4.21bO3 0.00t+00 7.74bO3 5.05b05 1.04b05 16Hb-97 2.22I-01 5.621-02 2.05I-02 0.00b00 6.541-02 2.40bO3 2.42bO2 17Mo-99 0.00b00 1.21bO2 2.30b01 0.00bO0 2.91bO2 9.12b04 2.48b05 18fe-99: 1.031-03 2.911-03 3.70E-02 0.00b00 4.421-02 7.64bO2 4.16bO3 19Ru-103 1.53bO3 0.00h00 6.58bO2 0.00D00 5.83bO3 5.05b05 1.10D05 20Ru-106 6.91b04 0.00h00 8.72bO3 0.00h00 1.34b05 9.36b06 9.12b05 21As-110s 1.08b04 1.00b04 5.94bO3 0.00b00 1.97b04 4.63b06 3.02b05 22Sb-124 3.12E+04 5.89b02 1.24b04 7.55b01 0.00b00 2.48b06 4.06b05 23Sb-125 5.34b04 5.95bO2 1.26b04 5.40b01 0.00D00 1.74b06 1.01b05 24fe-127s 1.26h04 5.77bO3 1.57bO3 3.29b03 4.58b04 9.60D05 1.50D05 25fe-129s 9.76bO3 4.67bO3 1.58bO3 3.44bO3 3.66b04 1.ltb06 3.83905 26I-131 2.52b04 3.58b04 2.05b04 1.19bO7 6.13b04 0.00b00 6.28bO3 27I-133 8.64bO3 1.48D04 4.52bO3 2.15b06 2.58b04 0.00b00 8.88bO3 28Cs-134 3.73b05 8.48b05 7.28b05 0.00b00 2.87b05 9.76b04 1.04D04 29Cs-136 3.90b04 1.46b05 1.10b05 0.00h00 8.56b04 1.20b04 1.17b04 30Cs-137 4.78b05 6.21h05 4.28105 0.00b00 2.22b05 7.52b04 8.40bO3 31Ba-140 3.90b04 4.90h01 2.57bO3 0.00b00 1.67b01 1.27b06 2.18b05 32La-140 3.44bO2 1.74bO2 4.58b01 0.00b00 0.00D00 1.36D05 4.58D05 33Ce-141 1.99b04 1.35b04 1.53D03 0.00 BOO 6.26bO3 3.62b05 1.20b05 34Ce-144 3.43b06 1.43D06 1.84b05 0.00b00 8.48D05 7.78b06 8.16b05 CalculatedperODCMequation2.3-22 ISSUI3 2-80
(
. ~ . . -. - . - - ---. - .. - - .- . - - . . .. - - - - -- .- -_-
5 BV-1and2ODCM fable 2.3-3 O iVALUISF0IBliVIIVALLEYSITI i
l (ares /frperuC1/cuseter)
Pathwar: Inhalation AgeGroup: feen ;
Nuclide' Bone Liver f. Body thfroid lidner Long GI-I,LI .
- 1 H-3 ' O.00l+00 1.27I+03 1.271+03 1.27I+03 1.27I+03 1.27I+03 1.27I+03 l 2P-32 1.898+06 1.10l+05 7.16I+04 0.00l+00 0.00l+00 0.00l+00 9.281+04 ,
3Cr-51 0.00l+00 0.00l+00 1.35E+02 7.50E+01: 3.07I+01 2.10l+04 - 3.00l+03 ;
4Mn-54 0.00l+00 ~ 5.11t+04 8.40l+03 -0.00l+00 . 1.27t+04 1.98I+06 6.68I+04
- 5Fe-59 1.59I+04 3.70I44 1.43B+04 0.00l+00 0.00l+00 1.53E+06- 1.788+05 6Co-57 0.00I40 9.44I42 9.20l+02 0.00l+00 0.00I40 5.86t+05 3.14t+04 7Co-58 0.00I40 2.07I+03 2.788+03 0.MI+00 0.00l+00 1.34E+06 9.52E+04.
8Co-60~ 0.00I 4 0 1.51B+04- 1.98I+04 0.00I40 0.00I40 8.72t+06 2.598+05 >
9Zn-65 3.86t+04. 1.34I+05 6.24144 0.HI+00 8.64I 44 1.24E+06 4.66t+04 10lb-86 0.00l+00 1.90E+05 8.40E+04 0.00It00 0.00I40 0.00l+M 1.77t+04 11St-89 4.34I+05 0.00l+00 - 1.25E+04 0.00l+M 0.00I40 2.42E+06 3.715 45 12St-90 1.08I+08 0.00I 40 6.68t+06 0.00I40 0 M I+00 1.65E+07 7.65I 45-13Y-91 6.61t+05 0.00l+M 1.778+04' 0.008 40 0.00l+00 2.94t+06~ 4.095+05
-14Zr-95 1.46I45 4.58I 44' 3.15E+04 0.00I40 6.74E+04 2.695+06 1.495+05 O 15lb-95 1.868+04 1.03t+04 5.66t+03 0.00I40 1.00t+04' 7.51E+05 9.68I 4 4-16Nb-97 3.141-01 7.78I-02 2.84I-02 0.00l+00 . 9.128-02 3.93I43 2.17I43 17Mo-99 0.00l+00 ~ 1.895+02 3.22t+01~ 0.00I 40~ 4.11I+02 1.54I+05 2.69845 18fe-99s. 1.38I-03 . 3.868-03 4.99I-02 . 0.MI+00 5.768-02 1.158+036.13Id3 19In-103 2.10I4 3 -0.00540 ,8.96t+02 'O.00l do 7.43I4 3 7.83E+05 1.09t+05 20 h-106 9.84t+04 0.00l+00 1.24B+04 0.00l+00 1.90l+05 1.61I47 9.60l+05 21As-110s .1.38t+04' 1.315+04 7.99t+03 - 0.00E+00 2.50l+04 6.75t+M 2.73E+05 22Sb-124 4.30l+04 7.94X+02 ~1.68t+04 9.765+01 0.00I40 3.34E+06 3.98t+05 >
23Sb-125 7.38I44 8.08I+02. 1.72t+04 7.04I41 0.00l+00' 2.74t+06 9.92E+04 24fe-127s 1.80It04 8.16It03 2.168t03 4.36It03 6.548t04 1.665t06 1.595t05 25te129s 1.39I44 6.585+03 2.25t+03 4.58t+03 . 5.19I44 1.98t+06 4.05I+05 26I-131- 3.54E+04 4.91E+04 2.64B+04 1.46t+07 8.40l+04 0.00E+00 6.498+03 27I-133 1.22I44 2.05t+04 6.22t+03 2.92It06 3.59I+04 0.00t+00 1.03E+04 28Cs-134 5.02I45 1.13Id6 5.49t+05 0.00l+00 3.75I+05 1.46I+05 9.76td3 29Co136 5.15t+04 - 1.94I 45 1.37t+05 0.00l+M . 1.10l+05. 1.788+04 1.095+04 30Cs-137 6.70t+05 8.48845 3.11I45 0.00l+00 3.04I+05 .1.21I 4 5 8.48I+03 31Ba-140 5.47I+04 6.70t+01 3.52Id3 0.00E+00 2.28I 4 1 2.03Id 6 - 2.291+05 32La-140 4.791+02 2.368+02 6.26I+01 0.00l+00 0.00t+00 2.14E+05 4.87I 4 5 33Ce-141 2.84I+04 1.90l+04 2.17I+03 0.00I40 8.88I+03 6.14t+05 1.265+05 34Ce-144 4.898+06 2.02Id6 2.62145 0.00It00 1.21t+06 1.34I+07 8.64t+05 CalculatedperODCMequation2.3-22 2 ISSUI3 2-81
BV-1and2ODCM fable 2.3-4 I RVALDISFORBIAVIIVALLEYSIf!
(ares /yrperuCi/cuseter)
Pathway:Ichalation AgeGroup: Child Nuclide Bone Liver f. Body Thyroid lidney Lung GI-LLI 1H-3 0.00!+00 1.12t+03 1.12It03 1.12f+03 1.12t+03 1.12t+03 1.12I+03 2P-32 2.60!+06 1.14E+05 9.88I+04 0.00!+00 0.00!+00 0.00t+00 4.22E+04 3Cr-51 0.00l+00 0.00!+00 1.54E+02 8.55E+01 2.43E+01 1.70!+04 1.08I+03 4Ma-54 0.00!+00 4.291+04 9.511+03 0.00E+00 1.00E+04 1.58I+06 2.29t+04 5Fe-59 2.071+04 3.34E+04 1.67Et04 0.00t+00 0.00!+00 1.27I+06 7.078+04 600-57 0.00!+00 9.03E+02 1.071+03 0.00!+00 0.00!+00 5.07I+05 1.32E+04 7Co-58 0.00E+00 1.77t+03 3.16t+03 0.00!+00 0.00l+00 1.111+06 3.44E+04 8Co-60 0.00!+00 1.31t+04 2.268+04 0.00t+00 0.00!+00 7.071+06 9.62t+04 9Zn-65 4.25E+04 1.13E+05 7.03E+04 0.00E+00 7.14t+04 9.95E+05 1.63E+04 10Hb-86 0.00E+00 1.98I+05 1.14t+05 0.00E+00 0.00!+00 0.00E+00 7.99t+03 11Sr-89 5.99t+05 0.00t+00 1.72E+04 0.00t+00 0.00!+00 2.16Et06 1.67I+05 12Sr-90 1.011+08 0.00E+00 6.44Et06 0.00l+00 0.00E+00 1.48I+07 3.43I+05 13 T-91 9.14E+05 0.00l+00 2.44t+04 0.00!+00 0.00E+00 2.63I+06 1.84t+05 14Zr-95 1.90!+05 4.18t+04 3.70E+04 0.00t+00 5.961+04 2.23E+06 6.11t+04 15Nb-95 2.35t+04 9.18I+03 6.55t+03 0.00!+00 8.62t+03 6.14E+05 3.Y'I+04 16 Nb-97 4.20I-01 7.50E-02 3.601-02 0.00E+00 8.55I-02 3.42t+03 2.78t+04 17Ho-99 0.00!+00 1.72I+02 4.26t+01 0.00!+00 3.921+02 1.35E+05 1.27I+05 18fe-99s 1.78I-03 3.481-03 5.77I-02 0.00t+00 5.071-02 9.51E+02 4.81t+03 19Hu-103 2.79t+03 0.00!+00 1.071+03 0.00E+00 7.03t+03 6.62E+05 4.48E+04 20Hu-106 1.36t+05 0.00!+00 1.691+04 0.00It00 1.84t+05 1.43t+07 4.291+05 21Ag-110s 1.691+04 1.14E+04 9.14E+03 0.00!+00 2.12E+04 5.481+06 1.00!+05 22Sb-124 5.74E+04 7.40!+02 2.00!+04 1.261+02 0.00!+00 3.24I+06 1.64t+05 23Sb-125 9.84t+04 7.59t+02 2.071+04 9.10!+01 0.00!+00 2.32t+06 4.03t+04 24fe-127a 2.491+04 8.55I+03 3.02E+03 6.07I+03 6.361+04 1.48t+06 7.14t+04 25fe-129s 1.92It04 6.65t+03 3.04t+03 6.33E+03 5.03t+04 1.761+06 1.82E+05 26I-131 4.81t+04 4.81E+04 2.73E+04 1.62It07 7.88I+04 0.00!+00 2.84It03 27I-133 1.66t+04 2.03t+04 7.70t+03 3.85E+06 3.38I+04 0.00E+00 5.48tt03 28Cs-134 6.51E+05 1.011+06 2.25E+05 0.00!+00 3.30!+05 1.21E+05 3.85E+03 29Cs-136 6.511+04 1.711+05 1.16t+05 0.00l+00 9.55E+04 1.45t+04 4.18t+03 30Cs-137 9.07t+05 8.25E+05 1.28t+05 0.00!+00 2.82X+05 1.04t+05 3.62t+03 31Ba-140 7.40!+04 6.48t+01 4.33E+03 0.00!+00 2.11t+01 1.74E+06 1.02t+05 32La-140 6.44E+02 2.25t+02 7.55E+01 0.00t+00 0.00!+00 1.83t+05 2.261+05 33Ce-141 3.92I+04 1.95I+04 2.90t+03 0.00t+00 8.55t+03 5.44t+05 5.661+04 34Ce-144 6.77I+06 2.12t+06 3.61E+05 0.00t+00 1.178+06 1.20!+07 3.89t+05 CalculatedperODCMequation2.3-22 2-82
~
m __ _ __- _ _ _ _- -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ..
_ __.___4 m. _ _ _ _ . . _ _ _ _ _ _ - _ _ _ _ . _ . _ _ . _ _ . . _ _
BV-1and2ODCM fable 2.3-5 IVALUISFORBIAVIIVALLIfSITI .
(sres/yrpernCi/cuseter)
Pathway: Inhalation AgeGroup: Infant hclide' ' Bone Liver f. Body Thyroid lidney Lung GI-LL1 1 H-3 : 0.00l+00 6.47t+02 6.47I+02 6.47t+02 6.47I+02 6.47t+02 6.47I+02 2P-32 2.03E+06 't.12t+05 7.74t+04 0.00l+00 0.00l+00 0.00t+00 1.61t+04 3Cr-51 .0.00I40 0.00l+00 8.95141 5.75841 1.32E+01 1.28I44 3.57t+02 4Mn-54 0.00l+00 2.53t+04 4.98I+03 ~ 0.00E+00 4.981+03 1.00l+06 7.068+03
- 5Fe-59 .1.36t+04 2.35t+04 9.481+03 0.00840 0.00l+00 .1.01t+06 2.48t+04 6Co-57 0.00l+00 6.51t+02 6.41t+02 0.00I 40 0.00l+M 3.798+05 4.86t+03 7Co-58 0.00I40 1.22E+03 1.82t+03 . 0.00l+00 0.00l+00 7.77I+05 1.11E+04
! 8Co-60 0.00l+00 8.02E+03 .1.18I+04 -0.00E+00 0.00l+M 4.51t+06 3.19I44
- l. 9Zn 1.93t+04 6.26I+04 3.11E+04 -0.00l+00 3.25t+04 6.47t+05 5.14I+04 L 10Ib-86 0.00l+00 1.90l+05 8.82t+04 0.00l+M 0.00l+00 0.00l+00 ~3.04I 43
? >
l 11Sr 3.98I+05 0.00I40 1.14t+04 0.00840 0.00l+00 2.03E+06 6.40Id4 12St-90 4.098+07' 0.00l+00 2.59t+06 0.00E+00 0.00l+00 1.12E+07 1.31I 4 5 13 T-91 5.88t+05 0.00t+00 1.57144 0.00t+M 0.00t+00 2.45E+06 1 7.03t+04-O 14Zr-95 15lb 1.15I 45 2.79I+04 2.03E+04 0.00l+00 3.11E+04 1.75E+06 2.17I44 1.57t+04' 6.43t+03 3.788+03 0.00I+00' 4.72t+03 4.795+05 1.27I+04 '
16Ib ' 3.42I-01' 7.295 32 2.631-02 0.00l+00 5.708-02 3.32t+03 2.698+04.
17Mo-99 0.00t+M 1.65I+02 3.23E+01 0.00l+00 . 2.65t+02-.1.35t+05 4.87I 4 4 i . 187c-99 1.40I-03 2.888-03 .' 3.725-02 0.00l+00 3.115-02 8.11t+02 2.03E+03' l 19Iu-103 2.02E+03. 0.00l+00 6.79I+02 . 0.00I 40 4.24t+03 5.52I 45 1.61I 4 4 '
20In-106 8.688+04 0.00l+M 1.098+04 0.00l+00 1.07I+05- 1.16I+07 1.64t+05 21As-lion 9.988+03 7.22t+03 5.H I+03 0.00E+00 1.09t+04 3.67t+06 3.30l+04 22Sb-124' 3.79544 5.56t+02 1.20l+04 1.01R+02 0.00l+00 2.65t+06- 5.911 44 23Sb-125 5.17I 4 4 4.77I+02 1.09t+04 6.23E+01 0.00E+M 1.64t+06 . 1.47t+04 24fe-127s 1.67I+04 6.90B+03 2.07I+03 4.87I+03 3.75t+04 1.31t+06 2.73E+04 25fe-129s 1.415 44 :6.09t+03 2.23E+03 4.21E+03 3.18t+04 1.68I+06 6.90l+04 261-131 3.79I+04 4.44I+04 1.96I 4 4 1.48I+07 5.188+04 0.00l+00 1.06t+03 27I-133 1.32t+04 1.92844 5.60l+03 3.568+M 2.24t+04 0.00l+M 2.16t+03 28Cs-134 3.96Ed5 7.03E+05 7.451+04 . 0.00B+00 1.90t+05 7.97I+04 1.33I+03 29Cs-136 4.83E+04 1.35t+05 5.29I+04 0.00I40 5.64t+04 1.18t+04 1.43I+03 30Cs-137 5.49I45 6.12t+05 4.55E+04 0.00l+00 1.72t+05 7.13t+04 1.33t+03
~31Ba-140 5.60l+04 5.60t+01 2.90l+03 0.00l+00 1.34t+01 1.60I 46 . 3.84t+04 i i 32La-140 '5.05E+02 2.00I 42 5.15B+01 0.0M+00 0.00l+00--1.68I45 8.488+04 l
- 33Ce-141 2.77t+04 1.671+04 1.99t+03 0.00I40 5.25E+03 5.17I+05 2.168+04 34Ce-144 3.191+06 1.211+06 1.76t+05 0.00t+00 5.385+05 9.84t+06 1.48td5 ,
Calculated per ODCM epation 2.3-22 I
ISSUI3 2-83
BV-1and2ODCM fable 2.3-6 RVALDISFOREIAVERVALLEYSIf
(egseter-ares /yrpernC1/seci Pathwar-Ground Nuclide .,sne Liver f. Body thyroid Ildney Lung GI-LL1 1H-3 0.00!+00 0.00E+00 0.00!+00 0.00!+00 0.00!+00 0.00t+00 0.00E+00 2P-32 0.00E+00 0.00l+00 0.00l+00 0.00l+00 0.00E+00 0.00l+00 0.00E+00 3Cr-51 4.661+06 4.66t+06 4.66I+06 4.66t+06 4.66I+06 4.66t+06 4.661+06 4Mn-54 1.39t+09 1.39t+09 1.392+09 1.39E+09 1.39t+09 1.391+09 1.39t+09 :
5Fe-59 2.73E+08 2.73t+08 2.73E+0B 2.73E+08 2.73E+08 2.73E+08 2.73E+08 !
1 6Co-57 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00It00 700-58 3.79t+08 3.79I+08 3.791+08 3.791+08 3.79t+08 3.798+08 3.791+08 8Co-60 2.15E+10 2.15f+10 2.15E+10 2.15E+10 2.15t+10 2.15t+10 2.15t+10 :
9Zn-65 7.47I+08 7.471+08 7.47I+08 7.47t+08 7.47t+08 7.47I+08 7.475+08 10Hb-86 8.99t+06 8.991+06 8.991+06 8.99t+06 8.991+06 8.99t+06 8.99t+06 11St-89 2.16t+04 2.161+04 2.16t+04 2.16I+04 2.16t+04 2.161+04 2.16I+04 12Sr-90 0.00!+00 0.00E+00 0.00N0 0.00!+00 0.00l+00 0.00E+00 0.00E+00 13f-91 1.071+06 1.071+06 ' ~ id 1.071+06 1.071+06 1.071+06 1.07t+06 14Zr-95 2.45E+08 2.45E+08 e 0 08 2.45E+08 2.451+08 2.45I+08 2.45t+08 '
15Hb-95 1.37I+08 1.371+08 .. 71+08 1.371+08 1.371+08 1.371+0B 1.37I+08 16 Nb-97 0.00!+00 0.00E+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00E+00 17Mo-99 4.00!+06 4.00E+06 4.00l+06 4.00!+06 4.00!+06 4.00!+06 4.00E+06 18fc-99: 1.84E+05 1.84I+05 1.84t+05 1.84E+05 1.84t+05 1.84E+05 1.84t+05 19Ru-103 1.081+08 1.08I+08 1.08t+08 1.08t+08 1.98I+08 1.08t+08 1.08t+08 20Rn-106 4.22I+08 4.22E+08 4.22t+08 4.22t+08 4.22E+08 4.22E+08 4.22E+08 21Ag-110s 3.44E+09 3.44IiO9 3.44t+03 3.44E+09 3.44X+09 3.44t+09 3.44It09 22Sb-124 0.00!+00 0.00l+00 0.00!+00 0.00!+00 0.00E+00 0.00t+00 0.00!+00 23Sb-125 0.00!+00 0.00!+00 0.00!+00 0.00t+00 0.00!+00 0.00!+00 0.00t+00 24fe-127 9.17t+04 9.17I+04 9.17t+04 9.17t+04 9.17t+04 9.17I+04 9.17t+04 25fe-129s 1.981+07 1.98t+07 1.98t+07 1.98I+07 1.981+07 1.98I+07 1.98I+07 26I-131 1.72It07 1.72t+07 1.72E+07 1.72It07 1.721+07 1.72E+07 1.72I+07 27I-133 2.45t+06 2.45E+06 2.45t+06 2.45t+06 2.45I+06 2.45t+06 2.45t+06 28Cs-134 6.86I+09 6.86t+09 6.86tt09 6.88t+09 6.86I+09 6.86t+09 6.86t+09 29Cs-136 1.51!+08 1.51E+08 1.51t+08 1.51E+08 1.511+08 1.51E+08 1.51t+08 30Cs-137 1.03E+10 1.03E+10 1.03t+10 1.03E+10 1.03E+10 1.03t+10 1.03E+10 31Ba-140 2.05E+07 2.05t+07 2.05t+07 2.05E+07 2.05I+07 2.05t+07 2.05It07 32La-140 1.92E+07 1.92t+07 1.32t+07 1.92E+07 1.92E+07 1.92t+07 1.92E+07 33Ce-141 1.37t+07 1.37t+07 1.37t+07 1.37tt07 1.371+07 1.37t+07 1.37t+07 34Ce-144 6.961+07 6.96I+07 6.96t+07 6.961+07 6.96I+07 6.96t+07 6.96t+07 i
a eu a e Per equa on 2.3-D ISSUI3 284
l BV-1and2ODCM l
l Table 2.3-7 ,
~
RVALUISFORBIAVIRVALLIfS1TI (egseter-ares /yrperuC1/sec) l Pathway: Vegetation AgeGroup: Adult i Huclide Bone Liver f. Body Thyrold lidney Lung GI-LL1 1H-3 0.00t+00 2.261+03 2.26t+03 2.26I+03 2.26I+03 2.26t+03 2.26I+03 2P-32 1.40It09 8.74I+07 5.431+07 0.00t+00 0.00l+00 0.00E+00 1.581+08 3Cr-51 0.00l+00 0.00l+00 4.64I+04 2.78144 1.02I+04 6.16t+04 1.17t+07
- 4Mn-54 0.00l+00 3.13t+08 5.97I+07 0.00!+00 9.311+07 0.00l+00 9.598+08 5Fe-59 1.26I+08 2.96I+08 1.148+08 0.00l+00 0.00E+00 8.288+07 9.88t+08 6Co-57 0.00l+00 1.17t+07 1.95147 0.00t do 0.00I 40 0.00E+00 2.97I+08 7Co-58 0.00l+00 3.071+07 6.898+07 0.00l+00 0.00l+00 0.00E+00 6.23E+08 800-60 0.00l+00 1.67t+08 3.69I+08 0.00l+00 0.00l+00 0.00t+00 3.14t+09 9Zn-65 3.171+08 1.01t+09 4.56I+08 0.00I+00 6.751+08 0.00I40 6.36t+08 l 10Rb-86 0.00l+00 2.191+08 1.02E+08 0.00I40 0.00l+00 0.00t+00 4.33t+07 l 11St-89 9.97t+09 0.00t+00 2.86I+08 0.00B+00 0.00It00 0.00t+00 1.60!+09 l
12St-90 6.05E+11 0.00l+00 1.4BI+11 0.00l+00 0.00l+00 0.00l+00 1.75t+10 13 ' il 5.11146 0.00!+00 1.37I+05 0.00It00 0.00l+00 0.00l+00 2.81E+09
(") - 14Zr-95 1.17t+06 3.77t+05 2.55I+05 0.00l+00 5.91I+05 0.00td0 1.19td9, V 15Nb-95 1.421+05 7.92E+04 4.26t+04 0.00l+00 7.83t+04 0.00I40 4.81E+08 16Ib-97 2.16I-06 5.461-07 1.998-07 0.00l+00 6.371-07 0.00E+00 2.02I-03 17Ho-99 0.00I40 6.15I+06 1.17It06 0.00l+00 1.39t+07 0.00l+00 1.43t+07 16fc-99: 3.10l+00 8.77I40 1.12E+02 0.00It00 1.33t+02 4.30l+00 5.191+03 l 19Ra-133 4.77td6 0.00t+00 2.06t+06 0.00l+00 1.82t+07 0.00l+00 5.57I+08 20In-106 1.93E+08 0.00t+00 2.44t+07 0.00It00 3.72E+08 0.00l+00 1.25t+10 21Ag-110s 1.05I+07 9.75t+06 5.79t+06 0.00It00 1.92t+07- 0.00l+00 3.98I+09 22Sh-124 1.04E+0B 1.96t+06 4.111+07 2.51t+05 0.00l+00 8.07167 2.94149 23Sh125 1.37t+08 1.53E+06 3.25t+07 1.39t+05 0.00Id0 1.05t+08 150E+09 24fe-127: 3.49t+08 1.25t+08 4.26t+07 8.92It07 1.42I+09 0.00t+00 1.17I:09 25fe-129a 2.51148 9.38t+07 3.981+07 8.64I+07 1.05t+09 0.00l+00 1.27I+09 26I-131 8.08I+07 1.16t+08 6.62t+07 3.79t+10 1.98I+08 0.00l+00 3.05t+07
- 271-133 2.09I46 3.63E+06 1.111+06 5.33I+08 6.33I+06 0.00l+00 3.26t+06 28Cs-134 4.67I+09 1.11t+10 9.081+09 0.00l+00 3.59t+09 1.19t+09 1.94t+08 l 29Ce-136 4.271+07 1.69t+08 1.211+08 0.00l+00 9.385+07 1.29t+07 1.91I47 30Cs-137 6.36I409 8.70!+09 5.70l+09 0.00l+00 2.95t+09 9.81t+08 1.68I+08 I
! 31Ba-140 1.298+08 1.611+05 8.42t+06 0.00t+00 5.49t+04 9.24t+04 2.65E+08 l 32La-140 1.981+03 9.97I+02 2.63t+02 0.00l+00 0.00l+00 0.00I40 7.32I+07 33Ce-141 1.971+05 1.33t+05 1.511t04 0.00l+00 6.19844 0.00l+00 5.10l+08 34Ce-144 3.29t+07 1.38I+07 1.77t+06 0.00l+00 8.16t+06 0.00t+00 1.111+10
. Allnuclides(exceptH-3)calculatedperODCMegnation2.3-26 H-3calculatedperODCMegnation2.3-29 1SSUIJ 2-85 l
BV-1and2ODCM fable 2.3-8 RVALDISFORBIAVIHVALLEYSlf!
