ML20045E229
| ML20045E229 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/17/1993 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20045E213 | List: |
| References | |
| PROC-930617, NUDOCS 9307010270 | |
| Download: ML20045E229 (200) | |
Text
{{#Wiki_filter:I . DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit 1 & Unit 2 Offsite Doce Calculation Manual L I D 9307010270 930617 PDR ADOCK 05000334 P PDR
BEAVER VALLEY POWER STATION UNIT NO. I and UNIT NO. 2 i g OFFSITE DOSE CALCULATION MANUAL l l B
DUQUESNE LIGHT Cot!PANY INCLUDED
-i FOR
- LJ HISTORICAL ODCtf Review and Approval Sheet PURPOSES BV-1 ODCM Admin.
Issue Rev. Pgs. RSC Review OSC Review Approv. Eff, No. No. Issd. t!eeting No. Date tieeting No. Date Sign. Date Date 2 2 Title BV-RSC- May BV-OSC- June 12-89 25 13-89 June Q.d.[ 62fM 30 15- G h[y 1989 1989 1989 l thru 1-20 2-1 thru 2-99 3-1 thru 3-14 4-1 3-1 i A-1 < thru A-7 l B-1 thru B-4 3 RE 6.101-1 O
DUQUESNE. LIGHT COMPANY - Nuclear Group , y- FOR "'d HISTORICAL Review and Approval Sheet llNIT 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 PCS BV-RSC-11-87 BV-OSC-17-87
^ "
i thru vifi BV-RSC-12-87 June 12, 1987 7/24/87-1-1 thru l-17 BV-RSC-14-87 /6/ 6~) 2-1 thru 2-96 May 29, 1987 3-1 thru 3-14 ggpg 4,1, 5-1 A-1 thru A-7 B-1 thru B-4 1 2-11 BV-RSC-38-87 BV-1-OSC-25-87 , _ , , 12/22/87 2-14 12/3/87 12/15/87 ' v n/a4 /2/22/87 m ~
DUQUE3';E LIGHT COM0ASY suelear services uni: lNCLUDED FOR b Review anc Accreval Sheet
. . HISTORICAL PURPOSES
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UNIT 1 - 0FFSITE DOSE CALCULATION RANUAL ISSUE 1
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i f Admin. Rev. Pgs. Tech. Rev. OSC Approv. Eff. No. Issd. Sign. Date Review Date Sign. Date 'Date
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I~ Rev. 1 111 1 17,18,19 645 - h FM ' f *~ #7 2-12,13, /:A s - /m m - P " ' t o 14,15 gg ,jgg ,ey-2/ 9/2 D/ 2-27 thru 2-37 and /7VF5'#"'""#+ 2-51 4 !' t IV * ' I**lo &J I&Ilh y gI17/irr . v'
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Rev. 2 1-4,1-5 ERS-SFL-85-031 1-6,1-16 ERS-ATL-86-008 2-2,2-2a BVPS-RSC-5-86 BV-OSC-25-86 2-3,2-4 May 1, 1986 6/12/84 , 2-7,2-17 - 2-19,2-65 J.W. Wenkhous
, y and 2-82 May 2, 1986 y7,gg <7 pf, 9
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I i DUQUESNE LIGHT COMPANY FOR CDC'i Review and Approval Sheet HISTORIC AL 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 g,/g 7 June i 12-89 25 13-89 15 * . 30 thru 1989 1989 1989 viii 1-1 thru 1-21 2-1 thru 2-101 3-1 thru 3-14 4-1 5-1 l A-1 thru A-7 B-1 thru B-2 l l RE 6.101-1 I
DUQUESNE LIGHT COMPANY Nuclear Group FOR I 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 PGS BV-RSC-11-87 BV-OSC-17-87 w w i thru viii BV-RSC-12-87 June 12, 1987 7/24/87 1-1 thru l-18 BV-RSC-14-87 7//G /5 7 2-1 thru 2-98 May 29, 1987 3-1 thru 3-14 Q$ 4-1, 5-1 A-1 thru A-7 g B-1 and B-2 2 2-12 BV-RSC-38-87 BV-1-OSC-25-87 %J 12/22/87 2-15 12/3/87 12/15/87
@ t RA' /2/22/97 I
DUQUESNE LICliT COMPANY-Beaver Valley Power Station Unit'l Docket No. 50-334 License No. DPR-66 Beaver Valley Power Station Unit 2 Docket No. 50-412 License No. NPF-73 BEAVER VALLEY POWER STATION UNIT 1 (BV-1) BEAVER VALLEY POWER STATION UNIT 2 (BV-2) 0FFSITE DOSE CALCULATION-MANUAL (ODCM) l F ISSUE 3
1 BV-1 and 2 ODCM TABLE OF CONTENTS SECTION TITLE PAGE NO. Table Of Contents................................... 1 List Of Tab 1es...................................... iii List Of Figures..................................... ' vi ODCM Equation Cross Reference....................... vil 0DCM Table Cross Reference.......................... ix Preface............................................. xi History Of ODCM Changes............................. xii 1.0 LIQUID EFFLUENTS.................................... 1-1 1.1 Alarm Setpoints................................. 1-2 1.1.1 BV-1 Monitor Alarm Setpoint Determination..... 1-2 _ 1.1.1.1 BV-1 Setpoint Determination Based on A Conservative Mix............................ 1-2 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release................... 1-5 1.1.2 BV-2 Monitor Alarm Setpoint Determination. ... 1-7 1.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix............................ 1-7 1.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release.:................. 1-10 References For Liquid Alarm Setpoints......... ..... 1 1.2 Compliance Vith 10 CFR 20 MPC Limits............ 1-16 D 1.2.1 Batch Releases................................ 1.2.2 Continuous Releases........................... 1-16 1-18 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 2.0p GASE0US EFFLUENTS................................... 2-1 2.1 Alarm Setpoints................................. 2-2 l i 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 2.1.2.2 BV-2 Setpoint Determination Based on Analysis Prior To Releare (Ground Releases). 2-19 2.1.3 BV-1/2 Monitor Alarm Setpoint Determination... 2-22 2.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix-(Elevated Releases).......... 2-22 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 i ISSUE 3
BV-1 and 2 ODCM TABLE OF CONTENTS 1 SECTION TITLE PAGE NO. 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 Radiciodines And Particulates 2-41 2.3 Compliance Vith 10 CFR 50 Dose Limits........... 2-59 2.3.1 Dose Due To Noble Gases....................... 2-59 2.3.1.1 Cumulation of Doses......................... 2-59
- 2. 3.1. 2 Proj ec t ion O f Doses . . . . . . . . . . . . . . . . . . . . . . . . . 2-65 2.3.2 Doses Due To Radiciodines And Particulates.... 2-66 2.3.2.1 Cumulation of Doses......................... 2-66 2.3.2.2 Projection Of Doses......................... 2-78 2.4 Gaseous Radvaste System......................... 2-117 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM....... 3-1 4.0 INFORMATION RELATED TO 40 CFR 190................... 4-1 5.0 SITE BOUNDARY FOR GASEOUS AND LIQUID EFFLUENTS...... 5-1 Appendix A Summary Of Dispersion Calculational Procedures. . . . . . A-1 Appendix B Inputs To Computer Codes For Generation Of Source Terms........................................ B-1 Appendix C ODCM Controls....................................... C-1 Appendix D Bases For ODCM Controls............................. D-1 Appendix E Annual Reports...................................... E-1 l
11 ISSUE 3
-.3 BV-1 and 2 ODCM LIST OF TABLES ]
TABLE NO. TITLE PAGE NO. g LIQUID EFFLUENT TABLEe l 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............................... 1-19f 1.2-lb BV-2 Recirculation Times Required Before Sampling Of Liquid Discharge Tanks............................... 1-20 1.3-1 Ag Values For An Adult For The Beaver Valley Site... 1-24 GASEOUS EFFLUENT TABLES 2.1-la BV-1 Radionuclide Mix For Gaseous Effluents.......... 2-29 2.1-1b BV-2 Radionuclide Mix For Gaseous Effluents.......... 2-30 2.1-2a BV-1 Monitor Detector Efficiencies................... 2-31 2.1-2b BV-2 Monitor Detector Efficiencies................... 2-32 2.2-1 Modes Of Gaseous Release From Beaver Valley Site Vents For Implementation Of 10 CFR 20 And 10 CFR 50.. 2-45 2.2-2a BV-1 Radionuclide Mix For Gaseous Effluents.......... 2 46 2.2-2b BV-2 Radionuclide Mix For Gaseous Effluents.......... 2 47 2.2-3 Distances Of Limiting Maximum Individual Receptors To Release Points For Annual X/0 Values.............. 2-48 g ANNUAL AVERAGE X/0 VALUES FOR CONTINUOUS RELEASES (SPECIAL DISTANCES AND CONTROL LOCATIONS) 2.2-4 BV-1 And 2 Containment Vents (Ground Release)........ 2-49 2.2-5 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-50 2.2-6 BV-1 And 2 Process Vent (Elevated Release)............- 2-51 2.2-7 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-52 2.2-8 BV-2 Decontamination Building Vent (Ground Release).. 2-53 2.2-9 BV-2 Vaste Gas Storage Vault Vent (Ground Release)... .2-54 2.2-10 BV-2 Condensate Polishing Building (Ground Release).. 2-55 DOSE FACTORS AND DOSE PARAMETERS FOR CASEOUS EFFLUENTS 2.2-11 Dose Factors For Noble Gases And Daughters........... 2-56 2.2-12 Dose Parameters For Finite Elevated Plumes, Beaver Valley Site.......................................... 2-57 2.2-13 Pg , Values For A Child For The Beaver Valley Site.... 2-58 MODES OF GASE0US RELEASES 2.3-1 Modes Of Gaseous Release Form The Beaver Valley Site Ver.ts For Implementation Of 10 CFR ' 20 And 10 CFR 50. . 2-79 I 111 ISSUE 3 s i
BV-1 and 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 - Chi 1d................................... 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 - Chi 1d................................... 2-87 2.3-10 Heat - Adult......................................... 2-88 2.3-11 Heat - Teen.......................................... 2-89 2.3-12 Meat - Child......................................... 2-90 2.3-13 Cow Milk - Adult..................................... .2-91 2.3-14 Cow Milk - Teen....................................... 2-92 2.3-15 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 q 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 AN'UAL AVERAGE D/0 VALUES FOR CONTINUOUS RELEASES (SPECIAL DISTANCES) 2.3-28 BV-1 And 2 Process Vent (Elevated Release)........... 2-106 2.3-29 BV-1 And 2 Containment Vents (Ground Release)........ 2-107 2.3-30 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-108 2.3-31 BV-1 And 2 Turbine Building Vents (Ground Release)... 2-109 2.3-32 BV-2 Condensate Polishing Building (Ground Release).. 2-110 2.3-33 BV-2 Decontamination Building Vent (Ground Release).. 2-111 2.3-34 BV-2 Vaste Gas Storage Vault Vent (Ground Release)... 2-112 SHORT TERM X/0 VALUES FOR BATCH RELEASES 2.3-35 BV-1 And 2 Containment Vents (Ground Release)........ 2-113 2.3-36 BV-1 And 2 Ventilation Vents (Ground Release)........ 2-114 2.3-37 BV-1 And 2 Process Vent (Elevated Release)........... 2-115 2.3-38 BV-1 And 2 Process Vent (Elevated Release)........... 2-116 l
. iv ISSUE 3
BV-1 and 2 ODCH. LIST OF TABLES TITLE PAGE NO. TABLE NO. l ENVIRONMENTAL MONITORING 3.0-1 Radiological Environmental Monitoring Program........ 3-4 DISPERSION CALCULATION PROCEDURES A:1.1 BV-1 And 2 Release Conditions........................ A-3 INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS B:1.la Inputs To GALE Code For Generation Of BV-1 Liquid' Source Term Mixes.................................... B-2 Bil.lb Inputs To SVEC LIO1BB Code For Generation Of BV-2 Liquid Source Term Mixes............................. B-3 B:1.2a Inputs To SVEC GAS 1BB Code For Generation Of BV-1 Gaseous Source Term Mixes............................ B-4 B:1.2b Inputs To SVEC GAS 1BB Code For Generation of BV-2 Gaseous Source Term Mixes............................ B-5 ODCM CONTROLS FOR INSTRUMENTATION, SAMPLING, AND ANALYSIS REQUIREMENTS C:1.1 Operational Modes.................................... C-5 C: 1.2 Frequency Notation................................... C-6 C 3.3-12 Radioactive Liquid Effluent-Monitoring Instrumentation C-10 h 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 I v ISSUE 3
BV-1 and 2 ODCM LIST OF FIGURES FIGURE NO. TITLE PAGE NO. g LIQUID EFFLUENT FIGURES 1,4-1 BV-1 Liquid Radvaste System......................... 1-28 1.4-2 BV-2 Liquid Radvaste System......................... 1-29 GASE0US EFFLUENT FIGURES 2.4-1 BV-1 And 2 Gaseous Radvaste System.................. 2-118 2.4-2 BV-1 And 2 Gaseous Effluent Release Points.......... 2-119 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FIGURES 3.0 Air Sampling Locations.............................. 3-8 3.0-2 TLD Locations - Northwest Quadrant.................. 3-9. 3.0-3 TLD Locations - Northeast Quadrant.................. 3-10 3.0-4 TLD Locations - Southeast Quadrant.................. 3-11 3.0-5 TLD Locations - Southwest Quadrant.................. 3-12 3.0-6 Shoreline Sediment, Surface Water, And Drinking Vater Sampling Locations............................ 3-13 3.0-7 Milk Sampling Locations............................. 3-14 3.0-8 Fooderop Sampling Locations......................... 3-15 3.0-9 Fish Sampling Locations............................. 3-16 SITE BOUNDARY FIGURES 5-1 Site Boundary For Gaseous And Liquid Effluents...... 5-1 i vi ISSUE 3 j
BV-1 and 2 ODCM ODCM EQUATION CROSS REFERENCE FOR LIQUID EFFLUENTS k FROM: TO: FROM: PREVIOUS CURRENT PREVIOUS BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3-AND EARLIER AND LATER AND EARLIER 1.1-1 1.1(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 k 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 b l vii ISSUE 3
BV-1 and 2 ODCM ODCM EQUATION CROSS REFERENCE FOR GASE0US 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 - 2.1-3 2.1(1)-3 -- 2.1-4 2.1(1)-4 -- 2.1-5 2.1(1)-5 -- 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 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 Thru Thru Thru 2.1-16 2.1-16 2.1-16 2.1-17 2.1(1)-17 - 2.1-18 2.1(1)-18 -- 2.1-19 2.1(1)-19 - . 2.1-20 2.1(1)-20 -- l 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 Thru Thru Thru 2.2-14 2.2-14 2.2-14 2.3-1 2.3-1 2.3-1 Thru Thru Thru 2.3-36 2.3-36 2.3-36 viii ISSUE 3 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _
BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR LIQUID EFFLUENTS FROM: TO: FROM: PREVIOUS CURRENT PREVIOUS BV-1 ODCM BV-1 AND 2 ODCM BV-2 ODCM ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER 1.1-1 1.1-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 l
l l ix ISSUE 3
BV-1 and 2 ODCM ODCM TABLE 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-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 2.2-1 2.2-2 2.2-2a --
-- 2.2-2b 2.2-2 2.2-3 2.2-3 2.2-3 Thru Thru Thru 2.2-13 2.2-13 2.2-13 -
2.3-1 2.3-1 2.3-1 Thru Thru Thru 2.3-34 2.3-34 2.3-34 A-2 2.3-35 A-2 A-3 2.3-36 A-3 A-4 2.3-37 A-4 A-5 2.3-38 A-5 3.0-1 3.0-1 3.0-1 x ISSUE 3
BV-1 and 2 ODCM ODCM TABLE CROSS REFERENCE FOR ODCH APPENDICES FROM: TO: FROM: PREVIOUS CURRENT PREVIOUS BV-1 ODCH BV-1 AND 2 ODCH BV-2 ODCH ISSUE 2, REV. 2 ISSUE 3 ISSUE 1, REV. 3 AND EARLIER AND LATER AND EARLIER A-1 A:1.1 A-1 - (Unnumbered) B:1.la --
-- B: 1.lb (Unnumbered)
(Unnumbered) B:1.2a --
-- B:1 2b (Unnumbered)
-- C:1.1 --
-- C:1.2 --
C:3.3-12 -- C:4.3-12 --
-- C:3.3-13 --
C:4.3-13 -- C:4.11-1 --
-- C:4.11-2 --
-- C:3.12-1 --
C:3.12-2 -- D -- C:4.12-1 --
-- E:6.9-1 --
e xi ISSUE 3
BV-1 and 2 ODCM PREFACE This OFFSITE DOSE CALCULATION MANUAL (ODCM) provides the information and methodologies to be used by Beaver Valley Power Station Unit 1 and Unit 2 (BV-1) and (PV-2) to assure compliance with the Administrative Controls Section of the operating Technical Specifications. They are intended to show compliance with 10 CFR 20.106, 10 CFR 50.36a, Appendix I of 10 CFR 50, and 40 CFR 190. This ODCM is based on the following United States Nuclear Regulatory Commission (USNRC) documents:
- NUREG-0472, Draft 7 for Rev. 3, September, 1982, Standard Radiological Effluent Technical Specifications For PVRs.
- NUREG-0133, Octuoer, 1978, Preparation Of Radiological Effluent Technical Specifications For Nuclear Power Plants.
- Generic Letter 89-01, January 31, 1989, Implementation Of Programatic Controls For Radiological Effluent Technical Spacifications In The Administrative Controls Section Of The Technical Specifications And The Relocation Of Procedural Details Of RETS To The ODCM Or To The PCP.
- NUREG-1301, April, 1991, Offsite Dose Calculation Manual Guidance: Standard Radiolog; al Effluent Controls For Pressurized Vater Reactors, Generic Letter 89-01, Supplement No. 1.
- Other miscellaneous inputs from the USNRC.
Specific plant procedures for implementation of this manual are included in the Radiological Control Manual (BVPS-RCM) and the Radiological Engineering Administrative Manual (REAM). These procedures are utilized by the operating staff to assure compliance with Technical Specifications and the 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 will be properly prepared, reviewed, and approved as indicated in the Administretive Control Section of the Technical Specifications. An implementation procedure for control of the ODCM is included in the REAM. In summary, any ODCH changes will be properly justified to ensure that ODCM changes vill maintain the lesel of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculation. xii ISSUE 3
BV-1 and 2 ODCM HISTORY OF ODCM CHANGES F (1) BV-1 ODCM, Issue 1 (Effective First Half, 1984) This is the initial issue of the BV-1 ODCM, as prepared for implementation of the Radiological Effluent Technical Specifications (PETS). Implementation of this manual was commensurate with Amendment No. 66 to the Unit 1 Technical Specifications as approved by the NRC on March 28, 1983. (2) BV-1 ODCM, Issue 1, Revision 1 (Effective Second Half, 1984) A description of the changes that vere implemented with this revision are as follovs:
- 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-PDC-1-84 on January 31, 1984. The equations vere revised to clarify flow rate terminology.
- Section 2.2.2 was r e~ i sed 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 "as revised to include 7 organs rather than only the Also, the receptor was changed from infant to child, and D maximum organ.
addition / deletion of nuclides to be consistent with the Technical Specifications and nuclides identified at BV-1. (3) BV-1 ODCM, Issue 1, Revision , (Effective Second Half, 1986) A description of the change. vere implemented with this revision are as follows:
' Provide a flov based monitor setpoint adjustment factor in Section 1.1.2. This change makes Section 1.1.2 consistent with Section 1.1.1 and current procedures.
l
- 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 softvare.
- 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. l 1 xiii ISSUE 3 % k-
BV-1 and 2 ODCM (4) BV-1 ODCH, Issue 2, (Effective Second Half, 1987) BV-2 ODCM, Issue 1, Revision 1 (Effective Second Half, 1987) Vith the start-up of BV-2 in the second half of 1987, the BVs1 ODCM required revision and the BV-2 ODCM required initial implementation. A description of the changes are as follows:
- Produce functionally compatible BV-1 and BV-2 ODCMs which address site dose rate limits and meet regulatory requirements. Note that due to the scope of the revisions to the Unit 1 ODCM, it was re-issued as Issue 2.
Also, for clarity, the draft BV-2 ODCM previously submitted to the NRC vas regarded as Issue 1 (historical) and operation of BV-2 began with Issue 1, Revision 1 of the BV-2 ODCM.
*A shared liquid radvaste system, permitting mixing of vaste for processing, the sharing of dilution water, and the apportionment of dose according to NUREG-0133 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 was incorporated into both ODCMs.
- Separate ground level gaseous releases vere maintained. The BV-1 ODCM was updated to incorporate the BV-2 five year meteorology base. Gr.seous source terms were revised to that calculated for BV-1 in the BV-2 FSAR, and terms were added for calculation of a turbine building release.
- The gaseous effluent monitor alarm setpoints of both ODCMs were revised as required by revisions to mateorology, source terms, monitor efficiencies, and revised percentages of site dore rate limits.
- Formal justification was provided for use of the "T" factor in Containment Purge Dose Rate calculations. Whereas, the dose rate for a Containment Purge may be average over a time period not to exceed 960 minutes. Since the Centainment air volume change time period is 60 minutes, then the maximum value for "T" is 16 (i.e., 960 minutes /
60 minutes - 16). (5) BV-1 ODCM, Issue 2 Revision 1 (Effective Second Half, 1987) BV-2 ODCM, Issue 1, Revision 2 (Effective Second Half, 1987) Sections 2.1.3 and 2.1.4 of both ODCMs were changed to delete a note concerning noble gas nuclides as requested by a NRC letter dated July 14, 1987 titled Beaver Valley Unit 2 - Offsite Dose Calculation Manual. ODCM (TAC 63996). (6) BV-1 ODCM, Issue 2, Revision 2 (Effective First Half, 1989) BV-2 ODCM, Issue 1, Revision 3 (Effective First Half, 1989) A description of the changes that were implemented with this revision are as follovs: Both ODCMs vere revised for addition of Sections 1.4 and 2.4. This addition given a description of and includes flow diagrams of the Liquid Radvaste System and the Gaseous Radvaste System. (See justification 1) xiv ISSUE 3
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)- D B. Add the division sign. (See Justification 1)
- Re-define Fkin equation 1.3-1 of both ODCMs, as allowed by the NRC. (See Justification 1)
- Correct typos to the following:
A. BV-1 ODCM equation 1.3 7, add a division sign between the brackets. (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 vith the current requirements of the Technical Specifications. (See Justification 2) D. Equation 2.1-20 of both ODCMs, hange the HHSP to HSP multiplier from 0.70 to 0.33. (SeeJustific[lon1) E. Equation 2.1- 24 of both ODCid s , 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. (Eee Justification 2)
- Add Reference (7) to Section 2 of the BV-1 ODCM. (See Justification 3)
- Add the words "from the site" to section 2.2.2 of both ODUMs. This ensures compliance with the current requirements of the Technical Specifications. (See Justification 2)
- Revise BV-1 ODCH Table 2.2-2 to change the particulate and iodine radionuclide mix for the Unit i Ventilation Vent and to correct a typo for Xe-135m in the containment Vacuum Pumps. (See Justification 3)
- Provide re-verified P IT values for the Beaver Valley site in Table 2.2-13 of both 0DCHs. (See Justification 1)
- Correct the definition for the t value in the cov-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 D BV-1 ODCM. (See Justification 3) xv ISSUE 3
BV-1 and 2 ODCM The justification used for Change (6) to the ODCMs are as follows:
- 1. A letter dated March 2, 1989 (from the NRC) vas received by Duquesne Light regarding acceptance of the Offsite Dose Calculation Manusls.
The NRC acceptance of the BV-1 and BV-2 ODCMs was based on Technical Evaluation Reports (TER No. EGG-PHY-8194 and EGG-PHY-8217) provided by the Idaho National Engineering Laboratory. As stated in the letter, minor concerns are delineated in Section 4 of the TER. In general, these concerns are considered typos or additions and in one way impact any of the calculations currently being performed for dose contributions. However, one of these concerns is regarding the inability to reproduce the ODCM R values for the cov-meat, cow-milk and goat-milk pathways when using the ODCM/NUREG-0133 methodology. These R values (along with all other ODCM R values) vere re-validated VIA Calculation Package No. ERS-ATL-89-014. The results of this package shoved that the R u.locs for the three aforementioned pathways were in error. Since the R values in error do not involve the controlling receptor for gaseous release (i.e.; the controlling receptor is VIA the Inhalation, Ground, and Vegetation pathvays, not the pathways subject to error) than these changes to the ODCM vill not adversely impact the accuracy or reliability of effluent dose calculations.
- 2. As requested by DLC letters ND3NSM:3431, NDINSM:3522, and ND1NSM:3652, Technical Specifications were required to be verified in all plant implementing procedures. As part of this effort, wording errors / typos were identified in various sections of the ODCM. This revision corrects the anomalies identified during the verification effort.
- 3. As delineated in letter NDISHP:776, dated February 12, 1988 (BVPS-1 ODCM Table 2.2-2, Appendix B) a series of apparent discrepancies were identified between ODCM Table 2.2-2 and similar tables of the BVPS-2 FSAR. Evaluation shoved that apparent credit was given for continuous filtration of SLCRS releases which is invalid at Unit 1. However, the calculation package on which the BVPS-2 FSAR expected release tables are based, is correct (i.e.; no credit was taken for routine filtration for Unit 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.
l Therefore, this change does not adversely impact the accuracy or reliability of setpoint calculations. (7) BV-1 and 2 ODCM Issue 3 (Tentative Effective Date, First Half, 1992) The combined ODCM, as implemented by ISSUE 3, contains the following changes! Prior to ISSUE 3, BV-1 and BV-2 had individual ODCMs that vere generically equal. In an effort to simplify the implementing documents, the ODCMs have been combined. This merger of the individual ODCMs vill maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50. Also, this merger vill not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. xvi ISSUE 3
BV-1 and 2 ODCM
- Revised Section 1.0 (Liquid Effluents) and Section 2.0 (Gaseoup 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 vere transferred to the combined ODCM, the numbering vas kept generically equal. The only exception to this are as follows:
- If a table was contained in both ODCMs, but each had data specific to BV-1 or BV-2, then an a or b vas 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-lb de'oting n BV-1 and BV-2 respectively. A cross reference for ODCM tables is provided in the Table of Contents. - If an equatior 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 l 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 example, all dispersion parameters are nov included in one area of the ODCM.
- Added Appendix C: Procedural details for the Radiological Effluent Technical Specifications (RETS) were transferred from the Technical Specifications to Appendix C of
~
the ODCM per Generic Letter 89-01 and Generic Letter 89-01, Supplement No. 1 (NUREG 1301). This Appendix also includes selected Definitions and Tables as delineated in the Technical Specifications (Section 1) and selected Applicability and Surveillance Requirement statements as del %eated in the Technical Specifications (Section 3/4 0). These vert Med to Appendix C for reference purposes, even though they are currently described in the Technical Specification. Added Appendix D: The bases for ODCM Controls vere transferred from the 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 ODCH. xvii ISSUE 3
BV-1 and 2 ODCM non-editorfal changes) in this ODCM ' There are three differences (i.e., previous b61 and BV-2 Technical revision when compared to the Specifications. These are the only changes that are identified by revision bars. These differences are as follovs:
- First Difference:
There was a sentence removed in the LLD Standard Deviation l Definitions delineated in Appendix C Tables 4.11-1 and 4.11-2. This /( sentence stated: "In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium in milk samples)." It should be noted that this sentence was removed by justification of NUREG-0472, Rev. 2 (i.e., this revision to the NUREG remo'/ed the sentence from Tables 4.11-1 and 4.11-2). It should be noted that at BV-1 and 2, there are n_o other radionuclides norm:lly present in effluent samples. However, there is applicability to environmental LLD calculations due to the existence of therefore, other radionuclides vill not be in environmental samples. This sentence, removed from Appendix C, Table 4.12-1. Removal of the sentence from Appendix C, Tables 4.11-1 and 4.11-2 does not adversely impact the accuracy or reliability of current or past effluent LLD calculations. This change maintains the level off - radioactive effluent control required by 10 CFR 20.106, 40 CFR1to10CFRPart50 Part 190, 10 CFR 50.36a, and Appendix dose, not adversely impact the accuracy orre[abilityofeffluent, or setpoint calculations. This change brings ODCM Appendix C, Tables 4.11-1 and 4.11-2 in generic agreement vith NRC guidance (i.e., NUREG-0472) and industry standard.
- Second Difference:
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 hall 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 radioactive10 effluent CFR 50.36a, and centrol required by 10 CFR 20.106, 40 CFR Part 190, Appendix I to 10 CFR Part 50, and does not adversely impact the V accuracy or reliability of effluent, dose, or setpoint calculations. O xviii ISSUE 3
BV-1 and 2 ODCM Third Difference: The process flow rate operability and surveillance requirements for l gaseous effluent radiation monitors 2RMQ-RQ-301, 2RM0-RO-303, and A 2HVL-RQ-112 vere removed from t'ne BVPS-2 Technical Specifications (Tables 3.3-13 and 4.3-13). These items were not transferred to the ODCM by justification provided in Operating License Change Request No. 2A-61 and DLCo Calculation Package No. ERS-ATL-90-021. The following is a summary of the justification. BVPS-1 and BVPS-2 is currently using, and vill continue to use design (maximum) system flow rates in ODCM Dose & Dose Rate Calculations, rather than those flov - rates observed during normal plant operation. The imum organ dose for gaseous releases due to particulates and l radioiodines (from these three pathways) resulted in < 0.1% of the BVPS-1 plus BVPS-2 Technical Specification Yearly Limit (15 mrem + l l 15 mrem). I BVPS-2 UFSAR Section 11.3.3 indicates that the source term for these three pathways are not significant. These pathways are, therefore, not included in UFSAR Tables 11.3-1 through 11.3-4 that list the expected and design releases for each potentially radioactive pathway. The DLC commitment to RG 1.97, Rev. 2 (as stated in Section 1.8-1 of not affected. This RG applies to the BVPS-2 UFSAR) is postulated accident instrumentation used during and after conditions. The three process flow rate instruments addressed by this calculation package vere not used in any accident analysis, nor are they used to assess plant conditions during and following an accident. The DLC commitment to RG 1.21, Rev. 1 (as stated in Section 1.8-1 of RG 1.21, Section C.2 (Location. the BVPS-2 UFSAR) is not affected. "All major and potentially Of Monitoring) states in part: significant paths for release of radioactive material during normal reactor operation, including anticipated operational occurrences, should oe monitored. Measurements of effluent volume, rates of release, and specific radionuclides should be made, insofar as practical..." As previously stated, the threethat process flow rate do not have a instruments are located on effluent pathways significant source term. BVPS-2 UFSAR Sections 9.4.13 and 9.4.16 indicates 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 Moniti s are still capable of performing their intended functions as d cribed in BVPS-2 UFSAR Section h/ 11.5.2.4. O xix ISSUE 3
BV-1 and 2 ODCM
SUMMARY
Per Generic Letter 89-01, the transfer of RETS procedural details fulfills the goal of the USNRC Policy Statement for Technical Specification improvements. It is not the USNRC's (or DLC's) intent to reduce the level of radioactive effluent control. Rather, the intent is to provide programmatic controls for RETS (as delineated in Technical' Specification 6.8.6) and allow for relocation of the procedural details of the RETS to the ODCM. l xx 1SSUE 3
BV-1 and 2 ODCM ] 1.0 LIQUID EFFLUENTS I BV-1 and SV-2 uti.1.ize the concept of a shared liquid radioactive vaste system according to NUREG 0133. This permits the mixing of liquid radvaste for processing and allocating of dose due to release as defined in Section 1.4. In Section 1.1, effluent monitor setpoints for a conservative mix are based on the individual Units' specific parameters, but effluent 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. Vhere BV-1 uses HIGH and 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, but the indicated uCi/ml value may differ from the actual value. D l-1 ISSUE 3
l BV-1 and 2 ODCM l 1.1 Alarm Setpoints I 1.1.1 BV-1 Monitor Alarm Setpoint Determination This procedure determines the monitor HIGH-HIGH Alarm Setpoint that indicates if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2 E-4 uCi/ml for dissolved or entrained noble gases. The methodology described in Section 1.1.1.2 is an alternative method to be used to determine the monitor HIGH-HIGH Alarm Setpoint (HHSP). The methodology in Section 1.1.1.2 may be used for any batch release and shall be used when the total gamma activity concentration of the liquid effluent prior to dilution exceeds 1.49E-4 uCi/ml. This concentration is equivalent to the HHSP's of 1.69 E4 ncpm and 8.46 E4 nepm (net counts.per minute) derived in Section 1.1.1.1 and allows for a tritium concentration up to 1.5E-1 uCi/ml. 1.1.1.1 BV-1 Setpoint Determination Based On A Conservative Mix The HIGH-HIGH Alarm Setpoint for the Liquid Vaste Effluent Monitor (RM-LV-104) should be set at 1.69E4 nepm and the HIGH-HIGH Alarm Setpoint for the Liquid Vaste Contamination Monitor (RM-LV-116) should be set at 8-.46E4 nepm. These setpoints are based on.the following conditions:
- Source terms given in Table 1.1-la. These source terms have been generated from the computer code GALE, Revision 0 (NUREG-0017). The inputs to GALE are given in Appendix B.
- Dilution water flow rate of 15,000 gpm.
- Discharge flow rate prior to dilution of 50 gpm for the Liquid Vaste Effluent Monitor (RM-LV-104).
- Discharge flow rate prior to dilution of 10 gpm for the Laundry and Contaminated Shower Drains Monitor (RM-LV-116).
The above setpoints can be varied based on actual operating conditions resulting in changes in the discharge and dilution flow rates as follows: HHSP = 6.3 F [1.1(1)-1] f where: HHSP = Monitor HIGH-HIGH Alarm Setpoint above background (nepm). 56.3 = Proportionality constant based on nominal flow conditions (56.3 = 1.69 E4 ncpm x 50 gpm + 1.5 E4 gpm for RM-LV-104 er l 56.3 = 8.46 E4 nepm x 10 gpm + 1.5 E4 gpm f or RM-LV-116). 1-2 ISSUE 3
r .. l BV-1 and 2 ODCM' F = Dilution vater flow rate (gpm), BV-1 Cooling Tover Blovdown Rate (not including BV-2 Blowdown or the BV-2 release out -
~
through the Emergency Outfall Structure).
^
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 radioactivity levels of the radionuclides in the effluent from Table 1.1-la.
- b. The fraction of the total radioactivity in the liquid effluent comprised by radionuclide "i" (Sg ) for each individual radionuclide in the liquid effluent was determined as follows:
A S g,IA i [1.1(1)-2] g i where: Ag = Annual release of radionuclide "i" (Ci/yr) in the liquid. effluent from Table 1.1-la. 1.1.1.1.2 BV-1 Maximum Acceptable Concentration (All Radionuclides) The maximum acceptable total radioactivity concentration (uCi/ml) of all radionuclides in the liquid effluent prior to dilution (C ) was determined by: t i C t = F [1.1(1)-3] S fE i MPC g where: F = Dilution water flow rate (gpm), BV-1 Cooling Tover Blovdown Rate (not including BV-2 Blowdown or the BV-2 release out through the Emergency Outfall Structure).
= 15,000 gpm ,
f = Maximum acceptable discharge flow rate prior to dilution (gpm).
= 50 gpm for Liquid Vaste Effluent Monitor (RM-LV-104).
= 10 gpm for Laundry and Contaminated Shover Drains Monitor
~{
(RM-LV-116). 1-3 ISSUE 3
BV-1 and 2 ODCM MPCg = Liquid effluent radioactivity concentration' limit for radionuclide "i" (uC1/ml) from Table 1.1-la. If not
) listed there, from Reference 1.1.3, 5 = The fraction of total radioactivity attributed to 1
radionuclide "i", from Equation [1.1(1)-2]. 1.1.1.1.3 BV-1 Maximum Acceptable Concentration (Individual Radionuclide) The maximum acceptable radioactivity concentration (uci/ml) of radionuclide "i" in the liquid effluent prior to dilution (C g) was determined by: Cg=Sg C t [1.1(1)-4] 1.1.1.1.4 BV-1 Monitor Count Rate The calculated monitor count rate (nepm) above background attributed-to the radionuclides, C.R., was determined by: C.R = E Cy E g [1.1(1)-5] i where: Eg - Detection efficiency of the monitor for radionuclide "i" (cpm /uC1/ml) from Table 1.1-la. If not listed there, from Reference 1.1.4. 1.1.1.1.5 BV-1 Monitor HHSP The monitor HIGH-HIGH Alarm Setpoint above background (nepm) should be set at the C.R. value. Since only one tank can be released at a time, adjustment of this .value is not necessary to compensate for release from more than one source. i ; e 14 ISSUE 3 , I
BV-1 and 2 ODCM 1.1.1.2 BV-1 Setpoint Determination Based On Analysis Prior To Release l The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flov rate prior to dilution and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the Liquid Vaste Effluent Monitor (RM-LV-104) and the Laundry and Contaminated Shower Drains Monitor (RM-LV-116) during all operational conditions. The monitor alarm setpoint is set slightly above (a factor of 1.25) the count rate that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm .setpoint, the allovable discharge 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] 1.25 I i MPC g where: F = Dilution water flow rate, BV-1 Cooling Tower Blovdown (gpm). The dilution water flow rate may include the combined cooling tower blovdown flov from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges are administratively prohibited. Cg = Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uCi/ml) from analysis of the liquid effluent to be released. 1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response. MPCg = The liquid effluent radioactivity concentration limit for I radionuclide "i" (uci/ml) from Table 1.1-la. If not listed there, from Reference 1.1.3. G 1-5 ISSUE 3
BV-1 and 2 ODCH 1 1.1.1.2.2' BV-1 Monitor Count Rate j l The calculated monitor count rate (nepm).above background attributed to the radionuclides-(C.R.) is determined by: C.R. - 1.25 I Cy E g [1.1(1)-7] i 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 lj response. , 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 j '- 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-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 limitations or administrative selection. 1-6 ISSUE 3
BV-t and 2 ODCM 1.1.2 BV-2 Monitor Alarm Setp_oint Determination This procedure determines the monitor HIGH Alarm Setpoint that indicates l if the concentration of radionuclides in the liquid effluent released from the site to unrestricted areas exceeds the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases or exceeds a concentration of 2 E-4 uCi/ml for dissolved or entrained noble gases. The methodology described in Section 1.1.2.2 is an alternative method to be used to determine the monitor HIGH Alarm Setpoint (HSP). The methodology in Section 1.1.2.2 may be used for any batch release and shall be used when the total gamma radioactivity concentration of the liquid effluent prior to dilution exceeds 2.97E-5 uci/ml. This concentration is equivalent to a monitor response of 5.84E3 nepm (net counts per minute above background). The HIGH Alarm Setpoint derived in Section 1.1.2.1 of 2.97E-5 uCi/ml above background allows for a tritium concentration of up to 6.28E-2 uC1/ml. The setpoint was obtained by use of a conversion factor (cpm to uCi/ml) of 5.09E-9 determined for the nuclide mix. (See Reference 1.2.5) 1.1.2.1 BV-2 Setpoint Determination Based On A Conservative Mix The HIGH Alarm Setpoint for the Liquid Vaste Effluent Monitor (2SGC-ROIL 00) should be set at 2.97E-5 uCi/ml above background. This setpoint is based on the following conditions: Source terms given in Table 1.1-1b. These source terms have been generated by using models and input similar to NUREG-0017. The l inputs are given in Appendix B. Dilutlen water flow rate of 7,800 gpm. Discharge flov rate prior to dilution of 116 gpm for the Liquid Vaste Effluent Monitor (2SGC-ROIL 00). A software conversion factor (cpm to uCi/ml) of 5.09E-9 associated with Liquid Vaste Effluent Monitor (2SGC-ROIL 00). The above setpoints can be varied based on actual operating conditions resulting in the discharge and dilution flow rates as follows: ggp , 4.42E-7 F [1.1(2)-11 f where: HSP = Monitor HIGH Alarm Setpoint (uCi/ml) above background. 4.42E-7 = Proportionality constant based on nominal flow conditions (4.42E-7 = 2.97E-3 uCi/ml above background x 116 gpm + 7.8 E3 gpm). 1-7 ISSUE 3
BV-1 and 2'0DCM 1 F = Dilution water flow rate, BV-2 Cooling Tower Blowdown Rate
-(gpm).
D f = Discharge flow rate prior to dilution (gpm). i 1.1.2.1.1 BV-2 Mix Radionuclides The " mix" (radionuclides and composition) of the liquid effluent was determined as follows:
- a. The liquid source terms that are re$resentative of the " mix" of the liquid effluent vere 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" (Sg ) for each individual radionuclide in the liquid effluent was determined as follows:
A 5 i [1.l(2)-2] 1,EA 1 - 1 where: Ag - Annual release of radionuclide "i" (Ci/yr) in the liquid effluent from Table 1.1-1b. I 1.1.2.1.2 BV-2 Maximum Acceptable Concentration (All Radionuclides) The maximum acceptable total radioactivity concentration (uci/ml) of all radionuclides in the liquid effluent prior to dilution (C ) was t determined by: C t - F [1.1(2)-3) S I fI i MPC 3 where: F = Dilution water flow rate (gpm), BV-2 Cooling Tower Blovdown Rate (not including BV-1 Blovdown or the BV-2 release out through the Emergency Outfall Structure). .
- 7,800 gpm.
f - Maximum acceptable discharge flov rate prior to dilution (gpm).
- 116 gpm for Liquid Vaste Process Effluent Monitor (2SGC-R0Il00).
I 1-8 ISSUE 3
BV-1 and 2 ODCM MPCg = Liquid effluent radioactivity concentration limit for radionuclide "i" (uC1/ml) from Table 1.1-lb. If not listed there, from Reference 1.2.1. l S 1
= The fraction of total radioactivity attributed ta I radionuclide "i", from Equation [1.1(2)-2].