(sqseter-ares /yrperUCl/sec)
Patbvar : Vegetation Age Group : Teen Nuclide Bone Liver f. Body Thyroid Ildney Lung GI-LLI 1H-3 0.00!+00 2.59h03 2.59b03 2.59bO3 2.59b03 2.59t+03 2.59b03 2P-32 1.61b09 9.98bO7 6.24bO7 0.00!+00 0.00b00 0.00!+00 1.35E+08 3Cr-51 0.00!+00 0.00D00 6.17t+04 3.43b04 1.35E+04 8.81b04 1.04bO7 4Mn-54 0.00b00 4.54b08 9.01E+07 0.00b00 1.36bO8 0.00b00 9.32D06 5Fe-59 1.79bO8 4.19t+08 1.62bO8 0.00b00 0.00D00 1.32bO8 9.90bO8 6Co-57 0.00b00 1.79b07 3.00bO7 0.00b00 0.00b00 0.00!+00 3.33E+08 7 Co-58 0.00b00 4.36bO7 1.00bO8 0.00b00 0.00D00 0.00b00 6.011+08 8Co-60 0.00b00 2.49b08 5.60bO8 0.MI+00 0.00!+00 0.00b00 3.24b09 9Zn-65 4.24bO8 1.47b09 6.87bO8 0.00h00 9.42t+08 0.00bO3 6.23b08 10Rb-86 0.00b00 2.74bO8 1.29b08 0.00b00 0.00b00 0.00b00 4.05bO7 11St-89 1.51b10 0.00D00 4.34 BOB 0.00b00 0.00b00 0.00D00 1.80D09 12Sr-90 7.51b11 0.00D00 1.85b11 0.00D00 0.00D00 0.00b00 2.11b10 13T-91 7.84b06 0.00b00 2.10b05 0.00b00 0.00b00 0.00b00 3.21b09 14Zr-95 1.72b06 5.43b05 3.74b05 0.00D00 7.98b05 0.00b00 1.25b09 15Hb-95 1.9?b05 1.07b05 5.87b04 0.00b00 1.03b05 0.00b00 4.56bO8 16Hb-97 2.001-06 4.971-07 1.811-07 0.00b00 5.811-07 0.00D00 1.191-02 17Mo-99 0.00b00 5.65b06 1.08b06 0.00b00 1.29b07 0.00!+00 1.0lbO7 18fe-99: 2.74b00 7.64b00 9.90b01.0.00b00 1.14bO2 4.24b00 5.02bO3 19Ru-103 6.82b06 0.00b00 2.52b06 0.00b00 2.41t+07 0.00b00 5.70 BOB 20Ro-106 2.38bO8 0.00b00 3.90bO7 0.00b00 5.97bO8 0.00b00 1.48b10 21Ag-110s 1.52bO7 1.43E+07 8.72b06 0.00b00 2.74bO7 0.00D00 4.03b09 22Sb-124 1.5(bO8 2.84b06 6.02bO7 3.50b05 0.00b00 1.35bO8 3.11b09 23Sb-125 2.14 BOB 2.34b06 5.0lbO7 2.05b05 0.00b00 1.88t+08 1.67b09 24fe-127s 5.52bO8 1.96D08 6.56bO7 1.31 BOB 2.24b09 0.00b00 1.37b09 25fe-129 3.62 BOB 1.34bO8 5.73bO7 1.17bO8 1.51bo9 0.00b00 1.36b09 26 E131 7.69b07 1.08bO8 5.78bO7 3.14b10 1.85bO8 3.00b00 2.13bO7 27 E133 1.94b06 3.29h06 1.00b06 4.59b08 5.77b06 6.90FC 2.49b06 28Cs-134 7.10b09 1.67b10 7.75b09 0.00b00 5.31b09 2.03b09 2.08bO8 29Cs-136 4.38bO7 1.72bO8 1.16bO8 0.00b00 9.37bO7 1.4BbO7 1.39bO7 30Cs-137 1.0lb10 1.35b10 4.69b09 0.00b00 4.59b09 1.78b09 1.92bO8 31Ba-140 1.38 BOB 1.69b05 8.90D06 0.00b00 5.74bo4 1.14b05 2.13 BOB 32La-140 1.81bO3 8.88bO2 2.36bO2 0.00b00 0.00b00 0.00b00 5.10bO7 33Ce-141 2.83b05 1.89b05 2.17b04 0.00b00 8.90b04 0.00b00 5.41bO8 l 34Ce-144 5.27bO7 2.18bO7 2.83b06 0.00b00 1.30bO7 0.00b00 1.33b10 All nuclides (except H-3) calculated per ODCM equation 2.3-26
, 6-3calculatedperODCMequation2.3-29 l
ISSUI3 2-86
BV-1and2ODCH fable 2.3-9 RVALDISFORBIAVIIVALLIYSlft (sqseter-area /yrperuC1/see)
Patbaar: Vegetation AgeGroup: Child Nuclide Bone Liver f. Body Ibyroid Eidney Lung GI-LL1 1H-3 0.00X+00 4.011+03 4.011+03 4.011+03 4.01E+03 4.01D03 4.011+03 2P-32 3.37I+09 1.58t+08 1.30E+08 0.00l+00 0.00t+00 0.00l+00 9.32E+07 3Cr51 0.00l+00 0.00l+00 1.17t+05 6.50l+04 1.78t+04 1.19t+05 6.21E+06 4Hn-54 0.00l+00 6.65E+08 1.77I+0B 0.00l+00 1.86t+08 0.00l+00 5.58t+08 5Fe-59 3.988+08 6.43t+08 3.20t+08 0.00l+00 0.00t+00 1.878+08 6.70I+08 6Co-57 0.00!+00 2.99I+07 6.04X+07 0.00l+00 0.00l+00 0.00X+00 2.45I+08 7Co-58 0.00l+00 6.44t+07 1.97I+08 0.00t+00 0.00t+00 0.00I+00 3.76I+08 8Co-60 0.00l+00 3.78t+08 1.12t+09 0.00It00 0.00l+00 0.00I40 2.10l+09 9Zn-65 8.13t+08 2.17td9 1.351+09 0.00I40 1.36I+09 0.00l+00 3.80l+08 10lb-86 0.00l+00 4.52t+08 2.78t+08 0.00t+00 0.00I40 0.00I00 2.91I+07 11Sr-89 3.60l+10 0.00I40 1.03I+09 0.00t+00 0.00It00 0.00l+00 1.39t+09 12St-90 1.24t+12 0.00l+00 3.15I+11 0.00l+00 0.00l+00 0.00l+00 1.67t+10 13T-91 1.86t+07 0.00t+00 4.99t+05 0.00l+00 0.00t+00 0.00I40 '2.48I+09 14Zr-95 3.86I+06 8.48t+05 7.55t+05 0.00I40 1.211+06 0.00l+00 8.85I+08
\ 15Nb-95 4.111+A5 1.60l+05 1.14I+05 0.00l+00 1.50t+05 0.00I40 2.96t+08 16 lb-97 3.651-06 6.59I-07 3.08I-07 0.00l+00 7.31I-07 0.00l+00 2.03I-01 17Mo-99 0.00t+00 7.711+06 1.911+06 0.00I40 1.65847 0.00t+00 6.38t+06 18fc-99 4.711+00 9.24It00 1.53t42 0.00I40 1.34t+02 4.69t+00 5.26t+03 19lu-103 1.53t+07 0.00l+00 5.90l+06 0.00t+00 .3.86t+07 0.00l+00 3.97t+08 20lu-106 7.45I 4 8 0.00ft00 9.30I47 0.00l+00 1.01149 0.00l+00 1.16I+10 21Ag-110s 3.21t+07 2.171+07 1.73t+07 0.00I00 4.04I+07 0.00E+00 2.58I+09 22Sb-124 3.52t+08 4.57t+06 1.23I+08 7.77t+05 0.00I00 1.95I+08 2.20I+09 23Sb-125 4.99t+08 3.85146 1.05I+08 4.63t+05 0.00t+00 2.78I+08 1.19I+09 24fe-127s 1.32B49 3.561+08 1.57t+08 3.16I06 3.77t+09 0.00l+00 1.071+09 25fe-129s 6.41t+08 2.35t+08 1.31t+0B 2.71t+08 2.47I49 0.00I 4 0 1.03I+09 26I-131 1.43t+08 1.44f+08 8.17t+07 4.76t+10 2.36t+08 0.00t+00 1.281+07 27I-133 3.53I+06 4.37td6 1.65I+06 8.12t+08 7.281+06 0.00l+00 1.76t+06 28Cs-134 1.60l+10 2.63t+10 5.55t+09 0.00l+00 8.15t+09 2.93I49 1.42t+08 29Cs-136 8.24f+07 2.27I+08 1.47848 0.00E+00 11X+08 1.80t+07 7.96t+06 30Cs-137 2.39I+10 2.298+10 3.38t+09 0.00t+00 7.46t+09 2.68I+09 1.43t+08 ,
3tBa-140 2.77I+08 2.42Id7 1.62X+07 0.00I40 7.89144 1.45t+05 1.40l+08 32La-140 3.25I+03 1.13Id3 3.83t+02 0.00I40 0.00l+00 0.00It00 3.16t+07 33Cc-141 6.568+05 3.271+05 4.861+05 0.00I40 1.43I+05 0.00I40 4.08t+08 34Ce-144 1.27I+08 3.981+07 6.781+06 0.00l+00 2.21I+07 0.00I00 1.04I+10 O Allnuclides(exceptH-3)calculatedperODCHequation2.3-26 H-3calculatedperODCHequation2.3-29 ISSUI3 2-87 i
I
BV-1 and 2 ODCM fable 2.3-10 ,
RVALUISFORBIAVIRVALLifSITI '
(sqseter-ares /yrperuC1/see)
Fatbvay: Meat AgeGroup: Adult Nueilde Bone Line f. Body Thyroid Ildney Lung GI-LLI l
1H-3 0.00E+00 3.25t+02 3.25Et02 3.25E+02 3.25E+02 3.25I+02 5.25E+02 2P-32 3.95t+09 2.461+08 1.53E+08 0.00!+00 0.00E+00 0.00!+00 4.44E+08 1 3Cr-51 0.00E+00 0.00!+00 5.861+03 3.50!+03 1.29t+03 7.78t+03 1.47t+06 I 4Mn-54 0.00l+00 6.491+06 1.24E+06 0.00!+00 1.93t+06 0.00E+00 1.99E+07 l 5 Fe-59 2.14t+08 5.04E+08 1.93E+08 0.00l+00 0.00!+00 1.41E+08 1.68t+09 1
6Co-57 0.00!+00 4.011+06 6.66I+06 0.00t+00 0.00l+00 0.00l+00 1.02E+08 ;
700-58 0.00!+00 1.42I+07 3.18t+07 0.00E+00 0 wit 00 0.00!+00 2.87I+0B !
8Co-60 0.00t+00 5.12It07 1.13E+08 0.00t+00 0.00!+00 0.00l+00 9.61t+08 9Zn-65 2.54t+08 8.09t+08 3.66t+08 0.00l+00 5.41E+08 0.00E+00 5.10l+08 ,
10Rb-86 0.00t+00 4.11E+08 1.92It08 0.00E+00 0.00!+00 0.00E+00 8.11t+07 l 11Sr-89 2.41E+08 0.00!+00 6.921+06 0.00!+00 0.00!t00 0.00!+00 3.87I+07 12Sr-90 8.41E+09 0.00!+00 2.061+09 0.00l+00 0.00l+00 0.00!+00 2.43t+08 13T-91 8.94t+05 0.00!+00 2.39I+04 0.00E+00 0.00!+00 0.00E+00 4.92E+08 14Zr-95 1.471+06 4.71E+05 3.19I+05 0.00t+00 7.39I+05 0.00t+00 1.49t+09 15Nb-95 1.891+06 1.05I+06 5.64E+05 0.00t+00 1.04t+06 0.00l+00 6.37t+09 16Ib-97 testtttttttttttttttttttttttttttts 0.00t+00 settstststs 0.00t+00 settsstetst 17No-99 0.00!+00 8.51E+04 1.62t+04 0.00E+00 1.93t+05 0.00!+00 1.97t+05 18fc-99: 3.83I-21 1.061-20 1.38t-19 0.00l+00 1.641-19 5.301-21 6.401-18 19Ru-103 8.578+07 0.00!+00 3.69E+07 0.00!+00 3.27t+08 0.00t+00 1.00E+10 20Ru-106 1.971+09 0.00E+00 2.49t+08 0.00!+00 3.80l+09 0.00l+00 1.271+11 21Ag-110s 4.77tt06 4.41It06 2.62t+06 0.00E+00 8.67I+06 0.00t+00 1.80!+09 22Sb-124 0.00!+00 0.00t+00 0.00l+00 0.00!+00 0.00!+00 0.00t+00 0.00E+00 ,
23Sb-125 0.00!+00 0.00t+00 0.00!+00 0.00!t00 0.00!+00 0.00t+00 0.00!+00 '
24fe-127s 8.38t+08 3.00l+08 1.02It08 2.14t+08 3.40t+09 0.00!+00 2.811t09 25fe-129s 9.33t+08 3.48It08 1.48t+08 3.21E+08 3.89t+09 0.00!+00 4.70E+09 26I-131 9.13E+06 1.31E+07 7.481+06 4.28t+09 2.24It07 0.00!+00 3.45t+06 27I-133 3.128-01 5.42I-01 1.651-01 7.96!+01 9.461-01 0.00!+00 4.87I-01 28Cs-134 4.53E+08 1.08t+09 8.81t+08 0.00!+00 3.49t+08 1.161+08 1.89I+07 29Cs-136 1.021+07 4.04t+07 2.91E+07 0.00t+00 2.25t+07 3.088+06 4.59t+06 30Cs-137 5.90t+08 8.06I+08 5.28t+08 0.00!+00 2.74E+08 9.10t+07 1.56t+07 31Ba-140 2.44E+07 3.06I+04 1.60t+06 0.00!+00 1.04I+04 1.75t+04 5.02It07 32La-140 3.1SI-02 1.591-02 4.211-03 0.00t+00 0.00t+00 0.00!+00 1.17t+03 33Ce-1(1 1.16t+04 7.83E+03 8.881+02 0.00t+00 3.64t+03 0.00t+00 2.991+07 34Ce-144 1.03t+06 4.32E+05 5.55E+04 0.00E+00 2.56I+05 0.00E+00 3.50!+08 allnuclides(exceptH-3)calculatedperODCMequation2.3-25 H-3 cales1ated per ODCX epation 2.3-30 '
ISSUE 3 2-88
4 BV-1 ar.d 2 ODCH g fable 2.3-11 5 4 RVALUISFORBIAVIHVALLEYSITI (egseter-ares /yrperuCi/see) ;
Patbvar: Meat AgeGroup: feen l
lluelide Bone Liver T. Body Thyroid tidney Lug ~ GI-LL1 1H-3 0.00!+00 1.94t+02 1.94E+02 1.94t+02 1.94t+02 1.94E+02 1.94E+02 2P-32 3.34t+09 2.07t+08 1.291+08 0.00t+00 0.00t+00 0.00t+00 2.80t+08 3Cr-51 0.00t+00 0.00l+00 4.69t+03 2.60!+03 1.03t+03 6.69t+03 7.88t+05 l 4Mn-54 0.00!+00 4.95tt06 9.81t+05 0.00t+00 1.481+06 0.00!+00 1.01t+07 5 Fe-59 1.71t+08 4.00l+08 1.54k+08 0.00t+00 0.00!+00 1.26t+08 9.45E+08 6Cc-57' O.00!+00 3.22t+06 5.40l+06 0.00l+00 0.00t+00 0.00t+00 6.01t+07 700-58 0.00!+00 1.09I+07 2.52t+07 0.00t+00 0.00t+00 0.00l+00 1.511+08 8Co-60 0.00l+00 3.971+07 8.95t+07 0.00t+00 0.00t+00 0.00t+00 5.17t+08 9Zn-65 1.79I+08 6.21E+08 2.90l+08 0.00E+00 3.97t+08 0.00t+00 2.63E+08 10lb-86 0.00t+00 3.43E+08 1.61E+08 0.00E+00 0.00l+00 0.00l+00 5.08t+07 11Sr-89 2.03E+08 0.00t+00 5.83E+06 0.00It00 0.00t+00 0.00t+00 2.42E+07 12Sr-90 5.44t+09 0.00t+00 1.34t+09 0.00t+00 0.00E+00 0.00l+00 1.53I+08 13Y-91 7.53t+05 0.00t+00 2.02t+04 0.00t+00 0.00t+00 0.00l+00 3.09t+08
/"' 14 Zr-95 1.18t+06 3.71t+05 2.55t+05 0.00t+00 5.45t+05 0.00l+00 8.56I+08
\ 15 lib-95 1.471+06 8.171+05 4.50E+05 0.00t+00 7.92t+05 0.00t+00 3.49t+09 16 lib-97 sssssssssssssssssssssssssssssssst 0.00t+00sssssssssst 0.00t+00sssssssssss 17No-99 0.00!+00 7.03t+04 1.34E+04 0.00l+00 1.611+05 0.00t+00 1.261+05 18fe-99n 3.041-21 8.481-21 1.10E-19 0.00l+00 1.26t-19 4.71I-21 5.57t-18 ,
19 In-103 6.98t+07 0.00!+00 2.981+07 0.00!+00 2.46t+08 0.00l+00 5.83t+09 l 20Ru-106 1.281+09 0.00!+00 2.098+08 0.00t+00 3.19t+09 0.00t+00 7.94E+10 21Ag-110s 3.61t+06 3.421i06 2.081+06 0.00I+00 6.521+06 0.00t+00 9.60t+08 l 22Sb-124 0.00!+00 0.00t+00 0.00l+00 0.00t+00 0.00!+00 0.00E+00 0.00t+00 l 23Sb-125 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0,00!+00 0,00t+00 0.00t+00 24fe-127s 7.07!+08 2.51E+08 8.41E+07 1.68t+08 2.87t+09 0.00t+00 1.76I+09 25fe-129s 7.821+08 2.90l+08 1.24I+08 2.52I+0B 3.27I+09 0.00t+00 2.93t+09 26I-131 7.59t+06 1.06t+07 5.711+06 3.10E+09 1.83t+07 0.00!+00 2.10t+06 27I-133 2.611-01 4.421-01 1.351-01 6.17t+01 7.758-01 0.00t+00 3.34t-01 28Cs-134 3.60t+08 8.48t+08 3.93I+08 0.00l+00 2.898+08 1.03t+08 1.05t+07 29Cs-136 7.988+06 3.14t+07 2.11E+07 0.00t+00 1.71t+07 2.69t+06 2.53t+06 30Cs-137 4.90!+08 6.51t+08 2.27I+08 0.00It00 2.22t+08 8.611+07 9.27I+06 31Ba-140 2.02t+07 2.47t+04 1.30l+06 0.00t+00 8.38t+03 1.661+04 3.11t+07 32La-140 2.601-02 1.281-02 3.40I-03 0.00l+00 0.00t+00 0.00l+00 7.33t+02 33Ce-141 9.72t+03 6.49t+03 7.461+02 0.00l+00 3.06t+03 0.00t+00 1.86t+07 34Ce-144 8.72t+05 3.61t+05 4.68t+04 0.00t+00 2.15t+05 0.00t+00 2.19t+08 Allnuclides(exceptH-3)calculatedperODCHequation2.3-25 k H-3calculatedperODCMequation2.3-30 ISSUI3 2-89
BV-1and3ODCM I l
fable 2.3-12 RVALDISFORBEATERVALLifS1ft (sqseter-stes/yrperuCl/see) l Pathway: Heat AgeGroup: Child Nuclide Bone Liver f. Body Thyroid lidney Lung GI-LLI 1H-3 0.00b00 2.34bO2 2.34bO2 2.34bO2 2.34bO2 2.34bO2 2.34bO2 2P-32 6.29b09 2.94t+08 2.43bO8 0.00b00 0.00b00 0.00b00 1.74 BOB 3Cr-51 0.00E+00 0.00b00 7.31E+03 4.06t+03 1.11bO3 7.41bO3 3.88b05 4Mn-54 0.00b00 5.66b06 1.51b06 0.00b00 1.59b06 0.00b00 4.75b06 5Fe-59 3.04E+08 4.91bO8 2.45bO8 0.00D00 0.00b00 1.42 BOB 5.12bO8 6Co-57 0.00b00 4.21h06 8.52b06 0.00l+00 0.00b00 0.00b00 3.45bO7 700-58 0.00h00 1.2EbO7 3.91bO7 0.00b00 0.00b00 0.00h00 7.45bO7 8Co-60 0.00E+00 4.72bO7 1.39b08 0.00b00 0.00b00 0.00h00 2.61bO8 9Zn-65 2.68bO8 7.15 BOB 4.44 BOB 0.00b00 4.50bO8 0.00E+00 1.25bO8 10Rb-86 0.00h00 4.87bO8 2.99b08 0.00E+00 0.00D00 0.00b00 3.13bO7 11Sr-89 3.85bO8 0.00b00 1.10bO7 0.00b00 0.00b00 0.00b00 1.49b07 12St-90 7.03b09 0.00b00 1.78b09 0.00D00 0.00D00 0.00b00 9.47bO7 13f-91 1.42b06 0.00b00 3.81b04 0.00b00 0.00000 0.00D00 1.90bO8 14Zr-95 2.09b06 4.59b05 4.09b05 0.00D00 6.57b05 0.00 BOO 4.79bO8 15Hb-95 2.54b06 9.90D05 7.07b05 0.00b00 9.30D05 0.00b00 1.83b09 4
16gb-97' sssssssssssssssssssssssssssssssss 0.00h 00 sssssssssss 0.00 b 00 sssssssssss 17Mo-99 0.00b00 9.79b04 2.42b04 0.00b00 2.09b05 0.00b00 8.09004 18fe-99: 5.33I-21 1.05b20 1.731-19 0.00b00 1.521-19 5.31b21 5.95I-18 19Ra-103 1.26bO8 0.00h00 4.85bO7 0.00b00 3.18 BOB 0.00b00 3.26h09 20Rn-106 3.12b09 0.00b00 3.89b08 0.00b00 4.21b09 0.00D00 4.85b10 21Ag-110e 5.99b06 4.04b06 3.23b06 0.00b00 7.53b06 0.00D00 4.81bO8 :
22Sb-124 0.00b00 0.00b00 0.00b00 0.00D00 0.00D00 0.00b00 0.00b00 '
23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00h00 0.00b00 0.00b00 24fe-127s 1.33b09 3.59bO8 1.58bO8 3.19b08 '3.80D09 0.00D00 1.08b09 25fe-129s 1.47b09 4.11 BOB 2.29bO8 4.75bO8 4.33b09 0.00E+00 1.80b09 26I-131 1.41bO7 1.42bO7 8.04b06 4.68D09 2.32b07 0.00D00 1.26h06 27I-133 4.841-01 5.991-01 2.27I-01 1.11bO2 9.981-01 0.00b00 2.41F01 28Cs-134 6.35bO8 1.04b09 2.20bO8 0.00b00 3.23bO8 1.16bO8 5.62D06 29Cs-136 1.38bO7 3.78007 2.45bO7 0.00b00 2.01bO7 3.00b06 1.33D06 30Cs-137 9.02bO8 8.63bO8 1.27bO8 0.00b00 2.81bO8 1.01bO8 5.40h06 31Ba-140 3.72bO7 3.26b06 2.17b06 0.00D00 1.06b04 1.94b04 1.89bO7 32La-140 4.76bO2 1.66F02 5.611-03 0.00b00 0.00b00 0.00b00 4.63b02 33Ce-141 1.83b04 9.13bO3 1.36b04 0.00b00 4.00bO3 0.00b00 1.14bO7 34Ce-144 1.64b06 5.15b05 8.77b04 0.00b00 2.85b05 0.00D00 1.34bO8 Allnuclides(exceptH-3)calentatedperODCMequation2.3-25 H-3calenlatedperODCMequation2.3-30 l
2-90
l i
BV-1and2ODCM fable 2.3-13 O IVALUISFOIBIAVIIVALLI7Slft (egseter-stes/yrpernC1/see)
Pathver:CowHilk AgeGroup: Adult Nuclid'e. . Bone Liver 7. Body ; Thyroid tidney Lug GI-LLI 1H-3L 0.00l+00 7.63t+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63I 4 2 2P-32 1.45t+10 9.015+08 5.60l+08 0.00l+00 0.00l+00 0.00l+00 1.63E+09 3Cr-51 0.MI+00 0.MI+00 2.38t+04 1.42E+04 5.24I+03 3.15I44 5.965+06 :
4Mn-54 0.00I 00 5.95td6 1.13t+06 ' O.00t+00 1.775+06 0.00I 40 1.82B+07 5Fe 2.40l+07 5.63t+07 2.16I+07 0.M I do 0.00I40 1.575+07. 1.885 4 6 6Co-57 0.00l+00 9.10ld5 1.51It06 0.00I40 0.00I40 0.00l+00 2.31E+07 7 Co-58' '0.00840 3.67146 8.22I+06 0.00l+00 0.00I40 0.00l+00 .7.438 47 8 Co-60 0.00E+00 1.12t+07 2.46t+07 ' O.00l+00 0.M I+00 0.00I 40 2.10l+08
. '9In-65 9.80148' 3.12t+09 .1.41E+09 ' O.00l+00 2.09I49 0.00l+00 1.96b09 l 1
10 lb 0.00l+00 2.195+09 1.02E+09 0.00l+M -0.00B+00 0.00l+00 '4.328 48 11St-89 1.16I49 0.00l+00 3.33I47 0.00l+00 0.00l+00 0.M Ido 1.865 48 12St-90 3.16t+10 0.00l+00 7.76I+09 0.00I 4 0 0.00140 0.H I+00. 9.14I 48 137 6.785+03 ' O.M I+00 1.81t+02 0.00B+00 0.00l+00 0.00l+00 3.73I+M 7.40l+02;.2.37I42 1.61142 0.00l+00 3.72E+02 0.Mido 7.52145 O 14Zr-95 15Mb-95 6.77t+04 3.77I+04 2.038+04. 0.00l+M 3.72144 0.001 40. 2.295+08 3
16Ib-97 2.811-12 7.118-13 2.608-13 ~ 0.00l+00. 8.305-13 0.00I 4 0 2.628-09 I
17No-99. 0.00l+00 2.11I47 4.01t+06 C.M I+00 4.778+07 0.00l+00' 4.88t+07 18fe-99: 2.83840 7.99540 1.02I d2. 0.H I+00 1.21E+02. 3.91t+ M 4.73Id3 .i U
19In-103 8.291+02 0.00l+00 3.57I+02' 0.00I 40 3.16I43 0.00l+00. 9.68144~
20Bo-106~ 1.43I+04 0.00l+00 -1.81I 45 0.00E+00 2.775+04. 0.MI 40 9.27I45 i
'21'As-110s 4.168+07 3.84t+07 2.28I47. 0.00l+00 7.568d7 0.00l+ M . 1.57I+10
-22 Sb-124 0.M I+00' 0.00I 40 .0.00I40. 0.00I 40 0.00l+00 0.00l+M 0.00l+M 23Sb-125 'O.00l+00 - 0.00l+00 0.00It00 0.00I40. 0.00l+00: 0.00840 0.00l+00 24fe-127s- 3.44I47 .1.23E+07 4.19I46 8.79146 1.40548 0.HI+# 1.15E+08-25fe-129s 4.95t+07 1.85t+07 7.84E+06 .1.70547 2.07Id8 0.00B+00 2.491+06' 261-131 2.52t+08 3.60I 4 8 2.068+08 1.18I+11 .6.171+08 0.MI+00 9.50147 1 27I-133 3.29846 5.72I46' 1.75td6 8.41I 4 8 9.99846 0.MI+00 5.14I46-28Cs-134 3.89t+09 9.27t+09 7.588+09. 0.00l+00 3.00149 9.96I 48 -1.62X+08 29Cs-136 2.23I 4 8 8.82E+08. 8.35t+08 0.00I40 4.91I48 6.73I 47 1.00l+08
.30Cs-137 4.99I49 6.82t+09 4.47t+09-- 0.00l+M 2.32B+09 7.70I 4 8 1.32I 4 8 31Ba440 2.28I+07 - 2.87844 1.49546 0.00I40 9.74I43 1.64X+04 4.70547 32La-140 3.84t+00 1.93I40 5.11I-01 0.00l+00 ' 0.00I40. 0.00I40 1.42545 33Ce-141 3.998+03 2.70l+03 3.068+02 0.00l+00 1.25t+03 0.00l+00 1.08t+07' 34Ce-144 2.54t+05 1.06td5 1.36t+04 0.00l+M 6.29I44 0.00I40 B.58147 O Allnuclides(exceptI3)calentatedper0005egnation2.3-24 I-3calenlatedperODCMegnation2.3-28 ISSUI3-2-91'
BV-1 and 2 ODCH fable 2.3-14 RVALUISFORBIAVERVALLITSITI (sgseter-stes/yrperuC1/see)
Pathway:CowHill AgeGroup: feen helide Bone Liver f. Body Thyroid tidney Lung GI-LLI 1H-3 0.00!+00 9.94t+02 9.941+02 9.94t+02 9.94E+02 9.94t+02 9.94E+02 2P-32 2.67t+10 1.661+09 1.04E+09 0.00!+00 0.00!+00 0.00!+00 2.25E+09 3Cr-51 0.00!+00 0.00!+00 4.15E+04 2.31t+04 9.10!+03 5.93t+04 6.97t+06 4Hn-54 0.00!+00 9.91E+06 1.961+06 0.00!+00 2.95I+06 0.00E+00 2.03E+07 5Fe-59 4.18t+07 9.76I+07 3.778t07 0.00!+00 0.00E+00 3.08E+07 2.31E+08 6Co-57 0.00!+00 1.60t+06 2.681+06 0.00E+00 0.00H+00 0.00t+00 2.98t+07 7Co-58 0.00!+00 6.17It06 1.42E+07 0.00!+00 0.00E+00 0.00t+00 8.51t+07 800-60 0.00E+00 1.89t+07 4.261+07 0.00!+00 0.00E+00 0.00t+00 2.46t+08 9Zn-65 1.51t+09 5.23t+09 2.44I+09 0.00!+00 3.34E+09 0.00!+00 2.211+09 10lb-86 0.00E+00 3.991+09 1.871+09 0.00l+00 0.00E+00 0.00E+00 5.911+08 11St-89 2.14E+09 0.00E+00 8.12t+07 0.00E+00 0.00E+00 0.00!+00 2.55E+08 12St-90 4.47t+10 0.00!+00 -1.10E+10 0.00t+00 0.00!+00 0.00E+00 1.25E+09 13T-91 1.25t+04 0.00t+00 3.35E+02 0.00!+00 0.00!+00 0.00l+00 5.11t+06 14Zr-95 1.29I+03 4.08I+02 2.81It02 0.00!+00 6.00!+02 0.00!+00 9.42E+05 15Xb-95 1.161+05 6.41It04 3.53E+04 0.00!+00 6.21R+04 0.00!+00 2.74E+08 16lb-97 5.13I-12 1.27E-12 4.651-13 0.00!+00 1.49I-12 0.00!+00 3.04I-08 17Ho-99 0.00t+00 3.80I+07 7.25t+06 0.00E+00 8.70E+07 0.00!+00 6.81E+07 18fe-99: 4.90I+00 1.371+01 1.77t+02 0.00E+00 2.04t+02 7.591+00 8.981+03 19 h-103 1.47t+03 0.00!+00 6.30E+02 0.00E+00 5.20!+03 0.00I+00 1.23E+05 20Ru-106 2.03E+04 0.00t+00 3.32It03 0.00l+00 5.08t+04 0.00l+00 1.26I+06 21Ag-110s 6.87t+07 6.50!+07 3.95t+07 0.00!+00 1.241+08 0.00!+00 1.83E+10 22Sb-124 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00t+00 0.00!+00 0.00l+00 23Sb-125 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.00E+00 0.00!+00 0.00E+00 24fe-127s 6.341+07 2.25E+07 7.54E+06 1.51E+07 2.571+08 0.00E+00 1.58t+08 25fe-129: 9.06t+07 3.36t+07 1.43E+07 2.92t+07 3.79E+08 0.00t+00 3.40l+08 26I-131 4.571+08 6.39t+08 3.43t+08 1.871+11 1.10E+09 0.00!+00 1.261+08 27I-133 6.01E+06 1.02I+07 3.111+06 1.42E+09 1.79t+07 0.00E+00 7.711+06 i 28Cs-134 6.76t+09 1.591+10 7.38I+09 0.00I+00 5.00!+09 1.93E+09 1.98t+08 29Cs-136 3.80t+0B 1.50!+09 1.01E+09 0.00!+00 8.15t+08 1.28I+08 1.20l+08 30Cs-137 9.05E+09 1.20!+10 4.191+09 0.00E+00 4.10I+09 1.591+09 1.71t+08 31Ba-140 4.12t+07 5.05E+04 2.65E+06 0.00!+00 1.71t+04 3.39t+04 6.35t+07 32La-140 6.891+00 3.39I+00 9.011-01 0.00E+00 0.00!+00 0.00!+00 1.94I+05 33Ce-141 7.32t+03 4.891+03 5.62t+02 0.00E+00 2.30!+03 0.00E+00 1.40E+07 34Ce-144 4.67t+05 1.93f+05 2.511+04 0.00!+00 1.15t+05 0.00!+00 1.17t+08 All nuclides (except H-3) calculated per ODCH equation 2.3-24 H-3calculatedperODCHequation2.3-28 ISSUI3 2-92
BV-1and2ODCM fable 2.3-15 R val #IS F0IIIATH VALLEY SITI L
! -(sqseter-ares /yrperuC1/sec)
Pathwar:CowMilk AgeGroup: Child-helide Bone Liver 7. Body Thyroid- tidner- Lans GI-LLI 1H-3 0.00l+00,'1.57I+03 1.57t+03 1.571+03: 1.57t+03 1.57I+03 1.57t+03 2P-32 6.598+10 3.095+09 .2.54I+09'- 0.00t+00 0.00I40 0.00t+00= 1.82t+09 l
3Cr-51 0.00l+00 0.00l+00. 8.46t+04 4.70l+04 1.28I44 8.58544 4.49t+06-4Mn 0.00l+00 1.48t+07 3.95I+06 0.00E+00 4.165+06 0.00t+00 1.24t+07 5Fe-59 9.70I 4 7 1.57t+08 ' 7.82B+07 - 0.00l+00 0.00I40 4.55I47 1.63E+08 l 6Co-57l 0.00l+00 2.73I+06' 5.52I+06 0.00I 40 0.H I+00 . 0.00B+00 2.24t+07 7Co-58 0.00t+00- 9.43E+06 2.895+07 0.00E+00 ' O 00l+00 0.00I40 5.50547 8Co-60 0.00E+00 '2.94E+07 8.67I+07 0.00l d0 0.00I40 0.M I40 1.63t+08 9Za-65 2.95E+09 - 7.875 49 4.898+09 0.00l+00 -4.96I 49 0.00t+00 1.38I+09 10Ib-86 -0.00l+00 7.40l+09 4.55E+09 0.00l+00. 0.H I+00 0.00540 -4.765+08 11Sr-89 5.295+09 0.00l+M 1.51E+08 0.00l+00 0.00I 4 0 0.00I40 2.05I 4 8.
l-12Sr-H- 7.55B+10- 0.00I40 1.91E+10 0.00t+00 . 0.00B+00 0.00I40 - L02E+09 '
13T-91 3.08t+04 0.00I40 8.24t+02 0.00I40 0.00l+00 0.00I40 4.11146
. 14Ir-95 3.00I 43- 6.60I4 2 5.885+02 0.00I40 9.45I42 '0.00l+00 6.89I 4 5
~y 15Nb 2.61E+05 1.02t+05- 7.26I 4 4 -0.00l+00 9.54E+04 0.00I40 1.88I 4 8 -
.16Bb-97 1.25I-11 2.25I-!1 1.05I 0.00l+00 2.50I-12 0.00I40 6.94I-07 17No-99 0.00I40 6.92t+07 1.715+07 0.00t+00 . 1.48I46 0.00I 40 5.721 47 18Yc-99s 1.12t+01= 2.20l+01 3.85I42 0.H I+00 3.20I42 1.12I41 1.25E+04 19In-103 3.495+03 - 0. M i d0 1.34t+03 0.00I40 . 8.78t+03 0.00l+M 9.01I44 I
L 20 h-106 6.498+04 0.00t+00; 8.10E+03 0.HI+00 ' 8.76544 0.00I40 1.01I46
- - 21As-110s. 1.49I 4 8 1.01148 8.05t+07 0.00l+00 1.87I+08 0.00E+M 1.20l+10 0.00I 40 0.00l+00 0.HI+00 0.00t+M 0.00l+00 0.00l+00 0.00I 40 22Sb-124 t
23Sb-125 0.00l+M 0.00l+M 0.00I 4 0 0.00ft00 0 HI+00 0.00l+00 0.00E+00 24fe-127s 1.56t+08 4.21I 47 1.868+07 3.74t+07 4.46I48 0.00l+00 1.27I48 25fe-129s 2.23I+08 6.24Id7 3.47I+07 -7.20t+07 6.568+08 0.00l+M 2.72t+08 L
l 26I-131 1.11E+09 1.11E+09 6.33I+08 3.685+11 1.83I+09 0.00I40 9.92E+07 L 27I-133 1.46t+07 1.81t+07 6.83t+06 3.36I49 3.01I47 0.00I40 7.28846 L 28Cs-134 1.56t+10 2.568+10 5.40l+09 0.00I 40 7.93I 4 9 2.85849 1.38548 29Cs-156 8.58I+06 2.368+09 1.53Id9 0.00I40 1.26I+09 1.875+08 8.29547 30Cs-137 2.18t+10 . 2.098+10 3.08I 49 0.00I 40 6.80l+09 2.45I49 1.31I46 31Ba-140 9.94I+07 8.71846 5.80l+06 0.00t+00 2.84t+04 ' 5.198+04 5.04I+07 I 32La-140 ' 1.65I 4 1 5.77I+00 1.94140 0.00I40 0.00I40 0.MI+00 1.61845 33Ce-141 1.80l+04 - 8.995+03 1.34t+04 0.00I40 3.94t+03 0.00l+M 1.12847 l 34Co-144 1.15t+06 3.61t+05 6.15I+04 0.00l+00 2.00l+05 0.00l+M 9.41147 o All ns11 des (except H-3) calculated per ODON egnation 2.3-24 H-3calenlatedper0D05 equation 2.3-28 ISSOE3 2-93
BV-1and2ODCH fable 2.3-16 EVALUISFORBRAVIRVALLIYS1f!
(sqseter-ares /yrperuCi/sec)
Pathway:CowHilk AgeGroup: infant Nuclide Bone Liver T. Body Thyroid tidney Lung GI-LLI 1H-3 0.00!+00 2.38D03 2.38bO3 2.38bO3 2.38bO3 2.38bO3 2.38bO3 2P-32 1.36t+11 7.99b09 5.27b09 0.00D00 0.00D00 0.00D00 1.84b09 3Cr-51 0.00b00 0.00b00 1.34b05 8.75b04 1.91b04 1.70b05 3.91b06 4Mn-54 0.00t+00 2.76bO7 6.25b06 0.00b00 6.11b06 0.00b00 1.01t+07 5Fe-59 1.81 BOB 3.16bO8 1.25bO8 0.00b00 0.00b00 9.35t+07 1.51E+08 6Co-57 0.00b00 6.36b06 1.03bO7 0.00b00 0.00b00 0.00!+00 2.17bO7 700-58 0.00b00 1.89h07 4.70bO7 0.00b00 0.00b00 0.00b00 4.70bO7 8Co-60. 0.00b00 6.00bO7 1.42bO8 0.00b00 0.00b00 0.00t+00 1.43b08 9Zn-65 3.97b09 1.36b10 6.27b09 0.00D00 6.60D09 0.00b00 1.15b10 10Rb-86 0.00 BOO 1.88b10 9.28b09 0.00bO0 0.00b00 0.00b00 4.81008 11Sr-89 1.0lb10 0.00t+00 2.89bO8 0.00 BOO 0.00b00 0.00b00 2.07bO8 12Sr-90 8.22t+10 0.00b00 2.09b10 0.00b00 0.00b00 0.00D00 1.03b09 13Y-91 5.79b04 0.00b00 1.5(b03 0.00D00 0.00b00 0.00b00 4.15b06 14Zr-95 5.33bO3 1.30bO3 9.22bO2 0.00b00 1.40bO3 0.00b00 6.47b05 15Nb-95 4.87b05 2.0lb05 1.16b05 0.00b00 1.44bo5 0.00D00 1.69b08 16Nb-97 2.631-11 5.621-12 2.03t-12 0.00b00 4.391-12 0.00b00 1.771-06 17 No-99 0.00b00 1.77bO8 3.45bO7 0.00b00 2.64bO8 0.00b00 5.83t+07 18fc-99: 2.34b01 4.82b01 6.21bO2 0.00h00 5.19bO2 2.52b01 1.40b04 19Ru-103 7.06bO3 0.00b00 2.36bO3 0.00b00 1.47b04 0.00D00 8.59b04 20Ru-106 1.34b05 0.00b00 1.67b04 0.00b00 1.5Bb05 0.00h00 1.01b06 21Ag-110s 2.75bO8 2.01b08 1.33bO8 0.00h00 2.88bO8 0.00b00 1.04b10 22Sb-124 0.00b00 0.00b00 0.00b00 0.00h00 0.00b00 0.00D00 0.00D00 23Sb-125 0.00b00 0.00 BOO 0.00b00 0.00h00 0.00 BOO 0.00b00 0.00 BOO 24fe-127 3.16 BOB 1.05bO8 3.83b07 9.14bO7 7.79b08 0.00b00 1.28bO8 25fe-129s 4.58bO8 1.57bO8 7.06bO7 1.76bOS 1.15b09 0.00b00 2.74bO8 26I-131 2.31b09 2.72b09 1.20b09 8.95b11 3.18h09 0.00b00 9.72bO7 27!-133 3.08bO7 4.49b07 1.31bO7 8.17b09 5.28bO7 0.00b00 7.60b06 28Cs-134 2.51h10 4.69b10 4.73b09 0.00 BOO 1.21b10 4.95b09 1.27 BOB 29Cs-136 1.68b09 4.93b09 1.84b09 0.00h00 1.97b09 4.02bO8 7.49b07 30Cs-137 3.48b10 4.07b10 2.89b09 0.00b00 1.09b10 4.43b09 1.27bO8 31Ba-140 2.05bO8 2.05b05 1.05bO7 0.00b00 4.86b04 1.26b05 5.02bO7 32La-14A 3.45b01 1.36b01 3.50D00 0.00D00 0.00h00 0.00b00 1.60D05 33Ce-141 3.57b04 2.18b04 2.57bO3 0.00b00 6.72bO3 0.00b00 1.13bO7 34Ce-144 1.65b06 6.75D05 9.25b04 0.00D00 2.73b05 0 Y D 00 9.47bO7 Allnuclides(exceptH-3)calculatedperODCHequation2.3-24 H-3calculatedperODCMequation2.3-28 1S50!3 2-94
._ __._..__.._. _. __..____._ _ _._ _ _ __=- _ _ _ _
BV-1and2ODCM fable 2.3-17 IVALUISFOIBIAVIIVALLIYSlft (sq seter-eres/fr per sci /sec) s Pathway:GoatMilk AgeGroup: Adult Nuclide Bone Liver T. Body Thyroid Eidner Lung GI-LLI 1H-3 0.00E+00 1.56t+03 1.56I+03 1.56I+03 1.56t+03 1.56I+03 1.56t+03 2P-32 1.74I+10 1.08t+09 6.72E+08 0.00l+00 0.00!+00 - 0.00I+00 1.96I+09 3Cr-51 0.00It00 0.00l+00 2.85t+03 ' 1.70t+03 6.285+02 3.78I+03 7.17I+05 4Mn-54 0.00I40 7.14I+05 1.36I45 0.00t+00 2.12I 45 - 0.H I+00 2.19tt06 5Fe-59 3.12t+05 7.32t+05 2.81I+05 0.00l+00 0.H I+00 '2.05t+05 2,44I46-
, 6Co-57 0.00l+00 --1.09t+05 1.82I+05. 0.00E+00. 0.00l+00 0.00t+00~ 2.77I46-
-7Co-58 0.00l+00 4.40l+05 9.86t+05 0.00l+00 0.00l+00 0.00E+H 8.91t+06 8Co-60 0.00I40 1.34I+06 2.968+06 0.00l+00 0.00I40 0.00l+00 2.52547 9In-65 1.18Ed8 3.74t+08 1.69t+08 0.0H+00 2.50l+08 0.00l+00 2.365+08 10Ib-86 0.00l+00 2.63t+08 1.22I+08 0.00l+00 0 HI+00 0.00l+00 5.188+07-11St 2.43E+09 0.00l+00 6.99t+07 0.00l+00 0.00E+00 0.00I40 3.91t+06 12St-90 6.64E+10 0.00t+00 1.63I+10 0.00I40 0.00l+H 0.00l+00 1.92Id9 13f-91 8.14I+02 0.00I40 2.18t+01: 0.00I40 0.00t+00 0.HI+00 4.48I 4 5 C 14Zr-95 8.87I+01 2.85I+01 1.93t+01' O.H I+00 4.47t+01. 0.H I+H 9.02E+04 15lb-95 8.13E+03 4.52E+03 2.43Id3 0.00t+00 4.47I+03 0.00l+00 2.74t+07-16Nb-97 -3.388-13 8.54I-14 3.12I-14 0.00It00 9.96I-14 0.00t+00 3.15I-10 17Ho-99 0.00l+00 2.53t+06 4.81t+05 0.HI+00 5.72I+06 0.00l+00 5.86t+06 18fc-99: 3.39I-01 9.59I-01 1.22I41 0.00l+00 1.46t+01 4.70I-01 5.675+02 19In-103 9.95t+01 0.HI+00 4.29t+01 0.HI+00 3.80l+02 0.00l+H 1.16544 20In-106 1.72t+03 ' O.H I+H 2.18t+02 0.00l+00 3.32t+03 0.00l+00 1.11145 21As110e 4.998+06 4.61I 4 6 2.74I+06 0.00l+H 9.07t+06 0.00l+00 1.88t+09 22Sb-124 0.00l+00 0.00I40 0.00t+00- 0.00l+00 0.00l+00 0.HI+00 0.HI+00 23Sb-125 0.00l+H 0.00I40 0.00I40 0.00t+00 0.00l+00 0.00l+00 0.HI+00 24fe-127a 4.13E+06 1.43I+06 5.03t+05 .1.05E+06- 1.685+07 0.HI+00 -1.38t+07 25fe-129s 5.94546 2.22866 9.41145 2.04E+06 2.488+07 0.00I00 2.99I47 26 I-131 3.02t+08 4.321 48 2.48I+08 1.42I+11 7.40l+08 0.00l+00 1.14Ed8 27I-133 3.95146 6.87t+06 2.095+06 1.01t+09 1.20I47 0.00t+00 6.17I46 28Cs-134 4.67148 1.11E+09 9.095+08 0.00l+H 3.60BH3 1.198+08 1.95t+07 29Cs-136 6.70l+08 2.65I 4 9 1.HI+09 0.HId0 1.47I+09 2.02E+08 3.01t+08 30Cs-137- 1.50l+10 2.0$I+10 1.34X+10 0.00l+00 6.95I+09 2.31t+09 3.93E+08 31Ba-140 2.74t+06 3.44E+03 1.79I+05' O.00l+00 1.17I43 1.971+03 5.64I46 32La-140 4.60I-01 2.32I-01 6.13I-02 0.00E+H 0.00l+00 0.00I40 1.70l+04 33Co-141 4.79t+02 3.24I+02 3.68I+01 0.00It00 1.51B+02 0.00l+H 1.24I+06 34Ce144 3.05t+04 1.27t+04 1.64E+03 0.00I40 7.55t+03 0.00l do 1.03t+07 Allnuclides(uceptH-3)calenintedperODCMognation2.3-24 H-3calenlatedperODCNegnation2.3-28 ISSUI3 2-95
BV-1and2OiCH fable 2.3-18 RVALUISFORBIAVIIVALLIISITI (sgseter-arsa/yrperuCl/sec)
Pathway:GoatMilk Age Group : feen Nuclide Bone Liver f. Body Thyroid Ildney Lung GI-LLI 1H-3 0.00!+00 2.03t+03 2.03t+03 2.03E+03 2.03t+03 2.03E+03 2.03E+03 2P-32 3.21X+10 1.99I+09 1.24I+09 0.00E+00 0.00!+00 0.00!+00 2.70!+09 3Cr-51 0.00!+00 0.00E+00 4.981+03 2.77t+03 1.09E+03 7.11t+03 8.37t+05 4Hn-54 0.00E+00 1.191+06 2.36t+05 0.00!+00 3.55t+05 0.00!+00 2.44t+06 5Fe-59 5.44E+05 1.27t+06 4.90l+05 0.00!+00 0.00E+00 4.00!+05 3.00E+06 6Co-57 0.00i9 1.92E+05 3.21E+05 0.00E+00 0.00t+00 0.00!+00 3.57t+06 7Co-58 0.00E+00 7.40!+05 1.711+06 0.00!+00 0.00E+00 0.00!+00 1.02E+07 800-60 0.00!+00 2.i7t+06 5.111+06 0.00E+00 0.00!+00 0.00!+00 2.96t+07
. 9Zn-65 1.81t+08 6.27td 2.93E+08 0.00!+00 4.01E+08 0.00!+00 2.661+08 10Rb-86 0.00!+00 4.79t+08 2.25E+08 0.00!+00 0.00l+00 0.00!+00 7.091+07 11Sr-89 4.49t+09 0.00E+00 1.291+08 0.00!+00 0.00!+00 0.00!+00 5.35E+08 12Sr-90 9.39t+10 0.00!+00 2.32I+10 0.00!+00 0.00t+00 0.00!+00 2.64t+09 13T-91 1.50!+03 0.00!+00 4.01E+01 0.00E+00 0.00!+00 0.00!+00 6.14It05 14Zr-95 1.55E+02 4.90l+01 3.371+01 0.00!+00 7.19t+01 0.00!+00 1.13t+05 15lb-95 1.391+04 7.691+03 4.23t+03 0.00!+00 7.45It03 0.00!+00 3.29t+07 16 lib-97 6.151-13 1.538-13 5.57I-14 0.00!+00 1.79I-13 0.00!+00 3.651-09 17Ho-99 0.00E+00 4.56t+06 8.70!+05 0.00!+00 1.04I+07 0.00!+00 8.17t+06 18fc-99: 5.881-01 1.64E+00 2.13E+01 . 0.00!+00 2.45E+01 9.111-01 1.08t+03 19lu-103 1.77I+02 0.00!+00 7.561+01 0.00!+00 6.24t+02 0.00l+00 1.4BI+04 20Ru-106 2.44t+03 0.00!+00 3.98I+02 0.00!+00 6.10l+03 0.00!+00 1.52t+05 21Ag-110s 8.2(I+06 7.80!+06 4.75Et06 0.00Et00 1.49t+07 0.00!+00 2.191+09 22Sb-124 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00!+00 23Sb-125 0.00!+00 0.00E+00 0.00!+00 0.00E+00 0.00!+00 0.00!+00 0.00!+00 24fe-127a 7.61It06 2.70It06 9.05I+05 1.81E+06 3.08tt07 0.00!+00 1.90E+07 25fe-129s 1.09t+07 4.03t+06 1.72E+06 3.51E+06 4.55Et07 0.00!+00 4.08t+07 26I-131 5.481+08 7.67t+08 4.12E+08 2.24E+11 1.32t+09 0.00!+00 1.52E+08 !