1.1.2.1.3 BV-2 Maximum Acceptable Concentration (Individual Radionuclide) l The maximum acceptable radioactivity concentration (uci/ml) of radionuclide "i" in the liquid effluent prior to dilution (C g) vas determined by: Cy=S1 C t [1.1(2)-4] 1.1.2.1.4 BV-2 Monitor Display Value The calculated monitor Display Value (uCi/ml) above background attributed to the radionuclides, D.V., was determined by: D.V. - 5.09E-9 I Cg E g [1.1(2)-5] i where: 5.09E-9 = Conversion factor (cpm to uCi/ml), 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 Monitor HSP l The monitor HIGH Alarm Setpoint above background (uCi/ml) should be set at the D.V. value. e 1-9 ISSUE 3
BV-1 and 2 ODCM 1.1.2.2 BV-2 Setpoint Determination Based on Analysis Prior To Release l The following method applies to liquid releases when determining the setpoint for the maximum acceptable discharge flow rate prior to dilution and the associated HIGH Alarm Setpoint based on this flow rate for the Liquid Vaste Effluent Monitor (2SGC-ROIL 00) during all operational conditions. The monitor alarm setpoint is set slightly above (a factor of 1.25) the concentration reading that results from the concentration of gamma emitting radionuclides in order to avoid spurious alarms. To compensate for this increase in the monitor alarm setpoint, the allovable discharge flow rate is reduced by the same factor. When the discharge flow rate is limited by the radvaste discharge pump rate capacity or by administrative selection rather than the allovable flow rate determined form activity concentration, the alarm setpoint vill be proportionally adjusted based upon the excess dilution factor provided. 1.1.2.2.1 BV-2 Maximum Acceptable Discharge Flov Rate The maximum acceptable discharge flow rate (f) prior to dilution (gpm) is determined by: f, F [1.l(2)-6] C l 1 1.25 I D i MPC g where: F = Dilution water flow rate, BV-2 Cooling Tower Blovdown (gpm). The dilution water flow rate may include the combined cooling tower blovdown flov from both units exiting the discharge structure (but excluding emergency outfall structure flow) when simultaneous liquid discharges from both plants are administrative 1y prohibited. Cg - Radioactivity concentration of radionuclide "i" in the liquid effluent prior to dilution (uci/ml) from analysis of the liquid effluent to be released. 1.25 = A factor to prevent spurious alarms caused by deviations in the mixture of radionuclides which affect the monitor response. MPC. = The liquid effluent radioactivity concentration limit for radionuclide "i" (uci/ml) from Table 1.1-lb. If not listed there, from Reference 1.2.1. 1-10 ISSUE 3
BV-1 and 2 ODCH 1.. 2.2.2 BV-2 Monitor Display Value 'j The calculated monitor Display Value (uci/ml) above background attributed to the radionuclides (D.V.) is determined by: 7 D.V. = (1.25) (5.09E-9) I C; Eg [1 1(2)-7] i where: 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. 5.09E Conversion factor (cpm to uCi/ml), an average determined for the source term mix. 1.1.2.2.3 BV-2 Monitor HSP The liquid effluent mo.. i t o r 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. , [1.1(2)-8] where: 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 nrior to dilution determined by equation [1.1(2)-61 f' = Actual maximum discharge flow rate,to be maintained for the discharge. The reduced value of f may be due to pump limitations or administrative selection, i 1-11 ISSUE 3
BV-1 and 2 ODCM TABLE 1,1-la BV-1 LIQUID SOURCE-TERM l 1 A l DETECTION
.MPC ANNUAL RELEASE I EFFICIENCY NUCLIDE (Cl)** (uCi/ml)*** (cpm /uCi/ml)****
Cr-51 9E-5 2E-3 1.07E7 Mn-54 2E-5 1E-4 8.80E7 Fe-55 8E-5 8E-4 5.20E3 Fe-59 SE-5 SE-5 ' 9.02E7 Co-58 7.7E-4 9E-5 1.19E8 Co-60 1.0E-4 3E-5 1.72E8 Np-239 SE-5 1E-4 .5.14E7 Br-83 6E-5 3E-6 1.36E6 Rb-86 1E-5 2E-5 7 . 571:6 Sr-89 2E-5 3E-6 7.84E3 Sr-91 1E-5 SE-5 1.27E8 Mo-99 3.90E-3 4E-5 2.42E7 Tc-99m 5.37E-3 3E-3 9.00E7 Te-127m 1E-5 5E-5 5.34E4 Te-127 3E-5 2E-4 4.17E5 Te-129m 7E-5 2E-5 5.37E6 Te-129 5E-5 8E-4 r.91E7 I-130 2.5E-4 3E-6 3.10E8 Te-131m 9E-5 4E-5 1.39E8 l- Te-131 2E-5 -- 1.09E8-I-131 6.027E-2 3E-7 1.06E8 Te-132 1.15E-3 2E-5 1.17E8 I-132 5.38E-3 8E-6 2.75E8 I-133 5.769E-2 1E-6 1.01E8 I-134 1E-5 2E-5 2.43E8 Cs-134 3.80E-3 9E-6 2.06E8 I-135 1.338E-2 4E-6 1.22E8 Cs-136 1.90E-3 6E-5 3.02E8 Cs-137 2.70E-3 2E-5 7.65E7 Ba-140 1E-5 2E-5 5.21E7 La-140 1E-5 2E-5 1.74E8 H-3 1.60E+2 3E-3 OE0 All Others* 4E-5 1E-7 OE0 TOTAL
- 1.60E-1 -- --
- Excluding Tritium and Entrained Noble Gases
** Reference (1.1.2)
) *** Reference (1.1.3)
**** Reference (1.1.4) 1-12 ISSUE 3
BV-1 and 2 ODCM TABIE 1,1-lb BV-2 LIQUID SOURCE TERM E G i MFC DETECTION ANNUAL RELEASE i EFFICIENCY NUCLIDE (Cl)*** (uCi/ml)** (cpm /uCi/ml)**** Cr-51 1.00E-4 2E-3 2.01E7 Mn-54 2.50E-5 1E 4 1.27E8 Fe-55 1.30E-4 8E-4 -* Fe-59 6.50E-5 5E-5 1.26E8 Co-58 1.10E-3 9E-5 1.82E8 Co-60 1.60E-4 3E-5 2.38E8 Np-239 3.20E-5 1E-4 1.65E8 Br-83 2.90E-5 3E-6 2.42E6 Br-84 5.90E-9 -- 1.38E8 Rb-86 3.70E-5 2E-5 1.04E7 Rb-88 0.0 -- 4.84E7 Sr-89 2.20E-5 3E-6 1.83E4 Sr-90 8.50E-7 3E-7 -* Sr-91 5.30E-6 SE-5 1.04E8 Mo-99 2.30E-3 4E-5 4.47E7 Tc-99m 2.10E-3 3E-3 1.40E8 Te-125m 1.90E-6 1E-4 3.94E5 Te-127m 2.10E-3 SE-5 1.26ES Te-127 2.50E-5 2E-4 2.43E6 Te-129m 8.20E-5 2E-5 6.53E6 'l Te-129 5.30E-5 8E--4 1.96E7 I-130 2.30E-4 3E-6 5.18E8 Te-131m 5.20E-5 4E-5 2.85E8 Te-131 9.40E-6 -- 1.88E8 I-131 1.00E-1 3E-7 1.96E8 Te-132 7.80E-4 2E-5 1.76E8 I-132 2.30E-3 8E-6 4.22E8 I-133 6.50E-2 1E-6 1.73E8 I-134 4.60E-6 2E-5 4.06E8 Cs-134 3.00E-2 9E-6 3.25E8 I-135 9.20E-3 4E-6 1.71E8 Cs-136 3.90E-3 6E-5 4.28E8 Cs-137 2.20E-2 2E-5 1.28E8 Ba-140 9.30E-6 2E-5 7.50E7 La-140 8.40E-6 2E-5 3.08E8
- Insignificant
** Reference (1.2.1) *** Reference (1.2.3) **** References (1.2.2) and (1.2.4) 1-13 ISSUE 3 i
BV-1 and 2 ODCM TABLE 1.1-lb (continued) BV-2 LIQUID SOURCE TERM E g A i " i DETECTION ANNUAL RELEASE EFFICIENCY NUCLIDE (C1)*** (uCi/ml)** (cpm /uCi/ml)**** Y-90 6.00E-7 2E-5 -* Y-91m 3.60E-6 3E-3 1.59E8 Y-91 4.40E-6 3E-5 3.55E5 Y-93 3.00E-7 3E-5 2.03E7 Zr-95 4.00E-6 6E-5 1.35E8 Nb-95 4.00E-6 1E-4 1.33E8 Ru-103 2.70E-6 8E-5 1.71E8 Ru-106 8.20E-7 1E-5 -* Rh-103m 2.70E-6 1E-2 -* Rh-106 8.20E-7 -- 5.65E7 Ce-141 4.00E-6 9E-5 7.75E7 Ce-143 8.60E-7 4E-5 1.20E8 Ce-144 2.60E-6 1E-5 1.87E7 Pr-143 2.30E-6 SE-5 1.63E0 Pr-144 2.60E-6 -- 3.40E6 H-3 5.50E+2 3E-3 0.0 j
- Insignificant
** Reference (1.2.1)
*** Reference (1.2.3) q **** References (1.2.2) and (1.2.4) 1-14 ISSUE 3
BV-1 and 2 ODCH REFERENCES BV-1 LIQUID EFFLUENT MONITOR SETPOINTS. 1.1.1 " Beaver Valley Power Station, Appendix I Analysis - Docket.No. 50-334 and 50-412"; Table 2.1.3 1.1.2 " Beaver Valley Power Station, Appendix I Analysis - Docket No. 50-334 and 50-412"; Table 2.1.2 1.1.3 10 CFR 20, Appendix B, Table II, Column 2 and footnotes 1.1.4 "Duquesne Light Co., Beaver Valley Nuclear Plant, Specification No. BVPS' 414, Table V Nuclide Data, 5/30/74"; Table 2 and Figure 1 REFERENCES BV-2 LIQUID EFFLUENT HONITOR SETPOINTS 1.2.1 10 CFR 20, Appendix B, Table II, Column 2 and footnotes 1.2.2 Unit 2 DRMS Isotopic Efficiencies; DLCo Calculation Package No. ERS-SFL-86-026 1.2.3 Stone and Vebster Computer Code LIO1BB; " Normal Liquid Releases From A Pressorized Vater Reactor" 1.2.4 Isotopic Efficiencies For 2SGC-ROIL 00; DLCo Calculation Package No. ERS-JVV-87-015 1.2.5 Conversion Factor for 2SGC-R0Il00; D'.Co Calculation Package No. ERS-VFV-87-021 1-15 ISSUE 3
K :1 l 40 4+3+* %Q @f 'k y/ IMAGE EVALUATION v x //q// 'tj' *gk/ TEST TARGET (MT-3)- b ssk4 4h
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BV-1 and 2 ODCM 1.2 Compliance Vith 10 CFR 20 MPC Limits (ODCM Appendix.C CONTROL 3.11.1.1) I~ 1.2.1 Batch Releases l'.2.1.1 Pre-Release The radioactivity content of each batch release vill be determined prior to release in accordance with ODCM Appendix C, Table 4.11-1. in order to assure representative samples, at least two tank volumes of entrained fluid from each tank to be discharged shall be recirculated through the mixing eductors. This vill be accomplished by recirculating the tank contents for at least the time periods indicated 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 manner: The activity of the various radionuclides in the batch release, determined in accordance with ODCM Appendix C, Table 4.11-1, is divided by the minimum filution flow to obtain the concentration at the unrestricted area. This calculation is shown in the following equation: C R Cone 1 [1.2-1] I " MDF vhere: Coneg = Concentration of radionuclide "i" at the unrestricted area (uCi/ml). I Cg = Concentration of radionuclide "i" in the potential batch release (uCi/ml). R = Release rate of the batch (gpm). MDF = Minimum dilution flow (gpm). (May be combined BV *./BV-2 flov vhen simultaneous liquid discharges are administratively prohibited). The projected concentrations in the unrestricted area are compared to the concentrations in Appendix B, Table II of 10 CFR 20. The most common MPC g concentrations are listed in Table 1.1-la and 1.1-lb and vere taken from Appendix B, Tab 1c II of 10 CFR 20. Before a release is authorized, Expression [1.2-2] must be satisfied. I f (Cone g/MPCg ) < 1 [1.2-2] vhere MPCg = Maximum permissible concentration of radionuclide "i" (uCi/ml) from Appendix B Table II of 10 CFR 20. D 1-16 ISSUE 3
[ BV-1 and 2 ODCM 1.2.1.2 Post-Release The concentration of each radionuclide following re: ase from the batch tank vill be calculated in the unrestricted ar- a in the following
. 1 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: C Y Cone g, ik tk ADF [1.2-3] k where: Concik = The concentration of radionuclide "i" (uCi/ml) at the unrestricted area, during the release period of time k. Note: Since discharge is from an isolated well-mixed tank at essentially a uniform rate, the difference between average and peak concentration within any discharge period is minimal. C ik = Concentration of radionuclide "i" (uci/ml) in batch release during time peirod k. V tk = Volume of tank released during time period k (gal). ADF k - Actual volume of dilution flow during the time period of release k (gal). To show compliance with ODCM Appendix C CONTROL 3.11.1.1, the following relationship must hold: Ei (Conc ik/MPC;) f1 [1.2-4) G 1-17 ISSUE 3
BV-1 and 2 ODCM 1.2.2 Continuous Releases Continuous releases of liquid effluents do not presently occur at BV-1 or BV-2. If they did occur, the concentration of various radionuclides in the unrestricted area vould be calculated using Equation J1.2-ll with C g p' , the concentration of isotope i in the continuous release. To shov compliance with ODCM Appendix C CONTROL 3.11.1.1, Expression [1.2-4] must again hold. B b 1-18 ISSUE 3
'l BV-1 and 2 ODCM TABLE 1.2-la BV-1 RECIRCULATION TIMES REQUIR3D BEFORE SAMPLING OF LIQUID DISCHARGE TANKS l
l APPR0XIMATE RECIRCULATION NAME (BY OPERATING MANUAL) MARK NO.
"d Laundry And Contaminated ILV-TK-6A & 6B 4.5~
Shover Drain Tanks Low Level Vaste Drain Tanks ILV-TK-3A & 3B 2.5" c High Level Vaste Drain Tanks ILV-TK-2A & 2B 6" a Evaporator Test Tanks ILV-TK-5A & 5B 2 8 Steam Generator Drain Tanks 1LV-TK-7A & 7B 11.5 Boron Recovery Test Tanks 1BR-TK-2A & 2B 9.7 b G 8 From BVPS-1 Operating Manual, Chapter 17, Section 4. b Derived from information in BVPS-1 Operating Manual, Chapter 8, Section 1. c Not normally a direct source of discharge. d The times listed are those required for two recirculations cf a full tank with one recirculation pump in operation. Partially full tank recirculation times , are directly proportional to the fraction of the tank capacity occupied by the entrained liquid vaste after isolation. 1-19 ISSUE 3
BV-1 and 2 ODCM j TABLE 1.2-lb I BV-2 RECIRCULATION TIMES REQUIRED BEFORE SAMPLING OF LIQUID DISCHARGE TANKS l l APPROXIMATE RECIRCULATION NAME MARK NO. a (BY OPERATING MANUAL) (h ) Liquid Waste Tanks 2LVS-TK21A,B 8.3 Steam Generator Blowdown 2SGC-TK21A,B 33.3 Hold Tanks SGC Test Tanks 2SGC-TK23A,B 6.0
)
I I l 1
^ The times listed are those required for two recirculations of a full tank with one recirculation pump in operation. Partially full tank recirculation times are directly proportional to the fraction of the tank capacity occupied by the entrained liquid vaste after isolation.
D information in BVPS-2 Operating Manuals 2.17.1 and 2.25.1. Values were derived from I 1-20 ISSUE 3
BV-1 and 2 ODCM 1.3 Compliance Vith 10 CFR 50 Dose Limits (ODCM Appendix C CONTROLS 3.11.1.2 And 3.11.1.3) BV-1 and 2 utilize the concept of a shared liquid radioactive vaste system according to NUREG 0133. This permits mixing of the liquid radvaste for processing. Since the resulting effluent release cannot accurately be ascribed to a specific reactor unit, the treated effluent releases are allocated as defined below. 1.3.1 Cum lation Of Doses (ODCM Appendix C CONTROL 3.11.1.2) The dose contribution from the release of liquid effluents vill be calculated monthly for each batch release during the month and a cumulative summation of the total body and organ doses vill be maintained for each calendar month, current calendar quarter, and the calendar year to date. The dose contribution vill be calculated using the following equation: DT = UAF I A h E ot C *-} i k=1 k ik k where: DT = The cumulative dose commitment to the total body or any organ, T, from the liquid effluents for the total time period m I otk (*#**) k=1 otk = The length of the kth release over which Cik and F k e averaged for all liquid releases (hours). C9' - The average concentration of radionuclide, "i" (uci/ml), in undiluted liquid effluent during time period ot from any liquid k release. A IT = 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 flow to the product of the average flov from the site discharge structure during the report period to unrestricted receiving waters, times 3. (3 is ' .e site specific applicable factor for the mixing effect of the LV-1 and BV-2 discharge structure).
= Vaste Flow (3)(Dilution Vater Flow) 1-21 ISSUE 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 f vas calculated for an adult for each isotope using thefollowingequk'tionfromNUREG-0133. Ah = 1.14E5 (730/Dy+ 21BF g)DF H [1.3-2] where: 1.14E5 = IE6 pCi x IE3 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 vithin 1/4 mile of the release point to the potable water intake for adult vater consumption.
21 = Adult fish consumption (kg/yr). BF I = Bioaccumulation factor for radionuclide "i" in fish from Table A-1 of Regulatory Guide 1.109 Rev. 1 (pCi/kg per pCi/1). If none, from Regulatory Guide 1.109, Rev. O. DF IT = Dose conversion factor for radionuclide "i" for adults for a particular organ T f rom 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 DV-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 vater surface, essentially fully mixed conditions vould have to exis' for the radioactive effluent to be transported to the intake. The cumulative doses (from each reactor unit) for a calendar quarter and a calendar year are compared to ODCM Appendix C CONTROL 3.11.1.2 as follows: For the calendar quarter, D < 1.5 mrem total body [1.3-3] D T-
- 5 mrem any organ [1.3-4) 1-22 ISSUE 3
BV-1 and 2 ODCM 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] _ce exceeded, a Specia! Report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and Technical Specification 6.9.2f must be filed with the NRC at the identified locations. 1.3.2 Projection Of Doses (ODCM Appendix 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, when the projected doses due to liquid effluent releases from each reactor unit, when averaged over 31 days vould exceed 0.06 mrem to the total body or 0.2 mrem to any organ. Doses used in the projection are obtained according to equation [1.3-1j. The 31-day dose projection shall be performed according to the following equations: When including pre-release data, [1.3-7] D A+B 31 + C 31 = When not including pre-release data, [1.3-8] D A 31 + c 31 = r where: D Projected 31 day dose (mrem). A 31 =
= 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). 1-23 ISSUE 3
BV-1 and 2 ODCM TABLE 1,3-1 Ag VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem /hr per uCi/ml) NUCLIDE B0NE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 C-14 3.13E 04 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 6.26E 03 Na-24 4.08E 02 4.08E 02 4.06E 02 4.08E 02 4.08E 02 4.08E 02 4.08E 02 P-3h 4 hbb bbb h9k bb b bbb bk b$bbb bk b bbb bk 5 9b b6 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 bobh b bbb bk h kbb bk b Sbb bk b$bbb bk b bbb bk b$bbb b5 b bbb bh 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 Nibb b hb bk h k6b bb k bbb bb b bbb bk b bbb bk b bbb bk 5 hkb bh 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 n 5 h 3hh b$ h bhk b$ 3 bbb b4 b bbh bk b 95b b4 b$bbk b5 4$b4h b4 Zn-69 4.93E 01 9.43E 01 6.56E 00 0.00E-01 6.13E 01 0.00E-01 1.42E 01 l Br-83 0.00E-01 0.00E-01 4.04E 01 0.00E-01 0.00E-01 0.00E-01 5.82E 01 Br-84 0.00E-01 0.00E-01 5.24E 01 0.00E-01 0.00E-01 0.00E-01 4.11E-04 Br-85 0.00E-01 0.00E-01 2.15E 00 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Rb-86 0.00E-01 1.01E 05 4.71E 04 0.00E-01 0.00E-01 0.00E-01 1.99E 04 Rb b bb b h 9bb bh $ bkb bh b bbk b$ b bbk b$ b bbh bk b bbk b9 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 brhb 555bb b5 b$bbb b5 5 35b b5 b$bbb5b5 b$bbb5b5 b5bbb5b5 5$5bb b5 Sr-91 4.10E 02 0.00E-01 1.65E 01 0.00E-01 0.00E-01 0.00E-01 1.95E 03 Sr-92 1.55E 02 0.00E-01 6.72E 00 0.00E-01 0.00E-01 0.00E-01 3.08E 03 l h9b b$bbb b5 b bbb bi k$bbb bh b.bbb bk b$bbb b5 b bbb bk 65kbb bb Y-91m 5.48E-03 0.00E-01 2.12E-04 0.00E-01 0.00E-01 0.00E-01 1.61E-02 Y-91 8.50E 00 0.00E-01 2.27E-01 0.00E-01 0.00E-01 0.00E-01 4.68E 03 l 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 hr-9h kbbb2 h hhb bb k h9h bb b bbb b b hhb bb b bbk bk b hbh bh Nb-95 4.47E 02 2.48E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 Nb-97 3.75E 00 9.48E-01 3.46E-01 0.00E-01 1.11E 00 0.00E-01 3.50E 03 1-24 ISSUE 3
BV-1 and 2 ODCM TABLE 1,3-1 Ag VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE l- (mrem /hr per uCi/ml) NUCLIDE BONE LIVER T-BODY THYROID KIDNEY LUNG GI-LLI Mo-99 0.00E-01 1.05E 02 2.00E 01 0.00E-01 2.38E 02 0.00E-01 2.43E 02 Tc-99m 8.97E-03 2.54E-02 3.23E-01 0.00E-01 3.85E-01 1.24E-02 1~50E 01 . Tc-101 9.23E-03 1.33E-02 1.30E-01 0.00E-01 2.39E-01 6.79E-03 4.00E-14 Ru-103 4.51E 00 0.00E-01 1.94E 00 0.00E-01 1.72E 01 0.00E-01 5.26E 02 Ru-105 3.75E-01 s.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 Te555m UIbhb b3 9$5bb b3 b$5 b b3 h$h5b bb 5$bkb b5 bIbbb bk 5$b3b b5 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 5.53E 04 Te-129 3.01E 01 1.13E 01 7.33E 00 2.31E 01 1.26E 02 0.00E-01 2.27E 01 Te-131m 1.66E 03 8.10E 02 6.75E 02 1.28E 03 8.21E 03 0.00E-01 8.05E 04 Te-131 1.89E 01 7.88E 00 5.96E 00 1.55E 01 8.27E 01 0.00E-01 2.67E 00 } Te-132 2.41E 03 1.56E 03 1.47E 03 1.72E 03 1.50E 04 0.00E-01 7.39E 04 Te-134 3.10E 01 2.03E 01 1.25E 01 2.71E 01 1.96E 02 0.00E-01 3.44E-02 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 Ol' O.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 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 C.00E-01 6.85E 04 9.39E 03 1.40E 04 Cs5bh b 8hb bb 5$hhb b5 b$$hb bb b$bbb bk k$hhb b5 bb9bb4 b E b4 Cs-138 2.64E 02 5.22E 02 2.59E 02 0.00E-01 3.84E 02 3.79E 01 2.23E-03 Ba-139 9.69E-01 6.90E-04 2.84E-02 0.00E-01 6.45E-04 3.92E-04 1.72E 00 ba kkb h bbb bh h 5bb bk k$35b hk b bbb hk b 6bk bh k 46k b b bb b Ba-141 4.71E-01 3.56E-04 1.59E-02 0.00E-01 3.31E-04 2.02E-04 2.22E-10 Ba-142 2.13E-01 2.19E-04 1.34E-02 0.00E-01 1.85E-04 1.24E-04 3.00E-19 La54b k bkk bk h 59b bh h$bkb bh b bbb bk b bbb bk b$bbb bk 5 bhb b3 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 1-25 ISSUE 3
i i BV-1 and 2 ODCM l TABLE 1.3-1 A t VALUES FOR THE ADULT FOR THE BEAVER VALLEY SITE (mrem /hr per uCi/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 C.00E-01 1.28E 02 Ce-144 1.37E 00 5.73E-01 7.36E 02 0.00E-01 3.40E-01 0.00E-01 4.64E 02 Pr-143 5.54E-01 2.22E-01 2.75E-02 0.00E-01 1.28E-01 0.00E-01 2.43E 03 P k bkb 7 bhb bh h hhb b b bbk b 4b5hb4 bbbbb h6 b Nd- 147 3.79E-01 4.38E-01 2.62E-02 0.00E-01 2.56E-01 0.00E-01 2.10E 03 'J-18 7 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 e 1-26 ISSUE 3
l BV-1 and 2 ODCM I 1.4 LIQUID RADVASTE SYSTEM ! l 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 stee.m 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. , k 1 1-27 ISSUE 3
BV-1 and 2 OCCM FIGURE 1.4-1 BV-1 LIQUID RADWASTE SYSTEM STREAM STREAM COLLECTION, TREATMENT. f. OlSCH ARGE e PS-
- 1. CONT SUMP 40GPD TOWER HIGH -LEVEL LIQUID EV APOR ATOR BLOWOOWN
- 2. 2OOGPD TE WASTE TEST AUX BLOG SUMP SO GPM '
ORAIN EVAPORATOR TAN N S (2)
- 3. LAB DRAINS 4000PD TANMS (2) ' '
OR a,000 GA L 3.000 G AL
- 4. R.P. SA MPLES 35GPD g, g i' TOWER S. MISC. SOURCE S 660GPD ;i BLOWOOWN STEAM 15,000 GPM
- 6. MISC. SOURCES 400PD GENERATOR
~
' 'B S-l 6-2 7 SG PRE FtLTER 10 GFD TANKS (2) 8ACK WAS*1 30,000 CAL dis ARGE SO GPM pot N T BORON TEST TANKS (2) 14,500 G AL PURIFICATION CS lON BORON BORON
- 8. CVCS LETDOWN 60GPM ION EXCHANGER
- DEGASIRER 500# EXCHANGER RECOVERY EVAPOR ATORS(2)l TA NKSL2) --
1SGPM (SVP S -1) ' DF 2 10* 2*10 DF
- lO,2,30 '
/HR 195,000 IOS ALL EXCEPT I GAL 108 I BVPS-2 HI PURlFIC A T IO N CS ION S TE AM CVCS LETDOWN iN E XCH A NGER 500 # EXCHANGE 0 GENERATOR 9- 60 GPM
- DEGAStFIER " BLOW DOWN (8vPS-2) -
Op s 10,2,60 OF s lO,2,10 EVAPORATOR
/ HR
- 80. BVPS-1 TURB1NE T,2 OO G PO NO COLLECTION OR TREATMENT-BLOG DRAINS ENVIRONMENT " COOLING TOWER lBVPS-1 YARo NOTESs. ORAINAGE BLOWDOWN AND ENVIRONMENT
- 1. INPUT TO BVPS-2 STE AM GENERATOR DISCHARGE POINT)
BLOWDOWN EVAPOR ATOR IS NOT USE D DURING NORMAL B ASE LOADED OPERATIONS. SEE SEC 11.2.1 FOR OtSCUSSION. ISSUE 3 1-28
- - b_.__________
BV-1 M
. FIGURE 1.4-2 BV-2 LIQUID RADWASTE_ SYSTEM b "[A N
STREAM AT COLLECTION, TREATM ENT, C. DISCH ARGE OVPS-l B V PS -I COOLIN G EVAPORATOR TOWER BLOWDOWN
- l. CON T SUMP 40GPO FEED PUMPS 15,000 GPM
- 2. AUX eLDG SUMP 2OO GPD WASTE LIQUID WASTE BVPS-2 DR AINS 1P WASTE TEST 100 GPM , COOLING
~* TOWER
- 3. MISC SOURCES 700 GPD TANKS (2) EVAPORATOR TANKS (2)
OR BLO W OOWN
- 4. R.P. S A M PLES 35 GPD STEAM S. LAB DRAINS 400 GPD 80 DO _
HOLD TANKS BV P S-16 -2 CONDENS ATE DEMIN 6* RINSE WASTE 2*685 GPO COOLING TOWER O DISCH ARG E 7* BVPS-2 TURBINE 7,200 GPO NO COLLECTION OR TREATMENT ist E N VIRON ME NT P Olf4 T BUILDING DRAINS - (BVPS-2 YARD DR AIN AGE DISCHARGE POINT I NOTES:
- 1. NO STEAM GENER ATOR BLOWOOWN IS DISCHARGED.
- 2. THE WASTE EVAPOR ATORS ARE ACTU ALLY TITLED STEAM GEN E R ATOR BLOWDOWN EVAPOR ATORS.
- 3. DECONTAMIN ATION FACTORS STATE D ARE FOR EVAPOR ATOR DISCHARGES TO BVPS-2 SYSTEM INCLUDING inE CttAN UP ION EXCHANGERS. COOLING TOWER
- 4. THERE IS NO EXPECTED INPUT FROM BVPS-l EVAPORATOR BLOWDOWN AND ENVIRONMENT FEE D PUMPS DURING NORM AL BASE LOADED OPER ATION.
OPER ATIONS IS DISCUSSED IN SECTION It,2.1. 1 TURBINE BUILDING DR AINS ARE PROCESSED BY THE LlOut0 WASTE SYSTEM UPON HtGH ACTIVITY. ISSUE 3 1-29 i i
BV-1 and 2 ODCM 2.0 GASEOUS EFFLUENTS ODCM Appendix C CONTROLS applicable to dose rate apply to the site. The D 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 specific unit in the determination of site dose rate and dose attributed to ~ that unit. Elevated releases from both units are considered to originate from a shared radvaste system and are discharged- from a common release point, the Process Vent, at the top of the BV-1 cooling tower. At BV-1 and-BV-2, the dose from the shared radvaste system via the Process Vent is normally apportioned equally to the units. However, a containment purge via the Process Vent shall be attributed to a specific unit. I 2-1 ISSUE 3
BV-1 and 2 ODCM 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 j 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. The methodologies described in Section 2.1.1.2, 2.1.2.2, and 2.1.3.2 provide an alternate means of determining monitor alarm setpoints that may be used when an analysis is performed prior to release. Control of the site dose rate limit due to noble gases is exercised by a total of 8 effluent stream monitors, of whicn 3 are located in BV-1 (alternates exists for these monitors), and 5 are located in BV-2. As previously noted, BV-2 elevated releases are via the BV-1 Process Vent. Differences exist between the setpoint presentations of the radiation monitoring systems of BV-1 and BV-2. First, there is a difference in setpoint terminology. Where BV-1 uses HIGH and HIGH-HIGH the BV-2 equivalents are ALERT and HIGH. The second difference is that the BV-2 setpoint is presented in uCi/cc rather than cpm as in BV-1. This difference is due to BV-2 software which applies a conversion factor to B the BV-2 raw data (cpm). The user is cautioned that the uCi/cc presentation is technically correct only for the specific isotopic mix used in the determination of the conversion factor. In practice, setpoints determined for a calculated mix are correct for that mix. Setpoints determined on analysis prior to release vill be correct for 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 HIGH (BV-2) Alarm Setpoints established at 30 percent of the site limit, and except 3 monitors noted belov, HIGH (BV-1) or ALERT (BV-2) Alarm Setpoints established at 10 percent of the site limit. 2-2 ISSUE 3
BV-1 and 2 ODCH Monitor Setpoint Specifications Based On Fraction Of Site Limit 4 UNIT, RELEASE POINT AND MONITOR FRACTION OF SITE LIMITING DOSE R 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) 2RM0-R0301B Unit 2, Condensate Polishing Building Vent 30% (HIGH) 0.6% (ALERT) 2HVL-R0112B Units 1/2, Turbine Building Vent < 0.1% (Unmonitored) With the monitor setpoints based on fractions of the site limit as defined above, the following criteria may be applied to determine that the dose rate due to noble gas released from the site complies with ODCM 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) and ALERT (BV-2) Alarm Setpoints.
- Vith all monitors below the normal HIGH-HIGH (BV-1) and HIGH (BV-2)
Alarm Setpoints, a combination of 3 HIGH (BV-1) or ALERT (BV-2) Alarms indicate releases may have exceeded site limits.
- To provide operational flexibility any 1 of the HIGH-HIGH (BV-1) or HIGH (BV-2), Containment. Ventilation, or Process Vent monitor setpoint may be doubled to 60% of the site limit if all other monitors in this group are held below the HIGH (BV-1) and ALERT (BV-2) Alarm Setpoints.
From this condition any 1 monitor alarm would indicate the site dose rate limit may have been exceeded. G 2-3 ISSUE 3
BV-1 and 2 ODCM l l A release may be batch or continuous in nature. Batch refers to releases that are intermittent in radionuclide concentrations or flow, such as releases from gas storage tanks, containment ventings and purges, and
} Batch releases may be due to systems or components with infrequent use.
operational variations which result in radioactive releases greater than 50% of the releases normally considered as continuous. Batch teleases from these sources during normal operation, including anticipated operational occurrences, are defined as those which occur for a total of 500 hours or less in a calendar year, but not more than 150 hours 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 lovest setpoint obtained according to the following Sections 2.1.1.1 through 2.1.3.2. B B 24 ISSUE 3
BV-1'and 2'0DCM 2.1.1.1 BV-1 Setpoint Determination Based On A Calculated Mix For Ventilation Vent And Containment Building Vent Releases (Ground Releases) The calculated monitor count rate above background (C.R.), in nepm, the monitor HIGH-HIGH alarm setpoint above . background (HHSP), and the monitor HIGH alarm setpoint above background (HSP) for each vent and operational condition should be as follows: BV-1 ALARM SETPOINTS FOR GROUND RELEASES cpm AB0VE BACKGROUND (P) PRIMARY
- 30% 10%
MONITOR SITE SITE (A) ALTERNATE LIMIT LIMIT MONITOR C.R. HHSP HSP
' Continuous Release Via The (P)RM-VS-101B 3.00E3 9.00E2 3.00E2 .
BV-1 Ventilation Vent (A)RM-VS-109(5) 1.47E3 4.40E2 1.47E2
- Batch Release Of Containment (P)RM-VS-101B 3.90E2 1.17E2 3.90E1 Purge Via The BV-1 Ventila- (A)RM-VS-109(5) 4.68E2 1.40E2 4.68E1 tion Vent
- Continuous Release Via The (P)RM-VS-107B 6.44E3 1.93E3 6.44E7 BV-1 Containment Building (A)RM-VS-110(5) 3.38E3 1.01E3 3.38E2 i 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(3) 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 vere 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).
G 2-5 ISSUE 3
BV-1 and 2 ODCM
Discharge flov' rate of 49,300 cfm ~ for the BV-1 Containment Vent (Both continuous and batch release of Containment Purge).
I
- 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 was used to derive the monitor setpoints for.the following operational conditions:
' Continuous release via the BV-1 Ventilation Vent.
- Continuous release via the BV-1 Containment Building Vent.
- Batch release of BV-1 Containment Purge via the BV-1 Ventilation Vent.
- Batch release of BV-1 Containment Purge via the BV-1 Containment Building Vent.
2.1.1.1.1 BV-1 Mix Radionuclides The " mix" (noble gas radionuclides and compositien) 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. Gaseous source terms are the radioactivity of the noble gas radi6nuclides in the effluent.
I Gaseous source terms can be obtained from Table 2.1-la,
- b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (5 ) for each individual 4
noble gas radionuclide in the gaseous effluent vas determined by: A S i [2.1(1)-1] y,IA g i where: A y = 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 icaximum Acceptable Release Rate (Vhole Body Exposure) The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (O ) based upon the whole body t exposure limit was calculated by: 0 500 [2.1(1)-21 t = (X/0) EKg S; i I
~
2-6 ISSUE 3
BV-1 and 2 ODCM where: (X/0)yy - The highest calculated annual average relative concentration of effluents released via the Ventilation . Vent for any area at or beyond 3 the_ unrestricted area boundary for all sectors-(sec/m ) f rom 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/m for batch release of containment purge.
(X/0)C" = 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/m3) from Table 2.2-4. 3
= 9.24E-5 sec/m for continuous releases.
(X/q)cv = released The shortvia term relative concentration of effluents the containment 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/m for batch release of containment purge.
Kg = The total whole body dose factor due to gamma 3 emissions from noble gas radionuclide "i" (mrem / year /uCi/m ) i from Table 2.2-11. Sg = From equation [2.l(1)-1) above. 2.1.1.1.3 BV-1 Maximum Acceptable Release Rate (Skin Exposure) O was also determined based upon the skin exposure limit by: t 0 3000 [2.1(1)-31 t
= (X/0) E (L1 + 1.1Mg) Sg i
vhere: Lg = The skin dose factor due to beta 3emissions from noble gas radionuclide "i"(mrem / year /uci/m ) 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. G 2-7 ISSUE 3
BV-1 and 2 ODCM 1.1 = The ratio of the tissue to air absorption coefficients over the energy range of the photons of interest, D (mrem / mrad). (X/0) = Same as in Section 2.1.1.1.2. 2.1.1.1.4 BV-1 Maximum Acceptable Release Rate (Individual Radionuclide) The maximum acceptable release rate (uCi/sec) of noble gas radionuclide "i" in the gaseous effluent (0 ) for each individual 1 noble gas radionuclide in the gaseous effluent was determined by: Og -S i O t I'( )~ I (NOTE: Use the lover of the Q values obtained in Section 2.1.1.1.2 and 2!1.1.1.3.) 2.1.1.1.5 BV-1 Maximum Acceptable Concentrations (Individual Radionuclide) The maximum acceptable radioactivity concentration (uci/cc) of noble gas radionuclide "i" in the gaseous effluent (C;) for each individual noble gas radionuclide "i" in the gaseous effluent was determined by: O [2.1(1)-5] C i 3 ~_ F vhere: F = The maximum acceptable effluent flow rate at the point of release (cfm).
= 62,000 cfm (BV-1 Ventilation Vent)
= 49,300 cfm (BV-1 Containment Building Vent) 3 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-5 ft /cc).
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. = IC E g [2.1(1)-6)] i 3 where: Eg = The detection efficiency of the monitor for noble gas radionuclide "i" (cpm /uci/ce) from Table 2.1-2a. 2-8 ISSUE 3
t -. k BV-1 and 2 ODCM 2.1.1.1.7 BV-l'Honitor Setpoints The monitor alarm setpoints above background vere determined as follows:
- a. The monitor HIGH-HIGH Alarm Setpoint above background (nepm) was determined by:
HHSP - 0.30 C.R. [2.1(1)-71
- b. The monitor HIGH Alarm Setpoint above background (nepm) was determined by:
HSP = 0.10 C.R. [2.1(1)-8] NOTE: The values 0.3 for the HHSP and 0.1 for the HSP are fractions of the total radioactivity concentration that may be released-via the monitored pathway to ensure that the site boundary limit is not exceeded due to simultaneous releases from both units. G
.)
l l f til 2-9 ISSUE 3
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 Releases) When the setpoints established using "the calculated mix" for ground i 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 ll[ the Containment Building Gas Monitor (RM-VS-107B) during the following operational conditions:
- Batch release of Containment Purge via the BV-1 Ventilation Vent.
- Batch release of Containment Purge via the BV-1 Containment Building Vent.
2.1.1.2.1 BV-1 Maximum Acceptable Release Rate The maximum acceptable discharge flov rate from Containment Vent or Ventilation Vent during purging is determined as follows:
- a. The maximum acceptable gaseous discharge flow rate (f) from the Containment Vent or Ventilation Vent (cfm) during purging based upon the whole body exposure limit is calculated by:
1.06 S T [2.1(1)-17] (X/q) IKg C 1 1 where: 1.06 = 500 mrem /yr x 2.12E-3 500 mrem /yr = dose rate limit 2.12E-3 = unit conversion factor 3
= (60 sec/ min x 3.53E-5 ft /ce)
S = Percent of site dose rate released via this pathway. Up to 60% of the site dose rate is permissible for one release point under the alarm set point rules of Section 2.1.1. To exceed 60% of the site limit from one release point, the remaining release point limits must be correspondingly reduced or secured to provide the necessary mare i n below the site dose rate limit. T = Maximum valve for T is 16 based on the limiting restriction in ODCM Appendix C CONTROL 3.11.2.1.a where the dose rate for a containment purge may be averaged over a time period not to exceed 960 minutes. (As containment air volume change time period is 60 minutes: Tx 960/60 = 16). See Reference 2.1.6. 2-10 ISSUE 3
~BV-1 and 2 ODCM (X/q)vv = The highest calculated short term relative 'I concentration of effluents released via the Ventilation Vent for any area at or beyond3the unrestricted area boundary for all sectors (sec/m.) from' Table 2.3-36.
- 3.32E-4 sec/m 3 (X/q)C" - The highest calculated short term relative concentration of effluents released via'the Containment Building Vent for areas 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. C - The undiluted radioactivity concentration of noble gas 1 radionuclide "i" in the gaseous source (uCi/cc) as determined by analysis of the gas to be released,
- 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 (Lg + 1.1Mg ) Q i where: 6.36 - 3000 mrem /yr x 2.12E-3 3000 mrem /yr = dose rate limit 2.12E-3 = unit conversion factor
= (60 sec/ min x 3.53E-5 ft /cc)
L 3
= 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 3I "** 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 rkin 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.
G 2-11 ISSUE 3
BV-1 and 2 ODCM 2.1.1.2.2 BV-1 Honitor Setpoints' l The monitor alarm setpoints above background are determined 6s follows:
- a. The calculated monitor HIGH-HIGH Alarm Setpoint above background-(ncom) attributed to the noble gas radionuclides is determined by:
fLC Eg g [2.1(1)-19] HHSP = , F where: f = The maximum acceptable gaseous discharge flow rate (cfm) determined in Section 2.1.1.2.1. F = The maximum actual or design effluent flow rate (cfm) at the point of release.
= 92,000 cfm (BV-1 Ventilation Vent -- design)
- 49,300 cfm (BV-1 Containment Vent -- design)
Cf = The undiluted radioactivity concentration of noble gas radionuclide "i" in the gaseous source (uci/ce) as determined by analysis of the gas to be released. 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 thi::
section, the monitor HIGH Alarm Setpoint above background.(nepm) is determined as follows: HSP = HHSP x 0.33 [2.1(1)-20) i l 2-12 ISSUE 3 .l l
BV-1 and 2 ODCM 2.1.2 BV-2 Monitor Alarm Setpoint Determination of Monitor Alarm Setpoint See Section 2.1.1 De t er:aina t i ons . for a description ( 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 V er. t Releases The table below gives the calculated monitor count rate abo a background (C.R.) in nepm, and provides the equivalent monitar 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 uC1/cc ABOVE BACKGROUhD 30%
- SITE SITE C.R. D.V. LIMIT LIMIT MONITOR ncpm uCi/cc HSP ASP
' Continuous 2HVS-R0101B 8.26E3 3.01E-4 9.04E-5 3.01E-5 Release (
Via The BV-2 Ventilation Vent Batch Release Of 2HVS-R0101B 1.13E3 4.13E-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 Toe 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 2RMO-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 The setpoints were determined using the following conditions: } ' Source terms given in Table 2.1-lb. These gaseous source terms vere derived from Stone 6 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 l Decontamination Building and Condensate Polishing Building ventilation exhaust are not expected to be radioactive. However, for purposes of determining an alarm setpoint, it is conservatively assumed that Xe-133 is in the ventilation exhaust at concentrations that would result in the appropriate dose rate limits. The Vaste Gas Storage Vault ventilation exhaust is also not normally radioactive. However, che monitor alarm sutpoint is based on the assumption that the ventilation exhaust radionuclide spectrum is similar to the gaseous inventory in the system housed by the vaste gas storage vault. This spectrum is listed in Table 2.1-1b under Gaseous Waste System.
- Onsite meteorological data for the period January 1, 1976 through December 31, 1980.
- Discharge flow rate of 23,700 cfm for the BV-2 Ventilation Vent (Continuous).
I
- Discharge flow rate of 53,700 cfm for the BV-2 Ventilation Vent (Batch release of containment purge).
t
- Discharge flow rate of 59,000 cfm for the BV-2 Containment Vent (Both continuous and batch release of containment purge).
- Discharge flow rate of 30,556 cfm for the BV-2 Condensate Polishing Building Vent.
- Discharge flow rate of 12,400 cfm for the BV-2 Decontamination Building Vent.
- Discharge 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 ; vas used to derive the alarm setpoints for the Ventilation Vent Gas Monitor (2HVS-R0101B), Containment Vent Gas Monitor (2HYS*R0109B), Condensate Polishing Building Vent Gas Monitor (2HVL-R0112B), j Decontamination Building Vet Gas Monitor (2RM0-Rb301P), and Waste Gas ' Storage Vault Vent Gas Monitor (2RM0-R0303B) during the following , operational conditions: )
- Continuous release via the BV-2 Ventilation Vent.
l
- Continuous release via the BV-2 Containment Vent.
2-14 ISSUE 3 i l l
BV-1 and 2 ODCM
- Batch release of BV-2 Containment Purge via the BV-2 Ventilation Vent. l
- 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.
I
- Continuous release via the BV-2 Vaste Gas Storage Vault Vent.
2.1.2.1.1 BV-2 Mix Radionuclides The " mix" (noble gas radionuclides and composition) of the gaseous effluent was determined as follows:
- a. The gaseous source terms that are representative of the " mix" of the gaseous effluent were selected based on the relative stream composition and volumetric flowrate. Gaseous source terms are the radioactivity of the noble gas radionuclides in the effluent.
Gaseous source terms can be obtained from. Table 2.1-lb.
- b. The fraction of the total radioactivity in the gaseous effluent comprised of noble gas radionuclide "i" (S,) for each individual noble gas radionuclide in the gaseous effloent was determined by:
A S. i [2.l(2)-1] fA i i 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 ) based upon the whole body t exposure limit was calculated by: 0 t= 500 [2.l(2)-2] (X/Q) EKg S g i where: 1 (X/0)" = The highest calculated annual average relative i concentration of effluents released via the Ventilation Vent for any area at or beyond 3 the unrestricted area 1 boundary for all sectors (sec/m ) from Table 2.2-5.
= 1.03E-4 sec/m for continuous releases.
2-15 ISSUE 3 i i
I l BV-1 and 2 ODCM (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/m for batch release of containment purge.
(X/0) " = The highest calculated annual average relative concentration of effluents released via the Containment Vent for any arez. at or beyond3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-4. 3
= 9.24E-5 sec/m for continuous releases.
(X/q)cv = The short term relative concentration of effluents released via the containment vent for any area at or beyond,the unrestricted area boundary for all sectors (sec/m') from Table 2.3-35.
= 3.08E-4 sec/m for batch release of containment purge.
(X/0)'E = The highest calculated annual average relative concentration of effluents released via the Condensate Polishing Building Vent for any area at or beyond3the unrestricted area boundary for all sectors (secim ) from Table 2.2-10.
= 7.35E-3 sec/m for continuous releases.
(X/0)dv = The highest calculated annual average relative concentration of effluents released via the Decontamination Building Vent for any area at or beyond 3 the unrestricted area boundary for all sectors (sec/m ) from Table 2.2-8.
= 9.24E-5 sec/m3 for co- - releases.
(X/0)yy - The highest calculated onva' sverage relative concentration of effluents _ eased via the Vaste Gas Storage Vault Vent for any ac i at or beyono the 3 unrestricted area boundary fo all sectors (sec/m ) from Table 2.2-9.
= 9.24E-5 sec/m for continuous releases.
K g
= The total whole body dose factor due to gamma 3 emissions f rom noble gas radient.clide "i" (mrem / year /uci/m )
from Table 2.2-11. S g
= From equation [2.1(2)-1].
2-16 ISSUE 3 I
BV-1 and 2 ODCM 2.1.2.1.3 BV-2 Maximum Acceptable Release Rate (Skin Exposure)
- 1 O was also determined based upon the skin exposure limit by:
t 0 3000 [2.1(2)-3]
" (X/0) E (Lg + 1.1Mg ) S g 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. 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.
'l 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. i radionuclide in the gaseous effluent was determined by: Og-53 O t [2.1(2)-4 (NOTE: Use the lower of the 0 tvalues obtained in l 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/ce) of noble (C for each individual gar radionuclide "i" in the gaseous effluentnoblegasradionuclideinthegase C g, 2.12E-3 0 1 12.1(2)-5) j F vhere: F = The maximum acceptable effluent flow rate at the point of release (cfm) as listed in Section 2.1.2.1. 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-5 ft3 fcc), G 2-17 ISSUE 3
BV-1 and 2 ODCM 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.) was determined by: C.R. = I C E g 3 [2.1(2)-6)] i where: 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 vere determined as follows: -
- a. The. monitor HIGH Alarm Setpoint above background (uci/cc) vas determined by:
HSP 0.30 C.R. .[2.1(2)-7] E g: ave
- b. The monitor ALERT Alarm Setpoint above background (uCi/cc) was determined by:
i ggp , FR x C.R. [2.1(2)-8] 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. D.s . 2-18 ISSUE 3
BV-1 and 2 ODCM 2.1.2.2 BV-2 Setpoint Determination Based On Analysis Prior To Release (Ground Releases) Vhen the setpoints established using "the calculated mix" do not provide adequate flexibility for operational needs, the method described below 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 {2.1(2)-17] f " (X/q) IK Cg 1 i vhere: i 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 4
= (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 necessary margin below the site dose rate limit. T = Maximum value for T is 16 based on the limiting restriction in ODCM Appendix C CONTROL 3.ll.2.1.a where the dose rate for a containment purge may be averaged 3 over a time period not to exceed 960 minutes. (As 1 containment air volume change time period is 60 minutes; T = 960/60 = 16). See Reference 2.2.4. , l l 2-19 ISSUE 3
BV-1 and 2 ODCM (X/q)" = The highest calculated short term relative concentration of effluents released via the Ventilation l Vent for any area at or beyond the unrestricted area boundary for all sectors (set /m3) from Table 2.3-36.
= 3.32E-4 sec/m (X/q)cv = The highest calculated short term relative concentration of effluents released via the Containment 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. C = The undiluted radioactivity concentration of noble gas 1 radionuclide "i" in the gaseous source (uC1/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.l(2)-18] f " (X/q) I (L1 + 1.lM ) C1 g vhere: 6.36 = 3000 mrem /yr x 2.12E-3 3000 mrem /yr = dose rate limit, skin exposure 2.12E-3 = unit conversion factor
= (60 sec/ min x 3.53E-5 ft /cc)
L I
= The skin dose factor due to beta emissions from noble gas radionuclide "i" (mrem / year /uCi/m ) from Table 2.2-11.
M = The air dose factor due to gamma emissions 3 from 1 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 (Section 2.1.2.2.1.a) and based on the skin exposure limit (Section 2.1.2.2.1.b). The actual purge flow rate (cfm) must be maintained at or belov this calculated (f) value or the discharge cannot be made from the vent.
k 2-20 ISSUE 3
BV-1 and 2 ODCM 2.1.2.2.2 BV-2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows: ,
- a. The calculated monitor HIGH Alarm Setpoint above background (net uCi/cc) attributed to the noble gas radionuclides is determined by:
fIC E 1 3 [2.l(2)-19] HSP = ,g F i ave where: f = The maximum acceptable containment purge flov rate (cfm) determined in Section 2.1.2.2.1. F = The maximum actual or design effluent flow rate (cfm) at the point of release.
- 53,700 cfm (BV-2 Ventilation Vent -- design)
= 59,000 cfm (BV-2 Containment Vent -- design)
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.
-l E
g
= The detection efficiency of the monitor for noble gas radionuclide "i" (cpm /uci/cc) from Table-2.1-2b.
Ei ave = The C.R. of equation [2.l(2)-6] divided by the sum of the Cy for the respective mix. NOTE: To enable maintaining a constant conversion factor from epm to uCi/cc in the Digital Radiation Monitoring System software, the " calculated mix" is used rather than the analysis mix to calculate E above. This does not cause any change'in the I **the monitor setpoint to properly control dose - function of rate. However, the monitor indicated uCi/cc value may differ from the actual value.
- b. When a HIGH Alarm Setpoint has been calculated according to this section, the monitor ALERT Alarm Setpoint above background (net uCi/cc) is determined as follows:
ASP = HSP x 0.33 [2.l(2)-20] I 2-21 ISSUE 3
BV-1 and 2 ODCM 2.1.3 BV-1/2 Monitor Alarm Setpoint Determination l See Section 2.1.1 for a description of Monitor Alarm Setpoint Determination. 2.1.3.1 BV-1/2 Setpoint Determination Based On A Calculated Mix For Process Vent Releases (Elevated Releases) The calculated monitor count rate above background (C.R.), in nepm, the monitor HIGH-HIGH alarm setpoint above background (HHSP), and the ' monitor HIGH alarm setpoint above background (HSP) for each operational condition are as follows: BV-2 AND ALARM SETP01NTS FOR ELEVATED RELEASES cpm AB0VE BACKGROUND (P) PRIMARY
- 30% 10%
MONITOR SITE SITE (A) ALTERNATE LIMIT LIMIT MONITOR C.R. HHSP HSP
' Continuous Release (P)RM-GV-108B 3.83E7 1.15E7 3.83E6 (A)RM-GV-109(5) 2.20E7 6.61E6 2.20E6
- Batch Release Of BV-1 Decay (P)RM-GV-108B 3.93E5 1.18E5 3.93E4 Tanks (A)RM-GV-109(5) 7.87E6 2.36E6 7.87E5
- Batch Release of BV-2 Decay (P)RM-GV-108B 2.11E5 6.33E4 2.11E4 Tanks (A)RM-GV-109(3) 7.75E6 2.32E6 7.75E5
- Batch Release Of BV-1 (P)RM-GV-108B 5.55E6 1.67E6 5.55E5 Containment Purge (A)RM-GV-109(5) 7.37E6 2.21E6 7.37ES
- 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: r
- 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 l Process Vent.
2-22 ISSUE 3
BV-1 and 2 ODCM 2.1.3.1.1 BV-1/2 Mix Radionuclides The " mix" (noble gas radionuclides and composition) of zaseous { effluent was determined as follows:
- a. The gaseous source terms that are representative of ne ' nix" of the gaseous effluent were evaluated. Gaseous sourca '.erms are the radioactivity of the noble gas radionuclides in the effluent.
The gaseous source terms can be obtained from Tables 2.1-la. and' 2.1-lb.
- b. The fraction of the total radioactivity in the gaseous effluent comprised by noble gas radionuclide "i" (S ) for each individual noble gas radionuclide in the gaseous effluent was calculated by:
A S i [2.1-9] I*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.lb. 2.1.3.1.2 BV-1/2 Maximum Acceptable Release Rate (Vhole Body Exposure) The maximum acceptable total release rate (uCi/sec) of all noble gas radionuclides in the gaseous effluent (Ot ) based upon the whole body exposure limit was determined by: 0 " 500 [2.1.10] IV 3 S g i vhere: V1 - The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated finite plume (mrem / year /uci/sec) from Table 2.2-12. 2.1.3.1.3 BV-1/2 Maximum Acceptable Release Rate (Skin Exposure) O was also determined based upon the skin exposure limit as follows: t I 3000 12.1-11} 0* " I [L i(x/0)py + 1.1Bi ls i G 2-23 ISSUE 3
BV-1 and 2 ODCM vhere:
- The skin dose factor due to beta emissions 3 f'
- D Lg noble gas radionuclide "i"(mrem / year /uCi/m ) from 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 3 the unrestricted area boundary for all seetors (sec/m-) from Table 2.2-6.
- 2.31E-6 sec/m (X/q)pV = released The short term relative concentration of effluents 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.
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 gas.
)
radionuclide "i" in the caseous effluent (0,) for each individual noble gas radionuclide in the gaseous effluent Oas determined by: O [2.1-121 01=s1 t (NOTE: Use the lover of the 0 values obtained in Section2.1.3.1.2and2!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 noble gas radionuclide in the gaseous effluent Oas determined by: C g, 2.12E-3 0 1 [2.1-13] F where: 2.12E-3 = Unit conversion factor (60 sec/ min x 3.53E-5 ft 3fcc), F = The maximum acceptable effluent flow rate at the point of release (cfm).
= 1450 cfm (BV-1/2 Process Vent)
I' 1 2-24 ISSUE 3 I l
BV-1 and 2 ODCM 2.1.3.1.6 BV-1/2 Monitor Count Rate The calculated monitor count rate (nepm) above background attributed to the noble gas radionuclide (C.R.) was determined by: C.R. - E Cy E g [2.1-14] i where: E g = 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] e G 2-25 ISSUE 3
BV-1 and 2 ODCM 2.1.3.2 BV-1/2 Setpoint Determination Based On Analysis Prior To Release For Process Vent Releases (Elevated Releases)_ I
'The following calculation method applies to.-gaseous releases via the BV-1/2 Process Vent when the " calculated mix" does not provide adequate operational flexibility. This method is used to determine the setpoint for the maximum acceptable discharge flow rate and the associated HIGH-HIGH Alarm Setpoint based on this flow rate for the BV-1/2 Gaseous Vaste Gas Monitor (RM-GV-108B) or alternate (RM-GV-109 CH #5) during the following operational conditions:
- Continuous release via the BV-1/2 Process Vent, ,
- Batch release of BV-1 or BV-2 Vaste Gas Decay Tank via the BV-1/2 Process Vent.
- Batch release of BV-1 or BV-2 Containment- Purge via the BV-1/2 Process Vent.
2.1.3.2.1 BV-1/2 Maximum Acceptable Release Rate Determine the maximum acceptable discharge flow rate for the' release from the Process Vent for the analyzed mix.
- a. The maximum acceptable gaseous discharge flow rate (f) f rom .the :
Process Vent (cfm) based upon the whole body expo,sure limit is determined by: f , 1.06 S [2.1-21] IV C 3 1 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 belov
.the site dose rate limit.
V g
- The constant for noble gas radionuclide "i" accounting for the gamma radiation from the elevated plume (mrem / year /uC1/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 S [2.1-22] f , I [L3 (X/0)py + 1.18 JC 3 3 where: 6.36 = 3000 mrem /yr x 2.12E-3 3000 mrem /yr = dose rate limit, skin exposure 2.12E-3 = unit conversion factor
=
(60 sec/ min x 3.53E-5 ft /cc) Lg - The skin dose factor due to beta emissions f " noble gas radionuclide "i" (mrem / year /uC1/m3)'from Table 2.2-11. (X/0)py = 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)P" = The short term relative concentration of effluents released via the Process Vent for any area at or beyond the unrestricted area boundary for all sectors 3
(sec/m ) from Table 2.3-38.
= 1.07E-5 sec/m B
1
= 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/sec) from Table 2.2-12.
- c. Select the smaller of the calculated f values based on the whole body exposure limit (Section 2.1.3.2.1.a) and based on the skin exposure limit (Section 2.1.3.2.1.b). The actual discharge flow rate (cfm) must be maintained at or below this f value.
2.1.3.2.2 BV-1/2 Monitor Setpoints The monitor alarm setpoints above background are determined as follows:
- a. The calculated monitor HIGH-HIGH Alarm Setpoint above background (nepm) attributed to the noble gas radionuclides is determined by:
f I C; Ej [2.1-23] I HHSP = F 2-27 ISSUE 3
BV-1 and 2 ODCM where:
- The maximum acceptable gaseous discharge flow rate (cfm) 9 f determined in Section 2.1.3.2.1.
F = The maximum actual or design effluent flow rate (cfm) at the point of release.
= 1450 cfm (BV-1/2 Process Vent -- design)
C g = The undiluted radioactivity of noble gas radionuclide "i" in the gaseous source (uci/ce) as determined by analysis of the gas to be released. E g = The detection efficiency of the respective monitor (RM-GV-108B) or (RM-GV-109 CH 5) for noble gas radionuclide "1" (cpm /uci/cc) from Table 2.1-2a and 2.1-2b.
- b. Vhen 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] ,m. 2-28 ISSUE 3
BV-1 and 2 ODCM TABLE 2.1-la BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)** TURBINE CONTAIUMENT 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 B.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
- Containment can be purged via Ventilation Vent, Containment Vent, or Process Vent
** Reference (2.1.2) *** Reference (2.1.E1 2-29 ISSUE 3
BV-1 and 2 ODCM-TABLE 2.1-lb BV-2 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS (Ci/yr)** TURBIT 1E VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS VENT ____, Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS BUILDING CONDENSER / VACUUM VASTE CONTAINMENT BUILDING PUMPS SYSTEM NUCLIDE BUILDING VENTILATION VENTILATION AIR EJECTOR Short Term Long Term Long Term Long Term Long Term Short Term 4.0E-05 4.2E-01 3.9E-05 2.7E-01 3.7E-04 0.0 Kr-83m 1.2E-02 Kr-85m 1.4E-02 1.9E+00 1.7E-04 1.2E+00 3.9E-03 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-85 6.1E+01 5.3E-06 1.3E+00 1.1E-04 8.2E-01 7.8E-04 0.0 Kr-87 0.0 Kr-88 4.1E-03 3.8E+00 3.5E-04 2.4E+00 5.0E-03 Kr-89 0.0 1.2E-01 1.1E-05 7.7E-02 3.1E-06 0.0 7.2E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 8.3E-01 Xe-131m 7.6E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133m 8.4E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-133 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 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0 Xe-137 0.0 Xe-138 0.0 1.1E+00 9.7E-05 6.6E-01 1.2E-04 0.0 1 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)
O *** Reference (2.2.5) 2-30 ISSUE 3
BV-1 and 2 ODCM TABLE 2.1-2a BV-1 MONITOR DETECTOR EFFICIENCIES (cpm /uci/cc, CORRECTED)* O VENTILATION PROCESS CONTAINMENT 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 E5 2.47 E7 3.56 E5 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 2.28 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 O
- The listed detector efficiencies for the respective primary monitors (Victoreen) are corrected for the reduced pressures observed 'and documented during operation. Also listed are the alternate monitors (Eberline SPING Channel 5) efficiencies corrected for detector unique installation factors. (Pressure corrections are not required for the SPING Monitors.) See Reference (2.1.4) for additional information.
2-31 ISSUE 3
BV-1 and 2 ODCM TABLE 2.1-2b BV-2 MONITOR DETECTOR EFFICIENCIES (cpm /uCi/cc)* j VASTE GAS CONDENSATE STORAGE DECON POLISHING VENTILATION CONTAINMENT VAULT BUILDING BUILDING VENT VENT VENT VENT VENT NUCLIDE 211VS-RQ101B 2HVS-RQ109B 2RMO-R0303B 2RMQ-R0301B 2HVL-RQ112B Kr-83m -- -- -- -- Kr-85m 3.20E7 5.83E7 3.20E7 3.20E7 3.20E7 Kr-85 3.60E7 7.19E7 3.60E7 3.60E7 3.60E7 Kr-87 3.73E7 8.85E7 3.73E7 3.73E7 3.73E7 Kr-88 3.05E7 6.80E7 3.05E7 3.05E7 3.05E7 Kr-89 3.72E7 8.73E7 3.72E7 3.72E7 3.72E7 Kr-90 3.86E7 8.80E7 3.86E7 3.86E7 3.86E7-Xe-131m 2.44E7 4.61E4 2.44E7 2.44E7 2.44E7 Xe-133m 2.86E7 6.06E4 2.86E7 2.86E7 2.86E7 Xe-133 1.80E7 2.94E7 1.80E7 1.80E7 1.80E7 Xe-135m 7.22E6 1.55E4 7.22E6 7.22E6 7.22E6 Xe-135 3.86E7 7.48E7 3.86E7 3.86E7 3.86E7 Xe-137 3.78E7 9.07E7 3.78E7 3.78E7 3.78E7 Xe-138 3.52E7 7.74E7 3.52E7 3.52E7 3.52E7 Ar-41 3.79E7 7.90E7 3.79E7 3.79E7 3.79E7 J jlll
- Reference (2.2.1) 2-32 ISSUE 3
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 2.1.5 Unit 1/ Unit 2 ODCM Gaseous Alarm Setpoint Determinations; DLCo Calculation Package No. ERS-HHM-87-014 2.1.6 BVPS-1 and BVPS-2 ODCM T Factor Justification; DLCo Calculation Package No. ERS-ATL-87-026 2.1.7 Let ter ND1SHP:776, c'ated 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 O REFERENCES BV-2 GASEOUS 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 Fover 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 2.2.5 Gaseous Releases From Containment Vacuum Pumps; Stone and Vebster Calculation No. UR(B)-262-t 2-33 ISSUE 3
1 BV-1 and 2 ODCM 2.2 Compliance Vith 10 CFR 20 Dose Rate Limits (ODCM Appendix C CONTROL 3.11.2.1) 2.2.1 Dose Rate Due To Noble Gases 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 ODCM Appendix C CONTROL 3.ll.2.1.a. I [V 01 1s + Ki (X7 )y 01y] < %0 mtem/yr [2.2-1) i I [L (X/0)s + 1.1Bi} Oh
- Ibi 3
+
1.1M;J(X/Q)y O gy $ 3000 mrem /yr i [2.2-2] where: K = The total body dose factor due to gamma emissions for each 3 identified noble gas radionuclide "i", mrem / year /uC1/m3 . L 3
= The skin dose factor due to beta emissions for each identified noble gas radionuclide "i", mrem / year /uCi/m3 .
k Mg = The air dose factor due to gamma emissions for each identifled noble gas radionuclide "i", mrad / year /uci/m 3. V. = The constant for each identified noble gas radionuclide 1
"i" accounting for the gamma radiation from the elevated finite plume, mrem / year /uci/sec.
B 3
= 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 /nrad. O is
= 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. (XTO)s = The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for elevated releases (sec/m3). 2-34 ISSUE 3
BV-1 and 2 ODCM (X/U)" - The highest calculated annual average relative concentration for any area at or beyond the unrestricted area boundary for ground level releases (sec/m3). At the Beaver Valley site gaseous releases may occur from:
- 1. The Containment Vents atop the Containment Domes
- 2. The Ventilation Vents atop the Auxiliary Buildings
- 3. The Process Vent atop the BV-1 Cooling Tover
- 4. The Turbine Building Vents
- 5. The BV-2 Condensate Polishing Building Vent
- 6. The BV-7 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 above are not normally radioactive release points. The Process Vent releases are elevated and the sources of these releases are the Main Condenser Air Ejectors and the Vaste Gas Decay Tanks and Containment Vacuum Pumps !Joble gas releases may normally occur Irom release points 1 through 3 above. To show compliance with the site limits of ODCM Appendix C C0f1 TROL 3.11.2.1.a. Expressions [2.2-1J and [2.2-2l are nov expressed in terms of the actual release points for the site. flo t e 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: IV0ii + I.K. [(X/0)cv 0 g + (X/0)vv 9. yg 4 (X/0)tv 0. g g py 1 1 i l i + (X/0)cv 0 I
+
(X/0)"" 0, + (X/0)tv O. 0 +
+ (X/0)CP g2 + (X/0)dv O. dv2 I I I cv2 vv2 t'd i
(XTO). , 0; ] < 500 mrem /yr [2.2-3] vv2 l 2-35 ISSUE 3
BV-1 and 2 ODCM For The Skin Dose Rate: l I [L (XTd)py g
+ 1.lB ] 0 1 g +Eg (Lg + 1.1M g l [(X/0)cy 0 3 + (X/0)yy i pv cv1 (X/0)tv O g tvl + (X/0)cy O g cv2 + (X/0)yy o g vv2 + (X/0)ty O g Og + +
vvl tv2 (X/0)dv 0 i dv2 + (X/0)" 9. uv2 ] < 3000 arem/yr
+
(X/0)CP 0 I cp2 [2.2-4] where: Og = Release rate of radionuclide "1" from the BV-1/2 Process pv Vent, uCi/sec. Og = Release rate of radionuclide "i" from the BV-1 Containment cvl Vent, uCi/sec. Og = Release rate of radionuclide "i" from the BV-2 Containment ev2 Vent, uCi/sec. Og = Release rate of radionuclide "i" from the BV-1 Ventilation vv1 Vent, uCi/sec. Og = Release rate of radionuclide "i" from the BV-2 Ventilation vv2 Vent, uCi/sec. D 0 1 tvl
= Release rate of radionuclide "i" from the BV-1 Turbine 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. O *. = Release rate of radionuclide "i" from the BV-2 dv2 Decontamination Building Vent, uCi/sec. O *, = Release rate of radionuclide "i" from the BV-2 Vaste Gas vv2 Storage Vault Vent, uCi/sec. (X/0)PV = Highest calculated annual average relative3 c ncentration
- g. hm h & Pen Vm , m/m (576)cv = Highest calculated annual average relative3 concentration for releases from the Containment Vent, sec/m (576)yy = Highest calculated annual average relative3 c ncentration for releases from the Ventilation Vent, sec/m (X/0)tv = Highest calculated annual average relative3c ncentration for releases for the Turbine Building Vent, sec/m 2-36 ISSUE 3
BV-1 and 2 ODCM (X/0)cp = Highest calculated annual average relative concentration for releases 3for the BV-2 Condensate Folishing Building Vent, sec/m l (X/0)dv = Highest calculated annual average relative concentration3 for releases for the BV-2 Decontamination Building Vent, sec/m . (XTO)yy = Highest calculated annual average relative concentration 3 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/see 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 ODCM 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: EVo gg +EKg [9.24E-5 Og + 1.03E-4 O g + 7.35E-5 O g + 9.24E-i i pv i cv1 vv1 tv1 ! Og + 1.03E-4 O g + 7.35E-5 O g + -5 Q i ' tv2 dv2 v2 7.35E-5 0 ] 3 500 mrem /yr [2.2-5] For The Skin Dose Rate: E [ 7.0E-10 L1 + 1.1Bg ] 0; + I [L; + 1.1M gj [9.24E-5 O g + 1.03E 4 i pv i cv1 0 i vv1 + 7.35E-5 0 I + 9.24E-5 0*. cv2 + 1.03E-4 0*, + 7.35E-5 0 I + tv1 vv2 tv2 9.24E-5 O g + 9.24E-5 O g + 7.35E-5 O g j f 3000 mrem /yr dv2 vv2 cp2 [2.2-6] For the release Mode 4, the controlling location is 0.75 miles-N. Inserting the appropriate X/O's from Tables 2.2-4 through 2.2-10 for this location, Expressions [2.2-3 and 2.2-4] become: l 2-37 ISSUE 3
BV-1 and 2 ODCM For The Total Body Dose Rate: [ EV0 1g +EKg [3.95E-6 Oy + 4.99E-6 O g + 4.26E-6 o g + 3.95E-6 i pv i cvl vv1 tvl 0 i
+ 4.99E-6 0 I + 4.26E-6 0*. + 3.95E-6 0 i + 3.95E-6 0 I +
cv2 vv2 tv2 dv2 vv2 4.26E-6 O g ] $ 500 mrem /yr [2.2-7] For The Skin Dose Rate: E [2.31E-6 L1 + 1.lB g] Og + E [L 3 + 1.lMg ] [3.95E-6 Og vl + 4.99El6-i pv i c Og + 3.95E-6 0 + 4.99E-6 O g + 4.26E-6 0 + 4.26E-6.0 g + 3.95E-6 O g + 3.95E-6 O g + 4.26E-6 O g ] f 3000 mrem /yr dv vv cp [2.2-8J The determination of controlling location for implementation of ODCM Appendix C CONTROL 3.ll.2.1.a for noble gases is a function of the following parameters:
- 1. Radionuclide mix and their isotopic release rate
- 2. Release mode l 3. Meteorology The incorporation of these 3 parameters into Expressions [2.2-3] and
[2.2 4) resulted in the expressions for the controlling locations as presented in Expressions [2.2-5 through 2.2-8). The radionuclide mix used to determine controlling locations was based on - source terms calculated with the Stone and -Vebster Engineering Corporation computer code CASIBB which is similar to,the NRCLGALE code. Inputs vere 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.ll-.2.1.a are based upon the maximum long-term annual-average X/0 in the unrestricted area. Table 2.2-3 presents the distances from the release points to the nearest unrestricted area for each of the 16 sectors as well as to the nearest vegetable-garden, cow, goat, and beef animal. Tables 2.2-4 through 2.2-10 present the long-term annual average (X/0) values for the Process Vent, Containment Vent, Ventilation Vent, Turbine Building Vent, and if applicable for BV-2, Decontamination Building Vent, Vaste Gas Storage Vault Vent, and the Condensate Polishing Building Vent release points to the special locations presented in Table 2.2-3. A description of their derivation is provided in ) Appendix A. 2-38 ISSUE 3
[ ) l BV-1 and 2 ODCM l I For release modes 1, 2, and 3, dose calculations vere performed using the highest calculated site boundary X/0 values applicable to the release points involved and the p r oj ec t ed radionuclide mix applicable to the release source. In that a simultaneous, continuous elevated release l could contribute to the dose at a given location, the selection of the tvo 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 vere selected as the l controlling location. 1 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 j Ventilation Vent and BV-2 Containment Vent). In Modes 2 and 3, the } dominant release is a Containment Purge from the respective Ventilation l Vent or Containment Vent. ! l For release Mode 4, a similar evaluation was performed. Long-term annual j 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, I 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 dir tance was selected at 0.75 miles. From the calculated dose results, the controlling sector vas shown to 'oe North. In this mode, the dominant release is a Containment Purge via the Process Vent. Neither of the controlling receptor locations are presently inhabited. M., Values for K , L; tor location which controllinghecep,and and whichvere are used to in Iethe useddetermination in of the Expressions [2.2-5) through [2.2-8) to show compliance with ODCM Appendix C CONTROL 3.11.2.1.2, are presented in Table 2.2-11. Values taken from Table B-1 of NRC Regulatory Guide 1 l I were multiplied by 1E6 to convert picocuries -7 109, Revisionto microcuries-y ,for use l in Table 2.2-11. Values for Vg and B. for the finite plume model can be expressed as sbovn in Equation [2!2-9] and [2.2-10]. Values were calculated using the NRC code R/,BFIN at the site boundary location which would receive the highest total dose from combined Process -Vent, Ventilation Vent, and Turbine Building Vent, and Containment Vent releases. These values are presented in Table 2.2-12 and calculated from the following relation: A B=K- III jk li "a 1 [2.2-9) i r djk1 u. 3 where: I = The results of numerical integration over the plume spatial distribution of the airborne activity as defined by the meteorological condition of vind speed (u.) and atmospheric stability class "k" for a particular vind 3 direction. G 2-39 ISSUE 3
BV-1 and 2 ODCM K = A numerical constant representing unit conversions.
=
(260 mrad)(radians) (m ) (transformation) 16 sectors (sec)(Mev)(Ci) 2n radians 1E-6 Ci 3.15E7 sec uCi yr
- 2.1E4 mrad (m ) (transformation)/yr(Mev)(uCi).
r d
- The distance from the release point to the receptor location, meters.
u 3
= The mean vind speed assigned to the "j" th vind speed class, meters /sec.
fjk - The joint frequency of occurrence of the "j" th wind speed class and kth stability class (dimensionless). Ayg = The number of photons of energy corresponding to the "1" th energy group emitted per transformation of the "i" th radionuclide, number / transformation. Ey - The energy assigned to the "1" th energy group, Mev. u, = The energy _7 absorption coefficient in air for photon energy H', meters D The V factor is computed with conversion from air dose to tissue depth dose,3 thus: A u K EIE jk 13 a 1 e ~"T d [2.2-10) Vi = 1.1 r djk1 u. 3 where: u T = The tissue energy 9 absorption coefficient for photons of energy E y, em"/gm. T d
= The tissue density thickness taken to rerresent the total body dose (5gm/cm2 ).
1.1 - The ratio of the tissue to air absorption coefficients over the energy range of photons of interest, mrem / mrad. 2-40 ISSUE 3
BV-1 and 2 ODCM 2.2.2 Dose Rate Due To Radioiodines And Particulates 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 up)n NUREG-0133, the following basic expression is used to show compliance with ODCM Appendix C CONTROL 3.11.2.1.b: IPh [(X/0)s Ois + X/0)y O gy j f 1,500 mrem /yr [2.2-11) { i i vhere: P h = Dose parameter for any organ T for each identified radionuclide "i", mrem /yr per uCi/m 3 0 is = The release rate of radionuclide "i", in gaseous effluents from elevated releases, uCi/sec. O gy = The release rate of radionuclide "i", in gaseous effluents from Fround level releases, uC1/sec. (X76)s = The highest calculated annual average relative concentration at3the unrestricted area boundary for elevated releases, sec/m . 1 (RTd)y = The highest calculated annual average relative concentration at the unrestricted 3 area boundary for ground level releases, sec/m j NOTE: The dispersion parameters specified in Section 2.2.2 are l limited to the site boundary as defined above.
)
Releases may occur from any of the site vents in the release modes listed in Table 2.2-1. To show compliance with ODCM Appendix C CONTROL ' 3.ll.2.1.b, Expression [2.2-11] is now 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 0 1 + i pv cv1 vv1 + (X/0)tv O g tv1 (X/0)cy O g "" tv S tv2 cp Oi dv ev2 vv2 cp2 Og + (X/0)yy O g ~ vv2 vhere: (iTd)Py = Highest calculated annual average relative3con untration for releases from the Process Vent, sec/m (XTO)cy = Highest calculated annual average relative c neentration fcr releases from the containment Vents, sec/m3 , i l 2-41 ISSUE 3
l BV-I and 2 ODCM ( FO)yy = Highest calculated annual average relative3 concentration for releases from the Ventilation Vents, sec/m (X/0)tv = Highest calculated annual average relative concentration for releases for the Turbine Building Vents, sec/m 3 (X/0) E = Highest calculated annual average relative concentration for releases 3f r the BV-2 Condencate Polishing Building Vent, sec/m (X/0)dv = Highest calculated annual average relative concentration for releases 3f r the BV-2 Decontamination Building Vent, sec/m ( FO)" = Highest calculated annual average relative concentration for release fr m the BV-2 Vaste Gas Storage Vault Vent, sec/m 3 Og = Long-term release rate of radionuclide "i" from the BV-1/2 pv Process Vent, uCi/sec. Og = Long-term releaae rate of radionuclide "i" from the BV-1 cvl Containment Vent, uCi/sec. O. = Long-term release rate of radionuclide "i" from the BV-2 I cv2 Containment Vent, uCi/sec. h F Og vvl
= Long-term release rate of radionuclide "i" from the BV-1 Ventilation Vent, uCi/sec.
Og = Long-term release rate of radionuclide "i" from the BV-2 vv2 Ventilation Vent, uCi/sec. 0 = Long-term release rate of radionuclide "i" from the BV-1 3 tvl Turbine Building Vent, uCi/sec. Og = Long-term release rate of radionuclide "i" from the BV-2 tv2 Turbine Building Ve,t, uCi/sec. 0 = Long-term release rate of radionuclide "i" from the BV-2 1 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. 0 - Long-term release rate of radionuclide "i" from the BV-2 1 vv2 Waste Gas Storage Vault Vent, uCi/sec. All other terms are the same as those defined previously. h 2-42 ISSUE 3
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 pathvay is considered. Values of the organ dose parameters, P g , were calculated using niethodology given in NUREG-0133. For the child age group, the following. equation was used for all nuclides. The Ph, values are presented in Table 2.2-13. Ph = 3.7E9 DFAh [2.2-13] vhere: 3 3.7E9 = Breathing rate of child (3,700 m /yr) x unit conversion factor (1E6 pCi/uCi). DFA. = The organ inhalation dose factor for a child from Table 6 of 1T 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 tL boundary, 0.35 miles NV. Expression [2.2-12] becomes: IPh [7.00E-10 Og + 9.24E-5 O g + 1.03E-4 O g + 7.35E-5 O g + i pv cv1 vv1 tv1 j 9.24E-5 0*. + 1.03E-4 0 I + 7.35E-5 0 + 7.35E-5 0 I + 9.24E-5 cv2 vv2 tv2 cp2 Og + 9.24E-5 O g $ 1500 mrem /yr [2.2-14] The determination of the controlling location for irplementation of ODCM Appendix C CONTROL 3.11.2.1.b for radiciodines and particulates is a function of the same 3 parameters as for noble gases plus a fourth, the actual receptor pathways. The incorporation of these parameters into Expression [2.2-12] results in the respective equations for each release mode at the site- boundary controlling locations. The radionuclide mix was again based upon the source terms presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point. In the determination of the controlling site boundary for each release mode, the highest 2 site boundary X/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. 1 e 2-43 -ISSUE ~3
BV-1 and-2 ODCM l-2 The X/0 values in Expression [2.2-14] vere obtained from Tables 2.2-4 through 2.2-10. A description of the derivation of the X/0 values is provided in Appendix A. 1 i P b h 2-44 ISSUE 3
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 HODE 1 MODE 2 MODE 3 MODE 4 2 BVPS BVPS-2 !!ain 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 1 BVPS-1 Containment Leakage Same As Same As Same As + Vent (cvi) 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 Contiguous Contagnment Same As Same As Vent (vv2) Areas Purge Mode 1 Mode 1 BVPS-2 Containment Aux. Bldg. Same As Same As Same As Vent (cv2) Ventilation Mode 1 Mode.1 And Mode 1 Contajnment Purge BVPS-2 Turbine Bldg. Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust
- Mode 1* Mode 1* Mode 1*
l BVPS-2 Condensate * * *
- Polishing Bldg. Vent (cp2)
I *
- BVPS-2 Decontamination *
- Bldg. Vent (dv2) i BVPS-2 Vaste Gas , , , ,
Storage Vault Vent (vv2)
- Not normally a radioactive release point NOTE: For the purpose of implementing 10 CFR 50, batch discharges may use continuous meteorology since short term meteorology is used at the time of the annual report.
fContinuousgroundlevelmeteorologyisapplicable 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
BV-1 and 2 ODCM TABLE 2.2-2a BV-1 RADIONUCLIDE MIX FOR GASEOUS EFFLUENTS l (Ci/yr)**- 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 1.2E-02 Kr-85 6.1E+01 2.5E+00 2.3E-04 1.6E+00 7.2E-01 2.3E+02 Kr-87 5.4E-02 1.3E+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 8.3E-01 Xe-133m 8.9E-01 8.9E-01 8.1E-05 5.6E-01 2.2E-02 0.0 Xe-133 8.9E+01 3.6E+01 3.4E-03 2.3E+01 1.9E-00 8.2E+00 Xe-135m 4.5E-03 3.2E-01 2.9E-05 2.0E-01 4.4E-05 0.0 Xe-135 7.0E-01 4.5E+00 4.2E-04 2.8E+00 1.9E-02 0.0 Xe-137 1.0E-03 2.1E-01 2.1E-05 1.3E-01 6.3E-06 0.0 I Xe-138 1.5E-02 1.1E+00 9.7E-05 6.6E-01 1.2E-04 0.0 I-131 1.2E-03 4.6E-02 6.5E-04 2.1E-02 4.7E-04 0.0 I-132 0.0 0.0 0.0 0.0 2.5E-06 0.0 I-133 2.0E-04 6.7E-02 8.7E-04 3.0E-02 8.4E-05 0.0 I-134 0.0 0.0 0.0 0.0 4.7E-07 0.0 I-135 0.0 0.0 0.0 0.0 1.4E-05 0.0 Co-58 7.5E-04 6.0E-02 0.0 0.0 1.6E-05 0.0 Co-60 3.4E-04 2.7E-02 0.0 0.0 7.4E-06 0.0 Hn-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-05 1.3E-03 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-06 2.0E-04 0.0 0.0 6.6E-08 0.0 Cs-134 2.2E-04 1.8E-02 0.0 0.0 4.9E-06 0.0 Cs-137 3.8E-04 3.0E-02 0.0 0.0 8.4E-06 0.0 C-14 1.0E+00 0.0 0.0 0.0 0.0 7.0E+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
BV-1 and 2 ODCM TABLE 2.2-2b BV-2 RADIONUCLIDE MIX FOR GASEnUS EFFLUENTS (Ci/yr)** j TURBINE VENTILATION CONTAINMENT BUILDING VENT VENT VENT PROCESS VENT Long Term And AUXILIARY TURBINE MAIN CONTAINMENT GASEOUS CONTAINMENT BUILDING BUILDING CONDENSER / VACUUM VASTE NUCLIDE PUILDING VENTILATION VENTILATION AIR EJECTOR PUMPS SYSTEM Short Term Long Term Long Tetm 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 Kr-85 3.9E-03 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 Kr-89 5.0E-03 0.0 0.0 1.2E-01 1.1E-05 7.7E-02 Xe-131m 3.1E-06 0.0 7.2E-01 1.3E-01 1.2E-05 8.0E-02 1.3E-02 Xe-133m 7.6E-01 8.3E-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 Xe-135 0.0 2.4E-01 4.5E400 4.2E-04 2.8E+00 1.9E-02 Xe-137 0.0 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 { I-131 0.0 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 I-133 0.0 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 1-135 0.0 0.0 0.0 Co-58 0.0 1.4E-05 0.0 7.5E-02 6.0E-04 0.0 0.0 1.6E-05 Co-60 0.0 3.4E-02 2.7E-04 0.0 0.0 7. 4 E-06 Mn-54 0.0 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 Fe-59 0.0 7.5E-03 6.0E-05 0.0 0.0 1.6E-06 Sr-89 1.7E-03 0.0 1.3E-05 0.0 0.0 3.7E-07 0.0 Sr-90 3.0E-04 2.0E-06 0.0 Cs-134 0.0 6.6E-08 0.0 2.2E-02 1.8E-04 0.0 0.0 4.9E-06 Cs-137 0.0 3.8E-02 3.0E-04 0.0 0.0 8.4E-06 C-14 0.0 1.0E+00 0.0 0.0 0.0 0.0 Ar-41 7.0E400 2.5E+01 0.0 0.0 0.0 0.0 0.0
*** Reference Containment 2.2.3can be purged via Ventilation Vent. Containment Vent, or Process V
- See Section 2.1.2.1 2-47 ISSUE 3
BV-1 and 2 ODCM TABLE 2.2-3 DISTANCES OF LIMITING MAXIMUM INDIVIDUAL RECEPIDIG 'IO RELEASE POINTS FOR AfUUAL X/Q VALUES * (meters) VEGETABLE MEAT DOWN- SITE BOUNIERY GARDEN MILK COW MILK GOAT ANIMAI. RESIDE 24T WIto SECIOR GROUND ELEV. GROUND ELEV. GROUtC ELEV. GROUND ELEV. GROUND ELEV. GROUIO ELEV. (1) (2) N 670 579 413 2,623 2,423 - - 4,651 4,418 4,152 3,919 2,527 2,295 NNE 535 792 632 2,704 2,461 - - 6,276 6,033 2,848 2,605 2,639 2,461 NE 490 442 327 724 901 7,741 7,526 20,760 20,545 7,741 7,526 708 790 ENE 490 448 394 1,674 1,658 - - 6,824 6,671 - - 708 1,562 E 545 546 551 1,979 1,922 7,065 6,998 4,265 4,200 4,265 4,200 756 1,922 ESE 575 607 672 1,577 1,619 - - 2,865 2,899 1,577 1,619 1,577 1,650 SE 575 701 815 1,835 1,961 5,729 5,848 5,729 5,848 3,299 3,420 1,835 1,961 SSE 655 762 912 1,738 1,933 5,053 5,244 9,977 10,166 1,770 1,964 1,432 1,628 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 3,590 538 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 NNW 645 558 420 1,464 1,285 - - 15,450 15,262 3,959 3,774 1,143 1,253 NOTE:
- Distances for ground releases are measured from the centerpoint between the BV-1 and BV-2 Containment Buildings. Distances for elevated release are measured from the BV-1 Cooling Tower. Elevated release is applicable to the Process vent. Ground release is applicable to all other release points. Site boundary ground releases: (1) BV-2 Turbine Building and Condensate Polishing Building.