27I-133 7.21E+06 1.22t+07 3.73t+06 1.71t+09 2.15t+07 0.00!+00 9.261+06 j 28Cs-134 8.11E+08 1.911+09 8.86I+08 0.00t+00 6.07I+08 2.32I+08 2.381+07 '
29Cs-136 1.14E+09 4.49t+09 3.02E+09 0.00!+00 2.44t+09 3.85t+08 3.61E+08 ;
30Ce-137 2.711+10 3.61t+10 1.26I+10 0.00!+00 1.23t+10 4.771+09 5.14I+0B j 31Ba-140 4.98t06 6.06t+03 3.181+05 0.00!+00 2.05t+03 4.07t+03 7.62t+06 32La-140 8.278-01 4.061-01 1.081-01 0.00!+00 0.00!+00 0.00!+00 2.33I+04 33Ce-141 8.79tt02 5.87t+02 6.74t+01 0.00!+00 2.76t+02 0.00!+00 1.68I+06 34Ce-144 5.60!+04 2.32E+04 3.01E+03 0.00It00 1.398+04 0.00!+00 1.411t07 All nuelides (except B-3) calculated per ODCH equation 2.3-24 H-3calculatedperODCHequation2.3-28 ISSUI3 l 2-96 I I
i BV-1and2ODCM e fable 2.3-19 RVALUISFORBIAVIIVALLITSlft (sqseter-stes/yrperuCi/see)
Pathway:CoatMill AgeGroup: Child helide Bone Liver f. Body Thyroid tidney Lung GI-LL1-1H-3 0.00t+00 3.20t+03 3.20t+03 3.20t+03 3.20!+03 3.20!+03 3.20l+03 2P-32 7.911+10 3.70!+09 3.05I+09 0.00R+00 0.00t+00 0.00t+00 2.19149 3Cr-51 0.00t+00 0.00t+00 1.02t+04 5.64t+03 1.54t+03 1.03I+04 5.39t+05 4 h-54 0.00E+00 1.781+06 4.74Id5 0.00t+00 4.991+05 0.00It00 1.49t+06 5Fe-59 1.268+06 2.04t+06 1.02I+06 0.00t+00 0.00l+00 5.91t+05 2.12846 600-57 0.00!+00 3.27t+05 6.63t+05 0.00E+00 0.00t+00 0.00I40 2.68I+06 7Co-58 0.00I40 1.13R+06 3.46t+06 0.00t+00 0.00It00 0.00l+00 6.60l+06 8Co-60 0.00t+00 3.53td6 1.04t+07 0.00l+00- 0.00t+00 0.00l+00 1.95E+07 9Zn-65 3.54td8 9.44t+08 5.87t+0B 0.00l+00 5.95I+08 0.00E+00 1.66t+08 10 Rb-86 0.00t+00 8.88t+08 5.46td8 0.00t+00 0.00I 60 0.00t+00 5.71t+07 11Sr-89 1.111+10 0.00t+00 3.17tt08 0.00I00 0.00t+00 0.00t+00 4.30I+08 12St-90 1.59t+11 0.00t+00 4.02t+10 0.00I00 0.00l+00 0.00t+00 2.14t+09 13Y-91 3.70143 0.00l+00 9.69t+01 0.00l+00 0.00l+00 0.00t+00 4.93t+05 p 14Zr-95 3.60l+02 7.92t+01 7.05t+01 0.00l+00 1.13I+02 0.00t+00 8.27t+04 d 15Nb-95 3.13t+04 1.22E+04 8.71t+03 0.00t+00 1.14t+04 0.00l+00 2.25I+07 16Ib-97 1.491-12 2.70E-13 1.26E-13 0.00t+00 2.99I-13 0.00l+00 8.33I-08 17Mo-99 0.00t+00 8.30I46 2.05t+06 0.00It00 1.77I+07 0.00tt00 6.87t+06 18fe-99: 1.35t+00 2.651+00 4.39t+01 0.00l+00 3.84t+01 1.34t+00 1.51t+03 19In-103 4.181+02 0.00t+00 1.61t+02 0.00t+00- 1.05I 4 3 0.00l+00 1.08t+04 20Ru-106 7.791+03 0.00td0 9.72t+02 0.00I40 1.05I+04 0.00I+00 1.211+05 21Ag-110s 1.79t+07 1.21t+07 9.65It06 0.00l+00 2.25t+07 0.00l+00 1.44t+09 22Sb-124 0.00t+00 0.00t+00 0.00l+00 0.00l+00 0.00I40 0.00I00 0.00t+00 23Sb-125 0.00!d0 0.00l+00 0.00t+00 0.00l+00 0.00I40 0.00l+00 0.00E+00 24fe-127s 1.88t+07 5.05t+06 2.23t+06 4.48t+06 5.35E+07 0.00Edo ' 1.52I47 25fe-129s 2.68t+07 7.48I+06 4.16t+06 8.64I+06 7.87I+07 0.00I+00 3.27t+07 26I-131 1.33t+09 1.34t+09 7.60l+08 4.42E+11 2.19I+09 0.00ld0 1.19t+08 27I-133 1.75I+07 2.171+07 8.20t+06 4.03t+09 3.61t+07 0.00t+00 8.73E+06 28Cs-134 1.871+09 3.07t+09 6.48I+08 0.00t+00 9.52t+06 3.42td8 1.66t+07 29Cs-136 2.58t+09 7.08t+09 4.58I+09 0.00t+00 3.77t+09 5.62Id8 2.49t+08 30Cs-137 6.54t+10 8.26I+10 9.24I+09 0.00td0 2.04I+10 7.34t+09 3.92t+08 31Ba-140 1.19t+07 1.05tt06 6.96I+05 0.00t+00 3.40l+03 6.23143 6.04t+06 32La-140 1.98t+00 6.921-01 2.33I-01 0.00!+00 0.00l+00 0.00l+00 1.93E+04 33Ce-141 2.16t43 1.08I 4 3 1.60It03 0.00l+00 4.73t+02 0.00t+00 1.35td6 34Ce-144 1.38t+05 4.33144 7.371+03 0.00td0 2.40t+04 0.00l+00 1.13E+07 Allnuclides(exceptH-3)calculatedperODCMequation2.3-24 H-3calculatedperODCMequation2.3-28 ISSUI3 2-97
Bi-1and2ODCN fable 2.3-20 R VALUIS FOR BIAVIR VALLI! S!ft (sqseter-stes/yrperuCi/sec)
Pathway:GoatHilk AgeGroup: Infant Nuclide Bone Liver f. Body Thyroid tidney Lung GI-LLI 1H-3 0.00!+00 4.86E+03 4.861+03 4.86I+03 4.86t+03 4.86t+03 4.861+03 2P-32 1.63t+11 9.59t+09 6.32E+09 0.00t+00 0.00E+00 0.00!+00 2.21E+09 3Cr-51 0.00E+00 0.00It00 1.61t+04 1.05E+04 2.29E+03 2.04t+04 4.69t+05 4Mn-54 0.00!+00 3.31E+06 7.50!+05 0.00E+00 7.33E+05 0.00H+00 1.21H+06 5 Fe-59 2.35E+06 4.11E+06 1.62E+06 0.00E+00 0.00!+00 1.21E+06 1.96t+06 600-57 0.00E+00 7.64E+05 1.24I+06 0.00!+00 0.00E+00 0.00!+00 2.60E+06 7 Co-58 0.00!+00 2.26I+06 5.64E+06 0.00!+00 0.00t+00 0.00!+00 5.64E+06 8 00-60 0.00!+00 7.20!+06 1.70E+07 0.00l+00 0.00t+00 0.00!+00 1.71It07 9Zn-65 4.76t+08 1.63I+09 7.53E+08 0.00t+00 7.92I+08 0.00E+00 1.38I+09 10 Rb-86 0.00!+00 2.25I+09 1.11E+09 0.00!+00 0.00!+00 0.00l+00 5.778+07 11Sr-89 2.11E+10 0.00l+00 6.061+08 0.00E+00 0.00!+00 0.00l+00 4.34E+08 12St-90 1.73E+11 0.00H+00 4.39I+10 0.00!+00 0.00!+00 0.00!+00 2.16t+09 13Y-91 6.94E+03 0.00l+00 1.85E+02 0.00t+00 0.00t+00 0.00t+00 4.9BI+05 14Zr-95 6.40E+02 1.561+02 1.11E+02 0.00!+00 1.68t+02 0.00!+00 7.77t+04 15Nb-95 5.84t+04 2.41E+04 1.39E+04 0.00!+00 1.72t+04 0.00t+00 2.03t+07 16Hb-97 3.161-12 6.741-13 2.431-13 0.00!+00 5.271-13 0.00l+00 2.13I-07 17Mo-99 0.00!+00 2.12E+07 4.14H+06 0.00!+00 3.17t+07 0.00l+00 6.99I+06 18fc-99: 2.81It00 5.79t+00 7.461+01 0.00!+00 6.23E+01 3.03E+00 1.681+03 19In-103 8.471+02 0.00E+00 2.83E+02 0.00!+00 1.76I+03 0.00!+00 1.03I+04 20 Ru-106 1.60!+04 0.00t+00 2.00!+03 0.00!+00 1.90E+04 0.00!+00 1.22H+05 21As-110s 3.30!+07 2.41E+07 1.60!+07 0.00!t00 3.45t+07 0.00l+00 1.25t+09 22Sb-124 0.00!+00 0.00E+00 0.00l+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 23Sb-125 0.00!+00 0.00!+00 0.00!+00 0.00!+00 0.00E+00 0.00E+00 0.00!+00 24fe-127s 3.80!+07 1.26I+07 4.59t+06 1.10!+07 9.35t+07 0.00E+00 1.53t+07 25fe-129s 5.50!+07 1.891+07 8.47t+06 2.11E+07 1.38I+08 0.00l+00 3.281+07 26I-131 2.77t+09 3.27I+09 1.44It09 1.07Et12 3.82t+09 0.00!+00 1.17t+08 271-133 3.70!+07 5.391+07 1.58I+07 9.80l+09 6.34t+07 0.00E+00 9.12E+06 28Cs-134 3.02E+09 5.62t+09 5.68F+0B 0.00E+00 1.45E+09 5.93t+08 1.53E+07 29 Cs-136 5.03I+09 1.481+10 5.52E+09 0.00l+00 5.90!+09 1.21t+09 2.25E+08 30 Cs-137 1.04t+11 1.22E+11 8.66t+09 0.00!+00 3.28t+10 1.33E+10 3.82E+08 31Ba-140 2.45E+07 2.45t+04 1.26t+06 0.00!+00 5.83E+03 1.51t+04 6.03t+06 32 La-140 4.14t+00 1.63t+00 4.1SI-01 0.00!+00 0.00E+00 0.00E+00 1.92t+04 33Ce-141 4.291+03 2.62t+03 3.08t+02 0.00!+00 8.07t+02 0.00!+00 1.35E+06 34Ce-144 1.981+05 8.11H+04 1.11E+04 0.00!+00 3.28I+04 0.00!+00 1.1(I+07 Allnuclides(exceptB-3)calculatedperODCMequation2.3-24 B-3calculatedperODCHequation2.3-28 ISSUI3 2-98
BV-1 and 2 CDCM.
TABLE 2.3-21 UV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (D/ Q) foR courINUOUS ELEVATED RELEASES >500 HRS /YR OR >150 HRSAyrR (meters-2)
DISTANCES TO T11E CCNIROL Ur'ATICES, IN MILES 4.0 - 4.5 4.5 - 5.0 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 ,
3.14E-09 1.76E-09 8.12E-10 5.70E-10 4.24E-10 3.29E-10 2.63E-10 2.15E-10 N 6.00E-10 8.60E-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 WE 6.66E-10 5.64E-09 6.42E-10 1.57E-09 1.32E-09 3.62E-09 2.63E-09 1.64E-09 1.23E-09 6.13E-10 7.85E-10 NE 1.03E-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 ENE 1.13E-09 1.55E-09 5.10E-10 4.09E-09 3.12E-09 1.91E-09 1.36E-09 1.01E-09 7.83E-10 4.15E-10 E 1.35E-09 1.28E-08 3.00E-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
- ESE 9.82E-10 1.97E-09 1.18E-09 8.27E-10 5.68E-10 4.40E-10 2.93E-10 2.43E-10 SE 2.76E-09 6.41E-09 3.52E-09 1.68E-09 1.02E-09 7.14E-10 4.25E-10 3.29E-10 2.19E-10 1.80E-10 4.66E-09 3.01E-09 SSE 2.22E-09 2.68E-10 2.20E-10 4.81E-09 3.76E-09 2.10E-09 1.36E-09 9.52E-10 5.12E-10 3.96E-10 S 3.00E-09 1.98E-10 1.84E-10 1.51E-10 1.44E-08 2.89E-09 7.83E-10 8.84E-10 5.70E-10 4.00E-10 2.55E-10 SSW 2.50E-10 2.54E-10 2.08E-10 1.89E-08 5.55E-09 1.55E-09 8.71E-10 2.61E-10 3.94E-10 1.57E-10 SW 1.36E-09 1.04E-09 5.44E-10 2.39E-10 3.84E-10 2.98E-10 2.17E-10 1.78E-10 WSW 1.57E-09 6.63E-09 1.75E-10 1.84E-09 1.03E-09 6.63E-10 4.66E-10 1.37E-10 2.68E-10 1.12E-10 W 3.78E-10 2.95E-09 1.80E-10 3.09E-10 4.71E-10 7.35E-10 5.16E-10 1.93E-10 1.10E-10 1.12E-10 NNW 4.54E-10 4.13E-10 2.09E-10 1.71E-10 4.09E-10 2.86E-10 1.18E-09 7.04E-10 4.94E-10 3.37E-10 2.10E-10 NN 4.52E-10 1.73E-10 1.42E-10 2.05E-09 1.63E-09 9.12E-10 5.86E-10 4.13E-10 2.79E-10 2.16E-10 NNN 3.40E-10 2-99 ISSUE 3 .
BV-1 and 2 00CM -
%BLE 2.3-22 BV-1 AND 2 CONIAIt#ENT VENTS DISPERSICE PARAMETERS (D/Q) .
FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRSNTR l
(meters ~)
{
l DISTANCES TO 'IHE C[NIBOL IOCATICNS, 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 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 l 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-10 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 WNW 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 2.10E-09 1.56E-09 1.21E-09 7.83E-10 6.41E-10 tem 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 t
2-100 ISSUE 3 0 .
O O
BV-1 and 2 CDCM-TABLE 2.3-23
. BV-1 Ale 2 SITE VENTIIATION VENTS DISPERSION PARAMETERS (D/Q)'
POR CDfrI!WOUS GROIRO LEVEL RELEASES .>500 HRS /YR OR >150 HRS /UFR (meters-2).
DISTRNCES TO THE CCNTROL IDCATIGIS, 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 tele 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 5.69C-10 4.66E-10 i 1
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 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 i
. SSE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E 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.%E-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 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 WNW 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.%E-10 5.79E-10 4.75E-10
- NN 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 NNN 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
BV-1 and 2 CDCM TABLE 2.3-24 BV-1 AND 2 HJRBINE BUILDING VENTS DISPERSION PARAMETERS (D/Q)
FOR CONTINUOUS GROUND LEVEL RELEASES >500 ImS/YR OR >150 HRS NIR (meters ~ )
DISTANCES 'IO 'IHE CCNTROL IDCATIONS, IN MILES SEC'IDR 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 SSN 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 1.98E-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 WNR 9.2SE-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 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 2-102 ISSUE 3 O O O
o o
~
O ,
BV-1 and 2 CDCN.
t TABLE 2.3-25 ,
- FGL INE0BMATIN GILY ;
BV-2 CONDENSATE POLISHING BUIIDING VENT DISPERSIM PARAMETERS (D/Q)
FOR CONTINUOUS GROL30 LEVEL RELEASES >500 HRS /YR OR >150 HRSA7fR (meters ~)
l .
DISTANCES TO THE CGmOL IOCATIGIS, 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' 1.08E-09 7. 57*,-10 , 5.16E i10 4.00E-10' 2.91E-10 2.38E-10 4.46E 7.73E-09 3.24E-09 1.81E-09 N
1.89E-09 1.22E-09 8.54E-10 6.35E 4.92E 3.94E-10~ 3.22E-10 .!
-tele 5.42E-08 9.39E 3.37E 4.60E-10 j 6.21E-09 3.47E-09 2.24E-09; 1.57E-09 1.00E-09 7.77E 5.69E-10 NE 7.32E-08 1.27E-08 r 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 6.51E-09. 3.64E-09 5.06E-10 4.05E-10 3.32E-10 !
1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 E 6.08E 4.05E-10 3.14E-10 2.28E-10 1.87E-10 l 3.23E-08 5.60E-09 2.54E-09' 1.42E-09 8.46E-10 5.94E-10 ESE !
9.32E-10' 6.55E-10: 4.12E-10 3.19E-10' L2.55E-10 2.09E-10 .
SE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 1.52E-10 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E 1.85E-10 SSE 2.84E-08 3.86E-10 2.99E-10 2.39E-10 1.96E-10 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14::-10 5.71E-10 S 1.39E-10 8.97E-10 5.78E-10 4.06E-10' 3.02E-10 2.34E-10 1.70E-10 SSN 2.61E-08 4.52E 1.60E-09 3.24E-10 2.35E 1.93E-10 5.30E-09 2.62E-09 1.47E-09 8.01E :5.62E-00 4.18E-10 SW 3.06E-08 i I 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 3.15E-10 t 2.64E-09 .1.19E-09 8.36E-10 6.22E-10 '4.82E-10 -3.85E-10 W 6.49E-08 -1.13E-08 4.72E-09 '5.79E-10 4.75E-10 6.43E-09 3.60E-09 2.21E-09 '1.55E-09 1.16E-09 8.%E-10 MNW 9.25E-08 1.60E-08 1.21E-09 7.83E-10 6.41E-10 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 NW 1.19E-07 6.2SE-10 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-10 i feet l i
i
- l i
i I
~
103 ISsus 3 l
. . - - . . . . -__.--_..o.-.__~ .
. _ - . - - - - _ _ _ _ _ _ . _ . -. - - - - . - - - _ - - _ _ - _ - - _ - . _ _ - - - - . _ . _ _ _ _ _ _ = . - - . - . - - _ - - - - - ~ . _ - - - _ _ _ _ - - - _ - - - _ . _ _ _ _ - - - _ . _ _ _ _ - - - - - - . _ . --
BV-1 and 2 ODCM TABLE 2.3-26 EOR INMRMATION ONLY BV-2 DECONTAMINATION BUILDING VENF DISPERSION PAMMETERS (D/Q)
! EDR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /UIR
! (meters ~ )
l DISTANCES TO THE CONTROL IDCATIONS, IN MILES l
! 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 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 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 l
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 8.35E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 MM 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E 1.55E-09 1.16E-09 8.96E-10 5.79E-10 4.75E-10 NW l.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 4.34E-10 3.59E-10 2.94E-10 2-104 ISSUE 3 O O O
O O- O BV-1 and 2 CDCN ThBLE 2.3-27 FOR INFORMATI N W LY f
BV-2.WhSTE GAS STORAGE VAULT VENT DISPERSIM PARAMETERS (D/Q) .
FOR CONTINUOUS GROLIO LEVEL RELEASES >500 HRS /YR OR >150 HRS /QFR (meters-2)
DISTANCES TO'THE ON1BOL IDCATIWS, IN MILES SEC1DR 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 5.16E-10 4.00E-10 2.91E-10 2.38E-10
, tele 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 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 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 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.%E-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 NSW 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 1.19E-09 8.36E 6.22E-10 4.82E-10 3.85E 3.15E-10 '
Met 9.2SE-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 8.68E-09 4.86E-09 2.99E-09 2.19E-09 -1.56E-09 1.21E-09 7.83E-10 6.41E-10 !
test 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 2.94E-10 l i
i i
4 2-105 ISSUE 3-
- t
- _ . _ _ __ -. - . _ _ . ~ _ . - . -
BV-1 and 2 ODCM TABLE 2.3-28 l l
BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (D/0) l FOR CONTINUOUS ELEVATED LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR l 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 .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 VNV .424 .746 .497 .029 .746 .746 NV .447 .425 -- .070 .488 422 NNV .340 1.840 -- .043 .545 1.92 0
2-106 ISSUE 3 0
BV-1-and 2 ODCM TABLE 2.3-29 BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (D/0)
N FOR CONTINU0US GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR s 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 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 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 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 NV 70.60 15.00 -- .276 1.990- 15.60 NNV 31.50 6.52 -- .068 1.090 9.91
. Q V
I e
BU-1 end 2 ODCH TABLE 2.3-30 BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (D/0) j FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR ,
FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(1E-9 meters )
INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN HILK COV HILK GOAT HEAT 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 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 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 NV 70.60 15.00 -- .276 1.990 15.60 NNV 31.50 6.52 -- .068 1.090 9.91 0
2-108 ISSUE 3 I
- .-- . _ . - - - . ~ . -. . . . . . . - - . . ~ . _ - _ . - - _ . - - . - . - . _ - . - . . . - - , . . . - . . ~ - - _ . ,
BV-1 end 2 ODCM' ;
TABLE 2.3-31' .I BV-1 AND 2 TURBINE BUILDING VENTS DISPERSION PARAMETERS (D/0)
FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR O
FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters-) ;
INDIVIDUAL RECEPTORS
- D0VNVIND SITE VEGETABLE ;
~ SECTOR BOUNDARY- GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE- -t
~
N 20.20 2.05 -- .693 .847 7.190~
NNE :34.90 2.02. -- .459 1.850. 2.110 ;
-NE 54.20 29.30 .455 .078 .455 '30.400 32.200. -?
ENE 57.50 8.92 -- .661 --
E 38.10 3.90 .382 1.020 1.020) '22.700 !
.; ESE 18.60 3.56 --:- 1.380; 3.560- 3.560 i SE 19.00' 3.03 .351 .351- 1.100- 3.030.
SSE 13.30 2.65 .318 .094L 2.570 3.690 l S. L11.30 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- '
USV 25.10 2.65 .597 --
2.380 2.650 V 28.40 1.23 .646 , - - . '. 961 '1.230. t VNV 30.90 2.23 .1.490 .045 2.230 2.230- 1 NV . 56.10 14.90' -- .276 1.980' 15.500 NNV 25.10 6.53 -- .068 1.100- 9.920- '(
1 i
1 I
2-109 ISSUE 3 O
W
- ,w ----w- ,r ,
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 /QTR '
FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters ~2)
I 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 USV 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 2-110 ISSUE 3 0
4
-l BV-1 and 2 ODCM i 1
. TABLE 2.3-33 FOR INFORMATION ONLY I l
l O 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) .
-1 (IE-9 meters 2)
INDIVIDUAL RECEPT 0RS ,
DOWNVIND SITE VEGETABLE
-SECTOR- BOUNDARY GARDEN MILK COU - MILK GOAT ~ ' MEAT ANIMAL ' RESIDENCE- !
-l N' 25.40 2.05 -- .693 .847. 2.190 NNE -18.80 2.02 :-- .459 i.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 -- 11.320 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 CJ NNV- 31.50- 6.52 -- .068. 1.090 9.910 l
l l
i l
6
% . - - - ,-,----,,.a:w - - - - wn- , . . .---. , , , , - e s-- -
BV-1 cnd 2 ODCM TABLE 2.3-35 FOR INFORMATION ONLY BV-2 VASTE GAS STORAGE VAULT VENT DISPERSION PARAMETERS (D/0) 1 FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(IE-9 meters ~)
INDIVIDUAL RECEPTORS l
.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 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 0
E
I BV-l'and 2 ODCM TABLE 2.3-35 i BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (X/0)
FOR' BATCH GROUND LEVEL RELEASES <500 HRS /YR OR <150 HRS /QTR O FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3)
(sec/m )
INDIVID'JAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR
- BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE i N -8.21E-5 8.38E-6 -- 3.72E-6 4.34E-6 8.82E-6 JNNE 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 6.05E-7 2.28E-5 ENE 3.72E-5 5.25E-6 -- 5.66E-7 -- 1.88E-5 E 2.93E-5 3.79E-6 5.15E-7 1.17E-6 1.17E-6 1.7dE-5 1 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
, USV 1.09E-4 1.29E-5 4.10E-6 --
1.19E-5 1.29E-5 ;
L :
V 1.49E-4 1.05E-5 '6.55E-6 -- 8.77E-6 1.05E-5 VNV 1.91E-4 1.72E-5 1.28E-5 1.23E-6 1.72E-5 1.72E-5 ~'
NV 1.08E-4 6.13E-5 -- 3.80E-6 1.36E-5 6.36E-5 r' s NNV i.GOE-4 3.54E-5 -- 1.35E-6 9.27E 5.29E-5 l N~-
1
'l l
i i
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings i
5 Period of Record 1976 - 1980 b
- i a >
i
. . - . . , . -l
BU-1 ond 2 ODCM TABLE 2.3-36 i
BV-1 AND 2 VENTILATION VENTS DISPERSION PARAHETERS (X/Q)
FOR BATCH GROUND LEVEL RELEASES <500 HRS /YR OR <150 HRS /QTR .
FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE Y.2-3)
(sec/m ) <
INDIVIDUAL RECEPT 0RS DOVNVIND SITE VEGETABLE SECTOR
- BOUNDARY GARDEN MILK COV MILK C0AT MEAT ANIHAL RESIDENCE 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 l SSE 2.65E-5 6.72E-6 1.12E-6 3.95E-7 6.53E-6 9.22E-6 S 2.52E-5 3.14E-6 2.83E 6 -- 5.29E-6 5.53E-6 l 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 I VSV 1.34E-4 1.51E-5 4.46E-6 -- 1.38E-5 1.51E-5 V 1.77E-4 1.25E-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-5 NNV 1.90E-4 4.69E-5 -- 1.45E-6 1.09E-5 6.75E-5 O
l l
l I
i
- Measured relevant to center point between BV-1 and BV-2 containment Buildings s
Period of Records 1976 - 1980 2-114 ISSUE 3 Ol 1
i
q BV-1 end 2 ODCM TABLE 2.3-37 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (X/0)
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 ESE 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-5 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 1.52E-9 3.73E-6 1.73E-7 1.31E-6 3.81E-6
/~N NNV V i h
- Measured relevant to BV-1 natural draft cooling tower Period of Records 1976 - 1980 2-115 ISSUE 3
a BV-1 and 2 ODCM TABLE 2.3-38 BV-1 AND 2 PROCESS VENT DISPERSICH PARAME'IERS (X/Q)
EDR BAICH ELEVATED RELEASES 3500 HRS /YR OR 3150 HRSNTR*
(sec/m )
DISPJWCES 'IU 'IHE CONTROL IOCATICNS, IN MILES SEC'IDR 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 ItiE 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 E 1.84E-15 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.S2E-7 ESE 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 SE 9.16E-8 3.13E-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 i SSE 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 3.32E-7 S 1.22E-7 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 SSW 1.75E-5 6.22E-6 2.84E-6 2.18E-6 1.48E-6 1.08E-6 7.83E-7 6.31E-7 5.62E-7 4.77E-7 SW 2.08E-5 9.11E-6 3.47E-6 2.19E-6 1.25E-6 1.11E-6 8.19E-7 7.17E-7 6.89E-7 5.85E-7 WSW 8.56E-8 9.35E-6 3.16E-6 2.29E-6 1.46E-6 1.01E-6 9.06E-7 7.52E-7 5.99E-7 5.07E-7 W 5.44E-17 4.52E-6 4.21E-6 2.49E-6 1.69E-6 1.25E-6 4.86E-7 7.68E-7 5.80E-7 5.48E-7 WNW 9.2SE-18 1.44E-8 5.66E-8 1.92E-6 1.59E-6 1.17E-6 7.75E-7 4.61E-7 5.28E-7 4.89E-7 NW 2.61E-16 1.98E-8 8.37E-8 2.24E-6 1.46E-6 1.08E-6 8.09E-7 6.12E-7 5.42E-7 4.60E-7 teH 1.91E-15 3.91E-6 3.66E-6 2.15E-6 1.40E-6 1.08E-6 8.03E-7 6.48E-7 5.37E-7 4.56E-7
- Transmittal via Stone and Webster Engineering Corp. letter 2DLS-29981 under J.O.12241 on January 30, 1987.
2-116 ISSin. 3 O O O
BV-1 cnd 2 ODCM :
2.4 Gaseous Radvaste System 9
()
.\ ,/
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. ',
l D
3 s
2-117 ISSUE 3
BV-1 cnd 2 ODCH 2.4.1 BV-1 Gaseous Radvaste System Components 2.4.1.1 BR-EV-2A & 2B: Degasifiers There are two Degasifiers. They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
2.4.1.2 GV-E-1A & IB: Vaste Gas Chillers There are two Chillers. Non-condensable gases from the degasifiers are directed by system pressure to the Vaste Gas Chillers.
2.4.1.3 GV-TK-3A, 3B, 3C, & 3D: Gaseous Vaste Charcoal Delay Beds There are four Charcoal Beds. The dry effluent from the Chillers is directed to the Vaste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radioiodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.
2.4.1.4 GV-FL-5A & 5B: Overhead Gas compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Gaseous Waste Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
2.4.1.5 GV-C-1A & IB: Gas Compressors There are two compressors. The vaste gas enters one of the compressors after passing through the Prefilters.
2.4.1.6 GV-TK-2 Gaseous Vaste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. After compression to about 65 psig, the vaste gas is sent to the Surge Tank.
This can be done automatically or manually.
2.4.1.7 GV-TK-1A, 1B, & IC: Vaste Gas Decay Tanks There are three Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.
l l
l 2-118 ISSUE 3 i
BV-1 and 2 ODCM 2.4.1.8 RM-GV-108 And RM-GV-109: Gaseous Effluent Radiation Monitors
' There are redundant Radiation Monitors on the combined. BV-1 and'2 ,
gaseous vaste release path. These Radiation Monitors continuously ,
analyze gaseous vaste as it is being discharged. . Gaseous Monitor-RM- t GV-108B is an off-line games scintillator, while RM-GV-109. Channel 5 is i sn off-line beta scintillator. .The upper activity alarm on the gaseous- !
. Channels of these Radiation Monitors have setpoints that would indicate- i ve are-approaching the Total -Lody Dose Rate or Skin Dose Rate limits for radioactive gas leaving the site. If an upper activity alarm on !
RM-GV-108 is received, it automatically terminates. the discharge by closing an isolation valve downstream of the Decay Tanks. !
5 i
/N !
(-) '
1 I
a 2-119 ISSUE 3 )
i j
BV-1 and 2 ODCM '
2.4.2 BV-2 G stous Redvrste System Components 2.4.2.1 2BRS-EV21A & 21B: Degasifiers There are four Degasifiers (two at Unit 1 and Ivo at Unit 2). They are designed to continuously process reactor coolant letdown for reducing entrained noble gases in the liquid.
2.4.2.2 2GVS-E21A & 21B: Vaste Gas Chillers There are four Chillers (two at Unit 1 and two at Unit 2). Non-condensable gases from the degasifiers are directed by system pressure to the Vaste Gas Chillers.
2.4.2.3 2GVS-TK22A, 22B, 22C, & 22D: Vastc Gas Charcoal Delay Beds There are four Charcoal Beds (four at Unit 1 and four at Unit 2). The dry effluent from the Chillers is directed to the Vaste Gas Charcoal Delay Beds for holdup of xenon and krypton and adsorption of radiciodines. When four beds are operated in series, they provide a holdup of xenon isotopes for about 30 days.
1 2.4.2.4 2GVS-FLT24A & 24B: Overhead Gas Compressor Prefilters There are two Prefilters. The gaseous effluent (primarily hydrogen) is directed from the Vaste Gas Charcoal Delay Beds to one of the Overhead Gas Compressor Prefilters. The filters remove carbon solids from the gas stream.
2.4.2.5 2GVS-C21A & 21B: Gas Compressors There are two Compressors. _The vaste gas enters one of the compressors after passing through the Prefilters.
2.4.2.6 2GVS-TK21: Gaseous Vaste Surge Tank There is one Surge Tank. It has a capacity of 52 cuft. Afte-compression to about 65 psig, the vaste gas is sent to the Surge Tank.
This can be done automatically or manually.
2.4.2.7 2GVS-TK25A, 25B, 250, 25D, 25E, 25F, & 25G: Gaseous Vaste Storage Tanks There are seven Decay Tanks. Each has a capacity of 132 cuft. The contents of the Surge Tank is transferred to the Decay Tanks for storage and decay. After 30 days of storage, all xenon and iodine should have decayed, and the resulting predominant nuclide should be krypton 85.
2.4.2.8 RM-GV-108 And RM-GV-109 Gaseous Effluent Radiation Monitors Previously described in Section 2.4.1.
O' 2-120 ISSUE 3
BV-1 and 2 ODCM FIGURE 2.4-1 BV-1 AND 2 GASEOUS RADVASTE SYSTEM O .n -
U$ i R WT! TO ATMOSNERE cn I l ' '
C00ffkfWD FRDILTD$ GA$ GA$ I C08EPRES$0R COMPRESSOR , , ,
i i i i l l "
n f 4
(
un tas (uni = .
(__ .)
r- 15 6 nCAT TM
(-_-) .
4_,,_y j l
(__ .) < _, _ y j g ,
(:-) p _y j
_ R.
__ <_ , _ y 4,_ ,_y l
~
near tam ucar tem
. 1
.ECAT T M MCAV TM _
,c .
=
X =
Monsirin
,i_i m u,. oum ,rJ-[}-
c=miaS=0R c Ai a=i= == *
.u- n,.i m mCm r
,g 0 f
,g WA O
2-121 ISSUE 3 1
BV-1 and 2 ODCM l FIGURE 3 4-2 BV-1 AND 2 GASE0US EFFLUENT RELEASE FOIITIS
~
w ohio River g w-a, , .a ,
l kU m
\ m\./ -5)
T i
\ ,
e l
1 f
i A Unit 2 Unit 1 i_ 1 i m s h 6 C 1
i l
l l RILIA51POIIT&DISCRIPTION ILIYAfl0B
- 1. Unit 1: VentilationVent 79 feet: 24 meters
- 2. Unit 1: Containment /SICRSVent 154 feet: 47 seters
- 3. Unit 1&2:ProcessVent
- 4. Unit 2: VentilationTent 475 feet:145 meters 85 feet: 26 meters b i7
- 5. Unit 2:
- 6. Unit 2:
Centainment/SLC15 Vent CondensatePolishingBuildingVent 154 feet: 47 seters M 80 feet: 24seters G
- 7. Unit t VasteGasStorageVanitVent 80 feet: 24seters i N B. Unit 2: DecentasinationBuildingVent 80 feet: 24 meters O'
2-122 ISSUE 3
I BV-1 cnd 2 ODCM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM tN The following program requirements are excerpts from the Radiological (vI 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 pathways 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.
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 that the measurable concentrations of ::dic:: tite =sterials and levels of radiation are not higher than eagected 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 those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. The initial radiological environmental monitoring program should be conducted for the first 3 years of commercial -operation (or other period corresponding to a
,-_s maximum burnup in the initial core cycle). Following this period, program changes may be proposed based on operational experience.
(s--}
The specified detection capabilities are state-of-the-art for routine environmental measurements in industrial laboratories.
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 next sampling period. All deviations from the sampling schedule shall be 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 1 (Crosscheck) Program or equivalent program. This participation shall 1 include all of the determinations (sample medium-radionuclide combination) i 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 !
EPA's participant data directly in lieu of submission in the annual report. I 1
- l. l
,i
(N) 3-1 ISSUE 3
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BV-1 and 2 ODCM If the results of a determination in the EPA crosscheck program (or i equivalent program) are outside the specified control limits, the j laboratory shall investigate the cause of the problem and take steps to l 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 program, 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 vegetc. tion 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 bro F 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 submitted to the Director of Operating Reactors, NRR (with a copy to the Director of the NRC Regional 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 surve! '.ance program as .soon as practicable.
The sampling location (excluding the control sample location) having the lowest calculated dose may the,n 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 pathways of exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation contaminated by airborne radiolodine is a major potential source of exposure. Samples from milk animals are considered a better indicator of radioiodine in the environment than vegetation. If the census reveals milk animals are not present or are unavailable for sampling, then vegetation must be sampled.
3-2 ISSUE 3 0 ;
BV-1 and 2 ODCM The 50 square meter -garden, considering 20% used for growing broad leaf vegetation2 (i.e., similar to lettuce and cabbage), and a vegetation yield m 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 Regulatory
-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 (msn-rem) in accordance with Criterion 64 - monitoring radioactivity releases, 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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O 9
BV-1 and 2 CDCM TABLE 3.0-1 RADIOIOGICAL DNIRONMEN'IAL MNITORING PROGRAM DLC SAMPLING AND EXPOSURE PA111 HAY SITE y COLLECTIm TYPE AND FREQUENCY 7 OF ANALYSES AND/DR SAMPLE NO. SECTOR MILES SAMPLE POINT DESCRIPTION FREQUENCY
- 1. AIRBORNE Radioiodine and 13 11 1.6 Hookstown (Meyer's Farm) Continuous Radioiodine Cartridge:
Particulates 30 4 0.6 shippingport (Cooke's Ferry sampler I-131 analysis weekly.
Substation) operation w/
32 15 0.8 Midland (Midland Substation) collection Particulate Sampler:
46.1 3 2.1 Industry at least Grossbetaanalysisgol-48 10 16.5 Weirton, W4 (Weirton Water weekly. lowing filter change ;
Storage Tank) Gamma isotopic analysis on composite (by loca-tion) gaarterly.
- 2. DIRECT RADIATION 10 4 0.8 Shippingport Boro (Post Office) Continuous Gama dose quarterly.
13 11 1.6 Meyer's Farm measurement 14 11 2.6 Hookstown with quarterly 15 14 3.3 Georgetown collection.
27 7 6.2 Brunton's Farm 28 1 8.7 Sherman's Farm 29B 3 8.1 Beaver County Hospital 30 4 0.6 Shippingport Boro (Cooke's Ferry) 32 15 0.8 Midland Boro (Midland Substation) 45 5 2.2 Raccoon TVp. (Mt. Pleasant Church) 45.1 6 2.0 Raccoon TVp. (Kennedy's Corner) 46 3 2.5 Industry (Church) 46.1 3 2.1 Industry (Tire Company) 47 14 4.8 East Liverpool, OH (Water Company) 48 10 16.5 Weirton, W (Water Company) 51 5 8.0 Aliquippa 59 7 1.1 Iron's Farm 3-4 ISSUE 3 O O O
O O O BV-1 and 2 CDCM TABLE 3.0-1 (continued)
. RADIOIOGICAL DNIlOWEENDd. Infl10 RING PROGRAM DLC SAMPLING Am EXPOSURE PR1150LY SITE ' COLLECTIN TYPE AND FREQUENCY 1 2- SAMPLE POINT DESCRIPTIN' OF ANALYSES Ale /OR SAMPLE NO. SEC10R MILES FREQUENCY DIRECT RADIATION '60 13 3.7 Haney's Farm' Continuous r m dose quarterly..
(continued) 70 1 3.0 Western Beaver High 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 ( h wsity College) 75 5 4.3 Raccoon Twp. (Holt Road) 76 6 3.8 Raccoon 'IVp. School 77 6 5.8 Raccoon w p. (Green Garden Road) 78 7 2.3 Raccoon '1%p. Municipal' Building 79 8 4.6 Raccoon 1Mp. (Routes 18 & 151) 80 9 8.4 Raccoon Park 3.9 .Southside School
~
81 9 82 9 7.1 Hanover Township Municipal Building 83 10 4.5 Greene Township (Mill Creek Road) 84 11 8.5 Hancock County, W (Children's Home) 85 12 5.8 . Hancock County, W (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 '1%p. (Pine Grove & Doyle Roads) 92 12 3.0 Greene Township (Georgetown Road) 93 16 1.3 Midland (Sunset Hills)'
94 8 2.4 Raccoon '1%p. (McCleary Road) 95 10 2.4 'Greene Township (McCleary Road) 3-5' ISSUE 3
BV-1 and 2 ODCM TABLE 3.0-1 (continued)
RADIOT4GICAL ENVIRONMENTAL MONITORI!G PROGRAM DLC SAMPLING AND EXPOSURE PA7HWAY SITE COLLECTION TYPE AND FREQUENCY l 2 OF ANALYSES AND/OR SAMPLE NO. SECTOR MILES SAMPLE POINE DESCRIPTION FREQUENCY
- 3. WATERORNE a) Surface (River) 49.1 4 S.0 Upsgream-invicinityofMontgomery Composite Gama isotopic analysis Dam (ARQ Chemical Company, sample w/ monthly; tritium analy-formerly ARCO Polymers) sanple col- sis on composite (by 2.1 14 1.3 Downstream-Midlard lection at location) quarterly, least 6
monthly ,
b) Drinking Water 4 14 1.3 Midland (Midland Water Treatment Composite I-131 analysis bi-Plant) sample w/ weekly; gama isotopic 5 14 4.8 East Liverpool, OH (East Liver- sample col- analysis on composite pool Water Treatment Plant) lection at (by location) monthly; leastgi- tritium analysis on com-posite (by location) weekly .
c) Ground Water None required 2A 13 0.2 vicinity of BVPS Discharge Semi- Gamma isotopic analy-d) Shoreline annually. sis semi-annually.
Sediment Structure
- 4. INGESTION At least bi- Gamma isotopic and I-131 a) Milk 25 10 2.1 Searight's Dairy
- 8 - - weekly when analysis on each sample.
- 8 - - ""I"*18 #f" i
- 8 4 on pasture; at 96 10 10.3 Windsheimer's Dairy least monthly at other times.
2A 13 0.2 Downstream-in vicinity of BVPS Semi-annually Gamma isotopic analysis.
b) Fish one sample of on edible portion.
Discharge Structure 49 3 4.7 Upstream-in vicinity of Montgomery available Dam species.
l 3-6 ISSUE 3 9 9 e
O o .
o BV-1 and 2 Coot TABLE'3.0-1 (continued)
RADIOLOGICAL'ENVIROSENEL IMI'ICRIFC PROGRAM SAMPLING ' Atc DLC COLLECTIG( TfPE Als FREQUENCY EXPOSURE PA'119ihY SITE 1 2 3 OF NN ANDf0R SAMPLE NO. SECTOR MIES SAMP2 POIM GIPTION 6
- 4. INGESTION (continued) Three (3) locations within 5 miles Annually at c.amma. isotopic and I-131
-c) Food Products 10 4 0.8 14 3.3 of BVPS- harvest analysis on edible.
(Leafy vege-' 15 time. portion.
tables) 46 3 .2.5 48 10 16.5 One -(1) location (weirton, WV area) 1 Sector numbers 1-16 correspond to the 16 compass direction sectors N - t@lW.
2 Distance (in miles) is as neasured'from BVPS Unit 1 Containment Building.
3All Sample Points, unless otherwise noted, are'in the en-nrwealth of Pennsylvania. Maps showing the approximate locations of the Sample Points are provided as Figures 3.0-1 through 3.0-9.
hisisaControlStationandispresumedtobeoutsidetheinfluenceofBVPSeffluents.
~
5A gasuna isotopic analysis is to be performed on each sample when the gross beta actisity is found 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_ hours.
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.
8these Sample' Points will vary and are chosen based upon calculated annual deposition factors (highest).
3-7 ISSUE 3
BV-1 and 2 ODCH I
FIGURE 3.0-1 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM AIR SAMPLING LOCATIONS EN4fueadCNTAL MONIT0Ha#43 L4CATl004S- AIR f#PLitG LKATi(16 N uwwora amwry I A!P. WFt f E STAf fffK .
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BV-1 and 2 ODCM FIGURE 3.0-2 !
l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM {
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i 3-9 ISSUE 3
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BV-1 and 2 ODCM FIGURE 3.0-3 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM TLD LOCATIONS - NORTHEAST QUADRANT
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BV-1 and 2 ODCM FIGURE 3.0-4 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM TLD LOCATIONS - SOUTHEAST GUADRANT a >6 i 4 ..r. -
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BV-1 and 2 ODCM FIGURE 3.0-5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD LOCATIONS - SOUTHVEST QUADRANT l
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3-12 ISSUE 3 0
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,- /y V (> O BV-1 and 2 GEM FIGURE 3.0-6 RADIOtOGICAL EhvIBOt@ENIAL NEIN PROGRAM SHORELINE, SEDIMENT, SURFACE WATER, AND DRINKING WATER SAMPLING LOCATIONS f[ '
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TYPE OF SAMPLE SAMPLING POINT \f'-
SAMPLE POINT DESCRIPTION SURFACE 2.1 DOWNSTREAH-MIDLAND WATER 49.1 ARCO POLYMERS LEGEND DRINKING 4 HIDIAND WATER PLANT MOOWN8#
WATER (TREATED WATER) 5 EAST LIVERPOOL WATER PLANT O SHORELINE SEDIMENT (TREATG WATER) b SURFACE WATER & DRINKING WATER EnwsoNMEN5A' L Maviroainq &srsous LOCATIONS - S!!ORELINE SEDIMENT
- SURFACE WATER & DRINKING WATER ISSUE 3 3-13
BV-1 and 2 ODCH FIGURE 3.0-7 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MILK SAMPLING LOCATIONS ENVlFacNadCNTAL 6aONITOFuta3 LDCAf tons- FULK N u"""4 ***rY
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maan ca irr 1 J MIIX b'D
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3-14 ISSUE 3 9
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BV-1 and 2 ODCM FIGURE 3.0-9 RADIOIDGICAL DNIRCNENIAL MONI'IORING PROGRAM FISH SAMPLI?Ki LOCATICNS
\
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e NOMTQ OMEN / MM-r--
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No. LocArro" -
LEGEND tati c arge Fish Sampling Locations 49 Upstream - Montgomery Dam I ENVIRONMENTAL MONITORING PROGRAM FISH SAMPLING LOCATIONS 3-16 Issue 3 O O O
BV-1 and 2 ODCM l l
4.0 INFORMATION RELATED TO 40 CFR 190
/G 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 CONTROL 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b, 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 racioactivity and to radiation from uranium J fuel cycle sources exceeds the limits of f 25 mrem to the total body or any organ, except the thyroid, which is limited to $ 75 mrem for a calendar year. If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Repotc pursuant to Technical Specitication 6.9.2f. The following shall be included in the Special Repor. t :
- 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 pathvays 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.
d
- 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, a.si a variance is granted until staff action on the request is complete.
i 9
[%
4-1 ISSUE 3
(
I 9
4 -
o BV-1 and 2 ODCM o
FIGURE 5-1 SITE BCUNDARY EDR GASEOUS AND LIQUID EFFIDE2frS sa <1 p% s a t.: -,i +f %
i..*.2..*! <
g W Midland r, # g e, .
tea w
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. 4 s MILES
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Shippingport
% % .s * * * ,,,.i l N
This Site Boundary for Liquid Effluents does not g% [
include the areas over the Ohio River. With this exception
%g 8 the site Boundaries are identical. I 16 8 a sm an n Site Boundary-Effluents ap -Direction of Drainage-Liquids ]
Issue 3 5-1
BV-1 and 2 ODCM APPENDIX A
SUMMARY
OF DISPERSION CALCULATIONAL PROCEDURES lO l
Annual average and grazing season average values ef relative concentration (X/0) l and deposition (D/0) vere calculated for continuous and intermittent gaseous releases of activity from the site according to the straight-lineUndecayed airflov j (Gaussian) model described in NRC Regulatory Guide 1.11., Revision 1. i 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 i
- receptors. For an elevated release, defined as occurring at a height that is I 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 liseous release points that have been evaluated include the process vent attacheo to the BVPS-1 natural draft cooling tower, the Containment Vents, Ventilation Vents, Turbine Building Vents, the BVPS-2 Condensate Polishing Building Vent, Decontamination Building Vent, and Gaseous 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 O
h given in Appendix A, Table 1.1. t i
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 NRC Regulatory Guide 1.23 as described in l
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 6T as an indicator of atmospheric stability. The lover level vinds (35 ft) and 6T (150-35 ft) were used for all ,
release points except the process vent which required the use of 500 ft vinds '
and 6T (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 l nearest meat animal. In the case of the process vent releases, several of each receptor type were evaluated in each downvind sector to determine the maximum X/0-D/0 values. The distances of the limiting maximum individual receptors from i
the radioactive release points are given in Table 2.2-3. The continuous release annual average X/0 values at the special locations for the Containment Vents, Ventilation Vents, Process Vent, Turbine Building Vents, Decontamination l j
Building Vent, Vaste Gas Storage Vault Vent, and Condensate Polishing Building Vent are given in Tables 2.2-4 through 2.2-10 respectively. Continuous release annual average X/0's for these same release points are also given at ten A-1 ISSUE 3 j 1
1
BV-1 end 2 ODCM 1
APPENDIX A l
SUMMARY
OF DISPERSION CALCULATIONAL PROCEDURES (continued) incremental downwind distances. Continuous release D/0 values for these same release points are given in Tables 2.3-21 through 2.3-27 for the incremental distances and in Tables 2.3-28 through 2.3-34 for the special locations. Due to their location adjacent to the containment building, the BVPS-2 Decontamination Building and Gaseous Vaste Storage Tank Vault X/0's and D/0's are the same as i . the containment vent X/0's and D/0's. Likewise, the Turbine Building Vent X/0's and D/0's apply to the BVP'H2 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.
l l O 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 i For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear 1 Power Stations, NUREG/CR-2919, U. S. Nuclear Regulatory Commission, September, 1982.
A-2 ISSUE 3
i
)
BV-1 and 2 ODCM APPENDIX A TABLE A:1 BV-1 AND 2 RELEASE CONDITIONS TURBINE )
VENTILATION CONTAINHENT PROCESS BUILDING VENT VENT VENT VENT ;
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) l Adjacent Building 19 44 155 33 Height (m) i Relative Loca- E. Side Of Top Center Of Atop Cooling Turbine I tion To Adjacent Primary Auxi- Containment Tower Building Structures liary Bldg Dome j 9.4 NA l (m Exit Velocity NA NA
()
(m/sec)
Internal Stack NA NA 0.25 NA l
Diameter (m)
Building Cross- 1600 1600 NA NA 2
Sectional Area (m )
Purge Frequency
- 32 32 74 NA (hours / year)
Purge Duration 8 8 NA NA i (hrs / release)
O.
I
)
- Applied to Short Term calculations only A-3 ISSUE 3 Revision 1
BV-1'end 2 ODCM l
-APPENDIX B l O- INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS i b !