(2) All other ground release points. 2-48 ISSUE 3
BV-1 and 2 CDCM TABLE 2.2-4 BV-1 AND 2 CONTAINMENT VENTS ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES EUR CWTINUOUS GRWND LEVEL RELEASES, EUR SPECIAL DISTANCES (IDENIIFIED IN TABLE 2.2-3), AND SELECTED CONTROL LOCATIONS (IE-7 sec/m ) INDIVIDUAL RECEPIDRS DISTANCES 'IO 'IIIE CONTROL IOCATIN, IN MILES DOWN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-TOR DARY GARDEN CCW GOAT MAL DE2K'E 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.P N 125.0 12.80 -- 5.360 6.27 13.50 233.0 39.5 18.70 11.80 7.68 5.82 4.240 3.480 -2.660 2.280 NNE 50.2 6.92 - 2.040 6.42 7.16 148.0 26.8 10.80 6.62 4.60 3.44 2.690 2.190 1.830 1.560 NE 102.0 47.40 1.200 0.265 1.20 49.10 120.0 21.6 11.60 6.99 4.81 3.55 2.370 1.910 1.450 1.230 ENE 85.8 12.50 - 0.124 - 42.20 103.0 18.4 9.55 5.70 4.14 3.04 2.340 1.880 1.260 1.060 E 54.5 6.16 0.807 1.910 1.91 32.60 89.5 15.7 6.08 3.65 2.49 1.83 1.300 1.040 0.859 0.726 ESE 31.1 6.92 - 3.010 6.92 6.92 59.1 10.5 5.16 3.10 1.95 1.43 1.020 0.815 0.612 0.517 SE 27.8 6.70 0.994 0.994 2.74 6.70 65.9 12.0 5.89 3.54 2.41 1.77 1.160 0.931 0.768 0.649 SSE 24.1 6.68 1.030 0.372 6.50 9.01 67.2 12.0 5.46 3.30 1.91 1.41 0.997 0.803 0.665 0.563 S 27.5 3.40 3.090 - 5.57 5.81 99.9 17.5 6.77 4.11 2.84 2.10 1.490 -1.200 0.999 0.848 SSN 23.8 6.31 3.700 1.740 6.31 19.30 110.0 19.9 7.83 4.80 3.33 2.48 .1.940 1.580 1.190 1.020-SW 22.3 13.90- - 9.050 12.30 13.90 160.0 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 487.0 40.70 30.100 1.810 40.70 40.70 1290.0 203.0 92.10 59.20 40.60 31.20 25.000 20.700 14.200 12.200 NW 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 NNW 302.0 63.00 - 1.720 15.40 92.30 547.0 86.4 40.80 26.20 17.60 13.50 10.100 8.350 6.560 5.660 2-49 ISSUE 3
BV-1 and 2 ODCM TABLE 2.2-5 BV-1 AND 2 VENTILATION VENTS ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR C04TINUOUS GROUND LEVEL RELEASES, FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CONTROL LOCATIQ4S (1E-7 sec/m ) INDIVIDUAL RECEPTORS DISTANCES 'IO 'IEE CONIROL LOCATICN, IN MILES DOWN-WIND SITE VEGE- PIAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-
'IOR DARY GARDEN 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 152.0 15.00 --
5.980 7.06 15.90 276.0 49.9 22.70 13.70 8.75 6.52 4.69 3.810 2.900 2.470 NNE 62.3 7.66 - 2.150 7.08 7.95 189.0 32.0 12.20 7.31 4.99 3.69 2.87 2.320 1.920 1.630 NE 132.0 57.90 1.240 0.269 1.24 60.20 156.0 24.8 12.70 7.51 5.09 3.73 2.47 1.980 1.500 1.270 ENE 110.0 13.60 - 1.270 - 50.40 135 0 20.6 10.20 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. 38.80 116.0 17.7 6.57 3.86 2.61 1.90 1.34 1.070 0.883 0.774 ESE 38.0 7.64 -- 3.200 7.64, 7.64 76.7 11.9 5.59 3.29 2.05 1.49 1.05 0.842 0.630 0.531 SE 33.3 7.27 1.030 1.030 2.88 7.27 86.2 13.5 6.37 3.75 2.53 1.84 1.20 0.960 0.790 0.666 SSE 29.1 7.41 1.080 0.382 7.19 10.10 ~87.0 13.7 5.98 3.53 2.02 1.48 1.04 0.833 0.688 0.531 S 32.8 3.65 3.300 -- 6.10 6.38 127.0 20.3 7.56 4.48 3.04 2.23 1.57 1.260 1.050 0.885 SSN- 28.7 7.08 4.040 1.850 7.08 22.90 140.0 23.6 8.87 5.28 3.60 2.66 2.07 1.670 1.260 1.070 SW 26.2 15.70 - 9.980 13.80 15.70 204.0 34.P 18.40 11.40 6.38 4.71 3.66 2.960 2.230 1.900 WSW 201.0 22.40 6.230 - 20.40 22.40 347.0 61.3 27.70 16.60 11.40 8.49 6.19 5.020 3.880 3.300 N 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 hTM 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 23.100 15.900 13.600 tM 1030.0 262.00 - 9.520 47.80 271.00 1820.0 350.0 164.00 100.00 66.60 50.10 39.50 32.300 21.900 18.800 NNW 345.0 83.40 - 1.840 18.10 121.00 601.0 114.0 52.80 32.20 21.00 15.80 11.60 9.450 7.360 6.310 2-50 ISSUE 3'
BV-1 and 2 ODCM TABLE 2.2-6 BV-1 AND 2 PROCESS VEtn ANNUAL AVERAGE, EIIVATED RELEASE, X/Q VALUES FOR CONTINUOUS GROUND LEVEL RELEASES, EDR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CONTROL II) CATIONS (IE-7 sec/m ) INDIVIDUAL RECEP'IURS DISTANCES TO THE CONTROL II) CATION, IN MILES DOWN-WIND SITE
- VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-
'IOR DARY- GARDEN CGi GOAT MAL 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 -- 1.910 2.27 6.790 0.0289 23.1000 8.2700 5.32 2.56 1.91 1.480 1.200 0.996 0.846 NNE 0.0280 6.690 - 1.430 6.14 6.890 0.0175 14.5000 6.9800 5.47 3.27 2.69 1.770 1.430 1.290 1.100 NE 0.0110- .074 1.610 0.350 1.61 0.055 0.0069 0.1160 .2300 7.10 5.38 3.68 2.880 2.090 1.880 1.570 ENE 0.0110 9.090 - 1.770 - 0.525 0.0135 0.3310 7.2800 6.02 4.75 3.22 2.620 2.030 1.710 1.100. E 0.0360 8.300 1.240 2.870 2.87 8.300 0.0124 17.1000 7.8600 6.20 3.67 2.83 2.190 1.730 1.280 1.200 ESE 0.0426 11.600 - 4.570 11.60 11.200 0.0208 12.7000 8.1400 4.78 3.00 2.20 1.'360 1.160 0.830 0.737 SE 0.0750 7.890 1.230 1.233 3.G5 7.890 0.4770 7.4000 7.5700 4.45 2.79 2.05 1.460 1.180 0.811 0.686 SSE 0.2060 7.390 1.160 0.357 7.20 9.770 0.3030 9.4400 6.9300 4.06 2.58 1 89 1.170 0.937 0.646 0.546 5 5.740 3.760 3.490 -- 6.06 6.310 0.7960 8.5100 8.4900 4.98 3.37 2.47 1.380 1.110 0.774 0.655 SSW 7.640 3.610 2.140 0.872 3.61 5.820 26.1000 9.1000 4.0300 3.11 2.11 1.56 1.030 0.834 0.807.0.684 SW 6.500 3.900 - 2.560 3.47 3.900 36.1000 15.9000 4.9300 3.12 1.77 1.57 1.201 1.060 1.150 0.977 WSW 0.126 4.350 1.420 - 3.98 4.350 0.3870 17.8000 4.9000 3.53 2.36 1.64 1.460 1.210 0.920 0.781 W 0.029 2.490 0.764 -- 2.02 2.490 0.0147 .8.7200 6.2300 3.68 2.50 1.84 0.741 1.120 0.851 0.795 WNW 0.033 2.530 1.780 0.163 2.53 2.530 0.0202 0.0549 0.0809 3.07 2.50 1.84 1.110 0.686 0.791 0.731 tM 0.007 0.074 - 0.305 1.67 0.073 0.0084 0.0650 0.1170 3.66 2.30 1.69 1.210 0.903 0.804 0.683 NNW 0.008 6.460 - 0.224 1.81 6.590 0.0135 6.7800 5.0200 2.96 1.93 1.49 1.050 0.849 0.705 0.599
- Elevated release K/Q value at site boundary location where ground level release X/Qs maximize.
-51 ISSUE 3 a i- a
BV-1 and 2 ODCM TABLE 2.2-7 BV-1 NJD 2 'IURBINE BUILDItG VENTS NeiUAL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CONTINUOUS GROUND LEVEL RELEASES, FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CORROL IDCATIO4S (IE-7 sec/m ) INDIVIDUAL RECEPIORS DISTNiCES TO THE COTITOL LOCATIOi, IN MILES DOWN-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK R4I- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-ER_ DARY GARDEN COW GOAT MAL DDiCE 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 -- tc4E 102.0 7 . 3~. 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 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 51.9( ENE 84.1 13.20 1.2301.2800.268 -1.23 53.80 132.0 23.0 12.10 7.24 4.95 3.64 2.42 1.950 1.480 1.250 46.30 115.0 19.4 9.89 5.85 4.23 3.09 2.38 1.900 1.270 1.070 E 60.7 6.49 .829 1.980 1.98 35.70 99.2 16.6 6.32 3.75 2.55 1.87 1.32 1.060 0.871 0.735 ESE 37.1 7.25 -- 3.100 7.25 7.25 65.8 11.1 5.36 3.19 2.00 1.46 1.03 0.829 0.621 0.524 SE 41.8 7.06 1.020 1.020 2.85 7.06 73.5 12.6 6.12 3.64 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 1.806 o.73 20 00 120.0 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 a.iu 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 tM 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 tcM 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 S.980 2-52 ISSUE 3
BV-1 and 2 ODCM TABLE 2.2-8 FOR INERMATION ONLY - USED IN CALCULATICN OF BV-2 CORRIBUTION 'IU SITE DOSE RATE LIMITS BV-2 DECORAMINATION BUILDING VDE ANNUAL AVERAGE, GROUND LEVEL, X/ 01 VALUES EUR CORINUOUS GROUND LEVEL RELEASES, EDR SPECIAL DISTANCES (IDDRIFIED IN TABLE 2.2-3), AND SELECIED CONTROL LOCATIONS (lE-7 sec/m ) INDIVIDUAL RECEPTORS DISTANCES 'ID THE CONTROL LOCATION, IN MILES DOWri-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0- 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-
'IOR DARY GARDEN COW GOAT MAL DDK'E 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' O.665 0.563 S 27.50 3.40 3.090 -- 5.57. 5.81 99.9 17.50 6.77 4.11 2.84 2.10. 1.490 1.200 0.999 0.848 SSW 23.80 6.31 3.700 1.740 6.31 19.30 110.0 19.90 7.83 4.80 3.33 2.48 1.940 1.580 1.190 1.020 SN 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 WtM 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 NtM 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 ISSUE 3 -- - e - - 2-e -53 _a
BV-1 and 2 ODCM TABLE 2.2-9 mR INFORMATION ONLY - USED IN CALCUIATIW OF BV-2 CONTRIBUTION TO SITE DOSE RATE LIMITS BV-2 NASTE GAS STORAGE VNJLT VENT ANNUAL AVERAGE, GROUND LEVEL, X/Q VALUES ECR CCNTINUQUS GROUND LEVEL RELEASES, EUR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3), AND SELECTED CCNTROL IOCATIONS (lE-7 sec/m ) INDIVIDUAL RECEPTORS DISTANCES TO THE 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~ 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 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 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 SW 22.30 13.90 - 9.050 12.30 13.90 160.0 29.20 16.10 9.94 5.85 4.37 3.430 2.790 2.110 1.800 WSW 163.00 19.30 5.720 - 17.70 19.30 283.0 49.80 23.50 14.60 10.30 7.72 5.690 4.650 '3.620 3.090 W 278.00 15.70 9.540 - 13.00 15.70 615.00 103.00 49.00 31.00 15.40 11.70 9.320 7.660 6.460 5.550 WNW 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 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 2-54 ISSUE 3
d BV-1 and 2 ODCM TABLE 2.2-10 FOR INFORMATION WLY - USED IN CALCULATIm OF BV-2 CORRIBITTIm 'IO SITE DOSE RATE LIMITS BV-2 CONDENSATE POLISHING BUILDING VENT ANtGL AVERAGE, GROUND LEVEL, X/Q VALUES FOR CGTTINUOUS GROUND LEVEL RELEASES, EUR SPECIAL DISTANCES (IDDEIFIED IN TABLE 2.2-3), AND SELECTED CONTROL IOCATINS (IE-7 sec/m ) INDIVIDUAL REurwxS DISTANCES 'IO 'IIIE COtEROL I4 CATION, IN MILES DOhW-WIND SITE VEGE- MEAT SEC- BOUN- TABLE MILK MILK ANI- RESI- 0. 0.5- 1.0- 1.5- 2.0- 2.5- 3.0- 3.5- 4.0- 4.5-
"IOR DARY GARDEN COW GOAT MAL DEtK'E 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 l'.46 1.03 d.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 SSN 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' 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 22.000 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 t
BV-1 and'2 ODCM TABLE 2.2-11 I l DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
- Kg Lg Mg Ng TOTAL BODY GAMMA AIR BETA AIR NUCLIDE DOSE FACTOR SKIN DOSE FACTOR DOSE FACTOR DOSE FACTOR mrem /yr mrem /yr mrad /yr mrad /yr Per Per uCi/m 3 I*'3 uCi/m I*'3 uCi/m 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 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 , Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-ia3 2.94E+02 3.06E+02 3.53C+02 1.05E+03 Xe-135m 3.12E+03 '7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 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
) *The listed dose factors are for radionuclides that may be detected in gaseous effluents.
2-56 ISSUE 3
BV-1 and 2 ODCM TABLE 2.2-12. 1 DOSE PARAMETERS FOR FINITE ELEVATED PLUMES - BEAVER VALLEY SITE
- l l,2 y 3 3 Vg Bg Bg 3
NOBLE GAS TOTAL 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 i
**The listed dose parameters are for radionuclides that may be detected in gaseous effluents.
I V1 and B; values used to implement Modes 1, 2, and 3 of Section 2.2.1 (10CFR20) 2 Bg 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 imhlement*monitorsetpointdeterminationsofSection2.1.2and2.1.4 2-57 ISSUE'3
1 Eb 1 and 2 ODCM Table 2.2-13 P VALUIS FOR A CHILD FOR THE EEAVER VALLEY SITE if (stes/yrperuCi/cuseter) Nuclide Bor,e Liver T. Body Thyroid lidney Lung Ol-Lll 1 H-3 0.00b00 1.12bO3 1.12003 1.12bO3 1.12bO3 1.12bO3 1.12bO3 2 P-32 2.60b06 1.14b05 9.88b04 0.00b00 0.00D00 0.00b00 4.22b04 3Cr-51 0.00b00 0.00b00 1.54bO2 8.55b01 2.43b01 1.70D04 1.08bO3 4Mn-54 0.00E+00 4.29b04 9.51003 0.00b00 1.00b04 1.5Bb06 2.29b04 5 Fe-59 2.07b04 3.34b04 1.67b04 0.00!+00 0.00D00 1.27b06 7.07b04 6Cc-57 0.00 BOO 9.03bO2 1.07bO3 0.00b00 0.00b00 5.07b05 1.32b04 7 Co-58 0.00b00 1.77bO3 3.16bO3 0.00D00 0.00b00 1.11b06 3.44b04 8 00-60 0.00b00 1.31b04 2.26b04 0.00b00 0.00b00 7.07b06 9.62b04 9 In-65 4.25b04 1.13b05 7.03b04 0.00D00 7.14b04 9.95b05 1.63b04 10 Hb-86 0.00b00 1.9Bb05 1.14b05 0.00b00 0.00b00 0.00b00 7.99bO3 11 St-89 5.99b05 0.00 BOO 1.72b04 0.00D00 0.00b00 2.16b06 1.67b05 12Sr-90 1.01bO8 0.00b00 6.4(b06 0.00D00 0.00D00 1.48bO7 3.43b05 13 Y-91 9.14b05 0.00b00 2.44b04 0.00b00 0.00b00 2.63b06 1.84b05 D 14 Zr4 5 15 Nb-95 1.90b05 4.1Bb04 3.70b04 0.00D00 5.96b04 2.23b06 6J1b04 2.35b04 9.18bO3 6.55bO3 0.00b00 8.62bO3 6.14b05 3.70904 16Nb-97 4.291-01 7.70bO2 3.601-02 0.00b00 8.55b02 3.42bO3 2.7Bb04 17 Mo-99 0.00b00 1.72bO2 4.26b01 0.00b00 3.92bO2 1.35b05 1.27b05 18 fc-99: 1.78003 3.48bO3 5.77E-02 0.00b00 5.07bO2 9.51bO2 4.81bO3 19Ru-103 2.79bO3 0.00D00 1.07bO3 0.00D00 7.03bO3 6.62b05 4.4Bb04 20 Ru-106 1.36b05 0.00b00 1.69b04 0.00b00 1.84b05 1.43bO7 4.29b05 21ag-110s 1.69b04 1.14b04 9.14bO3 0.00b00 2.12b04 5.48b06 1.00b05 22Sb-124 5.74b04 7.40bO2 2.00b04 1.261+02 0.00b00 3.24b06 1.64bOS 23Sb-125 9.h'b04 7.59b02 2.07b04 9.10b01 0.00b00 2.32b06 4.03b04 24Te-127s 4.49b04 8.55bO3 3.02bO3 6.07bO3 6.36b04 1.48b06 7.14b04 25fe-129s 1.92b04 6.65bO3 3.04bO3 6.33bO3 5.03b04 1.76b06 1.82b05 26I-131 4.81b04 4.81b04 2.73b04 1.62bO7 7.88b04 0.00b00 2.84bO3 27l-133 1.66b04 2.03b04 7.70bO3 3.85b06 3.36b04 0.00b00 5.48bO3 28Cs-134 6.51b05 1.0lb06 2.25b05 0.00b00 3.30b05 1.21b05 3.65bO3 29Cs-136 6.51b04 1.71b05 1.16b05 0.00b00 9.55b04 1.45b04 4.18bO3 30 Cs-137 9.07b05 8.25b05 1.28b05 0.00b00 2.82b05 1.04b05 3.62bO3 31 Ba-140 7.40b04 6.4Bb01 4.33bO3 0.00b00 2.11b01 1.74D06 1.02b05 32 La-140 6.44bO2 2.25bO2 7.55b01 0.00b00 0.00b00 1.83h05 2.26b05 33 Ce-141 3.92b04 1.95b04 2.90bO3 0.00b00 8.55D03 5.44b05 5.66b04 34 Ce-144 6.77b06 2.12b06 3.61b05 0.00b00 1.17b06 1.20bO7 3.89b05 Calculated per ODCH equation 2.2-13 ISSUE 3 2-58
BV-1 and 2 ODCM 2.3 Compliance Vith 10 CFR 50 Dose Limits (ODCM Appendix C CONTROLS 3.11.2.2 And 3.11.2.3) (Gaseous) At the Beaver Valley site all elevated gaseous releases are considered to originate from a shared radvaste system. The effluent from both units are mixed and discharged from a common release point, the Process Vent, at the top of the Unit 1 Cooling Tower. The resulting dose for the purpose of implementing 10 CFR 50 is normally apportioned equally to each unit. The only exception vould be a Containment Purge via the Process Vent. The resulting dose shall be attributed to the contributing reactor unit. Since this operation is expected to be rare, equations are sheen throughout this section with the apportionment set at 0.5. 2.3.1 Dose Due To Noble Gases 2.3.1.1 Cumulation Of Duses Section II.B.1 of Appendix I of 10 CFR 50 (ODCM Appendix C CONTROL 3.11.2.2) limits the releases of gaseous effluents from each reactor such that the estimated annual gamma air dose is limited to 10 millirad and the beta air dose is limited to 20 millirad. In addition, ODCM Appendix C CONTROL 3.11.2.4 requires use of radvaste system if air doses when averaged over 31 days exceed 0.2 mrad for gamma and 0.4 mrad for beta. Based upon NUREG-0133, the air dose limits in the unrestricted area due to noble gases released in gaseous effluents are defined by the following expressions: During Any Calendar Quarter, For Gamma Radiation: h . . 3.17E-8 I My [(X/0)y0;y + (X/q)yq;y] + [B;0gg + b;qis]- f 5 mrad 1 [2.3-1] During Any Calendar Quarter, For Beta Radiation: 3.17E-8 I N g (X/0)y0 gy + (X/q)yggy + (X/0)s0is + (X/q)s 19s < 10 mrad 1 - [7. 3-2 ) During Any Calendar Year, For Gamma Radiation: 3.17E-8 I My [(X/0)y0 gy +
%)yq;y] + [B 0g is + bg qis] $ 10 mrad 1 -
[2.3-3] During Any Calendar Year, For Beta Radiation: e - 3.17E-8 E N g (X/0)y 09 , + (X/q)yq;y + (X/0)g0is
- I '4)s i9s < 20 mrad 1
[ 2. 3-41 I 2-59 ISSUE 3
BV-1 and 2 ODCM Averaged over 31 Days, For The Gamma Radiation Projection: 3.17E-8 I M1 [(X/0)y0 gy + 1 - (X/q)yggy] + [B 0g is + b gq13]- 3 0.2 mrad 12.3-5) Averaged Over 31 Days, For The Beta Radiation Projection: 3.17E-8 I N g (X/0)y0 iy + (X/q)yggy + (X/0)s01s + (X/q)s 91s < 0.4' mrad 1 - [7.3-6) where: Mg = The air dose factor due to gamma emissions for each identified n ble gas radionuclide "1" (mrad /yr
- 3 per uCi/m ).
Ng = The air dose factor due to beta emissions for each identified n ble gas radionuclide "1" (mrad /yr 3 per uCi/m ). (X/0)" - 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 ). ' (X/q)y = The relative concentration for areas at or beyond the unrestricted area boundary for short-term vent releases equal to or less than 500 hrs / year (sec/m3 ). { (X/0)s = The annual average relative concentration for areas at or beyond the unrestricted area boundary for 1-ong-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 ). qis = 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 is = 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). 2-60 ISSUE 3
BV-1 and 2 ODCM By = The constant for long-term releases (greater than ! 500 hrs / year) for each_ identified noble gas radionuclide l "i" accounting for the gamma radiation from the elevated i I finite plume (mrad /yr per uCi/sec). by = The constant for short-term releases (equal to or less than 500 hrs / year) 'for each identified noble gas radionuclide "i" accounting for- the gamma radiation from the elevated finite plume (mrad /yr per uCi/sec). 3.17E The inverse of the number of seconds in a year. NUREG 0133 permits eliminati.j the short-term release term and short-term meteorological terms in the determination of doses when short-term releases are sufficiently random in both time of day and duration to be represented by annual average dispersion conditions. This special consideration is applied in Expressions [2.3-1] through [2.3-6], however, a summary of the "real . time" meteorological data coupled with the corresponding releases shall be-included in the Semi-Annual Radioactive Effluent Release Report. Short-term releases are also evaluated annually in computer codes technically consistent with X00D00 and GASPAR for inclusion in the Annual Radiological Environmental Report. The incorporation of this option and the release modes of Table 2.3-1 results in the following expressions to show compliance with 10 CFR 50 I for the calendar quarter or year. For Release Modes 1 2, 3, And 4 During Any Month, Calender Quarter, Or Year: Gamma Radiation: 3.17E-8 I Mg [(X/0)cv0 1 + (X/0)yy0 1 + (X/0)cpU i (X/0)dv 0g + i cv vv cp dv (X70),y0 g ] + 0.5 B 33 0 vv v 0.2 mrad (per 31 days) [2.3-7]
< 5.0 mrad (per quarter) 10.0 mrad (per year)
I 2-61 ISSUE 3
BV-1 and 2 ODCM Beta Radiation: i 3.17E-8 I N g (X/0)cy0 g + (X/0)yy 03 + (X/0)cp0 g + O/O 0
+
i cv vv cp dv 1 dv (X/0)yy0 g + 0.5 (X/0)py 0 g vv 0.4 mrad (per 31 days) [2.3-8] $ 10.0 mrad (per quarter) 20.0 mrad (per year) where: (276)cy = Annual average relative concentration f r releases from 3 the Containment Building Vent (sec/m ). (276)"" = Annual average relative concentration for 3 releases from the Ventilation Vent (sec/m ), (276)PV = Annual average relative3 concentration for releases from the Process Vent (sec/m ). (576)tv = Annu 1 average relative concentration 3 fI **1*"S*8 from the Turbine Building Vent (sec/m ). 04 = Release of radionuclide "i" from the Containment Building
'ev Vent 'uCi). I Og - Release or radionuclide "i" from the Ventilation Vent vv (uCl).
Og = Release of radionuclide "i" from the Process Vent pv (uCi). Og = Release of radionuclide "1" from the Turbine Building tv Vent (uci). Og = Release of radionuclide "i" from the Condensate Polishing cp Building Vent (uCi). Og = Release of radionuclide "i" from the Decontamination dv Building Vent (uci). Og = Release of radionuclide "i" from the Vaste Gas Storage vv Vault Vent (uCi). For Modes 1, 2, 3, and 4 the controlling location is 0.35 miles NV. Substitution of the appropriate X/0 values into Expressions [2.3-7J and 12.3-8] results in the following: i G 2-62 ISSUE 3
BV-1 and 2 ODCM Release' Modes 1, 2, 3. And 4' [ During Any' Month, Calendar Quarter, Or Year: - Gamma Radiation: 3.17E-8 I Mg [9.24E-5 O f + 1.03E-4 O g + 7.35E-5 O .g +:7.35E-5 O .g + i cv vv tv ep 9.24E-5 O g + 9.24E-5 O g J + 0.5 B g10 0.2 mrad (per 31 days) [2.3-9]
$ 5.0 mrad (per quarter) 10.0 mrad (per year)
Beta Radiation: 3.17E-8 I N g 9.24E-5 O g + 1.03E-4 0 + 7.35E-5 o g + 7.35E-5 0 3 + i cv vv tv cp 9.24E-5 O g + 9.24E-5 O g 4 (0.5) 7.0E-10 O g ; dv vv pv 0.4 mrad (per 31 days) .[2.3-10] f 10.0 mrad (per quarter) I 20.0 mrad (per year) The determination of the controlling locations for implementation of 10 CFR 50 is a function of the following parameters: (1) Radionuclide mix and their isotopic release (2) Release mode (3) Meteorology The incorporation of these . parameters into Expressionn [2.3-7] and [2.3-8] resulted in the expressions for the controlling locations as . presented in Expressions [2.3-9] and [2.3-10]. The radionuclide mix , was based upon source terms calculated using the NRC GALE Code (inputs presented in Appendix B) and is presented in Tables 2.2-2a and 2.2-2b as a function of release type and release point. As in Section 2.2.1, for each release mode, the two highest boundary X/0 values for each release point and release duration vere 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 vere obtained for the midpoint of the 10 standard distance intervals previously presented in Tables 2.2-4 through 2.2-10. 2-63 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 I the Ventilation Vent. For Release Mode 3, the controlling release is the Containment Building Vent. Values for M g and N controlling locati$n,whichwereusedinthedeterminationofthe 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, yRevision 1 vere multiplied by 1E6 to convert from picocuries- to microcuries'y 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 y values to be utilized are the same values which vere presented in Table 2.2-12. A description of the derivation of the various X/0 values is presented in Appendix A. The following relationship should hold for BV-1 or BV-2 to show compliance with ODCM Appendix C CONTROL 3.11.2.2: For The Calendar Quarter: D 3 5 mrad [2.3-11] Dg 3 10 mrad [2.3-12] l For The Calendar Year: D $ 10 mrad [2.3-13] Dg 3 20 mrad [2.3-14] vhere: D = The air dose from gamma radiation (mrad). DS = The air dose from beta radiation (mrad). The quarterly limits given above represent one-half the annual design objective of Section II.B.1 of Appendix I of 10 CFR 50. If any of the limits of Expressions [2.3-11] 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. In addition, ODCM Appendix C CONTROL 3.1.2.4 requires that the gaseous radvaste system must be used to reduce radioactive materials in that vaste when projected doses from each reactor unit when averaged over 31 days exceed any of the following: D 3 0.2 mrad [2.3-15] . Dg j 0.4 mrad [2.3-16] 2-64 ISSUE 3
BV-1 and 2 ODCM 2.3.1.2 Projection Of Doses (Noble Gas) l 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 Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge in accordance with ODCM Appendix C CONTROL 3.11.2.4 when the projected gaseous effluent air dose due to gaseous effluent releases from each reactor unit, when averaged over 31 days, vould 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: When Including Pre-Release Data, D ( 1) + C [2.3-17] 31
- T When Not Including Pre-Release Data, D (31) +C [2.3-18]
31 = vhere: ' D31 = Projected 31 day dose (mrad). A = Cumulative dose for quarter (mrad). B = Projected dose from this release (mrad). T = Current days into quarter. C = Value which may be used to anticipate plant trends (mrad). l h 2-65 ISSUE 3
BV-1 and 2 ODCM l l 2.3.2 Dose Due To Radioiodines And Particulates l 2.3.2.1 Cumulation of Doses l Section IIC of Appendix I of 10 CFR 50 (ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4) limits the release of 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 l 15 mrem to any organ. In addition, ODCM Appendix C CONTROL 3.11.2.4 l 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 j unrestricted areas, can be determined by the following expression: During Any Month, Calendar Quarter, Or Year: 3.17E-8 I R g [V Q is 1
* "s9 h ^ v v0h * "v9h I l 0.3 mrem (per 31 days) [2.3-19] ;
$ 7.5 mrem (per quarter) l 15.0 mrem (per calendar year) 1 l l where:
O is
= Release of radionuclide "i" for long-term free standing stack releases greater than 500 hrs /yr (uci).
O gy = Release of radionuclide "i" for long-term vent releases ! greater than 500 hrs /yr (uCi). qis = Release of radionuclide "i" for short-term free standing stack releases equal to or less than 500 hrs /yr (uCi). qgy = 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 8 at the controlling location for long-term free standing stack releases greater than 500 hrs /yr. 3
= sec/m for the inhalation pathway, (UTU)s '
= meters
-2 for the food and ground plane pathway, (liTU)s '
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.
= sec/m for the inha]ation pathway, (57U) .
= meters ~ for the food and ground plane p thway, (DTU)y.
b 2-66 ISSUE 3 l l
BV-1 and 2 ODCM v = Dispersion parameter for estimating the dose to an 8 individual at the controlling location for short-term stack releases equal to or less than 500 hrs /yr.
= see/m for the inhalation pathway, (RM),.
-2
= meters for the food and ground plane pathway, (D/q)s' v = 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.
= sec/m for the inhalation pathway, (25)y.
= meters- for the food and ground plane pathway, (if7q)y.
3.17E-8 = The inverse of the number of seconds in a year. R
= the Theorgan dose" T" factor for each identified radionuclide "i" 2for of interest (mren/yr per uCi/sec per m- or mrem /yr per uCi/m3).
Radionuclides and particulates may be teleased from any of ths BV-1 and BV-2 vents in the release modes identified in Table 2.3-1. As described previously in Section 2.3.1.1, NUREG 0133 permits use of long-term annual average dispersion calculations which with the release modes of Table 2.3-1 results in the following expressions to show compliance with ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4. For a particular organ, Expression [2.3-19] becomes: 3.17E-8 I R h 0.5 Vpy01 +V cy 03
+V yy 0;
+V 0
- 0 +
i pv cv vv tv 1 tv cp 1 cp dv 0g
"" I dv vv 0.3 mrem (per 31 days) [2.3-20] $ 7.5 mrem (per quarter) 15.0 mrem (per calendar year) vhere:
V py
= Dispersion parameter for releases from the Process Vent.
V cv
= Dispersion parameter for releases from the Containment Building Vent.
V = Dispersion parameter for releases from the Ventilation Vent. yy V tv
= Dispersion parameter for releases from the Turbine Building Vent.
k 2-67 ISSUE 3
BV-1 and 2 ODCM V CP
= Dispersion parameter for releases from the_ Condensate Polishing Building Vent.
,I 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 p = Release of radionuclide "i" from the Process Vent (uci). 0 1
"" - Release of radionuclide "i" from the Containment Building Vent (uCi).
O l yy - Release of radionuclide "i" from the Ventilation Vent (uci). O i ty = Release of radionuclide "i" from the Turbine Building Vent (uCi). O i,P = Release
- of radionuclide "i" -from the Condensate Polishing.
Building Vent (uCi). O i dy = Release of radionuclide "i" from the Decontamination Building Vent (uC1). 0 1
" = Release of radionuclide "i" from the Vaste Gas Storage Vault Vent (uCi).
The Turbine Building Vent is not normally a radioactive release point. It is included only for use if a radioactive release is identified in the future. In determining the dose at a particular location, dispersion parameter V, is a function of the pathway. For the food and ground plane pathway, V is in terms of D/0 If the inhalation -pathway is considered, V is in terms of X/0., Incorporation of the various pathways into Expression [2.3-20] results in the following expression for a particular organ: 3.17E-8 I [R gT +R +R +V +V yy0g gM g% +RhB][0.5 Vpyog pv cy 01
+
1 G cv vv tv0g 0 CP i cp dv i dv "I P" tv vv I pv
+ (X/0)cy0 3 + (X/0)yy0 g (X/0)tv 03 tv
+ +
vv + (X/0)cp0 g cv cp (X/0)dv0g + (X/Olyy03 i dv vv 0.3 mrem (per 31 days) [2.3-21] ; < 7.5 mrem (per quarter) 15.0 mrem (per year) 2-68 ISSUC 3
BV-1 and 2 ODCM where: I itg - Dose f actor for an organ "T" for radionuclide "1" for the ground plane exposure pathvay (mrem /yr per uCi/sec per m -2). iTg = Dose f actor for an organ "T" for radionuclide "i" for either the cov m uCi/see per m -2) ilk or goat milk pathway (mrem /yr per R iT = Dose f actor for an organ "T" for rad.onuclide vegetable pathway (mrem /yr per uCi/see per m -2")i" . f r the iTB = Dose f actor for an organ "T" for the meat pathway (mrem /yr for per radionuclide uCi/see per m"i"2). R iT = Gose f actor for an organ "T" for radionuclide "i" 3 for the inhalation pathway (mrem /yr per uCi/m ). It should be noted that V V V V V and cv,b ""termsty,g cp, V dv,/0(m-2), V yy in Expression [2.3-21]pV, ue g D Values of the dose factor, R were calculated using the methodology of NUREG-0133. The followind, equations were used for all nuclides except tritium: R it - K'(BR),(DFAg ),
= mrem /yr per uCi/m [2.3-22]
I where: K' = A constant of unit conversion (1E6 pCi/uCi). (BR) - The breathing 3 rate of the receptor of age group "a" (m /yr). (DFAg) - Each organ inhalation dose factor for the receptor of age group "a" for the "1" th radionuclide (mrem /pCi). Inhalation dose factors (DFAg ) by organ for the various age groups are given in Table E-7 through E-10 of Regulatory Guide 1.109, Rev. 1 or Tables 5 through 8 of NUREG-0172. used for the various age groups are tabulated The breathing rates belov, as given in Table (BR)*E-5 of the Regulatory Guide 1.109. Age Group (a) Breathing Rate (m /yr) Infant 1400 Child 3700 Teen 8000 Adult 8000 2-69 ISSUE 3
r: - BW1 and 2 ODCM iTg = K'K" (SF)DFGg [(1 - e~ i )/Ag ]
= m -mrem /yr per uC1/sec [2.3-23]
.where K' = A constant of unit conversion (1E6 pCi/uCl). K" = A constant of unit conversion (8/60 hr/ year). i = The decay constant for_the "i" th radionuclide (sec-1). t - The exposure time (4.73E8 set or 15 years). DFGH = The grour.dplane dose conversion factor f r organ "T" for the "i" in radionuclide (mrem /hr per pCi/m 2). A tabulation of DFG values is presented in Table E-6 of RegulathyGuide1.109. SF = The shielding factor (dimensionless). A shielding factor of 0.7 as suggested in Table E-15 of Regulatory Guide 1.109 is used. 1 t t R 0 (U ) ff (1 - f f )e~ i h ~i f gTH,p A pm(r)(DFL37),[ + (8 ]e 2
. = m -mrem /yr per uCi/sec [2.3-2A]
where K' = A constant of unit conversion (1E6 pCi/uCi). O F = The animal's consumption rate, vet veight (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 2pr ductivity 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. (DFLgT)* = The maximum organ ingestion dose factor for the "i" th radionuclide for the receptor in age group "a" (mrem /pCi). Ingestion dose factors (DFLg )a for the various age groups are given in Table E gy through E-14 of Regulatory Guide 1.109 or Tables 1 through 4 of NUREG-0172. 2-70 ISSUE 3
BU-1 and 2 ODCM A i = The decay constant for the "i" th radionuclide (sec~1). l b = The decay constant for removal of activity on 1eaf and plant surfaces by weathering 5.73E-7 sec -7 (corresponding to a 14 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 aninal, I to milk, to receptor (sec). I p = Fraction of the year that the animal is on pastu.e (dimensionless). E s = Fraction of the animal feed that is pasture grass while the animal is on pasture (dimensionless). Tabulated below are the parameter values used for cow's milk and their reference to Regulatory Guide 1.109. Parameter Value Table r (dimensionless) 1.0 for radioiodine E-15 0.2 for particulates E-15 F* (days / liter) each stable element E-1 (cow milk) E-2 (goat milk) 330 E-5 U ap (liters /yr) - infant child 330 E-5 teen 400 E-5 adult 310 E-5
), (mrem /pci) each radionuclide E-11 to E-14 (DLF1 Y 0.7 E-15 p (kg/m )
2 Ys (kg/m ) 2.0 E-15 t 1.73E5 (2 days) E-15 f (seconds) t 7.78E6 (90 days) E-15 h (seconds) Op (kg/ day) 50 E-3 f 0.5 -- p fs 1.0 -- For goat's milk, all values remain the same except for 70 vhich is 6 kg/ day. 2-71 ISSUE 3
BV-1 and 2 ODCM Op (U ff t igt ) (1 - f f )e ih iT B " K'q + P)F (r)(DFLf H}aI
- I*
2
= m -mrem /yr per uCi/sec [2.3-25]
where: Fg = The stable element transfer coefficients (days /kg). U,p = The receptor's meat consumption rate for age "a" (kg/yr), tf = 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 Ff which is obtained from Table E-1, t, which is obtained from Table E-I5 and U vhich is obtained from Table E-5. The values 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 Man is considered to consume 2 types of vegetation (fresh and stored) that differ only in the time period between harvest and consumption; therefore: R t -At I it gh y = K' [
](DLF1) [U f ge +Ufe ].
2
= m -mrem /yr per uCi/sec {2.3-26]
vhere: K' = A constant of unit conversion (1E6 pCi/uci). b U" = The consumption rate of fresh leafy vegetation by the receptor in age group "a" (kg/yr). Uf=Theconsumptionrateofstoredvegetationbythereceptorin age group "a" (kg/yr). fy' = The fraction of the annual intake of fresh leafy vegetation grown locally. 2-72 ISSUE 3
BV-1 and 2 ODCM f E= The fraction of the annual intake of stored vegetation grown locally. tg - The average time between harvest of leafy vegetation and its consumption (seconds). t h = The average time between harvest of stored vegetation and its consumption (seconds). 2 Yy = The vegetation area density (kg/m ), all other factors are defined previously. Tabulated below are the appropriate parameter values and their reference to Regulatory Guide 1.109. Parameter Value Table r (dimensionless) 1.0 for radiciodines E-15 0.2 for particulates E-15 (DFLh}a (mrem /P Ci) each stable element E-11 to E-14 U (kg/yr) - infant 0 E-5 child 26 E-5 teen 42 E-5 adult 64 E-5 l U* (kg/yr) - infant 0 E-5 child 520 E-3 teen 630 E-5 adult 520 E-5 fg (dimensionless) 1.0 E-15 F (dimensionless) 0.76 E-15 t g (seconds) 8.6E4 (1 day) E-15 t h (seconds) 5.18E6 (60 days) E-15 Yy (kg/m ) 2.0 E-15 As discussed in Section 2.2.2 for tritium, the parameter V for the food pathvay is based upon X/0. The ground plane pathway is not appropriate for tritium. Therefore, the left-hand portion of Expression [2.3-20J may be expressed for purposes of implementation of 40 CFR 190. discussed in Section 4.0, as: For Tritium: 3.17E-8 (R TT +R +R TT
*R TT ) [0.5 (X/0)py 0 T + (X/0)cy0T
- M Th B I pv cv (X/0)yy0 T + 0 0 0 +
(X/0)yy0 7 ) D vv (X/0)tv Tvv+ (X/0)cp ,cp+ (X/0)dv T dv vv [2.3-27] 2-73 ISSUE 3
BV-1 and 2 ODCM vhere: R - Dose f actor for organ "T" for3 tritium for the milk TT H pathway (mrem /yr per uCi/sec ). R = Dose f actor for organ "T" 3 f r tritium for the vegetable Th pathway (mrem /yr per uC1/m ). R - Dose factor for organ "T" f r tritium for the beef TT 3 B pathway (mrem /yr per uCi/m ). R - Dose factor for organ "T" 3 f r tritium for the inhalation TT pathway (mrem /yr per uCi/m ). I Expression [2.3-27] is used to show compliance with 40 CFR 190, as discussed in Section 4.0. The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R is based on [X/01: TM R T g- K'K'"F,0 7U,p(DLFh)a[0.75(0.5/H)]
= mrem /yr per uCi/m 3 [2.3-28]
where: 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 Mner parameters and values are the same as for Rg7 . H The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, is based' the R g t on [X/0): R T g* K'K'"IU fL
- U f ](DFLg g ),[0.75(0.5/H)]
- mrem /yr per uci/m 3 [2.3-29]
vhere all terms have been defined above. The concentratien of- tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R is based on [X/0]: T3 4 2-74 ISSUE 3,
BV-1-and 2 ODCH R l f7U,p(DFL h a[0.75(0.5/H)] T g= K'K'"F 0 l
= mrem /yr per uCi/m [2.3-30]
vhere all terms have been dafined above. To show compliance with ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4, Equation [2.3-21] is evaluated at the controlling pathway location. For Release Modes 1 through 4, the controlling location is a residence 0.89 miles in the NV sector. Inserting appropriate X/0. values from Tables 2.2-4 to 2.2-10 and D/0 values from Tables 2.3-28 to 2.3-34, Expression [2.3-21] becomes: Release Modes 1 Through 4 Per Month, Calendar Quarter, Or Year: 3.17E-8 E g [Rh+Rg 3][(0.5)4.22E-10 O g + 1.56E-8 O cv + 1.56E-8 G pv Og + 1.55E-8 O g + 1.55E-8 0 3
+ 1.56E-8 O g + 1.56E-8 vv tv I cp dv
+ 2.71E-5 O g 0 )+Rh [(0.5) 7.30E-9 Og + 2.00E-5 O g 3
vv I pv cv vv
+ 2.22E-5 O g + 2.22E-5 O g
+ 2.00E-5 0 3
+ 2.00E-5 O g ]
tv cp dv vv , 0.3 mrem (per 31 days) [2.3-31]
< 7.5 mrem (per quarter - 15.0 mrem (per year)
For tritium, for purposes of implementation of 40 CFR 190, as discussed-in Section 4.0, Expression [2.3-28] reduces to:
+
3.17E-8 [R +RTT ][(0,5)7.30E-9 Og + 2.00E-5 Og + 2.71E-5 0-3 vv Tb I pv cv 2.22E-5 O g + 2.22E-5 O g + 2.00E-5 O g + 2.00E-5 O g ] tv cp dv vv [2.3-32] The determination of a controlling locating for implementation of ODCM Appendix C CONTROLS 3.11.2.3 and 3.11.2.4 for radioiodines and particulates is a function of: (1) Radionuclide mix and their isotopic release (2) Release mode (3) Heteorology (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. I ! 2-75 ISSUE 3 i
BV-1 and 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 q presented in Tables 2.2-2a and 2.2-2b as a function of release mode and release point. For the ground plane exposure pathway, all radionculides (excluding H-3 and C-14) were considered in the determination of the controlling location. For the inhalation and food pathways H-3 and C-14 vere also censidered in determination of the controlling location. In the determination of the controlling location for each release mode, all of the exposure pathways, as presented in Table 2.2-3, were evaluated. These include cov milk, goat milk, beef and vegetable ingestion and inhalation and ground plane exposure. An infant was assumed to be present at all milk pathvay locations. A child was assumed to be present at all vegetable garden and beef animal locations. The ground plane and inhalation exposure pathways vere 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 pathvays vere 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. l i Tables 2.3-2 through 2.3-20 present R values for the total body, 4 GI-tract, bone, liver, kidney, thyr 61d, and lung organs for the ground plane, inhalation, cov milk, goat milk, vegetable, and meat ingestion pathways for the infant, child, teen, and adult age groups as apptopriate to the pathways. These values vere calculated using the methodology described in NUREG-0133 usirg a grazing period of 6 months. In the determination of the controlling location for Release Modes 1-4, Tables 2.2-4 through 2.2-10 are utilized for X/0's Tables 2.3-28 through 2.3-34 are utilized for long term D/0 values. A description of the derivation of the various X/0 and D/0 values is presented in Appendix A. Long-term D/0 values for the Process Vent, Containment Building Vent, the Ventilation Vent, Turbine Building Vent, Condensate Polishing Building Vent, Decontamination Building Vent, and the Vaste Gas Storage Vault Vent are provided for the midpoints of the following distances: 0.0-0.5 mi., 0.5-1.0 mi., 1.0-1.5 mi., 1.5-2.0 mi., 2.0-2.5 mi., 2.5-3.0 mi., 3.0-3.5 mi., 3.5 4.0 mi., 4.0-4,5 mi., 4.5-5.0 mi. The values appear in Tables 2.3-21 through 2.3-27. These values may be utilized if an additional special location arises different from those presented in the special locations of Table 2.2-3. q 2-76 ISSUE 3
BV-1 and 2 ODCM The following relationship should hold for BV-1 or BV-2 to show compliance with ODCM Appendix C CONTROL 3,11.2.3. For The Calendar Quarter: D f 7.5 mrem to any organ [2.3-33) For The Calendar Year: D f 15 mrem to any organ [2.3-34] vhere: D - The dose to any organ from radiciodines and particulates (mrem). The quarterly limits given above represent one-half the annual design objective of Section IIC of Appendix I of 10 CFR 50. If any of the limits of Expressions [2.3-33] and [2.3-34] are exceeded, a special report pursuant to both Section IV.A of Appendix I of 10 CFR 50 and ODCM Appendix C CONTROL 3.11.2.3.a must be filed with the NRC at the identified locations. I 2-77 ISSUE 3 i
l BV-1 and 2 ODCM 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 least once per 31 days in accordance with ODCM Appendix C CONTROL 4.11.2.4 and this section. (See also Section 2.3.1.2 Projection Of Doses). The 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 projected doses due to gaseous effluent releases from each reactor unit, when averaged over 31 days, would exceed 0.3 mrem to any organ. (See also Section 2.3.1.2 Projection Of Doses for additional specifications). Doses resulting from the gaseous effluent release of 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 Day , D 31
- A+B (31) + C [2.3-35]-
.I
. - l When Not Including Pre-Release Data, D
31 =. 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). 2-78 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-1 MODES OF GASEGUS RELEASE FROM BEAVER VALLEY SITE VENTS FOR l IMPLEMENTATION OF 10 CFR 20 AND 10 CFR 50 RELEASE POINT MODE 1 MODE 2 MODE 3 MODE 4 BVPS BVPS-2 Main Cond. Air Same As Same As Same As Process Vent (pv) Ejector, Vaste Mode 1 Mode 1 Mode'l-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 (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 (tv1) Exhaust
- Mode 1* Mode 1* Mode 1*
BVPS-2 Ventilation Contiguous Contajnment Same As Same As Vent (vv2) Areas Purge 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.1- Turbing Bldg. Same As Same As Same As Vent (tv2) Exhaust
- Mode 1* Mode'1* Mode.1*
BVPS-2 Condensate l * * * *= Polishing Bldg. Vent (cp2)
'BVPS-2 Decontamination * * *
- Bldg. Vent (dv2)
BVPS-2 Vaste Gas * * *
- Storage Vault Vent (vv2)
*Not normally a radi~oactive release point NOTE: For the purpose of implementing 10 CFR 50, batch discharges'may use continuous meteorology since short term meteorology is used at the-time of the annual report.