This Appendix contains the input parameters to the various computer code's used ;
by.Duquesne Light Company and its subcontractors for determination of the Liquid and Gaseous source term mixes. The inputs are contained in the following Tables of:this Appendix:
Table Bila ' Inputs To Gale Code For Generation Of BV-1 Liquid Source Term j Mixes Table Bilb Inputs To SVEC LIQ 1BB Code For Generation Of BV-2 Liquid Source -
Term Mixes Table B:2a Inputs To SVEC GAS 1BB Code For Generation Of BV-1 Gaseous Source !
Term Mixes Table B:2b Inputs To SVEC GAS 1BB Code For Generation Of BV-2 Gaseous Source j Term Mixes i
l
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l I
i l
O 1 l
O B-1 ISSUE.3 Revision 1 ;
i
r Bif-1 and 2 ODCM APPENDIX B TABLE B:la INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES BV-1 PVR INPUTS VALUE Thermal Power Level (megavatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 345.000 Percent Fuel Vith Cladding Defects .120 Primary System Letdown Rate (gpm) 60.000 Letdovn Cation Demineralizer Flov 6.000 Number Of Steam Generators 3.000 Total Steam Flov (million lbs/hr) 11.620 Mass Of Steam In Each Steam Generator (thousand lbs) 6.772 Mass Of Liquid In Each Steam Generator (thousand Ibs) 97.000 Total Mass Of Secondary Coolant (thousand Ibs) 1296.000 Mass Of Vater In Steam Generator (thousand lbs) 291.000 Blovdown Rate (thousand Ibs/hr) 33.900 Primary To Secondary Leak Rate (1bs/ 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) 22.500 BV-1 LIQUID VASTE INPUTS COLLECTION DELAY DECONTAMINATION 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 IE7 1E7 Drains Clean Vaste' 7.50E1 1.000 1.000 0.071 0.648 IES 2E4 1ES Input Dirty Vaste 1.35E3 0.035 1.000 0.071 0.648 IES 2E4 1E5 Input Blovdown 9.75E4 --
1.000 0.071 0.648 1ES 2E4 1ES Untreated 0.0 -- -- -- -- -- -- --
Blovdown O
B-2 ISSUE 3 Revision 1
BV-1 end 2 ODCM APPENDIX B TABLE B:1b
()
INPUTS TO SVEC LIQ 1BB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PVR INPUTS VALUE Thermal Pover 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 Ibs/hr) 11.600-Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 Mass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand lbs)- 2000.000 Mass Of Vater In Steam Generator (thousand lbs) 298.000 Blovdown Rate (thousand lbs/hr) 22.300 Primary To Secondary Leak Rate (1bs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction .700 Radvaste Dilution Flov (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 i Miscellaneous 700 0.010 1.0 35.5 6.2 1E3 1E4 1E4 Sources Rx Plant
- 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 1E3 1E4 1E4 Rinse Water CVCS 60 -- 1.0 1300 173 1E4 4E3 1E5 I' Turbine Bldg. 7200 -- 1.0 -- -- -- -- --
Drains-B-3 ISSUE 3.
Revision 1
BV-1 and 2 ODCM APPENDIX B TABLE B:2a o N /
INPUTS TO SVEC GAS 1BB CODE FOR GENERATION OF BV-1 GASE0US SOURCE TERM MIXES BV-1 PVR INPUTS VALUE Thermal Power Level (megavatts) 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 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 lbs) 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 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 Flov Fraction 0.000 Radvaste Dilution Flov (thousand gpm) 15.000 BV-1 GASE0US VASTE INPUTS VALUE 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 Frequency Of Primary Coolant Degassing (times /yr) 2.000 Primary To Secondary Leak Rate (lb/ day) 100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand efm) 2.000 Purge Time Of Containment (hours) 8.000 There Is Not A Condensate Demineralizer Iodine Part,ition Factor (gas / liq) In Steam Generator 0.010 Frequency Of Containment Building High Vol Purge (times /yr)* 4.000 Containment Volume Purge Iodine Release Fraction 1.000 Particulate Release Fraction 1.000 Steam Leak To Turbine Building (lbs/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
- 2 cold and 2 hot purges B-4 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX B TABLE B:2b
' INPUTS TO SVEC GASlBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES !
BV-2 PVR INPUTS VALUE ,
. Thermal Power Level _(megavatts) 2766.000 ;
Plant. Capacity Factor .800
, Mass Of Primary Coolant (thousand lbs) 385.000 :
Percent Fuel With Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 !
Total Steam Flov (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 ;
Mass Of Liquid In Each Steam Generator (thousand Ibs) 100.000 i Total Hass Of Secondary Coolant (thousand lbs) 2000.000 i Mass Of Vater In Steam Generator (thousand lbs) 298.000 Blovdown Rate (thousand lbs/hr) 22.300 t Primary To Secondary Leak Rate (1bs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction .700 Radvaste Dilution Flov (thousand gpm) 7.800 BV-2 GASEOUS VASTE INPUTS VALUE
' There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time for Xenon (days) 45.800 Hold Up Time For Krypton (days) 2.570 Primary Coolant Leak To Auxiliary Building (lb/ day) 160.000 Auxiliary Building Leak Iodine Partition Factor 7.5E-3 Gas 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 (lb/ day) 100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand cfm) 20.000 Purge Time Of Containment (hours) 8.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gas / liq) In Steam Generator 0.010 Frequency O'f 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 Blowdown 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 Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS
,O
's ,) This appendix contains procedural details for the Radiological Effluent Technical Specification (RETS) that vere transferred from the Technical Specifications per Unit 1/2 Amendments 188/70, and in accordance with 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 Section 1 of the Technical Specifications and selected applicability and surveillance requirement statements as delineated in Section 3/40 of the Technical Specifications. These vere added to Appendix C for reference purposes, even though they are currently described in the Technical Specification. -
The numbering of each specific Control, Surveillance Requirement and Table contained in the appendix does not appear to be sequential. This is intentional, as all Control, Surveillance Requirement and Table numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
/~'h U
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l 1 I
i b[\
C-1 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these CONTROLS.
THERMAL POWER 1.2 THERMAL POVER shall be the total reactor core heat transfer rate to the reactor coolant.
RATED THERMAL POWER 1.3 RATED THERMAL POVER shall be a total reactor core heat transfer rate to the reactor coolant of 2652 MVt.
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 e._ch principal CONTROL and shall be part of the CONTROLS.
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 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
CHANNEL CALIBRATION 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, cverlapping, cc total channel steps such that the entire channel is calibrated.
C-2 ISSUE 3 Revision 1
. . .- - _ . _ _ _ - ~ _ .
-BV-1 and'2 ODCM APPENDIX C ODCM CONTROLS l l-A- .CONTROLSi DEFINITIONS (continued) ;
U !
lL CHANNEL CHECK l .
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-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 t 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. !
q 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 l l i 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
OFFSITE DOSE CALCULATION MANUAL (ODCM) l.30 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology 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 ,
contain (1) the Radioactive Effluent Controls and Radiological l Envir'onmental 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.
l GASEOUS RADVASTE TREATMENT SYSTEM 1.31 A GASEOUS RADVASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant h
d system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to f the environment.
C-3 ISSUE 3 I
Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS (continued)
VENTILATION EXHAUST TREATMENT SYSTEM 1.32 VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing lodines 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 gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
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 1.34 VENTING 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 not provided or required during VENTING. Vent, used in system names, does not imply a VENTING process.
MEMBER (S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all individuals in a controlled or unrestricted area. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives occupational dose. 8/9 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 B0UNDARY 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. For gaseous release dose calculations, the UNRESTRICTED AREA should exclude any public road, railway, or watervay adjacent to or crossing the site that is not occupied continuously by MEMBER (S) 0F TH PUBLIC.
8A O
C-4 ISSUE 3 Revision 1 i
BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS TABLE 1.1 OPERATIONAL MODES o
REACTIVITY % RATED AVERAGE COOLANT THERMAL POWER
- TEMPERATURE MODE CONDITION, K,gg
- 1. Power Operation >0.99' >5% >350'F
- 2. Startup >0.99 f5% >350'F
- 3. Hot Standby <0.99 0 >350'F
- 4. Hot Shutdown <0.99 0 350'F >T
>200*F avs
- 5. Cold Shutdown <0.99 0 3200*F
- 6. Refueling ** 0 3140*F 30.95 O
- Excluding decay heat.
O ** Reactor vessel head unbolted or removed and fuel in the vessel.
C-5 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROL 5 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 O 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 P Completed prior to each release N.A. Not applicable O
1 0' .
C-6 ISSUE 3 l 1
BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS C'# 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 CONTROL 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 within 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 SHUTDOVN vithin the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operatio.1 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 CONTROLnot aremet not within met and the associated a specified time ACTION requires a shutdown if they are interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTTON requirements when conformance to them permits 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 nCTION requirements. Exceptions to these requirements are stated in the individual CONTROLS.
O !
C-7 ISSUE 3 l
J
BV-1 cnd 2 ODCM APPENDIX C ODCH 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.
O O.'
C-8 ISSUE 3
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS (d CONTROLS: RADI0 ACTIVE 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 with 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'vith Section 1.1.1 and 1.1.2 of this manual.
Applicability:
During releases through the flow path.
Actions
- a. Vith 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 O conservatively reduce the alarm setpoint. Exert a best effort to return the N b 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.
-4.3.3.9 Each 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.
df I C-9 ISSUE 3
BV-1 and 2 ODCM i
APPENDIX C ODCM CONTROLS l TABLE 3.3-12 BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION HINIMUM CHANNELS
. INSTRUMENT OPERABLE ACTION
- 1. Gross Activity Monitors Providing Automatic Termination Of Release
- a. Liquid Vaste Effluents Monitor (RM-LV-104) (1) 23
- b. Liquid Vaste Contaminated Drain Monitor (RM-LV-116) (1) 23
- c. Auxiliary Feed Pump Bay Drain Monitor (RM-DA-100) (1) 24
- 2. Gross Activity Monitors Not Providing Termination Of Release
- a. Component Cooling-Recirculation Spray Heat (1) 24 Exchangers River Vater Monitor (RM-RV-100)
- 3. Flow Rate Measurement Devices
- a. Liquid Radvaste Effluent Line (1) 25 <
(1) FR-LV-103/RM-LV-116 (2) FR-LV-104/RM-LV-104
- b. Cooling Tower Blowdown Line (1) 25 (1) FT-CV-101 (2) FT-CV-101-1
- 4. Tank Level Indicating Devices (for tanks outside plant building)
- a. Primary Water 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
- d. Steam Generator Drain Tank (LV-TK-7B) (1) 26 O
C-10 ISSUE 3 i
i
____-_i
- _ _ . ~. .. . - .- . . . . .- . . - - . . . . . . . . . . .-
BV-1 and 2 ODCM ;
APPENDIX C ODCM CONTROLS
() TABLE 3.3-12 (continued)
BV-2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1
1 1
MINIMUM
' CHANNELS INSTRUMENT OPERABLE ACTION j
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
-s. Liquid Vaste Process Effluent Monitor (2SGC-RQ100) (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 Cooling Tower Blovdown Line (2CVS-FT101) (1) 25
- b. ,,
- 4. Tank Level Indicating Devices (for tanks outside
( plant buildings)
None l l
l C-11 ISSUE 3 i
BU-l and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-12 (continued) 1 ACTION STATEMENTS 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 oc gamma) at a Lover Limit of Detection (LLD) of at least lE-7 uCi/ml.
Action 25 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 /> during actual releases. Pump curves may be used to estimate flow.
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.
O C-12 ISSUE 3
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12
.J BV-1 RADIOACTIVE 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) O(1)
(RM-LV-104)
- b. Liquid Vaste Contaminated D P(5) R(3) O(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 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 Blovdown Line D(4) NA R 0 (FT-CV-101, 101-1) i C-13 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS l
TABLE 4.3-12 (continued)
BV-1 RADIOACTIVE LIQUID EFPLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL j CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 4. Tank Level Indicating Devices !
(for tanks outside plant buildings)
- a. Primary Water Storage Tank D* NA R 0 (BR-TK-6A) 1
- b. Primary Vater Storage Tank D* NA R 0 1 (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)
O
)
)
l I
- During liquid additions to the tank. 4 C-14 ISSUE 3 )
. I
i BV-1 cud 2 ODCM APPENDIX C '
ODCM CONTROLS
() TABLE 4.3-12 (continued)
BV-2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION TEST INSTRUMENT
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. Liquid Vaste Process Effluent D P(5) R(8)(3) O(7)
- 2. Flow Rate Measurement Devices i Liquid Radvaste Effluent D(4) NA R 0 t a.
Cooling Tower Blowdown Line D(4) NA R 0 l b.
(2CVS-FT101) i
- 3. Tank Level Indicating Devices i
[) (for tanks outside plant buildings) i
\m / ,
None !
?
l 1
l l
C-15 ISSUE 3 I
BV-1 cnd 2 ODCH APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued)
TABLE NOTATION O (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:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Downscale 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. Downscale 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 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 subcequent 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 flow 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.
O C-16 ISSUE 3
i
{ BV-1 and'2 ODCM APPENDIX C ;
ODCM CONTROLS ~
i i
TABLE 4.3-12 (continued) d- i TABLE NOTATION l
l (6) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation l of this pathway .and Control Room Alarm Annunciation occurs when the l 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 l of this pathway and Control Room . Alarm Annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint. ,
l (8) 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. 5 i
l l
I 4
C-17 ISSUE 3 l l
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 6.8.6a, 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. With 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. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Appendix C, Table 3.3-13 or d, conservatively reduce the alarm setpoint. Exert a best effort to return the Y channel to operable status within 30 days, and if unsuccessful, explain in ,
the next Annual Radioactive Effluent Release Report why the inoperability 6hr was not corrected in a timely manner.
- c. The provisions of Appendix C CONTROL 3.0.3 are not applicable, b 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 shovn in Appendix C, Table 4.3-13.
Ol C-18 ISSUE 3 l
l
BV-1 end 2 ODCM APPENDIX C ODCH CONTROLS (j 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.Flov Rate 28 i Flow Rate Measurement Measuring Device
~(FR-GV-108) or .f (RM-GV-109 Ch 10) {-
- d. Sampler Flow (1)
- Sampler Flow Rate 28 Q(~'N Rate Measuring Heasurement i
Device ;
- 2. Auxiliary Building Ventilation System (RM-VS-101A&B).
- Radioactivity Rate. 29,30***
- a. Noble Gas (1)
Activity Monitor Measurement
- b. Particulate (1)
- 32 {
Activity Monitor j
- c. System Effluent (1)
- System Flow Rate 28 ! '
Flov Rate Measurement Heasuring Device (FR-VS-101) or-(RM-VS-109 Ch 10)
- d. Sampler Flov (1)
- Sampler Flov Rate- 28 Rate Measuring Measurement Device
- During Releases via this pathway.
- During purging of Reactor Containment via this pathway. 4 C-19 ISSUE 3 Revision 1 l l
BU-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS !
TABLE 3.3-13 (continued) l BV-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION l
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-112) or (RM-VS-110 Ch 10)
- d. Sampler Flov (1)
- Sampler Flow Rate 28 Rate Measuring Measurement Device O
C-20 ISSUE 3 ;
Revision 1 1 i
l
BV-1 and 2 ODCH APPENDIX C !
ODCM CONTROLS TABLE 3.3-13'(continued)
BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION HINIMUM CHANNELS
' INSTRUMENT OPERABLE- APPLICABILITY ' PARAMETER ACTION
- 1. Ventilation System (2HVS-R0101A&B) j
- a. Noble Gas- 1
- Radioactivity Rate 29,30***-
Activity Monitor Measurement
- 32
'I
- b. . Particulate' 1 Activity Monitor ,
- c. Process Flov 1
- Process Flow Rate 28 Rate Monitor Measurement
- d. Sampler Flow 1
- Sampler Flov Rate 28 Rate Monitor Measurement, 2.- Elevated Release (2HVS-R0109A&B) 7)
' a. Noble Gas 1
- Radioactivity Rate 29,30*** ,
Activity Monitor Measurement j
- 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 1
- 3. Decontamination Bldg. '
Vent (2RM0-R0301A&B)
- a. Noble Gas 1
- Radioactivity Rate 29 Act'ivity Monitor Measurement
- b. Particulate 1
- 32 -
Activity Monitor
- c. Process Flov None None Process Flow Rate =None Rate Monitor Measurement !
- d. Sampler Flov 1
- Sampler Flov Rate 28 .
O Rate Monitor Measurement i C-21 ISSUE 3 I
Revision 1 i
l BU-1 and 2 ODCH l APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued)
BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION HINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION l
- 4. Condensate Polishing Building Vent (2HVL-R0112A&B)
I a. Noble Gas 1
- Radioactivity Rate 29 Activity Monitor Measurement
- b. Particulate 1
- 32 Activity Monitor
- c. Process Flov None None Process Flov Rate' Rate Monitor Measurement None,b i d. Sampler Flov 1
- Sampler Flov Rate 28 Rate Monitor Measurement
- 5. Vaste Gas Storage Vault (2RM0-R0303A&B)
- a. Noble Gas 1
- Radioactivity Rate 29 Activity Monitor Measurement
- b. Particulate 1
- 32 Activity Monitor
- c. Process Flov None None Process Flov Rate None Rate Monitor Measurement Yi
- d. Sampler Flov 1
- Sampler Flov Rate 28 Rate Monitor Measurement l
i 1
C-22 ISSUE 3 Revision 1 l l
I l
l
..m .. , . . .
I BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS O
%J 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 may 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 Facility Staff independently verify the release rate calculations and discharge valve lineup, 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 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 channels 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 FOR 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.
O C-23 ISSUE 3
BU-l and 2 ODCH APPENDIX C ODCH CONTROLS TABLE 3.3-13 (continued)
ACTION STATEHENTS e
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 />.
O l
l 9
C-24 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS
/ TABLE 4.3-13 BV-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. Gaseous Vaste/ Process Vent System (RM-GV-108A&B)
- a. Noble Cas Activity Monitor P P(4) R(3) 0(1)
- b. Particulate Activity Monitor V NA NA NA
- c. System Effluent Flow Rate P NA R 0 Measuring Device (FR-GV-108) g or (RM-GV-109 Ch 10)
- d. Sampler Flow Rate Measuring D* NA R 0 Device
- 2. Auxiliary Building Ventilation System (RM-VS-101A&B)
,m, a. Noble Gas Activity Monitor D M(4), R(3) 0(2)
( ) P(4)***
U b. Particulate Activity Monitor V NA NA NA
- c. System Effluent Flov Rate D NA R 0 Measurement Device (FR-VS-101) or (RM-VS-109 Ch 10) b
- d. Sampler Flow Rate Measuring D NA R 0 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) l P(4)***
- b. Par'ticulate Activity Monitor V NA NA NA
- c. System Effluent Flov Rate D NA R 0 Heasuring Device (FR-VS-112) 4.f or (RM-VS-110 Ch 10) 16
- d. Sampler Flow Rate Measuring D NA R 0 l Device
[d
't *During releases via this pathway.
- During purging of Reactor Containment via this pathway.
C-25 ISSUE 3 Revision 1 l
I l
BV-1 rnd 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-13 (continued)
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)
P(4)***
- b. Particulate Activity Monitor V NA NA ha
- c. Process Flov Rate Monitor D NA R 0
- d. Sampler Flov Rate Monitor D NA R 0
- 2. Elevated Release (2HVS-R0109A&B)
- a. Noble Gas Activity Monitor D M(4), R(3)(6) 0(5)
P(4)***
- b. Particulate Act.ivity Monitor V NA NA NA
- c. Process Flow Rate Monitor D NA R 0
- d. Sampler Flow Rate Monitor D NA R 0
- 3. Decontamination Bldg. Vent (2RMQ-RQ301A&B)
- a. Noble Gas Activity Monitor D M(4) R(3)(6) 0(5)
- b. Particulate Activity Monitor V NA NA NA
- c. Process Flov Rate Monitor NA NA NA NA
- d. Sampler Flow Rate Monitor D NA R 0
- 4. Condensate Polishing Building Vent (211VL-R0112A&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 NA NA NA NA
- d. Sampler Flow Rate Monitor D NA R 0 e'
C-26 ISSUE 3 Revision 1 1
. . . ~ . - - _ _ . - . . - _ . . - . - . . - - . . - . . . _ . . - . _ . . . - - . _ -
t BV-1 and 2 ODCM APPENDIX C r ODCH CONTROLS t TABLE 4.3-13'(continued)
BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING
' INSTRUMENTATION SURVEILLANCE REQUIREMENTS (
CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL !
INSTRUMENT- CHECK CHECK CALIBRATION TEST
- 5. Vaste Gas Storage-Vault !
(2RMO-RQ303A&B)
. . . i
- a. Noble Gas Activity Monitor D M(4) R(3)(6) Q(5)
- b. Particulate Activity. Monitor V NAL NA NA l
- c. Process Flow Rate Monitor NA NA NA NA
- d. Sampler Flov Rate Monitor- D NA R 0 I
-i O !
1 i
l l
l C-27 ' ISSUE 3 i Revision 1 1 i
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-13 (continued)
TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway ar.d 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.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm Annunciation occurs if any of the following conditions exists
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Downscale failure.
- c. Instrument controls 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 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 obtain an upscale increase in the existing count rate to verify channel response.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm i Annunciation occurs if the instrument indicates neasured levels above the alarm / trip setpo'.nt.
(6) The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm i Annunciation occurs if either of the following conditions exist:
- 1. Downscale failure.
1
- 2. Instrument controls are not set in operate mode. l l
l C-28 ISSUE 3
BV-1 and 2 ODCM APPENDIX C . ,
ODCH CONTROLS CONTROLS: LIQUID EFFLUENT CONCENTRATION 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 relea' sed at .
any time from the site (see Figure 5-1) shall be limited to 10 times i the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20.2401), ;
Table 2, Column 2'for radionuclides other than dissolved or entrained ;
noble gases. This is referred to as.the ODCM Effluent Concentration l
' Limit (0EC). For dissolved or entrained noble gases, the '
concentration shall be limited to 2E-4 uCi/ml total activity. 8/9 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. )
g .
t c. The provisions of Appendix C CONTROL 3.0.3 are not applicable. l 1
I SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid vastes shall be sampled and analyzed according to l the sampling and analysis program of Appendix C, Table 4.11-1*. )
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 BV-1 primary to secondary leakage exceeds 0.1 gpm (142 gpd),
samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to ensure that the Turbine Building Sump concentration does not I
' exceed 1 OEC. Once it is determined. that an OEC is reached, th Turbine Building Sump shall be routed to the Chemical Vaste Sump.
C-29 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.11.1.1.4 When BV-2 primary to secondary leakage exceeds 0.1 gpm (142 gpd),
samples of the Turbine Building Sump shall be obtained every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to ensure that the Turbine Building Sump concentration does not exceed 1 OEC. Once it is determined that an OEC is reached, the Turbine Building Sump shall be routed to Steam Generator blowdown hold tank (2SGC-TK21A or 2SGC-TK21B). p 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 IE-7 uCi/ml. Vater volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided.
O 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 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 Appendi,: C SURVEILLANCE REQUIREMENT 4.11.1.1.5 respectively.
O C-30 ISSUE 3 Revision 1
~BV-1 and 2 CDCM APPENDIX C ,
0DCM CONTROLS TABLE 4.11-1 RADIOACTIVE LIQUID VASTE SAMPLING AND ANALYSIS PROGRAM i
l l
i MINIMUM .
L LIQUID RELEASE ' SAMPLING ANALYSIS TYPE OF ACTIVITY LOVER LIMIT i
TYPE FREQUENCY -FREQUENCY ANALYSIS OF DETECTION '
i (LLD) l ,.
1 (uCi/ml)" i i
A. Batch Vaste d
P h
P PrincipalfGamma SE-7
. Release Tanks Each Batch - Each Batch h Emitters 1, ,
I-131' IE-6 l P h
M Dissolved And. 1E-5
'. One Batch /M Entrained Gases (Gamma Emitters)
P M M 1E-5 -;
h b Each Batch Composite '
Gross Alpha 1E-7 Sr-89, Sr-90 O" P Each Batch h
Q Composite b.
B.Continuog& Grab Sample V Principal Gamma SE-7 c
Releases Composite Emitters f !
g Grab Sample M' Dissolved And 1E-5 '
Entrained Gases (Gamma Emitters)
Grab Sample 8 M Composite
Grab Sample 0 Sr-89, Sr.-90 SE-8 c
\.)
C-31 ISSUE 3 Revision 1 ,
BV-1 end 2 ODCH 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 concluding that a blank observation represents a "real" signal.with 5% probability For a particular separation): measurement system (which may include radiochemical LLD = 4.66 S (E)(V)(2.22)(Y)bexp(- AoT) where LLD is mass or the lover limit of detection as defined above (as pCi per unit volume);
s h is the standard deviation of the background counting rate or of the counting 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);
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:
6T 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).
The value of us used in the calculation of the LLD for a detection n system shall counting ratebM based on the actual observed variance of the background or of the counting rate of the blank samples (as appropriate) rather variance. Typical values thanofon an unverified theoretically predicted g E, V, calculations. Y and oT should be used in the y Thei,LDisdefinedasan 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. l l
C-32 O
ISSUE 3
l l
BV-1 end 2 ODCH APPENDIX C ODCM CONTROLS
\ TABLE 4.11-1 (continued)
]
TABLE NOTATION l I
- 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- J 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 solume. 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. Releases .from the Turbine Building drains and the AFU Pump Bay Drain System and chemical vaste' sump'are considered
- n. continuous when the primary to secondary leak rate exceeds'O.1 gpm (149 Q gpd).
- f. The principal gamma emitters for which the LLD specification will apply are exclusively the following' radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-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 below 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 that nuclide. The "less than" values should not be used in the required dose calculations. 'When unusual circumstances result in LLD's higher than' required, the reasone shall be documented in the Annual Radioactive Effluent Release Report. M'
- g. When radioactivity-is identified in the secondary system, a RVDA-L should be prepared on a monthly basis to account for the radioactivity that vil eventually be discharged to the Ohio River. Ys' 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.
i O
C-33 ISSUE 3 Revision 1 i
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 &
proposed corrective actions to be taken to assure the subsequent releases W vill be within the above limits. (This Special Report shall also include (1) the results of radiological analyses of the drinking vater source and (2) the radiological impact on' finished drinking vater 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 accordance with Section 1.3 of this manual at least once per 31 days.
- Applicable only if drinking water supply is taken from the receiving vater body within three miles of the plant discharge (three miles downstream only).
C-34 ISSUE 3 Revision 1
BV-1 and 2 ODCM-APPENDIX C ODCH CONTROLS O'"' CONTROLS's 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. Vith liquid vaste being discharged without treatment and exceeding the limits specified, ' prepare and submit to the Commission .vithin 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.
f-~s. 2. Action (s) taken to restore the inoperable equipment to operational status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
1
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable. l SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 j days, in accordance with Section 1.3 of this manual.
1 i
I l
rm C-35 ISSUE 3 Revision 1 N
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 f 500 mrem /yr to the total body and f 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 f 1500 mrem /yr to any organ.
Applicability:
~At all times.
Actions
- 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-36 ISSUE 3 Revision 1
,- . - - . . . . . . - ~. .. .- .. .- .. .. . .. . . _
IBV-1 End 2 ODCM zAPPENDIX C. !
ODCM CONTROLS l
( ,j TABLE 4.11-2
.RADI0 ACTIVE GASEOUS VASTE' SAMPLING AND ANALYSIS PROGRAM ,
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 IE-4 Tank. Each Tank Each Tank- Emittersg ;
B. Containment Purge P- P Principal Gamma. 1E-4 ,
b b Each Purge Each Purge EmittersE- ;
H-3. .1E-6 b ,c,e, gb Principal Gamma' IE-4 C.Ventilagion M g Systems Grab Sample Emitters
- 1. Unit i Ventila- _;
- 2. Unit 1 Contain-ment /SLCRS Vent }*
- 3. Unit.1/2 Process O. 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 I Storage Vault Vent
- 8. Unit 2 Condensate Polishing Bldg. !
Vent f
1 l
l C-37 ISSUE 3 Revision 1 l
l 1
i BV-1 cnd 2 ODCM l APPENDIX C ODCM CONTROLS
]
TABLE 4.11-2 (continued) i RADIOACTIVE GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM l MINIMUM LOVER LIMIT OF i SAMPLING ANALYSIS TYPE OF '
GASEOUS RELEASE TYPE DETECTION,(LLD)
FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)
D. All Systems f d Continuous V I-131 1E-12 !
Listed Above Charcoal I Which Produce Sample I-133 1E-10 l Continuous Belease Continuous f d V Principal Gamma IE-11 Particulate Emitters 8 Sample (I-131, Others)
Continuous f M Gross Alpha 1E-11 Composite Particulate Sample i f
Continuous 0 Sr-89, Sr-90 1E-11 Composite '
Particulate i Sample f
Continuous Noble Gas Noble Gases 1E-6 Monitor Gross Beta A:id Gamma 4
9 O
C ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS Q TABLE 4.11-2 (continued)
TABLE NOTATION t
- a. The Lover 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 POWER 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 af ter removal' from sampler. _l 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% l 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 and analyses shall be. l
, 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 /> i are analyzed, the corresponding LLDs may be increased by a factor of 10. I g This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more 1\ ]- than a factor of 3; and (2) the noble gas monitor shows that effluent 1 activity has not increased more than a factor of 3.
I 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.
l f. The average ratio of the sample flow rate to the sampled stream flow rate
' shall 'e known. for the time period covered by each dose or dose rate 4
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 J 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, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.
This li'st 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. When 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.
1(v C-39 ISSUE 3 Revision 1
BV-1 rnd 2 ODCM APPENDIX C ODCM CONTROLS l CONTROLS: DOSE-NOBLE GASES 9,
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 f 5 mrad for gamma radiation and f 10 mrad for beta radiation.
- b. During any calendar year, to f 10 mrad for gamma radiation and 3 20 mrad for beta radiation.
Applicability:
At all times.
Actions
- a. Vith 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 vill 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.
O I C-40 ISSUE 3 l Revision 1 ;
l
! l l
l BV-1 and 2 ODCM l l l APPENDIX C l ODCM CONTROLS
' ' f~) .
! V CONTROLS: DOSE-RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND l
i: RADIONUCLIDES OTHER THAN NOBLE GASES i
l 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'radioio'ines d l' and radioactive materials in particular form (excluding C-14), and radionuclides (other than noble gases) vith half-lives greater than l
l eight days in gaseous effluents releases from the reactor unit (see l
Figure 5-1) shall be limited to-the following:
- a. During any calendar quarter to 5 7.5 mrem to any organ, and
- b. During any calendar year to f 15 mrem to any. organ.
Applicability:
At all times.
l Action:
- a. Vith the calculated dose from .the release of radioiodines, radioactive- h materials in particulate form, (excluding C-14), and radionuclides (other j than noble gases) with half-lives greater than eight days, in gaseous p effluents exceeding any of the above . limits,- prepare and submit to the ;
Commission within 30 days, pursuant to Technical Specification 6.9.2f, a
, V)
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.
i b. The provisions of Appendix C CONTROL 3.0.3 are not applicable, j i
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.
i Dr V .
C-41 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: GASEOUS RADVASTE TREATMENT SYSTEM 3.11.2.4 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, 1 Item 6, the Gaseous Radvaste Treatment System and the Ventilation I 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, vould 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 vould 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 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 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 4.11.2.4.1 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.
O C-42 ISSUE 3 ,
Revision 1 l l
l
- - . - . . _. - - . - . _. . . _ .~ ~- -- - . _ . - .. . . , _ _
BV-1 and 2 ODCM [
APPENDIX C ;
ODCH CONTROLS ;
O +
! V' CONTROLS: TOTAL DOSE j
i 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 co.mitment to any MEMBER OF THE PUBLIC due to releases of radioactivity ar.d t . tion j from uranium fuel cycle sources shall be limited to < 25 m.emt, i the j vhole body or any organ, except the thyroid, which shall be ,ed to l 3 75 mrems. l i
Applicability: !
At all. times.
i Actions j
- a. Vith 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, calculations shall be made including direct radiation contributions'from the units (including outside storage tanks, etc.) to determine whether the above limity of Appendix C CONTROL 3.11.4.1 have been exceeded. If such is the i case, prepare and submit to the Commission within 30 days, pursuant to. ')
Technicsl 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 includes the schedule -for achieving j conformance with the above limits. .This Special Report, as defined in 1 10 CFR 20.405(c), shall include an analysis that estimates the radiation j exposure (dose) to a HEMBER 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 contentrations. . 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.
i
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable. !
I i
v C-43 ISSUE 3 Revision 1 l
BF-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 REQUIREMENTS 4.11.1.2.a. 4.11.1.2.b, 4.11.2.2.a, 4.11.2.2.b, 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.
O l
l O'
C-44 ISSUE 3 Revision 1
4 BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS
.(h 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. With the radiological environmental monitoring program not being conducted '
as specified in Appendix C, Table 3.12-1, prepare and subait 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. With 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 l
- ( 's' ') 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 l
calendar quarter a Special Report pursuant to Technical Specification 6.9.2f which includes an evaluation of any re lease 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.
1 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 accordante with Appendix C CONTROL 3.12.2 and listed in the ODCM, 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 ODCM provided the locations from which the replacement samples were obtained are added to the env' ,imental monitoring program as replacement locations, if available.
- d. The provisions of Appendix C CONTROL 3.0.3 are not app 4 cable.
\ :
(~'Y
\ u-i C-45 ISSUE 3 f
Revision 1 I
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (ctntinued) 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.
O O
C-46 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCM CONTROLS A
(,) TABLE 3.12-1 i RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND COLLECTION TYPE AND FREQUENCY I ")
EXPOSURE PATHVAY NUMBER OF SAMPLES AND/OR SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS
- 1. AIRBORNE
- a. Radioiodine 5 locations. Continuous opera- Each radioiodine ,
And tion of sampler canister.
Particulates 1. One sample from with sample col-a control loca- lection at least Analyze for I-131; tion 10-20 weekly.
miles distant Particulate sampler, and in the Analyze for gross least prevalent beta weekly g); 7 wind direction. !
Perform gamma isoto-
- 2. One sample from pic analysis on vicinity of composite (by loca-community tion) sample at having the least quarterly.
,- highest calcu-lated annual (v ) average ground ,
level D/0
- 2. DIRECT 40 locations. Continuous Gamma dose, RADIATION measurement with quarterly.
2 TLD or a pres- collection at surized ion least quarterly.
chamber at each location.
Analysis frequency same as sampling frequency unless otherwise specified.
Particulate samples are not counted for 224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br /> 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.
(J)
C-47 ISSUE 3 Revision 1
BV-1 end 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.12-1 (continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHVAY NUMBER OF SAMPLES COLLECTION TYPE AND FREQUENCY (a)
AND/OR SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS
- 3. WATERBORNE
- 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; exceed 2 weeks.
Gamma isotopic analy-sis of composite sample (by location) monthly; Tritium analysis of composite sample quarterly.
- c. Groundwater N/A - No vells in lover elevations between plant and river.
- d. Sediment From 1 location. Semi-annually. Gamma isotopic analy-Shoreline sis semi-annually.
I") Analysis frequency same as sampling frequency unless otherwise specified.
- 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-48 ISSUE 3 Revision 1
'BV-1 and 2.0DCM APPENDIX C ODCM CONTROLS p).
( TABLE 3.12-l~(continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND EXPOSURE PATHVAY' NUMBER OF SAMPLES CGLLECTION TYPE AND FREQUENCY (*)
AND/OR SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS
- 4. INGESTION
- a. Milk 4 locations.(C} 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. Fish 2 locations. Semi-annual. One Gamma isotopic.
O sample of avail-- analysis on edible able species. portions.- j
- c. Food 4 locations. Annually at time. Gamma' isotopic -I Products .
of harvest. analysis and I-131 l (Leafy 1. Three locations ,
analysis on edible :
Vegetables) within 5 miles, portion..
- 2. One control l location.
Analysis frequency same as sampling frequency unless otherwise specified.
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.
C-49 ISSUE 3 Revision 1
BV-1 ond 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 HILK VEGETABLES ANALYSIS (pCi/1) (pC1/m3 ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET)
H-3 2E+4(")
i 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 I")For drinking vater samples. This is a 40 CFR Part 141 value.
O C-50 ISSUE 3 Revision 1
BV-1 cnd 2 ODCM APPENDIX C ODCH CONTROLS n
(ss ) TABLE 4.12-1
, HAXIMUM VALUES FOR THE LOVER LIMITS OF DETECTION (LLD)"
l l AIRBORNE PARTICUL' ATE ANALYSIS VATER OR GAS FISH HILK FOOD PRODUCTS SEDIMENT (pCi/1) (pCi/m ) (pci/kg, VET) (pCi/l) (pCi/kg, VET) (pCi/kg, DRY)
Gross Beta 4 1E-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 c
Nb-95 15
(-) I-131 l b
7E-2 1 60 Cs-134 15 5E-2 130 15 60 150 Cs-137 18 6E-2 150 18 80 180 C
Ba-140 60 60 C
La-140 15 15 l
l l
I NOTE: This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together
/~' vith the above nuclides, shall be identified and reported.
N. .)T C-51 ISSUE 3 Revision 1
BV-1 end 2 ODCM APPENDIX C ODCH CONTROLS TABLE 4.12-1 (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.
For a particular measurement system (which may include radiochemical separation):
LLD = 4.66 S (E)(V)(2.22)(Y)bexp(- AaT) where:
LLD is the lover limit of detection as defined above (as pCi per unit mass or volume);
Sg 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);
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 collection period) and time of counting (for environmental samples, not plant effluent samples).
The value of Su used in the calculation of the LLD for a detection system shall bM 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.
O C-52 ISSUE 3 Revision 1
. . . . . . - . . . - . . - . . . - . . ... . . - . . . - - - = _ _ . . _ . . . _ ,
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.12-1 (continued)
TABLE NOTATION
- b. LLD for drinking water.
- c. If parent and daughter are totaled, the most restrictive LLD should be applied.
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C-53 ISSUE 3 Revision 1
BV-1 and 2 ODCM APPENDZX 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. With 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 pr.ovisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 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.
- Confirnation by telephone is equivalent to door-to-door.
C-54 ISSUE 3 Revision 1
l BV-1 and 2 ODCM ;
APPENDIX C ODCM CONTROLS
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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, L analyses shall be performed on radioactive materials supplied as part of I an Interlaboratory Comparison Program. i Applicability.
-At all times. 1 Actions i
- a. Vith' 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 l
.h Interlaboratory Comparison Program shall be included in the Annual
'.. Radiological Environmental Report.- ;
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i C-55 ISSUE 3 I Revision 1 !
BV-l'end 2 ODCH APPENDIX D !
BASES FOR ODCH CONTROLS l LyS 'l
,( j This appendix contains the ' Bases for the ODCH Controls that vere transferred ;
l from the Bases Section of the Technical Specification per Unit 1/2 Ar.endments ;
188/70,'and in accordance with Generic Letter 89-01 and Generic Letter 89-01, l
, Supplement No. 1 (NUREG-1301). g(
The numbering of each specific Bases contained in this appendix does not appear l to be sequential. 'This is intentional, .as all Bases numbers remained the same vhen they were' transferred from the . Technical Specifications. .This was done in ;
an effort to minimize the amount of plant procedure changes and'co eliminate any l
-confusion associated with numbering changes. !
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D-1 ISSUE 3 .
Revision 1 l
i BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: INSTRUMENTATION 3/4.3.3.9 RADI0 ACTIVE 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 t
I 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 will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to'10 CFR Part 50.
3/4.3.3.10 RADI0 ACTIVE GASE0US EFFLUENT HONITORING INSTRUMENTATION I
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive 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 l manual to ensure that the alarm / trip will 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.
The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of l l Appendix A to 10 CFR Part 50.
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D-2 ISSUE 3 Revision 1 l
BV-1 end 2 ODCM APPENDIX D BASES FOR ODCH CONTROLS ,
BASES: LIQUID EFFLUENTS 3/4.11.1.1 LIQUID EFFLUENT CONCENTRATION This CONTROL is provided to ensure that the concentration of i -radioactive materials released in Liquid vaste effluents from the i site to unrestricted areas vill be less than 10 times the EC's specified in 10 CFR Part 20, Appendix B (20.1001-20-2401), Table 2, 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 50, to an individual and (2) i the limits of 10 CFR Part 20.1302 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 HPC in air (submersion) was converted to an equivalent concentration in water using the methods described in Internationa
~
Commission on Radiological Protection (ICRP) Publication 2.
3/4.11.1.2 LIQUID EFFLUENT DOSE 4
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 f- g Limiting Condition for Operat in 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 j guides set forth in Section IV.A of Appendix I to assure that the i releases of radioactive material in liquid effluents vill be kept j "as lov as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility vill not result in radionuclide concentrations in '
the finished drinking water 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.
.(.b) .
D-3 ISSUE 3 Revision 1
1 BU-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS l BASES: LIQUID EFFLUENTS (continued)
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 low 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 obj ec tive 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 treatment 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, for liquid effluents. This specification applies to Beaver Valley Power Station, Unit No. 1 or Unit No. 2.
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D-4 ISSUE 3 Revision 1
BV-1 and 2 ODCM I APPENDIX D l BASES FOR ODCM CONTROLS
BASES: GASEOUS EFFLUENTS l
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. l 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 i site boundary, the occupancy of the individual vill be sufficiently i lov to compensate for any increase in the atmospheric diffusion l factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose 1 rates above background to an individual at or beyond the site i boundary to j 500 mrem / year to the total body or to f 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.
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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 will be kept "as low 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 this manual for calculating the doses due to the actual release rates of radioactive noble gases in gaseous 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 With 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide l
1.111, "Hethods 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 the exclusion area boundary, and are based upon the historical average
(J)
L D-5 ISSUE 3 Revision 1 I
BV-1 cnd 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, RADI0 ACTIVE 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 will 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 subj ec t 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 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. 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 pathways 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. l O ,
D-6 ISSUE 3 l Revision 1 l
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. - . .~..-.. .. ..- ~ .-. ~ . - ..-. - - - . . - . - . . . - - - . . - - - . . -
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BV-1 and 2 ODCM l
( APPENDIX D L BASES FOR ODCH CONTROLS. -
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-BASES: GASEOUS EFFLUENTS'(continued) l l' 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 !
j radioactive materials in gaseous' effluents vill be kept "as lov as l
is reasonably achievable.". This specification implements 'the !
i, requirements.of 10 CFR Part 50.36a, General Design Criterion 60 of i b 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 objectives set forth in j
l 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. .;
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BV-1 end 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: TOTAL DOSE 3/4.11.4 TOTAL DOSE 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 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 within the 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 within 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 .
Part 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 NRC staff action is completed. The variance only relates to the limits ,
of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in CONTROLS 3.11.1.1 and 3.11.2.1. An individual is not considered a HEMBER 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.
O D-8 ISSUE 3 Revision 1
BV-1 end 2 ODCM APPENDIX D BASES FOR ODCH CONTROLS A
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BASES: RADIOLOGICAL ENVIRONMENTAL MONITORING j l
l 3/4.12.1 MONITORING PROGP.AM 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 highest 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
/ i
\s ) 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 tne 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 pathways 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 COMPARIS0N PROGRAM 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 l
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.
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D-9 ISSUE 3 Revision 1 l
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BV-1 and 2 ODCM APPENDIX E ANNUAL REPORTS
( .This appendix contains the reporting requirements for the Annual Radioactive Effluent Release Report and. the Annual ~ Radiological Environmental Report that were transferred from the Technical-Specification per Unit 1/2 Amendments 188/70 and in accordance with Generic; Letter 89-01 and. Generic Letter 89-01,-Supplement No. 1 (NUREG 1301).
The numbering of'each-specific Report contained in.this appendix does'not appear
- to be sequential. This is intentional, as all Report numbers remained the same when they were transferred from the Technical Specifications. This was done in an effort to~ minimize the amount of plant procedure changes and to eliminate any confusion associated with numbering changes.
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E-1 ISSUE 3 Revision 1 l
BV-1 and 3 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT ANNUAL RADIOLOGICAL ENVIRONMENTAL REPORT 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 with 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 surveillance 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 problem 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-2 O
ISSUE 3 Revision 1
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BV-1 and 2 ODCM APPENDIX E A MUAL REPORIS TABLE E:6.9-1 ;
DNIRONMENTAL RADIOLOGICAL MONI'IORING PROGRAM
SUMMARY
Name Of Facility Docket No.
Location Of Facility Reporting Period (County, State) .
ALL INDICA'IOR IOCATIONS WI'IH HIGIEST MEDIUM OF PA'1HNAY TYPE AND 'ICIAL ICWER LIMITS IDCATIONS AINIAL MEAN CONTROL IDCATIONS SAMPLED NUMBER OF OF NUMBER OF a
(LNIT OF ANALYSES DETECTION MEAN NAME DISTANCE MEAN REPORTABLE MEASUREMENT)- PERFORMED (LLD) .RANGh AND DIRECTION MEAN(h RANG RANGh OCCURRENCES I
I aNominal Lower Limits Of Detection (LLD) as defined in Table Notation a. of Table. 4.11-1 of Appendix C CONTROL 3.11.1.1.
bMean and range based upon detectable measurement only. Fraction of detectable measurement at specified locations is indicated in p renthesis (1).
E-3 ISSUE 3 Revision 1
BV-1 end 2 ODCM APPENDIX E ANNUAL REPORTS ANNUAL REPORT Ol ANNUAL RADIOACTIVE 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 RCH Appendix 5, and at a minimum, shall contai the following: a/tf
- 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 desult in LLD's higher than required by Appendix C, Table 4.11-1 and 4.11-2.
l 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-4 ISSUE 3 Revision 1
BV-1 r.nd 2 ODCH APPENDIX E ANNUAL REPORTS t.
[ ANNUAL REPORT (continued) l
- 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 precioitation (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.
-[D ' An assessment of the radiation doses from radioactive effluents to
() HEMBER(S) 0F THE PUBLIC due to their activities inside the site boundary (Figure 5-1) during the report- period. All assumptions 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 re..ctor 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, (ORNL)) is ,
acceptable for calculating the dose contribution from direct l I
radiation due to N-16.
- If quantities of radioactive materials released during the reporting period are significantly above design objectives, the. report must cover this specifically.
, 10.
U E-5 ISSUE 3 Revision 1
CV-1 and 2 OD:M I Appendix F A ODCM Controls Procedurt Matrix I
This' appendix contains plant procedure references 'for Radiological Effluent Technical Specifications (RETS) that were transferred from the Technical Specification Procedure Matrix. g The numbering of each specific Control, Surveillance Requirement and Table contained ,
in this Appendix does not appear to be sequential. This-is intentional,' as all Control, Surveillance Requirement and Table numbers remained the same when they were transferred from the Technical Specifications Procedure Matrix. This was done in an effort - to minimize the amount of plant procedure changes and - to eliminate any confusion associated with numbering changes.
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BV 1 cnd 2 ODCM APPENDlX F ODCM CONTROLS PROCEDURE MATRIX lo/;
TABLE F:1a BV 1 LIQUID EFFLUENT MONITOR SURVEILLANCES Control Number 3.3.3.09 LIQUID EFFLUENT MONITORS IN APPENDlX C TABLE 3.3.12 OPEF. ABLE APPLICABILITY: DURING RELEASES THROUGH THE FLOW PATH ODCM SR _CySCR;PTP'/N 4.3.3.09 ' PROCEDURE TEST V,0Nh ORS / i TABLE 4.3-12 FREQUENCY 4.3.3.09.1 MONITORS PROVIDING ALARM AND AUTOMATIC TERM 4.3.3.09.1. J LIOUID RADWASTE EFFLUENT MSP 43.18 CHANNEL CALIBRATION LINE (RM LW-104) OM 1.54.3 (L5 ITEM 089) CHANNEL CHECK OM 1/217.4A.D SOURCE CHECK !
OST 1.43.09 FUNCTIONAL TEST 4.3.3.09.1.b l LlOUlD WASTE MSP 43.23 CHANNEL CAL!BRATION CONTAMINATED DRAIN LINE OM 1.54.3 (L5 ITEM 106) CHANNSL CHECK (RM LW 116) OM 1/2.17.4 A.D SOURCE CHECK OST 1.43.09 FUNCTIONAL TEST 4.3.3.09.1.c AUXILIARY FEED PUMP MSP 43.70 CHANNEL CAllBRATION BAY DRAIN MONITOR OM 1.54.3 (L5 ITEM 102) CHANNEL CHECK (RM-DA-100) OM 1.54.3 (L5 ITEM 102a) SOURCE CHECK OST 1.43.09 FUNCTIONAL TES' 4.3.3.09.2 MONITORS PROVIDING ALAF M BUT NO AUTO TERMINATION 4.3.3.09.2.a COMPONENT-COOLING MSF 43.10 CHANNEL CAllBRATION RECIRCULATION SPRAY HX OM 1.54.3 (L5 ITEM 099) CHANNEL CHECK RIVER WATER MONITOR OST 1.43.09 FUNCTIONAL TEST (RM RW-100) OST 1.43.09A SOURCE CHECK 4.3.3.09.3 FLOW RATE MEASUREMENT '
4.3.3.09.3a LIQUlO RADWASTE EFFLUENT MSP 17.05 CHANNEL CAllBRATION LINES MSP 17.06 F-LW-1041 CHANNEL CALIBRATION (FR-LW 103/RM-LW- 116) MSP 17.07 F-LW-104-2 CHANNEL CALIBRATION (FR-LW-104/RM-LW-104) MSP 17.08 F LW-104-1 FUNCTIONAL TEST MSP 17.09 F-LW 104-2 FUNCTIONAL TEST MSP 17.10 F-LW 103 FUNCTIONAL TEST OM 1.54.3 (L5 ITEM 090) FR LW 103 CHANNEL CHECK OM 1.54.3 (L5 ITEM 091) FR-LW 104-1 CHANNEL CHECK OM 1.54.3 (L5 ITEM 092) FR LW-104-2 CHANNEL CHECK 4.3.3.09.3.b COOLING TOWER BLOWDOWN MSP 31.04 F-CW-101 CHANNEL CALIBRATION LINE MSP 31.05 F-CW-101 FUNCTIONAL TEST (FT-CW-101) MSP 31.06 F CW-101 1 CHANNEL CALIBRATION (FT-CW-101 1) MSP 31.07 F-CW-101 1 FW;CTIONAL TEST OM 1.54.3 (L5 ITEM 095) FT-CW-101 CHANNEL CHECK OM 1.54.3 (L5 ITEM 096) FT-CW-101 1 CHANNEL CHECK
_4.3.3.09.4 TANK LEVEL DEVICES 4.3.3.09.4.a PRIMARY WATER STORAGE TANK MSP 08.01 L-PG115A FUNCTIONAL TEST (BR TK-6A) MSP 08.03 L-PG115A CHANNEL CALIBRATION OM 1.54.3 (L5 ITEM 133) WHEN ADD TO TANK 4.3.3.09.4.b PRIMARY WATER STORAGE TANK MSP 08.02 L-PG 115B FUNCTIONAL TEST (BR TK-68) MSP 08.04 L-PG-1158 CHANNEL CALIBRATION l OM 1.54.3 (L5 ITEM 135) WHEN ADD TO TANK 4.3.3.09.4.c STEAM GENERATOR DRAIN TANK MSP 17.01 L-LW110 FUNCTIONAL TEST (LW-TK 7A)
MSP 17.0.'4 L-LW110 CHANNEL CALIBRATION OM 1.54.3 (L5 ITEM 129) WHEN ADD TO TANK 4.3.3.09.4.d STEAM GENERATOR DRAIN TANK MSP 17.02 l
L-LW1111 FUNCTIONAL TEST l (LW TK 7B) MSP 17.04 L-LW111 CHANNEL CALIBRATION OM 1.54.3 l (L5 ITEM 131) WHEN ADD TO TANK F-2 ISSUE 3 O
REVISION 1 l
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BV 1 cnd 2 ODCM l APPENDIX F fo i ODCM CONTROLS PROCEDURE MATRIX t
f" TABLE F:1b BV 2 LIQUID EFFLUENT MONITOR SURVEILLANCES ODCM NUMBER: 3.3.3.09 LlOUID EFFLUENT MONITORS IN APPENDlX C TABLE 3.3.12 OPERABLE APPLICABILITY; DURING RELEASE THROUGH THE FLOW PATHS ODCM SR DESCRIPTION PROCEDURE 4.3.3.09 TEST MONITORS AT TABLE 4.3-12 FREQUENCY i
4.3.3.09.1 MONITOR PROVIDING ALARM AND AUTOMATIC TERMINATION 4.3.3.09.1.a LIQUID WASTE PROCESS HPM RP 6.05A SOURCE CHECK EFFLUENT MONITOR MSP 2-43.39 CAllBRATION (2SGC-RO1100) OM 2.54.3 (LOG L5 ITEM 81) CHANNEL CHECK
, OST 2.43.03 FUNCTIONAL TEST
! 1/2OM-17.4A.C (SOURCE CHECK) l 20M 25.4.L (SOURCE CHECK) 20M-25.4.N (SOURCE CHECK) ,
4.3.3.09.2 FLOW RATE MEASUREMENT DEVICES 4.3.3.09.2.a LlOUID RADWASTE EFFLUENT MSP 2-25.01 2SGC-P26A.B CALIB/FUNCT (2SGC-FIS100) MSP 2-43.39 CAllBRATION OM 2.54.3 (LOG L5 ITEM 82) CHANNEL CHECK 4.3.3.09.2.b COOLING TOWER MSP 2-31.04 CALIBRATION BLOWDOWN LINE MSP 2-31.05 FUNCT TEST (2CWS FT101) OM 2.54.3 (LOG LS ITEM 83) CHANNEL CHECK I
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F-3 ISSUE 3 REVISION 1 i
1 BV 1 cnd 2 ODCM l
APPENDIX F ODCM CONTROLS PROCEDURE MATRIX af; TABLE F:2a DV 1 G ASEOUS EFFLUENT MONITOR SURVEILLANCES l l CONTROL NUMBER: 3.3.3.10 GASEOUS EFFLUENT MONITORS IN APPENDIX C TABLE 3.3.13 OPE APPLICABILITY: DURING RELEASE THROUGH THE FLOW PATHS ODCM SR DESCRIPTION 4.3.3.10 PROCEDURE TEST MONITORS AT TABLE 4.3-13 FREQUENCY i 4.3.3.10.1 GASEOUS WASTE I
(RM-GW-108A AND B) '
4.3.3.10.1.a NOBLE GAS ACTIVITY OM 1.19.4.E CHANNEL CHECK MONITOR !