2 Continuous ground level meteorology is applicable Continuous elevated meteorology is applicable 3 Mode established by purge from one unit, all other release points remain same I- as Mode 1 1 2-79 ISSUE 3
EV-1 and 2 ODCH Table 2.3-2 q R VAL'JIS FOR EEAVER VALLEY SITE (ares /yrperuC1/cuseter) Pathway:Inbalation AgeGroup: Adult Nuclide Bone Liver T. Bod! Tbrrold Eidner. Long GI-LLI IH-3 0.00!+00 '26t+03 1.26E+03 1.26E+03 1.26t+03 1.26E+03 1.26I+03 2P-32 1.32E+06 7.71E+04 5.01E+04 0.00!+00 0.00E+00 0.00!+00 8.64E+04 3Cr-51 0.00E+00 0.00E+00 1.00!+02 5.95E+01 2.28t+01 1.44E+04 3.32E+03 4Mn-54 0.00E+00 3.961+04 6.30E+03 0.00E+00 9.84E+03 1.40!+06 7.74E+04 5 Fe-59 1.18I+04 2.78E+04 1.06t+04 0.00E+00 0.00E+00 1.02E+06 1.88t+05 6 Co-57 0.00E+00 6.92E+02 6.71E+02 0.00E+00 0.00l+00 3.70E+05 3.14Et04 7 00-58 0.00E+00 1.58t+03 2.071+03 0.00!+00 0.00!+00 9.281+05 1.06t+05 8 Co-60 0.00!+00 1.15E+04 1.48E+04 0.00!+00 0.00E+00 5.97E+06 2.65E+05 9 Zn-65 3.24I+04 1.03E+05 4.66t+04 0.00!+00 6.90E+04 8.64E+05 5.34E+04 10 Rb-86 0.00!+00 1.35E+05 5.90E+04 0.00E+00 0.00E+00 0.00E+00 1.66I+04 11 Sr-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00!+00 1.40!+06 3.50E+05 12St-90 9.92E+07 0.00Et00 6.10!+06 0.00E+00 0.00!+00 9.60E+06 7.22I+05 13Y-91 4.62E+05 0.00E+00 1.24E+04 0.00E+00 0.00E+00 1.70!+06 3.851+05 14 Zr-95 1.071+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50!+05 15Nb-95 1.41E+04 7.82E+03 4.21I+03 0.00!+00 7.74E+03 5.05E+05 1.04E+05 16Nb-97 2.22I-01 5.62E-02 2.05E-02 0.00E+00 6.54E-02 2.40!+03 2.42E+02 17 Ho-99 0.00E+00 1.21E+02 2.30!+01 0.00E+00 2.91E+02 9.12I+04 2.48t+05 18fc-99: 1.03E-03 2.911-03 3.70E-02 0.00E+00 4.42E-02 7.64E+02 4.16E+03 19 2a-103 1.53E+03 0.00E+00 6.581+02 0.00E+00 5.83E+03 5.05E+05 1.10!+05 20Ra-106 6.91E+04 0.00It00 8.721+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 21Ag-110s 1.08E+04 1.00E+04 5.94E+03 0.00Et00 1.97E+04 4.63E+06 3.02Et05 22Sb-124 3.12E+04 5.898+02 1.24E+04 7.55E+01 0.00E+00 2.48E+06 4.061+05 23 Sb-125 5.34t+04 5.95E+02 1.268+04 5.40E+01 0.00E+00 1.74E+06 1.01E+05 24Te-127a 1.26t+04 5.77t+03 1.57t+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 25fe-129: 9.76t+03 4.67t+03 1.581+03 3.44E+03 3.66t+04 1.161+06 3.83E+05 26l-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13I+04 0.00E+00 " 2BE+03.. 27I-133 8.64E+03 1.481+04 4.52E+03 2.15E+06 2.58t+04 0.00E+00 8.88t+03 28Ce-134 3.73E+05 8.48!+05 7.28t+05 0.00E+00 2.87t+05 9.76t+04 1.04E+04 29 Cs-136 3.90E+04 1.481+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.171+04 30Co-137 4.78E+05 6.21E+05 4.28E+05 0.00!+00 2.22E+05 7.52E+04 8.40!+03 31Ba-140 3.90E+04 4.90E+01 2.57E+03. 0.00!+00 1.67t+01 1.271+06 2.18Et05 32 La-140 3.44I+02 1.74I+02- 4.581+01 0.00E+00 0,00!+00 1.36E+05 4.5BE+05 33Ce-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26t+03 3.62E+05 1.20E+05 34 Ce-144 3.42E+06 1.43E+06 1.84I+05 0.00!+00 8.48E+05 7.78E+06 8.16!+05 CalculctedperODCMequation2.3-22 4 ISEE 3 j 2-60
BY-1and2ODCM fable 2.3-3 HVALUISFORBEAVIRVALLEYSITE (sres/yrperiC1/cuseter) Pathway:Inhalatica , Age Group : Teen Nuclide Bone Liver f. Body Ibyroid lidney Long GI-LLI 1 F3 0.00b00 1.27bO3 1.27bO3 1.27bO3 1.27 b O3- 1.27 b O3 1.27bO3 2P-32 1.89b06 1.10b05 7.16b04 0.00 BOO 0.00b00 0.00b00 9.28b04 3Cr-51 0.00D00 0.00h00 1.35D02 7.50b01 3.07b01 2.10D04 3.00bO3 4 Mn-54 0.00D00 5.11b04 8,40bO3 -0.00b 00 1.27b04 1.98b06 6.68b04 5 Fe-59 1.59b04 3.70D04 1.43b04 0.00b00 0,00D00 1.53b06 1.iBb05 600-57 0.00b00 9.44bO2 9.20bO2 0.00b00 0.00 BOO 5.86b05 3.14b04 7 00-58 0.00b00 2.07bO3 2.7BbO3 0.00b00 0.00b00 1.34b06 9.52b04 8 Co-60 0.00b00 1.51b04 1.98b04 0.00b00 0.00b00 8.72b06 2.59b05 9 Zn-65 3.86b04 1.34b05 6.24b04 0.00D00 864b04 1.24b06 4.66b04 10 Rb-86 0.00b00 1.90b05 8.40bO( 0.00000 0.00b00 0.00b00 1.77b04 , 11St-89 4.34b05 0.00b00 1.25b04 0.00b00 0.00b00 2.42h06 3.71Et05 12St-90 1.0BbOB 0.00b00 6.68b06 0.00b00 0.00b00 1.65bO7 7.65b05 13Y-91 6.61b05 0.00D00 1.77b04 0.00D00 0.00b00 2.94b06 4.09b05 } 14Ir-95 1.46b05 4.5Bb04 - 3.15b04 0.00b00 6.74b04 2.69b06 1.49b05 15Nb-95 1.86b04 1.03D04 5.66bO3 0.00b00 1.00b04 7.51b05 9.68b04 16Nb-97 3.141-01 7.78b02 2.848-02 0.00h00 9.12b02 3.93bO3 2.17bO3 17 Mo-99 0.00b00 1.69b02 3.22b01 0.00b00 4.11bO2 1.54b05 2.69b05 18fc-99: 1.38b03 3.86b03 4.99002 0.00b00 5.76b02 1.15bO3 6.13bO3 19 Ru-103 2.10bO3 0.00b00 8.96bO2 0.00 BOO 7.43bO3 7.83b05 1.09b05 20Ru-106 9.84b04 0.00b00 1.24b04 0.00D00 1.90b05 1.61bO7 9.60b05 21Ag-110s 1.38b04 1.31b04 7.99bO3 0.00 BOO 2.50b04 6.75b06 2.73b05 22Sb-124 4.30b04 7.94bO2 1.68h04 9.76b01 0.00D00 3.34b06 3.98b05 ' 23 Sb-125 7.38b04 8.08bO2 1.72b04 7.04b01 0.00b00 2.74 b06' 9.92b 04 24fe-127s 1.5cb04 8.16bO3 2.1BbO3 4.38bO3 . 6.54bo4 1.66b06 1.59b05 25fe-129s 1.39b04 6.5SbO3 2.25bO3 4.58bO3 5.19b04 1.98b06 4.05b05 26I-131 3.54b04 4.91b04 2.64b04 1.46bO7 8.40b04 0.00b00 6.49bO3 271-133 1.22b04 2.05bO( 6.22bO3 2.920 06 3.5Sb04 0.00b00 1.03b04 28Cs-134 5.02b05 1.13b06 5.(9b05 0.00b00 3.75bo5 1.46b05 9.76bO3 29 Cs-136 5.15b04 1.94t+05 - 1.37 b05 0.00b00 1.10 b 05' l.78b 04 1.09b04 30 Cs-137 6.70b05 8.46b05 3.11b05 0.00b00 3.04b05 1.21b05 8.4BbO3 31Ba-140 5.47b04 6.70b01 3.52bO3 0.00b00 2.28b01 2.03b06 2.29b05 32La-140 4.79bO2 2.36bO2 6.26b01 0.00b00 0.00b00 2.14b05 4.87b05 ; 33Ce-141 2.84b04 1.90b04 2.17bO3 0.00b00 8.88D03 6.14b05 1.26b05 34Ce-144 4.89b06 2.02b06 2.62b05 0.00b00 1.21b06 1.34bO7 8.64b05 - I CalculatedperODCMequation2.3-22 ISKE 3 2-81
y BV-1 and 2 ODCM fable 2.3-4 RVALUESFOREIAVERVALLEYSlfE I (tres/1. per vCi/cu seter) Pathver: Inhalation Age Group : Child Nuclide Bone Liver f. Body Thyroid Eidney Lung GI-LLI 1H-3 0.00E+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 2 P-32 2.60!+06 1.14E+05 9.88E+04 0.00E+00 0.00!+00 0.00I+00 4.221:04 3Cr-51 0.00!+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08H+03 4 Mn-54 0.00!+00 4.29I+04 9.51E+03 0.00E+00 1.00E+04 1.58t+06 2.29E+04 5 Fe-59 2.07t+04 3.34E+04 1.672+04 0.00E+00 0.00l+00 1.27E+06 7.07E+04 6 00-57 0.00E+00 9.03t+02 1.07E+03 0.00!+00 0.00E+00 5.07t+05 1.32E+04 7 Co-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+34 8 00-60 0.00E+00 1.31E+04 2.26Et04 0.00E+00 0.00!+00 7.07E+06 9.62E+04 9Zn-65 4.25E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63H+04 10 Rb-86' O.00E+00 1.98E+05 1.14I+05 0.00E+00 0.00E+00 0.00E+00 7.99E+03 11Sr-89 5.991+05 0.00!+00 1.72E+04 0.00E+00 0.00!+00 2.10E+06 1.67E+05 12St-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.43E+05 13Y-91 9.14E+05 0.00!+00 2.44E+04 0.00!+00 0.00E+00 2.63E+06 1.841&05 14 Zr-95 1.90E+05 4.181+04 3.70E+04 0.00K+00 5.961+04 2.23E+06 6.11E+04 -l 15Nb-95 2.35E+04 9.181+03 6.55E+03 0.00E+00 8.62E+03 6.14E+05 3.70l+04 16 Nb-97 4.29E-01 7.70E-02 3.60E-02 0.00E+00 8.61-02 3.42E+03 2.78E+04 17 Mo-99 0.00E+00 1.72E+02 4.261+01 0.00E+00 3.92f+02 1.35E+05 1.271+05 18fc-95 1.78E-03 3.48E-03 5.771-02 0.00E+00 5.07E-02 9.51E+02 4.81E+03 19 Hu-103 2.79E+03 0.00E+00 1.071+03 0.00E+00 7.03I+03 6.62E+05 4.48t+04 20 Rn-106 1.36t+05 0.00l+00 1.69E+04 0.00!+00 1.84E+05 1.43E+07 4.29E+05 21Ag-110 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 22Sb-124 5.74E+04 7.40E+02 2.00!+04 1.261+02 0.00!+00 3.2dI+06 1.64E+05 23 Sb-125 9.84t+04 7.59E+02 2.07E+04 9.10E+01 0.00!+00 2.32E+06 4.03E+04 24fe-127a 2.49t+04 8.55E+03 3.02E+03 6.07E+03 6.36I+04 1.48t+06 7.14E+04 25 fe-129s 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.761+06 1.82E+05 26I-131 4.81E+04 4.61E+04 2.73E+04 1.62E+07 7.88t+04 0.00E+00 2.84E+03 27I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38t+04 0.00E+00 5.48E+03 28 Cs-134 6.51E+05 1.011+06 2.25E+05 0.00!+00 3.30E+05 1.21E+05 3.85E+03 29Cs-136 6.51E+04 1.71E+05 1.16t+05 0.00!+00 9.551+04 1.45E+04 4.18t+03 30 Cs-137 9.071+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 31 Ba-140 7.40E+04 6.48t+01 4.33E+03 0.00!+00 2.11E+01 1.74E+06 1.02E+05 32 la-140 6.44E+02 2.25E+02 7.55t+01 0.00E+00 0.00E+00 1.83E+05 2.261+05' 33 Ce-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04-34 Ce-144 6.77t+06 2.12E+0S 3.61E+05 0.00E+00 1.17E+06 1.20E+07 3.891+05 l Calculated per ODCM equation 2.3-22 1550! 3 2-82
EV-1and2ODCM fable 2.3-5 RVALUESFORBEAVIRVAli.EYSITI (stes/yrperuC1/cuseter) Pathway:Inhalatics AgeGroup: Infant hellde Bone Liver f. Body Thyroid tidney Lung GI-LL1 1 F3 0.00 BOO 6.47bO2 6.47bO2 6.47bO2 6.47bO2 6.47bO2 6.47bO2 2P-32 2.03b06 1.12b05 7.74b04 0.00b00 0.00b00 0.00b00 1.61b04 3Cr-51 0.00b00 0.00b00 8.95b01 5.75b01 1.32b01 1.28b04 3.57bO2 4Mn-54 0.00b00 2.53b04 4.98bO3 0.00D00 4.96bO3 1.00b06 - 7.06bO3 5 Fe-59 1.36b04 2.35b04 9.48bO3 0.00b00 0.00b00 1.01b06 2.48b04 6Co-57 0.00b00 6.51bO2 6.41bO2' O.00 b 00 0.00b00 3.79b05 4.86bO3 7 Co-58 0.00b00 1.22bO3 1.82bO3 0.00D00 0.00b00 7.77D05 1.11b04 0.00D00 8.02bO3 1.18b04 0.00b00 0.00b00 4.51b 06 ' 3.19b 04
~
8 Co-60 9 Zn-65 1.93b04 6.26b04 3.11b04 0.00b00 3.25b04 6.47b05 5.14b04 10Rb-86 0.00b00 1.90b05 8.82b04 0.00b00 0.00b00 0.00b00 3.04bO3 11St-89 3.98b05 0.00b00 1.14b04 0.00b00 0.00b00 2.03b06 6.40b04 12St-90 4.09bO7 0.00b00 2.59b06 0.WD00 0.00b00 1.12bO7 1.31b05 13Y-91 5.8Bb05 0.00b00 1.57b04 0.00b00 0.00D00 2.45b06 7.03h04-l~ 14Zr-95 1.15b05 2.79b04 2.03b04 0.00b00 3.11b04 1.75b06 2.17b04 15Nb-95 1.57b04 6.43bO3 3.78bO3 0.00b00 4.72bO3 4.79b05 1.27b04 16Nb-97 3.42b01 7.29002 2.63002 0.00 BOO 5.70F02 3.32b O3 '2.69h04-17 Mo-99 0.00b00 1.65bO2 3.23b01 0.00b00 2.65bO2 1.35b05 4.87b04 18Tc-99: 1.40003 2.88003 3.72002 0.00b00 3.11bO2 8.11bO2 2.03bO3 19Ru-103 2.02bO3 0.00b00 6.79bO2 0.00 b 00 4.24bO3 5.52b05 1.61b04 26 h-106 8.68Et04 0.00b00 1.09b04 0.00b00 1.07b05 1.16bO7 1.64b05 21Ag-110s 9.98bO3 7.22bO3 5.00bO3 0.00b00 1.09b04 3.67b06 3.30b04 22Sb-124 3.79b04 5.56bO2 1.20b04 1.01bO2 0.00b00 2.65b06 5.91b04 23Sb-125 5.17b04 4.77bO2 1.09b04 6.23b01 0.00b00 1.64b06 1.47b04 24fe-127 1.67b04 6.90bO3 2.07bO3 4.87bO3 3.75b04 ' 1.31006 2.73b04 25fe-129s 1.41b04 6.09bO3 2.23bO3 4.21bO3 3.18b04 1.6Sb06 6.90b04 261-131 3.79b04 4.44b04 1.96b04 1.4BbO7 5.18b04 0.00000 1.06bO3 27I-133 1.32b04 1.92b04 5.60bO3 3.56b06 2.24b04 0.00b00 2.16bO3 28Cs-134 3.96b05 7.03b05 7.45b04 0.00b00 1.90b05 7.97b04 1.33bO3 29Ca-136 4.83b04 1.35b05 5.29b04 0.00b00 5.64b04 1.16b04 1.43bO3 30Cs-137 5.49b05 6.12b05 4.55b04 0.00D00 1.72b05 7.13b04 1.33bO3 31Ba-140 5.60b04 5.60b01 2.90bO3. 0.00b00 1.34b01 1.60b06 3.84b04 32 La-140 5.05bO2 2.00bO2 5.15b01 0.00D00 0.00b00 1.68b05 6.4BD04 33Ce-141 2.77b04 1.67D04 1.99bO3 0.00b00 5.25bO3 5.17b05 2.16b04 34Ce-144 3.19b06 1.21D06 1.76b 05 0.00 b 00 5.38b05 9.84b06 1.48b05 I CalculatedperODCMequation2.3-22 IEEE 3 2-83
BV-1 and 2 ODCM Table 2.3-6 q' R VALUIS FOR BEAVER VALLET SITE (n meter-stes/yr per uCi/see) Pathway: Ground Fuelide Bone Liver T. Body Thyroid lidney Lung GI-LLI 1H-3 0.00E+00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 2P-32 0.00b00 0.00D00 0.00b00 0.00D00 0.00b00 0.00b00 0.00b00 3Cr-51 4.66b06 4.66b06 4.66b06 4.66b06 4.66b06 4.66b06 4.66b06 4 Mn-54 1.39b09 1.39b09 1.39b09 1.39b09 1.39b09 1.39b09 1.39b09 5 Fe-59 2.73 BOB 2.73 BOB 2.73b08 2.73b08 2.73b08 2.73bO8 2.73bO8 6 Co-57 0.00b00 0.00000 0.00D00 0.00D00 0.00b00 0.00D00 0.00b00 7 Co-58 3.79 BOB 3.79bO8 3.79bO8 3.79b08 3.79 BOB 3.79D08 3.79b08 B Co-60 2.15b10 2.15b10 2.15b10 2.15b10 2.15b10 2.15b10 2.15b10 9 Zn-65 7.47bO8 7.47 BOB 7.47b06 7.47bO8 7.47bO8 7.47 BOB 7.47bO8 10 Eb-86 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 8.99b06 11 Sr-89 2.16b04 2.16b04 2.16b04 2.16h04 2.16b04 2.16b04 2.16b04 12 Sr-90 0.00D00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00D00 11 b 91 1.07b06 1.07b06 1.07b06 1.07b06 1.07D06 1.07b06 1.07b06 14Zr-95 2.45 BOB 2.45bO8 2.45D08 2.45bO8 2.45D08 2.45bO8 2.45bO8 l 15 Nb-95 1.37bO8 1.37bO8 1.37bO8 1.37 BOB 1.37bO8 1.37bO8 1.37bO8 16 Nb-97 0.00b00 0.00000 0.00b00 0.00b00 0.00h00 0.00h00 0.00b00 17 Mo-99 4.00D06 4.00D06 4.00b06 4.00b06 4.00b06 4.00b06 4.00 BOG 1BTc-99: 1.84b05 1.84b05 1.84b05 1.84b05 1.84b05 1.84b05 1.84b05 19 Ru-103 1.08bO8 1.08bO8 1.08 BOB 1.08bO8 1.08bO8 1.08bO8 1.0BbOB 20 Ru-106 4.22bO8 4.22 BOB 4.22bO8 4.22bO8 4.22 BOB 4.22 BOB 4.22 BOB 21 Ag-110 3.44b09 3.44b09 3.44b09 3.44b09 3.44b09 3.44b09 3.44b09 22 Sb-124 0.00b00 0.00D00 0.00b00 0.00D00 0.00D00 0.00b00 0.00D00 23 Sb-125 0.00D00 0.00b00 0.00b00 0.00b00 0.00D00 0.00D00 0.00b00 24 fe-127 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 9.17b04 25 fe-129 1.98bO7 1.98bO7 1.98bO7 1.98bO7 1.98bO7 1.9BbO7 1.96bO7 26I-131 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 1.72bO7 27I-133 2.45b06 2.45b06 2.45b06 2.45b06 2.45b06 2.45b06 2.45b06 28 Cs-134 6.86b09 6.86b09 6.86b09 6.86b09 6.86b09 6.86b09 6.86b09 29Cs-136 1.51bO8 1.51bO8 1.51bO8 1.51bO8 1.51bO8 1.51bO8 1.51bO8 30 Cs-137 1.03D10 1.03b10 1.03b10 1.03b10 1.03bl0 1.03b10 1.03b10 31 Ba-140 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 2.05bO7 32La-140 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 1.92bO7 33Ce-141 1.37bO7 1.37bO7 1.37bO7 1.37bO7 1.37bO7 1.37bO7 1.37bO7 34Ce-144 6.96bO7 6.96bO7 6.96bO7 6.96bO7 6.96bO7 6.96bO7 6.96bO7 l CalculatedperODCMeguation2.3-23 IEE3 2-84
BV-1and2ODCH e fable 2.3-7 RVALUESFORBEAVIBVALLEYSlf! (egseter-stes/yrperuCl/see) Pathway: Vegetation AgeGroup: Adult Nuclide Bone Lher T. Body thyroid tidney Lung GI-LLI 1 b3 0.00b00 2.26E+03 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2.26bO3 2P-32 1.40D09 8.74bO7 5.43bO7 0.00D00 0.00 D00' O.00 b 00 1.58bO8 3Cr-51 0.00b00 0.00b00 4.64b04 2.78b04 1.02b04 6.16b04 1.17bO7 4 Ma-54 0,00E+00 '3.13bO8 5.97b07 0.00D00 9.31bO7 0.00D00 9.59bO8 5Fe-59 1.26bOS 2.S6 BOB 1.1@08 0.00b00 0.00D00 8.28bO7. 9.88 BOB 6Co-57 0.00b00 1.17bO7 1.95bO7 0.00b00 0.00Et00 0.00b00 2.97bOS 7 00-58 0.00D00 3.07bO7 6.89bO7 0.00b00 0.00b00 0.00b00 6.23b08 8 Co-60 0.00b00 1.67bO8 3.69bO8 0.00b00 0.00000 0.00b00 3.14b09 9Zn-65 3.17bO8 1.0lb09 4.56bO8 0.00b00 6.75 b06. 0.00D 00 6.36bO8 10Eb-86 0.00b00 2.19bO8 1.02 BOB 0.00 BOO 0.00D00 0.00 BOO 4.33bO7 11$r-89 9.971+09 0.00b00 2.86 BOB 0.00D00 0.00b00 0.00D00 1.60b09 12Sr-90 6.05b11 0.00b00 1.48b11 0.00D00 0.00b00 0.00b00 1.75b10 13 b91 5.11b06 0.00b00 1.37b05 0.00b00 0.00 b 00. 0.00b 00 2.81b09 ) 14Zr05 1.17b06 3.77b05 2.55b05 0.00b00 5.91b05 0.00b00 1.19b09' 15Nb-95 1.42005 7.92b04 4.26b04 0.00D00 7.83b04 0.00D00 4.81 BOB 16Nb-97 2.16b06 5.46007 1.99b07 0.00b00 6.37E-07 0.00b00 2.02003 17Mo-99 0.00b00 6.15 b06 1.17 b06 0.00b00 1.39D07 0.00b00 1.43bO7 18fe-99: 3.10b00 ~ 8.77b00 1.12bO2 0.00b00 1.33bO2 4.30D00 5.19b03 19Eu-103 4.77b06 0.00b00 2.06b06 0.00b00 1.82bO7 0.00b00' 5.57 BOB 20Hu-106 1.93bO8 0.00b00 2.4(bO7 0.00b00 - 3.72D08 0.00b00 1.25b10 . 21 Ag-110s 1.05bO7 9.75b06 5.79b06 0.00b00 1.92bO7 0.00 b00 3.98b09 - 22Sb-124 1.04bO8 1.96b06 4.11bO7 2.51b05 0.00b00 8.07bO7 2.94b09 ' 23Sb-125 1.37bO8 1.53b06 3.25bO7 1.39D05 0.00b00 1.05 bO8 - 1.50b 09 , 24fe-127 3.49bO8 1.25bO8 4.26bO7 8.92bO7 1.42b09 0.00 b00 1.17b 09. 25fe-129s 2.51bO8 9.38bO7 - 3.98bO7 8.64D07 1.05b09 0.00b00 1.27b09-26l-131 8.08bO7 1.16 BOB 6.62bO7 3.79b10 1.98bO8 ' O.00b00 3.05bO7 27I-133 2.09b0B 3.63b06 1.11b06 5.33 BOB 6.33b06 0.00h00. 3.26b06 28Ca-134 4.67b09 1.11b10 9.0Bb09 0.00 b 00- 3.59b 09 1.19b09 1.94bO8 29Cs-136 4.27bO7 1.69b08 1.21 BOB 0.00b00 9.38bO7 1.29bO7 1.91bO7 30Cs-137 6.36b09 8.70b09 5.70b09 0.00b00 2.95b09 9.81bO8 1.68b08 31Ba-140 1.29bO8 1.61bo5 8.42b06 0.00D00 5.49b04 9.24b04 2.65 BOB , 32La-140 1.98bO3 9.97bO2 2,63bO2 0.00b00 0.00b 00 -0.00b00 7.32b07 33Ce-141 1.97b05 1.33b05 1.51b04 0.00b00 6.19b04 0.00b00 5.10 BOB' 34 Ce 144 3.29bO7 1.38bO7 1.77b06 0.00b00 8.16b06 0.00b00 1.11bl0 I All nuclides (except b 3) calculated per ODCM equation 2.3-26 b3calculatedperODCHequation2.3-29 i 155UI3 2-B5
B7-1 and 2 ODCM l 1 Table 2.3-8 . R VALUIS FOR BEAVER VALLEY SITE l (eqsetertres/yrperuCi/sec) Pathway: Vegetation Age Group : Teen Nuclide Bone Liver f. Body Thyroid Eldney Lung Gl-LLI 1 H-3 0.00E+00 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59E+03 2.59Et03 2P-32 1.611+09 9.981+07 6.24E+07 0.00!+00 0.00!+00 0.00E+00 1.35E+08 3 Cr-51 0.00!+00 0.00E+00 6.li!+04 3.43E+04 1.35E+04 8.81E+04 1.04E+07 4 En-54 0.00E+00 4.54t+08 9.01E+07 0.00!+00 1.36E+08 0.00E+00 9.32E+08 5 Fe-59 1.79E+08 4.19t+0B 1.62E+0B 0.00E+00 0.00!+00 1.32E+08 9.90!+08 6 Co-57 0.00E+00 1.79I+07 3.00E+07 0.00!+00 0.00!+00 0.00!+00 3.331+08 7 00-58 0.00E+00 4.36E+07 1.00!+09 0.00E+00 0.00!+00 0.00E+00 6.01E+08-8 Co-60 0.00E+00 2.498+08 5.60I+06 0.00E+00 0.00!+00 0.00E+00 3.24E+09 9 Zn-65 4.24E+08 1.47E+09 6.87E+08 0.00!+00 9.42E+08 0.00E+00 6.23E+08 10 Rb-86 0.00E+00 2.74E+0B 1.29I+08 0.00E+00 0.00!+00 0.00E+00 4.05E+07 11 Sr-89 1.51E+10 t %00 4.34I+08 0.00!+00 0.00E+00 0.00!+00 1.80!+09 12Sr-90 7.51E+11 0.00!+00 1.85E+11 0.00E+00 0.00!+00 0.00!+00 2.11E+10 13 Y-91 7.84E+06 0.00!+00 2.10I+05 0.00!+00 0.00E+00 0.00E+00 3.21E+09 14Zr-95 1.72E+06 5.43E+05 3.74E+05 0.00E+00 7.96E+05 0.00!+00 1.25E+09 15 Nb-95 1.92E+05 1.07E+05 5.878+04 0.00!+00 1.03E+05 0.00E+00 4.56E+08 16Nb-97 2.00E-06 4.97I 1.81E-07 0.00E+00 5.811-07 0.00E+00 1.191-02 17 Mo-99 0.00E+00 5.65E+06 1.08I+06 0.00!+00 1.291+07 0.00!+00 1.01E+07 18 fe-99: 2.74E+00 7.64E+00 9.90!+01 0.00E+00 1.14t+02 4.24E+00 5.02E+03 19 Ru-103 6.82E+06 0.00E+00 2.921+06 0.00E+00 2.41E+07 0.00E+00 5.70!+08 20Es-106 2.38E+08 0.00!+00 3.90!+07 0.00E+00 5.97I+03 0.00!+00 1.48t+10 21 Ag-110s 1.52E+07 1.43E+07 8.72E+06 0.00!+00 2.74E+07 0.00!+00 4.03!+09 22Sb-124 1.54I408 2.84I+06 6.02E+07 3.50!+05 0.00E+00 1.35E+08 3.11E+09 23Sb-125 2.14E+08 2.34E+06 5.01E+07 2.05E+05 0.00E+00 1.88t+0B 1.67E+09 24 fe-127: 5.52E+08 1.96I+08 6.56E+07 1.311+0B 2.24E+09 0.00E+00 1.37E+09 25fe-129n 3.62t+08 1.34E+08 5.73E+07 1.17t+08 1.51E+09 0.00E+00 1.361+09 26I-131 7.691+07 1.08t+08 5.78I+07 3.14t+10 1.85E+08 0.00Et00 2.13E+07 27I-133 1.94E+06 3.291+06 1.00!+06 4.59E+08 5.77E+06 0.00E+00 2.491+06 28Cs-134 7.10!+09 1.671+10 7.75E+09 0.00!+00 5.31E+09 2.03E+09 2.081+08 29 Cs-136 4.38t+07 1.721+08 1.16E+08 0.00!+00 9.37I+07 1.48I+07 1.39E+07 30 Cs-137 1.01E+10 1,35I+10 4.69I+09 0.00E+00 4.591+09 1.78I+09 1.92E+08 31 Ba-140 1.381+08 1.69E+05 8.90!+06 0.00!+00 5.74E+04 1.14E+05 2.13E+0B 32 La-140 1.81E+03 8.88t+02 2.36E+02 0.00E+00 0.00E+00 0.00!+00 5.10E+07 33Ce-141 2.83I+05 1.891+05 2.17E+04 0.00E+00 B.90!+04 0.00E+00 5.41E+08 34 Ce-144 5.27E+07 2.181+07 2.83E+06 0.00!+00 1.30E+07 0.00!+00 1.33E+10 Allcu:lidesiexceptH-3)calculatedperODCMequatien2.3-26 H-3calculatedperODCMequation2.3-29 155UE3 2-86
BV-1 and 2 ODCM fable 2.3-9 R VALUIS FOR BEAVIR VALLEY SITE (sqseter-stes/yrperuCl/sec) Pathway: Vegetation Age Group : Child helide Bone Liver T. Body Thyroid fidney Lung GI-LLI. Ih-; 0.00D00 4.0lbO3 4.0lbO3 4.0lbO3 4.0lbO3 4.01bO3 4.01E+03 2 P-32 3.37b09 1.58 BOB 1.30 BOB 0,00b00 0.00b00 0.00b00 9.32bO7 3Cr-51 L O0 BOO 0.00D00 1.17b05 S.50b04 1.76b04 1.19h05 6.21b06 4 !!n-54 0.00000 6.65 BOB 1.77bO8 0.00b00 1.86 BOB 0.00 BOO 5.58bO8 5 Fe-59 3.98bO8 6.43bOS 3.20bO8 0.00b00 0.00D00 1.87bO8 6.70 BOB 6 00-57 J.00b00 2.99bO7 6.04bO7 0.00b00 0.00h00 0.00000 2.45bO8 7 Co-58 0.00 BOO 6.44bO7 1.97bO8 0.00D00 0.00b00 0.00b00 3.76bOS 8 Co-60 0.00s+00 3.78bOS 1.12b09 0.00b00 0.00b00 0.00 b 00. 2.10 b09 9 Zn-65 8.13 BOB 2.17b09 1.35b09 0.00b00 1.36b09 0.00b00 3.80 BOB 10 Rb-86 0.00D00 4.52bO8 2.78bO8 0.00b00 0.00b00 0.00b00 2.91bO7 11Sr-89 3.60b10 0.00b00 1.03b09 0.00b00 0.00h00 0.00h00 1.39b09 12St-90 1.24b12 0.00b00 3.15b11 0.00D00 0.00b00 0.00 BOO 1.67b10 13Y-91 1.86bO7 0.00b00 4.99b05 0.00b00 0.00 BOO 0.00b 00 .2.48b09 l 14Zr-95 3.86b06 8.48b05 7.55b05 0.00b00 1.21b06 .0.00b00 8.85bOS 15 E 95 4.11b05 1.60D05 1.14b05 0.00b00 1.50D05 0.00b00 2.96 BOB 16Nb-97 3.65E-08 6.59E-07 3.081-07 0.00b00 7.31E-07 0.00b00 2.03E-01 17Mo-99 0.00b00 7.71b06 1.91b06 0.00D00 1.65bO7. 0.00b 00 6.38b06 187c-99: 4.71b00 9.24h00 1.53bO2 0.00D00 1.34bO2 4.69b00 5.26bO3 19 Hu-103 1.53bO7 0.00b00 5.90b06 0.00b00 3.86bO7 0.00D00 3.97 BOB 20 Ru-106 7.45bO8 0.00b00 9.30bO7 0.00b00 1.01b09 0.00b00 1.16b10 21Ag-110 3.21bO7 2.17bO7 1.73bO7 0.00b00 4.04bO7 0.00000 2.58b09 22Sb-124 3.52 BOB 4.57b06 1.23bO8 7.77b05 0.00b00 ~1.95 BOB: 2.20b09 23 Sb-125 4.99b08 3.85906 1.05bO8 4.63b05 0.00b00 2.78bO8 1.19b09' 247e-127s 1.32b09 3.56bO8 1.57 BOB 3.16bO8 3.77b09 0.00b00 1.07b09 25fe-129s 8.41bO8 2.35 BOB 1.31 BOB 2.71bO8 2.47b09 0.00h00 1.03b09 26I-131 1.43b08 1.4(bO8 8.17bO7 4.76b10 2.36b06 0.00b00 1.28bO7 27I-133 3.53b06 4.37b06 1.65b06 8.12bO8 7.28b06 0.00h00 1.76b06 28Cs-134 1.60b10 2.63b10 5.55b09 0.00 BOO 8.15b09 2.93b09- 1.42bOS 29Cs-136 8.24bO7 2.27bO8 1.47bO8 0.00b00 1.21 BOB 1.80bO7 7.96b06 30 Ca 137 2.39b10 2.29b10 3.38b09 0.00b00 7.46b09 2.68b09 1.43bOS 31Ba-140 2.77 BOB 2.42bO7 1.62bO7 0.00h00 7.89b04 1.45b05 1.40bO8 - 32 La-140 3.2fbO3 1.13bO3 3.83bO2 0.00 b00' O.00b00 0.00b00 3.16bO7 33Ce-141 6.56b05 3.27b05 4.86b05 0.00b00 1.43b05 0.00D00 4.08 BOB 34 Ce-144 1.27bO8 3.98bO7 6.78b06 0.00b00 2.21bO7 0.00b00 1.04b10 Allnuclides(exceptH-3)calculatedperODCNequation2.3-26 b3calculatedperODCllequation2.3-29 IS5UE3 , 2-87 i
EV-1 and 2 ODCH Table 2.3-10 RVALUISFOREIAVERVALLIYSITI (sq seter-ares /yr per uC1/sec) Pathway : Meat AgeGroup: Adult Nuclide Bone Liver f. Body Thyroid Ildney Lung GI-lli 1 F3 0.00D00 3.25bO2 3.25D02 3.25bO2 3.25bO2 3.25bO2 3.25bO2 2 P-32 3.95b09 2.46bO8 1.53b08 0.00b00 0.00b00 0.00b00 4.44 BOB 3 Cr-51 0.00b00 0.00b00 5.86bO3 3.50D03 1.29bO3 7.78bO3 1.47b06 4Mn-54 0.00b00 6.49b06 1.24D06 0.00b00 1.93b06 0.00b00 1.99bO7 5 Fe-59 2.14bO8 5.04bO8 1.93bO8 0.00D00 0.00b00 1.41D0B 1.68b09 6 Co-57 0.00b00 4.01b06 6.66b06 0.00D00 0.00b00 0.00 BOO 1.02 BOB 7 Co-58 0.00b00 1.42bO7 3.1BbO7 0.00b00 0.00b00 0.00b00 2.87 BOB 8 Co-60 0.00b00 5.12bO7 1.13b08 0.00b00 0.00b00 0.00b00 9.61 BOB 9 Zn-65 2.54bOS 8.09 BOB 3.66 BOB 0.00b00 5.41bOS 0.00b00 5.10bO8 10 Eb-86 0.00 BOO 4.11 BOB 1.92bO8 0.00E+00 0.00b00 0.00b00 8.11bO7 11 St-89 2.41 BOB 0.00b00 6.92b06 0.00b00 0.00b00 0.00b00 3.87bO7 12 Sr-90 8.41b09 0.00b00 2.06b09 0.00b00 0.00D00 0.00b00 2.43bO8 13 E 91 8.94b05 0.00b00 2.39b04 0.00D00 0.00E+00 0.00b00 4.92bO8 14 Zr-95 1.47b06 4.71b05 3.19b05 0.00b00 7.39b05 0.00 BOO 1.49b09 l 15 lib-95 1.89b06 1.05b06 5.64b05 0.00b00 1.04b06 0.00D00 6.37b09 16 lib-97 ********************************* 0.00D 00 *********** 0.00b 00 *********** 17 Ma-99 0.00b00 8.51b04 1.62b04 0.00000 1.93b05 0.00D00 1.97b05 18 Tc-99: 3.83b21 1.08b20 1.38bl9 0.00b00 1.64bl9 5.30b21 6.401-18 19 Eu-103 8.57bO7 0.00b00 3.69bO7 0.00b00 3.27 BOB 0,00b00 1.00b10 20 Ru-106 1.97b09 0.00b00 2.49bO8 0.00b00 3.50D09 0.00D00 1.27b11 21Ag-110s 4.77b06 4.41b06 2.62b06 0.00b00 8.67b06 0.00D00 1.80b09 22 Sb-124 0.00b00 0.00b00 0.00b00 0.00 BOO 0.00b00 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00D00 0.00b00 0.00b00 0.00b00 24 fe-127a 8.38bO8 3.00bO8 1.02bO8 2.14bO8 3.40b09 0.00b00 2.81b09 25te-129s 9.33bO8 3.48 BOB 1.48 BOB 3.21bO8 3.89b09 0.00b00 4.70b09 26I-131 9.13b06 1.31bO7 7.48h06 4.28b09 2.24bO7 0.00b00 3.45b06 27 I-133 3.12b01 5.42001 1.65b01 7.96b01 9.46b01 0.00b00 4.87b01 28Cs-134 4.53bO8 1.08b09 8.81bO8 0.00b00 3.49b08 1.16bO8 1.89bO7 29 Cs-136 1.02bO7 4.04bO7 2.91bO7 0.00b00 2.25bO7 3.08b06 4.59b06 30 Cs-137 5.90 BOB 8.06bO8 5.28bO8 0.00b00 2.74 BOB 9.10bO7 1.56bO7 31 Ba-140 2.44bO7 3.06b04 1.60D06 0.00D00 1.04b04 1.75b04 5.02bO7 32 La-140 3.16b02 1.59b02 4.21b03 0.00D00 0.00b00 0.00b00 1.17bO3 33Ce-141 1.16b04 7.83b03 8.88bO2 0.00b00 3.64bO3 0.00b00 2.99b07 34 Ce-144 1.03b06 4.32b05 5.55b04 0.00D00 2.56b05 0.00b00 3.50bO8 l All nuclides (except 0 3) calculated per 00CM equation 2.3-25 F 3 calculated per ODCM equatica 2.3-30 ISES 3 2-88
EV-1 and 2 ODCM Table 2.3-11 R VALUES FOR EIAVIR VALLEY SITE y (sqseter-ares /yrperuC1/seel Pathway : Meat Age Group : Teen Nuclide Bene Liver T. Body Thyroid lidney Lung GI-LLI 1H-3 0.00D00 1.94bO2 1.94bO2 1.94bO2 1.94bO2 1.94bO2 1.94bO2 2 P-32 3.34bO3 2.07bOS 1.29bOS 0.00D00 0.00b00 0.00b00 2.80bO8 3 Cr-51 0.00b00 0.00b00 4.69bO3 2.60D03 1.03bO3 6.69b03 7.88b05 4Mn-54 0.00b00 4.95b06 9.81b05 0.00b00 1.4Sb06 0.00b00 1.01bO7 5 Fe-59 1.71bO8 4.00b08 1.54bO8 0.00b00 0.00D00 1.26 BOB 9.45D08 6 00-57 0.00b00 3.22b06 5.40b06 0.00h00 0.00b00 0.00b00 6.0lbO7 7 Co-58 0.00b00 1.09bO7 2.52b07 0.00D00 0.00b00 0.00b00 1.51 BOB 8Co-60 0.00b00 3.97bO7 8.05bO7 0.00b00 0.00b00 0.00D00 5.17D08 9Zn-65 1.79b08 6.21bO8 2.90D08 0.00b00 3.97bO8 0.00b00 2.63 BOB 10 Rb-86 0.00000 3.43bO8 1.61bOS 0.00b00 0.00b00 0.00b00 5.08bO7 11St-89 2.03bO8 0.00D00 5.83b06 0.00b00 0.00b00 0.00b00 2.42bO7 12 St-90 5.44b09 0.00D00 1.34b09 0.00b00 0.00b00 0.00b00 1.53 BOB 13 E 91 7.53b05 0.00b00 2.02b04 0.00b00 0.00b00 0.00h00 3.09 BOB h 14 Zr-95 1.18D06 3.71b05 2.55b05 0.00b00 5.45b05 0.00D00 8.56bOS 15Nb-95 1.47b06 8.17b05 4.50b05 0.00D00 7.92b05 0.00b00 3.49b09 16Nb-97 ********************************* 0. 00 b00 * * * * * * * * * *
- 0. 00b00 * * * * * * * * * *
- 17 Mo-99 0.00b00 7.03b04 1.34b04 0.00h00 1.61b05 0.00b00 1.26b05 18Tc-99: 3.00-21 0.48b21 1.10E-19 0.00b00 1.26t-19 4.71021 5.57b18 19 Ru-103 6.98bO7 0.00b00 2.98bO7 0.00D00 2.46 BOB 0.00b00 5.83b09 20 h-106 1.28b09 0.00b00 2.09bO8 0.00b00 3.19tH9 0.00D00 7.94b10 21Ag-110 3.61b06 3.42b06 2.08b06 0.00b00 6.52b06 0.00b00 9.60bO8 22 Sb-124 0,00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 24Te-127a 7.07bO8 2.51bO8 8.41bO7 1.68b08 2.87b09 0.00b00 1.76b09 25fe-120s 7.82bO8 2.90bO8 1.24 BOB 2.52 BOB 3.27b09 0.00b00 2.93b09 261-131 7.59 BOB 1.06bO7 5.71b06 3.10D09 1.83bO7 0.00b00 2.10b06 27l-133 2.61b01 4.42b01 1.35001 6.17b01 7.75E-01 0.00b00 3.34001 28 Cs-134 3.60 BOB 8.4BbOB 3.93bOS 0.00b00 2.69bO8 1.03 BOB 1.05bO7 29Cs-136 7.98b06 3.14bO7 2.11bO7 0.00D00 1.71bO7 2.69b06 2.53b06 30Cs-137 4.90 BOB 6.51 BOB 2.27bOS 0.00b00 2.22bO8 8.61bO7 9.27b06 31Ba-140 2.02bO7 2.47b04 1.30b06 0.00b00 8.38bO3 1.66b04 3.11bO7 32 La-140 2.60002 1.281-02 3.40003 0.00b00 0.00b00 0.00b00 7.33bO2 33Ce-141 9.72bO3 6.49bO3 7.46D02 0.00D00 3.06bO3 0.00D00 1.86bO7 34 Ce-144 8.72b05 3.61b05 4.68b04 0.00D00 2.15b05 0.00b00 2.19bO8 All cu lides texcept 11-3) calculated per ODCM equatica 2.3-25 F3calculatedperODCMequatico2.3-30 15FI 3 2-89
s BV-1and2ODCM fable 2.3-12 q RVALUESFORBEAVIRVALLIfSifE (sqseter-ares /yrperuCl/sec) Pathway: Meat Age Group : Child Nuclide Bone Liter T. Body Thyroid Eldney Lung GI-LLI 1H-3 0.00!+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2P-32 6.29E+09 2.94It08 2.43E+08 0.00E+00 0.00E+00 0.00E+00 1.74E+08 3Cr-51 0.00!+00 0.00E+00 7.31E+03 4.061+03 1.11E+03 7.41E+03 3.88E+05 4Mn-54 0.00E+00 5.66E+06 1.51E+06 0.00E+00 1.59t+06 0.00!+00 4.75E+06 5 Fe-59 3.04E+08 4.911+08 2.45E+08 0.00E+00 0.00!+00 1.42H+08 5.12E+08 6Co-57 0.00E+00 4.21E+06 8.52It06 0.00!+00 0.00!+00 0.00!+00 3.45E+07 7 Co-58 0.00!+00 1.28I+07 3.91E+07 0.00!+00 0.00!+00 0.00E+00 7.45E+07 8 Co-60 0.00Et00 4.72E+07 1.39E+08 0.00E+00 0.00!+00 0.00E+00 2.61E+08 9Zn-65 2.68I+08 7,15E+08 4.44E+08 0.00!t00 4.50E+08 0.00!+00 1.25E+08 10Rb-86 0.00E+00 4.87t+08 2.991+08 0.00E+00 0.00E+00 0.00!+00 3.13E+07 11Sr-89 3.85E+08 0.00E+00 1.10E+07 0.00E+00 0.00E+00 0.00!+00 1.49I+07 12Sr-90 7.03E+09 0.00E+00 - 1.781+09 0.00E+00 0.00!+00 0.00!+00 9.47t+07 13T-91 1.42E+06 0.00E+00 3.81E+04 0.00!+00 0.00E+00 0.00!+00 1.90l+0B _ 14Ir-95 2.09E+06 4.59E+05 4.09E+05 0.00!+00 6.57t+05 0.00E+00 4.79t+08 15Nb-95 2.54E+06 9.90!+05 7.07I+05 0.00E+00 9.30E+05 0.00!+00 1.83E+09 16Nb-97 sssssssssssssssssssssssssssssssss 0.00!+00sssssssssss 0.00E+00sssssssssst 17Mo-99 0.00E+00 9.75E+04 2.42E+04 0.00E+00 2.091+05 0.00!+00' 8.09E+04 18fc-99: 5.33I-21 1.05I-20 1.73E-19 0.00E+00 1.52E-19 5.31E-21 5.95E-18 19Ru-103 1.26t+08 0.00E+00 4.85I+07 0.00!+00 3.18E+08 0.00E+00 3.261+09 20Ru-106 3.12I+09 0.00E+00 3.891+08 0.00!+00 4.21E+09 0.00!+00 4.85E+10 21Ag-110s 5.991+06 4.04t+06 3.23E+06 0.00E+00 7.53E+06 0.00E+00 4.811+08 22Sb-124 0.00!+00 0.00E+00 0.00E+00 0.00!+00 0.00!+00 0.00!+00 0.00E+00 _ 23Sb-125 0.00!+00 0.00E+00 0.00l+00 0.00!+00 0.00E+00 0.00!+00 0.00E+00 24fe-127 1.33E+09 3.59I+08 1.561+08 3.191+08 3.80l+09 0.00!+00 1.0BE+09 25fe-129 1.47E+09 4.11E+08 2.29E+08 4.75E+08 4.33E+09 0.00E+00 1.80E+09 261-131 1.41E+07 1.42I+07 8.04E+06 4.681+09 2.32E+07 0.00!+00 1.26E+06 l 27I-133 4.841-01 5.99E-01 2.27E-01 1.11E+02 9.981-01 0.00!+00 2.411-01 28Cs-134 6.35t+08 1.04I+09 2.20Et0B 0.00E+00 3.23E+08 1.16t+08 5.62E+06 , 29Cs136 1.381+07 3.78t+07 2.45E+07 0.00E+00 2.01E+07 3.00!+06 1.33E+06 1 30 Cs-137 9.02E+08 8.63!+08 1.27E+0B 0.00Et00 2.81E+08 1.01E+08 5.40E+06 31Ba-140 3.72E+07 3.261+06 2.17t+06 0.00E+00 1.06t+04 1.94E+04 1.89E+07 4 32La-140 4.76E-02 1.66E-02 5.611-03 0.00!+00 0.00!+00 0.00!+00 4.63E+02 33Ce-141 1.83E+04 9.131+03 1.36!+04 0.00E+00 4.00E+03 0.00E+00 1.14E+07 34Ce-144 1.64E+06 5.15E+05 8.77t+04 0.00E+00 2.85I+05 0.00E+00 1.34E+08 Allcuelides(exceptH3)calculatedperODCMeqution2.3-25 E-3calculatedperODCMequation2.3-30 ISE!3 2-90 m
EV-1and2ODCM Table 2.3-13 EVALUESFORBEAVERYALLETSITE (sqseter-stes/yrperaCl/ rec) Pathway:CowMill AgeGroup: Adult Nuclide Bone Liver T. Body Thrrold Eidney Lung 01-LLI 1H-3 0.00E+00 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 7.63E+02 2P-32 1.45E+10 9.01E+08 5.60E+08 0.00E+00 0.00E+00 0.00E+00 1.63E+09 3Cr-51 0.00E+00 0.00E+00 2.38E+04 1.42E+04 5.24E+03 3.15E+04 5.98E+06 4Mn-54 0.00E+00 5.95E+06 1.13E+06 0.00E+00 1.77E+06 0.00E+00 - 1.82E+07 5 Fe 59 2.40bO7 5.63b07 2.16bO7 ' O.00D00 0.00D00 1.57bO7 1.BBD08 : 600-57 0.00E+00 9.10!+05 1.51E+06 0.00E+00 0.00E+00 0.00E+00 2.31E+07 7 00-58 0.00E+00 3.67b06 8.22b06 0.00b00 0.00b00 0.00b00 7.43bO7-8 Co-60 0.00E+00 1.12bO7 2.46E+07 0.00b00 0.00b00 0.00b00 2.10bO8, 9 Zn-65 9.80bO8 3.12b09 1.41b09 0.00E+00 2.09b09 0.00b00 1.96b09 10 Rb-66 0.00b00 2.19b09 1.02b09 0.00D00 0.00b00 0.00b00 4.32E+08 11 Sr-89 1.16b09 0.00D00 3.33bO7 0.00E+00 0.00b00 0.00000 1.86 BOB 12St-90 3.16b10 '0.00b00 7.76b09 0.00b00 0.00b00 0.00b00 9.14bO8 13Y-91 6.7BbO3 0.00!+00 1.81bO2 0.00b00 0.00D00 0.00D00 3.73b06. ) 142r-95 7.40bO2 2.37bO2 1.61bO2 0.00b00 3.72002 0.00D00 7.52b05 15Nb-95 6.77b04 3.77b04 2.03E+04 0.00b00 3.72E+04 0.00b00 2.29b08 ' . 16 Nb-97 2.81E-12 7.11b13 2.60E-13 0.00b00 B.30E-13 0.00b00 2.62b09 17 Mo-99 0.00b00 2.11bO7 4.0lb06 0.00b00. 4.77bO7 0.00b00 4.88bO7 18Te-99: 2.83h00 7.99b00 1.02E+02 0.00 D00 1.21bO2 3.91b00 4.73bO3 19Eu-103 8.29bO2 0.00b00 3.57bO2 0.00b00 3.16bO3 0.00b00- 9.68h04 20 En-106 1.43b04 0.00b00 1.81bO3 0.00b00 2.77b04 0.00h00 9.27b05 21Ag-110s 4.16bO7 3.84bO7 2.28bO7 0.00b00 7.56bO7 0.00b00 1.57b10 22 Sb-124 0.00b00 0.00b00 0.00h00 0.00b00 0.00D00 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 - 0.00b 00- 0.00b00 24fe-127s- 3.44bO7 1.23bO7 4.19E+06 8.79b06 1.40 BOB 0.00b00 1.15bOS 25fe-129s 4.95bO7 1.85bO7 7.84b06 1.70bO7 2.07bO8 0.00D00 2.49bO8 261-131 2.52 BOB 3.60bO8 2.06 BOB 1.18b11 6.17108 0.00b00 9.50bO7 27l-133 3.29b06 5.72b06 1.75b06 8.41 BOB 9.99b06 0.00b00 5.14b06 28Cs-134 3.B9b09 9.27b09 7.58b 09. 0.00D00 3.00D09 9.96bO8 1.62 BOB 29Cs-136 2.23 BOB 8.82bO8 6.35 BOB 0.00b00 - 4.91bOS 6.73D07 1.00bOS 30Cs-137 4.99b09 6.82b09 4.47b09 0.00b00 2.32b09 7.70 BOB 1.32bO8 31Ba-140 2.28bO7 2.87b04 1.49b06 0.00b00 9.74bO3 1.64b04 4.70bO7 - 32 La 140 3.84b00 1.93b00 5.11E-01 0.00b00 0.00b00 0.00b00 1.42b05 33Ce-141 3.99bO3 2.70bO3 3.06bO2 0.00b00 1.25bO3 0.00b00 1.03b07 34Ce-144 2.54b05 1.06b05 1.36b04 0.00D00 6.29b04 0.00b00 8.5BbO7 - . l Allnuclides(exceptH-3)esiculatedperODCMequation2.3-24 H-3calculatedperODCHequation2.3-28 ISSUE 3 , l 2-91