OM 1.19.4.E SOURCE CHECK MSP 43.22 CHANNEL CALIBRATION 8 OM 1.54.3 (L5 ITEM 063) RM GW-1088 CHANNEL CHECK OM 1.54.3 (L5 ITEM 206) RM-GW-109 CHANNEL CHECK OST 1.43.09 FUNCTIONAL TEST 4.3.3.10.1.b PARTICULATE \CTIVITY OM 1.54.3 (L5 ITEM 062) CHANNEL CHECK MONITOR 4.3.3.10.1.c SYSTEM EFFLUENT FLOW MSP 19.05 FUNCTIONAL TEST RATE MEASURING DEVICE MSP 19.06 CHANNEL CAllBRATION ,
(FR-GW-108) OR OM 1.54.3 (L5 ITEM 094) CHANNEL CHECK ;
(RM GW-109. CH.10) 4.3.3.10.1.d SAMPLER FLOW RATE MSP 43.21 CHANNEL CALIBRATION MEASURING DEVICE MSP 43.71 ROTOMETER FUNCTIONAL TEST '
4.3.3.10.2 AUXILIARY BUILDING (RM VS 101 A and B) 4.3.3.10.2.a NOBLE GAS ACTlVITY MSP 43.13 CHANNEL CAllBRATION .
MONITOR OM 1.54.3 (L5 ITEM 068) RM-VS-1018 CHANNEL CHECK OM 1.54.3 (L5 ITEM 204) RM-VS-109 CHANNEL CHECK OST 1.43.09 OST 1.43.07A ALT NOBLE GAS MONITOR FUNCTIONAL TES". l FUNCTIONAL TEST OST 1.43.09A SOURCE CHECK 4.3.3.10.2.b PARTICULATE ACTIVITY OM 1.54.3 (L5 ITEM 067) CHANNEL CHECK MONITOR ,
4.3.3.10.2.c SYSTEM EFFLUENT FLOW MSP 44.07 FUNCTIONAL TEST RATE MEASUREMENT DEVICE MSP 44.08 CHANNEL CALIBRATION ,
(FR-VS 101) OR OM 1.54.3 (L5 ITEM 0748) CHANNEL CHECK l (RM-VS 109 CH 10) 4.3.3.10.2.d SAMPLER FLOW RATE MSP 44.07 FUNCTIONAL TEST MEASURING DEVICE MSP 44.08 CHANNEL CAllBRATION 4.3.3.10.3 SLCRS (RM.VS-107A and B) !
4.3.3.10.3.a NOBLE GAS ACTIVITY , MSP 43.20 CHANNEL CAllBRATION ;
MONITOR OM 1.54.3 (L5 ITEM 072) RM-VS 1078 CHANNEL CHECK l OM 1.54.3 (L5 ITEM 205) RM-VS-110 CHANNEL CHECK l OST 1.43.07A ALT NOBLE GAS MONITOR FUNCTIONAL TEST OST 1.43.09 FUNCTIONAL TEST OST 1.43.09A SOURCE CHECK 4.3.3.10.3.b PARTICULATE ACTIVITY OM 1.54.3 (L5 ITEM 071) CHANNEL CHECK MONITOR 4.3.3.10.3.c SYSTEM EFFLUENT FLOW MSP 44.09 CHANNEL CALIBRATION RATE MEASURING DEVICE MSP 44.10 FUNCTIONAL TEST l (FR VS-112) OR OM 1.54.3 (L5 ITEM 093) CHANNEL CHECK (RM-VS-110 CH 10) 4.3.3.10.3.d SAMPLER FLOW RATE MSP 43.19 CHANNEL CALIBRATION MEASURING DEVICE MSP 43.72 ROTOMETER FUNCTIONAL TEST !
RADCON LOG CHANNEL CHECK i F-4 ISSUE 3
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REVISION 1 !
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l BV 1 cnd 2 ODCM APPENDIX F */t !
ODCM CONTROLS PROCEDURE MATRIX !
TABLE F:2b BV 2 GASEOUS EFFLUENT MONITOR SURVElLLANCES CONTROL NUMBER: 3.3.3.10 GASEOUS EFFLUENT MONITORS IN APPcNDIX C TABLE 3.3.13 OPERABLE i l APPLICABILITY: DURING RELEASE THROUGH THE FLOW PATH l ODCM SR DESCRIPTION PROCEDURE l 4.3.3.10 TEST MONITORS AT l TABLE 4.3-13 FREQUENCY '
I 4.3.3.10.1 SLCRS - UNFILTERED (2HVS RO101 A and B) 4.3.3.10.1.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.36 CHANNEL CALIBRATION OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST *
[ DRMS SOURCE CHECK (DRMS AUTO FUNCTION) '
i 4.3.3.10.1.b PARTICULATE ACTIVITY OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK MONITOR l 4.3.3.10.1.c PROCESS FLOW RATE MSP 2-43.36 CHANNEL CAllBRATION I MONITOR MSP 2-43.36A FUNCTIONAL TEST
! MWR VELOCITY PROBE CALIBRATION
! OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK
- l. SAMPLER FLOW RATE MONITOR MSP 2-43.36 CHANNEL CAllBRATION l MSP 2-43.36A FUNCTIONAL TEST l OM 2.54.3 (LOG L5 ITEM 74) CHANNEL CHECK l 4.3.3.10.2 SLCRS FILTERED l (2HVS-RO109A and B) 4.3.3.10.2.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.32 2HVS*RQ109A CHANNEL CAllBRATION MSP 2-43.33 2HVS*RO109B,C,D CHANNEL CALIBRATION l j OM 2.54.3 OST 2.43.08 (LOG L5 ITEM 71) CHANNEL CHECK l FUNCTIONAL TEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.2.b PARTICULATE ACTIVITY MSP 2-43.32 CHANNEL CAllBRATION
, MONITOR ' OM 2.54.08 (LOG L5 ITEM 71) CHANNEL CHECK l 4.3.3.10.2.c PROCESS FLOW RATE MSP 2-43.32a FUNCTIONAL TEST MONITOR MSP 2-43.33 2HVS*RO1098,C,0, CHANNEL CAllBRATION MWR VELOCITY PROBE CALORATON OM 2.54.3 (LOG L5 ITEM 71) CHANNEL CHECK 4.3.3.10.2.d SAMPLER FLOW RATE MONITOR MSP 2-43.32 2HVS*RO109A CHANNEL CALIBRATION MSP 2 43.32A FUNCTIONAL TEST MSP 2-43.33 2HVS*RO1098,C,0, CHANNEL CALIB OM 2.54.3 (LOG LS ITEM 71) CHANNEL CHECK 4.3.3.10.3 DECONTAM; NATION BUILDING -
l (2RMO-RO301 A and B) !
4.3.3.10.3.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.35 CHANNEL CAllBRATION OM 2.54.3 (LOG L5 ITEM 73) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST
. DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.3.b PARTICULATE ACTIVITY OM 2.54.3 (LOG L5 ITEM 73) CHANNEL CHECK MONITOR i
- O F-5 ISSUE 3 REVISION 1 l
APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:2b BV 2 GASEOUS EFFLUENT MONITOR SURVEILLANCES r CONTROL NUMBER: 3.3.3.10 GASEOUS EFFLUENT MONITORS IN APPENDIX C TABLE 3.3.13 OPERABL APPLICABILITY: DURING RELEASE THROUGH THE FLOW PATH ODCM SR DESCRIPTION PROCEDURE 4.3.3.10.3.d SAMPLE FLOW RATE MONITOR MSP 2-43.35 CHANNEL CAllBRATION MSP 2-43.35A FUNCTIONAL TEST OM 2.54.3 (LOG L5 ITEM 73) CHANNEL CHECK 4.3.3.10.4 CONDENSATE POLISHING (2HVL-RO112A and B) 4.3.3.10.4.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.38 CHANNEL CALIBRATION OM 2.54.3 (LOG LS ITEM 76) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.4.b PARTICULATE ACTIVITY OM 2.54.3 MONITOR (LOG L5 ITEM 76) CHANNEL CHECK 4.3.3.10.4.d SAMPLE FLOW RATE MONITOR MSP 2-43.38 CHANNEL CAllBRATION MSP 2-43.38A FUNCTIONAL TEST OM 2.54.3 (LOG L5 ITEM 76) CHANNEL CHECK 4.3.3.10.5 WASTE GAS STORAGE VAULT (2RMO-RO303A and B) 4.3.3.10.5.a NOBLE GAS ACTIVITY MONITOR MSP 2-43.37 CHANNEL CALIBRATION OM 2.54.3 (LOG L5 ITEM 75) CHANNEL CHECK OST 2.43.09 FUNCTIONAL TEST DRMS SOURCE CHECK (DRMS AUTO FUNCTION) 4.3.3.10.5.b PARTICULATE ACTIVITY OM 2.54.3 MONITOR (LOG L5 ITEM 75) CHANNEL CHECK 4.3.3.10.5.d SAMPLE FLOW RATE MONITOR MSP 2-43.37 CHANNEL CALIBRATION MSP 2-43.37A FUNCTIONAL TEST OM 2.54.3 (LOG L5 ITEM 75) CHANNEL CHECK F-6
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ISSUE 3 e
REVISION 1
BV 1 cnd 2 ODCM APPENDlX F ODCM CONTROLS PROCEDURE MATRIX
(
r TABLE F:3 BV-1 AND 2 LIQUID 8 EFFLUENT CONCENTRATION SURVEILLANCES CONTROL NUMBER: 3.11.1.1 EFFl.UENT CONCN RATION WITHIN 10 TIMES 10CFR20 EC's APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.1.1.1 SAMPLE AND ANALYZE HPM CP 1 LIQUID RADWASTE DISCHARGES j RADIOACTIVE LlQUID WASTES -
PER TABLE 4.11-1 {
4.11.1.1.1.A BATCH WASTE RELEASE TANKS CHM CP 3 SAMPLING AND TESTING i CHM CP 5 RADIOCHEMICAL PROC l CHM CP8 LOGS AND FORMS (ANALYSIS)
CHM CP 9 ' CONDUCT OF OPERATION HPM CP 3 RP 6.01 LIQ WASTE TANK SAMPLING HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIPS.17 ND-9900 COUNTING SYSTEM HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITOR 4.11.1.1.1.B CONTINUOUS RELEASES CHM CP 3 SAMPLING AND TESTING CHM CP 5 RADIOCHEMICAL PROC I CHM CP 8 LOGS AND FORMS (ANALYSIS)
CHM CP 9 CONDUCT OF OPERATION HPM CP 4 RIP 2.02 EFFLUENT MONITORS ,
HPM CP 4 RIPS.17 ND-9900 COUNTING SYSTEM HMP CP 4 RIP 2.21 DRMS EFFLUENT MONITOR 4.11.1.1.2 USE ODCM METHOD TO HPM CP 3 RP 6.05 . LW OlSCHARGE AUTHORIZATION ASSURE COMPLIANCE HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION OM 1/2.17.4A.D LIQUID WASTE DISCHARGE (W/RP 6.5) o t
4.11.1.1.3 WHEN BV-1 PRIMARY TO SECONDARY LEAKAGE EXCEEDS 0.1 GPM, TAKE TURBINE BLDG GRAB SAMPLES CHM CP 1 CHM CP 5 CHM CP 8 HPM CP 3 HPM CP 3 SPECS & GUIDELINES LEAK RATE CALCULATION LOGS AND FORMS RP6.05 LW DISCHARGE AUTHORIZATION i
{
RP6.05A LW DISCHARGE AUTHORIZATION l HPM CP 4 RIP 2.02 EFFLUENT MONITORS 4.11.1.1.4 WHEN BV-2 PRIMARY TO CHM-CP 1 SPECS & GUIDELINES SECONDARY LEAKAGE CHM CP 5 LEAK RATE CALCULATION I EXCEEDS 0.1 GPM, TAKE CHM CP 8 LOGS AND FORMS l TURBINE BLDG GRAB SAMPLES HPM CP 3 RP6.05 LW DISCHARGE AUTHOIRZATION HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION ]
HPM CP 4 RIP 2.21 EFFLUENT MONITORS 4.11.1.1.5 TAKE GRAB SAMPLES PRIOR TO HPM CP3 RP6.05 LIQUID WASTE GRAB SAMPLES BV-2 RECIRC DRAIN PUMP OM 2.09.2 RX PLANT VENTS AND DRAINS (CB-16)
DISCHARGE TO CATCH BASIN OM 2.09.4F DRAIN RSS PUMP CASING / PIT NO.16 O M 51-86 OM CLEARANCE 51-86 (2DAS-P215A/P1 l
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BV 1 AND 2 ODCM APPENDIX F to ODCM CONTF 's PROCEDURE MATRIX T .BLE F:4 BV 1 AND 2 LIQUID EFF. UENT DOSE SURVEILLANCES Control Number 3.11.1.2 LIQUID EFFLUENT DOSE APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.1.2.1 EVERY 31 DAYS DETERMINE HPM CP 3 RP 6.05A LW DISCHARGE AUTHORIZATION CUMULATIVE DOSE FROM HPM CP 3 RP 6.05 LW DISCHARGE AUTHORIZATION LIQUID EFFLUENTS USING HP LETTER ODCM MONTHLY DOSE PROJECTION OM 1/2174A.D LIQUID WASTE DISCHARGE O
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F-8 ISSUE 3 -
O REVISION 1
l BV 1 AND 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:5 BV 1 AND 2 LIQUID EFFLUENT TREATMENT SURVEILLANCES Control Number 3.11.1.3 LIQUID EFFLUENT TREATMENT SYSTEM APPLICABILIT(: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE j 4.11.1.3.1 EVERY 31 DAYS PROJECT THE HPM CP 3 RP 6.05 LW DISCHARGE AUTHORIZATION j LIQUID RELEASE DOSE USING HPM CP 3 RP 6.05 A LW DISCHARGE AUTHORIZATION s THE ODCM HP LETTER MONTHLY DOSE PROJECTION l OM 1/2174A.D LIQUID WASTE DISCHARGE (W/RP 6.5) 1 l
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REVISION 1
BV 1 AND 2 ODCM APPENDIX F OD CM CONTROLS PROCEDURE MATRIX l h TABLE F:6 BV-1 AND 2 GASEOUS EFFLUENT DOSE SURVEILLANCES Control Number 3.11.2.1 GASEOUS EFFLUENT DOSE RATES APPLICABill1Y: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.2.1.1 DETERMINE NOBLE GAS HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION EFFLUENT DOSE RATE USING HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE THE ODCM HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION OM 1.19.4E BV 1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/219.4A.B BV-2 DECAY TANK DISCHARGE (W/RP 6.6) 4.11.2.1 .2 SAMPLE AND ANALYZei FER HPM CP 1 RADWASTE DISPOSAL TABLE 4.11-2 TO DETERMINE INHALATION PASTHWAY DOSE 4.11.2.1.2.A WASTE GAS STORAGE TANK- CHM CP 3 SAMPLING & TESTING GRAB SAMPLE EACH TANK CHM CP 8 LOGS & FORMS HPM CP 3 RP 6.03 BV-1 GAS TANK SAMPLING HPM CP 3 RP 6.04 BV-2 GAS TANK SAMPLING HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIP 2.20 DRMS PROCESS MONITORS HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITORS 4.11.2.1.2.B CONTAINMENT PURGE-GRAB CHM CP 3 SAMPLING & TESTING SAMPLE EACH PURGE CHM CP 8 LOGS & FORMS HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION l l HPM CP 3 RP 7.03 AIR SAMPLING HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIP 2.20 DRMS PROCESS MONITORS HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITCRS 4.11.2.1.2.C VENTILATION SYSTEMS 4.11.2.1.2.C.1 BV 1 GRAB AND CONTINUOUS CHM CP 3 SAMPLING & TESTING lHRU SAMPLES CHM CP 8 LOGS & FORMS 4.11.2.1.C.3 CHM CP 9 AND CONDUCT OF OPERATION HPM CP 3 RP 6.08 RMS SAMPLE FLOW LINE-UP (NSA) 4.11.2.1.2.D.1 HPM CP 3 RP 6.09 THRU RMS SAMPLE FLOW LINE-UP ( FILTER CHG)
HPM CP 4 RIP 2.02 EFFLUENT MONITORS 4.11.2.1.2.D.3 HPM CP 4 RIP 2.08 SA-9/10 NOBLE GAS MONITOR HPM CP 4 RIP 2.10 SPING-4 MONITOR HPM CP 5 REOP1.1 SA-9/10 EMERGENCY OPERATE l HPM CP 5 REOP1.2 SPING-4 EMERGENCY OPERATE HPM CP 3 RP 6.10 (CONTIN VENT PATH RELEASE) 4.11.2.1.2.C.4 BV 2 GRAB AND CONTINUOUS CHM CP 3 SAMPLING & TESTING THRU SAMPLES. CHM CP 8 LOGS & FORMS 4.11.2.1.2.C.8 CHM CP 9 AND CONDUCT OF OPERATIONS HPM CP 5 REOP4.1 EMERG OPER OF WRGM ASSEM 4.11.2.1.2.C.4 HPM CP 4 RIP 2.21 THRU INSTRUMENT PROCEDURE HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE 4.1.2.1.2.C.8 F-10 ISSUE 3 O
REVISION 1 l
w BV 1 and 2 ODCM
\ APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:7 BV 1 AND 2 GASEOUS EFFLUENT AIR DOSE SURVEILLANCES Control Number 3.11.2.2 GASEOUS EFFLUENT AIR DOSES APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.2.2.1 EVERY 31 DAYS DETERMINE HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION CUMULATIVE DOSE HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE CONTRIBUTIONS USING THE HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION ODCM HPM CP 3 RP 6.12 - ABNORMAL GAS RELEASES HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 3 RP 6.12A ABNORMAL GAS RELEASES OM 1.19.4E BV-1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/219.4A.B BV-2 DECAY TANK DISCHARGE (W/RP 6.6)
HPM CP 4 RP 2.21 - DRMS EFFLUENT MONITORS I
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O F-11 ISSUE 3 -
REVISION I
BV 1 AND 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX
- 95 TABLE F:8 BV 1 AND 2 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSE SURVEILLANCES l h Control Number 3.11.2.3 GASEOUS EFFLUENT PARTICULATE AND IODINE DOSES APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION 4.11.2.3.1 PROCEDURE EVERY 31 DAYS DETERMINE HPM CP 3 RP 6.06 CUMULATNE DOSE GW DISCHARGE AUTHORIZATION HPM CP 3 RP6.06A GW DISCHARGE AUTHORIZATION CONTRIBtfTIONS USING THE HPM CP 3 RP 6.10 ODCM CONTIN VENT PATH RELEASE HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 4 RIP 2.02 EFFLUENT MONITORS HPM CP 4 RIP 2.21 DRMS EFFLUENT MONITORS HPM CP 6.12A ABNORMAL GAS RELEASES OM 1.19.4E OM 1/2.M.4A.38 BV-1 DECAY TANK DISCHARGE (W/RP 6.6)
BV 2 DECAY TANK DISCHARGE (W/RP 6.6)
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BV 1 AND 2 ODCM APPENDIX F l ODCM CONTROLS PROCEDURE MATRIX l TABLE F:9 1 BV 1 AND 2 GASEOUS EFFLUENT TREATMENT SURVElLLANCES l Control Number 3.11.2.4 GASEOUS EFFLUENT TREATMENT SYSTEM APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.11.2.4.1 EVERY 31 DAYS PROJECT GAS HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION RELEASE DOSE FROM THE SITE HPM CP 3 RP 6.06A GW DISCHARGE AUTHORIZATION USING THE ODCM HPM CP 3 RP 6.10 CONTIN VENT PATH RELASE HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 6.12A ABNORMAL GAS RELEASES HP LETTER MONTHLY DOSE PROJECTION OM 1.19.4E BV-1 DECAY TANK DISCHARGE (W/RP 6.6)
OM 1/219.4A.B BV-2 DECAY TANK DISCHARGE (W/RP 6.6)
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BV.1 cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX @
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TABLE F:10 BV 1 AND 2 TOTAL DOSE SURVEILLANCES Control Number 3.11.4.1 LIQUID AND GASEOUS DOSES APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION 4.11.4.1.1 PROCEDURE DETERMINE CUMULATIVE GAS & HPM APP 05 LIQUID DOSE PER APPENDlX C HPM CP 3 RP 6.05 COMP. WITH RG 1.21 & T.S. (40 CFR 190)
CONTROL 3.11.1.2,3.11.2.2, LW DISCHARGE AUTHORIZATION 3.11.2.3 HPM CP 3 RP6.05A LW DISCHARGE AUTHORIZATION HPM CP 3 RP 6.06 GW DISCHARGE AUTHORIZATION HPM CP 3 RP6.06A GW DISCHARGE AUTHORIZATION HPM CP 3 RP 6.10 CONTIN VENT PATH RELEASE HPM CP 3 RP 6.12 ABNORMAL GAS RELEASES HPM CP 3 RPG.12A ABNORMAL GAS RELEASES REAM REAP 6.105 EFFLUENT DATA PROCESSING (40 CFR 190)
O F-14 ISSUE 3 O
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BV 1 and 2 ODCM APPENDIX F 4
ODCM CONTROLS PROCEDURE MATRIX df TABLE F:11 BV 1 AND 2 REMP SURVEILLANCES Control Number 3.12.1 REMP APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION PROCEDURE 4.12.1.1 COLLECT AND ANALYZE EP ENVIRONMENTAL PROC MANUAL (SECTION 3.0)
SAMPLES PER TABLES 3.12-1 & ODCM SECTION 3 4.12-1: USE LOCATIONS IN OOCM O
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.LJ F-15 ISSUE 3 REVISION 1 l
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BV.1 cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX TABLE F:12 BV 1 AND 2 LAND USE CENSUS SURVEILLANCES Control Number 3.12.2 LAND USE CENSUS APPLICABILITY: AT ALL TIMES ODCM SR DESCRIPTION '
PROCEDURE 4.12.2.1 YEARLY BETWEEN 6/1 & 10/1 EPM ~~ '
ENVIRONMENTAL PROC MANL %L CONDUCT LAND CENSUS USING BEST AVAILABLE METHOD O
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REVISION 1
. . - _ . .. _ _ __ _ . . . _ _ . - .._ _ . - _ _ _ _ . _ _ . . ~ . _ . . . _ . .
t CV-1 cnd 2 ODCM APPENDIX F ODCM CONTROLS PROCEDURE MATRIX seg l G TABLE F:13 BV 1 AND 2 INTERLABORATORY COMPARISON PROGRAM !
Control Number 3.12.3 INTERLABORATORY COMPARISON PROGRAM j APPLICABILITY: AT ALL TIMES f
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ODCM SR DESCRIPTION PROCEDURE l 4.12.3.1 INCLUDE PROGRAM ANALYSIS EPM ENVIRONMENTAL PROC MANUAL RESULTS IN THE ANNUAL RADIOLOGICAL ENVIRONM REPORT l
0 1
1
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F-17 ISSUE 3 REVISION 1