EV-1 and 2 ODCM fable 2.3-14 E VALUES FOR EEAVER VALLEY SITE (egseter-stes/yrperuCi/see) Patbvay:CowMilk AgeGroup: Teen Nuclide Bone Liver f. Body ' Thyroid tidney Lung GI-LLI 1 F3 0.00D00 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 9.94bO2 2P-32 2.67b10 1.66b09 1.04b09 0.00b00 0.00b00 0.00b00 2.25b09 3Cr-51 0.00b00 0.00b00 4.15b04 2.31b04 9.10bO3 5.93b04 6.97b06 4Mn-54 0.00b00 9.91E+06 1.96b06 0.00b00 2.95 BOB 0.00b00 2.03bO7 5 Fe-59 4.18bO7 9.76bO7 3.77bO7 0.00b00 0.00b00 3.0BbO7 2.31 BOB 6.00-57 0.00b00 1.60b06 2.68b06 0.00b00 0.00000 0.00b00 2.98bO7 700-58 0.00b00 6.17b06 1.42bO7 0.00b00 0.00h00 0.00b00 8.51bO7 800-60 0.00h00 1.89bO7 4.26bO7 0.00D00 0.00l+00 0.00 BOO 2.46bO8 9 Zn-65 1.51b09 5.23b09 2.44b09 0.00b00 3.34b09 0.00b00 2.21b09 10Eb-86 0.00b00 3.99b09 1.87b09 0.00D00 0.00b00 0.00b00 5.91b06 j i 11St-89 2.14b09 0.00b00 6.12bO7 0.00b00 0.00b00 0.00D00 2.55 BOB 1 12Sr-90 4.47b10 0.00b00 1.10b10 0.00D00 0.00D00 0.00b00 1.25b09 ; 13 E 91 1.25b04 0.00tt00 3.35bO2 0.00 BOO 0.00!+00 0.00D00 5.11b06 14Zr-95 1.29bO3 4.08bO2 2.81bO2 0.00D00 6.00bO2 0.00D00 9.42D05 15Nb-95 1.16b05 6.41b04 3.53b04 0.00D00 6.21b04 0.00 BOO 2.74 BOB 16Nb-97 5.131-12 1.271-12 4.65b13 0.00b00 1.49b12 0.00b00 3.04b08 17Mo-99 0.00b00 3.80bO7 7.25b06 0.00b00 8.70bO7 0.00D00 6.81bO7 18fc-99: 4.90D00 1.37b01 1.77bO2 0.00D00 2.04bO2 7.59b00 S.9BbO3 i 19Ra-103 1.47bO3 0.00b00 6.30bO2 0.00b00 5.20bO3 0.00D00 1.23b05 20 Ru-106 2.03h04 0.00h00 3.32bO3 0.00D00 5.0Bb04 0.00 BOO 1.26b06 4 i 21Ag-110s 6.87bO7 6.50bO7 3.950 0.00 BOO 1.24bO8 0.00D00 1.83b10 22 Sb-124 0.00h00 0.00b00 0.00bt 00 BOO 0.00b00 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 1b00 0.00b00 0.00b00 0.00 BOO 24fe-127: 6.34bO7 2.25bO7 7.54b06 t ,1bu7 2.57bO8 0.00b00 1.5BbOB 25 fe-129s 9.06bO7 3.36bO7 1.43bO7 2.92007 3.79E+0B 0.00b00 3.40 BOB 261-131 4.57 BOB 6.39bOS 3.43bOS 1.87b11 1.10b09 0.00D00 1.26 BOB 27I-133 6.0lb06 1.02bO7 3.11b06 1.42b09 1.79bO7 0.00h00 7.71b06 28Cs-134 6.76b09 1.59b10 7.3Bb09 0.00D00 5.06b09 1.93b09 1.98 BOB 29Cs136 3.80bO8 1.50b09 1.0lb09 0.00D00 8.15bO8 1.28 BOB 1.20b06 30Cs-137 9.05b09 1.20b10 4.19b09 0.00b00 4.10b09 1.59b09 1.71bO8 31 Ba 140 4.12bO7 5.05b04 2.65b06 0.00D00 1.71b04 3.39b04 6.35bO7 32La-140 6.89b00 3.39b00 9.01b01 0.00b00 0.00b00 0.00b00 1.94b05 33Ce-141 7.32bO3 4.89bO3 5.62bO2 0.00b00 2.30bO3 0.00b00 1.40bO7 34Ce-144 4.67b05 1.93b05 2.51b04 0.00D00 1.15b05 0.00b00 1.17bO8 All cuelides (except 0 3) calculated per ODCM equation 2.3-24 F 3 enleviated per ODCM equation 2.3-28 ISKE 3 ) 2-92
I EV-1 and 2 DDCM Table 2.3-15 R VALUIS FOR EEAVER VALLEY SITI (sqseter-ares /yrperuCi/sec) Pattvar : Cow Milk Age Group : Child helide Bone Liver T. Body Thyroid Eidney Lung GI-LLI 1H-3 0.00E+00 1.57t+03 1.57E+03 1.571+03 1.57E+03 1.57I+03 1.57t+03 2P-32 6.59I+10 3.09E+09 2.54E+09 0.00E+00 0.00E+00 0.00!+00 1.82E+09 3Cr-51 0.00E+00 0.00E+00 8.46E+04 4.70E+04 1.28E+04 8.5BI+04 4.498+06 4No-54 0.00E+00 1.48I+07 3.95E+06 0.00E+00 4.161+06 0.00E+00 1.24E+07 5 Fe-59 9.70I+07 1.57E+08 7.82E+07 0.00!+00 0.00!+00 4.55E+07 1.63E+0B 6 Co-57 0.00E+00 2.73E+06 5.52E+06 0.00E+00 0.00E+00 0.00!+00 2.24E+07 7 00-58 0.00E+00 9.43E+08 2.891+07 0.00E+00 0.00l+00 0.00!+00 5.50!+07
~
8 Co-60 0.00E+00 2.94E+07 8.671+07 0.00E+00 0.00I+00 0.00E+00 1.63E+0B 9 Zn-65 2.95I+09 7.87t+09 4.89E+09 0.00!+00 4.96I+09 0.00!+00 1.38E+09 10 Rb-86 0.00E+00 7.40E+09 4.55I+09 0.00E+00 0.00E+00 0.00E+00 4.76I+08 11St-89 5.29E+09 0.00!+00 1.51E+08 0.00!+00 0.00!+00 0.00E+00 2.05E+0B 12 St-90 7.55E+10 0.00E+00 1.91E+10 0.00E+00 0.00!+00 0.00!+00 1.02E+09 13 Y-91 3.081+04 0.00E+00 8.24E+02 0.00l+00 0.00E+00 0.00!+00 4.11E+06 h 14Zr-95 3.00!+03 6.60!+02 5.88I+02 0.00l+00 9.45E+02 0.00!+00 6.891+05 15Nb-95 2.61E+05 1.02E+05 7.26E+04 0.00E+00 9.54E+04 0.00E+00 1.58E+08 16Nb-97 1.25E-11 2.25E-12 1.051-12 0.00E+00 2.50E-12 0.00E+00 6.948-07 17 Mo-99 0.00E+00 6.92E+07 1.71E+07 0.00E+00 1.4BE+08 0.00E+00 5.72E+07 18 te-99: 1.12It01 2.20!+01 3.65E+02 0.00E+00 3.20E+02 1.12E+01 1.25E+04 19 h-103 3.491+03 0.00!+00 1.34E+03 0.00E+00 8.781+03 0.00!+00 9.01E+04 20 h-106 6.4SE+04 0.00!+00 8.10E+03 0.00E+00 8.76I+04 0.00!+00 1.0lI+06 21Ag-110s 1.49E+08 1.01E+08 8.05E+07 0.00E+00 1.87t+08 0.00E+00 1.20E+10 22 Sb-124 0.00E+00 0.00!+00 0.00E+00 0.00E+00 0.00!+00 0.00!+00 0.00!+00 23Sb-125 0.00E+00 0.00!+00 0.00E+00 0.00!+00 0.00!+00 0.00E+00 0.00!+00 24 fe-127a 1.56t+08 4.21E+07 1.86E+07 3.74E+07 4.46I+0S 0.00E+00 1.271+08 25fe-129s 2.23I+08 6.24E+07 3.47t+07 7.2CE+07 6.56I+08 0.00E+00 2.72I+08 26 I-131 1.11I+09 1.111+09 6.33I+08 3.681+11 1.83E+09 0.00E+00 9.92E+07 27I-133 1.46E+07 1.81E+07 6.83E+06 3.36I+09 3.01E+07 0.00E+00 7.28E+06 28Cs-134 1.56E+10 2.561+10 5.40E+09 0.00E+00 7.93E+09 2.851+09 1.381+08 29Cs-138 8.581+08 2.3EI+09 1.53E+09 0.00E+00 1.26!+09 1.871+08 8.29E+07 30 Cs-137 2.18tt10 2.091+10 3.08I+09 0.00E+00 6.80E+09 2.45E+09 1.31E+08 31 Ba-140 9.94E+07 8.71E+06 5.80E+06 0.00E+00 2.84I+04 5.191+04 5.04I+07 32 La-140 1.65E+01 5.77E+00 1.94E+00 0.00!+00 0.00E+00 0.00!+00 1.61E+05 33 Ce-141 1.80E+04 8.99I+03 1.34E+04 0.00E+00 3.94E+03 0.00E+00 1.12E+07 34Ce-144 1.151+06 3.61E+05 6.15E+04 0.00E+00 2.00E+05 0.00E+00 9.41E+07 B AllnuclidesIuceptH-3)calculatedperODCMequation2.3-24 H-3calculatedperODCMequation2.3-28 ISSUE 3 2-93
EV-1and2ODCH fable 2.3-16 BVALUISFORBEAVIHVALLEYSITE (sqseter-tres/yrperuCi/sec) Pathway:CowMilk j AgeGroup: infant Nuclide Bone Liver T. Body Thyroid Eidney Lung GI-LLI 1 F3 0.00D00 2.36bO3 2.38bO3 2.36bO3 2.3BbO3 2.38bO3 2.38bO3 2P-32 1.36b11 7.99b09 5.27b09 0.00b00 0.00b00 0.00b00 1.84b09 3 Cr-51 0.00b00 0.00bn0 1.34b05 8.75b04 1.91b04 1.70b05 3.91b06 { 4 Mn-54 0.00b00 2.76bO7 6.25b06 0.00b00 6.11b06 0.00 BOO 1.01bO7 i 5 Fe-59 1.81 BOB 3.16b08 1.25 BOB 0.00D00 0.00b00 9.35bO7 1.51 BOB 6 Co-57 0.00b00 6.3Eb06 1.03bO7 0.00b00 0.00 BOO 0.00D00 2.17bO7 l 7 00-58 0.00D00 1.89bO7 4.70bO7 0.00b00 0.00b00 0.00h00 4.70bO7 8 00-60 0.00b00 6.00bO7 1.42b08 0.00b00 0.00b00 0.00b00 1.43 BOB 9Zn-65 3.97b09 1.36b10 6.27b09 0.00b00 6.60b09 0.00b00 1.15b10 10 Rb-86 0.00b00 1.88b10 9.28b09 0.00b00 0.00D 00 'O.00D 00 4.81b08 11Sr-89 1.0lb10 0.00b00 2.89bO8 0.00b00 0.00D00 0.00b00 2.07bO8 12 Sr-90 8.22b10 0.00 BOO 2.09b10 0.00b00 0.00b00 0.00b00 1.03b09 13 Y-91 5.79b04 0.00D00 1.54bO3 0.00b00 0.00b00 0.00b00 4.15b06 14 Zr-95 5.33D03 1.30bO3 9.22bO2 0.00b00 1.40bO3 0.00b00 6.47b05 15Nb-95 4.87b05 2.0lb05 1.16b05 0.00b00 1.44b05 0.00b00 1.69b08 l 16 lib-97 2.63E-11 5.62b12 2.03b12 0.00b00 4.39b12 0.00 BOO 1.77b06 l 17 Mo-99 0.00b00 1.77bO8 3.45bO7 0.00b00 2.64bO8 0.00b00 5.83b07 18 Te-99: 2.34b01 4.82b01 6.21bO2 0.00D00 5.19b02 2.52b01 1.40D04 19Ra-103 7.06bO3 0.00b00 2.36bO3 0.00D00 1.47b04 0.00b00 8.59b04 20fu-106 1.34b05 0.00b00 1.67b04 0.00h00 1.58b05 0.00b00 1.0lb06 - 21Ag-110s 2.75bO8 2.01bO8 1.33 BOB 0.00b00 2.88bO8 0.00b00 1.04b10 22Sb-124 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 l 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00F00 0.00b00 l 24Te-127: 3.16bO8 1.05 BOB 3.83b07 9.14bO7 7.79b08 0.00b00_ .1.28bO8 25fe-129: 4.58 BOB 1.57 BOB 7.06bO7 1.76bO8 1.15b09 0.00D00 2.74 BOB 26 F131 2.31b09 2.72b09 1.20b09 8.95b11 3.18b09 0.00D00 9.72b37 27I-133 3.08bO7 4.49bO7 1.31bO7 8.17b09 5.28bO7 0.00b00 7.60D06 28Cs-134 2.51b10 4.69b10 4.73b09 0.00 BOO 1.21b10 4.95b09 1.27bO8 29Cs-136 1.68b09 4.93b09 1.84b09 0.00b00 1.97b09 4.02bO8 7.49bO7 30 Cs-137 3.48bl0 4.07b10 2.89b09 0.00b00 1.09b10 4.43D09 1.27 BOB 31 Ba-140 2.05bO8 2.05b05 1.05bO7 0.00b00 4.86b04 1.26b05 5.02bO7 32 La-140 3.45b01 1.36b01 3.50b00 0.00b00 0.00b00 0.00b00 1.60b05 3.57b04 2.18b04 2.57bO3 0.00b00 6.72bO3 0.00b00 1.13bO7 33 Ce-141 34 Ce-144 1.65b06 6.75b05 9.25b04 0.00b00 2.73b05 0.00000 9.47bO7 All nuclides tercept 11-3) calculated per ODCM equation 2.3-24 11-3calculatedperODCMequation2.3-28 15EE 3 2-94
EV-1 and 2 ODCM Table 2.3-17 RVALUESFOREIAVERVALLEYSITE (sqseter-sres/yrperuCi/aec) Pathway:GoatMilk Age Grcup : Adult i Nuclide Bone Liver f. Body thyroid tidney Lung GI-LLI 1 b3 0.00 BOO 1.56bO3 1.56bO3 1.56bO3 1.56bO3 1.56bO3 1.56bO3 l 2P-32 1.74b10 1.08b09 6.72 BOB 0.00b00 0.00 h 00 ' O.00 b00 1.96b09 3Cr-51 0.00b00 0.00b00 2.85bO3 1.70D03 6.28bO2 3.78bO3 7.17b05 4 Mc-54 0.00b00 7.14b05 1.36h05 0.00b00 2.12b05 0.00h00 2.19006 1 5 Fe-59 3.12005 7.32b05 2.81h05 0.00000 0.00D00 2.05b05 2.44b06 -{ 600-57 0.00b00 1.09b05 1.82b05 0.00b00 0.00E+00 0.00 b 00 2.77b06 7 Co-58 0.00h00 4.40b05 9.86b05 0.00b00. 0.00b00 0.pb00 8.91D06 , B Co-60 0.00b00 1.34b06 2.96b06 0.00b00 0.00000 0.00t+00 2.52bO7 ! 9Zn-65 1.16bO8 3.74 BOB 1.69 BOB 0.00b00 2.50 BOB 0.00 D 00 2.36bO8 10Rb-B6 0.00b00 2.63 BOB 1.22 BOB 0.00b00 0.00 D 00 0.00 BOO 5.18bO7 11Sr-89 2.43b09 0.00b00 6.99bO7 0.00b00 0.00b00 0.00b00 3.91bO8 12 St-90 6.64b10 0.00b00 1.63b10 0.00 BOO 0.00h00 0.00b00 1.92b09- j 13T-91 8.14bO2 0.00bM 2.16b01 0.00D00 0.00b00 0.00b00 4.4Bb05 ; D 14Zr-95 15Nb-95 8.87b01 2.B5b01 1.93b01 0.00b00 4.47001 0.00b00 9.02b04 8.13bO3 4.52bO3 2.43bO3 0.00b00 4.47bO3 0.00b00 2.74bO7 1 16 Nb-97 3.38b13 8.54E-14 3.121-14 0.00h00 9.961-14 0.00b00 3.15E-10 17 Mo-99 0.00b00 2.53b06 4.81b05 0.00b00 5.72b06 0.00b00 5.86b06 , 18fe-99: 3.39b01 9.59001 1.22b01 0.00b00 1.46D01 4.70b01 5.67bO2 I 19Ru-103 9.95b01 0.00b00 4.29b01 0.00b00 3.80bO2 0.00b00 1.16b04 20En-106 1.72bO3 0.00b00 2.1BbO2 0.00000 3.32bO3 0.00b00 1.11b05 21 Ag-110s 4.99b06 4.61b06 2.74b06 0.00b00 9.07b06 0.00b(0 1.88b09 22 Sb-124 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 - 1' 23Sb-125 0.00 BOO 0.00 BOO 0.00b00 0.00t+00 0.00b00 0.00b00 0.00b00 24fe-127s 4.13b06 1.48b06 5.03b05 1.05b06 1.68bO7 0.00b00 1.38bO7 25fe-129s 5.94b06 2.22b06 9.41b05 2.04b06 2.48bO7 0.00b00 2.99bO7 261-131 3.02bO8 4.32b08 2.48bO8 1.42b11 7.40bO8 0.00b00 1.14 BOB 271-133 3.95b06 6.87b06 2.09b06 1.01b09 1.20bO7 0.00 b 00 -6.17b06-28 Cn-134 4.67 BOB 1.11b09 9.09 BOB 0.00b00 3.60 BOB 1.19b08 1.95bO7 29Cs-136 6.70 BOB 2.65b09 1.90b09 0.00b00 1.47b09 2.02 b O8' 3.0lb OB 30Ce-137 1.50b10 2.05b10 1.34b10 0.00b00 6.95b09 2.31b09 3.96 BOB 31 Ba-140 2.74b06 3.44bO3 1.79b05 0.00b00 1.17bO3 1.97bO3 5.64b06 32 La-140 4.60E-01 2.32001 6.13bO2 0.00b00 0.00000 0.00b00 1.70b04 33 Ce-141 4.79bO2 3.24bO2 3.6Bb01 0.00b00 1.51bO2 0.00b00 1.24bOS 34 Ce-144 3.05b04 1.27b04 1.64bO3 0.00b00 7.55bO3 0.00D00 1.03bO7 All nuclides (except b 3) calculated per ODCM egn tion 2.3-24 H-3 calculated per ODCM equation 2.3-28 IEE: 2-95
EV-1 and 2 ODCM fable 2.3-18 RVALUESFOREEAVIRVALLEYSITE (sq seter-sres/yr per uCihec) Pathway:GoatMill Age Group : Teen Nuclide Bone Liver f. Body thyroid Kidney Long GI-LLI 1 H-3 0.00i+00 2.03b03 2.03bO3 2.03bO3 2.03bO3 2.03bO3 2.03bO3 2 P-32 3.21b10 1.99b09 1.24b09 0.00b00 0.00D00 0.00000 2.70D09 3Cr-51 0.00b00 0.00b00 4.9BbO3 2.17bO3 1.09b03 7.11bO3 8.37b05 4 Hn-54 0.00D00 1.19b06 2.36D05 0.00D00 3.55b05 0.00D00 2.44b06 5 Fe-59 5.44b05 1.27b06 4.90b05 0.00b00 0.00b00 4.00 D 05 -3.00 b 06 6 Co-57 0.00 BOO 1.92b05 3.21b05 0.00h00 0.00b00 0.00b00 3.57b06 7 Co-58 0.00b00 7.40D05 1.71b06 0.00D00 0.00D00 0.00D00. 1.02bO7 8 00-60 0.00D00 2.27b06 5.11b06 0.00b00 0.00b00 0.00D00 2.96bO7 9Zn-65 1.81 BOB 6.27bO8 2.93 BOB 0.00b00 4.01b 08 0.00b 00 2.66bO8 10 Rb-86 0.00b00 4.79b0B 2.25bO8 0.00b00 0.0Jb00 0.00D00 7.09bO7 11 St-89 4.49h09 0.00h00 1.29b08 0.00b00 0.00b00 0.00b00 5.35bO8 12 Sr-90 9.39b10 0.00D00 2.32b10 0.00D00 0.00b00 0.00b00 2.64b09 13Y-91 1.50bO3 0.00D00 4.0lb01 0.00b00 0.00b00 0.00b00 6.14b05 m IIZr-95 1.55bO2 4.90D01 3.37b01 0.00h00 7.19b01 0.00b00 1.13b05 .g 15 Nb-95 1.39b04 7.69b03 4.23bO3 0.00b00 7.45bO3 0.00b00 3.29bO7 16 Nb-97 6.15E-13 1.53E-13 5.57b14 0.00b00 1.79E-13 0.00D00 3.65E-09 17 Mo-99 0.00b00 4.56b06 8.70b05 0.00b00 1.04bO7 0.00b00 8.17b06 18fc-99: 5.88001 1.64b00 2.13b01 0.00b00 2.45b01 9.11E-01 1.08bO3 19 Ru-103 1.77bO2 0.00b00 7.56b01 0.00b00 6.24bO2 0.00b00 1.48b04 20 Ra-106 2.44bO3 0.00b00 3.98bO2 0.00b00 6.10bO3 0.00b00 1.52b05 21Ag-110s 8.24b06 7.80b06 4.75b06 0.00b00 1.49bO7 0.00h00 2.19b09 22 Sb-124 0.00b00 0.00b00 0.00 b OO 0.00 BOO 0.00D00 0.00b00 0.00b00 23Sb-125 0.00000 0.00D00 0.00D00 0.00D00 0.00b00 0.00b00 0.00b00 24 fe-127s 7.61b06 2.70b06 9.05b05 1.81b06 3.08bO7 0.00b00 1.90bO7 25fe-129s 1.09bO7 4.03b06 1.72b06 3.51b06 4.55bO7 0.00b00 4.08bO7 26I-131 5.48 BOB 7.67 BOB 4.12bO8 2.24b11 1.32h09 0.00b00 1.52 BOB . 27 F133 7.21b06- 1.22bO7 3.73b06 1.71b09 2.15bO7 0.00b00 9.26b06 28 Cs-134 8.11b08 1.91b09 8.86bO8 0.00b00 6.07bO8 2.32bO8 2.38bO7 29Cs-136 1.14b09 4.49b09 3.02b09 0.00b00 2.44b09 3.85 BOB 3.61bO8 30 Ce-137 2.71b10 3.61D10 1.26b10 0.00b00 1.23b10 4.77b09 5.14b00 31 Ba-140 4.94b06 6.06bO3 3.18b05 0.00b00 2.05bO3 4.07bO3 7.62b06 32 La-140 8.27001 4.06b01 1.08b01 0.00b00 0.00b00 0.00h00 2.33b04 33Ce-141 8.79b02 5.87bO2 6.74b01 0.00b00 2.76bO2 0.00b00 1.68b06 34 Ce-144 5.60b04 2.32b04 3.0lbO3 0.00b00 1.39b04 0.00h00 1.41bO7 Allnuclides(exceptH-3)calculatedperODCHequation2.3-24 H-3calculatedperODCMequation2.3-28 IS5UE 3-2-96 4
I B7-1 and 2 ODCM Table 2.3-19 R VALDIS FOR EEAVER VALLEY SITE (sqseter-stes/yrperuCi/ree) Pattvir : Goat Milk Age Group : Child Wuclide Bone Liver T. Body Thyroid Eidney Lung GI-LL1 1 H-3 0.00b00 3.20bO3 3.20bO3 3.20bO3 3.20bO3 3.20bO3 3.20bO3 2 P-32 7.91b10 3.70b09 3.05b09 0.00b00 0.00b00 0.00h00 2.19b09 3 Cr-51 0.00b00 0.00b00 1.02b04 5.64bO3 1.54bO3 1.03b04 5.39b05 4 Mn-54 0.00b00 1.78b06 4.74b05 0.00b00 4.99b05 0.00b00 1.49b06 5 Fe-59 1.26b06 2.04b06 1.02b06 0.00D00 0.00b00 5.91D05 2.12b06 600-57 0.00b00 3.27h05 6.63b05 0.00b00 0.00b00 0.00b00 2.68b06 7 Co-58 0.00b00 1.13b06 3.46b06 0.00b00 0.00D00 0.00 BOO 6.60b06 8 Co-60 0.00b00 3.53b06 1.04bO7 0.00b00 0.00D00 0.00b00 1.95bO7 9Zn-65 3.54b08 9.44 BOB 5.87bOS 0.00b00 5.95bO8 0.00b00 1.66bO8 10 Eb-86 0.00D00 8.88bO8 5.46bO8 0.00b00 0.00b00 0.00b00 5.71bO7 11Sr-89 1.11b10 0.00b00 3.!7 BOB 0.00b00 0.00b00 0.v0b00 4.30bO8 12 St-90 1.59b11 0.00b00 4.02b10 0.00D00 0.00b00 0.00D00 2.14b09 13 Y-91 3.70bO3 0.00b00 9.89b01 0.00b00 0.00b00 0.00b00 4.93b05 14Zr-95 3.60bO2 7.92b01 7.05b01 0.00000 1.13b02 0.00b00 8.27b04 15Nb-95 3.13b04 1.22b04 8.71bO3 0.00b00 1.14b04 0.00b00 2.25bO7 16 Nb-97 1.49b12 2.70F13 1.26b13 0.00b00 2.99b13 0.00b00 B.33bO8 17 Mo-99 0.00b00 8.30D06 2.05b06 0.00b00 1.77bO7 0.00b00 6.87b06 18fe-99: 1.35b00 2.65b00 4.39b01 0.00D00 3.B4b01 1.34b00 1.51bO3 19Ru-103 4.18bO2 0.00b00 1.61002 0.00b00 1.05bO3 0.00000 1.0Bb04 20 Eu-106 7.79bO3 0.00D00 9.72bO2 0.00h00 1.05b04 0.00b00 1.21b05 21Ag-110s 1.79bO7 1.21bO7 9.65b06 0.00b00 2.25bO7 0.00000 1.44b09 22Sh-124 0.00 BOO 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 23Sb-125 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 0.00b00 24fe-127s 1.88bO7 5.05b06 2.23b06 4.48b06 5.35bO7 0.00h00 1.52bO7 25 fe-129 2.6BbO7 7.4Bb06 4.16b06 8.64b06 7.67bO7 0.00b00 3.27bO7 26I-131 1.33b09 1.34b09 7.60 BOB 4.42b11 2.19b09 0.00b00 1.19b08 27I-133 1.75bO7 2.17bO7 8.20b06 4.03b09 3.61bO7 0.00b00 8.73b06 28 Cs-134 1.87b09 3.07b09 6.48bO8 0.00 BOO 9.52bO8 3.42 BOB 1.66bO7 29 Ce-136 2.56b09 7.08b09 4,5Bb09 0.00b00 3.77b09 5.62bO8 2.49 BOB 30Cs-137 6.54b10 6.26b10 9.24b09 0.00b00 2.04b10 7.34b09 3.92 BOB 31 Ba-140 1.19bO7 1.05b06 6.96h05 0.00b00 3.40bO3 6.23bO3 6.04b06 32 La-140 1.98b00 6.921-01 2.33E-01 0.00b00 0.00b00 0.00b00 1.93b04 33 Ce-141 2.16bO3 1.0BbO3 1.60003 0.00b00 4.73bO2 0.00b00 1.35b06 34 Ce-144 1.38b05 4.33b04 7.37bO3 0.00b00 2.40b04 0.00D00 1.13bO7 All nuclides (except b3) calculated per ODCM equation 2.3-24 H-3calculatedperODCMequation2.3-28 1550! 3 2-97
BV-1and2ODCM fable 2.3-20 RVALUESFORBEAVIRVALLIISlft (sqseter-stes/yrperuCi/sec) Pathway:GoatMilk AgeGroup: Infant Nuclide Bone Liver f. Body Thyroid Eidney lung GI-LLI 1H-3 0.00t+00 4.86E+03 4.861+03 4.86t+03 4.86I+03 4.861+03 4.86t+03 2P-32 1.63E+11 9.59E+09 6.32t+09 0.00t+00 0.00!+00 0.00E+00 2.211+09 3Cr-51 0.00!+00 0.00E+00 1.61t+04 1.05E+04 2.29E+03 2.04E+04 4.691+05 4Ma-54 0.00E+00 3.31E+06 7.50!+05 0.00E+00 7.33I+05 0.00E+00 1.21t+06
$ Fe-59 2.35E+06 4.11t+06 1.62E+06 0.00!+00 0.00!+00 1.21t+06 1.961+06 6Co-57 0.00t+00 7.64I+05 1.24E+06 0.00t+00 0.00l+00 0.00!+00 2.60E+06 7 Co-58 0.00E+00 2.26t+06 5.64t+06 0.00E+00 0.00E+00 0.00!+00 5.64E+06 8 Co-60
~
0.00E+00 7.20!+06 1.70!+07 0.00l+00 0.00l+00 0.00!+00 1.711+0i 9Zn-65 4.761+08 1.631+09 7.53E+08 0.00E+00 7.92!t08 0.00!+00 1.38E+09 10Eb-86 0.00t+00 2.25t+09 1.11E+09 0.00E+00 0.00!+00 0.00!+00 5.77I+07 11St-89 2.11t+10 0.00!+00 6.061+08 0.00t+00 0.00!+00 0.00!+00 4.34t+08 12 Sr-90 1.73E+11 0.00!+00 4.39I+10 0.00E+00 0.00!+00 0.00t+00 2.16E+09 13 Y-91 6.94E+03 0.00!+00 1,851+02 0.00!+00 0.00!+00 0.00!+00 4.98t+05 14Zr-95 6.40E+02 1.56IK2 1.11E+02 0.00E+00 1.68t+02 0.00E+00 7.77E+04-15Nb-95 5.84E+04 2.41E+04 1.39t+04 0.00!+00 1.72E+04 0.00E+00 2.03E+07 16Nb-97 3.161-12 6.74t-13 2.43I-13 0.00!+00 5.271-13 0.00!+00 2.13E-07 17Mo-99 0.00!+00 2.12t+07 4.14E+06 0.00!+00 3.17t+07 0.00E+00 6.991+06 18fe-99: 2.81E+00 5.79t+00 7.461+01 0.00E+00 6.23t+01 3.03E+00 1.681+03 19 Ru 103 8.471+02 0.00E+00 2.83E+02 0.00E+00 1.76t+03 0.0rI+00 1.03It04 20 Ro-106 1.60!+04 0.00t+00 2.00!+03 0.00t+00 1.90!+04 0.00!+00 1.22E+05 21Ag-110 3.30!+07 2.41E+07 1.60t+07 0.00!+00 3.45E+07 0.00!+00 1.25E+09 22Sb-124 0.00t+00 0.00E+00 0.00It00 0.00!+00 0.00!+00 0.00t+00 0.00E+00 23Sb-125 0.00!+00 0.00!+00 0.00l+00 0.00t+00 0.00t+00 0.00E+00 0.00!+00 24fe-127: 3.80!+07 1.26I+07 4.591+06 1.10E+07 9.35t+07 0.00E+00 1.53Et07 25fe-129s 5.50t+07 1.891+07 8.47t+06 2.11E+07 1.381t08 0.00!+00 3.281+07 26I-131 2.77tt09 3.27t+09 1.44t+09 1.07t+12 3.82E+09 0.00!+00 1.17E+08 27I-133 3.70t+07 5.39I+07 1.581+07 9.80!+09 6.34f+07 0.00!+00 9.12E+06 28Cs-134 3.02t+09 5.62t+09 5.681+08 0.00!+00 1.45t+09 5.93t+08 1.53E+07 29Cs-136 5.03I+09 1.48t+10 5.52t+09 0.00t+00 5.90!+09 1.21E+09 2.25t+08 30Cs-137 1.04E+11 1.22t+11 8.66t+09 0.00t+00 3.28E+10 1.33t+10 3.82t+08 31Ba-140 2.45E+07 2.45t+04 1.26t+06 0.00!+00 5.83E+03 1.51t+04 6.03I+06 32La-140 4.14t+00 1.63I+00 4.19I-01 0.00!+00 0.00E+00 0.00!+00 1.92t+04 33Ce-141 4.29E+03 2.62t+03 3.08!+02 0.00E+00 8.075+02 0.00!+00 1.35E+06 34 Ce 144 1.9BI+05 8.11t+04 1.11E+04 0.00E+00 3.28t+04 0.00t+00 1.14E+07 Allnuclides(exceptH-3)calculatedperODCMequation2.3-24 H-3calculatedperODCMequation2.3-28 ISSUE 3 2-98
BV-1 and 2 ODC2i TABLE 2.3-21 BV-1 AND 2 PROCESS VEtC DISPERSION PAFA'iETCRS (D/Q) FOR CCXCINUOUS ELEVATED RELEASES >500 HRS /YR OR >150 HRS /QTR (meters ~ ) DISTANCES 'IO 'IIIE Ct2RROL 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 6.00E-10 8.60E-09 3.14E-09 1.76E-09 8.12E-10 5.70E-10 4.24E-10 3.29E-10 2.63E-10 2.15E-10 NNE 6.66E-10 5.64E-09 1.98E-09 2.55E-09 1.33E-09 1.07E-09 6.75E-10 5.23E-10 4.56E-10 3.74E-10 NE 1.03E-09 1.57E-09 1.32E-09 3.62E-09 2.63E-09 1.64E-09 1.23E-09 6.13E-10 7.85E-10 6.42E-10 ENE 1.13E-09 1.55E-09 3.69E-09 3.27E-09 2.31E-00 1.29E-09 1.21E-09 6.78E-10 6.72E-10 3.89E-10 E 1.35E-09 1.28E-08 4.09E-09 3.12E-09 1.91E-e' 1.36E-09 1.01E-09 7.83E-10 4.15E-10 5.10E-10 ESE 9.82E-10 7.85E-09 4.40E-09 2.46E-09 1.47E-09 1.03E-09 5.65E-10 5.05E-10 3.25E-10 3.00E-10 SE 2.76E-09 6.41E-09 3.52E-09 1,97E-09 1.18E-09 8.27E-10 5.68E-10 4.40E-10 2.93E-10 2.43E-10 SSE 2.22E-09 4.66E-09 3.01E-09 1.68E-09 1.02E-09 7.14E-10 4.2SE-10 3.29E-10 2.19E-10 1.80E-10 S 3.00E-09 4.81E-09 3.76E-09 2.10E-09 1.36E-09 9.52E-10 5.12E-10 3.96E-10 2.68E-10 2.20E-10 SSW 1.44E-08 2.89E-09 7.83E-10 8.84E-10 5.70E-10 4.00E-10 2.55E-10 1.98E-10 1.84E-10 1.51E-10 SW 1.89E-08 5.55E-09 1.55E-09 8.71E-10 2.61E-10 3.94E-10 1.57E-10 2.50E-10 2.54E-10 2.08E-10 WSW 1.57E-09 6.63E-09 1.36E-09 1.04E-09 5.44E-10 2.39E-10 3.84E-10 2.98E-10 2.17E-10 1.78E-10 W 3.78E-10 2.95E-09 1.84E-09 1.03E-09 6.63E-10 4.66E-10 1.37E-10 2.68E-10 1.12E-10 1.75E-10 WtM 4.54E-10 4.13E-10 3.09E-10 4.71E-10 7.35E-10 5.16E-10 1.93E-10 1.10E-10 1.12E-10 1.80E-10 4.52E-10 4.09E-10 2.86E-10 1.18E-09 7.04E-10 4.94E-10 3.37E-10 2.10E-10 2.09E-10 1.71E-10 NW NtM 3.40E-10 2.05E-09 1.63E-09 9.12E-10 5.86E-10 4.13E-10 2.79E-10 2.16E-10 1.73E-10 1.42E-10 2-99 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-22 BV-1 AND 2 CNTAItPENP VENTS DISPERSION PARAMETERS (D/Q) EUR CCNTIIAKXJS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS / VIR (meters ~ ) DISTANCES 'IU 'IIIE CCNTROL II)CATIWS, IN MILES SEC'IOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.66E-10 ENE 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 E 6.08E-08 1.05E-08 3.79E-09 2.12E-09 1.37E-09 -9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 ESE 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 SE 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 WrM 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 4.75E-10 tM 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 tam 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
.2-100 ISSUE.3 e a
BV-1 and 2 CDCM TABLE 2.3-23 BV-1 AND 2 SITE VENTILATICN VENTS DISPERSION PARAMETERS (D/Q) EOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /UIR (meters-) DISTANCES 'IO 'ITE CarrROL LC*'ATIONS, IN MILES SECIOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NtE 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 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 3.06E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 1.93E-10 SW 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 WSW 4.60E-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 W 6.49E-08 4.75E-10 wtM 9.25E-08 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 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 tM 1.19E-07
-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 NtM 5.22E-08 2-101 ISSUE 3
BV-1 and 2 CDCM TABLE 2.3-24 BV-1 AND 2 'IURBINE BUIIDING VENTS DISPERSIQ1 PARAMETERS (D/Q) FOR CCNTINOJUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR (meters ~) DISTANCES 'IO 'IllE CONTROL 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 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 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SE 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 SSE 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 S 2.61E-08 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SSW 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 SW 3.06E-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 WSW 4.60E-08 3.15E-10 1.13E-08 4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 W 6.49E-08 4.75E-10 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 MM 9.25E-08 7.83E-10 6.41E-10 1.19E-07 2.07E-08 8.68E-09 4.86E-09 2.99E-09 2.19E-09 1.56E-09 1.21E-09 tM 2.94E-10 9.04E-09 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.2SE-10 4.84E-10 3.59E-10 tRM 5.22E-08 2-102 . ISSUE 3 - - __ _ _ _ _ _ _ _ _ _ _ . ______h _ _ h
BV-1 ard 2 ODCM TABLE 2.3-25 FOR INFORMATICN (NLY BV-2 CONDENSATE POLISHIt0 BUILDIl0 VEIR DISPERSICN PARAME'IERS (D/Q) FOR CCNTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 Is&vrR (meters ~) DISTANCES 'IO 'IHE CORROL IDCATICES, IN MILES SEC'IOR 0.0 - 0.5 3.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 NNE 5.42E-08 9.39E-09 3.37E-09 1.89E-09 1.22E-09 8.54E-10 6.35E-10 4.92E-10 3.94E-10 3.22E-10 NE 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E-09 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.60E-10 ENE 7.77E-08 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 E 6.08E-08 1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 3.32E-10 ESE 3.23E-08 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10 1.87E-10 SE 3.29E-08 5.70E-09 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 2.84E-08 4.92E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 SSE 3.67E-08 6.37E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 S 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SSW 2.61E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 1.93E-10 SW 3.06E-08 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 WSW 4.60E-08 7.97E-09 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 W 6.49E-08 4.75E-10 1.60E-08 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 NNW 9.25E-08 7.83E-10 6.41E-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 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 4.84E-10 3.59E-10 2.94E-10 tm 5.22E-08 9.04E-09 2-103 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-26 mR INERNATICN OILY BV-2 DECOfrAMINATICN BUILDI?G VENT DISPERSICH PAPMETERS (D/Q) mR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS N TR (meters ~ ) DISTANCES 'IO 'IHE CatirROL IDCATICNS, IN MILES 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 SECIOR 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 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 NNE 5.42E-08 7.32E-08 1.27E-08 6.21E-09 3.47E-09 2.24E 1.57E-09 1.00E-09 7.77E-10 5.69E-10 4.66E-10' NE 1.35E-08 6.51E-09 3.64E-09 2.50E-09 1.76E-09 1.31E-09 1.01E-09 6.58E-10 5.39E-10 ENE 7.77E-08 3.32E-10 1.05E-08 3.79E-09 2.12E-09 1.37E-09 9.59E-10 6.54E-10 5.06E-10 4.05E-10 E 6.08E-08 1.87E-10 5.60E-09 2.54E-09 1.42E-09 8.46E-10 5.94E-10 4.05E-10 3.14E-10 2.28E-10' ESE 3.23E-08 2.59E-09 1.45E-09 9.32E-10 6.55E-10 4.12E-10 3.19E-10 2.55E-10 2.09E-10 SE 3.29E-08 5.70E-09 2.06E-09 1.15E-09 6.29E-10 4.42E-10 2.99E-10 2.32E-10 1.85E-10 1.52E-10 SSE 2.84E-08 4.92E-09 2.26E-09 1.26E-09 8.14E-10 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 S 3.67E-08 6.37E-09 1.39E-10 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 SSW 2.61E-08 3.24E-10 2.35E-10 1.93E-10 3.06E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 SW 1.87E-09 1.20E-09 8.45E-10 5.87&l0 4.55E-10 3.38E-10 2.77E-10 WSW 4.60E-08 7.97E-09 3.34E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 W 6.49E-08 1.13E-08 .4.72E-09 4.75E-10 6.43E-09 3.60E-09 2.21E-09 1.55E-09 1.16E-09 8.96E-10 5.79E-10 WtM 9.25E-08 1.60E-08 7.83E-10 6.41E-10 8.68E-09 4.86E-09 2.99E-09' 2.19E-09 1.56E-09 1.21E-09 NW 1.19E-07 2.07E-08 '3.59E-10 2.94E-10 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.25E-10 4.84E-10 NtM 5.22E-08 9.04E-09 ISSUE 3 2-104 - -- - - - - - _ _ ._ h _. _
'g
BV-1 and 2 ODCM TABLE 2.3-27 FOR IN NRMATIOi 04LY BV-2 WASTE GAS STORNIE VAULT VDJT DISPERSIOi PARAMETERS (D/Q) mR CCh"rINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR (neters~) DISTANCES 'IU 'IEE CONTROL II)CATIOIS, IN MILES SEC'IOR 0.0 - 0.5 0.5 - 1.0 1.0 - 1.5 1.5 - 2.0 2.0 - 2.5 2.5 - 3.0 3.0 - 3.5 3.5 - 4.0 4.0 - 4.5 4.5 - 5.0 N 4.46E-08 7.73E-09 3.24E-09 1.81E-09 1.08E-09 7.57E-10 5.16E-10 4.00E-10 2.91E-10 2.38E-10 t:JE 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 DJE 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 'O 5.71E-10 3.86E-10 2.99E-10 2.39E-10 1.96E-10 SSW 2.61E-08 4.52E-09 1.60E-09 8.97E-10 5.78E-10 4.06E-10 3.02E-10 2.34E-10 1.70E-10 1.39E-10 SW 3.06E-08 5.30E-09 2.62E-09 1.47E-09 8.01E-10 5.62E-00 4.18E-10 3.24E-10 2.35E-10 1.93E-10 WSW 4.60E-08 7.97E-09 3.34E-09 1.87E-09 1.20E-09 8.45E-10 5.87E-10 4.55E-10 3.38E-10 2.77E-10 W 6.49E-08 1.13E-08 4.72E-09 2.64E-09 1.19E-09 8.36E-10 6.22E-10 4.82E-10 3.85E-10 3.15E-10 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 2.19E-09 1.56E-09 1.21E-09 7.83E-10 6.41E-10 tam 5.22E-08 9.04E-09 3.79E-09 2.12E-09 1.28E-09 9.00E-10 6.2SE-10 4.84E-10 3.59E-10 2.94E-10 2-105 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-28 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS (D/0) FOR CONTINUOUS ELEVATED LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR FOR SPECIAL DISTANCES -(IDENTIFIED IN TABLE 2.2-3) (IE-9 meters- ) INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV HILK 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 VSV 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 l
i I 2-106 ISSUE 3
BV-1 and 2 ODCH. TABLE 2.3 BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (D/0) I FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TT FOR SPECIAL DISTANCES (IDENTIFIED IN. TABLE 2.2-3) (IE-9 meters-2) INDIVIDUAL RECEPT 0RS 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 l I 2-107 ISSUE 3
BU-1 and 2 ODCM TABLE 2.3-30 BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (D/0) FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /QTR~ FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) , (IE-9 meters-2) INDIVIDUAL RECEPT 0RS D0VNVIND 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 g NV 70.60 15.00 -- .276 1.990 15.60 NNV 31.50 6.52 -- .068 1.090 9.91 l 2-108 ISSUE 3
BV-1 and 2.0DCM
-TABLE 2.3-31 ,
BV-1 AND 2 TURBINE BUILDING VENTS DISPERSION PARAMETERS (D/0) ) FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) ' (IE-9 meters ~) INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE SECTOR 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 , 1.020 ^4 E 38.10 3.90 .382 1.020 it 1.380 3.560 3 59, ESE 18.60 3.56 -- SE 19.00 3.03 .351 .351 1.100 ,.010 2.65 .318 .094 2. 57. , 34 595 SSE 13.30 S 11.30 10.40 .934 -- 1 460 1 15c SSV 6.44 1.26 .664 .266 3.260 4.93 SV 3.95 2.21 -- 1.320 1 920 ? ?!3 VSV 25.10 2.65 .597 -- 2.3Bn 7. 6' ' , V 28.40 1.23 .646 -- .961 1.230 VNV 10.90 2.23 1.490 .045 . 23" '. 230 ) .276 45.500 NV 5 .10 14.90 -- 1.33' NNV 2'.10 6.53 -- .068 1.100 9.920 l 2-109 ISSUE 3
BV-1 and 2 ODCH- ; TABLE 2.3-32 FOR INFORMATION ONLY 1 BV-2 CONDENSATE POLISHING BUILDING VENT DISPERSION PARAMETERS (D/0) FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (IE-9 meters-2) , INDIVIDUAL RECEPT 0RS 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_ l S 11.30 10.40 .934 -- 1.860 1.950 SSV 6.44 1.26 .664 .266 1.260 4.430 SV 3.95 2.21 -- 1.320 1.920 2.210 VSV 25.10 2.65 .597 -- 2.380 2.650 i 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 ,
W mW # b G 2-110 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-33 FOR INFORMATION ONLY f BV-2 DECONTAMINATION BUILDING VENT DISPERSION PARAMETERS (D/0) FOR CONTINUOUS GROUND LEVEL RELEASES >500 HRS /YR OR >150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (IE-9 meters- ) INDIVIDUAL RECEPTORS D)VNVIND SITE VEGETABLE j{ECTOR BOUNDARY CARDEN MILK COV MILK G0AT 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 I
2-111 ISSUE 3
BV-1 and 1 ODCM TABLE 2.3-34 l FOR INFORMATION ONLY BV-2 VASTE GAS STORAGE VAULT VENT DISPERSION PARAMETERS (D/Q) 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) INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR BOUNDARY GARDEN MILK COV MILK G0AT 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 5 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 3'1.60 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 4
2-112 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-35 BV-1 AND 2 CONTAINMENT VENTS DISPERSION PARAMETERS (X/Q) I FOR BATCH GROUND LEVEL RELEASES <500 HRS /YR OR <150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED'IN TABLE 2.2-3) (sec/m ) . INDIVIDUAL RECEPTORS DOVNVIND SITE VEGETABLE SECTOR
- BOUNDARY GARDEN MILK COV MILK GOAT HEAT ANIMAL RESIDENCE N 8.21E-5 8.38E-6 -- 3.72E-6 4.34E-6 8'.82E-6 NNE 3.04E-5 4.71E-6 -- 1.40E-6 4.38E-6 4.87E-6 NE 4.59E-5 2.21E-5 6.05E-7 1.38E-7 6.05E-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 1.78E-5 ESE 2.47E-3 5.61E-6 ---
2.34E-6 5.61E-6 5.61E-6
.SE 2.14E-5 5.00E 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
'1SV 1.09E-4 1.29E-5 4.10E-6 --
1.19E-5 1.29E-5 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 ) 6.36E-5 NV 3.08E-4 6.13E-5 -- 3.80E-6 1~.36E-5 NNV 1.80E-4 3.54E-5 -- 1.35E-6 9.27E-6 5.29E-5
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980 2-113 ISSUE 3
BV-1 and 2 ODCM TABLE 2.3-36 BV-1 AND 2 VENTILATION VENTS DISPERSION PARAMETERS (X/0) FOR BATCH GROUND LEVEL RELEASES $500 HRS /YR OR $150 HRS /QTR { FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (sec/m ) INDIVIDUAL RECEPT 0RS DOWNVIND SITE VEGETABLE SECTOR
- BOUNDARY GARDEN MILK COV MILK GOAT MEAT ANIMAL 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 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 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 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-3 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 1 l
'l i
- Measured relevant to center point between BV-1 and BV-2 Containment Buildings Period of Record: 1976 - 1980 2-114 ISSUE 3
BV-1 and 2 ODCM TABLE ".3-37 BV-1 AND 2 PROCESS VENT DISPERSION PARAMETERS. (X/Q) l FOR BATCH ELEVATED RELEASES $500 HRS /YR OR 3150 HRS /0TR FOR SPECIAL DISTANCES (IDENTIFIED IN TABLE 2.2-3) (sec/m ) INDIVIDUAL RECEPTORS DOWNVIND SITE VEGETABLE SECTOR
- BOUNDARY ' GARDEN MILK COV MILK GOAT MEAT ANIMAL RESIDENCE N 3.09E-9 3.30E -- 1.13E-6 1.34E-6 3.36E-6 NNE 2.85E-9 2.68E-6 -- 6. 52 E--7 2.47E-6 2.68E NE 2.02E-10 7.42E-9 5.44E-7 1.24E-7 5.44E 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 2.52E-6 3.96E-6 SV 4.82E-6 2.75E-6 -- 1.78E-6 2.44E-6 2.75E-6 VSV 5.77E-7 2.81E-6 8.79E-7 -- 2.57E-6 2.81E-6 V 2.8BE-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 fW 1.34E-9 3.31E-8 -- 2.03E-7 1.07E-6 '3.10E-8
) NNV 1.52E-9 3.73E-6 -- 1.73E-7 1.31E-6 3.81E-6 l
- Measured relevant to BV-1 natural draft cooling tower Feriod of F.ecord: 1976 - 1980 2-115 ISSUE 3 f
BV-1 and 2 ODCM 7 NILE 2.3-38 BV-1 AND 2 PROCESS VENP DISPERSIN PARAMETERS (X/Q) FOR BATCH ELEVATED RELEASES $500 HRS /YR OR 3150 HRS /QTR* 3 (sec/m ) DISTANCES TO THE CCNTROL IDCATIWS, 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 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 NNE 5.90E-17 5.39E-6 2.83E4 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 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 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 4.82E-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 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 5 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 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 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 9.25E-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 l.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 NNW
- Transmittal via Stone and Webster Engineering Corp. letter 2DLS-29981 under J.O.12241 on January 30, 1987.
2-116 ISSUE 3 hj
BV-1 and 2 ODCM 2.4 GASEOUS RADVASTE SYSTEM The gaseous radvaste system has the capability to control, collect, process, store, recycle, and dispose of gaseous radioactive vaste generated as a result of plant operations, including anticipated operational occurrences. A simplified flow diagram of the gaseous radvaste system for BV-1 and BV-2 is provided as Figure 2.4-1. A diagram shoving 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. D 2-117 ISSUE 3
. - - .- ~ . . . . . BV-1-and 2 ODCM .. FIGURE 2.4-1 BV-1 AND 2 GASEOUS RADVASTE-SYSTEM . r I U$ht)RYUft1 70 afMOSPHERI L e r
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BV-1 and 2 ODCM FIGURE 2.4-2 BV-1 AND 2 GASEOUS EFFLUENT RELEASE POINTS I. w Ohio R'ver ol l L .A s v e o
\
x./ , ys . T \ c i
* . -]
i I s ' Unit 2 ( l
/ Unit 1 1 1 I ca C RELIASE POINT & DISCE!P!I0li ILEVAtl0N
- 1. Unit 1: Ventilati:nient 79 feet: 24 meters
- 2. Unit 1: Contair.sent / SLCRS Vent 154 feet: 47 seters
- 3. Unit ! & 2: Process Vent 475 feet:145 meters
- 4. Unit 2: Ventilation Vent 85 feet : 26seters
- 5. Unit 2:
- 6. Unit 2:
- 7. Unit 2:
Containment / SLCRS Vent CondensatePolishingBuildingVent Waste Gas Sterage Vault Vent 154 feet : 47 seters 80 feet : 24seters 80 feet : 24 meters O(
-6. Unit 2: Decentasination Building Vent 80 feet: 24 meters I
2-119 ISSUE 3
BV-1 and 2 ODCM 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING FROGRAM The following program requirements are excerpts from the Radiological Assessment Branch Technical Position, Revision 1, 1979. Table 3.0-1 contains the DLC site number, sector, distance, sample point description, sampling and collection frequency, analysis, and analysis l 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 i Appendix C, Table 3.0-1. Analytical techniques used shall be such that the l 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 etfluent monitoring 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. 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 D maximum burnup in the initial core cycle). Following this period, program changes may be proposed based on operational experience. 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. ; i The laboratories of the licensee and licensee's contractors which perform j analyses shall participate in the Environmental Protection Agency's (EPA's) { Environmental Radioactivity Laboratory Intercomparisons Studies j (Crosscheck) Program or e ;alvalent program. This participation shall . include all of the determinations (sample medium-radionuclide combination) ! that are offered by EPA and that also are included in the monitoring j program. The results of analysis of these crosscheck samples shall be { included in the annual report. The participants in the EPA crosscheck j program may provide their EPA program code so that the NRC can review the l EPA's participant data directly in lieu of submission in the annual report. j l l 1 3-1 ISSUE 3 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - -_ 5
BV-1 and 2 ODCM If the results of a determination in the EPA crosscheck program (or equivalent program) are outside the specified control limits, the laboratory shall investigate the cause of the problem and take steps to correct it. The results of this investigation and corrective action shall be included in the annual report. The requirement for the participation in the EPA crosscheck program, or similar 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 vegetation sampling may be performed at the site boundary in a sector with the highest D/0 in lieu of the garden census. For elevated releases as defined in Regulatory Guide 1.111, Rev. 1, the census shall also identify the locations of all milk animals, and gardens greater than 50 square meters producing broad leaf vegetation out to a distance of 5 km (3 miles) for each radial sector. If it is learned from this census that the milk animals or gardens are present at a location which yields a calculated thyroid dose greater than those previously sampled, or if the census results in changes in the location used in ODCM dose calculations, a written report shall be 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 surveillance program as soon as practicable. The sampling location (excluding the control sample location) having the lovest calculated dose may then be dropped from the surveillance program at the end of the grazing or growing season during which the census was conducted. Any location from which milk can no longer be obtained may be dropped from the surveillance program after notifying the URC in writing that they are no longer obtainable at that location. The results of the land-use census shall be reported in the annual report. The census of milk animals and gardens producing broad leaf vegetation is based on the requirement in Appendix I of 10 CFR Part 50 to " Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals from principal pathvays of exposure." The consumption of milk from animals grazing on contaminated pasture and of leafy vegetation contaminated by airborne radioiodine is a maj or 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. l 3-2 ISSUE 3
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 of 2 kg/m , vill produce- the 26 kg/yr assumed in Regulatory Guide 1.109, D 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 (man-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. 1 D { 3-3 ISSUE 3 l
BV-1 and 2 ODCM TABLE 3.0-1 , RADIOIOGICAL DNIRONMENTAL MCNI'IORING PROGRAM 1 i DLC SAMPLING AND EXPOSURE PA'HMAY SITE COLLECTION TYPE AND FREQUDiCY 1 2 OF ANALYSES AND/OR SAMPLE NO. SECIOR MILES SAMPLE POINT DESCRIPTIO FREQUD4CY ,
- 1. AIRBORNE Radiciodine and 13 11 1.6 Hookstown (Meyer's Farm) Continuous Radiciodine 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 -l on composite (by loca- .{ tion) quarterly. ]
- 2. DIRECT RADIATION 10 4 0.8 shippingport Boro (Post Office) Continuous Gamma 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 Twp. (Mt. Pleasant Church) 45.1 6 2.0 Raccoon Twp. (Kennedy's Corner) 46 3 2.5 ~ Industry (Church) 46.1 3 2.1 Industry (Tire Company) 47 14 4.8 East Liverpool, OH (Water Company) 48 10 16.5 Weirton, WV (Water company) 51 5 8.0 Aliquippa 59 7 1.1 . Iron's Farm 3-4 ISSUE 3
; 8
BV-1 and 2 ODCM TABLE 3.0-1 (continued) RADIOLOGICAL EINIRO@iENTAL MCNI'IORING PROGRNi DLC SAMPLIIC AND EXPOSURE PATEMAY SITE COLLECTIO1 TYPE AND FREQUENCY 1 3 AND/OR SAMPLE tO. SEC'IOR MILES SAMPLE POINT DESCRIPTICN FREQUENCY OF ANALYSES DIRECT RADIATION 60 13 3.7 Ilaney's Farm Continuous Gama 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 (Comunity College) 75 5 4.3 Raccoon Twp. (liolt Road) 76 6 3.8 Raccoon Twp. School 77 6 5.8 Raccoon Twp. (Green Garden Road) 78 7 2.3 Raccoon Twp. Municipal Building 79 8 4.6 Raccoon Twp. (Routes 18 & 151) 80 9 8.4 Raccoon Park 81 9 3.9 Southside School 82 9 7.1 Hanover Township Municipal Building 83 10 4.5 Greene Township (Mill Creek Road) 84 11 8.5 Hancock County, WV (Children's Home) 85 12 5.8 Hancock County, WV (Routes 8 & 30) 86 13 6.5 East Liverpool, Oli (Cahill's) 87 14 7.0 Calcutta, Oil 88 15 3.1 Midland fleights 89 15 4.7 Ohioville 90 16 5.2 Fairview School 91 2 3.7 Brighton 'IVp. (Pine Grove & Doy. ' Roads) 92 12 3.0 Greene Township (Georgetown Road) 93 16 1.3 Midland (Sunset Ilills) 94 8 2.4 Raccoon Twp. (McCleary Road) 95 10 2.4 Greene Township (McCleary Road) 3-5 ISSUE 3
BV-1 and 2 ODCM TABLE 3.0-1 (continued) RADIOIDGICAL ENVIRCNMDRAL MONITORING PROGRAM DLC SAMPLING AND EXPOSURE PATHWAY SITE 3 ENON MEE N C 1 2 OF ANALYSES AND/OR SAMPLE NO. SECTOR MILES SAMPLE POINT DESCRIPTION FREQUENCY
- 3. WATERORNE 5.0 Upsgream-invicinityofMontgomery Cmposite Gamma isotopic analysis a) Surface (River) 49.1 4 sample w/ monthly; tritium analy-Dam (ARCO Chemical company, formerly ARCO Polymers) sample col- sis on composite (by 2.1 14 1.3 Downstream-Midland lection at location) quarterly.
least 0 monthly . b) Drinking Water 4 14 1.3 Midland (Midland Water Treatment Composite I-131 analysis bi-Plant) sample w/ weekly; gamma isotopic 5 14 4.8 East Liverpool, OH (East Liver- sample col- analysis on composite pool Water Treatment Plant) lection at. (by location) monthly; least bi- tritium analysis on com-weekly . posite (by location) 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 - - animals are
*8 on pasture; at 96 10 10.3 Windsheimer's Dairy 4 least monthly
'- at other times.
13 0.2 Downstream-in vicinity of BVPS Semi-annually Gamma isotopic analysis. b) Pish ^ 2A Discharge Structure one sample of on edible portion. 49 3 4.7 Upstream-in vicinity of Montgomery available Dam species. 3-6 ISSUE 3
av-l and 2 CoCM TABLE 3.0-1 (continued) RADIOLOGICAL EINIRGiMmTAL P10NITORING PROGRAM DLC SAMPLIFO AND EXPOSURE PAT 1!WAY SITE ., 3 COLLECTION TYPE AND FRB20ENCY 1 OF ANALYSES AND/OR SAMPLE NO. ?ECTOR MILES' SAMPLE POINr DESCRIPTION ~ FREQUENCY
- 4. INGESTION (continued) Gamn isotopic and I-131 c) Food Products 10 4 0.8 Three (3) locations within 5 miles Annually at (Leafy vege- 15 14 3.3 of BVPS harvest analysis on edible tables) 46 3 2.5 time. portion.
48 10 16.5 One (1) location (Weirton, WV area) Sector numbers 1-16 correspond to the 16 compass direction sectors N - NNW. 2 Distance (in miles) is as measured from BVPS Unit 1 Containment' Building. 3All Sample Points, unless otherwise noted, are in the Commonwealth'of Pennsylvania. Maps showing the approximate locations of the Sample Points are provided as Figures 3.0-1 through.3.0-9. 4This is a. Control Station and is presumed to be outside the influence of BVPS effluents. , 5A gamma isotopic analysis is to be performed on each sample when the gross beta activity is 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. 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 dclnot affect local wells and ground water sources-in the area. 8 These Sample' Points will vary and are chosen based upon ' calculated annual deposition ' factors (highest). 3-7 ISSUL 3-
BV-1 and 2 ODCM FIGURE 3.0-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l AIR SAMPLING LOCATIONS DMR06J8 DENTAL 6dOP4TolfutM LOCAT50645- AJR tjmpf, NTICIC y Lawaos.t caserry AlfJRlifEIIALKIS -
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3-8 ISSUE 3
BV-1 and 2 ODCM ; I FIGURE 3.0 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD LOCATIONS - NORTHVEST GUADRANT NORT;4 WEST QUADEIANT I ScAvret VALry h Star.o e
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3-9 ISSUE 3
b BV-1 and' 2'ODCM FIGURE 3.0-3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD LOCATIONS - NORTHEAST QUADRANT 1
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BV-1 and 2 ODCM FIGURE 3.0 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TLD LOCATIONS - SOUTHEAST GUADRANT q.L-k. A+fg Megg>A [-[ \ m j J _ \, \ 9
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BV-1 and 2 ODCM-FIGURE 3.0-6 RADIOIOGICAL EtNIRCNMENTAL NCNI'IORIIU PROGRAM SHORELINE, SEDIMENT, SURFACE WATER, AND DRINKING WATER SAMPLIIU LOCATIONS flc
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- SURFACE WATER & DRINKING WATER 3-13 issue 3
BV-1 and 2 ODCM FIGURE 3.0-7
. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MILK SAMPLING LOCATIONS f.fMHONuCNTAL MONETOfuP43 LOCATIOttS- MllK y awoes. am.as
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BV-1 and 2 ODCM FIGURE 3.0-8 RADIOLOGICAL DNIPOMINIAL MCNI1DRING PROGRAM EVODCROP SAMPLING II)CATICES (f.
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4 BV-1 and 2 ODCM FIGURE 3.0-9 RADIOIDGICAL EINIRCMEITIAL fGI'IORING PROGRAM I FISH SAMPLING LOCATICES 1 Nr-l '
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BV-1 and 2 ODCM 4.0 INFORMATION RELATED TO 40 CFR 190
'O Appendix C CONTROL 3.11.4.1 requires that when the calculated doses V associated with the effluent releases exceed twice the limits of Appendix C 3.11.2.3.a, or 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.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 TFE PUBLIC from all facility releases of radioactivity and to radiation from uranium fuel cycle sources exceeds the limits of f 25 mrem to the total body or any organ, except the thyroid, which is limited to 3 75 mrem for a calendar year. If any of these limits are exceeded, prepare and submit to the Commission within 30 days a Special Report pursuant to Technical Specification 6.9.2f. The following shall be included in the Special Report:
- Define the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Appendix C CONTROL 3.11.4.1.
- Include the schedule for achieving conformance within the limits of Appendix C CONTROL 3.11.4.1.
- Include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. ;
- Describe levels of radiation and concentrations of radioactive material b involved, and the cause of exposure levels or concentrations.
- If the estimated dose (s) exceeds the limits of Appendix C CONTROL 3.11.4.1, and if the release condition resulting in violation of 40 CFR f Part 190 has not already been corrected, include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
O 4-1 ISSUE 3
BV-1 and 2 ODCM FIGURE 5-1 SITE BOUNDARY FOR GASEXXJS AND LIQUID EFFLUEtTrS s
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!. ISSUE 3 5-1 l
l BV-1 and 2 ODCM-APPENDIX A
SUMMARY
OF DISPERSION CALCULATIONAL PROCEDURES f Annual average and grazing season average values of relative concentration (X/0) and deposition (D/0) were calculated for continuous and intermittent gaseous releases of activity from the site according to the' straight-line airflow (Gaussian) model described in IEC Regulatory Guide 1.111, Revision 1. _ Undecayed and undepleted sector average X/0 and D/0 values vere obtained for each of sixteen 22.5-degree sectors at the site boundary and maximum individual receptors. For an elevated release, defined as occurring at a height that is twice the height or more of a nearby structure, credit was taken for the effective release height which is comprised of the physical release height plus momentum plume rise minus the terrain height at a given receptor. A building. vake correction factor was used to adjust calculations for. ground-level releases. Airflow reversals were also accounted for by applying site-specific terrain recirculation factors for both ground and elevated releases at the site (Albersheim, 1978). The methodology employed in the calculation of intermittent release X/0 and D/0 values is that described in NUREG/CR-2919 (Sagendorf, et. al. 1982). l The site continuous gaseous release points that have been evaluated include the process vent attached to the BVPS-1 natural draft cooling tover, the Containment ~ Vents, Ventilation Vents, Turbine Building Vents, the BVPS-2 Condensate l Polishing Building Vent, Decontamination Building Vent, and Gaseous Vaste Storage Tank Vault Vent. The intermittent releases are from the Process Vent,. Containment Vents, and Ventilation Vents. Only the process vent was considered to be an elevated release with all other release points being treated as ground level releases. A summary of the release characteristics and their locations is . given in Appendix A, Table 1.1. Onsite meteorological data for the period January 1, 1976 through December 31, 1980 vere used as input for the annual-average calculations. The grazing season was represented by a six-month period from May 1 through October 31 for each year of the 5-year meteorological data base. This grazing i season corresponds reasonably well with the growing season. The data were collected according to guidance in NRC Regulatory Guide 1.23'as described in ! Section 2.3 of the BVPS-2 FSAR. The parameters used in the X/0-D/0 calculations-consist of vind speed, vind direction, and oT as an indicator of-atmospheric stability. The lover level vinds (35 ft) and oT (150-35 ft) were used for all release points except the process vent which required the use of 500 ft vinds and oT (500-35 ft) which are representative of the release height (510 ft). 1 The annual average and grazing season X/0 and D/0 values for the continuous and j 1"termittent radioactive releases vere calculated at the site boundary, nearest . { resident, nearest vegetable garden, nearest milk cow, nearest milk goat, and _, 1 nearest meat animal. In the case of the process vent releases, several of each l receptor type were evaluated in each downvind sector to determine the maximum l X/0-D/0 values. The distances of the limiting maximum individual receptors from the radioactive release points are given in Tabla 2.2-3. The continuous release. annual average X/0 values at the special locations for the Containment Vents, Ventilation Vepts, Process Vent, Turbine Building Vents, Decontamination 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 D i annual average X/0's for these same release points are also given at ten e ' A-1 ISSUE 3 g ___ __ j
BV-1 and 2 ODCM 7 APPENDIX A
SUMMARY
OF DISPERSION CALCULATIONAL PROCEDURES (continued) l incremental downwind distances. Continuous release D/0 values for these same 4 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 the containment vent X/0's and D/0's. Likewise, the Turbine Building Vent X/0's and D/O's apply to the BVPS-2 Condensate Polishing Building as well due to its location adjacent to the Turbine Building. Tables 2.3-35 through 2.3-38 contain short term X/0 values for batch releases originating from the Containment Vent, Ventilation Vent, and Process Vent releases respectively. The values in these tables are based on 32 hours per year of Containment and Ventilation Vent purges and 74 hours per year of Process Vent purges. Albersheim, S. R., Development Of Terrain Adjustment Factors For Use At the Beaver Valley Power Station For the Straight-Line Atmospheric Dispersion Model, NUS-2173, NUS Corporation, June 1978 Sagendorf, J. F., Goll, J. T. and Sandusky, V. F., X00D00: Computer Program For The Meteorological Evaluation Of Routine Effluent Releases At Nuclear Power Stations, NUREG/CR-2919, U. S. Nuclear Regulatory Commission, September, 1982. A-2 ISSUE 3
BV-1 and 2 ODCH APPENDIX A
. TABLE 1.1 I
BV-1 AND 2 RELEASE CONDITIONS TURBINE VENTILATION CONTAINMENT- 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 t Release Point 26 47 155 33 Height (m) Adjacent Building 19 44 155 33 Height (m) -- Relative Loca- E. Side Of Top Center Of Atop Cooling Turbine tien To Adjacent Primary Auxi- Containment Tower- Building Structures liary Bldg Dome Exit Velocity NA NA 9.4 NA - l (m/sec) Internal Stack NA NA 0.25 NA Diameter (m) Building Cross- 1600 1600 NA NA 2 Sectional Area (m ) Purge Frequency
- 32 32 74 NA (hours / year)-
Purge Duration 8 8 NA NA (hrs / release) I
- Applied to Short Term calculations only s
A-3 ISSUE 3
BU-1 and 2 ODCM APPENDIX B INPUTS TO COMPUTER CODES FOR GENERATION OF SOURCE TERMS l
- 1. Inputs To Gale Code For Generation Of BV-1 Liquid Source Term Mixes
- 2. Inputs To SVEC LIQlBB Code For Generation Of BV-2 Liquid Source Term Mixes
- 3. Inputs To SVEC GASIBB Code For Generation Of BV-1 Gaseous Source Term Mixes
- 4. Inputs To SVEC GAS 1BB Code For Generation Of BV-2 Gaseous Source Term Mixes t
l l t i i B-1 ISSUE 3
BV-1 end 2 ODCH APPENDIX B TABLE 1.la l INPUTS TO GALE CODE FOR GENERATION OF BV-1 LIQUID SOURCE TERM MIXES 4 I BV-1 PVR INPUTS PVR Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor _ .800 Mass Of Primary Coolant (thousand lbs) 345.000 Percent Fuel Vith Cladding Defects .120 L' Primary System Letdown Rate (gpm) 60.000 Letdown 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 Ibs) 6.772 Mass Of Liquid In Each Steam Generator (thousand Ibs) 97.000 Total Mass Of Secondary Coolant (thousand lbs) 1296.000 ,j Mass Of Vater In Steam Generator (thousand Ibs) 291.000 Blowdown Rate (thousand lbs/hr) 33.900 Primary To Secondary Leak Rate (lbs/ day) 100.000 j Fission Product Carry-Over Fraction .001-Halogen Carry-Over Fraction .010 L 1 Condensate Demineralizer Flow Fraction 0.000 i Radvaste Dilution Flov (thousand gpm) 22.500 l ML BV-1 LIQUID VASTE INPUTS COLLECTION DELAY DECONTAMINATION FLOV RATE FRACTION FRACTION TIME TIME FACTORS STREAM (gal / day) 0F PCA DISCHARGE (days) (days) 1 Cs OTHERS Shim Bleed 1.32E4 1.000 0.000 11.260 7.220 1E7 IE7 1E7 Rate Equipment 6.00E2 1.000 0.000 11.260 7.220 1E7 1E7 1E7 Drains Clean Vaste 7.50E1 1.000 1.000 0.071 0.648 1ES 2E4 1E5 Input Dirty Vaste 1.35E3 0.035 1.000 0.071 0.648 1ES 2E4 1E5 q Input Blowdown 9.75E4 -- 1.000 0.071 0.648 1ES 2E4 1E5 Untreated 0.0 -- -- -- -- -- -- -- Blowdown . G B-2 ISSUE 3 i
BV-1 and 2 ODCH AFPENDIX B TABLE 1.lb I INPUTS TO SVEC LIQ 1BB CODE FOR GENERATION OF BV-2 LIQUID SOURCE TERM MIXES BV-2 PVR INPUTS PVR Thermal Power Level.(megawatts) 2766.000' Plant Capacity Factor .800 Mass Of Primary Coolant (thousand lbs) 385.000 Percent Fuel 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/ht) 11.600 8.700 Mass 6f Steam In Each Steam Generator (thousand lbs) 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 (thorsand-lbs/hr) 22.300 Primary To Secondary Leak Rate (lbs/ day) 100.000 Fission Product Carry-Over Fraction .001-Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction .700 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 Hiscellaneous 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.' 6.2 1E3 1E4 1E4l Cond. Demin. 2685 1.1E-4 1.0 35.5 6.2 1E3 1E4 1E4- q Rinse Vater CVCS 60 -- 1.0 1300 173 1E4 4E3 1E5 Turbine Bldg. 7200 -- 1.0 -- -- -- -- -- Drains B-3 ISSUE 3 h
BV-1 ond 2 ODCH APPENDIX B TABLE 1.2a R f INPUTS TO SWEC GAS 1BB CODE FOR GENERATION OF BV-1 GASE0US SOURCE TERM MIXES ( BV-1 PVR INPUTS PVR Thermal Power Level (megavatts) 2766.000 Plant Capacity Factor .800 Hass 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 Hass Of Steam In Each Steam Generator (thousand Ibs) 8.700 Hass Of Liquid In Each Steam Generator (thousand lbs) 100.000 Total Mass Of Secondary Coolant (thousand Ibs) 2000.000 Hass Of Vater In Steam Generator (thousand lbs) 298.000 Blowdown Rate (thousand lbs/hr) 52.000 Primary To Secondary Leak Rate (lbs/ day) 100.000 - Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction 0.000 Radvaste Dilution Flov (thousand gpm) 15.000 BV-1 GASEOUS VASTE INPUTS i There Is Not Continuous Stripping Of Full Letdown Flow Hold Up Time For Xenon (days) 39.000 l 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 Partition 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 i There Is Not A Cryogenic Off Gas System
*2 cold and 2 hot purges l B-4 ISSUE 3
BU-l and 2 ODCM APPENDIX B TABLE 1.2b INPUTS TO SVEC GASlBB CODE FOR GENERATION OF BV-2 GASEOUS SOURCE TERM MIXES BV-2 PVR INPUTS PVR Thermal Power Level (megawatts) 2766.000 Plant Capacity Factor .800 Mass Of Primary Coolant (thousand Ibs) 385.000 Percent Fuel Vith Cladding Defects .120 Primary System Letdown Rate (gpm) 57.000 Letdown Cation Demineralizer Flow 5.700 Number Of Steam Generators 3.000 Total Steam Flov (million lbs/hr) 11.600 Mass Of Steam In Each Steam Generator (thousand lbs) 8.700 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 Ibs/hr) 22.300 Primary To Secondary Leak Rate (1bs/ day) 100.000 Fission Product Carry-Over Fraction .001 Halogen Carry-Over Fraction .010 Condensate Demineralizer Flow Fraction 700 Radvaste Dilution Flov (thousand gpm) 7.800 BV-2 GASE0US VASTE INPUTS 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 (Ib/ day) 100.000 There Is A Kidney Filter Containment Atmosphere Cleanup Rate (thousand efm) 20.000 Purge Time Of Containment (hours) 8.000 There Is Not A Condensate Demineralizer Iodine Partition Factor (gas /lig) In Steam Generator 0.010 Frequency Of Containment Building High Vol Purge (times /yr)* 4.000 Containment Volume Purge Iodine Release Fraction 1.000 Particulate Release Fraction 1.000 Steam Leak To Turbine Building (lbs/hr) 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 D *2 cold and 2 hot purges e B-5 ISSUE 3
BU-l 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 POWER 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 each 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 water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related safety function (s). REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. I C-1 ISSUE 3
DV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: DEFINITIONS (continued) 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 FUNCTIONS. TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other 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 q OPERABILITY including alarm and/or trip functions. DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 sball be that concentration of I-131 (uCi/ gram) which alone would product the same thyroid dose as the quantity and isotopic mixture of I-l'11,
. I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, Revision 1, 1977 or Table III of TID 14844.
FREQUENCY NOTATION 1.21 The FREQUEN^Y NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2. SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. C-2 ISSUE 3
g BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS ! CONTROLS: DEFINITIONS (continued) 0FFSITE DOSE CALCULATION MANUAL (0DCM) , 1.30 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 Environmental Monitoring Programs required by Section 6.8.6' and (2) descriptions of the information that should -be included in the Annual Radiological Environmental' Operating and Annual ' Radioactive Effluent Release Reports required by TS 6.9.1.10 and 6.9.1.11. GASEOUS RADVASTE TREATMENT SYSTEM 1.31 A CASE 0US RADVASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant-system offgases from the primary-system and providing for delay or holdup for the purpose of reducing. the- total radioactivity prior to release-to the environment. VENTILATION EXHAUST TREATMENT SYSTEM d 1.32 -VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to redace gaseous radiciodine 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 iodines or particulates from the gaseous exhaust. stream prior to the release to the environment (such a system'is not considered- to have any.effect on noble gas effluents). Engineered Safety Feature (ESP) atmospheric cleanup, systems are not considered to be VENTILATION.-EXHAUST TREATMENT SYSTEM. components. PURGE-PURGING 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 'q 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. C-3 ISSUE 3 I i 1
BV-1 and 2 ODCM APPENDIX-C ODCM CONTROLS CONTROLS: DEFINITIONS (continued) ll HEMBER(S) 0F THE PUBLIC 1.36 MEMBER (S) 0F THE PUBLIC shall include all persons who are not-occupationally associated with the plant. This category does not include employees of the utility, its contractors, or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries and persons who traverse portions of the site as the consequence of a public highway, . railway, or waterway located within the confines of the site boundary. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant. , SITE BOUNDARY 1.38 The SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee. (See Figure 5-1) UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is- net controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive I materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. 3 4 2 g C4 ISSUE 3
BV-1 and.2 ODCM APPENDIX C ODCM CONTROLS TABLE 1.1 } OPERATIONAL MODES REACTIVITY % RATED AVERAGE COOLANT MODE CONDITION, K,gg THERMAL POWER
- TEMPERATURE-
- 1. Power Operation >0.99 >5% >350*F-
- 2. Startup >0.99 $5% >350*F
- 3. Hot Standby <0.99 0 >350*F-
- 4. Hot Shutdown <0.99 0 350*F >T avg
>200*F
- 5. cold Shutdovn <0.99 0 f200*F .
- 6. Refueling ** <0.95 0 $140*F-I g-
- Excluding decay heat.
** Reactor vessel head unbolted or removed and fuel in the vessel.
C-5 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours D At least once per 24 hours V At least once per 7 days M At least once per 31 days 0 At least once per 92 days SA At least once per 184 days R At least once per 18 months S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable 1 G C-6 ISSUE 3 , a
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS D CONTROLS: APP!.ICABILITY 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 hours,
- 2. At least HOT SHUTD0VN vithin the following 6 hours, and
- 3. At least COLD SHUTD0VN vithin the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ACTION. requirements, the ACTION may be taken in accordance with the
) specified time limits as measured from the time of failure to meet the CONTROL. Exceptions to these requirements are stated in the individual CONTROLS.
3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the CONTROL are not met and the associated ACTION requires a shutdown if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an un?~.mited period of time. This provision shall not prevent passage through ar to OPERATIONAL MODES as required to comply with ACTION requireme (s. Exceptions to these requirements are stated in the individual CONTR'L3. I C-7 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual CONTROLS unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allovable extension not to exceed 25% of the surveillance interval. 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by CONTROL 4.0.2, shall constitute non-compliance with the OPERABILITY requirements for a CONTROL. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours to permit the completion of the surveillance when the allovable outage time limits of the ACTION requirements are less than 24 hours. 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 i to OPERATIONAL MODES as required to comply with ACTION requirements. C-8 ISSUE 3
jd BV-1 and 2 ODCM ' l APPENDIX C ODCH CONTROLS ' l h CONTROLS: RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION : ,
; l I
3.3.3.9 In accordance with BV-1 and BV-2 Technical Specification 6.8".6a, ' Item 1, the radioactive liquid effluent monitoring instrumentation channels shown in Appendix C, Table 3.3-12 shall be OPERABLE vith their alarm / trip setpoints set to ensure that the limits of Appendix C CONTROL 3.11.1.1 are not exceeded. The alarm / trip setpoints of the radiation monitoring channels shall be determined in accordance with Section 1.1.1 and 1.1.2 of this manual. Applicability: During releases through the flow path. Actions
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or correct the alarm / trip setpoint.
- b. Vith one or more radioactive liquid effluent monitoring instrumentation-I channels inoperable, take the ACTION shown in Appendix C, Table 3.3-12 or 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 was not corrected in a timely manner.
- c. The provisions of Appendix C CONTROL 3.0.3 are not applicable. b
]
SURVEILLANCE REQUIREMENTS 4.3.3.9 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. l I C-9 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-12
'~
BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM 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 Train 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 Tover 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 Vater Storage Tank (BR-TK-6A) (1) 26
- b. Primary Vater Storage Tank (BR-TK-6B) (1) 26
- c. Steam Generator Drain Tank (LV-TK-7A) (1) 26
- d. Steam Generator Drain Tank (LV-TK-7B) (1) 26 l
C-10 ISSUE 3
BV-1 and 2 ODCM APPENDfX C' ODCM CONTROLS l TABLE 3.3-12 (continued) BV-2 RADI0 ACTIVE LIQUID EFFLUENT NONITORING INSTRUMENTATION MIt'THUM CHANNELS INSTRUMENT OPERABLE ACTION-
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. Liquid Vaste Process Effluent Monitor (2SGC-R0100) (1)- 23-
- 2. Gross Radioactivity Msnitors Providing Alarm But Not Providing Termination Of Release None
- 3. Flow Rate Measurement Devices
- a. Liquid Radvaste Effluent (2SGC-FS100) (1) 25
- b. Cooling Tover Blowdown Line (2CVS-FT101) (1) 25
- 4. Tank Level Indicating Devices (for tanks outside l plant buildings)
None A C-11 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-12 (continued) 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 L.ERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that at least once per 8 hours grab samples are analyzed for gross radioactivity (beta or gamma) at a Lower Limit of Detection (LLD) of at least 13-7 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 j once per 4 hours during actual releases. Pump curves may be used to estimate flov. Action 26 Vith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue provided the tank liquid level is estimated during all liquid additions to the tank. I C-12 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. Gross Beta Or Gamma Radioactivity Monitors Providing Alarm And Automatic Termination Of Release
- a. Liquid Radvaste Effluent Line D P(5) R(3) 0(1)
(RM-LV-104)
- b. Liquid Vaste Contaminated D P(5) R(3) O(1)
Drain Lina (RM-LV-116)
- c. Auxiliary Feed Pump Bay D D R(3) 0(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. Flov 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 Tower Blovdown Line D(4) NA R 0 (FT-CV-101, 101-1)
C-13 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued) BV-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT' CHECK CHECK CALIBRATION TEST
- 4. Tank Level Indicating Devices (for tanks outside plant buildings)
- a. Primary Vater Storage Tank D* NA R 0 (BR-TK-6A)
- b. Primary Water Storage Tank D* NA R Q (BR-TK-6B)
- c. Steam Generator Drain Tank D* NA R Q (LV-TK-7A)
- d. Steam Generator Drain Tank D* NA R 0 (LV-TK-7B)
- During liquid additions to the tank.
C-14 ISSUE 3
+
-{
BU-l and 2 ODCM APPENDIX C ODCH CONTROLS TABLE 4.3-12 (continued) l BV-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 1. Gross Radioactivity Monitor Providing Alarm And Automatic Termination Of Release
- a. Liquid Vaste Process Effluent D P(5) R(8)(3) 0(7)
(2SGC-R3100)
- 2. Flow Rate Measurement Devices
- a. Liquid Radvaste Effluent D(4) NA R 0 -
(2SGC-FS100)
- b. Cooling Tower Blowdown Line D(4) NA R 0 (2CVS-FT101)
- 3. Tank Level Indicating Devices
}. (for tanks outside plant buildings)
None C-15 ISSUE 3-
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS l TABLE 4.3-12 (continued)- TABLE NOTATION i (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs if any of the ' following conditions exist:
- l. 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 Annu" lation 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.
CALIBRATION for radioactivity measurement (3) The initial CHANNEL 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 l the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per 18 months. This can normally be accomplished during refueling outages. (Existing plants may substitute previously established calibration procedures for this requirement). (4) CHANNEL CHECK shall consist of verifying indication of 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. i G C-16 ISSUE 3
BV-1 a'nd 2.0DCM' j APPENDIX C ODCM CONTROLS TABLE 4.3-12 (continued).
) 1 TABLE NOTATION f f
i (6) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic ks of this pathway and Control ' Room Alarm Annunciation occurs when the instrument indicates measured levels above the Alarm / Trip Setpoint. The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Alarm-Annunciation occurs if any of the folloving conditions exists:
- 1. Downscale failure. ,
- 2. Instrument controls are not set in operate mode. q (7) The CHANNEL FUNCTI0NAL TEST shall also demonstrate that automatic isolation of this pathway and Control Room Alarm Annunciation occurs- if the ;
instrument indicates measured levels above the alarm / trip setpoint. (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.
j r C-17 ISSUE 3
BV-l'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. Vith a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which vill ensure that the limits of Appendix C CONTROL 3.11.2.1 are met, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or correct the alarm / trip setpoint,
- b. With one or more radioactive gaseous effluent monitoring instrumentation channels inoperable, take the ACTION shown in Appendix C, Table 3.3-13 or conservatively reduce the alarm setpoint. Exert a best effort to return the )
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. Ik SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Appendix C, Table 4.3-13.
l I G I C-18 ISSUE 3 l i l
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 BV-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER _ ACTION
- 1. Gaseous Vaste/
Process Vent System (RM-GV-108A&B)
- a. Noble Gas (1)
- Radioactivity Rate 27,30***
Activity Monitor Measurement
- b. Particulate (1)
- 32 Activity Monitor
- c. System Effluent (1)
- System Flow Rate 28 Flow Rate Measuremti t Measuring Device (FR-GV-108)
- d. Sampler Flov (1)
- Sampler Flow Rate 28 Rate Measuring Measurement
) Device
- 2. Auxiliary Building Ventilation System (RM-VS-101A&B)
- a. Noble Gas (1)
- Radioactivity Rate 29,30***
Activity Monitor Measurement
- b. Particulate (1)
- 32 Activity Monitor
- c. System Effluent (1)
- System Flow Rate 28 Flow Rate Measutement Measuring Device (FR-VS-101)
- d. Sampler Flov (1)
- Sampler Flow Rate 28 Rate Measuring Measurement Device
*Du' ing Releases via this pathway. ***Du ig purging of Reactor Containment via this pathway.
C-19 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABl.E 3.3-13 (continued) BV-1 RADIOACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION
- 3. Reactor Building /
Supplementary Leak Collection And Release System (RM-VS-107A&B)
- a. Noble Gas (1)
- Radioactivity Rate 29,30***
Activity Monitor
- b. Particulate (1)
- 32 Activity Monitor
- c. System Effluent (1)
- System Flow Rate 28 Flow Rate Measurement Measuring Device (FR-VS-112)
- d. Sampler Flov (1)
- Sampler Flow Rate 28 Rate Measuring Measurement :
Device 1 G C-20 ISSUE 3 l
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued) ll BV-2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE APPLICABILITY PARAMETER ACTION INSTRUMENT
- 1. Ventilation, System (2HVS-R0101A&B)
Noble Gas
- Radioactivity Rate 29,30***
- a. 1 Activity Monitor Measurement
- 32
- b. Particulate 1 Activity Monitor
- Process Flow Rate 28
- c. Process Flow 1 Rate Monitor Measurement
- Sampler Flow Rate 28
- d. Sampler Flov 1 Rate Monitor Measurement
- 2. Elevated Release w (2HVS-R0109A&B)
)
- Radioactivity Rate 29,30***
- a. Noble Gas 1 Activity Monitor Measurement
- 32
- b. Particulate 1 Activity Monitor
- Process Flow Rate 28
- c. Process Flov 1 Rate Monitor Measurement
- Sampler Flow Rate 28
- d. Sampler Flov 1 Rate Monitor Measurement
- 3. Decontamination Bldg.
Vent (2RMO-R0301A&B)
- Radioactivity Rate 29
- a. Noble Gas 1 Activity Monitor Measurement V
- 32
- b. Particulate 1 Activity Monitor
- Sampler Flow Rate 28
- c. Sampler Flov 1 Rate Monitor Measurement g
+.J C-21 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued) BV-2 RADI0ACTIsE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE APPLICABILITY PARAMETER ACTION N INSTRUMENT -v
- 4. Condensate Polishing Building Vent (2HVL-R0112A&B)
- Radioactivity Rate 29
- a. Noble Gas 1 Activity Monitor Measurement
- 32
- b. Particulate 1 Activity Monitor
- c. Sampler Flow 1
- Sampler Flov Rate 28 Rate Monitor Measurement
- 5. Vaste Gas Storage Vault (2RMO-R0303A6B)
- Radioactivity ". ate 29
- a. Noble Gas 1 Activity Monitor Measurement
- 32
- b. Particulate 1 Activity Monitor
- c. Sampler Flov 1
- Sampler Flow Rate 28 Rate Monitor Measurement g O
C-22 ISSUE 3
=. BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.3213 (continued) '. T J 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 relea;e:
- 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 hours. 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 hours and these samples are analyzed for gross activity within 24 hours, 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 AP_PLICABLE 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. 9 C-23 ISSUE 3
BV-1 and 2 ODCM . APPENDIX C ODCM CONTROLS TABLE 3.3-13 (continued) ACTION STATEMENTS Action 30 APPLICABLE FOR PURGES OF THE BV-2 REACTOR CONTAINMENT With the number of channels OPERABLE less than required by Minimum Channels OPERABLE requirement, immediately suspend purging of Reactor Containment via this pathvay. 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 hours. 9 C-24 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-13 BV-1 RADI0 ACTIVE GASEOUS 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 Gas 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)
- d. Sampler Flow Rate Measuring D* NA R 0 Device
- 2. Auxiliary Building Ventilation System (RM-VS-101A&B)
) a. Noble Gas Activity Monitor D M(4), R(3) 0(2) P(4)***
- b. Particulate Activity Monitor V NA NA NA
- c. System Effluent Flov Rate D NA R 0 Measurement Device (FR-VS-101)
- 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)
P(4)***
- b. Particulate Activity Monitor V N/A N/A N/A
- c. System Effluent Flow Rate D N/A R 0 Measuring Device (FR-VS-112)
- d. Sampler Flow Rate Measuring D N/A R 0 l Device
*During releases via this pathway. ***During purging of Reactor Containment via this pathway.
C-25 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.3-13 (continued) O BV-2 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION TEST INSTRUMENT
- 1. Ventilation System (2HVS-R0101A&B)
Noble Gas Activity Monitor D M(4), R(3)(6) O(5) a. P(4)*** V NA NA NA
- b. Particulate Activity Monitor D NA R 0
- c. Process Flow Rate Monitor D NA R 0
- d. Sampler Flow Rate Monitor
- 2. Elevated Release (2HVS-R0109A&B)
Noble Gas Activity Monitor D M(4), R(3)(6) O(5) a. P(4)*** V NA NA NA
- b. Particulate Activity Monitor D NA R 0
- c. Process Flow Rate Monitor D NA R 0
- d. Sampler Flow Rate Monitor
- 3. Decontamination Bldg. Vent (2RM0-R0301A&B)
Noble Gas Activity Monitor D M(4) R(3)(6) O(5) a. V NA NA NA
- b. Parti,culate Activity Monitor D NA R 0
- c. Sampler Flow Rate Monitor N
- 4. Condensate Polishing Building Vent (2HVL-R0112A&B)
Noble Gas Activity Monitor D M(4) R(3)(6) 0(5) a. Particulate Activity Monitor V NA N/A NA b. NA R 0
- c. Sampler Flow Rate Monitor D A
O C-26 ISSUE 3
e BV-1 and'2 ODCM tr APPENDIX C ODCM CONTROLS. , TABLE 4.3-13 (continued)
)
BV-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING-INSTRUMENTATION SURVEILLANCE REQUIREMENTS
-CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION TEST INSTRUMENT
- 5. Vaste Gas Storage Vault (2RM0-R0303A&B)
- a. Noble Gas Activity Monitor D M(4) R(3)(6) 0(5)
V- , Particulate Activity Monitor V NA NA NA s. b. Sampler Flow Rate Monitor- D NA R' 0 c.
'l\
/) d 1 e
%-)
C-27 ISSUE 3 i
BV-1 and 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 and 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.
(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.
CALIBRATION radioactivity measurement (3) The initial CHANNEL for 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 l l existing-count rate to verify channel response. (5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room Alarm l Annunciation occurs if the instrument indicates measured levels above the alarm / trip setpoint. (6) The CHANNEL CALIBRATION shall also demonstrate that Control Room Alarm Annunciation occurs if either of the following conditions exist: [ 1. Downscale failure. 1
- 2. Instrument controls are not set in operate mode.
l O C-28 ISSUE 3 l l
BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS D CONTR,0LS: LIQUID EFFLUENT CONCENTRATION 3.11.1.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Items 2 and 3, the concentration of radioactive material released at any time from the site (see Figure 5-1) shall be limited to the concentrations specified in 10. CFR Part 20, Appendix B,. Table II, Column 2 for radionuclides other than dissolved or entrained noble ' gases. For dissolved or entrained noble gases, the concentration' shall be limited to 2E-4 uCi/ml total activity. Applicability: At all times. Action:
- a. Vith the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits; immediately restore the concentrstion within the above limits, and
- b. Submit a Special Report to the Commission within 30 days in accordance with Technical Specification 6.9.2f.
- c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
I SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid vastes shall be sampled and analyzed according to the sampling and analysis program of Appendix C, Table 4.11-1*. 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 When the activity of the BV-1 secondary coolant is greater than IE-5 uCi/ml gross, grab samples shall be taken for each sump discharge from the turbine building and chemical vaste sumps. The sample shall be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml and recorded in plant records. Vater volume discharged shall be estimated from the number of pump operations unless alternate flow or volurae instrumentation is provided. I C-29 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.11.1.1.4 When the activity of the BV-2 secondary coolant is greater than 1E-5 uCi/ml gross and the Turbine Building transfer pumps (2DBS-P42, 2DBS-P43, 2DBS-P44) are not pumping their sumps to the steam generator blovdown tank (2SGC-TK21B), grab samples shall be taken for each sump discharge from the turbine building. The sample shall be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml and recorded in plant records. Vater volume discharged shall be estimated from the number of pump operations unless alternate flov or volume instrumentation is provided. 4.11.1.1.5 Prior to the BV-2 Recirculation Drain Pump (s) (2DAS-P215A/B) discharging to catch basin 16, a grap sample vill be taken. The samples vill be analyzed for gross activity at a sensitivity of at least 1E-7 uCi/ml. Vater volume discharged shall be estimated from the number of pump operations unless alternate flow or volume instrumentation is provided. 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 Appendix C SURVEILLANCE REQUIREMENT 4.11.1.1.5 respectively.
C-30 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 4.11-1 .,
'\
RADI0 ACTIVE LIQUID VASTE SAMPLING AND ANALYSIS PROGRAM N MINIMUM LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY LOVER LIMIT TYPE FREQUENCY FREQUENCY ANALYSIS OF DETECTION (LLD) (uCi/ml)" A. Batch Vaste d P P Principal Gamma SE-7 h h f Release Tanks Each Batch Each Batch Emitters I-131 1E-6 P M Dissolved And 1E-5 h One Batch /M Entrained Gases (Gamma Emitters) P h
" b H-3 1E-5 Each Batch Composite Gross" Alpha IE-7 P 0 Sr-89, Sr-90 SE-8 h b Each Batch Composite Fe-55 1E-6 Grab Sample E V Principal Gamma SE-7 B.ContinuogE Composite c
Emitters f Releases I-131 1E-6 g IE-5 Grab Sample M Dissolved And Entrained Gases (Gamma Emitters) g IE-5 Grab Sample H H-3 C Composite Gross Alpha 1E-7 g Sr-89, Sr-90 SE-8 Grab Sample 0 Composite' Fe-55 1E-6 h C-31 ISSUE 3
BV-1 and 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 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(-MT) where: LLD is the lover limit of detection as defined above (as pCi per unit mass or volume); sg is the standard deviaticn of the background c.ounting 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); 4 2.22 is the number of transformations per minute per picocurie; 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 pulod) 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 a 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. Typical values of E, V, Y and AT should be used in the y 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. l C-32 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS 4 l TABLE 4.11-1 (continued)
^
TABLE NOTATION 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 the liquids released.
- c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent' stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order.for the composite sample to be representative of the effluent release.
- d. A batch release exists when the discharge of liquid vastes is from a discrete volume. Prior to sampling for analyses,- each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
- e. A continuous release exists when the discharge of liquid vastes is from a non-discrete volume; e.g., from a volume of- a system having an input flow during the continuous release. For BV-1, this is applicable to the Turbine Building drains and the AFV Pump Bay Drain System and chemical vaste sump,_
vhen the secondary coolant gross radioactivity (beta and gamma) is greater i than 1E-5 uci/ml. For BV-2, this is applicable to the Turbine Building I drains when the secondary coolant gross radioactivity (beta and gamma)'is greater than IE-5 uCi/ml.
- f. The principal gamma emitters for which the LLD specification vill apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are 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 y than" values should not be used in the required dose calculations. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
- g. Whenever there is primary to secondary leakage, sampling is done for Turbine d Building drain effluents by means of grab samples taken every four hours ,
during the period of discharge and analyzed for gross radioactivity (beta j and gamma) at a sensitivity of at least 1E-7 uCi/ml and recorded in the i plant records, along with the flow rate. Primary to secondary leakage is considered to be occurring whenever measurements indicate that secondary coolant gross radioactivity (beta and gamma) is greater than lE-5 uci/ml. i In addition, two (2) plant personnel shall check release calculations to verify that the limits of Appendix C CONTROLS 3.11.1.1 and 3.11.1.2 are not i exceeded. ! I l C-33 ISSUE 3 i l
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS 4 I TABLE 4.11-1 (continued) TABLE NOTATION-
- h. Whenever the BV-2 Recirculation Drain Pump (s) are discharging to catch basin 16, sampling vill be performed by means of a grab sample taken every.4 hours during pump operation.
4 C-34 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS D CONTROLS: LIQUID EFFLUENT DOSE 3.11.1.2 In accordance with BV-1 and EV-2 Technical Specification 6.8.6a, Items 4 and 5, the dose or dose commitment to MEMBER (S) 0F Tile PUBLIC from radioactive materials in liquid effluents released from the reactor unit (see Figure 3-1) shall te 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 c,f the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases, and the D proposed corrective actions to be taken to assure the subsequent releases (This Special Report shall also include vill be within the above limits.
(1) the results of radiological analyses of the drinking water 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 vater supply is taken from the receiving vater body within three miles of the plant discharge (three miles downstream only).
C-35 ISSUE 3
BV-1 and 2 ODCM APPENDTX C ODCM CONTROLS l CONTROLS: LIQUID RADVASTE TREATMENT SYSTEM i 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' waste 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 would 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 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 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 1.3 of this manual. l C-36 ISSUE 3
BV-1 and 2 ODCM 1 APPENDIX C ODCM CONTROLS l 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 5 500 mrem /yr to the total body and 3 3000 mrem /yr to the skin *, and
- b. The dose rate limit, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding Cal 4) with half-lives greater than eight days shall be f 1500 mrem /yr to any organ.
Applicability: At all times. Action:
- a. Vith the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the above limits (s), and
) b. Submit a Special Report to the Commission within 30 days pursuant to Technical Specification 6.9.2f.
- c. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gaseous effluents shall be determined to be within the above limits in accordance with Section 2.2 of this manual. 4.11.2.1.2 The dose rate, inhalation pathway only, for I-131, tritium and all radionuclides in particulate form (excluding C-14) with half-lives greater than eight days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis-program specified in Appendix C Table 4.11-2.
*During containment purge the dose rate may be averaged over 960 minutes.
C-37 ISSUE 3
BV-1 and 2 ODCH APPENDIX C ODCH CONTROLS TABLE 4.11-2 RADI0 ACTIVE GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM J MINIMUM I LOVER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD) GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (UCi/ml)" A. Vaste Gas Stnrage P P Principal Gamma 1E-4 Tank Each Tank Each Tank EmittersE Grab Sample H-3 1E-6 B. Containment Purge P P Principal Gamma 1E-4 b b Each Purge Each Purge Emitters 8 Grat Sample H-3 1E-6 Mb ,c e, gb Principal Gamma 1E-4 C.Ventilagion Emittersg Systems Grab Sample
- 1. Unit i Ventila-tion Vent H-3 1E-6
- 2. Unit 1 Contain-ment /SLCRS Vent
- 3. Unit 1/2 Process .
Vent
- 4. Unit 2 Ventila- !
tion Vent
- 5. Unit 2 contain-ment /SLCRS Vent
- 6. Unit 2 Decon.
Bldg. Vent
- 7. Unit 2 Vaste Gas Storage Vault Vent
- 8. Unit 2 Condensate Polishing Bldg.
Vent G C-38 ISSUE 3
BV-1 and 2 ODCM APPENDIX C
- ODCH CONTROLS TABLE 4.11-2 (continued) l PADI0 ACTIVE GASEOUS VASTE SAMPLING AND ANALYSIS PROGRAM HINIMUM LOVER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION,(LLD)
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml) D. All Systems Continuous V I-131 IE-12 Listed Above Charcoal Vhich Produce Sample I-133 1E-10 Continuous Release f d 1E-11 Continuous U Principal Gamma Particulate Emitters 8 Sample (I-131, Others) Continuous I M Gross Alpha IE-11 Composite Particulate Sample Continuous f 0 Sr-89, Sr-90 1E-11 Composite D Particulate Sample Continuous f Noble Gas Noble Gases 1E-6 Honitor Gross Beta And Gamma I l C-39 ISSUE 3
BV-1 and 2 ODCM ] APPENDIX C ODCM CONTROLS TABLE 4.11-2 (continued) TABLE NOTATION
- 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 F0VER change exceeding 15% of RATED THERMAL POVER vithin a 1 hour period. This requirement does not apply if (1) analysis shows that the Dose Equivalent I-131 concentration in the primary coolant has not increased qiore 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 hours (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 within 48 hours after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or THERMAL POVER change exceeding 15% of RATED THERMAL POVER vithin a 1 hour- period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
- f. The average ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Appendix C CONTROLS 3.11.2.1, 3.11.2.2, and 3.11.2.3.
- g. The principal gamma emitters for which the LLD specification vill apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present y at the LLD level for that nuclide. Vhen unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Effluent Release Report.
- h. Only when this release path is in use.
C-40 -ISSUE 3
BU-1 and 2-0DCH APPENDIX C l ODCH CONTROLS CONTROLS: DOSE-NOBLE GASES j l 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
_< 10 mrad for beta radiation.
- b. During any calendar year, to f 10 mrad for gamma radiation and
_< 20 mrad for beta radiation. Applicability: At all times. Action:
-a. With the calculated air dose- from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare; and submit to the Commission with in 30 days, pursuant to Technical Specification 6.9.2f, a Special Report which identifies the cause(s) for exceeding the-limit (s) and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases vill be i
within the above limits.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS i 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. L t D C 41 ISSUE 3 _ _ ------.--_____----- - _ --- _--_-----.--__ _ ___--_--_----------------- ---------- - _ .- - ------o
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: DOSE-RADI0 IODINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES 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 FUBLIC from radiolodines and radioactive caterials in particular form (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days in gaseous effluents releases from the reactor unit (see Figure 5-1) shall be limited to the following: 1 I a. During any calendar quarter to 3 7.5 mrem to any organ, and
- b. During any calendar year to f 15 mrem to any organ.
l Applicability: l At all times. l l Action:
- a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, (excluding C-14), and radionuclides (other than noble gases) with half-lives greater than eight days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective actions to be taken to assure the subsequent releases vill be within the above limits,
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations. Cumulative dose contributions shall be determined in accordance with Section 2.3 of this manual at least once every 31 days. C-42 ISSUE 3
1 BV-1 and 2 ODcM APPENDIX C ODCH CONTROLS I CONTROLS: GASEOUS RADVASTE TREATMENT SYSTEM 3.11.2.4 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 6, the Gaseous Radvaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous vaste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the reactor unit (see Figure 5-1), when averaged over 31 days, 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 would exceed 0.3 mrem te any organ. Applicability: At all times. Action:
- a. Vith 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 I following information.
l
- 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, 1
- 2. Action (s) taken to restore the inoperable equipment to operational l status, and l 1
- 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 REQUIREME! TIS i 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at j least once per 31 days, in accordance with Section 2.3 of this I i manual. I C-43 ISSUE 3
i> lJ ' BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS CONTROLS: TOTAL DOSE 3.11.4.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6a, Item 10, the annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to < 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to
< 75 mrems.
Applicability: At all times. Action:
- 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 limits of Appendix C CONTROL 3.11.4.1 have been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving {
conformance with the above limits. This Special Report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a 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 concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
I C-44 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS SURVEILLANCE REQUIREMENTS (continued) 4.11.4.1.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Appendix C SURVEILLANCE 4.11.1.2.a. 4.11.1.2.b, 4.11.2.2.a, 4.11.2.2.b, REQUIREMENTS 4.11.2.3.a, and 4.11.2.3.b. ) 4.11.4.1.2 Cumulative dose contributions from direct radiation from the units (including outside storage tanks, etc.) shall be determined in accordance with Section 4 of this manual. This requirement is 4 I l applicable only under conditions set forth in Action a. of Appendix C CONTROL 3.11.4.1. J l l i l l I C 45 ISSUE 3
BU-l and 2 ODCM APPENDIX C ODCM CONTROLS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.12.1 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 1, the radiological environmental monitoring program shall be conducted as specified in Appendix C, Table 3.12-1. Applicability: At all times. l l Action l
- a. Vith the radiological environmental monitoring program not being conducted as specified in Appendix C, Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological En*>ironmental 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 limits of Appendix C, Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of affected calendar quarter a Special Report pursuant to Technical Specification 6.9.2f which includes an evaluation of any release conditions, environmental factors or other aspects which caused the-limits of Appendix C, Table 3.12-2 to be exceeded. This report is not required if the measured level of radioactive was not the result of plant effluents; however, in such an ,
event, the condition shall be reported and described in the Annual ' Radiological Environmental Report. Vhen 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. Vith milk or fresh leafy vegetable samples unavailable from the required number of locations selected in accordance with Appendix C CONTROL 3.12.2 and listed in the ODCM, obtain replacement samples. The locations from which samples vere 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 environmenta' monitoring program as replacement locations, if available,
- d. The provisions of Appendix C CONTROL 3.0.3 are not applicable.
C 46 ISSUE 3
BU-1 and 2 ODCM APPENDIX C ODCM CONTROLS D SURVEILLANCE REQUIREMENTS (continued) 4.12.1.1 The radiological environmental monitoring samples shall be collected l pursuant to Appendix C, Table 3.12-1 from the locations given in the l ODCH and shall be analyzed pursuant to be requirements of Appendix C, j Tables 3.12-1 and 4.12-1. l l t i
.)
4 l l l
~l l
i l l C 47 ISSUE 3-l l l
- _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ . ________-____-__________________D
BV-1 and 2 ODCH APPENDIX C ODCH CONTROLS TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM SAMPLING AND EXPOSURE PATHVAY NUMBER OF SAMPLES COLLECTION TYPE AND FREQUENCY (*) AND/0R SAMPLE Aid 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- 1ection at least Analyze for I-131; tion 10-20 weekly. miles distant Partisulate sampler. and in the least prevalent Analyze for gross (b); beta weekly vind 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 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. f8 Analysis frequency same as sampling frequency unless otherwise specif.'ed. Particulate samples are not counted for 224 hours after filter change. Perform gamma isotopic analysis on each sample vhrn gross beta is >10 times the yearly mean of control samples.
** Sample locations are given on figures and tables in Section 3 of this manual.
C 48 ISSUE 3
BV-1 and 2 ODCM L APPENDIX C ODCM CONTROLS o TABLE 3.12-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING AND I EXPOSURE PATHVAY NUMBER OF SAMPLES COLLECTION TYPE AND FREQUENCY ") AND/0R SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS
- 3. VATERBORNE
- a. Surface 2 locations. Composite
- sample Gamma isotopic collected over a ana ysis of each
- 1. One sample period not to compsite samples upstream, exceed 1 month.
l Tritium enalysis 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 veeks. Gamma isotopic analy-sis of composite sample (by location) monthly; Tritium analysis of composite sample quarterly,
- c. Groundwater N/A - No wells in lover elevations between plant and river,
- d. Sediment From 1 location. Semi-annually. Gamma isotopic analy-Shoreline sis semi-annually.
(#) Analysis frequency same as sampling frequency unless otherwise specified.
- Composite samples shall be collected by collecting an aliquot at intervals not exceeding two hours.
D ** Sample locations are given on figures and tables in Section 3 of this manual. C 49 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCM CONTROLS TABLE 3.12-1 (continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I SAMPLING AND EXPOSURE PATHVAY NUMBER OF SAMPLES COLLECTION TYPE AND FREQUENCY (*} AND/OR SAMPLE AND LOCATIONS ** FREQUENCY OF ANALYSIS l
- 4. INGESTION
- a. Hilk 4 locations.IC) At least bi-veekly Gamma isotopic and when animals are I-131 analysis of
- 1. Three samples on pasture; at each sample.
selected on least monthly at basis of other times. highest poten-tial thyroid dose using milch census - data.
- 2. One local large dairy.
- b. Fish 2 locations. Semi-annual. One Gamma isotopic sample of avail- analysis on edible able species. portions.
- c. Food 4 locations. Annually at time Gamma isotopic Products of harvest. analysis and I-131 (Leafy 1. Three locations analysis on edible l Vegetables) within 5 miles. portion. 1
- 2. One control location. i 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-50 ISSUE 3 l
BV-1 and 2 ODCM .. APPENDIX C ODCM CONTROLS TABLE 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS AIRBORNE PARTICULATE BROAD LEAF l VATER OR GASES FISH MILK VEGETABLES ANALYSIS (pci/1) (pCi/m ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET) l H-3 2E+4(a) Mn-54 1E+3 3E+4 Fe-59 4E+2 1E+4 Co-58 1E+3 3E+4 Co-60 3E+2 1E+4 2n-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 water samples. This is a 40 CFR Part 141 value. C-51 ISSUE 3
BV-1 and 2 ODCH APPENDIX C ODCM CONTROLS TABLE 4.12-1 MAXIMUM VALUES FOR THE LOVER LIMITS OF DETECTION (LLD)" AIRBORNE PARTICULATE VATER OR GAS FISH HILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/l) (pCi/m ) (pCi/kg, VET) (pCi/1) (pCi/kg, VET) (pCi/kg, DRY) Gross Beta 4 1E-2 H-3 2000 Hn-54 15 130 Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-95 30' C Nb-95 15 b 60 I-131 l 7E-2 1 5E-2 130 15 60 150 Cs-134 15 18 6E-2 150 18 80 180 Cs-137 C 60 Ba-140 60 C 15 La-140 IS NOTE: This list does not mean that only mese nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall be identified and reported. C-52 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS TABLE 4.12-1 (continued) TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will 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 5 (E)(V)(2.22)(Y)bexp(- AoT) where: LLD is the lover limit of detection as defined above (as pCi per unit mass or volume); l Sh is the standard deviation of the background counting rate or of the I 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); I A is the radioactive decay constant for the particular radionuclide; AT 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 ofhS used in the calculation of the LLD for a detection
. system shall b6 based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate ) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E, V, Y and AT 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. C-53 ISSUE 3
N - BV-1~and 2 ODCM APPENDIX C ODCH CONTROLS TABLE 4.12-1 (continued) TABLE NOTATION
- b. LLD for drinking water.
- c. If parent and daughter are totaled, the most res".rictive LLD should be applied.
1 C-54 ISSUE 3
BV-1 and 2 ODCM APPENDIX C ODCH CONTROLS D 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 l 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. 1 Applicability: At all times. I Action: j
- a. With 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 l' Commission within 30 days, pursuant to Technical Specification 6.9.2f, a Special Report, which identifies the nev 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 provisions 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.
D ** Confirmation by telephone is equivalent to door-to-door. C-55 ISSUE 3 __ _ _ - - - - - - - - - - - - - - - _ - - - - _ - - - - - - - - - - - - - - - - - _ - - - - - - - _ - - - - _- a
BV-1 and 2 ODCM APTENDIX C ODCM CONTROLS CONTROLS: RADIOLOGICAL ENVIRONMENTAL MONITORING - INTERLABORATORY COMPARISON PROGRAM 3.12.3 In accordance with BV-1 and BV-2 Technical Specification 6.8.6b, Item 3, analyses shall be performad on tadioactive materials supplied as part of an Interlaboratory Lomparison Program. Applicability: At all times. Action:
- 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 Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Report. I C-56 ISSUE 3
BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS D 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 liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with SectSon 1 of this manual to ensure that the alarm / trip vill 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 GASEOUS EFFLUENT MONITORING INSTRUPENTATION 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 manual to ensure that the alarm / trip vill occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of D potentially explosive gas mixtures in the vaste gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Des.4gn Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. D-1 ISSUE 3
BV-1 and 2 ODCM APPENDIX D i BASES FOR ODCH CONTROLS
)
BASES LIQUID EFFLUENTS i 3/4.11.1.1 LIQUID EFFLUENT CONCENTRATION i This CONTROL is provided to ensure that the concentration of radioactive materials released in Liquid vaste effluents from the site to unrestricted areas vill be less than the concentration i levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site vill result in exposure within (1) the Section II. A design objectives of l Appendix I, 10 CFR Part 50, to an individual and (2) the limits of l f 10 CFR Part 20.106(e) to the population. The concentration limit l 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 vater l using the methods described in International Commission on l Radiological Protection (ICRP) Publication 2.
3/4.11.1.2 LIQUID EFFLUENT DOSE This CONTROL is provided to implement the requirements of Sections II.A, III.A, and IV.A of Appendix I, 10 CFR Part 50. The Limiting condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating f1:xibility and at the same time implement the , guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents vill be kept "as lov as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation i of the facility vill not result in radionuclide concentrations in the finished drinking vater that are in excess of the requirements of 40 CFR 141. The dose calculations in the Section 1.3 of this manual implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in Section 1.3 of this manual for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation Of Annual Doses To Man From Routine Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance Vith 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, " Estimating Aquatic Dispersion Of Effluents From Accidental And Routine Reactor Releases For The Purpose Of Implementing Appendix I," April, 1977. NUREG-0133 J provides methods for dose calculations consistent with Regulatory l Guides 1.109 and 1.113. D-2 ISSUE 3
BV-1 and 2 ODCH APPENDIX D BASES FOR ODCH CONTROLS k BASES: LIOUID 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 TREATHENT SYSTEM The CONTROL that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents vill be kept "as lov as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radvaste treatment system vere 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. l l l D-3 ISSUE 3
BV-1 and 2 ODCM APPENDIX D BASES FOR ODCH CONTROLS BASES: GASEOUS EFFLUENTS 3/4.11.2.1 GASEOUS 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 J concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material' discharged in gaseous effluents vill not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual vill be sufficiently lov to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate i limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site 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 f 1,500 mrem / year. 3/4.11.2.2 DOSE, N0BLE 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 j CONTROL implements the guides set forth in Section II.B of q Appendix I. The ACTION statements provide the required operating flexibility and at the same time . implement the guides set forth in Section IV.A of Appendix I to assure that the release of radioactive material in gaseous effluents vill be kept "as lov as is reasonably achievable." The Surveillance Requirements implement the l requirements in Section III.A of Appendix I that conformance with l 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, j
" Calculation Of Annual Doses To Man From Routine Releases Of Reactor 4 Effluents For The Purpose Of Evaluating Compliance Vith 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, " Methods For Estimating Atmospheric Transport And Dispersion i of Gaseous Effluents In Routine Releases From Light Vater-Cooled Reactors," Revision 1, July, 1977. The equations in Section 2.3 of I this manual are provided for determining the air doses at the exclusion area boundary, and are based upon the historical average I
I D-4 ISSUE 3 l i
BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS D BASES: GASE0US 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. l The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents vill be kept 'as lov as is reasonably achievable." The calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appetidix 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 l Section 2.3 of this manaual are for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses To Man From Routing Releases Of Reactor Effluents For The Purpose Of Evaluating Compliance Vith 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111,
" Methods For Estimating Atmospheric Transport And Dispersion Of ..
Gaseous Effluents In Routine Releases From Light-Vater-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto vcgetation 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.
8 D-5 ISSUE 3
BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS l BASES: GASEOUS EFFLUENTS (continued) 3/4.11.2.4 GASEOUS RADVASTE TREATMENT SYSTEM The CONTROL that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents vill be kept "as lov as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of. the systems were specified as a suitable fraction of the dose design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. This specification applies to gaseous radvaste from Beaver Valley Power Station, Unit No. 1 or Unit No. 2. l l l l l l l D-6 ISSUE 3
BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS BASES: TOTAL DOSE I l 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 I a Special Report whenever the calculated doses due to releases of l 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 f resultant dose to a MEMBER OF THE PUBLIC vill exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within tvice the dose design objectives of Appendix I, and if direct radiation doses from the units (including outside storages tanks, etc.) are l kept small. The Special Report vill describe a course of action I that should res"It 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 J of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely I request and fulfills the requirements of 40 CFR Part 190 until NRC l staff action is completed. The variance only relates to the limits l 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 ; MEMBER OF THE PUBLIC during any period in which he/she is engaged in ; carrying out any operation that is part of the nuclear fuel cycle. D D7 ISSUE 3 e_____- _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - - _ _ _ -
BV-1 and 2 ODCM APPENDIX D BASES FOR ODCM CONTROLS l BASES: RADIOLOGICAL ENVIRONMENTAL MONITORING
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3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this CONTROL provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the 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 ar2 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. l l 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. j 3/4.12.2 LAND USE CENSUS This CONTROL is provided to ensure that changes in the use of . unrestricted areas are identified and that modifications to the monitoring programs are made if required by the results of this census. The best survey information from the door-to-door survey, aerial survey, or by consulting with local agriculture authorities j i 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 l The CONTROL for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the ; precision and accuracy of the measurements of radioactive material -) in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. 1 D-8 ISSUE 3 l l
BV-1 and 2 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-l
-deviations not reported under 6.9.2f with respect to any Appendix C l CONTROL.
l The annual radiological environmental reports shall include:
- Summaries, interpretations, and . statistical evaluation -o'f. '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. ,s
- 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. ~l
- The results of licensee participation in the Interlaboratory l Comparison Program required by Appendix C CONTROL 3.12.3.
l A single submittal may be made for a multiple unit site. The submittal.should' combine those sections that are common to both units. E-1 ISSUE 3 i
BU-l and 2 ODCM APPENDIX E N@ RIAL REPORTS TABLE 6.9-1 ENVIROOMENIAL RADIOIDGICAL MONI'IORING PROGRM
SUMMARY
Name Of Facility Docket No. Location Of Facility Reporting Period (County, State) ALL INDICA'IOR LOCATIONS WITH HIGEIEST
/GRicE MEAN CONTROL LOCATIONS MEDIUM OF PATIMAY TYPE AND 'IUPAL LOKER LIMITS LOCATIONS NUMBER OF NUMBER OF OF SAMPLED DETECTION a 1)b NAME DISTANCE MEAN(1)b p,g (1)b REPORTABLE (UNIT OF ANALYSES b h MEASUREMENT) PERFORMED (LLD) MEAN(h RANG AND DIRECTION RANGE RMK;E OCCURRENCES nal Lower Limits Of Detection (LLD) as defined in Table Notation a. of Table 4.11-1 of Appendix C CONTROL 3.11.1.1.
Mean and range based upon detectable measurement only. Fraction of detectable measurement at specified locations is indicated in parenthesis (1). E-2 . ISSUE 3
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BV-1 and 2 ODCM APPENDIX E ANNUAL REFORTS ANNUAL REPORI' ANNUAL RADIOACTIVE EFFLUEN1 RELEASE REPORT 6.9.1.11 Routine radioactive effluent release reports covering the operation of the unit during the previous calendar year shall be submitted prior to April 1 of each year. This report is prepared and submitted in accordance with BVPS RCM Appendix 5, and at a minimum, shall contain the following: A summary of the quantities of radioactive liquid and gaseous effluent and solid vaste released from the unit as outlined in Regulatory Guide 1.21, Revision 1, June, 1974, " Measuring, Evaluating, And Reporting Radioactivity In Solid Vastes And Releases of Radioactive Materials In Liquid And Gaseous Effluents From Light-Water-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. 9
- Any licensee initiated changes to the ODCM made during the 12 month period.
Any radioactive liquid or gaseous effluent monitoring instrumentation channels not returned to OPERABLE status within 30 days, and why the inoperability was not corrected in a timely manner. This applies to the liquid or gaseous effluent monitoring instrumentation channels required to be OPERABLE per Appendix C CONTROLS 3.3.3.9 and 3.3.3.10. Any ODCM Appendix C SURVEILLANCE REQUIREMENT deficiencies. This applies to monitoring, sampling and analysis and dose projection. The reasons when unusual circumstances result in LLD's higher than required by Appendix C, Table 4.11-1 and 4.11-2. 4 A single submittal may be made for a multiple unit site. The submittal should combine those sections that are common to all units at the site; however, for units with separate radvaste systems, the submittal shall specify the releases of radioactive material from each unit. E-3 ISSUE 3
BV-1 and 2 ODCM APPENDIX E j i ANNUAL REPORTS
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ANNUAL REPORT (continued) l
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- The..following information for each type of solid waste shipped offsite during the report period:
- container volume
- total curie quantity (determined by measurement or estimate) !
- principal radionuclides (determined by measurement or estimate)
- type of vaste (e.g., spent resin, compacted dry vaste, evaporator bottoms)
- type of container (e.g., LSA, Type A, Type B, Large Quantity)
- solidification agent (e.g., cement)
- classification and other requirements specified by 10 CFR Part 61
- An annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of vind speed, vind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distributions of vind speed, vind direction, and atmospheric stability.
- An assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
- An assessment of the radiation doses from radioactive effluents to MEMBER (S) 0F THE PUBLIC due to 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 reactor releases for the previous calendar year to show conformance with 40 CFR 190, Environmental Radiation Protection Standards For Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1. The SKYSHINE Code (available from Radiation Shielding Information Center, (0RNL)) is acceptable for calculating the dose contribution from direct radiation due to N-16.
If quantities of radioactive materials released during the reporting period are significantly above design obj ec tives , the report must cover this specifically. O E-4 SUE 3}}